RC-98-0060, VC Summer Nuclear Station 1997 Annual Operating Rept
| ML20217J593 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 12/31/1997 |
| From: | Gabe Taylor SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| RC-98-0060, RC-98-60, NUDOCS 9804060332 | |
| Download: ML20217J593 (12) | |
Text
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j _e C olina Electric & G:s Company ry J.T;
% Jenkinsville. Sc 29065 Nuclear Operations (803) 345 4344 f
i NM Ascatuomm' l
March 27, 1998 RC-98-0060 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
Dear Gentlemen:
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Subject:
VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 OPERATING LICENSE NO. NPF-12 ANNUAL OPERATING REPORT Enclosed is the 1997 Annual Operating Report for the South Carolina Electric & Gas l
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.
Very tr yours, l Gary . y 9
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sbr /GJT I
Attachment c: J. L. Skolds W. F. Conway R. R. Mahan (w/o attachments) R. J. White L.A.Reyes L. M. Padovan i Mary L. Thomas (NRC) J. B. Knotts Jr. ,
! D. L. Abstance Charleen T. Raddatz W. G. Wendland Marsh & McLennan i NRC Res': dent inspector RTS (ANN 2800)
NSRC 'l j
~/ l File (813.02-10)
DMS (98-0060)
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9804060332 971231 PDR ADOCK 05000395 R PDR NUCLEAR EXCELLENCE - A SUMMER TRADITIONI
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1997 ANNUAL OPERATING REPORT
PREFACE The 1997 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.
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TABLE OF CONTENTS i
SECTION TITLE PAGE I 1.0 Introduction -1
, 2.0 Operational Data 2 3.0 Operating Summary 3 4.0 Exposures 4 l
5.0 Failed Fuel 5 I
l j' ATTACHMENTS
! l.' Outages or Power Reductions Caused by Maintenance Activities l'
II. 1997 Man-Rem Report l
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' l ANNUAL OPERATING REPORT l
1.0 INTRODUCTION
The Virgil C. Summer Nuclear Station (VCSNS) utilizes a pressurized water reactor rated at 2900 MWT. The maximum dependable capacity is 954 Mwe.
The station is located approximately 26 miles northwest of Columbia, South Carolina.
! 2.0 OPERATIONAL DATA l I For the reporting period of January 1 through December 31,1997, the station operated at a capacity factor of 87.5 percent (using maximum dependable capacity) and a unit availability of 89.1 percent. The reactor was critical for a
, total of 7870.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, the generator remained on line 7806.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />, and the total l gross electrical energy generated for 1997 was 7,560,230 MWH.
1 On August 20th, VCSNS began using a leading edge flow meter to determine the value of feedwater flow rate used by the station's calorimetric computer l program. This resulted in an increase in indicated core thermal power from 2868 j MWth to 2897 Mwth which is within the licensed value of 2900 MWth. The 1 increase in electrical power was 9.0 Mwe.
I- The station successfully completed its tenth refueling outage in 34 days 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.
3.0 OPERATING
SUMMARY
The Virgil C. Summer Nuclear Station (VCSNS) Unit No.1 operated at 100 percent power until January 5th, when a power reduction began to support
,, repairs to a casing leak on the 'D' feedwater booster pump. Power was reduced
! to 95 percent. Power escalation began on January 8th and reached 100 percent on January 10th.
VCSNS operated at 100 percent from January 10 through April 17th. On April
.17th the plant was dorated to 90 percent to repair a main turbine control valve pressure switch. On April 22nd, the reactor was manually tripped due to a large EHC leak. The reactor was taken critical on April 25th and the main generator breaker was closed on April 26th. During power escalation and station load on April 26th, a feedwater flow transient caused a. turbine trip on hi hi steam generator level followed by a reactor trip due to lo-lo steam generator level. On April 28th the reactor went critical and the main generator breaker was closed.
On May 1st,100 percent power was reached.
