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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) |
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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
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Category:Memoranda
MONTHYEARML24124A0342024-05-0101 May 2024 Summary of Public Meeting Concerning Annual Assessment of Catawba Nuclear Station Units 1 and 2, McGuire Nuclear Station Units 1 and 2, Oconee Nuclear Station Units 1, 2, and 3, Brunswick Steam Electric Plant Units 1 and 2, Shearon Harris ML23151A1232023-05-31031 May 2023 Public Meeting Summary - 2022 Annual Assessment Meeting Regarding Shearon Harris Nuclear Plant ML22130A0302022-05-0909 May 2022 Summary of Public Meeting on 2021 Annual Assessment Meeting Regarding Brunswick Steam Electric Plant, Docket Nos. 50-325 and 50-324; and Shearon Harris Nuclear Power Plant, Docket No. 50-400, Meeting Number 20220350 ML22075A3592022-03-17017 March 2022 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML22034A3932022-02-16016 February 2022 Calendar Year 2021 Security Baseline Completion Memo ML21131A1472021-05-11011 May 2021 Public Meeting Summary 2020 Annual Assessment Meeting Regarding Brunswick Steam Electric Plant, Docket Nos. 50-325 and 50-324; and Shearon Harris Nuclear Power Plant, Docket No. 50-400, Meeting Number 20210385 RA-21-0097, Notification of Permit Revision Request Regarding Copper and Zinc Limits2021-03-15015 March 2021 Notification of Permit Revision Request Regarding Copper and Zinc Limits ML20136A2222020-05-15015 May 2020 Har - Bru 2019 Aam Meeting Summary ML19113A0652019-05-14014 May 2019 Summary of Meeting with Duke Energy to Discuss Proposed License Amendment Request for Shearon Harris, Unit 1, Technical Specification Changes Associated with Departure from Nucleate Boiling Ratio Safety Limit ML19123A3522019-05-0202 May 2019 Public Meeting Summary - Shearon Harris Nuclear Plant, Docket No. 50-400 ML18109A0912018-04-19019 April 2018 Summary of 2017 Annual Assessment Public Meeting Regarding Shearon Harris Nuclear Plant, Docket No. 50-400 ML18074A0202018-03-20020 March 2018 Fpra FAQ 16-0011 Closure Memo ML17145A3142017-05-25025 May 2017 EOC Meeting Summary ML16300A1802016-10-27027 October 2016 Verbal Authorization of Relief Request I3R-16, for Reactor Vessel Closure Head Penetration Nozzle Repair Technique, Inservice Inspection Program -Third 10-Year Interval ML16138A0502016-05-24024 May 2016 Audit Report - Application For Amendment Shearon Harris Nuclear Power Plant, Unit 1 - The Proposed License Amendment Revises The As-Found Lift Setting Tolerance For Main Steam Line Code Safety Valves In Technical Specifications (TAC No. MF7195) ML16134A1552016-05-12012 May 2016 Public Meeting Summary - 2015 Annual Assessment Public Meeting Regarding Shearon Harris Nuclear Plant ML16103A2552016-04-14014 April 2016 05/02/2016 Notice of Forthcoming Closed Pre-Submittal Meeting with Duke Energy Progress, Inc., to Discuss Fuel Reload Design Methodology Reports and Proposed LAR Re. H. B. Robinson and Shearon Harris Plants (CAC Nos. MF7443 and MF7444) ML15149A3222015-05-29029 May 2015 2014 Harris Annual Assessment Meeting Summary ML15107A4252015-04-17017 April 2015 4/20/2015, Forthcoming Closed Meeting with Duke Energy Progress, Inc. to Discuss Shearon Harris Nuclear Power Plant, Unit 1, Relief Request I3R-15 Revision and Supplement, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspe ML13330B6392013-11-27027 November 2013 Verbal Authorization of Relief Request 13R-13 for Reactor Vessel Closure Head Penetration Nozzle Repair Inservice Inspection Program - Third 10-Year Interval ML13295A3062013-10-22022 October 2013 Meeting Notice with Duke Energy Carolinas, LLC Discuss the Planned Modifications Related to the Fukushima Flood Hazard Reevaluations for the Sites Operated by Duke Energy Carolinas, LLC ML13150A0712013-05-31031 May 2013 Verbal Authorization of Relief Request I3R-11 for Reactor Vessel Closure Head Penetration Nozzel Repair Inservice Inspection Program - Third 10-Year Interval ML13142A4672013-05-22022 May 2013 Special Inspection Charter to Evaluate Harris Reactor Vessel Head Nozzle 49 Flaw Issue ML13120A1372013-05-0202 May 2013 Notice of Forthcoming Meeting with Duke Energy, Inc. Regarding a Non-Conservative Technical Specification Loss-of-Offsite Power Voltage Setpoint License Amendment Request for Shearon Harris, Unit 1 ML13106A3372013-04-17017 April 2013 Notice of Forthcoming Meeting with Duke Energy, Inc. Concerning the Relocation of the Emergency Operating Facilities ML12300A4032012-10-26026 