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{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE RD. SUITE 210 LISLE, IL  60532-4352  September 2, 2014   Ms. Karen Fili Site Vice President Monticello Nuclear Generating Plant Northern States Power Company, Minnesota 2807 West County Road 75 Monticello, MN  55362-9637   
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE RD. SUIT E 210 LISLE, IL  60532
-4352  September 2, 2014 Ms. Karen Fili Site Vice President Monticello Nuclear Generating Plant Northern States Power Company, Minnesot a 2807 West County Road 75 Monticello, MN  55362
-9637   


==SUBJECT:==
==SUBJECT:==
MID-CYCLE ASSESSMENT LETTER FOR MONTICELLO NUCLEAR GENERATING PLANT
MID-CYCLE ASSESSMENT LETTER FOR MONTICELLO NUCLEAR GENERATING PLANT


==Dear Ms. Fili:==
==Dear Ms. Fili:==
On August 6, 2014, the U.S. Nuclear Regulatory Commission (NRC) completed its mid-cycle performance review of Monticello Nuclear Generating 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 the performance at Monticello Nuclear Generating Plant during the most recent quarter was within the Degraded Cornerstone Column of the NRC's Reactor Oversight Process (ROP) Action Matrix because of one Yellow finding, with substantial safety significance, in the Mitigating Systems Cornerstone. The finding involved the failure to maintain a procedure addressing all of the effects of an external flooding scenario on the plant As described in our Assessment Followup-Letter issued on August 28, 2013 (ADAMS Accession No. ML 13240A435), Monticello Nuclear Generating Plant transitioned from the Licensee Response column to the Degraded Cornerstone Column of the ROP Action Matrix in the second quarter of 2013 due to the Yellow finding related to the failure to maintain a procedure addressing all of the effects of an external flooding scenario on the plant. This failure resulted in the site not being able to support the timely implementation of flood protection activities within the 12-day timeframe credited in the design basis as stated in the updated safety analysis report. This finding will remain open until the successful completion of Inspection Procedure 95002, "Supplemental Inspection for One Degraded Cornerstone or Any Three White Inputs in a Strategic Performance Area."
 
