ML20112J066

Monthly Operating Repts for May 1996 for Ehnp

ML20112J066
Person / Time
Site:	Hatch
Issue date:	05/31/1996
From:	Shannon Rogers GEORGIA POWER CO.
To:
Shared Package
ML20112J064	List: HL-5188, Forwards MOR for May 1996 & Revised MOR for April 1996 for Ei Hatch Nuclear Plant ML20112J066 ML20112J069
References
NUDOCS 9606190178
Download: ML20112J066 (12)

Text

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- Enclosure 1 ,

1-t Plant Hatch Unit 1 Monthly Operating Report May 1996

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Table of Contents t

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Narrative Report El-la j i'

l ' Operating Data Report El-2 3  ;

4-l' Average Daily Power Level E l-3 i

Unit Shutdowns and Power Reductions El-4a ,

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9606190178 960612 PDR ADOCK 05000321 R PDR i

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1 PLANT E. I. HATCH - UNIT ONE DOCKET NO.: 50-321 DATE: JUNE 6, 1996

) NARRATIVE REPORT COMPLETED BY: S. B. ROGERS j TELEPHONE: (912) 367-7781 x2878 1

l MAY 1 0000 Shift continued activities associated with unit startup.

MAY 2 1813 Shift tied the Main Generator to the grid.

! MAY 3 0236 Shift removed the Mair Generator from the grid for Turbine overspeed trip testing.

! MAY 3 0808 Shift tied the Main Generator to the grid and began ascension to 95% of rated thermal power with Startup and Power Uprate testing in a

progress.

- MAY 5 2348 The unit attained 95% of rated thermal power.

I MAY:6. 2043 Shift began ascension to 98% of rated thermal power for power uprate monitoring.

MAY 6 2300 The unit attained 98% of rated thermal power.

f I MAY 7 1410 Shift began ascension to rated thermal power.

! MAY 7 1434 The unit attained rated thermal power.

i MAY 11 0203 Shift began reducing load to approximately 455 GMWe to remove

' Reactor Feedwater Pump "B" from service for repair to the pump discharge check valve.

I MAY 12 1736 Shift began ascension to rated thermal power. Fuel preconditioning l measures were implemented to prevent fuel degradation during l ascension.

4 MAY 13 0520 The unit attained rated thermal power.

MAY 13 0525 Shift began reducing load when Main Turbine Control Valve No. 4 closed due to a failed linkage to the linear variable (TCV)

differential transducer. Main Turbine Bypass Valve No. 1 opened,d 3 i to control reactor ressure. Main TCVs Nos. 1, 2, an per design,between approximate 45 oscillated 1 and 75% open. Load reduction was stopped at approximately 71 GMWe after the Main Turbine i Valves stabilized.

MAY 13 1020 Shift began reducina load to approximately 620 GMWe to repair Main TCV No. 4.

MAY 13 1535 Shift began ascension to rated thermal power. Fuel preconditioning measures were implemented to prevent fuel degradation during ascension.

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4 PLANT E. I. HATCH - UNIT ONE DOCKET NO.: 50-321 DATE: JUNE 6, 1996 NARRATIVE REPORT COMPLETED BY: S. B. ROGERS TELEPHONE: (912) 367-7781 x2878 MAY 13 2317 The unit attained rated thermal power.

MAY 25 2200 Shift began reducing load in preparation to remove the Main Turbine / Generator from service for repair of an Electrohydraulic Control (EHC) system fluid leak at the Main Turbine Front Standard area.

MAY 26 0353 Shift manually tripped the Main Turbine to repair the EHC system fluid leak.

MAY 26 0517 Shift manually scrammed the reactor when both Reactor Feedwater Pumps tripped due to a false Thrust Bearing failure signal j and reactor water level decreased. Shift manually initiated the Reactor Core Isolation Cooling (RCIC) system to restore reactor water level.

MAY 27 0050 Shift began withdrawing control rods for unit startup.  !

l MAY 27 0959 Shift brought the reactor critical.  ;

MAY 28 0407 Shift tied the Main Generator to the grid and began ascension to )

rated thermal power. Fuel preconditioning measures were implemented to prevent fuel degradation during ascension.

MAY 28 2308 The unit attained rated thermal power.

MAY 29 1030 The unit dropped below rated thermal power due to current Rod Pattern. ,

MAY 29 1410 Shift began reducing load to approximately 685 GMWe to perform a Rod Pattern Adjustment.

MAY 29 1730 Shift .hegan ascension to rated thermal power. Fuel preconditioning measures were implemented to prevent fuel degradation during ascension.

