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] |
Text
.* VIRGINIA ELECTRIC .A.ND POWER COMPANY RICHMOND, VIRGINIA 23261
/ . . .
_. , ; - , - ~
Apr,:L:f>1s, t,;J/9~T : ~ " ' llf.~U1
- 1'r: *;.- *~ ~ \ \'"~l-\U\LUU
1*,.
P¢'.;~-},~")
~- ~
o_,,.~~'1},-o{,S,
~;~*::o
\\./
.--~
\-
/ ~ . &'("\ *",~o~
Ir:,:,
'-" = /../"i. v::.i. *-a 0 t *,
\ ~-- J~**\ ~cf, ~~ ..
\ *., ~~) ~ ; /:: ...
1--p Mr. Benard C. Rusche \V>>--
"-\) ~~"'
v""
Director of Nuclear Reactor Regulat'i~7'7r~\(j)~ PO&M/TAP:dgt f~;)'
tr,"'"
Serial No. 057/021177 U. s. Nuclear Regulatory Commission ~~ Docket No. 50-280 Washington, D. C. 20555 License No. DPR-32 Attn: Mr. Robert w. Reid, Chief Operating Reactors Branch 4
Dear Mr. Rusche:
The purpose of this letter is to present our Unit No. 1 steam generator surveillance program for this present outage. The program will consist of the following:
- 1) An eddy current program will be accomplished from the cold leg side over the U-bends including Rows 1-5, all columns. This is to provide current data for this area.
- 2) A tube dent sizing and accompanying eddy current program will be accomplished from the hot leg side for the interior tube lane region, the wedge regions and the patch plate region. Specifically, these areas are shown on the attachment. Initially, a 00650 probe will be used at 400 KHz, which will detect tube wall flaws. Then, any of the tubes which will not pass the 0.650 probe will be probed with a 0.610 probe at 3.5 KHz, which will map any defects in the support plates (an additional number of tubes will be added to pro-vide a representative example for TSP condition). Finally, any tubes which will not pass the 0.610 probe will be probed with a 0.540 probe at 25 KHz, which will map the level of sludge (an additional number of tubes will be added to provide a representative example for sludge measurement).
- 3) A photography and inspection program through the lower handholes and the three inch inspection ports will be accomplished. The upper-most and lowest support plates will be inspected and the lowest plate flow slots gauged. The upper support plate will be inspected to the extent possible without d~sturbing the flow slot blocking device.
- 4) The shell to wrapper annulus gauging program will be accomplished.
This ~ata will be related to previously established strain maps.
e e VIRGINIA ELECTRIC AND POWER COMPANY TO Mr. Benard C. Rusche Page No. 2 This program is designed to provide the information necessary to estab-lish a plugging criteria that will allow an acceptable operating period.
The plugging criteria is expected to be similar to the criteria used for Unit No. 2, which was submitted in Attachment No. 2 of our March 21, 1977 ietter.
The plugging program and its associated operating period will be for-warded when the surveillance program data has been evaluated.
We hope that this type of continuing communication will allow your time* far review*to be minimized. Our expected startup date is May 2, 1977.
Very truly yours,
~*- Yt? ~11/!Lt,~rvt1'
- c. M. Stallings Vice President-Power Supply and Production Operations Attachments cc: Mr. Norman C. Moseley
Hot Leg*
- -A'irAci: IBN1' Rl-Rl2 All tolumns ;
Rl3..:R25 Cl-Cl5
- *1. =; Rl3-R25 C80~C92.
~ ..... . .R29-R38 Cl"l-C21
- .: : *, *. :. R33-R;38 C40:,* C41, C48, C54.; C55
t .( -~
. . ~ -.
~
I *;;.~. ,o **
, A srr. Ay \'C~nmi. .
. (h/lLl'J7e~~,.t~"~~"':11'M,1,'f~,.r~*N91,.111,,1~u*l'd'~ ,;..,.,,.'tJ.O,,....y.iti~rl')
.* .... "i*
\ ,..rr I * ). '
_. !""1~,.~~. t:!:.i I. * . . * ,. *
,::::,*q,:'::l .,,,,, ,,;..,,.,.,..,.,,.,_..,,,,.,,..,,...,.,..,,.,,_,. ..,,9'\.,f't*""~,r.-,-.**1~,-,-,,,..1,"1*lt'1',11'**,**':fc"' "*
' -~
- -*,,.,....,,.,,,r,,u ..,,.,._., _ ..,.,.,.,....,._,.., * .,..:... _,.**--~--*-**' -
. z.a. z m +/-et: fi WWW -UV.1~ ~~
.,~-* *-. *.
1.
~
. .* 't! ..
~ ~
1'1/:/ APR f_i:l /Wi ro 51