ML19343A155

Monthly Operating Repts for Aug 1980

ML19343A155
Person / Time
Site:	Point Beach
Issue date:	09/04/1980
From:	Fay C WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML19343A154	List: ML19343A153 ML19343A155
References
NUDOCS 8009160304
Download: ML19343A155 (9)

Text

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4 p OPERATIl1G DATA REPORT

• DOCFET 110. 50-266 DATE September 4, 1980 COMPL ETED BY C. W. FAY TEi EPilO?iE

- 414 277 2811 OPERATIl4G STATUS QD e3 . . . . . . . . . . . . . . . . . . . . . . . .

O 1. UfJIT I4AME: POIllT I;EACil liUCLEAR PLAIJT Ui4IT 1 . IJOTES .

e 2. REPORTIl4G PERIOD AUGUST 1980 . .

N 3. LICEl4 SED TilERMAL PObER (MWT:: 1518. . .

C2 4. IJAMEPLATE RATIl1G (GROSS MhE): 523.8 . .

'C S. DESIGiJ ELECTRICAL RATI!1G (NET MhE): 497. . .

6. MAXIMUM DEPE!JDAULE CAPACITY (GROS 5 MWE): 519. . .

M 7. MAXIMUM DEPEtJDAGLE CAPACITY'(NET MWE): 495. . . . . . . . . . . . . . . . . . . . . . . . .T g d. IF CilAf4GES OCCUR Il4 CAPACITY RATIl4GS (ITEMS WUMiiER 3 TiiROUCil 7) SIl4CE LAST REPORTe GIVE REASOIJS: O IJOT api LICAULE 4 9. POhER LEVEL TO htlICli hESTRICTED, IF AIJY (llET MhE): 390.0 g

10. REASoi4S FOR RESTRICTIOl4Se (IF AIJY): SICnxAIxmGt4MittxMi Power restriction is the result of a self-imposed reduction in core aver age teinperature in an attempt to inhibit corrosion of steam generator tubes within the tubesheet crevice. Tills MolJTli YR TO DATE CUNULATIVE O lt. IIOURS Ili REPORTIi4G PERIOD 744 Seabb 86,087 M

12. IJUMBER OF llOURS REACTOR hAS CRITICAL S42.3 4,760.8 71,277.3 9

13. REACTOR RESERVE SiluTDOWlJ llOURS 0.4 19.5 601.7

14. iiOURS GEtJERATOR Oil LINE S36.9 4,610.2 69,004.2 M i

15. UlJIT RESERVE SliUTDOWii ilOURS

16. GROSS TlIERMAL ElJERGY LEhERATED (NWill 650,041 1.3 5e558e06o 152.8 7SS.2g $

96,310e861

17. GROSC ELECTRICAL El1ERGY GEi1ERATED (Mbil) 209e220 1,807,220 32e440,970 id. IJET ELECTRICAL ElJLhGY GE!JERATED (Mbil) 197,101 1e706,515 30,896,693

19. UlJIT SERVICE FACTOR 72.2 78.7 80.2

20. UllIT AVAILABILITY FACTOR 72.4 81.4 81.0

21. UllIT CAPACITY FACTOR (USIl4G MDC IJET ) 53.5 58.9 73.7 2J. Ul4IT CAPACITY FACTOR (USIlJG DER NET) 53.3 58.6 72.2

23. UllIT FORCED OUTAGE RATE 0.0 0.1 3.4

24. SiiUTDOhi45 SCliEDULED OVER (JEXT 6 MOf 4Tils (TYPEe DATE, AlJD DURATIOl1 OF EACil):

Unit scheduled to shutdown Novenber 7, 1980, for approximately one month for refueling.

25. IF SiiUTDObH AT EllD OF REPORT PERIODe ESTIMATED DATE OF STARTUP: IJOT SilUTDOWlJ DATA REPORTED AliD FACTORS CALCULATED AS REuUESTED I!J IiRC LETTER DATED SEPTEMBER 22, 1977

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OPERATIl1G DATA REPORT DOCMET 110. 50-301 "TEP (E__3 DATE september 4, 1980 gg COMPLETED BY C. W. FAY bb TELEPiiOt1E 414 277 2811 O OPERATIlJG STATUS

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1. UNIT IJAME: POINT DEACll NUCLEAR PLAIJT Ui1IT 2 . [10TES . 6d c3

2. REPORTIl1G PERIOD: AUGUST 1980 . .

3. LICEllSLD TiiERMAL POWER (MWT): 1518. . . N"'

4. IJAMEPLATE RATIi1G (GROSS MhE): 523.8 .

53ED S. DESIGil LLECTRICAL RATIllG (liET MhE); 497. . .

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6. MAXIMUN Dt.'ENDADLE CAPACITY (GROSb MhE): 519. . .

