RNP-RA/17-0034, Modification of Request for Technical Specification Change to Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles (MF9544)
CNL-16-031, Application to Modify Technical Specifications Regarding Discrepancies in Control Room Ventilation and Other Administrative Changes to the Technical Specifications (WBN-TS-16-03)
PNP 2016-037, Response to Request for Additional Information Regarding the License Amendment Request for Implementation of an Alternate Repair Criterion on the Steam Generator Tubes (CAC No. MF7435
PLA-3150, Semiannual Effluent & Waste Disposal Rept,Jul-Dec 1988
PLA-3354, Semiannual Effluent & Waste Disposal Rept for Jul-Dec 1989
PNP 2015-093, Response to Non-Cited Violation Dated October 30, 2015
PNP 2015-058, Technical Specification Required Report
NL-14-1870, License Amendment Request for Adoption of TSTF-432-A, Rev. 1, Change in Technical Specifications End States (WCAP-16294), Using the Consolidated Line Item Improvement Process
ONS-2014-020, License Amendment Request to Remove Obsolete Information from Technical Specifications, Delete Surveillance Requirements That Equipment Design Cannot Support and Correct a Non-Conservative Condition Statement, LAR No. 2013-05
DCL-13-057, License Amendment Request 13-01, Administrative Revisions to Technical Specifications 3.7.10 and 5.6.5
PNP 2012-097, Report to NRC of Changes to Technical Specifications Bases
ULNRC-05793, Application for Amendment to Facility Operating License NPF-30 (LDCN 10-0036) Revision of Technical Specification 3.3.8,
CNL-17-119, Application to Modify Watts Bar Nuclear Plant, Units 1 and 2 Technical Specifications 3.8.9 Regarding Alternating Current (AC) Vital Buses (WBN-TS-17-19)
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Bases for Improved Technical Specifications
NL-16-031, Watts Bar, Units 1 and 2 - Application to Modify Technical Specifications Regarding Discrepancies in Control Room Ventilation and Other Administrative Changes to the Technical Specifications (WBN-TS-16-03)
NL-15-156, Sequoyah Nuclear Plants, Units 1 and 2 - Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 3. Part 3 of 9
NL-15-156, Sequoyah Nuclear Plants, Units 1 and 2 - Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 3. Part 2 of 9
NL-15-128, Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 5 of 8
NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Technical Specification Bases List of Effective Sections
ET 18-0018, Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term
RS-12-221, Byron, Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, Technical Requirements Manual
NL-10-107, Indian Point 2 (IP2) Nuclear Power Plant Amendment Update to the Final Safety Analysis Report (Fsar), Revision 22, Improved Technical Specifications Bases
ULNRC-05566, Amplification for Amendment, Revision of Technical Specification 3.3.2 and 3.7.2 and Addition of New Technical Specification 3.7.19 (License Amendment Request OL-1277 Revised)
NL-08-1519, Response to Request for Information Regarding Revision to Technical Specifications 3.3.1, 3.3.2, 3.3.6, 3.3.7, and 3.3.8
NL-08-1365, Response to Request for Information Regarding Revision to Technical Specifications 3.3.1, 3.3.2, 3.3.6, 3.3.7, and 3.3.8
ULNRC-05494, Application for Amendment to Facility Operating License NPF-30 OL1283 - Revision of Technical Specifications 3.3, 3.7, and 3.8
NL-07-2299, Request for Technical Specification Amendment Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process
RBG-40919, LAR 94-11,revising TS 4.11.2.1.2 Table 4.11.2.1.2-1,by Removing one-hour Requirement for Completing Noble Gas & Tritium Sampling & Analysis
L-PI-06-043, License Amendment Request (LAR) for Miscellaneous Technical Specification (TS) Improvements
ULNRC-05301, Proposed Revision to Technical Specification TSs 3.7.10, 3.7.11 and 3.7.13
NRC-2017-0238, Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: January 2, 2018
NRC-2011-0187, Biweekly Sholly Report - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations; Fr Publication Date: 8/23/2011
CNL-19-033, Revised Response to Request for Additional Information Regarding Application to Modify Technical Specifications 3.8.9 Regarding Alternating Current (AC) Vital Buses (WBN-TS-17-19)
NL-19-0331, License Amendment Request: Revise Measurement Units Associated with Reactor Trip System Nuclear Instrument Comparison Surveillance and Trip Setpoint for Control Room Air Intake Radiation Monitors
NL-04-158, Supplement to Proposed Change to Technical Specifications Regardinq Full Scope Adoption of Alternate Source Term
CPSES-200400149, License Amendment Request (LAR) 03-08 Common Stars License Amendment Implementation of WCAP-14333 and WCAP-15376 RTS and ESFAS Test Times, Completion Times, and Surveillance Test Intervals
ULNRC-04929, Common Stars License Amendment Regarding Implementation of WCAP-14333 and WCAP-15379, RTS and ESFAS Test Times, Completion Times, and Surveillance Test Intervals
NL-03-103, Response to Request for Additional Information Regarding Section 3.7, Plant Systems, of the Improved Technical Specifications (ITS)
ULNRC-04856, Technical Specification Bases, Revision 4
NL-03-052, Response to Request for Additional Information Regarding Section 3.3, Instrumentation, of the Improved Technical Specification (ITS)
RNP-RA/02-0136, Response to Request for Additional Information on Technical Specifications Change Regarding Selective Implementation of Alternative Radiological Source Term
