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Category:Letter
MONTHYEARIR 05000282/20230042024-02-0101 February 2024 Integrated Inspection Report 05000282/2023004 and 05000306/2023004 ML23356A1232024-01-29029 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) ML24024A0722024-01-24024 January 2024 Independent Spent Fuel Storage Installation, Onticello, Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML24017A0182024-01-19019 January 2024 Confirmation of Initial License Examination ML23356A0032024-01-17017 January 2024 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 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 Report IR 07200010/20234012023-12-20020 December 2023 Independent Spent Fuel Storage Installation Security Inspection Report 07200010/2023401 ML23349A0572023-12-15015 December 2023 and Independent Spent Fuel Storage Installation, Revision to Correspondence Service List for Northern States Power - Minnesota ML23215A1672023-12-15015 December 2023 Acceptance of Requested Licensing Action Amendment Request to Revise Surveillance Requirement 3.8.1.2 Note 3 IR 05000282/20234012023-12-13013 December 2023 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 Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 3 ML23304A1632023-11-15015 November 2023 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 Integrated Inspection Report 05000282/2023003 and 05000306/2023003 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 License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 3 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 Baffle Former Bolts Alternate Aging Management Strategy IR 05000282/20230052023-08-30030 August 2023 Updated Inspected Plan for Prairie Island Nuclear Generating Plant Report 05000282/2023005 and 05000306/2023005 IR 05000282/20230102023-08-17017 August 2023 NRC Inspection Report 05000282/2023010 and 05000306/2023010 ML23222A0122023-08-10010 August 2023 Independent Spent Fuel Storage Installation and Monticello Nuclear Generating Plant - Changes in Foreign Ownership, Control or Influence IR 05000282/20230022023-08-0303 August 2023 Integrated Inspection Report 05000282/2023002 and 05000306/2023002 ML23214A2032023-08-0202 August 2023 Request for Information for an NRC Quadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000282/2024010; 05000306/2024010 ML23206A2342023-07-25025 July 2023 Independent Spent Fuel Storage Installation, and Monticello Nuclear Generating Plant, Changes in Foreign Ownership, Control or Influence ML23202A0032023-07-21021 July 2023 Independent Spent Fuel and Independent Spent Fuel Storage Installation, Monticello Nuclear Generating Plant, Submittal of Quality Assurance Topical Report (NSPM-1) ML23199A0922023-07-18018 July 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000306/2023004 ML23195A1732023-07-14014 July 2023 Revision of Standard Practice Procedures Plan L-PI-23-018, License Amendment Request to Revise ISFSI Technical Specification 4.4 to Allow Use of a Code Alternative to ASME Code, NB-5130, Examination of Weld Edge Preparation Surfaces, for the TN-40HT2023-07-14014 July 2023 License Amendment Request to Revise ISFSI Technical Specification 4.4 to Allow Use of a Code Alternative to ASME Code, NB-5130, Examination of Weld Edge Preparation Surfaces, for the TN-40HT ML23181A0192023-06-30030 June 2023 Independent Spent Fuel Storage Installation, Revision to Correspondence Service List for Northern States Power - Minnesota ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III L-PI-23-006, License Amendment Request to Revise Technical Specification 3.7.8 Required Actions2023-06-22022 June 2023 License Amendment Request to Revise Technical Specification 3.7.8 Required Actions L-PI-23-016, 2022 10 CFR 50.46 LOCA Annual Report2023-06-14014 June 2023 2022 10 CFR 50.46 LOCA Annual Report IR 05000282/20234202023-06-0101 June 2023 Security Baseline Inspection Report 05000282/2023420 and 05000306/2023420 ML23150A1722023-05-30030 May 2023 Preparation and Scheduling of Operator Licensing Examinations 2024-02-01
