ML20080E649
| ML20080E649 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 09/10/1983 |
| From: | Blackwell R, Nix H GEORGIA POWER CO. |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| GM-83-789, NUDOCS 8309140028 | |
| Download: ML20080E649 (15) | |
Text
s Georgia Power Company f
- ,c Post Office CJ4 439
- Baxleyl Georgia 31513 Telephone 912 367-7781 912 537-9444 GeorgiaPower Edwin 1. Hak.h Nuclear Plant h;;emEr w uct 10, 1983 GM-83-789 PLANT E.
I. HATCH NRC-Monthly Operating Report Director Office of' Inspection and Enforcement United States Nuclear Regulatory Commission Washington, D. C.
20555
Dear Sir:
~
Per Tech Specs' section 6.9.1.6 please find atta" the NRC Monthly Operating Report for Hatch Unit 1, Docket #50-321, and for-Hatch Unit 2, Docket #50-366.
2 m
H.-C.
Nix General Manager HLS/hh d
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OPERATING DATA REPORT f
. DOCKET NO.-
50-321~
DATE 09-10-83 COMPLETED'BY: R. M. Blackwell.
TELEPHONE (912) 367-7851.
OPERATING STATUS.
Notes 1.
Unit Name:'E. I.' Hatch Nuclear Plant Unit 1 2.
Reporting Period: 08-83 3.
Licensed Thermal Power (MWt):'2436 4.>
Nameplate Rating (Gross'MWe): 809.3 4
5.
Design Electrical Rating-(Net MWe): 777.3
- 6. - Maximum Dependable Capacity (Gross MWe):.801.2 7.
Maximum Dependable Capacity (Net MWe): 764.7 8.
If Changes Occur.In Capacity Ratings (Items Number 3 through 7) Since Last Report, Give Reasons':
9.
Power Level to Which Restricted, If Any (Net MWe).
- 10. Reasons for Restrictions, If Any:
This Month Yr-to-Date Cumulative
- 11. Hours In Reporting Period 744 5831-67199
- 12. Number of Hours Reactor was Critical' 657.7-4500-47452.5
- 13. Reactor Reserve Shutdown Hours 0
0 0
- 14. Hours Generator On-Line 622.7 4257.0
'44407.3
- 15. Unit Reserve Shutdown Hours 0
0 0
- 16. Gross Thermal Energy Generated (MWH) 1454607 9510677 93759040
- 17. Gross Electrical Energy Generated (MWH) 468480 3091310 30360800 i
- 18. Net' Electrical Energy Generated (MWH) 445774 2941625' 28827840
- 19. Unit Service Factor 83.7 73.0 66.1
- 20. thit Availability Factor 83.7 73.0 66.1 1
- 21. Unit Capacity Factor (Using MDC Net) 78.4 66.0 56.1
- 22. Unit Capacity Factor (Using DER Net) 77.1 64.9 55.2
- 23. Unit Forced Outage Rate 16.3 6.7 19.0 l
- 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 4
INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION
,(_.;.
g.^y.
[]
- O:
C
. AVERAE DAILY; UNIT; POWER LEVELf DOCKET NO.
- 50--321
DATE:.
. 09-10-83' s.*
COMPLETED BY: R. M. Blat.xwell-TELEPHONE (912) 367-7851 1
i MONTH.~08-83 DAY AVERAE DAILY POWER LEVEL
. DAY AVERAE DAILY POWER LEVEL ^
j
-(MWe-Net)
(MWe-Net) l
~
1 748.
17 740' 2
752' 18 746 3
'751 19-747-4 749 20 728 5
750 21
~746 6'
704 22 749 L
7 750 23 746.
8 751 24
.745.
i 9
749 25'
-620 10 747 26
-19 11
-745 27
-18 i
12 734 28
-17 13 718 29
-19 t
14 736 30 280 15 726 31 4
l 16 684 3
(9/77) l i
4 i
(
h OPERATING DATA' REPORT i
DOCKET NO.
