|
|---|
Category:Federal Register Notice
MONTHYEARML24141A2852024-05-21021 May 2024
FRN - Northern States Power Company, Prairie Island Independent Spent Fuel Storage Installation License Amendment Application
ML24044A0732024-02-28028 February 2024
Federal Register Notice - Issuance of Multiple Exemptions Regarding 10 CFR Part 73 - January 2024
ML23235A0762023-09-0101 September 2023
FRN: Docketing- Prairie Island ISFSI Amendment Request 12
ML21280A3842021-10-15015 October 2021
Individual Notice of Consideration of Issuance of Amendments to Renewed Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing
ML21280A3852021-10-15015 October 2021
FRN -Prairie Island Nuclear Generating Plant, Units 1 and 2 Individual Notice of Consideration of Issuance of Amendments to Renewed Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, and Opportunity Fo
ML20335A0902020-12-21021 December 2020
Federal Register Notice - November 2020 COVID-19 Exemptions
ML20247J3972020-10-30030 October 2020
Federal Register - Notice of Issuance of License Amendment Application
ML20035C4082020-02-18018 February 2020
Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 02/25/2020
ML19168A0842019-06-26026 June 2019
Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 07/02/2019
ML19162A1632019-06-21021 June 2019
Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations
NRC-2019-0065, Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 03/12/20192019-02-28028 February 2019
Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 03/12/2019
ML19056A5352019-02-28028 February 2019
Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 03/12/2019
ML19042A3062019-02-15015 February 2019
Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 2/26/2019
ML18173A1792018-08-0707 August 2018
OEDO-17-00070 - Notice of Issuance of Director'S Decision, 2.206 Petition for Emergency Enforcement Action Per 10 CFR 2.206 at Listed U.S. Reactors with Forged Components and Parts Manufactured at France'S AREVA-Le Creusot Forge and Japan C
NRC-2018-0096, Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: May 22, 20182018-05-14014 May 2018
Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: May 22, 2018
ML18127B7232018-05-14014 May 2018
Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: May 22, 2018
ML18068A1792018-04-0404 April 2018
Federal Register Notice: 72-10 Renewed License Amendment 10
ML17200A0652017-08-30030 August 2017
OEDO-17-00070 - Acknowledgement FRN, Paul Gunter, Beyond Nuclear, 2.206 Petition for Emergency Enforcement Action Per 10 CFR 2.206 at Listed U.S. Reactors with Forged Components and Parts Manufactured at France'S AREVA-Le Creusot Forge and
ML17198A3292017-08-30030 August 2017
OEDO-17-00070 - Acknowledgement Letter, Paul Gunter, Beyond Nuclear, Petition for Emergency Enforcement Action Per 10 CFR 2.206 at Listed U.S. Reactors with Forged Components and Parts Manufactured at France'S AREVA-Le Creusot Forge and Jap
ML15239A6882015-09-17017 September 2015
Withdrawal of an Amendment Request
ML15148A3762015-06-0101 June 2015
Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Published June 9, 2015
ML14266A1912014-08-11011 August 2014
Draft FRN - Issuance of Environmental Assessment and Finding of No Significant Impact (Prairie Island ISFSI Exemption)
ML14189A6652014-07-24024 July 2014
Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Considerations and Containing Sensitive Unclassified Non-Safeguards Information - August 5, 2014
ML14100A3112014-04-0909 April 2014
Frn/Draft - Issuance of Environmental Assessment and Finding of No Significant Impact - PI-PSP Exemption
NRC-2014-0028, Biweekly Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: February 18, 20142014-02-10010 February 2014
Biweekly Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: February 18, 2014
ML14037A4142014-02-10010 February 2014
Biweekly Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: February 18, 2014
ML13228A3992013-08-12012 August 2013
Letter to Holders of Independent Spent Fuel Storage Installation (ISFSI) Licenses Re Rescission of Certain Security Orders Concerning Spent Nuclear Fuel in Transit - Rin 3150-AI64 (NRC-2009-0163) EA-02-109
ML13225A5572013-08-12012 August 2013
Rescission of Certain Security Orders Concerning Spent Nuclear Fuel in Transit
ML12056A0442012-03-12012 March 2012
Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Effective Immediately) - to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status
NRC-2012-0067, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Effective Immediately) - to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status2012-03-12012 March 2012
Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Effective Immediately) - to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status
ML11349A0052011-12-15015 December 2011
Biweekly Report - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations: Fr Publication Date December 27, 2011
NRC-2011-0290, Biweekly Report - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations: Fr Publication Date December 27, 20112011-12-15015 December 2011
Biweekly Report - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations: Fr Publication Date December 27, 2011
