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| number = ML14063A316 | | number = ML14063A316 | ||
| issue date = 03/04/2014 | | issue date = 03/04/2014 | ||
| title = 2013 Annual Assessment Letter for Pilgrim Nuclear Power Station (Report 05000293/2013001)( | | title = 2013 Annual Assessment Letter for Pilgrim Nuclear Power Station (Report 05000293/2013001)(w/Inspection Plan) | ||
| author name = Dean W | | author name = Dean W | ||
| author affiliation = NRC/RGN-I/ORA | | author affiliation = NRC/RGN-I/ORA | ||
| addressee name = Dent J | | addressee name = Dent J | ||
| Line 9: | Line 9: | ||
| docket = 05000293 | | docket = 05000293 | ||
| license number = DPR-035 | | license number = DPR-035 | ||
| contact person = McKinley | | contact person = McKinley R | ||
| case reference number = IR-13-001 | | case reference number = IR-13-001 | ||
| document type = Inspection Plan, Letter | | document type = Inspection Plan, Letter | ||
| Line 18: | Line 18: | ||
=Text= | =Text= | ||
{{#Wiki_filter: | {{#Wiki_filter:arch 4, 2014 | ||
==SUBJECT:== | |||
ANNUAL ASSESSMENT LETTER FOR PILGRIM NUCLEAR POWER STATION (REPORT 05000293/2013001) | |||
==Dear Mr. Dent:== | |||
On February 11, 2014, the U.S. Nuclear Regulatory Commission (NRC) completed its end-of-cycle performance review of Pilgrim Nuclear Power Station. The NRC reviewed the most recent quarterly performance indicators 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 the performance at Pilgrim Nuclear Power Station during the most recent quarter was within the Degraded Cornerstone Column of the NRCs Reactor Oversight Process (ROP) Action Matrix because two white performance indicators exist in the initiating events cornerstone. In the third quarter of 2013, the Unplanned Scrams with Complications performance indicator crossed the green to white threshold, which moved Pilgrim Nuclear Power Station from the licensee response column to the regulatory response column. Due to a scram on October 14, 2013, Pilgrim Nuclear Power Station crossed the green to white threshold for a second performance indicator for Unplanned Scrams per 7000 Critical Hours. When your staff notifies the NRC of your readiness, the NRC will conduct a supplemental inspection to review the actions taken to address the performance issues. Therefore, in addition to ROP baseline inspections, the NRC plans to conduct a supplemental inspection in accordance with Inspection Procedure 95002, Supplemental Inspection for One Degraded Cornerstone or Any Three White Inputs in a Strategic Performance Area. | |||
The NRC evaluates cross-cutting themes to determine whether a substantive cross-cutting issue exists in a particular area and to encourage licensees to take appropriate actions before more significant performance issues emerge. The NRC identified a cross-cutting theme in the Problem Identification and Resolution area. Specifically, the NRC identified four findings with a documented cross-cutting aspect of P.1(d) - Timeliness of Corrective Actions. The NRC determined that a substantive cross-cutting issue associated with P.1(d) does not exist because the theme was identified at the end of the assessment period and Entergy has not had sufficient time to evaluate the theme. Entergy has recognized the cross-cutting theme and entered it into the corrective action program. The NRC will evaluate corrective actions once Entergy has had time to evaluate the theme and implement corrective actions. Currently, the NRC does not have a concern with your staffs scope of effort and progress in addressing the cross-cutting theme. The NRC will continue to monitor your staffs effort and progress in addressing the theme until the theme criteria are no longer met. | |||
