ML19261F002
| ML19261F002 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/16/1973 |
| From: | Schwencer A US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Grimes B US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 7910171054 | |
| Download: ML19261F002 (4) | |
Text
..
M
/
P 5
~
, j
- p,,
UNITED STATES
~ (
_ f
$N ATOMIC ENERGY COMMISSION
M+ f i
WASHINGTON, D.C. 20545
\\;
%ne DocketNo.[,50-289 FEB 1 6 573 5
B. Grimes, Chief, Accident Analysis Branch, Directorate of Licensing SUPPLEMENTARY TECHNICAL REVIEW: RADIOLOGICAL CONSEOUENCES OF FUEL CASK DROP Plant Name:
Three Mile Island, Unit 1 Licensing Stage:
OL Docket No.:
50-289 Licensing Branch:
FWR-4
. Project Manager:
H. J. Faulkner Review Branch:
Accident Analysis Branch Requested Co: pletion Date:
March 19, 1973 Your assistance is requested for the review of Part VII Supplement 2 to the Three Mile Island Unit'1 FSAR. A copy of this material is enclosed.
This information was supplied in response to an additional information request concerning the potential drop height of the fuel cask. The applicant states that assuming the escape of all gap noble gases and Iodine from the entire contents of the cask, the resulting boundary doses are within the limits specified in 10 CFR 100.
It is the applicants opinion that based on these accident doses, no facility changes are necessary to prevent dropping the cask through a distance greater than the design height of 30 feet.
You are requested to review the applicants analysis and dose figures for correctness and to advise me of your opinion concerning the need for facility modifications.
Such 1486 049 5
q910171
B. Grimes modifications are subject to the requirements of 10 CFR 50.109, Backfitting. As such it is the staff's responsibility to demonstrate that such modifications will provide substantial, additional protection required for the public health and safety.
A. Schwencer, Chief Pressurized Water Reactors Branch No. 4 Directorate of Licensing
Enclosure:
As Stated i
Rhonnie Smith cc:
DISTRIBUTION Docket File PWR-4 Reading RP Reading HJFaulkner ASchwencer RCDeYoung 1486 050
... PWR-4 l--
l l
PWR-4 i
...................l.......
,i cmcc >
..s i
suame > HJ.NIlkner1 mf__,ASchwe$cer k
om, i 21..L.S...D.3..
..l. 2 /.
/73
., {,.,
J Form AEC-3:a (Rev. 9 53) AECM 0240
- v. s. covramurm7 rna Taic orp z, sete o..ca.s.e
i
~
f
\\
Docket No. 50-289
/
!f i
\\
i
'\\
l
\\
i J. Hendria, Deputy Director for Tachei al Review, L
\\
TECHNICAL ASSISTANCE REQUEST: BADI CAL CONSEQUENCES OF FUEL CASE.DEOP Flant Name Three Mile Island, Unit 1 Licensing Stag OL Dockat No.:
50-289 Licensing Branch:
PWR-4 Project Managers N. J. y n11r=*r Enview Eranch:
Accident Analysis Branch Esquested Completion Dates Mardhh19, 1973 Your assistance is req / \\
uested.for the review of Part VII Supplement 2 to the Three Mila Twi==J Umi 1 FSA1. A copy of this material is maelamad.
This informatios was supplied in tysyonee to an additional information request --- --- 4=g the btential drop height of the fuel cask 4 The app 1fe==t statesNhat assumfag the escape l
of all say noble gases and Iodine fromM he entire contents of the cask, the resulting boundary doses ' e within the limits specified<in 10 CFR 100. It is the app to opinice tht based on/these accident doses, no facility M es are necessary to prevent dropping the cak through a distance greater than the design height of 30 fee,
\\
i
/
You,are requested to review the applicants smalys add dose figures for correctness and to advise me of your op ion l
eencerming the need for facility modifications. Such' i
l 1486 OSI I
I
I l
.T. Hendrie l l
modifications are subject to the requirements of 10 CFR 50.109, l
Backfitting. As such it is the staff's responsibilitv 'o c
demonstrate that such modifications will provide substantial, additional protection required for the public he11th and safety.