[Table view] Category:Notice of Violation
MONTHYEARIR 05000282/20150082016-01-0505 January 2016 IR 05000282/2015008 and 05000306/2015008; 10/05/2015 - 11/24/2015; Prairie Island Nuclear Generating Plant, Units 1 and 2; Annual Problem Identification and Resolution Inspection (Njf) ML16005A5672016-01-0505 January 2016 IR 05000282/2015008 and 05000306/2015008; 10/05/2015 - 11/24/2015; Prairie Island Nuclear Generating Plant, Units 1 and 2; Annual Problem Identification and Resolution Inspection (Njf) IR 05000282/20134072014-02-12012 February 2014 EA-13-210, Prairie Island Nuclear Generating Plant; Notice of Violation - Closure of NRC Investigation 3-2013-017; NRC Report No. 05000282/2013407; 05000306/2013407 - Cover Letter Only IR 05000282/20130032013-07-30030 July 2013 IR 05000282-13-003 & 05000306-13-003, 04/01/2013 - 06/30/2013, Prairie Island Nuclear Generating Plant, Unit 1 & 2, NRC Integrated Inspection Report and Notice of Violation IR 05000282/20135032013-03-26026 March 2013 EA-12-273, Prairie Island Nuclear Generating Plant, Unit 1, Final Significance Determination of a White Finding with Assessment Followup and Notice of Violation; NRC Inspection Report No. 05000282/2013503 ML12104A1742012-04-12012 April 2012 IA-12-003 Barnes, Final Letter and Notice of Violation IR 05000282/20110112011-08-17017 August 2011 EA-11-110, Prairie Island Nuclear Generating Plant, Units 1 and 2, Final Significance Determination of White Finding with Assessment Followup and Notice of Violation; NRC Inspection Report 05000282-11-011 IR 05000282/20090142009-10-27027 October 2009 IR 050000282-09-014, on 05/01/2009, for Prairie Island, Units 1 and 2, Notice of Violation ML0924506242009-09-0303 September 2009 EA-09-167, Prairie Island Nuclear Generating Plant, Unit 2, Final Significance Determination for a White Finding and Notice of Violation, NRC Inspection Report No. 05000306-09-013 IR 05000282/20090082009-05-0606 May 2009 NRC000021-Final Significance Determining of White Finding and Notice of Violation; NRC Inspection Report No. 05000282/2009008; 05000306/2009008; Prairie Island Nuclear Generating Plant, Units 1 and 2 ML0912700802009-05-0606 May 2009 IR 05000282-09-008, and IR 05000306-09-008, for Prairie Island, Units 1 & 2, Final Significance Determination of White Finding and Notice of Violation IR 05000282/20060152006-09-28028 September 2006 EA-06-162, Prairie Island Nuclear Generating Plant, Notice of Violation (NRC Inspection Report 05000282/2006015; and 05000306/2006015 and NRC Investigation Report No. 3-2006-004) ML0701001382006-08-22022 August 2006 Dennis L. Koehl Ltr. Apparent Violation of Employee Protection Requirements (Office of Investigations Report No. 3-2005-010) ML0235002672002-12-13013 December 2002 IA-02-012, Hiedeman, Notice of Violation 2016-01-05
[Table view] Category:Inspection Report
MONTHYEARIR 05000282/20230042024-02-0101 February 2024 Integrated Inspection Report 05000282/2023004 and 05000306/2023004 IR 07200010/20234012023-12-20020 December 2023 Independent Spent Fuel Storage Installation Security Inspection Report 07200010/2023401 IR 05000282/20234012023-12-13013 December 2023 Security Baseline Inspection Report 05000282/2023401 and 05000306/2023401 IR 05000282/20230032023-11-0808 November 2023 Integrated Inspection Report 05000282/2023003 and 05000306/2023003 IR 05000282/20230052023-08-30030 August 2023 Updated Inspected Plan for Prairie Island Nuclear Generating Plant Report 05000282/2023005 and 05000306/2023005 IR 05000282/20230102023-08-17017 August 2023 NRC Inspection Report 05000282/2023010 and 05000306/2023010 IR 05000282/20230022023-08-0303 August 2023 Integrated Inspection Report 05000282/2023002 and 