IR 05000285/2006401: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
 
Line 19: Line 19:


=Text=
=Text=
{{#Wiki_filter:December 8, 2006EA-06-163R. T. RidenoureVice President Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.
{{#Wiki_filter:ber 8, 2006


P.O. Box 550 Fort Calhoun, NE 68023-0550SUBJECT:FORT CALHOUN STATION - NRC SUPPLEMENTAL INSPECTIONREPORT 05000285/2006401
==SUBJECT:==
FORT CALHOUN STATION - NRC SUPPLEMENTAL INSPECTION REPORT 05000285/2006401


==Dear Mr. Ridenoure:==
==Dear Mr. Ridenoure:==
On November 1, 2006, the US Nuclear Regulatory Commission (NRC) completed asupplemental inspection pursuant to Inspection Procedure 95001 at your Fort Calhoun Station to follow up on previous security inspection findings. The enclosed report presents the results of this inspection, which were discussed with Mr. Jeff Reinhart, Site Director, and other members of your staff on November 1, 2006. The NRC was informed of your readiness for the inspection on October 26, 2006. NRC performed the inspection to verify the adequacy of the root cause analysis and correctiveactions implemented in response to a finding of greater than green security significance, as documented in NRC Inspection Report 05000285/2006015. This supplemental inspection was conducted to provide assurance that the root causes and contributing causes of the greater than green finding were understood, to independently assess the extent of the condition and cause, and to provide assurance that the corrective actions to security significant performance issues were sufficient to address the root causes and contributing causes, and prevent recurrence. To accomplish these objectives, the inspector reviewed your root cause analysis and evaluation of extent of condition and conducted an independent inspection to verify or refute your conclusions.This inspection examined activities conducted under your license as they relate to public health Fort Calhoun Station-2 and safety, the common defense and security, and to compliance with the Commission's rulesand regulations, orders, and with the conditions of your license. Within these areas, the inspection consisted of selected examination of procedures and representative records, observations of activities, and interviews with personnel.Based on the results of this inspection no findings of significance were identified.
On November 1, 2006, the US Nuclear Regulatory Commission (NRC) completed a supplemental inspection pursuant to Inspection Procedure 95001 at your Fort Calhoun Station to follow up on previous security inspection findings. The enclosed report presents the results of this inspection, which were discussed with Mr. Jeff Reinhart, Site Director, and other members of your staff on November 1, 2006. The NRC was informed of your readiness for the inspection on October 26, 2006.


In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter will beavailable electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of the NRC's document system, ADAMS.
NRC performed the inspection to verify the adequacy of the root cause analysis and corrective actions implemented in response to a finding of greater than green security significance, as documented in NRC Inspection Report 05000285/2006015. This supplemental inspection was conducted to provide assurance that the root causes and contributing causes of the greater than green finding were understood, to independently assess the extent of the condition and cause, and to provide assurance that the corrective actions to security significant performance issues were sufficient to address the root causes and contributing causes, and prevent recurrence. To accomplish these objectives, the inspector reviewed your root cause analysis and evaluation of extent of condition and conducted an independent inspection to verify or refute your conclusions.


ADAMS is accessible from the NRC Website at http://WWW.nrc.gov/reading-rm/adams.html(the Public Electronic Reading Room). However, because of the security-related concernscontained in the enclosure, and in accordance with 10 CFR 2.390, a copy of this letter's enclosure will not be available for public inspection. In accordance with 10 CFR 2.390(b)(1)(ii), the NRC is waiving the affidavit requirements foryour response, if any. This practice will ensure that your response will not be made availableelectronically for public inspection in the NRC Public Document Room or from the NRC's document system, ADAMS. If Safeguards Information is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21. Otherwise, mark your entire response "Security-Related Information-Withhold under 10 CFR 2.390" and follow the instructions for withholding in 10 CFR 2.390(b)(1).
This inspection examined activities conducted under your license as they relate to public health Fort Calhoun Station  -2-and safety, the common defense and security, and to compliance with the Commissions rules and regulations, orders, and with the conditions of your license. Within these areas, the inspection consisted of selected examination of procedures and representative records, observations of activities, and interviews with personnel.
 
Based on the results of this inspection no findings of significance were identified.
 
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 the NRC's document system, ADAMS.
 
ADAMS is accessible from the NRC Website at http://WWW.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). However, because of the security-related concerns contained in the enclosure, and in accordance with 10 CFR 2.390, a copy of this letter's enclosure will not be available for public inspection.
 
In accordance with 10 CFR 2.390(b)(1)(ii), the NRC is waiving the affidavit requirements for your response, if any. This practice will ensure that your response will not be made available electronically for public inspection in the NRC Public Document Room or from the NRC's document system, ADAMS. If Safeguards Information is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21. Otherwise, mark your entire response "Security-Related Information-Withhold under 10 CFR 2.390" and follow the instructions for withholding in 10 CFR 2.390(b)(1).


