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Category:Annual Operating Report
MONTHYEARRA-24-0083, Annual Report of Changes Pursuant to 10 CFR 50.462024-04-25025 April 2024 Annual Report of Changes Pursuant to 10 CFR 50.46 RA-23-0044, Aduke Energy Annual Report of Changes Pursuant to 10 CFR 50.462023-04-26026 April 2023 Aduke Energy Annual Report of Changes Pursuant to 10 CFR 50.46 RA-23-0046, Annual Radioactive Effluent Release Report - 20222023-04-24024 April 2023 Annual Radioactive Effluent Release Report - 2022 RA-22-0028, Annual Report of Changes Pursuant to 10 CFR 50.462022-04-27027 April 2022 Annual Report of Changes Pursuant to 10 CFR 50.46 RA-21-0051, Shearon Harris Nuclear Power Plant, McGuire Nuclear Station, Oconee Nuclear Station, and H. B. Robinson Steam Electric Plant - Annual Report of Changes Pursuant to 10 CFR 50.462021-04-0505 April 2021 Shearon Harris Nuclear Power Plant, McGuire Nuclear Station, Oconee Nuclear Station, and H. B. Robinson Steam Electric Plant - Annual Report of Changes Pursuant to 10 CFR 50.46 RA-20-0126, Annual Report of Changes Pursuant to 10 CFR 50.462020-05-27027 May 2020 Annual Report of Changes Pursuant to 10 CFR 50.46 RA-18-0022, Carolinas, LLC (Duke Energy) - Annual Report of Changes Pursuant to 10 CFR 50.462018-05-24024 May 2018 Carolinas, LLC (Duke Energy) - Annual Report of Changes Pursuant to 10 CFR 50.46 RA-17-0027, Duke Energy Carolinas, LLC - Annual Report of Changes Pursuant to 10 CFR 50.462017-05-25025 May 2017 Duke Energy Carolinas, LLC - Annual Report of Changes Pursuant to 10 CFR 50.46 BSEP 17-0038, Annual Radiological Environmental Operating Report - 20162017-05-10010 May 2017 Annual Radiological Environmental Operating Report - 2016 RA-16-0025, Duke Energy Annual Report of Changes Pursuant to 10 CFR 50.462016-05-31031 May 2016 Duke Energy Annual Report of Changes Pursuant to 10 CFR 50.46 BSEP 16-0034, Submittal of Annual Radiological Environmental Operating Report for 20152016-05-11011 May 2016 Submittal of Annual Radiological Environmental Operating Report for 2015 RA-15-0036, Annual Report of Changes Pursuant to 10 CFR 50.462015-08-31031 August 2015 Annual Report of Changes Pursuant to 10 CFR 50.46 BSEP 12-0100, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors2012-09-10010 September 2012 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors BSEP 12-0047, Radioactive Effluent Release Report for 20112012-04-30030 April 2012 Radioactive Effluent Release Report for 2011 BSEP 11-0044, Annual Report of Results of Individual Monitoring for 20102011-04-19019 April 2011 Annual Report of Results of Individual Monitoring for 2010 BSEP 10-0061, Radiological Environmental Operating Report for 20092010-05-13013 May 2010 Radiological Environmental Operating Report for 2009 BSEP 09-0049, Radiological Environmental Operating Report for 20082009-05-13013 May 2009 Radiological Environmental Operating Report for 2008 BSEP 09-0045, Submittal of Radioactive Effluent Release Report for 20082009-04-27027 April 2009 Submittal of Radioactive Effluent Release Report for 2008 BSEP 07-0095, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors2007-09-11011 September 2007 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors BSEP 07-0037, Annual Radiological Environmental Operating Report for 20062007-05-14014 May 2007 Annual Radiological Environmental Operating Report for 2006 ML0712402802007-04-30030 April 2007 Enclosure 1 - Brunswick, Unit 1 and 2, BSEP 07-0036, Radioactive Effluent Release Report for 2006 BSEP 06-0102, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors2006-09-28028 September 2006 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors BSEP 04-0034, Annual Radiological Environmental Operating Report for 20032004-05-0707 May 2004 Annual Radiological Environmental Operating Report for 2003 ML0424704352003-08-25025 August 2003 Submittal of 10-Q Report for Quarterly Period Ending, June 30, 2004 BSEP 03-0107, Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models2003-07-0909 July 2003 Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models 2024-04-25
[Table view] Category:Letter type:BSEP
