ML20134G496

Monthly Operating Rept for Jul 1985

ML20134G496
Person / Time
Site:	Wolf Creek
Issue date:	07/31/1985
From:	Koester G, Mike Williams KANSAS GAS & ELECTRIC CO.
To:	Denise R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV), NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
KMLNRC-85-198, NUDOCS 8508260282
Download: ML20134G496 (12)

Text

.

WOLF CREEK GENERATING STATION MONIELY OPERATING REPORT MONIE:

July YEAR: 1985 Docket No.: SIN 50-482 Facility Operatirg License No.: NPF-42 Report No.

5 Subnitted by:

Kansas Gas and Electric Canpany 8508260282 850731

~~~

PDR ADOCK 05000482 R

PDR

We following report highlights the operating experience of Wolf Creek C+nerating Station for the month of July,1985. This repart is beirg provided pursuant to Technical Specification 6.9.1.8.

I.

SUMMARY

OF OPERATING EXPERIENCE During the month of July, Ibwer Ascension Testiry was completed at the fifty percent aM seventy-five percent power plateaus. m is testing included the Large Inad Reduction Wst frm a reactor power level of seventy-five percent, which was ampleted satisfactorily without a reactor trip.

Several Engineered Safety Features actuations and Reactor trips occurred due to feedwater control problems. These problems were a conbination of personnel activities aM equignent problems, aM have been resolved by cmbination of equipment re-adjustments, procedure modifications, aM operator retraining.

II.

MAJOR SAFETY REIATED MAINTENANCE ACTIVITIES The major safety related maintenance activities that were performed during the month of July involved the Main Steamline Isolation Valves (MSLIV's) and Feedwater Isolation Valves (FWIV's). W ese activities included the development of a comprehensive trouble-shooting procedure, the construction of a test bench for testing the 4-way valves on the MSLIV's and FWIV's, aM the repair of oil leaks.

Other activities included adjusting the pressure equalizing valve on the contairment access hatch, repair of the jacket water heaters on the staMby emergency diesel generators, aM repair of hinge pin leakage on a Main Feedwater check valve.

III. CHANGES, TESTS, AND EXPERIMENTS

%e following is a brief description of safety evaluations performed pursuant to 10 CFR 50.59 on charges, tests, and experiments darire the month of July.

1.

Temporary fedification 85-SE Replace pipe caps with quick disconnect couplirgs on two test connections on the personnel airlock door seals to simplify the attachment of equipnent to leak test the seals. No unreviewed safety or environnental questions are generated as a result of this temporary change.

2.

Temporary Modification 85-SE Install a blank plate at an existing joint in duct 200-5NL-4 to cut off normal exhaust flow frm the Fuel Buildirg. No unreviewed safety or environmental questions are generated as a result of this temporary change.

3.

T m porary Modification 85-SE Install temporary insulation on check valve BB-V8378B, normal charging connection to the Reactor Coolant System, and on flow element BB-FE-427, measurirg the cmbined flows of the Inop 2 bot and cold leg RfD manifolds.

Insulation will remain until the next major outage. No unreviewed safety or environmental questions are generated as a result of this temporary charge.

Page 2 of 11

Temporary Modification 85-SE Install scaffolding to work on 4.

damper GIr-D-172 on the 2047' elevation of the Auxiliary Building. No unreviewed safety or environmental questions are generated as a result of this temporary change.

'Ibnporary mdification 85-SE Install scaffolding to reach 5.

ducts on suction and discharge of fans CGF03A aM B, main steau enclosure exhaust fans, in Area 4 of the Auxiliary Building on elevation 2047'. No unreviewed safety or environmental questions are generated as a result of this temporary change.

6.

Tenporary Modification 85-SE Install scaffolding on elevation 1974' of the Auxiliary Building to clean and insulate various 4" lines in the Essential Service Water and Auxiliary Building Heating, Ventilation, and Air Conditioning systems to rom coolers SGLO9A aM B, SGL10A aM B, SGL12A and B, and SGL13 A aM B.

Scaffolding was to be installed in only one of two redundant safety equipnent roons at one time. No unreviewed safety or environnental questions are generated as a result of this temporary change.

Temporary !bdification 85-SE Install scaffolding in Area 5 7.

of the Auxiliary Building on the 2039' elevation to facilitate cleaning of miscellaneous heating, ventilation aM air conditioning equipment. No unreviewed safety or environmental questions are generated as a result of this temporary change.

