ML19276G415
| ML19276G415 | |
| Person / Time | |
|---|---|
| Site: | 07002623 |
| Issue date: | 04/11/1979 |
| From: | Cunningham R NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Christenbury E NRC OFFICE OF THE EXECUTIVE LEGAL DIRECTOR (OELD) |
| Shared Package | |
| ML19276G418 | List: |
| References | |
| NUDOCS 7905310132 | |
| Download: ML19276G415 (4) | |
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f UrH TED STATES j
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WASHINGTOfJ, D. C,20555 AH( 11 079
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MEM0RANDUti FOR:
E. Christenbury, Director and Chief Counsel Hearing Division Office of the Executive Legal Director FROM:
Richard E. Cunningham, Director Division of Fuel Cycle and Material Safety Office of Nuclear Material Safety and Safeguards
SUBJECT:
INFORMATION RELEVANT AND MATERIAL TO LICENSING BOARD AND PARTIES OF COMMISSION PROCEEDINGS Pursuant to the Commission Policy on Notification to Licensing Boards, Appeal Boards, or the Commission of new relevant and material information, this memorandum is considered relevant to the proceedings before the ASLB in the matter of Duke Power Company (Amendment to Materials License No. SNM-1773 for storage of Oconee spent fuel at McGuire Nuclear Station).
This memorandum describes an event relative to the packaging to be used for the shipment of spent fuel by Duke Power Company.
At a meeting with Nuclear Assurance Corporation (NAC) on March 29, 1979, we were informed by representatives of NAC, that NAC used and then sold a Model No. NFS-4 (NAC-1), Serial A, cask to Duke Power Company that may not meet the design approved by the Cocmission in Certificate of Compliance No. 6698.
Apparently, one or more of the shells is warped or bowed.
The exact cause or extent of the warp or bow is unknown to NAC (and Duke Power Company) at this time. The conditions were suspected by ganma scanning during construction of the package in 1974 by the cask manufacturer, EXCELCO, Silver Creek, NY.
To increase the shielding material in the area of reduced shielding thickness, copper plates were welded to the outer cask shell.
The safety implications of this reported defect have not been assesse.d, however, this could represent a substantial reduction in the effective-ness of the packaging.
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E. Christenbury APR 1 1 U/3 Subsequent to the meeting, flAC informed us by letter of April 2,1979 (copy enclosed) of a deviation during fabrication of a spent fuel cask.
To resolve this issue with regard to safety, the Office of NMSS has issued an order (copy enclosed) which prohibits the use of the Model fio. NFS-4 packaging by fiRC licensees until a determination is made that the packaging meets the requirements of Certificate of Compliance No. 6698. The order also requires the owner / user to evaluate deviations from the approved design, and Commission approval prior to return of the packagings to service.
Further information relevant to the above will be furnished to the Board when it becomes available to the staff.
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Richard E. Cunningham, Director Division of Fuel Cycle and Material Safety, NMSS
Enclosures:
1.
Ltr 4/2/79 NAC to NRC 2.
Order to Registered Users of Model No. NFS-4 Packaging
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Jun/79/3S/TrS Director Nuclear Material Cafety and Safoguards 1J.
S. Nuclear Regulatory Comminnion unshington, D.C 205SS Dear Sirns In accordance with the requirew.:nta o f ID CFrt71, Paragraph 71.G.
"Repo r tG *', the Nuclear Annurance Corporation hereby reportn on an unrecolved deviation f roin requirements unecified in the Certificate of Compliance No. 6693, *ievision No.
C.
This deviation e::iste in the NAC-1 Cank Serial DeiEgnat2on A transport packaging.
The devi-ution was detected au a renuit of re views of manufacturing rc:cor lh The deviction includan:
1.
An out-of-specification condition for the dinension be tween oton1 chella idqntified as part n.ur.bern 67 unc 69 as called out in NFS Drawing No. 10000, Sevinion 16, and 2.
An addition of welded-in-pince copper plucco to the outside ci part number 69.
In. order to bring the deviation into ccmpliance with e:-inting UnC reauiren'ents Nuclear Anourance Corporation will take the follo;i-ing correctivo actions:
A.
Addrosc the ncceptability of the NAC-In caek deviation in rega rd::. to the major technical dincipl'.nen cGdrenced in the UAC-1 Safe ty Analyciu Repo r t,
e.g.,
struc-tural, the r:ral, cri ticali ty, chielding, including the ef fect of the on-built condition.
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direbtor-Nuclear Material Sa fety and Safeguarda Pago 2 April 2, 1979 D.
Perform on-site mennuretrento of, the NAC-IA cank inner shell to characterine e.xiuting nholl configuration.
C.
noview f abrication records of the I AC-1A cas?( to determine the cause of*the devi-ntion and whether th.i.s devintion can rmni-
,fest ituelf in other NnC-1 cachs of uimilar denign.
'D.
Notify the owner of the NAC-ln canh (Duke
- Power Com,oeny) o f the clavintion and requect they inform the Nnc th.at the ouhject cault will be withdrawn-f rom road nervice until the deviation is reuolvec.
If the HRC has quections regarding thic notification, plence contact ny; at (404) 325-4200.
Very truly yourn, NU("J;nR A PIURMtCM CORPORATICM
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Ro lli:h3, vice President and General acnngar, I.:nginocring and Transportation Se:..riceu JDR:ot e
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