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{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE ROAD, SUITE 210 LISLE, IL 60532-4352 March 5, 2012  
{{#Wiki_filter:March 5, 2012


Mr. Eric Larson Acting Site Vice President
==SUBJECT:==
 
ANNUAL ASSESSMENT LETTER FOR PERRY NUCLEAR POWER PLANT (REPORT 05000440/2011007)
FirstEnergy Nuclear Operating Company Perry Nuclear Power Plant P. O. Box 97, 10 Center Road, A-PY-A290 Perry, OH 44081-0097 SUBJECT: ANNUAL ASSESSMENT LETTER FOR PERRY NUCLEAR POWER PLANT (REPORT 05000440/2011007)


==Dear Mr. Larson:==
==Dear Mr. Larson:==
On February 15, 2012, the U.S. Nuclear Regulatory Commission (NRC) staff completed its end-of-cycle performance review of Perry Nuclear Power Plant. The NRC reviewed the most recent quarterly performance indicators (PIs) in addition to inspection results and enforcement actions for the period from January 1, 2011, through December 31, 2011. This letter informs you of the NRC's assessment of your facility during this period and its plans for future inspections at your facility. This performance review and enclosed inspection plan does not  
On February 15, 2012, the U.S. Nuclear Regulatory Commission (NRC) staff completed its end-of-cycle performance review of Perry Nuclear Power Plant. The NRC reviewed the most recent quarterly performance indicators (PIs) in addition to inspection results and enforcement actions for the period from January 1, 2011, through December 31, 2011. This letter informs you of the NRCs assessment of your facility during this period and its plans for future inspections at your facility. This performance review and enclosed inspection plan does not include security information. A separate letter will include the NRCs assessment of your performance in the Security Cornerstone and its security-related inspection plan.


include security information. A separate letter will include the NRC's assessment of your performance in the Security Cornerstone and its security-related inspection plan.
The NRC determined that the performance at the Perry Nuclear Power Plant during the most recent quarter was within the Degraded Cornerstone Column of the NRCs Reactor Oversight Process (ROP) Action Matrix because of one finding having a low-to-moderate safety significance (i.e., White) from the second quarter of 2011 and a White Occupational Exposure Control Effectiveness Performance Indicator (PI) with four occurrences (the threshold for Green-to-White is more than 2 occurrences) during the second and third quarters of 2011. The finding and the performance indicator were both in the Occupational Radiation Safety Cornerstone. One of the PI occurrences was in November 2010 and, therefore, no longer counted in the fourth quarter 2011. Additionally, one of the remaining three PI occurrences from the second quarter of 2011 had the same underlying cause as the White finding (a situation which could result in double counting the PI and the finding as White).


The NRC determined that the performance at the Perry Nuclear Power Plant during the most
Therefore, for the fourth quarter of 2011, in accordance with the guidance in Section 11.03 of Inspection Manual Chapter 0305, Operating Reactor Assessment Program, the White PI is not considered an Action Matrix input. Despite having only the single White finding as an input to the Action Matrix, Perry will remain in the Degraded Cornerstone Column of the ROP until a supplemental inspection in accordance with Inspection Procedure (IP) 95002, Supplemental Inspection for One Degraded Cornerstone or Any Three White Inputs in a Strategic Performance Area" is completed. We will schedule and conduct the inspection after you have completed your investigation on the reasons for the White performance indicator and White finding in the same cornerstone, and after you have advised us, in writing, that you are ready for the inspection. This supplemental inspection is in addition to ROP baseline inspections at your facility.


