ML20080H814
| ML20080H814 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 01/31/1984 |
| From: | Nix H, Rafeedie D GEORGIA POWER CO. |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| GM-84-113, NUDOCS 8402140334 | |
| Download: ML20080H814 (14) | |
Text
OPERATING DATA kEPORT DOCKET NO.
50-321 l
l DATE 02-10-84 CUMPLETED BY: D. P. Rafeedie TELEPHONE (912) 367-7851 i
OPERATING STPTUS Notes 1.
Unit Name: E. I. Hatch Nuclear Plant Unit 1 2.
Reporting Period: 01-84 3.
Licensed Thermal Power (MWt): 2436 4.
Nameplate Rating (Gross MWe): 809.3 5.
Design Electrical Rating (Net MWe): 777.3 6.
Maximum Dependable Capacity (Gross Mne): 801.2 7.
Maximum Dependable Capacity (Net MWe): 752.2 8.
If Changes occur in Capacity Ratings (Items Number 3 through 7) Since Last Report, Give Reast The MDC (Net Mne) Value Has been Updateo 9.
Power Level to nhich Hestrictea, If Any Oet Mne)
- 10. Reasons for Restrictions, If Any:
This Month Yr-to-Date Cumt
- 11. Hours In Reporting Period 744 744 7L
- 12. Number of tburs keactor was Critical 744.0 744.0 SC l
- 13. Reactor Reserve Shutdown Eburs 0
0 0
- 14. Hours Generator On-Line 744.0 744.0 4i
- 15. Unit Reserve Shutdown fburs 0
0 0
- 16. Gross Thermal Energy Generated (MWH) 1799976 1799976 95
- 17. Gross Electrical Energy Generateo (NWH) 599160 599160 3:
- 18. Net Electrical Energy Generateo (MWH) 574346 574346 3(
- 19. Unit Service Factor 100.0 100.0 6d
- 20. Unit Availability Factor 100.0 100.0 6(
- 21. Unit Capacity Factor (Using MDC Net) 102.6 102.6 Si
- 22. Unit Capacity Factor (Using UER Net) 99.3 99.3 Sj
- 23. Unit Forced Outage Rate 0.u 0.0 lt
- 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. Units in Test Status (Prior to Commercial Operation):
Forecast Ao INITIAL CRITICALITY 9402140334 840131 INITIAL ELECTRICITY PDR ADOCK 05000321 COMMERCIAL OPERAIION R
CPERATING DATA REPORT DOCKET NO.
50-321 DATE 02-1C-84 COMPLETED BY: D. P. Rafeedle TFLEPHONE (912) 367-7851 OPERATING STATUS Notes 1.
Unit Name: E. I. Hatch Nuclear Plant Unit 1 2.
Reporting Period: 01-84 3.
Licensed Thermal Power (MWt): 2436 4.
Nameplate Rating (Gross MWe): 809.3 5.
Design Electrical Rating (Net MWe): 777.3 6.
Maximum Dependable Capacity (Gross HWe): 801.2 7.
Maximum Dependable Capacity (Net MWe): 752.2 8.
If Changes Occur in Capacity Ratings (Items Number 3 through 7) Since Last Report, Give Reasons:
The MDC (Net MWe) Value Has Been Updated 9.
