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Docket ID: [Docket No.: 70-27]
SUBJECT CATEGORY: BWX Technologies, Inc.; Environmental Assessment and Finding of No Significant Impact Related to Proposed Issuance of an Exemption From 10 CFR 70.24 Requirements
SUMMARY: BWX Technologies, Inc.,
Under U.S. Nuclear Regulatory Commission (NRC) license SNM42 and
the provisions of 10 CFR Part 70, Domestic Licensing of Special Nuclear
Material, BWX Technologies, Inc. (BWXT or the licensee) is authorized
to receive and possess special nuclear material for the research,
fabrication and assembly of nuclear fuel and related components at its
facility, located in Lynchburg, Virginia. Under this license, BWXT is
also allowed to receive, acquire, and transfer irradiated fuel (spent
nuclear fuel) at its facility. The NRC staff is considering the
issuance of an exemption to requirements of Title 10 of the Code of
Federal Regulations (10 CFR) Section 70.24, under a certain condition,
for the spent nuclear fuel storage areas at the BWXT site. If the NRC
decides to grant the exemption, then the license will be amended to incorporate a license condition to reflect
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the exemption. These actions would then allow BWXT to implement its
proposed method to meet the January 16, 2007, NRC Order (EA07011)
requiring BWXT to implement additional security measures at the BWXT
site. The licensee found that if these measures are taken, it would not
be in full compliance with the criticality monitoring requirements of
10 CFR 70.24. Granting this exemption would also allow BWXT to continue to store, in a safe configuration, spent nuclear fuel.
The NRC has prepared an EA in support of granting an exemption and
amending the license. Based on this EA, the NRC has concluded that a
FONSI is appropriate and, therefore, an environmental impact statement
(EIS) is not warranted. The NRC is also conducting a safety review of
the BWXT request for exemption. The results of the safety review will be documented in a separate Safety Evaluation Report.
II. Environmental Assessment
By letter, dated May 2, 2007, BWXT submitted its exemption request. On May 14, 2007, BWXT submitted, via email, a clarification that stated its current Environmental Report (ER), dated March 10, 2004, addresses the areas where spent nuclear fuel, previously used for research, is stored at the site.
The documents that were evaluated in preparing this EA included the NRC's EA for Renewal of License SNM42, dated August 2005, the current BWXT ER for Renewal of License SNM42, dated March 10, 2004, and the e mail from BWXT (Leah Morrell, May 14, 2007) stating, with respect to this exemption request, that the BWXT's ER, dated March 10, 2004, is the current ER.
The purpose of this EA is to assess the environmental impacts of the proposed exemption and associated license amendment. It does not approve the request. This EA is limited to the proposed exemption from the requirements of 10 CFR 70.24 in spent nuclear fuel storage areas, and any cumulative impacts on existing plant operations. The existing conditions and operations at the BWXT facility were evaluated, by the NRC, for environmental impacts in an EA for the renewal of the BWXT license. This assessment presents the information and analysis of the proposed actions for determining whether issuance of a FONSI is appropriate.
As a result of the events of September 11, 2001, the NRC has required heightened security measures for facilities that are authorized to possess special nuclear material. BWXT is one such facility. Following an evaluation, by BWXT, of ways to meet these required security measures, BWXT concluded that the best method to meet those measures would affect the current criticality monitoring system. Specifically, the implementation of BWXT's proposed method to implement the NRC Security Order (EA07011) would make the detection of a criticality challenging for the criticality monitoring systems located in each spent nuclear fuel storage area when the additional security measures imposed by EA07011 are in place. The additional security measures are not currently in place.
The proposed actions are: (1) The NRC granting an exemption to the
requirements of 10 CFR 70.24 in the spent fuel storage areas during the
period of time the licensee does not need to access the spent nuclear
fuel; and (2) the NRC issuing an amendment to the license reflecting
such an exemption. These actions would allow BWXT to continue to safely
store spent nuclear fuel in storage systems. This exemption would not
apply during the short and very infrequent periods during which access
to the stored material is required, or if BWXT no longer has spent
nuclear fuel at its licensed site. The proposed actions are in
accordance with the licensee's application dated May 2, 2007. Alternative to the Proposed Actions
The actions available to the NRC are:
1. Approve the exemption and associated license amendment as described; or
2. No action (i.e., deny the request and do not amend the license the noaction alternative.)
The affected environment for the proposed action and the
alternative is the BWXT site. The affected environment is identical to
the affected environment assessed in the EA, dated August 2005. A full
description of the site and its characteristics is given in the NRC's 2005 EA.
Environmental Impacts of the Proposed Action and the No Action Alternative
The NRC staff has completed its evaluation of the environmental impacts of the proposed action and concludes granting the licensee an exemption to the criticality monitoring requirements of 10 CFR 70.24 for the spent nuclear fuel storage system during periods when access to the spent nuclear fuel is not required; and would not increase the probability or consequences of accidents previously analyzed and would not affect facility radiation levels or facility radiological effluents. No changes are being made in the types of effluents that may be released offsite. There is no significant increase in the amount of any effluent released offsite. There is no significant increase in occupational or public radiation exposure. Therefore, there are no significant radiological environmental impacts associated with the proposed action.
With regard to potential nonradiological impacts, the proposed action does not have a potential to affect any historic sites because no previously undisturbed area will be affected by the proposed actions. The proposed action does not affect nonradiological plant effluents and has no other effect on the environment. Therefore, there are no significant nonradiological environmental impacts associated with the proposed action.
