ML20134F873
| ML20134F873 | |
| Person / Time | |
|---|---|
| Site: | 07007001 |
| Issue date: | 02/04/1997 |
| From: | Paperiello C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20134F856 | List: |
| References | |
| NUDOCS 9702100191 | |
| Download: ML20134F873 (7) | |
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7590-01 l 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 [
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 i'
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 i 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 l 1
safety; and (7) the proposed changes will not result in an overall decrease in the i
effectiveness of the plant's safety, safeguards or security programs. The basis for this i i
determination for the amendment request is shown below.
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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.
9702100191 970205 PDR ADOCK 07007001 C PDR
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The NRC staff has determined that this amendment satisfies the criteria for a i I
categorical exclusion in accordance with 10 CFR 51.22. Therefore, nursuant to 10 CFR ]
51.22(b), no environmental impact statement or environmental assessment need be prepared for this amendment. j I
J 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 filed with the Commission not later than 15 days after publication of this Federal Reaister Notice. A petition for review of the Director's Decision shall set forth with particularity the l 1
interest of the petitioner and how that interest may be affected by the results of the i i
decision. The petition should specifically explain the reasons why review of the Decision
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should be permitted with particular reference to the following factors: (1) the interest of ;
I the petitioner: (2) how that interest may be affected by the Decision, including the reasons j l
why the petitioner should be permitted a review of the Decision; and (3) the petitioner's )
i areas of concern about the activity that is the subject matter of the Decision. Any person
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described in this paragraph (USEC or any person who filed a petition) may file a response l
to any petition for review, not to exceed 30 pages, within 10 days after filing of the I 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 finalin 60 days, unless the Commission grants the petition for review or otherwise acts within 60 days after publication of this Federal Reaister Notice.
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A petition for review must be filed with the Secretary of the Commission, U.S.
- l Nuclear Regulatory Commission, Washington, DC 20555-0001, Attention: Docketing and j Services Branch, or may be delivered to the Commission's Public Document Room, the . ,
3 Gelman Building, 2120 L Street, NW, Washington, DC, by the above date. ;
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! 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 L Street, NW, Washington, DC, and at the local public document room.
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Date of amendment request: September 30,1996 i l Brief description of amendment: The amendment changes the Technical Safety ;
Requirement for the cascade cell trip function and revises limiting specific values for f l
I battery performance, j l
i Basis for finding of no significance:
l l 1. The proposed amendment will not result in a change in the types or significant f f
l increase in the amounts of any effluents that may be released offsite. l l
l The proposed changes to TSR 2.4.4.12 and SAR section 3.9.1.3.2 provide limits )
for battery voltage and air circuit breaker air pressure, improve the surveillance )
requirements for measuring battery cell specific gravity, as well as improved bases for the i 3 l
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. i liinits. These changes provide improved assurance that the cell trip function will be available,if required. As such, these changes enhance the ability of the cascade trip 4
function to deenergize the process motors (" tripping the cell"), thus bringing the cell below l l
atmospheric pressure. By enhancing the ability to perform the cell trip function, the ability <
1 1 to mitigate the consequences of postulated accidents has been improved. As such, these changes have no impact on plant effluents and will not result in any impact to the environment. l 1
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- 2. The proposed amendment will not result in a significant increase in individual or cumulative occupational radiation exposure. l The proposed changes provide enhanced assurance that the cell trip function will be available if necessary. The changes will not increase exposure. )
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- 3. The proposed amendment will not result in a significant construction impact. l 4
i 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 changes enhance the availability of the cascade cell trip function and affect no other equipment functions. The cascade cell trip function is not involved in any 4
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. precursor to an evaluated accident; therefore, the potential of occurrence of en evaluated ;
I event is unaffected. The cell trip function is involved in the mitigation of the consequences of previously evaluated accidents by deenergizing the process motors, thus i bringing the cell below atmospheric pressure. Revising the limiting specific values n 't f i battery performance and the air pressure requirements for the "000" air circuit breakers enhances the ability of the cell trip function by ensuring that adequate DC voltage and air I
pressure are available to effect cell trip. Since the proposeo changes provide enhanced i
- assurance that the function will be available if required, the consequences of previously 1
l evaluated accidents are not increased. I
- 5. The proposed amendment will not result in the possibility of a new or different kind of accident.
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The proposed changes establish new operating limits for plant equipment that are j within the existing operating ranges of that equipment. The changes create no 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 minimum air pressures and battery voltages established by these proposed
- changes are within the existing operating ranges of the equipment and have bean increased to enhance the cell trip function, which is the only safety function affected by 5 ;
these par m;t:rs. Ths proposed chang:s caus3 no rsductions in tha margins of saf ty.
- 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 changes enhance the availability of the cascade cell trip function and 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 decreased.
Effective date: 60 days after issuance Certificate of Compliance No. GDP-1: Amendment will revise the Technical Safety Requirements.
Local Public Document Room location: Paducah Public Library, 555 Washington Street, Paducah, Kentucky 42003.
Dated at Rockville, Maryland, this h day of f 1997.
FOR THE NUCLEAR REGULATORY COMMISSION MMN Carl J. Paperiello, Director Office of Nuclear Material Safety and Safeguards DISTRIBUTION:
NRC FILE CENTER PUBLIC NMSS r/f FCSS r/f SPB r/f K'OBrien, Rlli CCox, Rlli NMSS Dir. Off. r/f G:\ AMEND 1FR.MLH 'See Previous Concurrence CMOOFEDTSRUARY $f 1997 OFC SPB' E SPB' E SPB OGC* E SPB E FCSS NMjp5 fl/)
NAME MHorn:ij DHoadley DMartin KWinsburg RPierson ETenEyck CPahekeIlo DATE 1/28/97 1/28/97 1/28/97 1/23/97 1/30/97 2/3/97 M/Y/97 C = COVER E = COVliR & ENCLO SURE N = NO COPY OFFICIAL RECORD COPY 6
these parcm:t:rs. The propos3d changis cause no raductions in the argins of s:f:ty.
- 7. The proposed amendment will not result in an erall decrease in the effectiveness of the plant's safety, safeguards or urity programs.
The proposed changes enhance the av lity of the cascade cell trip function and do not affect any other equipment func ns or administrative requirements. The cell trip function is not addressed in the sa guards and security programs. The effectiveness of the safety, safeguards, and se rity programs is not decreased.
Effective date: 60 ays after issuance Certificate f Compliance No. GDP-1: Amendment will revise the Technical Safety Requirement L al Public Document Room location: Paducah Public Library,555 Washington Stre , Paducah, Kentucky 42003.
ted at Rockville, Maryland, this day of 1997.
FOR THE NUCLEAR REGULATORY COMMISSION Carl J. Paperiello, Director Office of Nuclear Material Safety and Safeguards DISTRIBUTION:
NRC FILE CENTER PUBLIC NMSS r/f FCSS r/f SPB r/f K'OBrien, Rlll CCox, Rill G:\ AMEND 1 FR.MLH g ge,c, M r . AC s rle OFC SPB T3 SPB/7 g SPL ,
OGC 6 SPp , E FCSS/ NMSS NAMC MHor$}E NoNiey 'NltE u, ,, , L, , Rhson ETenkyck CPaperiello DATE 1 /;d97 / PA97 /?897 i/497 \ h/97 2 /3 /97 / /97 C = COVER E = COVER & ENCLO SURE N = NO COPY OFFICIAL RECORD COPY pff 6
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