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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
MONTHYEAR05000395/LER-2024-002, Loss of Control Room Emergency Filtration System2024-10-15015 October 2024 Loss of Control Room Emergency Filtration System ML24290A1052024-10-0707 October 2024 Core Operating Limits Report VCSNS Unit 1 Cycle 29, Revision 0 ML24274A1942024-09-26026 September 2024 (Vcsns), Unit 1 Subsequent License Renewal Application (SLRA) First 10 CFR 54.21(b) Annual Amendment IR 05000395/20244042024-09-26026 September 2024 Cyber Security Inspection Report 05000395-2024404 - Public ML24267A0542024-09-23023 September 2024 Clarification Regarding Area of Potential Effect for the Subsequent Operating License Renewal for Virgil C. Summer Nuclear Station Fairfield County, South Carolina (SHPO Project Number: 22-EJ0147) (Docket Number: 50-395) ML24267A0642024-09-23023 September 2024 Clarification Regarding Area of Potential Effect for the Subsequent Operating License Renewal for Virgil C. Summer Nuclear Station Fairfield County, South Carolina (SHPO Project Number: 22-EJ0147) (Docket Number: 50-395) ML24267A0592024-09-23023 September 2024 Clarification Regarding Area of Potential Effect for the Subsequent Operating License Renewal for Virgil C. Summer Nuclear Station Fairfield County, South Carolina (SHPO Project Number: 22-EJ0147) (Docket Number: 50-395) ML24267A0552024-09-23023 September 2024 Clarification Regarding Area of Potential Effect for the Subsequent Operating License Renewal for Virgil C. Summer Nuclear Station Fairfield County, South Carolina (SHPO Project Number: 22-EJ0147) (Docket Number: 50-395) IR 05000395/20244022024-09-10010 September 2024 Security Baseline Inspection Report 05000395/2024402 IR 05000395/20240052024-08-22022 August 2024 Updated Inspection Plan for Virgil C. Summer Nuclear Station - Report 05000395/2024005 ML24190A4012024-08-19019 August 2024 Request for Withholding Information from Public Disclosure Regarding the Subsequent License Renewal Application - Dominion Energy Letter Dated May 30, 2024 IR 05000395/20240022024-08-12012 August 2024 Integrated Inspection Report 05000395/2024002 ML24180A0062024-08-0505 August 2024 Issuance of Amendment No. 227 to Modify Technical Specification 3.8.3.1 to Increase Completion Time for 120-Volt A.C. Vital Busses ML24218A3002024-08-0101 August 2024 Environmental Review Response to NRC Requests for Additional Information and Response to NRC Requests for Confirmation of Information Set 1 ML24158A3882024-07-31031 July 2024 Issuance of Amendment No. 226 to Change Emergency Plan Staff Augmentation Times and Relocate Emergency Operations Facility ML24162A3292024-07-0505 July 2024 Letter to E Carr - V.C. Summer Unit 1 - Summary of the May 2024 Audit Regarding the Environmental Review of the Subsequent License Renewal Application IR 05000395/20240112024-06-26026 June 2024 – Comprehensive Engineering Team Inspection Report 05000395/2024011 ML24178A2422024-06-25025 June 2024 2023 Annual Report of Emergency Core Cooling System (ECCS) Model, Changes Pursuant to the Requirements of 10 CFR 50.46 ML24178A1192024-06-25025 June 2024 Update to License Amendment Request- Inverter Allowed Outage Time (AOT) Extension ML24177A1382024-06-25025 June 2024 Aging Management Audit Report- VC Summer, Unit 1 - Subsequent License Renewal Application ML24177A2792024-06-20020 June 2024 Preparation and Scheduling of Operator Licensing Examinations ML24171A0152024-06-17017 June 2024 Update to Subsequent License Renewal Application (SLRA) Response