[Federal Register Volume 71, Number 193 (Thursday, October 5, 2006)]
[Notices]
[Pages 58884-58888]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E6-16450]


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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 the Removal of the Main Steam and Main Feedwater Isolation 
Valve Times Using the Consolidated Line Item Improvement Process

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 NUREG-1430, 1431, 1432, 
(STS) 3.7.2, ``Main Stream Isolation Valves (MSIVs);'' NUREG-1430, STS 
3.7.3, ``Main Feedwater Stop Valves (MFSVs), Main Feedwater Control 
Valves (MFCVs), and Associated Startup Feedwater Control Valves 
(SFCVs);'' NUREG-1431, STS 3.7.3, ``Main Feedwater Isolation Valves 
(MFIVs), Main Feedwater Regulation Valves (MFRVs), and Associated 
Bypass Valves;'' and NUREG-1432, STS 3.7.3,''Main Feedwater Isolation 
Valves (MFIVs), and MFIV Bypass Valves.'' These valves are herein 
referred to generically as the Main Steam and Main Feedwater Isolation 
Valves. The Babcocks and Wilcocks Owners Group (BWOG), the Combustion 
Engineering Owners Group (CEOG) and the Westinghouse Owners Group (WOG) 
participants in the Technical Specifications Task Force (TSTF) proposed 
these changes to the STS in TSTF-491, Revision 2 ``Removal of Main 
Steam and Feedwater Valve Isolation Times.''

[[Page 58885]]

    The purpose of these models is to permit the NRC to efficiently 
process amendments to incorporate these changes into plant-specific 
Technical Specifications (TS) for Babcock and Wilcock Pressurized Water 
Reactors (BWPWR), Combustion Engineering Pressurized Water Reactors 
(CEPWR) and Westinghouse Pressurized Water Reactors (WPWR). 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 November 6, 2006. 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, Rulemaking, Directives, and 
Editing 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: CLIIP@nrc.gov. 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, e-mail pch@nrc.gov.

SUPPLEMENTARY INFORMATION:

Background

    Regulatory Issue Summary 2000-06, ``Consolidated Line Item 
Improvement Process 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 comment on 
a proposed change to the STS that relocates the Main Steam and Main 
Feedwater Isolation Valves Closure Times for the Babcock and Wilcock 
PWR STS Revision 3.0 of NUREG-1430, Combustion Engineering PWR STS 
Revision 3.0 of NUREG-1432 and Westinghouse PWR STS Revision 3.0 of 
NUREG-1431 to a Licensee Controlled Document that is referenced in the 
Bases. 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 relocating the Main Steam and Main Feedwater 
Isolation Valves Closure Times for the Babcock and Wilcock PWRs, 
Combustion Engineering PWRs and Westinghouse PWRs to a Licensee 
Controlled Document that is referenced in the Bases. By letter dated 
May 18, 2006, the BWPWR, CEPWR and the WPWR OG proposed these changes 
for incorporation into the STS as TSTF-491, Revision 2. 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. ML061500078) 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 pdr@nrc.gov.

Applicability

    These proposed changes will revise the Sections 3.7.2 and 3.7.3 for 
the Babcock and Wilcock, Combustion Engineering and Westinghouse 
plants.
    To efficiently process the incoming license amendment applications, 
the NRC staff requests that each licensee applying for the changes 
addressed by TSTF-491, Revision 2, 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-491.

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 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.

    Dated at Rockville, Maryland this 28th day of September 2006.

    For the Nuclear Regulatory Commission.
Timothy J. Kobetz,
Chief, Technical Specifications Branch, Division of Inspection and 
Regional Support, Office of Nuclear Reactor Regulation.
    Attachments--For inclusion on the Technical Specification Web Page 
the following example of an application was

[[Page 58886]]

prepared by the NRC staff to facilitate the adoption of Technical 
Specifications Task Force (TSTF) Traveler TSTF-491, Revision 2. The 
model provides the expected level of detail and content for an 
application to adopt TSTF-491, Revision 2. Licensees remain responsible 
for ensuring that their actual application fulfills their 
administrative requirements as well as NRC regulations.
    U.S. Nuclear Regulatory Commission, Document Control Desk, 
Washington, DC 20555.Subject: Plant Name, Docket No. 50-[XXX,] Re: 
Application For Technical Specification Improvement To Adopt TSTF-491, 
Revision 2 ``Removal of Main Steam and Feedwater Valve Isolation 
Times.''
    Dear Sir or Madam:
    In accordance with the provisions of Section 50.90 of Title 10 of 
the Code of Federal Regulations (10 CFR), [LICENSEE] is submitting a 
request for an amendment to the technical specifications (TS) for 
[PLANT NAME, UNIT NOS.]. The proposed changes would revise Sections 
3.7.2, ``Main Steam Isolation Valves'' and 3.7.3, ``Main Feedwater 
Isolation Valves''. The changes are consistent with NRC-approved 
Industry Technical Specification Task Force (TSTF) Standard Technical 
Specification Change Traveler, TSTF-491, Revision 2 ``Removal of Main 
Steam and Feedwater Valve Isolation Times.'' The availability of this 
TS improvement was announced in the Federal Register on [DATE] ([ ]FR[ 
]) as part of the consolidated line item improvement process CLIIP.
    Enclosure 1 provides a description and assessment of the proposed 
changes, as well as confirmation of applicability. Enclosure 2 provides 
the existing TS pages and TS Bases marked-up to show the proposed 
changes. Enclosure 3 provides final TS pages and TS Bases pages.
    [LICENSEE] requests approval of the proposed license amendment by 
[DATE], with the amendment being implemented [BY DATE OR WITHIN X 
DAYS]. In accordance with 10 CFR 50.91, a copy of this application, 
with enclosures, is being provided to the designated [STATE] Official.
    I declare under penalty of perjury under the laws of the United 
States of America that I am authorized by [LICENSEE] to make this 
request and that the foregoing is true and correct. [Note that request 
may be notarized in lieu of using this oath or affirmation statement]. 
If you should have any questions regarding this submittal, please 
contact [ ].

