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Monthly Operating Rept for Apr 1981
	ML19345H410
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	05/12/1981
From:	; CONNECTICUT YANKEE ATOMIC POWER CO.
To:	;
Shared Package
ML19345H409	List: ML19345H408; ML19345H410;
References
	NUDOCS 8105200249
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.

- CONNECTICUT YANKEE ATOMIC POWER COMPANY

.HADDAM NECK PLANT HADDAM, CONNECTICUT 4

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MONTHLY OPERATING REPORT NO. 81-4 i

FOR THE MONTH OF APRIL 1981 810520 0 W

PI. ANT OPERATIONS The following is a chronological description of plant operations for the month of April 1981:

4-1-81 The plant was operating at 100 percent full power (605 MWe) at the beginning of this report period and remained at full power until 0400 hours0.00463 days 0.111 hours 6.613757e-4 weeks 1.522e-4 months on 4-11-81 when load reduction was commenced for valve test and condenser tube cleaning.

4-3-81 Spurious signal from pressurizer pressure channel #1 opened PR-A0V-570 and PR-MOV-569. Operator placed control switch for PR-A0V-570 in closed position to terminate loss of pressurizer pressure at 1980 psig. at 0929 hours0.0108 days 0.258 hours 0.00154 weeks 3.534845e-4 months .

Pressure restored to 2000 psig at 0935 hours0.0108 days 0.26 hours 0.00155 weeks 3.557675e-4 months . I&C department found connector to signal indicator on main control board loose causing signal to fail high.

4-6-81 Burned leads on 'B' heater drain pump on attempted start.

Isolated and tagged 'B' heater drain pump for Maintenance.

4-8-81 Environmental monitoring package out of-service for cleaning 1000 hours0.0116 days 0.278 hours 0.00165 weeks 3.805e-4 months to 1300 hours0.015 days 0.361 hours 0.00215 weeks 4.9465e-4 months .

4-11-81 Commenced load reduction at 0400 hours0.00463 days 0.111 hours 6.613757e-4 weeks 1.522e-4 months to 350 MWe. Performed turbine stop and control valve test and increased load to 400 MWe at 0705 hours0.00816 days 0.196 hours 0.00117 weeks 2.682525e-4 months .

'A' condenser waterbox isolated, drained and opened for Maintenance 0 0645.

'A' condenser waterbox returned to service after cleaning tubes and checking for leaks at 1828 hours0.0212 days 0.508 hours 0.00302 weeks 6.95554e-4 months .

'B' condenser waterbox out of service 0 1945 hours0.0225 days 0.54 hours 0.00322 weeks 7.400725e-4 months .

4-12-81 Completed cleaning and leak check of 'B' condenser water box tubes and commenced load increase @ 0523 hours0.00605 days 0.145 hours 8.647487e-4 weeks 1.990015e-4 months . Reached full load at 0919 hours0.0106 days 0.255 hours 0.00152 weeks 3.496795e-4 months and remained at full load for the remainder of this report period.

4-13-81 Removed discharge canal environmental package from canal. On backup surveillance schedule.

i 4-24-31 13 service water pump returned to service following overhaul at i

1435 hours0.0166 days 0.399 hours 0.00237 weeks 5.460175e-4 months .

l Turbine control system problem causing load fluctuations of approximately l

6 MWe several times this month.

i l

4-28-81 EG-2A out of service 0710 hours0.00822 days 0.197 hours 0.00117 weeks 2.70155e-4 months for redundant systems check.

i EG-2A retested and returned to service at 1735 hours0.0201 days 0.482 hours 0.00287 weeks 6.601675e-4 months .

4-29-81 EG-23 out of service at 0700 hours0.0081 days 0.194 hours 0.00116 weeks 2.6635e-4 months for redundant systems check. 1A

^

heater drains pump cavitating. 13 heater drain pump returned to service following maintenance and 1 3 heater drains pump shut down. EG-23 retested and returned to service at 1842 hours0.0213 days 0.512 hours 0.00305 weeks 7.00881e-4 months .

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EFFECT SPECIAL PEECAUTIOXS ON CORRECTIVE ACTION TAKEN TO PRO?,IDE SYSfE:1 OR MALFU!!CTION SAFE TAKEN TO PREVENT FOR REACIG*l Sal'ETY COMptr:ENT CAUSE RESULT OPERATION REPETITION DURING REPAlil O Pressurizer Pressure Loose connector Loss of channel None: Pressur-Connector taped to control-Use of portions of

, Channel on Plc 401-1 control on PORV.

izer pressure ler.

Checked all other SUR 5.2-4.

Plc - 401-1 (controller for Opened PORV 570 decreased connectors for tightness.

Redundant indication PORV) and MOV 569.

s 25-30 PSIC of pressurizer pressure Reason for loose were available, connector was possibly jarring of flCli by workmen Area Monitors -

Failed liigh Vol-Loss of area None Replaced transistors None Left Side Lage power supply monitors R-31, transistors.

