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Rubidium# QUERYd1764d99ac8c9270bdaff87b82f354e8
Rubidium
Rubidium# QUERYc8e05d785cf02a2695da21e22ca6c008
LR-N20-0025, 2019 Annual Radioactive Effluent Release Report (Rerr)
NOC-AE-07002215, Response to Request for Additional Information on Proposed Amendment for Alternate Radiological Source Term (AST) Methodology
RAIO-0817-55190, LLC Response to NRC Request for Additional Information No. 76 (Erai No. 8792) on the NuScale Design Certification Application
L-2016-222, Emergency Plan Exercise Scenario
RS-16-248, Byron/Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Appendix a - Application of NRC Regulatory Guides
RAIO-0319-64956, LLC - Supplemental Response to NRC Request for Additional Information No. 256 (Erai No. 9161) on the NuScale Design Certification Application
LR-N10-0140, Hope Creek - Attachment 1, Offsite Dose Calculation Manual Revision, 23
NL-16-0388, Draft License Amendment Request Regarding Alternative Source Team
NSD-NRC-98-5514, Forwards W Responses to FSER Open Items Re AP600.NRC Should Review Encl & Inform W of Status to Be Designated in NRC Status Column of Oits
SECY-18-0075, Weekly Information Report - Week Ending July 20, 2018
PNO-IV-85-029, increase in Gaseous Activity in Accessible Radiological Control Areas,Including Auxiliary Bldg,Reported Since Reaching 100% Power.Probably Caused by Positive Displacement Charging Pump Gland Leak Off
RS-08-132, LaSalle County Station, Units 1 and 2 - Transmittal Letter of Additional Information Regarding Request for License Amendment Regarding Application of Alternative Source Term. Attachments 1 - 5
NRC 2003-0028, License Amendment Request 234, Selective Scope Implementation of Alternative Source Term for Fuel Handling Accident
RS-02-174, Co., Llc. (EGC) Application for Amendment to Licenses DPR-19, DPR-25, DPR-29 & DPR-30, Related to Application of Alternative Source Term, Attachments a - E-1
GNRO-2011/00024, Response to Request for Additional Information Regarding Extended Power Uprate
LR-N15-0078, Annual Radioactive Effluent Release Report
2CAN031001, License Amendment Request, Technical Specification Changes and Analyses Relating to Use of Alternative Source Term
RA-08-060, Transmittal of Supplemental Response - Amergen Application to Revise Technical Specifications Secondary Containment Operability Requirements During Refueling
L-MT-04-023, License Amendment Request: Selective Scope Application of an Alternative Source Term Methodology for Re-evaluation of the Fuel Handling Accident
NRC 2009-0026, Transmittal of Supplement to License Amendment Request 241 Regulatory Guide 1.183 Compliance Matrix
LR-N09-0099, Hope Creek, and Salem, Units 1 and 2, 2008 Annual Radioactive Effluent Release Report, Cover Through Page 180
LIC-12-0027, License Amendment Request (LAR) 12-02, Proposed Change to Relocate Operating and Surveillance Requirements for Technical Specifications 217 and 3.13 Concerning Miscellaneous Radioactive Material Sources
RAIO-0618-60288, Submittal of Response to NRC Request for Additional Information No. 329 Erai No. 9270) on the Design Certification Application
WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 11.0 - Radioactive Waste Management
LIC-03-0151, 5 to TSC-8, Core Damage Assessment and Revised EPIP Index Page 1 and 2
3F0884-19, Effluent & Waste Disposal Semiannual Rept,Jan-June 1984
LR-N14-0084, Hope Creek and Salem, Units 1 and 2, 2013 Annual Radioactive Effluent Release Report
LR-N12-0121, Salem and Hope Creek - 2011 Annual Radioactive Effluent Release Report
LR-N17-0087, 2016 Annual Radioactive Effluent Release Report
L-PI-04-065, FAI/01-86, Rev 1 Gap - User Documentation
