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Initiation
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- Acceptance, Acceptance, Acceptance, Acceptance
- Supplement, Supplement
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MONTHYEARML0725500632007-08-30030 August 2007 NFPA 805 Transition Pilot Plant FAQ 06-0019, Revision 2 Project stage: Request ML0730605502007-09-0707 September 2007 NFPA 805 Transition Pilot Plant FAQ 07-0040 Project stage: Request ML0727402622007-09-20020 September 2007 NFPA-805 Transition Pilot Plant FAQ 07-0038 Project stage: Request ML0727402482007-09-20020 September 2007 NFPA-805 Transition Pilot Plant FAQ 06-0011, Revision 2 Project stage: Request ML0727402682007-09-20020 September 2007 NFPA-805 Transition Pilot Plant FAQ 07-0039 Project stage: Request ML0727402552007-09-28028 September 2007 NFPA-805 Transition Pilot Plant FAQ 06-0019, Revision 3 Project stage: Request ML0735500232007-11-12012 November 2007 NFPA 805 Transition Pilot Plant FAQ 07-0033, Revision 1 Project stage: Request ML0735100822007-11-12012 November 2007 NFPA 805 Transition Pilot Plant FAQ 06-0025, Revision 3 (Corrected Version) Project stage: Request ML0733200282007-11-26026 November 2007 NFPA 805 Transition Pilot Plant FAQ 06-0012, Revision 5, Determining Manual Actions That Require a Change Evaluation During Transition. Project stage: Request ML0733700252007-12-0303 December 2007 NFPA 805 Transition Pilot Plant FAQ 06-0008, Revision 8, Alternative Method for Fire Protection Engineering Analyses Project stage: Request ML0734001472007-12-0606 December 2007 NFPA 805 Transition Pilot Plant FAQ 06-0025, Revision 3 Project stage: Request ML0735500252007-12-20020 December 2007 NFPA 805 Transition Pilot Plant FAQ 07-0036, Revision 1 Project stage: Request ML0735402622007-12-20020 December 2007 Afpb Staff Response to NFPA 805 Transition Pilot Plant FAQ 07-0035, Revision 0 Project stage: Request ML0807004112008-03-10010 March 2008 NFPA 805 Transition Pilot Plant FAQ 07-0032, Revision 1, Clarification of 10 CFR 50.48(c), 50.48(a), and GDC 3. Project stage: Request ML0809101362008-03-28028 March 2008 NFPA 805 Transition Pilot Plant FAQ 07-0039, Revision 1, Lessons Learned - NEI 04-02 B-2 and B-3 Tables Project stage: Request ML0814300412008-05-22022 May 2008 NFPA 805 Transition Pilot Plant FAQ 07-0040, Revision 2 Project stage: Request HNP-08-061, Request for License Amendment to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants (2001 Edition)2008-05-29029 May 2008 Request for License Amendment to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants (2001 Edition) Project stage: Request ML0820410142008-05-30030 May 2008 Public Version of Enclosures 2 Through 6 of License Amendment Request to Adopt NFPA-805 Project stage: Request 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).. Project stage: Meeting ML0818406962008-07-0707 July 2008 Meeting with Progress Energy Carolinas, Inc. and Duke Energy Carolinas, LLC, to Discuss the 05/29&30/2008, License Amendment Requests to Transition Shearon Harris, Unit 1, and Oconee, Units 1, 2, & 3 to NFPA Standard 805 Project stage: Meeting ML0818905292008-07-11011 July 2008 Summary of Closed Meeting with Progress Energy Carolinas Regarding May 29, 2008, License Amendment Request to Transition the Shearon Harris Nuclear Plant Unit 1, to National Fire Protection Association Standard 805, Performance-Based.... Project stage: Meeting ML0820703912008-07-17017 July 2008 Meeting Handouts from 7/17/08 Public Meeting on the Harris and Oconee LARs to Transition to NFPA-805 Project stage: Meeting ML0820605362008-08-0707 August 2008 Summary of Mtg. with Progress Energy Carolinas, and Duke Energy Carolinas to Discuss the LARs to Transition the Shearon Harris and Oconee Nuclear Plants to National Fire Protection Association Standard NFPA-805 Project stage: Acceptance Review ML0828700162008-09-26026 September 2008 Nc Warn'S Response to Board Notification - Enclosure P-1 - Shearon Harris Nuclear Power Plant, Unit 1 - Acceptance Review NFPA-805 License Amendment Request, September 26, 2008 Project stage: Request ML0827011582008-09-26026 September 2008 Acceptance Review Regarding the License Amendment Request to Transition to NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants. Project stage: Acceptance Review ML0830900742008-11-12012 November 2008 Summary of Category 2 Public Meeting Held to Discuss National Fire Protection Association Standard 805 Pilot Plant Process: Current Lessons Learned from the Pilot License Amendment Request Reviews (TAC Nos. MD8807, MD8832, MD8833, & MD8834) Project stage: Meeting HNP-08-113, Supplement to Request for License Amendment, to Adopt NFPA 805 Performance-Based Standards for Fire Protection for Light Water Reactor Generating Plants (2001 Edition)2008-11-14014 November 2008 Supplement to Request for License Amendment, to Adopt NFPA 805 Performance-Based Standards for Fire Protection for Light Water Reactor Generating Plants (2001 Edition) Project stage: Supplement ML0829601532008-11-17017 November 