Text

1991 Annual Operating Rept for Wolf Creek Nuclear Generating Station
	ML20090B654
Person / Time
Site:	Wolf Creek
Issue date:	12/31/1991
From:	Bailey J, Maynard O; WOLF CREEK NUCLEAR OPERATING CORP.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	NO-92-0068, NO-92-68, NUDOCS 9203040017
	Download: ML20090B654 (13)
	v • d • e

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o LF CREEK W@ NUCLEAR OPERATING C John A Bauey

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february 26, 1992 NO 92-0068 U. S. Nuclear Regulatory Commission ATTH: Document Control Desk liail Station F1-137 Washington, D. C. 20555 Subjects Docket No. 50-482: 1991 Annual Operating Report for Wolf Creek Nuclear Generating Station Gentlemen The attached Annual Operating Report is being submitted pursuant to Wolf Creek Generating Station Unit No. 1, Technical Specifications 6.9.1.4 and 6.9.1.5. Alto included in this report is information required by 10 CFR 20.407. This report covers operations for the period of January 1, 1991 to December 51, 1991 Very truly yours, 8 .

John A. Bailey I Vice President Operations JAB /jra Attachment cci A. T. Howell (NRC), w/a R. D. Hartin (NRC), w/a G. A. Pick (NRC). v/a W. D. Reckley (NRC), w/a OCO M a ao4 4'i ' nori>"9'oa. xs c< 839 < enome- (aisi ac4 883i 38R3 iB8M 3!$881ea PDR An Iavai cvsoturuty Emraoyer M r +tcNET "7 7 N

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Attachmsnt to NO 92 0068 *

.Page 1 of 12 i WOLF CREEK NUCLEAR OPERATIllG CORPORATION WOLF CREEK GENERATING STATION ,

r DOCKET NO: 50 482 FACILITY OPERATING LICENSE HPF-42 ANNUAL OPERATING REPORT REPORT NO. 7 Reporting Pet ads January 01, 1991 through D cember 31, 1991 Prepared by: S. G. Videman

, yy Approved by: // /// f/(.v/

0. L. Maynard /

Director Plant Operations

i Attachment to 140 92 0068 !

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EXECUTIVE $UMMARY r

The purpose of the Annual Operating Report is to provide a comprehensive I summary of the operating experience at Wolf creek Generating Station. The Annual Operating Report also provides a summary of the major safety related ,

maintenance activities completed during the year. This report covers the i period beginning on January 1. 1991 and ending on December 31, 1991. a t

The 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 i that provided in Regulatory Position C.I.b of Regulatory Guide 1.16 Revision 4. August. 1975.

Also included in this report is the information on personnel monitoring as required by 10 CFR 20.407.

In 1991. Wolf Creek Generating Station's availability factor was 71.8 percent and capacity factor (using maximum dependable capacity) was $8.9 percent.

Volf Creek Generating Station experienced no Reactor tripe in 1991 and started the fifth refueling outage after completing a record 487 days of continuous on-line operation on September 20. 1991.

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Attachment to NO 92 0068

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1.

SUMMARY

OF OPERATING EXPERIENCE -

A summary of Wolf Creek Generating Station's operating ex9erience and major safety-related maintenance activities completed daring 1991 is provided by month below. This information has been previou11y submitted in accordance with the requirements of Technical Specification 6.9.1.8 f in the Monthly Operating Reports for January through December. 1991. l January The unit operated at or near 100% power throughout the first ten days of January, 1991. On January 11 the unit commenced power reduction at 2252 hours0.0261 days 0.626 hours 0.00372 weeks 8.56886e-4 months to 902 power for fuel conservation purposes. Power remained at or near 902 for the remainder of the month. i No major safety-related me "'enance activities were performed during d

the month of January. P February i

The unit began the month at 902 power with power being further reduced to 80% on February 5 for tvel conservation purposes. Power remained at 802 for the remainder o' February uith the exception of a

-sixteen hour period beginning late February 14, when power wac i reduced to 752 as a result of a main generator stator cooling instrumentation problem. The instrumentation problem was corrected 1 and the unit returned to 802 power on February 15, 1991.

j Major safety-related maintenance activities for February:

l a. Replacement of hydraulic pump on Main Steam Isolation Valve ABHV11. ,

b. Rep.lacement of compressor heads on Control Room Air Conditioning ,

Unit SGK04A in support of Plant Modification Request (PMR) 2062.

