ML20052G589

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Monthly Operating Rept for Apr 1982
ML20052G589
Person / Time
Site: Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 05/14/1982
From: Donna Anderson
CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML20052G582 List:
References
NUDOCS 8205180488
Download: ML20052G589 (10)


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CONNECTICUT YANKEE ATOMIC POWER COMPANT llADDAM NECK PLANT HADDAM, CONNECTICUT MONTHLY OPERATING REPORT NO. 82-4 FOR THE MONTil 0F APRIL 1982 l

820518M"

PLAF" OPERATIONS:

The following is a summary of plant operations for the month of April:

The unit operated at full power until April 24.

At 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br />, a load reduction to 300 Mwe was commenced to repair a hand hole gasket leak on the secondary side of #3 steam generator and to investigate high "B" main feed pump motor vibration.

Condenser tube leaks were plugged while the plant was at reduced power.

A load increase to 400 Mwe was commenced on April 26, to conduct a turbine stop valve test.

The unit reached full power on April 26, at 1505 hours0.0174 days <br />0.418 hours <br />0.00249 weeks <br />5.726525e-4 months <br /> and remained there throughout the rest of the month.

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EmMA9tf SPECIAL FREGAUTIONS SYSTM-Instrument and Control ON CORRECTIVE ACTION TAKEN TO PROVIDE OR MALFUNCTION SAFE TAKEN TO PREVENT FOR REACTOR SAFETY COMPONENT CAUSE RESULT OPERATION REPETITION DURING REPAIP.

  1. 1 Pressurizer Level Failed power Erronous reading NONE Replaced power supply Channel trip in service Indicator supply due to due to channel while repairs were made, failed output
failure, filter capacitors
  1. 1 Steam Line Indicator drive Loss of main NONE Replaced drive motor Channel trip in service Break Flow Indicator motor stuck, control board while unit out of main indication of control board.

steam line flow (excess flow trip still in service and computer readout of flow still available:.

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SYSTEM MAINTENANCE ON CORRECTIVE ACTION TAKEN TO PROUIDE l

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f COMPONENT CAUSE RESULT OPERATION REPETITION DURING REPAIR I

"B"' Emergency Leak in flexi-Loss of service NONE Replaced flexible hose N/A Diesel Heat ble hose.

water with straight pipe.

Exchanger Inlet Reason. Age Line

  1. 1 Main Steam Tight stem Sluggish valve NONE Readjusted packing and N/A Isolatior Trip
packing, operation.

successfully retested Valve valve.

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-213 Conn. Yankee UNIT Haddam Neck DATE 5-14-82 COMPLETED BY D. Anderson TELEPHONE (203) 267-2556 MONTH:

April 1982 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWEk LEVEL (FNe-Net)

(bMe-Ne t) 1 581 17 581 2

581 18 581 3

581 19 580 4

581 20 580 5

580 21 580 6

580 22 579 579 7

580 23 338 8

579 24 311 9

580 25 10 581 26 453 11 580 27 580 12 580 28 580 580 13 580 29 580 14 580 30 580 15 31 580 16 INSTRUCTIONS On this format, list the avarage daily unit power 1cvel in MWe-Net for each day in the reporting month.

Complete the nearest whole megawatt.

(9/77)

p 4

" m W g=

maarm mum.J+ m a diuEmm mN N645 4

NTenewW+es%-m==-m-CONNECTICUT YANKEE REACTDIL. COOL ANT DATA MONTH: APRIL 1982 REACTOR COOLANT ANALYSIS MINIMUM.

AVERAGE MAXIMUM 6.55E+b0 6.69E+00 PH h 2b DEbiNEC C 6.15E+00

' CONDUCTIVITY (UMHOS/CM) 1.65E+01 :

1.87E401 :

2.15E+01 :

!--CHLOR I DE S-4 PPM L-

-- 4-45+40 E42--- ' % COE-02

<5;00E-02 !

DISSOLVED OXYGEN (PPB)

<5.00E+00 : <5.00E+00 : <5.00E+00 :

DORON (PPM) 6.86Lt02 7.45E+02 :

8.54E+02 1

72EF^^

1: 07E+00 L.LT HIUt L 4L PiR 1_32EtOO TOTAL GAMMA ACT. (UC/ML) 1.13E+00 :

1.58E+00 :

2.11E+00

-IODINE-131 ACT. (UC/MLJ 5.76E-03 :

1.14E-02 6.95E-02

--I-131/ I-13 3 -R A TI G---

?-5.59E-O-1 Lote-O1 !

1 + 04E-400 CRUD (MG/ LITER)

<1.00E-02 : <1.00E-02 : <1.00E-02 :

TRITIUM (UC/ML) 2.08E+00 3.07E+00 :

3.58E+00 :

-RYDROGEt4-4CC/KG )

'J 90EL^1

'7;04F'^1 3;5cE101

+

1 l

l l

AERATED LIQUID WASTE PROCESSED (GALLONS):

9.61E+04 4ASJF4dGUI-D-FROGEG8ED-THRGUGH-BORON-REGOVEM4G^LLONS } *

^ 00E-01

(

AVERAGE PRIMARY LEAK RATE (GALLONS PER MINUTE):

2.04E-01 i

PRIMARY TO SECONDARY LEAK RATE (GALLONS PER MINUTE)*' O.00E+00 g

l f

I i

1 1

-~ _

~

UNIT SilUTDOWNS AND POWER REDUC 110NS POCKET NO.

50-213 UNIT N/J!E Conn Yankee DATE 5/14/82 COMPLETED BY D. Anderson TELEP110NE(203)267-2556 REPORT MONTIl April 1982 e N)

YwU U

cm m

d3 0 E

e Ji E Licensee

@<r E*o Cause & Corrective No.

Cate E.

E SU#

Event U$

S. 'E Action to

$?

jEi Report #

$70

@U Prevent Recurrence l

u Emg i

82-05 820424 S

0 A

N/A N/A CH PUMPXX Reduce power to repair A) Vibration on IB Steam Generator feed pump, i

HJ HTEXCH B) Leaking Steam Generatorinspectioh hand hole on #3 l

S.C.

I HC HTEXCH C) Check for tube

{

leaks in all four Water Boxes.

1 I

l l

i 1

2 3

4 Method:

Exhibit G-Ins t ruc t ions F Forced Reason:

S Scheduled A-Equipment Failure (Explain)

II-Other(Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee 3-Automatic Scram.

Event Report (LER) File C-Refueling D-Regulatory Restriction 4-Other(Explain (NUREC-0161)

E-Operator Training & License Examination

/

F-Administrative 5

Exhibit 1 Same Source i

G-Operational.. Error (Explain

3 REFUELING INFORMATION RE0'IEST 1.

Name of facility

(

Connecticut Yankee Atomic Power Company.

i 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 specification changes are anticipated at this time.

(b)

If answer is yes, what, in general, will these be?

9 N/A (c) If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee 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 associa*ed.

(d) If no such review has taken place, when is it 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 assemblies (a) in the core and (b) in the spent fuel ntorage 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 l

!