2008 Summary of Meeting with Progress Energy Carolinas, Inc., to Discuss Shearon Harris Unit 1 National Fire Protection Association Standard 805 License Amendment Request Project stage: Meeting HNP-08-121, Supplement 2 to Request for License Amendment to Adopt NFPA 805 Performance-based Standard for Fire Protection for Light Water Reactor Generating Plants (2001 Edition)2008-12-11011 December 2008 Supplement 2 to Request for License Amendment to Adopt NFPA 805 Performance-based Standard for Fire Protection for Light Water Reactor Generating Plants (2001 Edition) Project stage: Supplement ML0903000302009-01-30030 January 2009 Acceptance Review Regarding Amendment to Adopt National Fire Protection Association 805 Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants, 2001 Edition Project stage: Acceptance Review ML0902903272009-03-10010 March 2009 Regulatory Audit in Support of the License Amendment Request to Implement a Risk-Informed, Performance-Based Fire Protection Program as Allowed by Title 10 of the Code of Federal Regulations, Paragraph 50.48(c) Fire Protection Project stage: Other 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 Project stage: Meeting ML0916002812009-06-11011 June 2009 Notice of Consideration of Issuance of Amendment to Facility Operating License and Opportunity for a Hearing Project stage: Other ML0921707152009-08-0606 August 2009 Request for Additional Information Regarding Amendment to Adopt National Fire Protection Association Standard 805 (NFPA 805), Performance-Based Standard for Fire Protection for Light Water Reactor ... Project stage: RAI HNP-09-084, Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-based Standard for Fire Protection for Light Water Generating Plants.2009-08-13013 August 2009 Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-based Standard for Fire Protection for Light Water Generating Plants. Project stage: Response to RAI HNP-09-086, Second Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-based Standard for Fire Protection for Light Water Reactor...2009-08-28028 August 2009 Second Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-based Standard for Fire Protection for Light Water Reactor... Project stage: Response to RAI HNP-09-094, Third Response to Request for Additional Information License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light Water Reactor....2009-10-0909 October 2009 Third Response to Request for Additional Information License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light Water Reactor.... Project stage: Response to RAI HNP-09-096, Additional Information Re License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants2009-12-16016 December 2009 Additional Information Re License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants Project stage: Request ML1001302542010-01-14014 January 2010 Second Request for Additional Information Regarding the License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plant Project stage: RAI HNP-10-008, Response to Second Request for Additional Information Regarding License Amendment Request to Anfp Association Standard 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants.2010-02-0404 February 2010 Response to Second Request for Additional Information Regarding License Amendment Request to Anfp Association Standard 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants. Project stage: Request ML1006009872010-03-0909 March 2010 Discussion of Clarification Questions Related to the License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance - Based Standard for Fire Protection for Light ... Project stage: Other HNP-10-040, Response to 3rd Round of RAI License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants.2010-04-0505 April 2010 Response to 3rd Round of RAI License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants. Project stage: Request HNP-10-064, Additional Items Related to License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for LWR Generating Plants.2010-06-0909 June 2010 Additional Items Related to License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for LWR Generating Plants. Project stage: Request ML1017506042010-06-28028 June 2010 Redacted - Regarding Adoption of National Fire Protection Association Standard 805 Project stage: Acceptance Review ML1017506022010-06-28028 June 2010 Issuance of Amendment Regarding Adoption of National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants.. Project stage: Approval ML1025108522010-12-28028 December 2010 Corrections of Typographical and Formatting Errors Regarding Amendment No. 133 and the Associated Safety Evaluation Project stage: Approval 2008-07-11
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Category:Letter type:HNP
