ML20029D882

Monthly Operating Repts for Apr 1994 for Point Beach Nuclear Plant,Units 1 & 2.W/940504 Ltr

ML20029D882
Person / Time
Site:	Point Beach
Issue date:	04/30/1994
From:	Arnold R, Maxfield G WISCONSIN ELECTRIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
PBL-94-0140, PBL-94-140, NUDOCS 9405110346
Download: ML20029D882 (10)

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a Wisconsin 1 Bectnc POWER COMPANY Point Ekaoch Nuclear Plant 6610 Nucioor Pd . Two Rimra WI 54241 (414) 765 2321 PBL 94-0140 May 4, 1994 Document Control Desk U. S. NUCLEAR REGULATORY COMMISSION Mail Station P1-137 Washington, DC 20555 Gentlemen:

POCKETS 50-266 AND.50-3]ll ROtTIHLY ORERAENG REPORTE EQTET.. BEACH NUCLEAR _ELANT. 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 April, 1994.

Sincerely, G. J. xfield PBNP Manager GJM/rll ,

1 AttachrTento cc: L. L. Smith, PSCW NRC Regional Administrator, Region III NRC Resident Inspector i

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OPERATING DATA REPORT DOCKET NO. 50-266 .- 5 t

DATE: 05/02/94 COMPLETED BY: Richard F. Arnold '

TELEPHONE: (414) 755-6193 I OPERATING STATUS

'.. UNIT NAME: POINT BEACH NUCLEArt PLANT - UNIT 1 . . NOTES .

2. REPORTING PERIOD: April - 1994 .

3. LICENSED THERMAL POWER (MWT). 1518.5 .

4. NAMEPLATE RATING ~(GROSS MWE): 523.8 .  !

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

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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 TO WHICH RESTRICTED, IF.ANY (NET MWE) : NA

10. REASONS FOR RESTRICTIONS, (IF ANY):

NA THIS MONTH YEAR TO DATE CUMULATIVE

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l 11. HOURS IN REPORTING PERIOD 719.0 2,879.0 205,847.0

12. NUMBER OF HOURS REACTOR WAS CRITICAL 93.6 2,253.6 170,972.5

13. REACTOR RESERVE SHUTDOWN HOURS O.O O.0 667.3

14. HOURS GENERATOR ON LINE 4 9 . ~7 2,205.1 167,845.3

15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 846.9

'16. GROSS THERMAL ENERGY GENERATED (MWH) 42,165 3,260,009 236,741,779

17. . GROSS ELECTRICAL ENERGY GENERATED 12,570 1,102,090 79,956,220 18.' NET ELECTRICAL ENERGY GENERATED (MWH) 8,330 1,052,854 76,208,444 1 19. UNIT SERVICE FACTOR 6.9% 76.6% '81.5%

20. UNIT AVAILABILITY FACTOR 6.9% 76.6% 82.0% ~ j

21. UNIT CAPACITY FACTOR'(USING MDC NET) 2.4% 75.4% 76.0% ,

l 22. UNIT CAPACITY FACTOR ~(USING DER NET) 2.3% 73.6% .74.5% ~

! 23. UNIT FORCED OUTAGE RATE 0.0% 0.0% 1.6%

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

NONE

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

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

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OPERATING DATA REPORT DOCKET NO. 50-301 - .

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DATE: 05/02/94 COMPLETED BY: Richard F. Arnold 4

