Letter Sequence Meeting |
|---|
|
|
MONTHYEARML15202A4752015-09-24024 September 2015
Summary of Meeting with Duke Energy Progress, Inc. to Discuss Shearon Harris Nuclear Power Plant, Unit 1, Proposed License Amendment Request Regarding Technical Specifications for the Pressurizer and Main Steam Line Safety Valves (MF6233)
Project stage: Meeting
2015-09-24
[Table View] |
|
|---|
Category:Meeting Summary
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
ML24011A1652024-02-12012 February 2024
December 11, 2023, Summary of Meeting with Duke Energy to Discuss a Shearon Harris Nuclear Power Plant, Unit 1 Planned Exemption Request Related to Turbine Control System and Reactor Protection System Circuitry
ML23157A3202023-06-26026 June 2023
Summary of April 26, 2023, Meeting with Duke Energy to Discuss a Shearon Harris Nuclear Power Plant, Unit 1 Planned License Amendment Request Related to Turbine Control System and Reactor Protection System Circuitry
ML23151A1232023-05-31031 May 2023
Public Meeting Summary - 2022 Annual Assessment Meeting Regarding Shearon Harris Nuclear Plant
ML22167A1852022-06-30030 June 2022
Summary of June 6, 2022, Meeting with Duke Energy to Discuss Shearon Harris Nuclear Power Plant, Unit 1 Closeout of Generic Safety Issue (GSI) 191
ML22129A0062022-05-10010 May 2022
Summary of April 20, 2022, Meeting with Duke Energy Progress, LLC, to Discuss Proposed License Amendment Request to Revise Reactor Coolant System Pressure Isolation Valve Operational Leakage Surveillance Requirement Frequency (L-2022-LRM 00
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
ML21341A5542021-12-29029 December 2021
Summary of November 29, 2021, Meeting with Duke Energy Progress, LLC and Duke Energy Carolinas, LLC to Discuss a Planned License Amendment Request to Relocate
ML21172A2672021-08-13013 August 2021
Regulatory Audit Summary Related to the Review of LAR to Revise 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors, Categorization Process to Reflect an Alternative Seis
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
ML20136A2222020-05-15015 May 2020
Har - Bru 2019 Aam Meeting Summary
ML19331A8062020-01-29029 January 2020
Summary of November 13, 2019 Closed Meeting with Duke Energy Carolinas, LLC and Duke Energy Progress, LLC, to Discuss Security-Related Information for Its Licensed Facilities
ML19329A0232019-11-27027 November 2019
Summary of October 29, 2019 Conference Call with Duke Energy Progress, LLC Regarding the Fall 2019 Steam Generator Tube Inspections
ML19241A2902019-09-24024 September 2019
Summary of August 22, 2019, Meeting with Duke Energy Progress, LLC Proposed License Amendment Request to Adopt Risk-Informed Completion Times
ML19220A6702019-08-26026 August 2019
Summary of August 7, 2019, Meeting with Duke Energy Progress, LLC and Duke Energy Carolinas, LLC to Discuss a Proposed License Amendment Request for a Common Emergency Plan
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
ML19120A1342019-05-0606 May 2019
3/15/19 Summary of Public Meeting with Nuclear Entergy Institute, Duke Energy, and Southern Nuclear Operating Company Post-Pilot Implementation of Tornado Missile Risk Evaluator Methodology at Vogtle, Units 1 and 2 and Shearon Harris, Unit
ML19123A3522019-05-0202 May 2019
Public Meeting Summary - Shearon Harris Nuclear Plant, Docket No. 50-400
ML19087A0622019-04-11011 April 2019
Summary of March 25, 2019, Public Teleconference with Duke Energy to Discuss the Request for Additional Information Response Regarding the Proposed Alternative to the Depth Sizing Qualification Requirement (Duke Energy Fleet Relief Request
ML18352A3572019-01-0808 January 2019
Summary of Meeting with Duke Energy Progress, LLC to Discuss Proposed License Amendment Request for Shearon Harris Nuclear Power Plant, Unit 1, Regarding Emergency Plan Changes
ML18361A6712019-01-0808 January 2019
Summary of Meeting with Duke Energy Progress, LLC to Discuss License Amendment Request for Shearon Harris Unit 1, Regarding 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures,
ML18355A8142019-01-0707 January 2019
Summary of December 20, 2018, Teleconference Meeting with Duke Energy Progress, LLC to Discuss a Proposed License Amendment Request for Shearon Harris Unit 1, Regarding a Risk-Informed Essential Services Chilled Water System TS
ML18094A2632018-08-17017 August 2018
Summary of 01/18/2018, Public Meeting with Nuclear Energy Institute, Duke Energy, Southern Nuclear Operating Co., Entergy Operations, Inc. to Discuss Development of Tornado Missile Risk Evaluator Methodology
ML18109A0912018-04-19019 April 2018
Summary of 2017 Annual Assessment Public Meeting Regarding Shearon Harris Nuclear Plant, Docket No. 50-400
ML18088A0732018-04-0303 April 2018
March 27, 2018, Summary of Presubmittal Meeting with Duke Energy Progress, LLC to Discuss a Proposed Relief Request for Shearon Harris Nuclear Power Plant, Unit 1
ML18064A1332018-03-19019 March 2018
Summary of February 27, 2018, Meeting with Duke Energy Progress, LLC to Discuss Proposed License Amendment Request for Shearon Harris Nuclear Power Plant, Unit 1, Regarding Emergency Plan Emergency Action Level Scheme Changes (L-2017-LRM-00
ML17340A1302017-12-22022 December 2017
Summary of November 29, 2017, Meeting with Duke Energy Progress, LLC to Discuss Proposed License Amendment Requests to Implement the Requirement of 10 CFR 50.69 at Brunswick, Shearon Harris, and H. B. Robinson
ML17340A0612017-12-0808 December 2017
11/8/17 Summary of Teleconference with Entergy Operations, Inc., Tornado Missile Risk Evaluator with Applicability to Submittals from Duke Energy and Southern Nuclear Operating Co, Inc.
