ML20084L721

Monthly Operating Repts for Apr 1984

ML20084L721
Person / Time
Site:	Hatch
Issue date:	04/30/1984
From:	Mcbay M, Nix H GEORGIA POWER CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
GM-84-397, NUDOCS 8405150001
Download: ML20084L721 (14)

Text

..

OPERATI!G LATA REPORP '

DOCKET NO. 50-321 05-10-84 DATE OJMPIEIED BY: .M. G. McBay TEIEPH34E (912) 367-7851 ,

OPERATI!G STATUS Notes

1. Unit Narne: E. I. Hatcn Nuclear Plant Unit 1

2. Reporting Period: 04-84

3. Licensed Thermal Power _ (Mt): 2436

4. Nameplate Rating (Gross MWe): 809.3

5. Design Electrical Rating (Mt MWe): 777.3

6. Maximum Dependable Capacity (Gross MWe): 801.2

7. Maximum Dependable Capacity (Net MWe): 752.2

8. If Changes Occur in Capacity Ratings (Items Number 3 tnrough 7) Since Last Report, Give Reasons:

9. Power Ievel to m icn mstricted, If Any (Net MWe)

10. Reasons for Restrictions, If Any:

This bbnth Yr-to-Date Cumulative

11. Hours In Reporting Period 719 2903 73030

12. Number of Hours Reactor was Critical 719.0 2234.6 51759.7

13. Reactor mserve Snutdown Hours 0 0 0

14. Hours Generator On-Line 719.0 2138.5 48531.5

15. Unit Mserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated '(NH) 1727182 4888468 102106496

17. Gross Electrical Energy Generated (MWH) 543900 1568180 33026350

18. mt Electrical Energy Generated (IMI) 520412 1493314 31352677

19. Unit Service Factor 100.0 73.7 66.5

20. thit Availability Factor 100.0 73.7 66.5

21. Unit Capacity Factor (Using MDC Net) 96.2 68.4 57.1

22. thit Capacity Factor (Using DER Net) 93.1 66.2 55.2

23. Unit Ebrced Outage Rate 0.0 24.1 18.7

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

25. If Shutdown at End of Report Period, Estimated Date of Startup:

26. thits in Test Status (Prior to Comnercial Operation): Ebrecast Acnieved INITIAL CRITICALITY l 4\- INITIAL ELECTRICITY

, W COMMERCIAL OPERATION 9

! + 8405150001 840430 Il l PDR ADOCK 05000321

! J Ftfi!R _ _ _ . . _ _ _ _ . - _ . . _ _ - -- ---

r r

AVERAGE DAILY UNIT IOWER LEVEL ,

DOCKET NO. 50-321 DATE: 05-10-84' CDMPLETED BY: M. G. McBay TELEPHCNE (912) 367-7851 MONIH 04-84 DAY AVERAGE DAILY POhER IEVEL DAY AVERAGE 1RILY POhER LEVEL (MWe,-Net) (MWe-Net) 1 690 17 715 2 734 18 735 3 7 28 19 733 4 681 20 728 5 730 21 720 6 723 22 705 7 696 23 725 8 734 24 732 9 7 29 25 732 10 734 26 731 <

11 731 , 27 729 12 732 28 - 722 13 731 29 696 14 715 30 729 15 730 16 734 (9/77) k

~_

OPERATING DATA' REEORT ,

DOCKET NO. 50-366 .

DNIE 05-10-84 COMPLETED BY: M. G. McBay TELEPHONE (912) 367-7851 OPERATING STATUS Notes 1.- Unit Name:.E. I.' Hatch Nuclear Plant Unit 2

2. Deporting Period: 04-84

3. Licensed Thermal Power (M4t): 2436

4. Nameplate Rating (Gross MWe): 817.0

5. Design Electrical Ratirs (Net MWe): 784.0

6. Maximum Dependaole Capacity (GrossIWe): 803.9

7. Maximum Dependable Capacity (Net IWe): 747.9

8. If Changes Occur in Capacity Ratings (Items mmber 3. througn 7) Since Last Report, Give Beasons:

9. Pow & Ievel to hhich Restricted, If Any (Net MWe):

10. Reasons for Restrictions, If Any:

Tnis Month Yr-to-Date Cumulative

11. Hours In Reporting Period 719 2903 40656

12. mmoer of Hours Reactor was Critical 0.0 308.2 27379.4

13. Reactor & serve Shutdown Hours 0.0 0 0

14. Hours Generator On-Line 0.0 308.2 26096.1

15. thit Mserve Shutdown Hours 0.0 0 0 *

16. Gross Tnermal Energy Generated (ElH) 0 726912 55943167

17. Gross Electrical Energy Generated (MWH) 0. 242640 18414420

'18. Net Electrical Energy Generated (mlH) -1969 223948 17513055

19. Unit Service Factor 0.0 10.6 64.2 20'. thit Availability Pactor G.0 10.6 64.2

21. Unit Capacity Factor (Using MDC Net) -0.4 10.3 57.6

22. thit Capacity Factor (Using DER Net) -0.3 9.8 55.9

23. Unit Ebrced Outage Rate 0.0 0.0 13.1

24. snutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

25. If Shutdown at End of Report Period, Estimated Date of Startup:

26. thits in Test Status (Prior to Connercial Operation): Ebrecast Achieved

.* INITIAL CRITICALITY INITIAL EIEC'IRICITY .

