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Category:Code Relief or Alternative
MONTHYEARML24026A2802024-01-25025 January 2024 Acceptance Review for Virgil C. Summer Relief Requests RR-5-V1, RR-5-V2, and RR-5-V3 (EPIDs L-2023-LLR-0067, L-2023-LLR-0068, and L-2023-LLR-0069) (Email) ML23244A2352023-09-18018 September 2023 Request to Use a Subsequent Edition of the ASME Code, Section XI ML23062A7292023-03-31031 March 2023 Deferral of Pressurizer and Steam Generator Weld Examinations ML20248H3782020-12-0202 December 2020 Alternative Requests RR 4-19 and RR-4-21 Related to the In-Service Testing Program (Epids L-2020-LLR-0077 and L-2020-LLR-0078) ML19242E0272019-09-0606 September 2019 Relief Request (RR-4-22) for Use of ASME Code Case N-513-4 ML19140A4732019-06-0404 June 2019 Relief Request (RR-4-23) to Utilize Code Case N-513-4 ML19003A1882019-01-18018 January 2019 Relief Request (RR-4-16) for Use of ASME Code Case N-513-4 and NRC Generic Letter 90-05 ML19091A0582019-01-10010 January 2019 Draft Application Related to April 4, 2019, Pre-Application Public Meeting for Two Proposed Relief Request ML18345A0602018-12-17017 December 2018 Relief Request Regarding Use of a Performance Based Testing Frequency for Pressure Isolation Valves (RR-4-14) ML18296A1112018-11-0808 November 2018 Relief Request (RR-4-15) for Use of ASME Code Case N-513-4 RC-18-0070, (Vcsns), Unit 1 - Relief Request RR-4-14, Use of a Performance Based Testing Frequency for Pressure Isolation Valves as an Alternative to the Requirements of the American Society of Mechanical Engineers Code for ...2018-10-0808 October 2018 (Vcsns), Unit 1 - Relief Request RR-4-14, Use of a Performance Based Testing Frequency for Pressure Isolation Valves as an Alternative to the Requirements of the American Society of Mechanical Engineers Code for ... RC-18-0118, (Vcsns), Unit 1 - Relief Request RR-4-18, Request for a Temporary Non-Code Repair of a Service Water System Flange2018-09-14014 September 2018 (Vcsns), Unit 1 - Relief Request RR-4-18, Request for a Temporary Non-Code Repair of a Service Water System Flange RC-18-0105, (Vcsns), Unit 1 - Relief Request RR-4-17, Request to Utilize Code Case N-513-3 'Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1' for a Service Water ..2018-08-14014 August 2018 (Vcsns), Unit 1 - Relief Request RR-4-17, Request to Utilize Code Case N-513-3 'Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1' for a Service Water .. ML18186A5882018-07-19019 July 2018 Relief Request (RR-4-13) for Use of a Risk-Informed Process as an Alternative for the Selection of Class 1 and Class 2 Piping Welds. ML17031A0152017-02-0909 February 2017 Relief from the Requirements of the ASME Code Regarding Service Water System Piping ML16161A0452016-07-0101 July 2016 Relief from the Requirements of the ASME Code ML16124A8972016-05-0606 May 2016 Relief from the Requirements of the ASME Code ML15176A3152015-08-12012 August 2015 Alternative Request Regarding Snubbers ML15007A1612015-01-0909 January 2015 Alternative Request During the Fourth Ten-Year Inservice Inspection Interval ML14079A6142014-03-24024 March 2014 Acceptance Review Concerning Alternative Request RR-4-05 Alternative Weld Repair for Reactor Vessel Upper Head Penetrations R-4-04 ML13301A7672013-11-0505 November 2013 Relief Request (RR-4-01, RR-4-02, RR-4-03) for Third and Fourth Ten- Year Inservice Inspection Interval (TAC Nos. MF1900, 1901, 1902) ML13177A0782013-07-0808 July 2013 Acceptance Review Concerning Relief from Limited Pressurizer Surge Nozzle-to-Vessel Examination (TAC No. MF1848)(RC-13-0068) ML13101A3332013-04-19019 April 2013 Alternative RR-III-09 Alternative Weld Repair for Reactor Vessel Head Penetration (TAC No. ME9851) (RC-12-0165) RC-12-0179, Relief Request RR-III-09 Request for Information Fatigue Crack Growth and Transients2012-11-16016 November 2012 Relief Request RR-III-09 Request for Information Fatigue Crack Growth and Transients RC-12-0165, Relief Request RR-III-09 Alternative Weld Repair for Reactor Vessel Head Penetration2012-10-30030 October 2012 Relief Request RR-III-09 Alternative Weld Repair for Reactor Vessel Head Penetration ML12289A0502012-10-17017 October 2012 Alternative RR-III-08 for Third 10-Year Inservice Inspection Interval ML0630705402006-11-21021 November 2006 Relief Requests RR-111-03 and RR-111-04, Relief from Certain