MAY 29 2315 The unit attained rated thermal power.

MAY 31 2400 Shift continued to maintain rated thermal power.

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i OPERATING DATA REPORT DOCKET NO.: 50-321 DATE: JUNE 6, 1996 COMPLETED BY: S. B. ROGERS

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OPERATING STATUS ,

1. UNIT NAME: E. I. HATCH - UNIT ONE

2. REPORT PERIOD: MAY 1996 l

3. LICENSED THERMAL POWER (MWt : 2558

4. NAMEPLATE RATING (GROSS MWe : 850

5. DESIGN ELECTRICAL RATING N T MWe : 776.3

6. MAXIMUM DEPENDABLE CAPACI Y GROS MWe): 840

7. MAXIMUM DEPENDABLE CAPACITY NET MWe 805

8. IF CHANGES OCCUR IN CAPACITY RATINGS):

(ITEMS 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONS:

was increased Licensed from 2436 Thermal Power to 2558 MWt, (Item Gross #3)imum Dependable Max Capacity (Item #6) was increased from 789 to 840 MWe, and Net Maximum Dependable Capacity Item #7) was increased from 756 to 805 MWe due to ower j Uprate. j

9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWe): NO RESTRICTIONS  !

10. REASONS FOR RESTRICTION, IF ANY: N/A THIS MONTH YEAR-TO-DATE CUMULATIVE

11. HOURS IN REPORTING PERIOD: 744.0 3647 178966

12. NUMBER OF HOURS REACTOR WAS CRITICAL: 715.3 2694.2 137095.8

13. REACTOR RESERVE SHUTDOWN HOURS: 0.0 0.0 0.0

14. HOURS GENERATOR ON LINE: 648.0 2529.3 131789.4

15. UNIT RESERVE SHUTDOWN HOURS: 0.0 0.0 0.U l

16. GROSS THERMAL ENERGY GENERATED MWHt : 1495726 5408810 297217577

17. GROSS ELECTRICAL ENERGY GENERAT D (M He): 477528 1713910 95586242

18. NET ELECTRICAL ENERGY GENERATED (MWHe): 454326 1617225 90980765

, 19. UNIT SERVICE FACTOR: 87.2% 69.4% 73.6%

20. UNIT AVAILABILITY FACTOR: 87.2% 69.4% 73.6%

21. UNIT CAPACITY FACTOR USING MDC NET : 75.9% 57.9% 67.9%

22. UNIT CAPACITY FACTOR USING DER NET : 78.7% 57.1% 65.2% 1'

23. UNIT FORCED OUTAGE RA E: 12.6% 7.2% 10.6%

24. SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH): NA l

25. IF SHUTDOWN AT END OF REPORT PERIOD ESTIMATED DATE OF STARTUP: NA l

26. UNITS IN TEST STATUS (PRIOR TO C0F4ERCIAL OPERATION): NA El-2 i

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PLANT E. I. HATCH - UNIT ONE DOCKET NO.: 50-321 DATE: JUNE 6, 1996 AVERAGE DAILY POWER LEVEL COMPLETED BY: S. B. ROGERS TELEPHONE: (912) 367-7781 x2878 DAY Net MWe  !

, 1 .............. 0 2 .............. 10 3 .............. 79 4 .............. 388

. 5 .............. 586 6 .............. 747 7 .............. 786 8 .............. 794 9 .............. 795 10 .............. 796 11 .............. 477 s 12 .............. 524 13 .............. 701

14 .............. 804

. 15 .............. 800 16 .............. 801 17 .............. 797 18 .............. 798 19 .............. 797 20 .............. 797 21 .............. 796 '

1 22 .............. 795 23 .............. 794 24 .............. 794 l 25 .............. 751 i 26 .............. 0 27 .............. 0 28 .............. 409 l 29 .............. 763 l 30 .............. 798 i 31 .............. 802 i

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t UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.: 50-321 DATE: 1996 JUNE 6, S. B. ROGERS COMPLETED BY:

UNIT NAME: E. I. HATCH - UNIT ONE TELEPHONE: (912) 367-7781 x2878 REPORT MONTH: MAY 1996 R M S E E Y T A T LICENSEE SC Y S H EVENT T0 COMPONENT CAUSE & CORRECTIVE P DURATION O O REPORT ED CODE ACTION TO 2 NO. DATE E (HOURS) N D NUMBER HE (SUBC00E) PREVENT RECURRENCE 96-004 960430 F 42.2 F 4 96-008 HB PIPEXX Activities associated with (A) unit startup continued.

