Similar Documents at Surry |
---|
Category:Graphics incl Charts and Tables
MONTHYEARML20332A1592020-12-0707 December 2020 Documentation of Completion of Required Actions Taken in Response to Lessons Learned from the Fukushima Dai-Ichi Accident ML20203M1602020-07-20020 July 2020 VA Elec. & Power Co., Dominion Energy Nuclear Co. Inc., Dominion Energy Sc Inc., Millstone Power Station 2, N. Anna & Surry Power Stations 1 & 2, Virgil C. Summer Station 1, Updated Anchor Darling Double Disc Gate Valve Information & Status ML17213A0802017-07-28028 July 2017 Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules ML16130A5642016-05-0202 May 2016 NRC Regulatory Issue Summary 2015-16 Planned Licensing Action Submittals ML16056A1392016-03-11011 March 2016 Correction to the U.S. Nuclear Regulatory Commission Analysis of Licensees' Decommissioning Funding Status Reports ML16049A5422016-03-0101 March 2016 Tables 1 and 2 ML12124A2972010-03-11011 March 2010 Soarca Documents Review/Approval Process ML0806406572008-02-22022 February 2008 Inservice Inspection Owner'S Activity Report (Form OAR-1), Refueling Outage S1R21, Second Period of the Fourth Ten-Year ISI Interval ML0728203072007-10-11011 October 2007 Electronic Distribtion Initiative Letter, Licensee List, Electronic Distribution Input Information, Division Plant Mailing Lists ML0722801962007-08-10010 August 2007 Response to Request for Additional Information 2006 Steam Generator Inservice Inspection Reports ML0609500942006-04-0303 April 2006 North Anna Units 1 and 2, and Surry Units 1 and 2, Response to Generic Letter 2006-02, Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power ML0508804122005-03-23023 March 2005 Virginia Electric and Power Company Surry Power Station Unit 2, ASME Section XI Fourth Inservice Inspection (ISI) Interval Update, Risk Informed Inservice Inspection (RI-ISI) Program, Response to NRC Request for Additional Information ML0501802572005-01-13013 January 2005 Stations Units 1 & 2, Millstone Power Station Units 2 & 3, Request for Approval of Appendix B of Topical Report DOM-NAF-2, Qualification of Westinghouse WRB-1 CHF Correlation in the Dominion VIPRE-D Computer Code. ML0501202612005-01-12012 January 2005 December Monthly Report on the Status of Open TIAs Assigned to NRR ML0434802422004-12-29029 December 2004 November Monthly Report on the Status of Open TIAs Assigned to NRR ML0501903172004-12-17017 December 2004 Virginia Electric and Power Company Surry Power Station Units 1 and 2 - Proposed Technical Specifications Change Request for Reactor Coolant System Pressure/Temperature Limits. Ltops Setpoint, and Ltops Enable Temperature with Exemption. ML0424700192004-08-24024 August 2004 Attachment 4 - Table of Where ANSI N18.7 Requirements Are Addressed by NQA-1-1994 Standards And/Or the New QA Topical Report ML0312902322003-05-0808 May 2003 Graph Emergency Diesel Fuel Oil Consumption ML19093B1121978-07-14014 July 1978 Response to Concerns Use of a Certain Type Cable Manufactured by the Continental Wire and Cable Company ML19093B0681978-04-28028 April 1978 Response to Letter of 03/16/1978 Which Requested Certain Information Regarding 11/22/1977 Submittal for Permanent Solution of Low Head Safety Injection & Recirculation Spray Pumps Net Positive Suction Head Problems ML19093B0691978-04-26026 April 1978 Purpose of Letter to Present the Surry Unit No.1 Steam Generator Surveillance Program for the Outage Which Began on 04/22/1978 ML19093B0721978-04-17017 April 1978 Vepco Is Pleased to Provide Attached Responses to Request for Additional Information Dated March 16, 1978. Submittal Contains Program Description for Monitoring Fish Populations in James River Near Power Station ML19093B0201978-02-22022 February 1978 Response to 02/02/78 Letter Possibility That Reactor Cavity Annulus Seal Ring or Associated Biological Shielding Could Become