[Federal Register Volume 70, Number 188 (Thursday, September 29, 2005)]
[Rules and Regulations]
[Pages 56809-56813]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 05-19443]



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  Federal Register / Vol. 70, No. 188 / Thursday, September 29, 2005 / 
Rules and Regulations  

[[Page 56809]]



NUCLEAR REGULATORY COMMISSION

10 CFR Part 50

RIN 3150-AH35


Incorporation by Reference of ASME BPV Code Cases

AGENCY: Nuclear Regulatory Commission.

ACTION: Final rule.

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

SUMMARY: The Nuclear Regulatory Commission (NRC) is amending its 
regulations to incorporate by reference NRC Regulatory Guides listing 
Code Cases published by the American Society of Mechanical Engineers 
(ASME) which the NRC has reviewed and found to be acceptable for use. 
These Code Cases provide alternatives to requirements in the ASME 
Boiler and Pressure Vessel Code (BPV Code) pertaining to construction 
and inservice inspection of nuclear power plant components. This action 
updates the incorporation by reference of two regulatory guides that 
address NRC review and approval of ASME-published Code Cases. 
Concurrent with this action, the NRC is publishing a notice of the 
issuance and availability of the final regulatory guides. As a result 
of these related actions, the Code Cases listed in these regulatory 
guides are incorporated by reference into the NRC's regulations.

DATES: Effective Date: October 31, 2005. The incorporation by reference 
of certain publications listed in the regulation is approved by the 
Director of the Office of the Federal Register as of October 31, 2005.

FOR FURTHER INFORMATION CONTACT: Harry S. Tovmassian, Office of Nuclear 
Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 
20555-0001, telephone (301) 415-3092, e-mail [email protected].

SUPPLEMENTARY INFORMATION:

Background

    New editions of the ASME BPV and Operation and Maintenance of 
Nuclear Power Plants (OM) Codes are issued every three years and 
addenda to the editions are issued annually. It has been the 
Commission's policy to update 10 CFR 50.55a to incorporate the ASME 
Code editions and addenda by reference. Section 50.55a was last amended 
on October 1, 2004 (69 FR 58804), to incorporate by reference the 2001 
Edition of these Codes, up to and including the 2003 Addenda. The ASME 
also publishes Code Cases for Section III and Section XI quarterly and 
Code Cases for the OM Code yearly. ASME Code Cases are alternatives to 
the requirements of the ASME BPV Code and the OM Code. Thus, the 
incorporation by reference of the regulatory guides (RGs) listing NRC-
approved and conditionally approved ASME Code Cases accords the Code 
Cases the same legal status as the ASME provisions which they replace.

Discussion

    The NRC staff reviews ASME BPV Code Cases,\1\ rules upon the 
acceptability of each Code Case, and publishes its findings in RGs. The 
RGs are revised periodically as new Code Cases are published by the 
ASME. On July 8, 2003 (68 FR 40469), the NRC published a final rule 
which initiated the practice of incorporating by reference in 10 CFR 
50.55a the RGs listing acceptable and conditionally acceptable ASME 
Code Cases. Thus, NRC RG 1.84, Revision 32, Design, Fabrication, and 
Materials Code Case Acceptability, ASME Secion III; NRC RG 1.147, 
Revisions 0 through 13, Inservice Inspection Code Case Acceptability, 
ASME Section XI, Division 1; and NRC RG 1.192, Operation and 
Maintenance Code Case Acceptability, ASME OM Code were incorporated 
into NRC's regulations.
---------------------------------------------------------------------------

    \1\ The NRC staff also reviews OM Code Cases; however, the 
regulatory guide listing NRC-approved OM Code Cases is not being 
revised at this time because no new OM Code Cases have been 
published by the ASME.
---------------------------------------------------------------------------

    This final rule incorporates by reference the latest revisions of 
the NRC RGs that list acceptable and conditionally acceptable ASME BPV 
Code Cases. RG 1.84, Revision 33 supersedes Revision 32 which was 
previously incorporated by reference. The incorporation by reference of 
Revision 14 to RG 1.147 will supplement Revisions 0 through 13. This 
final rule adds Revision 14 to the series of RG 1.147 revisions 
currently incorporated by reference in Sec.  50.55a. Concurrent with 
this action, the NRC is publishing notices of availability of the final 
RGs listing acceptable ASME BPV Code Cases.

