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| | number = ML15128A178 | | | number = ML15128A178 |
| | issue date = 05/08/2015 | | | issue date = 05/08/2015 |
| | title = 2015/05/08 NRR E-mail Capture - Corrections to ANO-1 NFPA 805 Requests for Additional Information - TAC No MF3419 | | | title = NRR E-mail Capture - Corrections to ANO-1 NFPA 805 Requests for Additional Information - TAC No MF3419 |
| | author name = George A | | | author name = George A |
| | author affiliation = NRC/NRR/DORL/LPLIV-1 | | | author affiliation = NRC/NRR/DORL/LPLIV-1 |
| | addressee name = Bice D B | | | addressee name = Bice D |
| | addressee affiliation = Entergy Nuclear Operations, Inc | | | addressee affiliation = Entergy Nuclear Operations, Inc |
| | docket = 05000313 | | | docket = 05000313 |
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| | page count = 6 | | | page count = 6 |
| | project = TAC:MF3419 | | | project = TAC:MF3419 |
| | stage = Other | | | stage = RAI |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:1NRR-PMDAPEm ResourceFrom:George, AndreaSent:Friday, May 08, 2015 8:58 AMTo:'BICE, DAVID B (ANO)'Cc:Miller, BarrySubject:Corrections to ANO-1 NFPA 805 Requests for Additional Information - TAC NO MF3419Attachments:ANO-1 Corrected RAI response table.docxGood morning, Due to numbering/formatting changes after the onsite audit was complete, errors were introduced into the RAI response timeline table, as well as the introduction to PRA RAI 3. The corrected RAI response timeline table is attached, and it wholly supercedes Enclosure 2 to the NRC's letter dated May 5, 2015 (ADAMS Accession No. ML15091A431). | | {{#Wiki_filter:NRR-PMDAPEm Resource From: George, Andrea Sent: Friday, May 08, 2015 8:58 AM To: 'BICE, DAVID B (ANO)' |
| | | Cc: Miller, Barry |
| Additionally, regarding the introduction to PRA RAI 3, the following language is correct, and does not change any of the PRA RAI 3 requests for information that follow: PRA RAI 03 - Integrated Analysis
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| Section 2.4.4.1 of NFPA-805 states that the change in public health risk arising from transition from the current fire protection program to an NFPA-805 based program, and all future plant changes to the program, shall be acceptable to the NRC. RG 1.174, "An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis," Revision 2, dated May 2011 (ADAMS Accession No. ML100910006), provides quantitative guidelines on CDF and LERF, and identifies acceptable changes to these frequencies that result from proposed changes to the plant's licensing basis and describes a general framework to determine the acceptability of risk-informed changes. The NRC staff review of the information in the LAR has identified additional information that is required to fully characterize the risk estimates.
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| | ==Subject:== |
| | Corrections to ANO-1 NFPA 805 Requests for Additional Information - TAC NO MF3419 Attachments: ANO-1 Corrected RAI response table.docx Good morning, Due to numbering/formatting changes after the onsite audit was complete, errors were introduced into the RAI response timeline table, as well as the introduction to PRA RAI 3. The corrected RAI response timeline table is attached, and it wholly supercedes Enclosure 2 to the NRCs letter dated May 5, 2015 (ADAMS Accession No. ML15091A431). |
| | Additionally, regarding the introduction to PRA RAI 3, the following language is correct, and does not change any of the PRA RAI 3 requests for information that follow: |
| | PRA RAI 03 - Integrated Analysis Section 2.4.4.1 of NFPA-805 states that the change in public health risk arising from transition from the current fire protection program to an NFPA-805 based program, and all future plant changes to the program, shall be acceptable to the NRC. RG 1.174, An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis, Revision 2, dated May 2011 (ADAMS Accession No. ML100910006), provides quantitative guidelines on CDF and LERF, and identifies acceptable changes to these frequencies that result from proposed changes to the plants licensing basis and describes a general framework to determine the acceptability of risk-informed changes. The NRC staff review of the information in the LAR has identified additional information that is required to fully characterize the risk estimates. |
