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MONTHYEARML15336A0832015-09-30030 September 2015 WCAP-18030-NP, Revision 0, Criticality Safety Analysis for Palo Verde Nuclear Generating Station, Units 1, 2, and 3. Project stage: Request ML15336A0872015-11-25025 November 2015 License Amendment Request to Revise Technical Specifications to Incorporate Updated Criticality Safety Analysis Project stage: Request ML16012A0032016-01-11011 January 2016 Draft Unacceptable with Opportunity to Supplement Requested Licensing Action Email, Revise Technical Specifications to Incorporate Updated Criticality Safety Analysis Project stage: Draft Other ML16014A0012016-01-15015 January 2016 Supplemental Information Needed for Acceptance of Requested Licensing Action, Revise Technical Specifications to Incorporate Updated Criticality Safety Analysis Project stage: Acceptance Review ML16043A3612016-01-29029 January 2016 Supplemental Information Regarding License Amendment Request to Revise Technical Specifications to Incorporate Updated Criticality Safety Analysis Project stage: Supplement ML16043A3892016-02-18018 February 2016 Acceptance of Requested Licensing Action License Amendment Request to Revise Technical Specifications to Incorporate Updated Criticality Safety Analysis Project stage: Acceptance Review ML16155A0752016-06-0202 June 2016 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Aphb and Esgb RAIs for Spent Fuel Pool Criticality Safety Analysis LAR Project stage: RAI ML16182A5192016-06-30030 June 2016 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Incorporate Updated Critical Safety Analysis Project stage: Response to RAI ML16197A0062016-07-14014 July 2016 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Official RAIs from Snpb for LAR That Requested Revision to TSs to Incorporate Updated Criticality Safety Analysis Project stage: RAI ML16286A2402016-10-0606 October 2016 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Incorporate Updated Criticality Safety Analysis Project stage: Response to RAI ML16321A0022016-11-0909 November 2016 Response to RAI, Amendment Request to Revise Technical Specifications to Incorporate Updated Criticality Safety Analysis - Revised Technical Specifications and Bases and WCAP-18030, Revision 1 Project stage: Response to RAI ML17062B0362017-03-0303 March 2017 Supplemental Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Incorporate Updated Criticality Safety Analysis Project stage: Supplement ML17144A3762017-05-24024 May 2017 Supplemental Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Incorporate Updated Criticality Safety Analysis Project stage: Supplement ML17145A2732017-06-15015 June 2017 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance 2016-11-09
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Category:Acceptance Review Letter
MONTHYEARML18312A3322018-11-13013 November 2018 Acceptance Review for License Amendment and Exemption Requests Regarding the Implementation of Framatome High Thermal Performance Fuel ML16043A3892016-02-18018 February 2016 Acceptance of Requested Licensing Action License Amendment Request to Revise Technical Specifications to Incorporate Updated Criticality Safety Analysis ML16012A0032016-01-11011 January 2016 Draft Unacceptable with Opportunity to Supplement Requested Licensing Action Email, Revise Technical Specifications to Incorporate Updated Criticality Safety Analysis ML15303A0982015-11-0909 November 2015 Acceptance Review Letter, License Amendment Request, Adopt Technical Specification Task Force (TSTF)-505, Revision 1, Provide Risk-Informed Extended Completion Times-RITSTF Initiative 4b ML15113A6362015-04-22022 April 2015 Acceptance of Relief Request 53 ML13358A0492013-12-24024 December 2013 Acceptance Review Following Supplement, License Amendment Request to Revise TS 3.3.3, Control Element Assembly Calculators and TS 3.3.6, Engineered Safety Features Actuation System (ESFAS) Logic and Manual Trip ML13247A5512013-09-0404 September 2013 Acceptance Review E-mail, Review of Pressurized-Water Reactor Internal Aging Management Program Plan ML13032A5372013-02-0101 February 2013 Acceptance Review Email, License Amendment Request to Adopt TSTF-500, Revision 2, DC Electrical Rewrite - Update to TSTF-360 ML13025A2482013-01-25025 January 2013 Acceptance Review Email, License Amendment Request to Adopt TSTF-490, Revision 0, Deletion of E-Bar Definition and Revision to RCS Specific Activity Technical Specifications