[Federal Register Volume 71, Number 242 (Monday, December 18, 2006)]
[Notices]
[Pages 75774-75777]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: E6-21462]


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NUCLEAR REGULATORY COMMISSION


Notice of Opportunity To Comment on Model Safety Evaluation and 
Model License Amendment Request on Technical Specification Improvement 
Regarding Adding an Action Statement for Two Inoperable Control Room 
Air Conditioning Subsystems

AGENCY: Nuclear Regulatory Commission.

ACTION: Request for comment.

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SUMMARY: Notice is hereby given that the staff of the U.S. Nuclear 
Regulatory Commission (NRC) has prepared a model license amendment 
request (LAR), model safety evaluation (SE), and model proposed no 
significant hazards consideration (NSHC) determination related to 
changes to Standard Technical Specification (STS) 3.7.5 (STS 3.7.4 for 
BWR/6), ``Control Room Air Conditioning (AC) System'' for NUREG-1433 
and NUREG-1434. The proposed changes would also revise the Bases for 
STS 3.7.5 (STS 3.7.4 for BWR/6). The General Electric Boiling Water 
Reactor Owners Group (BWROG) participants in the Technical 
Specifications Task Force (TSTF) proposed these changes to the STS in 
TSTF-477, Revision 3, ``Add an Action for Two Inoperable Control Room 
AC Subsystems.''
    The purpose of these models is to permit the NRC to efficiently 
process amendments to incorporate changes into plant-specific Technical 
Specifications (TS) for General Electric Boiling Water Reactors (BWR). 
Licensees of nuclear power reactors to which the models apply can 
request amendments conforming to the models. In such a request, a 
licensee should confirm the applicability of the model LAR, model SE 
and NSHC determination to its plant. The NRC staff is requesting 
comments on the model LAR, model SE and NSHC determination before 
announcing their availability for referencing in license amendment 
applications.

DATES: The comment period expires 30 days from the date of this 
publication. Comments received after this date will be considered if it 
is practical to do so, but the Commission is able to ensure 
consideration only for comments received on or before this date.

ADDRESSES: Comments may be submitted either electronically or via U.S. 
mail.
    Submit written comments to: Chief, Rules and Directives Branch, 
Division of Administrative Services, Office of Administration, Mail 
Stop: T-6 D59, U.S. Nuclear Regulatory Commission, Washington, DC 
20555-0001. Hand deliver comments to: 11545 Rockville Pike, Rockville, 
Maryland, between 7:45 a.m. and 4:15 p.m. on Federal workdays. Submit 
comments by electronic mail to: [email protected].
    Copies of comments received may be examined at the NRC's Public 
Document Room, One White Flint North, Public File Area O1-F21, 11555 
Rockville Pike (first floor), Rockville, Maryland.

FOR FURTHER INFORMATION CONTACT: Peter C. Hearn, Mail Stop: O-12H2, 
Division of Inspection and Regional Support, Office of Nuclear Reactor 
Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555-
0001, telephone (301) 415-1189.

SUPPLEMENTARY INFORMATION:

Background

    Regulatory Issue Summary 2000-06, ``Consolidated Line Item 
Improvement Process [CLIIP] for Adopting Standard Technical 
Specifications Changes for Power Reactors,'' was issued on March 20, 
2000. The CLIIP is intended to improve the efficiency and transparency 
of NRC licensing processes. This is accomplished by processing proposed 
changes to the STS in a manner that supports subsequent license 
amendment applications. The CLIIP includes an opportunity for the 
public to comment on proposed changes to the STS following a 
preliminary assessment by the NRC staff and finding that the change 
will likely be offered for adoption by licensees. This notice is 
soliciting comments on a proposed change to the STS that adds an action 
statement for two inoperable control room subsystems to the General 
Electric BWR STS Revision 3.0 of NUREG-1433 and NUREG-1434. The CLIIP 
directs the NRC staff to evaluate any comments received for a proposed 
change to the STS and to either reconsider the change or proceed with 
announcing the availability of the change for proposed adoption by 
licensees. Those licensees opting to apply for the subject change to 
TSs are responsible for reviewing the staff's evaluation, referencing 
the applicable technical justifications, and providing any necessary 
plant-specific information. Following the public comment period, the 
model LAR and model SE will be finalized, and posted on the NRC Web 
page. Each amendment application made in response to the notice of 
availability will be processed and noticed in accordance with 
applicable NRC rules and procedures.
    This notice involves adding an action statement for two inoperable 
control room air conditioning subsystems. By letter dated September 8, 
2006, the BWROG proposed these changes for incorporation into the STS 
as TSTF-477, Revision 3. These changes are accessible electronically 
from the Agency-wide Documents Access and Management System's (ADAMS) 
Public Electronic Reading Room on the Internet (ADAMS Accession No. 
ML062510321) at the NRC Web site http://frwebgate.access.gpo.gov/cgi-bin/leaving.cgi?from=leavingFR.html&log=linklog&to=http://www.nrc.gov/reading-rm/adams.html.
    Persons who do not have access to ADAMS or who encounter problems 
in accessing the documents located in ADAMS should contact the NRC 
Public Document Room Reference staff by telephone at 1-800-397-4209, 
301-415-4737, or by e-mail to [email protected].

