ML20214J323

Monthly Operating Rept for Oct 1986

ML20214J323
Person / Time
Site:	Wolf Creek
Issue date:	10/31/1986
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-86-219, NUDOCS 8612010254
Download: ML20214J323 (13)

Text

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e WOLF CREEK GENERATING STATION M0tmiLY OPERATING REPORT MON 1H:

October YEAR: _1986 Docket No.: STN 50-482-Facility Operating License No.: NPF-42 Report No.

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4 Subnitted by:

I Kansas Gas ard Electric company t

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34 sh e612o10254 e61oai PDR ADOCK 05000482

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- me following report highlights the opertting experience of Wlf Creek Generating Station for the moni of October,1986. This report is bein3 provided pursuant to Technical Specification 6.9.1.8.

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SUMARY OF OPERATING EXPERIENCE ~

The plant operated in m de 1, Power Operation until October 16, 1986, when the plant was shutdown for the first refueling outaje. No major power reductions occurred prior to connencement of the shutdown.

4-II.

MMOR SAFETY RELATED MAINFENANCE ACTIVITIES a-Major safety related maintenance activities include replacement of a-logic board in Etnergency Fuel Oil level transnitter JE-LIT'025, replacement of an anplifier in Stean generator "D" level transnitter AD-LY504, replacement of a broken switch for RCS loop 2 RTD manifold l

flow transnitter BB-FIS427, replacement of RCP "C" seal cartridge, i

rework of "B" Centrifugal Charging Pump to correct leaks, removal of l

the Reactor vessel head, repacking various RfD manifold isolation valves, rework of Main Stean Isolation Valves and Feedwater Isolation Valves including the incorporation of plant modifications, eddy current testing of "B" and "C" stean generators, testing of all Main Stean safeties, annual maintenance of "A" RHR pump motor,-annual maintenance of Diesel Generator ventilation danpers, annual maintenance of "A" Centrifugal Charging Pump, -inspection of NB circuit j

breakers and insulation testing of NB tranformers.

l III. CHANGES, TESTS, AND EXPERIMEMPS j

W e following is a brief description of safety evaluations performed pursuant to 10 CFR 50.59 on changes, tests, and experiments during the i

month of October.

I 1.

Plant Modification Request WO64-KE023, revision 1 - Originated to i

add the RCC tool technical manual to the docunentation for this l

PMR, which provided alditional tool hangers on the wall of the i

cask loaling pit and generic supports on the Spent Fuel Pool Bridge Crane. The PMR also added air and electric service to j

allow the use of the RCC Chanjing Tool fran the bridge crane. No

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unreviewed safety or environnental qiestions are generated as a j

result of this plant modification.

i 2.

Plant m dification Request KN84-065, revision 1 - Originated to change the monitor display to show the location for radiation j

monitor SD-RE-41 as being on the Refueling Machine Manipulator Crane as it was relocated in revision O.

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

modification.

i 3.

Plant Modification Request 00657, revision 1 - Originated to provide permanent scaffold supports an1 aiditional docunentation

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to the PMR, which changed the method of attachment of the diaphran j

to the Boric Acid Tanks. No unreviewed safety or environmental j

questions are generated as a result of this plant modification.

4.

Plant Edification Request 01099, revision 3 - Originated to i revise the safety evaluation to the PMR, which modified the f

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

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5., Plant Modification Request 01235, revision 3 - Originated to add acoustical' booths in the Turbine Building and Contairunent and Public Address Systen devices in the ESW Pumphouse and Chlorination Buildirg. No unreviewed safety or nnvirornnental questions are generated as a result of this plant modification.

6.

Plant Modification Request 01235, revision 4'- Originated to add a tenninal box in the Auxiliary Building. No unreviewed safety or

. envirornnental questions are generated as a' result _of this plant modification.

7.

Plant' Modification Request 01327, revision 1 - Originated to revise the safety evaluation to the PMR, which provided work platfonns around the Main Stean Isolation valves and Main Feedwater Isolation Valves. No unreviewed safety or environmental questions are generated as a result of this plant modification.

8.

Plant Modification Request 01327, revision 2 - Originated to change the fixed ladder support provided in the PMR. No unreviewed safety or environnental questions are generated as a result of this plant modification.