Power Level to hhich Restricted, If Any (Net Mhe)
- 10. Reasons for Restrictions, If Any:
This Month Yr-to-Date Cumulative
- 11. Hours In Reporting Period 744 744 70871
- 12. Number of Hours Reactor was Critical 744.0 744.0 50269.2
- 13. Reactor Reserve Shutdown Hours 0
0 0
- 14. Hours Generator On-Line 744.0 744.0 47137.0
- 15. Unit Reserve Shutdown Hours 0
0 0
- 16. Gross Thermal Energy Generated (MWH) 1799976 1799976 99018004
- 17. Gross Electrical Energy Generated (MWH) 599160 599160 32057330
- 18. Net Electrical Energy Generated (Mwrt) 574346 574346 30433709
- 19. Unit Service Factor 100.0 100.0 66.5
- 20. Unit Availability Factor 100.0 100.0 66.5
- 21. Unit Capacity Factor (Using MDC Net) 102.6 102.6 57.1
- 22. Unit Capacity Factor (Using DER Net) 99.3 99.3 55.2
- 23. Unit Forced Outage Rate 0.0 0.0 18.2
- 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. Units in Test Status (Prior to Commercial Operation):
Forecast Achieved INITIAL CRITICALITY 8402140334 840131 INITIAL ELECTRICITY PDR ADDCK 05000321 COMMERCIAL OPERATION R
AVERAGE DAILY UNIT POWER LEVEL I
DOCKET NO.
50-321 DATE:
02-10-84 COWLETED BY: D. P. Rafeedle TELEPHONE (912) 367-7851 4
1 MONTH 01-84 4
DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY P0ieER LEVEL (MWe-Net)
(MWe-Net) i 1
767 17
. 7 71 2
774 18 772 3
774 19 776 4
774 20 777 5
773 21 776 1
6 775 22 742 j
7 756 23 772 i
8 775 24 772 l
9 773 25 77 l
10 766 26 775 11 773 27 776 l
12 777 28 769 1
13 776 29 777 I
14 776 30 779 15 765 31 779 j;
16 773 I
l 4
't (9/77) r J
u i
1 i
a e
i l
3 1
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OPERATING U41A HEPUkT DUCKET tr 50-306 U41L Uz-lu-64 LUMPLE'EU BY: U.
OPERATING STATUS TELEPHONE P. Mafeecie (y12) 30/-7851 1.
Unit Name: E.
Reporting Period:1. Hatch Nuclear Plant Unit.
2.
01-84 2
Notes 3.
Licensed Thermal Power (MWt):
4.
Nameplate Rating (bross MWe):
243o 5.
Design EJectrical Rating (Net MWe):
817.0 6.
Maximum Dependable Capacity (bross NWe) 764.0 7
Maximum Uepen.Jaule Lapacity (Net MWe):
- 803.9 8.
It The MDC (Net MWe) changes Occur in Capacity katings (Items N 747.9 Nwer Level to Which hestricteu,Value Has Been Updated umber 3 through /)
9.
Since Last Report, Uive keaso ~
- 10. Reasons for Restrictions, If Any:It any (Net Mhe):
- 11. Hours In Reporting Period
- 12. Number of hours Reactor was Critical This Month fr-to-Late
- 13. keactor Reserve Shutdown Hours 744 Cumul 74%
14.
Hours Generator Un-Line 3uo. e 364 300.2
- 15. Unit Reserve Shutdown hours u
473 u
- 16. Gross Thermal Energy Generated 306.z 0
2u0.2
- 17. Gross tlectrical (MhH)
L 260 U
Net Electrical Energy benerated (MWh> Energy benerateo (MnH)
/2091z 0
lb.
7 6912
- 19. Unit bervice Factor t
24zo40 559 24e64U
- 20. Unit Availability Factor z30541 1641 23uS41
- 22. Unit Capacity Factor (Usirig21. Unit Capacity Factor (Using MDC 41.4 1751 41.4
- 41. 4 67.8 41.4
- 23. Unit Forceo Outage Hate UEk Net) 41.4 67.8 41.4 24.
Shutdowns Scheouleo Over Next 6 Months ( Typ 3y. 5 60.8 39.5 0.0 56.0 e, Date, and Duration of Each):
0.0 13.1 25.
If Shutdown at End of Report Perloo
- 26. lkiits in lest 5tatus (Prior to Lommerci l, Estimated Date of Startup:
a Operation):
INITIAL CRITICALITY Forecast INITIAL ELECTRICITY Achie COMMERCIAL UPERATION
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OPERATING DATA REPORT DOCKET NO.
