GNRO-2017/00009, Proposed Alternative with 10 CFR 50.55a(z)(1), Use of Boiling Water Reactor Vessel and Internals Project (BWRVIP) Guidelines
ULNRC-06327, Operating Quality Assurance Manual (Oqam) Revision 32
GNRO-2015/00024, Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt Technical Specification Task Force TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month
CNL-15-026, Submittal of Pre-operational Test Instruction
CNL-15-025, Submittal of Pre-operational Test Instruction 2-PTI-999-01, Rev. 0, Operational Vibration Testing
CNL-15-024, Submittal of Pre-operational Test Instruction 2-PTI-043-02, Rev. 0, Primary Sampling System
CNL-14-230, Submittal of Pre-operational Test Instruction, 2-PTI-074-02B, Rev. 0, RHR Hft Heatup/Cooldown
CNL-14-219, Submittal of Pre-operational Test Instruction, 2-PTI-999-02, Rv. 0, Thermal Expansion
LIC-15-0003, Revision of Standard Practice Procedures Plan
RS-14-210, Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design- Basis External Events (Order Number EA-12-049)
RS-13-256, Additional Information Regarding Request for License Amendment to Revise Battery Surveillance Requirements
3F0413-07, Request for Approval of the Certified Fuel Handler Training and Retraining Program
L-2012-323, Strainer Fiber Bypass Test Protocol
L-2012-077, License Amendment Request No. 220, Permanent Alternate Repair Criteria (H*) for Steam Generator Expansion Region
L-2012-191, Responses to Requests for Additional Information Related to LAR 210, DC Sources
NL-11-2155, HNP-ISI-ALT-14, Version 1 Temporary Non-Code Repair of Plant Service Water Piping
NL-11-1451, Pilot 10 CFR 50.69 License Amendment Request, Draft Risk-Informed Categorization Procedures
L-11-081, Submittal of Snubber Program for Beaver Valley Power Station Unit Nos. 1 and 2
W3F1-2011-0033, UNT-005-014, Rev. 302, Offsite Dose Calculation Manual
SBK-L-11044, Response to Request for Additional Information Regarding License Renewal Environmental Report
TSTF-14-02, Transmittal of TSTF-529, Revision 2, Clarify Use and Application Rules
RS-14-029, Standard Operating Procedures for Braidwood Station'S Fisheries Monitoring Program in the Kankakee River and Horse Creek
DCL-11-104, Attachment 13: Inter-Departmental Administrative Procedure CF2.ID9, Rev. 2, Software Quality Assurance for Software Development.
DCL-11-104, Attachment 12: Revision 10 to CF2.ID2, Software Configuration Management for Plant Operations and Operations Support.
DCL-11-104, Attachment 11: Revision 8 to Procedure CF2, Computer Hardware, Software and Database Control.
TMI-11-055, PSC Procedure Sq 6.0, Grease Cap Removal Data Sheet 6.0, July 31, 2009, Rev. 0
LR-N10-0355, Salem/Operations, SC.OP-AB.ZZ-0001(Q), Rev. 13, Adverse Environmental Conditions.
LR-N10-0355, Salem/Operations, SC.OP-AB.CR-0003(Q), Rev. 6, Control Room Habitability.
LR-N10-0355, Pseg Nuclear LLC Maintenance, Salem Common Procedure SC.IC-CC.NIS-0011(Q), Rev. 6, N31 Source Range.
LR-N10-0355, Pseg Nuclear LLC Maintenance, Salem Common Procedure, SC.IC-CC.NIS-0012(Q), Rev. 7, N32 Source Range.
LR-N10-0355, Salem/Operations, S2.OP-ST.RC-0008(Q), Rev. 32, Reactor Coolant System Water Inventory Balance.
LR-N10-0355, Salem/Operations, S2.OP-ST.CAN-0007(Q), Rev. 24, Refueling Operations - Containment Closure.
LR-N10-0355, Salem/Operations, S2.OP-SO.RC-00004(Q), Rev. 15, Identifying and Measuring Leakage.
LR-N10-0355, Salem/Operations, S2.OP-SO.CVC-0002(Q), Rev. 38, Charging Pump Operation.