On July 18, 2014, your staff notified the NRC of your readiness for it to 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," to review the actions taken to address the performance issues. The NRC has not yet scheduled this inspection.
On August 6, 2014, the U.S. Nuclear Regulatory Commission (
K. Fili The NRC identifies substantive cross-cutting issues (SCCIs) to communicate a concern with the licensee's performance in a cross-cutting area and to encourage the licensee to take appropriate actions before more significant performance issues emerge. The NRC identified a cross-cutting theme in the Human Performance, Conservative Bias aspect (H.14). Specifically, five inspection findings for the current 12-month assessment period were a cross-cutting aspect of H.14, "Individuals use decision-making practices that emphasize prudent choices over those that are simply allowable."  The NRC determined that an SCCI exists because the NRC has a concern with your staff's scope of effort and progress addressing the cross-cutting theme associated with Human Performance, Conservative Bias (H.14). Specifically, the NRC noted that your staff missed an early opportunity to identify this SCCI and, therefore failed to recognize that the SCCI affected overall plant performance. As a result, corrective actions to address the SCCI were unnecessarily delayed resulting in continued, declining performance in this area. In October 2013, after an adverse trend was identified in your corrective action program for three NRC-identified issues associated with this cross-cutting aspect, your staff determined that an apparent cause evaluation was necessary to address this issue. The apparent cause evaluation was subsequently cancelled and justifications were determined to be incorrect and delayed full understanding of the significance of the lack of conservative bias in decision making until April 2014, after another three NRC-identified findings with related H.14 aspects had been identified during the first quarter 2014. In total, six NRC-identified findings with H.14 aspects had been identified between February 2013 and April 2014. In May 2014, your staff completed a root cause evaluation which concluded that these issues reflected current organizational behavior and resulted from inadequate decision making and delayed corrective action from prior, similar issues. In particular, the root cause evaluation noted that the failure to take corrective actions in October 2013 was a result of underlying organizational behaviors. Given these circumstances and the recency of your additional actions, we cannot conclude that the corrective actions will be fully effective in addressing the cross-cutting theme. This human performance SCCI will remain open until the number of findings with a cross-cutting  aspect of H.14 is reduced, the corrective actions taken to mitigate the cross-cutting theme prove effective, and sustained performance improvement is observed in the H.14 aspect of the human performance area. The NRC will monitor your staff's effort and progress in addressing the SCCI by evaluating your corrective action program, any root cause evaluations for the SCCI, and performance improvement initiatives. In its assessment letter dated March 4, 2014 (ML14063A307), the NRC opened an SCCI in human performance with the aspect of H.7, "the organization creates and maintains complete, accurate and up-to-date documentation" (formally referred to as H.2(c)). As stated in the letter, this SCCI will remain open until the number of findings with a cross-cutting theme in H.7 is reduced, the corrective actions taken to mitigate the cross-cutting theme prove effective, and sustained performance improvement is observed in the H.7 aspect of the human performance area. To address the SCCI in H.7, your staff performed an apparent cause evaluation in July 2013 and a root cause evaluation in February 2014. These evaluations identified weaknesses in site leadership not enforcing quality work documents for procedures that are being approved for use K. Fili in the plant. In response, your staff developed performance improvement plans for each department, improved supervisory field oversight, and implemented additional training for supervisors. The NRC noted that that the number of findings with a cross-cutting aspect of H.7 remains above the threshold for assigning a cross-cutting aspect and that those corrective actions taken have not yet proven effective in substantially mitigating the cross-cutting theme even though a reasonable duration of time has passed. Therefore, this SCCI will remain open until the closure criteria stated above are met. Because this letter is the second consecutive assessment letter documenting an SCCI with the same cross-cutting aspect, the NRC requests your staff to provide a written response documenting your planned actions to address this SCCI. The NRC will continue to monitor your staff's effort and progress in addressing the SCCI by evaluating your corrective action program, any evaluations for the SCCI, and performance improvement initiatives. 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.
NRC) completed its mid
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 9-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. 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.   
-cycle performance review of Monticello Nuclear Generating 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 the performance at Monticello Nuclear Generating Plant during the most recent quarter was within the Degraded Cornerstone Column of the NRC
's Reactor Oversight Process (ROP) Action Matrix because of one Yellow finding, with substantial safety significance, in the Mitigating Systems Cornerstone. The finding involved the failure to maintain a procedure addressing all of the effects of an external flooding scenario on the plant As described in our Assessment Followup
-Letter issued on August 28, 2013 (ADAMS Accession No. ML 13240A435), Monticello Nuclear Generating Plant transitioned from the Licensee Response column to the Degraded Cornerstone Column of the ROP Action Matrix in the second quarter of 2013 due to the Yellow finding related to the failure to maintain a procedure addressing all of the effects of an external flooding scenario on the plant. This failure resulted in the site not being able to support the timely implementation of flood protection activities within the 12
-day timeframe credited in the design basis as stated in the updated safety analysis report.
This finding will remain open until the successful completion of Inspection Procedure 95002, "Supplemental Inspection for One Degraded Cornerstone or Any Three White Inputs in a Strategic Performance Area."
 