NRC-92-0085, Semiannual Radioactive Effluent Release Rept for Jan-June 1992
NRC-89-0138, Semiannual Radioactive Effluent Release Rept, Jan-June 1989
CNL-21-038, Application to Revise the Measurement Units for the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for the Containment Vent Isolation Instrumentation and Control Room Emergency Ventilation System Radiation Monitors (W
LR-N970515, Special Rept 97-03:on 970808,TS Actions Statements 3.3.7.5 & 3.3.7.11 Were Entered Due to Inoperability of SPV Radiation Monitoring Sys.Caused by Failure of Low Range Detector pre- amplifier.Pre-amplifier Was Replaced
U-601253, Semiannual Radioactive Effluent Release Rept,Jan-June 1988
RBG-23-551, Responds to Notice of Violation Contained in Insp Rept 50-458/86-05.Corrective Actions:Procedure CSP-0100 Revised to Ref Procedures CSP-0121 & COP-0206 Requiring Standardization of Gas Partitioner
AECM-88-0108, Special Rept 88-003/0:on 880505,loose Parts Monitor Channel Inoperable for More than 30 Days.Caused by Extended Investigation.Temporary Loose Parts Detector Installed & Monitor Returned to Svc
SNRC-1485, Semiannual Radioactive Effluent Release Rept,First & Second Quarters of 1988
RBG-22-117, Rev 3 to Offsite Dose Calculation Manual
AECM-84-0529, Special Rept 84-37/0:on 841129,loose Parts Detection Sys Declared Inoperable for 30 Days Per Tech Specs.Caused by High Alarm Which Sealed in W/No Loose Parts Present.Matter Under Investigation for Corrective Action
AECM-85-0050, Special Rept 84-37/1:on 841129,loose Parts Detection Sys Declared Inoperable for 30 Days Reaching Time Limit of Tech Spec.Caused by Alarm Susceptibility to Changing Plant Conditions.Alarm Response Instruction Revised
PLA-2420, Semiannual Effluent & Waste Disposal Rept,Jul-Dec 1984
AECM-84-0150, Semiannual Radioactive Effluent Release Rept,Jul-Dec 1983
AECM-84-0438, Semiannual Radioactive Effluent Release Rept, Jan-June 1984
PLA-2309, Responds to NRC Re Violations Noted in Insp Repts 50-387/84-22 & 50-388/84-28.Corrective Actions:Samples Drawn After 10 H Time Limit Expired Indicated No Detectable Activity in RHR Svc Water Effluent Line
PLA-2216, Responds to NRC Re Violation Noted in Insp Repts 50-387/84-07 & 50-388/84-08.Corrective Actions:Samples of Svc Water Taken Every 8 H & Plant Mod Implemented to Add Shielding Matl Around Radiation Monitor
AECM-84-0229, Forwards Program Completion Rept Re Conclusion of Tech Spec Review Program.Rept Documents That Thorough & in-depth Engineering,Operations & Licensing Review of Tech Specs Conducted Per Programmatic Commitments
1CAN059505, Application for Amend to License DPR-51.Amend Would Revise SR for Verifying Adequate SW Flow to Each Train of RB Emergency Cooling
1CAN059506, Documents Util Position Discussed on 950512 W/Nrc & Requests Enforcement Discretion from Specific Test Flow Requirement of TS 4.5.2.1.2(a)(1) to Allow Determining Proper Sys Operation by Engineering Evaluation in Bases of TS 3.3
PLA-1492, Ro:On 821211,channels to Loose Parts Monitoring Sys Determined Inoperable Due to Erroneous Data.Caused by Incorrect Low Level Alarm Settings.Alarm Levels Reset
AECM-83-0598, Updated RO 83-066/1:on 830709 & 13,triaxial Peak Recording Accelerograph Used for Seismic Monitoring of Auxiliary Bldg Foundation & Reactor Vessel Support Failed Surveillance.New Instruments Installed
AECM-83-0600, Updated RO 83-067/1:on 830819,accelerographs Used for Seismic Monitoring Discovered Damaged Due to over-ranging. Instrument on HPCS Spray Line Replaced 830713.LPCS Spray Line Instrument Replaced 830713
L-94-025, Ter,Audit of Plant Specific License Conversion to STS: Crystal River Unit 3
U-602348, Special Rept:On 940906,CPS Declared Loose Parts Monitoring Sys Out of Svc.Caused by False Alarms.Util Will Recalibrate Channel Six
AECM-83-0468, RO83-066/0:on 830709 & 13,triaxial Peak Recording Accelerographs Used for Seismic Monitoring of Auxiliary Bldg Foundation & Reactor Vessel Support Failed Surveillance. Caused by Damage Apparently Incurred from Const Activity
L-22-246, Response to Request for Additional Information Regarding a Request to Consolidate Fuel Decay Time Technical Specifications to New LCO
L-22-286, Supplement to Request for an Amendment to Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time
NL-23-0010, Response to Request for Additional Information Regarding License Amendment Request for Alternative Source Term, TSTF-51, TSTF-471, and TSTF-490
RBG-21545, Rev 2 to River Bend Station Offsite Dose Calculation Manual
AECM-82-410, Documents Interpretations of Tech Specs 3.3.7.12 Re Radioactive Gaseous Effluent Monitoring Instrumentation & 3.5.1 Re ECCS Operability
U-602311, Special Rept:On 940624,inoperabilities of Meteorological Monitoring Instrumentation Channels for More than 7 Days Identified.Personnel Worked Expeditiously to Return Meteorological Instrumentation to Operable Status
PY-CEI-NRR-0701, Semiannual Radioactive Effluent Release Rept for Jan-June 1987
PY-CEI-NRR-0978, Semiannual Radioactive Effluent Release Rept for Jul-Dec 1988
PY-CEI-NRR-0469, Forwards List of Tech Spec Changes to Accompany Full Power Ol,Representing Minor Editorial Corrections,Clarifications & Enhancements.Justifications & Proposed marked-up Tech Spec Pages Also Encl
PY-CEI-NRR-0902, Special Rept NP-38-04:on 880805,primary Containment Area Gross Radiation Monitors Had Less than Min Required Channels Due to Failed Monitor.Caused by High Voltage Failure Due to Defective Voltage Power Supply Circuit Board.Board Repl