50-366
'DATE 09-10-83 COMPLETED BY: R. M. Blackwelli
' TELEPH0tE -
(912) 367-7851 OPERATING' STATUS Note 3 1.
Unit Name: E. I. Hatch POclear Plant. 11t 2-2.
Reporting Period:-08-83
. 3.
Licensed Thermal Power (MWt): 2436
'4.
Nameplate Pating (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): 774.5 8.
If Changes.0ccur in Capacity. Ratings (Items tomber 3 through 7) Since Last Report, Give Reasons:
9.
. Power Level to Which Restricted, If Any (Net MWe):
- 10. Reasons for Restrictions, If Any:
Tnis Month Yr-to-Date Cumulative
- 11. Hours In Reporting Period 744 5831 34969
- 12. tomber of Hours Reactor was Critical.
563.7 3244.1 24395.2
- 13. Reactor Reserve Shutdown Hours 0
0 0
- 14. Hours Generator On-Line 457.7
.2989.4 23144.5
- 15. Unit Reserve Shutdown Hours 0
0 0
- 16. Gross Thermal Energy Generated (MWH) 982392 5533556 49139239'
- 17. Gross Electrical Energy Generated (MWH) 316140 1852470 16128940
- 18. Net Electrical Energy Generated =(MWH) 297513 1744799 15333125
- 19. Unit Service Factor 61.5 51.3
.66.2
- 20. Unit Availability Factor 61.5 51.3 66.2
- 21. Unit Capacity Factor (Using MCC Net) 51.6 38.6 56~6-
- 22. Unit Capacity Factor (Using DER Net) 51.0 38.2 55.9
- 23. Unit Forced Outage Rate 38.5 23.6 14.1
- 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 INITIAL ELECTRICITY COMMERCIAL OPERATION
..a
+
)
. AVERAGE DAILY; UNIT POWER. LEVEL ~-
DOCKET M).
'50-366 DATE:
09-10-83!-
L M ETED BY: R..M. Blackwell' TELEPHONE (912);367-7851'
. MONTH 08-83.
DAY AVERAGE DAILY POWER LEVEL DAY
~ AVERAGE DAILY. POWER LEVEL (MWe-Net)
(MWe-Net) 1 1
748 17
-16 2
289 18
-8 3
-14 19:
-13 4
- 7' 20
-18 5
.-13
- 21
-18 6
-18
'22
-17 7
213 23
-19 8
- 520 :-
24 247 9
554 25 609 10 658 26 727 11 717 27' 709 12 721 28 762 13
- 759 29
-763 14
'742 30 763 15 773-31 764-
-16 519 (9/77)
.l' i
l i-
i 4
73 (N.
p.
V.
V.
v 50-321~
DOCKETNO. " Hatch 1
' UNIT SHUTDOWNS AND FOWEP. REDUCTIONS UNIT NAME DA'IE 9-2-83 A ust COMPLETED BY R.M. Blac h REFORTMONui
' TELE?!IONE. 912-367-78'il e.
Licensee g-e, hn -
'Cause & Currective
,j g 1
).E o
Nd.
Date <
g Eg j!!
jg5 Event gg
- 9. ~3 -
Action to Prevent Recurrence jU mO y5 5
jgg Report #
P 6
83-58 830816
.S 16.3 H
5 NA IC 00NIOD Fm p up from above' reduction.
83-59 830820 S
3.2 B
5 NA HA TURBIN Ioad reduction due to weekly turbine test.
'5.7 H
5 NA HA TURBIN Pecovery from above reduction.
i
.83-50 830820
.2 83-61 830825 F
116.1 B
2-1-83-90 CH VALVEX Unit brought off line for repair of feedwater check valve causing excess-1.-83-93' drywell inleakage.
