ML19310A401

Monthly Operating Repts for May 1980

ML19310A401
Person / Time
Site:	Point Beach
Issue date:	06/05/1980
From:	Fay C WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML19310A400	List: ML19310A399 ML19310A401
References
NUDOCS 8006170477
Download: ML19310A401 (9)

Text

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j OPERATItr., DATA REPORT s DOCKET NO. 50-266

=4 o DATE June 5, 1980 4

N COMPLETED DY C. h. FAY 41 TELEPilOt4E 414 277 2811 h OPERATIt4G STATUS

1. UNIT IJAME: POINT tiEACil NUCLEAR PLANT UNIT 1 . NOTES .

2. REPORTING PERIOD: MAY 1980 . .

3. LICEIJSED TilERMAL POWER (MWTI: 1518. . .

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

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

6. MAXIMUM DEPLt1DAl!LE CAPACITY (GROSS MWE): 519 . .

7. MAXIMUM DEPENDA!iLE CAPACITY (NET MWE): 495. . . . . . . . . . . . . . . . . . . . . . . . .

8. IF CllAtlGES OCCUR IN CAPACITY RATINGS (ITEMS NUMi1ER 3 TilROUOli 7) SINCE LAST REPORT, GIVE REASOlJS:

NOT APILICA11LE

9. POWER LEVEL TO hilICil RESTRICTEDe IF ANY (NET MWE): 390 0 10 REASONS FOR RESTRICTIONSe (IF ANY): SEExWRINCmMR)dIR Power restriction is the result of a self-imposed reduction in core average temperature in an attempt to inhibit corrosion of steam generator tubes within the tubesheet crevice. TilIS MONTil YR TO DATE COMULA1IVE

11. IlOURS Ill HEPORTING PERIOD 744 3e647 83,679

12. NUMiiER OF fiOURS PEACTOR WAS CRITICAL 744 0 2e898.5 69,415.0

13. REACTOR i<ESLRVE SilOTDOhN llOURS 00 18.8 601.0

14. IlOURS GENERATOR ON LIl4E 744.0 2e755.5 67e149.5

10. UNIT DESERVE SiluTDOhtJll0URS 00 151.5 753.9

16. GROSS TilERMAL E11ERGY GENER ATED (MWil) 901,815 3,314e924 94e067,719

17. GROSL ELECTRICAL ENERGY GENERATED (Mwil) 294e140 1,081,600 31,715,430

18. NET ELLCTRICAL ENLRGY GENERATED (MWil) 278e216 1,021e793 30e211e971

19. UNIT SERVICE FACTOR 100.0 75.6 80.1

20. UNIT AVAIL AllILITY F ACTOR 100.0 79.7 81.0

21. UNIT CAPACITY FACTOk (USING MDC NET) 75.S 56.6 74.0 2.1. UNIT CAPACITY FACTOR (USItJG DER NET) 75 2 56.4 72.5

23. UNIT FORCED OUTAGE RATE 00 0.0 3.4

24. SilVTDOWNS SCllEDULED OVER NEXT 6 Mol4Tels (TYPEe DATEe AND DURATIOl4 OF EACil):

Unit scheduled to shutdown July 25, 380, for ten days to perform steam generator leak testing and eddy current inspection.

25. IF Silu1DOhu AT EllD OF REPORT PERIODe ESTIMATED l) ATE OF STAbTUP: NOT SiluTDOLl4 DATA REPORTED AllD FACTOFS CALCULATED AS PEOUESTED IN NRC LETTEk DATED SEPTEMilLF 22e 1977