MONTHYEARHNP-18-050, Request to Extend Reactor Vessel Surveillance Capsule Report Submission Date2018-09-17017 September 2018 Request to Extend Reactor Vessel Surveillance Capsule Report Submission Date HNP-18-004, License Amendment Request to Change Shearon Harris Nuclear Power Plant, Unit 1, Emergency Plan Emergency Action Level Scheme2018-08-13013 August 2018 License Amendment Request to Change Shearon Harris Nuclear Power Plant, Unit 1, Emergency Plan Emergency Action Level Scheme HNP-18-035, Relief Request I3R-18, Alternative Repair and Replacement Testing Requirements for the Containment Building Equipment Hatch Sleeve Weld, Lnservice Inspection Program for Containment, Third Ten-Year Interval2018-06-0404 June 2018 Relief Request I3R-18, Alternative Repair and Replacement Testing Requirements for the Containment Building Equipment Hatch Sleeve Weld, Lnservice Inspection Program for Containment, Third Ten-Year Interval HNP-18-049, Submittal of 1 0 CFR 50.54(q) Evaluation Form of Changes to Procedure EMP-420, Emergency Program Maintenance, Revision 192018-05-0303 May 2018 Submittal of 1 0 CFR 50.54(q) Evaluation Form of Changes to Procedure EMP-420, Emergency Program Maintenance, Revision 19 HNP-18-023, Report of Changes Pursuant to 10 CFR 50.59 and Summary of Commitment Changes2018-05-0202 May 2018 Report of Changes Pursuant to 10 CFR 50.59 and Summary of Commitment Changes HNP-18-042, Annual Environmental (Non-radiological) Operating Report2018-04-30030 April 2018 Annual Environmental (Non-radiological) Operating Report HNP-18-032, Annual Radiological Environmental Operating Report2018-04-25025 April 2018 Annual Radiological Environmental Operating Report HNP-18-031, Annual Radioactive Effluent Release Report2018-04-25025 April 2018 Annual Radioactive Effluent Release Report HNP-18-047, Relief Request I4R-18, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program, Fourth Ten-Year Interval, Non-Proprietary Version of Calculation2018-04-20020 April 2018 Relief Request I4R-18, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program, Fourth Ten-Year Interval, Non-Proprietary Version of Calculation HNP-18-045, Submittal of Relief Request I4R-18, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program, Fourth Ten-Year Interval2018-04-18018 April 2018 Submittal of Relief Request I4R-18, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program, Fourth Ten-Year Interval HNP-18-044, Cycle 22 Core Operating Limits Report, Revision O2018-04-16016 April 2018 Cycle 22 Core Operating Limits Report, Revision O HNP-18-039, Supplement to License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses2018-04-13013 April 2018 Supplement to License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses HNP-18-021, Annual Report in Accordance with Technical Specification 6.9.1.22018-02-19019 February 2018 Annual Report in Accordance with Technical Specification 6.9.1.2 HNP-18-020, Supplement to Response to Request for Additional Information Regarding License Amendment Request for Spent Fuel Storage Pool Criticality Analyses2018-02-16016 February 2018 Supplement to Response to Request for Additional Information Regarding License Amendment Request for Spent Fuel Storage Pool Criticality Analyses HNP-18-019, Cycle 21 Core Operating Limits Report, Revision 12018-02-14014 February 2018 Cycle 21 Core Operating Limits Report, Revision 1 HNP-18-017, CFR 50.54(q) Evaluations2018-02-0505 February 2018 CFR 50.54(q) Evaluations HNP-18-001, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors.2018-02-0101 February 2018 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors. HNP-18-002, Response to Request for Additional Information Regarding a License Amendment Request Proposing Changes to Emergency Diesel Generator Technical Specifications Surveillance Requirements2018-01-22022 January 2018 Response to Request for Additional Information Regarding a License Amendment Request Proposing Changes to Emergency Diesel Generator Technical Specifications Surveillance Requirements HNP-18-003, Response to Request for Additional Information Regarding License Amendment Request for Spent Fuel Storage Pool Criticality Analyses2018-01-18018 January 2018 Response to Request for Additional Information Regarding License Amendment Request for Spent Fuel Storage Pool Criticality Analyses HNP-18-007, License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis - Supplement Regarding De Minimis Penetrations2018-01-11011 January 2018 License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis - Supplement Regarding De Minimis Penetrations HNP-18-006, Submittal of 14-Day Special Report for Accident Radiation Monitors2018-01-0404 January 2018 Submittal of 14-Day Special Report for Accident Radiation Monitors HNP-17-093, Supplement to License Amendment Request Proposing a New Set of Fission Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 32017-11-29029 November 2017 Supplement to License Amendment Request Proposing a New Set of Fission Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3 HNP-17-078, Response to Request for Additional Information Regarding a License Amendment Request Proposing Changes to Emergency Diesel Generator Technical Specifications Surveillance Requirements2017-11-27027 November 2017 Response to Request for Additional Information Regarding a License Amendment Request Proposing