ML20137K335

Notice of Amend to Coc GDP-1 for Us Enrichment Corp Paducah Gaseous Diffusion Plant Paducah,Ky

ML20137K335
Person / Time
Site:	07007001
Issue date:	03/27/1997
From:	Paperiello C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20137K317	List: ML20137K313 ML20137K319 ML20137K335
References
NUDOCS 9704070011
Download: ML20137K335 (8)

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U.S. NUCLEAR REGULATORY COMMISSION NOTICE OF AMENDMENT TO CERTIFICATE OF COMPLIANCE GDP-1 FOR THE U.S. ENRICHMENT CORPORATION PADUCAH GASEOUS DIFFUSION PLANT PADUCAH, KENTUCKY DOCKET 70-7001 The Director, Office of Nuclear Material Safety and Safeguards, has made a determination that the following amendment request is not significant in accordance with 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 released offsite; (2) there is no significant increase in individuct or cumulative occupational radiation exposure; (3) there is no significant construction impact: (4) there is no significant increase in the potential for, or radiological or chemiccl consequences from, previously analyzed accidents:

(5) the proposed changes do not result 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 programs. The basis for this determination for the amendment request is shown below.

I The NRC staff has reviewed the certificate amendment application and concluded that it j provides reasonable assurance of adequate safety, safeguards, and security, and compliance with NRC requirements. Therefore, the Director, Office of Neclear Material l

Safety and Safeguards,is prepered to issue an amendment to the Certificate of Compliance i

for the Padt.cah Gaseous Diffusion Plant. The staff has prepared a Compliance Evaluation Report which provides details of the staff's evaluation.

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The NRC staff has determined that this amendment satisfies the crheria for a categorical l

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

amendment.

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USEC or any person whose interest may be affected may file a petition, not exceeding 30 I

pages, requesting review of the Direct 's Decision. The petition must be filed with the l Commission not later than 15 days after publication of this Federal Reaister 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 i 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 petitioner should be permitted a review of the Decision; and (3) the petitioner's l l

areas of concern about the activity that is the subject matter of the Decision. Any person  !

described 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 amendment to the Certificate of Compliance without further delay. If a j

petition for review is received, the decision on the amendment application will become final 1 in 60 days, unless the Commission grants the petition for review or otherwise acts within

.60 days after publication of this Federal Reaister Notice.

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A petition for review must be filed with the Secretary of the Commission, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, Attention: Docketing and Services Branch, or may be delivered to the Commission's Public Document Room, the Gelman Building,2120 L Street, NW, Washington, DC, by the above date.

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 public inspection at the Commission's Public Document Room, the Gelman Building,2120 L Street, NW, Washington, DC, and at the Local Public Document Room.

Date of amendment request: February 14,1997, revised March 10,1997 Brief description of amendment: The amendment revises the Technical Safety Requirement for the design features for the cranes in the feed facilities and reflects the associated I

changes to the Safety Analysis Report.

i Basis for finding of no significance:

1. The proposed amendment 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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~ The proposed change to TSR 2.2.5.2 involves a change to the design features of the hoist brakes for the feed facility cranes. These changes have no impact on plant effluents and will not result in any impact to the environment.

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

The proposed design change for the brakes will not affect individual or cumulative occupational radiation expo <,ure.

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

The proposed change 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.

3 The proposed change involves a change to the description of the safety features on the feed facility cranes. The changes are being made to reflect the field configuration of the cranes. The brake design in question complies with the requirements of ANSI B30.2-1990 and will continue to perform its safety function. As such, the potential of occurrence of an

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evaluated event is unaffected. The consequences of previously evaluated accidents are not increased.

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

L The proposed changes revise the design feature for the brakes of the feed facility cranes to match the field configuration. The brakes meet ANSI B30.2-1990and will continue to meet their safety feature. The change does not create the possibility for a new or different ,

I type of accident.

6. The proposed amendment will not result in a significant reduction in any margin of safety.

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The brake designs for the cranes comply with the requirements of ANSI B30.2-1990. The TSR change is necessary to reflect the field configuration of the brakes. The accident analysis is not affected by this change. The proposed changes cause no reductions in 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 The oposed TSR change is being made to reflect the field configuration of the brakes'for the feed facility cranes. The effectiveness of the safety, safeguards, and security programs is not decreased.

Effective date: Upon issuance of amendment Certificate of Compliance No. GDP-1: Amendment will revise a Technical Safety Requirement on crane design and incorporate safety analysis report changes.

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

Dated at Rockville, Maryland, this d') day of 4(d1997.

FOR THE NUCLEAR REGULATORY COMMISSION  ;

Nd M By i

Carl J. Paperiello, Director Office of Nuclear Material Safety and Safeguards i

s DISTRIBUTION:

NRC FILE CENTER PUBLIC NMSS r/f FCSS r/f SPBr/f K'OBrien, Rlli CCox, Rlli NMSS Dir. Off. r/f '

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-.. l The proposed TSR change is being made to reflect the field configuration of the brakes for I l

the feed facility cranes. The effectiveness of the safety, safeguards, and security l programs is not decreased. f I

Effective date: upon issuance of amendment i Certificate of Compliance No. GDP-1: Amendmer't will revise a Technical Safety l Requirement on crane design and incorporate safety analysis report changes. l

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Local Public Document Room location: Paducah Public Library, E55 Washington Street,

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Paducah, Kentucky 42003.

Dated at Rockville, Maryland, this day of 1997.

FOR THE NUCLEAR REGULATORY COMMISSION Carl J. Paperiello, Director Office of Nuclear Material Safety and Safeguards N

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D$TRIBUTION:  !

. NRC FILE CENTER PUBLIC NMSS r/f FCSS r/f l SPSr/f K'OBrien, Rlli CCox, Rlli NMSS Dir. Off, r/f A:\FRNAMD4. PAD

'See previous concurrence

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i e proposed TSR change is being made to reflect the field configuratio the brakes for i the ed facility cranes. :The effectiveness of the safety, safegua , and security program is not decreased. l l

Effective date: u n issuance Certificate of Compliance .GDP : Amendment will revise a Technical Safety  !

Requirement on crane design incorporate safety analysis report changes.

1 Local Public Docu nt Room location: ducah Public Library, 555 Washington Street, Paducah, Ken cky 42003. l i

. Dated t Rockville, Maryland, this day of 1 7.

FOR THE NUCLEAR REG ATORY COMMISSION Carl J. Paperiello, Director Office of Nuclear Material Safety and Safeguards I

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I DISTRIBUTION

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