Letter Sequence Request |
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EPID:L-2019-LLA-0244, Proposed License Amendment Request: Temporary, One Time 14-Day Allowed Outage Time for Replacement of Reserve Station Service Transformer C 5KV Cables to Transfer Bus F (Approved, Closed) |
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MONTHYEARML19309D1992019-10-30030 October 2019 Proposed License Amendment Request: Temporary, One Time 14-Day Allowed Outage Time for Replacement of Reserve Station Service Transformer C 5KV Cables to Transfer Bus F Project stage: Request ML20034F0532020-01-31031 January 2020 Proposed License Amendment Request: Allowed Outage Time Extension for Replacement of Reserve Station Service Transformer C 5KV Cables to Transfer Bus F Response to Request for Clarification and Additional Information Project stage: Request ML20058F9662020-03-16016 March 2020 Issuance of Amendment Nos. 297 and 297 to Revise Technical Specifications 3.16, Emergency Power System, to Allow a One Time 14-Day Allowed Outage Time for Replacement of 5-KV Cables Associated with Reserve Station Project stage: Approval 2020-01-31
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Similar Documents at Surry |
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Category:Drawing
MONTHYEARML20034F0532020-01-31031 January 2020 Proposed License Amendment Request: Allowed Outage Time Extension for Replacement of Reserve Station Service Transformer C 5KV Cables to Transfer Bus F Response to Request for Clarification and Additional Information ML19105B0552019-04-15015 April 2019 Superseded Pages Per Revision No. 01 to Environmental Sampling Program ML0501805082004-07-19019 July 2004 Associated System Drawings in Support of North Anna Power Station Units 1 & 2, and Surry Power Station Units 1 & 2, ASME Section XI Inservice Inspection Program End of Intervals System Pressure Testing ML0413302072004-05-0505 May 2004 Drawing 11548-FM-1E, Rev 10, Machinery Location Reactor Continment Sections A-A, X-X & F-F Surry Power Station - Unit 2. Sheet 1 of 1 ML0413302082004-05-0505 May 2004 Drawing 11548-FM-1F, Rev 9, Mach. Loc. Reactor Cont. Sections B-B. E-E. Y-Y & Z-Z Surry Power Station - Unit 2. Shet 1 of 1 ML0413302092004-05-0505 May 2004 Drawing 11548-FM-10, Rev 9, Mach Loc Reactor Cont Sections C-C & D-D Surry Power Station - Unit 2. Sheet 1 of 1 ML0414804032004-01-30030 January 2004 Drawing 11448-FE-7B, Rev 21, Wiring Diagram Annunciator (ANN-VSP) Surry Power Station - Unit 1. Sheet 1 of 1 ML0414804142002-05-29029 May 2002 Drawing 11448-FB-27A, Rev 16, Plumbing and Fire Protection Service Building Surry Power Station - Unit 1. Sheet 1 of 1 ML0414804152002-01-31031 January 2002 Drawing 11448-FB-25E, Rev 22, Ventilation & Air Conditioning Service Building - El. 9' - 6 Surry Power Station - Unit 1. Sheet 1 of 1 ML19095A2821978-02-22022 February 1978 Response to Request for Information on LOCA Pipe Break Inside Reactor Vessel Cavity ML19095A2841978-02-15015 February 1978 Presenting, Unit 2 Steam Generator Surveillance Program Outage Schedule & Information of Program ML19093B0471977-12-23023 December 1977 Request for NRC Review of Test Performance Data on Defense Apparel Air Hood & for Permission to Continue Using of Hood Indicated by VEPCO Letter of 12/6/1977 with Serial No. 558 ML19093B0821977-12-0101 December 1977 Response to a Letter of 09/14/1977 Regarding the Potential for a Boron Dilution Accident at Surry Unit Nos. 1 & 2 Due to Injection of Contents of Naoh Tank Into Reactor Coolant System ML19093A9671977-09-0101 September 1977 Letter Serial # 374 Dated 08/29/1977 Provided Information Regarding NPSH Available for Lead Safety Injection Pumps at Surry. Determined That Procedures Should Be Implemented to Throttle Valves in Lhsi Pump Discharge ML19098B4441977-06-28028 June 1977 Provide Requested Information Relative to Site Settlement to Close Previously Unresolved Item Identified as 76-15/1, Site Settlement Surveillance ML19095A5541977-01-11011 January 1977 Submit Licensee Event Report No. AO-S1-76-08 Re Broken Stud from 2A Steam Generator Girth Strap with Unit 2 ML19105A1811975-12-31031 December 1975 Submit Supplement to Initial Report Dated 12/4/1975, Which Responded to IE Bulletin 75-04B, as Requested ML19098B2971975-10-28028 October 1975 10/28/1975 Letter Supplemental Information in Technical Specification Change No. 33 2020-01-31
