ML060940276

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Annual Operating Report
ML060940276
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 03/31/2006
From: Archie J
South Carolina Electric & Gas Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML060940276 (11)
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Text

Jeffrey B. Archie Vice President, Nuclear Operations 803.345.4214 A SCANA COMPANY March 31, 2006 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 2005 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 Specifications 6.9.1.4, 6.9.1.5, and Regulatory Guide 1.16.

If there are any questions, please call at your convenience.

VerytB. yours, B.Archie SBR/JBA/sr Attachment c: N. 0.Lorick D. L. Abstance S. A. Byrne W. G. Wendland J. H. Hamilton (w/o attachment) J&H Marsh & McLennan R. J. White NRC Resident Inspector W. D. Travers NSRC R. E. Martin RTS (L-99-0107)

REIRS Project Manager File (818.02-1 0, RR 8225)

M. L. Thomas DMS (RC-06-0055)

K. M. Sutton 13u SCE&G i Virgil C.Summer Nuclear Station

  • P.0.Box 88 . Jenkinsville, South Carolina 29065 .T (803) 345.5209 . www.scono.com

VIRGIL C. SUMMER NUCLEAR STATION 2005 ANNUAL OPERATING REPORT

Document Control Desk Attachment L-99-0107 RC-06-055 Page 2 of 10 PREFACE The 2005 Annual Operating Report for the Virgil C. Summer Nuclear Station is hereby submitted in accordance with Technical Specifications 6.9.1.4, 6.9.1.5, and Regulatory Guide 1.16 under Docket Number 50/395 and Facility Operating License NPF-12.

Document Control Desk Attachment L-99-0107 RC-06-055 Page 3 of 10 TABLE OF CONTENTS SECTION TITLE PAGE 1.0 Introduction 4 2.0 Operational Data 4 3.0 Operating Summary 4 4.0 Exposures 7 5.0 Failed Fuel 7 ATTACHMENTS

1. 2005 Man-Rem Report 9

Document Control Desk Attachment L-99-0107 RC-06-055 Page 4 of 10 ANNUAL OPERATING REPORT

1.0 INTRODUCTION

The Virgil C. Summer Nuclear Station (VCSNS) utilizes a pressurized water reactor rated at 2900 MWT. 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, 2005, the station operated at a capacity factor of 88.3 % (using maximum dependable capacity) and a unit availability of 88.4 %. The reactor was critical for a total of 7787.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, the generator remained on line 7746.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br />, and the total gross electrical energy generated for 2005 was 7,774,380 MWH.

3.0 OPERATING

SUMMARY

The Virgil C. Summer Nuclear Station (VCSNS) Unit No.1 operated at 100

% power from January Ist, through March 1st. On March 1st, power was reduced to 95% during the repair of the back-up computer in the heater drain level control system. The power reduction provided "reactivity management" margin in the unlikely event that both heater drain control processors failed. Power was restored to 100% at 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> on March 3rd.

3.

VCSNS operated at 100% power from March 3rd to April 17 th. As part of a pre-planned power reduction in preparation for Refueling Outage Fifteen (RF-15), power was reduced to 90% on April 17th to support maintenance on the "C" Main Feedwater Pump Turbine. Power was further reduced to 80% on April 21 't and on April 23rd the refueling outage began with the opening of the Main Generator breaker. The plant remained shutdown for the refueling outage until June 1 st when the Main Generator breaker was closed. Reactor power was restored to 100% on -June 7 th

Document Control Desk Attachment L-99-0107 RC-06-055 Page 5 of 10 VCSNS operated at 100 % power from June 7th to July 27th. On July 27th power was reduced to 85% due to the failure of the "B" Circulating Water Pump Motor. The pump was repaired and reactor power was restored to th 100% at 2003 hours0.0232 days <br />0.556 hours <br />0.00331 weeks <br />7.621415e-4 months <br /> on August 13 VCSNS operated at 100% power from August 13th to August 25tt. On August 25 ,the plant experienced a reactor trip following the failure of the 1B" Condensate Pump Motor. The trip occurred due to the slow operation of the discharge isolation valve for the standby UA' Condensate Pump resulting in a secondary side transient. Reactor power was restored to 100% at 1800 hours0.0208 days <br />0.5 hours <br />0.00298 weeks <br />6.849e-4 months <br /> on August 28th*

VCSNS operated at 100% power from August 28th to September 27 h. On September 27th, power was reduced to 87% when the "C" Main Feedwater Pump tripped due to the failure of the pump speed control. The 'C" Main Feedwater Pump controller and flow control valve were repaired and reactor power was restored to 100% on September 2 8 1h.

