ML19351E917
| ML19351E917 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 12/12/1980 |
| From: | CONNECTICUT YANKEE ATOMIC POWER CO. |
| To: | |
| Shared Package | |
| ML19351E914 | List: |
| References | |
| NUDOCS 8012190526 | |
| Download: ML19351E917 (10) | |
Text
.
M i
L CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT I
HADDAM, CONNECTICUT j
)
4 4
i i.
!ONTHLY OPERATING REPORT NO. 80-11 FOR THE MONTH OF NOVEMBER, 1980 O
801239053G
)
1 Pl. ANT OPERATIONS The following is a chronological description of plant operations f
for the month of November,1980. -
11/1/80 The plant was operating at 100% full power (607 MWe) at the beginning of this report period and remained at full power until 0708 hrs. on 11/18/80.
11/1 Backwashed 'C' condenser water box @ 1145 hrs, and backwashed' i
'D' condenser water box @ 1148 hrs.
N.R.C. dedicated phone line out of service 1411 hrs. until 1431 hrs.
11/5 NRC.
dedicated phone line out of service for repairs 6 1230 hrs. Returned to service @ 1700 hrs.
11/6 ADT ion exchanger out of service for resin replacem,ent 9 1305 hrs. Returned to service @ 2130 hrs.
11/11 Backwashed all condenser water boxes 0405 to 0522 hrs.
11/13 Tested operation of MOVs 310,555 and 567 following the shifting of leads to a qualified terminal block @l230 hrs.
11/18 Reactor tripped manually when Rods 30 and 33 in Bank
'B'
/
dropped into Core @ 0711 hrs.
7MC1 relay ou movable gripper coils on Bank 'B' was replaced and reactor was brought critical @ 1749 hurs. Unit phased to line @ 2058 hrs. and load increased to 25% full power @ 2240 hrs.
11/19 Commenced load increase from 25% full power @ 1055 hrs and plant was @ full power @ 1945 hrs.
11/20 Turbine trip and Reactor trip @ 0338 caused by mechanical overspeed trip on turbine. Reactor returned to criticality e 0501 hrs.
11/21 Overspeed trip tested @ 0458 hrs. Turbine tripped at 1810 RPM. Reset and retested to trip @ 1840 RPM @ 1120 hrs.
Unit phased to line @ 1229 hrs. and load increased to 25%
full power @ 1410 hrs.
Commenced load reduction @ 1748 and unit off line @ 1845.
Turbine overspeed retested to trip @ 1831 RPM.
Unit phased to line at 1956 hrs, and load at 25% full power at 2124 hrs.
Connenced load increase @ 2323 hrs.
11/22 Unit at full power 0 0730 hrs, and remained at full power for the remainder of this report period.
11/24 NRC dedicated phone out of service 0623 to 0935 hrs.
l l
'A' charging pump out of service for seal line leak repairs 9 1130 hrs. Returned to service @l655 hrs.
(
~ ~ _. _
_ _ -... --__..-.. - ~ _-.-.
4 2-t
~
t 11/26 Diesel Fire Pimp out of service @ 0912 hrs. to repair fuel line leak. Diesel fire pump ratested and returned to service l
f 1035 hrs.
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EFFECT SPECIAL PP.ECAUTIONS SYSTEM s
ON CORRECTIVE ACTION TAKEN TO PROVIDE OR -
MALFUNCTION SAFE TAKEN TO PREVENT FOR REACTOR SAFETY COMPONENT CAUSE RESULT OPERATION REPETITION DURING REPAIR Rrdiction Faulty wiring to Loss of reliable None Replaced wiring from rerote N/A Monitering detector indication indicator to detector Ch:nn21 R-32 connector St am Line Break Failed servo-Loss of flow None Replaced servo-mocor None RX-Shutdown Det:ctor motor indication h2FW. Regulating Worn Snubber Eiratic valve None Replaced all worn internal None RX-Shutdown V21va snubber parts ~
movement parts Pow;r Range Static on meter "A" Ion' chamber None Replaced NIS drawer Follo: Procedure Nuc1:ar Instrument current drif ting Channel 33 M
8-2-1 Draw;r MA 1884 Weeping fittings Airborne None Resealed pipe fittings "A" pump running "B" CHG. Pump Seal activity Wat r fittings MA 1891 Valve internals Valve leaks by None Replaced plug & stem None required Atmohpheric Steam worn 9
Dump Valve MA 1904 Sheared pin on could not close None Replaced pin None required "C: Service handwheel valve W:ttr Valve Replaced 7MCl Relay Reactor Tripped Manually MA 1377 7MC1 Relay Dropped Rods None Rod Control malfunction 30 & 33 System
,MA 1370 Unqualified Block could fail None Replaced Terminal Block Retest of MOV Tcrminal Block Replace -Westinghouse under LOCA Installed Beta Shield 567, 555, & 310 ment and Beta shield Block conditions im tcllation s
O 8
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1 mm.
