ML19320C984
| ML19320C984 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 07/11/1980 |
| From: | CONNECTICUT YANKEE ATOMIC POWER CO. |
| To: | |
| Shared Package | |
| ML19320C979 | List: |
| References | |
| NUDOCS 8007180395 | |
| Download: ML19320C984 (12) | |
Text
/ 3 5,)
CONNECTICUT YANKEE ATOMIC POWER COMI'ANY HADDAM NECK PIANT HADDAM, CONNECTICUT MONTHLY OPERATING REPORT NO. 80-6 FOR THE MONTP OF JUNE, 1980 8007180 3c)g
PIANT OPERATIONS The plant wi.a shutdown forrefuelingoper[itions for the entire month.
w G
~.
t CONNECTICUT YANKEE REACTOR COULANT DATA ~~~~ ~~~~ ~ ~ ~~~~~ ~ ~ ~ '
~ ~ ~ ' ' ~ ~ " -
~
~
MONTH: JUNE 1980 REACTOR COULANT ANALYSIS MINIMUM A'!ERAGE MAXThUM PH G 25 DEGREES C 4.48E+00 :
4.65E+00 :
4.76E+00 :
CONDUCTIVITY (UMHOS/Cil) 5.30E+00 :
5.95E+00 :
6 30E+00
- 4.00E -02 ~ !
.'4.00E-02 i ~ ~ ~ ~ ~
C HL O.i'I D E S (PPM)
T~WO'O t-:-02 DISSOLVED OXYGEN (PPB)
~*
2.28E+03 :
2.35Et03
!'- ~~~
LIlHIUM (PPM) 10fAL GAMMA ACT. ( UC/tiL )
7.63E-03 :
8.18E-02 :
2.52E-01 :
10 DINE-131 ACT. (UC/ML)
^'~f: U17f 133~ RATIO ~~~~~
~ ~~' T".
~!'
~ !
CRUD (MG/ LITER)
IRITIUM (UC/ML) 1.17E-01 0 1.2SE-01 :
- 1. '!9 E -01 :
~~ HYDROGEN (CC/KG)'
0
_ _. ~.._ _ _ _ _... _ _ _
AERATED LIQUID WASTE PROCESSED (GALLONS):
1.71E+05
~ ' -W AMCL IOU'ID PROCESSED THROUGil DORON RECOVERY '. Ontr. OMS ) :
0. 0 0E --01
~~ ~
~
AVERAGE PRIMARY LEAK RATE (GALL.ONS PER HINUTE):
PRIMARY 10 SECONDARY LE AK RATE (G ALLONE PER (11NUTE ):
- Shutdowr. for Refueling Outage.
m
,m.,.-w.e-
-e
--e.e--.
.gie
-.m m..-.
m.
-s e-em+..h._hw.wes-e
..t es
.g.m,.
4-
...a m
_p-.
4.we emm hw...m.-
'em-,
9-he e
4%m-.
- .--h
.w
-6 h
e es-
.,m-.