9.

Plant Modification Request 01333, revision 4 - Originated to modify the piping, add a safety evaluation and improve the.

doctanentation to this PMR, which improves the drainage in the Decontanination Systen. No unreviewed safety or envirorynental questions are generated as a result of this plant modification.

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10. Plant Modification Request 01518,^ revision 1 - Originated to allow a missirg tooth on the rotor adjusting sleeve and improve the I

doctsnentation to this PMR which changes the Diesel Generator lube oil keep wann ptsnps.No unreviewed safety or environnental i.

questions are generated as a result of this plant modification.

11. Plant Modification Request 01573, revision 2 - Originated to change the scope and to improve the doctanentation to this PMR l

which changes the piping in the Steam Generator Blowdown Systen and improves access to valve BM v003. No unreviewed safety or environmental questions are generated as a result of this plant modification.

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12. Plant Modification Request 01624, revision 2 - Originated to i

revise the safety evaluation armi knprove the doctanentation to this 1

PMR, which provides positive venting of the starting air to the i

Diesel Generators. No unreviewed 'safoty or envirorsnental questions are generated as a result of this plant modification.

13. Plant 1%3ification Request 01722, revision 4 - Originated to provide additional settings and improve the docunentation to this P4R, which revises motor operated valve limit switch settirgs. No unreviewed safety or environmental questions are generated as a result of this plant modification.

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~ 14. Plant Modific:_ tion Request 01722, revision 5 - Originated to pewide alditional settings and improve the docunentation to this PMR. No unreviewed safety.or environeental questions are generated as a result of this plant modification.

15. Plant ledification Request 01772, revision 6 - Originated to provide additional settings to this PMR. No unreviewed safety _or environmental questions are generated as a result of this plant

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modification.

16. Plant Modification Request 01790 - Originated to improve the turbine generator trip system reliability'and reduce the probability of forced outaJes. No unreviewed safety _or environnental' questions are generated as a result 'of this' plant modification.

17. Plant Modification Request 01796 - Originated to provide for.

venting entrapped air fran the cooling water lines to the Chilled Water system lube oil cooler. No unreviewed safety or environmental questions are generated as a result of this plant modification.

18. Plant ledification Request 01831.- Originated to identify the proper reference documentation for calibration of the thermocouple / core cooling monitor. No unreviewed safety or environnental questions are generated as a result of this plant modification..

19. Plant Modification Request 01842 - Originated to modify the wiring to motor operated valve limit switches. No unreviewed safety or environmental questions are generated as a result of this plant modification.

20. Plant Modification Request 01855 - Originated to allow installation of Heli-Coils in Stean Generator manway bolt holes.

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

21. Safety Evaluation 86-SE-121 - Originated to modify the security computer software concerning the card reader for door 14031. No unreviewed safety or environmental questions are generated as a result of this temporary modification.

22. Safety Evaluation 86-SE-122 - Originated to temporarily relocate a card reader associated with room 1403. No unreviewed safety or environnental questions are generated as a result of this tenporary modification.

23. Safety Evaluation 86-SE-129 - Originated to provide a tenporary Breathing Air manifold inside containnent. No unreviewed safety or environnental questions are generated as a result of this tenparary modification.

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24. Safety Evaluation 86-SE-131 - Originated to provide a shroud to prevent impingenent of cold air on the low tenperature alarm switch for the Diesel Generator jacket water heating system. No unreviewed safety or environnental questions are generated as a result of this tenporary modification.

25. Safety Evaluation 86-SE-132 - Originated to tenporarily change the torque switch setting for valve AUW33 perding a revision to PMR 1722. No unreviewed safety or environnental questions are generated as a result of this temporary modification.

26. Safety Evaluation 86-SE-133 - Originated to allow tenporary lead blanketing of the CVCS regenerative heat exchanger durirs Modes 5 and 6.

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

27. Safety Evaluation 86-SE-134 - Originated to tenporarily defeat Radiation Monitor BM-RE-52 isolation signal while no flow exists in the fluid it monitors to prevent blowdown isolation fran its spurious alarms. No unreviewed safety or environmental questions.

are generated as a result of this tenporary modification.

