Text

Monthly Operating Rept for Sept 1978
	ML20027A157
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	10/13/1978
From:	; CONNECTICUT YANKEE ATOMIC POWER CO.
To:	;
Shared Package
ML20027A156	List: ML20027A155; ML20027A157;
References
	NUDOCS 7810180136
	Download: ML20027A157 (9)
	v • d • e

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CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT HADDAM, CONNECTICUT e

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MONTHLY OPERATING REPORT NO. 78-9 FOR THE MONTH OF-SEPTEMBER, 1978 7Tfott ot34 g

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PLANT OPERATIONS The f'ollowing is a chronological descrip' tion of plant ~

operations for the month of September, 1978.

9/1/78 1A Boric. Acid pump out of service (0500-1400 hours) to replace the pump discharge flange gasket.

9/2/78 Furmanite was injected into the packing gland of #4 main steam line trip valve to stop a packing leak.

The valve was successfully tested after the i

injection.

9/6/78 "B" Ser.vice Water Pump was removed from service to refurbish the impellors.

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9/9/78 Load was reduced 10 MWe due to a failure of i

2 steam line break signal.

At 1534 hours0.0178 days 0.426 hours 0.00254 weeks 5.83687e-4 months a l

4-jumper was installed to provide a trip signal and load was increased to full power.

Replaced blown fuse in #2 steam line break circuitry at 1626 hours0.0188 days 0.452 hours 0.00269 weeks 6.18693e-4 months and removed the jumper.

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9/11/78 "B" battery charger was taken out of service on 9/11/78 (0838-1300 hours) due to D.C. ground.

9/13/78 MWe load was reduced at 2346 hours0.0272 days 0.652 hours 0.00388 weeks 8.92653e-4 months due to high bearing temperature on "B" steam generator feed pump motor.

i 9/14/78 MWe load was reduced to 50% of full power (300 MWe)

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and "B" steam generator feed pump was shutdown at 0115 hours0.00133 days 0.0319 hours 1.901455e-4 weeks 4.37575e-5 months .

I "B" steam generator feed pump was taken out of s

service at 0115 hours0.00133 days 0.0319 hours 1.901455e-4 weeks 4.37575e-5 months to 902 hours0.0104 days 0.251 hours 0.00149 weeks 3.43211e-4 months on 9/15/78 for r

replacement of the inboard motor bearing.

1 9/15/78 MWe load was at 50% full power until 0940 hours0.0109 days 0.261 hours 0.00155 weeks 3.5767e-4 months ,

. i at which time load was increased to full power.

9/25/78 Pressurizer spray valve #574 was found inoperative at 0032 hours3.703704e-4 days 0.00889 hours 5.291005e-5 weeks 1.2176e-5 months due to a broken valve stem.

Operated 1B reheater drain tank control on high 9/27/78 level dump.(1000-1100 hours) while the normal level controller was repaired.

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Pl. ANT OPERATIONS (CONTINUED) l i

9/28/78 Pressurizer spray valve #574 was repaired (replaced valve stem and plug) and returned to service at 1355 hours0.0157 days 0.376 hours 0.00224 weeks 5.155775e-4 months .

The diesel room and cable spreading area fire detection system was found out of service at 1140 hrs.

The diesel room and cable spreading area detection system relay was replaced with the relay from the switchgear room fire detection system, at 1520 hours0.0176 days 0.422 hours 0.00251 weeks 5.7836e-4 months . The switchgear room was inspected hourly.

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.ON CORF"-TIVE ACTION TAKES TO PROVIDE

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MALFUFCTION SAFE TAKE.. TO PREVE!Tr FOR REACTOR SAFETY SYSTE:4 COMPCNENT CAUSE f

RESULT OPERATION REPETITION DURISC REPAIR OR

?roccurizer Spray Broken Valve Valve would None Replaced valve stem and plug Valve #573 was available 121ve #574 Stem not moye open or close Preccurizer Level Noncondensable Pressurizer None Vented reference leg at condenser None Chr_nnal #3 gases entered level readings pot tbc pressurizer were high by reference leg

~ 4%.