Missiles in Event of Loss of Coolant Accident Pipe... ML19093B0241978-01-23023 January 1978 Response to a Request of 05/18/1977 for Additional Information on the Reactor Vessel Material Surveillance Program ML19093A1511977-12-31031 December 1977 Annual Operating Report 1977, Volume 4 ML19093B0661977-12-14014 December 1977 Forwarding Table 4.3-2, Which Was Omitted from Revision 1 to Steam Generator Program, Surry Power Station, Unit Nos. 1 & 2, Submitted on 12/2/1977, Serial No. 532 ML19093B0671977-12-14014 December 1977 Letter to Inform of a Delay in Final Installation of Reactor Coolant System Overpressure Protection System ML19093B0331977-11-30030 November 1977 Enclosed Justification for Tube Inspection Program & Plugging Criteria, Results of Completed Surry Unit No. 1 Inspection Program with Small Change in Denting ML19093A9811977-10-31031 October 1977 Purpose of the Letter Is to Present the Surry Unit No. 1 Steam Generator Surveillance Program for the Forthcoming Outage ML19094A5601977-09-26026 September 1977 09/26/1977 Letter Proposed Design Change to Allow the Lhsi Discharge Valves to Be Remotely Throttled from the Control Room ML19093A9871977-09-26026 September 1977 a Submission of a Proposed Design Change Which Allows the Lhsi Discharge Valves to Be Remotely Throttled from Control Room. Provides Completed Description of Tests Along with Evaluation of Results ML19093B0081977-08-29029 August 1977 Informs of Necessary Change to Operating Procedures to Require Throttling Lhsi Pump Discharge Valves During Recirculation Mode of Pump Operation in Order to Assure That Lhsi Pump Cavitation Does Not Occur During ... ML19098B4841977-07-0808 July 1977 Forwarding Corrected Pages to 1976 Annual Operating Report 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 ML19098B4411977-06-0202 June 1977 Response to Letter of 4/13/1977, Provide Requested Information Regarding Iodine Spiking ML19098B4241977-04-15015 April 1977 Furnishing Information to Present Unit 1 Steam Generator Surveillance Program for Present Outage ML19094A7491976-07-0101 July 1976 Submits a Copy of the Supplement to Surry Unit Nos. 1 & 2 Startup Reports Dated 05/01 & 07/31/1973 Respectively ML19093B3531975-08-12012 August 1975 Response to Requested for Reasons of Surry Power Technical Specification TS 4.14.A.1 Be Waived on an Interim Basis Until 12:00 PM 09/20/1975 ML19098B3051975-07-23023 July 1975 5/13/1975 Summary of Meeting with NRC Staff, VEPCO, & Stone & Webster Corp to Discuss Possibility of Differential Settlement for Major Safety Related Structures ML19098B3071975-07-18018 July 1975 Confirming Vepco'S Plan to Conduct Large Load Reduction Test on Unit 2, on Tentative Date of 8/2/1975, as Discussed in Meeting of 7/9/1975 ML19093B3351975-05-16016 May 1975 Refers to Letter of 01/17/1975 Which Advised Replacement of Certain Water Temperature Monitoring Equipment at Station & Informing VEPCO of a Purchased & Installed New Monitoring System to Comply with Provisions ML19093B3361975-02-0303 February 1975 Confirms a Report of a Fish Impingement Incident Which Occurred on 01/28/1975 Reported to Paul Leech of Staff by John White of VEPCO on 01/19/1975 2020-07-20
[Table view] Category:Letter
MONTHYEARML24164A0012024-08-12012 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 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 IR 05000280/20244032024-05-22022 May 2024 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000280/2024403 and 05000281- 2024403 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 IR 05000280/20240012024-04-30030 April 2024 Integrated Inspection Report 05000280-2024001 and 05000281-2024001 ML24142A3852024-04-30030 April 2024 2023 Annual Radioactive Effluent Release Report ML24122C6522024-04-30030 April 2024 Annual Radiological Environmental Operating Report IR 05000280/20244022024-04-29029 April 2024 