ML20205J953
| ML20205J953 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek |
| Issue date: | 01/31/1986 |
| From: | Koester G, Mike Williams KANSAS GAS & ELECTRIC CO. |
| To: | Johnson E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV), NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| KMLNRC-86-026, KMLNRC-86-26, NUDOCS 8602260702 | |
| Download: ML20205J953 (9) | |
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NOIE CREEK GENERATING STATION MON 1MLY OPERATING REPORP M:NIH:
January YEAR: 1986 p
Docket No.: SIN 50-482 Facility Operating License No.: NPF-42 Report No.
11 Sulnitted by:
Kansas Gas and Electric Company 8602260702 860131
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%e following report highlights the operating experience of Elf Creek Generating Station for the month of January,1986. W is report is being provided pursuant to Technical Specification 6.9.1.8.
I.
SUN 44RY OF OPERATING EXPERIENCE During the entire month of January, the unit operated in Mode 1, Power Operation, bringing Wolf Creek's record continuous days on line to one hundred twelve days. %ere were no significant load reductions during January.
II.
MAJOR SAFETY RELATED MAINIENANCE ACTIVITIES
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During the leonth of January, Essential Service Water train "B" was taken out of service to allow corrective ard preventive leaintenance work on its camponents. Following this, probleas with tlw Service Water supply valves to Essential Service Water train "B",, EP-HV-024 and EP-HV-026, necessitated continuous systen operation until the Limitorque operators were repaired.
III. CHANGES, TESTS, AND EXPERIMENTS We following is a brief description of safety evaluations performed i
pursuant to 10 CPR 50.59 on changes, tests, and experiments during the month of January.
1.
Safety Evaluation 86-SE Originated to allow the installation of performance monitoring instrumentation on secondary plant equipnent. No safety related equipnent is affected. No unreviewed safety or environnental questions are generated as a result of this tenporary modification.
I 2.
Safety Evaluation 86-SE Originated to allow opening the two j
Tornalo Missile Resistant Plugs marked A-3010-1 and 2 to i
facilitate repair to Main Steam Isolation Valve Hoists HKF29A and B.
Conditions were established to provide for Shift Supervisor notification of any tornado threats during the estimated 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> repair time. No unreviewed safety or environmental questions are generated as a result of this tenporary modification.
3.
Safety Evaluation 86-SE Originated to replace a section of 1.5 inch carbon steel pipe and flange with 1.5 inch schedule 40 inoonel pipe and a stainless steel flange in the condensate denineralizer system. % e carbon steel pipe and flange had corroded apparently due to reaction with acid feeding in just downstrean and leaking through a check valve. No unreviewed safety or environnental questions are generated as a result of this tenporary modification.
l 4.
Temporary Modification 85-394-KJ - Originated to reroute the emergency diesel engine starting air compressors CKJ01A and CKJ01D condensate dump valve drain piping directly to a drain. No unreviewed safety or erwironnental questions are generated as a result of this tenporary modification.
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5.
Temporary Modification 85-413-KJ - Originated to reroute the emergency diesel engine starting air compressors CKJ01B and CKJ01C condensate dep valve drain piping directly to a drain. No unreviewed safety or envirornental questions are generated as a 1
result of this temporary modification.
1 6.
Temporary Modification 85-477-BG - Originated to install a site-manufactured aligrement pin in the number 5 cylinder of the Positive Displacement Charging Pump. Once aligned, pump integrity i
and reliability is maintained by other supplier manufactured parts, and the pinp will function and perform as originally l
supplied. No unreviewed safety or environmental questions are generated as a result of this temporary modification.
7.
Technical Specification Otange 86-SE Originated to eliminate the axial flux difference target band and its associated penalty.
It also causes a small change to the Over-Temperature Differential
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Tenperature setpoints. Wis change, which allows greater operating flexibility, is a result of the Nuclear Steam Supply System vendor recalculating the allowable margins in the accident analysis. No unreviewed safety or environmental questions are generated as a result of this r W Technical Specification Change.
-1 8.