ML17244A0742017-09-28028 September 2017
8/17/2017 Summary of Public Meeting with Nuclear Energy Institute and Licensees to Discuss the Tornado Missile Risk Evaluation Tool for Grand Gulf, Shearon Harris, and Vogtle, Units 1 and 2
ML17257A0992017-09-26026 September 2017
Summary of Public Meeting with Nuclear Energy Institute and Licensees to Discuss the Tornado Missile Risk Evaluation Tool for Grand Gulf, Shearon Harris, and Vogtle, Units 1 and 2
ML17223A1212017-08-17017 August 2017
Summary of August 3, 2017, Meeting with Duke Energy Progress, LLC on Proposed License Amendment Request to Implement Fuel Reload Design Methodology Reports for Shearon Harris and H. B. Robinson
ML17145A3142017-05-25025 May 2017
EOC Meeting Summary
ML16286A0152016-11-0101 November 2016
Summary Of September 29, 2016, Duke Energy Progress, LLC. To Discuss Proposed License Amendment Request Regarding Shearon Harris Nuclear Power Plant, Unit 1, BWR Storage Rack Inserts And The Spent Fuel Pool Criticality Analysis (CAC No. MF8327)
ML16235A2382016-10-17017 October 2016
Summary of the July 12-13, 2016 Audit Supporting the U.S. Nuclear Regulatory Commission Review of DPC-NE-1008-P, Nuclear Design Methodology Using CASMO-5/SIMULATE-3 for Westinghouse Reactors
ML16125A0992016-05-20020 May 2016
Summary of May 2, 2016, Meeting with Duke Energy Progress, Inc. to Discuss Fuel Reload Design Methodology Reports and Proposed Supplement to a License Amendment Request Regarding Shearon Harris and H.B. Robinson
ML16134A1552016-05-12012 May 2016
Public Meeting Summary - 2015 Annual Assessment Public Meeting Regarding Shearon Harris Nuclear Plant
ML16112A3772016-04-25025 April 2016
Summary of Meeting with Duke Energy Progress, Inc. to Discuss the Shearon Harris Nuclear Plant, Unit 1, TSTF-425 LAR Request for Additional Information Reponses
ML16034A5242016-03-11011 March 2016
Summary of February 1, 2016, Pre-submittal Meeting with Duke Energy Regarding Consolidation of Emergency Operations Facilities
ML16035A4802016-02-12012 February 2016
Jsc Meeting Summary Attachment
ML15280A2532015-11-25025 November 2015
Summary of Mtg. with Duke Energy Progress Inc. to Discuss Fuel Reload Design Methodology Reports & Proposed License Amendment Request Shearon Harris Nuclear Power Plant Unit 1 and H.B. Robinson Steam Electric Plant Unit No. 2 (MF6701/MF6702
ML15202A4752015-09-24024 September 2015
Summary of Meeting with Duke Energy Progress, Inc. to Discuss Shearon Harris Nuclear Power Plant, Unit 1, Proposed License Amendment Request Regarding Technical Specifications for the Pressurizer and Main Steam Line Safety Valves (MF6233)
ML14129A3352014-05-0909 May 2014
Summary of Category 1 Public Meeting - Annual Assessment of Shearon Harris Nuclear Plant
ML13312A9882013-11-0808 November 2013
Summary of Public Meeting with Duke Energy Carolinas, LLC, to Provide Opportunities to Discuss the Planned Fukushima-Related Modifications
ML13204A2672013-09-27027 September 2013
07/09/13 Summary of Meeting with Duke Energy Regarding a Nonconservative Technical Specification Loss of Offsite Power Voltage Setpoint License Amendment Request
ML13218B3692013-09-27027 September 2013
7/30/2013 - Summary of Meeting with Duke Energy Regarding a Change to the Emergency Response Facility Activation Timeliness and Criteria
ML13225A2932013-08-12012 August 2013
7/23-24/2013, Summary of Meeting 2013 U.S. Nuclear Regulatory Commission (NRC) Initial Exam Writers' Workshop
ML13171A3292013-06-20020 June 2013
Public Meeting Summary, Category 3, NRC Special Inspection on Reactor Vessel Head Nozzle Repair of Shearon Harris Nuclear Plant
ML13155A1052013-06-12012 June 2013
May 2, 2013, Summary of Meeting with Duke Energy Concerning the Relocation of the Emergency Operating Facilities
ML13151A2262013-05-30030 May 2013
Meeting Summary - Category 1 Public Meeting Annual Assessment - Shearon Harris Nuclear Plant - Docket 50-400
