ML12093A252
| ML12093A252 | |
| Person / Time | |
|---|---|
| Site: | Summer |
| Issue date: | 03/30/2012 |
| From: | Gatlin T South Carolina Electric & Gas Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML12093A252 (10) | |
Text
Thomas D. Gatlin Vice President, Nuclear Operations 803.345.4342 March 30, 2012 A SCANA COMPANY U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
Dear Sir/Madam:
Subject:
VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50-395 OPERATING LICENSE NO. NPF-12 ANNUAL OPERATING REPORT Enclosed is the 2011 Annual Operating Report for the South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station Unit No. 1. This report is being submitted in accordance with Technical Specification 6.9.1.4 and Regulatory Guide 1.16.
If there are any questions, please call at your convenience.
Very truly yours, Thomas D. Gatlin SBR/TDG/gr Attachment c:
K. B. Marsh S. A. Byrne J. B. Archie N. S. Cams J. H. Hamilton R. J. White W. M. Cherry V. M. McCree R. E. Martin REIRS Project Manager M. L. Thomas K. M. Sutton J. C. Mellette C. Stewart (ANI)
Marsh USA, Inc.
NRC Resident Inspector NSRC RTS (LTD 292)
File (818.02-10, RR 8225)
PRSF (RC-12-0051)
P b I OKý Virgil C. Summer Station
- Post Office Box 88
- Jenkinsville, SC. 29065
- F (803) 345-5209
VIRGIL C. SUMMER NUCLEAR STATION 2011 ANNUAL OPERATING REPORT
Document Control Desk LTD 292 RC-1 2-0051 Page 2 of 9 PREFACE The 2011 Annual Operating Report for the Virgil C. Summer Nuclear Station is hereby submitted in accordance with Technical Specification 6.9.1.4 and Regulatory Guide 1.16 under Docket Number 50/395 and Facility Operating License NPF-12.
Document Control Desk LTD 292 RC-12-0051 Page 3 of 9 TABLE OF CONTENTS SECTION 1.0 2.0 3.0 4.0 5.0 TITLE Introduction Operational Data Operating Summary Exposures Failed Fuel PAGE 4
4 4
7 7
ATTACHMENTS 1.
2011 Man-Rem Report
Document Control Desk LTD 292 RC-12-0051 Page 4 of 9 ANNUAL OPERATING REPORT
1.0 INTRODUCTION
The Virgil C. Summer Nuclear Station (VCSNS) utilizes a pressurized water reactor rated at 2900 MW-IT.
The maximum dependable capacity is 966 MWe.
The station is located approximately 26 miles northwest of Columbia, South Carolina.
2.0 OPERATIONAL DATA For the reporting period of January 1 through December 31, 2011, the station operated at a capacity factor of 81.8% (using maximum dependable capacity) and a unit availability of 84.4%. The reactor was critical for a total of 7671.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />, the generator remained on line 7626.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and the total gross electrical energy generated for 2011 was 7,723,825 MWH.
3.0 OPERATING
SUMMARY
The Virgil C. Summer Nuclear Station (VCSNS) Unit No.1 operated at 100% power from January 1st through January 1 8th. On January 1 8th, the unit was taken off line to investigate and repair the "C" reactor coolant pump motor oil high level indication.
Reactor power was restored to 100% on January 2 1st.
VCSNS operated at 100% power from January 2 1st to April 14 th. On April 14th power was reduced to approximately 29% due to the loss of cooling to the main generator breaker. Reactor power was maintained at 29% until April 1 5 th when the unit was-taken off line for Refueling Outage Nineteen (RF 19). The plant remained shut down for the refueling outage until May 2 9 th when the reactor was returned to criticality and synchronized to the grid at 1721 hours0.0199 days <br />0.478 hours <br />0.00285 weeks <br />6.548405e-4 months <br /> on May 3 1st. The turbine was taken off line on May 3 1st to perform the Turbine Overspeed trip test. Reactor power was restored to 100% on June 2 nd
,VCSNS operated at 100% power from June 2 nd to June 1 5 th. On June 15 th power was reduced to approximately 76% to support a repair to a non-isolable leak on the closed cycle cooling system generator hydrogen cooler.
