ML20211D474

Monthly Operating Rept for Jan 1987

ML20211D474
Person / Time
Site:	Wolf Creek
Issue date:	01/31/1987
From:	Bailey J, Mike Williams WOLF CREEK NUCLEAR OPERATING CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
ET-87-0040, ET-87-40, NUDOCS 8702200442
Download: ML20211D474 (11)

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WOLF CREEK GENERATING STATION MON 1HLY OPERATING REPORT MOR1H: January YEAR: 1987_

Docket No.: 50-482 Facility Operatirg License No.: NPF-42 Report No.

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Subnitted by:

Wolf Creek Nuclear Operating Corporation i

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%e following report highlights the operating experience of Wolf Creek

'Generatirs. Station for the month of January,1987. Wis report is being provided pursuant to Technical Specification 6.9.1.8.

I.

SUMMARY

OF OPERATING EXPERIENCE On January 1,1987, Wolf Creek Nuclear Operating Corporation asstuned the management of Wolf Creek Generating Station. W e plant operated in Made 1, Power Operation throughout most of the month. On January 8, 1987, a personnel error caused a Safety Injection signal which resulted in a Reactor Trip and Turbine Trip. We plant renained in Mode 3, Hot Standby, in a maintenance outage until it returned to Mode 1 on January 12. Following.this, excessive Turbine Generator.

vibration forced the plant to operate in a derated condition and caused one Turbine Trip on January 20 and two maintenance outages on January 17 arxl 31.

II.

MAJOR SAFE 1"I RELATED MAIb7 PENANCE ACTIVITIES Major safety related maintenance activities included the followirg:

1.

Replacenent of a fuel pressure indicator and the differential pressure indicator for the rocker lube oil filter on Standby Diesel Generator "B".

2.

Replacement of the feed water flow transmitter for Stean Generator i

ngn, 3.

Replacenent of one of four 15 volt D' power supplies in each l.

energency load sequencer.

1 l

4.

Replacement of the position indicator in pressurizer Power Operated Relief Valve BB PCV-455A.

5.

Rework of the hydraulic operator on GK V767, the Class lE electrical equipment air conditioning unit SA condenser outlet isolation valve to the Essential Service Water Systen.

l III. CHANGES, TESTS, AND EXPERIMENTS The following is a brief description of safety evaluations perfonned pursuant to 10 CFR 50.59 on changes, tests, and experiments during the month of January.

1.

Safety Evaluation 86-SE-109 - Originated to replace part of the l

Process Sanpling Systen 3/8" sanple tubirg fran the Steam Generator Blowdown line with 3/4" pipe. No unreviewed safety or environmental questions are generated as a result of this i.

tenporary modification.

2.

Safety Evaluation 87-SE-001 - Originated to replace the stainless steel bushing on the handwheel shaft with a bronze bushing on 15 watertight doors. No unreviewed safety or environmental questions are generated as a result of this tenporary modification.

i 3.

Safety Evaluation 87-SE-002 - Originated to replace five handset stations with headset stations in the Gai-tronics connunications systen. No unreviewed safety or environmental questions are generated as a result of this tenporary modification.

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4.

Safety Evaluation 87-SE-003 - Originated to increase the instantaneous current setting required to trip the breake.rs for the FORV block valves to assure they can reverse direction during valve stroke without initiating a breaker trip. No unreviewed safety or enviromental questions are generated as a result of this temporary modification.

5.

Safety Evaluation 87-SE-004 - Originated to allow reusing a gasket built up with Grafoil ribbon on FORV BB PCV-455A. No unreviewed safety or enviromental questions are generated as a result of this tenporary modification.

6.

Safety Evaluation 87-SE-005 - Originated to allow various lifted leads and junpers while troubleshooting radiation monitor BM RE-

52. 'Ihe monitor's trip signal remains defeated by a temporary modification described in Safety Evaluation 86-SE-ll7. No unreviewed safety or environmental questions are generated as a result of this temporary modification.