Sincerely,
Sincerely,
/RA/ RJC1 for Dwight D. Chamberlain, DirectorDivision of Reactor SafetyDocket No.: 50-285License No.: DPR-40 Enclosure: Inspection Report 05000285/2006-401w/Attachment: Supplemental Information Fort Calhoun Station-3 cc w/o enclosure:Joe l. McManis, Manager - Licensing Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.
/RA/ RJC1 for Dwight D. Chamberlain, Director Division of Reactor Safety Docket No.: 50-285 License No.: DPR-40 Enclosure: Inspection Report 05000285/2006-401 w/Attachment: Supplemental Information Fort Calhoun Station -3-cc w/o enclosure:
Joe l. McManis, Manager - Licensing Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.


P.O. Box 550 Fort Calhoun, NE 68023-0550David J. BannisterManager - Fort Calhoun Station Omaha Public Power District Fort Calhoun Station FC-1-1 Plant P.O. Box 550 Fort Calhoun, NE 68023-0550
P.O. Box 550 Fort Calhoun, NE 68023-0550 David J. Bannister Manager - Fort Calhoun Station Omaha Public Power District Fort Calhoun Station FC-1-1 Plant P.O. Box 550 Fort Calhoun, NE 68023-0550
}}
}}

Latest revision as of 11:26, 23 November 2019

IR 05000285-06-401, - Fort Calhoun Station - NRC Supplemental Inspection Report
ML063450264
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 12/08/2006
From: Chamberlain D
Division of Reactor Safety IV
To: Ridenoure R
Omaha Public Power District
References
EA-06-163 IR-06-401
Download: ML063450264 (3)


Text

ber 8, 2006

SUBJECT:

FORT CALHOUN STATION - NRC SUPPLEMENTAL INSPECTION REPORT 05000285/2006401

Dear Mr. Ridenoure:

On November 1, 2006, the US Nuclear Regulatory Commission (NRC) completed a supplemental inspection pursuant to Inspection Procedure 95001 at your Fort Calhoun Station to follow up on previous security inspection findings. The enclosed report presents the results of this inspection, which were discussed with Mr. Jeff Reinhart, Site Director, and other members of your staff on November 1, 2006. The NRC was informed of your readiness for the inspection on October 26, 2006.

NRC performed the inspection to verify the adequacy of the root cause analysis and corrective actions implemented in response to a finding of greater than green security significance, as documented in NRC Inspection Report 05000285/2006015. This supplemental inspection was conducted to provide assurance that the root causes and contributing causes of the greater than green finding were understood, to independently assess the extent of the condition and cause, and to provide assurance that the corrective actions to security significant performance issues were sufficient to address the root causes and contributing causes, and prevent recurrence. To accomplish these objectives, the inspector reviewed your root cause analysis and evaluation of extent of condition and conducted an independent inspection to verify or refute your conclusions.

This inspection examined activities conducted under your license as they relate to public health Fort Calhoun Station -2-and safety, the common defense and security, and to compliance with the Commissions rules and regulations, orders, and with the conditions of your license. Within these areas, the inspection consisted of selected examination of procedures and representative records, observations of activities, and interviews with personnel.

Based on the results of this inspection no findings of significance were identified.

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 the NRC's document system, ADAMS.

ADAMS is accessible from the NRC Website at http://WWW.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). However, because of the security-related concerns contained in the enclosure, and in accordance with 10 CFR 2.390, a copy of this letter's enclosure will not be available for public inspection.

In accordance with 10 CFR 2.390(b)(1)(ii), the NRC is waiving the affidavit requirements for your response, if any. This practice will ensure that your response will not be made available electronically for public inspection in the NRC Public Document Room or from the NRC's document system, ADAMS. If Safeguards Information is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21. Otherwise, mark your entire response "Security-Related Information-Withhold under 10 CFR 2.390" and follow the instructions for withholding in 10 CFR 2.390(b)(1).

Sincerely,

/RA/ RJC1 for Dwight D. Chamberlain, Director Division of Reactor Safety Docket No.: 50-285 License No.: DPR-40 Enclosure: Inspection Report 05000285/2006-401 w/Attachment: Supplemental Information Fort Calhoun Station -3-cc w/o enclosure:

Joe l. McManis, Manager - Licensing Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.

P.O. Box 550 Fort Calhoun, NE 68023-0550 David J. Bannister Manager - Fort Calhoun Station Omaha Public Power District Fort Calhoun Station FC-1-1 Plant P.O. Box 550 Fort Calhoun, NE 68023-0550