1987 ANNUAL OPERATING REPORT

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PREFACE-

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The 1987 Annual Operating. Report for the Virgil C. Summer Nuclear Station ishereby 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 FacilityOperating License HPF-12.

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- *: TABLE OF CONTENTS

:3 :- SECTION TITLE PAGE,

1.0 Introduction 1

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2.0 Highlights 1,

3.0' Scheduled or Forced Power Reduction Sumaries 1

4.0- Exposures 5

5.0 Failed Fuel 5 ,

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ATTACHMENTS,

I. 1987 Man-Rem Report,

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'1. 0 INTRODUCTION

The Virgil C. Summer Nuclear Station utilizes a pressurized waterreactor rated at 2775 MWt. The turbine generator is capable ofproducing approximately 885 MWe net (approximately 900 MWe gross) ofelectrical power. The plant is located approximately 26 milesnorthwest of_ Columbia, South Carolina.

2.0 HIGHLIGHTS

For the reporting period of January 1 through December 31,1987 theplant operated at a capacity factor of 66.5% and a unit availabilityof 70.1%. The reactor was critical for a total of 6.222.4 hours, thegenerator remained on-line for a total of 6,136.9 hours, and the totalgross electrical energy generated for 1987 was 5,419,990 MWh.

3.0 SCHEDULED OR FORCED POWER REDUCTION SUMMARIES

During the 1987 report period the plant experienced one scheduled andseven forced power reductions of greater than 20% which exceeded fourhours in duration. The plant experienced five reactor trips.

A. On January 3,1987, at 0532 hours, a forced power redti,t'on from100% was initiated due to an oil reservoir level alarm on "C"Reactor Coolant Pump. Power was stabilized at approximately 15%(0820 hours) while oil was added to the reservoir. The plant wasreturned to 100% power at 1505 hours on January 5, 1987. Thepower reduction was approximately 57.5 hours in duration.

B. On March 5, 1987, at 2310 hours, the plant commenced a loadreduction for entry into the third refueling outage. Thegenerator breaker was opened at 2010 hours on March 6, 1987.Major activities scheduled for the outage were:

Steam Generator

a. Sludge Lance and Upper Internal Inspection on SteamGenerator "C"

b. U-Bend Stress Relief

c. Shot Peening

d. Plug Removal

e. Eddy Current Testing

f. Tube Plugging

Sludge lancing and upper internal inspection of Steam Generator"C" was completed on March 16, 1987. The upper internalsinspection revealed the presence of a light dust (5% blockage)

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with an oil film on the lower plate. The oil residue was from a'

previously identified lube oil leak on a feedwater pump.Approximately 24 pounds of sludge was removed following thesludge lancing.

The third inservice eddy current examination of steam generatortubing was performed between the dates of March 17 and April 26,1987. The results of this inspection, contcined in the followingtable, were reported in a Special Report (SPR 87-005) dated May11, 1987.

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S/G A S/G B S/G C

Total Number of Tubes Plugged Previously 40 199 56

Total Number of Tested Tubes 4634 4475 4618

Number of tubes plugged unnecessarily this 5 0 0outage

Number of plugs removed 0 24 0

Number of tubes plugged for stuck heaters 1 0 2

Number of tubes > 40% indications 102 173 102

Humber of tubes F* applied (including plug 31 73 31

removal tubes)

Number of tubes plugged this outage for ECT 71 118 71,

indicationsi

Number of tubes repaired (i.e. sleeved) 0 0 0

Total Number of tubes now plugged 117 293 129

Total Number plugged - percent (%) 2.5% 6.27% 2.76%

On April 7, 1987, at approximately 1300 hours, the preliminaryresults of the eddy current examination concluded that Technical

; Specifications Section 3.4.5, "Steam Generators," sample

| inspection category C-3 applied, since more than 1% of theinspected tubes were defective. The entry into this inspectioncategory was reported in LER 87-006 per the requirements of10CFR50.73(a)(2)(ii). SCE&G has completed stress relieving of

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! the U-bends of the unplugged row I and 2 tubes and shot peeningi of the tubes in the inlet side tubesheet area of each steam

generator. This corrective action is designed to reduce tensilestress in the steam generators at Virgil C. Summer NuclearStation and to reduce the rate of tube degradation.

