Similar Documents at Surry |
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Category:Inspection Report
MONTHYEARIR 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 IR 05000280/20233012023-12-28028 December 2023 NRC Operator License Examination Report 05000280/2023301 and 05000281/2023301 IR 05000280/20230032023-10-25025 October 2023 Integrated Inspection Report 05000280/2023003 and 05000281/2023003 ML23256A2672023-09-21021 September 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report IR 05000280/20220042023-09-0101 September 2023 Reissue - Surry Power Station - Integrated Inspection Report 05000280/2022004 and 05000281/2022004 IR 05000280/20230052023-08-23023 August 2023 Updated Inspection Plan for Surry Power Station, Units 1 and 2 (Report 05000280/2023005 and 05000281/2023005) IR 05000280/20230022023-08-0404 August 2023 Integrated Inspection Report 05000280/2023002 and 05000281/2023002 IR 05000280/20230012023-05-0505 May 2023 Integrated Inspection Report 05000280/2023001 and 05000281/2023001 IR 05000280/20234012023-04-21021 April 2023 Security Baseline Inspection Report 05000280 2023401 and 05000281 2023401 ML23086B9172023-03-24024 March 2023 Steam Generator Tube Inspection Report for the Fall 2022 Refueling Outage IR 05000280/20220062023-03-0101 March 2023 Annual Assessment Letter for Surry Power Station, Units 1 and 2 - NRC Inspection Reports 05000280/2022006 and 05000281/2022006 ML23041A0232023-02-13013 February 2023 Integrated Inspection Report 05000280/2022004 and 05000281/2022004 IR 05000280/20220032022-11-0707 November 2022 Integrated Inspection Report 05000280/2022003 and 05000281/2022003, Operation of an Independent Spent Fuel Storage Installation Report 07200055/2022001, and Exercise of Enforcement Discretion IR 05000281/20224022022-10-21021 October 2022 Security Baseline Inspection Report 05000280/ 2022402 and 05000281/2022402 IR 05000280/20224042022-10-19019 October 2022 Security Baseline Inspection Report 05000280/2022404 and 05000281/2022404 IR 05000280/20224032022-09-0808 September 2022 Security Baseline Inspection Report 05000280/2022403 and 05000281/2022403 IR 05000280/20220052022-08-24024 August 2022 Updated Inspection Plan for Surry Power Station, Units 1 and 2 (Reports 05000280/2022005 and 05000281/2022005) IR 05000280/20220022022-08-0404 August 2022 Integrated Inspection Report 05000280/2022002 and 05000281/2022002 Final IR 05000280/20220112022-07-0606 July 2022 Biennial Problem Identification and Resolution Inspection Report 05000280/2022011 and 05000281/2022011 IR 05000280/20220012022-05-11011 May 2022 Integrated Inspection Report 05000280/2022001 and 05000281/2022001 IR 05000280/20224012022-03-29029 March 2022 Security Baseline Inspection Report 05000280/2022401 and 05000281/2022401 IR 05000280/20224052022-03-22022 March 2022 Material Control and Accounting Program Inspection Report 05000280/2022405 and 05000281/2022405 IR 05000280/20220102022-03-15015 March 2022 NRC Inspection Report 05000280/2022010 and 05000281/2022010 IR 05000280/20210062022-03-0202 March 2022 Annual Assessment Letter for Surry Power Station, Units 1 and 2 (Reports No. 05000280/2021006 and 05000281/2021006) IR 05000280/20210042022-02-11011 February 2022 Integrated Inspection Report 05000280/2021004 and 05000281/2021004 IR 05000280/20210032021-11-24024 November 2021 Integrated Inspection Report 05000280/2021003 and 05000281/2021003 IR 05000280/20213012021-11-10010 November 2021 NRC Operator License Examination Report 05000280/2021301 and 05000281/2021301 IR 05000280/20210112021-11-0101 November 2021 Triennial Fire Protection Team Inspection Report 05000280/2021011 and 05000281/2021011 ML21265A4532021-10-0505 October 2021 Inspection Report 2021 FOF (IP92707) IR 