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| | number = ML15118A380 | | | number = ML15118A380 |
| | issue date = 05/05/2015 | | | issue date = 05/05/2015 |
| | title = Virgil C. Summer Nuclear Station, Unit 1 - Request for Additional Information Regarding Snubber Program Alternative Request (TAC No. MF5775) | | | title = Request for Additional Information Regarding Snubber Program Alternative Request |
| | author name = Williams S A | | | author name = Williams S |
| | author affiliation = NRC/NRR/DORL/LPLII-1 | | | author affiliation = NRC/NRR/DORL/LPLII-1 |
| | addressee name = Gatlin T D | | | addressee name = Gatlin T |
| | addressee affiliation = South Carolina Electric & Gas Co | | | addressee affiliation = South Carolina Electric & Gas Co |
| | docket = 05000395 | | | docket = 05000395 |
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| | page count = 4 | | | page count = 4 |
| | project = TAC:MF5775 | | | project = TAC:MF5775 |
| | stage = Other | | | stage = RAI |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Thomas D. Gatlin Vice President, Nuclear Operations South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station Post Office Box 88, Mail Code 800 Jenkinsville, SC 29065 May 5, 2015 SUBJECT: VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO. 1 -REQUEST FOR ADDITIONAL INFORMATION REGARDING SNUBBER PROGRAM ALTERNATIVE REQUEST (TAC NO. MF5775) Dear Mr. Gatlin: By letter dated February 19, 2015, the South Carolina Electric & Gas Company (SCE&G, the licensee) submitted an alternative request for Virgil C. Summer, Unit 1. SCE&G proposes to perform the visual examination of snubbers and associated attachment hardware per the Snubber Program that will be documented in a surveillance test procedure per the American Society of Mechanical Engineers (ASME) OM Code, Subsection ISTD. The NRC staff has determined that additional information is needed to continue the review as discussed in the Enclosure. We request that SCE&G respond to these RAls within 30 days of the date of this letter. Please note that the NRC staff's review is continuing and further requests for information may be developed. Docket No. 50-395 Enclosure: Request for Additional Information cc w/encl: Distribution via Listserv Sincerely, Shawn Williams, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation REQUEST FOR ADDITIONAL INFORMATION ALTERNATIVE REQUEST REGARDING THE SNUBBER PROGRAM VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO. 1 DOCKET NO. 50-395 The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the South Carolina Electric & Gas Company .(SCE&G) alternative request dated February 19, 2015 (Agencywide Documents Access and Management System Accession No. ML 15055A588), for the Virgil C. Summer Nuclear Station, Unit 1. The NRC staff has determined that the following request for additional information (RAI) is required to complete its review. RAI No.1 In submitted relief request, two different ASME Codes are being used (a) ASME OM Code for snubbers (pin-to-pin), and (b) ASME Boiler & Vessel Code, Section XI for snubber C!SSociated attachment hardware (pin-to-pipe and pin-to-structure) excluding integral attachments. The submittal states ASME Section XI is 2007 Edition with 2008 Addenda. Please verify that ASME OM Code 2004 Edition will be used. RAI No. 2 In Relief Request RR-4-08, Section 4, "Reason for Request," it states that "VCSNS Unit 1 is required to perform VT-3 visual examination on Class 1, 2, and 3 supports, including attachment hardware, per ASME Section XI. VCSNS is also required to perform visual examinations and testing on snubber assemblies in accordance with ASME OM Code, Subsection ISTD. When incorporating the criteria of Subsection ISTD into the Snubber Program, VCSNS Unit 1 will update Surveillance Test Procedure STP-803.002, Mechanical Snubber Visual Examination to include the visual examination of snubber attachment hardware (pin-to-pipe and structure) along with the visual examination of the snubber assembly (pin-to-pin). With the proposed procedure update, the visual examination criteria of snubber program will meet the . requirements established by ASME Section XI. (1) Please verify and confirm that the