ML20216D801
| ML20216D801 | |
| Person / Time | |
|---|---|
| Site: | Portsmouth Gaseous Diffusion Plant |
| Issue date: | 04/09/1998 |
| From: | Paperiello C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20216D783 | List: |
| References | |
| NUDOCS 9804160011 | |
| Download: ML20216D801 (9) | |
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7590-01 U.S. NUCLEAR REGULATORY COMMISSION NOTICE OF AMENDMENT TO CERTIFICATE OF COMPLIANCE GDP 2 FOR THE U.S. ENRICHMENT CORPORATION PORTSMOUTH GASEOUS DIFFUSION PL\NT PORTSMOUTH, OHIO DOCKET 70-7002 f
The Commission made a determination tnat the following amendment request is significant in accordance with 10 CFR 76.45. Notice of Receipt of Amendment Requent appeared in the i
Federal Register on January 5,1998, allowing a 30-day public comment period on the application. No public comments were received.
l The Nuclear Regulatory Commission (NRC) staff has reviewed the certificate amendment application and concluded that it provides reasonable assurance of adequate safety, safeguards, l and security, and campliance 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. The staff has prepared a Compliance l Evaluation Tepon which provides details of the staffs evaluation.
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The Commission has determined that this amendment satisfies the criteria for a categorical j 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 araendment.
United States Enrichment Corporation (USEC) or any person whose interest may be affected, and who submitted written comments in response to the Notice on the amendment application, 9804160011 900409 PDR ADOCK 070070C2 C PDR
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'under 976.37, 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 i of this Federal Register Notice. A petition for rev:ew of the Director's Decision shall set fodh with l
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 factors: (1) the interest of the l
l petitioner, (2) how that interest may be affected by the Decision, including the reasons why the l petitioner should be permitted a review of the Decision; and (3) the petitioner's areas of concem about the activity that is the subject matter of the Decision.
Any person described in this paragraph may file a response to any petition for review, not to exceed 30 pages, within 10 days after filing of the podlion. If no petition is received within the j l
designated 15-day period, the Director will issue the final amendment to the Certificate of l
l Compliance without further delay. If a petition for reviev, 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.
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- 1 i A petition for review must be filed with the Secretary of the Commission, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0031, Attention: Rulemakings and Adjudications Staff, or l may be delivered to the Commission's Public Document Room, the Gelman Building,2120 L 1
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 Street, NW, Washington, DC, and at the Local Public Document Room.
3 Date of amendment request: February 25,1997 Brief description of amendment: On February 25,1997, USEC submitted a request to provide for an additionalidentified criticality accident case fu the X-333 cascade building related to the previously approved increase in assay limit to 3 percent. The operation at increased assay creates conditions where the location of an inadvertent nuclear criticality event might be closer to the X-333 Area Control Room (ACR-1), thus producing higher potential doses to personnel at l that location. It should be noted that this hypothetical accident case was identified by USEC after the NRC approved USEC's initial certificate application in November 1996. It should also be noted that the increase in the X-333 assay limit was approved by the NRC as part of the initial certification of PORTS. For this hypthetical a :cident case, an estimate is maJe that personnel in ACR-1 could, under the conservative assumption that they remained in ACR-1 for 50 n.inutes l
p despite the likely criticality alarm, receive a dose of 49 rem and not 0.005 rem as is currently ;
indicated in the Accident Analysis section of the PORTS Safety Analysis Report (SAR). Based l
on an initial review of the amendment request, the NRC staff feels that sufficiently adequate 4 safety controls are currently in place at PORTS to prevent and mitigate this accident. Therefore, other than the proposed modification to the PORTS SAR, this amendment would likely not require any other changes to plant operations.
Effective date: The amendment to Certificate of Compliance GDP-2 will become effective 60 l
days after issuance.
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., 4 Certificate,of Compliance No GDP-2: Amendment will revise the consequences of a criticality accident in the X-333 cascade building in the Safety Analysis Report.
Local Public Document Room location: Portsmouth Public Library,1220 Gallia Street, Portsmouth, Ohio 45602.
Dated at Rockville, Maryland, this d day of pbL1998.
