ML14245A317: Difference between revisions
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
||
Line 15: | Line 15: | ||
=Text= | =Text= | ||
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE RD. | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE RD. SUIT E 210 LISLE, IL 60532 | ||
-4352 September 2, 2014 Mr. Ernest Harkness Site Vice President FirstEnergy Nuclear Operating Company Perry Nuclear Power Plant P. O. Box 97, 10 Center Road, A-PY-A290 Perry, OH 44081-0097 | |||
==SUBJECT:== | ==SUBJECT:== | ||
Line 21: | Line 22: | ||
==Dear Mr. Harkness:== | ==Dear Mr. Harkness:== | ||
On August 5, 2014, the U.S. Nuclear Regulatory Commission (NRC) completed its mid-cycle performance review of the Perry Nuclear Power Plant. The NRC reviewed the most recent quarterly performance indicators (PIs) in addition to inspection results and enforcement actions from July 1, 2013, through June 30, 2014. This letter informs you of the NRC's assessment of your facility during this period and its plans for future inspections at your facility. The NRC determined that overall, Perry Nuclear Power Plant was operated in a manner that preserved public health and safety and met all cornerstone objectives. The NRC determined the performance at Perry during the most recent quarter was within the Licensee Response Column (Column 1) of the NRC's Reactor Oversight Process (ROP) Action Matrix because all inspection findings had very low (i.e., green) safety significance, and all PIs indicated that your performance was within the nominal, expected range (i.e., green). Therefore, the NRC plans to conduct ROP baseline inspections at your facility. | On August 5, 2014, the U.S. Nuclear Regulatory Commission (NRC) completed its mid-cycle performance review of the Perry Nuclear Power Plant. The NRC reviewed the most recent quarterly performance indicators (PIs) in addition to inspection results and enforcement actions from July 1, 2013, through June 30, 2014. This letter informs you of the NRC's assessment of your facility during this period and its plans for future inspections at your facility. The NRC determined that overall, Perry Nuclear Power Plant was operated in a manner that preserved public health and safety and met all cornerstone objectives. | ||
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. 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. | The NRC determined the performance at Perry during the most recent quarter was within the Licensee Response Column (Column 1) of the NRC's Reactor Oversight Process (ROP) Action Matrix because all inspection findings had very low (i.e., green) safety significance, and all PIs indicated that your performance was within the nominal, expected range (i.e., green). Therefore, the NRC plans to conduct ROP baseline inspections at your facility. | ||
The NRC also plans to conduct non-routine inspections and temporary instructions at your facility, including: Inspection Procedure (IP) 71111.11(B), "Licensed Operator Requalification Program and Licensed Operator Performance (Biennial)," and IP 71152(B), "Problem Identification and Resolution (Biennial)." In response to the accident at Fukushima, the Commission issued Order EA | |||
Please contact me at 630-829-9618, with any questions you may have regarding this letter or the inspection plan. Sincerely, | 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. 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. | |||
The NRC also plans to conduct non-routine inspections and temporary instructions at your facility, including: Inspection Procedure (IP) 71111.11(B), "Licensed Operator Requalification Program and Licensed Operator Performance (Biennial)," and IP 71152(B), "Problem Identification and Resolution (Biennial)." In response to the accident at Fukushima, the Commission issued Order EA 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 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 2.390, "Public Inspections, Exemptions, Requests for Withholding," of the NRC's "Rules of Practice," a copy of this letter | |||
