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MONTHYEARML16188A3332016-07-0101 July 2016 Description and Assessment of Proposed License Amendment - Technical Analysis Project stage: Other ML16190A2272016-07-13013 July 2016 Request for Withholding Information from Public Disclosure, 6/30/16 Affidavit Executed by J. Gresham, Westinghouse; Technical Analysis Next Generation Fuel Implementation Amendment Request Project stage: Withholding Request Acceptance ML16216A4612016-08-0303 August 2016 NRR E-mail Capture - Palo Verde Units 1, 2, and 3 - Acceptance Review of Next Generation Fuel License Amendment and Exemption Requests (CAC Nos. MF8076, MF8077, and MF8078; MF8079, MF8080, and MF8081) Project stage: Acceptance Review ML16217A1652016-08-0404 August 2016 NRR E-mail Capture - Palo Verde Units 1, 2, and 3 - Acceptance Review of Next Generation Fuel License Amendment and Exemption Requests (CAC Nos. MF8076, MF8077, and MF8078; MF8079, MF8080, and MF8081) Project stage: Acceptance Review ML16291A4482016-10-19019 October 2016 Audit Plan - 11/2-3/2016 Regulatory Audit at Westinghouse Facility in Rockville to Support Amendment and Exemption Requests Related to Implementation of Next Generation Fuel (CAC MF8076-MF8081) Project stage: Other ML17003A0862016-11-0303 November 2016 Enclosure 2 Slides Regulatory Audit Report for November 2-3, 2016 Project stage: Other ML17003A0762017-01-10010 January 2017 Regulatory Audit Report for the November 2-3, 2016, Audit at the Westinghouse Facility in Rockville, MD, for the License Amendment and Exemption Requests Associated with Next Generation Fuel (CAC Nos. MF8076-MF8081) Project stage: Other ML17054C4642017-02-27027 February 2017 Second Regulatory Audit Plan for March 8, 2017, Audit at Excel Facility in Rockville, Maryland, in Support of Next Generation Fuel License Amendment Request and Exemption Project stage: Other ML17076A3702017-03-16016 March 2017 Submittal of Proprietary Westinghouse Information Presented at the Regulatory Audit Held on March 8, 2017, at Excel Facility in Rockville, Maryland, Regarding Next Generation Fuel License Amendment Request and Exemption Project stage: Request ML17079A4462017-03-27027 March 2017 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML17082A4462017-03-28028 March 2017 PVNGS Units 1, 2, and 3 Transition to CE 16x16 Ngf - Draft RAIs Rev 3 Project stage: Draft RAI ML17107A0052017-04-14014 April 2017 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Ngf LAR and Exemption RAIs (CAC Nos. MF8076 to MF8081) Project stage: RAI 2016-08-04
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Category:Audit Plan
MONTHYEARML24295A0362024-10-23023 October 2024 Regulatory Audit Plan in Support of Relief Request No. 71; Resubmittal of Relief Request-30 ML19154A4692019-06-0404 June 2019 Second Regulatory Audit Plan for June 17-20, 2019, in Support of Framatome High Thermal Performance Fuel License Amendment Request and Exemption ML19011A1082019-01-15015 January 2019 First Regulatory Audit Plan for January 22-23, 2019, in Support of Framatome (EPID L-2018-LLA-0194 and EPID L-2018-LLE-0010) ML17054C4642017-02-27027 February 2017 Second Regulatory Audit Plan for March 8, 2017, Audit at Excel Facility in Rockville, Maryland, in Support of Next Generation Fuel License Amendment Request and Exemption ML16259A1892016-12-0505 December 2016 Nuclear Regulatory Commission Plan for the Audit of Mitigation Strategies Assessment Submittals Related to Order EA-12-049, Order to Modify Licenses With Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events ML16291A4482016-10-19019 October 2016 Audit Plan - 11/2-3/2016 Regulatory Audit at Westinghouse Facility in Rockville to Support Amendment and Exemption Requests Related to Implementation of Next Generation Fuel (CAC MF8076-MF8081) ML16230A6042016-08-18018 August 2016 Regulatory Audit Plan for 8/26/16 Audit at Westinghouse Facility in Rockville, MD, in Support Degraded and Loss of Voltage Relays License Amendment Request ML15177A1492015-07-0707 July 2015 Nuclear Regulatory Commission Plan for the Audit Arizona Public Service Company'S Flood Hazard Reevaluation Report Submittal Relating to the Near-Term Task Force Recommendation 2.1 - Flooding for Palo Verde Nuclear Generating Station, Units ML14083A6202014-03-26026 March 2014 Nuclear Regulatory Commission Audits of Licensee Responses to Reliable Spent Fuel Pool Instrumentation Order EA-12-051 ML14069A5162014-03-19019 March 2014 Plan for the Onsite Audit Regarding Implementation of Mitigating Strategies Related to Order EA-12-049 (Mitigating Strategies) 2024-10-23
