ML20135C004

Monthly Operating Rept for June 1985

ML20135C004
Person / Time
Site:	Wolf Creek
Issue date:	06/30/1985
From:	Koester G, Mike Williams KANSAS GAS & ELECTRIC CO.
To:	Denise R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV), NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
KMLNRC-85-181, NUDOCS 8509110256
Download: ML20135C004 (12)

Text

3 l

WOLF CREEK GENERATING STATION MON 1HLY OPERATING REPORP MONIM:

June YEAR: 1985 Docket No.: STN 50-482 Facility Operating License No.: NPF-42 Report No.

4 Subnitted by:

Kansas Gas and Electric Cbnpany 8509110256 850830 PDR ADOCM 05000482 R

pm

We following report highlights the operating experience of Wolf Creek Generatire Station for the month of June,1985. This report is being provided pursuant to Technical Specification 6.9.1.8.

I.

OPERATING EXPERIENCE On June 4,1985, full power operating license NPP-42 wan issued for the Wolf Creek Generating Station. The initial entry into Mode 1, Ibwer Operation, was mMe on June 6,1985, at approximately 2222 CrTP, aM the initial synchronization of the unit with the grid occurred on June 12, 1985, at approximately 1900 CDP.

Durity the month of June, testirg was empleted at the 20 percent and the 30 percent power plateaus. On June 29, 1985, the reactor was successfully shut down frm the Auxiliary Shutdown Panel.

II.

MAJOR SAFETY RELATED MAINTENANCE We major safety related activity performed during the month of June was work on the Main Steamline Isolation Valves ard replacement of sme of the associated 4-way solenoid valves to resolve probles.

In addition, work has been performed on several miscellaneous valves and flanges to eliminate leakage.

III. CHANGES, TESTS, AND EXPERIMENTS

%e following is a brief description of safety evaluations performed pursuant to 10 CFR 50.59 on changes, tests, and experiments durirg the month of June.

1.

'1bnporary Modification 85-SE Install scaffoldirn around recycle evaporator skid SHE02 on 2000' elevation of rMwaste buildirg. No unreviewed safety or environmental questions are generated as a result of this tmporary charge.

2.

Temporary Modification 85-SE Install union connections to facilitate disassm.bly of the drain gas traps, FHA 02 and FHA 03, cming off the waste gas empressors and off the catalytic hydrogen recmbiners. No unreviewed safety or environmental questions are generated as a result of this temporary charge.

3.

Tmporary Modification 85-SE Install a manual isolation valve rpstream of a check valve in the Gaseous Radwaste System to allow discharge of gas decay tanks while maintainirg nitrogen supply to the gas analyzer racks. No unreviewed safety or environmental questions are generated as a result of this temporary change.

4.

T mporary Modification 85-SE Install scaffolding on the Essential Service Water house on the 2013' elevation. No unreviewed safety or environmental questions are generated as a result of this temporary charge.

Page 2 of 11

5.

Temporary Modification 85-SE Install mechanical j mpers in place of solenoid valves AB-WO38B arxl AB-WO44C which permit operation of steam dung valves AB-WO38 and AB-UV044 until the solenoid valves can be replaced. Wis change does constitute a change to the FSAR, however no unreviewed safety or environnental questions are generated as a result of this tenporary change.

6.

Temporary Procedure Change 85-SE Change the " Hot Standby to Cold Shutdown" procedure, GEN 00-006, Rev. 6, step 4.13 to manually isolate steam dunp valves AB-WO38 and AB-WO44 until solenoid valves AB-UYO38B and AB-UY044C are replaced. Wis permits "as-designed" operation. No unreviewed safety or environmental questions are generated as a result of this temporary change.

7.

Tenporary Procedure Gange 85-SE Charyje the " Power Operation" procedure, GEN 00-004, Rev. 2, to limit reactor power to < 30% until solenoid valves AB-UY038B and AB-UY044C are repTaced on steam dump valves AB-WO38 arri AB-WO44. Wis permits rejection of all load without a reactor trip. No unreviewed safety or environmental questions are generated as a result of this temporary chanje.

8.

Temporary Modification 85-SE Install pressure instrunentation at existing pressure points to monitor feedwater heater performance.

Instrunentation added downstream of existin3 isolation valves. No unreviewed safety or environmental questions are generated as a result of this tenporary charx3e.

9.

Temporary Modification 85-SE Install scaffolding in the Access control Area of the Radiological Control Area. tb unreviewed safety or environnental questions are generated as a result of this temporary change.

10. Temporary Modification 85-SE Install scaffolding in Auxiliary Building area 5.

Due to close proximity of Main Steanline Isolation Valves' actuators arri main stean safety valves and patential for danaje to same in event of scaffolding collapse, restricted installation to Modes 4, 5, and 6.

tb unrefiewed safety or environmental questions are generated as a result of this temporary change.

