ML20216F107
| ML20216F107 | |
| 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 | |
| ML20216F085 | List: |
| References | |
| NUDOCS 9804160419 | |
| Download: ML20216F107 (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 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 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 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 described below.
The Nuclear Regulatory Commission (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 which provides details of the staff's evaluation.
9804160419 980409
{DR ADOCK 07007002 PDR
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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 l
environmental impact statement or environmental assessment need be prepared for this l
amendment.
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USEC or any person whose interest may be affected may file a petition, not exceeding 30 pages, 1
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 Register 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 j 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 petitioner; (2) how I l 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 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 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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3 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 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, 1
Washington, DC, and at the Local Public Document Room.
Date of amendment request: February 27,1998 Brief description of amendment: The United States Enrichment Corporation (USEC) submitted a certificate amendment request for PORTS to add four facilities including the conversion shop and cleaning building (X-700), the maintenance and stores building (X-720), the chemical and engineering building (X-760) and the storage warehouse (XT-847) to Technical Safety Requirement (TSR) Section 2.8 entitled " Specific TSRs for X-710 Laboratory," and to delete the associated operational mode descriptions in TSR Section 2.8.1.
An NRC Inspector Followup Item, 70-7002/97-206-108, which was identified in an NRC nuclear criticality safety inspection report for PORTS dated September 29,1997, noted that no specific Criticality Accident Alarm System (CAAS) TSR existed for the X-700, X-720, X-760 and XT-847 f acilities even though fissile material operations (FMOs) involving greater than 700 grams of U235 at an enrichment equal to or greater than 1.0% U235 could be
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conducted in those facilities, and CAAS coverage was being provided. As such, USEC has proposed to apply the existing NRC-approved CAAS TSRs for X-710 in TSR Section 2.8, to l
X-700, X-720, X-760 and XT 847. In addition, USEC has proposed to delete the three l
operational modes described in TSR Section 2.8.1, namely (1) " General Analytical -
analyses of production, ES&H, waste management, technical support, maintenance / fabrication activities," (2) " Uranium Sampling - subsampling uranium
- hexafluoride," and (3) "Polybottle Operations - movement of polybottles to and from labs l
l and storage areas," since there are no specific operational modes associated with the TSRs l
for X-700, X-710, X-720, X-760 and XT-847.
Basis for finding of no significance:
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- 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 (1) adds the X 700, X-720, X-760 and XT-847 facilities to TSR Section 2.8 l
entitled " Specific TSRs for X-710 Laboratory," since similar FMOs are conducted in these l
facilities and (2) deletes the associated operational modes listed in T SR 2.8.1. This amendment would enhance safety by adding more rigor to CAAS operability in terms of maintenance, calibration, testing, etc., in the four additional facilities. Ir, addition, deleting the current operational modes in TSR 2.8.1, which do not apply to TSR 2.8.3.1 (CAAS TSR) since the CAAS is required to be operable at all times when more than 700 grams of U235 at an enrichment equal to or greater than 1.0% U235 is present in the facility, will
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l l have no significant safety impact. As such, this amendment will nu result in a 1
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 increase in individual or cumulative occupational radiation exposure.
For the reasons provided in the assessment of criterion 1, the proposed amendment 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.
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i 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, 1
or radiological or chemical consequences from, previously analyzed accidents. ;
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l For the reasons provided in the assessment of criterion 1, the proposed amendment will not result in a significant increase in the potential for, or radiological or chemical j 1
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consequences from, previoutly analyzed accidents. j l :
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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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For the reasons provided in the assessment of criterion 1, the proposed amendment will not t
l result in new or different kinds of accidents.
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! 6. The proposed amendment will not result in a significant reduction in any margin of 1
l safety.
l For the reasons provided in the assessment of criterion 1, the proposed amendment will not I
l result in a significant reduction in any margin of safety. l 2
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- 7. The proposed amendment will not result in an overall decrease in the effectiveness of j the plant's safety, safeguards, or security programs.
l For the reasons provided in the assessment of criterion 1, the proposed amendment will not result in an overall decrease in the effectiveness of the 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. l
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( Effective date: The amendment to GDP 2 will become effective sixty (60) days after issuance by NRC.