05000306/2023002 IR 05000282/20234202023-06-0101 June 2023 Security Baseline Inspection Report 05000282/2023420 and 05000306/2023420 IR 05000282/20230112023-05-16016 May 2023 Biennial Problem Identification and Resolution Inspection Report 05000282/2023011 and 05000306/2023011 IR 05000282/20230012023-05-10010 May 2023 Integrated Inspection Report 05000282/2023001 and 05000306/2023001 IR 05000282/20220062023-03-0101 March 2023 Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report, Units 1 and 2 (Report 05000282/2022006 and 05000306/2022006) IR 05000282/20224042023-01-30030 January 2023 Material Control and Accounting Program Inspection Report 05000282/2022404 and 05000306/2022404 (Public) IR 05000282/20220042023-01-26026 January 2023 Integrated Inspection Report 05000282/2022004 and 05000306/2022004 IR 05000282/20224032023-01-24024 January 2023 Security Baseline Inspection Report 05000282/2022403 and 05000306/2022403 IR 05000282/20220022022-12-0808 December 2022 RE-Issue Prairie Island Nuclear Generating Plant Integrated Inspection Report 05000282/2022002 and 05000306/2022002 IR 05000282/20224022022-11-30030 November 2022 Cyber Security Inspection Report 05000282/2022402 and 05000306/2022402 IR 07200010/20222012022-11-0909 November 2022 TN-40HT, Dry Storage Cask, Inspection Report No. 07200010/2022201 IR 05000282/20220032022-11-0101 November 2022 Integrated Inspection Report 05000282/2022003 and 05000306/2022003 IR 05000282/20220112022-09-26026 September 2022 Phase 4 Post-Approval Site Inspection for License Renewal Report 05000282/2022011 and 05000306/2022011 IR 05000282/20223012022-08-31031 August 2022 NRC Initial License Examination Report 05000282/2022301; 05000306/2022301 IR 05000282/20220052022-08-29029 August 2022 Updated Inspection Plan for Prairie Island Nuclear Generating Plant (Report 05000282/2022005; 05000306/2022005) IR 05000282/20225012022-08-22022 August 2022 Emergency Preparedness Biennial Exercise Inspection Report 05000282/2022501 and 05000306/2022501 ML22227A1902022-08-16016 August 2022 Island Nuclear Generating Plant, Unit 1 - Notification of NRC Baseline Inspection and Request for Information: Inspection Report 05000282/2022004 ML22222A1732022-08-11011 August 2022 Integrated Inspection Report 05000282/2022002 and 05000306/2022002 IR 05000282/20220102022-06-24024 June 2022 Triennial Fire Protection Inspection Report 05000282/2022010 and 05000306/2022010 IR 05000282/20224012022-05-23023 May 2022 Security Baseline Inspection Report 05000282/2022401 and 05000306/2022401 ML22103A2522022-05-0404 May 2022 Review of the 2021 Steam Generator Tube Inspection Report IR 05000282/20220012022-05-0303 May 2022 Integrated Inspection Report 05000282/2022001, 05000306/2022001, and 07200010/2020001 IR 05000282/20210062022-03-0202 March 2022 Annual Assessment Letter (Report 05000282/2021006 and 05000306/2021006) IR 05000282/20210042022-02-11011 February 2022 Integrated Inspection Report 05000282/2021004 and 05000306/2021004 ML22017A0052022-01-17017 January 2022 (PINGP) 2021 Unit 2 180-Day Steam Generator Tube Inspection Report IR 05000282/20214032021-12-0202 December 2021 Security Baseline Inspection Report 05000282/2021403 and 05000306/2021403 IR 05000282/20210032021-11-12012 November 2021 Integrated Inspection Report 05000282/2021003 and 05000306/2021003 IR 05000282/20210122021-10-27027 October 2021 NRC Inspection Report 05000282/2021012 and 05000306/2021012 IR 05000282/20210052021-09-0101 September 2021 Updated Inspection Plan for Prairie Island Nuclear Generating Plant Units 1 and 2 (Report 05000282/2021005 and 05000306/2021005) IR 05000282/20215012021-08-25025 August 2021 Emergency Preparedness Biennial Exercise Inspection Report 05000282/2021501 and 05000306/2021501 IR 05000282/20210022021-08-0606 August 2021 Integrated Inspection Report 05000282/2021002 and 05000306/2021002 IR 05000282/20214022021-07-28028 