[Table view] Category:Letter
MONTHYEARML24295A0362024-10-23023 October 2024 Regulatory Audit Plan in Support of Relief Request No. 71; Resubmittal of Relief Request-30 ML24296B2152024-10-22022 October 2024 Transmittal of Valve Relief Request (VRR) - 03: Alternative Request Allowing Removal of the Lower Acceptance Criteria Threshold from Solenoid-Operated Valves ML24296B2142024-10-22022 October 2024 Transmittal of Valve Relief Request (VRR) - 02: Alternative Request Allowing Normally Closed Valves with a Safety Function to Close to Be Exercise Tested Once Per Refueling Cycle IR 05000528/20244022024-10-22022 October 2024 Security Baseline Inspection Report 05000528/2024402 and 05000529/2024402 and 05000530/2024402 ML24296B2172024-10-18018 October 2024 Submittal of Unit 1 Core Operating Limits Report, Revision 34, Unit 2 Core Operating Limits Report, Revision 26, and Unit 3 Core Operating Limits Report, Revision 3 ML24292A2192024-10-18018 October 2024 Core Operating Limits Report Revision 34, 26 and 33 ML24292A0322024-10-17017 October 2024 Th Refueling Outage Steam Generator Tube Inspection Report ML24285A2562024-10-11011 October 2024 License Renewal - Alloy 600 Management Program Plan Response to Request for Additional Information IR 07200044/20244012024-10-0808 October 2024 Independent Spent Fuel Storage Installation Security Inspection Report 07200044/2024401 ML24269A1542024-09-27027 September 2024 Summary of Presubmittal Meeting with Arizona Public Service Company to Discuss Proposed Life-of-Plant Alternatives for a Pressurizer Thermowell Nozzle Repair at Palo Verde Nuclear Generating Station, Unit 1 ML24262A0972024-09-23023 September 2024 Notification of Post-Approval Site Inspection for License Renewal and Request for Information Inspection (05000529/2024011) ML24241A2542024-08-28028 August 2024 Inservice Inspection Request for Information ML24241A2782024-08-28028 August 2024 License Amendment Request to Revise the Technical Specifications 3.5.1 and 3.5.2 Safety Injection Tank Pressure Bands, and to Use GOTHIC Code ML24240A2682024-08-27027 August 2024 Transmittal of Technical Specification Bases Revision 79 IR 05000528/20240052024-08-22022 August 2024 Updated Inspection Plan for Palo Verde Nuclear Generating Station - Units 1, 2, and 3 (Report 05000528/2024005, 05000529/2024005, 05000530/2024005) 05000530/LER-2024-001-01, Inoperable Boron Dilution Alarm System(Bdas) with Technical Specification Violation2024-08-21021 August 2024 Inoperable Boron Dilution Alarm System(Bdas) with Technical Specification Violation ML24208A0612024-08-20020 August 2024 Issuance of Amendment Nos. 224, 224, and 224 Regarding Revision to Technical Specifications 3.5.1, 3.5.2 and 3.6.5 IR 05000528/20244042024-08-0808 August 2024 Cybersecurity Inspection Report 05000528/2024404, 05000529/2024404 and 05000530/2024404 ML24213A3232024-07-31031 July 2024 Transmittal of Relief Request (RR) No. 71: Re-Submittal of RR-30 ML24213A3292024-07-31031 July 2024 Transmittal of Relief Request (RR) No. 72: Re-Submittal of RR-39 IR 05000528/20240022024-07-29029 July 2024 Integrated Inspection Report 05000528/2024002 and 05000529/2024002 and 05000530/2024002 ML24173A3302024-07-24024 July 2024 Pressurizer Surge Line Inspection Program ML24159A4702024-07-17017 July 2024 Issuance of Amendment Nos. 223, 223, and 223 Revision to Technical Specifications 3.5.1 and 3.5.2 Using Risk Informed Process for Evaluations ML24198A0662024-07-16016 July 2024 Program Review - Simulator Testing Methodology ML24193A3442024-07-11011 July 2024 Fourth 10-Year Interval, Second Period Owner’S Activity Report Number 3R24 ML24129A0522024-07-0303 July 2024 Review of the Spring 2023 Steam Generator Tube Inspection Report IR 05000528/20240042024-06-25025 June 2024 Notification of Inspection (NRC Inspection Report 05000528/2024004, 05000529/2024004, 