ML19296B338

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Monthly Operating Rept for Jan 1980
ML19296B338
Person / Time
Site: Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 02/06/1980
From:
CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML19296B336 List:
References
NUDOCS 8002200431
Download: ML19296B338 (8)
v • d • e


Text

.

CONNECTICUT YANKEE ATOMIC POWER COMPANY IIADDAM NECl; PLANT IIADDSI, CONNF.CTICUT 4

MONT11LY OPERATING REPORT NO. 80-1 FOR TIIE MONTil 0F JANUARY, 1980 8002200 I

\\

PLAMT OPERATIONS The following in a chronological description of plant operations for the month of January, 1980.

At the beginning of this report period the plant was at 607 inte, 100% power.

Da 3/3/80 the titars for the "B"

train of core cooling equi p: rent mtfunctioned and were r epaired t he ca.ne day.

On 1/20/80 the 3oad var reduced to 400 E'c to do a turbine stop trip valve test.

The plant was returned to 606 !Ge, 100%

power the same day.

On 1/23/80 the "A" auxiliary feed pump was removed from service to repair the oteam control valve.

It was returned to nervice on 1/24/80.

On 1/28/80 the fire protection pressure maintenance pump was removed from service for repair.

All periodic teste, were completed as scheduled.

On 1/14/80 and 1/30/80 14B-4T-2 345 KV output trancmission bhr. opened.

e

EFFECT l

SPECIAL PRECAUTIONS SYSTEM ON CORRECTIVE ACTIO.N l

TAKEN TO PR0"IDE OR MALFUNCTION SAFE TA E TO PREVENT i

FOR REACTOR SAFETY '

COMPONENT CAUSE RESULT i OPERATION I

R" PETITION DURINo, REPAIR 1

"A" Aux. Feed Pun AOV Errosien Leaks by None Replaced internals of 13 available J.O.

'10899 valves I

f EG2A Diesel sequenc-Faulty Timers operated Mone Replaced tiners

' Tested redundant equipment, ing Timers 62-5 and manufacturing to fast j eroved available 62-10 process 63XLC100A Relay in Wear Arcing contacts None Replaced relay Nonc required Chemical and Volume causing spike Control System on other (FCVll2C bypass) circ:its Pressurizer Spray Not known No flou None Valve isolated-will be

'.:one--valve will. be VV 574 repaired during outage repaired during outage f!3 steam line break Indicating Did not fellow None Replaced motor Inserted trip signal indicator balancing motor load change stuck "A" Auxiliary SG Worn internal Aux. SG FP None Maintenance replaced Redundant Aux. Feed Terry FP steam valve parts spray supply internals Turbine available valve leaked through Containment Sump.

Faulty capacitor Constant to None Replaced capacitor None Alarm L-lS03L in alarm unit level alarm

_ _. _ ~ _.

L O N N E C T I CI.l T YANKEE

.. _. _.. _.. _._. _ _ _.. _. ____ ! l" AC 10R J.00LJ,N L U A I A.

t Di FI H : JnNiiARY 1000 Ril ACTOR COUIANT ANALYSIS MIlullLIM AVERAGE MAXIMUM

-...,.........-,...-,.....,,v.,-c,r,....,...-,,cv..e..-r,.,...,-,.ve,-,ve,-r.-,-,.,,.

Pil G

$ DEG!&ES C 6.4.1E400 :

6.60E+00 :

6.00E+00 :

Cnid DilC T ] V T 1 Y (UHHOS/CM) 1.60EF01 :

1.80E+01 :

1.95E+01 Gi H.1 H d DrG 4.PPi1 L -__

044,0 0D - 02

_._M.O OE 4/ 2 a _l)3! 202 '

D i!.',U L'K D O X YOEN ( l'P B )

P5.00EiOO ! CU.00F+00 : C5.00E+00 :

UOQnN (PPM) 2.10E+0? :

2.59E+02 :

2.90E+02 :

_ _ _L.I T l i 1 U; i-. ( P F M ) - _ --.-..

1_ 1.OOE100.'-_1+33E!00 1-.50E.i 0()

  • Torn! GAhMA ACT. (UC/ML) 6.00E+00 :

7.84EFOO 9.14Ef00 :

IUDINE-13] ACT. (UC/ML) 4.42E -02 S.00E-02 :

5.87E-02 :

__4.=4,.;, /.1.=Lu _ in:,_T n)

-.7_ 14 E..O L '

a,1.4 E = 0 '

t 02E400.'

CR(ID (MU/lIIER) 2.00E-0M :

3.60i' 02 5.00E-02 TRITrUN C UC/tiL )

3.29E+00 :

3 74E+00 :

4.25E+00 :

__ HYDROGEN (CC/NG)._

_,1. 82E5 01 :. __2. 3 0 E+ 01_.1___2.93Ed o 1 AERATED LlGUID UASTE PROCESSED (GALLONS):

1.76E+05

._.- 1dAGTE_1_IQUID_ PROCESSED Jf1IROUCH_.DURON.EECOVERY1 GALLONS L _ __L36E+04 AVERAGE PRIt1ARY LEAK RATE (GALLONS PER MINUTE):

5.50E-02 PRIMARY 10 SECONDARY LEAK RATE (GALLONS PER MINUTE):

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AVE 1EE DAILY UNIT POWER LEVEL DOCKET NO.

50-213 Conn. Yankee U!11T Iladdaa 'ie c k DATE 6,

1980 COMP LET F.D BY 't e a c t o r

.n g ' r e ? r i n e, TEL!:PHO' E_(203) 267-2556 gg;;73;.

