RC-95-0057, Annual Operating Rept for 1994 for VC Summer Nuclear Station Unit 1

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Annual Operating Rept for 1994 for VC Summer Nuclear Station Unit 1
ML20092H255
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 12/31/1994
From: Gabe Taylor
SOUTH CAROLINA ELECTRIC & GAS CO.
To: Ebneter S
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
RC-95-0057, RC-95-57, NUDOCS 9509200327
Download: ML20092H255 (9)
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So th Car fina Electric & Gas Company G J.T  ;

Jenkinsville, SC 29065 Nua. lear Operations -

, (803) 345-4344 * '

Ascamaxroeny SS MAR '

EPZ Askuary 27, 1995 Refer to: RC-95-0057

- Mr. S. D. Ebneter .

Regional Administrator l U. 5. Nuclear Regulatory Commission l- Region ll, Suite 2900 101 Marietta Street, N. W.

" Atlanta, Georgia 30323

Dear Mr. Ebneter:

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Subject:

VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 OPERATING LICENSE NO. NPF-12

. ANNUALOPERATING REPORT Attached is the 1994 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.

Very truly yours, Ggy . aylor .

Gar RAM /GJT/nkk Attachment c: O. W. Dixon R. R. Mahan (w/o attachments) e R. J. White f G. F. Wunder.

J. B. Knottr Jr.

NRC Resident inspector l' ?NSRC-RTS (ANN 2800)

File (818.02-10)-

Central File System s

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1.0 INTRODUCTION

The -Virgil' C. Summer Nuclear Station (VCSNS) utilizes a pressurized . water reactor rated at 2775 MWT. The unit has produced a maximum dependable capacity (MWe-Net) ' of 885 MWe.

. The - plant is located approximately 26 miles northwest of ,

Columbia, South Carolina.

i 2.O OPERATIONAL DATA.

For the reporting period of January 1 through December 31, 1994, the plant operated at a capacity factor of 57.3 percent

. (using maximum dependable capacity) and a unit availability of 68.8 percent. The reactor was critical for a total of 6090.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />, the generator remained on line 6023.1 huurs, and the total gross electrical energy generated for 1994 was 4,701,600 MWH.

3.0 OPERATING StDe4ARY

.The Virgil C. Summer Nuclear Station Unit No. 1 operated at 300 percent power for the entire month of January and until February 9, when power was reduced to 65% for fuel conservation. The plant operated at 65% power for the rest of I the month. As of the end of February the plant had been on l line continuously for 302 days. This is a new plant record, surpassing the previous record of 279 days.

The plant was taken off line at 1524 hours0.0176 days <br />0.423 hours <br />0.00252 weeks <br />5.79882e-4 months <br /> on March 1, 1994, to repair hydrogen leaks in the main generator. During this outage the "B" reactor coolant pump seal was replaced and work was performed on the reactor building polar crane to support the upcoming refueling 8 outage activities.

On March 18, at 1223 hours0.0142 days <br />0.34 hours <br />0.00202 weeks <br />4.653515e-4 months <br />, the main generator breaker was l closed. Power was maintained at 30% for secondary water chemistry cleanup. On March 21, power was increased to 65% and maintained at that level until April 14, for fuel conservation. On April 14, power was increased to 72% and remained at 72% until May 7, for fuel conservation. On May 7, 4 power was increased to 100%. I On' June 17, power was reduced to 90% to repair an air leak on a high - load steam supply valve to the moisture separator reheater. The plant was returned to. full power ori June 18. As a result of . the power transient, the plant experienced an

increased steam generator leakage rate (primary to secondary) from the "B" steam generator. (See Attachment II for a graph of.the leak.)

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The plant operated at 100% power until July 24, when power was reduced to 90% as part of a strategy to manage the "B" steam generator tube leak and to maintain the circulating water

discharge temperature below the maximum allowable temperature.
The reduced power level also helped to conserve fuel until the
scheduled refueling outage. The "B" steam generator leak rate
was the major plant operational restraint and continued to be
monitored very closely for the rest of the operating cycle.
Contingency plans were developed to address actions to_be taken if the leakage rate was to significantly increase.