11. Tenporary Procedure Change MA 85-SE Change in procedure S'IS-IC-925, " Containment Coolers Flow Rate Verification", to allow use of essential service water punps rather than normal service water, allow collection of additional data and provide a caution for personnel performinj test. No unreviewed safety or environnental questions are generated as a result of this tenporary change.

12. Temporary Madification 85-SE Install scaffoldirr3 in the Fuel Building rail bay area to facilitate performance of a surveillance test. No unreviewed safety or environmental questions are generated as a result of this temporary change.

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13. Tenporary Modification 85-SE Install scaffolding in the Auxiliary Building on the 2047' elevation. No unreviewed safety or environmental questions are generated as a result of this temporary change.

14. Temporary Modification 85-SE Install scaffolding in the Auxiliary Building on the 1988' elevation in the pipe chase area. No unreviewed safety or enviromental questions are generated as a result of this temporary charge.

15. Temporary Modification 85-SE Install scaffoldiry in Auxiliary Building, area 5, to facilitate the installation of a filter over an exhaust duct in '

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

16. Temporary Modification 85-SE Install a clear 3/8" tubing to read level in the boron recycle holdup tank, 'IHE02B, until a replacement level transmitter is obtained for HE LT-262. No unreviewed safety or environmental questions are generated as a result of this temporary change.

17. Temporary Modification 85-SE-39/ Revision 1 - Install two temporary fire retardant plastic walls with lurber frames containing two 48" exhaust fans in each wall in the Auxiliary Building, area 5, on the 2090' elevation and situated on a concrete slab. 'Ihe security door will be opened for ventilation arri a full time security watch established while door is open.

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

18. Temporary Modification 85-SE Install scaffoldiry in the Auxiliary Buildirg on the 2047' elevation near the containment purge radioactive gaseous effluent radiation monitor GT-RE-22 to facilitate rework of danper GL-D-172.

No unreviewxl safety or envircrrnental questions are generated as a result of this temporary change.

19. Tenporary Modification 85-SE Install scaffoldiry in the Auxiliary Building on the 2047' elevation near contalment purge radioactive gaseous effluent radiation monitor GT-RE-22 to facilitate rework of danper Gr-D-014. No unreviewed safety or environmental questions are generated as a result of this tenporary change.

20. Temporary Wx11fication 85-SE Install scaffolding in the Auxiliary Buildity on the 2047' elevation to facilitate rework of danper GL-D-174.

tb unreviewed safety or environmental questions are generated as a result of this temporary charge.

21. Temporary Modification 85-SE Install scaffoldiry in the Auxiliary Building outside of stairwell #11275 on the 2047' elevation to facilitate rework of damper GF-D-088.

No unreviewxl safety or enviromental questions are generatal as a result of this temporary change.

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,22. Temporary Modification 85-SE Install scaffolding in the Fuel Building general floor area #6301 in front of door #63031 on the 2047' elevation to facilitate rework of danper GG-D-062.

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

23. Plant Modification Request WO82-KC015-(85-SE-45) - Installation of pipe unions in the wet pipe sprinkler system trim piping in the Fire Protection System to accmmodate maintenance activities.

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

24. Temporary Modification 85-SE Install scaffolding in the Auxiliary Building, area 5, on the 2026' elevation to facilitate cleaning. No unreviewed safety or environmental questions are generated as a result of this tenporary change.

25. Temporary Modification 85-SE Install scaffolding in the Auxiliary Building on the 2047' elevation in front of fire door

1. 11273 in the stairwell landing to facilitate rework of danper GF-D-087. No unreviewed safety or environmental questions are generated as a result of this temporary change.

26. Temporary Modification'85-SE Install scaffolding in the Auxiliary Building on the 2047' elevation near radiation monitor GT-RE-31 and mer penetration #99 to facilitate rework of danper GIeD-173. No unreviewed safety or environmental questions are generated as a result of this tenporary change.

27. Temporary Modification 85-SE Install scaffolding in the Auxiliary Building on 2026' elevation in the electrical penetration rom to facilitate work on damper GP-D-06" No unreviewed safety or environnental questions are generated as a result of this temporary change.

28. Temporary Modification 85-SE Originated to reverse the jtsupers on the logic cards of the status lights associated with the recirculation portion and heaters of the boron injection systen. W e recirculation portion and heaters are not required to be operable due to boron concentration reduction to 2000 ppn within the system, and consequently have Safety Injection Signal power lifted resulting in amber status lights on status panels SA066X and SA066Y. %e Temporary Modification would cause the status lights to be cleared ani to turn amber if the cmponents are energized, thus avoiding operator confusion. No unreviewed safety or enviromental questions are generated as a result cf this temporary change.