VCSNS operated at 100% power from September 28th to October 28th. On October 28 th , power was reduced to 93.5% to repair an air leak in the level control system for the 1A Feedwater Heater. Power was restored to 100%

at 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> on October 29'.

VCSNS operated at 100% from October' 29th to November 8th On November 8 h, power was reduced to 80% due to a level fluctuation in the 1A Feedwater Heater. Repairs were completed and power was restored to 100% on November 9 th.

The plant operated at 100% for the remainder of 2005.

Refueling Outage 15 Summary The Main Generator breaker was opened at 0007 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> on April 23rd for Refueling Outage 15.

Major work included:

  • Modification of Refueling Water Storage Tank (RWST) Automatic Swap- over to Cold Leg Recirculation
  • Modification of the Pressure Relief/Component Cooling Water (CCW) Cross-Train Isolation Valve

Document Control Desk Attachment L-99-0107 RC-06-055 Page 6 of 10

  • Relocation of Suction Tap to RMA-9 (Condenser Offgas Radiation Monitor)
  • Replacement of the Integrated Plant Computer System
  • Installation of Reactor Vessel Fluence Monitor
  • Rewind of Main Generator
  • Main Feedwater Flow Control Piping Upgrade Cycle-1 6 Core Design
  • Identification of Failed Fuel Refueling Outage 15 duration was 39.9 days. Outage planned duration was 35 days. Personnel exposure in 2005 due to the outage was 65.3 rem based on thermoluminescent dosimeters (TLDs).

Forced Power Reduction >20% Exceeding 4 Hours On August 25 t, the "B" Condensate Pump tripped and "A" Condensate Pump was started immediately. The "A"Condensate Pump discharge valve was slow to respond to the open signal resulting in a decreasing Deaerator level. This resulted in a reactor trip. The event was reported in Licensee Event Report 2005-003 submitted on October 24, 2005. The cause of the trip of "B"Condensate Pump was determined to be a phase to ground short in the motor windings. A root cause analysis is being performed to determine the cause of the "A" Condensate Pump discharge valve failure to open in a timely manner. This root cause will be completed during Refueling Outage 16 when plant conditions will allow completion of confirmatory tests. Interim measures are in place to eliminate the concern.

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 outage was approximately 54 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br />.

Document Control Desk Attachment L-99-01 07 RC-06-055 Page 7 of 10 Safety-related work performed during this forced outage included:

Repack of 'C" Steam Generator Turbine Driven Emergency Feedwater Pump Control Valve Repair of Intermediate Range NI 36 Channel 2

  • Repair of Reactor Coolant Loop "B"Standpipe Isolation Valve 4.0 EXPOSURES Attachment I consists of tables, which list 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 have indications of failed fuel in 2005.

The reactor coolant system specific activity did not exceed the 1.0 microcuries per gram dose equivalent iodine-131 specific activity or the 100/E microcuries per gram limits of Technical Specification 3.4.8, for this reporting period. VCSNS imposed an administrative limit for reactor coolant system specific activity of 0.059 microcuries per gram dose equivalent iodine-1 31. This limit was not exceeded during 2005.

