ML20154P719

Monthly Operating Rept for Feb 1986

ML20154P719
Person / Time
Site:	Wolf Creek
Issue date:	02/28/1986
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-89-039, KMLNRC-89-39, NUDOCS 8603200403
Download: ML20154P719 (13)

Text

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i WOLF CREEK GENERATING STATION M0hTIHLY OPERATING REPORT 1

MONTH:

February YEAR: 1986 Docket No.: S'IN 50-482 Facility Operating License No.: NPF-42 Report No.

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Subnitted by:

Kansas Gas and Electric Company d

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%e following report highlights the operating expzrience of Elf Creek Generating Station for the month of February, 1986. his report is beiry

. provided pursuant to Technical Specification 6.9.1.8.

I.

SUMMARY

OF OPERATING EXPERIENCE

%e plant operated in Mode 1, Power Operation, most of the month. A forced shutdown was connenced due to a loss of rod control on Shutdown Banks C, D and E.

It was terminated at 54 percent power when a faulty card was replaced. A bad card in the Main Turbine speed control caused a turbine trip and reactor trip on February 22, ending our longest continuous run at 134 days. W e plant was started up on February 24 and, after a hold at 30 percent to allow Stean Generator chmistry to come into specification, operated at near 100 percent for the remainder of the month.

II.

MAJOR SAFETI RELATED MAINTENANCE ACTIVITIES mtor-driven Auxiliary Feedwater Pump "B" was repacked and the Limitorque operators of two of its motor driven valves, AL HV-005 and AL HV-034, were lubricated and adjusted. W e bearings were replaced on Fuel Pool Cleanup Pmps "A" and "B".

Main Stean Pilot Operated Relief Valve, AB PV-004, was reworked. 'Ihe governor controller for the Turbine-driven Auxiliary Feedwater Pung was replaced, as was the Main Turbine impluse pressure transmitter, a power supply in the Emergency Safety Features Actuation Systs and a power isolation board in Radiation mnitor GK-RE-05.

III. CHANGES, TDSTS, 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 February.

1.

Safety Evaluation 86-SE Originated to allew the removal of the valve internals frm the recirculation manual stop valve, HF V326, for the Secondary Liquid Waste Systm High TDS Collector Tanks. No unreviewed safety or environmental questions are generated as a result of this temporary modification.

2.

Safety Evaluation 86-SE Originated to provide a connection point for a Temporary Danineralized Water Unit. W e connections were ma3e to non-safety related piping. No unreviewed safety or environmental questions are generated as a result of this tm porary modification.

3.

Safety Evaluation 86-SE Originated to allow the installation of sanple lines of the rotmeter for Main Condenser vacuan Pumps CCG01A, B, and C.

'Ihe rotmeter pipiry is not safety related. No unreviewed safety or envirorsnental questions are generated as a result of this t m porary modification.

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Safety Evaluation 86-SE Originated to allow the installation of smple lines on the discharge of Condensate Pmps PAD 01A, B and C.

'Ihe affected piping is not safety related. No unreviewed safety or enviromental questions are generated as a result of this tmporary modification.

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5.

Safety Evaluation 86-SE Originated to allow the installation of a speaker on the Gaitronics at the Reactor Operator's Desk in the Control Rom. No unreviewed safety or environmental questions are generated as a result of this temporary modification.

6.

Safety Evaluation 86-SE Originated to allow the installation of "B" reactor trip bypass breaker into the "A" reactor trip breaker cubicle during hot full flow control rod system testing.

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

7.

Safety Evaluation 86-SE Originated to disconnect the input of free-field strong motion accelermeter SG-AR-1 from Seismic Instrmentation Panel SG058 while reworking the accclermeter. No unreviewed safety or enviromental questions are generated as a result of this temporary modification.

8.

Safety Evaluation 86-SE Originated to allow connection of an ungrounded 15 volt direct current power supply to the output of power supply CPS-117 in Seismic Instrunentation Panel SG058, due to the failure of CPS-ll7. No unreviewed safety or enviromental questions are generated as a result of this tmporary modification.