proposed visual examination criteria of the Snubber Program will be identical to the VT-3 visual examination per IWA-2213 (IWA-2213(a) thru IWA-2213(9)) of ASME Section XI, Edition 2007 with 2008 Addenda. (2) The relief request did not mention details about hydraulic snubbers and the proposed update of the procedure is related to mechanical snubbers. Please verify that hydraulic snubbers are not installed at VCSNS or VCSNS hydraulic snubbers procedures will be revised | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 5, 2015 Mr. Thomas D. Gatlin Vice President, Nuclear Operations South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station Post Office Box 88, Mail Code 800 Jenkinsville, SC 29065 |
| * to add the VT-3 requirements. | | |
| -2 -RAI No. 3 In a VCSNS, Unit 1, Technical Specification amendment request submittal dated October 3, 2013 (ADAMS Accession No. ML 13281A 190), Attachment 5, "Snubber Examination, Testing, and Service Life Monitoring (SLM) Program Plan." (a) Section 1.3 states, in part, that inspection, testing and SLM of snubbers shall be implemented and performed in accordance with the requirements of SAP-101, "Station Administrative Snubber Program Document". Please verify and confirm that VT-3 will be implemented in STP-101 along with Procedure STP-803.002. (b) Section 4.2, states that VCSNS will be implementing Code Case OMN-13 to extend visual examination of snubbers (pin-to-pin) frequency at least once every 10 years. Please provide the frequency of visual examination of snubbers associated attachment hardware to-pipe and pin-to-structure) during this extended 10 year interval. RAI No. 4 * 'While using OMN-13 for snubbers during the extended interval of 10 years, if the number of unacceptable snubbers (pin-to-pin) exceeds the ISTD-4252-1 limits (these unacceptable snubbers can be found during non-inspection activities such as walkdowns or any other events i.e. water hammer, etc.), what action will be taken and how will these findings align with the supports and attachments inspection. RAINo.5 IWF-2430(a) states, in part, that component supports examinations performed in accordance
| | ==SUBJECT:== |
| * with Table IWF-2500-1 that reveal flaws or relevant conditions exceeding the acceptance standards of IWF-3400, and that require corrective measures, shall be extended, during the current outage, to include the component supports immediately adjacent to flawed supports. Please explain how this situation (to include supports adjacent to flawed supports) will be considered, while using the proposed r:elief request to perform the visual examination of snubbers (pin-to-pin) and associated attachment hardware (pin-to-pipe and pin-to-structure, excluding integral attachments). (Note: The adjacent flawed supports could be with or without a snubber). RAI No. 6 NRC staff believes that the contents of referenced precedence documents listed in the Section 7, "Precedents," are different than the submitted relief request of RR-4-08. Please verify and revise as appropriate. | | VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO. 1 - REQUEST FOR ADDITIONAL INFORMATION REGARDING SNUBBER PROGRAM ALTERNATIVE REQUEST (TAC NO. MF5775) |
| . ,, May 5, 2015 Mr. Thomas D. Gatlin Vice President, Nuclear Operations South Carolina Electric & Gas Company Virgil C. Summer Nyclear Station Post Office Box 88, Mail Code 800 Jenkinsville, SC 29065 SUBJECT: VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO. 1 -REQUEST FOR ADDITIONAL.INFORMATION REGARDING SNUBBER PROGRAM ALTERNATIVE REQUEST (TAC NO. MF5775) Dear Mr. Gatlin: By letter dated February 19, 2015, the South Carolina Electric & Gas Company (SCE&G, the licensee) submitted an alternative request for Virgil C. Summer, Unit 1. SCE&G proposes to | | |
