|
|
Line 3: |
Line 3: |
| | issue date = 11/05/2015 | | | issue date = 11/05/2015 |
| | title = IR 05000280/2015201 and 05000281/2015201, on 06/26/2015, Surry Power Station, Unit Nos. 1 and 2, NRC Security Inspection | | | title = IR 05000280/2015201 and 05000281/2015201, on 06/26/2015, Surry Power Station, Unit Nos. 1 and 2, NRC Security Inspection |
| | author name = Johnson R C | | | author name = Johnson R |
| | author affiliation = NRC/NSIR/DSO | | | author affiliation = NRC/NSIR/DSO |
| | addressee name = Heacock D A | | | addressee name = Heacock D |
| | addressee affiliation = Virginia Electric & Power Co (VEPCO) | | | addressee affiliation = Virginia Electric & Power Co (VEPCO) |
| | docket = 05000280, 05000281 | | | docket = 05000280, 05000281 |
Line 18: |
Line 18: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:November 5, 2015 | | {{#Wiki_filter:November 5, 2015 |
|
| |
|
| Mr. David President & Chief Nuclear Officer Virginia Electric & Power Company Surry Power Station, Units 1 and 2 Innsbrook Technical Center 5000 Dominion Boulevard
| | ==SUBJECT:== |
| | | SURRY POWER STATION, UNIT 1 AND 2 - NRC SECURITY INSPECTION REPORT 05000280/2015201 AND 05000281/2015201 |
| Glen Allen, VA 23060 SUBJECT: SURRY POWER STATION, UNIT 1 AND 2 - NRC SECURITY INSPECTION REPORT 05000280/2015201 AND 05000281/2015201
| |
|
| |
|
| ==Dear Mr. Heacock:== | | ==Dear Mr. Heacock:== |
Revision as of 18:16, 20 June 2019
Similar Documents at Surry |
---|
Category:Letter
MONTHYEARML24318C4622024-11-13013 November 2024 Emergency Plan Revision - Relocation of the Technical Support Center (TSC) - License Amendment Nos. 315 and 315 Updated Information Regarding TSC Ventilation Design IR 05000280/20240032024-11-12012 November 2024 Integrated Inspection Report 05000280-2024003 and 05000281-2024003 ML24302A1762024-10-22022 October 2024 Core Operating Limits Report Surry 2 Cycle 33 Pattern Hot Revision 0 ML24283A0702024-10-0707 October 2024 Annual Submittal of Technical Specifications Bases Changes Pursuant to Technical Specification 6.4.J IR 05000280/20240102024-10-0202 October 2024 Biennial Problem Identification and Resolution Inspection Report 05000280/2024010 and 05000281/2024010 ML24270A0022024-09-25025 September 2024 Inservice Inspection Owners Activity Report (OAR) ML24248A1712024-09-0303 September 2024 Proposed License Amendment Request - Temporary Service Water Supply to the Component Cooling Heat Exchangers IR 05000280/20240052024-08-26026 August 2024 Updated Inspection Plan for Surry Power Station, Units 1 and 2 (Report 05000280/2024005 and 05000281-2024005), Rev 1 ML24219A2372024-08-23023 August 2024 Issuance of Amendment Nos. 319 and 319, Adoption of TSTF-577, Rev. 1, Revised Frequencies for Steam Generator Tube Inspection, ML24207A0402024-08-21021 August 2024 Summary of July 17, 2024, Public Meeting - TS 3.7/3.14 AOT for SW Piping Maintenance ML24164A0012024-08-12012 August 2024 Proposed Alternative Relief Request V-1 Inservice Testing of Pressure Isolation Valves (EPID l-2023-LLR-0060) IR 05000280/20240022024-08-0101 August 2024 Integrated Inspection Report 05000280/2024002 and 05000281/2024002 05000280/LER-2024-001, Troubleshooting Initiated Unknown Turbine Trip Feature in Control System2024-07-30030 July 2024 Troubleshooting Initiated Unknown Turbine Trip Feature in Control System ML24165A2782024-07-17017 July 2024 Issuance of Amendment Nos. 318 and 318, Reclassification of Regulatory Guide 1.97 Variable for Low Head Safety Injection ML24165A1232024-07-17017 July 2024 Proposed Alternative Relief Request P-1, P-2 Inservice Testing of Residual Heat and Containment Spray Pumps (EPID l-2023-LLR-0058) ML24190A4192024-07-0808 July 2024 Inservice Testing (IST) Program for Pumps and Valves Revised Sixth IST Interval Start Date and Updated Technical Specifications References for Alternative Request V-1 ML24179A2932024-07-0101 July 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML24178A2422024-06-25025 June 2024 2023 Annual Report of Emergency Core Cooling System (ECCS) Model, Changes Pursuant to the Requirements of 10 CFR 50.46 ML24177A2792024-06-20020 June 2024 Preparation and Scheduling of Operator Licensing Examinations ML24166A0622024-06-18018 June 2024 – Proposed Alternative Relief Request P-3, P-4 Inservice Testing of Boric Acid, Component Cooling Water Pumps ML24157A0542024-06-13013 June 2024 Audit Summary in Support of License Amendment Request for Proposed Reclassification of Low Head Safety Injection Flow Instrumentation Related to Regulatory Guide 1.97 ML24143A1622024-06-12012 June 2024 – Correction to Issuance of Amendment Nos. 297 and 280 and Surry Units 1 and 2, Correction to Issuance of Amendment Nos. 317 and 317, to Change Emergency Plan Staff Augmentation Times ML24170B0532024-06-10010 June 2024 DOM-NAF-2-P/NP-A, Revision 0.5, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code