ML20078K238
| ML20078K238 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 10/10/1983 |
| From: | Curtis C, Nix H GEORGIA POWER CO. |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| GM-83-996, NUDOCS 8310190014 | |
| Download: ML20078K238 (14) | |
Text
OPERATING DATA REPORT DOCKET NO.
50-321
'M DATE 10-10-83 g
COMPLETED BY: C. M. Curtis Q
TELEPHONE (912) 367-7851 g
OPERATING STATUS Notes 1.
Unit Nane: E. I. Hatch Wclear Plant Unit 1
- 2. -Reporting Period: 09-83 3.
Licensed Thermal Power (MWt): 2436 4.
temeplate Rating (Gross MWe): 809.3 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 01anges occur in Capacity Ratings (Items Number 3 through 7) Since Last Report, Give Reasons:
9.
Power Level to Which R?stricted, If Any (Net MWe) 5\\5 MWe.
- 10. Reasons for Restrictions, If Any: Wgh OW p Qehdy This Month Yr-to-Date Cumulative
- 11. Hours In Reporting Period 720 6551 67919
- 12. mmber of Hours Reactor was Critical 709.5 5209.5 48162.0
- 13. Reactor Reserve Shutdown Hours 0
0 0
- 14. Hours Generator On-Line 699.7 4956.7 45107.0
-z oNA
- 15. Unit Reserve Shutdown Hours 0
0 0
co'
- 16. Gross Thermal Energy Gcnerated (MWH) 1207872 10718549 94966912 58
- 17. Gross Electrical Energy Generated (MWH) 379650 3470960 30740450 mn
- 18. Net Electrical Energy Generated (MWH) 358380 3300005 29186220 O
- 19. Unit Service Factor 97.2 75.7 66.4 e
56
- 20. Unit Availability Factor 97.2 75.7 66.4 oo
- 21. Unit Capacity Factor (Using MOC Net) 65.1 65.9 56.2
%t
- 22. Unit Capacity Factor (Using DER Net) 64.0 64.8 55.3 0,g
- 23. Unit Forced Outage Rate 2.8 6.2 18.8 QQ
- 24. Shutdowns Scheduled Over Next 6 m nths (Type, Date, and Duration of Each):
g
- 25. If Shutdown at End of Report Period, Estimated Oate of Startup:
- 26. lklits in Test Status (Prlor to Commercial Operation):
Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION
AVERA E DAILY UNIT POWER LEVEL 4
00CKET NO.
50-321 DATE:
10-10-83 COMPLETED BY: C. M. Curtis TELEPHONE (912) 367-7851 1
MONTH 09-83 DAY AVERAE DAILY POWER LEVEL DAY AVERAE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 1
122 17 497 2
247 18 499 l
3 591 19 499 4
722 20 501 5
739 21 502 6
600 22 518 7
338 23 506 8
491 24 511 9
496 25 515 10 498 26 514 11 499 27 514 4
12 498 28 494 13 501 29 504 3
)
14 504 30 508 15 506 31
]
16 498 1
(9/77) 3 i
I I.
O d
O', __
NARRATIVE REPORT UNIT 1 September 1st 0318 Unit tied to system grid.
September 1st 1536 Reactor scram on turoine trip due to stop valve fast closure.
September 2nd 0205 Reactor critical.
September 2nd 0837 Unit tied to system grid.
September 6th 1335 Reduced load for rod sequence exchange.
September 8th 0000 Load held due to leaking fuel problems.
September lith 0030 Reduced loac for weekly turbine testing.
September 16th 2120 Reduced load for weekly turbine testing.
September 23rd 2102 Reduced load for rod pattern adjustment.
September 23rd 2217 Reduceo load for weekly turbine testing.
September 28th 1014 Reduced load due to loose bolts in bearing retainer on "A" cire.
water pump.
.3
- 21 DOCKET NO.
UNIT SI:UTDOWNS AND POWER REDUCTIONS UNIT N AME
. Hatch One
,j au-/-u; y
DATE COMPLETED BY C.M. Curtis SE N ben REPORT MONT11 TELEPHONE 912-367-7Rs1
,a Ext.-2882 I
% e4 5 c
1
'Cause & Corrective
$*3 c
n S3 LI' "5CC 5_s j
~
gjg Action to No.
Date E.
Event I
0 6
p,cvent Recurrence Report #
Q-
$M g g
y 1
o 83-63 83-09-01 F
3.3 A
3 IVA HB Valvex Rx. scram while performing daily stop valve & control intermxliate valve testing due to pressure transient in EHC system.
q r.
83-64 83-09-01 S
12.3 H
5 N/A
!!B Valvex Power ascension from above outage.
