NRC-15-0059, Response to NRC Request for Additional Information Associated with Near-Term Task Force Recommendation 2.1, Seismic Hazard and Screening Report
NL-09-056, Reply to Request for Additional Information - Open Items
LR-N04-0361, Response to Second Request for Additional Information for LCR-H03-07 Request for Change to Technical Specifications Emergency Diesel Generator (EDG) Surveillance Testing
NUREG/CR-6456, Forwards for Info & Use,Aeod Rept, Review of Industry Efforts to Manage PWR Feedwater Nozzle,Piping & Feedring Cracking & Wall Thinning, NUREG/CR-6456
2CAN058704, Requests Approval to Utilize Temper Bead Weld Repair Technique,Described in Winter 1985 Addenda of 1983 Edition of Section III of ASME Boiler & Pressure Vessel Code for Temporary Repair of Pressurizer.Supporting Info Encl
B12136, Forwards Revised Pages to Attachments 2 & 3 of Re 10CFR50,App J Exemption Request Concerning Testing of Containment Isolation Valve in Reverse Direction & Addition of Penetration Requiring Schedular Exemption
NG-97-1597, Forwards Response to Request for Addl Info on Improved Tech Spec Change Re Not Entering LCO Action Statements During Certain Surveillances
DCL-84-195, Forwards Response to 146 Allegations in . Safeguards Info Withheld (Ref 10CFR73.21)
RBG-16-335, Final Deficiency Rept DR-125 Re RHR Spool Piece Welds Provided by Bf Shaw Co.Condition Not Reportable Under 10CFR50.55(e)
LD-88-099, Responds to NRC Request for Addl Info Re Chapters 5 & 9 of CESSAR-DC Re Steam Generator Secondary Water Chemistry, Reactor Coolant Water Chemistry,Fire Protection Sys,Letdown Purification Line & Hydrogen Ignition
NPL-98-0470, Responds to NRC Re Violations Noted in Insp Rept 50-301/98-05 on 971216-980309.Corrective Actions:Subsequent to Issuance of QFR 01,PQR GT-SM/1.1-Q6 Was Developed
05000354/LER-1987-011, :on 870202,during Nuclear QA Audit,Discovered That Four Cs-137 Sources Not Leak Tested within Period Specified by Tech Spec 4.7.6.2.Caused by Personnel Error. Personnel Counseled Re Compliance W/Tech Specs
05000413/LER-1988-019, :on 880425,valid Failure of Diesel Generator 1A Occurred Due to Faulty Oil Pressure Sensor.Caused by Design, Mfg,Const/Installation Deficiency.Components Known or Suspected to Have Failed Replaced & Tested
AECM-88-0107, Forwards Computer Tape of Hourly Meteorological Data for 1987.Note Tape Formatted Similar to Tape Sent Earlier by Ltr Except That Ebcdic Format Rather than Ascii Format Used.Sample Tape Dump Printout Also Encl
A04142, Forwards Addl Info in Response to NRC 840619 Request Re Amend 2 to Probabilistic Safety Study
05000387/LER-1983-077-03, /03L-0:on 830510,seven Snubbers W/Inadequate Clearance Identified,Indicating Possible Rear Bracket Interference.Caused by Lack of Info from Snubber Vendor. Snubbers Reworked
L-82-427, Final Deficiency Rept Re Incorrect Shaft Bearings on Diesel Generator Motors 2A1 & 2A2.Initially Reported on 820826.Shaft Bearings Replaced w/self-aligning Bearings.Not Reportable Per 10CFR50.55e,but Reportable Per Part 21
B14638, Forwards Addl Info Re GL 92-01,Rev 1, Reactor Vessel Structural Integrity 10CFR50.54(f) to Support NRC Evaluation of Util 920706 Response
05000369/LER-1981-098, Forwards LER 81-098/03L-0.Detailed Event Analysis Encl
05000265/LER-1979-005-03, /03L-0 on 790223:2A Recirculation Motor Generator Field Breaker Opened,Causing Flow Mismatch.Caused by Loosening of Coupling Between Main Shaft & Recirculation Motor Generator Set Tachometer.Tachometer Coupling Reset
05000338/LER-1979-031-03, /03L-0 on 790302:surveillances of Engineered Safety Feature Pumps Not Performed within Interval.Caused by Personnel Error Due to Long Period from Preoperational Tests to Operation.Surveillances Will Be Performed
05000400/LER-1996-002-04, :on 960508,failed to Properly Perform Tech Spec Surveillance Testing.Caused by Personnel Error.Personnel Counseled,Procedure Revised & Continued in-program Tech Spec Testing Program Review
L-83-155, Forwards Corrected Page 3 to 830315 Submittal, Control of Heavy Loads, Technical Evaluation Rept
NL-17-127, Supplemental Information Regarding the Service Water Integrity Aging Management Program for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3 License Renewal Application (LRA)
GO2-88-262, Forwards Rev 1 to Insp of Anf Fuel Assemblies 1163 & 1164 After One-Cycle of Irradiation at Washington Nuclear Plant 2 Reactor. Insps Motivated in Part by Util Concerns Re Crud Induced Localized Corrosion.Rept Withheld (Ref 10CFR2.790)
NL-17-053, Reply to Request for Additional Information for the Review of the Indian Point License Renewal Application RAI Set 2017-03
NL-17-005, Actions Concerning License Renewal Commitments 41 and 42 in Response to LR-ISG-2016-01, Changes to Aging Management Guidance for Various Steam Generator Components
NL-16-122, Reply to Request for Additional Information for the Review of License Renewal Application, Set 2016-01
NL-12-089, Official Exhibit - ENT000554-00-BD01 - NL-12-089, Letter from F. Dacimo, Entergy, to NRC, Reply to Request for Additional Information Regarding the License Renewal Application Indian Point Nuclear Generating Unit Nos. 2 & 3
NL-11-074, New York State (NYS) Pre-Filed Evidentiary Hearing Exhibit NYS000152, Entergy Response (NL-11-074) to Request for Additional Information (Rai), Aging Management Programs, Indian Point Nuclear Generating Unit Nos. 2 & 3, Docket Nos. 50-247
NL-11-090, New York State (NYS) Pre-Filed Evidentiary Hearing Exhibit NYS000153, Entergy Response (NL-11-090) to Request for Additional Information for the Review of the Indian Point Nuclear Generating Unit Number 2 and 3 (Jul. 27, 2011) (Entergys Ju
NL-10-082, License Renewal Application - Completion of Commitment 33 Regarding the Fatigue Monitoring Program
NL-08-143, Additional Information Regarding License Renewal Application - Reactor Vessel Fluence Clarification
NL-09-106, Response to Questions Regarding Buried Piping Inspections
NLS2008067, Response to Nuclear Regulatory Commission Request for Additional Information Reactor Equipment Cooling System
NL-17-161, Supplemental Information Regarding the Service Water Integrity Aging Management Program for the Review of the Indian Point Nuclear Generating Units 2 and 3 License Renewal Application (LRA)
ST-HL-AE-3711, Proposes Alternative Wording for NRC SER on Util Turbine Sys Maint Program,Submitted to Util Via NRC .Changes Cover Insp Invervals for Low Pressure Turbines & Insp of Low Pressure Turbine Rotors
NL-17-060, Reply to Requests for Additional Information for the Review of the Indian Point License Renewal Application RAI Set 2017-02
A02477, Forwards Response to Generic Ltr 82-10 Requesting Info Re Implementation Dates for Selected TMI Action Plan Items in NUREG-0737