Text

Monthly Operating Repts for Mar 1983
	ML20073F269
Person / Time
Site:	Point Beach
Issue date:	04/08/1983
From:	Fay C; WISCONSIN ELECTRIC POWER CO.
To:	;
Shared Package
ML20073F245	List: ML20073F235; ML20073F269;
References
	NUDOCS 8304150459
	Download: ML20073F269 (9)
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OPERATING DATA REPORT DOCKET NO. 50-266 x.*

o DATE April 8, 1983 un COMPLETED BY C. W. FAY OPERATING STATUS

1. UNIT NAME: POINT BEACH NUCLEAR PLANT UNIT 1

. NOTES

2. REPORTING PERIOD:

MARCH 1983

3. LICENSED THERMAL POWER (MUT): 1518.

4. NAMEPLATE RATING (GROSS MWE):

523.8

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

6. MAXIMUM DEPENDABLE CAPACITY (6ROSS MWE): 519.

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

8. IF CHAN6ES OCCUR IN CAPACITY RATINGS (ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONS:

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

390.0

10. REASONS FOR RESTRICTIONS, (IF ANY):

Power level restricted because of self-imposed hot leg limitation in attempt to limit steam generator tube corrosion.

THIS MONTH YR TO DATE CUMULATIVE

11. HOURS IN REPORTIN6 PERIOD 744 2,160 108,696

12. NUMBER OF HOURS REACTOR WAS CRITICAL 695.6 2,111.6 89,683.9

13. REACTOR RESERVE SHUTDOWN HOURS 1.4 1.4 625.4

14. HOURS 6ENERATOR ON LINE 688.9 2,104.9 87,213.2

15. UNIT RESERVE SHUTDOUN HOURS 0.0 0.0 793.5

16. GROSS THERMAL ENER6Y GENERATED (MUH) 799,717 2,447,805 118,394,794

17. 6ROSS ELECTRICAL ENERGY 6ENERATED (MWH) 267,020 814,740 39,690,530

18. NET ELECTRICAL ENER6Y 6ENERATED (MWH) 252,276 771,956 37,753,674

19. UNIT SERVICE FACTOR 92.6 97.4 80.2

20. UNIT AVAILABILITY FACTOR 92.6 97.4 81.0

21. UNIT CAPACITY FACTOR (USING MBC NET) 68.5 72.2 71.1

22. UNIT CAPACITY FACTOR (USING DER NET) 68.2 71.9 49.9

23. UNIT FORCED DUTA6E RATE 0.7 0.2 2.8

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

Twenty-six week refueling and steam generator replacement outage scheduled to commence September 30, 1983.

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

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-266 UNIT NAME Point Beach Unit 1 DATE April 8, 1983 REPORT MONTH March, 1983 COMPLETED BY C.

W.

Fay TELEPHONE 414/277-2811

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Date g

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g'g Cause and Corrective Action e

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v4 Report No.

m eo To Prevent Recurrence Qw N

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830308 F

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3 N/A IE 1ELAYX Spurious turbine trip caused by contractor inadvertently bumping main steam stop valve relay during NRC-mandated fire system backfit.

2 830319 S

50.2 F

1 N/A ZZ ZZZZZZ Shutdown as a conservative measure to perform maintenance on purge supply valve to diminish contain-ment air leakage.

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F: Forced Reason:

Method:

Exhibit G-Instruc-j S: Scheduled A-Equipment Failure (explain) 1-Manual tions for Prepar-B-Maintenance or Test 2-Manual Scram ation of Data Entry

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C-Refueling 3-Automatic Scram Sheets for LER File D-Regulatory Restriction 4-Other (explain)

(NUREG-0161) l E-Operator Training & License Exam F-Administrative 5 Exhibit I-Same 1

AD-28B G-Operational Error (explain)

Source (01-78)

H-Other (explain)

DOCKET NO.

50-266 UNIT NAME Point Beach Unit 1 DATE April 8, 1983 COMPLETED BY C.

W.

Fay TELEPHONE 414/277-2811 AVERAGE DAILY UNIT POWER LEVEL MONTH March, 1983 AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL DAY MWe NET D_A Y MWe NET DAY MWe NET 1

37 3 11 372 21 190 2

373 12 372 22 371 3

372 13 371 23 372 4

372 14 371 24 373 5

372 15 372 25 373 6

346 16 371 26 372 7

355 17 373 27 373 8

260 18 373 28 372 9

371 19 72 29 371 10 372 20

-9 30 370 31 373 i

i AD-28A (1-77) j

NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE l

Docket No.

