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Category:REPORTS-TOPICAL (BY MANUFACTURERS-VENDORS ETC)
MONTHYEARML20217L8931999-10-31031 October 1999 Rev 1 to BAW-10235, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs ML20210K8831999-07-29029 July 1999 Non-proprietary Addendum B to BAW-2346P,Rev 0 Re ANO-1 Specific MSLB Leak Rates ML20196A6251999-05-31031 May 1999 Non-proprietary Rev 0 to TR BAW-10235, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs ML20198G4491998-07-31031 July 1998 Rev 1 to WCAP-15015, Specific Application of Laser Welded Sleeves for SCE San Onofre Units 2 & 3 Sgs ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML20248D6011998-03-31031 March 1998 Suppl 9 to CENPD-279, Annual Rept on Abb CE ECCS Performance Evaluation Models ML20154E4211998-01-31031 January 1998 Amend 1 to CE NPSD-911, Analysis of Moderator Temperature Coefficients in Support of Change in TSs End of Cycle Negative Mtc Limit. App a Consists of Responses to 970226 NRC RAI ML20203H6701998-01-31031 January 1998 Rev 0 to non-proprietary Version of BAW-10232, OTSG Repair Roll Qualification Rept (Including Hydraulic Expansion Evaluation) ML20199G9531998-01-31031 January 1998 Non-proprietary Alternate Repair Criteria for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once- Through Sgs ML20211N4921997-09-30030 September 1997 Rev 1 to SIR-94-080-A, Relaxation of Reactor Coolant Pump Flywheel Insp Requirements ML20141L9791997-02-28028 February 1997 Suppl 8 to Annual Rept on Abb CE ECCS Performance Evaluation Models, Final Rept ML20135F3681996-11-30030 November 1996 Non-proprietary Final Rept Repair of 3/4 O.D. SG Tubes Using Leak Tight Sleeves ML20112G5301996-06-10010 June 1996 Annual Report on Abb CE ECCS Performance Evaluation Models ML20135A2961996-02-29029 February 1996 Annual Rept on Abb CE ECCS Performance Evaluation Models, Final Rept ML20112E8491996-02-28028 February 1996 Suppl 7 to Annual Rept of Abb C-E ECCS Performance Evaluation Models ML17353A4341995-10-31031 October 1995 Rev 1 to BAW-2245, Initial Rt of Linde 80 Welds Based on Fracture Toughness in Transition Range. ML17311B3441995-09-30030 September 1995 Safety Analysis Rept for Use of Advanced Zr Based Cladding Matl in PVNGS Unit 2 Batch J Demonstration Fuel Assemblies. ML17264A1181995-07-31031 July 1995 Response to Part (1) of GL 92-01,Rev 1,Suppl 1. ML20083Q9261995-05-30030 May 1995 Joint Applications Rept for Safety Injection Tank Aot/Sti Extension ML20083Q9861995-05-30030 May 1995 Joint Applications Rept for Emergency Diesel Generators AOT Extension ML20082H4011995-02-28028 February 1995 Annual Rept on Abb CE ECCS Performance Evaluation Models, Feb 1995 ML20085H3221995-02-28028 February 1995 Suppl 6 to Topical Rept CENPD-279, Annual Rept on Abb CE ECCS Performance Evaluation Models,Final Rept,Ceog Task 865, Dtd Feb 1995 ML20073D4561994-09-30030 September 1994 Verification of Cecor Coefficient Methodology for Application to PWRs of Entergy Sys ML17310B2471994-02-28028 February 1994 Nonproprietary Analysis of 137 Degree Capsule from APS Palo Verde Unit 2 Reactor Vessel Radiation Surveillance Program. ML20069D4261994-02-28028 February 1994 Annual Rept on C-E ECCS Codes & Methods for 10CFR50.46 ML20063C7571993-12-31031 December 1993 Qualification of Reactor Methods for Pressurized Water Reactors of Entergy Sys ML20058A4121993-08-31031 August 1993 Rev 1 to Suppl 4 to CENPD-279, Annual Rept on C-E ECCS Codes & Methods for 10CFR50.46 ML20079C1621993-05-31031 May 1993 Analysis of Moderator Temp Coefficients in Support of Change in TS of EOC Negative Mtc Limit ML20044G5181993-04-30030 April 1993 Suppl 4 to Annual Rept on C-E ECCS Codes & Methods for 10CFR50.46, Final Rept ML20127M2731992-11-30030 November 1992 Analysis of Capsule W-97 Entergy Operations,Inc Waterford Generating Station,Unit 3,Reactor Vessel Matl Surveillance Program ML20128E0741992-07-31031 July 1992 Nonproprietary Pvngs,Unit 1 EOC 3 Exam Rept ML20081K9821991-05-31031 May 1991 Final Rept on Reactor Vessel App G Pressure-Temp Limits for Arkansas Nuclear One Unit 2 for 21 Efpys ML17305B5141991-04-30030 April 1991 Suppl 2 to, Annual Rept on C-E ECCS Codes & Methods for 10CFR50.46. ML20073H8181991-03-30030 March 1991 WCAP-12920, Analysis of Southern California Edison Co San Onofre Unit 3 Reactor Vessel Surveillance Capsule Removed from 97 F Location ML20067A5241990-12-31031 December 1990 Final Submittal in Response to NRC Bulletin 88-011, 'Pressurizer Surge Line Thermal Stratification.' ML20062G8021990-11-30030 November 1990 Applicability of Notrump to San Onofre Nuclear Generating Station Unit 1 ML20055H2451990-06-25025 June 1990 Overheads/Passouts from NRC Review of San Onofre Nuclear Generating Station 1 Thermal Shield Design Analysis ML20042F3391990-04-30030 April 1990 Suppl 1 to Responses to Questions on C-E Rept CEN-386-P, 'Verification of Acceptability of 1-Pin Burnup Limit of 60 Mwd/Kg for C-E 16X16 PWR Fuel.' ML20059M4481990-03-31031 March 1990 Unit 1 Pressure-Temp Limits for 15 Efpy ML17305A6051990-02-28028 February 1990 Annual Rept on C-E ECCS Codes & Methods for 10CFR50.46, Suppl 1 ML20006A8231990-01-10010 January 1990 Errata to Rev 3 to BAW-1543, Master Integrated Reactor Vessel Surveillance Program Consisting of Revised Tables 3-20 & E-1 ML19327C1951989-10-31031 October 1989 Nonproprietary Palo Verde