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| {{Adams | | {{Adams |
| | number = ML12339A679 | | | number = ML12091A049 |
| | issue date = 03/31/2012 | | | issue date = 03/31/2012 |
| | title = Official Exhibit - NRC000107-00-BD01 - Indian Point Nuclear Generating Units 2 and 3 - NRC License Renewal Inspection Report 05000247/2008006 & 05000286/2008006 | | | title = NRC Staff Pre-Filed Hearing Exhibit NRC000107, Indian Point Nuclear Generating Units 2 and 3 - NRC License Renewal Inspection Report 05000247/2008006 & 05000286/2008006 |
| | author name = Conte R | | | author name = Conte R |
| | author affiliation = NRC/RGN-I/DRS/EB1 | | | author affiliation = NRC/RGN-I/DRS/EB1 |
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| | case reference number = RAS 22176, 50-247-LR, 50-286-LR, ASLBP 07-858-03-LR-BD01 | | | case reference number = RAS 22176, 50-247-LR, 50-286-LR, ASLBP 07-858-03-LR-BD01 |
| | document report number = IR-08-006 | | | document report number = IR-08-006 |
| | document type = Legal-Exhibit | | | package number = ML12091A044 |
| | | document type = Legal-Pre-Filed Exhibits |
| | page count = 43 | | | page count = 43 |
| }} | | }} |
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| 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 | | 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 |
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| extended operation. | | extended operation. 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 |
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| NRC000107 Submitted: March 31, 2012 United States Nuclear Regulatory Commission Official Hearing Exhibit In the Matter of
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| : Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating Units 2 and 3)
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| ASLBP #:07-858-03-LR-BD01 Docket #:05000247 l 05000286 Exhibit #:
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| Identified:
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| Admitted: Withdrawn:
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| 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
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| =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). | | =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). |
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Revision as of 01:19, 29 June 2019
Letter Sequence ' |
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MONTHYEARML0926405582009-02-27027 February 2009
Comments to the Advisory Committee on Reactor Safeguards on the Indian Point License Renewal Application and Safety Evaluation Report with Open Items
Project stage: Other
ML0911706252009-04-16016 April 2009
Riverkeeper, Inc., Followup Comments to the ACRS on the Indian Point License Renewal Application and Safety Evaluation Report with Open Items
Project stage: Other
ML0922402682009-08-11011 August 2009
Safety Evaluation Report Related to the License Renewal of Indian Point Nuclear Generating Unit Nos. 2 and 3
Project stage: Approval
ML0925403602009-09-0404 September 2009
September 10-12, 2009 ACRS Meeting to Discuss License Renewal Application and Final Safety Evaluation Report (SER) for the Indian Point Nuclear Generating Units 2 and 3
Project stage: Meeting
ML0927201702009-09-23023 September 2009
G20090549/LTR-09-0472/EDATS: SECY-2009-0431 Ltr. from Mario V. Bonaca Report on the Safety Aspects of the License Renewal Application for the Indian Point Nuclear Generating, Units 2 and 3
Project stage: Other
ML0927900132009-10-21021 October 2009
G20090549/LTR-09-0472/EDATS: SECY-2009-0431 - Dr. Mario Bonaca Ltr. Report on the Safety Aspects of the License Renewal Application for the Indian Point Nuclear Generating Units 2 and 3
Project stage: Other
2009-04-16
[Table View] |
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Category:Legal-Pre-Filed Exhibits
MONTHYEARML16081A3252016-03-21021 March 2016
NRCR12001 - NRC Staff Prefiled Hearing Exhibit List (Revised)
ML16078A4172016-03-18018 March 2016
ENTR20726 - Entergy Track 2 Exhibit List
ML16078A4122016-03-18018 March 2016
NRC000236 - Crack Growth Rate Comparison - Eason Pathania Model to MRP Model- Excel Spreadsheet
ML16078A4132016-03-18018 March 2016
NRCR11001 - Exhibt List NRC Staff Prefiled Hearing Exhibit List (Revised)
ML15321A0352015-11-17017 November 2015
NYS000582 - Diagram of Strength Vs Amplitude by Dr. Richard T. Lahey
ML15315A0132015-11-11011 November 2015
ENTR00726 - Track 2 Hearing Exhibit List
ML15309A1292015-11-0505 November 2015
ENT000726 - Entergy Track 2 Hearing Exhibit List
ML15309A1712015-11-0505 November 2015
RIVR14001 - Riverkeeper Tailored Track 2 Exhibit List
ML15309A2212015-11-0505 November 2015
NRCR10001 - NRC Staff Track 2 Exhibit List
ML15309A1552015-11-0404 November 2015
NYSR25001 - NYS Revised Tailored Exhibits List Relevant to Track 2 Contentions
ML15313A4602015-11-0404 November 2015
NYSR25001 - Corrected Page 24 to Exhibits List Relevant to Track 2 Contentions
ML15307A1152015-11-0303 November 2015
NYSR24001 - State of Ny Revised Hearing Exhibits List
ML15307A8112015-11-0303 November 2015
