ML19282C777

From kanterella
Jump to navigation Jump to search
Reports Deviation of NAC-l Cask from Specs in Certificate of Compliance.Corrective Action Being Taken
ML19282C777
Person / Time
Site: 07106698
Issue date: 04/02/1979
From: Jesse Rollins
NAC INTERNATIONAL INC. (FORMERLY NUCLEAR ASSURANCE
To:
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
JDR-79-35-ETS, NUDOCS 7905020252
Download: ML19282C777 (2)


Text

'7/- 6 A 92 Nuclear Assurance Corporation 24 Enoutive Park West Atlanu. Georgo 30323 (404)325-4200 Teler 549%7. S12703 715 Horizon Dnvo Grand.Junc!an. Colarado SI'>til

,,, \\ \\ Zn (303)?4543?O i

u J

g TWX 9109?vC331 l

Wcn!wq;; raw 9

~

.1.

~

8901 ? urb. Sr. ucil md m'

(01).170344 f,il

"'S N.hr57?75 April 2, 1979 JDR/79/35/ETS

/

s Director Nuclear Matercial Safety and Safeguards U.

S.

Nuclear Regulatory Commission Washin g ton, D.C 20555

Dear Sirs:

In accordance with the requirercents of 10CFR71, Paragraph 71.61

" Repo rts ", the Nuclear Assurance Corporation hereby reports on an unresolved deviation from requirements specified in the Certificate of Compliance No. 6698, Revision No.

8.

This deviation exists in the NAC-1 Cask Serial Designation A_ transport packaging.

The devi-ation was detected as a result of revie.:s of manufacturing records.

The deviation includes :

1.

An out-of-specification condition for the dimension between steel shells identified as part numbers 67 and 69 as called out in NFS Drawing No. 10080, Revision 16, and 2.

An addition of welded-in-place copper plates to the outside of part Number 69.

In order to l> ring the deviation into compliance with existing NRC requirements Nuclear Assurance Corporation will take the follow-ing corrective actions :

A.

Address the acceptability o f the NAC-lA cask deviation in regards to the major technical disciplines addressed in the NAC-1 Safety Analysis Report, e.g.,

struc-tural, thermal, criticality, shielding, including the effect of the as-built condition.

s?J

.e e.

f b N i' if A 4 J ; h 2 g %,

w--

dig q

[ :'

~a a.

Je

/90hcacy:LC;2

JY Director-Nuclear Material Safety and Safeguards Page 2 April 2, 1979 3

B.

Perform on-site measurements of the NAC-1A cask inner shell to characterize existing shell configuration.

C.

Review fabrica tion records of the NAC-lA cask to determine the cause of the devi-ation and whether this deviation can mani-fest itself in other NAC-1 casks of similar design.

D.

Notify the owner of the NAC-lA cask (Duke Power Company) of the deviation and request they inform the NRC that the subject cask will be withdrawn from road service until the deviation is resolved.

If the NRC has questions regarding this notification, please contact me at (404) 325-4200.

Very truly yours, NUC, LEAR ACSU

')B(/d h

<MyE CORPORATION Ab ack D.

Rollin Vice President and General Manager, Engineering and Transportation Services JDR:ot