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Category:REPORTS-TOPICAL (BY MANUFACTURERS-VENDORS ETC)
MONTHYEARML20198G4491998-07-31031 July 1998 Rev 1 to WCAP-15015, Specific Application of Laser Welded Sleeves for SCE San Onofre Units 2 & 3 Sgs ML20217A8281997-06-30030 June 1997 Rev 2 to Final Rept, Repair of 3/4 O.D. SG Tubes Using Leak Tight Sleeves ML20217A8371997-04-27027 April 1997 Rev 0 to EPRI SG Exam Guidelines App H Qualification for Eddy Current Plus-Point Probe Exam of ABB CE Welded Sleeves ML20135A2961996-02-29029 February 1996 Annual Rept on ABB CE ECCS Performance Evaluation Models, Final Rept ML20058A4121993-08-31031 August 1993 Rev 1 to Suppl 4 to CENPD-279, 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 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 ML20043G6711990-04-30030 April 1990 Review of Upper Shelf Charpy Energy Behavior of Matls in San Onofre Unit 1 Reactor Vessel ML19324C4241989-10-31031 October 1989 Rev 0 to San Onofre Units 2 & 3 Fuel Rack Seismic Analysis for Final Pool Layout. ML20073K6781989-06-30030 June 1989 Risk Evalution of Removal of Shutdown Cooling Sys Autoclosure Interlock, Prepared for C-E Owners Group ML20235K9371989-02-28028 February 1989 Engineering Evaluation of San Onofre Nuclear Generating Station I Thermal Shield Supports ML20235Z0931989-02-28028 February 1989 Fuel Rack Seismic Analysis Methods & Parameters ML20154A6351988-07-31031 July 1988 Steam Generator U-Bend Tube Fatigue Evaluation ML20155J4911986-05-31031 May 1986 Rev 0 to Core Protection Calculator/Control Element Assembly Calculator Software Mods for CPC Improvement Program Reload Data Block ML20155J5051986-05-31031 May 1986 Rev 1 to Functional Design Requirements for Control Element Assembly Calculator ML20155J5231986-05-31031 May 1986 Rev 1 to Functional Design Requirement for Core Protection Calculator ML20205Q4601986-05-31031 May 1986 Nonproprietary SONGS 2 End of Cycle 2 Shoulder Gap Evaluation ML20151Z0641986-01-31031 January 1986 Rev 0 to CEN-323-NP Reload Data Block Constant Installation Guidelines ML20151Z0521986-01-31031 January 1986 Rev 3 to CEN-39(A)-NP, CPC Protection Algorithm Software Change Procedure ML20154L6991985-12-31031 December 1985 Spray Additive Tank Deletion Analysis for San Onofre Nuclear Generating Station Units 2 & 3 ML20135A9021985-09-30030 September 1985 Rev 00-NP to Overview Description of Core Operating Limit Supervisory Sys ML20134M7891985-08-31031 August 1985 Nonproprietary Rev 0 to Cpc/Ceac Software Mods for CPC Improvement Program ML20134N3021985-07-31031 July 1985 Rev 00 to Functional Design Requirement for Core Protection Calculator ML20134N2941985-07-31031 July 1985 Rev 00 to Functional Design Requirement for Control Element Assembly Calculator ML20126H8321985-04-30030 April 1985 Nonproprietary Core Protection Calculator Improvement Program:Detailed Presentation to Nrc ML20112K0551985-03-31031 March 1985 Evaluation of Steam Generator Tube & Diagonal Spacer Strip Interaction & Wear,San Onofre Unit 2 ML20114B8211985-01-31031 January 1985 Nonproprietary Addendum to CEN-291(S) Response to NRC Questions on San Onofre Nuclear Generating Station Units 2 & 3,Cycle 2 ML20114C3771985-01-31031 January 1985 Nonproprietary End of Cycle 1 Shoulder Gap Evaluation ML20099C2851984-11-30030 November 1984 Nonproprietary Rev 1 to Core Protection Calculator/Control Element Assembly Calculator Software Mods ML20214E4801984-11-30030 November 1984 Review & Evaluation of Tdi Diesel Engine Reliability & Operability - San Onofre Nuclear