PY-CEI-NRR-0831, Responds to NRC Re Violations Noted in Insp Rept 50-440/88-03.Corrective Actions:Instrument Declared Inoperable & Required Actions,Per Tech Spec 3.3.7.9 Initiated & Tagging Error Corrected
PY-CEI-NRR-1425, Application for Amend to License NPF-58,changing TS 3.3.7.4-1 Re Remote Shutdown Sys Controls to Remove Line Item for Controls to RCIC Pump Discharge to Lube Oil Cooler Valve
PY-CEI-NRR-1384, Semiannual Radioactive Effluent Release Rept for 1991: Quarters 1 & 2
1CAN092301, Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4
U-601719, Semiannual Radioactive Effluent Release Rept,Jan-June 1990
NMP1L3584, License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling
RBG-25841, Rev 0 to Procedure RSP-0008, River Bend Station,Offsite Dose Calculation Manual
PY-CEI-NRR-1796, Annual Radioactive Effluent Release Rept 1993
ULNRC-05463, Revision to Technical Specification Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process (License Amendment Request OL-1287)
NL-08-1688, Response to Request for Information Regarding Revision to Technical Specifications 3.3.1, 3.3.2, 3.3.6, 3.3.7, and 3.3.8
NRC-2017-0142, Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Consideration and Containing SUNSI and Order Imposing Procedures for Access to SUNSI - Publication Date: July 5,
CP-202400335, License Amendment Request to Adopt TSTF-51, TSTF-471, and TSTF-571-T to Eliminate Use of the Term Core Alterations and Revise Requirements During Handling of Irradiated Fuel
RBG-22535, Submits Addl Info Re Background of 851021 & 1105 Tech Spec Change Requests,In Response to Recent NRC Request.Smoke Detections in Zones SD-102 & SD-156 Unnecessary Due to Absence of safety-related Equipment
WO 03-0059, Application for Amendment for Revision to Technical Specification 3.3.1, Reactor Trip System Instrumentation, and Technical Specification 3.3.2, Engineered Safety Feature Actuation System Instrumentation (Common Stars License Amendment.)
NSD-NRC-98-5559, Forwards W Response to FSER Open Items on AP600.Summary of Encl Responses,Fser Open Item Number,Associated Oits Number & Status to Be Designated in W Status Column of Oits, Included in Table 1
AECM-85-0054, Semiannual Radioactive Effluent Release Rept,Jul-Dec 1984
1CAN069506, Submits Suppl to TS Change Request Re SW Flow Rate to Reactor Bldg Emergency Cooling Sys
AECM-83-0472, RO 83-067/0:on 830704,05 & 12,instruments on HPCS Spray Line,Lpcs Spray Line & Reactor Recirculation & Main Steam Piping,Respectively,Found Damaged.Caused by over-ranging. Instruments Will Be Replaced by 830826
RBG-35007, Application for Amend to License NPF-47,changing Tech Spec 3.3.7.1-1 to Reduce Alarm Setpoint for Condenser Air Ejector Pretreatment Noble Gas Activity Monitor from Current Value
U-601799, Semiannual Radioactive Effluent Release Rept Jul-Dec 1990
AECM-84-0252, Special Rept 83-067/3:on 830819,during Scheduled Surveillance on Four Pipe Mounted Triaxial Peak Recording Accelerographs Used for Seismic Monitoring,Instruments Damaged Due to over-ranging.Design Changes Under Way
DCL-14-058, License Amendment Request 14-03 for Adoption of Technical Specification Task Force Traveler TSTF-432, Revision 1. Change in Technical Specification End States (WCAP-16294)
ONS-2014-020, Oconee, Units 1, 2 and 3 - License Amendment Request to Remove Obsolete Information from Technical Specifications, Delete Surveillance Requirements That Equipment Design Cannot Support and Correct a Non-Conservative Condition Statement,
NL-15-128, Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 4 of 8
AECM-90-0134, Rev to 870519 Application for Amend to License NPF-29, Incorporating Fire Protection Program Into Fsar,Per Generic Ltrs 86-10 & 88-12.Attachment 5 Contains Proposed Changes to Updated Fsar.Responses to NRC Recommendations Also Encl
DCL-04-013, License Amendment Request 03-17, Common Stars Amendment, Implementation of WCAP-14333 and WCAP-15376, RTS and ESFAS Test Times, Completion Times, and Surveillance Test Intervals
05000458/LER-1989-028, :on 890512,particulate Channel of Fuel Bldg Exhaust Radiation Monitor Spiked Resulting in Automatic Initiation of Fuel Bldg Filter Trains.Caused by Degraded Voltage Conditions Due to Electrical Outage
05000440/LER-1989-009, :on 890321,discovered That Vent Sampler Flow Rate Monitor Had Inoperable Alarm Channel Since 890311 W/O Performing Action Required by Tech Spec.Caused by Personnel Error.Listed Alarms Reviewed
05000352/LER-1987-036, :on 870722,grab Sample from RHR Svc Water Loop B Taken 30 Minutes Late.Caused by Personnel Error. Technician Verified No Change Occurred in Sample Analysis & Sampling Intervals Returned to Every 8 H
05000352/LER-1987-031, :on 870613,hot Maint Shop Ventilation Operating W/O Exhaust Radiation Monitoring.Caused by Personnel Not Following Procedures for Responding to Alarms. Shop Shut Down & Personnel Counseled
05000440/LER-1987-060, :on 870822,turbine Bldg/Heater Bay Vent Radiation Monitor Found to Have Been Inoperable for Approx 19 H.Caused by Personnel Error Due to Inattention to Detail. Tagging Error Corrected & Noble Gas Sample Drawn
05000269/LER-1986-011-04, :on 861001,suction to Low Pressure Svc Water Lost When Performing Load Shed Test on Unit 2.Caused by Inadequate Design & Testing of Emergency Condenser Cooling Water Sys.Load Shed Test Date Evaluated