ML12277A0252012-11-0202 November 2012
10/2/12 Summary of Meeting with Duke Energy Carolinas to Discuss Nonconservative Technical Specifications License Amendment Requests
2024-05-01
[Table view] |
Text
LICENSEE:
Duke Energy Progress, Inc. FACILITY:
Shearon Harris Nuclear Power Plant, Unit 1
SUBJECT:
SUMMARY
OF JULY 15, 2015, MEETING WITH DUKE ENERGY PROGRESS, INC. TO DISCUSS THE SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1, PROPOSED LICENSE AMENDMENT REQUEST REGARDING TECHNICAL SPECIFICATIONS FOR THE PRESSURIZER AND MAIN STEAM LINE SAFETY VALVES (TAC NO. MF6233) On July 15, 2015, a Category 1 public meeting was held between the U.S. Nuclear Regulatory Commission (NRC) and representatives of Duke Energy Progress, Inc. (Duke Energy, the licensee) that was conducted as a public teleconference.
The purpose of the meeting was to have followup discussions to a June 11, 2015, meeting between Duke Energy and the NRC staff, including discussions regarding pressurizer water level technical specifications (TSs) and analysis.
At the June 11, 2015, meeting, Duke Energy discussed a proposed license amendment request (LAR) for Shearon Harris Nuclear Power Plant, Unit 1 (Harris) regarding TSs for the pressurizer safety valves (PSVs) and main steam line safety valves (MSLSVs) lift setting setpoints.
The meeting notice and agenda, dated July 1, 2015, are available in the Agencywide Documents Access and Management System (ADAMS) at Accession No. ML 15183A266.
There were no presentation materials for the meeting. A list of attendees is enclosed.
During the meeting, the licensee and the NRC staff discussed two main topics: 1. The impact of modifying the PSV and MSLSV TS lift setting tolerances on the pressurizer water level TS and associated analyses; and 2. The impact of modifying the PSV and MSLSV TS lift setting tolerances with regard to meeting Three Mile Island (TMI) Item 11.D.1. Regarding topic 1 above, the licensee discussed the historical and licensing basis for the pressurizer water level TSs for Westinghouse plants, in general, and for the Harris plant, in particular.
The licensee referred to the following publicly available documents:
- 1. Section 3.4.9 of NUREG-1431, "Standard Technical Specifications, Westinghouse Plants, Revision, Volume 1, Specifications," and "Standard Technical Specifications, Westinghouse Plants, Revision 4.0, Volume 2, Bases" (ADAMS Accession Nos. ML 12100A222 and ML 12100A228, respectively)
- 2. Harris TS 3.4.3, included in Amendment Nos. 93 and 109 to the Facility Operating License for Harris (ADAMS Accession Nos. ML993570130 and ML020370248, respectively) 3. Technical Specification Task Force Traveler-162, "Maximum Pressurizer Water Level Limit Bases" (ADAMS Accession No. ML040490213)
- 4. Section 2.4.19 of the Safety Evaluation for Amendment No. 107 to the Facility Operating License for Harris (ADAMS Accession No. ML012830516)
- 5. SLNRC 84-0087, Letter from N. Petrick to H. Denton, _dated May 25, 1984, "SNUPPS [Standardized Nuclear Unit Power Plant System] Technical Specifications Reactor Systems Branch Issues" (ADAMS Legacy Library No. 8405310209)
The NRC staff discussed a sensitivity study of the pressurizer water level using acceptable methods and reflecting the allowable tolerance changes associated with PSVs and MSLSVs setpoints for the applicable events discussed in the updated final safety analysis report (UFSAR), Chapter 15 for the proposed LAR. The staff discussed conformance to the acceptance criterion specified in various sections of Chapter 15, 'Transient and Accident Analysis," of NUREG-0800, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition" (hereafter SRP) (see collections/nuregs/staff/sr0800/ch15/),which states that an incident of moderate frequency should not generate a more serious plant condition without other faults occurring independently.