Generating Station Unit 1, Technical Evaluation Rept ML20099C2321984-10-31031 October 1984 Nonproprietary Rev 1 to San Onofre Nuclear Generating Station Unit 2 Core Protection Calculator & Control Element Assembly Calculator Data Base Listing ML20204H4971984-10-31031 October 1984 Nonproprietary Statistical Combination of Uncertainties, Part Iii,Uncertainty Analysis of Limiting Conditions for Operation ML20204H4281984-10-31031 October 1984 Nonproprietary Statistical Combination of Uncertainties, Part Ii,Uncertainty Analysis of Limiting Safety Sys Settings ML20093N2661984-07-31031 July 1984 Nonproprietary Cpc/Ceac Software Mods for San Onofre Nuclear Generating Station Units 2 & 3. Info Deleted ML20093N2501984-06-30030 June 1984 Nonproprietary Safety Analysis & CPC Methodology Changes for San Onofre Nuclear Generating Station,Units 2 & 3. Info Deleted ML20095F9411984-03-31031 March 1984 Nonproprietary Version of Rev 0 to SONGS-2 Cycle 1,CPC & Ceac Data Base ML20080K3231983-09-30030 September 1983 Suppl 1,Rev 1,to PRA of Effects of PORVs on Depressurization & Dhr ML20072J5071983-06-30030 June 1983 Depressurization & Dhr,Responses to NRC Questions ML20072J5371983-06-30030 June 1983 Suppl 1 to CEN-239, PRA of Effects of PORVs on Depressurization & Dhr,San Onofre Nuclear Generating Station,Units 2 & 3 ML20070M1291983-01-31031 January 1983 Natural Circulation Test Program,San Onofre Nuclear Generating Station,Unit 2,Natural Circulation Cooldown ML20052B6411982-03-31031 March 1982 Effects of Vessel Head Voiding During Transients & Accidents in C-E Nsss.Prepared for C-E Owners Group. ML20039D4621981-12-31031 December 1981 Summary Rept on Reactor Vessel Integrity for Westinghouse Operating Plants ML20039F8601981-12-31031 December 1981 Evaluation of Pressurized Thermal Shock Effects Due to Small Break LOCAs W/Loss of Feedwater for San Onofre 2 & 3 Reactor Vessels ML20040D0161981-11-30030 November 1981 Nonproprietary Version of Revision 2 to Response to Questions on Documents Supporting San Onofre Nuclear Generating Station 2 License Submittal ML20040D0131981-09-30030 September 1981 Nonproprietary Version of Revision 1 to CETOP-D Code Structure & Modeling Methods for San Onofre Nuclear Generating Station,Units 2 & 3 ML20010F2971981-09-0303 September 1981 Errata Pages to CEN-160-(S)-P, CETOP-D Code Structure & Modeling Methods for San Onofre Nuclear Generating Station, Units 2 & 3. Formal Submittal Will Be Provided ML20010C7781981-08-0505 August 1981 Nonproprietary Version of San Onofre Nuclear Generating Station 2,Cycle 1,CPC & Ceac Data Base Document ML20010A2931981-07-31031 July 1981 To Comprehensive Vibration Assessment Program Final Rept ML20126L3571981-05-31031 May 1981 Nonproprietary Version of, Responses to NRC Concerns on Applicability of CE-1 Correlation to SONGS Fuel Design 1998-07-31
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217B4471999-10-0707 October 1999 Safety Evaluation Supporting Amends 159 & 150 to Licenses NPF-10 & NPF-15,respectively ML20217E3381999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Songs,Units 2 & 3 05000361/LER-1999-005-01, :on 990831,loss of Physical Separation in Control Room,Occurred.Caused by Personnel Error.Creacus Train a Was Returned to Standby on 9908311999-09-23023 September 1999
- on 990831,loss of Physical Separation in Control Room,Occurred.Caused by Personnel Error.Creacus Train a Was Returned to Standby on 990831
