ML20134P180

Operating Rept for Wolf Creek Nuclear Operating Corp for Jan 1996-Dec 1996

ML20134P180
Person / Time
Site:	Wolf Creek
Issue date:	12/31/1996
From:	Warren C WOLF CREEK NUCLEAR OPERATING CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
WO-97-0029, WO-97-29, NUDOCS 9702250169
Download: ML20134P180 (9)

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W@) LF NUCLEAR CREEKOPERATING Clay C. Warren Churf Operating Officer February 21, 1997 WO 97-0029 U. S., Nuclear, Regulatory Commission ATTN: Document Control Desk Mail Station P1-137 Washington, D. C. 20555

Subject:

Docket No. 50-482: 1996 Annual Operating Report for Wolf Creek Generating Station Gentlemen:

The attached Annual Operating Report is being submitted pursua:4t to Wolf Creek Generating Station, Unit No. 1, Technical Specifications 6.9.1.4 and 6.9.1.5. This report covers operations for the period of January 1, 1996, I through December 31, 1996. If you have any questions regarding this report, j please contact me at (316) 364-8831, extension 4000, or Mr. Richard D. j Flannigan at extension 4500.

1 Very truly yours, l

l Cl C. Warren CCW/jad Attachment cc J. E. Dyer (NRC), w/a - ,

l D. N. Graves (NRC), w/a - )

W. D. Johnson ' (NRC) , w/a j J. F. Ringwald (NRC), w/a J C. Stone (NRC), w/a ,

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9702250169 961231 PDR ADOCK 05000482 R PDR PO. Box 411/ Burkngton KS 66839 / Phone:(316) 364 8831 An Equal Opportunity Employer M FHC VET l

Attechment to WO 97-0029

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l WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATIOri DOCKET NO: 50-482

- FACILITY OPERATING LICENSE: NPF-42 ANNUAL OPERATING REPORT REPORT NO. 12 Reporting Period: January 1, 1996 through December 31, 1996 1

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4 Attachmtnt to W') 97-0029 Paga 2 of 8 EXACUTIVE StnetARY This Annual Operating Report provides a summary of the operating experience at Wolf Creek Generating Station. This report also provides a summary of the -

major safety-related maintenance activities completed during the year, and covers the period beginning on January 1, 1996, and ending on December 31, 1996.

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.

In 1996, the availability factor for Wolf Creek Generating Station (WCGS) was 80.6 percent with a capacity factor (using maximum dependable capacity) of 80.2 percent. WCGS experienced a Reactor trip due to loss of Circulating Water in January, 1996, and subsequently entered the Refuel VIII outage earlier than scheduled. WCGS returned to power in early April, 1996, decreased load briefly for turbine balancing, and synchronized to the grid on April 20, 1996.

In June, 1996, the unit experienced a reactor trip caused by the failure of a roll pin in a Main Feedwater Control Valve causing the valve to close. This resulted in a " low low" Steam Generator "C" water level, and subsequent Reactor trip In August, 1996, the unit reduced power to repair a' crack in a weld at condenser connection #072. Also in August, 1996, the unit reduced power to replace power supply cards in order to eliminate recurring oil fluctuations and filter alarms on the "A" Main Feedwater Pumps. In October, 1996, power was reduced to repair a damaged wire in the "A" Main Feedwater Pump speed control panel.

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Attachment to WO 97-0029 Page 3 of 8

1.

SUMMARY

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

major safety-related maintenanca activities completed during 1996 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, 1996.

January The unit operated at or near 100% power, Mode 1, from January 1, 1996, until 0337, January 30, 1996. At that tiee, the unit was manually tripped due to an ice accumulation on the ecreens at the circulating Water Intake Structure. At 1531, on January 30, 1996, the unit entered Mode 4, and at 2248, on January 31, 1996, the unit entered Mode 5.

The unit was scheduled for Refuel VIII Outage to begin approximately March 1, 1996. Because of this event, the unit began the outage at 1800 on February 3, 1996.

February The unit remained shutdown the entire month of February, 1996, as activities associated with Refuel VIII continued. The unit began the month in Mode 5, and entered Mode 6 at 0315, February 14, 1996. The unit completed fuel off-load at 0623, February 23, 1996.

March The unit remained in outage conditions throughout the month of March, 1996, as activities associated with Refuel VIII continued. The unit completed reloading fuel on March 16, 1996, in Mode 6. The unit entered Mode 5 at 1343 on March 20, 1996, and entered flode 4 at 0313 on March 29, 1996.

April The unit began the month of April, 1996, in Mode 4. The unit was in the process of start-up following Refuel VIII. The unit entered Mode 3 at 2312, April 2, 1996; Mode 2 at 2315 on April 5, 1996; and Mode 1 at 0550 April 7, 1996. The plant reached Mode 1, 100% power at 0430, April 11, 1996. The unit operated at approximately 100% power until commencing turbine / generator load decrease at 2106, April 19, 1996; at 0950 April 20, 1996, the unit was in Mode 2, approximately 5% power, to balance the turbine. Upon completion of turbine balancing work, the unit commenced increasing power. The unit reentered Mode 1 at 1458, and the generator was synchronized to the grid at 2145, April 20, 1996. The unit reached Mode 1, 100% power, at 0000, April 22, 1996, and remained at that level through the end of April, 1996.

y-1 Attachraent to WO 97-0029

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U*Y l The unit operated at or near 100% power, Mode 1, from May 1, 1996, through May 31, 1996.

