[Federal Register Volume 83, Number 69 (Tuesday, April 10, 2018)]
[Notices]
[Pages 15420-15421]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2018-07304]
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NUCLEAR REGULATORY COMMISSION
[Docket No. 72-10; NRC-2018-0057]
Northern States Power Company--Minnesota; Prairie Island Nuclear
Generating Plant; Independent Spent Fuel Storage Installation; Correct
Inspection Intervals Acceptance Criteria
AGENCY: Nuclear Regulatory Commission.
ACTION: License amendment application; issuance.
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SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) reconciled an
error in the Northern States Power Company--Minnesota (NSPM) Renewed
License No. SNM-2506. Under this license, NSPM is authorized to
receive,
[[Page 15421]]
possess, store, and transfer spent nuclear fuel and associated
radioactive materials at the Prairie Island Independent Spent Fuel
Storage Installation.
DATES: April 10, 2018.
ADDRESSES: Please refer to Docket ID NRC-2018-0057 when contacting the
NRC about the availability of information regarding this document. You
may obtain publicly-available information related to this document
using any of the following methods:
Federal Rulemaking Website: Go to http://www.regulations.gov and search for Docket ID NRC-2018-0057. Address
questions about NRC dockets to Jennifer Borges; telephone: 301-287-
9127; email: [email protected]. For technical questions, contact
the individual listed in the FOR FURTHER INFORMATION CONTACT section of
this document.
NRC's Agencywide Documents Access and Management System
(ADAMS): You may obtain publicly available documents online in the
ADAMS Public Documents collection at http://www.nrc.gov/reading-rm/adams.html. To begin the search, select ``ADAMS Public Documents'' and
then select ``Begin Web-based ADAMS Search.'' For problems with ADAMS,
please contact the NRC's Public Document Room (PDR) reference staff at
1-800-397-4209, 301-415-4737, or by email to [email protected]. The
ADAMS accession number for each document referenced (if it is available
in ADAMS) is provided the first time that it is mentioned in this
document.
NRC's PDR: You may examine and purchase copies of public
documents at the NRC's PDR, Room O1-F21, One White Flint North, 11555
Rockville Pike, Rockville, Maryland 20852.
FOR FURTHER INFORMATION CONTACT: John-Chau Nguyen, Office of Nuclear
Material Safety and Safeguards, U.S. Nuclear Regulatory Commission,
Washington, DC 20555-0001; telephone: 301-415-0262; email: [email protected].
SUPPLEMENTARY INFORMATION: After receiving Renewed License No. SNM-
2506, the NSPM staff began to review it and prepare procedures to
implement new requirements. NSPM submitted an email on February 9, 2016
(ADAMS Accession No. ML17324B332), requesting the NRC to, among other
things, address an apparent error in License Condition 22(a) of Renewed
License No. SNM-2506 so that NSPM could establish procedures containing
the correct inspection intervals acceptance criteria for Renewed
License No. SNM-2506. License Condition 22(a) set inspection intervals
to be ``not less than'' those in the American Concrete Institute (ACI)
Code; however, NRC-issued documents demonstrated the NRC had intended
the intervals ``not to exceed'' those in the ACI Code.
As a result of its review, the NRC staff determined that License
Condition 22(a) should read ``not to exceed'' instead of ``not less
than'' and has amended the license to correct this error. When the NRC
staff evaluated visual inspection intervals in its Safety Evaluation
Report (SER) dated December 2015 (ADAMS Accession No. ML15336A230) for
Renewed License No. SNM-2506, Section 3.5.1.3 of the SER clearly
articulated the staff's expectation that accessible areas of the
concrete pads would be visually inspected at intervals ``not to
exceed'' 5 years. Further, the SER states the staff determined that the
specific inspection intervals and areas of inspection coverage in the
Aging Management Program (AMP) for concrete pads are appropriate based
upon the technical references pertinent to age-related degradation of
concrete in similar environments, including American Concrete Institute
guides (ACI) 349.3R-02 (ACI, 2002), ACI 201.1R-08 (ACI, 2008), American
National Standards Institute/American Society of Civil Engineers
guidelines (ANSI/ASCE) 11-99 (ASCE, 2000), and reactor renewal guidance
provided in NRC NUREG-1801 (NRC, 2010b). The ``not less than'' language
included in error is inconsistent with the NRC staff's SER and has the
unintended consequence of preventing NSPM from conducting more frequent
inspections.
Accordingly, based on the staff's findings, the NRC made the
necessary change and issued Amendment No. 10 to License No. SNM-2506 to
correct License Condition 22(a). Amendment No. 10 was effective as of
its date of issuance. The NRC staff's findings are documented in a SER
dated March 6, 2018 (ADAMS Accession No. ML18057A284), which determined
that the amendment complies with the Atomic Energy Act of 1954, as
amended, and NRC regulations. The issuance of Amendment No. 10
satisfies the criteria specified in Sec. 51.22(c)(11) of title 10 of
the Code of Federal Regulations (10 CFR) for a categorical exclusion.
Therefore, the preparation of an environmental assessment or an
environmental impact statement is not required.
In accordance with 10 CFR 72.46(b)(2), the NRC has determined that
Amendment No. 10 does not present a genuine issue as to whether the
public health and safety will be significantly affected. Therefore, the
publication of a notice of proposed action and an opportunity for
hearing or a notice of hearing is not warranted. Notice is hereby given
of the right of interested persons to request a hearing on whether the
action should be rescinded or modified.
Dated at Rockville, Maryland, this 4th day of April, 2018.
For the Nuclear Regulatory Commission.
John McKirgan,
Chief, Spent Fuel Licensing Branch, Division of Spent Fuel Management,
Office of Nuclear Material Safety and Safeguards.
[FR Doc. 2018-07304 Filed 4-9-18; 8:45 am]
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