RS-17-076, License Amendment Request to Revise Spent Fuel Pool Level
L-14-258, Response to Request for Supplemental Information Regarding Spent Fuel Storage Pool Minimum Inadvertent Drainage Elevation License Amendment Request
L-14-166, Revise Technical Specification 4.3.2, Spent Fuel Storage Pool Minimum Inadvertent Drainage Elevation
LIC-05-0089, License Amendment Request to Support Use of M5 Fuel Cladding, and 10 CFR 50.46 and 10 CFR Appendix K Exemption Request
LIC-96-0125, Proposed Tech Specs Revising Paragraph 2.B(2) of License to Allow Use of Source Matl as Reactor Fuel.Ts 4.3.2 Revision Would Include Depleted U in Describing Reactor Core
B14272, Application for Amend to License NPF-49,revising TS 4.3.2 to Further Clarify Footnote in Table 4.3-2 Re ESFAS Instrumentation Surveillance Requirements
AECM-84-0229, Forwards Program Completion Rept Re Conclusion of Tech Spec Review Program.Rept Documents That Thorough & in-depth Engineering,Operations & Licensing Review of Tech Specs Conducted Per Programmatic Commitments
LIC-96-0165, Forwards Application for Amend to License DPR-40,revising TS 4.3.2, Reactor Core & Control, to Allow Use of Either Zircaloy or ZIRLO Cladding
LIC-96-0163, Forwards Application for Amend of Operating License DPR-40 & Tech Spec 4.3.2, Reactor Core & Control to Allow Use of Either Zircaloy or ZIRLO Cladding & Proposed Addl Ref to WCAP-12610 in TS 5.9.5b
LIC-96-0099, Forwards Application for Amend to License DPR-40,revising TS 4.3.2, Reactor Core & Control to Allow Use of Either Zircaloy or ZIRLO Cladding
05000354/LER-1987-006, :on 870123,while Performing Instrumentation & Control Surveillance Procedure,Filtration,Recirculation & Ventilation Sys auto-started.Caused by Deenergizing Wrong Channel.Technicians Counseled
05000483/LER-1997-010, :on 971118,inadequate Testing of Ssps Was Noted.Caused by Inadequate Vendor Testing Design/ Instructions of Subject Ssps Circuitry.Work Instructions Were Written to Test Affected Logic Circuits
05000382/LER-1988-005, :on 880321,blown Undervoltage Circuit Fuse Replacement Results in Tech Spec 3.0.3 Entry.Caused by Inadvertent Shortening of Two Wire Connections.Change to Tech Spec Being Pursued to Correct Deficiency
05000341/LER-1985-037, :on 850711,surveillance Channel Check for Four Isolation Actuation Instruments Required by Tech Spec 4.3.2.1-1 Inadvertently Missed.Caused by Procedural Deficiency.Procedure Reviewed & Revised
05000267/LER-1983-032-03, /03L-0:on 830819,motor Driven Boiler Feed Pump Removed from Svc to Repair Leaking Water Valve.Caused by Normal Wear.Valve,Pipe & Flange Assembly Prefabricated & Installed
05000416/LER-1983-173-03, /03L-0:on 831031,reactor Water Cleanup Differential Flow Channels a & B Read 30 & 3 Gpm, Respectively.Channel a Declared Inoperable.Caused by Failed Card in Instrument Square Root Extractor
05000498/LER-1993-019, :on 930709,determined That TS Requirement of MSIV Was Not Met Due to Inadequate Design of Field Change to Testing Function of Solid State Protection Sys.Corrected Missing Jumpers & Overlap Testing Discrepancy
1CAN039303, Application for Amend to License DPR-51,updating RCS Leakage Test Pressure in TS 4.3.2 to Agree W/Requirements of ASME Boiler & Pressure Vessel Code,Section XI (Through Winter 1981 Addenda)
05000267/LER-1980-044-03, /03L-0:on 800816,while Operating at 30% Power, Boiler Feed Pump a Was Removed from Svc Due to Unstable Governor Controls.Boiler Feed Pump B Was Out of Svc Also. Caused by Governor Worm Gear Being Loose on Shaft
HNP-96-025, Application for Amend to License NPF-63,revising TS 4.3.2 Re ESFAS Instrumentation
AECM-86-0362, Forwards Rept of 10CFR50.59 Safety Evaluations,Jan-June 1986,Grand Gulf Nuclear Station, Discussing Changes,Tests & Experiments