Reactor Water Recirculation# QUERYc6b85d30dd72fb2ef4cda49a405a9cf4
Reactor Water Recirculation
Reactor Water Recirculation# QUERY7047d4b8a504036eff8216505ee97848
Reactor Water Recirculation# QUERY642a82eb521dce1f762c54bfe7a58b47
Reactor Water Recirculation# QUERYf1e8a1d163e1059d95ea0f3c812469c2
Reactor Water Recirculation# QUERY2f7cba4c1f39b2bcf631d007547826d4
BSEP-87-0065, Annual Rept of Facility Changes,Tests & Experiments,1986
JAFP-92-0470, Ja Fitzpatrick Nuclear Power Plant Annual Summary of Changes,Tests & Experiments for 1990
JAFP-18-0113, Fifth Ten-Year Inservice Inspection Interval Program Plan
JAFP-07-0019, License Renewal Application, Amendment 9
LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 5, Reactor Coolant System and Connected Systems
JAFP-21-0073, Response to Request for Additional Information Regarding Application to Revise the James A. FitzPatrick Nuclear Power Plant Limiting Condition for Operation (LCO) 3.5.1, ECCS - Operating Surveillance.
RS-08-045, LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Chapter 5.0 - Reactor Coolant System and Connected Systems
RS-13-009, Clinton, Unit 1, Updated Safety Analysis Report, Revision 15, Chapter 5 - Reactor Coolant System and Connected Systems
RS-14-006, Clinton, Unit 1, Updated Safety Analysis Report, Revision 16, Chapter 5 - Reactor Coolant System and Connected Systems
RS-16-196, Clinton - Updated Safety Analysis Report (Usar), Revision 18, Chapter 5 - Reactor Coolant System and Connected Systems
JAFP-02-0098, Part 7 of 7, James A. FitzPatrick Nuclear Power Plant - Revision J to Proposed Technical Specification Change (License Amendment) Conversion to Improved Standard Technical Specifications, Bases
JAFP-17-0093, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2
NRC-16-0034, Fermi 2 Revision 20 to Updated Final Safety Analysis Report, Chapter 12
PY-CEI-NRR-0106, Responds to NRC Requesting Addl Copies of Inservice Testing Program for Pumps & Valves.Program & Drawings Encl.W/O Encl
JAFP-99-0171, Forwards Revised Ja FitzPatrick Nuclear Power Plant 1999 FSAR Update. Update Also Includes Changes to Chapter 17, QA Program Which Described in Attachment 1.No Commitments Contained in Ltr
AECM-84-0205, Submits Addl Response to IE Bulletin 80-24, Prevention of Damage Due to Water Leakage Inside Containment. Insp & Surveillance of Containment Sumps,Drywell,Piping & Closed Coolant Water Sys Discussed.Action Completed
PY-CEI-NRR-0302, Forwards Revised Vibration & Thermal Expansion Test Program. Categories of Proposed Changes Listed
NLS2017062, Licensee Guarantees of Payment of Deferred Premiums
JAFP-94-0150, Annual Summary of Changes,Tests & Experiments for 1993
JAFP-07-0116, Fourth Interval Inservice Testing Program for Pumps and Valves
RS-14-006, Clinton, Unit 1, Updated Safety Analysis Report, Revision 16, Chapter 9 - Auxiliary Systems
PY-CEI-NRR-0441, Forwards Info Re Status of Pending Changes to FSAR, Correcting Editorial Errors & Typos.Pending FSAR Change Pages Encl
RS-17-126, Quad Cities Nuclear Power Station, Units 1 & 2, Revision 14 to Updated Final Safety Analysis Report, Chapter 9, Auxiliary Systems
JAFP-99-0175, Annual Summary of Changes,Tests & Experiments for 1997/1998. with
JPN-92-040, Forwards Summary of IGSCC Insp During 1992 Refueling Outage. Core Spray Piping B in Primary Containment Replaced w/347 Modified Stainless Steel.Electrochemical Potential Monitoring Sys Installed in Reactor Water Recirculation Sys
BECO-89-094, Requests Exemption from Primary Containment Leakage Testing Requirements of 10CFR50,App J for Local Leak Rate Tests of Shutdown Cooling Suction Isolation Valves,Reactor Bldg Closed Cooling Water Isolation Valve & Drywell Head
CNL-22-002, Request for Relief from American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, in Accordance with 10 CFR 50.55a(g)(5)(iii) and 50.55a(g)(6) (BFN-2-ISI-003)
RS-16-196, Clinton - Updated Safety Analysis Report (Usar), Revision 18, Chapter 9 - Auxiliary Systems
JAFP-08-0038, Inservice Inspection Program Relief Requests Third Ten-year Interval Closeout
JPN-99-020, Submits Response to RAI Re ISI Program Relief Requests for Second 10-yr Interval Closeout & Summary Rept,Per 990426 Telcon with Nrc.Info Provided to Clarify or Withdraw Individual Relief Requests Contained in Summary Rept
JAFP-09-0072, Response to Request for Additional Information Regarding: Emergency License Amendment Request Application for Technical Specification 3.8.1 Required Action B.4 Completion Time
JAFP-06-0110, James A.Fitzpatrick, License Renewal Application Drawing List
NLS2018037, Licensee Guarantees of Payment of Deferred Premiums
NLS2017058, Nebraska Public Power District 2016 Financial Report
BVY-97-137, Forwards Response to 971009 RAI Re Plans for Implementing ASME Code Case N560 at Vermont Yankee Nuclear Power Station
JAFP-92-0598, Ja Fitzpatrick Nuclear Power Plant,Annual Summary of Changes,Tests & Experiments for 1991
JAFP-18-0078, Fifth Ten-Year Interval Inservice Testing Program Plan
JAFP-95-0176, Annual Summary of Changes,Tests & Experiments for 1994. W/
JAFP-20-0012, License Amendment Request - Application to Adopt Technical Specification Task Force Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2, Using the Consolidated Line.
