ML20195C115

Monthly Operating Rept for Apr 1986

ML20195C115
Person / Time
Site:	Wolf Creek
Issue date:	04/30/1986
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-86-094, KMLNRC-86-94, NUDOCS 8605290753
Download: ML20195C115 (11)

Text

.

NOLF CREEK GENERATING STATION MONIELY OPERATING REPORT MON 1H:

April YEAR: 1986 Docket No.: STN 50-482 Facility Operating License No.: NPF-42 Report No.

14 Subnitted by:

Kansas Gas and Electric Canpany 4

8605290753 860430 PDR ADOCK 0500 2

R ll

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

I.

SUMMARY

OF OPERATING EXPERIENCE We unit operated in Mode 1, Power Operation, near 100 percent power until April 6, when power was reduced to allow repair of a Main Feedwater Pmp recirculation valve and Feedwater Heaters. On April 8, a non-nuclear switchyard technician inadvertently tripped the Main Generator Breaker, causing a Reactor trip. 'Ihe Reactor was returned to critical on April 8, but shutdown on April 9 to permit repair of a Pressurizer Spray Bypass Valve and conduct of 18 month surveillance tests which required Mode 5, Cold Shutdown. We unit was returned to Mode 1, Power Operation, on April 25.

II.

MAJOR SAFE 1"I RELATED MAINTENANCE ACTIVITIES The major safety related maintenance activities performed during April included repacking fourteen Reactor Coolant System valves and four valves in the Chenical and Volune Control System, and encapsulation of the normal charging check valves and two feedwater inlet check valves. We nitrcgen supply isolation valve to "D" Safety Injection Accumulator was reworked. The nozzle ring settings for the Main Stean Safety Valves were changed in accordance with Plant mdification Request #01642. A conoflow regulator was replaced on one Safety Injection test valve.

Preventive maintenance during April included several Local Leak Rate Tests, lubrication of eight 12" gate valve motor operators in the Canponent Cooling Water Systen and semiannual maintenance of the reactor trip breakers.

III. CHANGES, TESTS, AND EXPERIMENTS

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

1.

Plant M3dification Request #00540, Revision 1 - Originated to change the access provided for radiation survey capability of the Radwaste and Auxiliary Building filters and denineralizers. No unreviewed safety or environnental questions are generated as a result of this plant modification.

2.

Plant Maciification Request #00639 - Originated to provide an interconnection for sanple lines HB-ll2-HXD-3/4" and HB-ll3-HXD-3/4" to allow for more effective and easier sampling. No unreviewed safety or environmental questions are generated as a result of this plant modification.

3.

Plant Modification Request #01186, Revision 2 - Originated to change the paperwork associated with the addition of a permanent nitrogen charging systen for the Main Steanline Isolation Valve and Feedwater Isolation Valve nitrogen accunulators. No unreviewed safety or environmental questions are generated as a result of this plant modification.

=_-

4.

Plant Modification Request #01206 - Originated to provide a threaded cap on the blind flange connection for vent valves BG-V496, EH-V206, EM-V207, EM-V208 and EM-V209 to pranote venting of the Dnergency Core Cooling Systen. No unreviewed safety or environmental questions are generated as a result of this plant modification.

5.

Plant tbdification Request #01250 - Originated to reduce the noise level in the Control Room by reducing the ventilation system air flow. No unreviewed safety or environmental questions are generated as a result of this plant nodification.

6.

Plant tbdification Request #01358, Revision 1 - Originated to eliminate nuisance annunciators associated with the Boron Injection Recirculation Systen, which is no longer required to be operable. No unreviewed safety or environmental questions are generated as a result of this plant modification.

7.

Plant Modification Request #01382 - Originated to replace the Allen Bradley differential pressure switches which are not qualified to IEEE standards with qualified United Electric pressure switches on the Dnergency Diesels. No unreviewed safety or environmental questions are generated as a result of this plant modification.

8.

Plant ledification Request #01425 - Originated to provide two spare halon bottles and associated storage racks for the Control Ibom halon systen. Ib unreviewed safety or environmental questions are generated as a result of this plant modification.

9.

Plant Modification Request #01520 - Originated to provide encapsulation of valves BB-V082, BB-V083 and BB-V099 which are experiencing leakage thru the valve packing. No unreviewed safety or environmental questions are generated as a result of this plant modification.

