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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARRA-24-0164, Inservicee Inspection Program Owners Activity Report Refueling Outage 252024-06-19019 June 2024 Inservicee Inspection Program Owners Activity Report Refueling Outage 25 RA-23-0045, Inservice Inspection Program Owner'S Activity Report for Unit 2 Refueling Outage 262023-06-28028 June 2023 Inservice Inspection Program Owner'S Activity Report for Unit 2 Refueling Outage 26 RA-22-0308, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for Inservice Inspection of the Torus Metallic Liner2022-12-16016 December 2022 Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for Inservice Inspection of the Torus Metallic Liner RA-20-0373, Submittal of IWB-3640 Analytical Evaluation of RPV Nozzle N4D Safe End to Pipe Weld Indication2021-01-19019 January 2021 Submittal of IWB-3640 Analytical Evaluation of RPV Nozzle N4D Safe End to Pipe Weld Indication RA-20-0247, Supplement to Proposed Alternative for RPV Nozzle-to-Vessel Weld and Inner Radii Examination Requirements in Accordance with 10 CFR 50.55a(z)(1)2020-07-30030 July 2020 Supplement to Proposed Alternative for RPV Nozzle-to-Vessel Weld and Inner Radii Examination Requirements in Accordance with 10 CFR 50.55a(z)(1) RA-19-0447, Proposed Alternative for RPV Nozzle-to-Vessel Weld and Inner Radii Examination Requirements in Accordance with 10 CFR 50.55a(z)(1)2020-06-23023 June 2020 Proposed Alternative for RPV Nozzle-to-Vessel Weld and Inner Radii Examination Requirements in Accordance with 10 CFR 50.55a(z)(1) RA-19-0256, Submittal of Inservice Inspection Program Owner'S Activity Report for Refueling Outage 242019-06-20020 June 2019 Submittal of Inservice Inspection Program Owner'S Activity Report for Refueling Outage 24 RA-18-0067, Inservice Inspection Program Owner'S Activity Report for Unit 1 Refueling Outage 222018-06-28028 June 2018 Inservice Inspection Program Owner'S Activity Report for Unit 1 Refueling Outage 22 BSEP 18-0014, Fifth 10-Year Inservice Testing Program Plan2018-02-19019 February 2018 Fifth 10-Year Inservice Testing Program Plan 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 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 17-0044, Inservice Inspection Program Owner'S Activity Report for Refueling Outage 222017-05-25025 May 2017 Inservice Inspection Program Owner'S Activity Report for Refueling Outage 22 BSEP 16-0037, Inservice Inspection Program Owner'S Activity Report for Unit 1 Refueling Outage 212016-05-18018 May 2016 Inservice Inspection Program Owner'S Activity Report for Unit 1 Refueling Outage 21 BSEP 15-0051, Inservice Inspection Program Owner'S Activity Report for Refueling Outage 212015-06-29029 June 2015 Inservice Inspection Program Owner'S Activity Report for Refueling Outage 21 BSEP 13-0089, Inservice Inspection Program Owner'S Activity Report for Refueling Outage 202013-08-0606 August 2013 Inservice Inspection Program Owner'S Activity Report for Refueling Outage 20 BSEP 12-0086, Inservice Inspection Program Owner'S Activity Report for Unit I Refueling Outage 182012-07-25025 July 2012 Inservice Inspection Program Owner'S Activity Report for Unit I Refueling Outage 18 BSEP 11-0060, Inservice Inspection Program Owner'S Activity Report for Unit 2 Refueling Outage 192011-06-17017 June 2011 Inservice Inspection Program Owner'S Activity Report for Unit 2 Refueling Outage 19 BSEP 11-0027, Response to Request for Additional Information Regarding Proposed Alternatives for the Third 10-Year Inservice Inspection Program2011-02-28028 February 2011 Response to Request for Additional Information Regarding Proposed Alternatives for the Third 10-Year Inservice Inspection Program BSEP 11-0011, Response to Request for Additional Information - Proposed Alternatives for the Third 10-Year Inservice Inspection Program2011-01-28028 January 2011 Response to Request for Additional Information - Proposed Alternatives for the Third 10-Year Inservice Inspection Program BSEP 10-0043, Proposed Alternatives for the Third 10-Year Inservice Inspection Program2010-07-23023 July 2010 Proposed Alternatives for the Third 10-Year Inservice Inspection Program BSEP 10-0091, Inservice Inspection Program Owner'S Activity Report, Refueling Outage 172010-07-23023 July 2010 Inservice Inspection Program Owner'S