[Table view] Category:Letter
MONTHYEARML24283A0702024-10-0707 October 2024 Annual Submittal of Technical Specifications Bases Changes Pursuant to Technical Specification 6.4.J IR 05000280/20244032024-10-0303 October 2024 Cyber Security Inspection Report 05000280-2024403 and 05000281-2024403 Cover Letter (Public) IR 05000280/20240102024-10-0202 October 2024 Biennial Problem Identification and Resolution Inspection Report 05000280/2024010 and 05000281/2024010 ML24270A0022024-09-25025 September 2024 Inservice Inspection Owners Activity Report (OAR) ML24248A1712024-09-0303 September 2024 Proposed License Amendment Request - Temporary Service Water Supply to the Component Cooling Heat Exchangers IR 05000280/20240052024-08-26026 August 2024 Updated Inspection Plan for Surry Power Station, Units 1 and 2 (Report 05000280/2024005 and 05000281-2024005), Rev 1 ML24219A2372024-08-23023 August 2024 Issuance of Amendment Nos. 319 and 319, Adoption of TSTF-577, Rev. 1, Revised Frequencies for Steam Generator Tube Inspection, ML24207A0402024-08-21021 August 2024 Summary of July 17, 2024, Public Meeting - TS 3.7/3.14 AOT for SW Piping Maintenance IR 05000280/20240112024-08-13013 August 2024 Comprehensive Engineering Team Inspection Report 05000280/2024011 and 05000281/2024011 ML24164A0012024-08-12012 August 2024 Proposed Alternative Relief Request V-1 Inservice Testing of Pressure Isolation Valves (EPID l-2023-LLR-0060) IR 05000280/20240022024-08-0101 August 2024 Integrated Inspection Report 05000280/2024002 and 05000281/2024002 05000280/LER-2024-001, Troubleshooting Initiated Unknown Turbine Trip Feature in Control System2024-07-30030 July 2024 Troubleshooting Initiated Unknown Turbine Trip Feature in Control System ML24165A2782024-07-17017 July 2024 Issuance of Amendment Nos. 318 and 318, Reclassification of Regulatory Guide 1.97 Variable for Low Head Safety Injection ML24165A1232024-07-17017 July 2024 Proposed Alternative Relief Request P-1, P-2 Inservice Testing of Residual Heat and Containment Spray Pumps (EPID l-2023-LLR-0058) ML24190A4192024-07-0808 July 2024 Inservice Testing (IST) Program for Pumps and Valves Revised Sixth IST Interval Start Date and Updated Technical Specifications References for Alternative Request V-1 ML24179A2932024-07-0101 July 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection 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 ML24177A2792024-06-20020 June 2024 Preparation and Scheduling of Operator Licensing Examinations ML24166A0622024-06-18018 June 2024 – Proposed Alternative Relief Request P-3, P-4 Inservice Testing of Boric Acid, Component Cooling Water Pumps ML24157A0542024-06-13013 June 2024 Audit Summary in Support of License Amendment Request for Proposed Reclassification of Low Head Safety Injection Flow Instrumentation Related to Regulatory Guide 1.97 ML24143A1622024-06-12012 June 2024 – Correction to Issuance of Amendment Nos. 297 and 280 and Surry Units 1 and 2, Correction to Issuance of Amendment Nos. 317 and 317, to Change Emergency Plan Staff Augmentation Times ML24170B0532024-06-10010 June 2024 DOM-NAF-2-P/NP-A, Revision 0.5, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code ML24141A2512024-05-20020 May 2024 Proposed License Amendment Request - Reclassification of Low Head Safety Injection Flow Indication Regulatory Guide 1.97 Variable - Supplemental Information ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24136A2302024-05-13013 May 2024 Core 1 Cycle 33 Pattern Mdr Revision 0 ML24130A2492024-05-0909 May 2024 Submittal of Information in Support of Surry Power Station Unit 1 Thermal Shield Flexure Replacement Campaign ML24130A2032024-05-0909 May 2024 Proposed License Amendment Request Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections Supplemental Information ML24130A1192024-05-0707 May 2024 Inservice Test Program for Pumps and Valves Sixth Interval Update and Associated Relief and Alternative Requests - Response to Request for Additional Information Regarding Alternative Request V-1 ML24142A3852024-04-30030 April 2024 2023 Annual Radioactive Effluent Release Report IR 05000280/20240012024-04-30030 April 2024 Integrated Inspection Report 05000280-2024001 and 05000281-2024001 ML24122C6522024-04-30030 April 2024 Annual Radiological Environmental Operating Report ML24122B3032024-04-29029 April 2024 Associated Independent Spent