ML20235Z643
| ML20235Z643 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 09/30/1987 |
| From: | Miller D, Wall K CONNECTICUT YANKEE ATOMIC POWER CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8710210238 | |
| Download: ML20235Z643 (10) | |
Text
_
, (: ;
[( }
i~,
!y t
i 3
s
/
4 y
,e ;
,., j;,
1 cf
'/c
.I ' '
- -1' ur.n,.
5 e
l
' AVER GE DAILY UNIT POWER LEVEL-i,
{
fl f
~'il DOCKET No.
50-213 i
~!I
'/.
Conn. YackeA ~
't UNIT Haddam Neck!
.m s
ll; October 15, 198'7~
DATE L
COMPLETED BY K. C. Wal1 n
'g TELEPHONE (203) 267-2556
-MONTH:
SEPTEMBER 1987 j l; DAY AVERAGE DAILY POWER' LEVEL DAY AVERAGE DAILY POWER LEVEL i
s (MWe-Net)
(MWe-Net)
'l 1-0 17 0
.i
'2 0-M' 0
3 0
'19 0
I 4'
0 20 O'
5.
0
~21 O!
,,, o 6-0" 22 0
'^
7 0
23 0
'.l.
8 0
24 0
9 0
25 0
10 0
26 0
l 11 0
27 0
r, 12 0
28 0
13 0
29 0
i 14 0
30 0
'15.
0 31 n/a 0
16 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.
p 8710210238 870930
)\\y PDR ADOCK 050002131 R
- PDR, (9/77)
w 9.,., 6 ws. a.@y. 6.nwe~-.-e
.w.2:,.
.; s w.;
,.n+m..-,
u ~ i., a -
u.-a
. 4.~. - -
e I$
)]&p%
E i
t'
.- [_6, t
k" b
n;},. &ld J
,e 3
)
CONNECTICUT YANKEE F
r REACTOR COOLANT DATA
@t..</H MONTH: SEPTEMBER 1987-u e
- Kn: y 4., y y')
W'
-1 1
e R
- jg.. n
' REACTOR COOL-ANT ANALYSIS -
MINIMUM AVERAGE-M AXIMUM W
.PH e 25 DEGREES C' 4.54E+00
- 4.70E+00 4.92 E+ 00 ~
CONDUCTIVITY -(UNHOS/CH)-
6.40E+00 8.88E+00 1.04E+ 01 CHLORIDES '(PPM)
<5.00E-02.
< 5.00E-02
. < 5,00E-02
' DISSOLVED OXVGEN (PPB) 2.10E+ 03 2.40E+03 3.20E+03
-100RON (PPM) 2.46 E+03
- 2.57E+03
- 2.66 E+03
,,*4 yJ LfTHlUM. (PPM) 0.00E+00 0.00E+ 00 0.00 E+ 00
' ~ TOTAL GAMMA ~ ACT. '(UC/ML)
' 2.68E-04 '
1.83E-03 2.83E-03 r
10DINEh 31 ACT. '(UC/ML)-
0.00E+00 0.00E+ 00 0.00 E+ 00
' l-131' / l-133 RATIO '
O.00E+00 0.00E+00 0.00 E+ 00 t-CRUD JMG/ LITER) 0.00E+ 00 0.00E+ 00 0.00E+00 TRI'i IUN (UC/ML) -
2.97E-02 3.52E-02 4.37E-02
-HYDROGEN (CC/KG) 0.00E+ 00 0.00E+00 0.00E+ 00 ya jf,,
.g WOh AER ATED Ll0VID WASTE PROCESSED'(GALLONS):
1.88 E+ 05 WASTE LIQUID PROCESSED THROUGH BORON RECOVERY (GALLONS): 2.52E+04 f/
AVERAGE PRIM ARY LEAK RATE (GALLONS PER MINUTE):
0.00E+01
' PRIMARY TO SECONDARY LEAK RATE (GALLONS PER MINUTE):
0.00 E+ 00
'l',
\\
.[.'
j{l' 1.
t Y,
[( (
m S'
y.j f f I
/ ;
.g q
q l
, [#QW ; :f
-._3 i
l
.o NRQ Oparatiog Ststun RGport 9
+..
v.
a 7
y; y,ge,,,
yggy j'
'e A
J
- 1. ' Docket: 50413 L
- 2. Reporting Period! 08/87 Outage t On-line Hours: 720.0 + 0.0 = 720.0.