R-40, R-32, R-37, Reason: Probably R-33.

caused by age (had been operat-Ing for > five years).

Area Monitors -

Fa11ed-25 volt Loss of area None Replaced cable in R-34 None required Right side power supply -

Monitors R-34, channel, repaired -25 volt caused by ground R-39, R-35, R-38, power supply, installed on R-34 cabling R-36 correct fuses in all and improper channels a

-25 volt fuse.

Pressurizer pressure Failed capacitors 1.oss of indica-None Installed higher voltage None required Channel 3 in Indicator tion on channel 3 rated capacitors.

power supply, pressure Reason: failure (computer reading probably caused still available).

by low voltage rating of capacitors O This item was inadvertently reportei. In March, pleas delete.

CONNECTICUT YANKEE REACTOR COOLANT DATA MONTHi APRIt.~1781 REACTOR COOLANT ANALYSIS MINIMUM AVERAGE MAXIMUM T W 7 25 DEGREES C--

6.07E F00

- 6 i37E+00-:--- 6 i50E+00 ;

CONDUCTIVITY (UMHOS/CM) 8.20E+00

1 15E+01 :

1.90E+01 :

CHLORIDES (PPM)

<4.00E-02 : <4.00E-02 : <4.00E-02 :

--DISG CLVE Er0X YG EN-t PPE i 5. 00E + 00-0--< 5 ; 00 E+ 00-MS. 00E+00-:

EORON (PPM) 3.90E+02 :

4.32E+02 :

5.42E+02 :

LITHIUM (PPM) 7.00E-01 :

.04E+00 :

2.00E+00 :

M OTALM AMMA-ACT. (UC/MLi 2726 E + 0 Cr-;

1. 31E + 00- -4T 52E+00- P IODINE-131 ACT. (UC/ML) 1.25E-02 :

1.91E-02 :

2.54E-02 :

I-131/I-133 RATIO 7.00E-01 :

7.83E-01 :

8.70E-01 :

--CRtjD7M Gft-! T E R) 0. 0 0 E-'01 OWOE-01 ;

OT00C-01 ;

e TRITIUM (UC/ML) 3.18E+00 :

3 56E+00 :

4.33E+00 :

HYDROGEN (CC/NG) 1.86E+01 :

2 50E+01 3.19E+01 :

AERATED LIQUID WASTE PROCESSED (GALLONS):

9.69E+04 WASTE LIQUID PROCESSED THROUGH BORON RECOVERY (GALLONS):

3.26E+04 AVER AGE-PRI M ARPtE AK-R AT E ( G alt 0NS-PER-MI NUTE )M 47E-01 PRIMARY TO SECONDARY LEAK RATE (GALLONS PER MINUTE):

0.00E+00 200R OR8 K

AVERAGE DAILY UNIT P0b'ER LEVEL DOCKET NO.

50-213 Conn. Yankee UNIT _Haddam Neck DATE by 12, 19.*,1 COMPLETED BY Reactor Engineering TELEPHONE (203) 267-2556 April 1981 MONTH:

DAY AVERAGE DAILY P0b'ER LEVEL DAY AVERAGE DAILY P0kE.1 LEVEL (FNe-Set)

(FNe-Net) 1 579 17 577 i

579 578 18 578 3

19 578 4

579 20 577 5

579 21 577 6

579 22 576 7

579 23 577 8

578 24 578 578 579 9

25 577 10 26 580 l

412 11 27 580 517 12 28 579 577 13 29 576 578 14 30 577 578 15 31 577 16 I! STRUCTIO: S On this formac, list the average daily unit power level in >Ne-Net for each day in the teporting month.

Complete the nearest whole megawatt.

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.CKT.INO I;70itu"M'i-RI:CUEC.

1,. N,a D2 c i fC C 111Cy Connecticut Yankee Atomic Power Co=pany Scheduled date for next refueling shutdown.

s Septe=ber/ October 1981 3.

Scheduled date for restart following refueling Approxi=stely six to eight weeks.

4.

(a) Will refueling or resu=ption of operation thereaf ter require a technical specification change or other license asendment?

No technical specification changes are anticipated at this time.

(b)

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

N/A (c)

If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Cc==ittee to determine whether any unreviewed safety questions are associated with the core reload (Ref. 10 CFR Section 50.59)?

When the above stated documents are received fro = the fuel vendor they will be reviewed in accordance with 10CFR50.59 to determine if any unreviewed safety cuestions 4.re associated with the Core reload.

~

(d)

If no cuch 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.

I=portant licensing consideration associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis t

methods, significant changes in fuel design, new operating procedures.

l None 7.

The nu=ber of fuel asse=blies (a) in the core and (b) in the spent fuel storage pool.

(a) 157 (b) 38'9 8.

The present licensed spent fuel pool storage capacity and the si:e of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assc=blics.

1168 l

The projected date of the last refueling that can be discharged to the spent

~ ~ ~ ~ ' '

fuci pool assuming the present licensed capacity.

t 1994 to 1995 w

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ML19345H410

Text

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