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 ML20211R0571999-09-0909 September 1999 Safety Evaluation Supporting Amends 158 & 149 to Licenses NPF-10 & NPF-15,respectively ML20212A2391999-09-0707 September 1999 Safety Evaluation Supporting Amends 157 & 148 to Licenses NPF-10 & NPF-15,respectively 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 05000206/LER-1999-001-02, :on 990808,unattended Security Weapon Was Discovered Inside Pa.Caused by Posted Security Officer Falling Asleep.Officer Was Relieved of Duties,Pa Access Was Removed & Officer Was Placed on Investigatory Suspension1999-08-31031 August 1999
- on 990808,unattended Security Weapon Was Discovered Inside Pa.Caused by Posted Security Officer Falling Asleep.Officer Was Relieved of Duties,Pa Access Was Removed & Officer Was Placed on Investigatory Suspension
ML20211Q8201999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Songs,Units 2 & 3. with 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 ML20211E9441999-08-19019 August 1999 Safety Evaluation Supporting Amends 156 & 147 to Licenses NPF-10 & NPF-15,respectively ML20211F2211999-08-19019 August 1999 Safety Evaluation Supporting Amends 155 & 146 to Licenses NPF-10 & NPF-15,respectively ML20210P4731999-08-11011 August 1999 COLR Cycle 10 Songs,Unit 2 ML20210P4791999-08-11011 August 1999 COLR Cycle 10 Songs,Unit 3 05000361/LER-1999-004-01, :on 990708,automatic Tgis Actuation Occurred. Caused by Small Leak in Suction Side of Tgis Train a Sample Pump.Small Leak Repaired1999-08-0606 August 1999
- on 990708,automatic Tgis Actuation Occurred. Caused by Small Leak in Suction Side of Tgis Train a Sample Pump.Small Leak Repaired
ML20210Q6521999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Songs,Units 2 & 3 ML20210L2771999-07-30030 July 1999 SONGS Unit 3 ISI Summary Rept 2nd Interval,2nd Period Cycle 10 Refueling Outage U3C10 Site Technical Services 05000362/LER-1999-005, :on 990630,discovered LTOP Sys Relief Valve Setpoint Was Higher than Allowed by Ts.Cause Indeterminate. Subject Valve Will Be Disassembled & Inspected to Determine Caused of High Setpoint.With1999-07-28028 July 1999
- on 990630,discovered LTOP Sys Relief Valve Setpoint Was Higher than Allowed by Ts.Cause Indeterminate. Subject Valve Will Be Disassembled & Inspected to Determine Caused of High Setpoint.With
05000362/LER-1999-006, :on 990623,EDG 3G003 Was Inadvertently Made Inoperable.Caused by Operators Aligning EDG to Inoperable Automatic Voltage Regulator.Licensee Will Revise Process of Locating Tags.With1999-07-26026 July 1999
- on 990623,EDG 3G003 Was Inadvertently Made Inoperable.Caused by Operators Aligning EDG to Inoperable Automatic Voltage Regulator.Licensee Will Revise Process of Locating Tags.With
ML20209G8991999-07-12012 July 1999 Safety Evaluation Supporting Amends 154 & 145 to Licenses NPF-10 & NPF-15,respectively ML20209C9281999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Songs,Units 2 & 3. with 05000362/LER-1999-004, :on 990515,reactor Manually Tripped Due to Feedwater Control Valve Opening.Caused by Faulty Valve Positioner.Faulty Positioner Was Replaced1999-06-11011 June 1999
- on 990515,reactor Manually Tripped Due to Feedwater Control Valve Opening.Caused by Faulty Valve Positioner.Faulty Positioner Was Replaced
05000362/LER-1999-003-01, :on 990513,reactor Manually Tripped Due to Loss of Main Feedwater.Caused by Open Relay Contact in Output of Feedwater Regulation Control Sys.Faulty Relay Was Replaced1999-06-11011 June 1999
- on 990513,reactor Manually Tripped Due to Loss of Main Feedwater.Caused by Open Relay Contact in Output of Feedwater Regulation Control Sys.Faulty Relay Was Replaced