March The unit operated continuously in March at 802 power for fuel conservation purposes with the exception of a reduction to 60! power ;

on March 20-for the replacement of the 'B' main feedwater pump ,

inboard bearing. Power was returned to 80% on March 22 and remained at 80Z for the remainder of the month.

Major safety-related maintenance activities for March

a. Repair of speed- sensing circuitry on 'A' emergency diesel

-generator. -

b. Ongoing-repair of Fuel Pool Coeling Pump Room Cooler SGG04A.

, c. -Replacement- of compressor heads on Control Room Air Conditioning Unit SGK05A in support of FMR 2061.

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Attochment to NO 92 0068

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April ,

1 The udit began the month at 802 power with power being reduced to 601 on April 6, and to $0! on April 13. for fuel conservation purposes. !

! Power was further reduced to 46% on April 1$ to allow the repair of I Hain Turbine Control Valve AC FCV047. Following repair of the valve. i power was restored to 60! on April 16 and remained at or near t hi.s l 1evel for the remainder of the month.

Major safety related maintenance activities for April ,

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a. Replacement of the mechanical overspeed trip mechanism on Turbine Driven Auxiliary Feedwater Pump PALO2. ;

May The unit began the month at 60! power for fuel conservation i purposes. Power remained at or near 602 for the remainder of the !

month with the exception of one Technical Specification required "

power reduction and two System Operations requested increases to full power. i A Notification of Unusual Event (NUE) van declared and a plant shutdown commenced May 12 at 2115 hours0.0245 days 0.588 hours 0.0035 weeks 8.047575e-4 months as a result of the failure of a 15V power supply in Engineered Safety Features Actuation System Cabinet SA036D. The power supply was replaced and the NUE was terminated before a total plant shutdown was achieved. Reactor power was reduced to a low of $0! during this event. (This event was reported as Licensee Event Report 482/91-006 00).

Power was increased from 60% to 1002 on May 13 at the request of ;

System Operations to meet grid demand. The unit remained at 1002 until May 17 when a power reduction to 60% was commenced for fuel conservation. Power was again increased to 100! on May 30 at the request of System Operations and remained at this level for the ,

remainder of the month. l Major safety-related maintenance activities for May:

a. Replacement of Instrument and Service Air Compressor CKA01A in ;

support of PMR 2495.

b. Ongoing replacement of Balance of Plant and Nuclear Steam Supply ,

System computers in support of PMR 1479.

June The operating experience for Wolf Creek Generating Station in June was highlighted by surpassing 400 days of continuous operation at i 0025 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months on June 25. The unit operated at or near 1002 for the entire month of June. This was the first full month of operation at i 1002 power since-fuel conservation efforts began.

Attochment to NO 92-0068 page 3 of 12 No major safety-related maintenance activities were performed during the month of June.

July The unit operated at or near 1002 power throughout the month of July 1991.- At month's end, the unit had operated continuously for 436 days.

n No major safety-related maintenance activities were performed during the month of July.

August The unit operated at or near 2002 power through August 17 power began ramping down as the coastdown to the fifth refueling outage was commenced at 1700 hours0.0197 days 0.472 hours 0.00281 weeks 6.4685e-4 months on August 18. At months end, power had been reduced to 892 and the unit had operated continuously for 467 days.

No major safety-related maintenance activities were performed during the month of August.

September The unit began the month at 892 power and continued coastdown to the fifth refueling outage. The power decrease continued until a 72 per hour power decrease was initiated at 1400 hours0.0162 days 0.389 hours 0.00231 weeks 5.327e-4 months on September 19 to remove the unit from service for refueling. The main generator output breakers were opened at 0125- hours on September 20 to officially commence the fifth refueling outage. -The unit had operated continuously for 487 days.

