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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
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jProgress Energy DEC 0-8 2011 SERIAL: BSEP 11-0106 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Subject:
Brunswick Steam Electric Plant, Unit No. 2 Renewed Facility Operating License No. DPR-62 Docket No. 50-324 Revision of Regulatory Commitment Regarding Replacement of Unit 2 Core Plate Plugs Ladies and Gentlemen:
The purpose of this letter is to request NRC approval of a change to a license renewal-related commitment to replace the existing Brunswick Steam Electric Plant (BSEP), Unit 2 core plate plugs prior to entering the period of extended operation authorized by the renewed facility operating licenses. A description of the commitment and reason for the commitment change is provided in Enclosure 1. Enclosure 2 provides Structural Integrity Associates, Inc., Report No. 1000771.402, Revision 0, Life Extension for Core Plate Plugs at Brunswick Steam Electric Plant Unit 2. The revised regulatory commitment is provided in Enclosure 3.
Please refer any questions regarding this submittal to Ms. Annette Pope, Supervisor -
Licensing/Regulatory Programs, at (910) 457-2184.
Sincerely, Phyllis N. Mentel Manager - Support Services Brunswick Steam Electric Plant Progress Energy Carolinas, Inc.
Brunswick Nuclear Plant P.O. Box 10429 Southport, NC 28461
Document Control Desk BSEP 11-0106 /Page 2 WRM/wrm
Enclosures:
- 1. License Renewal Commitment and Basis for Change
- 2. Structural Integrity Associates, Inc. Report No. 1000771.402, Revision 0, Life Extensionfor Core Plate Plugs at Brunswick Steam ElectricPlant Unit 2
- 3. List of Regulatory Commitments cc (with enclosures):
U. S. Nuclear Regulatory Commission, Region II ATTN: Mr. Victor M. McCree, Regional Administrator 245 Peachtree Center Ave, NE, Suite 1200 Atlanta, GA 30303-1257 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 11-0106 Enclosure I Page 1 of 3 License Renewal Commitment and Basis for Change Summary Carolina Power & Light Company (CP&L), now doing business as Progress Energy Carolinas, Inc., is requesting NRC approval of a change to a license renewal-related commitment to replace the existing Brunswick Steam Electric Plant (BSEP), Unit 2 core plate plugs prior to entering the period of extended operation authorized by the renewed facility operating license. The period of extended operation for Unit 2 begins December 28, 2014 (i.e., the original license expiration date for Unit 2 was midnight, Debember 27, 2014).
CP&L attempted to replace the Unit 2 core plate plugs during the 2011 refueling outage, but encountered problems with installing the replacement plugs. CP&L currently plans to replace the Unit 2 core plate plugs during the 2013 refueling outage. This commitment change is being requested as a contingency, in case unforeseen problems occur during the 2013 replacement work that preclude completion of the core plate plug replacement work at that time.
Discussion By letter dated October 18, 2004 (i.e., Reference 1), CP&L submitted an application for renewal of the operating licenses for Brunswick Steam Electric Plant (BSEP), Units I and 2. Section 4.2.8 of the license renewal application provided a time limited aging analysis (TLAA) analyzing stress relaxation of the Unit 2 spring-loaded core plate plugs.
The Unit 2 core plate plugs are fabricated with a nickel-based alloy spring that is subject to loss of preload due to stress relaxation. The Unit I core plate plugs are welded in place and thus are not subject to the spring relaxation concern.
In a response to an NRC request for additional information dated June 14, 2005 (i.e.,
Reference 2), CP&L committed to manage the loss of preload due to stress relaxation of the spring-loaded core plate plugs by replacing the core plate plugs.
Subsequently, in a letter dated July 18, 2005 (i.e., Reference 3), CP&L stated the following:
Based on current fluence projections, the replacement of the spring-loaded core plate plugs installed in Unit 2 will occur during the refueling outage that is currently scheduled for 2011. Any evaluation to extend the service life of the spring-loaded core plate plugs will be submitted to the NRC for review and approval.
