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Monthly Operating Repts for Oct 1990 for Point Beach Nuclear Plant Units 1 & 2
	ML20058G805
Person / Time
Site:	Point Beach
Issue date:	10/31/1990
From:	Fay C, Jack J; WISCONSIN ELECTRIC POWER CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	CON-NRC-90-114 VYNPD-90-463, NUDOCS 9011130406
	Download: ML20058G805 (9)
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A Wisconsin Electnc.

POWER COMPANY 231 W MicNgtn PO Box 2M6. Mhookne.W 53201 1414) 221-2X6 VPNPD-90-4M %.3 NRC-90-114

. November 9,.1990 l

l U.:S. NUCLEAR REGULATORY COMMISSION ]

l Document Control Desk: ;

L Mail'. Station F1-137 )

Washington, D. C. 20555 '

Gentlemen:

DOCKETS'50-266 AND 50-301-

MONTHLY OPERATING REPORTS POINT BEACH NUCL. EAR PLANT, UNITS 1 AND 2 I

1.ttached are monthly operating reports for Units 1 and 2, Foint-Beach-Nuclear. Plant ~, for the calendar month of October l

,1990.

Very truly;yours,

. s (W g

'C..W. Fay' i Vice President-Nuclear Power 1

.' Attachments 1

.Copics to R. S. Cullen, PSCW i NRC. Regional Administrator, Region III l

NRC Resident Inspector i l

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POllTr BEACH NUCLEAR plint:. DOCKET NO. 50-266' UNIT NAME Point Beach. IJnit 1

' AVERAGE DAILY UNIT POWER LEVEL MONTH OCTOBER

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DATE Nod.- 8.1990 '

COMPLETED BY J. W. Jack TELEPHONE 414n55-2321 AVERAGE AVERAGE

AVERAGE DAILY DAILY ' DAILY .

POWER LEVEL POWER LEVEL

. POWER LEVEL MWe NET

-DAY MWe NET DAY DAY MWe NET -

490 21 428 1 488 -11 490 22 490 2 489 12 491 23 491 3 490 13 490 24 492 4 492 14 490 25 489 5 493 15 491 26 495 6 494 16 491 27 490 7 492 17 491 28 483 8 492 18 491 29 492 9 493 19 30 491 20 491 0 489 31 492 PDF-0028a (03-90)

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m ~ POINT BEACH NUCLEAR PLANT . Docket No. :-50-266

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l. Unit Name - Point Beach! Unit l

- UNIT SHUTDOWNS AND POWER REDUCTIONS Date Nostmber 8.1990

Completed By J. W. Jack REPORT MONTH OCTOBER ' Telephone No.

414n55-2321 l- . . .

j Method of -

l . i Shut'% _

L No. Date Type': Duration ' Reason,' ~'Down- Licensee Event System . Cbeponent Cause and Corrective Action Glours) Reactor' ' Reoort No. ' Code' Code' To Prevent Recurrence l

'F: Fceced ' Reason- .

.' Method: ' Exhibit G - Instructions S: Scheuuled A - Equipment Failure (explain) 1 - Manual fx preparation of B - Maintenance er Testing 2 - Manual Scram data entry sheets C - Refueling. . 3 - Automatic Scram LER file (NUREG-0161)

~ D - Regulatory Restriction 4 - Continuation of

-E - Opera:or Training & - Previous Shutdown Licensing Exam 5 - Reduced Imad

' F - Administrative . ..

6 - Other (explain) ' Exhibit I - Same Source G - Operational Error (explain)

II - Other (explain)

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4 DOCKET NO. 50-266 -

UNIT NAME . Point Beach Unit 1 DATE November 8,1990 COMPLETED BY J. W. Jack TELEPHONE _ 414n55 2321 L

1.

Unit 1 operated 4 approximately 491 MWe net throughout this report period with no significant load reductions of greater than 20 percent.

I The following reportable event occurred during this report period.

On October 12, 1990, an engineering evaluation discovered a potential single failure condition j resulting from inadequate train separation in cable raceways. It was postulated that a single event could cause grounds or cable-to-cable short circuits in the control power circuits to bus tie breakers B03 D01 and B04 B02 which may cause the bruikers to shut inadvertently, if the i breakers shut, both diesel generators could be overloaded and fail (LER 266-90-912).

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OPERATING DATA' REPORT- ; / * -

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DOCKET'WO. 50-301 ,

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DATE- -November.8, 1990 COMPLETED BY' J. W. Jack; TELEPHONE 414/755-2321 OPERATING STATUS

1. UNIT NAME: POINT BEACH NUCLEAR PLANT UNIT 2. . NOTES .

2.: REPORTING: PERIOD: OCTOBER 1990- . .

3. LICENSED-THERMAL POWER (MWT): . 1518.5! . .

4.' NAMEPLATE RATING (GROSS MWE): 523.8- .- ..

-5. DESIGN ELECTRICAL RATING (NET MWE):- 497. . .

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE):-.509. . .

7. MAXIMUM DEPENDABLE CAPACITY (NET MWE): 485. - . . .. . . .. . . . . . . . . . . . . . . . . .

8. IF CHANGES OCCUR.IN CAPACITY RATINGS'(ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONS:

-NOT APPLICABLE..

