ML19323A471

Monthly Operating Rept for Mar 1980

ML19323A471
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	04/10/1980
From:	CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML19323A468	List: ML19323A467 ML19323A471
References
NUDOCS 8004210253
Download: ML19323A471 (8)

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CONNECTICUT YANKEE ATOMIC POWER COMPANY llADDAM NECK PLANT llADDAM, CONNECTICUT MONTilLY OPERATING REPORT No. 80-3 FOR Tile MONTil 0F MARC 11, 1980 8004210 2

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PLANT OPERATIONS The following is a chronological description of plant operations for the month of March 1980.

At the beginning of this report period the plant was at 100% full power 603 MWe.

On 3/6/80 @ 0930, the #2 CAR Fan recire damper was found partially disconnected and the fan was declared out of service until 3/7/80 at 1245 when the damper linkage was repaired and the fan was returned to service.

A reactor and turbine trip on 3/27/80 at 1422 was experienced during wiring modifications per NUREG 0578 under job order #M01025.

The reactor was taken critical on 3/28/80 at 0144 and full load was achieved on 3/29/80 at 0745.

Problems were experienced with the NRC dedicated telephone line on the following dated; 3/7/83, 3/11/80 and 3/21/80.

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

1. 2 FW Valve Positioner Worn Pilot Excessive Air None

-Replaced worn pilot valve Clamped main FW Valve and Valve Use/ Erratic used bypass for FW Control control

1. 1 Stcam Line Break Worn Slidewire Failure of None Replaced worn slidewire Inserted trip signal Indicr. tor indicator to follow load

1. 2 Ccr Fan Broken Coupling Dampers failed None Replaced coupling with None to operate steel coupling Air Ejector RMS Dirty Contacts Failed output None Clean connectors None Required "B" Boric Acid Pump Loose bolts Leak None Tighten bolts None Required N

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CONNECTICUT YANKEE utric i un Laut.m i ute i e4 MONTH: MARCH 1980 REACTER '100LANT ANALYSIS MINIMUM AVERAGE MAXIMUM PH & 25 DEGREES C 6.74E+00 :

6.87E+00 :

6.99E+00 :

CONDUCTIVITY (UMHOS/CM) 2.00E+00 :

5.94E+00 :

7.10E+00 LHLOi(1sta (PPii)

Ot.OOt-v2 9.vvE-OJ s4.OOE-02 DISSOLVED OXYGEN (PPB)

<5.00E+00 : <5.00E+00 : <5.00E+00 :

DORON (PPM) 4.30E+01 :

8.62E+01 :

1.29E+02 :

t i i r u. u. 6 s t i vi s s. u v c. - v i..

o.uu -v1 u.vut-vA.

TOTAL GAMMA ACT. (UC/ML) 3.97E+00 :

7.63E+00 :

8.79E+00 :

IODIAE-131 ACT. (UC/ML) 3.75E-02 :

5.63E-02 :

1.78E-01 :

1-131/I-ib3 niiTIU o.90E-Oi d.30E-01 v. 2 0 E -- 01 ;

CRUD (MG/ LITER) 4.00E-02 5.75E-02 :

9.00E-02 :

TRITIUM (UC/ML) 1.11E+00 :

1.59E+00 :

1.80E+00 :

iiY DROUdis s us,<,,U )

. < 7.c_ + v i o.s1a1Ji

'i. i v o.1 v i AERATED LIQUID WASTE PROCESSED (GALLONS):

1.90E+05 wn,i u ua.J 4 -E a c-v o.

i.. i.. v u e,4 u visa.4 n u u s i._ n - -

A.aiurus AVERAGE PRIMARY LEAK RATE (GALLONS PER MINUTE):

1.10E-01 PRIMARY TO SECONDARY LEAK RATE (GALLONS PER MINUTE):

0.00E+00

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• oox'lRC OPERATING STATUS REPORT COMPLETED BY REACTOR EtGlilEERINGr***

.. I 1.

uJ f4A4E....CUNN. YAto;EE ATOMIC FWER CO.

p DOCKET NO.

50-213

-d a v 2.

HEPodTl!G PERIOg.... March 1980 DATE April 10. 1980 i

3. - ' LICENSEu THERMAL PudERDUT)...1825

-~-----

COMPLETED BY Reactor Engineering 4.

NAEPLATE dATileG(GUSS e '.. 600.3 TELEPtU:4E (203).267-2556 5.

vESIGil ELECrdlCAL dATilGC4EI 4.E)... 575 b.-

sLAAIN4 UEFEICABLE CAPACITV(LIOSS 3.E)...

577-

--]

7.

dA41N4 OEPEf;UAOLE CAPACITYC4ET IL.E)... 550 l

8.

IF CHNJLES UCCG( lti CAPACITY KATI:4GS(ITE!G 3 TIIROUG'_l 7)SINCE LAST REPORT, GIVE REASONS...None 9.

1%Ed LEVEL Tu t<Hicit RESTdlCTED.

IF ANY('lET f f.lE)....None

10. d[AW!i EUR 1 ESTRICTlUN.