BSEP 11-0106 Enclosure 1 Page 2 of 3 The July 18, 2005, letter also revised the License Renewal Commitment for the Reactor Vessel Internals Structural Integrity Program as follows:
Loss of preload due to stress relaxation of the Unit 2 spring-loaded core plate plugs will be managed by replacing the plugs. Any evaluation to extend service life of the spring-loaded core plate plugs will be submitted to the NRC for review and approval.
By letter dated March 31, 2006 (i.e., Reference 4), the NRC issued the final safety evaluation report associated with license renewal of BSEP Units 1 and 2. In the final safety evaluation, the NRC accepted CP&L's commitment to replace the Unit 2 spring-loaded core plate plugs prior to the period of extended operation for Unit 2 and noted any decision to extend the life of the plugs would be evaluated by CP&L and the evaluation would be submitted to the NRC for review and approval (i.e., see page 3-129 of Reference 4). The renewed facility operating licenses for BSEP Units I and 2 were subsequently issued by letter dated June 26, 2006 (Reference 5).
During the 2011 Unit 2 refueling outage, replacement of the Unit 2 core plate plugs was attempted, but problems with the configuration of the replacement plugs prevented them from being installed. As a result, the core plate plug replacements were postponed until the 2013 Unit 2 refueling outage.
CP&L plans to replace the Unit 2 core plate plugs during the 2013 Unit 2 refueling outage. However, as a contingency, in case unforeseen problems occur during the replacement work, CP&L proposes the following change to the core plate plug replacement commitment:
Replacement of the spring-loaded core plate plugs installed in Unit 2 will be completed during the refueling outage currently scheduled for 2013. However, if installation problems preclude completion of the core plate plug replacements during the 2013 refueling outage, replacement of the Unit 2 spring-loaded core plate plugs may be deferred for completion during the refueling outage currently scheduled for 2015. provides Structural Integrity Associates, Inc., Report No. 1000771.402, Revision 0, "Life Extension for Core Plate Plugs at Brunswick Steam Electric Plant Unit 2." This report evaluates core plate plug design life, using plant-specific fluence and reactor pressure vessel pressure differences, and concludes the core plate plugs will remain functional for at least 30 effective full power years (EFPY) of plant operation. As of October 31, 2011, Unit 2 has operated for approximately 25.09 EFPY Continued operation at an assumed 100 percent capacity factor will not result in reaching the 30 EFPY threshold until approximately calendar year 2016. Thus, this demonstrates that degradation of the core plate plugs is not expected to occur during the additional period that may be needed if core plate plug replacement cannot be accomplished during the 2013 Unit 2 refueling outage.
BSEP 11-0106 Enclosure 1 Page 3 of 3 References
- 1. Letter from Cornelius J. Gannon (CP&L) to U.S. NRC Document Control Desk, "Application for Renewal of Operating Licenses," dated October 18, 2004.
- 2. Letter from Cornelius J. Gannon (CP&L) to U.S. NRC Document Control Desk, "Response to Request for Additional Information - License Renewal (NRC TAC Nos. MC4639 and MC4640)," dated June 14, 2005, ADAMS Accession Number ML051720468, RAI B.2.28-5.
- 3. !Letter from Cornelius J. Gannon (CP&L) to U.S. NRC Document Control Desk, "Clarification of Responses to Request for Additional Information - License Renewal (NRC TAC Nos. MC4639 and MC4640)," dated July 18, 2005, ADAMS Accession Number ML052070762.
- 4. Letter from Frank P. Gillespie (NRC) to James Scarola (CP&L), "Final Safety Evaluation Report Related to the License Renewal of Brunswick Steam Electric Plant, Units I and 2 (TAC Nos. MC4639 and MC4640),"dated March 31, 2006, ADAMS Accession Number s ML060890414 and ML060890421.
- 5. Letter from Maurice Heath (NRC) to James Scarola (CP&L), "Issuance of Renewed Facility Operating License Nos. DPR-71 and DPR-62 for Brunswick Steam Electric Plant, Units 1 and 2 (TAC Nos. MC4639 and MC4640)," dated June 26, 2006, ADAMS Accession Numbers ML061660358, ML061660375, ML061660378 and ML061660381.