Certificates of compliance: United States Enrichment Corp.— Paducah Gaseous Diffusion Plant, KY,

[Federal Register: September 1, 1998 (Volume 63, Number 169)]

[Notices]

[Page 46487-46489]

From the Federal Register Online via GPO Access [wais.access.gpo.gov]

[DOCID:fr01se98-105]

NUCLEAR REGULATORY COMMISSION

[Docket 70-7001]

Notice of Amendment to Certificate of Compliance GDP-1 for the U.S. Enrichment Corporation, Paducah Gaseous Diffusion Plant, Paducah, KY

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

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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 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 provides details of the staff's evaluation.

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

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 filedwith the Commission not later than 15 days after publication of this Federal Register 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 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 fileda 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 filedwith the Secretary, U.S. Nuclear 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.

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: May 13, 1998, revised August 12, 1998.

Brief description of amendment: The amendment proposes to revise two technical Safety Requirements (TSRs). USEC proposes to revise the quarterly surveillance for the calibration of the Criticality Accident Alarm System (CAAS) equipment in the product withdrawal facility to an annual calibration. This would require a revision to TSR 2.3.4.7. USEC also proposes to correct a cross reference contained in a Feed Facility TSR, TSR 2.2.4.4. The current TSR cross references a TSR for the Toll Transfer and Sampling Facility instead of the one for the Feed Facilities. The two TSRs contain identical requirements.

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 changes to revise a calibration frequency and correct a cross reference have no effect on the generation or disposition of effluents. Therefore, the proposed TSR modifications will not result in a change to the types or amount of effluents that may be released offsite.

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

   The proposed changes will not significantly increase any exposure to radiation. Therefore, the changes will not result in a significant increase in individual or cumulative radiation 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 change to TSR 2.3.4.7 revises the calibration frequency for the CAAS equipment. This change is consistent with the calibration requirements for the other facility CAASs. This change has no impact on the potential for or occurrence of an accident. TSR 2.2.4.4 is being revised to reflect the appropriate cross reference for the required action associated with this TSR and has no impact upon either the potential for an accident or the resulting consequences. Therefore these changes will not increase the probability of occurrence or consequence of any postulated accident currently identified in the safety analysis report.

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

   The proposed TSR modifications revise a surveillance frequency and correct an editorial error. The proposed changes will not create the possibility of a new or different type of equipment malfunction or a new or different type of accident.

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

   The proposed changes to the TSRs revise a calibration frequency for the product withdrawal CAAS and correct a cross reference in a TSR for the feed facilities and have no impact on the margin of safety. Therefore, 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.

   Implementation of the proposed changes do not change the safety, safeguards, or 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 becomes effective 30 days after being

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   signed by the Director, Office of Nuclear Material Safety and Safeguards.

   Certificate of Compliance No. GDP-1: Amendment will revise TSR 2.3.4.7 to change the calibration frequency from quarterly to annual and revise TSR 2.2.4.4 to correct a cross reference to another TSR.

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

   Dated at Rockville, Maryland, this 24th day of August 1998.

   For the Nuclear Regulatory Commission. Carl J. Paperiello, Director, Office of Nuclear Material Safety and Safeguards.

   [FR Doc. 98-23456Filed8-31-98; 8:45 am]

   BILLING CODE 7590-01-P