OPERATING DATA REPORT DOCKET NO. 50-301 DATE June 5, 1980 COMPLETED DY C. W. FAY TELEPHONE 414 277 2811 OPERATING STATUS

1. UNIT NAME: POINT DEACH NUCLEAR PLANT UNIT 2 . NOTES .

2. REPORTING PERIOD: MAY 1980 . .

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

4. NAMEPLATE RATING (GROSS MWE): 523.8 . .

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

6. MAXIMUM DEPENDADLE CAPACITY (GROSS MWE): 519. . .

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

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

NOT APPLICABLE

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

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

11. HOURS IN REPORTING PERIOD 744 3e647 68e664

12. NUMBER OF HOURS REACTOR WAS CRITICAL 458.7 2e546.9 61,443.8

13. REACTOR RESERVE SHUTDOWN HOURS 98 19.2 185.3

14. HOURS GENERATOR ON LINE 407.7 2e480.7 60e207.7

15. UNIT RESERVE SHUTDOWN HOURS 10 4 13.5 119 9

16. GROSS THERMAL ENERGY GENERATED (MWH) 539,505 3,566,569 81e219,105

17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 182e120 le186e790 27,548,130

18. NET ELECTRICAL ENERGY GENERATED (MWH) 170e733 le127e626 26e202,753

19. UNIT SERVICE FACTOR 54.8 68.0 87.7

20. UNIT AVAILA91LITY FACTOR 56 2 68.4 87.9

21. UNIT CAPACITY FACTOR (USING MDC NET) 46 4 62.5 77.8

22. UNIT CAPACITY FACTOR (USING DER NET) 46 2 62.2 75.8

23. UNIT FORCED OUTAGE RATE 0.0 12.4 20

24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPEe DATEe AND DURATION OF EACH):

NONF,

25. IF SHUTDOWN AT L:7 0F REPORT PERIODr ESTIMATED DATE OF STARTUP: NOT SHUTDOhN DATA REPORTED AND FACTORS CALCULATED AS REQUESTED IN NRC LETTER DATED SEPTEMUEk 22e 1977

DOCKET NO. 50-266 UNIT NAME Point Beach Unit 1 DATE June 5, 1980 COMPLETED BY C. W. Pav TELEPHONE 414/277-2811 AVERAGE DAILY UNIT POWER LEVEL 5

MONTH May, 1980 AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LE* EL DAY MWe NET DAY MWe NET DAY MWe NET 1 377 11 367 21 374 2 374 12 374 22 373 3 375 13 37g 23 376 i 4 374 14 17a 24 371 5 375 15 373 25 373 6 374 16 377 26 373 7 375 17 370 27 374 8 373 18 375 28 373 9 376 19 372 29 374 10 375 20 375 30 375 31 374 AD-28A (1-77)

DOCKET NO. 50-301 UNIT NAME Point Deach Unit 2 DATE June 5, 1980 COMPLETED BY C. W. Fay TELEPHONE 414/277-2811 AVERAGE DAILY UNIT POWER LEVEL MONTH May, 1980 AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL DAY MWe NET DAY MWe NET DAY MWe NET 1 -

3 11 - 11 21 492 2 -

2 12 - in 22 483 3- -

2 13 - 12 23 431 4 -

4 14 21 24 287 5 -

4 15 116 25 466 6 -

2 16 346 26 467 7 -

9 17 361 27 474 8 - 11 18 167 28 490 9 -

7 19 42g 29 493 10 -

8 20 492 30 493 31 494 AD-28A (1-77)

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-266 UNIT NAME Point Beach Unit 1 REPORT MONTH May, 1980 COMPLETE , 1 ha TELEPHONE 414/277-2811

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o 3R co o e Vea in ce No. Date D. gg a jgg Licensee Event ag 'g g'g Cause and Corrective Action N :s m e v .c Report No. m eo To Prevent Recurrence O- M gmg g 8

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! 1 3 4 F: Forced Reason: Method: Exhibit G-Instruc-1 S: Scheduled A- Equipment Failure (explain) 1- Manual tions for Prepar-B- Maintenance or Test 2- Manual Scram ation of Data Entry

,1 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 i AD-28B Exhibit I- Same G- Operational Error (explain) Source (01-78) 11- Other (explain)

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-301 UNIT NAME Point Beach Unit 2 DATE June 5, 1980 REPORT MONTH May, 1980 COMPLETED BY C. W. Fay TELEPHONE 414/277-2811

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e 2* 8 msM Be ce gy No. Date g gg a jgg Licensee Event gg Cause and Corrective Action e om e v ;c Report No. m eu To Prevent Recurrence O- M gmg g 8

2 800411 S 326.6 C 1 N/A N/A N/A 3 800515 S 2.6 B 1, N/A HA TURBIT Turbine overspeed trip testing.

