Pages that link to "L-2022-016, Report of 10 CFR 50.59 Plant Changes"
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The following pages link to L-2022-016, Report of 10 CFR 50.59 Plant Changes:
Displayed 50 items.
- L-2003-180, Third 10-Year Inservice Inspection Interval Inservice Inspection Program-Revision 0 (← links)
- L-76-230, Forwards Impingement of Aquatic Organisms - March 1976 and Impingement of Aquatic Organisms - April 1976 (← links)
- L-2018-215, Resubmittal of Fourth Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b (← links)
- L-2018-205, Response to Request for Additional Information Regarding License Amendment Request to Reduce the Number of Control Element Assemblies (← links)
- L-2018-182, License Amendment Request Iodine Removal System Elimination (← links)
- L-2018-178, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4 (← links)
- L-2018-171, Report of 10 CFR 50.59 Plant Changes (← links)
- L-2018-188, Inservice Inspection Plan - Fifth Ten-Year Interval Unit 1 Relief Request 6 (← links)
- L-2018-167, Cycle 24 Core Operating Limits Report (← links)
- L-2018-162, Inservice Inspection Plan Fifth Ten-Year Interval Unit 1 Relief Request 6 (← links)
- L-2018-135, In-Service Inspection Program, ISI Fourth Interval- Third Period; Fifth Interval- First Period; SL1-28 Owner'S Activity Report (OAR-1) (← links)
- L-2018-121, License Amendment Request to Reduce the Number of Control Element Assemblies (← links)
- L-78-243, 07/20/1978 Letter Whether Cutler-Hammer Type M Relays with a DC Coil Are Used or Planned for Use in Safety Related Systems at Facility (← links)
- L-75-427, as Discussed and Noted by NRC, FP&L Requests to Postpone Final Report of Crane Counterweight Drop (Control No. H00556F2) Until 10/15/1975 (← links)
- L-76-241, Regarding Nrc'S Letter of 5/25/1976 Informing Inservice Inspection Requirements Were Changed, FP&L Requests Submittal of Amendment to Technical Specifications to Be Delayed Until 7/1/1977 (← links)
- L-75-522, Report of Leaking Socket Welds Will Not Be Available Until 11/21/1975 (← links)
- L-78-064, Response to Request of Information within 30 Calendar Days of Date of IE Bulletin 78-02 Regarding Environmental Qualifications of Unprotected Terminal Blocks. Plant Is in Early Construction Stages and FP&L Will Answer by 3/31/1978 (← links)
- L-78-253, Response to IE Bulletin 78-06 Concerning Defective Cutler-Hammer Type M Relays with DC Coils, FP&L Will Either Replace or Modify in Accordance with Recommended Action If Such Relays to Be Found on Equipment (← links)
- L-78-269, Response to IE Bulletin 78-07 Concerning Protection Afforded by Air-Line Respirators and Supplied-Air Hoods, FP&L States Respiratory Protection Program Does Not Intend to Utilize Supplied-Air Respirators in Demand Mode (← links)
- L-77-178, Letter Furnishing Information Concerning Refueling Surveillance Testing (← links)
- L-77-245, Letter Forwarding Additional Information Regarding Neutron Shielding in the Reactor Vessel Cavity (← links)
- L-77-279, Letter Indicating Preparation of a Response on the Subject of Control Room Leak Rate Testing and Dose Calculations. Plan to Forward Response by 09/23/1977 (← links)
- L-77-290, Letter Forwarding Supplement 1 to Revision 1 of CEN-38 (F) Containing Five Figures Reclassified as non-proprietary (← links)
- L-77-305, Submittal of Drawings for Inservice Inspection and Testing Program (← links)
- L-77-333, Letter Regarding Inservice Inspection Program. Expects to Complete Response in About 30 Days & Plan to Forward by 11/30/1977 (← links)
- L-77-164, Letter Forwarding Copies of a Supplementary Startup Report Covering the Remainder of the Test Program (← links)
- L-77-276, Proposed Amendment to Facility Operating License DPR-67, Supplemental Information. Requests That Extension of Due Date for Specification 4.4.5 Be Deleted from Proposed Amendment (← links)
- L-77-392, Combustion Engineering Reported Potential CEA-to-Guide-Tube Interaction That Lead to Deterioration of Guide Tube. FP&L Implemented Weekly Cycling of Cea'S as Requested by NRC Per Phone Conversation on 12/23/1977. Will Prepare ... (← links)
- L-76-326, Response to Letter of 8/13/1976 to Evaluate Reactor Coolant System Design and Provide Certain Information Regarding Susceptibility to Overpressurization Events, FP&L Will Report the Results by 10/15/1976 (← links)
- L-76-381, Response to Request of 9/30/1976 for Information on Operating Experience with Loose-Parts and Loose-Parts Monitoring System (← links)
- L-76-401, Letter Supplements Information Repair Report CEN-38(f)-P, Rev. 1, and Documents Results of Recent Discussions with Staff. FP&L Concluded Additional Monitoring Using Traversing Incore Probes Would Not Be Appropriate (← links)
- L-76-415, Forwards Preoperational Test Procedure No. 0700080B,, Steam Generator Feedwater Hammer Test. (← links)
- L-76-416, Response to Letter of 11/5/1976, Forwards Requested Additional Appendix I Information (← links)
- L-76-412, Correction for Fp&L'S Letter of 12/2/1976 (← links)
- L-76-437, Florida Power & Light Co.'S Response to Nrc'S Letter of 8/1/1976 Concerning Anticipated Transients Without Scram (← links)
- L-77-111, 04/08/1977 Response to Request for Additional Information Steam Generator Operating History (← links)
- L-76-414, 12/03/1976 Letter Enclosure of Generic Report on Overpressure Protection for Operating CE Ness (← links)
- L-77-116, 04/18/1977 Letter RWT Overflow (← links)
- L-77-365, 12/08/1977 Letter Finding of No Proprietary Information in Inspection Report No. 18, Conducted on November 9-10, 1977 (← links)
- L-2018-110, Submittal of Fifth Ten-Year Inservice Inspection Interval ISI Program Plan, Revision 0 (← links)
- L-78-122, Refueling Outage Schedule (← links)
- L-78-138, Letter Correcting Typographical Error in Fp&L'S Response to Nrc'S Request 3/23/1978 Regarding Asymmetric Loads (← links)
- L-78-144, CEA Guide Tube Sleeving. Forwards Outline of Sleeving Procedures (← links)
- L-78-158, Fp&L'S Request to Delete Conditions of License N, O, and P from Enclosure 1 as Having Been Satisfied (← links)
- L-78-175, Forwards Responses to Questions from NRC Regarding Cycle 2 Reload Safety Evaluation (← links)
- L-78-180, Response to Nrc'S 5/17/1978 Letter, Fp&L'S Commitment to Complete Testing Concerning Resistance Temperature Detector Response Times by 12/1/1978 (← links)
- L-78-177, Response to Letter of 5/8/1978 Requesting Certain Information to Complete Review of Application to Restart St. Lucie Unit 1 Following Refueling. FP&L Will Provide Schedule to Responses by 6/8/1978 (← links)
- L-78-195, Information Regarding Fracture Toughness and Potential for Lamellar Tearing of Steam Generator and Reactor Coolant Pump Support Materials Was Turned Over to NRC Staff (← links)
- L-78-199, Forwards Response to Two Staff Positions on Diesel Generator Lockout Enclosed in 5/8/1978 Letter (← links)
- L-78-207, Forwards Diesel Generator Information in Response to 12/15/1977 Letter (← links)