On March 20, 1987, reactor vessel stud detr.nsioning commenced,

| placing the plant in Mode 6. All fuel issemblies had been| removed from the reactor vessel by March 28, 1987, and by April' 30, 1987 Cycle 4 fuel loading was complete.

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On March 31, 1987, SCE&G was notified by Wyle Laboratories that*

all three pressurizer safety valves had been tested and the as-found setpoints were outside the Technical Specification limitsof 2485 1% psig but less than the safety limit of 2735 psig. OnApril 1, 1987, the deviation of the pressurizer safety valvessetpoints outside the Technical Specification limits was reportedper 10CFR50.72(b)(2)(1). SCE&G considers the use of differenttesting methods to be the primary contributor to this situation.These valves were last tested using the hot nitrogen method andsetpoints verified for the second operating cycle in April 1984.The 1987 test at Wyle involved the use of steam. The correctsetpoints were verified during startup when testing was conductedat hot plant conditions using a steam medium and a calibratedpressure assist device, together with a test method which bestsimulates actual plant conditions. Complete details arecontained in LER 87-005.

On May 12, 1987, a Service Water Screen Wash Pump failed to startduring Engineered Safety Feature Loading Sequencer (ESFLS)testing. Investigation attributed the failure to a defective lugcrimp on the internal vendor wiring in the ESFLS panel. TheESFLS provides sequenced loading of equipment (necessary foraccident mitigation) to the Engineered Safety Feature buses. Asa result of wiring discrepancies noted during the investigation,the internal wiring for both ESFLS panels was reworked. Thepotential failure of both ESFLS units due to defective lug crimpswas reported in LER 87-010.

On May 26,1987, at 1745 hours, a pressure boundary leak in thereactor coolant system forced the plant into a controlledshutdown and a declaration of a Notification of Unusual Event at1820 hours. On May 27,1987, at 0130 hours, cold shutdown (Mode5) condition was established satisfying Technical Specifications.The cause of this event was a crack originating at the root ofthe seal injection inlet nozzle weld in the "C" RCP thermalbarrier flange. The weld in the area of the crack was ground outand repaired by welding. The other Reactor Coolant Pumps (A andB) were inspected in the area of the Thermal Barrier SealInjection interface by dye penetrant exa11 nation. Theseexaminations showed no indication of cracks or leaks in thisarea. Details of event are addressed in LER 87-013.

Initial criticality was achieved on June 6, 1987, at 0750 hours.The main generator was placed on line at 1102 hours on June 9,1987. The refueling outage was approximately 1,666.0 hours induration.

C. On June 16, 1987, at 2003 hours, a reactor trip occurred from100% power. The failure of a capacitor in inverter XIT 5904caused an output fuse to blow which resulted in the loss of PowerRange Nuclear Instrument (HI) 44. The loss of NI-44 caused theSteam Generator (SG) program level control signal to decreasefrom full load to no load (38%). The Feedwater Regulating Valves(FWRVs) reduced flow to decrease actual level to meet the

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programmed level. When the operator placed the FWRV controls to*

manual and demanded an open signal, the addition of coolerfeedwater (in conjunction with the already lower level) caused"B" Steam Generator level to shrink below the Low-Low LevelReactor Trip Setpoint. An alternate inverter was aligned and thereactor taken critical at 1142 hours or. June 17, 1987. Thegenerator was back on line at 2127 hours on June 17. The forcedoutage was 25.4 hours in duration.

D. On July 24,1987, at 2030 hours, a forced power reduction from100% was made to determine the cause of an oil level alarm on "A"Reactor Coolant Pump. A reactor building entry was made to lowerthe oil level when the plant reached 22% power level atapproximately 0345 hours on July 25, 1987. During the return to100% power on July 26, high vibration on one main feedwater pumpcaused the power escalation to be halted at approximately 87%power and a subsequent 12% reduction in power to be initiated.The power reduction was approximately 45.2 hours in duration.

