[Federal Register Volume 66, Number 150 (Friday, August 3, 2001)]
[Proposed Rules]
[Pages 40626-40640]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 01-19414]


 ========================================================================
 Proposed Rules
                                                 Federal Register
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 This section of the FEDERAL REGISTER contains notices to the public of 
 the proposed issuance of rules and regulations. The purpose of these 
 notices is to give interested persons an opportunity to participate in 
 the rule making prior to the adoption of the final rules.
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  Federal Register / Vol. 66, No. 150 / Friday, August 3, 2001 / 
Proposed Rules  

[[Page 40626]]



NUCLEAR REGULATORY COMMISSION

10 CFR Part 50

RIN 3150-AG61


Industry Codes and Standards; Amended Requirements

AGENCY: Nuclear Regulatory Commission.

ACTION: Proposed rule and withdrawal of proposed rule.

-----------------------------------------------------------------------

SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) proposes to amend 
its regulations to incorporate by reference a later edition and addenda 
of the American Society of Mechanical Engineers (ASME) Boiler and 
Pressure Vessel Code (BPV Code) and the ASME Code for Operation and 
Maintenance of Nuclear Power Plants (OM Code) to provide updated rules 
for construction, inservice inspection (ISI), and inservice testing 
(IST) of components in light-water cooled nuclear power plants. The 
proposed rule identifies the latest edition and addenda of the ASME BPV 
and OM Codes that have been approved for use by the NRC subject to 
certain limitations and modifications. The NRC is also withdrawing a 
supplemental proposed rule that would have eliminated the requirement 
for licensees to update their ISI and IST programs every 120 months to 
the latest ASME Code edition and addenda incorporated by reference in 
the regulations.

DATES: Comments regarding the proposed amendment must be submitted by 
October 17, 2001. Comments received after this date will be considered 
if it is practical to do so, but the Commission is only able to ensure 
consideration of comments received on or before this date.

ADDRESSES: Comments may be sent to: Secretary, U.S. Nuclear Regulatory 
Commission, Washington, DC 20555-0001, ATTN: Rulemaking and 
Adjudications Staff. Comments may be hand-delivered to 11555 Rockville 
Pike, Rockville, Maryland, 20852, between 7:30 a.m. and 4:15 p.m. on 
Federal workdays.
    You may also provide comments via the NRC's interactive rulemaking 
Website at http://ruleforum.llnl.gov. This site provides the ability to 
upload comments as files (in any format), provided that your Web 
browser supports that function. For information about the interactive 
rulemaking Website, contact Ms. Carol Gallagher at, (301) 415-5905, or 
via e-mail at: [email protected]. Certain documents related to this 
rulemaking, including comments received, may be examined at the NRC's 
Public Document Room (PDR), located at One White Flint North, 11555 
Rockville Pike, Rockville, Maryland.
    The NRC maintains an Agencywide Documents Access and Management 
System (ADAMS), which provides text and image files of NRC's public 
documents. The documents may be accessed through the NRC's Public 
Electronic Reading Room on the Internet at http://www.nrc.gov/NRC/ADAMS/index.html. If you do not have access to ADAMS or if there are 
problems in accessing the documents located in ADAMS, contact the NRC 
PDR Reference staff at 1-800-397-4209, (301) 415-4737, or by email to 
[email protected]. The availability of documents associated with this 
rulemaking is further discussed in Section 6 below, under SUPPLEMENTARY 
INFORMATION.

FOR FURTHER INFORMATION CONTACT: Stephen Tingen, Division of 
Engineering, Office of Nuclear Reactor Regulation, U.S. Nuclear 
Regulatory Commission, Washington, D.C. 20555-0001. Alternatively, you 
may contact Mr. Tingen at (301) 415-1280, or via e-mail at: 
[email protected].

SUPPLEMENTARY INFORMATION:

1. Background
2. Summary of Proposed Revisions to 10 CFR 50.55a
2.1  Section III
2.2  Section XI
2.2.1  Owner-Defined Requirements for Class CC and Class MC 
Components
2.2.1.1  Concrete Containment Visual Examination Qualification
2.2.1.2  Visual Examination Qualification Requirements for 
Containment Surfaces
2.2.1.3  General and Detailed Examinations
2.2.1.4  Bolting Acceptance Standard
2.2.2  Examination of Containment Bolted Connections
2.2.3  Acceptance Standard for Surfaces Requiring Augmented 
Ultrasonic Examinations
2.2.4  Containment Penetration Piping
2.2.5  Certification of Nondestructive Examination Personnel
2.2.6  Substitution of Alternative Methods
2.2.7  System Leakage Tests
2.2.8  Table IWB-2500-1 Examination Requirements
2.2.9  Supplemental Annual Training Requirements for Ultrasonic 
Examiners
2.2.10  Underwater Welding
2.3  Appendix VIII to Section XI
2.3.1  Examination Coverage for Dissimilar Metal Pipe Welds
2.3.2  Reactor Vessel Single Side Examinations
2.3.3  Qualification Test Samples
2.3.4  Implementation of Appendix VIII to Section XI
2.4  ASME OM Code
3. Section-by-Section Analysis of Substantive Changes
4. Withdrawal of a Proposed Rule to Eliminate 120-Month Update
5. Draft Generic Aging Lessons Learned Report
6. Availability of Documents
7. Plain Language
8. Voluntary Consensus Standards
9. Finding of No Significant Environmental Impact: Availability
10. Paperwork Reduction Act Statement
11. Regulatory Analysis
12. Regulatory Flexibility Certification
13. Backfit Analysis

1. Background

    The regulations in 10 CFR 50.55a require that nuclear power plant 
licensees--
    (1) Construct Class 1, 2, and 3 components in accordance with the 
provisions provided in Section III, Division 1, ``Requirements for 
Construction of Nuclear Power Plant Components,'' of the ASME BPV Code;
    (2) Inspect Class 1, 2, and 3, metal containment (MC), and concrete 
containment (CC) components in accordance with the provisions provided 
in Section XI, Division 1, ``Requirements for Inservice Inspection of 
Nuclear Power Plant Components,'' of the ASME BPV Code; and
    (3) Test Class 1, 2, and 3 pumps and valves in accordance with the 
provisions provided in the ASME OM Code.
    The regulations in 10 CFR 50.55a also require that licensees revise 
their ISI and IST programs every 120 months to the edition and addenda 
of the ASME Code incorporated by reference into 10 CFR 50.55a that is 
in effect 12 months prior to the start of the new 120-month interval; 
permit licensees to voluntarily update their construction, ISI, and IST

[[Page 40627]]

programs at any time to the most recent edition and addenda of the ASME 
BPV and/or OM Codes incorporated by reference in 10 CFR 50.55a with the 
approval of the NRC; and specify the edition and addenda of Section III 
of the ASME BPV Code that must be applied to the construction of 
reactor coolant pressure boundary components and Quality Group B and C 
components.
    The NRC proposes to amend its regulations in 10 CFR 50.55a to 
incorporate by reference the 1997 Addenda, the 1998 Edition, the 1999 
Addenda, and the 2000 Addenda of Division 1 rules of Section III of the 
ASME BPV Code; the 1997 Addenda, the 1998 Edition, the 1999 Addenda, 
and the 2000 Addenda of Division 1 rules of Section XI of the ASME BPV 
Code; and the 1997 Addenda, the 1998 Edition, the 1999 Addenda, and the 
2000 Addenda of the ASME OM Code for construction, ISI, and IST of 
components in nuclear power plants. The NRC has reviewed the 1997 
Addenda, 1998 Edition, the 1999 Addenda, and the 2000 Addenda of the 
ASME BPV Code, Sections III and XI, and the ASME OM Code, and concluded 
that--
    (1) Section III of the ASME BPV Code is acceptable for use with no 
new proposed limitations or modifications;
    (2) Section XI of the ASME BPV Code is acceptable for use subject 
to proposed limitations and modifications; and
    (3) The ASME OM Code is acceptable for use subject to one proposed 
modification.
    The NRC-proposed limitations and modifications address enhancements 
to the provisions in the ASME BPV and OM Codes. The ASME OM Code does 
not issue an addenda in the same year that an edition is issued. 
Therefore, there is not a 1998 Addenda to the ASME OM Code. The ASME 
BPV Code also did not issue an addenda in the same year that 1998 
Edition was issued. Therefore, there is not a 1998 Addenda to Section 
III and Section XI of the ASME BPV Code.
    The NRC also proposes revisions to the regulations in 10 CFR 50.55a 
that licensees use to modify the implementation of Appendix VIII, 
``Performance Demonstration for Ultrasonic Examinations Systems,'' to 
Section XI of the ASME BPV Code. The proposed amendment would clarify 
existing ultrasonic examination qualification requirements in 10 CFR 
50.55a. The proposed amendment would also add new requirements to 
clarify the coordination of Appendix VIII with other parts of Section 
XI.
    On April 27, 1999 (64 FR 22580), the NRC proposed to eliminate the 
requirement for licensees to update their ISI and IST programs beyond a 
baseline edition and addenda of the ASME BPV Code. In a staff 
requirements memorandum (SRM) dated April 13, 2000, the Commission 
disapproved the elimination of the 120-month update requirement. 
Therefore, the Commission is withdrawing the April 27, 1999 proposed 
rule (64 FR 22580), as discussed in Section 4 below.

2. Summary of Proposed Revisions to 10 CFR 50.55a

2.1  Section III

    The proposed amendment would revise 10 CFR 50.55a(b)(1) to 
incorporate by reference the 1997 Addenda, the 1998 Edition, the 1999 
Addenda, and the 2000 Addenda of Division 1 of Section III of the ASME 
BPV Code. The proposed amendment would extend the requirements in 10 
CFR 50.55a(b)(1)(ii), 50.55a(b)(1)(iii), and 50.55a(b)(1)(v) to the 
1997 Addenda, the 1998 Edition, the 1999 Addenda, and the 2000 Addenda 
of Section III of the ASME BPV Code. The remaining limitations and 
modifications would remain the same. No new limitations or 
modifications would be imposed on the 1997 Addenda, the 1998 Edition, 
the 1999 Addenda, and the 2000 Addenda.

2.2  Section Xl

    The proposed amendment would revise 10 CFR 50.55a(b)(2), to 
incorporate by reference the 1997 Addenda, the 1998 Edition, the 1999 
Addenda, and the 2000 Addenda of Division 1 of Section XI of the ASME 
BPV Code. The proposed amendment would extend the requirements in 10 
CFR 50.55a(b)(2)(viii) and 50.55a(b)(2)(ix) to the 1998 Edition, the 
1999 Addenda, and the 2000 Addenda of Section XI of the ASME BPV Code. 
The proposed amendment would extend the requirements in 
50.55a(b)(2)(xi), 50.55a(b)(2)(xv), and 50.55a(b)(2)(xvii) to the 1997 
Addenda, the 1998 Edition, the 1999 Addenda, and the 2000 Addenda of 
Section XI of the ASME BPV Code.
    The proposed amendment would delete 50.55a(g)(6)(ii)(B)(1) through 
(4) because the implementation dates have expired and all licensees 
have completed their first containment inservice inspection 
requirements or have been approved by an exemption for a delay. As 
licensees have begun implementing their containment ISI programs, the 
NRC has received requests to clarify the start of the first 120-month 
interval. Therefore, the new proposed 10 CFR 50.55a(g)(6)(ii)(B)(1) 
would clarify that the start date of the first 120-month interval for 
the ISI of Class MC and Class CC components must coincide with the 
start of the first containment inspection. The requirement in 10 CFR 
50.55a(g)(6)(ii)(B)(5) would be redesignated as 50.55a(g)(6)(ii)(B)(2). 
New limitations and modifications proposed are as follows:
2.2.1  Owner-Defined Requirements for Class CC and Class MC Components
    The proposed 10 CFR 50.55a(b)(2)(viii)(F), 50.55a(b)(2)(ix)(F), 
50.55a(b)(2)(ix)(G), and 50.55a(b)(2)(ix)(H), address ``owner-defined'' 
requirements. Revisions to the 1997 Addenda, the 1998 Edition, the 1999 
Addenda, and the 2000 Addenda of Section XI would permit each licensee 
to define personnel qualification and visual examination requirements. 
Each licensee would not only be responsible for developing the 
procedures and requirements for the instruction, training, and approval 
of examination personnel, but they would also be responsible for 
developing procedures and requirements for performing examinations. In 
addition, each licensee would be permitted to define the acceptance 
criteria for these requirements; i.e., by evaluating the results of the 
examination and determining whether the results are acceptable. ASME 
Code requirements associated with the use of these ``owner-defined'' 
requirements provide little control. A licensee could re-define these 
requirements at any time. Because a set of ``minimum requirements'' has 
not been defined, it cannot be determined whether the new requirements 
would maintain safety and ensure the protection of public health and 
safety. Versions of the ASME Code prior to 1997 contained requirements 
that are acceptable to the NRC. Therefore, the proposed modifications 
and limitations provide specific requirements that the licensee shall 
meet in lieu of establishing its own requirements.
    However, in some instances the use of ``owner-defined'' provisions 
are acceptable. Subparagraph IWE-2310(e) of the 1998 Edition, the 1999 
Addenda, and the 2000 Addenda provides specific criteria for coated and 
non-coated areas of containment surfaces subject to detailed visual 
inspection. It states that painted or coated areas shall be examined 
for evidence of flaking, blistering, peeling, discoloration, and other 
signs of distress. For non-coated areas, it states that those areas 
shall be examined for evidence of cracking, discoloration, wear, 
pitting, excessive corrosion, gouges, surface

