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| | number = ML16257A544 | | | number = ML16257A544 |
| | issue date = 09/09/2016 | | | issue date = 09/09/2016 |
| | title = Palo Verde, Units 1, 2 & 3 - Response to NRC Instrumentation and Controls Staff Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Related to Degraded and Loss of Voltage Relay Modifica | | | title = Response to NRC Instrumentation and Controls Staff Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Related to Degraded and Loss of Voltage Relay Modifications |
| | author name = Lacal M L | | | author name = Lacal M L |
| | author affiliation = Arizona Public Service Co | | | author affiliation = Arizona Public Service Co |
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MONTHYEARML16123A0482016-05-0202 May 2016 NRR E-mail Capture - Palo Verde Nuclear Generating Station, Units 1, 2, and 3 - Acceptance Review of Degraded and Loss of Voltage Relay Modifications License Amendment Request Project stage: Acceptance Review ML16181A3342016-06-29029 June 2016 NRR E-mail Capture - Palo Verde Nuclear Generating Station, Units 1, 2, and 3 - Aphb Official RAIs for Degraded and Loss of Voltage Relay Modifications License Amendment Request Project stage: RAI ML16203A3812016-07-21021 July 2016 Response to NRC Staff Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Related to Degraded and Loss of Voltage Relay Modifications Project stage: Request ML16230A2312016-08-17017 August 2016 NRR E-mail Capture - Palo Verde Nuclear Generation Plant, Units 1, 2, and 3 - Official Eicb RAIs for LAR Associated with Degraded and Loss of Voltage Relay Modifications Project stage: RAI 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 Project stage: Other ML16257A5442016-09-0909 September 2016 Response to NRC Instrumentation and Controls Staff Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Related to Degraded and Loss of Voltage Relay Modifications Project stage: Request ML16251A2452016-09-0909 September 2016 Regulatory Audit Report for 8/26/16 Audit Performed at Westinghouse Facility in Rockville, MD, in Support Degraded and Loss of Voltage Relays License Amendment Request Project stage: Other ML16257A3302016-09-13013 September 2016 NRR E-mail Capture - Palo Verde Nuclear Generation Plant, Units 1, 2, and 3 - Official Eeeb RAIs for LAR Associated with Degraded and Loss of Voltage Relay Modifications Project stage: RAI ML16300A1562016-10-26026 October 2016 Response to NRC Electrical Engineering Branch Staff Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Related to Degraded and Loss of Voltage Relay ... Project stage: Request ML17090A1642017-04-27027 April 2017 Issuance of Amendment No. 201, 201, and 201 to Revise Technical Specifications Related to Degraded and Loss of Voltage Relay Modifications Project stage: Approval 2016-08-17
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Category:Letter
MONTHYEARML24295A0362024-10-23023 October 2024 Regulatory Audit Plan in Support of Relief Request No. 71; Resubmittal of Relief Request-30 IR 05000528/20244022024-10-22022 October 2024 Security Baseline Inspection Report 05000528/2024402 and 05000529/2024402 and 05000530/2024402 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 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 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 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 ML24032A1542024-04-0303 April 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) 2024-09-27
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARML24285A2562024-10-11011 October 2024 License Renewal - Alloy 600 Management Program Plan Response to Request for Additional Information 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 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 ML24066A0472024-03-0606 March 2024 Response to 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 and TS ML24012A2452024-01-12012 January 2024 Response to Request for Additional Information to Proposed Method to Manage Environmentally Assisted Fatigue for the Pressurizer Surge Line ML23299A3052023-10-26026 October 2023 Response to Request for Additional Information – Relief Request 70 – Proposed Alternatives for Pressurizer Lower Shell Temperature Nozzle ML23048A3202023-02-17017 February 2023 Response to NRC Requests for Additional Information Regarding 2022 Unit 1 Steam Generator Tube Inspections