Call Number (LC) Title Results
Y 3.N 88:56/95-10 Relocation of selected technical specifications requirements related to instrumentation. 1
Y 3.N 88:56/96-01 Testing of safety-related logic circuits 1
Y 3.N 88:56/96-02 Reconsideration of nuclear power plant security requirements associated with an internal threat 1
Y 3.N 88:56/96-03 Relocation of the pressure temperature limit curves and low temperature overpressure protection system limits 1
Y 3.N 88:56/96-04 Boraflex degradation in spent fuel pool storage racks 1
Y 3.N 88:56/96-05 Periodic verification of design-basis capability of safety-related motor-operated valves 1
Y 3.N 88:56/96-06 Assurance of equipment operability and containment integrity during design-basis accident conditions. 1
Y 3.N 88:56/96-07 Interim guidance on transportation of steam generators 1
Y 3.N 88:56/97-01 Degradation of control rod drive mechanism nozzle and other vessel closure head penetrations 1
Y 3.N 88:56/97-02 Revised contents of the monthly operating report 1
Y 3.N 88:56/97-03 Annual financial surety update requirements for uranium recovery licenses 1
Y 3.N 88:56/97-04 Assurance of sufficient net positive suction head for emergency core cooling and containment heat removal pumps 1
Y 3.N 88:56/97-05 Steam generator tube inspection techniques 1
Y 3.N 88:56/97-06 Degradation of steam generator internals 1
Y 3.N 88:56/98-01 Year 2000 readiness of computer systems at nuclear power plants 1
Y 3.N 88:56/98-02 Loss of reactor coolant inventory and associated potential for loss of emergency mitigation functions while in a shutdown condition 1
Y 3.N 88:56/98-03 NMSS licensees' and certificate holders' year 2000 readiness programs 1
Y 3.N 88:56/98-04 Potential for degradation of the emergency core cooling system and the containment spray system after a loss-of-coolant accident because of construction and protective coating deficiencies and foreign material in containment 1
Y 3.N 88:56/98-05 Boiling water reactor licensees use of the BWRVIP-05 report to request relief from augmented examination requirements on reactor pressure vessel circumferential shell welds 1
Y 3.N 88:56/99-01 Recent nuclear material safety and safeguards decision on bundling exempt quantities 1