ML20070G301

1990 Annual Operating Rept for VC Summer Nuclear Station, Unit 1

ML20070G301
Person / Time
Site:	Summer
Issue date:	12/31/1990
From:	Skolds J SOUTH CAROLINA ELECTRIC & GAS CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
NUDOCS 9103110386
Download: ML20070G301 (11)

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Mr. S. D. Ebneter Regional Administrator V. S. Nuclear Regulatory Commission Region II, Suite 2900 101 Marietta Street, N. W.

Atlanta, Georgia 30323

Subject:

VIRGIL C. SUMMER ;1UCLEAR STATION DOCKET NO. 50/395 OPERATING LICENSE NO. NPF-12 ANNUAL OPERATING REPORT Attached is the 1990 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 Tachnical 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.

John L. Skolds DCH:JLS:mtm Attachment c:

0. W. Dixon Jr. (w/o attachments)

R. R. Mahan (w/o attachments)

R. J. White General Managers G. F. Wunder J. 8. Knotts Jr.

NRC Resident Inspector NSRC RTS (ANN 2800)

File (818.02-10)

ANI Library NUCLEAR EXCELLENCE - A SUMMER TRADITION!

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1990 ANNUAL OPERATING REPORT I

1 VIRGlt C. SUMMER NUCLEAR STATION I

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16.BLE OF CONTENTS SECTION TITLE PAGE 1.0 Introduction 1

2.0 Highlights 1

3.0 Scheduled or Forced Power Reduction Summaries 1

4.0 Exposures 5

5.0 Failed fuel 5

ATTACHMENTS 1.

1990 Man-Rem Report II.

Specific Activity Graphs

PREFACE The 1990 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.

1 l

1.0 INTRODUCTION

I The Virgil C. Summer Nuclear Station (VCSNS) utilizes a pressurized water reactor rated at 2775 MWt. The unit produces a maximum dependable capacity of 885 MWe net of electrical power. The plant is located approximately 26 miles northwest of Columbia, South Carolina, i

2.0 HIGHLIGHTS I

for the reporting period of January 1 through December 31, 1990, the plant operated at a capacity factor of 78.8% (using maximum dependable capacity) and a unit availability of 82.9%.

It is important to note that, excluding the refueling outage, the unit availability for the t

year was 99.6%, and the capacity factor for the year was 95%. The reactor was critical for a total of 7,346.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, the generator remained on-line for a total of 7.262.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, and the total gross electrical energy generated for 1990 was 6.395,150 MWh.

i 3.0 SCHEDULED OR FORCED POWER REDUCTION SUMMARIES During the 1990 report period, the plant experienced no forced and four scheduled power reductions of greater than 20% of design power which exceeded four hours in duration.

Included in these power reductions is one outage, which was the fifth refueling outage.

1.

Power was reduced on March 20, 1990, to allow pre-outage testing of the Main Steam Safety Valves.

Power was reduced further on March 23 to enter into the fifth refueling outage. The generator was taken off-line at 2325 hours0.0269 days <br />0.646 hours <br />0.00384 weeks <br />8.846625e-4 months <br /> on March 23, and Mode 3 was i

entered on March 24 at 0205 hours0.00237 days <br />0.0569 hours <br />3.38955e-4 weeks <br />7.80025e-5 months <br />. The outage was completed on May 24, 1990, at 0640 hours0.00741 days <br />0.178 hours <br />0.00106 weeks <br />2.4352e-4 months <br /> (approximately 62 days) when the generator output breaker was clostd. The plant reached 100%

l power at 1345 on May 31. The following is a summary of major safety related corrective maintenance performed during the outage.

Ma.ior Task Work list l

A.

Mechanical Work Activities 1.

Reactor Coolant Pump "A" Seal inspection 2.

Reactor Coolant Pump "B" Seal inspection 3.

Turbine Overhaul B Low Pressure (LP) l 4.

Valve repacks and grooming PMs i

5.

System A H (HVAC) filter Surveillance Test Procedures (STPs) i 6.

Mechanical corrective maintenance 7.

IS! valve inspections 8.

An LP turbine last stage visual inspection 9.

Diesel generator A and B overhaul and STPs i

l Page 1 of 5

B.

Electrical Work Activities 1.

Breaker STPs and PMs 2.

Electrical corrective maintenance 3.

Electrical modifications 4.

Mai' Cenerator 5.

CQ inspection tasks 6.

Reactor coolant pump "B" motor inspection 7.

MOVATS C.

I&C Work Activities 1.

Instrument STPs & PMs 2.

EQ inspection and replacement 3.

Instrument corrective maintenance 4.

Instrument modifications 5.

Calibration and functional retests for modifications 6.

Guide thimhle cleaning 0.

Quality Control Work Activities 1.

Snubber STPs 2.

ISI Hanger inspections 3.

