ML20199E638

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Notice of Amend to Coc GDP-2 for Us Enrichment Corp Porsmouth Gaseous Diffusion Plant Portsmouth,Oh
ML20199E638
Person / Time
Site: Portsmouth Gaseous Diffusion Plant
Issue date: 11/12/1997
From: Paperiello C
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20199E615 List:
References
NUDOCS 9711210269
Download: ML20199E638 (8)


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" U.S. NUCLEAR REGULATORY COMMISSION ' -

NOTICE OF AMENDMENT TO' UV -n- 2 CERTIFICATE OF COMPLIANCE GDP-2 FOR : 1 THE U.S. ENRICHMENT CORPORATION. "

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  • PORTSMOUTH GASEOUS DIFFUSION PLANT PORTSMOUTH, OHIO
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Tho DEector, Office of Nuclea'rg.Mat'eriel Safety and Safeguards, has,made a'determ: nation that. -

[the following amendhiant request is riot significant 5 accordance with 10pFR 76.45. In making .

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that d$ termination, 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 T.,hanges 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 described 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 s_ e , w , ,, - . .

ths Portsinouth Gaseous Diffusion Plant (PORTS) The staff has prepared a Compliance hvaluation Report which provides details of the staffs evaluation.

9711210269 971112 PDR ADOCK 07007002 C PDR

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%y.The e e. NRC staff, , y has determined that this amendment satistles the criteria for a catego

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, :einvironmental impact statement or environmental assessment need.be prepared for this .

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i gUSEC or any person whose interest may be affected may file a petition, not exceeding 30 -

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E page.slrequestjngfWiew of the Directors Decision..The petition'must be filed with the;

{Comrrission not later than 15 days after publication of this Federal Register Notice. A petition for review of the Directors 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 shou.d 1

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 petitioners areas of concem about the activity that is ths subject matter of the Decision.' Any person described 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 a:15. g Director willissue the final amendment to the Certificate of Compliance without further delay. If I

l c 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 filed with the Secretary of the Commission, U.S. Nuclear l Regulatory Commission, Washington, DC 20555 0001, Attention: Rulemakings and I

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  • Wor further details with respect to the action see:t (1) the application.for~ amen'mdment and,(2) the" e

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Date c,f amenoment requec June 16, its97 "

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= 1 Brief description of amendmen'.:: The proposed amendment, in accordane,e with a commitment f made in the USEC certificate application, adds an additional criticality safety program element x ,

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. to the list of elements cominitted to in Technical Safety Requirement (TSR) 3.11.1.

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Section 3/s nf the PORTS Safety Analysis Report (SAR) Revision 4 dated July 26,1996,

'summarites the upgrades required to bring the process facilities in compliance with the

, descrip' ions provided in SAR Chapter 3.: One of the upgrades involves the identification of r y . <m y, + ,

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Structures [ Systems and Components'(SSCs) and associated support systems required to ? _

_;e u . . . .. 1 .- -. . . o meet the nuclear cnticalitylmifety (NCS) double contingency principle.' These SSCs are also 1- -

referredh as AQ NCS.SSCon I By March 3l1997, USEC ~wis rhuired by issue 23 of the 2 L l L L n . I L : l - x _ -.. ..

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,1 Compliance Plan (DOE /ORO-2027/R3) submitted as part'of their certificate application, to-

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identify and dsEneate AQ NCS SSCs end their associated support systems.: According to -

1 USEC, this adtion has been completed. ' A commitment made in SAR Section 3.9.10 entitled L" Identification of Nuclear Criticality Safety SSCs," requires USEC to follow-up by revising TSR O

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f F s 3.11 1; to reflect identification of AQ NCS SSCs and their associated support s'ystemsJ As such, USEC has proposed to add a new fourth bullet to TSR 3.11.1 to state that the NCS V

prog,am will address the identification of SSCs c,nd support sy tems necessary to meet the v w '- 9~ ' i

double contingency principle.

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IB 'asts for finding of r o significan.ce: I

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.

This amendment adds an additional TSR commitment related to the PORTS NCS program by requiring identification of SSCs and support systems necessary to meet the doubh contingency principle. As such, it will not result in a significant change in the types or significant increase in the amounts of any effluents that may be released offsite.