7. MAXIMUM DEPE4DAOLE CAPACITY (NET NhE): 495. . . . . . . . . . . . . . . . . . . . . . . . .

8. IF CilANGES OCCUR 114 CAPACITY RATIi4GS (ITEMS IJUNDER 3 TiiROUGil 7) SINCE LAST REPORTe GIVE REASOliS:

IJOT APPLICAULE

9. POWER LEVEL TO WNICil RESTRICTED, IF Ai1Y (IJET MhE): 140T APPLICAGLE

10. REAS0ils FOR HESTRICTIOl4Se (IF Ai4Y): NOT api >LICADLE TilIS MGNTli YR TO DATE CUMULATIVE li. IlOURS IN REPORTItJG PERIOD 744 5,855 70,872

12. NUMBER OF il0URS REACTOR WAS CRITICAL 744.0 4e754.9 63e651.8

13. REACTOR RESERVE SilVTD0hil il0URS 0.0 19.2 185.3

14. iiOURS GENERATOR ON LIllE 744.0 4,688.7 62,415.7 IS. UtJIT RESERVE SiiUTD0hl4 ilOURS 0.0 13.5 119.9

16. GROSS TilERMAL EijlRGY GEi4ERATED (MWil) 1,124,200 6,873,370 84,525,906

17. GROSS ELECTRICAL EtiERGY GEi4LRATED (MWill 376,080 2,298,650 28,659,990

18. 11ET ELECTRICAL El4ERGY GENERATED (MWill 358,959 2,188e746 27,263,873

19. UllIT SERVICE FACTOR 100.0 80.1 80.1

20. Ul41T AVAILADILITY FACTOR 100.0 80.3 88.2

21. Ul41T CAPACITY FACTOR (USIllG MDC NET) 97.5 75.5 78.4 2t. UlJIT CAPACITY FACTOR (USIl4G DER I4ET) 97.1 75.2 77.4

23. UNIT FORCED OUTAGE RATE 0.0 7.0 1.9

24. SilUTD0hNS SCilEDULED OVER NEXT 6 M0ilTil5 (TYPE, DATEe AND DURATIOiJ OF EACil):

ilOllE

25. IF SliUTD0hl4 AT EllD OF REPORT PERIODe ESTIMATED DATE OF STARTUP: 110T SiiUTDobii DATA REPORTED AND FACTORS CALCULATED AS REQUESTED 114IJRC LETTER DATED SEPTEMUER 22, 1977

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DOCKET NOo 50-266 UNIT NAME Point Beach Unit 1 .

DATE September 4, 1980 COMPLETED BY C. W. Fay TELEPHONE 414/277-2811 AVERAGE DAILY UNIT POWER LEVEL MONTH August, 1980 AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL DAY MWe NET DAY MWe NET DAY MWe NET 1 -

2 11 370 21 375 2 -

2 12 370 22 374 3 -

2 13 369 23 373 4 -

2 14 36 8 24 374 5 -

2 _

15 369 25 374 6 -

2 16 369 26 375 7 -

8 17 370 27 375 8 - 13 18 369 28 373

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9 86 19 370 29 372

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10 369 20 371 30 366 31 365 4

AD-28A (1-77)

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DOCKET NOo 50-101 UNIT NAME Point Beach Unit 2

• DATE Septembe r 4. 1980 COMPLETED BY C. W. Fay TELEPHONE 414/277-2811 AVERAGE DAILY UNIT POWER LEVEL

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MONTH August, 1980 1

4 AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY POWER LEVEL F NER LEVEL POWER LEVEL t DAY MWe NET DAY MWe NET DAY MWe NET

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l 482 11 484 21 483 2 484 12 484 22 482 1

3 483 ___

13 482 23 481 4 484 14 482 24 483 5 488 15 480 25 482 6 484 16 479 26 480

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4 7 484 17 478 27 481 8 473 18 477 28 480 9 485 19 478 29 480 10 484 20 480 30 494 i

i 31 495

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AD-28A (1-77)

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UNIT SIIUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-266 .

UNIT NAME point Beach Unit 1 REPORT MONTil DATE sentember 4, 1980 Aunus t . 1980 COMPLETED BY c. W. Pav TELEPIIONE 414/277-2811

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o as au "co mae St am Po L ao No. Date g 5g g jgg Licensee Event {g gy Cause and Corrective Action e om o u se Report No. m eo To Prevent Recurrence c- m o Eo m >c U 0

4 800726 S 207.1 D 1 80-009/OlT CB ITEXCII As required by NRC Confirmatory Order of 11-30-79 (amended 4-4-80),

the unit was taken off line for the 90 ef fective full power day steam generator testing. A 100% inspec-tion through the first support was conducted in both steam generators.

In addition, the full length of 3%

of the tubes was examined. A total of 28 crevice indications and two above the tubeshee t were found in the " A" steam generator and 22 crevice indications were found in "B". The tubes with crevice indica-tions were mechanically plugged.