| The PRA methods currently under review in the LAR include: | | The PRA methods currently under review in the LAR include: |
| * PRA RAI 1.a regarding spatial separation | | * PRA RAI 1.a regarding spatial separation |
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Line 43: |
| * PRA RAI 12 regarding multiple versus single cables | | * PRA RAI 12 regarding multiple versus single cables |
| * PRA RAI 14 regarding large reduction credit for modifications | | * PRA RAI 14 regarding large reduction credit for modifications |
| * FM RAI 1.k regarding evaluation of MCR abandonment times If you have any questions, please let me know. | | * FM RAI 1.k regarding evaluation of MCR abandonment times If you have any questions, please let me know. |
| 2Thank you, Andrea George Project Manager Division of Operating Reactor Licensing U.S. Nuclear Regulatory Commission 301-415-1081
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| Hearing Identifier: NRR_PMDA Email Number: 2051 Mail Envelope Properties (6F9E3C9DCAB9E448AAA49B8772A448C50254CA969EF5) | | Thank you, Andrea George Project Manager Division of Operating Reactor Licensing U.S. Nuclear Regulatory Commission 301-415-1081 2 |
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| | Hearing Identifier: NRR_PMDA Email Number: 2051 Mail Envelope Properties (6F9E3C9DCAB9E448AAA49B8772A448C50254CA969EF5) |
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| ==Subject:== | | ==Subject:== |
| Corrections to ANO-1 NFPA 805 Requests for Additional Information - TAC NO MF3419 Sent Date: 5/8/2015 8:58:08 AM Received Date: 5/8/2015 8:58:00 AM From: George, Andrea Created By: Andrea.George@nrc.gov Recipients: "Miller, Barry" <Barry.Miller@nrc.gov> Tracking Status: None | | Corrections to ANO-1 NFPA 805 Requests for Additional Information - TAC NO MF3419 Sent Date: 5/8/2015 8:58:08 AM Received Date: 5/8/2015 8:58:00 AM From: George, Andrea Created By: Andrea.George@nrc.gov Recipients: |
| "'BICE, DAVID B (ANO)'" <DBICE@entergy.com> Tracking Status: None Post Office: HQCLSTR01.nrc.gov Files Size Date & Time MESSAGE 3183 5/8/2015 8:58:00 AM ANO-1 Corrected RAI response table.docx 37505 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: Recipients Received: | | "Miller, Barry" <Barry.Miller@nrc.gov> |
| | Tracking Status: None |
| | "'BICE, DAVID B (ANO)'" <DBICE@entergy.com> |
| | Tracking Status: None Post Office: HQCLSTR01.nrc.gov Files Size Date & Time MESSAGE 3183 5/8/2015 8:58:00 AM ANO-1 Corrected RAI response table.docx 37505 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: |
| | Recipients Received: |
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| ==Enclosure==
| | PRA RAI 03 - Integrated Analysis Section 2.4.4.1 of NFPA-805 states that the change in public health risk arising from transition from the current fire protection program to an NFPA-805 based program, and all future plant changes to the program, shall be acceptable to the NRC. RG 1.174, An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis, Revision 2, dated May 2011 (ADAMS Accession No. ML100910006), provides quantitative guidelines on CDF andLERF, and identifies acceptable changes to these frequencies that result from proposed changes to the plants licensing basis and describes a general framework to determine the acceptability of risk-informed changes. The NRC staff review of the information in the LAR has identified additional information that is required to fully characterize the risk estimates. |
| 1 PRA RAI 03 - Integrated Analysis Section 2.4.4.1 of NFPA-805 states that the change in public health risk arising from transition from the current fire protection program to an NFPA-805 based program, and all future plant changes to the program, shall be acceptable to the NRC. RG 1.174, "An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis," Revision 2, dated May 2011 (ADAMS Accession No. ML100910006), provides quantitative guidelines on CDF andLERF, and identifies acceptable changes to these frequencies that result from proposed changes to the plant's licensing basis and describes a general framework to determine the acceptability of risk-informed changes. The NRC staff review of the information in the LAR has identified additional information that is required to fully characterize the risk estimates. The PRA methods currently under review in the LAR include:
| | The PRA methods currently under review in the LAR include: |
| * PRA RAI 1.a regarding spatial separation | | * PRA RAI 1.a regarding spatial separation |
