L-95-029, Monthly Operating Repts for Nov 1995 for Point Beach Nuclear Plant Units 1 & 2

Monthly Operating Repts for Nov 1995 for Point Beach Nuclear Plant Units 1 & 2

ML20095C156
Person / Time
Site:	Point Beach
Issue date:	11/30/1995
From:	Koudelka M, Maxfield G WISCONSIN ELECTRIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
PL-95-0296, PL-95-296, NUDOCS 9512110387
Download: ML20095C156 (10)

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' Wisconsin Electnc POWER COMPANY' Point Booch Nuclear Plant 6610NuclearRd TwoRhersWI54241 (414) 7 S 2321 1

Y PBL'95-0296 ,

December 6, 1995

-Document Control Desk '

U. S. NUCLEAR REGULATORY COMMISSION Mail Station P1-137 Washington, DC 20555 ,

Gentlemen t

DOCKETS 50-266 AND 50-301 HONTHLY OPERATING REPORTS POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 Attached are monthly operating reports for Units 1 and 2 of the Point Beach Nuclear Plant for the calendar month of November 1995. ,

Sincerely,

& I G. J. Maxf eld PBNP Manager amb.

Attachments l cca L. L. Smith, PSCW .

NRC Regional Administrator, Region III NRC Resident Inspector i

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Coyg 9512110387 951230 l PDR ADOCK 05000266 i

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pi A sa6sainty af Hhassin Ewigy Qvywatin '

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q OPERATING DATA REPORT

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L DOCKET NO. 50-266 -

i DATE: '12/06/95 '

COMPLETED BY: M. B. Koudelka--

TELEPHONE: 414 755-6480' OPERATING STATUS

1. UNIT MAME

POINT BEACH NUCLEAR PLANT - UNIT 1 . NOTES .,

2. REPORTING PERIOD: November - 1995 .

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3. LICENSED THERMAL POWER (MNT) : '2518.5 ..

4. NAMEPLATE RATING (GROSS MWE) : 523.8 .

5. DESIGN ELECTRICAL RATING (NET MWE) : 497.0 .

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE): 509.0 . ,

7. MAXIMUM DEPENDABLE CAPACITY (NET MWE): 485.0 . . . . . . . . . . . . . . . . . . t

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

9. POWER LEVEL TO WHICH RESTRICTED, IF-ANY (NET MWE): NA

10. REASONS FOR RESTRICTIONS, (IF ANY) :

-NA .

THIS MONTH YEAR TO DATE CUMULATIVE [

11. HOURS IN REPORTING PERIOD 720.0 8,016.0 219,744.0

12. NUMBER OF HOURS REACTOR WAS CRITICAL 720.0 7,070.8 183,910.4

13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 667.3

14. HOURS GENERATOR ON LINE 720.0 7,025.0 180,737.4  ;

15. UNIT RESERVE SHUTDOWN HOURS 0.0 'O.0 _.846.9  !

16. GROSS THERMAL ENERGY GENERATED (MWH) 1093320.0 10L41426.0 .256086423.0 'L

17. GROSS ELECTRICAL ENERGY GENERATED 372630.0 3582530.0 86521180.0 -4

18. NET ELECTRICAL ENERGY GENERATED (MWH) 356852.5 3423228.5 82483879.5

19. UNIT SERVICE FACTOR 100.0% 87.6% 82.2% '

20. UNIT AVAILABILITY FACTOR 100.0%- 87.6% 82.6%  !

21. UNIT CAPACITY FACTOR (USING MDC NET) 102.2% 88.1%- 77.1% i

22. UNIT CAPACITY FACTOR (USING DER NET) 99.7% 85.9% 75.5% i

23. UNIT FORCED OCTTAGE RATE 0.0% 0.0%' 1.5% I

24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH): i Refueling, 03/30/96, 34 days

25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

'NA DATA REPORTED AND FACTORS CALCULATED AS REQUESTED IN NRC LETTER DATED SEPTEMBER 22, 1977

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POINT BEACH NUCLEAR PLANT DOCKET NO. 50-266 * '

AVERAGE DAILY UNIT POWER LEVEL UINT NAME Point Beech, Unit 1 MONTH NOVEMBER - 1995 DATE December 6,1995 COMPLETED BY M. 6. Koudoka TELEPHONE 414-755-6480 i

AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL DAY MWe NET DAY MWe NET DAY MWe NET 1 496 11 497 21 494 2 496 12 496 .

