Calvert Cliffs Independent Spent Fuel Storage Installation Issuance of Environmental Assessment and Finding of No Significant Impact Regarding a License Amendment, 53812-53813 [05-17971]

Download as PDF 53812 Federal Register / Vol. 70, No. 175 / Monday, September 12, 2005 / Notices We will not officially file the plat until the day after we have accepted or dismissed all protests and they have become final, including decisions on appeals. Dated: September 1, 2005. Stephen D. Douglas, Chief Cadastral Surveyor. [FR Doc. 05–17975 Filed 9–9–05; 8:45 am] BILLING CODE 4310–GJ–P DEPARTMENT OF THE INTERIOR Bureau of Land Management [ES–960–1910–BJ–4789] ES–053725, Group No. 35, Missouri Eastern States: Filing of Plat of Survey Bureau of Land Management. Notice of Filing of Plat of Survey; Missouri. AGENCY: ACTION: SUMMARY: The Bureau of Land Management (BLM) will file the plat of survey of the lands described below in the BLM-Eastern States, Springfield, Virginia, 30 calendar days from the date of publication in the Federal Register. FOR FURTHER INFORMATION CONTACT: Bureau of Land Management, 7450 Boston Boulevard, Springfield, Virginia 22153. Attn: Cadastral Survey. SUPPLEMENTARY INFORMATION: This survey was requested by the U.S. Army Corps of Engineers. The lands we surveyed are: Fifth Principal Meridian, Missouri T. 48 N., Rs. 4 and 5 E. The plat of survey represents the survey of a portion of the Lock and Dam No. 26 acquisition boundary on an island in the Mississippi River in Township 48 North, Range 4 and 5 East, of the Fifth Principal Meridian, in the State of Missouri, and was accepted September 2, 2005. We will place a copy of the plat we described in the open files. It will be made available to the public as a matter of information. Dated: September 2, 2005. Stephen D. Douglas, Chief Cadastral Surveyor. [FR Doc. 05–17973 Filed 9–9–05; 8:45 am] Board Room, 7th Floor, Room 7074, 1775 Duke Street, Alexandria, VA 22314–3428. STATUS: Open. MATTERS TO BE CONSIDERED: 1. Request from a Federal Credit Union to Convert to a Community Charter. 2. Proposed Rule: Section 741.6(a) of NCUA’s Rules and Regulations, Financial and Statistical and Other Reports. 3. Final Rule: Part 712 of NCUA’s Rules and Regulations, Credit Union Service Organizations. TIME AND DATE: 9 a.m., Thursday, September 15, 2005. PLACE: Board Room, 7th Floor, Room 7047, 1775 Duke Street, Alexandria, VA 22314–3428. STATUS: Closed. MATTERS TO BE CONSIDERED: 1. One (1) Insurance Appeal. Closed pursuant to Exemption (6). 2. Internal Board Procedures and Technical Corrections. Closed pursuant to Exemption (2). RECESS: 9:30 a.m. FOR FURTHER INFORMATION CONTACT: Mary Rupp, Secretary of the Board, Telephone: (703) 518–6304. PLACE: Mary Rupp, Secretary of the Board. [FR Doc. 05–18173 Filed 9–8–05; 3:39 pm] BILLING CODE 7535–01–M NUCLEAR REGULATORY COMMISSION [Docket No. 72–8] Calvert Cliffs Independent Spent Fuel Storage Installation Issuance of Environmental Assessment and Finding of No Significant Impact Regarding a License Amendment Nuclear Regulatory Commission (NRC). ACTION: Issuance of an Environmental Assessment and Finding of No Significant Impact. AGENCY: FOR FURTHER INFORMATION CONTACT: NATIONAL CREDIT UNION ADMINISTRATION Joseph M. Sebrosky, Senior Project Manager, Spent Fuel Project Office, Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, Washington, DC 20555. Telephone: (301) 415–1132; Fax number: (301) 415–8555; E-mail: jms3@nrc.gov. Notice of Meeting SUPPLEMENTARY INFORMATION: BILLING CODE 4310–GJ–P 10 a.m., Thursday, September 15, 2005. TIME AND DATE: VerDate Aug<18>2005 15:25 Sep 09, 2005 Jkt 205001 The U.S. Nuclear Regulatory Commission (NRC or the Commission) is considering issuance of an amendment to Special PO 00000 Frm 00040 Fmt 4703 Sfmt 4703 Nuclear Materials License No. 2505 that would incorporate changes to the updated safety analysis report to alter the design basis limit for the dry shielded canister (DSC) internal pressure from 50 psig to 100 psig. Calvert Cliffs Nuclear Power Plant, Inc. (CCNPP) is currently storing spent nuclear fuel at the Calvert Cliffs independent spent fuel storage installation (ISFSI) located in Calvert County, Maryland. Environmental Assessment (EA) Identification of Proposed Action: By letter dated May 16, 2005, CCNPP submitted a request to the NRC to amend license SNM–2505 in order to incorporate changes to the updated safety analysis report