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Regulatory Guide 1.196
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RS-16-198, Request for License Amendment Regarding High Burnup Atrium-10 Partial Length Fuel Rods
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RS-15-163, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 2, Flood Hazard Reevaluation Report
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RS-15-064, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 2, Flood Hazard Reevaluation Report
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RC-14-0179, Calculation - DC00040-123 - Rod Ejection Accident - TSC
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RS-14-052, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 2, Flood Hazard Reevaluation Report
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2CAN111301, Response to Request for Additional Information, Adoption of National Fire Protection Association Standard NFPA-805
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3F0913-01, Response to NRC Request for Information Re Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident - 1.5 Year Response for CEUS Site
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GNRO-2013/00020, Required Response 2 for Near-Term Task Force Recommendation 2.1: Flooding - Hazard Reevaluation Report
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W3F1-2012-0064, Response to Request for Additional Information Regarding Adoption of National Fire Protection Association Standard NFPA 805 License Amendment Request
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GO2-12-017, License Amendment Request to Change Technical Specification in Support of Prnm/Arts/Mellla Implementation
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RS-14-053, Byron Station, Units 1 and 2, Exelon Generation Company, LLC Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 2, Flood Hazard Reevaluation Report
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RS-14-054, Clinton Power Station, Unit 1 - Exelon Generation Company, LLC Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 2, Flood Hazard Reevaluation Report (FHRR)
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RS-11-100, Dresden, Units 2 and 3, Updated Final Safety Analysis Report (Ufsar), Revision 9, Technical Specification Bases
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ML20235Q519
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ML20235L699
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ML20234C122
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ML20217P154
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ML21063A324
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ML21074A306
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IA-99-234, Partially Withheld Investigation Rept 4-1998-045.No Nonconformance Noted.Major Areas Investigated:Discrimination Against Former Contract Employee by Supervisor for Reporting Concerns to Nuclear Safety Concerns Program
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ML21101A002
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HBL-89-020, Annual Survey & Facility Status Rept,880719-1231
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HBL-98-006, Forwards Annual Facility Status & Survey Rept for 1997. Section a Addresses Facility Status & Section B Presents Results of Monitoring Performed for Radiological Environ Monitoring Program
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ML20210T690
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ML20210T310
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ML20209E160
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B12440, Startup Test Rept Cycle 8
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JAFP-87-0297, Forwards Rev 5 to Ja Fitzpatrick Nuclear Power Plant Offsite Dose Calculation Manual & Util Response to NRC Questions Re Commission Review of Manual,Per Hi Abelson 861002 Request
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A05027, Forwards Addl Info Re 850102 Draft 2 to Rev 0 of Emergency Plan,Per 850520 & 0701 Requests.Responses to Items Identified in NRC 850722-26 Emergency Preparedness Appraisal Also Encl.Rev 0 of Plan to Be Submitted by 850913
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ML20268B084
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ML21305A182
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ML22033A158
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ML22033A156
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ML22033A155
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ML22033A148
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ML22033A144
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ML22033A141
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ML22118B143
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ML20153A801
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ML22122A230
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ML20149K692
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L-97-029, Annual Facility Status & Survey Rept for Jan-Dec 1996
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ML20115E359
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JAFP-96-0190, Ja FitzPatrick Nuclear Power Plant,Radiological Environ Operating Rept for 1995
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NRC-92-1106, Step 1 TER of Perry IPE Back End Submittal,Final Rept
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ET-NRC-93-4027, Forwards Responses to RAIs on AP600 from NRC
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ML21187A240
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ML20213B074
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ML24039A183
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L-2023-098, And Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2
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NMP2L2794, Supplemental Information to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Adopt TSTF-582, Revision 0
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ML20210S952
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ML20205C357
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ML20205N819
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LER-1985-024, :on 851212,turbine Trip & Subsequent HPCI Mode of Feedwater Initiation Occurred.Caused by Difference Between Level Indications Due to Different Indicator Mfg. Water Level Lowered & HPCI Reset
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ML20101H126
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05000271/LER-1984-018, :on 840801,w/reactor Shut Down & While Shifting 480-volt Vital Buses,Voltage Transient Caused Inadvertent hi-hi Trip from APRM C Which Resulted in Reactor Scram.Scram Reset
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CNL-20-005, License Amendment Request to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position, (WBN-TS-20-02)
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ML20092H451
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03L-0:on 830617,during Functional Surveillance Testing by Wyle Lab,One Main Steam Snubber Failed to Meet Bleed Rate Criteria & One Svc Water Snubber Failed to Meet Lockup Rate.Caused by Plugging by Foreign Matl
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label: 05000298/LER-1983-010-03, /03L-0:on 830617,during Functional Surveillance Testing by Wyle Lab,One Main Steam Snubber Failed to Meet Bleed Rate Criteria & One Svc Water Snubber Failed to Meet Lockup Rate.Caused by Plugging by Foreign Matl
page: https://kanterella.com/05000298/LER-2D1983-2D010-2D03-2C_/03L-2D0-3Aon_830617-2Cduring_Functional_Surveillance_Testing_by_Wyle_Lab-2COne_Main_Steam_Snubber_Failed_to_Meet_Bleed_Rate_Criteria_-26_One_S…
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830608 Ltr
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label: 05000298/LER-1983-006-03, /03L-0:on 830509,during Performance of Surveillance Procedure 6.3.10.9.1,four RHR Mechanical Snubbers Frozen.Caused by RHR Shutdown Cooling Creating Water Hammer & Overloading snubbers.w/830608 Ltr
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ML20072A818
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ML20092H460
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ML20077D859
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ST-HL-AE-1220, Forwards Response to FSAR Questions 032.42,032.44 & 032.45 to Support Resolution of Questions from Instrumentation & Controls Sys Branch 850326 Review Meeting.Info Will Be Included in FSAR Amend 46
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JAFP-94-0240, 1993 Radiological Environ Operating Rept Ja FitzPatrick Nuclear Power Plant
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544 Snubber Exceeded Specified Acceleration Rate.Caused by Improper Installation of Clutch Spring.Snubber Sent to Manufactures for Repair
type: Subject
label: 05000298/LER-1982-008-03, /03L-0:on 820415,during Diagnostic Testing of Mechanical Snubbers,Model PSA-10 SN/544 Snubber Exceeded Specified Acceleration Rate.Caused by Improper Installation of Clutch Spring.Snubber Sent to Manufactures for Repair
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ML20058L409
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ML20064J027
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ML20092F621
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IR 05000424/1993005
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HBL-90-018, Annual Facility Status & Survey Rept,1989
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ML20029B208
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ML20003F005
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Vent Header Deflector Installation Outage,B Standby Gas Treatment Filter Train Would Not Auto Start. Caused by Previous Trip from Local Control Panel
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