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 ML20195H5491999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Songs,Units 2 & 3 05000362/LER-1999-002-01, :on 990328,RWST Outlet Isolation Valve Failed to Open After Being Closed for Testing.Caused by Degradation of Valve.Rwst Oulet Valve Was Repaired.With1999-05-20020 May 1999
- on 990328,RWST Outlet Isolation Valve Failed to Open After Being Closed for Testing.Caused by Degradation of Valve.Rwst Oulet Valve Was Repaired.With
ML20207A0211999-05-13013 May 1999 Safety Evaluation Supporting Amends 153 & 144 to Licenses NPF-10 & NPF-15,respectively ML20196L3221999-05-11011 May 1999 SONGS Unit 2 ISI Summary Rept 2nd Interval,2nd Period Cycle-10 Refueling Outage 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 ML20206S7281999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Songs,Units 2 & 3 ML20206G6561999-04-27027 April 1999 SER Accepting Proposed Exemption from 10CFR50.71(e)(4) for SONGS Units 2 & 3 ML20206D1461999-04-26026 April 1999 Safety Evaluation Supporting Amend 152 to License NPF-10 ML20205Q6221999-04-19019 April 1999 Safety Evaluation Authorizing Proposed Alternative to Use Wire Penetrameters for ISI Radiography in Place of ASME Code Requirement ML20205R0371999-04-16016 April 1999 SER Approving Proposed Deviation from Approved Fire Protection Program Incorporating Technical Requirements of 10CFR50,App R,Section III.0 That Applies to RCP Oil Fill Piping ML20205N2691999-04-0909 April 1999 Safety Evaluation Supporting Amends 151 & 143 to Licenses NPF-10 & NPF-15,respectively ML20205G2611999-04-0101 April 1999 Special Rept:On 990328,3RT-7865 Was Removed from Service. Monitor Is Scheduled to Be Returned to Service Prior to Mode 4 Entry (Early May 1999) Which Will Exceed 72 H Allowed by LCS 3.3.102.Alternate Method of Monitoring Will Be Used ML20205Q0981999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Songs,Units 2 & 3 05000362/LER-1999-001-01, :on 990211,TS 3.0.3 Entered Due to Both Chilled Water Trains Being Inoperable.Warm Main Condenser Discharged Water Diverted in Salt Water Cooling (Swc)(Bs) Intake.With1999-03-12012 March 1999
- on 990211,TS 3.0.3 Entered Due to Both Chilled Water Trains Being Inoperable.Warm Main Condenser Discharged Water Diverted in Salt Water Cooling (Swc)(Bs) Intake.With
05000361/LER-1999-002, :on 990208,pressurizer Safety Valves Were Above TS Limit.Caused by Setpoint Drift.Sce Submitted License Amend Application on 980904 Requesting Tolerence Be Changed to +3/-2%.With1999-03-10010 March 1999
- on 990208,pressurizer Safety Valves Were Above TS Limit.Caused by Setpoint Drift.Sce Submitted License Amend Application on 980904 Requesting Tolerence Be Changed to +3/-2%.With
05000361/LER-1999-001, :on 990201,automatic Start of EDG Was Noted. Caused by Workers Closing Breaker 2A0418 by Discharging Closing Springs.Operators Restored SDC in Approx 26 Minutes. with1999-03-0303 March 1999
- on 990201,automatic Start of EDG Was Noted. Caused by Workers Closing Breaker 2A0418 by Discharging Closing Springs.Operators Restored SDC in Approx 26 Minutes. with