L I
83-65 83-09-01 F
17.0 A
3 N/A HB Valvex Rx. scram on turb. trip due to stop valve fast closure.
j 83-66 83-09-02 S
39.4 A
5' N/A HB Valvex Power ascension from abow outage.
l 83-67 83-09-06 S
14.4 H
5
?VA RB Conrod Load reduction for rod sequence exchancy 83-68 83-09-07 S
20 H
5 N/A RB Conrod Recomry from above reduction.
l 83-69 83-09-08 F
552.0 H
5 N/A IC Fuelxx Inad reduction due to leaking fuel 4
problems.
1 1
2 3
4 F: Forced Reason:
Method:
Exhibit G -Instructions J
for Preparation of Data
't i
S: Scheduled A Equipment' Failure (Explain)
- 1. Manual
- 2. Mar.ual Scram.
Entry Sheets for Licensee. -
B Maintenance or Test c.Refu: lina,
- 3. Automatic Scram, j
Event R port (LER) File (NUREG-:
016I)
D Regulatory Rest:.c; ion 4 -Continuations 5-Icad Feduction i
y*
E Operator 1 raining & License Examination 9-Other (Explain)
Exhibit 1-Same Source,
3 F. Adminis.ra:!ve G Operational Errer(.ixplain)
N/M)
Il Other (Explain) i- ;
- {
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t l
50-321 DOCKET NO UNIT SI;UTDOWNS AND POWER REDUCTIONS UNIT N A'.lE DATE COMPLETED BY SN REPORT MONTil TELEP110NE u
e c
"Cause & Corrective
${"., -
}
$.Y ~
Licensec 5%,
Action to No.
Date E-3l n
3s5 Event g
Prevent Recurrence O ~c e
tgc Report #
mU o
=-
1
's u
S 83-70 83-09-11 S
2.5 B
5 lyA
!!A Turbin Ioad reduction due to weekly turbine test.
83-71 83-09-16 S
5.7 B
5 IVA IIA Turbin load reduction due to weekly turbine test.
83-72 83-09-23 S
3.0 11 5
N/A IU Conrod load reduction for rod pattern adjust-ment.
83-73 83-09-23 S
3.0 B
5 IMA IIA
'Iurbin Ioad reduction due to weekly turbine test.
83-74 83-09-28 F
3.8 A
5 N/A
.3 Purquoc Ioad reduction due to loose bolts in bearing retainer on "A" cire, water pmp.
4 I
2 3
F: Forced Reason:
Method:
Exhibit G -Instructions for Preparation of Data S: Scheduled A Equipment' Failure (Explain) 1 -Manual B4taintenance of Test 2-Manual Scram.
Entry Sheets for Licensee. -
C-Refuelian 3-Automatic Scram.
}
Event Report (LERI File (NUREG -
0161)
D Regulatory ilest:.e. ion 4 -Continuations i
E-Operator Training & Ucense Examination 5-Inad Peduction 5
ro/77)
Il-Other(Explain) t ;3 -
9 -Oh (Mlain)
Exhibit 1 Same Source F Adminis.r.i:ive G-Operational Erre (dxplain) h",,,
~
v v
s
HATCH 1 SAFETY-RELATED MAINTENANCE REQUESTS TO BE REPORTED FOR SEPTEMBER 1983 NUMBER DATE COMPLETED DESCRIPTION 83-6740 9-le-83 Replace existing camaged cryogenic valve on nitrogen storage tank.
83-5805 7-31-83 Removed present gauges &
snubber. Installeo WeKsler compound liquid filled gcuges with diaphragm as per DCR 83-174.
82-6779 3-09-83 Replaced needle & calibrated tne floor drain filter pressure indicator gauge.
82-1444 8-30-83 Cut opening in masonry wall 16A(B) between rooms C20 &
C21. Installed H.M.
door &
frame (C-2A). Removed existing door & frame between rooms C20 & C23.
Installed new grill & closed opening.83-683 6-24-83 Fabricated & installeo conduit supports. Hemoved cable from ESS-II-320 & 321.
Rerouted conduit. Pulled in cables H11-P654-E58-C074A &
C075A per DCR 80-348 &
terminated cables.
OPERATING DATA REPJRT DOCKET NO.
50-366 DATE 10-10-83 COMPLETED BY: C. M. Curtis TELEPHONE (91') 367-7851 2
OPERATING STATUS Notes 1.
Unit mme: E. I. Hatch Nclear Plant thit 2 2.
Reporting Period: 09-83 3.
Licensed Thermal Power (MWt): 2436 4.
mmeplate Ratirig (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 Occur in Capacity Ratings (Items Wmber 3 through 7) Since Last Report
, Give Reasons:
9.
