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| issue date = 09/02/2014
| issue date = 09/02/2014
| title = Mid-Cycle Assessment Letter and Inspection Plan 2014 (ROP-15) - James A. FitzPatrick Nuclear Power Plant (Report 05000333/2014006)
| title = Mid-Cycle Assessment Letter and Inspection Plan 2014 (ROP-15) - James A. FitzPatrick Nuclear Power Plant (Report 05000333/2014006)
| author name = Nieh H K
| author name = Nieh H
| author affiliation = NRC/RGN-I/DRP
| author affiliation = NRC/RGN-I/DRP
| addressee name = Coyle L
| addressee name = Coyle L
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| docket = 05000333
| docket = 05000333
| license number = DPR-059
| license number = DPR-059
| contact person = Burritt A L
| contact person = Burritt A
| document report number = IR-2014-006
| document report number = IR-2014-006
| document type = Inspection Plan, Letter
| document type = Inspection Plan, Letter
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=Text=
=Text=
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 2100 RENAISSANCE BLVD., SUITE 100 KING OF PRUSSIA, PA 19406-2713 September 2, 2014  
{{#Wiki_filter:mber 2, 2014


Mr. Lawrence Coyle Site Vice President Entergy Nuclear Northeast James A. FitzPatrick Nuclear Power Plant P. O. Box 110
==SUBJECT:==
 
MID-CYCLE ASSESSMENT LETTER FOR JAMES A. FITZPATRICK NUCLEAR POWER PLANT (REPORT 05000333/2014006)
Lycoming, NY 13093
 
SUBJECT: MID-CYCLE ASSESSMENT LETTER FOR JAMES A. FITZPATRICK NUCLEAR POWER PLANT (REPORT 05000333/2014006)


==Dear Mr. Coyle:==
==Dear Mr. Coyle:==
On August 13, 2014, the U.S. Nuclear Regulatory Commission (NRC) completed its mid-cycle performance review of James A. FitzPatrick Nuclear Power Plant (FitzPatrick). The NRC reviewed the most recent quarterly performance indicators in addition to inspection results and enforcement actions from July 1, 2013 through June 30, 2014. This letter informs you of the  
On August 13, 2014, the U.S. Nuclear Regulatory Commission (NRC) completed its mid-cycle performance review of James A. FitzPatrick Nuclear Power Plant (FitzPatrick). The NRC reviewed the most recent quarterly performance indicators in addition to inspection results and enforcement actions from July 1, 2013 through June 30, 2014. This letter informs you of the NRCs assessment of your facility during this period and its plans for future inspections at your facility.


NRC's assessment of your facility during this period and its plans for future inspections at your facility.
The NRC determined that overall, FitzPatrick was operated in a manner that preserved public health and safety and met all cornerstone objectives. The NRC determined the performance at FitzPatrick during the most recent quarter was within the Regulatory Response Column of the NRCs Reactor Oversight Process (ROP) Action Matrix, because all inspection findings had very low safety significance (Green) and one performance indicator was of low to moderate safety significance (White) in the Initiating Events cornerstone. Specifically, the Unplanned Power Changes per 7,000 Critical Hours performance indicator exceeded the Green/White threshold value in the fourth quarter of 2012. From January 20 through 24, 2014, NRC inspectors conducted the onsite portion of a supplemental inspection for the White performance indicator in accordance with Inspection Procedure (IP) 95001, "Supplemental Inspection for One or Two White Inputs in a Strategic Performance Area." The NRC inspectors concluded that the corrective actions taken by FitzPatrick to preclude repetition of the unplanned power changes were not sufficient to meet the inspection objectives. As a result, the inspection was not closed and remains open until additional corrective actions, including the replacement of the condenser tubes during the current refueling outage, have been completed. The NRC will review Entergys implementation of these additional corrective actions during a future inspection. The performance indicator will continue to be a White ROP Action Matrix input until the performance indicator results allow it to transition below the Green/White threshold. The NRC will notify you via separate correspondence when the plant will transition to the Licensee Response Column.
 
