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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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Brunswick Nuclear Plant P.O. Box 10429 ENERGY, Southport, NC 28461 MAY 2 1 2014 Serial: BSEP 14-0056 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Subject:
Brunswick Steam Electric Plant, Unit Nos. 1 and 2 Renewed Facility Operating License Nos. DPR-71 and DPR-62 Docket Nos. 50-325 and 50-324 Response to Request for Additional Information License Renewal Commitment Completion Evaluation of Operating Experience at Extended Power Uprate Conditions
References:
- 1. Letter from Annnette H. Pope (Duke Energy Progress, Inc.) to U.S. Nuclear Regulatory Commission (Serial: BSEP 13-0137), License Renewal Commitment Completion Evaluation of OperatingExperience at Extended Power Uprate Conditions,dated December 17, 2013, ADAMS Accession No. ML14023A594
- 2. Electronic Mail from Siva Lingam (U.S. Nuclear Regulatory Commission) to William R.
Murray (Duke Energy Progress, Inc.), Brunswick I and 2 - Request for Additional Information (RAI) Regarding License Renewal Commitment Completion of Evaluation of OperatingExperience at Extended Power Uprate Conditions, dated April 25, 2014, ADAMS Accession No. ML14115A443
- 3. NUREG-1 856, Safety Evaluation Report Related to the License Renewal of the Brunswick Steam Electric Plant, Units I & 2, published June 2006, ADAMS Accession Nos. ML061730123 and ML061730129 Ladies and Gentlemen:
On December 17, 2013 (i.e., Reference 1) Duke Energy Progress, Inc., informed the NRC of the completion of a license renewal commitment (i.e., Commitment Number 31 in Appendix A of NUREG-1856), for the Brunswick Steam Electric Plant (BSEP), Units 1 and 2. The commitment was to perform an evaluation of plant and industry operating experience to assure that relevant aging effects caused by operation at power uprate conditions are adequately addressed by aging management programs. Subsequently, on April 25, 2014 (i.e., Reference 2), the NRC provided an electronic version of a Request for Additional Information (RAI) concerning closure of this commitment. The response to this RAI is enclosed.
This document contains no new regulatory commitments.
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U.S. Nuclear Regulatory Commission Page 2 of 2 Please refer questions regarding this submittal to Mr. Lee Grzeck, Manager - Regulatory Affairs, at (910) 457-2487.
Sincerely, Annette H. Pope Director - Organizational Effectiveness Brunswick Steam Electric Plant MAT/mat
Enclosure:
Response to Request for Additional Information cc:
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. Andrew Hon (Mail Stop OWFN 8G9A) (Electronic Copy Only) 11555 Rockville Pike Rockville, MD 20852-2738 U. S. Nuclear Regulatory Commission ATTN: Ms. Michelle P. Catts, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 Chair - North Carolina Utilities Commission P.O. Box 29510 Raleigh, NC 27626-0510
Enclosure Page 1 of 3 Response to Request for Additional Information
Background
On December 17, 2013 (i.e., Serial: BSEP 13-0137) Duke Energy Progress, Inc., informed the NRC of the completion of a license renewal commitment (i.e., Commitment Number 31 in Appendix A of NUREG-1856), for the Brunswick Steam Electric Plant (BSEP), Units 1 and 2.
Commitment 31 states:
An evaluation of plant and industry operating experience will be submitted for NRC review at least one year prior to the period of extended operation. The purpose of the evaluation will be to assure that relevant aging effects caused by operation at power uprate conditions are adequately addressed by aging management programs.
Subsequently, on April 25, 2014, the NRC provided an electronic version of a Request for Additional Information (RAI) concerning closure of this commitment. The response to this RAI follows.
NRC RAI The commitment states that the licensee would evaluate both plant-specific and industry operating experience. However, the review methodology described in the licensee's submittal only discusses consideration of industry operating experience. As such, the scope of the licensee's review does not fully address the intent of the commitment.
Describe the evaluation of plant-specific operating experience to ensure that the aging management programs adequately address aging effects caused by operation at extended power uprate conditions. In this description, address:
(a) the specific sources of information that were reviewed, (b) the evaluation methodology and rationale for attributing the operating experience to operation at power uprate conditions, (c) the results of the review including any relevant items that were found and the actions that were or will be taken in response.