Changes to Emergency Diesel Generator Technical Specifications Surveillance Requirements HNP-17-082, Response to Request for Additional Information Regarding License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Limit Detailed In..2017-10-30030 October 2017 Response to Request for Additional Information Regarding License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Limit Detailed In.. HNP-17-084, Response to Request for Additional Information Regarding a License Amendment Request Proposing Changes to Emergency Diesel Generator Technical Specifications Surveillance Requirements2017-10-30030 October 2017 Response to Request for Additional Information Regarding a License Amendment Request Proposing Changes to Emergency Diesel Generator Technical Specifications Surveillance Requirements HNP-17-025, Fourth Interval Lnservice Inspection Plan, Third Interval Containment Lnservice Inspection Plan, and Fourth Interval Lnservice Inspection Pressure Test Plan2017-10-23023 October 2017 Fourth Interval Lnservice Inspection Plan, Third Interval Containment Lnservice Inspection Plan, and Fourth Interval Lnservice Inspection Pressure Test Plan HNP-17-072, License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis2017-10-19019 October 2017 License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis HNP-17-077, License Amendment Request Regarding Rod Control Movable Assemblies Technical Specifications2017-10-10010 October 2017 License Amendment Request Regarding Rod Control Movable Assemblies Technical Specifications HNP-17-076, Supplement to License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106, and Delete Duplicate Reporting Requirements.2017-10-0202 October 2017 Supplement to License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106, and Delete Duplicate Reporting Requirements. HNP-17-073, Supplemental Information for License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses2017-09-14014 September 2017 Supplemental Information for License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses HNP-17-062, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal2017-09-13013 September 2017 Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal HNP-17-061, Supplement to License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses2017-07-20020 July 2017 Supplement to License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses HNP-17-008, License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses2017-06-28028 June 2017 License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses HNP-17-003, License Amendment Request for Emergency Diesel Generator Surveillance Requirements Regarding Voltage and Frequency Limits and the Voltage Limit for Emergency Diesel Generator Load Rejection2017-06-0505 June 2017 License Amendment Request for Emergency Diesel Generator Surveillance Requirements Regarding Voltage and Frequency Limits and the Voltage Limit for Emergency Diesel Generator Load Rejection HNP-17-040, Snubber Program Plan2017-06-0101 June 2017 Snubber Program Plan HNP-17-051, 10 CFR 50.54(q) Evaluation2017-05-24024 May 2017 10 CFR 50.54(q) Evaluation HNP-17-050, Transmittal of 10 CFR 50.54(q) Evaluation for Revision 21 to PEP-250, Activation and Operation of the Joint Information Center2017-05-24024 May 2017 Transmittal of 10 CFR 50.54(q) Evaluation for Revision 21 to PEP-250, Activation and Operation of the Joint Information Center HNP-17-041, Response to Request for Additional Information Regarding License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106, and Delete2017-05-22022 May 2017 Response to Request for Additional Information Regarding License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106, and Delete Du HNP-17-033, License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3, Footnote 112017-05-22022 May 2017 License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3, Footnote 11 HNP-17-049, Transmittal of 10 CFR 50.54(q) Evaluation and Revision 26 to PEP-110, Emergency Classification and Protective Action Recommendations.2017-05-18018 May 2017 Transmittal of 10 CFR 50.54(q) Evaluation and Revision 26 to PEP-110, Emergency Classification and Protective Action Recommendations. HNP-17-047, 10 CFR 50.54(q) Evaluation2017-05-18018 May 2017 10 CFR 50.54(q) Evaluation HNP-17-048, Transmittal of 10 CFR 50.54(q) Evaluation and Revision 28 to PEP-230, Control Room Operations.2017-05-18018 May 2017 Transmittal of 10 CFR 50.54(q) Evaluation and Revision 28 to PEP-230, Control Room Operations. HNP-17-046, 10 CFR 50.54(q) Evaluation2017-05-18018 May 2017 10 CFR 50.54(q) Evaluation HNP-17-024, Annual Environmental (Nonradiological) Operating Report2017-04-28028 April 2017 Annual Environmental (Nonradiological) Operating Report HNP-17-023, Annual Radioactive Effluent Release Report2017-04-28028 April 2017 Annual Radioactive Effluent Release Report HNP-17-034, Response to Request for Additional Information Regarding License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106..2017-04-25025 April 2017 Response to Request for