On July 18, 2014, your staff notified the NRC of your readiness for it to 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," to review the actions taken to address the performance issues.
The NRC has not yet scheduled this inspection.
K. Fili The NRC identifies substantive cross
-cutting issues (SCCIs) to communicate a concern with the licensee's performance in a cross
-cutting area and to encourage the licensee to take appropriate actions before more significant performance issues emerge. The NRC identified a cross-cutting theme in the Human Performance, Conservative Bias aspect (H.14). Specifically, five inspection findings for the current 12
-month assessment period were a cross-cutting aspect of H.14, "Individuals use decision
-making practices that emphasize prudent choices over those that are simply allowable."  The NRC determined that an SCCI exists because the NRC has a concern with your staff's scope of effort and progress addressing the cross
-cutting theme associated with Human Performance, Conservative Bias (H.14). Specifically, the NRC noted that your staff missed an early opportunity to identify this SCCI and, therefore failed to recognize that the SCCI affected overall plant performance. As a result, corrective actions to address the SCCI were unnecessarily delayed resulting in continued, declining performance in this area
. In October 2013, after an adverse trend was identified in your corrective action program for three NRC
-identified issues associated with this cross
-cutting aspect, your staff determined that an apparent cause evaluation was necessary to address this issue.
The apparent cause evaluation was subsequently cancelled and justifications were determined to be incorrect and delayed full understanding of the significance of the lack of conservative bias in decision making until April 2014, after another three NRC
-identified findings with related H.14 aspects had been identified during the first quarter 2014. In total, six NRC
-identified findings with H.14 aspects had been identified between February 2013 and April 2014. In May 2014, your staff completed a root cause evaluation which concluded that these issues reflected current organizational behavior and resulted from inadequate decision making and delayed corrective action from prior, similar issues. In particular, the root cause evaluation noted that the failure to take corrective actions in October 2013 was a result of underlying organizational behaviors.
Given these circumstances and the recency of your additional actions, we cannot conclude that the corrective actions will be fully effective in addressing the cross-cutting theme.
This human performance SCCI will remain open until the number of findings with a cross
-cutting  aspect of H.14 is reduced, the corrective actions taken to mitigate the cross
-cutting theme prove effective, and sustained performance improvement is observed in the H.14 aspect of the human performance area.
The NRC will monitor your staff's effort and progress in addressing the SCCI by evaluating your corrective action program, any root cause evaluations for the SCCI, and performance improvement initiatives.
In its assessment letter dated March 4, 2014 (ML14063A307), the NRC opened an SCCI in human performance with the aspect of H.7, "the organization creates and maintains complete, accurate and up
-to-date documentation" (formally referred to as H.2(c)). As stated in the letter, this SCCI will remain open until the number of findings with a cross
-cutting them e in H.7 is reduced, the corrective actions taken to mitigate the cross
-cutting theme prove effective, and sustained performance improvement is observed in the H.7 aspect of the human performance area. To address the SCCI in H.7, your staff performed an apparent cause evaluation in July 2013 and a root cause evaluation in February 2014.
These evaluations identified weaknesses in site leadership not enforcing quality work documents for procedures that are being approved for use
 
K. Fili in the plant. In response, your staff developed performance improvement plans for each department, improved supervisory field oversight, and implemented additional training for supervisors
. The NRC noted that that the number of findings with a cross
-cutting aspect of H.7 remains above the threshold for assigning a cross
-cutting aspect and that those corrective actions taken have not yet proven effective in substantially mitigating the cross
-cutting theme even though a reasonable duration of time has passed. Therefore, this SCCI will remain open until the closure criteria stated above are met. Because this letter is the second consecutive assessment letter documenting an SCCI with the same cross
-cutting aspect, the NRC requests your staff to provide a written response documenting your planned actions to address this SCCI. The NRC will continue to monitor your staff's effort and progress in addressing the SCCI by evaluating your corrective action program, any evaluations for the SCCI, and performance improvement initiatives.
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 9
-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.
In response to the accident at Fukushima, the Commission issued Order E A-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 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 Regulati ons 2.390, "Public Inspections, Exemptions, Requests for Withholding," of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any) 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 Kenneth Riemer at 630
-829-9628 with any questions you have regarding this letter. Sincerely,
  /RA/  Cynthia D. Pederson Regional Administrator Docket Nos.
50-263 License Nos. DPR-22 
 
==Enclosure:==
 
Monticello Nuclear Generating Plant Inspection/Activity Plan cc w/encl:  Distribution via LISTSERV


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, its enclosure, and your response (if any) 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).
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, its enclosure, and your response (if any) 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).
ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading
Please contact Kenneth Riemer at 630-829-9628 with any questions you have regarding this letter. Sincerely, /RA/  Cynthia D. Pederson Regional Administrator Docket Nos. 50-263 License Nos. DPR-22   
-rm/adams.html (the Public Electronic Reading Room).
Please contact Kenneth Riemer at 630
-829-9628 with any questions you have regarding this letter. Sincerely,
  /RA/  Cynthia D. Pederson Regional Administrator Docket Nos.
50-263 License Nos. DPR-22   


