CNL-17-024, Update to License Amendment Request to Revise NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor - Revision to Tables S-2 and S-3
L-PI-15-041, License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors - Response to Request for Additional Information
CNL-14-001, Response to NRC Request for Additional Information Regarding the License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plant
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 1 of 9
GO2-09-050, Supplemental Response to Request for Additional Information Regarding License Amendment Request Involving Core Operating Limits Report and Scram Time Testing
GNRO-2008/00061, To Amendment Request, Changes to Technical Specification 5.6.5, Core Operating Limits Report (Colr)
NRC 2013-0028, Point Beach Nuclear Plant, Units 1 and 2: License Amendment Request 271 - Transition to 10 CFR 50.48(c) - NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition. Part 2
RA06-038, Post-Outage 90-Day Inservice Inspection Summary Report
DCL-03-009, Inservice Inspection Program Plan, Revision 2, Drawings104628, Sheets 1 - 52
NRC-91-0088, Forwards Proposed Changes to QA Program Re Assignment of Responsibilities for Procurement Document Review & Receiving Insp.Review/Insp Functions Can Be Effectively Performed W/O in-line QA Functions
SNRC-1283, BWR Owners Group Rept on Operational Design Basis of Selected Safety-Related Motor-Operated Valves
AECM-88-0107, Forwards Computer Tape of Hourly Meteorological Data for 1987.Note Tape Formatted Similar to Tape Sent Earlier by Ltr Except That Ebcdic Format Rather than Ascii Format Used.Sample Tape Dump Printout Also Encl
NRC-94-4237, Forwards Responses to NRC RAIs on AP600 from Ltrs of 940428, 29,0502,05,16 & 26.Revs of Responses Previously Submitted Also Provided
W3P87-0969, Cycle 2 Reload Startup Test Rept for Period Ending 870301
ULNRC-06011, Responses to RAI Set 3 Regarding Adoption of National Fire Protection Association Standard NFPA 805
L-2022-143, Subsequent License Renewal Application - Aging Management Requests for Additional Information Set 1A Response
ELV-00902, Requests Exemption from 10CFR20,App A,Footnote d-2(c) Re Worker Respiratory Protection Apparatus to Permit Utilization of Air Purifying Respirators in Lieu of Supplied Air or self-contained Breathing Apparatus
05000324/LER-1987-004-02, :on 870311,reactor Scram on Low Level Due to Loss of Uninteruptible Power Supply & Subsequent Loss of Feedwater.Caused by Noncompliance W/Procedure to Transfer Power.Motor Replaced & Sys Returned to Normal
U-600509, Forwards Qualification Installation Status by Equipment Number Rept for Feb 1986,in Response to Open Item 5,Section 3.10.1.3 of Sser 5 (NUREG-0853)
NOC-AE-000488, Forwards Repts on Status of Decommissioning Funding Available for Facility,Including Amount of Decommissioning Funds Estimated to Be Required,Amount Accumulated to End of CY98 & Schedule of Annual Amounts to Be Collected
B11972, Forwards Results of Evaluation of Ref Temp for Pressurized Thermal Shock from Time of Submittal to Expiration Date of Ol.Values Do Not Exceed Screening Criteria.Paragraphs (b)(3)-(6) of 10CFR50.61 Inapplicable to Facilities
B11878, Forwards Revised Responses to Sqrt Questions During 850304-08 Audit & Provides Status of Each Question
05000267/LER-1985-008, :on 850516,plant Protective Sys Scram Circuitry Actuated by Erroneous Signal Spike on Startup Channel 1. Caused by Moisture Leakage Into Startup Channel 1 Instrument Box Resulting in Mineral Deposits
05000382/LER-1985-017, :on 850505,uncomplicated Reactor Trip Occurred. Caused by Inadvertent Closure of MSIV 2 Due to Pressure Transducer Malfunction & Back Leakage of Oil in Check Valve. Faulty Components Replaced
0CAN058402, Annual Environ Radiological Monitoring Rept,1983
05000353/LER-1992-001, :on 920104,high Pressure Coolant Injection Sys, D24 Emergency Diesel Generator D RHR Sys & D Core Inoperable Due to Blown Fuse.Switches in Card File E21A-Z3D Inspected. Failed Switch Replaced
LD-91-067, Forwards Response to NRC 910729 Request for Addl Info Re Engineering SSAR - Design Certification Covering IEEE Stds, Offsite Power Sys,Control Room Indication of Emergency Diesel Generator Operational Status & Dc Power Sys
05000318/LER-1978-049-03, /03L-0 on 781225:during Normal Operation,Cracked Weld Was Found on Suction Line of 23 Reactor Cooling Pump, Due to Crack in Charging Pump Suction Line Pumping
05000305/LER-1983-024-03, /03L-0:on 831020,during Full Power Operation, Technical Review of Maint Work Requests Disclosed That Svc Water Pump 1B2 Removed from Svc on 830914 for Corrective Maint.Limiting Condition Reportable
05000370/LER-1990-001-05, :on 900122,containment Isolation Valve Inoperable.Caused by Unanticipated Interaction of Components Due to Field Routing.Inside Personnel Air Lock Door Closed to Provide Addl Flow Path Barrier
05000320/LER-1979-014-01, /01L-0:on 790328,during Normal Operation,Unit Experienced Loss of Feedwater.Intensive Study of Procedural Activities Carried Out by Nrc.Summary of Violations,Causes, Sequence of Events & Corrective Actions Encl
NRC-17-0067, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control
05000482/LER-2011-009, Regarding Inadequate Oil Analysis Caused Inoperable Auxiliary Feedwater Pump Longer than Required Action Completion Time
RBG-46943, Supplement to License Amendment Request (LAR) Changes to Technical Specification 5.6.5, Core Operating Limits Report (Colr)
05000254/LER-2006-003, Regarding Unexpected Start of the Division II Emergency Diesel Generator Due to Failure to Open Test Switch
IA-89-360, Package of Records Re Automated Info Documentation Sys
LR-N25-0038, License Amendment Request (LAR) - Hope Creek Technical Specification Conversion to NUREG-1433, Revision 5, Supplement 3
BSEP-98-0090, Provides Comments on Draft SE Re Conversion to Improved Tech Specs.Encl 2 Provides Draft SE pages,marked-up to Reflect Comments as Well as Addl Editorial Comments
05000325/LER-1987-007-01, :on 870307 & 08,common Control Bldg HVAC Sys Autoisolated,By Design,Due to Spurious Actuations of Sys Air Intake Plenum Chlorine Detector.Caused by Momentary Electrical Resistance Changes in Detector