Sincerely,

Name, Title

Enclosures:

1. Description and Assessment of Proposed Changes
2. Proposed Technical Specification Changes and Technical Specification 
Bases Changes
3. Final Technical Specification and Bases pages
cc: NRR Project Manager, Regional Office, Resident Inspector, State 
Contact, T. Kobetz.

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 3.7.2 `` 
Main Steam Valves Closure Times'' and 3.7.3 ``Main Feedwater Isolation 
Valves Closure Times'' to allow relocating the closure times to a 
Licensee Controlled Document that is referenced in the BasesTechnical 
Specification Task Force (TSTF) change traveler TSTF-491, Revision 2, 
``Removal of Main Steam and Feedwater Valve Isolation Times'' 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--491, Revision 2, the proposed TS 
changes include: Relocating the main steam and main feedwater isolation 
closure times to a Licensee Controlled Document that is referenced in 
the Bases.

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-491, 
Revision 2.

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-491, Revision 2 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-491, Revision 2.

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 [ ]).
    Model Safety Evaluation--U.S. Nuclear Regulatory Commission.
    Office of Nuclear Reactor Regulation-``Technical Specification Task 
Force TSTF-491, Revision 2, ``Removal of Main Steam and Feedwater Valve 
Isolation Times.''
    Model Safety Evaluation--U.S. Nuclear Regulatory Commission, Office 
of Nuclear Reactor Regulation--``Technical Specification Task Force 
TSTF-491, Revision 2,''--``Removal of Main Steam and Feedwater Valve 
Isolation Times.''

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-491, Revision 2, ``Removal 
of Main Steam and Feedwater Valve Isolation Times'' which was proposed 
by the Technical Specification Task Force (TSTF) by letter on May 18, 
2006. The proposed changes would revise Technical Specification 3.7.2 
`` Main Steam Valves Closure Times'' and 3.7.3 ``Main Feedwater 
Isolation Valves Closure

[[Page 58887]]

Times.'' The proposed TSTF would allow relocating the isolation valve 
closure times to a Licensee Controlled Document that is referenced in 
the Bases. Technical Specification Task Force (TSTF) change traveler 
TSTF-491, Revision 2, 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 (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 3.7.2 and 3.7.3, 
the staff used the accumulation of generically approved guidance in 
NUREG-1430, ``Standard Technical Specifications, Revision 3 Babcock and 
Wilcox Plants,'' dated June, 2004; NUREG-1431, Revision 3, ``Standard 
Technical Specifications, Westinghouse Plants,'' dated June, 2004; and 
NUREG-1432, ``Standard Technical Specifications, Revision 3 Combustion 
Engineering Plants,'' dated June, 2004.
    Licensees may revise the TS to adopt current improved STS 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. Nomenclature specific to the 
Westinghouse Plants is used in the following Technical Evaluation.

3.0 Technical Evaluation

    The NRC staff has reviewed the justification for the proposed TSTF 
as described in the September 13, 2005 submittal. The detailed 
evaluation below will support the conclusion 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.

3.1 Main Steam Isolation Valves (MSIV)

    One MSIV is located in each main steam line outside of the 
containment. Closing the MSIVs isolates each steam generator from the 
others and isolates the turbine, steam bypass system and other 
auxiliary steam supplies from the steam generator.
    By isolating the steam flow from the secondary side of the steam 
generator the MSIVs prevent over cooling the reactor core following a 
high energy line break (HELB). By preventing core overcooling the MSIVs 
protect the reactor core from being damaged.
    TSTF-491 is proposing to relocate the required closure times for 
the MSIVs to the Licensee Controlled Document (LCD) that is referenced 
in the Bases. Changes to LCDs are subject to the 10 CFR 50.59 process. 
The 10 CFR 50.59 criteria provide adequate assurance that prior staff 
review and approval will be requested by the licensee for changes to 
the Bases or LCD requirements with the potential to affect the safe 
operation of the plant. Furthermore, the MSIVs are subject to periodic 
testing and acceptance criteria in accordance with the Inservice 
Testing (IST) Program. Compliance with the IST Program is required by 
Section 5.5.7 of the Standard Technical Specifications (STS) and 10 CFR 
50.55. The IST Program includes specific reference value baseline 
operating times for valves that are not subject to arbitrary changes.
    10 CFR 50.36 requires the inclusion of the periodic testing of the 
MSIVs in the Surveillance Requirements not the actual closure time of 
the valves. TSTF-491 change maintains the periodic testing requirements 
for MSIVs in accordance with 10 CFR 50.36.
    Based on the requirements of 10 CFR 50.36, 10 CFR 50.59 and IST 
Program, the staff concludes that relocating the MSIV closure time to 
the LCD as referenced in the Bases is acceptable.

