ML20134H722
| ML20134H722 | |
| Person / Time | |
|---|---|
| Issue date: | 11/06/1996 |
| From: | Miraglia F NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20134H706 | List: |
| References | |
| 2.206, DD-96-18, GL-91-18, NUDOCS 9611140258 | |
| Download: ML20134H722 (5) | |
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7 7590-OlP UNITED STATES NUCLEAR REGULATORY COMMISSION
't ALL POWER REACTOR LICENSEES ISSUANCE OF FINAL DIRECTOR'S DECISION UNDER 10 CFR 2.206 1
4 Notice is hereby given that the Acting Director, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission (NRC) has granted in part and i
denied in part a Petition, dated April 13, 1994, submitted by Mr. Paul M.
i Blanch (Petitioner). The Petition requested that the NRC take action with regard to all power reactor licensees, concerning the potential failure of the fuel in the spent fuel pools for all reactors in the United States.
Specifically, the Petitioner requested that the NRC: (1) immediately issue an information notice or other appropriate notification forwarding all I
information in its possession to all power reactor licensees regarding the potential failure of fuel in spent fuel pools, and reminding licensees of their responsibilities to perform timely operability determinations in accordance with their technical specifications and NRC Generic Letter 91-18; (2) direct each licensee to immediately perform an evaluation of this 4
potential deficiency to determine compliance with its current licensing basis; i
(3) deny all requests for license amendments for the expansion of spent fuel pool capacity until these safety concerns are fully resolved; and (4) after J
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evaluation by each licensee, if the NRC determines there is little or no risk 4
to public health and safety, the NRC may issue a Notice of Enforcement i
Discretion. Request (3) was determined to be a request for a licensing action and so was beyond the scope of 10 CFR 2.206.
9611140258 961106 PDR ORG NRRA PCM l
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The Acting Director of the Office of Nuclear Reactor Regulation has j
granted in part Requests (1) and (2) of the April 13, 1994, Petition. With regard to Petitioner's Request (4), the Director has concluded that there has
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been no need for issuance of N0EDs regarding potential failure of fuel in I
spent fuel pools. The reasons for these decisions are explained in the " Final Director's Decision Under 10 CFR 2.206" (DD-96-18), the complete text of which follows this notice, and which is available for public inspection at the l
Commission's Public Document Room, the Gelman Building, 2120 L Street, NW.,
Washington, DC, and at the local public document room for all power reactor licensees.
A copy of this Final Director's Decision has been filed with the Secretary of the Commission for review in accordance with 10 CFR 2.206(c) of the Commission's regulations. As provided in this regulation, this Decision will constitute the final action of the Commission 25 days after the date of its issuance, unless the Commission, on its own motion, institutes review of the Decision within that time.
Dated at Rockville, Maryland, this 6th day of November 1996.
FOR THE NUCLEAR REGULATORY COMMISSION S
i a)J.
agla,h.,Actn Frank J.
Director Office o uclear Reactor Regulation i
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$ d hf Docket Nos.
Plant Name j
50-313 and 50-368 Arkansas Nuclear One, Units 1/2 ht hoclv.l' 50-334 and 50-412 Beaver Valley Power Station, Units 1/2
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50-438 and 50-439 Bellefonte Nuclear Plant, Units 1/2 50-155 Big Rock Point Plant STN 50-456 and STN-50-457 Braidwood Units 1/?
50-259,50-260 and 50-296 Browns Ferry, Units 1/2/3 50-325 and 50-324 Brunswick, Units 1 and 2 STN 50-454 and STN-50-455 Byron Station, Units 1 and 2 i
STN-50-483 Callaway Plant, Unit 1 50-317 and 50-318 Calvert Cliffs, Units 1 and 2 50-413 and 50-414 Catawba Nuclear Station, Units 1/2 50-461 Clinton Power Station, Unit 1 50-445 and 50-446 Comanche Peak, Units 1 and 2 50-298 Cooper Nuclear Station 50-302 Crystal River Unit 3 50-346 Davis-Besse Unit 1 50-275 and 50-323 Diablo Canyon Units 1 and 2 50-315 and 50-316 Donald C. Cook, Units 1 and 2 1
50-237 and 50-249 Dresden Units 2 and 3 50-331 Duane Arnold Energy Center 50-341 Fermi, Unit 2 50-285 Fort Calhoun Station, Unit 1 50-416 Grand Gulf Nuclear Station, Unit 1 50-261 H. B. Robinson Unit 2 50-213 Haddam Neck Plant 50-321 and 50-366 Hatch Nuclear Plant, Units 1 and 2 50-354 Hope Creek 50-247 and 50-286 Indian Point, Units 2 and 3 I
50-333 J. A. FitzPatrick 50-348 and 50-364 Joseph M. Farley, Units 1 and 2 50-305 Kewaunee Nuclear Power Plant i
50-373 and 50-374 LaSalle, Units 1 and 2 i
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4 50-352 and 50-353 Limerick, Units 1 and 2 50-309 Maine Yankee Atomic Power Station 50-369 and 50-370 McGuire Nuclear Station, Units 1/2 50-245, 50-366, and 50-423 Millstone, Units 1/2/3 50-263 Monticello Unit 1 50-220 Nine Mile Point Unit 2 j
50-338 and 50-339 North Anna, Units 1 and 2 50-269,50-270 and 50-287 Oconee Nuclear Station, Units 1/2/3 i
50-219 Oyster Creek 50-255 Palisades Plant 50-528,50-529 and 50-530 Palo Verde 1/2/3 50-277 and 50-278 Peach Bottom, Units 2 and 3 50-440 and 50-441 Perry, Units 1 and 2 l
50-293 Pilgrim Unit 1 50-266 and 50-301 Point Beach, Units 1 and 2 50-282 and 50-306 Prairie Island, Units 1 and 2 50-254 and 50-265 Quad Cities, Units 1 and 2 50-244 R. E. Ginna j
50-458 River Bend Station 50-361 and 50-362 San Onofre, Units 2 and 3 50-272 and 50-311 Salem, Units 2 and 3 50-443 Seabrook Station 50-327 and 50-328 Sequoyah, Units 1 and 2 50-400 Shearon Harris Unit 1 50-498 and 50-499 South Texas, Units 1 and 2 50-335 and 50-389 St. Lucie Plant, Units 1 and 2 50-280 and 50-281 Surry Power Station, Units 1 and 2 50-387 and 50-388 Susquehanna, Units 1 and 2 50-289 Three Mile Island Unit 1 50-250 and 50-251 Turkey Point Units 3 and 4 50-395 V. C. Summer Unit 1 50-271 Vermont Yankee 50-424 and 50-425 Vogtle, Units 1 and 2
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50-382-Waterford Station Unit 3
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50-390 and 50-391 Watts Bar, Units 1 and 2 j
bO-397 WNP Unit 2 STN-50-482 Wolf Creek Unit 1 4
50-295 and 50-304 Zion Station, Units 1 and 2 i
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