ML19341A229

Monthly Operating Rept for Dec 1980

ML19341A229
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	01/12/1981
From:	CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML19341A227	List: ML19341A226 ML19341A229
References
NUDOCS 8101220410
Download: ML19341A229 (8)

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CONNECTICUT YANKEE ATOMIC POWER COMPANY 4

HADDAM NECK PLANT j

f HADDAM, CONNECTICUT i

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I MONTHLY OPERATING REPORT NO. 80-12 FOR THE MONTH OF i

DECEMBER, 1980 1

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PLANT OPERATIONS The following is a chronological description of plant operations

'for the month of December 1980:

12/1/80 The plant was operating at 100 percent full power (606 MWe) at the beginning of this report period'and remained at full power until 2201 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.374805e-4 months <br /> on 12/12/80 when a load decrease was commenced to remove plant from line to test turbine over-speed trip mechanism.

12/5/80 Backwashed "D" Condenser waterbox at 0310 hours0.00359 days <br />0.0861 hours <br />5.125661e-4 weeks <br />1.17955e-4 months <br />. NRC hot-line phone out of service from 1640 hours0.019 days <br />0.456 hours <br />0.00271 weeks <br />6.2402e-4 months <br /> to 2105 hours0.0244 days <br />0.585 hours <br />0.00348 weeks <br />8.009525e-4 months <br />.

12/8/80 I&C Department replaced failed light source on Pressurizer Level Channel #1 at 1507 hours0.0174 days <br />0.419 hours <br />0.00249 weeks <br />5.734135e-4 months <br />.

i 12/12/80 Commenced' load reduction at 2201 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.374805e-4 months <br />.

12/13/80 Plant off line at 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br />. Tested turbine overspeed trip satisfactorily. Found no drift in set point. Unit phased to the line at 0548 hours0.00634 days <br />0.152 hours <br />9.060847e-4 weeks <br />2.08514e-4 months <br />. Load increased to 150 MWe at i

0710 and holding for Chemistry of Steam Generators.

i Backwashed all Condenser water boxes at 0944 hours0.0109 days <br />0.262 hours <br />0.00156 weeks <br />3.59192e-4 months <br />.

Commenced load increase.

1460 hours0.0169 days <br />0.406 hours <br />0.00241 weeks <br />5.5553e-4 months <br />. Plant was at full power at 2118 hours0.0245 days <br />0.588 hours <br />0.0035 weeks <br />8.05899e-4 months <br /> and remained at full power throughout he remainder of this report period.

12/14/80 Circulating water warming line placed in service at 2225 hours0.0258 days <br />0.618 hours <br />0.00368 weeks <br />8.466125e-4 months <br />.

12/15/80 #3 Rod drive cooling fa.- failed, 12/16/80 "B" Charging pump out of 1,ervice at 0957 hours0.0111 days <br />0.266 hours <br />0.00158 weeks <br />3.641385e-4 months <br /> to clean component cooling flow indicator.

"B" Charging pump returned to service at 1043 houre.

12/17/80 Charged air to Containment per SUR 5.1-6 from 2230 hours0.0258 days <br />0.619 hours <br />0.00369 weeks <br />8.48515e-4 months <br /> to 0420 hours0.00486 days <br />0.117 hours <br />6.944444e-4 weeks <br />1.5981e-4 months <br /> on 12/18/80 12/25/80 Received Hi AP alarm on #2 Steam line at 0703 hours0.00814 days <br />0.195 hours <br />0.00116 weeks <br />2.674915e-4 months <br />.

Sensing line frozen due to extremely cold weather, placed extra heaters in terry turbine room. Alarm cleared at 0754 hours0.00873 days <br />0.209 hours <br />0.00125 weeks <br />2.86897e-4 months <br />.

12/26/80 Pressurizer level, Channel #1 indication, did not move during six-week check, SUR 5.2-9, at 0956 hours0.0111 days <br />0.266 hours <br />0.00158 weeks <br />3.63758e-4 months <br />. Replaced level indicator at 1057 hours0.0122 days <br />0.294 hours <br />0.00175 weeks <br />4.021885e-4 months <br /> and tested satisfactorily.

