ML20136B640
| ML20136B640 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/13/1979 |
| From: | Miraglia F Office of Nuclear Reactor Regulation |
| To: | Grimes B, Vollmer R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7909100062 | |
| Download: ML20136B640 (10) | |
Text
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j UNITED STATRS
,y NUCLEAR REGULATORY COMMISSION g
g wAsumarow, n.c. massa April 13,1979 F
NOTE TO:
B. K. Grimes, NRR, TMI-2 R. H. Vollmer NRR, TMI-2 FROM:
F. J. Miraglia, Jr., Coordinator, Team B is information B. Grimes requested of 5. Bland on April 12,1979. is information R. Vollmer requested of R. Emch on April 13, 1979.
s.( d A F.O.
hia,Jr.
Coordinator Team B i
Attachments:
As Stated cc: see attached distribution list 000100cesy l
O
ATTACHMENT 1 STORAGE OF LIQUID RADWASTE IN TANKCARS l' w
- 8. Grimes requested on 04/12/79 that we provi.de an isotopie breakdown of the dose rates from a 30,000-gallon railroad.tankcar containing liquid radweste. We had sent him the dose rates on 04/11/79. The.
dose rate at contact was 40 R/hr as calculated by ORNL (D. Bartina).
Grimes also requested that we provide the dose rates for a 10,000-gallon tankcar.
We contacted ORNL but learned that today (04/13/79) is a state holiday in Tennessee and ORNL was not working. Therefore, we calculated the dose rates by hand in order to provide a timely response to the site.
We will follow-up on this on Monday (04/16/79) and contact ORNL again.
We calculated 7 R/hr at one matar from the 30.000-gallon tank and 4 R/hr at one meter from the 10,000-gallon tank.
We were unsure of the dimensions of a 10,000-gallon tankcar; 4 R/hr is for a tank as-sisned to be 10 feet in diameter and 17 feet long.
A tank 8 feet in diameter would give a dose rate of about 3 R/hr at one meter.
The isotopic distribution for the 7 R/hr dose rate is given below:
CONCENTRATION 5 0F DOSE RATE NUCLICE uCi/cc
_DUE TO NUCLIDE I-1 31 100 82 I-133 5
9 Xe-133 4
0.25 C5-134 0.4 0.5 CS-136 0.8 4
CS-137 1.4 3
La-140 1.6 1
This work was done by R. Emch and F. Akstulewicz.
U 4
,j ATTACHMENT 2 RESPONSE TO RE00EST OF R. V0LLMER CONCERNING
?,.j, s.
TRANSURANIC CONCENTRATIONS IN COOLANT _
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yi on Friday afternoon (04/13/79), R. Vollmer requested that we provide infomation to him on transuranic contamination of the primary coolant at PWRs other than TMI-2.
i Turkey Point has reported the following measurements of transuranics in the primary coolant.
Pu-238 5(11.6) x 10-8 uC1/gm Pu-239 and Pu-240 4.3 x 10"I uCi/gm Indian Point 1 and 2 has reported these measurements of transuranics in
-l 1975:
Pu + AM241 + cm242 10~I-10~7 vCi/spu We called Duke Power Company today. Robert Gill informed us that the MDA for gross alpha measurements in the primary coolant at Oconee is 4 x 10-6 uci/cc. Oconee measurements of gross alpha in the primary coolant have always been less than 4 x 10-6 uC1/cc.
l Generic calculations for a straight tube steam generator plant were done during the GESMO study. The calculated uranium concentrations in primary
~ coolant were:
U-235 2 x 10-12 pC1/cc U-237 3.8 x 10-5 pC1/cc i
U-238 2 x 10*II pC1/cc
t.
ATTACHMENT 2 (CONT'D.)
2
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r Note that U-237 has a 6.8 day half-life. Thu's. U-237 has a very high
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specific activity.
1 Printouts of calculated primary coolant concentrations for Davis-Besse and GESMO are attached.
We have estimated the concentrations of uranium in water which cor-respond to 10 ppb:
{
4 10 ppb - U-235 2 x 10 uC1/gm 10 ppb - U-237 8 x 10+2 pC1/gm
-I 10 ppb - U-238 3 x 10 pCi/gm l
Without knowing the isotopic content of the uranium, it is impossible to supply better correlations between ppb and uti/gm.
When LAC 8WR had fuel problems in 1976-1977, they measured 6 x 10-5 pCi/gm of gross alpha radioactivity in the primary coolant.
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