ML20081L310

Monthly Operating Repts for Oct 1983

ML20081L310
Person / Time
Site:	Point Beach
Issue date:	11/04/1983
From:	Fay C WISCONSIN ELECTRIC POWER CO.
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8311160084
Download: ML20081L310 (9)

Text

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DOCKET NO. 50-266 T

UNIT NAME Point Beach Unit 1 ,

t DATE November 4, 1983 l COMPLETED BY C. W. Fay g-l TELEPHONE 414/277-2811 AVERAGE DAILY UNIT POWER LEVEL October f MONTH AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL DAY MWe NET _ DAY MWe NET DAY MWe NET 1 4 11 -2 21 -2

!' 2 -9 12 -2 22 -2 3 -3 13 -2 23 -2

=I- 4 -2 14 __

24 -1

5 -2 15 -2 25 -2 16 26 6 -2 -2 i 7 -2 17 -2 27 -2 8 -2 18 -2 28 -2 9 -2 19 -2 29 -2

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-, 10 -2 2d -2 30 -2 l

31 -2 e

8311160084 831104 PDR ADOCK 05000266

? AD-28A (1-77)

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UNIT SIIUTDOWNS AND POWER REDUCTIONS DOCKET MO. 50-266 ~

UNIT NAME Point Beach Unit 1 REPORT MONTH October DATE November 4, 1983 COMPLETED BY C. W. Fay TELEPIIONE 414/277-2811 en k

c w tn o u O

as vu "co St co v m Pe eo co No. Date g e

gg am g

o jgy oa Licensee Event Report No.

y y Cause and Corrective Action o- a; emc m so To Prevent Recurrence o

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Q 3 801001 S 740.7 C 1 N/A ZZ ZZZZZ2 Commenced 26-week refueling and steam generator replacement outage.

F: Forced Reason: 3 4 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 AD-28B Exhibit I- Same -

G- Operational Error (explain) Source (01-78) II- Other (explain)

OPERATING DATA REPORT DOCKET NO. 50-266 -

DA1E November 4, 1983 COMPLETED BY C. W. FAY TELEPHONE 414 277 2811 OPERATIN6 STATUS

1. UNIT NAME: POINT BEACH NUCLEAR PLANT UNIT 1 . NOTES $ l I

2. REPORTIN6 PERIOD: OCTOBER 1983 . .

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

4. NAMEPLATE RATIN6 (GROSS MUE): 523.8 . . i

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

6. MAXIMUM DEPENDABLE CAPACITY (6ROSS MUE): 519. . . I

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

8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORT, 6IVE REASONS: j NOT APPLICABLE

9. POWER LEVEL TO UNICH RESTRICTED, IF ANY (NET MUE): Nui APPLICABLE i

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

11. HOURS IN REPORTING PERIOD 745 7,296 113,832

12. NUMBER OF HOURS REACTOR WAS CRITICAL 3.6 6,506.2 94,078.5

13. REACTOR RESERVE *bdTDOWN HOURS 0.0 1.4 625.4

14. HOURS 6ENERATOR 6N LINE 3.3 4,499.2 91,607.5

15. UNIT RESERVE SHUTBOUN HOURS 0.0 0.0 793.5

16. 6ROSS THERMAL ENER6Y 6ENERATED (MUH) 1,496 7,586,323 123,535,3'2 ,

17. GROSS ELECTRICAL ENER6Y 6ENERATED (MUN) 500 2,520,190 41,395,'.e0

18. NET ELECTRICAL ENER6Y 6ENERATED (MUH) 0 2,383,497 39,365,215

19. UNIT SERVICE FACTOR 0.4 89.1 80.5

20. UNIT AVAILABILITY FACTOR 0.4 89.1 81.2

21. UNIT CAPACITY FACTOR (USING MDC NET) 0.0 66.0 70.7

22. UNIT CAPACITY FACTOR (USIN6 DER NET) 0.0 65.7 69.6 .

23. UNIT FORCED OUTA6E RATE 0.0 0.1 2.6

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

NONE

25. IF SHUTD99N AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: MARCH 30, 1984 DATA REPORTED AND FACTORS CALCULATED AS REQUESTED IN NRC LETTER DATED SEPTEMBER 22, 1977

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NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE Docket No. 50-266 Unit Name Point Beach Unit 1 Date November 4, 1983 1 Completed By C. W. Fay Telephone 414-277-2811 i

i Unit 1 was in a coastdown status at the beginning of the 1

period in preparation for the eleventh refueling shutdown and  ;

t steam generator replacement outage. The generator was taken off line at 0320 hours0.0037 days <br />0.0889 hours <br />5.291005e-4 weeks <br />1.2176e-4 months <br /> on October 31, 1983. .. Hot rod drop testing was i completed 0340 hours0.00394 days <br />0.0944 hours <br />5.621693e-4 weeks <br />1.2937e-4 months <br /> that same day. The reactor vessel core was

] unloaded, the head rein' stalled,>and primary system put in layup

with a nitrogen gas cover.

