ML19256F296

Monthly Operating Rept for Nov 1979

ML19256F296
Person / Time
Site:	Point Beach
Issue date:	12/05/1979
From:	Burstein S WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML19256F294	List: ML19256F293 ML19256F296
References
NUDOCS 7912180449
Download: ML19256F296 (10)

Text

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OPERATING DATA REPORT e DOCKET NO. 50-266 DATE December 5,1979 COMPLETED DY SOL DURSTEIN TELEPHONE 414 277 2121 OPERATING STATUS

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

2. REPORTING PERIOQ: NOVEMDER 1979 . .

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 DEPENDADLE CAPACITY,(NET.MWE): . 495. . . . . t . .................. .

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

C7' NOT APPLICADLE CC)

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9. POWER LEVEL TO WHICH.RESTRICTEDs.IF ANY (NET MWE): NOT APPLiCADLE -

10. REASONS FCR RESTRICTIONSe (IF ANY): NOT APPLICADLE

$$ THIS MONTH '% YR TO DATE CUMULATIVE

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11. HOURS IN REPORTING PERIOD 720 8e016 79,488

12. NUMBER OF HOURS REACTOR WAS. CRITICAL 102.1 6e151.1 66,039.0

13. REACTOR RESERVE SHUTDOWN HOURS 125.9 135.3 574.9

14. HOURS GENERATOR ON LINE 0.0 Se991.4 63e928.4

15. UtHT RESERVE SHUTDOWN HOURS 200.9 207.2 590.6

16. GROSS THERMAL ENERGY "PiERATED (MWH) 0 8,879,112 90e245e727 q 17. GROSS ELECTRICAL FNERGY GENERATED (MWH) 0 3,039,190 30,466e830 e 18. NET ELECTRICAL ENERGY GENERATED (MWH) 0 2e898,940 29,033,694 y 19. UNIT SERVICE FACTOR 0.0 74.7 80.4 b3 .70. UNIT AVAILADILITY FACTOR. 27.9 77.3 81.2

• 21. UNIT CAPACITY FACTOR (USTNG MDC NET) 0.0 73.1 75.1

$ 23. UNIT FORCED OUTAGE RATE

22. UNIT CAPACITY FACTOR (USING DER NET) 0.0 0.0 72.8 5.6 73.5 3.2 g,

x 24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPEe DATEe AND CURATION OF EACHit I Unit scheduled to shut down on January 6, 1980, for five days to perform steam generator leak testing and on February 16, 1980, for ten days to perform steam generator leak testing and eddy current inspection.

25. IF SHUTDOWN AT END OF REPORT PERIODe ESTIMATED DATE OF STARTUP: DECEMDER le 1979 DATA REPORTED AND FACTORS CALCULATFD AS RFOUFSTFD IN NRC LETTFR DATED SEPTEMDFR 22e 1977

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OPERATING DATA REPORT ,

DOCKET NO. 50-301 DATE December 5,1979 COMPLETED BY SOL DURSTEIN TELEPHONE 414 277 2121 OPERATING STATUS

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

2. REPORTING PERIOD: NOVEMBER 1979 . .

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 DEPENDADLE CAPACITY (NET MWE): 495. . . . . . . . . . . . . . . . . . . . . . . . .

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

NOT APPLICADLE

9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWE): NOT APPLICADLE

10. REASONS FOR RESTRICTIONSe fIF ANY): NOT APPLICADLE THIS MONTH YR TO DATE CUMULATIVE

11. HOURS IN REPORTING PERIOD 720 8e016 64e273

12. NUMDER OF HOURS REACTOR WAS CRITICAL 716.5 7eU63.8 58,152.9

13. REACTOR RESERVE SHUTDOWN HOURS 0.4 16.5 166.1

14. HOURS GENERATOR ON LINE 715.4 6,988.2 56,983.0

15. UNIT RESERVE SHUTDOWN HOURS 0.0 18.6 106.4

16. GROSS THERMAL ENERGY CENERATED (MWH) le045e777 10,272,046 76,557,263

17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 353e400 3e519e370 25e944,480

18. NET ELECTRICAL ENERGY CENERATED (MWH) 337e250 3e356e943 24e724e620

19. UNIT SERVICE FACTOR 99.4 87.2 88.7

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20. UNIT AVAILADILITY FACTOR

21. UNIT CAPACITY FACTOR (USING MDC NET) 99.4 94.6 87.4 84.6 8 tt . 8 78.5 m 22. UNIT CAPACITY FACTOR (USING DER NET) 94.2 84.3 77.4

23. UNIT FORCED OUTAGE RATE 0.6 0.1 1.5 a 24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPEe DATEe AND DURATION OF EACH).

U Unit scheduled to shut down December 8 or 15, 1979, for one day to perform secondary side maintenance.

U1 Refueling shutdown scheduled for March 7, 1980, to last approximately five weeks.

