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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217K9011999-10-18018 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 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 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 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 ML20210H1771999-07-29029 July 1999 Proposed Tech Specs 3.8.1.1 Re EDG AOT Increase from 72 H to Ten Days 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 ML20210B3411999-07-19019 July 1999 Proposed Tech Specs 4.5.2.f.2,increasing Performance Requirement for LPSI Pumps ML20210D0521999-07-15015 July 1999 Proposed Tech Specs Creating New TS for Feedwater Isolation Valves 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 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 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 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 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 ML20203C4891999-02-0505 February 1999 Proposed Revised Tech Specs Pages 3/4 3-12a & B 3/4 3-1a Re Reactor Trip Circuit Breaker Surveillance Interval Extension ML20199D9851999-01-12012 January 1999 Proposed Tech Specs,Adding Requirement That CR Intake Monitors Be Operable & SRs Be Applicable During Movement of Irradiated Fuel ML20199E0861999-01-12012 January 1999 Proposed Tech Specs Re Rev 1 for TS Change Request NPF-38-174 ML20198G2401998-12-23023 December 1998 Proposed Tech Specs,Modifying LCO for 3.3.3.7.1 for Chlorine Detection Sys by Changing Alarm/Trip Setpoint from 3 Ppm to 2 Ppm ML20196D2181998-11-30030 November 1998 Proposed Tech Specs Pages 3/4 8-8,3/4 9-8,3/4 9-9 & B 3/4 9-2,revised for Consistency Between Action Statements & NUREG-1432,Rev 1, Std Tech Specs for CE Plants ML20154E4171998-10-0606 October 1998 Proposed Tech Specs Pages Re TS Change Request NPF-38-212, Modifying Requirement to Perform Mtc Test Near End of Each Cycle ML20154E1141998-10-0101 October 1998 Proposed Tech Specs Modifying TS 3.3.3.7.3 & SR 4.3.3.7.3 for Broad Range Gas Sys ML20153D5771998-09-23023 September 1998 Proposed Tech Specs Revising Description Re Reactor Power Input Used by Operating Bypass Permissive & Trip Enable of 10-4% Bistable ML20153B4441998-09-18018 September 1998 Proposed Tech Specs Modifying Notes in Tables 2.2-1 & 3.3-1 Re Reactor Protective Instrumentation ML20151W5971998-09-11011 September 1998 Proposed Tech Specs Re Notes in Table 2.2-1 Re Reactor Protective Instrumentation Trip Setpoints Limits & Table 3.3-1 Re Reactor Protective Instrumentation ML20237A7921998-08-12012 August 1998 Proposed Tech Specs,Increasing Max Boron Concentration in SITs & Rwsp from 2300 Ppm to 2900 Ppm ML20236U7361998-07-29029 July 1998 Proposed Tech Specs Pages Revising TS 6.9.1.11.1 to Replace Ref to Abb Combustion Engineering SBLOCA ECCS Performance Evaluation Model ML20236H1501998-07-0202 July 1998 Proposed Tech Specs Section 3/4.3.2,adding Restriction on Period of Time Channel of Efas Instrumentation Can Remain in Tripped Condition ML20249C8321998-06-29029 June 1998 Proposed Tech Specs 3.7.6.1,3.7.6.2,3.7.6.3,3.7.6.4 & 3.7.6.5,revising Control Room Ventilation to Be Consistent w/NUREG-1432 ML20249C7901998-06-29029 June 1998 Proposed Tech Specs Adding Footnote to Action Statements to Allow CR Ventilation Sys to Be Unisolated Periodically Under Administrative Controls ML20249A3101998-06-12012 June 1998 Proposed Tech Specs Pages,Adding Footnote to TS Refueling Operations,Surveillance Requirements 4.9.7.2,to Effect Limited Deviation to Allow Crane Main Hook Electrical Interlocks to Be Replaced W/Administrative Controls ML20248B7611998-05-28028 May 1998 Proposed TS Pages Supporting Change to TS 3.7.1.2, Surveillance Requirement 4.7.1.2 & Bases for Emergency Feedwater Sys ML20248H7871998-05-25025 May 1998 Rev 1 to Waterford Unit 3 Second Interval ISI Plan ML20247P2431998-05-21021 May 1998 Proposed Tech Specs Re Design Feature Suppl ML20217P8411998-05-0101 May 1998 Rev TS Pages Changing Actions Required Should Channel of Recirculation Actuation Signal (RAS) Be Placed in Tripped Condition,Replacing TS Pages Submitted in 970603 Submittal ML20217L9971998-04-30030 April 1998 Small Break LOCA ECCS Performance Analysis Using Abb/Ce Suppl 2 Model ML20217D5181998-03-25025 March 1998 Proposed TS 3.9.8.1,3.9.8.2,TS Action 3.9.8.2a,3.8.1.2 & Bases 3/4.9.8 ML20198R3081998-01-21021 January 1998 Errata to Proposed TS Change Request NPF-38-196 Which Changed TS 3.1.1.1,3.1.1.2,3.10.1 & Figure 3.1.-1 by Removing Cycle Dependent B Concentration & Boration Flow Rate from Action Statements ML20198R1251998-01-21021 January 1998 Corrections to Proposed Tech Spec 3/4.1 Re Reactivity Control Sys ML20197C6431997-12-22022 December 1997 Proposed Tech Specs Page Supplementing TS Change Request NPF-38-186,by Retaining Operations Superintendent in Paragraph 6.2.2.f of Administrative Controls Section 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 ML20199A0011997-11-13013 November 1997 Errata to Proposed Tech Specs Change Request NPF-38-193, Replacing Pages 13 Through 21 ML20199A1101997-11-13013 November 1997 Proposed Tech Specs,Modifying 6.8.4.a, Primary Coolant Sources Outside Containment to Add Portions of Containment Vacuum Relief Sys & Primary Sampling Sys to Program ML20217M0221997-10-28028 October 1997 Rev 8 to RW-001-210, Process Control Program ML20217H5931997-10-14014 October 1997 Revised Page of App B of FOL, Environ Protection Plan (Nonradiological) ML20217G2421997-10-0707 October 1997 Proposed Tech Specs Modifying 3.3.3.7.3 & Surveillance Requirement 4.3.3.7.3 for Broad Range Gas Detection Sys ML20211F8141997-09-25025 September 1997 Proposed Tech Specs Pages Modifying LCO 3.6.1.2, Containment Leakage, Associated Action & SR 4.6.1.2 ML20141G7131997-07-0707 July 1997 Proposed Tech Specs Expanding Applicability of TS 3.7.1.3 to Include Mode 4 Operational Requirements & Maintains 91 Percent Minimum Condensate Storage Pool Level Previously Requested for Modes 1,2 & 3 ML20141D8551997-06-26026 June 1997 Proposed Tech Specs Revising TS Tables 3.7-1 & 3.7-2 by Changing MSSVs Orifice Size from 26 Inches to 28.27 Inches & Relocating Orifice Size from TS to TS Bases 1999-08-04
[Table view] Category:TEST REPORT
MONTHYEARML20217L9971998-04-30030 April 1998 Small Break LOCA ECCS Performance Analysis Using Abb/Ce Suppl 2 Model ML20237A0981992-05-14014 May 1992 Rev 0 to Anchor/Darling Valve Company Rept on Blowdown Testing, for A/Dv 900 Double Disc Gate Valve ML20082F5031991-06-30030 June 1991 Reactor Containment Bldg Integrated Leak Rate Test, Final Rept ML20059E7901990-01-22022 January 1990 ASTM E-72 Load Testing of 2-h Solid Stud Wall ML20151Y7241988-05-31031 May 1988 Reactor Containment Integrated Leak Rate Test,Final Rept W3P87-0969, Cycle 2 Reload Startup Test Rept for Period Ending 8703011987-03-0101 March 1987 Cycle 2 Reload Startup Test Rept for Period Ending 870301 ML20207G4611986-12-30030 December 1986 Basemat Monitoring Program Special Rept W3P86-0048, Addendum 1 to Waterford Steam Electric Station Unit 3 Startup Rept1986-03-14014 March 1986 Addendum 1 to Waterford Steam Electric Station Unit 3 Startup Rept W3P85-3218, Startup Rept for Us Nrc1985-10-10010 October 1985 Startup Rept for Us Nrc ML20116N5291985-04-25025 April 1985 Rev 1 to Evaluation of Potential Adverse Effects of Failure of Containment Coatings on Post-Accident Fluid Sys, Rept on License Condition 16 ML20106F3671984-10-31031 October 1984 NDT Evaluation of Basemat Concrete ML20106F3551984-10-25025 October 1984 Summary Evaluation,Structural Significance of Basemat NDT Results ML20080U4931984-01-31031 January 1984 Evaluation of Natural Circulation Cooldown Test Performed at San Onofre Nuclear Generating Station ML20079L4731983-06-0101 June 1983 Fire Qualification Test Hemyc Cable Wrap Sys as Installed by Insulco,Inc & Affiliated Co, Final Rept ML20077A7391983-05-0101 May 1983 Reactor Containment Bldg Integrated Leakage Rate Test, Final Rept ML20079L4591983-02-14014 February 1983 Comparison of Hemyc Sys Fire Test to Sandia 20-Ft Separation Test & Cmeb 9.5.1 ML20028G3131982-11-30030 November 1982 Nonproprietary Version of, Suppl to Waterford 3,Cycle 1 Cpc/Ceac Phase II Software Verification Test Rept. ML20063D2011982-06-30030 June 1982 Nonproprietary CEN-209(C)-NP, Waterford 3,Cycle 1 Cpc/Ceac Phase 1 Software Verification Test Rept ML20063D2051982-06-30030 June 1982 Nonproprietary CEN-208(C)-NP, Waterford 3,Cycle 1 Cpc/Ceac Phase II Software Verification Test Rept ML20054J9001982-06-30030 June 1982 Model Testing of Safety Injection Sys Sump ML20063D2091982-06-21021 June 1982 Nonproprietary CEN-207(C)-NP, Waterford 3,Cycle 1 CPC & Ceac Data Base Document ML20063H6381982-05-25025 May 1982 Post-weld Heat Treatment Test Results ML20076B9391981-11-30030 November 1981 Eddy Current Exam,Oct-Nov 1981 ML20028G2191981-10-0909 October 1981 Az Nuclear Power Project 150-Inch Reed Switch Position Transmitter & Litton Electrical Connector Seismic Qualification Test (Sine Sweep Testing). Age Considerations for Seismic Design & Surveillance in Mild Environs Encl ML20127B6151976-05-31031 May 1976 Mat 10B Placement Rept. Related Info Encl ML20127B6081975-11-30030 November 1975 Clam Shell Filter Blanket Test Rept 1998-04-30
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, LOUISIANA POWER & LIGHT COMPANY CEN 208 (C)-NP, SUPPLEMENT 1- NP SUPPLEMENT TO WATERFORD 3, Cycle 1 CPC/CEAC Phase II SOFTWARE VERIFICATION TEST REPORT COMBUSTION ENGINEERING, INC.