Fuel Storage Installation, Revision to Emergency Plan Report of Change IR 05000280/20244022024-04-29029 April 2024 Security Baseline Inspection Report 05000280/2024402 and 05000281/2024402 ML24115A1952024-04-24024 April 2024 Notification of Surry Power Station Comprehensive Engineering Team Inspection - U.S. NRC Inspection Report 05000280/2024011 and 05000281/2024011 ML24054A0142024-04-22022 April 2024 Issuance of Amendment Nos. 297 and 280, and Surry Power Station Unit Nos. 1 and 2, Issuance of Amendment Nos. 317 and 317, to Change Emergency Plan Staff Augmentation Times ML24108A1812024-04-15015 April 2024 Proposed License Amendment Request - Reclassification of Low Head Safety Injection Flow Indication Regulatory Guide 1.97 Variable Supplemental Information ML24095A2172024-04-12012 April 2024 – Review of the Spring 2023 Steam Generator Tube Inspection Report ML24088A2482024-03-26026 March 2024 Inservice Testing Program for Pumps and Valves Sixth Interval Update and Associated Relief and Alternative Requests- Response to Request for Additional Information ML24087A2082024-03-22022 March 2024 Proposed License Amendment Request Addition of Containment Limiting Condition for Operation and Surveillance Requirements ML24078A2642024-03-21021 March 2024 – Regulatory Audit in Support of License Amendment Request to Proposed Reclassification of Regulatory Guide 1.97 Variable for Low Head Safety Injection Flow Instrumentation ML24087A1522024-03-18018 March 2024 Annual Changes, Tests, and Experiments Report Regulatory Commitment Evaluation Report ML24023A5762024-03-0808 March 2024 Correction to Issuance of Amendment Nos. 315 and 315, Regarding Revised Emergency Plan for Relocation of the Technical Support Center IR 05000280/20230062024-02-28028 February 2024 Annual Assessment Letter for Surry Power Station, Units 1 and 2 - NRC Inspection Reports 05000280/2023006 and 05000281/2023006 ML24032A4712024-02-20020 February 2024 Exemption from Select Requirements of 10 CFR Part 73 - Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML24051A1782024-02-19019 February 2024 Proposed License Amendment Request - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML24057A0612024-02-19019 February 2024 and Virgil C. Summer Power Nuclear Stations - Nuclear Property Insurance Coverage IR 05000280/20230042024-02-0909 February 2024 Integrated Inspection Report 05000280/2023004 and 05000281/2023004 IR 05000280/20244012024-02-0606 February 2024 Security Baseline Inspection Report 05000280/2024401, 05000281/2024401 and 07200002/2024401 IR 05000280/20230102024-01-18018 January 2024 – Age Related Degradation Inspection Report 05000280-2023010 and 05000281-2023010 ML23312A1922024-01-18018 January 2024 Issuance of Amendment Nos. 316 & 316 Regarding a Risk Informed Approach for Tornado Classification of the Fuel Handling Trolley Support Structure 2024-09-03
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARML24141A2512024-05-20020 May 2024 Proposed License Amendment Request - Reclassification of Low Head Safety Injection Flow Indication Regulatory Guide 1.97 Variable - Supplemental Information ML24130A1192024-05-0707 May 2024 Inservice Test Program for Pumps and Valves Sixth Interval Update and Associated Relief and Alternative Requests - Response to Request for Additional Information Regarding Alternative Request V-1 ML23220A1482023-08-0707 August 2023 Proposed Emergency Plan Revision - Relocation of the Technical Support Center (TSC) Response to Request for Additional Information ML23208A0922023-07-26026 July 2023 Request for Approval of Appendix F of Fleet Report DOM-NAF-2-P Qualification of Framatome ORFEO-GAIA and OORFE-NMGRID CHF Correlations in the Dominion Energy Vipre-D Computer Code Response L-04-002, Stations - NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Fleet Response to Request for Additional Information2023-05-0808 May 2023 Stations - NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Fleet Response to Request for Additional Information ML23096A1972023-04-0606 April 2023 License Amendment Request - Application of Risk-Informed Approach for Tornado Classification of the Fuel Handling Trolley Support Structure - Response to Request for Additional Information ML23096A2982023-04-0606 April 2023 Units 1 and 2 and Millstone Power Station, Units 2 and 3 - Request for Approval of Appendix F of Fleet Report