25. IF SHUTDOWN AT END OF REPORT PERIODe ESTIMATED DATE OF STARTUP: NOT SHUTDOWN DATA REPORTFD AND FACTORS CAL Cill ATFD A% RFollESTFD TN NRC tETTFR DATFD SFPTFMDFR 22e 1977

UNIT SIIUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-266 UNIT NAME Point Beach Unit' 1 REPORT MONTII November, 1979 DATE December 5, 1979 COMPLETED BY Sol Burstein TELEPHONE 414/277-2121 c*

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7 791005 S 720 C 1 N/A 'N/A N/A -

1 3 4 F: Forced Reason: Method: Exhibit G-Instruc-5: 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) o E- Operator Training & License Exam Co F- Administrative 5 Exhibit I- Same AD-28B G- Operational Error (explain) Source (01-78) U 11- Other (explain)

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-301 UNIT NAME Point Beach Unit , 2 DATE December 5, 1979 REPORT MONTH November, 1979 COMPLETED BY Sol Burstein TELEPHONE 414/277-2121

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o 32 au "ao BR mae om en co No. Date g nc g jgg Licensee Event gg gy Cause and Corrective Action e am o a4 Report No. m Eu To Prevent Recurrence o~ m gmg g 8

5 791121 F 4 A 3 N/A EC IENERA The cause of the trip was deter-mined to be due to the failure of a capacitor in the "A" battery inverter which supplies the red instrument bus. The capacitor has been replaced. The unit was limite d to 223 MWe for 27 hours3.125e-4 days <br />0.0075 hours <br />4.464286e-5 weeks <br />1.02735e-5 months <br /> following the trip because of delta flux limitations.

1 3 4 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 Cys C- Refueling 3- Automatic Scram Sheets for LER File CZ) D- Regulatory Restriction 4- Other (explain) (NUREG-0161)

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

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DOCKET NO. 50-301 -

UNIT NAMF Point Beach Unit 2 ,

DATE December 5, 1979 COMPLETED BY Sol Burstein TELEPHONE 414/277-2121 AVERAGE DAILY UNIT POWER LEVEL MONTH November, 1979 AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL DAY MWe NET DAY MWe NET DAY MWe NET 1 485 11 476 21 425 2 489 12 485 22 186 3 488 13 485 23 355 4 489 14 484 24 484 5 489 15 484 25 480 cps 6 487 16 484 26 482 CD CD 7 488 17 486 27 484

{, 8 488 18 486 28 481 9 486 19 482 29 483 10 486 20 485 30 481 31 ---

AD-28A (1-77)

NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE Docket No. 50-266 Unit Name Point Beach Unit 1 Date December 5, 1979 Completed By Sol Burstein Telephone 414/277-2121 Unit 1 was shut down on October 5, 1979, for Refueling 7.

The unit was in the final phase of plant startup as of November 30, 1979.

Steam generator tube pulling as described in the last report was completed this period. Portions of three tubes were removed from the "A" steam generator; included was a tube with a known defect in the portion of the tube within the tubesheet; i. e., a deep crevice defect; a nondefective tube in the tubesheet area where deep crevice cracking has occurred; and a nondefective tube from an area where deep crevice cracking has not been observed. The characteristics of all three tubes have been investigated. Full details of these findings were made available tc and were discussed with the NRC.

An 800 psi leak test was performed on both the "A" and "B" steam generators both prior to and after explosive tube plugging following the eddy current program. In the "A" steam generator a tube with a 91% defect was found to be leaking in the test conducted prior to plugging and a tube with no eddy current identified defect was found to be dripping during the test conducted after plugging. No leaking plugs were identified during either leak test on the "A". The initial 800 psi leak test in the "B" steam generator produced four leaking plugs and three leaking tubes. One of the leaking tubes was previously identified by eddy current as having a 92% defect. The other two tubes dripping approximately one drop every ten seconds were not previously identified as defective by the eddy current program. All the leaking tubes were explosively plugged and the leaking plugs were weld repaired. The second test, that following repairs, produced no further leaking tubes. The following is a summary of the plugging that occurred during the refueling.

1608 340

2 "A" Steam "B" Steam Generctor Generator 69 62 Tubes with defects >40% (includes one defective tube removed from "A" for evaluation) 3 3 Tubes with defects <40%

2 -

Good tubes removed for evaluation 1 2 Leaking tubes, no eddy current defects 2 1 Good tubes mistakenly plugged 77 68 TOTAL Licensee Event Report No. 79-017/0lT-0 describing the steam generator eddy current program, tube removal, tube plugging, plug repair, etc., has been filed.

The reactor coolant system was filled and vented on November 13, 1979. Steam generator tube crmvice boilout commenced on November 14, 1979. A total of 14 cycles of boilout were conducted, each cycle consisting of heating up the tubesheet and several hundred gallons of water on the secondary side (utilizing the reactor coolant system and pump heat), then quickly depressurizing the secondary side while simultaneously adding cold water to cool the water above the tubesheet. The 23" thick hot tubesheet then induced boiling of the water deep in the crevice area surrounding the tubes , forcing out i apurities. A detectable amount of sodium / phosphate was removed each cycle, with a declining trend in magnitude as the tests progressed.

