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{{#Wiki_filter:WNP-2 SIMULATOR CERTIFICATION NRC FORM 474 SUPPORTING DOCUMENTATION WASHINGTON PUBLIC POWER SUPPLY SYSTEM DOCKET NO.50-397 DECEMBER 7, 1994 9501040182 941207 PDR ADOCK 05000397 P PDR NRC FORM 474 SUPPORTING DOCUMENTATION WNP-2 SIMULATOR CERTIFICATION WASHINGTON PUBLIC POWER SUPPLY SYSTEM 1.INTRODUCTION 1~1 Certification Approach 1.2 Simulator Application | {{#Wiki_filter:WNP-2 SIMULATOR CERTIFICATION NRC FORM 474 SUPPORTING DOCUMENTATION WASHINGTON PUBLIC POWER SUPPLY SYSTEM DOCKET NO.50-397 DECEMBER 7, 1994 9501040182 941207 PDR ADOCK 05000397 P PDR NRC FORM 474 SUPPORTING DOCUMENTATION WNP-2 SIMULATOR CERTIFICATION WASHINGTON PUBLIC POWER SUPPLY SYSTEM 1.INTRODUCTION 1~1 Certification Approach 1.2 Simulator Application | ||
~Pa e SIMULATOR INFORMATION | ~Pa e SIMULATOR INFORMATION 2.1 General Information 2.1.1 Owner/Operator/Manufacturer 2.1.2 Reference Plant/Fype/Rating 2.1.3 Date Available for Training 2.1.4 7ype of Certification Report 2.2 Control Room Physical Fidelity 2.2.1 Control Room Physical Arrangement 2.2.2 Panels&Equipment 2.2.3 Simulator Control Room Environment 2.2.4 Systems 2.3 Instructor Control Features 2.3.1 Initial Conditions 2.3.2 Malfunctions 2.3.3 Items Outside the Control Room 2.3.4 Additional Special Instructor ffraining Features 2.4 Operating Procedures for Reference Plant 3.SIMULATOR DESIGN DATA 3.1 Design Basis 3.2 Update Information 3.3 Simulator Discrepancy Resolution and Upgrading 4.PERFORMANCE VERIFICATION 4.1 Simulator Tests 4.1.1 Computer Real Time Verification 4.1.2 Normal Plant Evolutions 4.1.3 Steady State Operation 4.1.4 Transient Performance 4.1.5 Plant Malfunctions 4.2 Quadrennial Test Schedule 4.2.1 Annual Testing 4.2.2 Quadrennial Testing 10 0~. | ||
5.COMPLIANCE 5.1 10 CFR 55.45 Regulatory Requirements 5.2 Regulatory Guide 1.149 5.3 Exceptions to ANSI/ANS-3.5 (1985)5.3.1 Simulator Capabilities 5.3.2 Simulator Environment 5,3.3 Systems Simulated and the Degree of Completeness 5.3.4 Simulator Training Capabilities 5.3.5 Simulator Design Control 5.4 Upgrades and Corrections 12 13 APPENDIX A-SIMULATOR SCOPE DIAGRAMS A-1WNP-2 Simulator Scope APPENDIX B-SIMULATOR CRITICAL PARAMETERS B-1 Simulator Critical Parameters APPENDIX C-INSTRUCTOR INTERFACES C-1 Initial Conditions C-2 Local Operator Actions C-3 Malf'unctions C4 Component Level Failures APPENDIX D-SIMULATOR ACCEPTANCE TESTS D-1 ANSI/ANS-3.5 (1985)Requirements Versus Simulator Acceptance Tests D-2 Computer Spare Capacity Test Abstract D-3 Normal Plant Evolution Test Abstracts D-4 Steady State Operation Test Abstracts D-5 Transient Performance Test Abstracts D-6 Plant Malfunction Test Abstracts APPENDIX E-QUADRENNIAL TESTING E-1 Quadrennial Test Schedule e | |||
Information 2.1.1 Owner/Operator/Manufacturer | |||
Plant/Fype/Rating 2.1.3 Date Available for Training 2.1.4 7ype of Certification Report 2.2 Control Room Physical Fidelity 2.2.1 Control Room Physical Arrangement 2.2.2 Panels&Equipment 2.2.3 Simulator Control Room Environment | |||
2.3 Instructor Control Features 2.3.1 Initial Conditions | |||
2.3.3 Items Outside the Control Room 2.3.4 Additional Special Instructor ffraining Features 2.4 Operating Procedures for Reference Plant 3.SIMULATOR DESIGN DATA 3.1 Design Basis 3.2 Update Information | |||
Discrepancy Resolution and Upgrading 4.PERFORMANCE VERIFICATION | |||
Tests 4.1.1 Computer Real Time Verification | |||
Plant Evolutions | |||
State Operation 4.1.4 Transient Performance | |||
Malfunctions | |||
Test Schedule 4.2.1 Annual Testing 4.2.2 Quadrennial Testing 10 0~. | |||
5.COMPLIANCE 5.1 10 CFR 55.45 Regulatory Requirements | |||
Guide 1.149 5.3 Exceptions to ANSI/ANS-3.5 (1985)5.3.1 Simulator Capabilities | |||
Environment 5,3.3 Systems Simulated and the Degree of Completeness | |||
Training Capabilities | |||
Design Control 5.4 Upgrades and Corrections 12 13 APPENDIX A-SIMULATOR SCOPE DIAGRAMS A-1WNP-2 Simulator Scope APPENDIX B-SIMULATOR CRITICAL PARAMETERS B-1 Simulator Critical Parameters APPENDIX C-INSTRUCTOR INTERFACES C-1 Initial Conditions C-2 Local Operator Actions C-3 Malf'unctions C4 Component Level Failures APPENDIX D-SIMULATOR ACCEPTANCE TESTS D-1 ANSI/ANS-3.5 (1985)Requirements Versus Simulator Acceptance Tests D-2 Computer Spare Capacity Test Abstract D-3 Normal Plant Evolution Test Abstracts D-4 Steady State Operation Test Abstracts D-5 Transient Performance Test Abstracts D-6 Plant Malfunction Test Abstracts APPENDIX E-QUADRENNIAL TESTING E-1 Quadrennial Test Schedule e | |||
1.INTRODUCTION This report is submitted in accordance with Title 10, Code of Federal Regulations, part 55.45 and Regulatory Guide 1.149.The report provides the information prescribed by Appendix A of the American National Standards Institute/American Nuclear Society Standard, ANSI/ANS-3.5 (1985),"Nuclear Power Plant Simulators for Use in Operator Training". | 1.INTRODUCTION This report is submitted in accordance with Title 10, Code of Federal Regulations, part 55.45 and Regulatory Guide 1.149.The report provides the information prescribed by Appendix A of the American National Standards Institute/American Nuclear Society Standard, ANSI/ANS-3.5 (1985),"Nuclear Power Plant Simulators for Use in Operator Training". | ||
Its puxpose is to provide supporting documentation to substantiate our submittal of NRC Form 474"Simulation Facility Certification" for the Washington Public Power Supply System's (Supply System)Nuclear Plant No.2 (WNP-2)Operator Training Simulator. | Its puxpose is to provide supporting documentation to substantiate our submittal of NRC Form 474"Simulation Facility Certification" for the Washington Public Power Supply System's (Supply System)Nuclear Plant No.2 (WNP-2)Operator Training Simulator. | ||
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-these difFerences represent all exceptions for which priority has been established to correct the identified discrepancies. | -these difFerences represent all exceptions for which priority has been established to correct the identified discrepancies. | ||
The criterion for this category is that the exception requires correction to meet training or examination plans using this simulator. | The criterion for this category is that the exception requires correction to meet training or examination plans using this simulator. | ||
These discrepancies are planned for correction consistent with the requirements of 10 CFR 55.45 (b)(4)(i)1of13 | These discrepancies are planned for correction consistent with the requirements of 10 CFR 55.45 (b)(4)(i)1of13 1.2 Simulator Application The training program administrative procedures and technical support procedures ensure that licensee examinations and associated training are fully compliant with 10 CFR 55.45 requirements and associated guidelines. | ||
Application The training program administrative procedures and technical support procedures ensure that licensee examinations and associated training are fully compliant with 10 CFR 55.45 requirements and associated guidelines. | |||
The scope, design, and operation of the simulator are for the specific support of the training tasks used on the WNP-2 simulator for license operator training and testing.Simulator training is structured around scenarios'hat include clearly defined learning objectives based on job task analysis.Training materials based on those requirements are systematically compared to plant modifications, Licensee Event Reports;Significant Operating Experience Reports and changes to p'rocedures. | The scope, design, and operation of the simulator are for the specific support of the training tasks used on the WNP-2 simulator for license operator training and testing.Simulator training is structured around scenarios'hat include clearly defined learning objectives based on job task analysis.Training materials based on those requirements are systematically compared to plant modifications, Licensee Event Reports;Significant Operating Experience Reports and changes to p'rocedures. | ||
The simulator is intended to fully meet all known or anticipated requirements as well as'ubstantiate the Supply System's commitment to quality training.It is the Supply System's intent to fully support its training program by making the most effective use of the simulator. | The simulator is intended to fully meet all known or anticipated requirements as well as'ubstantiate the Supply System's commitment to quality training.It is the Supply System's intent to fully support its training program by making the most effective use of the simulator. | ||
2.0 SIMULATOR INFORMATION This section of the WNP-2 Simulator Certification provides general information about the WNP-2 replacement simulator and reference plant, summarizes the comparison made between the simulator and reference plant's physical attributes, instrumentation, and environment and discusses the available instructor interface features.The use of the reference plant's operating procedures in the simulator is also addressed. | |||
2.1 General Information The foHowing general information is provided as reference and for familiarization with the WNP-2 replacement simulator; 2.1.1 Owner/Operator/Manufacturer The WNP-2 simulator is owned and operated by the Washington Public Power Supply System, a municipal corporation and joint operating agency of the State of Washington. | |||
INFORMATION This section of the WNP-2 Simulator Certification provides general information about the WNP-2 replacement simulator and reference plant, summarizes the comparison made between the simulator and reference plant's physical attributes, instrumentation, and environment and discusses the available instructor interface features.The use of the reference plant's operating procedures in the simulator is also addressed. | |||
Information The foHowing general information is provided as reference and for familiarization with the WNP-2 replacement simulator; 2.1.1 Owner/Operator/Manufacturer The WNP-2 simulator is owned and operated by the Washington Public Power Supply System, a municipal corporation and joint operating agency of the State of Washington. | |||
The simulator is.located at the Supply System's Plant Support Facility, approximately one mile from the reference plant.The Supply System address is: 2 of 13 Washington Public Power Supply System P.O.Box 968 3000 George Washington Way Richland, WA 99352-0968 The WNP-2 simulator was manufactured by Westinghouse at their Monroeville Pennsylvania site.2.1.2 Reference Plant/Type/Rating The WNP-2 power generating station (plant)is the designated reference plant for the WNP-2 operator training simulator. | The simulator is.located at the Supply System's Plant Support Facility, approximately one mile from the reference plant.The Supply System address is: 2 of 13 Washington Public Power Supply System P.O.Box 968 3000 George Washington Way Richland, WA 99352-0968 The WNP-2 simulator was manufactured by Westinghouse at their Monroeville Pennsylvania site.2.1.2 Reference Plant/Type/Rating The WNP-2 power generating station (plant)is the designated reference plant for the WNP-2 operator training simulator. | ||
WNP-2 is a 1145 MWe/3323 MWt General Electric boiling water reactor (BWR-5)with a Mark H containment. | WNP-2 is a 1145 MWe/3323 MWt General Electric boiling water reactor (BWR-5)with a Mark H containment. | ||
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The identification of simulated panels is shown in Appendix A, Figure A-l,"WNP-2 Simulator Scope".The figure also provides equipment lists which identify major panels and items on panels included in the simulator's scope of simulation. | The identification of simulated panels is shown in Appendix A, Figure A-l,"WNP-2 Simulator Scope".The figure also provides equipment lists which identify major panels and items on panels included in the simulator's scope of simulation. | ||
3 of 13 The simulator has, for those panels in its current scope, retained a one-to-one relationship except as noted in the exceptions per Section 5 of this report.Those control room panels included in the simulator scope have been compared to the plant control room and an evaluation performed for training impact based on normal plant evolutions and for responding to malfunctions listed in ANSI/ANS 3.5 (1985)Section 3.1.2.Panels not included in the simulator were evaluated for impact to training.It is recognized that the physical scope of the simulator does not include all control room back panels.The area of back panel simulation required to support operator training relative to the use for all plant procedures as well as the trainees'bility to monitor all of the controls within the area of operator responsibility was addressed as part of tliis assessment. | 3 of 13 The simulator has, for those panels in its current scope, retained a one-to-one relationship except as noted in the exceptions per Section 5 of this report.Those control room panels included in the simulator scope have been compared to the plant control room and an evaluation performed for training impact based on normal plant evolutions and for responding to malfunctions listed in ANSI/ANS 3.5 (1985)Section 3.1.2.Panels not included in the simulator were evaluated for impact to training.It is recognized that the physical scope of the simulator does not include all control room back panels.The area of back panel simulation required to support operator training relative to the use for all plant procedures as well as the trainees'bility to monitor all of the controls within the area of operator responsibility was addressed as part of tliis assessment. | ||
2.2.2 Panels and Equipment Physical fidelity of the controls and simulated panels per ANSI/ANS 3.5 (1985)Section 3.2.2 has been verified against current photographs taken in October 1993 of actual panels in the WNP-2 control room.Design changes to the plant which physically affect the simulator have been identified in an ongoing process where changes which affect simulated panels and controls are classified as to their training impact.Differences between the simulator and the reference plant are evaluated, cataloged, entered and tracked in the simulator's Configuration Management System.2.2.3 Simulator Control Room Environment The verification of the simulator's fidelity to the WNP-2 control room included a comparison of the physical environment. | |||
and Equipment Physical fidelity of the controls and simulated panels per ANSI/ANS 3.5 (1985)Section 3.2.2 has been verified against current photographs taken in October 1993 of actual panels in the WNP-2 control room.Design changes to the plant which physically affect the simulator have been identified in an ongoing process where changes which affect simulated panels and controls are classified as to their training impact.Differences between the simulator and the reference plant are evaluated, cataloged, entered and tracked in the simulator's Configuration Management System.2.2.3 Simulator Control Room Environment The verification of the simulator's fidelity to the WNP-2 control room included a comparison of the physical environment. | |||
The comparison criteria includes color, console arrangement, physical furnishings, lighting as well as the audible background. | The comparison criteria includes color, console arrangement, physical furnishings, lighting as well as the audible background. | ||
Deficiencies in the category are assessed in the same manner for training impact.2.2.4 Systems The simulator provides a simulated system scope consistent with the scope of the panels and controls included in the simulator. | Deficiencies in the category are assessed in the same manner for training impact.2.2.4 Systems The simulator provides a simulated system scope consistent with the scope of the panels and controls included in the simulator. | ||
Certain systems which would not, by plant procedure, be observed and/or controlled by plant operators are not simulated or are simulated partially. | Certain systems which would not, by plant procedure, be observed and/or controlled by plant operators are not simulated or are simulated partially. | ||
Simulator performance testing has identified discrepancies in simulated systems responses which are are identified as items to be corrected.(See Section 3.3 for details)4of13 | Simulator performance testing has identified discrepancies in simulated systems responses which are are identified as items to be corrected.(See Section 3.3 for details)4of13 2.3 Instructor Control Features The WNP-2 instructor interface consists of instructor control and monitoring equipment located in an elevated station overlooking the simulator Hoor, The xoom permits viewing of the main simulator control area through tinted windows.Observation is further enhanced by use of audio/video equipment which provides the capability to recoxd activities at the panels.The current instructor station has a full set of features summarized as follows: 2.3.1 Initial Conditions The simulator can support one hundred twenty (120)IC's or"snapshots" of plant conditions. | ||
Control Features The WNP-2 instructor interface consists of instructor control and monitoring equipment located in an elevated station overlooking the simulator Hoor, The xoom permits viewing of the main simulator control area through tinted windows.Observation is further enhanced by use of audio/video equipment which provides the capability to recoxd activities at the panels.The current instructor station has a full set of features summarized as follows: 2.3.1 Initial Conditions The simulator can support one hundred twenty (120)IC's or"snapshots" of plant conditions. | |||
Thirty-five (35)IC's are reserved for training use and are password protected. | Thirty-five (35)IC's are reserved for training use and are password protected. | ||
An additional twenty-five (25)IC's are for general use and sixty (60)IC's are for use with the"backtrack" feature.The IC's include a variety of operating conditions and fission product poison concentrations. | An additional twenty-five (25)IC's are for general use and sixty (60)IC's are for use with the"backtrack" feature.The IC's include a variety of operating conditions and fission product poison concentrations. | ||
Attachment C-1 of Appendix C is a list of the current IC's used in the simulator. | Attachment C-1 of Appendix C is a list of the current IC's used in the simulator. | ||
2.3.2 Malfunctions Forty (40)malfunctions may be"active" or available for use in the simulator at any given time.Where operator actions are a function of the degree of severity of the malfunction, the malfunction has adjustable values and ramp times to final value of such a range to represent the plant malfunction condition. | |||
Forty (40)malfunctions may be"active" or available for use in the simulator at any given time.Where operator actions are a function of the degree of severity of the malfunction, the malfunction has adjustable values and ramp times to final value of such a range to represent the plant malfunction condition. | |||
Malfunctions may be activated as gxoups or individually. | Malfunctions may be activated as gxoups or individually. | ||
They can be activated by remote device, time delay trigger, console keyboard or by a combination of conditional simulator events called conditional triggers.These alternate approaches to initiate malfunctions effectively eliminate any cues to trainees that a malfunction has been introduced into the simulation. | They can be activated by remote device, time delay trigger, console keyboard or by a combination of conditional simulator events called conditional triggers.These alternate approaches to initiate malfunctions effectively eliminate any cues to trainees that a malfunction has been introduced into the simulation. | ||
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't Network.In addition the Emergency NRC communication phone system is installed. | 't Network.In addition the Emergency NRC communication phone system is installed. | ||
The simulator also includes remote and alternate remote shutdown panels, located separately from the simulator. | The simulator also includes remote and alternate remote shutdown panels, located separately from the simulator. | ||
5 of 13 | 5 of 13 2.3.4 Additional Special Instructor/Training Features The WNP-2 simulator includes capabilities to freeze simulation, run simulation in slower than real time, fast time, and backtrack. | ||
Special Instructor/Training Features The WNP-2 simulator includes capabilities to freeze simulation, run simulation in slower than real time, fast time, and backtrack. | |||
The"fast" function can be used to change the rate of xenon buildup or turbine warm-up by a factor from 1 to 10 times real time.Parameters identified for performance testing are obtainable in hard copy either as plots or printouts. | The"fast" function can be used to change the rate of xenon buildup or turbine warm-up by a factor from 1 to 10 times real time.Parameters identified for performance testing are obtainable in hard copy either as plots or printouts. | ||
Plots are available through either the Simulator Performance Verification System, at a resolution of up to model calculation rates, via Parameter Trending, and from a strip chart recorder, The instructor station also has the capability of alerting the instructor when an evolution has proceeded beyond the design limits of the plant.Selected parameters are monitored and when simulator operating limits are exceeded a message is provided to the instructor. | Plots are available through either the Simulator Performance Verification System, at a resolution of up to model calculation rates, via Parameter Trending, and from a strip chart recorder, The instructor station also has the capability of alerting the instructor when an evolution has proceeded beyond the design limits of the plant.Selected parameters are monitored and when simulator operating limits are exceeded a message is provided to the instructor. | ||
2.4 Operating Procedures for Reference Plant The procedures used in the simulator are controlled copies of the WNP-2 reference plant procedures. | |||
Procedures for Reference Plant The procedures used in the simulator are controlled copies of the WNP-2 reference plant procedures. | |||
All procedures and reference documentation in the simulator control room is maintained at the same revision level as available in the reference plant control room.Plant procedure deviations are implemented as they occur to ensure the Simulator procedures are identical to those utilized in WNP-2 Contxol Room.Simulator certification tests were conducted using revisions of procedures current to the date the tests were conducted. | All procedures and reference documentation in the simulator control room is maintained at the same revision level as available in the reference plant control room.Plant procedure deviations are implemented as they occur to ensure the Simulator procedures are identical to those utilized in WNP-2 Contxol Room.Simulator certification tests were conducted using revisions of procedures current to the date the tests were conducted. | ||
3.SIMULATOR DESIGN DATA The simulator's design configuration and performance are correlated to the reference plant control room's configuration and the plant's performance. | 3.SIMULATOR DESIGN DATA The simulator's design configuration and performance are correlated to the reference plant control room's configuration and the plant's performance. | ||
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6of13 This documentation includes computer software and model documentation, simulator hardware and physical configuration information, updated design data, and completed changes to the simulator. | 6of13 This documentation includes computer software and model documentation, simulator hardware and physical configuration information, updated design data, and completed changes to the simulator. | ||
These documents are controlled by the simulator organization. | These documents are controlled by the simulator organization. | ||
3.2 Update Information Modifications to plant configuration are reviewed for applicability to the simulator. | |||
Information Modifications to plant configuration are reviewed for applicability to the simulator. | |||
When changes occur in the plant configuration, they are reviewed for impact on simulator training and evaluation scenario's. | When changes occur in the plant configuration, they are reviewed for impact on simulator training and evaluation scenario's. | ||
The simulator's design basis is established, maintained, and tracked by use of the simulator's CMS.Design basis and update/status information is available through the CMS system.Documents identified in the CMS are available in hardcopy.3.3 Simulator Discrepancy Resolution and Upgrading The simulator fidelity will be maintained on the basis of evaluating plant change packages, determining the effect of the change on the conduct of training, incorporating changes where appropriate and then maintaining this change in the simulator's scope.Information about planned or implemented engineering changes to the plant is reviewed using established criteria and processes. | The simulator's design basis is established, maintained, and tracked by use of the simulator's CMS.Design basis and update/status information is available through the CMS system.Documents identified in the CMS are available in hardcopy.3.3 Simulator Discrepancy Resolution and Upgrading The simulator fidelity will be maintained on the basis of evaluating plant change packages, determining the effect of the change on the conduct of training, incorporating changes where appropriate and then maintaining this change in the simulator's scope.Information about planned or implemented engineering changes to the plant is reviewed using established criteria and processes. | ||
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These discrepancies have been either corrected and retested via the TR process in advance of this submittal or are represented by outstanding TR's.All outstanding TRs have been reviewed, assessed for resolution priority and are automatically tracked in the simulator's Configuration Management System..Outstanding Plant Changes not implemented into the simulator at the time of this certification submittal will be evaluated and incorporated into the simulator update design data base within 18 months, and the modification will be implemented within 12 months following the annual establishment of the simulator update design data, in accordance with ANSI/ANS 3.5 (1985)'items 5.2 and 5.3.7of13 4.PERFORMANCE VERIFICATION The entire set of tests described in this section were performed for this initial certification. | These discrepancies have been either corrected and retested via the TR process in advance of this submittal or are represented by outstanding TR's.All outstanding TRs have been reviewed, assessed for resolution priority and are automatically tracked in the simulator's Configuration Management System..Outstanding Plant Changes not implemented into the simulator at the time of this certification submittal will be evaluated and incorporated into the simulator update design data base within 18 months, and the modification will be implemented within 12 months following the annual establishment of the simulator update design data, in accordance with ANSI/ANS 3.5 (1985)'items 5.2 and 5.3.7of13 4.PERFORMANCE VERIFICATION The entire set of tests described in this section were performed for this initial certification. | ||
The simulator performance tests are divided into the four recommended categories in Appendix A of ANSI/ANS-3.5 (1985).This suggested format is followed with a further sub-division in the second of the categories: | The simulator performance tests are divided into the four recommended categories in Appendix A of ANSI/ANS-3.5 (1985).This suggested format is followed with a further sub-division in the second of the categories: | ||
(1)Computer Real-Time Verification (2)Steady State and Normal Operations a)Normal Plant Evolutions b)Steady State Operation (3)Transient Performance (4)Plant Malfunctions | (1)Computer Real-Time Verification (2)Steady State and Normal Operations a)Normal Plant Evolutions b)Steady State Operation (3)Transient Performance (4)Plant Malfunctions 4.1 Simulator Tests The performance tests conducted for certification were developed to address the specific requirements of ANSI/ANS-3.5 (1985).To assure that the tests provided adequate coverage of the requirements, a cross reference between the tests and requirements was prepared.This cross-index is provided as Attachment D-1 in Appendix D.Operational Review Summaries have been prepared for each of the tests conducted for this certification submittal. | ||
Tests The performance tests conducted for certification were developed to address the specific requirements of ANSI/ANS-3.5 (1985).To assure that the tests provided adequate coverage of the requirements, a cross reference between the tests and requirements was prepared.This cross-index is provided as Attachment D-1 in Appendix D.Operational Review Summaries have been prepared for each of the tests conducted for this certification submittal. | |||
