IR 05000282/2015005: Difference between revisions
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| issue date = 09/01/2015 | | issue date = 09/01/2015 | ||
| title = Mid-Cycle Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2015005; 05000306/2015005) | | title = Mid-Cycle Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2015005; 05000306/2015005) | ||
| author name = Riemer K | | author name = Riemer K | ||
| author affiliation = NRC/RGN-III/DRP/B2 | | author affiliation = NRC/RGN-III/DRP/B2 | ||
| addressee name = Davison K | | addressee name = Davison K | ||
| Line 18: | Line 18: | ||
=Text= | =Text= | ||
{{#Wiki_filter: | {{#Wiki_filter:September 1, 2015 | ||
==SUBJECT:== | |||
MID-CYCLE ASSESSMENT LETTER FOR PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 (REPORT 05000282/2015005; 05000306/2015005) | |||
==Dear Mr. Davison:== | ==Dear Mr. Davison:== | ||
On August 1 3, 2015, the U.S. Nuclear Regulatory Commission (NRC) completed its mid | On August 1 3, 2015, the U.S. Nuclear Regulatory Commission (NRC) completed its mid-cycle performance review of Prairie Island Nuclear Generating Plant. The NRC reviewed the most recent quarterly performance indicators (PIs) in addition to inspection results and enforcement actions from July 1, 2014 through June 30, 2015. This letter informs you of the NRC's assessment of your facility during this period and its plans for future inspections at your facility. The NRC determined that overall, Prairie Island Units 1 and 2 operated in a manner that preserved public health and safety and met all cornerstone objectives. The NRC determined the performance at Prairie Island Units 1 and 2 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 for both units at your facility. | ||
-cycle performance review of Prairie Island Nuclear Generating Plant. The NRC reviewed the most recent quarterly performance indicators (PIs) in addition to inspection results and enforcement actions from July 1, 2014 through June 30, 2015. This letter informs you of the NRC's assessment of your facility during this period and its plans for future inspections at your facility. The NRC determined that overall, Prairie Island Units 1 and 2 operated in a manner that preserved public health and safety and met all cornerstone objectives. The NRC determined the performance at Prairie Island Units 1 and 2 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 for both units at your facility. | |||
In the mid | In the mid-cycle assessment letter dated September 2, 2014 (ML14245A201), the NRC opened a substantive cross-cutting issue (S CCI 1) associated with the aspect of Documentation (H.7). This assessment letter stated that the SCCI would remain open until the number of findings with a cross-cutting aspect of H.7 is reduced, the corrective actions taken to mitigate the cross-cutting theme prove effective, and sustained performance improvement is observed in the human performance area. To address the SCCI, your staff performed a root cause evaluation and developed corrective actions. Since the last assessment period, the associated corrective actions have been completed and there have been no findings associated with the H.7 cross-cutting aspect over the last four quarters. Therefore, the SCCI will be closed. The enclosed inspection plan lists the inspections scheduled through June 30 , 2017. Routine inspections performed by resident inspectors are not included in the inspection plan. | ||
-cycle assessment letter dated September 2, 2014 (ML14245A201), the NRC opened a substantive cross | |||
-cutting issue (S CCI 1) associated with the aspect of Documentation (H.7). This assessment letter stated that the SCCI would remain open until the number of findings with a cross-cutting aspect of H.7 is reduced, the corrective actions taken to mitigate the cross-cutting theme prove effective, and sustained performance improvement is observed in the human performance area. To address the SCCI, your staff performed a root cause evaluation and developed corrective actions. Since the last assessment period, the associated corrective actions have been completed and there have been no findings associated with the H.7 cross-cutting aspect over the last four quarters. Therefore, the SCCI will be closed. The enclosed inspection plan lists the inspections scheduled through June 30 , 2017. 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 1 The term "substantial cross | The inspections listed during the second half of the inspection plan are tentative and may be revised 1 The term "substantial cross-cutting issue" was changed to "cross cutting issue (CCI)" in the most recent revision to Inspection Manual Chapter 0305, "Operating Reactor Assessment Program." 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. | ||
-cutting issue" was changed to "cross cutting issue (CCI)" in the most recent revision to Inspection Manual Chapter 0305, "Operating Reactor Assessment Program." 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 | This inspection plan does not include security related inspections, which will be sent via separate, non-publicly available correspondence. | ||
-publicly available correspondence. | |||
As discussed during a previous conversation between us, the NRC and Prairie Island will meet publicly to discuss the station's efforts associated with improving the corrective action program. | As discussed during a previous conversation between us, the NRC and Prairie Island will meet publicly to discuss the station's efforts associated with improving the corrective action program. | ||
| Line 44: | Line 38: | ||
The NRC also plans to conduct Inspection Procedure 71111.05XT "Fire Protection - NFPA 805 (Triennial)" at your facility. | The NRC also plans to conduct Inspection Procedure 71111.05XT "Fire Protection - NFPA 805 (Triennial)" at your facility. | ||
In response to the accident at Fukushima, the Commission issued Order EA | 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," which requires licensees to develop, implement, and maintain guidance and strategies to maintain or restore core cooling, containment, and spent fuel pool cooling capabilities following a beyond-design-basis external event. Additionally, the Commission issued Order EA-12-051, "Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation," which requires licensees to have a reliable means of remotely monitoring wide-range Spent Fuel Pool levels to support effective prioritization of event mitigation and recovery actions in the event of a beyond-design-basis external event. The NRC is conducting audits of licensee efforts towards compliance with these Orders. The audit has been completed for the first unit at Prairie Island, 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 Final Safety Evaluation will be issued. Then, the NRC staff will confirm through inspections the full implementation of the orders mentioned above 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 accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390 of the NRC | ||