05000458/LER-1986-046, :on 860611,while Routine Filter & Cartridge Replacement on Monitors performed,wide-range Gas Monitor Found Turned Off.Caused by Min Number of Channels Not Operable.Condition Rept 86-0726 Written
05000440/LER-1986-074, :on 861027,nuclear Steam Supply Shutoff Sys Div 2 balance-of-plant Isolation Occurred When One Leg of Transformer Opened on Transformer Supplying Power for Isolation Actuation Relays
05000373/LER-1987-008-01, :on 870203,required Sample of Offgas to Determine Hydrogen Content Taken Late.Caused by Personnel Error.Individual Foreman Counseled & Second Alarm Programmed Into Reminder Clock
05000410/LER-1987-014, :on 870129,inoperable Instrumentation in Radioactive Gaseous Effluent Monitoring Sys Utilized W/O Establishment of Required Compensatory Measures.Cause Under Investigation
RNP-RA/02-0118, Response to Request for Additional Information on Technical Specifications Change Re Selective Implementation of Alternative Radiological Source Term
05000322/LER-1986-012, :on 860303,loss of Continuous Monitoring of Station Ventilation Exhaust Occurred Resulting from Panel 1D11-PNL-041 Sample Pump Being Shut Off for Maint.Caused by Personnel Miscommunication
05000440/LER-1986-049, :on 860818 & 19,gaseous Effluent Vent Stack Flow Estimates Not Performed Once Per 4 H as Required by Tech Specs.Caused by Personnel Error.Operators Counseled & Administrative Procedures Revised
05000269/LER-1998-018, :on 981209,identified Potential for Loss of Essential Siphon Vacuum Sys.Caused by Design Oversight. Procedure Revised.With
05000413/LER-1999-004, :on 990310,operation Prohibited by TSs Was Noted.Caused by Incorrect TS Requirements for Cravs & Auxiliary Bldg Filtered Ventilation Exhaust Sys Actuation Instrumentation.Submitted Lar.With
L-07-074, Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3 (License Amendment Request No. 07-008)
05000322/LER-1986-025, :on 860611,two Noble Gas Grab Samples Discarded Prior to Being Analyzed.Caused by Personnel Error. Instructions Given to Technicians to Obtain Foreman Approval Prior to Disposal of Samples
05000373/LER-1986-021-02, :on 860608,ESF Actuation of HVAC Emergency make-up Train B Occurred Due to Spurious Radiation Monitor Trip.Cause Attributed to Electronics Problem W/Radiation Detector 2D18-K751D.Detector Replaced
05000416/LER-1986-018, :on 860513,grab Samples Not Collected During Limiting Condition for Operation Due to Inoperability of Hydrogen Monitors.Caused by Failure of Supervisor to Verify Termination of Condition
CNL-16-039, Application to Modify Technical Specifications Regarding Use of Component Cooling System (Ccs)Pump 2B-B to Support CCS Train B Operability (WBN-TS-14-004)
CNL-18-121, Response to Request for Additional Information Regarding Application to Modify Watts Bar Nuclear Plant, Units 1 and 2 Technical Specifications 3.8.9 Regarding Alternating Current (AC) Vital Buses (WBN-TS-17-19)
05000353/LER-1997-004-01, :on 930316,failed to Obtain Offgas Sys Grab Sample within Four Hour Interval Required by Ts.Caused by Personnel Error.Analyzed Sample within Following Four Hours, IAW TS & Revised Chemistry Section Sample Program
05000461/LER-1988-015, :on 880509,motor-operated Flush Valve on Off Gas Pretreatment Process Radiation Monitor Discovered Partially Open.Caused by Util Control & Instrumentation Technician Error.Procedure Revised for Clarity
05000374/LER-1988-006, :on 880513,Technical Surveillance LTS-500-12 Re Loose Parts Monitor Functional Test Not Performed as Required.Caused by Personnel Error.Surveillance Immediately Performed
05000373/LER-1988-017-04, :on 880821,control Room HVAC Sys B Ammonia Detector a Tripped.Maint Dept Found Takeup Spool Drive Motor Had Jammed.Caused by Design Deficiency in Chemcassette Tape Mechanism.Tech Spec Amend Request Submitted
05000352/LER-1987-068, :on 871230,Tech Spec 3.3.7.12 Violated.Caused by Radiation Monitor Sampling Sys for Hot Maint Found Out of Svc Due to Inadequate Training & Equipment Failure.Pressure Switch Replaced & Tested Satisfactorily
05000354/LER-1988-009-01, :on 880413,reported That Contrary to Tech Spec Requirement,Two 4-h Flow Rate Estimates Not Made During South Plant Vent Monitor Outage.Caused by Operator Failure to Initiate & Complete Daily Log
05000461/LER-1988-020, :on 880806,discovered That Div II Shutdown Svc Water Radioactive Liquid Effluent Monitor Incorrectly Declared Operable.Caused by Vague Communications. Departmental Responsibilites Clarified
05000458/LER-1986-011, :on 860120,Tech Spec Action Required Sample for Hydrogen Downstream of Recombiners of Offgas Treatment Sys Missed.Caused by Changed Lock on Door to Sample Station. Sampling Performed & Personnel Counseled
05000458/LER-1985-064, :on 851228,hydrogen Gas Grab Sample Not Performed When Main Condenser Offgas Explosive Gas Monitoring Sys Declared Inoperable.Caused by Inaccessible Sample Point.Personnel Counseled
05000354/LER-1988-001-01, :on 880106 & 28,liguid & Gaseous Radwaste Discharge Monitors Failed to Pass Functional Tests.Caused by Design & Procedure Deficiencies.Gaseous Radwaste Monitor Surveillance Procedures Revised
05000373/LER-1996-010, :on 960829,violations of TS & Design Basis Occurred.Caused by Inadequate Standards for TS Clarification.Deleted Clarifications in Question on 960829 & Revised One Clarification
05000352/LER-1984-027, :on 841207,svc Water Sys Effluent Line Gross Radioactivity Sample Not Obtained within 8 H Period.Caused by Personnel Error.Supervisor Counseled
