ML19319E041
| ML19319E041 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 04/08/1976 |
| From: | Mattimoe J SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | Reid R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8003310508 | |
| Download: ML19319E041 (8) | |
Text
_ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
NRC,$Ru t95 U.S. NUCLIC AR REGULATORY CO*
- SION DOCKET PELMBER l
(2 76)
DD=$
NRC DISTRIBUTION FOR PART 50 DOCKET MATERIAL
.c TO:
FROM: SMUD DATE OF DOCUMENT A
MR R W REID DATE RECEIVED J J MATTIMOE gg g
l LETTER O NOTOR IZE D PROP INPUT FORM NUMBER OF COPtES RECEIVED ORIGINAL UNC LASSIFIE D
$%4ngy CorY DESCRIPTION EN CLOSU RE LTR RE THETR PREVIOi!S SI'BMITTALS OF DEC 19/75 DETAILED 2D MODEL RAMCHO SECO SPENT FUEL MAR 5, 75/ AND MAR 30, 75............FIMN rack MITH TABLE 1 R\\ TION 0.F LIMITING LOADS COMMENTS OVER THE MODELING Uf 1 BY EDS NUCLEA" FOR STRUCTURAL ELEMENTS.
....IABLE 4.
14 FOR SESTMIC EVAL OF THE FUEL *'CY DESIGN...
r,Ost liniting 10 ads On welds..... TABLE 1.1 TR ANS THE FOLLONING..
SUMMARY
OF THE MOST LIMITING STRESS EVALUA-TIONS FOR RACK STRUCTURAL MEMBERS.........
y,_ :. :..
5ENVQ$
PLANT NAME:
AQdo O
i.I i
SAFETY FOR ACTION /INFORMATION ENVIRO t \\-\\Mt. W.lS_
ASSIGNED AD :
A ASSIGNED AD :
~ y BRANCH CHIEF :
(lo)
KElh BRANCH CHIEF :
PROJECT MANAGER:, ~(
PROJECT MANAGER :
_ X LIC. ASST. :
(} }
hgg,m LIC. ASST..
, l INTERNAL DISTRIBUTION lY N P" PT SYSTEMS SAFETY PLANT RYRTxi'4R PMUT40 T:'r'n l
X NFC PDR HETNEMAN TFnRRcn ERNST X
I&E SCHn0pngn BENAROYA BALLARD M
OELD LAINAS SPANGLER GOSSICK & STAFF ENGUIE_ERING IPPOLITO MIPC MACEARY SITE TECH CASE KNIGHT OPERATING REACTORS GAMMILL HANAUER SIIMEIL STELLO STEPP HARLESS PAULICKI HULMAN OPERATING TECH PROJECT MANAGEMENT REACTOR SAFETY N
EISENHUT SITE ANAI.YSIS BOYD ROSS N
SHA0 VOLIJER P. COLLINS NOVAK s
BAER BUNCH HOUSTON ROSZTOCZY N
SCIMENCER N
J. COLLINS PETERSON CHECK N
GRIMES KREGER MELTZ HELTEMES AT & I SITE SAFETY & EI;VIRC SKOVHOLT SALTZMAN ANALYSIS
~
"UTBERG DENTON & MifLLER EXTERNAL DISTRIBUTION CONTROL NUMBEF' M
LPDR;hAmtAio.M NATL LAB ~
BROOKHAVEN NATL LAB 400g Oy [
X TIC X
REG. V-IE ULRIKSON(ORNL)
LA NSlc LA PDR ASLB CONSULTANTS ACRS Ik N FEN10 un m
u
E'
^
0~=suu.
SACRAMENTO MUNICIPAL UTILITY DISTRICT O 6201 S Street, Box 15830, Sacramento California 95813; (916) 452-3211
^
April 8,1976 b$i!!2lCp>' L...
4@US,,,
~
~
Director of Nuclear Reactor Regulation e'Y b
Attention: Mr. Robert W. Reid, Chief 7
Operating Reactors, Branch 4 f"f
)%g$
< gn i N !
n U. S. Nuclear Regulatory Conmission V
,p
^y ggygg.
q gg Wash ington, D. C.
20555 k
Docket No. 50-312 Rancho Seco Nuclear Generati Q h j.f(J hW 1 O~
E-!
Station, Unit No. 1
Dear Mr. Reid:
N ~.