50-366 DATE 02-10-84 COMPLETED BY: D. P. Rafeedle TELEPHONE (912) 367-7851 OPERATING STATUS Notes 1.
Unit Name: E. I. Hatch % lear Plant Unit 2 2.
Reporting Period: 01-84 3.
Licensed Thermal Power (MWt): 2436 4.
Nameplate Rating (Gross MWe): 817.0 5.
Design Electrical Rating (Net MWe): 784.0 6.
Maximum Dependable Capacity (Gross MWe): 803.9 7.
Maximum Dependable Capacity (Net MWe): 747.9 8.
If Changes Occur in Capacity Ratings (Items Number 3 through 7) Since Last Report, Give Reasons:
The MDC (Net MWe) Value Has Been Updated 9.
Power Level to Which Restricteo, If Any (Net MWe):
- 10. Reasons for Restrictions, If Any:
This Month Yr-to-Date Cumulative
- 11. Hours In Reporting Period 744 744 38497
- 12. Number of Hours Reactor was Critical 308.2 308.2 27379.4
]
- 13. Reactor Reserve Shutdown Hours 0
0 0
- 14. Hours Generator On-Line 308.2 308.2
'm 26096.1
- 15. Unit Reserve Shutdown Hours 0
0
- 10
- 16. Gross Thermal Energy Generated (MWH) 726912 726912 55943167
- 17. Gross Electrical Energy Generated (MWH) 242640 242640 18414420
- 18. Net Electrical Energy Generated (MWH) 230541 230541 17519648
- 19. Unit Service Factor 41.4 41.4 67.8
- 20. Unit Availability Factor 41.4 41.4 67.8
- 21. Unit Capacity Factor (Using MOC Net) 41.4 41.4 60.8 j
- 22. Unit Capacity Factor (Using DER Net) 39.5 39.5 58.0
- 23. Unit Forced Outage Rate 0.0 0.0 13.1
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
- 25. If Shutdown at End of Report Perloo, Estimated Date of Startup:
- 26. Units in Test Status (Prior to Commercial Operation):
Forecast Achieveo INITIAL CRITICALITY.
INI"AL ELECTRICITY COF (CIAL OPERATION
AVERAGE _ DAILY UNIT POWEk LEVEL DOCKET NO.
50-366 DATE:-
02-10-84 COWLETED BY: D. P. Rafeedle
. TELEPHONE (912) 367-7851 MONTH '01-84 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 647 17
-6 2
768 18
-6 3
775 19
-5 4
776 20
-5 5
780 21
-5 6
779 22
-5 7
780 23
-3 8
771 24
-5 9
778 25
-5 10 773 26
-3 11 773 27
-4 12 777 28
-4 13 524 29
-4 14
-11 30
-4 15
-7 31
-4 16
-6 (9/77)
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c, e
O. 50-321 J
ET UNIT SHUTDOWNS AND POWER !! EDUCTIONS i.,
1 DATE W-lu-M January COMPLETED BY D.P. Rafeedie REPORT MONTri TELEPHONE 912-J67-7851 e.
E E
.Eg 3
$.Y 3 Licensee
,Es D, -
'Cause & Corrective No.
' Date.
g 7; g
's jg5 Event p
E-3 Prevent Recurrence Action to yU g5 5
j g5 g Report c mO H
6 84-1 01-06-84 S
5.1 B
5 NA.
HA TURBIN Weekly turbine test.
84-2 01-15-84 S
2.95 B
5 NA HA TURBINE Weekly turbine test.
f.s4-3 01-22-84 S
9'.34 8
5 NA HA TURBIN Weekly turbine test.
Weekly turtbne test.
84-4 01-28-84 5
'3.58 B
5 NA HA TURBIN 4
l I
2 3
F: Forced R:ason:
Plethod:
4 Exhibit G - Instructions S: Sch:duled A.E;uiprn:nt Teitur:(Explain) 1-)!:nu:1 r.for Prepzration of Data 13 :.!:ir.tenance cf Test 2-Manual S:r:m.