83-62 830830 S
21.7 H
5 NA Cil VAINEX Power' ascension from above outage.
^
83-63 830831 F
23.0 A
3 NA HB VALVEX Rx. ' scram while performing daily stop valve & control intemediate valve testing due to pressure transient in l
EllC system.
i l
4 3
1 2
?!ethod:
Exhibit G -Instructions I-Manuel for Preparation of Data i
F: Forced Reason:
S: S:h:duled A6;uipm:nt'Failur:(Exp!:in) 2-Manu 1 Scr:m.
Entry Sh:ets for Licensee Event Report (LER) File (NUREG-E..!:intenance ci Test 3 Automatic Scram.
C-Refueling 4 -Continuations 0161)
D Regulatory Restriction E-Operator Traiaing & License Examination 5'-Ioad Pcduction 3'
F-Administrative 9-Other (Explain)
Exhibit I-Same Source G Operational Error (Explain)
~
19/77)
Il-O:h:r (Exp!:in) s
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p
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U
.Q 50-366
DOCKET NO.-
IUNIT SHUTDOWNS AND FOWER REDUCTIONS UNIT NAME Hatch 2 DATE 9-2-R3 August COMPLETED BY - # A R1eh11 REFORT MONTH TELEPi!ONE Q17-V7-7RM1 Licensee' po h"o -
~
--J,
.! ?
1 k.5
'Cause & Corrective No.
' Date -
g.
-i g g
jg g 5 Event u3 c.
Action to -
yb 5
jgg Report #.
tN O Prevent Recurrence
~6 83-18 830802 F
121.3.
B 2
NA CC VALVEX Manually brought unit off line for re -
pair of nitrogen leaks in'drywell.
83-19 830807 S
98.9' H
5 NA CC VALVid..C Power ascension from above reduction.
83-20 830816 F
'7. 0 A
3 NA Cil TURBIN Rx. scram on low water. level due to RFPT control signal spike.
83-21 830816 F
81.5 B
9 NA BC.
INSTRU Outage prolonged due to repair of "A" TIP tube.
83-22 830820_
F 92.6 B
9 NA SA PEtEPR Shutdown prolonged due to problems with drywell airlock door.
83-23 830824 S
36.6 H
5 NA SA PENETR Power ascension from above outage.
83-24 830827 S
2.6 H
5 NA IC COBOD Reduced power in order to perform rod pattern adjustment.
lS 20.1 11 5
.NA RC CDtGOD Power ascension from above outage.
83-25 830827 I
2 3
4 F: Fare:d R:ason:
Plethod:
Exhibit G -Instructions S: S:heduied A E ;uip.m:nt'Failur:(Explain) 1-?hnuel
. for Prepzration of Data C-Refueling 3-Auturnatic Scram.
Eritty Sh:ets for Licensee E.'hintenance cf Test 2 Manu:1 Scr:m.
Event Report (LER) File (NUREG-D Regulatory Restriction 4 -Continuations 4.'r0161)
- E-Operator Training & License Examination 5-Ioad Reduction
~
S F Administrative 9-Other (Explain)-
Exhibit I Same Source G Operational Error (Explain)
(9/77) iI Oth:r (Expkin)
~
t 1 NARRATIVE REPORTL UNIT-1 H I IlAugustj6th 0031-Reduceo load in order to perform
'~
weekly turbine testing.
- August 16th 0430 Brought power to less than 70% in order to perform MSIV Testing.
JAugusti6th 0540 Weeklp turbine. testing completed-increasing load.
~ August-6th 0600 MSIV. Testing' completed ano began returning the unit to rated. power.
Augustfl2th 1855
' Plant Service Water Pump "B"
taken out of service for
' maintenance.
'Augustfl2th
.2132
. Received alarm indicating insufficient Bus Cooling Flow due to "B" PSW Pump being out o f service.
Began Recucing Load.
'AugustJ13th.
0306-Began load increase to bring unit T-back to rated power upon return of "B" PSW pump.
.(N August 14th;
'0200 Reduced loao in order to perform X-)
weekly turbine testing.
'Augustf14th-0330 Weekly Turbine Testing completed.
Began increasing load.
August'15th 2030 Roc Pattern adjustment began.