05000280/20210052021-08-31031 August 2021 Mid-Cycle Letter Revised Updated Inspection Plan for Surry Power Station, Units 1 and 2 (05000280/2021005 and 05000281/2021005) IR 05000280/20210012021-08-26026 August 2021 Updated Inspection Plan for Surry Power Station, Units 1 and 2 -(05000280/2021001 and 05000281/2021001) IR 05000280/20210102021-08-16016 August 2021 Design Basis Assurance Inspection (Programs) Inspection Report 05000280/2021010 and 05000281/2021010 IR 05000280/20210022021-08-12012 August 2021 Integrated Inspection Report 05000280/2021002 and 05000281/2021002 IR 05000280/20214022021-06-14014 June 2021 Security Baseline Inspection Report 05000280/2021402, 05000281/2021402 and 07200002/2021401 ML21120A1552021-04-30030 April 2021 Integrated Inspection Report 05000280/2021001 and 05000281/2021001 IR 05000280/20200062021-03-0303 March 2021 Annual Assessment Letter for Surry Power Station, Units 1 and 2 NRC Inspection Reports 05000280/2020006 and 05000281/2020006 IR 05000280/20214012021-02-0909 February 2021 Security Baseline Inspection Report 05000280/2021401 and 05000281/2021401 IR 05000280/20200042021-02-0202 February 2021 Integrated Inspection 05000280/2020004 and 05000281/2020004; and 07200055/2020003 IR 05000281/20200402020-12-30030 December 2020 95001 Supplemental Inspection Supplemental Report 05000281/2020040 IR 05000280/20200032020-11-0606 November 2020 Integrated Inspection Report 05000280/2020003, 05000281/2020003; and 07200055/2020002 IR 05000280/20200102020-11-0505 November 2020 NRC Design Bases Assurance Inspection Report 05000280/2020010 and 05000281/2020010 IR 05000280/20200112020-09-24024 September 2020 Biennial Problem Identification and Resolution Inspection Report 05000280/2020011 and 05000281/2020011 IR 05000280/20204012020-08-25025 August 2020 Inspection Report 05000280/2020401 and 05000281/2020401 IR 05000280/20200052020-08-24024 August 2020 Updated Inspection Plan for Surry Power Station, Units 1 and 2 (Report 05000280/2020005 and 05000281/2020005) IR 05000280/20200022020-08-10010 August 2020 Integrated Inspection Report 05000280/2020002 and 05000281/2020002 and Exercise of Enforcement Discretion IR 05000281/20200912020-07-30030 July 2020 Final Significance Determination of a White Finding and Notice of Violation and Assessment Followup Letter; NRC Inspection Report 05000281/2020091 IR 05000281/20200902020-06-26026 June 2020 NRC Inspection Report 05000281/2020090 and Preliminary White Finding and Apparent Violation IR 05000280/20200012020-05-0808 May 2020 Integrated Inspection Report 05000280/2020001 and 05000281/2020001; and 07200055/2020001 IR 05000280/20190062020-03-0303 March 2020 Annual Assessment Letter for Surry Power Station, Units 1 and 2 - NRC Inspection Reports 05000280/2019006 and 05000281/2019006 2024-02-06
[Table view] Category:Letter
MONTHYEARIR 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 ML23256A2672023-09-21021 September 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report ML23244A2352023-09-18018 September 2023 Request to Use a Subsequent Edition of the ASME Code, Section XI ML23230A0012023-09-15015 September 2023 Request to Use a Provision of a Previous Edition of the ASME Boiler and Pressure Vessel Code, Section XI, for Non-Destructive Examinations IR 05000280/20220042023-09-0101 September 2023 Reissue - Surry Power Station - Integrated Inspection Report 05000280/2022004 and 05000281/2022004 ML23244A0142023-08-30030 August 2023 Inservice Inspection Owner'S Activity Report IR 05000280/20230052023-08-23023 August 2023 Updated Inspection Plan for Surry Power Station, Units 1 and 2 (Report 05000280/2023005 and 05000281/2023005) ML23226A1862023-08-10010 August 2023 Proposed License Amendment Request - Reclassification