ML20137N288
| ML20137N288 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 08/31/1985 |
| From: | Kanipe L, Nix H GEORGIA POWER CO. |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| LR-MGR-017-0985, LR-MGR-17-985, NUDOCS 8509190059 | |
| Download: ML20137N288 (15) | |
Text
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4 NARRATIVE REPCRT.
UNIT 1 i
August 1st 0000 Unit in cold shutdown following scram on 7-24-85.
MSIV repair continues.
1 August 4th 0349 Rod withdrawal commencing.
0501 Reactor Critical i
l August 5th 1153 Generator tied to line. Ramping toward rated Maximum Dependable
' Capacity (MDC).
August 7th 1930 Reached rated MDC.
August 10th 0005 Reducing power for rod pattern adjustment.
0850 Rod pattern' adjustment complete, Ramping back to rated, i
August lith 2037 Back at rated MDC.
1 August 18th 0001 Reducing load for weekly turbine test and MSIV exercise.
4 0110 MSIV exercise complete.
0200 Turbine testing complete.
)
Ramping back to rated.
1 0341 Back at rated MDC.
j August 25th 0000 Reducing load for weekly turbine test and MSIV exercise.
4 0240 MSIV exercise complete.
0312 Turbine testing complete.
Ramping back to rated.
0721 Back at rated MDC.
August 31st 2400 Reducing load to approximately 710 GPME for weekly turbine testing.
8509190059 850031 PDR ADOCK 05000321 R
PDR l]
NARRATIVE REPORT UNIT 2 August 1st 0000 Unit on line at 792.3 GMWE and 2436 CMWT with no major equipment problems.
August 3rd 0125 Reducing load for weekly turbine testing.
0301 Testing complete.
Ramping back to rated MDC.
0355 Back at rated MDC.
August lith 0030 Reducing load for weekly turbine testing.
0221 Testing complete. Ramping back to rated.MDC.
0257 Back at rated MDC.
August 17th 0003 Reducing load for rod pattern adjustment and turbine testing.
0200 Investigating high temperature reading on "A"
Recirc pump motor.
0312 "A" Recirc pump taken out of service.
0830 Reducing power for reactor shutdown.
1025 Reactor manually scrammed, to investigate cause of "A" Recirc pump motor bearing high temperature.
August 18th 0450 Reactor startup in progress.
Pulling rods.
0730 Reactor critical.
August 19th 0432 Generator tied to line.
Ramping toward rated MDC.
August 21st 1705 Back at rated MDC.
August 23rd 2315 Reducing load for weekly turbine testing.
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NARRATIVE REPORT UNIT 2 t
k August-24th 0140 Testing complete l
0149 Back at rated MDC.
4 August 30th-2331 Reducing load for weekly turbine testing.
l August 31st 0205 Testing complete.
Back at rated i
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MDC.
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2400 Unit on line at 791 GMWE.
No major equipment problems,
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HATCH 1 SAFETY-RELATED MAINTENANCE WORK ORDERS TO BE REPORTED FOR AUGUST 1985 NUMBER DATE COMPLETED DESCRIPTION 85-3128 06-13-85 Replaced Tektronix hard copier (lX75-P631) with spare unit in the SPDS control room console.
Ref.
DCR 80-157, Rev. 1.
82-3269 06-25-85 Cut flanged section of 8" fire protection line and rotated horizonally 180* to a point out from under fuel pool condensate line.
Pipe was rewelded, hydro tested, and inspected per DCR 85-64.
84-2242 08-06-85 Temporary cable for Temp.
Recorder 1N30-R901 - MWO voided.
Work for DCR-82-265 postponed.
84-7485 07-31-85 Clean, prime and coat new
't pipe supports.
Work completed under MWO-1-85-2014.
r Ref.
DCR 80-183 and MWO-1-84-5910 85-4099 08-06-85 Replace bad conductor for RWCU Isolation valve (lG31-F001) indicating light with existing spare cable in panel Hll-P622.
