Reactor Building Closed Loop Cooling# QUERYc6b85d30dd72fb2ef4cda49a405a9cf4
Reactor Building Closed Loop Cooling
Reactor Building Closed Loop Cooling# QUERY60f14cd075e1b78f54c9d3d81d7f0fb8
Reactor Building Closed Loop Cooling# QUERYbcee7ea8a6bce8dd2c2eff37d7595c95
Reactor Building Closed Loop Cooling# QUERY1e4b054dece01d3999a0b2b93bf0b67d
Reactor Building Closed Loop Cooling# QUERY61aad43330585e944a33ab191ac96a3a
RS-15-057, February 2015 Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
L-14-028, August 2014 Six-Month Status Report in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order EA-12-049)
JAFP-07-0116, Fourth Interval Inservice Testing Program for Pumps and Valves
JAFP-07-0019, License Renewal Application, Amendment 9
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
JPN-99-039, Proposed Change to TS (JPTS-99-006) Laboratory Testing of Nuclear-Grade Charcoal 180-Day Response to NRC Generic Letter 99-02
JAFP-18-0078, Fifth Ten-Year Interval Inservice Testing Program Plan
JAFP-18-0106, License Amendment Request: Proposed Change to the Technical Specifications to Remove Ultimate Heat Sink Bar Rack Heaters from Technical Specifications
JAFP-03-0065, Summary of Plant Changes, Tests, & Experiments for 2001/2002 as Required by 10 CFR 50.59 & 10 CFR 72.48, & Summary of Commitment Changes for 2001/2002
IA-87-546, Final Response to FOIA Request for Rept to ACRS Re Util Facility.App a Document Encl & Available in PDR
JAFP-89-0689, Responds to NRC Re Violations Noted in Rept 50-333/89-80.Corrective Actions:Util Established Formal Preventive Maint Program in 1984 Which Includes 600-volt Class 1E Circuit Breakers,Motor Starters & Transformers
JAFP-88-0004, Summary of Changes,Tests & Experiments Implemented at Plant During 1986,per Requirements of 10CFR50.59
JAFP-97-0326, Submits Info Requested by NRC on 970729 Re Maintenance Rule Insp Planned for Week of 970929
JAFP-99-0097, Forwards JAFNPP Referenced Simulation Facility Four Year Performance Testing Rept, Containing Description of Performance Testing Completed During Past Four Years & Description of Testing Scheduled During Next Four Years
JPN-97-019, Provides Summary of Detailed Evaluation of Postulated Scenarios Described in GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions & CA for JAFNPP IAW Ref Commitment
JAFP-97-0202, Annual Summary of Plant Changes,Tests & Experiments for 1996
JPN-97-003, Provides Required 120 Day Response to NRC GL-96-06, Assurance of Equipment Operability....Conditions, to Determine If Cacss Susceptible to Water Hammer or two-phase Flow Conditions During Postulated Accident Conditions
JAFP-85-0587, Annual Summary of Mods,Changes & Experiments Implemented at James a Fitzpatrick Nuclear Power Plant During 1984
SNRC-1397, Forwards Rev 1 of Updated Sar,Rev 3 of Fire Hazard Analysis Rept & 10CFR50.59 Rept for 860101-870607.Format for 10CFR50.59 Rept Listed.Jd Leonard Affidavit Encl
SNRC-1348, Forwards Addl Info Re Low Power Operation at 25%,per 870616 Request.Info Should Close Out Correspondence in View of NRC Cancellation of Util 25% Power Request
SNRC-1305, Rept of Changes,Tests & Experiments Completed During 1985, Per 10CFR50.4 & 50.59
SNRC-1464, Forwards Comments W/Supporting Documentation Re post-NRC Written Operator Exams,To Assist in Evaluating Responses to Exam Questions
SNRC-1416, Discusses Util Plans to Continue Effort for High Level of Performance,Including Actions Re post-work Housekeeping & Increased Supervisory Field Time,Lers & Technical Support, Per SALP Rept for Mar 1986 - Jul 1987
JAFP-96-0168, Annual Summary of Changes,Tests & Experiments for 1995. W/
SNRC-1092, Forwards Revised FSAR Sections,Providing Detailed Technical Bases & Methods Utilized in Developing Qualified Load of 3,300 Kw,In Response to Section 4.6 of SER on Tdi Owners Group Program Plan.Revs to Be Included in Fsar,Rev 34
JAFP-92-0470, Ja Fitzpatrick Nuclear Power Plant Annual Summary of Changes,Tests & Experiments for 1990
