ML20010C098

Monthly Operating Repts for Jul 1981

ML20010C098
Person / Time
Site:	Point Beach
Issue date:	08/05/1981
From:	Fay C WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML20010C096	List: ML20010C095 ML20010C098
References
NUDOCS 8108190118
Download: ML20010C098 (9)

Text

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D O OPERATING DATA REPORT

$g4 DOCKET NO. 50-301

?O Eg DATE August 5, 1981 O

EU3 COMPLETED BY C. U. FAY ouO 88 TELEPHONE 414 277 2811 E$'4: OPERATING STATUS

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

2. REPORTING PERIOD: JULY 1981 . .

3. LICEh3ED THERMAL POWER (MWT): 1518. . .

4. NAMEPLATE RATING ; GROSS MUE): 523.8 . .

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

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

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

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

NOT APPLICABLE

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

11. HOURS IN REPORTING PERIu 744 5,087 78,888

12. NUMBER OF HOURS REACTOR 9 CRITICAL 744.0 4,189.9 70,739.9

13. REACTOR RESERVE SHUTDOWN ns. . 0.0 0.0 186.3

14. HOURS GENERATOR ON LINE 744.0 4,166.2 69,464.7

15. UNIT RESERVE SHUTDOWN HOURS 0.0 7.3 131.2

16. GROSS THERMAL ENERGY GENERATED (MWH) 1,112,509 6,142,771 94,932,517

17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 378,190 2,085,100 32,208,950

18. NET ELECTRICAL ENERGf GENERATED (MWH) 361,050 1,988,660 30,652,081

19. UNIT SERVICE FACTOR 100.0 81.9 88.1

20. UNIT AVAILABILITY FACTOR 100.0 82.0 88.2

21. UNIT CAPACITY FACTOR (USING MDC NET) 98.0 79.0 79.2

22. UNIT CAPACITY FACTOR (USING DER NET) 97.6 78.7 78.2

23. UNIT FORCED OUTAGE RATE 0.0 0.0 1.7

24. SHUTDOWNS SCHEDULED DVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):

NONE i 25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: NOT SHUTDOWN 1

DATA REPORTED AND FACTORS C LCULATED AS REQUESTED IN NRC LETTER DATED SEPTEMBER 22, 1977

1 J

1 OPERATING DATA REPORT DOCKET NO. 50-266 d

DATE August 5, 1981 COMPLETED BY C. W. FAY TELEPHONE 414 277 2811 OPERATING STATUS

1. UNIT NAME: POINT BEACH NUCLEAR PLANT UNIT 1 . NOTES .

2. REPORTING PERIOD: JULY 1981 .

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

4. NAMEPLATE RATING (GROSS MUE): 523.8 .

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

6. MAXIMUM DEPENDABLE CAP 4 CITY (GROSS MWE): 519. .

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

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

9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWE): 445.0

10. REASONS FOR RESTRICTIONS, CUX1ul%I: Maximum dependable capacity reduced because of a self-imposed hot leg temperature limitation in an attempt to limit steam generator tube corrosion.

THIS MONTH YR TO DATE CUMULATIVE 10D 744 5,087 94,103

11. HOURS IN REPORTINC 367.5 4,705.9 78,140.7

12. NUMBER OF HOURS REACTOR WAS CRITICAL

13. REACTOR RESERVE SHUT 30WN HOURS 0.0 0.6 606.3

14. HOURS GENERATOR ON LINF 360.0 4,691.0 75,827.9

15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 764.3

16. GROSS THERMAL ENERGY GENERATED (MWH) 467,103 5,689,458 104,527,902

17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 150,750 1,844,770 35,104,490

18. NET ELECTRICAL ENERGY GENERATED (MWH) 141,229 1,747,183 33,414,469 48.4 92.2 80.6 )

19. UNIT SERVICE FACTOR 48.4 92.2 81.4

20. UNIT AVAILABILITY FACTOR 38.3 69.4 72.8

21. UNIT CAPACITY FACTOR (USING MDC NET) 38.2 69.1 71.4

22. UNIT. CAPACITY FACTOR (USIhG DEP 'T) 0.0 0.3 3.1

23. UNIT FORCED OUTAGE RATE

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

Refueling outage October 9, 1981, expected to last approximately eight weeks.