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- p. 2 12/28/80 Failed light source on LIC 401-3 caused letdown trip valves to close and deenergized pressurizer heaters. Restored letdown valves to open and energized pressurizer heaters with Channel #3 override switch at 0624 hours0.00722 days <br />0.173 hours <br />0.00103 weeks <br />2.37432e-4 months <br />.

I&C replaced light source in LIC-401-3 and returned override switch to normal at 0858 hours0.00993 days <br />0.238 hours <br />0.00142 weeks <br />3.26469e-4 months <br />.

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es EFFECT SPECIAL FRECAUTIOiS SYSTEM ON CORRECTIVE ACTION TAKEN TO PROVIDE OR MALFUNCTION SAFE TAKEN TO PREVENT FOR REACTOR SAFEfY COMPONENT CAUSE RESULT OPERATION REPETITION DURING REPAIR

1. 3 Rod Duct Failed Fan Inoperable None.

Replaced Fan and Motor None required s

Cooling Fan Motor Bearings-Reason unknown "B" PAB Purge Wear on Outboard Noisy Outboard None Replaced Outboard Bearing None required Fan Bearing Bearing Prcssurizer Light Source Close letdown None Replaced Light Source None required Heater Failure valves, turn off (able to bypassi Controller pressurizer heat-LIC 401-1 er Feed Flow Failed Solenoid High level in None Replaced Solenoid Valves None re. quired Solenoid Valve Valve -

S.G. on Trip (MOV closure)

SV 1 6 3 on Reason, Mechani-Loop 2 cal Binding Pressurizer Level Failed drive Loss of Level None Replaced Motors None required LIA 401-1 &

Motor for indication 401-3 Indicator -Reason Indicators Mechanical Binding Reheater Control Failed Mercoid Loss of hi-level None Replaced Mercoid None required Mercoid on reheater hi-protection of level protection "C"

& "D" Reason, Mechani-Reheaters cal (Glass Broken)

Degasifier Improper level Overshoot on None Readjusted Controller None required Controller level control on setting -

startup Reason unknown e

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CONNECTICUT YANKEE REACTOR COOLANT DATA MONTH DECEMBER ~1980 REACTOR COOLANT ANALYSIS MINIMUM AVERAGE MAXIMUM PH7 25 DEGREES-~C 5.96Ef 00 :

6717Ef 00 ;

6732Ef00~i CONDUCTIVITY (UMHOS/CM) 8.91E+00 :

1.55E+01 :

2.05E+01 :

CHLORIDES (PPM)

<4.00E-02 : <4.00E-02 : <4.00E-02 :

7SS0tVED 0XYGEN-CPPB) e <5T00E+00- M 5700E+00 ; <5T00E+00 BORON (PPM) 7 42E+02 :

7.93E+02 :

8.42E+02 :

LITHIUM (PPM) 7.00E-61 :

1.40E+00 :

1.81E+00 :

(OTAL-GAMMA Au l. (UC/ML) i 1.73F+00 ;

3732Ef 00- !

4T29E+00 IODINE-131 ACT. (UC/ML) 1.69E-02 :

2.13E-02 :

2.49E-02 :

I-131/I-133 RATIO 6.90E-01 :

7.94E-01 :

9.20E-01 :

---CR U D-( M G/L'I T E R)

OT00E"Oi e 2.00E=04 e iT00E=O3 !

a TRITIUM (UC/ML) 1.14E+00 :

2.66Ef00 :

4.20E+00 :

HYDROGEN (CC/KG) 2.20Ef01 :

2.30E+01 :

2.40E+01 :

AERATED LIQUID WASTE PROCESSED (GALLONS):

8.83Ef04 WASTE LIQUID PROCESSED THROUGH BORON RECOVERY (GALLONS):

2.00E+04 AVERAGE-PRI M ARYTE AK'-R AT E( G ALLONS-PER-M I NUT E11--1. 06E-01 PRIMARY TO SECONDARY LEAK RATE (GALLONS PER MINUTE):

0.00E+00 l

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AVERAGE DAILY UNIT POWER LEVEL DbCKETNO.