Evaluation of Code Cases

    When the NRC evaluates ASME Code Cases to be incorporated by 
reference in its RGs, it determines which of the new, revised, or 
reaffirmed Code Cases are acceptable, conditionally acceptable, or 
unacceptable. When the NRC published the July 8, 2003, rulemaking (68 
FR 40469) incorporating by reference RGs 1.84 and 1.147, the regulatory 
analysis accompanying that action contained a section listing those 
Code Cases which were deemed acceptable or conditionally acceptable. 
For those Code Cases found to be conditionally acceptable, a summary of 
the basis for the limitations or conditions placed on the application 
of the Code Case was provided. In order to clearly explain NRC's 
rationale for limitations placed on Code Cases and to enhance public 
participation in the entire rulemaking process, the NRC has prepared a 
separate document entitled ``Evaluation of Code Cases in Supplement 12 
to the 1998 Edition and Supplement 1 Through Supplement 6 to the 2001 
Edition,'' which contains this information. Copies of this document are 
available to the public as indicated in the ``Availability of 
Documents'' section of this preamble.

Resolution of Public Comments

    The NRC received one comment letter on the proposed rulemaking. The 
commenter made observations about Code Cases N-416-3 and N-504-2 in 
Revision 14 of RG 1.147 that were duplicative of comments that he 
submitted in response to the notice announcing the availability of the 
draft guide for comment (69 FR 46597; August 3, 2004). The NRC finds 
that no change in the rule language is required as a result of these 
comments. The NRC's resolution of these comments can be found in the 
``Response to Public Comments'' document which is available to the 
public as indicated in

[[Page 56810]]

the ``Availability of Documents'' section of this preamble.

Status of Code Case N-586

    In Revision 13 to NRC RG 1.147, Code Case N-586 entitled, 
``Alternative Additional Examination Requirements for Class 1, 2, and 3 
Piping, Components, and Supports, Section XI, Division 1,'' was 
approved with two conditions. The first condition required licensees to 
perform additional examinations in the event that during a refueling 
outage they discover indications that exceed Section XI acceptance 
criteria. Furthermore, should these additional examinations detect 
other indications that Section XI criteria are exceeded, further 
examinations must be conducted during the refueling outage. In the 
proposed Revision 14 of RG 1.147, these conditions were inadvertently 
removed and Code Case N-586 was listed as acceptable without condition. 
Since the conditions placed on Code Case N-586 listed in RG 1.147, 
Revision 13 received no adverse public comment, Revision 14 is 
incorporated by reference with the same conditions that applied to this 
Code Case in Revision 13 of this RG. The staff notes that the cognizant 
ASME Section XI committees have considered the NRC's position vis-a-vis 
the conditions on this Code Case and have published Code Case N-586-1 
which will be formally evaluated by the staff in the next revision of 
this RG.

Paragraph-by-Paragraph Discussion

    On August 3, 2004, (69 FR 46596 and 69 FR 46597), the NRC published 
notices of availability of proposed revisions to RGs 1.84 and 1.147. 
The NRC has considered the public comments on these RGs and has 
resolved those comments by modifying the guides, as appropriate, or 
providing its rationale for not doing so. This rulemaking supersedes 
the incorporation by reference of RG 1.84, Revision 32 with Revision 33 
and incorporates by reference Revision 14 of RG 1.147 to augment 
previously incorporated Revisions 0 through 13.