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Annual Operating Report ;
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VCSNS operated at 100 percent power from May 1st until May 30th, when power !
was reduced to 85 percent to support scheduled maintenance on the 'C' main feedwater pump _ seals and the' main voltage regulator. Power was returned to j
- 100 percent on June 2nd. !
VCSNS operated at 100 percent power from June 2nd until September 21st ;
when the plant was dorated to 95 percent power to support planned Moisture !
Separator Reheaters (MSR) thermal performance testing. On September 26th, a planned power coastdown began in preparation for the tenth refueling outage.
The main generator breaker was opened on October 4th.
On November 5th the reactor was taken critical. The main generator breaker was closed on November 7th ending the tenth refueling outage.100 percent i power was reached on November 15th.
The station operated at 100 percent power until December 3rd. A power reduction was made to perform seal repairs on 'A' and 'B' main feedwater i pumps. On December 6th power was reduced to 40 percent to isolate one loop !
of condenser cooling water to support condenser leak detection and repair. On December 8th power was restored to 100 percent. The station operated at 100 ;
percent fer the remainder of 1997.
Maintenance Attachment I, " Power Reductions Caused by Maintenance Activities," provides more detailed information on operating time lost as a result of maintenance l activities.
Refuel 10 Summary The main generator breaker was opened at 0130 on October 4,1997 for
.refueling ou tage 10.
During the outage personnel radiation exposure was much higher than anticipated due to an unexpected precipitation of contamination within piping systems and due to additional work performed on snubbers. The exposure accumulated by personnel for the refueling outage was 170 man rem. !
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Annual Operating Report
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Major accomplishments during the outage include:
A. Completed thermolag removal modification. Completion of this modification resolves all thermolag issues at the VCSNS.
B. Completed major maintenance of "A" and "B" Diesel Generators. ;
C. Swapped out "C" Reactor Coolant Pump with a reworked spare.
D. Completed eddy current inspections of "C" Steam Generator (30%)
E. Performed inspections of other heat exchangers in the plant.
F. Made numerous repairs to primary and secondary plant equipment.
G. Completed snubber reduction effort (363 snubbers removed), functionally tested 411 snubbers and replaced 42 (11%) degraded snubbers and 20 (7%)
failed snubbers. !
H. Performed motor operated valve testing; 27 static tests and 3 DP tests.
- l. Completed upgrade of the Fuel Handling Manipulator Crane inside the j reactor building. '
J. Replaced reactor coolant pump seal injection filter isolation valvss. i K. Completed 29 modifications.
. The L mn generator breaker was closed on November 7,1997 at 0630. The total time of the refueling outage was 34 days and 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />. This was the shortest duration refueling outage to date.
No significant nuclear safety challenges occurred during RF-10. Outage Management stressed nuclear safety as the highest priority and strongly supported the defense-in-depth outage safety philosophy.
The excellence in RF-10 nuclear safety performance can be attributed to:
- 1. Pre-planning safety into the outage schedule.
- 2. Cooperation between the applicable work groups.-
- 3. The effective use of Shift Engineers (Licensed Senior Reactor Operators) as Window Managers controlling specific work areas.
- 4. A safety minded philosophy stressed by Senior Management that carried over into worker implementation.
- 5. Independent Safety Engineering Group (!SEG) 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on-site coverage including the startup through 100% Power Pitysics Testing.
- 6. Use of Industry Operating Experience.
i Annual Operating Report 1 Page 4 of 4 l l
l 4.0 -EXPOSURES i l
Attachment ll consists of tables which list the number of station, utility, and other !