9.

Safety Evaluation 86-SE Originated to provide temporary power frm the PG bus to a compressor and to connect the output of that tmporary cmpressor to the plant service air systen at valve KA V104. No unreviewed safety or enviromental questions are generated as a result of this temporary modification.

10. Safety Evaluation 86-SE Originated to allow removal of the card for alarm window 90B (Diesel Generator Fuel Tank B Level Iow) at the annunciator logic cabinet to silence a nuisance alarm for that window. 'Ihis alarm is not safety related. No unreviewed safety or environmental questions are generated as a result of this temporary modification.

11.

Safety Evaluation 86-SE Originated to allow the installation of a temporary tail piece on high pressure heater 7A relief valve, AE V979, to divert its flow to a separate point in the sane drain, while workmen were working on High Pressure Heater 7B relief valve.,Since both relief valves normally discharge to a comon header, this temporary modification was needed for personnel safety. No unreviewed safety or environmental questions are generated as a result of this temporary modification.

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12. Safety Evaluation 86-SE Originated to allow the installation of tenporary piping fran AE V980 to AE V989 to ciremvent blockage in Seal Water Transmitter instrunent root valve AE V989. '1he jumper was needed to ensure proper seal sater flow to Stean Generator Feed Pump B.

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

13. Safety Evaluation 86-SE Originated to allow the improvenent of connunications for turbine generator testing by replacing four handsets with headsets on the Gaitronics connunications system.

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

14. Safety Evaluation 86-SE Originated to allow reterminating the cable to the Standby Diesel Generator KKJ01A jacket water heater by cutting off the danaged section, stripping and usirg heat shrinking tubing, until new cable can be installed under Plant Mdification Request 1329. No unreviewed safety or environnental questions are generated as a result of this temporary modification.

15.

Safety Evaluation 86-SE Originated to allow the installation of the shaft seal on Energency Exhaust Fan assenbly CGG02B using four temporary bolts. No unreviewed safety or environmental questions are generated as a result of this temporary modification.

16. Safety Evaluation 86-SE Originated to allow the charging of a single cell in non-safety related battery PK14. No unreviewed safety or environmental questions are generated as a result of this temporary modification.

17. Safety Evaluation 86-SE Originated to allow the removal of alaan card 15 for alarm window 93D, Instrument Air Humidity High, in RKC45E3, cubicle 5 until the air dryer unit is repaired. No unreviewed safety or environmental questions are generated as a result of this temporary modification.

18. Safety Evaluation 86-SE Originated to allow the installation of pressure gauges on the Demineralized Water Degasification Punps PAN 02A and PAN 02B, to obtain suction pressure. No unreviewed safety or environnental questions are generated as a result of this temporary modification.

19. Safety Evaluation 86-SE Originated to allow installation of a hose to demineralized water valve AN V079 for use in cleaning the Main Stean Isolation Valve Boon. No unreviewed safety or environnental questions are generated as a result of this temporary modification.

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20. Safety Evaluation 86-SE Originated to allow lifting leads 97 and 98 on TB4 in cabinet RK045C4 to clear a ground on cable 6 LER07HA.which feeds annunciator RK045, North Condensate Pit Smp Level High Alarm. No unreviewed safety or enviromental questions are generated as a result of this temporary modification.

21. Safety Evaluation 86-SE Originated to reverse the wires on terminals 'IB4-8-01 and TB4-8-04 in panel RP05BC for the Diesel Generator "A" day tank level control circuit to make the wirirg agree with the schm atic diagrm. No unreviewed safety or environmental questions are generated as a result of this temporary modification.

22. Safety Evaluation 86-SE Originated to allow lifting the horizontal proximity lead on Reactor Coolant Pmp "A" vibration monitor, to prevent nuisance alarms in the Control Rom. No unreviewed safety or environmental questions are generated as a result of this temporary modification.

23. Safety Evaluation 86-SE Originated to allow'the installation of pressure gauges and isolation valves in the service gas systs upstream of the flex connections to the accmulators for the Main Steam Isolation Valves and the Feedwater Isolation Valves. No unreviewed safety or environmental questions are generated as a result of this temporary modification.