Applicability

    These proposed changes will revise Section 3.7.5 (Section 3.7.4 for 
BWR/6) for the General Electric plants.
    To efficiently process incoming license amendment applications, the 
NRC staff requests that each licensee applying for the changes 
addressed by TSTF-477, Revision 3, using the CLIIP submit an LAR that 
adheres to the following model. Any variations from the model LAR 
should be explained in the licensee's submittal. Variations from the 
approach recommended in this notice may require additional review by 
the NRC staff, and may increase the time and resources needed for the 
review. Significant variations from the approach, or inclusion of 
additional changes to the license, will result in staff rejection of 
the submittal. Instead, licensees desiring significant variations and/
or additional changes should submit a LAR that does not claim to adopt 
TSTF-477.

Public Notices

    This notice requests comments from interested members of the public 
within 30 days of the date of this publication. Following the NRC 
staff's evaluation of comments received as a result of this notice, the 
NRC staff may reconsider the proposed change or may proceed with 
announcing the availability of the change in a subsequent notice 
(perhaps with some changes to the model LAR, model SE or model NSHC 
determination

[[Page 75775]]

as a result of public comments). If the NRC staff announces the 
availability of the change, licensees wishing to adopt the change will 
submit an application in accordance with applicable rules and other 
regulatory requirements. The NRC staff will, in turn, issue for each 
application a notice of consideration of issuance of amendment to 
facility operating license(s), a proposed NSHC determination, and an 
opportunity for a hearing. A notice of issuance of an amendment to 
operating license(s) will also be issued to announce the revised 
requirements for each plant that applies for and receives the requested 
change.

    For the Nuclear Regulatory Commission.
    Dated at Rockville, Maryland, this 7th day of December, 2006.
Timothy J. Kobetz,
Chief, Technical Specifications Branch, Division of Inspection and 
Regional Support, Office of Nuclear Reactor Regulation.

ENCLOSURE 1

 1.0 Description

    This letter is a request to amend Operating License(s) [LICENSE 
NUMBER(S)] for [PLANT/UNIT NAME(S)].
    The proposed changes would revise Technical Specification 3.7.5 
(3.7.4 for BWR/6) ``Control Room Air Conditioning (AC) System'' to add 
an action statement for two inoperable control room subsystems. 
Technical Specification Task Force (TSTF) change traveler TSTF-477, 
Revision 3, ``Add Action for Two Inoperable Control Room AC 
Subsystems'' was announced for availability in the Federal Register on 
[DATE] as part of the consolidated line item improvement process 
(CLIIP).

2.0 Proposed Changes

    Consistent with NRC-approved TSTF-477, Revision 3, the proposed TS 
changes include: Add an action statement for two inoperable control 
room subsystems.

3.0 Background

    The background for this application is as stated in the model SE in 
NRC's Notice of Availability published on [DATE] [ ] FR [ ]), the NRC 
Notice for Comment published on [DATE] ([ ] FR [ ]), and TSTF-477, 
Revision 3.

4.0 Technical Analysis

    [LICENSEE] has reviewed References 1 and 2, and the model SE 
published on [DATE] ([ ] FR [ ]) as part of the CLIIP Notice for 
Comment. [LICENSEE] has applied the methodology in Reference 1 to 
develop the proposed TS changes. [LICENSEE] has also concluded that the 
justifications presented in TSTF-477, Revision 3 and the model SE 
prepared by the NRC staff are applicable to [PLANT, UNIT NOS.], and 
justify this amendment for the incorporation of the changes to the 
[PLANT] TS.

