ML103560088

Issuance of Amendment Nos. 184, 184, and 184, Revise Technical Specification 5.5.8, Inservice Testing Program, to Implement TS Task Force (TSTF)-479-A as Modifed by TSTF-497-A (TAC ME3914, ME3915, and ME3916)

ML103560088
Person / Time
Site:	Palo Verde
Issue date:	01/19/2011
From:	Hall J Plant Licensing Branch IV
To:	Edington R Arizona Public Service Co
Gibson, Lauren, NRR/DORL/LPL4, 415-1056
References
TAC ME3914, TAC ME3915, TAC ME3916
Download: ML103560088 (19)

Text

UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 January 19, 2011 Mr. Randall K.

Executive Vice President Chief Nuclear Officer Mail Station 7602 Arizona Public Service Company P.O. Box 52034 Phoenix, AZ 85072-2034 PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2, AND ISSUANCE OF AMENDMENTS RE: REVISE TECHNICAL SPECIFICATION 5.5.8, INSERVICE TESTING PROGRAM (TAC NOS. ME3914, ME3915, AI\ID ME3916)

Dear Mr. Edington:

The Commission has issued the enclosed Amendment No. 184 to Facility Operating License No. NPF-41, Amendment No. 184 to Facility Operating License No. NPF-51, and Amendment No. 184 to Facility Operating License No. NPF-74 for the Palo Verde Nuclear Generating Station, Units 1, 2, and 3, respectively.

The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated April 29, 2010, as supplemented by letter dated August 24, 2010. The amendments revise the TSs to incorporate Technical Specifications Task Force (TSTF) change traveler TSTF-479-A, "Changes to Reflect Revision of 10 CFR 50.55a," as modified by TSTF-497-A, "Limit Inservice Testing Program SR [Surveillance Requirement]

3.0.2 Application to Frequencies of 2 Years or Less." Specifically, the changes associated with TSTF-479-A replace the reference in TS 5.5.8, "Inservice Testing Program," with a reference to the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code to the ASME Code for Operation and Maintenance of Nuclear Power Plants (OM Code) and specify that the extension allowance of SRs is applicable to the frequencies in the Inservice Testing Program (1ST). The changes associated with TSTF-497-A limit the applicability of SR 3.0.2 to frequencies of 2 years or less. In addition, the amendment removes the reference to component supports for consistency with the Standard Technical Specifications because the supports are included in the licensee's Inservice Inspection Program.

R. Edington -2 A copy of the related Safety Evaluation is also enclosed.

The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice. Sincerely, J" 7U1:" a es R. Hall, Senior Project Manager ant Licensing Branch Division of Operating Reactor Office of Nuclear Reactor Docket Nos. STN 50-528, STN and STN

Enclosures:

1. Amendment No. 184 to 2. Amendment No. 184 to 3. Amendment No. 184 to 4. Safety Evaluation cc w/encls: Distribution via Listserv UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 ARIZONA PUBLIC SERVICE COMPANY, ET AL. DOCKET NO. STN 50-528 PALO VERDE NUCLEAR GENERATING STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 184 License No. NPF-41 The Nuclear Regulatory Commission (the Commission) has found that: The application for amendment by the Arizona Public Service Company (APS or the licensee) on behalf of itself and the Salt River Project Agricultural Improvement and Power District, EI Paso Electric Company, Southern California Edison Company, Public Service Company of New Mexico, Los Angeles Department of Water and Power, and Southern California Public Power Authority dated April 29, 2010, as supplemented by letter dated August 24, 2010, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations set forth in 10 CFR Chapter I; The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

Enclosure 1

R. -2Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C(2) of Facility Operating License No. NPF-41 is hereby amended to read as follows: (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 184, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license. APS shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, except where otherwise stated in specific license conditions. This license amendment is effective as of the date of issuance and shall be implemented within 90 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Michael T. Markley, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Facility Operating License No. NPF-41 and Technical Specifications Date of Issuance:

January 19, 2011 UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 ARIZONA PUBLIC SERVICE COMPANY, ET AL. DOCKET NO. STN 50-529 PALO VERDE NUCLEAR GENERATING STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 184 License No. NPF-51 The Nuclear Regulatory Commission (the Commission) has found that: The application for amendment by the Arizona Public Service Company (APS or the licensee) on behalf of itself and the Salt River Project Agricultural Improvement and Power District, EI Paso Electric Company, Southern California Edison Company, Public Service Company of New Mexico, Los Angeles Department of Water and Power, and Southern California Public Power Authority dated April 29, 2010, as supplemented by letter dated August 24, 2010, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations set forth in 10 CFR Chapter I; The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

Enclosure 2

-Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C(2) of Facility Operating License No. NPF-51 is hereby amended to read as follows: (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 184, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license. APS shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, except where otherwise stated in specific license conditions. This license amendment is effective as of the date of issuance and shall be implemented within 90 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Michael T. Markley, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Facility Operating License No. NPF-51 and Technical Specifications Date of Issuance:

January 19, 2011 UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 ARIZONA PUBLIC SERVICE COMPANY, ET AL. DOCKET NO. STN 50-530 PALO VERDE NUCLEAR GENERATING STATION, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 184 License No. NPF-74 The Nuclear Regulatory Commission (the Commission) has found that: The application for amendment by the Arizona Public Service Company (APS or the licensee) on behalf of itself and the Salt River Project Agricultural Improvement and Power District, EI Paso Electric Company, Southern California Edison Company, Public Service Company of New Mexico, Los Angeles Department of Water and Power, and Southern California Public Power Authority dated April 29, 2010, as supplemented by letter dated August 24, 2010, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations set forth in 10 CFR Chapter I; The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

Enclosure 3

-2Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C(2) of Facility Operating License No. NPF-74 is hereby amended to read as follows: (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 184, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license. APS shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, except where otherwise stated in specific license conditions. This license amendment is effective as of the date of issuance and shall be implemented within 90 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Michael T. Markley, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Attachment Changes to the Facility Operating License No. NPF-74 and Technical Specifications Date of Issuance:

January 19, 2011 ATTACHMENT TO LICENSE AMENDMENT NOS. 184, 184, AND FACILITY OPERATING LICENSE NOS. NPF-41, NPF-51. AND DOCKET NOS. STN 50-528. STN 50-529, AND STN Replace the following pages of the Facility Operating Licenses Nos. NPF-41, NPF-51, and NPF-74, and Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change. Operating REMOVE Replace Page 5 of Facility Operating License No. NPF-41 with the attached Page Replace Page 6 of Facility Operating License No. NPF-51 with the attached Page Replace Page 4 of Facility Operating License No. NPF-74 with the attached Page Technical Specifications REMOVE INSERT 5.5-5 5.5-5 (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 184, and the Environmental Protection Plan contained in Appendix S, are hereby incorporated into this license. APS shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, except where otherwise stated in specific license conditions. Antitrust Conditions This license is subject to the antitrust conditions delineated in Appendix C to this license. Operating Staff Experience Requirements Deleted Post-Fuel-Loading Initial Test Program (Section 14, SER and SSER 2)* Deleted Environmental Qualification Deleted Fire Protection Program APS shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report for the facility, as supplemented and amended, and as approved in the SER through Supplement 11, subject to the following provision:

APS may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire. Emergency Preparedness Deleted "The parenthetical notation following the title of many license conditions denotes the section of the Safety Evaluation Report and/or its supplements wherein the license condition is discussed.

Amendment No. 184 (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 184, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license. APS shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, except where otherwise stated in specific license conditions. Antitrust Conditions This license is subject to the antitrust conditions delineated in Appendix C to this license. Operating Staff Experience Requirements (Section 13.1.2. SSER 9)* Deleted Initial Test Program (Section 14. SER and SSER 2) Deleted Fire Protection Program APS shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report for the facility, as supplemented and amended, and as approved in the SER through Supplement 11, subject to the following provision:

APS may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire. Inservice Inspection Program (Sections 5.2.4 and 6.6, SER and SSER 9) Deleted Supplement NO.1 to NUREG-0737 Requirements Deleted *The parenthetical notation following the title of many license conditions denotes the section of the Safety Evaluation Report and/or its supplements wherein the license condition is discussed.