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CONNECTICUT YANKEE REACTOR COOLANT DATA MONTH: NOVEMBER 1980 REACTOR COOLANT ANALYSIS MINIMUM AVERAGE MAXIMUM FH & Zu UEUntt6 L D.0/Etov ;
c.12Ltov i o.JattOu i CONDUCTIVITY (UNHOS/CM) 1.00E+01 :
1.51E+01 :
2 05E+01 :
- <4.00E-02 : <4.00E-02 : <4.00E-02 :
s,.v0erov ss.ovutvu
,a.vuttuu vid;sutvtu uA s utu wr u e 8.48E+02 :
9.28E+02 :
1.19E+03 :
1.30E+00 :
1.88E+00 :
IUIAL U H nPI A HL6.
(UL/ML/
1.UYtrVU ;
J. / UL rVV 4
- 0. ult 1VU 10 DINE-131 ACT. (UC/ML) 8.35E-03 :
1.93E-02 3.09E-02 :
7.21E-01 :
7.80E-01 :
8.56E-01 :
I-131/I-133 RATIO
/
4 U.UUt-v1 i
4.VVt-UL 4
/.Uvt-v1 TRITIUM (UC/ML) 3.19Ef00 :
3.08EF00 :
4.60E+00 :
LMUD inb/ L A l tn e HYDROGEN (CC/KG) 2.20E+01 :
2.32E+01 :
2.60E+01 :
AERATED LIQUID WASTE PROCESSED (GALLONS):
S.52E+04 1.10E+04 WASTE LIQUID PROCESSED THROUGH BORON RECOVERY (GALLONS):
svennut rnionni Lesa naattuattuna run niuuiE/.
2:03 *E -- 0.
0.00E+00 PRIMARY TO SECONDARY LEAK RATE (GALLONS PER MINUTE):
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+
AVERAGE DAILY UNIT POWER LEVEL DOCFET NO.
50-2 3 Conn. Yankee UNIT Haddam Neck 12/12/80 DATE COMPLETED BY i
TELEPHONE (203) 267-2556 MONTH:
November 1980 DAY AVERACE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 580 578 1
17 580 180 2
18 580 302 3
19 579 88 4
20 j
579 5
21 578 524 6
22 577 579 7
23 578 578 8
24 577 579 l
9 25 577 579 10 26 578 580 l
11 27 580 12 578 28 13 579 581 29 580 14 580.
30 l
15 579 31 l
578 16 i
INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month. Complete the nearest whole megawatt.
(9/77) i
d
~
q 50-213 UNITSilUll:0WNS AND ECWER REDUCTIONS IX)CKET NO.
UNIT NA%f E _ C nn. Yankee I; ATE 121121* '
HEPO'tT Al0N111 Nov. 1980 COMPLETEls IsY React r Eng.
),.g,g.g.: gas (203) 267-2556 Q
~
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e ee i (CZ))
N...
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f,5 INU
I#"'*#
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'03 E'" 8' I " . '"
62 A6:nni te 3:
l{cpeut er e/g'd yb
,.,,,,,,, g;g,,, C,,L,
I N $[j e
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f 80-7 801118 F,
13.8 A
2 80-16/03L RB CRDRV While stepping in Control Bank Rods, one Step, both audible and visual Alarms indicated two dropped rods-moyable gripper coi1s were at fault 80-8
- 801120 F
32.9 H
3 ZZ ZZZZZZ It was defermined that the mechanical overspeed devise on the ll.P. Turbine
.was out of adjustment.