i t
t l
R. C. DeYoung, Assistant Director i
for Pressurized Water Reactors l
Directorate of Licensing i
Eneinsure:
DISTRIBUTION l
As Stated Docket File PWR-4 Reading cct RSBoyd RP Reading i
ICDeYoung HJFaulkner DIt:11er ASchwencer I
DSlovbolt f
EDenton liMcDonald INKleckar MResen i
FWR Branch Chiefs BGrimes
)ican-411 Esaith 1486 052 l
l l
I on :: >
..L:.C/F4R L__ RAD /P h..
sumw > 11y pe -. i f ASchwencer---RCDuYoung"-
DATE >
- 3.f.],?)....).7A.J. 2 f.
I??
1l......l13...
Form AEC-Ste (Rev. 9-53) AICM 0240 e u s c.cvem.we%v -va.o orect t 372-466 983
~
~
RL. v... PJ)H A:ht'D O.*.U.1:!OL:-??S'IO:s E.'tm)NL LTAIi.: BISON CO:WA:iY_
'i'lliiM., N ! :.i: i ; U.M o u.; l 'i'1 (Docket.N0. ')0-LV))
'D "
D o fit a T,,.6 n
n }m n, }
]
' V U, 'j ll f}
,' i / '
C. ~_o,, C..
uu au, u:
i..
It appears frc= Figure 9-18 of your FSAR that the maximus drop height for a fuel cask is L3 feet during transfer operations of a fuel cask onto a rail car. What nethods are provided to prevent dropping the cask through this
~
height. Provide the results of an analysis of this accident that includes the radiological consequences.
EESPC :SE 1.0 FUIL CASK DROP ACCIDENT The attached, tables contain the results of an analysis performed to deter-mine the radiological consequences at the T:C site boundary fcr a gross release of activity frc= a Oc11y loaded fuel cask.
Tne analysis used for the accident is considered to be the vorst probable result of dropping the fuel cask frc= a height (k3 ft) greater than the design height (30 ft).
It is assumed that the cask and its entire contents of ten fuel assemblies are rufficiently da= aged to allow the escape of all the noble gases and Iodine in the gcp.
(See Table 1).
The release of the noble gases cnd Iodine is ascu=ed to be directly to the atmosphere and to occur instantaneously.
Hevertheless, the resulting site boundary doses shcvn in Table 2, even though calculated using this conservative approach, are still vell within the li=its specified in 10 CFR 100. Based on the results of this analysis it is the applicant's opinion that no additional means need be provided to prevent dropping the fuel cask.
1486 053 Supplement 2, Part VII Am. 35 (12-20-72)
g a
- m...,-aa NO3LE GAS AND IODINE OA~* A0TIVITY nacz, aus.3
.c
. 0.,. -,cuzu 120 DAY LECAY
(
Kr - 85 4.22 x 10' Curies Xe - 131M h.08 Curies
~
Xe - 133 L.90 x 10 Curies I - 131 1.64 Curies TA3LE 2 SITE 3CUNDARY DCSIS**
WHOLI 300Y Ganna Dose 3 eta Dose Tetai "ese Kr,85
.026 R
5 22 5 2h3 3
-o Xe - 131x 4.02 x 10 R 0
- .02 x 10 R
-6
-6
-6 Xe - 133 1.2 x 10 R 3 12 x 10 R L.32 x 10 R
-k
-h
-k I - 131 1.812 x 10 R 1.o,S x 10 R 3.h92 x 10 a s
Whole 3ody - Total 5 2k3 R f'
\\_
INHALATION I - 131 1.02 R
- Taken from Table 6, Appendix 1, T'E Environmental Report - Operating License Stage
- Site' Meteorciogical Dispersion Facter (X/Q) = 1.2 x 10~3 sec/n f7cm 3
letter to ye. John G. Miller, Vice President, Xetropolitan Edison Ccapany from R. C. DeYoung, Assistant Directer for Pressurized Water Reactors, Atc=ic Energy Cc= ission, October 2,1972.
Supplement 2, Part VII Am. 35 (12-20-72) i486 054