ML19289D777

Monthly Operating Rept for Feb 1979

ML19289D777
Person / Time
Site:	Point Beach
Issue date:	03/02/1979
From:	WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML19289D773	List: ML19289D771 ML19289D777
References
NUDOCS 7903140378
Download: ML19289D777 (8)

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OPERATIrlG DAT' PEPO T

• DOCxET NO. 50-301 DATE March 2, 1979 COMPLETED BY WISCOrdblN ELECTRIC POWER CO.

TELtPHONE OPERATING STATUS

1. UNIT IIAME: POINT BEACH tJUCLEAR PL M !T UNIT 2 . !OTES .

2. REPORTING PERIOD: FEBRUARY 1979 . .

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

4. NAMEPLATE RATIflG (GROSS IML): 523.8 . .

5. DESIGN ELECTRICAL HATING (i :E T Me ): 497. . .

6. MAXIMU'* DEPF NOAHLE C ADICITY (GROSS MhE): bl9. . .

7. MAXIMU:' DEPENDABLE CAP? CITY (NET "WE): 495. . . . + - . . . . . . , , . . . . . . . . . .

8. IF CHANGES OCCUR III CAP WITY RATINGS (ITEMb t .U' iB E R 3 THh0VGH 7) Sli1CE LAST H-POETe GIVE i' t ASO: ' <

• NOT APPLICABLE

9. POWER LEVEL TO nHICH PESTPIClEDe IF ANY (i 'ET MM. ) : ' :O T AP"LICABLE

10. REASONS FC7 i'EST F ICT ION 5 e (IF AtlY): ' :O T APPLICAHLE THIS MONTH YR TO DATE CUWL AT IVE

11. HOURS IN REPOx TIl fG PEriIOD 672 le410 b7ec/0

12. IlUMBER OF HDUPS dEACTOF WAS CRITICAL o72.0 le410.0 5 2 r 5 0': . 1

13. REACTOR 1E5r V, SHUTDOWN HDURL 0 . '; 0.0 149.0 14 HOURS GEN!RATOL i il L!' E 672.0 1,43e.U 517410.6 lb. UNIT' RES' R'/L $HUTDOM1 HOURb 0.u 0.. 67.E

16. GROSS THERMAL FN_PGY G: J r: A T: D (!AWH) laPldr.47 2r126eb24 06e41'r791

17. GRO5~ ELt CTRICAL EN-FGY T tl AT'TD (MnH)

. 343r1b0 723rc70 23,198,480

18. NET EL;:CTRICAL HJi'GGY GD ; .h AT! D (MWH) 323,6::5 092e769 2.'rooJe400

19. UNIT SERVICE FACTOR 10s.1 10 . 89.1

20. UNIT AV"41LABIL:TY FACFOR 10 - . 10 ' . 89.5

21. UNIT CAPACITY FACTOR (USING MDC l JET) 96.o VS., 7e.2 2?. UNIT CAP,", CITY FACTOR (USING DER r 1.T ) 98.4 98 4 77.0

23. UNIT FORCED OUTAGE R .' T L 0.o U.. 1.o

24. SHUTDOWNS : CHE DUL'. s OV;.R N ..X T 6 MD'1THd (TYPE, DAl r MiD uuRATIOtj .F EACH):

Refueling maintenance shutdown scheduled for March 23, 1979, to last approximately three and one-half weeks.

25. IF SHUTDOWN AT Eliv GF REPO:<T Pt.'InDe ESTIMA~LD _ i; OF STAP;Up: r10 r LHm Dom t DAT? PEPOrtTED MO F ACTOH3 C AL jut iiED '5 Wi.GV._5T: D Ifl

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DOCKET NO. 50-266 ,

UNIT NAME Point Beach Unit 1 DATE March 2, 1979 COMPLETED BY Wisconsin Electric Power Co.

TELEPHONE AVERAGE DAILY UNIT POWER LEVEL MONTH February, 1979 AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL DAY MWe NET DAY MWe NET DAY MWe NET 1 405 11 491 _

21 493 2 488 12 485 22 492 3 488 13 488 23 494 4 475 14 484 24 492 5 488 15 486 25 490 6 486 16 484 26 489 7 487 17 482 27 493 8 471 18 487 28 494 9 486 19 489 29 ---

10 484 20 489 30 ---

3x ---

AD-28A (1-77)

DOCKET NO. 50-301 ,

UNIT NAME Point Beach Unit 2 DATE March 2, 1979 COMPLETED BY Wisconsin Electric Power Co.