ML22090A0802022-03-31031 March 2022 Response to NRC Requests for Additional Information Regarding 2021 Unit 3 Steam Generator Tube Inspections ML22053A2122022-02-22022 February 2022 Response to Requests for Confirmation of Information for Exemption from Certain Requirements of 10 CFR 50.62(c)(1) Using Risk-Informed Process for Evaluations ML21173A3602021-06-22022 June 2021 Response to Request for Additional Information for Permanent Extension of Type a and Type C Leak Rate Test Frequencies ML21061A1562021-02-26026 February 2021 Spent Fuel Storage Installation, Response to Request for Additional Information Regarding Application for Order Approving Indirect Transfers of Control of Licenses ML21005A2712020-12-29029 December 2020 102-08208 PVNGS Communication Required by Confirmatory Order EA-20-054 ML20090L9442020-03-30030 March 2020 APS Response to Request for Additional Information- Relief Request 65 Unit 2, COVID-19, Request for Relief from Bottom Mounted Instrumentation Nozzles and a Pressurizer Nozzle to Surge ML20073R7532020-03-13013 March 2020 Independent Spent Fuel Storage Installation (ISFSI) - APS Response to Request for Additional Information for Changes to PVNGS Emergency Plan Staffing Requirements ML20054A2692020-02-19019 February 2020 Response to Request for Additional Information - Relief Request 64 - Unit 1 Impractical Examinations for the Third 10-Year Inservice Inspection Interval ML19340B2142019-12-0606 December 2019 Response to NRC Request for Additional Information Regarding 2019 Steam Generator Tube Inspections ML19331A3612019-11-26026 November 2019 Supplemental Response to NRC Request for Additional Information Regarding License Amendment and Exemption Requests Related to the Implementation of Framatome CE16HTP Fuel ML19277J4572019-10-0404 October 2019 Response to NRC Request for Additional Information Regarding License Amendment and Exemption Requests Related to the Implementation of Framatome CE16HTP Fuel ML19165A1402019-06-14014 June 2019 Response to Request for Additional Information - Relief Request 63 - Unit 3 Impractical Examinations for the Third 10-Year Inservice Inspection Interval ML19137A1182019-05-17017 May 2019 Response to NRC Staff Request for Additional Information from Reactor Assessment and Human Performance Branch Regarding License Amendment and Exemption Requests Related to the Implementation of Framatome High Thermal ML19074A1382019-03-14014 March 2019 Response to Request for Additional Information - Relief Request 62 - Third and Fourth 10-Year Inservice Inspection Intervals, Proposed Alternative - Pressurizer Heater Sleeve Repairs ML19031C9052019-01-31031 January 2019 Supplemental License Amendment Request to Revise Technical Specifications Regarding Response Time Testing of Pressure Transmitters and Request for Additional Information Response ML18296A4662018-10-18018 October 2018 Supplemental Information Regarding License Amendment Request and Exemption Request to Support the Implementation of Framatome High Thermal Performance Fuel ML18278A2952018-10-0505 October 2018 Response to Request for Additional Information for Risk-Informed Completion Times Supplemental Responses for Items 17.f and 21 ML18264A3182018-09-21021 September 2018 Response to Request for Additional Information for Risk-Informed Completion Times ML18194A9142018-07-13013 July 2018 Supplemental Response to Request for Additional Information 3.a for License Amendment Request to Adopt 10 CFR 50.69 Risk-Informed Categorization and Treatment of Structures, Systems, and Components ML18152B8742018-06-0101 June 2018 Response to Electrical Engineering Operating Reactor Branch (Eeob) Request for Additional Information for Risk-Informed Completion Times ML18138A4802018-05-18018 May 2018 Response to Request for Additional Information for Risk-Informed Completion Times ML18129A4482018-05-0909 May 2018 APS Response to Request for Additional Information for License Amendment Request to Adopt 10 CFR 50.69 Risk-Informed Categorization and Treatment of Structures, Systems, and Components ML17272B0332017-09-29029 September 2017 Response to Request for Additional Information Regarding Fourth 10-Year Interval Pump and Valve Inservice Testing Program Relief Requests ML17153A3732017-06-0202 June 2017 Response to NRC Staff Request for Additional Information Regarding License Amendment and Exemption Requests Related to the Implementation of Next Generation Fuel 