E. On September 2, 1987, at 2109 hours, while the plant wasoperating at 100% power the reactor tripped due to a turbine tripcondition above the 50% power P-9 permissive. A main generatorstator ground resulted in an electrical fault which caused a mainturbine trip. A failed main generator bushing was the cause nfthe generator stator ground condition. The failed generatorbushing was replaced. The other generator bushings wereinspected, and meggar readings revealed no abnormalities. A leakin the stator water cooling system was identified as the mostlikely cause of the bushing failure. After repair of thebushing, an air leak was discovered in the main condenser bootseal which required replacement in order to draw a condenservacuum. The reactor was taken critical on September 12, at 1552hours, and the generator was back on line September 13 at 2131hours. The plant returned to 100 percent power at 0915 hours, onSeptember 15. The forced outage of approximately 264.4 hours induration was reported in LER 87-021.

F. On September 24, 1987, at 2210 hours, the plant tripped from 100%power. A control rod drive system redundant power supply wasbeing removed from service for repair. When the neutral wasdisconnected, the redundant power supply also lost its neutralwhich caused 12 control rods to drop. This resulted in anegative rate reactor trip. The power supply was restored andthe reactor was critical on September 25, 1987, at 1740 hours.The generator was synchronized at 2356 hours on September 25 andthe plant was back at 100% power at 0545 hours, on September 27.The forced outage of approximately 25.7 hours in duration wasreported in LER 87-024.

G. On October 14, 1987, at 2102 hours, a power reduction wasinitiated to 30 percent power to allow access for the performanceof surveillance / rework of some Reactor Building Cooling Unitelectrical connections. LER 87-025 was submitted describing theidentification of a kerite taped back to back "V" configuration

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connection not previously tested for environmental qualification.The plant was returned to 100% at 1400 hours on October 17. Theforced power reduction was approximately 65 hours in duration.

H. On October 29, 1987, at 0313 hours with the plant at 100% power,both the primary and backup power supplies to one of theWestinghouse 7300 system process rack panels failed. Thisresulted in a loss of various instrumentation and controlfunctions including feedwater controls, pressurizer pressure andlevel controls, and steam dump controls. Manual control of thefeedwater system was attempted, but due to the nature of thecontrol failures, recovery was not possible. The plant trippedon low steam generator "C" level coincident with steam flow / feedflow mismatch. The cause of the event was attributed to a failedcapacitor on a steam dump control signal converter card in one ofthe process rack panels. This capacitor shorted to groundcausing the breakers to both the primary and backup powersupplies for the process rack panel to trip.

On October 30,1987, at 0903 hours prior to startup (the reactorstill subcritical, control rod shutdown banks withdrawn), a powerloss to a source range cabinet occurred as a result of a blownfuse. The shutdown banks inserted when the associated bistablewas actuated by the power loss. This loss of power occurred whenthe wrong type of light bulb was inserted in both the instrumentand control power status indicating lights in one of the sourcerange drawers in the Control Room. The incorrect light bulbscaused both the instrument and control power fuses to blow whenthe light bulb holder assembly was reinserted.

Subsequent to making the necessary repairs, the main generatorwas synchronized at 1658 hours on October 30. The forced outagewas approximately 37.8 hours in duration. Event details areaddressed in LER 87-027 and LER 87-028.

4.0 EXPOSURES

Attachment I consists of tables which list the number of station,utility, and other personnel (including contract personnel) receivingexposures greater than and less than 100 Mrem / Year, and theirassociated man-rem exposure according to work and job functions.

5.0 FAILE0 FUEL

: The Virgil C. Summer Nuclear Station has had no significant indication! of failed fuel. The specific activity of the primary coolant remained

within the limits of Technical Specification 3.4.8, "Specific|l Activity."