3.UtilityContacts}) Stanford (203)26)-2556 ext.452-
- 4. Licensed theraat Pwe.F(MWt): 1825 5.NaseplateRatinjABrossMWe): 667 x 0.9 = 1600.3 I
- 6. Design Elecitical Rating (Net MWe): 582-
- 7. Maximus Dephh41e Capacity (Gross MWe): 595.8 9:
- 8. Maximus Dependable Capacity (Net M4e): SA9
?
9/ If Lt.anges occur above since hst report, reasons are: NONE
'10. Power level to which restricted, if a:q (Net MWe): N/A'
- 11. Reasons for restriction,.if any: N/A MONTH YEAR-TO-DATE CUMULA71VE
- 12. Report period hours:
720.0 6,551.0 173,111.0 s
- 13. Hours reactor critical:
0.0 4,728.9 146,189.0 14.geactorreserveshutdownhours:
0.0 0.0 1,285.0
- 15. Hours generator on-lines 0.0 4,700.2
-140,187.9
- 16. Unit reserve shutdown hourst- \\
0.0 0.0 398.0
- 17. Gross theraal energy euersted,JMWtH):
0.0 0,389,543.0 242,770,004.0 t.
al
- 18. Grosc electrical nergy generatef9MWeH;f 0.0
.2,667,885.0 79,480,807.0 t lb A Net electrical entq(generated (MWeH)'s
-2,428.3 2,533,692.9 75,565,181.0 t 1
,e
& A ft stivita d actors 0.0 71.7 81.0 J;
- 21. Unit availaMilty f& tor
- 0. 0.
71.7 81.2
/
1,
)
- x
'd. Unit' capacity f actoihsing MDC net 0.0 68.0 79.8 p
- 23. Unit capacity f actor ut.ing PER /tl 0.0 66.5 75.0
- 24. br t forced outage rate:
E 0.0 6.0 4 fr,rced catage hours:
0.0 54.4 8,975.6 a
j $
s i
l.
/ p$
j.
- 26. Shutdowns scheduled over next 6 Panths (type,date, duration): NONE f
,/
2/ If currenti phutdown, Mtinated dortup date: 11/06/87 (y.
ii e
i Cuaulative va:ites f:a'a the first criticality (07/24/6L (T4 remaining cumulative values are from the first date of ceasercial operation, 01/01/68).
/(
- nt 3
i n
e I at r1 0oc b t
e fu
- reo6 Z
c r
of G a e p1 5TO e
r
- e ph e0
'e E E r~-
u nR t e S_R u:
oMT E
roc o
i r NAA ot e i5 bP ytE ND R
t1 i
rnR ET ~
C 'n h rt eU a -
T
&iot u4 xonvN
~
n n1
~ E f E. E KI CN et e i
4 OU scv t e D
uAe nr aJ r oo C
P CC m
ar mci aS a
^
r-x c cp
'e8o tE x
S i x ll a(
ME$$O l
e aa m
u d uu oe F
onn th h aa ut tMM AO e - -
M1 2 34 3
S EO
!SN NO 4
~
CR I
TC U
7 D
8 E
9 n
R 1
R T a
i E P
/
L R n
a R
R l
E E
p W
B gyg" x
O M
M-.
E P
E ha
(
T f
r
& j 3'%
e D
P o
1 i
t N
E h
'A S
_'O o. jjf ji t
O S
N H
W H
O T
$EO D
N N
l T
O C
U M
H
)
S T
R n
i T
O a
I P
l N
E U
R 9$E" p
0 x
bUE5 2
E 7
( t s ee rT u
l r i o eS*
a F e 5
c t ngr nanort enit o mel at pt el a ninuurir ouif geme 7
sqaeepd p e
8 aEMRROA t
e - - -
a 1
RABCDEF D
9 2
de l
d u ed 3
ce o
0 rh oc N
FS 7
8 FS 1
1 1
l li
' REFUELING INFORMATION REQUEST 1..