recent quarter was within the Degraded Cornerstone Column of the NRC's Reactor Oversight Process (ROP) Action Matrix because of one finding having a low-to-moderate safety significance (i.e., White) from the second quarter of 2011 and a White Occupational Exposure Control Effectiveness Performance Indicator (PI) with four occurrences (the threshold for Green-to-White is more than 2 occurrences) during the second and third quarters of 2011. The finding and the performance indicator were both in the Occupational Radiation Safety Cornerstone. One of the PI occurrences was in November 2010 and, therefore, no longer counted in the fourth quarter 2011. Additionally, one of the remaining three PI occurrences from the second quarter of 2011 had the same underlying cause as the White finding (a situation which could result in double counting the PI and the finding as White). Therefore, for the fourth quarter of 2011, in accordance with the guidance in Section 11.03 of Inspection Manual Chapter 0305, "Operating Reactor Assessment Program," the White PI is not considered an Action Matrix input. Despite having only the single White finding as an input to the Action Matrix, Perry will remain in the Degraded Cornerstone Column of the ROP until a supplemental inspection in accordance with Inspection Procedure (IP) 95002, "Supplemental Inspection for One Degraded Cornerstone or Any Three White Inputs in a Strategic Performance Area" is completed. We will schedule and conduct the inspection after you have completed your investigation on the reasons for the White performance indicator and White finding in the same cornerstone, and after you have advised us, in writing, that you are ready for the inspection. This supplemental inspection is in addition to ROP baseline inspections at your facility.
Performance at the Perry Nuclear Power Plant during the assessment period continued to exhibit weaknesses in the area of human performance (HP) with 12 findings identified.


Performance at the Perry Nuclear Power Plant during the assessment period continued to exhibit weaknesses in the area of human performance (HP) with 12 findings identified. This assessment period is the ninth consecutive assessment period identifying a substantive cross-cutting issue in the HP cross-cutting area. In our mid-cycle assessment letter  
This assessment period is the ninth consecutive assessment period identifying a substantive cross-cutting issue in the HP cross-cutting area. In our mid-cycle assessment letter
[ADAMS ML112440084] dated September 1, 2011, we advised you of substantive cross-cutting issues (SCCIs) in the HP area with cross-cutting themes in Work Planning, H.3(a), and Documentation/Procedures, H.2(c). In addition, we advised you that the HP SCCIs would remain open until the number of findings in the H.3(a) and H.2(c) aspects were reduced and you demonstrated the implementation of effective corrective actions that resulted in sustained performance improvement in the HP area.
[ADAMS ML112440084] dated September 1, 2011, we advised you of substantive cross-cutting issues (SCCIs) in the HP area with cross-cutting themes in Work Planning, H.3(a), and Documentation/Procedures, H.2(c). In addition, we advised you that the HP SCCIs would remain open until the number of findings in the H.3(a) and H.2(c) aspects were reduced and you demonstrated the implementation of effective corrective actions that resulted in sustained performance improvement in the HP area.


Regarding H.3 (a), at the time of the mid-cycle assessment, this SCCI was open for eight consecutive assessment periods. We performed an inspection [ADAMS ML120190153] in December 2011, and determined your corrective actions on this SCCI had been successful in reducing the findings and addressing the underlying causes. There were no findings in this aspect during this assessment cycle and there has been sustained performance improvement. For this reason, the SCCI in Work Planning, H.3(a), is closed.
Regarding H.3 (a), at the time of the mid-cycle assessment, this SCCI was open for eight consecutive assessment periods. We performed an inspection [ADAMS ML120190153] in December 2011, and determined your corrective actions on this SCCI had been successful in reducing the findings and addressing the underlying causes. There were no findings in this aspect during this assessment cycle and there has been sustained performance improvement.


During the same inspection performed in December 2011, regarding the SCCI in H.2(c), evaluations and actions had not been completed to allow NRC review. Your staff informed us that your facility was ready for the inspection in December; however, we determined while onsite that several key evaluations were not completed. We concluded the site was not ready for us to inspect your actions in regards to this SCCI. To date, the actions implemented by your staff have not resulted in sustained performance improvement in this aspect. Specifically, three inspection findings were identified with this aspect as the most significant contributing cause.
For this reason, the SCCI in Work Planning, H.3(a), is closed.
 
During the same inspection performed in December 2011, regarding the SCCI in H.2(c),
evaluations and actions had not been completed to allow NRC review. Your staff informed us that your facility was ready for the inspection in December; however, we determined while onsite that several key evaluations were not completed. We concluded the site was not ready for us to inspect your actions in regards to this SCCI. To date, the actions implemented by your staff have not resulted in sustained performance improvement in this aspect. Specifically, three inspection findings were identified with this aspect as the most significant contributing cause.