These test abstracts provide a description of each test including a brief overview of the results.The test category, identification number and the test title is on each abstract as well as the initial and final condition of the test, Each Summary also briefly describes the simulator features tested, the source of evaluation data and test results.They are provided as Attachments D-2 through D-6 in Appendix D.Where appropriate, the performance tests selected for certification are supported by analysis data which includes the plant response recorded from specific events and evolutions, Power Ascension Testing, License Event Reports, Significant Operational Event Reports, engineering analyses, the WNP-2 Final Safety Analysis Report as well as other supporting information. | These test abstracts provide a description of each test including a brief overview of the results.The test category, identification number and the test title is on each abstract as well as the initial and final condition of the test, Each Summary also briefly describes the simulator features tested, the source of evaluation data and test results.They are provided as Attachments D-2 through D-6 in Appendix D.Where appropriate, the performance tests selected for certification are supported by analysis data which includes the plant response recorded from specific events and evolutions, Power Ascension Testing, License Event Reports, Significant Operational Event Reports, engineering analyses, the WNP-2 Final Safety Analysis Report as well as other supporting information. | ||
This baseline information is cross-indexed to test procedures and is available from the Configuration Management System (CMS)to Simulator and License Training personnel. | This baseline information is cross-indexed to test procedures and is available from the Configuration Management System (CMS)to Simulator and License Training personnel. | ||
The test results shown on the abstract are those which existed at the time of this certification report.All identified discrepancies from these performance tests have been evaluated for potential impact to simulator training and performance evaluations, 8 of 13 | The test results shown on the abstract are those which existed at the time of this certification report.All identified discrepancies from these performance tests have been evaluated for potential impact to simulator training and performance evaluations, 8 of 13 4.1.1 Computer Real Time Verification The simulator is monitored for real time operation through timing tests.Each of the computers in the simulator computer complex has total time execution per frame measured.The test has no effect on the simulation and runs as a background task.The simulator presently maintains acceptable real-time operation during the conduct of its assigned training and evaluation scenarios. | ||
Real Time Verification The simulator is monitored for real time operation through timing tests.Each of the computers in the simulator computer complex has total time execution per frame measured.The test has no effect on the simulation and runs as a background task.The simulator presently maintains acceptable real-time operation during the conduct of its assigned training and evaluation scenarios. | |||
This test is intended to verify ANSI/ANS-3.5 (1985)requirements for real-time operation. | This test is intended to verify ANSI/ANS-3.5 (1985)requirements for real-time operation. | ||
The abstract is provided as Attachment D-2 of Appendix D.4.1.2 Normal Plant Evolutions This series of tests demonstrates the simulator's ability to be operated over the full operating range from full power to cold shutdown and back to full power.The tests are based directly on WNP-2 operating pxocedures. | The abstract is provided as Attachment D-2 of Appendix D.4.1.2 Normal Plant Evolutions This series of tests demonstrates the simulator's ability to be operated over the full operating range from full power to cold shutdown and back to full power.The tests are based directly on WNP-2 operating pxocedures. | ||
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A listing of the Annual Tests is provided in Appendix E, Attachment E-l.4.2.2 Quadrennial Testing The tests that will be conducted in years one through four following the Supply System's submittal of Form 474 are identified, by year, in Appendix E.These schedules represent performance of approximately 25 percent of the total tests required for certification per year.Any deletions or changes in scope or to ANSI/ANS-3.5 (1985)acceptance criteria related to these tests will be addressed by the refiling of Form 474 to refiect changes in the Supply System's plans.A listing of Quadriennal Tests is provided in Appendix E, Attachment E-l.10 of 13 5.COMPLIANCE The following section summarizes the fidelity of the simulator with respect to the applicable requirements and the endorsed standard.The Supply System's certification submittal follows the recommended guidance of ANSI/ANS-3.5 (1985)Appendix A.The information here is intended to provide a sufficient basis to exhibit that simulator fidelity to the reference plant has been assessed and simulator performance has been verified.5.1 10 CFR 55.45 Regulatory Requirements The Supply System takes no exception to the requirements of 10 CFR 55.45-Operating Tests.5.2 Regulatory Guide 1.149 The Supply System has prepared its certification to conform to the regulatory direction of U.S.NRC Regulatory Guide 1.149-Nuclear Power Plant Simulation Facilities for Use in Operator License Examinations. | A listing of the Annual Tests is provided in Appendix E, Attachment E-l.4.2.2 Quadrennial Testing The tests that will be conducted in years one through four following the Supply System's submittal of Form 474 are identified, by year, in Appendix E.These schedules represent performance of approximately 25 percent of the total tests required for certification per year.Any deletions or changes in scope or to ANSI/ANS-3.5 (1985)acceptance criteria related to these tests will be addressed by the refiling of Form 474 to refiect changes in the Supply System's plans.A listing of Quadriennal Tests is provided in Appendix E, Attachment E-l.10 of 13 5.COMPLIANCE The following section summarizes the fidelity of the simulator with respect to the applicable requirements and the endorsed standard.The Supply System's certification submittal follows the recommended guidance of ANSI/ANS-3.5 (1985)Appendix A.The information here is intended to provide a sufficient basis to exhibit that simulator fidelity to the reference plant has been assessed and simulator performance has been verified.5.1 10 CFR 55.45 Regulatory Requirements The Supply System takes no exception to the requirements of 10 CFR 55.45-Operating Tests.5.2 Regulatory Guide 1.149 The Supply System has prepared its certification to conform to the regulatory direction of U.S.NRC Regulatory Guide 1.149-Nuclear Power Plant Simulation Facilities for Use in Operator License Examinations. | ||
As such it takes no exception to the specific guidance contained therein.The evaluations conducted in accordance with this guidance have documented a number of deficiencies with respect to the ANSI/ANS-3.5 (1985)Standard endorsed by Regulatory Guide 1.149.The following subsections provide a summary of the limitations of the current simulator to the certification requirements. | As such it takes no exception to the specific guidance contained therein.The evaluations conducted in accordance with this guidance have documented a number of deficiencies with respect to the ANSI/ANS-3.5 (1985)Standard endorsed by Regulatory Guide 1.149.The following subsections provide a summary of the limitations of the current simulator to the certification requirements. | ||
5.3 Exceptions to ANSI/ANS-3.5 (1985)Exceptions to ANSI/ANS-3.5 (1985)not planned to be corrected on the simulator are summarized here.The identified exceptions that significantly affect training are identified and tracked utilizing the simulator's Configuration Management System and Compensatory Training Tracking system.The following summary is provided to parallel applicable requirements of ANSI/ANS-3.5 (1985).5.3.1 Simulator Capabilities Simulator perfonnance has been established by the conduct of performance tests per ANSI/ANS-~~~~3.5 (1985)Section 5.4 Simulator Testing.These tests were performed and the results assessed using the guidance of Section 4.-Performance Criteria, of the Standard.11 of 13 5.3.2 Simulator Environment The degree of panel simulation is shown on Figure A-l,"WNP-2 Simulator Scope" in Appendix A.The simulated and partially simulated panels are shown as highlighted. | |||
to ANSI/ANS-3.5 (1985)Exceptions to ANSI/ANS-3.5 (1985)not planned to be corrected on the simulator are summarized here.The identified exceptions that significantly affect training are identified and tracked utilizing the simulator's Configuration Management System and Compensatory Training Tracking system.The following summary is provided to parallel applicable requirements of ANSI/ANS-3.5 (1985).5.3.1 Simulator Capabilities Simulator perfonnance has been established by the conduct of performance tests per ANSI/ANS-~~~~3.5 (1985)Section 5.4 Simulator Testing.These tests were performed and the results assessed using the guidance of Section 4.-Performance Criteria, of the Standard.11 of 13 | |||
Environment The degree of panel simulation is shown on Figure A-l,"WNP-2 Simulator Scope" in Appendix A.The simulated and partially simulated panels are shown as highlighted. | |||
The panels and panel sections not simulated were determined to have minor impact and did not need to be incorporated into the simulator, for one or more of the following reasons: operator actions on these panels are routine, or compensatory classroom or on-the-job training is utilized for panel manipulation instruction. | The panels and panel sections not simulated were determined to have minor impact and did not need to be incorporated into the simulator, for one or more of the following reasons: operator actions on these panels are routine, or compensatory classroom or on-the-job training is utilized for panel manipulation instruction. | ||
This information is available from the simulator CMS.A detailed comparison for each instrument and control on each simulator panel was made with each matching reference plant control room item.The simulator control room environment assessment identified no discrepancies that have significant training impact.5.39 Systems Simulated and the Degree of Completeness The systems included in the simulator and their functional range have been established by the capabilities required to support training and evaluations. | This information is available from the simulator CMS.A detailed comparison for each instrument and control on each simulator panel was made with each matching reference plant control room item.The simulator control room environment assessment identified no discrepancies that have significant training impact.5.39 Systems Simulated and the Degree of Completeness The systems included in the simulator and their functional range have been established by the capabilities required to support training and evaluations. | ||
As noted, the simulator provides a simulated system scope consistent with the scope of panel simulation. | As noted, the simulator provides a simulated system scope consistent with the scope of panel simulation. | ||
The degree of completeness of simulation necessary to perform the reference plant evolutions described in ANSI/ANS-3.5 (1985)Sections 3.1.1 (Normal Plant Evolutions) and 3.12 (Plant Malfunctions) has been assessed as part of the test program.5.3.4 Simulator Training Capabilities The current instructor station has aH the capabilities required by Section 3.4 of ANSI/ANS-3.5 (1985).Simulator Initial Conditions, Local Operator Actions, Malfunctions, and an overview of the scope of Component Level Failures are listed in Appendix C, items C-l, C-2, C-3, and C-4 respectively. | The degree of completeness of simulation necessary to perform the reference plant evolutions described in ANSI/ANS-3.5 (1985)Sections 3.1.1 (Normal Plant Evolutions) and 3.12 (Plant Malfunctions) has been assessed as part of the test program.5.3.4 Simulator Training Capabilities The current instructor station has aH the capabilities required by Section 3.4 of ANSI/ANS-3.5 (1985).Simulator Initial Conditions, Local Operator Actions, Malfunctions, and an overview of the scope of Component Level Failures are listed in Appendix C, items C-l, C-2, C-3, and C-4 respectively. | ||
5.3.5 Simulator Design Control The Supply System takes no exceptions to the requirements of Sections 5.1 Simulator Design Data and 5.2 Simulator Update Design Data of ANSI/ANS-3.5 (1985).The simulator's design information is controlled and maintained to provide for the correlation of the simulators physical configuration and performance to the reference plant.12 of 13 Outstanding plant changes not implemented into the simulator at the time of this certification submittal will be incorporated into the simulator update design data base within 18 months and the modification will be implemented within 12 months following the annual establishment of the simulator update design data, in accordance with ANS 3.5 (1985)items 5.2 and 5.3.Those Plant Modification Requests (PMR's)which are determined to impact scheduled training will have (TR's)written.These TR's will in turn be evaluated for Compensatory Training.requirements and documented via the CMS.PMR's may also be deferred and will not be implemented on simulator. | |||
Design Control The Supply System takes no exceptions to the requirements of Sections 5.1 Simulator Design Data and 5.2 Simulator Update Design Data of ANSI/ANS-3.5 (1985).The simulator's design information is controlled and maintained to provide for the correlation of the simulators physical configuration and performance to the reference plant.12 of 13 Outstanding plant changes not implemented into the simulator at the time of this certification submittal will be incorporated into the simulator update design data base within 18 months and the modification will be implemented within 12 months following the annual establishment of the simulator update design data, in accordance with ANS 3.5 (1985)items 5.2 and 5.3.Those Plant Modification Requests (PMR's)which are determined to impact scheduled training will have (TR's)written.These TR's will in turn be evaluated for Compensatory Training.requirements and documented via the CMS.PMR's may also be deferred and will not be implemented on simulator. | |||
Although having an impact on physical fidelity and/or training, either 1)require excessive resources or materials to implement and other training measures are used to compensate or 2)the PMR has minor or no impact on current or planned training.5.4 Upgrades and Corrections All outstanding TR's were evaluated for their impact in a manner similiar to that described above for PMR's.TR's are planned to be implemented as training schedules and priorities dictate.The priority for making these corrections will be determined based on the need to meet ongoing training requirements. | Although having an impact on physical fidelity and/or training, either 1)require excessive resources or materials to implement and other training measures are used to compensate or 2)the PMR has minor or no impact on current or planned training.5.4 Upgrades and Corrections All outstanding TR's were evaluated for their impact in a manner similiar to that described above for PMR's.TR's are planned to be implemented as training schedules and priorities dictate.The priority for making these corrections will be determined based on the need to meet ongoing training requirements. | ||
Open TR's include discrepancies identified f'rom certification testing and reviews.All TR's will be evaluated for compensatory training requirements and documented via the CMS.The identified compensatory training requirements will be approved with access provided to simulator instructors along with the paralleled administrative instructions for their use.13 of 13 | Open TR's include discrepancies identified f'rom certification testing and reviews.All TR's will be evaluated for compensatory training requirements and documented via the CMS.The identified compensatory training requirements will be approved with access provided to simulator instructors along with the paralleled administrative instructions for their use.13 of 13 | ||
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N.Process Transmitters (including radiation monitoring system detectors): | N.Process Transmitters (including radiation monitoring system detectors): | ||
1)Variable severity transmitter failure;transmitter output set equal to severity value in percent of span.If no severity value is entered, the transmitter output is frozen at the value in existence just prior to failure activation. | 1)Variable severity transmitter failure;transmitter output set equal to severity value in percent of span.If no severity value is entered, the transmitter output is frozen at the value in existence just prior to failure activation. | ||
2)Variable severity transmitter offset;transmitter output is offset from the process value by a constant percentage equal to the severity value (+or-)entered.O.Resistance temperature detectors (RTD): 1)Open circuit on the sensor (resistance element)side of the RTD.2)Variable severity transmitter onset;RTD output is ofFset from the process temperature value by a constant percentage equal to the severity value (+or-)entered.P.Process Loop Power Supplies: 1)Power supply output fails to zero volts, (open circuit)5of5 APPENDIX D WASHINGTON PUBLIC POWER SUPPLY SYSTEM SIMULATOR ACCEPTANCE TESTS Attachment D-1 ANSI/ANS-3.5 (1985)Requirements Versus Simulator Acceptance Test Procedures Attachment D-2 Computer Spare Capacity Test Abstract Attachment D-3 Normal Plant Evolutions Test Abstracts Attachment D-4 Steady State Operation Test Abstracts Attachment D-5 Transient Performance Test Abstracts Attachment D-6 Plant Malfunction Test Abstracts APPENDIX D ATTACHMENT D-1 WASHINGTON PUBLIC POWER SUPPLY SYSYTEM ANSI/ANS-3.5 (1985)REQUIREMENTS VERSUS SIMULATOR ACCEPTANCE TEST PROCEDURES General Requirements | 2)Variable severity transmitter offset;transmitter output is offset from the process value by a constant percentage equal to the severity value (+or-)entered.O.Resistance temperature detectors (RTD): 1)Open circuit on the sensor (resistance element)side of the RTD.2)Variable severity transmitter onset;RTD output is ofFset from the process temperature value by a constant percentage equal to the severity value (+or-)entered.P.Process Loop Power Supplies: 1)Power supply output fails to zero volts, (open circuit)5of5 APPENDIX D WASHINGTON PUBLIC POWER SUPPLY SYSTEM SIMULATOR ACCEPTANCE TESTS Attachment D-1 ANSI/ANS-3.5 (1985)Requirements Versus Simulator Acceptance Test Procedures Attachment D-2 Computer Spare Capacity Test Abstract Attachment D-3 Normal Plant Evolutions Test Abstracts Attachment D-4 Steady State Operation Test Abstracts Attachment D-5 Transient Performance Test Abstracts Attachment D-6 Plant Malfunction Test Abstracts APPENDIX D ATTACHMENT D-1 WASHINGTON PUBLIC POWER SUPPLY SYSYTEM ANSI/ANS-3.5 (1985)REQUIREMENTS VERSUS SIMULATOR ACCEPTANCE TEST PROCEDURES General Requirements 3.1 Simulator Capabilities 3.1.1 Normal Plant Evolutions 3.1.1(1)3.1.1(2)3.1.1(3)3.1.1(4)3.1.1(5)3.1.1(6)3.1.1(8)3.1.1(9)3.1.1(10)Plant Startup 14.4.7.1-Normal Plant Operations Nuclear Startup 14.4.7.2.1 | ||
Capabilities | |||
Plant Evolutions 3.1.1(1)3.1.1(2)3.1.1(3)3.1.1(4)3.1.1(5)3.1.1(6)3.1.1(8)3.1.1(9)3.1.1(10)Plant Startup 14.4.7.1-Normal Plant Operations Nuclear Startup 14.4.7.2.1 | |||
-Startup from Hot Shutdown to Rated Pressure Turbine Startup and Gen Synchronization 14.4.7.1-Normal Plant Operations Reactor SCRAM/Recovery to 100%Power 14.4.7.2.1 | -Startup from Hot Shutdown to Rated Pressure Turbine Startup and Gen Synchronization 14.4.7.1-Normal Plant Operations Reactor SCRAM/Recovery to 100%Power 14.4.7.2.1 | ||
-Startup from Hot Shutdown to Rated Pressure Operations at Hot Standby 14.4.7.2.3 | -Startup from Hot Shutdown to Rated Pressure Operations at Hot Standby 14.4.7.2.3 | ||
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INI'rlAL CONDITIONS: | INI'rlAL CONDITIONS: | ||
IC-14, Plant operating at 100%power or less.FINAL CONDITIONS: | IC-14, Plant operating at 100%power or less.FINAL CONDITIONS: | ||
IC-14, Plant operating at 100%power or less.SOURCE OF COMPARISON DATA: PLANT DATA SET g ENGINEERING EVALUATION FSAR SUER/LER OPERATIONAL ASSESSMENT | IC-14, Plant operating at 100%power or less.SOURCE OF COMPARISON DATA: PLANT DATA SET g ENGINEERING EVALUATION FSAR SUER/LER OPERATIONAL ASSESSMENT 5.5 Review TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES Z TEST RESULTS SATISFACI'ORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW | ||
TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES Z TEST RESULTS SATISFACI'ORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW | |||
==SUMMARY== | ==SUMMARY== | ||
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INITIAL CONDITIONS: | INITIAL CONDITIONS: | ||
N/A FINAL CONDITIONS: | N/A FINAL CONDITIONS: | ||
N/A SOURCE OF COMPARISON DATA: PLANT DATA SEI'ENGINEERING EVALUATION FSAR SOER/LER OPERATIONAL ASSESSMENT | N/A SOURCE OF COMPARISON DATA: PLANT DATA SEI'ENGINEERING EVALUATION FSAR SOER/LER OPERATIONAL ASSESSMENT 5.5 Review TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW | ||
TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW | |||
==SUMMARY== | ==SUMMARY== | ||
Revision as of 06:43, 6 May 2019
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| Issue date: | 12/07/1994 |
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Text
WNP-2 SIMULATOR CERTIFICATION NRC FORM 474 SUPPORTING DOCUMENTATION WASHINGTON PUBLIC POWER SUPPLY SYSTEM DOCKET NO.50-397 DECEMBER 7, 1994 9501040182 941207 PDR ADOCK 05000397 P PDR NRC FORM 474 SUPPORTING DOCUMENTATION WNP-2 SIMULATOR CERTIFICATION WASHINGTON PUBLIC POWER SUPPLY SYSTEM 1.INTRODUCTION 1~1 Certification Approach 1.2 Simulator Application
~Pa e SIMULATOR INFORMATION 2.1 General Information 2.1.1 Owner/Operator/Manufacturer 2.1.2 Reference Plant/Fype/Rating 2.1.3 Date Available for Training 2.1.4 7ype of Certification Report 2.2 Control Room Physical Fidelity 2.2.1 Control Room Physical Arrangement 2.2.2 Panels&Equipment 2.2.3 Simulator Control Room Environment 2.2.4 Systems 2.3 Instructor Control Features 2.3.1 Initial Conditions 2.3.2 Malfunctions 2.3.3 Items Outside the Control Room 2.3.4 Additional Special Instructor ffraining Features 2.4 Operating Procedures for Reference Plant 3.SIMULATOR DESIGN DATA 3.1 Design Basis 3.2 Update Information 3.3 Simulator Discrepancy Resolution and Upgrading 4.PERFORMANCE VERIFICATION 4.1 Simulator Tests 4.1.1 Computer Real Time Verification 4.1.2 Normal Plant Evolutions 4.1.3 Steady State Operation 4.1.4 Transient Performance 4.1.5 Plant Malfunctions 4.2 Quadrennial Test Schedule 4.2.1 Annual Testing 4.2.2 Quadrennial Testing 10 0~.
5.COMPLIANCE 5.1 10 CFR 55.45 Regulatory Requirements 5.2 Regulatory Guide 1.149 5.3 Exceptions to ANSI/ANS-3.5 (1985)5.3.1 Simulator Capabilities 5.3.2 Simulator Environment 5,3.3 Systems Simulated and the Degree of Completeness 5.3.4 Simulator Training Capabilities 5.3.5 Simulator Design Control 5.4 Upgrades and Corrections 12 13 APPENDIX A-SIMULATOR SCOPE DIAGRAMS A-1WNP-2 Simulator Scope APPENDIX B-SIMULATOR CRITICAL PARAMETERS B-1 Simulator Critical Parameters APPENDIX C-INSTRUCTOR INTERFACES C-1 Initial Conditions C-2 Local Operator Actions C-3 Malf'unctions C4 Component Level Failures APPENDIX D-SIMULATOR ACCEPTANCE TESTS D-1 ANSI/ANS-3.5 (1985)Requirements Versus Simulator Acceptance Tests D-2 Computer Spare Capacity Test Abstract D-3 Normal Plant Evolution Test Abstracts D-4 Steady State Operation Test Abstracts D-5 Transient Performance Test Abstracts D-6 Plant Malfunction Test Abstracts APPENDIX E-QUADRENNIAL TESTING E-1 Quadrennial Test Schedule e
1.INTRODUCTION This report is submitted in accordance with Title 10, Code of Federal Regulations, part 55.45 and Regulatory Guide 1.149.The report provides the information prescribed by Appendix A of the American National Standards Institute/American Nuclear Society Standard, ANSI/ANS-3.5 (1985),"Nuclear Power Plant Simulators for Use in Operator Training".
Its puxpose is to provide supporting documentation to substantiate our submittal of NRC Form 474"Simulation Facility Certification" for the Washington Public Power Supply System's (Supply System)Nuclear Plant No.2 (WNP-2)Operator Training Simulator.
The ANS 3.5 (1985)was used versus the ANS 3.5 (1993)due to the new standard not referenced by NUREG 1258, 10CFR55, nox Regulatory Guide 1.149.1.1 Certification Approach This certification submittal documents the performance of the WNP-2 simulatox to be placed in service January 1995 at the Supply System.The Training facility is a plant-referenced simulator designed to meet all known and anticipated requirements.
Its design documentation and configuration managed system will also permit the Supply System to maintain its fidelity to changes in the reference plant.The Supply System has recognized that its simulator has some limitations in its fidelity to the reference plant.These differences are delineated in this submittal.
The Supply System has assessed the impacts of these differences in meeting its training objectives and examinations requirements.
This has resulted in a continuing program of upgrades for differences that affect training.The Supply System has identified compensatory training xequixements for instances in which the simulator fidelity significantly impacts training or examination scenarios.
The diffexences in correlation between the simulator and reference plant were determined to be of two categories:
1.Exceptions to the ANSI/ANS-3.5 (1985)Standard-these differences are founded in the physical scope of the simulator haxdware and the range of simulated system operation.
2.Upgrades and Corrections
-these difFerences represent all exceptions for which priority has been established to correct the identified discrepancies.
The criterion for this category is that the exception requires correction to meet training or examination plans using this simulator.
These discrepancies are planned for correction consistent with the requirements of 10 CFR 55.45 (b)(4)(i)1of13 1.2 Simulator Application The training program administrative procedures and technical support procedures ensure that licensee examinations and associated training are fully compliant with 10 CFR 55.45 requirements and associated guidelines.
The scope, design, and operation of the simulator are for the specific support of the training tasks used on the WNP-2 simulator for license operator training and testing.Simulator training is structured around scenarios'hat include clearly defined learning objectives based on job task analysis.Training materials based on those requirements are systematically compared to plant modifications, Licensee Event Reports;Significant Operating Experience Reports and changes to p'rocedures.
The simulator is intended to fully meet all known or anticipated requirements as well as'ubstantiate the Supply System's commitment to quality training.It is the Supply System's intent to fully support its training program by making the most effective use of the simulator.
2.0 SIMULATOR INFORMATION This section of the WNP-2 Simulator Certification provides general information about the WNP-2 replacement simulator and reference plant, summarizes the comparison made between the simulator and reference plant's physical attributes, instrumentation, and environment and discusses the available instructor interface features.The use of the reference plant's operating procedures in the simulator is also addressed.
2.1 General Information The foHowing general information is provided as reference and for familiarization with the WNP-2 replacement simulator; 2.1.1 Owner/Operator/Manufacturer The WNP-2 simulator is owned and operated by the Washington Public Power Supply System, a municipal corporation and joint operating agency of the State of Washington.
The simulator is.located at the Supply System's Plant Support Facility, approximately one mile from the reference plant.The Supply System address is: 2 of 13 Washington Public Power Supply System P.O.Box 968 3000 George Washington Way Richland, WA 99352-0968 The WNP-2 simulator was manufactured by Westinghouse at their Monroeville Pennsylvania site.2.1.2 Reference Plant/Type/Rating The WNP-2 power generating station (plant)is the designated reference plant for the WNP-2 operator training simulator.
WNP-2 is a 1145 MWe/3323 MWt General Electric boiling water reactor (BWR-5)with a Mark H containment.
WNP-2 began commercial operations in December 1984.2.19 Date Available For Training The simulator will be available for operator training in January 1995.2.1.4 Type of Certification Report This is the initial Simulator Certification Report for the WNP-2 simulator, which is a plant-specific simulator for the WNP-2 power generating station.2.2 Control Room Physical Fidelity The WNP-2 simulator consists of a full scale replica of significant portions of the WNP-2 plant's main control room with f'ront panel devices fully functional.
