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 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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
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Inspection Report - Surry - 2019010 |
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UNITED STATES NUCLEAR REGULATORY COMMISSION May 3, 2019
SUBJECT:
SURRY UNITS 1, 2 -NRC EVALUATION OF CHANGES, TESTS, AND EXPERIMENTS REPORT 05000280/2019010 AND 05000281/2019010
Dear Mr. Stoddard:
On April 25, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Surry Units 1, 2 and discussed the results of this inspection with Mr. Fred Mladen and other members of your staff. The results of this inspection are documented in the enclosed report.
The NRC inspectors did not identify any finding or violation of more than minor significance.
This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely,
/RA/
Jonathan M. Montgomery, Acting Chief Engineering Branch 1 Division of Reactor Safety Docket Nos.: 05000280 and 05000281 License Nos.: DPR-32 and DPR-37
Enclosure:
Inspection Report 05000280/2019010 and 05000281/2019010
Inspection Report
Docket Number(s): 05000280 and 05000281 License Number(s): DPR-32 and DPR-37 Report Number(s): 05000280/2019010 and 05000281/2019010 Enterprise Identifier: I-2019-010-0028 Licensee: Virginia Electric & Power Co.
Facility: Surry, Units 1 and 2 Location: Surry, VA 23060 Inspection Dates: April 22, 2019 to April 25, 2019 Inspectors: B. Davis, Sr. Reactor Inspector N. Morgan, Reactor Inspector M. Schwieg, Reactor Inspector Approved By: Jonathan M. Montgomery, Acting Chief Engineering Branch 1 Division of Reactor Safety Enclosure
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a 10 CFR 50.59 inspection at Surry Units 1 and 2 in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information. Findings and violations being considered in the NRCs assessment are summarized in the table below.
List of Findings and Violations No findings were identified.
INSPECTION SCOPE
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
REACTOR SAFETY
71111.17T - Evaluations of Changes, Tests, and Experiments Sample Selection (IP Section 02.01)
Main article: IP 71111.17
The inspectors reviewed the following evaluations, screenings, and/or applicability determinations for 10 CFR 50.59 from March 2015 to February 2019.
- (1) DCP 07-046, Replacement of 1-FP-P-2 Diesel Driven Fire Pump, Units 1 & 2
- (2) DCP SU-15-01144, 2-SI-MOV-2869A Motor Replacement, Unit 2
- (3) DCP SU-16-01101, Reactor Coolant Loop Flow Transmitter 1-RC-FT-1414 Rosemount Model 1153HA5 Replacement with Rosemount Model 3152ND3, Unit 1
- (4) DCP 04-088, Replacement of the Emergency Diesel Temperature Switches, Unit 1
- (5) DCP SU-13-00006, Emergency Diesel Generator #1 Cable Replacement, Unit 1
- (6) DCP 04-076, Oversized Breakers and Undersized Cables Replacement, Units 1 & 2
- (7) DCP SU-09-0017, Mechanical Equipment Room 3 & 4 Service Water Chemical Injection, Units 1 & 2
- (8) DCP SU-15-01046, Replacement of Pressurizer Spray Bypass Valve 1-RC-139, Unit
- (9) DCP SU-15-01056, Mechanical Equipment Room 4 Service Water Material Evaluation, Unit 2
- (10) DCP SU-15-01074, Reactor Coolant Pump 1-RC-P-1B Seal Face Change, Unit 1
- (11) DCP SU-15-01123, Refueling Water Storage Tank Controller Replacement, Units 1 &
- (12) DCP SU-18-00105, Ventilation System Set Point Changes (1-VS-PS-128A, 128A-1, 128B & 128B-1), Unit 1
- (13) DCP 98-043, Turbine Driven Auxiliary Feedwater Pump Steam Supply Circuit Upgrades, Unit 1
- (14) DCP SU-14-01153, "C" Safety Injection Accumulator Discharge Motor Operated Valve Modification, Unit 1
- (15) DCP SU-14-01083, Replacement Flow Switch for 1-VS-FS-117A/B and Setpoint Change, Units 1 & 2
- (16) DCP SU-15-01014, Thermal Overload Replacement for Safety Related Motor Operated Valves, Units 1 & 2
- (17) DCP 05-048, Circulating Water Inlet Motor Operated Valve Modification, Units 1 & 2
- (18) DCP SU-15-01063, Reconfiguration of Direct Current Circuit Breakers, Units 1 & 2
- (19) DCP SU-15-01075, Reconfiguring Reactor Protection Trip Breaker Ladder Logic Wiring, Units 1 & 2
- (20) DCP SU-09-0008, Motor Operated Valve Stem Cuts, Unit 2
- (21) DCP SU-10-01041, High Head Safety Injection Motor Operated Valve Pressure Locking Modifications, Units 1 &
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On April 25, 2019, the inspector presented the inspection results to Mr. Fred Mladen and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection Type Designation Description or Title Revision or
Procedure Date
71111.17T Calculations EE-0183 CSA Calculation for Surry Power Station Units 1 and 2 Rev. 5
Reactor Coolant Flow
ME-0615 Auxiliary Ventilation System Flow/Pressure Model Rev. 0
ME-0977 Hydraulic Calculation of Fire Main Loop Rev. 0
ME-0977 Hydraulic Calculation of Fire Main Loop Rev. A
SM-1323 Pressurizer Spray Bypass Flow Rate Calculation, Surry Rev. 0
Power Station, Units 1 and 2
Corrective Action 1002002
Documents 1017294
2165
2632
553409
554091
2198
Corrective Action 1121608 Missing Record for 0-NSP-RC-001 Vibration Testing 4/23/2019
Documents
Resulting from
Inspection
Drawings 11448-FB-47A Flow/Valve Operating Numbers Diagram Fire Protection & Rev. 34
Domestic Water System Surry Power Station - Unit 1
Miscellaneous ET-S-04-0018 Evaluate SW Pipe Spool for IEER Rev. 0
MOV 2-SI-2869A Motor Current Evaluation 11/18/2015
Procedures 0-ECM-1403-01 Electrical Corrective Maintenance Rev. 40
0-NSP-RC-001 Reactor Coolant Pump Vibration and Balancing Data Rev. 2
ET-CEE-08-0015 Motor Operated Valve (MOV) Overcurrent Issue Six Sigma Rev. 1
Project Results
Work Orders 38102423911
38102423911
38102586663
71111.17T Work Orders 38103521042
38103564388
38103584837
38103584844
38103631355
38103631403
38103635555
38103638419
38103676443