RS-17-076, License Amendment Request to Revise Spent Fuel Pool Level
RS-16-228, License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition
NG-16-0052, License Amendment Request (TSCR-159) to Revise Technical Specifications Fuel Storage Requirements
RA-17-072, License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition
RS-15-326, Request for License Amendment Regarding Spent Fuel Storage Pool Criticality Methodology for Fuel Channel Bow/Bulge
RS-13-148, License Amendment Request - Use of Neutron Absorbing Inserts in Units 1 and 2 Spent Fuel Pool Storage Racks
NOC-AE-13003012, Submittal of Operations Quality Assurance Plan Change QA-079
RS-12-061, License Amendment Request Regarding the Removal of License Conditions Addressing Interim Configurations of the LaSalle County Station Unit 2 SFP
NOC-AE-12002887, Submittal of Operations Quality Assurance Plan Change QA-075
NOC-AE-12002863, Submittal of Operations Quality Assurance Plan Change QA-074
NOC-AE-12002781, Submittal of Revised Operations Quality Assurance Plan
L-PI-11-075, Letter from Xcel Energy License Amendment Request for Spent Fuel Pool Criticality Changes
NOC-AE-11002637, Submittal of Operations Quality Assurance Plan Change QA-072
NL-14-121, Indian Point, Unit 2, Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 25
LR-N10-0355, Hope Creek, HC.IC-CC.SE-0002(Q), Rev. 23, Nuclear Instrumentation System - Channel B Source Range Monitor C51-K600B
RS-10-202, Additional Information Supporting License Amendment Request Re Use of Neutron Absorbing Inserts in Unit 2 Spent Fuel Pool Storage Racks
RCF 10-03, Response to Request for Additional Information Regarding the Renewal of Facility Operating License
L-09-009, Response to NRC Request for Information Pertaining to Diablo Canyon Independent Spent Fuel Storage Installation (ISFSI) License Amendment Request 08-001
NL-09-076, Indian Point, Units 2 and 3 - Application for Unit 2 Operating License Condition Change and Units 2 and 3 Technical Specification Changes to Add Inter-Unit Spent Fuel Transfer Requirements
NOC-AE-09002418, Submittal of Operations Quality Assurance Plan Change QA-068
NOC-AE-08002314, Submittal of Operations Quality Assurance Plan Change QA-067
NOC-AE-08002256, Submittal of Revised Operations Quality Assurance Plan
NOC-AE-18003588, Submittal of Operations Quality Assurance Plan Change QA-086
NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 9 - Auxiliary and Emergency Systems
NRC 2008-0044, Point Beach, Units 1 & 2, License Amendment Request No. 247, Transmittal of Changes to Technical Specifications Spent Fuel Pool Storage Criticality Control
RS-07-165, License Amendment Request Regarding Spent Fuel Storage Pool Criticality
NRC-07-0022, Request for Exemption Form 10 CFR 74.19(c) Regarding Physical Inventory of Special Nuclear Material Located in the Spent Fuel Pool
RS-07-044, Amergen Energy Company, LLC, Request for Amendment to Technical Specifications Section for the Inservice Testing Program
NLS2007012, Non-Proprietary Version of Response to Request for Additional Information Regarding License Amendment Request for Onsite Spent Fuel Storage Expansion
BSEP 06-0128, Request for License Amendments Regarding Fuel Design and Storage Requirements for Areva Np Fuel
1CAN070603, License Amendment Request to Support the Use of Metamic@ Polson Insert Assembles in the Spent Fuel Pool
NOC-AE-06001961, Submittal of Revised Operations Quality Assurance Plan
CNL-18-113, Response to Request for Additional Information Regarding Application to Revise Watts Bar Unit 2 Technical Specification 4.2.1, Fuel Assemblies, and Watts Bar Units 1 and 2 Technical Specifications Related to Fuel Storage (WBN-TS-17-028) .