ISI weld inspections 4.

BOP Pipe thinning inspections 5.

BOP eddy current inspections 6.

Raw water "MIC" inspections 7.

Safety and quality related work inspections B.

Steam Generator Tech Spec eddy current testing 9.

Flux thimble eddy current

10. Reactor Building tendon inspections 11.

"B" RCP flywheel inspections 12.

Reactor vessel inspection Steam Generator Work As reported in LER 90-005, the results of the fifth inservice eddy current examination of the Virgil C.

Summer Nuclear Station steam generators were completed during the outage.

The results indicated that more than 1% of the inspected tubes in each steam generator were defective, a C-3 inspection category per Technical Specification 4.4.5.2.

When each steam generator entered Category C-3, a prompt notification was made to the NRC Operations Center per the requirements of Technical Specification 4.4.5.5 and 10CFR50.72(b)(2)(i).

Page 2 of 5

The following is a summary of S/G activities which were implemented during RF5.

Code Eddy Current S/G 'A' 4394 Tubes Inspected S/G 'B' 4167 Tubes inspected S/G 'C' 4370 Tubes Inspected RPC Inspection S/G 'A' 40 Tubes Inspected S/G 'B' 60 Tubes Inspected S/G 'C' 40 Tubes Inspected Note:

A sample RPC inspection was performed to satisfy in-house requirements.

Rolled Plua insDection S/G ' A' H/L 275 Plugs S/G 'A' C/L 19 Plugs S/G 'B' H/L 394 Plugs S/G 'B' C/L 41 Plugs S/G 'C' H/L 300 Plugs S/G 'C' C/L 136 Plugs Ro] led Plua Removal S/G 'A' No Plugs removed in H/L or C/L S/G 'B' H/L 34 Plugs S/G 'B' C/L 0 Plugs S/G 'C' H/L 9 Plugs S/G 'C' C/L 4 Plugs Rolled Plua Installation S/G 'A' H/L 88 Plugs S/G 'A' C/L 88 Plugs S/G 'B' H/L 110 Plugs S/G 'B' C/L 110 Plugs S/G 'C' H/L 81 Plugs S/G 'C' C/L 81 Plugs Note:

Above totals do not include tubes which were replugged after having cracked plugs removed.

Plua-A-Plua (PAP) Installation S/G 'A' H/L 5 Plugs Installed S/G 'B' H/L 111 Plugs Installed, S/G 'C' H/L 2 Plugs Installed Note:

PAPS were installed in Westinghouse ribbed plugs.

Page 3 of 5 1

Tube Sleevinq Installation S/G 'A' H/L 76 Sleeves Installed S/G 'B' H/L 50 Sleeves Installed Note:

One sleeve out of fifty installed in S/G

'B' was plugged as a result of NDE inspection.

Tube U-Bend Stabilization S/G 'A' 1 Tube Stabilized S/G 'B' 1 Tube Stabilized S/G 'C' 5 Tubes Stabilized in addition to the above activities, the following were also implemented:

a.

FOSAR (Foreign Object Search and Retrieval) was performed on the secondary side of 'C' S/G.

b.

Tube sheet photography was performed in l

all three S/G's.

2.

A slight misalignment in the coupling between the alterex and generator shaft was responsible for " higher than normal" vibration readings. The piant entered a scheduled generator outage at 2010 hours0.0233 days <br />0.558 hours <br />0.00332 weeks <br />7.64805e-4 months <br /> on July 6, 1990, to correct the misalignment. The generator was off-line for approximately 28 hours3.240741e-4 days <br />0.00778 hours <br />4.62963e-5 weeks <br />1.0654e-5 months <br /> and the plant was returned to 100% power at 1800 hours0.0208 days <br />0.5 hours <br />0.00298 weeks <br />6.849e-4 months <br /> on July 9.

The maintenance successfully lowered the vibrations to within the normal range.

l 3.

On November 2, 1990, a scheduled power reduction to 30% power was initiated at 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br />.

The power reduction allowed the repair of leaking tubes in the stator cooling heat exchangers. Also, while the plant was at reduced power, a containment entry was made to replace a reactor coolant drain tank pump. Work was completed, and full power operations was resumed at 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> on November 4.

l Page 4 of 5

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4 The plant had experienced an extremely high capacity factor (96.4% using maximum dependable capacity) since completing the fifth refueling outage.

if this level of performance were to continue, the burnup o' this fuel cycle would not allow full power operation during the demands of the upcoming summer seasonal loads, lherefore, a scheduled power reduction to 47:

reactor power was initiated at 1330 on December 18, 1990, to conserve fuel.

This should allow the plant to maintain full power conditions through the summer of 1991.

The power reduction was maintained through the remainder of the month of December.