DOM-NAF-2-P Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion ML23089A3542023-03-30030 March 2023 Response to Request for Additional Information Regarding Proposed License Amendment Request to Revise Emergency Plan Staff Augmentation Times ML23044A0392023-02-11011 February 2023 Alternative Request to Defer ASME Code Section XI Inservice Inspection Examinations for Pressurizer and Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzles Response to Request for Additional Information ML23025A1252023-01-25025 January 2023 Response to Request for Additional Information License Amendment Request, NRC Approval of Methodology Change and Reclassification of the Turbine Building as a Tornado Resistant Structure ML22343A0002022-12-0909 December 2022 Response to Request for RAI on ASME Operation & Maintenance Code Inservice Testing Program - Request for Approval of Alternative Request V-01 Use of Mechanical Agitation Process for Pressure Isolation Valve 1-SI-241 Seat Leakage Testing ML22342A4242022-12-0707 December 2022 Response to 3/12/2012 Request for Information Enclosure 2, Recommendation 2.0, Flooding Focused Evaluation Integrated Assessment Submittal Revised Commitment Completion Date ML22312A4432022-11-0707 November 2022 NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Fleet Response to RAI ML22300A1882022-10-27027 October 2022 License Amendment Request 10-Day Allowed Outage Time for Opposite Unit Auxiliary Feedwater Cross-Connect Capability Response to Request for Additional Information ML22220A2162022-08-0808 August 2022 License Amendment Request 10-Day Allowed Outage Time for Opposite Unit Auxiliary Feedwater (AFW) Cross-Connect Capability Supplemental Information ML22164A8532022-06-13013 June 2022 Proposed License Amendment Request Removal of Refueling Water Chemical Addition Tank and Replacement of Containment Sump Buffer - 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316(b) 40 CFR 122.21(r)(2)-(13), Part 1 of 3 ML20149K6942020-05-28028 May 2020 Response to Request for Additional Information, to Proposed License Amendment Requests Addition of Analytical Methodology to the Core Operating Limits Report for a Small Break Loss of Coolant Accident ML20034F0532020-01-31031 January 2020 Proposed License Amendment Request: Allowed Outage Time Extension for Replacement of Reserve Station Service Transformer C 5KV Cables to Transfer Bus F Response to Request for Clarification and Additional Information ML19350A0042019-12-12012 December 2019 License Amendment Request Addition of 24-Hour Completion Time for an Inoperable Reactor Trip Breaker Response to NRC Request for Additional Information ML19283B6222019-10-10010 October 2019 Subsequent License Renewal Application Safety Review - Documentation of Draft Third Round Requests for Additional Information ML19291B0342019-10-0101 October 2019 Response to March 12, 2012 Request for Information Enclosure 2, Recommendation 2.1, Flooding Focused Evaluation/Integrated Assessment Submittal ML19269B7342019-09-19019 September 2019 Subsequent License Renewal Application - Response to Requests for Additional Information - Sets 3 and 4 Revised SLRA Mark-Ups ML19267A0422019-09-16016 September 2019 Subsequent License Renewal Application Response to NRC Requests for Confirmation of Information Set 2 ML19253B3302019-09-0303 September 2019 Response to Requests for Additional Information - Sets 3 and 4 - Subsequent License Renewal Application ML19249B7672019-08-29029 August 2019 Enclosure 1 - Millstone, Units 2 and 3 and ISFSI; North Anna, Units 1 and 2 and ISFSI; and Surry, Units 1 and 2 and ISFSI - Response to EAL Scheme Change RAIs ML19204A3572019-07-17017 July 2019 Subsequent License Renewal Application Response to Request for Additional Information - Set 2 ML19198A0592019-07-11011 July 2019 Subsequent License Renewal Application - Response to NRC Requests for Confirmation of Information ML19196A1102019-07-0909 July 2019 Attachments 2, 3 & 4 - Response to NRC Request for Additional Information and Correction of SBLOCA Analysis Error and Revised Marked-Up/Typed NAPS and SPS Technical Specifications Pages ML19183A3862019-06-27027 June 2019 Subsequent License Renewal Application - Response to Requests for Additional Information - Set 1 ML19148A4212019-05-10010 May 2019 All Enclosures with Coversheets ML18304A3302018-10-25025 October 2018 Proposed License Amendment Request TSTF-490 & Update of Alternative Source Term Analyses Response to Request for Additional Information & Revised Proposed Technical Specifications ML18302A1212018-10-18018 October 2018 Response to Request for Additional Information, Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules ML18303A2882018-10-18018 October 2018 Response to Request for Additional Information Regarding Relief Request S2-I5-LMT-P01 Examination Category R-A, Preservice Weld Examinations 2024-05-07
