| DCL-03-006, Twenty-Day Response to NRC Order for Compensatory Measures Related to Access Authorization | 27 January 2003 | Twenty-Day Response to NRC Order for Compensatory Measures Related to Access Authorization | |
| DCL-03-007, Response to Request for Additional Information for Diablo Canyon Independent Spent Fuel Storage Installation (ISFSI) Physical Security Program and Associated Revised Request for Exemption to Two 10 CFR 73.55 Requirements | 31 January 2003 | Response to Request for Additional Information for Diablo Canyon Independent Spent Fuel Storage Installation (ISFSI) Physical Security Program and Associated Revised Request for Exemption to Two 10 CFR 73.55 Requirements | Exemption Request |
| DCL-03-008, Response to NRC Request for Additional Information Regarding NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity. | 31 January 2003 | Response to NRC Request for Additional Information Regarding NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity. | Boric Acid
Hydrostatic
VT-2
Pressure Boundary Leakage
Pressure boundary leak
Through-Wall Leak |
| DCL-03-009, Inservice Inspection Program Plan, Revision 2, Drawings104628, Sheets 1 - 52 | 31 January 2003 | Inservice Inspection Program Plan, Revision 2, Drawings104628, Sheets 1 - 52 | |
| DCL-03-011, License Amendment Request 03-01, Revision to TS 3.3.1, Reactor Trip System Instrumentation | 6 February 2003 | License Amendment Request 03-01, Revision to TS 3.3.1, Reactor Trip System Instrumentation | Anticipated operational occurrence
Probabilistic Risk Assessment |
| DCL-03-016, License Amendment Request 03-02, Response Time Testing Elimination & Revision to TS 3.3.1, Reactor Trip System Instrumentation | 28 February 2003 | License Amendment Request 03-02, Response Time Testing Elimination & Revision to TS 3.3.1, Reactor Trip System Instrumentation | Anticipated operational occurrence
Probabilistic Risk Assessment
Fuel cladding |
| DCL-03-017, Revised Steam Generator Voltage-Based Repair Criteria Probability of Detection Method for Diablo Canyon Unit 2 Cycle 12 | 24 February 2003 | Revised Steam Generator Voltage-Based Repair Criteria Probability of Detection Method for Diablo Canyon Unit 2 Cycle 12 | Nondestructive Examination |
| DCL-03-019, Revision to TS 3.5.2 - Increase in Completion Time for Charging Pump During Unit 1 Cycle 12 from 72 Hours to 7 Days | 28 February 2003 | Revision to TS 3.5.2 - Increase in Completion Time for Charging Pump During Unit 1 Cycle 12 from 72 Hours to 7 Days | Enforcement Discretion
Probabilistic Risk Assessment
Large early release frequency |
| DCL-03-020, Response to NRC Request for Additional Information Regarding License Amendment Request 02-03, Spent Fuel Cask Handling | 28 February 2003 | Response to NRC Request for Additional Information Regarding License Amendment Request 02-03, Spent Fuel Cask Handling | Earthquake
Control of Heavy Loads
Affidavit |
| DCL-03-022, Day Response to NRC Order Modifying Licenses (EA-03-009) | 28 February 2003 | Day Response to NRC Order Modifying Licenses (EA-03-009) | |
| DCL-03-023, Request to Use an Alternative Method of Determining Probability of Detection for Diablo Canyon Unit 2 Steam Generator 4 Tube R44C45 Indication | 28 February 2003 | Request to Use an Alternative Method of Determining Probability of Detection for Diablo Canyon Unit 2 Steam Generator 4 Tube R44C45 Indication | |
| DCL-03-024, Emergency Plan Implementing Procedure Update | 5 March 2003 | Emergency Plan Implementing Procedure Update | Fitness for Duty
Job Performance Measure
Minimum staff |
| DCL-03-026, Emergency Request for Approval to Use an Alternative Method of Determining Probability of Detection for Steam Generator 4 Tube R44C45 Indication | 3 March 2003 | Emergency Request for Approval to Use an Alternative Method of Determining Probability of Detection for Steam Generator 4 Tube R44C45 Indication | |