3.2 Main Feedwater Isolation Valve (MFIV), Main Feedwater Regulation/
Control Valve (MFRV) and Associated Bypass Valves (BV)

    The MFIVs and BVs or the MFRVs and BVs isolate the nonsafety 
related portions from the safety related portions of the system. In the 
event of a secondary side pipe rupture inside containment, these valves 
limit the quantity of high energy fluid that enters the containment 
through the break and provide a pressure boundary for the controlled 
addition of auxiliary feedwater to the intact loops.
    By isolating the feedwater flow from the affected steam generator 
the MFIVs, MFRVs and BVs prevent overcooling the reactor core and over 
pressurizing of the containment from feedwater pump runout.
    As with the MSIVs, TSTF-491 is also proposing to relocate the 
required closure times for the MFIVs, MFRVs and BVS to the LCD that is 
referenced in the Bases. Changes to the Bases or LCD are subject to the 
10 CFR 50.59 process. The 10 CFR 50.59 criteria provide adequate 
assurance that prior staff review and approval will be requested by the 
licensee for changes to the Bases or Licensee Controlled Document 
requirements with the potential to affect the safe operation of the 
plant. Furthermore, the MFIVs, MFRVs and BVs are subject to periodic 
testing and acceptance criteria in accordance with the Inservice 
Testing (IST) Program. Compliance with the IST Program is required by 
Section 5.5.7 of the Standard Technical Specifications (STS) and 10 CFR 
50.55. The IST Program includes specific reference value baseline 
operating times for valves that are not subject to arbitrary changes.
    10 CFR 50.36 requires the inclusion of the periodic testing of the 
MFIVs, MFRVs and BVs in the Surveillance Requirements not the actual 
closure time of the valves. TSTF-491 maintains the periodic testing 
requirements for MFIVs, MFRVs and BVs in accordance with 10 CFR 50.36.
    Based on the requirements of 10 CFR 50.36, 10 CFR 50.59 and the IST 
Program, the staff concludes that relocating the MFIVs, MFRVs and BVs 
closure times to the LCD as referenced in the Bases is acceptable.

[[Page 58888]]

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 Babcock and Wilcock PWR STS Revision 3.0 of 
NUREG-1430, Combustion Engineering PWR STS Revision 3.0 of NUREG-1432 
and Westinghouse PWR STS Revision 3.0 of NUREG-1431 plant specific 
technical specifications (TS), to allow relocating the main steam and 
main feedwater isolation valve closure times to a Licensee Controlled 
Document that is referenced in the Bases. The changes are consistent 
with NRC approved Industry/Technical Specification Task Force (TSTF) 
Standard Technical Specifcation Change Traveler, TSTF-491, Revision 2.
    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 allows relocating main steam and main 
feedwater valve isolation times to the Licensee Controlled Document 
that is referenced in the Bases. The proposed change is described in 
Technical Specification Task Force (TSTF) Standard TS Change 
Traveler TSTF-491 related to relocating the main steam and main 
feedwater valves isolation times to the Licensee Controlled Document 
that is referenced in the Bases and replacing the isolation time 
with the phase, ``within limits.''
    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 relocate the main steam and main feedwater 
isolation valve times to the Licensee Controlled Document that is 
referenced in the Bases. The requirements to perform the testing of 
these isolation valves are retained in the TS. 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 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 relocate the main steam and main feedwater 
valve isolation times to the Licensee Controlled Document that is 
referenced in the Bases. In addition, the valve isolation times are 
replaced in the TS with the phase ``within limits''. 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 testing of the main steam and main feedwater 
isolation valves to ensure the proper functioning of these isolation 
valves.
    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 relocate the main steam and main feedwater 
valve isolation times to the Licensee Controlled Document that is 
referenced in the Bases. In addition, the valve isolation times are 
replaced in the TS with the phase ``within limits''. Instituting the 
proposed changes will continue to ensure the testing of main steam 
and main feedwater isolation valves. 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 main steam and feedwater isolation valve testing is 
conducted such that there is no significant reduction in the margin 
of safety.
    The margin of safety provided by the isolation valves is 
unaffected by the proposed changes since there continue to be TS 
requirements to ensure the testing of main steam and main feedwater 
isolation valves. 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. E6-16450 Filed 10-4-06; 8:45 am]
BILLING CODE 7590-01-P