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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
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Text
August 20, 2008 MEMORANDUM TO: AFPB File FROM: Alexander Klein, Chief /RA/
Fire Protection Branch Division of Risk Assessment Office of Nuclear Reactor Regulation
SUBJECT:
CLOSE-OUT OF NATIONAL FIRE PROTECTION ASSOCIATION STANDARD 805 FREQUENTLY ASKED QUESTION 07-0032, CLARIFICATION OF TITLE 10 OF THE CODE OF FEDERAL REGULATIONS PART 50.48(c), 50.48(a) AND GENERAL DESIGN CRITERION 3 The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed Frequently Asked Question (FAQ) 07-0032, Revision 2. FAQ 07-0032, Revision 2 was proposed by the transition team at the Shearon Harris nuclear plant (the authors) to clarify that satisfying Title 10 of the Code of Federal Regulations Part 50.48(c) (10 CFR 50.48(c)) will satisfy 10 CFR 50.48(a) and General Design Criterion 3 (GDC 3) in 10 CFR Part 50 Appendix A.
The need for this Frequently Asked Question was identified during several National Fire Protection Association (NFPA) 805 Pilot Observation Meetings between the NRC staff and the technical staff of the two NFPA 805 Pilot Plants. The existing industry guidance document developed to assist in NFPA 805 transition, Nuclear Energy Institute document NEI 04-02, Guidance for Implementing a Performance-Based, Risk-Informed Fire Protection Program Under 10 CFR 50.48(c) (NEI 04-02) contains an overview of the new rule in Section 2.1 but does not clearly explain how meeting 10 CFR 50.48(c) satisfies 10 CFR 50.48(a) and GDC 3.
The authors of FAQ 07-0032, Revision 2, included a line by line review of the requirements in 10 CFR 50.48(a) and GDC 3 and compared them to the requirements in National Fire Protection Association Standard 805 (NFPA 805). The authors have documented that all requirements in 10 CFR 50.48(a) and GDC 3 would be met through corresponding requirements in NFPA 805.
Industry Proposal The authors of FAQ 07-0032, Revision 2 proposed revising NEI 04-02, Section 2.2.2, Relationship to Other Fire Protection Requirements, to discuss the relationship between 10 CFR 50.48(a), 10 CFR 50.48(c) and GDC 3.
CONTACT: Harry Barrett, NRR/DRA (301) 415-1402
A. Klein The authors stated that the new rule does not supersede the requirements of GDC 3 or 10 CFR 50.48(a). By implementing a fire protection program that meets the requirements of NFPA 805 in accordance with 10 CFR 50.48(c), the requirements of 10 CFR 50.48(a) and GDC 3 will be met.
NRC Staff Evaluation
The NRC staff (the staff) has evaluated the FAQ 07-0032, Revision 2 proposal with respect to regulatory compliance and technical adequacy.
The proposed additions to NEI 04-02 are consistent with the regulation as well as the explanation provided in the statements of consideration for the final rule. The proposed changes are technically adequate because each of the requirements contained in NFPA 805 meet or exceed the requirements in 10 CFR 50.48(a) and GDC 3. Therefore, the staff finds the proposed changes to NEI 04-02 to be acceptable.
The staff has reviewed the proposed changes to NEI 04-02 as presented in FAQ 07-0032, Revision 2 and finds that nothing in this FAQ would prevent continued endorsement of NEI 04-02. In accordance with RIS 2007-19, the guidance in this FAQ is acceptable for use by licensees in transition. The final endorsement of this FAQ will be addressed by the next revision to Regulatory Guide 1.205.
See the enclosure to this memorandum for a chronological history of this FAQ.
References:
For details regarding this FAQ, please see the following:
- NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition (available through the Public Document Room or NFPA)
A. Klein
- NRC Regulatory Information Summary 2007-19, Process For Communicating Clarifications Of Staff Positions Provided In Regulatory Guide 1.205 Concerning Issues Identified During The Pilot Application Of National Fire Protection Association Standard 805 (ADAMS accession number ML071590227)
Enclosure:
As Stated
ML081400292 NRR-106 OFFICE NRR/DRA/AFPB NRR/DRA/AFPB NRR/DRA/AFPB OGC NAME H Barrett DFrumkin AKlein BJones DATE 06 / 28 /08 06 / 30 /08 07 / 01 /08 08 / 20 /08 FAQ 07-0032 History INITIAL FREQUENTLY ASKED QUESTION FAQ 07-0032 PROPOSAL The National Fire Protection Association (NFPA) 805 Transition Team at the Shearon Harris nuclear plant initiated FAQ 07-0032 and processed it through the Nuclear Energy Institutes NFPA 805 Task Force in order to provide guidance to licensees transitioning to NFPA 805 clarifying that satisfying Title 10 of The Code of Federal Regulations Part 50 (10 CFR 50.48(c) will satisfy 10 CFR 50.48(a) and General Design Criterion 3 (GDC 3).
NRC STAFF RESPONSE TO FAQ 07-0032, REVISION 0 The U.S. Nuclear Regulatory Commission (NRC) staff responded with a comment that the FAQ as written adequately addressed the discussion regarding systems, structures and components (SSCs) important to safety, but did not address the other sections of GDC 3 and 10 CFR 50.48(a). The comment also pointed out that 10 CFR 50.48(a)(1)(iv) has a requirement that the fire protection program plan must outline the plans for fire protection, fire detection and suppression capability, and limitation of fire damage. The language in the regulation does not limit fire damage to only SSCs.
FAQ 07-0032, REVISION 1 The FAQ authors added a comprehensive list of attributes included in GDC 3 and 10 CFR 50.48(a) and indicated how each of those attributes is addressed in the NFPA 805 standard. In addition, revision 1 also removed proposed changes to the License Amendment Request template provided in Appendix H in NEI 04-02.
NRC STAFF RESPONSE TO FAQ 07-0032 The NRC staff identified minor issues with the table listing the requirements in GDC 3 and 10 CFR 50.48(a) and how some of the attributes are addressed in NFPA 805.
FAQ 07-0032, Revision 2 The FAQ authors addressed all the NRC staff comments.
ENCLOSURE