JAFP-11-0046, 2011 Updated Final Safety Analysis Report, Technical Specification Bases and Technical Requirements Manual Changes Transmittal
RS-08-045, LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Appendix a Through Appendix N
JAFP-05-0069, Summary of Plant Changes, Tests, and Experiments for 2003 and 2004 as Required by 10 CFR 50.59 and 10 CFR 72.48, and Summary of Commitment Changes for 2003 and 2004
SNRC-1904, Forwards 10CFR50.59 Rept for Period from Jan-Dec 1991
BVY-97-105, Provides NRC W/Degradation Mechanism Evaluation & Results of Element & Segment Risk Rankings.Util Intends to Submit Revised ISI Program Following NRC Review of Evaluations & Risk Ranking,As Stated in Ltr
RS-13-009, Clinton, Unit 1, Updated Safety Analysis Report, Revision 15, Chapter 9 - Auxiliary Systems
JAFP-10-0079, Application for Amendment to Modify the Technical Specifications Requirements for Testing of Low Pressure Coolant Injection Inverter
JAFP-02-0008, December 2001 Monthly Operating Report for James A. FitzPatrick Nuclear Power Plant
JAFP-17-0085, High Frequency Confirmation Report for March 12, 2012, Information Request Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1, Seismic
NG-03-0642, August 2003 Monthly Operating Report for Duane Arnold Energy Center
PNO-III-83-100, on 831020,ultrasonic Testing Identified One Crack & Ten Crack Indications in Unit 2 Primary Sys Piping, Including Seven Indications in Reactor Water Recirculation Sys.Licensee Intends to Issue News Announcement
JAFP-91-0105, Monthly Operating Rept for Jan 1991 for Ja FitzPatrick Nuclear Power Plant
PNO-III-07-009, A: Perry: Update to Unexpected Reactor Shutdown Exceeding 72 Hours Due to Problem with Reactor Recirculation Pump Motor
JAFP-02-0064, Revised November 2001 Monthly Operating Report for James A. FitzPatrick
JAFP-03-0169, November 2003 Monthly Operating Report for James A. FitzPatrick Nuclear Power Plant
JAFP-09-0086, Application for Amendment for James A. FitzPatrick Nuclear Power Plant to Modify the Technical Specifications Requirements for Testing of the Shutdown Cooling System Isolation, Reactor Pressure - High Function
JAFP-03-0139, September 2003 Monthly Operating Report for James A. FitzPatrick Nuclear Power Plant
JAFP-02-0086, March 2002 Monthly Operating Report for James A. FitzPatrick Nuclear Power Plant
JAFP-02-0107, April 2002 Monthly Operating Report for James A. FitzPatrick Nuclear Power Plant
JAFP-14-0123, Response to Request for Additional Information (RAI) for Low Pressure Safety Limit License Amendment
JAFP-10-0033, Attachment 2 to JAFP-10-0033, Calculation JAF-CALC-NBS-02052, Revision 4
JPN-88-030, Forwards Addl Info Re Plant Alternate Rod Insertion & Recirculation Pump Trip Designs,Per ATWS Rule W/21 Oversize Drawings
JPN-91-032, Forwards Application for Amend to License DPR-59,changing TS Tables 3.2-7 & 4.2-7 to Reflect Change in Reactor Water Recirculation Pump Trip Logic & Increasing Min Number of Operable Channels from One to Two
JAFP-07-0079, License Renewal Application, Amendment 12
JAFP-98-0168, Monthly Operating Rept for Apr 1998 for Ja FitzPatrick Nuclear Power Plant
JAFP-89-0586, Monthly Operating Rept for Jul 1989 for Ja Fitzpatrick Nuclear Power Plant
JAFP-02-0199, September 2002 Monthly Operating Report for James A. FitzPatrick
HL-5107, Forwards Response to NRC Re Violations Noted in Insp Rept 50-366/95-26.Corrective Actions:Repaired Aforementioned Deficient Conditions
JAFP-02-0226, November 2002 Monthly Operating Report for James A.Fitzpatrick Nuclear Power Plant
NUREG-1905, Safety Evaluation Report Related to the License Renewal of James A. FitzPatrick Nuclear Power Plant
05000333/LER-2023-001, Primary Containment Isolation System Isolation Due to Initiation of Main Condenser Fire Protection Foam System
05000333/LER-1989-011-01, :on 890531,plugging of Non safety-related Floor Drains in Emergency Diesel Generator Rooms Performed W/O Prior Evaluation Required by 10CFR50.59.Cause Not Stated. Mod of Control Procedures Revised