The NRC determined that overall, FitzPatrick was operated in a manner that preserved public health and safety and met all cornerstone objectives. The NRC determined the performance at FitzPatrick during the most recent quarter was within the Regulatory Response Column of the NRC's Reactor Oversight Process (ROP) Action Matrix, because all inspec tion findings had very low safety significance (Green) and one performance indicator was of low to moderate safety significance (White) in the Initiating Events cornerstone. Specifically, the "Unplanned Power Changes per 7,000 Critical Hours" performance indicator exceeded the Green/White threshold value in the fourth quarter of 2012. From January 20 through 24, 2014, NRC inspectors conducted the onsite portion of a supplemental inspection for the White performance indicator in accordance with Inspection Procedure (IP) 95001, "Supplemental Inspection for One or Two White Inputs in a Strategic Performance Area." The NRC inspectors concluded that the corrective actions taken by FitzPatrick to preclude repetition of the unplanned power changes were not sufficient to meet the inspection objectives. As a result, the inspection was not closed and remains open until additional corrective actions, including the replacement of the condenser tubes during the current refueling outage, have been completed. The NRC will review Entergy's implementation of these additional corrective actions during a future inspection. The performance indicator will continue to be a White ROP Action Matrix input until the performance indicator results allow it to transition below the Green/White threshold. The NRC will notify you via separate correspondence when the plant will transition to the Licensee Response Column.


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 2014 reflect this revision to Inspection Manual Chapter (IMC) 0310. Cross-cutting aspects identified in 2013 using the 2013 terminology were 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.
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 2014 reflect this revision to Inspection Manual Chapter (IMC) 0310. Cross-cutting aspects identified in 2013 using the 2013 terminology were 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.
Line 37: Line 32:
The enclosed inspection plan lists the inspections scheduled through December 31, 2015.
The enclosed inspection plan lists the inspections scheduled through December 31, 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 end-of-cycle performance review. In addition to baseline inspections, the NRC will perform IP 71003, "Post-Approval Site Inspection for License Renewal," and IP 60855, "Operation of an Independent Spent Fuel Storage Installation (ISFSI)." 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 possi ble 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.
Routine inspections performed by resident inspectors are not included in the inspection plan.


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-des ign-basis external event. The NRC is conducting audits of licensee efforts towards compliance with these Orders. This audit includes an onsite component in order for the NRC to evaluate licensee plans for complying with the Orders, as described in site-specific 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 date for the onsite component at your site is being coordinated with your staff.
The inspections listed during the last nine months of the inspection plan are tentative and may be revised at the end-of-cycle performance review. In addition to baseline inspections, the NRC will perform IP 71003, Post-Approval Site Inspection for License Renewal, and IP 60855, Operation of an Independent Spent Fuel Storage Installation (ISFSI). 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 site-specific audit plan for the visit will be provided in advance to allow sufficient time for  
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. This audit includes an onsite component in order for the NRC to evaluate licensee plans for complying with the Orders, as described in site-specific 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 date for the onsite component at your site is being coordinated with your staff.


preparations.
A site-specific audit plan for the visit will be provided in advance to allow sufficient time for preparations.


In accordance with Title 10 of the Code of Federal Regulations (10 CFR) Part 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 component of the NRC's Agencywide Document Access and Management System (ADAMS). ADAMS is accessible from the NRC website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
In accordance with Title 10 of the Code of Federal Regulations (10 CFR) Part 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 component of the NRC's Agencywide Document Access and Management System (ADAMS).
 
ADAMS is accessible from the NRC website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).


Please contact Arthur Burritt at (610)337-5069 with any questions you have regarding this letter.
Please contact Arthur Burritt at (610)337-5069 with any questions you have regarding this letter.


Sincerely,
Sincerely,
/RA/ Ho K. Nieh Director Division of Reactor Projects  
/RA/
 
Ho K. Nieh Director Division of Reactor Projects Docket No. 50-333 License No. DPR-59 Enclosure: Inspection Plan cc w/encl: Distribution via ListServ
Docket No. 50-333 License No. DPR-59  


