ML20214P551

Monthly Operating Rept for Aug 1986

ML20214P551
Person / Time
Site:	Wolf Creek
Issue date:	08/31/1986
From:	Koester G, Mike Williams KANSAS GAS & ELECTRIC CO.
To:	Johnson E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV), NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
KMLNRC-86-168, NUDOCS 8609230239
Download: ML20214P551 (9)

Text

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..e eo WOLF CREEK GENERATING STATION M0tmlLY OPERATING REPORT MON 1H: Atsust YEAR: 1986 Docket No.: S'IN 50-482 Facility Operating License No.: NPF-42 Report No. 18 Subnitted by:

Kansas Gas and Electric Company

/a f, h 8609230239 860831 ((,

PDR ADOCK 05000482 R PDR

te following report highlights the operating experience of Wolf Creek Generating-Station for the month of August, 1986. This report is being

-provided pursuant to Technical Specification 6.9.1.8.

SU191ARY OF OPERATING EXPERIENCE 4

.I.-

During the entire month of August, 1986, the unit operated in Mode 1, Power Operation. . On August 1, unit' power was reduced to 75 percent due to ~a storm causing the loss of the Rose Hill line. Unit power was increased to 100 percent on August 2. . Unit power was reduced to 90 percent on August 17 to allow repair of "B" Circulating Water Pmp oil cooler.- W is repair was completed on August 18. A failure in "B" Condensate Pump Motor on August 21 caused a power reduction to about 94 percent. During this repair effort, power was further reduced for

, about 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> on August 23-24 to allow repair of "A" Main Feedwater Pep recirculation pipirg. Unit power was returned to 100 percent on August 28.

II. MAJOR SAFETfY RELATED MAINTENANCE ACTIVITIES A leak developed on the Steam Generator blowdown piping which was weld repaired. A pmp was replaced on radiation monitor GG-RE-28. A leaky

. fittire on the Chemical volme and Control System flow transmitter BG-FT-143 was reworked.

b III. CHANGES, TESTS, AND EXPERIMENTS

%e following is a brief description of safety evaluations performed pursuant to 10 CFR 50.59 on changes, tests, and experiments during the month of August.

1. Proposed revision to Technical Specifications 3/4.8 - Originated

'to reduce tha emergency diesel testing requirements to cmply with manufacturer reconnendations and reduce unnecessary wear on the 1-ergines due to testirs. No unreviewed safety or enviromental questions are generated as a result of this Technical Specification proposed revision.

! 2. Safety Evaluation 86-SE Originated to provide a temporary  !

access to the Auxiliary Building from the Comnunications Corridor via rom 1403 on the 2026 foot elevation during the refueling

, outage. No unreviewed safety or enviromental questions are generated as a result of this temporary modification.

3. Safety Evaluation 86-SE Originated to disable the local alarm

bell for the Fire Protection System remote panel KC 257, which controls the preaction valve for sme cable trays on the 2000 foot

} elevation of the Auxiliary Building. No fire detection or suppression capability is affected. No unreviewed safety or i enviromental questions are generated as a result of this temporary modification.

4. Safety Evaluation 86-SE Originated to allow the use of

, temporary peps in the Turbine Building condensate pit smps. No unreviewed safety or environmental questions are generated as a result of this temporary modification.

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5. Safety Evaluation 86-SE Originated to allow the temporary use of a non-nuclear safety grade capacity control valve on the Control Doom air conditioning unit SGK04B. No unreviewed safety or enviromental questions are generated as a result of this tmporary modification.

6. Safety Evaluation 86-SE-102 - Originated to provide a temporary rack to hold the Westinghouse BPRA tool and RCCA tool in the Cask Ioading Pit. No unreviewed safety or enviromental questions are generated as a result of this temporary modification.

7. Safety Evaluation 86-SE-103 - Originated to allow the temporary-installation of an air empressor on the breathing air systs. No unreviewed safety or enviromental questions are generated as a result of this temporary modification.

8. Safety Evaluation 86-SE-104 - Originated to allow installing hardware to provide access from either side of doors 32051, 32071, 32091 and 32111. No unreviewed safety or enviromental questions are generated as a result of this temporary modification.

9. Safety Evaluation 86-SE-106 - Originated to allow temporary replacement of the o-ring seal on the pmp side of the coupliry on Auxiliary Feedwater Pmp, PAIMB, with a commercial grade o-ring until a replacement can be obtained frm the vendor. No unreviewed safety or environmental questions are generated as a result of this temporary modification.