This replica is driven by a computer complex such that the visual/audible characteristics of the plant control room are reproduced for a given operating condition.
The physical scope of the plant-referenced simulator was reviewed in accordance with Section 3.2 of ANSI/ANS 3.5-1985.2.2.1 Control Room Physical Arrangement The physical location of simulated panels as well as other control room equipment (e.g.desks and cabinets)was compared to the WNP-2 control room as part of this assessment.
The identification of simulated panels is shown in Appendix A, Figure A-l,"WNP-2 Simulator Scope".The figure also provides equipment lists which identify major panels and items on panels included in the simulator's scope of simulation.
3 of 13 The simulator has, for those panels in its current scope, retained a one-to-one relationship except as noted in the exceptions per Section 5 of this report.Those control room panels included in the simulator scope have been compared to the plant control room and an evaluation performed for training impact based on normal plant evolutions and for responding to malfunctions listed in ANSI/ANS 3.5 (1985)Section 3.1.2.Panels not included in the simulator were evaluated for impact to training.It is recognized that the physical scope of the simulator does not include all control room back panels.The area of back panel simulation required to support operator training relative to the use for all plant procedures as well as the trainees'bility to monitor all of the controls within the area of operator responsibility was addressed as part of tliis assessment.
2.2.2 Panels and Equipment Physical fidelity of the controls and simulated panels per ANSI/ANS 3.5 (1985)Section 3.2.2 has been verified against current photographs taken in October 1993 of actual panels in the WNP-2 control room.Design changes to the plant which physically affect the simulator have been identified in an ongoing process where changes which affect simulated panels and controls are classified as to their training impact.Differences between the simulator and the reference plant are evaluated, cataloged, entered and tracked in the simulator's Configuration Management System.2.2.3 Simulator Control Room Environment The verification of the simulator's fidelity to the WNP-2 control room included a comparison of the physical environment.
The comparison criteria includes color, console arrangement, physical furnishings, lighting as well as the audible background.
Deficiencies in the category are assessed in the same manner for training impact.2.2.4 Systems The simulator provides a simulated system scope consistent with the scope of the panels and controls included in the simulator.
Certain systems which would not, by plant procedure, be observed and/or controlled by plant operators are not simulated or are simulated partially.
Simulator performance testing has identified discrepancies in simulated systems responses which are are identified as items to be corrected.(See Section 3.3 for details)4of13 2.3 Instructor Control Features The WNP-2 instructor interface consists of instructor control and monitoring equipment located in an elevated station overlooking the simulator Hoor, The xoom permits viewing of the main simulator control area through tinted windows.Observation is further enhanced by use of audio/video equipment which provides the capability to recoxd activities at the panels.The current instructor station has a full set of features summarized as follows: 2.3.1 Initial Conditions The simulator can support one hundred twenty (120)IC's or"snapshots" of plant conditions.
Thirty-five (35)IC's are reserved for training use and are password protected.
An additional twenty-five (25)IC's are for general use and sixty (60)IC's are for use with the"backtrack" feature.The IC's include a variety of operating conditions and fission product poison concentrations.
Attachment C-1 of Appendix C is a list of the current IC's used in the simulator.
2.3.2 Malfunctions Forty (40)malfunctions may be"active" or available for use in the simulator at any given time.Where operator actions are a function of the degree of severity of the malfunction, the malfunction has adjustable values and ramp times to final value of such a range to represent the plant malfunction condition.
Malfunctions may be activated as gxoups or individually.
They can be activated by remote device, time delay trigger, console keyboard or by a combination of conditional simulator events called conditional triggers.These alternate approaches to initiate malfunctions effectively eliminate any cues to trainees that a malfunction has been introduced into the simulation.
All malfunctions are easily inserted, controlled, and removed using the available instructor station functions.
2.39 Items Outside the Control Room The simulator provides realism as required for training in selected operator interfaces to systems and components outside the control xoom.The simulator includes a communications system which allows instructoxs to communicate with trainees just as control room operators would communicate with equipment operators using telephones, radios and the Plant Communication
't Network.In addition the Emergency NRC communication phone system is installed.
The simulator also includes remote and alternate remote shutdown panels, located separately from the simulator.
5 of 13 2.3.4 Additional Special Instructor/Training Features The WNP-2 simulator includes capabilities to freeze simulation, run simulation in slower than real time, fast time, and backtrack.
The"fast" function can be used to change the rate of xenon buildup or turbine warm-up by a factor from 1 to 10 times real time.Parameters identified for performance testing are obtainable in hard copy either as plots or printouts.
Plots are available through either the Simulator Performance Verification System, at a resolution of up to model calculation rates, via Parameter Trending, and from a strip chart recorder, The instructor station also has the capability of alerting the instructor when an evolution has proceeded beyond the design limits of the plant.Selected parameters are monitored and when simulator operating limits are exceeded a message is provided to the instructor.
2.4 Operating Procedures for Reference Plant The procedures used in the simulator are controlled copies of the WNP-2 reference plant procedures.
All procedures and reference documentation in the simulator control room is maintained at the same revision level as available in the reference plant control room.Plant procedure deviations are implemented as they occur to ensure the Simulator procedures are identical to those utilized in WNP-2 Contxol Room.Simulator certification tests were conducted using revisions of procedures current to the date the tests were conducted.
3.SIMULATOR DESIGN DATA The simulator's design configuration and performance are correlated to the reference plant control room's configuration and the plant's performance.
The simulator's design is controlled, documented, and maintained in accordance with ANSI/ANS-3.5 (1985).This information is available via the simulator's Configuration Management System (CMS).3.1 Design Basis Information used as the basis for the simulator's design includes the WNP-2 refexence plant design documentation and simulator design documentation.
Reference plant design documentation includes all drawings, reports, manuals, calculations, test data and operating records which describe the reference plant configuration and performance.
These documents are controlled external to the simulator organization.
Simulator design documentation refiects the configuration of the simulator.
6of13 This documentation includes computer software and model documentation, simulator hardware and physical configuration information, updated design data, and completed changes to the simulator.
These documents are controlled by the simulator organization.
3.2 Update Information Modifications to plant configuration are reviewed for applicability to the simulator.
When changes occur in the plant configuration, they are reviewed for impact on simulator training and evaluation scenario's.
The simulator's design basis is established, maintained, and tracked by use of the simulator's CMS.Design basis and update/status information is available through the CMS system.Documents identified in the CMS are available in hardcopy.3.3 Simulator Discrepancy Resolution and Upgrading The simulator fidelity will be maintained on the basis of evaluating plant change packages, determining the effect of the change on the conduct of training, incorporating changes where appropriate and then maintaining this change in the simulator's scope.Information about planned or implemented engineering changes to the plant is reviewed using established criteria and processes.
Required modifications to the simulator are documented as Trouble Reports (TR's)and are used as the basis for all simulator updates and modification.
Other sources which may result in simulator TR's include feedback from students and instructors, certification testing, and external information, such as industry events.Outstanding TR's are prioritized and assigned for resolution.
Completed TR's are checked and validated, by testing.Each is initiated and processed through analysis, implementation and validation by established instructions.
The testing and validation program conducted in accordance with the simulator's certification also identified additional discrepancies.
These discrepancies have been either corrected and retested via the TR process in advance of this submittal or are represented by outstanding TR's.All outstanding TRs have been reviewed, assessed for resolution priority and are automatically tracked in the simulator's Configuration Management System..Outstanding Plant Changes not implemented into the simulator at the time of this certification submittal will be evaluated and incorporated into the simulator update design data base within 18 months, and the modification will be implemented within 12 months following the annual establishment of the simulator update design data, in accordance with ANSI/ANS 3.5 (1985)'items 5.2 and 5.3.7of13 4.PERFORMANCE VERIFICATION The entire set of tests described in this section were performed for this initial certification.
The simulator performance tests are divided into the four recommended categories in Appendix A of ANSI/ANS-3.5 (1985).This suggested format is followed with a further sub-division in the second of the categories:
(1)Computer Real-Time Verification (2)Steady State and Normal Operations a)Normal Plant Evolutions b)Steady State Operation (3)Transient Performance (4)Plant Malfunctions 4.1 Simulator Tests The performance tests conducted for certification were developed to address the specific requirements of ANSI/ANS-3.5 (1985).To assure that the tests provided adequate coverage of the requirements, a cross reference between the tests and requirements was prepared.This cross-index is provided as Attachment D-1 in Appendix D.Operational Review Summaries have been prepared for each of the tests conducted for this certification submittal.
These test abstracts provide a description of each test including a brief overview of the results.The test category, identification number and the test title is on each abstract as well as the initial and final condition of the test, Each Summary also briefly describes the simulator features tested, the source of evaluation data and test results.They are provided as Attachments D-2 through D-6 in Appendix D.Where appropriate, the performance tests selected for certification are supported by analysis data which includes the plant response recorded from specific events and evolutions, Power Ascension Testing, License Event Reports, Significant Operational Event Reports, engineering analyses, the WNP-2 Final Safety Analysis Report as well as other supporting information.
This baseline information is cross-indexed to test procedures and is available from the Configuration Management System (CMS)to Simulator and License Training personnel.
The test results shown on the abstract are those which existed at the time of this certification report.All identified discrepancies from these performance tests have been evaluated for potential impact to simulator training and performance evaluations, 8 of 13 4.1.1 Computer Real Time Verification The simulator is monitored for real time operation through timing tests.Each of the computers in the simulator computer complex has total time execution per frame measured.The test has no effect on the simulation and runs as a background task.The simulator presently maintains acceptable real-time operation during the conduct of its assigned training and evaluation scenarios.
This test is intended to verify ANSI/ANS-3.5 (1985)requirements for real-time operation.
The abstract is provided as Attachment D-2 of Appendix D.4.1.2 Normal Plant Evolutions This series of tests demonstrates the simulator's ability to be operated over the full operating range from full power to cold shutdown and back to full power.The tests are based directly on WNP-2 operating pxocedures.
All control board indications and alarms affected during the plant evolution are verified in the simulator.
These tests also verify the nuclear chaxactexistics of the simulated core model.The core's response is verified against the WNP-2 cycle 8 beginning of cycle core.Flux profiles, thermal performance and flux response to core flow were also verified.This set of tests addresses ANSI/ANS-3.5 (1985)section 3,1.1 (1)through 3.1.1 (10)Normal Plant Evolutions.
Attachment D-3 of Appendix D pxovides the abstracts for these tests.4.19 Steady State Operation The purpose of the tests in this category is to verify the accuracy of the simulator at steady state power levels.At various power levels, the energy balance is checked to determine that reactor power is consistent with turbine power and that there are no unknown energy losses in the simulation.
Heat balance performance is compared for key parameters as identified in ANSI/ANS-3.5 (1985)Appendix B 1.1 Steady State Performance.
Steady state stability is also verified here.Abstracts of test xesults are pxovided in Attachment D-4 of Appendix D.Additionally a listing of Simulator Critical Parameters evaluated during performance of Steady State Accuracy testing is provided in Attachment B-1 of Appendix B.4.1.4 Transient Performance
)This series of tests are to verify that the WNP-2 simulator performs in accordance with the criteria of ANSI/ANS-3.5 (1985)Appendix B 1.2 Transient Performance.
Transients are introduced into 9of13 a stable operating condition and the effects observed and recorded.Response of the simulator is verified to be consistent with the expected response of the plant under similar conditions.
Appendix D, Attachment D-5 pxovides abstxacts for these tests, 4.1.5 Plant Malfunctions This series of tests were performed to verify the proper response of the simulator to abnormal and emergency events.These tests are intended to verify the inherent plant response as predicted or known for the particular type of failuxe.The test procedures are written to specifically address each of the malfunctions listed per ANSI/A'NS-3.5 (1985)Sections 3.1.2 (1)thxough 3.1.2 (25).Appendix D, Attachment D-6 provides abstracts for these tests.4.2 Quadrennial Test Schedule Consistent with this certification, the Supply System will conduct continued testing in accordance with Regulatory Guide 1.149, Section C.5.Selected pexformance tests are planned annually and all others will be performed at the rate of 25%a year such that all are tested within the four year required time period.4.2.1 Annual Testing The tests that will be conducted annually following the submittal of Form 474 are identified in Appendix E.These tests are conducted annually as a baseline evaluation to ensure WNP-2 simulator performance will provide a consistent quality platform for Licensed Operator training and evaluations.
A listing of the Annual Tests is provided in Appendix E, Attachment E-l.4.2.2 Quadrennial Testing The tests that will be conducted in years one through four following the Supply System's submittal of Form 474 are identified, by year, in Appendix E.These schedules represent performance of approximately 25 percent of the total tests required for certification per year.Any deletions or changes in scope or to ANSI/ANS-3.5 (1985)acceptance criteria related to these tests will be addressed by the refiling of Form 474 to refiect changes in the Supply System's plans.A listing of Quadriennal Tests is provided in Appendix E, Attachment E-l.10 of 13 5.COMPLIANCE The following section summarizes the fidelity of the simulator with respect to the applicable requirements and the endorsed standard.The Supply System's certification submittal follows the recommended guidance of ANSI/ANS-3.5 (1985)Appendix A.The information here is intended to provide a sufficient basis to exhibit that simulator fidelity to the reference plant has been assessed and simulator performance has been verified.5.1 10 CFR 55.45 Regulatory Requirements The Supply System takes no exception to the requirements of 10 CFR 55.45-Operating Tests.5.2 Regulatory Guide 1.149 The Supply System has prepared its certification to conform to the regulatory direction of U.S.NRC Regulatory Guide 1.149-Nuclear Power Plant Simulation Facilities for Use in Operator License Examinations.
As such it takes no exception to the specific guidance contained therein.The evaluations conducted in accordance with this guidance have documented a number of deficiencies with respect to the ANSI/ANS-3.5 (1985)Standard endorsed by Regulatory Guide 1.149.The following subsections provide a summary of the limitations of the current simulator to the certification requirements.
5.3 Exceptions to ANSI/ANS-3.5 (1985)Exceptions to ANSI/ANS-3.5 (1985)not planned to be corrected on the simulator are summarized here.The identified exceptions that significantly affect training are identified and tracked utilizing the simulator's Configuration Management System and Compensatory Training Tracking system.The following summary is provided to parallel applicable requirements of ANSI/ANS-3.5 (1985).5.3.1 Simulator Capabilities Simulator perfonnance has been established by the conduct of performance tests per ANSI/ANS-~~~~3.5 (1985)Section 5.4 Simulator Testing.These tests were performed and the results assessed using the guidance of Section 4.-Performance Criteria, of the Standard.11 of 13 5.3.2 Simulator Environment The degree of panel simulation is shown on Figure A-l,"WNP-2 Simulator Scope" in Appendix A.The simulated and partially simulated panels are shown as highlighted.
The panels and panel sections not simulated were determined to have minor impact and did not need to be incorporated into the simulator, for one or more of the following reasons: operator actions on these panels are routine, or compensatory classroom or on-the-job training is utilized for panel manipulation instruction.
This information is available from the simulator CMS.A detailed comparison for each instrument and control on each simulator panel was made with each matching reference plant control room item.The simulator control room environment assessment identified no discrepancies that have significant training impact.5.39 Systems Simulated and the Degree of Completeness The systems included in the simulator and their functional range have been established by the capabilities required to support training and evaluations.
As noted, the simulator provides a simulated system scope consistent with the scope of panel simulation.
The degree of completeness of simulation necessary to perform the reference plant evolutions described in ANSI/ANS-3.5 (1985)Sections 3.1.1 (Normal Plant Evolutions) and 3.12 (Plant Malfunctions) has been assessed as part of the test program.5.3.4 Simulator Training Capabilities The current instructor station has aH the capabilities required by Section 3.4 of ANSI/ANS-3.5 (1985).Simulator Initial Conditions, Local Operator Actions, Malfunctions, and an overview of the scope of Component Level Failures are listed in Appendix C, items C-l, C-2, C-3, and C-4 respectively.
5.3.5 Simulator Design Control The Supply System takes no exceptions to the requirements of Sections 5.1 Simulator Design Data and 5.2 Simulator Update Design Data of ANSI/ANS-3.5 (1985).The simulator's design information is controlled and maintained to provide for the correlation of the simulators physical configuration and performance to the reference plant.12 of 13 Outstanding plant changes not implemented into the simulator at the time of this certification submittal will be incorporated into the simulator update design data base within 18 months and the modification will be implemented within 12 months following the annual establishment of the simulator update design data, in accordance with ANS 3.5 (1985)items 5.2 and 5.3.Those Plant Modification Requests (PMR's)which are determined to impact scheduled training will have (TR's)written.These TR's will in turn be evaluated for Compensatory Training.requirements and documented via the CMS.PMR's may also be deferred and will not be implemented on simulator.
Although having an impact on physical fidelity and/or training, either 1)require excessive resources or materials to implement and other training measures are used to compensate or 2)the PMR has minor or no impact on current or planned training.5.4 Upgrades and Corrections All outstanding TR's were evaluated for their impact in a manner similiar to that described above for PMR's.TR's are planned to be implemented as training schedules and priorities dictate.The priority for making these corrections will be determined based on the need to meet ongoing training requirements.
Open TR's include discrepancies identified f'rom certification testing and reviews.All TR's will be evaluated for compensatory training requirements and documented via the CMS.The identified compensatory training requirements will be approved with access provided to simulator instructors along with the paralleled administrative instructions for their use.13 of 13
APPENDIX A WASHINGTON PUBLIC POWER SUPPLY SYSTEM SIMULATOR SCOPE DIAGRAMS Figure A-1 WNP-2 Simulator Scope BD-RAD-22 a BD'Gl'BD'P-.P841 P842 BD'Y'D'V'835 F831 BD'T'832 BD-RAD-24 BD-RAD-23 BD'GIP P833-a ARC-A P82 BD'L BD'D'A CONS LE CMS Cp CMSCP BD'M'D'P'301 1401 BD'KII'D'R'D'H'D'J'828 00~P P811 P812 P818 P814'10'II I II I II F821 BD'N'827 F825 ooo]-P620B P628 P607B P607D g 522 51]g Q CO~'O Q K 0-CO]25]I-0 co aa MP 452 O o g P608 222 F824 BD W'620A P607A P607C P 607 E P607 P P627 F633 F611 a P609 P606 P1 P2 P3 F626 0250 P619 P622 P62 P618 a P642 P629 P628 F632 P623 P613 P 631 F673 P614 P604 P600 P625 P MP2 V24A 002 A2 VT4B MP1 A1 u.P612 P65 P672 (ATWS)FCP-2 RRE CONTROL PANEL'FCP'CP-1 FOP'D'S'601 DRWNG FILES SRO OPER.DESK VT2B RC-B ARC-B RC-2 e-Qg QERQQEIlQK TOUCH PAD DISPLAY CATH9DE RAY TUBE DISPLAY TOUCH PAD DISPLAY CATHODE RAY TUBE DISPLAY PPCRS COLOR GRAPHIC TERMINALS PPCRS ALARM PRINTERS REMOTE SHUTDOWN REMOTE SHUTDOWN RELAY CABINET RELAY CABINET RELAY CABINET RELAY CABINET RELAY CABINET LDDL C 750-GDS].T p C750-GDS1-CRT C70-GDS2-Tp C70GDS2-CRT VT2 TO VT5 PPCRS-A1&A2 H22.P100 C61-P001 ARC-A RC-1 RC-B ARC-B RC-2 3 659 R D SEQU C CO 0 S 8 C750-GD2 C750-MP1 C750.MP2 FRTP-1 BOARD'A'OARD'B'OARD'C'OARD'D'RAPHIC DISPLAY TERMINAL 2 MATRIX PRINTER MATRIX PRINTER RRE REMOTE TRANSFER PANEL BENCHBOARD BENCHBOARD BENCHBOARD TEMPERATURESCANNER BOA OGEN&RANS PRO E ON BOARD'H'OARD'J'OARD'KI'OARD
'Kll'OARD'L'OARD'M'OARD'N'OARD'P'OARD'R'OARD'S'OARD T BOARD'W'OARD'V'OARD'Y'OARD'Gl'NALOG)
IA OG]2%~NI]5h]'hzmQam CONTAINMENT VENT&PURGE CONTAINMENT MONITOR SYSTEM SGT TRAIN A&CAC DIV 1 SGT TRAIN B&CAC DIV 2 STRONG MOTION RECORDR/MET RECD TMU/COOLING TOWER SYSTEMS RCC/SW SYSTEMS CONTROL ROOM HVAC REACTOR/RADWASTE BLDG HVAC ISOLATION VALVE&STAT LT DSPLY FEEDER WTR&HTRBYPASS DSPLY MNSTREAM LEAKAGE CRNTL SYSTEM.CNTRLS.WETWELL MONITOR FEEDWATER HTR LVL CONTOL IDEKE P600 P601 P602 P603 P604 P606 P607 P608 P609 maze())(PROCESS RADIATION MONITORS BENCHBOARD BENCHBOARD BENCH BOARD PROCESS RADIATION MONITORS R PS-A/RADIATION MONITO TIP CONTROL&MONITOR POWER RANGE NEUTRON MONITOR TRIP SYSTEhl'A'pS I F611 TPJp SYSTEM B RPS PROC<<SI'U F612 OL POS D DIVISION 8 RHR PUMPS'BC'P618 F621 P622 P623 F625 F626 F627 F628 F629 F631 P632 P633 P634 P642 F650 P672 F673 RFT GOV 1A,B FCP FD ARS Cp-1301 Cp-1401.P REACTOR CORE ISOLATION COOLANT INBOARD ISOLATION VALVES OUTBOARD ISOLATION VALVES HIGH PRESSURE CORE SPRAY DIV.I FUEL POOL COOLING FPC-1 DIV.II FUEL POOL COOIJNG FPC-2 AUTOMTC DEPRESSURIZATION SYSTEM'A'IVISION I LPCI&RHR PUMP'A'UTOMTC DEPRESSURIZATION SYSTEM'B'IVISION I LEAK DETECTION RPS-B/RADIATION MOMTOR RECIRCULATION CONTROL DIVISION II LEAK DETECTION ATWS (AUTOMATIC TRIP WITHOUT SCRAM)OFF GAS AREA RADIATION MONITORING REACTOR FEED PUMP TURB CNTRL PNL RRE CONTROL PANEL BOARD RRE PROTECTION CABINET ALTERNATE REMOTE SHUTDOWN PANEL H2/02 MONITOR H2/02 MONITOR ANSTEC APERTURE CARO I F614 pROCE SS MISC.MONOITORS SHIFT MANAGER OFRCE+VTS RO OPER.DESK RO OPER.DESK F602 FRTP-1 C61-P001 H22.P100 Also Available on Aperture Card P603 ARS BD'C'800 BD'B'820 BD'A'840 GOY 1A GOY 1B LEGEND: PARTIAL PANEL SIMULATED FULL SCOPE SIMULATION Figure A-1 920436.2 DECEMBER 1994 2 l P APPENDIX B WASHINGTON PUBLIC POWER SUPPLY SYSTEM STEADY STATE OPERATlON Attachment B-1 Critical Parameter Listing APPENDIX B ATTACHMENT B-1 WASHINGTON PUBLIC POWER SUPPLY SYSTEM CRITICAL PARAMETERS LISTING~D~crigtjgn RPV FUEL ZONE APRM POWER CH A APRM POWER CH B APRM POWER CH C APRM POWER CH D APRM POWER CH E APRM POWER CH F GENERATOR LOAD IvMN TURB 1SI'TG PRESS TOTAL STEAM FLOW TOTAL FEED FLOW STEAM FLOW LINE A STEAM FLOW LINE B STEAM FLOW LINE C STEAM FLOW LINE D RPV NR LEVEL RPV WR LEVEL RPV WR LEVEL RP PRESSURE WR TOTAL CORE FLOW RECIRC LOOP A FLOW RECIRC LOOP B FLOW RECIRC LOOP A SUCT TEMP RECIRC LOOP B SUCI'TEMP DRYWELL PRESSURE NR DRYWELL PRESSURE NR DRYWELL PRESSURE WR DRYWELL PRESSURE WR DRYWELL AVE TEMP WR DRYWELL AVE TEMP WR SUPPRESSION POOL LVL WR SUPPRESSION POOL LVL WR w arne LMS:044A SNISAM'R(1)
SNISAMTR(2)
SNISAIvHR(3)
SNISAMTR(4)
SNISAIvKR(5)
SNISAMTR(6)
TG;00MW PMS:020B WFWCST WFWCFT PRF:803A PRF:803B PRF:803C PRF:803D PRF:004A BRRS51AR BRRS51BR PMS:005 WRRS 613 WNISFA(1)WNISFB(1)TRR:023A TRR:023B PCM:007 PCM:008 PCM:001 PCM:002 TPCNDSUM(1)
TPCNDSUM(2)
LCM:006A LCM:006B P evince MS-LR-615R APRM-LI-603A APRM-LI-603B APRM-LI-603 C APRM-LI-603 D APRM-LI-603 E APRM-LI-603 F DEH-RI-M06 MS-PI-20B RFW-FR-607R RFW-FR-607G RFW-FI-603A RFW-FI-603 B RFW-FI-603 C RFW-FI-603 D RFW-LR-608 MS-LRPR623A MS-LRPR623B RFW-PI-605 MS-FR-613R RRC-FR-614R RRC-FR-614G RRC-TR-650R RRC-TR-650G CMS-PR-1R CMS-PR-2R CMS-PR-1G CMS-PR-2G CMS-TR-5-110 CMS-TR-6-128 CMS-LR-3G CMS-LR-4R 1 of 3 APPENDIX B ATTACHMENT B-1 WASHINGTON PUBLIC POWER SUPPLY SYSTEM CRITICAL PARAMETERS LISTING~Descri rion SUPPRESSION POOL TEMP SUPPRESSION POOL TEMP SUPPRESSION POOL PRESS SUPPRESSION POOL PRESS CONDENSER VACUUM CONDENSER VACUUM CONDENSER VACUUM REACTOR PRESSURE NR AVION TURB GOV VLV POS MAIN TURB GOV VLV POS MAIN TURB GOV VLV POS MAIN TURB GOV VLV POS MAIN TURBINE SPEED RFP SPEED RFP SPEED RFP SUCT PRESSURE RFP SUCT PRESSURE RFP DISCH PRESSURE RFP DISCH PRESSURE CBP DISCH PRESSURE MAIN STEAM LINE RAD MAIN STEAM LINE RAD MAIN STEAM LINE RAD 1VL4dN STEAM LINE RAD MSIV VLV POSITION MSIV VLV POSITION MSIV VLV POSITION MSIV VLV POSITION MSIV VLV POSITION MSIV VLV POSITION MSIV VLV POSITION MSIV VLV POSITION Software Name TPCNI41R TPCNI43R PCM:004 PCM:003 PMS:008A PMS:008B PMS:008C PMS:808 RDEHGV(1)RDEHGV(2)RDEHGV(3)RDEHGV(4)MTG:00SD MFT:001A MFT:001B PCD:028A PCD:028B PRF:001A PRF:001B PCD:016 ERMS JMI(1)ERMS JMI(2)ERMS JMI(3)ERMS JMI(4)RMSH022A RMSH022B RMSH022C RMSH022D RMSH028A RMSH028B RMSH028C RMSH028D Device CMS-TI-41AR CMS-TI-43R CMS-PR-4R CMS-PR-3R MS-PI-8A MS-PI-8B MS-PI-8C MS-PR/FR-609 MS-V-GV/1 MS-V-GV/2 MS-V-GV/3 MS-V-GV/4 DEH-RI-M05 RFT-SI-1A RFT-SI-1B COND-PI-28A COND-PI-28B RFW-PI-1A RFW-PI-1B COND-PI-16 MS-RIS-601A MS-RIS-601B MS-RIS-601C MS-RIS-601D MS-V-22A MS-V-22B MS-V-22C MS-V-22D MS-V-28A MS-V-28B MS-V-28C MS-V-28D 2of3 APPENDIX B ATTACHMENT B-1 WASHINGTON PUBLIC POWER SUPPLY SYSTEM CRITICAL PARAMETERS LISTING~Descri tion SCRAM DISCH VOLUME SCRAM DISCH VOLUME SCRAM DISCH VOLUME SCRAM DISCH VOLUME RX BLDG VENT HI RAD RX BLDG VENT HI RAD RX BLDG VENT HI RAD RX BLDG VENT HI RAD Software Name LRD:012A LRD:P12B LRD:012C LRD:012D ERMSAPMI(2)
ERMSAPMI(3)
ERMSAPMI(4)
ERMSAPMI(5)
Device CRD-LI-601A CRD-LI-601B CRD-LI-601C CRD-LI-601D REA-RIS-609A REA-RIS-609B REA-RIS-609 C REA-RIS-609D 3of3
APPENDIX C WASHINGTON PUBLIC POWER SUPPLY SYSTEM INSTRUCTOR INTERFACES Attachment C-1 Simulator Initial Conditions Attachment C-2 Local Operator Actions Attachment C-3 Simulator Malfunctions Attachment C-4 Simulator Component Level Failures APPENDIX C Attachment C-1 WASHINGTON PUBLIC POWER SUPPLY SYSTEM SMULATOR INITIAL CONDITIONS IC 01 02 03 04 05 06 07 CORE AGE EOC BOC BOC BOC BOC BOC BOC (degf)150 150 150 340 480 535 RPV PRESS (psig)ATMOS ATMOS ATMOS ATMOS 100 920 POWER (%)SRM 1-2 1-2 1-2 1-2 DESCRIPTION Ready For Startup-XE Free Ready for Startup-XE Free 5 Rods Fm Critical Heatup In Progress Heatup In Progress Heatup In Progress Heatup In Progress 08 09 10 12 13 14 15 16 17 18 19 BOC TSAT BOC TSAT BOC BOC 350 BOC TSAT BOC TSAT BOC TSAT BOC TSAT BOC TSAT BOC TSAT BOC TSAT BOC TSAT PSAT PSAT PSAT PSAT PSAT PSAT PSAT PSAT PSAT 850 120 ATMOS 15 20 32 100 100 40 20 Turbine Ready To Latch Turbine@1800 RDY To SYNC Ready to Shift RFW-FCV-10A/8 Ready To Xfer RRP to 60HZ 100%Rod Line Q 50%Core Flow 100%Power/Flow 100%Equilibrium Power/Flow RDY To Xfer RRC Pumps to 15HZ S/D In Progress S/D In Progress-All Rods In C/D In Progress S/D Cooling In Progress 20 21 22 25 BOC BOC BOC BOC BOC MOC 520 280 260 100 100 800 32 ATMOS 20 ATMOS ATMOS S/U In Progress@PK Xenon Ready to Start S/D Cooling S/D Cooling In Progress-Low XE Ready To Start S/D Cooling Cold S/D-Most Systems Secured Cold S/D-Most Systems Secured Page 1 of2 APPENDIX C ATTACHMENT C-1 WASHINGTON PUBLIC POWER SUPPLY SYSTEM SMULATOR INITIAL CONDITIONS continued IC CORE TEMP RPV POWER AGE (d f)PRESS (%)(psig)DESCRIPTION 26 27 28 29 30 31 32 33 34 35 MOC 540 1000 EOC 100 ATMOS EOC 540 1000 EOC 125 ATMOS EOC TSAT-1000 EOC 120 ATMOS EOC TSAT 850 EOC 467 500 MOC 540 975 MOC 150 ATMOS 100 100-95 0 100%Equilibrium Power/Flow Cold S/D-Most Systems Secured 100%Equilibrium Power/Flow Refueling In Progress 105%Core Age-Coastdown 105%Core Age-Ready For S/U XE Free S/D In Progress-All Rods In S/D To HSD with MSIV's Closed Heatup In Progress Ready To Startup-XE Free Page 2 of 2 APPENDIX C ATTACHMENT C-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID CAC-001 CAC-002 CAC-003 CAC-004 CAS-001 CAS-002 CAS-003 CAS-004 CAS-005 CAS-006 CAS-007 CAS-008 CAS-009 CAS-010 CAS-011 CAS-012 CAS-013 CAS-014 CAS-015 CAS-016 CAS-017 CAS-018 CAS-019 CAS-020 CAS-021 CAS-022 CFW-001 CFW-002 CFW-003 CFW-004 CFW-005 CFW-006 CFW-007 CFW-008 CFW-009 CFW-010 CFW-011 CFW-012 CFW-013 CFW-014 CFW-015 CFW-016 CFW-017 SYSTEM CAC CAC CAC CAC CAS CAS CAS CAS CAS CAS CAS CAS CAS CAS CAS CAS CAS CAS CAS CAS CAS CAS CAS CAS CAS CAS CFW CFW CFW CFW CFW CFW CFW CFW CFW CFW CFW CFW CFW CFW CFW CFW CFW DESCRIPTION CAC-FN-1A 0/C RESET CAC-FN-1B 0/C RESET CAC-EHC-1A 0/C RESET CAC-EHC-1B 0/C RESET CAS-V-152 AIR ISOL TO SERV BLDG CAS-V-153 AIR ISOL TO TUR BLDG CAS-V-154 AIR ISOL TO TUR BLDG CAS-V-155 AIR ISOL TO RW BLDG CAS-V-151 AIR ISOL TO RX BLDG CAS-V-210 N2 ISOL TO VAC BKR AIR DRYER SELECT A/B CAS-V-97-55 CAS ISOL TO VAC BKR CAS-C-1A RESET CAS-C-1B RESET CAS-C-1C RESET SA-C-1 COMPRESSOR START/STOP CAS-C-1A 0/C RESET CAS-C-1B 0/C RESET CAS-C-1C 0/C RESET SA-C-1 0/C RESET CN-V-761A BYPASS FOR CN-SPV-61 CN-V-761B ISOL FOR CN-SPV-61 CN-V-761C ISOLATION BOTl LE CON.CN-V-765A BYPASS FOR CN-SPV-65 CN-V-765B ISOL FOR CN-SPV-65 CN-V-765C ISOL FOR BOTI'LE CON.COND-V-674 COND PCV-105 ISOL VLV COND-V-672 COND-PCV-105 BYP VLV COND-V-108 GS COND INLET VLV COND-V-154 GS COND OUTLET VLV COND-V-1062 FIRE WATER CROSS TIE COND-V-107A CND PMP 1A DISCH VLV COND-V-107B CND PMP 1B DISCH VLV COND-V-107C CND PMP 1C DISCH VLV COND-V-120A CND BST PMP DIS VLV COND-V-120B CND BST PMP DIS VLV COND-V-120C CND BST PMP DIS VLV COND-V-161A SS-EV-1A LCV BP VLV COND-V-161B SS-EV-1B LCV BP VLV COND-V-76 CND DEMIN BP VLV COND-V-12A CST-1A FILL VLV OPEN COND-V-12B CST-1B FILL VLV OPEN COND-V-131 CND-LCV-1A BP VLV November 16, 1994 Page 1 of 51 APPENDIX C ATTACHMENT C-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID CFW-018 CFW-019 CFW-020 CFW-021 CFW-022 CFW-023 CFW-024 CFW-025 CFW-027 CFW-028 CFW-029 CFW-030 CFW-031 CFW-032 CFW-033 CFW-034 CFW-035 CFW-036 CFW-037 CFW-038 CFW-039 CFW-040 CFW-041 CFW-042 CIA-001 CIA-002 CIA-003 CIA-004 CIA-005 CIA-006 CIA-007 CIA-008 CIA-009 CRD-001 CRD-002 CRD-003, CRD-004 CRD-005 CRD-006 CRD-007 CRD-008 CRD-009 CRD-010 SYSTEM CFW CFW CFW CFW CFW CFW CFW CFW CFW CFW CFW CFW CFW CFW CFW CFW CFW CFW CFW CFW CFW CFW CFW CFW CIA CIA CIA CIA CIA CIA CIA CIA CIA CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD DESCRIPTION COND-V-170 CND-LCV-1C BP VLV COND-V-612 CND-LCV-11 BP VLV COND-V-147A FW PMP 1A SUCl'LV COND-V-147B FW PMP 1B SUCT VLV COND-V-15A CST-A DISCH ISOL COND-V-15B CST-B DISCH ISOL COND-V-28 RHR C FLUSH CONN COND-P-3 RB COND SUPPLY PMP ON NUMBER OF DEMINERALIZERS AR-V-3A,3B,3C COND VAC BRKRS COND-P-1A 0/C RESET COND-P-1B 0/C RESET COND-P-1C 0/C RESET COND-P-3 0/C RESET COND-P-AOP1A 0/C RESET COND-P-AOP1B 0/C RESET COND-P-AOP1C 0/C RESET MD-M-1A 0/C RESET MD-M-1B 0/C RESET COND-V-9A COND-TK-1A ISOLATION COND-V-9B COND-TK-1B ISOLATION COND-P-2A 0/C RESET COND-P-2B 0/C RESET COND-P-2C 0/C RESET CIA-V-728 N2 INERT ISOL VLV REFILL REMOTE STAT 1A CIA-TK-20A REFILL REMOTE STAT 1B CIA-TK-20B CIA-V-104A N2 BOTI'LE DISCH CIA-V-104B N2 BOTI'LE DISCH CIA-V-740 SUP HDR DNSM BLEED ISO CIA-V-741 SUPPLY HDR BLEEDOFF CIA-V-739 SUP HDR UPSM BLEED ISO CAS-V-98-88 CAS SUPPLY TO CIA CRD-FCV-2A LOCAL VAR CTRL CRD-FCV-2B LOCAL VAR CIRL CRD-FCV-2A M/A SELECTOR SWITCH CRD-FCV-2B M/A SELECTOR SWITCH CRD-V-4 DRV WTR PRESS STA BYP CRD-V-13A P-1A SUCTION CRD-V-13B P-1B SUCTION CRD-V-14A P-1A DISCHARGE CRD-V-14B P-1B DISCHARGE CRD-V-20A DRV WTR FLTR 3A INLET November 16, 1994 Page 2 of 51 APPENDIX C ATTACHMENT C-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID CRD-011 CRD-012 CRD-013 CRD-014 CRD-015 CRD-016 CRD-017 CRD-018 CRD-019 CRD-020 CRD-021 CRD-022 CRD-023 CRD-024 CRD-025 CRD-026 CRD-027 CRD-028 CRD-029 CRD-030 CRD-031 CRD-032 CRD-033 CRD-034 CRD-035 CRD-036 CRD-037 CRD-038 CRD-039 CRD-040 CRD-041 CRD-042 CRD-043 CRD-044 CRD-045 CRD-046 CRD-047 CRD-048 CRD-049 CRD-050 CRD-051 CRD-052 CRD-053 SYSTEM CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD DESCRIPTION CRD-V-20B DRV WTR FLTR 3B INLET CRD-V-21A DRV WTR FLTR 3A OUTLET CRD-V-21B DRV WTR FLTR 3B OUTLET CRD-V-34 CHARGING WTR HDR ISOLET CRD-V-46A FCV-2A INLET ISOL VLV CRD-V-46B FCV-2B INLET ISOL VLV CRD-V-47A FCV-2A OUTLET ISOL VLV CRD-V-47B FCV-2B OUTLET ISOL VLV CRD-V-61 DRV WTR PRESS CNTRL OUT CRD-V-95 SCRAM AIR HDR ISOL VLV CRD-V-520 RWCU PMP MTR PURGE ISO CRD-V-114 PMP SUCT FTR 10A OUTLT CRD-V-115 PMP SUCT FTR 10A INLT CRD-V-116 PMP SUCI'TR 10B OUTLT CRD-V-117 PMP SUCT FLT 10B INLET CRD-V-729 PI-13 ISOLATION CRD-PI-13 VENT PLUG REMOVED CRD-V-102 CR 1803 WD LINE VENT CRD-V-102 CR 2203 WD LINE VENT CRD-V-102 CR 2603 WD LINE VENT CRD-V-102 CR 3003 WD LINE VENT CRD-V-102 CR 3403 WD LINE VENT CRD-V-102 CR 3803 WD LINE VENT CRD-V-102 CR 4203 WD LINE VENT CRD-V-102 CR 1407 WD LINE VENT CRD-V-102 CR 1807 WD LINE VENT CRD-V-102 CR 2207 WD LINE VENT CRD-V-102 CR 2607 WD LINE VENT CRD-V-102 CR 3007 WD LINE VENT CRD-V-102 CR 3407 WD LINE VENT CRD-V-102 CR 3807 WD LINE VENT CRD-V-102 CR 4207 WD LINE VENT CRD-V-102 CR 4607 WD LINE VENT CRD-V-102 CR 1011 WD LINE VENT CRD-V-102 CR 1411 WD LINE VENT CRD-V-102 CR 1811 WD LINE VENT CRD-V-102 CR 2211 WD LINE VENT CRD-V-102 CR 2611 WD LINE VENT CRD-V-102 CR 3011 WD LINE VENT CRD-V-102 CR 3411 WD LINE VENT CRD-V-102 CR 3811 WD LINE VENT CRD-V-102 CR 4211 WD LINE VENT CRD-V-102 CR 4611 WD LINE VENT November 16, 1994 Page 3 of 51
