ML20212E127

Notice of Amend to Coc GDP-2 for Portsmouth Gaseous Diffusion Plant

ML20212E127
Person / Time
Site:	Portsmouth Gaseous Diffusion Plant
Issue date:	10/23/1997
From:	Paperiello C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20212E118	List: ML20212E114 ML20212E120 ML20212E127
References
NUDOCS 9711030062
Download: ML20212E127 (10)

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i U.S. NUCLEAR REGULATORY COMMISSION NOTICE OF AMENDMENT TO  :

. CERTIFICATE OF COMPLIANCE GDP 2 FOR  :

THE U.S. ENRICHMENT CORPORATION  !

PORTSMOUTH GASEOUS DIFFUSION PLANT

- PORTSMOUTH, OHIO DOCKET 70 7002  ;

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 ar y effluents that may be released offsite; (2) there is no significant increase in individual or cumulative occupational radiation exposure; i

(3) there is no significant construction impact; (4) there is no significant increase in the potentie! foi c. Hiological or chemical consequences from, previously analyzed accidents; (5) the propot.ed chanf as 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.

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

. Safety and Safeguards,is prepared to issue an amendment to the Certificate of Compliance for the Portsmouth Gaseous Diffusion Plant (PORTS). The staff has prepared a Compliance Evaluation Report whicii provides details of the staff's evaluation. ,

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The NRC staff has determined that this amendment satisfies the criteria for a categorical exclusion in a::cordance 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, requestin , review of the Director's Decir.lon. The petition must be filed with the

. Commission not later thn 15 days af ter publication of this Ecderal Renister 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 ma,* 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 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 amenc' ment application will become final in 60 days, unless the Commission grants the petition foi  : or otherwise acts within 60 days after publication of this Endcal Reaister Notice.

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i A petition for review must be filed with the Secretary of the Commission, U.S. Nuclear Regulatory Commission, Washington, DC 20555 0001, Attention: Rulemakings and Adjudications Staff, 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 Street, NW, Washington, DC, and at the Local Public Document Room.

Date of amendment request: June 9,1997 Brief description of amendment: The proposed amendment,in accordance with a ,

commitment made in the USEC certificate application, revises Technical Safety Requirement (TSR) 2.1.3.5 entitled " Autoclave Shell High Pressure Containment Shutdown," to account for the added capability to separately test inner and outer loop containment valves on autoclaves in buildings X 342, X 343, and X 344.

The Portsmouth Caseous Diffusion Plant uses thirteen autoclaves in buildings X-342, X 343 and X 344 to feed, transfer and sample UF. These autoclaves were designed and constructed in accordance with ASME Section Vill and are utilized to confine UF6 and any 1

reaction products in the event of a major UF, release inside an autoclave. Steam used to heat a UF cylinder within an autoclave is typically controlled at approximately 5 psig.

'However,if a large UF release occurs inside an autoclave, its internal pressure could rise-

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4 to as high as 90 psig very rapidly. To ensure that the contents of a release are confined inside the autoclave, except for that which is roused due to the proper operation of the autoclave pressure relief system (rupture disc rated at r.*ar 150 psig and relief valvel, each ,

t line which penetrates the autoclave boundary is equipped s ith at least two valves that can serve as isolation valves. These close automatically to isolate the autoclave in the event of high internal pressure; the actuation pressure being less than or equal to 15 psig.

As noterlin the Description of Noncompliance for Issue 3 of the " Plan for Achieving Compliance with NRC Regulations at the Portsmouth Gaseous Diffusion Plant" Revision 3 (Compliance Plan) dated July 9,1996, the capability to pressure decay test the autoclave containment valves (i.e., inner and outer loop valves) separately did not exist. According to item 1 of the Plan of Action and Schedule (POA) for issue 3 of the Compliance Plan, USEC was committed to providing this capability before July 1,1997, and submitting to the NRC, a revised TSR to reflect the new autoclave containment valve configuration, in addition, the POA stated that until the capability to separately test the inner ar.d outer loop containment valve is provided, the applicable TSR requirement will be to declare an autoclave inoperable and taken out of service when,in any mode of operation, either containment valve is determined to be inoperable or, in the heating mode, either pressure instrument channelis determined to be inoperable. According to USEC's certificate amendment request, since this capability has been provided, the Action conditions of TSR 2.1.3.5 thould allow comp etion of the current operating cycle if only one instrument channel, or one containment isolation valve on one or more autoclave penetrations, is operable. However, if both instrument channels or all containment isolation valves on any

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5 one autoclave penttration are Inoperable, then TSR 2.1.3.5 requires USEC to shut down the autoclave within one hour.

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.

Each line penetration for the thirteen autoclaves at PORTS, has at least two valves, that when actuated, would isolate the autoclaves, in addition, each autoclave has, as part of the autoclave shell high pressure containment shutdown system, two independen. high pressure containment actuation channels. The proposed change to TSR 2.1.3.5 allows completion of the current autoclave operating cycle if one instrument channel, or one containment isolation valve on one or more autoclave penetrations, is inoperable, it is noted that the proposed TSR 2.1.3.5 still requires at least two channels and two isolation valves on each autoclave penetration to be operable prior to initiating a new operating cycle. Allowing an autoclave cycle to be completed, with one instrument channel and one containment valve operable, instead of requiring it to be shut down within one hour, will not result in a change in the types or significent increase in the amounts of any effluents that may be released offsite for the taasons given in the following paragraph.