l personnel (including contract personnel) receiving exposures greater than 100 ;
mrom/ year and their associated man-rem exposure according to work and job function. l I
5.0 FAILED FUEL VCSNS has not had indication of failed fuel in 1997.
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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 penod. i l
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l ATTACHMENT 11 TO 1997 ANNUAL REPORT
. SOUTH CAROLINA ELECTRIC AND GAS CO. V.C. SUMMER NUCLEAR STATION PEOPLE COMPUTERIZED EXPOSURE NUCLEAR TRACKING SYSTEM PAGE 1 CNTRPT PERG116R
- 28-JAN-1998 11:27 PERSONNEL AND MAN-REM BY WORK AND DUTY FUNCTION FINAL END OF YEAR REPORT FOR 1997 NUMBER OF PERSONNEL OVER 100 MREM TOTAL MAN-REM STATION UTILITY CONTRACT STATION UTILITY CONTRACT WORK AND JOB FUNCTION WORKERS WORKERS WORKERS WORKERS WORKERS WORKERS ROUTINE MAINTENANCE MAINTENANCE PERSONNEL 53 4 219 15.774 1.099 69.901 OPERATIONS PERSONNEL 18 0 32 4.599 0.000 8.587 HEALTH PHYSICS PERSONNEL 9 0 35 3.826 0.000 10.459 SUPERVISORY PERSONNEL 3 0 0 0.816 0.000 0.010 ENGINEERING PERSONNEL 3 0 9 1.024 0.000 3.048 SPECIAL MAINTENANCE MAINTENANCE PERSONNEL 1 2 8 1.194 0.228 3.946 OPERATIONS PERSONNEL 0 0 0 0.092 0.000 0.056 HEALTH PHYSICS PERSONNEL 0 0 2 0.177 0.000 0.484 SUPERVISORY PERSONNEL 1 0 0 0.932 0.000 0.000 ENGINEERING PERSONNEL 0 0 0 0.030 0.000 0.035 REACTOR OPERATIONS & SURVEILLANCE MAINTENANCE PERSONNEL 3 0 11 1.569 0.000 4.307 OPERATIONS PERSONNEL 29 0 4 6.535 0.000 1.527 ,
HEALTH PHYSICS PERSONNEL 9 0 22 3.063 0.000 5.890 )
SUPERVISORY PERSONNEL 0 0 0 0.303 0.000 0.027 '
ENGINEERING PERSONNEL 0 0 1 0.216 0.000 0.171 WASTE PROCESSING MAINTENANCE PERSONNEL 0 0 1 0.278 0.000 0.228 OPERATIONS PERSONNEL 0 0 0 0.015 0.000 0.025 HEALTH PHYSICS PERSONNEL 7 0 1 3.763 0.000 0.458 SUPERVISORY PERSONNEL 0 0 0 0.062 0.000 0.000 l ENGINEERING PERSONNEL 0 0 0 0.000 0.000 0.000 !
IN-SERVICE INSPECTION MAINTENANCE PERSONNEL 2 0 36 0.452 0.000 12.682 l OPERATIONS PERSONNEL 2 0 11 0.587 0.000 2.227 HEALTH PHYSICS PERSONNEL 0 0 2 0.015 0.000 0.422 SUPERVISORY PERSONNEL 0 0 0 0.000 0.000 0.000 ENGINEERING PERSONNEL 0 0 1 0.008 0.000 0.324 REFUELING MAINTENANCE PERSONNEL 6 0 20 1.638 0.000 6.702 OPERATIONS PERSONNEL 1 0 8 0.707 0.000 4.110 HEALTH PHYSICS PERSONNEL 0 0 4 0.110 0.000 1.228 SUPERVISORY PERSONNEL 0 0 0 0.052 0.000 0.000 ENGINEERING PERSONNEL 0 0 3 0.071 0.000 1.607 TOTALS MAINTENANCE PERSONNEL 65 6 295 20.905 1.327 97.766 .
OPERATIONS PERSONNEL 50 0 55 12.535 0.000 16.532 HEALTH PHYSICS PERSONNEL 25 0 66 10.954 0.000 18.941 SUPERVISORY PERSONNEL 4 0 0 2.165 0.000 0.037 ENGINEERING PERSONNEL 3 0 14 1.349 0.000 5.185 GRAND TOTAL 147 6 430 47.908 1.327 138.461
- END OF REPORT ***********