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accession number: ML003740046
atomic element: Iron
atomic element: Sodium
atomic element: Molybdenum
atomic element: Chloride
CFR: 10 CFR 50
committee: Advisory Committee on Reactor Safeguards
from: Office of Nuclear Regulatory Research
general design criterion: GDC 14
general design criterion: GDC 1, Quality standards and records
index number: 36
issue date: 1973-02-28Z
issue date#aux: 2441741.5
page count: 3
reg guide group number: 1
start date: 1973-02-28Z
start date#aux: 2441741.5
state: Tennessee
state: Washington
title: Nonmetallic Thermal Insulation for Austenitic Stainless Steel
topic: Stress corrosion cracking
wiki page modification date: 2025-01-17T07:07:52Z
modification date#aux: 2460692.7971296
wiki page sort key: Regulatory Guide 1.36
URL: http://pbadupws.nrc.gov/docs/ML0037/ML003740046.pdf

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ML21294A194
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ML21294A190
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ML21294A184
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wiki page sort key: ML21294A184

ML20309A746
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BVY-97-137, Forwards Response to 971009 RAI Re Plans for Implementing ASME Code Case N560 at Vermont Yankee Nuclear Power Station
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Degradation Mechanism Evaluation & Results of Element & Segment Risk Rankings.Util Intends to Submit Revised ISI Program Following NRC Review of Evaluations & Risk Ranking,As Stated in Ltr
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ML20209A036
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ST-HL-AE-1710, Forwards marked-up FSAR Pages Re Deletion of Containment Spray Sump Additive Tank.Requests NRC Review Changes as Soon as Possible to Avoid Impacting Project Schedule
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ML20160A060
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ML20147A027
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ML20142A532
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ML22111A208
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ML20106E914
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ML20106E911
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ML20106E902
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ML20105A261
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ML20105A245
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NG-75-1559, Forwards Responses to NRC Questions Re 750613 Rept on Wetted Insulation & Lagging Following Reactor Coolant Pump C Seal Failure.Summary of Piping & Insulation Insp to Be Performed During Next Refueling Outage Encl
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TXX-4462, Forwards Revised Method for Temporary Changes Made to Plant Procedures.All Temporary Changes to Procedures Which Do Not Change Intent of Approved Procedures Will Be Approved by Two Members of Station Mgt Staff
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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
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LD-91-071, Responds to NRC Requests for Addl Info for Review of C-E SSAR-Design Certification Rept.Proposed Revs to SSAR Encl
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LD-95-013, Transmits Supplementary Revs for Incorporation Into DCD & Affidavit.Changes Resolve Inconsistencies Identified by NRC & by ABB-CE
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ML23202A003
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ML23291A412
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ML23291A386
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ML23291A374
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L-24-207, License Renewal Application for the Perry Nuclear Power Plant-Response to Request for Additional Information - Set 1
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ML22278A267
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ML20210D023
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ML20211G453
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ML20150C900
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NG-88-0424, 1987 Annual Rept of Facility Changes,Tests,Experiments & Safety & Relief Valve Failures & Challenges
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page: https://kanterella.com/NG-2D88-2D0424-2C_1987_Annual_Rept_of_Facility_Changes-2CTests-2CExperiments_-26_Safety_-26_Relief_Valve_Failures_-26_Challenges
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ML20142A537
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wiki page sort key: ML20142A537

ML20136C997
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IR 05000483/1984045
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ML20055A335
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wiki page sort key: ML20055A335

ML20141D068
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ML20058B378
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ML20059H948
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ML20069D581
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page: https://kanterella.com/ML20069D581
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NG-20-0006, Request for Approval of NextEra Energy Duane Arnold, LLCs Quality Assurance Topical Report (FPL-3) Revision 0
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page: https://kanterella.com/NG-2D20-2D0006-2C_Request_for_Approval_of_NextEra_Energy_Duane_Arnold-2C_LLCs_Quality_Assurance_Topical_Report_-28FPL-2D3-29_Revision_0
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ML20036A910
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AECM-81-394, Forwards Identified & Recommended Corrections to NUREG-0831, Facility Ser.Errors Consist Primarily of Technical Errors & Clarification Affecting Correctness of Rept
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wiki page sort key: AECM-81-394, Forwards Identified & Recommended Corrections to NUREG-0831, Facility Ser.Errors Consist Primarily of Technical Errors & Clarification Affecting Correctness of Rept

AECM-82-358, Forwards Comments & Status of Util Review of OL & Ser.Info Provided to Assist in Generation of Fourth Suppl to SER & Full Power OL
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page: https://kanterella.com/AECM-2D82-2D358-2C_Forwards_Comments_-26_Status_of_Util_Review_of_OL_-26_Ser.Info_Provided_to_Assist_in_Generation_of_Fourth_Suppl_to_SER_-26_Full_Power_OL
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wiki page sort key: AECM-82-358, Forwards Comments & Status of Util Review of OL & Ser.Info Provided to Assist in Generation of Fourth Suppl to SER & Full Power OL

LD-90-008, Forwards Response to 881216 Request for Addl Info Re CESSAR-DC,Chapters 3,4,5 & 6 Re Turbine Missiles,Control Element Drive Structural Matls,Cleaning & Contamination Protection Procedures & Reactor Internals Matls
type: Subject
page: https://kanterella.com/LD-2D90-2D008-2C_Forwards_Response_to_881216_Request_for_Addl_Info_Re_CESSAR-2DDC-2CChapters_3-2C4-2C5_-26_6_Re_Turbine_Missiles-2CControl_Element_Drive_Structural_Matls-2CClean…
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wiki page sort key: LD-90-008, Forwards Response to 881216 Request for Addl Info Re CESSAR-DC,Chapters 3,4,5 & 6 Re Turbine Missiles,Control Element Drive Structural Matls,Cleaning & Contamination Protection Procedures & Reactor Internals Matls

ML20023A781
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ML20041C740
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ML20028F871
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ML20136F302
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ML20094C241
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ML20039F096
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ML20039H235
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ML20023B611
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ML20096D588
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ML20024H335
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ML19326D391
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ML19326D483
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ML19329C504
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01T-0:on 800516,during Cold Pressure Test,Leakage Discovered at Gasket Joint Between Pump Casing & Pump Cover on Reactor Coolant Pumps RC-3A,3B & 3C.Closure Studs Corroded by Boric Acid.Leaks Caused by Deteriorated Gaskets
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label: 05000285/LER-1980-010-01, /01T-0:on 800516,during Cold Pressure Test,Leakage Discovered at Gasket Joint Between Pump Casing & Pump Cover on Reactor Coolant Pumps RC-3A,3B & 3C.Closure Studs Corroded by Boric Acid.Leaks Caused by Deteriorated Gaskets
page: https://kanterella.com/05000285/LER-2D1980-2D010-2D01-2C_/01T-2D0-3Aon_800516-2Cduring_Cold_Pressure_Test-2CLeakage_Discovered_at_Gasket_Joint_Between_Pump_Casing_-26_Pump_Cover_on_Reactor_Coolant_Pum…
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CNL-24-060, Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description
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L-2024-114, Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal
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ML24114A121
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CNL-24-020, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements
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ML23193A895
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ML23062A618
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L-2023-071, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal
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ML22292A091
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L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update
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ML22193A130
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ML22193A073
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ML19282B445
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IR 05000098/1978001
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ML19261B290
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CNL-25-010, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Response to Request for Additional Information - TVA Request for Approval of Revision 43 to TVA Fleet Quality Assurance Program Description
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