[[Page 40628]]

discontinuities, dents, and other signs of surface irregularities. 
Therefore, the provision for the owner to define visual examination 
requirements in IWE-2310(a) of the 1998 Edition, the 1999 Addenda, and 
the 2000 Addenda, as supplemented by the requirements in IWE-2310(e), 
is acceptable.
    Paragraphs IWE-3510 and IWE-3511, of the 1998 Edition, the 1999 
Addenda, and the 2000 Addenda, state that the owner shall define the 
acceptance criteria to be used when conducting a visual examination of 
a metal containment surface. Modifications are not imposed on these 
``owner-defined'' provisions because other requirements exist in 
Subsection IWE of the 1998 Edition, the 1999 Addenda, and the 2000 
Addenda that provide sufficient requirements to identify and correct 
degradations in metal containment surfaces that would be identified 
during visual examinations. For example, paragraph IWE-3510.2, states, 
``Areas that are suspect shall be accepted by engineering evaluation or 
corrected by repair/replacement activities in accordance with IWE-3122. 
Supplemental examinations in accordance with IWE-3200 shall be 
performed when specified as a result of the engineering evaluation.'' 
Paragraph IWE-3122 provides specific acceptance criteria for evaluating 
the acceptability of metal containment surface visual examination 
results. The ``owner-defined'' acceptance criteria for visual 
examination of metal containment surfaces is a screening for 
determining when areas of degradation must be further evaluated. 
Therefore, the ``owner-defined'' acceptance criteria for visual 
examination of metal containment surfaces in IWE-3510 and IWE-3511 are 
acceptable.
    Paragraph IWL-2310(e) of the 1998 Edition, the 1999 Addenda, and 
the 2000 Addenda, states that the owner shall define the requirements 
to be used for conducting visual examinations of tendon anchorage 
hardware, wires, or strands. A modification is not imposed on this 
``owner-defined'' provision because other requirements in Subsection 
IWL of the 1998 Edition, the 1999 Addenda, and the 2000 Addenda provide 
sufficient requirements to be used for conducting visual examinations 
of tendon anchorage hardware, wires, or strands. For example, the 
provisions in Table IWL-2500-1, Examination Category L-B, provide 
specific requirements to be used for conducting visual examinations of 
tendon anchorage hardware, wires, or strands. Therefore, licensees are 
required to use the requirements in Table IWL-2500-1, Examination 
Category L-B, to conduct visual examinations of tendon anchorage 
hardware, wires, and strands.
2.2.1.1  Concrete Containment Visual Examination Qualification
    The proposed modification in 10 CFR 50.55a(b)(2)(viii)(F) would 
require that personnel examining containment concrete surfaces and 
tendon anchorage hardware, wires, or strands be qualified in accordance 
with the procedures of IWA-2300 of the 1998 Edition, the 1999 Addenda, 
and the 2000 Addenda in lieu of ``owner-defined'' personnel 
qualification provisions in IWL-2310(d) of the 1998 Edition, and the 
1999 Addenda and the 2000 Addenda. Prior to the 1997 Addenda, IWL-
2310(c) required that visual examination personnel be qualified in 
accordance with specific requirements in IWA-2300. The qualification 
requirements were revised in IWL-2310(d), 1997 Addenda, to allow the 
owner to define the qualification requirements for personnel who 
perform visual examinations of concrete and tendon anchorage hardware, 
wires, or strands. However, the new Code provision does not provide any 
criteria that the licensee must use when developing qualification 
requirements. Therefore, the NRC is proposing that licensees continue 
to use the provisions in IWA-2300 to qualify personnel who perform 
visual inspections of containment concrete surfaces and tendon 
anchorage hardware, wires, or strands.
2.2.1.2  Visual Examination Qualification Requirements for Containment 
Surfaces
    The proposed modification in 10 CFR 50.55a(b)(2)(ix)(F) would 
require that personnel who conduct visual examinations of containment 
surfaces be qualified in accordance with IWA-2300 of the 1998 Edition, 
the 1999 Addenda, and the 2000 Addenda in lieu of ``owner-defined'' 
qualification provisions in IWE-2330(a) of the 1998 Edition, the 1999 
Addenda, and the 2000 Addenda. Prior to the 1998 Edition, the NRC 
approved provisions in IWA-2300 were used to define the qualification 
requirements for personnel who conduct visual examinations of 
containment surfaces. Paragraph IWE-2330(a) was added in the 1998 
Edition and states that the licensee must define the qualification 
requirements for personnel who conduct visual examinations of 
containment surfaces. However, the revised Code provision does not 
provide any criteria that the licensee must use when developing 
qualification requirements. Therefore, the NRC is proposing that 
licensees continue to use the provisions in IWA-2300 to qualify 
personnel who conduct visual examinations of containment surfaces.
2.2.1.3  General and Detailed Visual Examinations
    The proposed modification in 10 CFR 50.55a(b)(2)(ix)(G) would 
require that the general and detailed visual examinations required by 
IWE-2310(b) and IWE-2310(c) of the 1998 Edition, the 1999 Addenda, and 
the 2000 Addenda meet the VT-3 and VT-1 examination provisions in IWA-
2210 of the 1998 Edition, the 1999 Addenda, and the 2000 Addenda, in 
lieu of the ``owner-defined'' general and detailed visual examination 
provisions in IWE-2310(a) of the 1998 Edition, the 1999 Addenda, and 
the 2000 Addenda. Paragraph IWE-2310(a), was revised in the 1998 
Edition to require that the owner define general and detailed visual 
examinations. Therefore, the general and detailed visual examinations 
in IWE-2310(b) and IWE-2310(c) are now required by the Code to be 
defined by the owner. However, the revised Code provision does not 
provide any criteria that the licensee must use to define general and 
detailed visual examination requirements. Prior to the 1998 Edition, 
the NRC-approved provisions in IWA-2210 were used to defined the 
general (VT-3) and detailed (VT-1) visual examinations required by 
Subsection IWE. Therefore, the NRC is proposing that licensees continue 
to use the VT-3 and VT-1 provisions of IWA-2210 to define the general 
and detailed visual examinations required by IWE-2310(b) and IWE-
2310(c), and continue to extend Table IWA-2210-1 maximum direct 
examination distance and decrease Table IWA-2210-1 minimum illumination 
requirements as currently stated in 10 CFR 50.55(b)(2)(ix)(B).
2.2.1.4  Bolting Acceptance Standard
    The proposed modification in 10 CFR 50.55a(b)(2)(ix)(H) would 
require licensees to use the acceptance standard of IWC-3513 of the 
1998 Edition, the 1999 Addenda, and the 2000 Addenda to evaluate flaws 
in pressure-retaining bolting that is greater than or equal to 51 
millimeters [2.0 inches] in diameter identified during the examination 
of containment surfaces in lieu of the ``owner-defined'' acceptance 
standard of IWE-3510.1 of the 1998 Edition, the 1999 Addenda, and the 
2000 Addenda. Prior to the 1998 Edition, IWE-3515.1 specified an NRC-
approved acceptance standard for evaluating bolting flaws. However, the 
bolting acceptance standard in IWE-3515.1 was deleted in the 1998 
Edition and the ``owner-defined'' acceptance standard in IWE-

[[Page 40629]]

3510.1 was added. The revised Code provision does not provide any 
criteria that the licensee must use when developing an acceptance 
standard for evaluating bolting flaws. The acceptance standard in IWC-
3513 has been approved by the NRC for evaluating bolting flaws, and the 
NRC is proposing that the acceptance standard in IWC-3513 be used to 
evaluate flaws in containment pressure-retaining bolting that is 
greater than or equal to 51 millimeters [2.0 inches] in diameter.
2.2.2  Examination of Containment Bolted Connections
    The proposed modification in 10 CFR 50.55a(b)(2)(ix)(I)(1) through 
(4) would require licensees to supplement the examination requirements 
for containment bolted connections in Table IWE-2500-1, Examination 
Category E-A, Items E1.10 and E1.11, of the 1998 Edition, the 1999 
Addenda, and the 2000 Addenda with additional examination requirements. 
Prior to the 1998 Edition, the provisions in Table IWE-2500-1 required 
a VT-1 visual examination on 100 percent of the pressure-retaining 
bolting, as well as a torque test of each bolted connection. The 
provisions in the 1998 Edition, the 1999 Addenda, and the 2000 Addenda 
relax these requirements and state that a general visual examination of 
100 percent of bolted surfaces is to be conducted during each 
inspection interval, without requiring the torque test of bolts. These 
provisions will not identify flaws or degradation in inaccessible 
areas, nor will the acceptance criteria for general visual examinations 
provide sufficient guidance for the acceptance of flaws. Therefore, the 
proposed modification in 10 CFR 50.55a(b)(2)(ix)(I)(1) through (4) 
would require that licensees supplement the examination requirements 
for containment bolted connections in Table IWE-2500-1, Examination 
Category E-A, Items E1.10 and E1.11, with the following--
     The general visual examination must include the 
examination of bolted connections that are disassembled at the time of 
a scheduled inspection.
     A detailed visual examination must be performed for areas 
where flaws or degradation are indicated.
     Damaged bolted connections must be disassembled and a 
detailed visual examination of the bolted connection components must be 
performed.
     If a bolted connection is disassembled at times other than 
a periodic (or planned) inspection and is not examined by a qualified 
visual examiner before reassembly, written maintenance procedures must 
be followed to ensure that the integrity of the reassembled bolted 
connection is maintained. The written procedures must include 
acceptance criteria for the continued use of all parts of the 
connection including bolts, studs, nuts, bushings, washers, threads in 
base material, and flange ligaments between fastener holes.
2.2.3  Acceptance Standard for Surfaces Requiring Augmented Ultrasonic 
Examinations
    The proposed modification in 10 CFR 50.55a(b)(2)(ix)(J) would 
require that the ultrasonic (UT) examination acceptance standard 
specified in IWE-3511.3 of the 1998 Edition, the 1999 Addenda, and the 
2000 Addenda for Class MC pressure-retaining components also apply to 
metallic liners of Class CC pressure-retaining components. The 1995 
Edition applied the same UT acceptance standard to both Class MC and 
metallic liners of Class CC pressure-retaining components. The 
acceptance standard was revised in the 1995 Addenda to apply only to 
Class MC pressure-retaining components. A UT acceptance standard is 
needed for metallic liners of Class CC pressure-retaining components to 
evaluate conditions that are identified during an examination that may 
be unacceptable. Therefore, the NRC proposes to continue to use the UT 
acceptance standard in IWE-3511.3 for metallic liners of Class CC 
pressure-retaining components.
2.2.4  Containment Penetration Piping
    The proposed limitation in 10 CFR 50.55a(b)(2)(xii)(A) would not 
allow welds in high-energy fluid system piping that are located inside 
a containment penetration assembly or encapsulated by a guard pipe to 
be exempted from examination provisions of Subsection IWC as permitted 
by IWC-1223 of the 1997 Addenda, the 1998 Edition, the 1999 Addenda, 
and the 2000 Addenda. The provisions of the Code that exempted 
containment penetration piping welds located inside a containment 
penetration assembly or encapsulated by a guard pipe from Subsection 
IWC examination requirements were incorporated into IWC-1223 in the 
1994 Addenda. These provisions conflict with the ``break exclusion 
zone'' design and examination criteria developed by the NRC that are 
utilized for most containment penetration piping. Branch Technical 
Position EMEB 3-1, ``Postulated Rupture Locations in Fluid System 
Piping Inside and Outside Containment,'' an attachment to NRC Standard 
Review Plan (SRP) Section 3.6.2, ``Determination of Rupture Locations 
and Dynamic Effects Associated with Postulated Rupture of Piping'' 
(NUREG-0800), allows that breaks and cracks in high-energy fluid piping 
in containment penetration areas need not be postulated provided that 
where guard pipes are used, the enclosed portion of fluid system piping 
is seamless construction and without circumferential welds unless 
specific access provisions are made to permit inservice volumetric 
examination of the longitudinal and circumferential welds; and a 100 
percent volumetric inservice examination of all pipe welds is conducted 
during each inspection interval as defined in IWA-2400 of Section XI of 
the ASME BPV Code.
    In designs where these welds are inaccessible, relief from 
impractical Code requirements will continue to be granted by the NRC 
when appropriate bases are provided by the licensee under 10 CFR 
50.55a(g)(5). The proposed limitation does not apply to moderate-energy 
fluid system piping. Licensees would be permitted to exempt welds in 
moderate-energy system piping that are located inside a containment 
penetration assembly or encapsulated by a guard pipe from examination 
in accordance with IWC-1223. The definitions of high-and moderate-
energy fluid systems are contained in SRP Section 3.6.1, ``Plant Design 
for Protection Against Postulated Piping Failures in Fluid Systems 
Outside Containment'' (NUREG-0800).
    The proposed limitation in 10 CFR 50.55a(b)(2)(xii)(B) would not 
allow piping that penetrates the containment that is connected to 
piping outside the scope of Section XI to be exempted from the pressure 
testing provisions of Subsection IWA as permitted by IWA-5110(c) of the 
1997 Addenda, the 1998 Edition, the 1999 Addenda, and the 2000 Addenda. 
Paragraph IWA-5110(c) of the 1997 Addenda incorporated the provisions 
of Code Case N-522, ``Pressure Testing of Containment Penetration 
Piping,'' to allow piping that penetrates containment to be exempted 
from periodic system pressure testing when the piping and containment 
isolation valves perform a containment function, and the balance of the 
piping is not in the scope of Section XI. As discussed in the preceding 
paragraph, volumetric examinations of welds are no longer required for 
moderate-energy containment penetration piping. Therefore, pressure 
testing is the only practicable remaining ISI method capable of 
detecting through-wall leakage in the piping. Moderate-energy 
containment penetration piping must be