to NRC Request for Additional Information Set 2 Safety Review ML24157A3352024-06-0606 June 2024 – Notification of an NRC Cybersecurity Baseline Inspection (NRC Inspection Report 05000395-2024404 and Request for Information ML24155A2042024-05-31031 May 2024 Proposed Alternative Request RR-24-123, Containment Unbonded Post-Tensioning System Inservice Inspection Requirements ML24155A1462024-05-30030 May 2024 Update to Subsequent License Renewal Application (SLRA) -Response to NRC Request for Additional Information Set 1 Response to NRC Request for Confirmation of Information Set 1 and Supplement 3 ML24143A1792024-05-22022 May 2024 Special Report 2024-001-01 for Virgil C. Summer Nuclear Station (Vcsns), Unit 1, Waste Gas System Inoperability ML24141A2822024-05-20020 May 2024 (Vcsns), Unit 1 - License Amendment Request - Emergency Response Organization (ERO) Augmentation Time Change, Emergency Operations Facility Relocation and Other Emergency Plan Changes IR 05000395/20240012024-05-10010 May 2024 Integrated Inspection Report 05000395/2024001 ML24129A2002024-05-0606 May 2024 Update to Subsequent License Renewal Application, Supplement 2 IR 05000395/20240402024-05-0101 May 2024 95001 Supplemental Inspection Report 05000395/2024040 and Follow-Up Assessment Letter ML24120A2072024-04-29029 April 2024 Submittal of Annual Radiological Environmental Operating Report ML24121A1002024-04-29029 April 2024 Response to Request for Additional Information Regarding Alternative Request RR-5-V2 ML24116A2052024-04-23023 April 2024 Annual Radioactive Effluent Release Report ML24109A1792024-04-19019 April 2024 Aging Management Audit Plan Regarding the Subsequent License Renewal Application Review ML24108A0392024-04-18018 April 2024 Letter to E Carr-V.C. Summer Unit 1- Regulatory Audit Regarding the Environmental Review of the Subsequent License Renewal Application ML24108A1432024-04-17017 April 2024 (Vcsns), Unit 1, Automatic Actuation of B Emergency Diesel Generator ML24108A0672024-04-17017 April 2024 Submittal of Summary for Condition of the Service Water Intake Structure Provided in Accordance with License Condition 2.C.5.d ML24100A7312024-04-0909 April 2024 Personnel Exposure and Monitoring Annual Report ML24095A2072024-04-0101 April 2024 Update to Subsequent License Renewal Application (SLRA) Supplement 1 ML24088A2062024-03-26026 March 2024 Annual Operating Report ML24087A2182024-03-26026 March 2024 (Vcsns), Unit 1 - License Amendment Request - Emergency Response Organization (ERO) Augmentation Time Change, Emergency Operations Facility Relocation and Other Emergency Plan Changes - Response to Request. ML24087A2262024-03-26026 March 2024 License Amendment Request - Inverter Allowed Outage Time Extension Response to Request for Additional Information ML24067A0232024-03-0707 March 2024 (Vcsns), Unit 1 - Readiness for 95001 Supplemental Inspection; EA-23-093 IR 05000395/20230062024-02-28028 February 2024 Annual Assessment Letter for Virgil C. Summer Nuclear Station - Report 05000395/2023006 IR 05000395/20244032024-02-27027 February 2024 Security Baseline Inspection Report 05000395/2024403 ML24057A1132024-02-22022 February 2024 Special Report 2024-001 Waste Gas System Inoperability ML24051A0112024-02-20020 February 2024 Fws to NRC, List of Threatened and Endangered Species That May Occur in Proposed Project Location or May Be Affected by Proposed Project for V.C. Summer SLR ML24057A0612024-02-19019 February 2024 and Virgil C. Summer Power Nuclear Stations - Nuclear Property Insurance Coverage ML24032A3062024-02-15015 February 2024 Exemption from Select Requirements of 10 CFR Part 73 - Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML24040A1802024-02-12012 February 2024 Notification of NRC Supplemental Inspection (95001) and Request for Information 2024-09-26