January 19EO DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL

(!L'e-Ne t )

(MWe-Net) 1 580 17 578 2

580 18 578 3

579 19 578 4

579 20 567 5

580 21 578 6

579 22 578 579 7

23 578 8

579 24 578 9

578 25 577 10 578 26 578 11 578 27 579 12 579 28 579 13 578 29

_578 14 579 30 579 15 580 31 579 16 580 I!1STRUCTIONS On this fo rma t, list the average daily unit power level in MWe-Met for each day in the reporting nonth.

Co:nple te the nearest whole :negawatt.

(9/77)

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          • NRC OPERATING STATUS REPORT CC:F ETD SY RE/ COR EN3!NEERING*****

m 4

- - 1.

U;.!T fate....CmN. Y/J.KEE AIDt!C FUWER CO.

r?CHET !D.

50-213 7 -' 2.

RErbtTii6 fed!OD.. Jnum lHO Di.i E Jan. 6, 1980 3.-- Lt CD.s EJ TnDGL FU.ER( 1l'... 132 5

- ~ ~ ~ - - - -

- C "LETED 3Y hacter En:ineering 4

ts/v.E F LATE etATI N 3 (C n 3 GE )... 00 ). 3

, ; J.a ciE (2:3) 257-2550 5.

GESIO ELECirtiCAL RATI J(NET ;L;)... 575 G r-Wal!'ut OEPO ?AOLE CAPACt TY(GISS #4;E)... 577 7.

!w. V LEFE;.XLE CVAJITYO tT 1%E)... 550 E.

IF Cm%E> OCCU4 IN CAPACIT( RAT!;40S(ITCt3 3 TIG3 UGH 7)SINCE LAST REPC;T, GIVE EEASCNG....nene S.

Fw ER LEVEL ID Lh!Oi RECTRICT D.

IF ALYCiET 15lE)....None

10. REASON FCa RESTRICTION.

IF AfiY....Not Applicable

--- -- THIS REP 0GT!!G PERIOD -

YR. TO DATE~

~ ~ C '7 ATIVE TO DATE

~

-'~i 11.-iCVHS IN REfCRTit:3 FERioD

~ - - - - -

7W.0

~7W.3

-~ ~ 1339? 3. 0

  • 1 12.

TMER OF IUJRS THE REACTOR liAS Ch!TICAL 73.0 7:.4. 0 51 % 0.7

  • 13.

etEACTOR RESERVE SirJTDC N l0GR3 0.0 0.0 1152.6

  • 14 NL5th GEt.ERATU3 CN Lit.E 7W.0 744.0

-- S753:. 2

  • 15.

UNI T RESERVE 5HUTUO41 10U3S 0.0 0.0 333.9 15.

GNSS TIGGL DiERGY GEtiERATED 04Ji) 135G093.

1355093.

1 1v. 7a 7.

17.

CNu ELECTitlCAL DiERGY GE;.ERATED (f t.it) 450221; 45C221.

G 3ME7 -

Is.

1.ET ELECTRICA1. EhERGY GDEATED 0434) 4299S4 42 SOS 4 2730:.7 7.

13.

UNIT SERVICE FACTod 103.0 103.0 S 2. 8

  • 3 20.

UNIT AVAlU.BlLITY FACTOR

- 100.0 100.0 33.1

  • 21.

UNIT CAPACITY FACTOR COSitiG IOC fiET) 105.1 105.1 E2.3

  • 22.

UNIT CAPACITY FACTOR (Usitr5 DER fiET) 100.5 103.5 77.0 e D

23.

UNIT FORCED OUTAGE RATE 0.0 - - -

0.0 7.2

  • g]

2:e.

SlOTDOWNS SOiEDJALED OVER tiEXT 610tiTHS(TYPE,DATE AND DURAT10?10F EAC1).... Refueling, May 19S0, approxinately S to 12 vecks M-- -

25.

I. SHUTUGi:1 AT Er.D OF REPORTING PERIOD, EST! MATED DATE OF ST/RTUP....Not applicable J

g;---,'

26.

Uti!TS 1:4 TEST STATUS (Pd10R TO C0 rIRCI AL OPERATIC:1)....NOT APPLICA0LE g

c]==g-

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  • SitiCE DATE CF CCHERCI AL CPERATION 1-1-68

{F==

l'EFUE!,1 MC It;FOMATION REOUEST 1.

Name of facility Connecticut Yankee Atomic pover Coripany 2.

Scheduled date for next refueling shutdown.

AprIt, 1980 3.

SchcJuled Gate f m: restat* f ollouj ng ref aclin;.

Ap,, r m: at ely ei; ht t o 1.9.:e t ', frem Mcu f cmn t! n t e.

4.

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

No t.echnical specification changes are anticipated at this date.

(b)

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

N/A (c)

If answer An no, has tha reload fuel design and core configuration been reviewed by your I'lant Safety Revicu Comitt ee to detet:mine whether any in.Tevicued r,af et.y questions are associated with the

'.ef. 10 CFR Section 50.59)? When the above utated core reload docur:ents are received i rom the fuci vendor they uill 'ae review'er) in accordanc.: tiit.1 10CER50.59 to determine if nny unreviewed ;afety questions are associated with the (d)

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

core relo.

N/t.

5.

Schedulnd date(s) for submitting proposed licensing action and supporting information.

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

6.

Important licensing consi.derations associated with refueling, e.g.,

new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operacing precedures.

None 7.

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

e (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 assemblies.

1168 9.

The projected date of the last refueling that can be discl.arged to the spent fuel pool assuming the present licensed capacity.

1994 to 1995

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