Additional Information Regarding License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106.. HNP-17-035, Request for Pilot Plant Status and Fee Waiver to Implement Tornado Missile Risk Evaluator2017-04-12012 April 2017 Request for Pilot Plant Status and Fee Waiver to Implement Tornado Missile Risk Evaluator HNP-17-045, 10 CFR 50.54(q) Evaluation of Change in Emergency Plan Implementation Procedure PEP-241, Revision 7, Technical Support Center (TSC) Emergency Ventilation System Operation2017-03-30030 March 2017 10 CFR 50.54(q) Evaluation of Change in Emergency Plan Implementation Procedure PEP-241, Revision 7, Technical Support Center (TSC) Emergency Ventilation System Operation HNP-17-014, Annual Report in Accordance with Technical Specifications, Section 6.9.1.22017-02-16016 February 2017 Annual Report in Accordance with Technical Specifications, Section 6.9.1.2 HNP-17-015, Summary of 10 CFR 50.54(q) Evaluation2017-02-15015 February 2017 Summary of 10 CFR 50.54(q) Evaluation 2018-09-17
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Progress Energy Christopher L.Burton Vice President Harris Nuclear Plant Progress Energy Carolinas, Inc.
Serial: HNP-10-064 1JUK 002 10 CFR 50.90 U. S. Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, D.C. 20555-0001 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 ADDITIONAL ITEMS RELATED TO LICENSE AMENDMENT REQUEST TO ADOPT NATIONAL FIRE PROTECTION ASSOCIATION STANDARD 805, "PERFORMANCE-BASED STANDARD FOR FIRE PROTECTION FOR LIGHT WATER REACTOR GENERATING PLANTS" (TAC NO. MD8807)
Reference:
Letter from M. Vaaler, Nuclear Regulatory Commission, to C. L. Burton, "Shearon Harris Nuclear Power Plant, Unit 1 - Additional Items Related to the License Amendment Request to Adopt National Fire Protection Association Standard 805, 'Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants' (TAC NO. MD8807)", dated May 18, 2010 Ladies and Gentlemen:
Harris Nuclear Plant (HNP) has reviewed the revised fire protection license condition and list of items to be completed during the implementation of NFPA 805 at HNP as provided in Enclosures 1 and 2 of the above Reference. In accordance with the guidance in this Reference, Carolina Power & Light Company, doing business as Progress Energy Carolinas, Inc. (PEC) is providing assurance via this formal letter of its commitment to (1) implementing the fire protection license condition as stated and (2) completing the outstanding implementation items within the timeframe specified. to this submittal is the license condition to be included in the revised license for the Shearon Harris Nuclear Power Plant, Unit 1, replacing Renewed Operating License No. NPF-63 Condition 2.F. HNP is cognizant that New Transition License Condition 2.F(3)(b), which specifies that the listed modifications will be implemented by December 31, 2010, incorporates Regulatory Commitment # 3 as provided in Licensee Event Report (LER) 2002-004-09, dated October 28, 2005 (ML053070550). to this submittal contains the associated Regulatory Commitments.
Please refer any questions regarding this submittal to Mr. Dave Corlett, Supervisor -
Licensing/Regulatory Programs, at (919) 362-3137.
I declare under penalty of perjury that the foregoing is true and correct. Executed on JUN 0. 2010 P0. Box 165
+0%oa New Hill, NC 27562 T> 9A9.362.2502 F> 919.362.2095
Serial: HNP-10-064 Page 2 Sincerely, Christopher L. Burton CLB/kms
Enclosures:
- 1. Replacement License Condition 2.F
- 2. List of Regulatory Commitments Cc: Mr. J. D. Austin, NRC Sr. Resident Inspector, HNP Mr. W. L. Cox, III, NC DENR Mr. L. A. Reyes, NRC Regional Administrator, Region II Ms. M. G. Vaaler, NRC Project Manager, HNP
Enclosure 1 to SERIAL: HNP-10-064 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 ADDITIONAL ITEMS RELATED TO LICENSE AMENDMENT REQUEST TO ADOPT NATIONAL FIRE PROTECTION ASSOCIATION STANDARD 805 LICENSE CONDITION The following license condition is included in the revised license for the Shearon Harris Nuclear Power Plant, Unit 1, and will replace Renewed Operating License No. NPF-63 Condition 2.F:
F. Fire Protection Program Carolina Power & Light Company shall implement and maintain in effect all provisions of the approved fire protection program that comply with 10 CFR 50.48(a) and 10 CFR 50.48(c), as specified in the revised license amendment request dated October 9, 2009, supplemented by letters dated February 4, 2010, and April 5, 2010, and approved in the associated safety evaluation dated June XX, 2010. Except where NRC approval for changes or deviations is required by 10 CFR 50.48(c) and NFPA 805, and provided no other regulation, technical specification, license condition or requirement would require prior NRC approval, the licensee may make changes to the fire protection program without prior approval of the Commission if those changes satisfy the provisions set forth in 10 CFR 50.48(a) and 10 CFR 50.48(c), the change does not require a change to a technical specification or a license condition, and the criteria listed below are satisfied.
