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Category:Letter
MONTHYEARIR 05000334/20240052024-08-29029 August 2024 Updated Inspection Plan for Beaver Valley Power Station, Units 1 and 2 (Reports 05000334/2024005 and 05000412/2024005) L-24-188, Submittal of Quality Assurance Program Manual, Revision 302024-08-27027 August 2024 Submittal of Quality Assurance Program Manual, Revision 30 IR 05000334/20244022024-08-22022 August 2024 Security Baseline Inspection Report 05000334/2024402 and 05000412/2024402 (Cover Letter Only) IR 05000334/20240102024-08-20020 August 2024 Comprehensive Engineering Team Inspection - Inspection Report 05000334/2024010 and 05000412/2024010 IR 05000334/20240022024-08-0505 August 2024 Integrated Inspection Report 05000334/2024002 and 05000412/2024002 ML24208A0462024-07-26026 July 2024 NRC Office of Investigations Case No. 1-2023-005 L-24-182, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-07-23023 July 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-24-161, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-07-19019 July 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-24-014, Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling Svstem Evaluation Models2024-07-16016 July 2024 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling Svstem Evaluation Models ML24193A2912024-07-16016 July 2024 Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule IR 05000334/20245012024-07-0808 July 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000334/2024501 and 05000412/2024501 L-24-164, BV-2, Post Accident Monitor Report2024-06-27027 June 2024 BV-2, Post Accident Monitor Report IR 05000334/20244012024-06-26026 June 2024 Material Control and Accounting Program Inspection Report 05000334/2024401 and 05000412/2024401 (Cover Letter Only) L-24-094, Reactor Vessel Surveillance Capsule Withdrawal Schedule2024-06-24024 June 2024 Reactor Vessel Surveillance Capsule Withdrawal Schedule L-24-152, Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations2024-06-17017 June 2024 Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations ML24135A1702024-05-29029 May 2024 – Steam Generator Tube Inspection - Review of the Spring 2023 Tube Inspection Reports ML24135A2282024-05-29029 May 2024 Review of the Spring 2023 Outage Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F Star Reports L-24-021, Cycle 30 Core Operating Limits Report2024-05-23023 May 2024 Cycle 30 Core Operating Limits Report L-24-121, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-05-23023 May 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 ML24141A1052024-05-20020 May 2024 Senior Reactor and Reactor Operator Initial License Examinations L-24-107, CFR 50.55a Request 1-TYP-5-RRP-l, for Alternative Method of Nondestructive Examination for River Water Outlet Piping Weld Repair2024-05-13013 May 2024 CFR 50.55a Request 1-TYP-5-RRP-l, for Alternative Method of Nondestructive Examination for River Water Outlet Piping Weld Repair IR 05000334/20240012024-05-0808 May 2024 Integrated Inspection Report 05000334/2024001 and 05000412/2024001 L-23-269, Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions2024-05-0707 May 2024 Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions L-24-054, Submittal of 2023 Annual Radioactive Effluent Release Report 2023 Annual Radiological Environmental Operating Report and 2023 Annual Environmental Operating Report (Non-Radiological)2024-04-29029 April 2024 Submittal of 2023 Annual Radioactive Effluent Release Report 2023 Annual Radiological Environmental Operating Report and 2023 Annual Environmental Operating Report (Non-Radiological) L-24-089, Emergency Preparedness Plan2024-04-23023 April 2024 Emergency Preparedness Plan L-24-088, Discharge Monitoring Report (NPDES) Permit No. PA0025615 for March 20242024-04-22022 April 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 for March 2024 ML24101A2752024-04-10010 April 2024 Response to Request for Additional Information Regarding Spring 2023 180-Day Steam Generator Tube Inspection Report L-24-082, Withdrawal of Exemption Request2024-04-0303 April 2024 Withdrawal of Exemption Request L-24-013, Annual Notification of