Examination Qualification Requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code., RC-06-0117, Relief, Request to Use Alternatives to ASME Code Requirements in VCSNS Third Inservice Inspection Interval (RR-III-03, RR-III-04)2006-06-20020 June 2006 Relief, Request to Use Alternatives to ASME Code Requirements in VCSNS Third Inservice Inspection Interval (RR-III-03, RR-III-04) ML0601004482006-01-20020 January 2006 Relief, Second 10-year Inservice Inspection, Requests for Relief RR-II-9, RR-II-10, & RR-II-12 ML0523006162005-09-0606 September 2005 Relief Request, RI-ISI Program ML0512901982005-05-10010 May 2005 Relief, Relief Request No. RR-III-01 Snubber Visual Examination and Functional Testing RC-04-0148, Request to Use Alternatives to ASME Code Requirements in Plant Third Inservice Inspection Interval (RR-111-01, RR-111-02)2004-09-0808 September 2004 Request to Use Alternatives to ASME Code Requirements in Plant Third Inservice Inspection Interval (RR-111-01, RR-111-02) ML0410503842004-04-0707 April 2004 Request to Use Alternative to ASME Code Requirements in VCSNS Third Inservice Inspection Interval ML0404203862004-02-11011 February 2004 2/11/04, Virgil C. Summer Nuclear Station, Bwn, Relief Request RR-11-16 Regarding Reduced Ultrasonic Testing, TAC No. MC0108 RC-03-0234, Submittal of Information Requested by NRC for Evaluation of Request to Use Alternatives to ASME Boiler and Pressure Vessel Code, Section XI RR-II-18 (0-C-03-0262)2003-11-13013 November 2003 Submittal of Information Requested by NRC for Evaluation of Request to Use Alternatives to ASME Boiler and Pressure Vessel Code, Section XI RR-II-18 (0-C-03-0262) RC-03-0223, Response to Request for Additional Information Regarding Request to Use Alternatives to ASME Boiler and Pressure Vessel Code, Section XI, Relief Request RR-II-15, RR-II-18 (0-C-03-0262)2003-10-23023 October 2003 Response to Request for Additional Information Regarding Request to Use Alternatives to ASME Boiler and Pressure Vessel Code, Section XI, Relief Request RR-II-15, RR-II-18 (0-C-03-0262) ML0330101602003-10-23023 October 2003 Response to Request for Additional Information Regarding Request to Use Alternatives to ASME Boiler and Pressure Vessel Code, Section XI, Relief Request RR-II-11,RR-II-12(0-C-02-3202) RC-03-0196, Resubmittal of Request to Use Alternatives to ASME Boiler and Pressure Vessel Code, Section XI (C-03-0262), RR-II-15, RR-II-16, RR-II-17, RR-II-192003-09-16016 September 2003 Resubmittal of Request to Use Alternatives to ASME Boiler and Pressure Vessel Code, Section XI (C-03-0262), RR-II-15, RR-II-16, RR-II-17, RR-II-19 RC-03-0191, Withdrawal of Request for Relief (0-C-02-3202) (RR-II-09, RR-II-10, RR-II-11, and RR-II-12) Request to Use Alternatives to ASME Boiler and Pressure Vessel Code, Section XI2003-09-11011 September 2003 Withdrawal of Request for Relief (0-C-02-3202) (RR-II-09, RR-II-10, RR-II-11, and RR-II-12) Request to Use Alternatives to ASME Boiler and Pressure Vessel Code, Section XI RC-03-0142, Request for Use Alternatives to ASME Boiler & Pressure Vessel Code, Section XI, RR-II-15, RR-11-15, RR-II-17, RR-II-18, RR-II-19, RR-II-20 and RR-II-212003-07-11011 July 2003 Request for Use Alternatives to ASME Boiler & Pressure Vessel Code, Section XI, RR-II-15, RR-11-15, RR-II-17, RR-II-18, RR-II-19, RR-II-20 and RR-II-21 ML0317402382003-06-13013 June 2003 Response to Request for Additional Information Regarding Request to Use Alternatives to ASME Boiler and Pressure Vessel Code, Section XI, Relief Request RR-II-13 (0-C-03-0883) 2024-01-25
[Table view] Category:Letter
MONTHYEARML24038A0322024-02-0707 February 2024 (Vcsns), Unit 1, 10 CFR 21 Report - Emergency Diesel Generator Flash Contactor Relay IR 05000395/20230042024-01-31031 January 2024 Integrated Inspection Report 05000395/2023004 ML24022A1582024-01-22022 January 2024 (Vcsns), Unit 1 - Reply to a Notice of Violation: EA-23-093 ML24022A1202024-01-22022 January 2024 Notification of Target Set Inspection and Request for Information (NRC Inspection Report 05000395/2024403) ML24018A0112024-01-18018 January 2024 CFR 21 Report Emergency Diesel Generator Fuel Oil Piping IR 05000395/20240112024-01-17017 January 2024 Notification of VC Summer Station Comprehensive Engineering Team Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000395/2024011 ML23361A1042023-12-21021 December 