ML20236W400

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Monthly Operating Repts for Aug 1987
ML20236W400
Person / Time
Site: Hatch  Southern Nuclear icon.png
Issue date: 08/31/1987
From: Gucwa L, Richardson J
GEORGIA POWER CO.
To:
NRC
References
SL-3196, NUDOCS 8712080002
Download: ML20236W400 (14)


Text

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GEORGIA POWER COMPANY  :

M ONTH LY OPERATING DATA REPORTS PLANT HATCH UNITS 1 AND 2 m

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d LENCLOSURE-1 TABLE OF CONTENTS . ,

PLANT HATCH - UNIT 1-NRC DOCKET ~DPR-57 HONTHLY OPERATING REPORT. :i

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AUGUST 1987 j d

NARRATIVE REPORT - Page'El ,

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-0PERATING DATA REPORT LPage El-2 '-l AVERAGE DAILY POWER LEVEL-  :

Page El-3 .

UNIT SHUTD0HNS AND POWER REDUCTIONS- Page.El'-4 '

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. NARRATIVE REPORT DOCKET NO. 50-321' UNIT li- DATE1 ~

.Leieptember 2,i1987.

COMPLETED BY: J.H. RICHARDSON' TELEPHONE:- J912). 367-7781'x2078  ;

August-l' 0000. Operating at . reduced ' load .of' 680 MWe:.f or Weekly .

i Turbine Valve / Auxiliaries Test. j

' August l' 0130 Returning to'100% Power.. ,

Y August 3 2010 Automatic reactor scram on vessel . low water '1evel:

due to malf unction .of of RFP Master. Flow Controller.J AugustD4 0332 , Began pulling rods f or startup.

August 4 0900. Reactor critical.

August 4 1924 Main Generator tied to line.., . Ascension- to1100% .

Power in progress.

August 8 0008 Reducing load to .700 MWe ' f or Weekly.. Turbine 1 Valve / Auxiliaries, Test.and CRD Exercise.' ,

August B 0100 Returning to 100% Power.

l August 15 0005 Reducing load to 740 MWe f or Weekly Turbine ,

Valve / Auxiliaries Test and .CRD Exercise.

o l August 15 0035 Returning to 100% Power._

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1 August 22 2305 Reducing load to 650 MWe for Weekly.. Turbine  !

Valve / Auxiliaries Test-and CRD Exercise. 1 August 23 0115 Returning to 100% Power.

August 30 0010 Reducing load to 720 MWe Mor Weekly < Turbine-Valve /Auxili aries Test and CRD Enercise.

.i August 30' 0130 Returning to 100% Power'.

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August 31 2400 Maintaining 100% power.

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,a-OPERATING DATA R'EPORT DOCKET-NO. 50-321-DATE:- ' September-. 2s; 1997'-- ,

' COMPLETED BY ~ J. H.~ RICHARDSON TELEPHONE: (912).'367-7781 x2878=

OPERATING STATUS 1 UNIT NAME:

. ' E. I. ' HATCH UNIT'1

2. REPORT PERIOD: _ AUGUST 1987 3.' LICENSED' THERMAL' POWER-(MWt): 2436
4. NAMEPLATE RATING (GROSS-MWe): - 850
5. DESIGN ELECTRICAL RATING (NET MWe) 776.3'
6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWe): 783
7. MAXIMUM DEPENDABLE CAPACITY (NET MWe): '750
8. IF. CHANGES OCCUR IN CAPACITY RATINGS (ITEMS 3 THROUGH 7) SINCE LAST REPORT,.GIVE REASONSs. NO CHANGES 1
9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWe): NO RESTRICTIONS'
10. REASONS FOR RESTRICTION, IF ANY: N/A THIS MONTH YR.'TO DATE . CUMULATIVE'-
11. HOURS IN REPORTING PERIOD: 744' 5831' . 102262 c
12. NUMBER OF HOURS REACTOR WAS CRITICALs 731.2 4262.7 71910.2
13. REACTOR RESERVE SHUTDOWN HOURS: .0.0 0.0 .O.0-
14. HOURS GENERATOR ON-LINE: 700.8 4117.0.. '67842.4
15. UNIT RESERVE SHUTDOWN HOURS: 0.0 0.0 .

