ML19296A767
| ML19296A767 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 01/29/1980 |
| From: | Gallo J ISHAM, LINCOLN & BEALE |
| To: | Grossman H, Paris O, Shon F Atomic Safety and Licensing Board Panel |
| References | |
| NUDOCS 8002190018 | |
| Download: ML19296A767 (1) | |
Text
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January 29, 1980 f, EI-lG s A Herbert Grossman, Esquire Dr. Oscar H. Paris Atomic Safety and Licensing Atomic Safety and Licensing Board Panel Board Panel U. S. Nuclear Regulatory U.S. Nuclear Regulatory Commission Commission Washington, D.C. 20555 Washington, D.C. 20555 Mr. Frederick J. Shon Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Re: In the Matter of Consumers Power Company (Big Rock Point Nuclear Power Plant) Docket No. 50-155 Gentlemen: Consumers Power Company has responded to a number of questions posed by the NRC Staff with respect to the Company's application for a license amendment which would authorize the Company to increase the capacity of the spent fuel pool at Big Rock Point. This information is set forth in the Company's letters of December 28, 1979 and January 7, 1980, and they are enclosed for the information of the Licensing Board and the parties. Sincerely, v Jose h Gallo One of the Attorneys for Consumers Power Company cc: Big Rock Point Service List 800m oo o k.
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, _,;' C0mpany - J L W 9 LS U V LS L c 3.s%.k' o.n.: on.c..: 2i2 w.. u cnia.n 4 .nu.. s ca.on, u.cn.g.n moi. Area Cod. S17 788 O350 6 January 7, 1980 Director, Nuclear Reactor Fegulatien Att: Mr Dennis L Zie= ann, Chief Operating Reactors Branch No 2 US Nuclear Regulatory Cc=issien Washington, DC 20555 DOCKET 50-155 - LICENSE DPR BIG ROCK POINT PLANT - PROPCSED EXPANSION OF SPINT FUEL STORAGE CAPACITY: CORRECTION TO LTrER DATED CCTOBER 19, 1979 Consuners Power Co=pany letter dated October 19, 1979, in response to NBC questions on the subject modification, stated that an analysis of potential drops of tvo casks used in the spent fuel pool was attached for infomation. The analysis was inadvertently not attached to the letters distributed on October 19, 1979 The analysis is transrltted herewith for infomation. As noted in the October 19, 1979, letter, this analysis was originally per-formed to support handling of the 15 and 7.5 casks during reactor operation. That project, however, was ter=inated and the casks are not handled during operation. The attached analysis, therefore, has never been used as a basis for plant operation. David P Hoffhan (Signed) David P Hoffman Nuclear Licensing Ad=inistrator Attachment (Supplement Cask Drop Analysis for 15 Ten Cobalt & 71/2 Ten Treat II Casks, Bechtel Associates) CC: JGKeppler, USNRC '~ N s ,s \\ u.-
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BECHTEL ASSOC 1ATES PROFESSIONAL CORPORATION f h h f$ DUPLICATE DOCUMENT C ly entered into system under: s 5 ,kT Entire document previouuly ANO No. of pages. rj h. 2..
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.rl General Off>ces. 212 West Mecm gan Avenue Jackson, Michigan 49201. Area Code S17 788-0550 December 28, 1979 Director, Nuclear Reactor Regulation Att Mr Dennis L Ziemann, Chief Operating Reactors Branch No 2 US Nuclear Regulatory Commissica Washington, DC 20555 DOCKET 50-155 - LICENSE DPR BIG ROCK POINT PLANT - PROPOSED EXPANSION OF SPENT FUEL STORAGE: RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION NRC letter dated November 28, 1979 requested additional information concerning the proposed expansion of spent fuel storage at Big Rock Point. The questions asked and the related responses are as follows: Question 1 Wita retard to installation considerations, your October 1, 1979 and October 19, 1979 responses indicate that no rack will be handled in the vicinity of stored spent fuel. Verify and provide a basis for your conclusion that the possibility of a dropped or tipped rack on an empty rack will not impact and damage an adjacent rack with stored spent fuel. Response 1 Installation of the new spent fuel racks will be in accordance with detailed procedures. The procedures, which will be prepared by the installation contractor, will address specific transit paths and installation sequences to assure no damage to stored spent fuel from a postulated dropped rack. A copy of the detailed installatica procedures will be submitted for NRC review prior to commencement of any movement of racks in the spent fuel pool. DUPLICATE DOCUMENT racks which are not Type 304 stainless e of corrosion, if any, related to these Entire document previously entered into syste und-ANO No. of pages: h" 7 #[ [ 2 [ j 2 [3' '}}