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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
[Table view] Category:Updated Final Safety Analysis Report (UFSAR)
MONTHYEARRA-22-0190, Submittal of Updated Final Safety Analysis Report (UFSAR) Revision 28, 10 CFR 54.37 Update, Technical Requirements Manuals, Quality Assurance Program Description, Technical Specification Bases, 10 CFR 50.59 and 10 CFR .2022-08-11011 August 2022 Submittal of Updated Final Safety Analysis Report (UFSAR) Revision 28, 10 CFR 54.37 Update, Technical Requirements Manuals, Quality Assurance Program Description, Technical Specification Bases, 10 CFR 50.59 and 10 CFR . RA-20-0244, Submittal of Updated Final Safety Analysis Report Revision 27, 10 CFR 54.37 Update, Technical Specifications Bases, Technical Requirements Manuals, Quality Assurance Program Description2020-08-12012 August 2020 Submittal of Updated Final Safety Analysis Report Revision 27, 10 CFR 54.37 Update, Technical Specifications Bases, Technical Requirements Manuals, Quality Assurance Program Description ML18249A1552018-08-13013 August 2018 Revision 26 to Updated Final Safety Analysis Report, Chapter 17A, Quality Assurance, Figures ML18249A1542018-08-13013 August 2018 Revision 26 to Updated Final Safety Analysis Report, Chapter 15A, Operational Safety Analysis, Figures ML18249A1532018-08-13013 August 2018 Revision 26 to Updated Final Safety Analysis Report, Chapter 15, Accident Analyses, Figures ML18249A1512018-08-13013 August 2018 Revision 26 to Updated Final Safety Analysis Report, Chapter 14, Initial Test Program, Figures ML18249A1502018-08-13013 August 2018 Revision 26 to Updated Final Safety Analysis Report, Chapter 13, Conduct of Operations, Figures ML18249A1492018-08-13013 August 2018 Revision 26 to Updated Final Safety Analysis Report, Chapter 12, Radiation Protection, Figures (Redacted) ML18249A1482018-08-13013 August 2018 Revision 26 to Updated Final Safety Analysis Report, Chapter 11, Radioactive Waste Management, Figures ML18249A1472018-08-13013 August 2018 Revision 26 to Updated Final Safety Analysis Report, Chapter 9, Auxiliary Systems, Figures ML18249A1462018-08-13013 August 2018 Revision 26 to Updated Final Safety Analysis Report, Chapter 8, Electric Power, Figures ML18249A1452018-08-13013 August 2018 Revision 26 to Updated Final Safety Analysis Report, Chapter 7, Instrumentation and Controls, Figures ML18249A1432018-08-13013 August 2018 Revision 26 to Updated Final Safety Analysis Report, Chapter 6, Engineered Safety Features, Figures ML18249A1422018-08-13013 August 2018 Revision 26 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems, Figures. (Redacted) ML18249A1402018-08-13013 August 2018 Revision 26 to Updated Final Safety Analysis Report, Chapter 4, Reactor, Figures ML18249A1352018-08-13013 August 2018 Revision 26 to Updated Final Safety Analysis Report, Chapter 3, Design of Structures, Components, Equipment, and Systems, Figures. (Redacted) ML18249A1342018-08-13013 August 2018 Revision 26 to Updated Final Safety Analysis Report, Chapter 2, Representative Excavation and Stockpiling Summary Sheets, Appendix 2E ML18249A1332018-08-13013 August 2018 Revision 26 to Updated Final Safety Analysis Report, Chapter 2, Representative Examples of Backfill Progress Sketches and Field and Laboratory Test Data Summary Sheet, Appendix 2D ML18249A1312018-08-13013 August 2018 Revision 26 to Updated Final Safety Analysis Report, Chapter 2, Pertinent Portions of BSEP Structural Fill Quality Assurance Specifications, Appendix 2C ML18249A1302018-08-13013 August 2018 Revision 26 to Updated Final Safety Analysis Report, Chapter 2, Additional Geophysical Information, Appendix 2B ML18249A1292018-08-13013 August 2018 Revision 26 to Updated Final Safety Analysis Report, Chapter 2, Site Characteristics, Appendix 2A Figures ML18249A1282018-08-13013 August 2018 Revision 26 to Updated Final Safety Analysis Report, Chapter 2, Site Characteristics, Figures ML18249A1262018-08-13013 August 2018 Revision 26 to Updated Final Safety Analysis Report, Chapter 1, Introduction and Summary, Figures ML18250A0132016-08-11011 August 2016 Revision 25 to Updated Final Safety Analysis Report, Chapter 2, Site Characteristics, Appendix 2A, Figures BSEP 16-0069, Revision 25 to Updated Final Safety Analysis Report, Chapter 9, Auxiliary Systems, Figures2016-08-11011 