ML20080L882

Annual Operating Rept,Rept 10, for Reporting Period of 940101-1231

ML20080L882
Person / Time
Site:	Wolf Creek
Issue date:	12/31/1994
From:	Maynard O WOLF CREEK NUCLEAR OPERATING CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
WO-95-0032, WO-95-32, NUDOCS 9503030030
Download: ML20080L882 (9)

Text

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NUCLEAR OPERATING CORPORATION Otto L Maynard Vice President Plar.t Operations February 28, 1995 i

WO 95-0032 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1-137 Washington, D.

C.

20555

Subject:

Docket No. 50-482:

1994 Annual Operating Report for Wolf Creek Generating Station Gentlemen:

The attached Annual Operating Report is being submitted pursuant to Wolf Creek Generating Station, Unit No.

1, Tcchnical Specifications 6.9.1.4 and 6.9.1.5.

This report covers operations for the period of January 1, 1994,.

through December 31, 1994.

very truly yours, 1

Otto L.

aynard OLM/jad Attachment cc:

L. J. Callan - (NRC), w/a D. D. Chamberlain (NRC), w/a D. N. Graves (NRC), w/a J.

F. Ringwald (NRC), w/a J.

C. Stone (NRC), w/a W

(, n p' c.n n

/p r

U v t, J

9503030030 941231 O. B x 411/ Burlington, KS 66839 / Phone: (316) 364-8831 l

PDR ADOCK 05000492 An Eqst Opportunity Emploser M/F/HC/VE1 k

R PDR I

' Attcchment to CO 95-0032 Page-1 of B

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WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION DOCKET NO:

50-482 FACILITY OPERATING LICENSE:

NPF-42 ANNUAL OPERATING REPORT REPORT NO. 10 neporting Period: January 1, 1994 through December 31, 1994

Attcchm:nt to WO 95-0032 Page 2 of 8 l

EXECUTIVE

SUMMARY

This Annual Operating Report provides a summary of the operating experience at l

Wolf Creek Generating Station.

This Annual Operating Report also provides a j

summary of the major safety-related maintenance activities completed during the year.

This report covers the period beginning on January 1, 1994, and ending on December 31, 1994.

This Annual Operating Report is submitted in accordance with the requirements of Technical Specification 6.9.1.4 and contains the information required by Technical Specification 6.9.1.5.

The format of this report is similar to that provided in Regulatory Position C.1.b of Regulatory Guide 1,16, Revision 4,

August, 1975.

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In 1994, Wolf Creek Generating Station's availability factor was 85.6 percent I

with a capacity factor (using maximum dependable capacity) of 84.7 percent.

l Wolf Creek Generating Station experienced brief periods of manually initiated l

power reduction in January.

The unit completed its seventh refueling outage in November, 1994.

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• ' Attachment 1to WO 95-00321

'Page.3 of 8' 1.

_SDRAEARY OF OPERATING EXPERIENCE' A. summary of Wolf. Creek Generating Station's operating experience and

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major: safety-related maintenance activities completed during 1994 is provided by month below. This information has been previously submitted in accordance with the requirements of' Technical-Specification 6.9.1.8 in the' Monthly Operating Reports for' January through. December, 1994.

T Januarv j

The unit operated near 100% power until January 14, 1994, at 1945 l

hours, when the unit commenced power reduction to repair a containment cavity cooling fan.

At 2334, the unit was at.50% power.

January 15, 1994,-at 1049 hours0.0121 days <br />0.291 hours <br />0.00173 weeks <br />3.991445e-4 months <br />, the unit entered Mode 2,

startup, and at 1251 hours0.0145 days <br />0.348 hours <br />0.00207 weeks <br />4.760055e-4 months <br />, the unit entered Mode 3, hot' standby.