APPENDIX C ATTACHMENT C-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID CRD-054 CRD-055 CRD-056 CRD-057 CRD-058 CRD-059 CRD-060 CRD-061 CRD-062 CRD-063 CRD-064 CRD-065 CRD-066 CRD-067 CRD-068 CRD-069 CRD-070 CRD-071 CRD-072 CRD-073 CRD-074 CRD-075 CRD-076 CRD-077 CRD-078 CRD-079 CRD-080 CRD-081 CRD-082 CRD-083 CRD-084 CRD-085 CRD-086 CRD-087 CRD-088 CRD-089 CRD-090 CRD-091 CRD-092 CRD-093 CRD-094 CRD-095 CRD-096 SYSTEM CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD DESCRIPTION CRD-V-102 CR 5011 WD LINE VENT CRD-V-102 CR 0615 WD LINE VENT CRD-V-102 CR 1015 WD LINE VENT CRD-V-102 CR 1415 WD LINE VENT CRD-V-102 CR 1815 WD LINE VENT CRD-V-102 CR 2215 WD LINE VENT CRD-V-102 CR 2615 WD LINE VENT CRD-V-102 CR 3015 WD LINE VENT CRD-V-102 CR 3415 WD LINE VENT CRD-V-102 CR 3815 WD LINE VENT CRD-V-102 CR 4215 WD LINE VENT CRD-V-102 CR 4615 WD LINE VENT CRD-V-102 CR 5015 WD LINE VENT CRD-V-102 CR 5415 WD LINE VENT CRD-V-102 CR 0219 WD LINE VENT CRD-V-102 CR 0619 WD LINE VENT CRD-V-102 CR 1019 WD LINE VENT CRD-V-102 CR 1419 WD LINE VENT CRD-V-102 CR 1819 WD LINE VENT CRD-V-102 CR 2219 WD LINE VENT CRD-V-102 CR 2619 WD LINE VENT CRD-V-102 CR 3019 WD LINE VENT CRD-V-102 CR 3419 WD LINE VENT CRD-V-102 CR 3819 WD LINE VENT CRD-V-102 CR 4219 WD LINE VENT CRD-V-102 CR 4619 WD LINE VENT CRD-V-102 CR 5019 WD LINE VENT CRD-V-102 CR 5419 WD LINE VENT CRD-V-102 CR 5819 WD LINE VENT CRD-V-102 CR 0223 WD LINE VENT CRD-V-102 CR 0623 WD LINE VENT CRD-V-102 CR 1023 WD LINE VENT CRD-V-102 CR 1423 WD LINE VENT CRD-V-102 CR 1823 WD LINE VENT CRD-V-102 CR 2223 WD LINE VENT CRD-V-102 CR 2623 WD LINE VENT CRD-V-102 CR 3023 WD LINE VENT CRD-V-102 CR 3423 WD LINE VENT CRD-V-102 CR 3823 WD LINE VENT CRD-V-102 CR 4223 WD LINE VENT CRD-V-102 CR 4623 WD LINE VENT CRD-V-102 CR 5023 WD LINE VENT CRD-V-102 CR 5423 WD LINE VENT November 16, 1994 Page 4 of 51 APPENDIX C ATTACHMENT C-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID CRD-097 CRD-098 CRD-099 CRD-100 CRD-101 CRD-102 CRD-103 CRD-104 CRD-105 CRD-106 CRD-107 CRD-108 CRD-109 CRD-110 CRD-111 CRD-112 CRD-113 CRD-114 CRD-115 CRD-116 CRD-117 CRD-118 CRD-119 CRD-120 CRD-121 CRD-122 CRD-123 CRD-124 CRD-125 CRD-126 CRD-127 CRD-128 CRD-129 CRD-130 CRD-131 CRD-132 CRD-133 CRD-134 CRD-135 CRD-136 CRD-137 CRD-138 CRD-139 SYSTEM CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD DESCRIPTION CRD-V-102 CR 5823 WD LINE VENT CRD-V-102 CR 0227 WD LINE VENT CRD-V-102 CR 0627 WD LINE VENT CRD-V-102 CR 1027 WD LINE VENT CRD-V-102 CR 1427 WD LINE VENT CRD-V-102 CR 1827 WD LINE VENT CRD-V-102 CR 2227 WD LINE VENT CRD-V-102 CR 2627 WD LINE VENT CRD-V-102 CR 3027 WD LINE VENT CRD-V-102 CR 3427 WD LINE VENT CRD-V-102 CR 3827 WD LINE VENT CRD-V-102 CR 4227 WD LINE VENT CRD-V-102 CR 4627 WD LINE VENT CRD-V-102 CR 5027 WD LINE VENT CRD-V-102 CR 5427 WD LINE VENT CRD-V-102 CR 5827 WD LINE VENT CRD-V-102 CR 0231 WD LINE VENT CRD-V-102 CR 0631 WD LINE VENT CRD-V-102 CR 1031 WD LINE VENT CRD-V-102 CR 1431 WD LINE VENT CRD-V-102 CR 1831 WD LINE VENT CRD-V-102 CR 2231 WD LINE VENT CRD-V-102 CR 2631 WD LINE VENT CRD-V-102 CR 3031 WD LINE VENT CRD-V-102 CR 3431 WD LINE VENT CRD-V-102 CR 3831 WD LINE VENT CRD-V-102 CR 4231 WD LINE VENT CRD-V-102 CR 4631 WD LINE VENT CRD-V-102 CR 5031 WD LINE VENT CRD-V-102 CR 5431 WD LINE VENT CRD-V-102 CR 5831 WD LINE VENT CRD-V-102 CR 0235 WD LINE VENT CRD-V-102 CR 0635 WD LINE VENT CRD-V-102 CR 1035 WD LINE VENT CRD-V-102 CR 1435 WD LINE VENT CRD-V-102 CR 1835 WD LINE VENT CRD-V-102 CR 2235 WD LINE VENT CRD-V-102 CR 2635 WD LINE VENT, CRD-V-102 CR 3035 WD LINE VENT CRD-V-102 CR 3435 WD LINE VENT CRD-V-102 CR 3835 WD LINE VENT CRD-V-102 CR 4235 WD LINE VENT CRD-V-102 CR 4635 WD LINE VENT November 16, 1994 Page 5 of 51 APPENDIX C ATTACHMENT C-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID CRD-140 CRD-141 CRD-142 CRD-143 CRD-144 CRD-145 CRD-146 CRD-147 CRD-148 CRD-149 CRD-150 CRD-151 CRD-152 CRD-153 CRD-154 CRD-155 CRD-156 CRD-157 CRD-158 CRD-159 CRD-160 CRD-161 CRD-162 CRD-163 CRD-164 CRD-165 CRD-166 CRD-167 CRD-168 CRD-169 CRD-170 CRD-171 CRD-172 CRD-173 CRD-174 CRD-175 CRD-176 CRD-177 CRD-178 CRD-179 CRD-180 CRD-181 CRD-182 SYSTEM CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD DESCRIPTION CRD-V-102 CR 5035 WD LINE VENT CRD-V-102 CR 5435 WD LINE VENT CRD-V-102 CR 5835 WD LINE VENT CRD-V-102 CR 0239 WD LINE VENT CRD-V-102 CR 0639 WD LINE VENT CRD-V-102 CR 1039 WD LINE VENT CRD-V-102 CR 1439 WD LINE VENT CRD-V-102 CR 1839 WD LINE VENT CRD-V-102 CR 2239 WD LINE VENT CRD-V-102 CR 2639 WD LINE VENT CRD-V-102 CR 3039 WD LINE VENT CRD-V-102 CR 3439 WD LINE VENT CRD-V-102 CR 3839 WD LINE VENT CRD-V-102 CR 4239 WD LINE VENT'RD-V-102 CR 4639 WD LINE VENT CRD-V-102 CR 5039 WD LINE VENT CRD-V-102 CR 5439 WD LINE VENT CRD-V-102 CR 5839 WD LINE VENT CRD-V-102 CR 0243 WD LINE VENT CRD-V-102 CR 0643 WD LINE VENT CRD-V-102 CR 1043 WD LINE VENT CRD-V-102 CR 1443 WD LINE VENT CRD-V-102 CR 1843 WD LINE VENT CRD-V-102 CR 2243 WD LINE VENT CRD-V-102 CR 2643 WD LINE VENT CRD-V-102 CR 3043 WD LINE VENT CRD-V-102 CR 3443 WD LINE VENT CRD-V-102 CR 3843 WD LINE VENT CRD-V-102 CR 4243 WD LINE VENT CRD-V-102 CR 4643 WD LINE VENT CRD-V-102 CR 5043 WD LINE VENT CRD-V-102 CR 5443 WD LINE VENT CRD-V-102 CR 5843 WD LINE VENT CRD-V-102 CR 0647 WD LINE VENT CRD-V-102 CR 1047 WD LINE VENT CRD-V-102 CR 1447 WD LINE VENT CRD-V-102 CR 1847 WD LINE VENT CRD-V-102 CR 2247 WD LINE VENT CRD-V-102 CR 2647 WD LINE VENT CRD-V-102 CR 3047, WD LINE VENT CRD-V-102 CR 3447 WD LINE VENT CRD-V-102 CR 3847 WD LINE VENT CRD-V-102 CR 4247 WD LINE VENT November 16, 1994 Page 6 of 51 APPENDIX C ATTACHMENT C-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACHONS LISTING ID CRD-183 CRD-184 CRD-185 CRD-186 CRD-187 CRD-188 CRD-189 CRD-190 CRD-191 CRD-192 CRD-193 CRD-194 CRD-195 CRD-196 CRD-197 CRD-198 CRD-199 CRD-200 CRD-201 CRD-202 CRD-203 CRD-204 CRD-205 CRD-206 CRD-207 CRD-208 CRD-209 CRD-210 CRD-211 CRD-212 CRD-213 CRD-214 CRD-215 CRD-216 CRD-217 CRD-218 CRD-219 CRD-220 CRD-221 CRD-222 CRD-223 CRD-224 CRD-225 SYSTEM CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD DESCRIPTION CRD-V-102 CR 4647 WD LINE VENT CRD-V-102 CR 5047 WD LINE VENT CRD-V-102 CR 5447 WD LINE VENT CRD-V-102 CR 1051 WD LINE VENT CRD-V-102 CR 1451 WD LINE VENT CRD-V-102 CR 1851 WD LINE VENT CRD-V-102 CR 2251 WD LINE VENT CRD-V-102 CR 2651 WD LINE VENT CRD-V-102 CR 3051 WD LINE VENT CRD-V-102 CR 3451 WD LINE VENT CRD-V-102 CR 3851 WD LINE VENT CRD-V-102 CR 4251 WD LINE VENT CRD-V-,102 CR 4651'WD LINE VENT CRD-V-102 CR 5051 WD LINE VENT CRD-V-102 CR 1455 WD LINE VENT CRD-V-102 CR 1855 WD LINE VENT CRD-V-102 CR 2255 WD LINE VENT CRD-V-102 CR 2655 WD LINE VENT CRD-V-102 CR 3055 WD LINE VENT CRD-V-102 CR 3455 WD LINE VENT CRD-V-102 CR 3855 WD LINE VENT CRD-V-102 CR 4255 WD LINE VENT CRD-V-102 CR 4655 WD LINE VENT CRD-V-102 CR 1859 WD LINE VENT CRD-V-102 CR 2259 WD LINE VENT CRD-V-102 CR 2659 WD LINE VENT CRD-V-102 CR 3059 WD LINE VENT CRD-V-102 CR 3459 WD LINE VENT CRD-V-102 CR 3859 WD LINE VENT CRD-V-102 CR 4259 WD LINE VENT CRD-V-101 CR 1803 HCU INSERT ISO CRD-V-101 CR 2203 HCU INSERT ISO CRD-V-101 CR 2603 HCU INSERT ISO CRD-V-101 CR 3003 HCU INSERT ISO CRD-V-101 CR 3403 HCU INSERT ISO CRD-V-101 CR 3803 HCU INSERT ISO CRD-V-101 CR 4203 HCU INSERT ISO CRD-V-101 CR 1407 HCU INSERT ISO CRD-V-101 CR 1807 HCU INSERT ISO CRD-V-101 CR 2207 HCU INSERT ISO CRD-V-101 CR 2607 HCU INSERT ISO CRD-V-101 CR 3007 HCU INSERT ISO CRD-V-101 CR 3407 HCU INSERT ISO November 16, 1994 Page 7 of 51 APPENDIX C ATTACHMENT C-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID CRD-226 CRD-227 CRD-228 CRD-229 CRD-230 CRD-231 CRD-232 CRD-233 CRD-234 CRD-235 CRD-236 CRD-237 CRD-238 CRD-239 CRD-240 CRD-241 CRD-242 CRD-243 CRD-244'RD-245 CRD-246 CRD-247 CRD-&8 CRD-249 CRD-250 CRD-251 CRD-252 CRD-253 CRD-254 CRD-255 CRD-256 CRD-257 CRD-258 CRD-259 CRD-260 CRD-261 CRD-262 CRD-263 CRD-264 CRD-265 CRD-266 CRD-267 CRD-268 SYSTEM CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD DESCRIPTION CRD-V-101 CR 3807 HCU INSERT ISO CRD-V-101 CR 4207 HCU INSERT ISO CRD-V-101 CR 4607 HCU INSERT ISO CRD-V-101 CR 1011 HCU INSERT ISOCRD-V-101 CR 1411 HCU INSERT ISO CRD-V-101 CR 1811 HCU INSERT ISO CRD-V-101 CR 2211 HCU INSERT ISO CRD-V-101 CR 2611 HCU INSERT ISO CRD-V-101 CR 3011 HCU INSERT ISO CRD-V-101 CR 3411 HCU INSERT ISO CRD-V-101 CR 3811 HCU INSERT ISO CRD-V-101 CR 4211 HCU INSERT ISO CRD-V-101 CR 4611 HCU INSERT ISO CRD-V-'101 CR 5011 HCU INSERT ISO CRD-V-101 CR 0615 HCU INSERT ISO CRD-V-101 CR 1015 HCU INSERT ISO CRD-V-101 CR 1415 HCU INSERT ISO CRD-V-101 CR 1815 HCU INSERT ISO CRD-V-101 CR 2215 HCU INSERT ISO CRD-V-101 CR 2615 HCU INSERT ISO CRD-V-101 CR 3015 HCU INSERT ISO CRD-V-101 CR 3415 HCU INSERT ISO CRD-V-101 CR 3815 HCU INSERT ISO CRD-V-101 CR 4215 HCU INSERT ISO CRD-V-101 CR 4615 HCU INSERT ISO CRD-V-101 CR 5015 HCU INSERT ISO CRD-V-101 CR 5415 HCU INSERT ISO CRD-V-101 CR 0219 HCU INSERT ISO CRD-V-101 CR 0619 HCU INSERT ISO CRD-V-101 CR 1019 HCU INSERT ISO CRD-V-101 CR 1419 HCU INSERT ISO CRD-V-101 CR 1819 HCU INSERT ISO CRD-V-'101 CR 2219 HCU INSERT ISO CRD-V-101 CR 2619 HCU INSERT ISO CRD-V-101 CR 3019 HCU INSERT ISO CRD-V-101 CR 3419 HCU INSERT ISO CRD-V-101 CR 3819 HCU INSERT ISO CRD-V-101 CR 4219 HCU INSERT ISO CRD-V-101 CR 4619 HCU INSERT ISO CRD-V-101 CR 5019 HCU INSERT ISO CRD-V-101 CR 5419 HCU INSERT ISO CRD-V-101 CR 5819 HCU INSERT ISO CRD-V-101 CR 0223 HCU INSERT ISO November 16, 1994 Page 8 of 51 APPENDIX C ATTACHMENT C-2, WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING CRD-269 CRD-270 CRD-271 CRD-272 CRD-273 CRD-274 CRD-275 CRD-276 CRD-277 CRD-278 CRD-279 CRD-280 CRD-281 CRD-282 CRD-283 CRD-284 CRD-285 CRD-286 CRD-287 CRD-288 CRD-289 CRD-290 CRD-291 CRD-292 CRD-293 CRD-294 CRD-295 CRD-296 CRD-297 CRD-298 CRD-299 CRD-300 CRD-301 CRD-302 CRD-303 CRD-304 CRD-305 CRD-306 CRD-307 CRD-308 CRD-309 CRD-310 CRD-311 SYSTEM CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD DESCRIPTION CRD-V-101 CR 0623 HCU INSERT ISO CRD-V-101 CR 1023 HCU INSERT ISO CRD-V-101 CR 1423 HCU INSERT ISO CRD-V-101 CR 1823 HCU INSERT ISO CRD-V-101 CR 2223 HCU INSERT ISO CRD-V-101 CR 2623 HCU INSERT ISO CRD-V-101 CR 3023 HCU INSERT ISO CRD-V-101 CR 3423 HCU INSERT ISO CRD-V-101 CR 3823 HCU INSERT ISO CRD-V-101 CR 4223 HCU INSERT ISO CRD-V-101 CR 4623 HCU INSERT ISO CRD-V-101 CR 5023 HCU INSERT ISO CRD-V-101 CR 5423 HCU INSERT ISO CRD-V-101 CR 5823 HCU INSERT ISO CRD-V-101 CR 0227 HCU INSERT ISO CRD-V-101 CR 0627 HCU INSERT ISO CRD-V-101 CR 1027 HCU INSERT ISO CRD-V-101 CR 1427 HCU INSERT ISO CRD-V-101 CR 1827 HCU INSERT ISO CRD-V-101 CR 2227 HCU INSERT ISO CRD-V-101 CR 2627 HCU INSERT ISO CRD-V-101 CR 3027 HCU INSERT ISO CRD-V-101 CR 3427 HCU INSERT ISO CRD-V-101 CR 3827 HCU INSERT ISO CRD-V-101 CR 4227 HCU INSERT ISO CRD-V-101 CR 4627 HCU INSERT ISO CRD-V-101 CR 5027 HCU INSERT ISO CRD-V-101 CR 5427 HCU INSERT ISO CRD-V-101 CR 5827 HCU INSERT ISO CRD-V-101 CR 0231 HCU INSERT ISO CRD-V-101 CR 0631 HCU INSERT ISO CRD-V-101 CR 1031 HCU INSERT ISO CRD-V-101 CR 1431 HCU INSERT ISO CRD-V-101 CR 1831 HCU INSERT ISO CRD-V-101 CR 2231 HCU INSERT ISO CRD-V-101 CR 2631 HCU INSERT ISO CRD-V-101 CR 3031 HCU INSERT ISO CRD-V-101 CR 3431 HCU INSERT ISO CRD-V-101 CR 3831 HCU INSERT ISO CRD-V-101 CR 4231 HCU INSERT ISO CRD-V-101 CR 4631 HCU INSERT ISO CRD-V-101 CR 5031 HCU INSERT ISO CRD-V-101 CR 5431 HCU INSERT ISO November 16, 1994 Page 9 of 51 APPENDIX C ATTACHMENT C-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID CRD-312 CRD-313 CRD-314 CRD-315 CRD-316 CRD-317 CRD-318 CRD-319 CRD-320 CRD-321 CRD-322 CRD-323 CRD-324 CRD-325 CRD-326 CRD-327 CRD-328 CRD-329 CRD-330 CRD-331 CRD-332 CRD-333 CRD-334 CRD-335 CRD-336 CRD-337 CRD-338 CRD-339 CRD-340 CRD-341 CRD-342 CRD-343 CRD-344 CRD-345 CRD-346 CRD-347 CRD-348 CRD-349 CRD-350 CRD-351 CRD-352 CRD-353 CRD-354 SYSTEM CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD DESCRIPTION CRD-V-101 CR 5831 HCU INSERT ISO CRD-V-101 CR 0235 HCU INSERT ISO CRD-V-101 CR 0635 HCU INSERT ISO CRD-V-101 CR 1035 HCU INSERT ISO CRD-V-101 CR 1435 HCU INSERT ISO CRD-V-101 CR 1835 HCU INSERT ISO CRD-V-101 CR 2235 HCU INSERT ISO CRD-V-101 CR 2635 HCU INSERT ISO CRD-V-101 CR 3035 HCU INSERT ISO CRD-V-101 CR 3435 HCU INSERT ISO CRD-V-101 CR 3835 HCU INSERT ISO CRD-V-101 CR 4235 HCU INSERT ISO CRD-V-101 CR 4635 HCU INSERT ISO CRD-V-101 CR 5035 HCU INSERT ISO CRD-V-101 CR 5435 HCU INSERT ISO CRD-V-101 CR 5835 HCU INSERT ISO CRD-V-101 CR 0239 HCU INSERT ISO CRD-V-101 CR 0639 HCU INSERT ISO CRD-V-101 CR 1039 HCU INSERT ISO CRD-V-101 CR 1439 HCU INSERT ISO CRD-V-101 CR 1839 HCU INSERT ISO CRD-V-101 CR 2239 HCU INSERT ISO CRD-V-101 CR 2639 HCU INSERT ISO CRD-V-101 CR 3039 HCU INSERT ISO CRD-V-101 CR 3439 HCU INSERT ISO CRD-V-101 CR 3839 HCU INSERT ISO CRD-V-101 CR 4239 HCU INSERT ISO CRD-V-101 CR 4639 HCU INSERT ISO CRD-V-101 CR 5039 HCU INSERT ISO CRD-V-101 CR 5439 HCU INSERT ISO CRD-V-101 CR 5839 HCU INSERT ISO CRD-V-101 CR 0243 HCU INSERT ISO CRD-V-101 CR 0643 HCU INSERT ISO CRD-V-101 CR 1043 HCU INSERT ISO CRD-V-101 CR 1443 HCU INSERT ISO CRD-V-101 CR 1843 HCU INSERT ISO CRD-V-101 CR 2243 HCU INSERT ISO CRD-V-101 CR 2643 HCU INSERT ISO CRD-V-101 CR 3043 HCU INSERT ISO CRD-V-101 CR 3443 HCU INSERT ISO CRD-V-101 CR 3843 HCU INSERT ISO CRD-V-101 CR 4243 HCU INSERT ISO CRD-V-101 CR 4643 HCU INSERT ISO November 16, 1994 Page 10 of 51 APPENDIX C ATTACHMENT C-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID CRD-355 CRD-356 CRD-357 CRD-358 CRD-359 CRD-360 CRD-361 CRD-362 CRD-363 CRD-364 CRD-365 CRD-366 CRD-367 CRD-368 CRD-369 CRD-370 CRD-371 CRD-372 CRD-373 CRD-374 CRD-375 CRD-376 CRD-377 CRD-378 CRD-379 CRD-380 CRD-381 CRD-382 CRD-383 CRD-384 CRD-385 CRD-386 CRD-387 CRD-388 CRD-389 CRD-390 CRD-391 CRD-392 CRD-393 CRD-394 CRD-395 CRD-396 CRD-397 SYSTEM CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD DESCRIPTION CRD-V-101 CR 5043 HCU INSERT ISO CRD-V-101 CR 5443 HCU INSERT ISO CRD-V-101 CR 5843 HCU INSERT ISO CRD-V-101 CR 0647 HCU INSERT ISO CRD-V-101 CR 1047 HCU INSERT ISO CRD-V-101 CR 1447 HCU INSERT ISO CRD-V-101 CR 1847 HCU INSERT ISO CRD-V-101 CR 2247 HCU INSERT ISO CRD-V-101 CR 2647 HCU INSERT ISO CRD-V-101 CR 3047 HCU INSERT ISO CRD-V-101 CR 3447 HCU INSERT ISO CRD-V-101 CR 3847 HCU INSERT ISO CRD-V-101 CR 4247 HCU INSERT ISO CRD-V-101 CR 4647 HCU INSERT ISO CRD-V-'101 CR 5047 HCU INSERT ISO CRD-V-101 CR 5447 HCU INSERT ISO CRD-V-101 CR 1051 HCU INSERT ISO CRD-V-101 CR 1451 HCU INSERT ISO CRD-V-101 CR 1851 HCU INSERT ISO CRD-V-101 CR 2251 HCU INSERT ISO CRD-V-101 CR 2651 HCU INSERT ISO CRD-V-101 CR 3051 HCU INSERT ISO CRD-V-101 CR 3451 HCU INSERT ISO CRD-V-101 CR 3851 HCU INSERT ISO