Maine Yankee Atomic Power Company; Issuance of Environmental Assessment and Finding of No Significant Impact Regarding a Proposed Exemption, 20607-20608 [E5-1854]

Download as PDF Federal Register / Vol. 70, No. 75 / Wednesday, April 20, 2005 / Notices also should arrive early in order to gain on-time admission to the hearing room. It is so ordered. Issued in Rockville, Maryland, on April 13, 2005. For the Pre-License Application Presiding Officer Board. Thomas S. Moore, Chairman, Administrative Judge. [FR Doc. E5–1850 Filed 4–19–05; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [Docket 72–30] Maine Yankee Atomic Power Company; Issuance of Environmental Assessment and Finding of No Significant Impact Regarding a Proposed Exemption Nuclear Regulatory Commission. ACTION: Environmental assessment. AGENCY: FOR FURTHER INFORMATION CONTACT: Jeremy A. Smith, Project Manager, Spent Fuel Project Office, Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, Washington, DC 20555. Telephone: (301) 415–8500; fax number: (301) 415– 8555; e-mail: jas5@nrc.gov. SUPPLEMENTARY INFORMATION: The U.S. Nuclear Regulatory Commission (NRC or the staff) is considering issuance of an exemption, pursuant to 10 CFR 72.7, from the provisions of 10 CFR 72.72(d) to Maine Yankee Atomic Power Company (Maine Yankee or applicant). The requested exemption would allow Maine Yankee to maintain a single set of spent fuel, high-level radioactive waste, and reactor-related Greater Than Class C (GTCC) waste records in accordance with the requirements of 10 CFR 50.71(d)(1), for the Independent Spent Fuel Storage Installation (ISFSI) at Maine Yankee in Wiscasset, Maine. Environmental Assessment (EA) Identification of Proposed Action: By letter dated November 29, 2004, Maine Yankee requested an exemption from the requirement in 10 CFR 72.72(d) which states in part that, ‘‘Records of spent fuel, high-level radioactive waste, and reactor-related GTCC waste containing special nuclear material meeting the requirements in paragraph (a) of this section must be kept in duplicate. The duplicate set of records must be kept at a separate location sufficiently remote from the original records that a single event would not destroy both sets of records.’’ VerDate jul<14>2003 14:54 Apr 19, 2005 Jkt 205001 The proposed action before the Commission is whether to grant this exemption pursuant to 10 CFR 72.7. Need for the Proposed Action: The applicant stated that ISFSI spent-fuel, high-level radioactive waste, and reactor-related GTCC waste records will be maintained in a manner consistent with the records of Maine Yankee, which are stored in compliance with the requirements established in 10 CFR 50.71(d)(1). No exemption is requested from the 10 CFR 72.72(d) requirements for the records retention period requirements. The applicant seeks to provide consistency in recordkeeping maintenance for the Maine Yankee ISFSI spent fuel, high-level radioactive waste, and reactor-related GTCC waste records. The exemption request will also preclude the need to construct and operate a separate, second records storage facility to store a duplicate set of spent-fuel, high-level radioactive waste, and reactor-related GTCC waste records. 10 CFR 50.71(d)(1) provides requirements for the maintenance of nuclear power plant records. The regulation states: 20607 Records which must be maintained pursuant to this part may be the original or a reproduced copy or microform if such reproduced copy or microform is duly authenticated by authorized personnel and the microform is capable of producing a clear and legible copy after storage for the period specified by the Commission regulations. The record may also be stored in electronic media with the capability of producing legible, accurate, and complete records during the required retention period. Records such as letters, drawings, specifications, must include all pertinent information such as stamps, initials, and signatures. The licensee shall maintain adequate safeguards against tampering with and loss of records. location, and assigned responsibility.’’ ANSI N.45.2.9–1974 also satisfies the requirements of 10 CFR 72.72 by providing for adequate maintenance of records regarding the identity and history of the spent fuel in storage. Such records would be subject to and need to be protected from the same types of degradation mechanisms as nuclear power plant Quality Assurance records. Environmental Impacts of the Proposed Action: An exemption from the requirement to store a duplicate set of ISFSI records at a separate location has no impact on the environment. Storage of records does not change the methods by which spent fuel will be handled and stored at the Maine Yankee ISFSI and does not change the amount of effluents, radiological or nonradiological, associated with the ISFSI. Alternative to the Proposed Action: Since there is no environmental impact associated with the proposed action, alternatives are not evaluated other than the no action alternative. The alternative to the proposed action would be to deny approval of the exemption and, therefore, not allow storage of ISFSI spent fuel records at a single qualified record storage facility. The no action alternative would require the applicant to construct or identify a separate storage facility; therefore, the environmental impacts of the proposed action would be less than, or the same as, the no action alternative. Agencies and Persons Consulted: On March 28, 2005, Maine State Nuclear Safety Inspector Mr. Patrick Dostie was contacted regarding the environmental assessment for the proposed action and had no comments. Regulatory Guide 1.88, ‘‘Collection, Storage, and Maintenance of Nuclear Power Plant Quality Assurance Records,’’ establishes guidance for the storage of nuclear plant quality assurance records. Maine Yankee plans to implement Revision 2 of Regulatory Guide 1.88, with minor exceptions described in the Maine Yankee Quality Assurance Plan (QAP). The requirements in ANSI N45.2.9– 1974 have been endorsed by the NRC in Regulatory Guide 1.88 as adequate for satisfying the recordkeeping requirements of 10 CFR Part 50, Appendix B, which states in part that ‘‘records shall be identifiable and retrievable.’’ Additionally, conditions in 10 CFR Part 50, Appendix B establish that ‘‘[c]onsistent with applicable regulatory requirements (including 10 CFR 50.71(d)(1)), the applicant shall establish requirements concerning record retention, such as duration, 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 Environmental Assessment, the Commission finds that the proposed action of granting the exemption from 10 CFR 72.72(d), so that Maine Yankee may store spent fuel records for the ISFSI in a single records storage facility which meets the requirements of ANSI N.45.2.9–1974, with the given exception listed in the Maine Yankee QAP, will not significantly impact the quality of the human environment. Accordingly, the Commission has determined that an environmental impact statement for the proposed exemption is not necessary. The request for exemption was docketed under 10 CFR Part 72, Docket 72–30. For further details with respect to this exemption request, see the Maine Yankee letter requesting the exemption PO 00000 Frm 00093 Fmt 4703 Sfmt 4703 E:\FR\FM\20APN1.SGM 20APN1 20608 Federal Register / Vol. 70, No. 75 / Wednesday, April 20, 2005 / Notices dated November 29, 2004. Supporting documentation is available for inspection at the NRC’s Public Electronic Reading Room at https:// www.nrc.gov/reading-rm/adams.html. A copy of the Finding of No Significant Impact can be found at this site using the Agencywide Documents Access and Management System (ADAMS). These documents may also be viewed electronically on the public computers located at the NRC’s Public Document Room (PDR), O1–F21, One White Flint North, 11555 Rockville Pike, Rockville, MD 20852. The PDR reproduction contractor will copy documents for a fee. Persons who do not have access to ADAMS or who encounter problems in accessing the documents located in ADAMS, should contact the NRC PDR Reference staff at 1–800–397–4209 or (301) 415–4737, or by e-mail to pdr@nrc.gov. Dated at Rockville, Maryland, this 13th day of April 2005. For the Nuclear Regulatory Commission. Jeremy A. Smith, Project Manager, Spent Fuel Project Office, Office of Nuclear Material Safety and Safeguards. [FR Doc. E5–1854 Filed 4–19–05; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards; Subcommittee Meeting on Planning and Procedures; Notice of Meeting The ACRS Subcommittee on Planning and Procedures will hold a meeting on May 4, 2005, Room T–2B1, 11545 Rockville Pike, Rockville, Maryland. The entire meeting will be open to public attendance, with the exception of a portion that may be closed pursuant to 5 U.S.C. 552b(c)(2) and (6) to discuss organizational and personnel matters that relate solely to the internal personnel rules and practices of the ACRS, and information the release of which would constitute a clearly unwarranted invasion of personal privacy. The agenda for the subject meeting shall be as follows: Wednesday, May 4, 2005–10 a.m.