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	Issue date	Title	Topic
DCL-01-095, Response to NRC Request for Additional Information Re License Amendment Request 01-03, Expansion of Steam Generator Tube W* Alternate Repair Criteria for Indications in Westinghouse Explosive Tube Expansion (Wextex) Region.	14 March 2002	Response to NRC Request for Additional Information Re License Amendment Request 01-03, Expansion of Steam Generator Tube W* Alternate Repair Criteria for Indications in Westinghouse Explosive Tube Expansion (Wextex) Region.	Nondestructive Examination
DCL-01-127, License Amendment Request 01-09, Revision to Diablo Canyon Power Plant Physical Security Program to Incorporate Diablo Canyon ISFSI & Associated Request for Exemption for Four 10CFR73.55 Requirements	21 December 2001	License Amendment Request 01-09, Revision to Diablo Canyon Power Plant Physical Security Program to Incorporate Diablo Canyon ISFSI & Associated Request for Exemption for Four 10CFR73.55 Requirements	Exemption Request
DCL-01-138, Special Report 00-01, Revision 1-90 Day Report, Results of Steam Generator Alternate Repair Criteria for Diablo Canyon Power Plant Unit 2 Ninth Refueling Outage	3 January 2002	Special Report 00-01, Revision 1-90 Day Report, Results of Steam Generator Alternate Repair Criteria for Diablo Canyon Power Plant Unit 2 Ninth Refueling Outage	Nondestructive Examination
DCL-02-004, Response to NRC Regulatory Issue Summary 2001-21	18 January 2002	Response to NRC Regulatory Issue Summary 2001-21
DCL-02-014, Supplemental Information Regarding Implementation ASME Code Case N-597	13 February 2002	Supplemental Information Regarding Implementation ASME Code Case N-597
DCL-02-020, Supplement 1 to License Amendment Request 01-04 Revision to Technical Specifications 3.9.4 Containment Penetrations	26 February 2002	Supplement 1 to License Amendment Request 01-04 Revision to Technical Specifications 3.9.4 Containment Penetrations
DCL-02-022, Response to NRC Request for Additional Information Re License Amendment Request 01-02	27 February 2002	Response to NRC Request for Additional Information Re License Amendment Request 01-02
DCL-02-023, Gregory M. Rueger, P G& E Co., Response to NRC Request for Additional Information Regarding Supplement 3 to License Amendment Request 00-06, Alternate Repair Criteria for Axial PWSCC at Dented, Intersections in Steam Generator Tubing.	11 March 2002	Gregory M. Rueger, P G& E Co., Response to NRC Request for Additional Information Regarding Supplement 3 to License Amendment Request 00-06, Alternate Repair Criteria for Axial PWSCC at Dented, Intersections in Steam Generator Tubing.
DCL-02-028, Twenty-Day Answer to NRC Order for Interim Safeguards and Security Compensatory Measures	18 March 2002	Twenty-Day Answer to NRC Order for Interim Safeguards and Security Compensatory Measures
DCL-02-033, Diablo Units 1 & 2 Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity.	1 April 2002	Diablo Units 1 & 2 Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity.	Boric Acid Packing leak Weld Overlay Nondestructive Examination VT-2 Condition Adverse to Quality Through-Wall Leak
DCL-02-038, License Amendment Request 02-02, Revision to Technical Specifications Re Suspension of Positive Reactivity Additions	10 April 2002	License Amendment Request 02-02, Revision to Technical Specifications Re Suspension of Positive Reactivity Additions	Boric Acid Shutdown Margin Anticipated operational occurrence Offsite Circuit Power change
DCL-02-039, Emergency Plan Implementing Procedure Update	12 April 2002	Emergency Plan Implementing Procedure Update
DCL-02-041, Annual Technical Specification 5.6.1 Report for 2001	16 April 2002	Annual Technical Specification 5.6.1 Report for 2001
DCL-02-042, Submittal of Proposed Changes to the DCPP Physical Security Program to Incorporate the Diablo Canyon ISFSI and Associated Request for Exemption to Four 10 CFR 73.55 Requirements	18 April 2002	Submittal of Proposed Changes to the DCPP Physical Security Program to Incorporate the Diablo Canyon ISFSI and Associated Request for Exemption to Four 10 CFR 73.55 Requirements	Exemption Request
DCL-02-044, License Amendment Request 02-03, Spent Fuel Cask Handling	15 April 2002	License Amendment Request 02-03, Spent Fuel Cask Handling	Safe Shutdown Tornado Missile Safe Shutdown Earthquake Hydrostatic Coatings Finite Element Analysis Tornado-Generated Missile Tornado Generated Missile Design basis earthquake Overtravel Exemption Request Earthquake Control of Heavy Loads Fuel cladding Liquid penetrant Fire Protection Program Affidavit
DCL-02-045, Response to Final NRC Request for Additional Information Re Supplement 3 to License Amendment Request 00-06, Alternate Repair Criteria for Axial PWSCC at Dented Intersections in Steam Generator Tubing.	18 April 2002	Response to Final NRC Request for Additional Information Re Supplement 3 to License Amendment Request 00-06, Alternate Repair Criteria for Axial PWSCC at Dented Intersections in Steam Generator Tubing.
