W3F1-2017-0003, Responses to Request for Additional Information Set 10 Regarding the License Renewal Application
L-17-253, Supplemental Information Regarding License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 805
ONS-2015-050, Emergency Plan Revision 2015-003
ONS-2015-048, Emergency Plan Implementing Procedures Manual Volume 1, Revision 2015-003
RC-14-0196, License Amendment Request LAR-06-00055 - License Amendment Request to Adopt NFPA 805 Response to Request for Additional Information
MNS-14-016, Emergency Plan, Revision 14-1
CNL-13-130, Response to NRC Request for Additional Information Regarding the Review of the License Renewal Application, B.1.41-4b, 3.0.3-1 (Requests La, 3a, 4a, 6a), B.1.23-2e, 3.4.2.1.1-2a, Tables (3.4.1, 3.4.2-3-5, 3.3.1
ONS-2013-015, Emergency Plan, Volume a, Revision 2013-01
NRC 2013-0038, Submittal of 2012 Annual Monitoring Report
L-11-322, License Amendment Request Regarding Use of a Delayed Access Circuit as a Required Offsite Circuit in Technical Specification 3.8.1, AC Sources - Operating
LR-N10-0355, Hope Creek, HC.IC-CC.SE-0002(Q), Rev. 23, Nuclear Instrumentation System - Channel B Source Range Monitor C51-K600B
LR-N10-0164, Response to NRC Request for Additional Information Dated April 12, 2010, Related to the Severe Accident Mitigation Alternatives Review
RC-18-0091, License Amendment Request - LAR-16-01490 National Fire Protection Association Standard 805 Program Revisions
05000530/LER-1989-001-01, :on 890303,electrical Grid Disturbance Resulted in Opening Main Generator Output Breakers,Low Pressure Reactor Trip & Turbine Trip.Caused by Steam Bypass Control Sys Malfunction.Plant Stabilized
L-PI-05-012, Request for Relief No. 17, Revision 0, for the Plant 3rd 10-year Interval Inservice Inspection Program
U-603019, Requests Initial Licensing Examination to Be Conducted in Nov of 1998.There Are 6 RO License candidates,2 Upgrades to Senior RO Licenses & 7 to 10 Senior RO Licenses
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
L-01-220, Rev 0 to Grand Gulf In-Plant Safety Relief Valve Test Final Rept
ST-HL-AE-2250, Forwards Annotated Revs to Fsar,Including Tables 3.9-1.2, Active Valves (BOP Sys) & 6.2.4-1, Containment Isolation Sys Failure Modes & Effects Analysis Re Deficiency Reported on 831118 Involving Target Rock Solenoid Valves
DCL-85-112, Public Version of Revised Emergency Plan Implementing Procedures,Including Table of Contents,Rev 4 to EP OR-1 Re Offsite Support & Assistance & Rev 3 to OR-2 Re Release of Info to Public & 850401 Release Memo
BECO-91-047, Beco Annual Rept 1990, & Securities & Exchange Commission Form 10K
LD-89-107, Forwards Addl Info Re CESSAR-DC Chapter 7
TXX-7068, Forwards Table of Interpretations/Clarifications of Codes, Stds & Reg Guides,Providing Refs for Util Compliance W/Cable Tray Hanger Design & Acceptance Criteria,Per NRC
TXX-9924, Forwards Responses to Questions by NRC Re Application for Amends to Licenses NPF-87 & NPF-89,by Incorporating Changes Increasing RWST low-level Setpoint from Greater than But Equal to 40% to Greater than But Equal to 45% of Span
TXX-4959, Interim Deficiency Rept CP-86-41 Re Effects of Operational Status of Plant Equipment During Mode 4 Operations.Initially Reported on 860626.Westinghouse Owners Group Developing Program to Address Concern.Next Rept by 861029
W3P88-1843, Responds to NRC Ltr Re Violations & Deviations Noted in Insp Rept 50-382/88-21.Policy Amended to Allow Correspondence to NRC for Commitment Extension to Be Signed Based on Verbal Concurrence Rather than More Detailed Review Process
B17366, Monthly Operating Rept for June 1998 for Millstone Nuclear Power Station,Unit 3
05000455/LER-1987-001-01, :on 870115,during Initial Criticality/Low Power Physics start-up Test Requiring Bistable Trip,Reactor Trip Occurred.Caused by Reactor Coolant Resistance Temp Detector Splice Failure.Splice Connection Corrected
B12607, Forwards Partial Response to NRC 870318 Questions & Comments Re NUREG-0737,Item II.D.1, Performance Testing of Relief & Safety Valves. Responses to Remaining Questions Not Yet Available,But Will Be Provided on or Before 870831
NPL-01-008, In-plant Safety Relief Valve Test Plan
05000186/LER-2019-002, Univ. of Missouri Research Reactor, Written Communication as Required by University of Missouri Research Reactor Technical Specification 6.6.c(3) Regarding a Deviation from Technical Specification 3.2.a
CNS-16-016, Emergency Plan Implementing Procedures, Including Revision 035 to RP/0/A/5000/001 and Revision 036 to RP/0/A/5000/001
3F1111-01, Document P23-1651-001, Rev. 0, Preliminary Decommissioning Cost Estimate for the Crystal River, Unit 3 Nuclear Generating Plant
05000331/LER-1981-004-03, /03L-0:on 810111,drywell Particulate Radiation Monitor B Failed Downscale.Caused by Condensate on NMC Model RAK-221F Radiation Element Re 8101B.Design Review Initiated & Particulate & Iodine Filters Examined Daily
CNRO-2003-00020, Arkansas, Unit 2 and Waterford, Unit 3, Relaxation Requests to NRC Order EA-03-009
05000247/LER-2000-001, Unit, 2 - Manual Reactor Trip Following Steam Generator Tube Rupture Dtd 03/17/2000
RNP-RA/17-0019, Supplemental Submittal to Correct Marked Up Technical Specifications (TS) Pages Transmitted with Application for Technical Specification Task Force (TSTF)-339, Relocate TS Parameters to the COLR Consistent with WCAP-14483, Revision 2
ONS-2014-066, Emergency Plan Implementing Procedures Manual Volume C, Revision 2014-014
NL-04-025, Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process
NUREG-0750 Volume 94, Nuclear Regulatory Commission Issuances: Opinions and Decisions of the Nuclear Regulatory Commission with Selected Orders (July 1, 2021 - December 31, 2021)
DCL-24-111, License Amendment Request 24-05 Revision to Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times – RITSTF Initiative 4b for TS 3.3.1 and 3.3.2
NSD-NRC-98-5702, Forwards Formal Transmittal of Correspondence W Previously Sent to NRC Informally Over Period 980223-0316.Index of Attached Matl,Encl Per Request
A07899, Provides Addl Info Re Undervoltage Detection Mods & Related License Amend Request,Per NRC 890320 Request.Actual Wiring Drawings Represent True Indication of Separation & Redundancy & Design Single Failure Proof
05000498/LER-1991-021, :on 911010,power from 1J Bus Lost When Electrician Misapplied Multimeter Test Leads in Energized Circuit,Resulting in Reactor Trip.Caused by Personnel Error. Pump Reenergized & Training Session Held
05000339/LER-1991-009-03, :on 910920,main Feed Regulating Valve B Closed Due to Driver Card Failure,Causing Reactor Trip & Safety Injection.Caused by Malfunction of Steam Dump Control Sys. Driver Card Replaced & Signal Reset