IR 05000247/2008006: Difference between revisions

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[[Issue date::August 1, 2008]]
[[Issue date::August 1, 2008]]


Mr. Joseph Pollock Site Vice President Entergy Nuclear Operations, Inc. Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249
Mr. Joseph Pollock  
 
Site Vice President Entergy Nuclear Operations, Inc. Indian Point Energy Center  
 
450 Broadway, GSB P.O. Box 249  
 
Buchanan, NY 10511-0249


SUBJECT: INDIAN POINT NUCLEAR GENERATING UNITS 2 AND 3 - NRC LICENSE RENEWAL INSPECTION REPORT 05000247/2008006 & 05000286/2008006
SUBJECT: INDIAN POINT NUCLEAR GENERATING UNITS 2 AND 3 - NRC LICENSE RENEWAL INSPECTION REPORT 05000247/2008006 & 05000286/2008006
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The purpose of this inspection was to examine, on a sampling basis, the plant activities and documents that support the application for a renewed license of the Indian Point Nuclear Generating Unit Nos. 2 and 3. The inspection team reviewed the scoping of nonsafety-related systems, structures, and components, as required in 10 CFR 54.4(a)(2). Further, the team determined whether the proposed aging management programs are capable of reasonably managing the effects of aging. These NRC inspection activities constitute one of several inputs into the NRC review process for license renewal applications.
The purpose of this inspection was to examine, on a sampling basis, the plant activities and documents that support the application for a renewed license of the Indian Point Nuclear Generating Unit Nos. 2 and 3. The inspection team reviewed the scoping of nonsafety-related systems, structures, and components, as required in 10 CFR 54.4(a)(2). Further, the team determined whether the proposed aging management programs are capable of reasonably managing the effects of aging. These NRC inspection activities constitute one of several inputs into the NRC review process for license renewal applications.


The team concluded that the scoping of nonsafety-related systems, structures, and components was implemented as required in 10 CFR 54.4(a)(2). Further, the team concluded that the aging management portion of the license renewal activities was conducted as described in the License Renewal Application. The team concluded that the documentation supporting the application was in an auditable and retrievable form. The team identified a number of areas that resulted in changes to the application. Overall, the inspection results support a conclusion of reasonable assurance that actions have been identified and have been taken or will be taken to manage the effects of aging in the systems, structures, and components identified in your application and that the intended functions of these systems, structures, and components will be maintained in the period of extended operation.NRC000107 Submitted: March 31, 2012 United States Nuclear Regulatory Commission Official Hearing Exhibit In the Matter of: Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating Units 2 and 3) ASLBP #:07-858-03-LR-BD01 Docket #:05000247 l 05000286 Exhibit #: Identified: Admitted: Withdrawn: Rejected: Stricken: Other: NRC000107-00-BD0110/15/201210/15/2012 In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure 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 Website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
The team concluded that the scoping of nonsafety-related systems, structures, and components was implemented as required in 10 CFR 54.4(a)(2). Further, the team concluded that the aging management portion of the license renewal activities was conducted as described in the License Renewal Application. The team concluded that the documentation supporting the application was in an auditable and retrievable form. The team identified a number of areas that resulted in changes to the application.
 
Overall, the inspection results support a conclusion of reasonable assurance that actions have been identified and have been taken or will be taken to manage the effects of aging in the systems, structures, and components identified in your application and that the intended functions of these systems, structures, and components will be maintained in the period of  
 
extended operation.
 