10. Safety Evaluation 86-SE-107 - Originated to replace the caps at valves SPC002 and SPC003 with Swagelok Quick-Connects to facilitate obtaining tritin grab samples. No unreviewed safety or environmental questions are generated as a result of this temporary modification.

11. Safety Evaluation 86-SE-108 - Originated to replace the plugs at valves SPC001 and GSV030 with Swagelok Quick-Connects to facilitate obtaining tritim grab samples. No unreviewed safety or environmental questions are generated as a result of this temporary modification.

12. Safety Evaluation 86-SE-110 - Originated to replace Safety Evaluation 85-SE-33 which contained a statement that cauld be misinterpreted. It concerns a change to Surveillance Test Procedure STS-IC-925 which allows using Essential Service Water peps to test the flow thru the Contaiment Coolers. No unreviewed safety or environmental questions are generated as a result of this temporary procedure change.

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13. Safety Evaluation 86-SE-lll - Originated to allow defeating the isolation signal from radiation monitor BM-RE-52 while awaitirg test equipnent repair. 'Ihere is no flow thru the. system that is monitored by BM-RE-52. Should flow be initiated, action 32 of Technical Specifications 3.3.3.10 would be entered. No unreviewed safety or environmental questions are generated as a result of this temporary modification.

14. Plant Modification Request KN84-044 - Originated to replace the heaters in.the Fuel Building ventilation system with electric heaters. No unreviewed safety or envirormental questions are generated as a result of this plant modification.

15. Plant ledification Request 01157 - Originated to provide a fire barrier in the floor openings in the Auxiliary Buildirg which provide access to the contairnent post-tensioning system tendons.

No unreviewed safety or environnental questions are generated as a result of this plant modification.

16. Plant Modification Request 01634 - Originated to provide an isolation valve for the Reactor Coolant Drain Tank reli~ef valve. The isolation valve would normally be locked open. No unreviewed safety or environmental questions are generated as a result of this plant modification.

17. Plant Modification Request 01683 - Originated to replace a vendor supplied jtuper wire in seven Limitorque operators. No unreviewed safety or environmental questions are generated as a result of this plant modification. ,

18. Plant Ltdification Request 01683, Revision 1 - Originated to add five Limitorque operators. No unreviewed safety or environmental questions are generated as a result of this plant modification.

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OPERATING DATA REPORP DOCKE7f NO. STN 50-482 WOLF CREEK GENERATING STATIOi KANSAS GAS'AND ELECTRIC COMPANY DATE 09-01-86

. COMPLETED BY M. Williams TELEPHONE 316-364-8831 OPERATING STATUS

1. Reporting Period: August, 1986 Gross Hours in Reportirg Period: 744 i

'2.

Currently Authorized Power Level (MWt): 3411 Max. Depend. Capacity (MWe-Net): 1128 i

Design Electrical Rating (MWe-Net): 1170

3. Power Ievel to Which Restricted (If Any)(Mwe-Net): N/A

4. Reasons for restriction (If Any): N/A

'Ihis Month Yr to Date Cunulative

5. Number of Hours Reactor was Critical 744.0 5133.6 7923.9

6. Reactor Reserve Shutdown Hours 0.0 92.5- 171.3

7. Hours Generator on Line 744.0 5096.4 7868.0

-8.- Unit Reserve Shutdown Hours 0.0 0.0 0.0

9. Gross Thermal Energy Generated (MHH) 2,439,547 16,593,833 25,468,766 10.' Gross Electrical Energy Generated (MWH) 846,083 5,792,888 8,863,978

11. Net Electrical Energy Generated (MWH) 812,042 5,539,528 8,481,628

12. Reactor Service Factor 100.0 88.0 91.0

13. Reactor Availability Factor 100.0 89.6 92.9

14. Unit Service Factor 100.0 87.4 90.3

15. Unit Availability Factor 100.0 87.4 90.3

. 16. Unit Capacity Factor (Using MDC) 96.8 84.2 86.3

17. Unit Capacity Factor (Using Design MWe) 93.3 81.2 83.2

18. Unit Forced Outage Rate 0.0 5.4 4.8

, 19. Shutdowns Scheduled Over Next 6 2nths (Type, Date, and Duration of each):

Refueling Outage, currently scheduled to start on October 16, 1986, approximate duration is 55 days.

