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| | number = ML16064A497 | | | number = ML16064A497 |
| | issue date = 03/07/2016 | | | issue date = 03/07/2016 |
| | title = Palo Verde, Units 1, 2, and 3 - Request for Additional Information, Adopt Technical Specification Task Force (TSTF)-505, Revision 1, Provide Risk-Informed Extended Completion Times-RITSTF Initiative 4b (CAC MF6576, MF6577, and MF6578) | | | title = Request for Additional Information, Adopt Technical Specification Task Force (TSTF)-505, Revision 1, Provide Risk-Informed Extended Completion Times-RITSTF Initiative 4b |
| | author name = Lingam S P | | | author name = Lingam S |
| | author affiliation = NRC/NRR/DORL/LPLIV-1 | | | author affiliation = NRC/NRR/DORL/LPLIV-1 |
| | addressee name = Edington R K | | | addressee name = Edington R |
| | addressee affiliation = Arizona Public Service Co | | | addressee affiliation = Arizona Public Service Co |
| | docket = 05000528, 05000529, 05000530 | | | docket = 05000528, 05000529, 05000530 |
| | license number = NPF-041, NPF-051, NPF-074 | | | license number = NPF-041, NPF-051, NPF-074 |
| | contact person = Singal B K | | | contact person = Singal B |
| | case reference number = CAC MF6576, CAC MF6577, CAC MF6578 | | | case reference number = CAC MF6576, CAC MF6577, CAC MF6578 |
| | document type = Letter, Request for Additional Information (RAI) | | | document type = Letter, Request for Additional Information (RAI) |
| | page count = 6 | | | page count = 6 |
| | project = CAC:MF6576, CAC:MF6576, CAC:MF6577, CAC:MF6578 | | | project = CAC:MF6576, CAC:MF6577, CAC:MF6578 |
| | stage = Other | | | stage = RAI |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:Mr. Randall K. Edington UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 .M:lrdi 7' 2016 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 -REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATIONS TO IMPLEMENT TSTF-505 (CAC NOS. MF6576, MF6577, AND. MF6578) Dear Mr. Edington: By letter dated July 31, 2015 (Agencywide Documents Access and Management System Accession No. ML 15218A300), Arizona Public Service Company (the licensee) submitted a license amendment request (LAR) regarding Palo Verde Nuclear Generating Station, Units 1, 2, and 3. The proposed amendment would revise Technical Specifications (TS) to Implement TS Task Force (TSTF)-505, Revision 1, "Provide Risk-Informed Extended Completion Times -RITSTF [Risk-informed TSTF] Initiative 4b." The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the licensee's LAR and has determined that additional information is needed to support its review. Enclos!=ld is the NRC staff's request for additional information (RAI). The RAI was discussed with your staff in a clarification call on March 4, 2016, and it was agreed that your response would be provided by April 11, 2016. | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 |
| R. Edington -2 -If you have any questions, please contact me at (301) 415-1564 or via e-mail at Siva.Lingam@nrc.gov. , Docket Nos. STN 50-528, STN 50-529, and STN 50-530 Enclosure: Request for Additional Information cc w/encl: Distribution via Listserv Sincerely, Siva P. Lingam, Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST TO ADOPT TSTF-505 ARIZONA PUBLIC SERVICE COMPANY PALO.VERDE NUCLEAR GENERATING STATION, UNITS 1. 2. AND 3 DOCKET NOS. STN 50-538, STN 50-529, AND STN 50-530 By letter dated July 31, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15218A300), Arizona Public Service Company submitted a license amendment request (LAR) regarding Palo Verde Nuclear Generating Station, Units 1, 2, and 3. The proposed amendment would revise Technical Specifications (TSs) to Implement TS Task Force (TSTF)-505, Revision 1, "Provide Risk-Informed Extended Completion Times -RITSTF [Risk-informed TSTF] Initiative 4b." Based on the U.S. Nuclear Regulatory Commission (NRC) staff's review of the licensee's LAR, the staff has determined the following additional information is necessary to support completion of its technical reviE;!w: ' EICB-RAl-1 The NRC .staff seeks clarification on how probabilistic risk assessment (PRA) Functionality will be determined in the risk-informed completion time (RICT) program as implemented. The LAR does not describe conditions where Actuation Logic channels are INOPERABLE but PRA Functional. (a) Please provide several example conditions that would allow one or more Actuation Logic channels (see TS 3.3.6, "Engineered Safety Features Actuation System (ESFAS) Logic and Manual Trip," Action E insert for TS page 3.3.6-2) to be considered both INOPERABLE and PRA Functional. (b) For each example in part (a), please include ari evaluation against the criteria in Nuclear Energy Institute (NEI) 06-09, "Risk-Informed Technical Specifications Initiative 4b, Risk-Managed Technical Specifications (RMTS)," November 2006 (ADAMS Accession No. ML 12286A322), Section 2.3.1, "Configuration Risk Management Process & Application of Technical Specifications," Item Nos. 10 and 11. (c) The NRC staff understands that by meeting the criteria in Items Nos. 10 and 11 in NEI 06-09, Section 2.3.1, all design basis events would be protected against. Please describe any associated design basis events that are NOT protected against in each example condition in part (a). Enclosure | | .M:lrdi 7' 2016 Mr. Randall K. Edington Executive Vice President Nuclear/ |
| -2 -EICB-RAl-2 Enclosure 1, "List of Revised Required Actions to Corresponding PRA Functions," to the model application for licensee adoption of TSTF-505 dated January 31, 2012 (ADAMS Accession No. ML 12032A065) states: This enclosure [Enclosure 1] should provide a description of PRA functionality for each associated specified safety function that corresponds to each proposed Required Action that is applicable when all trains of equipment are inoperable as discussed in Section 2.3.1.10 of NEI 06-09. For example, the number and identity of instrumentation and control channels (or functions) required to be PRA functional is highly dependent on the specific plant and associated equipment design. Enclosure 1 guidance is included as part of the model application because the NRC staff seeks clarity on how PRA Functional will be used during full power operation following "loss of a specified safety function or inoperability of all required trains or divisions of a system." In the LAR, Attachment 5, "List of Revised Required Actions to Corresponding Probabilistic Risk Assessment Functions," the "PRA Success Criteria" is indicated as being the same as the "Design Success Criteria" (i.e., the same minimum number of channels actuate for some instrumentation and controls (l&C) functions). (Regarding: TS 3.3.4, "Reactor Protective System (RPS) Logic and Trip Initiation," and TS 3.3.6.) * (a) Please confirm that the PRA Success Criteria ensures all associated design basis events are protected against in the condition where two Actuation Logic channels are INOPERABLE and PRA Functional or justify how adequate protection is maintained, if not. (b) Attachment 5 of the LAR identifies some l&C structures, systems, and components that are partially modeled (or not modeled) in the PRA. Item No. 11 in NEI 06-09, Section 2.3.1 includes criteria for determining PRA Functionality of components, and these criteria were developed based on the assumption that the function would be modeled in the PRA. (i) Please describe how PRA Functionality of these partial models (or un-modeled items) will be determined (i.e., how the criteria of Item No. 11 will be applied). (ii) Please describe how PRA Functionality of bounding evaluations will be determined (i.e., how the criteria of Item No. 11 will be applied).
| | Chief Nuclear Officer Mail Station 7602 Arizona Public Service Company P.O. Box 52034 . |
| -3 -EICB-RAl-3 NEI 06-09, Revision 0-A, states that a RICT cannot be used in a condition where there is a total loss of TS specified safety function; however, it does not describe how to determine when a total loss of safety function has occurred. (a) For two Actuation Logic channels inoperable, please describe the process of how it will be determined if there is a total loss of TS specified safety function. '
| | Phoenix, AZ 85072-2034 |
| R. Edington -2 -If you have any questions, please contact me at (301) 415-1564 or via e-mail at Siva.Ungam@nrc.gov. Sincerely, /RA/ Siva P. Lingam, 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 Enclosure: Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION: PUBLIC LPL4-1 r/f RidsNrrDorllpl4-1 Resource RidsNrrLAJBurkhardt Resource RidsNrrPMPaloVerde Resource RidsRgn4MailCenter Resource NCarte, NRR/DE/EICB RBeacom, NRR/DE/EICB RidsACRS MailCTR Resource RidsNrrDeEicb Resource ADAMS Accession No. ML 16064A497 OFFICE NRR/DORL/LPL4-1 /PM NRR/DORL/LPL4-1/LA NAME SLingam JBurkhardt DATE 03/07/16 03/07/16 NRR/DE/EICB/BC NRR/DORL/LPL4-1/BC MWaters RPascarelli (BSingal for) 03/07/16 03/07/16 OFFICIAL RECORD COPY NRR/DORL/LPL4-1 /PM SLingam 03/07/16