to alter the design basis limit for the DSC internal pressure from 50 psig to 100 psig. The design basis limit change is being made to support CCNPP adding the NUHOMS– 32P as an optional design to the existing NUHOMS–24P design for dry storage of spent fuel. The NUHOMS–32P design stores eight more spent fuel assemblies than the NUHOMS–24P design. The proposed action before the NRC is whether to approve the amendment. Need for the Proposed Action: The proposed action would allow CCNPP to optimize its dry spent fuel storage capacity by upgrading portions of its ISFSI to use the NUHOMS–32P DSC. The proposed action would allow CCNPP to reduce the minimum number of canister loadings each year from four (using the NUHOMS–24P design) to three (with the NUHOMS–32P design). Environmental Impacts of the Proposed Action: By letter dated December 12, 2003, CCNPP submitted a request to amend license SNM–2505 to add the NUHOMS–32P as an optional design to the existing NUHOMS–24P design for dry storage of spent fuel. An EA and Finding of No Significant Impact (FONSI) were published in the Federal Register on May 24, 2005 (70 FR 29784) for CCNPP’s December 12, 2003, license amendment request which concluded that adding the NUHOMS– 32P as an optional design to the existing NUHOMS–24P design for dry storage of spent nuclear fuel would have no significant impact on the environment. The proposed action contained in CCNPP’s May 16, 2005, request is to incorporate changes to the updated safety analysis report to alter the design basis limit for the DSC internal pressure from 50 psig to 100 psig. The DSC provides confinement, an inert environment, structural support, and criticality control for 32 pressurized water reactor fuel assemblies. The DSC shell is a welded stainless steel pressure E:\FR\FM\12SEN1.SGM 12SEN1 Federal Register / Vol. 70, No. 175 / Monday, September 12, 2005 / Notices vessel that includes thick shield plugs at either end. To support the pressure increase structural design changes were made to the DSC to ensure that the confinement boundary for the spent nuclear fuel is maintained under the proposed design pressure limit of 100 psig for all specified normal operation, off-normal operation, and accident conditions. The staff has determined that the proposed action would not endanger life or property. No effluents are released from the ISFSI during operation and the proposed changes have no impact to DSC loading activities. Therefore, there is no significant change in the type or significant increase in the amounts of any effluents that may be released offsite. There is also no significant increase with regard to individual or cumulative occupational radiation exposures because of the proposed action. There are no significant radiological environmental impacts associated with the proposed action because the NUHOMS–32P DSC includes design changes to ensure the confinement boundary for the spent nuclear fuel is maintained under the proposed design pressure limit of 100 psig. The amendment only affects the requirements associated with the loading of the casks and does not affect non-radiological plant effluents or any other aspects of the environment. Therefore, there are no significant nonradiological impacts associated with the proposed action. Accordingly, the Commission concludes that there are no significant environmental impacts associated with the proposed action. Alternative to the Proposed Action: As an alternative to the proposed action, the staff considered denial of the amendment request (i.e., the ‘‘noaction’’ alternative). Approval or denial of the amendment request would result in minimal change in the environmental impacts. Therefore, the environmental impacts of the proposed action and the alternative action are similar. Agencies and Persons Consulted: On August 11, 2005, Richard McLean of the State of Maryland was contacted regarding the proposed action and had no concerns. The NRC staff has determined that consultation under Section 7 of the Endangered Species Act is not required for this specific amendment and will not affect listed species or critical habitat. The NRC staff has also determined that the proposed action is not a type of activity having the potential to cause effects on historic properties. Therefore, no consultation is VerDate Aug<18>2005 15:25 Sep 09, 2005 Jkt 205001 required under Section 106 of the National Historic