CDMMERCIAL OPERATION

r o

AVEREE DAILY UNIT IOWER LEVEL -

DOCKET NO. 50-366 DATE: 05-10-84 CDMPIEIED BY: M. G. McBay-TEIEPHCNE (912) 367-7851 i

M0tml 04-84 DAY AVERAGE DAILY POWER IEVEL DAY AVERME DAILY POhER LEVEL (MWe-Net) (MWe-Net)

, 1 -2 17 -3 2' -2 18 -3 3 -3 19- -3 4 -2 20 -3 5 -3 21 -3 6 -3 22 -3 7 -3 23 -3 8 -3 24 -3 9 -3 25 -3 ,

10 -3 26 -3 11 -3 27 -

-3 12 -2 28 -3 13 -3 29 -3 14 -3 30 -3 15 -3' 31 -3 16 -3

, (9/77)

< =

l' 5

• P

.Y .

UNITSI:UTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-3N UNIT NA'.1E ; Ha t c h 1

' DATE 5-10-R4 COMPLETED BY M n u c r% u REPORT MONTil Apri1 71ELEPilONE . 912-367-7851 EXT. 2882 e.

u E c .

,$g }; $,Y3 Licensec ,E% "1, g~' - 'Cause & Correc{ive No. Date Q ~g .855 Event U gg' Action to -

t-dE $ j;gg Report # mU g ,

Prevent Recurtcoce 84-22 4-01-84 S 17.0 B 1 N/A RC Conrod Ramping back to rated power from Rod adjustment on 3-30-84. .

84-23 4-04-84 F 6.13 A 5 N/A CB PumpXX Recirc Pump "A" tribped.

84-24 4-06-84 S 6.23 B 5 N/A HA Turbin Reducing. load for the weekly turbine test. >

l 84-25 4-07-84 F 7.98 A 5 N/A CH Valvex Reducing load due to leaks dis-covered in 7 & 8th ' stage Feed- '

water heater drain valves.

84-26 4-11-84 F 3.25 A 5- N/A WC Deminx Reduced load due to, condensate demin "F" out of service. .

84-27 4-14-84 S 3.52 8 5 N/A HA Turbin Reducing load for w eekly Turbine Testing.

84-28 4-17-84 S 1.58 B 5 N/A HA Turbin Reducing load for w.eekly Turbine Testinn.

I 2 3 .

4 F: Forced Reason: Method: Exhibit G. L structions .

S: Scheduled A Equipment' Failure (Explain) 1 Manual - for Preparatlin of Data l,'

B4taintenance o(Test

" 2 Manual Scram.

Entry Sheets'for Licensee + -

C R:fu:line, . 3. Automatic Scram. } Event Report (LER) File (!JUREG-:

. D Regulatory Rest:.etion 4 -Continuations . OI6I) ,

E Operator ' training & Licensc Examination " 5-Ioad Peduction j .i n' I

F Adminis.ra:ive 9-Other (Explain) '

t G Operational Erre:(Explain) ,..,

. Exhibit ! SameSource , .

• g;

_j' ; ..

('2/77) Il-OLher(Explain) * .- -

..V

.,. , .g n . .

. .g

- Page 2 ,

O V

50-32M

• DOCKET NO. - d UNIT SI:UTDOWNS AND POWER REDUCTIONS UNIT N A*,lE . H a t c h 1

' 5-10-84 DATE 4_j _M . G McBay COMPLETED BY REPORT MONT11 Apri1 TELEPliONE . 912 - 3 b / - / 3 b 1 EXI. 2882

, l e.

N. . Date g

.$ ?

g 33 3;; .Y

,g g 5 Licensec Event E%

u s? E 'S "Cause & Corrective Action to -

• c3 5 5 jsgO Report 4; $0 [U , Prevent Recurrenc.o 5.91 N/A CE Reducing load for RCIC oil leak 84-29 4-17-84 F B 5 repair.

~

8.17 N/A HA Turbin Reducing load for weekly 84-30 4-21-84 S B 5 Turbine Testing.

4-21-84 12.45 N/A IB Instru Holding load due to loss of 84-31 F A 9 process computer. Load at approx 735 GMllE. l t

84-32 4-28-84 S 3.93 B 5 N/A HA Turbin Load reduction for weekly Turbine Testing.

