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| issue date = 09/02/2014 | | issue date = 09/02/2014 | ||
| title = ROP-15 Mid-Cycle Performance Review and Inspection Plan Report 05000443/2014006 | | title = ROP-15 Mid-Cycle Performance Review and Inspection Plan Report 05000443/2014006 | ||
| author name = Dentel G | | author name = Dentel G | ||
| author affiliation = NRC/RGN-I/DRP/PB3 | | author affiliation = NRC/RGN-I/DRP/PB3 | ||
| addressee name = Curtland D | | addressee name = Curtland D | ||
| Line 20: | Line 20: | ||
{{#Wiki_filter:September 2, 2014 | {{#Wiki_filter:September 2, 2014 | ||
SUBJECT: MID-CYCLE ASSESSMENT LETTER FOR SEABROOK STATION, UNIT NO. 1 (REPORT 05000443/2014006) | ==SUBJECT:== | ||
MID-CYCLE ASSESSMENT LETTER FOR SEABROOK STATION, UNIT NO. 1 (REPORT 05000443/2014006) | |||
==Dear Mr. Curtland:== | ==Dear Mr. Curtland:== | ||
On August 14, 2014, the U.S. Nuclear Regulatory Commission (NRC) completed its mid-cycle performance review of Seabrook Station, Unit No. 1 (Seabrook). The NRC reviewed the most recent quarterly performance indicators in addition to inspection results and enforcement actions from July 1, assessment of your facility during this period and its plans for future inspections at your facility. The NRC determined that overall, Seabrook was operated in a manner that preserved public health and safety and met all cornerstone objectives. The NRC determined the performance at Seabrook during the most recent quarter was within the Licensee Response Column of the (i.e., green) safety significance, and all performance indicators demonstrated that your performance was within the nominal, expected range (i.e, green). Therefore, the NRC plans to conduct Reactor Oversight Process 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 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. As part of our baseline inspection program, (ASR) non-conforming condition impacting safety-related reinforced concrete structures at Seabrook. This will be accomplished through scheduled six-month inspection activities using sampling guidance. In addition to baseline inspections, the NRC will perform IP 60855.1, 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-Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-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- Modifying Licenses with Regard to Reliable Spent Fuel Pool 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 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 Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). Please contact me at (610) 337-5233 with any questions you have regarding this letter. | On August 14, 2014, the U.S. Nuclear Regulatory Commission (NRC) completed its mid-cycle performance review of Seabrook Station, Unit No. 1 (Seabrook). 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, Seabrook was operated in a manner that preserved public health and safety and met all cornerstone objectives. The NRC determined the performance at Seabrook during the most recent quarter was within the Licensee Response Column of the NRCs Reactor Oversight Process Action Matrix because all inspection findings had very low (i.e., green) safety significance, and all performance indicators demonstrated that your performance was within the nominal, expected range (i.e, green). Therefore, the NRC plans to conduct Reactor Oversight Process 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 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. As part of our baseline inspection program, we will maintain a focused oversight of NextEras actions to address the Alkali Silica Reaction (ASR) non-conforming condition impacting safety-related reinforced concrete structures at Seabrook. This will be accomplished through scheduled six-month inspection activities using Inspection Procedure (IP) 71152, Problem Identification and Resolution Inspection, annual sampling guidance. In addition to baseline inspections, the NRC will perform IP 60855.1, Operation of an Independent Spent Fuel Storage Installation at Operating Plants. 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 Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). | |||