You should also be aware that the NRC plans to conduct a public meeting with you in which we will review station performance. During this meeting, in accordance with Inspection Manual Chapter (IMC) 0305, you will be given the opportunity to respond to any information contained in the annual assessment letter and to present any new or existing programs that are designed to maintain or improve current performance. | You should also be aware that the NRC plans to conduct a public meeting with you in which we will review station performance. During this meeting, in accordance with Inspection Manual Chapter (IMC) 0305, you will be given the opportunity to respond to any information contained in the annual assessment letter and to present any new or existing programs that are designed to maintain or improve current performance. | ||
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 IMC 0310. The CY 2013 end- | 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 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 cross-cutting theme/substantive cross-cutting issue in the Problem Identification and Resolution area identified during this assessment period will be carried forward to the mid-cycle assessment period using the revised terminology. | ||
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 cross-cutting theme/substantive cross-cutting issue in the Problem Identification and Resolution area identified during this assessment period will be carried forward to the mid-cycle assessment period using the revised terminology. 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. In addition to baseline inspections, the NRC will perform IP 92702, | |||
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. In addition to baseline inspections, the NRC will perform IP 92702, Followup on Corrective Actions for Violations and Deviations, IP 60854.1, Preoperational Testing of an Independent Spent Fuel Storage Facility Installations at Operating Plants, IP 60855.1, Operation of an Independent Spent Fuel Storage Installation at Operating Plants, and IP 60856.1, Review of 10 CFR 72.212(b) Evaluations. 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 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) 2.390, Public Inspections, Exemptions, Requests for Withholding, 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 Documents 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 Raymond McKinley at (610)337-5150 with any questions you have regarding this letter. | |||
Sincerely, | |||
/RA DCLew for/ | |||
William M. Dean Regional Administrator Docket No: 50-293 License No: DPR-35 Enclosure: Inspection Plan cc w/encl: Distribution via ListServ | |||
ML14063A316 Non-Sensitive Publicly Available SUNSI Review Sensitive Non-Publicly Available OFFICE RI/DRP RI/DRP RI/DRP RI/ORA NAME EKeighley/EMK RMcKinley/RRM MScott/EJB for WDean/DCL for DATE 2/27/14 2/27/14 2/28/14 3/4/14 | |||
Page 1 of 2 Pilgrim 02/27/2014 09:18:48 Inspection / Activity Plan Report 22 01/01/2014 - 06/30/2015 Unit Planned Dates No. of Staff Number Start End Inspection Activity Title on Site 2/24 EXM - PILGRIM INITIAL OL EXAM 4 1 01/27/2014 01/31/2014 U01876 FY14-PILGRIM INITIAL OPERATOR LICENSING EXAM 1 02/24/2014 02/28/2014 U01876 FY14-PILGRIM INITIAL OPERATOR LICENSING EXAM 71124 - 01-EXPOSURE CONTROL, 02-ALARA & 06 GWPP 1 1 02/18/2014 02/21/2014 IP 71124.01 Radiological Hazard Assessment and Exposure Controls 1 02/18/2014 02/21/2014 IP 71124.02 Occupational ALARA Planning and Controls 1 02/18/2014 02/21/2014 IP 71124.06 Radioactive Gaseous and Liquid Effluent Treatment ISFSI - ISFSI CRANE INSPECTION 2 1 03/24/2014 03/28/2014 IP 60853 On-Site Fabrication Of Components And Construction On An ISFSI EP EXER - EP EXERCISE INSPECTION 2 1 04/28/2014 05/02/2014 IP 7111407 Exercise Evaluation - Hostile Action (HA) Event CDBI - CDBI 6 1 05/19/2014 05/23/2014 IP 7111121 Component Design Bases Inspection 1 06/02/2014 06/05/2014 IP 7111121 Component Design Bases Inspection 1 06/16/2014 06/20/2014 IP 7111121 Component Design Bases Inspection 71124 - 05 RAD MONITORING INSTRUMENTATION 1 1 06/09/2014 06/12/2014 IP 71124.05 Radiation Monitoring Instrumentation ISFSI - DRY RUN & INITIAL ISFSI INSPECTION 3 1 09/01/2014 09/19/2014 IP 60854 Preoperational Testing Of An