719.0 N/A HA Turbin 13th stage buckets,on low pres-84-33 4-01-84 F A 5 sure Turbine"were damaged and .

out for the durati6n of April.

I 2 3 .

4 F: Forced Reason: Method: Exhibit G . Instructions .

S: Scheduled A Equipment' Failure (Explain) I Manual -

for Preparation of Data *

11. Maintenance of Test 2 Manual Scram. Entry Sheets for Licensee . -

C R:fu: ling- . 3 Automatic Scram. j Event Report (LER) File (!JUREG-:

D.Regulatury Rest:.ction 4 -Continuations . 0161) -

E. Operator ' training,& U:ense Examination  :-

5-Ioad Feduction  ; i n' F Adruinis.ra: ivc 9 -Other (Deplain) S  :

G Operr.tional Erre:(;ixplain) ,..,- Exhibit ! SameSourec , .

• p

• Il Other (Explain) t Wl??) . .

_ y.z .

. O 50-366V 'g UNITSI:UTDOWNS A POWER REDUCTIONS DOCKET NO. Ha t c2h

• UNIT N AME DATE!5-10-84 COMPLETED BY < M . G . McBav REPORTMONT!! Aoril TELEPil0NE 912- 3 67 - 7 R 51 EXT. 2882 e.

c c c. 4 w5 Lf'

• b#" "g9. - 'Cause & Correciive -

No* Date E. 5 _E eo  !.

c 3 EU

.c is cc Event u '2 O Action to i

• x c3 5 5 jg5 Repori# N0 yd , Prevent Recuttene.o O .

84-5 04-01-84 S 719.0 H 2 N/A CB PipeXX Recirc Pipe Replacment Outage.

I >

I e

t 1 2 3 .

4 F: Forced Reason: Method: Exhibit G-It structions .

5: S heduled A Equipment' Failure (Explain) I M.inual .

for Preparation of Data l' Entry Sheets'for Licensee . -

B41sintenance of Test 2 Manual Scram.

C-Refu: liar, . 3.Automstic Scram. j Event R:purt (LER) Fire (!JUREG-:

D Regulatory Rest:.c; ion 4 -Continuations . 016I) -

E Operator Training & Ucense Examination i 5-Ioad Reduction i } n' F.Adrainis.ra::ve 5  ? -

9gg (gg) Exhibit ! Same Source ,, . p G Operatten21 Erre:(Explain) to/77) Il Other(Eylain)

, , .3 i.-

j *

. .: . ; 2,

{

> ~

NARRATIVE REPORT UNIT 1 i April 4th 1252 "A" Recirc Pump Tripped. Load reduced to approximately 50%. t

-April 4th 1540 Started increasing load from Recirc Pump "A" trip via Recirc flow to approximately 600 GMWE.

April 4th 2230 Load back to rated power. 770 GMWE.

April 6th 2146 Dropping load for daily & weexly turbine testing.

April 7th 0120 Load at 700 MWE. Increasing load back to rated.

April 7th 1301 started dropping load to 500 MWE i due to leaks in 7tn and 8tn Stage ,

Feedwater Heater Drain valves, i

April 7th 1514 Increasing load to approximately 650 MWE after repairing valves.

April 7th 2100 Back to rated power.

April lltn 0945 Dropping load due to cond. demin ,

"F" out of service for backwash & '

precoating.

April 11th 1035 Started increasing load to approx. 750 GMWE "F" cond. demin

.back in service.

April 14th 0014 Dropping-load from 767 MWE to 650 i: MWE for weekly turbine & reactor feedpump trip test.

April 14tn 0345 Weekly turbine tests & RFPT tests complete.  ;

April 17th 0025 Load reduction for Daily Turbine r Te sts .

. April 17th 0108 Load at rated power, approx. 760 GMWE. ,

1:

-April 17th 1620 Notified System Operator that load reduction in progress due to RCIC oil leak. Reducing reactor [

power via recirc. '

i-I__-.

i NARRATIVE REPORT <

UNIT 1

• April 17th 2225 Load at rated power, approx. 770 GMWE.

April 21st 2135 Started Reducing Reactor power i via recirc flow for daily &

weekly turbine test. '

April 22nd 05454 Stopping power increases due to loss of process computer. '

April 22nd 1020 Began .3 MW step increases via Reactor Recirc. Process Computer returned to service.

April 23rd 0120 Reactor Power at 98%, CMWT at 2410.

April 28th 0004 Starting Load Reduction for Main Turbine Weekly Test. l.