FOR THE NUCLEAR REGULATORY COMMISSION Oficinal ggned By Carl J. Paperiello, Director Office of Nuclear Material Safety and Safeguards DISTRIBUTION:
Docket 70-7002 NRC FILE CENTER PUBLIC NMSS r/f FCSS r/f SPB rif PHiland, Rlll DHartland, Rlli NMSS Dir. Off. r/f DDamon, FCLB YFaraz WSchwink,FCOB KO' Brian, Rlll
- See previous concurrence CP/ PROOFED / APRIL 7.1999 OFC SPB* SPB* SPB* SPB* FCSS* NMSS*
NAME CCox:ij DHoadley DMartin RPierson ETenEyck CPaperiello DATE 3/16/98 3/25/98 3/26/98 3/27/98 4/7/98 Y/9 /r/f '
C r COVER E m COVER & ENCLOSURE N = NO COPY OFFICIAL RECORD COPY c:\x333frn.por l
m i- i Mr. James H. Miller j
'ce President, Production U. . Enrichment Corporation 2 De ocracy Center 6903 kledge Drive Bethesda, D 20817
SUBJECT:
RTIFICATE AMENDMENT REQUEST - PORTSMOUTH GASEOUS DIF SlON PLANT ADDITIONAL HYPOTHETICAL CRITICALITY SCENARIO DOS OR BUILDING X-333 (TAC NO. L32014) j
Dear Mr. Miller:
l Enclosed is a copy of the pliance Evaluation Report prepared to support the amendment of Certificate of Compliance DP-2. A copy of the Notice of Amendment, which has ]
been forwarded to the Office of the Federal R ister for publication, is also enclosed. This notice provides the opportunity for the public to pet n for review of the decision in accordance with 10 CFR Part 76, Subpart C. Final action on your a ndment request will not be taken until after the time allowed for requesting review of the Director's ision is over. If you have any questions regarding this action, I can be reached at (301) 415-675 .
Sincerely, l
l Charles R. Cox, Mechanical Svatems Eng er l Enrichment Section ,
Special Projects Branch Division of Fuel Cycle Safety and Safeguards, NMSS Docket 70-7002 i Certificate GDP-2 l cc: Mr. Steven A. Toalle, USEC Mr. Randall M. DeVault, DOE
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Enclosures:
- 1. Compliance Evaluation Report I
- 2. Notice of Amendment i DISTRIBUTIQN (ControlNo. 060S)
Docket 70-7002 NRC File Center PUBUC NMSSr# FCSS r#
WSchwink. FCOB SPB r# OGC PHiland, Ritt DHartland, Rill DDemons. FCLB OFC SPB SPB B SPB, SlH/)
l NAM CCox 1l YFarar $ ioedley rtin f DATE- / 198 3 /kI98 /98 Y /98 h /98 C = CO% ER . E = COVER & ENCLOSURE N = NO COPY )
a \w333cvit por OFFICIAL RECORD COPY
- . 2 Tha hypothyJeal criticality sc;ntrio involves Isaktga of wat air into th3 cascida producing a slow build-up of a UO2 F2 deposit. USEC has calculated that once criticality is achieved, the nuclear (eaction from such an event is a protracted pulse of 50 minutes duration. Personnel would only rbgelve the 49 rem dose if they remained in ACR-1 for the entire 50 minut-os. USEC estimates tha(the criticality alarm system would activate 10 minutes into the transient. This late detection is expected due to the low power levels early in this slow transient. Personnel evacuating at this 10 mi te point would have received only 5 rem.
Due to allowed higher enrichment levels in the X-330 cascade building, the same hypothetical criticality s nario could occur right above the ACR. The dose to personnelin the ACR from this i hypothetical 'ticality scenario would be 124 rem. Therefore, this type of accident with a higher dose had alreqy been identified as a possibility. The probability of such events, though, in i either the X-333 r the X-330 cascade buildings remains highly unlikely since these operations I are conducted in cordance with either the double contingency principle, where two unlikely, independent, and c current changes in process conditions would be required before a criticality accident would be po sible, or in accordance with the Technical Safety Requirement for operations where only single contingency is relied upon.
l A criticality event in the X- 3 cascade building has minimalimpact offsite. Figure 4.1.1-3, page 4.1-80, of the SAR indicates that a criticality of 2x10 " fissions cou!d produce as dose from ,
direct radiation of about 0.03 re{n at 1200 feet. At its closest point, the site fence line is over l 1000 feet from the X-333 cascace building. Thus the direct dose to any person offsite is small in comparison with NRC's public do limit in 10 CFR 20.1301.
The amendment application was detergninod to be significant pursuant to 10 CFR 76.45. That determination was based upon the incregse in consequences in ACR-1 from 0.005 rem to 49 ,
rem. A thirty day comment period was noticed on January 5,1998 in the Eedgr4Re9tsnAL{63 FR 274). No comments were received by the end of the comment period on February 5,1998.
ENVIRONMENTAL REVIEW lssuance of the requested amendment to the Ports uth Certificate of Compliance (GDP-2), to amend the SAR, Section 4.1.1.2.3.5, is subject to the tegorical exclusion provided in 10 CFR 51.22(c)(19) and will not have a significant impact on th uman environment. Therefore,in accordance with 10 CFR 51.22(b), neither an environment assessment nor an environmental impact statement is required for the proposed action.