The plant continued to operate at 90% power until August 5, when a gradual power reduction was initiated and on August 11, a power level of 80% was established. The power reduction was made in order to further conserve fuel for the remainder of

the operating cycle and to minimize the "B" steam generator tube leak rate.

l On September 9,1994, power was reduced and the main generator taken off line to commence Refueling Outage 8.

Cycle 9 initial criticality was achieved at 1012 hours0.0117 days <br />0.281 hours <br />0.00167 weeks <br />3.85066e-4 months <br /> on

December 14th. Physics testing was ' ampleted at 1047 hours0.0121 days <br />0.291 hours <br />0.00173 weeks <br />3.983835e-4 months <br /> on
the 15th and MODE 1 entered at 2350 hours0.0272 days <br />0.653 hours <br />0.00389 weeks <br />8.94175e-4 months <br />. The generator 4

breaker was closed at 0215 on the 16th. Additional testing was

pe
:ormed during the power ascension due to the steam i ;r* c rator replacement. 100% power was reached on December 29.

At the end of December the plant was operating at 100 percent l

power.

MAINTENANCE l

l During this reporting period 5168 maintenance work requests

(MWR) were completed requiring 183,260 manhours. There were l 10,165 preventive maintenance tasks and 7186 surveillance tests performed.

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REFUEL 8

SUMMARY

This was a planned refueling outage with a scheduled duration of 98 days and 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, with expectation that the main generator breaker would be closed on or before December 17.

During this outage all three Westinghouse model D-3 steam generators were replaced with Westinghouse model Delta 75 steam generators. This required rerouting of the feedwater system piping to the upper portion of the new steam generators

, and removal of the feedwater prewarming system. Changing from a variable water level to a single water level in the new i steam generators resulted in extensive changes to the plant

! instrumentation.

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The combined refueling and steam generator replacement outage  !

was completed in 97 days and 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, breaker to breaker. This I included eight days at the end of the outage to repair a leak on the seal injection line to "C" reactor coolant pump which was discovered on December 13 (LER 940006) during the heatup for plant startup.

The steam generator critical path replacement activities were accomplished.in 38 days. This established a new record for steam generator replacement in the United States. The steam generator replacement activities were accomplished with a total man-rem dose of 224, which also set a new United States record.

In addition to refueling and steam generator replacement the following major work items were completed during the refueling 8 outage:

  • Reactor Building Polar Crane Upgrade Rebuilt the crane's mechanical brake, replaced the main and aux. hoist wire ropes, and performed a required structural modification to resolve a Whiting Corporation 10CFR21 notification.
  • Motor Operated Valve Testing The requirements of Generic Letter 89-10 initial commitments were completed. 48 motor operated valves were refurbished, 56 were dp tested, and 84 were statically tested. This ,

established a new ITI Movats record for the number of valves I worked in a single outage.

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  • On site rewind of the Main Electrical Generator I This was the first on site main generator rewind for a 4 pole unit performed by General Electric. It was also the first time induction heating was used for brazing stator bars in the field.

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  • [Replacemen+ of.two-' Reactor' Coolant Pump Seals  ;

< ._ Replaced;the mechanical. seals on'"A" and'"C": reactor coolant

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t' pumps.s The se'al on "B", . reactor: coolant pump ? was :-replaced

'during.the' plant mini-outage in March.

< 4;O'.- EXPOSURES E Attachment J 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-ren' exposure accorcing to. work'and: job function. .

E

~5 . 0'- FAILED FUEL l

,Following core offload, 'two fuel rods were identified as l

' defective! by., ultrasonic testing and' visual inspection. The

.. defects were . debris - induced. One ' rod in assembly K-46, was  :'

from its' initial cycle in the core and the other in assembly-J-64 was from> its second core cycle. - Assembly K-46 was reconstituted and' loaded for cycle 9 and assembly J-64 was. -

= discharged.