Adjusted device., titen tested and came back on line i
80-9 80x121 S
Os 7
- B 1
ZZ ZZZZZZ Test of overspeed setting on turbine 6
i 4
l
- J 1
4 l' l'inced Itcawn:
MetiniJ:
Estuhit G. ls...sustiins 5
1 5 S.I.cJulcil
. A 1:.piipment trailniellarlain) l Manual fi. Perpasainm ul flera ll. Maintenance in les 2 Manual Seeam.
lines) Sleccis fin I ssemce
('.Itcf nelmg
.l Antinualle Surans.
l sen Hep.no II.I HiI sicINilRLC.
D l(cr l.si.n> Hessel (tion 44hlice ll'aplaisil 01118 I tlpes.i.n l'eanimg." I kenw l maminatient t
4 l LIin.nistiative e
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Ii t Ipcsais.esal I si..e II:mplaeol I sinlet I.%4nw.%ns.o
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'It JOB 0000011111 It tFO PO4 FI J.
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essesNRC CFEP4 TING STATUS REPORT COMPLETED BT REACTOR ENGINEERINCessee
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1.- UNI 1 wriF....f 40. TtME ATOMIC F0JER CO.
DOCAET h0.
50-213
- l h2. RFi n Tit.(. Fill 00.... tavenitier 1990
[4TE 12/12/80 Ig. g 3.
LIGttlO Thir:W. FWLia rN T ).... l L;.5 CGMPLETED BT Reactor Engineering
- 4.-- ts.Wt ATE lailNCicit055 t'WL)... 6N.3
- - TELEFH0tE (203) 267-2556
-i 5.
t(sICH FLI.( TRICcl MTING(NET MUO... 500 n
6.
MAXIMUM L4.f FNDAftE CAPACITT(CAOSS M'WEl... 577 7:- MA11MM idFENDAELE (MACITI(NET MWE)... 555 -
-- -- q
, n f8.
IF CHANCI.S OCO>R IN CAFACITT RATINGS (ITEM 3 3 THROUCH 7)SINCE LAST REFORT, CIVE REASONS....None l.
POWER LEVEL TO WHICH RESTRICTED.
IF ANTINET PCE)....None 9
- 10. REASON FOR RESTRICTION.
IF ANT,,,,N/A O
THl$ REPORTING PERIOD TR. TO LATE CLTULATIVE TO DATE l ~
d
-l 11.
H0l0S IN RFF0HTINC FERIOD 710.0 0040.0 113232.0 e g.
12.'
NUMPIR OF ilnURS THF EEA(T(C WAS CRITICAL 703.0 6031.8 97? 9.6
- M
-13.-
REACTOR REftr.VE SilVIICWN HntmS.... _ _ - -.
0.0 -
2 7. 0 -.. - -- - -- - - - -
1877.6 e g]
14.
FXRS CEttRATOR C'N LINE 672.7 5640.6 92780.8 e 15.
UN!T RLELRVF LHUTDOWN HOURC 0.0 0.0 367.9 g
4 16.--
CROSS THEIS.L ENERCT X.'!ERATED (MWit).
1184775. --
10001831. -
. 160222720.... -. - -
.1 M
i.
17.
CI:0SS ELICTRICAL EtERCT CENERATED (MWH) 391585.
3307160.
52661626.
?
(~]D f 18.
NET ELFCTRICAL EtKRCT GFNERATCD (ME0 373247.
3141191.
500k954.
e i
1.19. ---. UNIT STRVICF FACTOR 93.4 -
72.6 --
-. St.9 e
'I
=
20.
UNIT AVAILABILITT FACTOR 93.4 72.6 62.3
- 7 l 21.
UNIT CAFACITT FACTiA (U51tC MDC NET)
?3.6 -
70.4 s!.7 e
- 22..... UNIT CAFACITT FACTOR (USING !(.R NETI G7.5
.-...----67.4---.--------..
75.5
- 23.
UNIT FORCED OUTACE RATE 6.5 1.3 6.9 e
-.s.
[24.
SHUIDOWNS SCHEDULED OVER LETT 6 MONTHS (TTFEsDATE.*ND DURATION OF EACH)....None e
25.