Security Baseline Inspection Report 05000280/2024402 and 05000281/2024402 ML24122B3032024-04-29029 April 2024 Associated Independent Spent Fuel Storage Installation, Revision to Emergency Plan Report of Change IR 05000280/20240112024-04-24024 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 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 ML24057A0612024-02-19019 February 2024 and Virgil C. Summer Power Nuclear Stations - Nuclear Property Insurance Coverage 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 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 ML24003A9022024-01-0303 January 2024 Stations, Units 1 and 2, Emergency Plan Revision - Relocation of the Technical Support Center (TSC) - Editorial Correction IR 05000280/20233012023-12-28028 December 2023 NRC Operator License Examination Report 05000280/2023301 and 05000281/2023301 ML23283A3052023-12-20020 December 2023 Review of Appendix F to DOM-NAF2, Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion Energy VIPRE-D Computer Code (EPID L-2022-LLT-0003) (Nonproprietary) ML23352A3692023-12-18018 December 2023 Associated Independent Spent Fuel Storage Installation, Revision to Emergency Plan Report of Change ML23334A2342023-11-30030 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23242A2292023-11-0707 November 2023 Issuance of Amendment Nos. 315 and 315, Regarding Emergency Procedure Relocation of the Technical Support Center ML23200A2622023-11-0202 November 2023 Issuance of Amendment Nos. 314 and 314, Regarding Technical Specification and Spent Fuel Pool Criticality Change IR 05000280/20230032023-10-25025 October 2023 Integrated Inspection Report 05000280/2023003 and 05000281/2023003 ML23286A0372023-10-13013 October 2023 Annual Submittal of Technical Specifications Bases Changes Pursuant to Technical Specification 6.4.J ML23285A0922023-10-12012 October 2023 Inservice Testing Program for Pumps and Valves Sixth Interval Update and Associated Relief and Alternative Requests ML23277A1172023-10-0303 October 2023 Operator Licensing Examination Approval 05000280/2023301 and 05000281/2023301 ML23230A0502023-10-0202 October 2023 5 of the Quality Assurance Topical Report - Review of Program Changes 2024-08-12
[Table view] Category:Meeting Summary
MONTHYEARML23345A1092023-12-14014 December 2023 December 7, 2023, Summary of Public Meeting with Virginia Electric and Power Company Concerning a License Amendment Request to Revise Emergency Augmentation Times for North Anna Station, Units 1 & 2, and Surry Station, Units 1 & 2 ML23167A7012023-06-26026 June 2023 Summary of Public Meeting with VEPCO Concerning a License Amendment Request to Revise Emergency Plan Staff Augmentation Times ML23151A5472023-06-0101 June 2023 Public Meeting Summary - 2022 Annual Assessment Meeting Regarding North Anna Power Station, Docket Nos. 50-338 and 50-339; and Surry Power Station ML22335A5172022-12-0505 December 2022 Summary of Conference Call Regarding the Fall 2022 Steam Generator Tube Inspections (RFO 31) ML22130A1702022-05-20020 May 2022 Summary of April 21, 2022, Public Meeting to Discuss Potential Emergency Preparedness License Amendment Request ML22115A0032022-05-17017 May 2022 Summary of Public Meeting with Virginia Electric and Power Company on April 13, 2022 Regarding Future LAR Request to Change the Auxiliary Feedwater System Allowed Outage Time ML22130A0332022-05-0909 May 2022 Public Meeting Summary 2021 Annual Assessment Meeting Regarding North Anna Power Station, Docket Nos. 50-338 and 50-339; and Surry Power Station, Docket Nos. 50-280 and 50-281, Meeting Number 20220349 ML22091A0902022-04-0101 April 2022 Combined 2021 Assessment Meeting Slides ML22070A8092022-03-15015 March 2022 Public Webinar Summary with Virginia Electric and Power Company Regarding Further License Amendment Relocating the Technical Services Center to the Local