IR 05000247/2013403: Difference between revisions

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| number = ML13262A049
| number = ML13262A049
| issue date = 09/18/2013
| issue date = 09/18/2013
| title = IR 05000247-13-403, 05000286-13-403; 8/5/2013 8/9/2013; Indian Point Energy Center, Units 2 and 3; Access Control and Equipment Performance (Letter Only)
| title = IR 05000247-13-403, 05000286-13-403; 8/5/2013 8/9/2013; Indian Point Energy Center, Units 2 and 3; Access Control and Equipment Performance (Letter Only)
| author name = Dimitriadis A
| author name = Dimitriadis A
| author affiliation = NRC/RGN-I/DRS/PSB1
| author affiliation = NRC/RGN-I/DRS/PSB1
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==Dear Mr. Ventosa:==
==Dear Mr. Ventosa:==
On August 9, 2013, the U.S. Nuclear Regulatory Commission (NRC) completed a security inspection at your Indian Point Energy Center, Units 2 and 3. The inspection covered one or more of the key attributes of the security cornerstone of the NRC's Reactor Oversight Process.
On August 9, 2013, the U.S. Nuclear Regulatory Commission (NRC) completed a security inspection at your Indian Point Energy Center, Units 2 and 3. The inspection covered one or more of the key attributes of the security cornerstone of the NRCs Reactor Oversight Process.


The enclosed inspection report documents the inspection results which were discussed on August 9, 2013, with Mr. Patric Conroy, Nuclear Safety Assurance Director, and other members  
The enclosed inspection report documents the inspection results which were discussed on August 9, 2013, with Mr. Patric Conroy, Nuclear Safety Assurance Director, and other members of your staff.


of your staff.
The inspection examined activities conducted under your licenses as they relate to security and compliance with the Commissions rules and regulations and with the conditions of your licenses. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.


The inspection examined activities conducted under your licenses as they relate to security and compliance with the Commission's rules and regulations and with the conditions of your licenses. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.
Three NRC identified findings of very low significance (i.e., Green as determined by the Baseline Security Significance Determination Process) were identified during this inspection.


Three NRC identified findings of very low significance (i.e., Green as determined by the Baseline Security 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 inspectors left site.
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 inspectors left site.


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 the  
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 the report. The NRC is treating this violation as a non-cited violation (NCV) consistent with section 2.3.2 of the Enforcement Policy.
 
report. The NRC is treating this violation as a non-cited violation (NCV) consistent with section 2.3.2 of the Enforcement Policy.


Enclosure contains Sensitive Unclassified Non-Safeguards Information. When separated from enclosure, the transmittal document is decontrolled. 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 U.S.
Enclosure contains Sensitive Unclassified Non-Safeguards Information. When separated from enclosure, the transmittal document is decontrolled. 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 U.S.
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Cross-cutting aspects were assigned in the area of Human Performance because the licensee failed to follow procedures [H.4(b)] and failed to use conservative assumptions in decision making and adopt a requirement to demonstrate that the proposed action was safe in order to proceed rather than a requirement to demonstrate that it was unsafe in order to disapprove the action [H.1(b)]. A cross-cutting aspect was assigned in the area of Problem Identification and Resolution because the licensee failed to implement a corrective action program with a low threshold for identifying issues completely, accurately, and in a timely manner commensurate with their security significance [P.1(a)]. 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 I; and the NRC Resident Inspectors at the Indian Point Energy Center, Units 2 and 3.
Cross-cutting aspects were assigned in the area of Human Performance because the licensee failed to follow procedures [H.4(b)] and failed to use conservative assumptions in decision making and adopt a requirement to demonstrate that the proposed action was safe in order to proceed rather than a requirement to demonstrate that it was unsafe in order to disapprove the action [H.1(b)]. A cross-cutting aspect was assigned in the area of Problem Identification and Resolution because the licensee failed to implement a corrective action program with a low threshold for identifying issues completely, accurately, and in a timely manner commensurate with their security significance [P.1(a)]. 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 I; and the NRC Resident Inspectors at the Indian Point Energy Center, Units 2 and 3.


