ML20207R897

Monthly Operating Rept for Feb 1987

ML20207R897
Person / Time
Site:	Wolf Creek
Issue date:	02/28/1987
From:	Mike Williams, Withers B WOLF CREEK NUCLEAR OPERATING CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
WM-87-0066, WM-87-66, NUDOCS 8703180272
Download: ML20207R897 (9)

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NOLF CREEK GENERATING STATION MON'1HLY OPERATING REPORf MONIH: February YEAR: 1987-Docket No.: 50-482 Facility Operatire License No.: NPF-42 Report No.

24 Subnitted by:

i Wlf Creek Nuclear Operating Corporation 1

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8703180272 87022S' PDR ADOCK 05000482 R

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.%e following report highlights the operating experience of Wolf Creek

. Generating Station for the month of February,1987. B is report is being provided pursuant to Technical Specification 6.9.1.8.

-I.

SUl44ARY OF OPERATING EXPERIENCE t e month began with the reactor critical in Mode 2 and the Turbine Generator shut down to correct a vibration problen. We Turbine Generator was synchronized with the grid, tripped, balanced and synchronized again on February 1, 1987. % is was followed by power ascension in Mode 1, reaching 98 percent power on February 2.. We plant operated at or near 100 percent power for the renainder of the month.

II.

MILTOR SAFETY RELATED MAINTENANCE ACTIVITIES 1.

Replacenent of "A" Steau Generator feedwater flow transmitter AD FT-510A.

2.

Replacement of the hydraulic fluid in two stean generator snubbers.

III. CHANGES, TESTS, AND EXPERIMEVPS 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 February.

1.

Safety Evaluation 87-SE-Oll - Originated to temporarily install feedwater flow differential pressure indicators in parallel with the feedwater flow transmitters. No unreviewed safety or environmental questions are generated as a result of this tenporary modification.

2.

Safety Evaluation 87-SE-012 - Originated to tenporarily seal door 36092 with Tuck tape type 6224. No unreviewed safety or environmental questions are generated as a result of this tenporary modification.

3.

Safety Evaluation 87-SE-013 - Originated to tenporarily install a non-safety related bearire in the motor for the Limitorque i

operator for the Residual Heat Removal to Safety Injection Pump A suction valve EM HV-8807A. No unreviewed safety or environnental questions are generated as a result of this tenporary modification.

4.

Safety Evaluation 87-SE-014 - Originated to tenporarily increase the range on the secondary sanple systen hydrazine analyzer to 0-100 ppb. No unreviewed safety or environmental questions are j

generated as a result of this tenporary modification.

5.

Technical Specification, Tables 3.3-1 arri 4.3-1, Change Request -

Originated to relax the operability and surveillance requirenents for the Reactor Trip Systen Instrunentation in order to reduce the number of inadvertant reactor trips occurring during testing of the instrunentation. No unreviewed safety or environmental questions are generated as a result of this Technical Specification change request.

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Technical Specification, Table 3.3-6, Change Request - Originated to relax the operability requirements for the radiation monitorim l

instrmentation for plant operations. No unreviewed safety or environnental questions are generated as a result of this Technical Specification change request.

7.

Plant Modification Request 00378, revision 3 - Originated to provide a method of returning the Filter Cask transport skid with the Filter Cask in place to the equipnent hatch between R-3 and R-4 at elevation 2031' 6 " in the Radwaste Building for this PMR, which provides a method to transport the Filter Cask from the Auxiliary Building filter /denineralizer room to the filter drop area of the Radwaste Buildirg. No unreviewed safety or environmental questions are generated as a result of this plant modification.

8.. Plant Modification aequest 1286 - Originated to modify the Balance of Plant computer data base for point MAX 0002 to accept a signal proportional to -1500 MVAR to +1500 MVAR. No unreviewed safety or environnental questions are generated as a result of this plant modification.

9.

Plant ledification Request 01809 - Originated to reflect the as-built condition of havirg thermoneters installed in existing threaded ports to measure chilled water tenperature for the Central Chilled Water System. No unreviewed safety or environnental questions are generated as a result of this plant modification.

10. Plant Modification Request 01934 - Originated to replace the 1/4 inch tubing connecting the "A" Diesel Generator Fuel Oil system accanulator overflow to the fuel return header. 'the replacement tubing has a thicker wall. No unreviewed safety or environmental questions are generated as a result of this plant modification.

11. Plant Modification Request 01997 - Originated to allow the use of Raychem WCSF-N tubing to repair insulation danage on motor leads T1 ard T2 of a spare motor that will be installed in a Limitorque operator for Essential Service Water return to the Ultimate Heat Sink valve EP IN-38. No unreviewed safety or environnental questions are generated as a result of this plant modification.

12. Plant Pbdification Request KN84-051, revision 5 - Originated to relocate halon bottles and re-route halon piping to eliminate interference with the new fan box provided by the PMR, which modifies the Security Building ventilation system. No unreviewed safety or environnental questions are generated as a result of this plant modification.

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13. Plant Modification Request WO83-SLO 30, revision 4 - Originated to provide a wiring change to the PMR, which allows testing of the meters in the Site Auxiliary Power Systen buses without de--

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

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'7 OPERATING DATA REPORP DOCKE7f NO.

