ML19351D754
| ML19351D754 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 05/05/1976 |
| From: | French J YANKEE ATOMIC ELECTRIC CO. |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| WYR-76-53, NUDOCS 8011170926 | |
| Download: ML19351D754 (8) | |
Text
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YANKEE ATOMIC ELECTRIC COMPANY 20 Turnpike Road Westborough, Massachusetts 01581
.YAuxsi m _.
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May 5, 1976 O-a+
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_9 United States nuclear Regulatory Commission
,D Washington, D. C.
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Attention: Office of Nuclear Reactor Regulation O
References (a) License No. DPR-3 (Docket No. 50-29)
(b)
Letter J. L. French, Yankee Atomic, to
. 's
/[W' 4h NRC dated April 27, 1976.
Dear Sirs d.
sy 6 87.67 2 The attachment is a revision to Reference (b) concerning t 1 heat load of the spent fuel pool at Yankee Rowe. The revision
,,,a w indicates that 14 days of decay time instead of 10 days is requi e.
o*** **
before unloading a full core in the theoretical " worst case" anal A
Mb e
It is Yankee's intent to conduct an analysis of the required decay time before discharging a full core since we believe that significantly less than fourteen days would be required in an actual situation.
We trust you will find this information satisfactory; however, should you desire additional information, please contact us.
Very truly yours, YANKEE A'IOMIC ELECTRIC COMPANY J. L. French Manager of Operations TMC/kg Attachment 0.F %
8011170 M[
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YANKEE ROWE
^"
-3 DECAY HGT RATES FOR 30 DAY CORE WITH 14 DAYS DECAY Coverming Equations
- a 1)
P (t
.Ek) ( P (m, t,)) -
P (m t,+t,)
P, P,
P, 11 2)
_P
(=,t,) =
1, 2
A exp(-a t )
n s P
200 n=1 o-
't Where:
t, = cumulative operating time t, = time after shutdown P = ratio of reactor power (P )
o P,
full core = 76 assemblies c
CASE 1 CASE 2 40 assemblies 36 as'semblies 2 yr operation 30 days operation 14 days decay 14 days decay 7
6 t, = 6.3072 x 10 seconds t, = 2.5920 x 10 seconds 0
6 t = 1.2096 x 10 seconds t = 1.2096 x 10 seconds a
s
.1 K
=
1 P = 618 mwt o
v
~-
(
(
YANKEE ROWE DECAY HEAT RATES CASE 3 t = 1.2090 x 10 t = 6.4282 x 10 1
2
-a t l
t
~*n i
Ae -a tni
-a t2 Ae n2 n
A a
e n
e l:
n n
n n
~
~
~
1
.5980 1.772x10 (10 (10 (10 (10
-1
-99
-99
-99
-99 2
1.650 5.774x10 (10
( 10 (10 (10 3
3.100 6.743x10 (10 (10
( 10 (10 l'
-2
-99
_99
-99
-99
-3
-99
-99
-99
. -99 4
3.870 6.214x10 (10 (10 (10 (10
-4
-99
-99
-99
-99 5
2.330 4.739x10
( 10 (10 (10 (10
-5
-26
-26
-99
-99l l
6 1.290 4.810x10 5.3949x10 6.9594x10 (10
( 10
-6
-3
-4
-99
-99 7
.4620 5.344x10 1.5584x10 7.1998d0 (10 (10 8
.3280 5.716x10 5.0087x10 1.6429x10" 1.1027x10 3.6169x10"
-7
-1
-1
-3
-4 I
9
.1700 1.036x10 8.8222x10 1.4998x10 1.2816x10 2.1788x10
-8
-1 9
-1 9
10
.0865 2.959x10 9.6484x10 8.3459x10 1.4925x10 1.2910x10 '
~
~1
~
11
.1140 7.585x10 9.9908x10" 1.1390x10" 9.5241x10 1.0857x10 4
-1 2Ae 5.1235x10 1.2170x1'0".
v
(-
YANKEE ROWE DECAY HEAT RATES CASE 2 6
6 t = 1.2096 x 10 t = 3.8016 x 10 1
2 l
-a tni
-a tnt
,-a tn2 n2'
-* t n
A a
e Ae Ae n
n n
n l
0
-99
-99
-99
-99 1
.5980 1.772x10
( 10 (10
( 10 (10
-1
-99
-99
-99
-99 l
2-1.650 5.774x10 (10 (10 (10 (10
-2
-99
-99
-99
-99 3
3.100 6.743x10 (10
( 10
( 10
( 10
-3
-99
-99
-99
-99 l
4 3.870 6.214x10 (10
( 10 (10 (10 l
l
-4
. -99
-99
-99 l
5 2.330 4.739x10 (10 99
( 10 (10 (10
-6 6
1.290 4.810x10 5.3949x10 6.9594x10~
-0
~
3.8568x10 4.9753x10'
-6
-3
-4
-4 7
.4620 5.344x10 1.5584x10 7.1998x10 1.5031x10 6.9442x10 1
-7
-1
-1
-1
-3 8
-.3280 5.716x10 5.0087x10 1.6429x10 1.1384x10 3.7338x10
-7
-1
-1
-1
-g 9
.1700 1.036x10 8.8222x10 1.4998x10 6.7446x10 1.1466x10
-8
-1
-2
-1
-8 10
.0865 2.95sx10 9.6484x10 8.3459x10 8.9361x10 7.7297x10
-10
-1
-1
-1 11
.1140 7.585x10 9.9908x10 1.1390x10 9.9712x10 1.1367x10 '
-a t
-1 n
-3 2Ae 5.1235x10-3.4297x10 n
m-YANKEE R0WE' DECAY HEAT RATES '
CASE 1
~
P (m,14 days) = 1 5.1235x10-1
. 2.5618 x 10 P
200
~
~
P
(=,2 yrs +14 days) = 1 1.2170 x 10
= 6.0850 x 10 P
-200 o
P (2 yrs,14 days) = 1.1(2.5618x10-3) - 6.0850x10" = 2.2095 x 10
~
P
~
P = 1.2095 x 10 x 618 x 10
= 1.3655 x 10 Decay Heat Rate 1.3655 x 10 x '3.4129 x 40,= 2.4527 x 10 BTU /hr 76 CASE 2
-3 P ( m,14 days) = 2.5618 x 10
.p o
-l'
-3 P
( =.30 days +1'4 days) = 1 3.4297 x 10
= 1.7149 x 10 P
200 o
P (30 days,14 days) = 1.1 (2.5618 x 10~
-3
) - 1.7149 x 10 P-
_3 0
= 1.1031 x 10
-3 6
P = 1.1031 x 10 x 618 >.10
= 6.8170 x 10 s
(
s..