October 2012 11/8/2012 Meeting Notice with Duke Energy to Discuss NRC Order on Mitigation Strategies for Beyond-design-Basis External Events ML12284A4612012-10-12012 October 2012 Forthcoming Meeting Notice with Duke Energy to Discuss NRC Order on Mitigation Strategies for Beyond-Design-Basis External Events ML12261A0992012-09-17017 September 2012 10/2/12 - Notice of Forthcoming Public Conference Call with Duke Energy Carolinas Regarding Shearon Harris Nuclear Plant, Unit 1 ML12249A1702012-09-0606 September 2012 Notice of Forthcoming Conference Call Public Meeting with Duke Energy Regarding the Non Conservative Technical Specifications License Amendment Requests for Shearon Harris Nuclear Plant Unit 1 ML1219805572012-09-0505 September 2012 Close-Out of National Fire Protection Association Standard 805 Frequently Asked Question 12-0062: Updated Final Safety Analysis Report Content ML12144A4402012-05-24024 May 2012 Verbal Authorization of Relief Request I3R-06 for Reactor Vessel Closure Head Penetration Nozzles Repair Inservice Inspection Program - Third 10-Year Interval ML1127300822011-09-30030 September 2011 Request for Additional Information Regarding Measurement Uncertainty Recapture Power Uprate ML1103804972011-02-0808 February 2011 Notice of Forthcoming Preapplication Meeting with Carolina Power & Light Company and Representatives Regarding Shearon Harris Nuclear Plant, Unit 1 ML1024301722010-10-0505 October 2010 Trip Report on Observing the National Fire Protection Association 805 Readiness Self Assessment Performed at the Shearon Harris Nuclear Plant ML1015805092010-06-0808 June 2010 the Nuclear Regulatory Commission Staff Spot-Check Review of North Carolina Eastern Municipal Power Agency'S Ownership Interest of Shearon Harris, Unit 1 and Brunswick, Units 1 and 2 on May 21, 2010 - Finding of No Potential Issues in Bank ML1015901992010-06-0808 June 2010 the Nuclear Regulatory Commission Staff Spot-Check Review of Progress Energy Carolina'S Ownership Interest of H.B. Robinson Steam Electric Plant Unit 2, Brunswick Steam Electric Plant Units 1 and 2 & Shearon Harris Nuclear Power Plant Unit ML1015900142010-06-0808 June 2010 the Nuclear Regulatory Commission Staff Spot-Check Review of North Carolina Eastern Municipal Power Agency'S Ownership Interest of Shearon Harris, Unit 1 and Brunswick, Units 1 and 2 on May 20, 2010 - Finding of No Potential Issues in Bank ML1005702002010-02-26026 February 2010 Notice of Closed Meeting with Progress Energy to Observe a Live Test Fire of Mackenzie River Partner'S Remotely Operated Weapon System at the Shearon Harris Nuclear Plant ML0936406952010-01-0707 January 2010 Notice of Meeting with Carolina Power & Light Company to Discuss Requests for Additional Information Associated with Generic Letter 2004-02 ML0916605042009-06-24024 June 2009 04/21-22/2009 Summary of Category 2 Meeting with Progress Energy Carolinas, Inc., and Duke Energy Carolinas, LLC, to Discuss Topics Involving the License Amendment Requests to Transition Shearon, Unit 1 and Oconee to NFPA 805 ML0909604362009-05-28028 May 2009 Lessons from Regulatory Audits of the Pilot Plants That Are Transitioning to a Fire Protection Licensing Basis Based on the National Fire Protection Association (NFPA) Standard NFPA 805 as Allowed by 10 CFR 5.48 (C) ML0909905052009-04-29029 April 2009 03/20/09 Summary of Site Audit to Support the Review of a License Amendment Request for Shearon Harris to Transition to the National Fire Protection Association Standard 805 Fire Protection Licensing Basis ML0909900182009-04-10010 April 2009 04/21-22/2009, Notice of Meeting with Progress Energy Carolinas, Inc., and Duke Energy Carolinas, LLC, to Discuss Topics Involving the License Amendment Requests to Transition the Shearon, Unit 1 and the Oconee, Units 1, 2 and 3 ML0829501872008-09-0909 September 2008 DHS Shearon Harris Consultation Report Cover Letter ML0814002922008-08-20020 August 2008 Close-out of National Fire Protection Association (NFPA) Standard 805 Frequently Asked Question 07-0032 ML0818302602008-07-0101 July 2008 Meeting Minutes of the ACRS Plant License Renewal Subcommittee Regarding Shearon Harris, May 7, 2008 ML0816901212008-06-17017 June 2008 Forthcoming Closed Meeting with Progress Energy Carolinas, Inc., to Discuss the May 29, 2008, License Amendment Request (LAR) to Transition the Shearon Harris Nuclear Plant, Unit 1 (Harris) to National Fire Protection Association (Nfpa).. ML0808501922008-03-26026 March 2008 Forthcoming Meeting with Cp&L to Discuss an Open Item Related to the License Renewal Review for Shearon Harris Nuclear Power Plant, Unit 1 ML0807400842008-03-14014 March 2008 Draft Regulatory Guide for Comment ML0807203352008-03-0303 March 2008 Comment (7) of Chatham County Board of Commissioners Opposing Generic Environmental Impact Statement (GEIS) for License Renewal of the Shearon Harris Nuclear Power Plant 2024-05-01
