ML20054G166
| ML20054G166 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 06/14/1982 |
| From: | Donna Anderson CONNECTICUT YANKEE ATOMIC POWER CO. |
| To: | |
| Shared Package | |
| ML20054G163 | List: |
| References | |
| NUDOCS 8206210197 | |
| Download: ML20054G166 (9) | |
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CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT.
i HADDAM, CONNECTICUT i
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MONTHLY OPERATING REPORT NO. 82-5 FOR THE MONTH OF i
I MAY 1982 4
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4 8206210197 820614 DR ADOCK 05000213 PDR
PIANT OPERATIONS:
The following is a summary of plant operations for the month of May:
The unit operated at full power until May 14, when load was reduced at 400 MWe to plug leaking condenser tubes.
The plant reached full power on May 15 and remained there throughout the rest of the month.
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L0717 LEG 1C a d r.u 1 AA. rar.LAvatLl,a SYSTEM INSTRUMENT AND CONTROL ON CORRECTIVE ACTION TAKEN TO PROUIDE OR MALFUNCTION SAFE TAKEN TO PREVENT FOR REACIOR SAFETY COMPONENT CAUSE t
RESULT OPERATION REPETITION DURING REPAIR NIS Power Range Faulty full power Drifting of NONE Replaced full power NONE amplifier.
output.
amplifier.
Loop 4 AT Resistance to Drifting of NONE Replaced R/I Converter with Loop instrumentation current converter reading and improved design, placed in defeat mode, failed due to output to faulty magnetic Reactor Control amplifier.
System.
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CONNECTICUT YANKEE REACTOR COOLANT DATA O
MONTH: MAY 1982 O
REACTOR COOLANT ANALYSIS MINIMUM AVERAGE MAXIMUM O
PH G 25 DEGREES C 6.24E+00 :
6.52E+00 :
6.74E+00 :
CONDUCTIVITY (UMHOS/CM) 1.40E+01 1.67E+01 :
2.50E+01 :
CHLORIDES CPPM)
- <E00E 02r !75 00E;02 ; o.00E-02 ;
C DISSOLVED OXYGEN (PPB)
- <5.00E+00 : <5.00E+00 : <5.00Ef00 :
DORON (PPM) 5.87E+02 6.36E+02 :
6.83E+02 :
1.43E+00 :
1.94E+00 :
C TOTAL GAMMA ACT. (UC/ML) 1.08E+00 :
1.53E+00 :
1.78E+00 :
IODINE-131 ACT. (UC/ML) 5.60E-03 :
7.89E-03 :
9.37E-03 !
T;13r/ r-T3TRATIO 6.85E-01 :
8.49E-01 :
1.00EF6D :
Cl CRUD (MG/ LITER)
- <1.00E-02 : <1.00E-02 : <1.00E-02 :
TRITIUM (UC/HL) 3.31E+00 :
3.44Ef00~
3.'74Ef01 :
3.63E+00 :
~~~~ HYDROGEN ~'CC/KG) 2'.29E+01~T-~3.00E+0'1
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O AERATED LIQUID WASTE PROCESSED (GALLONS):
1.35E+05 WASTE ~LIOUID PROCESSED THROUGH DDRON RECOVERY (GALLONS):
8.44E+04
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O AVERAGE PRIMARY LEAK RATE (GALLONS PER MINUTE):
2.25E-01 PRIMARY TO SECONDARY LEAK RATE (GALLONS PER MINUTE):
0.00E+00 O
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l AVERAGE DAILY UNIT POWER LEVEL DOCKET No. 213 Conn. Yankee UNIT Haddam Neck DATE 6-14-82 COMPLETED BY D. Anderson TELEPHONE (203) 267-2556 MONTH:
May 1982 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 580 1
17 576 580 2
18 575 579 3
19 575 579 4
20 574 578 5
21 574 6
578 22 575 7
578 23 576 8
578 24 577 578 578 25 9
575 577 26 10 577 573 11 27 577 574 12 28 576 575 13 29 532.6 575 30 14 561.5 575 15 37 576 16 INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month.
Complete the swarest whole megawatt.
(9/77)
UNIT SilUTDOWNS AND POWER REDUCTIONS DOCKET NO.
50-213 UNIT NAME Conn.. Yankee DATE 6/15/82 COMPLETED BY D. Anderson REPORT MONTil May 1982 TELEPHONE (203)267-2556 mo
$ ud U
cm N
-o d E Licensee
$,e E%
Cause & Corrective No.
Date E.
US E
.S U
- Event U$
8.3 Action to N
$6 U.E $
Report #
$d 8U Prevent Recurrence o
Emg o
82-06 82-05 14 S
0 A
N/A N/A HC llTEXCII Load decrease to 400 MWe to check for t
condenser tube leakage.
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4 Method:
Exhibit G-Instructions
~
F Forced Reason:
S Scheduled A-Equipment Failure (Explain)
Il-Other(Explain) 1-Manual fur Preparation of Data B-Maintenance or Test 2-Manual Scram Entry Sheets for Lic2asce C-Refueling 3-Automatic Scram.
Event Report (LER) File D-Regulatory Restriction 4-Other(Explain (NUREG-0161)
E-Operator Training & License Examination
/
F-Administrative 5
Exhibit 1 Same Source l'
C-Operational Error (Explain
REFUELIt:0 I!; FORMA *i10N REQUEST 1..
Name of facility Connecticut Yankee Atomic Power Company 2.
Scheduled date for next refueling shutdown.
Late January 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 speci'ications changes are anticipated at this time.
(b)
If answer is yes, what, in general, will these be?
N/A (c)
If answe'r is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Co=mittee to determine whether any unreviewed safety questions 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 19)eqqyggfsuchreviewhastakenplace,whenisit scheduled?
N/A 5.
Scheduled date(s) for submitting proposed licensing action and supporting information.
There are no scheduled dates because of (4) above.
6.
Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures.
NONE 7.
The number of fuel assemblics (a) in the core and (b) in the spent fuel storage pool.
(A) 157 (B) 441 8.
The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies.
1168 9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.
1994 to 1995 I
I
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