C.R: fueling 3-Autumatic Scram.
Entry Sh:ets for Licensee Event Report (LER) File (NUREG-D Regulatcry Restriction 4 -Continuations 0161)
E-Operator Training & License Examination 5'-Ioad Pcduction 9 Other (Explain)
[:
3 F Administrative G-0,neration:1 Error (Explain) 2 Exhibit I Same Source (9/77)
Il Oth:r (Exp!am) 74.p
.v: :.
$ Qg. '
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UNITSHUTDOWNS AND POWER REDUCTIONS i.
K 50-366
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IT IE" Hatch 2 DATE 02-10-84 REFORTMONTH _ ganuary
- COMPLETED BY D_ P.
Ra fondia i :
g _ 3 7,7 g w
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4.Ei Licensee
,E-,
ja., -
Cause & Corrective c
s No.
Date.
g 3g
- 5 Jg5 Event
~
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E-3 Action to
$5 5
g di Report #
va O yV Prevent Recurrence
(
84-1 01-01-84 S
24 A
5 NA CB ELECON Ramp from "A" 4160 ' bus trip whie.h. trip "A" recirc pump.
84-2 01-08-84 S
2.28 B
5 NA HA TURBIN Weekly turbine test.
84-3 01-13-84 S
11.2 H
5 NA CB PIPEXX Ramp down for recirc pipe replacement &
refueling outage.
84-4 01-13-84 S
435.8 H
2 NA CB PIPEXX Recirc p'pe~ replacement outage.
i 1
1 I
2 3
4 F: Forced Reason:
!!: hod:
S: S:h:du!cd A 0;uipm:ntTeilur:(Exphin) 14hnu:1 f
Exhibit C-Instructions B.'.hir.tensn=e cf Test
.-for Preparation of Data 2-Manu:1 S:r:m.
Entry Sh:ets for Licensee C-Refueling 3-Autumatic Scram.
D Regulatory Restriction Esent Report (LER) Fife (NUREG-4 -Continuations 0161)
E-Operator Training & Ucense Exsmination F Administtative 5-Ioad Ibduction G-Operational Error (Exp!ain) 9-Other (Explain)
S (9/77)
Il-Oth:r(Expkin)
Exhibit !-Same Source
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-_m-Georg4 Power Company i
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Post Offic) C x 439 B: arty, Georgia 31513 I
Telephone 912 367-7781 912 537-9444 t
GeorgiaPbwer Edwin 1. Hatch Nuclear Plant February 10,~
i 1984 GM-84-ll3 PLANT E.
I. HATCH NRC Monthly Operating Report Director Office of Inspection and Enforcement United States Nuclear Regulatory Commission
. Washington, 0. C.
20555
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, Docket #50-366.
i
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/1 H.
C.
N1x General Manager HLS/hh
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NARHATIVE REPORT UNIT 1 January 1st 0000 Unit at rateo power.
January 6th 2356 Loao reduction for weekly turbine test.
January 7th 0146 Weekly turbine test complete ramping to rated power.
January 7th 0500 Unit at rated power.
January 15th 0015 Load reduction weekly turbine test.
January 15th 0312 Weekly turoine test complete ramping to rated..
January 15th 0400 Unit at rated power.
January 22nd 0440 Load reduction for weekly turbine test.
January 22no 0950 Turbine test complete ramping to rateo.
January 22nd 1400 Unit at rateo power.
January 28th 0025 Loao reduction for weekly turbine test.
January 28th 0150 Turbine test complete ramping to rateo.
January 28th 0400 Unit at rated power.
k
NAHRATIVE REPORT UNIT 2 January 1st 0000 Ramping to rated after 4160 "A" bus tripped causing "A" recirc pump to trip.
January 2nd 0000 Unit at rated power.
January 8th 0010 Load reduction for weekly turbine test.
January-8th 0500 Unit at rateo power.