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ATTACHMENT IPags 1 of 3

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SOUTH CAROLINA ELECTRIC & GAS COMPANYV. C. SUMMER NUCLEAR STATION*

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1987 MAN REM REPORT'

N'JM8ER OF PERSONNEL >0 MREM TOTAL MAN-REMs

WORK & JOB FUNCTION

STATION UTILITY CONTRACT STATION UTILITY CONTRACT

Reactor Operations & Surveillance

Maintenance Personnel 90 0 93 3 046 0.000 2 862

Operating Personnel 75 1 58 8 136 005 1.458

Health Phys;cs Personnel 22 2 118 2.470 270 14 875

Supervisory Personnel 9 3 9 250 080 .101

Engineering Personnel 13 23 25 .515 .709 449

Routine Maintenance

Maintenance Personnel 165 2 382 9 269 085 27.146

Operating Personnel 7 0 0 .135 0 000 0 000

Health Physics Personnel 10 2 74 865 020 2 792

Supervisory Personnel 3 0 3 .045 0 000 009

11 27 22 .302 848 1 062 _Engineering Personnel

inservice inspection

Maintenance Personnel 48 1 89 4 645 070 6 045

Operating Personnel 19 0 0 492 0 000 0 000

Health Physics Personnel 4 0 63 095 0 000 3 675

Supervisory Personnel 1 0 1 040 0 000 005

Engineering Personnel 5 13 35 .435 2 601 3 795

Special Maintenance

Maintenance Personnel 160 1 442 42.566 025 298 843


Health Physics Personnel 11 3 99 1.369 718 55 080i

Supervisory Personnel 5 2 2 332 055 011

Engineering Personnel 11 22 33 1 820 5.764 8 582

Waste Processing

Maintenance Personnel 49 0 56 3 220 0 000 4 605

Operating Personnel 4 0 t 074 0 000 384

Health Phys:cs Personnel 11 1 52 1.300 040 5.183

Supervisory Personnel 0 0 0 0 000 0 000 0 000

Engineering Personnel 1 9 1 040 .172 035

Refueling


Operating personnel ,12 0 0 502 0 000 0 000

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Health Physics Personnel 4 0 53 301 0 000 3.385

Supervisory Personnel 2 0 0 350 0 000 0 000

E ngineering Personnel 2 8 26 036 1 315 2 475

TOTAL 5



Health Phys:cs Personnel 62 8 459 6 400 1 048 84 990

Supervisory Personnel 20 5 15 1017 135 126

E ngineering Personnel 43 102 142 3 148 11 409 16 398

G R ANO TOTAL 650 121 1841 96 225 12 857 466 546

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ATTACHMENT IPagt 2 of 3

SOUTH CAROLINA ELECTRIC & GAS COMPANYV. C. 5UMM ER NUCLEAR STATION

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1987 MAN. REM REPORT

NUM8ER OF PERSONNEL >100 MREM TOTAL MAN-RE M

WORK & JO8 FUNCTION

STATION UTILITY CON'RACT STATION UTILITY CONTRACT

Reactor Operations & Surveil!ance

Maintenance Personnel 6 0 6 .925 0.000 1.207

Operating Personnel 34 0 2 6.788 0 000 .435

Health Physics Personnel 8 1 55 2.105 250 12.432


E ngineering Personnel 2 0 0 335 0 000 0 000

Routine Maintenance


Operating Personnel 0 0 0 0 000 0 000 0 000



Engineering Personnel 1 2 2 .105 279 495

Inservice Inspection

Ma'ntenance Personnel 13 0 19 3.580 0.000 4 324

Operatmg Personnel 0 0 0 0 000 0 000 0 000

Health Phys cs Personnel 0 0 11 0 000 0 000 1 863


Engineering Personnel 1 6 12 355 2 430 2 920

Special Maintena nce

Maintenance Personnel 90 0 317 39.760 0 000 293 099

Operating Personnel 8 0 0 1.459 0 000 0 000

Health Phys 4cs Personnel 7 1 71 1.221 688 53 936

Supervisorypersonnel 1 0 0 .120 0 000 0 000

| Engineering Personnel 4 16 17 1.713 5 606 8 040

Waste Processing


1 Operating Personnel 0 0 1 0.000 0 000 375

Health Phys,cs Personnel 2 0 10 890 0 000 3 965

Supervisory Personnel 0 0 0 0 000 0.000 0 000

E ngineerirq Personnel 0 0 0 0 000 0 000 0 000

Re f ueling




Superv sory Personnel 1 0 0 325 0 000 0 000

Engineering Personnel 0 5 9 0 000 1 295 1 830

TOTALS




| Su perv,sorypersonnel 2 0 0 445 0 000 0 000

| Engsneering Personnel 8 29 40 2 508 9 610 13 285

| GRAND TOTAL 239 31 685 76 813 10 548 429 838

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ATTACHMENT IPago 3 of 3,.