| * perform the visual examination of snubbers and associated attachment hardware per the Snubber Program that will be documented in a surveillance test procedure per the American Society of Mechanical Engineers (ASME) OM Code, Subsection ISTD. The NRC staff has determined that additional information is needed to continue the review as discussed in the Enclosure. We request that SCE&G respond to these RAls within 30 days of the date of this letter. Please note that the NRC staff's review is continuing and further requests for information may be developed. Docket No. 50-395 Enclosure: Sincerely, /RAJ Shawn Williams, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION: PUBLIC RidsNrrDorlDpr Resource RidsNrrLASFigueroa Resource BGurjendra, NRR LPL2-1 R/F RidsNrrDorllpl2-1 Resource RidsNrrDRA Resource RidsAcrsAcnw_MailCTR Resource RidsRgn2MailCenter Resource RidsNrrPMSummer Resource ADAMS Accession No.: ML15118A380 *by email OFFICE LPL2-1/PM LPL2-1/LA NRR/DE/EPNB/BC LPL2-1/BC LPL2-1/PM NAME SWilliams $Figueroa DAiiey* RPascarelli $Williams. DATE 04/30/15 04/30/15 04/29/15 05/05/15 05/05/15 OFFICIAL RECORD COPY
| | ==Dear Mr. Gatlin:== |
| }} | | |
| | By letter dated February 19, 2015, the South Carolina Electric & Gas Company (SCE&G, the licensee) submitted an alternative request for Virgil C. Summer, Unit 1. SCE&G proposes to perform the visual examination of snubbers and associated attachment hardware per the Snubber Program that will be documented in a surveillance test procedure per the American Society of Mechanical Engineers (ASME) OM Code, Subsection ISTD. |
| | The NRC staff has determined that additional information is needed to continue the review as discussed in the Enclosure. We request that SCE&G respond to these RAls within 30 days of the date of this letter. Please note that the NRC staff's review is continuing and further requests for information may be developed. |
| | Sincerely, Shawn Williams, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-395 |
| | |
| | ==Enclosure:== |
| | |
| | Request for Additional Information cc w/encl: Distribution via Listserv |
| | |
| | REQUEST FOR ADDITIONAL INFORMATION ALTERNATIVE REQUEST REGARDING THE SNUBBER PROGRAM VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO. 1 DOCKET NO. 50-395 The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the South Carolina Electric & |
| | Gas Company .(SCE&G) alternative request dated February 19, 2015 (Agencywide Documents Access and Management System Accession No. ML15055A588), for the Virgil C. Summer Nuclear Station, Unit 1. The NRC staff has determined that the following request for additional information (RAI) is required to complete its review. |
| | RAI No.1 In submitted relief request, two different ASME Codes are being used (a) ASME OM Code for snubbers (pin-to-pin), and (b) ASME Boiler & Vessel Code, Section XI for snubber C!SSociated attachment hardware (pin-to-pipe and pin-to-structure) excluding integral attachments. The submittal states ASME Section XI is 2007 Edition with 2008 Addenda. Please verify that ASME OM Code 2004 Edition will be used. |
| | RAI No. 2 In Relief Request RR-4-08, Section 4, "Reason for Request," it states that "VCSNS Unit 1 is required to perform VT-3 visual examination on Class 1, 2, and 3 supports, including attachment hardware, per ASME Section XI. VCSNS is also required to perform visual examinations and testing on snubber assemblies in accordance with ASME OM Code, Subsection ISTD. When incorporating the criteria of Subsection ISTD into the Snubber Program, VCSNS Unit 1 will update Surveillance Test Procedure STP-803.002, Mechanical Snubber Visual Examination to include the visual examination of snubber attachment hardware (pin-to-pipe and pin-to-structure) along with the visual examination of the snubber assembly (pin-to-pin). With the proposed procedure update, the visual examination criteria of snubber program will meet the |
| | . requirements established by ASME Section XI. |
| | (1) Please verify and confirm that the proposed visual examination criteria of the Snubber Program will be identical to the VT-3 visual examination per IWA-2213 (IWA-2213(a) thru IWA-2213(9)) of ASME Section XI, Edition 2007 with 2008 Addenda. |
| | (2) The relief request did not mention details about hydraulic snubbers and the proposed update of the procedure is related to mechanical snubbers. Please verify that hydraulic snubbers are not installed at VCSNS or VCSNS hydraulic snubbers procedures will be revised |
| | * to add the VT-3 requirements. |
| | |