ML11237A0072011-08-25025 August 2011
FRN: General Notice. Biweekly Sholly Report - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations; Fr Publication Date: 9/6/11
NRC-2011-0205, FRN: General Notice. Biweekly Sholly Report - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations; Fr Publication Date: 9/6/112011-08-25025 August 2011
FRN: General Notice. Biweekly Sholly Report - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations; Fr Publication Date: 9/6/11
ML1122302752011-08-11011 August 2011
Biweekly Sholly Report - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations; Fr Publication Date: 8/23/2011
NRC-2011-0187, Biweekly Sholly Report - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations; Fr Publication Date: 8/23/20112011-08-11011 August 2011
Biweekly Sholly Report - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations; Fr Publication Date: 8/23/2011
ML11147A1232011-06-27027 June 2011
Issuance of Renewed Facility Operating Licenses for Prairie Island Nuclear Generating Plant
ML11147A1402011-06-27027 June 2011
Notice of Issuance of Renewed Facility Operating License Nos. DPR-42 and DPR-60 for an Additional 20-Year Period Record of Decision
NRC-2009-0507, Prairie Island Nuclear Generating Plant, Units 1 and 2 Notice of Issuance of Renewed Facility Operating License Nos. DPR-42 and DPR-60 for an Additional 20-Year Period Record of Decision2011-06-27027 June 2011
Prairie Island Nuclear Generating Plant, Units 1 and 2 Notice of Issuance of Renewed Facility Operating License Nos. DPR-42 and DPR-60 for an Additional 20-Year Period Record of Decision
ML1107400442011-05-17017 May 2011
Notice of Availability of the Final Plant-Specific Supplement 39 to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding Prairie Island Nuclear Generating Plant, Units 1 and 2
ML1105303992011-02-23023 February 2011
FRN: General Notice: Prairie Island Nuclear Generating Plant, Unit 1 - Correction to Notice of Consideration of Issuance of Amendments to Facility Operating Licenses Involving No Significant Hazards Consideration; Correction
ML1104103732011-02-10010 February 2011
Sholly Report for Fr Publication on February 22, 2011
NRC-2011-0040, Sholly Report for Fr Publication on February 22, 20112011-02-10010 February 2011
Sholly Report for Fr Publication on February 22, 2011
ML1024302392010-11-22022 November 2010
Exemption from the Requirements of 10 CFR Section 50.46 and Appendix K to 10 CFR Part 50, to Allow Use of Optimized Zirlo as Fuel Rod Cladding Material
ML1026407762010-10-0101 October 2010
Withdrawal of an Amendment Request
ML1026407802010-10-0101 October 2010
United States Nuclear Regulatory Commission Northern States Power Company - Minnesota Docket Nos. 50-282 and 50-306 Notice of Withdrawal of Application for Amendment to Facility Operating License
NRC-2010-0325, United States Nuclear Regulatory Commission Northern States Power Company - Minnesota Docket Nos. 50-282 and 50-306 Notice of Withdrawal of Application for Amendment to Facility Operating License2010-10-0101 October 2010
United States Nuclear Regulatory Commission Northern States Power Company - Minnesota Docket Nos. 50-282 and 50-306 Notice of Withdrawal of Application for Amendment to Facility Operating License
ML1017201962010-09-27027 September 2010
Environmental Assessment and Finding of No Significant Impact
NRC-2010-0324, Environmental Assessment and Finding of No Significant Impact2010-09-27027 September 2010
Environmental Assessment and Finding of No Significant Impact
ML1016500342010-07-20020 July 2010
G20090510/EDATS: OEDO-2009-0541 - Federal Register Notice of Issuance of Director'S Decision Under 10 CFR 2.206
2024-05-21
[Table view] |
Text
[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 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, 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 Web Site: 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; e-mail: Jennifer.Borges@nrc.gov. For technical questions, contact the individual listed in the FOR FURTHER INFORMATION CONTACT section of this document.
- NRCs 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 NRCs Public Document Room (PDR) reference staff at 1-800-397-4209, 301-415-4737, or by e-mail 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.
- NRCs PDR: You may examine and purchase copies of public documents at the NRCs 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; e-mail: John-Chau.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 e-mail on February 9, 2016 (ADAMS Accession No.
2
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 staffs 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 staffs SER and has the unintended consequence of preventing NSPM from conducting more frequent inspections.
3
Accordingly, based on the staffs 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 staffs 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 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.
/RA/
John McKirgan, Chief, Spent Fuel Licensing Branch, Division of Spent Fuel Management, Office of Nuclear Material Safety and Safeguards.
4