28. Safety Evaluation 86-SE-135 - Originated to allow tenporary lead blanketing of the CVCS excess letdown heat exchanger during Modes 5 and 6.

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

29. Safety Evaluation 86-SE-136 - Originated to temporarily allow access to the Auxiliary Building fran the 2032 foot level of the Ocmnunications Corridor during the refueling outage. No unreviewed safety or environnental questions are generated as a result of this tenporary modification.

30. Safety Evaluation 86-SE-137 - Originated to allow teuporary lead blanketing of the reactor vessel head while it is on the storage stan3. No unreviewed safety or environmental questions are generated as a result of this temporary modification.

31. Safety Evaluation 86-SE-139 - Originated to temporarily bypass an underground section Auxiliary Boiler excess fuel oil return line.

No unreviewed safety or envirornnental questions are generated as a result of this tenprary m dification.

32. Safety Evaluation 86-SE-141 - 3riginated to tenporarily renove two 15KW heaters fron service in the ESW pumphouse and to provide a functional load shed signal for lightire transformer X0B-51. No unreviewed safety or environnental questions are generated as a result of this tenporary modification.

33. Safety Evaluation 86-SE-142 - Originated to tenprarily defeat the autanatic isolation feature of the Feedwater Isolation Valves, during Modes 4, 5 and 6.

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

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34. Safety Evaluation 86-SE-143 - Originated to tenporarily install pressure gages on the discharge of stean generator drain punps PBM03A and PIE 03B. No unreviewed safety or environmental questions are generated as a result of this tenporary modification.

35. Safety Evaluation 86-SE-144 - Originated to temporarily prevent flow thru the gland sten leakoff tubing for valves BB-V8085, BG-LV459 and BG-LV460. No unreviewed safety or environmental qaestions are generated as a result of thic tenporary modification.

36. Safety Evaluation 86-SE-145 - Originated to allow a filter purchased for special scope usage to be used as CVCS filter FBG06, downstrean of the letdown denineralizers. No unreviewed safety or environnental questions are generated as a result of this tenporary modification.

37. Safety Evaluation 86-SE-146 - Originated to allow tenporary lea 3 blanketing of RCS loop 2 drain valves BB-V028 and BB-V029, during M3 des 5 and 6.

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

38. Safety Evaluation 86-SE-147 - Originated to allow tenporary lead blanketing of RCS pipe 54-BCA-3" (loop 3 to CVCS letdown), during modes 5 and 6.

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

39. Safety Evaluation 86-SE-148 - Originated to allow temporary lead blanketing of RCS pipe 74-BCA-2" and valve BB-V065 (loop 4 to excess letdown), during Modes 5 and 6.

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

40. Safety Evaluation 86-SE-149 - Originated to temporarily defeat Radiation Monitor BM-RE-52 Blowdown and Sanple Isolation Signal to prevent unnecessary isolations from its spurious alaans. No unreviewed safety or environnental questions are generated as a result of this temporary nodification.

41. Safety Evaluation 86-SE-150 - Originated to allow tenporary leal blanketing of RCS loop 1 RfD manifold valves BB-V8073A, BB-V8074A, BB-V006, BB-V012, BB-V013 and BB-V014 and associated piping 17-DCA-2" and BCB-3/4", 2007'6" to 2015' elevation, during nades 5 aM 6.

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

42. Safety Evaluation 86-SE-151 - Originated to allow temporary lea 3 blanketing of RCS loop 1 drain valves BB-V008 and BB-V009 aM pipe 20-BCA-2", during Modes 5 and 6.

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

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43. Safety Evaluation 86-SE-152 - Originated to tmporarily defeat the Stean Generator LoIo water level trip signals during Modes 4, 5 and 6.

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

44. Safety Evaluation 86-SE-153 - Originated to allow temporary lead blanketing of RCS loop 2 RfD manifold valves BB-V8073B, BB-V8074B, BB-V031, BB-V038, BB-V039, associated piping aM 33-BCA-3" fran 2008'6" to 2015' elevation, during Modes 5 ard 6.