LIC-18-0003, License Amendment Request (LAR) 18-01; Revised Fort Calhoun Station Permanently Defueled Technical Specifications to Align to Those Requirements for Permanent Removal of Spent Fuel from Spent Fuel Pool
NL-92-012, Rev 1 to Engineering Analysis (EA) EA-A-NL-92-012-02, Offsite Doses and CR Habitability Following Large Break LOCA to Justify Continued Operation Until Cycle 12
NRC-2016-0079, Federal Register Notice on Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Considerations and Containing SUNSI and Order Imposing Procedures for Access to SUNSI
U-602274, Special Rept:On 940328,meteorological Tower Instrumentation Not Returned to Svc within Allowed Out of Svc Time.Caused by Difficulty in Calibr of Input Card.Meteorological Monitoring Instrumentation Declared Operable on 940408
CNL-19-038, License Amendment Request to Make Miscellaneous Administrative Changes (WBN-TS-19-02)
NOC-AE-18003540, Submittal of Revised Operations Quality Assurance Plan
RS-05-109, Revised No Significant Hazards Consideration Supporting the Request for License Amendment Related to Onsite Spent Fuel Storage Expansion
1CAN060404, Withdrawal of License Amendment Request to Modify Fuel Assembly Enrichment, Spent Fuel Pool (SFP) Boron Concentration Technical Specification (TS) 3.7.14, the Loading Restrictions in SFP in TS 3.7.15, and to Modify Fuel Storage Design Fea
NOC-AE-04001686, Submittal of Operations Quality Assurance Plan Change QA-056
NOC-AE-04001665, Submittal of Revised Operations Quality Assurance Plan
RNP-RA/03-0038, Request for Technical Specifications Change Re Credit for Spent Fuel Storage Pool Dissolved Boron
NL-20-0403, Response to Request for Additional Information Regarding License Amendment Request to Update the Spent Fuel Pool Criticality Safety Analysis and Revise Technical Specification (TS) 3.7.15 Spent Fuel Assembly Storage
NL-20-012, Application to Revise Provisional Operating License and Technical Specifications
B12544, Proposed Tech Specs,Incorporating Guarantee That New motor-operated Valves Scheduled for Installation During 1987 Refueling Outage Remain in Respective Positions,Causing No Adverse Effects to ECCS
B17621, Application for Amend to License DPR-21,reflecting Permanently Defueled Condition of Unit 1,Tech Specs Administrative Controls Section as Allowed by Guidance Contained in NRC Administrative Ltr 95-06
B12067, Proposed Tech Specs Allowing Implementation of Measures Approved by NRC as One Element of Response to Previously Addressed Small Break LOCA Issue
B12828, Proposed Tech Specs,Renumbering Manual High Pressure Safety Injection Throttle Valves for Consistency W/Plant Loop Numbering Scheme
A07250, Forwards Addl Info Re Third 10-yr Interval Inservice Testing Program,Per NRC 880511 Request.Revised Third 10-yr Inservice Testing Program Will Be Submitted by 880901
ULNRC-03510, Forwards Exam Outline as Required by NUREG-1021, Operator Licensing Examiner Stds
RS-22-064, License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies with Proposed Change to Technical Specifications Section 4.3.1
NL-22-0288, License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel
HL-5166, Requests Exemption from 10CFR70.24(a), Criticality Accident Requirements, Requirements for Units 1 & 2.Criticality Accident Monitoring Sys Unnecessary
HL-2002, NPDES Noncompliance Notification:On 911230,chlorinated Water Discharged Into Altamaha River Due to Internal Failure of Valve Which Isolates Chlorine Addition Sys from Svc Water Sys Intake.Failed Valve Replaced
NRC-94-4328, Forwards Draft Outlines for AP600 Test & Analysis Repts. During 940924 Telcon,Opportunity for Dec Meeting Discussed. Westinghouse Believes Meeting to Provide Good Opportunity to Discuss Outlines W/Nrc Staff
NL-22-0609, Response to NRC Requests for Information License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel
L-2023-077, License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis
RS-11-067, Response to Request for Additional Information Regarding Unit 2 Spent Fuel Pool Storage Racks
NOC-AE-06002030, Submittal of Operation Quality Assurance Plan Change QA-060
NOC-AE-16003326, Submittal of Revised Operations Quality Assurance Plan, Revision 22
W3F1-2003-0079, 6 to EP-002-050, Offsite Dose Assessment (Manual)
