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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 ML15309A2212015-11-0505 November 2015 NRCR10001 - NRC Staff Track 2 Exhibit List ML15309A1712015-11-0505 November 2015 RIVR14001 - Riverkeeper Tailored Track 2 Exhibit List ML15309A1292015-11-0505 November 2015 ENT000726 - Entergy Track 2 Hearing Exhibit List ML15313A4602015-11-0404 November 2015 NYSR25001 - Corrected Page 24 to Exhibits List Relevant to Track 2 Contentions ML15309A1552015-11-0404 November 2015 NYSR25001 - NYS Revised Tailored 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 ML15252A5792015-09-0909 September 2015 NYS 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) ML15252A5112015-09-0909 September 2015 RIVR13001 - Riverkeeper Updated Exhibit List 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) 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) 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) ML15252A4432015-09-0909 September 2015 NYS000566 - Figure 1 for Supplemental Reply Testimony of Dr. Richard T. Lahey 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) ML15222B1242015-08-10010 August 2015 ENT000680 - Curriculum Vitae of Barry M. Gordon ML15223A4542015-08-10010 August 2015 NRC000207 - Regulatory Information Conference Presentation Slides, Recent Materials Inspections of PWR Reactor Internals (Mar. 2015) ML15223A6752015-08-10010 August 2015 NRC000227 - Gary Stevens Statement of Professional Qualifications ML15223A7792015-08-10010 August 2015 NRC000224 - IP3 FSAR Rev. 04 Chapter 16 ML15222B1692015-08-10010 August 2015 ENTR00031 - Curriculum Vitae of Alan B. Cox ML15222A8482015-08-10010 August 2015 ENT000637 - NUREG-1874, Recommended Screening Limits for Pressurized Thermal Shock (PTS) (March 2010) ML15261A8342015-08-10010 August 2015 ENT000698 - Entergy'S Revised Statement of Position Regarding Contention NYS-38/RK-TC-5(Safety Commitments) (Aug. 10, 2015)Redacted ML15261A8322015-08-10010 August 2015 ENT000678 - NL-07-140, Letter from F. Dacimo, Entergy, to NRC Document Control Desk, Reply to Request for Additional Information Regarding License Renewal Application (Nov. 28, 2007)Redacted ML15223A3452015-08-10010 August 2015 ENTR15001 - Entergy Hearing Exhibit List (Ent Exhibit List) ML15223A3932015-08-10010 August 2015 NRCR00104 - on Yee Statement of Professional Qualifications (Revised) 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) ML15223A3862015-08-10010 August 2015 NRC000222 - IP3 FSAR Rev. 04 Chapter 3 (2011) (Excerpt) ML15222B1612015-08-10010 August 2015 ENTR00186 - Curriculum Vitae of Mark A. Gray ML15223A3702015-08-10010 August 2015 NRC000220 - Pressurized Water Reactor Owners Group (PWROG) Presentation Slides, Industry and NRC Coordination Meeting Materials Programs Technical Exchange: Clevis Insert Bolt Update, (June 2014) ML15223A8052015-08-10010 August 2015 NRC000169 - Indian Point, Unit 2 Technical Specifications (Excerpt) ML15223A2722015-08-10010 August 2015 NRC000226 - Jeffrey C. Poehler Statement of Professional Qualifications ML15223A7872015-08-10010 August 2015 NRC000196 - NRC Staff'S Initial Statement of Position on Contention NYS-25 (Reactor Vessel Internals) ML15223A7832015-08-10010 August 2015 NRC000228 - Indian Point Unit 2 Technical Specifications 3.1.4 ML15223A9452015-08-10010 August 2015 NRC000223 - IP3 FSAR Rev. 04 Chapter 14 (2011) ML15223A6122015-08-10010 August 2015 NRCR20101 - NRC Staff'S Revised Statement of Position Regarding NYS 26B/RK-TC-1B ML15223A4512015-08-10010 August 2015 NRC000206 - Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Rev. 25, Chapter 14 - Safety Analysis (2014) ML15223A2692015-08-10010 August 2015 NRC000183 - NRC Inspection Manual, Inspection Procedure 71013, Site Inspection for Plants with a Timely Renewal Application (Sept. 25, 2013) 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) ML15222B1702015-08-10010 August 2015 ENTR00184 - Curriculum Vitae of Jack R. Strosnider ML15223A7022015-08-10010 August 2015 NRCR900001 - NRC Staff Pre-filed Hearing Exhibit List (Revised) ML15223A7812015-08-10010 August 2015 NRC000226 - Jeffrey C. Poehler Statement of Professional Qualifications 2016-03-21
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ENT000553 Submitted: August 20, 2012 Entergy CONDITION REPORT I LO-LAR-2011-00174 Originator: Caputo, Charles M Originator Phone: 6656 Originator Site Group: IP2 Projects Staff IP2 Operability Required: N Supervisor Name: Curry,John J Reportability Required: N Discovered Date: 08/18/2011 15:02 Initiated Date: 08/18/2011 15 :07 Condition
Description:
