ML20083L255

Monthly Operating Repts for Mar 1984

ML20083L255
Person / Time
Site:	Point Beach
Issue date:	03/31/1984
From:	Fay C WISCONSIN ELECTRIC POWER CO.
To:	NRC
References
NUDOCS 8404170194
Download: ML20083L255 (10)

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. F UNIT SHUTDOWNS AND POWER REDUCTIONS ' DOCKET NO. 50-266 UNIT NAME Point Beach Unit 1 REPORT MONTH March, 1984 DATE April 6. 1984 COMPLETED BY C. W. Fay TELEPHONE 414/277-2811 I '

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0- N oC4 Ev c i e4 . ,4 m c ~4 o ee en '

e su o com um ce g ay Licensee Event y l

No. Date a jjg g'g Cause and Corrective Action 1

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v .c Report No. u) eo To Prevent Recurrence

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l 3 831001 S 744 C 1 N/A ZZ EZZZZZ Continuation of 26-week refueling j l and steam generator replacement '

outage. ,

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i F: Forced Reason: 3 S: Scheduled A- Equipment Failure (explain)

Method: Exhibit G-Instruc- !

1- Manual tions for Prepar- l B- Maintenance or Test 2- Manual Scram ation of Data Entry l 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 D 283 Exhibit I- Same G- Operational Error (explain) Source (01-78) H- Other (explain)

, .. .- _ _ _ - - . - - - - ~ _ _ . .- . - . _ - -_- . _ . . , _ . - - - _ - _ . . .. .--

DOCKET NO. 50-266 UNIT NAME Point Beach Unit 1 DATE April 6, 1984 COMPLETED BY C. W. Fay TELEPHONE 414/277-2811 AVERAGE DAILY UNIT POWER LEVEL MONTH March, 1984 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 -4 2 -2 12 -2 22 -4 3 -2 13 -2 23 -4 4 -2 14 -3 24 -4 5 -2 15 -3 25 -4 6 -2 16 -3 26 -3 7 -2 17 -4 27 -3 8 -2 18 -4 28 -3 9 -2 19 -4 29 -3 10 -2 20 -4 30 -3 31 -3 AD-28A (1-77)

/

l NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE Docket No. 50-266 Unit Name Point Beach Unit 1 Date April 6, 1984 Prepared By C. W. Fay Telephone 414/277-2811 Unit 1 completed weeks 23 through 26 of the refueling and steam generator replacement outage.

An inspection of the reactor vessel outlet nozzle-to-shell welds was performed using remote mechanized ultrasonics. This exam was part of the second ten-year interval firnt period inservice inspection program requirements. Four indications in the " A" nozzle and seven indications in the "'T . nozzle were recorded, sized, and evaluated. On 02/28/84, Southwest Research Institute notified Wisconsin Electric that there was an indication in each of the outlet nozzle welds that exceeded the Code allowable size. The indications are located in the root area of the welds.

It is believed that the reflectors are due to entrapped foreign material in the weld and/or adjacent base metal repair area, and have been there since the vessel was fabricated and are not indicative of service-induced flaws. A Licenseo Event Report was draft 1 for submittal to the NRC.

On 02/25/84, a visual inspection of the control rod guide tube split pins revealed that three nuts were missing. The visual inspection was performed after an ultrasonic inspection of the pins identified cracks in 67 of 74 pins (two pins per guide tube).

The UT indications on the shank-to-collar region of the CRGT support pins and the three missing support pin nuts and shanks at Point Beach Unit 1 are judged not to be a cafety concern due either to CRGT misalignment preventing RCCA insertion or the adverse effects of loose parts on safety systems and components. The long-range solution to this problem is to replace the pins at a future outage when the tooling and parts are available. A Licensee Event Report was drafted for submittal to the NRC.

Minor insulation work on the steam generators was completed <

and the equipment hatch was reinstalled. The core barrel and '

lower internals were removed from the reactor vessel for further When the par examination par examination of the cold leg nozzles.

was complete, the core barrel and lower internals were replaced and the core reload began on Monday, 03/05/84.

The reactor was refueled and the upper internals were put back in place. A problem with debris in the upper internals was discovered when difficulty was encountered in latching the control rods. The upper internals were again removed and the debris was cleaned away from them. Dobris removal via the "hydrolaser" method was completed on 03/24/84 and the internals were replaced.

Thirteen of the 33 full-length rod control cluster guide tube assemblies had one or two particles left in them. On 03/25/84, the control rods were latched. The head was again set in place and tensioned.

On 03/30/84, the pump-up of containment commenced for the integrated leak rate test (ILRT). The temporary structures erected for the steam generator replacement were disassembled and removed along with the Morrison-Knudson health physics operation being shut down. The containment was completely turned back to Point Beach Nuclear Plant and the only remaining job for Morrison-Knudsen is the steam generator shim gap measurements to be taken during heat-up.

Safety-related maintenance performed during the period included repairing the pressurizer power-operated relief valves, modifying the control room control panels, repairing the pressurizer spray valve, modifying the solenoid valves on the main feed regulating valves, inspecting / repairing the "A" and "B" component cooling pumps, inspecting the containment spray pumps, and repairing the "B" loop RTD bypass manifold outlet isolation valve.

