ML20132E138

Monthly Operating Rept for Apr 1985

ML20132E138
Person / Time
Site:	Wolf Creek
Issue date:	04/30/1985
From:	Koester G, Mike Williams KANSAS GAS & ELECTRIC CO.
To:	Denise R NRC - WOLF CREEK TASK FORCE, NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
KMLNRC-85-111, NUDOCS 8507170633
Download: ML20132E138 (10)

Text

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l WOLF CREEK GENERATING STATION MONIELY OPERATING REN RP MONIE: April YEAR: 1985 Docket No. : SIN 50-482 Facility Operating License No.: NPP-32 Report No. 2 1

Subnitted by:

Kansas Gas and Electric Capany 1

i es507170633 850430 PDR R

ADOCK 05000482 PDR j7@Qp

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!- %e following report highlights the operating experience of Wolf Creek i i Generating Station for the month of April,1985. Wis report is being provided pursuant to Technical Specification 6.9.1.8.

! - I. Operating Experience '

During the month of April, cold rod drop testing was completed. We i- plant has been heated up and pressurized to normal operating temperature and pressure, and has entered Mode 3.

j .Several Engineered Safeguards Features actuations occurred during i April. A portion of these were due to personnel errors or spurious signals. Two actuatioss' occurred in response to valid plant j conditions generated as a result of personnel actions.

t II. Major Safety Related Maintenance Activities 4

! The major safety related maintenan performed during the month of April includes the rework of the Power Operated helief Valves to '

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-increase the clearances between the plugs and the ca3es and the replacanent of the inboard oil seal of a centrifugal charging punp.

l_ Sane work was performed on the Bnergency Diesel Generators including i the performance of web deflection tests and inspection of the pillow  ;

i block bearings.

1 l III. CHANGES, TESTS, AND EXPERIMENTS

{ The following is a t,cief description of safety evaluations performed pursuant to 10 CFR 50.59 on changes, tests, and experiments during the

! month of April.

i j 1. Plant Modification Request (IMR) #00588 - Rework of Ruskin fire i

danpers due to failure of. the dampers to close. if ' flow is present .

f in the ductwork. No unreviewed safety or environmental questions  !

j are generated as a result of this change.  ;

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2. Plant Pbdification Request 200637 - Addition of a closure to a )

{ . fire penetration through a seismic block wall in the Auxiliary '

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

) 3.. Plant Modification Request'900681 - Rework of a leaking check l valve, AE-V-121, in the Main Feedwater System. ' W e PMR was i- evaluated, and it was determined that no unreviewed safety or envirormental questions are generated as a result of this change.

4. Plant Modification Request #00606 - Upgrade of fusing protection at containment electrical penetrations. We PMR was evaluated and it was determined that no unreviewed safety or enviro:nnental-2 questions are generated by this' change provided the modification

.was completed prior to Mode 4 operation.

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5. Plant Modification Request #00743 - Change the storage location 1 of the reactor vessel O-rings to the top of the pressurizer enclosure and change the storage location of the reactor cavity seal ring lifting fixture to the bottm of the fuel pool. No I unreviewed safety ot enviromental questions are generated as a  ;

result of this change.

6. Plant Modification Hequest #00808 - Modify the Power Opera'.ed Relief Valves, BB-PCV 455A ard 456A, to increase the clearances between the plugs and cages of the valves. We IHR was evaluated, and it was determined that no unreviewed safety or enviromental questions are generated as a result of this change, provided the modification was cmpleted prior to Mode 3 operation.

7. Plant Modification Request #00823 - Change cable termination points to support reactor trip signal P-4 interlock logic. We IHR was evaluated and .it was determined that no unreviewed safety or enviromental questions are generated as a result of this change, provided the modification is empleted prior to Mode 2 operation.

8. Plant Modification Request #00816 - Addition of seal table drains to prevent drainage onto the thimble guide tubing. No unreviewed safety or enviromental questions are generated as a result of this change.

9. Plant Modification Request #00798 - Replacement of instrument air / backup nitrogen system brass tee with a type 316 stainless tee on a valve in the Auxiliary Feedwater System. No unreviewed safety or enviromental questions are generated as a result of this change.

10. Plant M3dification Request #00654 - Seal floor penetrations in Spent Resin Sluice Pmp Ibm of the Radwaste Building to prevent possible spread of contanination in accordance with AIARA program. No unreviewed safety or enviromental questions are generated as a result of this change.

11. Plant Modification Request #00646 - Relocation of ralicactive waste compactor frm the Containment Building to the Radwaste Building. No unreviewed safety or environmental questions are generated as a result of this change.

12. Temporary Modification #85-204-EC - Installation of flush adaptors on fuel pool cooling valves EC-V037, EC-V043, and EC-V104 to allow draining of demineralized water frm the spent fuel pool. m is temporary modification was reviewed and it was determined that no unreviewed safety or environmental questions are generated as a result of this change, provided the flush adapters are removed prior to the first refueling outage.