==Enclosure:==
==Enclosure:==
Monticello Nuclear Generating Plant  Inspection/Activity Plan  cc w/encl:  Distribution via LISTSERV 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, its enclosure, and your response (if any) 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 Kenneth Riemer at 630-829-9628 with any questions you have regarding this letter. Sincerely,  /RA/  Cynthia D. Pederson Regional Administrator Docket Nos. 50-263 License Nos. DPR-22 


==Enclosure:==
Monticello Nuclear Generating Plant Inspection/Activity Plan cc w/encl:  Distribution via LISTSERV DISTRIBUTION w/encl
Monticello Nuclear Generating Plant   Inspection/Activity Plan cc w/encl:  Distribution via LISTSERV DISTRIBUTION w/encl: Anthony Bowers RidsNrrDorlLpl3-1 Resource  RidsNrrPMMonticello 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:  Monticello 2014 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        NAME JMancuso:mt KRiemer ABoland CPederson DATE 08/25/14 08/25/14 08/22/14 08/26/14 OFFICIAL RECORD COPY Page 1 of 208/22/201409:41:08Report 22UnitNumberPlanned DatesStart           EndInspection ActivityTitleNo. of Staffon SiteMonticelloInspection / Activity Plan09/01/2014-12/31/2015ISFSI-PROGRAM REVIEW21     IPOperation of an Independent Spent Fuel Storage Installation at Operating Plants60855.109/01/201410/31/2014PI&R-BIENNIAL PI&R INSPECTION41     IPProblem Identification and Resolution71152B09/22/201410/10/2014BI RP-RADIATION PROTECTION BASELINE INSPECTION11     IPRadioactive Solid Waste Processing and Radioactive Material Handling, Storage, and Transportation71124.0812/01/201412/06/2014BI RP-RADIATION PROTECTION BASELINE INSPECTION21     IPOccupational ALARA Planning and Controls71124.0212/15/201412/19/20141     IPRadioactive Gaseous and Liquid Effluent Treatment71124.0612/15/201412/19/20141     IP71151-BI0112/15/201412/19/20141     IP71151-OR0112/15/201412/19/20141     IP71151-PR0112/15/201412/19/2014BI RP-RADIATION PROTECTION BASELINE INSPECTION11     IPIn-Plant Airborne Radioactivity Control and Mitigation71124.0301/12/201501/16/20151     IPOccupational Dose Assessment71124.0401/12/201501/16/2015BI ISI-ISI INSPECTION11     IPInservice Inspection Activities - BWR7111108G04/11/201505/11/2015BI RP-RADIATION PROTECTION BASELINE INSPECTION11     IPRadiological Hazard Assessment and Exposure Controls71124.0104/20/201504/24/20151     IPOccupational ALARA Planning and Controls71124.0204/20/201504/24/2015OL PREP-INIT EXAM/JUNE 201531     OL - INITIAL EXAM - 2015 MAY-JUN - MONTICELLOW9033105/11/201505/15/2015OL EXAM-INIT EXAM/JUNE 201531     OL - INITIAL EXAM - 2015 MAY-JUN - MONTICELLOW9033106/01/201506/12/2015BI ENG-COMPONENT DESIGN BASIS INSPECTION61     IPComponent Design Bases Inspection711112106/22/201507/24/2015BI RP-RADIATION PROTECTION BASELINE INSPECTION11     IPRadiological Environmental Monitoring Program71124.0708/10/201508/14/20151     IP71151-BI0108/10/201508/14/20151     IP71151-OR0108/10/201508/14/20151     IP71151-PR0108/10/201508/14/2015BL EPR-EP ROUTINE INSPECTION / PI VERIFICATION11     IPExercise Evaluation - Hostile Action (HA) Event711140708/17/201508/21/2015This report does not include INPO and OUTAGE activities. This report shows only on-site and announced inspection procedures.
: Anthony Bowers RidsNrrDorlLpl3
Page 2 of 208/22/201409:41:08Report 22UnitNumberPlanned DatesStart           EndInspection ActivityTitleNo. of Staffon SiteMonticelloInspection / Activity Plan09/01/2014-12/31/2015BL EPX-EP EXERCISE / PI VERIFICATON21     IPExercise Evaluation - Hostile Action (HA) Event711140708/17/201508/21/20151     IPExercise Evaluation - Scenario Review711140808/17/201508/21/20151     IPPerformance Indicator Verification7115108/17/201508/21/2015BI RP-RADIATION PROTECTION BASELINE INSPECTION11     IPOccupational ALARA Planning and Controls71124.0209/28/201510/02/2015BI OLRQ-BIENNIAL REQUAL PROGRAM INSPECTION21     IPLicensed Operator Requalification Program7111111B10/19/201510/23/2015This report does not include INPO and OUTAGE activities. This report shows only on-site and announced inspection procedures.}}
-1 Resource  RidsNrrPMMonticello 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:  Monticello 2014 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        NAME JMancuso:mt KRiemer ABoland CPederson DATE 08/25/14 08/25/14 08/22/14 08/26/14 OFFICIAL RECORD COPY
 
Page 1 of 2 08/22/2014 09:41:08Report 22 UnitNumberPlanned Dates Start           EndInspection ActivityTitleNo. of Staff on SiteMonticelloInspection / Activity Plan 09/01/2014
-12/31/2015 ISFSI-PROGRAM REVIEW 21     IPOperation of an Independent Spent Fuel Storage Installation at Operating Plants 60855.109/01/2014 10/31/2014 PI&R-BIENNIAL PI&R INSPECTION 41     IPProblem Identification and Resolution71152B09/22/2014 10/10/2014 BI RP-RADIATION PROTECTION BASELINE INSPECTION 11     IPRadioactive Solid Waste Processing and Radioactive Material Handling, Storage, and Transportation71124.0812/01/2014 12/06/2014 BI RP-RADIATION PROTECTION BASELINE INSPECTION 21     IPOccupational ALARA Planning and Controls71124.0212/15/2014 12/19/2014 1     IPRadioactive Gaseous and Liquid Effluent Treatment71124.0612/15/2014 12/19/2014 1     IP71151-BI01 12/15/2014 12/19/2014 1     IP71151-OR01 12/15/2014 12/19/2014 1     IP71151-PR01 12/15/2014 12/19/2014 BI RP-RADIATION PROTECTION BASELINE INSPECTION 11     IPIn-Plant Airborne Radioactivity Control and Mitigation71124.0301/12/2015 01/16/2015 1     IPOccupational Dose Assessment71124.0401/12/2015 01/16/2015 BI ISI-ISI INSPECTION 11     IPInservice Inspection Activities - BWR7111108G04/11/201505/11/2015 BI RP-RADIATION PROTECTION BASELINE INSPECTION 11     IPRadiological Hazard Assessment and Exposure Controls71124.0104/20/2015 04/24/2015 1     IPOccupational ALARA Planning and Controls71124.0204/20/2015 04/24/2015OL PREP-INIT EXAM/JUNE 2015 31     OL - INITIAL EXAM - 2015 MAY-JUN - MONTICELLO W9033105/11/2015 05/15/2015OL EXAM-INIT EXAM/JUNE 2015 31     OL - INITIAL EXAM - 2015 MAY-JUN - MONTICELLO W9033106/01/2015 06/12/2015 BI ENG-COMPONENT DESIGN BASIS INSPECTION 61     IPComponent Design Bases Inspection711112106/22/2015 07/24/2015 BI RP-RADIATION PROTECTION BASELINE INSPECTION 11     IPRadiological Environmental Monitoring Program71124.0708/10/2015 08/14/2015 1     IP71151-BI01 08/10/2015 08/14/2015 1     IP71151-OR01 08/10/2015 08/14/2015 1     IP71151-PR01 08/10/2015 08/14/2015BL EPR-EP ROUTINE INSPECTION / PI VERIFICATION 11     IPExercise Evaluation - Hostile Action (HA) Event711140708/17/2015 08/21/2015 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 09:41:08Report 22 UnitNumberPlanned Dates Start           EndInspection ActivityTitleNo. of Staff on SiteMonticelloInspection / Activity Plan 09/01/2014
-12/31/2015BL EPX-EP EXERCISE / PI VERIFICATON 21     IPExercise Evaluation - Hostile Action (HA) Event711140708/17/2015 08/21/2015 1     IPExercise Evaluation - Scenario Review711140808/17/2015 08/21/2015 1     IPPerformance Indicator Verification7115108/17/2015 08/21/2015 BI RP-RADIATION PROTECTION BASELINE INSPECTION 11     IPOccupational ALARA Planning and Controls71124.0209/28/2015 10/02/2015 BI OLRQ-BIENNIAL REQUAL PROGRAM INSPECTION 21     IPLicensed Operator Requalification Program7111111B10/19/2015 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 11:23, 1 July 2018

Mid-Cycle Assessment Letter for Monticello Nuclear Generating Plant
ML14245A144
Person / Time
Site: Monticello Xcel Energy icon.png
Issue date: 09/02/2014
From: Pederson C D
Region 3 Administrator
To: Fili K
Northern States Power Co
References
Download: ML14245A144 (7)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE RD. SUIT E 210 LISLE, IL 60532

-4352 September 2, 2014 Ms. Karen Fili Site Vice President Monticello Nuclear Generating Plant Northern States Power Company, Minnesot a 2807 West County Road 75 Monticello, MN 55362

-9637

SUBJECT:

MID-CYCLE ASSESSMENT LETTER FOR MONTICELLO NUCLEAR GENERATING PLANT

Dear Ms. Fili:

On August 6, 2014, the U.S. Nuclear Regulatory Commission (

NRC) completed its mid

-cycle performance review of Monticello Nuclear Generating 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 the performance at Monticello Nuclear Generating Plant during the most recent quarter was within the Degraded Cornerstone Column of the NRC

's Reactor Oversight Process (ROP) Action Matrix because of one Yellow finding, with substantial safety significance, in the Mitigating Systems Cornerstone. The finding involved the failure to maintain a procedure addressing all of the effects of an external flooding scenario on the plant As described in our Assessment Followup

-Letter issued on August 28, 2013 (ADAMS Accession No. ML 13240A435), Monticello Nuclear Generating Plant transitioned from the Licensee Response column to the Degraded Cornerstone Column of the ROP Action Matrix in the second quarter of 2013 due to the Yellow finding related to the failure to maintain a procedure addressing all of the effects of an external flooding scenario on the plant. This failure resulted in the site not being able to support the timely implementation of flood protection activities within the 12

-day timeframe credited in the design basis as stated in the updated safety analysis report.

This finding will remain open until the successful completion of Inspection Procedure 95002, "Supplemental Inspection for One Degraded Cornerstone or Any Three White Inputs in a Strategic Performance Area."

On July 18, 2014, your staff notified the NRC of your readiness for it to 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," to review the actions taken to address the performance issues.

The NRC has not yet scheduled this inspection.

K. Fili The NRC identifies substantive cross

-cutting issues (SCCIs) to communicate a concern with the licensee's performance in a cross

-cutting area and to encourage the licensee to take appropriate actions before more significant performance issues emerge. The NRC identified a cross-cutting theme in the Human Performance, Conservative Bias aspect (H.14). Specifically, five inspection findings for the current 12

-month assessment period were a cross-cutting aspect of H.14, "Individuals use decision

-making practices that emphasize prudent choices over those that are simply allowable." The NRC determined that an SCCI exists because the NRC has a concern with your staff's scope of effort and progress addressing the cross

-cutting theme associated with Human Performance, Conservative Bias (H.14). Specifically, the NRC noted that your staff missed an early opportunity to identify this SCCI and, therefore failed to recognize that the SCCI affected overall plant performance. As a result, corrective actions to address the SCCI were unnecessarily delayed resulting in continued, declining performance in this area

. In October 2013, after an adverse trend was identified in your corrective action program for three NRC

-identified issues associated with this cross

-cutting aspect, your staff determined that an apparent cause evaluation was necessary to address this issue.

