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Monthly Operating Rept for Aug 1981
	ML20042B340
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	09/14/1981
From:	Donna Anderson; CONNECTICUT YANKEE ATOMIC POWER CO.
To:	;
Shared Package
ML20042B335	List: ML20042B334; ML20042B340;
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T CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT HADDAM, CONNECTICUT MONTHLY OPERATING REPORT NO. 81-8 FOR THE MONTH OF AUGUST 1981 i

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Plant Operations The following is a summary of plant operations for the month of August 1981:

The plant operated at full power until 1605 hours0.0186 days 0.446 hours 0.00265 weeks 6.107025e-4 months on August 23, when the unit was taken off line to repair RHR valve that had excessive valve stem leakoff.

This leakage contributed to a total RCS leakrate of approximately 2.7 g.p.m.

Repairs were started on RH-M0V-804 at 1400 hours0.0162 days 0.389 hours 0.00231 weeks 5.327e-4 months on August 24 and were completed at 1934 hours0.0224 days 0.537 hours 0.0032 weeks 7.35887e-4 months the same day.

The reactor was critical at 1218 and the plant was phased onto the grid at 1505 on August 25. The unit reached full power at 1251 hours0.0145 days 0.348 hours 0.00207 weeks 4.760055e-4 months on August 26, 1981.

The plant remained at full power for the remainder of the month.

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triEUI SPEclAL PRE ( M SYSTEM Page 1 of 2 ON CORRECTIVE ACTION TAKEN TO PROVIDE OR MALFUNCTION SAFE TAKEN TO PREVENT FOR REACTOR SAFETY COMPONENT CAUSE RESULT OPERATION REPETITION DURING REPAIR Steam Generator Transmitter Loss of NONE Replaced Transmitter

3 Steam Generator

3 vide range level failure.(reason indication on placed in manual channel unknown at this main control control.

time) board and 69%

high level over-ride.

River Effluent Failed detector Unreliable NONE Replaced Detector No Discharges were Monitor RMS R-18 caused by open Indication permitt ed'.

resistor in photomultiplier tube base. The reason for open resistor cannot

.be determined.

Turbine Overspeed Mercoid lost Turbine trips NONE Replaced Mercoid NONE Protection (OPC) snap-action when reducing Mercoid effect causing electrical power unreliable below 20%.

reset action.

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EttECT Page 2 of 2 STFLEI/A tytgcatalION4 SYSTEM ON CORRECTIVE ACTION TNGN TO PROVIDZ OR MALFUNCTION SAFE TAKEN TO PREVENT FCR REACTOR SATETf COMPONENT CAUSE RESULT OPERATIOil REPETITION DURING REPAIR RHR Valve Higher than High leakage thru NONE Capped valve stem leak off Reactor Shutdown MOV 80f4 normal Primary valve stem leak and added 3 rings of water leak rate.

off system.

packing to stuffing box.

This was normal packing wear due to age.

Emergency Diesel Unit would not Diesel NONE Replaced failed component Redundant diesel EG-2A electrically inoperative in governor control circuit (EG-2B) Tested phase on line and realigned governor.

Operable during surveillance test due to Governor control box

' failure.

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e CONNECTICUT YANKEE prarTnn rnni AMT NATA MONTH: AUGUST 1981 REACTOR COOLANT ANALYSIS MINIMUM AVERAGE-MAXIMUM 6 36E+b0 h 6.b6b+bb.

PH025bEGREESC 5.62E+00 :

CONDUCTIVITY (UNHOS/CM) 1.40E+00 :

3.18E+00 5.00Ef00 :

PHI nRTnrA (PPM)

? /4.onr-69 ? /A Oor-09 ? (4.OOF-09 ?

DISSOLVED OXYGEN (PPB)

<5 00E+00 : <5.00E+00 : <5.00E+00 :

BORON (PPM) 3.40E+01 1.24E+02 :

5 42E+02 :

LTTMTUM (ppMs

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/_nnr-n1 ?

A.nor-n1 ?

A.oOF-01 i t

UOTAL GAMMA ACT. (UC/ML) 6.52E-01 :

2.99E+00,1 4.01E+00 :

10 DINE-131 ACT. (UC/ML) 8.83E-03 :

1.69E-02 :

2.40E-02 :

T-171 / T-177 RATTn

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M.4Ar-01

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7.M7F-01 !

9.OOF-01 !

CRUD (MG/ LITER)

<1.00E-02 : <1.00'E-02 : <1.00E-02 :

TRITIUM (UC/ML) 2.74E-01 :

5.81E-01 8.49E-01 :

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HYDRnGEN (CC/kni AERATED LIQUID WASTE PROCESSED (GALLONS):

2.27E+05 uanTr iTngin pnerregEn THROOnH nno0s nrrnurnvenaisnncit 1.7mr4ng AVERAGE PRIMARY LEAN RATE (GALLONS PER MINUTE):

1.18E+00 AVG. PRIMARY TO SECONDARY LEAK RATE (GALLONS PER MINUTE):

5.55E-03 o

AVERAGE DAILt UNIT POWER I.EVEL DOCKET NO.

50-213 Conn, Yankee UNIT Haddam Neck DATE Aug 14. 1981 ss COMPLETED BY Reactor Engineering TELEPHONE (203) 267-2556 MONTH:

August 1981 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 546 17 550 2

546 7.8 552 3

544 19 555 4

542 20 554 5

545 21 555 6

545 22 557 7

544 23 492 8

544 24 9

547 25 36 10 545 26 404 555 11 545 27 556 12 546 28 4

555 13 545 29 555 14 546 30 546 554 15 31 547 16 INSTRUCTIONS On this format, list the average daily unit power levc.1 in MWe-Net for each day in the reporting month.

