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=Text=
=Text=
{{#Wiki_filter:August 31, 2016
{{#Wiki_filter:gust 31, 2016


==SUBJECT:==
==SUBJECT:==
MID-CYCLE ASSESSMENT LETTER FOR PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 (REPORT 05000282/2016005; 05000306/2016005)
MID-CYCLE ASSESSMENT LETTER FOR PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 (REPORT 05000282/2016005; 05000306/2016005)


Dear Mr. Northard
==Dear Mr. Northard:==
:
On August 10, 2016, the U.S. Nuclear Regulatory Commission (NRC) completed its mid-cycle performance review of [official plant name and applicable units]. The NRC reviewed the most recent quarterly performance indicators (PIs) in addition to inspection results and enforcement actions from July 1, 2015 through June 30, 2016. This letter informs you of the NRCs assessment of your facility during this period and its plans for future inspections at your facility.
On August 10, 2016, the U.S. Nuclear Regulatory Commission (NRC) completed its mid-cycle performance review of [official plant name and applicable units]. The NRC reviewed the most recent quarterly performance indicators (PIs) in addition to inspection results and enforcement actions from July 1, 20 15 through June 30, 20 1 This letter informs you of the NRC's assessment of your facility during this period and its plans for future inspections at your facilit The NRC determined that overall, Prairie Island Plant Unit 1 operated in a manner that preserved public health and safety and met all cornerstone objective The NRC determined the performance at Prairie Island Plant Unit 1 during the most recent quarter was within the Licensee Response Column of the NRC
's Reactor Oversight Process (ROP) Action Matrix because all inspection findings had very low (i.e., green) safety significance, and all PIs indicated that your performance was within the nominal, expected range (i.e., green).


Therefore, the NRC plans to conduct ROP baseline inspections at your facilit The NRC determined the performance at Prairie Island Plant Unit 2 during the most recent quarter was within the Regulatory Response Column of the NRC
The NRC determined that overall, Prairie Island Plant Unit 1 operated in a manner that preserved public health and safety and met all cornerstone objectives. The NRC determined the performance at Prairie Island Plant Unit 1 during the most recent quarter was within the Licensee Response Column of the NRCs Reactor Oversight Process (ROP) Action Matrix because all inspection findings had very low (i.e., green) safety significance, and all PIs indicated that your performance was within the nominal, expected range (i.e., green).
's ROP Action Matrix because of one low-to-moderate (White) PI for Unplanned Scrams per 7000 critical hour Therefore, in addition to ROP baseline inspections, the NRC will conduct a supplemental inspection in accordance with Inspection Procedure 95001, "Supplemental Inspection for One or Two White Inputs in a Strategic Performance Area." On May 23, 2016, your staff notified the NRC of you r readiness for this supplemental inspection
. to review the actions taken to address the performance issue Therefore, the NRC plans to perform Inspection Procedure 95001 beginning on September 12, 2016
. This inspection procedure is conducted to provide assurance that the root cause and contributing cause of risk significant performance issues related to the Performance Indicator are understood, the extent of condition and the extent of cause are identified, and the corrective actions are sufficient to prevent recurrence
.
S. Northard-2- The enclosed inspection plan lists the inspections scheduled through June 30 , 201 Routine inspections performed by resident inspectors are not included in the inspection pla The inspections listed during the second half of the inspection plan are tentative and may be revised at the end-of-cycle performance revie The NRC provides the inspection plan to allow for the resolution of any scheduling conflicts and personnel availability issue The NRC will contact you as soon as possible to discuss changes to the inspection plan should circumstances warrant any change This inspection plan does not include security related inspections, which will be sent via separate, non-publicly available correspondenc In response to the accident at Fukushima, the Commission issued Order EA-12-049, "Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events
," and Order EA-12-051, "Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation." The NRC conducted audits of licensee efforts towards compliance with these Orders, and the information gathered will aid staff in development of the ultimate Safety Evaluation for the sit After the NRC staff receives the Final Compliance letter for the site, the Safety Evaluation will be issue Then, the NRC staff will confirm through inspections the full implementation of the orders mentioned above by performing Temporary Instruction 191, "Inspection of the Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communication/Staffing/Multi-Unit Dose Assessment Plans."