7.

Safety Evaluation 87-SE-006 - Originated to connect a flow path with instrunents for measuring dissolved oxygen between the high pressure condenser and Condensate Pump PAD 01A. No unreviewed safety or environmental questions are generated as a result of this tenporary modification.

8.

Safety Evaluation 87-SE-007 - Originated to provide a vent path fran the high point of the suction lines on Condensate Sanple Punps PFM01A and PRM01B to the condenser. No unreviewed safety or environnental questions are generated as a result of this temporary modification.

9.

Safety Evaluation 87-SE-008 - Originated to defeat the high vibration trip on the main turbine. No unreviewed safety or environmental questions are generated as a result of this tenporary modification.

10. Safety Evaluation 87-SE-009 - Originated to defeat the main turbine high exhaust hood tenperature trip. No unreviewed safety or environmental questions are generated as a result of this tenporary modification.

11. Safety Evaluation 87-SE-010 - Originated to allow repair of water tight door dea 3 bolts by weld buildup an3 machinin3 to original dimensions. No unreviewed safety or environmental questions are generated as a result of this tenporary modification.

12. Safety Evaluation to a proposed revision to Technical Specifications 3/4.3.1, " Reactor Trip Systen Instranentation", and the Bases for 3/4.3.1 and 3/4.3.2, which affects the Reactor Protection Systen as follows:

a.

Increase the analog channel operational test surveillance interval to once per quarter.

b.

Increase the time an inoperable analog channel may remain untripped to six hours, and Page 2 of 9

c.

Increase the time an analog channel may remain bypassed to allow testirg of another channel to four hours.

No unreviewed safety or environmental questions are generated as a result of this proposed Technical Specification revision.

13. Plant Modification Request WO83-ZL004, revision 1 - Originated to add the installation of a boat ramp near the Make-Up Water Discharge Structure to this PMR which corrects erosion at the Main Dan. No unreviewed safety or environmental questions are generated as a result of this plant modification.

14. Plant Modification Request 00920, revision 3 - Originated to add drawing M-531-W-M-12HA02-0, which replaces M-531-W-M-02HA02-0. No unreviewed safety or environnental questions are generated as a result of this plant modification.

15. Plant Edification Request 01542, revision 2 - Originated to allow use-as-is of replacement 4-way valves for the Main Feedwater Isolation Valves, whose dimensions are out of the given tolerence. No unreviewed safety or environmental questions are generated as a result of this plant modification.

16. Plant mdification Request 01744 - Originated to revise P&ID M-23 sheet 1 to reflect the as built condition of a pressure test point and pressure regulatirs valve 1FPl54A 1/2. No unreviewed safety or environmental questions are generated as a result of this plant modification.

17. Plant Modification Request 01852 - Originated to provide chilled water to the steau tunnel heating coil. No unreviewed safety or environnental questions are generated as a result of this plant modification.

18. Plant mdification Request 01927 - Originated to allow use-as-is of a gouged rebar in the Auxiliary Buildiry wall. No unreviewed safety or environmental questions are generated as a result of this plant modification.

19. Plant maification Request 01937 - Originated to correct danage caused to feedwater system piping caused by a transient which produced excessive piping movenent. No unreviewed safety or environmental questions are generated as a result of this plant modification.

20. Plant ledification Bequest 01940 - Originated to repair the 4.16KV Class lE breaker NB0201 lift limit switch mountirg. No unreviewed safety or environmental questions are generated as a result of this plant modification.

21. Plant ledification Request 01945 - Originated to relocate Condensate Denineralizer valve AK PCV-216 and install pressure indicator AK PI-311. No unreviewed safety or environmental questions are generated as a result of this plant nodification.

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22. Plant Modification Request 01953 - Originated to allow the use of heat shrink tubing to repair nicked insulation in Conax Connector conductors. No unreviewed safety or environmental questions are

_ > generated as a result of this plant modification.

