Text

Monthly Operating Repts for Sept 1978
	ML20064C177
Person / Time
Site:	Point Beach
Issue date:	10/05/1978
From:	; WISCONSIN ELECTRIC POWER CO.
To:	;
Shared Package
ML20064C175	List: ML20064C171; ML20064C177;
References
	NUDOCS 7810170173
	Download: ML20064C177 (9)
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C3 OPERATING DATA REPORT .

] DOCKET NO. 50-301 -

C) DATE october 5, 1978 d COMPLETED BY WISCONSIN ELECTRIC POWER CO'.

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OPERATING STATUS TELEPHONE

1. UNIT tJAME: POINT BEACH NUCLEAR PLANT UNIT 2 .. NOTES

2. REPORTING PERIOD: SEPTEMBER 1978 . .. .

3. LICENSED THERMAL POWEh (MWT): 1518,. .. .

4. tJAMEPL ATE R ATING (Gh0SS MWE): 523.8 . . .

5. DESIGil ELECTRIC AL R ATItJG (ilET MhE): 497. . . .

6. MAXIMUM DEFENDABLE CAPACITY (GROSS MWE): 5,19. , , , , , , .

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

8. IF CHANGES OCCUR IN CAPACITN RATINGS (ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORTr GIVE REASONS:

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

10. REASOr15 FOR RESTRICTIONS, (IF ANY): NOT APPLTCABLF THIS MONTH YR TO D' ATE CLMULATIVE 1 1',. HO U R S IN REPOPTING PERIOD . . . .. 720 6 r 551,' 54,048

13. NtlMEER OF HObRS REACTOR WAS CRITICAL 720.0 Sr922.1 48r887.1 1i. REArTO6 pkSFRVF SHbTCOWN HObRS 0.0 6.6 147.8 l ii. Hnt ip t GrNFP'ATOR ON LIrlE 720.0 5,855'.9 47e810.8 i-(. ttliT i PFctEVF SHL)TDOWN hot;RS .

0.0 0'. 0 85.9 1 ei . GROCC THEE f.'tL Ft4ERGY GENER ATED (MWH) 1r059e006 Br441r489 63,026e451 17, GR055 ELFCTRICAL EtJERGY GENFR ATED (MWH) 366e520 2e921,150 21e354e860

18. NET ELECTRICAL ENERGY GENERATED (MWH) 349r769, 2e787e960 20e296e762 10 UtlIT SERVICE FACTOR 100.0 89.4 88.5

10,. UtlIT AVAILABILITY FACTOR. 100.0 89.4 88.6

21. UNIT CAPACITY FACTOR (USING MDC NET) 98.1 86 0 76.8

32. UNIT CAPACITY FACTOR (USING DER NET) 97.7 85.6 75.6

23. UtJIT FORCED OUTAGE RATE , . 0.0 . .

0.5 1.8

24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPEr DATER AND DURATION OF EACH):

Refueling maintenance shutdown scheduled for March 9, 1979, to last approximately five weeks.

25'. IF SHUTDOWN AT END OF RFPORT PERIODr FSTIMATFD DATF OF STAP1 iip: NOT SHbTOOWN DATA RFPORTFD AND FArinkC C IClLAikn At IFQlIFc1kD itl f lRi' IkiiiP CATkD N P7hMHFP 2pr 1977

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00CKET NO. ,50-301 -

UNIT NAME Point Beach Unit 2 ~. ,

DATE October 5, 1978

. COMPLETED BY Wisconsin Electric Power Cd TELEPHONE AVERAGE DAILY UNIT POWER LEVEL MONTH September, 1978 AVERAGE AVERAGE AVERAGE '

DAILY DAILY DAILY l POWER LEVEL POWER LEVEL POWER LEVEL l DAY MWe NET -

DAY MWe NET DAY MWe NET 1 490 11 495 21 492 2 497 12 492 22 492 3 478 13 494 23 495 ll 411 14 492 24 497 i

, 5 473 15 486 25 495 6 500 16 472 26 497 7 501 17 438 -

27 497 8 499 18 458 28 489 9 495 19 487 29 497 10 471 20 495 30 499 31 ---

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NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE DOCKET NO. 50-266 UNIT NAME Point Beach Unit 1 DATE October 5, 1978 COMPLETED BY Wisconsin Electric Power Company Unit 1 was base loaded until September 20, 1978, when the unit was taken off line because of "A" steam generator primary-to-secondary leakage. The sixth annual refueling outage scheduled to begin September 29, 1978, was rescheduled to commence with the unexpected shutdown. Core stretch operation had commenced September 14, 1978.