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16. GROSS THERMAL ENERGY GENERATED.(MWH): -1722379 9410135 145580046
17. GROSS ELEC. ENERGY GENERATED (MWH): 550900 3030680 47098030
18. NET ELEC. ENERGY GENERATED (MWH): 525079 -2884623 44727533

[ 19. UNIT SERVICE FACTOR: 96.9%' "70.6% 66.3%,

20. UNIT AVAILABILITY FACTOR:

96.9% 70.6% 66.3%

21. UNIT CAPACITY FACTOR (-USING MDC NET): .94.1%- .66.0% 58.3%

E22. UNIT CAPACITY FACTOR (USING DER NET): ' 90.9% 63.7% 56.0%

23. UNIT FORCED OUTAGE' RATES. '3.1% .L3.7% 15.8% -j 04 SHUTDOWNS SCHEDULED DVERcTHE NEXT'6 MONTHB'(TYPE,.DATE,'AND DURATION;OF EACH): N/A J
25. IF SHUTDOWN AT END.0F REPORT PERIOD, ESTIMATED DATE OF STARTUP: N/A'  !
26. UNITS IN TEST STATUS ( PRIOR TO COMMERCIAL OPERATION): - N/A 1

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UNIT 1 AVEPAGE DAILY' DOCKET NO. 50-321 POWER LEVEL' DATE: September 2,'1987 COMPLETED BY: J. H. RICHARDSON TELEPHONE: (912) 367-7761 N2878 1

DAY Net MW 1 1 ......... 742 746 3 ......... 625 . ,

4 ......... 2 f 5 ......... 408 j 6 ......... 683 7 ......... 744 8'......... 739 9 ......... 745 10 ......... 746 '

11 ......... 746 J 12 ......... '50' 1 13 ......... 748 j 14 ......... 751 i I

15 ......... 749-16 ......... 751 17 ......... 750 19 ......... 747 'j 19 ......... 748 '

20 ......... 750 21 ......... .749 22 ......... 749 23 ......... 740 j 24 ......... 747 25 ..,...... 749' i 26 ......... 748 )

27 ......... 747 -

28 ......... 747- i 29 ........ 746 30 ......... 742 31 ......... 744 l

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UNIT SHUTDOWNS AND POWER REDUCTIONS.' DOCKET NO. 50-321

-DATE: . September 2,.-1987[

UNIT NAME: E.I. HATCH 1 COMPLETED.BYs J.HA RICHARDSON 4 TELEPHONE: (912) . 367-7781 xOB78 ' ,

REPORT MONTH AUGUST 1987 1 l l 1 1 R'I M 1 1 S l 1 LJ 1 I i 1 i E! El . 1. Y L -l- I. .l 1- 1 I T I IA 1 T !LICENSEEl SC I .  ! . . l'

! I 1 Y l 'l S IH I EVENT 1TO ICOMPONENTI CAUSE & CORRECTIVE - 1'

! I I P IDURATIONI O 1 OI REPORT LED l- CODE I ACTION TO l-I NO. I DATE-I E I(HOURS) 1 N 1D I NUMBER I M EJ1(SUBCODE)i PREVENT RECURRENCE 'l' I __ I l___1 __l___I___f________t il _______l- .

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.l@7-014 18708038 F l ^ 23.17 i A I3 11-87-13 1 CH l'INSTRU IAutomatic' scram on low level .1  :

I I I- I i 1 I l I .(C) Idue to Reactor Feed Pump.  ! l 1 1 I i t 1 I l  !. :IMaster Flow Controller L . , 1- -

Malfunction.'. Replaced two 1 1 1  !  ! I I. I i I. .,

1  !  ! I I i 1 i  ! lMaster Flow Controller I-l 1 1 1 1  ! I 'i' l 'ipre-amp' diodes. .

