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| number = ML13115A095
| number = ML13115A095
| issue date = 04/24/2013
| issue date = 04/24/2013
| title = Fort Calhoun Station 05000285-13-405-LTR-Non-SGI-JMR-1
| title = 05000285-13-405-LTR-Non-SGI-JMR-1
| author name = Hay M C
| author name = Hay M
| author affiliation = NRC/RGN-IV/DRP
| author affiliation = NRC/RGN-IV/DRP
| addressee name = Cortopassi L
| addressee name = Cortopassi L
Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:" " April 24, 2013 Louis Cortopassi, Vice President
{{#Wiki_filter:UNITE D S TATE S NUC LEAR RE GULATOR Y C OMMI S SI ON ril 24, 2013


and Chief Nuclear Officer Omaha Public Power District
==SUBJECT:==
 
FORT CALHOUN STATION - NRC IMC 0350 SECURITY INSPECTION REPORT 05000285/2013405
Fort Calhoun Station FC-2-4 P.O. Box 550 Fort Calhoun, NE 68023-0550
 
SUBJECT: FORT CALHOUN STATION - NRC IMC 0350 SECURITY INSPECTION REPORT 05000285/2013405


==Dear Mr. Cortopassi:==
==Dear Mr. Cortopassi:==
On March 14, 2013, the U.S. Nuclear Regulatory Commission (NRC) completed a supplemental inspection at your Fort Calhoun Station. The enclosed inspection report documents the inspection results, which were discussed on March 14, 2013, with you and other members of  
On March 14, 2013, the U.S. Nuclear Regulatory Commission (NRC) completed a supplemental inspection at your Fort Calhoun Station. The enclosed inspection report documents the inspection results, which were discussed on March 14, 2013, with you and other members of your staff.
 
your staff.


In accordance with Inspection Manual Chapter (IMC) 0350, "Oversight of Reactor Facilities in a Shutdown Condition Due to Significant Performance and/or Operational Concerns," this supplemental inspection was performed to follow-up on performance issues which occurred in the first, second, and third quarter of 2011, and again during the second quarter of 2012. These issues were previously documented and assessed in NRC Inspection Reports 05000285/2011404, 05000285/2011406, and 05000285/2012403.
In accordance with Inspection Manual Chapter (IMC) 0350, Oversight of Reactor Facilities in a Shutdown Condition Due to Significant Performance and/or Operational Concerns, this supplemental inspection was performed to follow-up on performance issues which occurred in the first, second, and third quarter of 2011, and again during the second quarter of 2012. These issues were previously documented and assessed in NRC Inspection Reports 05000285/2011404, 05000285/2011406, and 05000285/2012403.


The objectives of this supplemental inspection were to provide assurance that: (1) the root causes and the contributing causes for the significant issues were understood; (2) the extent of condition and extent of cause of the issues were identified; and (3) corrective actions were or will be sufficient to address and preclude repetition of the root and contributing causes.
The objectives of this supplemental inspection were to provide assurance that: (1) the root causes and the contributing causes for the significant issues were understood; (2) the extent of condition and extent of cause of the issues were identified; and (3) corrective actions were or will be sufficient to address and preclude repetition of the root and contributing causes.


During this inspection, the NRC determined that your staff had not performed a comprehensive evaluation of the causes for the Greater-than-Green findings. Specifically, the team identified significant problems with your staff's collective evaluation of the events and the extent of cause reviews. This led the NRC to conclude that the fundamental performance issues within security, and their impact on security processes, have yet to be identified and corrected. Based on these findings, the Greater-than-Green security violations will be held open until adequate causal analyses, extent of cause reviews, and corrective actions are completed by  
During this inspection, the NRC determined that your staff had not performed a comprehensive evaluation of the causes for the Greater-than-Green findings. Specifically, the team identified significant problems with your staffs collective evaluation of the events and the extent of cause reviews. This led the NRC to conclude that the fundamental performance issues within security, and their impact on security processes, have yet to be identified and corrected. Based on these findings, the Greater-than-Green security violations will be held open until adequate causal analyses, extent of cause reviews, and corrective actions are completed by your staff, and are assessed by the NRC during a future inspection.
 
your staff, and are assessed by the NRC during a future inspection.


Additionally, nine NRC identified findings of very low security significance (i.e., Green as determined by the Physical Protection Significance Determination Process) were identified during this inspection. The deficiencies were promptly corrected or compensated for, and the plant was in compliance with applicable physical protection and security requirements within the scope of this inspection before the team left the area.
Additionally, nine NRC identified findings of very low security significance (i.e., Green as determined by the Physical Protection Significance Determination Process) were identified during this inspection. The deficiencies were promptly corrected or compensated for, and the plant was in compliance with applicable physical protection and security requirements within the scope of this inspection before the team left the area.


Nine of these findings were determined to involve violations of NRC requirements. Further, a licensee-identified violation which was determined to be of very low security significance is listed  
Nine of these findings were determined to involve violations of NRC requirements. Further, a licensee-identified violation which was determined to be of very low security significance is listed in this report. The NRC is treating these violations as noncited violations (NCVs) consistent with Section 2.3.2.a of the Enforcement Policy.
 
in this report. The NRC is treating these violations as noncited violations (NCVs) consistent with Section 2.3.2.a of the Enforcement Policy.
 
