ML20212A493

Annual Operating Rept 2,Wolf Creek Generating Station, 1986

ML20212A493
Person / Time
Site:	Wolf Creek
Issue date:	12/31/1986
From:	Withers B WOLF CREEK NUCLEAR OPERATING CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
WM-87-0059, WM-87-59, NUDOCS 8703030362
Download: ML20212A493 (10)

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l WOLF CREEK GENERATING STATION DOCKET NO: 50-482 FACILITY OPERATING LICENSE: NPF-42 AISERL (PERATING REPORF REPORT NO: 2 REPORT PERIOD: JANUARY 1,1986 to DECDIBER 31, 1986 Submitted by:

Wolf Creek Nuclear Operating Corporation 8703030362 861231 PDR ADOCK 05000482 H PDR

TL ANNUAL OPERATING REPORT This 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. The format of this report is similar to that provided in Regulatory 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. 'Ihis reporting period includes the time between January 1, 1986, through December 31, 1986.

1.

SUMMARY

OF OPERATING EXPERIENCE Wolf Creek Generating Station completed its first year of cmmercial

. operation on September 3,1986. During its first year of commercial operation, the unit's gross generation was 8,922,510 Megawatt-hours, with a unit availability factor of 90.4 percent and net capacity factor of 86.4 percent. On October 16, 1986, the unit was shutdown for the first Refueling Outage, which was cmplete on December 21, 1986.

A sumnary of the major safety related maintenance activities during 1986 is provided below. This information has previously been subnitted in the Monthly Operating Reports for January through December, 1986.

January - Essential Service Water train "B" was taken out of service to allow corrective and preventive maintenance work on its components. Following this, problems with the Service Water supply valves to Essential Service Water train "B", EF IN-024 and EF IN-026, necessitated continuous system operation until the Limitorque operators were repaired.

February - Motor-driven Auxiliary Feedwater Pump "B" was repacked and the Limitorque operators of two of its notor driven valves, AL IN-005 and AL IN-034, were lubricated and adjusted. The bearings were replaced on Fuel Pool Cleanup Pumps "A" and "B". Main Steam Pilot Operated Relief Valve, AB PV-004, was reworked. The governor controller for the Turbine-driven Auxiliary Feedwater Pump was replaced, as was the Main Turbine impulse pressure transmitter, a power supply in the Emergency Safety Features Actuation System and a power isolation board in Radiation Monitor GK RE-05.

March - A damaged containment minipurge supply fan unit was replaced and work was performed on Essential Service Water Train

' A' , including the rework of the Limitorque for strainer FEF02A.

In cddition, during a turbine driven Auxiliary Feedwater Pump outage, an oil changeout was performed on several Limitorque valves

- and two flow orifice flange leaks were repaired in the Auxiliary Feedwater System.

Preventative maintenance activities included the semiannual oil change on the Centrifugal Charging Pumps; quarterly maintenance of the Positive Displacement Charging Pump, Diesel Generator 'B', and the Motor Driven Fire Pump; and annual maintenance of the Spent Fuel Pool Cooling Pumps and the Safety Injection Pumps.

April - h e major safety related maintenance activities pertormed included repacking fourteen Reactor Coolant System valves and four valves in the Chemical and Voluma Control System, and encapsulation of the normal charging check valves and two feedwater inlet check valves. %e nitrogen supply isolation valve to "D" Safety Injection Accumulator was reworked. The nozzle ring settings for the Main Steam Safety Valves were changed in accordance with Plant Modification Request 901642. A conoflow regulator was replaced on one Safety Injection test valve.

Preventive maintenance included several Local Leak Rate Tests, lubrication of eight 12" gate valve motor operators in the Component Cooling Water System and semiannual maintenance of the reactor trip breakers.

May - The major safety related maintenance activities performed included replacement of fuel pool cooling valve II V091, replacement of the Fuel Building Emergency Exhaust filter adsorber pre-filter section, replacement of wire jumpers in several Limitorque valve operators to correct Equipment Qualification discrepancies, adjustment of Limitorque operators for Auxiliary Feedwater valves AL IN-30, AL Ilv-31, AL IN-32 and AL IN-33 and plugging of leaking tubes in central chiller SGB01A.

%e Instrument and Control group replaced the I/P converter on atmospheric dump valves AB PV-1 and AB PV-2 and replaced the vacuum pump on radiation monitor GT RE-33.

June - The major safety related maintenance activities performed included replacement of the internal wiring on 152 Limitorque valve operators, replacement of one Reactor Coolant System loop flow transmitter, replacement of the charcoal in the Radwaste Building filter adsorber unit and replacement of the supply air cooling coil on one Auxiliary Building INAC unit.