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TYPES REASON: . METHOD: .  : EVENTS REPORTED INVOLVE-F: FORCED A-EOUIPMENT FAILURE (EXPLAIN) 1 - MANUAL A GREATER THAN 20*4 S SCHEDULED B-MAINTENANCE OR TEST 2 - MANUAL SCRAML REDUCTION IN AVERAGE-C-REFUELING 3.- AUTO.l SCRAM DAILY POWER LEVEL COR D-REGULATORY. RESTRICTION 4 - CONTINUATIONS. THE PRECEEDING'04-HOURS. -)

E-OPERATOR TRAINING & LICENSE 5 -' LOAD REDUCTION" 'l F-ADMINISTRATIVE .9 - OTHER (EXPLAIN)

-G-OPERATIONAL ERROR (EXPLAIN)

H-0THER (EXPLAIN)  ;

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-ENCLOSURE'2 TABLE OF CONTENTS ~ ,

PLANT HATCH - UNIT 2- 4

~1 NRC DOCKET:NPF-5 MONTHLY:0PERATING REPORT'

._ AUGUST 1987 -

. NARRATIVE REPORT . Page.;E2-1, OPERATING DATA REPORT PageLE2-3  ;

1 AVERAGE DAILY P0HtR LEVEL . Page E2 UNIT SHUTDOWNS AND POWER REDUCTIONS - Page_E2-5 q

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NARRATIVE REPORT DOCKET NO. 50-366 i UNIT ? DATE: September 2, 1997 <I COMPLETED BY: J.H. RICHARDSON 'l TELEPHONE: (912) 367-7701 x2878 August 1 0000 Maintaining 90% power to limit offgas activity.

August 1 2135 Reducing load to 620 MWe for Rod Pattern Adjustment. i August 2 0140 Returning to 90% power.

August 3 1201 Automatic Reactor. scram on vessel low water level due to loss of Vital AC. The alternate supply _' breaker .

inadvertently tripped while work was being performed ,l in the~ Vital AC cabinet. Hardwire connection was '

made around the breaker.

August 5 0732 Began pulling rods.

August 5 0929 Reactor critical.

August 5 2029 Generator tied to line. Ascension to 90% power in progress.

August 8 0003 Reducing load to 650 MWe f or Weekly Turbine .

Valve / Auxiliaries Test and CRD Exercise.

August 8 0103 Returning to 90% power.

August 12 0315 Reducing load to 350 MWe for repair of Condenser Tube leaks as indicated by increased Reactor Water conductivity.

August 13 0505 Returning to 90% power. Unable to isolate. water box due to isolation valve leaking by.

August 14 0755 Reducing load to Hot Shutdown for repair of Concienser Tube leaks as indicated by increased Reactor Water conductivity.

August 14 2130 Main Generator off line.

August 15 0310 Mar.u al scram initiated.

August 17 0426 Began pullirg Rods.

August 17 0558 Reactor critical. Rod pull stopped due to 1RM repair.

August 19 0050 Manual scram initiated. Drywell wal kdown revealed a pres-sure boundary leak where the flow element instrument line taps into the 'B' Recirc loop.

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6 NARRATIVE REPORT DOCKET NO. 50-366 UNIT 2 DATE: September 2,.1987 COMPLETED BY: 3.H. RICHARDSON.

TELEPHONE: (912) 367-7781.x2878 August 20' 2337 Began pulling rods. Weld repair of leak was satisfactorily completed.

August 21 0302 Reactor critical.

August 22 0352 Gettrator tied to line. Ascension to 90% power in progress.

August 28 2315 Reducing load to 650 MWe for Weekly Turbine Valve / Auxiliaries Test, CRD Exercise, and Rod Pattern Adjustment.~

August 29 0045 Returning to 90% power.

August 31 2400 Maintaining 90% power to limit offgas activity.

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OPERATING' DATA FEPORT. DDCKET NOi.50-3e6 -]

'DATE:. September-2,.1987. j COMPLETED-BY ,J. H. RICHARDSON. l

.. TELEPHONE: --(912) i 367-77811 x 2878 '

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2. REPORTING. PERIOD: . AUGUST'1987
3. LICENSED THERMAL POWER (MWtis- 2436 l 4. NAMEPLATE RATING (GROSS-MWe): 850 1 1