Emergency Operations Facility ML21342A1402021-12-0909 December 2021 Summary of Public Meeting in Tarrytown, Ny, to Discuss Indian Point Units 1, 2, and 3 (IPEC) Post-shutdown Decommissioning Activities Report ML21159A0932021-06-16016 June 2021 May 20, 2021, Summary Regarding Pre-Application Meeting to Discuss Planned License Amendment Requests ML21155A1632021-06-11011 June 2021 Summary Regarding Pre-Application Meeting to Discuss Planned License Amendment Requests ML21131A1612021-05-11011 May 2021 Public Meeting Summary - 2020 Annual Assessment Meeting Regarding Virgil C. Summer Nuclear Station, Docket No. 50-395; North Anna Power Station, Docket Nos. 50-338 and 50-339; and Surry Power Station, Docket Nos. 50-280 and 50-281, Meeting ML21027A0232021-01-28028 January 2021 Summary of January 26, 2021 Closed Meeting with Dominion Energy Regarding Performance of Force on Force Exercises in a Pandemic Environment ML20335A1122020-12-0707 December 2020 Summary of November 30, 2020, Meeting with the National Marine Fisheries Service and Dominion Energy, Inc. Regarding Atlantic Sturgeon Capture at Surry Power Station ML20296A4072020-11-12012 November 2020 Summary of October 14, 2020, Public Meeting with Virginia Electric and Power Company to Discuss Presubmittal Supplements for Surry Units 1 and 2 ML20136A1752020-05-15015 May 2020 Sur 2019 Aam Meeting Summary ML19266A4842019-10-0101 October 2019 Summary of Pre-Licensing Meeting with Dominion Energy Regarding a License Amendment Request to Adopt a Risk-Informed 10 CFR 50.69 Categorization Program ML19253D7082019-09-24024 September 2019 Summary of August 13, 2019, Category 2 Public Meeting Related to the Safety Review of the Surry Power Station, Units 1 and 2, Subsequent License Renewal Application ML19219A2842019-08-13013 August 2019 July 29, 2019, Summary of Category 2 Public Meeting Related to the Safety Review of the Surry Power Station, Units 1 and 2, Subsequent License Renewal Application ML19135A1982019-06-0404 June 2019 Issuance of Environmental Scoping Summary Report Associated with the Staff'S Review of the Surry Power Station, Unit Nos 1 and 2, Subsequent License Renewal Application ML19144A1292019-05-30030 May 2019 Summary of November 20, 2018, Pre Application Meeting with Dominion Energy Regarding the Planned License Amendment Request to Revise Emergency Action Levels ML19128A3372019-05-0808 May 2019 Public Meeting Summary - 2018 Annual Assessment Public Meeting Regarding Surry Power Station Docket Nos. 50-280 and 50-281 ML19106A4162019-04-25025 April 2019 Summary of the Subsequent License Renewal Severe Accident Mitigation Alternatives Audit ML19024A3862019-01-30030 January 2019 01/08/2018 Summary of Meeting Regarding Public Scoping Meeting for Environmental Review of Surry Power Station, Units 1 and 2 Subsequent License Renewal Application ML18144A0712018-05-23023 May 2018 Summary of Annual Assessment Public Meeting Regarding Surry Power Station ML18129A3142018-05-16016 May 2018 04/17/2018 Summary of Pre-Application Meeting with Dominion Energy Regarding the Surry, Units 1 and 2, Subsequent License Renewal Application ML18066A0192018-03-16016 March 2018 Meeting Summary of October 4, 2017 Pre-Submittal Public Meeting to Discuss LAR Request Regarding Consolidation of the Emergency Operations Facilities ML18057A2752018-03-0101 March 2018 February 7, 2018, Summary of Pre-Application Meeting with Dominion Energy Regarding the Surry Power Station, Units 1 and 2 Subsequent Renewal Application ML17123A1162017-05-0303 May 2017 Summary of Meeting to Discuss Annual Assessment of the Surry Power Station, Units 1 and 2 with the Public for Period of January 01, 2016 Through December 31, 2016 ML16320A4602016-12-0707 December 2016 Summary of Meeting with Virginia Electric and Power Company Regarding Pre-Submittal Information on Proposed Alternative to ASME