Letter Sequence Response to RAI |
---|
TAC:MF3143, Predicting END-OF-CYCLE Mtc and Deleting Need for END-OF-CYCLE Mtc Verifiation (NPSD-911-A), Revise Mtc Surveillance for Startup Test Activity Reduction (STAR) Program (WCAP-16011) (Approved, Closed) |
|
MONTHYEARML13329A0382013-08-31031 August 2013 WCAP-17787-NP, Rev 0, Palo Verde Nuclear Generating Station STAR Program Implementation Report. Project stage: Request ML13365A2072013-09-25025 September 2013 Westinghouse Application for Withholding Proprietary Information from Public Disclosure for WCAP-17787-P Project stage: Request ML13329A7002013-11-20020 November 2013 Transmittal of Proprietary Documents for Startup Test Activity Reduction (STAR) Program License Amendment Request Project stage: Request ML13357A2492013-12-20020 December 2013 NRR E-mail Capture - Acceptance Review of Palo Verde Amendment Request Regarding Startup Test Activity Reduction (STAR) Program Project stage: Acceptance Review ML14027A7012014-01-16016 January 2014 Transmittal of Updated Affidavit from Westinghouse for Proprietary Document for Startup Test Activity Reduction (STAR) Program License Amendment Request (LAR) Project stage: Request ML14006A2242014-01-24024 January 2014 Request for Proprietary Withholding of Information - 9/25/13 Affidavit Executed by J. Gresham, Westinghouse WCAP-17787 Project stage: Other ML14042A1822014-02-27027 February 2014 Request for Withholding Information from Public Disclosure - 1/10/14 Affidavit Executed by J. Gresham, Westinghouse WCAP-16011-P-A, Revision 0 Project stage: Withholding Request Acceptance ML15005A0282014-12-19019 December 2014 Response to Request for Additional Information Regarding Application for Technical Specification Change Regarding Moderator Temperature Coefficient Surveillance for Startup Test Activity Reduction Program Project stage: Response to RAI ML15070A1242015-03-30030 March 2015 Issuance of Amendment Nos. 195, 195, and 195, Adopt TSTF-486, Revision 2, Revise Mtc Surveillance for Startup Test Activity Reduction (STAR) Program (WCAP-16011) and TSTF-406, Revision 2 Project stage: Approval 2014-01-16
[Table View] |
|
---|
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] |
Text
I 10 CFR 50.90 DWIGHT C. MIMS Senior Vice President, Nuclear Regulatory & Oversight Palo Verde Nuclear Generating Station P.O. Box 52034 Phoenix, AZ 85072 Mail Station 7605 102-06973-DCM/TNW Tel 623 393 5403 December 19, 2014 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station Units 1, 2, and 3 Docket Nos. STN 50-528/529/530 Response to Request for Additional Information Regarding Application for Technical Specification Change Regarding Moderator Temperature Coefficient (MTC) Surveillance for Startup Test Activity Reduction (STAR) Program Using the Consolidated Line Item Improvement Process (CLIIP)
By letter number 102-06784, dated November 20, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13329A037), as supplemented by letter number 102-06819, dated January 16, 2014 (ADAMS Accession No. ML14027A701), Arizona Public Service Company (APS) requested an amendment to the Palo Verde Nuclear Generating Station (PVNGS) technical specifications relating to the moderator temperature coefficient surveillance requirements for Startup Test Activity Reduction Program.
The U.S. Nuclear Regulatory Commission (NRC) staff provided a request for additional information (RAI) by e-mail dated December 1, 2014, to complete its review of the license amendment request. A draft RAI was originally transmitted on November 13, 2014, and a clarification call relating to the draft RAI was held on November 24, 2014, with participants from NRC and APS. The NRC staff requested the APS response to the final RAI within 30 days of December 1, 2014.
The enclosure to this letter provides the APS response to the NRC RAI. The RAI response remains consistent with the conclusion of the no significant hazards consideration determination [10 CFR 50.91(a), Notice for public comment] provided in the original LAR.
By copy of this letter, this LAR update is being forwarded to the Arizona Radiation Regulatory Agency (ARRA) pursuant to 10 CFR 50.91(b)(1), State consultation.