Ref.:
DCR 85-112 85-4102 08-21-85 Installed padlock on circuit breaker for MSL Drain Throttle Valve per WPS-84-007-E001.
Ref. DCR 84-007 85-3860 08-l'5-85 Remove duplicate circuit and raceway labels in the intake structure building and replaced with new labels for the circuits indicated by DCR 85-101 and SDR-85-101-001.
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HATCH 1 SAFETY-RELATED MAINTENANCE WORK ORDERS TO BE REPORTED FOR AUGUST 1985 i
NUMBER DATE COMPLETED DESCRIPTION 85-3885 08-09-85 Removed excess flow check 4
i valve 1B31-F055 and t
performed wiring changes per WPS 83-26-E001.
Ref.: DCR 83-26 83-4112 08-24-85' Replaced bearing cartridge in RWCU dump valve (lG31-F034) with cartridge ordered for 2E51-F007 as per DCR-85-133.
85-2700 08-30-85 Upgraded masonry walls in the oil conditioner rooms 1
(lC-117 and 2C-117) from two hour rating to three hour rating per WPS-83-242-F001.
Ref. DCR 83-242 (Appendix "R")
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HATG 2 SAFETY-RELATED MAINTENANCE WORK ORDERS
'IO BE REPORTED FOR AUGUST 1985 NUMBER DATE COMPLETED DESCRIPTION 84-1484 08-30-85 Modified pipe supports to satisfy design requirements for piping system supports per I.E.B. 79-14.
Ref.: DCR 82-257, Rev. 1 and HNP-6942 84-5135 08-12-85 Replaced temporary recorder scales cn recorders 2P33-R601A&B and 2P33-R602A&B on panels 2Hil-P689 and 2Hll-P690 with permanent scales.
Ref. DCR 81-165 84-6052 08-28-85 Installed cable XZX901C29 between 2X75-P600 and 2X75-P602 per work package WPS 80-157-EC15. Redlined cable XZX901C29 per work package WPS 80-157-EM39 82-5716 06-13-85 Sealed penetration with silicone foam per HNP-6908.
Work done under MR 2-82-5729.
Ref. DCR 82-133 84-5746 08-02-85 Calibrated Validyne buffer amplifier modules in ERP panel 2X75-P601 per WPS 80-157-EM35 and HNP-2-5394. Replaced amplifier cards 2X75-K778 and 2X75-K797 which were found to be defective.
Ref. DCR 80-157, Rev. 1 84-5391 08-02-85 Disconnected existing cables and reconnected the same cables at different terminal block points in main control room panel 2Hil-P603 and SPDS consoles 2X75-P606 and 2X75-P608 and redlined the wiring.
Ref. DCR 80-157, Rev. 1 85-1289 08-06-85 Reworked and retagged the conduit supports CS-703-34 and CS-703-35 and clamped 2" outer diameter aluminum 2E12095 down to the conduit support CS-706-36.
Ref. DCR 80-157, Rev. 1 4
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HATCH 2 SAFETY-RELATED MAINTENANCE WORK ORDERS TO BE REPORTED FOR AUGUST 1985 NUMBER DATE COMPLETED DESCRIPTION 85-2750 07-04-85 Added anti-pumping circuitry to 2E51-F119 valve.
Ref. DCR 80-440, Rev. 1, FCR 80-440-23.
i 85-1945 07-25-85 Modify raceway supports per WPS 84-258-E001 FCR's 84-258-1 thru 6, HNP-6942 and 40AC-FPX01-0.
- Ref.:
DCR 84-258, (Appendix R) l 85-849 08-06-85 Installed raceways and terminal boxes, and revised routing of conduit in the TSC to accomodate field conditions for installation of new cables to 2X75-N020 and N019, and new spare cables.
Ref. DCR 80-157 Rev. 1 and WPS-80-157-RC10 & RC11.