Reactor power was restored to 100% on June 1 5th.
Document Control Desk LTD 292 RC-12-0051 Page 5 of 9 VCSNS operated at 100% power from June 1 5th to June 1 7th. On June 1 7th power was reduced to approximately 99% to support Delta T and Nuclear Instrumentation operational testing. Reactor power was restored to 100%
on June 1 9 th.
VCSNS operated at 100% power from June 1 9th to July 7 th. On July 7 th power was reduced to approximately 99% to support calibration of the power range nuclear instrumentation. Power was restored to 100% on July 8 th, The plant operated at 100% power July 7th to August 2 6th. On August 2 6 th power was reduced to approximately 99% to support calibration of the reactor coolant system Delta T channels. Power was restored to 100% on August 2 8 th The plant operated at 100% power August 2 8 th to September 2 2 nd.
On September 2 2 nd power was reduced to approximately 95% due to a level transit in the 2B feedwater heater. Repairs were made and power was restored to 100% on September 2 2nd.
The plant operated at 100% power September 2 2 nd to October 7 th. On October 7 th power was reduced to approximately 90.5% to support main turbine control valve testing. Power was restored to 100% October 8 th. The plant operated at 100% power for the remainder of 2011.
Refueling Outage 19 Summary The main generator breaker was opened at 2332 hours0.027 days <br />0.648 hours <br />0.00386 weeks <br />8.87326e-4 months <br /> on April 1 5 th for Refueling Outage 19.
Major work included:
Digital EHC System Main generator breaker replacement Service Water to Emergency Feedwater Pipe Liner - "B" Train Alternate Seal Injection Reactor Coolant System Leak Detection -
Control Rod Drive Mechanism Drain Line
Document Control Desk LTD 292 RC-12-0051 Page 6 of 9 Reactor Coolant System Leak Detection -
Control Rod Drive Mechanism Drain Line 0 Reactor Coolant Pump vibration monitoring Reactor Building Safety Upgrades - Phase 1 Volume Control Tank inlet header check valve Switchyard Bus 1 upgrades 0
Pressurizer Power Operated Relief Valve air accumulator replacement - Phase 1 a
Reactor Cavity Lift Polar Crane Telemotive Refueling Outage 19 duration was 45 days. Outage planned duration was 36.5 days.
Personnel exposure in 2011 due to the outage was approximately 34 Rem, based on electronic dosimeters.
Forced Power Reduction >20% Exceeding 4 Hours On January 1 8th, the plant was taken off line to investigate and repair the "C" reactor coolant pump motor oil high level indication.
Following the repair the reactor was returned to criticality on January 1 9 th at 1914 hours0.0222 days <br />0.532 hours <br />0.00316 weeks <br />7.28277e-4 months <br /> and was synchronized to the grid on January 2 0 th at 0412 hours0.00477 days <br />0.114 hours <br />6.812169e-4 weeks <br />1.56766e-4 months <br />. Reactor power was restored to 100% on January 2 1't at 0503 hours0.00582 days <br />0.14 hours <br />8.316799e-4 weeks <br />1.913915e-4 months <br />. This outage did not result in any single release of radioactivity or single radiation exposure that accounted for more than 10% of the allowable annual values.
The duration of the down power was approximately 50.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br />.
On April 1 3 th, reactor power was reduced to approximately 80% to test the main steam safety valves.
On April 1 4th power was reduced to approximately 29% due to loss of cooling to the main generator breaker.
On April 15t at 2332 hours0.027 days <br />0.648 hours <br />0.00386 weeks <br />8.87326e-4 months <br />, the plant was taken off line for Refueling Outage 19. The outage was completed in 45 days with breaker closure occurring at 0112 hours0.0013 days <br />0.0311 hours <br />1.851852e-4 weeks <br />4.2616e-5 months <br /> on May 3 1st. Reactor power was restored to 100%
at 2339 hours0.0271 days <br />0.65 hours <br />0.00387 weeks <br />8.899895e-4 months <br /> on June 2 nd.