In accordance with Title 10 of the Code of Federal Regulations (10 CFR) Part 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).
In accordance with Title 10 of the Code of Federal Regulations (10 CFR) Part 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).


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 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
ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).


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 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,
Sincerely,
/RA/ Anthony Dimitriadis, Chief Plant Support Branch 1 Division of Reactor Safety Docket Nos. 50-247, 50-286 License Nos. DPR-26, DPR-64
/RA/  


Nonpublic Enclosure:
Anthony Dimitriadis, Chief
Inspection Reports 05000247/2013403 and 05000286/2013403 w/Attachment: Supplemental Information (OUO-SRI)
cc w/o encl; OUO-SRI: Distribution via ListServ cc w/encl; OUO-SRI D. Gagnon, Site Security Manager J. Hauer, Commissioner, NY State Div. of Homeland Security and Emergency Services F. Murray, President and CEO, NY State Energy Research and Development Authority 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 U.S.


Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region I; the Director, Office of Enforcement, U.S. Nuclear Regulatory Commission, Washington, DC 20555-001; and the NRC Resident Inspectors at the Indian Point Energy Center.
Plant Support Branch 1


Two cross-cutting aspects were assigned to the findings in the areas of Human Performance and one cross-cutting aspect was assigned in the area of Problem Identification and Resolution. Cross-cutting aspects were assigned in the area of Human Performance because the licensee failed to follow procedures [H.4(b)] and failed to use conservative assumptions in decision making and adopt a requirement to demonstrate that the proposed action was safe in order to proceed rather than a requirement to demonstrate that it was unsafe in order to disapprove the action [H.1(b)]. A cross-cutting aspect was assigned in the area of Problem Identification and Resolution because the licensee failed to implement a corrective action program with a low threshold for identifying issues completely, accurately, and in a timely manner commensurate with their security significance [P.1(a)]. 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 I; and the NRC Resident Inspectors at the Indian Point Energy Center.
Division of Reactor Safety Docket Nos. 50-247, 50-286 License Nos. DPR-26, DPR-64


In accordance with Title 10 of the Code of Federal Regulations (10 CFR) Part 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).
Nonpublic Enclosure:
 
Inspection Reports 05000247/2013403 and  
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 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/
Anthony Dimitriadis, Chief Plant Support Branch 1 Division of Reactor SafetyDistribution: See Next Page Non-Public Designation Category: MD 3.4 Non-Public A.3 DOCUMENT NAME: G:\DRS\Plant Support Branch 1\Security\2013 IR Draft\IPEC\IPEC 2 4 7 PI 2013-403 Rev 11.docx ADAMS ACCESSION NO.: ML13262A049 (Cover ltr)  ADAMS ACCESSION NO.: ML13262A052 (Cover ltr w/encl)
Cover Letter SUNSI Review Non-Sensitive Sensitive Publicly Available Non-Publicly Available Cover Letter w/Enclosure SUNSI Review Non-Sensitive Sensitive Publicly Available Non-Publicly Available OFFICE RI/DRS RI/DRS RI/DRS RI/DRP RI/DRS NAME JBream/DCC JCherubini/TD DCaron ABurritt ADimitriadis DATE 09/16/13 09/14/13 09/09/13 09/13/13 09/18/13        OFFICIAL RECORD CO PY Distribution w/o encl; w/o OUO-SRI: W. Dean, RA (R1ORAMAIL RESOURCE)
D. Lew, DRA (R1ORAMAIL RESOURCE) D. Roberts, DRP (R1DRPMAIL RESOURCE)
M. Scott, DRP (R1DRPMAIL RESOURCE) R. Lorson, DRS (R1DRSMAIL RESOURCE)
J. Rogge, DRS (R1DRSMAIL RESOURCE)
A. Burritt, DRP


T. Setzer, DRP S. McCarver, DRP L. McKown, DRP S. Stewart, DRP, SRI K. Dunham, DRP, RI Ami Patel, DRP, RI D. Hochmuth, DRP, AA V. Campbell, RI OEDO RidsNrrPMIndianPoint Resource RidsNrrDorlLpl1-1 Resource ROPReports Resources
05000286/2013403 w/Attachment: Supplemental Information (OUO-SRI)