85-2653 08-21-85 Modified raceway supports in east cableway and control building (elevation 130') as a
detailed in WPS-83-273-E001.
Ref. DCR 83-273 and DCR 83-237.
(Appendix "R")
84-5740 08-21-85 Repulled 11 cables to panel 2X75-P601 and 2X75-P104 to correct raceway routing per WPS 80-157-EC14.
j Ref. DCR 80-157, Rev. 1 85-2680 08-17-85 Modified contacts in relays a
2P33-K15A and 2P33-K15B in panels 2P33-P600A and 4
2P33-P600B respectively per FCR-81-165-117 and WPS-81-165-E031.
Ref. DCR 81-165.
85-2086 08-09-85 Modified existing supports and added new supports for existing conduit to accomodate the addition of fire protection wrapping.
Ref. WPS-83-224-E005 and DCR 83-224 l
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HATCH 2 SAFETY-RELATED MAINTENANCE WORK ORDERS TO BE REPORTED FOR AUGUST 1985 NUMBER DATE COMPLETED DESCRIPTION 85-3137 08-17-85 Replaced final filter module, installed new tubing, tubing l
clamp, and pressure regulator, and checked all tubing connections on panel 2P33-P006 i
per WPS-83-044-J009.
Ref.'DCR 83-44 84-1548 07-23-85 Reactor Building to outside atmosphere dp instrLmention MWO vcided.
Implementation of DCR 82-147 not performed due to design problems.
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84-6144 08-13-85 Revised internal wiring in panel Y33-P100 to provide a separate power supply to 1
Y33-P008.
1 Ref.: 'WPS-80-157-EM40 and DCR 7
80-157. Rev. 1 1
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WtEAnNG DATA REMk(T DOCKET NO.
50-321 DNIE 09-10-85 COMPLETED BY: Lee M. Kanipe, Jr.
TELEPHONE (912) 367-7781 x 2882 OPERATING STNIUS
- 1. Unit Name: E. I. Hatch Nuclear Plant Unit 1
- 2. Reporting Period:.
08-85
- 3. Licensed % ermal Power (tMt):
2436
- 4. Nameplate Rating (Gross PHe):
809.3
- 5. Design Electrical Rating (Net }We):
777.3
- 6. Maximum Dependable Capacity (Gross FMe):
801.2 7.11aximum Depenchble Capacity (Net }Me):
752.2
- 8. If Changes Occur in capacity Ratings
. (Items Number 3 through 7) Since Lcst Report, Give Reasons:
N/A
- 9. Power Ievel *o Wiich Restricted, If Any (Net PHe)
No Restrictions
- 10. Reasons for Restrictions, If Any:
N/A t
This Month Yr-to-Date Cumulative
- 11. Hours In Reporting Period 744 5831 84742
- 12. Number of Hours Reactor was Critical 667.0 4922.1 60086.1
- 13. Reactor Reserve Shutdown Hoars 0.0 0.0 0.0
- 14. Hours Generator On-Line 636.1 4693.1 56561.0
- 15. Unit Reserve Shatdown Hours 0.0 0.0 0.0
- 16. Gross hermal Energy Generated (PMH) 1498545 10565104 119934294
- 17. Gross Electrical Energy Generated (IMH) 488210 3462460 38718180
- 18. Net Electrical Energy Generated (PMH) 466525 3303624 36761470
- 19. Unit Service Factor 85.3 80.5 66.7
- 20. Unit Availability Factor 85.5 80.5 66.7
- 21. Unit capacity Factor (Using MDC Net) 83.4 75.3 57.7
- 22. Unit Capacity Factor (Using DER Net) 80.7 72.9 55.8
- 23. Unit Forced Outage Rate 14.5 15.4 17.9
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Refueling. Outage beginning Novecber 30, 1985 14 weeks
- 25. If Shutdown at End of Report Period, Estimated Date of Startup:
- 26. Units in Test Status (Prior to Cct:vnercial Operation):
Forecast Achieved INITIAL GITICALITY INITIAL EIECTRICITY OJPMERCIAL OPERATION e
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-321 DATE:
09-10-85 COMPLETED BY: Lee M. Kanipe Jr.