(1) Risk-Informed Changes that May Be Made Without Prior NRC Approval A risk assessment of the change must demonstrate that the acceptance criteria below are met. The risk assessment approach, methods, and data shall be acceptable to the NRC and shall be appropriate for the nature and scope of the change being evaluated; be based on the as-built, as-operated and maintained plant; and reflect the operating experience at the plant. Acceptable methods to assess the risk of the proposed change may include methods that have been used in the peer-reviewed Fire PRA model, methods that have been approved by the NRC via a plant-specific license amendment or through NRC approval of generic methods specifically for use in NFPA 805 risk assessments, or methods that have been demonstrated to bound the risk impact.
(a) Prior NRC review and approval is not required for changes that clearly result in a decrease in risk. The proposed change must also be consistent with the defense-in-depth philosophy and must maintain sufficient safety margins. The change may be implemented following completion of the plant change evaluation.
(b) Prior NRC review and approval is not required for individual changes that result in a risk increase less than 1x 1OE-7 per year (/yr) for CDF and less than 1 x 1OE-8/yr for LERF. The proposed change must also be consistent with the defense-in-depth philosophy and must maintain sufficient safety margins. The change may be implemented following completion of the plant change evaluation.
Page 1 of 3
Enclosure 1 to SERIAL: HNP-10-064 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 ADDITIONAL ITEMS RELATED TO LICENSE AMENDMENT REQUEST TO ADOPT NATIONAL FIRE PROTECTION ASSOCIATION STANDARD 805 LICENSE CONDITION (2) Other Criteria for Changes that May Be Made Without Prior NRC Approval (a) Changes to NFPA 805 Chapter 3, Fundamental Fire Protection Program Prior NRC review and approval is not required for changes to the NFPA 805 Chapter 3 fundamental fire protection program elements and design requirements for which an engineering evaluation demonstrates that the alternative to the Chapter 3 element is functionally equivalent or adequate for the hazard. The licensee may use an engineering evaluation to demonstrate that a change to an NFPA 805 Chapter 3 element is functionally equivalent to the corresponding technical requirement. A qualified fire protection engineer shall perform the engineering evaluation and conclude that the change has not affected the functionality of the component, system, procedure, or physical arrangement, using a relevant technical requirement or standard.
The licensee may use an engineering evaluation to demonstrate that changes to certain NFPA 805 Chapter 3 elements are acceptable because the alternative is "adequate for the hazard." Prior NRC review and approval would not be required for alternatives to four specific sections of NFPA 805 Chapter 3, for which an engineering evaluation demonstrates that the alternative to the Chapter 3 element is adequate for the hazard. A qualified fire protection engineer shall perform the engineering evaluation and conclude that the change has not affected the functionality of the component, system, procedure, or physical arrangement, using a relevant technical requirement or standard.
The four specific sections of NFPA 805 Chapter 3 are as follows:
- Fire Alarm and Detection Systems (Section 3.8);
- Automatic and Manual Water-Based Fire Suppression Systems (Section 3.9);
- Gaseous Fire Suppression Systems (Section 3.10); and
- Passive Fire Protection Features (Section 3.11).
(b) Fire Protection Program Changes that Have No More than Minimal Risk Impact Prior NRC review and approval is not required for changes to the licensee's fire protection program that have been demonstrated to have no more than a minimal risk impact. The licensee may use its screening process, as approved in the NRC safety evaluation dated June XX, 2010, to determine that certain fire protection program changes meet the minimal risk criterion. The licensee shall in all cases ensure that fire Page 2 of 3
I, Enclosure Ito SERIAL: HNP-10-064 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 ADDITIONAL ITEMS RELATED TO LICENSE AMENDMENT REQUEST TO ADOPT NATIONAL FIRE PROTECTION ASSOCIATION STANDARD 805 LICENSE CONDITION protection defense-in-depth and safety margins are maintained when changes are made to the fire protection program.
r (c) Unless item (2)(b) above is met, risk-informed changes to the licensee's fire protection program which involve fire areas that credit incipient detection may not be made without prior NRC review and approval until the Harris Fire PRA model has been modified to incorporate an NRC-accepted method for modeling incipient detection.