of Regulatory Guide 1.97 Variable for Low Head Safety Injection Flow Instrumentation ML23220A1492023-08-0707 August 2023 Independent Spent Fuel Storage Installation - Submittal of Cask Registrations for Spent Fuel Storage ML23220A1482023-08-0707 August 2023 Proposed Emergency Plan Revision - Relocation of the Technical Support Center (TSC) Response to Request for Additional Information IR 05000280/20230022023-08-0404 August 2023 Integrated Inspection Report 05000280/2023002 and 05000281/2023002 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 ML23207A1102023-07-26026 July 2023 NRC Regulatory Issues Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations ML23198A0322023-07-18018 July 2023 Regulatory Audit Report Regarding Review of License Amendment to Modify Emergency Plan Staff Augmentation Times ML23193A9382023-07-18018 July 2023 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML23173A0602023-07-11011 July 2023 Audit Summary for License Amendment Request Revision of the Emergency Plan to Support Relocation of the Technical Support Center ML23136B1392023-06-29029 June 2023 Issuance of Amendment No. 313 Administrative Changes to Subsequent Renewed Operating Licenses and Technical Specifications ML23178A1682023-06-26026 June 2023 2022 Annual Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the Requirements of 10 CFR 50.46 ML23152A0432023-06-22022 June 2023 Audit Plan License Amendment Requests to Change Emergency Plan Staff Augmentation Times ML23153A1732023-06-16016 June 2023 Correction to Amendment Nos. 346 & 286 Millstone, 294 & 277 North Anna, 311 & 311 Surry, and 225 Summer to Revise Technical Specifications to Adopt TSTF-554,Rev Reactor Coolant Leakage Requirement ML23163A2352023-06-12012 June 2023 Request to Use a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI, for the SPS Sixth Inservice Inspection (Isi) Intervals and VCSNS Fifth ISI Interval ML23151A6612023-05-31031 May 2023 ES-2.1-1, Surry 2023-301 Corporate Notification Letter (Revised) ML23167B0072023-05-31031 May 2023 Proposed Emergency Plan Revision - Relocation of the Technical Support Center (TSC) Supplemental Information - LOCA Dose Calculation Summary ML23117A0952023-05-10010 May 2023 Audit Plan License Amendment Request to Support Relocation of the Technical Support Center ML23130A3742023-05-10010 May 2023 Request to Delay NRC Intial Licensing Examination 2024-02-06
[Table view] Category:Licensee Response to Notice of Violation
MONTHYEARML20304A2032020-10-0808 October 2020 Readiness Notification for 95001 Supplemental Inspection Notice of Violation: EA-20-057 ML20244A2832020-08-28028 August 2020 Reply to Notice of Violation; EA-20-057 ML1112300532011-05-0202 May 2011 Reply to a Notice of Violation EA-10-255, NRC Inspection Report No. 50-280/2011-012 and 50-281/2011-012, NRC Office of Investigations Report 2-2010-029 and Notice of Violation ML0623600122006-08-22022 August 2006 NRC Inspection Nos. 50/280/2006-010 & 05-281/2006-010, Reply to Notice of Violation ML0202901912002-01-18018 January 2002 Reply to a Notice of Violation NRC IR 05000280/2001-006 & 05000281/2001-006 ML19093A9191978-07-26026 July 1978 Response to a Letter of 07/12/1978, in Reference to Inspection Conducted on 05/16-19/1978, 05/22-26/1978, 06/21-23/1978 & Reported in IE Inspection Report Nos. 05000280/1978016 & 05000281/1978016 ML19093A9331978-04-11011 April 1978 Response to a Letter of 03/20/1978, in Reference to Inspection Conducted on 01/20/1978 & 01-24-25/1978 & Reported in IE Inspection Report Nos. 05000280/1978004 & 05000281/1978004 ML19093A9341978-04-11011 April 1978 Response to a Letter of 03/20/1978, in Reference to Inspection Conducted on 01/20/1978 & 01/24-25/1978 & Reported in IE Inspection Report Nos. 