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This page provides a simple browsing interface for finding entities described by a property and a named value. Other available search interfaces include the page property search, and the ask query builder.

List of results

• ML18227B679  + (ML18227B679)
• ML18227B703  + (ML18227B703)
• ML18227B706  + (ML18227B706)
• ML18227B708  + (ML18227B708)
• L-77-434, Answers to Question Nos. 2 and 7 and Revised Answers to Questions 8 and 9 Pertaining to the Steam Generators Tube Integrity Supplemental Information  + (ML18227B711)
• ML18227B715  + (ML18227B715)
• ML18227B733  + (ML18227B733)
• ML18227B739  + (ML18227B739)
• L-76-347, Cycle 4 Reload Safety Evaluation Information  + (ML18227B744)
• ML18227B758  + (ML18227B758)
• L-76-288, Referring FPLs Letter of 6/23/1976, 6 Sets of marked-up Blueprints of Spent Fuel Transfer Process. Drawings May Be Released for Public Disclosure Provided That Any Westinghouse Proprietary Information Statement Is Blanked Out  + (ML18227B767)
• L-76-283, Letter Advising Florida Power & Light Company Recently Has Recently Become a Full Participating Member of Nuclear Plant Reliability Data System, & Is Expending Effort Necessary for Full Implementation of This Voluntary Program  + (ML18227B769)
• L-76-270, Letter Requesting Copy of Discussion of the Spent Fuel Storage Pool Leaks at Turkey Point Nuclear Generating Unit Nos. 3 and 4 Which Was Developed by NRC  + (ML18227B771)
• L-76-257, Responding to Letter of 6/10/1976, Letter Furnishing Information Concerning Reactor Pressure Vessel Supports  + (ML18227B774)
• L-76-248, Referring to FPLs Letter of 6/23/1976, Letter Furnishing Supplemental Information Concerning Transfer of Spent Fuel Between Unit Nos. 3 & 4  + (ML18227B775)
• L-76-238, Letter Transmitting Supplemental Information Related to Evaluation of Spent Fuel Transfer Process Submittal of 6/23/1976  + (ML18227B777)
• L-76-234, Referring to Request at Meeting of 6/18/1976, Letter Submitting Evaluation of Spent Fuel Transfer Process Between Spent Fuel Pits with 6 Sets of Marked Up Blueprints to Assist the Staff to Evaluate  + (ML18227B778)
• ML18227B779  + (ML18227B779)
• L-76-210, Responding to Letter of 4/26/1976, Letter Furnishing Information Concerning Inservice Inspection Testing of ASME Code Class 1, 2, & 3 Components, & Advising, Will Submit Unit 3 Amendment by 2/14/1979  + (ML18227B780)
• L-76-197, Letter Furnishing Definition of Certain Technical Specification Terminology to Avoid Ambiguity or Violations at a Later Date  + (ML18227B781)
• L-76-203, Letter Transmitting Appendix C, as Supplemental Information to Proposed Modification of Spent Fuel Storage Facility  + (ML18227B783)
• ML18227B784  + (ML18227B784)
• ML18227B785  + (ML18227B785)
• ML18227B786  + (ML18227B786)
• L-77-393, Letter Transmitting Information Regarding Results of Unit 3 Steam Generator Inspections Conducted During the Current Refueling Outage  + (ML18227B787)

• L-77-381, Letter Transmitting Revision 1 to Steam Generator Repair Report Which Was Forwarded on 9/20/1977  + (ML18227B788)

• L-77-326, Responding to Letter of 5/20/1977, Letter Transmitting Information Regarding Reactor Vessel Material Surveillance Program  + (ML18227B789)
• ML18227B790  + (ML18227B790)
• L-77-296, Letter Consists of Steam Generator Repair Report Which Evaluates All Safety Related Aspects of the Repair Effort  + (ML18227B791)
• ML18227B792  + (ML18227B792)
• ML18227B793  + (ML18227B793)
• L-77-231, Response to Request for Additional Information Re Large Scale Topographical Map in Compliance with Appendix I to 10 CFR 50  + (ML18227B794)
• ML18227B797  + (ML18227B797)
• ML18227B798  + (ML18227B798)
• ML18227B801  + (ML18227B801)
• ML18227B802  + (ML18227B802)
• ML18227B806  + (ML18227B806)
• ML18227B808  + (ML18227B808)
• L-77-352, Letter Requesting Authorization to Provide for Transfer of Byproduct, Source, & Special Nuclear Material to NRC  + (ML18227B817)
• L-77-344, Referring Request for Additional Information Dated 10/5/1977, Advising Requested Information Will Be Delivered by 12/15/1977  + (ML18227B818)
• L-77-323, Responding to Letter of 6/30/1977, Consists of Information Concerning Safety Injection Flow Throttling  + (ML18227B821)
• L-77-320, Responding to Letter of 9/13/1977, Consists of Information Regarding Fracture Toughness & Lamellar Tearing Potential for Steam Generator & Reactor Coolant Pump Supports  + (ML18227B822)
• L-77-297, Letter Extension of Technical Specification Surveillance Requirement  + (ML18227B829)
• ML18227B832  + (ML18227B832)
• ML18227B835  + (ML18227B835)
• ML18227B847  + (ML18227B847)
• ML18227B857  + (ML18227B857)
• ML18227B865  + (ML18227B865)
• ML18227B867  + (ML18227B867)
• ML18227B868  + (ML18227B868)
• ML18227B869  + (ML18227B869)