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 ML17002A0012017-01-0202 January 2017 Response to NRC Requests for Additional Information (Rais) Regarding Emergency License Amendment Request (LAR) to Extend Diesel Generator 3B Completion Time ML17066A1842017-01-0202 January 2017 Response to NRC Requests for Additional Information (Rais) Regarding Emergency License Amendment Request (LAR) to Extend Diesel Generator 3B Completion Time ML16358A7152016-12-23023 December 2016 Response to Request for Additional Information Regarding Emergency License Amendment Request for a One-Time Extension of the Diesel Generator Completion Time ML16340A9882016-12-0101 December 2016 Addendum to Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML17167A2152016-11-23023 November 2016 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Incorporate Updated Criticality Safety Analysis - Revised ... 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 ML16300A1562016-10-26026 October 2016 Response to NRC Electrical Engineering Branch Staff Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Related to Degraded and Loss of Voltage Relay ... ML16286A2422016-10-0606 October 2016 Westinghouse Electric Company, WCAP-18030-NP Review, Suggested Response to Request for Additional Information 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 ML16257A5442016-09-0909 September 2016 Response to NRC Instrumentation and Controls Staff Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Related to Degraded and Loss of Voltage Relay Modifications ML16203A3812016-07-21021 July 2016 Response to NRC Staff Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Related to Degraded and Loss of Voltage Relay Modifications 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 ML16147A0922016-05-20020 May 2016 Response to Request for Additional Information Regarding Relief Request 54, Alternative to Flaw Removal ML16133A6212016-05-12012 May 2016 ISFSI - Response to Request for Additional Information Regarding Proposed Changes to Emergency Action Levels ML16102A4632016-04-11011 April 2016 Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-505 ML16029A5062016-01-29029 January 2016 Response to Request for Additional Information Regarding the Request to Change the Quality Assurance Program Description ML15273A4702015-09-30030 September 2015 IR 05000528/2015004, 05000529/2015004, and 05000530/2015004; 11/16/2015 - 11/20/2015; Palo Verde Nuclear Generating Station, Units 1, 2, and 3 - Notification of NRC Triennial Heat Sink Performance Inspection ML15258A8482015-09-15015 September 2015 Response to Request for Additional Information Regarding Exigent License Amendment Request to Amend Technical Specification Surveillance Requirement 3.1.5.3 2024-06-18
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10 CFR 50.90 A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway
- Diablo Canyon Palo Verde Wolf Creek MARIA L. LACAL Senior Vice President, Nuclear Regulatory & Oversight Palo Verde Nuclear Generating Station P.O. Box 52034 Phoenix, AZ 85072 Mail Station 7605
Tel 623.393.6491
102-07330-MLL/MDD September 9, 2016 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station (PVNGS) Units 1, 2, and 3 Docket Nos. STN 50-528, 50-529, and 50-530 Renewed Operating License Nos. NPF-41, NPF-51, NPF-74 Response to NRC Instrumentation and Controls Staff Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Related to Degraded and Loss of Voltage Relay Modifications By letter dated April 1, 2016 [Agencywide Documents Access and Management System (ADAMS) Accession No. ML16096A337], Arizona Public Service Company (APS) submitted a license amendment request (LAR) pursuant to the provisions of Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), for Palo Verde Nuclear Generating Station (PVNGS), Units 1, 2, and 3, requesting approval of proposed changes to the PVNGS Technical Specifications (TS). The proposed LAR would revise TS requirements related to the degraded and loss of voltage relays that are planned to be modified to be more aligned with designs generally implemented in the industry. Specifically, the licensing basis for degraded voltage protection will be changed from reliance on a TS initial condition that ensures adequate post-trip voltage support of accident mitigation equipment to crediting automatic actuation of the degraded and loss of voltage relays to ensure proper equipment performance.