50-482 WOLF CREEK GENERATING STATION NOLP CREEK NUCLEAR OPERATING CORPORATION DATE 03-01-87 COMPLETED BY M. Willians TELEPHONE 316-364-8831 OPERATING STATUS 1.

Reporting Period:

February, 1987 Gross Hours in Reporting Period: 672 2.

Currently Authorized Power Level (MWt): 3411 Max. Depend. Capacity (MWe-Net) : 1128 Design Electrical Rating (MWe-Net): 117_0 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 Ctznulative 5.

Ntanber of Hours Reactor was Critical 672.0 1325.3 10639.2 6.

Reactor Reserve Shutdown Hours 0.0 77.9 249.2 7.

Hours Generator on Line

__661.8 1264.9 10455.0 8.

Unit Reserve Shutdown Hours 0.0 0.0 0.0 9.

Gross 'Ihennal Energy Generated (tMI) 2,192,444

_3,725,757 33,471,099_

10. Gross Electrical Energy Generated (PH1) 770,296 1,315,676_ 11_,682,046

11. Net Electrical Energy Generated (fM1) 738,939 1,250,204 11,149,493

12. Reactor Service Factor 100.0 93.6 81.5

13. Reactor Availability Factor 100.0 99._1 83.4

14. Unit Service Factor 98.5 89.3 80.1

15. Unit Availability Factor 98.5 89.3 80.1

16. Unit Capacity Factor (Using MDC) 97.5 78.3 75.7

17. Unit Capacity Factor (Using Design MNe) 94.0 75.5 73.0

18. Unit Forced Outage Rate 0.0 3.4 _

4.3_

19. Shutdowns Scheduled Over Next 6 Mnths (Type, Date, and Duration of each): None

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

N/A Page 4 of 7

o AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-482 WOLF CREEK GENERATING STATION WOLF CREEK NUCLEAR OPERATING CORIORATION DATE 03-01-87 COMPIETED BY M. Williams TELEPHONE 316-364-8831 MONTH February, 1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE IRILY POWER LEVEL (M4e-Net)

(MWe-Net) 1 199 17 1150 2

1041 18 1150 3

1097 19 1147 4

1096 20 1146 5

1099 21 1151 6

1145 22 1149 7

1148 23 1149 8

1147 24 1151 9

1148 25 1139 10 1114 26 1148 11 1106 27 1147 12 1106 28 1147 13 1124 29 N/A 14 1147_

30 N/A 15 1150 31 N/A 16 1150 4

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UNIT SHUrDOWN AND POWER REDUCTIONS DOCKER NO.. 50-482 WOLF CREEK GENERATING STATI m ;

WOLF CREEK NUCLEAR OPERATING (DRPORATICN DATE 3-01-87 00MPLETED BY M. Williauns =

REPORT MONIH February, 1987 TELEPHONE 316-364-8831 TYPE METHODS SHUITING F: FORCED DURATION REASCN DOWN THE REACIDR OORRECTIVE ACTIONS / COMMENTS No Date S: SCHEDULED (HOURS)

(1)

OR REDUCING POWER (2) 5 870201 S

7.0 B

1 Continued outage to correct turbine generator vibration 6

870201 S

3.2 B

1 Correct turbine generator vibration.

SIRGERf: An outage to merect turbine generator vibration was completed on February 1.

Durirg the startup, the unit was again taken off line for a balance shot.

(1)

REASON: A: EQUIPMENT FAIIURE (EXPIAIN)

E: OPERATOR TRAINING AND LICENSE EKAMINATION (2) MEIHOD:

1.

MANUAL B: MAINTENANCE OR TEST F: ADMINISTRATIVE 2.

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

AUIOMATIC SCRAM D: REGUIATORY RESTRICTION H: OIHER (EXPIAIN) 4.

OIHER (EXPIAIN)

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WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION UNIT NO. 1 M0tml February, 1987

SUMMARY

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

DATE TIME EVENP February 1, 1987 0000 Unit in Mode 2, Startup, with the reactor critical and turbine generator shutdown.

0533 Unit in Mode 1, Power Operation.

0659 Synchronized with grid, increased power to about 20 percent.

1139 Tripped turbine generator to add a balance shot.

1450 Synchronized with grid, increased power to about 19 percent.

1715 Comenced increasing power toward 100 percent.

February 6, 1987 0051 Reactor power 100 percent.

Note: Power held at 98% by managenent directive while investigating flow calibration.

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NUCLEAR OPERATING CORPORATION March 13, 1987 U. S. Nuclear Regulatory Comission ATTN: Document Control Desk Washington, D. C.

20555 Letter: WM 87-0066 Re:

Docket No. 50-482 Subj:

February, 1987, Monthly operating Report Gentlemen:

Enclosed is the February, 1987, 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.

Very truly yours,

_=)

Bart D. Withers President and Chief Ex a tive Officer BDN:jad Enclosure cc: P0'Connor (2), w/a RMartin, w/a JCumins, w/a j

PO Box dit < Dortmgton. AS (6839, Phone'(316) 364 8831 An Equal Ot'evtunty Ev7er M F HC VEf c