A bubble was established in the pressurizer and pre-critical testing was completed by November 21, 1979. Some experience with control rods stuck in their fully inserted position was encountered; however, after allowing temperatures to reach equilibrium and allowing the mechanisms to soak for a period of time, the control rods moved freely. The cause of the problem was considered to be due to oxidation caused by humid conditions in the control rod housings during the extended outage and/or differential thermal expansion of reactor components during heatup.

Following a required NRC review of steam generator eddy current results, tube plugging and the results of the metallurgical examination of the pulled tubes, NFC permission to take the reactor critical was granted and initial criticality was achieved at 5:50 p.m. on November 26, 1979.

Rod worth testing, flux mapping and temperature coefficient tests were completed on November 28, 1979.

An eddy current inspection of the secondary plant No. 4 feedwater heater tubes revealed only a small number of scattered defects. These defects consisted generally of fretting at the supports. A random sample inspection to 1608 341

3 check tube thinning showed that thinning may be occurring, but could not be verified with the equipment then available.

A leak test was also performed and no leakers were identified.

A leak check of the moisture separator reheaters was performed and two leaking tubes and one leaking plug were identified in the "B" moisture separator reheater. All general maintenance of the moisture separator reheaters has been completed.

Replacement of steam turbine crossunder and extraction carbon steel piping with stainless steel piping was completed this outage.

Following the discovery that certain terminal taping done during construction was of marginal quality, retaping of all four of the containment recirculation fan motor terminals according to Westinghouse specifications has been completed. Licensee Event Report No. 79-018/0lT-0 has been filed on this item.

Work on IE Bulletin Nos. 79-02, anchor bolt inspection, and 79-14, seismic analysis for as-built safety related piping systems, was completed in the Unit 1 containment; work outside containment continues. An engineering analysis in accordance with IE Bulletin No. 79-02 indicated that an anchor in the "A" steam generator auxiliary feedwater line did not meet design safety factor requirements. The anchor has been permanently modified to meet its functional require-ments. Licensee Event Report No. 79-020/01T-0 has been filed on this item.

Licensee Event Report No. 79-019/0lT-0 has been filed describing the inadvertent dilution of the reactor coolant system boron concentration below the Technical Specification limit of 1800 ppm while in the refueling condition. As the result of a scheduling oversight, the "A" steam generator secondary side was filled with water prior to plugging the cold leg side of the removed tubes. The water leaking from the secondary side to primary side resulted in some dilution of the primary system boron concentration despite several batch additions of boric acid to the system during the event.

Count rate was monitored by several means during the period it took to stop the leakage. At no time was the 10% minimum shutdown margin violated.

Work has been initiated on the construction of an on site radioactive waste storage vault.

A 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> load test of the site emergency Diesel generators in accordance with the requirements of IE Bulletin No. 79-23 was satisfactorily completed on November 7 and 9, 1979.

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

I608 342

/

NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE Docket No. 50-301 Unit Name Point Beach Unit 2 Date December 5, 1979 Completed By Sol Burstein Telephone 414/277-2121 Unit 2 was base loaded for 95% of the period with two load reductions and one inadvertent trip from full power.

Unit 2 load was reduced to 460 MWe net for two and one-half hours on November 1, 1979, in order to run a performance test on the secondary plant No. 4 feedwater heater. A second load reduction to 340 MWe net in order to perform routine turbine stop valve testing occurred on November 11, 1979. On November 21, 1979, at 9:11 p.m., the unit tripped from full power following receipt of a first-out alarm of a "B" steam generator feed flow / steam flow mismatch. Immediately prior to the trip, a DC ground fault and spike to zero of the red instrument bus (which controls the "A" steam generator level) occurred. The channel was shifted to the alternate bus and recovery of the unit commenced at 0:25 a.m. on November 22, 1979. Due to delta flux restrictions, the unit was held at 223 MWe net for 27 hours3.125e-4 days <br />0.0075 hours <br />4.464286e-5 weeks <br />1.02735e-5 months <br /> prior to attaining full power at 1:25 p.m. on November 23, 1979.

The cause of the trip was determined to be due to the failure of a capacitor in the "A" battery inverter, which supplies the red instrument bus. The capacitor has been replaced and power for the red instrument bus shifted back to the "A" battery inverter.

Following the discovery during the Unit 1 refueling outage that certain terminal taping done during construction was of marginal quality. Taping of three of four contain-ment recirculation fan motor terminals according to Westing-house specifications has been completed. Taping of the final fan will be performed during the next outage to limit personnel radiation exposure. Licensee Event Report No.

79-018/0lT-0 has been prepared on this item.

An 18 to 30 gallon per hour leak within containment on November 22, 1979, was determined to be due to packing leakage of an auxiliary charging valve. The packing was tightened and subsequent inspection has indicated the problem to be corrected.

No other major safety-rel'ated maintenance was performed during the period.

1608 343