05000530/2024004) 05000530/LER-2024-002, Invalid Specified System Actuation of Train B Emergency Diesel Generator2024-06-25025 June 2024 Invalid Specified System Actuation of Train B Emergency Diesel Generator ML24177A3212024-06-25025 June 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Transportable Storage Canisters Identification Numbers AMZDFX180, AMZDFX181, AMZDFX182 Vertical Concrete Cask Identification Nu ML24177A3222024-06-25025 June 2024 Invalid Specified System Actuation of Train B Emergency Diesel Generator ML24170A9962024-06-18018 June 2024 Response to Second Request for Additional Information to Revise Technical Specifications (TS) 3.5.1, Safety Injection Tanks (Sits) – Operating, TS 3.5.2, Safety Injection Tanks (Sits) – Shutdown a IR 05000528/20243012024-06-17017 June 2024 NRC Examination Report 05000528/2024301; 05000529/2024301; 05000530/2024301 ML24129A2062024-06-14014 June 2024 Issuance of Amendment Nos. 222, 222, and 222 Revision to Technical Specifications to Adopt TSTF-266-A 05000530/LER-2024-001, Inoperable Boron Dilution Alarm System(Bdas) with Technical Specification Violation2024-06-0505 June 2024 Inoperable Boron Dilution Alarm System(Bdas) with Technical Specification Violation ML24159A0262024-06-0303 June 2024 Annual Report of Guarantee of Payment of Deferred Premium 05000529/LER-2024-001, Valid Specified System Actuations of Unit 2 Train B Emergency Diesel Generator and Train B Auxiliary Feedwater2024-05-23023 May 2024 Valid Specified System Actuations of Unit 2 Train B Emergency Diesel Generator and Train B Auxiliary Feedwater ML24135A2482024-05-14014 May 2024 Response to Second Request for Additional Information to Proposed Method to Manage Environmentally Assisted Fatigue for the Pressurizer Surge Line ML24164A2582024-05-0909 May 2024 10-PV-2024-04 Post-Exam Comments ML24129A1482024-05-0707 May 2024 And Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Casks with Applied Changes ML24128A2702024-05-0707 May 2024 Docket Nos. Stn 50-528/529/530 - Response to NRC Regulatory Issue Summary (RIS) 2024-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000528/20240012024-05-0202 May 2024 Independent Spent Fuel Storage Installation, Integrated Inspection Report 05000528/2024001, 05000529/2024001, 05000530/2024001, 07200044/2024001, and Exercise of Enforcement Discretion ML24119A0022024-04-26026 April 2024 2023 Annual Environmental Operating Report ML24116A2082024-04-24024 April 2024 Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report 2023 ML24109A0712024-04-22022 April 2024 NRC Initial Operator Licensing Examination Approval 05000528/2024301, 05000529/2024301, and 05000530/2024301 IR 05000528/20244012024-04-22022 April 2024 Security Baseline Inspection Report 05000528/2024401 and 05000529/2024401 and 05000530/2024401 (Cover Letter) ML24112A0012024-04-19019 April 2024 Core Operating Limits Report, Revision 32 ML24108A1982024-04-16016 April 2024 Independent Spent Fuel Storage Installation - Registration of Dry Spent Fuel Storage Casks with Applied Changes Authorized by an Amended Certificate of Compliance ML24103A2482024-04-12012 April 2024 Emergency Core Cooling System Performance Evaluation Models, 10 CFR 50.46(a)(3)(ii) Annual Report for 2023 ML24131A0972024-04-10010 April 2024 Annual Radiological Environmental Operating Report 2023 ML24096A2202024-04-0505 April 2024 Transmittal of Technical Specification Bases Revision 78 2024-09-27
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 27, 2017 Mr. Robert S. Bement Executive Vice President Chief Nuclear Officer Arizona Public Service Company P.O. Box 52034, Mail Station 7602 Phoenix, AZ 85072-2034
SUBJECT:
PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2, AND 3-SECOND REGULATORY AUDIT PLAN FOR MARCH 8, 2017, AUDIT AT EXCEL FACILITY IN ROCKVILLE, MARYLAND, IN SUPPORT OF NEXT GENERATION FUEL LICENSE AMENDMENT REQUEST AND EXEMPTION (CAC NOS. MF8076, MF8077, MF8078, MF8079, MF8080, AND MF8081)
Dear Mr. Bement:
By letter dated July 1, 2016 (Agencywide Documents Access and Management System Accession No. ML16188A336), Arizona Public Service Company (APS) requested changes to the Technical Specifications (TSs) to support the implementation of next generation fuel (NGF) for Palo Verde Nuclear Generating Station (PVNGS), Units 1, 2, and 3. The proposed changes would revise TS 4.2.1, "Reactor Core, Fuel Assemblies," and TS 5.6.5.b, "Core Operating Limits Report (COLA)," and allow the use of Combustion Engineering 16x16 NGF clad with the Optimized ZIRLO' material in PVNGS, Units 1, 2, and 3. To support the fuel transition, APS also requested an exemption from certain requirements of Title 1O of the Code of Federal Regulations (1 O CFR), Part 50, Section 10 CFR 50.46 and 10 CFR 50 Appendix K to allow the use of Optimized ZIRLO' as a cladding material in PVNGS, Units 1, 2, and 3.
The U.S. Nuclear Regulatory Commission (NRG) staff conducted a regulatory audit on November 2-3, 2016, to focus the staff's requests for additional information and enhance technical understanding of the submitted documentation. During this audit, it was determined that further time would be needed to examine materials related to the statistical methodology proposed for analyzing the fuel assembly mislead event and the use of SKBOR code in the boric acid precipitation analysis that were provided during the audit, but not originally available as part of the submittal. Additionally, the NRC staff requested justification for the proposed penalty to address the lack of treatment of thermal conductivity degradation in the FATES-3B code.
As a result, the NRG staff will conduct another audit at the EXCEL facility in Rockville, Maryland, on March 8, 2017. The Enclosure to this letter provides an audit plan in support of this audit.
R. Bement If you have any questions, please contact me at 301-415-1564 or via e-mail at Siva.Lingam@nrc.gov.
Sincerely,
.
~~*~
Siva P. Lingam, 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
Enclosure:
Regulatory Audit Plan cc w/encl: Distribution via Listserv
R. Bement
SUBJECT:
PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2, AND 3-SECOND REGULATORY AUDIT PLAN FOR MARCH 8, 2017, AUDIT AT EXCEL FACILITY IN ROCKVILLE, MARYLAND, IN SUPPORT OF NEXT GENERATION FUEL LICENSE AMENDMENT REQUEST AND EXEMPTION (CAC NOS. MF8076, MF8077, MF8078, MF8079, MF8080, AND MF8081) DATED FEBRUARY 27, 2017 DISTRIBUTION:
PUBLIC LPL4 R/F RidsACRS_MailCTR Resource RidsNrrDorlLpl4 Resource RidsNrrDssSnpb Resource RidsNrrDssSrxb Resource RidsNrrLAPBlechman Resource RidsNrrPMPaloVerde Resource RidsRgn4MailCenter Resource DWoodyatt, NRR/DSS/SRXB DBeacon, NRR/DSS/SNPB JLehning, NRR/DSS/SNPB JKaizer, NRR/DSS/SNPB ADAMS Access1on No.: ML17054C464 *b1y memoran d um OFFICE NRR/DORL/LPL4/PM NRR/DORL/LPL4/LA* NRR/DSS/SNPB/BC*
NAME Slingam PBlechman RLukes DATE 02/23/17 02/23/17 02/21/17 OFFICE N RR/DORL/LPL4/BC NRR/DORL/LPL4/PM NAME RPascarelli Slingam DATE 02/2717 02/27/17 OFFICIAL RECORD COPY
REGULATORY AUDIT PLAN FOR MARCH 8, 2017, AUDIT AT EXCEL FACILITY IN ROCKVILLE. MARYLAND, TO SUPPORT REVIEW OF NEXT GENERATION FUEL LICENSE AMENDMENT REQUEST AND EXEMPTION ARIZONA PUBLIC SERVICE COMPANY PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2, AND 3 DOCKET NOS. 50-528, 50-529, AND 50-530
1.0 BACKGROUND
The U.S. Nuclear Regulatory Commission (NRC) staff is currently engaged in a review of a license amendment request for the Palo Verde Nuclear Generating Station (PVNGS), Units 1, 2, and 3. By letter dated July 1, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16188A336), Arizona Public Service Company (APS, the licensee) requested changes to the Technical Specifications (TSs) to support the implementation of next generation fuel (NGF) for PVNGS, Units 1, 2, and 3. The proposed changes would revise TS 4.2.1, "Reactor Core, Fuel Assemblies," and TS 5.6.5.b, "Core Operating Limits Report (COLR), and will allow the use of Combustion Engineering (CE) 16x16 NGF clad with the Optimized ZIRLO' material in PVNGS, Units 1, 2, and 3. To support the fuel transition, APS also requested an exemption from certain requirements of Title 1O of the Code of Federal Regulations (1 O CFR) Section 50.46, "Acceptance criteria for emergency core cooling systems
[ECCS] for light-water nuclear power reactors, and 10 CFR Part 50, Appendix K, "ECCS Evaluation Models," to allow the use of Optimized ZIRLO' as a cladding material in PVNGS, Units 1, 2, and 3.