LR-N10-0355, Salem/Operations, S2.OP-SO.125-0005(Q), Rev. 24, 2A 125VDC Bus Operation.
LR-N10-0355, Salem/Operations, S2.OP-IO.ZZ-0007(Q), Rev. 15, Cold Shutdown to Refueling.
LR-N10-0355, Salem/Operations, S2.OP-IO.ZZ-0006(Q), Rev. 40, Hot Standby to Cold Shutdown.
LR-N10-0355, Salem/Operations, S2.OP-AR.ZZ-0005(Q), Rev. 19, Overhead Annunciators Window E.
LR-N10-0355, Salem/Operations, S2.OP-AR.ZZ-0003(Q), Rev. 17, Overhead Annunciators Window C..
LR-N10-0355, Salem/Operations, S2.OP-AB.ZZ-0002(Q), Rev. 3, Flooding.
LR-N10-0355, Salem/Operations, S2.OP-AB.RHR-0001(Q), Rev. 17, Loss of Rhr.
LR-N10-0355, Salem/Operations, S2.OP-AB.RC-0002(Q), Rev. 8, High Activity in Reactor Coolant System.
LR-N10-0355, Salem/Operations, S2.OP-AB.RC-0001(Q), Rev. 10, Reactor Coolant System Leak.
LR-N10-0355, Salem/Operations, S2.OP-AB.RAD-0001(Q), Rev. 28, Abnormal Radiation.
LR-N10-0355, Salem/Operations, S2.OP-AB.LOOP-0001(Q), Rev. 23, Loss of Off-Site Power.
LR-N10-0355, Salem/Operations, S2.OP-AB.FUEL-0001(Q), Rev. 5, Fuel Handling Incident.
LR-N10-0355, Salem/Operations, S2.OP-AB.CW-0001(Q), Rev. 31, Circulating Water System Malfunction.
LR-N10-0355, Salem/Operations, S2.OP-AB.CR-0002(Q), Rev. 26, Control Room Evacuation Due to Fire in the Control Room, Relay Room, 460/230V Switchgear Room, or 4KV Switchgear Room.
LR-N10-0355, Salem/Operations, S2.OP-AB.CR-0001(Q), Rev. 22, Control Room Evacuation.
LR-N10-0355, Salem/Operations, S2.OP-AB.CONT-0001(Q), Rev. 14, Containment Closure.
LR-N10-0355, Salem/Operations, S2.OP-AB.ANN-0001(Q), Rev. 22, Loss of Overhead Annunciator System.
LR-N10-0355, Pseg Nuclear L.L.C., Maintenance, S2.IC-CC.RCP-0070(Q), Rev. 18, 2PT-403 Reactor Coolant System Hot Leg Pressure Channel Ii.
LR-N10-0355, Salem/Operations, S1.OP-ST.CAN-0007(Q), Rev. 22, Refueling Operations - Containment Closure.
LR-N10-0355, Salem/Operations, S1.OP-ST.RC-0008(Q), Rev. 23, Reactor Coolant System Water Inventory Balance.
LR-N10-0355, Salem/Operations, S1.OP-SO.RC-0006(Q), Rev. 26, Draining the Reactor Coolant System Less than 101 Ft. Elevation with Fuel in the Vessel.
LR-N10-0355, Salem/Operations, S1.OP-SO.RC-0005(Q), Rev. 34, Draining the Reactor Coolant System to Greater than or Equal to 101 Foot Elevation.
LR-N10-0355, Salem/Operations, S1.OP-SO.RC-0004(Q), Rev. 14, Identifying and Measuring Leakage.
LR-N10-0355, Salem/Operations, S1.OP-SO.CVC-0002(Q), Rev. 36, Charging Pump Operation.
LR-N10-0355, Salem/Operations, S1.OP-IO.ZZ-0006(Q), Rev. 33, Hot Standby to Cold Shutdown.
LR-N10-0355, Salem/Operations, S1.OP-AR.ZZ-0005(Q), Rev. 17, Overhead Annunciators Window E.