[Table view] Category:Probabilistic Risk Assessment
MONTHYEARML18074A0202018-03-20020 March 2018 Fpra FAQ 16-0011 Closure Memo 2018-03-20
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March 20, 2018 MEMORANDUM TO: APLB Files FROM: Greg A. Casto, Chief /RA/
PRA Licensing Branch B Division of Risk Assessment Office of Nuclear Reactor Regulation
SUBJECT:
CLOSE-OUT OF FIRE PROBABILISTIC RISK ASSESSMENT FREQUENTLY ASKED QUESTION 16-0011 ON ALTERNATIVE METHODOLOGY TO NUREG/CR-6850 FOR BULK CABLE TRAY IGNITION CRITERIA
Background
During industry peer reviews and Nuclear Regulatory Commission (NRC) staff review of Fire Probabilistic Risk Assessments (FPRAs) related to license amendment requests (LARs) to implement National Fire Protection Association Performance-Based Standard for Fire Protection for Light-Water Reactor Electric Generating Plants (NFPA 805, 10 CFR 50.48(c)),
methods and approaches different from the accepted methods were encountered. NRC staff, the Nuclear Energy Institute, and representatives from the nuclear industry worked to identify these methods, approaches, and factors in current LARs (including but not limited to NFPA 805 LARs), and to address them through a frequently asked question (FAQ) process. This FAQ process is only one NRC process whereby a new FPRA method can be reviewed or developed.
NUREG/CR-6850, EPRI/NRC-RES Fire PRA Methodology for Nuclear Power Facilities, Final Report, (NUREG/CR-6850) provides general ignition and fire damage criteria for thermoplastic and thermoset electrical cables in the form of a temperature and radiant heat flux damage criteria. These criteria effectively treat ignition and damage as the same; however, fire test data suggest that ignition and functional failure of the circuit do not always occur simultaneously and that more specific criteria are appropriate for the purpose of more realistically estimating vertical fire propagation in a stack of horizontal cable trays during certain fire scenarios at a nuclear power plant.
FPRA FAQ 16-0011, Cable Tray Ignition, (enclosed), updates, in part, the guidance available in Chapters 8, Appendix H, and Appendix R of NUREG/CR-6850. This FAQ provides adjusted ignition criteria for use in determining when conditions are present to initiate vertical fire propagation beyond a single cable tray.
CONTACTS: Brian Metzger, NRR/DRA (301) 415-3972 Greg Casto, NRR/DRA (301) 415-0565
G. Casto 2 March 20, 2018 Discussion and Conclusion The NRC staff and the nuclear industry held a series of public meetings to discuss the resolution of FPRA FAQ 16-0011.
The guidance in this FAQ establishes a new set of generic ignition criteria, 500C and 25 kW/m2, for determining when bulk cable tray ignition occurs such that subsequent vertical fire propagation begins. For instance, once either of the new criteria are reached, it should be assumed that a sufficient amount of energy is being released from a section of cabling to ignite a cable tray located directly above. It is worth noting that the criteria provided in NUREG/CR-6850, including cable damage criteria, still apply for assessing cable damage and fire spread independent of ignition. It is also worth noting that the new criteria provided in this FAQ is not to be used for individual cables or scenarios involving targets other than trays filled with cables.
Lastly, licensees are expected to monitor industry operating experience and fire research efforts for any new information that could affect the applicability of the new criteria provided in this FAQ and take any necessary steps to ensure that their FPRAs represent the as-built, as-operated plant.
The guidance in FPRA FAQ 16-0011 is acceptable for use by licensees.
Enclosure
- 1. FAQ 16-0011 Cable Tray Ignition
G. Casto 3 March 20, 2018
SUBJECT:
CLOSE-OUT OF FIRE PROBABILISTIC RISK ASSESSMENT FREQUENTLY ASKED QUESTION 16-0010 ON ALTERNATIVE METHODOLOGY TO NUREG/CR-6850 FOR MAINTAINING FIRE PROBABALISTIC RISK ASSESSMENT IGNITION FREQUENCIES WEIGHTING FACTORS DISTRIBUTION:
SRosenberg, NRR MSalley, RES RidsNrrDraAplb RidsNrrDraApla RidsNrrDra vka@nei.org ADAMS Package Accession: ML18074A023 ADAMS Memo Accession: ML18074A020 ADAMS Enclosure Accession No.: ML18074A021 OFFICE DRA/APLB DRA/APLB NAME BMetzger GCasto DATE 03 / 19 /18 03 / 20 /18 OFFICIAL RECORD COPY