[[Page 40630]]

included in ISI programs that are capable of identifying any through-
wall leakage. The NRC notes that containment penetration piping is 
required to be tested in accordance with Appendix J to 10 CFR Part 50, 
``Primary Reactor Containment Leakage Testing for Water-Cooled Power 
Reactors.'' However, the Appendix J test requirements do not contain 
provisions for the detection and location of through-wall leakage in 
containment penetration piping.
2.2.5  Certification of Nondestructive Examination (NDE) Personnel
    The proposed modification in 10 CFR 50.55a(b)(2)(xviii)(A) would 
require Level I and II NDE personnel and personnel qualified under the 
Nondestructive Testing Control Certifications Program to be recertified 
on a 3-year interval in lieu of the 5-year interval specified in IWA-
2314 of the 1997 Addenda and the 1998 Edition, and IWA-2314(a) and IWA-
2314(b) of the 1999 Addenda and the 2000 Addenda. Prior to 1997, Level 
I and II NDE personnel and personnel qualified under the Nondestructive 
Testing Control Certifications Program were recertified on a 3-year 
interval. Paragraph IWA-2314 of the 1997 Addenda incorporated the 
provisions of Code Case N-574, ``NDE Personnel Recertification 
Frequency,'' which increased the recertification interval from 3 years 
to 5 years. The proficiency of examination personnel decreases over 
time, and available data do not support recertification examinations at 
a frequency of every 5 years.
    The proposed modification in 10 CFR 50.55a(b)(2)(xviii)(B) would 
supplement the alternative qualification provisions for VT-2 visual 
examination personnel in IWA-2316 of the 1998 Edition, the 1999 
Addenda, and the 2000 Addenda. Paragraph IWA-2316 was added to the 1998 
Edition of Section XI and incorporates the provisions of Code Case N-
546, ``Alternative Requirements for Qualification of VT-2 Examination 
Personnel, Section XI, Division 1.'' Paragraphs IWA-2310 through IWA-
2314 also provide provisions that can be used to qualify VT-2 visual 
examination personnel. Prior to 1998, the NRC-approved provisions in 
IWA-2310 through IWA-2314 were used to qualify VT-2 visual examination 
personnel. These provisions require that VT-2 visual examination 
personnel pass an initial qualification examination and periodic 
recertification examinations. The alternative qualification provisions 
for VT-2 visual examination personnel in IWA-2316 do not address 
initial qualification or periodic recertification examinations. 
Therefore, the NRC is proposing that when qualifying VT-2 visual 
examination personnel in accordance with IWA-2316, the proficiency of 
the training must be demonstrated by administering an initial 
qualification examination and administering recertification 
examinations on a 3-year interval. The implementation of IWA-2316 is 
applicable only to the performance of VT-2 visual examinations.
    The proposed modification in 10 CFR 50.55a(b)(2)(xviii)(C) would 
supplement the alternative qualification provisions for VT-3 visual 
examination personnel in IWA-2317 of the 1998 Edition, the 1999 
Addenda, and the 2000 Addenda. Paragraph IWA-2317 was added to the 1998 
Edition of Section XI and applies the provisions of Code Case N-546 to 
the qualification of VT-3 visual examination personnel. Paragraphs IWA-
2310 through IWA-2314 also provide provisions that can be used to 
qualify VT-3 visual examination personnel. Prior to 1998, the NRC-
approved provisions in IWA-2310 through IWA-2314 were used to qualify 
VT-3 visual examination personnel. These provisions require that VT-3 
visual examination personnel pass an initial qualification examination 
and periodic recertification examinations. The alternative 
qualification provisions for VT-3 visual examination personnel in IWA-
2317 do not address initial qualification or periodic recertification 
examinations. Therefore, the NRC is proposing that when qualifying VT-3 
visual examination personnel in accordance with IWA-2317, the 
proficiency of the training must be demonstrated by administering an 
initial qualification examination and administering recertification 
examinations on a 3-year interval. The implementation of IWA-2317 is 
applicable only to the performance of VT-3 visual examinations.
2.2.6  Substitution of Alternative Methods
    The proposed limitation in 10 CFR 50.55a(b)(xix) would prohibit the 
use of the provision in IWA-2240 (1998 Edition, 1999 Addenda, and 2000 
Addenda) and IWA-4520(c) (1997 Addenda, 1998 Edition, 1999 Addenda, and 
2000 Addenda), which allows alternative examination methods, a 
combination of methods, or newly developed techniques to be substituted 
for the methods specified in the Construction Code, provided the 
Authorized Nuclear Inspector (ANI) is satisfied that the results are 
demonstrated to be equivalent or superior to those in the Construction 
Code. Paragraphs IWA-2240, 1998 Edition, and IWA-4520(c), 1997 Addenda, 
incorporate the provisions of Code Case N-587, ``Alternative NDE 
Requirements for Repair/Replacement Activities.'' The NDE requirements 
of the Construction Code are different from those of Section XI because 
the objectives of the examinations differ. The NDE methods and the 
qualification and examination criteria of the Construction Code serve 
to identify fabrication-and construction-related defects in components. 
The NDE methods and the qualification and examination criteria 
specified in Section XI serve to identify service-related and age-
related degradation in components after having been placed in 
operation. Methods, techniques, and criteria associated with 
construction and fabrication are not necessarily interchangeable or 
compatible with those of inservice inspection. Furthermore, there are 
examination coverage, volume, flaw acceptance, and qualification 
requirements related to these respective methods that are outside the 
scope of an ANI's responsibility. By introducing the Construction Code 
to paragraphs IWA-2240 and IWA-4520(c), the requirements of Section XI 
and the Construction Code become intertwined and the objectives of the 
examinations as well as the associated methods, qualifications and 
examination criteria become blurred. Construction Code examinations 
validate the integrity of the entire weld and the integrity of the 
fabrication material with full-volume examinations, whereas Section XI 
examinations validate the integrity of welds based on partial volume 
examinations and different criteria. These differences are not 
mentioned in IWA-2240 or IWA-4520(c). As a result, use of IWA-2240 and 
IWA-4520(c) could allow the improper application of a Section XI 
examination in lieu of a Construction Code examination, resulting in a 
component having welds whose integrity was never verified by a full 
volume examination. The NRC finds that IWA-2240 and IWA-4520(c) as 
applied to the Construction Code, are unacceptably broad and could 
allow unacceptable welds and components to be installed and placed in 
operation. Therefore, the substitution of alternative examination 
methods, a combination of methods, or newly developed techniques 
permitted by IWA-2240 and IWA-4520(c) for methods specified in the 
Construction Code are inappropriate.

[[Page 40631]]

2.2.7  System Leakage Tests
    The proposed limitation in 10 CFR 50.55a(b)(2)(xx) would require 
that the pressure and temperature hold time requirements of IWA-5213(a) 
of the 1995 Edition be applied in lieu of the revised provisions of 
IWA-5213(a) of the 1997 Addenda, the 1998 Edition, the 1999 Addenda, 
and the 2000 Addenda when performing system leakage tests. The 1995 
Addenda incorporates the provisions of Code Case N-498-2, ``Alternative 
Requirements for System Leakage Testing for Class 1, 2, and 3 
Systems,'' which deleted the provisions requiring system pressure and 
temperature conditions to be maintained for 4 hours on insulated 
systems or components, or 10 minutes on noninsulated systems or 
components, prior to conducting system leakage tests. The 4-hour and 
10-minute hold times are needed because--
    (1) The capability to detect and locate a small leak is directly 
proportional to the hold times of a pressurized system, particularly if 
the system is insulated;
    (2) System leakage tests, if performed without hold times, may be 
insensitive to small leaks because long hold times are necessary for 
them to become visible; and
    (3) Small leaks might not be detected by any other means (such as 
system walkdowns, installed leak detection systems, or leakage 
monitoring programs).
2.2.8  Table IWB-2500-1 Examination Requirements
    The proposed limitation in 10 CFR 50.55a(b)(2)(xxi)(A) would 
require licensees to use the provisions of Table IWB-2500-1, 
Examination Category B-D, Items B3.40 and B3.60 (Inspection Program A) 
and Items B3.120 and B3.140 (Inspection Program B) of the 1997 Addenda 
and 1998 Edition when using the 1999 Addenda and the 2000 Addenda. The 
1999 Addenda incorporates the provisions of Code Case N-619, 
``Alternative Requirements for Nozzle Inner Radius Inspections for 
Class 1 Pressurizer and Steam Generator Nozzles.'' Code Case N-619 
eliminated the pressurizer and steam generator nozzle inside radius 
inspections in Table IWB-2500-1, Examination Category B-D, Items B3.40 
and B3.60 (Inspection Program A) and Items B3.120 and B3.140 
(Inspection Program B). Given the inservice examination data available 
for these components, the NRC finds there is inadequate safety basis to 
support the elimination of inservice examination of steam generator and 
pressurizer nozzle inner radii. Furthermore, the ASME Code is 
considering a revision to Code Case N-619 that would reinstate some 
alternate examination requirements. Therefore, the NRC is proposing 
that pressurizer and steam generator nozzle inside radius inspections 
be retained in ISI programs.
    The proposed limitation in 10 CFR 50.55a(b)(2)(xxi)(B) would 
require licensees to apply the provisions of Table IWB-2500-1, 
Examination Category B-G-2, Item B7.80, of the 1995 Edition when using 
the 1997 Addenda, the 1998 Edition, the 1999 Addenda, and the 2000 
Addenda. The 1995 Addenda incorporates the provisions of Code Case N-
547, ``Alternative Examination Requirements for Pressure Retaining 
Bolting of Control Rod Drive Housings.'' Code Case N-547 deletes the 
examination of control rod drive (CRD) bolting whenever the CRD housing 
is disassembled. The examination of CRD bolting is appropriate prior to 
reinstallation because bending and galling of threads, and other damage 
to bolting, can occur when performing maintenance activities that 
require the removal and reinstallation of bolting. Inservice 
examination of bolting to be reused is appropriate in order to verify 
that service-related degradation of components is not occurring, and 
that the bolting was not damaged during the maintenance activity. 
Therefore, the NRC is proposing that the examination of CRD bolting be 
retained in ISI programs.
    The proposed limitation in 10 CFR 50.55a(b)(2)(xxi)(C) would 
require licensees to use the provisions of Table IWB-2500-1, 
Examination Category B-K, Item B10.10, of the 1995 Addenda when using 
the 1997 Addenda, the 1998 Edition, the 1999 Addenda, and the 2000 
Addenda. The 1997 Addenda incorporates the provisions of Code Case N-
323-1, Alternative Examination for Welded Attachments to Pressure 
Vessels.'' Code Case N-323-1 permits performance of a single-side 
surface examination in lieu of a surface examination from both sides of 
the weld, whereas the 1995 Addenda requires the performance of a 
single-side volumetric examination of the attachment weld if surface 
examination from both sides of the weld is not performed. The 
provisions of Code Case N-323-1 do not provide a level of quality and 
safety equivalent to that provided in the 1995 Addenda. A single-side 
surface examination is not sufficient because it would not identify 
flaws that would be identified by a single-side volumetric examination 
or a surface examination from both sides of the weld.
2.2.9  Supplemental Annual Training Requirements for Ultrasonic 
Examiners
    The proposed limitation in 10 CFR 50.55a(b)(2)(xxii) would require 
licensees to apply the UT examiner supplemental annual training 
provisions of Appendix VII, paragraph VII-4240, of the 1998 Edition 
when using the 1999 Addenda and the 2000 Addenda. The 1999 Addenda 
incorporates the provision of Code Case N-583, ``Annual Training 
Alternative, Section XI, Division 1.'' Code Case N-583 requires at 
least eight hours per year of practice of UT examination techniques by 
examining or by analyzing prerecorded data from material or welds 
containing flaws similar to those that may be encountered during 
inservice examination. However, the code case only provides training 
for techniques associated with data recording capabilities and does not 
provide for training using manual techniques. Hence the training 
alternative of Code Case N-583 is not sufficient because it is less 
complete than that provided by Appendix VII, paragraph VII-4240, of the 
1998 Edition.
2.2.10  Underwater Welding
    The proposed modification in 10 CFR 50.55a(b)(2)(xxiii) would 
require licensees to demonstrate the acceptability of the underwater 
welding method through the use of a mockup using material with similar 
neutron fluence levels, when welding on high neutron fluence Class 1 
material underwater in accordance with IWA-4660, of the 1997 Addenda, 
the 1998 Edition, the 1999 Addenda, and the 2000 Addenda. The 1997 
Addenda incorporates the provisions of Code Case N-516-1, ``Underwater 
Welding, Section XI, Division 1,'' which provides for alternative 
welding methods to those required by IWA-4000. The provisions of the 
code case are acceptable. However, due to susceptibility of cracking in 
high neutron irradiated steel material, the acceptability of the 
underwater welding method on high neutron fluence Class 1 material must 
be demonstrated on a mockup, using material with similar neutron 
fluence levels to verify that adequate crack prevention measures were 
used. Reactor vessel and internals are typically high neutron fluence 
Class 1 material. Use of a mockup is necessary because weld repairs 
using conventional welding techniques on in-vessel components exposed 
to high neutron fluences may be unsuccessful due to helium induced 
cracking and radiation damage, unless special welding techniques are 
used.

