ML20077A582
| ML20077A582 | |
| Person / Time | |
|---|---|
| Site: | Indian Point |
| Issue date: | 06/06/1983 |
| From: | Eich E, Otoole J CONSOLIDATED EDISON CO. OF NEW YORK, INC. |
| To: | Mcdonald W NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| NUDOCS 8307220365 | |
| Download: ML20077A582 (11) | |
Text
'I
~
\\
AVERAGE DAILY UNIT POWER LEVEL 50-247 DOCKET NO.
I.P. Unit 2 GIT
-~
DATE
. COMPLETED BY
~
TELEPHONE
~
MAY 1983 MONT11 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net)
(MWe-Neo 850 848 3
17-845 848 2
8 3
19 854 848 4
20 852 848 5
21 6
761 g49
- y 499 850 7
23 61 8
24 852 447 851 9
25 849 85'l 10 26 846 850 33 7
848 847 12 3
851 851 13 29 844 850 I4 30 849 853 l
15 33 855 l
l INSTRUCTIONS On this format. list the aserage daily unit power leselin MWe Net for each day in the reporting month. Compute to the nearest whole nwgawait.
PH77)
-go L-k l 'I 8307220365 830606 PDR ADOCK 05000247 R
i l
i.
OPERATING DATA REPORT 50-247 DOCKET NO.
D-D-N DATE COstPLETED BY R-F-
Wich TELEPIIONE 914-526-5155 OPERATING STATUS Indian Point Unit No. 2 Notes
- 1. Unit Name:
- 2. Reporting Period:
2758
- 3. Licensed Thermal Power (N!Wt):
1013
- 4. Nameplate Rating (Gross 31WeI:
873
- 5. Design Electrical Rating INet SIWE):
885
- 6. Slaximum Dependable Capacity (Gross 51We):
849
- 7. 51aximum Dependable Capacity (Net SlWe):
- 8. If Changes Occur in Capacity Rating (gms Number 3 Through 7) Since Last Report.Give Reasons:
- 9. Power Level To which Restricted.lf Any (Net 31We):
N/A
- 10. Reasons For Restrictions,if Any:
This Stonth Yr. to-Dat e Cumulative 744 3623 78168
- 11. Hoursin Reporting Pen d 33.26 3b W um
- e o
- 12. Number Of Hours Reactor Was Critical 10.72 33.85 1612.36
- 13. Reactor Resene Shu,tdown Hours 714.75 2874_50 49713_ An
- 14. Hours Generator On Line O
n n
IS. Unit Reserve Shutdown Hours 143??4A 7am?Ana 1 oooooo on
- 16. Gross Thermal Energy Generated (31WH)
- 17. Gross Electrical Energy Generated (51RHI 6168 0_,
2343366 39545655' 592950 2236926 37968983
- 18. Net Electrical Energy Generated (5tWH) 96.1 79.3 63_6
- 19. Unit Senice Factor 96.1 79_3 63_6
- 20. Unit Availability Factor 93_9 71 A RA_5
- 21. Unit Capacity Factor IUsing SIDC Net) 41.9 vn 7 55,g
- 22. Unit Capacity Factor IUsing DER Net) 1 Q o_g 9,o
- 23. Unit Forced Outage Rate
,24. Shutdowns Scheduled Oser Nest 6 31onths IType.Date.and Duration of Each):
NnNP NA
- 25. If Shut Down At End Of Report Period. Estimated Daie of Startup:
- 26. Units in Test Status IPrior to Commercial Operation):
Forecast Achiesed INITI\\L CRITICALITY h
INill \\L ELECTNICITY NA N
N Comirnent ornunoN es/771
=
50-247 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
y7 UNIT NAME Unit 2 DATE 6/6/83 D n E.
F.
Wh REPORT MONTil TELEPif0NE 414-526-5155 e.
.!'E 3
.Y Licensee
,E t,
4 Cause & Corrective.
No.
DJte i
5g
.s s E Event y
Action to
$E 5
j;5 Report #
mO Present Recurrence H
g O
N/A 830506 S
0 B
4 HA VALVEX Load Reduction Due to Turbine F
Valve Testing
.'N/A
,830507 S
0 B
4 CH PUMPXX Load Reduction Due to Repair B
of 22 MBFP Control System Unit Manually Tripped Due to Loss cf 9
830508 F
29.25 G
1 CH PUMPXX-21 MBFP. The Ioss of 21 MBFP Was B
Caused by Inadvertent Operator Introduction of Gasket Material into j
System During Oil Filter Change Blocking Orifice in 21 MBFP Controls.
I 2
3 4
F: Forced Reason:
Method:
Exhibit G-Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B Maintenance or Test 2-Manual Scram.
Entry Sheets for Licensee C-Refueling 3 Automatic Scram.
