ML20212H471

Monthly Operating Rept for Dec 1986

ML20212H471
Person / Time
Site:	Wolf Creek
Issue date:	12/31/1986
From:	Mike Williams, Withers B WOLF CREEK NUCLEAR OPERATING CORP.
To:	NRC OFFICE OF ADMINISTRATION (ADM)
References
WM-87-0018, WM-87-18, NUDOCS 8701210440
Download: ML20212H471 (11)

Text

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e WJLF CREEK GENERATING STATION M00miLY OPERATING REPORT MOtmi: December YEAR: 1986 Docket No.: 50-482 l

FEcility Operatiry License No.: NPF-42 Report No. 22

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Subnitted by:

Wolf Creek Nuclear Operatirg Corporation 8701210440 861231 fet !,I PDR ADOCK 05000482  :

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. We following report highlights the operating experience of Wolf Creek Generatin3 Station for the month of December,1986. W is report is being provided pursuant to Technical Specification 6.9.1.8.

I.

SUMMARY

OF OPERATING EXPERIENCE The plant renained in Made 6, Refueling, until Decenber 5. Plant heatup was comenced on December 11, criticality was achieved on Decenber 18, synchronization occurred on December 21 and 100 percent power was reached on Decenber 26. Reactor trips occurred on December 20 and 22 due to low-low Stemt Generator levels. Following each trip, plant startup and power ascension resuned the sane day, reaching 100 percent power on Decenber 26.

II. MAJOR SAFl?IY REIATED MAINTENANCE ACTIVITIES Major safety related maintenance activities included replacement of level transmitters for the Reactor Vessel, Stean Generators aM Safety Injection Accunulators; Reactor Vessel head assenbly; Stean Generator sludge lancing; a modification to the Reactor Coolant Systen PORV's; replacing, reworking and repacking valves; repairing leakin] fittinJs on the Diesel Generator fuel syste:n and reworking MSIV 4-way slides.

III. CHANGES, TESTS, AND EXPERIMENTS The following is a brief description of safety evaluations performed pursuant to 10 CFR 50.59 on changes, tests, and experiments during the month of Decenber.

1. Safety Evaluation 86-SE-172 - Originated to connect a hose to route the Recycle Evaporator concentrates to the Spent Fuel Pool:

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

2. Safety Evaluation 86-SE-173 - Originated to allow corrosion test coupons to be installed in the Service Water System, Component Cooling Water System, Condenser Vacuan Punp Seal Cooler and Stator Cooler Heat Exchanger. No unreviewed safety or environmental questions are generated as a result of this tenporary mcdification.

3. Safety Evaluation 86-SE-173, revision 1 - Originated to delete the Congnent Cooling Water Systen for the scope of this temporary modification. No unreviewed safety or environmental questions are generated as a result of this tenporary modification.

4. Safety Evaluation 86-SE-174 - Originated to defeat the high vibration trip fran the Instrunent and Service Air Canpressor. No unreviewed safety or environmental questions are generated as a result of this tenporary modification.

5. Safety Evaluation 86-SE-175 - Originated to replace the vent tubing frun the fuel return heMer of "A" Diesel Generator to its accunulator tank with slightly thicker walled tubing. No unreviewed safety or envircnnental questions are generated as a result of this temporary modification.

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6. Safety Evaluation 86-SE-176 - Originated to remove two 15KW heaters fran service at the ESW punp roan and provide a functional load shed signal for stand by lighting transformer XQB-51. No unreviewed safety or environmental questions are generated as a result of this tenporary modification.

7. Safety Evaluation 86-SE-177 - Originated to junper two limit switches on the Spent Fuel Bridge Crane to allow it to be used to move the Decon Machine to the Fuel Transfer Canal. No unreviewed safety or environmental questions are generated as a result of this tenporary modification.

8. Safety Evaluation 86-SE-178 - Originated to change tm Gai-Tronics stations fran handsets to headsets. No unreviewed safety or-environnental questions are generated as a result of this tenporary modification.

9. Safety Evaluation 86-SS-179 - Originated to allow connection of a temporary dp cell across flow elenent EM FE-928 and use it instead of flow indicator EM FI-928A for measuring leakage fran RCS pressure isolation valves. No unreviewed safety or environmental questions are generated as a result .of this tenporary modification.

10. Safety Evaluation 86-SE-180 - Originated to change one Gai-Tronics station fran handset to headset. No unreviewed safety or environmental questions are generated as a result of this tenporary modification. -

11. Safety Evaluation 86-SE-181 - Originated to provide two j connections from the Service Water Systen and one connection fran the Gland Water Systen to the MIC and Biocide Analysis trailer at the Circ Water Screen House. No unreviewed safety or environmental questions are generated as a result of this tenporary mcdification.

12. Safety Evaluation 86-SE-182 - Originated to cap the packing leak-off line for Stean Generator blowdown valve BM V002. No unreviewed safety or environmental questions are generated as a result of this temporary modification.

l 13. Safety Evaluation 66-SE-183 - Originated to replace the hand driven chain operated hoist HKF-13 with an electric motor driven

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

14. Safety Evaluation 86-SE-184 - Originated to replace hand-driven hoist HKF-33 with a motor-driven hoist. No unreviewed safety or environnental questions are generated as a result of this tenporary modification.

