ML20077F359

Monthly Operating Repts for Nov 1994 for Point Beach Nuclear Plant

ML20077F359
Person / Time
Site:	Point Beach
Issue date:	11/30/1994
From:	Koudelka M, Maxfield G WISCONSIN ELECTRIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
PBL-94-0344, PBL-94-344, NUDOCS 9412140044
Download: ML20077F359 (9)

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' Electnc POWER COMPANY Point Beach Nuclear Plant 6610 Nuclear Rd.. Two Ruers, WI 54241 (414) 755-2321 PBL 94-0344 December 6, 1994 Document Control Desk U. S. NUCLEAR REGULATORY COMMISSION Mail Station F1-137 Washington, DC 20555 Gentlement DOCKETS 50-266 AND 50-301 MONTHLY 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, 1994.

Sincerely, G.

J.

field PBNP Manager dje Attachments cc L. L. Smith, PSCW NRC Regional Administrator, Region III NRC Resident Inspector V

140012 9412140044 941130 PDR ADOCK 05000266 1h R

PDR a suwwwutsmauwwca;waam qg

OPERATING DATA REPORT DOCKET NO. 50-266 s

3 DATE:

12/06/94 COMPLETED BY:

LI.

B. Koudelka TELEPHONE:

414 755-6480 OPERATING STATUS

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

. NOTES

(

2. REPORTING PERIOD: November - 1994

3. LICENSED THERMM, POWER (MWT) :

1518.5 4.

NAMEPLATE RATING (GROSS MWE) :

523.8

5. DESIGN ELECTRICAL RATING (NET MWE):

497.0

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE) :

509.0.

7. MAXItCJM DEPENDABLE CAPACITY (NET MWE):

485.0 8.

IF CHANGES OCCUR IN CAPACITY RATINGS (I'fEMS 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONS:

NA 9.

POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWE) : NA l

10. REASONS FOR RESTRICTIONS, (IF ANY) :

NA THIS MONTH YEAR TO DATE CUMULATIVE i

11. HOURS IN REPORTING PERIOD 720.0 8,016.0 210,984.0

12. NUMBER OF HOURS REACIOR WAS CRITICAL 720.0 7,390.6 176,109.5

13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 667.3

14. HOURS GENERATOR ON LINE 720.0 7,342.1 172,982.3

15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 846.9

16. GROSS THERMAL ENERGY GENERATED (MWH) 1,093,320 10,966,795 244,448,565

17. GROSS ELECTRICAL ENERGY GEIERATED 371,560 3,712,760 82,566,890

18. NET ELECTRICAL ENERGY GENERATED (MWH) 355,510 3,508,907 78,704,497

19. UNIT SERVICE FACTOR 100.0%

91.6%

82.0%

20. UNIT AVAILABILITY FACTOR 100.01 91.6%-

82.4%

21. UNIT CAPACITY FACTOR (USING MDC NET) 101.8%

91.3%

76.6%

22. UNIT CAPACITY FACTOR (USING DER NET) 99.3%

89.1%

75.1%

23. UNIT FORCED OUTAGE RATE O.Ot 0.O%

1.5%

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

Refueling, 03/11/95, 39 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 o

POINT BEACH NUCLEAR PLANT -

Docket No.

50-266 Unit Name Point Beach, Unit 1 UNrr SlitTrDOWNS AND POWER REDUCTIONS Date December 6.1994 Completed By-M. B. Koudelka REPORT MONTH NOVEMBER - 1994 Telephone No.

414n55-6480 Method of Shumng 4-Darmten Down Licensee Event System Component Cause arki Conective Action No.

Date Type' 01ours)

Reason

• Reactora Report No Code

• Code' To Prevent Recurrence 1

NA NA NA NA NA NA NA NA NA NA i

t

'F: Forced 2 Reason:

' Method:

' Exhibit G - Instructions S: 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)

' Exhibit 1 - Same Source G - Operational Error (explain)

H - Other (explain)

PBF-CD28b (03-50)

POINT BEACH NUCLEAR PLANT DOCKET NO.

50-266 AVERAGE DAILY UNIT POWER LEVEL UNIT NAME Point Beach, Unit 1 MONTH NOVEMBER -

1994 DATE December 6,1994 COMPLETED BY M. B. Koudeika i

TELEPHONE (414)755-6480 AVERAGE AVERAGE AVERAGE I

DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL DAY MWe NET DAY MWe NET DAY MWe NET 1

494 11 494 21 494 2

494 12 494 22 493 3

494 13 495 23 493 4

494 14 494 24 494 5

494 15 493 25 493 6

495 16 494 26 497 L

7 496 17 494 27 490 8

493 18 494 28 493 9

494 19 494 29 493 10 494 20 494 30 492 M

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n

DOCKET NO.

50-266 UNIT NAME Point Beach Unit 1 DATE December 6, 1994 COMPLETED BY M.

B. Koudelka TELEPHONE 414/755-6480 Unit 1 operated at an average of 494 MWe net for the report period.

Licensee Event Report 50-266/94-011-00, Redundant Decay Heat Removal Requirements Not Met During Refueling Shutdown, was submitted.

Safety-related maintenance included:

1.

AF-51 P38B auxiliary feedwater pump suction header drain valve inspection and cleaning.

2.

AF-4009-0 and AF-4016-0 P38A&B auxiliary feedwater suction from service water operator 4-rotor limit switch and thermal overload installations.

i 3.

