ML20199L363

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

ML20199L363
Person / Time
Site:	07007001
Issue date:	11/25/1997
From:	Paperiello C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20199L355	List: ML20199L350 ML20199L359 ML20199L363
References
NUDOCS 9712020005
Download: ML20199L363 (7)

Text

_ _ _ _ .

l',

l: .

7590 01 U.S. NUCLEAR REGULATORY COMMISSION NOTICE OF AMENDMENT TO CERTIFICATE OF COMPLIANCE GDP 1 FOR THE U.S. ENRICHMENT CORPORATION PADUCAH GASEOUS Dll'FilSION PLANT PADUCAH, KENTUCKY DOCKE7 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 incrr,ase 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 potermal 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 complience 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.

9712020005 971125 l PDR ADOCM 07007001- J C PM.

2 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 environmentalimpact 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, requestoig review of the Director's Decision. The petition must be filed with the Commission not later than 15 days af ter 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 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 offected by the Decision, including the reasons why the petitioner should be pr.rmitted review of the Decision; and (3) the petitioner's areas of concern about the activity that is the subject matter of the Decision. Any per:on described in this paragraph (USEC or any person who filed a petitior.i 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 i= sue the final amendment to tho Certificate of Coinpliance without further delay, if a petition for review is received, the decision on the amendment application will becorre 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.

1

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

I For further details with respect to the action see (1) the application fsr amendment ard (I) the Commission's Compliance Evaluation Report. These stems are available for public inspection at the Commission's Public Document Room, the Gelman Building,2120 L Street, NW, Washington, L.C, and at the Local Public Document Room.

Date of amendment request: October 6.1997 Brief description of amendment: The amendment proposes to revise Technical Safety Requirement (TSR) 2.3.4.7 and TSR 2.4.4.2, Criticality Accident Alarm System (CAAS) for Product and Tails Withdrawal and Cascade Facili' - to provide a cross reference for the Required Acticos in order to assure all necessary Required Actions are performed when the C 310 CAAS is inoperable.

Basis for finding of no sigriificance:

\

~

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

l 4

. In the amounts of any efiluents that may be released offsite.

. The proposed changea are related to human f actors and do not change any requiremerits.

There are no associated effluent releasris. Thus, they will not affect any effluents that may be released offsite.

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

- cumt.,ative occupational radiation exposure.

The proposed changes do not change or add any new requirements. The changes provide a cross reference between TSRs to ensure all required actions are performed when necessary. The changes do not relate to controls used to minimize occupational radiation exposures; therefore, 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 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 eccidents.

The propored changes are administrative and serve only to relate the components of the

CAAS in C 310. The changes do not change the current TSRs, only link separate sections more clearly. Therefore, the proposed changes do no represent an increase in the potential for, or radiological or chemical consequences from, previously evaluated accidents.

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

The proposed changes to the TSRs do not add or change any TSR requirements.

Therefore, the changes would not create new operating conditions or new plant configuration that could lead to 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 attempt to rectify the situation in which an operator could overlook the linkage between the two TSRs that both contain required actions relatea to the CAAS.

By including a cross reference, the changes try to ensure all required actions are performed.

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

4 6

programs Therefore, the effectiveness of the safety, safeguards, and security programs is not decreased.

Effective date: The amendment to Certificate of Comp 4ance GDP-1 becomes effective 30 days after being signed by the Director, Office of Nuclear Material Safety and Safeguards.

Certificate of Compliance No. GDP-1: The Amerdment will provide cross references for two Technical Safety Requirements for the Criticality Accident Alarm System in Building C-310.

Local Public Document Room location: Paducah Public Library, 555 Washington Street, Paoscah, Ken'ucky 42003.

Dated at Rockville, Maryland, this2,6 day of oV. 1997.

FOR THE NUCLEAR REGULATORY COMMISSION Wnal Signed By Carl J. Paperiello, Director Office of Nuclect Material Safety and Safeguards DIS *RtBUTION:

Docket 70-7001NRC FILE CENTER PuSUC NMSS r/f FCSS r/f SPB t/f K'oBrien. Ritt NMSS Dir, off. r/f g:\frcrit. pad 'SEE PREVIOUS CONCURRENCE CP/PftOOFED/NOVEMBEft 34.1997 oFC SPB' SPB' SPB' SPB' SPB' FCSS' NIMS I NAME PPatel:i) DHoadley MHorn DMartin RPierson ETenEyck llo DATE 11/14/97 11/18/97 11/19/97 11/20/97 11/21/97 11/24/97 // /,jg7 C = COVER E = COVER & ENCLOSURE N = NO COPY OFFICIAL RECORD COPY l

9 e

-6

,= ... ,

programs. Therefore, the effectiveness of the safety, safeguards, and security programs is not decreased.

Effective date: The amendment to Certificate of Compliance GDPA becomes effective 30 days after being signed by the Director, Office of Nuclear Material Safety and Safeguards.

Certificate of Compliance No. GDP 1: The Amendment will provide cross references for two Technical Safety Requirements for the Criticality Accident Alarm System in Building C 310, t

Local Public Document Room location: Paducah Public Library, 555 Washington Street, 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 DISTRIBUTION

. Docket 70-7001 NRC FILE CENTER PuBUC NMSS r/f FCSSr/f SPB r/t K'OBrien, Rill NMSS oir. off. r/f c:\frcrit pad ' g//

oFC SPB b . SPB hp SPB C SPB SPB /1 Sh NMSS NAME PPatel:i oHoadley @ orn kin R on ETe Eyck CPaperiello DATE ll /tT97' ll 19 7 .If h197 / d[f"7 h 7 Ll. [M7 / /97 C = COVER E = COVER & Ei4 CLOSURE N = NO COPY OFFICIAL RECORD COPY

. . . .