At about 0030 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months on September 20, 1978, indication of a steam generator primary-to-secondary leak was observed

,- on the condenser priming air ejector radiation monitor. At f

0315 hours0.00365 days 0.0875 hours 5.208333e-4 weeks 1.198575e-4 months the leak was determined to be approximately 116 gallons per day in the "A" steam generator. Leakage increased to 200 gallons per day by 0410 hours0.00475 days 0.114 hours 6.779101e-4 weeks 1.56005e-4 months at which time shutdown of the unit was begun. Before the unit was taken off line at 0903 hours0.0105 days 0.251 hours 0.00149 weeks 3.435915e-4 months , September 20, 1978, the leak had increased to 560 gallons per day. Licensee Event Report No. 78-014/OlT-0 provided a description of this. event.

Hydrostatic leak testing of the steam generators revealed two leaking tubes (R23C32 and R23C34) and one leaking explosive tube plug (R21C36) in the "A" steam generator inlet side.

Eddy current testing showed the leaking tubes to have through-wall defects six to eight inches from the tube end and inside the tubesheet.

After completion of the refueling steam generator tube eddy current testing program, the following tubes were explosively plugged in the "A" steam generator:

Row Column Defect l

23 32 Leaking tube, 100% defect six inches from tube end, inle~t side 23 34 Leaking tube, 100% defect eight inches from tube end, inlet side 26 36 83% defect five inches from tube end, inlet side 26 38 80% defect eight inches from tube end, inlet side 25 40 94% defect six inches from tube end, inlet side l

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Row Column Defect 27 47 75% defect 19 inches from tube end, inlet side .,

1 8 Tube would not pass 0.650 inch probe The leaking explosive tube plug at R21C36 in the "A" steam generator inlet side was weld repaired using an auto-matic welding machine.

The following tubes were explosively plugged in the "B" steam generator:

Row Column Defect 45 41 85% defect at the first support, inlet side ,

p~ 22 38 76% defect five inches from the tube end, inlet side 21 36 90% defect 12 to 19 inches from tube end, inlet side 31 41 61% defect seven to nine inches from tube end, inlet side Radiation levels on the primary side of the steam generators were unexpectedly high (up to 45 R/ hour) upon initial opening, but decayed significantly (to the 25 R/ hour range) over the following five days.

End-of-life reactor physics testing was completed in the afternoon of September 20, 1978. Final burnup was 9302 megawatt-days per metric ton.

The "B" reactor coolant pump motor w's a removed and the seals were disassembled for inspection. The No. 1 seal insert and the No. 3 seal will be replaced although the general condition of the seals was very good considering approximately two and one-half years of use. The motor was disassembled for cleaning and inspection.

Other refueling outage work completed or in progress at the end of the period included reactor vessel head stripping, inservice inspection, charging pump pulsation dampener installation, condenser tube eddy current testing, high pressure turbine extraction piping modification,

~ moisture separator reheater cladding repair, and disassembly of turbine stop valves.

No other major safety-related maintenance was performed during the period.

- ____________________._________________________o

x , 4 OPERAT~ING DATA REPORT DOCKET NO. 50-266 -

DATE october 5, 1978 COMPLETED BY WISCONSIN ELECTRIC PObER CO'.

TELEPHONE OPERATING STATUS , ,

1. UNIT NAME: POINT. BEACH N CLEAR FL' ANT ONIT 1 . NOTES - .

2. PEPORTING PERIOD: SEPTEMBER 1978 ,

3. LICENSED THERMAL POWER (MWT): 1518. . .

4. NAMEPLATE RATING (GROSS MSE): 523.8 .

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

6. MAXIMUM DEPEtiDABLE CAPACITY (GROSS MWE): 519. . , , , . , , , , , .

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

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

NOT APPLICABLE O. POWER LEVEL TO hHICH RESTRICTED, IF ANY (NET MWE): NOT APPLICABLE

10. REASONS FOR RESTRICTIONSr (IF ANY): NOT APPLICABLE -

THIS MONTH YR TO D TE CUMLLATiVE ,,

it'. HOURS IN REPORTING PERIOD. . . 720. 6,551, 69r263 1!,. NUMBER OF HOURS REACTOR WAS CRITICAL 470.3 6,107,.6 57e992.7 13,. REACTOR.RFSERVE SHUTDOhN HOURS 0.0 2,. 6 439.6 14 HOUPS GENFRATOR ON 1.INE 465.1 6,004.0 56,071.8 1 G,. I'rJTT AESERVF SHUTDOhN HOURS 0.0 2.1 .