NOC-AE-07002127, Request for License Amendment Related to Application of the Alternate Source Term
NUREG-0090 Volume 42, Report to Congress on Abnormal Occurrences, Fiscal Year 2019
LR-N13-0093, 2012 Annual Radioactive Effluent Release Report, for the Period of January 1, 2012, to December 31, 2012
NRC-94-4311, Forwards Responses to NRC RAIs & Open Items on AP600 from NRC 940516,0815,18,29 & 30 Ltrs.Responses Associated W/ Complete
RA-08-045, Response to Draft Request for Additional Information - Amergen Application to Revise Technical Specifications Regarding Secondary Containment Operability Requirements During Refueling
NL-17-0643, Response to Request for Additional Information Regarding Alternative Source Term License Amendment Request
DCL-15-069, License Amendment Request 15-03 Application of Alternative Source Term - Updated Final Safety Analysis Report Markup. Part 6 of 8
L-PI-11-019, Supplement to License Amendment Request to Exclude Dynamic Effects Associated with Certain Postulated Pipe Ruptures from Licensing Basis Based Upon Application of Leak-Before-Break Methodology - Response to Requests for Clarification
L-14-245, Response to Request for Additional Information Regarding Request for Licensing Action on Alternative Accident Source Term Radiological Dose Calculations
LR-N14-0084, Offsite Dose Calculation Manual, Revision 27
NL-08-059, Indian Point, Units 2 & 3 - Transmittal of Final Design Report for the New Alert and Notification System
LR-N07-0069, Response to Request for Additional Information Request for License Amendment - Extended Power Uprate
LR-N10-0140, Salem - Attachment 1, Offsite Dose Calculation Manual, Revision 22
NUREG/CR-7282, Review of Accident Tolerant Fuel Concepts with Implications to Severe Accident Progression and Radiological Releases
LR-N04-0117, Stations, Radioactive Effluent Release Report
GO2-95-204, Informs That Ltr Submitted in Accordance W/License Condition 2.F Which Requires Written follow-up Rept within 14 Days of Facility Operation at Reactor Core Power Levels in Excess of Full Power
NL-23-0010, Response to Request for Additional Information Regarding License Amendment Request for Alternative Source Term, TSTF-51, TSTF-471, and TSTF-490
SVP-03-052, Radioactive Effluent Report for January Through December 2002, Chapters 10 and 12, Appendix a - F
RS-12-221, Braidwood, Units 1 and 2 and Byron, Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, Chapter 15.0 - Accident Analyses
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Section 10.3 Through Section 15.1
NRC 2002-0019, License Amendment Request 224 Control Room Habitability
NRC-03-0007, Proposed License Amendment for Implementation of Alternative Radiological Source Term Methodology
CNL-15-039, Severe Accident Management Alternatives for Reactor Coolant Pump Seals
W3F1-2005-0004, Supplement to Amendment Request NPF-38-249 Extended Power Uprate Waterford Steam Electric Station, Unit 3
LIC-98-0005, Provides Submittal as Suppl to Ltr Re SAR Update & 10CFR50.59 Rept for Fort Calhoun Station.Attachment a Describes Procedure Change & Summarizes Safety Analysis
IA-85-130, Responds to FOIA Request for License Application for Mallinckrodt Radiopharmacies in Philadelphia,Pa,Pittsburgh, Pa,St Louis,Mo & Cleveland,Oh.Documents Available in Pdr. Documents 24 & 25 Partially Withheld (Ref FOIA Exemption 6)
LR-N10-0140, Salem - Attachment 1, Offsite Dose Calculation Manual, Revision 23
LR-N14-0084, Salem, Units 1 and 2, Offsite Dose Calculation Manual, Revision 27
L-PI-10-076, Calculation No. GEN-PI-083, Revision 1, Locked Rotor Accident (LRA) Analysis Using AST, Attachment 5
NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 14 - Safety Analysis
DCL-21-040, Responses to NRC Requests for Additional Information on LAR 20-03, Proposed Technical Specifications and Revised License Conditions for the Permanently Defueled Condition
LR-N19-0042, 2018 Annual Radioactive Effluent Release Report (ARERR)
VR-SECY-20-0018, Report to Congress on Abnormal Occurrences: Fiscal Year 2019 (Caputo)
10 CFR 35.2204, Records of Molybdenum-99, Strontium-82, and Strontium-85 Concentrations
STC-22-057, Proposed Rule: Harmonization of Transportation Safety Requirements with International Atomic Energy Agency Standards (Rin 3150-AJ85; NRC-2016-0179) (STC-22-057)
05000354/LER-1994-003, :on 941121,average Power Exceeded License Power Limit.Caused by Personnel Errors.Counseled Personnel & Placed Limitations on Reactor Power and Thermal Limits Until Feedwater Transmitters Calibr
05000285/LER-1984-025, :on 841207,gaseous Leak in Waste Gas Vent Header Caused Stack Iodine Monitor RM-060 to Initiate Ventilation Isolation Actuation Signal.Leak Located & Stopped
05000285/LER-1984-017, :on 840803,unplanned Actuation of Ventilation Isolation Actuation Sys Occurred.Caused by Containment Air Activity Particulate Process Monitor RM-050 Trip.Monitor Discriminator Sensitivity Adjusted
05000254/LER-1994-004-04, :on 940228,results of Feedwater Flow Testing Found Flow Indications in Nonconservative Direction.Cause Not Determined.Management Issued Special Instructions.W/
PNO-I-81-089, on 810816,unusual Event Declared When Operator Noticed Inservice Gaseous Waste Decay Tank & Surge Tank Pressures Decreased,Indicating Sys Leakage.Apparently Caused by Intrasystem Leakage
PNO-I-81-074, on 810706,small Portion of Plant Stack Effluent Was Found Blowing from Partially Covered Duct Connecting New Radwaste Bldg to Stack.Caused by Back Pressure Which Blew Hole in Plastic Cover Over Ductwork
NUREG-1100 Volume 35, Congressional Budget Justification Fiscal Year 2020
RAIO-0918-61868, LLC Supplemental Response to NRC Request for Additional Information No. 356 (Erai No. 9253) on the NuScale Design Certification Application
WO 18-0004, Response to Request for Additional Information Re License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of .
05000251/LER-1987-025-01, :on 871012,containment Vent & Control Room Ventilation Isolation Actuated.Caused by High Levels of Rb-88 in Containment Following Unit Shutdown.Containment Activity Level Returned to Normal
05000251/LER-1987-025-02, :on 871012,containment & Control Room Ventilation Isolation Occurred.Cause by High Levels of Rb-88 in Containment Following Unit Shutdown.Particle Grab Sample Taken & Leak Rate Calculation Performed
L-88-122, Forwards Summary of mgt-on-shift Weekly Rept for Wk Starting 880229,per NRC 871019 Order
GO2-95-277, Reactor Power Uprate Startup Test Rept, for WNP-2
RAIO-0818-61468, LLC Response to NRC Request for Additional Information No. 356 (Erai No. 9253) on the NuScale Design Certification Application
NLS2005075, Calculation Nedc 05-031, Review of Alion Calculation ALION-CAL-NPPD-3236-001, Radiological Dose Analysis for a Fuel Handling Accident (FHA) at Cooper Nuclear Station
DCL-03-034, License Amendment Request 03-05 Revision of Technical Specification 3.7.10, Control Room Ventilation System, TS 3.7.12, Auxiliary Building Ventilation System, and TS 5.5.11, Ventilation Filter Testing Program
RA-02-008, Transmittal of Special Report, Transuranic and Other Hard to Detect Radionuclides in Maine Yankee Sample Media
NUREG-0016, Revision 2 Calculation of Release of Radioactive Materials in Gaseous and Liquid Effluents from Boiling-Water Reactors GALE-BWR 3.2 Code