24.

Safety Evaluation 86-SE Originated to allow the removal of power from danpers GF-D062 and GF-D063 while the associated ductwork was being cleaned. No unreviewed safety or enviromental questions are generated as a result of this temporary modification.

25. Safety Evaluation 86-SE Originated to allow the installation of pressure gauges to the Main Turbine stem seal lines. No unreviewed safety or environmental questions are generated as a result of this temporary modification.

26. Safety Evaluation 86-SE Originated to allow lifting wire J405-7 in cable SACQ08A to defeat the low T-ave signal to the Stop Turbine Loading Circuit, until the NBC Group 04 circuit card can be replaced with a NRC Group 10 circuit card pursuant to Plant Modification Request 01198. No unreviewed safety or environmental questions are generated as a result of this temporary modification.

27. Safety Evaluation 86-SE Originated to defeat the invalid alarms frcm Radiation Monitors SJ RE02 and GE RE92 which provide input to the Blowdown and Sample Isolation Valves. Redundant monitors BM RE25 and BM RES2 provide the sme isolation capability. No unreviewed safety or enviromental questions are generated as a result of this temporary modification.

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28. Safety Evaluation 86-SE Originated to cap the four drains to the Floor and Equipnent Drainage System fran the Main Steam Isolation valve Iban while Fyrquel hydraulic fluid was being cleaned up in the roan. No unreviewed safety or environmental questions are generated as a result of this temporary modification.

29. Safety Evaluation 86-SE Originated to allow machining off 3/32 inch fran the botton of the set screw that prevents movement of the nozzle ring on relief valve BG V8118 for the Positive Displacement Chargirg Pump. No unreviewed safety or enviromental questions are generated as a result of this temporary modification.

30. Safety Evaluation 86-SE Originated to allow the installation of test gauges on the suction and discharge of Steam Generator Feed Ptrnp "B".

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

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31. Safety Evaluation 86-SE Originated to allow replacement of a broken weatherhea3 (junction box) for low ta perature switch TSL-063 for Diesel Generator RKJ001A engine coolant system. We replacement weatherhead has the sane form fit and function, but is fran a different manufacturer. No unreviewed safety or environnental questions are generated as a result of this tmporary modification.

32. Safety Evaluation 86-SE Originated to allow the installation of filter / dryer elments on the suction an3 discharge refrigerant lines for the Turbine Building Process Sanpling Lab Air Handling Unit SGE15. No unreviewed safety or environnental questions are generated as a result of this temporary modification.

33. Safety Evaluation 86-SE Originated to allow a restraint of stainless steel wire to be employed to hold a flared swagelok fitting connection together where the stem leakoff tubirg for valve BG HV8146 connects to the two inch leakoff header. We tubiry is D-augmented, non-seismic I.

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

34. Safety Evaluation 86-SE Originated to demonstrate the operability of the Reactor Coolant System pressure isolation valves BB PV8702A, BB PV8702B, EJ HV8701A, and FJ HV8701B by verifyirg that the measured leakage meets the acceptance criteria of Technical Specifications 4.4.6.2.2.

No unreviewed safety or environnental questions are generated as a result of this special test procedure.

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35. Safety Evaluation 86-SE Originated to allow connection of a tsporary hose fran Chmical and Volme Control System drain valve BG V454 to drain valve BG V580 to provide a flow path for Reactor Coolant Pump seal water return while conducting Incal Leak Rate Testing of penetration P-24.

No unreviewed safety or I

enviromental questions are generated as a result of this tmporary modification.

36. Safety Evaluation 86-SE Originated to divert Reactor Coolant Pmp seal water return through the temporary hose installed by Safety Evaluation 86-SE-45, while conducting Local Leak Rate Testing of penetration P-24.

No unreviewed safety or environmental questions are generated as a result of this special test procedure.

37. Safety Evaluation 86-SE Originated to allow defeating the runback of the Main Turbine on loss of a Circulating Water P mp.