| DCL-03-027, Response to Request for Additional Information on Emergency Request for Approval to Use an Alternate Method of Determining Probability of Detection for Tube R44C45 Indication | 5 March 2003 | Response to Request for Additional Information on Emergency Request for Approval to Use an Alternate Method of Determining Probability of Detection for Tube R44C45 Indication | |
| DCL-03-029, Core Operating Limits Report | 14 March 2003 | Core Operating Limits Report | Shutdown Margin |
| DCL-03-032, February 2003 Monthly Operating Report for Diablo Canyon, Units 1 & 2 | 14 March 2003 | February 2003 Monthly Operating Report for Diablo Canyon, Units 1 & 2 | Coast down |
| DCL-03-033, Core Operating Limits Report for Unit 1 Cycle 12 | 21 March 2003 | Core Operating Limits Report for Unit 1 Cycle 12 | Shutdown Margin |
| DCL-03-034, License Amendment Request 03-05 Revision of Technical Specification 3.7.10, Control Room Ventilation System, TS 3.7.12, Auxiliary Building Ventilation System, and TS 5.5.11, Ventilation Filter Testing Program. | 2 April 2003 | License Amendment Request 03-05 Revision of Technical Specification 3.7.10, Control Room Ventilation System, TS 3.7.12, Auxiliary Building Ventilation System, and TS 5.5.11, Ventilation Filter Testing Program. | Recently irradiated fuel |
| DCL-03-045, 30-Day Response to NRC Bulletins 2001-01, Circumferential Cracking of Reactor Pressure Vessel Head Penetration Nozzles & 2002-01, Reactor Pressure Vessel Head Degradation & Reactor Coolant Pressure Boundary Integrity, 60-Day Response to N | 23 April 2003 | 30-Day Response to NRC Bulletins 2001-01, Circumferential Cracking of Reactor Pressure Vessel Head Penetration Nozzles & 2002-01, Reactor Pressure Vessel Head Degradation & Reactor Coolant Pressure Boundary Integrity, 60-Day Response to NRC | Boric Acid
VT-2
Through-Wall Leak |
| DCL-03-048, Annual Radiological Environmental Operating Report | 30 April 2003 | Annual Radiological Environmental Operating Report | Offsite Dose Calculation Manual
Met Tower
Annual Radiological Environmental Operating Report |
| DCL-03-049, 2002 Annual Radioactive Effluent Release Report | 30 April 2003 | 2002 Annual Radioactive Effluent Release Report | Boric Acid
Grab sample
Offsite Dose Calculation Manual
Anticipated operational occurrence
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Process Control Program
Annual Radiological Effluent Release Report
Tritium
Power change |
| DCL-03-054, Special Report 03-01: Results of Steam Generator Tube Eddy Current Inspections During Eleventh Refueling Outage | 19 May 2003 | Special Report 03-01: Results of Steam Generator Tube Eddy Current Inspections During Eleventh Refueling Outage | |
| DCL-03-056, Response to NRC Request for Additional Information Regarding License Amendment Request 02-05, Revision to TS Table 3.3.1-1, Reactor Trip System Instrumentation, & Revised Reactor Coolant System Flow Measurement | 16 May 2003 | Response to NRC Request for Additional Information Regarding License Amendment Request 02-05, Revision to TS Table 3.3.1-1, Reactor Trip System Instrumentation, & Revised Reactor Coolant System Flow Measurement | Boric Acid |
| DCL-03-060, License Amendment Request 03-06, Revision to Technical Specification 3.8.1, AC Sources - Operating. | 29 May 2003 | License Amendment Request 03-06, Revision to Technical Specification 3.8.1, AC Sources - Operating. | Safe Shutdown
High winds
Enforcement Discretion
Probabilistic Risk Assessment
Large early release frequency
Maintenance Rule Program
Offsite Circuit |
| DCL-03-061, License Amendment Request 03-07, Revision to Technical Specifications (TS) 3.8.1 AC Sources - Operating & 3.8.4 DC Sources - Operating Surveillance Requirements | 29 May 2003 | License Amendment Request 03-07, Revision to Technical Specifications (TS) 3.8.1 AC Sources - Operating & 3.8.4 DC Sources - Operating Surveillance Requirements | Safe Shutdown
Anticipated operational occurrence
Fuel cladding
Offsite Circuit |