10. Plant Pedification Request #01542 - Originated to replace the piston slide assembly of certain Main Steam Isolation Valve and Feedwater Isolation Valve 4-way hydraulic directional control valves. No unreviewed safety or environmental questions are generated as a result of this plant modification.

11. Plant Modification Request #01549 - Originated to provide quick disconnects on valves HA-V107 and HA-V108 to make it more convenient for obtaining a sanple. No unreviewed safety or environmental questions are generated as a result of this plant modification.

Page 2 of 9

12. Plant Modification Request #WO84-BG105 - Originated to provide quick disconnects on valves BG-V243 and BG-V244 to make it mre convenient for obtaining a sanple. No unreviewed safety or environmental questions are generated as a result of this plant modification.

13. Plant mdification Request #01551 - Originated to provide a manual valve upstrean of check valve HA-V037 in the nitrogen supply line to the Gas Decay Tank header. No unreviewed safety or environmental questions are generated as a result of this plant modification.

14. Plant Modification Request #01555 - Originated to replace the actuator springs on Auxiliary Feedwater Valves AL-FN06, AL-IN08, AL-IN10 and AL-IN12 to prevent developement of a hydraulic lock.

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

15. Plant Modification Request #01560 - Originated to correct drawings M02KJ03 and M02KJ06 and FSAR figure 9.5.7-1 sheets 1 and 2 to reflect as-built conditions on the Dnergency Diesels. No unreviewed safety or environmental questions are generated as a result of this plant modification.

16. Plant mdification Request #01564 - Originated to change the code class for certain valves and piping associated with vent and drain lines on the Component Cooling Water Systen from ASME Section III to ANSI B31.1 special scope. No unreviewed safety or environmental questions are generated as a result of this plant modification.

17. Plant M3dification Request #01566 - Originated to install fire danpers in the HVAC penetrations for Roan 1405. No unreviewed safety or environmental questions are generated as a result of this plant modification.

18. Plant M3dification Request #01566, Revision 1 - Originated to add a Q-List Charge to the modification that installs fire danpers in the INAC penetrations for Boan 1405. No unreviewed safety or environmental questions are generated as a result of this plant modification.

19. Plant !bdification Request #01573 - Originated to replace 1 1/2" stean generator blowdown pipire with 4" schedule 160 piping to reduce erosion. No unreviewed safety or envirorynental questions are generated as a result of this plant modification.

20. Plant Modification Request #01587 - Originated to remove radwaste canpactor SHC04 fron containnent. No unreviewed safety or environmental questions are generated as a result of this plant modification.

Page 3 of 9

i.

21. Plant Modification Request #01596 - Originated to show valves EF-V040 and EF-V072 as locked throttled valves to ensure that Essential Service Water flow to each Control Roan air conditioner is 140 gpn. No unreviewed safety or environnental questions are generated as a result of this plant modification.

22. Plant Modification Request #01639 - Originated to provide seal caps on valves BB-V8378A and BB-V83788 to control bonnet to body leakage. No unreviewed safety or envirorsnental questions are generated as a result of this plant modification.

23. Plant Madification Request #01642 - Originated to change the ring setting on the Main Stean Safety Valves in accordance with NRC Infonnation Notice 86-05. No unreviewed safety or environmental questions are generated as a result of this plant modification.

24. Plant Modification Request #01643 - Originated to weld repair holes drilled into the valve body on valve AE-V330. No unreviewed safety or environmental questions are generated as a result of this plant modification.

25. Safety Evaluation 86-SE Originated to provide a portable air compressor to back up the instninent air system. No unreviewed safety or environnental questions are generated as a result of this temporary modification.

26. Safety Evaluation 86-SE Originated to delete the particulate and iodine portions fran Surveillance Test STS-IC-250A for Containnent Atmospheric Radiation Monitor GT RE-32 until repair parts can be received. No unreviewed safety or environmental questions are generated as a result of this tenporary modification.

27. Safety Evaluation 86-SE Originated to defeat the "B" Stean Generator low-low trip signal while the reactor is shutdown, the "B" Stean Generator is drained and the "B" Diesel Generator is beirs tested. No unreviewed safety or environnental questions are generated as a result of this tenporary modification.

28. Safety Evaluation 86-SE Originated to provide temporary shielding on Pressurizer spray control valves BB PCV455B and BB PCV455C. No unreviewed safety or environmental questions are generated as a result of this temparary modification.