ML20204F8101999-02-28028 February 1999 Monthly Operating Repts for Songs,Units 2 & 3.With ML20203J1131999-02-12012 February 1999 Safety Evaluation Supporting Amends 150 & 142 to Licenses NPF-10 & NPF-15,respectively ML20203J1981999-02-12012 February 1999 Safety Evaluation Supporting Amends 149 & 141 to Licenses NPF-10 & NPF-15,respectively ML20202F7041999-01-21021 January 1999 Special Rept:On 990106,SCE Began to Modify 2RT-7865.2RT-7865 to Allow Monitor to Provide Input to New Radiation Monitoring Data Acquisition Sys.Monitor Found to Exceeds 72 H Allowed Bt LCS 3.3.102.Alternate Monitoring Established ML20206H2101998-12-31031 December 1998 SCE 1998 Annual Rept ML20199F0771998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Songs,Units 2 & 3 ML20198S5551998-12-22022 December 1998 Safety Evaluation Supporting Amends 147 & 139 to Licenses NPF-10 & NPF-15,respectively ML20198H5401998-12-21021 December 1998 Safety Evaluation Supporting Amends 146 & 138 to Licenses NPF-10 & NPF-15,respectively ML20206N6281998-12-16016 December 1998 Safety Evaluation Supporting Amends 145 & 137 to Licenses NPF-10 & NPF-15,respectively ML20198A6731998-12-11011 December 1998 Special Rept:On 981124,meteorological Sys Wind Direction Sensor Was Observed to Be Inoperable.Caused by Loss of Communication from Tower to Cr.Sensor Was Replaced & Sys Was Declared Operable on 981204 1999-09-09
[Table view] |
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Docket 50-361 CEN-302(S)-NP CPC IMPROVEMENT PROGRAM 1
Detailed Presentation to NRC April 1985 Combustion Engineering, Inc.
Nuclear Power Systems Power Systems Group Windsor, Connecticut 8506100428 850607 PDR ADOCK 05000361 P
PDR
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l LEGAL NOTICE i
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I THIS REPORT WAS PREPARED AS AN ACCOUNT OF WORK SPONSORED SY C00SLSTION ENGINEERING, INC. NEITHER COMEUSTION ENGINEERING l
NOR ANY PERSON ACTING ON ITS SEMALP:
l A.
M44WS ANY WARRANTY OR REPRESENTATION, EXPRESS OR IRWUSD IIICLUDING THE WARRANTIES' OF PITNESS POR A PARTICULAR PURPOSE OR RERCHANTAEIUTY, WITH RESPECT TO THE ACCURACY, l
CORWLETENESS, OR USEPULNESS OF THE INFORMATION CONTAINED IN THIS REPORT, OR THAT THE LNE OF ANY INFORMATION, APPARATUS, WTHOO, OR PROCESS Ol8 CLOSED IN THIS REPORT MAY NOT INFRlNGE PRIVATELY OUNIS RIGHTS:OR
- 3. ASSUMES ANY UAEIUTIES WITH RESPECT TO THE 1.NE OF, OR POR DAMMBES RESULTfNG PRORA THE USE OF, ANY INFORMATION, APPARATUS, RAETHOO OR PROCESS DISCLOSED IN THIS REPORT.
l l'
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- INTROPUCTION The COLSS/CPC Oversight Conmittee, consisting of Arizona Nuclear Power Project, Arkansas Power and Light Company, Louisiana Power and Light Company and Southern California Edison, with Combustion Engineering as its technical consultant, was formed to address common analysis and software issues related to the Combustion Engineering digital monitoring and protection systems -' the Core Operating Limit Supervisory System (COLSS)
. and the Core Protection Calculator System (CPCS). The Committee will attempt to provide a standardized approach to resolution of problems and implementation of improvements to the digital monitoring and protection systems, an information mechanism for sharing operating experience and a feedback mechanism for the software designer.
The'COLSS/CPC Oversight Committee will meet with the NRC on April 18, 1985 to present a detailed description of the CPC Improvement Program, a program of CPC Modifications and Methodology Improvements scheduled to be implemented in 1986 and 1987. An initial presentation of concepts was provided on November 8, 1984. The schedule for implementation of the program was presented to the NRC on March 8, 1985. The April 18 meeting will provide a detailed presentation of the portions of the program scheduled for implementation in early 1986. This document provides the NRC with copies of the slides to be presented at this meeting.
