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| | issue date = 03/04/2014 | | | issue date = 03/04/2014 |
| | title = Annual Assessment Letter for Byron Station, Units 1 and 2 (Report 05000454/2013001; 05000455/2013001) | | | title = Annual Assessment Letter for Byron Station, Units 1 and 2 (Report 05000454/2013001; 05000455/2013001) |
| | author name = Duncan E R | | | author name = Duncan E |
| | author affiliation = NRC/RGN-III/DRP/B3 | | | author affiliation = NRC/RGN-III/DRP/B3 |
| | addressee name = Pacilio M J | | | addressee name = Pacilio M |
| | addressee affiliation = Exelon Generation Co, LLC, Exelon Nuclear | | | addressee affiliation = Exelon Generation Co, LLC, Exelon Nuclear |
| | docket = 05000454, 05000455 | | | docket = 05000454, 05000455 |
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| =Text= | | =Text= |
| {{#Wiki_filter: | | {{#Wiki_filter:UNITED STATES rch 4, 2014 |
| [[Issue date::March 4, 2014]]
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| Mr. Michael Senior Vice President, Exelon Generation Co., LLC President and Chief Nuclear Officer, Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
| | ==SUBJECT:== |
| | ANNUAL ASSESSMENT LETTER FOR BYRON STATION, UNITS 1 AND 2 (REPORT 05000454/2013001; 05000455/2013001) |
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| SUBJECT: ANNUAL ASSESSMENT LETTER FOR BYRON STATION, UNITS 1 AND 2 (REPORT 05000454/2013001; 05000455/2013001)
| | ==Dear Mr. Pacilio:== |
| | On February 12, 2014, the U.S. Nuclear Regulatory Commission (NRC) completed its end-of-cycle performance review of Byron 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, 2013, through December 31, 2013. This letter informs you of the NRCs assessment of your facility during this period and its plans for future inspections at your facility. |
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| | The NRC determined that overall, Byron 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 Byron 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). |
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| | Therefore, the NRC plans to conduct ROP baseline inspections at your facility. |
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| | As a result of the Safety Culture Common Language Initiative, the terminology and coding of cross-cutting aspects were revised. All cross-cutting aspects identified during inspections conducted in Calendar Year (CY) 2014 will reflect this revision to Inspection Manual Chapter (IMC) 0310. The CY 2013 end-of-cycle assessments were conducted using the IMC 0310 guidance in effect in CY 2013 (dated October 28, 2011). Cross-cutting aspects identified in 2013 using the 2013 terminology will be converted to the latest revision in accordance with the cross-reference in IMC 0310 during the mid-cycle assessment review and evaluated for cross-cutting themes and potential substantive cross-cutting issues in accordance with IMC 0305. |
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| ==Dear Mr. Pacilio:==
| | The enclosed inspection plan lists the inspections scheduled through June 30, 2015. Routine inspections performed by resident inspectors are not included in the inspection plan. The inspections listed during the last nine 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. Additionally, an NRC audit of licensee efforts towards compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events is ongoing. This audit includes an onsite component in order for the NRC to evaluate mitigating strategies as described in licensee submittals, and to receive and review information relative to associated open items. This onsite activity will occur in the months prior to a declaration of compliance for the first unit at each site, and will aid staff in development of an ultimate Safety Evaluation for the site. The onsite component has been scheduled for the week of August 18, 2014. A site-specific audit plan for the visit will be provided in advance to allow sufficient time for preparations. |
| On February 12, 2014, the U.S. Nuclear Regulatory Commission (NRC) completed its end-of-cycle performance review of Byron 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, 2013, through December 31, 2013. 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, Byron 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 Byron Station, 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 at your facility. As a result of the Safety Culture Common Language Initiative, the terminology and coding of cross-cutting aspects were revised. All cross-cutting aspects identified during inspections conducted in Calendar Year (CY) 2014 will reflect this revision to Inspection Manual Chapter (IMC) 0310. The CY 2013 end-of-cycle assessments were conducted using the IMC 0310 guidance in effect in CY 2013 (dated October 28, 2011). Cross-cutting aspects identified in 2013 using the 2013 terminology will be converted to the latest revision in accordance with the cross-reference in IMC 0310 during the mid-cycle assessment review and evaluated for cross-cutting themes and potential substantive cross-cutting issues in accordance with IMC 0305.