August 2016 Revision 25 to Updated Final Safety Analysis Report, Chapter 9, Auxiliary Systems, Figures ML18250A0222016-08-11011 August 2016 Revision 25 to Updated Final Safety Analysis Report, Chapter 8, Electric Power, Figures ML18250A0212016-08-11011 August 2016 Revision 25 to Updated Final Safety Analysis Report, Chapter 7, Analog Channels for Engineered Safeguards Sensor Trip Inputs, Appendix 7B, Figures ML18250A0202016-08-11011 August 2016 Revision 25 to Updated Final Safety Analysis Report, Chapter 7, Instrumentation and Controls, Figures ML18250A0192016-08-11011 August 2016 Revision 25 to Updated Final Safety Analysis Report, Chapter 6, Engineered Safety Features, Figures ML18250A0182016-08-11011 August 2016 Revision 25 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems, Figures (Redacted) ML18250A0172016-08-11011 August 2016 Revision 25 to Updated Final Safety Analysis Report, Chapter 4, Reactor, Figures ML18250A0162016-08-11011 August 2016 Revision 25 to Updated Final Safety Analysis Report, Chapter 3, Design of Structures, Components, Equipment, and Systems, Figures (Redacted) ML18250A0142016-08-11011 August 2016 Revision 25 to Updated Final Safety Analysis Report, Chapter 2, Site Characteristics, Appendix 2B, Figures ML18250A0122016-08-11011 August 2016 Revision 25 to Updated Final Safety Analysis Report, Chapter 2, Site Characteristics, Figures ML18250A0112016-08-11011 August 2016 Revision 25 to Updated Final Safety Analysis Report, Chapter 1, Figures (Redacted) ML18250A0102016-08-11011 August 2016 Revision 25 to Updated Final Safety Analysis Report, Chapter 17A, Figures ML18250A0092016-08-11011 August 2016 Revision 25 to Updated Final Safety Analysis Report, Chapter 15A, Figures ML18250A0082016-08-11011 August 2016 Revision 25 to Updated Final Safety Analysis Report, Chapter 15, Figures ML18250A0072016-08-11011 August 2016 Revision 25 to Updated Final Safety Analysis Report, Chapter 14, Figures ML18250A0062016-08-11011 August 2016 Revision 25 to Updated Final Safety Analysis Report, Chapter 13, Conduct of Operations, Figures ML18250A0052016-08-11011 August 2016 Revision 25 to Updated Final Safety Analysis Report, Chapter 12, Radiation Protection, Figures (Redacted) ML18250A0042016-08-11011 August 2016 Revision 25 to Updated Final Safety Analysis Report, Chapter 11, Radioactive Waste Management, Figures ML16257A4042016-05-31031 May 2016 ANP-3280(NP), Revision 1, Brunswick Unit 1 Cycle 19 Mellla+ Reload Safety Analysis. BSEP 14-0095, Updated Final Safety Analysis Report, Revision 24, and Changes to Quality Assurance Program Description2014-08-14014 August 2014 Updated Final Safety Analysis Report, Revision 24, and Changes to Quality Assurance Program Description BSEP 10-0100, Updated FSAR, Revision 222010-08-19019 August 2010 Updated FSAR, Revision 22 BSEP 09-0066, Cycle 19 Startup Report2009-06-25025 June 2009 Cycle 19 Startup Report BSEP 04-0006, Application for Renewal of Operating Licenses2004-10-18018 October 2004 Application for Renewal of Operating Licenses BSEP 03-0062, Request for License Amendments Re Implementation of the Boiling Water Reactor Vessel and Internals Project Reactor Pressure Vessel Integrated Surveillance Program to Address the Requirements of Appendix H to 10 CFR Part 502003-05-29029 May 2003 Request for License Amendments Re Implementation of the Boiling Water Reactor Vessel and Internals Project Reactor Pressure Vessel Integrated Surveillance Program to Address the Requirements of Appendix H to 10 CFR Part 50 2022-08-11
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Progress Energy JUN 2 5 200 SERIAL: BSEP 09-0066 U. S. Nuclear Regulatory Commission ATTFN: Document Control Desk Washington, DC 20555-0001
Subject:
Brunswick Steam Electric Plant, Unit No. 2 Docket No. 50-324/License No. DPR-62 Cycle 19 Startup Report Ladies and Gentlemen:
In accordance with the Brunswick Steam Electric Plant (BSEP) Updated Final Safety Analysis Report (UFSAR), Section 13.4.2.1, "Startup Report," Carolina Power & Light Company (CP&L), now doing business as Progress Energy Carolinas, Inc., submits the enclosed Brunswick Unit 2 Cycle 19 Startup Report. The report is required as a result of installation of fuel that was manufactured by a different fuel supplier (i.e., the AREVA ATRIUM-10 fuel type) during the spring 2009 refueling outage.
