ML20207F853

Monthly Operating Rept for June 1986

ML20207F853
Person / Time
Site:	Wolf Creek
Issue date:	06/30/1986
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-86-127, NUDOCS 8607220625
Download: ML20207F853 (9)

Text

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s WOLF CREEK GENERATING STATION MONIELY OPERATING REPORP MONIH:

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

16 Submitted by:

Kansas Gas and Electric Company l

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

I.

SUMMARY

OF OPEBATING EXPERIENCE t e unit operated in mde 1, Power Operation, until June 3, when a plant shutdown was comenced to allow replacing wiring in certain Limitorque valve operators. We unit returned to mde 1 on June 11.

On June 17, Circulating Water Pump "A" was removed frm service for about five hours, limiting reactor power to 90 percent. On June 19, a power reduction was ccanenced due to an apparent loss of the Solid State Protection System. A shutdown was averted when the cause was identified and the power reduction was halted at 52 percent reactor power. m is power level was held for 41 minutes, until operability testing was completed. On June 21, reactor power was reduced to about 45 percent for three hours to allow repair of a Reactor Coolant Systs flow transmitter. On June 30, a reactor trip was experienced due to a low-low condenser hotwell level signal.

II.

MAJOR SAFEIT RELATED MAINTENANCE ACTIVITIES The major safety related maintenance activities performed during June 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 HVAC unit.

III. CHANGES, TESTS, AND EXPERIMENIS We following is a brief description of safety evaluations performed pursuant to 10 CFR 50.59 on changes, tests, and experiments during the month of June.

i 1.

Safety Evaluation 86-SE Originated to allow operating the plant in Mode 2, Startup, with the Main Steamline Isolation Valves l

and Main Feedwater Isolation Valves closed while releasing steam through one atmospheric steam dump valve and feeding that Steam l

Generator frm the Auxiliary Feedwater System. No unreviewed l

safety or envirormental questions are generated as a result of this tmporary procedure charege.

2.

S&fety Evaluation 86-SE Originated to change the l

responsibility of the warehouse and associated activities frm the l

j Superintendent of Maintenance to the Procurement and Materials l

Manager. No unreviewed safety or enviromental questions are generated as a result of this temporary procedure change.

3.

Safety Evaluation 86-SE Originated to allow connection of a piping jumper, consisting of a check valve, strainer and hose from one inch drain valve LF-V078 to one inen drain valve HB-V009 so that the Liquid Radwaste System may be used to remove water frm the Containment Normal Sumps while Incal Leak Rate Testing is being con 3ucted on the normal flow path at penetration P-32.

No unreviewed safety or environmental questions are generated as a l

result of this temporary modification.

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4.

Safety Evaluation 86-SE Originated to allow mnnection of a hose batween BG-V454 and BG-V580 to provide an alternate flow path for Reactor Coolant Pump (RCP) seal return flow to the Reactor Coolant Drain Tank while stroke testing the seal return Contairrnent Isolation Valves during RCP operation. No unreviewed safety or environmental questions are generated as a result of this special test procedure.

5.

Safety Evaluation 86-SE Originated to allow a stroke test of Residual Heat Removal valves EJ HV-8701A, EJ HV-8701B, BB PV-8702A and BB PV-8702B while the plant is being maintair.ed in Pbde 3, Hot Standby. No unreviewed safety or environmental questions are generated as a result of this temporary procedure change.

6.

Safety Evaluation 86-SE Originated to allow the replacement of the Safety Grade gasket on the Control Building air conditioning unit canpressor heat exchanger with a comnercial grade gasket of the sane form, fit, function, material and manufacturer. No unreviewed safety or environmental questions are generated as a result of this temporary modification.

7.

Safety Evaluation 86-SE Originated to allow the installation of a pressure gage on Service Water header vent valve EA-V107. No unreviewed safety or environmental questions are generated as a result of this temporary modification.

8.

Plant Modification Request 01619 - Originated to modify the Recycle Evaporator sample line HE-ll8-HCD-3/4". No unreviewed safety or environmental questions are generated as a result of this plant modification.

9.

Plant ibdification Request 01658 - Originated to allow the use of alternate part numbers on two gaskets for the motor driven Auxiliary Feedwater Ptunps. No unreviewed safety or environmental question <3 are generated as a result of this plant modification.

10. Safety Dialuation KELKNP 86-1001 - Originated to allow an experimental application of aquatic herbicide Aquathol K to approximately 1 1/3 acres of the Wolf Creek cooling lake intake cove for the control of sunnerged macrophytes. No unreviewed safety or environmental questions are generated as a result of this experimental application.

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f.

OPEPATING DATA REPORT DOCKET NO. STN 50-482 WOLF CREEK GENERATING STATION KANSAS GAS AND ELECTRIC COMPANY DATE 07-01-86 COMPLETED BY M. Willians TELEPHONE 316-364-8831 OPERATING STATUS 1.

Reporting Period:

June, 1986 Gross Hours in Reporting Period: 720 2.

Currently Authorized Power Level (MWt): 3411 Max. Depend. Capacity (MWe-Net): 1128 Design Electrical Rating (MWe-Net): 1170 3.

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

N/A 4.

Reasons for restriction (If Any):

N/A

'1his lenth Yr to Date Cunulative 5.

Number of Hours Reactor was Critical 522.7 3705.9 6496.2 6.

Reactor Reserve Shutdown Hours 0.0 41.4 120.2 7.

Hours Generator on Line 520.9 3687.6 6459.2 8.

Unit Reserve Shutdown Hours 0.0 0.0 0.0 9.