The apparent cause evaluation was subsequently cancelled and justifications were determined to be incorrect and delayed full understanding of the significance of the lack of conservative bias in decision making until April 2014, after another three NRC

-identified findings with related H.14 aspects had been identified during the first quarter 2014. In total, six NRC

-identified findings with H.14 aspects had been identified between February 2013 and April 2014. In May 2014, your staff completed a root cause evaluation which concluded that these issues reflected current organizational behavior and resulted from inadequate decision making and delayed corrective action from prior, similar issues. In particular, the root cause evaluation noted that the failure to take corrective actions in October 2013 was a result of underlying organizational behaviors.

Given these circumstances and the recency of your additional actions, we cannot conclude that the corrective actions will be fully effective in addressing the cross-cutting theme.

This human performance SCCI will remain open until the number of findings with a cross

-cutting aspect of H.14 is reduced, the corrective actions taken to mitigate the cross

-cutting theme prove effective, and sustained performance improvement is observed in the H.14 aspect of the human performance area.

The NRC will monitor your staff's effort and progress in addressing the SCCI by evaluating your corrective action program, any root cause evaluations for the SCCI, and performance improvement initiatives.

In its assessment letter dated March 4, 2014 (ML14063A307), the NRC opened an SCCI in human performance with the aspect of H.7, "the organization creates and maintains complete, accurate and up

-to-date documentation" (formally referred to as H.2(c)). As stated in the letter, this SCCI will remain open until the number of findings with a cross

-cutting them e in H.7 is reduced, the corrective actions taken to mitigate the cross

-cutting theme prove effective, and sustained performance improvement is observed in the H.7 aspect of the human performance area. To address the SCCI in H.7, your staff performed an apparent cause evaluation in July 2013 and a root cause evaluation in February 2014.

These evaluations identified weaknesses in site leadership not enforcing quality work documents for procedures that are being approved for use

K. Fili in the plant. In response, your staff developed performance improvement plans for each department, improved supervisory field oversight, and implemented additional training for supervisors

. The NRC noted that that the number of findings with a cross

-cutting aspect of H.7 remains above the threshold for assigning a cross

-cutting aspect and that those corrective actions taken have not yet proven effective in substantially mitigating the cross

-cutting theme even though a reasonable duration of time has passed. Therefore, this SCCI will remain open until the closure criteria stated above are met. Because this letter is the second consecutive assessment letter documenting an SCCI with the same cross

-cutting aspect, the NRC requests your staff to provide a written response documenting your planned actions to address this SCCI. The NRC will continue to monitor your staff's effort and progress in addressing the SCCI by evaluating your corrective action program, any evaluations for the SCCI, and performance improvement initiatives.

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 9

-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.

In response to the accident at Fukushima, the Commission issued Order E A-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 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 Regulati ons 2.390, "Public Inspections, Exemptions, Requests for Withholding," of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any) 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 Kenneth Riemer at 630

-829-9628 with any questions you have regarding this letter. Sincerely,

/RA/ Cynthia D. Pederson Regional Administrator Docket Nos.

50-263 License Nos. DPR-22

Enclosure:

Monticello Nuclear Generating Plant Inspection/Activity Plan cc w/encl: Distribution via LISTSERV

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, its enclosure, and your response (if any) 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 Kenneth Riemer at 630

-829-9628 with any questions you have regarding this letter. Sincerely,

/RA/ Cynthia D. Pederson Regional Administrator Docket Nos.

