ML20147E613

Annual Operating Rept 3 for 1987

ML20147E613
Person / Time
Site:	Wolf Creek
Issue date:	12/31/1987
From:	Bailey J WOLF CREEK NUCLEAR OPERATING CORP.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
ET-88-0022, ET-88-22, NUDOCS 8803070108
Download: ML20147E613 (16)

Text

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/ - ;c  : Attachment ~to ET 88-0022

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e WOLF CREEK GENERATING STATION DOCKET NO: 50-482 FACILITY OPERATING LICENSE: NPF ,

ABMUAL OPEIETING REPORP

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REPORP NO: 3 1

~REPORP PERIOD: JANUARY 1, 1987 to DECEMBER 31, 1987 -

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Iblf Creek Nuclear Operating Corporation ,

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4y ANNUAL OPERATING REPORP mis report is being subnitted in accordance with the requirements of Technical Specification 6.9.1.4 and contains the information required by Technical Specification 6.9.1.5. We founat of this report is similar to that provided in Begulatory Position C.l.b of Regulatory Guide 1.16,.

Revision 4, August 1975. Also included in this report is the information required by 10 CFR 20.407. %is reporting period inclMes the time between January 1, 1987,.and Decenber 31, 1987.

1. .SUfEARY OF OPERATIN3 EXPERIENCE vblf Creek Generating Station canpleted its secoM year of cotmercial operation on Septer.ber 03, 1987. During the first two years of.

cmmercial operation, the unit's gross generation was 16,575,413 Megawatt-Murs, with a unit availability factor of 83.7 percent and net capacity factor of 80.1 percent. On September 27, 1987, the unit was shutdown for the secoM Refueling Outage, which was axnpleted on January 05,'1988.

A sumnary of operating exerience aM major safety telated maintenance activities by month during 1987 is provided below. 'Ihis infonnation has previously been subnitted in the enthly Operatire Reports for January through December, 1987.

JANUARY On January 1, 1987, W31f Creek Nuclear Operating Corp 3 ration assumed the managenent of Wolf Creek Generating Station. %e plant operated in lede 1, Power Operation, throughout most of the month. On January 8,1987, a personnel error caused a safety Injection signal which resulted in a Reactor Trip aM Turbine Trip. We plant renained in ibde 3, Hot Standby, in a maintenance outage until it returned to fede 1 on January 12.

Following this, excessive Turbine Generator vibration forced the plant to operate in a derated condition aM caused one Turbine Trip on January 20 aM two maintenance outages on January 17 aM 31.

Major Safety Related Maintenance Activities for January

a. Replacanent of a fuel pressure indicator and the differential pressure indicator for the rocker lube oil filter on standby diesel generator "B".

b. Replacement of the feedwater flow transmitter for stean generator "A" .

c. Replacenent of one of four 15 volt DC power supplies in each energency load sequencer.

d. Replacement of the p>sition indicator in pressurizer p)wer operated relief valve BB PCV-455A. .

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e. Rework of the hydraulic operator' on GK V767, the class lE electrical equipnent air conditioning unit 5A condenser outlet isolation valve to the essential service water systen.

February

%e mnth began with the reactor critical in Mxle 2 aM the Turbine Generator shut down to correct a vibration problen. %e .

Turbine Generator was synchronized with the grid, tripped, balanced and synchronized again on February 1,1987. %is was followed by power ascension in Mx3e 1, reaching 98 percent power on February 2. W e plant operated at or near 100~ percent power for the renaiMer of the mnth.

MajorSafetyRelatedMainIenanceActivitiesforFebruary

a. Replacenent of stean generator "A" feedwater flow transnitter AD FT-510A.

b. Replacenent of the hydraulic fluid in two stean generator snubbers.

March he plant operated in Mxle 1, Power Operation, near 100 percent power throughout the month, except for a reduction to 74 percent on March 7 aM 8, due to reduced systen denaM.

Major Safety Related Maintenance Activities for March

a. Replacement of the control roon ventilation supply chlorine mnitor, GK AITS-3.

b. Replacenent of the regulator for the turbine driven auxiliary feedwater punp regulating valve to steam generator "C" , AL IN-12.

c. Replacenent of the fan shaft on the fuel pool cooling punp room cooler.