No regulatory commitments are contained in this letter. Please refer any questions regarding this submittal to Mr. Gene Atkinson, Supervisor - Licensing/Regulatory Programs, at (910) 457-2056.
Sincerely, Phyllis N. Mentel Manager - Support Services Brunswick Steam Electric Plant WRM/wrm
Enclosure:
Brunswick Unit 2, Cycle 19 Startup Report Progress Energy Carolinas, Inc.
Brunswick Nuclear Plant POBox 10429 Southport, NC 28461
Document Control Desk BSEP 09-0066 / Page 2 cc (with enclosure):
U. S. Nuclear Regulatory Commission, Region II ATTN: Mr. Luis A. Reyes, Regional Administrator Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, GA 30303-8931 U. S. Nuclear Regulatory Commission ATTN: Mr. Philip B. O'Bryan, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 U. S. Nuclear Regulatory Commission (Electronic Copy Only)
ATTN: Mrs. Farideh E. Saba (Mail Stop OWFN 8G9A) 11555 Rockville Pike Rockville, MD 20852-2738 Chair - North Carolina Utilities Commission P.O. Box 29510 Raleigh, NC 27626-0510
BSEP 09-0066 Enclosure Brunswick Unit 2 Cycle 19 Startup Report
BRUNSWICK UNIT 2, CYCLE 19 STARTUP REPORT June 2009 Hahn, Gregory Prepared By
-04'00'/1 .,
Prepared by: 2009.06.12 10:00:06 Gregory C. Hahn (BWR Fuel Engineering)
Thomas, Roger 2009.06.12 13:09:07 -04'00' Reviewed by:
Roger Thomas (BWR Fuel Engineering)
Westermark, Hans Reviewed By Reviewed by: 2009.06.15 07:46:19 -04'00' ".
Hans Westermark (BNP Reactor Engineering) 0* Oigned Dgitally byMur ray,WOiim0.[Bilr M urray, W illiam R. (Bi~l*\
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, nuU.r, Reviewed by: t Dl: 2W*9W5 15oll.32:$4-04W'00 William Murray (Regulatory Affairs)
Blom, Michael Management Approval..
Approved by: 2009.06.15 10:32:44 -04'00' Mike Blom (Superintendent, PWR Fuel Engineering)
Progress Energy Nuclear Fuels Management & Satbty Analysis Section B2C19 Startup Report Page 2 of 8, Revision 0 1.0 Introduction This report summarizes observed data from the Brunswick Steam Electric plant (BSEP)
Unit 2, Cycle 19 (B2C19) startup tests. The Cycle 19 core represents the first loading of thlc AREVA ATRIUM-I 0 fuel type in Unit 2. 238 ATRIUM-10 fuel assemblies have been loaded.
Pursuant to the requirements of Section 13.4.2.1 of the BSEP I & 2 Updated Final Safety Analysis Report (UFSAR), a summary report of plant startup and power escalation testing shall be submitted to the NRC should any one of four conditions occur. Condition (3) applies:
(3): "installation of fuel that has a different design or has been manufactured by a different fuel supplier."
This report shall include results of neutronics related startup tests following core reloading as described in the UFSAR.
2.0 References 2.1 BSEP UFSAR 2.2 BSEP Technical Specifications 2.3 OENP-24.13, "Core Verification" 2.4 OFH- 1I, "Refueling" 2.5 OPT-14.2.1, "Single Rod Scram Insertion Times Test" 2.6 OPT-14.3.1, "Insequence Critical Shutdown Margin Calculation" 2.7 OPT-14.5.2, "Reactivity Anomaly Check" 2.8 OPT-50.0, "Reactor Engineering Refueling Outage Testing" 2.9 OPT-50.3, "TIP Reproducibility And Uncertainty Determination" 2.10 OPT-90.2, "Friction Testing of Control Rods" 3.0 UFSAR Section 14.4.1, Item 1: Core Loading Verification A Core Loading Pattern Verification was performed per BSEP Engineering Procedure OENP-24.13, "Core Verification." The core was verified to be loaded in accordance with the analyzed B2C19 core design.
