ML20210F990

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

ML20210F990
Person / Time
Site:	07007001
Issue date:	07/28/1999
From:	Paperiello C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20210F982	List: ML20210F976 ML20210F986 ML20210F990
References
NUDOCS 9908020250
Download: ML20210F990 (6)

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• 7590-01 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 l 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 i significant increase in individual 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 chemical 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.

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 povides details of the staff's evaluation.

The NRC staff has determined that this amendment satisfies the criteria for a categorical 9900020250 990728 PDR ADOCK 07007001 C PDR

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. 2 exclusion in accordance with 10 CFR 51.22(c)(19). Therefore, pursuant to 10 CFR 61.22(b), no

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1 environmental impact statement or environmental assessment need t'o be prepared for this I amendment. j USEC or any person wnose 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 no'iater than 15 days after publication of this Federal Register Notice. A petition for reviev' 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 1

specifically explain the reasons why review of the Decision should be permitted with particular l 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 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 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.

A petition for review must be filed with the Secretary of the Commission, U.S. Nuclear i

Regulatory Commission, Washington, DC 20555-0001, Attention: Rulemakings and Adjudications Staff, or may be 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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3 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 Pubiic Document Room, the Gelman Building,2120 L Street, NW, Washington, DC, and at the Local Public Document Room.

Date of amendment request: March 1,1999 Brief description of amendment: The amendment proposes to revise the Technical Safety Requirements (TSRs) related to the audibility requirements for the criticality accident alarm systern (CAAS) at PGDP. It is related to the CAAS audibility upgrade modifications. The revision is necessary to ensure adequate TSR coverage during the modification and system changeover. This amendment also revises related sections in the Safety Analysis Report (SAR).

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.

The proposed change to the TSRs improves the performance and reliability of the CAAS at PGDP, and it does not involve any process which would change or increase the amounts of any i

effluents that may be released offsite. Therefore, the proposed change will not result in an l

increase in the amounts of effluents that may be released offsite or result in any impact to the environment.

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

The CAAS system does not prevent criticality, thus the possibility of a criticality occurring is not increased. The proposed change to the TSRs improves the performance and reliability of the CAAS which minimizes the consequences of a criticality accident. Therefore, the proposed change does not increase individual or cumulative occupational radiatior' e.yosure.

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

The proposed change to the TSRs reflects modifications associated with the CAAS upgrade, which has been planned as a part of Compliance Plan issues 46 and 50. The proposed change does not change the scope or expand the planned construction. Therefore, it does not result in a significant construction impact.

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 change to the TSRs improves the performance and reliability of the CAAS which minimizes the consequences of a criticality accident. The CAAS does not change any previously analyzed accidents and does not affect the possibility of occurrence of a criticality accident. Therefore, the proposed change does not result in a significant increase in the potential for, or radiological or chemical consequences from, previously analyzed accidents.

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

l The CAAS is an alarm system to warn peopiu of criticality events. It does not initiate or j contribute to an accident, and it is intended to mitigate the consequences of a criticality accident. The proposed change to the TSRs improves the performance and reliability of the i CAAS. Therefore, this change will not result in the possibility of a new or different type of accident.

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

l The proposed change to the TSRs improves the performance and reliability of the CAAS which i l

l j minimizes the consequences of a criticality accident. Therefore, the proposed change does not i

represent a reduction in any margin of safety.

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7. The proposed amendment will not result in an overall decrease in the effectiveness of the plant's safety, safeguards or security programs.

The proposed change to the TSRs improves the performance and reliability of the CAAS which minimizes the consequences of a criticality accident. Therefore, the overall effectiveness of the safety, safeguards, and security programs is not decreased.

Effective date: The amendment to Certificate of Compliance GDP-1 will become effective no later than 30 days after being signed by the Director, Office of Nuclear Material Safety and Safeguards.

6 Certificate of Compliance No. GDP-1: This amendment will revise the TSRs related to the audibility requirements for the criticality accident alarm system at PGDP and related sections in the SAR.

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

Dated at Rockville, Maryland, this 2 8 day of 1999.

FOR THE NUCLEAR REGULATORY COMMISSION

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Carl J. Paperiello, irector Office of Nuclear Material Safety and Safeguards 1