DCL-02-049, 10 CFR 50.59 Report of Changes, Tests, and Experiments for the Period January 1, 2000, Through December 31, 2001	26 April 2002	10 CFR 50.59 Report of Changes, Tests, and Experiments for the Period January 1, 2000, Through December 31, 2001	Safe Shutdown Shutdown Margin Loop seal Offsite Dose Calculation Manual Fire Barrier Anticipated operational occurrence Time to boil Probabilistic Risk Assessment Nondestructive Examination Emergency Lighting Pressure and Temperature Limits Report Process Control Program Operability Determination Earthquake Turbine Missile Fuel cladding Continuous fire watch Fire Protection Program Scaffolding Power change Operability Assessment Power Uprate
DCL-02-051, 2001 Annual Radiological Environmental Operating Report	30 April 2002	2001 Annual Radiological Environmental Operating Report	Offsite Dose Calculation Manual Met Tower Annual Radiological Environmental Operating Report
DCL-02-052, 2001 Annual Nonradiological Environmental Operating Report	30 April 2002	2001 Annual Nonradiological Environmental Operating Report
DCL-02-055, Clarification of the Twenty-Day Answer to NRC Order for Interim Safeguards and Security Compensatory Measures	1 May 2002	Clarification of the Twenty-Day Answer to NRC Order for Interim Safeguards and Security Compensatory Measures
DCL-02-056, Revision 31 to EP G-1, Emergency Classification and Emergency Plan Activation.	3 May 2002	Revision 31 to EP G-1, Emergency Classification and Emergency Plan Activation.
DCL-02-059, Comments Regarding April 17, 2002 End of Cycle Assessment Meeting	14 May 2002	Comments Regarding April 17, 2002 End of Cycle Assessment Meeting
DCL-02-061, Inservice Testing (IST) Program Plan, Revision 18	17 May 2002	Inservice Testing (IST) Program Plan, Revision 18	Safe Shutdown Unanalyzed Condition Boric Acid Ultimate heat sink Stroke time Incorporated by reference Cold shutdown justification Earthquake Power Operated Valves
DCL-02-062, Core Operating Limits Report, Cycle 12	17 May 2002	Core Operating Limits Report, Cycle 12	Shutdown Margin
DCL-02-063, Submittal of 60-day Response to NRC Bulletin 2002-01 Re Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity	17 May 2002	Submittal of 60-day Response to NRC Bulletin 2002-01 Re Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity	Boric Acid VT-2 Pressure Boundary Leakage
DCL-02-065, Special Report 02-01: Results of Steam Generator Tube Eddy Current Inspections During Tenth Refueling Outage	28 May 2002	Special Report 02-01: Results of Steam Generator Tube Eddy Current Inspections During Tenth Refueling Outage
DCL-02-066, Supplemental Answers to NRC Order for Interim Safeguards and Security Compensatory Measures	31 May 2002	Supplemental Answers to NRC Order for Interim Safeguards and Security Compensatory Measures
DCL-02-067, Comments of James E. Tomkins on Draft Report NUREG-XXX, Technical Assessment Generic Issue 186: Potential Risk & Consequences of Heavy Load Drops in Nuclear Power Plants.	31 May 2002	Comments of James E. Tomkins on Draft Report NUREG-XXX, Technical Assessment Generic Issue 186: Potential Risk & Consequences of Heavy Load Drops in Nuclear Power Plants.
DCL-02-070, Dcl 02-070 Change 20 to Revision 18 of the Physical Security Plan.	23 October 2002	Dcl 02-070 Change 20 to Revision 18 of the Physical Security Plan.
DCL-02-076, June 2002 Monthly Operating Report for Diablo Canyon Power Plant Units 1 and 2	12 July 2002	June 2002 Monthly Operating Report for Diablo Canyon Power Plant Units 1 and 2
DCL-02-078, Response to NRC Regulatory Issue Summary 2002-09; Preparation and Scheduling of Operator Licensing Examinations	12 July 2002	Response to NRC Regulatory Issue Summary 2002-09; Preparation and Scheduling of Operator Licensing Examinations	Generic Fundamentals Examination
DCL-02-079, Units, 1 and 2, License Amendment Request 02-04, Revision of Technical Specification 5.6.6 - Reactor Coolant System Pressure and Temperature Limits Report	31 July 2002	Units, 1 and 2, License Amendment Request 02-04, Revision of Technical Specification 5.6.6 - Reactor Coolant System Pressure and Temperature Limits Report	Shutdown Margin Stroke time Post Accident Monitoring Hydrostatic Pressure and Temperature Limits Report Affidavit
DCL-02-089, CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes	26 July 2002	CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes
DCL-02-095, Response to NRC Requests for Additional Information Regarding License Amendment Requests 01-04 and 01-05	14 August 2002	Response to NRC Requests for Additional Information Regarding License Amendment Requests 01-04 and 01-05
DCL-02-096, Inservice Inspection Report for Eleventh Refueling Outage	22 August 2002	Inservice Inspection Report for Eleventh Refueling Outage	Boric Acid Hydrostatic AnchorDarling
DCL-02-097, License Amendment Request 02-05, Revision to Technical Specification Table 3.3.1-1, Reactor Trip System Instrumentation, & Revised Reactor Coolant System Flow Measurement	27 August 2002	License Amendment Request 02-05, Revision to Technical Specification Table 3.3.1-1, Reactor Trip System Instrumentation, & Revised Reactor Coolant System Flow Measurement	Fuel cladding
DCL-02-098, Special Report 02-02 - Results of Steam Generator Inspections for Eleventh Refueling Outage	22 August 2002	Special Report 02-02 - Results of Steam Generator Inspections for Eleventh Refueling Outage	Boric Acid Nondestructive Examination
DCL-02-105, Emergency Plan Implementing Procedure Update	30 August 2002	Emergency Plan Implementing Procedure Update
DCL-02-107, Report of Full Compliance with NRC Order for Interim Safeguards & Security Compensatory Measures	30 August 2002	Report of Full Compliance with NRC Order for Interim Safeguards & Security Compensatory Measures
DCL-02-108, Change 21 to Revision 18 of the Physical Security Plan for Diablo Canyon Units 1 & 2	6 September 2002	Change 21 to Revision 18 of the Physical Security Plan for Diablo Canyon Units 1 & 2

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