| * PRA RAI 1.b regarding fire barriers | | * PRA RAI 1.b regarding fire barriers |
| Line 70: |
Line 77: |
| * PRA RAI 12 regarding multiple versus single cables | | * PRA RAI 12 regarding multiple versus single cables |
| * PRA RAI 14 regarding large reduction credit for modifications | | * PRA RAI 14 regarding large reduction credit for modifications |
| * FM RAI 1.k regarding evaluation of MCR abandonment times Please provide the following information: a) Results of an aggregate analysis that provides the integrated impact on the fire risk (i.e., the total transition CDF, LERF, CDF, LERF) of replacing specific methods identified above with alternative methods which are acceptable to the NRC. In this aggregate analysis, for those cases where the individual issues have a synergistic impact on the results, a simultaneous analysis must be performed. For those cases where no synergy exists, a one-at-a-time analysis may be done. For those cases that have a negligible impact, a qualitative evaluation may be done. It should be noted that this list may expand depending on NRC's review of the responses to other RAIs in this document. b) For each method (i.e., each bullet) above, please explain how the issue will be addressed in 1) the final aggregate analysis results provided in support of the LAR, and 2) the PRA that will be used at the beginning of the self-approval of post-transition changes. In addition, provide a method to ensure that all changes will be made, that a focused-scope peer review will be performed on changes that are PRA upgrades as defined in the PRA standard, and that any findings will be resolved before self-approval of post-transition changes. c) In the response, explain how the RG 1.205 risk acceptance guidelines are satisfied for the aggregate analysis. If applicable, include a description of any new modifications or operator actions being credited to reduce delta risk as well as a discussion of the associated impacts to the fire protection program. d) If any unacceptable methods or weaknesses will be retained in the PRA that will be used to estimate the change in risk of post-transition changes to support self-approval, explain how the quantification results for each future change will account for the use of these unacceptable methods or weaknesses. | | * FM RAI 1.k regarding evaluation of MCR abandonment times Please provide the following information: |
| | a) Results of an aggregate analysis that provides the integrated impact on the fire risk (i.e., the total transition CDF, LERF, CDF, LERF) of replacing specific methods identified above with alternative methods which are acceptable to the NRC. In this aggregate analysis, for those cases where the individual issues have a synergistic impact on the results, a simultaneous analysis must be performed. For those cases where no synergy exists, a one-at-a-time analysis may be done. For those cases that have a negligible impact, a qualitative evaluation may be done. It should be noted that this list may expand depending on NRCs review of the responses to other RAIs in this document. |
| | b) For each method (i.e., each bullet) above, please explain how the issue will be addressed in 1) the final aggregate analysis results provided in support of the LAR, and 2) the PRA that will be used at the beginning of the self-approval of post-transition changes. In addition, provide a method to ensure that all changes will be made, that a focused-scope peer review will be performed on changes Enclosure 1 |
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| ==Enclosure==
| | that are PRA upgrades as defined in the PRA standard, and that any findings will be resolved before self-approval of post-transition changes. |
| 2 Timetable for Request for Additional Information Response Request for Additional Information Response Date FPE 02, 03, 05, 08 SSA 01, 03, 04, 05 RR 01 05/26/2015 (*30 days) FPE 01, 04, 06 SSA 02, 06, 08 FM 05 PRA 01.a, .b, .c, .d,.f, .g, .h, .ij, .k, .l, 02.b, 04, 06, 12, 14 06/22/2015 (*60 days) FPE07 SSA 07, 09, 10 FM 01, 02, 03, 04, 06 PRA 01.e, .fh, .i, 02.a, .c, .d, .e, 05, 07, 08, 09, 16 07/22/2015 (*90 days) SSA 11 PRA 03**, 10, 11, 13, 15, 17**, 18 08/21/2015 (*120 days) *From conclusion of audit on April 23, 2015 **Final risk quantification information will be provided after the approaches outlined in all RAI responses that impact final risk quantification are acceptable to the NRC.