In Staff Requirements Memorandum
Therefore, the NRC plans to conduct ROP baseline inspections at your facility.
- SECY 16-0009, "Recommendations Resulting from the Integrated Prioritization and Re-Baselining of Agency Activities," the Commission approved the NRC staff recommendation to discontinue the formal mid-cycle assessment process beginning in calendar year 201 This will be the final mid-cycle assessment lette The staff will continue to conduct quarterly assessment meetings and communicate changes in the assessment of licensee performance in accordance with the guidance in Inspection Manual Chapter 0305, "Operating Reactor Assessment Program."


In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390 of the NRC
The NRC determined the performance at Prairie Island Plant Unit 2 during the most recent quarter was within the Regulatory Response Column of the NRCs ROP Action Matrix because of one low-to-moderate (White) PI for Unplanned Scrams per 7000 critical hours. Therefore, in addition to ROP baseline inspections, the NRC will conduct a supplemental inspection in accordance with Inspection Procedure 95001, Supplemental Inspection for One or Two White Inputs in a Strategic Performance Area. On May 23, 2016, your staff notified the NRC of your readiness for this supplemental inspection. to review the actions taken to address the performance issues. Therefore, the NRC plans to perform Inspection Procedure 95001 beginning on September 12, 2016. This inspection procedure is conducted to provide assurance that the root cause and contributing cause of risk significant performance issues related to the Performance Indicator are understood, the extent of condition and the extent of cause are identified, and the corrective actions are sufficient to prevent recurrence. The enclosed inspection plan lists the inspections scheduled through June 30, 2018. Routine inspections performed by resident inspectors are not included in the inspection plan. The inspections listed during the second half of the inspection plan are tentative and may be revised at the end-of-cycle performance review. The NRC provides the inspection plan to allow for the resolution of any scheduling conflicts and personnel availability issues. The NRC will contact you as soon as possible to discuss changes to the inspection plan should circumstances warrant any changes. This inspection plan does not include security related inspections, which will be sent via separate, non-publicly available correspondence.
's "Rules of Practice," a copy of this letter will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).


S. Northard-3- Please contact Kenneth Riemer at 630-829-9628 with any questions you have regarding this lette
In response to the accident at Fukushima, the Commission issued Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events, and Order EA-12-051, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation. The NRC conducted audits of licensee efforts towards compliance with these Orders, and the information gathered will aid staff in development of the ultimate Safety Evaluation for the site. After the NRC staff receives the Final Compliance letter for the site, the Safety Evaluation will be issued. Then, the NRC staff will confirm through inspections the full implementation of the orders mentioned above by performing Temporary Instruction 191, Inspection of the Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communication/Staffing/Multi-Unit Dose Assessment Plans.
 
In Staff Requirements Memorandum - SECY 16-0009, Recommendations Resulting from the Integrated Prioritization and Re-Baselining of Agency Activities, the Commission approved the NRC staff recommendation to discontinue the formal mid-cycle assessment process beginning in calendar year 2017. This will be the final mid-cycle assessment letter. The staff will continue to conduct quarterly assessment meetings and communicate changes in the assessment of licensee performance in accordance with the guidance in Inspection Manual Chapter 0305, Operating Reactor Assessment Program.
 
In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390 of the NRCs Rules of Practice, a copy of this letter will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). Please contact Kenneth Riemer at 630-829-9628 with any questions you have regarding this letter.


Sincerely,
Sincerely,
/RA/
/RA/
Patrick L. Louden, Director Division of Reactor Projects
Patrick L. Louden, Director Division of Reactor Projects Docket Nos. 50-282; 50-306 License Nos. DPR-42; DPR-60 Enclosure:
 
Docket No ; 50-306 License No DPR-42; DPR-60 Enclosure:
Inspection Plan cc: Distribution via LISTSERV
Inspection Plan cc: Distribution via LISTSERV
}}
}}

