Text

Monthly Operating Repts for Jan 1982
	ML20040H444
Person / Time
Site:	Point Beach
Issue date:	02/09/1982
From:	Fay C; WISCONSIN ELECTRIC POWER CO.
To:	;
Shared Package
ML20040H436	List: ML20040H435; ML20040H444;
References
	NUDOCS 8202180260
	Download: ML20040H444 (9)
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DOCKET NO. 50-266 otD 00 gg DATE February 9, 1982.

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@@"o OPERATING STATUS zw

1. UNIT NAME: POINT BEACH NUCLEAR PLANT UNIT 1

. NOTES

2. REPORTING PERIOD:

JANUARY 1982 t

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3. LICENSED THERMAL POWER (MUT):

1518.

1

4. NAMEPLATE RATING (GROSS hue):

523.8

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

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MUE):

519.

7. MAXIMUM DEPENDABLE CAPACITf (NET MWE): 495.

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

NOT APPLICABLE

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9. POWER LEVEL TO UHICH RESTRICTED, IF ANY (NET MWE):

445.0

10. REASONS F2r. RESTRICTIONS. (IF ANY): Maximum dependabic capacity reduced becc.use of self-ir/ posed,

hot leg temperature limitation in an attempt to limit steam' generator tube corrosion.'

THIS MONTH YR TO DATE conUL4itVE

11. HOURS IN REPORTING PERIOD 744 744 98,520

12. NUMBER OF HOURS REACTOR UAS CRITICAL 739.1 739.1 81,092.3

13. REACTOR RESERVE SHUTDOWN HOURS C.7 0.7 608.0

14. HOURS GENERATOR ON LINE 731.2 731.2 78,703.4

15. UNIT RESERVE SHUTDOWN HOURS 1.9 1.?

766.2

16. GROSS THERMAL ENERGY GENERATED (MUH) 952,450 952,450 108.305,290

17. GROSS ELECTRICAL ENERGY GENERATED (hWH) 318,360 318,360 36,339,640

18. NET ELECTRICAL ENERGY GENERATED (MUH) 303,391 303,391 34,584,602

19. UNIT dERVICE FACTOR 98.3 98.3 79.9

20. UNIT AVAILABILITY FACTOR 98.5 98.5 80.7

21. UNIT CAPACITY FACTOR (USING hDC NET) 82.4 82.4 71.9

22. UNIT CAPACITY FACTOR (USING DEC NET) 82.0 82.0 70.6

23. UNIT FORCED OUTAGE RATE 1.7 1.7 3.0

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

NONE

25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: NOT SHUTD0VN DATA REPORTED AND FACTORS CALCULATED AS REGUESTED IN NRC LETTER DATED SEPTEMBER 22, 1977

OPERATING DATA REPORT DOCKET N0.'50-301 DATE February 9, 1982 COnPLETED BY.

C. U. FAY TELEPHONE 414 277 2811 OPERATING STATUS

1. UNIT NAME: POINT BEACH NUCLEAR PLANT UNIT 2

. NOTES

2. REPORTING PERIOD:

JANUARY 1982

3. LICENSED THERMAL POWER (MUT):

1518.

4. NAMEPLATE RATING (GROSS hWE):

523.8

5. DESIGN ELECTRICAL RATING (NET MWE):

497.

6. nAXInUM DEPENDABLE CAPACITY (GROSS MWE): 519.

