ML20062G092
| ML20062G092 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 07/13/1982 |
| From: | CONNECTICUT YANKEE ATOMIC POWER CO. |
| To: | |
| Shared Package | |
| ML20062G089 | List: |
| References | |
| NUDOCS 8208120239 | |
| Download: ML20062G092 (12) | |
Text
.
CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT HADDAM, CONNECTICUT MONTilLY OPERATING REPORT NO. 82-6 FOR Tile MONTH OF JUNE 1982 9208120239 820713 PDR ADOCK 05000213 R
PLANT OPERATIONS The following is a summary of plant operations for the month of June 1982:
The unit operated at full power until June 4 at 1340 when the plant tripped due to fragmenting shim pieces in the generator' exciter which caused a loss of generator field. The exciter was repaired and the plant phased on line June 10 at 0220. Condenser tubes were plugged and the unit reached full load on June 11 at 0646.
The plant commenced a load reduction to 40 MWe on June 30 at 2200 to repair a steam leak on the high pressure turbine extraction line to the #2A and #2B feedwater heaters.
e
Instrum nt and Control June 1982 SYSTEM CN CORRECTIVE ACTION TA12N TO PROVIDE OR MALFUNCTION SAFE TAIGN TO PREVENT FOR REACTOR SAFETY COMPONENT CAUSE RESULT OPERATION REPETITION DURING REPAIR Ccntainment air recir-Damper control Decreased fan None Reconnected linkage and ad-None culation fan bypass linkage was found capability to justed switch damper disconnected, as-remove contain-sumed due to ment air activity normal wear a
LK1nrLECT s t' r.u i An ratun u iv.u SYSTEM Maintenance Report for June 1982 ON CORRECTIVE ACTION TAKEN TO PROVIDE OR MALFUNCTION SAFE TAKEN TO PREVENT FOR REACTOR SAFETY COMP 0 MENT CAUSE l
RESULT OPERATION REPETITION DURING REPAIR
- 1 Main Steam Trip Cause:
Valve Valve disk bound Valve failed to None Repaired tail link and Unit was already shutdown in open position close during aligned with rock shaft and main steam system valve test isolated Reason:
Disk tail link misaligned with rock shaft
i AVERAGE DAILY UNIT POWER LEVEL DOCKET No.
50-213 Conn. Yankee UNIT lladdam Neck DATE July 13. 1982 COMPLETED BY REACTOR ENGINEERING TELEPIIONE (203) 267-2556 MONTil:
JUNE 1982 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 sys 17 574 2
s71 18 573 3
s73 19 573 4
341 20 572 5
0 21 572 6
0 22 570 7
0 23 570 8
0 24 570 9
0 25 568 10 163 26 568 11 556 27 567 12 577 28 568 13 578 29 567
- 4 577 30 555 15 574 31 572 16 INSTRUCTIONS On thi s for
- nat, lisi the average daily unit power Icvel in MWe-Net for each day in the reporting month.
Complete the nearest whole megawatt.
(9/77)
CONNECTICUT YANKEE REACTOR COOLANT DATA MONT H :._ JUNE _1902.-.
MINIMUM AVERAGE MAXIMUM REACTOR COOLANT ANALYSIS
....................................................................._6 17E+ 0 0_
__6. ABELOO_ :._._6.44E+00_ :
CONDUCTIVITY (UNHOS/CH) 1 19E+01 :
1.75E+01 :
2.15EiO1 :
PH e_25 DEGREES C____
- <5.OOE-02 : <5.00E-02 : <5.00E-02 :
DISSOLVED.0XYGENJEER)
- <5100Ef_00
- <5 00EiDo : <5.00EiOO !
6 50E+02 :
1.05E+03 :
1.16E+00 :
1.63E+00 :
2.04E+00 :
DORON (PPM)
TOTAL GAhMA ACT.... (UC/ML)_
__I_ _ 1,.0 0 E - O L :
1_.27 EiO O _ L__1 t25E iOO _:
LITHIUM (PPM) 10 DINE-131 ACT. (UC/ML) 1.80E-03 :
8 52E-03 2.71E-02 :
2 62E-01 :
8.40E-01 1 1.51E+00 1
! <1100E-02 : <1100E-02 : <1.QQE-02 :
1-131/I-133 RATIO 2.33E+00 3.06E+00 ;
3.92Et00 :
CRUD _(MG/ LITER).
2.63E+01 2.97E+01 :
3.58E+01 TRITIUM (UC/ML)
(CC/KG) u m.. u _._._ u _ u m.
