Letter Sequence Request |
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MONTHYEARHNP-10-125, Request for Exemption in Accordance with 10 CFR 50.12 Regarding Use of M5 Alloy in Fuel Rod Cladding2011-01-19019 January 2011
Request for Exemption in Accordance with 10 CFR 50.12 Regarding Use of M5 Alloy in Fuel Rod Cladding
Project stage: Request
HNP-11-067, License Amendment Request for Revision to Technical Specification Core Operating Limits Report References for Realistic Large Break LOCA Analysis2011-08-22022 August 2011
License Amendment Request for Revision to Technical Specification Core Operating Limits Report References for Realistic Large Break LOCA Analysis
Project stage: Request
ML11238A0782011-08-31031 August 2011
ANP-3011(NP), Rev. 1, Harris Nuclear Plant Unit 1 Realistic Large Break LOCA Analysis
Project stage: Request
ML11272A0642011-09-29029 September 2011
NRR E-mail Capture - Acceptance Review for ME6999- Shearon Harris Unit 1, Realistic LBLOCA Methodology (TS 6.9.1.6.2)
Project stage: Acceptance Review
ML11336A1592011-12-0202 December 2011
Notice of Closed Meeting with Carolina Power & Light Company Regarding Shearon Harris Nuclear Plant, Unit 1 (TAC ME6999), the Purpose of the Meeting Is to Discuss the August 22, 2011, Large Break Loss of Coolant Accident Submittal
Project stage: Meeting
ML11354A2912011-12-13013 December 2011
Meeting Slides - Meeting with Carolina Power and Light Discussion of ANP-3011
Project stage: Request
ML11340A0852011-12-19019 December 2011
Request for Withholding Information from Public Disclosure
Project stage: Withholding Request Acceptance
ML11339A0502011-12-28028 December 2011
Acceptance of Requested Licensing Action Regarding Realistic Large Break Loss-of-Coolant Accident (TAC No. ME6999)(HNP-11-067)
Project stage: Acceptance Review
ML12076A1652012-01-11011 January 2012
Meeting Slides - Harris Realistic LBLOCA Question Response Meeting
Project stage: Meeting
ML12076A1422012-01-11011 January 2012
Meeting Topics - Suggested Discussion Items Regarding Large Break Loss-of-Coolant Accident Submittal - Shearon Harris Nuclear Power Plant, Unit 1
Project stage: Meeting
HNP-12-028, Realistic LBLOCA Question Response Meeting Handout, Enclosure 3 to HNP-12-0282012-01-11011 January 2012
Realistic LBLOCA Question Response Meeting Handout, Enclosure 3 to HNP-12-028
Project stage: Meeting
ML11354A2892012-02-0808 February 2012
Summary of Meeting with Carolina Power and Light to Discuss Realistic Large Break Loss-of-Coolant-Accident
Project stage: Meeting
ML11354A3782012-02-0808 February 2012
Meeting Handout - Meeting with Carolina Power and Light Suggested Discussion Items Regarding Realistic Large Break Loss-of-Coolant Accident
Project stage: Meeting
HNP-12-023, License Amendment Request for Revision to Technical Specification Core Operating Limits Report References for Realistic Large Break LOCA Analysis Response to Request for Additional Information2012-02-23023 February 2012
License Amendment Request for Revision to Technical Specification Core Operating Limits Report References for Realistic Large Break LOCA Analysis Response to Request for Additional Information
Project stage: Response to RAI
ML12073A2922012-02-24024 February 2012
License Amendment Request for Revision to Technical Specification Core Operating Limits Report for Realistic Large Break LOCA Analysis
Project stage: Request
ML12067A1802012-02-29029 February 2012
ANP-3011Q1(NP), Revision 000, Harris Nuclear Plant Unit 1 Realistic Large Break LOCA Analysis. Enclosure 4 Response to Request for Additional Information (Non-Proprietary)
Project stage: Response to RAI
ML12067A2322012-03-16016 March 2012
Request of Withholding Information from Public Disclosure
Project stage: Other
ML12067A2292012-03-16016 March 2012
Request for Withholding Information from Public Disclosure
Project stage: Withholding Request Acceptance
ML12067A2312012-03-20020 March 2012
Request for Withholding Information from Public Disclosure
Project stage: Withholding Request Acceptance
HNP-12-050, License Amendment Request for Revision to Technical Specification Core Operating Limits Report for Realistic Large Break LOCA Analysis Revised Technical Specification Page2012-04-0202 April 2012
License Amendment Request for Revision to Technical Specification Core Operating Limits Report for Realistic Large Break LOCA Analysis Revised Technical Specification Page
Project stage: Request
ML12076A1412012-04-0505 April 2012
Summary of Meeting Summary with Carolina Power & Light to Discuss Realistic Large Break Loss-of-Coolant
Project stage: Meeting
ML12076A1032012-05-30030 May 2012
Issuance of Amendment Regarding the Revision to Technical Specification Core Operating Limits Report References for Realistic Large Break Loss-of-Coolant Accident Analysis
Project stage: Approval
2012-01-11
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Text
- Progress Energy APR 2 201Z Christopher L. Burton Vice President Harris Nuclear Plant Progress Energy Carolinas, Inc.