,4 m
EFFEss l
SPl:CI AL PRECAUTIONS SYSTEM ON CORRECTIVE ACTION TARES T0 PROVIDE OM MALFUNCTION SAFE TAKEN TO PREVENT FOR REACTOR SAFETY COMPONENT
, i CAUSE RESULT OPERATION REPETITION DURING REPAIR 12 Feedwster Age and wear Noisy and some-None Overhauled valved None - shutdown for refuel =
Regulating Valve times sticky ing MA 1449 operation Io. I Main Stesm Trip Age Slight steam None Resealed and retightened None - shutdown for refuel-Valve leakage at pin pin cover ing MA 1476 cover Pressurizer Spray Plug detatched No pressure None - other Rebuilt valve, installed None - shutdown for refuel-Valve 574 from stem control with valve used new stem ing MA 1497 this valve CCdCV-721 RCP Thermal Age Leaked by None Replaced valve None-shutdown for refuel-Barrier Check Valve ing A6B RHR PP Seal Piping Age Slight leaks at None Remade joints None - shutdown for refuel-MA 1544 threaded fitting ing CC-V-760B and Wear Valves leaked None Rebuf1t valves cut din. and None - shutdown for refuel-CC-V ',64B by ground seats ing MA 1547 "B" Containment Sump Wear / Age No outtnet None Rebuilt PT - Installed new None - shutdown for refuel-shaft and impeller ing Pump pressure
- u 1559 b Service Water Pump Ikid hearing Noisy None Replaced faulty hearing None - other pumps in service
':a t o r
'T i 1562
- lD-!!!CV-1840 Conta i n-Age / wear I.eaked by None Rebuilt valve None - shutilown for Sump discharge trip refueling y.;
- Li 1574 B P>oric Acid PP Worn out Not pumping None - other Rebuilt pump - replaced None - shutdown for refuel-
- L\\ 1582 PP available bearings ing
EFFECT
. 5 ".3N. v. -
.SYSIDI ON CCRRECTIVE ACTION TA!;.;:: *ni P.k.'I2:
MALFUNCTIO:{
SAFE TAKEN TO PREV 2NT F0:1 aCl.CT;G iA $7?.
OR l-D'3INC REPAIR J
C'f:PO::E::T =
CAUSC t
RESULT l OPERATION REPETITION I
Disc' scored
-Valve hard to None Rebuilt valve - cut disc -
None - shutdown for refueld
[W-MOV-12 Feed Water l0V.#2.SG operate ground seats ing iervice Water Line l Worn pipe. fitting Slight leak None - equip-Replaced pipe nipple j None - shutdown"for'refuelg
- o #1 CAR Fan Cooler j ment still ting
't1596 operable CV-194 Wear Leak.3d by None Rebuilt valve l None shutdown' for refuels 1605 j ing I
ux. F.W. Check VV 6
[ Bad bearings Noisy None - other Replaced bearing None - ehutdown for refuel-;
PP's available jing
- tor i
l k\\ 1152'
. adjusted limit on MCB jNone-shutdownforrefuele D-A0V-202 l Improperly Dual indication.
None Adjusted switch
,ing switch i
I l
l i
i.
i i
I i
I
j..
AVERACE DAILY UNIT POWER LEVEL DOCKET NO.
50-213 Conn. Yalikee
~
UNIT limidam Neck DATE July 11, 1980__
COMPLETED BY__ Reactor Engineering TELEPIIONE (203) 267-2556 MONTH:
June 1980 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWo-Net)
(t!We-Net) 1 0
17 0
2 0
18 0
3 0
19 0
4 0
20 0
5 0
21 0
6 0
22 0
7 0
23 0
8 0
24 0
9 0
25 0
10 0
20 0
11
'O 27 0
12 0
28 0
13 0
29 0
1 14 0
30 0
15 0
31
'16 0
l INSTRUCTIONS On this format, list the averace' daily unit power icvel in MWe-Met for each day iti the reporting month.
Complete the nearest whole megawatt.
(9/77)
t el "c
w L
g.j,, p
.p 4
r 3
's
(*
y
's TJ i
.m t L C
a O
=
tw W
4 s""
=
b S1 0
y M
0 L
&,.=9 y
C m
a U
.e y
E.,, =u,-
N
=
,t.
O
- f.
A l
m t
-n 4
O O
0
??
e c w 3,
- c u
u.
== _.
=
e fwwww
..3.1
.= 1 0 -
s x
z << n 7-
- ~ =,
u :
s L
p.4 u.o
.- -=u
...-u..
i u
y
. = =
0
- u ;g =
s -
. = =.. - = --
xe
.=
w -=
=
.=-
z a.
.,, < =.,
. =- u -
o.
a Y.< p
.p MdM-M u
i
~-
- e o
I c
U i
T u ~x
.c c
=~
g c-
=.4 0
u =
cw av O L z"
I d
o apo) i ~, 5, NN D
- uauo4tuo N
- m. *....