CRD-V-101 CR 4251 HCU INSERT ISO CRD-V-101 CR 4651 HCU INSERT ISO CRD-V-101 CR 5051 HCU INSERT ISO CRD-V-101 CR 1455 HCU INSERT ISO CRD-V-101 CR 1855 HCU INSERT ISO CRD-V-101 CR 2255 HCU INSERT ISO CRD-V-101 CR 2655 HCU INSERT ISO CRD-V-101 CR 3055 HCU INSERT ISO CRD-V-101 CR 3455 HCU INSERT ISO CRD-V-101 CR 3855 HCU INSERT ISO CRD-V-101 CR 4255 HCU INSERT ISO CRD-V-101 CR 4655 HCU INSERT ISO CRD-V-101 CR 1859 HCU INSERT ISO CRD-V-101 CR 2259 HCU INSERT ISO CRD-V-101 CR 2659 HCU INSERT ISO CRD-V-101 CR 3059 HCU INSERT ISO CRD-V-101 CR 3459 HCU INSERT ISO CRD-V-101 CR 3859 HCU INSERT ISO CRD-V-101 CR 4259 HCU INSERT ISO November 16, 1994 Page 11 of 51 APPENDIX C ATTACHMENT C-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID CRD-398 CRD-399 CRD-400 CRD-401 CRD 402 CRD 403 CRD-404 CRD-405 CRD 406 CRD 407 CRD 408 CRD409 CRD-410 CRD 411 CRD 412 CRD 413 CRD 414 CRD 415 CRD-416 CRD-417 CRD-418 CRD 419 CRD420 CRD 421 CRD 422 CRD-423 CRD-424 CRD-425 CRD-426 CRD 427 CRD-428 CRD-429 CRD-430 CRD-431 CRD-432 CRD 433 CRD 434 CRD 435 CRD-436 CRD437 CRD438 CRD439 CRD-440 SYSTEM CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD DESCRIPTION CRD-V-102 CR 1803 HCU WD HDR ISO CRD-V-102 CR 2203 HCU WD HDR ISO CRD-V-102 CR 2603 HCU WD HDR ISO CRD-V-102 CR 3003 HCU WD HDR ISO CRD-V-102 CR 3403 HCU WD HDR ISO CRD-V-102 CR 3803 HCU WD HDR ISO CRD-V-102 CR 4203 HCU WD HDR ISO CRD-V-102 CR 1407 HCU WD HDR ISO CRD-V-102 CR 1807 HCU WD HDR ISO CRD-V-102 CR 2207 HCU WD HDR ISO CRD-V-102 CR 2607 HCU WD HDR ISO CRD-V-102 CR 3007 HCU WD HDR ISO CRD-V-102 CR 3407 HCU WD HDR ISO CRD-V-102 CR 3807 HCU WD HDR ISO CRD-V-102 CR 4207 HCU WD HDR ISO CRD-V-102 CR 4607 HCU WD HDR ISO CRD-V-102 CR 1011 HCU WD HDR ISO CRD-V-102 CR 1411 HCU WD HDR ISO CRD-V-102 CR 1811 HCU WD HDR ISO CRD-V-102 CR 2211 HCU WD HDR ISO CRD-V-102 CR 2611 HCU WD HDR ISO CRD-V-102 CR 3011 HCU WD HDR ISO CRD-V-102 CR 3411 HCU WD HDR ISO CRD-V-102 CR 3811 HCU WD HDR ISO CRD-V-102 CR 4211 HCU WD HDR ISO CRD-V-102 CR 4611 HCU WD HDR ISO CRD-V-102 CR 5011 HCU WD HDR ISO CRD-V-102 CR 0615 HCU WD HDR ISO CRD-V-102 CR 1015 HCU WD HDR ISO CRD-V-102 CR 1415 HCU WD HDR ISO CRD-V-102 CR 1815 HCU WD HDR ISO CRD-V-102 CR 2215 HCU WD HDR ISO CRD-V-102 CR 2615 HCU WD HDR ISO CRD-V-102 CR 3015 HCU WD HDR ISO CRD-V-102 CR 3415 HCU WD HDR ISO CRD-V-102 CR 3815 HCU WD HDR ISO CRD-V-102 CR 4215 HCU WD HDR ISO CRD-V-102 CR 4615 HCU WD HDR ISO CRD-V-102 CR 5015 HCU WD HDR ISO CRD-V-102 CR 5415 HCU WD HDR ISO CRD-V-102 CR 0219 HCU WD HDR ISO CRD-V-102 CR 0619 HCU WD HDR ISO CRD-V-102 CR 1019 HCU WD HDR ISO November 16, 1994 Page 12 of 51 APPENDIX C ATTACHMENT C-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID CRDM1 CRD-442 CRD-443 CRD 444 CRD-445 CRD-446 CRD-447 CRD-448 CRD-449 CRD-450 CRD 451 CRD-452 CRD-453 CRD-454 CRD 455 CRD-456 CRD 457 CRD-458 CRD-459 CRD 460 CRD 461 CRD462 CRD-463 CRD-464 CRD-465 CRD-466 CRD467 CRD-468 CRD 469 CRD 470 CRD 471 CRD 472 CRDP73 CRD 474 CRD-475 CRD 476 CRD 477 CRD 478 CRD 479 CRDP80 CRD-481 CRD-482 CRD-483 SYSTEM CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD DESCRIPTION CRD-V-102 CR 1419 HCU WD HDR ISO CRD-V-102 CR 1819 HCU WD HDR ISO CRD-V-102 CR 2219 HCU WD HDR ISO CRD-V-102 CR 2619 HCU WD HDR ISO CRD-V-102 CR 3019 HCU WD HDR ISO CRD-V-102 CR 3419 HCU WD HDR ISO CRD-V-102 CR 3819 HCU WD HDR ISO CRD-V-102 CR 4219 HCU WD HDR ISO CRD-V-102 CR 4619 HCU WD HDR ISO CRD-V-102 CR 5019 HCU WD HDR ISO CRD-V-102 CR 5419 HCU WD HDR ISO CRD-V-102 CR 5819 HCU WD HDR ISO CRD-V-102 CR 0223 HCU WD HDR ISO CRD-V-102 CR 0623 HCU WD HDR ISO CRD-V-102 CR 1023 HCU WD HDR ISO CRD-V-102 CR 1423 HCU WD HDR ISO CRD-V-102 CR 1823 HCU WD HDR ISO CRD-V-102 CR 2223 HCU WD HDR ISO CRD-V-102 CR 2623 HCU WD HDR ISO CRD-V-102 CR 3023 HCU WD HDR ISO CRD-V-102 CR 3423 HCU WD HDR ISO CRD-V-102 CR 3823 HCU WD HDR ISO CRD-V-102 CR 4223 HCU WD HDR ISO CRD-V-102 CR 4623 HCU WD HDR ISO CRD-V-102 CR 5023 HCU WD HDR ISO CRD-V-102 CR 5423 HCU WD HDR ISO CRD-V-102 CR 5823 HCU WD HDR ISO CRD-V-102 CR 0227 HCU WD HDR ISO CRD-V-102 CR 0627 HCU WD HDR ISO CRD-V-102 CR 1027 HCU WD HDR ISO CRD-V-102 CR 1427 HCU WD HDR ISO CRD-V-102 CR 1827 HCU WD HDR ISO CRD-V-102 CR 2227 HCU WD HDR ISO CRD-V-102 CR 2627 HCU WD HDR ISO CRD-V-102 CR 3027 HCU WD HDR ISO CRD-V-102 CR 3427 HCU WD HDR ISO CRD-V-102 CR 3827 HCU WD HDR ISO CRD-V-102 CR 4227 HCU WD HDR ISO CRD-V-102 CR 4627 HCU WD HDR ISO CRD-V-102 CR 5027 HCU WD HDR ISO CRD-V-102 CR 5427 HCU WD HDR ISO CRD-V-102 CR 5827 HCU WD HDR ISO CRD-V-102 CR 0231 HCU WD HDR ISO November 16, 1994 Page 13 of 51 APPENDIX C ATTACHMENT C-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACHONS LISTING ID CRD 484 CRD-485 CRD-486 CRD 487 CRD488 CRD489 CRD-490 CRD 491 CRD 492 CRD 493 CRD 494 CRDP95 CRD 496 CRD-497 CRD 498 CRD 499 CRD-500 CRD-501 CRD-502 CRD-503 CRD-504 CRD-505 CRD-506 CRD-507 CRD-508 CRD-509 CRD-510 CRD-511 CRD-512 CRD-513 CRD-514 CRD-515 CRD-516 CRD-517 CRD-518 CRD-519 CRD-520 CRD-521 CRD-522 CRD-523 CRD-524 CRD-525 CRD-526 SYSTEM CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD DESCRIPTION CRD-V-102 CR 0631 HCU WD HDR ISO CRD-V-102 CR 1031 HCU WD HDR ISO CRD-V-102 CR 1431 HCU WD HDR ISO CRD-V-102 CR 1831 HCU WD HDR ISO CRD-V-102 CR 2231 HCU WD HDR ISO CRD-V-102 CR 2631 HCU WD HDR ISO CRD-V-102 CR 3031 HCU WD HDR ISO CRD-V-102 CR 3431 HCU WD HDR ISO CRD-V-102 CR 3831 HCU WD HDR ISO CRD-V-102 CR 4231 HCU WD HDR ISO CRD-V-102 CR 4631 HCU WD HDR ISO CRD-V-102 CR 5031 HCU WD HDR ISO CRD-V-102 CR 5431 HCU WD HDR ISO CRD-V-102 CR 5831 HCU WD HDR ISO CRD-V-102 CR 0235 HCU WD HDR ISO CRD-V-102 CR 0635 HCU WD HDR ISO CRD-V-102 CR 1035 HCU WD HDR ISO CRD-V-102 CR 1435 HCU WD HDR ISO CRD-V-102 CR 1835 HCU WD HDR ISO CRD-V-102 CR 2235 HCU WD HDR ISO CRD-V-102 CR 2635 HCU WD HDR ISO CRD-V-102 CR 3035 HCU WD HDR ISO CRD-V-102 CR 3435 HCU WD HDR ISO CRD-V-102 CR 3835 HCU WD HDR ISO CRD-V-102 CR 4235 HCU WD HDR ISO'RD-V-102 CR 4635 HCU WD HDR ISO CRD-V-102 CR 5035 HCU WD HDR ISO CRD-V-102 CR 5435 HCU WD HDR ISO CRD-V-102 CR 5835 HCU WD HDR ISO CRD-V-102 CR 0239 HCU WD HDR ISO CRD-V-102 CR 0639 HCU WD HDR ISO CRD-V-102 CR 1039 HCU WD HDR ISO CRD-V-102 CR 1439 HCU WD HDR ISO CRD-V-102 CR 1839 HCU WD HDR ISO CRD-V-102 CR 2239 HCU WD HDR ISO CRD-V-102 CR 2639 HCU WD HDR ISO CRD-V-102 CR 3039 HCU WD HDR ISO CRD-V-102 CR 3439 HCU WD HDR ISO CRD-V-102 CR 3839 HCU WD HDR ISO CRD-V-102 CR 4239 HCU WD HDR ISO CRD-V-102 CR 4639 HCU WD HDR ISO CRD-V-102 CR 5039 HCU WD HDR ISO CRD-V-102 CR 5439 HCU WD HDR ISO November 16, 1994 Page 14of51 APPENDIX C ATTACHMENT C-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID CRD-527 CRD-528 CRD-529 CRD-530 CRD-531 CRD-532 CRD-533 CRD-534 CRD-535 CRD-536 CRD-537 CRD-538 CRD-539 CRD-540 CRD-541 CRD-542 CRD-543 CRD-544 CRD-545 CRD-546 CRD-547 CRD-548 CRD-549 CRD-550 CRD-551 CRD-552 CRD-553 CRD-554 CRD-555 CRD-556 CRD-557 CRD-558 CRD-559 CRD-560 CRD-561 CRD-562 CRD-563 CRD-564 CRD-565 CRD-566 CRD-567 CRD-568 CRD-569 SYSTEM CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD DESCRIPTION CRD-V-102 CR 5839 HCU WD HDR ISO CRD-V-102 CR 0243 HCU WD HDR ISO CRD-V-102 CR 0643 HCU WD HDR ISO CRD-V-102 CR 1043 HCU WD HDR ISO CRD-V-102 CR 1443 HCU WD HDR ISO CRD-V-102 CR 1843 HCU WD HDR ISO CRD-V-102 CR 2243 HCU WD HDR ISO CRD-V-102 CR 2643 HCU WD HDR ISO CRD-V-102 CR 3043 HCU WD HDR ISO CRD-V-102 CR 3443 HCU WD HDR ISO CRD-V-102 CR 3843 HCU WD HDR ISO CRD-V-102 CR 4243 HCU WD HDR ISO CRD-V-102 CR 4643 HCU WD HDR ISO CRD-V-102 CR 5043 HCU WD HDR ISO CRD-V-102 CR 5443 HCU WD HDR ISO CRD-V-102 CR 5843 HCU WD HDR ISO CRD-V-102 CR 0647 HCU WD HDR ISO CRD-V-102 CR 1047 HCU WD HDR ISO CRD-V-102 CR 1447 HCU WD HDR ISO CRD-V-102 CR 1847 HCU WD HDR ISO CRD-V-102 CR 2247 HCU WD HDR ISO CRD-V-102 CR 2647 HCU WD HDR ISO CRD-V-102 CR 3047 HCU WD HDR ISO CRD-V-102 CR 3447 HCU WD HDR ISO CRD-V-102 CR 3847 HCU WD HDR ISO CRD-V-102 CR 4247 HCU WD HDR ISO CRD-V-102 CR 4647 HCU WD HDR ISO CRD-V-102 CR 5047 HCU WD HDR ISO CRD-V-102 CR 5447 HCU WD HDR ISO CRD-V-102 CR 1051 HCU WD HDR ISO CRD-V-102 CR 1451 HCU WD HDR ISO CRD-V-102 CR 1851 HCU WD HDR ISO CRD-V-102 CR 2251 HCU WD HDR ISO CRD-V-102 CR 2651 HCU WD HDR ISO CRD-V-102 CR 3051 HCU WD HDR ISO CRD-V-102 CR 3451 HCU WD HDR ISO CRD-V-102 CR 3851 HCU WD HDR ISO CRD-V-102 CR 4251 HCU WD HDR ISO CRD-V-102 CR 4651 HCU WD HDR ISO CRD-V-102 CR 5051 HCU WD HDR ISO CRD-V-102 CR 1455 HCU WD HDR ISO CRD-V-102 CR 1855 HCU WD HDR ISO CRD-V-102 CR 2255 HCU WD HDR ISO November 16, 1994 Page 15 of 51 0
APPENDIX C ATTACHMENT C-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID CRD-570 CRD-571 CRD-572 CRD-573 CRD-574 CRD-575 CRD-576 CRD-577 CRD-578 CRD-579 CRD-580 CRD-581 CRD-582 CRD-583 CRD-584 CRD-585 CRD-586 CRD-587 CRD-588 CRD-589 CRD-590 CRD-591 CRD-592 CRD-593 CRD-594 CRD-595 CRD-596 CRD-597 CRD-598 CRD-599 CRD-600 CRD-601 CRD-602 CRD-603 CRD-604 CRD-605 CRD-606 CRD-607 CRD-608 CRD-609 CRD-610 CRD-611 CRD-612 SYSTEM CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD DESCRIPTION CRD-V-102 CR 2655 HCU WD HDR ISO CRD-V-102 CR 3055 HCU WD HDR ISO CRD-V-102 CR 3455 HCU WD HDR ISO CRD-V-102 CR 3855 HCU WD HDR ISO CRD-V-102 CR 4255 HCU WD HDR ISO CRD-V-102 CR 4655 HCU WD HDR ISO CRD-V-102 CR 1859 HCU WD HDR ISO CRD-V-102 CR 2259 HCU WD HDR ISO CRD-V-102 CR 2659 HCUWD HDR ISO CRD-V-102 CR 3059 HCU WD HDR ISO CRD-V-102 CR 3459 HCU WD HDR ISO CRD-V-102 CR 3859 HCU WD HDR ISO CRD-V-102 CR 4259 HCU WD HDR ISO CRD-V-103 CR 1803 HCU DRV ISOL CRD-V-103 CR 2203 HCU DRV ISOL CRD-V-.103 CR 2603 HCU DRV ISOL CRD-V-103 CR 3003 HCU DRV ISOL CRD-V-103 CR 3403 HCU DRV ISOL CRD-V-103 CR 3803 HCU DRV ISOL CRD-V-103 CR 4203 HCU DRV ISOL CRD-V-103 CR 1407 HCU DRV ISOL CRD-V-103 CR 1807 HCU DRV ISOL CRD-V-103 CR 2207 HCU DRV ISOL CRD-V-103 CR 2607 HCU DRV ISOL CRD-V-103 CR 3007 HCU DRV ISOL CRD-V-103 CR 3407 HCU DRV ISOL CRD-V-103 CR 3807 HCU DRV ISOL CRD-V-103 CR 4207 HCU DRV ISOL CRD-V-103 CR 4607 HCU DRV ISOL CRD-V-103 CR 1011 HCU DRV ISOL CRD-V-103 CR 1411 HCU DRV ISOL CRD-V-103 CR 1811 HCU DRV ISOL CRD-V-103 CR 2211 HCU DRV ISOL CRD-V-103 CR 2611 HCU DRV ISOL CRD-V-103 CR 3011 HCU DRV ISOL CRD-V-103 CR 3411 HCU DRV ISOL CRD-V-103 CR 3811 HCU DRV ISOL CRD-V-103 CR 4211 HCU DRV ISOL CRD-V-103 CR 4611 HCU DRV ISOL CRD-V-103 CR 5011 HCU DRV ISOL CRD-V-103 CR 0615 HCU DRV ISOL CRD-V-103 CR 1015 HCU DRV ISOL CRD-V-103 CR 1415 HCU DRV ISOL November 16, 1994 Page 16 of 51 APPENDIX C ATTACHMENT C-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID CRD-613 CRD-614 CRD-615 CRD-616 CRD-617 CRD-618 CRD-619 CRD-620 CRD-621 CRD-622 CRD-623 CRD-624 CRD-625 CRD-626 CRD-627 CRD-628 CRD-629 CRD-630 CRD-631 CRD-632 CRD-633 CRD-634 CRD-635 CRD-636 CRD-637 CRD-638 CRD-639 CRD-640 CRD-641 CRD-642 CRD-643 CRD-644 CRD-645 CRD-646 CRD-647 CRD-648 CRD-649 CRD-650 CRD-651 CRD-652 CRD-653 CRD-654 CRD-655 SYSTEM CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD DESCRIPTION CRD-V-103 CR 1815 HCU DRV ISOL CRD-V-103 CR 2215 HCU DRV ISOL CRD-V-103 CR 2615 HCU DRV ISOL CRD-V-103 CR 3015 HCU DRV ISOL CRD-V-103 CR 3415 HCU DRV ISOL CRD-V-103 CR 3815 HCU DRV ISOL CRD-V-103 CR 4215 HCU DRV ISOL CRD-V-103 CR 4615 HCU DRV ISOL CRD-V-103 CR 5015 HCU DRV ISOL CRD-V-103 CR 5415 HCU DRV ISOL CRD-V-103 CR 0219 HCU DRV ISOL CRD-V-103 CR 0619 HCU DRV ISOL CRD-V-103 CR 1019 HCU DRV ISOL CRD-V-103 CR 1419 HCU DRV ISOL CRD-V-103 CR 1819 HCU DRV ISOL CRD-V-103 CR 2219 HCU DRV ISOL CRD-V-103 CR 2619 HCU DRV ISOL CRD-V-103 CR 3019 HCU DRV ISOL CRD-V-103 CR 3419 HCU DRV ISOL CRD-V-103 CR 3819 HCU DRV ISOL CRD-V-103 CR 4219 HCU DRV ISOL CRD-V-103 CR 4619 HCU DRV ISOL CRD-V-103 CR 5019 HCU DRV ISOL CRD-V-103 CR 5419 HCU DRV ISOL CRD-V-103 CR 5819 HCU DRV ISOL CRD-V-103 CR 0223 HCU DRV ISOL CRD-V-103 CR 0623 HCU DRV ISOL CRD-V-103 CR 1023 HCU DRV ISOL CRD-V-103 CR 1423 HCU DRV ISOL CRD-V-103 CR 1823 HCU DRV ISOL CRD-V-103 CR 2223 HCU DRV ISOL CRD-V-103 CR 2623 HCU DRV ISOL CRD-V-103 CR 3023 HCU DRV ISOL CRD-V-103 CR 3423 HCU DRV ISOL CRD-V-103 CR 3823 HCU DRV ISOL CRD-V-103 CR 4223 HCU DRV ISOL CRD-V-103 CR 4623 HCU DRV ISOL CRD-V-103 CR 5023 HCU DRV ISOL CRD-V-103 CR 5423 HCU DRV ISOL CRD-V-103 CR 5823 HCU DRV ISOL CRD-V-103 CR 0227 HCU DRV ISOL CRD-V-103 CR 0627 HCU DRV ISOL CRD-V-103 CR 1027 HCU DRV ISOL November 16, 1994 Page 17 of 51 APPENDIX C ATTACHMENT C-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID CRD-656 CRD-657 CRD-658 CRD-659 CRD-660 CRD-661 CRD-662 CRD-663 CRD-664 CRD-665 CRD-666 CRD-667 CRD-668 CRD-669 CRD-670 CRD-671 CRD-672 CRD-673 CRD-674 CRD-675 CRD;676 CRD-677 CRD-678 CRD-679 CRD-680 CRD-681 CRD-682 CRD-683 CRD-684 CRD-685 CRD-686 CRD-687 CRD-688 CRD-689 CRD-690 CRD-691 CRD-692 CRD-693 CRD-694 CRD-695 CRD-696 CRD-697 CRD-698 SYSTEM CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD DESCRIPTION CRD-V-103 CR 1427 HCU DRV ISOL CRD-V-103 CR 1827 HCU DRV ISOL CRD-V-103 CR 2227 HCU DRV ISOL CRD-V-103 CR 2627 HCU DRV ISOL CRD-V-103 CR 3027 HCU DRV ISOL CRD-V-103 CR 3427 HCU DRV ISOL CRD-V-103 CR 3827 HCU DRV ISOL CRD-V-103 CR 4227 HCU DRV ISOL CRD-V-103 CR 4627 HCU DRV ISOL CRD-V-103 CR 5027 HCU DRV ISOL CRD-V-103 CR 5427 HCU DRV ISOL CRD-V-103 CR 5827 HCU DRV ISOL CRD-V-103 CR 0231 HCU DRV ISOL CRD-V-103 CR 0631 HCU DRV ISOL CRD-V-103 CR 1031 HCU DRV ISOL CRD-V-103 CR 1431 HCU DRV ISOL CRD-V-103 CR 1831 HCU DRV ISOL CRD-V-103 CR 2231 HCU DRV ISOL CRD-V-103 CR 2631 HCU DRV ISOL CRD-V-103 CR 3031 HCU DRV ISOL CRD-V-103 CR 3431 HCU DRV ISOL CRD-V-103 CR 3831 HCU DRV ISOL CRD-V-103 CR 4231 HCU DRV ISOL CRD-V-103 CR 4631 HCU DRV ISOL CRD-V-103 CR 5031 HCU DRV ISOL CRD-V-103 CR 5431 HCU DRV ISOL CRD-V-103 CR 5831 HCU DRV ISOL CRD-V-103 CR 0235 HCU DRV ISOL CRD-V-103 CR 0635 HCU DRV ISOL CRD-V-103 CR 1035 HCU DRV ISOL CRD-V-103 CR 1435 HCU DRV ISOL CRD-V-103 CR 1835 HCU DRV ISOL CRD-V-103 CR 2235 HCU DRV ISOL CRD-V-103 CR 2635 HCU DRV ISOL CRD-V-103 CR 3035 HCU DRV ISOL CRD-V-103 CR 3435 HCU DRV ISOL CRD-V-103 CR 3835 HCU DRV ISOL CRD-V-103 CR 4235 HCU DRV ISOL CRD-V-103 CR 4635 HCU DRV ISOL CRD-V-103 CR 5035 HCU DRV ISOL CRD-V-103 CR 5435 HCU DRV ISOL CRD-V-103 CR 5835 HCU DRV ISOL CRD-V-103 CR 0239 HCU DRV ISOL November 16, 1994 Page 18 of 51 APPENDIX C ATTACHMENT C-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID CRD-699 CRD-700 CRD-701 CRD-702 CRD-703 CRD-704 CRD-705 CRD-706 CRD-707 CRD-708 CRD-709 CRD-710 CRD-711 CRD-712 CRD-713 CRD-'714 CRD-715 CRD-716 CRD-717 CRD-718 CRD-719 CRD-720 CRD-721 CRD-722 CRD-723 CRD-724 CRD-725 CRD-726 CRD-727 CRD-728 CRD-729 CRD-730 CRD-731 CRD-732 CRD-733 CRD-734 CRD-735 CRD-736 CRD-737 CRD-738 CRD-739 CRD-740 CRD-741 SYSTEM CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD DESCRIPTION CRD-V-103 CR 0639 HCU DRV ISOL CRD-V-103 CR 1039 HCU DRV ISOL CRD-V-103 CR 1439 HCU DRV ISOL CRD-V-103 CR 1839 HCU DRV ISOL CRD-V-103 CR 2239 HCU DRV ISOL CRD-V-103 CR 2639 HCU DRV ISOL CRD-V-103 CR 3039 HCU DRV ISOL CRD-V-103 CR 3439 HCU DRV ISOL CRD-V-103 CR 3839 HCU DRV ISOL CRD-V-103 CR 4239 HCU DRV ISOL CRD-V-103 CR 4639 HCU DRV ISOL CRD-V-103 CR 5039 HCU DRV ISOL CRD-V-103 CR 5439 HCU DRV ISOL CRD-V-103 CR 5839 HCU DRV ISOL CRD-V-103 CR 0243 HCU DRV ISOL CRD-V-103 CR 0643 HCU DRV ISOL CRD-V-103 CR 1043 HCU DRV ISOL CRD-V-103 CR 1443 HCU DRV ISOL CRD-V-103 CR 1843 HCU DRV ISOL CRD-V-103 CR 2243 HCU DRV ISOL CRD-V-103 CR 2643 HCU DRV ISOL CRD-V-103 CR 3043 HCU DRV ISOL CRD-V-103 CR 3443 HCU DRV ISOL CRD-V-103 CR 3843 HCU DRV ISOL CRD-V-103 CR 4243 HCU DRV ISOL CRD-V-103 CR 4643 HCU DRV ISOL CRD-V-103 CR 5043 HCU DRV ISOL CRD-V-103 CR 5443 HCU DRV ISOL CRD-V-103 CR 5843 HCU DRV ISOL CRD-V-103 CR 0647 HCU DRV ISOL CRD-V-103 CR 1047 HCU DRV ISOL CRD-V-103 CR 1447 HCU DRV ISOL CRD-V-103 CR 1847 HCU DRV ISOL CRD-V-103 CR 2247 HCU DRV ISOL CRD-V-103 CR 2647 HCU DRV ISOL CRD-V-103 CR 3047 HCU DRV ISOL CRD-V-103 CR 3447 HCU DRV ISOL CRD-V-103 CR 3847 HCU DRV ISOL CRD-V-103 CR 4247 HCU DRV ISOL CRD-V-103 CR 4647 HCU DRV ISOL CRD-V-103 CR 5047 HCU DRV ISOL CRD-V-103 CR 5447 HCU DRV ISOL CRD-V-103 CR 1051 HCU DRV ISOL November 16, 1994 Page 19 of 51 APPENDIX C ATTACHMENT C-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID CRD-742 CRD-743 CRD-744 CRD-745 CRD-746 CRD-747 CRD-748 CRD-749 CRD-750 CRD-751 CRD-752 CRD-753 CRD-754 CRD-755 CRD-756 CRD-757 CRD-758 CRD-759 CRD-760 CRD-761 CRD-762 CRD-763 CRD-764 CRD-765 CRD-766 CRD-767 CRD-768 CRD-769 CRD-770 CRD-771 CRD-772 CRD-773 CRD-774 CRD-775 CRD-776 CRD-777 CRD-778 CRD-779 CRD-780 CRD-781 CRD-782 CRD-783 CRD-784 SYSTEM CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD DESCRIPTION CRD-V-103 CR 1451 HCU DRV ISOL CRD-V-103 CR 1851 HCU DRV ISOL CRD-V-103 CR 2251 HCU DRV ISOL CRD-V-103 CR 2651 HCU DRV ISOL CRD-V-103 CR 3051 HCU DRV ISOL CRD-V-103 CR 3451 HCU DRV ISOL CRD-V-103 CR 3851 HCU DRV ISOL CRD-V-103 CR 4251 HCU DRV ISOL CRD-V-103 CR 4651 HCU DRV ISOL CRD-V-103 CR 5051 HCU DRV ISOL CRD-V-103 CR 1455 HCU DRV ISOL CRD-V-103 CR 1855 HCU DRV ISOL CRD-V-103 CR 2255 HCU DRV ISOL CRD-V-103 CR 2655 HCU DRV ISOL CRD-V-103 CR 3055 HCU DRV ISOL CRD-V-103 CR 3455 HCU DRV ISOL CRD-V-103 CR 3855 HCU DRV ISOL CRD-V-103 CR 4255 HCU DRV ISOL CRD-V-103 CR 4655 