MONTHYEARBSEP 19-0012, Submittal of 2018 Sea Turtle Annual Report2019-01-17017 January 2019 Submittal of 2018 Sea Turtle Annual Report BSEP 18-0052, Annual Radiological Environmental Operating Report - 20172018-05-10010 May 2018 Annual Radiological Environmental Operating Report - 2017 BSEP 18-0051, Annual Radioactive Effluent Release Report - 20172018-04-26026 April 2018 Annual Radioactive Effluent Release Report - 2017 BSEP 18-0045, Request for License Amendment: Technical Specification 3.8.3, Diesel Fuel Oil, One-Time Extension of Main Fuel Oil Storage Tank Completion Time2018-04-25025 April 2018 Request for License Amendment: Technical Specification 3.8.3, Diesel Fuel Oil, One-Time Extension of Main Fuel Oil Storage Tank Completion Time BSEP 18-0054, Response to Request for Additional Information Regarding Inservice Inspection Program Proposed Alternative ISI-09 in Accordance with 10 CFR 50.55a(z)(1) Regarding Reactor Pressure Vessel Circumferential.2018-04-24024 April 2018 Response to Request for Additional Information Regarding Inservice Inspection Program Proposed Alternative ISI-09 in Accordance with 10 CFR 50.55a(z)(1) Regarding Reactor Pressure Vessel Circumferential. BSEP 18-0048, Response to Request for Additional Information Regarding Inservice Inspection Program Proposed Alternative ISI-09 in Accordance with 10 CFR 50.55a(z)(1) Regarding Reactor Pressure Vessel Circumferential Shell Weld Examinations2018-04-11011 April 2018 Response to Request for Additional Information Regarding Inservice Inspection Program Proposed Alternative ISI-09 in Accordance with 10 CFR 50.55a(z)(1) Regarding Reactor Pressure Vessel Circumferential Shell Weld Examinations BSEP 18-0044, Application of Dissimilar Metal Weld Full Structural Overlay - Reactor Pressure Vessel Nozzles N4A and N4D2018-04-11011 April 2018 Application of Dissimilar Metal Weld Full Structural Overlay - Reactor Pressure Vessel Nozzles N4A and N4D BSEP 18-0046, Supplement to Response to Request for Additional Information SRXB-RAI-2 Regarding Request for License Amendment Regarding Core Flow Operating Range Expansion2018-04-10010 April 2018 Supplement to Response to Request for Additional Information SRXB-RAI-2 Regarding Request for License Amendment Regarding Core Flow Operating Range Expansion BSEP 18-0047, Supplement to Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2) for End of Interval Leakage Test2018-04-0505 April 2018 Supplement to Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2) for End of Interval Leakage Test BSEP 18-0041, Request for License Amendment to Revise the Technical Specifications to Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report2018-04-0404 April 2018 Request for License Amendment to Revise the Technical Specifications to Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report BSEP 18-0043, Application of Dissimilar Metal Weld Full Structural Overlay - Reactor Pressure Vessel Nozzles N4A and N4D2018-03-31031 March 2018 Application of Dissimilar Metal Weld Full Structural Overlay - Reactor Pressure Vessel Nozzles N4A and N4D BSEP 18-0035, Response to Request for Additional Information Regarding Request for License Amendment Regarding Core Flow Operating Range Expansion2018-03-29029 March 2018 Response to Request for Additional Information Regarding Request for License Amendment Regarding Core Flow Operating Range Expansion BSEP 18-0042, Cycle 22 Core Operating Limits Report (COLR)2018-03-27027 March 2018 Cycle 22 Core Operating Limits Report (COLR) BSEP 18-0040, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for End of Interval Leakage Test2018-03-23023 March 2018 Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for End of Interval Leakage Test BSEP 18-0039, Proposed In-Service Inspection Alternative for Application of Dissimilar Metal Weld Full Structural Overlay - Nozzles N4A and N4D2018-03-19019 March 2018 Proposed In-Service Inspection Alternative for Application of Dissimilar Metal Weld Full Structural Overlay - Nozzles N4A and N4D BSEP 18-0034, Corrected Affidavit Relating to the Request for License Amendment Regarding Core Flow Operating Range Expansion2018-03-16016 March 2018 Corrected Affidavit Relating to the Request for License Amendment Regarding Core Flow Operating Range Expansion BSEP 18-0032, Additional Testing Information Relating to the Request for License Amendment Regarding Core Flow Operating Range Expansion2018-03-14014 March 2018 Additional Testing Information Relating to the Request for License