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List of results

• ML20133F969  + (Submits Request for Relief from ASME Code Requirements, Section IX IAW 10CFR50.55a(g)(6)(i) Allowing Braidwood to Continue Operation W/Drain Line Leak of Unit 1,Train a Essential Svc Water Strainer)
• ML20138B193  + (Submits Request for Relief from ASME Oma 1988 Part 10, Inservice Testing of Valves in Light-Water Reactor Power Plant, Requirements for WCNOC IST Program)
• ML20199F695  + (Submits Request for Relief from ASME Section XI Inservice Testing Valve Program to Extend Interval Between Disassembly of Check Valve,Within Group of Four Similar Check Valves for EECW Dgs,From 18 to 24 Months)
• FVY-90-102, Submits Request for Relief from ASME Section XI Code Re Indications Found During Insp of CRD Cap Screws.Even Under Extreme Stated Conditions,Cap Screws Have Adequate Structural Capacity to Perform Function  + (Submits Request for Relief from ASME Section XI Code Re Indications Found During Insp of CRD Cap Screws.Even Under Extreme Stated Conditions,Cap Screws Have Adequate Structural Capacity to Perform Function)
• ML17312B541  + (Submits Request for Relief from Asme,Section XI & Applicable Addenda for Reactor Exams Involving Unit 1.Requested Relief Would Not Be Used to Credit Exam Completion for Second 10-yr ISI Interval)
• ML20093N240  + (Submits Request for Relief from Modifying Pipe Supports SIS-63/65,SIH-3 & RCH-13 & That Supports Be Accepted W/ Current Listed Factor of Safety & Stress Margins)
• ML20134N429  + (Submits Request for Relief from Performing Substantial Flow Charging Pump Test at Increased Frequency Per Acceptance Criteria of Asme/Ansi Oma-1988,Part 6,Article 6.1)
• RC-97-0041, Submits Request for Relief to Provide Alternative to Current Commitments W/Regard to Leaks to Bolted Connections Re Section XI of ASME Code  + (Submits Request for Relief to Provide Alternative to Current Commitments W/Regard to Leaks to Bolted Connections Re Section XI of ASME Code)
• ML20207E876  + (Submits Request for Review & Approval of Rev to Plan for Achieving Compliance with NRC Regulations at Portsmouth Gaseous Diffusion Plant.Rev Involves Changes to Issue 8, Issue 9 & Portions of Issue 23)
• ML20247B737  + (Submits Request for Review & Endorsement of Proposed Safety Evaluation of BWR Owners Group Topical Rept NEDO-32291, Sys Analyses for Elimination of Selected Response Time Testing Requirements)
• L-95-206, Submits Request for Schedular Exemption from Requirements of 10CFR50,App J, Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors  + (Submits Request for Schedular Exemption from Requirements of 10CFR50,App J, Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors)
• 3F1093-13, Submits Request for Schedular Exemption for Annual Radiological Emergency Plan Exercise  + (Submits Request for Schedular Exemption for Annual Radiological Emergency Plan Exercise)
• ML17321A102  + (Submits Request for Schedular Exemption from 10CFR50,App R Mods for Listed Items.Matl Delivery Problems Will Extend Completion of Several App R Design Changes Beyond 840620)
• ML20202F020  + (Submits Request for Technical Assistance Re NRC Emergency Preparedness Program)
• ML20199J084  + (Submits Request for Technical Assistance to Determine Technical Adequacy of Util Revised Design Calculations for Reactor & Turbine Bldgs Blowout Panels)
• RNP-RA/15-0083, Submits Request for Technical Specification Change to Reactor Coolant System Pressure and Temperature Limits  + (Submits Request for Technical Specification Change to Reactor Coolant System Pressure and Temperature Limits)
• ML20096C726  + (Submits Request for Use of Alternative Rules for Post Repair/Replacement Hydrostatic Testing for ASME Class 1,2 & 3 Sys Based on Code Case N-416-1)
• ML20148G448  + (Submits Request for Verification of Final Survey & Issuance of Order to Terminate License R-127 Per 880126 Order. Certificate of Calibration Encl)
• ML20024J176  + (Submits Request for Voluntary Comment on Pilot Program for NRC Recognition of Good Performance by Nuclear Power Plants. Licensee Appreciates Opportunity to Comment on Issue)
• RA-97-091, Submits Request for Withdrawal of Application to Transfer & Amend License for Westinghouse Test Reactor Facility  + (Submits Request for Withdrawal of Application to Transfer & Amend License for Westinghouse Test Reactor Facility)
• ML20055A833  + (Submits Request for Withdrawal of Export License Application.Permission Received to Ship Under Ga Co License)
• ML17229A071  + (Submits Request for Withholding Info from Public Disclosure Re Rept, Plant Specific Seismic Adequacy Evaluation of Plant,Unit 2 to Resolve GL 88-20,Suppl 4. Request Granted)
• ML20090L795  + (Submits Request on Behalf of Petitioners Mecca,Hare & Hatling for ACRS Rept on Application for full-term Ol,Aec Fes,Safety Evaluation & Proposed full-term OL for Plant)
• ML17266A061  + (Submits Request to Amend App B to License DPR-67.Believes Effluent Limitations & Monitoring Requirements Are in Conflict w/ALAB-515.Requests Deletion of ETS Requirements Re Nonradiological Limitations)
• ML20054B657  + (Submits Request to Amend Export License,Increasing U from 15.0 Kg to 15.015 Kg)

• ML19290B799  + (Submits Request to Amend Export License,Adding Intermediate Consignee)