As a result, the H.2(c) SCCI will remain open.
As a result, the H.2(c) SCCI will remain open.


During this assessment period, the NRC staff identified a new SCCI in the HP area in the aspect of Conservative Assumptions, H.1(b). There were four findings during this assessment cycle which identified this aspect as the most significant contributing cause. At the close of 2011, your staff was performing a cause evaluation and the actions taken had not yet proven you were effective at mitigating the theme.
During this assessment period, the NRC staff identified a new SCCI in the HP area in the aspect of Conservative Assumptions, H.1(b). There were four findings during this assessment cycle which identified this aspect as the most significant contributing cause. At the close of 2011, your staff was performing a cause evaluation and the actions taken had not yet proven you were effective at mitigating the theme. Therefore, the NRC is opening an SCCI in Conservative Assumptions, H.1(b).


Therefore, the NRC is opening an SCCI in Conservative Assumptions, H.1(b).
The SCCIs in H.1(b) and H2(c) will remain open until the number of findings in the H.1(b) and H.2(c) aspects are reduced and you demonstrate the implementation of effective corrective actions that result in sustained performance improvement in each of these aspects of HP.


The SCCIs in H.1(b) and H2(c) will remain open until the number of findings in the H.1(b) and H.2(c) aspects are reduced and you demonstrate the implementation of effective corrective actions that result in sustained performance improvement in each of these aspects of HP. Although we noted some improvement in specific areas of HP during this assessment cycle, concerns with the SCCIs identified by this letter continue to exist. Because we were not able to inspect these SCCIs at the end of 2011 [since you had not completed your actions], we are asking you to provide to us within 30 days of this letter, in writing, the causes and corrective action planned and completed for the two SCCIs addressed in this letter. The plan should provide projected dates for actions, and you s hould provide any metrics you are using to determine whether sustained improvement has been achieved. In addition, you should be prepared to discuss these actions at the end-of-cycle assessment meeting. Based on the level of progress demonstrated at the end-of-cycle meeting, we will determine if additional meetings are needed.
Although we noted some improvement in specific areas of HP during this assessment cycle, concerns with the SCCIs identified by this letter continue to exist. Because we were not able to inspect these SCCIs at the end of 2011 [since you had not completed your actions], we are asking you to provide to us within 30 days of this letter, in writing, the causes and corrective action planned and completed for the two SCCIs addressed in this letter. The plan should provide projected dates for actions, and you should provide any metrics you are using to determine whether sustained improvement has been achieved. In addition, you should be prepared to discuss these actions at the end-of-cycle assessment meeting. Based on the level of progress demonstrated at the end-of-cycle meeting, we will determine if additional meetings are needed.


The enclosed inspection plan lists the inspections scheduled through June 30, 2013.
The enclosed inspection plan lists the inspections scheduled through June 30, 2013.


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 mid-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
Routine inspections performed by resident inspectors are not included in the inspection plan.


circumstances warrant any changes.
The inspections listed during the last 9 months of the inspection plan are tentative and may be revised at the mid-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.


In addition to the ROP baseline and IP 95002 inspections, inspections are planned for Temporary Instruction (TI) 2515/177, "Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems"; TI 2515/182, "Buried Piping and Tanks"; TI 2515/185, "Follow-up of NEI Groundwater Protection Initiative"; and Independent Spent Fuel Storage Installation (ISFSI) inspections: IP 60854.1, "Preoperational Testing of ISFSIs at Operating Plants"; IP 60855.1, "Operation of an ISFSI at Operating Plants"; and IP 60856.1, "Review of 10 CFR 72.212(b) Evaluations at Operating Plants."
In addition to the ROP baseline and IP 95002 inspections, inspections are planned for Temporary Instruction (TI) 2515/177, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems; TI 2515/182, Buried Piping and Tanks; TI 2515/185, Follow-up of NEI Groundwater Protection Initiative; and Independent Spent Fuel Storage Installation (ISFSI) inspections: IP 60854.1, Preoperational Testing of ISFSIs at Operating Plants; IP 60855.1, Operation of an ISFSI at Operating Plants; and IP 60856.1, Review of 10 CFR 72.212(b) Evaluations at Operating Plants.