IR 05000280/20244032024-05-22022 May 2024 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000280/2024403 and 05000281- 2024403 ML24141A2862024-05-22022 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 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 ML24130A2492024-05-0909 May 2024 Submittal of Information in Support of Surry Power Station Unit 1 Thermal Shield Flexure Replacement Campaign 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 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 ML24023A5762024-03-0808 March 2024 Correction to Issuance of Amendment Nos. 315 and 315, Regarding Revised Emergency Plan for Relocation of the Technical Support Center IR 05000280/20230062024-02-28028 February 2024 Annual Assessment Letter for Surry Power Station, Units 1 and 2 - NRC Inspection Reports 05000280/2023006 and 05000281/2023006 ML24032A4712024-02-20020 February 2024 Exemption from Select Requirements of 10 CFR Part 73 - Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML24051A1782024-02-19019 February 2024 Proposed License Amendment Request - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML24057A0612024-02-19019 February 2024 And Virgil C. Summer Power Nuclear Stations - Nuclear Property Insurance Coverage IR 05000280/20230042024-02-0909 February 2024 Integrated Inspection Report 05000280/2023004 and 05000281/2023004 2024-09-03
[Table view] |
Text
November 5, 2015
SUBJECT:
SURRY POWER STATION, UNIT 1 AND 2 - NRC SECURITY INSPECTION REPORT 05000280/2015201 AND 05000281/2015201
Dear Mr. Heacock:
On June 26, 2015, the U.S. Nuclear Regulatory Commission (NRC) completed a security inspection at your Surry Power Station, Unit 1 and 2. On August 6, 2015, the NRC inspectors discussed results of this inspection with Mr. Roy Simmons, Plant Manager and other members of your staff. Inspectors documented the results of this inspection in the enclosed inspection
report. The NRC inspectors documented two findings of very low security significance (Green) in this report. These findings were a violation of NRC requirements. The NRC is treating these violations as non-cited violations (NCV) consistent with Section 2.3.2.a of the Enforcement Policy. If you contest these violations or the significance of these NCVs, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S.
Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator Region II; Director, Office of Nuclear Security and Incident Response, and the Director, Office of Enforcement, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; and the NRC resident inspector at the Surry Power Station, Unit 1 and 2.
If you disagree with a cross-cutting assignment in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the Regional Administrator, Region II; the Director, Office of Nuclear Security, and Incident Response, and the NRC resident inspector at the Surry Power Station, Unit 1 and 2. In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390 "Public Inspections, Exemptions, Requests for Withholding,"
of the NRC's "Rules of Practice," a copy of this letter will be available electronically for public inspection in the NRC's Public Document Room or from the Publicly Available Records (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
However, the material enclosed herewith contains Safeguards Information as defined by 10 CFR 73.21 "Protection of Safeguards Information; Performance Requirements," and its disclosure to unauthorized individuals is prohibited by Section 147 of the Atomic Energy Act of 1954, as amended. Therefore, the material in the enclosure will not be made available electronically for public inspection in the NRC Public Document Room or from the PARS component of NRC's ADAMS. If you choose to provide a response and Safeguards Information
is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21. Otherwise, if Security-Related Information is necessary to provide an acceptable response, please mark your entire response "Security-Related Information - Withhold from Public Disclosure under 10 CFR 2.390" in accordance with 10 CFR 2.390(d)(1)
and follow the instructions for withholding in 10 CFR 2.390(b)(1). In accordance with 10 CFR 2.390(b)(1)(ii), the NRC is waiving the affidavit requirements for your response.
Sincerely,
/RA D. Cardenas for/
Robert C. Johnson, Chief
Security Performance Evaluation Branch Division of Security Operations Office of Nuclear Security and Incident Response
Docket Nos. 50-280, 50-281 License Nos. DPR-32, DPR-37
Nonpublic Enclosure: Inspection Report 05000280/2015201 and 05000281/2015201 w/Attachment: Supplemental Information
cc w/enclosure: Terry Rawls, Manager Site Security
ML15240A048 OFFICE NSIR/DSO/SPEB NSIR/DSO NSIR/DSO/SPEB RII NSIR/DSO/SPEB NAME D. Hostetter J. Clark J. Berry B. Desai D. Cardenas for/C. JohnsonDATE 08/24/2015 9/10/2015 8/26/2015 9/9/2015 11/05/2015