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MONTHYEARML22314A0752022-11-10010 November 2022 2B - Exam Administrative Items - Normal Release ML22034A3992022-02-16016 February 2022 Enclosure 1 - IP 71130.03 Cy 2021 - IR 8 Baseline Inspection Completion ML22034A3952022-02-16016 February 2022 Enclosure 3 - IP 96001 CY2021 - IR 8 Baseline Inspection Completion ML22034A3972022-02-16016 February 2022 Enclosure 2 - IP 92707 CY2021 - IR 8 Baseline Inspection Completion ML18338A0882018-12-0404 December 2018 Attachment FormerFAQResponses_11302018 ML18180A2602018-06-29029 June 2018 NFPA 805 FAQ 10-0059 - NFPA 805 Monitoring ML18073A3582018-03-15015 March 2018 NRC Staff Comments FAQ 18-0015 ML17235B1482017-08-23023 August 2017 U.S. Nuclear Regulatory Commission - Tornado Missile Risk Evaluator (TMRE) Methodology Topics and Methodology Feedback ML16315A2892016-11-10010 November 2016 Attachment 5 EPRI RETRAN-3D Computer Code Manuals, NP-7450(A) RA-16-003, Attachment 5 EPRI RETRAN-3D Computer Code Manuals, NP-7450(A)2016-11-10010 November 2016 Attachment 5 EPRI RETRAN-3D Computer Code Manuals, NP-7450(A) ML18039A8562016-06-0202 June 2016 Fpra FAQ 16-0011 - Cable Tray Ignition - Draft ML14191B2622014-07-10010 July 2014 NFPA 805 Transition FAQ 14-0070, Revision 0 ML13170A3282013-06-13013 June 2013 Special Inspection Question & Answers ML1214300352012-05-21021 May 2012 NFPA 805 Transition FAQ 12-0062, Revision 1 ML12056A0522012-03-12012 March 2012 Enclosure 6 - List of Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status ML1204105892012-02-10010 February 2012 NFPA 805 Transition FAQ 10-0059, Revision 5 ML1204105852012-02-10010 February 2012 NRC Staff Response to NFPA 805 Transition FAQ 10-0059, Revision 4 ML1203201932012-02-0101 February 2012 NFPA 805 Transition FAQ 10-0059, Revision 4 ML1202603842012-01-13013 January 2012 FAQ Revision NFPA 805 Monitoring ML1201903132012-01-13013 January 2012 NFPA 805 Transition FAQ 10-0059, Rev 3 ML1202603722012-01-13013 January 2012 NFPA 805 Monitoring ML1202604252012-01-13013 January 2012 FAQ-1 - NFPA 805 Monitoring ML1202604402012-01-13013 January 2012 FAQ - NFPA 805 Monitoring ML1128600532011-09-30030 September 2011 NRC Staff Comments on FAQ 59R2 ML1127304102011-09-30030 September 2011 NRC Staff Response to NFPA 805 Transition FAQ 10-0059, Revision 2 RA-11-025, Enclosure 1, Attachment 2 - Duke Energy Corporation and Progress Energy, Inc. Organization Charts Post Merger2011-09-0202 September 2011 Enclosure 1, Attachment 2 - Duke Energy Corporation and Progress Energy, Inc. Organization Charts Post Merger ML1123401522011-08-19019 August 2011 NFPA 805 Transition FAQ 10-0059, Rev 2 ML1111804812011-04-21021 April 2011 NFPA 805 Transition FAQ 10-0059, Rev 1 ML1109105082011-03-31031 March 2011 NRC Staff Response to NFPA 805 Transition FAQ 10-0059, Revision 0 (Part 2) ML0933507512010-01-14014 January 2010 Temporary Instruction 2515/180, Managing Fatigue ML0916101892009-06-0303 June 2009 NFPA 805 Transition Pilot Plant FAQ 07-0035, Revision 2, Bus Duct Counting Guidance for High Energy Arcing Faults ML0909905112009-04-29029 April 2009 Enclosure 1: Shearon Harris Regulatory Audit Participants ML1020301612009-04-12012 April 2009 Tritium Concern Talking Points ML1019402162009-04-12012 April 2009 Offsite Notification to State/Local Agencies Regarding Tritium Release Onsite - EN 44951 ML0909305002009-04-0303 April 2009 Afpb Staff Response to NFPA 805 Transition Pilot Plant FAQ 07-0035, Revision 1 ML1020301722009-04-0101 April 2009 Tritium Questions and Answers ML0908500122009-03-26026 March 2009 NFPA 805 Transition Pilot Plant FAQ 07-0035, Revision 1, Bus Duct Counting Guidance for High Energy Arching Faults ML0902902182009-01-22022 January 2009 NFPA 805 Transition Pilot Plant FAQ 07-0030 ML1019402762008-12-0202 December 2008 Nuclear Condition Report for Tritium in Groundwater NEI 04-02, NFPA 805 Transition Pilot Plant FAQ 07-0039, Revision 2, Lessons Learned - NEI 04-02 B-2 Table2008-09-12012 September 2008 NFPA 805 Transition Pilot Plant FAQ 07-0039, Revision 