| | RAI No. 3 In a VCSNS, Unit 1, Technical Specification amendment request submittal dated October 3, 2013 (ADAMS Accession No. ML13281A190), Attachment 5, "Snubber Examination, Testing, and Service Life Monitoring (SLM) Program Plan." |
| | (a) Section 1.3 states, in part, that inspection, testing and SLM of snubbers shall be implemented and performed in accordance with the requirements of SAP-101, "Station Administrative Snubber Program Document". Please verify and confirm that VT-3 will be implemented in STP-101 along with Procedure STP-803.002. |
| | (b) Section 4.2, states that VCSNS will be implementing Code Case OMN-13 to extend visual examination of snubbers (pin-to-pin) frequency at least once every 10 years. Please provide the frequency of visual examination of snubbers associated attachment hardware (pin-to-pipe and pin-to-structure) during this extended 10 year interval. |
| | RAI No. 4 |
| | * 'While using OMN-13 for snubbers during the extended interval of 10 years, if the number of unacceptable snubbers (pin-to-pin) exceeds the ISTD-4252-1 limits (these unacceptable snubbers can be found during non-inspection activities such as walkdowns or any other events i.e. water hammer, etc.), what action will be taken and how will these findings align with the supports and attachments inspection. |
| | RAINo.5 IWF-2430(a) states, in part, that component supports examinations performed in accordance |
| | * with Table IWF-2500-1 that reveal flaws or relevant conditions exceeding the acceptance standards of IWF-3400, and that require corrective measures, shall be extended, during the current outage, to include the component supports immediately adjacent to flawed supports. |
| | Please explain how this situation (to include supports adjacent to flawed supports) will be considered, while using the proposed r:elief request to perform the visual examination of snubbers (pin-to-pin) and associated attachment hardware (pin-to-pipe and pin-to-structure, excluding integral attachments). (Note: The adjacent flawed supports could be with or without a snubber). |
| | RAI No. 6 NRC staff believes that the contents of referenced precedence documents listed in the Section 7, "Precedents," are different than the submitted relief request of RR-4-08. Please verify and revise as appropriate. |
| | |
| | ML15118A380 *by email OFFICE LPL2-1/PM LPL2-1/LA NRR/DE/EPNB/BC LPL2-1/BC LPL2-1/PM NAME SWilliams $Figueroa DAiiey* RPascarelli $Williams. |
| | DATE 04/30/15 04/30/15 04/29/15 05/05/15 05/05/15}} |
|
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Category:Letter
MONTHYEARIR 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 ML24178A1192024-06-25025 June 2024 Update to License Amendment Request- Inverter Allowed Outage Time (AOT) Extension 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 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 ML24121A1002024-04-29029 April 2024 Response to Request for Additional Information Regarding Alternative Request RR-5-V2 ML24120A2072024-04-29029 April 2024 Submittal of Annual Radiological Environmental Operating Report 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 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 ML24087A2262024-03-26026 March 2024 License Amendment Request - Inverter Allowed Outage Time Extension Response to Request for Additional Information 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. 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 IR 05000395/20244012024-02-0808 February 2024 Security Baseline Inspection Report 05000395/2024401 ML24038A0322024-02-0707 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 ML24022A1202024-01-22022 January 2024 Notification of Target Set Inspection and Request for Information (NRC Inspection Report 05000395/2024403) ML24022A1582024-01-22022 January 2024 (Vcsns), Unit 1 - Reply to a Notice of Violation: EA-23-093 ML24018A0112024-01-18018 January 2024 CFR 21 Report Emergency Diesel Generator Fuel Oil Piping 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 2024-08-05