2023 Inservice Testing Program for Pumps and Valves Fifth Interval Update and Associated Relief and Alternative Requests IR 05000395/20230912023-12-21021 December 2023 Final Significance Determination of a White Finding and Notice of Violation and Assessment Followup Letternrc Inspection Report 05000395/2023091 ML23354A1802023-12-20020 December 2023 301 Examination Report with Cover Letter ML23347A0492023-12-12012 December 2023 Technical Specification Bases Changes Updated Through November 2023 ML23334A2462023-11-30030 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23334A2372023-11-30030 November 2023 (Vvsns), Unit 1 - Annual Commitment Change Summary Report ML23332A1942023-11-28028 November 2023 (Vcsns), Unit 1, Correction of Typographical Error in License Amendment Request - Inverter Allowed Outage Time (AOT) Extension ML23317A2242023-11-0909 November 2023 (Vcsns), Unit 1 - License Amendment Request - Inverter Allowed Outage Time (AOT) Extension ML23289A1172023-11-0303 November 2023 Tribal Request for Scoping Comments Concerning the Environmental Review of the V.C. Summer SLRA ML23289A1152023-11-0303 November 2023 Ltr to R. Nelson - Request for Scoping Comments Concerning the Environmental Review of the V.C. Summer SLRA ML23289A1162023-11-0303 November 2023 Ltr to W. Emerson - Request for Scoping Comments Concerning the Environmental Review of the V.C. Summer SLRA IR 05000395/20234032023-11-0101 November 2023 Material Control and Accounting Program Inspection Report 05000395/2023403 Cover IR 05000395/20230032023-11-0101 November 2023 Integrated Inspection Report 05000395/2023003 ML23284A1792023-10-16016 October 2023 Subsequent License Renewal Application Online Reference Portal ML23275A0142023-10-11011 October 2023 SLRA - Acceptance and Opportunity for Hearing - Letter ML23284A1662023-10-10010 October 2023 (Vcsns), Unit 1 - Request for Regulatory Conference; (EA-23-093) IR 05000395/20230902023-10-0404 October 2023 NRC Inspection Report 05000395/2023090 and Preliminary Yellow Finding and Apparent Violation IR 05000395/20230112023-09-27027 September 2023 Focused Engineering Inspection Report 05000395/2023011 ML23250A3112023-09-20020 September 2023 Request to Revise Reactor Vessel Material Surveillance Capsule Withdrawal Schedules ML23244A2352023-09-18018 September 2023 Request to Use a Subsequent Edition of the ASME Code, Section XI ML23230A0012023-09-15015 September 2023 Request to Use a Provision of a Previous Edition of the ASME Boiler and Pressure Vessel Code, Section XI, for Non-Destructive Examinations ML23235A0432023-09-0505 September 2023 Receipt and Availability of the Subsequent License Renewal Application IR 05000395/20234012023-08-30030 August 2023 Security Baseline Inspection Report 05000395/2023401 ML23242A1192023-08-29029 August 2023 (Vcsns), Unit 1 - Inservice Inspection (ISI) Owner'S Activity Report (OAR) for Refueling Outage 27 ML23243B0362023-08-25025 August 2023 Request for FEMA Consultation on the Dominion Energy Proposal to Consolidate the Emergency Operations Facility for the Virgil C. Summer Nuclear Station Unit 1 IR 05000395/20230052023-08-23023 August 2023 Updated Inspection Plan for Virgil C. Summer Nuclear Station (Report 05000395 2023005) ML23233A1752023-08-17017 August 2023 Application for Subsequent Renewed Operating License IR 05000395/20230022023-08-14014 August 2023 Integrated Inspection Report - Integrated Inspection Report 05000395/2023002 and Apparent Violation IR 05000395/20230102023-08-12012 August 2023 Biennial Problem Identification and Resolution Inspection Report 05000395/2023010 ML23207A1102023-07-26026 July 2023 NRC Regulatory Issues Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations IR 05000395/20234412023-07-17017 July 2023 95001 Supplemental Inspection Report 05000395/2023441 and Follow Up Assessment Letter ML23190A0012023-07-0909 July 2023 Special Report 2023-003 Inoperable Radiation Monitoring Instrumentation Channel ML23187A5092023-07-0606 July 2023 Request for Federal Emergency Management Agency Consultation on the Dominion Energy Proposal to Consolidate the Emergency Operations Facility for the Virgil C. Summer Nuclear Station Unit 1 ML23178A1682023-06-26026 June 2023 2022 Annual Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the Requirements of 10 CFR 50.46 ML23173A1052023-06-22022 June 2023 Special Report 2023-002 Inoperable Loose-Part Monitoring System Channel ML23163A2352023-06-12012 June 2023 Request to Use a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI, for the SPS Sixth Inservice Inspection (Isi) Intervals and VCSNS Fifth ISI Interval ML23159A2332023-06-0808 June 2023 License Amendment Request - Emergency Response Organization Augmentation Time Change, Emergency Operations Facility Relocation and Other Emergency Plan Changes ML23156A3092023-06-0505 June 2023 Requalification Program Inspection Virgil C. Summer Nuclear Station Unit 1 - 05000395/2023003 2024-02-07
