Similar Documents at Surry |
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Category:Inspection Report Correspondence
MONTHYEARML18222A3472018-08-10010 August 2018 Notification of Inspection and Request for Information for Nuclear Regulatory Commission Problem Identification and Resolution Inspection IR 05000280/20100042011-02-11011 February 2011 IR 05000280-10-004, 05000281-10-004, 05000280-10-501, and 05000281-10-501, on 10/29/10, Surry Power Station - Errata IR 05000280/20092012009-05-21021 May 2009 IR 05000280-09-201, and IR 05000281-09-201, on 03/27/2009, Surry Nuclear Power Plant - Security Inspection ML0711400732007-06-0606 June 2007 Ltr. to Mr. David A. Christian Surry Nuclear Power Station - Material Control and Accounting Program Inspection IR 05000280/20060092006-08-11011 August 2006 IR 05000280-06-009, IR 05000281-06-009, on 06/12-16/2006 & 06/26-30/2006 for Surry, Units 1 and 2; Triennial Fire Protection Inspection IR 05000280/20040042004-11-24024 November 2004 Errata Surry Power Station - NRC Integrated Inspection Report Nos. 5000280/2004004 and 5000281/2004004 - and Office of Investigations Case Number 2-2003-075 IR 05000280/20010052002-04-25025 April 2002 IR 05000280/2001-005, 05000281/2001-005, Surry Nuclear Power Station, Inspection on 12/30/2001 - 03/30/2002. No Findings of Significance Identified IR 05000280/20010072002-01-18018 January 2002 IR 05000280/2001-007, IR 05000281/2001-007, on 11/26-30 and 12/10-14/2001; Virginia Electric and Power Co., Surry Power Station, Units 1 & 2. Annual Baseline Inspection of the Identification and Resolution of Problems. No Violations Noted ML19095A2711978-04-0606 April 1978 Provide Information on Steam Generator Inspection on Unit 2, Which Supplement to Vepco'S Submittal of 4/4/1978 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 ML19095A5231977-09-0202 September 1977 Response to Non-Compliance Item Reported in IE Inspection Reports 50/280/77-20 & 50/281/77-20, & Determined No Proprietary Information Is Contained ML19098B4291977-05-26026 May 1977 Response to Letter of 5/6/1977, in Reference to IE Inspection Reports 50-280/77-7 & 50-281/77-7, Advising No Proprietary Information Is Contained in Reports ML19098B4281977-05-16016 May 1977 Response to Letter of 4/21/1977, in Reference to IE Inspection Reports 50-280/77-4 & 50-281/77-4, Advising No Proprietary Information Is Contained in Reports ML19098B4271977-05-16016 May 1977 Response to Letter of 4/22/1977, in Reference to IE Inspection Reports 50-280/77-5 & 50-281/77-5, Advising No Proprietary Information Is Contained in Reports ML19098B4261977-04-29029 April 1977 Advising Completeness of Unit 1 Steam Generator Inspection Program & Presenting Results of Program in Attachment 1 ML19105A1821975-07-0909 July 1975 Report No. ISI 75-3, Preliminary Results of Inservice Inspection Program Refueling Outage No. 1, Surry Power Station Unit No. 2. 2018-08-10
[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 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) ML24165A2782024-07-17017 July 2024 Issuance of Amendment Nos. 318 and 318, Reclassification of Regulatory Guide 1.97 Variable for Low Head Safety Injection 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 ML24122C6522024-04-30030 April 2024 Annual Radiological Environmental Operating Report 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 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 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 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 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 05000280/20230042024-02-0909 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 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 2024-08-12
[Table view] Category:Manual
MONTHYEARML15075A0152015-03-0404 March 2015 Proposed License Amendment Request Relocation of Augmented Inspection Requirements from TS 4.2 and TS 4.15 to Technical Requirements Manual Response to Request for Additional Information ML14126A5112014-04-26026 April 2014 2013 Annual Radioactive Effluent Release Report ML19095A2521978-06-30030 June 1978 06/30/1978 Letter Enclosed Revision 5 to Steam Generator Repair Program ML19095A2711978-04-0606 April 1978 Provide Information on Steam Generator Inspection on Unit 2, Which Supplement to Vepco'S Submittal of 4/4/1978 ML19093A7901978-02-10010 February 1978 VEPCO Nuclear Power Station Quality Assurance Manual, Corrective Action 2015-03-04
[Table view] |
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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND,VIRGINIA 23261 April 6, 1978 Mr. Edson G. Case, Acting Director Serial No *. 182A Nuclear Reactor Regulation PO&M/DLB:das U.S. Nuclear Regulatory Connnission Docket No. 50-281 Washington, D. C. 20555 License No. DPR-37 Attention: Mr. Albert Schwencer Operating Reactors Branch 1
Dear Mr. Case:
The attachment to this letter includes information on the recent steam generator inspection on Surry Unit.No. 2 and is a supplement to our submittal of April 4, 1978 (Serial No. 182).
Very truly yours,
- 67. )}7, ~aec~7 C. M. Stallings Vice President - Power Supply and Productions Operations Attachment 1{~\:;;
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.. e April . .1978 STEAM GENERATOR TUBE INSPECTION PROGRAM .
