ML20127H606

Monthly Operating Rept for May 1985

ML20127H606
Person / Time
Site:	Wolf Creek
Issue date:	05/31/1985
From:	Koester G, Mike Williams KANSAS GAS & ELECTRIC CO.
To:	Denise R NRC - WOLF CREEK TASK FORCE, NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
KMLNRC-85-152, NUDOCS 8506260393
Download: ML20127H606 (12)

Text

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Enclosure to KMLNRC 85-152:

WOLF CREEK GENERATING STATION MOLf1HLY OPERATING REPOIE MONIH: May YEAR: 1985 Docket No.: SIN 50-482 i

Facility Operating License No.: NPF-32 Report No. 3 .

Subnitted by:

Kansas Gas and Electric Company

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8506260393 850531 DR ADOCK050g4y2

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te followirg report highlights the operating experience of Wolf Creek Generating Station for the month of May, 1985. W is report is being provided pursuant to Technical Specification 6.9.1.8.

I. Operating Experience On May 22, 1985, the plant achieved initial criticality. Low power

. physics. testing has been completed.

Several Engineered Safety Features actuations occurred during the month of May, including one which was a Safety Injection into the  ;

Reactor Coolant System. Six of these actuations were due to the - '

spurious spiking of a radiation monitor.

II.- . Major Safety Related Maintenance Activities W ere were several safety related maintenance activities performed during the month of May. 'Nenty small Handcock root isolation valves off the steam generators had body-to-bonnet leaks and packing leaks which required encapsulation to terminate leakage. Two feedwater valves required repair involving welding and machining in steam cut areas. One of the Mair, Steamline Isolation Valves (MSLIV) required replacement of a solenoid valve and a hydraulic pump.

In addition, the shroud welds on the generator portion of the Bnergency Diesel Generators were inspected due to a concern for a possible generic problem. Some undercutting was discovered on one weld and has been repaired.

III. CHANGES, TESTS, AND EXPERIMENTS 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 May.

1. Plant Modification Request #KN84-076 - Installation of check valves downstream of Centrifugal Chargirg Punp Discharge Isolation Valves. No unreviewed safety or environmental questions.are generated as a result of this change.

2. Plant Modification Itxluest #KN84-094 - Installation of two non-safety related isolation valves downstream of each waste gas compressor to facilitate maintenance and AIARA concerns. No unreviewed safety or environmental questions are generated as a result of this change.

3. Plant Modification Request #311 - Originated to facilitate the redesign of the Service Air system air conpressors to reduce dirt intake and control cooling water flow. No unreviewed safety or environmental questions are generated as a result of this charge.

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'4. Plant Modification Request #615 - Implement wiring change for handswitch SB HS-1, Manual Reactor Trip Breaker Control to

. improve breaker reclosure reliability following a trip operation.

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

5. Plant Modification Request #726 - Replacement of the Steam Generator Pipe Peak Recording Accelerometer (SGAR7) with one of a higher range. No unreviewed safety or environmental questions -

are generated as a result of this change.

6. Plant Modification Request #849 - Originated to provide permanent connections for demineralized water, c m pressed air, power and other services for a portable radwaste solidification processing skid. No unreviewed safety or enviromental questions are generated as a result of this change.

7. Plant Modification Request #852 - Relocation of the bellows seals on level transmitters in the Boron Recycle and Liquid Radwaste Systems for ALARA considerations during calibration. No unreviewed safety or environmental questions are generated as a result of this change.

8. Plant Modification Request #882 - Originated to delete a flow switch from the plant heating system. Flow switch causes frequent false trips of the hot water pumps. No unreviewed-i safety or environmental questions are generated as a result of this change.

~

9. Plant Modification Request #911 - Originated to remove flush connections on Steam Generator drain pumps ami lergthen drain connection piping for increased maintainability. No unreviewed safety or envirormental questions are generated as a result of this change.

10. Plant Modification Request #920 - Originated to allow use of the plant O,3 and N supply rather than 0,3 and N,3 bottles in the hydrogen re iner analyzer roms in accordance with ALARA program. No unreviewed safety or environmental questions are generated as a result of this change.

11. Plant Modification Request #928 - Originated to change the alarm setpoint for the hydrogen recm biner. No unreviewed safety or enviromental questions are generated as a result of this charge.

