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=Text=
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{{#Wiki_filter:March 2, 2016
{{#Wiki_filter:UNITED STATES rch 2, 2016


==SUBJECT:==
==SUBJECT:==
ANNUAL ASSESSMENT LETTER FOR QUAD CITIES NUCLEAR POWER STATIONS, UNITS 1 AN D 2 (REPORT 05000 254/20 15006 AND 05000 265/20 15006)
ANNUAL ASSESSMENT LETTER FOR QUAD CITIES NUCLEAR POWER STATIONS, UNITS 1 AND 2 (REPORT 05000254/2015006 AND 05000265/2015006)


==Dear Mr. Hanson:==
==Dear Mr. Hanson:==
On February 10, 2016, the U.S. Nuclear Regulatory Commission (NRC) completed its end-of-cycle performance review of Quad Cities Nuclear Power Station, Units 1 and 2. The NRC reviewed the most recent quarterly performance indicators (PIs) in addition to inspection results and enforcement actions from January 1, 2015 , through December 31, 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.
On February 10, 2016, the U.S. Nuclear Regulatory Commission (NRC) completed its end-of-cycle performance review of Quad Cities Nuclear Power Station, Units 1 and 2. The NRC reviewed the most recent quarterly performance indicators (PIs) in addition to inspection results and enforcement actions from January 1, 2015, through December 31, 2015. 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, Quad Cities Nuclear Power 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 Quad Cities Nuclear Power Station, Units 1 and 2, during the most recent quarter was within the Licensee Response Column of the NRC
The NRC determined that overall, Quad Cities Nuclear Power 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 Quad Cities Nuclear Power 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)
'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.
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 December 31 , 20 17. Routine inspections performed by resident inspectors are not included in the inspection plan. The inspections listed during the last 9 months of the inspection plan are tentative and may be revised at the mid-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 December 31, 2017.


This inspection plan does not include security-related inspections, which will be sent via separate, non-publicly available correspondence.
Routine inspections performed by resident inspectors are not included in the inspection plan.


The NRC inspection schedule includes a biennial inspection conducted in accordance with Inspection Procedure 71152, "Problem Identification and Resolution
The inspections listed during the last 9 months of the inspection plan are tentative and may be revised at the mid-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.
;" a triennial inspection conducted in accordance with Inspection Procedure 71111.17T, "Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications;" and 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." This Order 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.
The NRC inspection schedule includes a biennial inspection conducted in accordance with Inspection Procedure 71152, Problem Identification and Resolution; a triennial inspection conducted in accordance with Inspection Procedure 71111.17T, Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications; and 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.


Additionally, the Commission issued Order EA-12-051, "Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation." This Order 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.
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. This Order 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. This Order 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 was completed for Quad Cities Nuclear Power Station, Units 1 and 2, and the information gathered will aid staff in development of the 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 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.


The NRC is conducting audits of licensee efforts towards compliance with these Orders.
In accordance with 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).
 
The audit was completed for Quad Cities Nuclear Power Station, Units 1 and 2, and the information gathered will aid staff in development of the 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 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 accordance with 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 630-829-9731 with any questions you have regarding this letter.
Please contact me at 630-829-9731 with any questions you have regarding this letter.


Sincerely,
Sincerely,
/RA/ Karla Stoedter, Chief Branch 1 Division of Reactor Projects Docket Nos.
/RA/
 
Karla Stoedter, Chief Branch 1 Division of Reactor Projects Docket Nos. 50-254, 50-265 License Nos. DPR-29, DPR-30 Enclosure:
50-254, 50-265 License Nos.
Inspection Plan cc: Distribution via LISTSERV
 
DPR-29, DPR-30 Enclosure:
Inspection Plan
 
cc: Distribution via LISTSERV
}}
}}

Latest revision as of 22:27, 30 October 2019

Annual Assessment Letter for Quad Cities Nuclear Power Stations, Units 1 and 2 (Inspection Report 05000254/2015006 and 05000265/2015006)
ML16060A342
Person / Time
Site: Quad Cities  Constellation icon.png
Issue date: 03/02/2016
From: Karla Stoedter
NRC/RGN-III/DRP/B1
To: Bryan Hanson
Exelon Generation Co, Exelon Nuclear
References
IR 2015006
Download: ML16060A342 (6)
v • d • e


Text

UNITED STATES rch 2, 2016

SUBJECT:

ANNUAL ASSESSMENT LETTER FOR QUAD CITIES NUCLEAR POWER STATIONS, UNITS 1 AND 2 (REPORT 05000254/2015006 AND 05000265/2015006)

Dear Mr. Hanson:

On February 10, 2016, the U.S. Nuclear Regulatory Commission (NRC) completed its end-of-cycle performance review of Quad Cities Nuclear Power Station, Units 1 and 2. The NRC reviewed the most recent quarterly performance indicators (PIs) in addition to inspection results and enforcement actions from January 1, 2015, through December 31, 2015. 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, Quad Cities Nuclear Power 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 Quad Cities Nuclear Power 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 December 31, 2017.

Routine inspections performed by resident inspectors are not included in the inspection plan.

The inspections listed during the last 9 months of the inspection plan are tentative and may be revised at the mid-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 inspection schedule includes a biennial inspection conducted in accordance with Inspection Procedure 71152, Problem Identification and Resolution; a triennial inspection conducted in accordance with Inspection Procedure 71111.17T, Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications; and 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. This Order 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. This Order 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 was completed for Quad Cities Nuclear Power Station, Units 1 and 2, and the information gathered will aid staff in development of the 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 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 accordance with 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 630-829-9731 with any questions you have regarding this letter.

Sincerely,

/RA/

Karla Stoedter, Chief Branch 1 Division of Reactor Projects Docket Nos. 50-254, 50-265 License Nos. DPR-29, DPR-30 Enclosure:

Inspection Plan cc: Distribution via LISTSERV

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