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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 January 31, 2020 10 CFR 50.90 U. S. Nuclear Regulatory Commission Serial No.: 20-015 Attention: Document Control Desk NRA/GDM: RO Washington, DC 20555-0001 Docket Nos.: 50-280/281 License Nos.: DPR-32/37 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 PROPOSED LICENSE AMENDMENT REQUEST ALLOWED OUTAGE TIME EXTENSION FOR REPLACEMENT OF RESERVE STATION SERVICE TRANSFORMER C 5KV CABLES TO TRANSFER BUS F RESPONSE TO REQUEST FOR CLARIFICATION AND ADDITIONAL INFORMATION By letter dated October 30, 2019 (ADAMS Accession No. ML193090199), Virginia Electric and Power Company (Dominion Energy Virginia) requested a license amendment to revise the Surry Power Station (Surry) Units 1 and 2 Technical Specification (TS) 3.16 "Emergency Power System." The license amendment request (LAR) would allow a one time extension of the Allowed Outage Time (AOT) in TS 3.16, Action 8.2, from 7 days to 14 days to allow replacement of the 5 kilo-volt (KV) cables from Reserve Station Service Transformer C (RSST C) to Transfer Bus F during the Surry Unit 2 spring 2020 refueling outage (RFO).
In an email dated January 9, 2020 from Mr. Vaughn Thomas, the Surry NRC Project Manager, to Mr. Gary D. Miller of Dominion Energy Virginia, the NRC staff requested additional information to facilitate their review of the subject LAR. The NRC's request and Dominion Energy Virginia's response are provided in the attachment.
NRC Requested Clarification In addition to the request for additional information, the NRC asked for clarification of the LAR scope as follows:
"In the LAR, the licensee stated, "To facilitate the replacement of the RSST C 5 kV cables to Transfer Bus F, RSST C must be removed from service. Thus, the electrical configuration of the plant for this modification is the same as it was for the RSST C replacement completed during the Unit 2 fall 2018 RFO. A temporary 21-day AOT for the RSST C replacement was approved by the NRC in TS Amendments 293/293 dated October 5, 2018."
The TS Amendments 293/293 dated October 5, 2018 (ML18621A099) was meant both for replacement of RSST C and associated cabling. Please clarify whether or not the replacement of associated cabling was completed during previous Unit 2 fall 2018 RFO, and whether the replacement of cables proposed in this LAR are different from those mentioned in previous amendment."
Serial No.20-015 Docket Nos. 50-280/281 Page 2 of 3 The RSST C cabling discussed in the current LAR is the same cabling that was previously approved for replacement during the Unit 2 fall 2018 RFO by Surry Units 1 and 2 TS Amendments 293/293. However, the cable was not able to be replaced as planned. The cable replacement design change was awarded to an engineering firm with the intent to use a specific insulated bus (tubular bus) product to eliminate a known failure mechanism, i.e., excessive mechanical forces on the cable shield. During the owner's review of the provided design change, it was identified that the proposed insulated bus design tolerances did not meet the Surry design specification requirements. Specifically, the proposed insulated bus was considered more robust but was unable to meet the existing GDC-17 reactance requirement. Therefore, the cable could not be replaced as planned during the previously approved 21-day AOT for the Surry Unit 2 fall 2018 RFO, and an alternate design solution was necessary. An improved cable design has since been completed and the cable procured for installation. The cables are now larger to meet the GDC-17 reactance criterion and to account for cable deration and have a higher temperature rating than the existing cables. Consequently, the additional AOT extension requested by this LAR will provide sufficient time to perform the cable replacement work during the upcoming Unit 2 spring 2020 RFO.
