Northern States Power Company-Minnesota; Prairie Island Nuclear Generating Plant; Independent Spent Fuel Storage Installation; Correct Inspection Intervals Acceptance Criteria, 15420-15421 [2018-07304]

Download as PDF 15420 Federal Register / Vol. 83, No. 69 / Tuesday, April 10, 2018 / Notices daltland on DSKBBV9HB2PROD with NOTICES minimum critical power ratio numeric values for Operating Cycle 17. Specifically, the amendment increased the numeric values of the safety limit minimum critical power ratio for Nine Mile Point Nuclear Station, Unit 2, from ≥1.15 to ≥1.17 for two recirculation loop operation, and from ≥1.15 to ≥1.17 for single recirculation loop operation. Date of issuance: March 16, 2018. Effective date: As of the date of issuance and shall be implemented prior to startup from the next refueling outage. Amendment No.: 167. A publiclyavailable version is in ADAMS under Accession No. ML18060A016; documents related to this amendment are listed in the Safety Evaluation enclosed with the amendment. Renewed Facility Operating License No. NPF–69: Amendment revised the Renewed Facility Operating License and Technical Specifications. Date of initial notice in Federal Register: February 6, 2018 (83 FR 5280). The Commission’s related evaluation of the amendment is contained in a Safety Evaluation dated March 16, 2018. No significant hazards consideration comments received: No. Florida Power & Light Company, et al., Docket Nos. 50–335 and 50–389, St. Lucie Plant, Unit Nos. 1 and 2, St. Lucie County, Florida Date of amendment request: January 31, 2018. Brief description of amendments: The amendments revised the Emergency Plan for St. Lucie to adopt the firerelated notification of unusual event requirement of the Nuclear Energy Institute 99–01, Revision 6, Emergency Action Level scheme. Date of issuance: March 26, 2018. Effective date: As of the date of issuance and shall be implemented within 90 days. Amendment Nos.: 244 and 195. A publicly-available version is in ADAMS under Accession No. ML18046A712; documents related to these amendments are listed in the Safety Evaluation enclosed with the amendments. Renewed Facility Operating License Nos. DPR–67 and NPF–16: The amendments revised the Renewed Facility Operating Licenses. Date of initial notice in Federal Register: February 14, 2018 (83 FR 6621). This notice provided an opportunity to request a hearing by April 15, 2018, but indicated that if the Commission makes a final no significant hazards consideration determination, any such hearing would take place after issuance of the amendments. VerDate Sep<11>2014 16:56 Apr 09, 2018 Jkt 244001 The Commission’s related evaluation of the amendments is contained in a Safety Evaluation dated March 26, 2018. No significant hazards consideration comments received: No. Florida Power & Light Company, Docket Nos. 50–250 and 50–251, Turkey Point Nuclear Generating Unit Nos. 3 and 4, Miami-Dade County, Florida Date of amendment request: April 9, 2017, as supplemented by letter dated October 4, 2017. Brief description of amendments: The amendments revised the Technical Specifications (TSs) to remove various reporting requirements. Specifically, the amendments removed the requirements to prepare the Startup Report, the Annual Report, and various special reports. In addition, the amendments revised the TSs to remove the completion time for restoring spent fuel pool water level, to address inoperability of one of the two parallel flow paths in the residual heal removal or safely injection headers for the Emergency Core Cooling Systems, and to make other administrative changes, including updating plant staff and responsibilities. Date of issuance: March 19, 2018. Effective date: As of the date of issuance and shall be implemented within 90 days of issuance. Amendment Nos.: 279 (Unit No. 3) and 274 (Unit No. 4). A publiclyavailable version is in ADAMS under Accession No. ML18019A078; documents related to these amendments are listed in the Safety Evaluation (SE) enclosed with the amendments. Renewed Facility Operating License Nos. DPR–31 and DPR–41: Amendments revised the Renewed Facility Operating Licenses and TSs. Date of initial notice in Federal Register: June 19, 2017 (82 FR 27889). The supplemental letter dated October 4, 2017, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the NRC staff’s original proposed no significant hazards consideration determination as published in the Federal Register. The Commission’s related evaluation of the amendments is contained in an SE dated March 19, 2018. No significant hazards consideration comments received: No. Southern Nuclear Operating Company, Docket Nos. 52–025 and 52–026, Vogtle Electric Generating Plant (VEGP), Units 3 and 4, Burke County, Georgia Date of amendment request: August 31, 2017. PO 00000 Frm 00067 Fmt 4703 Sfmt 4703 Description of amendment: The amendments authorized changes to the VEGP Units 3 and 4 Combined Operating License (COL) page 7 and COL Appendix A, Technical Specifications, to make necessary changes so that there will be adequate detection of reactor coolant system and main steam line leakage at all times and that the associated limits account for instrumentation sensitivities not accounted for in the current VEGP Technical Specification 3.4.9. Date of issuance: March 12, 2018. Effective date: As of the date of issuance and shall be implemented within 30 days of issuance. Amendment No.: 115 (Unit 3) and 114 (Unit 4). Publicly-available versions are in ADAMS Package Accession No. ML18036A782, which includes the Safety Evaluation that references documents related to these amendments. Facility Combined License Nos. NPF– 91 and NPF–92: Amendments revised the Facility Combined Licenses. Date of initial notice in Federal Register: October 10, 2017 (82 FR 47032). The Commission’s related evaluation of the amendment is contained in the Safety Evaluation dated March 12, 2018. No significant hazards consideration comments received: No. Dated at Rockville, Maryland, this 28th day of March 2018. For the Nuclear Regulatory Commission. Tara Inverso, Acting Deputy Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation. [FR Doc. 2018–06668 Filed 4–9–18; 8:45 am] BILLING CODE 7590–01–P 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 Nuclear Regulatory Commission. ACTION: License amendment application; issuance. AGENCY: 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, SUMMARY: E:\FR\FM\10APN1.SGM 10APN1 daltland on DSKBBV9HB2PROD with NOTICES Federal Register / Vol. 83, No. 69 / Tuesday, April 10, 2018 / Notices 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 https://www.regulations.gov and search for Docket ID NRC–2018–0057. Address questions about NRC dockets to Jennifer Borges; telephone: 301–287–9127; email: Jennifer.Borges@nrc.gov. 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 https://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 pdr.resource@nrc.gov. 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: JohnChau.Nguyen@nrc.gov. 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) VerDate Sep<11>2014 16:56 Apr 09, 2018 Jkt 244001 set inspection intervals to be ‘‘not less than’’ those in the American Concrete Institute (ACI) Code; however, NRCissued 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 § 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 PO 00000 Frm 00068 Fmt 4703 Sfmt 4703 15421 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] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [NRC–2017–0209] Information Collection: General Domestic Licenses for Byproduct Material Nuclear Regulatory Commission. ACTION: Renewal of existing information collection; request for comment. AGENCY: The U.S. Nuclear Regulatory Commission (NRC) invites public comment on the renewal of Office of Management and Budget (OMB) approval for an existing collection of information. The information collection is entitled, ‘‘General Domestic Licenses for Byproduct Material.’’ DATES: Submit comments by June 11, 2018. Comments received after this date will be considered if it is practical to do so, but the Commission is able to ensure consideration only for comments received on or before this date. ADDRESSES: You may submit comments by any of the following methods: • Federal Rulemaking Website: Go to https://www.regulations.gov and search for Docket ID NRC–2017–0209. Address questions about NRC dockets to Jennifer Borges; telephone: 301–287–9127; email: Jennifer.Borges@nrc.gov. For technical questions, contact the individual listed in the FOR FURTHER INFORMATION CONTACT section of this document. • Mail comments to: David Cullison, Office of the Chief Information Officer, Mail Stop: T–2–F43, U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001. For additional direction on obtaining information and submitting comments, see ‘‘Obtaining Information and Submitting Comments’’ in the SUPPLEMENTARY INFORMATION section of this document. SUMMARY: E:\FR\FM\10APN1.SGM 10APN1

Agencies

[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]


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

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.

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

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 https://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 https://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]
 BILLING CODE 7590-01-P
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