Activity Report, Refueling Outage 17 BSEP 09-0125, Response to Request for Additional Information Regarding Third 10-Year Inservice Inspection Interval Request for Relief RR-462009-12-0202 December 2009 Response to Request for Additional Information Regarding Third 10-Year Inservice Inspection Interval Request for Relief RR-46 BSEP 09-0078, Submittal of Inservice Inspection Program Owner'S Activity Report, Refueling Outage 182009-07-28028 July 2009 Submittal of Inservice Inspection Program Owner'S Activity Report, Refueling Outage 18 BSEP 09-0043, Submittal of Proposed Alternative for the Third 10-Year Inservice Inspection Program2009-05-0808 May 2009 Submittal of Proposed Alternative for the Third 10-Year Inservice Inspection Program BSEP 09-0024, Proposed Alternative for the Third 10-Year Inservice Inspection Program2009-04-27027 April 2009 Proposed Alternative for the Third 10-Year Inservice Inspection Program BSEP 08-0140, Proposed Alternative for Reactor Vessel Skirt Support Examinations2008-10-10010 October 2008 Proposed Alternative for Reactor Vessel Skirt Support Examinations BSEP 08-0109, Owner'S Activity Report for Third 10-Year Inservice Inspection Program2008-08-26026 August 2008 Owner'S Activity Report for Third 10-Year Inservice Inspection Program BSEP 08-0062, Inservice Inspection Plan for the Fourth 10-Year Inspection Interval2008-05-21021 May 2008 Inservice Inspection Plan for the Fourth 10-Year Inspection Interval BSEP 07-0110, BNP-TR-014, Rev. 1, IST Program Plan Fourth Ten-Year Inspection Interval.2007-10-25025 October 2007 BNP-TR-014, Rev. 1, IST Program Plan Fourth Ten-Year Inspection Interval. BSEP-07-0063, Inservice Inspection Program for the Third 10-Year Interval - Refueling Outage 17 Owner'S Activity Report2007-07-16016 July 2007 Inservice Inspection Program for the Third 10-Year Interval - Refueling Outage 17 Owner'S Activity Report BSEP-06-0066, Inservice Inspection Program for the Third 10-Year Interval - Refueling Outage 15 Owner'S Activity Report2006-06-26026 June 2006 Inservice Inspection Program for the Third 10-Year Interval - Refueling Outage 15 Owner'S Activity Report BSEP 03-0137, Inservice Inspection Program for the Third 10-Year Interval-Refueling Outage 15 (B216R1) Owner'S Activity Report2003-10-20020 October 2003 Inservice Inspection Program for the Third 10-Year Interval-Refueling Outage 15 (B216R1) Owner'S Activity Report BSEP 02-0102, Inservice Inspection Program for Third 10-Year Interval - Evaluation of Leakage at Bolted Connections2002-05-20020 May 2002 Inservice Inspection Program for Third 10-Year Interval - Evaluation of Leakage at Bolted Connections 2024-06-19
[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
[Table view] |
Text
.1 Progress Energy 10 CFR 50.55a(g)(5)(iii)
MAY 08 2009 SERIAL: BSEP 09-0043 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 Proposed Alternative for the Third 10-Year Inservice Inspection Program Ladies and Gentlemen:
This letter submits arequest, in accordance with 10 CFR 50.55a(g)(5)(iii), to use a proposed alternative to the applicable edition of the American Society of Mechanical Engineers (ASME) Code,Section XI for the Brunswick Steam Electric Plant (BSEP),
Units 1 and 2, on the basis that compliance with the specified requirements is impractical due to plant design. Carolina Power & Light Company (CP&L), now doing business as Progress Energy Carolinas, Inc., is submitting this relief request for ASME Code,Section XI control rod drive housing weld examinations performed during the third 10-year inservice inspection interval where the inspection coverage achieved was less than 100 percent due to physical obstructions and geometric interferences.
The relief request supports the third 10-year inservice inspection interval for both BSEP, Unit 1 and Unit 2. The third 10-year inservice inspection interval began on May 11, 1998.
As allowed by sub-article IWA-2430(d) of the ASME Code,'Section XI, the third 10-year inspection interval for Unit 2 was extended for one year. This extension enabled the examination of Unit 2 components to coincide with the B219R1 refueling outage, which began February 28, 2009. As such, the third 10-year inspection interval for BSEP, Unit 2 will conclude on May 10, 2009, and the third 10-year inspection interval for BSEP, Unit 1 concluded on May 10, 2008.