Nuclear Generating Station-Unit 1 End-of-Cycle 2 Fuel Exam Rept. ML19324C4241989-10-31031 October 1989 Rev 0 to San Onofre Units 2 & 3 Fuel Rack Seismic Analysis for Final Pool Layout. ML19351A4191989-09-30030 September 1989 Mark-BW Reload LOCA Analysis for Catawba & McGuire Units. ML20073K6781989-06-30030 June 1989 Risk Evalution of Removal of Shutdown Cooling Sys Autoclosure Interlock, Prepared for C-E Owners Group ML20247E3231989-06-30030 June 1989 Nonproprietary Verification of Acceptability of 1-Pin Burnup Limit of 60 Mwd/Kg for C-E 16x16 PWR Fuel ML20245G7121989-05-31031 May 1989 Submittal in Response to NRC Bulletin 88-11, 'Pressurizer Surge Line Thermal Stratification' ML17223A6971989-04-30030 April 1989 Annual Rept on C-E ECCS Codes & Methods for 10CFR50.46. ML20246N3841989-04-30030 April 1989 Analysis of Capsule ANI-C,Arkansas Power & Light Co, Arkansas Nuclear One,Unit 1,Reactor Vessel Matl Surveillance Program ML20235Z0931989-02-28028 February 1989 Fuel Rack Seismic Analysis Methods & Parameters 1999-07-29
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217N3171999-10-19019 October 1999 Rev 1,change 024-01-0 to OP-1903.011, Emergency Response Notifications ML20217K9011999-10-18018 October 1999 Proposed Tech Specs 3.6.2.2 Loc,Allowing Plant to Operate with Two Independent Trains of Containment Cooling, Consisting of One Fan Cooler Per Train,Operable During Modes 1,2,3 & 4 ML17300B3791999-10-0808 October 1999 Proposed Tech Specs,Waiving Requirement to Perform SR 3.8.4.8 for Unit 1 Channels A,B & C on One Time Basis ML20217J7641999-10-0505 October 1999 Rev 1 to Unit 1 Technical Requirement Manual, Replacing Index Page ML17300B3521999-09-29029 September 1999 Revised Bases Pages,Providing Addl Discussion of Options Available to Exit Required Action G of TS 3.8.1 & Revised Page for TS 3.3.7 ML20216G0881999-09-19019 September 1999 Proposed Tech Specs Pages,Changing TS 4.18.5.a.9 & Associated Bases for One Cycle of Operation Through End of Cycle 16 for Suppl Use of OTSG Repair Roll Technology ML20212F5851999-09-17017 September 1999 Proposed Tech Specs Pages,Changing TS by Revising Curie Limits for Radioactive Gas Storage Tanks ML20216G0721999-09-17017 September 1999 Proposed Tech Specs,Revising Once Through SG Tubing Surveillance Requirements to Provide Alternate Repair Criteria for Volumetric Integranular Attack ML17300B3321999-09-14014 September 1999 Marked-up Tech Specs Pages to TS 5.5.2 & 5.6.2,making Noted Administrative Changes ML20211P0061999-09-0707 September 1999 Proposed TS in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria ML17313B0601999-08-31031 August 1999 Rev 1 to PVNGS TS Bases Implemented Between Aug 1998 & Jul 1999 ML20211B2381999-08-31031 August 1999 Revised Interjurisdictional Policy for Songs ML20211F5501999-08-24024 August 1999 Proposed Tech Specs Page Xviii, Index Administrative Controls, Originally Submitted with TS Change Request NPF-38-220 ML20211F3701999-08-24024 August 1999 Proposed Tech Specs,Revising Efas,Originally Submitted on 980702 as TS Change Request NPF-38-207 ML20211B3291999-08-19019 August 1999 Proposed TS 4.18.3.a.4 Clarification Supporting Tube End Cracking Alternative Repair Criteria ML20211C4101999-08-18018 August 1999 Proposed Tech Specs Removing Requiremets for Tube Repair (Sleeving) & Clarifying Requirements for Preservice & ISI of Tubes to Facilitate Replacement of Original SGs ML20211C1701999-08-18018 August 1999 Proposed Tech Specs Revising ESAS Low RCS Pressure Setpoint to Ensure That TS Adequately Bounds Safety Analysis ML20210P5971999-08-11011 August 1999 Proposed Tech Specs SR 3.3.7.3,replacing Analytical Limits Currently Specified as Acceptance Criteria with Allowable Values,Per Calculation E4C-098,change Notice 25 ML20210P6301999-08-10010 August 1999 Corrected Proposed Tech Specs Re Diesel Generator Testing ML20210N5121999-08-0909 August 1999 Proposed Cycle 10 Update to TS Bases That Have Been Revised Between 980101-990630 ML20210M9861999-08-0404 August 1999 Existing & Proposed TS Pages Modifying TS 3.5.2 by Extending AOT to Seven Days for One HPSI Train Inoperable & TS 3.5.3, Changing end-state to Hot Shutdown with at Least One Operable Shutdown ML20210M9681999-08-0404 August 1999 Existing & Proposed marked-up TS Pages Modifying TS 3.5.2 by Extending AOT to Seven Days for One LPSI Train Inoperable & AOT of 72 Hours Imposed for Other Conditions ML20210N5541999-08-0404 August 1999 Rev 28,Permanent Change 4 to OP-1903.061, Communication Equipment Test ML20210N5571999-08-0404 August 1999 Rev 23,Permanent Change 5 to OP-1903.011, Emergency Response/Notifications ML20210H2371999-07-29029 July 1999 Proposed Tech Specs 3.6.2.1 Extending Allowable Outage Time to Seven Days for One Containment Spray Sys Train Inoperable ML20210H1771999-07-29029 July 1999 Proposed Tech Specs 3.8.1.1 Re EDG AOT Increase from 72 H to Ten Days ML20210K3571999-07-29029 July 1999 Proposed Tech Specs Revising SRs Pertaining to ISI Requirements for SG Tube Circumferential Cracking at top-of-tubesheet During 2P99 Planned mid-cycle Outage ML20210K5121999-07-29029 July 1999 Proposed Tech Specs,Revising Requirements Associated with Plant Station Batteries & DC Sources to 125 Vdc Switchyard Distribution Sys ML20210B3411999-07-19019 July 1999 Proposed Tech Specs 4.5.2.f.2,increasing Performance Requirement