July 2021 Security Baseline Inspection Report 05000282/2021402 and 05000306/2021402 IR 05000282/20210102021-06-22022 June 2021 Design Basis Assurance Inspection (Teams) Inspection Report 05000282/2021010 and 05000306/2021010 IR 05000282/20210112021-06-0303 June 2021 Biennial Problem Identification and Resolution Inspection Report 05000282/2021011 and 05000306/2021011 IR 05000282/20210012021-05-0606 May 2021 Integrated Inspection Report 05000282/2021001 and 05000306/2021001 IR 05000282/20214012021-04-21021 April 2021 Security Baseline Inspection Report 05000282/2021401 and 05000306/2021401; Independent Spent Storage Security Inspection Report 07200010/2021401 IR 05000282/20200062021-03-0404 March 2021 Annual Assessment Letter for the Prairie Island Nuclear Generating Plant (Report 05000282/2020006 and 05000306/2020006) IR 05000282/20200022021-02-16016 February 2021 Reissue - Prairie Island Nuclear Generating Plant - Integrated Inspection Report 05000282/2020002; 05000306/2020002; and 07200010/2020001 IR 05000282/20200042021-02-0404 February 2021 Integrated Inspection Report 05000282/2020004 and 05000306/2020004 ML20352A1562020-12-21021 December 2020 Review of the 2018 Steam Generator Tube Inspection Report IR 05000282/20204022020-11-12012 November 2020 Security Baseline Inspection Report 05000282/2020402 and 05000306/2020402 IR 05000282/20200032020-11-10010 November 2020 Integrated Inspection Report 05000282/2020003; 05000306/2020003; and 07200010/2020002 IR 05000282/20203012020-09-22022 September 2020 NRC Initial License Examination Report 05000282/2020301 and 05000306/2020301 IR 05000282/20200052020-09-0101 September 2020 Updated Inspection Plan for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2020005 and 05000306/2020005) 2024-02-01
[Table view] |
See also: IR 05000282/2009008
Text
May 6, 2009
EA-08-349
Mr. Michael D. Wadley
Site Vice President
Prairie Island Nuclear Generating Plant
Northern States Power Company-Minnesota
1717 Wakonade Drive East
Welch, MN 55089
SUBJECT: FINAL SIGNIFICANCE DETERMINATION OF WHITE FINDING AND NOTICE
OF VIOLATION; NRC INSPECTION REPORT NO. 05000282/2009008;
05000306/2009008; PRAIRIE ISLAND NUCLEAR GENERATING PLANT,
UNITS 1 AND 2
Dear Mr. Wadley:
This letter provides you the final significance determination of the preliminary Yellow finding
discussed in our previous communication dated February 10, 2009, which provided Inspection
Report Number 05000282/2008009; 05000306/2008009 (ML090410466). The finding involved
the shipment of a package containing radioactive material, via an exclusive-use open transport
vehicle. When the package arrived at its destination, the detected radiation levels exceeded
Nuclear Regulatory Commission (NRC) regulations, which invoke the Department of
Transportation requirements limiting the radiation level on the surface of a package shipped in an
open transport vehicle to 200 millirem per hour.
At your request, a Regulatory Conference was held on March 17, 2009, to further discuss your
views on this issue. During the conference, you and your staff described your assessment of
the significance of the finding, and the corrective actions taken to resolve it, including the root
cause evaluation of the finding. Specifically, your assessment of the significance of the finding
focused on the appropriateness of the different radiation detectors used to accurately
characterize the true dose rate for the source of the radiation. You presented information to
support your belief that an ion chamber detector was the appropriate instrument to be used, due
to the detectors slower response and its ability to accurately measure the true dose rate. You
also provided information to support your belief that a Geiger-Mueller detector would greatly
overestimate the actual dose rate. Therefore, you concluded that a White significance was the
appropriate outcome.