12. Plant Modification Request #944 - Originated to provide a liquid drain trap at each catalytic hydrogen recombiner purge line to prevent water from entering the gas analyzer racks. No unreviewed safety or enviromental questions are generated as a result of this change.

13. Temporary Modifcation 85-GK-232 - Replacement of chlorine monitor GK-AITS-002 with monitor KT-AITS-ll while awaiting replacement

. parts. No unreviewed safety or environmental questions are generated as a result of this change.

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7 Temporary Modification 85-CC-155 - Remove gauge CC-GA-7 and

.14.

install instrument air supply hose frta KA-V466, to supply instrtment air to generator casing. . No unreviewed safety or environmental questions are generated as a result of this change.

15. Temporary Modification 85-BB-231 - Removal of the keeper pin from the. top of the connecting rod of valve BB-PCV-455B to facilitate maintenance. To be used as is until first outage. No unreviewed safety or environmental questions are generated as a result of this change.

- 16. Temporary Modification 85-SE Allow the use of a revision of the temperature versus pressure graph for the Main Steanline Isolation Valve and Feedwater Isolation Valve acetnulator precharge to keep valves out of low pressure alarm. .No unreviewed safety or environmental questions are generated as a result of this change.

17. Temporary Modification 85-SE Install replacement snubbers on U-PDSH-10, U-PDSH-ll, and U-PSL-12. No unreviewed safety or environmental questions are generated as a result of this change.

18. Temporary Modification 85-SE Install temporary pressure gauges to measure Steam Generator pressure for testing purposes.

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

-19. Temporary Modification 85-BB-240 - Use lockwire to fasten together incore thermocouple connector on BB-TE-05 temporarily.

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

20. Temporary Modification 85-SE Install temporary differential pressure gauges to measure feedwater flow differential pressure for testing purposes. No unreviewed safety or environmental questions are generated as a result of this change.

21. Temporary Modification 85-SE Install replacement snubbers on U-PDSH-110, U-PDSH-lll, arv3 U-PSL-112. No unreviewed safety or environmental questions are generated as a result of this.

change.

22. Temporary Modification 85-SE-ll - Connect temporary scaler / timer to nuclear instrinent channel'N32 for testing purposes. No unreviewed safety or environmental questions are generated as a result.of this change.

23. Temporary Modification 85-SE Temporary installatic,n of ladders on 2047' level of Auxiliary Building, for testing purposes. No unreviewed safety or environmental questions are generated as a result of this change.

24. Temporary Modification 85-SE Install temporary bottle rack and nitrogen manifold at 2000' level of Turbine Building at KH-V130. No unreviewed safety or environmental questions are generated as a result of this change.

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25. Tenporary Modification 85-GL-246 - Install scaffolding for rework of damper GL-D057.- No unreviewed safety or environmental questions are generated as a result of this change.

26. - Temporary Modification 85-SE Install scaffolding on Auxiliary Building roof from Contaiment Air Purification and Cleanup plenum to radiation monitor. No unreviewed safety or enviromental questions are generated as a result of this change.

27. Temporary Modification 85-SE Install scaffolding at 2020' level in Auxiliary Building for rework of depers. No unreviewed safety or enviromental questions are generated as a result of this change.

28. Temporary Modification 85-SE Install saffolding at 2010' level in Auxiliary Building for deper rework. No unreviewed safety or enviromental questions are generated as a result of this change. *

29. Temporary Modification 85-SE Install _ scaffold.ing at 2026' level in Auxiliary Building to facilitate electrical corduit work. No unreviewed safety or environmental questions are generated as a result of this change.

30. Temporary Modification 85-AB-255 - Install scaffolding around Steam Generators to facilitate the encapsulation of instrunent isolation root valves. No unreviewed safety or environmental questions are generated as a result of this change.

31. Temporary Modification 85-SE Install scaffolding around Main Steamline Isolation Valves for installation of insulation. No unreviewed safety or enviromental questions are generated as a result of this change.