If you contest these violations or the significance of these NCVs, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington DC 20555-0001; with copies to the Regional Administrator, Region IV; the Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington, DC 20555-0001; and the NRC Resident Inspectors at Fort Calhoun Station Seven cross-cutting aspects were assigned to the findings in the area of Human Performance, and two cross-cutting aspects were assigned in the area of Problem Identification and Resolution. Cross-cutting aspects were assigned in the area of Human Performance because
 
your staff failed to: 1) make safety-significant decisions using a systemic process [H1.(a)]; 2) use conservative assumptions in decision making [H1.(b)]; 3) ensure the availability of complete, accurate, and up-to-date procedures [H.2(c)]; and 4) ensure the availability of adequate equipment [H2.(d)]. Cross-cutting aspects were assigned in the area of Problem Identification and Resolution because your staff failed to thoroughly evaluate problems such that the resolutions address causes and extent of conditions, as necessary [P1.(c)]. If you disagree with a cross-cutting aspect assignment in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the Regional Administrator, Region IV; and the NRC Resident Inspectors at Fort Calhoun Station.
 
In accordance with 10 CFR 2.390 of the NRC's "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 Agencywide Document Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
 
However, the material enclosed contains Security-Related Information in accordance with 10 CFR 2.390(d)(1) and its disclosure to unauthorized individuals could present a security vulnerability. Therefore, the material in the enclosure will not be made available electronically for public inspection in the NRC Public Document Room or from the PARS component of NRC's ADAMS. If you choose to provide a response and Security-Related Information is necessary to provide an acceptable response, please mark your entire response "Security-Related Information - Withhold from public disclosure under 10 CFR 2.390" in accordance with 10 CFR 2.390(d)(1) and follow the instructions for withholding in 10 CFR 2.390(b)(1). In accordance with 10 CFR 2.390(b)(1)(ii), the NRC is waiving the affidavit requirements for your response.
 
Sincerely,/RA/
Michael C. Hay, Chief Project Branch F Division of Reactor Projects
 
Docket No.: 50-285 License No.: DPR-40
 
Nonpublic
 
===Enclosure:===
NRC Inspection Report 05000285/2013405
 
===w/Attachment:===
Supplemental Information
 
cc w/enclosure:
Mr. Dennis A. Bakalar Manager, Site Security Omaha Public Power District


Fort Calhoun Station  
If you contest these violations or the significance of these NCVs, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington DC 20555-0001; with copies to the Regional Administrator, Region IV; the Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington, DC 20555-0001; and the NRC Resident Inspectors at Fort Calhoun Station Seven cross-cutting aspects were assigned to the findings in the area of Human Performance, and two cross-cutting aspects were assigned in the area of Problem Identification and Resolution. Cross-cutting aspects were assigned in the area of Human Performance because your staff failed to: 1) make safety-significant decisions using a systemic process [H1.(a)]; 2)
use conservative assumptions in decision making [H1.(b)]; 3) ensure the availability of complete, accurate, and up-to-date procedures [H.2(c)]; and 4) ensure the availability of adequate equipment [H2.(d)]. Cross-cutting aspects were assigned in the area of Problem Identification and Resolution because your staff failed to thoroughly evaluate problems such that the resolutions address causes and extent of conditions, as necessary [P1.(c)]. If you disagree with a cross-cutting aspect assignment in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the Regional Administrator, Region IV; and the NRC Resident Inspectors at Fort Calhoun Station.


Mail Stop FC-2-1
In accordance with 10 CFR 2.390 of the NRC's "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 Agencywide Document Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).


9610 Power Lane Blair, NE 68008
However, the material enclosed contains Security-Related Information in accordance with 10 CFR 2.390(d)(1) and its disclosure to unauthorized individuals could present a security vulnerability. Therefore, the material in the enclosure will not be made available electronically for public inspection in the NRC Public Document Room or from the PARS component of NRC's ADAMS. If you choose to provide a response and Security-Related Information is necessary to provide an acceptable response, please mark your entire response Security-Related Information - Withhold from public disclosure under 10 CFR 2.390 in accordance with 10 CFR 2.390(d)(1) and follow the instructions for withholding in 10 CFR 2.390(b)(1). In accordance with 10 CFR 2.390(b)(1)(ii), the NRC is waiving the affidavit requirements for your response.


cc w/o enclosure:
Sincerely,
/RA/
Michael C. Hay, Chief Project Branch F Division of Reactor Projects Docket No.: 50-285 License No.: DPR-40 Nonpublic Enclosure:
NRC Inspection Report 05000285/2013405 w/Attachment: Supplemental Information cc w/enclosure:
Mr. Dennis A. Bakalar Manager, Site Security Omaha Public Power District Fort Calhoun Station Mail Stop FC-2-1 9610 Power Lane Blair, NE 68008 cc w/o enclosure:
Electronic Distribution for Fort Calhoun Station
Electronic Distribution for Fort Calhoun Station
}}
}}