| | c) In the response, explain how the RG 1.205 risk acceptance guidelines are satisfied for the aggregate analysis. If applicable, include a description of any new modifications or operator actions being credited to reduce delta risk as well as a discussion of the associated impacts to the fire protection program. |
| | d) If any unacceptable methods or weaknesses will be retained in the PRA that will be used to estimate the change in risk of post-transition changes to support self-approval, explain how the quantification results for each future change will account for the use of these unacceptable methods or weaknesses. |
| | |
| | Timetable for Request for Additional Information Response Request for Additional Information Response Date FPE 02, 03, 05, 08 05/26/2015 SSA 01, 03, 04, 05 |
| | (*30 days) |
| | RR 01 FPE 01, 04, 06 SSA 02, 06, 08 06/22/2015 FM 05 (*60 days) |
| | PRA 01.a, .b, .c, .d,.f, .g, .h, .ij, .k, .l, 02.b, 04, 06, 12, 14 FPE07 SSA 07, 09, 10 07/22/2015 FM 01, 02, 03, 04, 06 (*90 days) |
| | PRA 01.e, .fh, .i, 02.a, .c, .d, .e, 05, 07, 08, 09, 16 SSA 11 08/21/2015 PRA 03**, 10, 11, 13, 15, 17**, 18 (*120 days) |
| | *From conclusion of audit on April 23, 2015 |
| | **Final risk quantification information will be provided after the approaches outlined in all RAI responses that impact final risk quantification are acceptable to the NRC. |
| Abbreviation Key: | | Abbreviation Key: |
| FPE - Fire Protection Engineering SSA- Safe Shutdown Analysis FM - Fire Modeling PRA - Probabilistic Risk Assessment RR - Radioactive Release | | FPE - Fire Protection Engineering SSA- Safe Shutdown Analysis FM - Fire Modeling PRA - Probabilistic Risk Assessment RR - Radioactive Release Enclosure 2}} |
| }} | |
Letter Sequence RAI |
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MONTHYEARML14139A2702014-05-20020 May 2014
One. Unit 1 - Acceptance of Licensing Action, Request to Adopt National Fire Protection Association NFPA 805, Performance-Based Standard for Fire Protection for LWR Generating Plants (2001 Edition)
Project stage: Acceptance Review
ML14139A2752014-05-30030 May 2014
One. Unit 1 - Online Reference Portal for License Amendment Request to Adopt National Fire Protection Association NFPA 805, Performance-Based Standard for Fire Protection for LWR Generating Plants (2001 Edition)
Project stage: Other
ML15086A0492015-03-27027 March 2015
Regulatory Audit Plan for 4/20-23/15 Audit in Support of Request to Adopt National Fire Protection Association NFPA 805, Performance-Based Standard for Fire Protection for LWR Generating Plants (2001 Edition)
Project stage: Other
ML15091A4312015-05-0505 May 2015
Request for Additional Information, Request to Adopt National Fire Protection Association NFPA 805, Performance-Based Standard for Fire Protection for LWR Generating Plants (2001 Edition)
Project stage: RAI
ML15128A1782015-05-0808 May 2015
NRR E-mail Capture - Corrections to ANO-1 NFPA 805 Requests for Additional Information - TAC No MF3419
Project stage: RAI
1CAN061501, 60-Day Response to Request for Additional Information Adoption of National Fire Protection Association Standard NFPA-8052015-06-16016 June 2015
60-Day Response to Request for Additional Information Adoption of National Fire Protection Association Standard NFPA-805
Project stage: Response to RAI
ML15225A2542015-08-14014 August 2015
Summary of 4/20-23/2015 Audit in Support of Request to Adopt National Fire Protection Association NFPA 805, Performance-Based Standard for Fire Protection for LWR Generating Plants (2001 Edition)
Project stage: Other
ML15251A2202015-09-0808 September 2015
NRR E-mail Capture - 2nd Round Requests for Additional Information - ANO-1 NFPA 805 LAR - TAC No. MF3419
Project stage: RAI
ML15280A1142015-10-0606 October 2015
NRR E-mail Capture - Second Round Follow-up Requests for Additional Information - ANO-1 NFPA 805 LAR - TAC No. MF3419 (Formal Transmittal)