Temporary Modification 85-SE Remove covers from Essential 8.

Service Water valve pits to ptanp out the pits. Work was to be performed in one bay at a time, leaving the co/er in place on the other bay. Covers were to be replaced if severe weather threatened, or if work was to be suspended for a period of time.

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

9.

Temporary Modification 85-SE Install scaffolding on the 2026' elevation of the Auxiliary Building to work on damper GF-D-065. No unreviewed safety or environmental questions are generated as a result of this temporary charge.

10. 'Iwnporary Modification 85-SE Install scaffolding on the 2026' elevation of t_he Auxiliary Building to repair a void in the concrete. No unreviewed safety or environmental questions are generatM as a result of this temporary change.

11. Tempcrary Modification 85-SE Install scaffolding at the west eM of wall A in the north Residual Heat Removal pump room of the Auxiliary Building on the 1967' elevation. No unreviewed safety or environnental questions are generated as a result of this temporary change.

12. Temporary Modification 85-SE Install scaffolding in Area 5 on the 2047' elevation of the Auxiliary Building to install insulation on Icop 3 Main Steamline Isolation Valve. No unreviewed safety or environmental questions are generated as a result of this temporary change.

Page 3 of 11

13. Temporary mdification 85-SE Install scaffolding in Ibom 1323 (North Pipire Penetration Ibm) on the 2000' elevation of the Auxiliary Building to clean and insulate Essential Service Water system piping. No unreviewed safety or enviromental i

questions are generated as a result of this temporary change.

14. Temporary Modification 85-SE Install a blank flarge in pipe EC 070-HCD-4, fuel pool cleanup system, in the Refuelirg Water Storage Tank valve pit to facilitate repair of valve BN-V002, at the inlet to the tank.- No unreviewed safety or environmental questions are generated as a result of this temporary charge.

4 i

15. Temporary Modification 85-SE Reduction of the Control' Room air conditionirg flow rate to docment noise reduction while maintaining temperature at or below 84 degrees F per Technical Specification 4.7.12.

No unreviewed safety or envirornental questions are generated as a result of this temporary charge.

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16. Temporary Modification 85-SE-70'- Add a 4" connection to the flange between valves AP-v005 and AP-LV-2, condensate storage tank isolation and level control valves, to supply demineralized water to the condensate storage tank, TAP 01, on the normal makeup line for the tank. No unreviewed safety or environmental j

questions are generated as a result of this temporary charge.

17. Temporary Modification 85-SE Install a temporary nitrogen supply to tanks TKA 02, 03, 04 and 05, auxiliary feedwater 1

control / main steam atmospheric relief valves accmulators, until pep lNIDlP returned to normal operation. No unreviewed safety or environmental questions are generated as a result of this temporary change.

18.'

Temporary Modification 85-SE Install scaffolding in Rom i

1322 (South Pipire Penetration Ibom) on the 2000' elevation of the Auxiliary Building to clean and insulate Essential Service i

l Water system pipirg. No unreviewed safety or environmental i

questions are generated as a result of this temporary change.

t l

19. Temporary Modification 85-SE Install a variable speed sheeve l

on SGK04, Main Control Ibom air conditioning unit, to support Control Ibm Air Conditionirg flow reduction. - No unreviewed j

safety or environmental questions are generated as a result of j

this temporary change.

l

20. Temporary Modification 85-SE-74 '- Install a jmper line to supply nitrogen to safety injection accmulator "D", bypassing valve EP-IW-8875D, nitrogen supply valve, until this-valve is-restored to l

normal service. The jmper will run from EP-V058, test

]

connection on the nitrogen header, to EP-V103, drain valve 'on the level transnitter. No unreviewed safety or envirornental l

questions are generated as a result of this temporary change.

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Page 4 of 11 i

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21. Temporary Modification 85-SE Install scaffolding to high point vent valves EM-V156 aM EM-V242 in the high pressure coolant injection system thus facilitating perfonnance of a surveillance test. No unreviewed safety or envirortnental questions are generated as a result of this temporary change.

22. Temporary Modification 85-SE Install pressure instrtmentation on the tube side of High Pressure Feedwater heaters at existing pressure points AE-V052, AE-V055, AE-V058 aM AE-V062. No unreviewed safety or environmental questions are generated as a result of this temporary change.

23. Temporary Modification 85-SE Install scaffolding at Iccation TA and T8 (acid neutralizer and degasifier area) ard Incation TA and T3 (railroad bay) on 2000' elevation of Turbine Building. No unreviewed safety or environmental questions are generated as a result of this temporary change.