05000374/LER-1985-047-02, :on 851115,RHR Svc Water Pump B Started in Conjunction w/post-maint Test.Test Failed & Pump Left Running.Caused by Personnel Error
05000373/LER-1997-001-02, :on 970108,special Rept Was Not Written as Required by TS When Loose Parts Monitoring Sys Was Inoperable During Power Operations.Automatic Recording Capability Will Be Installed on Unit Lpms
05000322/LER-1985-025, :on 850706,Temporary Mod Tm 85-03-010 to Steam Air Ejector Radiation Elements Made in Mar 1985 Discovered Improperly Implemented.Cause Not Stated.Mod Revised to Include Checklist for Temporary Mod Review
05000416/LER-1985-032, :on 850829,discovered That on 841201 & 04, Liquid Effluent Flow Rate Estimates Exceeded 4 H Frequency of Tech Specs Requirements.Caused by Late Flow Rate Measurements.Procedural Controls Revised
05000341/LER-1985-007, :on 850423,24 & 25,Tech Spec 3.3.7.11.b Violated Due to Grab Samples Not Taken within Required 8 H Period When Radiation Monitor Inoperable.Caused by Personnel Error.Personnel Counseled.Procedure Written
05000374/LER-1985-020-03, :on 850424,svc Water Monitor Not Sampled Once Per 8 H While Inoperable.Caused by Personnel Mistakenly Told to Sample Unit 2 RHR Svc Water Monitor A.Memo Issued Re Effective Verbal Communication
05000341/LER-1985-020, :on 850604,discovery Made That Grab Samples of Reactor Bldg Ventilation Effluent Not Taken within 8 H of Failure of Reactor Bldg Ventilation Effluent Radiation Monitor.Caused by Personnel Error
05000353/LER-1992-011-02, :on 921027,established Firewatch Insp for Area Containing Inoperable Fire Barrier Not Performed Per TS 3.3.7.Caused by Cognitive Personnel Error.All Firewatch Personnel Counseled Re Attention to Detail
05000354/LER-1992-012-02, :on 921017,RM Skid Declared Inoperable Due to Low Sample Flow Indication on Particulate,Iodine & Noble Gas Monitor Portion of Skid.Caused by Design Deficiency.Design Review of RMS Skid Will Be Performed
05000354/LER-1996-020, :on 960719,south Plant Vent Radioactive Gaseous Effluent Monitor Declared Inoperable.Caused by Failure to Perform Actions for Inoperable Instrumentation.Frequency of Grab Samples Flow Estimations Increased
05000373/LER-1985-031-01, :on 850311,while Discharging Radwaste,Sys Isolated on High Road Signal.Caused by Misreading of Max Allowable hi-hi Alarm/Trip Setpoint from Chart Recorder.Addl Training Instituted
05000302/LER-1995-018, :on 950922,inadequate ITS Note Allows Delayed Entry Into ITS Lco,Resulting in Violation of Its.Caused by Personnel Error.Its Not Clarified & Pertinent Procedures & Other ITS Notes Reviewed
05000352/LER-1984-018, :on 841128,liquid Radwaste Off/Vent Line Independent Sample Missed.Caused by Radwaste Effluent Monitor Being Out of Svc.Procedures Revised
05000352/LER-1984-009-02, :on 841116,svc Water Sys Effluent Line Gross Radioactivity Sample Not Obtained within 8 H Period as Required by Tech Specs.Caused by Failure to Adequately Address Obtaining Samples from Alternate Point
05000373/LER-1985-018-01, :on 850216,H2 Grab Sample Obtained for Unit Offgas Hydrogen Recombiner Effluent.Caused by Inoperability of Hydrogen Analyzers.Sample Obtained at Greater than Allowable Frequency
05000416/LER-1984-037, :on 840813,limiting Condition for Operation Time Limit for Sampling Exceeded Due to Inoperability of Radwaste Bldg Noble Gas Activity Monitor.Caused by Personnel Error.Chemists Reinstructed
05000397/LER-1984-088, :on 840814,RHR Standby Svc Water Monitor Loop B Determined Inoperable Since 840807 Due to Leaking Pump Seal at Sample Rack.Caused by Inadequate Procedures.Faulty Pump Seal Replaced
05000352/LER-1992-008-01, :on 920506,condition Prohibited by TS in That SRs Were Not Met for Certain fire-rated Encapsulations. Caused by Drawing & Procedural Deficiencies.Procedures ST-7-022-920-1 & 2 Will Be Revised
05000354/LER-1995-028, :on 951030,failed to Exert Best Efforts to Restore Liquid Effluent Radiation Monitoring Sys to Operable Status.Caused by Low Mgt Priority Given.Improved Related Processes
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-1995-024-01, :on 950928,missed Special Rept for Filtration Recirculation Ventilation Sys High Range Noble Gas Monitor Rendered Inoperable on 950913.Caused by Personnel Error. Required Special Rept 95-03 Issued on 951024
05000387/LER-1984-039, :on 840906,temporary Monitoring Equipment Failed W/Permanent Turbine Bldg Special Particulate Iodine Noble Gas Monitor Out of Svc.Caused by Gravel Drawn Into Pump.Sample Pump Replaced & Returned to Svc
05000387/LER-1984-027, :on 840622,two Grab Samples Required by Tech Spec Action Statements Not Taken within Requisite Time Limits.Caused by Personnel Oversight.Supervisor Met W/ Technicians to Review Responsibilities
05000416/LER-1984-021, :on 840501,main Condenser Offgas Treatment Sys Grab Samples Obtained 3 to 20 Minutes After 4 H Requirement. Error Due to Misinterpretation of Tech Spec 4.0.2
05000269/LER-1994-004, :on 950215,determined That LPSW Sys Inoperable in Past Due Design Deficiency.Hpsw Design Basis Document Will Be Reviewed & Updated as Required
05000373/LER-1983-135-03, /03L-0:on 831028,standby Gas Treatment wide-range Gas Monitor Inoperable When Power Lost to Detector Skid OPLD2J.Caused by Powering Up Tritium Sampler.Power Fuse Replaced
05000373/LER-1984-001-04, :on 840123,sample Flow Alarm Annunciated Following Start of Radwaste Discharge.Caused by Frozen Line. Line Thawed Out & Proper Flow Verified.Procedures Revised to Verify Proper Flow During Source Check