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OPERATING DATA REPORP DOCKET NO.

50-482 i

WOLF CREEK GENERATING STATION WOLF CREEK NUCLEAR OPERATING CORPORATION DATE 02-01-87 COMPLETED BY M. Willians TELEPHONE 316-364-8831 OPERATING STATUS 1.

Reporting Period:

January,1987 Gross Hours in Reporting Period: 744 2.

Currently Authorized Power Level (MWt): 3411 Max. Deperrl. Capacity (MWe-Net): 1128 Design Electrical Rating (IWe-Net): 1170 3.

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

N/A 4.

Reasons for restriction (If Any):

N/A

'Ihis Month Yr to Date Cumulative 5.

Number of Hours Reactor was Critical 653,3 653.3 9967.2 6.

Reactor Reserve Shutdown Hours 77.9 77.9 249.2 7.

Hours Generator on Line 603.1 603.1 9793.2 8.

Unit Reserve Shutdown Hours 0.0 0.0 0.0 9.

Gross Thermal Energy Generated (MEI) l_,533,313 1,533,313 31,278,655

10. Gross Electrical Energy Generated (MWH) 545,380 545,380 10,911,750

11. Net Electrical Energy Generated (MWH) 511,265 511,265 10,410,554

12. Reactor Service Factor 87.8 87.8 80.5

13. Reactor Availability Factor 98.3 98.3 82.5

14. Unit Service Factor 81.1 81.1 79.1

15. Unit Availability Factor 81.1 81.1 79.1

16. Unit Capacity Factor (Usirs MDC) 60.9_

60.9 74.5

17. Unit Capacity Factor (Using Design MNe) 58.7 58.7 71.9

18. Unit Forced Outage Rate 6.9 6.9 4.5

19. Shutdowns Scheduled Over Next 61%nths (Type, Date, and Duration of each) : None 20.

If Shut Down at End of Report Period, Estimated Date of Startup:

_2-01-87 Page 5 of 9 f

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AVERAGE 1%ILY UNIT POWER LEVEL

' DOCKET NO.

50-482 NOLF CREEK GENERATING STATION

~ ' WOLF CREEK NUCLEAR OPERATING CORPORATICN DATE 02-01-87' 00MPIETED BY M. Willims TELEPHCNE316-364-8831 MONTH January,1987

- ~ DAY AVERAGE DAILY POWER LEVEL IRY AVERAGE DAILY IGER LEVEL (M4e-Net)

(Mie-Net) 1 1150 17 142 2

1155 18 161 3

1133 19 976 4

1147 20 855 5

1147 21 0

6 1150 22 579 7

1152-23 896 8

862 24 901 9

0 25 902 10 0

26 873 11 0

27 838 12 72 28 708 13 840 29 590 t

14 862 30 589 j

15 863 31 69 16 866 i

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UNIT SHUIDOWN AND KMER REDUCTIONS DOCKET NO.

50-482 WOLF CREEK GENERATING STATION WOLF CREEK NUCLEAR OPERATING CORPORATION DATE 2-01-87 00MPLETED BY M. Williams REPORT MONTH January, 1987 TELEPHONE 316-36_4-8831 i TYPE ME1 HODS SIU1 TING F: EURCED DURATION REASO4 DOWN THE REACIOR CORRECTIVE ACTIONS / COMMENTS No Date S: _ SCHEDULED (HOURS)

_ (1)

_OR REDUCING POWER (2) 1 870108 F

92.6 B

3 Reactor Trip due to Safety Injection Signal. The outage was extended at 0900 on January 9,1987, to allow maintenance of Feed systen valves. 'Ihis created 14.7' hours of forced outage and 77.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> of scheduled outage.