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| | The NRC also plans to conduct infrequently performed inspections related to Inspection Procedure (IP) 60855.1, Operation of an Independent Spent Fuel Storage Installation at Operating Plants, and IP 92709, Licensee Strike Contingency Plans, if needed due to expiring contracts. |
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| The enclosed inspection plan lists the inspections scheduled through June 30, 2015. Routine inspections performed by resident inspectors are not included in the inspection plan. The inspections listed during the last nine 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. Additionally, an NRC audit of licensee efforts towards compliance with Order EA-12-049, "Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events" is ongoing. This audit includes an onsite component in order for the NRC to evaluate mitigating strategies as described in licensee submittals, and to receive and review information relative to associated open items. This onsite activity will occur in the months prior to a declaration of compliance for the first unit at each site, and will aid staff in development of an ultimate Safety Evaluation for the site. The onsite component has been scheduled for the week of August 18, 2014. A site-specific audit plan for the visit will be provided in advance to allow sufficient time for preparations. The NRC also plans to conduct infrequently performed inspections related to Inspection Procedure (IP) 60855.1, "Operation of an Independent Spent Fuel Storage Installation at Operating Plants," and IP 92709, "Licensee Strike Contingency Plans," if needed due to expiring contracts. In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records System (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). Please contact me at 630-829-9620 with any questions you have regarding this letter.
| | In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records System (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). |
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| Sincerely,/RA/ Eric R. Duncan, Chief Branch 3 Division of Reactor Projects Docket Nos. 50-454; 50-455 License Nos. NPF-37; NPF-66
| | Please contact me at 630-829-9620 with any questions you have regarding this letter. |
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| ===Enclosure:===
| | Sincerely, |
| | /RA/ |
| | Eric R. Duncan, Chief Branch 3 Division of Reactor Projects Docket Nos. 50-454; 50-455 License Nos. NPF-37; NPF-66 Enclosure: |
| Byron Station, Units 1 and 2 Inspection/Activity Plan cc w/encl: Distribution via ListServTM | | Byron Station, Units 1 and 2 Inspection/Activity Plan cc w/encl: Distribution via ListServTM |
| }} | | }} |
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[Table view] |
Inspection Report - Byron - 2013001 |
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Text
UNITED STATES rch 4, 2014
SUBJECT:
ANNUAL ASSESSMENT LETTER FOR BYRON STATION, UNITS 1 AND 2 (REPORT 05000454/2013001; 05000455/2013001)
Dear Mr. Pacilio:
On February 12, 2014, the U.S. Nuclear Regulatory Commission (NRC) completed its end-of-cycle performance review of Byron 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, 2013, through December 31, 2013. 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, Byron 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 Byron 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.
As a result of the Safety Culture Common Language Initiative, the terminology and coding of cross-cutting aspects were revised. All cross-cutting aspects identified during inspections conducted in Calendar Year (CY) 2014 will reflect this revision to Inspection Manual Chapter (IMC) 0310. The CY 2013 end-of-cycle assessments were conducted using the IMC 0310 guidance in effect in CY 2013 (dated October 28, 2011). Cross-cutting aspects identified in 2013 using the 2013 terminology will be converted to the latest revision in accordance with the cross-reference in IMC 0310 during the mid-cycle assessment review and evaluated for cross-cutting themes and potential substantive cross-cutting issues in accordance with IMC 0305.
The enclosed inspection plan lists the inspections scheduled through June 30, 2015. Routine inspections performed by resident inspectors are not included in the inspection plan. The inspections listed during the last nine 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. Additionally, an NRC audit of licensee efforts towards compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events is ongoing. This audit includes an onsite component in order for the NRC to evaluate mitigating strategies as described in licensee submittals, and to receive and review information relative to associated open items. This onsite activity will occur in the months prior to a declaration of compliance for the first unit at each site, and will aid staff in development of an ultimate Safety Evaluation for the site. The onsite component has been scheduled for the week of August 18, 2014. A site-specific audit plan for the visit will be provided in advance to allow sufficient time for preparations.
The NRC also plans to conduct infrequently performed inspections related to Inspection Procedure (IP) 60855.1, Operation of an Independent Spent Fuel Storage Installation at Operating Plants, and IP 92709, Licensee Strike Contingency Plans, if needed due to expiring contracts.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records System (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Please contact me at 630-829-9620 with any questions you have regarding this letter.
Sincerely,
/RA/
Eric R. Duncan, Chief Branch 3 Division of Reactor Projects Docket Nos. 50-454; 50-455 License Nos. NPF-37; NPF-66 Enclosure:
Byron Station, Units 1 and 2 Inspection/Activity Plan cc w/encl: Distribution via ListServTM