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 Issue dateTitle
B11655, Advises That Proposed Change to Axial Offsite Limits Will Be Requested for Cycle 14 to Allow 3-loop Operation at All Times During Cycle.Vendor Evaluation Indicated 4-loop Axial Offset Limits Not Always Conservative16 August 1985Advises That Proposed Change to Axial Offsite Limits Will Be Requested for Cycle 14 to Allow 3-loop Operation at All Times During Cycle.Vendor Evaluation Indicated 4-loop Axial Offset Limits Not Always Conservative
CY-02-010, Proposed Technical Specification Change Response to Request for Additional Information19 June 2002Proposed Technical Specification Change Response to Request for Additional Information
ENS 41089a Significant Reduction in the Effectiveness of Any Spent Fuel or Gtcc Waste Storage Containment System During Use.
IR 05000213/198501931 October 1985Insp Rept 50-213/85-19 on 850904-1015.No Violations Noted. Major Areas Inspected:Plant Operations,Radiation Protection, Physical Security,Fire Protection,Maint & Surveillance Testing & Previous Insp Findings
IR 05000213/19860992 September 1987Amended SALP Rept 50-213/86-99 for Mar 1986 - Mar 1987
IR 05000213/198701217 June 1987Insp Rept 50-213/87-12 on 870506-0609.No Violations Noted. Major Areas Inspected:Plant Operations,Radiation Protection, Fire Protection & Security.Unresolved Item Open Re Effect on Safety Limits
IR 05000213/19960105 November 1996Insp Rept 50-213/96-10 on 960811-0920.No Violations Noted. Major Areas Inspected:Plant Operations,Maint,Engineering & Plant Support
IR 05000213/19970039 October 1997Insp Rept 50-213/97-03 on 970408-0707 & 0805.Violations Noted.Major Areas Inspected:Operations,Engineering,Maint & Plant Support
IR 05000213/20040028 February 2005IR 05000213-04-002, Connecticut Yankee Atomic Power Company, East Hampton, Connecticut Site and Notice of Violation
Information Notice 1986-53, Improper Installation of Heat Shrinkable Tubing26 June 1986Improper Installation of Heat Shrinkable Tubing
Information Notice 1987-05, Miswiring in a Westinghouse Rod Control System2 February 1987Miswiring in a Westinghouse Rod Control System
Information Notice 1987-67, Lessons Learned from Regional Inspections of Licensee Actions in Response to IE Bulletin 80-1131 December 1987Lessons Learned from Regional Inspections of Licensee Actions in Response to IE Bulletin 80-11
Information Notice 1987-67, Lessons Learned from Regional Inspections of Licensee Actions in Response to Ie Bulletin 80-1131 December 1987Lessons Learned from Regional Inspections of Licensee Actions in Response to Ie Bulletin 80-11
Information Notice 1989-55, Degradation of Containment Isolation Capability by a High-Energy Line Break30 June 1989Degradation of Containment Isolation Capability by a High-Energy Line Break
Information Notice 1991-38, Thermal Stratification in Feedwater System Piping13 June 1991Thermal Stratification in Feedwater System Piping
Information Notice 1997-48, Inadequate or Inappropriate Interim Fire Protection Compensatory Measures9 July 1997Inadequate or Inappropriate Interim Fire Protection Compensatory Measures
ML0311405497 November 1991Withdrawn NRC Generic Letter 1991-018: Information to Licensees Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions and on Operability
ML17229B48229 February 1996Forwards Semiannual fitness-for-duty Performance Data for Jul-Dec 1995
ML20133A50324 December 1996Insp Rept 50-213/96-11 on 960921-1115.Violations Noted. Major Areas Inspected:Plant Operations,Maint,Engineering & Plant Support
ML20133B48820 December 1996Discusses Enforcement Conference Held on 961204,providing Considerable Info Related to Various Apparent Violations Resulting from Insp 50-213/96-201,96-06,96-07,96-08 & 96-80. W/Encl
ML20214X38714 May 1987SALP Rept 50-213/86-99 for Mar 1986 - Mar 1987
NRC Generic Letter 1983-4319 December 1983NRC Generic Letter 1983-043: Reporting Requirements of 10 CFR Part 50, Sections 50.72 & 50.73 & Standard Technical Specifications
NRC Generic Letter 1987-129 July 1987NRC Generic Letter 1987-012: Loss of Residual Heat Removal (RHR) While the Reactor Coolant System (RCS) Is Partially Filled
NRC Generic Letter 1992-026 March 1992NRC Generic Letter 1992-002: Resolution of Generic Issue 79, Unanalyzed Reactor Vessel (PWR) Thermal Stress During Natural Convection Cooldown.