[Table view] Category:Safety Evaluation
MONTHYEARML23250A3112023-09-20020 September 2023 Request to Revise Reactor Vessel Material Surveillance Capsule Withdrawal Schedules ML23244A2352023-09-18018 September 2023 Request to Use a Subsequent Edition of the ASME Code, Section XI ML23230A0012023-09-15015 September 2023 Request to Use a Provision of a Previous Edition of the ASME Boiler and Pressure Vessel Code, Section XI, for Non-Destructive Examinations ML23072A0892023-05-0101 May 2023 (Amendments 346 & 286), North Anna 1 & 2 (Amnds 294 & 277), Surry 1 & 2 (Amnds 311 & 311), and Summer 1 (Amd 225) - Issuance of Amendments to Revise TSs to Adopt TSTF-554 Revise Reactor Coolant Leakage Requirements ML23062A7292023-03-31031 March 2023 Deferral of Pressurizer and Steam Generator Weld Examinations ML23012A0152023-02-21021 February 2023 Issuance of Amendment No. 224 to Change Nozzle Blockage Testing Requirement for Reactor Building Spray System ML22341A1972022-12-15015 December 2022 Extension of Steam Generator Primary Inlet Nozzle Dissimilar Metal Weld Inspection Interval ML22244A1722022-09-22022 September 2022 Issuance of Amendment No. 223 to Relocate Main Steam Isolation Valve Isolation Times to the Updated Final Safety Analysis Report ML22160A3652022-08-16016 August 2022 Issuance of Amendment No. 222 to Relocate Selected Surveillance Frequencies to a Risk-Informed Licensee Controlled Program ML22041A0102022-03-0101 March 2022 V.C. Summer 1, Issuance of Amendment Nos. 283 (Millstone), 291 and 274 (North Anna), and 221 (Summer) to Revise TSs to Adopt TSTF-569 Revision of Response Time Testing Definition ML21319A2622021-12-28028 December 2021 Issuance of Amendment No. 220 to Relocate Unit Staff Qualifications from Technical Specification to Quality Assurance Program Description ML21188A3322021-08-10010 August 2021 Correction to Amendment No. 219 to Modify Technical Specification 6.9.1.11, Core Operating Limits Report ML21173A1632021-08-0606 August 2021 Authorization and Safety Evaluation for Alternative Request No. RR-4-25 ML21112A1082021-06-30030 June 2021 Issuance of Amendment No. 219 to Modify Technical Specification 6.9.1.11, Core Operating Limits Report ML21075A0452021-03-26026 March 2021 Request to Utilize Code Case N-885 ML20248H3782020-12-0202 December 2020 Alternative Requests RR 4-19 and RR-4-21 Related to the In-Service Testing Program (Epids L-2020-LLR-0077 and L-2020-LLR-0078) ML19361A0702020-01-24024 January 2020 Relief Request Regarding Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography (RR-4-20) ML19276D3772019-12-11011 December 2019 Issuance of Amendment Revise Company Name to Dominion Energy South Carolina, Inc. ML19242E0272019-09-0606 September 2019 Relief Request (RR-4-22) for Use of ASME Code Case N-513-4 ML19140A4732019-06-0404 June 2019 Relief Request (RR-4-23) to Utilize Code Case N-513-4 ML19080A1032019-04-30030 April 2019 Issuance of Amendment No. 215 Technical Specification 3.8.2, D.C. Sources - Operating ML19074A2222019-04-10010 April 2019 Issuance of Amendment No. 214 Removes the Expired One-Time Extension to Surveillance Requirement 4.3.3.6 and Removes the Index from Technical Specifications ML19023A4202019-03-0707 March 2019 Issuance of Amendment Reactor Coolant System Operational Leakage Technical Specification Surveillance Requirement 4.4.6.2.2 ML19035A2992019-02-26026 February 2019 Relief Request (RR-4-18) for Use of NRC Generic Letter 90-05 ML19030B8272019-02-13013 February 2019 Relief Request (RR-4-17) for Use of ASME Code Case N-513-3 ML19003A1882019-01-18018 January 2019 Relief Request (RR-4-16) for Use of ASME Code Case N-513-4 and NRC Generic Letter 90-05 ML18345A0602018-12-17017 December 2018 Relief Request Regarding Use of a Performance Based Testing Frequency for Pressure