ML20042B045
| ML20042B045 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 05/04/1978 |
| From: | Kawula L CONSOLIDATED EDISON CO. OF NEW YORK, INC. |
| To: | |
| Shared Package | |
| ML20042B044 | List: |
| References | |
| NUDOCS 8203240433 | |
| Download: ML20042B045 (9) | |
Text
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to Unit tio. 1 Instrumentation and Control Repair Data Component MWR #
Malfunction Corrective Action None during March, 1978.
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zu Indian Point Station Docket No.50-003 I
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OPERATING DATA REPORT DOCKET NO.
50-247 DATE 5/4/75 C051PLETED BY L. Kawula TELEP!10NE 914-694-6000 Ext. 209 @'I.P.
OPER ATING STATUS Indian Point Unit No. 2 Not'5 I' Unit N'*#'.
f Fuel shuffle completed
- 2. Reporting Period:
April, 197 g_7g g
- 3. Licensed Thermal Power I.\\lWt):
of tube support plate 1013
- 4. Nameplate Rating (Gross.\\lwel:
from No. 23 steam gen-
- 5. Design Electrical Rating (Net SIWel:
873 erator for inspection 900
- 6. Slasimum Dependable Capacity (Gross SIWel:
and testing.
004
- 7. Stasimum Dependable Capacity (Net.\\1We):
S. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:
NONE
- 9. Power Level To Which Restricted,if Any (Net.\\lwe):
- 10. Reasons For Restrictiom. lf Any:
This Month Yr..to Date Cumulative 719 2 879 33 goo iI. Ilours in Reporting Period
- 12. Number Of Ilours Iteactor Was Critical 0
1 032.30 21 386.60 0
0 0
- 13. Reactor Resene Shutdown flours
- 14. Ilours Generator on Line 0
1 032.30 20 756.27
- 15. Unit Resene Shutdown Hours 0
0 0
- 16. Gross Thermal Energy Generated t.\\lwif) 0 2 812 193 52 764 088
- 17. Gron Electrical Energy Generated t. lWil) 0,__..
840 450 16 358 976
\\
- 18. Net Electrical Energy Generated (SIWH)
-1 631 798 971 15 589 828
- 19. Unit Senice Factor 0
35.8 61.7
- 20. Unit Asailability Factor 0
35.8 61.7 0
32.1 53.7
- 21. Unit Capacity Factor iUsing %IDC Net) f
- 22. Unit Capacity Factor (Using DER Neti 0
31.7 53.1 0
0 9.6 l
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Oser Nest b.\\lonths (1)pc. Date,and Duration of Each t:
Refueling Outage in progress.
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- 25. If Shut Down At Fnd Of Report Period. Estimated Date of Startup:
May 23. 1978
- 26. Units in Test Status tPrior to Commercial Operationi:
Forceast Achieved 1
1 INITI A L CRITICALITY INITIA L El.ECTRICITY N/A N Co\\is1ERCiAt oPER sTioN 3
(4/77)
AVER AGE DAILY UNir POWER LEVEL 50-247 DOCKET NO.
incian roa.nt UNIT Unit.2p. 2 DATE 5/4/78 CONIPLETED BY L. Kawula TELEPflONE 914-694-6000 Ext. 209 0 I.P.
MON 111 APrile 1978 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (51We Net)
(5fWe Net) 1 0
0 37 O
2 0
18 r
3 0
19 0
4 0
20 0
5 0
21 0
0 6
22 0
7 0
23 0
g 0
24 0
9 0
2s 0
10 0
26 0
1I O
27 0
0 0
12 33 13 0
29 0
14 0
30 0
15 0
3, 16 0
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INSTRUCTIONS I
On this format. list the average daily unit power leses in h!We Net for each day in the reporting month. Compute to the nearest whole megawait.
(9/77)
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50-247 DOCKET NO.
UNIT SHUIDOWNS AND POWER REDUCTIONS UNI T NA%f E I.P. Unit No. 2 ~
DATE 5/4/78 G awula COMPLETED BY REPORT MONTil April, -1978 914-694-6000 TELEP2iONE Ext. 209 @ I.p.
E c
.! E 3
4 Yl Licensee
[-r, Cause & Cor receive No.
Date 3,
g 2;
.s i 5 Event 3,7 l'?
Assionto fE 5
y ;g c Report u
, u) L E
Present Recurrence O
e 6
1 780213 S
719 C
1 N/A RC ZZZZZZ Refueling outage in progress.
I 2
3 4
F: Forced Reason:
Method:
Exhibit G Instructions S: Scheduled A Equipment Failure (Explain)
I-Manual for Preparatien of Data B. Maintenance of Test 2-Manual Scram.
Enis) Sheets for Licensee C Refueling 3-Automatic Scram.
Event Repose (LER) Fde (NUREG-D-Regulatory Restriction 4 Other (Explain) 0161)
E-Operator Training & Ucense Examination F Administralise 5
G-Operational Error (Explain)
Eshibit I-Same Source 19/77)
Il4)ther (Explain) 1 4
Indian Point Station DOCKET NO.
50-247 UNIT Unit No. 2 DATE May 5, 1978 COMPLETED BY J. Makepeace TELEPHONE 914-739-8823 Summary of Operat.ng Experience - April, 1978 i
Unit No. 2 remainet. 11. the cold shutdown condition for the entire report period for Cycle 2/3 refueling / maintenance activi-ties.
Highlights of these activities during April, 1978 were as follows:
1)
Using remote underwater cameras, the loose object known to be located at the bottom of the reactor ves-sel was observed.