5.5 8 5 N/A HA TURBIN The generator was removed 96-005 960503 S from the grid for Turbine overspeed trip testing.96-006 960511 F 0.0 A 5 N/A' HH VALVEX Shift reduced load to (C) approximately 455 GMWe to remove Reactor Feedwater  !

' Pump "B" from service for repair to the pump discharge check valve.

960526 10.0 A 5 N/A HA PIPEXX Shift manually tripped the 96-007 F Main Turbine to repair an

(A)

EHC system fluid leak.

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t TYPE: REASON: METHOD: EVENTS REPORTED INVOLVE A GREATER THAN 20%

1-MANUAL REDUCTION IN AVERAGE F-FORCED S-SCHEDULED A-EQUIPMENT B-MAINTENANCE OR TEST FAILURE (EXPLAIN) 2-MANUAL SCRAM DAILY POWER LEVEL FOR C-REFUELING 3-AUTOMATIC SCRAM THE PRECEDING 24 HOURS.

D-REGULATORY RESTRICTION 4-CONTINUATIONS E-0PERATOR TRAINING & LICENSE 5-LOAD REDUCTION F-ADMINISTRATIVE 9-0THER (EXPLAIN) '

G-0PERATIONAL ERROR (EXPLAIN)

H-0THER (EXPLAIN)

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1 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.: 50-321 DATE: 1996 JUNE 6, S. B. ROGERS COMPLETED BY:

UNIT NAME: E. I. HATCH - UNIT ONE TELEPHONE: (912) 367-7781 x2878 REPORT MONTH: MAY 1996 R M S E E Y T A T LICENSEE SC Y S H EVENT T0 COMPONENT CAUSE & CORRECTIVE P DURATION 0 0 REPORT ED CODE ACTION TO NO. DATE E (HOURS) N D NUMBER HE (SUBCODE) PREVENT RECURRENCE 38.2 A 2 96-009 ED INSTRU Shift manually scrammed the ,96-008 960526 F '

(X) reactor when both Reactor Feedwater Pumps tripped and reactor water level decreased. The Reactor Feedwater Pumps tripped due to a failed circuit board, 1 which resulted in a loss of power to both pumps' f Thrust Bearing Wear Detector l logic and a subsequent false bearing failure signal.

The circuit board was replaced and the unit was returned to rated thermal power.

l rex 30N: METHOD: EVENTS REPORTED INVOLVE TYPE:  !

A GREATER THAN 20% i F-FORCED 1-MANUAL REDUCTION IN AVERAGE S-SCHEDULED A-EQUIPMENT B-MAINTENANCE OR TEST FAILURE (EXPLAIN) 2-MANUAL SCRAM DAILY POWER LEVEL FOR C-REFUELING 3-AUTOMATIC SCRAM THE PRECEEDING 24 HOURS.

D-REGULATORY RESTRICTION 4-CONTINUATIONS l

E-0PERATOR TRAINING & LICENSE 5-LOAD REDUCTION  !

F-ADMINISTRATIVE 9-0THER (EXPLAIN)

G-OPERATIONAL ERROR (EXPLAIN)

H-0THER (EXPLAIN)

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$- Enclosure 2 i

Plant Hatch Unit 2 Monthly Operating Report  :

May 1996 -  !

i Table of Contents 'j 1

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4 1 Paue t

i Narrative Report E2-1 Operating Data Report E2-2 4

Average Daily Power Level E2-3 Unit Shutdowns and Power Reductions E2-4

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4 PLANT E. I. RATCH - UNIT TWO DOCKET NO: 50-366 DATE: JUNE 6, 1996 NARRATIVE REPORT COMPLETED BY: S. B. ROGERS TELEPHONE: (912) 367-7781 x2878 MAY 1 0000 Shift continued to maintain rated thermal power.

J MAY 4 2106 Shift began reducing load to approximately 765 GMWe to perform Rod Pattern Adjustment, Control Rod Drive Exercises for selected control rod drives, and Turbine Stop Valve Testing.

MAY 5 0002 Shift began ascension to rated thermal power. Fuel preconditioning measures were implemented to prevent fuel degradation during ascension.

MAY 5 0724 The unit attained rated thermal power.

MAY 16 1235 Shift began reducing load to approximately 800 failed GMWetowhen Drywell Chiller B" tripped and Drywell Chiller "A" automatically start.

MAY 16 1253 Shift began ascension to rated thermal power following the restart of Drywell Chiller "B". .

MAY 16 1447 The unit attained rated thermal power. f MAY 31 2400 Shift continued to maintain rated thermal power.