OPERATING DATA REPORT DOCKET NO. 50-301 DATE April 6, 1984 COMPLETED BY C W. FAY TELEPHONE 414 277 2811 OPERATING STATUS

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

2. REPORTING PERIOD: MARCH 1984 . .

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

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

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

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

7. MAXIMUM DEPENDABLE CAPACITY (NET MWE): 485. ........................

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

NOT APPLICABLE

9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MUE): NOT APPLICABLE

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

11. HOURS IN REPORTING PERIOD 744 2,184 102,265

12. NUMBER OF HOURS REACTOR WAS CRITICAL 744.0 2,184.0 90,612.2

13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 198.3

14. HOURS GENERATOR ON LINE 744.0 2,184.0 89,086.8

15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 182.7

16. GROSS THERMAL ENERGY GENERATED (MWH) 1,125,590 3,288,250 124,183,027

17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 379,060 1,108,710 42,068,540

18. NET ELECTRICAL ENERGY GENERATED (MWH) 362,985 1,061,415 40,062,215

19. UNIT SERVICE FACTOR 100.0 100.0 87.1 '

20. UNIT AVAILABILITY FACTOR 100.0 100.0 87.3

21. UNIT CAPACITY FACTOR (USING MDC NET) 100.4 100.2 79.7

22. UNIT CAPACITY FACTOR (USING DER NET) 98.2 97.8 78.8

23. UNIT FORCED OUTAGE RATE 0.0 0.0 1.4

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

None

25. IF SHUTDOWN AT END UF REPORT PERIOD, ESTIMATED DATE OF STARTUP: NOT SHUTDOWN DATA REPORTED AND FACTORS CALCULATED AS REQUESTED IN NRC LETTER DATED SEPTEMBER 22, 1977

UNIT SHUTDOl/NS AND POWER REDUCTIONS DCCKET NO. 50-301 '

UNIT NAME Point Beach Unit 2 REPORT MONTH March, 1984 DATE April 6, 1984__

. COMPLETED BY C. W. Fay TELEPHCNE 414/277-2811 54 i

c 4 tD o u o~ N oC# G9 C -

.-4 -4 m c -4 o ee en e v 54 o eve vo co No. Date g ag a j#y Licensee Event g ,o, o'g Cause and Corrective Action '

j t-, :s :r: e v .c Report No. un EO To Prevent Recurrence  :. ,

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l F: Forced 3 S: Scheduled Reason: ,

Method: Exhibit G-Instruc- f l

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-283 Exhibit I- Same G- Operational Error (explain) Source (01-78) H- Other (explain)

DOCKET NO. 50-301 UNIT NAME Point Beach Unit 2 DATE April 6, 1984 COMPLETED BY C. W. Fay (

TELEPHONE 414/277-2811 AVERAGE DAILY UNIT POWER LEVEL MONTH March, 1984 AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL DAY MWe NET DAY MWe NET DAY MWe NET 1 490 11 488 21 488 2 489 12 489 22 486 3 490 13 490 23 486 4 490 14 488 24 487 5 490 15 490 25 484 6

487 16 490 26 467 7 490 17 488 27 487 8 489 18 489 28 488 9 490 19 489 29 488 10 490 20 489 30 488 31 488 AD-28A (1-77)

NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE Docket No. 50-301 Unit Name Point Beach Unit 2 Date April 6, 1984 Prepared By C. W. Fay Telephone 414/277-2811 Unit 2 operated at approximately 486 MWe net throughout the period with no significant load reductions.

Primary-to-secondary leakage remained stable at less than 10 gallons pc r day.

On 03/26/84, at 0843 hours0.00976 days <br />0.234 hours <br />0.00139 weeks <br />3.207615e-4 months <br />, Unit 2 reached the 42 billion kilowatt-hour mark. Also, On 03/26/84, the plant circulating water system was removed from the ice-melt mode of operation.

On 03/21/84,"the "A" and "D" moisture separator reheaters were isolated because of-tube leaks and operation continued with 2 moisture separator reheaters.

The pipe snubber'in location ID No. 2HS-M75 as listed in Technical Specification Table 15.3.13-1 *as removed prior to ob-ta!ning a Technical Specification change to allow its removal.

The snubber was reinstalled withini72 hours of the event date to satisfy the Limiting Condition of Operation specified in

. Technical Specification 15.3.13.2. The snubber had been removed

~

as part of a major modification to the pressurizer relief valve piping supports based on reanalysis required by NUREG-0737. At no time was the system in an unsafe or unanalyzed condition. A Technical Specification change to delete the snubber has been initiated. A Licensee Event Report has been submitted to the NRC.

Safety-related maintenance included repairing the "B" steam generator pressure bistable 2PC-483A and repairing a snubber on the safety injection line.

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WNSCORSin Electnc ma comr 231 W. MICHIGAN, P.O. BOX 2046, MILWAUKEE, WI 53201 April 10, 1984 Director of Regulatory Operations 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 March 1984.

Very truly yours,

- h9 '

(?c d 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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