for LPSI Pumps ML20209H3191999-07-15015 July 1999 Proposed Tech Specs Pages Modifying TS 3/4.4.8.1,Figures 3.4-2 & 3.4-3 to Extend RCS Pressure Temperature Curves to 20 EFPY ML20210D1071999-07-15015 July 1999 Proposed Tech Specs Adding TS Bases Control Program to TS Administrative Controls Section & Correcting Editorial Error Identified in TS Following Issuance of Amend 146,dtd 981019 ML20210D0521999-07-15015 July 1999 Proposed Tech Specs Creating New TS for Feedwater Isolation Valves ML20209H8701999-07-14014 July 1999 Proposed Tech Specs 6.2.2 & 6.2.2.h,replacing Functional Description of Operations Staff Middle Manager with Ref to Functional Description Assistant Operations Manager & Revising TS Table 6.2-1 Item 5 & TS 6.2.2.f ML20209H9721999-07-14014 July 1999 Proposed Tech Specs Changes for Elimination of Programmatic Requirements Associated with PASS & Regulatory Relief from PASS Requirements of NUREG-0737 & RG 1.97 ML17313B0081999-07-14014 July 1999 Rev 2 to Inservice Insp Program Summary Manual for PVNGS Unit 1. ML20209H5811999-07-14014 July 1999 Proposed Tech Specs Revising RB Structural Integrity Requirements Re ISI Reporting for Containment Structures, Tendons & Anchorages ML20209D4091999-07-0707 July 1999 Proposed Tech Specs,Revising Actions 19 & 20 for Table 3.3-3 for Functional Unit 7 Emergency Feedwater, Items B & C,Per 980702 TS Change Request NPF-38-207 ML20196A9981999-06-17017 June 1999 Revised Pages to Risk-Informed IST Program for Sce ML20195E5171999-06-0808 June 1999 Proposed Tech Specs Pages Re Application for Amend to Licenses NPF-10 & NPF-15,to Revise TS 3.5.2,3.1.9,3.7.1 & 5.1.7.5 ML20195D2371999-06-0101 June 1999 Proposed Tech Specs Re Surveillance Requirements & Applicable Bases Relevant to ISI Requirements for Portions of once-through SG (OTSG) Tubes Adjacent to Primary Cladding Region of tube-to Tubesheet Roll ML17313A9571999-05-26026 May 1999 Proposed Tech Specs,Reducing Spurious Reactor Trip Hazards Associated with Setpoints While Maintaining Plant Protection ML20207A3911999-05-24024 May 1999 Proposed Tech Specs 3.8,clarifying Bases for SRs 3.8.1.7, 3.8.1.12 & 3.8.1.15 ML20196E9971999-05-24024 May 1999 Rev 3 to NTP-203, Emergency Plan Training ML20195B1811999-05-20020 May 1999 Proposed Tech Specs Changes to Bases B 3/4.3.1 & 3/4.3.2, B 3/4.6.3,B 3/4.7.1.2 & B 3/4.7.12 ML20206T2651999-05-14014 May 1999 Proposed Tech Specs Revising SG Tubing SRs ML20206Q1281999-05-10010 May 1999 Proposed Tech Specs Bases,Page B 2-2,discussing Guidance to Be Used When Applying Later Editions & Addendas of ASME Code to RCS Components ML20216D9741999-05-0707 May 1999 Rev 3 to Abnormal Operating Instruction SO23-13-14, Reactor Coolant Leak ML20206J8021999-05-0404 May 1999 PC-03 to Procedure/Work Plan 1904-002, Offsite Dose Projections Rdacs Computer Method ML20205P3731999-04-0909 April 1999 Revised Proposed TS Page 5-1 Re Design Features Conversion ML20205P4081999-04-0909 April 1999 Proposed Tech Specs Changes,Revising Reactor Bldg Structural Integrity Requirements 1999-09-07
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20217N3171999-10-19019 October 1999 Rev 1,change 024-01-0 to OP-1903.011, Emergency Response Notifications ML20217J7641999-10-0505 October 1999 Rev 1 to Unit 1 Technical Requirement Manual, Replacing Index Page ML20211B2381999-08-31031 August 1999 Revised Interjurisdictional Policy for Songs ML20210N5571999-08-0404 August 1999 Rev 23,Permanent Change 5 to OP-1903.011, Emergency Response/Notifications ML20210N5541999-08-0404 August 1999 Rev 28,Permanent Change 4 to OP-1903.061, Communication Equipment Test ML17313B0081999-07-14014 July 1999 Rev 2 to Inservice Insp Program Summary Manual for PVNGS Unit 1. ML20196A9981999-06-17017 June 1999 Revised Pages to Risk-Informed IST Program for Sce ML20196E9971999-05-24024 May 1999 Rev 3 to NTP-203, Emergency Plan Training ML20216D9741999-05-0707 May 1999 Rev 3 to Abnormal Operating Instruction SO23-13-14, Reactor Coolant Leak ML20206J8021999-05-0404 May 1999 PC-03 to Procedure/Work Plan 1904-002, Offsite Dose Projections Rdacs Computer Method ML20205P6431999-04-0909 April 1999 Revised Proposed Technical Requirement Manual Pages ML20204H2591999-03-16016 March 1999 Rev 0 to STD-100-237, Procedure for Modification of RCS Pressure Boundary for Installation of Mechanical Nozzle Seal Assemblies (Mnsa) for Waterford Nuclear Generating Station Unit 3 ML20204H2511999-03-16016 March 1999 Rev 1 to C-NOME-EP-0189, Engineering Procedure for Installation of Mechanical Nozzle Seal Assemblies for Waterford 3 ML20198L5111998-12-23023 December 1998 Rev 0 to SONGS Risk-Informed Inservice Testing Program, Engineering Analysis & Program Description ML17313A7511998-12-16016 December 1998 Rev 2 to ISI Program Summary Manual, for PVNGS Unit 3 ML20196C9761998-11-24024 November 1998 Rev 1 to Unit 2 Technical Requirements Manual ML20154D6681998-10-0101 October 1998 Rev 28 to Procedure/Work Plan 1904.002, Offsite Dose Projections Rdacs Computer Method ML20153H1651998-08-12012 August 1998 Rev 0 to ANO Units 1 & 2 Technical Requirements Manual ML20206N5381998-08-12012 August 1998 Rev 15 to Emergency Operating Instruction S023-12-7, Loss of Forced Circulation/Loss of Offsite Power, Pages 1,3,18, 39 & 122 ML20248H7871998-05-25025 May 1998 Rev 1 to Waterford Unit 3 Second Interval ISI Plan