Please contact me at (610) 337-5233 with any questions you have regarding this letter. | |||
Sincerely, | Sincerely, | ||
/RA/ Glenn T. Dentel, Chief Projects Branch 3 Division of Reactor Projects Docket No.: 50-443 License No.: NPF-86 Enclosure: Inspection Plan cc w/encl: Distribution via ListServ | /RA/ | ||
Glenn T. Dentel, Chief Projects Branch 3 Division of Reactor Projects | |||
Docket No.: 50-443 License No.: NPF-86 | |||
Enclosure: Inspection Plan | |||
cc w/encl: Distribution via ListServ | |||
ML14239A182 SUNSI Review | |||
Non-Sensitive | |||
Sensitive | |||
Publicly Available | |||
Non-Publicly Available | |||
OFFICE RI/DRP RI/DRP RI/DRP | |||
NAME PCataldo/per email MSD MDraxton/ MSD GDentel/ GTD | |||
DATE 08/25/14 08/25/14 08/27/14 Distribution w/encl: (via e-mail) | |||
W. Dean, RA D. Lew, DRA H. Nieh, DRP M. Scott, DRP J. Trapp, DRS B. Welling, DRS G. Dentel, DRP R. Barkley, DRP M. Draxton, DRP B. Reyes, DRP P. Cataldo, DRP, SRI C. Newport, DRP, RI A. Cass, DRP, Resident AA A. Bowers, RI, OEDO R. J. Powell, DRP DRS Branch Chiefs (6) | |||
N. McNamara, RI, SLO D. Tifft, RI, SLO | |||
D. Screnci, RI, PAO N. Sheehan, RI, PAO RidsNrrDirslpab Resource ROPassessment Resource RidsNrrPMSeabrook Resource RidsNrrDorlLpl1-2 Resource ROPreports Resource | |||
Page 1 of 2 08/25/2014 08:58:13 Report 22 Unit Number Planned Dates Start End Inspection Activity Title No. of Staff on Site Seabrook Inspection / Activity Plan 07/01/2014 - 12/31/2015 TRI FI | |||
- TRIENNIAL FIRE PROTECTION | |||
1 IP Fire Protection [Triennial] | |||
7111105T 07/07/2014 07/11/2014 71152B | |||
- PI&R BIENNIAL | |||
1 IP Problem Identification and Resolution 71152B 10/06/2014 10/10/2014 | |||
IP Problem Identification and Resolution 71152B 10/20/2014 10/24/2014 71124.08 | |||
- RADWASTE | |||
1 IP Radioactive Solid Waste Processing and Radioactive Material Handling, Storage, and Transportation 71124.08 08/18/2014 08/22/2014 ASR | |||
- PI&R SAMPLE - ASR MONITORING | |||
1 IP Problem Identification and Resolution 71152 10/20/2014 10/24/2014 EP EXER | |||
- EP EXERCISE INSPECTION | |||
1 IP Exercise Evaluation - Hostile Action (HA) Event 7111407 11/03/2014 11/07/2014 3-23EXM | |||
- INITIAL OL EXAM | |||
1 FY15-SEABROOK INITIAL OPERATOR LICENSING EXAM U01915 02/17/2015 03/20/2015 | |||
FY15-SEABROOK INITIAL OPERATOR LICENSING EXAM U01915 03/23/2015 04/04/2015 71151 | |||
- 71151 PI VERIFY IP 71124.01, 02 & 05 | |||
1 IP Radiological Hazard Assessment and Exposure Controls 71124.01 12/08/2014 12/12/2014 | |||
IP Occupational ALARA Planning and Controls 71124.02 12/08/2014 12/12/2014 | |||
IP Radiation Monitoring Instrumentation 71124.05 12/08/2014 12/12/2014 | |||
IP 71151-OR01 12/08/2014 12/12/2014 | |||
IP 71151-PR01 12/08/2014 12/12/2014 ISFSI | |||
- ISFSI OPERATIONAL INSPECTION | |||
1 IP Operation of an Independent Spent Fuel Storage Installation at Operating Plants 60855.1 03/01/2015 04/30/2015 ASR | |||
- PI&R SAMPLE - ASR MONITORING | |||
1 IP Problem Identification and Resolution 71152 03/02/2015 03/06/2015 MODS | |||
- PERMANENT PLANT MODIFICATIONS | |||
1 IP Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications 7111117T 03/02/2015 03/06/2015 | |||
IP Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications 7111117T 03/16/2015 03/20/2015 71124 | |||
- RAD EFFLUENT CONTROL RETS | |||
1 IP Radioactive Gaseous and Liquid Effluent Treatment 71124.06 04/20/2015 04/23/2015 7111107T | |||
- TRIENNIAL HEAT SINK | |||
1 IP Heat Sink Performance 7111107T 06/01/2015 06/05/2015 71124 | |||
- REMP | |||
1 IP Radiological Environmental Monitoring Program 71124.07 07/06/2015 07/09/2015 This report does not include INPO and OUTAGE activities. | |||
This report shows only on-site and announced inspection procedures. | |||
Page 2 of 2 08/25/2014 08:58:13 Report 22 Unit Number Planned Dates Start End Inspection Activity Title No. of Staff on Site Seabrook Inspection / Activity Plan 07/01/2014 - 12/31/2015 ASR | |||