AND PLUGGING CRITERIA SURRY POWER STATION UNIT NO. 2 The following information is provided to supplement our previous submittals of February 15, 1978 (Serial No. 0742 and April 4, 1978 (J3erial No. 182).
1} Clar~fication of Figure 4 of attachment to our letter of April 4, 1978.
Figure 4 of the attachment to our April 4, 1978 letter is the same figure as Figure 1 of our February 15, 1978 letter. As explain-ed in our February 15, 1978 letter the dashed line defines the extent of tube gauging in the cold legs. This included ali tubes below the dashed line. The solid line defines the extent of gauging in the hot legs. This includes all tubes outside.the crosshatched area.
- 2) Our submittal of April 4, 1978 included the following typographical errors.
a) On-page 1 of the attachment, the fifth sentence in the first para-graph should read as follows:
It.has been established that the 15% strain contoµr is ~he most appropriate inspection boundary for-the Surry Units.
b) On page 2 of the attachment, under "3. Plugging Criteria", the second sentence in the first paragraph should read as follows:
This is consistent with the conservative inspection boundary of the 15% strain contour.
c) In Figures 5, 6, and 7 the legend should read as *follows:
X = .540" Probe A = .610" Probe 0 = .650" Probe
~) This inspection revealed three leaking tubes, one in each steam genera-tor.
Steam Generator A, Row 28, Column 10.
As shown in Figures 1, 2a, and 2b this tube is located on the periphery at a wedge location.
e e
- 5) Inspection Boundary Initially the 12.5% strain boundary was used in the gauging program when little plant specific data was available. After two initial inspections and three reinspections of the Surry plants, we now have the benefit of pl°ant .specific information which indicates the conser-vatism of the 12.5% boundary and the adequacy of the 15% boundary.
That is, the majority of.the tubes inspected do not restrict the .650 inch probe. In addition, all tubes restricting the .610 inch or .540 inch probe have all fallen well within the inspection boundary including the 15% strain boundary. This is significant since the .610 inch and the .540 inch restricted tubes form the basis for the plugging patterns in the tubelane region.
Furthermore, the following additional conservatisms were utilized in determining the Surry 2 inspection boundary:
A. The 15% strain boundary indicated by the finite element model at 11.5 EFPM beyond full closure was used. The plant is currently at approximately 9 EFPM beyond full closure.
B. In the flow slot area it is estimated that the 15% strain boundary at 11:5 EFPM beyond full closure extends to approximately the 9th row. The inspection boundary for this *inspection extended to the 12th row in order to be consistent with previous inspection plans.
C. When a restricted tube was found close to the inspection boundary, the inspection was expanded in that area.
It is concluded from the above that the inspection boundary was more than adequate.
- 6) The progression of strain contours over the intended operating period is utilized to preventively plug beyond a 0.540 inch restricted tube.
In earlier inspections the closeness of the strain contour lines pre-vented identification of the appropriate contour which most reasonably indicated the extent and progression of tubes with greatest deformation.
Initially, the 15% strain contour was chosen when limited plant specific data was available and the strain contour lines indicated by finite element analysis fell close together on the plots. A review of the re-lationship between the 0.540 inch restricted tubes at Surry 2 at this time and the finite element analysis strain contours at 8.5 EFPM beyond full closure indicates that the 17.5% strain contour more realistically estimates the boundary of 0.540 inch restricted tubes. Also the movement of the 17.5% strain contour over the next period of operation in the cen-tral tubelane region is less than two rows in six months. This is con-sistent with the plugging criteria previously used for Surry 1 and 2 and hence these plugging criteria were utilized for this outage.
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- e As explained on page 3 of our April 4, 1978 submittal, due to local plate cracking which is believed to occur at the periphery near wedge 1ocations, tube leaks can occur here at levels of tube restriction less than in the tubelane region. This tube leak was extremely small and was below the level detectable by chemical analysis:
All tubes surrounding this leaking tube were inspected with a .650 probe with satisfactory results. All surrounding tubes have been plugged. This is consistent with our plugging criteria defined on page 3 of our April 4, 1978 submittal and should preclude further tube leaks in this area during the next operating period.
Steam Generator B, Row 10, Column 91.
- This leak was detected during operation and was approximately 0.25 gpm at the time of shutdown. This leak was clearly in an area where leaks are predicted to occur. Surrounding tubes have been plugged consistent with our preventive plugging criteria specified on page 3 of our April 4, 1978 letter. This should preclude further tube leaks in this area during the next operating period.
Steam Generator C, Row 4, Column 35.
This tube leak was extremely small and was below the.level detectable by chemical analysis. This.leak was clearly in an area where leaks are predicted to occur. Surrounding tubes have been plugged consistent with our preventive plugging criteria sp.ecified on page 3 of our April 4, 1978 letter. This should preclude further tube leaks in this area during the next operating period.
- 4) Handhole Inspection Results Handhole inspection using photographs were performed in all steam gen-erators. As explained in prior submittals, the flow slots in all steam generators have reached the point of full closure. The "islanding" phenomena described in previous*submittals has also been observed to
.various degrees in all steam generators. This inspection was to verify that the support plates had undergone no further degradation since the last inspection and that no new phenomena had developed. Inspection revealed that the condition of ~he visible support plates had not chan-ged since previous inspections and that no new phenomena were observed.
The photographs will be available for inspection at the site.