April

@e unit operated near 100 percent power throughout most of the mnth. Ibd Control problens were experienced twice during the month, on April 19, aM 23. Each time boration to Hot StaMby was connenced, but reactor trips occurred at 60 and 50 percent power respectively.

Major Safety Related Maintenance Activities for April

a. Replaced the lube oil tenperature iMicator KJ TI-121 for diesel generator "B".

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b. Replaced the power isolation printed circuit board for containnent purge exhaust radiation monitor GT RE-33.

c. Replaced the regulator for the charging control valve BG HCV-182.

d. Replaced pressure switch DG PS-0018 for centrifugal chargirg pump "B" auxiliary lube oil pump.

e. We power operated relief valve for stean generator "C" was rewrked.

May

%e unit operated near 100 percent pwer throughout most of the month. On May 28, 1987, the main turbine electro-hydraulic control systen experienced a loss of pwer, resulting in a unit trip and reactor trip. We unit returned to power operation the next day.

Major Safety Related Maintenance Activities for May

a. Replaced the I/P converter for the turbine driven auxiliary feedwater punp flow control valve to stean generator "C", AL HY0012.

b. Replaced a power supply for engineered safety features actuation system, SA036C.

c. Replaced relays for engineered safety features actuation system status panel, SA066Y.

d. Replaced a card in reactor coolant loop 1 cold leg tenperature instrunent, BB TY411J.

e. Replaced the diesel generator building supply fan notor.

June

%e unit operated near 100 percent power throughout most of the nonth. We loss of Main Feedwater Punp "A" resulted in a Unit Trip on June 29, 1987. We unit resumed pwer operation on June 30, 1987.

Major Safety Related Maintenance Activities for June

a. Weld repair of the spent fuel pool liner.

b. 'eplacement of the seals on the containnent personnel hatch,

c. W31d overlay on two safety related pipes to restore pipe wall thickness that was eroded downstrean of throttle valves.

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d. Replaced the I/P converter on the turbine driven auxiliary feedwater pmp flow control valve to stean generator "C".

July

% e unit operated in Made 1, Power Operation, at 100 percent power until a partial loss of offsite power occurred when a switchyard ptential transformer failed. % is caused a Main Feedwater Pmp "A" trip, resulting in a Unit Trip on July 20, 1987. Followirg repair of a Containment Cooling Fan, the Unit returned to Mode 1 on July 26 and operated at 100 percent for the remainder of the month.

Major Safety Related Maintenance Activities for July

a. Replaced a circuit board in the flow indicator for auxiliary feedwater to stean generator "B".

b. Replaced a o>ntrol module for main stean isolation valve for steam generator "C".

c. Replaced a relay card for feedwater isolation valve for stean generator "A".

d. Replaced the air regulator for the letdown dtznp valve for high volume control tank level dtrnp to recycle holdup taru,

e. Replaced an input nudule on a refueling water storage tank tenperature indicator.

f. Replacement of the blaies and motor for one containment cooling fan.

August -

%e unit operated in Made 1, Pvwer Operation, near 100 percent power throughout the month.

Major Safety Related Maintenance Activities for August

a. MOVATS testing of selected valves,

b. Replaced a relay card for the feedwater isolation valve to stean generator "C".

c. Replaced an input nodule in canponent cooling water surge tank "A" level control.

d. Replaced a power isolation board in the containment purge radiation nonitor, GP RE-22.

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September Unit operation near 100 percent power was interrupted by.two unplanned trips in September,1987. Core coastdown ecmnenced on September 18, 1987. Following the eeeond trip, a decision was made on September 27, 1987 to renain shutdown for the refueling outage. %e month ended'with the Reactor in Mode 5, cold shutdown.

Major Safety Related Maintenance Activities for-Septenber

a. %e compressor for the control roon air conditioning unit, SGK04B, was rebuilt and returned to service.

b. Motor operated valve testing for IE Bulletin 85-03 was conpleted on six valves.

c. Replaced a potentioneter anc3 a mdutronic unit on auxiliary feedwater control valve, AL IN11, motor-driven pung "A" to stean generator "C".

d. Replaced a vacuan transducer in control room ventilation radiation monitor, GK RE-04.

e. Replaced a power isolation and input-output board in containnent radiation monitor Gr RE-31.

October

%e unit renained in a refueling outage throughout the mnth.