Isolation Valves (RR-4-14) ML18296A1112018-11-0808 November 2018 Relief Request (RR-4-15) for Use of ASME Code Case N-513-4 ML18253A1152018-10-0505 October 2018 Issuance of Amendment No. 212 Technical Specification Change Request for the Revision of the Surveillance Frequency of the Turbine Trip Functional Unit ML18260A0272018-09-25025 September 2018 Issuance of Exigent Amendment One Time Extension to the Surveillance Frequency 4.3.3.6 of the Core Exit Temperature Instrumentation ML18255A2562018-09-24024 September 2018 Correction to the Safety Evaluation and the Orders Approving Indirect Transfer of Licenses ML18129A0762018-08-30030 August 2018 Transmittal Letter and Safety Evaluation Related to the Orders Approving Indirect Transfer of Licenses for Units 1, 2, 3 and the Independent Spent Fuel Storage Installation ML18186A5882018-07-19019 July 2018 Relief Request (RR-4-13) for Use of a Risk-Informed Process as an Alternative for the Selection of Class 1 and Class 2 Piping Welds. ML18141A6682018-06-28028 June 2018 Issuance of Amendment No. 210, Revise Technical Specification 6.8.4.g for Integrated Leak Rate Test Peak Calculated Containment Internal Pressure Change ML17206A4122017-10-0404 October 2017 Issuance of Amendment TSTF-411, Revision 1, Surveillance Test Interval Extensions for Components of the Reactor Protection System (WCAP-15376-P-A). ML17089A6172017-08-0101 August 2017 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML17011A0502017-03-0909 March 2017 Issuance of Amendment to Revise Completion Date of Implementation Milestone 8 of the Cyber Security Plan ML17031A0152017-02-0909 February 2017 Relief from the Requirements of the ASME Code Regarding Service Water System Piping ML16348A2002017-01-18018 January 2017 Issuance of Amendment to Revise Technical Specification 3.5.4 Limiting Condition for Operation Refueling Water Storage Tank ML16264A4112016-10-26026 October 2016 Issuance of Amendment to Revise Technical Specification 3/4.7.1.2, Emergency Feedwater System ML16161A0452016-07-0101 July 2016 Relief from the Requirements of the ASME Code ML15231A6052016-05-16016 May 2016 Issuance of Amendment to Change Licensing Basis to Incorporate a Supplemental Analysis to the Steam Generator Tube Rupture Accident ML16104A2952016-05-0606 May 2016 Issuance of Amendment to Adopt TSTF-523, Revision 2 ML16124A8972016-05-0606 May 2016 Relief from the Requirements of the ASME Code ML16063A0902016-03-0909 March 2016 Issuance of Exigent Amendment Regarding Technical Specification 3.7.1.2 ML15208A0292015-10-15015 October 2015 Issuance of Amendment ML15222A5422015-09-0101 September 2015 Alternative Request Regarding Root Mean Square Depth Sizing Requirements ML15170A0872015-08-18018 August 2015 Issuance of Amendment to Revise the Radiation Emergency Plan ML15176A3152015-08-12012 August 2015 Alternative Request Regarding Snubbers ML15063A3552015-04-13013 April 2015 Issuance of Amendment to Revise Emergency Action Levels to a Scheme Based on NEI 99-01, Revision 6 2023-09-20
[Table view] |
Text
September 6, 2005 Mr. Jeffery Archie Vice President, Nuclear Operations South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station Post Office Box 88 Jenkinsville, South Carolina 29065
SUBJECT:
VIRGIL C. SUMMER NUCLEAR STATION RELIEF REQUEST-III-02 ASSOCIATED WITH THE RISK-INFORMED INSERVICE INSPECTION PROGRAM (TAC NO. MC4323)
Dear Mr. Archie:
By letter dated September 8, 2004, South Carolina Electric & Gas Company requested U.S. Nuclear Regulatory Commission (NRC) authorization to extend the risk-informed inservice inspection (RI-ISI) program plan for Virgil C. Summer Nuclear Station (VCSNS) to the third 10-year inservice inspection (ISI) interval. The VCSNS RI-ISI program was initially submitted to the NRC by letter dated September 16, 2002, and was approved by the NRC for use in the second 10-year ISI interval by letter dated May 12, 2003. The VCSNS RI-ISI program was developed in accordance with the methodology contained in the NRC approved Electric Power Research Institute (EPRI) Topical Report EPRI-TR-112657, Revision B-A. The proposed RI-ISI program is an acceptable alternative to the requirements of the American Society of Mechanical Engineers Code,Section XI, for inservice inspection of Code Class 1 piping, Categories B-F and B-J welds and Class 2 piping, Categories C-F-1 and C-F-2 welds.