05000373/LER-1983-134-03, /03L-0:on 831028,blowdown Recorder Failed Downscale & Instrumentation Failed in Radwaste Control Room. Caused by Large Concentrations of Shad Entering Blowdown Line & Plugging Sensing Ports.Probe Repaired
05000373/LER-1983-130-03, /03L-0:on 831021,stack wide-range Gas Monitor Alarm Received.Caused by Checksource Not Remaining Long Enough at Detector Window for Detector to respond.Mid-range Detector Manually Source Checked
05000387/LER-1983-144-01, /01T-0:on 831105,while Operating at Less than 2% Power,Failure to Locate Partially Obscured Deuterium Analyzer Return Valves Made Analyzer Channels Inoperable. Caused by Location of Analyzer Return Valves
05000416/LER-1983-131-01, /01T-0:on 830913,w/radioactivity Monitors Inoperable,Action 110 of Tech Spec 3.3.7.11 Not Fully Met. Caused by Personnel Error.Chemist Reinstructed on Requirements
05000440/LER-1991-012, :on 910605,determined That Effluent Sys Flow Rate Monitor for Turbine/Heater Bay Bldg Inoperable Since Summer 1988.Caused by Program Deficiencies.Pitot Tube Array Calibr by Capping Individual Pitot Tubes
05000395/LER-1983-141-03, /03L-0:on 831215,while in Mode 2,snubbers MSH-324 & MSH-325 Declared Inoperable.Caused by Transient in 32-inch Main Steam Line Which Induced 850 Lb Load in 4-inch Line. Snubbers Replaced
05000373/LER-1983-019-03, /03L-0:on 830302,lake Blowdown Flow Recorder Gave Incorrect Readings.Caused by Instrument Probe Being Either Airbound or Plugged.Operating Surveillance Revised to Restrict Valve Position
05000354/LER-1994-008-01, :on 940602,noncompliance W/Ts 3.3.7.11 Re Action for Out of Svc Radiation Monitoring Instrumentation Occurred.Caused by Personnel Error.Calibration Procedure Will Be Revised
05000373/LER-1983-025-03, /03L-0:on 830315,offgas Hydrogen Analyzer 1B Found Operating Incorrectly While Analyzer 1A Inoperable. Caused by Defective Timer & Defective Hydrogen Sensor, Respectively.Timer & Sensor Repaired
05000416/LER-1982-081-99, During Preoperational Test,Local Instrument Check Revealed Discrepancies in Containment Ventilation Monitoring Sys Effluent Flowrate Monitor Indications.Caused by Clogged Manifold
05000354/LER-1990-030-02, :on 901128,offgas Sys Hydrogen Grab Sample Not Taken within 4 H of Declaring Normal H2 Monitors Inoperable. Caused by Personnel Error.Personnel Responsible Counseled & LER Rept Forwarded to Nuclear Training Dept
05000269/LER-1994-001-04, :on 940221,determined Seismic/Loop Event May Result in Loss of post-accident Cooling Due to Design Deficiency.All Engineering Documents & Training Revised.W/
05000352/LER-1993-017, :on 930705,discovered Condition Prohibited by TS in Special Rept for Inoperable Seismic Monitoring Sys Not Submitted in TS Time Period.Caused by Misinterpretation of TS Limiting Conditions.Procedures Revised
05000354/LER-1990-027-02, :on 901116,discovered That Analysis of Offgas Sys Sample for Hydrogen Content Not Performed within 4 H as Required by Tech Specs.Caused by Personnel Error.Technician Counseled & Disciplinary Action Taken
05000373/LER-1982-057-03, /03L-0:on 820708,while in Mode 4 Cold Shutdown, RHR Svc Water Pump Found Cycling on & Off.Caused by Thermal Overload Due to Motor Being Rewired at 230-volt Configuration Instead of 110-volt.Motor Rewired
05000458/LER-1994-004, :on 940113,nonconservative Alarm Setpoint for Liquid Radwaste Gross Activity Monitor 1RMS-RE107.Caused by Personnel Error.Alarm Setpoint for Monitor 1RMS-RE107 Revised to Assure Setpoint Properly Set
05000373/LER-1982-007-03, /03L-0:on 820418-24,operating Personnel Used Newly Installed Vent Stack Radiation Microprocessor Rather than Monitor Ref by Surveillance.On 820424-28,no Radiation Readings Taken.Caused by Personnel Unawareness of New Sys
05000373/LER-1982-002-03, /03L-0:on 820419,station Vent Stack Flow Recorder DFR-VR019 Read Downscale.Caused by Flow Transmitter Core Hung at Zero Point.Flow Transmitter Repaired
05000354/LER-1990-005-02, :on 900419,determined That Inoperability of Liquid Radwaste Discharge Monitor Not Reported in Recent Radioactive Effluent Release Rept.Caused by Procedural Deficiency.Effluent Rept Revised
AECM-90-0089, Forwards Draft Tech Specs for Power Distribution Limits,Rcs, ECCS & Plant Sys as Part of Util Involvement W/Bwr Owners Group as BWR-6 Lead Plant
05000461/LER-1990-006, :on 900321,process Radiation Monitor Placed in Svc W/O Required Filter Due to Inadequately Specified Job Steps for Plant Mod.Caused by Personnel Error.Procedure 1502.01 to Be Revised
05000416/LER-1982-096-03, /03L-0:on 821001,fire Zone 2-04 Deactivated in Security & Fire Protection Computer Due to Inability to Reset Spurious Smoke Detector Alarm.Caused by Spurious Reaction,Not Component Failure.Alarm Reset
SNRC-1721, Requests Interim Relief from Action Requirements of Tech Specs 3.3.7.9,3.7.7.2,3.7.7.3 & 3.7.8 Re Establishing & Maintaining Continuous Fire Watches &/Or Hourly Fire Watch Patrols
RBG-32072, Special Rept:On 891121,loose Parts Monitoring Sys Channel 7, Main Steam Line 252 Degrees Azimuth Found in Alert Condition & Declared Inoperable on 891130 in Order to Ensure Valid Alert Signal Could Be Detected from Other Channels
05000440/LER-1989-029, :on 891117,heater Bay/Turbine Bldg Vent Gaseous Effluent Particulate & Iodine Samples Not Continuously Collected as Required by Tech Spec 3.3.7.10.Caused by Procedure Deficiency.Procedure Revised
