Text

Monthly Operating Rept for June 1979
	ML19225A183
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	07/13/1979
From:	; CONNECTICUT YANKEE ATOMIC POWER CO.
To:	;
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ML19225A182	List: ML19225A181; ML19225A183;
References
	MOR-790630, NUDOCS 7907180527
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CONNECTICUT YANKEE ATOMIC PC'JER COMPANY llADDAM N".CK PLANT IIADDAM, CONNECTICUT MONTitLY OPERATING REPORT No. 79-6 FOR Tile MONTil 0F JUNE, 1979 3 k, I

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PLANT OPERATIONS The following is a chronological description of plant operations for the month of June, 1979.

6/1/79 Hot line phone from Control Room to NRC in Bethesda installed and op rational.

6/6/79 1B Auxiliary Feedwater pump out of service 1050 hours0.0122 days 0.292 hours 0.00174 weeks 3.99525e-4 months to 1150 hours0.0133 days 0.319 hours 0.0019 weeks 4.37575e-4 months for Maintenance.

6/8/79 Load Reduction to < 65% full power commenced at 2l00 hrs.

Load at 350 MWe and #4 Loop idled at 2232 hrs. for repairs to leak on

4 Steam Generator hand hole.

6/9/79 Turbine stop and control valve test performed and all condenser waterboxes beckwashed while at reduced power.

4 loop returned to service at 1050 hrs. following maintenance and plant at full power at 1600 hrs.

6/13/79 Discontinued extra operator on feed water watch at 1330 hrs. with permission of NRC.

6/20/79 1B Auxiliary Feedwater pump out of service at 0740 hrs. for repairs.

Retested and returned to service at 1640 hrs.

6/26/79 Diesel fire pump removed from service for repairs at 0822 hrs.

Retested and returned to service at 0950 hrs.

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EFFECT SPECIAL PREQUTIONS SYSTEM ON CORRECTIVE ACTION TAKEN TO PROVIDE OR MALFUNCTION SAFE TAKEN TO PREVENT FOR REACTOR SAFETY COMPONENT CAUSE RESULT OPERfTION REPETITIOJ DURINC REPAIR Leop 2 Steam Line Air in sen ing Higher than None Vented transmitter and Placed trip signal in trip s

Break Transmitter lines normal reading check zero matrix duritig repai rs Loop 4 Steam Line Stuck motor No pointer None, trip Replaced rnotor Placed trip signal in Break indicator novement function trip matrix during independent repairs of pointer Loop 3 Steam Line Stuck motor and No pointer None, trip Replaced unit with spare.

Placed trip signal in Break indicator had slidewire movement function trip matrix indep mdent during repairs.

of pointer Loop 1 Steam Line Stuck motor No pointer None, trip Replaced motor Placed trip signal in Break indicator movement function trip matrix during independent repairs of pointer Aux. Feed System S-PICV-1206B Leakage by seat Long coastdown None Lapped valve Tested other pump for after test run operability before removing valve and B pump from service.

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CHEMISTRY DATA FOR MONTH OF June, 1979 Reactor Coolant Analycis Minimun Averare Maxinun l

Ph 9 25 C( 2.0E-01) 5.68 E+00 6.23 E+00 6.55 E+00 Conductivity, unbon/cmf 25) 1.40 E+01___

1.77 E+01 2.05 E+01 Chlorides, pnr.( 7.0E-02T

< 4.00 E-02

< 4.00 E-02 Dissolved Oxvren, pnb ( 5.0E+00)

< 5.0C E+00

< 5.00 E*00

< 5.00 E+00 Boron, ppm (125) 8.42 E+02 8.87 E+02 9.97 E+02 1.63 E+00 2.00 E+00 Lithium, num ( 55) 1.30 E+00 Total Gamma Act. uCi/ml (1 10%)

4.94 E+00 6.37 E+00 7.42 E+00 Iodine-131,uCi/m1( ?5) 2.89 E-02 3.51 E-02 4.24 E-02 1-131/I-133 Fatio 6.70 E-01 8.09 E-01 9.40 E-01 Crud, ng/1( 1.0E-02) 7.00 E-02 1.59 E-01 2.15 E-01 2.79 E+00 4.51 E+00 Tritium, uCi /r:1( 5.0E-02) 1.71 E+00 Hydrogen,cc/kc( 2.0E+00) 2.01 E+01 2.89 E+01 3.63 E+01 Aerated liquid waste processed:

1.38 E+05 gallons Waste liquid processed through Boron Recovery Systen' O.00 gallons Average primary plant leak rate:

0.110 gpm Primary to secondary leak rate:

0.00 gpm

OTERATING DATA REPORT DOCKET NO.