Also, explosive plugs in the "A"

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steam generator were weld repaired.

A leak test was performed following repairs.

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F: Forced Reason: 4 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)

E- Operator Training & License Exam F- Administrative 5 AD-28B Exhibit I- Same G- Operational Error (explain) Source (01-78) 11- Other (explain)

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NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE Docket No. 50-266 Unit Nate Point Beach Unit 1 Date September 4, 1980 Completed By C. W. Fay Telephone 414/277-2811 Unit 1 was base loaded for 72% of the period. The unit returned to line at 3:04 p.m. on August 9, 1980, following a required 90 effective full power day steam generator inspec-tion and testing outage. The unit operated at 370 MWe net for the remainder of the period with one load reduction.

Load was reduced to 350 MWe net for one hour on August 13, 1980, to perform steam stop valve testing.

In accordance with the Nuclear Regulatory Commission's Modification of the November 30, 1979, Order, dated April 4, 1980, Point Beach Nuclear Plant Unit 1 was taken out-of-service on July 25, 1980, for hydrostatic tests and eddy current examinations of the steam generator tubes.

An 800 psig secondary-to-primary leak check of both steam generators was performed on July 28, 1980. In the " A" steam generator, two dripping explosive plugs and two wet end plugs were identified in the hot leg with no leaks detected in the cold leg. In the "B" steam generator, one wet end '

explosive plug and one dripping tube were identified in the hot leg with no leaks detected in the cold leg. Pertinent information on the identified leaks is as follows:

" A" Steam Generator R31C44 - 84% defect, explosively plugged 0 3-75, one drop every 20 seconds.

R29C54 - 75% defect, explosively plugged 04-74, one drop every 90 seconds.

R2 4 C37 - 90 % de fect , explosively plugged 10-72, less than one drop every five minutes .

R21C49 - 45% defect, explosively plugged 10-72, wet end plug. l l

"B" Steam Generator  ;

R2 3C5 3 - 68% defect, explosively plugged 11-75, wet end plug.

R21C48 - Leaking tube , slow drip about one drop every two I minutes.

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The eddy current inspection program consisted of an examination of 100% of the tubes to the first support plate on the hot leg side and 3% of the tubes inspected over their entire length.

In the " A" steam generator hot log, 30 tubes were identified with eddy current indications. Twenty-eight (28) indications were in the tubesheet crevice region and two tubes , . R10C54 and R33C54, had 34t small volume indications at the top of the tubesheet and one-half inch above the tube-sheet, respectively. All 28 tubes with indications in the tubesheet crevice region have been mechanically plugged.

Three additional tubes , R0 7C58, R07C59 and R0 7C51, were plugged inadvertently. The two dripping plugs in the " A" steam generator have been weld repaired and the steam generator was successfully hydrostatically leak checked on August 3, 1980.

The two tubes with indications at the tubesheet and one-half inch above the tubesheet have been left unplugged since these indications do not exceed the Technical Specification plugging criterion. Further, review of old tapes revealed a stable condition of these tubes. These tubes will be reexamined during the next eddy current inspection.

In the "B" steam generator hot leg, 2 2 tube s we re identified with tubesheet crevice indications . As discussed previously, tube R21C48 had been observed to be dripping during the hydrostatic leak check; however, no through-wall eddy current indication was observable during the inspection.

All 22 tubes identified with tubesheet crevice indications have been mechanically plugged. A satisfactory hydrostatic leak check of the "B" steam generator was performed on August 5, 1980.

Licensee Event Report No. 80-009/0lT was issued on the results of the 90 effective full power day steam gen-erator examination and testing. The unit returned to line following the outage with only a trace primary-to-secondary leakage of about four gallons per day.

All Unit 1 W2 switches were modified and tested satis-factorily during the period in response to IE Bulletin No.

80-20.

Work on a modification to the circulating water intake crib commenced during the period and is still in progress.

Special nozzle-shaped intake pipes are being installed to prevent freezeup from occurring during adverse weather conditions. Other items performed during the period include the overhaul of a charging pump vari-drive unit and a Diesel fire pump and the installation of feed line orifice flanges.

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

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NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE Docket No. 50-301 Unit Name Point Beach Unit 2 Date September 4, 1980 Completed By C . W. Fay Telephone 414/277-2811 Unit 2 was base loaded for 98% of the period with three load reductions. Load was reduced to 345 MNe net for two hours on August 8,1980, for turbine stop valve testing, to 4 70 MWe net for approximately one hour on August 26, 1980, for maintenance of the "D" moisture separator reheater steam supply valve, and load was reduced to 440 MNe net for an average duration of three hours on August 29, 1980, at the request of Power Supply.

All Unit 2 W2 switches were modified and tested satis-factorily during the period in response to IE Bulletin No.

80-20.

No other major safety rclated maintenance was performed during the period.