(3) Transition License Conditions (a) Before achieving full compliance with 10 CFR 50.48(c), as specified by transition license condition (3)(b) below, risk-informed changes to the licensee's fire protection program may not be made without prior NRC review and approval unless the change has been demonstrated to have no more than a minimal risk impact, as described in item (2)(b) above.
(b) The licensee shall implement the following modifications to its facility in order to complete the transition to full compliance with 10 CFR 50.48(c) by December 31, 2010 (note that each modification is listed by Engineering Change (EC) Number, as described in Attachment S of the Shearon Harris NFPA 805 License Amendment Request Transition Report, and outlined in Table 2.8.1-2 of the associated NRC safety evaluation):
- EC 71147 (c) The licensee shall maintain appropriate compensatory measures in place until completion of the modifications delineated above.
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Enclosure 2 to SERIAL: HNP-10-064 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 ADDITIONAL ITEMS RELATED TO LICENSE AMENDMENT REQUEST TO ADOPT NATIONAL FIRE PROTECTION ASSOCIATION STANDARD 805 LIST OF REGULATORY COMMITMENTS The actions in this document committed to by Progress Energy Carolinas, Inc. (PEC) regarding License Amendment Request to Adopt National Fire Protection Association Standard 805, "Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants" are identified in the following table. Statements in this submittal, with the exception of those in the table below, are provided for information purposes and are not considered commitments. Please direct any questions regarding this document or any associated regulatory commitments to the Supervisor, Licensing/Regulatory Affairs.
Item Commitment Completion Date 1 The licensee stated that license amendment request (LAR) Table B-2, "Nuclear Safety Capability Assessment," refers to the appropriate circuit coordination studies, and that, with the No later than 180 days after exception of backfeed, all other non-power operation (NPO) the issuance date of the NRC concerns are bounded by the safe shutdown analysis. Safety Evaluation The updating / completion of the coordination study for the backfeed configuration is an outstanding item.
2 Providing additional procedural guidance related to residual heat No later than 180 days after removal flow control recovery actions is an outstanding item. the issuance date of the NRC Safety Evaluation 3 Providing procedural changes to address the 20 generic pinch No later than 180 days after points identified during the NPO review is an outstanding item. the issuance date of the NRC Safety Evaluation 4 Providing procedural changes to address potential spurious valve No later than 180 days after operations identified during the NPO review is an outstanding the issuance date of the NRC item. Safety Evaluation 5 Completion of the NFPA 805 Monitoring Program at HNP is an No later than 180 days after outstanding item. the issuance date of the NRC Safety Evaluation Successful completion/implementation of the monitoring program includes:
0 defining availability, reliability, and performance parameters to be measured for each performance monitoring group
- identifying action levels for availability, reliability, and performance parameters 0 identifying corrective actions to be taken when action levels have been exceeded Page 1 of 4
Enclosure 2 to SERIAL: HNP-10-064 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 ADDITIONAL ITEMS RELATED TO LICENSE AMENDMENT REQUEST TO ADOPT NATIONAL FIRE PROTECTION ASSOCIATION STANDARD 805 LIST OF REGULATORY COMMITMENTS Item Commitment Completion Date 6 Completion of the necessary changes to the HNP Fire Protection No later than 180 days after Program Manual is an outstanding item. the issuance date of the NRC Safety Evaluation 7 Revision of post-transition processes and procedures to include No later than 180 days after NFPA 805 requirements for verification and validation is an the issuance date of the NRC outstanding item. Safety Evaluation 8 Revision of post-transition processes and procedures to include No later than 180 days after NFPA 805 requirements for limitations of use is an outstanding the issuance date of the NRC item. Safety Evaluation 9 The licensee stated that a fire modeling qualification and training No later than 180 days after program would be developed to ensure that personnel performing the issuance date of the NRC future modeling activities will meet the requirements for Safety Evaluation qualification of use identified in NFPA 805, Section 2.7.3.4.
The establishment of this fire modeling qualification program and associated training is an outstanding item.