[[Page 40632]]

2.3  Appendix VIII to Section XI

    The proposed rule would extend the provisions in 10 CFR 
50.55a(b)(2)(xv) to the 1997 Addenda, the 1998 Edition, the 1999 
Addenda, and the 2000 Addenda of Appendix VIII of Section XI of the 
ASME BPV Code. The proposed rule would also revise 10 CFR 
50.55a(b)(2)(xv)(G)(4) and 50.55a(b)(2)(xv)(K)(1)(i), as discussed in 
Sections 2.3.2 and 2.3.3, to update and clarify existing Appendix VIII 
UT examination qualification requirements. The proposed rule would also 
revise 10 CFR 50.55a(b)(2)(xv)(A), (A)(1), and (A)(2), and 10 CFR 
50.55a(g)(6)(ii)(C)(1), and add 10 CFR 50.55a(b)(2)(xv)(M) and 
50.55a(g)(6)(ii)(C)(2), as discussed in Sections 2.3.1 and 2.3.4, to 
clarify the coordination of Appendix VIII with other parts of Section 
XI.
2.3.1  Examination Coverage for Dissimilar Metal Pipe Welds
    The proposed revision to 10 CFR 50.55a(b)(2)(xv)(A), (A)(1), and 
(A)(2), would update the UT examination coverage criteria to include 
examination coverage criteria for dissimilar metal piping welds when 
using personnel, procedures and equipment that are qualified in 
accordance with Supplement 10, ``Qualification Requirements for 
Dissimilar Metal Piping Welds,'' of Appendix VIII to Section XI. 
Currently, 10 CFR 50.55a(b)(2)(xv) provides the examination coverage 
requirements for those licensees who voluntarily choose to implement 
the Electric Power Research Institute (EPRI) Performance Demonstration 
Initiative (PDI) methodology to meet the qualification requirements of 
Appendix VIII to Section XI. However, 10 CFR 50.55a(b)(2)(xv) does not 
address the examination coverage requirements for dissimilar metal 
piping welds. Although examination coverage requirements for dissimilar 
metal piping welds are addressed in the 1989 Edition, and earlier 
editions and addenda of Section XI, these requirements are not 
addressed in later editions and addenda of Section XI. Therefore, the 
proposed revision to 10 CFR 50.55a(b)(2)(xv)(A), (A)(1) and (A)(2) 
provides examination coverage requirements for dissimilar metal piping 
welds that are consistent with the examination coverage requirements in 
the 1989 Edition and earlier editions and addenda of Section XI.
2.3.2  Reactor Vessel Single Side Examinations
    The provisions in 10 CFR 50.55a(b)(2)(xv)(G)(4), which specify the 
same examination criteria as those contained in 10 CFR 
50.55a(b)(2)(xv)(G)(3), are redundant and unnecessary and, therefore, 
would be deleted.
2.3.3  Qualification Test Samples
    The proposed revision to 10 CFR 50.55a(b)(2)(xv)(K)(1)(i) would 
resolve a discrepancy between 10 CFR 50.55a(b)(2)(xv)(K)(1)(i) and 
50.55a(b)(2)(xv)(K)(4). Currently, 10 CFR 50.55a(b)(2)(xv)(K)(1)(i) 
states that flaws that are perpendicular to the weld are not required 
to be included in the qualification test sample. This requirement 
conflicts with a provision in 10 CFR 50.55a(b)(2)(xv)(K)(4), which 
states that test samples must contain flaws that are perpendicular to 
the weld in the inner 15 percent of the weld, but that these same flaws 
are not required to be located in the outer 85 percent of the weld. The 
proposed revision to 10 CFR 50.55a(b)(2)(xv)(K)(1)(i) would clarify 
that flaws perpendicular to the weld located in the outer 85 percent of 
the weld are not required to be included in the qualification test 
sample.
2.3.4  Implementation of Appendix VIII to Section XI
    The proposed 10 CFR 50.55a(b)(2)(xv)(M) would clarify that only the 
provisions in Supplement 12 to Appendix VIII that are related to the 
coordinated implementation of Supplement 3 to Supplement 2 performance 
demonstrations are required to be implemented. Supplement 12 provides 
provisions for coordinated implementation of selected aspects of 
Supplements 2, 3, 10, and 11; however, Supplement 12 does not provide 
provisions for the coordinated implementation of Supplement 2 or 
Supplement 11 performance demonstrations to Supplements 3 and 10; and 
does not contain guidance for implementing single-side examinations as 
part of the coordinating process.
    The proposed revision to 10 CFR 50.55a(g)(6)(ii)(C)(1) would 
clarify that Appendix VIII to Section XI, 1995 Edition with the 1996 
Addenda, as well as its supplements, would be required. Although the 
final rule that implemented Appendix VIII (64 FR 51370; September 22, 
1999) requires a phased implementation of Appendix VIII over a 3-year 
period, the final rule addressed the implementation of the Appendix 
VIII supplements only and failed to mention the implementation of 
Appendix VIII itself. The failure to address the implementation of 
Appendix VIII was an oversight. The proposed revision would also 
eliminate Supplements 12 and 13 of Appendix VIII from the 
implementation schedule that is currently in 10 CFR 
50.55a(g)(6)(ii)(C)(1). Supplements 12 and 13 coordinate the 
implementation of selected aspects of Supplements 2, 3, 4, 5, 6, 7, 10, 
and 11 of Appendix VIII. Since the implementation schedule for 
Supplements 2, 3, 4, 5, 6, 7, 10, and 11 of Appendix VIII is addressed 
in 10 CFR 50.55a(g)(6)(ii)(C)(1), the imposition of a mandatory 
implementation date for Supplements 12 and 13 is redundant.
    The proposed 10 CFR 50.55a(g)(6)(ii)(C)(2) would clarify that the 
requirements of Appendix VIII and the supplements to Appendix VIII to 
Section XI, of the 1995 Edition and later editions and addenda, apply 
when implementing IWA-2232 of the edition and addenda of Section XI 
that are referenced in the ISI program Code of Record. Paragraph IWA-
2232 provides the rules for conducting the UT examinations required by 
Section XI. Appendix VIII was introduced into Section XI in the 1989 
Addenda. Before that time, Appendix VIII did not exist in the Code. As 
a result, IWA-2232 of the 1989 Edition and earlier editions and addenda 
of Section XI did not reference Appendix VIII, and therefore, the 
relationship between Appendix VIII and IWA-2232 is not clearly defined 
for those licensees who are using these earlier editions and addenda of 
Section XI. The final rule in 64 FR 51370 (September 22, 1999) imposed 
an expedited implementation of the supplements to Appendix VIII to 
Section XI, 1995 Edition with the 1996 Addenda, on all licensees. 
Therefore, the requirement to apply the provisions of Appendix VIII to 
Section XI, 1995 Edition or later editions and addenda, when 
implementing IWA-2232 is applicable to all licensees, including those 
licensees whose ISI programs are based on the 1989 Edition or earlier 
editions and addenda.

2.4  ASME OM Code

    The proposed revision to 10 CFR 50.55a(b)(3) would incorporate by 
reference the 1997 Addenda, the 1998 Edition, the 1999 Addenda, and the 
2000 Addenda of the ASME OM Code. The proposed amendment would extend 
the requirements in 10 CFR 50.55a(b)(3)(ii), 50.55a(b)(3)(iii), 
50.55a(b)(3)(iv), and 50.55a(b)(3)(v) to the 1997 Addenda, the 1998 
Edition, the 1999 Addenda, and the 2000 Addenda of the ASME OM Code. 
Subsections of the ASME OM Code were renumbered in the 1998 Edition; 
therefore, 10 CFR 50.55a(b)(3)(ii), 50.55a(b)(3)(iii), and 
50.55a(b)(3)(iv) were revised and 50.55a(b)(3)(iii)(D) was added to 
account for the renumbering. Currently, (b)(3)(ii) references ISTC 4.2 
of the 1995

[[Page 40633]]

Edition with the 1996 Addenda. Subsection ISTC 4.2 was renumbered to 
ISTC-3500 in the 1998 Edition, therefore (b)(3)(ii) is revised to 
reference ISTC-3500. Currently, (b)(3)(iii) references ISTC 4.3 of the 
1995 Edition with the 1996 Addenda. Subsection ISTC 4.3 was renumbered 
to ISTC-3600 in the 1998 Edition, therefore (b)(3)(iii) is revised to 
reference ISTC-3600. Currently, (b)(3)(iv)((C) references ISTC 4.5.1 
through 4.5.4 of the 1995 Edition with the 1996 Addenda. Paragraphs 
ISTC 4.5.1 through 4.5.4 were renumbered and reorganized in the 1998 
Edition. These same provisions are now in ISTC-3510, ISTC-3520, ISTC-
3540, and ISTC-5221 of the 1998 Edition, the 1999 Addenda, and the 2000 
Addenda. Therefore, (b)(3)(iv)(D) is added to reference ISTC-3510, 
ISTC-3520, ISTC-3540, and ISTC-5221, and (b)(3)(iv) is revised to 
require that (b)(3)(iv)(D) be used in lieu of (b)(3)(iv)(C) when using 
the 1998 Edition, the 1999 Addenda, and the 2000 Addenda.
    The proposed modification in 10 CFR 50.55a(b)(3)(vi) would require 
an exercise interval of 2 years for manual valves within the scope of 
the ASME OM Code in lieu of the exercise interval of 5 years specified 
in the 1999 Addenda and the 2000 Addenda of the ASME OM Code. The 1998 
Edition of the ASME OM Code (and previous Code editions and addenda) 
specified an exercise interval of 3 months for manual valves within the 
scope of the Code. The 1999 Addenda to the ASME OM Code revised ISTC-
3540 to extend the exercise frequency for manual valves to 5 years, 
provided that adverse conditions do not require more frequent testing. 
The NRC does not consider that sufficient justification exists at this 
time to allow the significant extension of the exercise interval for 
manual valves from 3 months to 5 years. Operating experience has 
revealed that a manual valve can become incapable of operating when not 
exercised or maintained over a long period of time. See, for example, 
NRC Information Notice 86-61 (July 28, 1986), ``Failure of Auxiliary 
Feedwater Manual Isolation Valve.'' The general provision in the 1999 
Addenda and the 2000 Addenda of the ASME OM Code regarding the absence 
of adverse conditions does not provide adequate guidance to allow a 
Code user to determine that a manual valve can remain idle for 5 years 
without adversely impacting its operating capability. The modification 
to the ASME OM Code in this proposed rule allows a significant 
relaxation of the exercising requirement for manual valves. Further, 
the proposed rule specifies an exercise interval for manual valves 
within the scope of the ASME OM Code consistent with the time period 
for general experience with the operation of plant equipment over a 
refueling cycle.

