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Category:Inspection Report
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[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] |
Text
UNITED STATES ust 8, 2011
SUBJECT:
SURRY POWER STATION - NRC EMERGENCY PREPAREDNESS INSPECTION REPORT 05000280/2011501 AND 05000281/2011501
Dear Mr. Heacock:
On July 22, 2011, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Surry Power Station, Units 1 and 2. The enclosed inspection report documents the inspection results, which were discussed on July 22, 2011, with Mr. B. Stanley and other members of your staff.
The inspection examined activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your license.
The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.
Based on the results of this inspection, no findings of significance were identified.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response, if any, will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/ RA / A. Nielsen for B. Bonser Brian Bonser, Chief Plant Support Branch 1 Division of Reactor Safety Docket No.: 50-280, 50-281 License No.: DPR-32, DPR-37
Enclosure:
Inspection Report 05000280/2011501 and 05000281/2011501 w/Attachment: Supplemental Information
REGION II==
Docket Nos: 05000280, 05000281 License Nos: DPR-32, DPR-37 Report Nos: 05000280/2011501 and 05000281/2011501 Licensee: Virginia Electric and Power Company (VEPCO)
Facility: Surry Power Station, Units 1 and 2 Location: 5850 Hog Island Road Surry, VA 23883 Dates: July 18-22, 2011 Inspectors: M. Speck, Senior Emergency Preparedness Inspector C. Murray, Emergency Preparedness Specialist W. Loo, Senior Health Physics Inspector Approved by: Brian Bonser, Chief Plant Support Branch 1 Division of Reactor Safety Enclosure
SUMMARY OF FINDINGS
IR 05000280/2011501 and 05000281/2011501; 08/18/2011 - 08/22/2011; Surry Power Station,
Units 1 and 2; Exercise and baseline inspection.
The report covered an announced inspection by one emergency preparedness inspector, one emergency preparedness specialist, and one health physics inspector. The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process.
NRC-Identified and Self-Revealing Findings
Cornerstone: Emergency Preparedness
No findings were identified.
Licensee-Identified Violations
.
None
REPORT DETAILS
REACTOR SAFETY
Cornerstone: Emergency Preparedness
1EP1 Exercise Evaluation
a. Inspection Scope
Prior to the inspection activity, the inspectors conducted an in-office review of the exercise objectives and scenario submitted to the NRC to determine if the exercise would test major elements of the emergency plan as required by 10 CFR 50.47(b)(14).
This inspection activity represents one sample on a biennial cycle.
The onsite inspection consisted of the following review and assessment:
$ The adequacy of the licensees performance in the biennial exercise conducted on July 19, 2011, was reviewed and assessed regarding the implementation of the Risk Significant Planning Standards (RSPSs) in 10 CFR 50.47 (b)(4), (5), (9), and (10),which address emergency classification, offsite notification, radiological assessment, and protective action recommendations respectively.
$ The overall adequacy of the licensees emergency response facilities with regard to NUREG-0696, Functional Criteria for Emergency Response Facilities and Emergency Plan commitments. The facilities assessed were the Control Room simulator, Operations Support Center (OSC), Technical Support Center (TSC), and Local Emergency Operations Facility (LEOF).
$ Other performance areas besides the RSPS, such as the emergency response organizations (ERO) recognition of abnormal plant conditions, command and control, intra-and inter-facility communications, prioritization of mitigation activities, utilization of repair and field monitoring teams, interface with offsite agencies, and the overall implementation of the emergency plan and its implementing procedures.
$ Past performance issues from NRC inspection reports, and Federal Emergency Management Agency (FEMA)/Department of Homeland Security (DHS) exercise reports to determine effectiveness of corrective actions as demonstrated during this exercise to ensure compliance with 10 CFR 50.47(b)(14).
$ The post-exercise critique process, and the presentation to the licensee's senior management conducted on July 21, 2011, to evaluate the licensees self-assessment of its ERO performance during the exercise and to ensure compliance with 10 CFR 50, Appendix E.IV.F.2.g.
The inspectors reviewed various documents which are listed in the Attachment.
b. Findings
No findings were identified.
1EP4 Emergency Action Level (EAL) and Emergency Plan Changes
a. Inspection Scope
Since the last NRC inspection of this program area, Revision 55, of the Surry Emergency Plan was implemented based on the licensees determination in accordance with 10 CFR 50.54(q) that the changes resulted in no decrease in the effectiveness of the Plan, and that the revised Plan continued to meet the requirements of 10 CFR 50.47(b), and Appendix E to 10 CFR Part 50. The inspector conducted a review of the Plan changes and a sampling review of the implementing procedure changes made between September 1, 2010, and June 30, 2011, to evaluate for potential decreases in effectiveness of the Plan. This review was not documented in a Safety Evaluation Report and does not constitute formal NRC approval of the changes. Therefore, these changes remain subject to future NRC inspection in their entirety.
The inspection was conducted in accordance with NRC Inspection Procedure 71114, 04, Emergency Action Level and Emergency Plan Changes. The applicable planning standard 10 CFR 50.47(b)(4), and related requirements contained in 10 CFR 50.54(q), and Appendix E to 10 CFR Part 50 were used as reference criteria.
This inspection activity represents one sample on an annual cycle.
The inspector reviewed various documents which are listed in the Attachment.
b. Findings
No findings were identified.
OTHER ACTIVITIES
4OA1 Performance Indicator (PI) Verification
a. Inspection Scope
The inspectors sampled licensee submittals for the three performance indicators (PI)listed below. For each of the submittals, the inspectors reviewed the period from July 1, 2010, through March 31, 2011. To verify the accuracy of the PI data reported during that period, PI definitions and guidance contained in Nuclear Energy Institute (NEI) 99-02, Regulatory Assessment Indicator Guideline, Revision 6, were used to verify the basis in reporting for each data element.
$ Emergency Response Organization Drill/Exercise Performance (DEP)
$ Emergency Response Organization Readiness (ERO)
$ Alert and Notification System Reliability (ANS)
The inspectors reviewed portions of the raw PI data developed from monthly performance indicator reports and discussed the methods for compiling and reporting the PIs with the responsible emergency preparedness personnel. The inspectors also independently screened drill and exercise opportunity evaluations, drill participation reports, and drill evaluations. Selected reported values were calculated to verify their accuracy. The inspectors compared graphical representations from the most recent PI report to the raw data to verify that the data was correctly reflected in the report.
Reviewed documents are listed in the Attachment.
The inspection was conducted in accordance with NRC Inspection Procedure 71151, Performance Indicator Verification. This inspection activity represents three samples on an annual cycle.
The inspectors reviewed various documents which are listed in the Attachment.
b. Findings
No findings were identified.
4OA6 Meetings, Including Exit
On July 22, 2011, the lead inspector for the emergency preparedness inspection presented the inspection results to Mr. B. Stanley, and other members of the onsite management staff. The inspectors confirmed that proprietary information was not provided or taken during the inspection.
ATTACHMENT:
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee personnel
- G. Bischof, Site Vice President
- J. Eggart, Manager, Radiation Protection and Chemistry
- B. Garber, Supervisor, Licensing
- W. Hoffner, Fleet EP Manager
- R. Johnson, Manager, Operations
- C. Olsen, Manager, Site Engineering
- K. Sloane, Plant Manager
- M. Smith, Manager, Nuclear Oversight
- B. Stanley, Director, Station Safety and Licensing
- N. Turner, EP Supervisor
ITEMS OPENED, CLOSED, AND DISCUSSED
None
LIST OF DOCUMENTS REVIEWED