1. Paragraph 50.55a(b)

    In Sec.  50.55a, paragraph (b)(2)(xxi)(C) is removed. The NRC had 
previously taken issue with the use of Code Case N-323-1 which 
permitted surface examinations from the accessible side for welded 
attachments to pressure vessels. Since this Code Case was incorporated 
in the 1997 Addenda to the 1995 Edition to the ASME BPV Code, the NRC 
placed a limitation on its use in Sec.  50.55a(b)(2)(xxi)(C) in which 
it required that Examination Category B-K, Item 10.10, of the 1995 
Addenda must be applied when using the 1997 Addenda through the latest 
Edition and Addenda incorporated in the NRC's regulations. Based on 
analysis of the configuration of these attachment welds and the 
environment in which they exist, no degradation mechanism would be 
expected to lead to failure of these welds. This conclusion has been 
confirmed by the results of examinations capable of detecting flaws 
since no degradation has been observed in these welds. The NRC 
considers that the proposed change in examination to a surface 
examination from either side of the weld or a volumetric examination of 
the weld provides an adequate level of defense in depth. Therefore, 
Code Case N-323-1 has been removed from RG 1.193, which lists Code 
Cases that the NRC has not generically approved for use, and listed it 
as unconditionally acceptable in RG 1.147, Revision 14 and the 
limitations placed on its use in Sec.  50.55a(b)(2)(xxi)(C) have been 
removed.
    Also, in Sec.  50.55a(b), (b)(4), and (b)(5), references to the 
revision number for RG 1.84 are changed from ``Revision 32'' to 
``Revision 33,'' and references to the revision numbers for RG 1.147 
are changed from ``through Revision 13'' to ``through Revision 14.'' 
Revision 33 of RG 1.84 is incorporated by reference in Sec.  50.55a in 
place of Revision 32. Revision 14 of RG 1.147 is incorporated by 
reference in Sec.  50.55a in addition to all previous revisions, which 
are incorporated by reference.

2. Paragraphs 50.55a(f)(2), (f)(3)(iii)(A), (f)(3)(iv)(A), (f)(4)(ii), 
(g)(2), (g)(3)(i), (g)(3)(ii), (g)(4)(i), and (g)(4)(ii)

    In these paragraphs, the phrase indicating that revisions of RG 
1.147 ``through Revision 13'' are the versions incorporated by 
reference in Sec.  50.55a(b) is modified to read ``through Revision 
14.''

Availability of Documents

    The NRC is making the documents identified below available to 
interested persons through one or more of the following:
    Public Document Room (PDR). The NRC Public Document Room is located 
at 11555 Rockville Pike, Public File Area O-1 F21, Rockville, Maryland. 
Copies of publicly available documents related to this rulemaking can 
be viewed electronically on public computers in the PDR. The PDR 
reproduction contractor will make copies of documents for a fee.
    Rulemaking Web site. The NRC's interactive rulemaking Web site is 
located at http://ruleforum.llnl.gov. Selected documents may be viewed 
and downloaded electronically via this Web site. Documents will remain 
available on the site for six months after the effective date of this 
rule.
    The NRC's Public Electronic Reading Room (PERR). The NRC's public 
electronic Reading Room is located at http:// www.nrc.gov/reading-rm.html. Through this site, the public can gain access to ADAMS, which 
provides text and image files of NRC's public documents.
    Reproduction and Distribution Services (DIST). Single copies of NRC 
Regulatory Guides 1.84, Revision 33; 1.147, Revision 14; and 1.192 may 
be obtained free of charge by writing the Reproduction and Distribution 
Services Section, U.S. Nuclear Regulatory Commission, Washington, DC 
20555-0001; or by fax to 301-415-2289; or by e-mail to 
[email protected].
    The NRC staff contact (NRC Staff). Single copies of the final rule, 
the regulatory analysis, the environmental assessment, and the 
regulatory guides may be obtained from Harry S. Tovmassian, Office of 
Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 
Washington, DC 20555-0001. Alternatively, you may contact Mr. 
Tovmassian at (301) 415-3092 or via e-mail to: [email protected].