TELEPHONE (912) 367-7781 x 2882 MONTH 08-85 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1
-14 17 760 2
-14 18 755 3
-14 19 758 4
-14 20 761 5
120 21 761 6
645 22 762 7
739 23 762 8
760 24 762 9
762 25 753 10 567 26 762 11 700 27 762 12 762 28 761 13 762 29 760 14 761 30 761 15 759 31 760 16 757 e
9 e
9
UNIT SituTDOWNS AND POWER REDUCTIONS DOCKET NO.
50-321 UNIT NAM g liatch One DALE 09-07-85 REPORT MONTH.Augu s t 85 COMPLETED isY Le Kanino TELEFilONE (912) %7-7asl x.288.
b 7
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Y T*
Lkensee Ee Cause A Cusseslive 4
gM Event Ei Atelun so Nie.
Once f
g Report e Wu Prevens Racessence 85-68 850801 F
107.9 A
3 1-85-27 CD VALVEX Continuing outage to repair MSIV's following scram on 07-24-85.
85-69 850805 S
55.6 B
5 N/A CD VALVEX Scram recovery from above outage 85-70 850810 S
44.5 B
5 N/A RC CONROD Reducing Load for Rod Pattern Adjustment 85-71 850818 S
3.7 B
5 N/A HA TURBIN Weekly Turbine Testing and MSIV exercise.
85-72 850825 S
7.4 B
5 N/A IIA TURBIN Weekly Turbine Testing and MSIV exercise 1 1 9
I 2
3 4
F: Fwcad Reason:
Method:
Exhible G. Instructiuns 5: Scheduled A Estulpment Failuie(Emplain) 1 Manual for Preparation of Dais 84taintenance of Test 2-Manual Scram.
Entry Shecis foe LAcnsee C-Refueling 3-Automatic Scram.
Event Rspoes (LER) Fale (NUREG-D-Regulatory Resteletion 4 -Continuations 0861)
E4pesalor Training & Ucenes Fumadan los 5-Tnad Rev tion e
F Administsainvc 5
Goperantonal Essw(Empleta) g g gg Enhibis I.5ame Soww (9/n)
H4thes(Empiala)
OPERATING DATA RERRT DOCKET NO.
50-366 DATE 09-10-85 00MPLETED BY: Lee M. Kanipe Jr.
TELEPHONE (912) 367-7781 x 2882 OPERATING STA'lVS 1
Unit Name: E. I. Hatch Nuclear Plant Unit 2 2.
Reporting Period:
08-85 3.
Licensed termal Power (mt):
2436 4.
Nameplate Rating (Gross MWe):
817.0 5
Design Electrical Rating (Net me):
784.0 6.
Maximum Dependable Capacity (Gross MWe):
803.9 7.
Maximum Dependable Capacity (Net me):
747.9 8.
If Changes Occur in Capacity Ratings (Items Number 3 through 7) Since Last Report, Give Reasons:
N/A 9.