9. POWER LEVEL'TO WHICH' RESTRICTED, IF ANY,(NET MWE): NOT APPLICABLE

10. REASONS FOR RESTRICTIONS, (IF ANY): -NOT APPLICABLE-

'THIS MONTH YR'TO DATEJ CUMULATIVE

11. HOURS IN REPORTING PERIOD 745 '7,296- 15?,985

12. n.2ER OF HOURS REACTOR WAS CRITICAL 123.8 6,674.8 140,020.5

13. REACTOR RESERVE SHUTDOWN HOURS O.0 0.0 - 216.7

14. HOURS GENERATOR ON LINE 121.6 6,672.6 137,877.8

' 15 . UNIT RESERVE SHUTDOWN HOURS- 0.0 0.0 302.2

16. GROSS THERMAL ENERGY GENERATED (MWH) 162,384 10,051,644 196,635,180

17. GROSS ELECTRICAL' ENERGY GENERATED (MWH) '55,330 3,445,240 66,770,460

18. NET ELECTRICAL ENERGY GENERATED (MWH) 50,587 3,292,576 63,631,186

19. UNIT SERVICE' FACTOR 16.3 91.5 86.2

20. UNIT AVAILABILITY' FACTOR :16.3 91.5 86.4

21. UNIT CAPACITY FACTOR (U3ING MDC NET) 14.0 93.0 81.3

22. UNIT CAPACITY FACTOR.(USING DER NET) 13.7 90.8 80.0

23. UNIT FORCED OUTAGE RATE 0.0 0.0 1.1

24. SHUTDOWNS SCHEDULED.OVER-'NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):

NONE

25. IF SHUTDOWN AT'END OF REPORT PERIOD,' ESTIMATED DATE OF STARTUP: November 10, 1990

' DATA REPORTED AND FACTORS - CALCULATED AS REQUESTED IN NRC Lt:;ma DATED SEPTEMBER 2' ', 1977'

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POthT BEACH NUCLEAR FIANT DOCKET NO 50-301 AVERAGE DAILY USTT FOWEk IIVEL TINIT NAME Point Beacit Unit 2 MONTH OCTOBER DATE November 8.1990 COMPLETED BY J. W. Jad TELEPHONE 414M55-2321 AVERAGE AVERAGE AVE 3tAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWERiEVEL DAY MWe NET DAY MWe NET DAY MWe NET 1 451 11 -2 21 -2 2 450 12 -2 22 -2 3 448 13 -2 23 -2 4 448 14 -2 24 -1 5 394 15 -2 25 -2 6 -13 16 -2 26 -2 7 -14 17 . -2 27 -2 8 -9 18 -2 28 -2 9 -5 19 -2 29 -2 4

10 -2 20 -2 30 -2 31 -2 PBre

( 3 90)

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POINT BEACH NUCLEAR PLO.T' Docket No. 50-301 Unit Name Point Beacit Unit 2 *-

UNIT SHUTDOWNS AND POWER REDUCTMyG Date November 8_1940 - <--

Completed By J. W. Jack ~

REPORT MONTH OCTOBER Telephone No. 414/755-2321

, Method of ShuttmE No. Date Type' Deretson Rea d Down Ixensee Eveet Syseem Oceponest Cause and Correctree Actice Giosus) Rd Renart Na Onde* Q:de8 To Psevent h

! 2 901006 S 623.4 C 1 N/A ZZ 777717 4 Annual refueing med temmeenmace outage.

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'F: Forced ' Reason: ' Method: ' Exhibit G - Instructions S: Scheduled A - Equipment Failure (explain) 1 - Manual for preparatior: of B - Maintenance or Testing 2 - Manual Scram data entry sheets C - Refueling 3- AutomaticScram LER file (NUREG-0161)

D - Regulatory Restriction 4 - Continuation of ,

E - Operator Training & Previous Shutdc=n i f_W=g Dam 5 - Reduced Imd

, F- Administrative 6 - Other (explain) M I - Same Soerzee G - Operational Error (explain)

H - Other (explain)

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1 1 .e s DOCKET NO. 50-301 UNIT NAME Point Beach Unit 2 !

DATE November 8,1990 l

COMPLETE 9 BY J. W. Jack TELEPilONE 414/755 2321 Unit 2 began this report period in end of life stretch operation at approximately 450 MWe net. Power was l being reduced as the Tref program limit was lowered to comperaate for fuel burnup. The Unit 2 Refueling 16 l outage legan by taking the unit off line on October 6,1990 at 0135 hours0.00156 days 0.0375 hours 2.232143e-4 weeks 5.13675e-5 months CDT, and then shutting down the reactor at 03$1 hours.

The following reportable events occurred during this report periocl.

On October 9,1990 at 1345 hours0.0156 days 0.374 hours 0.00222 weeks 5.117725e-4 months CDT, an automatic start occurred on auxiliary feal pump P38A. Due to maintenance, a low low signal was krked in to the steam generator level logic l relays. The resultant start signal to the auxiliary feed pumps was blocked by having the main feed pump control switches in pullout. As part of a hydrostatic test procalure, one of the main feed pumps was started. This action unblocked the automatic start signal and started i P38A (LER 30190-002).

l On October 23,1990, midy current testing was completed on the Unit 2 steam generator tubes.

Based on the results of the eddy current testing,50 tubes were plugged in steam generator

)

'A.' and (>7 were plugged in steam generator 'B' (LER 301 90-003).

On October 31,1990 at 1130 hours0.0131 days 0.314 hours 0.00187 weeks 4.29965e-4 months CDT, Unit 2 experienced an inadvertent actuation of an engineered safety feature. Valve 2MOV 2907 (service water supply to containment fan coolers) opened due to a signal from relay 2SI 13X. The cause for this relay generating the signal is still under investigation (LER 30190-004). !

l Safety related maintenance completed during this period consisted of oddy current testing on various heat exchangers and removal of control power fuses to breakers B03-B01 and B04 B02.

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ML20058G805

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