LR-N10-0355, Salem/Operations, S1.OP-IO.ZZ-0007(Q), Rev. 16, Cold Shutdown to Refueling.
LR-N10-0355, Salem/Operations, S1.OP-AR.ZZ-0003(Q), Rev. 17, Overhead Annunciators Window C.
LR-N10-0355, Salem/Operations, S1.OP-AR.ZZ-0001(Q), Rev. 47, Overhead Annunciators Window A.
LR-N10-0355, Salem/Operations, S1.OP-AB.RC-0002(Q), Rev. 9, High Activity in Reactor Coolant System.
LR-N10-0355, Salem/Operations, S1.OP-AB.RC-0001(Q), Rev. 9, Reactor Coolant System Leak.
LR-N10-0355, Salem/Operations, S1.OP-AB.RAD-0001(Q), Rev. 31, Abnormal Radiation.
LR-N10-0355, Salem/Operations, S1.OP-AB.LOOP-0001(Q), Rev. 23, Loss of Off-Site Power.
LR-N10-0355, Salem/Operations, S1.OP-AB.FUEL-0001(Q), Rev. 4, Fuel Handling Incident.
LR-N10-0355, Salem/Operations, S1.OP-AB.CW-0001(Q), Rev. 30, Circulation Water System Malfunction.
LR-N10-0355, Salem/Operations, S1.OP-AB.CR-0001(Q), Rev. 17, Control Room Evacuation.
LR-N10-0355, Salem/Operations, S1.OP-AB.CONT-0001(Q), Rev. 13, Containment Closure.
LR-N10-0355, Salem/Operations, S1.OP-AB.CR-0002(Q), Rev. 24, Control Room Evacuation Due to Fire in the Control Room, Relay Room, 460/230V Switchgear Room, or 4KV Switchgear Room.
LR-N10-0355, Salem/Operations, S1.OP-AB.ANN-0001(Q), Rev. 24, Loss of Overhead Annunciator System.
LR-N10-0355, OU-AA-103, Rev. 15, Shutdown Safety Management Program.
LR-N10-0355, OP-AA-108-111-1001, Rev. 5, Severe Weather and Natural Disaster Guidelines.
LR-N10-0355, CY-AA-170-500, Rev. 0, Meteorological Monitoring System Calibration and Maintenance.
LR-N10-0355, Salem, 2-EOP-LOPA-1, Rev. 26, Loss of All AC Power.
LR-N10-0355, Salem, 2-EOP-FRSM-1, Rev. 24, Response to Nuclear Power Generation.
LR-N10-0355, Salem, EAL Comparison Matrix
LR-N10-0355, EP-SC-111-200, Salem, Event Classification Guide Emergency Action Level Technical Bases.
LR-N10-0355, EP-SC-1 11-200, Salem, Event Classification Guide, Emergency Action Level Technical Bases.
LR-N10-0355, Hope Creek, SY-AA-101-132, Rev. 11, Threat Assessment.
LR-N10-0355, Hope Creek, OU-AA-103, Rev. 15, Shutdown Safety Management Program.
LR-N10-0355, Hope Creek, OP-HC-108-115-1001, Rev. 10, Operability Assessment and Equipment Control Program.
LR-N10-0355, Hope Creek, OP-AA-108-111-1001, Rev. 5, Severe Weather and Natural Disaster Guidelines.
LR-N10-0355, Hope Creek, HC.RP.AR.SP-001(Q) - Rev. 17, Radiation Monitoring System Alarm Response.
LR-N10-0355, Hope Creek, HC.OP-SO.SM-0001(Q), Rev. 17, Isolation Systems Operation.
LR-N10-0355, Hope Creek, HC.OP-SO.BC-0002(Q), Rev. 25, Decay Heat Removal Operation.
LR-N10-0355, Hope Creek, HC.OP-IO.ZZ-0008(Q), Rev. 29, Shutdown from Outside Control Room.
LR-N10-0355, Hope Creek, HC.OP-IO.ZZ-0005(Q), Rev. 30, Cold Shutdown to Refueling.
LR-N10-0355, Hope Creek, HC.OP-IO.ZZ-0004(Q), Rev. 82, Shutdown from Rated Power to Cold Shutdown.
