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Monthly Operating Repts for June 1983.W/830711 Ltr
	ML19277C594
Person / Time
Site:	Point Beach
Issue date:	07/07/1983
From:	Fay C; WISCONSIN ELECTRIC POWER CO.
To:	; Office of Nuclear Reactor Regulation
References
	NUDOCS 8307150066
	Download: ML19277C594 (9)
	v • d • e

23]Oj OPERATING DATA REPORT mc} DOCKET NO. 50-266

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c ui DATE July 7, 1983 R8 Fjp COMPLETED BY C. W. FAY O

tntD (jgj TELEPHONE 414 277 2811 cys4 OPERATING STATUS

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

2. REPORTING PERIOD: JUNE 1983 . .

3. LICENSED THERMAL POWER (MUT): 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 (FET MUE): 495. ........................

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

NOT APPLICABLE

9. POWER LEVEL TO UHICH RESTRICTED, IF ANY (NET NUE): 390.0

10. REASONS FOR RESTRICTIONS, (IF Ant): Power level restricted because of self-imposed hot leg limitation in an attempt to limit steam generator tube corrosion.

THIS NONTH YR TO DATE CUNULATIVE

11. HOURS IN REPORTING PERIOD 720 4,343 110,879

12. NUMBER OF HOURS REACTOR WAS CRITICAL 720.0 4,294.6 91,866.9

13. REACTOR RESERVE SHUIDOUN HOURS 0.0 1.4 625.4

14. HOURS GENERATOR ON LINE 720.0 4,287.9 89,396.2

15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 793.5

16. GROSS THERMAL ENERGY GENERATED (MWH) 846,076 5,003,925 120,952,914

17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 282,740 1.669,870 40,545,660

18. NET ELECTRICAL ENERGY GENERATED (MWH) 267,559 1,581,598 38,563,316

19. UNIT SERVICE FACTOR 100.0 98,7 80.6

20. UNIT AVAILABILITY FACTOR 100.0 98.7 81.3

21. UNIT CAPACITY FACTOR (USING MDC NET) 75.1 73.6 71.2

22. UNT! CAPACITY FACTOR (USING DER NET) 74.8 73.3 70.0

23. UNIT FORCED OUTAGE RATE 0.0 0.1 2.7

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

Twenty-six week refueling and steam generator replacing outage scheduled to commence September 30, 1983. (f

25. IF SHUTD0uN AT END OF REPORT PERIOD, ESildATED DATE OF STARTUP: NOT SHUTDOWN Rh i

00 9)

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

DOCKET NO. 50-266 UNIT NAME Point Beach Unit 1 DATE July 7, 1983 COMPLETED BY C. W. Fay TELEPIIONE 414/277-2811 AVERAGE DAILY UNIT POWER LEVEL MONTil June, 1983 AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL DAY MWe NET DAY MWe NET DAY MWe NET 1 372 11 371 21 371 2 372 12 372 22 371 3 372 13 373 23 372 4 372 14 372 24 372 5 373 15 373 25 372 6 357 16 372 26 373 1

7 372 17 373 27 371 8 372 18 373 28 371 9 372 19 372 29 373 10 372 20 372 30 370 31 ---

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NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE Docket No. 50-266 Unit Name Point Beach Unit 1 Date July 7, 1983 Completed By C. W. Fay Phone 414-277-2811 Unit 1 operated at approximately 371 MWe net throughout the period with no major load reductions. The primary-to-secondary leakage remains stable at less than ten gallons per day.

On June 18 the motor operator for redundant valve 1-826, which controls flow from the boric acid storage tanks to the safety injection pump suction, was discovered with an open breaker. A 30-day Licensee Event Report will be filed to cover this event.

On June 23 a Unit 1 pressure-operated relief valve lost indication due to a molded circuit breaker being open. Technical Specification 15.3.5-5, Item 1, requires indication of this valve, there: Tore, a 30-day LER will be filed with the NRC.