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SOUTH CAROLINA ELECTRIC & GAS COMPAMVV. C. SUMMER NUCLEAR STATION

*1987 MAN-REM REPORT

NUMBER OF PERSONNEL <100 MREM TOTAL MAN-REM

WORK & JOB FUNCTION

STATION UTILITY CONTRACT STATION UTILITY CONTRACT

Reactor Operations & Surveillance

Maintenance Personnel 84 0 87 2.121 0 000 1.655

Operating Personnel 41 1 56 1.348 005 1.023

Health Physics Personnel 14 1 63 .365 020 2.443

Supervisory Personnel 9 3 9 250 .080 .101

Engineering Personnel 11 23 25 .180 .709 449

Routine Maintenance


Operating Personnel 7 0 0 .135 0.000 0 000

Health Physics Personnel 8 2 72 240 020 2.508

Svoervisory Personnel 3 0 3 045 0 000 009

Engineering Personnel 10 25 20 .197 569 .567

Inservice Inspection

Maintenance Personnel 35 1 70 1 065 070 1.721

Operating Personnel 19 0 0 .492 0 000 0 000

Health Physics Personnel 4 0 52 095 0 000 1.812

Supervisory Personnel 1 0 1 .040 0 000 .005

Engineering Personnel 4 7 23 080 171 875

Special Maintenance

Maintenance Personnel 70 1 125 2 806 025 5 744,

| Operating Personnel 39 0 1 1.201 0 000 .025

Health Physics Personnel 4 2 28 .148 .030 1.144

! Supervisory Personnel 4 2 2 .212 .055 011

Engineering Personnel 7 6 16 .107 .158 .542

Waste Processing

Maintenance Personnel 42 0 45 1 005 0 000 1.435

Operating Personnel 4 0 2 .074 0 000 009


| Supervisory personnel 0 0 0 0 000 0 000 0 000

Engrneering Personnel 1 9 1 040 .172 C35

Refuebnq

Maintenance Personnel 24 1 43 .985 080 1 518



Supervisory Personnel 1 0 0 025 0 000 0 000

Engineering Personnel 2 3 17 036 020 645

TOTALS

Mainterpce Personnel 396 5 679 13.339 260 21 596

120 1 59 3 483 005 1 057Operating Personnel_.


Suoervrsory Personnel 18 5 15 572 135 126

|Engmeering Personnel 35 73 102 640 1 793 3 111

GRAND TOTAL 611 70 1156 19 412 2 309 36 657

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10CFR50.36 1.

, . ,~. th rouna Electric & Gas Company Dan umn

Columbia. SC 29218 Nuclear Operations

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Dr. J. Nelson GraceRegional Administrator

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U. S. Nuclear Reguletory CommissionRegion II, Suite 2900101 Marietta Street, N.W.Atlanta, Georgia 30323

Subject: Virgil C. Summer Nuclear StationDocket No. 50/395Operating License No. NPF-12Annual Report

Dear Dr. Grace:

Attached is the 1987 Annual Report for the South Carolina Electric & GasCompany Virgil C. Summer Nuclear Station Unit No. 1. This report is beingsubmitted in accordance with Technical Specifications 6.9.1.4, 6.9.1.5, andRegulatory Guide 1.16.

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

y tru y your ,

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D. A, N man

CJM/ DAN:jzAttachment

c: 'J. G. Connelly, Jr./0. W. Dixon, Jr./T. C. Nichols, Jr.E. C. Roberts0. S. BradhamW. A. Williams, Jr.General Managers

; L. A. BlueW. R. Baehr'

C. A. PriceR. B. ClaryW. R. HigginsJ. R. ProperR. M. Campbell, Jr.K. E. NodlandJ. C. SnelsonG. O. PercivalR. L. PrevatteJ. B. Knotts, Jr.

g4NNSRCRTS

NPCF $File t j;

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1987 ANNUAL OPERATING REPORT

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Transcript of 1987 ANNUAL OPERATING REPORT