29. Safety Evaluation 86-SE Originated to charge certain Gai-tronics handset stations to headset stations while Reactor Coolant System Isolation Valve Leakage Test is beirg conducted per STS PE-019. No unreviewed safety or environmental questions are generated as a result of this temporary modification.

Page 4 of 9

30. Safety Evaluation 86-SE Originated to provide temporary shielding on hot leg manifold valve BB V8073C. No unreviewed safety or environnental questions are generated as a result of this temporary shielding request.

31. Safety Evaluation 86-SE Originated to cut off danaged threads and rethread the pipe for the condenser vent GK V050 for the Control Roan Air Conditioner Unit. No unreviewed safety or environnental questions are generated as a result of this tenporary modification.

32. Safety Evaluation 86-SE Originated to remove power fran two heaters in the Essential Service Water Punp Roan and to provide a load shed signal for lighting transformer XQB-51 until a ground can be cleared. No unreviewed safety or environnental questions are generated as a result of this temporary modification.

33. Safety Evaluation 86-SE Originated to change certain Gai-tronics handset stations to headset stations while Reactor Coolant System Isolation Valve leakage test STS PE-019 is being conducted. No unreviewed safety or environmental questions are generated as a result of this temporary modification.

34. Plant Modification Request KN84-071, Revision 4 - Originated to provide a Breathing Air System. No unreviewed safety or environmental questions are generated as a result of this plant modification.

35. Plant Modification Request #01557 - Originated to change the annunciators involving the low pressure alarm setpoints for the accumulators for the Main Feedwater Control Valves, Auxiliary Feedwater Control Valves and Main Stean Atmospheric Relief Valves to enhance systen operability. No unreviewed safety or environnental questions are generated as a result of this plant modification.

36. Plant M3dification Request #01639, Revision 2 - Originated to provide an alternate method of closing the 1/4" hole in the seal cap that was installed to enclose the body to bonnet leakage on Reactor Coolant Systen check valves BB-8378A and BB-8378B for the normal charging flow. No unreviewed safety or envirorrnental questions are generated as a result of this plant modification.

37. Safety Evaluation 86-SE Originated to defeat the interlocks on the two ton hoist on the cask handling crane to allow it to transport a dumy fuel assenbly fran the new fuel storage area to the upender in the Fuel Building. No fuel is stored in the fuel pool. No unreviewed safety or environmental questions are generated as a result of this plant modification.

Page 5 of 9

OPERATING DATA REPORT DOCKET NO.

STN 50-482 WOLF CREEK GENERATING STATIOi KANSAS GAS AND ELECTRIC COMPANY DATE 05-01-86 COMPLETED BY M. Williams TELEPHONE 316-364-8831 OPERATING STATUS

'l.

Reporting Period:

April, 1986 Gross Hours in Reporting Period: 719.0 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

'Ihis Month Yr to Date Ctsnulative 5.

Ntsnber of Hours Reactor was Critical 332.4 2439.2 5229.5 6.

Reactor Reserve Shutdown Hours 0.0 41.4 120.2

7.. Hours Generator on Line 320.0 2422.7 5194.3 8.

Unit Reserve Shutdown Hours 0.0 0.0 0.0 9.

Gross Thennal Energy Generated (!461) 933,250 7,932,622 16,807,555

10. Gross Electrical Energy Generated (MWH) 323,585 2,793,388 5,864,478

11. Net Electrical Enorgy Generated (2641) 297,904 2,671,373 5,613,473

12. Reactor Service Factor 46.2 84.7 90.8

'13. ' Reactor Availability Factor 46.2 86.2 92.9 i

14 Unit Service Factor 44.5 84.2 90.2

15. Unit Availability Factor 44.5 84.2 90.2

16. Unit Capacity Factor (Using MDC) 36.7 82.3 86.4

17. Unit Capacity Factor (Using Design MWe) 35.4 79.3 83.3 18.- Unit Forced Outage Rate 6.3 3.1 3.5 l

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

Refueling Outage, currently scheduled to start on 0::tober 9,1986, approximate duration is 55 days.

20.

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

N,

21. Units in test Status (Prior to Commercial Operation): Forecast Achieved Initial Criticality 5-22-85 5-22-85 Initial Electricity 6-13-85 6-12-85 Consnercial Operation 9-09-85 9-03-85 Page 6 of 9

AVERAGE IRILY UNIT POWER LEVEL DOCKET NO.