. o.... u.......... u...... u. u.. _... u...... A. A. _ u. u_._._._u
. A.. u _u _. _._
1.56E+05 AERATED LIQUID WASTE PROCESSED (GALLONS):
1.62E+04 UASTE LIQUID PROCESSED THROUGH BORON RECOVERY (GALLONS
____ AVERAGE PRIMARY _ LEAK _ RATE (GALLONS.
0.00E+00 PRIMARY TO SECONDARY LEAK RATE (GALLONS PER MINUTE):
ew
-M ee---h.
s w-ew_
- h**-
m e __
ww_
--.i-M w.--, emww-h.
UNIT SIIUTDOWNS AND P0WER REDUCTIONS DOCKET S0.
UNIT !.AME CONN. YANKEE DATE July 13, 19ji? _
COMPLETED BY Reactor Eng._ __
TELEP110NE (203) 267-2556 REPORT MONTil June 1982 tw b
c^
N O tC U C
. 0
.o M O Licensee
@e
$^a Cause & Corrective No*
Date E
NS
.O U
- Event M.@
&3 Action to
$5
$.5 $
Report #
$0
$U Prevent Recurrence U
Emg
)
o 82-07 820604 F
132.7 A
3 N/A HA GENERA Reactor & Turbine trip!
due to short circuit in exciter causing los ;
of exciter field.
Re-i paired short circuit &i verified all materialsi secured in exciter, i
I, LER 82-04/IP CD MSIV 1 Also, during this timej period the number 1 I
main steam trip isola-:
tion valve would not j
go closed when cooled 3 down.
Repaired and realigned tail link and retested valve.
i 1
2 3
4 F Forced Reason:
Method:
Exhibit C-Instructions P
S Scheduled A-Equipment Failure (Explain)
Il-Other(Explain) 1-Manual for Preparation of D.1:a B-Maintenance or. Test 2-Manual Scram Eatry Shects for Licensee C-Refueling 3-Automatic Scram.
Event Report (LER) File D-Regulatory Restriction 4-Other(Explain (NUREC-0161)
E-Operator Training & License Exam
- nation F-Administrative 5
G-Operational Error (Explain Exhibit 1 Sanc Source
i
(
(
(
4 G
G f
f C
O O
O 3
3
')
)
~)
)
4
[
4 t
i
}
l l
l l
-i i
o na v.
i
- sc : :
t I
l 1
,c..
i
..r i
i oi
-- r.'
I.c
<r a
mm.
c, c.
,,e e
s.
o.,
c.
~.
r c.,.
c,.
~
.. ~.
r o.
p c.
e u
r
,n.
r.,
n e
~.,
~
oc. c.
c.
.:e.
s t
r c.
u o
2 o et N
P.
CD i
3....
t -*. <>
j
(
w ' 33
'e')
I
~
1 a
8 l
8 I
e l
1 s
i l
I
+
l 4
i L
1 t
l t
f i
6 I
{
l i
l l
e i
+
1 La
~!
9' C
O r,
r ti j
L7 :
t L~-
i =
t.=*
i l
Ol C
e
-l 6
ra.
+.
a.
-s Ce s
L e..
i, C
i g
j a.
&4 8
u t
e- ;
1 F-I l
F I
h 3
R l
Q M
. h s
f i
i i
6 6
b r.
=
L.
l t
4 k
s r --
e if-
, is Q kk v4. c... s, u
r 4 :
.~.y
- b1 i
,,i e.
l
. L6 s
c to s
d ee e,..
.p.
t.-
r-e e
.a rb=
~
F r-P as a
.'s J
I s
e.
d
[
g et e,.
. (ed a t
e s
(-
- e. ~ P. i e a.
. La i
e ;.
p
. r.
.Ie e *
. ft 5..
I s
. r.
7-(i
- 4!
1 j
f s
1 s
3 e
+ #a F-a i,g j
- h-e, l
j
.e h.
s t
L'*
Z., ', _
.u l
u e
[.L-
. e, h.k.
~ ;-
l e
p 1 -
1.
..W
-I a.-.
i
.-n'.
n C
w g
t e.a.
L a uks.
.- L a e
- 1 ra j. '
s.O D
... i
.4>--
.E t,. Q 1
I.i k--
t
.e e
et Lt J
'AD-f.
e o
LJ 7
(1 E
ea
,, ' C8.
si
. c a. i F-
..)
La ;-
r--
p q
J
- l. s ee tal hp (I (4^
s.'s n
- f Z
a;E o
.- 3 y
o r ue >-
i o
2 a
w
,w C l t-1 I
O.
be 4.;)
r-.
