RS-16-228, License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition
LR-N16-0092, Supplemental Information - License Amendment Request - Digital Power Range Neutron Monitoring (Prnm) System Upgrade
RA-17-072, License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition
RS-13-140, Exemption Request for Transnuclear TN-68 Casks Loaded with Fuel Bundles with Incorrect Cooling Times
L-2011-498, Units, 3 & 4 - 10 CFR 50.59 Summary Report of Changes, Tests and Experiments for Period Covering 12/04/2009 Through 05/16/2011 and Updated Technical Specification Bases
L-2011-400, Response to NRC Reactor Systems Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request No. 205
LR-N17-0044, Hope Creek - License Amendment Request for Measurement Uncertainty Recapture (Mur) Power Uprate
L-2010-259, St. Lucie, Unit 1 - License Amendment Request for Extended Power Uprate, Attachment 1; Descriptions and Technical Justifications for the Renewed Facility Operating License, Technical Specifications, and Licensing Basis Changes
L-2010-113, Turkey Point, Units 3 and 4 - License Amendment Request for Extended Power Uprate, Attachment 3; Technical Specifications Bases Markups for Information Only
RCF 10-03, Response to Request for Additional Information Regarding the Renewal of Facility Operating License
W3F1-2009-0024, License Amendment Request Technical Specification Change to Relocate Steam Generator High Level Trip Function
L-2008-245, Transmittal of 10 CFR 50.59 Summary Report of Changes, Tests and Experiments Made Without Prior Commission Approval for Period 12/09/06 - 05/11/08
NL-08-0522, License Amendment Request Regarding Removal of Spent Fuel from Unit I and Drain Down of the Spent Fuel Pool (LAR for Amendment 54)
LIC-07-0013, Special Report on Inoperability of Main Steam Line Radiation Monitor RM-064 for Post-Accident Monitoring
LR-N06-0061, Revised Technical Specification Bases for Arts/Mellla Implementation
BSEP 02-0012, Response to Request for Additional Information - Request for License Amendments to Adopt Alternative Radiological Source Term
05000325/LER-1980-042-03, /03L-0:on 800416,while Performing High Steam Line Radiation Channel Alignment & Functional Test,Drawer D12-RM-K603B,Model 238X660G3 Was Found Out of Spec.Caused by Instrument Drift.Drawer Recalibr
RNP-RA/04-0067, Standard Procedure, Volume 99, Book/Part 99, EGR-NGGC-0153, Rev 10, Engineering Instrument Setpoints
W3F1-2003-0055, TS Bases Update to NRC for Period April 8, 2003 Through July 23, 2003
B18817, License Basis Document Change Request 3-15-02 Relocation of Some TS Parameters to Core Operating Limits Report & Updating Description of Analytical Methods Used to Determine Core
NL-02-037, Technical Specification Bases Changes
NL-02-024, Submittal of Technical Specifications Bases Changes for Indian Point Unit 2
NL-20-012, Application to Revise Provisional Operating License and Technical Specifications
B12535, Application for Amend to License DPR-21,revising Tech Specs to Change Reactor Protection Sys Trip Level Settings.Amend Will Delete Electrical Power Ref & Change Both Scram Bypass Setpoints & APRM Flux Scram Trip Setting.Fee Paid
B16624, Application for Amend to License NPF-49,proposing Changes That Will Affect Nominal Trip Setpoints & Allowable Values. Proprietary Rev 5 to WCAP-10991 & non-proprietary Rev 5 to WCAP-10992,encl.Proprietary Rept Withheld,Per 10CFR2.790
SVP-99-182, Application for Amends to Licenses DPR-29 & DPR-30,to Remove Turbine EHC Low Oil Pressure Trip from RPS Trip Function Requirements in TS Sections 2.2 & 3/4.1.A
