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Category:- No Document Type Applies
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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Text
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 interpretation (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 interpretation or new guidance:
Reg. Guide 1.205, Risk informed. Performance-Based Fire Protection for Existing Light-Water Nuclear Power Plants, section 3.2.6 Cumulative 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, but 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 offsets 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 insights 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 considered 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 attributes 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 risk 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 program 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 equipment 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, emergency 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 plant 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 are 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 reliability 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 not in the fire SSA and the associated PSA revision is a plant change and as such would require the NRC pre-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 inclusion 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 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 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, emergency or off-normal procedures. Updates of 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.
The attached figure provides a visual explanation of the difference between FPP-related and not FPP-related.
All products to be developed and controlled by existing approved plant procedures:
Thermal Thermal Hydraulics - Engineering Changes Hydraulics Fire Modeling Fire Modeling - Calculations (compliance) (scenarios) (system success - Software (address sub-HRA timing - Databases cooling, etc.)
CDF/LERF)
Shared Database Information:
- Fire Compartment Data
- Ignition Source Data
- Component Scoping
- Cable/Circuit Routing PRA - FHA data Risk/Scoping Relationships - Fire Scenario Data FP Program (evaluate for impacts)
(SSA / FHA / +)
Mitigation Systems Models Risk/Scoping Examples:
- Compartment Risk Ranking Ign-Source/Impact Info - Component Importances Database Fires Internal Events Change HRA Timing Info - HRA Importances FP Program Plant Changes Impacted?
Implemented Delta CDF for change PRA Plant Changes NFPA-805 change process Impacted?
PRA Eval Request (includes non-power risk considerations)
Industry Standards and Related Guidance:
Change Log Non-Safety-Related Augmented Quality
- ASME RA-Sb-2005 (technical adequacy - ANS 58.23 (technical adequacy based on Industry - NUREG/CR-6850 controlled by Corp. QA Standards with - NEI 04-02 Manual and Site Peer Reviews)
Committments)
Progress Energy Fire PRA /
Fire Protection Program Interface June 19, 2006