- d. =e C
N s
O x
N
- A %*u W
- n N
.. - :; =-
K g
.2.=..=. =. u-2 5..2 = 3 y
VJPOJ 0
3:
LU 315 A-N
.u a s. < -
N-e..
O C
C Z
M Z
M
.C.
u.
a
- f. -.
Z
.c 3
H
~~E O,,
M
$.?.
C-
=.
2.'e
. *. *f.
~
n
==
==
m W
-2 D.
..g M
=
D
,.Jol.WH uMOQ h
Z Suitanyg
-=
~
3 D
.e
.=
10 P"413K
.2 5.
=i
.=
~-
=
a
~ ' ".
. Uof P.iy s
O
" te
.4.
.c u = s-E u~
2-(TJnOQ)
"l*-.d
-::: i.c..
.**.="1~='
m
.a =.
UOtteanQ r
g=
=.
... =, =, -
..=
_.=. _= 4u
_1
-5, =* *s..s, %. = - ~ = ~. ~.
. T.
y~
p Q g, l
- (4 9.,-.r".
- s
- N m
o f.
C M
2.
m o
s - o a
o O
C g
00 co
.=
+
3.
- "3, I mE m
.A t
O 2
cc
.= /.
~~.
n
~
4
n____--_-__
4 ;
O
~
eeoa*f4RC OPERATifG STATUS HEPORT COMPLETED BY REACTOR Ef4GINEEltlNGov**
j 1__: de l T fiA. E.... Cul4.4 YAr.KEE AT01,1C PUWE4 CO...._ _ _ _ ___ _... _..._......._._..___. - __._____ _ _.
-- _. DOCKET IJ0.
50-213
.n 4.
dEMjdTlik, PEdl0J.... June 1980 DATE July 11. 1980 3.
LI CEluf.o Titet. %L Pa.Ee< 01..T ).... id2 5 CX4r'LETED tiY.... Reactor Erga;..
-i._,_.__ A!!su rE dAilIG(G u o.4..E)....JJJ.3 TELEPKJNE- (203) 267-25 A.q,
2.
LEalG!. LLECTalCAL dATI.U(NET.1.E)... 580 v.
IMAbul OEPL.0AULE CVACITY(uto33.itt)... 577
- 7. _ s'.ul.ul,Ee'ElsvAdLE CAPACI TY C.ET ebE)... 550..
-~
o.
IF OWMES uCCot lie CAPACITY stATilH3(ITEMS 3 THIOUGH 7)SlflCE LAST REPORT, GIVE REASONS....N/A j.
lu.ER LEVEL TO WHICH REST,tlCTED. __lF. AfdtiET_1SEL
.) tone 10 HEA504 FOR dESTdiCTlori.
IF At4Y....N/A Tills REP 0lTitlG PEell0D YR. TO DATE CU4JLATIVE 10 DATE kl.
lOJKS I:4 i(EN;1Tilu PEA 10D 740.0 4387.0 109579.0
- l L
2957.1 94153.8
- 12 t;J'.CCR OF IUJ!s THE hEACTOR WAS CRITICAL 0.0 13
.dEACTod DESERVE SIUTD0tlIUUts 0.0
. 11.4
- 1164.0
- i 14 IUUdd bet.E.lATda di Lil4E 0.0 2947.7 89887.9
- l i
15._.. _ Jilt #1JL.4VE stuT00fti IUJts
.0.0 0.0 363.9 16.
(sun red,tAL E14 EDGY 6Er.E. TATE 0 (tOH) _
0.0 509J07d.
155231219. _.
i 17 Gut,S ELECidlCAL TJsEMY GEt.E.tATEJ 0441) 0.0 Iti92421.
51046887.
is.
- 4ET ELECidlCAL Cf.E,WY uEr.ERATED 01Al)
-19G8.
1609319.
4d564082.
19 vi.IT dErtv ICE FACIO4 0.0 67.2
.- t.2. 0.