ISFSI 1 09/01/2014 09/19/2014 IP 60854.1 Preoperational Testing of Independent Spent Fuel Storage Facility Installation at Operating Plants 1 09/01/2014 09/19/2014 IP 60855 Operation Of An ISFSI 1 09/01/2014 09/19/2014 IP 60856 Review of 10 CFR 72.212(b) Evaluations 1 09/01/2014 09/19/2014 IP 60856.1 Review of 10 CFR 72.212(b) Evaluations at Operating Plants 1 09/22/2014 09/26/2014 IP 60855.1 Operation of an Independent Spent Fuel Storage Installation at Operating Plants 71124 - 71151 03 AIRBORNE CONTROL 04 DOSE ASSESS 1 1 11/03/2014 11/06/2014 IP 71124.03 In-Plant Airborne Radioactivity Control and Mitigation 1 11/03/2014 11/06/2014 IP 71124.04 Occupational Dose Assessment 1 11/03/2014 11/06/2014 IP 71151 Performance Indicator Verification 71124 - 01 EXPOSURE CONTROL 02 ALARA 1 1 03/02/2015 03/05/2015 IP 71124.01 Radiological Hazard Assessment and Exposure Controls 1 03/02/2015 03/05/2015 IP 71124.02 Occupational ALARA Planning and Controls 7111108G - INSETRVICE INSPECTION 1 1 03/30/2015 04/03/2015 IP 7111108G Inservice Inspection Activities - BWR This report does not include INPO and OUTAGE activities. | |||
This report shows only on-site and announced inspection procedures. Enclosure | |||
Page 2 of 2 Pilgrim 02/27/2014 09:18:48 Inspection / Activity Plan Report 22 01/01/2014 - 06/30/2015 Unit Planned Dates No. of Staff Number Start End Inspection Activity Title on Site 71124.08 - RADWASTE 1 1 04/06/2015 04/10/2015 IP 71124.08 Radioactive Solid Waste Processing and Radioactive Material Handling, Storage, and Transportation 71124 - 01 EXPOSURE 02 ALARA 03 AIRBORNE 04 DOSE 1 1 05/04/2015 05/08/2015 IP 71124.01 Radiological Hazard Assessment and Exposure Controls 1 05/04/2015 05/08/2015 IP 71124.02 Occupational ALARA Planning and Controls 1 05/04/2015 05/08/2015 IP 71124.03 In-Plant Airborne Radioactivity Control and Mitigation 1 05/04/2015 05/08/2015 IP 71124.04 Occupational Dose Assessment 71124 - RADIOACTIVE EFFLUENT CONTROL RETS 1 1 06/22/2015 06/26/2015 IP 71124.06 Radioactive Gaseous and Liquid Effluent Treatment This report does not include INPO and OUTAGE activities. | |||
This report shows only on-site and announced inspection procedures. Enclosure | |||
}} | }} | ||
Latest revision as of 07:22, 4 November 2019
| ML14063A316 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 03/04/2014 |
| From: | Bill Dean Region 1 Administrator |
| To: | Dent J Entergy Nuclear Operations |
| McKinley R | |
| References | |
| IR-13-001 | |
| Download: ML14063A316 (6) | |
Text
arch 4, 2014
SUBJECT:
ANNUAL ASSESSMENT LETTER FOR PILGRIM NUCLEAR POWER STATION (REPORT 05000293/2013001)
Dear Mr. Dent:
On February 11, 2014, the U.S. Nuclear Regulatory Commission (NRC) completed its end-of-cycle performance review of Pilgrim Nuclear Power Station. The NRC reviewed the most recent quarterly performance indicators 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 the performance at Pilgrim Nuclear Power Station during the most recent quarter was within the Degraded Cornerstone Column of the NRCs Reactor Oversight Process (ROP) Action Matrix because two white performance indicators exist in the initiating events cornerstone. In the third quarter of 2013, the Unplanned Scrams with Complications performance indicator crossed the green to white threshold, which moved Pilgrim Nuclear Power Station from the licensee response column to the regulatory response column. Due to a scram on October 14, 2013, Pilgrim Nuclear Power Station crossed the green to white threshold for a second performance indicator for Unplanned Scrams per 7000 Critical Hours. When your staff notifies the NRC of your readiness, the NRC will conduct a supplemental inspection to review the actions taken to address the performance issues. Therefore, in addition to ROP baseline inspections, the NRC plans to conduct a supplemental inspection in accordance with Inspection Procedure 95002, Supplemental Inspection for One Degraded Cornerstone or Any Three White Inputs in a Strategic Performance Area.