• ML17207A762  + (Submits Request to Amend License Re Tech Spec Pages 3-10, 3-14,3-16 & 3-18.Changes Include Actuation Sys Instrumentation,Instrument Trip Valves & Actuation Sys Instrumentation Surveillance Requirements)
• ML17207A763  + (Submits Request to Amend License Re Tech Spec Pages 3-10, 3-14,3-16 & 3-18.Changes Include Actuation Sys Instrumentation,Instrument Trip Valves & Actuation Sys Instrumentation Surveillance Requirements)
• ML18101B381  + (Submits Request to Change QA Program for Salem & Hope Creek Stations)
• ML18101B382  + (Submits Request to Change QA Program for Salem & Hope Creek Stations)
• LR-N980154, Submits Request to Change QA Program for Hope Creek & Salem Generating Stations,Per Section 17.2 of Respective Ufsars. Changes to Section 17.2 of Hope Creek & Salem Ufsars, Respectively & Description of Proposed Changes Encl  + (Submits Request to Change QA Program for Hope Creek & Salem Generating Stations,Per Section 17.2 of Respective Ufsars. Changes to Section 17.2 of Hope Creek & Salem Ufsars, Respectively & Description of Proposed Changes Encl)
• ML20115G597  + (Submits Request to Delete Surface Exam of Reactor Pressure Vessel Re Support Integral Attachment Welds Relief Request ISI-017)
• ML20205N153  + (Submits Request to Elminate fitness-for-duty Requirement from Plant.Proposed Change Has Been Reviewed by PORC & Nuclear Safety Audit & Review Committee)
• ML20199E860  + (Submits Request to Extend Deferral Period for Implementation of ECCS Suction Strainer Mod Activities Associated W/Nrc Bulletin 96-003 from Dec 1998 Until Apr 1999)
• ML20198L485  + (Submits Request to Implement risk-informed Inservice Testing Program During Remainder of Second 10-yr Interval for SONGS, Units 1 & 2.Request Prepared Using Guidance of Reg Guide 1.175.Rept Encl)
• ML17313B015  + (Submits Request to Obtain All Data Previously Sent by PVNGS & Currently in REIRS for OLs NPF-41,NPF-51 & NPF-74.Data Is Requested in Electronic Form (Ascii Format) as It Currently Exists in REIRS Sys)
• ML20205K358  + (Submits Request to Reschedule Breaker Maint Insp for Braidwood Nuclear Power Station for Either Wk of 990607 or One of Last Two Wks in Jul 1999)
• U-603098, Submits Request to Reschedule Planned Insps for Corresponding Dates Listed.Util Ability to Ensure Result Dependent on Continued,Effective Communication with NRC Staff & NRC Restart Panel  + (Submits Request to Reschedule Planned Insps for Corresponding Dates Listed.Util Ability to Ensure Result Dependent on Continued,Effective Communication with NRC Staff & NRC Restart Panel)
• ML20210J269  + (Submits Request to See Attached File Containing Regional TAR)
• 0CAN079805, Submits Request to Withdraw Licenses for Ja Pierce,Te Voss & Rj Espolt,Iaw 10CRF50.74  + (Submits Request to Withdraw Licenses for Ja Pierce,Te Voss & Rj Espolt,Iaw 10CRF50.74)
• ML17334A640  + (Submits Request to Withdraw Refueling Operations Decay Time Tech Spec Amend Due to Desire to Maintain Option of Performing Regular Full Core Discharges to SFP)
• ML20216B909  + (Submits Requested 90-day Response to GL 96-04, Boraflex Degradation in Spent Fuel Pool Storage Racks. Racklife Evaluation Demonstrates That Racks Have Relatively Low Silica Loss & Correspondingly Low B4C Loss)
• ML20024H588  + (Submits Requested Addl Info Re 910325 Application for Export License)
• L-88-510, Submits Requested Addl Info Re Emergency Power Sys Enhancement Project.Project Will Be Implemented in Two Phases Consisting of Outage & pre-outage Activities to Meet Integrated Schedule 1990 Completion Date  + (Submits Requested Addl Info Re Emergency Power Sys Enhancement Project.Project Will Be Implemented in Two Phases Consisting of Outage & pre-outage Activities to Meet Integrated Schedule 1990 Completion Date)
• ML17251A828  + (Submits Requested Addl Info Re Isolation Devices Used in Conjunction W/Spds.Foxboro Model M66B Current Repeaters Are Isolation Devices Used for Reactor Protection Sys & ESFAS Inputs to SPDS)
• 3F1084-08, Submits Requested Addl Info Re NUREG-0737,Item II.K.2.16 Concerning Reactor Coolant Pump Seal Cooling Sys Providing Adequate Cooling Upon Loss of Offsite Power,Per NRC 840829 Safety Evaluation  + (Submits Requested Addl Info Re NUREG-0737,Item II.K.2.16 Concerning Reactor Coolant Pump Seal Cooling Sys Providing Adequate Cooling Upon Loss of Offsite Power,Per NRC 840829 Safety Evaluation)
• ML20206F887  + (Submits Requested Addl Info for Analysis of Firewater Cooldown for 82% Power Operation,Per)
• ML19259C521  + (Submits Requested Change to Page 3/4 3-13 & Associated Safety Evaluation,Increasing Certain Safety Margins)
• ML20140H471  + (Submits Requested Data Re PWR Total Critical Scram (Manual Plus Auto) Rates Per Reactor Yr)
• ML19270G466  + (Submits Requested Info Comparing Plant Design w/NRC-approved Browns Ferry Design)
• ML19269E333  + (Submits Requested Info Re Analysis on Capability of Dry & Isolated Steam Generator to Start Auxiliary Feedwater Pump 30 Minutes After Loss of All Main Auxiliary Feedwater & Test Results for Anticipatory Reactor Trip Sys)