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15. Plant ModificLtion Requcst N004-KE023, revision 3 - Originated to del ta the two bridga crane tool supports fran this PMR, which provides additional support racks on the cask loading pit walls for three new refueling tools. No unreviewd safety or environmental questions are generated as a result of this plant modification.

16. Plant Modification Request KN84-065, revision 2 - Originated to revise data for cable 15SDIO3G to be consistent with the previously installed vendor supplied cable for this PMR, which relocates radiation monitor SD-RE-41 to the Manipulater Crane. tb unreviewed safety or environmental questions are generated as a result of this plant modification.

17. Plant !bdification Request KN84-076, revision 1 - Originated to utilize WestinJ house check valves in lieu of Anchor /Darlinj check valves in this PMR, which installs check valves in the Antrifugal Charging Punps flow path to the Regenerative Heat Exchanger. No unreviewed safety or environnental questions are generated as a result of this plant modification.

18. P1 ant ?bdification Request KN84-088, revision 1 - Originated to aii a base plate and redesign a pipa hanger in this PMR, which installs pennanent flow iMicators for the Auxiliary Feed Punps.

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

19. Plant Modification Request 00441, revision 5 - Originated to correct the wiring on this PMR, which installs Control Ibom alacus for ESFAS Not in Nonnal, ERFIS Initiate and ICP Upper Bearing Lube Oil Level. No unreviewed safety or environnental questions are generated as a result of this plant modification.

20. Plant Pbdification Request 00899, revision 9 - Originated to delete all but one access platfonn for this PMR, which relocates the SI Accumulator Level Transmitters. No unreviewed safety or environnental questions are generated as a result of this plant modification.

21. Plant Modification Request 00899, revision 10 - Originated to delete the coMuit support plates on wall 26 of this PMR. No unreviewed safety or environnental questions are generated as a result of this plant modification.

22. Plant tbdification Request 00899, revision 11 - Originated to provide an alternate tubin) installation for this PMR. tb unreviewed safety or environnental questions are generated as a result of this plant mdification.

23. Plant Mxlification Ibquest 01233, revision 2 - Originated to revise the valving on this PMR, which replaces the level instrunents on the Caustic and Acid storage Tanks. No unreviewed safety or environnental questions are ' generated as a result of this plant modification.

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24. Plant Modification Request 01482, revision 1 - Originated to prevent a " Source Range High Voltage Failure Alarm" above P10 in this PMR, which keeps the Boron Dilution Flux Doubling relays operational while other relays are in test. No unreviewed safety or environmental questions are generated as a result of this plant nodification.

25. Plant itxlification Request 01574 - Originated to prevent back flow into the Decontanination Exhaust Scrubbers drain lines. No unreviewed safety or environmental questions are generated as a result of this plant modification.

26. Plant Wxlification Request 01888, revision 1 - Originated to accept hard surfacing performed on 0.250 inch thick base metal by procedures and welders qualified to a minimun base metal thickness of 1.000 inch on this PMR, which harx1 surfaces an area of pipe wall that has experienced cavitation erosion. No unreviewed safety or environnental questions are generated as a result of this plant modification.

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• OPERATING DATA REPORP DOCKET NO. 50-482 i-

. . WOLF CREEK GENERATING M M)LF CREEK NUCLEAR OPERATING CORPORATION DATE 01-01-87 COMPLETED BY M. Williasns

- TELEPHONE 316-364-8831

, _ OPERATING STATUS 4

1. Reporting Period: December, 1986 Gross Hours in Reportiry Period: 744

2. Currently Authorized Power Level (PMt): 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

. H is Month Yr to Date Cumulative

5. Ntanber of Hours Reactor was Critical 306_.9 _ 6523.6_ 9313.9

6. Reactor Reserve Shutdown Hours 0.0 92.5 171.3

7. Hours Generator on Line 240.1 6418.5 9190.1

{ 8. Unit Reserve Shutdown Hours 0.0 0.0 0.0

9. Gross hermal Energy Generated (BMH) __650,000 20,870,409 29,745,342

~10. Gross Electrical Energy Generated (MWH) 225,858 7,295,280 10,366,370 j 11. Net. Electrical Energy Generated (PMH) 199 t677 6,957,189 9,899,289

12. Reactor Service Factor 41.3 74.5 80.0

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i 13. Reactor Availability Factor _41.3 75.5 81.5 14.- Unit Service Factor 32.3 73.3 79.0 I 15. Unit Availability Factor 32_.3 73.3 79_.0

16. Unit Capacity Factor (Using MDC) 23.8 70.4 1 75.4

17. Unit Capacity Factor (Using Design PMe) 22.9 67.9 72.7

18. Unit Forced Outaje Rate _8.3 4.6 4.4

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_

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. AVERAGE DAILY UNIT POWER LEVEL

. DOCKET NO. 50-482 WOLF CREEK GENERATING STATIOi IOLF CREEK NUCLEAR OPERATING CORPORATION DATE 01-01-87 00MPLETED BY M. Williams TELEPHONE 316-364-8831 MONIH December, 1986 _

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (IWe-Net) (l@e-Net) 1 0 17 0 2 0 18 0 3 0 19 0 4 0 20 0 5 0 21 83 6 0 22 90 7 0 23 444 8 0 24 793 _

9 0 25 798 10 0 26 990 1137 11- 0 27 12 0 28 1139 13 0 29 1139 14 0 30 1141

'15 0 31 1149 16 0 _

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UNIT SHUIDOWN AND POWER REDUCTIONS .