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24190A0412024-07-0505 July 2024 Notification of Inspection and Request for Information ML24156A0032024-06-0303 June 2024 VC Summer SLRA - Requests for Additional Information - Set 2 ML24075A1872024-03-15015 March 2024 NRR E-mail Capture - Draft RAIs for Alternative Request RR-5-V2 (L-2023-LLR-0068) ML24067A0672024-03-0707 March 2024 NRR E-mail Capture - Draft RAIs for Inverter CT License Amendment Request TS 3.8.3.1, “Onsite Power Distribution - Operating,” (L-2023-LLA-0157) ML24052A0102024-02-16016 February 2024 NRR E-mail Capture - Draft RAIs for Emergency Plan (EP) Changes License Amendment Request (LAR) (L-2023-LLA-0083) ML23270B8712023-09-27027 September 2023 NRR E-mail Capture - Draft RAIs for License Amendment Request (LAR) to Revise the Virgil C. Summer Nuclear Station (VCSNS) Unit 1 Emergency Plan (L-2023-LLA-0083) ML22263A0502022-09-19019 September 2022 NRR E-mail Capture - Draft Request for Additional Information for Proposed Alternative Request RR-4-26 Extension of Steam Generator Primary Inlet Nozzle Dissimilar Metal Weld Inspection Interval V.C. Summer Unit 1 ML22194A9422022-07-13013 July 2022 NRC 50.59 Inspection (IP 71111.17T) Information Request ML22075A0482022-03-16016 March 2022 V.C. Summer Nuclear Station - Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000395/2022401 ML21333A1892021-11-29029 November 2021 NRR E-mail Capture - Draft RAI for Summer LAR Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5b, (TSTF-425) ML21253A1352021-09-0808 September 2021 Document Request for VC Summer Nuclear Station - Radiation Protection Inspection - Inspection Report 2021-04 ML21154A2792021-06-0303 June 2021 Requalification Program Inspection 05000395/2021003 - Virgil C. Summer Nuclear Station, Unit 1, ML21145A0222021-05-24024 May 2021 003 Radiation Safety Baseline Inspection Information Request ML21131A0402021-05-11011 May 2021 NRR E-mail Capture - V.C. Summer, Unit 1 - Final RAI for the Spring 2020 RFO Sgtir Review ML21020A0562021-01-20020 January 2021 Email Capture Upcoming V.C. Summer POV Inspection (IP71111.21N.02) Information Request ML20342A3822020-12-0707 December 2020 NRR E-mail Capture - Final RAIs for Summer Fs LOCA LAR ML20342A1822020-12-0707 December 2020 NRR E-mail Capture - Final RAI for Summer LAR - TS 3.6.4 ML20321A2112020-11-16016 November 2020 NRR E-mail Capture - Summer, Unit 1 - Final RAIs for the SG Tube Inspection Report Review ML20196L7782020-07-13013 July 2020 Notification of Virgil C. Summer Nuclear Station Design Bases Assurance Inspection U.S. Nuclear Regulatory Commission Inspection Report 05000395/2020010 ML20106E8902020-04-15015 April 2020 Program Inspection RFI ML20056E3042020-02-25025 February 2020 VC Summer 2020-002 Radiation Safety Baseline Inspection Information Request ML19211D5102019-07-30030 July 2019 NRR E-mail Capture - Virgil C. Summer Nuclear Station, Unit No. 1 - Request for Additional Information LAR-16-01490 NFPA-805 (Supplement to PRA RAI 03) ML19179A1262019-06-27027 June 2019 NRR E-mail Capture - Virgil C. Summer Nuclear Station, Unit No. 1 - Request for Additional Information LAR-16-01490 NFPA-805 Program Revisions ML19095A6532019-04-0404 April 2019 NRR E-mail Capture - Virgil C. Summer Nuclear Station, Unit No. 1 - Request for Additional Information NFPA-805 Program Revisions LAR ML19072A1442019-03-13013 March 2019 NRR E-mail Capture - Virgil C. Summer Nuclear Station, Unit No. 1 - Request for Additional Information LAR-16-01490 NFPA-805 Program Revisions ML19009A1052019-01-0909 January 2019 NRR E-mail Capture - Virgil C. Summer Nuclear Station, Unit No. 1 - Request for Additional Information LAR-10-02395, TS 3.8.2, D.C. Sources - Operating ML18249A1932018-09-0505 September 2018 TS 4.3.3.6 SR LAR - Request for Additional Information ML18225A0932018-08-13013 August 2018 Notification of Inspection and Request for Information ML18218A2622018-08-0101 August 2018 Emergency Preparedness Program Inspection Request for Information ML18066A0002018-03-0808 March 2018 Request for Additional Information Integrated Leak Rate Test Peak Calculated Containment Internal Pressure Change ML18023B0692018-02-15015 February 2018 Request for Additional Information Relief Request (RR-4-13), Use of Risk-Informed Process as an Alternative for the Selection of Class 1 and Class 2 Piping Welds ML17095A2842017-05-11011 May 2017 Request for Additional Information License Amendment Request for Implementation of TSTF-411 (WCAP-15376-P-A), Revision 1 