13. Temporary Procedure Change Form #MA 85-798 to SU8-BB13, Rev. 0 -

" Reactor Vessel Invel Indication System". - Written to allow for the collection of a3ditional data with different combinations of Reactor Coolant Peps running. No unreviewed safety or environmental questions are generated as a result of this change.

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14. Temporary Procedure G ange form #MA 85-894 to SU8-BB13, Rev. 0 -

" Pressurizer Relief Valve Test" - Written to allow test instrunentation change from digital thermaneter to a surface pyroneter. W is test instrument will be used for trending purposes only. No unreviewed safety or environmental questions are generated as a result of this change.

15. Temporary Procedure Gange Ebrm #MA 85-878 to SU8-BB13, Rev. O,

," Pressurizer Relief Valve Test" - Written to allow testiry to be performed at a lower temperature. W e lower Reactor Coolant System temperature will not affect the test results. No unreviewed safety or environmental questions are generated as a result of this change.

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OPERATING DATA REPORT DOCKEf NO. SIN 50/482 WOLF CREEK GENERATING STATION KANSAS GAS AND ELECTRIC COMPANY DATE 5-01-85 COMPLUTED BY M. Williams TELEPHONE 316-364-8831 OPERATING STATUS

1. Reporting Period: April, 1985 Gross Hours in Reporting Period: 719

2. Currently Authorized Power tevel(MWt): 170 Max. Deperx3. Capacity (MWe-Net) : 0 Design Electrical Rating (MWe-Net): 1186

3. Power Ievel to Which Restricted (If Any) (Mwe-Net): 0

4. Reasons for restriction (If Any): 5% License Issued

'1his Month Yr to Date Ctznulative

5. Number of Hours Reactor was Critical 0.0 0.0 0.0

6. Reactor Reserve Shutdown Hours 0.0 0.0 0.0

7. Hours Generator on Line 0.0 0.0 0.0

8. Unit Reserve Shutdown Hours 0.0 0.0 0.0

9. Gross Thermal Energy Generated (MWH) 0.0 0.0 0.0

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10. Gross Electrical Energy Generated (MWH) 0.0 _ 0.0 -

0.0

11. Net Electrical Energy Generated (MWH) 0.0 0.0 0.0

12. Reactor Service Factor N/A

13. Reactor Availability Factor N/A

14. Unit Service Factor N/A

15. Unit Availability Factor N/A

16. Unit Capacity Factor (Using MDC) N/A

17. Unit Capacity Factor (Using Design MWe) N/A

18. Unit Forced Outage Rate N/A

19. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of eadi): None

20. If Shut Down at End of Report Period, Estimated Date of Startup: N/A

21. Units in test Status (Prior to Connercial Operation): Forecast Achieved Initial Criticality 5-22-85 Initial Electricity 6-11-85 Coninercial Operation 8-10-85 Page 4 of 8

l DOCKET NO. STN 50/482 WOLF CREEK GENERATING SfATION KANSAS GAS AND ELECTRIC COMPANY DATE 5-01-85 COMPIRFED BY M. Williams TELEPHONE 316-364-8831 MONIH April, 1985 DAY AVERAGE DAILY FOWER LEVFL DAY AVERAGE DAILY FOWER LEVEL (We-Net) (MWe-Net) f l' 0 17 0

, 2- -

0 18 0 3 0 19 0 ___

4 0 20 0 5 0 21 0 1

] 7 0 23 0

} 8 0 24 0 9 0 25 0

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i 10 0 26 'O

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11 0 27 ~~ ~ ~ ~'~ ~ ~ 0'~~

j 12 0 28 0 13 0 29 0 14 0 30 0 15 0 31 N/A 16 0 On this form, list the average daily unit power level in Me-Net for each day in the reporting month. Campute to the nearest whole megawatt.

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

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UNIT SHUIDOWN AND POWER REDUCTIONS DOCKE7f NO. STN 50/482 _

WOLF CREEK GEN 8 HATING STATION KANSAS GAS AND ELECTRIC COMPANY DATE 5-01-85 O')MPIETED BY M. Williams REPORP M0tml April, 1985 TELEPHONE 316-364-8831 MEmiODS TYPE SHUITING DOWN

! F: EORCED' DURATION REASON 'IHE REACIOR OR CORPSCTIVE ACTIONS /

No Date S _: SCHEDULED (HOURS) (1) REDUCING IOWER (2) COPMENIS 4

I SLNMARY:

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Fuel Ioad and '55 power license issued 3-11-85. Fuel loading has been'canpleted.

Startup testirv3 is in progress.

l (1) REASON: (2) METfHOD:

A: EQUIPMENT FAILURE (EXPIAIN) 1. MANUAL ,

B: MAINTENANCE OR TEST 2. MANUAL SCRAM  !

