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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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NYS000378 Submitted: June 19, 2012
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Generators
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Plants Commercial Operation Dates Replacement Dates Ginna 07/1970 06/1996 Point Beach 1 12/1970 03/1983 H. B. Robinson 03i197i i0ii984 Point Beach 2 10/1972 12/1996 Turkey Point 3 12/1972 04/1982 Turkey Point 4 09/1973 05/1983 Indian Point 2 08/1974 N/A Indian Point 3 08/1976 06/1989 uegradation Mechanisms in Westinghouse Modei 44 Steam Generators Model44 Steam Generators (SGs) use alloy 600 material for tubing. The tubes are supported vertically by the thick tube sheet at the bottom of the steam generator and laterally by drilled-hole tube support plates which are made of carbon steeL Corrosive products (typically magnetite) tend to accumulate in the crevice bet"'Neen tube a.'1d tube support plates because of the d..ri!!ed-hole configuration and Lhe susce-ptibility of the carbon steel to corrosion. The corrosive products have caused tube denting which resulted in axially a.Tid drcum.ferentially oriented stress corrosion cracking in tubes. Th.is degradation rnechanism was the predominant reason for tube plugging in model 44 SGs.
The tubes in Model 44 SGs were mechanically rolled for only a few inches into the tubesheet starting at the primary (lower) face of the tubesheet. As a result, a crevice exists between the tube and the tubesheet for the portion of the tube within the tubesheet that is not expanded. Since the tube was mechanically rolled into the tubesheetj the expansion transition is conunonly referred to as a roll transition. Plants with SG tubes t.~at are or..ly roll expanded for a srr..all distance within t.lJ.e tubesheet :are referred to as partial-depth hardroll plants. The crevice region has been a site for corrosion. Degradation in the crevice andior at the roll transition has led some plants to re-roll the tubes above the original rolled region to provide a new pressure boundary free of any detectable defects. By so doing, the licensees have been able to apply alternate repair criteria, such as the F-star criterion, in which tubes with degradation in a certain specified distance below the top of the tubesheet or the bottom of the roll transition (whichever is lower),
~ay remain in service. Tubes accepted for continued service on the basis of the F-star criterion have structural !Llld lea...lcage integrity consistent with regulatory criteria.
In general, plants wit.1. SGs that have only been pw.1:ially expanded i...'1.to the tubesheet have exlllbited verj liitle circumferentially oriented degradation either at the expansion transition or at the top of the tubesheet.
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}v1ost of these pla."lts have exhibited axially oriented primary water stress corrosion craddng at Lhe roll trartsition, axially oriented outside diameter stress corrosion cracking in the tubesheet crevice region, andior intergranular attack in the tubesheet crevice region.
The small u-bend regions of the tubes have exhibited axial and circumferential cracking. The degradation is caused by excess ovality during tube fabrication process, residual stresses, and tube denting at the top tube support plate. However, some plants had preventively plugged the row of tubes with the smallest u-bends (innermost row)_
There were wastage problems in early operation of mcdel44 SGs (see tube rupture events below). With improved secondary side cherr.dstry, the tube wastage problem was essentially elirrJnated.
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