| | |
| }} | | ==SUBJECT:== |
| | PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2, AND 3 - |
| | REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATIONS TO IMPLEMENT TSTF-505 (CAC NOS. MF6576, MF6577, AND. MF6578) |
| | |
| | ==Dear Mr. Edington:== |
| | |
| | By letter dated July 31, 2015 (Agencywide Documents Access and Management System Accession No. ML15218A300), Arizona Public Service Company (the licensee) submitted a license amendment request (LAR) regarding Palo Verde Nuclear Generating Station, Units 1, 2, and 3. The proposed amendment would revise Technical Specifications (TS) to Implement TS Task Force (TSTF)-505, Revision 1, "Provide Risk-Informed Extended Completion Times - RITSTF [Risk-informed TSTF] Initiative 4b." |
| | The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the licensee's LAR and has determined that additional information is needed to support its review. Enclos!=ld is the NRC staff's request for additional information (RAI). The RAI was discussed with your staff in a clarification call on March 4, 2016, and it was agreed that your response would be provided by April 11, 2016. |
| | |
| | R. Edington If you have any questions, please contact me at (301) 415-1564 or via e-mail at Siva.Lingam@nrc.gov. , |
| | Sincerely, |
| | ~ ~* D'\.J~ |
| | Siva P. Lingam, 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 |
| | |
| | ==Enclosure:== |
| | |
| | Request for Additional Information cc w/encl: Distribution via Listserv |
| | |
| | REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST TO ADOPT TSTF-505 ARIZONA PUBLIC SERVICE COMPANY PALO.VERDE NUCLEAR GENERATING STATION, UNITS 1. 2. AND 3 DOCKET NOS. STN 50-538, STN 50-529, AND STN 50-530 By letter dated July 31, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15218A300), Arizona Public Service Company submitted a license amendment request (LAR) regarding Palo Verde Nuclear Generating Station, Units 1, 2, and 3. |
| | The proposed amendment would revise Technical Specifications (TSs) to Implement TS Task Force (TSTF)-505, Revision 1, "Provide Risk-Informed Extended Completion Times - RITSTF |
| | [Risk-informed TSTF] Initiative 4b." |
| | Based on the U.S. Nuclear Regulatory Commission (NRC) staff's review of the licensee's LAR, the staff has determined the following additional information is necessary to support completion of its technical reviE;!w: ' |
| | EICB-RAl-1 The NRC .staff seeks clarification on how probabilistic risk assessment (PRA) Functionality will be determined in the risk-informed completion time (RICT) program as implemented. The LAR does not describe conditions where Actuation Logic channels are INOPERABLE but PRA Functional. |
| | (a) Please provide several example conditions that would allow one or more Actuation Logic channels (see TS 3.3.6, "Engineered Safety Features Actuation System (ESFAS) Logic and Manual Trip," Action E insert for TS page 3.3.6-2) to be considered both INOPERABLE and PRA Functional. |
| | (b) For each example in part (a), please include ari evaluation against the criteria in Nuclear Energy Institute (NEI) 06-09, "Risk-Informed Technical Specifications Initiative 4b, Risk-Managed Technical Specifications (RMTS)," November 2006 (ADAMS Accession No. ML12286A322), Section 2.3.1, "Configuration Risk Management Process & Application of Technical Specifications," Item Nos. 10 and 11. |
| | (c) The NRC staff understands that by meeting the criteria in Items Nos. 10 and 11 in NEI 06-09, Section 2.3.1, all design basis events would be protected against. |
| | Please describe any associated design basis events that are NOT protected against in each example condition in part (a). |
| | Enclosure |
| | |
| | EICB-RAl-2 , "List of Revised Required Actions to Corresponding PRA Functions," to the model application for licensee adoption of TSTF-505 dated January 31, 2012 (ADAMS Accession No. ML12032A065) states: |
| | This enclosure [Enclosure 1] should provide a description of PRA functionality for each associated specified safety function that corresponds to each proposed Required Action that is applicable when all trains of equipment are inoperable as discussed in Section 2.3.1.10 of NEI 06-09. For example, the number and identity of instrumentation and control channels (or functions) required to be PRA functional is highly dependent on the specific plant and associated equipment design. guidance is included as part of the model application because the NRC staff seeks clarity on how PRA Functional will be used during full power operation following "loss of a specified safety function or inoperability of all required trains or divisions of a system." |