4 800523 S 7.2 B 1 N/A HB VALVE) Moisture separator reheater dump valves were clogged causing level control problems. Valves were cleaned during the shutdown.

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) (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)

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NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE

' Docket No. 50-266 Unit Name Point Beach Unit 1 Date June 5, 1980 Completed By C. W. Fay Telephone 414-277-2811 Unit.1 operated at 375 MWe net throughout the period with one load reduction. The-load was reduced to 285 MNe for five hours on May 11, 1980 for turbine stop valve testing.

No other major safety-related maintenance was performed durir 7 the period.

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NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE Docket No. 50-301 Unit Name Point Beach Unit 2 June 5,-1980 Data C. W. Fay Completed By Telephone 414-277-2811 Inspection of the Unit 2indications low pressurewereturbine found rotors in was completed. Thirty-five (35) l. The the L-3 and L-4 blade roots and disc steeples of LP 35 indications consisted of five blade root and have been 30 discThe five bla steeple indications.and all except one of the' disc steeple indicationsThe final disc removed by polishing and grinding.

ld Nine indications were The found in the nine indications L-1, L-3, and L-4 ,

roots and disc steeples of LP2. included fourlblade d androot and five disc disc steeple To repair the indications, two blades have been rep ace the other two blade indications, along withbines The inspection all theindica Numerous small tendon rivet cracks in both low pressure tur in the have also been removed by polishing and grinding.of th h safety factor No.

3 disc keyway apex on the governor end.

calculated lifetime-to-critical size of 7.7 years witAn indication below the equ based on initial interpretation. was also identified in definition capability (less than .020")No the generator end. indications were the No. 3 disc identified 1 ~

during the LP2 spindle inspection. l Significant events prior to goingcompleted on line were on Maysteam 9,

generator crevice and cleaning (eight cycles) heatup of the reactor coolant system on 1980; fill, vent, May 10, 1980; inservice 11, 1980; leak testing with satisfactory resultsinitial U completed on May and completion of BOL physics testing withSafety inject on.May 12, 1980; 1980. been satis-training startups on May 13, test.and all other operational refueling te factorily completed.

The unit was reduced to 97% of full power on May 22, l 1980 to administratively control FAH enthalpyThe riseunit hotwas channe -

factors within Technical Specification limits. i between taken.off line and remained in hot shut-down condit on1980 for moisture sepa full power 12:08 a.m. to 7:21 a.m. on May 23,the load was kept at 95% b reheater drain valve repairs; in order to limit the a ove l until-3:00 p.m. on May 27, 1980 6ing 1 mentioned hot channeldrain factors as a result of the shut-dow Four moisture separator "C" valve were cleancd during reheater dump valves with )

l the shut-down. ]

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Unit 2 Nos. 2 and 4 condenser waterboxes were tested for leakage by a freon detection method. The Nos. 1 and 3 condenser waterboxes were checked previously during unit shut-down.

The pressurizer access modification and the installation of the orifice flanges for auxiliary feedwater flow indication were completed.

The "C" charging pump motor was reassembled, the atmospheric steam dump valves were repaired, and the reactor coolant drain tank "A" discharge pump check valves were replaced.

Work continues on IE Bulletin Nos. 79-02, anchor bolt inspection, and 79-14, seismic analysis for as-built safety-related piping systems, with balance of Unit 2 containment work completed.

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

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