ML20212M041

Monthly Operating Rept for Jul 1986

ML20212M041
Person / Time
Site:	Wolf Creek
Issue date:	07/31/1986
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-86-146, NUDOCS 8608250348
Download: ML20212M041 (10)

Text

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NOLF CREEK GENERATING STATICN MONIHLY OPERATING REPORT MON 1H:

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

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Subnitted by:

Kansas Gas and Electric Company l

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86092'7348 860731 PDR eDOCK 05000482 R

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2 2 following report highlights the operating experience of Wolf Creek Generating Station for the month of July, 1986. W is report is being provided pursuant to Technical Specification 6.9.1.8.

I.

SUPf4ARY OF OPERATING EXPERIENCE

. A plant startup begun on July 1 ended with a low stean generator level trip. he subsequent recovery was empleted on July 1 and the unit operated in Bede 1 near 100 percent power. On July 24, the unit was shutdown to repair a stator cooling water leak in the main generator.

%e plant was restarted on July 26 and operated near 100 percent for the remainder of the month.

II.

MMOR SAFELY RELATED MAIN'IENANCE ACTIVITIES

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We major safety related maintenance during the month of July included replacing a card in Icop 4 average temperature instraent, replacing an alarm reset key switch on chlorine monitor GK-AITS 3, replacing the pushrods on 35 Cutler Hamer switches and correction of the leakage fra the Spent Fuel Pool by reworking several boundary valves.

III. CHANGES, TESTS, AND EXPERIMENTS t 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 July.

1.

Safety Evaluation 86-SE Originated to temporarily supply the Main Steam Enclosure Supply Air Unit, SGF01, heating coil with chilled water fra the Auxiliary Building Supply Air Unit, SGLOl during the sumwr months. No unreviewed safety or enviromental questions are generated as a result of this tenporary modification.

2.

Safety Evaluation 86-SE-89, Revision 1 - Originated to change the source of chilled water to the Contairunent Shutdown Purge Unit, SGT01. No unreviewed safety or enviromental questions are generated as 'a result of this temporary modification.

3.

Safety Evaluation 86-SE Originated to temporarily remove fire detector zone 115 from the alarm circuit for the Auxiliary Building so that another zone in the Auxiliary Building could activate the alarm if needed. Zone 115 is in continuous alarm and being checked hourly by a fire watch. No unreviewed safety or environmental questions are generated as a result of this temporary modification.

4.

Safety Evaluation 86-SE Originated to temporarily replace the stainless steel bushirgs on the handwheel shaft for door 13251, Auxiliary Feedwater Pep Rom "B", with a bronze bushing. No unreviewed safety or envirorsnental questions are generated as a result of this temporary modification.

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5.

Safety Evaluation 86-SE Originated to allow the Superintendent of Operations to become a "previously licensed Senior Reactor Operator at iblf Creek Generating Station". No unreviewed safety or environmental questions are generated as a result of this proposed change to the Final Safety Analysis Report.

6.

Safety Evaluation KMLNRC 86-133 - Originated to change the administrative organization as shown in Technical Specifications and to add a member to the Nuclear Safety Review Ccmnittee. Wese changes result fran the formation of the Wolf Creek Nuclear Operating Company as well as fran a reorganization of a portion of the Quality Branch. No unreviewed safety or environmental questions are generated as a result of this proposed change to the

'Ibchnical Specifications.

7.

Safety Evaluation 86-SE Originated to defeat the automatic fire protection deluge on the main transformers. No unreviewed safety or environmental questions are generated as a result of this temporary modification.

W e following safety evaluations were performed prior to July, but reporting of them was overlooked because the changes contain safeguards information as defined in 10CFR 73.21.

1.

Plant Pbdification Request KN84-051, with Revisions 1 thru 4 -

Originated to improve the Security Building ventilation system.

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

2.

Plant Pbdification Request WO84-CS064, with Revisions 1 thru 6 -

Originated to improve the radio connunications throughout the power block. No unreviewed safety or envirornental questions are generated as a result of this plant modification.