Amendment Regarding Core Flow Operating Range Expansion BSEP 18-0026, Additional Information Regarding Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for Reactor Pressure Vessel Nozzle-to-Vessel Weld Examination2018-03-0707 March 2018 Additional Information Regarding Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for Reactor Pressure Vessel Nozzle-to-Vessel Weld Examination BSEP 18-0014, Fifth 10-Year Inservice Testing Program Plan2018-02-19019 February 2018 Fifth 10-Year Inservice Testing Program Plan BSEP 18-0021, Response to Request for Additional Information Regarding Request for License Amendment Regarding Core Flow Operating Range Expansion (CAC Nos. MF8864 and MF8865). Without Proprietary Enclosure2018-02-0505 February 2018 Response to Request for Additional Information Regarding Request for License Amendment Regarding Core Flow Operating Range Expansion (CAC Nos. MF8864 and MF8865). Without Proprietary Enclosure BSEP 18-0017, Revision to Radiological Emergency Response Plan and Implementing Procedure2018-01-30030 January 2018 Revision to Radiological Emergency Response Plan and Implementing Procedure BSEP 18-0015, Inservice Inspection Program Proposed Alternative ISI-09 in Accordance with 10 CFR 50.55a(z)(1) Regarding Reactor Pressure Vessel Circumferential Shell Weld Examinations2018-01-23023 January 2018 Inservice Inspection Program Proposed Alternative ISI-09 in Accordance with 10 CFR 50.55a(z)(1) Regarding Reactor Pressure Vessel Circumferential Shell Weld Examinations BSEP 18-0013, Supplement to Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control2018-01-23023 January 2018 Supplement to Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control BSEP 18-0001, Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements2018-01-23023 January 2018 Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements BSEP 18-0012, Application to Revise Technical Specifications to Adopt TSTF-208, Revision 0, Extension of Time to Reach Mode 2 in LCO 3.0.32018-01-23023 January 2018 Application to Revise Technical Specifications to Adopt TSTF-208, Revision 0, Extension of Time to Reach Mode 2 in LCO 3.0.3 BSEP 18-0009, 2017 Sea Turtle Annual Report2018-01-15015 January 2018 2017 Sea Turtle Annual Report BSEP 17-0098, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors2018-01-10010 January 2018 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors BSEP 17-0119, Snubber Program Plan for Fifth 10-Year Interval Inservice Testing Program2018-01-10010 January 2018 Snubber Program Plan for Fifth 10-Year Interval Inservice Testing Program BSEP 17-0115, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control2018-01-0404 January 2018 Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control BSEP 17-0110, Seventh Six-Month Status Report in Response to June 6, 2013, Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions2017-12-20020 December 2017 Seventh Six-Month Status Report in Response to June 6, 2013, Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions BSEP 17-0121, Post-Examination Documentation and Comments for Operator Retake Initial Examination2017-12-14014 December 2017 Post-Examination Documentation and Comments for Operator Retake Initial Examination BSEP 17-0120, Withdrawal of Request for Risk-Informed Exigent License Amendment - Technical Specification 3.8.1, AC Sources - Operating, One-Time Extension of Emergency Diesel Generator Completion Times and Suspension..2017-12-12012 December 2017 Withdrawal of Request for Risk-Informed Exigent License Amendment - Technical Specification 3.8.1, AC Sources - Operating, One-Time Extension of Emergency Diesel Generator Completion Times and Suspension.. BSEP 17-0118, Supplement to Response to Request for Additional Information Regarding Request for Risk-Informed Exigent License Amendment - Technical Specification 3.8.1, AC Sources - Operating, One-Time Extension of Emergency Diesel..2017-12-0707 December 2017 Supplement to Response to Request for Additional Information Regarding Request for Risk-Informed Exigent License Amendment - Technical Specification 3.8.1, AC Sources - Operating, One-Time Extension of Emergency Diesel.. BSEP 17-0117, Response to Request for Additional Information (Probabilistic Risk Assessment and Human Performance Branches) Regarding Request for Risk-Informed