NONDISCRIMINATION IN FEDERALLY ASSISTED PROGRAMS OR ACTIVITIES RECEIVING FEDERAL FINANCIAL ASSISTANCE FROM THE COMMISSION
10 CFR 4# QUERY42a1c6ed2dacb0c2f1f2c427c1fa4a53

RIS 2009-12, U.S. Nuclear Regulatory Commission Regulatory Issue Summary 2009-Uranium Recovery Policy Regarding Pre-Licensing Construction Activities At Proposed, Unlicensed Uranium Recovery Facilities
Information Notice 1991-60, False Alarms of Alarm Ratemeters Because of Radiofrequency Interference
NRC-2017-0197, FRN: Exemption - Millstone Power Station, Unit No. 2 - Request for Exemption from Appendix R to 10 CFR Part 50, Section Iii.G (CAC No. MF8789; EPID L-2016-LLE-0002)
CPSES-200301954, Response to NRC Bulletin 2003-02
2CAN109603, Application for Amend to License NPF-6,changing Channel Functional Testing Frequency for Most of Reactor Protection Sys (RPS) & ESFAS Instrumentation from Monthly to Every Four Months
IA-86-231, Package of Exhibits Listing Info Collection Budget for FY86
IA-87-260, Forwards NRC FY87 Civil Rights Implementation Plan Update Required by Section I-403 of Executive Order 12250
JPN-99-010, Transmits Revised Exemption Request from Some of Requirements of 10CFR50,App R.Exemption Would Permit Use of CS for Rc Makeup to Achieve Safe Shutdown in Fire Area XI at JAFNPP
NSD-NRC-98-5576, Forwards Updated List of Requests for Exemption for AP600. Summary of Requests for Exemptions Have Been Revised as Result of Comments & Requests in Ltr from NRC Dtd 980130. Revised Summary Encl
BVY-97-151, Requests That 970609 SER Re Exemption from Requirements of 10CFR50,App R,Section Iii.G,To Permit Use of Fireproof Cable in Plant Areas That Require Enclosing Cables in Fire Barrier Having 1-hour Fire Rating,Be Revised to Show Clarificatio
DT-22-06, MD 10.161, Civil Rights Program and Affirmative Employment and Diversity Management Program
ST-HL-AE-4223, Responds to NRC Re Violation Noted in Insp Rept 50-499/92-24.Corrective Actions:Electrical Auxiliary Bldg (Eab) HVAC Sys Lineup Procedure Revised & Eab & Fuel Handling Bldg HVAC Sys Lineup Procedures Reviewed
DD-93-23, Directors Decision DD-93-23 Re M Daley & J M Block Requesting Per 10CFR2.206,that NRC Reconsider Civil Penalty Assessed Against Vynp for Operating Station Outside TS from 921015-930406.Request Denied
DT-24-05, Management Directive 9.24, Organization and Functions, Office of Small Business and Civil Rights
05000413/LER-1989-018, :on 890628,discovered That Required Charcoal Cartridge Missing from Particulate & Charcoal Samples.Caused by Inappropriate Personnel Action.Technician Removed Particulate Filter & Replaced W/New Filter
05000254/LER-1988-011-11, :on 880625,deviation Meter on RCIC Flow Controller Found to Be Indicating Full Pump Flow While Sys Was Off.Caused by Poor Electrical Contact in Controller Plug Connection.Connector Cleaned
05000341/LER-1987-041, :on 870329,accident Range Monitor Inoperable. Caused by Inadequate Sys Turn Over Following Preoperational Testing.Channel Parameters Will Be Verified Daily & Tech Spec Interpretation Issued
05000395/LER-1987-014, :on 870606,failure to Perform Setpoint Verification Occurred.Caused by Personnel Error.Event Discussed W/Supervisor & Ltr Documenting Event Forwarded to All Supervisors,Including Maint Supervisors
05000336/LER-1986-016-01, :on 861104,sufficient Number of Steam Generator Tubes Discovered to Have Flaws Greater than 40% through-wall to Place Generators in Category C-3 of Tech Spec Table 4.4-6.Defective Tubes Repaired Per Tech Specs