In-containment construction'during the period included l shield wall removal in both "A"'and "B" steam generator cubicles,

i containment crane upgrade, scaffolding support for shielding on the

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j primary loops, and construction of grillage and bridgework over.the reactor vessel cavity all in preparation for the changeout of the two steam generators.

, Among the items under construction on the secondary plant

! are the replacement of the Nos. 4 A&B feedwater heaters, the

, replacement of "A", "B", "C", and "D" moisture-separator-reheater l tube bundles, NDE inspection of the extraction steam lines, cleaning d

and inspection of the main feed pump motors, and the cleaning and lapping of the main steam safety valves.

j Other safety-related testing and maintenance completed

+

during the period included the 4D emergency diesel annual inspection, 2 maintenance to the spare residual heat removal pump, inspection of residual heat removal heat exchanger lHX-llA, inservice testing ~of-i the auxiliary feedwater system steam-driven pumps and valves,-and flow tests for the high and low-head safety injection pumps.

, During an initial review of Unit 1 refueling" leakage tests:

of containment isolation valves'on October 17, 1983,-three. valves were discovered to have leakage such that-the limit-in Technical i . Specification 15.4.4.3.B would have been-exceeded.  ; The three valves-j include the_ containment purge exhaust valve (3212), the containment i purge supply valveL(3245), and the charging-line check valve (370).

. This event is reportablecin accordance with Technical Specification.

j. 15.6.9.2.A.3, " abnormal degradation discovered in fuel: cladding, reactor coolant-pressure boundary, or-primary l containment", and a.

14-day LicenseesEvent Report will-be prepared forithe'NRC upon-completion.ofzall containment isolation valve testing.- The Residents '

Inspector was notified of this event.

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-301 UNIT NAME Point Beach Unit 2 REPORT MONTH October DATE November 4, 1983 COMPLETED BY C. W. Fay TELEPHONE 414/277-2811 m

u C M@o v o

as au "co St eae Po am En ao No. Date g (j g m jjg Licensee Event gg gg Cause and Corrective Action e am o or Report No. m so To Prevent Recurrence Q~ M emC o E 3 U O

4 831011 F 5.7 A 3 N/A EB INSTRU Voltage spike in the red instrument bus caused by a capacitor failure in inverter 2DY01 sent spurious "B" steam generator feed flow trip sig-nal. The capacitor was replaced.

1 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 AD-28B "

Exhibit I- Same G- Operational Error (explain) Source (03 -78 ) - H- Other (explain)

1

-=,1 DOCKET NO. 50-301 UNIT NAME Point Beach Unit 2 j DATE November 4, 1983 COMPLETED BY C. W. Fay l l

TELEPHONE 414/277-2811 1 AVERAGE DAILY UNIT POWER LEVEL MONTH October AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL DAY MWe NET DAY MWe NET DAY MWe NET 1 491 11 340 21 489 2 489 12 488 22 491 1

3 488 13 491 23 491 4 '488 14 488 24 491 5 489 15 491 25 490 6 488 16 491 26 491 -

l 7 489 17 492 27 490 8 489 18 489 28 492 9 489 19 492 29 490 10 489 20 492 30 490 31 490 AD-28A (1-77)

OPERATING DATA REPORT '

DOCKET NO. 50-301 DATE November 4, 1983 COMPLETED BY C. W. FAY TELEPHONE 414 277 2811 1 OPERATIN6 STATUS

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

l

2. REPORTIN6 PERIOD: OCTOBER 1983 . .

l

3. LICENSES THERNAL POWER (NUT): 1518. . .

4. NAMEPLATE RATING (6ROSS MUE): 523.8 . .

5. DESI6N ELECTRICAL RATING (NET MWE): 497. . .

4. NAXINUM DEPENSABLE CAPACITY (6ROSS MWE): 519. . . l

-7. MAXIMUM DEPENSABLE CAPACITY (NET MWE): 495. ........................ l

8. IF CHANGES OCCUR IN CAPACITY RATIN6S (ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONS:

NOT APPLICABLE l

9. POWER LEYEL 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 REPORTIN6 PERIOB 745 7,296 98,637

12. NUNDER OF HOURS REACTOR WAS CRITICAL 741.5 4,906.1 86,964.2 l

13. REACTOR RESERVE SHUTDOWN HOURS 0.0 1.5 198.3 l l' 14. NOURS SENERATOR ON LINE 739.3 4,783.6 85,438.8 l

15. UNIT RESERVE SHUT 90WN HOURS 0.0 1.5 182.7

14. GROSS THERNAL ENER6Y SENERATED (MWH) 1,115,645 7,169,793 118,685,387

17. BROSS ELECTRICAL ENER6Y 6ENERATED (NWH) 378,240 2,413,030 40,214,430 1

18. NET ELECTRICAL ENER6Y GENERATED (NWH) 361,310 2,298,630 38,287,597 l

19. UNIT SERVICE FACTOR 99.2 65.6 86.6

-20. UNIT AYAILABILITY FACTOR 99.2 65.6 86.8 i

21. UNIT CAPACITY FACTOR (USIN6 MBC NET) 98.0 63.6 79.0 l

22. UNIT CAPACITY FACTOR (USING DER NET) 97.6 63.4 78.1 )

'23. UNIT FORCEB OUTA6E RATE 0.8 0.8 1.5 J

24. SHUTBOUNS SCHEBULEB OVER NEXT 4 MONTHS (TYPE, DATE, AND DURATION OF EACH):

NONE

25. IF SHUT 90WN AT EN8 0F REPORT PERIO3, ESTINATED BATE OF STARTUP: NOT SHUTDOWN

. DATA REPORTES AND FACTORS CALCULATED AS RE00ESTED IN NRC LETTER 3*TED SEPTEMBER 22, 1977

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NARRATIVE sui 4 MARY OF OPERATING EXPERIENCE Docket No. 50-301 Unit Name Point Beach Unit 2

-Date November 4, 1983 Completed By C. W. Fay Telephone 414-277-2811 Unit 2 operated at approximately 490 MWe net throughout the period with'one unplanned outage. On October 10, 1983 at 0617 hours0.00714 days <br />0.171 hours <br />0.00102 weeks <br />2.347685e-4 months <br /> the unit experienced a turbine and reactor trip. The trip was initiated by a capacitor failure in inverter 2DY01 which sent a voltage spike to the red instrument bus causing a spurious "B" steam generator. feed flow alarm. Operators deenergized the inverter after shifting to an alternate power supply and commenced EOP-5A and EPIP 1.1.

While attempting to return the generator back on line, the unit experienced a second reactor trip from 9% thermal power caused by a low-low steam generator level. At 1057 hours0.0122 days <br />0.294 hours <br />0.00175 weeks <br />4.021885e-4 months <br /> the reactor was taken critical, at 1158 hours0.0134 days <br />0.322 hours <br />0.00191 weeks <br />4.40619e-4 months <br /> the generator went back on line, and the unit returned to full power at 1515 hours0.0175 days <br />0.421 hours <br />0.0025 weeks <br />5.764575e-4 months <br />, approximately nine hours after.the initial trip.

The primary-to-secondary leakage remains at less than ten gallons per day.

During the performance of the auxiliary feed pump tests, motor-operated valve 2MOV-4006, which provides-alternate supply from the service water system to the pump suction, tripped upon stroking. The thermal overload valves were reset and the valve-stroke tested satisfactorily. This event was not considered reportable.

Other safety-related testing completed-during the period included inservice testing of the.auxiliaryffeed system pumps and valves, inservice testing.ofqthe containment accident fan coolers, and the inservice testing of(the.high-head.safetyy injection pumps. ,

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v Sin Electnc roata couranr 231 W. MICHIGAN, P.O. BOX 2046, MILWAUKEE, WI 53201 November 9, 1983 Director of Regulatory Operations U. S. NUCLEAR REGULATORY COMMISSION Washington, D. C. 20555 Gentlemen:

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

Very truly yours, YbU Vice President-Nuclear Power C. W. Fay Attachments Copies to J. G. Keppler - NRC, Region III NRC Resident Inspector C. F. Riederer - PSCW 8+7 i

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