On' January 17, 1994, at ' 1007 hours0.0117 days <br />0.28 hours <br />0.00167 weeks <br />3.831635e-4 months <br />, the unit entered Mode 2,

startup, and entered Mode 1, power operation, at 1617 hours0.0187 days <br />0.449 hours <br />0.00267 weeks <br />6.152685e-4 months <br />. January 18, 1994, at i

2336 hours0.027 days <br />0.649 hours <br />0.00386 weeks <br />8.88848e-4 months <br />,.the unit operated at near 100% power, January 26, 1994, at 1633 hours0.0189 days <br />0.454 hours <br />0.0027 weeks <br />6.213565e-4 months <br />, the unit commenced power reduction due to

a. Rod

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Control Urgent Failure Alarm; at 30% power the reactor'was manually i

tripped, and the unit entered Mode 3, hot standby.

At 0244 hours0.00282 days <br />0.0678 hours <br />4.034392e-4 weeks <br />9.2842e-5 months <br /> on January 27, 1994, a Notification of Unusual Event (NUE) was declared, l

based on the inability. to meet Technical Specification 3.1.3.1, Action 4.

The NUE was-terminated'at 0423 hours0.0049 days <br />0.118 hours <br />6.994048e-4 weeks <br />1.609515e-4 months <br />.

Rod Control' repair ~

-l was performed, but.while returning the unit to service a subsequent Rod Control Urgent Failure Alarm. was received, and on - January. : 8, 1994, at 1733, the unit was manually tripped from Mode 2 for replacement of a thyristor in the rod control system.

The unit.

l entered' Mode 1,

power operation, on January 29, 1994, at 1321.

On_

January 30, 1994, the unit operated at approximately 100% power.

February The unit operated at or near 97% power for most of the month of February.

Full power could not be attained due to' main turbine, nozzle restriction.

l On February 18, power was reduced to approximately 92% power for a

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period of 19 hours2.199074e-4 days <br />0.00528 hours <br />3.141534e-5 weeks <br />7.2295e-6 months <br /> to accommodate main turbine valve testing.

The number 1 Control valve did not initially. full close, extending the time required for performance of the test.

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March The unit operated at or near 97% power for the first nine days of the month of March.

Full power could not'be attained due to main. turbine nozzle restriction. On March 9, 1994, unit rerate increased power to l

l approximately 100% power.

The unit remained at or near full power l

for the remair. der of the month.

April i

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The unit ' operated at or near. 100% power throughout the month of April.

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~ Attcchment to WO 95-0032 l

Page 4 of 8 l

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May The unit operated at or near 100% power until May 21, 1994, at 1025 hours0.0119 days <br />0.285 hours <br />0.00169 weeks <br />3.900125e-4 months <br />, when power was reduced to 90% for condenser tube cleaning.

The unit was returned to 100% power on May 23, 1994, at 1300, and continued to operate at or near 100% power for the remainder of the month of May.

J1me r-The unit operated at or near 100% power the entire month of June.

Julv j

The unit operated at approximately 96% power from July 1 through July 17 due to main condenser tube fouling. On July 17, when a switchyard breaker opened, power was reduced to 80%.

The breaker was reclosed after 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and power was restored to approximately 96%, where it remained until July 19.

Condenser tube cleaning on July 19 and July 20 allowed the unit to return to full power for the remainder of the month of July.

August The unit operated at approximately 100% power from August 1 through August 26.

On August 26, at 0341, power was reduced to approximately 93% for main turbine valve testing.

Power remained at approximately 93% for the remainder of August to minimize xenon transients, and to begin coastdown for the upcoming refueling cutage.

Sentember The unit was operating at 93% power on September 1,

1994, when it entered the end of core-life coastdown.

On September 14, 1994, at 0001, the generator output breakers were opened, and the unit began the seventh refueling outage.

October The unit was shut down for refueling during October.

By midnight of October 31, 1994, the unit had been heated up to full temperature, and low-power physics testing had been completed with the plant in Mode 2, startup.