50-211 7 13 7b DATE COMPLETED BY Reactor En,'incering TELEPHONE (203) 267-2556 OPERATINC STATL'S 1.

cnit Name: Conn. Yankee Atomic Power Co.

NOTES 2.

Reporting Period:

June, 1979 5

3.

Licensed Thermal Power (M2t):

}825 4.

Na:neplate Rating (vrass tr.Je): 600.3 5.

Desiga Electrical Rating (Net M'Je ) :

575 6.

hximum ' =pendable Capacity (Cross Fr.ce): 577 550 7.

Ma&

N

'dable Capacity (Not 1Ne):

8.

If Caanges e cur 'n Capacity Ratings (Items 3 Through 7)Since Last Raport, Give Reasons:

N/A 9.

Power Level To Which Restricted. If Any(Net Br.ic):

None 10.

Reasons For Restrictions. If Any:

N/A This Month Yr.-To-Date Cumulative 11.

Hours In Reporting Period 720.0 4,343.0 100,775.0 12.

Number of Hours Reactor tias Critical 720.0 3,378.7 87,034.2 0.0 0.0 898.1 13.

Reactor Reserve Shutdown Hours 720.0 3,274.0 82,786.6 14.

nours Generator on-Line 15.

Unit Reserve Shutdown Hours 0.0 0.0 136.4 16.

cross Thernal Energy Generated (M'.iii) 1,300,611 5,825,080 142,764,163 17.

Cross Electric 1 Energy Cencrated(3rJH) 423,688 1,917,294 46,949,708 18.

Net Electrical Energy Generated (>r.iii) 404,542 1,823,882 44,662,306 100.0 75.4 82.1 19.

Unit Service Facter 100.0 75.4 82.3 20.

Unir Availability Factor 102.

76.4 82.1

21. Unit Capacity Factor (Using MDC Net) 22.

Unit Capacity Factor (Using DER Net) 0.0 0.0 7.6 23.

Unit Forced Outage Rate 24.

Shutdowns Scheduled Over Next 6 Months (Type. Date and Duration of Each):

Shutdowns are being planned to meet requirements of Bulletins 79-13 and" 79-14.

Exact dates and duration not known at this time.

25.

If Shutdown At End Of Report reriod, Estiuted Date of Startup:

N/A 29.

Units In Test Status (Prior to Commercial Operations):

Forecast Achieved INITIAL CRITICALITY N/A N/A INITIAL ELECTRICITY N/A N/A N/A N/A C010!ERCIAL CPERATION

Since date of commercial operation 1/1/68.

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(9/77)

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-213 Conn. Yankee UNIT ltaddam Neck DATE 7/13/79 L

COMPLETED BY Reactor Engineering TELEPil0NE (203) 267-2556 MONTil:

June, 1979 DAY AVERACE DAILY PO'JER LEVEL DAY AVERAGE DAILY PO'iER LEVEL (MWe-Net)

(MWe-Net) 1 578 17 567 2

577 18 564 3

577 19 563 4

576 20 562 5

577 21 561 6

577 22 560 7

577 23 560 8

550 24 561 9

437 25 561 10 573 26 561 11 572 27 562 12 574 28 561 13 573 29 5,60 14 573 30 560 15 573 31 16 569 INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month.

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REFUELING INFORMATION REQUEST 1.

Name of facility Connecticut Yankee Atomic l'ower Company 2.

Scheduled date for next refueling shutdown.

April, 1980 c

3.

Schc duled date for restart following refueling.

Approximately eight weeks from shutdown date.

4.

(a) Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?

No refueling technical specifications 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 decign and core configuration been reviewed by your Plant Safety Review Committee to determine whether cay unreviewed safety questions are associated with the core relo.d (Ref. 10 CFR Section 50.59)?

No (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 infort ation.

There are no sch:duled dates because of (4) above.

6.

Important licens ing considerations associated with refueling, e.g.,

new or different fuel design or supplier, unreviewed design or performance aaalysis methods, significant changes in fuel design, new operating pro edures.

None 7.

The number of fuel assemblies (a) lu the core and (b) in the spent fuel storage pool.

(a) 157 (b) 340 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 9.

erhe projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.

1914 or 1995 a

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ML19225A183

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