ML17067A5322017-03-0808 March 2017 Notification of Radiation Protection Baseline Inspection and Request for Information ML17059C5382017-02-23023 February 2017 Notification of Inspection and Request for Information ML16302A1252016-11-0808 November 2016 Request for Additional Information License Amendment Request for Implementation of TSTF-411 and WCAP-15376-P-A, Revision 1 RC-16-0112, NRC Request Information Baseline Radiation Safety Inspection2016-07-0707 July 2016 NRC Request Information Baseline Radiation Safety Inspection ML16111A0912016-05-0303 May 2016 Request for Additional Information Regarding the Station Physical Security Plan, Revision 14 ML16097A0812016-04-0808 April 2016 Request for Additional Information ML16064A0332016-03-0303 March 2016 NRR E-mail Capture - Request for Additional Information Related to the March 1, 2016, Exigent Amendment Request ML16042A4712016-02-18018 February 2016 Request for Additional Information ML15320A3382015-12-0101 December 2015 Request for Additional Information Regarding License Basis Changes in Steam Generator Tube Rupture Analysis RC-15-0177, Submits LAR-12-04269, License Basis Changes in Steam Generator Tube Rupture Analysis Response to Response for Additional Information2015-11-0505 November 2015 Submits LAR-12-04269, License Basis Changes in Steam Generator Tube Rupture Analysis Response to Response for Additional Information ML15261A0512015-09-22022 September 2015 Request for Additional Information Regarding License Basis Changes in Steam Generator Tube Rupture Analysis ML15118A4592015-05-19019 May 2015 Request for Additional Information Regarding Alternative Request ML15118A3802015-05-0505 May 2015 Request for Additional Information Regarding Snubber Program Alternative Request ML15076A1182015-04-13013 April 2015 Request for Additional Information Regarding License Basis Changes in Steam Generator Tube Rupture Analysis ML15079A0992015-03-26026 March 2015 Request for Additional Information ML14339A0302015-01-0909 January 2015 Request for Additional Information Regarding License Basis Changes in Steam Generator Tube Rupture Analysis ML14268A5162014-10-23023 October 2014 Request for Additional Information Associated with Near-Term Task Force Recommendation 2.1, Seismic Re-evaluation Related to Southeastern Catalog Changes ML14226A2552014-08-29029 August 2014 Request for Additional Information 2024-07-05
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 5, 2015 Mr. Thomas D. Gatlin Vice President, Nuclear Operations South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station Post Office Box 88, Mail Code 800 Jenkinsville, SC 29065
SUBJECT:
VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO. 1 - REQUEST FOR ADDITIONAL INFORMATION REGARDING SNUBBER PROGRAM ALTERNATIVE REQUEST (TAC NO. MF5775)
Dear Mr. Gatlin:
By letter dated February 19, 2015, the South Carolina Electric & Gas Company (SCE&G, the licensee) submitted an alternative request for Virgil C. Summer, Unit 1. SCE&G proposes to perform the visual examination of snubbers and associated attachment hardware per the Snubber Program that will be documented in a surveillance test procedure per the American Society of Mechanical Engineers (ASME) OM Code, Subsection ISTD.
The NRC staff has determined that additional information is needed to continue the review as discussed in the Enclosure. We request that SCE&G respond to these RAls within 30 days of the date of this letter. Please note that the NRC staff's review is continuing and further requests for information may be developed.
Sincerely, Shawn Williams, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-395
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION ALTERNATIVE REQUEST REGARDING THE SNUBBER PROGRAM VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO. 1 DOCKET NO. 50-395 The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the South Carolina Electric &
Gas Company .(SCE&G) alternative request dated February 19, 2015 (Agencywide Documents Access and Management System Accession No. ML15055A588), for the Virgil C. Summer Nuclear Station, Unit 1. The NRC staff has determined that the following request for additional information (RAI) is required to complete its review.