STN 50-482 WOLP CREEK GENERATING STATION KANSAS GAS AND ELECTRIC COMPANY DATE ~05-01-86 COMPLETED BY M. Willians TELEPHONE 316-364-8831 MON 1H April, 1986 DAY AVERAGE IRILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (M4e-Net)

(MWe-Net) 1 1149 17 0

2 1151 18 O

P 3

1150 19 0

4 1150 20 0

5 1149 21 0

6-720 22 0

7-804 23 0

8 335 24 0

~

9 0

25 318 t

10 0

26 708 11 0

27 842 12 0

28 1126 13 0

29 1142

'14 0

30 1138 15 0

31 N/A 16 0

i 4

+

Page 7 of 9

..~

e UNIT SHlTfDOWN AND POWER REDUCTIONS DOCKET NO. SIN 50-482-WOLF CREEK GENERATING STATIM KANSAS GAS AND ELECTRIC COMPANY DATE 05-01-86 COMPLETED BY M. Williams REPORT KNIH April, 1986 TELEPHONE 316-364-8831 R

I TYPE MEIHODS SHUITING F: FORCED DURATION REASON DOWN 'IHE RFACIOR CORRECTIVE ACTIONS / COMMENTS No Date S: SCHEDULED (HOURS)

(1)

OR REDUCING IOWER(2) 2 860406 F

0 B

1 Repair "B" MFP recirc valve.

3 860408 P

399.0 G

3 Switchyard relay techs inadvertently tripped main generator breaker. (See LER 86-018-00)

The outage was extended to include a scheduled maintenance outage at 0800 on April 9.

W is created 21.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of forced outage and 377.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> of scheduled outage. (See LER 86-019-00)

SLMERY: On April 8,1986, non-nuclear switchyard relay technicians inadvertently tripped the main generator breaker. 'Ihis outage was extended to permit 18 month surveillance tests.

(1)

REASON: A: EQUIPMENT FAILURE (EXPIAIN)

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

METIOD:

1.

MANUAL B: MAINTENANCE OR TEST F: ADMINISTRATIVE 2.

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

AUIOMATIC SCRAM D: REGULA'10RY RESTRICTION H: OIEER (EXPIAIN) 4.

OIEER (EXPIAIN)

Page 8 of 9 5

.s KANSAS GAS AND ELECTRIC COMPANY WOLP CREEK GENERATING STATION UNIT NO. 1 MONDI April, 1986

SUMMARY

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

1%TE TIME EVENP

. April 1, 1986 0001 Unit in Mode 1, Power Operation.

April 6, 1986 0001 Comenced power reduction to 60 percent to allow repair of Main Peed Pump "B" recirculation valve.

1758 Power limited to approximately 84 percent by feedwater heater maintenance.

April 8, 1986 1037 Inadvertent Unit trip, reactor trip caused by switchyard relay technicians.

2137 Reactor Critical.

April 9, 1986 0310 Shutdown to repair pressurizer spray bypass valve.

0800 Outige extended to a Maintenance Outage includirg 18 month surveillance tests.

April 24, 1986 1849 Reactor Critical.

April 25, 1986 0137 Unit synchronized to grid. Unit in Mode 1, Power Operation.

Page 9 of 9

~

KANSAS GAS AND ELECTRIC COMPANY TW ELECTRC COMPANY GLENN L MOESTER vec a pat 6.of set hvCL4am May 15, 1986 U.S. Nuclear Regulatory Ccmnission h@

Director, Office of Resource Management i

Washington, D.C.

20555 j

L MAY l 91986 1

l Mr. E.H. Johnson, Director it/'

Division of Reactor Safety and Projects

~l U.S. Nuclear Regulatory Ccmnission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 KMLNRC 86-094 Re:

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

Enclosed is the April, 1986 Monthly Operating Report for Wolf Creek Generating Station.

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

Yours very truly,

'yh

[f ' h Glenn L. Koester Vice President - Nuclear GLK:see Enclosure xc: PO'Connor (2), w/a JTaylor (12), w/a JCuninins, w/a

, y30 i\\

201 N. Market - Wrctuta, Kansas - Mail Address: PO. Box 208 I M6 chits, Kansas 67201 - Telephone: Area Code (316) 261-6451