ML20148B204
| ML20148B204 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 01/11/1980 |
| From: | CONNECTICUT YANKEE ATOMIC POWER CO. |
| To: | |
| Shared Package | |
| ML20148B191 | List: |
| References | |
| NUDOCS 8001210163 | |
| Download: ML20148B204 (8) | |
Text
_ _. - _.
CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT HADDAM, CONNECTICUT 1
MONTHLY OPERATING REPORT NO. 79-12 FOR THE MONTH OF DECEMBER, 1979 96024316
)
a 0 0120 0 /lo3 i
n PLANT OPERATIONS The following is a chronological description of plant operations for the month of December, 1979.
At the beginning of this report period the plant was crerating at 100% power, 607 MWe.
On 12/16/79 the load was reduced to 400 MWe to perform a turbine stop trip valve test.
The plant returned to full power the same day and remained at full power throughout the month.
On 12/16/79 while returning to full power by diluting the Reactor Coolant system, the rupture disc on the Degasifier was ruptured due to malfunction of degasifier effluent valve.
Approximately 800 gallons of coolant was pumped to primary vent stack releasing its gas content to the atmosphere. This resulted in a Prompt Report to U.S.N.R.C. and notification to public on the basis of an event of high public interest.
On 12/24/79 EC2A was out of service due to damaged generator neutral cable insulation.
Cabic repaired and EG2A in standby status on same day.
On 12/28/79 the fire system piping was Hydroed after several modifications and tie ins for new systems.
On 12/31/79 lost control air pressure in the containment due to faulty solenoid pilot valve on pressurizer solenoid relief 570. Replaced pilot valve same day and air system returned to normal.
9l>0L24 317
EFFECT SPECIAL PRECAUTIONS SYSTEM ON CORRECTIVE ACTION TAKEN TO PROVIDE OR COMPONENT MALFUNCTION SAFE TAIEN TO PREVENT FOR REACTOR SAFETY CAUSE RESULT OPERATION REP _ETITION DURING REPAIR ______
PORV 568 Solenoid Diaphragms lost Excessive air None - valves Replaced diaphragms and Tagged valve closed and.
flexibility due comsumption failed closed ordered new Hi temperature shut off air to prevent to heat solenoid valves opening "A" Aux. Feed Pump Misalignment Vibration None Realigned pump per "B" pump available J.O. #MA 0788 procedure M 8.5-40 S.I. UCV 1881 RWST Loose lock nut Valve would not None Relocked stem by None required recirc. valve operate properly tightening lock nut J.O.
0796 Relay contacts Contacts stuck Shut off de-Unplanned gas Replaced relay with a more None LS-ll5 3BX closed gasifier trans-released reliable type fer pump 4160V cable from EG2B Contractor work-Damaged 4160V None -
The pre work checkoff has Redundant system avail.
diesel to control cab.
ing in area cables from Redundant been improved to require broke thru EG2B to control system avail, closer print review and PVC conduit cabinet additional precautions Q
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CONNECTICUT YANNEE REACTOR COOLANT DATA MONTH i~' 12-79 REACTOR COOLANT ANALYSIS MINIMUM AVERAGE MAXIMUM Ptf-t?1 5-DEGREES-C 6T4 O E + 00 -:-6T 60 E + 00 --*-6T76E + 00--t CONDUCTIVITY (UMHOS/CM) 1.05E+01 :
1.49E+01 :
1.90E+01 :
- <4.00E-02 : <4.00E-02 : <4.00E-02 :
-DI SSOL-VED - 0X YGEN ---( PPB >
-<5.00E+00-:-<5.00E+00-:-<5700E+00-:
3.47E+02 :
3.86E+02 :
1.29E+00 :
1 70E+00 :
-TOT AL-G A M M A--ACTM UC/ML-7 i
6T96E + 00-1-8745 E + 00-t -9750 E+-O O 10 DINE-131 ACT. (UC/ML) 4.29E-02 4.90E-02 :
5.53E-02 :
I-131/I-133 RATIO 7.70E-01 :
8.81E-01 :
1.28E+00 :
NUDN MG/LTTER7 5700E=O2d 665E=01 ;
a775E=DI ;
TRITIUM (UC/ML)
- - 2.53E+00 3.00E+00 :
3.50E+00 :
HYDROGEN (CC/KG) 2.05E+01 :
2.26E+01 :
2.68E+01 t
AERATED LICiUID WASTE PROCESSED (GALLONS):
6.37E+04 WASTE LIGUID PROCESSED THROUGH BORON RECOVERY (GALLONS):
2.14E+04 AVERAGE-PRI M A RY-1;E AK-R A TE ( G ALLONS--PER-M I NU T E ) :-4770E-02 PRIMARY TO SECONDARY LEAK RATE (GALLONS PER MINUTE):
0.00E+00 96024M9
r
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- flRC OPERATit!G STATUS REPORT CortPLETED CY ftEACTOR Ef; Git 1EDtitr.*****
______2 1 __Ulst T !aNIE....QJ:;!i. YA!JI;CE ATL11tc 1u1D1.C0.
D00*ET 10.-5'l-213 -
2 etEPutTIlaG PDtl00.... December 1979 DATE 1/11/80 3.
LICO4 SED TIIDtnL PGJE.t(.tlT)...1325 CD'!FLETED CY.. Reactor Engineering 4
l.AICPLATE MTI;au(G:cas 114C)....Guo.3 '_
TELEPlur:E- (203) 2G7-2556 - -
S.
IslGr. ELECTallCAL.tATl;G GIET itet)... 575 b.
14Ml;ut vEPD4aACLE cal %Cl TY(muss rtlE)... 577 7 _ F/dt:lJe t UCPG vAOLE CAPACITY (taET. L.E)...