Couplete the nearest whole megawatt.

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j' DOCKET NC5 50-213 UNITSilUll:0WNS AND POWER REDUCTIONS UNIT NAME ct. i Yankee Atomic DATE

'9-14-81 GMED W D.

Anh m n REPORT MONTil Au cu s t 1981 TELI.I'llONE 203-267-2 g,

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ZZZZZZ Shutdownreactortorepairvb1ve

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~ packing leals. Normal plant 810825 u'nloading for Reactor and Turbfne

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shutdown..

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4 I:nhibit G. Insitutii.ms l' 1. aJ lteaum:

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. A 1:iluigmient Ibiluiellaplain)

1. Manual f.. Psepasais..... Daia li Maintenance in Test 24Iannat Sesani.

liite) Sliccisfin Istcaisse C Itelueling

..l.Autumatic Scraus.

1.e.. Rep.us 11.1 RIl' ele INtiltl.G- -

Ilitegulat ny Heisticli.m 44Hisce (l'aplaise) 01111 I 4)pcialin l's.inimg A Iicenic l mandesseluse 4:.tinanistiaisve l

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- - - - NRC CPERATING STATUS REPORT CCtFLETED BT REACTOR ENG:NEERING*****

I UNIT t;AME....CCNN. TAWEE ATOMIC POWER CO.

[CCEET M. 50 2'3 i 1.

2.

FEPOPi!N3 FEP!0D...., August 1981 DATE 9-14-81 LICENSED THERMAL POWER'.N T3... 1825 CCMRIIID BT... D. /mderson Reactor Eng.

!_1.

5.

DESIGN ELECTRICAL RATING (NET TNT)... 580 TELEPHONE (203) 267-L*56 4.

NAMEPLATE PATING' GROSS MWEl... 600.3 6.

MAXIMUM DEFENDAELE CAPACITT(GROSS FS'E)... 582 MAXIMJM DEPENDACLE CAPACITY (NET MWEl... 555

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8.

IF CHANCES OCLUR IN CAPACITT RATING 3(ITEMS 3 TW OUGH 7)SINCE LAST REPORT:_ GIVE REASON 3.... NOME.. _ _

9.

POWER LEVEL TO WHICH RESTRICTED, IF ANT (NET MWEl.... NOME

10. REASON FOR RESTRICTION.

IF ANT... M/A p-l THIS REPORTING PERIOD TR. TO DATE CUMULATIVE TO DATE L_

11.

HOURS IN REFORTING PERIOD 744.0 5831.0 119307.0 *

{12.

NUMBER OF HOURS THE' REACTOR WA3 CRITICAL 712.7 5756.8 103729.5

b13.

REACTOR RESERVE SHUTDOWN HOURS 0.0 9.1 1192.5

14.

HOURS GENERATOR ON LINE 697.0 5728.4

?9249.4 *

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UNIT RESERVE SHUTDOWN HOUR 3 0.0 0.0 373.7

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GROSS THERMAL ENERCT GENERATED (MWH1

__ 1245695.

10242683.

171794 Y,6.

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GROSS ELECTRICAL ENERCT GENERATED OMil 392751.

3335302.

56438500.

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NET ELECTRICAL ENERGY CENERATED (MWHI

~~~ 373239. ~ ' ~ ~ ~ - ~ " ~ ~ 3iB0410. ~ ~ ~ ' ~

53698018.

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UNIT SERVICE FACTOR 93.7 98.2 62.8 +

20.

UNIT AVAILABILITT FACTOR 93.7 98.2 83.2

21.

UNIT CAPACITY FACTOR (USING MDC NET) 90.4 98.3 62.7

_22. __ UNIT CAFACITT FACTOR (USING DER NET) 86.5 94.0

'76.5

4 23.

UNIT FORCED OUTAGE RATE 6.3 1.7 6.6 *

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-.. SH'JTDOWN3 SCHEDULED OVER NEIT 6 MONT'43(TTPEeDATE AND DURATION OF EACH)_.......

26,1961.For Six lieeks..,

.... Refueling For Core II. Approximately September

25. ~ IFSHUTDOWNATENDOFREPORTINGPERIODeESTIMATEDDATEOFSTARTUP,,,]3p

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26.,,. UNITS IN TEST STATU3(PRIOR TO COMMERCIAL OPERATION)....NOT APPLICABLE._.._ _ _ _..

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SINCE DATE OF COMMERCIAL OPERATION 1-1-68 o

REFUELING INFORMATION REQUEST

/

1.

Name of facility Connecticut Yankee' Atomic Power Company 2.

Scheduled date for next refueling shutdown.

September / October 1981 3

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

h.

(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?

N/s (c)

.! answer is no, has the reload fuel design and core configuartion been reviewed by your Plant Safety Review Committee 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 from the fuel vendor they will be reviewed in accordance with 10 CFR 50.59 to determine if any unreviewed safety questions are associated with the Core reload.

(d) If no such review has t:: ken place, when is it scheduled?

N/A Scheduled date(s) for submittin, proposed licensing action and supporting 5

e information.

There are no scheduled dated because of (h) 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 fuel design, new operating procedures.

None 7

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

(m) 157 (b) 389 8.- The present licensed spent fuel pool storage capacity and the size of any increase in licensed st.orage 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 :;he spent fuel pool, assuming the present licensed capacity.

1994 to 1995

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ML20042B340

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