The NRC staff authorizes the proposed alternatives in Relief Request-III-02, for the third 10-year inservice inspection interval of VCSNS, pursuant to Title 10, Code of Federal Regulations, Section 50.55a(a)(3)(i) on the basis that the alternatives provide an acceptable level of quality and safety.
Sincerely,
/RA/
Evangelos C. Marinos, Chief, Section 1 Project Directorate ll Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-395
Enclosure:
Safety Evaluation cc w/encl: See next page
ML052300616 NRR-028 OFFICE PM: PDII-1 LA: PDII-2 OGC SC: PDII-1 NAME RMartin BClayton JHull EMarinos DATE 8/ 25 /2005 8/ 24 /2005 8/ 30 /2005 9/ 6 /2005 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REQUEST FOR RELIEF FROM ASME CODE REQUIREMENTS FOR THIRD 10-YEAR INSERVICE INSPECTION PROGRAM BASED ON RISK-INFORMED ALTERNATIVE APPROACH VIRGIL C. SUMMER NUCLEAR STATION SOUTH CAROLINA ELECTRIC AND GAS COMPANY DOCKET NO. 50-395
1.0 INTRODUCTION
By letter dated September 8, 2004 (Reference 1), South Carolina Electric & Gas Company (SCE&G, the licensee) requested U.S. Nuclear Regulatory Commission (NRC) authorization to extend the risk-informed inservice inspection (RI-ISI) program plan for Virgil C. Summer Nuclear Station (VCSNS) to the third 10-year inservice inspection (ISI) interval. The VCSNS RI-ISI program was initially submitted to the NRC by letter dated September 16, 2002 (Reference 2), and supplemented in a letter dated January 29, 2003 (Reference 3). The VCSNS RI-ISI program was reviewed and approved by the NRC for use during the second 10-year ISI interval in a letter dated May 12, 2003 (Reference 4).
The licensee considered relevant information since the development of the original program and reviewed and updated the RI-ISI program. The licensees current submittal proposes to extend the updated RI-ISI program to the third 10-year ISI interval.
2.0 REGULATORY EVALUATION
Title 10 of the Code of Federal Regulations (10 CFR), Section 50.55a(g) specifies that ISI of nuclear power plant components shall be performed in accordance with the requirements of the American Society of Mechanical Engineers (ASME), Boiler and Pressure Vessel Code (Code),
Section XI, except where specific written relief has been granted by the Commission pursuant to 10 CFR 50.55a(g)(6)(i). It states in 10 CFR 50.55a(a)(3) that alternatives to the requirements of paragraph (g) may be used, when authorized by the NRC, if (i) the proposed alternatives would provide an acceptable level of quality and safety or (ii) compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
The licensees RI-ISI program, as outlined in References 3 and 4, was developed in accordance with the methodology contained in the Electric Power Research Institutes (EPRIs)
Enclosure
Topical Report EPRI TR-112657, Rev. B-A (Reference 5), which was reviewed and approved by the NRC staff. The VCSNS RI-ISI program is an alternative pursuant to 10 CFR 50.55a(a)(3)(i). In Reference 1, the licensee requests NRC authorization to continue the implementation of an RI-ISI piping program for the third 10-year ISI interval at VCSNS. The scope of the RI-ISI program is limited to the inspection of ASME Code Class 1 and 2 piping (Categories B-F, B-J, C-F-1, and C-F-2 welds).