On March 26, 2009, your staff provided supplemental information in response to NRC
questions raised during the Regulatory Conference (ML090890369). After reviewing the
information developed during the inspection and provided during and after the conference, we
determined that both instruments provided valid measurements of the radiation levels near the
surface of the package. The differences in the instrument responses appeared to be primarily
due to the differences in detector geometries and response characteristics. While both
M. Wadley -2-
instruments provided measured radiation levels that exceeded the regulatory limit of
200 millirem per hour, the significance assessed using the public radiation safety Significance
Determination Process (SDP) resulted in different significance levels depending on the
instrument used.
The source of the radiation was from a discrete radioactive particle, which was a point source.
The NRC is aware that the biological effect of exposure to point sources of radiation is less than
that from an equivalent exposure to the whole body resulting from exposure to broader beams
of radiation. However, this risk insight is not fully factored into the current public radiation safety
cornerstone SDP, whose risk outcomes are based solely on the radiation level at the surface of
a package relative to the regulatory limits. In this particular case, the source of radiation, the
discrete radioactive particle, was located on the underside of the package in an area that was
not readily accessible to a member of the public during transport. Therefore, because of the
limited actual radiological risk to the public, the NRC determined that the application of
Inspection Manual Chapter 0609, Appendix M, Significance Determination Process Using
Qualitative Criteria, was more appropriate to evaluate the actual public radiation safety
significance of this finding.
The NRC used the results of the measurements obtained at the receipt of the package and the
relative risk from the point radiation source to develop the significance of the finding. As stated
above, both radiation detection instruments measured radiation levels that exceeded the
regulatory limit, which provides a level of protection to a member of the public that may come
into contact with the shipment. Although no exposures to the public resulted from the shipment,
the potential consequences could have been greater under less favorable circumstances. Any
shipment with radiation levels that exceed regulatory limits can be potentially significant, and in
this case the risk was more than minimal. Based on this assessment and after considering the
information developed during the inspection, the information you provided at the conference,
and the supplemental information, the NRC has concluded that the finding is appropriately
characterized as White, a finding with low to moderate increased importance to safety that may
require additional NRC inspections.
You have 30 calendar days from the date of this letter to appeal the staffs determination of
significance for the identified White finding. Such appeals will be considered to have merit only
if they meet the criteria given in the NRC Inspection Manual Chapter 0609, Attachment 2.
The NRC has determined that the failure to properly characterize, prepare, and ship a package
containing radioactive material and the failure to provide adequate training to workers who
were involved in the preparation of the package for transport are violations of 10 CFR 71.5,
which invokes 49 CFR 173.441(a) and 49 CFR 172.704, as cited in the enclosed Notice of
Violation (Notice). The circumstances surrounding the violations were described in detail in the
subject inspection report. In accordance with the NRC Enforcement Policy, the Notice is
considered escalated enforcement action because it is associated with a White finding.
The NRC has concluded that the information regarding the reason for the violations, the
corrective actions taken and planned to correct the violations and prevent recurrence, and
the date when full compliance was achieved were adequately addressed at the Regulatory
Conference and on the docket (ML090790543 and ML090700284). Therefore, you are not
required to respond to this letter unless the description therein does not accurately reflect your
corrective actions or your position.
M. Wadley -3-
As a result of our review of Prairie Island Units 1 and 2 performance, including this White
finding, we have assessed you to be in the Regulatory Response column of the NRCs
Action Matrix. Therefore, we plan to conduct a supplemental inspection using Inspection
Procedure 95001, Inspection for One or Two White Inputs in a Strategic Performance Area,
when your staff has notified us of your readiness for this inspection. This inspection procedure
is conducted to provide assurance that the root cause and contributing causes of risk significant
performance issues are understood, the extent of condition is identified, and the corrective
actions are sufficient to prevent recurrence.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter,
its enclosures, and your response, if you choose to provide one, will be made available
electronically for public inspection in the NRC Public Document Room or from the
NRCs document system (ADAMS), accessible from the NRC Web site at
http://www.nrc.gov/reading-rm/adams.html. To the extent possible, your response
should not include any personal privacy, proprietary, or safeguards information so that
it can be made available to the public without redaction.