Plant M3dification Request (PMR) 00852, Revision 1 - Refer to PMR 00852 reported in May, 1985. As previously reported, HE-LT-315 ard HB-LT-335 are the level transnitters on the Recycle Evaporator Package, SHE02, and the Waste Evaporator Package, SHB01, respectively. Se instrument piping configuration would not allow the calibration of these level transnitters without pressurizing the entire skids, thus prolonging the procedure and exposing personnel to large radiation exposures. Pbr AIARA reasons, the modification relocated the bellows seals to simplify calibration.
%is current revision alds the necessary supportive docunentation. % is modification revision generates no unreviewed safety or environmental questions.
9.
Plant Modification Request 01333, Revision 3 - Refer to PMR 01333 reported in October, 1985. As previously stated, this PMR facilitated the total draindown of the dip tanks, SHD01A and B and SHD02A ard B, and the turbulator, SHD03. It removed check valves in the drain lines, aMad vent valves and altered the vent piping. % is current revision adds the nacaaavy supportive documentation. his PMR revision generates no unreviewed safety or envirorseental questions.
- 10. Plant Modification Request 01006 - Carryover oil fran the Degasifier Vacuun Pumps, CAN01A and B, was causing the Condenser Air Removal Radiation Monitor, GE-RE-92, to malfunction. Wis modification added an Oil Mist Eliminator, PANO3, and associated
. piping in the discharge line of the Degasifier Vacuin Pumps, thus 1
eliminating carryover oil problems. No unreviewed safety or environmental questions are generated as a result of this modification.
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- 11. Plant ledification Request 01478 - This modification installed a drain valve assembly on the gear bones for tne bridge and trolley.
drive, main and auxiliary hoists of Polar Crane 19313 to prevent oil spillage during oil change and to simplify periodic maintenance. No unreviewed safety or environmental questions are generated as a result of this modification.
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b OPERATING DATA REPORT DOCKET NO.
STN 50-482 WOLF CREEK GDIERATING STIhTIGE KANSAS GAS Att ELBCTRIC 00MPANY DATE 02-01-86 COMPLEffED BY M. Willians TELEPHONE 316-364-8831 OPERATING STATUS 1.
Reporting Period:
January, 1986 Gross Hours in Reporting Period: 744.0 2.
Currently Authorized Power Level (Mit): 3411 Max. Depend. Capacity (Mie-Net): 1128 Design Electrical Rating (PWe-Net): 1170 3.
Power Level to Which Restricted (If Any)(Mwe-Net):
N/A 4.
Reasons for restriction (If Any):
N/A This Month Yr to Date Ctznulative S.
Number of Hours Reactor was Critical 744.0 744.0 3534.3 6.
Reactor Reserve Shutdown Hours 0.0 0.0 78.7 7.
Hours Generator on Line 744.0 744.0 3515.6 8.
Unit Reserve Shutdown Hours 0.0 0.0 0.0 9.
Gross Thennal Energy Generated (M41) 2,480,479 2,480,479 11,355,412
- 10. Gross Electrical Energy Generated (MEI) 873,294 873,294 3,944,384
- 11. Net Electrical Energy Generated (MEI) 840,300 840,300 3,782,400
- 12. Reactor Service Factor 100.0 100.0 97.5
- 13. Reactor Availability Factor 100.0 100.0 99.7
- 14. Unit Service Factor 100.0 100.0 97.0
- 15. Unit Availability Factor 100.0 100.0 97.0
- 16. Unit Capacity Factor (Using MDC) 100.1 100.1 92.5
- 17. Unit Capacity Factor (Usirs Design Nie) 96.5 96.5 89.2
- 18. Unit Forced Outage Rate 0.0 0.0 3.0
- 19. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of each): None
- 20. If Shut Down at End of Report Pericii, Estimated Date of Startup:
N/A
- 21. Units in test Status (Prior to Connercial Operation): Porecast Achieved Initial Criticality 5-22-85 5-22-85 Initial Electricity 6-13-85 6-12-85 Connercial Operation 9-09-85 9-03-85 Page 4 of 7
AVERAGE DAILY IMIT POWER IJMIL DOCKET ND. STN 50-482 WOLF CREEK GENERATItG STRf1GI KANSAS GAS AND ELBCFRIC COWANY DATE 02-01-86 COMPLETED BY M. Williams 6
M0tml January, 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (M4e-Net)
(lege-Net) 1 1112 17 1122 2
1071 18 1119 3
1141 19 1123 4
1144 20 1125 5
1145 21 1123 6
1149 22 1125 7
1144 23 1126 8
1065 24 1123 9
1134 25 1123 10 1150 26 1124 11 1116 27
. 1123 12 1146 28 1131 13 1147 29 1149 14 1114 30 1152 15 1121 31 1152 16 1117 r
Page 5 of 7 v
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V UNIT SHUFDO W AND POWER REDUCTIONS
.i DOCKET NO. SIN 50-482-4 WOLF CRESC GENERATING budiCui KANSAS GAS Ale ELECTRIC 00MANY, DATE 02-01 ;
COMPIRIED BY M. Williams REPORP 70tml January, 1986 TEMPHONE 316-364-8831 TYPE MEIHODS SHUTPING F: FORCED DURATION REASON DOM THE REACIOR CORRECTIVE ACTIONS /C000ENTS No Date S: SCHEDULED (HOURS)
(1)
OR REDUCING 10HER(2)
NONE IR395UtY: During the entire month of January, the unit operated in Ibde 1, Power Operation. '1here were no significant load reductions durirg this month.
