ML19210C997

Monthly Operating Repts for Oct 1979

ML19210C997
Person / Time
Site:	Point Beach
Issue date:	11/06/1979
From:	Burstein S WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML19210C995	List: ML19210C994 ML19210C997
References
NUDOCS 7911200396
Download: ML19210C997 (10)

Text

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OPERATIllG DATA REPORT DOCKET NO. 50-266 -

DATE November 6, 1979 COMPLETED BY SOL DURSTEIN TELEPilONE 414 277 2121 OPERATItJG STATUS b 9

. . . . . . . . . . . . . . . . . . . . . . . . E D

1. UtJIT tJAME: POINT DEACil IJUCLEAR PL ANT

2. REPORTIrlG PERIOD: OCTOBER 1979 UNIT 1 . NOTES W

3. LICEtiSLD TilERMAL POWER (mbt): 1518. . .

Q

4. IJANEPLATE RATItlG (GROSS MWE): 523.8 . .

S. DESIGti FLECTRICAL RATIrlG (IJET MWE): 497. . . ,

6. M AX I MU:l DEPtIJDAllLE CAPACITY (GROS' MWE): 519. . . gg

7. MAXIriuh DEPErlDADLE CAPACITY (tJET MUE): 495. . . . . . . . . . . . . . . . . . . . . . . . .

8. IF CilAtJGES OCCUR Ill CAPACITY RATItJCS (ITEMS NUMBER 3 TilROUGil 7) SINCE LAST REPORTe GIVE REASONS:

tJOT APILICAOLE W

9. POWER t.EVEL TO WilICil RESTRICTEDe IF ANY (NET MUE):

NOT APPLICAULE g

10., REASONS FOR I?ESTRICT)OtJS, (IF ANY): tJOT APPLICADLE b TilIS MOtJTl! YR TO DATE CUMULATIVE

^

IlOljRS IN REPORTING PERIOD 745 7,296 78e768

( 11.

12. tJtlMiiER OF ll0URS RFACTOR WAS CRITICAL

13. RE ACTOR I;ESERVE SittJTDOWN llOURS 105.3 6,049.0 6Se936.9 3.3 9.4 449.0

14. 110t JRS GEtJFR ATOR Oil LIllE 98.0 Se991.4 63,928.4

-- 15. tJNIT RESFRVF SiltlTDOWN IIOURL 0.0 6.3 389.7

.,S 16. GROS' TilERMAl. EtJERGY GEtFRATED (Mhil) 141e578 8e879e112 90e245e727

--*17. CROS" FI ECTRICAL EtJr.RGY GEi!ERATED (MWil) 47,870 3 039,190 30 46i.,830

'18. IlET FLFCTRICAL FiJLRGY LEtjr.RATFD (MWil) 44,390 2e903,123 29e037,877

19. tit 1IT SERVICF FACTOR 13.2 82.1 81.2

• 2 20. tirJIT AVAILAllILITY FACTOR 13.2 82.2 81.7 O 21. tJNIT CAPACITY FACTOR (USING MDC NET) 12.0 80.4 75.8 U 2 7. tJtJIT C APACITY F ACTOR (tiSItJG DER tJET) 12.0 80.1 74.2 to 23. Uti1T FORCED OUTAGE RATE 0.0 5.6 3.2 c 24. SNilTDOWrJS SCllEDULLD OVER NEXT 6 MOriTil5 (TYPE, DATEe AND l't!RATIOrt OF EACll):

ilOt.E

25. IF SifUTDOWN AT EtJD OF REPORT PERIODe ESTIMATED DATE OF STARTllP: November 24, 1979 DATA REPOPTED Afin FACTORS CAI rtil ATFD AS RFOllESTFD IN tJRC I FTYrR DATFD RFPTFMDER 22e 1977

OPERATING DATA REPORT .

DOCKET NO. 50-301 DATE November 6, 1979 COMPLETED DY SOL DURSTEIN TELEPilONE 414 277 2121 OPERATING STATUS

1. UNIT llAME: POINT DEACil NUCLEAR PLAIJT UNIT 2 . NOTES < .

2. REPOI<TIl1G PERIOD: OCTODER 1979 . .

3. LICEtlSED TilFRMAL POWER (MUT): 1518. . .

4. NAMFPLATE RATItJG (GROSS MWE): 523.8 . .

5. DESIGil FLTCTRICAL RATING (tsET MWE): 497. . .

6. MAXINU:-l DEPl.ilDADLE CAPACITY (GROSS MWE)I 519. . .

7. MAXIliUil DEPENDAULL CAPACITY ( N E T M WI.') : 495. . . . . . . . . . . . . . . . . . .......

8. IF CilANGES OC(.UR IN CAPnCITY RATINGS (ITEMS NUMBER 3 TilROUGil 7) SINCE LAST REPORTr GIVE REASONS:

NOT api'LICADLE

9. POWER LrVI:L TO WilICil RESTRICTEDe IF ANY (tJET MWE): NOT APPLICAULE

10. REASOtJS FOR 1:ESTICICTIONSe (IF ANY): NOT APPLICAULE TilIS MONTil YR TO DATE CUMULATIVE

11. IlOURS IN REPOltTING PERIOD 745 7e296 63,553

12. NUMf!ER OF llOURS RE ACTOR WAS CRITI'C AL 745.0 6,347.3 57e436.4 %

13. REACTOR l<ESLl!VE SituTDOWN 110URS

14. IlOURS GENERATOR OlJ LI!JE 00 746 0 16 1 6e272.8 165.7 6

15. UtJIT RESERVif SilUTDOWN llOURS 0.0 18.6 56e267.(

106.