TELEPHONE: (414) 755-6193 OPERATING STATUS

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

2. REPORTING PERIOD: April - 1994 .

3. LICENSED THERMAL POWER (MWT): 1518.5 .

4. NAMEPLATE RATING (GROSS MWE): 523.8 .

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

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

7. MAXIMUM DEPENDABLE CAPACITY (NET MWE) - 485.0 , . . . . . . . . . . . .

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

NA

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 719.0 2,879.0 190,632.0

12. NUMBER OF HOURS REACIOR WAS CRITICAL 719.0 2,879.0 167,079.6

13. REACTOR RESERVE SHUTDOWN HOURS O.0 0.0 233.9

14. HOURS GENERATOR ON LINE 719.0 2,879.0 164,'745.7

15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 302.2

16. GROSS THERMAL ENERGY GENERATED (MWH) 1,082,174 4,303,795 236,674,979

17. GPOSS ELECTRICAL ENERGY GENERATED 363,320 1,465,780 80,490,040

18. NET ELECTRICAL ENERGY GENERATED (MWH) 347,330 1,403,401 76,734,041

19. UNIT SERVICE FACTOR 100.0% 100.0% 86.4%

20. UNIT-AVAILABILITY FACTOR 100.0% 100.0% 86.6%

21. UNIT CAPACITY FACTOR (USING MDC NET) 99.6% 100.5% 82.4%

22. UNIT CAPACITY FACTOR (USING DER NET) 97.2% 98.1% 81.0%

23. UNIT FORCED OUTAGE RATE 0.0% 0.0% 1.0%

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

Refueling Outage, 09/24/94, 36 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 i

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POINT BEACH NUCLEAR PLANT DOCKET NO. 50-301 AVERAGE DAILY UNTT POWER LEVEL UNIT NAME Point Beach. Unit 2 MONTH APRIL - 1994 DATE May 2.1994 COMPLETED BY R. F. Arnold-TELEPHONE 414/755-6193 AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL DAY POWER LEVEL MWe NET DAY MWe NET DAY MWe NET I 483 11 483 21 484 2 482 12 483 22 4S4 3 483 13 483 23 484 4 480 14 485 24 483 5 479 15 482 25 483 6 488 16 485 26 484 7 479 17 483 27 484 8 484 18 484 28 4 84 9 483 19 483 29 484 10 481 20 482 30 483 PBNJU28a (03-90)

POINT BEACH NUCLEAR PLANT Docket No. 50-301 Unit Name Point Beach. Unit 2 UNIT SIIUTDOWNS AND POWER REDUCTIONS Date Mm 2.1994 '

Completed By - R. F. Amold REPORT MONTil _ APRIL - 1994 Telephone No. 414/755-6193 Method of Shuttmg l Duration %n Licensee Event System Component Cause and Corrective Actkin No. Date Type' Ofours) Reason' Reacers Report No. Code' Code' To Prevent Recurrence NA NA NA NA NA NA NA NA NA NA

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

D - Regulatory Restriction 4 - Continuation of E - Operator Training & Previous Shutdown Licensing Exam 5 - Reduced Load F - Administrative 6 - Other (explain) 5 Exhibit I - Same Source G - Operational Error (explain)

- H - Other (explain) 6 PBF-0028b (03-90)

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DOCKET NO. 50-301 UNIT NAME Point' Beach Unit 2 y DATE. May 2, 1994 R

. COMPLETED BY R. F.' Arnold l

- TELEPHONE 414/755-6193 l

Unit 2 operated at an average of 483 MWe net for the report period with no significant load reductions.

J.Acensee Event Report 50-301/94-001-00, Potential Feedwater Flow Measurement Inaccuracies, was submitted.

Safety-related maintenance included:

1. Oil changed on residual heat removal. pumps P-10A and P-10B.

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7i POINT BEACll NUCLEAR PLANT DOCKET NO. 50-266

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AVERAGE DAILY UNIT POWER LEVEL UNIT NAME Point Beach. Unit 1 MONTil APRIL - 1994 DATE May 2.1994 COMPLETED BY R. F. Amo!d TELEPilONE 414/755-6193 AVERAGE AVERAGE AVERAL.

DAILY DAILY DAILY POWER LEVEL POWER LEVEL DAY POWER LEVEL MWe NET DAY MWe NET DAY MWe NET I 410 11 -2 21 -2 2 -4 12 -2 22 -2 3 -14 13 -2 23 -3 4 -7 14 -2 24 -7 5 -1 15 0 25 -12 6 -2 16 -4 26 -12 7 -2 17 -2 27 -12 8 -2 18 -2 28 -13 9 -2 19 -2 29 -14 10 -2 20 -2 30 67 PBF41028a (03-90)

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POINT BEACll NUCLEAR. PLANT Docket No. 50-266 Unit Name Point Beach. Unit I >

UNIT SHUrDOWNS AND POWER REDUCTIONS Date May 2.1994 Completed By R. F. Arnold REPORT MON ~III APRIL - 1994 Telephone No. 414 055-6193 Met *r.M cf Shumng Duranon 1xemee Event System  ;