2. The proposed amendment will not result in a significant increas9 in individual or cumulative occupational radiation exposure.

This amendment adds an additional TSR commitment related to the PORTS NCS program by requiring identification of SSCs and support systems necessary to meet the double contingency principle. As such, it will not result in a significant increase in individual or cumulative occupational radiation exposures.

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proposed amendment will not result in a significant construction impact;-

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radiological or. chemical consequences from, previously analyzed accidents.

This amendment adds an ndditional TSR commitment related to the PORTS NCS program by requiring identification of SSCs and support systems necessary to meet the double contingency principle. As such, it will not significantly increase the potential for, or radiological or chemical consequences from, previously analyzed accidents.

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

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- requiring identification of SSCs' and support systems necessary to meet the double contingency 1

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pdnciple.l As such, it will not result in new or different kinds of accidents.-

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k<'ElhYh:'[hWh,'n 4 , [ v 7,iThe proposed' amendment will not result in an overall decrease in the effectiveness of the plant's safetyi safeguards, or security programs.

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This amendrnent adds an additional TSR commitment related to the PORTS NCS program by requiring ident!fication of SSCs and support systems necessary to meet the double contingency ponciple~.? As such,4it will not result in an overall decrease in the effectiveness of the plant's safety program. On the contrary, this amendment may increase the effectiveness of the plant's

.NCS program. .

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iThe staff has not identified any safeguards or security related implications from the proposed 1 ,

"amendmentaTherefore, the proposed amendment will not result in an overall decrease in the

ieffectiveness of thE plant's safeguards, or security prdgrams.

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Effective date: The an.9ndmant to GDP-2 will become effective immediately after issuance by )

, .q NRC.

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Certificate of Complianca No. GDP 2: Amendment will revise the Technical Safety Requirements.

Local Public Document Room location: Portsmouth Public Library,1220 Gallia Street, Portsmouth, Ohio 45662.

Dated a Rockville, Maryland, this /fbay of A/0/ 1997.

FOR THE NUCLEAR REGULATORY COMMISS'ON Oficinst signW By Carl J. Paperiello, Director Office of Nuclear Material Safety ,

and Safeguards DISTRIBUTION:

, Docket 70-7002 NRC FILE CENTER PUBLIC NMSS r/f NMSG Dir. Off. r/f FCSS r/f SPB r/f K'OBrien, Rill CCox WSchwink, FCOB PHilead, Rlli DHartland, Rlli

  • SEE PREVIOUS CONCURRENCEor/psuxwsD/NOVERABEft 3.1997 OFC *SPB *SPB *SPB *SPB TCSS NMfp5P)/7 NAME YFaraz:ij DHoadley DMartin RPierson ETen Eyck C riello DATE 10/17/97 10/23/97 10/21/97 10/23/97 11/4/97 )/ //j97 / /97 C = COVER E = COVER & ENCLOSURE N = NO COPY GANCSFR.YHF ' OFFICIA1. RECORD COPY

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Ef fective date: The amendment to GDP-2 will become effective immediately after issu 'ce  ;,

by NRC.

Certificate of Compliance No GDP-2: Amendment will revise the Tec ical Safety Requirements.

Local Public Document Room location: Portsmouth Public rary,1220 Gallia Street, b Portsmouth, Ohio 45662.

Dated at Rockville, Maryland, this day o 1997.

F R THE NUCLEAR REGULATORY COMMISSION Carl J. Paperiello, Director Office of Nuclear Material Safety and Safegua,-ds DISTRIBUIlON:

Docket 70-7002 NRC FILE CENTER PUBLIC NMSS r/f NMSS Dir. Off. r/f  ;

FCSS r/f SPB r/f K'OBrien, Ritt CCox WSchwink, F OB PHiland, Rill DHartland, Rlli OFC SP! d ,SPB SPB [ SPB J FCSj NMSS NAME Faraz?PF8soadiev M#14 Rei#bn eTeMyck CPaperieiio ,

DATE  !/o //7 /97 58 /D/97 /8/N/97 0 / "I 7 / /97 J/ / h/97 / /97 C y/ COVER E = COVER & ENCLOSURE N = NO COPY-G:\NpSFR.YHF ' OFFICIAL RECORD COPY jp/47/ 7f,y G

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