ML20148A587
| ML20148A587 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 10/04/1996 |
| From: | Tam P NRC (Affiliation Not Assigned) |
| To: | Lamastra M NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| Shared Package | |
| ML082490708 | List: |
| References | |
| FOIA-97-99 NUDOCS 9705090091 | |
| Download: ML20148A587 (2) | |
Text
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1l j' Miice Lcm, ym From Peter Tam;A -
To TWD2.TWP8.MXL2 Dates 10/4/96 9:20am
Subject:
Question Re. Criticality Monitor Mike:
My licensee (Catawba) raised the following question-but I do not know who to turn to in NMSS.
Can you help by either answering, or forwarding this e-mail to someone who can answer?
10 CFR 70.24 does not require criticality monitoring."when special nuclear material is being transported when packaged in accordance with requirements of Part 71..."
However, depending l
on the actual physical setup at a nuclear plant, upon arrival at I
the site, the nuclear fuel assemblies would be transported without packaging from the truck to the new fuel storage area.
~While it is easy to see that moving assemblies one at a time in air has no physical possibility of attaining criticality, and therefore is of no safety concern, it is not clear if criticality l
monitors, would be required on the route between the truck and the L
fresh fuel storage area.
What do you think?
l f -Ah kAg e ler, WR R i
CC:
HNB, DXW, VXN, DEL Hg e b)
Michael b a Nr#
M/l/t hp From:
a
/
WND2.WNP3(PST),('
, pf.; $ 4qS l
To Date 10/4/96 11:07am l
Subject:
Question Re. Criticality Monitor -Reply l
Peter, it seem pretty clear to me that the licensee is required to have a monitor or request an exemption based on no safety concern. I will forwarded your request to of criticality people to get their thoughts l
.From:
Eric Leeds ' 'I M/4 D " J' "f' To WND2.WNP3.PST, Date 10/8/96 9:52am
Subject:
Question Re. Criticality Monitor -Reply l
Peter'-
In response to your e-mail on criticality monitoring for transfer of fresh fuel in a Part 50 licensee's fuel handling building:
U:lless I misunderstand your e-mail, the issue should be addressed under Part 50 - its not a Part 70 issue.
I recommend you speak with the folks in reactor systems - I cc:d Lawrence Phillips and i
Tim Collins'on this e-mail.
If-your sure its a Part 70 issue, l
please come see me
- I'm in 0-6-G-24.
j Thanks!
9705090091 970506 l
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PDR ILLIAMs97-99 s
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From Peter Tam /A)
, a 3
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~,,
To:
TWD2.TWP8.'MXL2
' Y
3 Date 10/4/96 9:20am subject:
Question Re. Criticality Monitor Mike:
My licenssa (Catawba) raised the following question but I do not know who to turn to in NMSS.
Can you help by either answering, or forwarding this e-mail to someone who can answer?
10 CPR 70.24 does not require criticality monitoring "when special nuclear material is being transported when packaged in j
i accordance with requireatuts of Part 71..."
However, depending j
on the actual physical cetup e.t a nuclear plant, upon arrival at j
the site,-the nuclear fuel assemblies would be transported without packaging from the truck to the new fuel storage area.
]
I l
While it.is easy to.see that moving assembliec one at a time in i
air has no physical tpossibility of attaining criticality, and therefore is of no saafety concern, it is not clear if criticality monitors would be required on the route between the truck and the fresh fuel storage area.
What do you think?
t l
CC:
HNB, DXW, VXN, DEL l
From:
Michael Lamastra s'*
Date 10/4/96 11:07am
~
5 ( ~/2m g'/,'4 To:
WND2.WNP3(PST) a:
Subject:
Question Re. Criticality Monitor -Reply I
Peter, it seem pretty clear to me that the licensee is required j
to have a monitor or request an exemption based on no safety concern. I will forwarded your request to of criticality people j
to got their thoughts I
From Eric Leeds,J #)S To:
WND2.WNP3.PST,'O ^'f? W 4M/2 Dates 10/8/96 9:52am Subject Question Re. Criticality Monitor -Reply Peter -
In response to your e-mail on criticality monitoring for transfer of fresh fuel in a Part 50 licensee's fuel handling building:
Unless I misunderstand your e-mail, the issue should be addressed under Part 50 - its not a Part 70 issue.
I recommend you speak with the folks in reactor systems - I cc:d Lawrence Phillips and Tim Collins on this e-mail.
If your sure its a Part 70 issue, j
please come see me
- I'm in O-6-G-24.
Thanks!
d
_