Accordingly, the NRC staff concludes that there are no significant
environmental impacts associated with the proposed action and, thus,
concludes that the proposed action will not have any significant impact
to the human environment. The proposed action does not alter the
previous National Environmental Protection Act findings made in approving the license renewal.
Environmental Impacts of the Alternative to the Proposed Action
As an alternative to the proposed action, the NRC staff considered denial of the proposed action (i.e., the noaction alternative). Denial of the exemption request would result in: (1) No associated license amendment: and (2) no change to current environmental impacts, as the denial would result in the criticality monitoring requirements of 10 CFR 70.24 continuing to be fully applicable. Thus, the environmental impacts of the proposed action and the alternative action are identical because the present or absence of a criticality monitor and alarm for the spent nuclear fuel that is safety stored has no impact on the environment.
In accordance with NUREG 1748, ``Environmental Review Guidance for
Licensing Actions Associated with NMSS Programs,'' the NRC staff consulted with other agencies regarding
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the proposed actions. These consultations were intended to provide
other agencies an opportunity to comment on the proposed actions, and
to ensure that the requirements of Section 106 of the National Historic
Preservation Act, and Section 7 of the Endangered Species Act were met with respect to the proposed actions.
The staff, on October 10, 2007, consulted with the Virginia Department of Environmental Quality (VDEQ) and the Virginia Department of Health (VDH). The VDEQ reviewed the draft and agreed with NRC's conclusion that no significant environmental impacts would result from this proposed action, if implemented. The VDH had technical questions regarding the criticality monitoring systems.
The staff has determined that consultation for Section 7 of the Endangered Species Act is not required because the proposed action does not involve construction or any other change in physical environment, therefore, will not affect listed species or critical habitat. Virginia Department of Historic Resources
The staff has determined that the proposed action does not have the potential to effect on historic properties because it does not involve construction or any other change in physical environment. Therefore, no further consultation is required under Section 106 of the National Historic Preservation Act.
On the basis of the EA, the NRC concludes that the proposed action will not have a significant effect on the quality of the human environment and that preparation of an EIS is not warranted. III. Finding of No Significant Impact
On the basis of this assessment, the Commission has concluded that
environmental impacts that are associated with the proposed action
would not be significant and the Commission is making a finding of no significant impact.
Preparers
J. Wiebe, Project Manager, All Sections
A. Snyder, Project Manager, Sections 1.0, 4.0 and 5.0.
List of References
1. BWXT. Request for Exemption from 10 CFR 70.24, Letter (May 2,
2007) to Director, Office of Nuclear Material Safety and Safeguards,
U.S. Nuclear Regulatory Commission, Lynchburg, Virginia: BWXT, Nuclear Products Division (confidential)
2. NRC. NUREG 1748, Environmental Review Guidance for Licensing
Actions Associated with NMSS ProgramsFinal Report. (August 2003) Washington, DC: NRC (ML032450279)
3. BWXT. Environmental Report for Renewal of License SNM42, March 10, 2004 (nonpublic)
4. BWXT. Email to NRC, Criticality Exemption, dated May 14, 2007 (ML073180015)
5. NRC. Environmental Assessment Related to the Renewal of License
No. SNM42. Docket 70027 (August 2005) Washington, DC: NRC. (ML071300450)
6. NRC. Email to VDEQ, Predecisional EA, dated October 9, 2007, (ML073180022)
7. NRC. Email to VDH, Predecisional EA, dated October 10, 2007, (ML073180034)
8. VDH. Letter to NRC, Response to Predecisional EA, dated October 24, 2007 (ML73180017)
9. NRC. Email to VDH, Additional Comments on Predecisional EA, dated October 31, 2007 (ML073180027)
10. VDH. Email to NRC, Response to Additional Comments on Pre decisional EA, dated October 31, 2007 (ML073180029)
11. VEQ. Letter to NRC, Response to Predecisional EA, dated October 17, 2007 (ML073230756)
Dated at Rockville, Maryland this 30th day of November, 2007.
For the Nuclear Regulatory Commission.
Kevin M. Ramsey,
Acting Chief, Fuel Manufacturing Branch, Fuel Facility Licensing
Directorate, Division of Fuel Cycle Safety and Safeguards, Office of Nuclear Material Safety and Safeguards.
[FR Doc. E723784 Filed 12607; 8:45 am]
BILLING CODE 759001P
FOR FURTHER INFORMATION CONTACT Amy M. Snyder, Fuel Manufacturing Branch, Division of Fuel Cycle Safety and Safeguards, Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, Mail Stop EBB2C40M, Washington, DC 205550001, telephone (301) 492 3225 and email ams3@nrc.gov.
14 CFR Part 39 40 CFR Part 52 14 CFR Part 71 33 CFR Part 165 50 CFR Part 679 47 CFR Part 73 26 CFR Part 1 40 CFR Part 180 33 CFR Part 117 50 CFR Part 17 44 CFR Part 67 50 CFR Part 648 14 CFR Part 97 40 CFR Part 63 33 CFR Part 100 50 CFR Part 622 50 CFR Part 660 26 CFR Part 301 44 CFR Part 65 39 CFR Part 111 40 CFR Part 300 6 CFR Part 5 40 CFR Part 271 47 CFR Part 64 40 CFR Parts 52 and 81 50 CFR Part 665 10 CFR Part 50 44 CFR Part 64 49 CFR Part 571 39 CFR Part 3020