ML19269F468

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Responds to V Dierig Inquiry Re Transportation of Fuel. Nuclear Fuel Arrives at Facility in Line W/Earliest Date of Const Completion.Aslb 790809 Hearing Determined No Undue Safety Risk
ML19269F468
Person / Time
Site: Zimmer
Issue date: 10/31/1979
From: Gossick L
NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)
To: Huddleston W
SENATE
Shared Package
ML19269F469 List:
References
NUDOCS 7912210071
Download: ML19269F468 (3)


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,E pmRiog[g UNITED STATES

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NUCLEAR REGULATORY COMMISSION 3

4 E WASHINGTON, D. C. 20555 o

44.....,o The Honorable Walter D. Huddleston United States Senate Washington, D. C.

20510

Dear Senator Huddleston:

I am pleased to reply to your letter regarding the inquiry made by your constit-uent, Ms. Vicki Dierig, concerning transportation of fuel for the Zimmer Nuclear Power Station.

The Cincinnati Gas and Electric Company with two other utilities has applied for an operating license for the Zimmer Facility. At present, an ongoing license proceeding and hearings are being conducted regarding the operating license application. Ms. Dierig appeared at those hearings on May 23 to express her views. Under our rules the license to possess nuclear fuel may be treated as a separate and distinct issue apart from the operating license application and was so treated here.

Utilities place their orders for nuclear fuel so that the fuel will arrive at the site in line with the earliest date that the plant construction is projected to be completed. Should plant construction be deiayed, the utility must make a determination regarding storage of the completed fuel assemblies at the vendor's plant, or some other storage location, which will incur further financial charges; or storage at the plant site. Before new fuel can be delivered to the plant site, the utility applicant must obtain a separate materials license from the NRC.

In the case of da Zimmer plant, the NRC issued Mc+arials License No. SNh-1823 on June 26, 1978 after reviewing the utility's application and making a favorable safety evaluation (enclosed). The license authorizes receipt, possession, inspec-tion and storage; and packaging of the fuel for delivery to a carrier in accordance with Commission rules and conditions of the license.

It is my understanding that 560 fabricated fuel assemblies (one complete Ziiimer core) were actually delivered by truck by a licensed carrier as announced in the enclosed news release dated September 10, 1979. The fuel assemblies were unirradiated (contain no radioactive fission products) and were restricted (by the license) to a U-235 enrichment not to exceed 2"..

The fuel was shipped in 10 CFR Part 71 approved shipping containers. It is my understanding that the fuel passed through the State of Kentucky enroute from its storage location in the south to the Zimmer plant.

Regarding Ms. Dierig's concern about what is being done to protect the people and environment where this material is being shipped, I am enclosing the NRC staff's safety evaluation report pertinent to this matter.

2166 348 7912a00

The Honorable Walter D. Huddleston However, in view of local public concern, the titomic Safety and Licensing Board took cognizance of the license to possess nuclear fuel. The entire matter was made the subject of a hearing session held on Thursday, August 9, 1979 in Cincinnati.

(Transcript page 2988ff). Argunent was heard on whether fuel could be presently shipped to the Zimmer site; the Board concluded, based on the staff's safety evaluation and other testimony that there was no safety reason or other reason why this could not be done.

The operating license hearings will reconvene November 14 to consider an aspect of fire protection. There will be additional hearings at a later time to considar the aspects of the Three Mile Island accident, as they may impact upon the construction and operation of the Zimmer facility.

Sincerely, C.R

d Lee V. Gossick Executive Director for Operations

Enclosures:

As Stated 2166 349 9

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H it' Citat:INtJ Af t (I AS f. El E Cinic COMP ANY September.10, 1979

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.ani a v.a riis c.n,;..ui.in oeis,.. Mo2 Psione 032 2639 About 115 tonc of uranium fuel have boon dulivered to the tan. II. Zi msner flue l ea r power Stations, completing the shipment needed for thu initial fuel loading.

The shipnient, va l uud at S47 million, was delivered by trucks front Wilmington, ti.C.,

during the past 31s weeks.

The fuel lesh

.i n a ceramic-like mat.erial in the shape of a pullet than a halI'-luch in longth and diameter.

The pull e ts are a1.1yned in inu t.a1 rods about 13 feet long.

There are 560 fuel nanombiluu in the total shipment, with each assembly consLating at u bundle of 63 rode.

2nuido Zinuner Glo t lon, the fuel is being unctated, inspected und placed int.o a conarete storage pool in the re a c t.or building.

The Cinci..naLi Gas & E;1octr ic Co:npany expects.. o t ocu L vo att upuraLiau liconee for the alation next s uistme r.

Orico t b u t.

1icenue han buon obtained, the fuel will be loaded into Ihe redator.

'isn i nogmunt.s or a public hearing on the operating license we r.s by the Atomic Satoty and Licunning Board.

ce inshic ted t.h l o u i ntiau r The hearing is oxpected to rosumo this fall, but no dato has

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buon not.

z I nuaer St.at. ion ju ucheduled for commercial operation in early 1981 at a total cost of $850 million.

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e N.* e 2 & Qjf SAFETY EVALUATION REPORT - CIllCli'UATI GPS ' Elf.CTf,IC CC!!PAi!Y (CG&E)

COLUMBUS A!!D SOUTHER l101110 ELECIRIC C'JM?isflY (C50)

THE DAYI0tl POWER AND LIGHT CCUPld;Y (DPL)

APPLICAT0ff DATED MARCH 8, 1978, Al!D SUPPLEMENT THERET0 TRA!!Si1ITTED BY LETTER DATED MARCH 31, 1978, FOR A STORAGE LICEllSE FOR FUEL AND ACCES5ORIES FOR THE WM. H. ZIMMER flVCLEAR POWER STATION, UllIT 1 DOCKET N0. 70-2838 The subject application and supplement thereto submitted by CG&E on behalf of itself.and as agent for CS0 and DPL requests a license to receive approximately 2000 kilograms of U-235 as uraniu, enriched up to 1.95% in the U-235 isotope contained in reactor fuel assemblies, and 5 grams of U-235 at any enrichment contained in neutron detector',.

The fuel assemblies which the applicants wish to receive contain uranium enriched to a maximum of 1.95% in the U-235 isotope.

The fuel is con-tained in up to 560 fuel assemblies.

Because of measurement and enrich-ment variations usually Enccuntered, it is proposed that a maximum U-235 ent'chment of 2.0% be authorized.

The reactor in which the fuel assemblies wili be used is a General Electrit. Boiling Water Reactor.

The weight of uranium contained in a single fuel assembly is 186.214 kilograms and the weight of U-235 in a single assembly is 3.537 kilograms.

The fuel assemblies will be stored in their shipping containerr and in the spent fuel storage racks located in the spent fuel pool.

Each storage rack holds 20 assemblies in two rows.

Assemblies in a row are stored 6.625" center-to-center spacing.

The safety of these spacings have been previously established, for both the flooded and dry cases.

These spacings are currently used at several operating reactors (see Dockets 70-1972 and 70-1247).

Further, the fuel is to be stored dry.

Uranium enriched to 2%

in the U-235 isotope cannot be made accidentally critical unless a moderator such as water is present.

Cons ~rvative calculations by the staff have shown that four or more of e

these fuel assemblies are required in order to attain criticality.

A license condition has been added restricting the number of fuel assemblies which can be out of approved shipping containers or storage location at any one time to three assemblies.

In addition the Staff nas added a condition requiring that fuel assemblies be stored in such a manne.' that would allow water to drain freely from the assemblies in the event of flooding and subsequent draining of a storage area.

This prevents a 21-66 351 N00 0&{\\k 770 L ' ? s '?

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.g-condition where individual fuel assemblies could be water maderated without providing shielding between a3semblics.

As secondary controls, the applicants have caused water hoses in the area to be valved off and safety tagged, have provided a waterproof and fire resistant cover for the fuel assemblies, and have limited the amount of combustible materials in the area.

It is the Staff's opinion that under these conditions the applicants have established reasonable ed satisfactory precautions to avoid accidental criticality.

The applicant's industrial security program has been reviewed and it is the Staff's opinion that the program is satisfactory.

The applicants have also described the basic aspects of their radiation safety control. program, including a description of the training and.

experience of personnel responsible for administering the program.

The Staff has concluded that the applicant's radiation safety program and personnel are adequate to allow them to reasonably carry out tne activi-ties for which a license is requested.

The applicants have requested, pursuant to 10 C K 70.24(b), an exemption from the provisions of 10 CFR 70.24.

Because of the inherent features associated with the storage and inspection of unirradiated fuel contain-ing uranium enriched to less than 5% in the U-235 isotepe when no fuel processing activities are to be performed, the Staff hereby determines that granting such an exemption will not endanger life or property or the common defense and security, and is in the public interest.

This exemp-tion is authorized pursuant to 10 CFR 70.14.

Conclusion Based on the above statements, the Staff believes that the preposed activities can be performed without undue risk to the health and safety of t.he public.

It has been determined by the Staff that the application fulfills the requrements of 10 CFR 70.23(a).

Further, the issuance of this license is not a major federal action significantly affecting the quality of the human environment and thus, pursuant to 10 CFR 51.5 (a)(4),

no environmental impact statement, negative declaration, or environmental appraisal need be prepared.

?00ROR'8NAL 2:66 352

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The Staff recommends approval of the application with the addition of the above license conditions, and exemption of the licensee from the require-ments of 10 CFR 70.24.

a2.4 J. C. Delaney

. Fuel Processing and Fabricatien Branch Division of Fuel Cycle and Material Safety Approved:

L. C. Rouse 6p/,f P00R ORGINAL 2166 353 6

7912300

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