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

'45. Safety Evaluation 86-SE-154 - Originated to allow temporary lead blanketing of RCS loop 3 RfD manifold valves BB-V8073C, BB-V8074C, BB-V045, BB-V051, BB-V053, BB-V054 and associated piping 49-BCA-3", Sl-BCA-2" and BCB-3/4", during Modes 5 and 6.

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

46. Safety Evaluation 86-SE-155 - Originated to allow temporary lead blanketing of RCS loop 4 RID manifold valves BB-V8073D, BB-V8074D, BB-V064, BB-V070, BB-V073, BB-V074, the RfD manifold, associated piping, 65-BCA-2", 66-BCA-3", 68-BCA-2" ard 215-BCA-2" from 2008'6" to 2015' elevation, during Modes 5 ard 6.

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

47. Safety Evaluation 86-SE-156 - Originated to allow temporary lead blanketing to be laid flat on top of the gratinj of the work platform beneath RCP "C", during Modes 5 and 6.

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

48. Safety Evaluation 86-SE-157 - Originated to allow temporary lead blanketing of CVCS piping 020-HCB-4" and 204-HCB-3", during Modes 5 and 6.

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

49. Safety Evaluation 86-SE-158 - Originated to allow the temporary removal of the internals to check valve HF-V310 to allow flow from the Secondary Waste system evaporator bottoms to the bulk waste disposal connection. No unreviewed safety or environmental questions are generated as a result of this temporary mMification.

50. Safety Evaluation 86-SE-159 - Originated to allow the replacement of two O-rirgs fitted at the Lotton of the vertical stop of the actuator for Essential Service Water to Control Building HVAC valve GK-V768, with O-rirgs made of Viton. No unreviewed safety or environmental questions are generated as a result of this tenporary modification.

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51. Safety Evaluation 86-SE-160 - Originated to allow automatic transfer switches to be tenporarily installed in the non-class IE Instrunent AC Power Systen in accordance with drawings provided in PMR 935 preliminary package. No unreviewed safety or envirormental questions are generated as a result of-this temporary modification.

-52. Proposed FSAR, Section 15.7, Revision - Originated to allow fuel handling operations without running the hydrogen mixing fans and

' contairnent coolers. No unreviewed safety or envirormental questions are generated as a result of this FSAR revision.

53.WOGSCycle210CFR50.59 Evaluation-Originatedtoevbuatethe FSAR chapter 15 events with the Cycle 2 reload design. No unreviewed safety or envirornental questions are generated as a result of this safety evaluation.

54. Safety Evaluation 86-SE-126 - Originated to allow the temporary replacement of perimeter detection units with those of another manufacturer. No unreviewed safety or environmental questions are generated as a result of this temporary modification.

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OPERATING DATA M E g.

DOCKgf NO, S'IN 50-482 WOLF CREEK GENERATING STATION KANSAS GAS AND ELECTRIC COMPANY DATE 11-01-86 00MPLE7 PED BY M. Williams TELEPHONE 316-364-8831 OPERATING STATUS 1.

Reportiry Period:

October,1986 Gross Hours in Reporting Period: 745 2.

Currently Authorized Power Level (MWt): 3411 Max. Depend. Capacity (MWe-Net): 1128 Design Electrical Rating (lNe-Net): 1170 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 Cmulative 5.

Nmber of Hours Reactor was Critical 363.1 6216.7 9007.0 6.

Reactor Reserve Shutdown Hours 0.0 92.5 171.3 7.

Hours Generator on Line 362.0 6178.4 8950.0 8.

Unit Reserve Shutdown Hours 0.0 0.0 0.0 9.

Gross Thermal Energy Generated (MWH) 1,219,774 20,220,409 29,095,342

10. Gross Electrical Energy Generated (MWH) 428,192 7,069,422 10,140,512

11. Net Electrica' Energy Generated (fMI) 411,511 6,766,386 9,708,486

12. Reactor Service Factor 48.7 85.2 _

88.5

13. Reactor Availability Factor 48.7 86.5 90.2

14. Unit Service Factor 48.6 84.7 88.0

15. Unit Availability Factor 48.6 84.7 88.0

16. Unit Capacity Factor (Using MDC) 49.0 82.2 84.6

17. Unit Capacity Factor (Using Design MWe) 47.2 79.3 81.5

18. Unit c' breed Outage Rate 0.0 4.5 4.3

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

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

12-11-86

21. Units in test Status (Prior to Cmmercial Operation):

Forecast Achieval Initial Criticality 5-22-85 5-22-85 Initial Electricity 6-13-85 6-12-85 Cmmercial Operation 9-_09-85 9-03-85 Page 8 of 11

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,s AVERAGE DAILY UNIT POWER LEVEL DOCKE'f NO.