Exigent License Amendment - Technical Specification 3.8.1 AC Sources..2017-12-0606 December 2017 Response to Request for Additional Information (Probabilistic Risk Assessment and Human Performance Branches) Regarding Request for Risk-Informed Exigent License Amendment - Technical Specification 3.8.1 AC Sources.. BSEP 17-0116, Response to Request for Additional Information Regarding Request for Risk- Informed Exigent License Amendment - Technical Specification 3.8.1, AC Sources - Operating, One-Time Extension of ..2017-12-0404 December 2017 Response to Request for Additional Information Regarding Request for Risk- Informed Exigent License Amendment - Technical Specification 3.8.1, AC Sources - Operating, One-Time Extension of .. BSEP 17-0104, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for Reactor Pressure Vessel Nozzle-to-Vessel Weld Examination2017-11-29029 November 2017 Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for Reactor Pressure Vessel Nozzle-to-Vessel Weld Examination BSEP 17-0111, Request for Risk-Informed Exigent License Amendment - Technical Specification 3.8.1, AC Sources Operating, One-Time Extension of Emergency Diesel Generator Completion Times and Suspension of Surveillance Requirements2017-11-28028 November 2017 Request for Risk-Informed Exigent License Amendment - Technical Specification 3.8.1, AC Sources Operating, One-Time Extension of Emergency Diesel Generator Completion Times and Suspension of Surveillance Requirements BSEP 17-0109, Response to Request for Additional Information Regarding Request for Emergency License Amendment - Technical Specification 3.8.1, AC Sources - Operating, One-Time Extension of Emergency Diesel Generator Completion Times And.2017-11-24024 November 2017 Response to Request for Additional Information Regarding Request for Emergency License Amendment - Technical Specification 3.8.1, AC Sources - Operating, One-Time Extension of Emergency Diesel Generator Completion Times And. BSEP 17-0108, Request for Emergency License Amendment - Technical Specification 3.8.1, AC Sources - Operating, One-Time Extension of Emergency Diesel Generator Completion Times and Suspension of Surveillance Requirements2017-11-22022 November 2017 Request for Emergency License Amendment - Technical Specification 3.8.1, AC Sources - Operating, One-Time Extension of Emergency Diesel Generator Completion Times and Suspension of Surveillance Requirements BSEP 17-0017, Submittal of Request for License Amendment for Performance-Based Fire Protection Alternative for Thermal Insulation Material2017-11-15015 November 2017 Submittal of Request for License Amendment for Performance-Based Fire Protection Alternative for Thermal Insulation Material BSEP 17-0100, Fifth 10-Year Inservice Testing Interval2017-11-0202 November 2017 Fifth 10-Year Inservice Testing Interval BSEP 17-0089, Updates to Request for License Amendment Regarding Core Flow Operating Range Expansion2017-11-0101 November 2017 Updates to Request for License Amendment Regarding Core Flow Operating Range Expansion BSEP 17-0093, Response to Request for Additional Information Regarding Request for License Amendment Regarding Core Flow Operating Range Expansion2017-11-0101 November 2017 Response to Request for Additional Information Regarding Request for License Amendment Regarding Core Flow Operating Range Expansion BSEP 17-0078, Request for License Amendment - DC Sources - Operating Surveillance Requirement (SR) 3.8.4.52017-10-0303 October 2017 Request for License Amendment - DC Sources - Operating Surveillance Requirement (SR) 3.8.4.5 BSEP 17-0076, Registration for Use of General License Spent Fuel Casks2017-09-0606 September 2017 Registration for Use of General License Spent Fuel Casks BSEP 17-0081, Revision to Radiological Emergency Response Plan Implementing Procedures2017-09-0505 September 2017 Revision to Radiological Emergency Response Plan Implementing Procedures BSEP 17-0039, Submittal of Response to Inspection Report 05000324/2015404 and 05000325/2015404, Dated March 30, 2015, Inspection of Interim Cyber Security Milestones 1-7 and Target Set Requirements2017-08-15015 August 2017 Submittal of Response to Inspection Report 05000324/2015404 and 05000325/2015404, Dated March 30, 2015, Inspection of Interim Cyber Security Milestones 1-7 and Target Set Requirements BSEP 17-0071, ISFSI - Registration for Use of General License Spent Fuel Casks2017-08-15015 August 2017 ISFSI - Registration for Use of General License Spent Fuel Casks BSEP 17-0064, Application of Dissimilar Metal Weld Full Structural Overlay on Reactor Pressure Vessel Nozzle N92017-07-10010 July 2017 Application of Dissimilar Metal Weld Full Structural Overlay on Reactor Pressure Vessel Nozzle N9 BSEP 17-0060, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control.2017-06-29029 June 2017 Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control. 2019-01-17