2, Lessons Learned - NEI 04-02 B-2 Table ML0825904662008-09-12012 September 2008 NFPA 805 Transition Pilot Plant FAQ 07-0039, Revision 2, Lessons Learned - NEI 04-02 B-2 Table ML0914201382008-09-0909 September 2008 NFPA 805 Transition Pilot Plant FAQ 07-0039, Revision 2 - Clean Version ML0821000342008-07-24024 July 2008 NFPA 805 Transition Pilot Plant FAQ 07-0038, Revision 1 ML0813006972008-05-0909 May 2008 NFPA 805 Transition Pilot Plant FAQ 07-0032, Revision 2 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 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. ML0807001572008-03-10010 March 2008 NFPA 805 Transition Pilot Plant FAQ 06-0025, Revision 5 ML0806704192008-03-0707 March 2008 CDBI Findings ML0735500252007-12-20020 December 2007 NFPA 805 Transition Pilot Plant FAQ 07-0036, Revision 1 ML0735500212007-12-20020 December 2007 NFPA 805 Transition Pilot Plant FAQ 06-0025, Revision 4 2022-02-16
[Table view] Category:Graphics incl Charts and Tables
MONTHYEARRA-20-0263, Duke Energy Corp. - Request to Use Provision of Later Edition and Addenda of ASME Boiler and Pressure Vessel Code, Section XI for Repair/Replacement Activities in Accordance with 10 CFR 50.55a(g)(4)(iv)2020-09-16016 September 2020 Duke Energy Corp. - Request to Use Provision of Later Edition and Addenda of ASME Boiler and Pressure Vessel Code, Section XI for Repair/Replacement Activities in Accordance with 10 CFR 50.55a(g)(4)(iv) ML16056A1392016-03-11011 March 2016 Correction to the U.S. Nuclear Regulatory Commission Analysis of Licensees' Decommissioning Funding Status Reports HNP-15-043, Response to Request for Additional Information 4 Regarding License Amendment Request to Revise Technical Specification Table 3.3-4 Loss of Offsite Power 6.9 Kv Emergency Undervoltage Primary Setpoints2015-05-13013 May 2015 Response to Request for Additional Information #4 Regarding License Amendment Request to Revise Technical Specification Table 3.3-4 Loss of Offsite Power 6.9 Kv Emergency Undervoltage Primary Setpoints RA-13-012, Capability to Perform Multi-Unit Dose Assessment2013-06-26026 June 2013 Capability to Perform Multi-Unit Dose Assessment ML1020401472010-07-22022 July 2010 NFPA 805 Pilot License Amendment Request Review Schedule Update, July 2010 ML1020301682010-07-0707 July 2010 North Carolina Split Sample Results ML1020301692010-07-0707 July 2010 Photos ML0932400582009-11-19019 November 2009 NFPA 805 Pilot License Amendment Request Review and Infrastructure Update, November, 2009 ML0917603592009-06-25025 June 2009 NFPA 805 Pilot License Amendment Request Review and Infrastructure Update, June 2009 ML0914201292009-05-21021 May 2009 NFPA 805 Pilot License Amendment Request Review and Infrastructure Update, May 2009 ML0909905232009-04-29029 April 2009 Enclosure 2: Shearon Harris Regulatory Audit - Documents Reviewed ML0908403602009-03-25025 March 2009 NFPA 805 Pilot License Amendment Request Review and Infrastructure Update, March, 2009, Revised ML0834001812008-12-0404 December 2008 NFPA 805 Pilot License Amendment Request Review and Infrastructure Update ML0812003342008-04-17017 April 2008 NFPA 805 Transition Pilot Plant FAQ Log - April 2008 ML0729200822007-10-19019 October 2007 Index of References - Shearon Harris SEIS License Renewal ML0728203072007-10-11011 October 2007 Electronic Distribtion Initiative Letter, Licensee List, Electronic Distribution Input Information, Division Plant Mailing Lists ML0727801202007-08-0606 August 2007 August 2007 - Transition to National Fire Protection Association (NFPA) 805 - Fire Pra/Fire Protection Program Interface - Progress Energy - Briefing Materials/Meeting Handouts ML0727801242007-07-17017 July 2007 August 2007 - Transition to National Fire Protection Association (NFPA) 805 - Post Transition Documentation - Progress Energy - Briefing Materials/Meeting Handouts ML0727803252007-07-16016 July 2007 August 2007 - Transition to National Fire Protection Association (NFPA) 805 - Change Evaluation/Deficiency Resolution - 8/9/07 Slides - Progress Energy - Briefing