Amendment No. 184 Maximum Power Level Arizona Public Service Company (APS) is authorized to operate the facility at reactor core power levels not in excess of 3990 megawatts thermal (100% power),in accordance with the conditions specified herein. Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 184, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license. APS shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, except where otherwise stated in specific license conditions. Antitrust Conditions This license is subject to the antitrust conditions delineated in Appendix C to this license. Initial Test Program (Section 14, SER and SSER 2) Deleted Additional Conditions The Additional Conditions contained in Appendix D, as revised through Amendment No. 171, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Additional Conditions. Mitigation Strategy License Condition APS shall develop and maintain strategies for addressing large fires and explosions and that include the following key areas: Fire fighting response strategy with the following elements: Pre-defined coordinated fire response strategy and guidance. Assessment of mutual aid fire fighting assets. Designated staging areas for equipment and materials. Command and control. Training of response personnel.

Amendment No. 184 Programs and Manuals 5.5 Programs and Manuals 5.5.7 Reactor Coolant Pump Flywheel Inspection Program program shall provide for the inspection of each reactor coolant pump flywheel per the recommendations of regulatory position c.4.b of Regulatory Guide 1.14, Revision 0, October 1971. 5.5.8 Inservice Testing Program program provides controls for inservice testing of ASME Code Class 1, 2. and 3 components.

The program shall include the following: Testing frequencies applicable to the ASME Code for Operation and Maintenance of Nuclear Power Plants (ASME OM Code) and applicable Addenda as follows: OM Code applicable terminology for Required Frequencies inservice testing for perform'j ng i nservi ce acti viti es testing activities Weekly At least once per 7 days At least once per 31 days Quarterly or every 3 months At least once per 92 days Semi annually or every 6 months At least once per 184 days Every 9 months At least once per 276 days Yearly or annually At least once per 366 days Biennially or every 2 years At least once per 731 days b. The provisions of SR 3.0.2 are applicable to the above reqUired Frequencies and to other normal and accelerated Frequencies specified as 2 years or less in the Inservice Testing Program for performing inservice testing activities:

c. fhe provisions of SR 3.0.3 are applicable to inservice testing activities:

and Nothing in the ASME OM Code shall be construed to supersede the requirements of any T5. (continued)

PALO VERDE UNITS 1,2,3 AMENDMENT NO. 184 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 184 TO FACILITY OPERATING LICENSE NO. NPF-41, AMENDMENT NO. 184 TO FACILITY OPERATING LICENSE NO. NPF-51, AND AMENDMENT NO. 184 TO FACILITY OPERATING LICENSE NO. NPF-74 ARIZONA PUBLIC SERVICE COMPANY, ET AL. PALO VERDE NUCLEAR GENERATING STATION, UNITS 1,2, AND 3 DOCKET NOS. STN 50-528, STN 50-529, AND STN 50-530

1.0 INTRODUCTION

By letter dated April 29, 2010 (Agencywide Documents Access and Management (ADAMS) Accession No. ML101310224), as supplemented by letter dated August (ADAMS Accession No. ML102440121), Arizona Public Service Company (APS, the requested to amend the operating licenses for Palo Verde Nuclear Generating Station Units 1, 2, and 3, by revising Specification (TS) 5.5.8, "Inservice Testing requirements. The proposed amendment would implement Technical Specifications Task (TSTF) change travelers TSTF-479-A, Revision 0, "Changes to Reflect Revision of 10 [Title 10 of the Code of Federal Regulations]

50.55a," as modified by TSTF-497-A, Revision "Limit Inservice Testing Program SR [Surveillance Requirement]

3.0.2 Application Frequencies of 2 Years or The supplemental letter dated August 24, 2010, provided additional information that clarified application, did not expand the scope of the application as originally noticed, and did not the U.S. Nuclear Regulatory Commission (NRC) staffs original proposed no significant consideration determination as published in the Federal Register on July 27,2010 (75 In its letter dated April 29, 2010, the licensee proposed the following specific

• Revise the Technical Specifications (TS) to align with the requirements of 10 CFR 50.55a, "Codes and Standards;'

paragraph (f), "Inservice Testing (1ST) Requirements,

• Add a provision in the applicable TS section to only apply the extension allowance of Surveillance Requirement (SR) 3.0.2 to the frequency table Enclosure 4

-2 listed in the TS as part of the 1ST Program arid to normal and accelerated 1ST frequencies of two years or less, as applicable, and Remove a reference to component supports for consistency with the Standard Technical Specifications.