–11:30 a.m. The Subcommittee will discuss proposed ACRS activities and related matters. The Subcommittee will gather information, analyze relevant issues and facts, and formulate proposed positions and actions, as appropriate, for deliberation by the full Committee. VerDate jul<14>2003 14:54 Apr 19, 2005 Jkt 205001 Members of the public desiring to provide oral statements and/or written comments should notify the Designated Federal Official, Mr. Sam Duraiswamy (telephone: 301–415–7364) between 7:30 a.m. and 4:15 p.m. (ET) five days prior to the meeting, if possible, so that appropriate arrangements can be made. Electronic recordings will be permitted only during those portions of the meeting that are open to the public. Further information regarding this meeting can be obtained by contacting the Designated Federal Official between 7:30 a.m. and 4:15 p.m. (ET). Persons planning to attend this meeting are urged to contact the above named individual at least two working days prior to the meeting to be advised of any potential changes in the agenda. Dated: April 13, 2005. Michael L. Scott, Branch Chief, ACRS/ACNW. [FR Doc. E5–1851 Filed 4–19–05; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards; Subcommittee Meeting on Fire Protection; Notice of Meeting The ACRS Subcommittee on Fire Protection will hold a meeting on May 4, 2005, Room T–2B3, 11545 Rockville Pike, Rockville, Maryland. The entire meeting will be open to public attendance. The agenda for the subject meeting shall be as follows: Wednesday, May 4 , 2005—8:30 a.m. until 3 p.m. The purpose of this meeting is to discuss the NRC/EPRI joint work on the improved fire risk assessment methodology. The Subcommittee will discuss NUREG/CR–6850, ‘‘EPRI/NRC– RES Fire PRA Methodology for Nuclear Power Facilities.’’ The Subcommittee will also discuss the NRC staff’s efforts on verification and validation of fire models. The Subcommittee will hear presentations by and hold discussions with the NRC staff, representatives of the EPRI, and other interested persons regarding this matter. The Subcommittee will gather information, analyze relevant issues and facts, and formulate proposed positions and actions, as appropriate, for deliberation by the full Committee. Members of the public desiring to provide oral statements and/or written comments should notify the Designated Federal Official, Mr. Hossein P. Nourbakhsh (Telephone: 301–415–5622) PO 00000 Frm 00094 Fmt 4703 Sfmt 4703 five days prior to the meeting, if possible, so that appropriate arrangements can be made. Electronic recordings will be permitted. Further information regarding this meeting can be obtained by contacting the Designated Federal Official or the Cognizant Staff Engineer between 7:30 a.m. and 4:15 p.m. (ET). Persons planning to attend this meeting are urged to contact one of the above named individuals at least two working days prior to the meeting to be advised of any potential changes to the agenda. Dated: April 13, 2005. Michael L. Scott, Branch Chief, ACRS/ACNW. [FR Doc. E5–1852 Filed 4–19–05; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards; Meeting Notice In accordance with the purposes of Sections 29 and 182b. of the Atomic Energy Act (42 U.S.C. 2039, 2232b), the Advisory Committee on Reactor Safeguards (ACRS) will hold a meeting on May 5–6, 2005, 11545 Rockville Pike, Rockville, Maryland. The date of this meeting was previously published in the Federal Register on Wednesday, November 24, 2004 (69 FR 68412). Thursday, May 5, 2005, Conference Room T–2B3, Two White Flint North, Rockville, Maryland 8:30 a.m.–8:35 a.m.: Opening Remarks by the ACRS Chairman (Open)—The ACRS Chairman will make opening remarks regarding the conduct of the meeting. 8:35 a.m.–10 a.m.: Final Review of the License Renewal Application for Arkansas Nuclear One, Unit 2 (ANO–2) (Open)—The Committee will hear presentations by and hold discussions with representatives of the Entergy Operations, Inc. and the NRC staff regarding the license renewal application for ANO–2 and the associated final Safety Evaluation Report prepared by the NRC staff. 10:15 a.m.–11:45 a.m.: Draft Final Revisions to Standard Review Plan (SRP), Chapter 13, ‘‘Conduct of Operations’’ (Open)—The Committee will hear presentations by and hold discussions with representatives of the NRC staff regarding the draft final revisions to Sections 13.1.2–13.1.3, ‘‘Operating Organization,’’ of SRP Chapter 13 and related NUREG–1791, ‘‘Guidance for Assessing Exemption Requests from the Nuclear Power Plant Licensed Operator Staffing E:\FR\FM\20APN1.SGM 20APN1