4 s_s
- . La 4.e b*
Cs b6 La F ?
Q a.
- e-
&.. *H 14 i
a.1
- P L.*,.
C' 4
3-O rif w
e i
.,I
/ 6 1
- - t
.E t e%
s.-
e e e_i >
_. ; I L'i t ';
-4.J' If ts.e, O a
_3 J
e e a.
e.e e' - 7 s1 m.-
U s.e 1
- 4 el s t.
t si --,
'. {
u y
c w
x o
a c.
y cc u
.- c..
> ig n.
.. c. 4 i_. e -
!J 4.
1 L
w w
ij 7
je,
A...
3 a
.o s.-.... j
.7 e
4 t
u._
t
-...e'-
s
- G. G.
".e u
Ca n
_a la
,, +
Ls..
t ut st
-W. %..
6 s.<.
0 1
u I
<r 6.-
u m u Zs k:
s s--
a L.
1 C.
c.
u.
.r u
o, a.
in--
w
.I 4 -.-7
? v C
4 h
e-
.2 a
- o. V.,
e m4 Le.
bl O u
b.
L-e2 t.:
t ay c; F
12
!*!7 o
l*
tha ba s..I e
't 4.
o f.
e,_.,'..us
- c. a
_.a
-7 e
u u
u o
o g
r 6
a Le uj w i
Li-..us iA p (C Le e s_*
a aw ea ** 6 Li e*
C1_
s't 1
e.
v
'.t L.;
j
)
}
-u, :. 6 i' #. i i' ' I,
- i. b 5
E.
d 1 9 '.'
- d. i
".T.
'7 n'
a.s F-s 3-. u -r
' 1 7
-.e I
e
-i n
m v
F-si i
-..._. u. - u 2
2 a
2 v
_ i 7
us.,* G, k_.
..s.s*'
l
-s
\\
)
i,
~
b, s, ;a,.,
I W-c i
j.
l^.
l a r - fa O-6
)
l c.
c.
O.
=,.
h---*
6 V
._++
r e
ee c
t,-
r
++
. e a r<g *t h -
_. _ _ _.]
u.1 l
(
(
I I
(
t t
O il O
O O
9
)
')
)
)
}
}
I f
(
(
(
(
(
(
(
(
L O
O O
O O
O 3
3 3
1
)
i r
t I
t t'
,i l
i f
I i
i f
4
.,o e-
=
o j
4...
e e
+
4
/e
.l l
e 6,>
e l
e:.
44
+
f 4 si.. e LtJ e
e > a f
l ei e
F-6 0
F-e
<T o
e
'4 e
ap e
s.
I e
=
n s e rp.
f>
6, e
e e
'l l
e r a o
_.y l
(>
r Wo en f**
t-p.
f>
- 1. et I
g, e
's.
- ,(J
,,r-e-
e >..
e 4
p.--
te.
re -
ren g,
!r, i,.
ra. Gh >
t t
e 3 o
(*
e fa P.
e, to p.
to e 1ii cf e' laI t
Vi
=a M'
(
(f 44 f)
(')
,-d*
F4 f
. %"y r'-'
v.'
C. -
e.,'a' & 4 e; c-l
~
(a
't f'
04 g
.g r
~
a*
- ,4 i tL eJ
)
e 3Q ' ei E. 4 e
(T '
u-o P-Ca; I
e e eI
- N, ti s.
l' e:
+ s i
- 'a4 i.
o
+
e;e L-u, 1
-)
e L8 I
1 t
}
1 I
f i
3 j
t 1
L 4
l l
1 l
8 e
l.
La s t
7 C
7 i*g P
P
/
(,
-"e I
g g.,
i
/
F.
L^
O' qe.
f
f t
t-t.
et C
f
- L. -,-
vs
+
l F
(,
f-(
i eJ 43 t-i(.
f et ft'
,a FJ a
p a
t 0
I l
I 4
4 f
I g
l 4
f i
e t
b E e h
e i
6,
e la 6
f a
2 L
'4 6
F-r FJ f,t bo
. f
(,
, r.. L-a -.
4 e-
.L**
Le s,
g e t.a 1.
- ya a
y
(.
e,
- f P
f" '
. La 5 T
Ce C.,
P.
t.
y.
t F.e v
~e o to
=a A
Ci l
(*'s j
C, og t.
(.,
6 se be tr s' t (41
++
(s'
, e e
.1 ba e
aj Z.
P j P~
be G. i
-r t
es I..
er a
e rs
.d r a.
ist e
(-
i.
.r.
.-.u ee; 3
v eea.