[Table view] |
Text
Stephen A. Byrne Senior Vice President, Nuclear Operations 803.345.4622 A SCANA COMPANY October 23, 2003 RC-03-0221 Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555
Dear Sir/Madam:
Subject:
VIRGIL C. SUMMER NUCLEAR STATION (VCSNS)
DOCKET NO. 50/395 OPERATING LICENSE NO. NPF-12 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING REQUEST TO USE ALTERNATIVES TO ASME BOILER AND PRESSURE VESSEL CODE, SECTION Xi, RELIEF REQUEST RR-11-1 1, RR-11-12 (0-C-02-3202)
Reference:
- 1. SCE&G Letter to NRC (Document Control Desk), RC-03-0197, dated September 16, 2003, Resubmittal of Request To Use Alternatives To ASME Boiler and Pressure Vessel Code, Section Xi, (C-03-0262), RR-11-9, RR-11-10, RR-11-11, and, RR-11-12
- 2. SCE&G Letter to NRC (Document Control Desk), RC-02-0191, dated October 30, 2002, Request To Use Alternatives To ASME Boiler and Pressure Vessel Code, Section Xi, RR-11-8, RR-II-9, RR-11-10, RR-II-11, RR-1-12
- 3. NRC (K. R. Cotton) Letter to VCSNS October 2, 2003, Request for Additional Information ISI Relief Request RR-11-1 1, and 12 (TAC NO.
MB6647)
South Carolina Electric & Gas Company (SCE&G) hereby submits the attached response to the referenced request for additional information (RAI) regarding relief requests RR-11-1land RR-1-12 resubmitted by Reference I on September 16, 2003.
Based on Question 5.1 for relief request RR-11-11 and the accompanying response, SCE&G requests withdrawal of RR-11-11. Code Case N-598 was not yet accepted when Relief was applied for. As Code Case N-598 has been endorsed by Regulatory Guide 1.147, Revision 13, RR-11-11 is no longer needed by VCSNS. Also, two of the proposed areas for relief in RR-11-12 may be withdrawn, however, requested item (c) and the accompanying proposed alternative test (c) are requested for approval. Item (c) utilizes ASME Code Case N 307-3 (Revision 3) which is not yet endorsed by the NRC in Regulatory Guide 1.147 (Revision 13). 4 0(4 SCEG I Virgil CSummer Nucleor Station
- P.O. Box B8.Jenkinsille, South (rolina 29065.T (803) 345.5209 .www.scono.com
Document Control Desk 0-C-02-3202 RC-03-0221 Page 2 of 2 Should you have any questions, please call Mr. Ron Clary at (803) 345-4757.
Very truly yours, St pen A. Byrne £Sb o '43703 JT/SAB/dr Attachments (2) c: N. 0. Lorick N. S. Cams T. G. Eppink (w/o Attachiments)
R. J. White L. A. Reyes K. R. Cotton K. M. Sutton General Managers NRC Resident Inspector T. A. Mcalister A. R. Caban NSRC RTS (0-C-02-3202)
File (810.19-2)
DMS (RC-03-0221)
Document Control Desk Attachment I 0-C-02-3202 RC-03-0221 Page 1 of 1 South Carolina Electric & Gas Company (SCE&G)
Virgil C. Summer Nuclear Station (VCSNS)
Response to NRC Request for Additional Information (RAI)
Regarding Inservice Inspection Relief Request RR-11-11 TAC MB6647 - submittal dated October 30, 2002 as supplemented September 16, 2003 (RC-03-0197) and TAC MC0108 - submittal dated July 11, 2003 as supplemented September 16, 2003 (RC-03-0196).
5.0 RR-11-11, September 16, 2003 (RC-03-0197) submittal:
5.1 In the submittal, the alternate test section proposes using Code Case N-598 as an alternative to the selection percentages for the components subject to examination. Code Case N-598 is endorsed in Regulatory Guide 1.147, Revision 13. Explain the need for relief.
