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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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NRC000220 Submitted: August 10, 2015 Global Expertise
- One Voice Industry and NRC Coordination Meeting Materials Programs Technical Exchange Clevis Insert Bolt Update Bryan Wilson, Westinghouse June 2014 P R E S S U R I Z E D WAT E R R E A C T O R O W N E R S G R O U P
Industry and NRC Coordination Meeting Materials Programs Technical Exchange Clevis Insert Bolt Update - Background Section A-A (Internal Details Removed for Clarity) 2 P R E S S U R I Z E D WAT E R REACTOR OWNERS GROUP
Industry and NRC Coordination Meeting Materials Programs Technical Exchange Clevis Insert Bolt Update - Recent OE Root Cause
- D.C. Cook Issued Root Cause Evaluation (AR 2010-1804-10)
- Root Cause PWSCC of Alloy X-750 with a susceptible heat treatment
- All 29 bolts removed, were either already separated, separated during removal, or had cracks present
- All failures/cracking was at the head-to-shank transition radius
- Fracture mode was essentially 100% intergranular on all bolts
- All Westinghouse and CE plants are potentially susceptible:
- Similar heat treatments are used on all Alloy X-750 clevis insert bolts
- Preload stress in the bolts is similar for all plant
- Visual inspection of bolts alone is not 100% reliable for confirming bolt integrity 3 P R E S S U R I Z E D WAT E R REACTOR OWNERS GROUP
Industry and NRC Coordination Meeting Materials Programs Technical Exchange Clevis Insert Bolt Update - NRC 3/27/14 Meeting Summary
- Design Introduction
- Safety Functions
- Design Configurations
- Potential Failure Modes Related to Clevis Insert Bolt Failures
- Why Failure Modes are Unlikely to Occur
- Detection Methods
- Conclusion
- All design configurations are inherently safe
- Loose parts are captured (with the possible exception of lock bars)
- No single point failure leading to loss of function
- Concerns are primarily commercial in nature
- Visual inspection of wear surfaces and general condition will provide the appropriate level of aging management without the need for bolt inspections
- PWROG project, PA-MSC-1198, will provide utilities the technical basis for the safety case argument presented in the NRC discussion 4 P R E S S U R I Z E D WAT E R REACTOR OWNERS GROUP
Industry and NRC Coordination Meeting Materials Programs Technical Exchange Clevis Insert Bolt Update - Pending Westinghouse Communication
- Technical Bulletin (TB) is the proposed communication tool
- Much of the detail in IG-10-1 will be included
- Include a discussion on evaluations performed considering the 4 different Westinghouse and CE clevis insert designs
- Summarize the Root Cause Analysis findings and discuss industry impacts
- Reaffirm that the findings of the RCA do not change the conclusion that this is not an immediate safety concern
- Identify that there are asset management risks that need to be considered
- Provide clear inspection recommendations which can enhance focus of the base aging management program:
- For monitoring conditions directly related to functional performance
- For managing bolt degradation to reduce asset management risk
- Provide optional approaches to support a proactive asset management program 5 P R E S S U R I Z E D WAT E R REACTOR OWNERS GROUP
Industry and NRC Coordination Meeting Materials Programs Technical Exchange Clevis Insert Bolt Update - Potential Inspection Options
- Visual examination (VT3) of the following at your next 10-year ISI or earliest opportunity when the lower internals are removed
- For monitoring conditions related to functional performance:
- Radial key / clevis insert interfacing surfaces; look for aggressive or abnormal wear as compared to previous inspection (if available)
- Interface between the clevis insert and vessel lug; look for signs of looseness or dislocation
- For managing bolt degradation to reduce asset management risk:
- Bolt heads; look for wear between the bolt head and lock bar and/or bolt head dislocation (not 100% reliable for confirming bolt integrity)
- Optional Approaches to Support a Proactive Asset Management Program
- Bolt replacement 6 P R E S S U R I Z E D WAT E R REACTOR OWNERS GROUP
Industry and NRC Coordination Meeting Materials Programs Technical Exchange Clevis Insert Bolt Update - Aging Management Requirements Clarification
- MRP-227-A requires inspection of the clevis insert for wear only, but lacks specificity
- Considering the following changes for MRP-227, Rev. 1:
- Recatigorization of the clevis inserts and bolts as Primary components
- Add specifics related to inspection requirements and logic for requiring certain inspections 7 P R E S S U R I Z E D WAT E R REACTOR OWNERS GROUP
Questions?
The Materials Subcommittee is established to provide a forum for the identification and resolution of materials issues including their development, modification and implementation to enhance the safe, efficient operation of PWR plants.
8 P R E S S U R I Z E D WAT E R REACTOR OWNERS GROUP
Global Expertise