50-263 License Nos. DPR-22

Enclosure:

Monticello Nuclear Generating Plant Inspection/Activity Plan cc w/encl: Distribution via LISTSERV DISTRIBUTION w/encl

Anthony Bowers RidsNrrDorlLpl3

-1 Resource RidsNrrPMMonticello 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: Monticello 2014 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 NAME JMancuso:mt KRiemer ABoland CPederson DATE 08/25/14 08/25/14 08/22/14 08/26/14 OFFICIAL RECORD COPY

Page 1 of 2 08/22/2014 09:41:08Report 22 UnitNumberPlanned Dates Start EndInspection ActivityTitleNo. of Staff on SiteMonticelloInspection / Activity Plan 09/01/2014

-12/31/2015 ISFSI-PROGRAM REVIEW 21 IPOperation of an Independent Spent Fuel Storage Installation at Operating Plants 60855.109/01/2014 10/31/2014 PI&R-BIENNIAL PI&R INSPECTION 41 IPProblem Identification and Resolution71152B09/22/2014 10/10/2014 BI RP-RADIATION PROTECTION BASELINE INSPECTION 11 IPRadioactive Solid Waste Processing and Radioactive Material Handling, Storage, and Transportation71124.0812/01/2014 12/06/2014 BI RP-RADIATION PROTECTION BASELINE INSPECTION 21 IPOccupational ALARA Planning and Controls71124.0212/15/2014 12/19/2014 1 IPRadioactive Gaseous and Liquid Effluent Treatment71124.0612/15/2014 12/19/2014 1 IP71151-BI01 12/15/2014 12/19/2014 1 IP71151-OR01 12/15/2014 12/19/2014 1 IP71151-PR01 12/15/2014 12/19/2014 BI RP-RADIATION PROTECTION BASELINE INSPECTION 11 IPIn-Plant Airborne Radioactivity Control and Mitigation71124.0301/12/2015 01/16/2015 1 IPOccupational Dose Assessment71124.0401/12/2015 01/16/2015 BI ISI-ISI INSPECTION 11 IPInservice Inspection Activities - BWR7111108G04/11/201505/11/2015 BI RP-RADIATION PROTECTION BASELINE INSPECTION 11 IPRadiological Hazard Assessment and Exposure Controls71124.0104/20/2015 04/24/2015 1 IPOccupational ALARA Planning and Controls71124.0204/20/2015 04/24/2015OL PREP-INIT EXAM/JUNE 2015 31 OL - INITIAL EXAM - 2015 MAY-JUN - MONTICELLO W9033105/11/2015 05/15/2015OL EXAM-INIT EXAM/JUNE 2015 31 OL - INITIAL EXAM - 2015 MAY-JUN - MONTICELLO W9033106/01/2015 06/12/2015 BI ENG-COMPONENT DESIGN BASIS INSPECTION 61 IPComponent Design Bases Inspection711112106/22/2015 07/24/2015 BI RP-RADIATION PROTECTION BASELINE INSPECTION 11 IPRadiological Environmental Monitoring Program71124.0708/10/2015 08/14/2015 1 IP71151-BI01 08/10/2015 08/14/2015 1 IP71151-OR01 08/10/2015 08/14/2015 1 IP71151-PR01 08/10/2015 08/14/2015BL EPR-EP ROUTINE INSPECTION / PI VERIFICATION 11 IPExercise Evaluation - Hostile Action (HA) Event711140708/17/2015 08/21/2015 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 09:41:08Report 22 UnitNumberPlanned Dates Start EndInspection ActivityTitleNo. of Staff on SiteMonticelloInspection / Activity Plan 09/01/2014

-12/31/2015BL EPX-EP EXERCISE / PI VERIFICATON 21 IPExercise Evaluation - Hostile Action (HA) Event711140708/17/2015 08/21/2015 1 IPExercise Evaluation - Scenario Review711140808/17/2015 08/21/2015 1 IPPerformance Indicator Verification7115108/17/2015 08/21/2015 BI RP-RADIATION PROTECTION BASELINE INSPECTION 11 IPOccupational ALARA Planning and Controls71124.0209/28/2015 10/02/2015 BI OLRQ-BIENNIAL REQUAL PROGRAM INSPECTION 21 IPLicensed Operator Requalification Program7111111B10/19/2015 10/23/2015 This report does not include INPO and OUTAGE activities. This report shows only on-site and announced inspection procedures.

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