This LAR will be used to track the commitments required to implement License Renewal and ensure the commited actions are accomplished prior to the committed dates Immediate Action
Description:
Open LAR to track LRA commitments Suggested Action
Description:
Initated corrective actions to implement programs and other changes to meet the License Renewal conditions
Entergy I CORRECTIVE ACTION ILO-LAR-2011-00174 CA Number: 23 Site J _~~___.__G_rou.!..IIP__~_____-.J1 _____N_a_m_e_~
Assigned By: IP2 Projects Staff IP2 Caputo, Charles M Assigned To: IP2 P&C Eng Codes Mgmt IP2 Azevedo,Nelson F Subassigned To :
Originated By: Caputo, Charles M 8/2112011 13:53:42 Performed By: Azevedo,Nelson F 9/20/2011 12:22:11 Subperformed By:
Approved By:
Closed By: Caputo, Charles M 9/2112011 06:53:32 Current Due Date: 09/28/2011 Initial Due Date: 09/28/2011 CA Type: NRC COMMITMENT Plant Constraint: OTHER CA
Description:
NRC Commitment #33 At least 2 years prior to entering the period of extended operation, for the locations identified in LRA Table 4.3-13 (lP2) and LRA Table 4.3-14 (lP3), under the Fatigue Monitoring Program, IP2 and IP3 will implement one or more of the following:
(1) Consistent with the Fatigue Monitoring Program, Detection of Aging Effects, update the fatigue usage calculations using refined fatigue analyses to determine valid CUFs less than 1.0 when accounting for the effects of reactor water environment.
This includes applying the appropriate Fen factors to valid CUFs determined in accordance with one of the following:
- 1. For locations in LRA Table 4.3-13 (IP2) and LRA Table 4.3-14 (lP3), with existing fatigue analysis valid for the period of extended operation, use the existing CUF.
- 2. Additional plant-specific locations with a valid CUF may be evaluated. In particular, the pressurizer lower shell will be reviewed to ensure the surge nozzle remains the limiting component.
- 3. Representative CUF values from other plants, adjusted to or enveloping the IPEC plant specific external loads may be used if demonstrated applicable to IPEC.
- 4. An analysis using an NRC-approved version of the ASME code or NRC-approved alternative (e.g., NRC-approved code case) may be performed to determine a valid CUF.
(2) Consistent with the Fatigue Monitoring Program, Corrective Actions, repair or replace the affected locations before exceeding a CUF of 1.0.
Response
The analyses required by this CA have been completed with the results documented in WCAP-19199-P for IP2 and WCAP-19200-P for IP3. No other corrective actions are required at this time.
Subresponse :
Closure Comments:
Entergy I CORRECTIVE ACTION ILO-LAR-2011-00174 CA Number: 62
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_'-J~v~.u!-' ~ J ___ Name_ _.......
Assigned By: IP2 Projects Staff IP2 Caputo, Charles M Assigned To: IP2 P&C Eng Codes Mgmt IP2 Azevedo,Nelson F Subassigned To :
Originated By: Caputo, Charles M 8/23/2011 22:03:24 Performed By:
Sub performed By:
Approved By:
Closed By:
Current Due Date: 09/27/2013 Initial Due Date: 09/28/2013 CA Type: NRC COMMITMENT Plant Constraint: OTHER CA
Description:
NRC Commitment # 43 IPEC will review design basis ASME Code Class 1 fatigue evaluations to determine whether the NUREG/CR-6260 locations that have been evaluated for the effects of the reactor coolant environment on fatigue usage are the limiting locations for the IP2 and IP3 configurations. If more limiting locations are identified, the most limiting location will be evaluated for the effects of the reactor coolant environment on fatigue usage.
IPEC will use the NUREG/CR-6909 methodology in the evaluation of the limiting locations consisting of nickel alloy, ifany.
Response
Subresponse :
Closure Comments:
Entergy I CORRECTIVE ACTION ILO-LAR-2011-00174 CA Number: 64
____Site ~ £'~~ ~
_ _ _ _ _ _ _ _ _._ _ __ _..
~ IUU~p ________ ~ I Name
__________ ~
Assigned By: IP2 Projects Staff IP2 Caputo, Charles M Assigned To: IP2 P&C Eng Codes Mgmt IP2 Azevedo,Nelson F Subassigned To :
Originated By: Caputo, Charles M 8/23/201122:17:37 Performed By:
Subperformed By:
Approved By:
Closed By:
Current Due Date: 09/27/2013 Initial Due Date: 09/28/2013 CA Type: NRC COMMITMENT Plant Constraint: OTHER CA
Description:
NRC Commitment #45 I) IPEC will not use the NB-3600 option ofthe WESTEMS program in future design calculations until the issues identified during the NRC review of the program have been resolved.
- 2) During the Period of Extended Operations IPEC will not use the NB-3600 option of the WESTEMS program Program documents shall be revised or generated that ensures the program will be maintained during the PEO before closing this corrective action.
Response
Subresponse :
Closure Comments: