83 FR 15420 - Northern States Power Company-Minnesota; Prairie Island Nuclear Generating Plant; Independent Spent Fuel Storage Installation; Correct Inspection Intervals Acceptance Criteria
NUCLEAR REGULATORY COMMISSION Federal Register Volume 83, Issue 69 (April 10, 2018)
Federal Register Volume 83, Issue 69 (April 10, 2018)
| Page Range | 15420-15421 | |
| FR Document | 2018-07304 |
[Federal Register Volume 83, Number 69 (Tuesday, April 10, 2018)] [Notices] [Pages 15420-15421] From the Federal Register Online [www.thefederalregister.org] [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 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] BILLING CODE 7590-01-P
![15420 Federal Register / Vol. 83, No. 69 / Tuesday, April 10, 2018 / Notices
minimum critical power ratio numeric The Commission’s related evaluation Description of amendment: The
values for Operating Cycle 17. of the amendments is contained in a amendments authorized changes to the
Specifically, the amendment increased Safety Evaluation dated March 26, 2018. VEGP Units 3 and 4 Combined
the numeric values of the safety limit No significant hazards consideration Operating License (COL) page 7 and
minimum critical power ratio for Nine comments received: No. COL Appendix A, Technical
Mile Point Nuclear Station, Unit 2, from Florida Power & Light Company, Docket Specifications, to make necessary
≥1.15 to ≥1.17 for two recirculation loop Nos. 50–250 and 50–251, Turkey Point changes so that there will be adequate
operation, and from ≥1.15 to ≥1.17 for Nuclear Generating Unit Nos. 3 and 4, detection of reactor coolant system and
single recirculation loop operation. Miami-Dade County, Florida main steam line leakage at all times and
Date of issuance: March 16, 2018. that the associated limits account for
Effective date: As of the date of Date of amendment request: April 9, instrumentation sensitivities not
issuance and shall be implemented 2017, as supplemented by letter dated accounted for in the current VEGP
prior to startup from the next refueling October 4, 2017. Technical Specification 3.4.9.
outage. Brief description of amendments: The Date of issuance: March 12, 2018.
Amendment No.: 167. A publicly- amendments revised the Technical Effective date: As of the date of
available version is in ADAMS under Specifications (TSs) to remove various issuance and shall be implemented
Accession No. ML18060A016; reporting requirements. Specifically, the within 30 days of issuance.
documents related to this amendment amendments removed the requirements Amendment No.: 115 (Unit 3) and 114
are listed in the Safety Evaluation to prepare the Startup Report, the (Unit 4). Publicly-available versions are
enclosed with the amendment. Annual Report, and various special in ADAMS Package Accession No.
Renewed Facility Operating License reports. In addition, the amendments ML18036A782, which includes the
No. NPF–69: Amendment revised the revised the TSs to remove the Safety Evaluation that references
Renewed Facility Operating License and completion time for restoring spent fuel documents related to these
Technical Specifications. pool water level, to address amendments.
Date of initial notice in Federal inoperability of one of the two parallel Facility Combined License Nos. NPF–
Register: February 6, 2018 (83 FR flow paths in the residual heal removal 91 and NPF–92: Amendments revised
5280). or safely injection headers for the the Facility Combined Licenses.
The Commission’s related evaluation Emergency Core Cooling Systems, and Date of initial notice in Federal
of the amendment is contained in a to make other administrative changes, Register: October 10, 2017 (82 FR
Safety Evaluation dated March 16, 2018. including updating plant staff and 47032).
No significant hazards consideration responsibilities. The Commission’s related evaluation
comments received: No. Date of issuance: March 19, 2018. of the amendment is contained in the
Effective date: As of the date of Safety Evaluation dated March 12, 2018.
Florida Power & Light Company, et al., issuance and shall be implemented
Docket Nos. 50–335 and 50–389, St. No significant hazards consideration
within 90 days of issuance. comments received: No.
Lucie Plant, Unit Nos. 1 and 2, St. Lucie Amendment Nos.: 279 (Unit No. 3)
County, Florida and 274 (Unit No. 4). A publicly- Dated at Rockville, Maryland, this 28th day
Date of amendment request: January available version is in ADAMS under of March 2018.
31, 2018. Accession No. ML18019A078; For the Nuclear Regulatory Commission.
Brief description of amendments: The documents related to these amendments Tara Inverso,
amendments revised the Emergency are listed in the Safety Evaluation (SE) Acting Deputy Director, Division of Operating
Plan for St. Lucie to adopt the fire- enclosed with the amendments. Reactor Licensing, Office of Nuclear Reactor
related notification of unusual event Renewed Facility Operating License Regulation.
requirement of the Nuclear Energy Nos. DPR–31 and DPR–41: Amendments [FR Doc. 2018–06668 Filed 4–9–18; 8:45 am]
Institute 99–01, Revision 6, Emergency revised the Renewed Facility Operating BILLING CODE 7590–01–P
Action Level scheme. Licenses and TSs.