4.0 EXPOSURES Attachment I provides a table which lists the number of station, utility, and other personnel (including contract personnel) receiving exposures greater than 100 mrem in 1990 and their associated man-rem exposure according to work and job functions.

5.0 FAltED FUEL The specific activity of the primary coolant remained within the limits (1.0 microcurie per gram Dose Equivalent 1-131) of Technical Specification 3.4.8, " Specific Activity," except for one occasion where the limit was slightly exceeded following the reactor power reduction to enter Refueling Outage 5.

)

On March 24, 1990, at 0205 hours0.00237 days <br />0.0569 hours <br />3.38955e-4 weeks <br />7.80025e-5 months <br />, Dose Equivalent I-131 exceeded Technical Specificatirn limits.

The results of isotopic analyses for samples taken prior, during, and after the Occurrence were:

March 23 at 0815 hours0.00943 days <br />0.226 hours <br />0.00135 weeks <br />3.101075e-4 months <br /> - 2.76E-2 UCi/gm March 24 at 0205 hours0.00237 days <br />0.0569 hours <br />3.38955e-4 weeks <br />7.80025e-5 months <br /> - 1.11 uCi/gm March 24 at 0625 hours0.00723 days <br />0.174 hours <br />0.00103 weeks <br />2.378125e-4 months <br /> - 7.35E-1 uCi/gm Based on sampling results, the duration of the occurrence was 3.5

hours, in the 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded, letdown flow remained constant at a flow rate of 100 gpm.

Also, reactor power was reduced to approximately 85% on March 21, then returned to approximately 100% on March 23. Attachment 11 provides a graph showing the reactor power and activity levels for 1-131, 1-133, and 1-134 as a function of time.

Page 5 of 5

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Attacbent 1 to Mr. S. D. Ebneter Letter Page 1 of 1 1990 Annual Report SOUTH CAROLINA ELECTRIC & GAS COMPANY V. C. SUMMER NUCLEAR STATION 1990 MAN REM REPORT FOR PERSONNEL EXPOSURE GREATER THAN 100 MREM NUMBER OF P*RSONNEL > 100 MREM TOTAL MAN REM WORK AND JOB FUNCTION STATION UTILITY CONTRACT STATION UTILITY CONTRACT Reactor Operations & Surveillance Maintenance Personnel 7

0 3

2.150 0.000 2 440 Operating Personnel 35 0

1 9.695 0.010 1.005 Health Physics Personnel 8

0 35 2 485 0.000 10 965 Supervisory Personnel 0

0 1

0 810 0.000 0.190 Engineering Personnel 1

4 0.370 0.000 1.285 Routine Maintenance Maintenance Personnel 17 0

43 5.780 0.000 15.430 Operating Personnel 1

2 9

1087 0 415 2.910 Health Physics Personnel 2

0 40 0 555 0.000 14.670 Supervisory Personnel 0

0 0

0.405 0.000 0.040 Engineering Personnel 0

0 1

0.290 0 000 0.850 Inservice Inspection Maintenance Personnel 4

0 45 1.520 0.000 11.675 Operating Personnel 7

0 4

2.365 0.000 1.505 Health Physics Personnel 0

0 5

0.175 0.000 2.360 Supervisory Personnel 0

0 0

0.015 0.000 0.100 Engineering Personne!

0 0

2 0.000 0 000 0.685 Special Maintenance Maintenance Personnel 39 0

234 14.300 0.000 134.170 Operating Personnel 15 1

18 4.625 0.500 4.550 Health Physics Personnel 5

0 102 1.745 0.000 40 915 Supervisory Personnel 2

0 0

1.485 0.000 4.000 Engineering Personnel 5

0 110 1.385 0.000 63.140 Waste Processino Maintenance Personnel 39 0

1 0.140 0.000 0.425 Operating Personnel 15 0

0 0.030 0.025 0.465 Health Physics Personnel 5

0 1

0.755 0.000 1.025 Supervisory Personnel 2

0 0

0.005 0 000 0 000 Engineering Personnel 5

0 0

0.010 0.000 0.000 Refuelina Maintenance Personnel 0

0 29 3.060 0.000 10 050 Operating Personnel 0

0 2

1.045 0.030 1.170 Health Physics Personnel 3

0 28 0.960 0.000 8.985 Supervisory Personnel 0

0 0

0.200 0.000 0.000 Engineering Personnel 0

0 16 0.085 0.000 16.880 TOTALS Maintenance Personnel 76 0

355 26.950 0.000 174.190 Operating Personnel 60 3

34 18.847 0.980 11.605 Health Physics Personnel 21 0

211 6.675 0.000 78.920 Supervisory Personnel 2

0 1

2.920 0.000 0.330 Engineering Personnel 6

0 133 2.140 0.000 82.840 GRAND TOTAL 165 3

734 57 532 0.980 347.885 The above whole body dose assignments are based on pocket dosimeter estimates

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