ML20199F7211998-05-22022 May 1998 Rev 8 to Simulator Mod Control,Training Desk Guide 6.3 ML20206N5231998-03-16016 March 1998 Rev 15 to Emergency Operating Instruction S023-12-1, Std Post Trip Actions ML20206E6001998-02-27027 February 1998 Rev 31 to S023-ODCM, SONGS Units 2 & 3 Odcm ML20206N5021998-01-30030 January 1998 Temporary Change Notice 2-1 to Rev 2 to Alarm Response Instruction S023-15-50.A1, Annunciator Panel,50A Pzr/Cea Windows 1-30, Pages 1,3,14,15 & 62-64 ML20202E1611997-12-0101 December 1997 IST Program Third Ten Yr Interval Submittal. W/32 Oversize Drawings ML20202C2911997-12-0101 December 1997 Rev 0 to Pump & Valve Inservice Test Plan for Second 10-Yr Interval. Page 23 of Incoming Submittal Not Included ML20198P4011997-10-31031 October 1997 Rev 2 to Document 90022, Susceptibility of RCS Alloy 600 Nozzles to Primary Water Stress Corrosion Cracking & Replacement Program Plan ML20217M0221997-10-28028 October 1997 Rev 8 to RW-001-210, Process Control Program ML20198J8081997-10-14014 October 1997 Rev 28,Permanent Change 2 to Procedure/Work Plan 1903.061, Communications Equipment Tests ML20211Q1221997-10-14014 October 1997 Rev 22,change 2 to OP-1903.011, Emergency Response Notifications ML20217H5931997-10-14014 October 1997 Revised Page of App B of FOL, Environ Protection Plan (Nonradiological) ML20217K3001997-08-0808 August 1997 Change PC-03,Rev 21 to Work Plan 1903.030, Evacuation ML20151K2241997-07-29029 July 1997 Change PC-01,Rev 6 to OP-1903.035, Adm Potassium Iodide ML20148T0221997-07-0101 July 1997 Change AP-06 to Rev 6 to Procedure OP-1903.035, Adm Potassium Iodide ML20148T0051997-07-0101 July 1997 Change PC-01 to Rev 32 to Procedure OP-1903.060, Emergency Supplies & Equipment ML20148T0441997-07-0101 July 1997 Change PC-01 to Rev 12 to Procedures OP-1903.067, Emergency Response Facility - Emergency Operations Facility (Eof) ML20141C5421997-06-17017 June 1997 2 to Procedure Work Plan 1903.065, Emergency Response Facility Technical Support Center (Tsc) ML20148T5391997-06-0101 June 1997 Rev 0 to Third Ten-Year Interval ISI Plan for ANO Unit 1 ML20217P9981997-05-28028 May 1997 Rev 30 to SONGS Unit 2 & 3, Odcm ML20141B0441997-05-0808 May 1997 Performance Improvement Plan ML20140C0951997-03-26026 March 1997 Rev 11,Change AP-11,to OP-1903.034, Emergency Operations Facility Evacuation ML20137D9271997-03-18018 March 1997 Rev 21-04-00,Change PC-04 to OP-1903.011, Emergency Response/Notifications ML20137W3621997-03-17017 March 1997 Rev 2 to Test Procedure TR-228, Three Hour Fire Test of One and Three Hour Versawrap Raceway Fire Barrier Sys for Conduits & Cable Trays ML20203E4371997-02-12012 February 1997 Rev 2 to SO23-XVII-3.1.1, Refueling Outage Interval Exam of Reactor Coolant Pressure Boundary to Detect Leakage from Abb Combustion Engineering to SCE.W/18 Oversize Drawings ML20249A5311997-01-0707 January 1997 Rev 4 to PRA-REV-001, PRA Model Rev Procedure ML20203K7591996-11-0505 November 1996 Rev 1 to Du General Software Design Description ML20138D8951996-10-0606 October 1996 Rev 5 to Odcm ML20138H5571996-08-0505 August 1996 Rev 1 to Ultrasonic Exam of Vessel Welds & Adjacent Base Metal ML20138F0121996-07-31031 July 1996 Rev 29 to, Offsite Dose Calculation Manual,Nuclear Organization Units 2 & 3 ML20117A5681996-07-28028 July 1996 Ldcr 97-0047-Location of Cabinets C-3A(B) & C-4 Outside Cvas Boundary - Rev 1 1999-08-04
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217L8931999-10-31031 October 1999 Rev 1 to BAW-10235, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs ML20217F2891999-10-13013 October 1999 Drill 99-08 Emergency Preparedness Exercise on 991013 ML20212L1141999-10-0101 October 1999 Safety Evaluation Granting Request for Exemption from Technical Requirements of 10CFR50,App R,Section III.G.2.c ML17300B3811999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Pvngs,Units 1,2 & 3.With 991007 Ltr 0CAN109902, Monthly Operating Repts for Sept 1999 for Arkansas Nuclear One,Units 1 & 2.With1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Arkansas Nuclear One,Units 1 & 2.With ML20217G7211999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Waterford 3 Ses. with ML20217E3381999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Songs,Units 2 & 3 ML20216J6271999-09-27027 September 1999 Rev 0 to CALC-98-R-1020-04, ANO-1 Cycle 16 Colr ML20212F5261999-09-22022 September 1999 SER Approving Request Reliefs 1-98-001 & 1-98-200,parts 1,2 & 3 for Second 10-year ISI Interval at Arkansas Nuclear One, Unit 1 ML20212A1471999-09-13013 September 1999 Special Rept:On 990904,condenser Monitor Was Declared Inoperable.Difficulties Encountered During Component Replacement Precluded SCE from Restoring Monitor to Service within 72 H.Alternate Method of Monitoring Was Established ML20211N0511999-09-0303 September 1999 SER Approving Exemption from Certain Requirements of 10CFR50.44 & 10CFR50 App A,General Design Criterion 41 to Remove Requirements from Hydrogen Control Systems from SONGS Units 2 & 3 Design Basis ML20211Q2141999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Waterord 3 Ses.With ML20211Q8201999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Songs,Units 2 & 3. with ML17300B3271999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Pvngs,Units 1,2 & 3 0CAN099907, Monthly Operating Repts for Aug 1999 for Ano,Units 1 & 