Power Level to Which Restricted, If Any (Net MWe):
- 10. Reasons for Restrictions, If Any:
- 11. Hours In Reporting Period This Month Yr-to-Date Cumulative
- 12. mmber of Hours Reactor was Critical 720 6552 35689
- 13. Reactor Reserve Shutdown Hours 664.0 3908.2 25059.3 4
- 14. Hours Generator On-Line 0
0 0
- 15. Unit Reserve Shutdown Hours 644.3 3633.7 23788.8
- 16. Cross Thermal Energy Generated (MWH) 0 0
0
- 17. Cross Electrical Energy Generated (MWH) 1460664 6994220 50599903
- 18. Net Electrical Energy Generated (MWH) 482710 2335180 16611650 3
19.. Unit Service Factor 460332 2205131 15793457
- 20. Unit Availability Factor 89.5 55.5 66.7
- 21. Unit Capacity Factor (Using MDC Net) 89.5 55.5 66.7
- 22. Unit Capacity Factor (Using DER Net) 82.6 43.5 57.1
- 23. Unit Forced Outage Rate 81.5 42.9 56.4
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
10.5 21.5 14.0
- 25. If Shutdown at End of Report Period, Estimated Date of Startup:
- 26. Units in Test Status (Prior to Commercial Operation):
f Forecast Achieved INITIAL CRITICALITY b
INITIAL ELECTRICITY COMMERCIAL OPERATION e
AVERAE DAILY UNIT POWER LEVEL DOCKET NO.
50-366 DATE:
10-10-83 COMPLETED BY: C. M. Curtis TELE.; HONE (912) 367-7851 MONTH 09-83 DAY AVERAE DAILY POWER LEVEL DAY AVERAE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 765 17 773 2
765 18 758 3
750 19 771 4
767 20 769 5
766 21 769 6
767 22 775 7
766 23 425 8
765 24
-16 9
767 25 154 10 753 26 571 11 767 27 726 12 768 28 305 13 769 29
-18 14 770 30 163 15 775 31 16 775 (9/77) 8 4
8 t.
a_
i NARRATIVE REPORT UNIT 2 Saptember 3ro 0025 Reduceo loao for weekly turoine testing.
September 10th 0039 Recuced loao for weekly turbine testing.
September 17th 2335 Recuced loao for weekly turbine testing.
September 23rd 1320 Reactor scram on false high containment pressure signal caused by bumped instrument rack.
September 23rd.
1600 Extendeo shutdown for maintenance on E32 valve motor.
September 24th 1313 Reactor critical.
September 25th 0115 Unit tied to system gria.
September 28th 1013 Eeactor manual scram oue to trips on both reactor recirc pumps.
September 29th 1818 Reactor critica.'.
Sep& ember 30th 0159 Unit tieo to systein grid.
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50-366 DOCKET NO.
UNIT S!!UTDOWNS AND POWER REDUCTIONS UNIT N A.'.t E NM N DATE 10-7-83 COMPLETED By C.M. Curtin SEPTEPEER REPORT MONTil TELEP110NE 912-367-7851 Ext.-2882 q
s.
C C
9-4 o yt Licensee Ev E4-
"Cause & Corrective No.
Date E.
jk 3jS Event
~
N Action tu Prevent Recurrence O=-
y
.U g c Report #
mU o
=
g
^$
u b
W 83-26 83-09-03 S
4.6 B
5 N/A IIA Turbin Inad reduction due to weekly turbine testing.
83-27 83-09-10 S
4.4 B
5 N/A IIA Turbin Inad reduction due to weekly turbine testing..
83-28 83-09-17 S'
5.4 B
5 N/A
!!A Turbin-Inad reduction due to wmkly turbine testing.
83-29 83-09-23 F
35.9 11 3
N/A IB Instru Rx. scram on false high cont. press signal caused by btmped instr. rack.
83-30 83-09-23 S
10 A
9 N/A CD FbtorX Extended shutdown for maintem on E32 valve notor.
83-31 83-09-25 S
44.8 11 5
N/A IB Instru Power ascension from above outage.
i 2
3 4
Exhibit G. Instructions F: Forced Reason:
Method:
for Preparation of Data S: Scheduled A Equipment' Failure (Explain) 1-Manual B-Maintenance of Test
- 2. Manual Scram.
Entry Sheets for Licensee. -
C Refueling
- 3. Automatic Scram.
j Event Report (LER) Fila (!JUREG -
016I)
D Regulatory ilest:.c: ion 4 -Continuations E-Operator ' training & License Examination 5-Icad Feduction 3
F Adminis.ra:!ve 9-Oh (Explain)
Exhibit 1-Same Source,.
