ML20149G877

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Notice of Amend to Coc GDP-1 for Us Enrichment Corp,Paducah Gaseous Diffusion Plant,Paducah,Ky
ML20149G877
Person / Time
Site: 07007001
Issue date: 07/15/1997
From: Paperiello C
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20149G840 List:
References
NUDOCS 9707240109
Download: ML20149G877 (6)


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7590-01 U.S. NUCLEAR REGULATORY COMMISSION NOTICE OF AMENDMENT TO CERT 1FICATE OF COMPLIANCE GDP-1 FOR l THE U.S. ENRICHMENT CORPORATION  ;

l PADUCAH GASEOUS DIFFUSION PLANT PADUCAH, KENTUCKY l l

DOCKET 70-7001 1

The Director, Office of Nuclear Mate ial Safety and Safeguards, has made a )

I determination that the lollowing amendment request is not significant in accordance with l 10 CFR 76.45. In making that determination, the staff concluded that: (1) there is no change in the types or significant increase in the amounts of any effluents that may be l

.eleased offsite; (2) there is no significant increase in individual or cumulative occupational I radiation exposure; (3) there is no significant construction impact; (4) there is no significant increase in the potential for, or radiological or chemical consequences from, previously analyzed accidents; (5) the proposeo changes do not recu!: in the possibility of a new or different kind of accident; (6) there is no significant reduction in any margin of safety; and (7) the proposed changes will not result in an overall decrease in the effectiveness of the plant's safety, safeguards or security program,s. The basis for this determination for the amendment request is shown below.

The NRC staff has reviewed the certificate amendment application and concluded that it provides reasonable assurance of adequate safety, safeguards, and security, and compliance with NRC requirements. Therefore, the Director, Office of Nuclear Material Safety and Safeguards, is prepared to issue an amendment to the Certificate of Compliance for the Paducah Gaseous Diffusion Plant. The staff has prepared a Compliance Evaluation Report which provides details of the staff's evaluation.

9707240109 970715 PDR ADOCK 07007001 C PDR i

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The NRC staff has determined that this amendment satisfies the criteria for a

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categorical exclusion in accordance with 10. CFR 51.22. Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared for this amendment.

t USEC or any person whose interest may be affected may file a petition, not exceeding 30 pages, requesting review of the Director's Decision. The petition must be filed with the Commission not later than 15 days after publication of this Federal Regist.e r Notice. A petition for review of the Director's Decision shall set forth with particularity the interest of the petitioner and how that interest may be affected by the results of the decision. The petition should specifically explain the reasons why review of the Decision should be permitted with particular reference to the following factors: (1) the interest of

, the petitioner; (2) how that interest may be affected by the Decision, including the reasons why the petitior.er should be permitted a review of the Decision; and (3) the petitioner's

. areas of concern about the activity that is the subject matter of the Decision. Any perron descr: bed in this paragraph (USEC or any person who filed a petition) may file a response to any petition for review, not to exceed 30 pages, within 10 days after filing of the petition.

If no petition is received within the designated 15-day period, the Director will issue the final amend' ment to the Certificate of Compliance without further delay. If a petition for review is received, the decision on the amendment application will become final in 60 days, unless the Commission grants the petition for review or otherwise acts within 60 days after publication of this Federal Register Notice.

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. . 3 A petition for review must be filed with the Secretary, U.S. Nuclear Regulatory

  • Commission, Washington, DC 20555-0001, Attention: Rulemakings and Adjudications '

s Staff,'or may b'e delivered to the Commission's Public Document Room, the Gelman '

- . Building, 2120 L Street, NW, Washington, DC, by the above date.

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~ For further details with respect to the action see (1) the application for amendment and (2) the Commission's Compliance Evaluation Report. These items are available for -

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public inspection at the Commission's Public Document Room, the Gelman Building, 2120 l-

--L Street, NW, Washington, DC, and at the Local Public Document Room.

Date of amendment request: March 17,1997, as revised June 19,1997 ,

t .l l Brief description of amendment: The amendment proposes to revise the Technical Safety Requirements (TSRs) for the Nuclear Material Control and Accountability (NMC&A) scales used for uranium hexafluoride cylinder weight to allow the pre-heat cylinder weight to be determined on any operable accountability scale that has been calibrated to an adequate range and tolerance for the item being weighed. Similar changes are proposed for the Safety Analysis Report (SAR).

Basis for finding of no significance:

1. The proposed amen'dment will not result in a change in the types or significant increase in the amounts of any effluents that may be released offsite.

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4 The proposed change involves revision of the NMC&A scale usage TSRs to permit l

weighing on any operable scale instead of specified scales. Because there is no effluent i 1

l release associated with this change, the proposed changes will not affect the effluent. l

2. The proposed amendment will not result in a significant increase in individual or cumulative occupational radiation exposure.

The proposed changes do not relate to controls used to minimize occupational radiation exposures, therefore, the changes will not increase exposure.

3. The proposed amendment will not result in a significant construction impact.

The proposed changes will not result in any construction, therefore, there will be no construction impacts.

4. The proposed amendment will not result in a significant increase in the potential for, or radiological or chemical consequences from, previously analyzed accidents.

The proposed changes will allow any operable scate, instead of specified scales, to be used for weight verificatinn. The proposed changes do no affect the potential for or radiological or chemical consequences from previously evaluated accidents. l l

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5. The proposed amendment will not result in the possibility _ of a new or different kind of accident.

Changing the TSR requirements for the NMC&A scales allows any operable scale to

'be'used for weight verification prior to heating the uranium hexafluoride cylinder. The accident scenario of heating an overfilled cylinder has already been analyzed. The .

proposed changes wouid not create new operating conditions or new plant configuration

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that could' lead to a new or different type of accident.

6. The proposed amenoment will not result in a significant reduction in any margin of safety. 1 The margin of safety defined for heating cylindera ls the percent ullage or void space required to heat a cylinder. The ullage is not affected by this change. The proposed TSR will still require the use of operable scales, therefore, the ability to verify that the proper amount of utlage will be maintained during heating is not affected. Th change to allow any operable scale instead of a specified scale is to provide operational flexibility in case a scale is inoperable. These changes do not decrease the margins of safety.
7. The proposed amendment will not result in an overall decrease in the effectiveness of the plant's safety, safeguards or security programs.

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6 O Implementation of the proposed changes do not change the safety, safeguards, or

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.e ,. security programs. Therefore, the effectiveness of the safety, safeguards, and security programs is not decreased.

Effective date: The amendment to Certificate of Compliance GDP-1 becomaa effective 30 days af ter being signed by the Director, Office'of Nuclear Material Safety and Safeguards.

Certificate of Compliance No. GDP-1: Amendment will revise Technical Safety Requirements for the NMC&A scale usage and the SAR discussion on scale usage.

Local Public Document Room location: Paducah Public Library, 555 Washington Street, Paducah, Kentucky 42003.

FOR THE NUCLEAR REGULATORY COMMISSION OdginalsfgnedbyCarlJ.Papone!!o Carl J. Paperiello, Director Office of Nuclear Material Safety and Safeguards DISTRIBUTION:

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