An Unusual Event was declared at 2037 CST on October 14, 1987, due to a fire in a Class IE Switchgear Iban. % e fire alann was caused by an electrocution. We Unusual Event was terminated at 2111 CST.

Major Safety Related Maintenance Activities for October

a. Replaced the take-up spool magnets and the air punp in chlorine monitor, GK AITS-3.

b. Replaced a card in reactor coolant icop 2 average tenperature instrunent.

c. Replaced a flow transmitter on reactor coolant loop 4.

d. Replaced a lube oil tenperature instrunent on the turbine driven auxiliary feedwater punp.

o. Replaced a Irwer supply and an isolation mo3ule in "B" ESF switchgear, NB02.

f. Removed the reactor vessel heai and upper internals.

g. Replaced the punp seal on centrifugal charging pump "B".

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h. Replaced eroded 'essentia1' service water pipe.

'i. -Reworked residual heat removal pump "B" .

inlet flange.-

November te' unit remained in a r$fuelirg outage throtshout' the month.

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Major Safety Related Maintenance Activities for November

a. Replaced first 390 Raychen splices.

b'.  ; Replaced two power supplies in the nuclear instrumentation'.

c. Replaced an I/P converter, two pressure indicators and two

' gaskets in the main steam instrunentation. ,

d. Replaced a differential pressure switch,' a temperature sensor and two level indicators in the staMby diesel ergines.

e. Replaced a flow control valve for one rMiation monitor.

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f. Capped one tube in containnent cooler SGN01A.

g. Replaced two-sections of essential service water piping. .

h. Replaced the tube bundle in the jacket water heat exchanger for diesel generator "A".

1. Reworked the anit-reversity shock absorbers on the reactor coolant punps.

j. Removed the heaters fran 60 Limitorqua valve operators.

k. mworked control roan ventilation isolation danper GKD084.

December te unit remained in a refueling outage througrout the nonth.

At the end of December,1987, the unit was in Mode 2, Starttp.

Major Safety Related Maintenance Activities for Decenber

a. Replaced remainder of 544 Raychem splices on instrunent wires,

b. Ibworked 38 Valcor valve operators.

c. Replaced nine cards and two relays in the solid state protection systen.

d. Replaced the o-rings in 17 Conax connectors.

e. Replaced a speed switch in the diesel generator "A".

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.f..< Replaced a log'. current' anplifier in the nuclear instrumentation,

g. Replaced a power supply in the . load sequencer "A".

h. ' Replaced a reactor coolant systr . wssure transmitter.

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i. Repaired the governor ex* manual voltaje regulator on diesel generator "A" .

j. Repaired the autanatic voltage regulator on diesel generator '

"B".

k. Rebuilt the diesel generator "B" keep warm punp.

1. Replac3d the reactor coolant pump "B" nu:iber one seal.

m. Replaced the internals on two safety injection accunulator-check valves.

n. ' Rolaced the trip mechanism shafts on the reactor trip breakers.

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SUMMARY

OF CUPAGFS AND FORCED IWER REDUCTIONS Prwided below is a sumary of the 1987 outages and forced pywer reductions of wer- 20 percent of design pywer level whem.the reduction extended for more than four hours. References to reports of reportable occurrences directly related to each outage or loal reduction are included in parenthesis *here applicable.

1. Start 'bte 01/08/87 Completion Date: 01/12/87 Type: Forced / Scheduled Duratiart: 92.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> mason: Reactor trip due to Safety Injection Signal. W e outage was extended at 0900 on 01/09/87, to allow maintainance of feed systen valves. %is crea?ed 14.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> of forced outage and 77.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> of scheduled outaje. Licensee Event Report (LER 87--002-00).

2. Start Date: 01/17/87 Canpletion Datet 01/18/87 Typ3: Scheduled Duration: 23.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> ,

Reason: Manual shutdown to balance main turbine genc . or. .

3. Start Date: 01/20/87 Canpletion Date: 01/22/87 Type Forced Duration: 30.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> Reason: Turbine Trip / Reactor Trip due to turbine generator vibratiots.

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4. Start Date: 01/28/87 Completion Date: ~01/31/87 ,

Type:- Forced _ Duration: 65.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Reason: ' Reduction to 55 percent' Joe to turbine generator vibration.

5. Start Dater..'01/31/87 Cepletion Date: 02/01/87

-Type:' SchM uleC Duration:' 25.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Reason: Manual' shutdown'to balance main turbine generator.