----------------------------------------------------------------------------------------------------------------
                                                                                                           NRC
                 Document                    PDR      Web      DIST                  ERR                  staff
----------------------------------------------------------------------------------------------------------------
Regulatory Analysis......................       X        X   .......  ML043640553                             X
Regulatory Guide 1.84, Revision 33.......       X   .......       X   ML052130562                             X
Regulatory Guide 1.147, Revision 14......       X   .......       X   ML052510117                             X
Regulatory Guide 1.193, Revision 1.......       X   .......       X   ML052140501                             X
Response to Public Comments on Guides....       X        X   .......  ML050940285                             X
Evaluation of Code Cases.................       X        X   .......  ML050940259                             X

[[Page 56811]]

 
Public Comment Letter....................       X        X   .......  ML042960462                             X
----------------------------------------------------------------------------------------------------------------

Voluntary Consensus Standards

    The National Technology Transfer and Advancement Act of 1995, Pub. 
L. 104-113 (15 U.S.C. 3701 et seq.), requires agencies to use technical 
standards developed or adopted by voluntary consensus standards bodies 
unless the use of such standards is inconsistent with applicable law or 
is otherwise impractical. The NRC is amending its regulations to 
incorporate by reference regulatory guides that list ASME BPV Code 
Cases which have been approved by the NRC. ASME Code Cases, which are 
ASME-approved alternatives to the provisions of ASME Code editions and 
addenda, constitute national consensus standards, as defined in Pub. L. 
104-113 and Office of Management and Budget (OMB) Circular A-119. They 
are developed by bodies whose members (including the NRC and utilities) 
have broad and varied interests.
    The NRC reviews each Section III and Section XI Code Case published 
by the ASME to ascertain whether its application is consistent with the 
safe operation of nuclear power plants. Those Code Cases found to be 
generically acceptable are listed in the RGs which are incorporated by 
reference in Sec.  50.55a(b). Those that are found to be unacceptable 
are listed in RG 1.193, entitled Code Cases not Approved for Use; but 
licensees may still seek NRC's approval to apply these Code Cases 
through the relief request process permitted in Sec.  50.55a(a)(3). 
Other Code Cases, which the NRC finds to be conditionally acceptable, 
are also listed in the RGs which are incorporated by reference along 
with the modifications and limitations under which they may be applied. 
If the NRC did not provide for the conditional acceptance of ASME Code 
Cases, these Code Cases would be disapproved outright. The effect would 
be that licensees would need to submit a larger number of relief 
requests which would represent an unnecessary additional burden for 
both the licensee and the NRC. The NRC believes that this situation 
fits the definition of ``impractical,'' as it applies to Pub. L. 104-
113. For these reasons, The NRC believes that the treatment of ASME BPV 
Code Cases, and modifications and limitations placed on them, in this 
final rule does not conflict with any policy on agency use of consensus 
standards specified in OMB Circular A-119.

Finding of No Significant Environmental Impact: Availability

    The Commission has determined under the National Environmental 
Policy Act of 1969, Pub. L. 97-190 (42 U.S.C. 4321 et seq.), as 
amended, and the Commission's regulations in subpart A of 10 CFR part 
51, that this rule is not a major Federal action significantly 
affecting the quality of the human environment, and, therefore, an 
environmental impact statement is not required. The basis for this 
determination is that this rulemaking will not significantly increase 
the probability or consequences of accidents; no changes are being made 
in the types of effluents that may be released off site; and there is 
no significant increase in public or occupational radiation exposure. 
Therefore, there are no significant radiological impacts associated 
with the action. Also, no significant nonradiological impacts are 
associated with the action. Thus, the NRC determines that there will be 
no significant off site impact to the public from this action.
    The NRC requested the views of the States on the environmental 
assessment for the rule and did not receive any comments from the 
States.

Paperwork Reduction Act Statement

    This final rule decreases the burden on licensees by allowing the 
use of alternative Code Cases. There is an estimated industry-wide 
reduction of 713 hours annually for the anticipated reduction in the 
number information collections required. Because the burden for this 
information collection is insignificant, OMB clearance is not required. 
The existing requirements were approved by OMB, approval number 3150-
0011.

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.

Regulatory Analysis

    The ASME Code Cases listed in the RGs provide voluntary 
alternatives to the provisions in the ASME BPV Code and OM Code for 
construction, ISI, and IST of specific structures, systems, and 
components used in nuclear power plants. Implementation of these Code 
Cases is not required. Licensees use NRC-approved ASME Code Cases to 
reduce regulatory burden or gain additional operational flexibility. It 
would be difficult for the NRC to provide these advantages independent 
of the ASME Code Case publication process without a considerable 
additional resource expenditure by the agency. The NRC has prepared a 
regulatory analysis addressing the qualitative benefits of the 
alternatives considered in this rulemaking and comparing the costs 
associated with each alternative. The regulatory analysis is available 
to the public as indicated under the ``Availability of Documents'' 
section of this preamble.