Gross Thermal Energy Generated (MWH) 1,670,026 11,943,958 20,818,891

10. Gross Electrical Energy Generated (MWH) 574,255 4,184,535 7,255,625

11. Net Electrical Energy Generated (MWH) 543,798 3,999,103 6,941,203_

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12. Reactor Service Factor 72.6 85.3 89.9

13. Reactor Availability Factor 72.6 86.3 91.6 l

14. Unit Service Factor 72.3 84.9 89.4 f

15. Unit Availability Factor 72.3 84.9 89.4

16. Unit Capacity Factor (Using MDC) 67.0 81.6 85.2

17. Unit Capacity Factor (Using Design MWe) 64.6 78.7 82.1 1

18. Unit Forced Outage Rate 27.7 7.0 5.6

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:

7-01-86

21. Units in test Status (Prior to Camercial 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 Pge 3 of 7 l

AVERAGE DAILY UNIT POWER LEVEL-DOCKfr NO.

SIN 50-482 WOLF CREEK GENERATING STATION KANSAS GAS AND ELECTRIC COMPANY DATE 07-01-86 CDMPLETED BY M. Willians TELEPHONE 316-364-8831 MONIH June,1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(Mie-Net) 1 1100 17 1073 2

1124 18 1011 3

961 19 998 4

0 20 1121 5

0 21 1092 6

0 22 1064 7

0 23 1121 8

0 24 1125 9

0 25 1124 10 0

26 1124 11 18 27 1122 12 368 28 1122 i

13 1111 29 1120 14 1130 30 632 15 1128 31 N/A 16 1126 Page 4 of 7

9 UNIT SIRJIDOWN AND POWER REDUCTIONS DOCKET NO.

S'IN 50-482 WOLF CREEK GENERATING STATION KANSAS GAS AND ELECTRIC COMPANY DATE 07-01-86 00MPIETED BY M. Willims REIORT M07I11 June, 1986 TEIEPHONE 316-364-8831 i

TYPE MF1IllODS SERTITING P: FORCED DURATION REASON DOWN Tile REACIOR CORRECTIVE TCTIONS/ COP 9ENPS No Date S: SCIIEDULED (IlOURS)

(1)

OR REDUCING POWER (2) 6 860604 F

188.6 F

1 Unit shutdown to correct Limitorque valve operator jtrnper wiring discrepancies 7

860630 F

10.5 B

3 Unit Trip caused by low-low condenser hotwell level signal during testing SUPMARY: On June 4, the plant was shutdown to allow the correction of jmper wiring discrepancies in certain Liraitorque valve operators. Power Operation resmed on June 11. A unit trip resulted fran a low-low condenser hotwell level signal, on June 30, during calibration of the level switches.

(1)

PEA 901: A: EQUIPMENT FAILURE (EXPIAIN)

E: OPERA'IOR TRAINING AND LICENSE EXAMINATION (2)

ME'IllOD:

1.

MANUAL B: MAINTENANCE OR TFSF P: ADMINISTRATIVE 2.

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

AtrI0MATIC SCRAM D: REGUIA'IORY RESTRICTION H: OPIllER (EXPIAIN) 4.

OlllER (EXPIAIN)

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KANSAS GAS AND ELECTRIC COMPANY NOLF CREEK GENERATING STATION UNIT NO. 1 MON'IE June, 1986

SUMMARY

OF OPERATING EXPERIENCE Listed below in chronological sequence is a sumary of operating experiences for this month which required load reduction or resulted in significant non-load related incidents.

DA'IE TIME EVENT June 1, 1986 0001 Unit in Mxie 1, Power operation.

June 3, 1986 1600 Ccmnenced reducing power to allow wiring replacement in Limitorque valve operators.

June 4, 1986 0115 Tripped unit output breaker.

0200 Unit in Mode 3, Hot Standby.

June 11, 1986 1848 Reactor critical.

2149 Synchronized with grid, increased power to 30 pero it.

Held power at 30 percent until steam generator chemistry cane in specification.

June 12, 1986 1448 Ccanenced power increase.

June 13, 1986 0547 Reduced power 50 MW due to Main Feedwater Pung vibration.

0730 Comenced power increase.

June 17, 1986 1340 Reduced power to 90 percent to repair "A" Circulating Water Punp.

June 18, 1986 1850 Comenced power increase, j

June 19, 1986 0145 Comenced reducing power due to an apparent loss of the Solid State Protection System. (LER 86-035-

00).

0340 Stopped power reduction when cause identified.

0421 Ccmnenced power increase.

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June 21, 1986 2145 Reduced power to 45 percent to repair Reactor Coolant Syst s flow transmitter.

June 22, 1986 0045 Comenced power increase.

June 30, 1986 1331 Unit Trip, Reactor Trip caused by low-low condenser hotwell level signal (LER 86-038-00).

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KANSAS GAS AND ELECTRIC COMPANY THE ELECTRC COMPANY OLENN L KOESTER vece passiormt Nucitan July 15, 1986 ggg I

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JUL l 81986 i

Director, Office of Resource Management U.S. Nuclear Regulatory Commission Washington, D.C.

20555 Mr. E.H. Johnson, Director Division of Reactor Safety and Projects U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 KMLNRC 86-127 Re:

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

Enclosed is the June, 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,

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v Glenn'-L. Koester Vice President - Nuclear GLK:see Enclosure i

cc: P0'Connor (2), w/a JTaylor (12), w/a JCummins, w/a e

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201 N. Market - Wichita, Kansas - Mail Abdress: RO. Box 208 i Wchita, Kansas 67201 - Telephone: Area Code (316) d61-6451