The object was rectangular in shape wit approximate dimensions of 7 1/2" x 1 3/4 x 1/4" and was non magnetic.
A review of reactor internal drawings, fuel drawings, etc. did not disclose any hardware that could be the source of this object.
Attempts to retrieve the piece were unsuccessful.
A safety analysis was performed and the results in-dicate that the reactor can be operated safely with the object in the vessel.
2)
In the course of transferring a burnable poison assem-bly from fuel assembly D-44 to assembly B-09, one of the rodlets broke off and remained in one of the D-44 thimble tubes.
Since D-44 was to have been a rodded assembly, it was switched with a symmetrical assembly to accept the control rod in that particular location.
A thimble plugging device was installed in D-44 thus capturing the section of rodlet remaining in the fuel assembly.
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3)
Core refueling was successfully completed, and remote verification and inspection was accomplished.
During 5
refueling operations, all part length control rods were removed from the core (Reference Amendment No.
38 to DPR-26).
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4)
Reactor vessel inspections, as required by Section XI of the ASME B & PV Code, were completed.
5)
Following relatching of the full length control rods, the reactor head was landed, and all reactor vessel flange studs were tensioned.
6)
A containment spray system nozzle test was success-fully completed using infrared thermography to verify that all nozzles were clear.
7)
A sample of tubes and tube support plate was removed from No. 23 Steam Generator.
The sample contained several pieces as a result of cracks in ligaments between flow holes and second and third row tube holes.
Subsequent boroscopic examination of flow holes and tube hole ligaments beyond row three did not reveal additional cracking or observable elongation of flow holes.
The sample section will undergo further testing and evaluation in connection with the steam generator chemical cleaning development prbgram.
At the close of this report period, maintenance activities continue in preparation for the impending return to service scheduled for late May, 1978.
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Unit No. 2 Instrum2ntation and Control Repair Data Component MWR A
!!alfunction Corrective Action 3-3-78 LT-460 2H52318I Reads low.
Recalibrated.
3-11-78 Battery Chargers 2C52242I D.C. Bus grounds.
Freed grounds.
3 16-78 No. 22 Battery 2C52060I Ammete( erratic.
Replaced ammeter.
Charger 3-18-78 Bistable 427E 2H523371 Out of calibration.
Gleaned, reset pots.
3-23-78 Rod Selector 2H52328I Loose, readings Cleaned contacts.
Switch erratic.
3-23-78 RPI Voltmeter 2C22355I Readings erratic.
Cleaned contacts.
3-28-78 PC-455E 2C52388I Instrument drift.
Replaced power supply.
Indian Point Station Docket No. 50-247 1
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Unit No. 2 Mechanical and Electrical Maintenance Data Component MUR #
Malfunction Corrective Action 3-8-78 Valve IA-39 2N57250 Valve leaks through.
Renewed valve.
3-8-78 Valve 1616 2N57260 Valve leaks through.
Installed new valve.
3-8-78 Polar Crane 2H57289 Pendant float switch Installed new float defective.
switch.
3-9-78 Seismic Restraint 2C57229 Bolts missing.
Replaced bolts.
SR-M54 3-9-78 Seismic Restraint 2C57233 Bolts missing.
Replaced missing bolts.
SR-M26 3-10-78 80' Airlock 2N56048 Gear slips.
Installed new shaft seals and cam followers.
3-14-78 Valves 1822 2H55994 Valve leaks through.
Renewed discs, gaskets.
A, B
3-14-78 New Fuel 2H57302 Cracked weld, bent Repaired tool.
Handling Tool bar.
3-15-78 Valve 518 2N57263 Valve leaks through.
Installed new valve.
3-16-78 Spent Fuel 2N57269 Bearing worn.
Replaced bearings and Pit Pump mechanical seal.
3-17-78 Valve BFD-69 2C55569 Valve leaks through.
Relapped valve.
3-17-78 No. 22 Auxi-2C56375 Outboard pump gland Repacked pump.
liary Boiler leak.
Feed Pump Indian Point Station i
Docket No. 50-247
t.
Unit No. 2 Mechanical and Electrical Maintenance Date Component MWR #
Malfunction Corrective Action 3-19-78 Valva 1809 2N56939 Valve leaks through.
Repaired, rewelded valve.
3-21-78 Valve 989J 2N56772 Valve leaks externally.
Renewed valve.
3-21-78 21 Boric Acid 2N17312 Mechanical seal leak-Replaced mech. seal.
Transfer Pump age.
3-21-78 22 Boric Acid 2N17313 Pump seized.
Cleaned out crystallized Transfer Pump boron.
3-23-78 Valve 869B 2N57279 Valve leaks through.
Cleaned, renewed gasket.
3-24-78 Valve 1828 2H56787 Valve leaks through.
Cleaned, polished valve.
Indian Point Station Docket No. 50-247 i
-CA
May, 1978 Docket No. 50-247 Ref:
Letter Hartfield/Cahill, i
1/18-78.
1 Refueling Information Request l
1)
Indian Point Unit No. 2 2)
Currently in progress l
3)
Approximately May 23, 1978 4) a)
None for current outage b)
Yes 5)
N/A 6)
None 7) a)
193 assemblies b) 132 spent fuel assemblies.
8) a)
482 assemblics b)
Request for approval of preliminary design for the storage of Unit 2 spent fuel within the Unit No. 1 storage pools was submitted on May 4, 1978.
9)
January, 1981 (full core reserve)
January, 1984 (without full core reserve)
_1 k
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