3. Section-by-Section Analysis of Substantive Changes

    Paragraph (b)(1). The proposed revision would incorporate by 
reference the 1997 Addenda, the 1998 Edition, the 1999 Addenda, and the 
2000 Addenda of Division 1 of Section III of the ASME BPV Code. New 
applicants for a nuclear power plant submitting an application for a 
construction permit under 10 CFR Part 50 or design certification under 
10 CFR Part 52 would be required to use the 1998 Edition up to and 
including the 2000 Addenda for the design and construction of the 
reactor coolant pressure boundary and Quality Group B and C components.
    Paragraph (b)(1)(ii). The proposed revision would extend the 
limitation on weld leg dimension requirements to the 1997 Addenda, the 
1998 Edition, the 1999 Addenda, and the 2000 Addenda of Section III of 
the ASME BPV Code. Applicants and licensees using these Edition and 
Addenda would not be able to apply paragraph NB-3683.4(c)(1), Footnote 
11 to Figure NC-3673.2(b)-1, and Figure ND-3673.2(b)-1.
    Paragraph (b)(1)(iii). The proposed revision would extend the 
limitation on seismic design requirements to the 1997 Addenda, the 1998 
Edition, the 1999 Addenda, and the 2000 Addenda of Section III of the 
ASME BPV Code. Applicants and licensees using these edition and addenda 
would not be able to use Articles NB-3200, NB-3600, NC-3600, and ND-
3600.
    Paragraph (b)(1)(v). The proposed revision would extend the 
limitation on independence of inspection requirements to the 1997 
Addenda, the 1998 Edition, the 1999 Addenda, and the 2000 Addenda of 
Section III of the ASME BPV Code. Applicants and licensees using these 
edition and addenda would not be able to apply Sub-subparagraph NCA-
4134.10(a).
    Paragraph (b)(2). The proposed revision would incorporate by 
reference the 1997 Addenda, the 1998 Edition, the 1999 Addenda, and the 
2000 Addenda of Division 1 of Section XI of the ASME BPV Code. 
Licensees of nuclear power plants would be required to use the 1998 
Edition up to and including the 2000 Addenda when updating their ISI 
programs in their subsequent 120-month interval under 10 CFR 
50.55a(g)(4).
    Paragraph (b)(2)(viii). The proposed revision would extend the 
existing modification in paragraph (b)(2)(viii)(E) on concrete 
containment examination requirements to the 1998 Edition, the 1999 
Addenda, and the 2000 Addenda of Section XI of the ASME BPV Code and 
clarifies that the new modification in paragraph (b)(2)(viii)(F) would 
apply only to the 1998 Edition with the 1999 Addenda and the 2000 
Addenda.
    Paragraph (2)(viii)(F). The proposed modification would require 
that personnel who perform visual inspections of containment surfaces 
and tendon anchorage hardware, wires, or strands be qualified in 
accordance with IWA-2300 in lieu of the ``owner-defined'' personnel 
qualification provision in IWE-2310(d).
    Paragraph (b)(2)(ix). The proposed revision would clarify that the 
existing modifications in paragraphs (b)(2)(ix)(A) through (E) of this 
section on examination of metal containments and liners of Class CC 
components apply to Subsection IWE, 1992 Edition with the 1992 Addenda 
or the 1995 Edition with the 1996 Addenda. It would also extend the 
modifications in paragraphs (b)(2)(ix)(A) and (b)(2)(ix)(B) to the 1998 
Edition, the 1999 Addenda, and the 2000 Addenda of Section XI of the 
ASME BPV Code, and clarifies that the new proposed modifications in 
paragraphs (b)(2)(ix)(F) through (J) would apply only to the 1998 
Edition with the 1999 Addenda and 2000 Addenda.
    Paragraph (b)(2)(ix)(F). The proposed modification would require 
that personnel who perform visual inspections of containment surfaces 
be qualified in accordance with IWA-2300 in lieu of the ``owner-
defined'' personnel qualification provision in IWE-2330(a).
    Paragraph (b)(2)(ix)(G). The proposed modification would require 
that the general and detailed visual examinations specified in IWE-
2310(b) and IWE-2310(c) meet the VT-3 and VT-1 examination provisions 
in IWA-2210 in lieu of the ``owner-defined'' general and detailed 
visual examination provisions in IWE-2310(a).
    Paragraph (b)(2)(ix)(H). The proposed modification would require 
the use of the acceptance standard in IWC-3513 to evaluate flaws in 
pressure-retaining bolting identified during the examination of 
containment surfaces, in lieu of the ``owner-defined'' acceptance 
standard of IWE-3510.1.
    Paragraph (b)(2)(ix)(I)(1) through (4). The proposed modification 
would supplement the examination requirements for containment bolted 
connections that are in Table IWE-2500-1, Examination Category E-A, 
Items E1.10 and E1.11.

[[Page 40634]]

    Paragraph (b)(2)(ix)(J). The proposed modification would require 
that the UT examination acceptance standard specified in IWE-3511.3 for 
Class MC pressure-retaining components also apply to metallic liners of 
Class CC pressure-retaining components.
    Paragraph (b)(2)(xi). The proposed revision would extend the 
limitation on Class 1 piping exempted from ISI requirements to the 1997 
Addenda, 1998 Edition, the 1999 Addenda, and the 2000 Addenda of 
Section XI of the ASME BPV Code. Licensees using this edition and these 
addenda would be required to use IWB-1220 from the 1989 Edition.
    Paragraph (b)(2)(xii)(A). The proposed limitation would not allow 
welds in high-energy fluid system piping that are located inside a 
containment penetration assembly or encapsulated by a guard pipe to be 
exempted from the examination provisions of Subsection IWC as permitted 
by IWC-1223. In designs where these welds are inaccessible, relief from 
impractical Code requirements will continue to be granted by the NRC 
when appropriate bases are provided by the licensee pursuant to 10 CFR 
50.55a(g)(5). The proposed limitation would not apply to moderate-
energy fluid system piping. Licensees would be permitted to exempt 
welds in moderate-energy system piping that are located inside a 
containment penetration assembly or encapsulated by a guard pipe from 
examination in accordance with IWC-1223.
    Paragraph (b)(2)(xii)(B). The proposed limitation would not allow 
containment penetration piping that is connected to piping outside the 
scope of Section XI to be exempted from the pressure test provisions of 
Subsection IWA as permitted by IWA-5110(c) of the 1997 Addenda, the 
1998 Edition, 1999 Addenda, and 2000 Addenda.
    Paragraph (b)(2)(xv). The proposed revision would extend the 
modifications to Appendix VIII specimen set and qualification 
requirements to the 1997 Addenda, 1998 Edition, the 1999 Addenda, and 
the 2000 Addenda of Section XI of the ASME BPV Code. Licensees choosing 
to use these modifications would be required to apply all the 
modifications under paragraph (b)(2)(xv) except for those in 
(b)(2)(xv)(F) which are optional.
    Paragraphs (b)(2)(xv)(A), (A)(1), and (A)(2). The proposed revision 
would update the UT examination coverage criteria to include 
examination coverage criteria for dissimilar metal piping welds when 
using personnel, procedures and equipment that are qualified in 
accordance with Supplement 10 of Appendix VII to Section XI. Licensees 
are currently performing examinations of dissimilar metal piping welds 
in accordance with the requirements of the edition and addenda of 
Section XI of the ASME BPV Code applicable to their respective ISI 
programs, and are required to do so until November 22, 2002. At that 
time, licensees would be required to implement the dissimilar metal 
piping weld qualification requirements of Supplement 10 of Appendix 
VIII. On that date, and thereafter, licensees would no longer be 
permitted to examine dissimilar metal piping welds in accordance with 
the requirements of Section XI of the edition and addenda of the ASME 
BPV Code applicable to their respective ISI programs.
    Paragraph (b)(2)(xv)(G)(4). The proposed revision would delete 
paragraph (b)(2)(xv)(G)(4). This requirement is redundant with the 
requirement in paragraph (b)(2)(xv)(G)(3) and is unnecessary. As a 
result, this revision involves no substantive change.
    Paragraph (b)(2)(xv)(K)(1)(i). The proposed revision would clarify 
that flaws perpendicular to the weld located in the outer 85 percent of 
the weld are not required to be included in the qualification test 
sample. The proposed revision neither increases nor decreases current 
requirements, but would clarify conflicting requirements that currently 
exist.
    Paragraph (b)(2)(xv)(M). The proposed revision would clarify that 
only the provisions in Supplement 12 to Appendix VIII that are related 
to the coordinated implementation of Supplement 3 to Supplement 2 
performance demonstrations are required to be implemented.
    Paragraph (b)(2)(xvii). The proposed revision would extend the 
limitation on reconciliation of quality requirements to the 1997 
Addenda, 1998 Edition, the 1999 Addenda, and the 2000 Addenda of 
Section XI of the ASME BPV Code. Licensees using IWA-4200 of this 
edition and these addenda would be required to procure replacement and 
repair items under its approved quality assurance program required by 
10 CFR Part 50, Appendix B. The limitation would not permit licensees 
to use IWA-4200 to procure repair and replacement items to be used in 
ASME Code safety-related applications that are manufactured under a 
non-nuclear code or non-nuclear standard without an approved quality 
assurance program.
    Paragraph (b)(2)(xviii)(A). The proposed modification would require 
that Level I and II NDE personnel and personnel qualified under the 
Nondestructive Testing Control Certifications Program be recertified on 
a 3-year interval in lieu of the 5-year interval specified in IWA-2314.
    Paragraph (b)(2)(xviii)(B). The proposed modification would require 
that when qualifying VT-2 examination personnel in accordance with IWA-
2316, the proficiency of the training required under IWA-2316 must be 
demonstrated by administering initial qualification and recertification 
examinations. The implementation of IWA-2316 is only applicable to the 
performance of VT-2 visual examinations.
    Paragraph (b)(2)(xviii)(C). The proposed modification would require 
that when qualifying VT-3 examination personnel in accordance with IWA-
2317, the proficiency of the training required under IWA-2317 must be 
demonstrated by administering initial qualification and recertification 
examinations. The implementation of IWA-2317 is only applicable to the 
performance of VT-3 visual examinations.
    Paragraph (b)(2)(xix). The proposed limitation would prohibit the 
use of the provisions in IWA-2240 and IWA-4520(c) which would allow 
alternative examination methods, a combination of methods, or newly 
developed techniques to be substituted for the methods specified in the 
Construction Code during repair and replacement activities.
    Paragraph (b)(2)(xx). The proposed limitation would require that 
the system leakage test pressure and temperature hold time requirements 
of IWA-5213(a) of the 1995 Edition of Section XI be retained in ISI 
programs when using the 1997 Addenda, the 1998 Edition, the 1999 
Addenda, and the 2000 Addenda of Section XI. A 10-minute hold time for 
non-insulated systems and components or 4-hour hold time for insulated 
systems and components would be required after attaining system 
operating pressure.
    Paragraph (b)(2)(xxi)(A). The proposed limitation would require 
that pressurizer and steam generator nozzle inside-radius inspections 
be retained in ISI programs. Licensees would not be allowed to 
eliminate the pressurizer and steam generator nozzle inside-radius 
inspections of Table IWB-2500-1, Examination Category B-D, Items B3.40 
and B3.60 (Inspection Program A) and Items B3.120 and B3.140 
(Inspection Program B) as allowed by the 1999 Addenda and the 2000 
Addenda of Section XI.
    Paragraph (b)(2)(xxi)(B). The proposed limitation would require 
that the CRD bolting examinations of Table IWB-2500-1, Examination 
Category B-

[[Page 40635]]