The UF. containment boundaries provided by the cylinder, pigtail and valves inside an autoclave, and steam and UF, reaction product confinement boundaries provided by the

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6 autoclave shell and piping and valves out to and including the second containment valve, are designated as "Q" systems. As such, USEC is required to apply the highest level of quality control (ASME NOA-1) to ensure that the pressure boundarios within these systems are maintained. Taking into consideration the applicable safety features (administrative and installed hardware) for preventing and mitigating UF, releases associated with auton.es, and past operational history at PORTS, the staff concludes that a major accidental release of UF. Inside an autoclave is highly unlikely. The probability of inoperability of a containment valve or an instrument channel during an operating cycle is also low (none have been reported since March 3,1997). According to the surveillance requirements of TSR 2.1.3.5, these containment valves are required to be calibrated semiannually at or below '5 psig, and to be quarterly functionally tested and separately pressure Jacay tested at 90 psig with an acceptable leak rate of 10 psig/ hour or 12 standard cubic feet per minuto, it should be noted that requiring an autoclave to prematuroly shut down prior to completing an operating cycle could introduce added risk by necessitating additional handling of cylinders containing liquid UF for feed, camplmc and transfer autoclaves, or by introducing cascade process upsets for feed autoclaves.

The staff has concluded that since completing the current operating cycle followir.g inoperability of one instrument channel or one containment valve on an autoclave penetration will not significantly increase the risk of a UF, release, this amendment will not result in c significant change in the types or significant increase in the amounts of any effluents that rnay be released offsite.

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

For the reasons provided in the assesstnent of criterion 1, the proposed amendment will-f not significantly increase the risk of a UF. releasa. Therefore, allowing an autoclave cycle to be completed,instead of requiring it to be shut down within one hour after discovery of one inoperable instrument channel or containment valve, will not result in a significant increase in individual or cumulative occupational radiation exposures.

3. The proposed amendment will not result in a significant construction impact.

The proposed amendment does not involve 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.

For the reasons provided in the assessment of criterion 1, the proposed amendment will l not significantly increase the risk of a UF. release. Therefore, allowing an autoclave cycle to be tc ited, instead of requiring it to be shut down within one hour af ter discovering one inoperable' instrument che.nnel or containment valve, will not significantly' increase the

- potentlal for,' or radiological or chemical consequences from, previously analyzed accidents.

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

Based on the staff's review of the proposed amendment, no new or differ 3nt accidents

- were identified.

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

For the :casons provided in the assessment of criterion 1, the proposea amendment will not significantly increase the risk of a UF release. Based on the staff's review of the proposed amendment, the staff concludes that there will be no significant reduction of any margin 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, For similar reasons provided in the' assessment of criterion 1, the proposed amendment will not significantly increase the risk of a UFe release. In addition, the staff has not ider*tified

- any criticality related implications from the proposed amendment. Based on the staff's L

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4 review of the proposed amenenent, the staff concludes that there will be no dccrease in the effectiveness of the overall plant's safety program.

The staff has not identified any safeguards or security related implications from the proposed amendment. Therefore, the proposed amendment will not result in an overall decrease in the effectiveness of the plant's safeguards, or security programs.

Effective date: The amendment to GDP-2 will become effective 60 days after issuance by NRC.

Certificate of Compliance 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 at Rockville, Maryland, thisfp day of A1997.

FOR THE NUCLEAR R5EGULATORY COMMISSION Carl J. Paperiello, Director

- Office of Nuclear Material Safety and Safeguards DISTRIBUTION:

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

• SEE PREVIOUS CONCURRENCE ceuxwtwoctosta i4. iss OFC SPB' SPB' SPB' SPB* FCSS* NMyp . ,

NAME YFaraz:ij DHoadley DMartin RPierson ETenEyck Chdello DATE 9/2b/97 10/1/97 10/3/97 10/3/97 / /97 10/10/97 (f//897 C = COVtR E = COVRM & ENCLOS JRE N = NO COPY G:\lNOTFR.YHF OFFICIAL RECORD COPY.

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,' review of the proposed amendment, the staff conc!udes that there.will be .o decrease in

- the effectiveness of the overall plant's safety program.

The staf f has not identified any safeguards or security related implications from the proposed amendment. Therefore, the proposed amendment w not result in an overall decrease in the effectiveness of the plant's safeguards, or ocurity programs.

Effective date: The amendment to GDP 2 will be om effective 60 days af ter issuance by ,

- NRC.

. Certificate of Compliance No. GDP 2: Amen .ient will revise the Technical Safety Requirements.

Local Public Documer'. Room location: F,brtsmouth Public Library,1220 Gallia Street, ,

~ Portsmouth, Ohio 45662.

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 7002. N C FILE CENTER PUBLIC NMSS r/f NMSS Dir. Off r/f FCSSr/f IPB r/f K'OBrien, Rlli CCox WSchwink, FCOB /PHiland, Rlli DHartland, Rill

'See previous con (urrence /[

OFC SPB C, jiPB' l6 SPB, [ SPp FCSh NMSS NAME - YFaralk )Noadley ' h) tin hrson ETenkyck CPaperiello DATE 9 /4/97,/  !#/ l /97' /0/3/97 h M97 / /97 , 10 /l# 9 7 / /97 C = COVtn / E = COVun & ENGLO SURE N =- NO COPY

' G:\lNOTFR.YHF ' _ OFFICIAL RECORD COPY 4