- PI&R SAMPLE - ASR MONITORING | |||
1 IP Problem Identification and Resolution 71152 09/14/2015 09/18/2015 7111108P | |||
- INSERVICE INSPECTION | |||
1 IP Inservice Inspection Activities - PWR 7111108P 10/05/2015 10/16/2015 7111111B | |||
- REQUAL INSP W/ P/F RESULTS | |||
1 IP Licensed Operator Requalification Program 7111111B 12/07/2015 12/11/2015 71124 | |||
- HP 71124.01 02 03 04 | |||
1 IP Radiological Hazard Assessment and Exposure Controls 71124.01 10/19/2015 10/23/2015 | |||
IP Occupational ALARA Planning and Controls 71124.02 10/19/2015 10/23/2015 | |||
IP In-Plant Airborne Radioactivity Control and Mitigation 71124.03 10/19/2015 10/23/2015 | |||
IP Occupational Dose Assessment 71124.04 10/19/2015 10/23/2015 EP | |||
- EP PROGRAM INSPECTION | |||
1 IP Alert and Notification System Testing 7111402 11/02/2015 11/06/2015 | |||
IP Emergency Preparedness Organization Staffing and Augmentation System 7111403 11/02/2015 11/06/2015 | |||
IP Correction of Emergency Preparedness Weaknesses and Deficiencies 7111405 11/02/2015 11/06/2015 71151 | |||
- HP PI VERIFY RAD HAZARD ALARA | |||
1 IP Radiological Hazard Assessment and Exposure Controls 71124.01 12/07/2015 12/10/2015 | |||
IP Performance Indicator Verification 71151 12/07/2015 12/10/2015 This report does not include INPO and OUTAGE activities. | |||
This report shows only on-site and announced inspection procedures. | |||
}} | }} | ||
Latest revision as of 17:17, 10 January 2025
| ML14239A182 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 09/02/2014 |
| From: | Glenn Dentel Reactor Projects Branch 3 |
| To: | Dean Curtland NextEra Energy Seabrook |
| DENTEL, GT | |
| References | |
| IR-2014-006 | |
| Download: ML14239A182 (5) | |
Text
September 2, 2014
SUBJECT:
MID-CYCLE ASSESSMENT LETTER FOR SEABROOK STATION, UNIT NO. 1 (REPORT 05000443/2014006)
Dear Mr. Curtland:
On August 14, 2014, the U.S. Nuclear Regulatory Commission (NRC) completed its mid-cycle performance review of Seabrook Station, Unit No. 1 (Seabrook). 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, Seabrook was operated in a manner that preserved public health and safety and met all cornerstone objectives. The NRC determined the performance at Seabrook during the most recent quarter was within the Licensee Response Column of the NRCs Reactor Oversight Process Action Matrix because all inspection findings had very low (i.e., green) safety significance, and all performance indicators demonstrated that your performance was within the nominal, expected range (i.e, green). Therefore, the NRC plans to conduct Reactor Oversight Process 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 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. As part of our baseline inspection program, we will maintain a focused oversight of NextEras actions to address the Alkali Silica Reaction (ASR) non-conforming condition impacting safety-related reinforced concrete structures at Seabrook. This will be accomplished through scheduled six-month inspection activities using Inspection Procedure (IP) 71152, Problem Identification and Resolution Inspection, annual sampling guidance. In addition to baseline inspections, the NRC will perform IP 60855.1, Operation of an Independent Spent Fuel Storage Installation at Operating Plants. 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 Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Please contact me at (610) 337-5233 with any questions you have regarding this letter.
Sincerely,
/RA/
Glenn T. Dentel, Chief Projects Branch 3 Division of Reactor Projects
Docket No.: 50-443 License No.: NPF-86
Enclosure: Inspection Plan
cc w/encl: Distribution via ListServ
ML14239A182 SUNSI Review
Non-Sensitive
Sensitive
Publicly Available
Non-Publicly Available
OFFICE RI/DRP RI/DRP RI/DRP
NAME PCataldo/per email MSD MDraxton/ MSD GDentel/ GTD
DATE 08/25/14 08/25/14 08/27/14 Distribution w/encl: (via e-mail)