July - The major safety related maintenance included replacing a card in Loop 4 average temperature instrument, replacing an alarm reset key switch on chlorine monitor GK-AI'"3 3, replacing the pushrods on 35 Cutler Hammer switches and correction of the leakage from the Spent Fuel Pool by reworking several boundary valves.

August - The major safety related maintenance included weld repair of Steam Generator blowdown piping, a pump replacement on radiation monitor GG RE-28, and rework of a leaky fitting on the Chemical Volume and Control System flow transmitter BG FT-143.

September - Major safety related maintenance activities include the rep 1tcement of the actuator on the Control Room Air Conditioning L. . valve GK V765, comencement of MOVATS testing of Auxiliary Feedwater valve Limitorque operators, replacement of a Solid State Protection System universal logic card and replacement of a Ioad Shed/ Emergency Load Sequence power supply.

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October - Major safety related maintenance activities include replacement of a logic board in Emergency Fuel Oil level transmitter JE LIT-025 replacement of an amplifier in Steam Generator "D" level transmitter AB LY504, replace.nent of a broken switch for Reactor Coolant System loop 2 RTD manifold flow transmitter BB FIS427, rework of "B" Centrifugal Charging Pump to correct leaks, removal of the Reactor Vesel head, repacking various RTD manifold isolation valves, rework of Main Stean Isolation Valves and Feedwater Isolation Valves including the incorporation of plant modifications, eddy current testing of "B" and "C" steam generators, testing of all Main Steam safeties, annual maintenance of "A" Resideal Heat Removal pump motor, annual maintenance of niesel Generator ventilation dampers, annual maintenance of "A" Centrifugal Charging Pump, inspection of 4.16 kilovolt Class IE circuit breakers and insulation testing of NB transformers.

Povember - Major safety related maintenance activities included replacement of three primary loop and one seal water re: urn flow transmitters; replacement of three circuit boards; annual,18-month surveillance tests, and MOVATS tests of motor operated valves; repacking manual valves; reworking vent and drain valves and check valves; sludge lancing all steam generators; replacing Reactor Coolant Pump "C" seal cartridge; surveillance inspection of both diesel generators and replacing their keep-warm pumps; replacement of both Boric Acid Storage Tank diaphragms; surveillances of the RHR, ESW and SI pumps; replacement of the seals on both Centrifugal Charging Pumps; annual surveillance of switchgear; testing .7 relief valves; conducting MIC inspections; refueling the reactor and setting its head.

December - Major safety related maintenance activities included replacement of level transmitters for the Reactor Vessel, Steam Generator and Safety Injection Accumulator; Reactor Vessel head assembly; a modification to the Reactor Coolant System Power Operated Relief Valves, replacing, reworking and repacking valves; repairing leaking fittings on the Diesel Generator fuel system and reworking Main Steamline Isolation Valve 4-way slide valves.

2.

SUMMARY

OF OUTAGES AND FORCED POWER REDUCTIONS Provided below is a summary of the 1986 outages and forced power reductions of over 20 percent of design power level where the reduction extended for more than four hours. References to reports of reportable occurrences directly related to each outage or load reduction are included in parenthesis where applicable.

1. Outage Start Date: 02/22/86 Completion Date: 02/24/86 Typ : Forced Duration: 57.3 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 low-low steam generator level which was caused by a circuit failure in the Main Turbine electro-hydraulic control system. (Licensee Event Report 86-007-00)

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2. Ioad Reduction Start Date: 04/06/86 Completion Date: 04/06/86 Type: Forced Duration: 18.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> Reason: Reduced power to 61 percent to allow repair of "B" Main Feed Pump recirculation valve.

3. Outage Start Date: 04/08/86 Completion Date: 04/25/86 Type: Forced Duration: 399.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> Reason: Turbine Trip, Reactor Trip caused by testing activities in the Wolf Creek Substation switchyard (Licensee Event Report 86-018-00). The outage was extended to allow the repair of a pressurizer spray control valve and the conduct of 18 month surveillance tests. Wis created 21.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> forced outage and 377.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> maintenance outage.

4. Load Reduction Start Date: 05/16/86 Completion Date: 05/16/86 Type: Forced Duration: 9.7 inurs Reason: A plant shutdown was started to allow correction of Equipment Qualification discrepancies in Limitorque valve operators. @e :hutdown was averted and power leveled at 45 percent when prompt correction of discrepancies restored one train to service (Licensee Event Report 86-043-00).

5. Load Reduction Start Date: 05/24/86 Cmpletion Date: 05/25/86 Type: Forced Duration: 17.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> Reason: Reduced power to 30 percent while steam generator chemistry was brought back into specification.

6. Outage Start Date: 06/04/86 Completion Date: 06/11/86 Type: Forced Duration: 188.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Reason: Unit shutdown to allow correction of Limitorque valve operator wiring discrepancies (Licensee Event Report 86-043-00).