NL-19-023, Response to Request for Additional Information (RAI) - Proposed License Amendment Request Regarding Storage of Fresh and Spent Nuclear Fuel in the Spent Fuel Pool
NL-22-0289, License Amendment Request to Revise Technical Specification 4.3 Fuel Storage to Correct Tabulated Values from the Associated Spent Fuel Pool (SFP) Criticality Analysis
RS-09-133, LaSalle, Units 1 & 2 - License Amendment Regarding the Use of Neutron Absorbing Inserts in Unit 2 Spent Fuel Pool Storage Racks
L-2024-177, Revised Response to Requests for Additional Information Regarding Turkey Point License Amendment Request 277, Updated Spent Fuel Pool Criticality Analysis
NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Licensing Report on the Inter-Unit Transfer of Spent Nuclear Fuel at the Indian Point Energy Center
RS-21-065, License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies with Proposed Change to Technical Specifications Section 4.3.1
05000341/LER-1989-014, :on 890603 & 18,discovered That Both Channels Bypass/Unbypass Functions Were Slightly Above Limits Allowed in Tech Specs.Caused by Emphasis on Checking Bypass Function of Bistable.Channels Properly Calibrated
05000213/LER-1986-037, :on 860708,opening of Manual Isolation Valves Conflicted W/Tech Spec Definition of Containment Integrity. Caused by Imprecise Wording & Misinterpretation of Tech Specs.Surveillance Procedure Revised
BVY 08-007, Technical Specification Proposed Change No. 276 Revision to TS Sections 3.3/4.3 for Control Rod System
B12414, Application for Amend to License NPF-49,extending 18-month Surveillance Testing Requirements for Diesel Generator Up to 4 Months Beyond Max Allowed by Tech Spec Section 4.0.2,on one-time Basis
05000267/LER-1988-013, :on 881007,Class IA Snubber BFS-824 Not Maintained/Surveilled Per Tech Spec 4.3.10.Caused by Inadequate procedure.BFS-824 Incorporated Into Class I Snubber Listing
05000352/LER-1987-007, :on 870223,discovered Eight Surveillance Test Procedures for Intermediate Range Monitor (IRM) Channel Functional Test Did Not Include Check of IRM Inoperative Function.Caused by Procedural Deficiency
L-PI-05-075, Supplement to License Amendment Request (LAR) to Revise the Spent Fuel Pool Criticality Analyses and Technical Specifications (TS) 3.7.17, Spent Fuel Pool Storage and 4.3, Fuel Storage
1CAN100601, Supplement to License Amendment Request to Support Use of Metamic Poison Insert Assemblies in Spent Fuel Pool
05000461/LER-1992-007, :on 920515 & 0623,determined That Previously Performed Surveillance Test Procedures for Loss of Offsite Power Testing Not Conducted Per Ts.Caused by Improper Interpretation of Ts.Test Procedure Revised
05000445/LER-1992-005, :on 920218,operator Misinterpreted Procedure Step & Inadvertently Unblocked Actuation Signal Causing ESF Actuation.Caused by Personnel Error.Event Reviewed.Personnel Trained
HL-2260, NPDES Noncompliance Notification:On 920529,all 3 Unit 1 Cooling Towers Were Overflowing.Caused by Restriction in Cooling Tower Return Flow.Cooling Tower Screens Cleaned
05000387/LER-1984-032, :on 840323,staff Determined That Surveillance Testing of Ionization Fire Detectors Not Performed within Time Allowed by Tech Specs.Caused by Inconsistency Between Unit 1 & 2 Tech Specs.Tests Performed
05000354/LER-1995-018-01, :on 950720,surveillance Test Was Missed Due to Procedure & Personnel Error & Automatic Depressurization & HPCI Sys Inoperability.Memo Sent to All I&C Supervisors & Technicians Re Event
05000324/LER-1982-106-03, /03L-0:on 820917,while Reviewing Surveillance Procedures,Determined That Emergency Bus Degraded Voltage Channel Function Test Not Sufficient to Verify Operability of Emergency Bus Degraded Voltage Relays.Test Revised
05000416/LER-1983-003-01, /01T-0:on 830108,limiting Condition for Operation Entered Due to Intermediate Range Monitor Functional Test Not Being Performed within Required Time Period.Caused by Personnel Error.Personnel Made Aware of Error
05000325/LER-1982-072-03, /03L-0:on 820630,while Investigating Cause of Reactor Scram,Discovered Tech Spec-required Surveillance of Emergency Bus Degraded Voltage & Undervoltage Relays Not Performed.Caused by Personnel Error.Review in Progress