Enclosure: Inspection Plan
ML14241A040 Non-Sensitive  Publicly Available SUNSI Review Sensitive  Non-Publicly Available OFFICE RI/DRP  RI/DRP  RI/DRP NAME  TSetzer/TCS ABurritt/ALB HNieh/HKN DATE  08/20/14 08/25/14  08/28/14


cc w/encl: Distribution via ListServ
Page 1 of 2      FitzPatrick 08/19/2014 10:32:08    Inspection / Activity Plan Report 22 07/01/2014 - 12/31/2015 Unit Planned Dates        No. of Staff Number Start End Inspection Activity    Title  on Site 9/22EXAM - INITIAL OL EXAM (2)      4 1 08/18/2014 08/22/2014 U01888 FY14-FITZPATRICK INITIAL OPERATOR LICENSING EXAM (2ND)
1 09/22/2014 10/02/2014 U01888 FY14-FITZPATRICK INITIAL OPERATOR LICENSING EXAM (2ND)
EP PROG - EP PROGRAM INSPECTION      1 1 07/07/2014 07/11/2014 IP 7111402 Alert and Notification System Testing 1 07/07/2014 07/11/2014 IP 7111403 Emergency Preparedness Organization Staffing and Augmentation System 1 07/07/2014 07/11/2014 IP 7111405 Correction of Emergency Preparedness Weaknesses and Deficiencies 71124 - RADIATION SAFETY INSPECTION    1 1 07/14/2014 07/18/2014 IP 71124.05 Radiation Monitoring Instrumentation 71003 - LR COMMITMENTS INSP PHASE 2    3 1 08/11/2014 08/15/2014 IP 71003  Post-Approval Site Inspection for License Renewal 1 08/25/2014 08/29/2014 IP 71003  Post-Approval Site Inspection for License Renewal 7111108G - INSERVICE INSPECTION      1 1 09/03/2014 09/10/2014 IP 7111108G Inservice Inspection Activities - BWR 71124 - RADIATION SAFETY      1 1 09/01/2014 09/05/2014 IP 71124.01 Radiological Hazard Assessment and Exposure Controls 1 09/01/2014 09/05/2014 IP 71124.02 Occupational ALARA Planning and Controls 1 09/01/2014 09/05/2014 IP 71124.03 In-Plant Airborne Radioactivity Control and Mitigation 1 09/01/2014 09/05/2014 IP 71124.04 Occupational Dose Assessment 1 09/01/2014 09/05/2014 IP 71151  Performance Indicator Verification 71124 - RAD SAFETY INSP      1 1 11/17/2014 11/21/2014 IP 71124.01 Radiological Hazard Assessment and Exposure Controls 1 11/17/2014 11/21/2014 IP 71124.02 Occupational ALARA Planning and Controls 1 11/17/2014 11/21/2014 IP 71124.05 Radiation Monitoring Instrumentation TRI FI - TRIENNIAL FIRE PROTECTION    5 1 12/01/2014 12/05/2014 IP 7111105T Fire Protection [Triennial]
1 12/15/2014 12/19/2014 IP 7111105T Fire Protection [Triennial]
ISFSI - ISFSI OPERATIONAL INSPECTION    1 1 03/01/2015 04/30/2015 IP 60855  Operation Of An ISFSI 1 03/01/2015 04/30/2015 IP 60855.1 Operation of an Independent Spent Fuel Storage Installation at Operating Plants 8/3EXAM - INITIAL OL EXAM      4 1 07/06/2015 08/10/2015 U01907 FY15-FITZ INITIAL OPERATOR LICENSING EXAM 1 08/03/2015 08/07/2015 U01907 FY15-FITZ INITIAL OPERATOR LICENSING EXAM This report does not include INPO and OUTAGE activities.


ML14241A040 SUNSI Review Non-Sensitive Sensitive Publicly Available Non-Publicly Available OFFICE RI/DRP RI/DRP RI/DRP NAME TSetzer/TCS ABurritt/ALB HNieh/HKN DATE 08/20/14 08/25/14 08/28/14
This report shows only on-site and announced inspection procedures. Enclosure