June The unit operated at or near 100% power, Mode 1, June 1, 1996, until 1320, June 6, 1996, when the Unit experienced a reactor trip caused by a

" low-low" level in Steam Generator "C". This resulted from the failure of a 3/16" roll pin in the "C" Steam Generator Main Feedwater Regulating Valve (FRV) which allowed the valve plug to separate from the valve stem. After the pin was replaced in the "C" FRV and pins were replaced in two other FRVs, the unit reached criticality at 0435, June 8, 1996, i and the main generator output breakers were closed at 1421, June 8, 199G. The unit remained at or near 100% power, Mode 1, throughout the remainder of June, 1996.

Julv The unit operated at or near 100 % power, Mode 1, from July 1, 1996, through July 31, 1996.

Auuusl The unit operated at or near 100% power, Mode 1, August 1, 1996, through August 19, 1996, when power was reduced to repair a crack in the weld at condenser connection # 0 7'2 . At 0505, August 19, 1996, power was stabilized at 55%. Repatra were completed, and at 1800, August 19, 1996, the unit commenced power ascension. The unit was stabilized at 100% power, Mode 1, at 2258, August 19, 1996.

At 0836, August 20, 1996, the unit commenced power reduction fcr recurring oil fluctuations and filter alarms on the "A" Main Feedwater pumps. At 1128, August 20, 1996, power was stabilized at 55% for troubleshooting on power supply cards. Replacements were completed, and

,the unit commenced increasing power at 2200, August 20, 1996. The unit stabilized at 100% power, Mode 1, at 0220, August 21, 1996. The unit remained at 100% power, Mode 1, for the remainder of August, 1996.

September The unit operated at or near 100% power, Mode 1, September 1, 1996, through September 30, 1996.

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httachment to WO 97-0029 Page 5 of 8 October The unit operated at or near 100% power, Mode 1, October 1, 1996, through 1617 on October 25, 1996. The unit commenced power decrease to repair a damaged wire in the "A" Main Feedwater Pump speed control panel. At 1821, October 25, 1996, power was decreased to approximately 60%. At 2057, October 25, 1996, the unit stabilized at approximately 50% power; repairs were accomplished. At 1207, October 26, 1996, the unit commenced increasing power, and reached 96% at 1522, October 26, 1996. At 1653, October 26, 1996, the unit achieved 100% power, Mode 1, and continued operating at that level through the end of October, 1996.

November The unit operated at or near 100% power, Mode 1, November 1, 1996, through November 30, 1996.

December The unit operated at or near 100% power, Mode 1, December 1, 1996 through December 31, 1996.

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- I Attachment to WO 97-0029

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SUMMARY

OF OUTAGES AND FORCED POWER REDUCTIONS Provided below is a summary of the 1996 outages and forced power reductions of over 20 percent of design power level where the reduction extended for more than four hours:

1. Start Date: January 30, 1996 Comoletion Date: February 3, 1996 Iynglt: Forced Duration: 88.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> Reason: Manual Reactor trip necessitated by an ice accumulation at the Circulating Water Intake Structure.

2. Start Date: February 3, 1996 Comoletion Date: April 7, 1996 Type: Scheduled Duration: 1528.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Eg gqu: Refuel VIII outage

3. Start Date: April 19, 1996 Completion Date: April 22, 1996 Type: Scheduled Duration: 16.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Reason: Power was reduced to 5%, Mode 2, for turbine balancing.

4. Start Date: June 6, 1996 Comoletion Date: June 8, 1996 Iyng: Forced Duration: 49 hours5.671296e-4 days <br />0.0136 hours <br />8.101852e-5 weeks <br />1.86445e-5 months <br /> Reason: Replacement of failed pins in Main Feedwater Regulating valves

5. Start Date: August 19, 1996 Completion Date: August 19, 1996 Type: Forced Duration: 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> Reason: Repair condenser connection #072 (weld) (Power reduction)

6. Start Date: August 20, 1996 ,qgmoletion Date: August 20, 1996 I Type: Forced p_pration: 10.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> I Reason: Replacement of power supply cards (Power reduction)

7. Start Date: October 25, 1996 Completion Date: October 26, 1996 l Type: Forced Duration: 21 hours2.430556e-4 days <br />0.00583 hours <br />3.472222e-5 weeks <br />7.9905e-6 months <br />  !