10 CFR 50.90 Serial: HNP-12-050 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Shearon Harris Nuclear Power Plant, Unit No. 1 Docket No. 50-400 / Renewed License No. NPF-63
Subject:
License Amendment Request for Revision to Technical Specification Core Operating Limits Report for Realistic Large Break LOCA Analysis Revised Technical Specification Page
Reference:
Letter from K. Holbrook to the U.S. NRC, "License Amendment Request for Revision to Technical Specification Core Operating Limits Report," Serial HNP-11-067 dated August 22, 2011, ADAMS Accession No. ML11238A077 Ladies and Gentlemen:
By letter dated August 22, 2011, Carolina Power & Light Company (CP&L), doing business as Progress Energy Carolinas, Inc., requested approval from the U.S. Nuclear Regulatory Commission (NRC) of a license amendment request (LAR). The proposed amendment would revise Technical Specification (TS) 6.9.1.6, "Core Operating Limits Report," to add a plant-specific methodology that implements AREVA's NRC-approved topical report EMF-2103(P)(A), "Realistic Large Break LOCA Methodology for Pressurized Water Reactors,"
Revision 0, and also EMF-2103(P)(A), "Realistic Large Break LOCA Methodology for Pressurized Water Reactors," Revision 2 or higher upon approval of the specific revision by the NRC.
CP&L rescinds our request for approval of EMF-2103(P)(A), Revision 2 or higher. The attached retyped Technical Specification page 6-24a has been revised accordingly.
P.O.
Box 165 New Hill, NC 27562 T> 919.362.2502 F> 919.362.2095
U.S. Nuclear Regulatory Commission Page 2 HNP-12-050 This document contains no new Regulatory Commitment.
Please direct any questions regarding this submittal to Dave Corlett at (919) 362-3137.
Sincerely, CLB/jrc Enclosed: Revised Technical Specification Page cc:
Mr. J. D. Austin, NRC Sr. Resident Inspector, HNP Mr. W. L. Cox, III, Section Chief N.C. DENR Ms. A. T. Billoch Colon, NRC Project Manager, HNP Mr. V. M. McCree, NRC Regional Administrator, Region II
ADMINISTRATIVE CONTROLS 6.9.1.6 CORE OPERATING LIMITS REPORT (Continued)
- d.
XN-75-32(P)(A), "Computational Procedure for Evaluating Fuel Rod Bowing,"
approved version as specified in the COLR.
(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor, and 3.2.3 -
Nuclear Enthalpy Rise Hot Channel Factor).
- e.
EMF-84-093(P)(A), "Steam Line Break Methodology for PWRs," approved version as specified in the COLR.
(Methodology for Specification 3.1.1.3 - Moderator Temperature Coefficient, 3.1.3.5 - Shutdown Bank Insertion Limits, 3.1.3.6 - Control Bank Insertion Limits, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).
- f.
ANP-3011 (P), "Harris Nuclear Plant Unit 1 Realistic Large Break LOCA Analysis,"
Revision 1, as approved by NRC safety evaluation dated (Methodology for Specification 3.2.1 - Axial Flux Difference, 3.2.2 - Heat Flux Hot Channel Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).
- g.
XN-NF-78-44(NP)(A), "A Generic Analysis of the Control Rod Ejection Transient for Pressurized Water Reactors," approved version as specified in the COLR.
(Methodology for Specification 3.1.3.5 - Shutdown Bank Insertion Limits, 3.1.3.6 -
Control Bank Insertion Limits, and 3.2.2 - Heat Flux Hot Channel Factor).
SHEARON HARRIS - UNIT 1 6-24a Amendment No.