Page 1 of 2 08/19/2014 10:32:08 Report 22 Unit NumberPlanned Dates Start EndInspection ActivityTitle No. of Staff on Site FitzPatrickInspection / Activity Plan 07/01/2014
Page 2 of 2     FitzPatrick 08/19/2014 10:32:08   Inspection / Activity Plan Report 22 07/01/2014 - 12/31/2015 Unit Planned Dates        No. of Staff Number Start End Inspection Activity    Title  on Site 71124 - RAD SAFETY INSPECTION      1 1 04/06/2015 04/10/2015 IP 71124.01 Radiological Hazard Assessment and Exposure Controls 1 04/06/2015 04/10/2015 IP 71124.02 Occupational ALARA Planning and Controls 1 04/06/2015 04/10/2015 IP 71124.03 In-Plant Airborne Radioactivity Control and Mitigation 1 04/06/2015 04/10/2015 IP 71124.04 Occupational Dose Assessment 1 04/06/2015 04/10/2015 IP 71151  Performance Indicator Verification MODS - PERMANENT PLANT MODIFICATIONS    3 1 06/01/2015 06/05/2015 IP 7111117T Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications 7111107T - TRIENNIAL HEAT SINK      1 1 06/08/2015 06/12/2015 IP 7111107T Heat Sink Performance MODS - PERMANENT PLANT MODIFICATIONS    3 1 06/15/2015 06/19/2015 IP 7111117T Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications 71124.07 - RAD SAFETY INSPECTION      1 1 07/20/2015 07/24/2015 IP 71124.07 Radiological Environmental Monitoring Program 1 07/20/2015 07/24/2015 IP 71151  Performance Indicator Verification 71124 - RAD SAFETY INSPECTION     1 1 09/14/2015 09/18/2015 IP 71124.01 Radiological Hazard Assessment and Exposure Controls 1 09/14/2015 09/18/2015 IP 71124.02 Occupational ALARA Planning and Controls 1 09/14/2015 09/18/2015 IP 71124.03 In-Plant Airborne Radioactivity Control and Mitigation 1 09/14/2015 09/18/2015 IP 71124.04 Occupational Dose Assessment EP - EP EXERCISE      5 1 10/19/2015 10/23/2015 IP 7111407 Exercise Evaluation - Hostile Action (HA) Event 1 10/19/2015 10/23/2015 IP 7111408 Exercise Evaluation - Scenario Review 71124 - RAD SAFETY INSP      1 1 11/16/2015 11/20/2015 IP 71124.01 Radiological Hazard Assessment and Exposure Controls 1 11/16/2015 11/20/2015 IP 71124.02 Occupational ALARA Planning and Controls 1 11/16/2015 11/20/2015 IP 71124.05 Radiation Monitoring Instrumentation This report does not include INPO and OUTAGE activities.
-12/31/20159/22EXAM-INITIAL OL EXAM (2)
4 1 FY14-FITZPATRICK INITIAL OPERATOR LICENSING EXAM (2ND)
U01888 08/18/2014 08/22/2014 1 FY14-FITZPATRICK INITIAL OPERATOR LICENSING EXAM (2ND)
U01888 09/22/2014 10/02/2014EP PROG-EP PROGRAM INSPECTION 1 1 IP A lert and Notification System Testing7111402 07/07/201407/11/2014 1 IP Emergency Preparedness Organization Staffing and Augmentation System7111403 07/07/201407/11/2014 1 IP Correction of Emergency Preparedness Weaknesses and Deficiencies7111405 07/07/201407/11/201471124-RADIATION SAFETY INSPECTION 1 1 IP Radiation Monitoring Instrumentation71124.05 07/14/2014 07/18/2014 71003-LR COMMITMENTS INSP PHASE 2 3 1 IP Post-Approval Site Inspection for License Renewal 7100308/11/2014 08/15/2014 1 IP Post-Approval Site Inspection for License Renewal 71003 08/25/2014 08/29/20147111108G-INSERVICE INSPECTION 1 1 IP Inservice Inspection Activities - BWR7111108G 09/03/2014 09/10/201471124-RADIATION SAFETY 1 1 IP Radiological Hazard Assessment and Exposure Controls71124.01 09/01/2014 09/05/2014 1 IP Occupational ALARA Planning and Controls71124.02 09/01/2014 09/05/2014 1 IP In-Plant Airborne Radioactivity Control and Mitigation71124.03 09/01/2014 09/05/2014 1 IP Occupational Dose Assessment71124.04 09/01/2014 09/05/2014 1 IP Performance Indicator Verification71151 09/01/2014 09/05/201471124-RAD SAFETY INSP 1 1 IP Radiological Hazard Assessment and Exposure Controls71124.0111/17/201411/21/2014 1 IP Occupational ALARA Planning and Controls71124.0211/17/201411/21/2014 1 IP Radiation Monitoring Instrumentation71124.0511/17/201411/21/2014 TRI FI-TRIENNIAL FIRE PROTECTION 5 1 IP Fire Protection [Triennial]7111105T 12/01/2014 12/05/2014 1 IP Fire Protection [Triennial]7111105T 12/15/2014 12/19/2014 ISFSI-ISFSI OPERATIONAL INSPECTION 1 1 IP Operation Of An ISFSI 60855 03/01/2015 04/30/2015 1 IP Operation of an Independent Spent Fuel Storage Installation at Operating Plants 60855.1 03/01/2015 04/30/20158/3EXAM-INITIAL OL EXAM 4 1 FY15-FITZ INITIAL OPERATOR LICENSING EXAM U01907 07/06/2015 08/10/2015 1 FY15-FITZ INITIAL OPERATOR LICENSING EXAM U01907 08/03/2015 08/07/2015 This report does not include INPO and OUTAGE activities. This report shows only on-site and announced inspection procedures.