Project stage: RAI
1CAN111501, Second Set of Round 2 Responses to Request for Additional Information Adoption of National Fire Protection Association Standard NFPA-8052015-11-0404 November 2015
Second Set of Round 2 Responses to Request for Additional Information Adoption of National Fire Protection Association Standard NFPA-805
Project stage: Response to RAI
1CAN111502, Clarification of Response to Round 2 Request for Additional Information Adoption of National Fire Protection Association Standard NFPA-8052015-11-17017 November 2015
Clarification of Response to Round 2 Request for Additional Information Adoption of National Fire Protection Association Standard NFPA-805
Project stage: Request
ML16012A0492016-01-12012 January 2016
NRR E-mail Capture - 3rd Round Request for Additional Information - ANO-1 NFPA 805 LAR - TAC No. MF3419
Project stage: RAI
ML16070A1312016-03-10010 March 2016
NRR E-mail Capture - 4th Round Request for Additional Information - ANO-1 NFPA 805 LAR - TAC No. MF3419
Project stage: RAI
2015-05-05
[Table View] |
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Category:E-Mail
MONTHYEARML24296A0652024-10-22022 October 2024
NRR E-mail Capture - Arkansas Nuclear One, Unit 2 - Verbal Authorization of Relief Request for the Proposed Alternative ANO2-RR-24-001
ML24227A0072024-08-13013 August 2024
NRR E-mail Capture - LIC-109 Acceptance - ANO 2 - Proposed Alternative for Implementation of Extended Reactor Vessel In-Service Inspection Interval (ANO2-ISI-24-02) - EPID L-2024-LLR-0048
ML24218A0652024-08-0202 August 2024
NRR E-mail Capture - LIC-109 Acceptance Review - Arkansas Nuclear One, Unit 1 - License Amendment Request - Request for Review and Approval Changes to SAR and to a Confirmatory Order - Pzr Htr Emergency Power Supply - EPID L-2024-LLA-0092
ML24180A0022024-06-26026 June 2024
NRR E-mail Capture - LIC-109 Acceptance - ANO 1 and 2 - Proposed Alternatives for Examinations of SG Pressure Retaining Welds and Full Penetrations Nozzles - EPID L-2024-LLR-0038
ML24149A3672024-05-28028 May 2024
August 2024 Emergency Preparedness Exercise Inspection - Request for Information
ML24117A0262024-04-26026 April 2024
NRR E-mail Capture - ANO Unit 2 - Acceptance of Requested Licensing Action License Amendment Request to Revise Typographical Errors in Technical Specifications
ML24088A0082024-03-27027 March 2024
NRR E-mail Capture - ANO-2 -- TSTF-505 Post-Audit Final RAI (L-2023-LLA-0052)
ML23269A0232023-09-22022 September 2023
NRR E-mail Capture - Arkansas Nuclear One, Unit 2 - TSTF-505 Audit Questions
ML23240A3412023-08-28028 August 2023
NRR E-mail Capture - ANO-2, Grand Gulf, and River Bend - Acceptance Review of LAR Revising TSs to Adopt TSTF-205, Revision of Channel Calibration, Channel Functional Test, and Related Definitions
ML23194A1752023-07-13013 July 2023
NRR E-mail Capture - ANO-1 - Acceptance Review of Alternative Request ANO1-ISI-037
ML23187A0432023-07-0303 July 2023
NRR E-mail Capture - Arkansas Nuclear One, Unit 1 - TSTF-505 Audit Agenda
ML23166A0132023-06-14014 June 2023
NRR E-mail Capture - Arkansas Nuclear One, Unit 1 - TSTF-505 Audit Questions
ML23130A2752023-05-10010 May 2023
NRR E-mail Capture - ANO Unit 2- Acceptance of Requested Licensing Action LAR to Adopt TSTF-505 Revision 2
ML23118A0692023-04-28028 April 2023
NRR E-mail Capture - ANO Unit 1 - Acceptance of Requested Licensing Action LAR to Modify ANO-1 TS 3.3.1, Reactor Protection System Instrumentation (L-2023-LLA-0048)
ML23104A1052023-03-10010 March 2023
NRR E-mail Capture - ANO-2 Final RAI Alternative Request for Life-of-Repair of RVCH Pen. 46
ML23072A3672023-03-0909 March 2023
NRR E-mail Capture - Entergy Fleet - Acceptance Review of Quality Assurance Program Manual Reduction in Commitment
ML23039A0872023-02-0808 February 2023
NRR E-mail Capture - Arkansas Nuclear One, Unit 2 - Acceptance Review of Relief Request ANO2-RR-23-001, Half-Nozzle Repair of RVCH Penetration 46 (L-2023-LLR-0000)