C: REFUELING 3. AUIOMATIC SCRAM D: REGUIA'IORY RESTRICTION 4. OIEER (EXPIAIN)

E: OPERNIOR TRAINING AND LICENSE EXAMINATION )

F:. ADMINISTRATIVE G: OPERATIONAL ERROR (EXPIAIN)

H: OIHER (EXPIAIN) l l

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, KANSAS GAS AND ELECTRIC COMPANY I

WOLF CREEK GENERATING STATION UNIT NO. 1 '

r MONIH April SUlHARY OF OPERATING EXPERIENCE Listed below in chronological sequence is a sunnary of operating experiences for this month which required. load, reductio _ n or resulted in _signifi_ cant pon-load related , , _

4 incidents.

IRTE TIME EVENT April 1, 1985 1445 Received engineering evaluation on

! pressurizer heatup rate. Exited Technical Specification Action Statement 3.4.9.2.

April 6, 1985 2400 Plant connencing preparations for full flow l rod drop testing.

) April 7, 1985 1038 Received Control Room ventilation Isolation

} Signal (CRVIS) along with Fuel Buildirg t

Ventilation Isolation Signal (FBVIS) due to personnel. error. Reportable per 10 CFR 50.72 and 10 CFR 50.73.

,' 1133 Reset from CRVIS and FBVIS.

! April 8, 1985 0849 Received CRVIS due to radiation monitor not .

l being placed in bypass prior to commencement of surveillance activity. Reportable per 10 j CFR 50.72 and 10 CFR 50.73.'

0923 Reset fran CRVIS.

April 9, 1985 1409 Received Contairnent Purge Isolation Signal 1

(CPIS) and CRVIS due to a mechanical problem. Reportable per 10 CFR 50.72 and 10 j CFR 50.73.

1503 Reset from CPIS and CRVIS.

r April 12, 1985 1114 Received CPIS, FBVIS, and CRVIS. Reportable j -per 10 CFR 50.72 and 10 CFR 50.73.

. 1245 Determined CPIS, FBVIS and CRVIS was due to -

120v distribution panel feeder breaker ground fault.

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DATE TIME ' ' EVENP i

1855 Reset frm FBVIS and CRVIS.

Peceived CRVIS due to spurious trip of a 2215 i chlorine monitor. Reportable per 10 CFR 50.72 and 10 CFR 50.73.

2227 Reset frm CRVIS.

April 17, 1985 0753 Plant entered Mode 4.

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April 19, 1985- 1619 Received inadvertent Safety Injection Signal (SIS) due to personnel error during surveillance testing. Reportable per 10 CFR

_ _ 50.72 and_10 CFR 50.73.

1811 Reset from SIS in accordance with approved plant procedures.

April 21, 1985 1922 Received CRVIS due to a chlorine monitor running out of paper. Reportable per 10 CFR 50.72 and 10 CFR 50.73.

2008 Reset from CRVIS.

April 26, 1985 1854 Received Auxiliary Feed Actuation Signal

! (AFAS) due to a personnel error. Reportable  !

t per 10 CFR 50.72 and 10 CFR 50.73.

! 1953 Reset fran AFAS.

2239 Plant entered Mode 3.

April 28, 1985 1550 Received SIS due to a valid steamline low pressure signal resulting from a personnel-error. Reportable per 10 CFR 50.72 and 10 CFR 50.73. Declared an Unusual Event and termination of an Unusual Event.in accordance with Bnergency Plan Implenenting Procedures

, (EPP's) .

April 29, 1985 0153 Received Main Feedwater Isolation Signal due to a valid High Ievel Signal in Steam Generator "C", resulting from a personnel error. Reportable per 10 CFR 50.72 and 10 CFR 50.73.

April 30, 1985 1148 Received SIS due to low steamline pressure.

'Ihe signal was the result of hand held radio trarsnissions. Reportable per 10 CFR 50.72 and 10 CFR 50.73. Declared an Unusual Event 1- and termination of an Unusual Event in-accordance with Bnergency Plan Implementing Procedures (EPP's) .

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KANSAS GAS AND ELECTRIC COMPANY THE ELECTFkC COMPANY

@LENN L MOESTER wata possicant muctaan May 13, 1985 103 COPi Director, Office of Resource Managementk U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Mr. R.P. Denise, Director Wolf Creek Task Force U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 KMLNRC 85-111 Re: Docket No. STN 50-482 Subj: April, 1985 Monthly Operating Report Gentlemen:

Enclosed is the April,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 you have any questions concerning this matter, please contact me or Mr. Otto Maynard of my staff.

Yours very truly, GLK:bb Enc.  !

xc:PO'Connor (2) , w/a JTaylor (12) , w/a

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JCummins, w/a J

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9 201 N. Market -Wichita, Kansas - mar Address: PO. Box 208 i Nchita. Kansas 67201 - Telephone: Area Code (316) 261-6451 1