ML20141H737

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

ML20141H737
Person / Time
Site:	07007001
Issue date:	07/16/1997
From:	Paperiello C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20141H710	List: ML20141H706 ML20141H731 ML20141H737
References
NUDOCS 9708010121
Download: ML20141H737 (6)

Text

. . _ . .. _. _- -._ _. __ -- _ --__ _. _ _ _ _ .

w. . .

a 7590-01 U.S. NUCLEAR REGULATORY COMMISSION NOTICE OF AMENDMENT TO CERTIFICATE OF COMPLlANCE 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 followirg amendment request is not significant in accordance with 'O 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 individual or cumulative occupational radiation exposure; (3) there is ne 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 overali 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 provides reasonable assurance of adequate safety, safeguards, and security, and compliance with NRC requirements. Therefore, the Director, Office of Nuclear Material l

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 l Report which provides details of the staff's evaluation.

I i ""

! 9708010121 970716 PDR ADOCK 07007001 C PDR

' ~

]

i ,- ,

. 2 1 f .-

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

r i 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. (

1 i i 4 USEC or any person whose interest may be affected may file a petition, not exceeding 30 l pages, requesting redew of the Director's Decision. The petition must be filed with the

• Commission not later than 15 days after publication of this Federal Reaister Notice. A ,

i  !

petition for review of the Director's Decision shall set forth with particularity the interest of I l

4 l the petitioner and how that interest may be affected by the results of the decision. The i

l petition should specifically explain the reasons why review of the Decision should be ll 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 i

! 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 descrioed 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 Reaister Notice.

j

o _ s J. A im m **_ e_. ,.: p 3

A petition for review must be filed with the Secretary, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, Attention: Rulemakings and Adjudications Staff, or may he 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 l

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

4 Date of amendment request: October 31,1996, revised February 14, and June 16,1997 Brief description of amendment: The amendment proposes a new Technical Safety 4

Requirement for the autoclave manual isolation system in the feed facilities and makes the

. system a O system under the quality assurance program.

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.

TSR 2.4.4.13 is a new TSR to cover the autoclave manual isolation system installed for the s

feed facilities. This system provides a remote method of simultaneously isolating att the autoclaves in the facility in the event of an observed release of uranium hexafluoride from

.y. _ _ , . _ _ . _ _ _ _ . _ . . _ _ . . . _ . _ _ . _ - _ _ . _ _ _ _ . _ _ _ . _ . _ _ _

,f, -

l

. 4 from piping outside the autoclave. This new system enhances the operators ability to isolate the feed autoclaves in the event of a leak. As such, these changes have no impact l on plant effluents and will^not result in any impact to the environment.  !

l i 2. The proposed amendment will not result in a significant increase in individual or i

cumulative occupational radiation exposure.

l

! The proposed changes provide an enhanced ability to isolate the autoclaves in the event of I

a leak, thereby mitigating the consequences of a postulated accident. 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 building construction, therefore, there will be ,

no construction impacts.

4. The proposed amendment will"ot result in a significant increase in the potential for, or radiological or chemical consequences from, previously analyzed accidents.

The proposed changes enhance the operator's ability to isolate the feed autoclaves in the

-event of a leak in the piping outside the autoclave and affect no other equipment functions.

The autoclave manual isolation system is not involved in any precursor to an evaluated accident; therefore, the potential of occurrence of an evaluated event is unaffected. Tne ,

consequences of previously evaluated accidents are not increased.

.i

.4-5 e

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

' kind of accident.

The manual isolation system permits the simultaneous isolation of all the autoclaves in the l

affected facility. Autoclave isolation was previously performed individually. The changes affect the timing of autoclave isolation and create no new operating conditions or new plant configure %n Jiat c ould lead tn a new or different type of accident.

i

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

l The autoclave manual isolation system enhances the ability to isolate the feed autoclave in the event of a leak. 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, s

The proposed changes enhance the ability to isolate the feed autoclaves in the event of a leak. The changes do not affect any other equipment functions or administrative requirements. The cell trip function is not addressed in the safeguards and security programs. The effectiveness of the safety, safeguards, and security programs is not l

decreased.

, 7

. 6

', 'Effectiva date: This amendmant to Certificate of Compliance GDP-1 becomes effective 60 days after being signed by the Director, Office of Nuclear Material Safety and Safeguards. I 1

Certificate of Compliance No. GDP-1: Amendment willincorporate a new Technical Safety Requirement and safety analysis report changes. ]

i I

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

, Dated at Rockville, Maryland, this lh y of bf l 997.

4 FOR THE NUCLEAR REGULATORY COMMISSION

" Origine]signedbyCarlJ.Pc#do Carl J. Paperiello, Director Office of Nuclear Material Safety and Safeguards J

DISTRIBUTION:

NRC FILE CENTER PUBLIC NMSS r/f FCSS r/f SPB r/f K'OBrien, Rlll CCox, Rlll NMSS Dir. Off. r/f PHiland, Rlll A:\FRNAMD2. PAD OFC SPB C QPB [ QP,4 , SPB_ FCh NMSS. //

NAME bHorn:ij )%badley haYtin Rhdon ETekEyck Cdhbilo DATE 9 /7/97 1 /0 /97 N/97 ~) /lb7 7 /)/97 7 / /40 7 C = COVER E = COVER & ENCLO3URE N = NO COPY OFFICIAL RECORD COPY