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| | number = ML16320A449 | | | number = ML16320A449 |
| | issue date = 11/14/2016 | | | issue date = 11/14/2016 |
| | title = Prairie Island Nuclear Generating Plant, Units 1 and 2 - NRC Security Baseline Inspection Report 05000282/2016405; 05000306/2016405 (Cover Letter Only) | | | title = NRC Security Baseline Inspection Report 05000282/2016405; 05000306/2016405 (Cover Letter Only) |
| | author name = Orth S K | | | author name = Orth S |
| | author affiliation = NRC/RGN-III/DRS/PSB | | | author affiliation = NRC/RGN-III/DRS/PSB |
| | addressee name = Northard S | | | addressee name = Northard S |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE RD. SUIT E 210 LISLE, IL 60532 | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION ber 14, 2016 |
| -4352 November 14, 2016 Mr. Scott Northard Site Vice President Prairie Island Nuclear Generating Plant Northern States Power Company, Minnesota
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| 1717 Wakonade Drive East Welch, MN 55089
| | ==SUBJECT:== |
| | | PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 - |
| SUBJECT: PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 | | NRC SECURITY BASELINE INSPECTION REPORT 05000282/2016405; 05000306/2016405 |
| - NRC SECURITY BASELINE INSPECTION REPORT 05000282/2016405; 05000306/2016405
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| ==Dear Mr. Northard:== | | ==Dear Mr. Northard:== |
| On October 5, 201 6, the U.S. Nuclear Regulatory Commission (NRC) completed a security inspection at your Prairie Island Nuclear Generating Plant, Units 1 and 2 | | On October 5, 2016, the U.S. Nuclear Regulatory Commission (NRC) completed a security inspection at your Prairie Island Nuclear Generating Plant, Units 1 and 2, and the NRC inspector discussed the results of this inspection with you and other members of your staff. |
| , and the NRC inspector discussed the results of this inspection with you and other members of your staff. The results of this inspection are documented in the enclosed inspection report | |
| . The NRC inspector did not identify any finding or violation of more than minor significance.
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| This letter will be available electronically for public inspection and copying at http://www.nrc.gov/reading
| | The results of this inspection are documented in the enclosed inspection report. |
| -rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code o f Federal Regulations (CFR) 2.390, "Public Inspections, Exemptions, Requests for Withholding
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| ." However, the enclosed report contains Security
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| -Related Information, so the enclosed report will not be made publically available in accordance with 10 CFR 2.390(d)(1). If you choose to provide a response that contains Security
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| -Related Information, please mark your entire response "Security
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| -Related Information
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| - Withhold from Enclosure contains Sensitive Unclassified Non-Safeguards Information. When separated from enclosure, this transmittal document is decontrolled. public disclosure under 10 CFR 2.390" in accordance with 10 CFR 2.390(d)(1) and follow the instructions for withholding in 10 CFR 2.390 (b)(1). The NRC is waiving the affidavit requirements for your response in accordance with 10 CFR 2.390(b)(1)(ii).
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| Sincerely,/RA/ Steven K. Orth , Branch Chief Plant Support Branch Division of Reactor Safety
| | The NRC inspector did not identify any finding or violation of more than minor significance. |
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| Docket Nos. 05000282; 05000306 License Nos. DPR
| | This letter will be available electronically for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations (CFR) 2.390, Public Inspections, Exemptions, Requests for Withholding. However, the enclosed report contains Security-Related Information, so the enclosed report will not be made publically available in accordance with 10 CFR 2.390(d)(1). If you choose to provide a response that contains Security-Related Information, please mark your entire response Security-Related Information Withhold from Enclosure contains Sensitive Unclassified Non-Safeguards Information. When separated from enclosure, this transmittal document is decontrolled. public disclosure under 10 CFR 2.390 in accordance with 10 CFR 2.390(d)(1) and follow the instructions for withholding in 10 CFR 2.390 (b)(1). The NRC is waiving the affidavit requirements for your response in accordance with 10 CFR 2.390(b)(1)(ii). |
| -42; DPR-60 Nonpublic | |
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| ===Enclosure:===
| | Sincerely, |
| IR 05000282/2016405; 05000306/2016405 cc w/o encl: | | /RA/ |
| Distribution via LISTSERV | | Steven K. Orth, Branch Chief Plant Support Branch Division of Reactor Safety Docket Nos. 05000282; 05000306 License Nos. DPR-42; DPR-60 Nonpublic Enclosure: |
| | IR 05000282/2016405; 05000306/2016405 cc w/o encl: Distribution via LISTSERV |
| }} | | }} |
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Category:Letter
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Issuance of Amendments Revise Technical Specification 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)