Preservation Act. Conclusions: The staff has reviewed the amendment request submitted by CCNPP and changing the DSC design basis pressure limit would have no significant impact on the environment. Finding of No Significant Impact The environmental impacts of the proposed action have been reviewed in accordance with the requirements set forth in 10 CFR part 51. Based upon the foregoing EA, the NRC finds that the proposed action of approving the amendment to the license will not significantly impact the quality of the human environment. Accordingly, the NRC has determined that an environmental impact statement for the proposed license amendment is not warranted. The request for amendment was docketed under 10 CFR part 72, Docket 72–8. For further details with respect to this action, see the proposed license amendment dated May 16, 2005. The NRC maintains an Agencywide Documents Access Management System (ADAMS), which provides text and image files of NRC’s public documents. These documents may be accessed through the NRC’s Public Electronic Reading Room on the Internet at: http: //www.nrc.gov/reading-rm/adams.html. Copies of the referenced documents will also be available for review at the NRC Public Document Room (PDR), located at 11555 Rockville Pike, Rockville, MD, 20852. PDR reference staff can be contacted at 1–800–397–4209, 301–415– 4737 or by e-mail to pdr@nrc.gov. The PDR reproduction contractor will copy documents for a fee. Dated at Rockville, Maryland, this 31st of August, 2005. For the Nuclear Regulatory Commission. Joseph M. Sebrosky, Senior Project Manager, Spent Fuel Project Office, Office of Nuclear Material Safety and Safeguards. [FR Doc. 05–17971 Filed 9–9–05; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [Docket No. 72–39] Connecticut Yankee Atomic Power Company Haddam Neck Plant Independent Spent Fuel Storage Installation Environmental Assessment and Finding of No Significant Impact The U.S. Nuclear Regulatory Commission (NRC or Commission) is considering issuance of an exemption to PO 00000 Frm 00041 Fmt 4703 Sfmt 4703 53813 Connecticut Yankee Atomic Power Company (CYAPCO or licensee), pursuant to 10 CFR 72.7, from the specific provisions of 10 CFR 72.212(a)(2), 72.212(b)(2)(I), 72.212(b)(7), and 72.214. The licensee is using the NAC Multi-Purpose Canister System (NAC–MPC), Certificate of Compliance (CoC) No. 1025, to store spent fuel under a general license in an independent spent fuel storage installation (ISFSI) associated with the operation of the Haddam Neck Plant, located in Middlesex County, Connecticut. The requested exemption would allow CYAPCO to deviate from requirements of the NAC–MPC CoC No. 1025, Amendment No. 4, Appendix A, Technical Specifications for the NAC– MPC System, Section A 5.1, Training Program. Specifically, the exemption would relieve the licensee from the requirement to develop training modules under its Systems Approach to Training (SAT) that includes comprehensive instructions for the operation and maintenance of the ISFSI, except for the NAC–MPC System. Environmental Assessment Identification of the Proposed Action The proposed action would exempt CYAPCO from regulatory requirements to develop certain training. By letter dated June 1, 2005, the licensee requested exemptions from certain regulatory requirements of 10 CFR 72.212(a)(2), 72.212(b)(2)(I), 72.212(b)(7), and 72.214 which require a general license to store spent fuel in a NRC-certified spent fuel storage cask under the terms and conditions set forth in the CoC. The proposed exemption would allow the licensee to deviate from the requirements in CoC No. 1025, Amendment No. 4, Appendix A, Technical Specifications for the NAC– MPC System, Section A 5.1, Training Program. CoC No. 1025, Amendment 4, Appendix A, Technical Specifications for the NAC–MPC System, Section A 5.1, Training Program, requires that a training program for the NAC–MPC System be developed under the general licensee’s SAT Program. Further, the training modules must include comprehensive instructions for the operation and maintenance of both the NAC-MPC System and the ISFSI. By exempting the licensee from the requirements of 10 CFR 72.212(a)(2), 72.212(b)(2)(I), 72.212(b)(7), and 72.214 for this request, the licensee will not be required to develop training modules that include comprehensive instructions for the operation and maintenance of the ISFSI. E:\FR\FM\12SEN1.SGM 12SEN1