Should you have any questions or require additional information, please contact Mr. Gary D. Miller at (804) 273-2771.
Respectfully, Mark D. Sartain Vice President - Nuclear Engineering and Fleet Support Commitments contained in this letter: None
Attachment:
Response to NRC Request for Additional Information COMMONWEALTH OF VIRGINIA COUNTY OF HENRICO The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by Mr. Mark D. Sartain, who is Vice President - Nuclear Engineering and Fleet Support, of Virginia Electric and Power Company. He has affirmed before me that he is duly authorized to execute and file the foregoing document in behalf of that company, and that the statements in the document are true to the best of his knowledge and belief.
Acknowledged before me this day of JdY\ua.t- , 2020.
My Commission Expires: Ql-ly..b..\- \> "2,0'Z3.
Serial No.20-015 Docket Nos. 50-280/281 Page 3 of 3 cc: U.S. Nuclear Regulatory Commission - Region II Marquis One Tower 245 Peachtree Center Avenue, NE Suite 1200 Atlanta, GA 30303-1257 State Health Commissioner Virginia Department of Health James Madison Building - 7th floor 109 Governor Street Suite 730 Richmond, VA 23219 Mr. Vaughn Thomas NRC Project Manager - Surry U.S. Nuclear Regulatory Commission One White Flint North Mail Stop 04 F-12 11555 Rockville Pike Rockville, MD 20852-2738 Mr. G. Edward Miller NRC Senior Project Manager - North Anna U.S. Nuclear Regulatory Commission One White Flint North Mail Stop 09 E-3 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Surry Power Station
Serial No.20-015 Docket Nos. 50-280/281 Attachment RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION Virginia Electric and Power Company (Dominion Energy Virginia)
Surry Power Station Units 1 and 2
Serial No.20-015 Docket Nos. 50-280/281 Attachment REQUEST FOR ADDITIONAL INFORMATION REGARDING ONE-TIME 14-DAY ALLOWED OUTAGE TIME FOR REPLACEMENT OF 5 KV CABLES ASSOCIATED WITH RESERVE STATION SERVICE TRANSFORMER C SURRY POWER STATION UNITS 1 AND 2 NRC Comment:
By application dated October 30, 2019 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML193090199, Virginia Electric and Power Company (Dominion Energy Virginia) (the licensee) requested a license amendment to revise the Surry Power Station (Surry) Units 1 and 2 Technical Specification (TS) 3.16 "Emergency Power System." Specifically, the license amendment request (LAR) would allow a one-time extension of the Allowed Outage Time (AOT) in TS
. 3.16, Action 8.2, from 7 days to 14 days. The licensee requested a temporary 14-day AOT to allow replacement of the 5 kilo-Volt (KV) cables from Reserve Station Service Transformer C (RSST C) to Transfer Bus F during the Surry Unit 2 spring 2020 refueling outage (RFO). The RSST C 5 KV cables provide distribution of reliable offsite power from RSST C to Transfer Bus F, which supplies the 1H and 2J emergency buses. The RSST C and associated cables to Transfer Bus F provide offsite power to both units. Therefore, the TS change request applies to both units.
The NRG staff has identified the need for the following additional information to complete the review of the LAR:
Applicable Regulatory Requirements Title 10 of the Code of Federal Regulations (10 CFR) Part 50.36(c)(2) provides the requirement for the establishment of TS limiting conditions for operation (LCO).
Specifically, paragraph 50.36(c)(2)(ii) requires that a TS LCO of a nuclear reactor be established for each item meeting one or more of the criteria listed. For this LAR, Criterion 3 is applicable and states: ':A structure, system, or component that is part of the primary success path and which functions or actuates to mitigate a OBA or transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier."
Request for Additional Information (RAJ)
RAJ# 1 In the LAR, Attachment 1, Page 9, the licensee stated that during the temporary 14-day AOT, the one-time operating restrictions will be as follows: (1) Two Unit Load Shed Circuit (LSR1) will be defeated, and (2) Auto Start Blocking Circuit (LSR2) will be in operation.
Page 1 of 4
Serial No.20-015 Docket Nos. 50-280/281 Attachment Please provide a detailed description of the functions of the (1) Two Unit Load Shed Circuit (LSR1), and (2) Auto Start Blocking Circuit (LSR2). Also, explain why the operating restrictions on these circuits are considered necessary during the temporary 14-day AOT.