25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: NOT SHUTDOWN l

DATA REPORTED AND FACTORS CALCULATED AS REQUESTED IN NRC LETTER DATED SEPTEMBER 22, 1977

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-266 UNIT NAME Point Roach fin i t 1 REPORT MONTH July, 1981 DATE Aucust 5. 1991 COMPLETED BY c_71. Fav TELEPHONE 414 /2 77-2 R11

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No. Date a ea m o4o Licensee Event ot Cause and Corrective Action N $$

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$ $$* Report No. up o $O To Prevent Recurrence N gmg g o

O 3 810704 S 384.0 B 1 81-008/0lT-0 CB IITEXCI: Steam generator eddy current and tube plugging was completed on July ll, 1981. A total of five tubes were plugged. Two tubes in the "A" steam generator, both with indications greater than 40% within the tubesheet area were plugged.

Three tubes were plugged in the "B" steam generator, two with indica-tions within the tubesheet area and

" above the tubesheet. One indication within the tubesheet area was less than 40% and was plugged because it was located within one inch of the top of the tubeshee t. The other two indications were greater than 40%

1 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) H- Other (explain)

DOCKET NO. 50-301 UNIT SHUTDOWNS AND POWER REDUCT. TONS UNIT NAME Point Beach Unit 2 A Augus t 5, 1981 REPORT MONTH July' 1981 COMPLETED BY C. W. Fay TELEPHONE 414/277-2811 c - we v o

.h au "co .'i t co a un Poo En ao gg vg 'g No. Date g g jgg Licensee Event g'g Cause and Corrective Action e om o v .c Report No. m Eo To Prevent Recurrence Q* M o to a o E 3 0 0

L 1 3 4 F: Forced Reason: Method: Exhibit G-Instruc-S: Scheduled A- Equipment Failure (explain) l- M.unual 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)

DOCKET NO. 50-266 UNIT NAME Point Beach Unit 1 DATE August 5, 1981 COMPLETED BY C. W. Fay _

TELEPHONE 414/277-2811 i

AVERAGE DAILY UNIT POWER LEVEL MONTH July, 1981 AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL DAY MWe NET DAY MWe NET DAY MWe NET 1 374 11 -

2 21 412 2 374 12 -

2 22 412 3 36 3 13 -

1 23 413 4 1 14 -

7 24 #13 5 -

6 15 -

4 25 41 ~.

6 -

3 16 -

2 26 415 7 -

5 17 -

6 27 415 8 -

2 18 -

8 28 415 4

9 -

2 19 - 12 29 415 10 -

2 20 286 30 415 31 409 AD-28A (1-77)

DOCKET NO. 50-301 UNIT NAME Point Beach Unit 2 DATE August 5, 1981 COMPLETED BY C. W. Fay TELEPHONE 414/277-2811 AVERAGE DAILY UNIT POWER LEVEL MONTH July, 1981 AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL DAY MWe NET DAY MWe NET DAY MWe NET 1 492 11 494 21 485 2 491 12 491 22 484 3 478 13 490 23 482 4 493 14 489 24 482 5 492 15 486 25 484 6 467 16 487 26 476 7 493 17 491 27 470 8 486 18 491 23 476 9 492 19 489 29 474

, 10 491 20 ans 30 479 31 488 AD-28A (1-77)

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NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE Docket No. 50-266 Unit Name Point Beach Unit 1

. Date ' August 5, 1981 Completed By C. W. Fay Telephone 414-277-2811 Unit 1 operated at 390 MWe net until July 3, 1981