Following is a list of major safety-related corrective maintenance performed during the seventh refueling outage:

Replaced the seal injection throttle valves Replaced Reactor Coolant Pump "A"

seals Performed eddy current testing (100%) on Steam Generators "B" and

• C" Replaced inconel 600 plugs with inconel 690 plugs on Steam Generators "B" and

• C" Completed sludge lancing and pressure pulse cleaning of all four steam generators 1

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IAf.thchment'to NO'95s0072

1. • iPage 5 of 8 Performed inspection of feedwater nozzles on Steam Generators."B" and zj "C"

Changed out safety valves on Pressurizer Modified conoseals on Reactor head Performed inspection on underside of Reactor head for cracking around

'i Control Rod Drive Mechanism penetration welds

. Changed. inlet and. outlet isolation valves, and eliminated isolation by-pass loop on containment coolers Overhauled diesel' generators, including modification to:the exhaust system; and elimination of the fuel injector cooling system Replaced environmentally qualified parts on shaft seals.of Residual' j

Heat Removal Pump."B" l

Replaced rotating. assembly of Centrifugal Charging Pump."B"'

l Performed fiber optic search and. retrieval (FOSAR)'of Reactor vessel i

Completed the in-plant portion of Generic Letter 89-10 requirements.

l for motor operated valves 4

Modified steam generator supports and snubbers r

November The unit.was restarted following the completion of 'the' seventh.

refueling ~ outage.

On November 1,

1994, at 0118, the unit entered

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' Mode 1,

Power Operation.

Completed Turbine! Generator Torsional l

Restraint Testing; results indicated no problems.

On November 2,

1994, at 1231, the generator was synchronized to the ' grid.

.On i

November 2, 1994, at 1610, the plant held power at approximately;30%

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power for steam generator secondary side. chemistry control.

On.

November 3,

1994, at 0400, the unit commenced raising power.

On.

November 6, 1994, at 1426, the unit achieved 100% power, and remained at that level for the remainder of November.

December The unit operated at or near 100% for'the month of December, 1994.

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SUNNARY OF OUTAGES AND FORCED POWER REDUCTIONS I

Provided below is a summary of the 1994 outages and. forced power

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reductions of over 20 percent of design power level where the reduction i

extended for more than four hours:

1., Start Date: January 14, 1994 completion Date: January 17, 1994 Tysta: Scheduled Duration: 68 hours7.87037e-4 days <br />0.0189 hours <br />1.124339e-4 weeks <br />2.5874e-5 months <br />

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Reason: Repair of Centainment Cavity Cooling Fan 1

2. Start Date: January 26, 1994 Completion Date: January 29, 1994 5

Tysnt Forced Duration:

68.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />

-i Reason: Rod Control Urgent Failure Alarm v,,.

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A$techment to WO 95-0032 Page 6 of 8

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3. Start Date: September 16, 1994 comnietion Date November 2, 1994 Type Scheduled Duration:

1141.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> Reason: Manual shutdown on September 16, 1994, for seventh refueling outage.

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'j Attachment to WO 95-0032-Page 7 of 8, ij 1

3.

EXPOSURE INFORMATION I

a. NLPSER OF PERSONEL AND MW-REM BY ICRK AND JOB PINCI'ICN REPCRT - 1994 i

PERSONNEL ( > 100 mrem )

TOTAL MAN-REM WORK AND JOB FUNCTION STATION UTILITY CONTRACT STATION UTILITY CONTRACT ~

REACTOR OPERATIONS AND SURVEILLANCE MAINTENANCE AND CONSTRUCTION 4

0 4

1.423 0.000 1.815 l

OPERATIONS 13 2

3 4.332 0.679 0.372 HEALTH PHYSICS AND LAB 18 1

36 6.201 0.207 10.575 l

SUPERVISORY AND OFFICE STAFF 14 0

6 4.156 0.001-

,2.247-ENGINEERING STAFF 6

1 2.796 0.407 0.528 ROUTINE PLANT MAI7TENANCE MAINTENANCE AND CONSTRUCTION 15 0

29 5 ' 9.

0.009 13.129 OPERATIONS 1

0 0

0..

^ s 0.014-0.018.