B16626, Application for Amend to License NPF-49,changing TS Bases Section 2.2 to Clarify Function of P-6 Interlock for Increasing as Well as Decreasing Reactor Power
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
NOC-AE-000471, Application for Amends to Licenses NPF-76 & NPF-80, Relocating cycle-specific RCS-related TS Parameter Limits to COLR
NG-95-0333, Provides Description of Changes to TS Bases for Shutdown Cooling Piping Safety Limit
1CAN089103, Application for Amend to License DPR-51 for Tech Specs 2.2 & 3.1.1.3 Re Pressurizer Safety Valves
HL-5591, Application for Amends to Licenses DPR-57 & NPF-5, Respectively.Amends Would Implement Some of Generic Changes to ITSs Previously Approved by NRC
PY-CEI-NRR-2216, Forwards Supplemental Response to NRC Bulletin 96-003, Potential Plugging of ECCS Strainers by Debris in Bwrs. Updated Info to NRC on Several Design Approaches Which Have Been Revised During Final Design Process,Provided
TXX-9528, LAR 95-008 to License NPF-87 & NPF-89,incorporating Revised Core Safety Limit Curves & Revised N-16 Overtemp Reactor Trip Setpoints,Resulting from Reload Analyses for CPSES Unit 2,Cycle 3
L-2010-078, Attachment 1, St. Lucie License Amendment Request Extended Power Uprate, Description and Technical Justifications for the Renewed Facility Operating License, Technical Specifications, and Licensing Basis Changes
RBG-21-572, Forwards Revs to FSAR & Proposed Tech Specs,Per Changes to Design Spec Data Sheets & Installation of New Rosemount Transmitters for Review
NRC-84-0084, Forwards Responses to Instrumentation & Control Sys Branch Tech Spec Questions,Per 840516 Request for Addl Info
L-2007-095, CFR 50.59 Summary Report, Changes, Tests, and Experiments Implemented as Allowed by 10 CFR 50.59 for the Period Covering June 13, 2005 Through December 9, 2006
1CAN119604, Forwards Response to Questions Re Pressurizer Code Safety Valves,Per Insp Rept 50-313/94-14 & Unresolved Item 313/9424-02
05000328/LER-1989-006-03, :on 890505,determined That Unit Operated in Noncompliance W/Limiting Condition for Operation Since 890411 & Reactor Trip Setpoints Nonconservative.Caused by Detectors Being Placed in Withdrawn Position.W/Undated Ltr
05000285/LER-1987-008, :on 870321,unplanned Loss of All Ac Power Occurred.Caused by Personnel Error.Caution Signs Hung on Transmitters & Info Sent to Operations & Electrical Maint Personnel Re Precautions
05000341/LER-1988-012, :on 880316,rack Isolation Valve for Reactor Protection Sys Channel C Drywell Pressure Instrument Found Closed.Caused by Failure to Fully Open Valve After 861016 Surveillance.Procedure 23.137 Revised
05000285/LER-1996-006, :on 951218,all Charging Pumps Disabled.Caused by Inadequate Administrative Control.Guidance Insuring Consistent Interpretation of Affected TSs Issued.Process for Issuing TS Interpretations Revised
05000333/LER-1992-016, :on 920326,util Received Notification from Test Facility That 8 of 11 Safety Relief Valves Actuated at Pressures Exceeding TS Limits.Caused by Setpoint Drift. All Pilot Assemblies Replaced
05000278/LER-1995-005-03, :on 951108,three of Eleven MSRVs Did Not Lift within TS +1% Tolerance Due to Small Drift in Setpoint of Valves.Refurbished Valves Have Been Properly Setup at Test Facility & Install for All MSRVs & SVs
05000285/LER-1978-046-03, /03L-0 on 781227:during Operation,A Small Leak Developed at Weld on Charging Pump CH-1A Connection to Demineralized Water Line.Caused by Vibration of Piping in Svc.Crack Was Ground Out & Rewelded
05000416/LER-1983-134-03, /03L-0:on 830829,output of RPS Reactor Water Level Channel B Loop Discovered Out of Tolerance.Caused by Instrument Drift.Instrument Loop Recalibr