50-266 l

Unit Name Point Beach Unit 1 l

Date April 8, 1983 Completed By C.

W. Fay l

Phone 414/277-2811 Unit 1 operated at approximately 371 MWe net throughout the period with two brief outages.

On March 8, 1983, at 1136 hours0.0131 days 0.316 hours 0.00188 weeks 4.32248e-4 months , contractor personnel inadver-tently bumped the "B" train main steam stop valve relay while working on control panel IC02, sending a spurious trip signal to the Unit 1 turbine.

The relay was reset and at 1633 hours0.0189 days 0.454 hours 0.0027 weeks 6.213565e-4 months the generator was phased back on line.

Although this event is not considered LER reportable, the NRC was notified via the red phone.

Reactor coolant sampling, as required per the Confirmatory Order for Unit 1 following power trancients >15%/ hour, resulted in iodine levels ranging from 1.02 to 1.43 pCi/cc.

These results are reportable (those >1.0 pCi/cc) in a letter to the NRC.

This was done on a 30-day basis.

On March 19, 1983, it was discovered that air leakage through i

the containment purge supply valve when totaled with leakage through other penetrations and containment isolation valves was approaching Technical Specification limits.

An orderly shutdown was planned to perform maintenance to the containment purge supply valve and the turbine was taken off line at 0632 hours0.00731 days 0.176 hours 0.00104 weeks 2.40476e-4 months .

During the outage, maintenance was also performed on the switchyard motor-operated disconnect BS-2, reactor coolant hot leg bypass valve IRC-514B,

and a body-to-bonnet leak on an unused hot leg safety injection check valve.

Heatup of the primary system commenced and the reactor was taken critical at 0407 hours0.00471 days 0.113 hours 6.729497e-4 weeks 1.548635e-4 months on March 21, 1983 and the generator phased on line at 0846 hours0.00979 days 0.235 hours 0.0014 weeks 3.21903e-4 months .

Unit 1 returned to full power at the hot leg temperature restriction at 1430 hours0.0166 days 0.397 hours 0.00236 weeks 5.44115e-4 months on March 21, 1983 and remained at that level until the end of the reporting period.

The primary-to-secondary leakage remains stable at less than 10 gallons per day.

On March 9, 1983, emergency Diesel generator 3D failed to start while attempting to perform surveillance testing required by Technical Specification 15.4.6.A.l.

Upon investigation, the fuel rack was found to be in the low fuel position.

The fuel injector lever was exercised by hand and a start and test run was conducted satisfactorily.

Start failure was attributed to the engine governor not returning to its normal start position after the completion of the shutdown signal timing sequence from l

the previous test run of March 2, 1983.

This Woodward type UG8 l

governor was manually returned to its normal start position and l

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-l a special maintenance procedure was effected to ensure the governor returned to its normal start position until the governor is replaced.

j The redundant emergency diesel was operable during this reportable event, and LER 83-003/01T-0 was sent to the NRC Region III office.

On March 27, 1983, at approximately 2000 hours0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months , an upward l

trend was observed on the plant vent radiation gas monitor R14.

1 The source of the release was discovered to be loose allen screws

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which secure the process check valve assembly to the K10B cryogenic gas compressor.

The' screws were tightened and the release halted.

The NRC region office was notified via the red phone and the Resident i

Inspector was notified.

This event was not considered LER reportable.

Other safety-related maintenance completed during the period

{

included seal replacement on the vacuum pump for radiation monitors j

Rll and R12, the periodic inspection of diesel fire pump P35B, i

the replacement of 1P29 auxiliary feed pump discharge check valve, j

and the replacement of "B" train reactor trip relay 1RT7.

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OPERATIN6 DATA REPORT DOCKET NO. 50-301 DATE April 8, 1983 COMPLETED BY C. U. FAY TELEPHONE 414 277 2811 OPERATING STATUS