-12-049, "Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events," which requires licensees to develop, implement, and maintain guidance and strategies to maintain or restore core cooling, containment, and spent fuel pool cooling capabilities following a beyond | '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 Agencywide Documents Access and Management 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 me at 630-829-9628 with any questions you have regarding this letter. | ||
-design-basis external event. Additionally, the Commission issued Order EA-12-051, "Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation," which requires licensees to have a reliable means of remotely monitoring wide | |||
-range Spent Fuel Pool levels to support effective prioritization of event mitigation and recovery actions in the event of a beyond | |||
-design-basis external event. The NRC is conducting audits of licensee efforts towards compliance with these Orders. The audit has been completed for the first unit at Prairie Island, 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 Final Safety Evaluation will be issued. Then, the NRC staff will confirm through inspections the full implementation of the orders mentioned above 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 accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390 of the NRC | |||
'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 Agencywide Documents Access and Management 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 me at 630-829-9628 with any questions you have regarding this letter. | |||
Sincerely, | Sincerely, | ||
/RA/ Kenneth Riemer, Chief Branch 2 Division of Reactor Projects Docket Nos. 50 | /RA/ Kenneth Riemer, Chief Branch 2 Division of Reactor Projects Docket Nos. 50-282; 50-306 License Nos. DPR-42; DPR-60 Enclosure: | ||
-282; 50-306 License Nos. DPR | |||
-42; DPR-60 Enclosure: | |||
Prarie Island Nuclear Generating Plant | Prarie Island Nuclear Generating Plant | ||
Inspection Plan cc w/encl: Distribution via LIST SERV | Inspection Plan cc w/encl: Distribution via LIST SERV | ||
}} | }} | ||
Revision as of 18:18, 20 June 2019
| ML15239B433 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 09/01/2015 |
| From: | Kenneth Riemer NRC/RGN-III/DRP/B2 |
| To: | Davison K Northern States Power Co |
| References | |
| IR 2015005 | |
| Download: ML15239B433 (6) | |
Text
September 1, 2015
SUBJECT:
MID-CYCLE ASSESSMENT LETTER FOR PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 (REPORT 05000282/2015005; 05000306/2015005)
Dear Mr. Davison:
On August 1 3, 2015, the U.S. Nuclear Regulatory Commission (NRC) completed its mid-cycle performance review of Prairie Island Nuclear Generating Plant. The NRC reviewed the most recent quarterly performance indicators (PIs) in addition to inspection results and enforcement actions from July 1, 2014 through June 30, 2015. This letter informs you of the NRC's assessment of your facility during this period and its plans for future inspections at your facility. The NRC determined that overall, Prairie Island Units 1 and 2 operated in a manner that preserved public health and safety and met all cornerstone objectives. The NRC determined the performance at Prairie Island Units 1 and 2 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 for both units at your facility.
In the mid-cycle assessment letter dated September 2, 2014 (ML14245A201), the NRC opened a substantive cross-cutting issue (S CCI 1) associated with the aspect of Documentation (H.7). This assessment letter stated that the SCCI would remain open until the number of findings with a cross-cutting aspect of H.7 is reduced, the corrective actions taken to mitigate the cross-cutting theme prove effective, and sustained performance improvement is observed in the human performance area. To address the SCCI, your staff performed a root cause evaluation and developed corrective actions. Since the last assessment period, the associated corrective actions have been completed and there have been no findings associated with the H.7 cross-cutting aspect over the last four quarters. Therefore, the SCCI will be closed. The enclosed inspection plan lists the inspections scheduled through June 30 , 2017. 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 1 The term "substantial cross-cutting issue" was changed to "cross cutting issue (CCI)" in the most recent revision to Inspection Manual Chapter 0305, "Operating Reactor Assessment Program." 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.
As discussed during a previous conversation between us, the NRC and Prairie Island will meet publicly to discuss the station's efforts associated with improving the corrective action program.
Specific details associated with th is meeting will be issued in a separate correspondence.
The NRC also plans to conduct Inspection Procedure 71111.05XT "Fire Protection - NFPA 805 (Triennial)" at your facility.
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," which requires licensees to develop, implement, and maintain guidance and strategies to maintain or restore core cooling, containment, and spent fuel pool cooling capabilities following a beyond-design-basis external event. Additionally, the Commission issued Order EA-12-051, "Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation," which requires licensees to have a reliable means of remotely monitoring wide-range Spent Fuel Pool levels to support effective prioritization of event mitigation and recovery actions in the event of a beyond-design-basis external event. The NRC is conducting audits of licensee efforts towards compliance with these Orders. The audit has been completed for the first unit at Prairie Island, 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 Final Safety Evaluation will be issued. Then, the NRC staff will confirm through inspections the full implementation of the orders mentioned above 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 accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390 of the NRC
'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 Agencywide Documents Access and Management 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 me at 630-829-9628 with any questions you have regarding this letter.
Sincerely,
/RA/ Kenneth Riemer, Chief Branch 2 Division of Reactor Projects Docket Nos. 50-282; 50-306 License Nos. DPR-42; DPR-60 Enclosure:
Prarie Island Nuclear Generating Plant
Inspection Plan cc w/encl: Distribution via LIST SERV