Dominion Energy Virginia Response The response to the NRC request for additional information is provided below.
- Detailed description of the functions of the (1) Two Unit Load Shed Circuit (LSR1).
The primary concern in the plant load shed design is overload of the RSST and transfer bus electrical distribution system. If a breaker (15A2, 1582, or 15C2) from a Station Service Transformer (SST) to the normal station service unit bus trips automatically, an automatic transfer to the RSSTs occurs if no fault exists on the normal station service bus. The automatic transfer is accomplished by closure of Breakers 15A1, 1581, or 15C1.
(See Figure 1.) The affected normal station service bus is then supplied from the RSST through the transfer bus. The transfer bus continues to connect the RSST to the emergency buses to ensure continuous service for the safety-related equipment.
During the automatic transfer, voltage transients and bus overloading may occur. This is particularly true in the event of two-unit loading on the transfer buses. The load shed scheme reduces the electrical loading on RSS Transfer Buses D, E and F during events that necessitate two-unit simultaneous loading on an individual transfer bus. Per the Surry UFSAR (Chapter 8, Section 4.1), "To include the possibility of two-unit simultaneous loading of the reserve station service (RSS) system, within its design capability, a load shedding system is installed to remove the overloads on the RSS system. This system provides for automatic load shedding of selected non-safety-related loads from both units which limits RSST loading to under 4000A per transformer... ". Sensing relays detect when both units' station service feeder breakers from an RSS transfer bus are closed.
The actuating relays then send tripping signals to specific loads. The tripping signal trips specified running equipment and defeats the auto-start capability of non-running equipment.
- Detailed description of the functions of the (2) Auto Start Blocking Circuit (LSR2).
To alleviate potential low-voltage profile conditions of the Vital and Emergency Electrical Distribution System during a Safety Injection (SI) or Consequence Limiting Safeguards (CLS) actuation, an automatic start inhibit or blocking circuit is installed. When initiated, the auto-start blocking circuit sends signals to specific pieces of equipment based on the position of the associated bus feeder and defeats the auto-start capability of non-running equipment. The auto-start block circuit ensures sufficient power supply capacity and voltage levels for emergency equipment. Per the Surry UFSAR (Chapter 8, Section 4.1),
"The automatic starting of selected large non-Class 1 E loads is blocked. The loads that Page 2 of 4
Serial No.20-015 Docket Nos. 50-280/281 Attachment are prevented from auto starting are the condensate, bearing cooling, and component cooling pump motors. The auto-start block will remain in effect for 60 seconds following an SI signal and 315 seconds following a CLS signal. This feature will prevent any voltage degradation of the emergency buses as a result of starting of the non-Class 1 E loads... ".
Explain why the operating restrictions on these circuits are considered necessary during the temporary 14-day AOT.
The auto-start inhibit or blocking function described in the Surry UFSAR will function as intended, i.e., there are no new operating restrictions being imposed on this function. The Two Unit Load Shed Circuit is conservatively defeated during the 14-day AOT to avoid any inadvertent actuation of the circuitry while performing cabling installation at the transformer and the "F" transfer bus. This action is appropriate because the logic circuit for load shed is partially made-up when the shutdown unit is on the dependable alternate source (backfeed), which will be the case when the cable replacement is performed. With the refueling unit on backfeed, the refueling unit having reduced load, and RSST C out of service, there is no need for the load shed.
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Serial No.20-015 Docket Nos. 50-280/281 Attachment 05l2 NO '----- 05M4 NO c
n UNlT-1 STATION DIESEL UNIT-2 STATION INTAKE STRUCTURE SERVICE TRANSFORMERS RESERVE STATION SERVICE TRANSFORMERS TRANSFORMERS 22 KV/ 4.16 KV SERVICE TRANSFORMERS 22 KV/ 4.16 KV 34.5 KV / 4.16 KV 34.SKV / 4. i 6KV NO 1B BUS 28 BUS 15G8 NO NO 1581 ' 2581 iC BUS 2C BUS 00 00 I
I,.___---'ff""'----------------------------' 25 i 15C1 C DIESEL NC n 15H8 15J8 25J8 NC 25H8 -I DlESEL
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15H3 15H1 15J3 25J3 25H1 25H3 Figure 1 Page 4 of 4