- e. l 6
- I e 44
.+.
.j.p 1
t s
a t t
i..
.&4 6
e.
+.
.s.2
+
i s
I
-
"e
(:
't is (a
p-e tsi 3 C3 &**.5 he s1 Q-
~
ta t et
-3 -}.-
'y
- Lat tim e ~ 44 4
-d"4 7 i
ja>
Cfs
Z rm.-.e-.
4 i
....4e>.(t-..*o-*
s.,';
4 t
a
- j Lr la M
F-tr4' 3
us
,o o
s,.-
t v,.
y u
-o.
e 2
e L
it l-
. 3 3 t a..a ls.)
ea s e it' u
a J
E
.e--
Q' s_.
Ib n G
. ~
el leT
. * - (g in pl
,64 7.
N t
u C
,f O
i g.'
C.L L.',
1 6 e L.J f'.'f.
s.*
Q 2
a*
( 's L.4 4 :
. us t
se a)>, = f 'I. e-.
e--
u (f.
L.c is
,f D.J
(.-
si.
(.>
e i
+
C p.
L.
7
. '.4
- c: -
!?
er u,
.t
,.i ;
f L.
& i -
b--
o
~_ i I
e 6 L
e si l:: -
u o
v v.
s, a :u F
T s.
- .f-.3**
- 4 i
- c. e r 'i.
af.
- 6. Os a u b
e-m-
(,,D eT i
b.;
h' t > I E
(g t
c e-L. -
[' a.
o'S
[W T.p,**,.
. i, E
- i P--
c..,
tU 41
.'s' U #. y
- r.,
s v.;
,;L t-6 It' t:
s, '
C.4 T'
u.
L'
_a f.
ict b e
s.
'L.1 C, i,4 Le, ic
/
L4J.
h-'
La s e --
is f4 l
F y
J 4,.3 e'
-Y
&2
(.
L.
k C.
L.I 3La4 (O
+t9 Q
- a=
O s
Les h
L-L6l ieI
<T I
4..=
$44 L'
6*b
- _f. -If s LI 6
l*.
sg.
_s e
L-La i i.
. [i'
- i.,. 7 Q> C -
.;s we t
j
+
<I i
L; e-l--
r.< a i.-
ly s.a.s L.
..n e*
6 6..
(e Q
e--
(
p l_'-
C; 6,
+ T. 2 1
- se
=
, + 2 c
c, m
m,.._,
., o z
a.
w
~
L
.s.
v 3
2 p'r j
s
,.g _ a. L,.,.
I.-e w..
7 I....
..a..,
- .c.
.' g
. 1 g,g
'p L t
j 1
s t
,. j. -.._, ; -
,)
t-e i
e t
. t.,.
.i t.
w n.
1 s
~.
--.h e
.,q,,,.,
- .,-,o, f,,,
o we
(
(
t-(
(
4 4
6 6
e 8
0 0
0 0
3 3
3
)
J
)
I
REFUE1.11:0 It:FORMATIOM REOUEST_
~r D
/
1..
Name of facility Connecticut Yankee Atomic Power Company Scheduled date for next refueling shutdown.
2.
Late January l'983 Scheduled date for restart following refueling.
3.
t I
Mid March 1983 Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
4.
(a)
No technical specifications changes are anticipated at this time.
If answer is yes, what,,in general, will these be?
(b'),
N/A If answe'r is no, has the reload fuel design and core configuration
' your Plant Safety Review Committee to determine (c) been reviewed by whether any'unrcviewed safety questions are associated with the
. core reload (Ref. 10 CFR Section 50.59)?
When documents are received f rom the vendor they are reviewed in accordance
,s Y with 10CFR 50.59 to determine if unreviewed safdty questions are core reload scheduled?
'M cged such review has taken place, when is it N/A Scheduled date(s) for submitting proposed licensing action and S.
cupporting information.
'There are no scheduled dates because of (4) above.
Itnportant licensing considerations associated with refueling, f 6.
c.g., new or differentor performance analysis methods, significant cha l
new operating procedures.
r NONE (a) in the core and (b) in the Tle number of fuel assemblics 7.
spent fuel storage pool.
~~
(B) 441 (A) 157 licensed spent fuci pool storage capacity and the size d of any increase in licensed storage capacity that has been requeste The present 8.
or in planned, in number of fuel assemblics.
l pJ The projected date of the last refueling that can be discharged 1168 licensed capacity.
t-9.
fuel pool assuming the prer.cnt I
to the spent l
s L
1994 to 1995 l
\\
/
'<0s
/
E N- ~
d
,