Power Level to Which Restricted, If Any (Net MWe):
No Restrictions
- 10. Reasons for Restrictions, If Any:
N/A
'Ihis Month Yr-to-Date Cumulative
- 11. Hours In Reporting Period 744 5831 52368 1
- 12. Number of Hours Reactor was Critical 722.9 4599.5 34779.5
- 13. Reactor Reserve Shutdown Hours
. 0.0 0.0 0.0
- 14. Hours Generator On-Line 701.9 4482.7 33106.8
- 15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
- 16. Gross Thermal Energy Generated (MWH) 1669728 10522464 71724046
- 17. Gross Electrical Energy Generated ( WH) 544510 3487470 23646950
- 18. Net Electrical Energy Generated (WH) 520652 3333678 22496127
- 19. Unit Service Factor 94.3 76.9 63.2
- 20. Unit Availability Factor 94.3 76.9 63.2
- 21. Unit Capacity Factor (Using MDC Net) 93.6 76.4 57.4
- 22. Unit Capacity Factor (Using DER Net) 89.3 72.9 54.8
- 23. Unit Forced Outage Rate 5.7 3.5 11.6
- 24. Shutdowns Schech11ed 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 Cocmercial Operation):
Forecast Achieved INITIAL CRITICALITY INITIAL ELECIRICITY COMERCIAL OPERATION a-.,--.,
l l
AVERAGE DAILY UNIT POWER LEVEL i
1 j'
DOCKET NO.
50-366 t
DATE:
09-10-85
)
COMPLETED BY: Lee M. Kanipe Jr.
TELEPHONE (912) 367-7781 x 2882 l-I-
i.
MONTH 08-85 I.
DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL j
(MWe-Net)
(MWe-Net) 1 763 17 163 2
767 18
-18 3
765 19 283 l
4 772 20 667 5
768 21 743 6
764 22 759 t
7 766 23 758
[
8 767 24 760 l
9 764 25 762 10 760 26 761 11 766 27-762-t 12 ~
765 28 764 13 765 29 762 i
14 764 30 762 I
15 766 31 762 i
16 764 1
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UNIT SilUIDOWNS AND FOWER REDUCTIONS h
- f g
DALE 09-07-89 COMPl.ETED BY T"
""i P
REPORT MON 1y Aurm e t-R9 TEl.EFilONE (912) 367-78 51 x.288 -
"c_
S d'{
]q Y*
- License, Ev Cause & Currective
}
sM Event No.
Date k
Atelon to Re-i.
R _.s. _
85-41 850803 S
2.5 B
5 N/A HA TURBIN Weekly Turbine Testing 85-42 850811 S
2.5 B
5 N/A HA TURBIN Weekly Turbine Testing 85'817 S
10.4 B
5 N/A RC CONROD Rod Pattern Adjustment and 85-43 0
Weekly Turbine Testing 85-44 850817 F
42.1 A
2 N/A CB MOTORX Manual Scram for investigation of Recirc Pump Motor "A" Bearing High Temperature.
85-45 850819 S
60.6 B
5 N/A CB MOTORX Recovery from above Scram 85-46 850823 S
2.6 B
5 N/A HA TURBIN Weekly Turbine Testing 85-47 850830 S
2.6 B
5 N/A HA TURBIN Weekly Turbine Testing l
l l 9
E 2
3 4
F: Forced Reason:
Method:
Exhibit G Instrucitune A 0 ulpment Failure (Emplain) 1 Manual for Prepsistlun of Dasa S: Scheduled 1
4 84taintenance of Test 2-Manual Scram.
Entry Sheets foe Lkeniec C-Refueling 3-Automatic Scram.
Event Rapost (LER) File (NUREG.
D Regulatory Restriction 4 -Continuations 01611 E Operator Tealning a ucanes Emaalaatiost 5-Ioad IWhrtion l
F Administrative 5
gggg G4)perational Esrue(Emplain)
Enhible I-Sanne Soww (97T1) 144): hat (Empiaka) 1
Georgia Power Company Post Offico Box 439 Baxley, Georgia 31513 Telephone 912 367-7781 912 537-9444 Edwin 1. Hatch Nuclear Plant September 6, 1985 LR-MGR-017-0985 PLANT E.
I. HATCH NRC Monthly Operating Report Director Office of Inspection and Enforcement United States Nuclear Regulatory Commission Region II Suite 3100 101 Marietta Street Washington, D. 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.
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H.
C. Nix General Manager tX d 938' HCN/CTJ/ GAG /EZW/UHR/bb xc:
T. V. Greene E. Z. Wahab J. H. Richardson Document Control File 0
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