22 499 3 496 13 494 23 492 4 495 14 495 24 495 5 496 15 496 25 496 6 497 16 496 26 496 7 497 17 495 27 496 8 497 18 494 28 495 9 496 19 495 29 495 10 497 20 496 30 495 v - _ . _ _ _ . , _ -ve- w. t- 3 s __ _ . _-_ m .- - .- r-. -W

POINT BEACH NUCLEAR PLANT Docket No. 50-266 ..

Unit Name - Point Beach. Unit 1 UNIT SHUrDOWNS AND POWER REDUCTIONS Date Dmour 6.1995 -

Cornpleted By _ M. B. Koudelka .

REPOU MGNTH NOVEMBER - 1995 Telephone No. 414n55-6480 ,

Method of Shutung No. Date Tyg e' Duration Reason' Down 1xensre Event System Component Cause and Comenvc Action NA NA' NA NA NA NA NA NA NA NA

'F: Forced 2 Reason: ' Method:

• Exhibit G - Instructions S: Scheduled A - Equipment Failure (explain) 1 - Manual for preparatum of B - Maintenance or Testing 2 - Manual Scram data entry sheets C - Refueling 3 - Automatic Scram D - Regulatory Restriction LER file (NUREG-0161) 4 - Continuation of E - Operator Trammg & Previous Shutdow11 Licensing Exam 5 - Reduced Imad F- Administrative 6 - Other (explain) 8 Exhibit I- Same Source G - Operational Error (explain)

H - Other (explain)

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PBF41028b

. (03-90)

i e e DOCKET NO.= 50-266  !'

U)iIT NAME Point Beach Unit 11 IndME'  : December 7, 1995 l COMPLETED'BY M.:B. Koudelka.

TELEPHONE' ~414/755-6480 Unit 1 operated at an average of'496;MWe: net for the report period.

l Safety-related maintenance: included:  ;

1. .1B52-13B' power to 1B313B-2B337B charging pump crosstie power ,

panel breaker overhaul.

' 2. 'FO-140 T173' emergency diesel generator fuel oil fill tank outlet isolation valve' body-to-bonnet. gasket replacement.

3. FO-151 T175A G0;/G02 emergency diesel generator fuel oil storage tank' inlet from T173 fuel oil fill tank body-to-bonnet gasket .

replacement.  !

4. P32C service water pump' packing adjustment..

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OPERATING DATA REPORT

. DOCKET NO. 50-301 .

DATE: 12/06/95

• COMPLETED BY: M. B. Koudelka ,

TELEPHONE: 414 755-6480 OPERATING STATUS

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

2. REPORTING PERIOD: November - 1996 .

3. LICENSED THERMAL POWER (MWT) : 1518.5 .

4. NAMEPLATE RATING (GROSS MUE) : 523.8 .

5. DESIGN ELECTRICAL RATING (NET MWE): 497.0 .

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE) : 509.0 . .

7. MAXIMUM DEPENDABLE CAPACITY (NET MWE): 485.0 . . . . . . . . . . . . . . . . . .

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

NA

9. POWER LEVEL 'IU WHICH RESTRICTED, IF ANY (NET MWE) : NA

10. REASONS FOR RESTRICTIONS, (IF ANY) :

NA THIS MONTH YEAR TO DATE CUMULATIVE

11. HOURS IN REPORTING PERIOD 720.0 8,016.0 204,529.0

12. NUMBER OF HOURS REACTOR WAS CRITICAL 0.0 6,551.9 178,603.5

13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 233.9

14. HOURS GENERATOR ON LINE 0.0 6,471.5 176,166.2

15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 302.2

16. GROSS THERMAL ENERGY GENERATED (MWH) 0.0 9662294.0 253644219.0

17. GROSS ELECTRICAL ENERGY GENERATED 0.0 3253280.0 86204390.0

18. NET ELECTRICAL ENERGY GENERATED (MWH) 0.0 3100508.5 82181023.5

19. UNIT SERVICE FACTOR 0.0% 80.7% 86.1%

20. UNIT AVAILABILITY FACTOR 0.0% 80.7% 86.3%

21. UNIT CAPACITY FACTOR (USING MDC NET) 0.0% 79.8% 82.3%

22. UNIT CAPACITY FACTOR (USING DER NET) 0.0% 77.8% 80.8%

23. UNIT FORCED OUTAGE RATE 0.0% 0.0% 0.9%

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:

12/03/95 DATA REPORTED AND FACTORS CALCULATED AS REQUESTED IN NRC LE m x DATED SEPTEMBER 22, 1977

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- POINT BEACH NUCLEAR PLANT Docket No.- 50-301

- Unit Nanae.- Peint M Unit 2 -

UNIT SHUIDOWNS AND POWER REDUC 110NS Deee r- "

6. 1995

• Conipleted By - M. B. twv ,..