ML23026A1322023-01-26026 January 2023
NRR E-mail Capture - ANO Unit 1 - Acceptance of Requested Licensing Action LAR to Adopt TSTF-505 Revision 2
ML22354A0122022-12-19019 December 2022
NRR E-mail Capture - ANO-1 and ANO-2 - Acceptance Review of Request for Alternative ANO-CISI-002 Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (L-2022-LLR-0080)
ML22349A0112022-12-14014 December 2022
NRR E-mail Capture - Final RAI Relief Request ANO1-ISI-035
ML22341A1202022-12-0707 December 2022
NRR E-mail Capture - ANO Unit 1 - Acceptance of Requested Licensing Action LAR to to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation (L-2022-LLA-0161)
ML22273A0982022-09-30030 September 2022
NRR E-mail Capture - ANO Units 1 and 2 - Acceptance of Requested Licensing Action Emergency Plan Staffing Requirements
ML22265A2012022-09-22022 September 2022
NRR E-mail Capture - ANO-1 - Acceptance Review of Relief Request ANO1-ISI-036
ML22188A1782022-07-0707 July 2022
NRR E-mail Capture - ANO-1 - Acceptance Review of Relief Request ANO1-ISI-035
ML22174A1362022-06-23023 June 2022
NRR E-mail Capture - ANO-2 Final RAI Relief Requests ANO2-ISI-023 Through -028 (EPIDs L-2022-LLR-0022 Through -0027)
ML22151A3262022-05-31031 May 2022
August 2022 Emergency Preparedness Exercise Inspection - Request for Information
ML22124A2452022-05-0404 May 2022
NRR E-mail Capture - ANO-1 and ANO-2 - Final RAI 2 License Amendment Requests to Implement Provisions of 10 CFR 50.69 (L-2021-LLA-0105/-0106)
ML22108A1642022-04-18018 April 2022
NRR E-mail Capture - ANO-1: Final RAI License Amendment Request Concerning TS Changes Due to Revised Dose Calculations (L-2021-LLA-0181)
ML22081A3902022-03-22022 March 2022
NRR E-mail Capture - ANO-2 - Acceptance Review of Relief Requests ANO2-ISI-023, -024, -025, -026, -027, and -028 (Epids: L-2022-LLR-022, -023, -024, -025, -026, and -027)
ML22034A5482022-02-0303 February 2022
NRR E-mail Capture - Final RAI License Amendment Requests to Implement Provisions of 10 CFR 50.69 (L-2021-LLA-0105/-0106)
ML22020A0822022-01-19019 January 2022
NRR E-mail Capture - ANO-1 and 2 - Final RAI 2 License Amendment Requests to Allow the ECP to Remain Operable on a One-Time Basis for Up to 65 Days to Perform Piping Upgrade (L-2021-LLA-0015)
ML22020A0742022-01-13013 January 2022
NRR E-mail Capture - ANO Unit 2 - Acceptance of Requested Licensing Action Alternative ANO2-PT-003
ML21314A1212021-11-0909 November 2021
Verbal Authorization of Relief Request ANO2-RR-21-002
ML21312A0382021-11-0505 November 2021
NRR E-mail Capture - ANO-2 RAI Relief Request ANO2-RR-21-002
ML21312A4792021-11-0505 November 2021
Email: NRC Staff Preliminary Questions Regarding X Energy LLC Xe-100 Topical Report: Risk-Informed Performance-Based Licensing Basis Development
ML21308A5602021-11-0404 November 2021
NRR E-mail Capture - Arkansas Nuclear One, Units 1 and 2, Grand Gulf, River Bend, and Waterford, Unit 3 - Acceptance Review of LAR to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements
ML21292A0112021-10-18018 October 2021
NRR E-mail Capture - ANO, 1 and 2, Grand Gulf, River Bend, Waterford, 3 - Acceptance Review of LAR to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position
ML21287A1692021-10-13013 October 2021
Record of 10-13-21 Verbal Authorization of ANO2-R&R-012 (L-2021-LLR-0082)
ML21298A1562021-10-11011 October 2021
NRR E-mail Capture - ANO-2 Final RAI Relief Request ANO2-R&R-012 Concerning Rv Closure Head Penetration 46
ML21273A0672021-09-29029 September 2021
NRR E-mail Capture - ANO-2 Final RAI 2 License Amendment Request to Adopt a Safety Function Determination Program
ML21238A3742021-08-23023 August 2021
RFI Email - Cyber PI&R Inspection (ANO)
ML21252A0052021-08-20020 August 2021
NRR E-mail Capture - ANO-1 and 2 Final RAI License Amendment Request to Allow the ECP to Remain Operable on a One-Time Basis for Up to 65 Days to Perform Piping Upgrade (L-2021-LLA-0015)
ML21217A3302021-08-0505 August 2021
(ANO) Problem Identification and Resolution (PIR) Request for Information Combined
ML21202A1662021-07-20020 July 2021
NRR E-mail Capture - ANO Unit 2 - Acceptance of Requested Licensing Action Alternative ANO2-PT-003
ML21201A0062021-07-19019 July 2021
NRR E-mail Capture - Arkansas Nuclear One, Units 1 and 2, and Waterford, Unit 3 - Acceptance Review of LAR to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections
ML21197A0372021-07-16016 July 2021
NRR E-mail Capture - ANO-1 and 2 - Final RAI Final Response to GL 2004-02
ML21179A0052021-06-25025 June 2021
NRR E-mail Capture - ANO Unit 2 - Acceptance of Requested Licensing Action License Amendment Request to Adopt 10 CFR 50.69
ML21179A0042021-06-25025 June 2021
NRR E-mail Capture - ANO Unit 1 - Acceptance of Requested Licensing Action License Amendment Request to Adopt 10 CFR 50.69
ML21174A0342021-06-22022 June 2021
NRR E-mail Capture - Entergy Fleet (ANO, Ggulf, Rbend, & Waterford) - Acceptance Review for Relief Request to Use a Provision of a Later Edition of the ASME Code, Section XI for Periodic System Pressure Tests Exemptions
ML21116A1092021-04-26026 April 2021
NRR E-mail Capture - ANO-1 and ANO-2: Final Supplemental RAI Proposed Alternative to ASME Section XI Requirements for Repair/Replacement of ECP Supply Piping
2024-08-02
[Table view] |
Text
NRR-PMDAPEm Resource From: George, Andrea Sent: Friday, May 08, 2015 8:58 AM To: 'BICE, DAVID B (ANO)'
Cc: Miller, Barry
Subject:
Corrections to ANO-1 NFPA 805 Requests for Additional Information - TAC NO MF3419 Attachments: ANO-1 Corrected RAI response table.docx Good morning, Due to numbering/formatting changes after the onsite audit was complete, errors were introduced into the RAI response timeline table, as well as the introduction to PRA RAI 3. The corrected RAI response timeline table is attached, and it wholly supercedes Enclosure 2 to the NRCs letter dated May 5, 2015 (ADAMS Accession No. ML15091A431).
Additionally, regarding the introduction to PRA RAI 3, the following language is correct, and does not change any of the PRA RAI 3 requests for information that follow:
PRA RAI 03 - Integrated Analysis Section 2.4.4.1 of NFPA-805 states that the change in public health risk arising from transition from the current fire protection program to an NFPA-805 based program, and all future plant changes to the program, shall be acceptable to the NRC. RG 1.174, An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis, Revision 2, dated May 2011 (ADAMS Accession No. ML100910006), provides quantitative guidelines on CDF and LERF, and identifies acceptable changes to these frequencies that result from proposed changes to the plants licensing basis and describes a general framework to determine the acceptability of risk-informed changes. The NRC staff review of the information in the LAR has identified additional information that is required to fully characterize the risk estimates.
The PRA methods currently under review in the LAR include:
- PRA RAI 1.a regarding spatial separation
- PRA RAI 1.c regarding fire propagation from electrical cabinets
- PRA RAI 1.e regarding circuit failure likelihood analysis
- PRA RAI 1.g regarding modeling new fire Human Error Events
- PRA RAI 1.h regarding state of knowledge correlation (SOKC)
- PRA RAI 2.a regarding impact of phenomenological conditions
- PRA RAI 2.d regarding counting operational demands
- PRA RAI 2.e regarding counting failures
- PRA RAI 5 regarding treatment of sensitive electronics
- PRA RAI 7 regarding propagation of fire from >440 V electrical cabinets
- PRA RAI 9 regarding fire propagation in the MCR
- PRA RAI 11 regarding crediting MCR abandonment
- PRA RAI 12 regarding multiple versus single cables
- PRA RAI 14 regarding large reduction credit for modifications
- FM RAI 1.k regarding evaluation of MCR abandonment times If you have any questions, please let me know.