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. OPERATING DATA REPORP DOCKEP NO. STN 50-482 WOLF CREEK GENERATING STATION KANSAS GAS AND ELECTRIC COMPANY DATE 6-01-85 COMPLETED BY M. Willians TELEPHONE 316-364-8831 OPERATING STATUS

1. Reporting Period: May, 1985 Gross Hours in Reporting Period: 744

2. Currently Authorized Power Level (MWt): 170 Max. Depend. Capacity (MWe-Net) : 0 Design Electrical Rating (MNe-Net): 1117 (Expected)

3. Power tevel to Which Restricted (If Any) (Mwe-Net): 0

4. Reasons for restriction (If Any): 5% License Issued Wis Month Yr to Date Cumulative

5. Number of Hours Reactor was Critical 159.4 159.4 159.4

6. Reactor Reserve Shutdown Hours 0.0 0.0 0.0

7. Hours Generator on Line 0.0 0.0 0.0

8. Unit Reserve Shutdown Hours 0.0 0.0 0.0

9. Gross termal Energy Generated (MWH) 0 0 0

10. Gross Electrical Energy Generated (MWH) 0.0 0.0 0.0

11. Net Electrical Energy Generated (MWH) 0.0 0.0 0.0

12. Reactor Service Factor N/A

13. Reactor Availability Factor N/A

14. Unit Service Factor N/A

15. Unit Availability Factor N/A

16. Unit Capacity Factor (Using MDC) N/A

17. Unit Capacity Factor (Usirq Design MWe) N/A

18. Unit Forced Outage Rate N/A

19. Shutdowris Scheduled Over Next 6 Months (Type, Date, arxl Duration of each): None 20._ If Shut Down at End of Report Period, Estimated Date of Startup: N/A

21. Units in test Status (Prior to Catmercial Operation): Forecast Achieved Initial Criticality 5-22-85 5-22-85 Initial Electricity 6-13-85 Catnercial Operation 8-08-85 Page 6 of 11 h_

. UNIT SHUfDOWN AND POWER REDUCTIONS DOCKET NO. SIN 50-482 WOLF CREEK GENERATING STATION KANSAS GAS AND ELECTRIC COMPANY DATE 6-01-85 COiPLETED BY M. Williams REPORP MONIE May,'1985 TELEPHONE 316-364-8831 MEIHODS TYPE SHUffING DOWN F: EURCED' DURATION REASON 'IHE REACIOR OR CORRECTIVE ACfIONS/

No Date S: SCHEDULED (HOURS) (1) REDUCING POWER (2) COtt4ENTS SLN MRY:

Initial Reactor Criticality was achieved on May 22, 1985, and Low Ibwer Physics

% sting has been completed.

(1) REASON: (2) METHOD:

A: EQUIIMENT FAILURE (EXPIAIN) 1. MANUAL B: MAINTENANCE OR TEST 2. MANUAL SCRAM C: REFUELING 3. ALTI0MATIC SCRAM D: REGUIA'IURY RESTRICfION 4. OfHER (EXPIAIN)

E: OPERA'IOR TRAINING AND LICENSE EXAMINATION F: ADMINISTRATIVE G: CPERATIONAL ERROR (EXPIAIN)

H: 01EER (EXPIAIN)

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- - - D O CIETf N O , STN 50-482 WOLF CREEK GENERATING STATION KANSAS GAS AND ELECTRIC COMPANY DATE 6-01-85 COMPIEfED BY - M. Williams TELEPHONE 316-364-8831 M0tfIH May, 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (Nie-Net) (lefe-Net) 1 0 17 0

.2 0 18 0 3 0 19 0 _

4 0 20 0 5 0 21 0 6 0 22 0 7' 0 23 0

.8 0 24 0 9- 0 25 0 10 0 26 0 11 0 27 0 12 0 28 0 13 0 29 0 14 0 30 0

- 15 0 31 0 16 0 INSTRUCTIONS:

On this form, list the average daily unit power level in MWe-Net for each day in the reporting month. Campute to the nearest whole megawatt.

'1hese figures will be used to plot a graph for each reporting month. Note that when maximtn dependable capacity is used for the net electrical rating of the unit, there may be occasions when the daily average power level exceeds the 100% line (or the restricted power level line). In such cases, the averaje daily unit power output sheet should be footnotes to explain the apparent ancmaly.

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, .- KANSAS GAS AND ELECTRIC COMPANY WOLF CREEK GENERATING STATION UNIT NO. 1 MONIH May SGMARY OF OPERATING EXPERIENCE Listed below in chronological sequence is a sunmary of operating exp3riences for this month which required load reduction or resulted in significant non-load related incidents.-

DATE TIME EVENP May 1, 1985 0530 Received Feed Water Isolation Signal (FWIS) due to a personnel error. Reportable per 10 CFR 50.72 and 50.73.