Major safety-related maintenance activities for September:

a. Commenced Reactor Coolant System resistance temperature detector bypass manifold removal. ;

b. Commenced maintenance activities on 'A' emergency diesel generator,

c. Commenced replacement of "B* reactor coolant pump motor. .

d. Commenced modification of containment penetrations P36 and P68,

e. Commenced reactor vessel head disassembly in preparation for lifting, betober The unit remained shutdown the er.cire month as activities associated with the fifth refueling outage continued. The unit began the month in Mode 5, Cold Shutdown, entered Mode 6, Refueling,- on October 3, and' continued in Mode 6 until October 13 when all fuel was removed from the core. The unit then re-entered Mode 6 on October 30 when fuel' loading for Cycle 6 commenced, i

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i Attacknent to NO 92 0068

. Page 6 of 12 j Hajor safety related maintenance activities for October: l

a. Replaced 'B' reactor coolant pump motor.

b. Performed maintenance on 'A' and 'B' emergency diesel generators,

c. Completed Reactor Coolant System resistance temperature detector bypass manifold removal modification. ;

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d. Performed maintenance on 4160 Volt Bus NB01. i

e. Performed maintenance on 'A' and 'B' trains Emergency Core !

Cooling System. y

f. . Installed permanent reactor-cavity seal. >

g. Performeo eddy current testing on 'A' and 'C' steam generators. ,

November i The unit . remained shutdown for the- entire month for refueling l activities with November 30 representing day 72 of the continuing l refueling outage. The unit began the month in Mode 6 as fuel loading centinued in preparation for Cycle 6. Fuel loading and stud .

tensioning were completed November 14 and the unit entered Mode $

with the unit remaining in this mode for the remainder of the month.

Major safety.related maintenance activities for November: '

a. Completed maintenance on 'B' emergency diesel generator. "B' train Essential Service Water System, and. 'B' train Emergency ,

Core Cooling System. .

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b. Completed repair of 'B' residual heat removal pump motor.

including rotor balancing.

c. Completed fuel loading and reassembly of reactor vessel head and internals,

d. Completed procedure STS KJ.001A and B. integrated safeguards tests.

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e. Completed sludge lancing on all steam generators.

f, Completed filling and venting of React- Coolant System,

g. Continued inspection, testing, and evaluation of motor operated valves. . _ _ . _

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Attachment to NO 92 0068 [

. Tage 7 of 12 l t

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December P

The unit remained shutdown the entire month for refueling activities with December 31 representing day 103 of the continuing refueling outage. The unit remained in Mode 5 for the entire month. Unit l restart was delayed pending resolution of metor operated valve ;

testing issues, i

Major safety-related maintenance activities for Derumbers

a. Ongoing inspection, testing, evaluation, and resolution of motor ,

operated valves.

2.

SUMMARY

OF 0UTAGES AND FORCED POWER REDUCT10NS Provided below in a summary of the 1991 outages and forced power reductions of over 20 percent of design power level where the reduction- extended for more than four hours. References to reports ,

of reportable _ occurrences _directly related to each outage or load '

reduction are included in parenthesis where applicable.

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1. Start Date: 04/06/91 Completion Date: 05/13/91 Type Scheduled Duration: 912.0 hours0 days 0 hours 0 weeks 0 months Reason: Redeced power for fuel conservation purposes. Further ;

reduced power to 50! for $3.2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months on April 13. On April 35, reduced to 462 for 28.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months to repair main turbine control valve. Upon completion _of valve repair, t returned to 602 power. Operated at 501 for .3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months as a result of commencing a unit shutdown for declaration of a Notice of Unusual Event.

2. Start Date: 05/18/91 Completion Date: 05/31/91 Type Scheduled Duration: 278.7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months Reason: Reduced power to 60Z for fuel conservation purposes.

3. Start Date: 09/20/91 Completion Date: 12/31/91 Typei Scheduled Duration: 2470.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Reason: Manual shutdown on September 20 for fifth refueling outage.

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Attachm nt to NO 9?*0068 Pegoe8 of 12 l

3. EXPOSURE INFORMATION l

a. NUMBER OF PERSONNEL AND MAN.RDi BY WORK AND JOB FUNCTION REPORT .1991 -

2 NUMBER 01 PERSONNEL (>100 HREH)1 TOTAL MAN.REH WORK & JOB FUNCTION STATION UTILITY CONTRACT STATION UTILITY CONTRACT Reactor Operations & Serveillance Haintenance & Construction 2 0 3 1.071 0.000 1.758 !

Operations 16 0 3 0.112 0.286 0.922 l Health Physics & Lab 17 1 26 5.925 0.363 9.197 Supervisory & Office Staff 8 0 2 2.923 0.051 1.389. i Engineering Stcff 4 0 0 2.245 0.174 0.303 j Routine Plant Maintenance Maintenance & Construction 18 0 9 6.518 0.032 6.445 Operations 0 0 0 0.307 0.006 0.005 Health Physics & Lab 0 0 0 0.478 0.042 0.334 Supervisory & Office Staff 2 0 2 1.145 0.000 0.960 Engineering Staff 1 0 0 0.594- 0.018 0.074 Inservice inspection Maintenance & Construction 8 0 14 1.928 0.005 5.313 Operations 0 1 1 0.107 0.260 0.288 Health Physics & Lab 2 0 14 0.497 0.000- 3.631 Supervisory & Office Staff' 4 0 $ 0.738 0.000 1.666 Engineering Staff 0 0 46 0.529 0.000 20.838 Special Plant Maintenance Maintenance & Construction 45 1 223 13.715 0.906 90.571-Operations . 1 0 1 0.301 -0.037 0.228 Health Physics & Lab 7 0 16 3.556 0.018 6.597 Supervisory & Office Staff 10 0 9 2.740 0.000 4.637 Engineering Staff 5 1 121 3.484 0.283 49.128 Vaste Processing Maintenance & Construction 2 0 0 1.011 0.000 0.292 Operations 0 0 0 0.389 0.018 0.125 Health Physics & Lab 14 0 26 4.546 0.018 7.862 Supervisory & Office Staff 2 0 0 0.580 0,000 0.046 Engineering Staff 0 0 0 0.037 0.000 0.023 L

-Refueling Haintenance & Construction 28 0 56 7.349 0.000 14.665 Operations 7 1 1 2.016 0.292 0.195 Health Physics & Lab 0 0 6 0.046 0.033 1.909 Supervisory & Office Staff 4 0 2 1.364 0.000 0.840 Engineering Staff 4 0 2 1.331 -0.121- 0.859 Totals -

Maintenance & Construction. 103 1 305 31.591 0.943 119.043 Operations 24 2 6 9.232 0.900 1.763

-Health Physics & Lab 40 1 88 15.048- 0.475 29.550 Supervisory & Office Staff 30 0 20 9.490 0.051 9.539 Engineering Staff 14 1 169 8.219 0.595 71.225 Grand Totals 211 5 588 73.581 2.964 231.119 I

Number of personnel > 100 mrem based on PIC data 2 Total man. rem based on ratio of PIC data applied to TLD data

Attachment to NO 92 0068

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b. PERSONNEL MONITORINO REPORT

1. In 1971. 1797 individuals were provided personnel monitoring devices. Thic information is provided in accordance with 10 CFR 20.407(a)(2). This total includes the number of individuals required to be reported under 10 CFR 20.407(a)(1).

2. Below is a statistical summary report of the personnel monitoring information recorded for individuals for whom personnel monitoring was provided in 1991 in accordance with the requirements of 10 CFR 20.407(b).

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Estimated whole body exposure range . Number of individuals (rems) . in each range l No measurable exposure.................................................. 788 Hessurable exposure less than 0.1....................................... 327 l 0.1 to 0.25............................................................. 226 i.

0.25 to 0.5................................ ............................ 235 0.5 to 0.75............................................................. 133 0.75to1.0..............................................................46 1.0 to 2.0............................................................... 42 2.0 to 3.0................................................................ 0 3.0 to 4.0................................................................ 0 4.0 to 5.0......................... ...................................... 0 5.0 to 6.0...........................................................-..... 0 6.0 to 7.0................................................................ 0 7.0 to 8.0...................................................... ......... 0

[ ,

8.0 to 9.0................................................................. 0 9.0 to 10.0....................................................... ...... 0 10.0 to 11.0.............................................................. 0 11.0 to 12.0..................................................... ........ 0 i

12.0+. .................................................................. 0 i

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Attachment to NO 92-0068

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4. SINGLE RELEASE OF RADIDACTIVITY OR RADIATION EXPOSURE GREATER THAN 10 PERCENT OF ALLOWABLE ANNUAL VALUES i During 1991, there were no single releases of radioactivity or single radiation exposures greater than ten percent of allowable annual values.