G-2, Item B7.80, of the 1995 Addenda of Section XI be retained in ISI 
programs when using the 1997 Addenda, the 1998 Edition, the 1999 
Addenda, and the 2000 Addenda of Section XI.
    Paragraph (b)(2)(xxi)(C). The proposed limitation would require 
that the attachment weld single-side volumetric examination of Table 
IWB-2500-1, Examination Category B-K, Item B10.10, of the 1995 Addenda 
of Section XI be retained in ISI programs when using the 1997 Addenda, 
the 1998 Edition, the 1999 Addenda, and the 2000 Addenda of Section XI.
    Paragraph (b)(2)(xxii). The proposed limitation would not allow the 
use of the revised supplemental annual training requirements for UT 
examiners in Appendix VII, paragraph VII-4240, of the 1999 Addenda and 
2000 Addenda of Section XI. Licensees would be required to use the 
requirements in Appendix VII, paragraph VII-4240, of the 1998 Edition.
    Paragraph (b)(2)(xxiii). The proposed modification would require 
that the acceptability of underwater welding methods be demonstrated 
through the use of a mockup, when welding high neutron fluence Class 1 
material underwater in accordance with IWA-4660 of Section XI.
    Paragraph (b)(3). The proposed revision would incorporate by 
reference the 1997 Addenda, the 1998 Edition, the 1999 Addenda, and the 
2000 Addenda of the ASME OM Code. Licensees of nuclear power plants 
would be required to use the 1998 Edition up to and including the 2000 
Addenda when updating their inservice testing programs in their 
subsequent 120-month interval under 10 CFR 50.55a(f)(4).
    Paragraph (b)(3)(ii). The proposed revision would extend the 
modification to motor-operated valve stroke-time testing requirements 
to the 1997 Addenda, the 1998 Edition, the 1999 Addenda, and the 2000 
Addenda of the ASME OM Code, reconciling those subsections of the ASME 
OM Code that were renumbered in the 1998 Edition. Licensees using this 
edition and these addenda would be required to establish a program to 
ensure that MOVs continue to be capable of performing their design 
basis safety functions.
    Paragraph (b)(3)(iii). The proposed revision would extend the 
modification on Code Case OMN-1 to the 1997 Addenda, the 1998 Edition, 
the 1999 Addenda, and the 2000 Addenda of the ASME OM Code, reconciling 
those subsections of the ASME OM Code that were renumbered in the 1998 
Edition. The modification would continue to allow, as a voluntary 
alternative, licensees to use Code Case OMN-1 in lieu of the stroke-
time testing requirements of paragraph (b)(3)(ii) when using this 
edition and these addenda.
    Paragraph (b)(3)(iv). The proposed revision would extend the 
modifications in paragraphs (b)(3)(iv)(A), (B), and (C) on check valve 
condition monitoring requirements to the 1997 Addenda, the 1998 
Edition, the 1999 Addenda, and the 2000 Addenda of the ASME OM Code. 
There would be no substantive changes in the requirements, but rather 
they would be revised to reconcile the different subsection and 
paragraph numbers of the ASME OM Code that were renumbered in the 1998 
Edition.
    Paragraph (b)(3)(iv)(D). The proposed paragraph would not change 
requirements, but would rather reconcile, for the existing 
modification, the different subsection and paragraph numbers of the 
ASME OM Code that were renumbered in the 1998 Edition.
    Paragraph (b)(3)(v). The proposed revision would extend the snubber 
ISI requirements to the 1997 Addenda, the 1998 Edition, the 1999 
Addenda, and the 2000 Addenda of the ASME OM Code.
    Paragraph (b)(3)(vi). The proposed modification would require an 
exercise interval of 2 years for manual valves within the scope of the 
ASME OM Code in lieu of the exercise interval of 5 years specified in 
the 1999 Addenda and the 2000 Addenda of the ASME OM Code.
    Paragraphs (g)(6)(ii)(B)(1) through (4). The proposed revision 
would delete the containment examination requirements in 10 CFR 
50.55a(g)(6)(ii)(B)(1) through (4) because the implementation dates 
have expired and all licensees have completed their first containment 
inservice inspection requirements by that time or have been approved by 
an exemption for a delay; would add a new 10 CFR 50.55a(g)(6)(ii)(B)(1) 
to clarify that the start date of the first 120-month interval for the 
ISI of Class MC and Class CC components must coincide with the start of 
the first containment inspection; and would redesignate 10 CFR 
50.55a(g)(6)(ii)(B)(5) as 10 CFR 50.55a(g)(6)(ii)(B)(2).
    Paragraph (g)(6)(ii)(C)(1). The proposed revision would clarify 
that Appendix VIII to Section XI, 1995 Edition with the 1996 Addenda, 
as well as its supplements, would be required, and would also eliminate 
Supplements 12 and 13 of Appendix VIII from the implementation 
schedule.
    Paragraph (g)(6)(ii)(C)(2). The proposed paragraph would clarify 
the requirements of Appendix VIII and the supplements to Appendix VIII 
to Section XI when implementing IWA-2232 of Section XI.

4. Withdrawal of a Proposed Rule To Eliminate 120-Month Update

    On December 3, 1997 (62 FR 63892), NRC published a proposed rule to 
incorporate by reference in 10 CFR 50.55a the 1989 Addenda, 1990 
Addenda, 1991 Addenda, 1992 Edition, 1992 Addenda, 1993 Addenda, 1994 
Addenda, 1995 Edition, 1995 Addenda, and 1996 Addenda of Section III, 
Division 1 and Section XI, Division 1 of the ASME BPV Code; and the 
1995 Edition and 1996 Addenda of the ASME OM Code. The statements of 
consideration for the proposed rule noted that the Commission was 
considering a change to the 120-month update requirements of 10 CFR 
50.55a for ISI/IST programs. Several public comments were received on 
this issue, and as a result, the NRC issued a supplement to the 
December 1997 proposed rule on April 27, 1999 (64 FR 22580), that 
proposed to eliminate the requirement for licensees to update their ISI 
and IST programs beyond a baseline edition and addenda of the ASME BPV 
Code. The NRC staff held a public workshop on May 27, 1999, to discuss 
the 120-month ISI/IST update requirement. The final rule that 
incorporated by reference later editions and addenda of the ASME Code 
published on September 22, 1999 (64 FR 51370), stated that the 
Commission would consider elimination of the 120-month update 
requirement in a separate rulemaking. The Commission disapproved the 
elimination of the 120-month update requirement in an SRM dated April 
13, 2000, because the ASME Codes are subject to continuing refinement 
and improvement and it would be inappropriate to freeze these still 
evolving requirements. Therefore, the Commission is withdrawing the 
proposed rule published on April 27, 1999 (64 FR 22580).

5. Draft Generic Aging Lessons Learned Report

    On August 31, 2000 (65 FR 53047), the NRC issued a draft Generic 
Aging Lessons Learned (GALL) report for public comment. The draft GALL 
report evaluates existing generic programs, documents the basis for 
determining when generic existing programs are adequate without change, 
and documents when generic existing programs should be augmented for 
licensee renewal. Section XI, Division 1, of the ASME BPV Code is one 
of the generic existing programs in the draft GALL report that is 
evaluated as an aging management program for license renewal. 
Subsections IWB, IWC, IWD, and IWF of the 1989 Edition of Section

[[Page 40636]]

XI of the ASME BPV Code for ISI and the 1992 Edition of Subsections IWE 
and IWL of Section XI of the ASME BPV Code for ISI were evaluated in 
the draft GALL report. Changes between the 1989 and 1995 Editions of 
Section XI of the ASME BPV Code were also reviewed, and the conclusions 
in the draft GALL report remain valid for the 1995 Edition of Section 
XI of the ASME BPV Code.
    In the draft Gall Report, Sections XI.M1, ``ASME Section XI 
Inservice Inspection, Subsections IWB, IWC, and IWD,'' XI.S1, ``ASME 
Section XI, Subsection IWE,'' XI.S2, ``ASME Section XI, Subsection 
IWL,'' and XI.S3, ``ASME Section XI, Subsection IWF,'' describe the 
evaluation and technical basis for determining the adequacy of 
Subsections IWB, IWC, IWD, IWE, IWF and IWL. A 10-element program with 
such attributes as scope of program, preventive actions, parameters 
monitored/inspected, detection of aging effects, monitoring and 
trending, acceptance criteria, corrective actions, confirmation 
process, administrative controls, and operating experience was used to 
perform the evaluation.
    The NRC has completed an evaluation of Subsections IWB, IWC, IWD, 
IWE, IWF, and IWL of Section XI of the ASME BPV Code, 1997 Addenda, 
1998 Edition, 1999 Addenda, and 2000 Addenda, as part of the 10 CFR 
50.55a amendment process to ensure that the conclusions of the draft 
GALL report remain valid. Although some of the revisions in Section XI 
of the ASME BPV Code relax the provisions of the 1995 Edition, the 
revisions are acceptable and the conclusions of the draft GALL report 
remain valid. However, several of the revisions to Subsections IWA, 
IWB, IWE, and IWL that are discussed in the preceding Section 2, might 
affect the validity of the conclusions in the draft GALL report because 
provisions in the 1995 Edition that address examination requirements, 
acceptance standards, and leakage tests for Class 1, 2, CC, and MC 
components are significantly relaxed or eliminated in the 1997 Addenda, 
the 1998 Edition, the 1999 Addenda, and the 2000 Addenda. The proposed 
limitations and modifications, 50.55a(b)(2)(ix)(G), 
50.55a(b)(2)(ix)(H), 50.55a(b)(2)(ix)(I), 50.55a(b)(2)(ix)(J), 
50.55a(b)(2)(xii)(B), 50.55a(b)(2)(xix), 50.55a(b)(2)(xx), and 
50.55a(b)(2)(xxi) which are further discussed in the preceding Section 
2, would require that the revised provisions be supplemented with 
additional inspection requirements or would prohibit the use of the 
revised provisions. The conclusions of the draft GALL report remain 
valid for the 1997 Addenda, the 1998 Edition, the 1999 Addenda, and the 
2000 Addenda of Section XI of the ASME BPV Code with use of the 
proposed limitations and modifications presented in this proposed 
rulemaking. However, the NRC would impose these limitations and 
modifications to ensure consistency in the examination requirements, 
acceptance standards, and leakage tests, and not solely to validate the 
conclusions in the draft GALL report.

6. Availability of Documents

    The NRC is making the documents identified below available to 
interested persons through one or more of the following methods as 
indicated.
    Public Document Room (PDR). The NRC Public Document Room is located 
at 11555 Rockville Pike, Rockville, Maryland.
    Rulemaking Website (Web). The NRC's interactive rulemaking Website 
is located at http://ruleforum.llnl.gov. These documents may be viewed 
and downloaded electronically via this Website.
    NRC's Public Electronic Reading Room (PERR). The NRC's public 
electronic reading room is located at http://www.nrc.gov/NRC/ADAMS/index.html.
    NRC Staff Contact (NRC Staff). Single copies of the Federal 
Register Notice, Regulatory Analysis, and Environmental Assessment may 
be obtained from Stephen Tingen, Division of Engineering, Office of 
Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 
Washington, D.C. 20555-0001. Alternatively, you may contact Mr. Tingen 
at (301) 415-1280, or via e-mail at: [email protected].

------------------------------------------------------------------------
                                                                   NRC
            Document               PDR    Web         PERR        staff
------------------------------------------------------------------------
Federal Register Notice.........     X      X     (ML011970223)       X
Regulatory Analysis.............     X      X     (ML011970231)       X
Environmental Assessment........     X      X     (ML011970235)       X
------------------------------------------------------------------------

7. Plain Language

    The Presidential memorandum dated June 1, 1998, entitled, ``Plain 
Language in Government Writing,'' directed that the Federal 
government's writing must be in plain language. The NRC requests 
comments on this proposed rule specifically with respect to the clarity 
and effectiveness of the language used. Comments should be sent to: 
Secretary, U.S. Nuclear Regulatory Commission, Washington, DC 20555-
0001. ATTN: Rulemaking and Adjudications Staff. Hand deliver comments 
to 11555 Rockville Pike, Rockville, Maryland, 20852, between 7:30 a.m. 
and 4:15 p.m. on Federal workdays.

8. Voluntary Consensus Standards

    The National Technology Transfer and Advancement Act of 1995, Pub. 
L. 104-113, requires agencies to use technical standards that are 
developed or adopted by voluntary consensus standards bodies unless the 
use of such a standard is inconsistent with applicable law or is 
otherwise impractical. The NRC is amending its regulations to 
incorporate by reference a later edition and addenda of Sections III 
and XI of the ASME BPV Code and ASME OM Code, for construction, ISI, 
and IST of nuclear power plant components as identified in the 
preceding Section 2.
    In an SRM dated September 10, 1999, the Commission directed the NRC 
staff to identify all portions of an adopted voluntary consensus 
standard which are not adopted by the staff and to provide a 
justification for not adopting such portions. The portions of the ASME 
BPV Code and OM Code which the staff is proposing not to adopt, or to 
partially adopt, are identified in Section 2 of the preceding section.
    In accordance with the National Technology Transfer and Advancement 
Act of 1995 and Office of Management and Budget (OMB) Circular A-119, 
the NRC is requesting public comment regarding whether other national 
or international consensus standards could be endorsed as an 
alternative to the ASME BPV Code and the ASME OM Code.

9. Finding of No Significant Environmental Impact: Availability

    The Commission has determined, under the National Environmental 
Policy Act of 1969, as amended, and the Commission's regulations in 
Subpart A of 10 CFR Part 51, that this rule, if adopted, would not be a 
major Federal action significantly affecting the quality

[[Page 40637]]

of the human environment, and therefore, an environmental impact 
statement is not required.
    The proposed rulemaking will not significantly increase the 
probability or consequences of accidents; no changes are being made in 
the types of any effluents that may be released off-site; there is a 
decrease in occupational exposure; and there is no significant increase 
in public radiation exposure. Therefore, there are not significant 
radiological impacts associated with the proposed action. The proposed 
rulemaking does not involve non-radiological plant effluents and has no 
other environmental impact. Therefore, no significant non-radiological 
impacts are associated with the proposed action.
    The determination of this environmental assessment is that there 
will be no significant offsite impact to the public from this action. 
However, the general public should note that the NRC is seeking public 
participation. Comments on any aspect of the environmental assessment 
may be submitted to the NRC as indicated by under the ADDRESSES 
heading.
    Section 6 in the preceding section of this notice describes how to 
obtain a copy the draft environmental assessment. The Commission 
requests public comment on the draft environmental assessment and 
comments may be submitted to the NRC as indicated under the ADDRESSES 
heading.
    The NRC has sent a copy of the environmental assessment and this 
proposed rule to every State Liaison Officer and requested their 
comments on the environmental assessment.