On June 1 5 th, reactor power was reduced to approximately 76% to support a repair to a non-isolable leak on the closed cycle cooling system generator
Document Control Desk LTD 292 RC-1 2-0051 Page 7 of 9 4.0 EXPOSURES Attachment I lists the number of station, utility, and other personnel (including contract personnel) receiving exposures greater than 100 mrem/year and their associated man-rem exposure according to work and job function.
The exposures reported are estimated doses based on electronic dosimeters.
5.0 FAILED FUEL VCSNS did not have any indications of failed fuel in 2011.
Document Control Desk LTD 292 RC-1 2-0051 Page 8 of 9 ATTACHMENT I TO 2011 ANNUAL REPORT
Document Control Desk LTD 292 RC-12-0051 Page 9 of 9 South Carolina Electric & Gas Company V. C. Summer Nuclear Station Personnel and Man-Rem by Work and Duty Function Regulatory Guide 1.16 Annual Report for 2011 Number of Personnel Over 100 mRem Total Man-Rem Work and Job Function Station Utility Contract Station Utility Contract Workers Workers Workers Workers Workers Workers Inservice Maintenance Engineering Personnel 0
0 0
0.064 0.000 0.027 Health Physics Personnel 0
0 0
0.182 0.000 0.166 Maintenance Personnel 0
0 9
0.082 0.000 2.266 Operations Personnel 0
0 1
0.224 0.000 0.213 Supervisory Personnel 0
0 0
0.010 0.000 0.010 Reactor Operations & Surveillance Engineering Personnel 0
0 0
0.007 0.000 0.000 Health Physics Personnel 0
0 1
1.122 0.000 1.148 Maintenance Personnel 0
0 0
0.003 0.000 0.247 Operations Personnel 0
0 0
1.614 0.000 0.153 Superviso Personnel 0
0 0
0.096 0.000 0.000 Refueling Engineering Personnel 0
0 1
0.086
'0.000 0.357 Health Physics Personnel 1
0 0
0.531 0.000 0.215 Maintenance Personnel 0
0 26 0.264 0.000 7.587 Operations Personnel 0
0 0
0.224 0.000 0.055 Supervisory Personnel 0
0 0
0.009 0.000 0.000 Routine Maintenance Engineering Personnel 0
0 0
0.213 0.000 0.027 Health Physics Personnel 3
0 0
1.189 0.000 0.315 Maintenance Personnel 7
0 28 3.674 0.000 10.339 Operations Personnel 0
0 0
1.035 0.000 0.299 Supervisory Personnel 0
0 0
0.029 0.000 0.056 Special Maintenance Engineering Personnel 0
0 0
0.005 0.000 0.018 Health Physics Personnel 0
0 0
0.395 0.000 0.409 Maintenance Personnel 0
0 1
0.107 0.000 1.190 Operations Personnel 0
0 0
0.514 0.000 0.063 Supervisory Personnel 0
0 0
0.000 0.000 0.000 Waste Processing Engineering Personnel 0
0 0
0.000 0.000 0.000 Health Physics Personnel 1
0 0
0.472 0.000 0.004 Maintenance Personnel 0
0 0
0.013 0.000 0.003 Operations Personnel 0
0 0
0.002 0.000 0.002 Supervisory Personnel 0
0 0
0.069 0.000 0.000 Total Engineering Personnel 0
0 1
0.375 0.000 0.429 Health Physics Personnel 5
0 1
3.891 0.000 2.257 Maintenance Personnel 7
0 64 4.143 0.000 21.632 Operations Personnel 0
0 1
3.613 0.000 0.785 Supervisory Personnel 0
0 0
0.213 0.000 0.066 Sub Total 12 0
67 12.235 0.000 25.169 EDE Dose (Multiple Badging) 0 0
0 0.124 0.000 0.246 Grand Total 12 0
67 12.359 0.000 25.415