05000333/LER-1987-018, :on 871108,reactor Tripped from High Neutron Flux Due to Erratic Operation of Reactor Water Recirculation Pump Speed Controller.Caused by Malfunction in Pump Speed Controller Switch.Controller Replaced
JPN-87-035, Forwards Insp Summary of Igscc,Per Util 861028 Commitment. Welds Classified According to NUREG-0313,Rev 2.Specific Insp Plans Will Be Addressed Prior to Next Scheduled Refueling Outage.Two Oversize Drawings Encl
05000322/LER-1986-028, :on 860710,environmentally Unqualified Jumper Wires Installed in Valve Operators Contrary to License Condition.Caused by Inability to Provide Documentation for Jumpers.Faulty Valve Operators Replaced
05000321/LER-1986-030, :on 860802,main Turbine & Reactor Feedwater Pumps Tripped Due to Feedwater Flow Oscillations.Caused by Opening of Min Flow Bypass Valves Due to Setpoint Error. Procedure Revised & Instruments Calibr
05000237/LER-1986-011, :on 860520,full Reactor Scram Occurred Due to Low Reactor Water Level.Caused by Personnel Error.Procedural Violation Rept Completed & Reactor Operator Informed of Necessity of Proper RWCU Sys Isolation
05000271/LER-1997-023, :on 971125,plant Trip Occurred.Caused by Failure of Protective Device in Main Generator Protective Circuitry.Operating Staff Placed Plant in Normal Shutdown Configuration
05000333/LER-1998-012, :on 981104,failure to Meet Primary Containment Leakage Rate Testing Program Requirements Was Noted.Caused by Deficient Test Procedures.Leak Rate Test Procedures Were Revised & Testing Was Completed.With
05000333/LER-1998-008, :on 980803,automatic Reactor Scram Occurred Due to Low RPV Water Level Following Degradation in Feedwater Flow.Completed Post Transient Evaluation Prior to Startup & Correcting Filling & Venting Procedure
05000333/LER-1992-053, :on 921228,Group I Isolations Occurred While Performing Surveillance Testing in Support of Unit Startup. Caused by Failed Relay.Relay Replaced & Satisfactory Testing Completed
05000333/LER-1992-013, :on 920226,determined That Actual Design & Design Described in FSAR Differ for Air Conditioning Sys for Environ Encls.Caused by Incomplete Understanding of Design & Operation of Equipment.Load Ctrs Qualified
05000333/LER-1992-047, :on 921104,automatic Shutdown Cooling Occurred Due to Loss of Power to Rps.Caused by Voltage Drop When Starting Large Electrical Load.Protective Device Setpoint Will Be Evaluated
JPN-92-067, Forwards Root Cause Failure Analysis of Equalization Line on Reactor Water Cleanup Valve 12RWC-46, & ASME Section XI Repair Program for Repair of RWCU Valve 12RWC-46 - 1/2 Inch Equalization Line Plant Mod M1-92-383
05000333/LER-1995-015-01, :on 951215,discovered Omission of RWR Seal Purge Flow from Reactor Heat Balance.Caused by Inadequacy in Original Plant Design.Restricted Plant Output to 2434 Mwt to Maintain More than 1.4 Mwt Margin
05000333/LER-1995-013-01, :on 950905,discovered Loss Feedwater Flow Transient Due to Personnel Error.Revised Abnormal Operating Procedure AOP-1
05000333/LER-1992-001-01, :on 920103,fire Watches Missed,Per Tech Spec 3.12.F.Caused by Inadequate Training & Supervision of Temporary Personnel.Supervisors Hired to Provide Training & Supervision
05000333/LER-1995-003, :on 950114,primary Containment Isolation Sys Group 2 Isolation Occurred.Caused by Abnormal Electrical Lineup & Procedural Deficiency.Procedure Controlling Bus Outage Restoration Will Be Revised
05000333/LER-1990-020, :on 900626,shutdown Cooling Mode of RHR Sys Isolated.Caused by Air in Pressure Switch Sensing Line Due to Deficient Installation Design.Possible Design Mod to Sensing Line to Eliminate Air Trap Considered
05000333/LER-1982-027-03, /03L-0:on 820616,recirculation Flow Transmitter 02-FT-110D Found Out of Calibr Causing Small Error in Half of Average Power Range Monitor Setpoint.Caused by Instrument Drift.Instrument Recalibr