HEALTH PHYSICS AND LAB 1

0 1

0. 6. t 0.005 0.153 SUPERVISORY AND OFFICE STAFF 5

0 0 ~

0.495 0.055 0.211'

-i 1.546 0.060 0.688 ENGINEERING STAFF 1

0 0

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INSERVICE INSPECTION MAINTENANCE AND CONSTRUCTION 15 0

32 5.422

'O.000 11.641 OPERATIONS 0

0 0

0.115 ~

0.000 0.147 HEALTH PHYSICS AND LAB E

O 12 1.555-0.000 3.319 i

SUPERVISORY AND OFFICE STAFF 3

0 4

1.419 0.000 1.874 I

ENGINEERING STAFF 7

1 55 3.043 0.404 31.114 l

SPECIAL PLANT MAINTENANCE l

MAINTENANCE AND CONSTRUCTION 15 0

119 7.448 0.000 51.816.

OPERATIONS 0

0 0

0.127 0.000.

0.005 i

HEALTH PHYSICS AND LAB 10 0

3 3.104 0.052 1.275 SUPERVISORY AND OFFICE STAFF 2

0 5

2.119 0.000 2.554 ENGINEERING STAFF 3

0 46' 1.220 0.234 14.155 r

WASTE PROCESSING i

MAINTENANCE AND CONSTRUCTION O

O-0 0.733 0.000 0.501' OPERATIONS 1

0 0

0.326 0.005 0.064 HEALTH PHYSICS AND LAB 12 0

15 4.335 0.009 5.515 SUPERVISORY AND OFFICE STAFF 0

0 0

0.420 0.000 0.000 ENGINEERING STAFF 0

0 0

0.002 0.009 0.000 REFUELING l

MAINTENANCE AND CONSTRUCTION O

O 2

0.629 0.000 1.490 1

OPERATIONS 2

0 0

0.737 0.009 0.000 HEALTH PHYSICS AND LAB 3

0 1

0.666 0.000 0.773 l

SUPERVISORY AND OFFICE STAFF 3

0 2

1.309 0.000 0.624 ENGINEERING STAFF 2

0 47 0.749 0.005 13.253

.i TOTALS

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MAINTENANCE AND CONSTRUCTION 49 0

186 21.404 0.009 80.393 OPER?.TIGMS 17 2

3 5.901 0.707 0.606 HEALTH PHYSICS AND LAB 49 1

68 16.537 0.273 21.610 i

SUPERVISO:1Y AND OFFICE STASF 27 0

17 10.967 0.061 7.988 ENGINEERING STAFF 19 2

149 8.305 1.114 59.261 GRAND TOTALS 161 5

423 63.114 2.164 169.857 hNumberofpersonnel>100mrembasedonPICdata Total man-rem based on ratio of PIC data applied to TLD data Actual total mrem = 235088 (numbers may vary due to rounding) i-e-

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SINGLE RELEASE OF RADIOACTIVITY OR RADIATION EXPOSURE GREATER THAN 10 PERCENT OF ALLONABLE ANNUAL VALUES During 1994, no single release of radioactivity exceeded 10 percent of the allowable annual value.

During 1994, there was no single radiation exposure specifically f

associated with an outage which accounted for more than 10 percent of the allowable annual values.

5.

CHALLENGES TO THE PORVS AND SAFETY VALVES During 1994, there were no challenges to the Pressurizer Power Operated Relief Valves (PORVs) or Safety Valves.

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INDICATIONS OF FAILED FUEL-During the seventh refueling outage in the fall of 1994, ultrasonic inspection of the entire core positively identified two failed rods in one assembly (H33), which was scheduled for discharge.

The failed rods were visually inspected in-situ.

The collective information of assembly location, rod locations, rod conditions, and manufacturing traceability evaluation support a conclusion that the failure' root.cause is identical to that observed in the previous two cycles (i.e., grid-to-rod fretting at the bottom grid caused by fluid elastic instability of the fuel rods).

Following startup of the reactor in November, 1994, and through the end of the year, reactor coolant fission product activity indicated no failed fuel.

7.

REACTOR COOLANT SYSTEN SPECIFIC ACTIVITY IN EXCESS OF TECHNICAL SPECIFICATION 3.4.8 LINITATION The Reactor Coolant System Specific Activity did not exceed the Technical Specification 3.4.8 limitation during, 1994.

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