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jProgress Energy 10 CFR 50.46(a)(3)(ii)
SEP 11 2007 SERIAL: BSEP 07-0095 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Subject:
Brunswick Steam Electric Plant, Unit Nos. 1 and 2 Docket Nos. 50-325 and 50-324/License Nos. DPR-71 and DPR-62 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors
Reference:
Letter from Randy C. Ivey to the U.S. Nuclear Regulatory Commission, "Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors," dated September 28, 2006, ADAMS Accession Number ML062780225 Ladies and Gentlemen:
In accordance with 10 CFR 50.46, "Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors," paragraph (a)(3)(ii), Carolina Power &
Light Company (CP&L), now doing business as Progress Energy Carolinas, Inc., is submitting the annual report of the emergency core cooling system (ECCS) evaluation model changes and errors for the Brunswick Steam Electric Plant (BSEP), Unit Nos. I and 2.
This report covers the period from August 16, 2006, through August 15, 2007. The previous annual report for BSEP, Units 1 and 2, was submitted by CP&L's letter dated September 28, 2006. Since the previous annual report, no error or change notifications have been issued by Global Nuclear Fuels which affect the ECCS evaluation model for BSEP, Units 1 and 2. Therefore, the estimated licensing basis peak cladding temperatures (PCTs) remain unchanged from the values previously reported (i.e., <15670 F for GEl4 fuel).
Progress Energy Carolinas, Inc.
Brunswick Nuclear Plant POBox 10429 Southpoil, NC28461
Document Control Desk BSEP 07-0095 / Page 2 No regulatory commitments are contained in this letter. Please refer any questions regarding this submittal to Ms. Annette H. Pope, Supervisor - Licensing/Regulatory Programs, at (910) 457-2184.
Sincerely, Randy C. Ivey Manager - Support Services Brunswick Steam Electric Plant WRM/wrm cc: U. S. Nuclear Regulatory Commission, Region II ATTN: Dr. William D. Travers, Regional Administrator Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, GA 30303-8931 U. S. Nuclear Regulatory Commission ATTN: Mr. Joseph D. Austin, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 U. S. Nuclear Regulatory Commission (Electronic Copy Only)
ATTN: Mr. Stewart N. Bailey (Mail Stop OWFN 8B1) 11555 Rockville Pike Rockville, MD 20852-2738 Chair - North Carolina Utilities Commission P.O. Box 29510 Raleigh, NC 27626-0510
Progress Energy 2007 BRUNSWICK ANNUAL 10 CFR 50.46 REPORT Prepared By: David J. Pribyl (NFM&SA)
Date: August 22, 2007 PassPort NTM: 00207790 BNP 10 CFR 50.46 Assessment Period: August 16, 2006 - August 15, 2007 A. Introduction The documentation herein supports compliance to 10 CFR 50.46 (a)(3)(ii) (Reference B.1) requiring licensees of light-water nuclear power reactors to report the nature of a change or the error in an ECCS evaluation model to the Commission at least annually. The purpose of this assessment is to support the 2007 Brunswick Annual 10 CFR 50.46 Report. The requirements of 10 CFR 50.46 with regard to the identification and evaluation of changes to or errors in the LOCA evaluation model are implemented by Progress Energy procedure REG-NGGC-0006 (Reference B.2).
B. References B. 1 Title 10 Code of Federal Regulation 50.46, "Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors," June 29, 2007.
B.2 Progress Energy Procedure REG-NGGC-0006, "Identification of Changes to (or Errors in) LOCA Evaluation Models or Applications According to 10 CFR 50.46," Revision 2.
B.3 Email Correspondence from Mark Mneimneh (GNF) to Eric Geyer (PGN), "RE: 10 CFR 50.46 Notification - 2007 - Brunswick," August 21, 2007 (Attachment 1).
B.4 PassPort Condition Report 00168654, "2006 Annual 10 CFR 50.46 Report."