Name of facility-Connecticut Yankee Atomic. Power Company 2.
Scheduled date for next refueling shutdown.
Began'present refueling outage July 18,'1987
-3.
, Scheduled date for restart following refueling.
l L
November 18, 1987 (first day at full power) 4.
(a) Will refueling or resumption of operation thereafter require a technical speci-f1 cation change or other license amendment?
YES' (b): If answer is yes, what, in general, will these be?
Technical Specifications related-to revised physics reload methodology and transient analyses design basis.
(c). If answer is no, has'the reload fuel design cud 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)?
Not applicable.
(d). If no such.. review has taken p1' ace, wh'en is it scheduled?
Not applicable.
I 5.
Scheduled date(s) for submitting proposed licensing action and supporting information.
Submitted 6/1/o?
j 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.
f N0 7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool.
(a) 0' (b) 810 1
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 l
i 9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.
1996 l
J
CONNECTICUT YANKEE ATO MIC POWER COMPANY f
l HADDAM NECK PLANT l'
RR#1
- BOX 127E
- EAST HAMPTON, CONN. 06424 i
October 15, 1987 RE: Technical Specification 6.9.1d Docket No. 50-213 to en U.S.belcarRegulatoryCommission Dopme::s Control Desk Wan61ngon,D.C.20555 m
DeO S 1E In accordance with reporting requirements of Technical Specification 6.9.1d, the Connecticut Yankee Haddam Neck Plant Monthly Operating Report 87-09, covering operations for the period September-1, 1987 to September 30, 1987, is hereby forwarded.
Very truly yours, I
S Donaldf. Miller,Jr.
Station Superintendent DBM/mdw Enclosures cc:
(1) Regional Administrator, Region 1 U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 (1)
T. Shedlowsky Sr. Resident Inspector Connecticut Yankee I
'>'ei\\
.n CONNECTICUT YANKEE ATOMIC' POWER COMPANY l,
HADDAM NECK PLANT l
.HADDAM, CONNECTICUT i
I f'
l I
i MONTHLY OPERATING REPORT No. 87-09 FOR THE MONTH OF SEPTEMBER 1987
-______________a
s i
P_LANT OPERATIONS SUMHARY-- SEPTEMBER 1987-The following is a summary of plant operations for September 1987.
The 14th refueling and maintenance outage continued for the month of September.
.q
)
,4 i
l l
l
NAOU
- EG NRN E: I KRR TFD b
~-
NOT IN TE CVN AEO RI EPT V
I IOT TTE C
P ENE RER RK OA -
.. ~
N O
" - ET I
.PO kt TLU SE
- R S N L OI OR T T C N N O U C FL
& AM TN 7 E E 8 S f}
9 U U
1 A R
C T T S P M E I S
-sf
~-
T mo N
e 7
I E
ot h8 D
N nE t 9 I RO n1 S' OP eeo I
Y - T ab e
rl err S
- C aeb et h m rrt e eo t
h prp Teoe
. rfS g
!t d
P i
e 5i}11 1I
?
KITA EG uNRN fgE I
gKRR AOU
@TFD g
(
l Nc OT
,I N TE CVN AEO
- RI EPT V
I k
I OT TTE C[ P ENE R E I'
RK~
OA C_ T J
~
NO T
I C
.ET ENFA FOAR F
.SE E
l P
l O
T 7
L 8
U 9
S 1
E R
TPN E O S IT
~ C NUJ IA
~ M EC E
N S
A U
N A
E C
-.TN
,I A
M W
D ro f
. s T
m N
e 7
M E
t - 8 E
N oif9 TRO n
o1 SOP e
Y M
elh r S
O rbt e C
aanb
' - t om erme r o'e p t
ep h ehe T rtS d
I}tl 4
5$
i i.
1 j,
s i ; Ai1i
{'i.
l