Code to Repair Safety-Related Piping Using Carbon Fiber Reinforced Polymer at Surry Power Station, 1 & 2 ML16124A7592016-05-0303 May 2016 April 12, 2016 Summary of Public Meeting - Surry, Units 1 and 2 ML14210A0212014-08-0808 August 2014 June 25, 2014, Summary of Category 1 Public Meeting with Dominion Nuclear to Discuss Seismic Hazard Reevaluations Associated with Implementation of Japan Lessons-Learned Near-Term Task Force Recommendation 2.1 ML14101A1132014-04-11011 April 2014 Summary of Meeting with Public to Discuss Annual Assessment of Surry Power Station with the Public for the Period of January 1, 2013 - December 31, 2013 ML13225A2932013-08-12012 August 2013 7/23-24/2013, Summary of Meeting 2013 U.S. Nuclear Regulatory Commission (NRC) Initial Exam Writers' Workshop ML13151A1022013-05-31031 May 2013 Summary of Public Meeting with Virginia Electric and Power Company, to Discuss Annual Assessment of Surry Power Stationfor the Period of January 1, 2012 December 31, 2012 ML12129A2512012-05-0808 May 2012 Summary of Category 3 Public Meeting Annual Assessment for Surry Power Station ML12115A0702012-04-24024 April 2012 Summary of Public Meeting with Surry Power Station, Unit 2 to Discuss a Preliminary White Finding Involving One Apparent Violation of Technical Specification 6.4.A.7 ML1206600702012-03-0606 March 2012 02/21-22/2012 Meeting Summary with State-Of-The-Art Reactor Consequence Analyses (Soarca) for Public Meetings at Peach Bottom and Surry ML1206600902012-03-0606 March 2012 02/21-22/2012 Meeting Summary with State-Of-The-Art Reactor Consequence Analyses (Soarca) for Public Meetings at Peach Bottom and Surry ML11173A1542011-07-0505 July 2011 Summary of Conference Call Regarding the Spring 2011 Steam Generator Tube Inspections ML1110303992011-04-13013 April 2011 Public Meeting/Open House Summary Letter - Surry Power Station ML1023804682010-08-26026 August 2010 08/18/10 Summary of Meeting NRC Initial Exam Writer'S Workshop ML0923803922009-08-26026 August 2009 08/11-12/2009-Summary of Meeting Re 2009 Us NRC Initial Exam Development Workshop ML0911000832009-04-17017 April 2009 Summary of Meeting with Public/Open House to Discuss NRC Reactor Oversight Process and the Annual Assessment of the Surry Power ML0814901522008-06-10010 June 2008 Spring 2008 Refueling Outage Steam Generator Tube Inspections ML0811301672008-04-15015 April 2008 Annual Assessment Meeting Slides - Reactor Oversight Program - Cy 2007 ML0733801432007-12-11011 December 2007 Steam Generator Tube Inspections ML0728906642007-11-0101 November 2007 Summary of Meeting with Dominion Nuclear Regarding Chemical Testing Methods Related to GSI-191 ML0635302762006-12-21021 December 2006 Summary of Public Meeting with VEPCO Re Licensee Plan to Submit a License Amendment for Chilled Water Piping Replacement. 2023-06-26
[Table view] |
Text
- _.,_ - _. -, .\ *C~,r)*p_-_,"f'iJ11
~ J,;,
0
.:.: j,c w-'1;-1 1
VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND,VIROINIA 23261 July 23, 1975 Mr. K. R. Goller, Assistant Director Serial No. 541 for Operating Reactors PO&M/JTB:clw Division of Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-280 U.S. Nuclear Regulatory Commission 50-281 Washington, D. C. 20555 License Nos. DPR-32 DPR-37
Dear Mr. Goller:
On May 13, *197 5-, representatives of Vepco and our architect-engineers, Stone & Webster Engineering Corporation, met with members of the Regulatory Staff in Bethesda, Maryland to discuss the possibility of differential settle-ment having occurred.between various major safety related structures at the Surry Power Station, Unit Nos *. 1 and 2. The purpose of this letter is to for-mally document information presented at the meeting substantiating the fact that significant differential settlement has not occurred between structures and that there are no safety implications associated therewith.
The major items discussed at the meeting were:
.1. The presentation of survey data taken during the period May 1()-,13,' 1975-
- 2. The.comparison of the current data with prior data
- 3. The results of the visual inspection of structures
.4. The future surveillance which will be performed to provide additional information regarding potential settlement
- 5. The significance of our findings.
Each of these items is briefly discussed below.
Table 1, attached hereto, presents the data which was recorded during the May 15, 1975 survey. As indicated on the table, the elevations at the various locations are based on the U.S. Coast and Geodetic Survey (USC&GS) horizontal control marker "Vain" as the datum. As part of the investigation,
, e VIRGINIA E:r,ECTRIC AND POWER COMPANY TO Mr. K. R. Goller Page 2 a first order survey was run from USC&GS marker "Bacon 1932" located at Bacons Castle, approximately six (6) miles from the Surry Power Station, to "Vain 1938", a horizontal USC&GS marker located in close proximity to the station. The "Bacon" to "Vain" survey accuracies and level loop closures are within the definition specified by the .U.S. Department. of Commerce, National Oceanic and Atmospheric Administration, National Ocean Survey as First Order.
Based on the elevation of "Bacon 1932"; L953 adjustment, the elevation of l'Vain 1938 11 was measured to be 25.521. This value is 0.{)71 feet higher than the elevation of 25.45 used as the datum for the May 1975 station survey. The elevation of 11Vain 11 was surveyed in 1966 and found to be 25.45 at that time.
Table 1 also presents the data available for February 1971 and April 1972.
These data were obtained from original field survey*. books used during con-struction and were not meant to be used for the determination of long term settlement. Since they are the only historical data available, they are being used for comparison purposes. Several comments should be made in regard to*
the February 1971 and April 1972 data. Based on the field survey books, the February 1971 survey used "Vain" (25 *.45) as the original reference elevation, with "Manhole A.T. No. l" (27.43} as a temporary.benchmark. In April *1972, a survey loop was run from "Manhole A. T. No.* 111 (assumed at elevation 27. 43) to "Vain" which resulted in "Vain" having a measured elevation of 25.-54. Because "Vain" was a USC&GS marker, it was assumed.that it had not moved in the time between the two surveys, and therefore; the.elevation of "Manhole A.T. No. 1" was adjusted down by an amount equal t0 the difference between the measured elevation of "Vain" (25.54) and the original ,1966 value of (25.45), i.e .. 0.09 ft.
The corrected survey data is presented in Table 2. The original February 1971 data, as presented in Table 1, have been corrected by subtracting 0.09 foot from each of the.reported elevations. As can be seen, when this correction is made, the February 1971 data compare very favorably with the April 1972 and May
- 1975 data. The only significant difference indicated is the.elevation.of the auxiliary building sump; .i.e. the February *1971 data indicate a higher value than the other two surveys. The approximate 0.03 or.0.04 foot difference can be accounted for by.the thickness of the cover plate over the sump. Based on the review of the survey book, it is only indicated that the lip of the sump was shot, with no specification as to whether the c0ver plate was in position. Based on the physical arrangement, the type of survey which was being performed, and the other-wise_ good agreement of . all other data' it can reasonably be assumed that the February 1971 data include the thickness of the cover plate for the auxiliary building containment.sump. If this value is corrected for the approximate one-half inch thickness of the cover plate it agrees favorably with the other data.
As can be seen from a perusal of the attached tables., when the. corrections discussed above are considered, all data are in good _agreement and.are well within the accuracies of the survey. The corrections noted are based on
e e VIRGINIA EWCTRIC AND POWER COMPANY TO Mr. K. R. Goller Page 3 historical data and appear to be valid based on the review which has been conducted. When correlated with the results of the visual inspection described below, the evidence that no significant differentialsettlement has.occurred appears to.be incontrovertible.
Visual inspections of major interconnecting structures housing safety related equipment, systems, and components were made by individuals possessing expertise in station operations, structures, piping and geotechnical engineering.
Some of the inspectors were the*original designers of .the buildings and piping systems involved. The inspections revealed no indication of differential settlement between interconnecting structures or abnormal piping conditions.
The results of the inspections c0nfirmed that there has been no significant differential settlement of structures of the Surry Power Station, Unit Nos. 1 and 2.
Although there are no signs af differential settlement, a surveillance program has been initiated to reconfirm that differential settlement is not occurring. The surveillance program will consist of establishing a number of survey points which are accessible.duringnormal station operation and an appropriate vertical control benchmark which will.be surveyed on.a periodic basis. The planned frequency for these surveys, in addition to the baseline survey which has already been performed, is as follows:
- 1. 6 manths after initial survey
.2. 1 year after initial survey
- 3. 2 years after initial survey The surveys will be terminated after two (2) .years, unless there are s.ignificant indications of differential settlement.
The investigations conducted at the Surry Power Station, Unit Nos *. 1 and 2, indicate that signif.icant differential settlement has net. occurred and that piping systems have not been displaced as a result of differential settlement.
Therefore, there have.been no safety implications identified as a result of our investigations *
.We trust that the information contained herein will satisfy your needs.
v/
~ce v~~d Attachments cc: Mr. Norman . C. Moseley
TABLE 1 SURVEY DATA SURRY POWER STATION UNIT NOS. 1 AND 2 ELEVATION (FEET)
LOCATION FEB '71 3 APRIL '72 MAY '75 No. 1 Turbine Pedestal 5.814 5.733 5.73 5.797 5. 722 5. 72 No *. 2 Turbine Pedestal Auxiliary Building Sump 1. 784 1.652 1. 66 e
Containment No. l Column 16 21. 783 21.689 21.70 Column 18 21. 782 21. 682 21.69 Containment No. 2 Column 17 22.754 No Point Located No Point Located Manhole A.T. No. l 27.43 27.34 27.35 Vain 25.45 3 25.45 2 25.45 1 1 The elevation of 11 Vain 11 was assumed to be at elevation of 25.45 feet since it is a Coast and Geodetic Survey marker. Other recorded elevations for the May 1975 are based on "Vain" as the datum.
2 The elevation of 11 Vain 11 was checked following the measurement of the elevation of Manhole A.T.
No. 1. The check indicated that the elevation of 11 VainH was 25.54 feet. Since 11 Vain 11 is a USC&GS marker it was assumed to*be at its established elevation of 25.45 feet and "Manhole A.T. No. l" was adjusted downward by 0.09 foot.
3 February 1971 survey as*sumes a *datum of 25.45 feet at "Vain" based on the earlier (1966) survey from Bacons Castle.
072375
TABLE 2*
CORRECTED SURVEY DATA
. SURRY POWER STATION UNIT NOS. 1 AND 2 ELEVATION (FEET)
LOCATION FEB '71** APRIL '72 MAY '75 No. l Turbine Pedestal 5. 72 5.733 5,73 a No. 2 Turbine Pedestal 5. 71 5. 722 5. 72 Auxiliary Building Sump* 1.69 1.652 1.66 Containment No. l Column 16 21.69 21.689 21.70 Column 18 21.69 21. 682 21.69 Containment No. 2 Column 17 22.66 No Point Located No Point Located Manhole A.T. No. l 27.34 27.34 27.35 Vain 25.45 25.45 25.45
- In 1971 it is believed the top of the cover plate was shot rather than the lip of the sump which was shot in 1972 and 1975 (thickness of cover plate approximately 0.04- ft).
- February 1971 data cori;ected to Manhol~ A.T. No. 1" which is assumed at 27.34 ft.
072375.