Date of issuance: March 26, 2018. Date of initial notice in Federal
Effective date: As of the date of Register: June 19, 2017 (82 FR 27889). NUCLEAR REGULATORY
issuance and shall be implemented The supplemental letter dated October COMMISSION
within 90 days. 4, 2017, provided additional [Docket No. 72–10; NRC–2018–0057]
Amendment Nos.: 244 and 195. A information that clarified the
publicly-available version is in ADAMS application, did not expand the scope of Northern States Power Company—
under Accession No. ML18046A712; the application as originally noticed, Minnesota; Prairie Island Nuclear
documents related to these amendments and did not change the NRC staff’s Generating Plant; Independent Spent
are listed in the Safety Evaluation original proposed no significant hazards Fuel Storage Installation; Correct
enclosed with the amendments. consideration determination as Inspection Intervals Acceptance
Renewed Facility Operating License published in the Federal Register. Criteria
Nos. DPR–67 and NPF–16: The The Commission’s related evaluation
amendments revised the Renewed of the amendments is contained in an AGENCY: Nuclear Regulatory
Facility Operating Licenses. SE dated March 19, 2018. Commission.
Date of initial notice in Federal No significant hazards consideration ACTION: License amendment application;
Register: February 14, 2018 (83 FR comments received: No. issuance.
daltland on DSKBBV9HB2PROD with NOTICES
6621). This notice provided an
opportunity to request a hearing by Southern Nuclear Operating Company, SUMMARY: The U.S. Nuclear Regulatory
April 15, 2018, but indicated that if the Docket Nos. 52–025 and 52–026, Vogtle Commission (NRC) reconciled an error
Commission makes a final no significant Electric Generating Plant (VEGP), Units in the Northern States Power
hazards consideration determination, 3 and 4, Burke County, Georgia Company—Minnesota (NSPM) Renewed
any such hearing would take place after Date of amendment request: August License No. SNM–2506. Under this
issuance of the amendments. 31, 2017. license, NSPM is authorized to receive,
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![Federal Register / Vol. 83, No. 69 / Tuesday, April 10, 2018 / Notices 15421
possess, store, and transfer spent set inspection intervals to be ‘‘not less publication of a notice of proposed
nuclear fuel and associated radioactive than’’ those in the American Concrete action and an opportunity for hearing or
materials at the Prairie Island Institute (ACI) Code; however, NRC- a notice of hearing is not warranted.
Independent Spent Fuel Storage issued documents demonstrated the Notice is hereby given of the right of
Installation. NRC had intended the intervals ‘‘not to interested persons to request a hearing
DATES: April 10, 2018. exceed’’ those in the ACI Code. on whether the action should be
As a result of its review, the NRC staff rescinded or modified.
ADDRESSES: Please refer to Docket ID
determined that License Condition 22(a) Dated at Rockville, Maryland, this 4th day
NRC–2018–0057 when contacting the
should read ‘‘not to exceed’’ instead of of April, 2018.
NRC about the availability of
‘‘not less than’’ and has amended the
information regarding this document. For the Nuclear Regulatory Commission.
license to correct this error. When the
You may obtain publicly-available John McKirgan,
NRC staff evaluated visual inspection
information related to this document Chief, Spent Fuel Licensing Branch, Division
intervals in its Safety Evaluation Report
using any of the following methods: of Spent Fuel Management, Office of Nuclear
(SER) dated December 2015 (ADAMS
• Federal Rulemaking Website: Go to Material Safety and Safeguards.
Accession No. ML15336A230) for
http://www.regulations.gov and search [FR Doc. 2018–07304 Filed 4–9–18; 8:45 am]
Renewed License No. SNM–2506,
for Docket ID NRC–2018–0057. Address BILLING CODE 7590–01–P
Section 3.5.1.3 of the SER clearly
questions about NRC dockets to Jennifer
articulated the staff’s expectation that
Borges; telephone: 301–287–9127;
accessible areas of the concrete pads
email: Jennifer.Borges@nrc.gov. For NUCLEAR REGULATORY
would be visually inspected at intervals
technical questions, contact the COMMISSION
‘‘not to exceed’’ 5 years. Further, the
individual listed in the FOR FURTHER
SER states the staff determined that the [NRC–2017–0209]
INFORMATION CONTACT section of this
specific inspection intervals and areas
document. Information Collection: General
• NRC’s Agencywide Documents of inspection coverage in the Aging
Management Program (AMP) for Domestic Licenses for Byproduct
Access and Management System
concrete pads are appropriate based Material
(ADAMS): You may obtain publicly
available documents online in the upon the technical references pertinent
AGENCY: Nuclear Regulatory
ADAMS Public Documents collection at to age-related degradation of concrete in
Commission.
http://www.nrc.gov/reading-rm/ similar environments, including
American Concrete Institute guides ACTION: Renewal of existing information
adams.html. To begin the search, select collection; request for comment.