Event Report iLER) File (NUREG.
D Regulatory Restriction 4-Other (Explain) 0161)
E Operator Training & Ucense Examination F-Administrative 5
G-Operational Error (Explain)
Exhibit I - Same Source (9/77) 11-01her ( Explain)
SUMMARY
OF OPERATING EXPERIENCE Docket No.:
50-247 Date:
6/7/83 Completed by:
J. Curry Telephone No.: (914) 526-5235 Indian Point Unit No. 2 operated at 100% reactor power from May 1 through May 6, when load was reduced to conduct the turbine stop and control valve monthly test, and to make repairs on #22 Main Boiler Feedwater Pump (M.B.F.P.).
Load was maintained at 300 MWe during the test, and #22 M.B.F.P.
was shutdown and repaired. Upon completion of test and repairs, load was increased.
On May 8,
while the unit was at 90% reactor power #21 M.B.F.P.
ran down to zero load and the unit was tripped manually as the low steam generator level automatic trip was approached.
The unit was returned to service on May 9 and returned to 100% power.
t
Docket No.:
50-247 Dates 6/10/83 Completed by:R. Platt, D. Army May, 1983 INDIAN POINT UNIT NO. 2 MWR NO.
DATE SYSTEM COMPONENT CORRECTIVE MAINTENANCE 202-6607 1/13/83 SW 480 Volt Replaced. defective Amptector Breaker SWP trip device.
- 22 202-6342 1/13/83 RCS RCS Loop.3 Reconnected disconnected Delta-T RTD Indication 202-6491 1/13/83 480V 480 Volt Replaced defective Amptector Switchgear Breaker
. trip device.
52/6A 201-6436 1/13/83 MS
- 21 Steam Drained water and cleaned Atmospheric orifice in I/P converter Relief Valve i-i p
i--.-er-,av w
-w-
-a,p9.
g y,
9---y
-+-
p
+m-,
-p.r,y-wm--
9
,e e-y,w-,
Docket No.:
50-247 Date:
6/10/83 Completed by:R. Platt, D. Army May, 1983 INDIAN POINT UNIT NO. 2 MWR SYSTEM COMPONENT CORRECTIVE MAINTENANCE DATE 602 SW SWN 2 Thru 5 Replaced valves 12/27/82 1324 MRS MS 55A thru D Replaced valves 12/22/82 2765 WDS Weir Dump Replaced valves 12/22/82 Valves 21-25 3222 PMW Valve 522 Repaired operator 12/17/82 4256 FW FCV 417 Replaced operator 1/20/83 5364 Elec 21ABFP Breaker Replaced coil 1/18/83 5438 RCS Valve 529 Replaced valves 12/30/82 6136 CSS 21 Containment Replaced motor 12/22/82 Spray Pump 6237 HVAC PCV-1191 Repaired Air Operator 12/27/82 6415 SW SWN 46 Repaired Operator 1/7/83 6617 CVCS Valve 4007 Replaced Valve 1/26/83 192 RCS 24 RCP Motor
. Replaced Rotor / Stator 1/24/83 193 RCS 21 RCP Motor Replaced Rotor / Stator 1/24/83 1079 RCS RV 464-Tested Valve-12/15/82 1080 RCS RV 468 Tested Valve 12/15/82 1081 RCS RV 466 Tested Val"e 12/15/82 1231 SIS MOV 1822A Repaired Valve 12/23/82 1232 SIS MOV 1822B Repaired Valve 12/23/82 1517 PSS Valve 955E Repaired Operator 12/16/82 2269 RCS Valve 4140 Replaced valve 1/26/83 3893 SW 26 SW Pamp Overhauled pump 12/23/82 4258 HVAC FCV 1171 Adjusted Air Operator 12/23/82 5097 MRS MS-52 Tested Relief Valve 12/22/82 5153 CVCS PCV 213 Repacked Valve &
12/1*/82 Repaired Bonnet 5156 SIS MOV 850B Repaired Operator 12/1?/82 5255 SGB Blowdown Tank Repaired Leak on Tank 1 /21/.13 5360 RCS PCV 953 Replaced Packing Gland 1/26/E3 Nuts 5403 WDS Valve 5430 Replaced Valve 12/28/E1 5544 RHR MOV 731 Replaced Bonnet Studs 1/24/83 5582 SIS MOV 1803 Repaired Operator 12/22/82 5631 RCS Seal Table Repaired fitting leak 1/3/83 5720 CVCS RV 231 Replaced Valve 1/14/83 5895 Elec 23 Sta. Battery Removed 2 cells 1/18/83 5896 Elec 24 Sta. Battery Removed 2 cells 1/18/83 5909 MRS MS 1/2 Valves Lubricated Operators 1/6/83
[
Docket No.:
50-247 Date 6/10/83 Completed by:R. Platt, D. Army May, 1983 INDIAN POINT UNIT NO. 2 MWR SYSTEM COMPONEN?
