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MONTHYEARML0612301002006-05-0909 May 2006 RAI Regarding Risk Informed Inservice Inspection Program Request (TAC Nos. MC9627/28/29) Project stage: RAI ML0617104612006-06-10010 June 2006 Response to the NRC Request for Additional Information Regarding Risk-Informed Inservice Inspection Program Request Project stage: Request ML0624905362006-08-30030 August 2006 Response to NRC Request for Additional Information Regarding Risk-Informed Inservice Inspection Program Request Project stage: Response to RAI ML0627901822006-09-28028 September 2006 Information in Response to the NRC Phone Call on 07/21/06 Re Request for Relief to Section 50.55a(g) of Title 10 of the Code of Federal Regulations Project stage: Request ML0629302082006-11-0303 November 2006 Relief Request No. 32, Risk-Informed Inservice Inspection Program Project stage: Other 2006-06-10
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Category:Letter
MONTHYEARML24285A2562024-10-11011 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) 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 ML24241A2542024-08-28028 August 2024 Inservice Inspection Request for Information 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) 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 ML24157A3392024-06-0505 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 ML24144A2772024-05-23023 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 IR 05000528/20244012024-04-22022 April 2024 Security Baseline Inspection Report 05000528/2024401 and 05000529/2024401 and 05000530/2024401 (Cover Letter) ML24109A0712024-04-22022 April 2024 NRC Initial Operator Licensing Examination Approval 05000528/2024301, 05000529/2024301, and 05000530/2024301 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) ML24089A1892024-03-28028 March 2024 Present Levels of Financial Protection ML24068A2522024-03-0808 March 2024 License Amendment Request to Revise Technical Specifications 3.5.1 and 3.5.2 Using Risk-Informed Process for Evaluations 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 IR 05000528/20240122024-03-0404 March 2024 Age-Related Degradation Inspection Report 05000528/2024012, 05000529/2024012 and 05000530/2024012 IR 05000528/20230062024-02-28028 February 2024 Annual Assessment Letter for Palo Verde Nuclear Generating Station, Units 1, 2 and 3 Report 05000528/2023006 and 05000529/2023006 and 05000530/2023006 ML24053A3972024-02-22022 February 2024 License Renewal - Alloy 600 Management Program Plan ML24047A3632024-02-16016 February 2024 Independent Spent Fuel Storage Installation - Registration of Dry Spent Fuel Transportable Storage Canisters Identification Numbers AMZDFX177, AMZDFX178, AMZDFX179 Vertical Concrete Cask Identification No. AMZDNE179, AMZDNE178 2024-09-27
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David Mauldin Vice President Mail Station 7605 Palo Verde Nuclear Nuclear Engineering Tel: 623-393-5553 PO Box 52034 Generating Station and Support Fax: 623-393-6077 Phoenix, Arizona 85072-2034 102-05559-CDM/SAB/RJR August 30, 2006 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Reference:
APS letter 102-05398-CDM/SAB/RJR, "Proposed Alternative to PVNGS' ASME Section Xl Inservice Inspection Program for ASME Code Category B-F, B-J, C-F-I, and C-F-2 Piping (Relief Request 32)," dated January 16, 2006.
SUBJECT:
Palo Verde Nuclear Generating Station (PVNGS)
Units 1, 2 and 3 Docket Nos. STN 50-52815291530 Response to the NRC Request for Additional Information Regarding Risk-Informed Inservice Inspection Program Request (TAC NOS.
MC9627, MC9628, AND MC9629)
Dear Sirs:
In the letter referenced above, Arizona Public Service (APS) submitted proposed alternatives to section 50.55a(g) of Title 10 of the Code of FederalRegulations (10 CFR). Specifically, APS proposed using a risk-informed Inservice Inspection (ISI) program as an alternative to the current ISI program requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code of record for Palo Verde Nuclear Generating Station, Units 1, 2, and 3.
On August 2, 2006, the NRC requested a response to the following two questions.
NRC Question:
Please provide a paragraph or so describing a re-analysis or sensitivity study performed in response to NRC questions about Combustion Engineering Owners Group (CEOG)
Peer Review Facts and Observations (F&O) DA-02, 04, 06, and 08, which concluded that the revised PRA data analyses (completed after this application was submitted) had no impact on the relative consequence importance and/or risk-rankings of pipe segments.
NRC Document Control Desk Page 2 Second Response for Additional Information RR 32 APS Response:
The original analysis for the Risk-Informed (RI) Inservice Inspection (ISI) program was performed with Revision 13 of the PVNGS PRA model. This model had several peer review items that were still open, but considered to not substantially affect the results of the analysis. In a phone call with the NRC reviewer on July 26, 2006, the question was asked how PVNGS knew that some of the issues related to model data would not substantially affect the results.
Specifically, there were 4 CEOG Peer Review F&Os which dealt with the condition of data used within the PVNGS PRA model. They are Bayesian updating, grouping of components for each of the failure modes, common cause methodology and generic data sources. Palo Verde completed a subsequent update (Revision 14) to the PRA model in January 2006. These four F&Os were addressed and changes made to the PRA model. The changes included updating the generic data sources and revising the common cause methodology to the method described in NUREG CR-5485. As part of the next 10 year update of the ISI program, work was initiated to determine what the new segment consequence values would be. This work used the updated Revision 14 model. A comparison of the new consequence values and the current consequence values resulted in one consequence changing value from Low to Medium rank. A review of the final ranking for the welds was performed and resulted in no changes.
The results of the new model did not have any impact on ISI weld ranking.
NRC Question:
We would like to know what the intentions are with respect to crediting inspections of nickel-based dissimilar metal welds against the required number of inspections per the RI-ISI program. IfAPS does have such intentions, we would like to know the rationale for taking such credit and, to the degree that APS knows now, what inspection locations are expected to be dropped in order to take this credit.
APS Response:
We are keeping the dissimilar metal weld (DMW) exam scope separate from the RI-ISI exam scope. For example, if a PWSCC-susceptible weld is also selected for RI-ISI, it will receive the appropriate examination based on the EPRI topical report requirements as well as an exam for PWSCC per MRP-1 39.
On August 16, 2006, the NRC requested that APS commit to updating the Palo Verde RI-ISI program to incorporate any NRC-approved final EPRI/MRP guidance on thermal fatigue management.
NRC Document Control Desk Page 3 Second Response for Additional Information RR 32 PVNGS utilized EPRI Technical Report 1000701, Thermal Fatigue Management Guideline (MRP-24) for assessing thermal stratification, cycling, and striping (TASCS).
In addition, EPRI/MRP has revised the Thermal Fatigue Management Guidelines (MRP-146). These documents have not been reviewed and approved for use by the NRC. As a result, APS is making the following new commitment:
Upon NRC review and approval of MRP-24 and MRP-146, PVNGS will review and incorporate applicable NRC-approved final EPRI/MRP guidance on thermal fatigue management into the Palo Verde RI-ISI program for assessing TASCS.
If you have any questions about this change, please telephone Thomas N. Weber at (623) 393-5764.
Sincerely, CDM/SAB/RJPR-gt cc: B. S. Mallett NRC Region IV Regional Administrator M. B. Fields NRC NRR Project Manager G. G. Wamick NRC Senior Resident Inspector for PVNGS