Property Insurance Coverage2024-03-26026 March 2024 Annual Notification of Property Insurance Coverage L-24-064, Submittal of Discharge Monitoring Report (NPDES) Permit No. PA00256152024-03-13013 March 2024 Submittal of Discharge Monitoring Report (NPDES) Permit No. PA0025615 ML24044A0662024-03-0404 March 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0083 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML24057A0752024-03-0101 March 2024 the Associated Independent Spent Fuel Storage Installations IR 05000334/20230062024-02-28028 February 2024 Annual Assessment Letter for Beaver Valley Power Station, Units 1 and 2 (Reports 05000334/2023006 and 05000412/2023006) CP-202300502, Notice of Planned Closing of Transaction and Provision of Documents to Satisfy Order Conditions2024-02-23023 February 2024 Notice of Planned Closing of Transaction and Provision of Documents to Satisfy Order Conditions L-24-050, Retrospective Premium Guarantee2024-02-22022 February 2024 Retrospective Premium Guarantee IR 05000334/20230042024-02-12012 February 2024 Integrated Inspection Report 05000334/2023004 and 05000412/2023004 ML24025A0922024-01-25025 January 2024 Requalification Program Inspection L-23-267, Submittal of Discharge Monitoring Report (Npdes), Permit No. PA00256152023-12-18018 December 2023 Submittal of Discharge Monitoring Report (Npdes), Permit No. PA0025615 IR 05000334/20230112023-12-0404 December 2023 Age-Related Degradation Inspection Report 05000334/2023011 and 05000412/2023011 L-23-229, Request for Additional Information Regarding the Spring 2023 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F-Star Reports2023-11-29029 November 2023 Request for Additional Information Regarding the Spring 2023 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F-Star Reports IR 05000334/20233012023-11-27027 November 2023 Initial Operator Licensing Examination Report 05000334/2023301 L-23-247, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-11-17017 November 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 IR 05000334/20230032023-11-0606 November 2023 Integrated Inspection Report 05000334/2023003 and 05000412/2023003 L-23-227, Discharge Monitoring Report (NPDES) Permit No. PA0025615 for Third Quarter 20232023-10-20020 October 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 for Third Quarter 2023 ML23279A0612023-10-0505 October 2023 Paragon Energy Solutions LLC, Part 21 Final Report Re Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) ML23198A3592023-10-0202 October 2023 Issuance of Amendment Nos. 322 and 212 Analytical Methodology to the Core Operating Limits Report for a Full Spectrum Loss of Coolant Accident (EPID L-2022-LLA-0129) - Nonproprietary IR 05000334/20234022023-09-29029 September 2023 Security Baseline Inspection Report 05000334/2023402 and 05000412/2023402 (Cover Letter Only) ML23237B4222023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Letter Regarding Order Approving Transfer of Licenses and Draft Conforming License Amendments ML23269A1242023-09-27027 September 2023 Request for Withholding Information from Public Disclosure IR 05000334/20234012023-09-21021 September 2023 Cybersecurity Inspection Report 05000334/2023401 and 05000412/2023401 (Cover Letter Only) 2024-08-05
[Table view] Category:Safety Evaluation
MONTHYEARML24193A2912024-07-16016 July 2024 Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule ML23198A3592023-10-0202 October 2023 Issuance of Amendment Nos. 322 and 212 Analytical Methodology to the Core Operating Limits Report for a Full Spectrum Loss of Coolant Accident (EPID L-2022-LLA-0129) - Nonproprietary ML23237B4282023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Enclosure 2, Draft Conforming License Amendments ML23237B4302023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Enclosure 4, Safety Evaluation for Transfer of Licenses and Draft Conforming License Amendments (EPID L-2023-LLM-0000) (Public) ML23249A1842023-09-18018 September 2023 Authorization and Safety Evaluation for Alternative Request No. 2-TYP-4-RV-06 ML23188A0982023-07-17017 July 2023 Correction to the Safety Evaluation Issued Related to Amendment Nos. 321 and 211 Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time ML23102A1472023-05-22022 May 2023 Issuance of Amendment Nos. 321 and 211 Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time ML23019A0032023-03-16016 March 2023 Issuance of Amendment Nos. 320 and 210 Adoption of Technical Specifications Task Force (Tstf) Traveler Tstf-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML23062A5212023-03-0606 March 2023 Issuance of Amendment No. 319 Revise Technical Specification (TS) 3.5.2, ECCS Operating, Limiting Condition for Operation (LCO) 3.5.2, ML22277A8142022-10-0707 October 2022 Correction of Errors in Safety Evaluation Associated with License Amendment Nos. 315 and 205 Regarding Changes to the Emergency Preparedness Plan ML22210A0102022-09-16016 September 2022 Energy Harbor Fleet- Issuance of Amendments Regarding Adoption of TSTF 554, Revise Reactor Coolant Leakage Requirements ML22235A7672022-09-0101 September 2022 Correction of Errors in Safety Evaluation Associated with License Amendment Nos. 315 and 205 Regarding Changes to the Emergency Preparedness Plan ML22222A0862022-09-0101 September 2022 Issuance of Amendment Nos. 317 and 208 Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start and Bus Separation Instrumentation ML22202A4642022-06-29029 June 2022 Emergency Plan Safety Evaluation ML22140A2092022-06-28028 June 2022 Issuance of Amendment No. 207 Correct TS 3.1.7 Change Made by TSTF-547 ML22095A2352022-05-10010 May 2022 Issuance of Amendment Nos. 316 and 206 Revise Technical Specification 5.6.3, Core Operating Limits Report (COLR) ML21286A7822022-05-0606 May 2022 Issuance of Amendment Nos. 315 and 205 Regarding Changes to the Emergency Plan ML22077A1342022-05-0202 May 2022 Issuance of Amendment Nos. 314 and 204 Revise Technical Specifications to Adopt TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ML22082A2532022-03-29029 March 2022 Correction Letter - Issuance of Authorization of Proposed Alternative to Use ASME OM Code Case OMN-27 ML22012A2972022-01-21021 January 2022 Proposed Alternative to Use ASME OM Code Case OMN-27 ML21197A0092021-11-0101 November 2021 Issuance of Amendment Nos. 313 and 203 Reactor Coolant System, Pressure and Temperature Limits Report ML21214A2752021-10-15015 October 2021 Issuance of Amendment Nos. 312 and 202 Atmospheric Dump Valves ML21153A1762021-06-30030 June 2021 Issuance of Amendment No. 201 Revision of Technical Specifications Related to Steam Generator Tube Inspection, and Repair Methods ML21075A1132021-04-16016 April 2021 Issuance of Amendment Nos. 311, 200, and 302 to Incorporate the Applicable Standard Technical Specification 5.2.2, Unit Staff, Into the Technical Specifications ML21070A0002021-03-22022 March 2021 Issuance of Amendment 310, Revise Technical Specification 5.5.5.1, Unit 1 SG Program, to Defer Spring 2021 Refueling Outage Steam Generator Inspections to Fall 2022 Refueling Outage ML20346A0222021-03-10010 March 2021 Issuance of Amendment Nos. 309 and 199 to Change Technical Specifications to Implement New Surveillance Methods for the Heat Flux Hot Channel Factor ML20335A0522021-02-18018 February 2021 Issuance of Amendment Nos. 308 and 198 to Modify Certified Fuel Handler Related Technical Specifications for Permanently Defueled Condition ML20345A2362021-01-28028 January 2021 Issuance of Amendment Nos. 307 and 197 to Add Containment Sump Technical Specifications to Address GSI-191 Issues ML20335A0232020-12-28028 December 2020 Issuance of Amendment Nos. 306 and 196 to Remove License Conditions B and C Related to the Irradiated Fuel Management Plans ML20285A2662020-10-21021 October 2020 Correction to Safety Evaluation for Amendment Nos. 305 and 195 Issued September 23, 2020, Modify Primary and Secondary Coolant Activity Technical Specifications ML20279A4402020-10-0808 October 2020 Energy Harbor Fleet-Beaver Valley Power Station; Davis-Besse Nuclear Power Station, and Perry Nuclear Power Plant - Request to Use a Provision of a Later Edition of the ASME Engineers Boiler and Pressure Vessel Code, Section XI ML20213A7312020-09-23023 September 2020 Issuance of Amendment Nos. 305 and 195 to Modify Primary and Secondary Coolant Activity Technical Specifications