2 870117 S

23.2 B

1 Correct turbine generator vibration.

3 870120 F

30.3 B

3 Turbine Trip, Reactor Trip due to turbine generator vibration.

4 870128 F

0 B

4 Reduced power to 55 percent due to turbine generator vibration.

5 870131 S

18.8 B

1 Correct turbine generator vibration.

S0pMARY: A forced outage on January 8,1987, due to a personnel error while testirg was extended to nearly four days to allow maintenance of the Main Feed System. Much of the remainder of the month was involved with attempts to correct turbine generator vibration. This included one forced outage and two scheduled outages.

(1)

REASON: A: EQUIPMENT FAILURE (EXPLAIN)

E: OPERA'IOR TRAINING AND LICENSE EXAMINATION (2)

ME1 HOD:

1.

MANUAL B: MAINTENANCE OR TEST F: ADMINISTRATIVE 2.

MANUAL SCRAM C: REFUELING G: OPERATIONAL ERROR (EXPLAIN) 3.

AUIDMATIC SCRAM D: REGUIA'IORY RESTRICTION H: OIHER (EXPIAIN) 4.

OIHER (EXPIAIN)

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WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION UNIT NO. 1 MONIH January,1987

SUMMARY

OF OPERATING EXPERIENCE Listed below in chronological sequence is a stmnary of operating experiences for this month which required load reduction or resulted in significant non-loal related incidents.

DATE TIME EVENP January 1, 1987 0000 Unit in Mode 1, Power Operation January 8, 1987 1818 Reactor Trip due to Safety Injection signal. (LER 87-002-00) Unit in Itde 3, Hot Standby.

January 11, 1987 2327 Unit in Mxle 2, Startup.

January 12, 1987 0114

'Ihe reactor is critical.

0533 Unit in Mode 1, Power Operation, for turbine generator testing.

1453 Synchronized with grid, increased power to 30 percent. Held at 30 percent until stean generator chenistry in specification.

2138 Increased power to 77 percent. Held power at 77 percent due to turbine generator vibration.

January 17, 1987 0317 Ccmnenced reducing power.

0615 Opened generator ouput breakers to allow balancing turbine generator.

0647 Unit in lede 2, Startup.

January 18, 1987 0500 Unit in Mode 1, Power Operation.

0526 Synchronized with grid, increased power to 13 percent. Held power at 13 percent for turbine tenperature gradients to equalize.

0843 Increased power to 30 percent. Held power at 30 percent for repair of Stean Generator Blowdown Flash Tank relief valve.

January 19, 1987 0250 Ccanenced increasing power to 100 percent.

January 20, 1987 1800 Turbine Trip, Reactor Trip due to high vibration in turbine generator.

(LER 87-004-00)

Unit in Mode 3, Hot Standby.

Page 8 of 9

DATE TIME EVDTP January 21, 1987 0527 Unit in Mode 2, Startup.

0547

'1he reactor is critical.

0906 Unit in Mode 1, Power Operation, for turbine

. generator testirg.

1439 Unit in Mode 2, Startup, while balancing the turbine generator.

2003 Unit in Mxle 1, Power Operation, for turbine generator testing.

January 22, 1987 0017 Synchronized with grid, increased power to 84 percent. Held power at 84 percent due to turbine generator vibration.

January 26, 1987 1315 Reduced power to 75 percent due to turbine generator vibration.

January 28, 1987 0945 Reduced power to 55 percent due to turbine generator vibration.

January 31, 1987 0250 ccmnenced reducire power.

0510 Opened generator output breakers to allow correctirg turbine generator vibration.

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NUCLEAR OPERATING CORPORATION February 12, 1987 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C.

20555 Letter: ET 87-0040 Re:

Docket No. 50-482 Subj:

January, 1987 Monthly Operating Report Gentlemen:

Enclosed is the January, 1987 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.

Yours very truly, V O John A. Bailey Vice President Engineering and Technical Services JAB:see Enclosure cc: P0'Connor (2), w/a JCummins, w/a RHartin, w/a i

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PO. Box 411 > Burtengton, KS 66839 i Phone. (316) 364 8831

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