TELEPHONE AVERAGE DAILY UNIT POWER LEVEL MONTH February, 1979 AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL DAY MWe NET DAY MWe NET DAY MWe NET 1 473 11 492 21 495 2 492 12 484 22 494 3 495 13 487 23 496 4 489 14 490 24 490 5 492 15 491 25 488 6 492 16 486 26 485 7 489 17 489 27 488 8 480 18 432 28 487 9 487 19 496 29 ---

10 483 20 493 30 ---

31 ---

AD-28A (1-77)

NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE Docket No. 50-266 Unit Name Point Beach Unit 1 Date March 2, 1979 Completed By Wisconsin Electric Power Company Unit 1 was base loaded nearly 100% of the period with only four load reductions.

Freezing of the circulating water intake crib necessitated seven and one-half hours of reduced power operation for Unit 1 on February 1, 1979. After indications of freezing problems became evident, Unit 1 load was reduced to 470 MWe at 6:35 a.m., then to 250 MWe at 7:45 a.m., and finally it became necessary to reduce Unit 1 load to 165 MWe for about five and one-half hours. About noon the freezing problems were overcome and return to full power commenced at 12:45 p.m.

Full power was achieved about 2:00 p.m., February 1, 1979.

Load was reduced to 340 MWe for two and one-half hours on February 4, 1979, to conduct turbine stop valve tests.

Load was reduced about 5-10 MWe on two occasions totalling about 38 hours4.398148e-4 days <br />0.0106 hours <br />6.283069e-5 weeks <br />1.4459e-5 months <br /> to keep the discharge temperature from exceeding an 890F environmental limit applicable under normal operating conditions.

Primary-to-secondary leakage in the "A" steam generator gradually declined from 56 to 30 gallons per day over the period.

A 14-day reportable occurrence (Licensee Event Report No. 79-001/0lT-0) took place when radioactive gas was released while the K10B cryogenic system gas compressor was being returned to service at 6:19 p.m., February 19, 1979. As the compressor discharge valve was opened, the operator heard gas escaping through a vent valve inadvertently left open.

He immediately closed the vent valve, isolating the release.

The release was properly monitored, and the release rate was a little less than 3% of the permitted annual average release rate of 0.2 Curies per second. The total release was about 1 Curie.

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

NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE Docket No. 50-301 Unit Name Point Beach Unit 2 Date March 2, 1979 Completed By Wisconsin Electric Power Company Unit 2 was base loaded nearly 100% of the period with only two load reductions. Maximum available output of the unit has declined about 2% since commencing core stretch operation on February 19, 1979.

Freezing of the circulating water intake crib made it necessary to reduce Unit 2 load to 450 MWe for six and one-half hours on February 1, 1979.

Load was reduced to 405 MWe for 20 minutes to conduct turbine stop valve tests on February 18, 1979.

Unit 2 generated its 23 billionth kilowatt hour of electricity on February 12, 1979.

The Unit 2 refueling outage has been rescheduled to begin at midnight on March 22, 1979. The outage was originally scheduled to begin exactly two weeks earlier, but the severe winter conditions and the resulting load demands suggested that postponing refueling would be a prudent course of action.

All 36 new fuel assemblies have been received, unloaded, inspected, and placed in the spent fuel pit in preparation for the upcoming refueling.

A 14-day report (Licensee Event Report No. 79-001/0lT-0) was filed after a staff re-review on February 19, 1979, determined that the failure of both main steam isolation valves to close at hot shutdown conditions on December 9, 1978, was properly reportable rather than simply a significant operating event as originally determined. Although the Technical Specification requirements call for the valves to close in five seconds during the annual refueling test, it was felt following discussions with the chief site NRC inspector that failure to demonstrate closure of these valves under the specific conditions of the above shutdown was in fact reportable.

A 30-day reportable event (Licensee Event Report No.

79-002/03L-0) occurred on February 27, 1979, when a Unit 2 reactor trip relay ( 2-P.T 3 ) in the "A" train experienced a delay in dropping out. The relay was replaced. The defective relay was a Westinghouse Cat. No. BFD31 with a thermally deteriorated nylon sleeve. It is planned to replace all relays of this type associated with the Unit 2 reactor trip system as soon as practicable. The corresponding Unit 1 relays have already been replaced.

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