24. Temporary Modification 85-SE Replace bolts in bonnets of valves AE-V006, suction isolation for Main Feedwater Ptap "B",

and AE-V009, suction isolation for Main Feedwater Pump "A",

to allow sealant application and stop bonnet leaks. No unreviewed safety or environmental questions are generated as a result of this temporary change.

/-

i Page 5 of 11

i OPERATING DATA REFORT 4

DOCKET NO.

SIN 50-482 WOLF CREEK GENERATING STATION KANSAS GAS AND ELECTRIC COMPANY 4

DATE 8-01-85 COMPIEEED BY M. Williarns l

TELEPHONE 316-364-8831 OPERATING STATUS 1.

Reporting Period: July, 1985 Gross Iburs in Reporting Period:

744 7

2.

Currently Authorized Power Level (MWt): 3411 Max. Depend. Capacity (PMe-Net): 1117 Design Electrical Rating (?We-Net): 1170 l

3.

Power Level to Which Restricted (If Any) (Mwe-Net) :

N/A 4.

Reasons for restriction (If Any):

N/A l

'1his Month Yr to Date Cunulative 5.

Number of Hours Reactor was Critical 542 1180 1180 l

6.

Iwactor Reserve Shutdown Hours 202 443 443 l

7.

Hours Generator on Line 504 809 809 8.

Unit Reserve Shutdown Hours 240 343 343 4

l 9.

Gross Thermal Energy Generated (MH) 1,025,780 1,382,456 1,382,456 i

10. Gross Electrical Ewrgy Generated (MWH) 333,736 413,344 413,344 j

11. Net Electrical Energy Generated (IM1) 300,007 347,919 347,919

12. Reactor Service Factor N/A

13. Reactor Availability Factor N/A

14. Unit Service Factor N/A i

15. Unit Availability Factor N/A I

16. Unit Capacity Factor (Using MDC)

N/A

17. Unit Capacity Factor (Using Design MWe)

N/A i

18. Unit Forced Outage Rate N/A

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:

8-1-85 l

21. Units in test Status (Prior to Cannercial Operation): Foiecast Achieved Initial Criticality 5-22-85 5-22-85 l

Initial Electricity 6-13-85 6-12-85 l

Ccanercial Operation 9-09-85 Page 6 of 11 1

Ie DOCKER NO.

STN 50-482 WOLF CREEK GENERATING STATION e

KANSAS GAS AND ELECTRIC COMPANY DATE 8-01-85 COMPLETED BY M. Williams TELEPHONE 316-364-8831

M0tml, July, 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (Nie-Net)

(MWe-Net) 1 0

17 356 f

i 2

0 18 476 3

0 19 511 4

0 20 643

)

5 0

21 721 1'

6 423 22 782 7

474 23 809 8

481 24 225 9

0 25 765 10 0

26 804 11 0

27 806 12 0

28 704 13 9

29 801 14 441 30 832 15 467 31 719 16 291 INSTRUCTIONS:

i on this form, list the average daily unit power level in M4e-Net for each day in the reporting month. Ompute to the nearest whole megawatt.

'Ihese figures will be used to plot a graph for each reporting month Note that when maximtn.

dependable capacity is used for the net electrical rating of the unit, there may be occasions when the daily average power level exceeds the 100% line (or the restricted power level i

line). In such cases, the average daily unit power output sheet should be footnoted to explain the apparent anomaly..

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Page 7 of 11

UNIT SHIJfDOWN AND NWAR REDUCTIONS i

DOCKET NO.

S'IN 50-482 WOLF CREEK GENERATING STATION KANSAS GAS AND ELECTRIC COMPANY DATE 8-01-85 (XMPLETED BY M. Williams REIORT MONIE July, 1985 TELEPHONE 316-364-8831 MEnlos TYPE SHIJITING DOWN F: FORCED DURATION REASON Tile REACIOR OR CORRBCPIVE ACPIONS/CCNMENTS No Date S: SCHEDULED (HOURS)

(1)

REDUCING POWER (2) 3 850629 S

107.3 B

4 Manual Trip per Startup Test Program frca Auxiliary Shutdown Panel to demon-strate its operability.

4 850709 F

90.9 A

3 Trip due to feedwater con-trol problem durirg Startup

'1bst Program transient test-ing. A test recorder in-duced a false control signal.