DOCKErr NO.~ . 50-482 WOLF CRFEK GENERATING STATIW WOLF CREEK NUCLEAR OPERATING 00RPORATIN DA'IE l-01-87 l OOMPLET. ED BY M. Willians REPORP MCNTH December, 1986 TELEPHONE 316-364-8831 1

TYPE METIHODS SHDITING F: EORCED DURATION REASON DOWN THE REACIOR CORRECTIVE ACfIONS/COPMNTS

No Date S

SCHEDULED (HOURS) (1) OR REDUCING IOWER(2) l 11 861201 S 490.0 C 1 Continued r; fueling outage. W e refuelity outage was was extended by a reactor trip due to low-low Stean Generator level in manual control at 0951 on December 20.

W is created 481.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> of scheduled outage and 8.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> of forced outage.

I 12 861221 S 0.6 B 1 Turbine overspeed test i

i 13 861222 F 13.3 A 3 Feed flow transmitter failure StPMARY: te refueling outage was extended by one startup failure and eMed with unit synchronization on December 21.

The unit was taken off to corr 3uct an overspeed test on December 21. On December 22, a failed feed flow transmitter resulted in a trip due to low-low steau generator level. We power ascension restned later that day.

(1) REASON: A: EQUIPMENT FAILURE (EXPLAIN) E: OPERA'IOR TRAINING AND LICENSE EXAMINATION (2) METEOD: 1. MANUAL B: MAINTENANCE OR TEST F: ADMINISTRATIVE 2. MANUAL SCRAM C: REFUELING G: OPERATIONAL ERROR (EXPIAIN) 3. AUIOMATIC SCRAM D: REGUIA'IORY RESTRICTION H: OIEER (EXPLAIN) 4. 01EER (EXPLAIN) i Page 7 of 9 i

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. NOLF CREEK NUCLFAR G}ERATING CORPORATION WLF CREEK GENERATING STATICN ,

i UNIT NO. 1 MONTH December, 1986 SUM 4ARY OF OPERATING EXPERIENCE LiQted below in chronological sequence is a stenary of operating experiences for this month which required loal reduction or resulted in significant non-load related incidents.

DATE TIME EVENT Decenber 1,1986 0000 Unit in Itxle 6, Befueling December 5, 1986 1223 Unit in Mode 5, Cold Shutdown December 11, 1986 1415 Unit in Mode 4, Hot Shutdown December 13, 1986 1023 Unit in Mode 3, Hot Standby December 18, 1986 0444 Unit in Mode 2, Startup.

1437 The reactor is critical.

Decerber 20, 1986 0946 Unit in Mode 1, Power Operation.

0951 Reactor Trip due to 1(>-lo steam generator level (LER 86-068-00). Unit in Itxle 3, Hot Standby.

1509 Unit in Mode 2, Startup.

1610 '1he reactor is critical.

1820 Unit in Mode 1, Power Operation.

Decenber 21, 1986 0958 Synchronized with grid, increased generator output to 125 MW.

1404 Connenced lowering generator output.

1417 Opened generator output breakers.

1435 Conducted turbine overspeed trip test 1456 Synchronized with grid, increased power to 30 percent. Held power at 30 percent until stean generator chemistry in specification.

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'DME' TIME EVENP December 22, 1986 0253 Comnenced raisirs reactor power to 50 percent.

, 0858 Reactor Trip, Turbine Trip due to lo-lo stean generator level (LER 86-069-00). Unit in Mode 3, Hot Standby.

1634 Unit in Mode 2, Startup.

1710 Reactor is critical 1910 Unit in Mode 1, Power Operation.

2217 Synchronized with grid, increased power to 48 percent. Held power at 48 percent to get a reactor core flux map.

' December 23, 1986 1735 Increased power to 74 percent. Held power at 74 percent to get a reactor core flux map.

December 26, 1986 0405 Ccanenced raisirs reactor power to 100 percent.

1630 Achieved 100 percent reactor power.

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CNUCLEAR OPERATING l

CORPORATION January 15, 1987 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 Letter: WM 87-0018 Re: Docket No. 50-482 Subj:

December, 1986 Monthly Operating Report Gentlemen:

Enclosed is the December, 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, Bart D. Withers President and Chief Executive Officer BDW:see Enclosure cc: PO'Connor (2), w/a JCummins, w/a RMartin, w/a P O. Dou 411 ' Buri ngton. KS 66839 : Phone- (316) 364-8831 '\'

An Equai Opporturvey Erntw>yer M F HCN ET

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