(1)
REASON: A: BQUIPMENT FAIIURE (EXPIAIN)
E: OPERATOR TRAINING AND LICENSE EXAMINATION (2) METHOD:
1.
MANUAL B: MAINTENANCE OR TEST F: ADMINISTRNEIVE 2.
MARRIAL SCRAM C: REFUELING G: OPERATIONAL ERROR (EXPIAIN) 3.
AUTOMRTIC SCRAM D: REGUIATORY RESPRICTION B: OTHER (EXPIAIN) 4.
OTHER (EXPIAIN) l 1
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KANSAS GAS AND ELECTRIC COMPANY WOLP CREEK GENERATING SFATIOi UNIT NO. 1 MomH January, 1986 SUPMARY OF OPERATING EXPERIENCE Listed below in chronological sequence is a stmmary of operating experiences for this month which required load reduction or resulted in significant non-load related incidents.
DME TIE EVENF January 1, 1986 0000 Unit in Mode 1, Power Operation.
1538 Circulating Water Ptrap (CWP) "A" tripped because of a faulty auto transformer, causing a power reduction to approximately 90 grcent power.
January 2, 1986 0205 Commenced power increase to approximately 95 percent power.
1756 Conmenced power increase to 100 percent power.
January 7,1986 2300 Comnenced power reduction to approximately 95 percent power in preparation for annual preventive maintenance on CWP "B".
January 8, 1986 0400 Reduced power to less than 90 percent power and tripped CWP "B".
0900 Comnenced power increase to approximately 95 percent power.
January 9, 1986 0420 Cu.... arc e power increase to 100 percent power.
January 11, 1986 0957 Reduced power to approximately 95 percent power to allow surveillance testing of the reactor protection instrumentation.
2145 Comnenced power increase to 100 percent power.
January 13, 1986 2145 Reduced power to approximately 98 percent power to avoid spikes on the Over-Temperature Differential Temperature instrument which were causing partial trips.
January 28, 1986 1655 0-
-rce power increase to 100 percent power.
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i Kansas gas AND ELECTRlC COMPANY T>e ELECT 54C COMPANY l
GLENN L MOESTER vctentssotm' hwettaa February 11, 1986 Director, Office of Resource Management U.S. Nuclear Regulatory Commission Washington, D.C.
20555 m
Mr. E.H. Johnson, Acting Director g g gg Division of Reactor Safety and Projects U.S. Nuclear Regulatory Commission by
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Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 KMLNRC 86-026 Re:
Docket No. STN 50-482 Subj: January, 1986 Monthly Operating Report 1
Gentlemen:
Enclosed is the January, 1986 Monthly Operating Report for Wolf Creek i
Generating Station.
This submittal is being made in accordance with the requirements of Technical Specification 6.9.1.8.
Yours very truly, AN Glenn L. Koester Vice President - Nuclear GLK:see Enclosure xc: P0'Connor (2), w/a l
JTaylor (12), w/a JCummins, w/a 9 6 K fr JE dd i i 201 N. Mamet - McNts, Kansas -Mai Address: RO. Box 200 i NcNte, Kansas 67201 - W: Area Code (316) 261-6461
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