In accordance with 10 CFR 2.390 of the NRC
In accordance with 10 CFR 2.390 of the NRC=s ARules 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 (PARS) component of NRC's document system (ADAMS).
=s A 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 (PARS) component of NRC's document 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-rm/adams.html (the Public Electronic Reading Room).


Please contact John B. Giessner at 630-829-9619 with any questions you have regarding this letter.
Please contact John B. Giessner at 630-829-9619 with any questions you have regarding this letter.
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Sincerely,
Sincerely,
/RA/
/RA/
Cynthia D. Pederson  
Cynthia D. Pederson Acting Regional Administrator Docket No. 50-440 License No. NPF-58 Enclosure: Perry Nuclear Power Plant Inspection/Activity Plan cc w/encl: Distribution via ListServ
 
Acting Regional Administrator Docket No. 50-440 License No. NPF-58  
 
Enclosure: Perry Nuclear Power Plant Inspection/Activity Plan cc w/encl: Distribution via ListServ
}}
}}

Latest revision as of 08:12, 12 November 2019

Annual Assessment Letter for Perry Nuclear Power Plant (Report 05000440/2011007)
ML12065A157
Person / Time
Site: Perry FirstEnergy icon.png
Issue date: 03/05/2012
From: Pederson C
Region 3 Administrator
To: Emily Larson
FirstEnergy Nuclear Operating Co
References
IR-11-007
Download: ML12065A157 (7)


Text

March 5, 2012

SUBJECT:

ANNUAL ASSESSMENT LETTER FOR PERRY NUCLEAR POWER PLANT (REPORT 05000440/2011007)

Dear Mr. Larson:

On February 15, 2012, the U.S. Nuclear Regulatory Commission (NRC) staff completed its end-of-cycle performance review of Perry Nuclear Power Plant. The NRC reviewed the most recent quarterly performance indicators (PIs) in addition to inspection results and enforcement actions for the period from January 1, 2011, through December 31, 2011. This letter informs you of the NRCs assessment of your facility during this period and its plans for future inspections at your facility. This performance review and enclosed inspection plan does not include security information. A separate letter will include the NRCs assessment of your performance in the Security Cornerstone and its security-related inspection plan.

The NRC determined that the performance at the Perry Nuclear Power Plant during the most recent quarter was within the Degraded Cornerstone Column of the NRCs Reactor Oversight Process (ROP) Action Matrix because of one finding having a low-to-moderate safety significance (i.e., White) from the second quarter of 2011 and a White Occupational Exposure Control Effectiveness Performance Indicator (PI) with four occurrences (the threshold for Green-to-White is more than 2 occurrences) during the second and third quarters of 2011. The finding and the performance indicator were both in the Occupational Radiation Safety Cornerstone. One of the PI occurrences was in November 2010 and, therefore, no longer counted in the fourth quarter 2011. Additionally, one of the remaining three PI occurrences from the second quarter of 2011 had the same underlying cause as the White finding (a situation which could result in double counting the PI and the finding as White).

Therefore, for the fourth quarter of 2011, in accordance with the guidance in Section 11.03 of Inspection Manual Chapter 0305, Operating Reactor Assessment Program, the White PI is not considered an Action Matrix input. Despite having only the single White finding as an input to the Action Matrix, Perry will remain in the Degraded Cornerstone Column of the ROP until a supplemental inspection in accordance with Inspection Procedure (IP) 95002, Supplemental Inspection for One Degraded Cornerstone or Any Three White Inputs in a Strategic Performance Area" is completed. We will schedule and conduct the inspection after you have completed your investigation on the reasons for the White performance indicator and White finding in the same cornerstone, and after you have advised us, in writing, that you are ready for the inspection. This supplemental inspection is in addition to ROP baseline inspections at your facility.

