Pages that link to "Roderick D"

The following pages link to Roderick D:

Displayed 41 items.

• FOIA/PA-2003-0059 ‎ (← links)
• 3F0307-08, License Amendment Request No. 291, Revision 1, Application for Improved Technical Specification Change to Add LCO 3.0.8 on the Operability of Snubbers Using the Consolidated Line Item Improvement Process ‎ (← links)
• 3F0307-07, License Amendment Request 264, Revision 2: Application to Modify Improved Technical Specifications Regarding Steam Generator Tube Integrity and Response to Request for Additional Information ‎ (← links)
• 3F1206-02, License Amendment Request 264, Revision 1: Application to Modify Improved Technical Specifications Regarding Steam Generator Tube Integrity and Response to Request for Additional Information ‎ (← links)
• 3F1206-05, License Amendment Request No. 291, Revision 0, Application for Improved Technical Specification Change to Add LCO 3.0.8 on the Operability of Snubbers Using the Consolidated Line Item Improvement Process ‎ (← links)
• 3F1006-01, License Amendment Request 292, Revision 0, Additional Storage Patterns for Crystal River Unit 3 Storage Pools a and B ‎ (← links)
• 3F0705-02, Response to Request for Additional Information (RAI) Regarding the Crystal River Unit 3, 60 - Day Response to Generic Letter 2004-01, Requirements for Steam Generator Tube Inspections. ‎ (← links)
• 3F0304-10, Letter of Intent to Submit a License Amendment Request to Extend Type a Integrated Leakage Rate Testing (ILRT) Surveillance Interval Referencing a New Method for Frequency Determination ‎ (← links)
• 3F1203-13, 60-Day Report Regarding NRC Bulletin 2003-02, Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity. ‎ (← links)
• 3F1003-05, Supplemental Information and Proposed License Condition for License Amendment Request No. 277, Revision 0, Bhtp Departure from Nucleate Boiling Correlation. ‎ (← links)
• 3F0502-08, Service List Update and Signature Authorization ‎ (← links)
• 3F0602-05, Response to Request for Additional Information 263, Revision 0, Relocation of Reactor Coolant System Parameters to Core Operating Limits Report & 20 Percent Steam Generator Tube Plugging ‎ (← links)
• CY-01-012, License Amendment Request 270, Revision 0, Power Uprate to 2568 Mwt ‎ (← links)
• 3F0502-01, Day Response to Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity. ‎ (← links)
• 3F0402-05, 2001 Radioactive Effluent Release Report ‎ (← links)
• ML021140317 ‎ (← links)
• 3F0402-02, March 2002 Monthly Operating Report for Crystal River Unit 3 ‎ (← links)
• 3F0302-02, February 2002 Monthly Operating Report for Crystal River, Unit 3 ‎ (← links)
• 3F0202-02, January 2002 Monthly Operating Report for Crystal River Unit 3 ‎ (← links)
• ML020360438 ‎ (← links)
• 05000302/LER-1998-013, Forwards LER 98-013-00,discussing Personnel Errors That Resulted in Surveillance Procedures Not Verifying Certain Valves to Be in Correct Position Once Every 31 Days as Required by ITS SRs ‎ (← links)
• 3F1099-14, Requests Copy of NRC Radtrad Code & Copy of User Instructions.Conditions for Receiving Code Listed ‎ (← links)
• 3F1099-19, Part 21 Rept Re Damage on safety-grade Cable Provided to FPC by Bicc Brand-Rex Co.Damage Was Created During Cabling Process While Combining Three Conducters.Corrective Action Program Precursor Card PC99-2868 Was Initiated ‎ (← links)
• 3F0699-12, Provides Suppl Info for LAR 240,rev 0 & Pump Curve for EFP-3 to Facilitate Review,As Requested ‎ (← links)
• 3F0999-19, Provides Clarification of Minor Inconsistency Identified During Review of NRC SE for Plant Third 10-year Interval Inservice Insp Program Plan & Associated Requests for Relief ‎ (← links)
• 3F0899-05, Forwards Response to NRC 990716 RAI Re Proposed Alternate Repair Criteria for Axial Tube End crack-like Indications in Crystal River Unit 3 ‎ (← links)
• 3F0899-02, Forwards Rev 2 to Cycle 11 COLR IAW Plant TS Section 5.6.2.18.Rev 1 of Cycle 11 COLR Was Not Submitted Due to Administrative Error.Changes Made in Rev 1 Listed & Incorporated in Encl Rev 2 ‎ (← links)
• 3F0899-17, Submits Relief Request 99-0001-RR,seeking NRC Approval for Evaluation Performed by Util on through-wall Flaw in Nuclear Svc & Decay Heat Sea Water (RW) Sys,Per Guidance of GL 90-05 ‎ (← links)
• 3F0799-30, Forwards List of Licensing Actions Currently Estimated for Fys 2000 & 2001,in Response to Administrative Ltr 99-02,dtd 990603 ‎ (← links)
• 3F0799-09, Provides Response to NRC 990625 Telcon RAI Re Util Use of Relief Request 98-009-II for Plant ASME Section XI, Inservice Insp Second Interval.Ltr Established No New Regulatory Commitments ‎ (← links)
• 3F0399-04, Special Rept 99-01:on 990310,discovered Containment Tendons That Required Grease Addition in Excess of Prescribed Limits During Recent Insp Activites.Six Tendons Were Refilled with Appropriate Amount of Grease ‎ (← links)
• 3F0599-05, Responds to 990402 RAI Re Third 10-year Interval ISI Program Plan Requests for Relief.Util Revised Relief Requests 98-010-II,98-003-PT,98-005-PT & 98-001-SS Based on Responses to Rai.Revised Relief Requests Encl ‎ (← links)
• 3F0599-03, Provides Update Curves for Facility Pressure/Temp Limits Rept,Rev 2 & Updated Rev Bar ITS Pages Associated with LAR, in Response to NRC RAI Re Subject LAR ‎ (← links)
• 3F0599-17, Submits Update Response to GL 97-06, Degradation of SG Internals. Ltr Establishes No New Regulatory Commitments ‎ (← links)
• 3F0199-02, Submits Change in Analysis of Record for SBLOCA & 10CFR50.46 Notification.Attachment to Ltr Includes Description of How Limitations & Conditions Outlined in RELAP5 SER Are Addressed ‎ (← links)
• 3F0199-06, Responds to NRC 981002 RAI Re GL 97-01, Degradation of Crdm/Cedm Nozzle & Other Vessel Closure Head Penetrations. Util Concurs with NEI Generic Industry Response to NRC Rai. Plant-specific Response,Encl ‎ (← links)
• 3F1298-01, Forwards Response to NRC 980410 RAI Re Audit Rept of USI A-46,seismic Implementation & Subsequent Evaluations of Related Issues at Crystal River,Unit 3 ‎ (← links)
• 3F1298-16, Provides Summary of Review Performed by Licensee for Calculations & Analyses That Supported Util Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions ‎ (← links)
• 3F0399-12, Forwards Response to NRC 990225 Telcon RAI Re Util LAR 245 Re Methodology Change for Boraflex Degradation.Ltr Establishes No New Regulatory Commitments ‎ (← links)
• 3F0699-08, Provides Updated Info to Licensee Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions. Ltr Establishes No New Regulatory Commitments ‎ (← links)
• 3F0599-21, Submits Addendum to B&W Owners Group Topical Rept BAW-2346P, Rev 0.Addendum Includes Leak Rate Values Based on CR-3 Plant Specific Main Steam Line Break Tube Loads ‎ (← links)