05000454/LER-1991-003-09, :on 910729,identified Errors in Scaling Which Could Prevent Over Temp Delta Temp (OTDT) from Initiating Reactor Trip.Caused by Deficiency in Design That Indicated How OTDT Setpoint Was to Be Scaled
1CAN029504, Responds to NRC Citing of Unresolved Item (13/9424-02) Re Reportability of Failure of Both ANO-1 Pressurizer Code Safety Valves to Pass as-found Set Pressure Tests During Refueling Outage 1R11
05000259/LER-1983-036-01, /01T-0:on 830630,during Cycle 5 Refueling Outage, Seven of 13 two-stage Relief Valves Tested for as-found Set Pressure Initially Failed to Lift within Allowable 1% Tolerance.Cause Being Evaluated
05000285/LER-1994-002, :on 940308,boric Acid Pump Declared Inoperable Due to Inability to Ensure Reliable Starting of CH-4B Motor. Breaker Replaced W/Appropriate Model Breaker & Breaker for Boric Acid Pump Verified Appropriate
05000285/LER-1980-032-03, /03L-0:on 801210,primary Heat Tracing Circuits Associated W/Piping Between Boric Acid Pump Discharge & MCV-268 Found Inoperable.Caused by Blown Power Supply Fuses. Fuses Replaced
05000285/LER-1980-025-03, /03L-0:on 801027,during Power Operation While Completing Repairs on C Charging Pump,A Charging Pump Became Inoperable.Caused by Leak in Weld Joining Sys to Flushing Line.Weld Repaired & Pump Returned to Svc
05000285/LER-1980-031-03, /03L-0:on 801207,during Normal Operation,Leak Developed in Weld Connecting Demineralized Water Flush Line to Discharge Manifold of Charging Pump.Caused by Probable Piping Vibration.Crack Repaired & Pump Returned to Svc
05000285/LER-1980-024-03, /03L-0:on 800926,while Completing Repairs on B Charging Pump,A Charging Pump Became Inoperable.Caused by Packing Cooling Pump Failure.Motor Replaced
05000285/LER-1980-016-03, /03L-0:on 800621,weld on Suction Side of Pump CH-1B in Demineralized Water Flush Line Cracked.Caused by Vibration of Piping in Svc.Crack Was Ground Out & Rewelded Using Certified Procedure & Line Tested
05000325/LER-1980-019-03, /03L-0:on 800318,while Performing High Steamline Radiation Channel Alignment & Functional Test,Drawer D12-RM-K603D,Model 238X660G3,was Found Out of Specs.Caused by Instrument Drift.Drawer Recalibr
05000325/LER-1980-010-03, /03L-0:on 800122,while Performing Main Steam Line High Radiation Functional Check,Drawer 1D12-RM-K603B Found Out of Calibr.Instrument Drift Is Recurring Problem. Drawer Recalibr & Returned to Svc
PNP 2024-027, Supplement to License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations
05000325/LER-1979-114-03, /03L-0:on 791227,while Performing PT1.1.12PC,main Steam Line High Radiation Functional Check Drawer 1-D12-K603B Found Out of Calibr.Caused by Instrument Drift. Drawer Recalibr & Returned to Svc
05000324/LER-1979-104-03, /03L-0:on 791226,while Performing Main Steam Line High Radiation Functional Check,Drawer 2-D12-K603D Found Out of Calibr.Caused by Instrument Drift.Drawer Recalibr & Returned to Svc
LIC-06-0088, License Amendment Request (LAR) Change of Containment Building Sump Buffering Agent from Trisodium Phosphate to Sodium Tetraborate
1CAN031901, License Amendment Request Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an Lco
05000316/LER-2076-028, Re Pressurizer Pressure Transmitters Change Found by NRC Resident Inspector
05000316/LER-2077-002, Letter Abnormal Environmental Occurrence of Total Residual Chlorine at the Condensate Outlet Exceeding the 0.10 Ppm Limit in Violation of Appendix B Technical Specifications Section 2.2.1.2
L-95-137, Application for Amends to Licenses DPR-31 & DPR-41.Amends Would Use Changed Setpoint Presentation Format for RPS & ESFAS Instrumentation Setpoints