| | In the LAR, Attachment 5, "List of Revised Required Actions to Corresponding Probabilistic Risk Assessment Functions," the "PRA Success Criteria" is indicated as being the same as the "Design Success Criteria" (i.e., the same minimum number of channels actuate for some instrumentation and controls (l&C) functions). (Regarding: TS 3.3.4, "Reactor Protective System (RPS) Logic and Trip Initiation," and TS 3.3.6.) * |
| | (a) Please confirm that the PRA Success Criteria ensures all associated design basis events are protected against in the condition where two Actuation Logic channels are INOPERABLE and PRA Functional or justify how adequate protection is maintained, if not. |
| | (b) Attachment 5 of the LAR identifies some l&C structures, systems, and components that are partially modeled (or not modeled) in the PRA. Item No. 11 in NEI 06-09, Section 2.3.1 includes criteria for determining PRA Functionality of components, and these criteria were developed based on the assumption that the function would be modeled in the PRA. |
| | (i) Please describe how PRA Functionality of these partial models (or un-modeled items) will be determined (i.e., how the criteria of Item No. 11 will be applied). |
| | (ii) Please describe how PRA Functionality of bounding evaluations will be determined (i.e., how the criteria of Item No. 11 will be applied). |
| | |
| | EICB-RAl-3 NEI 06-09, Revision 0-A, states that a RICT cannot be used in a condition where there is a total loss of TS specified safety function; however, it does not describe how to determine when a total loss of safety function has occurred. |
| | (a) For two Actuation Logic channels inoperable, please describe the process of how it will be determined if there is a total loss of TS specified safety function. ' |
| | |
| | ML16064A497 OFFICE NRR/DORL/LPL4-1 /PM NRR/DORL/LPL4-1/LA NRR/DE/EICB/BC NRR/DORL/LPL4-1/BC NRR/DORL/LPL4-1 /PM NAME SLingam JBurkhardt MWaters RPascarelli (BSingal for) SLingam DATE 03/07/16 03/07/16 03/07/16 03/07/16 03/07/16}} |
Letter Sequence RAI |
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CAC:MF6576, Provide RISK-INFORMED Extended Completion Times - RITSTF Initiative 4B, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO (Approved, Closed) CAC:MF6577, Provide RISK-INFORMED Extended Completion Times - RITSTF Initiative 4B, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO (Approved, Closed) CAC:MF6578, Provide RISK-INFORMED Extended Completion Times - RITSTF Initiative 4B, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO (Approved, Closed) |
|
MONTHYEARML15065A0312015-02-27027 February 2015 License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-439-A, Revision 2, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO Project stage: Request ML15218A3002015-07-31031 July 2015 License Amendment Request to Revise Technical Specifications to Adopt TSTF-505-A, Revision 1, Risk-Informed Completion Times Project stage: Request 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 Project stage: Acceptance Review ML16060A0022016-02-26026 February 2016 NRR E-mail Capture - Palo Verde, Units 1, 2, and 3: Draft Request for Additional Information Amendment to Adopt TSTF-505 (CAC Nos. MF6576 MF6577 and MF6578) Project stage: Draft RAI ML16064A4972016-03-0707 March 2016 Request for Additional Information, Adopt Technical Specification Task Force (TSTF)-505, Revision 1, Provide Risk-Informed Extended Completion Times-RITSTF Initiative 4b Project stage: RAI NL-17-0447, Response to Request for Additional Information on Technical Specifications Change to Adopt Risk Informed Completion Times2017-04-14014 April 2017 Response to Request for Additional Information on Technical Specifications Change to Adopt Risk Informed Completion Times Project stage: Response to RAI ML17307A1882017-11-0303 November 2017 License Amendment Request Supplement for Risk-Informed Completion Times Project stage: Supplement ML18074A0202018-03-20020 March 2018 Fpra FAQ 16-0011 Closure Memo Project stage: Request ML18094B1122018-04-0404 April 2018 