Performance at the Perry Nuclear Power Plant during the assessment period continued to exhibit weaknesses in the area of human performance (HP) with 12 findings identified.

This assessment period is the ninth consecutive assessment period identifying a substantive cross-cutting issue in the HP cross-cutting area. In our mid-cycle assessment letter

[ADAMS ML112440084] dated September 1, 2011, we advised you of substantive cross-cutting issues (SCCIs) in the HP area with cross-cutting themes in Work Planning, H.3(a), and Documentation/Procedures, H.2(c). In addition, we advised you that the HP SCCIs would remain open until the number of findings in the H.3(a) and H.2(c) aspects were reduced and you demonstrated the implementation of effective corrective actions that resulted in sustained performance improvement in the HP area.

Regarding H.3 (a), at the time of the mid-cycle assessment, this SCCI was open for eight consecutive assessment periods. We performed an inspection [ADAMS ML120190153] in December 2011, and determined your corrective actions on this SCCI had been successful in reducing the findings and addressing the underlying causes. There were no findings in this aspect during this assessment cycle and there has been sustained performance improvement.

For this reason, the SCCI in Work Planning, H.3(a), is closed.

During the same inspection performed in December 2011, regarding the SCCI in H.2(c),

evaluations and actions had not been completed to allow NRC review. Your staff informed us that your facility was ready for the inspection in December; however, we determined while onsite that several key evaluations were not completed. We concluded the site was not ready for us to inspect your actions in regards to this SCCI. To date, the actions implemented by your staff have not resulted in sustained performance improvement in this aspect. Specifically, three inspection findings were identified with this aspect as the most significant contributing cause.

As a result, the H.2(c) SCCI will remain open.

During this assessment period, the NRC staff identified a new SCCI in the HP area in the aspect of Conservative Assumptions, H.1(b). There were four findings during this assessment cycle which identified this aspect as the most significant contributing cause. At the close of 2011, your staff was performing a cause evaluation and the actions taken had not yet proven you were effective at mitigating the theme. Therefore, the NRC is opening an SCCI in Conservative Assumptions, H.1(b).

The SCCIs in H.1(b) and H2(c) will remain open until the number of findings in the H.1(b) and H.2(c) aspects are reduced and you demonstrate the implementation of effective corrective actions that result in sustained performance improvement in each of these aspects of HP.

Although we noted some improvement in specific areas of HP during this assessment cycle, concerns with the SCCIs identified by this letter continue to exist. Because we were not able to inspect these SCCIs at the end of 2011 [since you had not completed your actions], we are asking you to provide to us within 30 days of this letter, in writing, the causes and corrective action planned and completed for the two SCCIs addressed in this letter. The plan should provide projected dates for actions, and you should provide any metrics you are using to determine whether sustained improvement has been achieved. In addition, you should be prepared to discuss these actions at the end-of-cycle assessment meeting. Based on the level of progress demonstrated at the end-of-cycle meeting, we will determine if additional meetings are needed.

The enclosed inspection plan lists the inspections scheduled through June 30, 2013.

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 mid-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.

In addition to the ROP baseline and IP 95002 inspections, inspections are planned for Temporary Instruction (TI) 2515/177, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems; TI 2515/182, Buried Piping and Tanks; TI 2515/185, Follow-up of NEI Groundwater Protection Initiative; and Independent Spent Fuel Storage Installation (ISFSI) inspections: IP 60854.1, Preoperational Testing of ISFSIs at Operating Plants; IP 60855.1, Operation of an ISFSI at Operating Plants; and IP 60856.1, Review of 10 CFR 72.212(b) Evaluations at Operating Plants.

In accordance with 10 CFR 2.390 of the NRC=s ARules 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 (PARS) component of NRC's document 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 John B. Giessner at 630-829-9619 with any questions you have regarding this letter.

Sincerely,

/RA/

Cynthia D. Pederson Acting Regional Administrator Docket No. 50-440 License No. NPF-58 Enclosure: Perry Nuclear Power Plant Inspection/Activity Plan cc w/encl: Distribution via ListServ