ML20211C429

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Us NRC Notice of Amend to Coc GDP-1 for Us Enrichment Corp Paducah Gaseous Diffusion Plant,Paducah,Ky.Amend Will Revise Compliance Plan Issue 3,Action 7 on Autoclave Upgrades
ML20211C429
Person / Time
Site: 07007001
Issue date: 09/15/1997
From: Paperiello C
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20211C422 List:
References
NUDOCS 9709260205
Download: ML20211C429 (6)


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7500 01 U.S NUCLEAR REGULATORY COMMISSION NOTICE OF AMcNDMENT TO CERTIFICATE OF COMPLIANCE GDP 1 FOR THE U.S. ENRICHMENT CORPORATION PADUCAH GASECUS DIFFUSION PLANT

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The Director, Office of Nuclear Material Safety and Safeguards, has made a

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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 g 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

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1 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 possiFlity of a new or different kind of accident; (6) there is no significant reduct:on 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 ar endment request is shown below.

The NRC staff has reviewed the certificate amendment application and concluded that it provider reasonable assurance of adequate safety, safeguards, and security, and

c. mpliance 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. T..e staff has prepared a Compliance Evaluation R4 ort which provides details of the staff's evaluation.

9709260205 970915 PDR ADOCK 07007001 C PDR

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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 exceoding 30 pages, requesting review of the Director's Decision. The petition must be filed with the Commission not later than 15 days af ter publication of this fadrial Register Notice. A petition for review of the Director's Decision shall set forth with particularhy 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 f actors: (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 fila a response to any petition for review, not to exceed 30 pages, within 10 days af ter filing of the petition.

If no petition is received within the designated 15-day period, the Director willissue the final amendment to the Ceitificate of Compliance without further delay. If a petition for review is received, the decision on the amendmert 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 cederal Reaister 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 Staf f, 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 O

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

Date (,f amendment request: August 11,1997 Brief description of amendment: The amendment proposes to revise Compliance Plan issue 3. Action 7 whico provides for the modification of the C-360 autoclave controls to add a iow instrument air pressure switch to initiate containment upon loss of instrument air. Instead of adding a low instrument air pressure switch, USEC proposes to provide a second channel for high pressure containment that does not rely on instrument air. USEC also proposes to extend the due date from August 31,1997 to October 31,1997.

Basis for finding of no significance:

1. The proposed amendment will not result in a change in the types or significant

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, increase in the amounts of any effluents that may be released offsite.

The proposed change involves the High Pressure isolation and Steam Pressure Control Systems. The change will not affect the function of the system. Because there are no effluent releases associated with this change, the proposed change will not affect effluents.

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 building construction, only equipment modification, therefore, there will be no construction impacts.

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

The proposed changes will not increase the probability of occurrence or consequence of any postulated accident currently identified in the safety analysis report. The proposed

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' change will reduce the f ailure modes of the High Pressure isolation and Steam Pressure Control Systems. The extension of the completion date will not significantly increase the probability of an accident. The existing Justification for Continued Operation will remain in effect during the two month extension. There is no significant increase in the potential for or radiological or chemical consequences from previously evaluated accidents.

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

The function of the High Pressure Isolation and Steam Pressure Control systems will not be changed by the modifications. The proposed changes will not create any new or different type of accident.

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

The safety limit associated with the modifications remains unchanged. The proposed change will provide for two safety channels for initiating auteclave containment that do not relv on instrument air. 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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Implementation of the proposed changes do not chang 3 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 immediately after being signed by Die Director, Office of Nuclear Material Safety and Safeguards.

Certificate of Compliance No. GDP-1: Amendment will revise the Compliance Plan issue 3, Action 7 on the autoclave upgrades to extend the due date by two months and to allow for mechanical-electrical pressure switches instead of pneumatic switches.

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

Dated at Rockville, Maryland, this / ay of 1997.

FOR THE NUCLEAR REGULATORY COMMISSION Cricint . . CG ry Cd J. P390fi?I!G Carl J. Paperia..o, Director Office of Nuclear Material Safety and Safeguards DISTRIBUTION:

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