550--
8 k.
IF OIA;6ES UCCud itt CAPACITY RATit G5(ITD15 3 TllROUGil 7)SillCE LAST REPORT, GIVE REASat!S....None j
I 9:
meDt LEVEL To tJIIOl P(5T;tlCTED. __.lF A1:YulET 211E)-.none I J.
HEASull Foil REST.tlCT10!i.
IF AtiY....Not applicable t
THIS REPORTillG PERIOD YR. TO DATE
~
Cult 1LATIVE 10 DATE 11.
luurts lll ItEP0dTitu.PCtt03 744.0 3760.0 105192.0
- 19.
f.tIk:Dt UF th51dS Tlik (EACTOR tfAS CRITICAL 744.0 7541.2 9119G.7
- i' 13_
ttEACTuR ltE5DNE SliUTlut!110Vits 0.0 254.5 1152.6 * --- -
J 14.
IdAtS GE!!DtATtXI Old LItaE 744.0 7427.6 8t,9t.o.2
- l'5.
O!.IT.tESDtvE uluTin.Jia IUuts 0.0 233.5 369.9 i
l u-u&s Tilt ttAL E!JDtGY GEl1GtAT'ED 04JI) 135G111.-
1320200G.
150141149. - - - - - - - -
---2 17.
G30:,J ELECTitICAL DJDtGY GEtiDIATC) Otal) 450730.
4322052.
493544GG.
16.
f4ET ELLCTitlCAL DiGtGY GE!!DIATED (flat) 430745.
411G339.
4G9547G3.
~
i b
g 19.
Ut.lT GL tVICE FACTOR 100.0-34.3 32.G
- 40.
dritT AVAILA3tLITY FACT 04 10J.0 87.5 83.0
- CD
' N il.
UNIT CAPACITY FACTOR (JS!!!G 10C IJET) 105.3 85.4 82.6
- j Ai 100.7 81.7
- - 7G. 8 * - - - - - - - - ---
v42-UfitT. CAPACITY FACT 0it (d5ti1G UER !!ET)
N g2 3.
UtilT F0;tCED OUTAGE.IATE 0.0 0.4 7.3 *
,, 2,4.
strJTlAI.J!;S SQlEDUALED OVER I4 EXT G 110f1TilS(TYPE,DATE AtJD DURATI0tt OF EAct)....Ref:seling. Hay 1930. Approximately 8 to 12 weeks t-45.
IF WivTunsta AT EllD OF ltEF0ttTil1G PERIOD, ESTIttATED DATE OF STntTUP.... Not Applicable gu-UlllT5 ili TE5T STATJ:,(P.tIO.t-TV C0!4tDICI AL.0?CRAT10:1).u. Not Applicable l
l
- SitiCE DATE (# CutttDtCIAL CPGlATIO!J 1-1-G3
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-213 Conn. Yankee UNIT Haddam Neck DATE 1/11/80 COMPLETED BY Reactor Engineering TELEPHONE (203) 267-2556 MONTH:
December, 1979 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 582 17 581 l
2 582 18 578 3
582 19 578 4
583 20 579 5
581 21 579 6
583 22 579 7
583 23 580 8
582 24 581 9
581 25 580 10 582 26 580 j
11 583 27 580 12 583 28 580 13 583 29 5.80 14 583 30 579 15 582 31 580 16 564 INSTRUCTIONS On this format, list the average daily unit power Icvel in MWe-Net for cach day in the reporting month.
Complete the nearest whole megawatt.
95024321 (9/77)
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DOCKETNO. 50-213 l
UNITSI:011:0WNS AND POWER REDUCTIONS C nn. Yankee UNIT NAME j
- 1) ATE 1/11/60 December 1974 COMPLETEI) ltY Reactor Ln:.:ineering ItEPORT MONTil 3 g;g,g g,ltONE. WO 3) 26/-2nb i
l h.
I.scettice
,E *t,
,3 Catsse & (".nrettive
. N.e.
- 1) ate y,
3g
(
jgy liverit
- r. 7 gg Atisini t..
$E 35c itepost 8'
- E U EU Psc$cnt itetturci.c4 H
s.
?
u 6
No unit sh6tdowns or significant l
power reductions during the month r
of December,- 1979 ' reporting period. j..
s l
~D-e s t.
c.
b w
I
'2 1
.p,.
l' l'..twJ lteau.n:
Method:
lishibit G. Inntrustnins u
5 Siliedulcil A !:ilnipinent Itailuie(laplain) i 1-Mantul for Preparatnin ut 1)ata g
Italaintenance in Test 24taniul Scrain.
I.nte> Sheets I.n l itemce g
(' ttcIncieng 1-Autornatis Scrant.
1 sen Itep.nt II.I lti i sfc (N*I;t.C.
- 1) Regulat.u) ltesteistion 4-(Ithes (!!aplain)
Ul t.I l I t apes.itue leatunig A Iicesaw l Xatnlitatiott
~ %
I binonistiative
- t. tleciation l i esi : (I apl.uit)
I sintist I - St.se Sna.c
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i'
REFUCLING INFORMATION REQUEST 1.
Name of facility Connecticut Yankee Atomic Power Company 2.
Scheduled date for next refueling shutdown.
May, 1980 3.
Scheduled date for restart following refueling.
Approximately eight to 12 weeks from shutdown date.
4.
(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 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 configuration 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 10CFR50.59 to determine if any unreviewed safety questions are associated (d) If no such review has taken place, when is it scheduled?
with the core reload.
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.
j 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 prescat licensed spent fuci pool storage capacity and the size or any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies.
bfe projected date of the last refueling that can'be discharged 9.
to the spent fuel pool assuming the present licensed capacity.
1994 to 1995 96024323
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