The NRC evaluates cross-cutting themes to determine whether a substantive cross-cutting issue exists in a particular area and to encourage licensees to take appropriate actions before more significant performance issues emerge. The NRC identified a cross-cutting theme in the Problem Identification and Resolution area. Specifically, the NRC identified four findings with a documented cross-cutting aspect of P.1(d) - Timeliness of Corrective Actions. The NRC determined that a substantive cross-cutting issue associated with P.1(d) does not exist because the theme was identified at the end of the assessment period and Entergy has not had sufficient time to evaluate the theme. Entergy has recognized the cross-cutting theme and entered it into the corrective action program. The NRC will evaluate corrective actions once Entergy has had time to evaluate the theme and implement corrective actions. Currently, the NRC does not have a concern with your staffs scope of effort and progress in addressing the cross-cutting theme. The NRC will continue to monitor your staffs effort and progress in addressing the theme until the theme criteria are no longer met.
You should also be aware that the NRC plans to conduct a public meeting with you in which we will review station performance. During this meeting, in accordance with Inspection Manual Chapter (IMC) 0305, you will be given the opportunity to respond to any information contained in the annual assessment letter and to present any new or existing programs that are designed to maintain or improve current performance.
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 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 cross-cutting theme/substantive cross-cutting issue in the Problem Identification and Resolution area identified during this assessment period will be carried forward to the mid-cycle assessment period using the revised terminology.
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. In addition to baseline inspections, the NRC will perform IP 92702, Followup on Corrective Actions for Violations and Deviations, IP 60854.1, Preoperational Testing of an Independent Spent Fuel Storage Facility Installations at Operating Plants, IP 60855.1, Operation of an Independent Spent Fuel Storage Installation at Operating Plants, and IP 60856.1, Review of 10 CFR 72.212(b) Evaluations. 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 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) 2.390, Public Inspections, Exemptions, Requests for Withholding, 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 Documents 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 Raymond McKinley at (610)337-5150 with any questions you have regarding this letter.
Sincerely,
/RA DCLew for/
William M. Dean Regional Administrator Docket No: 50-293 License No: DPR-35 Enclosure: Inspection Plan cc w/encl: Distribution via ListServ
ML14063A316 Non-Sensitive Publicly Available SUNSI Review Sensitive Non-Publicly Available OFFICE RI/DRP RI/DRP RI/DRP RI/ORA NAME EKeighley/EMK RMcKinley/RRM MScott/EJB for WDean/DCL for DATE 2/27/14 2/27/14 2/28/14 3/4/14