6. Start Daa: 02/01/87 Cmpletion Date: 02/01/87 Type: .ichedu ci Duration: 3.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />

-Reason: Manual shutcbwn to balance main turbine generator.

7. Start Date: Ci/19/87 Cmpletion Date: 04/19/87 Type: Forced Duration: 13.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Reason: M actor Trip due to rod control circuit card failure. (LER 87-017-00)3

8. Start Date: 04/23/37 Cmpletion Date: 04/24/87 Type: For d Duration: 33.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> Reason: Peactor Trip ("ue to rod control circuit card failure.

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(LER 87-017-00).

9. St. art Date: 05/28/87 cmpletion Date: 05/29/87 Type: Forced Duration: 22.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> Reason: Reactor Trip due to loss of power to turbir.a electro-hydraulic control system. (LER 87-022-01)

10. Start r. ate: 06/29/87 cmpletion Date: 06/30/87

- Type: Forced Duration: 38 hours4.398148e-4 days <br />0.0106 hours <br />6.283069e-5 weeks <br />1.4459e-5 months <br /> ,

Reason: Reactor Trip due to loss of main feedwater pump "A". (LER 87-027-00).

.11. Start Date: 07/20/87 Cmpletion Date: 07/26/87 Type Forced Duration: 129.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> mason: Reactor Trip frrn 100 percent power after a partial loss of offsite power owurred when a switchyard potential transformer failed. tis caused e. main feedwater pep "A" '

trip which caused a partial loss of feedwater flow and resulted in a unit trip. We outaga was exterded 5 days due to required repair of a containnent coolirg fan. (LER 87-030-00). .

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• i 12? Start Date: 09/10/87. Cmpletion .Date s . 09/12/,87-Type JPbreed' Duration: 33.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />

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Reason: ' A' 345 KV line frcm "B" phase main power transformer separated, causing a turbine trip and subsequent: reactor trip. . (LER 87-037-00).

13. Start Date 09/27/87. iCompletion Date: '01/05/88' Type Forced / Scheduled Durations- 2418.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />

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aeason: . An improperly positioned ' switch caused control rod Bank "D" to drop, resultiry in a-reactor trip. (LER 87-041-00).- A-n decision to stay down and start the refueling outage early

'resulted in 12.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> forced outage and 81. hours planned outage for September. Total outage hours was 2418.4.

3. MMOR SAFET1Y RELATED REF(72 LING OUTAGE MAINTENANCE ACTIVITIES

a. Mtor operated valve testing for IE Bulletin 85-03 was completed. .

'b. Replaced' a card 'in reactor coolant loop 2 average temperature instrment,

c. . Replaced a' flow transmitter on reactor coolant loop.4.

d. Renoved the reactor vessel head ard upper internals.

e. Replaced the pep seal on centrifugal chatv3i ng pep "B".

f. Replaced eroded essential service water pipin3 E g..- Reworked residual heat renwal pop "B" inlet flange.

h. Replaced an 1/P converter, two pressure indicators ani two gaskets  !

in the main stean instrm entation. .,

1. Replaced a differential pressure switch, a temperature senzor and two level indicators in the stardby diesel engines.

j. Replaced the tube bundle in the jacket water heat exchanger for diesel generator "A".

k. Reworked the anit-reversing shock absorbers on the reactor coolant peps.

1. Rewrked contral roon ventilation irolation danper GKD084. i

m. Replaced 544 Raychem splices on instement wires. ,

n. Reworked 18 Valcor valve operators.  ;

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o. : Replaced nine cards and two relays.in the' solid state protection.

systen.

p. ' Replaced the o-rings in 17 Conax. connectors.

q. Replaced .a ' speed switch in the~ diesel generator "A".

r. -Replaced a log current anplifier in' the nuclear instrunentation.

s. - Replaced -a power supply in load sequencer "A".

t. -Repaired the governor and manual voltage regulator on diesel.

generator "A" .

u. . Repaired the autanatic voltage regulator on diesel generator "B".

v. ' Rebuilt the diesel generator "B" keep warm puup.

.w. Replaced the reactor coolant pung "B" nunber one seal.

x. Replaced the internals on two safety injection accunulator check-valves.

y. Replaced the trip mechanism shafts on the reactor trip breakers. -

b z. - Reactor vessel disassenbly, reassenbly to allow refueling.

aa. Slu$ge lancing all stean generators.