5.0 Regulatory Analysis

    A description of this change and its relationship to applicable 
regulatory requirements and guidance was provided in the NRC Notice of 
Availability published on [Date] ([FR [ ]), the NRC Notice for Comment 
published on [Date] ([ ] FR [ ]) and TSTF-477, Revision 3.

6.0 No Significant Hazards Consideration

    [LICENSEE] has reviewed the proposed no significant hazards 
consideration determination published in the Federal Register on [DATE] 
([ ] FR [ ]) as part of the CLIIP. [LICENSEE] has concluded that the 
proposed determination presented in the notice is applicable to [PLANT] 
and the determination is hereby incorporated by reference to satisfy 
the requirements of 10 CFR 50.91(a).

7.0 Environmental Evaluation

    [LICENSEE] has reviewed the environmental consideration included in 
the model SE published in the Federal Register on [DATE] ([ ] FR [ ]) 
as part of the CLIIP. [LICENSEE] has concluded that the staff's 
findings presented therein are applicable to [PLANT] and the 
determination is hereby incorporated by reference for this application.

8.0 References

    1. Federal Register Notices: Notice for Comment published on [DATE] 
([ ] FR [ ]) Notice of Availability published on [DATE] ([ ] FR [ ])

Enclosure 2

    Proposed Technical Specification Changes and Technical 
Specification Bases Changes (Mark-Up)

Enclosure 3

    Final Technical Specification and Bases Pages
    [Clean copies of Licensee specific Technical Specification (TS) 
pages, corresponding to the TS pages changed by TSTF-477, Rev 3, are to 
be included in Enclosure 3]

Model Safety Evaluation--U.S. Nuclear Regulatory Commission

Office of Nuclear Reactor Regulation--Technical Specification Task 
Force TSTF-477, Revision 3, ``Add an Action for Two Inoperable Control 
Room AC Subsystems.''

1.0 Introduction

    By letter dated [--, 20--], [LICENSEE] (the licensee) proposed 
changes to the technical specifications (TS) for [PLANT NAME]. The 
requested changes are the adoption of TSTF-477, Revision 3, ``Add 
Action for Two Inoperable Control Room AC Subsystems'' which was 
proposed by the Technical Specification Task Force (TSTF) by letter on 
August---- , 2006. The proposed changes revising Technical 
Specification 3.7.5 (3.7.4 for BWR/6) ``Control Room Air Conditioning 
(AC) System'' involve adding the following Limiting Conditions for 
Operation (LCO):

------------------------------------------------------------------------
 
------------------------------------------------------------------------
B. Two [control room AC]        B.1 Verify control      Once per 4
 subsystems inoperable.          room area Temperature   hours.
                                 < [90] [deg]F.
                                AND...................
                                B.2 Restore one         72 hours.
                                 [control room AC] to
                                 OPERABLE status.
------------------------------------------------------------------------

    The Technical Specification Task Force (TSTF) change traveler TSTF-
477, Revision 3, was announced for availability in the Federal Register 
on [DATE] as part of the consolidated line item improvement process 
(CLIIP).

2.0 Regulatory Evaluation

    Section 182a of the Atomic Energy Act (the ``Act'') requires 
applicants for nuclear power plant operating licenses to include TS as 
part of the license. The TS ensure the operational capability of 
structures, systems and components that are required to protect the 
health and safety of the public. The Commission's regulatory 
requirements related to the content of the TS are contained in 10 CFR 
Section 50.36. That regulation requires that the TS include items in 
the following specific categories: (1) safety limits, limiting safety 
systems settings, and limiting control settings

[[Page 75776]]

(50.36(c)(1)); (2) Limiting Conditions for Operation (50.36(c)(2)); (3) 
Surveillance Requirements (50.36(c)(3)); (4) design features 
(50.34(c)(4)); and (5) administrative controls (50.36(c)(5)).
    In general, there are two classes of changes to TS: (1) Changes 
needed to reflect modifications to the design basis (TS are derived 
from the design basis), and (2) voluntary changes to take advantage of 
the evolution in policy and guidance as to the required content and 
preferred format of TS over time. This amendment deals with the second 
class of changes.
    In determining the acceptability of revising STS 3.7.5 (STS 3.7.4 
for BWR/6), the staff used the accumulation of generically approved 
guidance in NUREG-1433, ``Standard Technical Specifications, Revision 3 
General Electric Plants, BWR/4'' dated June, 2004 and; NUREG-1434, 
Revision 3, ``Standard Technical Specifications, General Electric 
Plants, BWR/6'' dated June, 2004.
    Licensees may revise the TS to adopt current improved STS (iSTS) 
format and content provided that plant-specific review supports a 
finding of continued adequate safety because: (1) The change is 
editorial, administrative or provides clarification (i.e., no 
requirements are materially altered), (2) the change is more 
restrictive than the licensee's current requirement, or (3) the change 
is less restrictive than the licensee's current requirement, but 
nonetheless still affords adequate assurance of safety when judged 
against current regulatory standards. The detailed application of this 
general framework, and additional specialized guidance, are discussed 
in Section 3.0 in the context of specific proposed changes.