(Licensee Event Reports85-049, 85-050, and 85-042).

5 850715 S

11.3 8

2 Reactor trip to test nega-tive rate trip circuitry arx3 analyze plant performance per Power Ascension Testing.

6 850723 P

10.7 A

3 Trip due to instrument power supply failure Ye?ulting in loss of control power to a l

feedpmp.

(Licensee Event Report 85-054) 7 850728 S

0 B

4 Large Load Reduction 'Ibst per Power Ascension Testirg.

8 850731 F

20.2 A

3 Trip due to failure of a power range Nuclear Instru-mentation channel while a second channel was under test.

(Licensee Event Report 85-058)

SLBMARY: Durirg the month of July, Ibwer Ascension Testing was empleted at the fifty and seventy-five percent power plateaus. This testing included a large load reduction test and Ibactor trip tests. Several trips occurred due to feedwater system related problems.

'Ihe Gross Electrical Energy Generated and Net Electrical Energy Generated figures for July have been adjusted due to recalibration on the kilowatt-hour meters.

(1)

REASON:

(2) ME1 BOD:

A: EQUIPMENP FAILURE (EXPLAIN) 1.

MANUAL B: MAINTENANCE OR TEST 2.

MANUAL SCRAM C: REFUELING 3.

AUI0MATIC SCRAM D: REGULA'IORY RESTRICTION 4.

OTHER (EXPIAIN)

E: OPERA'IOR TRAINING AND LICENSE EXAMINATION F: ADMINISTPATIVE G: OPERATIONAL ERROR (EXPLAIN) i H: OIHER (EXPIAIN)

Page 8 of 11

KANSAS GAS AND ELECTRIC 00KPANY WOLF CREEK GENERATING STATION UNIT NO. 1 M0tml July, 1985 SIM1ARY OF GPERATING EXPERIENCE Listed below in chronolcx3 cal sequence is a smmary of operating experiences for this month 1

which required load reduction or resulteJ in significant non-load related incidents.

DA'IE TIME EVENT June 6, 1985 2250 Erroneously reported that a Reactor Trip and Safety Injection occurred in Monthly Report #4. 'Ihis entry should read: Reactor Trip, Auxiliary Feed Actuation Signal (AFAS) and Feedwater Isolation Signal (EWIS) occurred.

July 1, 1985 0000 Plant in Mode 3.

July 2, 1985 2001 Received a Control Room Ventilation Isolation Signal (CRVIS) due to the spurious spiking of the gaseous channel of Control Rxxn ra31ation monitor GK-RE-04.

Reportable per 10 CFR 50.72 and 50.73.

July 4, 1985 2338 Cmmenced Reactor startup. Plant entered Mode 2.

July 5, 1985 0045 Plant entered Mode 3 due to operator discretion.

0501 Cmmenced Reactor startup. Plant entercl Mode 2.

0804 Entered Mode 1.

0946 AFAS and FWIS occurred due to high-high level in Stean Generator "A".

Reportable per 10 CFR 50.72 and 50.73.

0947 Plant entered Mode 2.

1016 Plant entered Mode 1.

1119 Synchronized with grid.

1506 Received CRVIS due to spurious spiking of GK-RE-04.

Reportable per 10 CFR 50.72 and 50.73.

July 7, 1985 0550

' Received CRVIS due to the spurious spiking of GK-RE-04.

Reportable per 10 CFR 50.72 and 50.73.

Page 9 of 11

-DATE TIME EVENT July 8, 1985' 0216 Received CRVIS due to the spurious spiking of M-RE-04.

Reportable per 10 CFR 50.72 and 50.73.

+

l 2205 Received CRVIS due to the spurious spiking of E-RE-04.

Reportable per 10 CFR 50.72 and 50.73.

July 9, 1985 0932 Received CRVIS due to the spurious spiking of E-RE-04.

Reportable per 10 CFR 50.72 and 50.73.

j.

i 1115 Reactor Trip, AFAS, and EWIS occurred on low-low stem generator level signal due to a personnel error. Entered Mode 3.

Reportable per 10 CFR 50.72

)

and 50.73.

I July 10, 1985 0228 Cmmenced Reactor startup. Entered Mode 2.

e j

0547 Received EWIS due to high level in Steam Generator "B".

Reportable per 10 CFR 50.72 and 50.73.