CP&L requests approval of this relief request by April 30, 2010.
Progress Energy Carolinas, Inc.
Brunswick Nuclear Plant PO Box 10429 Southport, NC 28461
Document Control Desk BSEP 09-0043 / Page 2 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
Enclosures:
10 CFR 50.55a Request Number RR-46
Document Control Desk BSEP 09-0043 / Page 3 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 Mr. Jack M. Given, Jr., Bureau Chief North Carolina Department of Labor Boiler Safety Bureau 1101 Mail Service Center Raleigh, NC 27699-1101 V
BSEP 09-0043 Enclosure Page 1 of 8 10 CFR 50.55a Request Number RR-46 Proposed Alternative In Accordance with 10 CFR 50.55a(g)(5)(iii)
- Inservice Inspection Impracticality -
- 1. ASME Code Components Affected Code Class: I
References:
Subarticle IWB-2500, Table IWB-2500-1 Examination Categories: B-O, "Pressure Retaining Welds in Control Rod Housings" Item Numbers: B 14.10, "Welds in CRD Housing"
Description:
Volumetric Examination Coverage Component Numbers: ICI 1-CRD06-11-SW1 CRD Housing Weld ICI I-CRD06-15-SWI CRD Housing Weld IC II -CRD 10-07-SW I CRD Housing Weld IC 11 -CRD 14-07-SW 1 CRD Housing Weld 2C1 1-CRD38-47-SW1 CRD Housing Weld 2C 1 I-CRD42-47-SW1 CRD Housing Weld 2C 11-CRD46-39-SWl CRD Housing Weld 2C 11-CRD46-43-SW1 CRD Housing Weld
2. Applicable Code Edition and Addenda
The Inservice Inspection Program for the third 10-year inservice inspection interval was based on the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, 1989 Edition with no Addenda.
3. Applicable Code Requirement
Sub-article IWB-2500, Table IWB-2500-1, requires essentially 100 percent volumetric or surface examination of 10 percent of the peripheral control rod drive (CRD) housing welds (Examination Category B-O, Item No. B14.10, as defined by Figure IWB-2500-18).
Carolina Power & Light Company (CP&L), now doing business as Progress Energy Carolinas, Inc., elected to perform surface examinations on the selected CRD housing welds.
- 4. Impracticality of Compliance In accordance with 10 CER 50.55a(g)(5)(iii), relief is requested from the requirement of the ASME Code,Section XI, Sub-article IWB-2500, Table IWB-2500-1 (Volumetric or Surface
BSEP 09-0043 Enclosure Page 2 of 8 Examination Category B-O, "Pressure Retaining Welds in Control Rod Drive Housings"),
Examination Item Number B 14.10, "Welds in CRD Housing." Limited accessibility for the 36 peripheral CRD housing welds is due to the close proximity of adjacent CRD housing flanges, neutron monitoring instrumentation and associated cabling, and horizontal beams, support bars and grids.
- 5. Burden Caused by Compliance Compliance with the examination coverage requirements of the ASME Code,Section XI, would require modification, redesign, or replacement of components where geometry is inherent to the component design.
- 6. Proposed Alternative and Basis for Use Proposed Alternative In accordance with 10 CFR 50.5 5a(g)(5)(iii), CP&L is requesting relief for the components listed above on the basis that the required examination coverage of "essentially 100 percent" is impractical due to physical obstructions and severely limited access in the work area. As an alternative, CP&L proposes selecting the four. additional upper CRD housing welds, listed" below, in lieu of the four lower housing-to-flange welds. This would provide the same total number of CRD housing welds for examination (i.e., eight welds) and will be an equivalent 100 percent inspection of 10 percent of the peripheral housings.
Unit 1 Additional CRD Unit 2 Additional CRD Housing Weld Examinations Housing Weld Examinations 1C 11-CRD38-47-SW2 2C 11-CRD06-11 -SW2 IC 11-CRD42-47-SW2 2C 11-CRD06-15-SW2 IC 11-CRD46-39-SW2 2C 11-CRD1O-07-SW2 iC 11-CRD46-43-SW2 2C 11-CRD 14-07-SW2 Basis for Use The ASME Code,Section XI, Sub-article IWB-2500, Table IWB-2500-1, requires essentially 100 percent volumetric or surface examination of 10 percent of the peripheral CRD housing welds (Examination Category B-O, Item No. B 14.10, as defined by Figure IWB-2500-18).