Progress Energy Nuclear Fuels Management & Sat'ety Analysis Section B2C19 Startup Report Page 3 of 8, Revision 0 4.0 UFSAR Section 14.4.1, Item 4A: "liPOperability and Bundle Power-tvaluation
- a. TI P Measurement Uncertainty Radial (bundle or 2D) and nodal (3D) gamma TIP measurement uncertainties were determined in accordance with BSEP Periodic Test Procedure OPT-50.3, "TIP Uncertainty Determination." Total radial TIP measurement uncertainty at high core thermal power (CTP) (>80% CTP) was 1.007% and total nodal TIP measurement uncertainty was 1.768%. These radial and nodal uncertainties were also determined at medium core thermal power (40% to 80% CTP) and were 0.909% and 1.594%,
respectively. All results met the test acceptance criteria.
- b. Measured and Calculated TIP Comparison Radial and nodal deviations between measured and calculated TIP data were determined in accordance with BSEP Periodic Test Procedure OPT-50.3, "TIP Uncertainty Determination." The radial deviation at high core thermal power (>80% CTP) was 1.778% and the nodal deviation was 3.945%. These radial and nodal deviations were also determined at medium core thermal power (40% to 80% CTP) and were 1.971% and 6.129%, respectively. All results met the test acceptance criteria.
- c. Monitored Power Uncertainty Radial and nodal monitored power uncertainties were determined in accordance with BSEP Periodic Test Procedure OPT-50.3, "TIP Uncertainty Determination." The radial monitored power uncertainty at high core thermal power (>80% CTP) was 2.288% and the nodal monitored power uncertainty was 2.992%. These radial and nodal uncertainties were also determined at medium core thermal power (40% to 80% CTP) and were 2.644% and 3.380%, respectively. All results, met the test acceptance criteria.
- d. Bundle Powers This analysis compares the MICROBURN-B2 predictions of bundle powers to the plant process computer's measured bundle powers in accordance with BSEP Periodic Test procedure OPT-50.0, "Reactor Engineering Refueling Outage Testing." Bundles located in peripheral control cells or uncontrolled peripheral locations are excluded. The maximum radial difference was calculated to be 4.67% at medium power (40% to 80%
CTP). All results met the test acceptance criteria.
IProgrcs,' Energ5y Nuclear Fuels Management & Safety Analysis Section B2C 9 Starnup Report Page 4 of 8, Revision 0 5.0 UFSAR Section 14.4.1, ltem 2: Control Rod Mobility Control rod mobility is verified by two tests: friction testing and scram timing. The results of these tests and their acceptance criteria are described below.
- a. Friction Testing Friction Testing was performed prior to startup per BSEP Periodic Test Procedure OPT-90.2, "Friction Testing of Control Rods." Control rods were verified to complete full travel without excessive binding or friction. In a pre-requisite to OPT-90.2, the reactor was observed to remain subcritical during the withdrawal of the most reactive rod in BSEP Fuel Handling Procedure OFH-11, "Refueling."
- b. Scram Time Testing Scram Time Testing was performed for each control rod prior to exceeding 40% power per BSEP Periodic Test Procedure OPT-14.2.1, "Single Rod Scramn Insertion Times Test."
The acceptance criteria for this test are found in Technical Specification 3.11.4. All control rods had a scram time of*< 7.0 seconds and thus were considered operable in accordance with Technical Specification 3.1.3. The maximum measured 5%, 20%, 50%,
and 90% insertion times are given in Attachment I of this report.
The average 20% insertion time measured from the low power testing was 0.816 seconds which is faster than the analyzed nominal speed limit of*!< 0.862 seconds.
6.0 UFSAR Section 14.4.1, Item 3: Reactivity Testing Reactivity Testing consists of a. shutdown margin (SDM) measurement, reactivity anomaly check, and measured critical kerr comparison to predicted values. The results of these tests are provided below with the acceptance criteria.
- a. Shutdown-Margin SDM measurements Were performed per BSEP Periodic.Test Procedure OPT-14.3.1, "Insequence Critical Shutdown Margin Calculation." The cycle minimum SDM was determined to be 1.0515% Ak/k compared to a predicted cycle 'Minimum SDM value of 1.09% Ak/k, an absolute difference of 0.0385% Ak/k. The cycle minimum SDM is determined by subtracting the maximum decrease in SDM which occurs at 0.0 GWD/MTU cycle exposure (R = 0.0% Ak/k) from the SDM at beginning-of-cycle (BOC). The acceptance criterion for minimum SDM is defined in Technical Specification 3.1.1.1, which requires the SDM be Ž> 0.38% Ak/k during the entire cycle.