Distribution w/encl; w/OUO-SRI R. Albert, NSIR S. Coker, NSIR C. Johnson, NSIR B. Desai, DRS, RII
cc w/o encl; OUO-SRI: Distribution via ListServ


R. Skokowski, DRS, RIII M. Haire, DRS, RIV
cc w/encl; OUO-SRI D. Gagnon, Site Security Manager J. Hauer, Commissioner, NY State Div. of Homeland Security and Emergency Services F. Murray, President and CEO, NY State Energy Research and Development Authority
}}
}}

Latest revision as of 05:28, 11 January 2025

IR 05000247-13-403, 05000286-13-403; 8/5/2013 8/9/2013; Indian Point Energy Center, Units 2 and 3; Access Control and Equipment Performance (Letter Only)
ML13262A049
Person / Time
Site: Indian Point  Entergy icon.png
Issue date: 09/18/2013
From: Anthony Dimitriadis
Plant Support Branch 1
To: Ventosa J
Entergy Nuclear Operations
References
IR-13-403
Download: ML13262A049 (5)


Text

September 18, 2013

SUBJECT:

INDIAN POINT ENERGY CENTER, UNITS 2 AND 3 - NRC SECURITY INSPECTION REPORT 05000247/2013403 AND 05000286/2013403)

Dear Mr. Ventosa:

On August 9, 2013, the U.S. Nuclear Regulatory Commission (NRC) completed a security inspection at your Indian Point Energy Center, Units 2 and 3. The inspection covered one or more of the key attributes of the security cornerstone of the NRCs Reactor Oversight Process.

The enclosed inspection report documents the inspection results which were discussed on August 9, 2013, with Mr. Patric Conroy, Nuclear Safety Assurance Director, and other members of your staff.

The inspection examined activities conducted under your licenses as they relate to security and compliance with the Commissions rules and regulations and with the conditions of your licenses. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.

Three NRC identified findings of very low significance (i.e., Green as determined by the Baseline Security 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 inspectors left site.

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 the report. The NRC is treating this violation as a non-cited violation (NCV) consistent with section 2.3.2 of the Enforcement Policy.

Enclosure contains Sensitive Unclassified Non-Safeguards Information. When separated from enclosure, the transmittal document is decontrolled. 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 U.S.

Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region I; the Director, Office of Enforcement, U.S.

Nuclear Regulatory Commission, Washington, DC 20555-001; and the NRC Resident Inspectors at the Indian Point Energy Center, Units 2 and 3.

Two cross-cutting aspects were assigned to the findings in the areas of Human Performance and one cross-cutting aspect was assigned in the area of Problem Identification and Resolution.

Cross-cutting aspects were assigned in the area of Human Performance because the licensee failed to follow procedures H.4(b) and failed to use conservative assumptions in decision making and adopt a requirement to demonstrate that the proposed action was safe in order to proceed rather than a requirement to demonstrate that it was unsafe in order to disapprove the action H.1(b). A cross-cutting aspect was assigned in the area of Problem Identification and Resolution because the licensee failed to implement a corrective action program with a low threshold for identifying issues completely, accurately, and in a timely manner commensurate with their security significance P.1(a). 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 I; and the NRC Resident Inspectors at the Indian Point Energy Center, Units 2 and 3.

In accordance with Title 10 of the Code of Federal Regulations (10 CFR) Part 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 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 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/

Anthony Dimitriadis, Chief

Plant Support Branch 1

Division of Reactor Safety Docket Nos. 50-247, 50-286 License Nos. DPR-26, DPR-64

Nonpublic Enclosure:

Inspection Reports 05000247/2013403 and

05000286/2013403 w/Attachment: Supplemental Information (OUO-SRI)

cc w/o encl; OUO-SRI: Distribution via ListServ

cc w/encl; OUO-SRI D. Gagnon, Site Security Manager J. Hauer, Commissioner, NY State Div. of Homeland Security and Emergency Services F. Murray, President and CEO, NY State Energy Research and Development Authority