Latest revision as of 19:17, 4 November 2019

05000285-13-405-LTR-Non-SGI-JMR-1
ML13115A095
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 04/24/2013
From: Hay M
NRC/RGN-IV/DRP
To: Cortopassi L
Omaha Public Power District
References
IR-13-405
Download: ML13115A095 (4)


Text

UNITE D S TATE S NUC LEAR RE GULATOR Y C OMMI S SI ON ril 24, 2013

SUBJECT:

FORT CALHOUN STATION - NRC IMC 0350 SECURITY INSPECTION REPORT 05000285/2013405

Dear Mr. Cortopassi:

On March 14, 2013, the U.S. Nuclear Regulatory Commission (NRC) completed a supplemental inspection at your Fort Calhoun Station. The enclosed inspection report documents the inspection results, which were discussed on March 14, 2013, with you and other members of your staff.

In accordance with Inspection Manual Chapter (IMC) 0350, Oversight of Reactor Facilities in a Shutdown Condition Due to Significant Performance and/or Operational Concerns, this supplemental inspection was performed to follow-up on performance issues which occurred in the first, second, and third quarter of 2011, and again during the second quarter of 2012. These issues were previously documented and assessed in NRC Inspection Reports 05000285/2011404, 05000285/2011406, and 05000285/2012403.

The objectives of this supplemental inspection were to provide assurance that: (1) the root causes and the contributing causes for the significant issues were understood; (2) the extent of condition and extent of cause of the issues were identified; and (3) corrective actions were or will be sufficient to address and preclude repetition of the root and contributing causes.

During this inspection, the NRC determined that your staff had not performed a comprehensive evaluation of the causes for the Greater-than-Green findings. Specifically, the team identified significant problems with your staffs collective evaluation of the events and the extent of cause reviews. This led the NRC to conclude that the fundamental performance issues within security, and their impact on security processes, have yet to be identified and corrected. Based on these findings, the Greater-than-Green security violations will be held open until adequate causal analyses, extent of cause reviews, and corrective actions are completed by your staff, and are assessed by the NRC during a future inspection.

Additionally, nine NRC identified findings of very low security significance (i.e., Green as determined by the Physical Protection Significance Determination Process) were identified during this inspection. The deficiencies were promptly corrected or compensated for, and the plant was in compliance with applicable physical protection and security requirements within the scope of this inspection before the team left the area.

Nine of these findings were determined to involve violations of NRC requirements. Further, a licensee-identified violation which was determined to be of very low security significance is listed in this report. The NRC is treating these violations as noncited violations (NCVs) consistent with Section 2.3.2.a of the Enforcement Policy.

If you contest these violations or the significance of these NCVs, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington DC 20555-0001; with copies to the Regional Administrator, Region IV; the Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington, DC 20555-0001; and the NRC Resident Inspectors at Fort Calhoun Station Seven cross-cutting aspects were assigned to the findings in the area of Human Performance, and two cross-cutting aspects were assigned in the area of Problem Identification and Resolution. Cross-cutting aspects were assigned in the area of Human Performance because your staff failed to: 1) make safety-significant decisions using a systemic process [H1.(a)]; 2)

use conservative assumptions in decision making [H1.(b)]; 3) ensure the availability of complete, accurate, and up-to-date procedures H.2(c); and 4) ensure the availability of adequate equipment [H2.(d)]. Cross-cutting aspects were assigned in the area of Problem Identification and Resolution because your staff failed to thoroughly evaluate problems such that the resolutions address causes and extent of conditions, as necessary [P1.(c)]. If you disagree with a cross-cutting aspect assignment in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the Regional Administrator, Region IV; and the NRC Resident Inspectors at Fort Calhoun Station.

In accordance with 10 CFR 2.390 of the NRC's "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 Agencywide Document Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

However, the material enclosed contains Security-Related Information in accordance with 10 CFR 2.390(d)(1) and its disclosure to unauthorized individuals could present a security vulnerability. Therefore, the material in the enclosure will not be made available electronically for public inspection in the NRC Public Document Room or from the PARS component of NRC's ADAMS. If you choose to provide a response and Security-Related Information is necessary to provide an acceptable response, please mark your entire response Security-Related Information - Withhold from public disclosure under 10 CFR 2.390 in accordance with 10 CFR 2.390(d)(1) and follow the instructions for withholding in 10 CFR 2.390(b)(1). In accordance with 10 CFR 2.390(b)(1)(ii), the NRC is waiving the affidavit requirements for your response.

Sincerely,

/RA/

Michael C. Hay, Chief Project Branch F Division of Reactor Projects Docket No.: 50-285 License No.: DPR-40 Nonpublic Enclosure:

NRC Inspection Report 05000285/2013405 w/Attachment: Supplemental Information cc w/enclosure:

Mr. Dennis A. Bakalar Manager, Site Security Omaha Public Power District Fort Calhoun Station Mail Stop FC-2-1 9610 Power Lane Blair, NE 68008 cc w/o enclosure:

Electronic Distribution for Fort Calhoun Station