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Final RAIs for TSTF-505 (Initiative 4b) LAR (CAC Nos. MF6576, MF6577, and MF6578: EPID L-2015-LLA-0001) Project stage: RAI ML18124A0112018-05-0303 May 2018 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Official Eeob RAIs for TSTF-505 (4b) LAR (CAC Nos. MF6576, MF6577, and MF6578; EPID L-2015-LLA-0001) Project stage: RAI ML18138A4802018-05-18018 May 2018 Response to Request for Additional Information for Risk-Informed Completion Times Project stage: Response to RAI ML18152B8742018-06-0101 June 2018 Response to Electrical Engineering Operating Reactor Branch (Eeob) Request for Additional Information for Risk-Informed Completion Times Project stage: Request ML18221A5102018-08-23023 August 2018 Request for Additional Information License Amendment Request to Adopt Risk-Informed Completion Times (CAC Nos. MF6576, MF6577, and MF6578; EPID: L-2015-LLA-0001) Project stage: RAI ML18264A3182018-09-21021 September 2018 Response to Request for Additional Information for Risk-Informed Completion Times Project stage: Response to RAI ML18278A2952018-10-0505 October 2018 Response to Request for Additional Information for Risk-Informed Completion Times Supplemental Responses for Items 17.f and 21 Project stage: Supplement ML18275A2752018-10-10010 October 2018 Summary of September 14, 2018, Clarification Call with Arizona Public Service to Discuss the Incomplete Responses in the May 18, 2018, Letter the Adoption of Rict (CAC Nos. MF6576, MF6577, MF6578; EPID L-2015-LLA-0001) Project stage: Other ML19085A5252019-05-29029 May 2019 Issuance of Amendments Nos. 209, 209, and 209 - Regarding Adoption of Risk Informed Completion Times in Technical Specifications (CAC Nos. MF6576, MF6577, and MF6578; EPID L-2015-LLA-0001) Project stage: Approval 2018-10-05
[Table View] |
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Category:Letter
MONTHYEARML24262A0972024-09-23023 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) 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 ML24213A3292024-07-31031 July 2024 Transmittal of Relief Request (RR) No. 72: Re-Submittal of RR-39 ML24213A3232024-07-31031 July 2024 Transmittal of Relief Request (RR) No. 71: Re-Submittal of RR-30 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 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 IR 05000528/20240042024-06-25025 June 2024 Notification of Inspection (NRC Inspection Report 05000528/2024004, 05000529/2024004, 05000530/2024004) 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 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) 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 IR 05000528/20230042024-02-12012 February 2024 Integrated Inspection Report Report 05000528/2023004 and 05000529/2023004 and 05000530/2023004 ML24019A2012024-01-19019 January 2024 Fourth 10-Year Interval, Second Period Owner’S Activity Report Number 1R24 ML24019A1362024-01-18018 January 2024 Inservice Inspection Request for Information ML24012A2452024-01-12012 January 2024 Response to Request for Additional Information to Proposed Method to Manage Environmentally Assisted Fatigue for the Pressurizer Surge Line 2024-09-23
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24257A1012024-09-11011 September 2024 Request for Additional Information License Renewal Commitment for AMP of Alloy 600 Components ML24143A1112024-05-20020 May 2024 Draft 2nd Round Request for RAIs Concerning LAR to Modify LCO for TS 3.5.2, LCO for TS 3.6.5, and Surveillance Requirements 3.5.1.2 and 3.5.2.2 for TS 3.5.1 and TS 3.5.2 ML24123A2002024-05-0101 May 2024 (E-Mail) Draft 2nd Round Request for Additional Information Concerning License Amendment Request to Modify Limiting Condition for Operation (LCO) for Technical Specification (TS) 3.5.2, LCO for TS 3.6.5, 3.5.1.2 and 3.5.2.2 for TS 3.5.1, a ML24114A2812024-04-19019 April 2024 Request for Additional Information (RAI-10150-R1) ML24011A1002024-01-10010 January 2024 March 2024 Emergency Preparedness Program Inspection - Request for Information ML23334A1612023-11-30030 November 2023 NRR E-mail Capture - Palo Verde 1, 2, and 3 - RAIs Associated with License Renewal Commitment for Pressurizer Surge Line Welds Inspection Program to Manage Environmentally Assisted Fatigue ML23334A0072023-11-29029 November 2023 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Official RAIs for LAR That Revises TSs 3.5.1, SITs - Operating; 3.5.2, SIT Shutdown; 3.6.5, Containment Air Temperature; and SRs for TS 3.5.1, SITs Operating ML23298A1232023-10-25025 October 2023 NRR E-mail Capture - Palo Verde, Unit 1 - RAIs for Relief Request 70, Proposed Alternatives for Pressurizer Lower Shell Temperature Nozzle ML23031A3392023-01-31031 January 2023 In-service Inspection Request for Information ML23013A0632023-01-13013 January 2023 NRR E-mail Capture - Palo Verde Unit 1 -Request for Additional Information - U1R23 Inspection Summary Report for Steam Generator Tubing ML22348A1672022-12-14014 December 2022 March 2023 Emergency Preparedness Exercise Inspection - Request for Information ML22339A2372022-12-0505 December 2022 NRR E-mail Capture - Palo Verde Unit 1 Request for Additional Information - U1R23 Inspection Summary Report for Steam Generator Tubing ML22272A3252022-09-29029 September 2022 Licensed Operator Positive Fitness-For-Duty Test Request for Additional Information ML22209A1752022-07-28028 July 2022 Inservice Inspection Request for Information ML22187A2632022-07-0606 July 2022 Notification of Inspection (NRC IR 05000528/2022004, 05000529/2022004 and 05000530/2022004) and Request for Information ML22067A2292022-03-0202 March 2022 Inservice Inspection Inspection PWR Request for Information ML22055A5842022-02-24024 February 2022 NRR E-mail Capture - Palo Verde, Unit 3 - Final RAIs for 22nd Refueling Outage (Spring 2021) Steam Generator Tube Inservice Inspection Report ML22035A3302022-02-10010 February 2022 Requests for Confirmation of Information for Exemption to Delete Diverse Auxiliary Feedwater Actuation System Based on Risk-Informed Process for Evaluations ML22025A4012022-01-0303 January 2022 March 2022 Emergency Preparedness Program Inspection - Request for Information ML21245A2222021-09-0101 September 2021 Request for Information ML21200A2392021-07-20020 July 2021 Docs Request AC - AA August 2021 ML21154A0082021-05-26026 May 2021 NRR E-mail Capture - Palo Verde 1, 2 and 3 - Official RAIs for LAR Associated with Permanent Extension of Containment ILRT Frequency to 15 Years (Type a) and CIV Leak Rate Test Frequency to 75 Months (Type C) ML21064A2372021-03-0303 March 2021 ISI Request for Information Rls ML21042B9692021-02-18018 February 2021 Notification of NRC Design Bases Assurance Inspection and Initial Request for Information ML21043A1462021-02-11011 February 2021 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Official RAI for an Order Associated with Indirect License Transfer from Public Service Company of New Mexico to Avangrid, Inc ML21023A0212021-01-13013 January 2021 PVNGS PI&R Request for Information RA ML21011A1972021-01-12012 January 2021 Unit 2, and Unit 3 - Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report 05000528/2021012, 05000529/2021012 and 05000530/2021012) and Request for Information ML20227A0992020-08-14014 August 2020 Licensed Operator Positive Fitness-For-Duty Test Request for Additional Information ML20118D1362020-04-28028 April 2020 Licensed Operator Positive Fitness-For-Duty Test Request for Additional Information ML20049A0992020-02-14014 February 2020 Notification of Cyber Security Inspection (NRC Inspection Report 05000528/2020401; 05000529/2020401; and 05000530/2020401) and Request for Information ML20049A0252020-02-12012 February 2020 NRR E-mail Capture - Palo Verde Nuclear Generating Station, Unit 1 - Official RAIs for License Amendment Request Associated with Changes to Emergency Plan Staffing Requirements ML20021A3172020-01-21021 January 2020 NRR E-mail Capture - Palo Verde Nuclear Generating Station, Unit 1 - Official RAIs for Relief Request 64, Impractical Examinations for the Third 10-Year ISI Interval ML19317D0782019-11-13013 November 2019 NRR E-mail Capture - Palo Verde 1 - Requests for Additional Information on Unit 1 21st Refueling Outage Steam Generator Tube Inspection Report ML19234A3202019-08-29029 August 2019 Redacted - Request for Additional Information for Amendment and Exemption Request to Support the Implementation of Framatome High Thermal Performance Fuel (EPID L-2018-LLA-0194; EPID L-2018-LLE-0010) ML19155A1842019-05-30030 May 2019 NRR E-mail Capture - Palo Verde Nuclear Generating Station, Unit 3 - Mvib Official RAIs for RR-63, Impractical Examinations for the Third 10-Year ISI Interval ML19095A6552019-04-0404 April 2019 NRR E-mail Capture - Palo Verde Nuclear Generating Station, Unit 3 - Mphb Official RAIs for RR-63, Impractical Examinations for the Third 10-Year ISI