2. with1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Ano,Units 1 & 2. with ML17313B0751999-08-27027 August 1999 LER 99-002-00:on 990730,test Mode Trip Bypass for EDG Output Breakers Not Surveilled.Cause Under Investigation.Operations Personnel Conservatively Invoked SR 3.0.3 for SR 3.8.1.13. with 990827 Ltr ML20211F4281999-08-25025 August 1999 Safety Evaluation Concluding That Licensee Provided Acceptable Alternative to Requirements of ASME Code Section XI & That Authorization of Proposed Alternative Would Provide Acceptable Level of Quality & Safety ML20211H8621999-08-23023 August 1999 Safety Evaluation Accepting Licensee Requests for Relief RR-E-2-03 - RR-E-2-08 from Exam Requirements of Applicable ASME Code,Section Xi,For First Containment ISI Interval ML20210P4731999-08-11011 August 1999 COLR Cycle 10 Songs,Unit 2 ML20210P4791999-08-11011 August 1999 COLR Cycle 10 Songs,Unit 3 ML20210S0581999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Waterford 3.With ML20210Q6361999-07-31031 July 1999 Corrected Monthly Operating Rept for July 1999 for Waterford 3 ML20210Q6521999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Songs,Units 2 & 3 0CAN089904, Monthly Operating Repts for July 1999 for Ano,Units 1 & 2. with1999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Ano,Units 1 & 2. with ML17313B0611999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Pvngs,Units 1,2 & 3.With 990810 Ltr ML20210L2771999-07-30030 July 1999 SONGS Unit 3 ISI Summary Rept 2nd Interval,2nd Period Cycle 10 Refueling Outage U3C10 Site Technical Services ML20210K8831999-07-29029 July 1999 Non-proprietary Addendum B to BAW-2346P,Rev 0 Re ANO-1 Specific MSLB Leak Rates ML20210D8951999-07-23023 July 1999 Safety Evaluation Accepting First 10-yr Interval Inservice Insp Plan Requests for Relief ISI-018 - ISI-020 ML17313B0191999-07-16016 July 1999 LER 99-005-00:on 990618,RT on Low DNBR Was Noted.Caused by Hardware Induced Calculation Error.Cr Operator Was Taken to Place Reactor in Stable Condition IAW Appropriate Operating Procedure ML17300B3151999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Pvngs,Units 1,2 & 3.With 990714 Ltr 0CAN079903, Monthly Operating Repts for June 1999 for Ano,Units 1 & 2. with1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Ano,Units 1 & 2. with ML20209H3781999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Waterford 3 Ses. with ML20209C9281999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Songs,Units 2 & 3. with ML17313A9921999-06-21021 June 1999 Special Rept:On 990525,RMS mini-computer Was Removed from Service to Implement Yr 2000 Mod & Was OOS Longer than 72 H Allowed.Caused by Planned Y2K Mods.Preplanned Alternate Sampling Program Was Initiated ML17313A9911999-06-18018 June 1999 Special Rept:On 990510,loose-part Detection Sys Channel 2 Was Declared Inoperable.Caused by Malfunction of Mineral Cable Connector to Accelerometer.Licensee Will Implement Modifications Which Will Enhance loose-part Detection Sys ML20195J8951999-06-17017 June 1999 Safety Evaluation Granting Relief for Listed ISI Parts for Current Interval,Per 10CFR50.55a(g)(5)(iii) ML20207E8631999-06-0303 June 1999 Safety Evaluation Accepting Licensee 990114 Submittal of one-time Request for Relief from ASME B&PV Code IST Requirements for Pressure Safety Valves at Plant,Unit 3 ML20195D3061999-06-0202 June 1999 Safety Evaluation of TR SCE-9801-P, Reload Analysis Methodology for San Onofre Nuclear Generating Station,Units 2 & 3. Rept Acceptable ML20207E7231999-06-0202 June 1999 Safety Evaluation Authorizing Proposed Alternative Exam Methods Proposed in Alternative Exam 99-0-002 to Perform General Visual Exam of Accessible Areas & Detailed Visual Exam of Areas Determined to Be Suspect ML20196A6251999-05-31031 May 1999 Non-proprietary Rev 0 to TR BAW-10235, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs ML20196A0191999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Arkansas Nuclear One,Units 1 & 2.With ML17313A9731999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Pvngs,Units 1,2 & 3.With 990608 Ltr ML20195H5491999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Songs,Units 2 & 3 ML20195K3391999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Waterford 3 Ses.With ML20195C3041999-05-28028 May 1999 Annual Rept on Abb CE ECCS Performance Evaluation Models ML20195D1991999-05-28028 May 1999 Probabilistic Operational Assessment of ANO-2 SG Tubing for Cycle 14 ML20206M7711999-05-11011 May 1999 SER Accepting Relief Request from ASME Code Section XI Requirements for Plant,Units 1 & 2 ML20196L3221999-05-11011 May 1999 SONGS Unit 2 ISI Summary Rept 2nd Interval,2nd Period Cycle-10 Refueling Outage ML17313A9281999-05-0707 May 1999 LER 99-004-00:on 990408,PSV Lift Pressures Were Outside of TS Limits.Caused by Lift Pressure Setpoint Drift.Psvs Have Been Tested,Disassembled,Inspected,Reassembled & Certified at Wyle Labs ML20206H2611999-05-0505 May 1999 Part 21 Rept Re Defect Found in Potter & Brumfield Relays. Sixteen Relays Supplied in Lot 913501 by Vendor as Commercial Grade Items.Caused by Insufficient Contact Pad Welding.Relays Replaced with New Relays 1999-09-30
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RELOAD DATA BLOCK CONSTANT INSTALLATION GUIDELINES CEN-323-NP REVISION 00-NP JANUARY 1986 COMBUSTION ENGINEERING, INC.