ML20223A0142020-08-20020 August 2020 Issuance of Relief Request SSR-1, Revision 0, from the Requirements of the ASME Code (EPID L-2020-LLR-0050 (COVID-19)) ML20206K8652020-08-0707 August 2020 Relief Requests 2-TYP-4-RV-06 and 2-TYP-4-RV-07 from the Requirements of the ASME Code (EPID L-2020-LLR-0053 and EPID L-2020-LLR-0054 (COVID-19)) ML20153A0142020-07-16016 July 2020 Relief from the Requirements of the American Society of Mechanical Engineers Code Regarding Request VRR4 (EPID L-2020-LLR-0052 (COVID-19)) ML20145A0002020-06-0303 June 2020 Relief from the Requirements of the ASME Code for Requests VRR6 and VRR5 (EPID L-2020-LLR-0049 and EPID L-2020-LLR-0051 (COVID-19)) ML20080J7892020-04-28028 April 2020 Relief Requests 2 TYP-3-B3.110-1, 2-TYP-3-C2.21-1, 2-TYP-3-C1.30-1, and 2-TYP-3-RA-1 Regarding Weld Examination Coverage for the Third Inservice Inspection Interval ML20079F8162020-03-26026 March 2020 Relief Requests 1-TYP-4-C2.21-1 and 1-TYP-4-RA-1 Regarding Weld Examination Coverage for the Fourth Inservice Inspection Interval ML19336A0282019-12-18018 December 2019 Safety Evaluation Irradiated Fuel Management Plans ML19305B1312019-12-0202 December 2019 Firstenergy Nuclear Operating Company - Enclosure 6, Non-Proprietary Safety Evaluation, Direct and Indirect Transfer of Licenses and Draft Conforming Amendments for Beaver Valley Units 1 and 2, Davis-Besse Unit 1, and Perry Unit 1 ML19275E2942019-10-16016 October 2019 Issuance of Relief Request Proposed Alternative to Reactor Vessel Nozzle Weld Examination Frequency Requirements in Lieu of Specific ASME Code Requirements ML19028A0302019-04-11011 April 2019 FENOC - Beaver Valley Power Station, Unit 1 & 2; Davis-Besse Nuclear Power Station Unit 1; and Perry Nuclear Power Plant Unit 1 - Approval of Certified Fuel Handler Training and Retraining Program ML18348B2062019-02-25025 February 2019 Issuance of Amendment No. 193 Revise Steam Generator Technical Specifications ML18249A1692018-09-0707 September 2018 Seismic Hazard Mitigation Strategies Assessment (CAC Nos. MF7800 and MF7801; EPID L-2016-JLD-0006) ML18227A7332018-08-27027 August 2018 Request for Relief from the Requirements of the ASME Code ML18205A2922018-08-10010 August 2018 Correction of Errors in Safety Evaluation Associated with Relief Request 2-TYP-4-RV-02 ML18179A4672018-07-30030 July 2018 FENOC-Beaver Valley Power Station, Unit No. 1 and 2; Davis-Besse Nuclear Power Station, Unit 1, and Perry Nuclear Power Plant, Unit 1 - Issuance of Amendments Request to Adopt TSTF-529, Clarify Use and Application Rules ML18178A1122018-07-0202 July 2018 Relief Request No. 2-TYP-4-RV-02 Regarding the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-729-4 Examination Requirements ML18065A4032018-04-0505 April 2018 Correction of Errors in Safety Evaluation Associated with License Amendment Nos. 301 and 190 ML18073A1062018-03-28028 March 2018 Safety Evaluation of Proposed Alternatives 1-TYP-4-BA-01 and TYP-4-BN-01 Regarding the Fourth 10- Year Interval of the Inservice Inspection Program 2024-07-16
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 30, 2013 Mr. Eric A. Larson, Site Vice President FirstEnergy Nuclear Operating Company Beaver Valley Power Station Mail Stop A-BV-SEB1 P.O. Box 4, Route 168 Shippingport, PA 15077
SUBJECT:
BEAVER VALLEY POWER STATION, UNIT NO. 1- NUCLEAR REGULATORY COMMISSION REVIEW OF CONTAINMENT LINER RANDOM AND NON RANDOM REPORTS (TAC NO. ME9626)
Dear Mr. Larson:
By letter dated February 14,2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML110470404), FirstEnergy Nuclear Operating Company, (FENOC, the licensee) submitted the containment liner random and non-random examinations report for the Beaver Valley Power Station (BVPS), Unit 1, fall 2010 refueling outage. By letter dated July 11,2012 (ADAMS Accession No. ML12195A155), FENOC submitted the containment liner random and non-random examinations report for the BVPS, Unit 1, spring 2012 refueling outage. In response to a request for additional information from the Nuclear Regulatory Commission (NRC) staff, FENOC submitted supplemental information regarding these exams by letter dated March 4,2013 (ADAMS Accession No. ML13064A333).