CONCLUSION The estimates underlying the criticality dose calculations were revie ed by NRC staff and found to be reasonable and with a degree of conservatism consistent with t remainder of the accident analysis in the SAR. The increased consequences in the hyp etical criticality scenario for the X-333 cascade building are bounded by the same hypot gtical criticality scenario in the X-330 cascade building. The NRC staff feels that sufficiently adequate safety controls are current!y in place at PORTS to prevent and mitigate this accident. Other tha the proposed modification to the PORTS SAR, this amendment would likely not require any her changes to plant operations.1he NRC staff recommends approval of this amendment. Re 'on lil staff have no objection to this proposed action.
Princioal Contnbutors Chirles Cox Yawar Faraz Dennis Damon DISTRIBUTION Docket 70 7002 NRC FILE CENIER PUBUC NMSS rd NMSS Der On en FCSS r# b 'O rd CCox WSchwedt FCOR PHdand RW OHMant* RW OFC SPR SPR _.
SPR fb NAME C 11 YFarap ey "
a n son \
DATE h/h M ] /kM M ht M b tb M a us333cer con C = COVER E = COVER & 1NCLOSURE N e NO COPY
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LScal Public Document Room location: Portsmouth Public Library,1220 Gallia Street, t 1
Portsmou h, Ohio 45662.
! l Dated at Rockville, M land, this day of 1998.
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l FOR THE NUCLEAR REGULATORY COMMISSION q l
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) Carl .sPaperiello, s
Director l i Office of' Nuclear Material Safety !
and SafegDa(ds
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DISTRIBUTION: i l Docket 70-7002 NRC FILE CENTER PUBLIC NMSS r/f FCSS r/f SPB r/f PHiland, Rll! DHartland, Rill NMSS Dir. Off. r/f DDamon, FC '.B YFaraz WSchwink,FCOB KO' Brian, Rll! !
- See previous concurrence op/PRooraD/APRN. 7, t 999 OFC SPB* SPB* SPB* SPB* FCSS* NySS /) j NAME CCox:ij DHoadley DMartin RPierson ETenEyck a'pbello DATE 3/16/98 3/25/98 3/26/98 3/27/98 4/7/98 h/7/@f l C = COVER E = COVER & ENCLOSURE ,
N = NO COPY j OFFICIAL RECORD COPY c:\x333frn.por ;
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l l Certificate.of Compliance No. GDP-2: Amendment will revise the consequences of a criticality accident in the X-333 cascade building in the Safety Analysis Report.
' i Local Public Document Room location: Portsmouth Public Library,1220 Gallia Stree ,
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Portsmouth, Ohio 45662. I l
l Dated at Rockville, Maryland, this day of 1998.
l FOR THE NUCLEA EGULATORY COMMISSION l l
l Carl J. Pap iello, Director Office of clear Material Safety and S eguarda t I l
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l DISTRIBUTidN:
Docket 704002 NRC FILE CENTER PUBLIC NMSS r/f FCSS SPB r/f PHiland, Rlli DHartland, Rill NMSS Dir Off, r/f DDa n,FCLB YFaraz WSchwink,FCOB KO' Brian, Rll!
- See' previous concurrence OFC ' S3P SPB* SPB* SPB* FCSSf NMSS NAME CCox:ij DHoadley DMartin RPierson ETenkyck CPaperiello DATE 3/16/98 3/25/98 3/26/98 3/27/98 4/7/ / /
C = COVER E = COVER & ENCLOSURE N = NO COPY OFFICIAL RECORD COPY c:\x333frn.por
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Local Public Document Room location: Portsmouth Public Library,1220 Gallia Street, -
Portsmouth, Ohio 45662.
Dated at Rockville, Maryland, this day of 1998.
1 FOR THE NUCLEAR REGU TORY COMMISSION Carl J. Paperiello, irector l Office of Nucleaf aterial Safety and Safegua ds l
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! DISTRIBUTION Docket 70-7002 NRC / FILE CENTER PUBLIC NMSS r/f l FCSS r/f S4B r/f PHiland, Rlll DHartland, Rlli NMSS Dir. Off. r/f DDamon, FdLB YFaraz WSchwink,FCOB R p
OFC SPB ,SPB h SEp, [ SPl? hCSS NMSS NAME /CN:ij -hoadley M[rtin Rhiarson #ETenEyck CPaperiello DATE/ 38//[/
)h/ 7 78 S $1/ 96 // //
C = COVER E = COVER & ENCLOSURE N = NO COPY OFFICIAL RECORD COPY e:\x333fm.por g4 1