i 0715

. Plant entered Mode 1.

0815 Received EWIS due to high' level in Steam Generator "B".

Reportable per 10 CFR 50.72 and 50.73.

0817 Reactor trip occurred due to low Steam Generator.

level. Entered Mode 3.

Reportable per.10 CFR 50.72 and 50.73.

i l

1156 Ctenenced Reactor startup. Entered Mode 2.

1321 Received EWIS due to high level'in Stea5 Generator

" B". Reportable per 10 CFR 50.72 and 50.73.

1 2347 Entered Mode 1.

I July 11, 1985 0220 Received EWIS and AFAS due to high level in Steam Generator "A".

Reportable per 10 CFR.50.72 and l

50.73.

0221

. Reactor trip occurred due to high flux on the Intermediate Range Nuclear Instrtunentation, due to j

. overly conservative setpoints.: Entered Mode 3.

Reportable per 10 CFR 50.72~and 50.73.

i July 12, 1985 0445

- Received CRVIS due to broken detector tape on a Control Room chlorine monitor. Reportable per 10 CFR 50.72 and 50.73.

0736 Received CRVIS due:to-the spurious spiking of l

E-RE-04.

Reportable per 10 CPR 50.72 and 50.73.

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Page 10 of 11.

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, ~__ _

DATE TIME EVENP 1246 Received CRVIS due to the spurious spiking of GK-RE-04.

Reportable par 10 CFR 50.72 and 50.73.

2158 Comnenced Reactor startup. Entered Fbde 2.

July 13, 1985 0212 Entered Mode 1.

0607 Synchronized with grid.

July 15, 1985 2245 Reactor trip initiated per Power Ascension Testing.

Entered Mode 3.

July 16, 1985 0236 Catmenced Reactor startup.

Entered Mode 2.

0326 9eentered Mode 3 due to operator discretion.

0526 Comtenced Reactor startup. Entered Mode 2.

0848 Eatered Fbde 1.

1005 Syrchronized with grid.

July 17, 1985 0848 Received CRVIS due to spurious signal fran Control Roan Raiiation nonitor due to a faulty bypass switch. Reportable per 10 CFR 50.72 and 50.73.

July 22, 1985 0353 Received CRVIS due to broken detector tape on Control Boon chlorine monitor. Beportable per 10 CFR 50.72 and 50.73.

July 23, 1985 0807 Reactor trip, EWIS ard AFAS occurred due to loss of control power to Main Feedwater Punp. Entered Mode 3.

Reportable per 10 CFR 50.72 and 50.75.

1356 Ccmnenced Reactor startup. Entered Mode 2.

1727 Entered Fbde 1.

1855 Synchronized with grid.

July 28, 1985 0059 CRJIS occurred due to a spurious Control Boan chlorine monitor spike. Reportable per 10 CFR 50.72 ard 50.73.

0615 Canpleted Large Ioad Reduction 7bst fran seventy-five percent reactor power. Reactor stable at twenty-five percent power.

July 31, 1985 0348 Reactor trip occurred due to a Nuclear Instrunentation channel spike while a second channel was out of service. Entered Mode 3.

Reportable per 10 CFR 50.72 and 50.73.

j Page 11 of 11

KANSAS GAS AND ELECTRIC COMPANY THE ELECTS *C COMPANY OLENN L MOESTER WDCE P.E$sOEpeT DeuCLE4.

August 15, 1985 Director, Office of Resource Managerent U.S. Nticlear Regulatory Comission Washington, D.C.

20555 Mr. R.P. Denise, Director Division of Reactor Safety and Projects U.S. IUclear Regulatory Comission Region IV 611 Ryan Plar.a Drive, Suite 1000 Arlington, Texas 76011 KMLPGC 85-198 Re:

Docket !b. SIN 50-482 Subj: Jt21y, 1985 Monthly Operating Report Gentlemen:

Enclosed is the Jtily, 1985 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.

If }ut have any questions concerning this natter, please contact me or Mr. Otto Maynard of my staff.

Yours very truly, Glenn L. Koester Vice President, Ibclear Gm: dab Enclosure xc: P0'Connor (2), w/a JIaylor (12), w/a f

f JCumins, w/a g

i I

l 201 N. Market - WicNta, Kansas - Mad Address: Po. Box 208 I Wichita, Kansas 67201 - Telephone: Area Code (316) 261-6451