‘‘ADAMS Public Documents’’ and then (ACI) 349.3R–02 (ACI, 2002), ACI
select ‘‘Begin Web-based ADAMS 201.1R–08 (ACI, 2008), American SUMMARY: The U.S. Nuclear Regulatory
Search.’’ For problems with ADAMS, National Standards Institute/American Commission (NRC) invites public
please contact the NRC’s Public Society of Civil Engineers guidelines comment on the renewal of Office of
(ANSI/ASCE) 11–99 (ASCE, 2000), and Management and Budget (OMB)
Document Room (PDR) reference staff at
reactor renewal guidance provided in approval for an existing collection of
1–800–397–4209, 301–415–4737, or by
NRC NUREG–1801 (NRC, 2010b). The information. The information collection
email to pdr.resource@nrc.gov. The
‘‘not less than’’ language included in is entitled, ‘‘General Domestic Licenses
ADAMS accession number for each
error is inconsistent with the NRC staff’s for Byproduct Material.’’
document referenced (if it is available in
SER and has the unintended
ADAMS) is provided the first time that DATES: Submit comments by June 11,
consequence of preventing NSPM from
it is mentioned in this document. 2018. Comments received after this date
• NRC’s PDR: You may examine and conducting more frequent inspections.
Accordingly, based on the staff’s will be considered if it is practical to do
purchase copies of public documents at so, but the Commission is able to ensure
findings, the NRC made the necessary
the NRC’s PDR, Room O1–F21, One consideration only for comments
change and issued Amendment No. 10
White Flint North, 11555 Rockville to License No. SNM–2506 to correct received on or before this date.
Pike, Rockville, Maryland 20852. License Condition 22(a). Amendment ADDRESSES: You may submit comments
FOR FURTHER INFORMATION CONTACT: No. 10 was effective as of its date of by any of the following methods:
John-Chau Nguyen, Office of Nuclear issuance. The NRC staff’s findings are • Federal Rulemaking Website: Go to
Material Safety and Safeguards, U.S. documented in a SER dated March 6, http://www.regulations.gov and search
Nuclear Regulatory Commission, 2018 (ADAMS Accession No. for Docket ID NRC–2017–0209. Address
Washington, DC 20555–0001; telephone: ML18057A284), which determined that questions about NRC dockets to Jennifer
301–415–0262; email: John- the amendment complies with the Borges; telephone: 301–287–9127;
Chau.Nguyen@nrc.gov. Atomic Energy Act of 1954, as amended, email: Jennifer.Borges@nrc.gov. For
SUPPLEMENTARY INFORMATION: After and NRC regulations. The issuance of technical questions, contact the
receiving Renewed License No. SNM– Amendment No. 10 satisfies the criteria individual listed in the FOR FURTHER
2506, the NSPM staff began to review it specified in § 51.22(c)(11) of title 10 of INFORMATION CONTACT section of this
and prepare procedures to implement the Code of Federal Regulations (10 document.
new requirements. NSPM submitted an CFR) for a categorical exclusion. • Mail comments to: David Cullison,
email on February 9, 2016 (ADAMS Therefore, the preparation of an Office of the Chief Information Officer,
Accession No. ML17324B332), environmental assessment or an Mail Stop: T–2–F43, U.S. Nuclear
requesting the NRC to, among other environmental impact statement is not Regulatory Commission, Washington,
daltland on DSKBBV9HB2PROD with NOTICES
things, address an apparent error in required. DC 20555–0001.
License Condition 22(a) of Renewed In accordance with 10 CFR For additional direction on obtaining
License No. SNM–2506 so that NSPM 72.46(b)(2), the NRC has determined information and submitting comments,
could establish procedures containing that Amendment No. 10 does not see ‘‘Obtaining Information and
the correct inspection intervals present a genuine issue as to whether Submitting Comments’’ in the
acceptance criteria for Renewed License the public health and safety will be SUPPLEMENTARY INFORMATION section of
No. SNM–2506. License Condition 22(a) significantly affected. Therefore, the this document.
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Document Created: 2018-04-09 23:51:38
Document Modified: 2018-04-09 23:51:38
| Category | Regulatory Information | |
| Collection | Federal Register | |
| sudoc Class | AE 2.7: GS 4.107: AE 2.106: | |
| Publisher | Office of the Federal Register, National Archives and Records Administration | |
| Section | Notices | |
| Action | License amendment application; issuance. | |
| Dates | April 10, 2018. | |
| 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: John- [email protected] | |
| FR Citation | 83 FR 15420 |
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