05000280/1978004 & 05000281/1978004 ML19093A9381978-03-22022 March 1978 Response to a Letter of 02/28/1978 in Reference to the Inspection Conducted on 01/16-20/1978 & 01/24/1978 and Reported in Inspection Reports IE-05000280/1978002 & 05000281/1978002 ML19093A9411978-03-10010 March 1978 Response to a Letter of 02/21/1978 in Reference to the Inspection Conducted on 0812/20-21/1977, 01/10-13/1978, 01/16-19/1978 & 01/25/1978 and Reported in Inspection Reports IE-05000280/1978001 & 05000281/1978001 ML19093A4041978-02-0707 February 1978 Response to Letter of 11/11/1977 in Reference to Inspection Conducted on 10/04-10/07/1977 and Reported in IE Inspection Report Nos. 05000280/1977029 & 05000281/1977029 ML19093A3911978-01-24024 January 1978 Response of Letter of 01/10/1978 in Reference to Inspection Conducted on 11/29-12/02/1977 and Reported in Inspection Report Nos. 05000280/1977035 & 05000281/1977035 ML19093A3991977-12-30030 December 1977 Response to Letter of 12/07/1977 in Reference to the Inspection Conducted on 10/25-10/28/1977 and Reported in I.E. Inspection Reports 05000280/1977031 & 05000281/1977031 ML19093A4071977-12-21021 December 1977 Response to a Letter of 11/11/1977 in Reference to Inspection Conducted on 10/04-10/07/1976 and Reported in IE Inspection Report Nos. 05000280/1977029 & 05000281/1977029 ML19093A3951977-12-14014 December 1977 Response to a Letter of 12/01/1977 in Reference to Inspection Conducted on 11/01-11/04/1977 and Reported in Inspection Report No. 05000280/1977033 & 05000281/1977033 ML19093A4081977-12-0606 December 1977 Response to a Letter of 11/11/1977 in Reference to the Inspection Conducted on 10/04-10/07/1977 and Reported in IE Inspection Reports 05000280/1977029 & 05000281/1977029 ML19093A4101977-11-30030 November 1977 Response to a Letter of 11/03/1977 in Reference to Inspection Conducted on 09/19-09/23/1977 and Reported in I.E. Inspection Reports 05000280/1977027 & 05000281/1977027 ML19093A4141977-11-0404 November 1977 Response to a Letter of 10/20/1977 in Reference to Inspection Conducted on 09/14-09/16/1977 and Reported in Inspection Reports IE 05000280/1977026 & 05000281/1977026 ML19093A4181977-10-25025 October 1977 Response to Letter of 09/27/1977 in Reference to Inspection Conducted on 08/08-08/12/1977 and Reported in IE Inspection Reports 0500280/1977022 & 05000281/1977022 ML19093A3891977-10-21021 October 1977 Response to a Letter of 09/28/1977 in Reference to Inspection Conducted on 08/30-09/02/1977 and Reported in Inspection Reports I.E. 05000280/1977024 & 05000281/1977024 ML19093A4151977-09-15015 September 1977 Response to Letter of 09/01/1977 in Reference to Inspection Conducted on 08/18-08/21/1977 and Reported in Inspection Reports IE 05000280/1977023 & 05000281/1977023 ML19093A4191977-09-0707 September 1977 Response to a Letter of 08/17/1977 in Reference to the Inspection Conducted on 08/04-08/08/1977 and Reported in Inspection Reports IE-05000280/1977021 & 05000281/1977021 ML19093A4351977-08-0101 August 1977 Reply to Letter of 07/12/4977, Concerning the Inspection of Vepco'S Surry Power Station Security Program on 05/04-05/05, 05/12-05/13, 05/23-05/26/1977 ML19093A3881977-07-15015 July 1977 Response to Letter of 06/28/1977 in Reference to Inspection Conducted on 05/24/1977 and Reported in Inspection Reports IE 05000280/1977010 & 05000281/1977010 ML19093A4511977-03-0404 March 1977 Response to a Letter of 02/25/1977 in Reference to Inspection Conducted on 01/25-01/28/1977 and Reported in Inspection Reports IE 05000280/1977002 & 05000281/1977002 2020-08-28
[Table view] |
Text
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. *VIRGINIA ELECTRIC AND POWER
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RIO~MOND: VIRO~NIA. ~-3261.