Page 1 of 2 Pilgrim 02/27/2014 09:18:48 Inspection / Activity Plan Report 22 01/01/2014 - 06/30/2015 Unit Planned Dates No. of Staff Number Start End Inspection Activity Title on Site 2/24 EXM - PILGRIM INITIAL OL EXAM 4 1 01/27/2014 01/31/2014 U01876 FY14-PILGRIM INITIAL OPERATOR LICENSING EXAM 1 02/24/2014 02/28/2014 U01876 FY14-PILGRIM INITIAL OPERATOR LICENSING EXAM 71124 - 01-EXPOSURE CONTROL, 02-ALARA & 06 GWPP 1 1 02/18/2014 02/21/2014 IP 71124.01 Radiological Hazard Assessment and Exposure Controls 1 02/18/2014 02/21/2014 IP 71124.02 Occupational ALARA Planning and Controls 1 02/18/2014 02/21/2014 IP 71124.06 Radioactive Gaseous and Liquid Effluent Treatment ISFSI - ISFSI CRANE INSPECTION 2 1 03/24/2014 03/28/2014 IP 60853 On-Site Fabrication Of Components And Construction On An ISFSI EP EXER - EP EXERCISE INSPECTION 2 1 04/28/2014 05/02/2014 IP 7111407 Exercise Evaluation - Hostile Action (HA) Event CDBI - CDBI 6 1 05/19/2014 05/23/2014 IP 7111121 Component Design Bases Inspection 1 06/02/2014 06/05/2014 IP 7111121 Component Design Bases Inspection 1 06/16/2014 06/20/2014 IP 7111121 Component Design Bases Inspection 71124 - 05 RAD MONITORING INSTRUMENTATION 1 1 06/09/2014 06/12/2014 IP 71124.05 Radiation Monitoring Instrumentation ISFSI - DRY RUN & INITIAL ISFSI INSPECTION 3 1 09/01/2014 09/19/2014 IP 60854 Preoperational Testing Of An ISFSI 1 09/01/2014 09/19/2014 IP 60854.1 Preoperational Testing of Independent Spent Fuel Storage Facility Installation at Operating Plants 1 09/01/2014 09/19/2014 IP 60855 Operation Of An ISFSI 1 09/01/2014 09/19/2014 IP 60856 Review of 10 CFR 72.212(b) Evaluations 1 09/01/2014 09/19/2014 IP 60856.1 Review of 10 CFR 72.212(b) Evaluations at Operating Plants 1 09/22/2014 09/26/2014 IP 60855.1 Operation of an Independent Spent Fuel Storage Installation at Operating Plants 71124 - 71151 03 AIRBORNE CONTROL 04 DOSE ASSESS 1 1 11/03/2014 11/06/2014 IP 71124.03 In-Plant Airborne Radioactivity Control and Mitigation 1 11/03/2014 11/06/2014 IP 71124.04 Occupational Dose Assessment 1 11/03/2014 11/06/2014 IP 71151 Performance Indicator Verification 71124 - 01 EXPOSURE CONTROL 02 ALARA 1 1 03/02/2015 03/05/2015 IP 71124.01 Radiological Hazard Assessment and Exposure Controls 1 03/02/2015 03/05/2015 IP 71124.02 Occupational ALARA Planning and Controls 7111108G - INSETRVICE INSPECTION 1 1 03/30/2015 04/03/2015 IP 7111108G Inservice Inspection Activities - BWR This report does not include INPO and OUTAGE activities.
This report shows only on-site and announced inspection procedures. Enclosure
Page 2 of 2 Pilgrim 02/27/2014 09:18:48 Inspection / Activity Plan Report 22 01/01/2014 - 06/30/2015 Unit Planned Dates No. of Staff Number Start End Inspection Activity Title on Site 71124.08 - RADWASTE 1 1 04/06/2015 04/10/2015 IP 71124.08 Radioactive Solid Waste Processing and Radioactive Material Handling, Storage, and Transportation 71124 - 01 EXPOSURE 02 ALARA 03 AIRBORNE 04 DOSE 1 1 05/04/2015 05/08/2015 IP 71124.01 Radiological Hazard Assessment and Exposure Controls 1 05/04/2015 05/08/2015 IP 71124.02 Occupational ALARA Planning and Controls 1 05/04/2015 05/08/2015 IP 71124.03 In-Plant Airborne Radioactivity Control and Mitigation 1 05/04/2015 05/08/2015 IP 71124.04 Occupational Dose Assessment 71124 - RADIOACTIVE EFFLUENT CONTROL RETS 1 1 06/22/2015 06/26/2015 IP 71124.06 Radioactive Gaseous and Liquid Effluent Treatment This report does not include INPO and OUTAGE activities.
This report shows only on-site and announced inspection procedures. Enclosure