Agencies

[Federal Register Volume 70, Number 75 (Wednesday, April 20, 2005)]
[Notices]
[Pages 20607-20608]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E5-1854]


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NUCLEAR REGULATORY COMMISSION

[Docket 72-30]


Maine Yankee Atomic Power Company; Issuance of Environmental 
Assessment and Finding of No Significant Impact Regarding a Proposed 
Exemption

AGENCY: Nuclear Regulatory Commission.

ACTION: Environmental assessment.

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

FOR FURTHER INFORMATION CONTACT: Jeremy A. Smith, Project Manager, 
Spent Fuel Project Office, Office of Nuclear Material Safety and 
Safeguards, U.S. Nuclear Regulatory Commission, Washington, DC 20555. 
Telephone: (301) 415-8500; fax number: (301) 415-8555; e-mail: 
jas5@nrc.gov.

SUPPLEMENTARY INFORMATION: The U.S. Nuclear Regulatory Commission (NRC 
or the staff) is considering issuance of an exemption, pursuant to 10 
CFR 72.7, from the provisions of 10 CFR 72.72(d) to Maine Yankee Atomic 
Power Company (Maine Yankee or applicant). The requested exemption 
would allow Maine Yankee to maintain a single set of spent fuel, high-
level radioactive waste, and reactor-related Greater Than Class C 
(GTCC) waste records in accordance with the requirements of 10 CFR 
50.71(d)(1), for the Independent Spent Fuel Storage Installation 
(ISFSI) at Maine Yankee in Wiscasset, Maine.

Environmental Assessment (EA)

    Identification of Proposed Action: By letter dated November 29, 
2004, Maine Yankee requested an exemption from the requirement in 10 
CFR 72.72(d) which states in part that, ``Records of spent fuel, high-
level radioactive waste, and reactor-related GTCC waste containing 
special nuclear material meeting the requirements in paragraph (a) of 
this section must be kept in duplicate. The duplicate set of records 
must be kept at a separate location sufficiently remote from the 
original records that a single event would not destroy both sets of 
records.''
    The proposed action before the Commission is whether to grant this 
exemption pursuant to 10 CFR 72.7.
    Need for the Proposed Action: The applicant stated that ISFSI 
spent-fuel, high-level radioactive waste, and reactor-related GTCC 
waste records will be maintained in a manner consistent with the 
records of Maine Yankee, which are stored in compliance with the 
requirements established in 10 CFR 50.71(d)(1). No exemption is 
requested from the 10 CFR 72.72(d) requirements for the records 
retention period requirements. The applicant seeks to provide 
consistency in recordkeeping maintenance for the Maine Yankee ISFSI 
spent fuel, high-level radioactive waste, and reactor-related GTCC 
waste records. The exemption request will also preclude the need to 
construct and operate a separate, second records storage facility to 
store a duplicate set of spent-fuel, high-level radioactive waste, and 
reactor-related GTCC waste records.
    10 CFR 50.71(d)(1) provides requirements for the maintenance of 
nuclear power plant records. The regulation states:

    Records which must be maintained pursuant to this part may be 
the original or a reproduced copy or microform if such reproduced 
copy or microform is duly authenticated by authorized personnel and 
the microform is capable of producing a clear and legible copy after 
storage for the period specified by the Commission regulations. The 
record may also be stored in electronic media with the capability of 
producing legible, accurate, and complete records during the 
required retention period. Records such as letters, drawings, 
specifications, must include all pertinent information such as 
stamps, initials, and signatures. The licensee shall maintain 
adequate safeguards against tampering with and loss of records.

