ML20148M417
| ML20148M417 | |
| Person / Time | |
|---|---|
| Site: | Palisades, Point Beach, Arkansas Nuclear, 07201007  |
| Issue date: | 06/18/1997 |
| From: | Knapp M NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20148M409 | List: |
| References | |
| 2.206, DD-97-15, NUDOCS 9706240111 | |
| Download: ML20148M417 (2) | |
Text
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DOCKETED 7@@69-P UNITED STATES NUCLEAR REGULATORY COMMISSION DOCKET NOS. 50-255. 50-266. 50-301. 50-313. 50-368 '97 JN 18 P1 :07 72-5. 72-7. 72-13. 72-1007 r] S RVl
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CONSUMERS POWER COMPANY ET PALISADES NUCLEAR PLANT.
BRANCH WISCONSIN ELECTRIC POWER COMPANY POINT BEACH NUCLEAR PLANT. UNITS 1 AND 2 ENTERGY OPERATIONS. INC.
ARKANSAS NUCLEAR ONE. UNITS 1 AND 2' ISSUANCE OF DIRECTOR'S DECISION UNDER 10 CFR 2.206 (DD-97-15)
Notice is hereby given that the Director. Office of Nuclear Material Safety and Safeguards, has issued a Dire:. tor's Decision concerning a Petition dated October 18. 1996, filed by Don't Waste Michigan and the Lake Michigan Federation (Petitioners) under Section 2.206 of Title 10 of the Code of Federal Regulations (10 CFR 2.206). The Petition requested that the U.S.
i Nuclear Regulatory Commission order all users of Ventilated Storage Casks
[
(VSC-24) systems to refrain from loading any casks until the certificate of j
compliance (C0C). safety analysis report (SAR). and safety evaluation report
-(SER) are amended to include operating controls and limits to prevent l
hazardous conditions. Such conditions include the generation of explosive gases, caused by the interaction between the VSC materials and the environments, encountered during loading, storage, and unloading.
Further Petitioners claim the VSC-24 should not be used until:
(1) an j
independent third-party review team has examined the safety issues they raise; j
(ii) the potential impacts of all material aspects of the casks have been fully ~ assessed: (iii) there is experimental verification of temperature calculations and heat transfer assessments and other design assumptions:
(iv) the safety of the material coatings on components and structures has been justified: and (v) the SAR. SER, and C0C are amended to include the necessary operating control and limits to direct safe use of the VSC-24.
The Director of the Office of Nuclear Material Safety and Safeguards has determined that the Petition should be denied for the reasons stated in the
" Director's Decision Under 10 CFR 2.206" (DD-97-15). the complete text of 73 -(!1 l
2 which follows this notice. The decision and documents cited in the decision are available for public inspection and copying in the Comission's Public 4
Document Room, the Gelman Building. 2120 L Street. NW. Washingtor.. DC.
A copy of this decision has been filed with the Secretary of the Comission for the Comission's review in accordance with 10 CFR 2.206(c). As provided therein. this decision will become the final action of the Commission 25 days after issuance unless the Commission, on its own motion, institutes review of the decision within that time.
7 Dated at Rockville Maryland. this /
day of c,77/H FOR THE NUCLEAR REGULATORY COMMISSION
/fA4N ks l
Malcolm R. Knapp. Acting Director Office of Nuclear Material Safety i
and Safeguards 4
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