, when at 2107 hours0.0244 days <br />0.585 hours <br />0.00348 weeks <br />8.017135e-4 months <br /> a' load reduction was commenced for a unit shut-down for steam generator inspections. Unit 1 was off line at 0331 hours0.00383 days <br />0.0919 hours <br />5.472884e-4 weeks <br />1.259455e-4 months <br /> and the reactor was shut down at 0356 hours0.00412 days <br />0.0989 hours <br />5.886243e-4 weeks <br />1.35458e-4 months <br /> on July 4, 1981. Following completion of the steam generator inspection, the unit returned to line at 0328 hours0.0038 days <br />0.0911 hours <br />5.42328e-4 weeks <br />1.24804e-4 months <br /> on July 20, 1981. Based on the results of the steam generator eddy current and flushing, Unit 1 was returned to line with a hot leg temperature of 575'F. This hot leg temperature is higher than the unit had been operating at since December 1979, but still less than design. The unit is operated at a reduced temperature to reduce the steam generator corrosion rate.

Unit 1 operated at 410 MWe net the remainder of the period with no load reductiocs.

Steam generator eddy current and tube plugging was completed on July 11, 1981. A total of five tubes were plugged.

Two tubes in the "A" steam generator, both with indications greater than 40% within the tubesheet area, were plugged. Three tubes were plugged in the "B" stcan generator, two with indica-tions within the tubesheet area and one one-half inch above the tubesheet. One indication within the tubesheet area was less

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than 40% and was plugged because it was located within one inch of the top of the tubesheet. The other two indications were greater than 40%. Licensee Event Report No. 81-008/0lT-0 has been filed on this event.

On July 14, 1981, during the Unit 1 check valve testing, valves 1-853 C&D (residual heat removal core deluge valves) were found leaking in excess of th acceptable criteria. Upon further investigation, it was ditsovered that the check valve discs were jammed in the full open position. This condition was caused by the disc retaining nut lock wire interfering with the valve body. It appears that this may be a generic design problem with six-inch "Velan" check valves. There are two other six-inch "velan" check valves installed in Unit 1 (1-853 A&B). These valves were also disassembled and found to function properly; however, as a preventive measure, the lock wires were replaced. '

. The' subject valves were repaired and returned to service at 2046 i hours on July 16, 1981. The Event V check valve tests were rerun on these particular valves at 1645 hours0.019 days <br />0.457 hours <br />0.00272 weeks <br />6.259225e-4 months <br /> on July 17, 1981 with satisfactory results. Licensee Event Report No. 81-010/01T-0 has been filed on this event.

f On July 21, 1981, while performing bi-weekly test ICP 2.6, Safeguards System Logic Periodic Testing, Unit 1 test switch PC-950A failed. This switch is one of three which test steam line isolation logic for high containment pressure. The switch was replaced and the test was completed satisfactorily. A 30-day Licensee Event Report will be issued on this event.

On July 14, 1981, Bechtel informed Wisconsin Electric Power Company that their analysis relating to NRC IE Bulletin 80-11 indicates that the west control room masonry wall and. the battery room masonry walls would exceed allowable limits during a safe shut-down earthquake. This event was reported in Licensee Event Report No. 81-009/01T-0.

Safety-related maintenance during this period included lock wire replacement on the residual heat removal core deluge valves following the Event V check valve test and steam generator tube plugging.

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l NARRATIVE

SUMMARY

OF OPERATING-EXPERIENCE 1

Docket No. 50-301 Unit Name. Point Beach Unit 2 Date August 5, 1981 Completed By. C. W. Fay Telephone 414-277-2811 Unit 2 operated at 490 MWe net throughout the period with eight load reductions. Seven of these load reductions to an average of 429 MWe for an average duration of 3.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> each were at-the direction of Power Supply for load following

-purposes. On July 6, 1981 at 0001 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, load was reduced to 360 MNe net to accommodate Technical Specification turbine stop valve testing. There was no safety-related maintenance performed during the period.

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