- kJ.
J4 t T AVAI LAdl LI TY F AC rud 0.0 G 7. 2 62.4
- 41.
Jilt CAPACI TY FACTJa (J31tu s0C f 4ET)
. -......., 0.0 EG.7 el.9
- 42, UtilT CMACI TY FACrdet (JSillG DER llET)._.
_.____0.0 _. _ ___.
_ 63.2 _____._____ __. _
. 75.G *.
t 23.
u.IT F0dCEO udf/dE dATE 0.0 0.5 7.1 *
- j 24 at uTJGeiw SCIEdutED UVER # EXT 6 sotiTIG(TYPE,CATE KM DU: TAT 10'4 OF EAGI).... Continuation of Core 10 Refueling. started May 3.1930 approximately 8 to 12 weeks.
2$.
,lF SlidTbairl AT EIO UF :tEPORTillG PERIOD, ESTl!%TED ') ATE OF STNITUP.... July 14. 1980 a
- 26. _
ullT4 IN TEST STATJ3(Pul0A TI) CoritERCI AL OPERAT10ti)....!J0T APPLICA3LE I-~~-
- alt 4CE DATE UF CJtEdCI AL OPERATlori 1-1-6d i
J L.
g
- ~
REFUELING TNF0mfATION ' REQUEST
- 1.
- Name cf fccility Connecticut Yankee Atomic Power Company 8
9 i
4
'2.
Scheduled date for next refueling shutdown.
September / October 1981 3.
Scheduled date for restart following refueling I
Approximately six to eight weeks 4.
(a) Will retucling or resumption of operation thercarter require a technical specification chang ~e or other license amendment?
No technical specification changes are anticipated at this time.
(b)
If answer is yes, what, in general, will these be?
t N/A (c)
If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee to deternine 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 s,y 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 supportin o information.
There are no scheduled dates because of (4) above.
6.
Important licensing considerations associated with refueling, e.g.,
new or different fuel design er supplier, unreviewed design or perfornance enalysis methods, signifi: ant changes in fuel design, new operating procedures.
None 7.
The number of fuel assenblics (a) in the core and (b) in the spent fuel storage pool.
(a) 157 (b) 389 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 pinnned, in number of fuel ass:mblics.
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 2
M
.._s
. C r4 4
0,4,
~s eac ar,
- s e
tr.
!3 o
- t. m J
c 4
C w
s'
.3 C
C v
b N
O M
C C
W
- ' u
.-e
. I w
e 3
9 E-et C
w L
F O
e C x
= c
= A -
3
~
o o s e m x
an U N
- t w
u 4
="
4
.E.
t U
- ~==
2 u)
E J i ~, -
- c. ' W::: W >= W:cd.d e
J. =
s 4.c. e<-O a
o
..,.s,
.n -.:
= u
- ~~
w
-u p.Z " LJ==
= ::
U f2=
w W
-u p-
"A D
- u. d.
A ' -=.
4_.
sm ;.~
-i_-
..c u p
_ t
,*J e
N Z
J."*
~
O at.
=D g
s u
W C J.~..J l O
-c
- w d-Q C O
w-ImJ l
Q w v
cc
@ G G-l e-c0 0 L u c.
mx m
g 2
- i O
o N
.R C
w
$ap03
',.
N b m '.
h N
g
'UJUOdtuC)
Nu
.., =
e y
s n
o W
L
.. :; g = -
ac c
y =r.= = :2
==
5 C
vee <E t po3
.2.2 :
6 3
o s
o LU215.sg g
j., g, 4,.7 0
u
- c.
e
=
z Z
m
.O u
.x =.-
z
.e 5
w
5
d~ ~M "-
Z o
c:
-=
c
. =.
~~
w c.
.3 W
D.