Decay
- Heat Rate i
5
'6-6.8170 x 10 x 3.4129 x 36, = 1.1021 x 10 76 Total Decay Heat Rate Case 1 40 assemblies 6
'l 2 yr operation 2.4527 x 10 14 days decay 1
e Case 2 36 assemblies 6
30 day operation 1.1021 x 10 14 days decay 3.5548 x 10 BTU /h ~
t e
i 4
l 9
4 f.
~
_[
. f.
s
, YANKEE ROWE TOTAL DECAY llEAT INPUT TO SPENT FUEL POOL (30 Day Operating Core + Fuel Stored to Date)~
-30 Day Remaining Total Refueling Operating.
-Fuel Heat Number Core BTU /hr Stored BTU /hr Input 6
6 6
1 3.55 x 10
.86 x 10 4.41 x 10 6
6 6
2-3.55 x 10
.99 x 10 4.54 x 10 6
6 6
3 3.55 x 10 1.17 x 10 4.72 x 10
~
6 6
6 4
3.55 x 10 1.17 x 10 4.72 x 10 6
6 6
5 3.55 x 10-1.32 x 10 4.87 x 10 6
6 6
6 3.55 x 10 1.30 x 10 4.85 x 10 6
-6 6
7 3.55 x 10 1.45 x 10 5.00 x 10 6
6 6
8 3.55 x 30 1.43 x 10 4.98 x 10 Therefore Design Heat Load = Total Heat Input 5.0 x 10 BTU /hr = 5.0 x 10 BTU /hr i
9 e
s 1.
iRC ernu 195 u.s. hucLtAR RE utATcRY cc. MISSION DOCKET NUM ZE R I) t>7e
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50-29 ll N8D. DISTRIBUTION ran 5 ART 50 DOCKET MATERIAL T.;;
NRC FROM: Yankee Atomid Elec. Co.
DATE OF DOCUME.NT Westboroughi Mass. 01581 5-5-76
,_ N J.L. French oATE REcEivEo 5-7-76 Uf.ETTEn ONOTORIZED PROP lNPUT FORM NUMBER OF COPIES RECEIVED DORIGIN AL DDNCLASSIFIED Ocoev 3 signed 37 CC
- s DE7CR:PTION Ltr re their 4-27-76 submittal...tran 3 ENCLOSU RE Revision to Yankee Rowe " Decay Heat the following:
Rat.e's for 30-Day Core dith 14-Days! Decay"...
~1 (40 cys enc 1 re,c'd).
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s
~
~
PLANT NAME:
YAEC 1
SAFETY FOR ACTION /INFORMATION ENVIRO UHL 3-10-/O
~
i ASSIGNED AD ;
,d ASSIGNED AD :
j BRANCH CHIEF :
fis I Fust.po.e BRANCH CHIEF :
gg PROJECT MANAGER:
B g g,g g &
PROJECT MANAGER ;
Jg LIC. ASST. :
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INTERNAL DISTRIBUTION t(" REG FILD SYSTEMS SAFETY PT AMT MYSTEMS vmrTon Trr'tt
!V NRC PDR.
H7TNEMAN TFnF sr'n ERNST 1V I&E{%)
SennoRnEn BENAROYA BALLARD OELD LAINAS SPANCLER
- F COSSICK & STAFF ENGINEERING IPPOLITO MIPC MAcaAny SITE TECH CASE KNIGHT OPERATING REACTORS GAMMILL HANAUER SIHWEIL STELLO STEPP MARLESS PAWLICKI HUIRAN OPERATING TECH PROJECT MANAGEMENT REACTOR SAFETY W
EISENHUT SITE ANALYSIS BOYD ROSS
- SHAO VOLLMER 1
~
P. COLLINS NOVAK V BAER BUNCH HOUSTON ROSZTOCZY p SCHWENCER
- J. COLI. INS PETERSON CHECK V GRIMES KLEGER MELTZ HELTEMES AT & I-SITE SAFETY & ENVIRC L
SKOVHOLT SALTZMAN ANALYSIS i_
RITIBERG DENTON & MULLER I
_ EXTERNAL DISTRIBUTION CONTROL NUMBER LPDR:CrKFFn/PifL G M TI ) B BR00KilAVEN NAE LAB
- W8$
~
ASLB COESULTANTS JL___AcaS /.'.
' set T_
.ncFORM 195 (2-78)