L-95-250, Application for Amends to Licenses DPR-31 & DPR-41, Implementing Revised Thermal Design Procedure & SG Water Level low-low Setpoint
L-95-181, Application for Amends to Licenses DPR-31 & DPR-41,modifying TS Tables 3.3-1 & 3.3-2 Action Statements for Rps/Nis/Esfas Instrumentation,Tables 4.3-1 & 4.3-2 SRs for Rps/Nis/Esfas Instrumentation & Bases 3/4.3.1 & 3/4.3.2
L-95-131, Application for Amends to Licenses DPR-13 & DPR-41 to Revise Plant TS 2.1.1 Safety limit-reactor core,2.2 Limiting Safety Sys settings-reactor Trip Sys Instrumentation Setpoints & 3/4.2.5 Power Distribution limits-DMB Parameters
L-93-081, Application for Amends to Licenses DPR-31 & DPR-41,modifying TS Table 2.2-1, Reactor Trip Sys Instrumentation Trip Setpoints to Remove Lead/Lag Compensator Term on Measured Delta T from Overtemp Delta T & Overpower Delta T
L-91-186, Responds to NRC 910606 Request for Addl Info Re 901219 Application for Amends to Licenses DPR-31 & DPR-41,revising Tech Specs Section 2.2, Limiting Safety Sys Settings & Section 3/4.3.2, ESF Actuation Sys Intrumentation
L-90-417, Application for Amends to Licenses DPR-31 & DPR-41,revising Tech Spec Sections 2.2, Limiting Safety Sys Settings & 3/4.3.2, ESFAS Instrumentation. Nonproprietary WCAP-12746 & Proprietary WCAP-12745 encl.WCAP-12745 Withheld
L-84-270, Revised Emergency Operating Procedures,Including O-ADM-110 Re Verification Guideline for Emergency Operating procedures,O-ADM-111 Re Emergency Procedure Validation Plan & Procedures Generation Package
L-91-098, Forwards Response to NRC Questions During 910307 Telcon Re 901219 Application for Amends to Licenses DPR-31 & DPR-41, Revising TS Section 2.2 on Limiting Safety Sys Settings & Section 3/4.3.2 on ESFAS Instrumentation
GO2-84-338, Reactor Containment Bldg Integrated Leak Rate Test. W/
L-86-452, Application for Amend to License NPF-16,changing Tech Specs Re Reactor Protection Instrumentation & ESFAS & Associated Bases.Fee Paid
LG-16-049, Issuance of the Core Operating Limits Report (COLR) for Reload 16, Cycle 17
DCL-14-018, License Amendment Request 14-01, Revision to Technical Specification 3.8.1, AC Sources - Operating
BSEP-89-0288, Forwards Response to Concerns Re NRC Requirements Noted in Insp Repts 50-324/88-200 & 50-325/88-200
L-2011-346, Response to NRC Instrumentation & Controls Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request
05000271/LER-2010-002, For Vermont Yankee Nuclear Power Station, Regarding Inoperability of Main Steam Safety Relief Valves Due to Degraded Thread Seals
05000251/LER-2006-002, Re Intermediate Range High Flux Trip Setpoint Exceeded Technical Specifications Allowable Value
LIC-04-0045, Unit No. I License Amendment Request (Lar), Trisodium Phosphate Volume
NUREG-1433, Part 1- Edwin I. Hatch, Units 1 & 2, License Amendments, Replace Current Technical Specification & Associated Bases
TXX-9711, Application for Amends to Licenses NPF-87 & NPF-89, Consisting of Change Request 97-002 Re Rev to Unit 2 RT Setpoint
1CAN078608, Application for Amend to License DPR-51,authorizing Tech Spec Change to Return RCS high-pressure Trip Setpoint to Original Value of 2,355 Psig,Per BAW-1890.Fee Paid
TSTF-21-03, TSTF Response to NRC Questions on TSTF-576, Revision 0, Revise Safety/Relief Valve Requirements and Submittal of Revision 1
B13269, Proposed Tech Specs Sections 2.0 & 3/4.3 Re Safety Limits & Limiting Safety Sys Settings & Instrumentation
LR-N15-0178, Hope Creek - License Amendment Request, Digital Power Range Neutron Monitoring (Prnm) System Upgrade