Pages that link to "L-2022-048, Submittal of Refueling Outage SL2-26 Steam Generator Tube Inspection Report"
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The following pages link to L-2022-048, Submittal of Refueling Outage SL2-26 Steam Generator Tube Inspection Report:
Displayed 50 items.
- L-2012-241, Fpl/St. Lucie Plant'S 90 Day Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Flooding Aspects of Recommendations 2.1 and 2.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Acciden (← links)
- L-2012-249, Fpl/St. Lucie Plant'S Clarification of the 60 Day Response to NRC Letter, Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation 9.3 of the Near-Term Task Force Review of Insights (← links)
- L-2012-128, Florida Power & Light Company (FPL) - St. Lucie Plant Answer to March 12, 2012 Commission Order Modifying License with Regard to Requirements for Mitigation Strategies for Beyond-Design Basis External Events (Order No. EA-12-049) (← links)
- 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)