IF ANY....Not Applicable l

~-

THl S REP 0'ITItG PERIOD -~ - --- -

YR. TO DATE -

-- - - ' CUNULATIVE TO DATE

- - ~ ^ -

11.-- tiuudS I N REPORTIfu PERIOD -- ---- - - ---- 7%.0 ' -

2184.0 -

- - 107376. 0 * ---

iit.

14 UMBER OF IUdtS THE REACTOR tJAS CRITICAL 732.6 2172.6 93369.3

• 13.

REACT 0d RESEHVE SIUTUGJf4 IUURS 11.4 11.4 1164.0

• lie,

itNaa LENEdaTOR ui Life 730.3 2170.3-

- 39110.5 *-

i l

1).

uit I dEaEdVE SHuTuulN IUURS 0.0 0.0 359.9 j

lu.

litubb TIOc4AL EHEdGY GElERATED C441) 130193G.

3858373.

154000122.

17.-- Oh ELECTRICAL ENERGY GENERATED (t4.11) 431516.

1278347.

50633413. --

lo.

IlET ELECTalCAL ENERGY GE!ERATED (1441)

411806, 1220391.

43175154.

13.

UNIT SERVICE FACTOR 98.2 93.4 83.0

• 20.

C'ili AVAILABILITY FACTOR '

'98.2 93.4 83.3

• 7

>~.

]'l 21.

ullT CAPACITY FACTOR (USlfU MDC NET) 100.6 101.6 83.0

• 22.

'dI;lT. CAPACITY F CTOR (USING DER f4ET) 96.3 97.2 77.2

• y 23.

UNIT FudCED OUTAGE RATE - ---

1.8 0.6

-7.1*-

]Q 24.

SIUTUGils SCHEDUALED UVER tlEXT 6 M0lTHS(TYPE,DATE AND DURATION OF EA01).... Refueling. May 1980 Approximately 8 to 12 weeks l

25.

IF SHUTDati AT END OF REPORTifG FERIOD, ESTIMATED DATE OF STARTUP....Not applicable 26.

delTS Ild TEST STATUS (PRIOR T0 C0f4ERCI AL OPERATION)....NOT APPLICA3LE

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• alliCE DATE OF OMERCI AL OPEHATION 1-1-68 i

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s...

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-213 Conn. Yankee UNIT lladdam Neck DATE April 10, 1980 COMPLETED BY Reactor Engineering TELEPHONE (203) 267-2556 rch 1980 MONT11:

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

(MWe-Net)

,1 577 17 579 2

577 18 579 3

577 19 577 4

578 20 579 3

579 21 580 6

578 22 579 7

579 23 580 8.

580 24 580 9

579 25 579 10 578 26 578 11 578 27' 346 12 577 28 152 13 577 29 5,11 14 579 30 577 15 578 31 578 16 578 INSTRUCTIONS On this format, list the average daily unit power 1rvel in MWe-Net for each day in the reporting month.

Complete the nearest whole megawatt.

(9/77)

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50-213 UNITSI:UTI:0WNS AND PCWER REDUCTIONS

• DOCKET NO.

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UNIT NA..f E Conn. Yankee DATE April 10, 1980 l(EPORT MONTil March 1980 COMPLETED isY 2rictor Encineering 1 E LI.I'll0N'.

(203) 267-255rz 3 o,3 3

e s4 1.iccinee h.

8.s

.2,e s

cause a r.iiic6nve c

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Eveni av L

Na.

Dete c.

3?

4 3

Asiion i.,

.a 52 ji;8 c Repunt8r 8:*0 8O Prevent l{ccutteni;4 u

c5 l

l 12 800327 F

13.7 H

3 ZZ ZZZZZZ Reactor.and. Turbine trip due to to high containment pressure /cor'e 800328 cooling actuation signal.

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4-l' l'uscrJ Heason:

Metlind:

Ex!nhis G. Instiussions 5 5.lieduled A l:.piipinent l'aifuie(lap ain) 1 Manual for Piepaiain.n ni l>as.i l

II.Maiiitensiice ivi Test 2.Maiiisal Serani.

1.nti> sr.eens I., I isciisse

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(*.lteliteling,

1. Autinnatie Strain.

lsent1(ep.n Il.1 HilileI;;;IP.:.".

l} ltegulatiny itestiietion l Oilici (I!xplain) oli.I 1 (Ipes.sini l'i.sinnig & Iivenise l aatniisalltsft I Linunisti.iii.e G t l vialinnaI I i:ui il'apl.iiii) lsinto I. M nie.*,.nn.c i

08/11) ll Othen il splanil

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REFUELING INF01DfATION REQUEST 1.

NL:e of facility Connecticut Yankee Atomic Power Company 2.

Scheduled date for next refueling shutdown.

May 1980 3.

Scheduled date for restart following refueling Approximately cight to 12 weeks from shutdown date.

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 date.

(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 confi,uration been t

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 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/A 5.

Scheduled date(s) for suomitting 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 dif ferent fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures.

None 7.

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

(a) 157 (b) 340 8.

The present licensed spent funi 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.

The projectcd date of the last refueling that can be discharged to the spent fuel pool assuming the present liccused capacity.

1994 to 1995 4

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