B.5 Brunswick Design Calculation 0B21-0112, "IOCFR50.46 SAFER/GESTR-LOCA ECCS Analysis Update," Revision 12, January 25, 2007.
C. Summary As reported by GNF in Reference B.3 (Attachment 1), there have been no additional notices for Brunswick since 2006-01. Notice 2006-001 was addressed in the 2006 Brunswick Annual 10 CFR 50.46 Report (Reference B.4). Therefore, there are no changes to (or errors in) the Brunswick LOCA evaluation model to record for the Brunswick 2007 10 CFR 50.46 assessment period. The assessment of the Brunswick LOCA evaluation model in Reference B.5 remains valid.
Page 1 of 4
. Progress Energy Tables 1, 2, and 3 (below) summarize the current LOCA evaluation results as documented in Reference B.5.
1Table 1 BNP SAFER/GESTR-LOCA ECCS Analysis Change/Error Summary Estimated BNP Cumulative BNP Change Notice Period Change or GE BWR Licensing PCT Licensing PCT Is BNP Licensing PCT or Error or Covered Error Estimated Impact and Change Change Greater than 50°F?
Notice Docu- Description Licensing Estimated PCT Incremental Cumulative ment PCT Impact (GEl4)
Date NA NA Through NA NA NA NA NA NA 8/15/07 Table 2 BNP Licensing PCT Change Summary Through 8/15/07*
Fuel Type Most Recent Licensing (most recent LOCA PCT Reported in a Current Estimated Change from reported analysis Licensing PCT) LOCA Document Licensing PCT Licensing PCT Submitted to the NRC (Analysis or Notice)
GE14 <1567°F <1567'F 0°F Table 3 BNP Upper Bound PCT Change Summary Through 8/15/07*
Upper Bound PCT Fuel Type Corresponding to Current Estimated Change from Previous (most recent LOCA Table 2 Most Recent Upper Bound PCT Upper Bound PCT analysis Upper Bound Submitted to the NRC PCT)
GE14 < 1497'F <1497°F 0°F
- BNP LOCA Results presented for Unit 2, which bounds Unit 1.
Page 2 of 4
Progress Energy ATTACHMENT 1 From: Mneimneh, Mark (GNF) [Mark.Mneimneh@gnf.com]
Sent: Tuesday, August 21, 2007 3:37 PM To: Geyer, Eric; Pribyl, David
Subject:
RE: 10 CFR 50.46 Notification - 2007 - Brunswick Eric, Dave;*
There have been no additional notices for Brunswick since 2006-01.
Annual notifications letters have not been sent since 2001. In the past these letters were sent to NRC and then sent to each customer as an attachment. At some point, GE realized that utilities, as the owner of plant configuration, are the right entities to send the annual notification to NRC.
The SRLR is now used as the means to summarize the 50.46 errors. We have been sending emails to customers (on request, similar to this) with the list of errors since their last SRLR.
Thanks Mark From: Geyer, Eric pqnmail.com
Sent: Monday, August 20, 2007 5:13 PM To: Mneimneh, Mark (GNF)
Cc: Lingenfelter, Andy (GNF); Pribyl, David
Subject:
FW: 10 CFR 50.46 Notification - 2007 - Brunswick
- Mark, Is an annual reporting letter pending? Or no news is good news?
Last notice we received (attached) was 7/28/06.
- Thanks, Eric
<<20060728 10 CFR50-46 Notification 2006-01 Brunswick GNF Email Attachment.pdf>>
<<20060728 10 CFR50-46 Notification 2006-01 Brunswick GNF Email.pdf>>
Original-----
Message -----
From: Pribyl, David Sent: Monday, August 20, 2007 1:41 PM To: Geyer, Eric
Subject:
10 CFR 50.46 Notification - 2007 - Brunswick
- Eric, Has GNF transmitted the 50.46 notification for Brunswick? Can I get a copy?
Page 3 of 4
Progress Energy I need to start preparing the Brunswick transmittal soon.
Thanks ... David David Pribyl Progress Energy - Carolinas BWR Fuels Engineer 410 S. Wilmington St., PEB06 Raleigh, NC 27601 T > 919.546.2516 F > 919.546.4361 C > 919.539.0009 E > david.pribyl@pgnmail.com Page 4 of 4