SIN 50-482 WOIE CREEK GENERATING SEATIOi KANSAS GAS AND ELECTRIC COMPANY DATE 11-01-86 00MPLE7 FED BY M. Williams TELEPHONE 316-364-8831 MON 1H October, 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL

(!We-Net)

(M4e-Net) 1 1144 17 0

2 1122 18 0

3 1115 19 0

4 1144 20 0

5 1147 21 0

6 1146 22 0

7 1145 23 0

8 1144 24 0

9-1144 25 0

10 1143 26 0

11 1144 27 0

12 1136 28 0

13 1135 29 0

14 li45 30 0

15 1118 31 0

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• ,c, UNIT SHUIYDel AND POWER REDUCTIONS DOCKET NO.

S'IN 50-482 WOLF CREEK GENERATING STATION KANSAS GAS AND ELECTRIC COMPANY DATE 11-01-86' 00MPLETED BY M. Willians RENRP M2ml October, 1986 TELEPHONE 316-364-8831 TYPE MEH100S SHUITING F: EORCED DURATION REASON DOW ' DIE REACIOR CORRECPIVE ACTIONS /CortefrS No Date S: SCHEDULED (HOURS)

(1)

OR REDUCING NWER(2) 11 861016 S

382.0 C

1 First refueling outa3e.

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spesutY: 'Ihe unit was shut 4wn for its first refuelirx3 outa3e at 0201 on October 16, 1986.

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REASON: A: EQUIPMENT FAIIIJPS (EXPIAIN)

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

ME'HIOD:

1.

MANUAL B: MAIITPENANCE OR TEST F: ADMINISTRATIVE 2.

MANUAL SCRAM t

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

AUIOMATIC SCRAM D: REGUIA'IORY RESTRICPION H: OniER (EXPIAIN) 4.

OniER (EXPIAIN) 1 J

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m-KANSAS GAS AND ELECTRIC COMPANY WOLF CREEK GENERATIfG STATION UNIT NO. 1 MORIN October, 1986 SUlHARY OF OPERATING EXPERIENCE Listed below in chronological sequence is a suamary of operatiry experiences for this month which required loa 3 reduction or resulted in significant non-load related incidents.

DA'IE TIME EVENT October 1, 1986 0000 Unit in Mode 1, Power Operation October 15, 1986 2150 Cmmenced reducing power in preparation for refueling outage.

October 16, 1986 0201 Tripped unit output breaker.

0304 Unit in %ie 3, Hot Standby.

October 17, 1986 0810 Unit in Mode 4, Hot Shutdown.

1619 Unit in %3e 5, Cold Shutdown.

October 25, 1986 2053 Unit in Mode 6, Refueling.

Page 11 of 11

KANSAS GAS AND ELECTRIC COMPANY THEE ELECTAC COMPANY November 13, 1986 ooa~~t oserea WTE pag.@gNY, Nyct gan l

I Director, Office of Resource Management M i 81986 U.S. Nuclear Regulatory Commission Washington, D.C.

20555 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 86-219 Re:

Docket No. STN 50-482 Subj: October, 1986 Honthly Operating Report Gentlemen:

Enclosed is the October, 1986 Honthly Operating Report for Wolf Creek Generating Station.

This submittal is beind made in accordance with the requirements of Technical Specification 6.9.1.8.

Yours very truly, AA-I Glenn L. Koester Vice President - Nuclear GLK:see Enclosure cc: P0'Connor (2), w/a JTaylor (12), w/a JCummins, w/a Lf m

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201 N. Market - Wichita, Kansas - Mad Address: PO. Box 208 I Wichita, Kansas 67201 - Telephone: Area Code (316) 26 t 6451