August 16th.
0440.
Rod. Pattern adjustment completed.
Began' increasing power.
August ~20th-0010 Began Reducing load in order to perform weekly turbine testing.
AugustL20th 0320
. Turbine testing completed and began increasing power.
August 25th 0615 Began reducing load to bring unit-
'to shutdown'for repair of HPCI, RCIC, Steam Leaks, RWCU and
-feedwater check valve leakage.
TAugustL26th.
0000 Rx' Manually Scrammed.
~
~
,,,_.,.~,m
-.,c
- - -, - - -- - ~,,. - - --,,- -, - -,,,, - -
/ August 26th 1148 Unit-in Cold Shutdo=n' 7
August.28th 1842-Began Pulling Rods
~ August;28th;
.2009-
.Rx' Critical.
iAugustD29th.
0018 cBegan inserting rods to bring pressure'under control.-
Augus t'. 29th.
. 0552.
Began Pulling Rods
- August 29th; 0620 Rx-Critical-
- August 30th 0220.
Unit tieo to: system gria.
'Abgust' 30th.
0915 Load held due to proolems with
' rod clock. monitor.
August 130th
. 1000 Problems with. rod block monitor
~
resolved ano continueo increasing power.
August :3'1st'
- 0103 Turbine Tripi& reactor scram on Stop valve fast closure while performing main turbine daily test due'to Hyoraulic Control oil pressure fluctuation.
August.;31st 1025
' Pulling rods.,
(-(
.l August.'31st -
1312--
'. Reactor critical.
9 3
4
- NARRATIVE REPORT UNIT 2
( Augu s t '.2nd 0051" Began power reduction due to f.s
(._)
nitrogen leakage in drywell..
August 2nd 0343 Continuing load reduction and began SRV testing.
' August 2nd.
0430 Completed SRV testing:and began increasing load after controlling nitrogen leakage.
' August.2nd-0845 Began bringing Unit to shutdown to repair nitrogen leakage in the drywell.
August:2nd
'1653 The turbine was manually tripped.
August 2nd 1708 Rx manually scrammed.
August 5th 2028 Began pulling rods to bring Rx to criticality.
August 6th 0019 Rx Critical
- August 7th 0208 Generator tied to the system grid.
August 7th 0922 Load held for 'APRM gain d_'/r N-adjustments.
1000 Began increasing load after
' August 7th completion of APRM gain
= adjustments.-
August-7th 1600 Began reducing load for control rod exercise.
. August 7th 1730 Resumed load increase.
~
' August-8th 0502 Continuing load increase.
E August 8th 0900 Intended to hold load because of poor.LPRM Dase: distribution ~but E
began to experience xenon poisoning and recirc pump downspeed drift.
August 8th 1900 Rod block monitor out of service to downscale spikes on-LPRM.
- August;8th 2318 Rod block monitor calibrated.
l August 8th-12330 Continued pulling-rods to 7
y increase power.
fk) ^
L
?
-August [$tts -
l0400-i Held-load'because of inability to
~
~
Lobtain computer values due-to defective TIP tube for T1P "A"._
j-sc JAugustl 10thl, 0020-Increasing load with recirc-flow'.:
%)
10lli Experienced.: power swings as great Augusti10th as 13 MWE due to 7th and 8th stage:feedwater heaters.
' Augus t t10th i
~
,1025
- Held 1 power to ~ repairifeedwater -
heaters.
E AugustL 10th
--1030:
'Feedwater. heater controllers adjustediand began increasing
-power' slowly-through 8-12-83 due n
Eto bad computer data on core caused by TIP "A" inoperability.
~
l August'12th
'0518 Reducing 1oad_to less than 95%
for APRM gain aajustments.
LAugust 12th-1000 Increasingiload to return to-rated' power.
7
- Augustil3th 2318 Re'ducing load to perform weekly turbine test.
-JAugustul4thi
~0130 Turbine testin.g complete and
~
began. increasing power.