Regulatory Flexibility Certification

    In accordance with the Regulatory Flexibility Act of 1980, Pub. L. 
96-354 (5 U.S.C. 605(b)), the Commission certifies that this final rule 
will not have a significant economic impact on a substantial number of 
small entities. This final rule 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 size standards 
established by the NRC (10 CFR 2.810).

Backfit Analysis

    The provisions in this final rule permit, but do not require, 
licensees to apply Code Cases that have been reviewed and approved by 
the NRC, sometimes with modifications or conditions. Therefore, the 
implementation of an approved Code Case is voluntary and does not 
constitute a backfit. Thus, the Commission finds that these amendments 
do not involve any provisions that constitute a backfit as defined in 
10 CFR 50.109(a)(1), that the backfit rule does not apply to this final 
rule, and that a backfit analysis is not required.

Small Business Regulatory Enforcement Fairness Act

    In accordance with the Small Business Regulatory Enforcement 
Fairness Act of 1996, the NRC has determined that this action is not a

[[Page 56812]]

major rule and has verified this determination with the Office of 
Information and Regulatory Affairs of OMB.

List of Subjects in 10 CFR Part 50

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

0
For the reasons set forth 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. 552 and 553, the NRC is adopting 
the following amendments to 10 CFR Part 50.

PART 50--DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION 
FACILITIES

0
1. The authority citation for Part 50 continues to read as follows:


    Authority:  Secs. 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, 2236, 2239, 2282); secs. 201, as amended, 202, 
206, 88 Stat. 1242, as amended, 1244, 1246 (42 U.S.C. 5841, 5842, 
5846); sec. 1704, 112 Stat. 2750 (44 U.S.C. 3504 note).
    Section 50.7 also issued under Pub. L. 95-601, sec. 10, 92 Stat. 
2951 (42 U.S.C. 5851). Section 50.10 also issued under secs. 101, 
185, 68 Stat. 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 sec. 204, 88 Stat. 1245 (42 U.S.C. 5844). Sections 50.58, 
50.91, and 50.92 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).


0
2. Section 50.55a is amended by removing paragraph (b)(2)(xxi)(C), 
revising the introductory text of paragraphs (b), (b)(4), and (b)(5), 
and paragraphs (f)(2), (f)(3)(iii)(A), (f)(3)(iv)(A), (f)(4)(ii), 
(g)(2), (g)(3)(i), (g)(3)(ii), (g)(4)(i) and (g)(4)(ii) to read as 
follows:


Sec.  50.55a  Codes and standards.