Latest revision as of 14:42, 30 October 2019

Mid-Cycle Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2016005; 05000306/2016005)
ML16242A382
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 08/31/2016
From: Louden P
Division Reactor Projects III
To: Northard S
Northern States Power Company, Minnesota
References
IR 2016005
Download: ML16242A382 (6)
v • d • e


Text

gust 31, 2016

SUBJECT:

MID-CYCLE ASSESSMENT LETTER FOR PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 (REPORT 05000282/2016005; 05000306/2016005)

Dear Mr. Northard:

On August 10, 2016, the U.S. Nuclear Regulatory Commission (NRC) completed its mid-cycle performance review of [official plant name and applicable units]. The NRC reviewed the most recent quarterly performance indicators (PIs) in addition to inspection results and enforcement actions from July 1, 2015 through June 30, 2016. This letter informs you of the NRCs assessment of your facility during this period and its plans for future inspections at your facility.

The NRC determined that overall, Prairie Island Plant Unit 1 operated in a manner that preserved public health and safety and met all cornerstone objectives. The NRC determined the performance at Prairie Island Plant Unit 1 during the most recent quarter was within the Licensee Response Column of the NRCs Reactor Oversight Process (ROP) Action Matrix because all inspection findings had very low (i.e., green) safety significance, and all PIs indicated that your performance was within the nominal, expected range (i.e., green).

Therefore, the NRC plans to conduct ROP baseline inspections at your facility.

The NRC determined the performance at Prairie Island Plant Unit 2 during the most recent quarter was within the Regulatory Response Column of the NRCs ROP Action Matrix because of one low-to-moderate (White) PI for Unplanned Scrams per 7000 critical hours. Therefore, in addition to ROP baseline inspections, the NRC will conduct a supplemental inspection in accordance with Inspection Procedure 95001, Supplemental Inspection for One or Two White Inputs in a Strategic Performance Area. On May 23, 2016, your staff notified the NRC of your readiness for this supplemental inspection. to review the actions taken to address the performance issues. Therefore, the NRC plans to perform Inspection Procedure 95001 beginning on September 12, 2016. This inspection procedure is conducted to provide assurance that the root cause and contributing cause of risk significant performance issues related to the Performance Indicator are understood, the extent of condition and the extent of cause are identified, and the corrective actions are sufficient to prevent recurrence. The enclosed inspection plan lists the inspections scheduled through June 30, 2018. Routine inspections performed by resident inspectors are not included in the inspection plan. The inspections listed during the second half of the inspection plan are tentative and may be revised at the end-of-cycle performance review. The NRC provides the inspection plan to allow for the resolution of any scheduling conflicts and personnel availability issues. The NRC will contact you as soon as possible to discuss changes to the inspection plan should circumstances warrant any changes. This inspection plan does not include security related inspections, which will be sent via separate, non-publicly available correspondence.

In response to the accident at Fukushima, the Commission issued Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events, and Order EA-12-051, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation. The NRC conducted audits of licensee efforts towards compliance with these Orders, and the information gathered will aid staff in development of the ultimate Safety Evaluation for the site. After the NRC staff receives the Final Compliance letter for the site, the Safety Evaluation will be issued. Then, the NRC staff will confirm through inspections the full implementation of the orders mentioned above by performing Temporary Instruction 191, Inspection of the Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communication/Staffing/Multi-Unit Dose Assessment Plans.

In Staff Requirements Memorandum - SECY 16-0009, Recommendations Resulting from the Integrated Prioritization and Re-Baselining of Agency Activities, the Commission approved the NRC staff recommendation to discontinue the formal mid-cycle assessment process beginning in calendar year 2017. This will be the final mid-cycle assessment letter. The staff will continue to conduct quarterly assessment meetings and communicate changes in the assessment of licensee performance in accordance with the guidance in Inspection Manual Chapter 0305, Operating Reactor Assessment Program.

In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390 of the NRCs Rules of Practice, a copy of this letter will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). Please contact Kenneth Riemer at 630-829-9628 with any questions you have regarding this letter.

Sincerely,

/RA/

Patrick L. Louden, Director Division of Reactor Projects Docket Nos. 50-282; 50-306 License Nos. DPR-42; DPR-60 Enclosure:

Inspection Plan cc: Distribution via LISTSERV

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