and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records System (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS). 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 630-829-9618, with any questions you may have regarding this letter or the inspection plan. | |||
Sincerely, | |||
/RA/ | /RA/ | ||
Michael Kunowski, Chief Branch 5 Division of Reactor Projects | Michael Kunowski, Chief Branch 5 Division of Reactor Projects Docket No. 50-440 License No. NPF-58 | ||
==Enclosure:== | ==Enclosure:== | ||
Perry Nuclear Power Plant Inspection/Activity Plan cc w/encl: Distribution via LISTSERV Please contact me at 630-829-9618, with any questions you may have regarding this letter or the inspection plan. Sincerely, | Perry Nuclear Power Plant Inspection/Activity Plan cc w/encl: Distribution via LISTSERV | ||
Michael Kunowski, Chief Branch 5 Division of Reactor Projects | |||
Please contact me at 630 | |||
-829-9618, with any questions you may have regarding this letter or the inspection plan. | |||
Sincerely, | |||
/RA/ | |||
Michael Kunowski, Chief Branch 5 Division of Reactor Projects Docket No. 50-440 License No. NPF-58 | |||
==Enclosure:== | ==Enclosure:== | ||
Perry Nuclear Power Plant Inspection/Activity Plan cc w/encl: Distribution via LISTSERV DISTRIBUTION w/ | Perry Nuclear Power Plant Inspection/Activity Plan cc w/encl: Distribution via LISTSERV DISTRIBUTION w/enc l: Anthony Bowers RidsNrrPMPerry Resource | ||
Page 2 of | |||
RidsNrrDorlLpl3 | |||
-2 Resource RidsNrrDirsIrib Resource Cynthia Pederson Darrell Roberts Steven Orth Allan Barker Carole Ariano Linda Linn DRPIII DRSIII Patricia Buckley Carmen Olteanu ROPassessment.Resource@nrc.gov DOCUMENT NAME: Perry MOC Letter Publicly Available Non-Publicly Available Sensitive Non-Sensitive To receive a copy of this document, indicate in the concurrence box "C" = Copy without attach/encl "E" = Copy with attach/encl "N" = No copy OFFICE RIII RIII RIII RIII NAME MKunowski:rj DATE 08/26/14 OFFICIAL RECORD COPY | |||
Page 1 of 2 08/22/2014 09:43:06Report 22 UnitNumberPlanned Dates Start EndInspection ActivityTitleNo. of Staff on SitePerryInspection / Activity Plan 09/01/2014 | |||
-12/31/2015 BI EPX-EP EXERCISE INSPECTION / PI VERIFICATION 21 IPPerformance Indicator Verification7115109/22/2014 09/26/2014 BI RP-RADIATION PROTECTION BASELINE INSPECTION 11 IPIn-Plant Airborne Radioactivity Control and Mitigation71124.0309/15/2014 09/19/2014 1 IPOccupational Dose Assessment71124.0409/15/2014 09/19/2014 EXERCISE-BIENNIAL EXERCISE 11 EXERCISE - PERRY - SEPT. 2014 - HAB - REGION ONLY W9032409/23/2014 09/23/2014 BI OLRQ-BIENNIAL REQUAL PROGRAM INSPECTION 21 IPLicensed Operator Requalification Program7111111B12/01/2014 12/05/2014OL PREP-INIT EXAM/FEB 2015 31 OL - INITIAL EXAM - 2015 FEB - PERRY W9033301/12/2015 01/16/2015OL EXAM-INIT EXAM/FEB. 2015 31 OL - INITIAL EXAM - 2015 FEB - PERRY W9033302/02/2015 02/13/2015 BI ISI-ISI INSPECTION 11 IPInservice Inspection Activities - BWR7111108G02/16/2015 03/29/2015 BI RP-RADIATION PROTECTION BASELINE INSPECTION 21 IPRadiological Hazard Assessment and Exposure Controls71124.0103/30/2015 04/03/2015 1 IPOccupational ALARA Planning and Controls71124.0203/30/2015 04/03/2015 BI RP-RADIATION PROTECTION BASELINE INSPECTION 11 IPRadioactive Gaseous and Liquid Effluent Treatment71124.0605/04/2015 05/08/2015 BI RP-RADIATION PROTECTION BASELINE INSPECTION 11 IPRadiological Environmental Monitoring Program71124.0706/08/2015 06/12/2015 1 IP71151-BI01 06/08/2015 06/12/2015 1 IP71151-OR01 06/08/2015 06/12/2015 1 IP71151-PR01 06/08/2015 06/12/2015 BI HS-TRIENNIAL HEAT SINK INSPECTION 21 IPHeat Sink Performance7111107T06/08/2015 06/12/2015 BI EPR-EP ROUTINE INSPECTION / PI VERIFICATION 21 IPAlert and Notification System Testing711140207/06/2015 07/10/2015 1 IPEmergency Preparedness Organization Staffing and Augmentation System711140307/06/2015 07/10/2015 1 IPCorrection of Emergency Preparedness Weaknesses and Deficiencies711140507/06/2015 07/10/2015 1 IPPerformance Indicator Verification7115107/06/2015 07/10/2015 This report does not include INPO and OUTAGE activities. This report shows only on-site and announced inspection procedures. | |||