None

4 Stccm Generator

4 steam Pressure signal None Replaced fuse Ptys:ure Channel generator failed low pressure power supply fuse

2 High Steam flow Fuse failure Flow signal, None Replaced fuse Jumpered to establish failure 1 out of 4 trip signal failed low indicstor __

on #2 steam flow LER #78-19/3L indicator (trip logic is 2 out of 4)

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CHCtISTRY DATA FOR MO:iTJI 0F September, 1978 Benetor Coolant Analysis Minimum Averace Maxinu.m Ph @ 250Cf 2.0E-01) 6.00 E+00 6.78 E+00 7.00 E+00 Conductivity, unhos/en( 25) 9.00 E+00 1.398 E+01 2.00 E+01 Chlorides, rpn(!7.CE-02)

< 3.00 5-02

< 3.00 E-02

< 3.00 E-02 Dinsolved Oxyren, tmb ( 5 0E+00) 0.00 E+00 0.00 E+00 0.00 E+OO r.

Boron, ppr. ( 25) 3.40 E+02 3.91 E+02 5.17 E+02 Lithium, rpm ( t 5'- )

5.00 E-01 1.21 E+00 1.50 E+00 Gross Derassed Act..uci/n1( 2,0E-02)

1. 60 E+00 2.36 E+00 4.31 E+00 Todine-131, u ci /n1( 35) 1.23 E-01 2.04 E-01 1.00 E+00 I-131/I-133 Ratio 2.09 EM)0 3.23 E+00 7.08 E+00 Crud, r1r-/1 (!1. 0E-02 )

1.00 E-01 4.00 E-01 1.00 E+00 Tritii:m, uCi /n1( 5.0E-02) 3.03 E+00 3.32 E+00 3.88'E+00 Ilydroren, cc /kr( t2. 0E+00 )

2.75 E+01 3.31 E+01 3.89 E+01

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Aerated liquid vaste processed:

2.16 E+05 gallons

.f Waste liquid processed through Boron Recovery System: 1.25 E+05 gallons Average pri=ary plant leak rate:

.0'647 spm Primary to secondary leak rate:

0.00-E+00 gpm b,

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C~~ RATING DATA REPORT Z

DOCKET NO.

50-213 DATE Oct. 13, 1978 C. Kokoszka C05tPLETED 11Y TELEPHONE (203) z67-2556 OPERATING ST ATUS Notes Conn. Yankee Atomic Power Co.

1. Unit Name:

September, 1978

2. Reporting Penod 1825

3. Licenwd Thermal Power 15this:

600.3

4. Nameplate Ratin;iGrow StWe,.

575

5. Desi;n Electrical Rating iNet 5thet:

577

6. 31stimum Dependable Capacity iGross StWei.

550

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7. Staximum Dependable Capacity sNet Sthet:

8. If Chan;es Occur in C,spacity Ratings iltems Number 3 Through 71 Since Last Report.Gise Reasons:

9. Power Leiel To Which Restricted.!f AnyINet StWes:

10. Reasons For Restnctions. If Any:

This 51onth Yr to.Date Cumuistive 720.0 6551.0 94,223.0

11. Hours In Reporting Period 720.0 6410.7 81,448.0

12. Number Of Houn Reactor was Cntics!

0.0 140.4 898.1

13. Resetor Resene Shutdow.n Hours 720.0 6259.4 77,306.8

14. Hours Generator On. Lee 0.0 136.4 136.4

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15. Unit Resene Shutdown Hours

16. Grou Thermal Ener;> Gercrated 451%He 1,283.751 11,109,940 132,932,499

17. Gross Electriest Energy Generated ISIWH1 414,830 _,

3,617,893 43,712,192 395,412 3,449,264 41,576,726

18. Net E!cetries! Energ> Generated i..thHs 100.0 95.5 82.0

19. Unit Senice Fsetor 100.0 97.6 82.2

20. Unit Assilability Factor 99.9 95.7 81.8

21. Unit Capacity Factor iUsing SIDC Neti 95.5 91.6 75.8

22. Unit Capacity Factor sUsmg DER Neti 0.0 2.1 8.J

23. Unit Forced Outage Rate

24. Shutdowns Scheduled Oser Nest 6 \\tonths iT>pe.Date.snd Durstmn of Eschi:

Core'9 Refueling, tentatively as early as January 15, 1979, approxituately six (6) weeks duration.

