PLA-2840, Forwards Application Proposing Amends 95 & 48 to Licenses NPF-14 & NPF-22,respectively,changing Tech Spec 4.1.3.1.4(a) Re Surveillance of Scram Discharge Vol Vent & Drain Valves. Fee Paid
L-2011-498, Units, 3 & 4 - 10 CFR 50.59 Summary Report of Changes, Tests and Experiments for Period Covering 12/04/2009 Through 05/16/2011 and Updated Technical Specification Bases
LR-N09-0164, License Amendment Request to Correct Technical Specification and Facility Operating License Editorial Items
L-2007-175, Rod Position Indication Systems
L-2007-083, License Amendment Request (LAR 192) Inoperable Rod Position Indication
L-2006-209, License Amendment Request Inoperable Rod Position Indication
NRC-95-0096, Application for Amend to License NPF-43,revising TS Re Sys Testing,Instrumentation Calibr,Component Insp,Component Testing,Response Time Testing & Logic Sys Functional Tests to Allow one-time Extension of Surveillance Intervals
U-601107, Responds to NRC Re Plant Inservice Testing Program.Listed Valves in CRD Sys & Diesel Generator Subsystem Will Be Added to Inservice Testing Program.Encl Relief Requests Describe Testing for Valves
LR-N970217, Application for Amend to License NPF-7,revising Sections of TSs to Delete Reference to Rod Sequence Control Sys & Reduce Rod Worth Minimizer Low Power Setpoint from 20% to 10%
ULNRC-03311, Advises That Amend 105 to License NPF-30,approving TS Changes to TS 4.1.3.1.2,4.4.6.2.2.b,4.4.3.2,4.6.2.1.d, 4.6.4.2 & TS Table 4.3-3 to Implement Recommendations of NRC GL 93-05 Implemented
ULNRC-03230, Application for Amend to License NPF-30.Amend Would Revise TSs to Implement Recommendations of GL 93-05 Re Reduction of SRs for Testing During Power Operation
05000454/LER-1986-012-01, :on 860327,RPI Surveillance Not Performed within 4 H.Caused by Personnel Error.Bank Demand Vs Digital RPI Surveillance Reinstated
05000370/LER-1987-002-02, :on 870113,surveillance to Detect Control Rod Deviations Not Performed After Control Rod Deviation Monitor Program on Operator Aid Computer Became Inoperable.Caused by Operator Oversight.Personnel Counseled
05000454/LER-1986-012-02, :on 860327,4 H Surveillance of Digital Rod Position Indication Vs Bank Demand Position Indication Mistakenly Stopped.Caused by Personnel Error.More Specific Instructions on Daily Orders Instituted
05000352/LER-1985-078, :on 850831,Tech Spec Surveillance Test for Control Rod Operability Not Performed.Caused by Personnel Error.Surveillance Test Performed on 851001.Test Now Listed on Weekly Schedule
05000370/LER-1984-032-01, :on 841207,Westinghouse Notified Util of CRD Mechanism Fabrication Error.Caused by Loose Guide Screw. Drive Mechanisms Inspected & Repaired as Necessary During Outage
05000370/LER-1984-032, :on 841205,notification Received of Event at Korean Unit 5 Re CRD Mechanism Design Similar to Mechanism Installed at Facility.Safety Implications of Continued Operation Evaluated & Interim Actions Taken
05000338/LER-1994-004-02, :on 940621,sixteen Individual Control Rod Position Analog Computer Points Were Discovered Off Scan. Caused by Computer Points Being Off Scan.Computer Points Were Returned to Scan & Operation
05000336/LER-1983-004-03, /03L-0:on 830218,while in Mode 1,CEA 16 Dropped 27 Steps During Surveillance Testing Per Tech Spec 4.1.3.1.2. Cause Unknown.Cea Withdrawn & Coil Power Programmer Power Main & Backup Supplies Tested
05000368/LER-1990-010, :on 900401,personnel Failed to Complete Control Element Assembly Position Log.Caused by Surveillance Program Deficiencies & Lack of Mgt Involvement.Shift Briefing Completed & Procedure Change Incorporated
AECM-83-0422, Application for Amend to License NPF-13,proposing Tech Spec Changes to Enhance Clarity or Provide Consistency W/Plant Design & Operation,Per NRC 821020 Confirmation of Action Ltr.Detailed Description of Proposed Changes Encl
05000336/LER-1978-014-03, /03L-0 on 780617:while Performing Monthly Control Element Assembly Surveillance Testing,Assembly 2 Dropped to Zero Steps from 178 Steps.No Component Failures Causing Control Element Assembly to Drop
05000311/LER-1998-004, :on 980204,failure to Comply W/Ts SR 4.1.3.1.1 Was Noted.Caused by Human Error.Review of Both Units 1 & 2 P250 Computer Points Was Conducted
HNP-99-149, Application for Amend to License NPF-63,implementing Selected Improvements Described in GL 93-05
GO2-94-248, Application for Amend to License NPF-21,revising TS 3/4.1.3.1, Reactivity Control Sys
GO2-94-208, Discusses Withdrawal of Requests for Amend to Tech Specs
GO2-93-029, Application for Amend to License NPF-21,changing TS 4.1.3.1.4.a, Reactivity Control Sys,Scram Discharge Vol Valve Testing from Normal Control Rod Configuration to Allow Test to Be Conducted Under Shutdown Conditions
05000335/LER-1990-006-01, :on 900426,surveillance Not Performed on Control Element Assemblies (Cea).Caused by Procedural Deficiency.Reactor Startup Procedure Revised to Require Performance of Addl CEA Surveillances
05000368/LER-1998-003-01, :on 980520,determined That Surveillance of Control Element Assembly Position Was Not Being Performed for One Control Element Assembly Group,Per Ts.Caused by Inadequate Verification.Change Implemented
05000499/LER-2013-001, Regarding Manual Reactor Trip Due to Dropped Rods M8 and D8
05000416/LER-1983-073-03, /03L-0:on 830623,review Revealed That 30 Closure Times for Scram Discharge Vol Vent & Drain Valves Not Verified on 820901.Caused by License Restrictions.Change to Tech Specs for 4.0.4 Applicability Requested
LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 1, Introduction and General Description of Plant