10. Paperwork Reduction Act Statement

    This proposed rule amends information collection requirements that 
are subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et 
seq.). This proposed rule has been submitted to OMB for review and 
approval of the information collection requirements.
    The burden to the public for these information collections is 
estimated to average 67 hours per response, including the time for 
reviewing instructions, searching existing data sources, gathering and 
maintaining the data needed, and completing and reviewing the 
information collection. The NRC is seeking public comment on the 
potential impact of the information collections contained in the 
proposed rule and on the following issues:
    1. Is the proposed information collection necessary for the proper 
performance of the functions of the NRC, including whether the 
information will have practical utility?
    2. Is the estimate of burden accurate?
    3. Is there a way to enhance the quality, utility, and clarity of 
the information to be collected?
    4. How can the burden of the information collection be minimized, 
including the use of automated collection techniques?
    Send comments on any aspect of these proposed information 
collections, including suggestions for reducing the burden, to the 
Records Management Branch (T-6 E6), U.S. Nuclear Regulatory Commission, 
Washington, DC 20555-0001, or by Internet electronic mail to 
[email protected]; and to the Desk Officer, Office of Information and 
Regulatory Affairs, NEOB-10202, (3150-0011), Office of Management and 
Budget, Washington, DC 20503.
    Comments to OMB on the information collections or on the above 
issues should be submitted by September 4, 2001. Comments received 
after this date will be considered if it is practical to do so, but 
assurance of consideration cannot be given to comments received after 
this date.

Public Protection Notification

    If a means used to impose an information collection does not 
display a currently valid OMB control number, the NRC may not conduct 
or sponsor, and a person is not required to respond to, the information 
collection.

11. Regulatory Analysis

    The NRC has prepared a draft regulatory analysis on this proposed 
rule. The draft analysis is available for review in the NRC's Public 
Document Room, located in One White Flint North, 11555 Rockville Pike, 
Rockville, Maryland. Section 6 in the preceding section of this notice 
describes how to obtain a copy of the draft regulatory analysis. The 
Commission requests public comment on the draft analysis and comments 
may be submitted to the NRC as indicated under the ADDRESSES heading.

12. Regulatory Flexibility Certification

    In accordance with the Regulatory Flexibility Act of 1980, 5 U.S.C. 
605(b), the Commission certifies that this proposed amendment will not, 
if promulgated, have a significant economic impact on a substantial 
number of small entities. This proposed amendment affects only the 
licensing and operation of nuclear power plants. The companies that own 
these plants do not fall within the scope of the definition of small 
entities set forth in the Regulatory Flexibility Act or the Small 
Business Size Standards set forth in regulations issued by the Small 
Business Administration at 13 CFR part 121.

13. Backfit Analysis

    The NRC's regulations in 10 CFR 50.55a require nuclear power plant 
licensees to construct Class 1, 2, and 3 components in accordance with 
the rules provided in Section III, Division 1, of the ASME BPV Code; 
inspect Class 1, 2, 3, Class MC, and Class CC components in accordance 
with the rules provided in Section XI, Division 1, of the ASME BPV 
Code; and test Class 1, 2, and 3 pumps and valves in accordance with 
the rules provided in the ASME OM Code. The proposed rule incorporates 
by reference the 1997 Addenda, the 1998 Edition, the 1999 Addenda, and 
the 2000 Addenda of Section III, Division 1, of the ASME BPV Code; 
Section XI, Division 1, of the ASME BPV Code; and the ASME OM Code.
    The NRC's regulations require licensees to revise their ISI and IST 
programs every 120 months to the edition and addenda of Section XI of 
the ASME BPV Code and the ASME OM Code incorporated by reference into 
10 CFR 50.55a that is in effect 12 months prior to the start of a new 
120-month interval. The regulation in 10 CFR 50.109 does not ordinarily 
require a backfit analysis for routine amendments to 10 CFR 50.55a. The 
bases for the NRC position are that--
    (1) Section III, Division 1, applies only to new construction 
(i.e., the edition and addenda to be used in constructing a plant are 
selected on the basis of the date of the construction permit, and are 
not changed thereafter, except voluntarily by the licensee);
    (2) Licensees understand that 10 CFR 50.55a requires that they 
revise their ISI and IST programs every 120 months to the latest 
edition and addenda of the ASME Code that were incorporated by 
reference in 10 CFR 50.55a and in effect 12 months before the start of 
the next inspection interval; and
    (3) The ASME Code is a national consensus standard developed by 
participants with broad and varied interests, in which all interested 
parties (including the NRC and utilities) participate.
    This consideration is consistent with both the intent and spirit of 
the Backfit Rule (i.e., the NRC provides for the protection of the 
public health and safety, and does not unilaterally impose undue burden 
on applicants or licensees).

[[Page 40638]]

    In the proposed revision to 10 CFR 50.55a(b)(2)(xv)(A), (A)(1) and 
(A)(2) that is discussed in the preceding Section 2.3.1, the Commission 
is adopting dissimilar metal piping weld examination coverage 
requirements. These requirements, although contained in the 1989 
Edition, and earlier editions and addenda of Section XI of the ASME 
Code, are not addressed in later editions and addenda of Section XI. 
The Commission concludes that the addition of dissimilar metal piping 
weld examination coverage requirements to the regulation is necessary 
to correct the omission by the ASME Code to ensure adequate protection 
of public health and safety.

List of Subjects in 10 CFR Part 50

    Antitrust, Classified information, Criminal penalties, Fire 
protection, Intergovernmental relations, Nuclear power plants and 
reactors, Radiation protection, Reactor siting criteria, Reporting and 
recordkeeping requirements.

    For the reasons set out in the preamble and under the authority of 
the Atomic Energy Act of 1954, as amended, the Energy Reorganization 
Act of 1974, as amended, and 5 U.S.C. 553, the NRC is proposing to 
adopt the following amendments to 10 CFR part 50.

PART 50--DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION 
FACILITIES

    1. The authority citation for Part 50 is revised to read as 
follows:

    Authority: Sections 102, 103, 104, 105, 161, 182, 183, 186, 189, 
68 Stat. 936, 937, 938, 948, 953, 954, 955, 956, as amended, sec. 
234, 83 Stat. 444, as amended (42 U.S.C. 2132, 2133, 2134, 2135, 
2201, 2232, 2233, 2239, 2282); secs. 201, as amended, 202, 206, 88 
Stat. 1242, as amended, 1244, 1246 (42 U.S.C. 5841, 5842, 5846).

    Section 50.7 also issued under Pub. L. 95-601, sec. 10, 92 Stat. 
2951 as amended by Pub L. 102-486, sec. 2902, 106 Stat. 3123 (42 
U.S.C. 5851). Section 50.10 also issued under secs. 101, 185, 68 
Stat. 936, 955 as amended (42 U.S.C. 2131, 2235), sec. 102, Pub. L. 
91-190, 83 Stat. 853 (42 U.S.C. 4332). Sections 50.13, 50.54(dd), 
and 50.103 also issued under sec. 108, 68 Stat. 939, as amended (42 
U.S.C. 2138). Sections 50.23, 50.35, 50.55, and 50.56 also issued 
under sec. 185, 68 Stat. 955 (42 U.S.C. 2235). Sections 50.33a, 
50.55a and appendix Q also issued under sec. 102, Pub. L. 91-190, 83 
Stat. 853 (42 U.S.C. 4332). Sections 50.34 and 50.54 also issued 
under Pub. L. 97-415, 96 Stat. 2073 (42 U.S.C. 2239). Section 50.78 
also issued under sec. 122, 68 Stat. 939 (42 U.S.C. 2152). Sections 
50.80-50.81 also issued under sec. 184, 68 Stat. 954, as amended (42 
U.S.C. 2234). Appendix F also issued under sec. 187, 68 Stat. 955 
(42 U.S.C. 2237).

    2. Section 50.55a is amended by:
    (a) Removing paragraphs (b)(2)(xv)(G)(4), (g)(6)(ii)(B)(3), and 
(g)(6)(ii)(B)(4);
    (b) Redesignating and revising paragraph (g)(6)(ii)(B)(5) as 
(g)(6)(ii)(B)(2);
    (c) Revising the introductory text of paragraph (b)(1), paragraphs 
(b)(1)(ii), (b)(1)(iii), and (b)(1)(v), the introductory text of 
paragraphs (b)(2), (b)(2)(viii), and (b)(2)(ix), paragraph (b)(2)(xi), 
the introductory text of paragraph (b)(2)(xv), paragraphs 
(b)(2)(xv)(A), (b)(2)(xv)(K)(1)(i), and (b)(2)(xvii), the introductory 
text of paragraph (b)(3), paragraph (b)(3)(ii), the introductory text 
of paragraphs (b)(3)(iii) and (b)(3)(iv), and paragraphs (b)(3)(v), 
(g)(6)(ii)(B)(1), and (g)(6)(ii)(C)(1);and
    (d) Adding paragraphs (b)(2)(viii)(F), (b)(2)(ix)(F) through 
(b)(2)(ix)(J), (b)(2)(xii), (b)(2)(xv)(M), (b)(2)(xviii) through 
(b)(2)(xxiii), (b)(3)(iv)(D), (b)(3)(vi), and (g)(6)(ii)(C)(2).


Sec. 50.55a  Codes and standards.

* * * * *
    (b) * * *
    (1) As used in this section, references to Section III of the ASME 
Boiler and Pressure Vessel Code refer to Section III, Division 1, and 
include editions through the 1998 Edition and addenda through the 2000 
Addenda, subject to the following limitations and modifications:
* * * * *
    (ii) Weld leg dimensions. When applying the 1989 Addenda through 
the latest editions and addenda incorporated by reference in paragraph 
(b)(1) of this section, licensees may not apply paragraph NB-
3683.4(c)(1), Footnote 11 to Figure NC-3673.2(b)-1, and Figure ND-
3673.2(b)-1.
    (iii) Seismic design. Licensees may use Articles NB-3200, NB-3600, 
NC-3600, and ND-3600 up to and including the 1993 Addenda, subject to 
the limitation specified in paragraph (b)(1)(ii) of this section. 
Licensees may not use these Articles in the 1994 Addenda through the 
latest editions and addenda incorporated by reference in paragraph 
(b)(1) of this section.
* * * * *
    (v) Independence of inspection. Licensees may not apply NCA-
4134.10(a) of Section III, 1995 Edition through the latest editions and 
addenda incorporated by reference in paragraph (b)(1) of this section.
    (2) As used in this section, references to Section XI of the ASME 
Boiler and Pressure Vessel Code refer to Section XI, Division 1, and 
include editions through the 1998 Edition and addenda through the 2000 
Addenda, subject to the following limitations and modifications:
* * * * *
    (viii) Examination of concrete containments. Licensees applying 
Subsection IWL, 1992 Edition with the 1992 Addenda, shall apply 
paragraphs (b)(2)(viii)(A) through (b)(2)(viii)(E) of this section. 
Licensees applying the 1995 Edition with the 1996 Addenda shall apply 
paragraphs (b)(2)(viii)(A), (b)(2)(viii)(D)(3), and (b)(2)(viii)(E) of 
this section. Licensees applying the 1998 Edition with the 1999 and 
2000 Addenda shall apply paragraphs (b)(2)(viii)(E) and (b)(2)(viii)(F) 
of this section.
* * * * *
    (F) Qualification provisions for personnel that examine containment 
concrete surfaces and tendon hardware, wires, or strands must be in 
accordance with IWA-2300 in lieu of ``owner-defined'' personnel 
qualification provisions in IWL-2310(d).
    (ix) Examination of metal containments and the liners of concrete 
containments. Licensees applying Subsection IWE, 1992 Edition with the 
1992 Addenda, or the 1995 Edition with the 1996 Addenda, shall satisfy 
the requirements of paragraphs (b)(2)(ix)(A) through (b)(2)(ix)(E) of 
this section. Licensees applying the 1998 Edition with the 1999 Addenda 
and 2000 Addenda shall only satisfy the requirements of paragraphs 
(b)(2)(ix)(A), (b)(2)(ix)(B), (b)(2)(ix)(F) through (b)(2)(ix)(J) of 
this section.
* * * * *
    (F) Qualification provisions for personnel who conduct visual 
examinations of containment surfaces must be in accordance with IWA-
2300 in lieu of ``owner-defined'' personnel qualification provisions of 
IWE-2330(a).
    (G) The general and detailed visual examinations required by IWE-
2310(b) and IWE-2310(c) must meet the VT-3 and VT-1 examination 
provisions of IWA-2210 in lieu of the ``owner-defined'' general and 
detailed visual examination provisions in IWE-2310(a). Table IWA-2210-1 
maximum direct examination distance may be extended and Table IWA-2210-
1 minimum illumination requirements may be decreased as permitted by 
(b)(2)(ix)(B) of this section.
    (H) The acceptance standard of IWC-3513 must be used to evaluate 
flaws in pressure-retaining bolting that is greater than or equal to 51 
millimeters [2 inches] in diameter identified during the examination of 
containment surfaces in lieu of the ``owner-defined'' acceptance 
standard in IWE-3510.1.