383.0

16. GkOc5 THFPMAL ENFRGY GENERATED (MWH) 693r385 Br875p951 78,653,976 t i. rpecc rI FCTPICAL Fi!FRGY GENFRATED (MWH) 235,500 3,038,400 26,497e000 I6. t'FT FI F rTRIC AL FUFRGY GENER ATED (MWH) 224,411 2,905r569 25,245,725 1 0,. I 'tJ T T SFRVICF FACTOR 64.6 91,.7 81.0 21 INIT AVAILABILITY FACTOR 64.6 91 7 81.5

21. UNIT CAPACITY FACTOR (bSING MDC NET) 63.0 89.6 75.1 3/ UtlIT CAPACITY FACTOR (USING DER NET) 62 7 89.2 73.3

31. Ur!IT FCRCED OUTAGE RATE . . .. . 11.9 . 2.4 3.1

!4. SHUTDObt!S SCHEDULED OVER NEXT 6 MONTHS (TYPEr DATER AND DUPATION OF EACH):

ilONE 2 5'. IF SHUTDOWN AT END OF REPORT PERIODr ESTiMdTED D' ATE OF STARTUP: O'CTOBER 17, 1978 D AT A AFPODirO ann F ACTO 9(- rALClt.MiFO Ac P'rQlFciin iht NRi' l 'FTi'rP PAiFr c'P1'rMRrR F 22r th77

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OCKET NO. 50-266 ;

UNIT NAME Point Beach Unit 1 -

DATE October 5, 1978 COMPLETED BY Wisconsin Electric Power Co.

TELEPHONE AVERAGE DAILY UNIT POWER LEVEL MONTH September, 1978 AVERAGE AVERAGE AVERAGE I

DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL DAY MWe NET DAY MWe NET DAY MWe NET 1 487 11 488 21 -

4 2 489 12 488 22 -

3 3 473 13 487 23 -

2 4 489 14 486 24 - -

2 5 490 15 - 487 25 -

1 6 493 16 487 26 -

1 7 492 17 484 27 -

1 8 491 18 482 28 -

1 9 487 19 479 29 -

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10 488 20 123 30 -

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s UNIT SIIUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-266 UNIT NAME Point Beach Unit:l-September, 1978 DATE October 5, 1978 REPORT MONTli COMPLETED BY Wis. Elec. Pwr. Co.

TELEPIIONE ci "u

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!Nu em sn ao No. Date g gg y jjg Licensee Event gg o'g Cause and Corrective Action E-. o ::: o u .c Report No. us so To Prevent Recurrence O~ M o U) c o E 3 o O

8 092078 F 62.9 A 1 78-014/0lT-0 CB IITEXCil Unit shutdown for repair beca,use of increasing steam generator primary-to-secondary leakage.

8 092078 S 192.0 C 1 78-014/01T-0 CB llTEXCil The unit's annual refueling outage-had been scheduled for 9-28-78.

The refueling work was rescheduled to commence immediately.following the unexpected shutdown. Forced shutdown hours reflect extension of scheduled refueling time due to steam generator leakage.

l 1 3 F: Forced Reason: Method: Exhibit G-Instruc-S: Scheduled A- Equipment Failure (explain) 1- 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) '

E- Operator Training & License Exam ,

(NUREG-0161).

F- Administrative b AD-28B Exhibit I- Same G- Operational Error (explain) Source (01-78) 11- Other (explain) .

I l

NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE DOCKET NO. 50-301 i UNIT NAME Point Beach Unit 2' ' '

q

DATE October 5, 1978 COMPLETED BY Wisconsin Electric Power Company -' -

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Unit 2 was based loaded for approximately 92% of the period with 13 load reductions. Power Supply requested on 12 occasions that load be reduced to an average of 375 MWe net for an average duration of four and one-half hours each.

Load was reduced to 165 MWe net for about one hour on September 28, 1978, in order to avoid an automatic unit

( trip from the overtemperature AT trip instrumentation (DNB protection) when a partial depressurization of the reactor coolant system occurred. The problem was traced to a defective electrical-to-air signal (I/P) converter in the controls of an air-operated pressurizer spray valve (431B) which caused the valve to remain partially open despite a full shut signal.A cuick personnel entry into the containment to fail the air to the valve succeeded in closing the valve and prevented a reactor trip. The event was described in Licensee

. Report 78-010/01T-0.

The unit generated its 21 billionth kilowatthour of electricity at 9:55 p.m., September 1, 1978.

A 30-day reportable event (Licensee Event Report No.

78-009/03L-0) occurred on September 13, 1978, when two of the three Unit 2 charging pumps were isolated for brief periods of time on two occasions because of relief valve leakage. Technical Specifications require that two charging pumps be operable under normal conditions, but permit plant operation with just one charging pump for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

The "B" reactor coolant pump continued to experience brief periods of intermittent seal flow problems.

No other major safety-related maintenance was performed during the period.

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ML20064C177

Text

SUMMARY

SUMMARY

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