The objective of the presentation is to provide a detailed description of the CPC Improvement Program in order to initiate the NRC review process, to solicit feedback from the NRC to guide in program development and to assist the NRC'in meeting the implementation schedule. A schedule for presentations, documentation and implementation will be presented at the meeting.
The CPC Improvement Program consists of three major areas:
- Part A - Optimization of CPC/CEAC Software for Reloads
- Part B - CEAC Sesensitization to Spurious Signals
- Part C - Reload Data Riock Constants This presentation will cover details of Parts A and B, scheduled to be implemented in early 1986. Part C, scheduled to be implemented initially in late 1986, will be presented in August 19R5.
The program to be described in this presentation will apply in whole or part to Arkansas Nuclear One Unit 2 (ANO-2); Palo Verde Nuclear Generating Station (PVNGS) Units 1, 2'and 3; San Onofre Nuclear Generating Station (SONGS) Units 2 and 3; and Waterford Unit 3.
This report is being presented on the SONGS Unit 2 docket since it is l
scheduled as the lead plant for implementation of the CPC Improvement j
Program.
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j CPC IMPROVEMENT PROGRAM PLANS FOR CPC PODIFICATIONS AND METHODOLOGY IMPROVEMENTS i
i I
DETAILED PRESENTATION TO NRC l'
APRIL 18, 1985 I
I ARIZONA NUCLEAR POWER PROJECT ARKANSAS POWER AND LIGHT COMPANY COMBUSTION ENGINEERING, INC.
LOUISIANA POWER AND LIGHT COMPANY SOUTHERN CALIFORNIA EDISON e
- ^'
AGENDA NRC - COLSS/CPC OVERSIGHT COMMITTEE MEETING APRIL 18, 1985 CPC IMPROVEMENT PROGRAM INTRODUCTIbH o
o PROGRAM GOALS o
PROGRAM APPROACH o
DESCRIPTION OF PROGRAM o
SCHEDULE FOR PRESENTATIONS, DOCUMENTATION AND IMPLEMENTATION o
SUMMARY
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CPC IMPROVEMENT PROGRAM
-PRESENTATION OBJECTIVE:
TO PROVIDE A DETAILED DESCRIPTION OF A PLANNED IMPROVEMENT PROGRAM FOR THE CORE PROTECTION CALCULATOR (CPC) SYSTEM IN ORDER TO INITIATE THE NRC REVIEW PROCESS, TO SOLICIT FEEDBACK FROM THE NRC TO GUIDE IN PROGRAM DEVELOPMENT, AND TO ASSIST THE NRC IN MEETING THE IMPLEMENTATION SCHEDULE.
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t CPC IMPROVEMENT PROGRAM PROGRAM GOALS o
AVOID FUTURE CPC SOFTWARE CHANGES
- REDUCE RELOAD EFFORT, CALENDAR TIME AND NEED l
FOR NRC REVIEWS o
REDUCE UNNECESSARY PLANT TRIPS
- AVOID TRANSIENTS CAUSED BY UNNECESSARY PLANT TRIPS
- IMPROVE PLANT AVAILABILITY o
SIMPLIFY RELOAD ANALYSES
- REDUCE RELOAD EFFORT AND CALENDAR TIME o
MAINTAIN MARGINS TO SAFETY I-I 3
S CPC IMPROVEMENT PROGRAM PROGRAM APPROACH I
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OPTIMIZATION OF CPC/CEAC SOFTWARE FOR RELOADS
- IMPLEMENT IN EARLY 19R6 1
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- IMPLEMENT IN EARLY 1986 C.