-5., DESIGN ELECTRICAL RATING (NET MWe): 784 ' li l 6.~ MAXIMUM DEPENDABLEjCAPACITY (GROSS MWe): 794 Sf

7. NAXIMUM DEPENDABLE CAPACITY'(NET MWe): .761"
8. IF CHANGES OCCUR IN CAPACITY RATINGS- . .

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(ITEPS^3.THROUGH 7) SINCE LAST REPORT, GIVE. REASONS: NO CHANGES-

9. POWER LEVEL TO WHICH RESRTICTED, IF ANY (NET MWe): 90%-(700 MWE).
10. REASONS FOR RESTRICTION, IF ANY: ADMINISTRATIVE, -..TO LIMIT- :j

, OFFGAS ACTIVITY.

l YHIS' MONTH YR-TO-DATE- CUMULATIVE'

11. HOURS IN. REPORTING PERIOD: 744 .5831- .69888
12. NUMBER'OF HOURS REACTOR WAS CRITICAL: 585.3 5590.6 49613.9 _
13. REACTOR RESERVE SHUTDOWN HOURBs 0.0 0.0, ~ .O. O  !

14 HOURS GENERATOR ON LINE: 513.3 5461.4- 47501.2

15. UNIT RESERVE SHUTDOWN HOURS: -
0. O ' O . O. .

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16. GROSS THERMAL ENERGY GENERATED (MWH): 1008536 12408681.. :102508616 ')

17.' GROSS ELEC. ENERGY GENERATED (MWH)s 321380 4081240 133676450

18. NE1 ELEC. ENERGY GENERATED (MWH): 302641 3901477 32051356.
19. UNIT SERVICE FACTOR: 69.0% 93.7%- 68.0%
20. UNIT AVAILABILITY FACTOR: 69.0% 93.7%. 60.0% '.,
21. UNIT CAPACITY FACTOR (USING MDC NET): 53.5% 1 87.9% 60,0% i 22.. UNIT CAPACITY FACTOR (USING DER NET): 51.9% 85.3%. 58.5% .I
23. UNIT FORCED OUTAGE RATE: 20.6% 4. 8% -: - % O% -l
24. SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS (TYPE, DATE,JAND DURATION OF EACH)'s' -]

Refueling Outage,-January 13, 1988, 8 weeks l.

23. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: '

N/A.

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

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.i UNIT 2 AVERAGE DAILY DOCVET NO. 50-366 .!

POWER LEVEL. DATE: September 2, 1987 i COMPLETED BY J. H. RICHARDSON j TELEPHONE: 5912) 367-7781 x2878 1 DAY Net MW 1 ......... 661" l 2 ......... 666 3 ......... 325 4 ......... O 5 ......... . O 6 ......... '382 l 7 ......... 632-  ;

l, 8 ......... 667 '

9 ......... 668 10 ......... 667 11 ......... 672 12 ......... 402 .

13 ......... 583 14 ......... 410 15 ......... O 16 ......... O 17 ......... O 18 ......... O 19 ......... O 20 ......... O 21 ......... O 22 ......... 122 J 23 ......... 431.

24 ......... 649 l 25 ......... 682 26 ......... 684 27 ......... 685 28 ........ -683 29 ......... 680 30 ......... 682 31 ......... 682 1

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i UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.50-066 i DATE: September 2, 1987 )

UNIT NAME: E.I. HATCH 7 COMPLETED BY: J.H. RICHARDSON 1 TELEFHONE: (712) 367-7781 x2878 REPORT MONTH AUGUST 1087 .

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i I I T I I A I T ILICENFEEl SC I I I I I I Y I S I H I EVENT I TO ICOMPONENT! CAUSE & CORRECTIVE I i 1 1 P IDURATIONI O I O 1 REPORT 1 ED l CODE I ACTION TO 1 i NO. I DATE I E l(HOURS) i N i D 1 NUMBER 1 ME l(SUBCODE)I PREVENT RECURRENCE i ,

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187-012 1870801! S I 0 .-l F I 5 I N/A_ _ _ _ - =IRC 1 FUELXX 1 Administrative decision f or- 1 I I I 1 1 1 1 1 1  ! maintaining 907. power tb i ,

i I l  !  ! 1 l l l 111mit of f gas activity. I j l 1 1 I I I I I i  ! I j

!87-013 18708031 F I 56.5 i A I 3 1 2-87-9 I ED 1 CKTBRK ! Automatic scram on low level I j

! I 1 1 I I i 1 I (A) Idue to loss of Vital AC (see I i

! i  !  !  !  ! I i 1  ! Narrative Report, page E2-1).1 I I I i  !  ! I I i  ! i l l 187-014 1870812! F i O I B 1 5 i N/A I HC 1 HTEXCH ! Load reduction to repair  !