Reason: Repair a damaged wire on the :A: Main Feed Pump speed I control panel (power reduction)

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Attachment to MO 97 0029 Page 7 of 8

3. EXP,OSURE INFORMATION

a. IU4ER OF PEPS 22EL MD MAN-RS4 BY IORK AND JOB FUCTICN REPORT .1996 WOLF CREEK NUCLEAR OPERATING CORPORATION - WCGS PO POV 411 BURLINGTON, KANSAS 66839 LICENSE: NPF-42 REGULATORY L;IDE 1.16 INFORMATION INTERIM REPORT FOR: 960101 TO 961231 PERSONNEL ( > 100 mrem ) TOTAL MAN. REM WORK AND JOB FUNCTION STATION UTILITY CONTRACT STATION UTILITY CONTRACT REACTOR OPERAT*.ONS AND SURVEILLANCE 0.555 MAINTENANCE AND CONSTRUCTION O O O 0.446 0.000

' OPERATIONS 11 1 0 5.446 0.535 0.007 HEALTH PHYSICS AND LAB 21 0 31 7.414 0.258 7.753 SUPERVISORY AND OFFICE STAFF 4 0 3 2.002 0.000 0.849 ENGINEERING STAFF 3 0 1 1.629 0.238 0.456 ROUTINE PLANT MAINTENANCE 7.119 MAINTENANCE AND CONSTRUCTION 10 0 12 6.227 0.000 OPERATIONS 0 0 0 0.330 0.054 0.010 0 0 0 0.870 0.105 0.024 HEALTH PHYSICS AND LAB 0.004 0.758 SUPERVISORY AND OFFICE STAFF 5 0 0 2.369 ENGINEERING STAFF 0 0 0 0.855 0.174 0.599 INSERVICE INSPECTION 0.000 5.143 MAINTENANCE AND CONSTRUCTION 9 0 13 2.288 0 0 0 0.015 0.000 0.004 OPERATIONS 2.101 HEALTH PHYSICS AND LAB 3 0 7 0.885 0.000 SUPERVISORY AND OFFICE STAFF 2 0 4 0.626 0.000 2.066 ENGINEERING STAFF 1 0 31 0.598 0.096 14.167 SPECIAL PLANT MAI!TIENANCE 33.553 MAINTENANCE AND CONSTRUCTILM 13 0 105 7.362 0.023 OPERATIONS 1 0 0 0.319 0.000 0.000 HEALTH PHYSICS AND LAB 2 0 1 1.039 0.020 0.678 SUPERVISORY AND OFFICE STAFF 6 0 3 2.870 0.000 1.508 ENGINEERING STAFF 1 1 70 0.838 0.144 18.522 WASTE PROCESSING MAINTENANCE AND CONSTRUCTION 0 0 0 0.562 0.000 0.387 OPERATIONS 1 0 1 0.562 0.022 0.328 HEALTH PHYSICS AND LAB 15 0 13 4.972 0.067 4.110 SUPERVISORY AND OFFICE STAFF 0 0 0 0.342 0.000 0.027 ENGINEERING STAFF 0 0 0 0.045 0.000 0.036 REFUELING MAINTENANCE AND CONSTRUCTION 1 0 9 1.211 0.000 3.933 OPERATIONS 1 0 0 0.256 0.007 0.000 HEALTH PHYSICS AND LAB 2 0 1 0.848 0.000 0.324

' 0 3 0.815 0.000 1.394 SUPERVISORY AND OFFICE STAFF 2 ENGINEERING STAFF 3 0 11 1.605 0.022 7.320 TOTALS i MAINTENANCE AND CONSTRUCTION 33 0 139 18.095 0.023 50.689 OPERATIONS 14 1 1 6.928 0.618 0.349

. HEALTH PHYSICS AJE) LAB 43 0 53 16.028 0.450 14.991 SUPERVISORY AND OFFICE STAFF 19 0 13 9.104 0.004 6.601 ENGINEERING STAFF 8 1 113 5.570 0.673 41.101 GRAND TOTALS 117 2 319 55.725 1.769 113.731 4

! Number of personnel > 100 mrem based on PIC data Total man-rem based on ratio of PIC data applied to TLD data j Actual total mrem = 171138 (numbers may vary due to rounding)

.O Attachmsnt to WO 97-0029

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4. SINGLE RELIASE OF RADIOACTIVITY OR RADIATION EXPOSURE GREATER THAN 10 PERCENT OF ALLONABLE ANNUAL VALUES During 1996, no single release of radioactivity exceeded 10 percent of the allowable annual value.

5. CHALLENGES TO THE PORVS AND SAFETY VALVES During 1996, there were no challenges to the Reactor Cc,olant System PORVs or the Reactor Coolant System Safety Valves.

6. INDICATIONS OF FAILED FUEL The Westinghouse computer modeling program indicated the presence of six fuel defects prior to Refuel VIII. There were no indications of failed fuel after Refuel VIII.

7. REACTOR COOLANT SYSTEM SPECIFIC ACTIVITY IN EXCESS OF TECHNICAL SPECIFICATION 3.4.8 LIMITATION The Reactor Coolant System Specific Activity did not exceed the Technical Specification 3.4.8 limitation of 100/E-bar during 1996.

However, Technical Specification 4.4.8 limitation of 1 microcurie per gram Dose Equivalent I-131 was exceeded when the reactor was tripped January 30, 1996. The peak value was 2.162 uCi/ml DEI at 0539 on Jar.uary 3 0, 1996. Technical Specification 4.4.8 was exited at 1735 on January 30, 1996, when coolant activity returned to less than 1 uCi/ml DEI.

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