Materials/Meeting Handouts ML0727801182007-07-16016 July 2007 August 2007 - Transition to National Fire Protection Association (NFPA) 805 - Change Evaluations/Deficiency Resolution - 8/6/07 Slides - Briefing Materials/Meeting Handouts ML0727801162007-06-0505 June 2007 August 2007 - Transition to National Fire Protection Association (NFPA) 805 - Harris Nuclear Plant Change Evaluation Development - Briefing Materials/Meeting Handouts ML0623500952006-07-21021 July 2006 NFPA-805 Transition Pilot Plant FAQ 06-0005 ML18230A4841979-06-12012 June 1979 Transmitting Affidavit of J. A. Jones, Marked for Identification as Applicant Exhibit Pp, & Revisions to Applicant'S Proposed Findings of Fact & Conclusion of Law in Form of Supplemental Initial Decision (Construction Permits) ML18230A5241979-01-23023 January 1979 Applicant'S Response to Conservation Council of North Carolina and Wake Environment, Inc.'S Motion to Remand to Licensing Board for Further Hearings ML18230A2141977-09-28028 September 1977 Transmitting Cost Estimates for Revised Cooling Tower Blowdown System, Letter Advising Cost Will Be Increased by Approximately $6.500,000 as a Result of Modifications to System ML18230B0281977-09-23023 September 1977 List of Carolina Power & Light Company (Cp&L) Equipment on Line as of 1977, and for the Period 1978-1990, a List of Equipment to Be Added and Subtracted from the CP&L System for Each Year ML18230A0881976-09-20020 September 1976 as Discussed, Letter Transmitting Information Regarding Containment Structure Load Combination, Containment Internal Structure, Seismic Category I Structure, Index to Positions & Regulatory Guides ML18230A9381975-01-28028 January 1975 Figure P1-1, Geologic Time in Perspective 2020-09-16
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FAQ TEMPLATE Plant: Harris Nuclear Plant (HNP) FAQ # 06-0005 Submittal Date: 07-21-06 Licensee Contact: Jeff Ertman Tele/email 919-546-3681 NRC Contact: Tele/email Distribution: Check all that apply (NEI Internal Use)
FPWG RIRWG NSSS OG X NFPA 805 TF
Subject:
Interpretation of guidance?
Yes Proposed new guidance not in NEI 04-02?
Yes Details: NEI 04-02 Guidance needing interp retation (include section, paragraph number, and line number):
Not currently in NEI 04-02 This is to address Parking Lot open items #19 and #23 Circumstances requiring guidance in terpretation or new guidance:
Reg. Guide 1.205, Risk informed. Performance-Based Fire Protection for Existing Light-Water Nuclear Power Plants, section 3.2.6 Cumula tive Risk of Changes, states that "Post-transition risk reductions for plant changes that are not related to the Fire Protection Program (FPP) may be used to offset the risk increases attributable to FPP-related changes in accordance with Section 2.1.2 of RG 1.174, bu t must be pre-approved by the NRC as required by the standard fire protection license condition. Risk reductions for changes related to the FPP may be used as offs ets without pre-approval by the NRC."
This guidance provides no insight as to what could be considered a FPP-related change or not. Since failure to obtain NRC pre-approval for using risk reductions from a non-FPP related change would be a violation, there should be some guidance as to what is considered a FPP-related change when NFPA-805 is implemented.
The implementation of FPP changes using risk in sights as one of the inputs for determining the acceptability requires a fire PSA. This results in a question as to whether changes in the fire PSA would be considered a FPP-related change.
Detail contentious points if licensee and NRC have not reached agreement The areas where agreement is required:
- 1. Reg Guide 1.205 requires NRC pre-approval post transition when using risk reductions not related to the FPP. The FPP program post transition needs to be clearly defined as to what
changes are FPP-related and what are not FPP-related.
- 2. Additionally it needs to be clarified as to what is considered a plant change when using the PSA to determine the importance of FPP-related changes.
