ML20205D372

Monthly Operating Rept for May 1986

ML20205D372
Person / Time
Site:	Wolf Creek
Issue date:	05/31/1986
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-86-107, NUDOCS 8608150341
Download: ML20205D372 (9)

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i WDLP CREEK GENERATING STATION MONIHLY OPERATING REPORT MNIN:

May YEAR: 1986 Docket No.: SIN 50-482 Facility Operating License No.: NPF-42 Report No.

15 1

Subnitted by:

l Kansas Gas and Electric Company l

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%e following report highlights the operating experience of Wblf Creek Generating Station for the month of May, 1986. % is report is being provided pursuant to Technical Specification 6.9.1.8.

I.

SUMERY OF OPERATING EXPERIl!NCE te unit operated in Mode 1, Power Operation, throughout the month of May. On May 2, Condensate Pump "A" was removed from service, limiting reactor power to about 94 percent until its return on May 25. On May-16, a power reduction was connenced when it was discovered that Limitorque operators for valves on both safety trains had Equipment Qualification problems. A shutdown was averted by the prompt repair of all valves on one train and the power reduction was halted at 43 percent. mis power level was held until all valves were repaired later that day. On May 24, reactor power was reduced to 30 percent when Steen Generator chemistry entered a self-imposed Action Imvel II while preparing to return Condensate Pump "A" to service. We chenistry was corrected and a power ranp began shortly after midnight that night.

II.

MMOR SAFETY REIATED MAIlffENANCE ACTIVITIES

% e major safety related maintenance activities performed during May included replacement of fuel pool cooling valve EC V081, replacement of the Fuel Building Dnergency Exhaust filter adsorber pre-filter section, replacement of wire jumpers in several Limitorque valve operators to correct Equipnent Qualification discrepancies, adjustment of Limitorque operators for Auxiliary Peedwater valves AL W-30, AL W-31, AL W-32 and AL W-33 and plugging of leaking tubes in central chiller SGB01A.

%e Instrument arri Control group replaced the I/P converter on atmospheric dunp valves AB W-1 and AB W-2 and replaced the vacuun punp on radiation monitor Gr RE-33.

III. CHANGES, TESTS, AND EXPERIMDfrS

%e Monthly Operating Report for March,1986, erroneously reported that a safety evaluation was performed for Plant Modification Request

1. 01591 pursuant to 10 CFR 50.59 on changes, tests and experiments. An evaluation of Plant Modification Request #01591 determined that a safety evaluation was not required.

We followiruj is a brief description of safety evaluations performed pursuant to 10 CPR 50.59 on changes, tests, and experiments during the month of May.

1.

Plant mdification Request #01652 - Originated to allow replacement of the 1/3 horsepower vacuan sanple punp with one rated at 1/2 horsepower on 10 process radiation monitors. Certain mechanical arti electrical conponents were also changed to acconnodate the latqer punp. No unreviewed safety or enviror1 mental questions are generated as a result of this plant modification.

r 2.

Plant mdification Request #01663 - Originated to provide an external port connecting the solenoid valve upper port to the chamber above the valve pitxj on both pressurizer pilot operated relief valves BB PCV-455A and BB PCV-456A. No unreviewed safety or environmental questions are generated as a result of this plant modification.

3.

Plant Modification Request #01669 - Originated to increase the maximta stroke times for Auxiliary Feedwater System valves E W-30, E W-31, E W-32 and E HV-33 frca 15 to 18 seconds. No unreviewed safety or envirornental questions are generated as a result of this plant modification.

4.

Safety Evaluation 86-SE Origi.nated to allow deletion of particulate and iodine portions of the Analog Channel Operation test on Contairnent Radiation Monitor Gr IE-32 while these portions of the Radiation mnitor are inoperable. No unreviewed safety or envirornental questions are generated as a result of this tmporary surveillance test procedure change.

5.

Safety Evaluation 86-SE Originated to replace the pump casing drain line with a plug on Reactor Make-Up Water Ptap PBL0lB. No unreviewed safety or envirornental questions are generated as a result of this temporary modification.

6.

Safety Evaluation 86-SE Originated to allow attaching stainless steel tubing to the telltale leak-off hole in the Positive Displacment Charging Pump discharge relief valve in order to quantify the leak-off. No unreviewed safety or envirornental questions are generated as a result of this temporary modification.