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Certificate of Compliance No. GDP-2: Amendment will revise PORTS TSR Section 2.8.
Local Public Document Room location: Portsmouth Public Library,1220 Gallia Street, Portsmouth, Ohio 45662.
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Dated at Rockville, Maryland, this day of 1998.
FOR THE NUCLEAR REGULATORY COMMISSION nrininal Signed By Carl J. Paperiello, Director Office of Nuclear Material Safety and Safeguards i
DISTRIBUTION:
Docket 70-7002 NRC FILE CENTER PUBLIC NMSS r/f NMSS Dir. Off. r/f FCSS r/f DMorey, FCOB K'OBrien, Rlli CCox JDavis, FCOB WSchwink, FDDand, Rlli DHartland, Rlli KWinsberg, OGC SPB r/f
- See previous concurrence CP/ PROOFED / APRIL S.1998 l
l OFC SPB *SPB SPB* SPB* FCSS* NMSS, a NAME YFaraz:ij DHoadley DMartin RPierson ETenEyck CPhr$ello DATE / /98 4/1/98 4/3/98 4/3/98 / /98 4/8/98 '// fl98 l C = COVER E = COVER & ENCLOSURE N = NO COPY G:%MD14FRN.POR OFFICIAL RECORD COPY 1
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Certificate of Compliance No. GDP-2: Amendment will revise PORTS TSR Section 2.8.
J Local Public Document Room location: Portsmouth Public Library,1220 Gallia Street, l
Portsmouth, Ohio 45662. I i
l l Dated at Rockville, Maryland, this day of 1998.
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FOR THE NUCLEAR REGULATO Y COMMISSION 1
Carl J. Paperiello, Dire or Office of Nuclear M erial Safety and Safeguards I
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DISTRIBUTION:
Docket 70-70 2 NRC FILE CENTER PUBLIC NMSS r/f NMSS Dir. Off. r/f FCSS r/f DMorey, FCOB K'OBrien, Rlli CCox JDavis, FCOB WSchwin FCOB PHiland, Rlli DHartland, Rill KWinsberg OGC SPB r/f
'See pr ious concurrence ////
OFC .S B d- *SPB SPB ,,[ S '8 7F SS , NMSS NAME. YFara DHoadley Nin R bibrson / .,Ehrbyck CPaperiello l -DATE 9/ E/98 4/1/98 ///3 /98 i/D /98 / /98 ! t'/ //98 / /98 C = COVER E = COVER & ENCLOSURE N = NO OPY G:\AMD14FRN.POR OFFICIAL RECORD COPY fj
T s.
7 Certificate of Compliance No. GDP-2: Amendment will revise PORTS TSR Section 2.8.
Local Public Document Room location: Portsmouth Public Library,1220 Gallia Street, Portsmouth, Ohio 45662.
l l Dated at Rockville, Maryland, this day of 1998.
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FOR THE NUCLEAR REGULATORY' COMMISSION l
l Carl J. Paperiello, Direct l Office of Nuclear Mate al Safety and Safeguards 1 l
I DISTRIBUTION:
Docket 70-7 2 NRC FILE CENTER PUBLIC NMSS r/f NMSS Dir. Off. r/f FCSS r/f DMorey, FCOB K'OBrien, Rlli CCox JDavis, FCOB WSchw' ,FCOB PHiland, Rlli DHartland, Rlli KWinsberg, OGC SPB r/f OFC iPB d. _ SPk b SPB SPB FCSS NMSS NAIGIE YFaraz MH adley DMartin RPierson ETenEsck CPaperiello DATE 4/ 1/98 h/ f/98 / /98 / /98 / /98 / /98 / /98 C = COVER E-- COVER & ENCLOSURE N = NO COPY G:\AMD14FRN.POR OFFICIAL RECORD COPY