$. CHALLENGES TO THE PORVS AND SAFETY VALVES During 1991, there were no challenges to the Pressuriter power operated relief valves (PORVs) or safety valves.

6. INDICATI0HB 0F FAILED FUEL During the fifth refueling-outage, all 193 fuel assemblies that were loaded during Cycle 5 were removed and were visually and ultrasonically inspected. Of the 193 assemblies inspected, three l t

were determined to have defective fuel pins with-one of.the assemblies having a fuel pin that was broken. It was determined l that all the fuel pellets were accounted for. The core design for Cycle 6 was completed without use of the three. defective assemblies or any others from the same manufacturing lot. (This i condition was reported as Licensee Event Report 482/91-019-00).

7. -REACTOR COOLANT SYSTEM SPECIFIC ACTIVITY IN EXCESS OF TECHNICAL l SPECIFICATION 3.4.8 LIMITATION On September 20 1991, it was determined through analysis that the specific activity of the Reactor Coolant System (RCS) had exceeded the Technical Specification (T/S) 3.4.8.a limit of 1 microcurie per ml Dose Equivalent 1-131 (DEI). The analysis results of the sample taken at 0218 CDT, indicated 3.04 microcuries per ml DEI. The peak DEI of 6.39 uCi/ml was reached on 9/20/91 at 0607 CDT. Maximum cleanup flew through the CVCS mixed bed demineralizer was maintained during this entire period i of time. By 9/21/91 at 0439 CDT. the DEI was back within the limits of T/S 3.4.8.a.

The following information is provided in accordance with T/S 6.9.1.5.cs ,

a. Reactor power history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded From 9/10/91 at 0218 CDT to 0218 CDT 9/20/91, Reactor power was approximately 80 percent.

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Attochment to NO 92 0006

. , Page 11 of 12 9

t Results of the isotopic analyses for radiciodines b.

SAMPLE I-131 1-132 1-133 1-134 1-135 DEI DATE & TIME UCI/ML UC1/ML UCI/ML UCI/ML UC1/ML UC1/ML 9/19/91 22:04 8.56E-02 0.11 0.12 4.79E-02 8.61E-02 0.13 9/20/91 02:18 2.34 1.35 2.06 0.19 1.07 3.04 9/20/91 04:05 3.85 1.609 3.26 0.11 1.57 4.92 9/20/91 06:07 5.10 1.55 4.04 3.25E-02 1.62 6.39 9/20/91 08:13 5.14- 1.29 3.87 0.00 1.38 6.35 9/20/91--10:30 4.02 0.87 2.86 0.00 0.88 4.90 9/20/91 12:30- 3.40 0.74 2.24 0.00 0.60 4.09

-9/20/91 14:15 2.72 0.62 1,74 0.00 0.39 3.25 9/20/91 16:30 2.33 0.58 1.36 0.00 0.28 2.74 9/20/91 18:40 1.86 0.49 1.04 0.00 0.20 2.18 9/20/91 20:53 1.53 0.46 0.79 0.00 0.13: 1.77 9/20/91 22:43 1.35 0.45 0.66 0.00 7.60E-02 1.54 9/21/91 00: 42 1.15 0.42 0.52 0.00 6.52E-02 1.31 9/21/91 02:46 0.97 0.40 0.42- 0.00 4.54E-02 -1.10 9/21/91 04:39 0.81 0.34 _0.34 ___0.00 2.46E-02 0.92_

c. Cleanup system flow history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded:

The cleanup flow through the CVCS mixed bed demineralizer was approximately 112 gpm far the 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to exceeding the limit of 1 microcurie per gram. This cleanup flow was maintained while the DEI I-131 limit was exceeded.

d. Time duration when the specific activity of the primary coolant exceeded the radiciodine limit. _

The specific activity of the RCS exceeded the T/S 3.448 limit of 1 microcurie per gram Dose Equivalent I-131 for 20.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months . from 0218 CDT 9/20/91 to 0439 CDT on 9/21/91.

e. Graph of the I-131 concentration and. one other radiciodine isotope concentration in microcuries per gram as a function of_ time for the duration that the specific activity was above the steady-state level.

See Graph 1: 'RCS-Iodines *

. . . _ _ = _

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p i Att,ichment to NO 92 006tl j Pagt 12 of 12 L

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Text

SUMMARY

SUMMARY

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