7. MAXIMUK DEPENDABLE CAPACITY (NET MWE): 495.

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

NOT APPLICABLE

9. POWER LEVEL TO UHICH RESTRICTED, IF ANY (NET MUE): NOT APPLICAELE

10. REASONS FOR RESTRICTIONS, (IF ANY): NOT APPLICABLE THIS MONTH YR TO DATE CUMULATIVE

11. HOURS IN REPORTING PERIOD 744 744 83,305

12. NUMBER OF HOURS REACTOR WAS CRITICAL 744.0 744.0 75,134.4

13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 193.0

14. HOURS GENERATOR ON LINE 744.0 744.0 73,802.6

15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 178.0

16. GROSS THERMAL ENERGY GENERATED (MWH) 1,106,250 1,106,250 101,363,094

17. GROSS ELECTRICAL ENERGY. GENERATED (MWH) 373,250 373,250 34,396,260

13. NET ELECTRICAL ENERGY GENERATED (MWH) 357,293 357,293 32,740,759-

19. UNIT SERVICE FACTOR 100.0 100.0

'88.6

20. UNIT AVAILABILITY FACTOR 100.0 100.0 88.8

21. UNIT CAPACITY FACTOR (USING MDC NET) 97.0 97.0 80.0

22. UNIT CAPACITY FACTOR.(USING DER NET) 96.6 96.'

79.1

23. UNIT FORCED OUTAGE RATE 0.0 0.0 1.6

24. SHUTDOWNS SCHEDULED DVER NEXT 4 MONTHS (TYPE, DATE,-AND DURATION OF EACH): Refueling outage scheduled for April 16, 1982, expected to last 5 weeks.

25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: NOT SHUID0uN DATA REPORTED AND FACTORS CALCULATED AS REQUESTED IN.NRC LETTER DATED SEPTEMBER 22, 1977

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-266 UNIT NAME Point Beach Unit 1 REPORT MONTH January, 1982 COMPLETED y

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1 820111 F

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3 82-001/03L-0 IB HEATEI Due to a steam pressure sensing line freeze-up, a 2/3 coincidence signal caused a unit trip on a safety injection signal from a low steam line pressure indication.

3 F: Forced Reason:

Method:

Exhibit G-Isstruc-S: Scheduled A-Equipment Failure (explain) l-Manual tions for Prepar-B-Maintenance or Test 2-Manual Scram ation of Data. Entry C-Refueling 3-Automatic Scram Sheets for LER File D-Regulatory Restriction 4-Other (explain)

(NUREG-0161)

E-Operator Training & License Exam F-Administrative 5 Exhibit I~ Same AD-28B G-Operational Error (explain)

Source (01-78)

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DOCKET NO.

50-266 UNIT NAME Point Beach Unit 1 DATE February 9, 1982 COMPLETED BY C. W.

Fay TELEPHONE 414/277-2811 AVERAGE DAILY UNIT POWER LEVEL MONTH January, 1982 AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL DAY MWe NET DAY MWe NET DAY MWe NET 1

417 11 375 21 420 2

411 12 177 22 420 3

410 13 408 23 418 4

416 14 420 24 416 5

416 15 420 25 418 6

416 16 418 26 418 7

415 17 416 27 419 8

416 18 419 28 419 9

414 19 419 29 420 10 412 20 419 30 419 31 419 AD-28A (1-77)

1 DOCKET NO.

50-301 UNIT NAME Point Beach Unit 2 DATE February 9, 1982 COMPLETED BY C. W.

Fay TELEPHONE 414/277-2811 AVERAGE DAILY UNIT POWER LEVEL MONTH January, 1982 AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL DAY MWe NET DAY MWe NET DAY MWe NET 1

449 11 482 21 483 2

469 12 483 22 484 3

454 13 484 23 482 4

487 14 485 24 482 5

480 15 484 25 481 6

485 16 479 26 481 7

482 17 484 27 483 8

484 18 483 28 482 9

481 19 478 29 483 10 479 20 487 30 482 31 483 AD-28A (1-77)

n NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE Docket No.

50-266 Unit Name Point Beach Unit 1 Date February 9, 1982 Completed By C. W.

Fay Telephone 414/277-2811 Unit 1 operated at 427 MWe net throughout the period with one reactor trip.

At 2151 hours0.0249 days 0.598 hours 0.00356 weeks 8.184555e-4 months on 01/11/82, a reactor trip on a safety injection signal occurred due to a two out of three coincident low steam line pressure signal.

The low steam lin' pressure signal was generated from "A" steam generator pressure transmitters, IPT-469 and 482, when their sensing lines froze.

At no time during the transient did primary plant pressure dip to the point of requiring safety injection.

After the sensing lines were thawed and provisions taken to prevent future freezeup, the Unit 1 reactor was taken critical at 0242 hours0.0028 days 0.0672 hours 4.001323e-4 weeks 9.2081e-5 months and the generator was placed on line at 1940 hours0.0225 days 0.539 hours 0.00321 weeks 7.3817e-4 months on 01/12/81.