7. Outage Start Date: 06/30/86 Cmpletion Date: 07/01/86 Type: Forced Duration: 16.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Reason: Reactor Trip, Turbine Trip due to low-low steam generator level which was caused by incomplete closure of an isolation valve during calibration of Iligh Pressure Condenser level switches (Licensee Event Report 86-038-00).

8. Outage Start Date: 07/01/86 Completion Date: 07/01/86 Type: Forced Duration: 6.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> Page 4 of 9

Reason: Reactor Trip, Turbine Trip due to low-low steam generator level control problems while transferring feedwater flow control from the Bypass Feedwater Control Valves to the Main Feedwater Control Valves (Licensee Event Report 86-037-00).

9. Outage Start Date: 07/24/86 Completion Date: 07/26/86 Type: Scheduled Duration: 66.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> Reason: The unit was taken off line to allow repair of a Main Generator stator cooling water leak. During the shutdown, at approximately 13 percent power, a Reactor Trip, Turbine Trip occurred due to steam generator level control problems while transferring feedwater flow control from the Main Feedwater Control Valves to the Bypass Feedwater Control Valves (Licensee Event Report 86-042-00).

10. Load Reduction Start Date: 08/23/86 Completion Date: 08/24/86 Type: Forced Duration: 8.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Reason: Reduced power to 45 percent to allow repair of 'A' Main Feedwater Pump recirculation line.

11. Outage Start Date: 10/16/86 Completion Date: 12/20/86 Type: Scheduled Duration: 1592.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> Reason: Unit shutdown to allow conduct o1. the first annual refueling outage. During the subsequent startup, a Reactor Trip occurred due to steam generator level control problems while in manual control (Licensee Event Report 86-068-00). This created 1583.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> scheduled outage and 8.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> forced outage. During the refueling outage, the following major safety related maintenance occurred:

a. Reactor vessel disassembly, reassembly te allow refueling.

b. Eddy current testing of two steam generators,

c. Replacement of 'C' Reactor Coolant Pump seal assembly.

d. Surveillance testing of Main Steam safety valves and other relief valves,

e. Surveillance inspection of both diesel generators.

f. Replacement of both emergency diesel generator lube oil keep warm pumps.

g. Sludge lancing all steam generators.

h. Modifiying the pressurizer power operated relief valves.

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1. MOVATS testing of certain motor operated valves.

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j. Reworking, replacing and repacking of various valves.

k. Annual surveillances of safety related pumps.

1. Replacement of seals on both centrifugal charging pumps.

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[ m. Annual maintenance of ventilation dampers.

n. Annual surveillance of switchgear.

o. Repair of diesel generator fuel oil leaks.

p. Replacing both Boric Acid Storage Tank diaphragms.

q. Conducting inspections for Microbiological Induced Corrosion.

r. Replacement of level transmitters and flow transmitters.

s. Replacement of circuit boards.

12. Outage Start Date: 12/21/86 Completion Date: 12/21/86 Type: Scheduled Duration: 0.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 5 Reason: Unit taken off line to conduct turbine overspeed test.

13. Outage Start Date: 12/22/86 Cmpletion Date: 12/22/86 Type: Forced Duration: 13.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> Reason: Failure of 'A' Main Feedwater Flow Transmitter caused a high steam generator level Turbine Trip and Reactor Trip.

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• 3. EXPOSURE INFORMATION A. NLNBER OF PERSONNEL AND MAN-REM BY WORK AND JOB FU?CTION REPORT - 1986 tRJMBER OF PERSONNEL (>100 MREM) 'IUPAL MAN-REN WORK & JOB FUNCTION STATION ITfILITY C0tTTRACT STATION ITTILITY COfffRACT Reactocpperations& Surveillance MainEenance & Construction 2 0 0 1.951 0.000 .642 Operations 13 0 0 3.883 0.000 .152 Health Physics & Lab 22 0 31 6.839 0.000 8.888 Supervisory & Office Staff 2 0 1 .983 .168 .367 Engineering Staff 0 1 2 .526 .288 .472 Routine Elant Maintenance Maintenance & Construction 26 0 9 7.638 .014 5.436 Operations 0 0 0 .121 0.000 .003 Health Physics & Lab 7 0 3 1.782 0.000 1.478 Supervisory & Office Staff 0 0 0 .470 .006 .382 Engineering Staff 0 0 1 .297 .007 .339 Inservice Inspection Maintenance & Construction 1- 0 48 .760 0.000 14.136 Operations 0 0 0 .063 0.000 .026 Health Physics & Lab 1 0 1 .508 0.000 .715 Supervisory & Office Staff 3 0 5 .948 .019 2.000 Engineering Staff 1 0 12 .319 .027 4.671

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Special Plant Maintenance Maintenance & Construction 44 0 69 13.604 .086 18.929

. Operations 0 0 0 .488 -0.000 .020 Health Physics & Lab 10 0 2 2.084 0.000 .888 Supervisory & Office Staff 9 0 3 2.484 .106 1.227 Engineering Staff 1 0 2 .429 0.000 .825 Waste Processing Maintenance & Construction 2 0 0 1.005 0.000 .265 Operations 0 0 0 .105 0.000 .019 Health Physics & Lab 8 0 4 3.327 0.000 1.774 Supervisory & Office Staff G 0 0 .039 .002 .002 Engineering Staff 0 0 0 0.000 .043 0.000 Refueling

' Maintenance & Construction 20 0 23 7.960 .007 7.617 Operations 5 0 0 .991 0.000 0.000 Health Physics & Lab 0 0 0 .122 0.000 .281 Supervisory & Office Staff 3 0 1 .790 .006 .348 Engineering Staff 0 0 2 .135 0.000 .909 Tbtals Maintenance & Construction 79 1 120 32.918 .108 47.025 Operations 21 0 0 5.696 0.000 .220 Health Physics & Lab 30 0 43 14.661 0.000 14.024 Supervisory & Office Staff 15 1 12 5.714 .307 4.327 Engineering Staff 4 1 21 1.707 .365 7.217 Grand Tbtals 149 3 196 60.696 .780 72.813 Page 7 of 9

B. PERSONNEL MONITORING REPORT

1. In 1986, 1532 individuals were provided personnel monitoring devices. This information is provided in accordance with paragraph (a) (2) of 10CFR 20.407. This total includes the number of individuals required to be reported under paragraph (a) (1) of this section.

2. Below is a statistical summary report of the personnel monitoring information recorded for individuals for whom personnel monitoring was provided in 1986 in accordance with the requirements of 10CFR 20.407(b) .

Number of Estimated whole body exposure range individuals in (rems) each range No measurable exposure.................................................. 851 Measu rable exposure less than 0.1. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 30 0.1 to 0.25............................................................. 160 0.25 to 0.5............................................................. 121 0.5 to 0.75..............................................................

47 0.75 to 1.0.............................................................. 18 1.0 to 2.0................................................................ 5 2.0 to 3.0................................................................ 0 3.0 to 4.0................................................................ 0 4.0 to 5.0................................................................ 0 0

5.0 to 6.0................................................................

0 6.0 to 7.0................................................................

0 7.0 to 8.0................................................................

0 8.0 to 9.0................................................................

0 9.0 to 10.0...............................................................

10.0 to 11.0.............................................................. 0 11.0 to 12.0.............................................................. 0 12 + ..................................................................... 0 Page 8 of 9

C. SOURCE OF DATA

%e information provided in Section 3.A is based on estimated exposures obtained from Pocket Ionization Chamber readings. The information provided in Section 3.B.2 is obtained from Thermal Luminescent 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 mrem exposure during 1986 in the two sections. H is discrepancy resulted form the two different I sources of exposure information utilized to determine the totals.

4. INDICATIONS OF FAILED FUEL During 1986, visual examinations of irradiated fuel were performed and there were no indications of failed fuel.

5. CIALLENGES TO TIIE PORV'S AND SAFLTI VALVfB A. On February 22, 1986, a Turbine Trip, Reactor Trip occurred from 100 percent reactor power. The cause of the event was a circuit failure in the Main Turbine electro-hydraulic control system. The pressurizer Power Operated Relief Valves lif ted to control Reactor Coolant System pressure. (Licensee Event Report 86-007-00)

B. On June 30, 1986, a Turbine Trip, Reactor Trip occurred from 100 percent power. The initiating signal was low Main Condensor Invel which occurred during testing of the Main Condensor level transmitters, causing all condensate pumps to trip. The pressurizer l Power Operated Relief Valves lifted to control Reactor Coolant System pressure. (Licensee Event Report 86-038-00) f Page 9 of 9

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W6LF i CREEK NUCLEAR OPERATING CORPORATION February 25,1987 U.S. Nuclear Regulatory Comission ATTN

Document Control Desk Washington, D.C. 20555 Letter: WM 87-0059 Re: Docket No. 50-482 Subj: Annual Operating Report for Wolf Creek Generating Station

- Gentlemen:

The attached Annual Operating Report is being submitted pursuant to Wolf Creek Generating Station, Unit No. 1, Technical Specifications 6.9.1.4 and 6.9.1.5. This report covers operations for the period of January 1, 1986, to December 31, 1986.

Very truly yours,

2 2 Bart D. Withers, President and Chief Executive Officer BDN:jad Attach cc: P0'Connor (2)

JCumins R% rtin SGUI uff PO. Dex 411/ Durtington. KS 66839 ' Phone. (316) 364-8831 e Equal Opportundy Employer M F HC VET

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