Component supports are part of the Inservice Inspection Program at PVNGS. The letter dated April 29, 2010, further states that'these proposed changes will align the PVNGS specification wording to that of NUREG-1432, Revision 3.1, Standard Technical Specifications Combustion Engineering Plants:' REGULATORY EVALUATION The Commission's regulatory requirements related to the content of the TSs are contained in Section 50.36, 'Technical specifications;'

of 10 CFR. That regulation requires that the TSs include items in the following specific categories:

(1) safety limits, limiting safety systems settings, and limiting control settings, (2) limiting conditions for operation, (3) SRs, (4) design features, and (5) administrative controls.

The Commission's regulations in 10 CFR 50.55a, 'Codes and standards;'

define the requirements for applying industry codes to each licensed power facility.

10 CFR 50.55a(f)(4)(i) requires licensees to prepare programs for inservice testing of certain ASME Code Class 1, 2, and 3 pumps and valves during the initial 120-month interval.

The regulations require that programs be developed using the latest edition and addenda incorporated into paragraph (b) of 10 CFR 50.55a on the date 12 months prior to the date of issuance of the operating license subject to the limitations and modifications identified in paragraph (b). Paragraph 50.55a(f)(4)(ii) requires that the inservice testing programs be updated during successive 120-month intervals to comply with the latest edition and addenda of the ASME Code incorporated by reference into 10 CFR 50.55a(b).

The NRC staff reviewed the proposed changes for compliance with 10 CFR 50.36 and consistency with the precedent as established in NUREG-1432, Revision 3 (ADAMS Accession No. ML041830597), including TSTF-479 (ADAMS Accession No. ML052990317) and TSTF-497 (ADAMS Accession No. ML061930221).

The NRC approved Revision 0 of TSTF-479, "Changes to Reflect Revision of 10 CFR 50.55a;' by letter dated December 6,2005 (ADAMS Accession No. ML053460302).

TSTF-479, Revision 0, revises references in the Standard Technical Specifications (STS) Administrative Controls 1ST Program and STS Bases to reflect the current edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) specified in 10 CFR 50.55a(b).

The NRC concluded that the revision was acceptable because the requirements of 10 CFR 50.55a adequately provide for 1ST. The NRC approved Revision 0 of TSTF-497, "Limit Inservice Testing Program SR 3.0.2 Application to Frequencies of 2 Years or Less;' by letter dated October 4, 2006 (ADAMS Accession No. ML062780321).

TSTF-497, Revision 0, revises the STS 1ST Program by clarifying that the application of the 25 percent 1ST interval extension allowed by SR 3.0.2 was for 1ST frequencies of 2 years or less. The NRC concluded that the revision was acceptable

-3 because it was an administrative change that clarified that the provisions of SR 3.0.2 (i.e., the 25 percent interval extension) are applicable to pumps and valves with 1ST intervals of 2 years or less. The changes were reviewed for consistency with the guidance in NUREG-1482, Revision 1, "Guidelines for Inservice Testing at Nuclear Power Plants" (ADAMS Accession No. M L050550290).

3.0 TECHNICAL EVALUATION The licensee requested this amendment to TS 5.5.8, "Inservice Testing Program," for PVNGS. TS 5.5.8 would, as the licensee explains in the application dated April 29, 2010, be revised to update references to the source of requirements for the Inservice Testing (1ST) of the American Society of Mechanical Engineers (ASME) Code Class 1, 2, and 3 pumps and valves and to address the applicability of Surveillance Requirement (SR) 3.0.2 to some non-standard pump and valve testing frequencies.

The proposed changes to the TS are consistent with NRC-approved Technical Specification Task Force (TSTF) Travelers TSTF-479-A, Revision 0, "Changes to Reflect Revision of 10 CFR 50.55a," ... as modified by TSTF-497-A, Revision 0, "Limit Inservice Testing Program SR 3.0.2 Application to Frequencies of 2 Years or Less, ... The licensee's submittal also proposes an editorial change to remove the reference to component supports in order to be consistent with the STS. Per the licensee's letter dated April 29, 2010, the component supports are part of the Inservice Inspection (lSI) Program. 3.1 TSTF-479, Revision 0, "Changes to Reflect Revision of 10 CFR 50.55a" As stated in Section 2.0 above, the regulations in 10 CFR 50.55a define the requirements for applying industry codes to each licensed nuclear powered facility.