Progress Energy Nuclear Fuels Management & Safety Analysis Section B2C 19 Startup Report Page 5 of 8, Revision 0 Since for B2CI9 the cycle minimum SDM was determined to be 1.0515% Ak/k, the acceptance criterion is met.
- b. teactivity Anomaly A reactivity anomaly test was performed at near rated conditions (2901.8 MWt or 99.3%)
per BSEP Periodic Test Procedure OPT-14.5.2, "Reactivity Anomaly Check." The acceptance criterion is defined by Technical Specification 3.1.2, which requires that the reactivity difference between monitored and predicted core ker- be within +/-1% 9Ak. The measured and predicted values for keff were 0.9980 and 1.0025, respectively, a difference of 0.45% Ak/k. This is within the +1% Ak requirement.
- c. Cold Critical Eigenvalue (kcrr)
The measured BOC cold critical krt-f per BSEP Periodic Test Procedure OPT-] 4.3.1, "Insequence Critical Shutdown Margin Calculation" was inferred as 0.99604 by nodal simulator code calculations with actual critical conditions as input (including period correction). The predicted BOC cold critical kff was 0.99600 resulting in a measured to predicted difference of 0.004% Ak/k. Therefore, per Technical Specification 3.1.2, the acceptance criterion requiring agreement within +/-1% Ak/k is met.
7.0 Additional Testing Results As a matter of course, key testing and checks beyond those specified in the UFSAR are performed during initial startup and power ascension. These "standard" tests are described in items (a) and (b) below.
- a. Core Monitoring Software Comparisons to Predictions Thermal limits calculated by the online POWERPLEX Core Monitoring'Software System were compared to those calculated by MICROBURN-B2 predictions at medium and high power levels. The results of these comparisons and the POWERPLEX statepoints are provided as Attachment 2. All results met the test acceptance criteria.
- b. Hot Full Power Eigenvalue After establishing a sustained period of full power equilibrium operation at 163.0 MWD/MTU on May 5, 2009, the predicted and core follow Hot Full Power Eigenvalues (ken-f) were compared. The core follow klt, was calculated as 0.9981 and the predicted ken- was 1.00235. The difference between the predicted and core follow values is 0.425% Ak/k which is within the +/-1% Ak/k reactivity anomaly requirements.
Progress Energy Nuclear Fuels Management & Safety Analysis Section B2C 19 Startup Report Page 6 of 8, Revision 0 8.o Summnary Evaluation of the BSEP Unit 2, Cycle 19 startup data concludes-the core has been loaded properly and is operating as expected. The startup and ifitia1 operating conditions and parameters compare well to predictions. Core thermal peaking design predictions and measured peaking comparisons, met the startup, acceptance criteria. The BOC SDM demonstration indicates adequate SDM will exist throughout B2C 19. All. UFSAR prescribed and additional tests met their acceptance criteria.
. . a Ilrogress Energy Nuclear Fuels Management & Safety Analysis Section 132C 19 Startup Report Page 7 of 8, Revision 0 Attachment 1 to the B2C19 Startup Report Results ot Control Rod Scram Time TestinE Maximum Measured Scram Insertion Time Technical Specification 3.1.4 Insertion Position/Notch Tech Spec Maximum Measured "Slow" Limit Insertion Time (seconds) (seconds) 5% 46 0.440 0.328 20% 36 1.080 1.003 50% 26 1.830 1.685 90% 06 3.350 3.083
Progress Energy Nuclear Fuels Management & Safety Analysis Section B2C 19 Startup Report Page 8 of 8, Revision 0 Attachment 2 to the B2C19 Startup Report Core Monitoring Software Comparisons to Predictions Medium Power Testing Plateau 66.9% CMWT, May 01, 2009 Thermal Limit POWERPLEX *MICROBURN-B2 Absolute On-Line Predicted Difference Monitoring CMFLCPR 0.741 0.753 0.012 CMAPRAT 0.746 0.767 0.021 CMFDLRX 0.697 0.724 0.027 CMFLPD 0.516 0.531 0.015 High Power Testing Plateau 99.3% CMWT, May 05, 2009 Thermal Limit POWERPLEX MICROBURN-B2 Absolute On-Line Predicted Difference Monitoring CMFLCPR 0.842 0.853 0.011 CMAPRAT 0.810 0.814 0.004 CMFDLRX 0.892 0.896 0.004 CMFLPD 0.698 0.703 0.005