16. GROS' TilERMAL ENEhGY GEtJER ATED (MWil) le117e434 9e226e269 75eS11e486 g-

-17. GROS: Ell'CTRICAL ENi RGY GENERATED (MWil) 383,260 3,165,970 25,641,080 N18. NET ELI CTRICAL EN! RGY GE!LRATED (MWil) 366e296 3e019e693 24e387e370

( N 19. UllIT SERVICE FACTOR 100.0 86.0 Ba t. !EE'S)

20. UtJIT AVAILnDILITY FACTOR 100.0 06.2 8t.'

21. UtlIT CAPACITY FACTOR (USING MDC NET) 99.3 83.6 78.

7 2 T' . UllIT CAPACITY FACTOR (USING DER NET) 98.9 83.3 77.' '

23. UrJIT FORCED OUTAGE RATE 0.0 0.0 1.

[24. SiluTDOWils SCilEDULED OVER IJEXT 6 MOtJTilS (TYPEe DATER AND DURATION OF EAcil):

Refueling shutdown scheduled for March 7, 1980, to last approximately five weeks. h

25. IF SiluTDOWi1 AT END OF REPORT PERIODe ESTIMATED DATE OF STARTUP: NOT SilUTDOWN DATA REPOPTFD AtJD FACTOPS C AI cllt ATFD A% RFOUESTI D TN tlRC i FT1FR DATFD 9FPTEMBrR 22e 1977

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

UNIT NAME PoinE Beach Unit 1

/

REPORT MONTH October, 1979 COMPLETED Y So Burst in TELEPHONE 414/277-2121 4

C ' %4 tn o 9 o

Man "co .'i t men Po am En a c' No. Date g gg g jjg Licensee Event gg gy Cause and Corrective Action p :s m o u .c Report No. m eo To Prevent Recurrence a- m gmc g 8

7 791005 S 647.0 C 1 N/A N/A N/A .

w .

N s

n 1 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)

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

.s i

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-301 i UNIT NAME Point Beach Unit 2 i REPORT MONTil October, 1979 COMPLETED o rt in TELEPilONE 414/277-2121 S

o N oc Ev b o $N $ m$N S$ co No. Date g yg y jjg Licensee Event gg o 'g Cause and Corrective Action e :s :c 0 o .c Report No. u2 Eo To Prevent Recurrence Q"  % 0 v3 c o llC 3 U S

t a

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)

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

DOCKET NO. 50-266 -

UNIT NAME Point Beach Unit 1 .

f DATE November 6, 1979 COMPLETED BY Sol Burstein TELEPHONE 414/277-2121 l

8 AVERAGE DAILY UNIT POWER LEVEL 8

MONTH October, 1979 '

6 AVERAGE AVERAGE AVERAGE I

DAILY DAILY DAILY i POWER LEVEL POWER LEVEL POWER LEVEL

, DAY MWe NET DAY MWe NET DAY MWe NET I 1 483 11 -1 21 -1 l 2 480 12 -1 22 -1 1

I 3 451 13 -1 23 -1 I

' 4 474 14 -1 24 -1 5 4 15 -1 25 -1 6 -

6 16 -1 26 -1 l

1

[ 7 -

3 ,

17 -1 27 -1 s ,

l

] 8 -

2 18 -1 28 -1 l _.- 9 -

1 19 -1 29 -1 m

ci,, 10 -

1 20 -1 30 -1 31 -1 AD-28A (1-77)

DOCKET NO. 50-301 UNIT NAME Point Beach Unit 2 .

j DATE November 6, 1979 COMPLETED BY Sol Burstein TELEPHONE 414/277-2121 AVERAGE DAILY UNIT POWER LEVEL t MONTH October, 1979 AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL DAY MWe NET DAY MWe NET DAY MWe NET 1 493 11 492 21 491 2 493 12 491 22 492 f

3 493 13 483 23 492 1

4 493 14 494 24 491 5 493 15 492 25 491 6 495 16 492 26 492 m 7 488 17 492 27 492

, 8 491 18 491 28 492 9 492 19 493 29 491

~

10 49) 20 496 30 492 31 490 AD-28A (1-77)

NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE Docket No. 50-266 Unit Name Point Beach Unit 1 Date November 6, 1979 Completed By Sol Burstein Telephone 414/277-2121 Unit 1 was base loaded for only about 12 per cent of the period. The unit had one load reduction to 390 MWe net for nine and one-half hours on October 3, 1979, extending into October 4, 1979, because of boron addition caused by equilibration of the mixed bed demineralizer when it was put in service to check the resin. Unit capacity dropped to 480 MWe net because of core stretch operation prior to Refueling 7 shutdown on October 5, 1979. The unit was taken off line at 1:57 a.m. on October 5, 1979, and cool-down commenced at 12:35 of the same day after completion of end-of-life physics testing and operator licensing exams.