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4. F.NPOSURE INFORMATION

'A. NIMBER OF PERSCNNfL AND .*%N-REM IW W3HK AND JOB fuCTION RIMORT - 1987

.NU.$0ER (F PERSONNFL (>100 MREM) 'IOTAL t%N-REM WORK & JOB FUNCPION RTATION UCILITY Cor(IWCr STATION UTILITY C0tflWCr IMactor Operations & Surveill'ince Maintenance & Construction 0 0 0 1.417 ~ 0.000 .888 operations 9 0 1 3.038 0.000 .300 4.844 .321 9.347, Health Physics & Lab 16 2 37

. Sujetvisory & Office Staff 1 0 2 .880 .144 .444' th)irecting Staff 3 1 1 765 .664 413 Ibutine plant Maintenance mintenance & Construction 16 0 6 5.396 0.000 4.497 0 0 .168 0.000 .042 omrations 1

.761 .009 .218 fica'sth Riysics & Lab 0 0 0 Supervisory & Office Staff. 0 0 0 .551 .021 -.183 Fngineering Staff 0 0 0 .185 .014 .241 Inservice Inspection Maintenance & Construction 0 0 48 .741 0.000 18.629

_ Operations 0 0 1 .031 0.000 .249 ~

Health Physics & Lab 0 0 0 .178 .057 .009 Supetvisory & Office Staff 2 0 3 .490 0.000 869 Engineering Staff 0 0 10 .120 0.000 4.725 Special Plant Maintenance 17.472-Maintenance & Construction  ?.7 0 50 9.974 0.000 Operations 1 0 0_ .339 0.000 .078 Health Physics & Lab 0 0 0 .836 .022 .071 Supervisory & Office Staff 4 0 1 1.456 .019 .453 l Diginee-ing Staff 2 0 5 .663 .004 1.962 Waste Processin3 mintenance & Cbnstruction 3 0 0 1.284 0.000 .184 Operations 0 0 1 .229 0.000 .381 Health Physics & Lab 11 0 5 2.874 .004 1.397 Supervisory & Office Staff ') 0 0 .098 0.000 .003 Engineerirg staff 0 0 0 .002 .068 .005 Refuelirg mintenance & Construction 31 0 21 7.925 0.000 8.379 Operations 7 0 1 1.423 0.000 .176 Health Ihysics & Lab 1 0 1 .204 0.000 .286 Supervisory & Office Staff 6 0 1 1.447 .050 .349 En31neerin; Staff 2 0 6 .475 .041 1.598

'Ibtals Maintenance & Construction 75 0 114 26.737 0.000 50.048 Operations 16 0 3 5 . 2 ~.1 0.000 1.226 Health Physics & Lab 28 2 43 9.697 .414 11.327 Supervisory & Office Staff 16 0 6 4.923 .234 2.300 Engineerirg Staff 10 1 24 2.209 .791 8.944 Grand Totals 145 3 190 48.793 1.439 73.845 Pa3e 11 of 14 l

B. PERSONNEL !ON1'IORING REPORP

1. In-1987, 2085 individuals were provided personnel monitoring devices. Wis infonnation is provided in accordance with paragraph (a) (2) of 10CFR 20.407. % is total includes the ntrnber of individuals required to be reported un3er paragraph (a) (1) of. this section.

2. Below is a statistical sumnary report of the personnel nonitoring-information recorded for individuals fo_ whan personnel monitoring was provided in 1987 in accordance with the requirements of 10CFR 20.407(b) .

Nunber of Entimated whole body exposure rarse individuals in (rans) each rarse No measurable exposure................................................. 1414 Measurable exposure less than 0.1. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 334 0.1 to 0.25............................................................. 159 0.25 to 0.5......... .................................................. 128 0.5 to 0.75.............................................................. 3 2 0.75 to 1.0............................................................... 9 1.0 to 2.0................................................................ 9 2.0 to 3.0.............,.................................................. 0 3.0 to 4.0................................................................ 0 4.0 to 5.0................................................................ 0 5.0 to 6.0................................................................ 0 6.0 bc 7.0................................................................ 0 7.0 to 8.0................................................................ 0 B.O to 9.0................................................................ 0 9.0 to 10.0............................................................... 0 10.0 to 11.0.............................................................. 0 11.0 to 12.0.............................................................. 0 12 + ................ .................................................... 0 Page 12 of 14

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[,t C. SOURCE OF EATA

%e infonnation provided in Section 4.A is based on estimated exp>sures obtained fran Backet Ionization Chanber readings. We information provided in Section 4.B.2 is obtained fran nennal Ianinescent Detector -(TLD)- readings whIch is the official record of exposures. %ere is a discrepancy in the total . number of personnel having received greater than 100 mren exposure during 1987 in' the two sections. Wis discrepancy resulted fron the two different sources of exposure information utilized to detecnine .the totals.

5. INDICATIONS OF FAILED FUEL Beginning June 8,1987, the Xe-133/Xe-135 ratio increased. This increase, along with an increase in noble gas activity, supports the possibility of a claiding defect. W e lack of iodine activity increase indicates a pin-hole type of defect.

After the Reactor Trip on 7/20/87, an increased iodine activity was detected. : Amther iodine "spike" was experienced after the Reactor startup on.7/26/87. It was also noted that Cs-137 was detected in the Reactor Coolant Systen in very snall quantity. W is is an indication that the claiing defect has becane slightly larger but is still classified as a small pin-hole defect.

A Reactor Coolant Systen sample was taken after the Reactor Trip on 9/10/87 and allowed to decay until 9/23/87 to detennine if Cs-134 ard Cs-137 could be detected. We Cs-137/Cs-134 ratio of 2.2 irdicated that j the snall defect is located in a fuel assembly that-has been in the core

for one cycle only.

6. CHALLENGES TO THE POW'S AND SAFETY VALVFE

a. On January 08, 1987, a Reactor trip and safety injection occurred from 100 percent power when a technician isolated the incorrect steamline pressure transnitter during calibration and testitu. %e pressurizer Power Operated Relief Valves (POWS) lifted to control Reactor Coolant Systen (RCS) pressure. (LER 87-002-00).

b. On January 20, 1987, a Reactor trip occurred fran 100 percent pywer occurred as a result of a main turbine high vibration turbine trip.

We pressurizer POWS lifted to control RCS pressure. (LER 87-004-i 00).

. c. On April 19 and April 23, 1987, Reactor trips fran 60 and 52 percent power, respectively, occurred due to defective circuit cards in the rod control power cabinet. %e pressurizer POWS lifted during bnth events to control RCS pressure. (LER 87-017-00).

d. On May 28, 1987, a Mactor trip fran 100 percent pywer occurred after a loss of house power to the main turbine Electo-Hydraulic Control (FK) systen. We pressurizer POWS lifted to control RCS pressure. (LER 87-022-01),

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'O.. On Septenber 10, 1987, c remtor trip from 100 percent power occurred den a 345 kilovolt transmission line conductor fran the "B" phase main transformer to the unit switchyard fell. We pressurizer PORVs lifted to control RCS pressure. (LER 87-037-00).

7. - SEALED SOURCE C0ffrAMINATION

. During the seni-annual sealed source contanination surveillance the

. uraniun slab source used for beta calibration ~was found to have snearable contanination of .09 uCi. We source was removed fran. use'-

innediately. A repair of-the source usiry shellac was performed which sealed in the contanination. W is source will now be used as a check source instead of a prianary calibration source.

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W$LF CREEK NUCLEAR OPERATING CORPORATION l

NO Engincomg and Techrucal SeMees l

February 29, 1988 ET 88-0022 U. S. Nuclear Regulatory Commission ATTN Document Control Desk Washington, D. C. 20555

Subject:

Docket No. 50-482: Annual Operating Report for Wolf Creek Generating Station Gentlemen:

The attached Annual Operating Report is being submitted pursuant to Volf Creek Generating Station, Unit No. 1, Technical Specifications 6.9.1.4 and 6.9.1.5. Also included in this report is information required by 10 CPR 20.407. This report covers operations for the period of January 1, 1987, to December 31, 1987.

Very_truly yours, 4L o, LL -

John A. Bailey <

Vice President Engineering & Technical Services JAB /jad -

Attachment co: B. L. Bartlett (NRC), w/a R. D. Ksrtin (NRC), w/a P. V. O'Connor (NRC), 2 w/a b

P.O. Box 411/ Burbngton, KS 66839 / Phone: (316) 364-8831 I

____ i i 1