3.0 Technical Evaluation

    The BWR STS for the Control Room Air Conditioning AC System do not 
contain an Action Statement for two inoperable subsystems. During the 
TS Conversion of the BWR/6 Plants, the BWR/6 Plants adopted Action 
Statements for the Ventilation and AC systems that contained Action 
Statements for 2 inoperable subsystems similar to the proposed Action 
Statements in TSTF-477. The STS for numerous safety related systems 
also contain Action Statements for 2 inoperable subsystems. The TSTF 
proposes to add an Action Statement for 2 inoperable CR AC subsystems 
to the BWR STS in order to be consistent with the BWR/6 current iSTS. 
Furthermore, the consistency of the BWR STS will be enhanced since most 
safety related systems presently have Action Statements in the STS to 
address two inoperable subsystems.

3.1 NUREG-1433, Revision 3, ``Standard Technical Specifications, 
General Electric Plants, BWR/4''

    The proposed BWR/4 Action statement allows 72 hours to restore 1 
subsystem to the operable status for 2 inoperable subsystems. During 
the 72 hour completion time the CR Temperature is verified < 90 degrees 
every 4 hours. If 1 CRAC can not be restored to operable status or the 
CR Temperature can not be maintained < 90 degrees then the unit must be 
placed in at least Mode 3 within 12 hours and Mode 4 within 36 hours. 
Maintaining the CR Temperature < 90 degrees assures that the Safety 
Related Equipment in the CR will remain within the original licensed 
design operating temperature, because the maximum allowable CR 
Temperature is unchanged by TSTF-477. The NRC staff finds that the 
proposed changes in TSTF-477 are acceptable for the BWR/4 because the 
TSTF-477 changes provide TS requirements that the CR Temperature will 
be maintained within the original licensed design operating temperature 
of the CR equipment or the plant will be placed in the Cold Shutdown 
Mode (Mode 4, Safe Shut Condition).

3.2 NUREG-1434, Revision 3, ``Standard Technical Specifications, 
General Electric Plants, BWR/6''

    The proposed BWR/6 Action statement allows 7 days to restore 1 
subsystem to the operable status for 2 inoperable subsystems. This is 
consistent with the current BWR/6 Plants iSTS. During the 7 days 
completion time the CR Temperature is verified < 90 degrees every 4 
hours. If 1 CR AC cannot be restored to operable status or the CR 
Temperature cannot be maintained < 90 degrees then the unit must be 
placed in at least Mode 3 within 12 hours and Mode 4 within 36 hours. 
Maintaining the CR Temperature < 90 degrees assures that the Safety 
Related Equipment in the CR will remain within the original licensed 
design operating temperature, because the original allowable CR 
Temperature remains unchanged by TSTF-477. The NRC staff confirms that 
the proposed changes in TSTF-477 are acceptable for the BWR/6 because 
the TSTF-477 changes provide TS requirements that the CR Temperature 
will be maintained within the original licensed design operating 
temperature of the CR equipment or the plant will be placed in the Cold 
Shutdown Mode (Mode 4, Safe Shut Condition).

4.0 State Consultation

    In accordance with the Commission's regulations, the [ ] State 
official was notified of the proposed issuance of the amendment. The 
State official had [(1) no comments or (2) the following comments--with 
subsequent disposition by the staff].

5.0 Environmental Consideration

    The amendment[s] change[s] a requirement with respect to the 
installation or use of a facility component located within the 
restricted area as defined in 10 CFR part 20 or surveillance 
requirements. The NRC staff has determined that the amendment involves 
no significant increase in the amounts, and no significant change in 
the types, of any effluents that may be released offsite, and that 
there is no significant increase in individual or cumulative 
occupational radiation exposure. The Commission has previously issued a 
proposed finding that the amendment involves no significant hazards 
consideration and there has been no public comment on such finding 
published [DATE] ([ ] FR [ ]). Accordingly, the amendment meets the 
eligibility criteria for categorical exclusion set forth in 10 CFR 
51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact 
statement or environmental assessment need be prepared in connection 
with the issuance of the amendment.