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OPERATING DATA REPORT DOCKET NO: 50-366 DATE: 1996

' JUNE 6, S. B.' ROGERS COMPLETED BY:

OPERATING STATUS:

1. UNIT NAME: E. I. HATCH - UNIT TWO

2. REPORTING PERIOD: MAY 1996

3. LICENSED THERMAL POWER (MWt : 2558

4. NAMEPLATE RATING (GROSS MWe : 850

5. DESIGN ELECTRICAL RATING N T MWe : 784

6. MAXIMUM DEPENDABLE CAPACI Y GROS MWe 844

7. MAXIMUM DEPENDABLE CAPACITY NET MWe):): 809

8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONS: NO CHANGES

9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWe): NO RESTRICTIONS

10. REASONS FOR RESTRICTION, IF ANY: N/A THIS MONTH YEAR-TO-DATE CUMULATIVE

11. HOURS IN REPORTING PERIOD: 744.0 3647 146592 d

12. NUMBER OF HOURS REACTOR WAS CRITICAL: 744.0 3540.1 114021.7

13. REACTOR RESERVE SHUTDOWN HOURS: 0.0 0.0 0.0

14. HOURS GENERATOR ON LINE: 744.0 3502.7 110153.7

15. UNIT RESERVE SHUTDOWN HOURS: 0.0 0.0 0.0

16. GROSS THERMAL ENERGY GENERATED (MWHt): 1900934 8763506 245129307

. 17. GROSS ELECTRICAL ENERGY GENERATED (MWHe): 635750 2944778 80379037 4

18. NET ELECTRICAL ENERGY GENERATED (WHe): 609567 2824857 76582318

19. UNIT SERVICE FACTOR: 100.0% 96.0% 75.1%

20. UNIT AVAILABILITY FACTOR: 100.0% 96.0% 75.1%

21. UNIT CAPACITY FACTOR USING MDC NET : 101.3% 95.7% 68.4%

22. UNIT CAPACITY FACTOR USING DER NET : 104.5% 98.8% 66.6%

23. UNIT FORCED OUTAGE RA E: 0.0% 1.7% 6.8%

24. SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS DATE AND DURATION OF EACH): NA

25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIKAT(TYPEEDDdTEOF,STARTUP: NA

26. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): N/A 4

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PLANT E. I. HATCH - UNIT TWO DOCKET NO: 50-366 '

DATE: 1996 JUNE 6, S. 8. ROGERS COMPLETED 8Y:

AVERAGE DAILY POWER LEVEL TELEPHONE: (912) 367-7781 x2878 MAY 1996 DAY Net MWe 1 .............. 828 2 .............. 827 3 .............. 824 4 ........... .. 808 t 5 .............. 813 6 .............. 819 7 .............. 821 8 .............. 819 9 .............. 820 10 .............. 821 11 .............. 820 12 .............. 822 I 13 .............. 825 l 14 .............. 824 15 .............. 821 16 .............. 821 17 .............. 819 18 .............. 819  ;

19 .............. 818 l 20 .............. 817  ;

21 .............. 816 i 816 l 22 ..............

23 .............. 816  ;

24 .............. 816 25 .............. 817 26 .............. 818 27 .............. 816  ;

28 .............. 818 4

29 .............. 817 30 .............. 819 31 .............. 823 4

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO: 50-366 DATE: JUNE 6, 1996 UNIT NAME: E. I. HATCH - UNIT TWO COMPLETED BY: S. B. ROGERS TELEPHONE: (912) 367-7781 x2878 REPORT MONTH: MAY 1996 R M S E E Y T A T LICENSEE SC -

Y S H EVENT T0 COMPONENT CAUSE & CORRECTIVE P DURATION 0 0 REPORT ED CODE ACTION TO NO. DATE E (HOURS) N D NUMBER ME (SUBC00E) PREVENT RECURRENCE

' No significant power reductions occurred this month.

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s TYPE: REASON: METHOD: EVENTS REPORTED INVOLVE A GREATER THAN 20%

F-FORCED A-EQUIPMENT FAILURE (EXPLAIN) 1-MANUAL REDUCTION IN AVERAGE 2

S-SCHEDULED B-MAINTENANCE OR TEST 2-MANUAL SCRAM DAILY POWER LEVEL FOR C-REFUELING 3-AUTOMATIC SCRAM THE PRECEDING 24 HOURS.

D-REGULATORY RESTRICTION 4-CONTINUATIONS l E-0PERATOR TRAINING & LICENSE 5-LOAD REDUCTION F-ADMINISTRATIVE 9-0THER(EXPLAIN)

G-OPERATIONAL ERROR (EXPLAIN)

H-0THER (EXPLAIN)

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