This letter is in response to concerns which have been expressed..
during telephone conversations between the NRC staff and District personnel regarding the District's submittals of December 19, 1975, March 5, 1976, and March 30, 1976' for increased fuel storage at the Rancho Seco Nuclear Gener-ating Station, Unit No.1.
The first concern was over the modeling used by EDS Nuclear for the seismic evaluation of the fuel rack design.
In this analysis, the fuel guides were lumped together to simplify the three dimensional calcula-tions. Additional calculations have now been performed as shown in Figure 1 and Figure 2 attached. These two dimensional calculations included the second antisymmetric mode of vibration.
The results of these calculations are shown in Table 1.
Although these results indicate that fuel guide connection end moments are greater than originally calculated, the three dimensional model used in the original analysis correctly represents general rack behavior.
The results of the original three dimensional analysis have been scaled using the linear factors identified in Table 1 in accordance with our discussions with the NRC staff. These modified results have been reevaluated as shown on Tables 1.1 and 4.14 from the original EDS seismic report,also attached.
It is therefore concluded that the racks are still well within acceptable stress limits.
A second item which was discussed during telephone conversations was a concern over the structural integrity of the racks assuming a fuel bundle drop incident. The fuel bundle drop incident has been evaluated to assure that a fuel bundle falling from the fuel handling height will not cause a condition of overstress in the attachment between the fuel storage cell and the fuel storage rack frame members.
3716 AN ELECTRIC SYSTEM S E RVIN G MORE THAN 600,000 IN THE HEART OF C A LI F 0 R N I A
~
Robert W. Reid April 8,1976 In the event a dropped fuel bundle strikes an empty ruei storage cell, the upper portion of the cell will undergo deformation limited to the upper 5" of the cell. The loads produced by this event will not result in a condition of overstress.
In the event the dropped fuel bundle strikes a stored fuel bundle, the bottom plate of the fuel cell will break away, protecting the attachment between the storage cell and the rack frame.
In summary, the calculations performed show that the guide tubes will not be deformed or break away in any manner which would increase the value of keff.
We feel the above addresses all of the con: erns expressed during recent telephone conversations. However, if we can provide any further information regarding our request for additional fuel storage, please advise.
Sincerely yours,
[. *, kbd
/J. J. Mattimoe Assistant General Manager and Chief Engineer Attachments
)
8
"=em WO
)0 iJ 0
0 h "' E T
5 b.il j " n[
mo G i.
b
_ Lj X)
\\'b 0
m C -}
o _o gx z )7 g 3
C V r lrI I
m b
O r
m b
o O
1-SEDIV4 LEUF 4 2
4 W
A nmvuoc e>raeb si 4
% U w
w A,,
h S.Za
- s
\\
/
l U
h[A s
f m0 m
ST%EMELE LEUF 4 s
o@
in 3
\\
/
/
9A b
S M u4 LEUF2 j
)
s n
/
N i
y on n
g n
t g
jg 31z e "
\\
/
y I
D9 STNEMELE LElbF 2 E s
/
m 3,g s
r.
e N,\\
9 on o
n
\\
/
k SE oivic teu p 2
\\'/
\\
ah X w
F m
_]_
h 3
_ny g
e----
F-r o e
z g
M/
h xf g 3U STNEM ELE LEUF '4
[
y k
/
g [
d g
SEDIU4 L.E/;F 2 q
j
\\
/
\\
7
-~
7_
w
/
3 5.TN EM[LE LEUF 2
\\
lU
/
g H
/
'\\
h j
/ SEpl04 LEUF 4 l
\\
m
/
+
s j
\\
j~
l s,'
/-
\\ H 7 5 J
$'6h 4PMVLoC EPIP 2*
STNEMELE LEUF 4 8R
,,A
,a
^
i v
'79 A.6
' 79 A.6
' A4.o g
u
'2iw d*3
"* '3 G " **
3XXON NO>T' 70 N p-3niul
,,,331 a riNpno sap c 5.da4r A d.0 3 7 re / P i>
5 W n o se w r one sa p O
) non N%D' ma sac uG (
ro uo.