Response 5.1:
Code Case N-598 can be applied as approved in RG 1.147 without relief. It is requested that Relief request RR-11-1 1 be withdrawn.
Document Control Desk Attachment II O-C-02-3202 RC-03-0221 Page 1 of 2 South Carolina Electric & Gas Company (SCE&G)
Virgil C. Summer Nuclear Station (VCSNS)
Response to NRC Request for Additional Information (RAI)
Regarding Inservice Inspection Relief Request RR-11-12 TAC MB6647 - submittal dated October 30, 2002 as supplemented September 16, 2003 (RC-03-0197) and TAC MC0108 - submittal dated July 11, 2003 as supplemented September 16, 2003 (RC-03-0196).
4.0 RR-11-12, September 16, 2003 (RC-03-0197) submittal:
4.1 In the submittal, the alternate test section (a) refers to examinations that had been previously deferred. Was the deferral for the first or second ISI interval?
Provide the reference requestinglauthorizing the deferral.
The deferral is associated with closure bolting examinations (Item B6.20). Does the deferral apply to the other items?
Response 4.1:
The Code allowed "deferral" referenced was for the first Interval. The first Interval examinations were performed in accordance with the 1977 Edition, 1978 Summer Addenda. This edition of the code did not specifically address deferral of these items.
The first interval Code examinations for category B-G-1 components were scheduled and performed in the final outage of the interval.
This request is associated with item numbers B6.10, B6.20, B6.40, B6.50 and B6.180.
4.2 In the submittal, Table IWB-2500-1 for the 1989 Edition of the Code provides in Footnote (5) a condition that permits deferring the examination until the end of the interval. Does Footnote (5) apply to any of the Items in this request? Islare there any ASME interpretation concerning deferring examination to the end of the interval?
Response 4.2:
The items detailed in this relief do specifically have application to footnote 5. There are no pertinent interpretations that apply to this relief. SCE&G requests that Item (a) and proposed Alternate Test (a) be withdrawn as the 1989 Edition of the Code allows for deferral of this item.
Document Control Desk Attachment II 0-C-02-3202 RC-03-0221 Page 2 of 2 4.3 The subject of permitting deferral to the end of the interval has changed several times in ASME Code. For example, the ASME Code permitted deferring the examination through the 1983 Edition and again in the 1992 Edition with 1994 Addenda and later editions and addenda. Discuss the ASME Code change that resulted in the limitation on deferring examinations to the end of the interval and in Footnote (5) for the interval between the 1983 Edition and 1992 Edition with 1994 Addenda.
Response 4.3:
The applicable Code for the first Interval was the 1977 Edition, 1978 Summer Addenda. The current Code for the second Interval is the 1989 Edition.
The Code has changed the presentation and content of the 2500 Tables during this time frame. The major change is the addition of the last column for deferral applicability. The 1977 Edition for the first interval contained limited verbiage concerning deferrals. The 1989 Edition has specific reference for deferrals for each item. There is some confusion as to the whether both items B6.20 and B6.30 examinations are required to be performed each interval. Allowing the deferral of item B6.20 to the end of the interval would clarify the scheduling examinations of the reactor vessel closure studs.
The VCNS second interval examinations for category B-G-1, items B6.10, B6.20, B6.40, B6.50 and B6.180 can be performed in accordance with the 1989 Edition of the code with the allowed deferral options of footnote 5.
4.4 In the submittal, the relief request section (b) references Item B6.10 and the alternate test section proposes using Code Case N-627 as an alternative to the surface examination for Item B6.10. Code Case N-627 is endorsed in Regulatory Guide 1.147, Revision 13. Explain the need for relief.
Response 4.4:
Code Case N-627 can be applied as approved in RG 1.147 without relief. It is requested that Relief request RR-11-12, Item (b) and proposed Alternate Test (b) be withdrawn. Also, SCE&G requests that Item (a) and proposed Alternate Test (a) be withdrawn as the 1989 Edition of the Code allows for deferral of this item.