ML20117L737
| ML20117L737 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 03/31/1985 |
| From: | Blatt M, Otoole J CONSOLIDATED EDISON CO. OF NEW YORK, INC. |
| To: | Taylor J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| NUDOCS 8505160377 | |
| Download: ML20117L737 (6) | |
Text
- -.
o.-
d OPERATING DATA REPORT DOCKET NO. ~
DATE 4/5/85 COMPLETED BY M-Blntt TELEPHONE O1^ 9 % 9127 OPERATING STATUS
- 1. Unit Name:
Indian Point Station Unit #2 Notes March 1985 i
- 2. Reporting Period:
- 3. Licensed Thermal Power (MWt): 2758 1013
- 4. Nameplate Rating (Gross MWe):
- 5. Design Electncal Rating (Net MWe): 873
- 6. Maximum Dependable Capacity (Gross MWe): 900
- 7. Maximum Dependable Capacity (Net MWe):
864
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
None t
None
- 9. Power Level To which Restricted,if Any (Net MWe):
None
- 10. Reasons For Restrictions,If Any:
This Month Yr to-Date Cumulative 744 2160 94249 I1. Hours In Reporting Period 723.53 2113.67 62779.39
- 12. Number Of Hours Reactor Was Critical
- 13. Reactor Reserve Shutdown Hours 10.32 78.74 2374.44
- 14. Hours Generator On.Line 713.35 2047.35 60797.73
- 15. Unit Reserve Shutdown Hours 0
0 0
- 16. Gross Thermal Energy Generated (MWH) 1951051 5579521 158283896 I
- 17. Gross Electrical Energy Generated (MWH) 619180 1774040 49091656 597080 1709567 46823474
(
- 18. Net Electiical Energy Generated (MWH)
- 19. Unit Service Factor 49 4 94.R 64.5 j
- 20. Unit Availability Factor 95.9 94.8 64.5 l
- 21. Unit. Capacity Factor (Using MDC Net) 92.9 91.6 57.8 91.9 90.7 56.9 l
- 22. Unit Capacity Factor (Using DER Net) 4.1 5.2 9.5
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Over Next 6 Months (Type. Date.and Duration of Each):
None
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
- 26. Units In Test Status (Prior to Commercial Operation):
Forecast Achieved A
N/A INITIAL CRITICALITY INITIAL ELECTRICITY
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COMMERCIAL OPER ATION
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505160377 8503h247 1'
ADOCK 0500 Tg79 (4/77)
R PDR Y,
a AVERAGE DAILY UNIT POWER LEVEL 50-247 DOCKET NO.
I. P. Unit No. 2 WIT DATE 4/5/85 COMPLETED BY Blatt, M.
(914) 526-5127 TELEPHONE MARCH 1985 MONTH DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 854 17 844 855 2
gg 845 3
852 848 39 856 846 4
20 5
21 03 841-6 22 560 7
23 845 851 8
24 840 9
851 25 846 10 A91 26 176 11 848 27 760 848 12 28 855 13 847 29 852 14 846 856 30 15 849 31 856 16 845 INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.
(4/77) m
r 50-247 DOCKET NO.
UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME I _ p _ fini t #7 DATE A/ s/R 9 MARCH.1985 COMTED BY M-R1=e+
REPORT MONTH TELEPHONE
/oin M?9 5!27 M
w
,5 g 3
- Yh Licensee Ev, gn, Cause & Corrective gg s
3ss g{
Action to Event p
No.
Date c.
Prevent Recurrence e--
gE s
jg Report a mu c5 t
3 850306 F
16.95 A
3 85-004 CH Instru Unit Tripped on 23 S/G Low Level when F
23 Feedwater Regulator failed closed.
Tested, identified and replaced
~~'
defective relay and similar relays in other controllers -
4 850326 F
13.70 A
2 85-005 CH Valve X Unit Trip due to loss of Main Feedwatec F
Pumps, while working on Feedwater Regulating velve. Possible cause of trip-momentary high discharge pressure due to hydrostatic transient.
I 2
3 4
F: Forced Reason:
Method:
Exhibit G - Instructio' s n
S: Schedu!cd A Equipment Failure (Explain) 1-Manual for Preparation of Data B Maintenance of Test 2-Manual Scram.
Entry Sheets for Licensee C Refueling 3-Automatic Scram.
Event Report (LER) File (NUREG-D-Regulatory Restriction 44)ther (Explain) 0161)
E-Operat'or Training & Ucense Examination F-Administrative 5
G-Operational Error (Explain)
Exhibit I - Same Source (9/77)
Il-Other (Explain)
I
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gryme-, _.
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Summary of Operating Experience March 1985 Unit 2 operated at 100% power until March 6th.
On March 6th, the reactor automatically ' tripped on a combination of #23 Steam Generator Iow Level and mismatch between steam flow an'd feed flow to #23 Steam Generator.
The cause of the trip was the -failure of the relay in the #23 Steam Generator ' level controller during a surveillance test.
The' unit was restarted on March 7th and remained at 100% power until an electrical failure in the supply to a reheater steam valve caused a 10%
derating.
The electrical power was immediately restored and reactor power returned to 100%.
e On ^ March 26th, during a preplanned power descent necessary to repair a Feedwater Regulating Valve, a
loss of both Main Feedwater Pumps necessitated
-a' manual' trip of the reactor.
The power output was approximately 200 MWe at the time of the occurrence.
The Feedwater Regulating Valve was repaired and the reactor was restarted on March 27th. The unit remained at 100% power for the remainder of the month.
f j
r MAJOR SAFETY ~RELATED CORRECTIVE MAINTENANCE MWR NO.
SYSTEM COMPONENT DATE WORK PERFORMED 20144-AFW Valves FCV 3/26/85 Replaced
.405B & 406A existing temporary I/P converters with permanent equivalent models.
20253 CVCS Boric Acid 3/2/85 Rebuilt Pump Transfer Pump
>+
m.
7.
John D. O'Tocis S
V:ce Presdent
/
)7 Consolidated Ec son Company of New York, Inc
[J ]
4 Irving Place, New York, NY 10003 Telephone (212) 460-2533
]
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f h
April 16, 1985 Re:
Indian Point Unit No. 2 Docket No. 50-247 Mr. James M. Taylor, Director Office of Inspection and Enforcement c/o Distribution Services Branch, DDC, ADM U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Dear Mr. Taylor Forwarded herewith is one copy of the Monthly Operating Report for Indian Point Unit No. 2 for the month of March 1985.
Ver truly you kn.h'p,4fh Encl.
cc:
Dr. Thomas E. Murley, Regional Administrator Region I U.S. Nuclear Regulatory Commission 631 Park Ase.
King of Prussia, Pa. 19406 Senior Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 38 Buchanan, New York 10511 I
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