1. UNIT NAME: POINT BEACH NUCLEAR PLANT UNIT 2

. NGTES

2. REPORTIN6 PERIOD:

MARCH 1983 I

3. LICENSED THERMAL POWER (MUT): 1518.

4. NAMEPLATE RATIN6 (6ROSS MWE):

523.8

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

l

6. MAXIMUM DEPENDABLE CAPACITY (6ROSS MUE): 519.

7. MAXIMUM CEPENDABLE CAPACITY (NET MUE): 495.

8. IF CHANGES OCCUR IN CAPACITY RATIN6S (ITEMS NUMBER 3 THROU6H 7) SINCE LAST REPORT, 6IVE REASONS:

1

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

~

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

11. HOURS IN REPORTIN6 PERIOD 744 2,160 93,481

12. NUMBER OF HOURS REACTOR WAS CRITICAL 587.6 2,003.6 84,061.7 I

13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 196.8 l

14. HOURS 6ENERATOR ON LINE 576.9 1,992.9 82,648.1

15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 181.2

16. 6ROSS THERMAL ENER6Y GENERATED (MWH) 869,556 3,007,255 114,522,849

17. 8ROSS ELECTRICAL ENER6Y GENERATED (MWH) 292,820 1,009,260 38,810,660

18. NET ELECTRICAL ENER6Y GENERATED (MWH) 278,817 965,028 34,953,995 1

19. UNIT SERVICE FACTOR 77.5 92.3 88.4

20. UNIT AVAILABILITY FACTOR 77.5 92.3 88.6 1

21. UNIT CAPACITY FACTOR (USING MBC NET) 75.7 90.3 80.4 j

22. UNIT CAPACITY FACTOR (USING DER NET) 75.4 89.9 79.5

23. UNIT FORCED OUTA6E RATE 0.0 0.0 1.5 I

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

NONE i

25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTINATED DATE OF STARTUP: JUNE 30, 1983 BATA REPORTED AND FACTORS CALCULATED AS REQUESTED IN NRC LETTER DATED SEPTEMBER 22, 1977

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-301 UNIT NAME Point Beach Unit 2 DATE April 8,

1983 REPORT MONTH March, 1983 COMPLETED BY C.

W.

Fay TELEPHONE 414/277-2811 l

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1 830325 S

156.4 C

1 N/A ZZ ZZZZZ:

Commenced 14-week refueling and steam generator sleeving outage.

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3 4

F: Forced Reason:

Method:

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

Source (01-78)

H-Other (explain)

DOCKET NOo 50-301 UNIT NAME Point Beach Unit 2 DATE April 8, 1983 COMPLETED BY C.

W.

Fay TELEPHONE 414/277-2811 AVERAGE DAILY UNIT POWER LEVEL MONTH March, 1983 AVERAGE AVERAGE AVERAGE DAILY DAILY DAT.LY POWER LEVEL POWER LEVEL POWER LEVEL DAY MWe NET DAY MWe NET DAY MWe NET 1

484 11 487 21 485 2

488 12 483 22 487 3

488 13 488 23 485 4

487 14 488 24 472 5

488 15 475 25

-11 6

490 16 472 26

-9 7

487 17 488 27

-6 8

489 18 488 28

-3 9

489 19 488 29

-3 10 490 20 486 30

-2 31

-2 AD-28A (1-77)

NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE Docket No.

50-301 Unit Name Point Beach Unit 2 Date April 8, 1983 Completed By C. W. Fay Phone 414/277-2811 Unit 2 operated at approximately 488 MWe net from the beginning of the period until March 24, 1983, when load was decreased to prepare for the planned 14-week refueling and sleeving outage.

The generator was taken off line at 0056 hours6.481481e-4 days 0.0156 hours 9.259259e-5 weeks 2.1308e-5 months on March 25, 1983.

Outage-related items completed during the period included sludge lancing of "A" and "B" steam generators, the s'; ripping of the reactor vessel head and the removal of "C" moisture separator reheater tube bundle for replacement.

On March 16, 1983, while completing Technical Specification testing, primary boric acid heat trace circuit 2P136 was discovered inoperable due to a faulty circuit controller.

Circuit 2P136 was one of two heat tracing circuits on the inlet to the emergency borate valve.

The controller was replaced, tested satisfactorily and returned to service at 1416 hours0.0164 days 0.393 hours 0.00234 weeks 5.38788e-4 months on March 18, 1983.

The circuit failure is the subject of LER 83-001/03L-0 submitted to the NRC regional office.

On March 29, 1983, at 1143 hours0.0132 days 0.318 hours 0.00189 weeks 4.349115e-4 months , Unit 2 containment was evacuated because of noble gas concentrations, as a precautionary measure.

The release resulted from an operation in which gas from the reactor head was vented to the containment atmosphere.

The release did not exceed Technical Specification limitations and was not considered reportable.

l

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ML20073F269

Text

SUMMARY

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