January 13th 0857 Ramping down for recirc pipe replacement outage & refueling.
January 13th 2009 Reactor manually scrammeo to Start recirc pipe replacement i
outage anc refueling.
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HATCH 1 SAFETY-RELATED MAINTENANCE REQUESTS TO BE REPORTED FOR JANUARY 1984 82-7899 11-28-83 E41, aojust u-Dolt on support E41-HPCIH-35 per drawing E41-HPCIH-35 &
E41-105, Ref. DCR 81-58.
83-8739 12-20-83 IE41-HPSEH-55, L31 hyd.
snubbers.-This snubber was leaking & was replaced with a new one.
83-8737 12-20-83 1E41-HPSEH-918 L31. This snubber was leaking it was replaced by a new one.
83-8736 12-20-83 1E41-HPSEH-92 same as above MR.
83-8734 12-20-83 1E11-RHRH-202 work same as above.
83-7903 12-02-83 1C41 pipe support adjusted u-bolt on snubber C41-F1-H001, Ref. DCR 81-58.
83-7897 12-06-83 PS2 pipe support adjust u-bolt. Ref. LER 1981-103, DCR 81-58.
83-7902 11-28-83 Ell pipe support adjust u-bolt. Ref. LER 1981-103.
83-7938 12-06-83 L36 pipe insulation removed pipe insulation for u-bolt adjustment & then replaced.
Ref. DCR 81-58.83-728 12-08-83 1243, fabricated & install supports & installed conduits for DCR 80-348.
82-6688 10-17-83 1E11-RHRH-20 mocified existing support per attached sketches for DCR 82-75.
83-7895 12-02-83 P41, adjusted u-bolts for DCR 81-58.
m HATCH 1 5AFETY-RELATED MAINTENANCE REQUESTS TO bE REPORTED FOR JANUAkY 1984 NUMBER DATE COMPLETED DESCRIPTION 83-8491 12-06-6>
1C11 reactor protection system, scram discharge volume, installed new raceways & supports Ref. OCR 82-219.
82-7603 11-11-83 1Z43, fire detection cables, disconnect cables shown on sketch 6-E-60-348-275 reconnect cables as shown on sketch B-E-80-348-276 after concuit IMC-7963 is rerouted. Ref. DCR 80-348, Rev.
1.
82-7373 11-11-83 1Z43, fire detection system reworked cables for DCR 80-398.
82-5064 12-05-83 1Y42, fire protection storage tanks level switches engraved annunciator wincows 79 & 80 on panel HJ1-655.
Ref. OCR 79-462.
83-7761 12-05-83 1C11-F014A, CRD pump discharge valve. Tne hand wheel on this valve was fixed so it could be turned.
OCR 83-256.
83-8738.
12-19-83 1E41-HPSEH-60B 3 kip snubbe r L-31 replaceo snuober with new hydraulic snubber.
83-8735 12-19,-83 1E11-RHRH-249 L31 hydraulic snubbers, this snubber had a leak it was replaced with a new one.
83-8751 12-21-83 C11-LE-N060A,B,C,D &
C11-Lb-N660A,B,C,D reactor protection system perform DCR 82-219 moolfications as per attachea work package.
Ref. DCR 82-219.
83-7696 12-02-83 831, pipe supports adjust u-Dolts on supports 631-101-H001 & b31-F12-H801.
Ref. DUR 61-56.
HATCH 2 SAFETY-RELATED MAINTENANCE REQUESTS TO BE REPORTED FOR JANUARY 1984 NUMBER DATE COMPLETE DESCRIPTION 83-le58 UA-09-e4 2A70 ATTb paas & tubing supports, painted the ATTS paos & tubing. Hef. OCR 81-139.
83-2324 12-06-63 2C11 CR0 vents & drains.
Pulled cables per cable pull cards. Ref. DCR 82-206.
83-5027 11-09-83 2T28 Paintea all hangers &
piping on attached list.
ref. OCR 82-076.