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- DETAILS TO BE PRESENTED IN AUGUST 19R5
- IMPLEMENT IN LATE 1986 w
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RELOAD DATA RLOCK CONSTANTS (CONTINUE 0)
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SCHEDULE FOR PRESENTATIONS, DOCUMENTATION AND IMPLEME!!TATION NOV. 1984 INITIAL PRESENTATION OF CONCEPTS MAR. 1985 DETAILED PRESENTATION OF IMPLEMENTATION AND REVIEW SCHEDULE APR. 1985 DETAILED PRESENTATION (PARTS A A B)*
MAY 1985 SONGS-2 CYCLE 3 " KICK-OFF" MEETING TO OUTLINE OVERALL LICENSING PLANS JUN. 1985 COLSS TOPICAL REPORT (FOR INFORMATION)
AUG. 1985 DETAILEO PRESENTATION (PART C PLUS UPDATE ON PARTS A A B)*
CPC UPDATED FUNCTIONAL DESIGH SPECIFICATION (PRIOR TO PROGRAM - FOR INFORMATION)
GENERIC SOFTWARE MODIFICATIONS AND METH000 LOGY DOCUMENTS (PARTS A & B)*
PLANT SPECIFIC M00lFICATI0tlS AND METHODOLOGY 00CUMENTS, IF NEEDED (SONGS)
REVISED SOFTWARE CHAf1GE PROCEntlRE FOR RELOAD OATA RLOCK AND ROR CONSTANT CHANGE PROCEntlRE (PART C)*
SONGS-2 CYCLE 3 RELOAD ANALYSIS REPORT AND TECH SPEC CHAf1GE 00CultE'lTATION
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'CPC TMPROVEMENT PROGRAM SCHEDULE FOR PRESENTATIONS, DOCUMENTATION AND IMPLEMENTATION (CONT'0)
NOV. 19R5 AN0-2 METHODOLOGY, ANALYSIS AND TECH-SPEC CHANGE DOCUMENTATION PHASE I/II TEST REPORT (SONGS)
JAN. 1986 PHASE I/II TEST REPORTS (ANO-2)
MAR. 1986 SONGS-2 CYCLE 3 STARTUP (IMPLEMENT PARTS A A B)*
ANO-2 MID CYCLE 5 IMPLEMEllTATION (PARTS A A B)*
MAY 1986 GENERIC SOFTilARE N00!FICATION 00CllMENT (PART C)*
JUL. 19R6 WATERFORD CYCLE 2 RELOAD ANALYSIS REPORT AND TECH SPEC CHANGE DOCUMENTATION SEP. 1986 PHASE T/II TEST REPORT (WATERFORD)
PVNGS-1 CYCLE 2 RELOAD ANALYSIS REPORT AND TECH SPEC CHANGE 00CllMENTATION NOV. 1986 WATERFORO CYCLE 2 STARTUP (INPLEMENT PARTS A, 8 A C)*
PHASE I/II TEST REPORTS (PALO VERDE)
JAN. 1987 PVNGS-1 CYCLE 2 STARTUP (IMPLEMENT PARTS A, 8 A C)*
i CPART A = OPTIMIZATION OF SOFTWARE FOR RELOADS PART B = CEAC DESENSITIZATION TO SPl!RIOUS S!GilALS PART C
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ELOA0 OATA RLOCK COPMTANTS R
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CPC IMPROVEMENT PROGRAft Sutt4ARY GOALS o
AVOID FUTURE CPC SOFTWARE CHANGES o
REDUCE UNNECESSARY PLANT TRIPS o
SIMPLIFY RELOAD ANALYSES o
PROGRAli o
OPTIMIZATION OF CPC/CEAC SOFTWARE FOR RELOADS o
CEAC DESENSITIZATION TO SPURIOUS SIGNALS RELOAODdTABLOCKCONSTANTS o
PLAN FOR INITIAL IMPLEMENTATION OPTIMIZATION OF SOFTWARE AND CEAC DESENSITIZATION o
FOR ANO-2 MID CYCLE 5 AND SONGS-2/3 CYCLE 3 o
RELOAD DATA BLOCK FOR WATERFORO-3 CYCLE 2 AND PVUGS-1 CYCLE 2 00CUtiENTATION FOR NRC REVIEW.
DETAILED PRESENTATIONS OF CPC MODIFICATIONS AND 0
METHODOLOGY o
CPC f100!FICATIONS AND fiETH000 LOGY 00CUPENTS o
PHASE I AND II TEST REPORTS 47
N COMBUSTION ENGINEERING, INC.
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