No unreviewed safety or environmental questions are generated as a 4

result of this temporary modification.

38. Plant fbdification Request 01502 - Originated to provide aininistrative controls for performance of the first Containment Post-Tensioning Systen inspection, as required by Technical Specification 4.6.1.6.1.

This PMR includes safety evaluations of the work including hoisting and transporting the equipnent involved and failure of the hoisting equipnent. No unreviewed safety or enviromental questions are generated as a result of this plant modification.

39. Plant Fbdification Regaest 01562 - Originated to provide a permanent sampling connection for the Refuelirq Water Storage Tank by connecting tubing and a valve to valve BN V018. No unreviewed safety or environmental questions are generated as a result of this plant modification.

40. Technical Specification 4.6.1.2.d. Change Request - Originated to request a one-time deferment to_the specified 24 month maximum surveillance interval for Incal Leak Rate Testire of certain Contaiment Penetrations that require the plant in Cold Shutdown to perform. No unreviewed safety or environmental questions are generated as a result of this Technical Specification change request.

41. 'Ibchnical Specification Change Request - Originated to request a one-time deferment of the 18 month surveillance interval for certain surveillances that require the plant in Cold Shutdown'for their performance. No unreviewed safety or enviromental questions are generated as a result of this 'Ibchnical Specification change request.

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42.

Safety Evaluation 86-SE Originated to allow installation of a pressure gauge on the suction of "B" Centrifugal Charging Pump to facilitate performance of a surveillance test. No unreviewed safety or environnental questions are generated as a result of this temporary modification.

43. Plant m dification Request 01358 - Originated to eliminate the Boron Injection Recirculation System (BIRS) annunciators. Since Boron Injection Tank concentration has been reduced to 2000 ppn, the BIRS is no longer required to be in service. No unreviewed safety or environnental questions are generated as a result of this plant modification.

44.

Safety Evaluation 86-SE Originated to allow the use of the five ton hoist of the cask handling crane to transport a dtuny fuel assenbly from the new fuel storage area to the upender, to facilitate functional testing of the upender. We fuel pool is flooded, the transfer canal is not, and the transfer canal gate is in place, preventing the use of the spent fuel pool bridge crane.

Were is no fuel in the spent. fuel pool. No unreviewed safety or environmental questions are generated as a result of this tenporary modification.

45. Safety Evaluation 86-SE Originated to allow the use of a temporary cover and fasteners on the lower right hand side of class IE, IEEE 323 qualified 480 Volt Motor Control Center NG03T, because the original ecner was lost. No unreviewed safety or environmental questions are generated as a result of this temporary modification.

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3 OPERATING DATA REPORP DOCKET NO.

SIN 50-482 WOLF CREEK GENERATING STATION KANSAS GAS AND ELECTRIC COMPANY DATE 03-01-86 COMPLETED BY M. Williams TELEPHONE 316-364-8831 OPERATING STATUS 1.

Reporting Period:

February, 1986 Gross Hours in Reporting Period: 672.0 2.

Currently Authorized Power. Level (MNt) : 3411 Max. Depend. Capacity (MNe-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 This mnth Yr to Date Cunulative 5.

Number of Hours Reactor was Critical 618.8 1362.8 4153.1 6.

Reactor Reserve Shutdown Hours 41.4 41.4 120.2 7.

Hours Generator on Line 614.7 1358.7 4130.3 8.

Unit Reserve Shutdown Hours 0.0 0.0 0.0 9.

Gross Thermal Energy Generated (MWH) 2,005,668 4,486,147 13,361,080

10. Gross Electrical Energy Generated (MWH) 711,183 1,584,477 4,655,567

11. Net Electrical Energy Generated (MWH) 681,191 1,521,491 4,463,591

12. Reactor Service Factor 92.1 96.2 96.7

13. Reactor Availability Factor 98.2 99.2 99.5-14.

Unit Service Factor 91.5 96.0 96.1

15. Unit Availability Factor 91.5 96.0 96.1

16. Unit Capacity Factor (Using MDC) 89.9 95.3 92.1

17. Unit Capacity Factor (Using Design MWe) 86.6 91.8 88.8

18. Unit Forced Outage Rate 8.5 4.0 3.8

19. Shutdowns Scheduled Over Next 6 Months (Type, Date, and 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 Connercial Operation): Forecast Achieved Initial Criticality 5-22-85 5-22-85 Initial Electricity 6-13-85 6-12-85 Commercial Operation 9-09-85 9-03-85 9

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AVERAGE DAILY UNIT POWER LEVEL l

DOCKET NO.