CORRECTIVE MAINTENANCE DATE 5985 WDS 22 RCDT Pump Rebuilt Pump 12/28/82 6072 PSS MOV 4399 Replaced Operator 12/20./82 6134 RHR 22 RHR Pump Replaced Pump 1/28/83 6259 SW 25 SW Pump Overhauled Pump.
12/23/82 6280 RCS 24 RC Pump Installed Balance Nut 12/22/82
-6698-IA 22 Inst Air Overhauled Compressor 1/27/83 Comp 6699 IA
- 22 Inst Air Overhauled Motor 1/27/83 Comp Motor
_.e..
--.i..-
.v Page 1 of 3 SYSTD4 INITIALS Reactor Cociant System (RCS)
Reacter Yessel and Internals (AVI)
Chemical and Volume Centrol Systes (CVCS)
Auxiliary Coolant Systen (ACS)
Waste Disposal Systern (kT)S)
Primary Make-up Water System (PMW)
Steam Generator Biowdown System (5G8}
Primary Sampling System (PSS)
Plant Chemistry (PC)
Safety Injectf:n Sy: tem (SIS) i Containment Spray System (CSS)
Isolation Yalve Seal Water System (IV5WS)
Nydrogen Recombiner System (HR)
~
Wald ChanneF and Containr.ent Penetration (WCCP)
Post Accident Containment Sacoling System (PACS) l l
Residual Heat Removal (RNR)
(
Vapor Containment Building (VC) l Containment Isolation System (CIS)
Hot Penetration Cooling System (HPS)
Radiation Monitoring and Protection System (RM)
In-Care Indrumentation System (IT)
Nuclear Instrumentation System (NI)
.P e4
-, erwve e
s a
ahe La e
- re e a W 'as A
Page 2 of 3 SYSTEM INITIALS Penetration Cooling Air System (FCA)
Main and Reheat Steam System (MRS)
Extraction Steam (EXS)
Condensate System (CS)
Secondary Sampling (55)
Main Botter Feedwater System (FW)
Aur Boiler.Feedwater System (AFW
~
Intake Structure (IS)
Service Wate,r System (SV)
Main Turbine and Generator (MTG)
Electrical System (ELEC)
Overall Unit Protection Systen (UP)
~
Heating. Ventilation and Air Conditioning (HVAC]
Ausf11ary St'eam (AS) lastrument Air Systers (IA)
StationAirSystem(SA) l Chemical Feed (CF) l City Water (CYW)
Fire Protection (FP)
Nitrogen. Hydrogen and Oxygen to Nuclear Equipraent (NHO)
Cranes and Monorails (CM)
- ~
Buildings and Grounds (B/G) e*
r
=
--- - -. - w
..., _ w -
_,.w
_.n.
n, m--
- m
Page 3 of 3 1,
Camputer(C)
General (GEM) - Lubricattca, Stoteroom, Coanunications New and Spent Fuel Handling and Storage (FH)
Hater Treatment Plant (hTP)
Emergency Diesei Generators (EDG) - 21,22,23 linit 1 Nuclear (UIN)
Support Facility (SF) - Unit I Mon-Nuclear systems, fe. RW Security $;/ stem (SEC)
Neusa Service Soilers (HSB)
Gas Turbines (GT) - 1,2,3 Condenser Air Removal and Ventitation (CAV)
Chlorination System (CL)
Closed Cooling Systen (CC) e
.s
?.
9 l
f
John D. O'Toole 4*
j V<e Pre 9 dent Consoudated Edison Company of New York, Inc.
4 lieng Piace, New York, NY 10003 Te!ephoree (212) 460 2533 June 15, 1933 Ret Indian Point Unit No. 2 Docket No. 50-247 Mr. William G. Mcdonald, Director Office of Management Information and Program Control c/o Distribution Services Branch, DDC, ADM U.
S. Nuclear Regulatory Commission Washington, D. C. 20555
Dear Mr. Mcdonald:
Enclosed you will find two copies of the Monthly Operating Report related to Indian Point Unit No. 2 for the month of May 1983.
Ver truly yours, Y]g 3'Y Encl.
cc:
Mr. Richard DeYoung, Director (40 copies)
Office of Inspection and Enforcement c/o Distribution Services Branch, DDC, ADM U. S. Nuclear Regulatory Commission Washington, D.
C. 20555 Mr. James M. Allan, Acting Regional Administrator Region I U.
S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pa.
19406 Mr. Thomas Foley, Senior Resident Inspector U.
S. Nuclear Regulatory Commission P. O. Box 38 Buchanan, New York 10511 W) l
@G 1
l 1 3