* * * * *
    (b) The ASME Boiler and Pressure Vessel Code and the ASME Code for 
Operation and Maintenance of Nuclear Power Plants, which are referenced 
in paragraphs (b)(1), (b)(2), and (b)(3) of this section, were approved 
for incorporation by reference by the Director of the Office of the 
Federal Register pursuant to 5 U.S.C. 552(a) and 1 CFR part 51. NRC 
Regulatory Guide 1.84, Revision 33, ``Design, Fabrication, and 
Materials Code Case Acceptability, ASME Section III'' (August 2005); 
NRC Regulatory Guide 1.147 (Revision 0-February 1981), including 
Revision 1 through Revision 14 (August 2005), ``Inservice Inspection 
Code Case Acceptability, ASME Section XI, Division 1''; and Regulatory 
Guide 1.192, ``Operation and Maintenance Code Case Acceptability, ASME 
OM Code'' (June 2003), have been approved for incorporation by 
reference by the Director of the Office of the Federal Register 
pursuant to 5 U.S.C. 552(a) and 1 CFR part 51. These regulatory guides 
list ASME Code cases which the NRC has approved in accordance with the 
requirements in paragraphs (b)(4), (b)(5), and (b)(6). Copies of the 
ASME Boiler and Pressure Vessel Code and the ASME Code for Operation 
and Maintenance of Nuclear Power Plants may be purchased from the 
American Society of Mechanical Engineers, Three Park Avenue, New York, 
NY 10016. Single copies of NRC Regulatory Guides 1.84, Revision 33; 
1.147, Revision 14; and 1.192 may be obtained free of charge by writing 
the Reproduction and Distribution Services Section, U.S. Nuclear 
Regulatory Commission, Washington, DC 20555-0001; or by fax to 301-415-
2289; or by e-mail to [email protected]. Copies of the ASME Codes 
and NRC Regulatory Guides incorporated by reference in this section may 
be inspected at the NRC Technical Library, Two White Flint North, 11545 
Rockville Pike, Rockville, MD 20852-2738, or at the National Archives 
and Records Administration (NARA). For information on the availability 
of this material at NARA, call 202-741-6030, or go to: http://www.archives.gov/federal_register/code_of_federal_regulations/ibr_locations.html.
* * * * *
    (4) Design, Fabrication, and Materials Code Cases. Licensees may 
apply the ASME Boiler and Pressure Vessel Code cases listed in NRC 
Regulatory Guide 1.84, Revision 33, without prior NRC approval subject 
to the following:
* * * * *
    (5) Inservice Inspection Code Cases. Licensees may apply the ASME 
Boiler and Pressure Vessel Code cases listed in Regulatory Guide 1.147 
through Revision 14, without prior NRC approval subject to the 
following:
* * * * *
    (f) * * *
    (2) For a boiling or pressurized water-cooled nuclear power 
facility whose construction permit was issued on or after January 1, 
1971, but before July 1, 1974, pumps and valves which are classified as 
ASME Code Class 1 and Class 2 must be designed and be provided with 
access to enable the performance of inservice tests for operational 
readiness set forth in editions and addenda of Section XI of the ASME 
Boiler and Pressure Vessel Code incorporated by reference in paragraph 
(b) of this section (or the optional ASME Code cases listed in NRC 
Regulatory Guide 1.147, through Revision 14, or 1.192 that are 
incorporated by reference in paragraph (b) of this section) in effect 
six months before the date of issuance of the construction permit. The 
pumps and valves may meet the inservice test requirements set forth in 
subsequent editions of this Code and addenda which are incorporated by 
reference in paragraph (b) of this section (or the optional ASME Code 
cases listed in NRC Regulatory Guide 1.147, through Revision 14, or 
1.192 that are incorporated by reference in paragraph (b) of this 
section), subject to the applicable limitations and modifications 
listed therein.
    (3) * * *
    (iii) * * *
    (A) Pumps and valves, in facilities whose construction permit was 
issued before November 22, 1999, which are classified as ASME Code 
Class 1 must be designed and be provided with access to enable the 
performance of inservice testing of the pumps and valves for assessing 
operational readiness set forth in the editions and addenda of Section 
XI of the ASME Boiler and Pressure Vessel Code incorporated by 
reference in paragraph (b) of this section (or the optional ASME Code 
cases listed in NRC Regulatory Guide 1.147, through Revision 14, or 
1.192 that are incorporated by reference in paragraph (b) of this 
section) applied to the construction of the particular pump or valve or 
the Summer 1973 Addenda, whichever is later.
* * * * *
    (iv) * * *
    (A) Pumps and valves, in facilities whose construction permit was 
issued before November 22, 1999, which are classified as ASME Code 
Class 2 and Class 3 must be designed and be