The reactor vessel head was stripped and removed at 8:28 a.m. on October 11, 1979. Fuel movement was initiated at 8:58 p.m. on October 11, 1979, and completed at 4:24 .

a.m. on October 14, 1979. Installation of the closure head and connection of head area vent ducting, etc., was completed on October 22, 1979.

Sludge lancing of both "A" and "B" steam generators was performed during the outage, with approximately 34 gallons of sludge being removed from "A" and 62 gallons removed from the "B" steam generator.

The initial eddy current inspection program of steam generator tubes consisted of inspecting 37 tubes in the "A" steam generator and 38 in the "B" steam generator. These tubes were suspected as potentially defective based on a reanalysis of eddy current results from a 100% inspection in August, 1979. The inspection identified 13 tubes in

, the "A" and six tubes in the "B" steam generator that require plugging. Because an additional defective tube was discovered during a subsequent testing program, a 200 tube sample inspection was performed in the "A" steam generator. The 200 tube sample inspection identified more defective tubes so the eddy current inspection program was expanded to a 100% inspection in compliance with the Technical Specifications.

A total of 70 tubes with defects which require plugging were discovered in the "A" steam generator. In addition, three tubes with defects less than 40% will be plugged, and two good tubes which are being pulled to ascertain the overall condition of the steam generators will also be plugged.

- ,,,- ;47

50-266 Page 2 This raises the total number of tubes that will be plugged in "A" to 75.* In the "B" steam generator, 65 defective tubes have been identified and will be plugged. All of the defects found are within the tubesheet in both steam generators. An over the U-bend inspection of the first row tubes in "A" was also performed as a precautionary inspection; no defects were identified.

Three tubes were pulled from the "A" steam generator.

These tubes were pulled to investigate deep crevice cracking (cracking of tubes within the tubesheet) and to determine the overall condition of the steam generators. Tube R15C45 was identified by eddy current inspection as having a defect within the tubesheet and was pulled for investigative study.

Tubes R20C73 and R22C37 were both identified as good tubes by eddy current inspection, but were pulled to ascertain the condition of the steam generators. Tube R20C73 represents the area where deep crevice cracking has not been a problem, whereas tube R22C37 is in the area where deep crevice cracking has occurred. All three tubes have been sent to Westinghouse Research for evaluation.

The steam generator 18" x 16" feed line nozzle reducers and a portion of the piping in each steam generator feed line have been replaced. No cracking was visually evident in the replaced nozzles.

The "A" reactor coolant pump upper motor bearings were removed for inspection and replaced. The "B" reactor coolant pump motor was removed for an inspection, and the pump seals were replaced. Assembly of both pumps is complete.

Low pressure turbine LPl was dismantled and cleaned.

Weld repairs were made on the housings and an ultrasonic inspection of the rotor discs was performed. Low pressure turbine LP2 was dismantled so that an ultrasonic inspection of its rotor discs could be performed also. Indications were discovered in the second and third discs of LPl; no indications were discovered in the LP2 discs. A detailed evaluation has shown that the discs will require replacement in the future but that the rotor may be operated for at least 28 months with no significant reduction in safety margin.

Work on IE Bulletins 79-02, anchor bolt inspection, and 79-14, seismic analysis for as-built safety-related ,

piping systems is being performed in containment. Work on inspection of lines containing stagnant borated water, IE Bulletin 79-17, is complete.

• As of October 31, 1979 '7(' ]40

50-266 Page 3 The No. 4 feedwater heaters have been cleaned in preparation for an eddy current inspection of the tubes.

Moisture separator reheater cleaning and general maintenance is being performed.

Other general work being performed this period includes containment recirculating fan maintenance and balancing, refueling interval calibrations, safety valve work, incore instrumentation thimble wora, crossunder and extraction piping changeout and inspection and addition of charging pump stabilizers.

Operations refueling test, ORT #3, loss of AC power was satisfactorily completed at 12:35 p.m. on October 26, 1979.

The 3D emergency Diesel generator was returned to service at 1:00 p.m. on October 5, 1979, after replacement of a defective reconditioned governor. Licensee Event Report No. 79-016/03L-0 has been filed on the failure of the Diesel to start during a test on October 3,1979.

Licensee Event Report No. 79-015/0lT-0 has been filed describing reduced redundancy of containment pressure transmitters and possible violation of containment integrity occasioned by a loose swagelok fitting on a containment pressure instrument line.

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

NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE Docket No. 50-301 Unit Name Point Beach Unit 2 Date November 6, 1979 Completed By Sol Burstein Telephone 414/277-2121 Unit 2 was base loaded for nearly 100% of the period with two load reductions.

Unit 2 load was reduced to 345 MWe net for two hours on October 13, 1979, in order to perform turbine stop valve testing. The second load reduction occurred on October 31, 1979, when load was reduced to 470 MWe net for one hour to run a performance test on the No. 4 feedwater heater.

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

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