August; lith l
.0154' Making small power increases due to.TIP-"A" tube problems.
1A gust?l6th 1621 Rx Auto. Scram on-low water level
.due to_ feed pump. turbine control
. signal problems;.
i
~
' ' August [16th L 23'20
. Bring Unit to cold shutdown to
~
performLrepairs_on TIP "A" tube.
LAugust[17th 2000 Unit in cold-shutdown.
jAugustjl9th 0342-L8eganipulling rods to-bring Rx to
~e criticality.
l
" Augustil9th 10449 Rx Critical-
[ August 19th 0903 Stopped withdrawing control rods dueLto~ refuel bridge problems.
kV,
,..-AUgustilSth
^
10850 Experienced problems with drywell x
airlock coor-latch.
a.
Au'gu'sii 0th
'2000 Inserted all' rods full in.
2 7
</~y 11 2(s'fAugust'22nd; 1139 Airlock door repair complete.
Began' pulling' rods.
N/_
u a
9
- ww-*- e v.or m<*w
-g
..c
-w.
~
August 22nd' 1238-
.Rx-Critical
. August;23rd--
0930
.BeganEinserting: control rods so-
'that1 bypass valves lcan-be closed for repair of EHC 011 leaks ts
'~
around control-valves.
f.X,)
EAugust.l23rd 1736 EHC oil leaks: repaired.
Began pulling rods.
- AugustL23rd-1836
RSCS system lockup experienced.
Stopped withdrawing rodsLinLorder-
-to resolve the problem.
- AugustL24thi 0100 Resolved RSCS problems and resumec rod withdrawal.
~
August 24th 0524 Unit on line.
August 24th; 0835-Held power.for SRV testing..
. August [24th-1100 Resum'ea power increase.
August;24th 1142
- Stopped pulling rods in order to perform "2A" RBM calibration.
August 24th-1214'
' Resumed rod withdrawal.
~AugustE26th
~0000' Xenon build in contributed to slow ramp rate throughout the day.
{ ~ (J j_
August'26th; 12030' Unit achieved rated power.
' August 27th
-0102-Reduced load in order to perform weekly turbine test.
Augst 27th1-0335 Turbine test complete.
1 m
Increasing power to return to rated conditions.
p
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i f
(7 '
a
- N_'
.y U"
' HATCH 1 SAFETY-RELATED MAINTENANCE REQUESTS-T018E REPORTED ~FOR' AUGUST 1983 s
NUMBER' DATE COMPLETED DESCRIPTIDN r~S 82-7149 8-1-83 Sealed post accident
(_)
sampling valves, DCR-79-475 82-1882 7-14-83 Fabricated and installed Service Water-Pipe Supports, DCR 80-348 83-4931.
7-18-83 Replaced Rx l'evel.. Pres's'.
Transmitters.
DCR 83-97
.81-5072.
2-13-83 Pulled Process Raciation Monitor cable i' rom Unit One Rx Bldg. to Main Control Room.
DCR 79-473 82-7050 7-9-83 Pulled and terminatea Post x
Accident-sampling system cable.
DCR 79-475" 82-8463 8-4-83
-Faoricated and instafled conduit support and conduit for Drywell Sump Radiation Monitor.
OCR 79-4731
.83-2767 8-4-83' Replaced,Drywell Press'.
scales with new scales.' OCR 1(,)79-439 5361' S-8-83 Relocated Grounding Cable-from Isolated grd.
Bus.in
-Cable spreading Rcom..DCR 81-031.
t 2144 8-1-83 Relocated Detector assemblies for Rx Bldg.~ Vent Plenum Hign Range Rad Monitor.
I 82-8389-6-9-83 Installed. Post accident
~
sampling. system conduit.
DCR 79-475.
82-7470. 9-83 Installed Post accident sampling system conduit.
DCR 79-475.
I.