Agencies

[Federal Register Volume 70, Number 175 (Monday, September 12, 2005)]
[Notices]
[Pages 53812-53813]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 05-17971]


=======================================================================
-----------------------------------------------------------------------

NUCLEAR REGULATORY COMMISSION

[Docket No. 72-8]


Calvert Cliffs Independent Spent Fuel Storage Installation 
Issuance of Environmental Assessment and Finding of No Significant 
Impact Regarding a License Amendment

AGENCY: Nuclear Regulatory Commission (NRC).

ACTION: Issuance of an Environmental Assessment and Finding of No 
Significant Impact.

-----------------------------------------------------------------------

FOR FURTHER INFORMATION CONTACT: Joseph M. Sebrosky, Senior Project 
Manager, Spent Fuel Project Office, Office of Nuclear Material Safety 
and Safeguards, U.S. Nuclear Regulatory Commission, Washington, DC 
20555. Telephone: (301) 415-1132; Fax number: (301) 415-8555; E-mail: 
jms3@nrc.gov.

SUPPLEMENTARY INFORMATION: The U.S. Nuclear Regulatory Commission (NRC 
or the Commission) is considering issuance of an amendment to Special 
Nuclear Materials License No. 2505 that would incorporate changes to 
the updated safety analysis report to alter the design basis limit for 
the dry shielded canister (DSC) internal pressure from 50 psig to 100 
psig. Calvert Cliffs Nuclear Power Plant, Inc. (CCNPP) is currently 
storing spent nuclear fuel at the Calvert Cliffs independent spent fuel 
storage installation (ISFSI) located in Calvert County, Maryland.

Environmental Assessment (EA)

    Identification of Proposed Action: By letter dated May 16, 2005, 
CCNPP submitted a request to the NRC to amend license SNM-2505 in order 
to incorporate changes to the updated safety analysis report to alter 
the design basis limit for the DSC internal pressure from 50 psig to 
100 psig. The design basis limit change is being made to support CCNPP 
adding the NUHOMS-32P as an optional design to the existing NUHOMS-24P 
design for dry storage of spent fuel. The NUHOMS-32P design stores 
eight more spent fuel assemblies than the NUHOMS-24P design.
    The proposed action before the NRC is whether to approve the 
amendment.
    Need for the Proposed Action: The proposed action would allow CCNPP 
to optimize its dry spent fuel storage capacity by upgrading portions 
of its ISFSI to use the NUHOMS-32P DSC. The proposed action would allow 
CCNPP to reduce the minimum number of canister loadings each year from 
four (using the NUHOMS-24P design) to three (with the NUHOMS-32P 
design).
    Environmental Impacts of the Proposed Action: By letter dated 
December 12, 2003, CCNPP submitted a request to amend license SNM-2505 
to add the NUHOMS-32P as an optional design to the existing NUHOMS-24P 
design for dry storage of spent fuel. An EA and Finding of No 
Significant Impact (FONSI) were published in the Federal Register on 
May 24, 2005 (70 FR 29784) for CCNPP's December 12, 2003, license 
amendment request which concluded that adding the NUHOMS-32P as an 
optional design to the existing NUHOMS-24P design for dry storage of 
spent nuclear fuel would have no significant impact on the environment.
    The proposed action contained in CCNPP's May 16, 2005, request is 
to incorporate changes to the updated safety analysis report to alter 
the design basis limit for the DSC internal pressure from 50 psig to 
100 psig. The DSC provides confinement, an inert environment, 
structural support, and criticality control for 32 pressurized water 
reactor fuel assemblies. The DSC shell is a welded stainless steel 
pressure