6.0 Conclusion

    The Commission has concluded, based on the considerations discussed 
above, that (1) There is reasonable assurance that the health and 
safety of the public will not be endangered by operation in the 
proposed manner, (2) such activities will be conducted in compliance 
with the Commission's regulations, and (3) the issuance of the 
amendment will not be inimical to the common defense and security or to 
the health and safety of the public. Proposed No Significant Hazards 
Consideration Determination Description of Amendment Request: [Plant 
name] requests adoption of an approved change to the standard technical 
specifications (STS) for Boiling Water Reactor (BWR) Plants (NUREG-1433 
and NUREG-1434) and plant specific technical specifications (TS), to 
add an action statement for two inoperable control room subsystems. The 
changes are consistent with NRC approved Industry/Technical 
Specification Task Force (TSTF) Standard Technical Specifcation Change 
Traveler, TSTF-477, Revision 3.

[[Page 75777]]

    Basis for proposed no-significant-hazards-consideration 
determination: As required by 10 CFR 50.91(a), an analysis of the issue 
of no-significant-hazards-consideration is presented below:
    Criterion 1--The Proposed Change Does Not Involve a Significant 
Increase in the Probability or Consequences of an Accident Previously 
Evaluated
    The proposed change is described in Technical Specification Task 
Force (TSTF) Standard TS Change Traveler TSTF-477 adds an action 
statement for two inoperable control room subsystems.
    The proposed change does not involve a physical alteration of the 
plant (no new or different type of equipment will be installed). The 
proposed changes add an action statement for two inoperable control 
room subsystems. The equipment qualification temperature of the control 
room equipment is not affected. Future changes to the Bases or 
licensee-controlled document will be evaluated pursuant to the 
requirements of 10 CFR 50.59, `` Changes, test and experiments'', to 
ensure that such changes do not result in more than a minimal increase 
in the probability or consequences of an accident previously evaluated.
    The proposed changes do not adversely affect accident initiators or 
precursors nor alter the design assumptions, conditions, and 
configuration of the facility or the manner in which the plant is 
operated and maintained. The proposed changes do not adversely affect 
the ability of structures, systems and components (SSCs) to perform 
their intended safety function to mitigate the consequences of an 
initiating event within the assumed acceptance limits. The proposed 
changes do not affect the source term, containment isolation, or 
radiological consequences of any accident previously evaluated. 
Further, the proposed changes do not increase the types and the amounts 
of radioactive effluent that may be released, nor significantly 
increase individual or cumulative occupation/public radiation 
exposures.
    Therefore, the changes do not involve a significant increase in the 
probability or consequences of any accident previously evaluated.
    Criterion 2--The Proposed Change Does Not Create the Possibility of 
a New or Different Kind of Accident from any Previously Evaluated
    The proposed changes add an action statement for two inoperable 
control room subsystems. The changes do not involve a physical altering 
of the plant (i.e., no new or different type of equipment will be 
installed) or a change in methods governing normal pant operation. The 
requirements in the TS continue to require maintaining the control room 
temperature within the design limits.
    Therefore, the changes do not create the possibility of a new or 
different kind of accident from any previously evaluated.
    Criterion 3--The Proposed Change Does Not Involve a Significant 
Reduction in the Margin of Safety
    The proposed changes add an action statement for two inoperable 
control room subsystems. Instituting the proposed changes will continue 
to maintain the control room temperature within design limits. Changes 
to the Bases or license controlled document are performed in accordance 
with 10 CFR 50.59. This approach provides an effective level of 
regulatory control and ensures that the control room temperature will 
be maintained within design limits.
    The proposed changes maintain sufficient controls to preserve the 
current margins of safety.
    Based upon the reasoning above, the NRC staff concludes that the 
amendment request involves no significant hazards consideration.

    For the Nuclear Regulatory Commission.
Project Manager, Plant Licensing Branch [ ], Division of Operating 
Reactor Licensing, Office of Nuclear Reactor Regulation.
 [FR Doc. E6-21462 Filed 12-15-06; 8:45 am]
BILLING CODE 7590-01-P