25. If Shut Down At End Of Report Period. Estimated Date of Sisttup: _

26. Units in Test Status Prior to Commercial Operstions:

Forecsst Achiesed INITI AL CRITICALITY INITl4 L ELECTRICITY CO\\t\\tERCI 4L OPER 4 TION

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AVER ACE D AILY UNIT POhER LEVEL

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50-213 DOCKET NO.

conn. tausee Haddam Neck UN 7 DATE 10/13/78 D. Anderson C051PLETED BY (203) 267-2556 1

TELEPHONE h

September, 1978

.slONTH DAY AVER ACE D ALLY P0hER LEVEL DAY AVERAGE D AILY POhER LEVEL 33nve.Nei,

8. ihe Net)

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569 564 17 I

568 562 33 2

570 561 39

,3 572 561

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570 560 5

568 560 6

571 559 33 7

564 571 7

g 24 571 563

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570 561

,6 10 570 564 13

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571 3

566 33

' 12 573 567 13 573 300 34 30 436 15 570 16 INSTRUCTIONS On this format. int the Efrage daib unit :..mer :eselin St%e. Net f.>r each ds) in the rep.,rting :n.. nth.C.nr.pute t..

the nearest uhule.neg3a3lf t

gas *= g 1

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50-213 D?!KET NO.

tlNIT SliU1 DOWNS AN!)PCWER REDUCTIONS -

UNI'I NA'.lE Conn. Yagkee-liiddam Neck }

DALE 10/11/78 COMPLET EI)liY D. Ancterson i

REl'OR I MDN111 Sept. 1978 1EI.I.I'llONE (203) 267-7556

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}O Psevent Recus cine i,

6 No. shutdowns during this month.-

i Power reduction to 300 MWe do to 14 10/14/78 F

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4 Maintenance on "B" Steam Generator to Feed Pump.

10/15/78 I

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I:=Inhis G. Inssenttiinis l' l'n.wJ Reauen.

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1412nnal f.u Psepausi.m ul Data S. 561.edulcJ A l'iluipment I ailuiell.splaia)

II. Maintenance on Test 24fanual Sceam.

1.nie) Slecess fin I nemce

.1 Autinaatie S6 tam.

liscut Re'pini11.1-RIl' ele (NilREC.

C.R.:Incling

l Ollies Ilimplaml Ullill D Rep las,.a> Ressaission I Opeut o luimng A Ii. cow I;maminatiini '

I Alnu m.unive I sintui I Same %=u.c G Opeuu.aul I e no il npl.u.il

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M REFUELING INFORMATION REQUEST 1.

Mame of facility.

Connecticut Yankee Atomic Power Company 2.

Scheduled date for next refueling shutdown.

January, 1979 3.

Scheduled date for restart following refueling.

Approximately six weeks from shutdown dste.

4.

Will refueling or resu=ption of operation thereafter require a technical specification change or other license amendment?

No.

Connecticut Yankee Technical Specif"ications are reload independent If answer is yes, what, in general, will these be?

N/A If answer is no, has the reload

fuel design and core configuration

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been reviewed by your Plant Safety Review Committee to determine x

whether any unreviewed safety questions are associated with the core reload (Ref. 10 CFR Section 50.59)?..

Yes, see answer to 4 above.

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.

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None 7.

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

(a) 157 (b) 288 8.

The prc'sent 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 refuel'ng that can be discharged i

to the spent fuel pool assuming the present licensed capacity.

1994 or 1995 e

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ML20027A157

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