Page 2 of 2 08/19/2014 10:32:08 Report 22 Unit NumberPlanned Dates Start EndInspection ActivityTitle No. of Staff on Site FitzPatrickInspection / Activity Plan 07/01/2014
This report shows only on-site and announced inspection procedures. Enclosure
-12/31/201571124-RAD SAFETY INSPECTION 1 1 IP Radiological Hazard Assessment and Exposure Controls71124.01 04/06/2015 04/10/2015 1 IP Occupational ALARA Planning and Controls71124.02 04/06/2015 04/10/2015 1 IP In-Plant Airborne Radioactivity Control and Mitigation71124.03 04/06/2015 04/10/2015 1 IP Occupational Dose Assessment71124.04 04/06/2015 04/10/2015 1 IP Performance Indicator Verification71151 04/06/2015 04/10/2015 MODS-PERMANENT PLANT MODIFICATIONS 3 1 IP Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications7111117T 06/01/2015 06/05/20157111107T-TRIENNIAL HEAT SINK 1 1 IP Heat Sink Performance7111107T 06/08/2015 06/12/2015 MODS-PERMANENT PLANT MODIFICATIONS 3 1 IP Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications7111117T 06/15/2015 06/19/201571124.07-RAD SAFETY INSPECTION 1 1 IP Radiological Environmental Monitoring Program71124.07 07/20/2015 07/24/2015 1 IP Performance Indicator Verification71151 07/20/2015 07/24/201571124-RAD SAFETY INSPECTION 1 1 IP Radiological Hazard Assessment and Exposure Controls71124.01 09/14/2015 09/18/2015 1 IP Occupational ALARA Planning and Controls71124.02 09/14/2015 09/18/2015 1 IP In-Plant Airborne Radioactivity Control and Mitigation71124.03 09/14/2015 09/18/2015 1 IP Occupational Dose Assessment71124.04 09/14/2015 09/18/2015 EP-EP EXERCISE 5 1 IP Exercise Evaluation - Hostile Action (HA) Event7111407 10/19/2015 10/23/2015 1 IP Exercise Evaluation - Scenario Review7111408 10/19/2015 10/23/201571124-RAD SAFETY INSP 1 1 IP Radiological Hazard Assessment and Exposure Controls71124.0111/16/201511/20/2015 1 IP Occupational ALARA Planning and Controls71124.0211/16/201511/20/2015 1 IP Radiation Monitoring Instrumentation71124.0511/16/201511/20/2015 This report does not include INPO and OUTAGE activities. This report shows only on-site and announced inspection procedures.
}}
}}

Latest revision as of 00:56, 4 November 2019

Mid-Cycle Assessment Letter and Inspection Plan 2014 (ROP-15) - James A. FitzPatrick Nuclear Power Plant (Report 05000333/2014006)
ML14241A040
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 09/02/2014
From: Ho Nieh
Division Reactor Projects I
To: Coyle L
Entergy Nuclear Northeast
Burritt A
References
IR-2014-006
Download: ML14241A040 (6)


Text

mber 2, 2014

SUBJECT:

MID-CYCLE ASSESSMENT LETTER FOR JAMES A. FITZPATRICK NUCLEAR POWER PLANT (REPORT 05000333/2014006)

Dear Mr. Coyle:

On August 13, 2014, the U.S. Nuclear Regulatory Commission (NRC) completed its mid-cycle performance review of James A. FitzPatrick Nuclear Power Plant (FitzPatrick). The NRC reviewed the most recent quarterly performance indicators in addition to inspection results and enforcement actions from July 1, 2013 through June 30, 2014. 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, FitzPatrick was operated in a manner that preserved public health and safety and met all cornerstone objectives. The NRC determined the performance at FitzPatrick during the most recent quarter was within the Regulatory Response Column of the NRCs Reactor Oversight Process (ROP) Action Matrix, because all inspection findings had very low safety significance (Green) and one performance indicator was of low to moderate safety significance (White) in the Initiating Events cornerstone. Specifically, the Unplanned Power Changes per 7,000 Critical Hours performance indicator exceeded the Green/White threshold value in the fourth quarter of 2012. From January 20 through 24, 2014, NRC inspectors conducted the onsite portion of a supplemental inspection for the White performance indicator in accordance with Inspection Procedure (IP) 95001, "Supplemental Inspection for One or Two White Inputs in a Strategic Performance Area." The NRC inspectors concluded that the corrective actions taken by FitzPatrick to preclude repetition of the unplanned power changes were not sufficient to meet the inspection objectives. As a result, the inspection was not closed and remains open until additional corrective actions, including the replacement of the condenser tubes during the current refueling outage, have been completed. The NRC will review Entergys implementation of these additional corrective actions during a future inspection. The performance indicator will continue to be a White ROP Action Matrix input until the performance indicator results allow it to transition below the Green/White threshold. The NRC will notify you via separate correspondence when the plant will transition to the Licensee Response Column.

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 2014 reflect this revision to Inspection Manual Chapter (IMC) 0310. Cross-cutting aspects identified in 2013 using the 2013 terminology were 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 December 31, 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 end-of-cycle performance review. In addition to baseline inspections, the NRC will perform IP 71003, Post-Approval Site Inspection for License Renewal, and IP 60855, Operation of an Independent Spent Fuel Storage Installation (ISFSI). 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, 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. This audit includes an onsite component in order for the NRC to evaluate licensee plans for complying with the Orders, as described in site-specific 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 date for the onsite component at your site is being coordinated with your staff.

A site-specific audit plan for the visit will be provided in advance to allow sufficient time for preparations.

In accordance with Title 10 of the Code of Federal Regulations (10 CFR) Part 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 component of the NRC's Agencywide Document Access and Management System (ADAMS).

ADAMS is accessible from the NRC website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Please contact Arthur Burritt at (610)337-5069 with any questions you have regarding this letter.

Sincerely,

/RA/

Ho K. Nieh Director Division of Reactor Projects Docket No. 50-333 License No. DPR-59 Enclosure: Inspection Plan cc w/encl: Distribution via ListServ

ML14241A040 Non-Sensitive Publicly Available SUNSI Review Sensitive Non-Publicly Available OFFICE RI/DRP RI/DRP RI/DRP NAME TSetzer/TCS ABurritt/ALB HNieh/HKN DATE 08/20/14 08/25/14 08/28/14

Page 1 of 2 FitzPatrick 08/19/2014 10:32:08 Inspection / Activity Plan Report 22 07/01/2014 - 12/31/2015 Unit Planned Dates No. of Staff Number Start End Inspection Activity Title on Site 9/22EXAM - INITIAL OL EXAM (2) 4 1 08/18/2014 08/22/2014 U01888 FY14-FITZPATRICK INITIAL OPERATOR LICENSING EXAM (2ND)

1 09/22/2014 10/02/2014 U01888 FY14-FITZPATRICK INITIAL OPERATOR LICENSING EXAM (2ND)

EP PROG - EP PROGRAM INSPECTION 1 1 07/07/2014 07/11/2014 IP 7111402 Alert and Notification System Testing 1 07/07/2014 07/11/2014 IP 7111403 Emergency Preparedness Organization Staffing and Augmentation System 1 07/07/2014 07/11/2014 IP 7111405 Correction of Emergency Preparedness Weaknesses and Deficiencies 71124 - RADIATION SAFETY INSPECTION 1 1 07/14/2014 07/18/2014 IP 71124.05 Radiation Monitoring Instrumentation 71003 - LR COMMITMENTS INSP PHASE 2 3 1 08/11/2014 08/15/2014 IP 71003 Post-Approval Site Inspection for License Renewal 1 08/25/2014 08/29/2014 IP 71003 Post-Approval Site Inspection for License Renewal 7111108G - INSERVICE INSPECTION 1 1 09/03/2014 09/10/2014 IP 7111108G Inservice Inspection Activities - BWR 71124 - RADIATION SAFETY 1 1 09/01/2014 09/05/2014 IP 71124.01 Radiological Hazard Assessment and Exposure Controls 1 09/01/2014 09/05/2014 IP 71124.02 Occupational ALARA Planning and Controls 1 09/01/2014 09/05/2014 IP 71124.03 In-Plant Airborne Radioactivity Control and Mitigation 1 09/01/2014 09/05/2014 IP 71124.04 Occupational Dose Assessment 1 09/01/2014 09/05/2014 IP 71151 Performance Indicator Verification 71124 - RAD SAFETY INSP 1 1 11/17/2014 11/21/2014 IP 71124.01 Radiological Hazard Assessment and Exposure Controls 1 11/17/2014 11/21/2014 IP 71124.02 Occupational ALARA Planning and Controls 1 11/17/2014 11/21/2014 IP 71124.05 Radiation Monitoring Instrumentation TRI FI - TRIENNIAL FIRE PROTECTION 5 1 12/01/2014 12/05/2014 IP 7111105T Fire Protection [Triennial]