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l i I I  ! I I 1 1 I t 187-015 18708071 S I O I F l 5 l N/A -1 RC i FUELXX Administrative decision for  ! l i 1 1 I  ! I I I  ! Maintaining 90% power to I j i  !  ! I  ! I I I I ilimit offgas activity.  ! l 1  !  ! 1 i i l i I  !  !  !

187-016 18708141 S I 97.4 I B l 2 1 N/A I HC 1 HTEXCH IShutdown to repair Condenser i l i I  !  ! I t  !  ! (D) ITube leaks.  !

1 1 l l  !  !  ?  ?  !  ! 1 187-017 18708181 F ! 76.9 i A ! 2 12-87-10 1 CB  ! PIPEXX  ! Shutdown to repair Recirc I i 1 1 1 1 1 l l l (A) linstrument line leek. I

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187-018 19708251 S 1 O 1 F ! 5 l N/A I RC I FUELXX  ! Administrative decision for 1

!  !  ! 1 1 1 1 1  ! maintaining 90% power to I i l l 1 1 I I 111mit offgas activity.  !

! I - 1 I I I l I l_________I_____________ =___________I TYPE: REASON: METHOD: EVENTS REPORTED INVOLVE q F: FORCED A-EQUIPMENT FAILURE (EXPLAIN) 1 - MANUAL A GREATER THAN 20%

S: SCHEDULED B-MAINTENANCE OR TEST 2 - MANUAL SCRAM FEDUCTION IN AVEPAGE C-REFUELING 3 - AUTO. SCRAM DAILY POWER' LEVEL FOR D-REGULATORY RESTRICTION 4 - CONTINUATIONS THE PRECEEDING 24 HOURS.

E-OPERATOR TRAINING &< LICENSE 5 - LOAD REDUCTION F-ADMINISTRATIVE 9 - OTHER'fEXPLAIN)

G-OPERATIONAL ERROR (EXPLAIN)

H-OTHER (EXPLAIN)

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'. - .. a. Georgia Power Company '

' 333 Piedmont Avenue

. Atlanta, Georgia 30300 .y  ;

Telephone 404 526-6526 - r .

Mailing Address: J' .

Post Office Box 4545 -

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- Atlanta, Georgia 30302 '

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GeorgiaPower l L T. Gucwa the southern t40ctrc system Manager Nuclear Safety 3" and Ucensing -

-SL-3196 v9 0166C- .

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., September'11, 1987  ;

Director, Office of Management and Program Analysis U. S. Nuclear Regulatory Commission R Washington, D. C. 20555  :

PLANT HATCH - UNITS-1, 2

-l NRC DOCKETS 50-321,'50-366 OPERATING LICENSES DPR-57, NPF-5 HONTHLY'0PERATING REPORTS <

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.j Gentlemen:

' Enclosed are the Monthly Operating ' Reports for Planti Hatch : Unit 1, Docket Number 50-321, and for Plant Hatch. Unit 2, Docket Number 50-366.

These reports are submitted in accordance with the. requirements of.

Technical Specifications Section 6.9.1.10. a Sincerely,.

-/ .:

ef74 e - l i

L. T. Gucwa- -

l LGB/lc '

Enclosures:

1. Monthly Operating Report.for.. Hatch-1  :

2; Honthly Operating Report for Hatch -

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. Georgia Power k .

Director, Office of Management and . Program hnalysis -

September. 11, 1987 -

Page Two 4

c: GgpIdihPowerCompany. .

Lj Mr._-J. P. 0'Reilly..Sr. Vice President - Nuclear.0perations i Mr..J. T. Beckham, Jr., Vice President - Plant. Hatch 4 GO-NORMS-U. S. Nuclear Reculatory Commission Hashinaton. D. C.

Mr. L. P. Crocker, Hatch Licensing Project Manager U. S. Nuclear Reaulatory Commission.'Reaion II

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Dr. J..N. Grace, Regional Administrator '

l Mr. P. Holmes-Ray,' Senior Resident Inspector - Hatch.

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