RS-16-248, Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Technical Requirements Manual
05000354/LER-1989-018-01, :on 891003,determined That Two Tech Spec Required Readings Not Taken as Required When Vent Monitoring Sys Inoperable on 890929.Caused by Lack of Adequate Communication.Personnel Involved Counseled
05000461/LER-1989-034, :on 891004,discovered That Inservice Station HVAC Exhaust Stack Process Radiation Monitor Had Not Been Verified as Operable,Contrary to Tech Spec 3.3.7.12.Caused by Lack of Training & Inadequate Communication
JAFP-24-0053, License Amendment Request to Eliminate Remaining Main Steam Line Radiation Monitor Initiated Isolation Functions
NMP1L3614, Response to Request for Additional Information for License Amendment Request to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling
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
SNRC-1429, Semiannual Radioactive Effluent Release Rept for Third & Fourth Quarters,1987,Meteorological Summary & Offsite Dose Assessment
PLA-2993, Semiannual Effluent & Waste Disposal Rept,Jul-Dec 1987. W/
PLA-3433, Semiannual Effluent & Waste Disposal Rept for Jan-June 1990 for Susquehanna Steam Electric Station
PLA-3739, Semiannual Radioactive Effluent Release Rept for Jul-Dec 1991
GO2-94-223, Special Rept:On 940825,loose Part Detection Sys Channel Number Eight Actuated Associated MCR Alarm & on 940908 Subj Channel Began Alarming Due to Electronic Noise Originating in Drywell.Electronic Module of Channel Removed
05000397/LER-1992-046, :on 921215,night Technicians Failed to Collect Main Condenser Offgas Sample within TS Time Requirements, Due to Personnel Error.Memo Issued That Will Address Requirements for Shift Personnel
05000397/LER-1992-038, :on 921014,technicians Failed to Perform Main Condenser Offgas Sample Analysis Per TS 3.3.7.12,due to Personnel Error & Inadequate Work Mgt Methods.C/A Included Counseling,Equipment Repair & Further Training
GO2-86-150, Semiannual Effluent Rept,Jul-Dec 1985
GO2-85-498, Washington Nuclear Plant Unit 2 Semiannual Effluent Rept, Jan-June 1985
GO2-83-881, Requests That Spent Fuel Storage Pool Monitors Not Be Made Requirement in Tech Specs,Based on Recent Exemption Granted for License SNM-1890.Storage in Spent Fuel Storage Area Exemption Predicated on Design of Storage Facility
GO2-92-234, Special Rept:On 920905,channel 1 on Main Steam Line D Nozzle in Drywell Did Not Pass Surveillance & Inoperable for More than 30 Days.Caused by Faulty Equipment in Drywell. Maint Work Request Initiated to Repair Failed Channel
GO2-95-156, Special Rept:On 950712,loose Part Detection Sys Channel 4 Failed Due to Electrical Noise During Daily Check.Channel 4 Will Remain Inoperable Until Next Forced or Scheduled Outage When Primary Containment de-inerted for Other Work
05000388/LER-1998-002, Forwards LER 98-002-00 Re Loss of Continuous Vent Sampling for Unit 2 Turbine Bldg
05000388/LER-1998-002-01, :on 980301,Unit 2 Turbine Bldg Discharge Vent Gaseous Effluent Monitor Declared Inoperable,Per Tech Specs 3.3.7.11.Caused by Design Uses Tubing Connectors,Do Not Clamp Tubing in Place.Tubing in All Vent Monitors Replaced
05000387/LER-1997-011, :on 970422,loss of Turbine Building Ventilation Stack Flowrate Occurred.Caused by Pinched & Damaged Tubing During Previous Maint Work.Maint Work Performed
05000269/LER-2016-003, Regarding Engineered Safeguards Protection System Automatic Actuation Output Logic Bypassed
CNL-15-188, Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Correction to ITS 3.3.7, Control Room Emergency Ventilation System (CREVS) Actuation Instrumentation
RS-17-029, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control
DCL-12-122, License Amendment Request 12-04, Emergency Revision to Technical Specification 3.7.10, Control Room Ventilation System (Crvs)
3F1212-06, CR-3 Extended Power Uprate LAR Supplement to Support NRC Accident Dose Branch (Aadb) Technical Review
05000361/LER-2012-002, Regarding Emergency Diesel Generator Vibration Trip Not Bypassed for Non-Accident Condition
LG-85-005, Forwards Reg Guide 1.97 Compliance Rept,Providing Description of Requirements & Method of Complying W/ Requirements for Each post-accident Variable Identified in Table 1 of Guide
05000362/LER-2011-002, Regarding As-Found Condition of Lovs Relays Not within Technical Specification Limits
IA-10-005, Final Response to Task Interface Agreement - Requirements for Degraded Voltage Relay Setpoints at Palo Verde Nuclear Generating Station (TIA 2010-005
ET 08-0041, Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation
TSTF-07-24, TSTF-431, Revision 2, Change in Technical Specifications End States (BAW-2441)
TSTF-06-26, Submittal of TSTF-431, Revision 1, Change in Technical Specifications End States (BAW-2441)
TSTF-05-12, TSTF-05-12, Transmit TSTF-448, Revision 2, Control Room Habitability
05000390/LER-2004-001, Regarding Automatic Reactor Trip Due to a Invalid Turbine Trip Signal (P-4)
05000454/LER-2003-001, Regarding Control Room Ventilation System Alignment Results in Inoperable Radiation Monitors Without Taking Required Actions Put Technical Specifications
05000353/LER-2002-002, Manual Scram Due to Failure of Main Condenser Air Removal System
NL-13-078, Proposed License Amendment Regarding Technical Change Traveler TSTF-432-A Revision 1
05000275/LER-2012-008, Regarding Loss of Control Room Ventilation System Due to Inadequate Design Control
NMP1L3545, Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems .
WO 11-0008, Revision to Technical Specifications 3.3, Instrumentation, 3.7, Plant Systems, and 3.8, Electrical Power Systems
ONS-2014-060, Letter Regarding Ufsar/Selected Licensee Commitments Change
L-22-053, Request for an Amendment to Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time
NL-06-099, Units, 2 and 3 - Proposed Changes to Technical Specifications: Miscellaneous Editorial Changes, Including TSTF-485
PNP 2025-002, License Amendment Request to Include Leak Before Break Methodology for Primary Coolant System Hot and Cold Leg Piping in Palisades Licensing Basis
ET 17-0010, License Amendment Request for Addition of New Technical Specification 3.7.20, Class 1E Electrical Equipment Air Conditioning (A/C)System
NL-16-109, Indian Point 2 Improved Technical Specifications Bases
05000354/LER-1989-001, :on 890106,during Testing,Valves Which Isolate Liquid Radwaste Discharge Line Did Not Close When Radwaste Monitor Downscale Failure Was Simulated.Caused by Design Deficiency.Design Change Implemented
05000322/LER-1986-023, :on 860520,Action Statement 120 of Tech Spec 3.3.7.11 Requiring Noble Gas Grab Samples Not Met.Caused by Poor Communication Between Technicians During Shift Change. Mgt Notified & Shift check-off List Revised
2CAN112004, License Amendment Request - Application to Adopt a Safety Function Determination Program (SFDP)
RBG-28747, Semiannual Radioactive Effluent Release Rept for Jan-June 1988
AECM-89-0010, Rept of 10CFR50.59 Safety Evaluations for June-Dec 1988
AECM-84-0041, Updated RO 83-067/2:on 830712,accelerographs Used for Seismic Monitoring Discovered Damaged.Caused by over-ranging.Design Tech Specs & FSAR Revised to Delete Instruments to Increase Range
PY-CEI-NRR-1538, Semiannual Radioactive Effluent Release Rept for 1992:Quarters 1 & 2
GO2-90-078, Application for Amend to License NPF-21,revising Tech Spec 3.3.7.5 to Allow Exception to Spec 3.0.4 During Periods When Accident Monitoring Instrumentation Channels Inoperable
PLA-3253, Semiannual Effluent & Waste Disposal Rept for Jan-June 1989
U-601018, Semiannual Radioactive Effluent Release Rept,870228-0630
RBG-27108, Forwards Suppl Rept of Safety Evaluations for Documents Only Changes Included in USAR for Mar 1986 - Feb 1987
U-601382, Semiannual Radioactive Effluent Release Rept for Jul-Dec 1988
SNRC-1315, Semiannual Radioactive Effluent Release Rept,Third & Fourth Quarters of 1986,1986 Meteorlogical Summary & Offsite Dose Assessment
GO2-96-132, Requests Amend to Ts,Revising Rev a, Including Changes in Vol 7.Proposed Rev Does Not Change Conclusion of Nhsc or Environ Assessment Provided in Rev a
05000416/LER-1987-001, :on 870108,chemistry Section Personnel Determined Hydrogen Samples Taken from Condenser Offgas Pretreatment Sample Station Not Representative of Main Condenser Offgas Due to Failed Solenoid Valve
05000440/LER-1986-024, :on 860612,gaseous Effluent Noble Gas Grab Sample Not Collected & Analyzed.Caused by Inadequate Knowledge of Radiological Effluent Tech Specs & Poor Communications.Chemistry Personnel Will Receive Training
05000373/LER-1982-149-03, /03L-0:on 821112,lake Blowdown Flow Recorder Discovered Giving Incorrect Readings.Caused by Algae Buildup on Instrument Probe.Probe Cleaned & Weekly Functional Test Will Be Performed
05000352/LER-1991-003, :on 910113,loose Parts Monitoring Sys Inoperable for More than 30 Days.On 901205,digital Loose Part Locator Circuit Discovered in Lockup Condition.Caused by Faulty Component.New Circuit Boards Ordered
05000373/LER-1983-062-03, /03L-0:on 830612,offgas Hydrogen Analyzer Train a Would Not Switch Automatically Out of Calibr Mode.Caused by Contact Failure within Control Switch.Work on Analyzer Completed on 830623
05000373/LER-1983-017-03, /03L-0:on 830222,lake Blowdown Flow Recorder Gave Incorrect Readings.Caused by Flow Instrument Probe Being Airbound Thus Preventing Transmittal of Correct Signal. Probe vented.LIS-WL-01 Performed Satisfactorily
05000416/LER-1983-127-03, /03L-0:on 830822,during Surveillance Testing, Control Room Ventilation Radiation Monitor Channel B & Channel C hi-hi Setpoints Exceeded Allowable Values.Caused by Instrument Drift
L-24-267, Vistra Operations Company LLC (Vistra Opco) Application to Revise Technical Specifications to Implement an Online Monitoring Program
TSTF-22-01, Technical Specifications Task Force - Transmittal of TSTF-589, Revision 0, Eliminate Automatic Diesel Generator Start During Shutdown