NRC000230 - Corrections to Prefiled Testimony NRC000168 and NRC000197
ML15302A4672015-10-29029 October 2015
ENTR16001 - Entergy Revised Exhibit List
ML15252A4442015-09-0909 September 2015
NYS000563 - Pressurized Water Reactor (PWR) Systems, USNRC Technical Training Center, Reactor Concepts Manual, Pages 4-1 to 4-28
ML15252A4432015-09-0909 September 2015
NYS000566 - Figure 1 for Supplemental Reply Testimony of Dr. Richard T. Lahey
ML15252A5042015-09-0909 September 2015
NYS000568 - Supplemental Reply Statement of Position of the State of New York in Support of Contention NYS-25 (Public, Redacted) (September 9, 2015)
ML15252A5062015-09-0909 September 2015
NYS000570 - Supplemental Reply Statement of Position of the State of New York and Riverkeeper, Inc. in Support of Contention NYS-26B/RK-TC-1B (Public, Redacted) (September 9, 2015)
ML15252A5092015-09-0909 September 2015
RIV000164 - NUREG-1740, ACRS, Voltage-Based Alternative Repair Criteria: a Report to the Advisory Committee on Reactor Safeguards by the Ad Hoc Subcommittee on a Differing Professional Opinion (2001)
ML15252A5112015-09-0909 September 2015
RIVR13001 - Riverkeeper Updated Exhibit List
ML15252A5752015-09-0909 September 2015
NYS000573 - Supplemental Reply Statement of Position of the State of New York and Riverkeeper, Inc. in Support of Contention NYS-38/RK-TC-5 (Public, Redacted) (September 9, 2015)
ML15252A5792015-09-0909 September 2015
NYS Updated Exhibit List
ML15261A8302015-09-0404 September 2015
ENTR00615 - Entergy'S Statement of Position Re Contention NYS-25 (Embrittlement) - Redacted
ML15222A9152015-08-10010 August 2015
ENT000648 - M. Mitchell, Chief, Vessels and Internals Integrity Branch, Response to Non-Concurrence Regarding Safety Evaluation for Topical Report MRP-227, Pressurized Water Reactor Internals Inspection and Evaluation Guidelines (Undated)
ML15223A4512015-08-10010 August 2015
NRC000206 - Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Rev. 25, Chapter 14 - Safety Analysis (2014)
ML15223A4542015-08-10010 August 2015
NRC000207 - Regulatory Information Conference Presentation Slides, Recent Materials Inspections of PWR Reactor Internals (Mar. 2015)
ML15223A4502015-08-10010 August 2015
NRC000205 - Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Rev. 25, Chapter 3 - Reactor (2014)
ML15223A3932015-08-10010 August 2015
NRCR00104 - on Yee Statement of Professional Qualifications (Revised)
ML15223A3912015-08-10010 August 2015
NRCR00105 - Ching Ng Statement of Professional Qualifications (Revised)
ML15222A8212015-08-10010 August 2015
ENT000617 - Curriculum Vitae of Timothy J. Griesbach
ML15223A6712015-08-10010 August 2015
NRCR00147- NRC Staff'S Revised Statement of Position on State of New York and Riverkeeper'S Joint Contention NYS-38/RK-TC5 (Revised)
ML15223A6752015-08-10010 August 2015
NRC000227 - Gary Stevens Statement of Professional Qualifications
ML15222A8222015-08-10010 August 2015
ENT000618 - Curriculum Vitae of Randy G. Lott
ML15223A7022015-08-10010 August 2015
NRCR900001 - NRC Staff Pre-filed Hearing Exhibit List (Revised)
ML15222A8252015-08-10010 August 2015
ENT000629 - Letter from C. Grimes, NRC, to D. Walters, NEI, License Renewal Issue No. 98-0030 Thermal Aging Embrittlement of Cast Austenitic Stainless Steel Components (May 19, 2000)
ML15222A8302015-08-10010 August 2015
ENT000634 - Entergy, IP2, FSAR Update, Revision 25 (2014) (Excerpts)
ML15223A7792015-08-10010 August 2015
NRC000224 - IP3 FSAR Rev. 04 Chapter 16
ML15223A7812015-08-10010 August 2015
NRC000226 - Jeffrey C. Poehler Statement of Professional Qualifications
ML15223A7832015-08-10010 August 2015
NRC000228 - Indian Point Unit 2 Technical Specifications 3.1.4
ML15223A7852015-08-10010 August 2015
NRC000229 - Indian Point, Unit 3 Technical Specifications 3.1.4
ML15223A7872015-08-10010 August 2015
NRC000196 - NRC Staff'S Initial Statement of Position on Contention NYS-25 (Reactor Vessel Internals)
ML15223A3872015-08-10010 August 2015
NRCR00118 - Indian Point Unit 3 Technical Specifications (Excerpt) (Revised)
ML15222A8352015-08-10010 August 2015
ENT000621 - Westinghouse, WCAP-17894-NP, Rev. 0, Component Inspection Details Supporting Aging Management of Reactor Internals at Indian Point Unit 2 (Sept. 2014)
ML15223A8052015-08-10010 August 2015
NRC000169 - Indian Point, Unit 2 Technical Specifications (Excerpt)
ML15223A9452015-08-10010 August 2015
NRC000223 - IP3 FSAR Rev. 04 Chapter 14 (2011)
ML15223A3862015-08-10010 August 2015
NRC000222 - IP3 FSAR Rev. 04 Chapter 3 (2011) (Excerpt)
ML15222B1242015-08-10010 August 2015
ENT000680 - Curriculum Vitae of Barry M. Gordon
ML15222B1262015-08-10010 August 2015
ENT000687 - NRC, Safety Evaluation Report, Topical Report on ASME Section III Piping and Component Fatigue Analysis Utilizing the Westems Computer Code (WCAP-17577, Revision 2) (Undated)
ML15222B1612015-08-10010 August 2015
ENTR00186 - Curriculum Vitae of Mark A. Gray
ML15222A8482015-08-10010 August 2015
ENT000637 - NUREG-1874, Recommended Screening Limits for Pressurized Thermal Shock (PTS) (March 2010)
2016-03-21
[Table view] |
Text
August 1, 2008
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. 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