| DCL-03-064, Answer, Response and Request for Clarification in Response to April 29, 2003 Order Requiring Compliance with Revised Design Basis Threat for Operating Power Reactors | 2 June 2003 | Answer, Response and Request for Clarification in Response to April 29, 2003 Order Requiring Compliance with Revised Design Basis Threat for Operating Power Reactors | Enforcement Discretion |
| DCL-03-065, Answer, Response and Request for Clarification in Response to April 29, 2003, Order for Compensatory Measures Related to Training Enhancements on Tactical and Firearms Proficiency and Physical Fitness Applicable to Amend Nuclear Power Pla | 2 June 2003 | Answer, Response and Request for Clarification in Response to April 29, 2003, Order for Compensatory Measures Related to Training Enhancements on Tactical and Firearms Proficiency and Physical Fitness Applicable to Amend Nuclear Power Plant | Enforcement Discretion |
| DCL-03-067, License Amendment Request 03-08 Revision to Technical Specification 3.5.1, Emergency Core Cooling Systems/Accumulator. | 5 June 2003 | License Amendment Request 03-08 Revision to Technical Specification 3.5.1, Emergency Core Cooling Systems/Accumulator. | Incorporated by reference |
| DCL-03-068, May 2003 Monthly Operating Report for Diablo Canyon Units 1 & 2 | 13 June 2003 | May 2003 Monthly Operating Report for Diablo Canyon Units 1 & 2 | |
| DCL-03-069, License Amendment Request 03-09, Revision of TS 3.1.7, Rod Position Indication 3.2.1, Heat Flux Hot Channel Factor, 3.2.4, Quadrant Power Tilt Ratio, & 3.3.1, Reactor Trip System Instrumentation for Beacon Implementation | 11 June 2003 | License Amendment Request 03-09, Revision of TS 3.1.7, Rod Position Indication 3.2.1, Heat Flux Hot Channel Factor, 3.2.4, Quadrant Power Tilt Ratio, & 3.3.1, Reactor Trip System Instrumentation for Beacon Implementation | Boric Acid
Shutdown Margin
Anticipated operational occurrence
Post Accident Monitoring
Probabilistic Risk Assessment |
| DCL-03-073, Emergency Plan Implementing Procedure Update | 19 June 2003 | Emergency Plan Implementing Procedure Update | Fitness for Duty
Reactor Vessel Water Level
Earthquake
Minimum staff
Power change |
| DCL-03-074, Inservice Inspection Report for Eleventh Refueling Outage | 21 June 2003 | Inservice Inspection Report for Eleventh Refueling Outage | Boric Acid
Hydrostatic
Anchor Darling |
| DCL-03-075, Core Operating Limits Report Cycle 12 | 20 June 2003 | Core Operating Limits Report Cycle 12 | Shutdown Margin |
| DCL-03-076, Response to NRC Questions on 2R11 Steam Generator Tube Inspections | 30 September 2003 | Response to NRC Questions on 2R11 Steam Generator Tube Inspections | Nondestructive Examination |
| DCL-03-077, Response to NRC Questions Regarding License Amendment Request 02-03, Spent Fuel Cask Handling | 24 June 2003 | Response to NRC Questions Regarding License Amendment Request 02-03, Spent Fuel Cask Handling | Safe Shutdown
Hydrostatic
Earthquake
Control of Heavy Loads
Affidavit |
| DCL-03-078, Response to NRC Request for Additional Information Regarding License Amendment Request 03-10, Revised Steam Generator Voltage-Based Repair Criteria Probability of Detection Methods for Cycle 12. | 30 September 2003 | Response to NRC Request for Additional Information Regarding License Amendment Request 03-10, Revised Steam Generator Voltage-Based Repair Criteria Probability of Detection Methods for Cycle 12. | |
| DCL-03-079, Response to NRC Request for Additional Information Regarding License Amendment Request 02-05, Revision to TS Table 3.3.1-1, Reactor Trip System Instrumentation, & Revised Reactor Coolant System Flow Measurement | 26 June 2003 | Response to NRC Request for Additional Information Regarding License Amendment Request 02-05, Revision to TS Table 3.3.1-1, Reactor Trip System Instrumentation, & Revised Reactor Coolant System Flow Measurement | |