Page 2 of 2 08/22/2014 09:43:06Report 22 UnitNumberPlanned Dates Start EndInspection ActivityTitleNo. of Staff on SitePerryInspection / Activity Plan 09/01/2014 | |||
-12/31/2015 BI PIR-BIENNIEL PROBLEM IDENT AND RESOLUTION 41 IPProblem Identification and Resolution71152B07/13/2015 07/31/2015 BI RP-RADIATION PROTECTION BASELINE INSPECTION 11 IPOccupational ALARA Planning and Controls71124.0209/21/2015 09/25/2015 BI FIRE-FIRE PROTECTION INSPECTION & BAG TRIP 31 IPFire Protection [Triennial]7111105T09/21/2015 10/23/2015 This report does not include INPO and OUTAGE activities. This report shows only on-site and announced inspection procedures.}} |
Revision as of 10:21, 1 July 2018
ML14245A317 | |
Person / Time | |
---|---|
Site: | Perry |
Issue date: | 09/02/2014 |
From: | Kunowski M A NRC/RGN-III/DRP/B5 |
To: | Harkness E FirstEnergy Nuclear Operating Co |
References | |
Download: ML14245A317 (6) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE RD. SUIT E 210 LISLE, IL 60532
-4352 September 2, 2014 Mr. Ernest Harkness Site Vice President FirstEnergy Nuclear Operating Company Perry Nuclear Power Plant P. O. Box 97, 10 Center Road, A-PY-A290 Perry, OH 44081-0097
SUBJECT:
MID-CYCLE ASSESSMENT LETTER FOR PERRY NUCLEAR POWER PLANT
Dear Mr. Harkness:
On August 5, 2014, the U.S. Nuclear Regulatory Commission (NRC) completed its mid-cycle performance review of the Perry Nuclear Power Plant. The NRC reviewed the most recent quarterly performance indicators (PIs) in addition to inspection results and enforcement actions from July 1, 2013, through June 30, 2014. This letter informs you of the NRC's assessment of your facility during this period and its plans for future inspections at your facility. The NRC determined that overall, Perry Nuclear Power Plant was operated in a manner that preserved public health and safety and met all cornerstone objectives.
The NRC determined the performance at Perry during the most recent quarter was within the Licensee Response Column (Column 1) of the NRC's Reactor Oversight Process (ROP) Action Matrix because all inspection findings had very low (i.e., green) safety significance, and all PIs indicated that your performance was within the nominal, expected range (i.e., green). Therefore, the NRC plans to conduct ROP baseline inspections at your facility.
As a result of the Safety Culture Common Language Initiative, the terminology and coding of cross-cutting aspects were revised. All cross
-cutting aspects identified during inspections conducted in calendar year 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. 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.
The NRC also plans to conduct non-routine inspections and temporary instructions at your facility, including: Inspection Procedure (IP) 71111.11(B), "Licensed Operator Requalification Program and Licensed Operator Performance (Biennial)," and IP 71152(B), "Problem Identification and Resolution (Biennial)." In response to the accident at Fukushima, the Commission issued Order EA 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 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 2.390, "Public Inspections, Exemptions, Requests for Withholding," of the NRC's "Rules of Practice," a copy of this letter
and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records System (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS). 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 630-829-9618, with any questions you may have regarding this letter or the inspection plan.
Sincerely,
/RA/
Michael Kunowski, Chief Branch 5 Division of Reactor Projects Docket No. 50-440 License No. NPF-58
Enclosure:
Perry Nuclear Power Plant Inspection/Activity Plan cc w/encl: Distribution via LISTSERV
Please contact me at 630
-829-9618, with any questions you may have regarding this letter or the inspection plan.