05000366/LER-1982-027-03, /03L-0:on 820325,while Refueling,Reactor Bldg Exhaust Vent Radiation Monitor Functional Test & Calibr Exceeded Surveillance Interval by 2 Days.Caused by Personnel Failure to Schedule Work Required
1CAN039303, Application for Amend to License DPR-51,updating RCS Leakage Test Pressure in TS 4.3.2 to Agree W/Requirements of ASME Boiler & Pressure Vessel Code,Section XI (Through Winter 1981 Addenda)
05000395/LER-1982-056, Forwards LER 82-056/03L-0.Detailed Event Analysis Encl
NOC-AE-200036, Submittal of Operations Quality Assurance Plan Change QA-088 and Revision 24
05000213/LER-1981-002-03, /03L-0:on 810322,operator Noticed Mar Readings of HPSI Pump Closed Discharge Pressure Had Not Been Plotted. Caused by New Operators Not Knowledgeable About Test or Requirements & Procedure Not Spelled Out
1CAN040302, License Amendment Request to Modify the Fuel Assembly Enrichment, the Spent Fuel Pool (SFP) Boron Concentration TS 3. 7.14, the Loading Restrictions in the SFP in TS 3,7,15m and to Modify the Fuel Storage Design Features in TS 4.3
05000335/LER-2076-029, Contrary to Tech Spec 4.3.3.3.1, Required Channel Check of 2 Triaxial Accelerographs Was Not Performed within Required Time Frame
L-92-173, Responds to Violations Noted in Insp Repts 50-250/92-10 & 50-251/92-10.Corrective Actions:Instrument & Control Maint Initial & Continuing Training Programs Revised to Incorporate self-checking
L-88-239, Responds to Generic Ltr 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR Plants. Program Implemented to Monitor,Identify,Evaluate & Correct Small Primary Coolant Leaks
L-79-188, Responds to NRC Re Violations Noted in IE Insp Repts 50-250/79-11 & 50-251/79-11.Corrective Actions:Qa Activity Audits Revised & Strengthened
GO2-91-036, Application for Amend to License NPF-21,revising Tech Spec 4.3.6-1 Re Control Rod Block Instrumentation Surveillance Requirements
GO2-89-214, Application for Amend to License NPF-21,amending Tech Spec 4.3.6-1, Source Range Monitor/Intermediate Range Monitor (Srm/Irm) Detector Not-Full-In Functional Test Such That Required Weekly Channel Test Surveillance Met as Stated
L-83-554, Forwards Procedures to Support Util Actions Re Generic Ltr 83-28 on Generic Implications of Salem ATWS Events
PNP 2012-071, Response to Request for Additional Information — License Amendment Request — Replacement of Spent Fuel Pool Region I Storage Racks
05000277/LER-2011-002, For Peach Bottom, Units 2 and 3 - Condition Prohibited by Technical Specifications Due to Degraded Spent Fuel Pool Racks Boraflex Panels
05000255/LER-2008-004, Noncompliance with Technical Specification 4.3.1.1.b
L-PI-04-075, Supplement to License Amendment Request (LAR) to Revise the Spent Fuel Pool Criticality Analyses and Technical Specifications (TS) 3.7.17, Spent Fuel Pool Storage and 4.3, Fuel Storage
1CAN120302, Supplement to Amendment Request to Changes to the Spent Fuel Pool Loading Restrictions
L-PI-04-129, License Amendment Request (LAR) to Revise the Spent Fuel Pool Criticality Analyses and Technical Specifications (TS) 3.7.17, Spent Fuel Pool Storage and 4.3, Fuel Storage
BSEP 02-0008, Response to Request for Additional Information Re Inservice Inspection Program Relief Request for Service Water System Piping non-code Repair
1CAN110302, Supplement to Amendment Request to Changes for the Spent Fuel Pool Loading Restrictions
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
NOC-AE-03001525, Submittal of Operations Quality Assurance Plan Change QA-054
NOC-AE-17003489, Submittal of Operations Quality Assurance Plan Change QA-085
L-PI-09-094, Independent Spent Fuel Storage Installation, Support for License Amendment Request to Modify TN-40 Cask Design (Designated as TN-40HT)
NOC-AE-03001553, Submittal of Operations Quality Assurance Plan Change QA-055
RA-19-0424, 2 to Updated Final Safety Analysis Report, Chapter 4, Reactor
SECY-23-0069, Weekly Information Report Week Ending August 4, 2023
L-2024-188, Supplement to License Amendment Request 277, Updated Spent Fuel Pool Criticality Analysis
CP-201300257, License Amendment Request (LAR) 13-01, Revision to Technical Specifications 3.7.16, Fuel Storage Pool Boron Concentration, 3.7.17, Spent Fuel Assembly Storage, 4.3, Fuel Storage, and 5.5 Programs & Manuals
NOC-AE-14003071, Submittal of Revised Operations Quality Assurance Plan