SNRC-1104, Forwards Requested Addl Info Re Various Aspects of Newly Developed Qualified Load for Tdi Diesel Generators,Per 841026 Telcon
SNRC-1078, Forwards Revs to FSAR Chapter 13, Conduct of Operations & Section 17.2, QA During Operations Phase, Reflecting Operational Readiness.Revs Will Be Included in Forthcoming Rev 33 to FSAR
JAFP-95-0483, Forwards Rev 9 to Ja Fitzpatrick Nuclear Power Plant IST Program for Pumps & Valves Second Interval
JPN-92-008, Forwards Response to NRC Request for Addl Info Re Certain Findings Noted in Diagnostic Evaluation Team Insp Rept
JAFP-84-0598, Summary of Changes,Mods & Tests Implemented During 1983,per 10CFR50.59
SNRC-1026, Forwards Supplemental Motion for Low Power OL
JAFP-95-0176, Annual Summary of Changes,Tests & Experiments for 1994. W/
JAFP-91-0414, Discusses Reevaluation of NRC Bulletin 80-10, Containment of Nonradioactive Sys & Resulting Potential for Unmonitored Release to Environ
BSEP-94-0362, Requests Relief from ASME Boiler & Pressure Vessel Code, Section Xi,Isi Program Re Use of ASME Code Case N-522
JAFP-91-0228, Forwards Update of Status of Activities for Emergency Svc Water Sys Per NRC 901009 Request Re 900821 Enforcement Conference.Updated Response to Generic Ltr 89-13 Will Be Provided by 910430
JAFP-94-0150, Annual Summary of Changes,Tests & Experiments for 1993
BECO-90-106, Responds to 900103 Request for Confirmation That Evaluations of Compliance W/Station Blackout Rule Conducted,Per NUMARC-87-00.Util Selects Diesel Generator Target of 0.975 & Station Blackout Coping Duration of 4 H to Implement Rule
JPN-93-089, Forwards Response to NRC 930518 Request for Addl Info Re Power Uprate Program & Errata to NEDC-32016P.Errata Withheld
NUREG-1905, Safety Evaluation Report Related to the License Renewal of James A. FitzPatrick Nuclear Power Plant
05000322/LER-1989-004, :on 890314,inadvertent Reactor Bldg Closed Loop Cooling Water Isolation/Split Occurred After Tech Specs Surveillance Test on Emergency Bus 101.Caused by Inadequate Procedural Guidance.Procedure Revised
05000322/LER-1987-023, :on 870717,reactor Bldg Closed Loop Cooling Water (RBCLCW) Unplanned Automatic sys-split Occurred. Caused by Lo Lo Water Level in RBCLCW Head Tank A.Alternate Methods of Filling HXs Under Consideration
05000220/LER-1998-001-01, :on 980129,violation of Secondary Containment Was Noted.Caused by Knowledge Deficiency of Personnel Assessing Plant Impact of Maint Work.Plant Impact Statements in Maint Procedure Have Changed
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
05000220/LER-1986-033, :on 861121,reactor Bldg Closed Loop Cooling HX Failed Inservice Insp Hydrostatic Test Due to Crack in Weld. Caused by Improper Welding of silicon-bronze to Carbon Steel Weld.Hx Isolated & Under Repair
05000410/LER-1986-027-01, :on 861215,Agastat GP Series Relay Failed to Function During Preoperational Test.Caused by Improper Seating of Relays in Sockets.Relays Properly Seated & Maint Procedure Revised.Part 21 Related
05000220/LER-1986-006, :on 860409,discovered That One of four-inch Sample Lines to Header Completely Plugged.Caused by Pebbles Washed Off Reactor Bldg Into Roof Drains.Roof Drain Screens Will Be Installed
05000410/LER-1986-018-01, :on 861216,while Testing Off Normal Status Sys Isolators,Electrician Placed Jumpers from 120-volt Dc Source to 120-volt Ac Line Source,Resulting in Blown Fuse.Caused by Test Engineer Error.Engineer Disciplined
05000322/LER-1986-030, :on 860727 & 0811,ESF Automatic Actuations Occurred.Caused by Thunderstorms Producing Power Spikes. Engineering Requested to Evaluate Events to Determine If Common Mode Failure Exists
05000322/LER-1986-024, :on 860522,unplanned Automatic Reactor Bldg Closed Loop Cooling Water Side a Isolation Occurred.Caused by Technician Placing Wrench on Lower Isolation Valve Piping.Investigation in Progress
05000322/LER-1987-003, :on 870318,loss of Offsite Power Experienced Coincident W/Starting of Condensate Pump 1N21-P-007A,causing Isolation of Normal Station Svc Transformer.Caused by Inadequate Procedure.Procedure Revised