G-Operatwnal Erre:(.:xplain)
,.g ro/77)
Il Other (Explain) i.
(,
s
~
50-366 DMET NO.
UNIT SilUTDOWNS AND POWER REDUCTIONS UNIT N A'.1E DATE
{
COMPLETED BY REPORT MON 111 SN TELEPl!ONE w.
,$?
}
).Y Licensee
[ *,,
n., -
'Cause & Corrective n.
Action to
[3 Nii.
Date g
3g js5 Event g'3 v
Prevent Recurrence I
l-dE j;$
Report #
to u a
83-32 83-09-28 F
39.8 A
2 N/A CD PtunEacc Manual scram due to trips on both Ibc. recirc punps.
83-33 83-09-30 S
22 II 5
N/A CB Piirpxx Ibwer ascension from above outage.
i l
I 2
3 4
F: Forced Reason:
Method:
Exhibit G -Instructions for Preparation of Data S: Scheduled A Equipment' Failure (Explain) 1 Manual B Maintenance of Test 2 Manual Scram.
Entry Sheets for Licensee C-Refueling 3 Automatic Scram.
}
Event Report (LER) Fi!* (NUREG. -
0161)
D Re,ulatory F.est:.sion 4 -Continuations t
E Operator T raining & License Examination 5-Icad Feduction
~
3 9-Other (Explain)
Exhibit ! Same Souree F Adminis.ra:!ve G-Operat:ena! Erret(.:xplain)
,.3 i
8cl??)
Il Other (Explain) i
?)
y y
L
HATCH 2 SAFETY-RELATED MAINTENANCE REQUEST 5 o
TO 6E REPORTED FOR SEPTEM6ER 1983 NUMBER DATE COMPLETE DESCRIPTION 83-4201 6-04-83 Provided drain lines for reactor feedpump loop seal level indicators.
83-2211 6-09-63 Conduit installed & core drills made in accordance with design sketches per DCR 80-157 & FDR 80-157-70.
f 83-2202 7-02-83 Use LW&J 2-83-32. Lifted wires & removed soler.oids.
Reattacheo wires as per LW&J sheet.
82-5714 3-31-83 Disconnected &,recannected as necessary circJits UCX706C16/B01 &
UCA90F20A/H01 from the B2 switch (2U43-N061) on the Unit 2 east cableway alarm valve, el. 112'-0" per DCR 82-133.
82-5713 3-16-83 Calibrated the 2 gauges (2043-R002A) & 2U43-R0028) the B2 pressure switch (2U43-N061) on the alarm valve - el. 112' turbine buildin per SM 82-133-3 Rev. A Ref. DCR 82-133).
83-3553 7-07-83 Reorient the flex hose shown on FDR 82-76-199 to a norizontal plane to eliminate the existing pocket.
83-1325 5-26-83 Prepare floor & construct equipment pads. Refer to design documents listed on attached continuation sheet.
(Ref. DCR 81-174).
83-1324 5-27-83 Fabricated mounting sub-plate, weloed plate to pad & bolted panel 2H21-P051 in place. Refer to sketches 5M-81-174-14, SM-81-174,15, and FDR 61-174-11.
c 83-1323 5-27-83 Fabricated mounting sub-plate, weloed plate to pad and bolted panel 2H21-P050 in place. Refer to sketches SM 81-174-14, SM-81-174-15, and FDR 81-174-11.
l l
82-1616 6-09-83 Installed insulation around Unit 2 D/W hangers &
installed tread pads in areas of high traffic.
83-2044 4-25-83 Remove 0 torus outboard purge valve from line, decontaminated, prepared valve & actuator for shipping to Wyle Lab.
Removed old Tee ring, 0-ring gland & o-rings, installed new Tee ring.
83-4514 8-25-83 Removed present plant service water pump discharge pressure gauges & snubbers iristalled Weksler compound liquia filled with diaphgram seals per DCR 83-124.
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Georgia Powtr Ccmptny Post Offica Box 439 Brxisy, Georgia 31513 3
Telephone 912 367-7781 912 537-9444 Edwin 1. Hatch Nuclear Plant September 10, 1983 GM-83-996 PLANT E.
I.
HATCH NRC Monthly Operating Report Director Office of Inspection and Enforcement United States NL: lear Regulatory Commission Washington, D.
C.
20555
Dear Sir:
Per Tech Specs section 6.9.1.6 please find attached the NRC Monthly Operating Report for liatch Unit 1, Docket #50-321, and for Hatch Unit 2, Docket #50-366.
b
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C.
Nix eneral Manager HLS/hh
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.