3.0 TECHNICAL EVALUATION
The licensee is requesting relief to use the proposed RI-ISI program plan in the third 10-year ISI interval instead of the ASME Section XI program for piping. An acceptable RI-ISI program plan is expected to meet the five key principles discussed in NRC Regulatory Guide 1.178 (Reference 6), Standard Review Plan 3.9.8 (Reference 7) and the EPRI TR-112657 (Reference 5), as stated below.
- 1. The proposed change meets the current regulations unless it is explicitly related to a requested exemption or rule change.
- 2. The proposed change is consistent with the defense-in-depth philosophy.
- 3. The proposed change maintains sufficient safety margins.
- 4. When proposed changes result in an increase in Core Damage Frequency (CDF) or risk, the increases should be small and consistent with the intent of the Commissions Safety Goal Policy Statement.
- 5. The impact of the proposed change should be monitored by using performance measurement strategies.
The first principle is met in this relief request because an alternative ISI program may be authorized pursuant to 10 CFR 50.55a(3)(i) and, therefore, an exemption request is not required. The second and third principles require assurance that the alternative program is consistent with the defense-in-depth philosophy and that sufficient safety margins are maintained, respectively. Assurance that the second and third principles are met is based on the application of the approved methodology and not on the particular inspection locations selected. The methodology used to develop the RI-ISI program for the third 10-year inspection interval is unchanged from the methodology approved for use in the second 10-year inspection interval and, therefore, the second and third principles are met.
As described in Reference 2 and approved by the NRC staff in Reference 4, the RI-ISI is a living program that requires periodic updating and that, as a minimum, risk ranking of piping segments will be reviewed on an ASME period basis. In Reference 1, the licensee described eight areas of review and the results of the review. The licensee stated that the only change in the RI-ISI program between the second 10-year inspection interval and the third 10-year inspection interval was an increase in the number of welds included in the risk-informed evaluation (i.e., the scope of the program). The licensee determined that no changes in the number and location of inspections were required in accordance with the approved methodology in Reference 5.
Relief was granted in Reference 4 from selected requirements in the ASME code, 1983 Edition through 1983 Addenda of Section XI, the licensees code of record when relief was requested.
The licensee reported that the code of record for the third ASME interval is the 1998 ASME Section XI through the 2000 addenda. The licensee reported that, as part of the ASME third interval update, ASME code classification was reviewed for all piping. The 1998 ASME Section XI through the 2000 addenda reduced the inspection exemption for emergency
feedwater lines from 4 inches to 11/2 inches. The licensee also changed the basis for the original ASME classification for some pipe segments from design stress considerations to functional considerations. The change in the basis caused some piping that had been previously classified as Class 2 to become Class 1 and reduced the inspection exemptions accordingly. Taken together, the changes removed the ASME inspection exemptions from a total of 107 welds.
As described in Section 3.2.1 of the EPRI Topical Report, the RI-ISI program scope is determined by the ASME inspection program scope. The licensee reported that the 107 welds were added to the RI-ISI program scope and, therefore, were included in the risk ranking. All the new welds are located in low safety significant (LSS) segments. The EPRI methodology does not require inspections of any LSS welds but the risk increase associated with discontinuing the inspections of the LSS welds must be included in the change in risk estimates.
The licensee reported in Reference 1 that the change in CDF and large early release frequency (LERF) were re-calculated using the latest revision of the Probabilistic Risk Analysis (PRA).
None of the 107 welds added to the RI-ISI program scope had been inspected under the previous ASME program and their addition to the RI-ISI program did not affect the risk estimates because no inspections were discontinued. Some ASME inspections might have been required in the 107 welds if a new ASME inspection program had been developed for the new code of record in the third 10-year inspection interval. Development of an acceptable RI-ISI program is primarily achieved through the risk-ranking and the inspection location selection processes. Estimates of the change in CDF and LERF is a final phase intended to provide additional assurance that aggregate changes in risk will be acceptable (Ref. 5). Although the ASME inspection program may change slightly when developed from the new code of record, the accuracy of the change in risk calculations does not warrant developing a new ASME program for the new code of record simply to be used as a new baseline and then discarded.
Therefore, the NRC staff finds that the comparison of the risk estimate between the RI-ISI program proposed in the submittal and the ASME program based on the code of record from which relief was granted in Reference 4 is appropriate and acceptable. No deviation from the risk acceptance criteria were identified and the NRC staff finds that the process provides assurance that the fourth key principle is met.
