ML20133N495

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Environ Assessment Supporting Issuance of License SNM-1886, Permitting Storage of SNM in Form of Unirradiated Nuclear Fuel Assemblies.Finding of No Significant Impact Appropriate
ML20133N495
Person / Time
Site: 07002947
Issue date: 05/17/1985
From: Crow W, Kodali K
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20133N479 List:
References
NUDOCS 8508130503
Download: ML20133N495 (3)


Text

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MAY 171985 DOCKET NO.: 70-2947 APPLICANT: Illinois Power Company (IP)

Soyland Power Cooperative, Inc.

Western Illinois Power Cooperative, Inc.

FACILITY: Clinton Power Station (CPS), Unit 1 Clinton, Illinois

SUBJECT:

ENVIRONMENTAL ASSESSMENT - LICENSE APPLICATION TO RECEIVE NEW FUEL

Background

By letter dated October 9, 1984 and its supplements dated February 8, and May 6, 1985, Illinois Power Company (IP), acting on its own behalf and as agonts for the above utilities applied for an NRC license to permit the receipt, possession, inspection, and storage of special nuclear material in the form of unirradiated nuclear fuel assemblies. In addition, IP as part of the license application, seeks authorization to receive, possess, inspect, and store Sb-Be neutron sources, U-235 in-core neutron detectors, and Pu-238 and Pu-239 alpha calibration standards and check sources. The materials are for eventual use in CPS, Unit 1. In accordance with 10 CFR 51.21, the NRC has prepared this assessment of the environmental impacts that may be caused by issuance of the requested license. Because of the form and small amount (gram quantities) of nuclear materials contained in the neutron sources, various detectors, and calibration standard and check sources, storage of these materials will pose no threat to the environment. Therefore, the discussion Lelow will be limited to assessing the potential for environ-mental impacts resulting from the storage of new fuel assemblies at CPS, Unit 1.

The Proposed Action The proposed action is issuance of a license pursuant to 10 CFR 70 that will authorize IP to receive, possess, inspect, and store 636 fresh fuel assemblies at CPS, Unit 1. The license has been requested by August 19, 1985, and would be effective until it can be superseded by IP's operating license under 10 CFR

50. The fuel assemblies contain uranium dioxide (UO 2 ) pellets that have a maximum uranium-235 enrichment of 3.00 percent by weight and are encapsulated in zircaloy tubing. Issuance of the license would result in the receipt, possession, inspection, and storage of the unirradiated fuel assemblies at CPS, Unit 1. The transport of new fuel to CPS, Unit 1 will be the responsibil Hy of the fuel fabricator. However, the proposed license would authorize the applicant to transport, or deliver to a carrier'for transport, the assemblies in approved packages if this should become necessary (e.g., to return defective fuel to the manufacturer).

850B130503 850B07 7 PDR ADOCK 0700

2 MAy 171985 e

Need for the Proposed Action The applicant proposes to receive and store fresh fuel prior to issuance of Part 50 operating license in order to inspect the assemblies and to finalize fuel preparation (e.g., add necessary hardware) needed to load the fuel into the reactor core vessel. Actual core loading, however, will not be authorized by the proposed license. Early completion of this fuel handling will help avoid delays in the CPS, Unit 1 startup once its operating license is issued.

Alternatives to the Proposed Action and their Environmental Impacts Alternatives to the proposed action include complete denial of IP's application.

Assuming the operating license will eventually be issued, denial of the storage only license now would merely postpone new fuel receipt at CPS, Unit 1. Such action, as well as any other alternative that can be imagined, would not present an environmental advantage because, as discussed below, no environmental impacts are expected to result from the proposed action.

Environmental Impacts of the Proposed Action A Final Environmental Statement (NUREG-0854) associated with the full-scale operation of CPS, Unit 1, has already been issued by the NRC. Based on the evaluation in this statement, the environmental impacts of plant operation subject to proposed conditions for environmental protection are excected to be small. New fuel receipt and storage is only a small part of CPS, Unit l's overall operation that will eventually include handling of irradiated fuel which is significantly more hazardous. Accordingly, the environmental impact from handling unirradiated fuel is expected to be very minor.

Once at CPS, Unit 1, the new fuel will be received at the Fuel Building. Each incoming shipment of radioactive material shall be handled in strict compliance with CPS, Unit 1 radiological control procedures. The fuel will be stored in three locations prior to fuel loading. These locations are the New Fuel Storage Vault and the Spent Fuel Storage Pool which are located in the Fuel Building and the Containment Storage Pool which is located in the Containment Building.

The design of these storage facilities combined with plant procedures will ensure acceptable protection of the fuel assemblies from excessive physical damage either under normal or abnormal conditions. If the new fuel cannot be immediately transferred inside the Fuel Building for some reason, such as an equipment mal-function, the fuel may be temporarily stored outdoors within the protected area boundary. Any fuel held in this interim storage area will be kept in its shipping box. The presence of engineered-safety features and administrative controls minimize the likelihood of an accident situation occurring during fuel handling activities.

Only a small amount, if any, of radioactive waste may be generated during the fuel handling (e.g., smear papers or contaminated package material).

Any waste that is produced will be properly packaged and stored onsite until it can be shipped to a licensed disposal facility. I In the event the applicant must return assemblies to the fuel fabricator, all packaging and transport of fuel will be in accordance with 10 CFR 71. The l l

3 NAY17jjjg package will meet NRC approval requirements for normal conditions of transport and hypothetical accident conditions. No significant external radiation hazards are associated with the unirradiated assemblies because the radiation level from the clad fuel pellets is low and because the shipping packages must meet the external radiation standards in 10 CFR 71. Therefore, any shipment of unirradiated fuel by the applicant is expected to have an insignificant environmental impact.

In the unlikely event that an assembly (either within or outside its shipping container) is dropped during transfer, the fuel cladding is not expected to rupture. Even if the fuel rod cladding were breached and the pellets were released, an insignificant environmental impact would result. The fuel pellets are composed of a ceramic UO2 that have been pelletized and sintered to a very high density. In this form, release of UO 2 aerosol is highly unlikely except under conditions of deliberate grinding. Additionally, UO2 is soluble only in acid solution so dissolution and release to the environment are extremely unlikely.

All fuel handling activities will be in accordance with approved procedures to assure nuclear criticality and radiation safety. Safety will be further assured by the presence of redundant engineering safeguards. Therefore, the proposed fuel handling and storage activities are critically safe (see the Safety Evaluation Report supporting this license) and no environmental impacts from an accidental criticality are expected.

Conclusion Based upon the information presented above, the environmental impacts associated with new fuel storage at CPS, Unit 1, are expected to be insignificant. - Essentially no effluents, liquid or airborne, will be released and acceptable controls will be implemented to prevent a radiological accident. Therefore, in accordance with 10 CFR 51.31, a Finding of No Significant Impact is considered appropriate for this action.

Original signed br Kishore Kodati Kishore K. Kodali Uranium Process Licensing Section Uranium Fuel Licensing Branch Division of Fuel Cycle and Material Safety, NMSS,,, .

Approved by: - '

  • W. T. Crow, Section Leader
b. _ lII__b _ .N_________b__________

NAME:KKodali/as:SWyngarden:NKetzlach:VTharpe :WTCrow  :  :

DATE 5 /85 5 /85 5 '785 5 85 5/ /85 0FFICIAL RECORD COPY

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