W. Dean, RA D. Lew, DRA H. Nieh, DRP M. Scott, DRP J. Trapp, DRS B. Welling, DRS G. Dentel, DRP R. Barkley, DRP M. Draxton, DRP B. Reyes, DRP P. Cataldo, DRP, SRI C. Newport, DRP, RI A. Cass, DRP, Resident AA A. Bowers, RI, OEDO R. J. Powell, DRP DRS Branch Chiefs (6)
N. McNamara, RI, SLO D. Tifft, RI, SLO
D. Screnci, RI, PAO N. Sheehan, RI, PAO RidsNrrDirslpab Resource ROPassessment Resource RidsNrrPMSeabrook Resource RidsNrrDorlLpl1-2 Resource ROPreports Resource
Page 1 of 2 08/25/2014 08:58:13 Report 22 Unit Number Planned Dates Start End Inspection Activity Title No. of Staff on Site Seabrook Inspection / Activity Plan 07/01/2014 - 12/31/2015 TRI FI
- TRIENNIAL FIRE PROTECTION
1 IP Fire Protection [Triennial]
7111105T 07/07/2014 07/11/2014 71152B
- PI&R BIENNIAL
1 IP Problem Identification and Resolution 71152B 10/06/2014 10/10/2014
IP Problem Identification and Resolution 71152B 10/20/2014 10/24/2014 71124.08
- RADWASTE
1 IP Radioactive Solid Waste Processing and Radioactive Material Handling, Storage, and Transportation 71124.08 08/18/2014 08/22/2014 ASR
- PI&R SAMPLE - ASR MONITORING
1 IP Problem Identification and Resolution 71152 10/20/2014 10/24/2014 EP EXER
- EP EXERCISE INSPECTION
1 IP Exercise Evaluation - Hostile Action (HA) Event 7111407 11/03/2014 11/07/2014 3-23EXM
- INITIAL OL EXAM
1 FY15-SEABROOK INITIAL OPERATOR LICENSING EXAM U01915 02/17/2015 03/20/2015
FY15-SEABROOK INITIAL OPERATOR LICENSING EXAM U01915 03/23/2015 04/04/2015 71151
- 71151 PI VERIFY IP 71124.01, 02 & 05
1 IP Radiological Hazard Assessment and Exposure Controls 71124.01 12/08/2014 12/12/2014
IP Occupational ALARA Planning and Controls 71124.02 12/08/2014 12/12/2014
IP Radiation Monitoring Instrumentation 71124.05 12/08/2014 12/12/2014
IP 71151-OR01 12/08/2014 12/12/2014
IP 71151-PR01 12/08/2014 12/12/2014 ISFSI
- ISFSI OPERATIONAL INSPECTION
1 IP Operation of an Independent Spent Fuel Storage Installation at Operating Plants 60855.1 03/01/2015 04/30/2015 ASR
- PI&R SAMPLE - ASR MONITORING
1 IP Problem Identification and Resolution 71152 03/02/2015 03/06/2015 MODS
- PERMANENT PLANT MODIFICATIONS
1 IP Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications 7111117T 03/02/2015 03/06/2015
IP Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications 7111117T 03/16/2015 03/20/2015 71124
- RAD EFFLUENT CONTROL RETS
1 IP Radioactive Gaseous and Liquid Effluent Treatment 71124.06 04/20/2015 04/23/2015 7111107T
- TRIENNIAL HEAT SINK
1 IP Heat Sink Performance 7111107T 06/01/2015 06/05/2015 71124
- REMP
1 IP Radiological Environmental Monitoring Program 71124.07 07/06/2015 07/09/2015 This report does not include INPO and OUTAGE activities.
This report shows only on-site and announced inspection procedures.
Page 2 of 2 08/25/2014 08:58:13 Report 22 Unit Number Planned Dates Start End Inspection Activity Title No. of Staff on Site Seabrook Inspection / Activity Plan 07/01/2014 - 12/31/2015 ASR
- PI&R SAMPLE - ASR MONITORING
1 IP Problem Identification and Resolution 71152 09/14/2015 09/18/2015 7111108P
- INSERVICE INSPECTION
1 IP Inservice Inspection Activities - PWR 7111108P 10/05/2015 10/16/2015 7111111B
- REQUAL INSP W/ P/F RESULTS
1 IP Licensed Operator Requalification Program 7111111B 12/07/2015 12/11/2015 71124
1 IP Radiological Hazard Assessment and Exposure Controls 71124.01 10/19/2015 10/23/2015
IP Occupational ALARA Planning and Controls 71124.02 10/19/2015 10/23/2015
IP In-Plant Airborne Radioactivity Control and Mitigation 71124.03 10/19/2015 10/23/2015
IP Occupational Dose Assessment 71124.04 10/19/2015 10/23/2015 EP
- EP PROGRAM INSPECTION
1 IP Alert and Notification System Testing 7111402 11/02/2015 11/06/2015
IP Emergency Preparedness Organization Staffing and Augmentation System 7111403 11/02/2015 11/06/2015
IP Correction of Emergency Preparedness Weaknesses and Deficiencies 7111405 11/02/2015 11/06/2015 71151
- HP PI VERIFY RAD HAZARD ALARA
1 IP Radiological Hazard Assessment and Exposure Controls 71124.01 12/07/2015 12/10/2015
IP Performance Indicator Verification 71151 12/07/2015 12/10/2015 This report does not include INPO and OUTAGE activities.
This report shows only on-site and announced inspection procedures.