[[Page 56813]]

provided with access to enable the performance of inservice testing of 
the pumps and valves for assessing operational readiness set forth in 
the editions and addenda of Section XI of the ASME Boiler and Pressure 
Vessel Code incorporated by reference in paragraph (b) of this section 
(or the optional ASME Code cases listed in NRC Regulatory Guide 1.147, 
through Revision 14, that are incorporated by reference in paragraph 
(b) of this section) applied to the construction of the particular pump 
or valve or the Summer 1973 Addenda, whichever is later.
* * * * *
    (4) * * *
    (ii) Inservice tests to verify operational readiness of pumps and 
valves, whose function is required for safety, conducted during 
successive 120-month intervals must comply with the requirements of the 
latest edition and addenda of the Code incorporated by reference in 
paragraph (b) of this section 12 months before the start of the 120-
month interval (or the optional ASME Code cases listed in NRC 
Regulatory Guide 1.147, through Revision 14, or 1.192 that are 
incorporated by reference in paragraph (b) of this section), subject to 
the limitations and modifications listed in paragraph (b) of this 
section.
* * * * *
    (g) * * *
    (2) For a boiling or pressurized water-cooled nuclear power 
facility whose construction permit was issued on or after January 1, 
1971, but before July 1, 1974, components (including supports) which 
are classified as ASME Code Class 1 and Class 2 must be designed and be 
provided with access to enable the performance of inservice examination 
of such components (including supports) and must meet the preservice 
examination requirements set forth in editions and addenda of Section 
XI of the ASME Boiler and Pressure Vessel Code incorporated by 
reference in paragraph (b) of this section (or the optional ASME Code 
cases listed in NRC Regulatory Guide 1.147, through Revision 14, that 
are incorporated by reference in paragraph (b) of this section) in 
effect six months before the date of issuance of the construction 
permit. The components (including supports) may meet the requirements 
set forth in subsequent editions and addenda of this Code which are 
incorporated by reference in paragraph (b) of this section (or the 
optional ASME Code cases listed in NRC Regulatory Guide 1.147, through 
Revision 14, that are incorporated by reference in paragraph (b) of 
this section), subject to the applicable limitations and modifications.
    (3) * * *
    (i) Components (including supports) which are classified as ASME 
Code Class 1 must be designed and be provided with access to enable the 
performance of inservice examination of these components and must meet 
the preservice examination requirements set forth in the editions and 
addenda of Section XI of the ASME Boiler and Pressure Vessel Code 
incorporated by reference in paragraph (b) of this section (or the 
optional ASME Code cases listed in NRC Regulatory Guide 1.147, through 
Revision 14, that are incorporated by reference in paragraph (b) of 
this section) applied to the construction of the particular component.
    (ii) Components which are classified as ASME Code Class 2 and Class 
3 and supports for components which are classified as ASME Code Class 
1, Class 2, and Class 3 must be designed and be provided with access to 
enable the performance of inservice examination of these components and 
must meet the preservice examination requirements set forth in the 
editions and addenda of Section XI of the ASME Boiler and Pressure 
Vessel Code incorporated by reference in paragraph (b) of this section 
(or the optional ASME Code cases listed in NRC Regulatory Guide 1.147, 
through Revision 14, that are incorporated by reference in paragraph 
(b) of this section) applied to the construction of the particular 
component.
* * * * *
    (4) * * *
    (i) Inservice examinations of components and system pressure tests 
conducted during the initial 120-month inspection interval must comply 
with the requirements in the latest edition and addenda of the Code 
incorporated by reference in paragraph (b) of this section on the date 
12 months before the date of issuance of the operating license (or the 
optional ASME Code cases listed in NRC Regulatory Guide 1.147, through 
Revision 14, that are incorporated by reference in paragraph (b) of 
this section), subject to the limitations and modifications listed in 
paragraph (b) of this section.
    (ii) Inservice examination of components and system pressure tests 
conducted during successive 120-month inspection intervals must comply 
with the requirements of the latest edition and addenda of the Code 
incorporated by reference in paragraph (b) of this section 12 months 
before the start of the 120-month inspection interval (or the optional 
ASME Code cases listed in NRC Regulatory Guide 1.147, through Revision 
14, that are incorporated by reference in paragraph (b) of this 
section), subject to the limitations and modifications listed in 
paragraph (b) of this section.
* * * * *

    Dated at Rockville, Maryland, this 31st day of August, 2005.

    For the Nuclear Regulatory Commission.
Luis A. Reyes,
Executive Director for Operations.
[FR Doc. 05-19443 Filed 9-28-05; 8:45 am]
BILLING CODE 7590-01-P