50-213 Conn. Yankee UNIT Haddam Neck DATE 1-12-81 COMPLETED BY TELEPHONE (203) 267-2556 DECEMBER 1980 MONTH:

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 580 17 578 2

581 18 577 577 3

580 19 4

581 20 577 5

580 21 578 6

581 22 576 7

580 23 577 8

578 24 579 9

576 25 579 10 577 26 578 11 577 27 579 12 565 28 579 13 237 29 578 577 14 577 30 15 577 31 574 16 5?S INSTRUCTIONS On this format, list the average daily unit power lev'l in MWe-Net for each day in the reporting month.

Complete the nearest whole megawatt.

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UNITSl'U1110WNS ANfNOWER REDUCTIONS DOCKETNO. C nn. Yankee UNIT NA5f E

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N/A N/A 7.Z 4ZZZZZ Verification test of turbine overspeed trip setting.

Reactor was not subcritical T

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rreggtry t'... REACTOR ENGINEERING

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a y,.. : Esp yiLE Ci:cC!Tf t%T *% >... 555 Ci s In (AcACITY Ft.TI%it!!E=S ? TW.%w 7) SIN:E LAST FEPORT CIVE SEACONS.

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IF f.9ftNET "wE)..... PONE Efei( 1 F 'L EEiT'IC T F.*:.

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Tw!S RES0; tit FERIOD TR. TO DATE CU"ULATIVE TO DATE

• F.;* IN EEML?It PES!0D 784.0 8794.0 112976.0 +

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Nt=cES Or w9;c5 TuE FEACTrA WAS CRITICAL 744.0 6775.9 97972.6 +

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E M T00 CE!EcVE f WT!*%N Ke 9 3.8

?O.e 1193.4 +

14 w 9 5 '.En ci70c ON LIM 740.2 65&0.9 9?521.0 +

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t+IT ;EfEteE S WTDevM N0t/c3 3.?

3.9 373.7 16.

crgg; t-E:a4 E%CGY CENEcATED taWW

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UMi Ei.ECICI9L EMEGY CD1'4TED tNm 441572.

37497?2.

5?!031+?.

muuamme, 16.

FET ELECT 5" ?L ENELGY CEWCaTED INun 421654.

35t2B45, 50517tC?.

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a. WIT iEGT.E FMTOL 99.5 74.9 -

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t*!!T W !LtE!LI?y c4CTOR 100.0 75.0 62.4 +

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1.N I T.AFM1TV EACT09 Mis!NG MDC NET) 102.1 73.1 61.9 +

D 22 Wii (AseCITY FMTOR (USING DEF MET) 97.7 69.9 75.6 +

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TWIT COECE9 09 TACE FATE 0.0 1.2 6.9 +

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SWTD0e:S SCwEDta.ED OVED PEIT 6 MWHStTVFE,DATE AND I*. CATION OF EACM..

NONE

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!E SWTIM ' END OF EE500T!*C FEFIOD, EST!"ATED PATE OF STAKT'Jo.... N/A N

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MITf-14 TEST 57A%$ttRIOR TO CO'=5 (Clot 06EteT10%)....NOT ADFi!C AttE

+i!% E EA'E OF CC""ERCIAL OFEtaT109 1-1-69 0'

-REFUELING INFORMATIO. TREPO J 1.

Name.cf f. cility a

Connecticut Yankee Atomic Power Company Scheduled date for next refueling shutdown.

t September / October 1981 3.

Scheduled date for restart following refueling Approximately six to eight vecks.

I 4.

(a) Will refueling or resumption of operation thereaf ter 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?

N/A (c'

If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Co=mittee to determine whether any unreviewed.afety questions are associated with the core reload c

(Ref. 10 CFR Section 50.59)?

When 'the above stated documents are received from the fuel vendor they will be reviewed in accordance with 10CFR50.59 to determine if any unreviewed safety questions are associated with the Core reload.

(d)

If no such review has taken place, when is it scheduled?

N/t.

5.

Scheduled date(s) for submitting proposed licensing uction and supporting information.

There are no scheduled dates because of (4) above.

6.

Important licensing consideration associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuci design, new operating procedures.

None 7.

The number of fuel assemblies (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 size of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblics.

1168 The projected date of the last refueling that can be discharged to the spent 4

fuel pool assuming the present licensed capacity.

1994 to 1995