Nuclear Power Systems Power Systems Group Windsor, Connecticut 0602130282 060210 '
PDR ADOCK 05000361 P PDR
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LEGAL NOTICE This report was prepared as an account of work sponsored by Combustion Engineering, Inc. Neither Combustion Engineering nor any l
person acting on its behalf:
- a. Makes any warranty or representation, express or implied r including the warranties of fitness for a particular purpose or merchantability, with respect to the accuracy, completeness, or usefulness of the information contained in this report, or that .the use of any information, apparatus, method, or process disclosed in this report may not infringe privately owned rights; or i b. Assumes any liabilities with respect to the use of, or for
. damages resulting from the use of, any information, apparatus, i method or process disclosed in this report.
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l TAB'LE OF' CONTENTS Page No.
'1. 0 INTRODUCTION AND OVERVIEW 5 1.1 Introduction 5 1.2 References 6 1.3 Software Overview 7 2.0 RELOAD DATA BLOCK DISK GENERATION 8 2.1 Purpose 8 2.2 Prerequisites 8 2.3 Procedure 8 3.0 RELOAD DATA BLOCK COMPARISON PROCEDURE 13 3.1 Purpose 13 3.2 . Prerequisites 13 3.3 Procedure 13 Appendix A - PRELIMINARY RDB CONSTANTS A-1 LIST OF FIGURES Page No. 4
- 1. Reload Data Block Interactive Utility Program Load -17 Procedure for Pre-System 80 Plants.
- 2. Reload Data Block Interactive Utility Program Load 19 Procedure for System 80 Plants.
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L 1.0- INTRODUCTION AND OVERVIEW 1.1 Introduction The Reload Data Block (RDB) is a group of constants __
A preliminary list of RDB constants is presented in Appendix A to illustrate the types and number of constants expected in the RDB.
A specialized System Loader will be used to load both the CPC/CEAC System Load disk and the Reload Data Block Constants disks.
This document provides guidelines for generating the RDB disk for a given change in RDB constants. It is expected that RDB constants willbechangedinfrequently,((
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1.2 References 1.2.1 Software Change Procedure for CPC/CEAC Protection Algorithms, CEN-39(A)-P, Rev. 3.-
1.2.2 Quality Assurance of Design Manual for C-E Nuclear Power Systems.
1.2.3 CPC Functional Design Requirements CEN-305-P.
1.2.4 CEAC Functional Design Requirements CEN-304-P.
1.2.5 Software Modifications Document, to be issued August, 1986.
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1.3 Software Overview 1.3.1 The RDB constants disk will be generated by the Reload Data Block Interactive Utility Program. This program contains an RDB Disk Generation Routine and a Disk Comparison Routine. The latter will be used for verification of changes in RDB constants.-
The Disk Generation Routine is designed to generate an RDB disk via a series of questions and answers at the TTY console. The program includes range checking to reduce the chances of mis-entry.
.Upon user request, the program can print a list of changes and/or a complete list of the RDB. constant values cross-referenced with the old values. The complete list will include identification of all constants that have changed, facilitating quality assurance of the final disk.
1.3.2 The RDB Interactive Utility Program will be quality assured to the requirements of Reference 1.2.2.
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2.0 RELOAD DATA BLOCK DISK GENERATION
2.1 Purpose
To create a floppy disk containing Reload Data Block constants.
2.2 Prerequisites
System Configuration: CPC SINGLE CHANNEL TELETYPE TERMINAL FLOPPY DISK DRIVE Software: RDB Interactive Utility Program Disk Other Items: Previous RDB constants disk with associated checksum and sequence numbers.
Blank. Disk List of New Constant Values
2.3 Procedure
- 1) Load the RDB Interactive Utility Program. Refer to Figure 1 for a Pre System 80 plant or to Figure 2 for a System 80 plant.
- 2) a) Program will print ' ENTER OPERATOR NAME AND DATE' b) Respond with operators name followed by a RETURN and then the date in.MM/DD/YY format followed by RETURN.
c) Program will then print ' LOAD THE RDB GENERATION OR COMPARISON PROGRAM? G/C' d) Respond with 'G', the program will print ' RELOAD DATA BLOCK GENERATION ROUTINE'
- 3) Program will then print ' INSERT CURRENT RELOAD DATA BLOCK DISK, HIT RETURN WHEN READY'. Insert the current RDB disk in drive 0 and hit RETURN. The program will then load the RDB constants into memory.