Interval ML19044A7342019-02-13013 February 2019 NRR E-mail Capture - Palo Verde1, 2, and 3 - Official Requests for Additional Information for RR 62, Third and Fourth 10-Year ISI Intervals, Proposed Alternative - Pressurizer Heat Sleeve Repairs ML19008A3612019-01-0808 January 2019 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Official RAIs for LAR Associated with Response Time Testing of Pressure Transmitters ML18341A0252018-12-0303 December 2018 Notification of NRC Design Bases Assurance Inspection (Teams)(05000528/2019011, 05000529/2019011, and 05000530/2019011) and Initial Request for Information ML18271A0392018-10-0202 October 2018 Non Proprietary - Supplemental Information Needed for Acceptance of Requested License Amendments and Exemptions Implementation of Framatome High Thermal Performance Fuel (Epids L-2018-LLA-0194 and L-2018-LLE-0010) ML18221A5102018-08-23023 August 2018 Request for Additional Information License Amendment Request to Adopt Risk-Informed Completion Times (CAC Nos. MF6576, MF6577, and MF6578; EPID: L-2015-LLA-0001) ML18229A3132018-08-17017 August 2018 NRR E-mail Capture - Request for Additional Information Relief Request 58: Impractical Examinations for the Third 10-Year Inservice Inspection Interval Arizona Public Service Company Palo Verde Nuclear Generation Station, Unit 2 - Second Se ML18227A8672018-08-15015 August 2018 NRR E-mail Capture - Request for Additional Information Relief Request 58: Impractical Examinations for the Third 10-Year Inservice Inspection Interval Arizona Public Service Company Palo Verde Nuclear Generation Station, Unit 2 ML18124A0112018-05-0303 May 2018 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Official Eeob RAIs for TSTF-505 (4b) LAR (CAC Nos. MF6576, MF6577, and MF6578; EPID L-2015-LLA-0001) ML18099A0072018-04-0606 April 2018 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Official RAIs for 10 CFR 50.69 LAR (CAC Nos. MF9971, MF9972, and MF9973; EPID L-2017-LLA-0276) ML18094B1122018-04-0404 April 2018 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Final RAIs for TSTF-505 (Initiative 4b) LAR (CAC Nos. MF6576, MF6577, and MF6578: EPID L-2015-LLA-0001) ML18066A7032018-03-0707 March 2018 Notification of Nrc Design Bases Assurance Inspection (Programs) 05000528/2018011, 05000529/2018011, and 05000530/2018011 Initial Request for Information ML17248A0162017-08-31031 August 2017 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Final RAI for RRs PRR-03, PRR-04 and PRR-05, Pump Testing 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) ML17082A4462017-03-28028 March 2017 PVNGS Units 1, 2, and 3 Transition to CE 16x16 Ngf - Draft RAIs Rev 3 2024-09-11
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001
.M:lrdi 7' 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 -
REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATIONS TO IMPLEMENT TSTF-505 (CAC NOS. MF6576, MF6577, AND. MF6578)
Dear Mr. Edington:
By letter dated July 31, 2015 (Agencywide Documents Access and Management System Accession No. ML15218A300), Arizona Public Service Company (the licensee) submitted a license amendment request (LAR) regarding Palo Verde Nuclear Generating Station, Units 1, 2, and 3. The proposed amendment would revise Technical Specifications (TS) to Implement TS Task Force (TSTF)-505, Revision 1, "Provide Risk-Informed Extended Completion Times - RITSTF [Risk-informed TSTF] Initiative 4b."
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the licensee's LAR and has determined that additional information is needed to support its review. Enclos!=ld is the NRC staff's request for additional information (RAI). The RAI was discussed with your staff in a clarification call on March 4, 2016, and it was agreed that your response would be provided by April 11, 2016.
R. Edington If you have any questions, please contact me at (301) 415-1564 or via e-mail at Siva.Lingam@nrc.gov. ,
Sincerely,
~ ~* D'\.J~
Siva P. Lingam, 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
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST TO ADOPT TSTF-505 ARIZONA PUBLIC SERVICE COMPANY PALO.VERDE NUCLEAR GENERATING STATION, UNITS 1. 2. AND 3 DOCKET NOS. STN 50-538, STN 50-529, AND STN 50-530 By letter dated July 31, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15218A300), Arizona Public Service Company submitted a license amendment request (LAR) regarding Palo Verde Nuclear Generating Station, Units 1, 2, and 3.
