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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
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NYS000222 Submitted: December 16, 2011 EXCERPT REGULATORY GUIDE 1.70 REVISION 3 STANDARD FORMAT AND CONTENT OF SAFE I Y ANALYSIS REPORTS FOR NUCLEAR POWER PLANTS LWR EDITION NOVEMBER 1178
. OFFICE OF STANDARDS DEVELOPMENT U.S. NUCLEAR REGULATORY COMMISSION OAGI0001264_00001
Revision 3 November 1978 described above to describe the population and its distribution at 10-mile intervals between the 10- and 50-mile radii from the reactor.
2.1.3.3 Transient Population. Seasonal and daily variations in population and population distribution resulting from land uses such as recreational or industrial should be generally described and appropriately keyed to the areas and population numbers contained on the maps and tables of paragraphs 2.1.3. 1 and 2. 1.3.2. If the plant is located in an area where significant population variations due to transient land use are expected, additional tables of population distribution should be provided to indicate peak seasonal and daily populations. The additional tables should cover projected as well as current populations.
- 2. 1.3.4 Low Population Zone. The low population zone (as defined in 10 CFR Part 100) should be specified and the basis for its selection discussed. A scaled map of the zone should be provided to illustrate topographic features; highways, railways, waterways, and any other trans-portation routes that may be used for evacuation purposes; and the location of all facilities and institutions such as schools, hospitals, prisons, beaches, and parks. Facilities and institutions beyond the low population zone which, because of their nature, may require special consideration when evaluating emergency plans, should be identified out to a distance of five miles. A table of population distribution within the low popula-tion zone should provide estimates of peak daily, as well as seasonal transient, population within the zone, including estimates of transient population in the facilities and institutions identified.
- 2. 1.3.5 Population Center. The nearest population center (as defined in 10 CFR Part 100) should be identified and its population and its direc-tion and distance from the reactor specified. The distance from the reactor to the nearest boundary of the population center (not necessarily the political boundary) should be related to the low population zone radius to demonstrate compliance with Part 100 guidelines. The bases for the boundary selected should be provided. Indicate the extent to which tran-sient population has been considered in establishing the population center.
In addition tc specifying the distance to the nearest boundary of a popula-tion center, discuss the present and projected population distribution and population density within and adjacent to local population groupings.
2.1.3.6 Population Densi~y. The cumulative resident population projected for the year of init1al plant operation should be plotted to a distance of at least 30 miles and compared with a cumulative population resulting from a uniform population density of 500 people/sq. mile in all directions from the plant. Similar information should be provided for the end of plar.t life but compared with a cumulative population resulting from a uniform population density ~f lOGO people/sq. mile.
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