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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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CASE CASES OF ASME BOILER AND PRESSURE VE.."lSEL CODE N-776 Approval Date: April 9, 2010 Code Cases will remain available for use until annulled by the applicable Standards Committee.
Case N-776 (I) A VT-2 visual examination shall be perfonned to Alternative to IWA-S244 Requirements for Buried identify evidence of leakage on ground surfaces in the Piping vicinity of the buried components and in areas where leak Section XI, Division 1 age might be channeled or accumulated. The examination shall be perfonned after the component has been pressur ized to system leakage test pressure for at least 24 hr.
Inquiry: What alternative to the requirement of Portions of buried components where a VT -2 examination IWA-5244 may be used for examination of buried compo is impractical (e.g., component is buried beneath imperme nents? able material or encased in concrete) are exempt from VT-2 Reply: It is the opinion of the Committee that the follow examination.
ing may be used as an altf~rnative to the requirements of (2) A test that detennines the rate of pressure loss, a IWA-5244 for examination of buried components. test that determines the change in flow between the ends (a) For buried components surrounded by an annulus, of the buried components, or a test that confirms that flow the VT-2 visual examination shall consist of an examina during operation is not impaired shall be performed. Per tion for evidence of leakage at each end of the annulus sonnel performing these tests need not be qualified for and at low point drains. VT-2 visual examination.
(b) For buried components without an annulus, the fol (3) The Owner shall specify criteria for the examina
. lowing examination requirements shall be met: tions and tests of (b)(I) and (b)(2) .
The Committee's function is to establish rules of safety. relating only to pressure integrity. governing the construction of boilers, pressure vessels f transport tanks and nuclear components. and inservic::6 inspection for pressure integrity of nuclear components and transport tanks, and to interprat these rules when questions arise regarding their lntent. This Code does not address other safety issues relating to the construction of boilers, pressure vessels. transport tanks and nuclear components, and the inservice inspection of nuclear compononts and transport tanks, The user of the Code should refer to other pertinent codes. standards. laws, regulations or other relevant documents, 1 (N-776) NC SUPP. 1 Copyright ASME In1ernationai iBPYC)
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