- 3. Whether changes in the fire PSA are consider ed a plant change or a FPP-related change. Potentially relevant existing FAQ numbers:
None Response Section Proposed Resolution of FAQ and the basis for the proposal:
- 1. The FPP-related items post transition would be all of the FPP attributes required by Chapter 3 of NFPA 805 and those other FPP attr ibutes used in Chapter 4. Examples include the fire detection, suppression, fire barriers and Electrical Raceway Fire Barrier Systems (ERFBS) wrap etc that are credited in reducing the ri sk of a fire. It would also include those fire protection programs such as fire brigade training or transient combustible control. It should also include the specific plant equipment, and fire procedures that are credited in the licensee fire safe shutdown analysis.
Basis:
These FPP attributes are part of the fire progra m licensing basis and are identified as such in the NFPA 805 License Amendment Request (LAR). What is not considered as FPP-related is the PSA model itself, which includes the documentation, data elements and associated logic. Additionally any plant equipmen t or procedures that is used in the fire PSA or the underlining Level I and Level II PSA, but is not specifically included as part of the safe shutdown analysis are not considered FPP-related. Some of these plant components or procedures could be used to reduce plant fire risk but are not included in the safe shutdown analysis. This provides a defined scope for FPP-related.
- 2. The term plant change is defined as a change to the physical plant systems structures or components (SSC) or plant operating, em ergency or off-normal procedures.
Basis:
The changes to SSC that alter the facility or plant operating procedures are subject to 10 CFR 50.59 and thus easily understood as a plan t change. With the scope of what is considered a FPP-related change defined, then changes that are not FPP-related, but offset the fire risk increase ar e also easily understood.
- 3. Changes in the fire PSA and the underlining Level I and Level II PSA are not FPP-related changes and also are not considered a plant change.
Basis: The PSA itself (data, logic, supporting documentation and analysis) is built to reflect the facility as designed and operated. Thus a change to the PSA itself cannot be a change to the SSC or plant procedures and is not a FPP related change. As an example of potential changes in is the fire PSA would be equipment reliab ility rates or changing the PSA logic such that only one of two ventilation fans are required to allow the supported equipment to perform its function. Plant changes, such as adding an additional high pressure injection pump to the facility that is no t in the fire SSA and the associated PSA revision is a plant change and as such would require the NRC pr e-approval per the requirements of RG1.205, if used to offset a FPP-related change with an associated risk increase.
If appropriate, provide proposed rewording of guidance for inclusi on in next revision.
The FPP-related items post transition would be all of the FPP attributes required by Chapter 3 of NFPA 805 and those other FPP attributes used in Chapter 4. Examples include the fire detection, suppression, fire barriers and ERFBS etc that are credited in reducing the risk of a fire. It would also include those fire protectio n programs such as fire brigade training or transient combustible control. It should also include the specific plant equipment, and fire procedures that are credited in the licensee safe shutdown analysis.
Plant Change is defined as: The term plant change is defined as a change to the physical plant systems structures or components (SSC) or plant operating, emer gency or off-normal procedures. Updates of the fire PSA and th e underlining Level I and Level II PSA are not FPP-related changes and also are not considered a plant change.
The attached figure provides a visual explan ation of the difference between FPP-related and not FPP-related.
FP Program(SSA / FHA / +)NFPA-805 change process(includes non-power risk considerations)Augmented Quality(technical adequacycontrolled by Corp. QAManual and SiteCommittments)Non-Safety-Related(technical adequacybased on IndustryStandards withPeer Reviews)ThermalHydraulics(address sub-cooling, etc.)ThermalHydraulics(system successHRA timingCDF/LERF)DatabaseAll products to be developed and controlled by existing approved plant procedures:- Engineering Changes- Calculations- Software
- DatabasesShared Database Information:- Fire Compartment Data- Ignition Source Data
- Component Scoping
- Cable/Circuit Routing
- FHA data
- Fire Scenario DataIndustry Standards and Related Guidance:- ASME RA-Sb-2005- ANS 58.23
- NUREG/CR-6850
- NEI 04-02Fire Modeling(compliance)Plant ChangesPlant ChangesIgn-Source/Impact InfoHRA Timing InfoChange LogDelta CDF for changePRA Eval RequestFP ProgramImpacted?ChangeImplementedPRAImpacted?PRAMitigation Systems ModelsFiresInternal EventsFire Modeling(scenarios)Progress Energy Fire PRA /Fire Protection Program InterfaceJune 19, 2006Risk/Scoping Relationships(evaluate for impacts)Risk/Scoping Examples:- Compartment Risk Ranking- Component Importances
- HRA Importances