NG-17-0095, Report of Facility Changes, Tests and Experiments, and Commitment Changes
L-16-298, Response to a Request for Additional Information Regarding a License Amendment Request for Upper Containment Pool (Ucp) Gate Installation in Modes 1, 2, and 3, and Drain-Down of the Reactor Cavity Portion of the Ucp in Mode 3
NL-13-1434, Application for Technical Specification Change to Revise Action Statements for Inoperable Control Room Air Conditioning Subsystems
GNRO-2012/00132, License Amendment Request for Revision of Technical Specification Allowable Value for Primary Containment and Drywell Isolation Instrumentation Function 3.c RCIC Steam Supply Line Pressure - Low
RBG-47176, Supplemental Information Changes to Technical Specification 3.3.6.1, Primary Containment and Drywell Isolation Instrumentation
RBG-47157, License Amendment Request, Changes to Technical Specification 3.3.6.1, Primary Containment and Drywell Isolation Instrumentation
L-MT-11-022, 002 Monticello - Technical Requirements Manual, Revision 7
NL-18-0074, License Amendment Request for Technical Specification 3.3.8.1 Regarding Degraded Voltage Protection
RS-18-020, Application to Revise Technical Specifications to Modify the APRM Channel Adjustment Surveillance Requirement
LR-N17-0044, Hope Creek - License Amendment Request for Measurement Uncertainty Recapture (Mur) Power Uprate
NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant
GO2-10-099, Response to Request for Supplemental Information for Completion of Acceptance Review for Prnm/Arts/Mellla System Upgrade
RS-10-116, Additional Information Supporting Request for License Amendment Regarding Measurement Uncertainty Recapture Power Uprate
L-MT-10-008, Technical Requirements Manual
NG-09-0507, Submittal of Tests, Experiments, Fire Plan and Commitment Changes for 07/14/07 Through 06/01/09
L-MT-09-009, Technical Requirements Manual
L-MT-08-049, Submittal of Response to Requests for Additional Information for License Amendment Request for Power Range Neutron Monitoring System Upgrade
NG-08-0366, Technical Specification Change Request (TSCR-106): 4160 Volt Emergency Bus Undervoltage (Degraded Voltage) Maximum Allowable Value Affected Technical Specification: Section 3.3.8.1
TSTF-06-19, TSTF-477, Revision 2, Add Action for Two Inoperable Control Room AC Subsystems
RBG-47896, Response to NRC Baseline Inspection Report 05000458/2018012
RA-18-0135, Request for License Amendment - Technical Specification 3.7.4, Control Room Air Conditioning (AC) System
L-MT-07-009, License Amendment Request: Revision to the Allowable Values and Surveillance Intervals for the Low Pressure Coolant Injection Loop Select Logic Time Delay Relays
NRC-19-0054, DTE Energy Company - License Amendment Request to Revise Technical Specifications to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle
RS-05-062, Additional Information Supporting the Request for License Amendment Related to 21-Month Fuel Cycle
M190008, GE-Hitachi Nuclear Energy Americas, LLC - Peak Cladding Temperature/10 CFR 50.46 for Advanced Boiling Water Reactor (ABWR) Design Certification Renewal Application, Supplemental Information
M180068, GE-Hitachi Nuclear Energy Americas, LLC - Advanced Boiling Water Reactor Design Certification Rule Renewal Application - Additional Information for Response to Rals 06.03-4 Through 06.03-9
NRC-93-0061, Application for Amend to License NPF-43,revising TS to Extend Instrument Calibr Intervals to 36 Months for Selected Instrumentation,Per BWROG Licensing Topical Rept NEDC-32160P,Dec 1992.GE Proprietary Rept Encl.Rept Withheld
RS-04-105, Additional Information to Support Review of the Request for Technical Specification Changes Related to Primary Containment Isolation Instrumentation (Main Steam Line Flow-High)
RS-04-110, Additional Information to Support Review of the Request for Technical Specification Changes Related to Primary Containment Isolation Instrumentation (Main Steam Line Flow-High)
PLA-4055, Forwards Proposed Amend 117 to License NPF-22 Re Power Uprate W/Increased Flow
BVY 03-115, Technical Specification Proposed Change No. 257 Implementation of Arts/Smella at VYNPS Supplemental Information and Proposed Allowable Value, Attachment 2, Calculation VYC-0693A
NLS2003077, License Amendment Request to Revise Technical Specification (TS) Surveillance Requirement (SR) 3.3.2.1.4 and TS Table 3.3.2.1-1 for Mathematical Symbols and Use of Allowable Values
NRC-95-0096, Application for Amend to License NPF-43,revising TS Re Sys Testing,Instrumentation Calibr,Component Insp,Component Testing,Response Time Testing & Logic Sys Functional Tests to Allow one-time Extension of Surveillance Intervals
NRC-98-0040, Application for Amend to License NPF-43,requesting to Allow one-time Extension of Surveillance Intervals to Delay Shutdown for Upcoming Sixth Refueling Outage (RFO6) Until 980904
NG-98-0531, Forwards Comments on NRC Draft SE for DAEC Conversion to Improved TS Based Upon NUREG-1433.Draft SE Contains Util Markups & Typed Inserts
RBG-25368, Application to Amend License NPF-47,revising Tech Specs Re Surveillance Interval of Recirculation Flow Transmitters Which Provide Input to Reactor Protection Sys.Fee Paid
RBG-28399, Application for Amend to License NPF-47,clarifying License Condition 2.C(13) & Revising Tech Spec Table 3.3.6-2, Item 1.b, High Power Setpoint. Fee Paid