.3
=
m rs t:
,,Jos. rsg umou
=
~
Z
- Suitanys g
3 3
s 5
4 10 P"413W Z
y-
-..u...=-
a
=
., g
.uosr.13
=5 14
=.,
6
- - s=
,= -
u
- ($Jno[{j
= 4 ~::: :;.e.. --
s
. ;; 3 :
= ',
a:
o uolicing c=-
.=3 :,4 ;E ;,
.c
- ,.h
= = =.=.
r 3*'*"- ass -*e
-p***--
8-f s
lQ {1 a
L
.m. 4,._==.=*~.e.m... '
"w e
. w
.m gy a
- I G
9-$
3, Nm O
O b
n?
- a 3
.e
- e 6
=
~.
o
~~
~^
E' O
Z 00 W
I tn
>4 o#
W a:
=
REVISED 50-213 DOCKET NO.
UNITSI Ull:0WNS AND POWER RED'J."TIONS UNIT NAME Conn-V,nt on I)A1 F.
7/8/90 COMPLETED itY Roactor Fnninoering HEPol!T MONTil March 1980 1 El.i.I'110P'E (20U 267-2ss6 3 v..E S
e c.
c *.;
l.kensee c-t, c4 Cau- & (*oisestive
.2 _e s
7 N"-
IIJ8C 9,
35 4
.c 5 5 I! vent F?
$.3 aunIn Repost a iE0 EO l'a c t.* liesuitenue
$5 3::
H c
3 t
u 6
80-2 800327 F
13.7 H
3 ZZ ZZZZZZ Reactor,and turbine trip due,to to high containment pressure / core 800328 cooling actuation signal.
?%
b I
- 2
.t.
4 l' l uised Iteas..n :
Metiniti:
ihinhit (;. in,s enstnins
. lipnpment I ailnic(I.splain) 1 Manual
.'.., pr epai.i...n.. l >au S 5.1 cJulr 1 ll Maintenance on Test 2 MannalScram.
Ic. >.slicels i. I escene
('l(elvelnig,
.1 Autoniatie Sstani.
hen Itepo,t ;l.l lu I sic (Nilltl.C.
- 1) 1(egul.it.n> l(e. ristion 8-011.:. (limplain)
()I t.1 )
I t) pes.stor is.itning a liscuse I aaniinatiini i
I binunnte.itr.r I; t)pceain *;.1 l nni (l aplas i)
I glntip i. s,,,, c 3.,n,,c.
t"lli)
'l!lilice iI spl.un) g O
O Y
e e
O m r -o.
n DOCKET NO.
50-213 UNITSI!Ull:0WNS AND PCWER REDUCTIONS
~
REVISED UNIT NAhlE Cotm. Yankee
~~
DATE 7/8/80 COMPLETED 1:Y
%ncyn"
- H"eering HEPORT 810NTil May 1980 1ELI.Pi!ONE (203) 267-2556 c
,5?
3 j E' ~;
l.icensee E.g,
. gut, Came & rosectitve N...
15:le h,
5g 4
2 E
liven 3,7 e1 Attnen in fE y
g, c Repost a v: O 5V Prevent Recurence t-g u
d 5
685.,6 C
1 ZZ ZZZZZZ Tripped. Turbine 80-3
.800503 t
Normal' Plant. unloading from 88%
power to zero for refueling outage.
~
s 9
A g
I
'J 1
4 l' l.uscJ It ea s..n :
h*ctinxt:
litinhit G Instenstuwis 5 S.I.cJuleil A l.ilurl.nnnt failnic(laptain) l Mannal fin Pseparation of thia II. Maintenance.n Test 2 ManualScrant.
l.iits) St cess I.. I nemee c.Ite neling
.1 Antunialie Strani.
ITen 1(epini 11.1 H I I ile I NilHl.G.
D !<egni.it.n> ltesiristion
.I Otties (lixplain)
Ultill I t)petJiest j's.gisiltig d l lecilhe l XalIIIsiallOll i
5 I kini nwii.nive Ii e:pesaiional I inn li splain)
I sin'ul 1.\\ n e.N on o O'111) 11 (litici il solanil 9
9 k 1
~
....