IR 05000373/2016005: Difference between revisions

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{{#Wiki_filter:ust 31, 2016
{{#Wiki_filter:UNITED STATES ust 31, 2016


==SUBJECT:==
==SUBJECT:==
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==Dear Mr. Hanson:==
==Dear Mr. Hanson:==
On August 10, 2016, the U.S. Nuclear Regulatory Commission (NRC) completed its mid-cycle performance review of LaSalle County Station, Units 1 and 2. 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 16. This letter informs you of the NRC's 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 LaSalle County Station, Units 1 and 2. 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, LaSalle County Station, 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 LaSalle County Station, Units 1 and 2 during the most recent quarter was within the Licensee Response Column of the NRC
The NRC determined that overall, LaSalle County Station, 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 LaSalle County Station, Units 1 and 2 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.
'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 facility. The enclosed inspection plan lists the inspections scheduled through June 30 , 201 8. 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.
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. The NRC plans to perform an infrequently performed inspection related to the operation of the Independent Spent Fuel Storage Installation (ISFSI) using IP 60855.1, Operation of an ISFSI Independent Spent Fuel Storage Installation at Operating Plants.


This inspection plan does not include security related inspections, which will be sent via separate, non-publicly available correspondence. The NRC plans to perform an infrequently performed inspection related to the operation of the Independent Spent Fuel Storage Installation (ISFSI) using IP 60855.1, "Operation of an ISFSI Independent Spent Fuel Storage Installation at Operating Plants."
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 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.
From July 1, 2015, to June 30, 2016, the NRC issued three Severity Level IV traditional enforcement violations associated with impeding the regulatory process. However, two of these violations had been the subject of a previous follow-up inspection using Inspection Procedure 92723, Follow-up Inspection for Three or More Severity Level IV Traditional Enforcement Violation in the Same Area in a 12-month Period with no significant issue identified. Therefore, the NRC does not plan to perform an inspection to follow-up on these violations at this time.


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/Mul ti-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).


From July 1, 20 15, to June 30, 2016, the NRC issued three Severity Level IV traditional enforcement violations associated with impeding the regulatory process. However, two of these violations had been the subject of a previous follow-up inspection using Inspection Procedure 92723, "Follow-up Inspection for Three or More Severity Level IV Traditional Enforcement Violation in the Same Area in a 12-month Period" with no significant issue identified. Therefore, the NRC does not plan to perform an inspection to follow-up on these violations at this time.
Please contact me at 630-829-9827 with any questions you have regarding this letter.
 
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 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 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 me at 630-829-9 827 with any questions you have regarding this letter.


Sincerely,
Sincerely,

Latest revision as of 14:42, 30 October 2019

Mid-Cycle Assessment Letter for LaSalle County Station Units 1 and 2 (Report 05000373/2016005; 05000374/2016005)
ML16242A374
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 08/31/2016
From: Billy Dickson
Division Reactor Projects III
To: Bryan Hanson
Exelon Generation Co
References
IR 2016005
Download: ML16242A374 (6)
v • d • e


Text

UNITED STATES ust 31, 2016

SUBJECT:

MID-CYCLE ASSESSMENT LETTER FOR LASALLE COUNTY STATION, UNITS 1 AND 2 (REPORT 05000373/2016005; 05000374/2016005)

Dear Mr. Hanson:

On August 10, 2016, the U.S. Nuclear Regulatory Commission (NRC) completed its mid-cycle performance review of LaSalle County Station, Units 1 and 2. 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, LaSalle County Station, 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 LaSalle County Station, Units 1 and 2 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 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. The NRC plans to perform an infrequently performed inspection related to the operation of the Independent Spent Fuel Storage Installation (ISFSI) using IP 60855.1, Operation of an ISFSI Independent Spent Fuel Storage Installation at Operating Plants.

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.

From July 1, 2015, to June 30, 2016, the NRC issued three Severity Level IV traditional enforcement violations associated with impeding the regulatory process. However, two of these violations had been the subject of a previous follow-up inspection using Inspection Procedure 92723, Follow-up Inspection for Three or More Severity Level IV Traditional Enforcement Violation in the Same Area in a 12-month Period with no significant issue identified. Therefore, the NRC does not plan to perform an inspection to follow-up on these violations at this time.

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 me at 630-829-9827 with any questions you have regarding this letter.

Sincerely,

/RA/

Billy Dickson, Chief Branch 5 Division of Reactor Projects Docket Nos. 50-373 and 50-374 License Nos. NPF-11 and NPF-18 Enclosure:

Inspection Plan cc: Distribution via LISTSERV

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