A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Ao Callaway
102-06973-DCM/TNW ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Response to Request for Additional Information Regarding Application for Technical Specification Change Regarding Moderator Temperature Coefficient (MTC)
Surveillance for Startup Test Activity Reduction (STAR) Program Using the Consolidated Line Item Improvement Process (CLIIP)
Page 2 No new commitments are being made to the NRC by this letter. Should you need further information regarding this submittal, please contact Thomas N. Weber, Licensing Department Leader, at (623) 393-5764.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on (Date)
Sincerely, DCM/TNW
Enclosure:
Response to Request for Additional Information Regarding Application for Technical Specification Change Regarding Moderator Temperature Coefficient (MTC) Surveillance for Startup Test Activity Reduction (STAR) Program Using the Consolidated Line Item Improvement Process (CLIIP) cc: M. L. Dapas NRC Region IV Regional Administrator B. K. Singal NRC NRR Project Manager for PVNGS M. M. Watford NRC NRR Project Manager C. A. Peabody NRC Senior Resident Inspector for PVNGS A. V. Godwin Arizona Radiation Regulatory Agency (ARRA)
T. Morales Arizona Radiation Regulatory Agency (ARRA)
Enclosure Response to Request for Additional Information Regarding Application for Technical Specification Change Regarding Moderator Temperature Coefficient (MTC) Surveillance for Startup Test Activity Reduction (STAR) Program Using the Consolidated Line Item Improvement Process (CLIIP)
Response to Request for Additional Information Regarding Application for Technical Specification Change Regarding Moderator Temperature Coefficient (MTC) Surveillance for Startup Test Activity Reduction (STAR)
Program Using the Consolidated Line Item Improvement Process (CLIIP)
Introduction By letter number 102-06784, dated November 20, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13329A037), as supplemented by letter number 102-06819, dated January 16, 2014 (ADAMS Accession No. ML14027A701),
Arizona Public Service Company (APS) requested an amendment to the Palo Verde Nuclear Generating Station (PVNGS) technical specifications relating to the moderator temperature coefficient surveillance requirements for Startup Test Activity Reduction Program.
The U.S. Nuclear Regulatory Commission (NRC) staff provided a request for additional information (RAI) by e-mail dated December 1, 2014, to complete its review of the license amendment request. A draft RAI was originally transmitted on November 13, 2014, and a clarification call relating to the draft RAI was held on November 24, 2014, with participants from NRC and APS. The NRC staff requested the APS response to the final RAI within 30 days of December 1, 2014.
The NRC request is stated first followed by the APS response.
NRC Request 1(a)
- 1. Arizona Public Service (APS) has proposed a modification to the PVNGS Technical Specifications (TS) that would allow the plant to perform a calculation in lieu of a measurement to complete Surveillance Requirement (SR) 3.1.4.2, which supports the Limiting Condition for Operation (LCO) for most negative Moderator Temperature Coefficient (MTC) established in LCO 3.1.4.
- a. How would APS ensure that PVNGS remains within LCO 3.1.4 if the plant deviates from normal operation, up to the TS limits, after performance of the two-thirds cycle surveillance required by SR 3.1.4.2?
APS Response APS performs a reload analysis (reload core safety evaluation) each cycle that includes a conservative calculation of the most negative MTC possible during the planned operating cycle. The analysis includes the biases, uncertainties and operating allowances required to ensure margin is maintained to the limits of LCO 3.1.4. The as-built core MTC will remain within the limits of LCO 3.1.4 provided the plant operates within the bounds established by the TS, the Core Operating Limits Report (COLR), and the cycle length evaluated in the reload analysis. If plans were made to operate in a condition beyond that which was evaluated in the reload analysis, then an additional evaluation would be performed to validate that the limits of LCO 3.1.4 would not be challenged by the planned change.
For example, the cycle specific reload analysis evaluates MTC beyond the planned cycle duration for operating margin. If plans were made to extend the expected life of the core beyond the burnup limit established in the reload analysis, an evaluation would be performed to validate that MTC remained within the bounds of LCO 3.1.4.
1
Response to Request for Additional Information Regarding Application for Technical Specification Change Regarding Moderator Temperature Coefficient (MTC) Surveillance for Startup Test Activity Reduction (STAR)
Program Using the Consolidated Line Item Improvement Process (CLIIP)
In addition,Section VIII, Deviation from Normal Operation, of topical report, CE NPSD-91 l-A, Analysis of Moderator Temperature Coefficients in Support of a Change in the Technical Specification End of Cycle Negative MTC Limit, dated September 15, 2000 (ADAMS Accession No. ML003752592), which is referenced in APS letter number 102-06784, dated November 20, 2013, uses PVNGS as an example for evaluations on the effects of off-normal plant operation on MTC. The topical report concludes that off normal plant operation has only minor effects on MTC.
NRC Request 1(b)
- b. If the answer to the previous question involves comparison of predicted values to the LCO limit, what criteria would APS use to determine whether or not a reanalysis of the MTC prediction would be required?
APS Response If plans were made to operate in a condition beyond that which was evaluated in the reload analysis, then an additional evaluation would be performed to validate that the limits of LCO 3.1.4 would not be challenged by the planned change. If the analysis performed for the off normal operation, including appropriate biases and uncertainties, predicted that MTC would exceed the LCO limit, then a revised operating plan would be needed to operate at less challenging conditions such that the predicted MTC will not challenge the LCO limits.
2