By letter dated July 21, 2016 (ADAMS Accession No. ML16203A381), APS supplemented the LAR in response to U.S. Nuclear Regulatory Commission (NRC) Probabilistic Risk Assessment Operations and Human Factors Branch (APHB) staff request for additional information (RAI) (ADAMS Accession No. ML16181A334), dated June 29, 2016.
The Instrumentation and Controls Branch (EICB) of the NRC staff provided RAIs by NRC document, dated August 17, 2016 (ADAMS Accession No. ML16230A231). The Enclosure to this letter provides the APS response to the RAIs. The RAI responses do not affect the conclusions of the no significant hazards consideration determination [10 CFR 50.91(a)] provided in the original LAR.
No new commitments are being made in this submittal. Should you need further information regarding this response, please contact Michael D. Dilorenzo, Licensing Section Leader, at (623) 393-3495
.
102-07330-MLL/MDD ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Response to EICB RAIs Regarding LAR to Revise TS Related to Degraded and Loss of Voltage Relay Modifications Page 2
I declare under penalty of perjury that the foregoing is true and correct.
Executed on : September 9, 2016 (Date)
Sincerely, MLL/MDD/CJS/af
Enclosure:
Response to NRC Instrumentation and Controls Staff Requests for Additional Information Regarding License Amendment Request to Revise Technical Specifications Related to Degraded and Loss of Voltage Relay Modifications cc: K. M. Kennedy NRC Region IV Regional Administrator S. P. Lingam NRC NRR Project Manager for PVNGS M. M. Watford NRC NRR Project Manager C. A. Peabody NRC Senior Resident Inspector for PVNGS T. Morales Arizona Radiation Regulatory Agency (ARRA)
Enclosure
Response to NRC Instrumentation a nd Controls Staff Requests for Additional Information Regardi ng License Amendment Request to Revise Technical Specifications Related to Degraded and Loss of Voltage Relay Modifications
Enclosure Response to NRC EICB Staff RAIs Regarding LAR to Revise Technical Specifications Related to Degraded and Loss of Voltage Relays 1
Introduction By letter dated April 1, 2016 [Agencywide Documents Access and Management System (ADAMS) Accession No. ML16096A337], Arizona Public Service Company (APS) submitted a license amendment request (LAR) pursuant to the provisions of Section 50.90 of Title 10 of the
Code of Federal Regulations (10 CFR), for Palo Verde Nuclear Generating Station (PVNGS), Units 1, 2, and 3, requesting approval of proposed changes to the PVNGS Technical Specifications (TS). The proposed LAR would revise TS requirements related to the degraded and loss of voltage relays that are planned to be modified to be more aligned with designs generally implemented in the industry. Specifically, the licensing basis for degraded voltage protection will be changed from reliance on a TS initial condition that ensures adequate post-trip voltage support of accident mitigation equipment to crediting automatic actuation of the degraded and loss of voltage relays to ensure proper equipment performance.
By letter dated July 21, 2016 (ADAMS Accession No. ML16203A381), APS supplemented the LAR in response to U.S. Nuclear Regulatory Commission (NRC) Probabilistic Risk Assessment Operations and Human Factors Branch (APHB) staff request for additional information (RAI) (ADAMS Accession No. ML16181A334), dated June 29, 2016. The Instrumentation and Controls Branch (EICB) of the NRC staff provided RAIs by NRC document, dated August 17, 2016 (ADAMS Accession No. ML16230A231). This enclosure provides the APS response to the EICB RAIs. The NRC staff RAIs are provided first, followed by the APS response.
NRC Staff RAI 1:
In Attachment 4, Technical Description of Modification of the Degraded and Loss of Voltage Relays, of the LAR the licensee referred to Calculation 13-EC-PB-0202, 4160 V Degraded Voltage Relay (DVR) and Loss of Voltage Relay (LoVR) Setpoint & Calibration , Revision 5. Figures 5-2 and 5-3 in Attachment 4, documents the final results of the Allowable Values derived in this calculation. These values correspond to the proposed Allowable Values in TS SR 3.3.7.4. Please provide or make Calculation 13-EC-PB-0202 available to the NRC staff for audit.