[[Page 53813]]

vessel that includes thick shield plugs at either end. To support the 
pressure increase structural design changes were made to the DSC to 
ensure that the confinement boundary for the spent nuclear fuel is 
maintained under the proposed design pressure limit of 100 psig for all 
specified normal operation, off-normal operation, and accident 
conditions. The staff has determined that the proposed action would not 
endanger life or property. No effluents are released from the ISFSI 
during operation and the proposed changes have no impact to DSC loading 
activities. Therefore, there is no significant change in the type or 
significant increase in the amounts of any effluents that may be 
released offsite. There is also no significant increase with regard to 
individual or cumulative occupational radiation exposures because of 
the proposed action. There are no significant radiological 
environmental impacts associated with the proposed action because the 
NUHOMS-32P DSC includes design changes to ensure the confinement 
boundary for the spent nuclear fuel is maintained under the proposed 
design pressure limit of 100 psig.
    The amendment only affects the requirements associated with the 
loading of the casks and does not affect non-radiological plant 
effluents or any other aspects of the environment. Therefore, there are 
no significant non-radiological impacts associated with the proposed 
action.
    Accordingly, the Commission concludes that there are no significant 
environmental impacts associated with the proposed action.
    Alternative to the Proposed Action: As an alternative to the 
proposed action, the staff considered denial of the amendment request 
(i.e., the ``no-action'' alternative). Approval or denial of the 
amendment request would result in minimal change in the environmental 
impacts. Therefore, the environmental impacts of the proposed action 
and the alternative action are similar.
    Agencies and Persons Consulted: On August 11, 2005, Richard McLean 
of the State of Maryland was contacted regarding the proposed action 
and had no concerns. The NRC staff has determined that consultation 
under Section 7 of the Endangered Species Act is not required for this 
specific amendment and will not affect listed species or critical 
habitat. The NRC staff has also determined that the proposed action is 
not a type of activity having the potential to cause effects on 
historic properties. Therefore, no consultation is required under 
Section 106 of the National Historic Preservation Act.
    Conclusions: The staff has reviewed the amendment request submitted 
by CCNPP and changing the DSC design basis pressure limit would have no 
significant impact on the environment.

Finding of No Significant Impact

    The environmental impacts of the proposed action have been reviewed 
in accordance with the requirements set forth in 10 CFR part 51. Based 
upon the foregoing EA, the NRC finds that the proposed action of 
approving the amendment to the license will not significantly impact 
the quality of the human environment. Accordingly, the NRC has 
determined that an environmental impact statement for the proposed 
license amendment is not warranted.
    The request for amendment was docketed under 10 CFR part 72, Docket 
72-8. For further details with respect to this action, see the proposed 
license amendment dated May 16, 2005. The NRC maintains an Agencywide 
Documents Access Management System (ADAMS), which provides text and 
image files of NRC's public documents. These documents may be accessed 
through the NRC's Public Electronic Reading Room on the Internet at: 
http: //www.nrc.gov/reading-rm/adams.html. Copies of the referenced 
documents will also be available for review at the NRC Public Document 
Room (PDR), located at 11555 Rockville Pike, Rockville, MD, 20852. PDR 
reference staff can be contacted at 1-800-397-4209, 301-415-4737 or by 
e-mail to pdr@nrc.gov. The PDR reproduction contractor will copy 
documents for a fee.

    Dated at Rockville, Maryland, this 31st of August, 2005.

    For the Nuclear Regulatory Commission.
Joseph M. Sebrosky,
Senior Project Manager, Spent Fuel Project Office, Office of Nuclear 
Material Safety and Safeguards.
[FR Doc. 05-17971 Filed 9-9-05; 8:45 am]
BILLING CODE 7590-01-P