    Regulatory Guide 1.88, ``Collection, Storage, and Maintenance of 
Nuclear Power Plant Quality Assurance Records,'' establishes guidance 
for the storage of nuclear plant quality assurance records. Maine 
Yankee plans to implement Revision 2 of Regulatory Guide 1.88, with 
minor exceptions described in the Maine Yankee Quality Assurance Plan 
(QAP).
    The requirements in ANSI N45.2.9-1974 have been endorsed by the NRC 
in Regulatory Guide 1.88 as adequate for satisfying the recordkeeping 
requirements of 10 CFR Part 50, Appendix B, which states in part that 
``records shall be identifiable and retrievable.'' Additionally, 
conditions in 10 CFR Part 50, Appendix B establish that ``[c]onsistent 
with applicable regulatory requirements (including 10 CFR 50.71(d)(1)), 
the applicant shall establish requirements concerning record retention, 
such as duration, location, and assigned responsibility.'' ANSI 
N.45.2.9-1974 also satisfies the requirements of 10 CFR 72.72 by 
providing for adequate maintenance of records regarding the identity 
and history of the spent fuel in storage. Such records would be subject 
to and need to be protected from the same types of degradation 
mechanisms as nuclear power plant Quality Assurance records.
    Environmental Impacts of the Proposed Action: An exemption from the 
requirement to store a duplicate set of ISFSI records at a separate 
location has no impact on the environment. Storage of records does not 
change the methods by which spent fuel will be handled and stored at 
the Maine Yankee ISFSI and does not change the amount of effluents, 
radiological or nonradiological, associated with the ISFSI.
    Alternative to the Proposed Action: Since there is no environmental 
impact associated with the proposed action, alternatives are not 
evaluated other than the no action alternative. The alternative to the 
proposed action would be to deny approval of the exemption and, 
therefore, not allow storage of ISFSI spent fuel records at a single 
qualified record storage facility. The no action alternative would 
require the applicant to construct or identify a separate storage 
facility; therefore, the environmental impacts of the proposed action 
would be less than, or the same as, the no action alternative.
    Agencies and Persons Consulted: On March 28, 2005, Maine State 
Nuclear Safety Inspector Mr. Patrick Dostie was contacted regarding the 
environmental assessment for the proposed action and had no comments.

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 Environmental Assessment, the Commission finds that 
the proposed action of granting the exemption from 10 CFR 72.72(d), so 
that Maine Yankee may store spent fuel records for the ISFSI in a 
single records storage facility which meets the requirements of ANSI 
N.45.2.9-1974, with the given exception listed in the Maine Yankee QAP, 
will not significantly impact the quality of the human environment. 
Accordingly, the Commission has determined that an environmental impact 
statement for the proposed exemption is not necessary.
    The request for exemption was docketed under 10 CFR Part 72, Docket 
72-30. For further details with respect to this exemption request, see 
the Maine Yankee letter requesting the exemption

[[Page 20608]]

dated November 29, 2004. Supporting documentation is available for 
inspection at the NRC's Public Electronic Reading Room at https://
www.nrc.gov/reading-rm/adams.html. A copy of the Finding of No 
Significant Impact can be found at this site using the Agencywide 
Documents Access and Management System (ADAMS). These documents may 
also be viewed electronically on the public computers located at the 
NRC's Public Document Room (PDR), O1-F21, One White Flint North, 11555 
Rockville Pike, Rockville, MD 20852. The PDR reproduction contractor 
will copy documents for a fee. Persons who do not have access to ADAMS 
or who encounter problems in accessing the documents located in ADAMS, 
should contact the NRC PDR Reference staff at 1-800-397-4209 or (301) 
415-4737, or by e-mail to pdr@nrc.gov.

    Dated at Rockville, Maryland, this 13th day of April 2005.
    For the Nuclear Regulatory Commission.
Jeremy A. Smith,
Project Manager, Spent Fuel Project Office, Office of Nuclear Material 
Safety and Safeguards.
[FR Doc. E5-1854 Filed 4-19-05; 8:45 am]
BILLING CODE 7590-01-P
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