April 28th 0053 Load Reduction stopped at 640 ,

GMWE for weekly turbine test. -

April 28th 0120 Started increasing load to approx. 740 GMWE.

April 28th 0240 Daily & weekly turbine tests &

Reactor feedpump tests have been i completed.

. . _ . _ - . . . . - _ ~ . .. .- - . _ - _ _ . _ - - . . .

l NARRATIVE REPORT  !

UNIT 2 i r

i April 1st 0000 Unit outage continues. Outage is ,

due to reactor scram from nign l turbine vibration on 2-11-84. -

Upon inspection found 13th stage '

' LP turbine buckets severely damagea. -

)

6 l

[

i h

I i ..

i s

h a

+

t

. s

. ~ . _ . . . - . . , . , ., . . _ . . . _ _ . , _ _ . _ . _ _ . . _ . . . , . . - - . . . . . . _ . . _ . . . . - . . -

HATCH.1 SAFETY-RELATED MAINTENANCE REQUESTS  !

! TO BE REPORTED FOR APRIL 1984  ;

NUMBER DATE COMPLETED DESCRIPTION 82-3754' 08-25-82 Fabricate Supports and install supports, ionization '

detectors, and rate-of-rise t detector and conduit in shift supervisor's office in main control room. (Ref: ,

DCR 80-348). '

82-4010 07-19-82 Route & support conduit IMC-9803-3A in main stack radiation monitoring I system. (Ref: DCR 80-53).

82-4011 08-12-82 Route & support conduit [

Dll-P006-M02-1 1/2 A in main stack radiation monitoring }

system. (Ref: DCR 80-53).

82-5072 10-09-82 Install Heat tracing on ,

Pressure gauge and 1/2"

, piping off 30" Div. II 1

P.S.W. strainer outlet line. (Ref: DCR 8 2-107) .

82-5073 10-09-82 Install Heat tracing on -

instruments, tuning, piping

& valves off Unit 1 Div. II

! P.S.W. header. (Ref: DCR '82-107).

• i 82-5074 10-09-82 Install Heat tracing on .

lines and pressure I instruments for botn divisions of plant service water. (Ref: DCR 82-107).

5075 10-09-82 Install Heat tracing on Unit

, 1, Div I & Div II, strainer  ;

I  !

Differential Pressure Instruments, Tubing , Piping ,

and Valves. (Ref: DCR  ;82-107). i r

l 82-5076 10-13-82 Install Heat tracing on flow l tube gauges & connections.

(Ref: DCR 82-107) .

82-5078 10-09-82 Install Heat tracing on 1/2" t

vavle & pipe located on 30" l PSW Div. I to dilution ,

line. (Ref: DCR 82-107) . '

l L i

1. 4 HATCH 1 SAFETY-RELATED MAINTENANCE REQUESTS TO BE REPORTED FOR APRIL 1984 NUMBER DATE COMPLETED DESCRIPTION 82-5079 10-13-62 Install Heat tracing on instruments, tubing, piping, and valves off Unit 1 Div. 1 P.S.W. header. (Ref: DCR 82-107).

82-7602 05-09-83 Remove caoles from conduit IMC-7963 so tnat conduit can De re-routed. Re-pull caoles after conduit has been re-routed. Cables a re located in Cont. Rm. Elev.

164'-0". (Ref: DCR 80-348).

83-7901 12-08-83 Adjust U-bolts on various pipe support nangers in tne B21 systems. (Ref: DCR 81-58).84-141 01-12-84 Functional Test of snubber as per HNP-1-3925. Rebuild snuocer, replacing all software.84-649 02-25-84 Pull cables (Torus Water Temp. Monitoring System)

Dack to associated pull ooxes and inspect. (Ref:

DCR 80-19 7) .

HATCH 2 SAFETY-RELATED MAINTENANCE REQUESTS

. TO BE REPORTED FOR APRIL 1984  !

No safety-related maintenance requests for April.

I 6

s I

'1 I

I e

b 3

4 i' ,

~

[

}

e i

E L

t 4

i s -

.w- -ne v -ve..g .

,,rv .-- , , - -we --

r w-

C . Georgb P wir Company

• Post Offici Box 439 raxt:y, Georgi 2 31513 Telephone 912 367-7781 912 537-9444 Edwin I. Hatch Nuclear Plant May 7, 1984 GM-84-397 PLANT E. I. HATCH NRC Monthly Operating Report Director Office of Inspection and Enforcement United States Nuclear Regulatory Commission Washington, D. C. 20555 i

Dear Sir:

Per Tech Specs section 6.9.1.6 please find attached the NRC Monthly Operating Report for Hatch Unit 1, Docket #50-321, and for Hatch-Unit 2, Docke t. # 50-3 66.

v vg _ sa m t H. C. Nix General Manager JAB /hn

$y,