05000259/LER-1987-011-01, :on 870424,maint Personnel Discovered Valve Disks So Heavily Coated W/Hard Deposits,Valves Would Not Close & Could Not Perform Backflow Function.Caused by Inadequate Insp Program.Instructions Written
L-99-098, Forwards Proposed Changes to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Change Would Reduce Operations QA Program Description Commitments by Limiting Required Onsite Safety Committee Reviews of Mods
05000286/LER-1986-004-01, :on 860519,source-range (SR) high-flux Reactor Trip Initiated Automatically by Nuclear Instrumentation Sys. Caused by Operator Failure to Block SR Instrumentation During Startup.Operator Counseled
05000423/LER-1986-052, :on 860918,during Mode 1,discovered That Surveillance of Fire Suppression Halon Bottles Missed.Caused by Administrative Error.Maint Dept Assumed Complete Responsibility for Halon Sys
05000324/LER-1987-005-02, :on 870330,HPCI Sys Steam Supply Outboard Primary Containment Isolation Valve E41-F003 Declared Inoperable.Caused by Blown Control Power Fuse in Valve Operator Motor Breaker.Fuse & Coil Replaced
05000528/LER-1986-042, :on 860617,automatic Reactor Trip Generated Due to Low DNBR Trips.Caused by Inadequate Procedure.Procedure Rev Will Be Implemented to Correct Inadequacies
HL-5728, Requests That RPV Shell Weld Ultrasonic Exams Be Performed Using Techniques & Procedures,Iaw ASME Section Xi,App Viii, 1992 Edition,1993 Addendum,In Lieu of ASME Section XI,1989 Edition Exam Techniques & Procedures
05000528/LER-1986-028, :on 860516,determined That Previous Testing Performed on Halon Portion of Fire Protection Sys Did Not Fulfill Tech Specs as Storage Tanks Could Not Be Calibr. Caused by Personnel Error.Fire Watch Posted
05000395/LER-1997-006, :on 971113,TS Breaker Alignment Surveillance Was Not Performed.Caused by Personnel Error.Operator Was Dispatched to Do Surveillance Following Identification That Surveillance Had Not Been Performed
05000251/LER-1986-018, :on 860824,auxiliary Feedwater Flow Control Valve CV-4-2831 Failed to Open Fully.Caused by Corroded Terminal Due to Water in Pressure Conversion Module.Terminal Cleaned
05000413/LER-1988-003, :on 880116,wide Range Temp Monitoring Instrumentation Technically Inoperable.Caused by Installation Deficiency.Affected Unit 1 Resistance Temp Detector/Cables Replaced
05000265/LER-1988-005-02, :on 880320,reactor Scram & Related ESFs Occurred Due to Spurious Turbine Trip.Caused by Packing Leak on 2B Feedwater Regulating Valve & Lack of Administrative Controls.Valve Repaired & Controls Developed
05000254/LER-1987-033-03, :on 871226,inadvertent Control Rod Scram Occurred When Control Rod H-9 (30-35) Scrammed Per Procedure.Caused by Personnel Error.Control Rod Returned to Prescram Position & Procedure Revised
05000265/LER-1988-002-05, :on 880223,HPCI Inoperable Due to Room Cooler Loss from Short Circuit of Control Relay.Caused by Short Circuit in Control Relay Causing Transformer to Overheat & Short.Control Relay & Transformer Replaced
05000265/LER-1988-003-04, :on 880301,RCIC Declared Inoperable.Caused by Failed Remote Hydraulic Servo on Turbine Govenor Valve.Servo Replaced & RCIC Successfully Tested
05000265/LER-1987-017-09, :on 871103,inadvertent Injection of HPCI Sys Into Reactor Vessel Occurred.Caused by Personnel Error. Individual Involved Counseled & Procedure Revised to Provide Ref for Relay Numbering Conventions