NRC000107 Submitted: March 31, 2012 United States Nuclear Regulatory Commission Official Hearing Exhibit In the Matter of
: Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating Units 2 and 3)
ASLBP #:07-858-03-LR-BD01 Docket #:05000247 l 05000286 Exhibit #:
Identified:
Admitted: Withdrawn:
Rejected: Stricken: Other: NRC000107-00-BD01 10/15/2012 10/15/2012 In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure 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 Website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
 
Sincerely,/RA/ Richard J. Conte, Chief Engineering Branch 1


Sincerely,/RA/ Richard J. Conte, Chief Engineering Branch 1 Division of Reactor Safety Docket Nos. 50-247 and 50-286 License Nos. DPR-26 and DPR-64  
Division of Reactor Safety Docket Nos. 50-247 and 50-286 License Nos. DPR-26 and DPR-64  


===Enclosure:===
===Enclosure:===
Inspection Report 05000247/2008006 and 05000286/2008006
Inspection Report 05000247/2008006 and 05000286/2008006
}}
}}

Revision as of 16:46, 22 July 2018

Official Exhibit - NRC000107-00-BD01 - Indian Point Nuclear Generating Units 2 and 3 - NRC License Renewal Inspection Report 05000247/2008006 & 05000286/2008006
ML12339A679
Person / Time
Site: Indian Point  Entergy icon.png
Issue date: 03/31/2012
From: Conte R J
Engineering Region 1 Branch 1
To: Joseph E Pollock
Entergy Nuclear Operations, Atomic Safety and Licensing Board Panel
SECY RAS
References
RAS 22176, 50-247-LR, 50-286-LR, ASLBP 07-858-03-LR-BD01 IR-08-006
Download: ML12339A679 (43)
v • d • e


Text

August 1, 2008

Mr. Joseph Pollock

Site Vice President Entergy Nuclear Operations, Inc. Indian Point Energy Center

450 Broadway, GSB P.O. Box 249

Buchanan, NY 10511-0249

SUBJECT: INDIAN POINT NUCLEAR GENERATING UNITS 2 AND 3 - NRC LICENSE RENEWAL INSPECTION REPORT 05000247/2008006 & 05000286/2008006

Dear Mr. Pollock:

On February 14, 2008, the U.S. Nuclear Regulatory Commission (NRC) completed the major onsite portion of the Region I team inspection of your application for license renewal of your Indian Point Nuclear Generating Unit Nos. 2 and 3, with additional followup inspections through June 6, 2008. The enclosed report documents the results of the inspection, which were discussed on June 18, 2008, with you, Fred Dacimo, and members of your staff in an exit meeting open for public observation in Cortlandt Manor, NY.

The purpose of this inspection was to examine, on a sampling basis, the plant activities and documents that support the application for a renewed license of the Indian Point Nuclear Generating Unit Nos. 2 and 3. The inspection team reviewed the scoping of nonsafety-related systems, structures, and components, as required in 10 CFR 54.4(a)(2). Further, the team determined whether the proposed aging management programs are capable of reasonably managing the effects of aging. These NRC inspection activities constitute one of several inputs into the NRC review process for license renewal applications.

The team concluded that the scoping of nonsafety-related systems, structures, and components was implemented as required in 10 CFR 54.4(a)(2). Further, the team concluded that the aging management portion of the license renewal activities was conducted as described in the License Renewal Application. The team concluded that the documentation supporting the application was in an auditable and retrievable form. The team identified a number of areas that resulted in changes to the application.

Overall, the inspection results support a conclusion of reasonable assurance that actions have been identified and have been taken or will be taken to manage the effects of aging in the systems, structures, and components identified in your application and that the intended functions of these systems, structures, and components will be maintained in the period of

extended operation.

NRC000107 Submitted: March 31, 2012 United States Nuclear Regulatory Commission Official Hearing Exhibit In the Matter of

Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating Units 2 and 3)

ASLBP #:07-858-03-LR-BD01 Docket #:05000247 l 05000286 Exhibit #:

Identified:

Admitted: Withdrawn:

Rejected: Stricken: Other: NRC000107-00-BD01 10/15/2012 10/15/2012 In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure 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 Website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Sincerely,/RA/ Richard J. Conte, Chief Engineering Branch 1

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

Enclosure:

Inspection Report 05000247/2008006 and 05000286/2008006

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