20. If Shut Down at End of Report Period, Estimated Date of Startup: N/A i 21. Units in test Status (Prior to Ccmnercial Operation): Forecast Achieved

, Initial Criticality 5-22-85 5-22-85 Initial Electricity 6-13-85 6-12-85

Comnercial Operation 9-09-85 9-03-85 Page 4 of 7

1 AVERAGE DAILY LWIT POWER LEVEL DOCKET NO. SIN 50-482_

WOLF CREEK GENERATING STATIOi KANSAS GAS AND ELECTRIC COMPANY

-DATE 09-01-86 COMPLETED BY M. Williams TELEPHONE 316-364-8831 MONIH August, 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL

-(MWe-Net) (MWe-Net) 1 1045 17 1061 2 1007 18 1058 1128 19 1115 4 1130 20 1133 5 1134 21 1074 6 1133 22 1063 7- 1133 23 1013 8 1131 24 729 9 1134 25 996 10 1136 26 1047 11 1135 27 1063 12 1136 28 1099

13 1137 29 1139 14 1138 30 1140 15 1138 31 1141

, 16 1137 Page 5 of 7

.. g

. UNIT SHUITXXt1 AND 10WER REDUCTIONS- /

DOCKET NO. STN 50-482 WOLF CREEK GENERATING STATICN .

KANSAS GAS AND ELECTRIC COMPANY ,

DATE '09-01-86 REPORP M0ffIE 00MPIEfED BY M. Williams August, 1986 TELEPHONE 316-364-8831 TYPE METHODS SHUITING F: FORCED DURATION REASON DOR 4 THE RFAC'IOR CORRECPIVE ACTIONS /COPMENPS No Date S: SCHEDULED (HOURS) (1) OR REDUCING POWER (2) 10 860823 F 0.0 A 4 Power reduction to 45 percent to allow repair of A" Main

l. Feedwater Pmp recirculation pipe.

1 i

l SIEMARY: On August 23, 1986, power was reduced to 45% to allow repair of "A" Main Feedwater Pmp recirculation pipe.

(1) REASON: A: EQUIPMENP FAILURE (EXPIAIN) E: OPERNIOR TRAINING AND LICENSE EXAMINATION METIHt;D: 1.

(2) MANUAL B: MAINTENANCE OR TFSF F: ADMINISTRATIVE 2. MANUAL SCRAM C: REFUELING G: OPERATIONAL ERROR (EXPIAIN) 3. AUf0MATIC SCRAM D: REGUIA'IORY RESTRICTION H: 01EER . (EXPLAIN) 4. . OTHER (EXPIAIN)

Page.6 of 7

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KANSAS GAS AND ELECTRIC COMPANY WOLF CREEK GENERATING SIATION-UNIT NO. 1 MONTH August, 1986 SUl9(ARY.OF OPERATING EXPERIENCE Listed below in chronological sequence is a sumnary of operatiry experiences for this month which' required load reduction or resulted in significant non-load related incidents.

DATE TIME EVENP August 1,1986 0001 Unit in Mode 1, Power Operation 1710 Reduced power to about 75 percent due to loss of Rose Hill line fran stonn danage.

August 2, 1986 0745 Comnenced increasing power to 100 percent.

August 17, 1986 0930 Reduced power to 90 percent to repair "B" CWP motor August 18, 1986 0845 Cannenced increasing power to 100 percent August 21, 1986 0433 Reduced power to 94 percent to repair "B" Condensate Punp August 23, 1986 2051 Reduced power to 45 percent to repair "A" MFP recirculation pipe.

August 24, 1986 0545 Connenced increasing power to 94 percent August 28, 1986 1039 Comnenced increasing power to 100 percent i

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,,..=d KANSAS GAS AND ELECTRIC COMPANY THE ELEC1 AC COMPANY GLENN L MOESTER ver *mEseEmY - hvCLE A8' September 15, 1986 Director, Office of Resource Management U.S. Nuclear Regulatory Commission  :

b- 4 }

Washington, D.C. 20555 js '

i l SEP l 8lg86 Mr. E. H. Johnson, Director

, :N Division of Reactor Safety and Projects U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 KMLNRC 86-168 Re Docket No. STN 50-482 Subj: August, 1986 Monthly Operating Report Gentlemen:

Enclosed is the August, 1986 Monthly Operating Report for Wolf Creek Generating Station. This submittal is being made in accordance with the requirements of Technical Specification 6.9.1.8.

Yours very truly,

[ tt4, Glenn L. Koe ter Vice President - Nuclear GLK:see Enclosure cc: P0'Connor (2), w/a JTaylor (12), w/a JCummins, w/a i

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