The proposed amendment would revise Technical Specifications (TSs) to Implement TS Task Force (TSTF)-505, Revision 1, "Provide Risk-Informed Extended Completion Times - RITSTF
[Risk-informed TSTF] Initiative 4b."
Based on the U.S. Nuclear Regulatory Commission (NRC) staff's review of the licensee's LAR, the staff has determined the following additional information is necessary to support completion of its technical reviE;!w: '
EICB-RAl-1 The NRC .staff seeks clarification on how probabilistic risk assessment (PRA) Functionality will be determined in the risk-informed completion time (RICT) program as implemented. The LAR does not describe conditions where Actuation Logic channels are INOPERABLE but PRA Functional.
(a) Please provide several example conditions that would allow one or more Actuation Logic channels (see TS 3.3.6, "Engineered Safety Features Actuation System (ESFAS) Logic and Manual Trip," Action E insert for TS page 3.3.6-2) to be considered both INOPERABLE and PRA Functional.
(b) For each example in part (a), please include ari evaluation against the criteria in Nuclear Energy Institute (NEI) 06-09, "Risk-Informed Technical Specifications Initiative 4b, Risk-Managed Technical Specifications (RMTS)," November 2006 (ADAMS Accession No. ML12286A322), Section 2.3.1, "Configuration Risk Management Process & Application of Technical Specifications," Item Nos. 10 and 11.
(c) The NRC staff understands that by meeting the criteria in Items Nos. 10 and 11 in NEI 06-09, Section 2.3.1, all design basis events would be protected against.
Please describe any associated design basis events that are NOT protected against in each example condition in part (a).
Enclosure
EICB-RAl-2 , "List of Revised Required Actions to Corresponding PRA Functions," to the model application for licensee adoption of TSTF-505 dated January 31, 2012 (ADAMS Accession No. ML12032A065) states:
This enclosure [Enclosure 1] should provide a description of PRA functionality for each associated specified safety function that corresponds to each proposed Required Action that is applicable when all trains of equipment are inoperable as discussed in Section 2.3.1.10 of NEI 06-09. For example, the number and identity of instrumentation and control channels (or functions) required to be PRA functional is highly dependent on the specific plant and associated equipment design. guidance is included as part of the model application because the NRC staff seeks clarity on how PRA Functional will be used during full power operation following "loss of a specified safety function or inoperability of all required trains or divisions of a system."
In the LAR, Attachment 5, "List of Revised Required Actions to Corresponding Probabilistic Risk Assessment Functions," the "PRA Success Criteria" is indicated as being the same as the "Design Success Criteria" (i.e., the same minimum number of channels actuate for some instrumentation and controls (l&C) functions). (Regarding: TS 3.3.4, "Reactor Protective System (RPS) Logic and Trip Initiation," and TS 3.3.6.) *
(a) Please confirm that the PRA Success Criteria ensures all associated design basis events are protected against in the condition where two Actuation Logic channels are INOPERABLE and PRA Functional or justify how adequate protection is maintained, if not.
(b) Attachment 5 of the LAR identifies some l&C structures, systems, and components that are partially modeled (or not modeled) in the PRA. Item No. 11 in NEI 06-09, Section 2.3.1 includes criteria for determining PRA Functionality of components, and these criteria were developed based on the assumption that the function would be modeled in the PRA.
(i) Please describe how PRA Functionality of these partial models (or un-modeled items) will be determined (i.e., how the criteria of Item No. 11 will be applied).
(ii) Please describe how PRA Functionality of bounding evaluations will be determined (i.e., how the criteria of Item No. 11 will be applied).
EICB-RAl-3 NEI 06-09, Revision 0-A, states that a RICT cannot be used in a condition where there is a total loss of TS specified safety function; however, it does not describe how to determine when a total loss of safety function has occurred.
(a) For two Actuation Logic channels inoperable, please describe the process of how it will be determined if there is a total loss of TS specified safety function. '
ML16064A497 OFFICE NRR/DORL/LPL4-1 /PM NRR/DORL/LPL4-1/LA NRR/DE/EICB/BC NRR/DORL/LPL4-1/BC NRR/DORL/LPL4-1 /PM NAME SLingam JBurkhardt MWaters RPascarelli (BSingal for) SLingam DATE 03/07/16 03/07/16 03/07/16 03/07/16 03/07/16