L-PI-23-034, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System,2024-01-0202 January 2024
Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System,
L-PI-23-035, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report2023-12-20020 December 2023
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Independent Spent Fuel Storage Installation Security Inspection Report 07200010/2023401
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and Independent Spent Fuel Storage Installation, Revision to Correspondence Service List for Northern States Power - Minnesota
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Acceptance of Requested Licensing Action Amendment Request to Revise Surveillance Requirement 3.8.1.2 Note 3
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Security Baseline Inspection Report 05000282/2023401 and 05000306/2023401
L-PI-23-033, Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 32023-12-0505 December 2023
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Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request to Revise SR 3.8.1.2 Note 3
ML23319A3182023-11-15015 November 2023
Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
IR 05000282/20230032023-11-0808 November 2023
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ML23311A3572023-11-0707 November 2023
Core Operating Limits Report (COLR) for Prairie Island Nuclear Generating Plant (PINGP) Unit 2. Cycle 33. Revision 0
ML23285A3062023-10-12012 October 2023
Implementation of the Fleet Standard Emergency Plan for the Monticello Nuclear Generating Plant and the Prairie Island Nuclear Generating Plant
ML23270B9022023-09-29029 September 2023
Review of Reactor Vessel Material Surveillance Program Capsule N Technical Report
L-PI-23-025, License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 32023-09-28028 September 2023
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ML23265A2532023-09-26026 September 2023
Review of Reactor Vessel Material Surveillance Program Capsule N Technical Report
ML23262B0372023-09-19019 September 2023
Response to NRC Request for Additional Information Regarding the 2023 Monticello and Prairie Island Plant Decommissioning Funding Status Reports
ML23256A1682023-09-13013 September 2023
Independent Spent Fuel Storage Installation and Monticello Nuclear Generating Plant - Voluntary Security Clearance Program 2023 Insider Threat Program Self-Inspection
L-PI-23-023, Baffle Former Bolts Alternate Aging Management Strategy2023-09-11011 September 2023
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Updated Inspected Plan for Prairie Island Nuclear Generating Plant Report 05000282/2023005 and 05000306/2023005
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NRC Inspection Report 05000282/2023010 and 05000306/2023010
ML23222A0122023-08-10010 August 2023
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Integrated Inspection Report 05000282/2023002 and 05000306/2023002
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Request for Information for an NRC Quadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000282/2024010; 05000306/2024010
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Independent Spent Fuel Storage Installation, and Monticello Nuclear Generating Plant, Changes in Foreign Ownership, Control or Influence
ML23202A0032023-07-21021 July 2023
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ML23199A0922023-07-18018 July 2023
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ML23195A1732023-07-14014 July 2023
Revision of Standard Practice Procedures Plan
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2024-02-01
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION ber 14, 2016
SUBJECT:
PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 -
NRC SECURITY BASELINE INSPECTION REPORT 05000282/2016405; 05000306/2016405
Dear Mr. Northard:
On October 5, 2016, the U.S. Nuclear Regulatory Commission (NRC) completed a security inspection at your Prairie Island Nuclear Generating Plant, Units 1 and 2, and the NRC inspector discussed the results of this inspection with you and other members of your staff.
The results of this inspection are documented in the enclosed inspection report.
The NRC inspector did not identify any finding or violation of more than minor significance.
This letter will be available electronically for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations (CFR) 2.390, Public Inspections, Exemptions, Requests for Withholding. However, the enclosed report contains Security-Related Information, so the enclosed report will not be made publically available in accordance with 10 CFR 2.390(d)(1). If you choose to provide a response that contains Security-Related Information, please mark your entire response Security-Related Information Withhold from Enclosure contains Sensitive Unclassified Non-Safeguards Information. When separated from enclosure, this transmittal document is decontrolled. public disclosure under 10 CFR 2.390 in accordance with 10 CFR 2.390(d)(1) and follow the instructions for withholding in 10 CFR 2.390 (b)(1). The NRC is waiving the affidavit requirements for your response in accordance with 10 CFR 2.390(b)(1)(ii).
Sincerely,
/RA/
Steven K. Orth, Branch Chief Plant Support Branch Division of Reactor Safety Docket Nos. 05000282; 05000306 License Nos. DPR-42; DPR-60 Nonpublic Enclosure:
IR 05000282/2016405; 05000306/2016405 cc w/o encl: Distribution via LISTSERV