Document Control Desk Attachment L-99-01 07 RC-06-055 Page 8 of 10 ATTACHMENT I TO 2005 ANNUAL REPORT

Document Control Desk Attachment L-99-01 07 RC-06-055 Page 9 of 10 SOUTH CAROLINA ELECTRIC AND GAS CO. V.C. SUMMER NUCLEAR STATION PEOPLE COMPUTERIZED EXPOSURE NUCLEAR TRACKING SYSTEM PAGE I CNTRPTPERG116R 31-JAN-2006 07:23 PERSONNEL AND MAN-REM BY WORK AND DUTY FUNCTION FINAL END OF YEAR REPORT FOR 2005 NUMBER OF PERSONNEL OVER 100mREM TOTAL MAN-REM STATION UTILITY CONTRACT STATION UTILITY CONTRACT WORK AND JOB FUNCTION WORKERS WORKERS WORKERS WORKERS WORKERS WORKERS ROUTINE MAINTENANCE MAINTENANCE PERSONNEL 17 0 59 5.693 0.002 22.391 OPERATIONS PERSONNEL 1 0 1 0.925 0.000 0.443 HEALTH PHYSICS PERSONNEL 4 0 1 1.253 0.000 1.062 SUPERVISORY PERSONNEL 0 0 0 0.182 0.000 0.011 ENGINEERING PERSONNEL 0 0 0 0.276 0.000 0.455 SPECIAL MAINTENANCE MAINTENANCE PERSONNEL 17 0 61 5.181 0.000 19.853 OPERATIONS PERSONNEL 6 0 5 1.245 0.000 1.207 HEALTH PHYSICS PERSONNEL 8 0 5. 1.674 0.000 1.357 SUPERVISORY PERSONNEL 1 0 0 0.443 0.000 0.003 ENGINEERING PERSONNEL 0 0 3 0.127 0.000 1.323 REACTOR OPERATIONS & SURVEILLANCE MAINTENANCE PERSONNEL 4 0 6 1.308 0.000 1.673 OPERATIONS PERSONNEL 3 0 0 1.109 0.000 0.155 HEALTH PHYSICS PERSONNEL 0 0 1 0.397 0.000 0.530 SUPERVISORY PERSONNEL 0 0 0 0.045 0.000 0.001 ENGINEERING PERSONNEL 0 0 0 0.033 0.000 0.008 WASTE PROCESSING MAINTENANCE PERSONNEL 0 0 0 0.051 0.000 0.071 OPERATIONS PERSONNEL 0 0 0 0.000 0.000 0.003 HEALTH PHYSICS PERSONNEL 4 0 1 0.555 0.000 0.186 SUPERVISORY PERSONNEL 0 0 0 0.068 0.000 0.000 ENGINEERING PERSONNEL 0 0 0 0.001 0.000 0.000 IN-SERVICE INSPECTION MAINTENANCE PERSONNEL 2 0 31 0.454 0.000 7.085 OPERATIONS PERSONNEL 1 0 0 0.492 0.000 0.012 HEALTH PHYSICS PERSONNEL 0 0 2 0.056 0.000 0.554 SUPERVISORY PERSONNEL 0 0 0 0.000 0.000 0.000 ENGINEERING PERSONNEL 0 0 0 0.000 0.000 0.129 REFUELING MAINTENANCE PERSONNEL 1 0 28 0.474 0.000 7.350 OPERATIONS PERSONNEL 0 0 0 0.134 0.000 0.000 HEALTH PHYSICS PERSONNEL 0 0 0 0.094 0.000 0.157 SUPERVISORY PERSONNEL 0 0 0 0.004 0.000 0.001 ENGINEERING PERSONNEL 0 0 1 0.024 0.000 0.369

Document Control Desk Attachment L-99-0107 RC-06-055 Page 10 of 10 TOTALS MAINTENANCE PERSONNEL 41 0 185 13.161 0.002 58.423 OPERATIONS PERSONNEL 11 0 6 3.905 0.000 1.820 HEALTH PHYSICS PERSONNEL 16 0 10 4.029 0.000 3.846 SUPERVISORY PERSONNEL 1 0 0 0.742 0.000 0.016 ENGINEERING PERSONNEL 0 0 4 0.461 0.000 2.284 GRAND TOTAL 69 0 205 22.298 0.002 66.389

  • END OF REPORT *
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