IR 05000333/2014006: Difference between revisions
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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 | | author name = Nieh H | ||
| author affiliation = NRC/RGN-I/DRP | | author affiliation = NRC/RGN-I/DRP | ||
| addressee name = Coyle L | | addressee name = Coyle L | ||
Line 9: | Line 9: | ||
| docket = 05000333 | | docket = 05000333 | ||
| license number = DPR-059 | | license number = DPR-059 | ||
| contact person = Burritt A | | 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: | {{#Wiki_filter:mber 2, 2014 | ||
==SUBJECT:== | |||
MID-CYCLE ASSESSMENT LETTER FOR JAMES A. FITZPATRICK NUCLEAR POWER PLANT (REPORT 05000333/2014006) | |||
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. | ||
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 | |||
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. | ||
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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 | 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. | |||
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 | 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,/RA/ Ho K. Nieh Director Division of Reactor Projects | Sincerely, | ||
/RA/ | |||
Docket No. 50-333 License No. DPR-59 | 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 | 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/ | |||
This report shows only on-site and announced inspection procedures. Enclosure | |||
}} | }} |
Latest revision as of 00:56, 4 November 2019
ML14241A040 | |
Person / Time | |
---|---|
Site: | FitzPatrick |
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