Response
Plant-specific operating experience (OE) to ensure that the appropriate aging management programs adequately address aging effects potentially caused by operation at extended power uprate (EPU) conditions was included in a 2013 detailed evaluation performed by BSEP plant personnel. That is, BSEP events were not excluded from the OE generated from multiple sources for this evaluation. The following describes, in more detail, some plant-specific examples in response to items (a), (b) and (c) above:
(a) The specific sources of information reviewed for plant-specific events were primarily from a review of the Institute for Nuclear Power Operations (INPO) Operating Experience (OE), Electric Power Research Institute (EPRI) Power Plant Uprate Database, and the Boiling Water Reactor Vessel Internals Project (BWRVIP) Uprate database, which included OE from BSEP. These searches did not exclude BSEP from the population. Plant-specific events that require an extent of condition between BSEP
Enclosure Page 2 of 3 Units 1 and 2, and/or a determination of internal and external OE is included in the BSEP Corrective Action Program. From a plant-specific perspective, this adequately addresses aging effects potentially caused by operation at EPU conditions due to newly discovered events since EPU was implemented at BSEP. For example, a feedwater (FW) corrosion sampling probe was found in a FW sparger at BSEP Unit 2 during the March 2011 in-vessel visual inspection. A potential contributing cause of the FW sampling probe breaking and transporting to the FW sparger was higher FW flow rate due to EPU. Damage to the FW sparger was evaluated by engineering and actions were taken to find and remove the sampling probe in BSEP Unit 1 during the next refuel outage in March 2012. The Unit 1 probe was also found to be broken. Although the FW sampling probes are not within the scope of License Renewal, the failure of these components impacted the downstream FW spargers, which are within the scope of License Renewal.
Another source of information for plant-specific OE was based on plant-specific BWRVIP Review Visit recommendations by INPO for relevant aging caused by operation at EPU.
BWRVIP review visits by INPO were conducted during October 2006 and November 2010. Plant-specific actions were entered into the Corrective Action Program based on these INPO review visits for any items related to EPU. For example, in the 2006 INPO final report, the only EPU-related recommendation for improvement was cited as follows:
Steam dryer locations that have experienced flaws in the industry should be inspected or dispositioned by the station. BWRVIP-139 outlines high-stress locations and locations that have experienced flaws. General Electric (GE)
Service Information Letter (SIL)-644 recommends that after a power uprate, both of these types of susceptible locations be inspected for two refueling outages following uprate. BWRVIP-139 does not give re-inspection or uprate guidance but suggests that the guidance of SIL-644 be followed. The station has done extensive inspections of the high-stress welds but has not re-inspected the locations that have failed in the industry after power uprates.
The detailed evaluation discusses plant-specific actions taken, including re-inspection plans, with regards to steam dryer inspections and monitoring and enhancements to the applicable aging management program.
In the 2010 INPO final report, the only EPU-related recommendation for improvement was cited as follows:
Since implementation of extended power uprates (EPUs) in 2003 and 2004, Units 1 and 2 have not met BWRVIP monitoring guidance to ensure sufficient chemical mitigation. Units 1 and 2 had previously used a sister plant as the primary mitigation parameter, but when EPU was implemented, the sister plant concept was invalidated. Without a sister plant, an [electrochemical corrosion potential] ECP probe is the only primary parameter that can be used to correlate secondary parameters.
BSEP is currently implementing the INPO recommendations for improvement to install ECP probes in the reactor vessel's lower plenum region. In March 2014, the ECP probes were installed in BSEP Unit 1 and will be installed in BSEP Unit 2 in March 2015.
Enclosure Page 3 of 3 (b) The evaluation methodology consisted of a determination of which EPU-related OE had components within the scope of License Renewal, which again included BSEP plant-specific OE. It was determined that the plant-specific components at BSEP within the scope of License Renewal with EPU-related OE were the steam dryer, core shroud head assembly/steam separator, jet pumps, and FW sparger end brackets. The rationale for attributing the OE to operation at EPU conditions, as described in the 2013 detailed evaluation, is as follows:
Keywords "FLY", "fatigue", "vibration", "EPU", "Uprate", "Dryer" and "Jet Pump" were used to assist in screening the OE events. Not all of the events tabulated were attributed to post-EPU; however, these were determined to be applicable to those components within the scope of License Renewal that are susceptible to potential increases in flow induced vibration and wear due to EPU. Thus, they were considered as applicable OE for the purposes of the evaluation.
(c) The results of the review performed in support of this RAI response did not add any relevant items not already included in the detailed evaluation completed by BSEP in August 2013, which was summarized in the letter submitted to NRC in December 2013 (i.e., Serial: BSEP 13-0137). There were no BSEP-specific events that impact the results and conclusions of the original BSEP detailed evaluation. Therefore, BSEP concludes that the commitment to perform an evaluation of plant and industry operating experience, to assure that relevant aging effects caused by operation at power uprate conditions are adequately addressed by aging management programs, has been satisfactorily met.