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=Text=
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{{#Wiki_filter:December 23, 2015
{{#Wiki_filter:ber 23, 2015


==SUBJECT:==
==SUBJECT:==
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==Dear Mr. Flores:==
==Dear Mr. Flores:==
On March 19, 2014, your staff determined that they had failed to meet a requirement or standard on approximately March 3, 2008. On August 29, 2014, the NRC completed a focused inspection at your Comanche Peak Nuclear Power Plant facility. Based on the results of this inspection, documented in NRC Inspection Report 05000445/2014404 and 05000446/2014404 (ADAMS Accession Number ML15065A211), dated March 6, 2015, and the final significance determination, documented in Inspection Report 05000445/2015406 and 05000446/2 015406, dated April 28, 2015 (ML15118A623), the NRC assigned a finding Action Matrix input to the Security cornerstone in the third quarter of 2014 for a Greater-than-Green security-related finding. In response to this Action Matrix input, the NRC informed you that a supplemental inspection would be required. On July 28, 2015, you informed the NRC that the station was ready for the supplemental inspection.
On March 19, 2014, your staff determined that they had failed to meet a requirement or standard on approximately March 3, 2008. On August 29, 2014, the NRC completed a focused inspection at your Comanche Peak Nuclear Power Plant facility. Based on the results of this inspection, documented in NRC Inspection Report 05000445/2014404 and 05000446/2014404 (ADAMS Accession Number ML15065A211), dated March 6, 2015, and the final significance determination, documented in Inspection Report 05000445/2015406 and 05000446/2015406, dated April 28, 2015 (ML15118A623), the NRC assigned a finding Action Matrix input to the Security cornerstone in the third quarter of 2014 for a Greater-than-Green security-related finding. In response to this Action Matrix input, the NRC informed you that a supplemental inspection would be required. On July 28, 2015, you informed the NRC that the station was ready for the supplemental inspection.


On December 8, 2015, the U.S. Nuclear Regulatory Commission (NRC) completed a supplemental inspection at the Comanche Peak Nuclear Power Plant, Units 1 and 2. The NRC inspector discussed the results of this inspection with Mr. K. Peters, Site Vice President, and other members of your staff. The results of this inspection are documented in the enclosed inspection report. The NRC documented two examples of one finding of very low security significance (Green) in this report. This finding involved a violation of NRC requirements. The NRC is treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2.a of the Enforcement Policy. If you contest the violation or the significance of this NCV, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region IV; and the Director, Office of Enforcement, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001.
On December 8, 2015, the U.S. Nuclear Regulatory Commission (NRC) completed a supplemental inspection at the Comanche Peak Nuclear Power Plant, Units 1 and 2. The NRC inspector discussed the results of this inspection with Mr. K. Peters, Site Vice President, and other members of your staff. The results of this inspection are documented in the enclosed inspection report. The NRC documented two examples of one finding of very low security significance (Green) in this report. This finding involved a violation of NRC requirements. The NRC is treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2.a of the Enforcement Policy. If you contest the violation or the significance of this NCV, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region IV; and the Director, Office of Enforcement, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001. 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 a basis for your disagreement, to the Regional Administrator, Region IV, and the NRC Resident Inspector at your facility.


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 a basis for your disagreement, to the Regional Administrator, Region IV, and the NRC Resident Inspector at your facility.
Based on this supplemental inspection, the NRC closed the Greater-than-Green finding that had been documented in Inspection Report 05000445/2015406 and 05000446/2015406, dated April 28, 2015 (ML15118A623), on December 8, 2015. The finding was being held open pending completion of a supplemental inspection and effective corrective actions.


Based on this supplemental inspection, the NRC closed the Greater-than-Green finding that had been documented in Inspection Report 05000445/2015406 and 05000446/2015406, dated April 28, 2015 (ML15118A623), on December 8, 2015. The finding was being held open pending completion of a supplemental inspection and effective corrective actions.
The NRC performed this supplemental inspection to determine if (1) the root and contributing causes for the significant issues were understood, (2) the extent of condition and extent of cause for the identified issues were understood, and (3) your completed or planned corrective actions were sufficient to address and prevent repetition of the root and contributing causes.


The NRC performed this supplemental inspection to determine if (1) the root and contributing causes for the significant issues were understoo d, (2) the extent of condition and extent of cause for the identified issues were understood, and (3) your completed or planned corrective actions were sufficient to address and prevent repetition of the root and contributing causes. As a result, the NRC determined the performance at the Comanche Peak Nuclear Power Plant, Units 1 and 2, to be in the Licensee Response Column of the Reactor Oversight Process Action Matrix as of the date of this letter. However, the finding will still be considered for agency actions in accordance with the Action Matrix until December 31, 2015.
As a result, the NRC determined the performance at the Comanche Peak Nuclear Power Plant, Units 1 and 2, to be in the Licensee Response Column of the Reactor Oversight Process Action Matrix as of the date of this letter. However, the finding will still be considered for agency actions in accordance with the Action Matrix until December 31, 2015.


In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, "Public Inspections, Exemptions, Requests for Withholding," of the NRC's "Rules of Practice and Procedure," a copy of this letter will be available electronically for public inspection in the NRC's Public Document Room or from the Publicly Available Records (PARS) component of the 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).
In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, Public Inspections, Exemptions, Requests for Withholding, of the NRCs Rules of Practice and Procedure, a copy of this letter will be available electronically for public inspection in the NRCs Public Document Room or from the Publicly Available Records (PARS) component of the NRCs 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).


However, the material enclosed herewith 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 res ponse and Safeguards Information is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21. Otherwise, if Security-Related Information is necessary to provide an acceptable response, please mark your entire re sponse "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.
However, the material enclosed herewith 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 NRCs ADAMS. If you choose to provide a response and Safeguards Information is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21. Otherwise, if 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,
Sincerely,
/RA/ Jeffrey A. Clark for  
/RA/ Jeffrey A. Clark for Anton Vegel Director, Division of Reactor Safety Docket Nos. 50-445 and 50-446 License Nos. NPF-87 and NPF-89 Nonpublic Enclosure:
 
Anton Vegel Director, Division of Reactor Safety  
 
Docket Nos. 50-445 and 50-446 License Nos. NPF-87 and NPF-89  
 
Nonpublic Enclosure:
Inspection Report 05000445/2015408; 05000446/2015408 w/Attachment:
Inspection Report 05000445/2015408; 05000446/2015408 w/Attachment:
Supplemental Information  
Supplemental Information cc w/o encl: Electronic Distribution for Comanche Peak
 
cc w/o encl: Electronic Distribution for Comanche Peak
}}
}}

Latest revision as of 02:43, 31 October 2019

NRC Supplemental Inspection Report and Assessment Follow-Up Letter for 05000445/2015408 and 05000446/2015408
ML15358A060
Person / Time
Site: Comanche Peak  Luminant icon.png
Issue date: 12/23/2015
From: Anton Vegel
Division of Reactor Safety IV
To: Flores R
Luminant Generation Co
References
EA-14-234 IR 2015408
Download: ML15358A060 (5)
v • d • e


Text

ber 23, 2015

SUBJECT:

COMANCHE PEAK NUCLEAR POWER PLANT - NRC SUPPLEMENTAL INSPECTION REPORT AND ASSESSMENT FOLLOW-UP LETTER FOR 05000445/2015408 AND 05000446/2015408

Dear Mr. Flores:

On March 19, 2014, your staff determined that they had failed to meet a requirement or standard on approximately March 3, 2008. On August 29, 2014, the NRC completed a focused inspection at your Comanche Peak Nuclear Power Plant facility. Based on the results of this inspection, documented in NRC Inspection Report 05000445/2014404 and 05000446/2014404 (ADAMS Accession Number ML15065A211), dated March 6, 2015, and the final significance determination, documented in Inspection Report 05000445/2015406 and 05000446/2015406, dated April 28, 2015 (ML15118A623), the NRC assigned a finding Action Matrix input to the Security cornerstone in the third quarter of 2014 for a Greater-than-Green security-related finding. In response to this Action Matrix input, the NRC informed you that a supplemental inspection would be required. On July 28, 2015, you informed the NRC that the station was ready for the supplemental inspection.

On December 8, 2015, the U.S. Nuclear Regulatory Commission (NRC) completed a supplemental inspection at the Comanche Peak Nuclear Power Plant, Units 1 and 2. The NRC inspector discussed the results of this inspection with Mr. K. Peters, Site Vice President, and other members of your staff. The results of this inspection are documented in the enclosed inspection report. The NRC documented two examples of one finding of very low security significance (Green) in this report. This finding involved a violation of NRC requirements. The NRC is treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2.a of the Enforcement Policy. If you contest the violation or the significance of this NCV, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region IV; and the Director, Office of Enforcement, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001. 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 a basis for your disagreement, to the Regional Administrator, Region IV, and the NRC Resident Inspector at your facility.

Based on this supplemental inspection, the NRC closed the Greater-than-Green finding that had been documented in Inspection Report 05000445/2015406 and 05000446/2015406, dated April 28, 2015 (ML15118A623), on December 8, 2015. The finding was being held open pending completion of a supplemental inspection and effective corrective actions.

The NRC performed this supplemental inspection to determine if (1) the root and contributing causes for the significant issues were understood, (2) the extent of condition and extent of cause for the identified issues were understood, and (3) your completed or planned corrective actions were sufficient to address and prevent repetition of the root and contributing causes.

As a result, the NRC determined the performance at the Comanche Peak Nuclear Power Plant, Units 1 and 2, to be in the Licensee Response Column of the Reactor Oversight Process Action Matrix as of the date of this letter. However, the finding will still be considered for agency actions in accordance with the Action Matrix until December 31, 2015.

In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, Public Inspections, Exemptions, Requests for Withholding, of the NRCs Rules of Practice and Procedure, a copy of this letter will be available electronically for public inspection in the NRCs Public Document Room or from the Publicly Available Records (PARS) component of the NRCs 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).

However, the material enclosed herewith 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 NRCs ADAMS. If you choose to provide a response and Safeguards Information is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21. Otherwise, if 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/ Jeffrey A. Clark for Anton Vegel Director, Division of Reactor Safety Docket Nos. 50-445 and 50-446 License Nos. NPF-87 and NPF-89 Nonpublic Enclosure:

Inspection Report 05000445/2015408; 05000446/2015408 w/Attachment:

Supplemental Information cc w/o encl: Electronic Distribution for Comanche Peak

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