1 12/15/2014 12/19/2014 IP 7111105T Fire Protection [Triennial]

ISFSI - ISFSI OPERATIONAL INSPECTION 1 1 03/01/2015 04/30/2015 IP 60855 Operation Of An ISFSI 1 03/01/2015 04/30/2015 IP 60855.1 Operation of an Independent Spent Fuel Storage Installation at Operating Plants 8/3EXAM - INITIAL OL EXAM 4 1 07/06/2015 08/10/2015 U01907 FY15-FITZ INITIAL OPERATOR LICENSING EXAM 1 08/03/2015 08/07/2015 U01907 FY15-FITZ INITIAL OPERATOR LICENSING EXAM This report does not include INPO and OUTAGE activities.

This report shows only on-site and announced inspection procedures. Enclosure

Page 2 of 2 FitzPatrick 08/19/2014 10:32:08 Inspection / Activity Plan Report 22 07/01/2014 - 12/31/2015 Unit Planned Dates No. of Staff Number Start End Inspection Activity Title on Site 71124 - RAD SAFETY INSPECTION 1 1 04/06/2015 04/10/2015 IP 71124.01 Radiological Hazard Assessment and Exposure Controls 1 04/06/2015 04/10/2015 IP 71124.02 Occupational ALARA Planning and Controls 1 04/06/2015 04/10/2015 IP 71124.03 In-Plant Airborne Radioactivity Control and Mitigation 1 04/06/2015 04/10/2015 IP 71124.04 Occupational Dose Assessment 1 04/06/2015 04/10/2015 IP 71151 Performance Indicator Verification MODS - PERMANENT PLANT MODIFICATIONS 3 1 06/01/2015 06/05/2015 IP 7111117T Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications 7111107T - TRIENNIAL HEAT SINK 1 1 06/08/2015 06/12/2015 IP 7111107T Heat Sink Performance MODS - PERMANENT PLANT MODIFICATIONS 3 1 06/15/2015 06/19/2015 IP 7111117T Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications 71124.07 - RAD SAFETY INSPECTION 1 1 07/20/2015 07/24/2015 IP 71124.07 Radiological Environmental Monitoring Program 1 07/20/2015 07/24/2015 IP 71151 Performance Indicator Verification 71124 - RAD SAFETY INSPECTION 1 1 09/14/2015 09/18/2015 IP 71124.01 Radiological Hazard Assessment and Exposure Controls 1 09/14/2015 09/18/2015 IP 71124.02 Occupational ALARA Planning and Controls 1 09/14/2015 09/18/2015 IP 71124.03 In-Plant Airborne Radioactivity Control and Mitigation 1 09/14/2015 09/18/2015 IP 71124.04 Occupational Dose Assessment EP - EP EXERCISE 5 1 10/19/2015 10/23/2015 IP 7111407 Exercise Evaluation - Hostile Action (HA) Event 1 10/19/2015 10/23/2015 IP 7111408 Exercise Evaluation - Scenario Review 71124 - RAD SAFETY INSP 1 1 11/16/2015 11/20/2015 IP 71124.01 Radiological Hazard Assessment and Exposure Controls 1 11/16/2015 11/20/2015 IP 71124.02 Occupational ALARA Planning and Controls 1 11/16/2015 11/20/2015 IP 71124.05 Radiation Monitoring Instrumentation This report does not include INPO and OUTAGE activities.

This report shows only on-site and announced inspection procedures. Enclosure