The NRC staff has reviewed the information described above and has concluded that the licensee has provided the information described in Commitment 34 of Appendix A of NUREG 1929, Supplement 1, "Safety Evaluation Report Related to the License Renewal of Beaver Valley Power Station, Units 1 and 2," (ADAMS Accession No. ML093140250). This commitment requires that the licensee conduct supplemental volumetric examinations at a minimum of 75 randomly selected locations and eight non-randomly selected locations and provide a summary of the results to the NRC. Further, the NRC staff concludes that the information provided demonstrates that the licensee has completed the actions described in Commitment Nos. 32, 33, and 34 of NUREG-1929, Supplement 1, Appendix A, for BVPS, Unit
- 1. Enclosed is the documentation of the NRC staff's review.
E. Larson - 2 Please contact me at 301-415-2833, if you have any questions.
Sincerely, Peter Bamford, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-334
Enclosure:
Safety Evaluation cc w/encl: Distribution via Listserv
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1.0 INTRODUCTION
By letter dated February 14, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML110470404), FirstEnergy Nuclear Operating Company, (FENOC, the licensee) submitted the containment liner random and non-random examinations report for the Beaver Valley Power Station (BVPS), Unit 1, fall 2010 refueling outage. By letter dated July 11, 2012 (ADAMS Accession No. ML12195A155), FENOC submitted the containment liner random and non-random examinations report for the BVPS, Unit 1, spring 2012 refueling outage. In response to a request for additional information from the Nuclear Regulatory Commission (NRC) staff, FENOC submitted supplemental information regarding these exams by letter dated March 4, 2013 (ADAMS Accession No. ML13064A333). The information submitted by the licensee documents and informs the NRC of the completion of license renewal commitments related to supplemental volumetric examinations of the BVPS, Unit 1 containment liner. The licensee's original requirements for supplemental volumetric examinations at BVPS, Unit 1, are given in Commitment Nos. 32, 33, and 34 in Appendix A of NUREG-1929, Supplement 1, "Safety Evaluation Report Related to the License Renewal of Beaver Valley Power Station, Units 1 and 2," (ADAMS Accession No. ML093140250). These commitments require that the licensee conduct supplemental volumetric examinations at a minimum of 75 randomly selected locations and eight non-randomly selected locations and provide a summary of the results to the NRC.
2.0 REGULATORY EVALUATION
In accordance with Title 10 of the Code of Federal Regulations, Part 54, "Requirements for Renewal of Operating Licenses for Nuclear Power Plants," the NRC issued Renewed Operating License DPR-66 for BVPS, Unit 1, on November 5,2009. NUREG-1929, Supplement 1 (October 2009), documents the NRC staff's technical review of the license renewal application for BVPS. Appendix A, "BVPS Units 1 and 2 License Renewal Commitments," of NUREG 1929, Supplement 1, lists the commitments that were made in relation to the licensee's aging management programs and time-limited aging analyses for managing the aging effects for the BVPS structures, systems, and components during the period of extended operation.
The subject commitments, applicable to Unit 1 of BVPS, are items number 32,33, and 34 in this list. They state:
-2 Commitment 32: Supplemental volumetric examinations will be performed on the Unit 1 containment liner prior to the period of extended operation. A minimum of seventy-five (one foot square) randomly selected (as described in FENOC Letter L-09-205) sample locations will be examined (as described in FENOC Letter L 09-243). If degradation is identified, it will be addressed through the corrective action program (as described in FENOC Letter L-09-243).
Commitment 33: Supplemental volumetric examinations will be performed on the Unit 1 containment liner prior to the period of extended operation. A minimum of 8 non-randomly selected locations will be examined, focusing on areas most likely to experience degradation based on past operating experience (as described in FENOC Letter L-09-242). If degradation is identified, it will be addressed through the corrective action program.
Commitment 34: A summary of results for each phase of volumetric testing (described in Unit 1 Commitments No. 32 and No. 33) will be documented in a letter to the NRC.
These commitments are incorporated, by reference, into license condition 2.F. In its letter dated July 11, 2012, the licensee stated that random supplemental volumetric examinations were performed on the Unit 1 containment liner during the twentieth refueling outage (1 R20) and the twenty-first (1 R21) refueling outage. The non-random examinations to satisfy commitment 33, along with 38 random examinations, were performed during 1R20. The results of these examinations were provided to the NRC by letter dated February 14, 2011. The licensee further stated that no evidence of loss of material was found during any of the examinations. The acceptance criterion was identified as 90 percent (%) of the nominal wall thickness, which varies depending on the location. The letter dated July 11, 2012, also contained the results of the examinations conducted during 1R21.