Each CRD housing contains two pressure retraining welds. Table IWB-2500-1 requires both the upper and lower welds of each of the selected CRD housings to be examined.
BSEP 09-0043 Enclosure Page 3 of 8 BSEP has 36 peripheral CRD housings; therefore, this requires four CRD housings (i.e., a total of eight CRD housing welds) to be examined. As previously stated, each CRD housing contains two pressure retaining welds: the housing-to-flange weld and the housing tube-to-tube weld. The housing-to-flange weld is located in the inaccessible lower section of the CRD housing, whereas the housing tube-to-housing tube weld is located in the accessible upper section of the CRD housing (i.e., shown on Drawings 0-FP-05609; C-24004, Sheet 26-1; and C-02404, Sheet 26-1; provided in Attachments 1, 2, and 3, respectively).
Limited access for the 36 peripheral CRD housing-to-flange weld welds is due to the work area under the reactor vessel being highly congested, as shown in the photographs in . Physical obstructions imposed by design, geometry, and materials of construction include vessel appurtenances, insulation support rings, structural and component supports, adjacent CRD housing flanges, and neutron monitoring instrumentation and associated cabling. These obstructions are not practical to remove or replace to achieve 100 percent volumetric or surface coverage of the welds in the CRD housings. The upper housing welds are without obstruction and can be completely examined.
Therefore, as an alternative, CP&L proposes selecting four additional upper CRD housing welds in lieu of the four lower housing-to-flange welds. This would provide the same total number of CRD housing welds for examination (i.e., eight welds).
CP&L performed qualified surface examinations that achieved the maximum, practical amount of coverage obtainable within the limitations imposed by the design of the components. The examinations conducted confirmed satisfactory results, with no unacceptable flaws being identified and no evidence of degradation mechanisms.
Percent of Code-Required Volume Achieved Original Sample Additional Sample IC I I-CRD06- 11 -SW2 100% Coverage Achieved 1CII -CRD3 8-47-SW2 100% Coverage Achieved ICI I-CRD06-15-SW2 100% Coverage Achieved C II-CRD42-47-SW2 100% Coverage Achieved ICI I-CRDI0-07-SW2 100% Coverage Achieved IC 11-CRD46-39-SW2 100% Coverage Achieved ICI I-CRD14-07-SW2 100% Coverage Achieved IC 1-CRD46-43-SW2 100% Coverage Achieved 2C1 1-CRD38-47-SW2 100% Coverage Achieved 2C1 I-CRD06-1 1-SW2 100% Coverage Achieved 2C1I-CRD42-47-SW2 100% Coverage Achieved 2C I-CRD06-15-SW2 100% Coverage Achieved 2CI I-CRD46-39-SW2 100% Coverage Achieved 2CI I-CRDI0-07-SW2 100% Coverage Achieved 2C II-CRD46-43-SW2 100% Coverage Achieved 2C1 1-CRD14-07-SW2 100% Coverage Achieved As Class 1 Examination Category B-O components, a visual (VT-2) examination is also performed on these components during system pressure tests each refueling outage. This was completed during the Unit 1 2008 refueling outage (i.e., the BI 17R1 outage) and Unit 2 2009 refueling outage (i.e., the B219R1 outage), and no evidence of leakage was identified for these components. Reactor coolant system leak rate limitations and atmospheric particulate radioactivity monitoring also ensure that any leakage would be detected prior to gross failure.
BSEP 09-0043 Enclosure Page 4 of 8
- 7. Duration of the Proposed Alternative Use of the proposed alternative is applicable to the third 10-year inservice inspection interval at BSEP, Units 1 and 2. The third 10-year interval began on May 11, 1998, and ended on May 10, 2008, for Unit 1 and will end on May 10, 2009, for Unit 2.
- 8. Precedents Similar relief request was granted for the Pilgrim Nuclear Power Station, as listed in Reference 1.
- 9. References
- 1. Letter from U.S. Nuclear Regulatory Commission (USNRC) to Entergy Nuclear Operations, Inc., Third 10-Year Interval Inservice Inspection Program Plan Request for Relief Request No. PRR-42, Revision 1 - Pilgrim Nuclear Power Station (TAC No. MD6767), dated June 27, 2008, ADAMS Accession Number ML081300415.
BSEP 09-0043 Enclosure Page 5 of 8 ATTACHMENT 1
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BSEP 09-0043 Enclosure Page 8 of 8 ATTACHMENT 4 Figure 1 - Under-Vessel Area Figure 2 - Under-Vessel Area, Looking Upwards