' \\,,-
F I
c HATCH 2 SAFETY-RELATED MAirJTENANCE REQUESTS TO BE REPORTED FOR AUGUST 1983 NUMBER" DATE~ COMPLETE DESCRIPTION 83-3604
.7-14-63 Fabricated anc installed j w)
RCIC Whip Restraint "D".
s_
DCR 83-103
.83-1127j
'5-23-83 Modified ~ Pipe Support 2 Ell-RHR-R93.
DCR 82-76
- 83-3541 8-2-83 Bypassed Dissolved oxygen cell 2P33-N053 with 1/4" S.S. tuoing on post accident sampling system.
DCR 79-476
'83-2760 6-27-83 Rerouted instrument air line to 2T48-F318 valve ana modified hangers.
DCR 82-76.
83-4142
'8-18-83 Replaced RHRSW Pump Discharge Pressure gauges with new ones.
DCR 83-124.
g 81-629' 5-3-83 Replaced solencio valve
~
2T41-F044A with environmentally qualifiec 5'
one.
DCR.79-460.81-608 5-19-83 Replaced 'solenoic 2E41-F054 S
with environmentally s (~J; 4*-
qualified one.
DCR 79-460 L82-4021 7-1 Formed pads for Equipment in Post accident sampling e
system room.
DCR 79-476.
E 83-2439 7-29-83 Reinstalleo SRV 2831-F013M.
83-2435 7-29-83 Reinstalled SRV 2B21-F013 H.
83-2437 7-29-83 Reinstallea SRV 2B21-F013A.
DCR'82-53 and DCR 83-25 83-2438 7-29-83 Reinstalled SRV 2821-F013 L.
p 83-2440 7-29-83 Reinstalled SRV 2821-F013C, DCR 82-53 and DCR 83-25.
83-2441 7-29-83 Reinstalled SRV 2B21-F013K, DCR 82-53 and DCR 83-25.
.7-29-83 Reinstallea SRV 2821-F013B,
(,,) 83-2442-
83-2443 7-29-83 Reinstallec SRV 2821-F013D, DCR'82-53 ana DCR-83-25.
a;
'83-2445 7-29-83 RainstN11cdSRV2821-F013E,
~
DCR~82-53 and DCR 83-25.
.83-2446 7-29-83 Reinstalled SRV 2821-F013F, f y DCR 82-53 and DCR 83-25.
~
~
.qj
'~'
83-2447-7-29-83 Reinstalled'SRV 2821-F013G, DCR 82-53 and DCR 83-25.
82-5628 6-24-83.
Replaced Motor Pinion Key on HPCI Pump discharge valve, 2E41-F006. IEN 81-08 83-2724-6-29-83 Modified 2E41 system pipe supports.
DCR 83-66.83-923 6-30-83 Replaced RTD's and Modified supports for Drywell cooling system.
DCR 82-004 83-967 6-22-83 Pulled cables for RCIC System MOV 2E51-F119..
DCR 80-440 83-3273 7-19-83 Installed conduit supports C5-05-173 & CS-05-174.
DCR 82-76.
82-4348 8-8-83 Removeo cable ZAE825C01 and Repulleo new cable
- (,)
ZAE815C02.
DCR 82-68
'83-1256 5-23-83 Installed Hanger 2E41-HPCI-A706 on HPCI System Torus Penetration.
DCR 82-76.
83-2049 6-25-83 Pulled cables CJX806M01 and CJX806C10 on Primary
~
Containment-Isolation System.
DCR 80-91.
~
i-83-3606:
7-14-83 Fabricateo and installed RCIC Whip Restraint "A".
DCR 83-103.
82-5274 7-9-83 Pulled and terminated cables L
for post accident sampling system.- DCR 79-475.
83-2533-29-83 Installed blind flanges on Main Steam Safety Relief-L-
Valves for RX Vessel Recirc hyorostatic Test.
DCR 83-63.
L.I^/
~
Replaced RCIC-RAMG GEN /SIG.
x.
83-3900-
~7-21-83 converter with new model.
m DCR 83-114 i
f:
- - -,.. - _ _ - _. _. _ -. - - _. - _ _ _-