05000260/LER-1985-013-03, :on 851002,during Performance of Plant Surveillance Instruction,Inadvertent Secondary Containment Isolation Occurred When Alternate Feeder Breaker to Shutdown Board Tripped.Caused by Binding Trip Button
JAFP-85-0299, 1984 Radiological Environ Surveillance Rept
05000259/LER-1997-002-02, :on 970314,inadequate CREVS Surveillance Instruction Was Identified During GL 96-01 Review.Caused by Deficient Procedure.Rev to O-SI-4.2.G-2 Was Made & SI Section Was Successfully Completed
05000413/LER-1985-045-01, :on 850710,during 18-month Surveillance Calibrs,Reactor Trip Occurred on lo-lo Steam Generator. Caused by Personnel Error.Technician in Field Will Be Provided Documentation
JPN-97-009, Forwards ISI Summary Rept for JAFNPP Which Provides Summary of ISI Exams Conducted During 1996 Refuel Outage & Info Re Operating Status of Feedwater Nozzle Leakage Monitoring Sys & Measured Leakage for Feedwater Nozzles
05000315/LER-1985-037, :on 850803 & 07,automatic ESF Actuations Occurred.Caused by Installation of Approved Design Change. No Corrective Actions Planned
B16300, Provides NRC W/Update Re Schedule for Independent Corrective Action Verification Program (ICAVP) for Unit 2
05000304/LER-1992-005-12, :on 921112,ESF Actuation Experienced While Getting Centrifugal Charging Pump Discharge Flow Control Valve to Go Closed from 18% Demand.Caused by Personnel Error.Wiring Corrected & Procedure Changed
05000334/LER-1996-008, :on 960531,reactor Trip Occurred.Caused by Test Circuit Applying More Test Current than Amount Required to Test Solenoid Coil.Performed Mod to Reduce Test Current for This Circuit to Lowest Practical Value
05000412/LER-1996-002-01, :on 960220,containment Penetration Not Isolated within Time Limit.Caused by Breakdown in Administrative Controls Governing Document Updates During Initial Plant Const in 1985.Manual Isolation Valves Shut
LD-92-091, Forwards Responses to 920409 Request for Addl Info Re Sys 80+ Severe Accident Design Features
05000296/LER-1984-013-03, :on 841122,HPCI Inoperable When Outboard Steam Supply Isolation Valve Failed to Open.Caused by Motor Pinion Gear to Isolation Valve Being Installed Backwards. Gears Correctly Repositioned
05000296/LER-1984-006, :on 840517,welds Inspected on Jet Pump Instrument Nozzles.Two Welds Needed Repair.Welds Will Be Repaired by Overlay Procedure Prior to Startup.Insp Plan Underway During Refueling Outage
DCL-89-155, Response to Re Backfitting of Nuclear Power Reactors
AECM-82-108, First Interim Deficiency Rept Re Unqualified Namco Limit Switches,Initially Reported 820225.Unqualified Switches That Perform safety-related Function Will Be Replaced.Next Rept by 820419.Also Reported Per Part 21
05000361/LER-1992-013, :on 921209,identified Deficiency Involving Check Valve Test Methodology.Applicable Check Valve Procedure Modified.Applicable SONGS Units 2 & 3 IST Implementing Procedures Will Be Evaluated
L-81-434, Ack Receipt of IE Insp Repts 50-250/81-17 & 50-251/81-17 on 810817-21.No Proprietary Info.Corrective Actions:On 810821, Notice Stating Where Listed Documents Could Be Examined Was Placed in Maint Bldg
NL-13-0676, Financial Assurance Requirements for Decommissioning, Nuclear Power Reactors (10 CFR 50.75(f)(1))
NL-13-0677, Financial Assurance Requirements for Decommissioning Nuclear Power Reactors (10 CFR 50.75(0(1))