- 4) Respond to the ' ENTER CHECKSUM' prompt with the checksum printed on the TTY output when the current RDB disk was generated.
a) The checksum entered will be compared to the checksum of the constants in memory, ensuring the correct sequencing of the RDB disk updates. If a mismatch does not occur, continue with step 5.
b) If a mismatch occurs, ' CHECKSUM ERROR -- RELOAD OR RE-ENTER L/E' will be printed. Enter 'L' to load again or
'E' to're-enter the checksum. Return to step 3 if 'L' was chosen or repeat step 4 if 'E' was chosen.
- 5) Respond to the ' ENTER DISK SEQUENCE NUMBER' with the sequence number printed on the TTY output when the current RDB disk was generated.
a) The seouence number entered will be compared to the sequence number on disk. If a mismatch does not occur, continue with step 6.
b) If a mismatch occurs, DISK SEQUENCE NUMBER ERROR -- RELOAD
! OR RE-ENTER L/E' will be printed. Enter 'L' to load again or 'E' to re-enter disk sequence number. Return to step 3 if 'L'~ is chosen or repeat step 5 if 'E' is chosen.
- 6) ' ENTER CONST/DONE' will be printed. If '00NE' is selected, go to step 11. Otherwise, continue to step 7 i
- 7) Enter the label of the constant to be changed as it appears in reference 1.2.5. (See notes #1 and #3 at end of this section.)
If the entered label is not found', ' CONSTANT LABEL ERROR' will be displayed and the program returns to step 6.
- 8) When a match occurs the label and its current value will be printed after which ' CHANGE? Y/N' will be printed.
- 9) Respond 'N' if the value is not to be changed, respond 'Y' if the value is to be changed. If 'N' is selected, return to step 6. If 'Y' is selected, go to step 10a. .
- 10) a) Program prints ' ENTER NEW VALUE'. Enter the new value.
(See note #2 at the end of this section.)
b) If an error is made in typing the new value, enter '#' to abort the current value. Then, reenter the value.
c) If the value is not within the pre-defined range for the constant being changed, ' RANGE ERROR' will be printed, and the program returns to step 8. If the value does not meet the requirements of note #2, ' INPUT FORMAT ERROR' wil.1 be printed and the program returns to step 8.
d) If the value is within the pre-defined ranges and of the correct format, the value will be updated and the program returns to step 8.
- 11) If '00NE' is selected in step 6, ' PRINT CHANGES? Y/N' will be printed. If 'Y' is chosen, the label, old value and new value of the constants which have changed will be printed. If 'N' is chosen they will not be printed.
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- 12) 'MORE CHANGES? Y/N' will be printed. If 'Y' is selected, execution returns to step 6. Otherwise execution continues with step 13.
- 13) ' INSERT NEW RELOAD DATA BLOCK CONSTANTS DISK' will be printed.
Place the new RDB disk in the floppy disk drive and hit RETURN.
The RDB constants, plant identification number, CPC/CEAC software revision number, new disk sequence number, and checksum will be written to the floppy disk.
- 14) After the new RDB disk has been generated, ' WRITE PROTECT NEW RDB DISK' will be printed. Remove the new RDB disk from drive 0 and write protect it, then replace it in the drive and hit RETURN.
- 15) After the new RDB disk has been write protected, '0ISK SEQUENCE NUMBER = XXXX' and ' CHECKSUM =.NNNN' will be printed on the TTY. Record both' values as they will be used to uniquely ,
identify this disk and will be used in future RDB changes (steps 4 and 5 above).
- 16) Next, ' COMPARE?Y/N' will be printed. . If 'N' is selected, the calculator will halt. If 'Y' is selected the Reload Data Block Comparison Routine will be executed starting at step 2 of Section 3.3.
Note #1: Array values are entered in standard FORTRAN notation. Example: The tenth constant of a fifty item array would be entered as 'CONST(10)'.
Note d2: All values are input at the TTY as real numbers either in decimal format or in FORTRAN format.
Examples: The floating point number 100.25 can be entered as ' 100.25', '100.25E+0', 'O.10025E+3', etc.
The integer number 56 can be entered as '56', '56.',
'56.0', '560E-l', '0.56E+2' etc. If an integer is incorrectly entered with a fractional value, ' INPUT FORMAT ERROR' will be printed.
Note #3: Appendix A contains a preliminary list of RDB constants. The list is provided for reference purposes only. Reference 1.2.5 will contain the final list of constants. After approval of Reference 1.2.5, the list will be incorporated in revised versions of References 1.2.3 and 1.2.4.
e 3.0 RELOAD DATA BLOCK COMPARISON PROCEDURE
3.1 Purpose
To compare new Relaad Data Block constants with previous values as an aid in verifying those constants that have ,
changed.
3.2 Prerequisites
System Configuration: CPC SINGLE CHANNEL TELETYPE TERMINAL
. FLOPPY DISK DRIVE ,
Software: RDB Interactive Utility Program Disk n
Other Items: Current RDB constants disk with associated checksum and sequence numbers.
Previous RDB constants disk with associated checksum and sequence numbers.
3.3 Procedure
- 1) (This step is not needed if the response was 'Y' in step 2.3.16). Load the Reload Data Block Interactive Utility Program. Refer to figure 1 for a pre System 80 plant and to figure 2 for a System 80 plant.
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a) Program will print ' ENTER OPERATOR NAME AND DATE' b) Respond with operators name followed by a RETURN and then the date in MM/DD/YY format followed by RETURN.
c) Program will then print ' LOAD THE RDB GENERATOR OR COMPARISON PROGRAM? G/C'.
d) Respond with 'C'.
- 2) The program will respond with: ' RELOAD DATA BLOCK COMPARISON ROUTINE'
- 3) ' INSERT NEW RDB CONSTANTS DISK. HIT RETURN WHEN READY.' will be printed. Insert the new RDB constants disk in drive 0 and hit RETURN. The program will then load the new RDB constants.
4). Respond to the ' ENTER CHECKSUM' prompt with the checksum printed on the TTY output wnen the new RDB disk was generated.
, a) The checksum entered will be compared to the checksum of the constants read from the disk, ensuring that the correct RDB disk was selected. If a mismatch does not i
occur, continue with step 5.
b) If a mismatch occurs, ' CHECKSUM ERROR -- RELOAD OR RE-ENTER L/E' will be printed. Enter 'L' to load again or
'E' to're-enter the checksum. Return to step 3 if 'L' was chosen or repeat step 4 if 'E' was chosen.