AF-4020-M, AF-4022-M and AF-4023-M P38A auxiliary feedwater pump discharge to 1&2HX-1A&B steam generator motor relay replacements.

4.

1B52-22B spare breaker pole piece replacement.

5.

1DY-02 Blue 125 Vdc/120 Vac inverter pilot light and relay replacements.

6.

FC-189B T6B boric acid tank nitrogen level flow controller rotometer inspection and cleaning.

7.

G05 combustion turbine wattmeter and ammeter connection in CO2 main control board.

8.

1MS-5916 P29 turbine-driven auxiliary feedwater pump turbine casing pressure sentinel lockwire installation from nozzle and guide ring set screws to the valve bonnet arms.

9.

P15 spare safety injection pump motor oil was changed.

10.

SW-114 and SW-136 1&2P29 turbine-driven auxiliary feedwater pump backup suction / supply line vent pipe nipple and plug installation.

11.

SW-122 and SU-131 P38A&B auxiliary feedwater pump backup supply line vent pipe nipple and plug installation.

12.

VA-8 2HX-8B boric acid evaporator valve diaphragm replacement.

OPERATING DATA REPORT DOCKET NO. 50-301 DATE:

12/06/94 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 - 1994 3.

LICENSED THERMAL POWER (MWT) :

1518.5

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 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

11. HOURS IN REPORTING PERIOD 720.0 8,916.0 195,769.0

12. NUMBER OF HOURS REACTOR WAS CRITICAL 720.0 7,107.0 171,307.6

13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 233.9

14. HOURS GENERATOR ON LINE 698.5 7,084.0 168,950.7

15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 302.2

16. GROSS THERMAL ENERGY GENERATED (MWH) 906,928 10,495,321 242,866,505 1~.

GROSS ELECTRICAL ENERGY GENERATED 306,480 3,549,640 82,573,900

18. NET ELECTRICAL ENERGY GENERATED (MWH) 290,909 3,388,824 78,719,464

19. UNIT SERVICE FACTOR 97.0%

88.4%

86.3%

20. UNIT AVAILABILITY FACTOR 97.0%

88.4%

86.5%

21. UNIT CAPACITY FACTOR (USING MDC NET) 83.3%

87.2%

82.3%

22. UNIT CAPACITY FAC'IVR (USING DER NET) 81.3%

85.1%

80.9%

23. UNIT FORCED OUTAGE RATE 0.0%

0.0%

1.0%

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:

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

4 POINT BEACll NUCLEAR PLANT Decket No.

50-301 Unit Name Point Beach, Unit 2 UNTT S11tTFDOWNS AND POWER REDUCTIONS Date December 6.1994 Completed By M. B Koudelka REPORT MONTil NOVEMBER - 1994 Telephone No.

414/755-6480 Method of Shutting Duration Down Licensee Event Sy: tem Component Cause and Corrective Action No.

Date Type' (llours)

Reason" Report No.

Code' Code' To Prevent Recurrence Reactnri 2

9/24 94 5

21.5 C

1 NA NA NA Scheduled refueling and maintenance outage (U2R20). Major work items include amptector upgrades. RIIR pump rotor replacement,4* tor limit switch upgrades, main feedwater check valve replacements, reactor heat shield, SI-854A&B internals replacement, Gai-tronics upgrade.

G04 emergency diesel generator tie-in work, reactor coolant pump seal water flow transrmtter replacement, safeguards sequence timing relay replacements, control red drive mechamsm control current timing modification, degraded grid voltage relay work, steam generator blowdown heat exchanger replacement, and containment service water pipe supports as part of continued Bulletin 79-14 upgrades.

4

'F: Forced 2 Reason:

' Method:

' Exhibit G - Instructions S: 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 l

Licensing Exam 5 - Reduced bad l

F - Administrative 6 - Other (explain)

' Exhibit I - Same Source G - Operational Error (explain) 11 - Other (explain) i s

PBF4028b (0340)

4 a

POINT BEACH NUCLEAR PLANT DOCKET NO.

50-301 AVERAGE DAILY UNIT POWER LEVEL UNIT NAME Point Beach, Unit 2 I

MONTH NOVEMBER -

1994 DATE December 6,1994 COMPLETED BY M. B. Koudelka TELEPHONE (4141755-6480 AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL DAY MWe NET DAY MWe NET DAY MWe NET 1

-10 11 439 21 460 2

64 12 439 22 457 i

3 186 13 440 23 459 4

315 14 440 24 460 5

297 15 443 25 459 a

6 413 16 443 26 459 7

418 17 443 27 460 I

8 420 18 451 28 475 9

423 19 461 29 454 10 428 20 459 30 467 f

1 N'

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7

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DOCKET NO.

50-301

-UNIT NAME Point Beach Unit 2 DATE December 6, 1994 COMPLETED BY M.

B. Koudelka TELEPHONE 414/755-6480 Unit 2 was shutdown for a refueling and maintenance outage since September 24, 1994.

The unit went online on November 1, 1994.

Safety-related maintenance included:

1.

2B52-406D breaker overload block replacement.

2.

Differential pressure transmitters were installed across 2FT-2896, 2FT-2898, 2FT-2900 and 2FT-2902.

3.

2HS-601R-93 and 2HS 601R-95B pressurizer safety valve discharge line snubber rebuilts.

4, 2P2A charging pump seals, stuffing box, and oil gauge replacements.

5.

2P29 turbine-driven auxiliary feedwater pump oil sample was drawn.

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