HCU DRV ISOL CRD-V-103 CR 1859 HCU DRV ISOL CRD-V-103 CR 2259 HCU DRV ISOL CRD-V-103 CR 2659 HCU DRV ISOL CRD-V-103 CR 3059 HCU DRV ISOL CRD-V-103 CR 3459 HCU DRV ISOL CRD-V-103 CR 3859 HCU DRV ISOL CRD-V-103 CR 4259 HCU DRV ISOL CRD-V-101 CR 1803 INS LINE VENT CRD-V-101 CR 2203 INS LINE VENT CRD-V-101 CR 2603 INS LINE VENT CRD-V-101 CR 3003 INS LINE VENT CRD-V-101 CR 3403 INS LINE VENT CRD-V-101 CR 3803 INS LINE VENT CRD-V-101 CR 4203 INS LINE VENT CRD-V-101 CR 1407 INS LINE VENT CRD-V-101 CR 1807 INS LINE VENT CRD-V-101 CR 2207 INS LINE VENT CRD-V-101 CR 2607 INS LINE VENT CRD-V-101 CR 3007 INS LINE VENT CRD-V-101 CR 3407 INS LINE VENT CRD-V-101 CR 3807 INS LINE VENT CRD-V-101 CR 4207 INS LINE VENT CRD-V-101 CR 4607 INS LINE VENT CRD-V-101 CR 1011 INS LINE VENT November 16, 1994 Page 20 of 51 APPENDIX C ATTACHMENT C-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID CRD-785 CRD-786 CRD-787 CRD-788 CRD-789 CRD-790 CRD-791 CRD-792 CRD-793 CRD-794 CRD-795 CRD-796 CRD-797 CRD-798 CRD-799 CRD-800 CRD-801 CRD-802 CRD-803 CRD-804 CRD-805 CRD-806 CRD-807 CRD-808 CRD-809 CRD-810 CRD-811 CRD-812 CRD-813 CRD-814 CRD-815 CRD-816 CRD-817 CRD-818 CRD-819 CRD-820 CRD-821 CRD-822 CRD-823 CRD-824 CRD-825 CRD-826 CRD-827 SYSTEM CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD DESCRIPTION CRD-V-101 CR 1411 INS LINE VENT CRD-V-101 CR 1811 INS LINE VENT CRD-V-101 CR 2211 INS LINE VENT CRD-V-101 CR 2611 INS LINE VENT CRD-V-101 CR 3011 INS LINE VENT CRD-V-101 CR 3411 INS LINE VENT CRD-V-101 CR 3811 INS LINE VENT CRD-V-101 CR 4211 INS LINE VENT CRD-V-101 CR 4611 INS LINE VENT CRD-V-101 CR 5011 INS LINE VENT CRD-V-101 CR 0615 INS LINE VENT CRD-V-101 CR 1015 INS LINE VENT CRD-V-101 CR 1415 INS LINE VENT CRD-V-101 CR 1815 INS LINE VENT CRD-V-101 CR 2215 INS LINE VENT CRD-V-101 CR 2615 INS LINE VENT CRD-V-101 CR 3015 INS LINE VENT CRD-V-101 CR 3415 INS LINE VENT CRD-V-101 CR 3815 INS LINE VENT CRD-V-101 CR 4215 INS LINE VENT CRD-V-101 CR 4615 INS LINE VENT CRD-V-101 CR 5015 INS LINE VENT CRD-V-101 CR 5415 INS LINE VENT CRD-V-101 CR 0219 INS LINE VENT CRD-V-101 CR 0619 INS LINE VENT CRD-V-101 CR 1019 INS LINE VENT CRD-V-101 CR 1419 INS LINE VENT CRD-V-101 CR 1819 INS LINE VENT CRD-V-101 CR 2219 INS LINE VENT CRD-V-101 CR 2619 INS LINE VENT CRD-V-101 CR 3019 INS LINE VENT CRD-V-101 CR 3419 INS LINE VENT CRD-V-101 CR 3819 INS LINE VENT CRD-V-101 CR 4219 INS LINE VENT CRD-V-101 CR 4619 INS LINE VENT CRD-V-101 CR 5019 INS LINE VENT CRD-V-101 CR 5419 INS LINE VENT CRD-V-101 CR 5819 INS LINE VENT CRD-V-101 CR 0223 INS LINE VENT CRD-V-101 CR 0623 INS LINE VENT CRD-V-101 CR 1023 INS LINE VENT CRD-V-101 CR 1423 INS LINE VENT CRD-V-101 CR 1823 INS LINE VENT November 16, 1994 Page 21 of 51 APPENDIX C ATTACHMENT C-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID CRD-828 CRD-829 CRD-830 CRD-831 CRD-832 CRD-833 CRD-834 CRD-835 CRD-836 CRD-837 CRD-838 CRD-839 CRD-840 CRD-841 CRD-842 CRD-843 CRD-844 CRD-845 CRD-846 CRD-847 CRD-848 CRD-849 CRD-850 CRD-851 CRD-852 CRD-853 CRD-854 CRD-855 CRD-856 CRD-857 CRD-858 CRD-859 CRD-860 CRD-861 CRD-862 CRD-863 CRD-864 CRD-865 CRD-866 CRD-867 CRD-868 CRD-869 CRD-870 SYSTEM CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD DESCRIPTION CRD-V-101 CR 2223 INS LINE VENT CRD-V-101 CR 2623 INS LINE VENT CRD-V-101 CR 3023 INS LINE VENT CRD-V-101 CR 3423 INS LINE VENT CRD-V-101 CR 3823 INS LINE VENT CRD-V-101 CR 4223 INS LINE VENT CRD-V-101 CR 4623 INS LINE VENT CRD-V-101 CR 5023 INS LINE VENT CRD-V-101 CR 5423 INS LINE VENT CRD-V-101 CR 5823 INS LINE VENT CRD-V-101 CR 0227 INS LINE VENT CRD-V-101 CR 0627 INS LINE VENT CRD-V-101 CR 1027 INS LINE VENT CRD-V-101 CR 1427 INS LINE VENT CRD-V-101 CR 1827 INS LINE VENT CRD-V-101 CR 2227 INS LINE VENT CRD-V-101 CR 2627 INS LINE VENT CRD-V-101 CR 3027 INS LINE VENT CRD-V-101 CR 3427 INS LINE VENT CRD-V-101 CR 3827 INS LINE VENT CRD-V-101 CR 4227 INS LINE VENT CRD-V-101 CR 4627 INS LINE VENT CRD-V-101 CR 5027 INS LINE VENT CRD-V-101 CR 5427 INS LINE VENT CRD-V-101 CR 5827 INS LINE VENT CRD-V-101 CR 0231 INS LINE VENT CRD-V-101 CR 0631 INS LINE VENT CRD-V-101 CR 1031 INS LINE VENT CRD-V-101 CR 1431 INS LINE VENT CRD-V-101 CR 1831 INS LINE VENT CRD-V-101 CR 2231 INS LINE VENT CRD-V-101 CR 2631 INS LINE VENT CRD-V-101 CR 3031 INS LINE VENT CRD-V-101 CR 3431 INS LINE VENT CRD-V-101 CR 3831 INS LINE VENT CRD-V-101 CR 4231 INS LINE VENT CRD-V-101 CR 4631 INS LINE VENT CRD-V-101 CR 5031 INS LINE VENT CRD-V-101 CR 5431 INS LINE VENT CRD-V-101 CR 5831 INS LINE VENT CRD-V-101 CR 0235 INS LINE VENT CRD-V-101 CR 0635 INS LINE VENT CRD-V-101 CR 1035 INS LINE VENT November 16, 1994 Page 22 of 51 APPENDIX C ATTACHMENT C-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID CRD-871 CRD-872 CRD-873 CRD-874 CRD-875 CRD-876 CRD-877 CRD-878 CRD-879 CRD-880 CRD-881 CRD-882 CRD-883 CRD-884 CRD-885 CRD-886 CRD-887 CRD-888 CRD-889 CRD-890 CRD-891 CRD-892 CRD-893 CRD-894 CRD-895 CRD-896 CRD-897 CRD-898 CRD-899 CRD-900 CRD-901 CRD-902 CRD-903 CRD-904 CRD-905 CRD-906 CRD-907 CRD-908 CRD-909 CRD-910 CRD-911 CRD-912 CRD-913 SYSTEM CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD DESCRIPTION CRD-V-101 CR 1435 INS LINE VENT CRD-V-101 CR 1835 INS LINE VENT CRD-V-101 CR 2235 INS LINE VENT CRD-V-101 CR 2635 INS LINE VENT CRD-V-101 CR 3035 INS LINE VENT CRD-V-101 CR 3435 INS LINE VENT CRD-V-101 CR 3835 INS LINE VENT CRD-V-101 CR 4235 INS LINE VENT CRD-V-101 CR 4635 INS LINE VENT CRD-V-101 CR 5035 INS LINE VENT CRD-V-101 CR 5435 INS LINE VENT CRD-V-101 CR 5835 INS LINE VENT CRD-V-101 CR 0239 INS LINE VENT CRD-V-101 CR 0639 INS LINE VENT CRD-V-101 CR 1039 INS LINE VENT CRD-V-101 CR 1439 INS LINE VENT CRD-V-101 CR 1839 INS LINE VENT CRD-V-101 CR 2239 INS LINE VENT CRD-V-101 CR 2639 INS LINE VENT CRD-V-101 CR 3039 INS LINE VENT CRD-V-101 CR 3439 INS LINE VENT CRD-V-101 CR 3839 INS LINE VENT CRD-V-101 CR 4239 INS LINE VENT CRD-V-101 CR 4639 INS LINE VENT CRD-V-101 CR 5039 INS LINE VENT CRD-V-101 CR 5439 INS LINE VENT CRD-V-101 CR 5839 INS LINE VENT CRD-V-101 CR 0243 INS LINE VENT CRD-V-101 CR 0643 INS LINE VENT CRD-V-101 CR 1043 INS LINE VENT CRD-V-101 CR 1443 INS LINE VENT CRD-V-101 CR 1843 INS LINE VENT CRD-V-101 CR 2243 INS LINE VENT CRD-V-101 CR 2643 INS LINE VENT CRD-V-101 CR 3043 INS LINE VENT CRD-V-101 CR 3443 INS LINE VENT CRD-V-101 CR 3843 INS LINE VENT CRD-V-101 CR 4243 INS LINE VENT CRD-V-101 CR 4643 INS LINE VENT CRD-V-101 CR 5043 INS LINE VENT CRD-V-101 CR 5443 INS LINE VENT CRD-V-101 CR 5843 INS LINE VENT CRD-V-101 CR 0647 INS LINE VENT November 16, 1994 Page 23 of 51 APPENDIX C ATTACHMENT C-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID CRD-914 CRD-915 CRD-916 CRD-917 CRD-918 CRD-919 CRD-920 CRD-921 CRD-922 CRD-923 CRD-924 CRD-925 CRD-926 CRD-927 CRD-928 CRD-929 CRD-930 CRD-931 CRD-932 CRD-933 CRD-934 CRD-935 CRD-936 CRD-937 CRD-938 CRD-939 CRD-940 CRD-941 CRD-942 CRD-943 CRD-944 CRD-945 CRD-946 CRD-947 CRD-948 CRD-949 CRD-950 CRD-951 CRD-952 CRD-953 CRD-954 CSS-001 CSS-002 SYSTEM CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CSS CSS DESCRIPTION CRD-V-101 CR 1047 INS LINE VENT CRD-V-101 CR 1447 INS LINE VENT CRD-V-101 CR 1847 INS LINE VENT CRD-V-101 CR 2247 INS LINE VENT CRD-V-101 CR 2647 INS LINE VENT CRD-V-101 CR 3047 INS LINE VENT CRD-V-101 CR 3447 INS LINE VENT CRD-V-101 CR 3847 INS LINE VENT CRD-V-101 CR 4247 INS LINE VENT CRD-V-101 CR 4647 INS LINE VENT CRD-V-101 CR 5047 INS LINE VENT CRD-V-101 CR 5447 INS LINE VENT CRD-V-101 CR 1051 INS LINE VENT CRD-V-101 CR 1451 INS LINE VENT CRD-V-101 CR 1851 INS LINE VENT CRD-V-101 CR 2251 INS LINE VENT CRD-V-101 CR 2651 INS LINE VENT CRD-V-101 CR 3051 INS LINE VENT CRD-V-101 CR 3451 INS LINE VENT CRD-V-101 CR 3851 INS LINE VENT CRD-V-101 CR 4251 INS LINE VENT CRD-V-101 CR 4651 INS LINE VENT CRD-V-101 CR 5051 INS LINE VENT CRD-V-101 CR 1455 INS LINE VENT CRD-V-101 CR 1855 INS LINE VENT CRD-V-101 CR 2255 INS LINE VENT CRD-V-101 CR 2655 INS LINE VENT CRD-V-101 CR 3055 INS LINE VENT CRD-V-101 CR 3455 INS LINE VENT CRD-V-101 CR 3855 INS LINE VENT CRD-V-101 CR 4255 INS LINE VENT CRD-V-101 CR 4655 INS LINE VENT CRD-V-101 CR 1859 INS LINE VENT CRD-V-101 CR 2259 INS LINE VENT CRD-V-101 CR 2659 INS LINE VENT CRD-V-101 CR 3059 INS LINE VENT CRD-V-101 CR 3459 INS LINE VENT CRD-V-101 CR 3859 INS LINE VENT CRD-V-101 CR 4259 INS LINE VENT CRD-P-1A 0/C RESET CRD-P-1B 0/C RESET HPCS-V-4 INJ LINE VLV MAN OPEN LPCS-V-5 INJ LINE VLV~OPEN November 16, 1994 Page 24 of 51 APPENDIX C ATTACHMENT C-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID CSS-003 CSS-004 CSS-005 CSS-006 CSS-007 CSS-008 CWS-001 CWS-002 CWS-003 CWS-004 CWS-005 CWS-006 CWS-007 CWS-008 CWS-009 CWS-010 CWS-011 CWS-012 CWS-013 CWS-014 CWS-015 CWS-016 CWS-017 CWS-018 CWS-019 CWS-020 CWS-021 CWS-022 CWS-023 CWS-024 CWS-025 CWS-026 CWS-027 CWS-028 CWS-029 CWS-030 CWS-031 CWS-032 CWS-033 CWS-034 CWS-035 CWS-036 CWS-037 SYSTEM CSS CSS CSS CSS CSS CSS CWS CWS CWS CWS CWS CWS CWS CWS CWS CWS CWS CWS CWS CWS CWS CWS CWS CWS CWS CWS CWS CWS CWS CWS CWS CWS CWS CWS CWS CWS CWS CWS CWS CWS CWS CWS CWS DESCRIPTION HPCS-V-51 IN CI'MT MANUAL SHUTOFF LPCS-V-51 IN CI'MT MANUAL SHUTOFF HPCS-P-1 0/C RESET HPCS-P-3 0/C RESET LPCS-P-2 0/C RESET LPCS-P-1 0/C RESET CBD-LCV-1 CIRC WTR BLOWDOWN VLV CBD-V-2 CBD-LCV-1 ISOL VLV CBD-V-3 CBD-LCV-1 BYPASS VLV TMU-V-4 TMU S/U LUB WTR SUP VLV TMU-V-5 TMU-LCV-2A ISOL VLV TMU-V-9 TMU-LCV-2A BYP VLV TMU-V-10A SPRAY POND FILL TMU-V-10B SPRAY POND FILL TMU-V-103A WEIR BOX SLUICE GATE TMU-V-103B WEIR BOX SLUICE GATE CW-FN-1 0/C RESET CW-FN-2 0/C RESET CW-FN-3 0/C RESET CW-FN-4 0/C RESET CW-FN-5 0/C RESET CW-FN-6 0/C RESET CW-FN-7 0/C RESET CW-FN-8 0/C RESET CW-FN-9 0/C RESET CW-FN-10 0/C RESET CW-FN-11 0/C RESET CW-FN-12 0/C RESET CW-FN-13 0/C RESET CW-FN-14 0/C RESET CW-FN-15 0/C RESET CW-FN-16 0/C RESET CW-FN-17 0/C RESET CW-FN-18 0/C RESET CW-FN-19 0/C RESET CW-FN-20 0/C RESET CW-FN-21 0/C RESET CW-FN-22 0/C RESET CW-FN-23 0/C RESET CW-FN-24 0/C RESET CW-FN-25 0/C RESET CW-FN-26 0/C RESET CW-FN-27 0/C RESET November 16, 1994 Page 25 of 51 APPENDIX C ATTACHMENT C-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID CWS-038 CWS-039 CWS-040 CWS-041 CWS-042 CWS-043 CWS-044 CWS-045 CWS-046 CWS-047 CWS-048 CWS-049 DEH-001 DEH-002 DEH-003 DEH-004 DEH-005 DEH-006 DGN-001 DGN-002 DGN-003 DGN-004 DGN-005 DGN-006 DGN-007 DGN-008 DGN-009 DON-010 DGN-011 DGN-012 DGN-013 DGN-014 DGN-015 DGN-016 DGN-017 DGN-018 DGN-019 DGN-020 DGN-021 DGN-022 DGN-023 DGN-024 DGN-025 SYSTEM CWS CWS CWS CWS CWS CWS CWS CWS CWS CWS CWS CWS DEH DEH DEH DEH DEH DEH DGN DGN DGN DGN DGN DGN DGN DGN DGN DGN DGN DGN DGN DGN DGN DGN DGN DGN DGN DGN DGN DGN DGN DGN DGN DESCRIPTION CW-FN-28 0/C RESET CW-FN-29 0/C RESET CW-FN-30 0/C RESET CW-FN-31 0/C RESET CW-FN-32 0/C RESET CW-FN-33 0/C RESET CW-FN-34 0/C RESET CW-FN-35 0/C RESET CW-FN-36 0/C RESET TMU-P-1A 0/C RESET TMU-P-1B 0/C RESET TMU-P-1C 0/C RESET DEH PRESS CONTROLLER A OR B SEL MAN TURBINE TRIP AT FRONT STNDRD DEH-P-1A 0/C RESET DEH-P-1B 0/C RESET DEH-FN-1A 0/C RESET DEH-FN-1B 0/C RESET BKR DG1-7 RACKED OUT BKR DG2-8 RACKED OUT BKR 4-DG3 RACKED OUT BKR 4-DG3 DG3 BREAKER CONTROL BKR DG1-7 DG1 BREAKER CONTROL BKR DG2-8 DG2 BREAKER CONTROL DG1 MODE SELECl'EY SWITCH DG2 MODE SELECT KEY SWITCH DG3 MODE SELECT SWITCH DGl LOCKOUT RLY&OVR SPD RESET DG2 LOCKOUT RLY&OVR SPD RESET DG3 LOCKOUT RLY&OVR SPD RESET DG1 EMERGENCY STOP PUSHBUTTON DG2 EMERGENCY STOP PUSHBVITON DG3 EMERGENCY STOP PUSHBVITON DG-1 LOCAL START PUSHBUTI'ON DG-2 LOCAL START PUSHBUTI'ON DG-3 LOCAL START PUSHBUITON DG1 ENGINE CONTROL SELECT DG2 ENGINE CONTROL SELECT DG1 EMERGENCY BYPASS SELECT DG2 EMERGENCY BYPASS SELECT DG1 EXCITATION MODE SELECTOR DG2 EXCITATION MODE SELECTOR DG3 GOVERNOR DROOP SWITCH November 16, 1994 Page 26 of 51 APPENDIX C ATTACHMENT C-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID DGN-026 DGN-027 EPS-001 EPS-002 EPS-003 EPS-004 EPS-005 EPS-006 EPS-007 EPS-008 EPS-009 EPS-010 EPS-011 EPS-012 EPS-013 EPS-014 EPS-015 EPS-016 EPS-017 EPS-018 EPS-019 EPS-020 EPS-021 EPS-022 EPS-023 EPS-024 EPS-025 EPS-026 EPS-027 EPS-028 EPS-029 EPS-030 EPS-031 EPS-032 EPS-033 EPS-034 EPS-035 EPS-036 EPS-037 EPS-038 EPS-039 EPS-040 EPS-041 SYSTEM DGN DGN EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS DESCRIPTION DG1 ENGINE SPEED SELECI'OR DG2 ENGINE SPEED SELECI'OR BATI'ERY BO-1A DISC BATI'ERY BO-1A FUSE BATTERY BO-1B DISC BATI'ERY BO-1B FUSE BATI'ERY BO-2A DISC BATI'ERY BO-2A FUSE BATI'ERY BO-2B DISC BATI'ERY BO-2B FUSE BATTERY B 1-1 DISC BATl'ERY B 1-1 FUSE BATl'ERY B 1-2 DISC BATI'ERY B 1-2 FUSE BATI'ERY B 1-3 OUTPUT BKR 0/C BATI'ERY B 1-7 DISC BATl'ERY B 1-7 FUSE BATI'ERY B2-1 DISC BATI'ERY B2-1 FUSE BKR 52-1-11 0/C RESET BKR 52-1-500S 0/C RESET BKR 52-1-7 0/C RESET BKR 52-11-1 0/C RESET BKR 52-2-21 0/C RESET BKR 52-2-4 0/C RESET BKR 52-21-11 0/C RESET BKR 52-21-2 0/C RESET BKR 52-3-31 0/C RESET BKR 52-3-8 0/C RESET BKR 52-31-21 0/C RESET BKR 52-31-3 0/C RESET BKR 52-5-53 0/C RESET BKR 52-6-63 0/C RESET BKR 52-CTA 0/C RESET BKR 52-CTB 0/C RESET BKR 52N1-1 0/C RESET BKR 52N1-2 0/C RESET BKR 52N1-3 0/C RESET BKR 52N2-5 0/C RESET BKR 52N2-6 0/C RESET BKR 52S-1 0/C RESET BKR 52S-2 0/C RESET BKR 52$-3 0/C RESET November 16, 1994 Page 27 of 51 0
APPENDIX C ATTACHMENT C-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID EPS-042 EPS-043 EPS-044 EPS-045 EPS-046 EPS-047 EPS-048 EPS-049 EPS-050 EPS-051 EPS-052 EPS-053 EPS-054 EPS-055 EPS-056 EPS-057 EPS-058 EPS-059 EPS-060 EPS-061 EPS-062 EPS-063 EPS-064 EPS-065 EPS-066 EPS-067 EPS-068 EPS-069 EPS-070 EPS-071 EPS-072 EPS-073 EPS-074 EPS-075 EPS-076 EPS-077 EPS-078 EPS-079 EPS-080 EPS-081 EPS-082 EPS-083 EPS-084 SYSTEM EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS DESCRIPTION BKR 52S-5 0/C RESET BKR 52$-6 0/C RESET BKR CB-4-2 0/C RESET BKR CB-4-41 0/C RESET BKR CB-LF1A 0/C RESET BKR CB-LF1B 0/C RESET BKR CB-LF2A 0/C RESET BKR CB-LF2B 0/C RESET BKR CB-RPT-3A 0/C RESET BKR CB-RPT-3B 0/C RESET BKR CB-RPTAA 0/C RESET BKR CB-RPT-4B 0/C RESET BKR CB-RRA 0/C RESET BKR CB-RRB 0/C RESET BKR CS-3-500S 0/C RESET BKR CS-7-1 0/C RESET BKR CS-7-71 0/C RESET BKR CS-7-73 0/C RESET BKR CS-7-75/1 0/C RESET BKR CS-7-DG1 0/C RESET BKR CS-75-72 0/C RESET BKR CS-8-3 0/C RESET BKR CS-8-81 0/C RESET BKR CS-8-83 0/C RESET BKR CS-8-85/1 0/C RESET BKR CS-8-DG2 0/C RESET BKR CS-85-82 0/C RESET BKR CS-B-7 0/C RESET BKR CS-B-8 0/C RESET CHARGER CO-1A INPUT BKR 0/C CHARGER CO-1A OUTPUT BKR 0/C CHARGER CO-1B INPUT BKR 0/C CHARGER CO-1B OUTPUT BKR 0/C CHARGER CO-2A INPUT BKR 0/C CHARGER CO-2A OUTPUT BKR 0/C CHARGER CO-2B INPUT BKR 0/C CHARGER CO-2B OUTPUT BKR 0/C CHARGER C 1-1 FUSE CHARGER C 1-1 INPUT BKR 0/C CHARGER Cl-1 INPUT DISC CHARGER Cl-1 OUTPUT BKR 0/C CHARGER Cl-1 OUTPUT DISC CHARGER Cl-2 FUSE November 16, 1994 Page 28 of 51 APPENDIX C ATI ACHMENT C-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACI'IONS LISTING ID EPS-085 EPS-086 EPS-087 EPS-088 EPS-089 EPS-090 EPS-091 EPS-092 EPS-093 EPS-094 EPS-095 EPS-096 EPS-097 EPS-098 EPS-099 EPS-100 EPS-101 EPS-102 EPS-103 EPS-104 EPS-105 EPS-106 EPS-107 EPS-108 EPS-109 EPS-110 EPS-111 EPS-112 EPS-113 EPS-114 EPS-115 EPS-116 EPS-117 EPS-118 EPS-119 EPS-120 EPS-121 EPS-122 EPS-123 EPS-124 EPS-125 EPS-126 EPS-127 SYSTEM EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS DESCRIPTION CHARGER Cl-2 INPUT BKR 0/C CHARGER Cl-2 INPUT DISC CHARGER Cl-2 OUTPUT BKR 0/C CHARGER Cl-2 OUTPUT DISC CHARGER Cl-7 FUSE CHARGER Cl-7 INPUT DISC CHARGER C 1-7 OUTPUT DISC CHARGER Cl-HPCS INPUT BKR 0/C CHARGER Cl-HPCS OUTPUT BKR 0/C CHARGER C2-1 FUSE CHARGER C2-1 INPUT BKR 0/C CHARGER C2-1 INPUT DISC CHARGER C2-1 OUTPUT BKR 0/C CHARGER C2-1 OUTPUT DISC IN1 KIRK KEY IN1 MAINTENANCE SW IN1 STATIC SWITCH INl-CB1 MC-7A NORM INPT AC 0/C IN1-CB2 DP-S2-1 NORM DC 0/C IN1-CB3 INV OUTPUT 0/C IN1-CB4 ALT AC OUT 0/C IN1-MIS MAINT BYPASS 0/C IN2 MANUAL XFER SWITCH IN2 STATIC SWITCH IN2-CB1 lN2 NORM DC BKR 0/C IN3 MANUAL XFER SWITCH IN3 STATIC SWITCH IN3-CB1 IN3 NORM DC BKR 0/C MC-1A DISC DEH-P-1A MC-1A DISC HY-P-A2/3 MC-1A DISC HY-P-B2/3 MC-1A DISC TO-BOP-1 MC-1A DISC TO-EX-1A MC-1A DISC TO-SOBP-1 MC-1B DISC RFT-MOP-1A MC-1B DISC RFT-TNG-1A MC-1E DISC HD-V-15A MC-2B DISC COND-V-135C MC-2C DISC DEH-P-1B MC-2C DISC RFW-V-112B MC-2D DISC SCW-P-2 MC-2D DISC TO-EX-4 MC-2P DISC CAS-C-1 c November 16, 1994 Page 29 of 51 APPENDIX C ATTACHMENT C-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID EPS-128 EPS-129 EPS-130 EPS-131 EPS-132 EPS-133 EPS-134 EPS-135 EPS-136 EPS-137 EPS-138 EPS-139 EPS-140 EPS-141 EPS-142 EPS-143 EPS-144 EPS-145 EPS-146 EPS-147 EPS-148 EPS-149 EPS-150 EPS-151 EPS-152 EPS-153 EPS-154 EPS-155 EPS-156 EPS-157 EPS-158 EPS-159 EPS-160 EPS-161 EPS-162 EPS-163 EPS-164 EPS-165 EPS-166 EPS-167 EPS-168 EPS-169 EPS-170 SYSTEM EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS DESCRIPTION MC-2P DISC RFT-MOP-18 MC-2P DISC RFT-TNG-1B MC-2R DISC BF-1B MC-2R-A DISC COND-V-1408 MC-3A DISC COND-V-140A MC-38 DISC BF-1A MC-38 DISC TG-TNG-1 MC-3C DISC AR-EX-1A MC-3C DISC TG-ASOP-1 MC-4A DISC HPCS-P-3 MC-4A BKR HPCS-V-1 RACKOUT MC-4A BKR HPCS-V-15 RACKOUT MC-4A BKR HPCS-V-4 