Sincerely,
/RA/
Mark A. Satorius
Regional Administrator
Docket Nos. 50-282; 50-306
License Nos. DPR-42; DPR-60
Enclosure:
Notice of Violation
cc w/encl: D. Koehl, Chief Nuclear Officer
Regulatory Affairs Manager
P. Glass, Assistant General Counsel
Nuclear Asset Manager
J. Stine, State Liaison Officer, Minnesota Department of Health
Tribal Council, Prairie Island Indian Community
Administrator, Goodhue County Courthouse
Commissioner, Minnesota Department of Commerce
Manager, Environmental Protection Division
Office of the Attorney General of Minnesota
Emergency Preparedness Coordinator, Dakota
County Law Enforcement Center
M. Wadley -3-
As a result of our review of Prairie Island Units 1 and 2 performance, including this White finding, we have
assessed you to be in the Regulatory Response column of the NRCs Action Matrix. Therefore, we plan
to conduct a supplemental inspection using Inspection Procedure 95001, Inspection for One or Two
White Inputs in a Strategic Performance Area, when your staff has notified us of your readiness for this
inspection. This inspection procedure is conducted to provide assurance that the root cause and
contributing causes of risk significant performance issues are understood, the extent of condition is
identified, and the corrective actions are sufficient to prevent recurrence.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, its enclosures,
and your response, if you choose to provide one, will be made available electronically for public
inspection in the NRC Public Document Room or from the NRCs document system (ADAMS), accessible
from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html. To the extent possible, your
response should not include any personal privacy, proprietary, or safeguards information so that
it can be made available to the public without redaction.
Sincerely,
/RA/
Mark A. Satorius
Regional Administrator
Docket Nos. 50-282; 50-306
License Nos. DPR-42; DPR-60
Enclosure:
Notice of Violation
cc w/encl: D. Koehl, Chief Nuclear Officer
Regulatory Affairs Manager
P. Glass, Assistant General Counsel
Nuclear Asset Manager
J. Stine, State Liaison Officer, Minnesota Department of Health
Tribal Council, Prairie Island Indian Community
Administrator, Goodhue County Courthouse
Commissioner, Minnesota Department of Commerce
Manager, Environmental Protection Division
Office of the Attorney General of Minnesota
Emergency Preparedness Coordinator, Dakota
County Law Enforcement Center
DISTRIBUTION:
See next page
DOCUMENT NAME: G:\EICS\ENFORCEMENT\Enforcement Cases 2008\EA-08-349 Prairie Island