During the month of January, several instances of steam pressure detector sensing line freezeup occurred resulting in a reduction of redundancy below the Technical Specification limit in each case.

In one case, as previously mentioned, a reactor trip occurred due to the simultaneous loss of two channels of steam pressure.

The first event occurred at 0945 hours0.0109 days 0.263 hours 0.00156 weeks 3.595725e-4 months on 01/07/82.

The sensing line for 1PT-482 froze with an outside temperature of 6*F.

The in-strument channel was tripped to restore redundancy and returned to service after the line thawed at 1115 hours0.0129 days 0.31 hours 0.00184 weeks 4.242575e-4 months .

At 0555 hours0.00642 days 0.154 hours 9.176587e-4 weeks 2.111775e-4 months on 01/10/82, with outside temperatures at -23*F, the sensing line for 1PT-469 froze.

In order to keep the other two sensing lines from freezing, it was decided to establish continuous blowdown of the lines to maintain the sensing lines free of blockage.

Because of the possibility of spiking pressure below the safety function setpoint when cracking open the drains, the trips on channel 469 were removed after concurrent approval was granted by L

the Duty & Call Superintendent and the Duty Shift Supervisor.

The trips were removed by installing a temporary sensing line from radwaste steam to PT-469 and placing PT-469 on line.

After review by the Manager's Supervisory Staff, channel 469 during this short period (2.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ) with its trip removed was technically inoperable.

Once continuous blowdown was established on the other two steam pressure transmitters, PC-469 trips were replaced and the temporary sensing line isolated.

During the interim time until the normal sensing line of 1PT-469 thawed, an alternate sensing line was installed off of the 1PT-482 sensing line. a

- At 0027 hours3.125e-4 days 0.0075 hours 4.464286e-5 weeks 1.02735e-5 months on 01/11/82, the normal sensing line for 1PT-469 thawed.

The instrument lineup was quickly restored to normal and blowdown was established on all transmitter drains.

All of the occcurrences of steam line freezeup were reported as a 30-day report in accordance with Technical Specification 15.6.9.2.B.2 (Licensee Event Report No. 82-001/03L-0, Docket No. 50-266),

At approximately 1015 hours0.0117 days 0.282 hours 0.00168 weeks 3.862075e-4 months on 01/12/82, while at hot standby critical operation, one of the steam pressure transmitters on the Unit 1 "A" loop steam line was isolated by Maintenance personnel due to a sensing line steam leak.

Prior to isolating the pressure transmitter, Maintenance personnel notified the Duty Shift Super-visor of the leak, who in turn directed that the appropriate instrument channels be placed in the tripped condition.

Before the instrument channels were tripped, the leak became excessive and Maintenance personnel isolated the pressure transmitter for personnel and equipment safety.

The pressure transmitter was isolated for approximately two minutes before the pressure channel was placed in the tripped condition.

Upon isolation, the channel failed low due to depressurization through the leak.

Steam pressure falling to zero causes steam. flow to go to zero, which is the non-conservative direction for the steam flow / feed flow mismatch trip.

Loss of one channel of steam flow is a violation of the minimum redundancy requirement specified in Technical Specification Table 15.3.5-2, Item No. 12..This requirement calls for a minimum degree of redundancy of one which was violated for the short period noted.

This occurrence was reported in accordance with Technical Specification 15.6.9.2.B.2 as a 30-day report (Licensee Event Report No. 82-002/03L-0, Docket No. 50-266),

Safety-related maintenance for the period included modification to 3D and 4D emergency Diesel generator control circuits, installa-tion of seismic restriants, and TMI electrical equipment backfitting.

NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE Docket No.

50-266 Unit Name Point Beach Unit 2 Date February _9, 1982 Completed By C. W.

Fay Telephone 414/277-2811 i

i Unit 2 operated at 497 MWe net with no significant load re-ductions.

Safety-related maintenance for the period included replacement of the 2P4B boric acid transfer pump and replacement of failed reactor trip relay 2RT-5B (Westinghouse NBFD relay).

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ML20040H444

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SUMMARY

SUMMARY

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