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

DATE July 7, 1983 COMPLETED BY L W. Fay TELEPIIONE 41./277-2811 AVERAGE DAILY UNIT POWER LEVEL MONTII June. 1983 AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL DAY MWe NET DAY MWe NET DAY MWe NET 1 -2 11 -2 21 -2 2 -2 12 -2 22 -2 3 -2 13 -2 23 -2 4 -2 14 -2 24 -2 5 -2 15 -2 25 -2 6 -2 16 -2 26 -6 7 -2 17 -2 27 -7 8 -2 18 -2 28 -10 9 -2 19 -2 29 -8 10 -? 20 -2 30 -10 31 ---

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UNIT SilUTDOWNS AND POMER REDUCTIONS DOCKET NO. 50-301 UNIT NAME Point Beach Unit 2 DATE July 7, 1(383 REPORT MONTli June, 1983 COMPLETED BY C. W. Fay TELEPilONE 414/277-2811 m

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No. Date g gg ty jgg Licensee Event y g'g Cause and Corrective Action To Prevent Recurrence e :3 :n a) v .c Report No. u) Eu O- (4 G) En C o

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1 830325 S 720 C 1 N/A ZZ 7,Z Z Z Z r Completing refueling and steam generator sleeving outage.

3 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 Ent C- Refueling 3- Automatic Scram Sheets for LER Fi D- Regulatory Restriction 4- Other (explain) (NUREG-0161)

E- Operator Training & License Exam

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

NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE Docket No. 50-301 Unit Name Point Beach Unit 2 Date July 7, 1983 Completed By C. W. Fay Phone 414-277-2811 Unit 2 was shut down during the entire report period as the 14-week steam generator sleeving and refueling outage drew to a close. Outage-related maintenance included the replacenent of primary coolant sampling isolation valve 2-955 and the completion of the steam generator sleeving.

On June 15 at 2100 hours0.0243 days 0.583 hours 0.00347 weeks 7.9905e-4 months it was discovered during core reloading that fuel assembly J69 was leaning in the core at an approximate angle of 30 from vertical. Another fuel assembly was substituted in the core in spite of the fact that there was no visual physical damage to J69.

The reloading of the core was completed on June 18 and the upper internals were installed on June 19. On June 23 containment isolation valve operability tests, safety injection signal actuation tests, auxiliary feedwater initiation test, and containment spray actuation sequence tests were performed. On June 26 the filling and venting of the reactor coolant system was completed and the primary heatup commenced. On June 28 cold rod drop tests were completed along with the first cycle on steam generator crevice flushing.

On June 16 at 2345 hours0.0271 days 0.651 hours 0.00388 weeks 8.922725e-4 months during fuel motion the sample pump P707A for radiation monitors 2RE-211 and 2RE-212, containment rad gas and air particulate monitors, was discovered out of service. On June 17 at 0130 hours0.0015 days 0.0361 hours 2.149471e-4 weeks 4.9465e-5 months a blown fuse was discovered in the power supply to P707A. This fuse was replaced and the system was returned to operation. The radiation monitoring system history file shows that P707A probably tripped at 2018 hours0.0234 days 0.561 hours 0.00334 weeks 7.67849e-4 months on June 16. This event is reportable in the format of a 14-day Licensee Event Report.

On June 21 safety injection pump 2P15A was being inspected for a seal problem and a broken shaft key was discovered. This is similar to a failure in November 1981. Further investigation into the cause of the pump failure mechanism is underway.

On June 27 during an attempt to equalize level in the safety injection accumulators the reactor coolant system was opened to the accumulator piping. This caused a pressurization of the reactor coolant system which caused a pressurizer pressure-operated relief valve to open. This event is being evaluated for reportability to the NRC at this time.

/g C Wisconsin Electnc eaara couraur 231 W. MICHIGAN, P.O. BOX 2046. MilnAUKEE, WI 53201 July 11, 1983 Director of Regulator, perations U. S. NUCLEAR REGULATORY COMMISSION Washington, D. C. 20555 Gentlemen:

MONTHLY OPERATING REPORTS POINT BEACH NUCLEAR PLANT Attached are monthly operating reports for Units 1 and 2, Point Beach Nuclear Plant, for the calendar month of June 1983.

Very truly yours,

/

Y 6CG f

Vice President-Nuclear Power C. W. Fay Attachments Copies to J. G. Keppler - NRC, Region III NRC Resident Inspector C. F. Riederer - PSCW

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ML19277C594

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SUMMARY

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