L-17-233, High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force (NTTF) Review of Insights from the Fukishima Dai-ichi Accident
RS-16-225, Revised Request for License Amendment Regarding High Burnup Atrium-10 Partial Length Fuel Rods and Request for Exigent Review
RS-16-198, Request for License Amendment Regarding High Burnup Atrium-10 Partial Length Fuel Rods
CNS-16-043, Additional Information Regarding Flood Hazard Reevaluation Report, Response to Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3 of the Near-Term Task Forc
RS-18-009, License Amendment Request for Temporary Extensions to Technical Specifications Supporting Maintenance on Portions of the Core Standby Cooling System
ONS-2015-106, Technical Specification (TS) Bases Change
RS-15-268, Regarding Response to NRC Audit Review Request for Additional Information Regarding Fukushima Lessons Learned - Flood Hazard Reevaluation Report
RS-15-163, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 2, Flood Hazard Reevaluation Report
RS-15-064, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 2, Flood Hazard Reevaluation Report
RNP-RA/15-0023, Response (60-Day) to Request for Additional Information Associated with License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 805
RC-14-0179, Calculation - DC00040-123 - Rod Ejection Accident - TSC
RS-14-052, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 2, Flood Hazard Reevaluation Report
2CAN111301, Response to Request for Additional Information, Adoption of National Fire Protection Association Standard NFPA-805
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
GNRO-2013/00020, Required Response 2 for Near-Term Task Force Recommendation 2.1: Flooding - Hazard Reevaluation Report
W3F1-2012-0064, Response to Request for Additional Information Regarding Adoption of National Fire Protection Association Standard NFPA 805 License Amendment Request
GO2-12-017, License Amendment Request to Change Technical Specification in Support of Prnm/Arts/Mellla Implementation
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
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)
RS-11-100, Dresden, Units 2 and 3, Updated Final Safety Analysis Report (Ufsar), Revision 9, Technical Specification Bases
L-2011-206, ANP-3000(NP), Rev. 0, St. Lucie Nuclear, Unit 1 - EPU-Information to Support License Amendment Request, Attachment 6
RS-09-130, Additional Information Supporting Request for License Amendment Regarding Application of Alternative Source Term
NEI 99-01, Arkansas Nuclear One Units 1 & 2, Proposed Emergency Action Levels Using NEI 99-01 Revision 5 Scheme
RS-17-088, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Integrated Assessment Submittal
RA-18-0282, Technical Specification Bases Changes
BSEP 05-0043, Submittal of Technical Specification Bases Change
BSEP 04-0046, Submittal of Technical Specification Bases Changes
BSEP 04-0015, Supplement to Request for License Amendments Regarding Core Flow Operating Range Expansion
NRC 2003-0025, Supplement to Generic Letter 96-06 Resolution
HL-6244, Request to Revise Technical Specifications, Deletion of Technical Specification 3.3.1.1.I.2
NRC-94-4194, Forwards Responses to NRC Requests for Addl Info Re AP600
IA-85-800, Package Consisting of Four Notifications of Personnel Action,Dtd 851127 & 0506,for WT Russell
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
HBL-89-020, Annual Survey & Facility Status Rept,880719-1231
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
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
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
L-97-029, Annual Facility Status & Survey Rept for Jan-Dec 1996
JAFP-96-0190, Ja FitzPatrick Nuclear Power Plant,Radiological Environ Operating Rept for 1995
NRC-92-1106, Step 1 TER of Perry IPE Back End Submittal,Final Rept
ET-NRC-93-4027, Forwards Responses to RAIs on AP600 from NRC
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
NMP2L2794, Supplemental Information to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Adopt TSTF-582, Revision 0
05000220/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
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
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)
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
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
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
JAFP-94-0240, 1993 Radiological Environ Operating Rept Ja FitzPatrick Nuclear Power Plant
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
HBL-90-018, Annual Facility Status & Survey Rept,1989
05000366/LER-1980-060-03, /03L-0:on 800411,w/unit in Cold Shutdown for Surveillance/Vent Header Deflector Installation Outage,B Standby Gas Treatment Filter Train Would Not Auto Start. Caused by Previous Trip from Local Control Panel
TSTF-19-08, Draft of Traveler TSTF-582, Revision 0, RPV WIC Enhancements
RAIO-0119-64281, LLC Response to NRC Request for Additional Information No. 512 (Erai No. 9634) on the NuScale Design Certification Application
L-83-578, Advises That Emergency Operations Facility Completed & Declared Operational on 830901
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)
L-15-074, FENOC, Perry Nuclear Power Plant - Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force (NTTF) Review of Insights from the Fukushima Dai-ichi Ac
05000482/LER-2010-014, For Wolf Creek Generating Station, Regarding Technical Specification Required Shutdown Due to Inadequate Planning Resulting in Extended Emergency Diesel Generator Inoperability
RAIO-0917-56153, LLC Response to NRC Request for Additional Information No. 156 (Erai No. 9031) on the NuScale Design Certification Application
NRC-93-0102, Enrico Fermi Atomic Power Plant,Unit 1 Annual Rept for Jul- 1992-June 1993
RBG-17-098, Forwards Responses to Containment Sys Branch Questions 480.7 & 480.16 Re Prv & Major Components & Suppression Pool Bypass Leakage & FSAR Revs to Be Included in Next Amend
NLS2021040, Submittal of Emergency Plan, Revision 77 and Summary of 50.54( Q) Analysis
L-16-091, Revision of Flood Hazard Reevaluation Report in Response to NRC Request for Additional Information, Per 10CFR50.54(f) Regarding the Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force (NTTF) Review of Insights from the Fukush
RA17-055, Post-Outage 90-Day Inservice Inspection (ISI) Summary Report