Licensees are required by 10 CFR 50.55a(f)(4)(i) to initially prepare programs to perform 1ST of certain ASME Code,Section III, Class 1,2, and 3 pumps and valves during the initial 120-month interval.

For subsequent 120-month intervals, the regulations in 10 CFR 50.55a(f)(4)(ii) require licensees to update their 1ST program to the latest approved edition and addenda of the ASME Code for Operation and Maintenance of Nuclear Power Plants (OM Code) incorporated by reference into 10 CFR 50.55a(b).

Beginning in 1990, ASME published the OM Code, which provides the rules for 1ST of pumps and valves. Prior to 1990, these rules were part of Section XI of the ASME Code. The ASME Code,Section XI rules for inservice testing of pumps are no longer being updated. The TS change does not eliminate any tests and does not absolve the licensee of its responsibility to seek relief from Code test requirements when they are impractical.

The proposed change of the ASME Code reference from "ASME Section XI" to "ASME OM Code" eliminates the ASME Code inconsistency between the 1ST program and the TS, as required by 10 CFR 50.55a(f)(5)(ii);

therefore, the NRC staff concludes these proposed changes are

-acceptable.

This change is also consistent with the NRC's basis for approval of TSTF-479 in that the requirements of 10 CFR 50.55a adequately provide for 1ST. TSTF-497, Revision 0, "Limit In-service Testing Program SR 3.0.2 Application to Frequencies of 2 Years or Less" TSTF-479, Revision 0, "Changes to Reflect Revision of 10 CFR 50.55a," revised the 1ST Program located in Chapter 5 of the STS to reflect the latest approved version of the ASME Code. TSTF-479 also revised paragraph b of the STS Chapter 5 "Inservice Testing Program," by adding: The provisions of SR 3.0.2 are applicable to the above required Frequencies and other normal and accelerated Frequencies specified in the Inservice Testing Program for performing inservice test activities.

This requirement referred to the valves in the table above it, which only lists valves with a test frequency interval of 2 years or less. In order to enhance the 2 years or less test frequency requirement, TSTF-497 revised the sentence in paragraph b to state: The provisions of SR 3.0.2 are applicable to the above required Frequencies and to other normal and accelerated Frequencies specified as 2 years or less in the Inservice Testing Program for performing inservice testing activities.

Without this limitation, some components, such as safety and relief valves that may be tested at surveillance intervals significantly greater than 2 years, could have extensions applied which would be much greater than needed for operational flexibility.

This is an administrative change to clarify that SR 3.0.2 is applicable to pumps and valves with 1ST intervals of 2 years or less. The proposed changes are consistent with the basis of the NRC's approval of TSTF-479 and TSTF-497.

These changes are also consistent with the relevant portions of 10 CFR 50.55a. In addition, the staff agrees with the licensee's editorial change concerning removal of a reference to 'including applicable supports' in TS 5.5.8, as the change is per the NRC staff's position as reflected in NUREG-1432. STATE CONSULTATION In accordance with the Commission's regulations, the Arizona State official was notified of the proposed issuance of the amendment.

The State official had no comments. ENVIRONMENTAL CONSIDERATION The amendments change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendments involve 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 amendments involve no significant hazards consideration, and there has been no public comment on such finding

-5 published in the Federal Register on July 27, 2010 (75 FR 44023). Accordingly, the amendments meet 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 amendments.

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 amendments will not be inimical to the common defense and security or to the health and safety of the public. Principal Contributor:

Ravi Grover Date: January 19, 2011

____--R. -2 A copy of the related Safety Evaluation is also enclosed.

The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice. Sincerely, IRA! James R. Hall, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN 50-528, STN 50-529, and STN 50-530

Enclosures:

1. Amendment No. 184 to NPF-41 2. Amendment No. 184 to NPF-51 3. Amendment No. 184 to NPF-74 4. Safety Evaluation cc w/encls: Distribution via Listserv DISTRIBUTION:

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