83-4943 12-06-83 2C11-N060A,b,C,0 reactor protection system / scram discnarge volume. Calibrated level elements & level switches. Ref. OCR 82-220.
83-4788 11-22-83 2V43 Radwaste sprinkler system engraved annunciator windows 17 & 18. Ref. OCR 82-128.
83-2428 06-08-83 2831-G001 Elbow to pipe weld overlayea the weld with ER300L welo material as per DCR 83-63 & associated welding procedures Ref. OCR 83-o3 & hhp-2-10174 & WP5-35.
83-2879 06-08-83 2b31-G001 Pipe'to pipe weld overlayed the weld with ER3066 weld material as per DCR 83-63 & associated welding procedures. Ref. OCR 4
83-63 HNP-2-10174 & WSP-35.
83-2876 06-08-83 2831-G001 pipe to elbow wela overlayed the weld with ER 308L weld material as per DCR 83-63 & associated weloing proceaures. Ref. OCR 83-63, HNP-2-10174 WPS-35.
83-2877 06-08-83 2831-G001 Pipe to pipe weld overlayeo weld with weld material as per DCR 83-63 &
associateo welding procedures. Ref. DCR 83-63, HNP-2-10174, WP5-35.
HATCH 2 SAFETY-RELATED MAINTENANCE REQUESTS TU BE REPORTED FOR JANUARY 1984 83-2577 06-08-83 2d31-G001 Pipe to pipe wela overlayed weld with wela material as per DCR 83-o3 &
associated weloing procecures. Hef. DCR 83-63, HNP-2-10174, WPS-35.
83-2582 06-08-83 2831-G001 Pipe to pipe weld overlayed weld with weld material as per DCH 83-63 &
associated welaing procedures. Ref. DCR 83-63, HNP-2-10174, WPS-35.
83-2581 06-08-83 2831-G001 Pipe to pipe weld overlayed weld with welo material as per DCR 83-63 &
associated welding procedures. Ref. DCR 83-63, HNP-2-10174, WPS-35.
83-2583 06-08-83 2831-G001 Pipe to elbow welu overlayed weld with ER308L welo material as per DCR 83-63 & associated welding procedures. Re f. DCR 83-63, HNP-2-10174, WPS-35.
83-2385 06-08-83 2831-G001 Pipe to elbow weld overlayed weld with Ek308L weld material as per DCH 83-o3 & associated weloing procedures. Ref. DCR 83-63, HNP-2-10174, WPS-35.
83-2473 06-08-83 2831-G001 Pipe to elbow welo overlayed weld with ER300L welo material as per DCR 83-63 & associateo weloing procedures. Ref. DCR 83-63, HNP-2-10174, WPS-35.
83-2448 06-08-8.3 2831-G001 Pipe to elbow weld overlayeo weld with ER30eL weld material as per DCR 83-63 & associated weloing procedures. Ref. DCR 83-63, HNP-2-10174, WPS-35.
83-2522 06-08-83 2B31-G001 Pipe to elbow weld overlayed welo with ER308L weld material as per DCR 83-63 & associated welding procedures. Ref. OCR 83-63, HNP-2-10174, WP5-35.
.=...
83-2523 06-08-83 2831-G001 Pipe to cibow cold overlayea weld with EH308L weld material as per DCR 83-63 & associated welding procedures. Ref. DCR 83-63, HNP-2-10174, WPS-35.
83-6058 11-22-83 2G31-F089 RWCU condensate
. pressure control valve installed 200 PSI bourdon tube in 2G31-F089. Ref. UCR 83-221.
83-2578 06-08-83 2831-G001 Pipe to elbow weld overlayea weld with ER308L weld material as per DCR 83-63 & associated welaing procedures. Ref. DCR 83-63, HNP-2-10174, WPS-35.
83-6481 12-21-83 2G31-N012 RWCU flow indicator repaireo indicator. Ref. DCH 83-285.
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