| DCL-03-080, Response to NRC Request for Additional Information Regarding License Amendment Request 03-03, Revision to TS 3.5.2 - Increase in Completion Time for Charging Pump During Unit 1 Cycle 12 from 72 Hours to 7 Days | 26 June 2003 | Response to NRC Request for Additional Information Regarding License Amendment Request 03-03, Revision to TS 3.5.2 - Increase in Completion Time for Charging Pump During Unit 1 Cycle 12 from 72 Hours to 7 Days | Safe Shutdown
Internal Flooding
Probabilistic Risk Assessment
Large early release frequency
Severe Accident Management Guideline |
| DCL-03-083, June 2003 Monthly Operating Report for Diablo Canyon Power Plant, Units 1 and 2 | 15 July 2003 | June 2003 Monthly Operating Report for Diablo Canyon Power Plant, Units 1 and 2 | |
| DCL-03-091, CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes | 24 July 2003 | CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes | |
| DCL-03-092, Response to NRC Request for Additional Information Regarding License Amendment Request 02-05, Revision to TS Table 3.3.1-1, Reactor Trip System Instrumentation & Revised Reactor Coolant System Flow Measurement | 1 August 2003 | Response to NRC Request for Additional Information Regarding License Amendment Request 02-05, Revision to TS Table 3.3.1-1, Reactor Trip System Instrumentation & Revised Reactor Coolant System Flow Measurement | |
| DCL-03-095, Supplement 1 to License Amendment Request 03-05, Revision of Technical Specification (TS) 3.7.10, Control Room Ventilation System (Crvs). TS 3.7.12. Auxiliary Building Ventilation System (Abvs). TS 3.7.13 | 8 August 2003 | Supplement 1 to License Amendment Request 03-05, Revision of Technical Specification (TS) 3.7.10, Control Room Ventilation System (Crvs). TS 3.7.12. Auxiliary Building Ventilation System (Abvs). TS 3.7.13 | |
| DCL-03-096, Day Response to Request for Information on Generic Letter 2003-01, Control Room Habitability | 8 August 2003 | Day Response to Request for Information on Generic Letter 2003-01, Control Room Habitability | Fire Barrier |
| DCL-03-097, Response to NRC Bulletin 2003-01, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors. | 8 August 2003 | Response to NRC Bulletin 2003-01, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors. | Boric Acid
High Radiation Area
Probabilistic Risk Assessment |
| DCL-03-101, Response to NRC Request for Additional Information Regarding License Amendment Request 02-04, Revision of TS 5.6.6 - Reactor Coolant System Pressure & Temperature Limits Report | 15 August 2003 | Response to NRC Request for Additional Information Regarding License Amendment Request 02-04, Revision of TS 5.6.6 - Reactor Coolant System Pressure & Temperature Limits Report | Shutdown Margin
Post Accident Monitoring
Pressure and Temperature Limits Report |
| DCL-03-102, Change 23 to Revision 18 of Physical Security Plan | 15 August 2003 | Change 23 to Revision 18 of Physical Security Plan | |
| DCL-03-109, Supplemental Information to Support License Amendment Request 03-10, Revised Steam Generator Voltage-Based Repair Criteria Probability of Detection Method for Unit 2 Cycle 12. | 3 September 2003 | Supplemental Information to Support License Amendment Request 03-10, Revised Steam Generator Voltage-Based Repair Criteria Probability of Detection Method for Unit 2 Cycle 12. | Nondestructive Examination |
| DCL-03-110, Commitment Change Summary Report, 01/01 - 12/31/02 | 10 September 2003 | Commitment Change Summary Report, 01/01 - 12/31/02 | High Radiation Area
Grab sample |
| DCL-03-111, License Amendment Request 03-12 Revision to Technical Specifications 3.3.1, RTS Instrumentation, and 3.3.2, ESFAS Instrumentation, Enclosures 1 - 4 | 12 September 2003 | License Amendment Request 03-12 Revision to Technical Specifications 3.3.1, RTS Instrumentation, and 3.3.2, ESFAS Instrumentation, Enclosures 1 - 4 | Anticipated operational occurrence |
| DCL-03-113, Response to NRC Questions on 1R11 Steam Generator Tube Inspections | 15 September 2003 | Response to NRC Questions on 1R11 Steam Generator Tube Inspections | Nondestructive Examination |