RAI No.1 In submitted relief request, two different ASME Codes are being used (a) ASME OM Code for snubbers (pin-to-pin), and (b) ASME Boiler & Vessel Code,Section XI for snubber C!SSociated attachment hardware (pin-to-pipe and pin-to-structure) excluding integral attachments. The submittal states ASME Section XI is 2007 Edition with 2008 Addenda. Please verify that ASME OM Code 2004 Edition will be used.
RAI No. 2 In Relief Request RR-4-08, Section 4, "Reason for Request," it states that "VCSNS Unit 1 is required to perform VT-3 visual examination on Class 1, 2, and 3 supports, including attachment hardware, per ASME Section XI. VCSNS is also required to perform visual examinations and testing on snubber assemblies in accordance with ASME OM Code, Subsection ISTD. When incorporating the criteria of Subsection ISTD into the Snubber Program, VCSNS Unit 1 will update Surveillance Test Procedure STP-803.002, Mechanical Snubber Visual Examination to include the visual examination of snubber attachment hardware (pin-to-pipe and pin-to-structure) along with the visual examination of the snubber assembly (pin-to-pin). With the proposed procedure update, the visual examination criteria of snubber program will meet the
. requirements established by ASME Section XI.
(1) Please verify and confirm that the proposed visual examination criteria of the Snubber Program will be identical to the VT-3 visual examination per IWA-2213 (IWA-2213(a) thru IWA-2213(9)) of ASME Section XI, Edition 2007 with 2008 Addenda.
(2) The relief request did not mention details about hydraulic snubbers and the proposed update of the procedure is related to mechanical snubbers. Please verify that hydraulic snubbers are not installed at VCSNS or VCSNS hydraulic snubbers procedures will be revised
- to add the VT-3 requirements.
RAI No. 3 In a VCSNS, Unit 1, Technical Specification amendment request submittal dated October 3, 2013 (ADAMS Accession No. ML13281A190), Attachment 5, "Snubber Examination, Testing, and Service Life Monitoring (SLM) Program Plan."
(a) Section 1.3 states, in part, that inspection, testing and SLM of snubbers shall be implemented and performed in accordance with the requirements of SAP-101, "Station Administrative Snubber Program Document". Please verify and confirm that VT-3 will be implemented in STP-101 along with Procedure STP-803.002.
(b) Section 4.2, states that VCSNS will be implementing Code Case OMN-13 to extend visual examination of snubbers (pin-to-pin) frequency at least once every 10 years. Please provide the frequency of visual examination of snubbers associated attachment hardware (pin-to-pipe and pin-to-structure) during this extended 10 year interval.
RAI No. 4
- 'While using OMN-13 for snubbers during the extended interval of 10 years, if the number of unacceptable snubbers (pin-to-pin) exceeds the ISTD-4252-1 limits (these unacceptable snubbers can be found during non-inspection activities such as walkdowns or any other events i.e. water hammer, etc.), what action will be taken and how will these findings align with the supports and attachments inspection.
RAINo.5 IWF-2430(a) states, in part, that component supports examinations performed in accordance
- with Table IWF-2500-1 that reveal flaws or relevant conditions exceeding the acceptance standards of IWF-3400, and that require corrective measures, shall be extended, during the current outage, to include the component supports immediately adjacent to flawed supports.
Please explain how this situation (to include supports adjacent to flawed supports) will be considered, while using the proposed r:elief request to perform the visual examination of snubbers (pin-to-pin) and associated attachment hardware (pin-to-pipe and pin-to-structure, excluding integral attachments). (Note: The adjacent flawed supports could be with or without a snubber).
RAI No. 6 NRC staff believes that the contents of referenced precedence documents listed in the Section 7, "Precedents," are different than the submitted relief request of RR-4-08. Please verify and revise as appropriate.
ML15118A380 *by email OFFICE LPL2-1/PM LPL2-1/LA NRR/DE/EPNB/BC LPL2-1/BC LPL2-1/PM NAME SWilliams $Figueroa DAiiey* RPascarelli $Williams.
DATE 04/30/15 04/30/15 04/29/15 05/05/15 05/05/15