ML20054A455
| ML20054A455 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 03/12/1982 |
| From: | Donna Anderson CONNECTICUT YANKEE ATOMIC POWER CO. |
| To: | |
| Shared Package | |
| ML20054A453 | List: |
| References | |
| NUDOCS 8204150468 | |
| Download: ML20054A455 (9) | |
Text
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CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM HECK PLANT HADDN4, COIUTECTICUT MONTHLY OPERATING REPORT NO, 82-1 FOR THE MONTH OF FEBRUARY 1982 8204150468 820210 DR ADOCK 05000213 PDR l
PLANT OPERATIONS:
The following is a summary of plant operations for the month of February.
Due to generator exciter repairs, the unit remained shut down until 2230 hours0.0258 days <br />0.619 hours <br />0.00369 weeks <br />8.48515e-4 months <br /> on February 7, 1982. The plant was phased on line and reached full power at 0315 hours0.00365 days <br />0.0875 hours <br />5.208333e-4 weeks <br />1.198575e-4 months <br /> on February 9, 1982.
On February 16 at 0905 hours0.0105 days <br />0.251 hours <br />0.0015 weeks <br />3.443525e-4 months <br /> the unit reduced load five MWe for approximately one hour to repair the west reheater drain tank level column.
The plant continued at full power until February 23 at lh05 when a load decrease was commenced to check for condenser tube leakage.
Leaking tubes were plugged in the "B" waterbox and the plant returned to full load 2150.
Another reduction to check for condenser tube leakage began at 0745 hours0.00862 days <br />0.207 hours <br />0.00123 weeks <br />2.834725e-4 months <br /> on February 26.
Leaks were found and plugged in "A, B and D" waterboxes.
The Engineering Department is conducting a study to determine the cause of these condenser tube leaks.
The unit returned to full power at 2205 hours0.0255 days <br />0.613 hours <br />0.00365 weeks <br />8.390025e-4 months <br /> and remained there through the rest of the month.
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......-..s SYSTEM GN CORRECTIVE ACTION TAKEN TO PROVIDE OR MALFUNCTION St.FE TAKEN TO FREVENT FOR KE!.0 TOR S EE'.'Y C09 0NENT CAUSE RESULT OPERATION P.EPETITION DURIEG REPAIR
'4.I.S.
Channel Unknown Priking
!!cne Peplaced Detector
!!one. Flant Shutdown.
v Charrine Flow pa:1 filter
-centro 11er
- cne. Pat Replaced capacitor.
- one Controller capacitor in would not work controller power supply.
in manual or in ~.anual autonatic.
backun mode.
2,ric Acic+ Tank Foric Acid Inrroper level
- cne Cleaned boric acid buildup,
'!anual observation Level buildup at indication.
of level by operator.
en of bubble tube.
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EFFECT SPECIAL PRECAUTIONS SYSTEM
?:AINTEiANCE CN CORRECTIVE ACTION TAKEN TO PRCVIDE.
OR MALFUNCTION COMPONENT CAUSE RESULT CAFE TAKEN TO PREVENT FOR REACTOR SAFETY OPERATION REPETITION DURING REPA1R di Beactor Coolnnt Lover oil Oil leakage None Eeplaced gasket.
U/A R mn'!ctor reservoir gasket lenl.
Retsen: Unknown EC3 Drain iender Corroded body Reduction in None Replaced 3 studs.
N/A Valve, "DV 53L to bcnnet studs.
cross sectional area of studs.
Penson: Foric acid leakage.
ECS Drain Header Corroded body Reduction in None Replaced 2 studs.
i/A Val.e "0V 521 to bonnet studs, cross sectional area of studs.
Reason:
Boric acid leakare.
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AVERAGE DAILY UNIT POWER LEVEL DOCKET No.
50-213 Conn. Yankee UNIT Haddam Neck DATE March 12, 1982 COMPLETED BY D. Andercon TELEPHONE (203) 267-2556 MONTil:
Februrity 1982 DAY AVLRAGE DAILY POWER LEVEL DA***
AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 0
17 581 2
18 581 0
0 581 3
19 0
4 20 582 5
21 582 0
6 22 582 0
7 23 537 1
281 581 g
24 580 9
575 25 h79 10 579 26 579 11 579 27 12 580 28 580 13 581 29 14 582 30 3c 581 31 582 16 4
INSTRUCTIONS On this format, list the averar,e daily unit power level in MWe-Net for each day in the reporting raonth.
Complete the nearest whole negawatt.
(9/77)
CONNECTICUT YANKEE REACTOR COOLANT DATA HONTH --FEBRUARY-1982 REACTOR COOLANT ANALYSIS MINIMUM AVERAGE MAXIMUM
-PH-G-25-DEGREES-C
- --5r18 E+00-:-5r62 E+0C :
S r90E+00 :
CONDUCTIVITY (UHHOS/CM) 8.65E+00 :
1.35E+01 :
1.90E+01 :
- <5.00E-02 : <5 00E-02 : <5.00E-02 :
-DISSOLVED-OXYGEN-(PPB)
- --45. 00E+00- -<5. 00E+00- -45,00E+00-BORON (PPM) 8.83E+02 :
1.08E+03 :
1.48E+03 :
1.15E+00 :
1.79E+00 :
-TOT AL-G A MM A-ADT,-( UG/ til->
2,09E-01 --:
1v29E+00 :
3,44 E-+OO-IODINE-131 ACT. (UC/ML) 4.16E-04 :
7.84E-03 :
1.08E-02 :
I-131/I-133 RATIO 6.40E-01 :
7.89E-01 8.86E-01
-CRUD-( MG/L-ITER >
-:-< 1. 0 0E -< 1. 00E-02 -:--<-1-. 00 E-02-1 TRITIUM (UC/ML) 1.28E+00 :
1.84E+00 :
2.20E+00 :
HYDROGEN (CC/KG) 2 48E+01 :
2.68E+01 :
2.84E+01 :
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AERATED LIQUID WASTE PROCESSED (GALLONS);
7.87E+04 WASTE LIQUID PROCESSED THROUGH BORON RECOVERY (GALLONS):
3.30E+04 AVER AGE-PR I MARY-LEAK-R AT E ( GALLONG-PER-J11NUTC )
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I REFUELING INFORMATION REQUEST 1
a 1
1.
Name of facility Connecticut Yankee Atomic Power Company
(
I 2.
Scheduled date for next refueling shutdown.
February 1983.
3.
Scheduled date for restart following refueling Mid March 1983 4.
(a) Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
No technical specification changes are anticipated at this time.
(b)
If answer is yes, what, in general, will these be?
U/A (c)
If answer is no, has the reload fuel design and core configaration been reviewed by your plant Safety Keview Comnittee to determine whether any unreviewed safety questiens are associated with the core reload (Ref. 10 CFR Section 50.59)? When documents are received from the vendor they are reviewed in accordance with 10CFR 50.59 to determine if unreviewed safety questions are core reload accociated.
(d)
If no such review has taken place, when is it scheduled?
U/A 5.
Scheduled date(s) for submitting proposed licensing action and supporting information.
There are no scheduled dated because of (h) above.
6.
Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance cnalysis methods, significant changes in fuel design, new operating procedures.
None 7.
The number of fuel assemblics (a) in the core atid (b) in the spent fuel e,torage pool.
(A) 157 (B) hh1 8.
The present licensed spent fuel pool storage capacity aiid the size of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies.
1168 9.
The projectcd date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.
199h to 1995
.