The NRC staff conducted a regulatory audit on November 2-3, 2016, to focus the staff's requests for additional information (RAls) and enhance technical understanding of the submitted documentation. During this audit, it was determined that further time would be needed to examine materials related to the statistical methodology proposed for analyzing the fuel assembly misload event and the use of SKBOR code in the boric acid precipitation analysis that were provided during the audit, but not originally available as part of the submittal. Additionally, the NRC staff requested justification for the proposed penalty to address the lack of treatment of thermal conductivity degradation (TCD) in the FATES-3B code.
Therefore, the NRC staff has proposed to conduct a second regulatory audit at this point in the review process in an effort to resolve or focus the questions that arose from further consideration of the outstanding issues, and to observe the justification for the proposed TCD penalty. This audit will help the NRC staff better understand the supporting documentation and analysis results through interaction with APS's technical experts and will help to focus the staff's RAls on those questions where docketed information is needed to complete the review. The proposed audit will be held in accordance with the Office of Nuclear Reactor Regulation (NRR)
Office Instruction LIC-111, "Regulatory Audits, dated December 16, 2008 (ADAMS Accession No. ML082900195).
Enclosure
2.0 REGULATORY AUDIT SCOPE The NRG staff would like APS to make available appropriate staff with detailed knowledge of the PVNGS licensing basis and the related topical reports, the statistical methods used in the fuel assembly mislead methodology, and SKBOR boric acid precipitation analysis method.
Additionally, APS staff should be prepared to present and answer questions about the justification for the proposed TCD penalty.
Discussion at the audit is expected to pertain to a limited scope of the submittal, specifically including the following subjects and related points of discussion:
- Boric acid precipitation analysis methodology (SKBOR).
- Statistical treatment of the inadvertent fuel assembly mislead event.
- Justification for the proposed penalty to FATES-3B to account for the lack of TCD treatment.
3.0 TEAM AND REVIEW ASSIGNMENTS Area of Review As$igned Auditor Branch Chief Robert Lukes (NRG)
Technical Reviewer Daniel Beacon (NRG)
Technical Reviewer John Lehning (NRG)
Project Manager Siva P. Lingam (NRG) 4.0 LOGISTICS The audit will be conducted at the EXCEL facility in Rockville, Maryland, on March 8, 2017.
Entrance and exit briefings will be held at the beginning and end of this audit, respectively.
The licensee is requested to provide a conference room with a white board for discussions, as well as printed copies of the following reports:
- Detailed description of the SKBOR boric acid precipitation methodology and relevant calculation notes.
- Detailed description of the statistical mislead methodology and relevant calculation notes.
- Justification for the adequacy of the proposed TCD penalty on FATES-38 and relevant calculation notes.
APS should also provide any other documentation that may aid discussion on the specific topics of interest.
The audit will start at 8:00 a.m. on Wednesday, March 8, 2017, and conclude on the same day at approximately at 3:30 p.m. (eastern standard time).
5.0 DELIVERABLES At the conclusion of the audit, the NRC staff will provide a summary of audit results for each of the topics defined in the audit scope. The NRC Regulatory Audit Report will be issued within 90 days of the completion of the audit.