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Mr. James P. O'Re:U_ly, Dir.ec.tor Se:i:lal*. No * .440/092077-*:' C
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This is- 1,n ~eopon~~ tQ, .Y9ur le~ter: of: September 20, ,1977, ' 'refer..: -**. : in .A
-,. ence. to* the tnapection conducted at Surry P()lJer *Stati~n on Aug~st *30 - Sept~ . .__ 'i:- * \
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e e VIBGINIA ELECTRIC AND POWER COMPANY RICHMOND,VIBGINIA 23261 October 21, 1977 Mr. James P. O'Reilly, Director Serial No. 440/092877 Office of Inspection and Enforcement PO&M/TAP:wbh U. S. Nuclear Regulatory Commission Docket Region II - Suite 818 230 Peachtree Street, Northwest License Nos. -J2 Atlanta, Georgia 30303 DPR-37
Dear Mr. O'Reilly:
This is in response to your letter of September 28, 1977, in refer-ence to the inspection conducted at Surry Power Station on August 30 - Sept-ember 2, 1977, and reported in inspection reports I.E.-50-280/77-24 and 50-281/77-24.
We have reviewed your letter and the enclosed inspection reports and have determined that no proprietary information is contained in the reports
- cordingly, the Virginia Electric and Power Company interposes no objection
- these inspections reports be~ng made a matter of public disclosure.
Very truly yours,
/ , ):1r' C ., .~ *
(_(_.-'. t~*t,'. / \..c::Jf£.ll{cc,/1,)
C. M. Stallings Vice President-Power Supply and Production Operations cc: Mr. Robert W. Reid
UNITED STATES.
NUCLEAR REGULATORY COMMISSION REGION II e 230 PEACHTREE STREET, N.W. SUITE 121_7 ATLANTA, GEORGIA 30303*
SEP 2 8 1977 In Reply Refer To:
RII:AKH 20-280/77-24 50-281/77-24 Virginia Electric and Power Company Attn: Mr. W. L. Proffitt Senior Vice President,
- Power P.O. Box 26666 Richmond, Virginia 23261
-Gentlem~n:
This refers to the inspection conducted by Mr. A. K. Hardin of this office on August 30 - September 2, 1977, of activities authorized by NRC Operating License Nos. DPR-32 and DPR-37 for the Surry 1 and 2 facilities, and to the discussion of our findings held with Mr. T. L. Baucom at the conclusion of the inspection.
~ Areas examined during the inspection and our findings are discussed in the enclosed inspection report. Within these areas, the inspection consisted of selective examinations of procedures and representative records, interviews with personnel, and observations by the inspector.
Within the scope of-this inspection, no items 0f no~compliance were disclosed.
In accordance with Section 2.790 of the ~C's "Rules of Practice",
Part 2, Title 10, Code of Federal Regulations; a copy of this letter and the enclosed inspection report will be placed in the NRC's Public Document Room. If this report contains any information that you (or your GOntractor) beiieve to be proprietary, it is necessary that you make a written application within 20 days to this office to withhold such information from public d,isclosure. Any such application must include a full statement of the reasons on the basis of which it is claimed that the information is proprietary, and should be prepared sp that proprietary information identified in the application is contained in a separate part of the document. If we do not hear from you in this regard within .the s.pecified period, the report, will' l?e placed in the Public Document Room.
e Virginia Electric and Power Company Should you have any questions concerning this letter, we will be glad to discuss them with you.
Very truly yours,
,~-:sr~
F. J. L o n g , ~
Reactor Operations and Nuclear Support Branch
Enclosure:
RII Inspection Report Nos.
~ 50-280/77-24 and 50-281/77-24 cc: Mr. T. L. Baucom Surry Power Station P. O. Box 315 Surry, Virginia 23883 e
e.
e UNITED STATES NUCLEAR REGULATORY COMMISSION
- REGION II 230 PEACHTREE STREET, N.W. SUITE f217 ATLANTA, GEORGIA 30303 Report Nos.: 50-280/77-24 and 50-281/77-24 Docket Nos.: 50-280 and 50-281 License Nos.: DPR-32 and DPR-37 Licensee: Virginia Electric and Power Company P.O. Box 26666 Richmond, Virginia 23261
- Facility Name:* Surry Uni ts 1 and 2
- Inspection at: Surry Power Station, Surry, Virginia Inspection conducted: August 30 - September 2, 1977 Inspector: A. K. Harnin Accompanying Personnel: *None e Reviewed by: e.c. ~ '7/U/77 R. C. L e ~ Date Reactor ProjeG.._ts Section No. 2 Inspection Summary Inspection on August 30 - September 2, 1977 (Report Nos. 50-280/77-24 and 50-281/77-24)
Areas Tnspected: Routine, unannounced inspection of employee training -
programs, plant operations, station access requirements and licensee events. The inspection involved 35 hours4.050926e-4 days <br />0.00972 hours <br />5.787037e-5 weeks <br />1.33175e-5 months <br /> of on site ~nspection. by one NRC inspector.