The information in this calculation will be used to confirm the proposed Allowable Values in SR 3.3.7.4 conform to the criteria of Regulatory Guide 1.105, Rev. 3.
APS Response 1:
APS made the calculation available for review during the NRC Audit of August 26, 2016 (ADAMS Accession No. ML16230A604). APS staff provided an overview of the calculation and a discussion of the methodology used in the derivation of the TS Surveillance Requirement (SR) allowable values.
Enclosure Response to NRC EICB Staff RAIs Regarding LAR to Revise Technical Specifications Related to Degraded and Loss of Voltage Relays 2 NRC Staff RAI 2:
Sections 5.11.2 and 5.11.3 documents the Work Order History of ABB Type 27N Relays and Agastat ETR Timers. Please provide or make data used to calculate the uncertainty limits available to the NRC staff for audit.
APS Response 2:
APS made the requested information available for review during the NRC audit of August 26, 2016 (ADAMS Accession No. ML16230A604).
NRC Staff RAI 3:
In Calculation 13-EC-PB-0202, where the parameters have been obtained from the vendors, explain how data provided is used to ensure conformance to 95/95 confidence level specified in Regulatory Guide 1.105, Rev. 3.
APS Response 3:
The channel uncertainty values in Calculation 13-EC-PB-0202, 4160 V Degraded Voltage Relay (DVR) and Loss of Voltage Relay (LoVR) Setpoint & Calibration , Revision 5, are based on vendor provided accuracy and uncertainty information. These channel uncertainties were used to ensure that the limiting setpoints and corresponding TS allowable values adequately protect the analytical limits (ALs) determined by the electrical design calculations.
APS used the results of the instrument vendor's accuracy and uncertainty information, since APS does not have the instrument vendor's supporting data. APS does, however, have high confidence in the use of these values as protecting the ALs. This confidence is based on the following factors.
- 1. Historical data: The calculation contains tables of data from many work orders for the potential transformers [PTs, General Electric (GE)] and the under voltage relays [UVRs, ASEA Brown Boveri (ABB)]. There is limited work order data from another power plant for the secondary timer (Agastat timer). This data for the ABB relays and the Agastat timers were reviewed as part of NRC Staff audit on August, 26, 2016 (ADAMS Accession No. ML16230A604). The historical data for both the PTs and UVRs show that the instrument performance history supports the uncertainties provided in the vendor specifications. The historical data for the Agastat timers also support the vendor specifications, but with fewer data points.
- 2. Future monitoring: The PVNGS surveillance test program (procedure 73DP-9ZZ14, Surveillance Testing), of which the test procedure for this equipment is a part, has steps for tracking and monitoring out-of-tolerance (OoT) conditions. Procedure 73DP-9ZZ14 requires a Condition Report be written for an OoT condition to enter it into the Corrective Action Program. Notification of control room staff is also required. Procedure 82DP-0PP01, Out of Tolerance Program Controls, is specifically mentioned as guidance to be used in procedure 73DP-9ZZ14. The OoT program monitors for incipient failures. Monitoring will have two common results: (1) the tolerances are reasonable but the particular equipment is failing Enclosure Response to NRC EICB Staff RAIs Regarding LAR to Revise Technical Specifications Related to Degraded and Loss of Voltage Relays 3 and, therefore, needs to be repaired or replaced; or (2) the tolerance is determined to be unreasonable and the calculation and the related uncertainties need to be revised accordingly. The setpoints and related parameters are evaluated as part of the calculation revision process.
- 3. Margin for Agastat timer: In the application where the Agastat timer is used there is adequate margin between the setpoints and the limiting conditions to allow for some variation beyond the vendor data without encroaching on the ALs.