Section 3.6.6.1 of EPRI TR-112657 states, in part, that the service history and susceptibility review and ongoing industry event reviews assure that the industry trends are being monitored to assure that if an unexpected or new mechanism is identified, or a new component is identified as susceptible to an existing degradation mechanism, the RI-ISI program will be updated to reflect that change. The program update will incorporate any additional inspections mandated by the NRC, as well as those inspections deemed appropriate by the industry groups addressing the specific issues.
Due to recent and ongoing issues related to degradation due to pressurized water stress corrosion cracking in components that contain alloy 600/82/182, the NRC staff requested that the licensee provide information related to welds containing alloy 82/182. The licensee participated in a teleconference to discuss the aforementioned issue. The licensee stated that it has taken the issue into account and is complying with industry guidance, and intends to continue to follow industry guidance in the future.
In addition to monitoring industry experience, the licensee stated that future updates to the PRA model and the RI-ISI program will be conducted in accordance with the Nuclear Energy Institute (NEI) document NEI-04-05, Living Program Guidance to Maintain Risk-Informed Inservice Inspection Programs for Nuclear Plant Piping Systems (Reference 8). Therefore, the NRC staff concludes that the RI-ISI program continues to be a living program and that the fifth key principle is met.
Based on the above discussion, the NRC staff finds that the five key principles of risk-informed decision making are ensured by the licensees proposed third 10-year RI-ISI interval program plan and, therefore, the proposed program for the third 10-year ISI inspection interval is acceptable.
3.0 CONCLUSION
S Based on the information provided in the licensees submittals, the NRC staff has determined that the proposed alternative provides an acceptable level of quality and safety, and, therefore, is authorized pursuant to 10 CFR 50.55a(a)(3)(i) for the third 10-year ISI interval at VCSNS.
4.0 REFERENCES
- 6. Letter from Jeffrey B. Archie, SCE&G, dated September 8, 2004, to NRC, Request to Use Alternatives to ASME Code Requirements in VCSNS Third Inservice Inspection Interval (RR-III-01, RR-III-02).
- 7. Letter from Stephen A. Byrne, SCE&G, dated September 16, 2002, to NRC, Request for Revision to ASME Boiler and Pressure Vessel Code,Section XI Relief Request RR-II-07.
- 8. Letter from Stephen A. Byrne, SCE&G, dated January 29, 2003, to NRC, Response to NRC Questions Regarding ASME Boiler and Pressure Vessel Code,Section XI, Relief Request RR-II-07.
- 9. Letter from NRC, dated May 12, 2003, to Stephen A. Byrne, SCE&G, Virgil C. Summer Nuclear Station - Relief Request II-07 Associated with the Risk-Informed Inservice Inspection (RI-ISI) Program (TAC No. MB6523).
- 10. EPRI TR-112657, Revision B-A, Revised Risk-Informed Inservice Inspection Evaluation Procedure, Final Report, December 1999.
- 11. NRC RG 1.178, An Approach for Plant-Specific Risk-Informed Decision Making:
Inservice Inspection of Piping, September 2003.
- 12. NRC NUREG-0800, Chapter 3.9.8, Standard Review Plan for the Review of Risk-Informed Inservice Inspection of Piping, September 2003.
- 13. NEI 04-05, Living Program Guidance To Maintain Risk-Informed Inservice Inspection Programs For Nuclear Plant Piping Systems, April 2004.
Principal Contributors: S. Dinsmore A. Keim Date: September 6, 2005
Mr. Jeffrey B. Archie VIRGIL C. SUMMER NUCLEAR STATION South Carolina Electric & Gas Company cc:
Mr. R. J. White Nuclear Coordinator S.C. Public Service Authority c/o Virgil C. Summer Nuclear Station Post Office Box 88, Mail Code 802 Jenkinsville, South Carolina 29065 Resident Inspector/Summer NPS c/o U.S. Nuclear Regulatory Commission 576 Stairway Road Jenkinsville, South Carolina 29065 Chairman, Fairfield County Council Drawer 60 Winnsboro, South Carolina 29180 Mr. Henry Porter, Assistant Director Division of Waste Management Bureau of Land & Waste Management Dept. of Health & Environmental Control 2600 Bull Street Columbia, South Carolina 29201 Mr. Thomas D. Gatlin, General Manager Nuclear Plant Operations South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station Post Office Box 88, Mail Code 300 Jenkinsville, South Carolina 29065 Mr. Ronald B. Clary, Manager Nuclear Licensing South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station Post Office Box 88, Mail Code 830 Jenkinsville, South Carolina 29065 Ms. Kathryn M. Sutton, Esquire Winston & Strawn Law Firm 1400 L Street, NW Washington, DC 20005-3502