ML20237J564

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Monthly Operating Rept for Jul 1987
ML20237J564
Person / Time
Site: Vogtle Southern Nuclear icon.png
Issue date: 07/31/1987
From: Dilworth S
GEORGIA POWER CO.
To:
Shared Package
ML20237J554 List:
References
NUDOCS 8708180235
Download: ML20237J564 (5)
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. 1 ENCLCSURE 1 V0GTLE UNIT 1 MONTHLY OPERATING REPORT FOR JULY, 1987 i

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I 3PE#A11NG DATA AEPORT UNjT: V06TLE 1

0CKET NO. 50-424 1 DATE: 03-Aug-87 l COMPLETED BY: S. C. DILWORTH {

TELEPHONE: (4046 724-8114 x;870 i OPERATING STATUS

1. UNIT NAME: A. W. V06TLE UNIT 1
2. REPORT PERIOD: Jul-87 j
3. LICENSED THERMAL POWER IMWt): 1411 4 NAMEPLATE RATING (6ROSS MWe): 1160 i 5. DESIGN ELECTRICAL RATING (NET MWe): 1101. 4

( 6. MAI! MUM DEPENDABLE CAPACITY (6ROSS MWe): 1122

l. 7. MAI! MUM PEPENDABLE CAPACITY (NET MWe): {

1069 j q

8. IF CHANCES OCCUR IN CAPACITY RATINGS i l (!TEMS 3 THROUGH 71 SINCE LAST REPORT, GIVE REASONS: NO CHANGES I 9 POWER LEVEL.TO WHICH RESTRICTED, !F ANY (NET MWe): NO RESTRICTIONS l
10. REASONS FOR RESTRICTION, IF ANY: NA l

THIS MONTH YR. TO DATE CUMULATIVE 1 I

11. HOURS IN REPORTING PERIOD: 744 1464 1464
12. NUMBER OF HOURS REACTOR WAS CRIT! CAL: -

617.1 942.4 942.4 1

13. REACTOR RESERVE SHUTDOWN HOURS: 0.0 0.0 0.0 14 HOURS 6ENERATOR ON-LINE: 588.1 864.5 .864.5 I
13. UNIT RESERVE SPUTDOWN HOURS: 0.0 0.0 0.0
16. 6ROSS THERMAL ENER6Y 6ENERATED (MWH): 1835718.5 2595464.2 2595464.2 j
17. 6ROSS ELECTRICAL ENERGY GENERATED (MWH): $99900 840170 840170
18. NET ELECTRICAL ENERBY GENERATED (MWH): 559400 761550 761550
19. REACTOR SERVICE FACTOR: 82.9% 64.4% 64.4%
20. REACTOR AVAILAPLITY FACTOR: 82.9% 64.4% 64.4%
21. UNIT SERVICE FACTOR: 79.01 59.1% 59.1%
22. UNIT AVAILABILITY FACTOR: 79.0% 59.1% $9.1%
23. UNIT CAPACITY FACTOR (USING MDC NET): 70.3% 48.7% 48.7%

24 UNIT CAPACITY FACTOR (USING DER NET): 63.3% 47.2% 47.2%

25. UNIT FORCED OUTAGE RATE: 20.9% 40.9% 40.9%
26. SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACHit TYPE MAINTENANCE AND TESTING. DATE: OCTOBER 2, 1987 6 DURATION 10 DAYS
27. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: N/A
28. UNITS IN TEST STATUS ( PRIOR TO COMMERCIAL OPERATION): N/A
  • TENTATIVE DATE.

8708180235 870812 PDR ADOCK 05000424 R pyg El-1

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l UN!7 1 AVEPAGE. DAILY UNITS V06TLE 1 1 PCWER LEVEL SOCKET NO. 50-424 DATE: 03-Aug-87 1 CC"5LETED BY: 5. C. SILWORTH I

  • ELEFHONE: (404) 724-0114 v3870 I

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1 UNIT SHUTDONNS AND PONER REDUCTIONS DOCKET NO. 50-424 DATE: 03.AU6-87 UNIT NAME: va6TLE 1 COMPLETED By: S.C. DILNORTH TELEPHONE: (404) 724-9119 (~3701 REPORT MONTH JULY 1987 i l 1 1  : I ,  ; i t  !

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l F: FORCED REASON: METHOD: EVENTS REPORTED INVOLVE Ss SCHEDULED A-EQUIPMENT FAILURE (EXPLAIN) ! - MANUAL A GREATER THAN 20%

! B MAINTENANCE OR TEST 2 - MANUAL SCRAM REDUCTION IN AVERABE C-REFUELINS 3 - AUTO. SCRAN DAILY PONER LEVEL FOR D-RESULATORY RESTRICTION 4 - CONTINUATIONS THE PRECEEDINB 24 HOURf.

E. OPERATOR TRAINING & LICENSE 5 - LOAD REDUCTION F-ADMINISTRATIVE 9 - OTHER (EXPLAIN) 6-OPERATIONAL ERROR (EXPLAIN)

  • LER NUMBER 70 BE ASSIGNED H-0THER (EXPLAIN)

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NRC MONTHLY OPERATING REPORT - JULY 1987

, ATTACMENT A - Cause B - Corrective Action to Prevent Reoccurrence 1&2 A. The root cause of the July 8' event was not determined. To ,

detemine~ the cause a . plan was developed to monitor all parameters which could have caused the trip.

1 The-cause of the July 22 event was due to the actuation of- ')

the temperature switch (TSH-6807). The root cause was 'j detemined to be.a combination of the type of switch used' 1

and its location. The vibration induced from the '1 l Generator Stator Cooling System _ (GSCS) skid resulted in j l the switch actuating at a lower trip _ value than the l calibrated setpoint.  ;

l 1 l A contributing factor to the events was a one out of one  !

l logic for the GSCS protection circuit. This = allowed a premature actuation of one switch, n which initiated the turbine trip although an actual. trip condition did not ,

exist. l The cause of the Main Feedwater Isolation Valve (MFIV),

HV-5228, dual indication was due to a bent actuator am for the limit switch. The- engineering evaluation .

detemined the am had been bent by workmen 'during a )

previous work task. i B. 1. The installation of a different type of _ mercoid " Snap Action" switch (Mode L DA70351536) to replace the mercoid mercury wet type (Model DA 383R61). The switch was also relocated to a new rigid support installation separate from the skid.

2. The installation of a new RTD amplifier (Fisher model LS113) into the $drogen Stator Cooling Panel (PHSC),

cooling water section. The signal to the new amplifier will come from the unused spare RTD already installed.

3. The utilization of a spare relay alrea@ located in the PHSC to provide a new 2 out of 3 logic circuit. The 3 ,

signals will come from the new RTD amplifier, the new mercoid " snap action" switch, and from 'the addition of a new circuit from the alam RTD. The present alam circuit will remain as is.

4. The corrective action taken from the MFIV, HV-5228, indication was to remove, straighten and~ reinstall the limit switch actuation am.

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3 A. ' The July 28 reactor trip occurred due to low ETS pressure. An I&C technician had improperly connected test  !

equipment across the generator current. transformers which produced a false momentary Power Load Unbalance- (PLU) signal. This signal energized the. fast closing solenoids on control valves and intermediate valves. j i

The direct cause was personnel error from improperly connected test equipment. The root cause was the lack of risk assessment performed during the review of the MWO. 1 l

'1 l B. The corrective action taken was to suspend all . test

activities associated with the ASME test. Individuals involved were counseled on their errors.

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