29. 'IWnporary Modification 85-SE Install RTD's and thermocouples in existing thermowells to monitor performance of Feedwater heaters. No unreviewed safety or environnental questions are generated as a result of this tenporary charrje.

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30. Temporary Modification 85-SE Install plywooC to support a laider above the Control Ibm ceiling on west end of the Control Ibam. No unreviewed safety or environnental questions are generated as a result of this temporary change.

31. Temporary Modification 85-SE Block open fire danper GE-D-049 and _ establish a fire watch until damper rework empleted to prevent stean frm the miscellaneous condensate drain tank ftm entering duct work. No unreviewed safety or environmental questions are generated as a result of this tenporary change.

32. Temporary Modification 85-SE Defeat the auto open and turbine trip interlock on valves AB W-23, 25, 27, and 29 and AC IN-134,135,136 and 137 which drain water from the steam lines following a turbine trip. 'Ihese valves can be operated manually frm the control roan and autmatic openiry of these valves causes uncontrolled rapid reduction of Reactor Coolant System temperature. No unreviewed safety or environnental questions are generated as a result of this temporary charge.

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OPERATING DATA REIORT DOCYEr NO.

STN 50-482 WOLF CREEK GENERATING STATION KANSAS GAS AND ELECTRIC QMPANY DATE 7-01-85 COMPIEEED BY M. Williams TELEPHONE 316-364-8831 OPERATING STA'1TS 1.

Reporting Period: June, 1985 Gross Hours in Reporting Period:

720 2.

Currently Authorized Power Invel(MNt): 3411 Max. Depend. Capacity (MNe-Net) : 1117 Design Electrical Rating (MWe-Net) :

1170 (Expected) 3.

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

N/A 4.

Reasons for restriction (If Any):

' Itis &bnth Yr to Date Ctnulative 5.

Number of Hours Reactor was Critical 479 638 638 6.

Reactor Reserve Shutdown Hours 241 241' 241 7.

Hours Generator on Line 305 305 305 8.

Unit Reserve Shutdown Hours 103 103 103 9.

Gross Thermal Energy Generated (MWH) 356676 356676 356676

10. Gross Electrical Energy Generated (MMI)

_ 78715 78715 78715

11. Net Electrical Energy Generated (MWH) 70829 70829 70829 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 (Usirg Design MWe)

N/A 18.

Unit Forced Outage Rate N/A

19. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of each) : None 20.

If Shut Ibwn at End of Report Period, Estimated Date of Startup: 7-2-85

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 Camercial Operation 8-08-85 Page 7 of 11

DOCKET NO.

STN 50-482 NOLF CREEK GENSIMTING STATION KANSAS GAS AND ELECfRIC COMPANY DATE.7-01-85 COMPLETED BY M. Willians TELEPfiONE 316-364-8831 MONI11 June, 1985 DAY AVERAGE IRILY POWER LEVEL DAY AVERAGE DAILY 10WER LEVEL (MWe-Net)

(MWe-Net) 1 0

17 145 2

0 18 174 3

0 19 174 4

0 20 197 5

0 21 200 6

0 22 247 7

0 23 250 8

0 24 75 9

0 25 26 10 0

26 270 11 0

27 273 12 0

28 288 13 7

29 269 14 7

30 42 15 127 31 N/A 16 179 INSTRUCTIONS:

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

These figures will be used to plot a graph for each reportiry rxanth. Note that when maximum depery3able capacity is used for the net electrical ratiry 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 average daily unit power output sheet should be footnotes to explain the apparent ananaly.

Page 8 of 11

UNIT SHUPDOWN AND POWER REDUCTIONS DOCKET NO.

STN 50-482 WOLF CREEK GENERATING STATION KANSAS GAS AND ELECTRIC COMPANY DATE 7-01-85 COMPLETED BY M. Willians REPORT MON 1H June, 1985 TELEPHONE _ 316-364-8831 MEN TYPE SHUITING DOWN F: EORCED DURATION REASON THE REACIOR OR CORRECTIVE ACTIONS /

No Date S: SCHEDULED (HOURS)

(1)

REDUCING POWER (2)

COPMENTS 850602 F

19.0 B

1 Rod Control Problems investigated-850602 F

55.5 B

1 Further investigation of Rod Control problems 850606 F

26.8 H

3 Power Ascension Testirq (Licensee Event Report 85-039-00) 1 850613 F

19.5 A

3 Main Feedwater Ptap Trip (Licensee Event Report 85-041-00) 2 850623 F

31.1 G

3 During Surveillance Testing, Reactor Trip Breaker inadvertently opened.

(Licensee Event Report 85-045-00) 3 850629 S

36.8 B

4 Denonstrate Auxiliary Shutdown Panel Operability SUPEARY:

Initial entry into Itxie 1 (Power Operation) occurred on June 6,1985, and the unit was initially synchronized to the grid on June 12, 1985. Testing at the twenty and thirty percent power plateaus has been completed.