LR-N10-0355, Hope Creek, HC.OP-GP.ZZ-0005(Q), Rev. 8, Drywell Leakege Source Detection.
LR-N10-0355, Hope Creek, HC.OP-EO.ZZ-0318(Q), Rev. 6, Containment Venting.
PLA-6603, Extended Power Uprate Master Test Procedure TP-199-013
NL-08-154, Supplement to Reply to Request for Additional Information Regarding Proposed Changes to Technical Specifications Regarding Diesel Generator Endurance Test Surveillance
PLA-6351, Transmittal of Startup Test Procedures Pursuant to License Conditions 2.C. (36) (B) 8 and 2.C. (36) (C)
STC-18-021, Notification of Acceptance to the Materials Control, Security Systems and Principles (S-201) Course - Chattanooga, Tn, May 21-25, 2018
L-MT-06-086, Response to Request for ECCS Surveillance Documentation to Confirm the Functionality of the LPCI Loop Select Time Delay Relays During Past Surveillance Testing
RA-19-0383, Snubber Program Plan for Fifth 10-Year Interval Inservice Testing Program
L-76-178, Responding to Letter of 4/6/1976, Letter Transmitting Supplemental Information Related to Proposed Modification of Spent Fuel Storage Facility Originally Submitted on January 28, 1976
L-76-184, Letter Transmitting Supplemental Information Related to Proposed Modification of Spent Fuel Storage Facility Originally Submitted on January 28, 1976
LR-N05-0001, Restart Readiness Hope Creek Generating Station. Includes HC.ER-AP.BB-0001 (Z) Rev. 0, HC.OP-AB.RPV-0003(Q) Rev 7, HC.OP-AR.ZZ-0008(Q) - Rev. 27
RNP-RA/04-0067, Standard Procedure, Volume 99, Book/Part 99, EGR-NGGC-0153, Rev 10, Engineering Instrument Setpoints
E900-03-014, Shonka Line Shack & Warehouse/Garage Pads FSS Survey Design
LIC-04-0073, Response to Request for Additional Information Regarding License Amendment Request, Addition of Diesel Generator Fuel Oil, Diesel Generator Lubricating Oil, & Diesel Generator Starting Air Requirements
LIC-03-0154, Relief Request Pertaining to Reactor Vessel Nozzle Inspection for Third 10-Year Interval Revision
L-2023-075, Response to Request for Additional Information (RAI) Regarding Exemption Request, License Amendment Request and Revised Response in Support of a Risk-Informed Resolution of Generic Letter 2004-02
STC-24-063, Notification of Acceptance to the Fundamental Health Physics Labs (H-122L) Course - Chattanooga, Tn January 13-17, 2025
STC-23-022, Notification of Acceptance to the Advanced Health Physics (H-201) Course - Chattanooga, Tn: June 5-9, 2023
L-76-415, Forwards Preoperational Test Procedure No. 0700080B,, Steam Generator Feedwater Hammer Test
CNL-15-047, Submittal of Pre-Operational Test Instruction, 2-PTI-062-03, Rev 0, Hft - Charging and Letdown
BW140009, Response to Request for Information - Tracking Number 13-A-0082 and Exelon Procedure MA-AA-716-021, Rev. 22, Rigging & Lifting Program
05000186/LER-2013-003, University of Missouri-Columbia Research Reactor - Written Communication as Required by University of Missouri Research Reactor Technical Specification 6.1.h(2) Regarding a Deviation from Technical Specifications 3.2.b
STC-19-046, Notification of Acceptance to the Root Case Workshop (G-205) Course - Chattanooga, Tn - September 17-20, 2019
LR-N10-0355, Salem/Operations, SC.OP-DL.ZZ-0011(Q), Rev. 9, Reactor Coolant System Heatup/Cooldown Log
L-91-004, Additional Information Supporting the Request for License Amendment Related to 24-Month Fuel Cycle
DCL-03-142, Response to NRC Request for Additional Information Regarding License Amendment Request 03-06, Revision to Technical Specification 3.8.1, AC Sources - Operating