Results: Of the four areas inspected, no items of noncompliance or deviations were observed.
e
e e
- RII Rpt. Nos. 50-280/77-24 and 50-281/77-24_
DETAILS I Prepared by:
I-1
,e.*c.~ ~ 'J/u/77 A. K. Hardin, React:6f Inspector Date Reactor Projects Section No. 2 Reactor Operations and Nuclear Support Branch Dates of Inspection: August 30 - September 2, 1977
,1Z_.
Reviewed by: _ _ _c__.._.~ - - - *- - - 9/.z.G./77 R. C. Lewis, Chief Date Reactor Projects Section No. 2 Reactor Operations and Nuclear Support Branch*
- 1. Persons Contacted T. L. Baucom, Station Manager
- w. L. Stewart, Operations Superintendent F. B. Curling, Training Supervisor J. s. Fisher, Fire Marshall
- c. F. Wheeler, Security Supervisor e J. L. Wilson, Operations Supervisor
- o. Smith,- ~raining.Manager
- F. L. Rentz, Quality Assurance Engineer E. P. Dewandel, Administrative-Assistant R. Cephas, Quality Assurance Engineer
- 2. Licensee Action on Previous Inspection Findings None inspected on this inspection.
- 3. Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of nonco;npliance, or deviations. Four unresotved items disclosed during i::he_inspe~tion are discussed in paragraphs 5.a., 5.b., ~.c.,-and 5.d.
4_. Exit Interview The inspector met with the Station Manager and other members of the
- VEPCO organization as denoted in "Paragraph 1.
- The results of- the inspection were discussed.
e RII Rpt. Nos. 50-280/77-24 I-2 e and 50-281/77-24
- 5. Training The licensee's general employee training program, not including licensed operators, as committed to in the licensee's Quality Assurance program and implemented by Administrative frocedure No.-12 was inspected. An, overali assessment of -the general em-ployee training program indicated compliance with commitments.
However, a review of certain areas in detail revealed what appears to be isolated deficiencies in the program and in procedure imple-mentation. These areas were discussed with the licensee during the inspection and summarized at the exit interview as potential:.
~iolation of quality assurance program commitments., Subsequent inoffice review and comparison o.f the findings with _regul~tory requirements and *1i--c-ensee commitments.revealed that noncompliance had not occurred. The areas referred to are as follows:_
- a. Administrative Procedure No. 12 Section 5.1.1.A.l This section of the procedure states that all regular em-ployees will be retrained and recertified in first aid once every three years. Records do not support this requirement.
In subsequent discussion the licensee stated that it was not the intent that all regular employees be_retrained and re-certif~ed in first aid every three years. The licensee stated that only those numbers and categories of people "t'equired to be certi£ied in first aid by the plant emergency plan should have to be in the retraining program. The inspector did not disagree with this contention, but stated that the procedure uses the mandatory "will" and either the program or the procedure is deficient. This item is designated as unresolved item 77-24/1-1.
- b. Fire Service Training The Virginia State Board of Education administers a fire service training program for Virginia Electric Power Company (VEPCO). personn~l.
- VEPCO Administrative Procedure No. -12, item 5.1.2.A.l -lists,14 areas to be covered in the' cour,se of instruction and states any area not specificaliy covered_ by the Virginia State Board of Education will be supplemented by the station training staff. Comparison~of tlie list of 14 areas in_Administrative Procedure No. 12 and the areas spe~i-
,fically covered by the Virginia State Bqard of Education
- indicates two areas not covered by the Virginia State Board.
These areas were not supplemented by the station training staff. The areas were "Ventilation" and "Making Forcible Entry". This item is designated Unresolved *rtem 77-24/I-2.
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- RI! Rpt. Nos. 50-280/77-24 and 50-281/77-24
- c. Advanced Training 1-3 (1) Records Section 5.1."2.A.2 of Adm 12 states that the fire brigade will meet on a quarterly basis for advanced training purposes. The inspector asked for a record to demonstrate this requirement of the procedure was being met. The licensee gave the inspector a record entitled "Fire Brigade Log Book."