0555 Reset from NIS.

1100 Received an Auxiliary Feed Actuation Signal (APAS) aM a NIS due to a spike on a steam generator level transmitter. Reportable per 10 CFR 50.72 aM 50.73.

1105 Reestablished normal feed flow.

May 6, 1985 0155 Received a Control Iban Ventilation Isolation Signal (CRVIS) due to a spurious spike on a rMiation monitor. Reportable per 10 CFR 50.72 and 50.73.

0337 Reset from CRVIS.

0852 Received Fuel Building Ventilation Isolation Signal (FBVIS), Containment Purge Isolation Signal (CPIS) and CRVIS due to a personnel error. Reportable per 10 CFR 50.72 and 50.73.

0925 Reset from FBVIS, CPIS, CRVIS.

1225 Safety Injection occurred due to a low steamline pressure signal. '1his signal was due to a personnel wersight in depressurizing the stean generator. Declared an Untisual Event per Bnergency Plan Implementing Procedures. Reportable per 10

, CFR 50.72 and 50.73.

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DATE TIME EVENP 1340 Received a CRVIS, FBVIS, and CPIS due to no flow on a containment atmosphere radiation monitor. The absence of flow was due to a procedural deficiency. Reportable per 10 CFR 50.72 and 50.73.

1413 Reset from CRVIS, FBVIS, ard CPIS.

1650 Received CRVIS due to the spurious spiking of a radiation monitor. Reportable per 10 CFR 50.72 and 50.73.

1715 Reset from CRVIS.

May 15, 1985 1054 Received CRVIS due to the spurious spiking of a rMiation monitor. Reportable per 10 CFR 50.72 and 50.73.

1141 Reset from CRVIS.

May 16, 1985 1515 Received AFAS due to low steam generator level. Reportable per 10 CFR 50.72 ard 50.73.

May 18, 1985 2131 Received EWIS due to high-high stean generator level. Reportable per 10 CFR 50.72 and 50.73.

May 21, 1985 0923 Received CPIS and CRVIS due to personnel error. Reportable per 10 CFR 50.72 and 50.73.

1000 Restored from CPIS and CRVIS.

2038 Plant initially entered Mode 2.

May 22, 1985 0745 Achieved initial criticality. Cmmenced low power physics testirg.

May 23, 1985 1037 Received CRVIS due to the spurious spiking of a radiation monitor. Reportable per 10 CFR 50.72 and 50.73.

1113 Restored frczn CRVIS.

1900 Received partial CRVIS. Reportable per 10 CFR 50.72 and 50.73.

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• DATE TIME EVEfff May 24, 1985 0930 Restored frm CRVIS.

May 26,:1985 1814 Received CRVIS due to spurious spiking of a radiation monitor. Reportable per 10 CFR 50.72 and 50.73.

1826 Reset frm CRVIS.

May 30, 1985 1407 Received CRVIS due to spurious spiking of a raliation monitor. Reportable per 10 CFR 50.72 and 50.73.

1410 Reset frm CRVIS.

'May 31, 1985 0840 Cm pleted low power physics testing..

1217 Received FWIS and AFAS due to a personnel error. Reportable per 10 CFR 50.72 and 50.73.

1220 Reset frm EWIS and AFAS.

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KANSAS GAS AND ELECTRIC COMPANY THE ELECTFDC CA3MPANY

@LENN L KOESTER wKa petseotm? - Nuctase June 11, 1985 Director, Office of Resource Management U.S. Nuclear Regulatory Commission j Al Washington, D.C. 20555 I]r[((6)[@[]S//.._.m l Mr. R.P. Denise, Director M l I l9 6 Wolf Creek Task Force  !! "y U.S. Nuclear Regulatory Commission - {  ;

Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 KMLNRC 85-152 Re: Docket No. STN 50-482 Subj : May, 1985 Monthly Operating Report Gentlemen:

Enclosed is the May, 1985 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.

If you have any questions concerning this matter, please contact me or Mr. Otto Maynard of my staff.

Yours very truly, Glenn L. Koester Vice President - Nuclear GLK: dab Enclosure xc: P0'Connor (2), w/a JTaylor (12), w/a JCummins, w/a s

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201 N. Market - Woctuta, Kansas - Mail Address: PO. Box 208 I Wichita, Kansas 67201 - Telephone: Area Code (316) 2616451