The licensee stated that the supplemental volumetric examinations had been successfully completed and; therefore, license renewal commitments 32, 33, and 34 are considered closed.
3.0 TECHNICAL EVALUATION
The NRC staff reviewed the information provided by the licensee in its letter dated July 11, 2012, against the commitments as described in Appendix A of NUREG-1929, Supplement 1.
The staff noted that the licensee's submittal dated February 14, 2011, did not identify the locations of the measurements (i.e., cylinder or dome), the nominal thickness, or the corresponding acceptance criteria for the measurements reported. Without this information, the licensee's conclusions regarding the measurements could not be verified by the NRC staff. In addition, Commitment No. 32 states that "if degradation is identified, it will be addressed through the corrective action program (as described in FENOC letter L-09-243)." In FENOC letter L-09 243, dated September 4,2009 (ADAMS Accession No. ML092530241), the licensee stated that "locations with identified loss of material less than 10%, but with a breadth and shape will be entered into the corrective action program and tracked as a point of interest for monitoring during subsequent outages until dispositioned." Five locations in the July 11, 2012, report had measurements below what appears to be the nominal thickness of the liner; however, it was not clear if these locations would be monitored in the future. Therefore, by letter dated February 5, 2013 (ADAMS Accession No. ML13023A377), the NRC staff requested that the licensee identify the appropriated nominal thickness and acceptance criteria for the measurement locations in
- 3 the letter dated February 14, 2011, and explain how it was determined what "breadth and shape" was necessary for degradation to be entered into the corrective action program and monitored.
By letter dated March 4, 2013, the licensee provided the nominal thickness, the acceptance criteria, and the lowest measured value for all of the measured locations reported in the letter dated February 14, 2011. All of the provided measurements were above the acceptance criteria; however, nine of the random exam locations (four reported in the 2011 letter and five reported in the 2012 letter) had thickness measurements below the nominal thickness. The licensee explained that the containment liner ultrasonic testing site procedure instructs examiners to record the lowest thickness found and to record whether any wear pattern exists that has a measurable breadth and shape. The licensee further stated that of the nine locations identified with a thickness below nominal, eight were isolated pOints that showed no evidence of a wear pattern with measurable shape or breadth. The licensee stated that the ninth location (1 RN-073, 2011 letter) was entered into the corrective action program, evaluated, and found acceptable. The location was also scheduled for reexamination in the fall 2013 refueling outage (1 R22) to validate the conclusions of the initial evaluation.
The NRC staff reviewed the licensee's response and noted that all of the measured values, both the random and non-random values from the 2011 and 2012 letters, were above the acceptance criteria. The staff also noted that the licensee had clear guidance in its site procedures regarding identifying possibly degraded areas with "a breadth and shape." The one location that showed a possible indication of wall loss was properly dispositioned and identified for follow-up inspections. Therefore, the staff concluded that the licensee provided the requested acceptance criteria, demonstrated that all measured values were above the acceptance criteria, and explained how areas below the nominal thickness are identified for future monitoring.
4.0 CONCLUSION
Based on the review described above, the NRC staff concludes that the licensee has provided the information described in Commitment No. 34 of Appendix A of NUREG-1929, Supplement 1.
The NRC staff also concludes that the information provided demonstrates that the licensee has completed the actions described in Commitment Nos. 32, 33, and 34 of NUREG-1929, Supplement 1, Appendix A.
Principal Contributor: B. Lehman Date: April 30, 2013
E. Larson -2 Please contact me at 301-415-2833, if you have any questions.
Sincerely, Ira!
Peter Bamford, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-334
Enclosure:
Safety Evaluation cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC RidsNrrLAABaxter Resource LPLI-2 R/F RidsAcrsAcnw_MailCTR Resource RidsNrrDlrRasb Resource BLehman, NRR RidsRgn1 MailCenter Resource RidsNrrDorlDpr Resource RidsNrrDorlLpl1-2Resouce RidsNrrPMBeaverValley Resource ADAMS Accession Number: ML13112A275 "via email OFFICE LPLI*2/PM LPLI-2/LA* DLRlRASB/BC* LPLI-2/BC LPLI-2/PM NAME PBamford ABaxter MMarshall MKhanna rd DATE 04/22/13 04/26/13 04112113 04/30/13 04/30/13 OFFICIAL RECORD COpy