3.

Plant Pbdification Request N084-JE075, with Revisions 1 thru 3 -

Originated to provide easier sanpling of the Bnergency Fuel Oil Storage Tank. No unreviewed safety or environnental questions are generated as a result of this plant modification.

4.

Plant !bdification Request WO85-SK01, with Revisions 1 thru 5 -

Originated to change the Control Roan entrance door for easier access. No unreviewed safety or environmental quastions are generated as a result of this plant modification.

i 5.

Plant Modification Request 01718 - Originated to add a base station / annunciator to the Secondary Alarm Station console. No unreviewed safety or environmental questions are generated as a result of this plant modification.

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6.

Plant Pbdification Request 00307 - Originated to replace certain breakwire detectors with steel grating. No unreviewed safety or environmental questions are generated as a result of this plant modification.

7.

Plant Modification Request 00915 - Originated to provide access to the Secondary Alarm Station radio mnsole for maintenance. No unreviewed safety or environmental questionc are generated as a result of this plant modification.

8.

Plant Modification Request 01152, with Revisions 1 thru 16 -

Originated to reduce the false and nuisance alarm rate on the Security perimeter zones. No unreviewed safety or envirornental questions are generated as a result of this plant modification.

9.

Plant !bdification Request 01153, with Pevisions 1 thru 4 -

Originated to reduce the false and nuisance slarm rate on the Security perimeter zones. No unreviewed safety or environmental questions ar; generated as a result of this plant modification.

10. Plant Pbdification Request 01309, Revision 2 - Originated to change the Emergency Plan c:mmunication system. No unreviewed safety or envirornental questions are generated as a result of this plant modification.

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_ OPERATING DATA REPORP DOCKET NO. SIN 50-482 WOLF CREEK GENERATING STATION KANSAS GAS AND ELECTRIC COMPANY DATE 08-01-86 COMPLETTED BY M. Williams TELEPHONE 316-364-8831 OPERATING STA'IUS 1.

Reporting Period:

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

Currently Authorized Power Level (Mt): 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 Month Yr to Date Cinulative 5.

Number of Hours Reactor was Critical 683.7 4389.6 7179.9 6.

Reactor Reserve Shutdown Hours 51.1 92.5 171.3 7.

Hours Generator on Line 664.8 4352.4 7124.0 8.

Unit Reserve Shutdown Hours 0.0 0.0 0.0 9.

Gross '1hermal Energy Generated (MH) 2,210,328 14,154,286 23,029,219

10. Gross Electrical Energy Gcnerated (MWH) 762,270 4,946,805 8,017,895

11. Net Electrical Energy Generated (WH) 728,383 4,727,486 7,669,586

12. Reactor Service Factor 91.9 86.3 90.1

13. Reactor Availability Factor 98.8 88.1 92.3

14. Unit Service Factor 89.4 85.6 89.4

15. Unit Availability Factor 89.4 85.6 89.4

16. Unit Capacity Factor (Using MDC) 86.8 82.4 85.3

17. Unit Capacity Factor (Using Design Me) 83.7 79.4 82.3

18. Unit Forced Outage Rate 1.9 6.3 5.3

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

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 Comercial Operation): Forecast Achieved Initial Criticality 5-22-85 5-22-85 Initial Electricity 6-13-85 6-12-85 Carercial Operation 9-09-85 9-03-8~,

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AVERAGE DAILY UNIT POWER IEVEL irxur NO. S'IN 50-482 WOLF CREEK GENERATING STATION KANSAS GAS AND ELECTRIC COMPANY DATE 08-01-86 00MPLETTED BY M. Williams TELEPHONE 316-364-8831 MONIH July, 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (hNet)

(M9e-Net) 1 208 17 1131 2

1094 18 1126 3

1068 19 1130 4

1124 20 1131 5

1128 21 1132 6

1132 22 1130 7

1134 23 1084 8

1131 24 0

9 1128 25 0

10 1129 26 83 11 1131 27 960 12 1132 28 11.27 13 1131 29 1127 14 1130 30 1124 15 1119 31 1126 16 1132 1

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4 UNIT SHtTfD06N AND POWER REDUCTIONS DOCKER ND.