ML12243A4662012-08-30030 August 2012 Acceptance Review Results Email - for Relief Request Related to Phased Array Ultrasonic Examination Techniques ML1213103802012-05-10010 May 2012 Acceptance Review Email, License Amendment Request to Revise Technical Specifications to Eliminate Use of the Term Core Alteration Consistent w/TSTF-471 and NUREG-1432, Revision 3 ML1202703432012-01-27027 January 2012 Acceptance Review Email, Request for Relief to Use Subsequent Edition/Addenda of ASME Code Section XI, for the 3rd 10-Year Inservice Inspection Interval ML1201800792012-01-18018 January 2012 Acceptance Review Email, Request for Approval of Proposed Changes to Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedules ML1135003762011-12-16016 December 2011 Acceptance Review E-mail, License Amendment Request to Modify Technical Specifications to Implement Administrative Changes Including Corrective Actions from U2 Event in LER 50-529/2011-001 ML1113101402011-05-11011 May 2011 Acceptance Review Email, Adoption of Technical Specification Task Force (TSTF)-425, Rev. 3, Relocate Surveillance Frequencies to Licensee Control - Risk Informed Technical Specification Task Force (RITSTF) Initiative 5b ML1027102522010-09-28028 September 2010 Acceptance Review E-mail, License Amendment Request to Revise Updated Final Safety Analysis Report, Feedwater Line Break Analysis with LOOP and Single Failure Analysis ML1022405612010-08-12012 August 2010 Acceptance Review Email LAR for Cyber Security Plan ML1018102662010-06-30030 June 2010 Acceptance Review Email, License Amendment Request, Adoption of TSTF-491, Revision 2, Removal of Main Steam and Main Feedwater Valve Isolation Times from Technical Specifications ML1014404232010-05-24024 May 2010 Acceptance Review Email LAR to Revise TS 5.5.8, Inservice Testing Program (TAC Nos., ME3914/5/6) ML0830802872008-11-0303 November 2008 Acceptance Review of Application to Modify Technical Specification 5.5.16, Containment Leakage Rate Testing Program, Risk-Informed ML0828407002008-10-0909 October 2008 Acceptance Review Email, License Amendment Request to Revise TS 5.6.5, Core Operating Limits Report (COLR) ML0900801172008-09-0505 September 2008 Acceptance Review Email, License Amendment Request, Revise Technical Specification 4.2.2, Control Element Assemblies 2018-11-13
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 18, 2016 Mr. Randall K. Edington Executive Vice President Nuclear/
Chief Nuclear Officer Mail Station 7602 Arizona Public Service Company P.O. Box 52034 Phoenix, AZ 85072-2034
SUBJECT:
PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2, AND 3-ACCEPTANCE OF REQUESTED LICENSING ACTION RE: LICENSE AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATIONS TO INCORPORATE UPDATED CRITICALITY SAFETY ANALYSIS (CAC NOS.
MF7138, MF7139, AND MF7140)
Dear Mr. Edington:
By letter dated November 25, 2015, as supplemented by letter dated January 29, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML15336A251 and ML16043A361), Arizona Public Service Company (APS, the licensee) submitted a license amendment request for Palo Verde Nuclear Generating Station, Units 1, 2, and 3. The proposed amendment would modify technical specification (TS) requirements to incorporate the results of an updated criticality safety analysis for both new and spent fuel storage. The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this amendment request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.
Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), an amendment to the license (including the technical specifications) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required.
This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations.
The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the NRC staff to complete its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staff's ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. You will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence.
R. Edington If you have any questions, please contact me at (301) 415-1233 or via e-mail at Margaret.Watford@nrc.gov.
Sincerely, 11
(}7l0cLt~ij Margaret M. Watfora, Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN 50-528, STN 50-529, and STN 50-530 cc: Distribution via Listserv
ML16043A389 *via email OFFICE NRR/DORL/LPL4-1 /PM NRR/DORL/LPL4-1 /LA NRR/DSS/SNPB/BC NRR/DORL/LPL4-1 /BC NRR/DORL/LPL4-1 /PM NAME MWatford JBurkhardt JDean* RPascarelli MWatford DATE 2/17/16 2/16/16 2/11/16 2/18/16 2/18/16