Request for: Approved, Closed | |
Initiation
Questions Answers | |
| From | |
MONTHYEARML17334B2391988-11-0909 November 1988
[table view]Forwards Safety Evaluation Re Cracking of Reactor Coolant Piping to Steam Generator Nozzle Welds at Plant.Cracking Considered Significant Event Due to Number & Depth of Repairs.Findings & Conclusions Listed 1988-11-09 | |