7.

Safety Evaluation 86-SE Originated to allow replacement of a drain line with a plug on Control Building air conditioning heat exchanger SGK05A. No unreviewed safety or envirornental questions are generated as a result of this tm porary modification.

8.

Safety Evaluation 86-SE Originated to allow replacm ent of the diaphrm on Steam Generator "C" blowdown control valve BM HV003 with a diaphram from the same manufacturer with the see form, fit and shape but not certified as an identical replacement. %is valve fails closed on a loss of,diaphrm. No unreviewed safety or environmental questions are generated as a result of this tmporary modification.

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Safety Evaluation 86--SE Originated to allow defeating a faulty isolation signal.fra Steam Generator Blowdown Radiation m nitor IM RE-52 while the monitor is out of service. No unreviewed safety or enviromental questions are generated as a result of this tm porary modification.

10. Safety Evaluation 86-SE Originated to allow defeating the Turbine setback on loss of Circulation Water Pump. No unreviewed safety or enviromental questions are generated as a result of this tmporary modification,

11. Safety Evaluation 86-SE-50, Revision 1 - Originated to provide supplemental information concerning the gagging of relief valve HB-7160. No unreviewed safety or environmental questions are generated as a result of this temporary modification.

12. Plant mdification Request #00590, Revision 1 - Originated to allow the use of existing junction boxes to house the splices for the high tmperature pigtails running to the 12 Stem Dump Valves, AB HYO34 thru AB HYO45. No unreviewed safety or enviromental questions are generated as a result of this plant modification.

13. Plant Modification Request #01624 - Originated to provide a positive means for venting starting air frm the rack boost cylinder and associated shuttle valves to prevent potential overspeed shuLiown of the mergency diesel engines. No unreviewed safety or enviromental questions are generated as a result of this plant modification.

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OPERATING DATA REIORT DOCKET NO, S'IN.50-482 WOLF CREEK GENERATING STATIOi KANSAS GAS AND ELECTRIC COMPANY DATE 06-01-86 00MPLETTED BY M. Willians TELEPHONE 316-364-8831 OPERATING STATUS 1.

Reporting Period:

May, 1986 Gross Hours in Reporting Period: 744 2.

Currently Authorized Power Level (mit): 3411 Max. Depend. Capacity (MWe-Net) : 1128 Design Electrical Rating (MWe-Net):

1170

'3.

Power Level to Which Restricted (If Any)(ME-Net):

N/A 4.

Reasons for restriction (If Any):.

WA his Month Yr to Date CtInulative 5.

Number of Hours Reactor was Critical 744.0 3183 2 5973.5 6.

Reactor Reserve Shutdown Hours 0.0 41.4 120.2 7.

Hours Generator on Line 744.0 3166.7 5938.3 8.

Unit Reserve Shutdown Hours 0.0 0.0 0.0 9.

Gross Wennal Energy Generated (M) 2,341,310 10,273,932 19,148,865

10. Grocs Electrical Energy Generated (MWH) 816,892 3,610,280 6,681,370

11. Net Electrical Energy Generated (M) 783,932 3,455,305 6,397,405

12. Reactor Service Factor 100.0 87.9 91.9-

13. Reactor Availability Factor 100.0 89.0 93.?

14. Unit Service Factor 100.0 87.4 91.3

15. Unit Availability Factor 100.0 87.4 91.3

16. Unit Capacity Factor (Using MDC) 93.4 84.5 87.2

17. Unit Capacity Factor (Using Design MWe) 90.1 81.5 84.1 18 Unit Forced Outage Rate 0.0 2.4 3.0

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

Refueling Outage, currently scheduled to start on October 9,1986, approximate duration is 55 days.