10 Revision of post-transition processes and procedures to include No later than 180 days after NFPA 805 requirements for uncertainty analyses is an the issuance date of the NRC outstanding item. Safety Evaluation 11 Expansion of the Fire Protection Quality Assurance (QA) Program No later than 180 days after to include systems in the power block that were not previously the issuance date of the NRC included in the scope of the QA Program, but which are required Safety Evaluation by NFPA 805 Chapter 4, is an outstanding item.
Specifically, the addition to the QA Program of certain fire protection and safe shutdown systems in the waste processing building, fuel handling building, and the turbine building that are required by NFPA 805 Chapter 4, as identified in LAR Tables 4-8-1 and 4-8-2.
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Enclosure 2 to SERIAL: HNP-10-064 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 ADDITIONAL ITEMS RELATED TO LICENSE AMENDMENT REQUEST TO ADOPT NATIONAL FIRE PROTECTION ASSOCIATION STANDARD 805 LIST OF REGULATORY COMMITMENTS Item Commitment Completion Date 12 The licensee stated that during the implementation of the NFPA No later than 180 days after 805 licensing basis, performance-based surveillance frequencies the issuance date of the NRC will be established as described in Electric Power Research Safety Evaluation Institute (EPRI) Technical Report (TR) 1006756, "Fire Protection Surveillance Optimization and Maintenance Guide for Fire Protection Systems and Features."
The performance-based surveillance frequencies will be evaluated in calculation HNP-M/BMRK-0015.
Establishment of the appropriate performance-based surveillance frequency process is an outstanding item.
13 Appropriate modification of plant procedures to meet the No later than 180 days after requirements of the NFPA 805 Chapter 3 element (3.3.10) the issuance date of the NRC regarding hot pipes and surfaces is an outstanding item. Safety Evaluation 14 The development and implementation of an outside yard pre-fire No later than 180 days after plan to address radioactive materials areas and Sea-Land type the issuance date of the NRC container storage is an outstanding item. Safety Evaluation 15 Completion of the revisions to calculation HNP-M/MECH-1127 No later than 180 days after and other affected fire safety analysis calculations to clearly state the issuance date of the NRC how the delta risks were determined is an outstanding item. Safety Evaluation 16 Completion of the revisions to calculation HNP-M/MECH-1 124 to No later than 180 days after incorporate the revised change evaluations documenting that the issuance date of the NRC conduit 14449T and cable 0153E are not within the zone of Safety Evaluation influence (ZOI) of a significant ignition source once the very early warning fire detection system (VEWFDS) is installed is an outstanding item.
17 Completion of the updates to the appropriate change evaluation in No later than 180 days after order to address the relationship of cables 0955C and 0970E to the issuance date of the NRC the ignition source ZOIs in Fire Area 1-A-BAL-B is an outstanding Safety Evaluation item.
18 Completion of the updates to the appropriate change evaluation in No later than 180 days after order to document that cable 2608C is not within the ZOI of a the issuance date of the NRC significant ignition source, as well as revising the compliance Safety Evaluation strategy and associated operator procedure, is an outstanding item.
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Enclosure 2 to SERIAL: HNP-10-064 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 ADDITIONAL ITEMS RELATED TO LICENSE AMENDMENT REQUEST TO ADOPT NATIONAL FIRE PROTECTION ASSOCIATION STANDARD 805' LIST OF REGULATORY COMMITMENTS item ! Commitment Completion Date 19 Completion of the updates to the appropriate change evaluation in No later than 180 days after order to document that cable 0245B is not within the ZOI of a the issuance date of the NRC significant ignition source is an outstanding item. Safety Evaluation 20 Completion of the updates to the appropriate change evaluation No later than 180 days after for Fire Area 1-A-BAL-B in order to document that the new the issuance date of the NRC configuration (i.e., installation of fire rated Meggit TM cable and Safety Evaluation associated analyses, as well as the commitment to install an alternate seal injection system) provides adequate defense-in-depth and safety margin is an outstanding item.
21 Completion of the updates to the appropriate change evaluation in No later than 180 days after order to document that cable 0270C is not within the ZOI of a the issuance date of the NRC significant ignition source is an outstanding item. Safety Evaluation 22 Completion of the updates to the appropriate change evaluation in No later than 180 days after order to document that cable 0153E is not within the ZOI of a the issuance date of the NRC significant ignition source is an outstanding item. Safety Evaluation 23 Since EC 48007 is closed, removing credit for the ionization No later than 180 days after detection system in Fire Zone 5-F-2-FPV1 and Fire Zone 5-F the issuance date of the NRC FPV2 will be reflected in calculation HNP-M/MECH-1188. Safety Evaluation Completion of the revisions to this calculation is an outstanding item.
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