1 The NRC staff noted that the events discussed in UFSAR, Chapter 15, which credited PSVs and MSLSVs in the analysis for consequence mitigation, may be considered the "applicable events" to be analyzed in support of TS changes on the allowable lift setting tolerances.
The NRC staff also indicated that since the pressurif:er water level is an input parameter to the safety analyses being evaluated regarding the change to the PSVs and MSLSVs lift setting TS tolerances, the NRC staff review would include, in part, confirming that the pressurizer water level TS continue to meet the requirements of Title 10 of the Code of Federal Regulations (10 CFR), Section 50.36, and in particular, 10 CFR 50.36(c)(2)(ii).
Regarding topic 2 above, the licensee described the considerations it was addressing regarding TMI Item 11.D.1. TMI Item 11.D.1 is associated with the qualification of RCS relief and safety valves and, for pressurized water reactors, power-operated relief valve block valves for all fluid conditions expected under operating conditions, transients, and accidents.
The NRC staff noted that the treatment of non-safety systems in the analysis of operating conditions, transients, and accidents should be conservative.
The conservative assumption of whether a non-safety system actuates or not will depend on the operating conditions, transients, and accidents.
No regulatory decisions were made at the meeting. No members of the public were in attendance.
No Public Meeting Feedback forms were received.
1 For example, see SRP Sections 15.2.1-15.2.5, "Loss of External Load; Turbine Trip; Loss of Condenser Vacuum; Closure of Main Steam Isolation Valve (BWR); and Steam Pressure Regulator Failure (Closed)," Revision 2, dated March 2007 (ADAMS Accession No. ML070300702), Subsection II, SRP Acceptance Criterion 2.C). Please direct any inquiries to Dennis Galvin at 301-415-6256 or Dennis.Galvin@nrc.gov.
Docket No. 50-400
Enclosure:
List of Attendees cc w/enclosure:
Distribution via Listserv Manager Plant Licensing Branch 11-2 Division of Operator Reactor Licensing Office of Nuclear Reactor Regulation LIST OF ATTENDEES JULY 15, 2015, MEETING WITH DUKE ENERGY PROGRESS, INC. SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 PROPOSED LICENSE AMENDMENT REQUEST REGARDING TECHNICAL SPECIFICATIONS FOR THE PRESSURIZER AND MAIN STEAM LINE SAFETY VALVES U.S. Nuclear Regulatory Commission C. Jackson S.Sun R. Beaton M. Hamm M. Barillas D. Galvin Duke Energy Progress, Inc. C. loppolo D. Earp N. Mirza M. Karki R. Harvey S. Thomas D. Tibbitts Enclosure
-3 '.'" Please direct any inquiries to Dennis Galvin at 301-415-6256 or Dennis.Galvin@nrc.gov.
Docket No. 50-400
Enclosure:
List* of Attendees Martha Barillas, Project Manager /RA/ Plant Licensing Branch 11-2 Division of Operator Reactor Licensing Office of Nuclear Reactor Regulation cc w/enclosure:
Distribution via Listserv DISTRIBUTION:
PUBLIC RidsNrrLABClayton Resource RidsNrrDssStsb Resource RidsNrrPMShearonHarris Resource RidsNrrDorlLpl2-2 Resource ADAMS A ccess1on No.: ML1 202A 5 5 47 OFFICEJ NRR/DORL/LPL2-2/PM NAME DGalvin DATE 09/24/15 OFFICE NRR/DSS/STSB/BC NAME RElliott
- DATE 08/26/15 RidsRgn2MailCenter Resource RidsACRS_MailCTR Resource RidsNrrDssSrxb Resource DGalvin, NRR TWertz, NRR RBeaton, NRR SSun, NRR MHamm, NRR CRosales-Cooper, OEDO LPL2-2 concurre db *1 1yema1 NRR/DORL/LPL2-2/PM NRR/DORL/LPL2-2/LA NRR/DSS/SRXB/BC MBarillas BClayton (LRonewicz for) CJackson 08/10/15 08/07/15 08/26/15 NRR/DORL/LPL2-2/BC NRR/DORL/LPL2-2/PM SHelton MBarillas 09/21/15 09/24/15 OFFICIAL RECORD COPY ; '