Down Corrierent Cause ami Corrective Acnon No. Dare Type' (Hours) Reason' Rescerr Report No. Code' Code' To Prevent Recurrence 2 4/02i94 5 669 3 C 1 NA NA NA Schedaled refuelmg armi mamrenance cutage (UIR21). Major work items mclude reactor vesset head inspecaon. "A* steam generator loose parts inspecoon, steam generator shidge lancmg.

cavny cooler cleanseg. removal of the circurs for the LO-LO bonc ack! s:orage tank level safety injecten auto transfer to the refuelmg water storage tank. replacement of safeguards sequence nmeng relays, adjust time delays on degraded grid voltage relays, modified safety injection supports as part of continued Bulletm 79-14 upgrades, resurface turbme govemot valve sests, replace thirty-two safety-related molded case circun breakers, four roter limit switches installed a on thirteen valve motor cgrators, as-budt electncal walkdowns of 4160 VAC a.,d 480 VAC switch gear, aM as-built electncal tracing of reactor proteccon aM safeguards system.

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'F: Forced 2 Reason: 3 Method: ' Exhibit G - Instructions 5: Scheduled A - Equipment Failure (explain) 1 - Manual for preparation of B - Maintenance or Testing 2 - Manual Scram data entry sheets C - Refueling 3 - Automatic Scram LER file (NUREG-0161)

D - Regulatory Restriction 4 - Continuation of E - Operator Training & Previous Shutdown Licensing Exam 5 - Reduced lead F - Administrative 6 - Other (explain) 'Ethibit I - Same Source G - Operational Error (explain)

II - Other (explain)

PBF M Gb (03-90)

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DOCKET NO. 50-266 UNIT NAME Point Beach Unit 1 DATE May 2, 1994 COMPLETED BY R. F. Arnold TELEPHONE 414/755-6193 Unit 1 operated at an average of 11 MWe net for the report period. The Unit was shutdown for refueling and maintenance outage on April 2, 1994 and was placed back on line on -

April 30, 1994.

Safety-related maintenance included:

1. The supply and return lines.for the cavity coolers were

chemically cleaned.

2. Installed new fire breaks on eleven tray / floor electrical penetrations.

3. Replaced "A" and "B" reactor coolant pump seal water return low range flow transmitters.

4. Replaced main feedwater check valves CS-00466AA and CS-00476AA.

5. Replaced gasket on reactor coolant system pressurizer manway.

6. Repaired leakage on cavity cooling fan motor cooler HX-03094.

7. Replaced reactor coolant system hot leg sample isolation valve (SC-00955) regulator.

8. Loose torque switch setting screws were tightened after the motor for the operator of safety injection pump.P-15B suction valve operator tripped on thermal overload.

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9. Replaced eight safety-related 125 VAC AC voltage rated breakers supplying DC loads with properly rated breakers. "

10. Adjusted degraded grid voltage time delay relays on 4160 VAC buses A05 and A06.

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11.

Replaced Miller slide valve on purge supply fan discharge control valve VNPSE-03244.

12. Replaced the anti-rotation keys on valves SI-00878A, SI-00878B, SI-00878C, SI-00878D, RC-00596, and CC-00815.

13. Replaced auxiliary feedwater pump discharge relief valve SW-04389.

14. Replaced excess letdown heat exchanger (HX-4) shell side outlet relief valve CC-00768.

15. Flushed containment accident recirculation heat exchanger HX-015A3 because of 77% blockage in the return line.

16. Vibration detection accelerometers were installed on containment accident recirculation fans W-001A1, W-001B1, W-001C1 and W-001D1.

17. Replaced governor valve on turbine driven auxiliary feedwater pump P-29.

18. Replaced thirty-two molded case circuit breakers as part of the breaker upgrade program.

19. Replaceu une upper operating arms on steam header main steam stop valves MS-02017 and MS-02018.

20. Replaced valve internals for refueling water storage tank to residual heat removal pump P-10A header suction valves ,

SI-00854A and SI-00854B.

21. Installed four rotor limit switches on thirteen valve motor operators.

22. Replaced rotating assembly on residual heat removal pump P-10B.

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