ML20206E026
| ML20206E026 | |
| Person / Time | |
|---|---|
| Site: | 07109079 |
| Issue date: | 04/14/1986 |
| From: | Leduc R WESTINGHOUSE HITTMAN NUCLEAR, INC. |
| To: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| Shared Package | |
| ML20206E030 | List: |
| References | |
| 26849, HN--733, HN-0-0733, NUDOCS 8606230049 | |
| Download: ML20206E026 (3) | |
Text
-
v~'x 7F '70 7c/
(=
PDA.
w O
x RETURN TO 396-SS
- $c'"
e k-PR 211986 > j0 Westinghouse AWesnngo,
gisi a,nsey w Hittman Nuclear W
q.
atycloa g u ayand 21045 s
Incorporated pocket CLERK 77 Refer to:
4
~
ffN-0-0733 April 14,1986 Mr. Charles MacDonald, Chief g
Transportation Certification Branch U.S. Nuclear Regulatory Commission g
Washington, D.C.
20555
]
cc
Subject:
One-Time Shipment Exemption 22 N
Dear Mr. MacDonald:
y co During August, 1985, Westinghouse liittman Nuclear Incorporated was contracted by GPU Nuclear Corporation to solidify various bead resin and sand filter waste at its Three Mile Island, Unit 2, nuclear plant. This waste was contained in a number of vessels, some of which were included in the initial specification, while others were subsequently added to liittman's scope.
During the solidification campaign and in preparation of the radio-active shipment records, it was discovered that liners #19 and #23 (IIN-100 sized liners) had been solidified containing non-LSA concentrations of Sr-90.
The quantity of Sr-90 in both liners is greater than A2.
All other isotopes in these liners are LSA. Specific details on each liner are listed below.
- 19
- 23 Quantity of Sr-90 (Curies) 70 105 A2 Quantity for Sr-90 (Curies) 0.4 0.4 Specific Activity of Sr-90 (milli Ci/gm) 0.013 0.019 LSA limit (milli Ci/gm) from 10CFR71.4 0.005 0.005 Since this solidified waste package is non-LSA and greater than an A2 quantity, the regulations call for shipment in a Type B package. A Type B package for these liners does not exist.
~
1N Leg Remitt7r 5d Checktb.[(left__________~kCMO 2
8606230049 B60414 Am c u n t _ _ J.W _ _ _ _ _ _ _ _ _ _ _ _
PDR ADOCK 07109079 Fc c C '_P m y. //E~. _ _ _ _. _.. _
C PDR Tyre tf.
di t pW@M 24Q9
..n n.
n
~ au; m
p Mr. Charles MacDonald U.S. Nuclear Regulatory Commission April 1,.1986 Page 2 The International Atomic Energy Agency (IAEA) has raised the A2 quan-tity of Sr-90 to 2 Ci.*
This value for A2 would raise the LSA limit to 4 milli Ci/gm by IAEA regulations, and to 0.3 milli Ci per 10CFR71.4.
This more recent safety assessment would make liners #19 and #23 LSA and quali-fied for shipment in a certified Type A package.
In order to preclude this situation in the future Hittman will modify its Training Procedure 0-011 and its Proposal Procedure M-002 to specifi-cally address and highlight the requirement to assess the suitability of the proposed waste container with an acceptable transportation package. GPU will develop a technical bid review program which includes perusal of all l
proposals requiring compatibili,ty between waste container and transportation package. This review will be performed by Three Mile Island's Shipping and Disposal Coordinator.
bbre specifically, this letter is to request a specific one-time ship-ment exemption for liners #19 and #23 to be shipped in a HN-100 Series 2 Cask (certificate No. 9079) from Three Mile Island to Richland, Washington.
Based on the specific conditions of this situation, the IAEA requirements for Sr-90 and the procedure improvements, I am looking forward to a favorable response from you on this request.
Thank you for your consideration of this exemption request.
Very truly yours,
- f' /w R ert J. Leduc Director, Engineering RJL/b1
\\
- Safety Series No. 6, Regulations for the Safe Transport of Radioactive Material, 1985 Edition.
DOCuET uO.
9 /- P D 2 9 CONTROL NO._
[kf DATE OF D00.
[k/((((
DATE RCVD._
8 [/[/((
FCUF _
PDR FCAF LPDR 100 ILE REF.___
UNUR SAFEGUARDS FCTC _
OTHER DESCRIPTION:
Wf CA
/>td 94 f
<, M8 b TNITIAI, ~
f i
l