I600020 9A l OVM l3W0- b9 loV13 MN Y l sH1*
tMW NO-os
8
\\
e e
neg 4 r
o 2
o.h
_ d
_A h
l eq-
- (
vc
.h 2 U l
y" QsEbg gim 5
d bk
$h p
p 7 g gI )y g O 7 m
m r
no 2
3 mm m
N_t j
mO h
SEDIV4 LGuF 8 4 n
s P
NMULoG EP1P \\
C
[
\\
V y
C hO m
,M A
-/
y v
z r
n e
x N
. ;y
/
3 l
N f
h f
3 M
ST4r:E LE LEUF 9 4
,/
D s
- 01 z
\\
gg g
9
,6 N ) s uae A, ro E
D m n
sen,octx o.4 N g
N g
f
)
f o
_\\_ _
l c.
/'4x P {--
5 y gn
- s. #
, c
\\
3T >
Ub 4
sr8tseLc Lcur 4 4 /
s r,,y p
/
N 1r k
/
\\
31U x
-c N
/
\\
01 E
d
/
g
/
\\
/
5eoive tsor9 4 N
/
f
\\,
~ : 7' JruvnocJe+i p
D
\\:
m A
STNEMELE LGuF 9. 4
- g,,
1 4
i d
y
-794 6
.t
'794 6
'144 0.l
.n yy, 31 9- ]
giW dh dI3IC Z T<
W9037 3XXON Hp?l * @' '.iit?*
dYN2HQ 5320 5dSUL dnS1 i2V ?tp 5Wl(G
- UV412HO 532 O u o,,,.,
7 d.OB NW d-SSdD9093(,
,09 no.
16000 26 9A bb lOV13 !!
l3W0" lOV13 OIO Y l swt-113W No-os
~
-q
)
TABLE 1 RATIO OF LIMITING LOADS FOR STRUCTURAL ELEMENTS RANCHO SECO SPENT FUEL RACKS Structural Ratio of Detailed Model/ Simplified Medel Element Type Shear Moment Axial Force Leveling Screws 0.77 0.97 Pipe Column
- 1. 0
- 1. 0 1.03 Fuel Guide 1.15 1.39 1.06 Tube Beam 1.43 0.97 1.03 Bracing 0.83
Location ~
Type hiost Limiting Type Afost Limiting Allowable rf Weld of Weld Load Combination of Stress Stress (psi) 1.imit (psi)
Fuel Guide 1/4" A D+L+E Shear
,5337 11,160 (Seam Welds) 613l '
Fuel Guide Brac-5/8" A D+L+E Shear p1f 11,160 ket to Tube Beam
%4605-
.)
Fuel Guide Brac-1/4" Q D+L+E Shear 5286' 11,160 ktt to Fuel Guide 10264 Pipe Column to 1/4" y
' D' + L + E Tensile 2910 16,740 Tube Beam Cross Brace to 1/8" -h D+L+E Shear 4744 11,160 Gusset Plate D+L+E Shear 8403 11,160
.Intertle to 1/4" y Tube Beam
\\
Cask Catcher 1/2" -
D + L + T + E' Shear 1840 17,920 Plate Attach-ment Leveling Design Not Screws Available h10ST Llh11 TING LOADS ON WELDS
- BASED ON Sc At E FACTOM TABLE 4.14 FROM TABLE d-
_r
- [ '
Most Limiting Structural -
Afost Limiting Combined Allowable hiember Load Combination Type of Stress Stress Ratio Limit
?
Tube Beams D+L+E Combined Axial 0.860
- 1. 0 and Bending Cross Braces D+L+E Axial 0.838 6
- 1. 0 Pipe Columns D.+ L + E Combined Axial 0.250
- 1. 0 and Bending
)
a Side Adjusting D + L + T + E' Axial 0.382
- 1. 6 g
Screws Rack Intertic D + L t-E Bending 0.675
- 1. 0 Fuel Guides D+L+E Combined Axial
<22 (,
- 1. 0 and Bending o.312 Fuel Guide D+L+E Combined Axial '
O._557'
- 1. O Attachment.
and Bending Bracket O'
Pool Walt D + L + T + E' Bearinc 0.396
- 1. 6
's, Bearing Levelmg Design Not Scr,ews
'Available i
TABLE 1.1 SUhth1ARY OF THE h!OST LIh11 TING STRESS EVALOATIONS FOR RACK STRUCTURAL MEh1BERS
- BASED ou SCALE F AcrR5
~
FRCM T'A b L2. i '
f