IF SHUTICWN AT D40 0F REPORTING FERIODe ESTIMATED DATE OF STARTUP....N/A
[' f
.26. -- UNITS IN TEST STATUS (PRIOR TO COMMERCIAL Cf ERATION)....NOT AFFLICABLE
a a
eSINCE DATE OF COMMERCIAL OPERATION 1-1-68 M
,// J08 0000011111 3
,// IE0 FtB F1 9
possNRC 0FERATINC STATUS REPORT EOMFtETED BT REACTOR ENGINEER!NCeeeee j
[
A 1.
UNIT NAMI....C@N. TANLEE ATOMIC POWER CO.
_. _.. DOCEET NO.
50-223 I:2.
FEFCRTING FERIOD... 0CTOBER 1980 Prvision 1 to correct Hours in Reporting LATE 12/12/80 0 ! 3.
LICETED THIFHat. routROWD....lC25 period from 744 to 745 CONFtETED E' REACTOR ENGINEERINC
' 4.
NAt&l ATF rATltir.(i.r005 ti;E)... 600.3 TELEFHONE (203) 267-2556 q
5.
DESIGN ELFCTRICIA RATINCtNFT huO... 5f:0 Q
0 6.
NAi! MUM DLIEtNILE CAPACITT(CROSS MWEl... 577 f.- MAtlMtri FfrENIAELE CAPACITTINET NWEl... 555IF CHANCES OCCUR IN CAPACITT PATINGS(ITEMS 3 THROUCH 7 7
7M 6.
O maximum dependable capacity of 555 ISiE. n the HDC 9... POWER LEVEL TC WHICH RESTRICTED.. !F ANT (NET NWE)....None.
_. -..__..'was increased from 550 to 555 MWE Net. effective this Q
- 10. REASCN FOR RECTRICTICN. IF ANT....N/A reporting period.
i n
..___..__._.,M F.
b THIS REPORTING PERIOD TR. TO DATE CUMULATIVE TO DATE N
i.
M
' 7 11.
HOURS IN REPORTINC FERIOD 745.0 7320.0 112512.0 e (W
i 745.0 5323.8 96520.6 e j
.12.
la.WPER OF HOUR.S THC REACTOR WAS CRITICAL l (.
)
r - - - - * -
k 13... FEt.CTOR RESERVE SHCTDOWN HOURS -. _
0.0 27.0 -
1179.6 *
}
H 745.0 5167.9 92108.1 e 14.'
, OURS CENERATOR ON LINE
. Il5.
UNIT RESFRVE SHUTr@WN 00LIRS 0.0 0'.0 369.9 J 16.
. CROSS THERMAL.'ENERCT CENERATED (MWHI.._.._. 1355070...
___. 8897036.
-... 159038185.
..]
.I l
17.
'ROSS ELFCTRICAL ENERCT CENERATED (IliHI 447699.
2914575.
52269041.
I t'8.
NETELECTRICALENERCTCENERATE'D(Miell i27876.
2'I 7N4!
49722107
~
19.
. UNIT SERVICE FACTOR 100.0 70.6.
91.9 *.
..i 20.
UNIT AVAILABILITT FACTOR 100.0 70.6 82.2 *
. _. _. UNIT CAPACITT FACTOR (USING MIC NFil 103.5 68.1 81.7 e 21.
22._... UNIT CifACITT FACTOR (USING DER NET) 99.0
. 65.2 75.4 e _ -.....
23.
UNIT FORCED OUTACE RATE 0.0 0.6 6.9 e
..g.
(2E "' SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHStTTPEeDATE AND DURATION OF EACHl....None
..... IF SHUTDOWN AT END OF REPORTINC FERIODe ESitMATED DATE OF STARTUP....N/A
.25.
s
.26.
ImlTS IN TEST.STATIElPRIOR TO COMMERCIAL OPERATION)....NOT APPLICAOLE.
e$1NCE DATE OF COMERCIAL QPERATION 1-1-68
REFUELING INFORMATION REQUEST 1.
1Gne 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.
I 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 time.
(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 Co=mittee 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 tendor they will be reviewed in accordance with 10CFR50.59 to determine if any unreviewed safety j
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 submitting proposed licensing action and supporting information.
There are no scheduled dates because of (4) 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.
j (a) 157 (b) 38'9 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 discharged to the spent fuel pool assuming the present licensed capacity.
1994 to 1995
.s