STN 50-4'82 j

WOLF CREEK GENERATING STATION KANSAS GAS AND ELECTRIC COMPANY DATE 08-01-86 COMPLETED BY M. Williams

• REPORT MONIH July, 1986 TEIEPHONE 316-364-8831 i

I TYPE METHODS SHLTITING F: EORCED DURATION REASON D06N THE REACIOR CORRECTIVE ACTIONS /COPMNFS No Dat.e S: SCHEDULED (HOURS)

(1)

.OR REDUCING POWER (2) 7 860701 F

6.0 B

3 Extension of June Unit Trip caused by low-low condenser hotwell level signal during testing 4

8 860701 F

6.7 G

3 Unit Trip, Reactor Trip due to low-low steam generator level in manual control.

9 860724 S

66.5 B

3 Unit Trip, Reactor Trip due to low-low steam generator level in manual control while taking unit off-line to repair a stator cooling water leak.

SIMERY: Two trips resulted fran loss of steam generator level while in manual control. The first occurred during a startup.

The second occurred while the unit was being taken off-line to repair the main generator.

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REASON: A: EQUIPMENf FAILURE (EXPIAIN)

E: OPERATOR TRAINING AND LICENSE EXAMINATION (2)

MEIHOD:

1.

MANUAL B: MAINTENANCE OR TEST F: ADMINISTRATIVE 2.

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

AtHOMATIC SCRAP D: REGUIATORY RESTRICTION H: OlHER (EXPIAIN) 4.

OfHER (EXPIAIND i

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KANSAS GAS AND ELECTRIC COMPANY WOLF CREEK GENERATING STATION UNIT NO. 1 MONITI July, 1986 SUM 4ARY 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.

DATE TIME EVENP July 1,1986 0001 Unit in m de 3, Hot Standby.

0129 Reactor Critical.

0557 Synchronized with grid, increased power to 30 percent.

0625 Unit Trip, Reactor Trip caused by low-low stem generator level.

(LER 86-037-00).

1157 Reactor critical.

1308 Synchronized with grid, increased pwer to 30 percent. Held power at 30 percent until ste m generator chemistry cme in specification.

1830 Carmenced power increase.

2015 Held power at 63 percent to investigate problen with Main Feedwater Pmp "A" discharge valve.

2212 Comenced power increase.

July 2,1986 2000 Reduced power to 92 percent to allow repairs to high pressure heater train "B".

July 3,1986 1218 Comenced power increase.

July 23, 1986 2150 cmmenced reducing power to take unit off to repair a stator coolirs water leak.

July 24, 1986 0042 Unit Trip, Reactor Trip due to low-low ste m generator level.

(LER 86-042-00).

July 26, 1986 0602 Reactor critical.

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1912 Synchronized with grid, increased power to 30 percent. Held power at 30 percent until stean generator ch m istry in specification.

2042 Cmmenced power increase.

July 27, 1986 0254 Held power at 65 percent to investigate a turbine electrical failure annunciator.

0338 Comenced power increase.

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,1 KANSAS GAS AND HECTMC COMPANY TW ELECTN COMPANY OLENN L MOESTER

- - + - = - -

VKE PRES # DENT Nucitas t

August 13, 1986 i

AUG I 51986

_d 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 86-146 Re:

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

Enclosed is the July, 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, Glenn L. Koester Vice President - Nuclear GLK:see Enclosure oci P0'Connor (2), w/a JTaylor (12), w/a JCummins, w/a l

/6 ' ' q, gr4l9 201 N. Market - Wichita, Kansas - Mail Address: RO. Box 208 I W1chita. Kansas 67201 - Telephone: Area Code (316) 261-6451