- Fol.lowing review of the log the inspector stated the record was inadequate for the follow-ing reasons.
May 4, 1977 entry states a fire drill was ~eld on
- April 22, 1977. There are no log entries in the 1.og fbr April 22, 1977.
The log states there was no meeting on June 15, 1977. Other records show_ther~ was a meeting at which five fire brigade members attended.
There is no listing in the log of those who attend
. meetings, although this can be attained elsewhere.
The inspector stated the log book was inadequate as a quality record. This item is desig~ted as unresolved item 77-24/1-3.
- d. Fire Dr-ills Section 5.1. 2.A_. 2 of A.dm 12 also states, among other fire
-drill requirements, that a once a year an announced fire drill will be conducted in conjunction with offsite fire fighting agencies to exercise the coordination of the station and the offsite agencies. The licensee stated the offsite fire fighting agencies have stated through their representatives a reluctance to participate in fire drills at the plant on 'the basis that there is insufficient information to be learned.
The inspector stated this procedure requirement must be met or the procedure and.program revised in a manner evaluated as safe by the licensee. This item is designated as unresolved item 77-24/I-4. .
The licensee did not raise any specific objection to the findings and agreed that corrections and adjustments will be made in the regular employee training program.
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e e Rll Rpt. Nos. 50-280/77-24 I-4 and 50:..281/77-24
- 6. Recirculation SFray'Pumps On August 24, 1977, VEPCO proposed plant modification and plant operating limits for Surry 1 and 2 to reduce concern related to insufficient net positive suction head (NPSH) to the containment recirculation spray pumps. By an Order dated August 24, 1977 the Office of Nuclear Reactor Regulation authorized the modifications and imposed limits on the operating parameters of service water temperature, containment temperature and containment air partial
,maximum pressure. During the current inspection, the'licensee's compliance with the order was audited.
By Plant Design --Change No. 77-41 entitled "Recirculation Spray NPSH
_ Modification" da:ted 8/25/77 the licensee installed flow restricting
,~ 'orifices in -thetdischarge lines innnediately downstream of the outside recirculation spray pumps, The inspector made a inspection of the above listed operating parameters at 10:45 a.m. on September 2, 1977, as follows:
Unit 1 Unit 2 Service Water Temperature, (limit 55°F to 85°F) 80.5°F 0
Containment Temperature (limit 100°F to 125°F) - 123 F*
Containment Air 0 Partial Maxi.mum Pressure (Limit 9.,0 PSIA 9..1 PSIA 9.3 PSIA at 85 F Service Water Temperature and 43°F 44°F 0
45 RWST Temperature)_ (_RWST Temp.}
The safety evaluation for the above modifications and operat'ing limits were transmitted by VEPCO to.Nuclear Reactor Regulation (NRR) on August 24, 1977. The design change implementing the modifications was approved by VEPCO's Station Nuclear Safety and Operating Committee, (SNS&OC). in Meeting No. 7Cr-77 dated August 23,
+977. , '
- 7. Low Head Safety Injection PumRs (LHSIPS)
A temporary solution to a similar concern for NPSH for the LHSIPS was resolved per instructions of NRR on August 29, 1977. The temporary solution consisted of adjusting the discharge valve of the LHSIPS to_a fl9w of 2100 GPM if both rumps ~ere running with a provision to adjust_ to 3250+/-250 GPM if only one pump is operating.-
The i-p.spector verif'ied that an adequate procedure had been written and approved to accomplish the above flow throttling requirements under conditions which would require the lliSIS's.
rj e RII Rpt. Nps. 50-280/77-24 1-5
- 8.
and 50-281/77-24 Security Inspection~ Station Access The inspector observed on a spot check basis throughou~ the inspec-tion the licensee's compliance with station access requirements.
Procedures.covering operational areas related to access requirements were reviewed. No areas of noncompliance with regulatory require-ments were observed.
- 9. Plant Operations The inspector observed unit operations in the Nuclear Control Center. Response toar..nunciator alarms, activities following a reactor trip and conduct bf periodic* tests were observed. No items of noncompliance were observ~d.
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