ML20207U105

Monthly Operating Rept for Feb 1987

ML20207U105
Person / Time
Site:	Hope Creek
Issue date:	02/28/1987
From:	Jensen H Public Service Enterprise Group
To:
Shared Package
ML20207U098	List: ML20207U097 ML20207U105 ML20207U107 ML20207U110
References
NUDOCS 8703240619
Download: ML20207U105 (4)

Text

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.86-354 UNIT Hope Creek Gen. Station DATE 03/06/87 COMPLETED BY H. Jensen TELEPHONE (609) 339-5261 February, 1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1937 939 37 1953 1932 18 1928 1930 39 1059 1037 20 5 21 M 1034 944 22 1025 1042 23 8 24 O 1933 0 25 1036 0 26

, 361 0 33 27 -

0 12 28 13 29 171 --

30 15 31 919 16 32((g 5

OPERATING DATA REPORT UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.86-354 UNIT NAME Hope Creek Gen. Sta.

DATE 03/06/87 COMPLETED BY H. Jensen REPORT MONTH Feb. 1987 TELEPHONE (609)339-5261 METHOD OF SHUTTING DOWN THE TYPE REACTOR OR F FORCED DURATION REASON REDUCINC CORRECTIVE ACTION /

NO. DATE S SCHEDULED (HOURS) (1) POWER (2) COMMENTS 2 02/0 3 F 0 B 1 Reactor Engg.

surveillance (Rod Swap) and MG Set maint.

3 02/l l F 69.9 A 2 Drywell leak.

4 02/24 F 12.2 G 3 Turbine trip during I&C surveillance testing.

5 02/2^ F 97.4 A 9 Main Steam Line '

Isolation Valve problems.

l l

l

SUMMARY

t See Attached

I

. OPERATING DATA REPORT DOCKET NO.86-354 UNIT Hane Creek Gen. Sta.

DATE 3/06/87 COMPLETED BY H. Jannen TELEPHONE (Ea91339-5261 OPERATING STATUS

, Feb 1987

1. REPORTING PERIOD GROSS HOURS IN REPORTING PERIOD 672

2. CURRENTLY AUTHORIZED POWER LEVEL (MWt) 3293 MAX. DEPEND. CAPACITY (MWe-Net) la39 DESIGN ELECTRICAL RATING (MWe-Net) 1967 l -

3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net) Nnna

4. REASONS FOR RESTRICTION (IF ANY)

THIS -YR TO MONTH DATE CUMULATIVE

5. NO. OF HOURS REACTOR WAS CRITICAL qaa_7 1?aR_7 1936.7

6. REACTOR RESERVE SHUTDOWN HOURS e a a

7. HOURS GENERATOR ON LINE ao? A 191s_a 1M?a_a

8. UNIT RESERVE SHUTDOWN HOURS a a a

9. GROSS THERMAL ENERGY GENERATED (MWH) 1_st?_1Rs 1_o1R R10 a_Rso_?a7 19 GROSS ELECTRICAL ENERGY GENERATED (MWH) 41A_1RQ 1_115:R1a 1_K11 a7a

11. NET ELECTRICAL ENERGY GENERATED (MWH) A 0 a : 017 1_?R1_Ran 1 ss7.16a 12 REACTOR SERVICE FACTOR 74 1 RR_? Qa_2

13. REACTOR AVAILABILITY FACTOR 75 1 RR_? on_?

14. UNIT SERVICE FACTOR 71 1 R7 1 RQ_R

15. UNIT AVAILABILITY FACTOR 71 1 R7 1 RQ_M 16 . - UNIT CAPACITY FACTOR (Using Design MDC) 7a 1 R7 1 RR 5

17. UNIT CAPACITY FACTOR (Using Design MWe) KR M RA R RK_?

18. UNIT FORCED OUTAGE RATE ?s_7 19 7 la M

19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, & DURATION): None

20. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: 3/01/87

O HOPE CREEK GENERATING STATION MONTHLY OPERATING

SUMMARY

FEBRUARY 1987 Hope Creek entered the month operating at 100% reactor power producing a daily average of 1925 MWe-Net. The unit operated at essentially full load until February'8 at which time load was reduced to 40% to accomplish preplanned control rod swapping and Reactor Recirculation Pump Motor Generator Set maintenance. The unit returned to 100% power on February 9 and operated at full load until a shutdown was initiated on February 11 due to reactor coolant system unidentified leakage exceeding the Technical Specification allowable value of 5.0 gpm (Actual leakage was just over 5 gpm). A drywell entry was made at approximately 20% reactor power in an attempt to identify and repair the leak. The origin of the leak was found to be a weld joint on the 'A' Reactor Recirculation Pump Discharge Valve body drain line (3/4" pipe).

Since the Technical Specifications prohibit reactor operation with any Reactor Coolant Pressure Boundary leakage, the unit shutdown was continued. The Rod Sequence Control System " locked up" during the ensuing controlled shutdown due to high a Xenon concentration adversely impacting the prescribed shutdown control rod sequence.

In response operators manually scrammed the unit and actions were undertaken to repair the subject weld. After successful repair, the reactor was restarted on February 14 and following maintenance on a Secondary Condensate Pump, the unit returned to 100% power on February 17.

An automatic reactor scram occurred on February 24 during the performance of an I&C test procedure. The test involved verifying the functionality of Reactor Level 8 trip signals to the main and Reactor Feed Pump turbines. An actual main turbine trip was inadvertently initiated during the test, causing a reactor scram.

All required plant systems performed as expected. The unit remained shutdown through the end of the month as repairs were made to Main Steam Line Isolation Valve electrical junction boxes and solenoid valves.

WJMatib

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