STN 50-482 WOLF CREEK GENERATING STATION KANSAS GAS AND ELECTRIC COMPANY DATE 03-01-86 i

COMPIETED BY M. Williams TELEPHONE 316-364-8831 I

M0tml February, 1986 DAY AVEPME DAILY POWER LEVEL DAY AVERAGE DAILY IOWER LEVEL (MWe-Net)

(MWe-Net) 1 1149 17 1149 2

1035 18 1150 3

1027 19 1152 4

1145 20 1154 5

1150 21 1149 6

1151 22 189 7

1152 23 0

8 1153 24 123 4

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1152 25 746 1

l 10 1143 26 1143 11 1152 27 1150 12 1144 28 1154-13 1134 29 N/A i

14 1140 30 N/A l

15 1148 31 N/A l

16 1148 i

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s DOCKET NO.

STN 50-482-WOLF CREEK GENERATI m SPATION KANSAS CAS AND ELFfTRIC COMPANY DATE 03-01-86 COMPLETPED BY M. Willians REPORT WNTil February, 1986 TELEPflONE 316-364-8831 j

TYPE M1-mlODS SIILTI' PING L

F: FORCED DURATION REASON DOLW1 'IllE RFACIOR CORRECP1VE ACr10NS/COtHENTS No Date S: SCliEDULED (HOURS)

(1)

OR REDUCING POWER (2) t 1

860222 F

57.3 A

3 Unit trip caused by a bad card in speed control circuit.

(See LER 86-007-00.)

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k StBGERY: On February 22, a bad card in the Main Turbine speed control circuit caused a unit trip and reactor scran.

4 (1)

REASON: A: EQUIPMENT FAILURE (EXPIAIN)

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

MimlOD:

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B: MAINIENANCE OR TEST F: ADMINISTRATIVE 2.

MANUAL SCRAM j

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

ALTPOMATIC SCIW1 D: REGJIA'IORY RESTRICTION H: Ofl11ER (EXPIAIN) 4.

OIllER (EXPIAIN)

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KANSAS GAS AND ELECTRIC COMPANY

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WOLF CREEK GENERATING STATION i

UNIT NO. 1 MONI11 February, 1986 i-

SUMMARY

OF OPERATING EXPERIENCE i

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

DATE TIME EVENP i

February 1, 1986 0000 Unit in Mode 1, Power Operation.

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February 3, 1986 1405 Carmenced power decrease to go to hot shutdown because of no autcmatic control of Shutdown Banks C, D, and E.

i 1534 Discontinued power decrease at 54 percent power.

f 1700 Carmenced power increase to 100 percent.

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February 22, 1986 0400 Turbine trip and reactor trip.

(LER 86-007-00)

February 24, 1986 0910 Reactor critical.

1316 Synchronized with grid, increased power to 30 l

percent. Held power at 30 percent until steam generator chmistry cane in specification.

February 25, 1986 0737 Comenced power increase to 100 percent.

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KANSAS GAS AND ELECTRIC COMPANY TM ELECTFUC CCWPANY GLENN L MOESTER v<s PmEs+0teer - %vct.Ese March 11, 1986 h

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Director, Office of Resource Management

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U.S. Nuclear Regulatory Commission ij Washington, D.C.

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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 86-039 Re:

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

Enclosed is the February, 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, i

46 Glenn L. Koester Vice President - Nuclear GLK:see Enclosure xc: P0'Connor (2), w/a JTaylor (12), w/a JCummins, w/a d

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

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