Sincerely,
/RA/
Michael Kunowski, Chief Branch 5 Division of Reactor Projects Docket No. 50-440 License No. NPF-58
Enclosure:
Perry Nuclear Power Plant Inspection/Activity Plan cc w/encl: Distribution via LISTSERV DISTRIBUTION w/enc l: Anthony Bowers RidsNrrPMPerry Resource
RidsNrrDorlLpl3
-2 Resource RidsNrrDirsIrib Resource Cynthia Pederson Darrell Roberts Steven Orth Allan Barker Carole Ariano Linda Linn DRPIII DRSIII Patricia Buckley Carmen Olteanu ROPassessment.Resource@nrc.gov DOCUMENT NAME: Perry MOC Letter Publicly Available Non-Publicly Available Sensitive Non-Sensitive To receive a copy of this document, indicate in the concurrence box "C" = Copy without attach/encl "E" = Copy with attach/encl "N" = No copy OFFICE RIII RIII RIII RIII NAME MKunowski:rj DATE 08/26/14 OFFICIAL RECORD COPY
Page 1 of 2 08/22/2014 09:43:06Report 22 UnitNumberPlanned Dates Start EndInspection ActivityTitleNo. of Staff on SitePerryInspection / Activity Plan 09/01/2014
-12/31/2015 BI EPX-EP EXERCISE INSPECTION / PI VERIFICATION 21 IPPerformance Indicator Verification7115109/22/2014 09/26/2014 BI RP-RADIATION PROTECTION BASELINE INSPECTION 11 IPIn-Plant Airborne Radioactivity Control and Mitigation71124.0309/15/2014 09/19/2014 1 IPOccupational Dose Assessment71124.0409/15/2014 09/19/2014 EXERCISE-BIENNIAL EXERCISE 11 EXERCISE - PERRY - SEPT. 2014 - HAB - REGION ONLY W9032409/23/2014 09/23/2014 BI OLRQ-BIENNIAL REQUAL PROGRAM INSPECTION 21 IPLicensed Operator Requalification Program7111111B12/01/2014 12/05/2014OL PREP-INIT EXAM/FEB 2015 31 OL - INITIAL EXAM - 2015 FEB - PERRY W9033301/12/2015 01/16/2015OL EXAM-INIT EXAM/FEB. 2015 31 OL - INITIAL EXAM - 2015 FEB - PERRY W9033302/02/2015 02/13/2015 BI ISI-ISI INSPECTION 11 IPInservice Inspection Activities - BWR7111108G02/16/2015 03/29/2015 BI RP-RADIATION PROTECTION BASELINE INSPECTION 21 IPRadiological Hazard Assessment and Exposure Controls71124.0103/30/2015 04/03/2015 1 IPOccupational ALARA Planning and Controls71124.0203/30/2015 04/03/2015 BI RP-RADIATION PROTECTION BASELINE INSPECTION 11 IPRadioactive Gaseous and Liquid Effluent Treatment71124.0605/04/2015 05/08/2015 BI RP-RADIATION PROTECTION BASELINE INSPECTION 11 IPRadiological Environmental Monitoring Program71124.0706/08/2015 06/12/2015 1 IP71151-BI01 06/08/2015 06/12/2015 1 IP71151-OR01 06/08/2015 06/12/2015 1 IP71151-PR01 06/08/2015 06/12/2015 BI HS-TRIENNIAL HEAT SINK INSPECTION 21 IPHeat Sink Performance7111107T06/08/2015 06/12/2015 BI EPR-EP ROUTINE INSPECTION / PI VERIFICATION 21 IPAlert and Notification System Testing711140207/06/2015 07/10/2015 1 IPEmergency Preparedness Organization Staffing and Augmentation System711140307/06/2015 07/10/2015 1 IPCorrection of Emergency Preparedness Weaknesses and Deficiencies711140507/06/2015 07/10/2015 1 IPPerformance Indicator Verification7115107/06/2015 07/10/2015 This report does not include INPO and OUTAGE activities. This report shows only on-site and announced inspection procedures.
Page 2 of 2 08/22/2014 09:43:06Report 22 UnitNumberPlanned Dates Start EndInspection ActivityTitleNo. of Staff on SitePerryInspection / Activity Plan 09/01/2014
-12/31/2015 BI PIR-BIENNIEL PROBLEM IDENT AND RESOLUTION 41 IPProblem Identification and Resolution71152B07/13/2015 07/31/2015 BI RP-RADIATION PROTECTION BASELINE INSPECTION 11 IPOccupational ALARA Planning and Controls71124.0209/21/2015 09/25/2015 BI FIRE-FIRE PROTECTION INSPECTION & BAG TRIP 31 IPFire Protection [Triennial]7111105T09/21/2015 10/23/2015 This report does not include INPO and OUTAGE activities. This report shows only on-site and announced inspection procedures.