1
Thank you, Andrea George Project Manager Division of Operating Reactor Licensing U.S. Nuclear Regulatory Commission 301-415-1081 2
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Corrections to ANO-1 NFPA 805 Requests for Additional Information - TAC NO MF3419 Sent Date: 5/8/2015 8:58:08 AM Received Date: 5/8/2015 8:58:00 AM From: George, Andrea Created By: Andrea.George@nrc.gov Recipients:
"Miller, Barry" <Barry.Miller@nrc.gov>
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"'BICE, DAVID B (ANO)'" <DBICE@entergy.com>
Tracking Status: None Post Office: HQCLSTR01.nrc.gov Files Size Date & Time MESSAGE 3183 5/8/2015 8:58:00 AM ANO-1 Corrected RAI response table.docx 37505 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
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PRA RAI 03 - Integrated Analysis Section 2.4.4.1 of NFPA-805 states that the change in public health risk arising from transition from the current fire protection program to an NFPA-805 based program, and all future plant changes to the program, shall be acceptable to the NRC. RG 1.174, An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis, Revision 2, dated May 2011 (ADAMS Accession No. ML100910006), provides quantitative guidelines on CDF andLERF, and identifies acceptable changes to these frequencies that result from proposed changes to the plants licensing basis and describes a general framework to determine the acceptability of risk-informed changes. The NRC staff review of the information in the LAR has identified additional information that is required to fully characterize the risk estimates.
The PRA methods currently under review in the LAR include:
- PRA RAI 1.a regarding spatial separation
- PRA RAI 1.d regarding fire propagation from electrical cabinets
- PRA RAI 1.h regarding circuit failure likelihood analysis
- PRA RAI 1.j regarding modeling new fire Human Error Events
- PRA RAI 1.k regarding state of knowledge correlation (SOKC)
- PRA RAI 2.a regarding impact of phenomenological conditions
- PRA RAI 2.d regarding counting operational demands
- PRA RAI 2.e regarding counting failures
- PRA RAI 5 regarding treatment of sensitive electronics
- PRA RAI 7 regarding propagation of fire from >440 V electrical cabinets
- PRA RAI 9 regarding fire propagation in the MCR
- PRA RAI 11 regarding crediting MCR abandonment
- PRA RAI 12 regarding multiple versus single cables
- PRA RAI 14 regarding large reduction credit for modifications
- FM RAI 1.k regarding evaluation of MCR abandonment times Please provide the following information:
a) Results of an aggregate analysis that provides the integrated impact on the fire risk (i.e., the total transition CDF, LERF, CDF, LERF) of replacing specific methods identified above with alternative methods which are acceptable to the NRC. In this aggregate analysis, for those cases where the individual issues have a synergistic impact on the results, a simultaneous analysis must be performed. For those cases where no synergy exists, a one-at-a-time analysis may be done. For those cases that have a negligible impact, a qualitative evaluation may be done. It should be noted that this list may expand depending on NRCs review of the responses to other RAIs in this document.
b) For each method (i.e., each bullet) above, please explain how the issue will be addressed in 1) the final aggregate analysis results provided in support of the LAR, and 2) the PRA that will be used at the beginning of the self-approval of post-transition changes. In addition, provide a method to ensure that all changes will be made, that a focused-scope peer review will be performed on changes Enclosure 1
that are PRA upgrades as defined in the PRA standard, and that any findings will be resolved before self-approval of post-transition changes.
c) In the response, explain how the RG 1.205 risk acceptance guidelines are satisfied for the aggregate analysis. If applicable, include a description of any new modifications or operator actions being credited to reduce delta risk as well as a discussion of the associated impacts to the fire protection program.
d) If any unacceptable methods or weaknesses will be retained in the PRA that will be used to estimate the change in risk of post-transition changes to support self-approval, explain how the quantification results for each future change will account for the use of these unacceptable methods or weaknesses.
Timetable for Request for Additional Information Response Request for Additional Information Response Date FPE 02, 03, 05, 08 05/26/2015 SSA 01, 03, 04, 05
(*30 days)
RR 01 FPE 01, 04, 06 SSA 02, 06, 08 06/22/2015 FM 05 (*60 days)
PRA 01.a, .b, .c, .d,.f, .g, .h, .ij, .k, .l, 02.b, 04, 06, 12, 14 FPE07 SSA 07, 09, 10 07/22/2015 FM 01, 02, 03, 04, 06 (*90 days)
PRA 01.e, .fh, .i, 02.a, .c, .d, .e, 05, 07, 08, 09, 16 SSA 11 08/21/2015 PRA 03**, 10, 11, 13, 15, 17**, 18 (*120 days)
- From conclusion of audit on April 23, 2015
- Final risk quantification information will be provided after the approaches outlined in all RAI responses that impact final risk quantification are acceptable to the NRC.
Abbreviation Key:
FPE - Fire Protection Engineering SSA- Safe Shutdown Analysis FM - Fire Modeling PRA - Probabilistic Risk Assessment RR - Radioactive Release Enclosure 2