The reactor coolant system specific activity did not exceed the 1.0 uCi/ml dose equivalent iodine-131 specific activity .i

~

' limit for this reporting period.  ;

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ATTACHMENT I TO 1994 N AL REPORT 1

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.- . l SOUTH CAROLINA ELECTRIC AND GAS CO. V.C. SUMMER NUCLEAR STATION PEOPLE . COMPUTERIZED EXPOSURE NUCLEAR TRACKING SYSTEM PAGE 1 j CNTRPT_PERG116R

'15-FEB-1995 09:04 <

PERSONNEL AND MAN-REM BY WORK AND DUTY FUNCTION FINAL END OF YEAR REPORT FOR 1994 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 47 0 146 11.773 0.026 48.736 OPERATIONS PERSONNEL 7 0 9 2.557 0.025 2.487 EEALTH PHYSICS PERSONNEL 6 0 57 1.903 0.000 17.287 SUPERVISORY PERSONNEL 0 0 1 0.290 0.000 0.383 ENGINEERING PERSONNEL 3 0 21 1.430 0.000 6.914 SPECIAL MAINTENANCE MAINTENANCE PERSONNEL 16 0 327 6.054 0.020 146.761 OPERATIONS PERSONNEL 5 0 2 1.675 0.000 0.811 HEALTH PHYSICS PERSONNEL 2 0 3 0.669 0.000 1.880 '

SUPERVISORY PERSONNEL 0 0 2 0.633 0.000 0.755 ENGINEERING PERSONNEL 1 0 104 0.994 0.000 47.135 REACTOR OPERATIONS & SURVEILLANCE 0.000 1.106 MAINTENANCE PERSONNEL 1 0 2 0.632 OPERATIONS PERSONNEL 9 0 1 3.513 0.001 0.402 HEALTH PHYSICS PERSONNEL 6 0 53 2.506 0.000 16.073 SUPERVISORY PERSONNEL 0 0 1 0.126 0.000 0.189 ENGINEERING PERSONNEL 0 0 1 0.102 0.000 0.249 WASTE PROCESSING

, MAINTENANCE PERSONNEL 0 0 0 0.036 0.000 0.158 OPERATIONS PERSONNEL 0 0 0 0.001 0.000 0.179 HEALTH PHYSICS PERSONNEL 3 0 2 0.957 0.000 1.041 SUPERVISORY PERSONNEL 0 0 0 0.000 0.000 0.015 ENGINEERING PERSONNEL 0 0 0 0.000 0.000 0.000 IN-SERVICE INSPECTION MAINTENANCE PERSONNEL 0 0 33 0.170 0.049 9.688

! OPERATIONS PERSONNEL 0 0 0 0.481 0.000 0.094 i

HEALTH PHYSICS PERSONNEL 0 0 0 0.020 0.000 0.206

, SUPERVISORY PERSONNEL 0 0 0 0.046 0.000 0.002 0.323 0.000 5.149 ENGINEERING PERSONNEL 0 0 18 REFUELING FWINTENANCE PERSONNEL 0 0 0 0.021 0.000 0.251 OPERATIONS PERSONNEL 0 0 0 0.085 0.000 0.108

' HEALTH PHYSICS PERSONNEL 0 0 0 0.000 0.000 0.119 SUPERVISORY PERSONNEL 0 0 0 0.000 0.000 0.000 ENGINEERING PERSONNEL 0 0 1 0.007 0.000 0.301 i

TOTALS

! MAINTENANCE PERSONNEL 64 0 508 18.686 0.095 206.700 OPERATIONS PERSONNEL 21 0 12 8.312 0.026 4.081 REALTH PHYSICS PERSONNEL 17 0 115 6.055 ~0.000 36.606 SUPERVISORY PERSONNEL 0 0 4 1.095 0.000 1.344 ENGINEERING PERSONNEL 4 0 145 2.856 0.000 59.748 L GRAND TOTAL 106 0 784 37.004 0.121 308.479

                      • END OF REPORT ***********

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d 4 ATTACHMENT II TO 1994 ANNUAL REPORT a

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