Transportation\EA-08-349 Draft Final Letter White and NOV.doc
- Publicly Available Non-Publicly Available Sensitive ; Non-Sensitive
OFFICE RIII RIII RIII RIII D: OE D: NRR RIII RIII
2
NAME Gryglak Lougheed Cassidy West Hilton for Pedersen Heck Satorius
1
for Orth Carpenter
DATE 05/04/09 05/01/09 05/04/09 05/04/09 04/30/09 04/30/09 05/05/09 05/05/09
OFFICIAL RECORD COPY
1 OE concurrence per N. Hilton received via e-mail from Gregory Bowman on April 30, 2009.
2 NRR concurrence per R. Pedersen received via e-mail from Gregory Bowman on April 30, 2009.
Letter to Mr. Michael D. Wadley from Mr. Mark A. Satorius dated May 6, 2009
SUBJECT: FINAL SIGNIFICANCE DETERMINATION OF WHITE FINDING AND NOTICE
OF VIOLATION; NRC INSPECTION REPORT NO. 05000282/2009008;
05000306/2009008; PRAIRIE ISLAND NUCLEAR GENERATING PLANT,
UNITS 1 AND 2
DISTRIBUTION:
ADAMS (PARS)
RidsSecyMailCenter Resource
OCADistribution
Bill Borchardt, EDO
Bruce Mallett, DEDR
Cynthia Carpenter, OE
Nick Hilton, OE
Gregory Bowman, OE
Mark Satorius, RIII
Catherine Marco, OGC
Marvin Itzkowitz, OGC
Eric Leeds, NRR
Bruce Boger, NRR
Daniel Holody, RI
Carolyn Evans, RII
Jared Heck, RIII
William Jones, RIV
MaryAnn Ashley, NRR
Karla Stoedter, RIII
Paul Zurawski, RIII
Eliot Brenner, OPA
Hubert Bell, OIG
Guy Caputo, OI
Mona Williams, OCFO
John Giessner, RIII
Scott Thomas, RIII
Martin J. Phalen, RIII
Mark W. Mitchell, RIII
Peter J. Lee, RIII
Viktoria Mitlyng, OPA RIII
Prema Chandrathil, OPA RIII
Allan Barker, RIII
Paul Pelke, RIII
Patricia Lougheed, RIII
Magdalena Gryglak, RIII
RidsNrrDirsIrib
OEMAIL Resource
OEWEB Resource
NOTICE OF VIOLATION
Northern States Power Company - Minnesota Docket Nos. 50-282; 50-306
Prairie Island Nuclear Generating Plant, Units 1 and 2 License Nos. DPR-42; DPR-60
EA-08-349
During an NRC inspection conducted on November 17, 2008 through January 21, 2009, two
violations of NRC requirements were identified. In accordance with the NRC Enforcement
Policy, the violations are listed below:
Title 10 CFR 71.5, Transportation of Licensed Material, requires licensees to comply
with the Department of Transportation (DOT) regulations in Title 49 CFR parts 170
through 189 relative to the transportation of licensed material. Specifically,
1) Title 49 CFR 173.441(a) requires that each package of radioactive material
offered for transportation must be designed and prepared for shipment, so that
under conditions normally incident to transportation, the radiation level does not
exceed 2 millisievert per hour (200 millirem per hour) at any point on the external
surface of the package.
Contrary to the above, on October 29, 2008, the licensee shipped a package
containing radioactive material that was not designed or prepared to assure that,
under conditions normally incident to transportation, the radiation level on the
external surface of the package would not exceed 200 mrem per hour.
2) Title 49 CFR 172.704, Training Requirements, requires that individuals involved
in the transport of hazardous materials receive function specific training relative
to their specific tasks, and that these individuals receive recurrent training at least
once every three years.
Contrary to the above, as of October 29, 2008, five people involved in preparing
a package for radioactive shipment and transport had not received the required
function-specific training.
These violations are associated with a White Significance Determination Process
finding.
The NRC has concluded that information regarding the reason for the violations, the corrective
actions taken and planned to correct the violations and prevent recurrence and the date
when full compliance was achieved was adequately addressed on the docket in Inspection
Report No. 05000282/2008009; 05000306/2008009, at the Regulatory Conference, and in
your letter dated March 26, 2009. However, you are required to submit a written statement or
explanation pursuant to 10 CFR 2.201 if the description therein does not accurately reflect
your corrective actions or your position. In that case, or if you choose to respond, clearly
mark your response as a "Reply to a Notice of Violation, EA-08-349", and send it to the
Notice of Violation -2-
U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-
0001 with a copy to the Regional Administrator, Region III, and a copy to the Prairie Island
Resident Inspectors, within 30 days of the date of the letter transmitting this Notice of
Violation (Notice).
If you contest this enforcement action, you should also provide a copy of your response, with
the basis for your denial, to the Director, Office of Enforcement, United States Nuclear
Regulatory Commission, Washington, DC 20555-0001.
If you choose to respond, your response will be made available electronically for public
inspection in the NRC Public Document Room or from the NRCs document system (ADAMS),
accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html. Therefore,
to the extent possible, the response should not include any personal privacy, proprietary, or
safeguards information so that it can be made available to the public without redaction.
In accordance with 10 CFR 19.11, you may be required to post this Notice within two working
days.
Dated this 6th day of May 2009