Nuclear Power Systems Power Systems Group Windsor, Connecticut 06095 NOVEMBER 1982 B302070621 830127 DRADOCK05000g
, LEGAL NOTICE This response was prepared as an aceount of work sponsored by Combustion Engineering, Inc. Neither Combustion Engineering nor any person acting on its behalf: .
- a. Makes any warranty or representation, express or implied 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 response, or that the use of any information, apparatus, method, or process disclosed .in this response may r:ot infringe privately owned rights; or
- b. Assumes any liabilities 'with respect to the use of, or for damages resulting from the use of, any information, apparatus, method or process disclosed in this response.
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ABSTRACT Phase II Testing is performed on the CPC/CEAC System to (1)
. verify that the CPC and CEAC software modifications have been properly integrated with CPC and CEAC software and system
. hardware; (2) provide confirmation that the static and dynamic operation of the integrated system as modified is consistent with that predicted by design analysis.
This supplement describes the results and resolutions of the open items which were identified in the Waterford 3, Cycle 1 CPC/CEAC Phase II Software Verification Test Report (Reference 1).
I Page 3
1.0 INTRODUCTION
The verification process for the CPC/CEAC software implementation includes Phase I and Phase II Testings (Reference 2). Phase I testing verifies the correct implementation of the software. Phase II testing verifies that the integrated CPC system, software including hardware, responds as expected.' The Phase I and Phase II testings are described in
, References 1 and 3.
In Reference 1, three of the test cases in Dynamic Software Verification Test (DSVT), had test results that fell outside the acceptance criteria.
This supplement describes the analyses performed to show the Waterford-3 CPC/CEAC System Software (Rev. 00) is acceptable for plant safety operation.
2.0 DYNAMIC SOFTWARE VERIFICATION TEST The Dynamic Software Verification Test (DSVT) is a real time exercise of the CPC application software and executive software with transient CPC input values read from a storage device. The same CPC input values (test case) are executed on the Single Channel CPC and the certified CPC/CEAC FORTRAN simulation code. Acceptance criteria for DSVT are defined (in Reference 2) as a trip time and initial values of DNBR and LPD for each test case. The trip time and initial values of DNBR and LPD calculated by the CPC/CEAC FORTRAN simulation code, with the processing uncertainties factored in, will provide an acceptance range for the Single Channel CPC results.
2.1 FLOW TRANSIENTS In Reference 1, the time-to-DNBR trip observed on the Single Channel CPC
[, ]exceededthemaximumallowabletriptimesasdeterminedbytheCPC Page 4
FORTRAN simulation code. Investigation showed the difference in trip times was due to the difference in I~
~~
by the two systems.
L a The results of the two modified FORTRAN test cases are as follows:
l Initial DNBR Initial LPD (KW/FT)
Case Min. Max. Min. Max.
DNBR Trip (Sec.) LPD Trip (Sec.)
Case Min. Max. Min. Max.
A new Single Channel CPC input disk was created incorporating the same
~
changesinthe([, .
l lwere rerun on the Single Channel CPC with the following results.
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Case Initial Initial DNBR LPD DNBR LPD Trip (sec) Trip (sec)
The Single Channel CPC results are in agreement with the FORTRAN simulation code results. It is concluded that no software errors were identified.
2.2 BOTH CEACS FAIL DtJRING BANK 6 DROP TRANSIENT t
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O
. .c 3.0 PHASE II TEST RESULTS
SUMMARY
All the test results from the Phase II testing have been evaluated and it is concluded no safety concern exists. The only discrepancy in the software implementation is related to the penalty factors when both CEACs -
, fail. Under these conditions, plant protection function of the CPC is maintained in the DNBR calculation, therefore the present software (Rev.
- 00) is acceptable for operation.
4.0 REFERENCES
- 1. Waterford 3, Cycle 1 CPC/CEAC Phase II Software Verification Test Report, CEN-208(C)-P, June 1982.
- 2. CPC Protection Algorithm Software Change Procedure, CEN-39(A)-P, Rev. 02, December 21, 1978.
- 3. Waterford-3 Cycle 1 CPC/CEAC Phase I Software Verification Test Report, CEN-209(C)-P, Rev. 00, June. 1982.
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,