'Ihe sta of the total outage hours plus the hours the generator was on line does not equal the gross hours in this reporting period due to the fact that the initial synchronization of the generator with the grid occurred on June 12, 1985.

(1)

REASON:

(2) METHOD:

A EQUIPMENT FAILURE (EXPLAIN) 1.

MANUAL B: MAINTENANCE OR TEST 2.

MANUAL SCRAM C: REFUELING 3.

AUI0MATIC SCRAM D: REGULA'IORY RESTRICTION 4.

01HER (EXPIAIN)

E: OPERA'IOR TRAINING AND LICENSE EXAMINATION F: AEMINISTRATIVE.

G:.OPER/.TIONAL ERR 0tt (EXPIAIN)

H: OTHER (EXPLAIN)

Page 9 of 11

)

i

KANSAS GAS AND ELECTRIC ONPANY WOLF CREEK GENERATING STATION UNIT NO. 1 M0tfIH June SIMtARY OF OPERATING EXPERIENCE Listed below in chronological sequence is a stenary of operating experiences for thin month which required load reduction or resulted in significant non-load related incidents.

DATE TIME EVENT June 2, 1985 1304-Received Control Room Ventilation Isolation Signal (CRVIS) due to spurious spiking of a rMiation monitor. Reportable per 10 CFR 50.72 and 50.73.

June 3, 1985 1630 Received notice that Ownercial Operatin) License had been granted.

June 4, 1985 1005 Received Auxiliary Feed Actuation Signal due to Main Feedwater Ptsap Trip due to loss of condenser vacuum. Reportable per 10 CFR 50.72 and 50.73.

June 5, 1985 0025 Received CRVIS due to spurious spiking of a radiation monitor. % portable per 10 CFR 50.72 and 50.73.

June 6, 1985 2222 Initial entry into Mode 1.

2250 Received Reactor Trip and Safety Injection due to low steam generator water level. Reportable per 10 CFR 50.72 and 50.73.

June 7, 1985 0255 Received CRVIS due to spurious spikinj of a rMiation monitor.. Reportable per 10 CFR 50.72 and 50.73.

June 9, 1985 0015 Received Auxiliary Feed Actuation Signal (AFAS),

- due to Main Feedwater Planp Trip. Reportable per 10 CFR 50.72 and 50.73.

0107 Received Main Feedwater Isolation Signal (NIS) and AFAS due to High-High Stean Generator level.

Reportable per 10 CFR 50.72 and 50.73.

June 11, 1985 1753 Received WIS arri AFAS due to High-High Steam

~

Generator level. Reportable per 10 CFR 50.72 and 50.73.

Page 10 of 11

DATE TIME EVENP June 12, 1985 1900 Performed initial synchronization of the main generator with the grid.

June 13, 1985 0401 Reactor trip frcxn 12% power due to Iow-Iow Stean Generator Invel while unloading after a turbine trip. Reportable per 10 CFR 50.72 and 50.73.

June 14, 1985 0631 Received RfIS and AFAS due to High Stean Generator level. Reportable per 10 CFR 50.72 arri 50.73.

June 23, 1985 1333 Reactor trip due to a personnel error while performing a surveillance test. Reportabic per 10 CFR 50.72 and 50.73.

June 24, 1985 0043 Reactor trip on low-low level in Stean Generator "A".

Reportable per 10 CFR 50.72 and 50.73.

June 29, 1985 1115 Manually tripped the reactor arxl turbine frun the Auxiliary Shutdown Panel.

Page 11 of 11

l KANSAS GAS AND ELECTRIC COMPANY THE ELECTf4C COMPANY GLENN L M O E S T E II watt P.assosset soucktaa July 12, 1985 Director, Office of Resource Management U.S. Riclear Regulatory Comission thshington, D.C.

20555 Mr. R.P. Denise, Director iblf Creek Task Force U.S. Riclear Regulatory Comission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 KMLPGC 85-181 Re Docket !b. SIN 50-482 Subj: June, 1985 Monthly Operating Report Gentlemen:

Enclosed is the June, 1985 Monthly Operating Report for iblf Creek Generating Station.

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

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

Yours very truly, Lt/

vt Glenn L. Kocster Vice President, Riclear GKidab Enclosure xc: FO'Connor (2), w/a Jraylor (12), w/a q

$[M JCumins, w/a 201 N. Market - WWirta, Kansas - Mad Address? Po. Box 200 l Wichita, Kansas 67201 - Telephone: Area Code (316) 2616451