- 5) Respond to the ' ENTER DISK SEQUENCE NUMBER' with the sequence number printed 6n the TTY output when the new RDB disk was generated.
a) The sequence number entered will be compared to the sequence number on the disk. If a mismatch does not occur, continue with step 6.
b) If a mismatch occurs, DISK SEQUENCE NUMBER ERROR -- RELOAD OR RE-ENTER L/E' will be printed. Enter 'L' to load again or 'E' to re-enter disk sequence number. Peturn to step 3 if 'L' is chosen or repeat step 5 if 'E' is chosen.
- 6) When the checksum and disk sequence number of the new gereration RDB constants have been verified the program will print ' INSERT PREVIOUS RDB CONSTANTS DISK. HIT RETURN WHEN READY.' ,
- 7) Insert previous RDB constants disk in drive 0 and hit RETURN. ,
i The program will then load the previous RDB Constants.
- 8) Respond to the ' ENTER CHECKSUM' prompt with the checksum printed on the TTY output when the previous RDB disk was generated.
a) The chacksum entered will be compared to the checksum rf
. the constants read from the disk, ensuring that the correct RDB disk was selected. If a mismatch does not i
occur, continue-with step 9.
If a mismatch occurs, ' CHECKSUM ERROR -- RELOAD GR b)
RE-ENTER L/E' will be printed. Enter 'L' to load again or
'E' to re-enter the checksum. ' Return to step 7 if 'L' was
! chosen or repeat step 8 ff 'E' was chosen.
i 9) Respond to the ' ENTER DISK SE0VENCE NUMBER' with the sequence number printed on the TTY output when the previous RDB disk was generated.
a) The sequence number entered will be compared to the sequence number on the disk. If a mismatch does not .
occur, continue with step 10.
b) If a mismatch occurs, DISK SEQUENCE NUMBER ERROR -- RELOAD OR RE-ENTER L/E' will be printed. Enter 'L' to load again or 'E' to re-enter disk secuence number. Return te step 7 if 'L' is chosen or repeat step 9 if 'E' is chosen.
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- 10) Next, the program will print out a comparison list of all constants in the following format:
USERS NAME DATE OLD CHECKSUM NEW CHECKSUM OLD DISK SEQUENCE.8 NEW OISK SEQUENCE #
SOFTWARE REVISION #- SOFTWARE REVISION #
CONSTANT 1 OLD VALUE NEW VALUE CONSTANT 2 OLO VALUE NEW VALUE **
etc. ;
i Where '**' means a value has been changed between the two revisions.
- 11) The program will then halt.
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, FIGURE 1 Reload Data Block Interactive Utility Program Load Procedure For Pre-System 80 Plants 5 .
- 1) Set the drive select switches on the AED_2500 so drive A is' drive 0, drive B is drive 1, and drive C is drive 2 (drives B&C are not used. -
The select switches are set to avoid hardware confusion).
J 2)' Place .the Reload Data Block Interactive Utility Program Disk in drive 0, with a write protect tab on, a) Set the INIT and WP on the disk drive switches up b) Lift the IPL switch c) Put the CPC Coldstart Loader tape in the teletype reader.
Ensure the teletype is connected.to the proper CPU (CPC or CEAC) and turn on (switch to 'on-line').
d) Unprotect memory with the key switch on the Operator's Module, e) -Set up the following memory locations, using the hex panel on the calculator:
Location Content 30 0000 32 0000 34 0000 ,
36 0050 50 D500 52 00CF 54 4300 56 0080 78 0294
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- . ' FIGURE 1-(continued) f) Check the entries in step e.
.' g) . Set _the address at 30, Press INI. button, s h) Start the processor at location 30 by pressing RUN button.
1 i) ' Start the punched tape reader.
_j) Respond to the TEST TRACK' prompt'; sit. 55.
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4 FIGURE 2 Reload Data Block Interactive
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Utilit'y Program Load Procedure For System 80 Plants r
Place the Reload Data' Block Interactive Utility Program Disk in the
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! disk drive, write protected.
a) Set the auto-load unit switch in the middle position, i b) On the hex-panel press the INI button.
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e APPENDIX A PRELIMINARY RDB CONSTANTS This appendix provides a preliminary list of the CPC/CEAC data base constants that are expected to be included in the Relcad Data Block (RDB). As noted in the list, some of the constants are single values while others are arrays of values. The list includes 240 data base constants which, counting individual.
array members, totals 556 individual values. The final list of RDB constants may differ in small ways from this list. However, the number of constants and/or.the number of values are not expected to change substantially.
The final list of constants will be defined in 'the Software Modification
' document for the Reload Da'es Block (Rcferance 1.2.5) and will be incorporated in revisicns to' the CPC and/or CEAC Functional Design Requirements documents (References 1.2.3 and 1.2.4) as appropriate.
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I APPENDIX A PPELIMINARY RDB CONSTANTS I
MODULE: TRIPSEQ VARIABLE NAME VARIABLE DESCRIPTION TOTAL RDB CONSTANTS IN TRIPSEQ 2 VARIABLES 2 VALUES MODULE: FLOW VARIABLE NAME VARIABLE DESCRIPTION M
M TOTAL RDB CONSTANTS IN FLOW 6 VARIABLES OR ARRAYS 14 VALUES A-2 L FIWYSEWiMTdME!W,M_81@@:@:M-i,EW$ @
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TOTAL RDB CONSTANTS IN UPDATE 100 VARIABLES AND ARRAYS 108 VALUES A-4
APPENDIX A- PRELIMINARY RDB CONSTANTS
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APPENDIX A PRELIMINARY RDB CCNSTANTS MODULE: : STATIC VARIABLE NAME VARIABLE DESCRIPTION M
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TOTAL RDB CONSTANTS IN CEAC 22 VARIABLES OR ARRAYS 202 VALUES .
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