05000333/LER-1990-016, :on 900424,automatic Isolation Signal Closed Suction Valves from Reactor Water Recirculation Sys.On 900425,suction Valves Closed & RHR Pump Tripped.Caused by Chattering Pressure Switch.Switches Replaced
JAFP-93-0207, Monthly Operating Rept for Mar 1993 for Ja Fitzpatrick Nuclear Power Plant
05000333/LER-1990-011, :on 900320,reactor High Pressure Logic Tripped, Isolating RHR Shutdown Cooling Sys B & Causing Trip of Isolation Pressure Switches.Caused by Internal Flow Transmitted in Reverse Direction
05000333/LER-1989-020, :on 891105,reactor Scram Occurred Due to Failure in Electronic Control Card of electro-hydraulic Control Sys.Caused by Void Collapse in Core Moderator. Circuit Boards Sent to Vendor for Analysis
JAFP-89-0820, Annual Summary of Changes,Tests & Experiments Completed at James a Fitzpatrick Nuclear Power Plant During 1988
JAFP-24-0053, License Amendment Request to Eliminate Remaining Main Steam Line Radiation Monitor Initiated Isolation Functions
JAFP-23-0064, Emergency Plan Document Revision
05000260/LER-1994-011, Forwards Voluntary LER 94-011 Re Failure of Magnesium Alloy Rotor Motor on Reactor Water Recirculation Sys Pump Discharge Valve.Rept Submitted Because of Potential Generic Applicability of Issues Surrounding Event to Other Util
05000260/LER-1994-011-01, :on 941001,magnesium Alloy Rotor Motor on Reactor Water Recirculation Sys Pump Discharge Isolation Valve Failed,Placing Facility in Lco.New Operator Motor Installed & Associated Breaker Replaced
JAFP-17-0054, Submittal of Stress Analysis Summary for the 24-10-130 Weld Overlay
05000333/LER-2017-002, Regarding Residual Heat Removal to Reactor Water Recirculation Loop a Weld Flaw Indication
05000333/LER-2016-001, Regarding System Actuations During Manual Scram in Response to Frazil Ice Blockage and Residual Transfer
RS-11-123, Supplemental Information Related to License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for Rcs
RS-11-036, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation
05000333/LER-2005-004, Re Residual Heat Removal (RHR) Shutdown Cooling Line Through-Wall Crack
RS-23-081, Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation
CNL-22-009, Request for Relief from American Society of Mechanical Engineers Boiler & Pressure Vessel Code, Section XI, In.
NUREG-1307, Rev. 20, Report on Waste Burial Charges: Changes in Decommissioning Waste Disposal Costs at Low-Level Waste Burial Facilities Final Report
JAFP-19-0083, License Amendment Request - Proposed Change to the Technical Specifications to Revise the Allowable Value for Reactor Water Cleanup (RWCU) System Primary Containment Isolation
PY-CEI-NRR-0716, Informs That Testing & Review of Updated Inservice Testing Program for Pumps & Valves Identified Need for New Relief Requests.Listing of New & Revised Relief Requests Encl.Fee Paid
05000333/LER-1995-011-01, :on 950531,leakage of Primary Containment Isolation Valves Was Exceeded.Caused by 02-2AOV-39 & 02- 2AOV-40 Experiencing Repeated Difficulty in Passing Llrt. Flushed Seat on Inboard Isolation Valve
05000333/LER-1995-010-01, :on 950530,TS Required Plant Shutdown Due to Unidentified Leakage Into Drywell.Repacked Valve 02-RWR-52B Using Current Maint Practice of Repacking w/non-asbestos Graphite
05000333/LER-1991-006-01, :on 910507,manual Reactor Shutdown Occurred Due to Inoperability of Both Low Pressure Coolant Injection Subsystems.Caused Mechancial Failure of One Valve in Each of Two Sys.Root Cause Investigation Started
05000333/LER-1994-009-01, :on 941129,partial Invalid Primary Containment Isolation as Result of Personnel Error During Electrical Bus Power Source Transfer.Operations Personnel Restored Sys to Normal in Accordance W/Plant Procedures
JAFP-25-0046, License Amendment Request - Proposed Change to the Technical Specifications to Revise the Allowable Value for Reactor Water Cleanup (RWCU) System Primary Containment Isolation