PLA-2756, Forwards Postulated Pipe Rupture Calculations M-MSS-010 & M-MSS-006,per NRC 861112 Telcon Request
NL-12-0016, Response to NRC Request for Additional Information on License Amendment Request for Technical Specification Table 3.3.1.1 in Response to Westinghouse NSAL 09-01, Rod Withdrawal at Power
L-PI-03-052, Annual Radioactive Effluent Report & Offsite Dose Calculation Manual. Attachment 4 Pages 77 - 211
ST-HL-AE-5654, Forwards Results for Hot,Full Flow Rod Drop Testing in Unit 2 Cycle 6,performed 970501.Core Map,Core Design Data & NRC Bulletin 96-001 Correspondence Table,Encl
ST-HL-AE-5605, Forwards Results of Control Rod Testing in Response to NRC Bulletin 96-001, Control Rod Insertion Problems
TXX-9333, Forwards Copy of Application for Renewal of NPDES Permit TX0065854
RA-21-0056, Refueling Outage 32 Steam Generator Tube Inspection Report
05000352/LER-1987-014, :on 870513,unplanned Nuclear Steam Supply Shutoff Sys Isolation Occurred When Momentary High Radiation Signal Received.Cause Unknown.Nuclear Steam Supply Shutoff Sys Isolation Logic Reset
05000410/LER-1986-014-01, :on 861203,scram Experienced to one-quarter of Control Rods During Recovery from Earlier Scram & Containment Isolation.Caused by Personnel Error.Addl Licensed Operator Training Requested
05000382/LER-1986-009, :on 860509,while Operating at 100% Power, Uncomplicated Reactor Trip Occurred.Caused by Failure of Reed Switch on Control Element Assembly 35.Faulty Switch Replaced & Assembly Calculator Returned to Svc
05000440/LER-1986-006, :on 860422 & 25,neutron Monitoring Sys Instrumentation Upscale Trips Resulted in One Manual & One Automatic Reactor Protection Sys Actuation.Spikes Caused by Electrical Noise.Bus Changes Implemented
05000250/LER-1985-021-01, :on 850722,two Automatic Initiations of Auxiliary Feedwater Sys Occurred Due to Bypass Feedwater Control Valves Malfunctioning.Caused by Moisture in Instrument Air.Actuators Inspected & Cleaned
05000482/LER-1985-077, :on 851031,hourly Fire Watches Not Initiated as Required When Fire Barrier Encl Around Auxiliary Feedwater Alternate Supply Valve Removed for Surveillance Testing. Caused by Personnel Error
05000344/LER-1993-001, :on 921008,determined That Sleeved Conduit Penetration Did Not Have Internal Seal Between Sleeve & Conduit Due to Personnel Error.Incorrect Drawing A-116 Revised to Show Wall Containing Penetration
05000482/LER-1985-012, :on 850419,inadvertent Train B Safety Injection Occurred.Caused by Loose Limit Switch Tug in Valve Motor Operator.Switch Lug Repaired
AECM-84-0465, Forwards Response to Generic Ltr 83-28,Items 1.1 & 1.2 Re post-trip Review Program Description & Procedure & Data & Info Capability,Respectively
05000324/LER-1990-010-02, :on 900822,reactor Protection Sys Bus a Deenergized During Cold Shutdown.Caused by Personnel Error. Operators Disciplined & Clearance Procedure Will Be Revised to Clarify Double/Independent Verification
05000259/LER-1981-061-03, /03L-0:on 811010,diesel Generator C Shut Down Prior to Normal Time Frame to Troubleshoot & Time ECR Relay. Cause Undetermined.Ecr Relay Calibr & Time Acceptable
05000352/LER-1991-002, :on 910109,replacement Cassette Drive Unit to Replace Inoperable Seismic Monitoring Sys Not Received by 910109,rendering Sys Inoperable for More than 30 Days.Caused by Grit on Gear.Sys Repaired
05000327/LER-1989-036, :on 891221,discovered That Surveillance Test Results Used for Declaring Diesel Generator 1B-B Operable Deficient.Caused by Instruction Not Including 60 Minute Run Time.Event Will Be Reviewed W/Supervisors
LR-N15-0169, Fifth Six-Month Status Report for the Hope Creek Generating Station in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events
RA-12-056, Submittal of Annual Radiological Environmental Operating Report for 2011
RS-02-145, Supplemental Request for Technical Specifications Change for Minimum Critical Power Ratio Safety Limit
SNRC-1315, Semiannual Radioactive Effluent Release Rept,Third & Fourth Quarters of 1986,1986 Meteorlogical Summary & Offsite Dose Assessment
05000456/LER-1996-003-03, :on 960308,Battery 112 Declared Inoperable Forcing Unit 1 Sd.Caused by Equipment Degradation Due to Successive Significant Discharges.Testing Performed to Verify Degraded Capacity & Battery Replaced