NG-97-1010, Proposed Tech Specs Change for Instrument Setpoints
NG-97-0846, Application for Amend to License DPR-49,consisting of Request for TS Change RTS-293 Which Would Revise Definitions of LSSS & Instrument/Channel Calibration to Ref New Program Being Added to TS for Control of Instrument Setpoints
U-602683, Provides Response to NRCs RAI Re Adequacy & Availabilty of Design Bases Info at Util,Per 10CFR50.54(f)
BSEP-96-0414, Application for Amends to Licenses DPR-71 & DPR-62,revising TSs to Format Consistent w/NUREG-1433,rev 1.Vols 1-15 of Improved TSs Encl
PLA-8005, Response to Request for Additional Information Regarding License Amendment to Revise Reactor Steam Dome Pressure - Low Instrumentation Function Allowable Value (PLA-8005)
NG-96-2322, Application for Amend to License DPR-49,converting Std TS Re NUREG-1433.Detailed Description & Justification for Proposed TS Amend Consists of 20 Vols & Summarized in Attachment 1
JPN-92-050, Forwards Response to RAI Re 920612 Application for Amend to License DPR-59 Re Power Uprate & Proposed Changes for GE NEDC-32016P Power Uprate Safety Analysis.Ge Power Uprate Safety Analysis Changes Withheld
HL-4812, Forwards Response to NRC 950310 RAI Re Util 950113 Power Uprate Submittal.Info Relative to Plant Setpoint Methodology & Calculations Also Encl
BSEP-95-0112, Forwards Supplemental Info Re 931028 Request for License Amends to Increase Instrument Surveillance Test Intervals & Allowable out-of-svc Times Addressed in TS 3/4.3,as Result of Discussions W/Nrc During 950208 Meeting & 950216 Telcon
RBG-40006, Requests Issuance of 931208 Proposed Amend to License NPF-47 to Allow One Time Extension of Specific Instrumentation & Electrical Surveillance Interval to Support Current Fuel Cycle Outage Schedule Before 940216
RBG-39815, Forwards Summary of Results from Instrument Setpoint Methodology Group Setpoint Calculations & Topical Rept NEDC-31336 for Plant,Per Util ,Plant Ser,Section 7.1.2.2 (NUREG-0989,Suppl 3) & Util
PY-CEI-NRR-2276, Forwards Response to NRC 980219 Request for Addl Info Re 950829 Application for License Amend to Revise Several TS Instrumentation Allowable Values
PY-CEI-NRR-1969, Application for Amend to License NPF-58,revising Tech Specs Allowable Values & Trip Setpoints for Selected Plant Process Instrumentation Using Instrument Setpoint Methodology Discussed in Util (PY-CEI/NRR-1706L)
JPN-93-016, Forwards Response to NRC Second Request for Addl Info Re Power Uprate Submittal Concerning Effects of Increased Process & Ambient Temp & Pressures on Instrument Accuracy. Calculations Supporting Response Encl
AECM-90-0036, Provides Addl Info to Support 880630 Proposed Amend to License NPF-29,extending Reactor Protection Sys Instrumentation Surveillance Test Intervals & Allowable Outage Times,Per GE Topical Rept NEDC-30851P
PY-CEI-NRR-1146, Forwards Nonproprietary & Proprietary Calculation of Proposed Rhr/Rcic Steamline Flow-High Setpoints Using GE Instrument Setpoint Methodology. Proprietary Rept Withheld
GNRO-2019/00028, Supplement to Revise Technical Specification (TS) 3.3.1.1, Reactor Protection System (RPS) Instrumentation, and TS 3.3.4.1, End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation
GO2-94-029, Forwards Proprietary Drf A00-01932-5 to GE-NE-208-23-1293-1, Power Uprate Condition Setpoint Calculations for WPPSS WNP-2 & NEDC-32141P,Section 5, Instrumentation & Control in Response to 931109 Rai.Repts Withheld
GO2-88-025, Forwards Response to Re Violations Noted in Insp Rept 50-397/87-19.Corrective Actions:Ped S218-E-C640 Issued to Rescind Previous Design Change & Document Acceptance of Existing Conductor motor-operated Valve Circuits
PLA-3850, Responds to NRC 920817 Request for Addl Info on Proposed Power Uprate.Info Supplied by Ge.Geitas Is GE Proprietary Computer Program Used to Automate Drift Evaluations Described in Section 4.4 of NEDC-31336
GO2-17-015, Energy Northwest - Transmittal of Response to Request for Additional Information, Columbia MUR LAR: Electrical Instrument and Controls Branch (Eicb) and Reactor Systems Branch (Srxb)
GNRO-2013/00001, Response to Electronic Request for Additional Information Supporting Completion of Safety Evaluation for the License Amendment Request for Revision of Technical Specification Allowable Value for Primary Containment and Drywell.
RBG-47211, Response to Request for Information Changes to Technical Specification 3.3.6.1, Primary Containment and Drywell Isolation Instrumentation
TSTF-06-22, TSTF-477, Revision 3, Add Action for Two Inoperable Control Room AC Subsystems
RBG-46051, Supplement to License Amendment Request 2002-08, Division 1, 2 & 3 Degraded Voltage Set Point Revision Due to Updated Calculations & Installation of Improved Relays
PY-CEI-NRR-0969, Discusses Proposed Changes to Commitments 7,14,16,4,8 & 10 to Resolve Issues Remaining from Plant SER (NUREG-0887),for Approval
BSEP-98-0090, Provides Comments on Draft SE Re Conversion to Improved Tech Specs.Encl 2 Provides Draft SE pages,marked-up to Reflect Comments as Well as Addl Editorial Comments
HL-5579, Forwards Proprietary & non-proprietary Response to 980210 RAI Re License Amend Request to Increase Authorized Max Power Level to 2,763 Mwt.Topical Rept NEDO-32749 Encl. Proprietary Info Withheld