20. ~ If Shut Down at End of Report Period, Estimated Date of Startup:

N/A

21. Units in test Status (Prior to Connercial Operation): Forecast Achieved Initial Criticality 5-22-85 5-22-85 Initial Electricity 6-13-85 6-12-85 Commercial Operation 9-09-85 9-03-85 Page 4 of 7

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

S'IN 50-482 WOLF CREEK GENERATING STATION KANSAS GAS AND ELECTRIC COMPANY s

DATE 06-01-86 COMPLETED BY M. Williams" TELEPHONE 316-364-8831 t

MOR1H May, 1986 u

DAY AVERAGE DAILY POWER LlWEL DAY AVERAGE DAILY R)WER LEVEL (We-Net) i (Me-Net) 1 1

1138 17 1070 2

1133 18 1069 3

1155 19 1068 4

1155 20 1065 5

1152 21 1062 6

1051 22 1061 7

1052 23 1061

,8_

1052 24 550 9

1060 25 986 10 1063 26 1133 11 1062 27 1141 12 1064 28 1140 13 1061 29 1137 g

14' 1061 30 1135 15 1061 31 1132 16 795 Page 5 of 7

- - _ _ -. - - - _ - - =. _..

UNIT SHUIDOWN AND POWER REDUCTIONS DOCKET NO.

SIN 50-4h2 NOLF CREEK GENERATING STATICH KANSAS GAS AND EIECTRIC COMPANY DATE 06-01-86 COMPIETED BY M. Willians REPORT MONTH May, 1986 TELEPHONE 316-364-8831 TYPE METHODS SHUTTING

{

F: FORCED DURATION REASCN DOWN 'INE REACTOR CORRECTIVE ACTIONS /COPMENTS No Date S: SCHEDULED (HOURS)

(1)

OR REDUCING POWER (2) 4 860516 F

0 F

1 Correct Equip 1ent Qualification discrepancies 5

860524 F

0 F

1 Correct Stean Generator chemistry I

SLDGERY: On May 16, 1986, Equipnent Qualification discrepancies were discovered in Limitorque operators in both safety trains. A shutdown was averted by pranpt correction of discrepancies on one train. On May 24, 1986, power was reduced to 30 percent while Stean Generator chenistry was brought back into specification.

(1)

REASON: A: EQUIPMENT FAILURE (EXPLAIN)

E: OPERATOR TRAINING AND LICENSE EXAMINATION (2)

MEIROD:

1.

MANUAL B: MAINTENANCE OR TEST F: ADMINISTRATIVE 2.

MANUAL SCRAM C: REFUELIII; G: OPERATIONAL ERROR (EXPIAIN) 3.

AUIOMATIC SCRAM D: REGULATORY RESTRICTION H: OIEER (EXPLAIN) 4.

01EER (EXPLAIN)

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r KANSAS GAS AND CLECTRIC COMPANY WOLF CREEK GENERATING STATION UNIT NO. 1 MONIH May, 1986 SUIEARY OF OPERATING EXPERIENCE Listed below in chronological sequence is a stenary of operating experiences for this month which required load reduction or resulted in significant non-load related incidents.

DA'IE TIME EVENT Hay 1, 1986 0001 Unit in Mode 1, Power Operation.

May 16, 1986 1000 Connenced reducing power due to Equipnent Qualification problems in Limitorque Operators.

1242 Power reduction was halted at 43 percent when one train was corrected.

14'08 With all Limitorque discrepancies corrected, began power increase.

May 24, 1986 0700 Began reducing power to 30 percent while correcting Stean Generator chemistry.

May 25, 1986 0020 Comnenced increasiry power, all Stear. Generator chemistry is in specification.

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KANSAS GAS AND ELECTRIC COMPANY THE ELECmC COMPANY GLENN L MOESTER w<f tssoth?.Nocteae June 13, 1986 Director, Office of Resource Management U.S. Nuclear Regulatory Comission Washington, D.C.

20555 Mr. E.H. Johnson, Director Division of Reactor Safety and Projects U.S. Nuclear Regulatory Cmmission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 KMLNRC 86-107 Re:

Docket No. STN 50-482 Subj: May, 1986 Monthly Operating Report Gentlemen:

Enclosed is the May, 1986 Monthly Operating Report for Wolf Creek Generating Station.

This subnittal is being made in accordance with the requirements of Technical Specification 6.9.1.8.

i Yours very truly, l

Glenn L. Koester Vice President - Nuclear GLK:see Enclosure cc: PO'Connor (2), w/a JTaylor (12), w/a JCumins, w/a J

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o 201 N. Market - Wrchtta, Kansas - Mail Address: RO. Box 206 I Wrchtta, Kansas 67201 - Telephone: Area Code (316) 261-6451

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