[[Page 40639]]

    (I) The examination provisions for containment bolted connections 
contained in Table IWE-2500-1, Examination Category E-A, Containment 
Surfaces, Items E1.10 and E1.11, must be supplemented with the 
following examination requirements:
    (1) The general visual examination must include the examination of 
bolted connections that are disassembled at the time of a scheduled 
inspection.
    (2) A detailed visual examination must be performed for areas where 
flaws or degradation are indicated.
    (3) Damaged bolted connections must be disassembled, and a detailed 
visual examination of the bolted connection components must be 
performed.
    (4) If a bolted connection is disassembled at times other than a 
periodic (or planned) inspection and is not examined by a qualified 
visual examiner before reassembly, written maintenance procedures must 
be followed to ensure that the integrity of the reassembled bolted 
connection is maintained. The written procedures must include 
acceptance criteria for the continued use of all parts of the 
connection including bolts, studs, nuts, bushings, washers, threads in 
base material, and flange ligaments between fastener holes.
    (J) The ultrasonic examination acceptance standard specified in 
IWE-3511.3 for Class MC pressure-retaining components must also be 
applied to metallic liners of Class CC pressure-retaining components.
* * * * *
    (xi) Class 1 piping. Licensees may not apply IWB-1220, ``Components 
Exempt from Examination,'' of Section XI, 1989 Addenda through the 
latest editions and addenda incorporated by reference in paragraph 
(b)(2) of this section, and shall apply IWB-1220, 1989 Edition.
    (xii) Containment penetration piping.
    (A) Welds in high-energy fluid system containment penetration 
piping located inside a containment penetration assembly or 
encapsulated by a guard pipe are not exempt from the examination 
provisions of Subsection IWC as permitted by IWC-1223 of the 1997 
Addenda through the latest editions and addenda incorporated by 
reference in paragraph (b)(2) of this section.
    (B) Piping that penetrates the containment that is connected to 
piping that is outside the scope of Section XI is not exempt from the 
pressure testing provisions of Subsection IWA as permitted by IWA-
5110(c) of the 1997 Addenda through the latest editions and addenda 
incorporated by reference in paragraph (b)(2) of this section.
* * * * *
    (xv) Appendix VIII specimen set and qualification requirements. The 
following provisions may be used to modify implementation of Appendix 
VIII of Section XI, 1995 Edition through the latest editions and 
addenda incorporated by reference in paragraph (b)(2) of this section. 
Licensees choosing to apply these provisions shall apply all of the 
following provisions under this subparagraph except for those in 
Sec. 50.55a(b)(2)(xv)(F) which are optional.
    (A) When applying Supplements 2, 3, and 10 to Appendix VIII, the 
following examination coverage criteria requirements must be used:
    (1) Piping must be examined in two axial directions, and when 
examination in the circumferential direction is required, the 
circumferential examination must be performed in two directions, 
provided access is available. Dissimilar metal welds must be examined 
axially and circumferentially.
    (2) Where examination from both sides is not possible, full 
coverage credit may be claimed from a single side for ferritic welds. 
Where examination from both sides is not possible on austenitic welds 
or dissimilar metal welds, full coverage credit from a single side may 
be claimed only after completing a successful single-sided Appendix 
VIII demonstration using flaws on the opposite side of the weld. 
Dissimilar metal welds must be examined from the side that is of the 
same base metal material as that from which qualification was 
demonstrated.
* * * * *
    (K) * * *
    (1) * * *
    (i) For detection, a minimum of four flaws in one or more full-
scale nozzle mock-ups must be added to the test set. The specimens must 
comply with Supplement 6, paragraph 1.1, to Appendix VIII, except for 
flaw locations specified in Table VIII S6-1. Flaws may be either 
notches, fabrication flaws or cracks. Seventy-five percent of the flaws 
must be cracks or fabrication flaws. Flaw locations and orientations 
must be selected from the choices shown in Sec. 50.55a(b)(2)(xv)(K)(4), 
Table VIII-S7-1-Modified, with the exception that flaws in the outer 85 
percent of the weld need not be perpendicular to the weld. There may be 
no more than two flaws from each category, and at least one subsurface 
flaw must be included.
* * * * *
    (M) When implementing Supplement 12 to Appendix VIII, only the 
provisions related to the coordinated implementation of Supplement 3 to 
Supplement 2 performance demonstrations are required.
* * * * *
    (xvii) Reconciliation of Quality Requirements. When purchasing 
replacement items, in addition to the reconciliation provisions of IWA-
4200, 1995 Edition through the latest editions and addenda incorporated 
by reference in paragraph (b)(2) of this section, the replacement items 
must be purchased, to the extent necessary, in accordance with the 
licensee's quality assurance program description required by 10 CFR 
50.34(b)(6)(ii).
    (xviii) Certification of NDE personnel.
    (A) Level I and II nondestructive examination personnel, and 
personnel qualified under the American Society for Nondestructive 
Testing Control Certifications Program shall be recertified on a 3-year 
interval in lieu of the 5-year interval specified in IWA-2314 of the 
1997 Addenda and the 1998 Edition, and IWA-2314(a) and IWA-2314(b) of 
the 1999 Addenda through the latest editions and addenda incorporated 
by reference in paragraph (b)(2) of this section.
    (B) Paragraph IWA-2316 of the 1998 Edition through the latest 
editions and addenda incorporated by reference in paragraph (b)(2) of 
this section, may be used to qualify visual examination personnel only 
for the performance of VT-2 visual examinations when the proficiency of 
the training required under IWA-2316 is demonstrated by administering 
an initial qualification examination and administering recertification 
examinations on a 3-year interval.
    (C) Paragraph IWA-2317 of the 1998 Edition through the latest 
editions and addenda incorporated by reference in paragraph (b)(2) of 
this section, may be used to qualify visual examination personnel only 
for the performance of VT-3 visual examinations when the proficiency of 
the training required under IWA-2317 is demonstrated by administering 
an initial qualification examination and administering recertification 
examinations on a 3-year interval.
    (xix) Substitution of alternative methods. The provision in IWA-
2240, 1998 Edition through the latest editions and addenda incorporated 
by reference in paragraph (b)(2) of this section, and IWA-4520(c), 1997 
Addenda through the latest editions and addenda incorporated by 
reference in paragraph (b)(2) of this section, that allows the 
substitution of alternative examination methods, a combination of 
methods, or newly developed techniques for the methods specified in the 
Construction Code may not be applied.

[[Page 40640]]

    (xx) System leakage tests. The pressure and temperature hold time 
requirements of IWA-5213(a) of the 1995 Edition must be applied in lieu 
of the provisions of IWA-5213(a) of the 1997 Addenda through the latest 
editions and addenda incorporated by reference in paragraph (b)(2) of 
this section, when performing system leakage tests.
    (xxi) Table IWB-2500-1 examination requirements.
    (A) The provisions of Table IWB-2500-1, Examination Category B-D, 
Full Penetration Welded Nozzles in Vessels, Items B3.40 and B3.60 
(Inspection Program A) and Items B3.120 and B3.140 (Inspection Program 
B) that are in the 1997 Addenda and 1998 Edition must be applied when 
using the 1999 Addenda through the latest editions and addenda 
incorporated by reference in paragraph (b)(2) of this section.
    (B) The provisions of Table IWB-2500-1, Examination Category B-G-2, 
Item B7.80, that are in the 1995 Edition must be applied when using the 
1997 Addenda through the latest editions and addenda incorporated by 
reference in paragraph (b)(2) of this section.
    (C) The provisions of Table IWB-2500-1, Examination Category B-K, 
Item B10.10, of the 1995 Addenda must be applied when using the 1997 
Addenda through the latest editions and addenda incorporated by 
reference in paragraph (b)(2) of this section.
    (xxii) Annual Training Requirements for Ultrasonic Examiners. 
Supplemental annual training for ultrasonic examiner qualification must 
be in accordance with Appendix VII, paragraph VII-4240, of the 1998 
Edition when using the 1999 Addenda through the latest editions and 
addenda incorporated by reference in paragraph (b)(2) of this section.
    (xxiii) Underwater welding. When welding high neutron fluence Class 
1 material underwater in accordance with IWA-4660, 1997 Addenda through 
the latest editions and addenda incorporated by reference in paragraph 
(b)(2) of this section, the acceptability of the welding method must 
include demonstration on a mockup using material with similar neutron 
fluence levels to verify that adequate crack prevention measures were 
used.
    (3) As used in this section, references to the OM Code refer to the 
ASME Code for Operation and Maintenance of Nuclear Power Plants, and 
include the 1995 Edition through the 2000 Addenda subject to the 
following limitations and modifications:
* * * * *
    (ii) Motor-Operated Valve stroke-time testing. Licensees shall 
comply with the provisions on stroke-time testing in OM Code ISTC 4.2, 
1995 Edition with the 1996 and 1997 Addenda, or ISTC-3500, 1998 Edition 
through the latest editions and addenda incorporated by reference in 
paragraph (b)(3) of this section, and shall establish a program to 
ensure that motor-operated valves continue to be capable of performing 
their design basis safety functions.
    (iii) Code Case OMN-1. As an alternative to Sec. 50.55a(b)(3)(ii), 
licensees may use Code Case OMN-1, ``Alternative Rules for Preservice 
and Inservice Testing of Certain Electric Motor-Operated Valve 
Assemblies in Light Water Reactor Power Plants,'' Revision 0, in 
conjunction with ISTC 4.3, 1995 Edition with the 1996 and 1997 Addenda, 
or ISTC-3600, 1998 Edition through the latest editions and addenda 
incorporated by reference in paragraph (b)(3) of this section. 
Licensees choosing to apply the Code Case shall apply all of its 
provisions.
* * * * *
    (iv) Appendix II. Licensees applying Appendix II, ``Check Valve 
Condition Monitoring Program,'' of the OM Code, 1995 Edition with the 
1996 and 1997 Addenda, shall satisfy the requirements of (b)(3)(iv)(A), 
(b)(3)(iv)(B), and (b)(3)(iv)(C) of this section. Licensees applying 
Appendix II, 1998 Edition through the latest editions and addenda 
incorporated by reference in paragraph (b)(3) of this section, shall 
satisfy the requirements of (b)(3)(iv)(A), (b)(3)(iv)(B), and 
(b)(3)(iv)(D) of this section.
* * * * *
    (D) The provisions of ISTC-3510, ISTC-3520, and ISTC-3540 in 
addition to ISTC-5221 must be implemented if the Appendix II condition 
monitoring program is discontinued.
    (v) Subsection ISTD. Article IWF-5000, ``Inservice Inspection 
Requirements for Snubbers,'' of the ASME BPV Code, Section XI, provides 
inservice inspection requirements for examinations and tests of 
snubbers at nuclear power plants. Licensees may use Subsection ISTD, 
``Inservice Testing of Dynamic Restraints (Snubbers) in Light-Water 
Reactor Power Plants,'' ASME OM Code, 1995 Edition through the latest 
editions and addenda incorporated by reference in paragraph (b)(3) of 
this section, in lieu of the requirements for snubbers in Section XI, 
IWF-5200(a) and (b) and IWF-5300(a) and (b), by making appropriate 
changes to their technical specifications or licensee controlled 
documents. Preservice and inservice examinations must be performed 
using the VT-3 visual examination method described in IWA-2213.
    (vi) Exercise interval for manual valves. Manual valves must be 
exercised on a 2-year interval in lieu of the 5-year interval specified 
in paragraph ISTC-3540 of the 1999 Addenda through the latest editions 
and addenda incorporated by reference in paragraph (b)(3) of this 
section, provided that adverse conditions do not require more frequent 
testing.
* * * * *
    (g) * * *
    (6) * * *
    (ii) * * *
    (B) * * *
    (1) The start of the first 120-month interval for inservice 
inspection of Class MC and Class CC components must coincide with the 
start of the first containment inspection.
    (2) Licensees do not have to submit to the NRC staff for approval 
of their containment inservice inspection program which was developed 
to satisfy the requirements of Subsection IWE and Subsection IWL with 
specified modifications and limitations. The program elements and the 
required documentation must be maintained on site for audit.
    (C) * * *
    (1) Appendix VIII and the supplements to Appendix VIII to Section 
XI, Division 1, 1995 Edition with the 1996 Addenda of the ASME Boiler 
and Pressure Vessel Code must be implemented in accordance with the 
following schedule: Appendix VIII and Supplements 1, 2, 3, and 8--May 
22, 2000; Supplements 4 and 6--November 22, 2000; Supplement 11--
November 22, 2001; and Supplements 5, 7, and 10--November 22, 2002.
    (2) The requirements of Appendix VIII and the supplements to 
Appendix VIII to Section XI, Division 1, 1995 Edition through the 
latest editions and addenda of the ASME Boiler and Pressure Vessel Code 
incorporated by reference in 10 CFR 50.55a(b)(2) apply when 
implementing paragraph IWA-2232 of the edition and addenda of Section 
XI referenced in the inservice inspection program Code of Record.
* * * * *

    Dated at Rockville, Maryland this 25th day of July 2001.

    For the U.S. Nuclear Regulatory Commission.
William D. Travers,
Executive Director for Operations.
[FR Doc. 01-19414 Filed 8-2-01; 8:45 am]
BILLING CODE 7590-01-P