REPORT MONTH NOVEMBER - 1995 Telephone No.' 414n55-6480 - .

Meemd of Samams Durumon po,, Laceasee Event Syseene Conspement - Casse and Conecave Acaion -

Me. Dese Type' ' Glours) - Reason' as Iteport No. Code

• Code' - To Psevent Rocariance 5 10/785 S 720 C I NA NA NA Schedmied refuehus and unumeenmace (U2R21). Major work itemas incInde sessme gamesmest addy :

corrent sessing and Plus-Point ===parma==: toric acid and sencest makeup thyw nummmmeur '

W: sad insenses limit casupuser W shield fuel suuster embe inside comeammment: Phase 3C of new essergency diesel gemernest tie-in work; seplace 2MS-2016

. sneem dump vehe: repiece HP serbine enhamet escesunder piping: modify W for 4s0 vek semeion - .-. degaded grid vossage ndays-bypass time delay seisys:iod coment catanet anchorage of 2C41: sembus of co-isoianom vehe 2sC-955:2A05 2/3 :

loss of vohnge logic: seisene upgrades for cosmponent

• waeer samall bore piping; usein -

• seesmi condenesse dump valve repincemeses, adan=an of test poimes in Unit 2 safegueses cucales:

and AIARA shoekhag for reactor coolant pump cabecles.

'F: Forced 2 Reason: ' Method:

• Exhibit G -Instructions S: Scheduled A - Equipment Failure (explain) 1 - Manual for preparanon of B - Maintenance or Testing 2 - Manual Scram data entry sheets C - Refueling 3 - Automauc Scram LER Tde (NUREG-0161)

D - Regulatory Restnction 4 - Continuation of.

, E - Operator Trammt & Previous Shutskmn Lacensing Exam 5 - Reduced Load F - Admmatrative 6 - Other (explain) . 'Exhibit I - Same Source PBF 6

' (03-90) -

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I POWT BEACH NUCLEAR PLANT DOCKET NO. 50-301 '*

I AVERAGE DAILY UNIT POWER LEVEL UNIT NAME Point Beach, Unit 2 l

l MONTH NOVEMBER - 1995 DATE ' December 6,1995 -

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COMPLETED BY M. B. Koudelke TELEPHONE 414-755-6480 ,

AVERAGE AVERAGE AVERAGE.

DAR.Y DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL DAY MWe NET DAY MWe NET DAY MWe NET 1 -2 11 -2 21 -2 2 -2 12 -2 22 -2 3 -2 13 -2 23 -2 4 -2 14 -2 24 -2 5 -2 15 -2 25 -2 6 -2 16 -2 26 -2 7 -2 17 -2 27 -3 8 -2 18 -2 28 -5 9 -2 19 -2 29 -12 10 -2 20 -2 30 -15

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DOCKET NO. .50-301' UNIT NAME Point Beach Unit 2 DATE December 7,>1995 COMPLETED BY M. B. Koudelka TELEPHONE- 414/755-6480 Unit 2 was in' refueling shutdown 21 during the report period.

Licensee Event Report 301/95-004-00, Inadvertent ESF Actuation as a Result of Improper Relay Alignment, was submitted.

. Licensee Event Report 301/95-005-00, Steam Generator Tube Degradation, was submitted.

Safety-related maintenance included:

1. Service water to engineered' safeguards piping HB-19 elbow ,

replacement.

2. 2C-1 and 2C-2 equipment and personnel access air lock seals and packings replacement.

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3. 2CC-17 T12 component cooling surge tank radiation controlled l

vent valve spring pressure and upper limit switch adjustment.

4. 2CC-719 containment equipment component cooling supply header outboard isolation valve packing adjustment.

5. 2CV-313A P1A&B reactor coolant pump No. 1 seal water return isolation valve stroke and spring pressure adjustment.

6. 2MS-265 HX-1A steam generator blowdown isolation valve replacement.

7, 2PIB-M reactor coolant pump motor oil lift strainer housing mounting holes repaired. l

8. 2P15A&B safety-injection pump oil indication sight glasses l installation and 2P15A control switch replacement.

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9. 2RC-570A R1. reactor vessel head vent solenoid valve position  ;

indicator adjustment.- l l

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-10, 2SI-V-08 Train A safety injection to R1 reactor vessel vent valve-packing replacement.

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11. 2SI-834C T34A&B safety injection accumulator nitrogen inlet  !

. isolation valve and test connection added for containment isolation valve' purposes. l P

12. 2SI-843A T34A safety injection accumulator local sample  !

valve replacement.  !

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