05000322/LER-1988-016, :on 881011,fluctuation in Sys Voltage Occurred & Numerous ESF Actuated Due to External Source.Caused by Circumstances Beyond Control of Plant.No Corrective Actions Warranted & LER Will Become Required Reading
05000322/LER-1988-019, :on 881106,reactor Building Closed Loop Cooling Water Split on lo-lo Head Tank Level During Placement of HX Into Svc Due to Filling & Venting Problem.Procedure Identifying Deficiencies Performed
05000333/LER-1988-011, :on 881031,trip of Operating 115 Kv Offsite Reserve Power Line Resulted in Short Loss of Alternating Current Power.Caused by Momentary Fault on 115 Kv Line.Sys Restored to Normal
05000322/LER-1988-006, :on 880430,loss of Emergency Bus 101 Occurred W/Subsequent Start of Emergency Diesel Generator 101 & Numerous ESF Actuations.Caused by Personnel Error.Procedural Revs Implemented to Emphasize Impact of Steps
05000322/LER-1985-046, :on 850927,ESF Actuations Occurred Due to Spiking Low Voltage Conditions on 138-kV Transmission Sys & Fire Watches Suspended.Caused by Hurricane Gloria.Sys Reset & Fire Watch Resumed
05000322/LER-1985-033, :on 850825,inadvertent Split of Reactor Bldg Closed Loop Cooling Water Into Accident Mode Occurred.Caused by Personnel Error Due to Reproductive Quality of Drawing. Drawings Reviewed for Clarity
05000333/LER-1996-012-01, :on 961111,primary Containment Accumulative Leakage in Excess of Maximum Allowed by TS Occurred.Caused by Build Up on Valve Seat Areas.Efes Were Completed for Each Failed Valve
05000220/LER-1984-015, :on 840807,protective Relaying Actuated Causing Loss of Power to Power Boards 103 & 17B.Caused by Personnel Error.Operator Reestablished Offsite Power to Powerboards.Procedural Changes Implemented
JAFP-92-0598, Ja Fitzpatrick Nuclear Power Plant,Annual Summary of Changes,Tests & Experiments for 1991
05000333/LER-1991-031, :on 911202,potential Design Deficiency Identified in Emergency Svc Water Sys.Caused by Inadequate Design Review During Original Const.Procedural Changes Made, Requiring Running RHR Swp During EDG Operation
JPN-91-047, Forwards Status Rept on 18 Tasks Committed to by Util to Complete Response to Generic Ltr 88-14, Instrument Air Supply Problems Affecting Safety-Related Equipment. Only 4 of 18 Tasks Remain to Be Completed
JAFP-82-0495, Forwards Annual Summary of Plant Mods,Changes & Experiments Implemented During 1981 & 1981-1982 Refueling Outage
JAFP-81-0871, Responds to NRC Re Violations Noted in IE Insp Rept 50-333/81-07.Corrective Actions:Remote Manual Motor Operated Valves for Reactor Bldg Closed Loop Cooling Sys Will Be Installed
JPN-90-015, Forwards Response to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Testing of Circulating Water/Svc Water Sys for Mussels Will Begin Spring 1990
JAFP-89-0820, Annual Summary of Changes,Tests & Experiments Completed at James a Fitzpatrick Nuclear Power Plant During 1988
05000333/LER-1989-015, :on 890918,two Remote Manually Operated Diaphragm Air Operated Isolation Valves Failed Closing Time Acceptance Criteria.Caused by Buildup of Iron Oxide Sludge. Valves Disassembled & Cleaned
JPN-89-068, Forwards Response to NRC 890518 Request for Addl Info Re Util 890117 Proposed Tech Specs Change Re Containment Isolation Valves.Proposed Tech Spec Page 186 Also Encl
JAFP-24-0053, License Amendment Request to Eliminate Remaining Main Steam Line Radiation Monitor Initiated Isolation Functions
JAFP-23-0064, Emergency Plan Document Revision
05000410/LER-2015-003, Regarding Primary Containment Isolation Function for Some Valves Not Maintained During Surveillance Testing
JAFP-03-0096, Proposed Relief Request No. VRR-08 to In-Service Testing Program
JPN-92-046, Responds to NRC 920520 Request for Addl Info Based on Review of 910913 Submittal of Ipe,In Response to Generic Ltr 88-20, IPE for Severe Accident Vulnerabilities
JAFP-21-0089, Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position
SNRC-1234, Suppl 1 to Startup Rept for 851115-860215
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