RACKOUT MC-5L DISC CW-FN-21 MC-5M DISC CW-FN-23 MC-5N DISC FP-P-2A MC-5P DISC CW-FN-25 MC-SQ DISC CW-FN-29 MC-5R DISC CW-V-7 MC-68 DISC TR-68-E MC-6L DISC CW-FN-2 MC-6M DISC CW-FN-14 MC-6N DISC FP-P-28 MC-6P DISC CW-FN-7 MC-6Q DISC CW-FN-11 MC-6R DISC CW-V-4 MC-7A BKR MC-7A-A 0/C MC-7A DISC CAS-C-1A MC-7A DISC IN1 NORM AC MC-7A DISC RFW-V-65A MC-7A DISC RFW-V-658 MC-7A DISC RPS-MG-A MC-7A DISC SW-V-12A MC-7A DISC SW-V-2A MC-7A DISC TR-7A MC-7A DISC TR-7A-C MC-7A-A DISC SW-V-4A MC-78 DISC CIA-V-20 MC-78 DISC CIA-V-30A MC-78 DISC CRA-FN-1A-1 MC-78 DISC CRA-FN-2A-2 MC-78 DISC LPCS-P-2 MC-78 DISC RCIC-P-3 November 16, 1994 Page 30 of 51 APPENDIX C ATTACHMENT C-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID EPS-171 EPS-172 EPS-173 EPS-174 EPS-175 EPS-176 EPS-177 EPS-178 EPS-179 EPS-180 EPS-181 EPS-182 EPS-183 EPS-184 EPS-185 EPS-186 EPS-187 EPS-188 EPS-189 EPS-190 EPS-191 EPS-192 EPS-193 EPS-194 EPS-195 EPS-196 EPS-197 EPS-198 EPS-199 EPS-200 EPS-201 EPS-202 EPS-203 EPS-204 EPS-205 EPS-206 EPS-207 EPS-208 EPS-209 EPS-210 EPS-211 EPS-212 EPS-213 SYSTEM EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS DESCRIPTION MC-78 DISC SLC-P-1A MC-78-A DISC LPCS-V-1 MC-78-A DISC LPCS-V-5 MC-78-A DISC PP-7A-Z MC-78-A DISC RCC-V-5 MC-78-A DISC RHR-FCV-64A MC-78-A DISC RHR-V-24A MC-78-A DISC RHR-V-27A MC-78-A DISC RHR-V-42A MC-78-A DISC RHR-V-4A MC-78-A DISC RHR-V-53A MC-78-A DISC RHR-V-538 MC-78-A DISC RHR-V-6A MC-78-8 DISC RHR-V-3A MC-78-8 DISC SGT-FN-1A-1 MC-78-8 DISC SGT-FN-18-1 MC-78-8 DISC SGT-V-3A-1 MC-7C DISC RRA-FN-8 MC-7C DISC RRC-V-67A MC-7C-A DISC CN-V-51 MC-7C-8 DISC TSW-V-64A MC-7E DISC WEA-FN-lA MC-7F DISC IN1 ALT SUPP MC-7F DISC WEA-FN-53A MC-7F DISC WMA-FN-51A MC-7F DISC WMA-FN-53A MC-7F DISC WMA-FN-54A MC-7R/MC-8R DISC PP-78 MC-8A BKR MC-8A-A 0/C MC-8A DISC CAS-C-18 MC-8A DISC CJW-P-18 MC-8A DISC RPS-MG-2 MC-8A DISC SW-V-128 MC-8A DISC SW-V-28 MC-8A DISC TR-8A MC-8A-A DISC SW-V-48 MC-88 DISC CRA-FN-18-1 MC-88 DISC CRA-FN-18-2 MC-88 DISC CRA-FN-28-1 MC-88 DISC CRA-FN-28-2 MC-88 DISC PP-8A-Z MC-88 DISC RHR-P-3 MC-88 DISC SLC-P-18 November 16, 1994 Page 31 of 51 APPENDIX C ATTACHMENT C-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID EPS-214 EPS-215 EPS-216 EPS-217 EPS-218 EPS-219 EPS-220 EPS-221 EPS-222 EPS-223 EPS-224 EPS-225 EPS-226 EPS-227 EPS-228 EPS-229 EPS-230 EPS-231 EPS-232 EPS-233 EPS-234 EPS-235 EPS-236 EPS-237 EPS-238 EPS-239 EPS-240 EPS-241 EPS-242 EPS-243 EPS-244 EPS-245 EPS-246 EPS-247 EPS-248 EPS-249 EPS-250 EPS-251 EPS-252 EPS-253 EPS-254 EPS-255 EPS-256 SYSTEM EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS DESCRIPTION CKOUT KOUT MC-8B-A DISC RCIC-V-63 MC-8B-A DISC RHR-V-16B MC-8B-A DISC RHR-V-17B MC-8B-A DISC RHR-V-24B MC-8B-A DISC RHR-V-27B MC-8B-A DISC RHR-V-42B MC-8B-A DISC RHR-V-42C MC-8B-A DISC RHR-V-4B MC-8B-A DISC RHR-V-4C MC-8B-A DISC RHR-V-64B MC-8B-A DISC RHR-V-64C MC-8B-A DISC RHR-V-6B MC-8B-A DISC RHR-V-9 MC-8B-A DISC RWCU-V-1 MC-8B-B DISC RHR-V-3B MC-8B-B DISC SGT-FN-1A-2 MC-8B-B DISC SGT-FN-1B-2 MC-8B-B DISC SGT-V-3A-2 MC-8C BKR RWCU-P-1A RA MC-8C BKR RWCU-P-1B RAC MC-8C DISC HY-P-Al/3 MC-8C DISC RRA-FN-9 MC-8C DISC RRC-V-23A MC-8C-A DISC HY-P-B1/3 MC-8C-B DISC TSW-V-64B MC-8C-B DISC TSW-V-64C MC-8E DISC WEA-FN-1B MC-8E DISC WEA-FN-1C MC-8F DISC WEA-FN-53B MC-8F DISC WMA-FN-51B MC-8F DISC WMA-FN-53B MC-8F DISC WMA-FN-54B MC-S1-1D DISC RCC-V-6 MC-S1-1D DISC RCIC-V-10 MC-S1-1D DISC RCIC-V-68 MC-S1-1D DISC RCIC-V-8 MC-S1-2D DISC CAC-V-11 MC-S2-1A DISC RCIC-P-4 MC-S2-1A DISC RCIC-V-1 MC-S2-1A DISC RCIC-V-13 MC-S2-1A DISC RCIC-V-45 MC-S2-1A DISC RHR-V-8 MC-S2-1A DISC RWCU-V-4 November 16, 1994 Page 32 of 51 APPENDIX C ATTACHMENT C-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID EPS-257 EPS-258 EPS-259 BPS-260 EPS-261 EPS-262 EPS-263 BPS-264 EPS-265 EPS-266 EPS-267 EPS-268 EPS-269 EPS-270 EPS-271 EPS-272 EPS-273 EPS-274 EPS-275 EPS-276 EPS-277 EPS-278 EPS-279 EPS-280 EPS-281 EPS-282 BPS-283 EPS-284 EPS-285 EPS-286 EPS-287 EPS-288 EPS-289 EPS-290 EPS-291 EPS-292 EPS-293 EPS-294 EPS-295 EPS-296 EPS-297 EPS-298 EPS-299 SYSTEM EPS EPS EPS EPS EPS EPS EPS EPS BPS EPS EPS BPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS DESCRIPTION MC-S2-1B DISC RFT-EOP-1A MC-S2-1B DISC RFT-EOP-1B MC-S2-1B DISC TG-ASOBP-1 MC-S2-1B DISC TO-P-1 PP-7A DISC C0-1A,1B PP-7A DISC IN-3 PP-8A DISC C0-2A,2B PP-8A DISC IN-2 RPS-CB-2A RPS-A TRIP SYS BKR 0/C RPS-CB-2B RPS-B TRIP SYS BKR 0/C RPS-CB-3A PWR RNG DIV 1 BKR 0/C RPS-CB-3B PWR RNG DIV 2 BKR 0/C RPS-CB-5A NS4 INBD BKR 0/C RPS-CB-5B NS4 OTBD BKR 0/C RPS-CB-6A PRM DIV 1 BKR 0/C RPS-CB-6B PRM DIV 2 BKR 0/C RPS-CB-7A NS4 OTBD BKR 0/C RPS-CB-7B NS4 INBD BKR 0/C RPS-CB-CB1 ALT SUP BKR 0/C RPS-CB-MG1 MG-A OUTPT BKR 0/C RPS-CB-MG2 MG-B OUTPT BKR 0/C RPS-EPA-3A RPS-A EPA-3A 0/C RPS-EPA-3B RPS-B EPA-3B 0/C RPS-EPA-3C RPS-A EPA-3C 0/C RPS-EPA-3D RPS-B EPA-3D 0/C RPS-EPA-3E ALT RPS BPA-3E 0/C RPS-EPA-3F ALT RPS EPA-3F 0/C RPS-MS-1 RPS-MG-A START SW RPS-MS-2 RPS-MG-B START SW S 1-1 DISC DP-Sl-1A S 1-1 DISC MC-S 1-1D S1-2 DISC MC-S 1-2D S1-3 DISC 4KV BKR CONTROL S004 S1-7 DISC DP-Sl-2C S2-1 DISC IN-1 S2-1 DISC MC-S2-1A S2-1 DISC MC-S2-1B SH-05 BKR 5-53 RACKOUT SH-05 BKR CTA RACKOUT SH-05 BKR N2-5 RACKOUT SH-05 BKR RRA RACKOUT SH-05 BKR S-5 RACKOUT SH-05 PT FUSE SH-5 November 16, 1994 Page 33 of 51 APPENDIX C ATTACHMENT C-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID EPS-300 EPS-301 EPS-302 EPS-303 EPS-304 EPS-305 EPS-306 EPS-307 EPS-308 EPS-309 EPS-310 EPS-311 EPS-312 EPS-313 EPS-314 EPS-315 EPS-316 EPS-317 EPS-318 EPS-319 EPS-320 EPS-321 EPS-322 EPS-323 EPS-324 EPS-325 EPS-326 EPS-327 EPS-328 EPS-329 EPS-330 EPS-331 EPS-332 EPS-333 EPS-334 EPS-335 EPS-336 EPS-337 EPS-338 EPS-339 EPS-340 EPS-341 EPS-342 SYSTEM EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS DESCRIPTION SH-06 BKR 6-63 RACKOUT SH-06 BKR CTB RACKOUT SH-06 BKR N2-6 RACKOUT SH-06 BKR RRB RACKOUT SH-06 BKR S-6 RACKOUT SH-06 PT FUSE SH-6 SH-09 BKR RPT-3A RACKOUT SH-10 BKR RPT-3B RACKOUT SH-ll BKR RPT-4A RACKOUT SH-12 BKR RPT-4B RACKOUT SH-13 BKR LF-2A RACKOUT SH-14 BKR LF-2B RACKOUT SL-11 BKR 11-1 RACKOUT SL-11 BKR AR-P-1A RACKOUT SL-21 BKR 21-11 RACKOUT SL-21 BKR 21-2 RACKOUT SL-21 BKR AR-P-1B RACKOUT SL-31 BKR 31-21 RACKOUT SL-31 BKR 31-3 RACKOUT SL-31 BKR MC-SC 0/C SL-51 BKR MC-5M 0/C SL-'S2 BKR MC-5Q 0/C SL-53 BKR WOA-FN-1A RACKOUT SL-61 BKR MC-6M 0/C SL-62 BKR MC-6Q 0/C SL-63 BKR WOA-FN-1B RACKOUT SL-71 BKR MC-7A-B 0/C SL-71 BKR MC-7B 0/C SL-71 BKR MC-7C 0/C SL-71 BKR RCC-P-1A RACKOUT SL-71 BKR REA-FN-1A RACKOUT SL-73 BKR MC-7A 0/C SL-73 BKR MC-7E 0/C SL-73 BKR MC-7F 0/C SL-73 BKR ROA-FN-1A RACKOUT SL-81 BKR MC-8B 0/C SL-81 BKR MC-8C 0/C SL-81 BKR RCC-P-1B RACKOUT SL-81 BKR RCC-P-1C RACKOUT SL-83 BKR MC-8A 0/C SL-83 BKR MC-8E 0/C SL-83 BKR MC-8F 0/C SL-83 BKR REA-FN-1B RACKOUT November 16, 1994 Page 34 of 51 APPENDIX C ATTACHMENT C-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID EPS-343 EPS-344 EPS-345 EPS-346 EPS-347 EPS-348 EPS-349 EPS-350 EPS-351 EPS-352 EPS-353 EPS-354 EPS-355 EPS-356 EPS-357 EPS-358 EPS-359 EPS-360 EPS-361 EPS-362 EPS-363 EPS-364 EPS-365 EPS-366 EPS-367 EPS-368 EPS-369 EPS-370 EPS-371 EPS-372 EPS-373 EPS-374 EPS-375 EPS-376 EPS-377 EPS-378 EPS-379 EPS-380 EPS-381 EPS-382 EPS-383 EPS-384 EPS-385 SYSTEM EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS DESCRIPTION SL-83 BKR ROA-FN-1B RACKOUT SM-1 BKR 1-11 RACKOUT SM-1 BKR 1-500S RACKOUT SM-1 BKR 1-7 RACKOUT SM-1 BKR C1A RACKOUT SM-1 BKR CB2A RACKOUT SM-1 BKR CW1A RACKOUT SM-1 BKR LF-1A RACKOUT SM-1 BKR Nl-1 RACKOUT SM-1 BKR S-1 RACKOUT SM-1 PT FUSE SM-1 SM-2 BKR 2-21 RACKOUT SM-2 BKR 2-4 RACKOUT SM-2 BKR C1B RACKOUT SM-2 BKR CB2B RACKOUT SM-2 BKR CW1B RACKOUT SM-2 BKR Nl-2 RACKOUT SM-2 BKR S-2 RACKOUT SM-2 PT FUSE SM-2 SM-3 BKR 3-31 RACKOUT SM-3 BKR 3-500S RACKOUT SM-3 BKR 3-8 RACKOUT SM-3 BKR C1C RACKOUT SM-3 BKR CB2C RACKOUT SM-3 BKR CW1C RACKOUT SM-3 BKR LF-1B RACKOUT SM-3 BKR Nl-3 RACKOUT SM-3 BKR S-3 RACKOUT SM-3 PT FUSE SM-3 SM-4 BKR 4-2 RACKOUT SM-4 BKR 4P1 RACKOUT SM-4 BKR HPCS RACKOUT SM-7 BKR 7-1 RACKOUT SM-7 BKR 7-71 RACKOUT SM-7 BKR 7-73 RACKOUT SM-7 BKR 7-75/1 RACKOUT SM-7 BKR 7-75/2 RACKOUT SM-7 BKR 7-DG1 RACKOUT SM-7 BKR B-7 RACKOUT SM-7 BKR CRD-1A RACKOUT SM-7 BKR LPCS RACKOUT SM-7 BKR RHR-2A RACKOUT SM-7 BKR SW-1A RACKOUT November 16, 1994 Page 35 of 51 APPENDIX C ATTACHMENT C-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID EPS-386 EPS-387 EPS-388 EPS-389 EPS-390 EPS-391 EPS-392 EPS-393 EPS-394 EPS-395 EPS-396 EPS-397 EPS-398 EPS-399 EPS-400 EPS-401 EPS-402 EPS-403 EPS-404 EPS-405 EPS-406 EPS-407 EPS-408 EPS-409 EPS-410 EPS-411 EPS-412 EPS-413 EPS-414 EPS-415 FPC-001 FPC-002 FPC-003 FPC-004 FPC-005 FPC-006 FPC-007 FPC-008 FPC-009 FPC-010 FPC-011 FPC-012 FPC-013 SYSTEM EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS FPC FPC FPC FPC FPC FPC FPC FPC FPC FPC FPC FPC FPC DESCRIPTION SM-72 BKR TMU-1A RACKOUT SM-75 BKR 75-72 RACKOUT SM-75 BKR TSW-lA RACKOUT SM-8 BKR 8-3 RACKOUT SM-8 BKR 8-81 RACKOUT SM-8 BKR 8-83 RACKOUT SM-8 BKR 8-85/1 RACKOUT SM-8 BKR 8-85/2 RACKOUT SM-8 BKR 8-DG2 RACKOUT SM-8 BKR B-8 RACKOUT SM-8 BKR CRD-1B RACKOUT SM-8 BKR RHR-2B RACKOUT SM-8 BKR RHR-2C RACKOUT SM-8 BKR SW1B RACKOUT SM-82 BKR TMU-1B RACKOUT SM-85 BKR 85-82 RACKOUT SM-85 BKR TSW-1B RACKOUT TMU-1C BKR RACKOUT TMU-1C BUS SELECT IN1-BTB MAINT BYPASS 0/C IN1-MBP MAINT BYPASS 0/C RRC-M-1A1 0/C RESET RRC-M-1B1 0/C RESET RPS-MG-1 0/C RESET RPS-MG-2 0/C RESET BKR 7-75/2 BKR 8-85/2 MC-8AA DISC MS-V-146 E-RMS-7FDA, IN-3 POWER E-RMS-8FDA, IN-2 POWER FPC-V-148 CONDENSER RETURN FPC-V-114 PUMP X CONN FPC-V-115A HX BYPASS FPC-V-115B HX BYPASS FPC-V-116A HX INLET ISOL FPC-V-116B HX INLET ISOL FPC-V-118A HX OUTLET ISOL FPC-V-118B HX OUTLET ISOL FPC-V-143 RX WELL RECIRC FPC-V-141 X-TIE TO RHR FPC-V-131 GATE DRAIN FPC-V-105 WELL DRAIN FPC-V-130 SURGE TANK DRAIN November 16, 1994 Page 36 of 51 APPENDIX C ATTACHMENT C-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID FPC-014 FPC-015 FPC-016 FPC-017 FPC-018 FPC-019 FPS-001 FPS-002 FPS-003 FPS-004 FPS-005 FPS-006 FPS-007 FPS-008 FPS-009 FPS-010 FPS-011 FPS-012 FPT-001 FPT-002 FPT-003 FPT-004 FPT-005 FPT-006 FPT-007 FPT-008 FPT-009 FPT-010 FPT-011 FPT-012 FPT-013 FPT-014 FWH-001 FWH-002 FWH-003 FWH-004 FWH-005 FWH-006 FWH-007 FWH-008 FWH-009 FWH-010 FWH-011 SYSTEM FPC FPC FPC FPC FPC FPC FPS FPS FPS FPS FPS FPS FPS FPS FPS FPS FPS FPS FPT FPT FPT FPT FPT FPT FPT FPT FPT FPT FPT FPT FPT FWH FWH FWH FWH FWH FWH FWH FWH FWH FWH FWH DESCRIPTION FPC-V-142 FP RECIRC FUEL POOL PLUG POSITION FPC-V-147 WETWELL CLEANUP ISOL FPC-P-1A 0/C RESET FPC-P-1B 0/C RESET FPC-P-3 0/C RESET FP-P-1 DIESEL FIRE PUMP FP-P-2A ELECTRIC FIRE PUMP FP-P-2B ELECTRIC FIRE PUMP FP-P-3 JOCKEY PUMP FP-P-110 DIESEL FIRE PUMP FP-P-111 JOCKEY PUMP FP-P-111 0/C RESET FP-P-2A 0/C RESET FP-P-2B 0/C RESET FP-P-3 0/C RESET FP-P-1 0/C RESET FP-P-110 0/C RESET TO-V-62A RFPT A LO CLR SEL 2A/B TO-V-62B RFPT B LO CLR SEL 2C/D RFT-P-AOPA 0/C RESET RFT-P-AOPB 0/C RESET RFT-P-EOPA 0/C RESET RFT-P-EOPB 0/C RESET RFT-P-MOPA 0/C RESET RFT-P-MOPB 0/C RESET RFT-TNG-1A 0/C RESET RFT-TNG-1B 0/C RESET TO-EX-3A 0/C RESET TO-EX-3B 0/C RESET WEDGE REMOVED/INSTALL RFT-TNG-1A WEDGE REMOVED/INSTALL RFT-TNG-1B HV-V-2D BYP HV-V-23D STRTUP VNT HV-V-2C BYP HV-V-23C STRTUP VNT HV-V-2H BYP HV-V-23H STRTUP VNT HV-V-2G BYP HV-V-23G STRTUP VNT HV-V-2L BYP HV-V-23L STRTUP VNT HV-V-2K BYP HV-V-23K STRTUP VNT HV-V-2I BYP HV-V-23I STRTUP VNT HV-V-2J BYP HV-V-23J STRTUP VNT HV-V-35A BYP HV-V-37A STRTUP VNT HV-V-35B BYP HV-V-37B STRTUP VNT HV-V-2A BYP HV-V-23A STRTUP VNT November 16, 1994 Page 37 of 51 APPENDIX C ATTACHMENT C-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID FWH-012 FWH-013 FWH-014 FWH-015 FWH-016 FWH-017 GEA-001 GEA-002 GEA-003 GEA-004 GEA-005 GEA-006 GEA-007 GEA-008 GEA-009 GEA-010 6EA-011 GEA-012 GEA-013 GEA-014 GEA-015 GEA-016 GEA-017 GEA-018 GEA-019 GEA-020 GEA-021 GEA-022 GEA-023 6EA-024 GEA-025 6EA-026 GEA-027 GEA-028 GEA-029 GEA-030 GEA-031 6 EN-001 GEN-002 GEN-003 GEN-004 GEN-005 GEN-006 SYSTEM FWH FWH FWH FWH FWH FWH GEA GEA GEA GEA GEA GEA GEA GEA GEA GBA GEA GEA GBA GEA GEA GEA GEA GEA GEA GEA GEA GEA GEA GBA GEA GEA GBA GEA GEA GEA GEA GEN GEN GEN GEN GEN GEN DESCRIPTION HV-V-2B BYP HV-V-23B STRTUP VNT HV-V-2E BYP HV-V-23E STRTUP VNT HV-V-2F BYP HV-V-23F STRTUP VNT HV-V-34A BYP HV-V-36A STRTUP VNT HV-V-34B BYP HV-V-36B STRTUP VNT MSR HD-TKS NON-RETURN VLV RESET SO-V-232 SEAL OIL TANK ISOL SCW-F05 HX 2 OUTLET SCW-V406 HX 1 OUTLET ISOLATION SCW-V-407 HX 2 INLET SCW-F08 HX 2 INLET ISOLATION SCW-V409 HX 1 INLET H2-V-7 H2 ISOLATION VALVE SCW-P-1A PUMP AUTO/START/STOP SCW-P-1B PUMP AUTO/START/STOP TG-HSOP H2 SEAL OIL PUMP TG-ASOP AIR SIDE SEAL OIL PUMP TG-ASOBP AIR SIDE SO B/U PUMP H2-V-52 H2 SUPPLY VALVE H2-V-34 H2 VENT VALVE C02-V-60 C02 SUPPLY VALVE C02-V-6 C02 ISOLATION IBD-AD-13B FRESH AIR INTAKE IBD-AD-2 VENT TO ATMOSPHERE IBD-AD-13A FRESH AIR INTAKE STATOR CLG WTR DEMIN A IN SERV STATOR CLG WTR DEMIN B IN SERV SO-V-231 SEAL OIL TANK DRAIN SCW-V-424 DEMIN BYPASS IBD-FN-1A 0/C RESET IBD-FN-1B 0/C RESET SCW-P-1A 0/C RESET SCW-P-1B 0/C RESET TG-ASOP 0/C RESET TG-ASOBP 0/C RESET TG-HSOP 0/C RESET TO-EX-4 0/C RESET MOD BANK 89-P 1/P3 E-MO-DIS189
¹1 MTR OP DISC E-MO-DIS189
¹2 MTR OP DISC E-MO-DIS289
¹1 MTR OP DISC E-MO-DIS289
¹2 MTR OP DISC GRID BUS SELECT November 16, 1994 Page 38 of 51 APPENDIX C ATTACHMENT C-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID GEN-007 GEN-008 GEN-009 LDS-001 LDS-002 MSL-001 MSL-002 MSL-003 MSL-004 NIS-001 NIS-002 NIS-003 NIS-004 NIS-005 NIS-006 NIS-007 NIS-008 NIS-009 NIS-010 NIS-011 NIS-012 NIS-013 NIS-014 NIS-015 NIS-016 NIS-017, NIS-018 NIS-019 NIS-020 NIS-021 NIS-022 NIS-023 NIS-024 NIS-025 NIS-026 NIS-027 NIS-028 NIS-029 NIS-030 NIS-031 NIS-032 NIS-033 NIS-034 SYSTEM GEN GEN GEN LDS LDS MSL MSL MSL MSL NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS DESCRIPTION MAIN GENERATOR DISCONNECT LINK BKR 4885 500KV BKR¹1 LOCAL CONT BKR 4888 500KV BKR¹2 LOCAL CONT LPDS SINGLE INPUT (SPURIOUS)
LPDS SUSTAINED INPUT MSLC-V-11 AIR INLET MSLC-V-12 AIR INLET MSLC-FN-1 0/C RESET MSLC-FN-2 0/C RESET APRM A GAIN ADJ FACTOR 0-10 APRM B GAIN ADJ FACTOR 0-10 APRM C GAIN ADJ FACTOR 0-10 APRM D GAIN ADJ FACTOR 0-10 APRM E GAIN ADJ FACI'OR 0-10 APRM F GAIN ADJ FACl OR 0-10 LPRM 08-17A BYPASS/OPERATE SWTCH LPRM 08-17C BYPASS/OPERATE SWTCH LPRM 08-17D BYPASS/OPERATE SWTCH LPRM 08-25A BYPASS/OPERATE SWTCH LPRM 08-25B BYPASS/OPERATE SWTCH LPRM 08-25D BYPASS/OPERATE SWTCH LPRM 08-33A BYPASS/OPERATE SWTCH LPRM 08-33B BYPASS/OPERATE SWTCH LPRM 08-33C BYPASS/OPERATE SWTCH LPRM 0841B BYPASS/OPERATE SWTCH LPRM 0841C BYPASS/OPERATE SWTCH LPRM 0841D BYPASS/OPERATE SWTCH LPRM 08-49A BYPASS/OPERATE SWTCH LPRM 08-49C BYPASS/OPERATE SWTCH LPRM 0849D BYPASS/OPERATE SWTCH LPRM 16-09B BYPASS/OPERATE SWTCH LPRM 16-09C BYPASS/OPERATE SWTCH LPRM 16-09D BYPASS/OPERATE SWTCH LPRM 16-17A BYPASS/OPERATE SWTCH LPRM 16-17B BYPASS/OPERATE SWTCH LPRM 16-17C BYPASS/OPERATE SWTCH LPRM 16-25A BYPASS/OPERATE SWTCH LPRM 16-25B BYPASS/OPERATE SWTCH LPRM 16-25D BYPASS/OPERATE SWTCH LPRM 16-33A BYPASS/OPERATE SWTCH LPRM 16-33C BYPASS/OPERATE SWTCH LPRM 16-33D BYPASS/OPERATE SWTCH LPRM 16-41B BYPASS/OPERATE SWTCH November 16, 1994 Page 39 of 51 APPENDIX C ATTACHMENT C-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID NIS-035 NIS-036 NIS-037 NIS-038 NIS-039 NIS-040 NIS-041 NIS-042 NIS-043 NIS-044 NIS-045 NIS-046 NIS-047 NIS-048 NIS-049 NIS-050 NIS-051 NIS-052 NIS-053 NIS-054 NIS-055 NIS-056 NIS-057 NIS-058 NIS-059 NIS-060 NIS-061 NIS-062 NIS-063 NIS-064 NIS-065 NIS-066 NIS-067 NIS-068 NIS-069 NIS-070 NIS-071 NIS-072 NIS-073 NIS-074 NIS-075 NIS-076 NIS-077 SYSTEM NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS DESCRIPTION LPRM 16-41C BYPASS/OPERATE SWTCH LPRM 16-41D BYPASS/OPERATE SWTCH LPRM 1649A BYPASS/OPERATE SWTCH LPRM 1649B BYPASS/OPERATE SWTCH LPRM 1649C BYPASS/OPERATE SWTCH LPRM 16-57A BYPASS/OPERATE SWTCH LPRM 16-57B BYPASS/OPERATE SWTCH LPRM 16-57D BYPASS/OPERATE SWTCH LPRM 24-09A BYPASS/OPERATE SWTCH LPRM 24-09B BYPASS/OPERATE SWTCH LPRM 24-09D BYPASS/OPERATE SWTCH LPRM 24-17A BYPASS/OPERATE SWTCH LPRM 24-17B BYPASS/OPERATE SWTCH LPRM 24-17C BYPASS/OPERATE SWTCH LPRM 24-25B BYPASS/OPERATE SWTCH LPRM 24-25C BYPASS/OPERATE SWTCH LPRM 24-25D BYPASS/OPERATE SWTCH LPRM 24-33A BYPASS/OPERATE SWTCH LPRM 24-33C BYPASS/OPERATE SWTCH LPRM 24-33D BYPASS/OPERATE SWTCH LPRM 2441A BYPASS/OPERATE SWTCH LPRM 24-41B BYPASS/OPERATE SWTCH LPRM 24-41D BYPASS/OPERATE SWTCH LPRM 24-49A BYPASS/OPERATE SWTCH LPRM 24-49B BYPASS/OPERATE SWTCH LPRM 24-49C BYPASS/OPERATE SWTCH LPRM 24-57B BYPASS/OPERATE SWTCH LPRM 24-57C BYPASS/OPERATE SWTCH LPRM 24-57D BYPASS/OPERATE SWTCH LPRM 32-09A BYPASS/OPERATE SWTCH LPRM 32-09B BYPASS/OPERATE SWTCH LPRM 32-09D BYPASS/OPERATE SWTCH LPRM 32-17A BYPASS/OPERATE SWTCH LPRM 32-17C BYPASS/OPERATE SWTCH LPRM 32-17D BYPASS/OPERATE SWTCH LPRM 32-25B BYPASS/OPERATE SWTCH LPRM 32-25C BYPASS/OPERATE SWTCH LPRM 32-25D BYPASS/OPERATE SWTCH LPRM 32-33A BYPASS/OPERATE SWTCH LPRM 32-33B BYPASS/OPERATE SWTCH LPRM 32-33C BYPASS/OPERATE SWTCH LPRM 32-41A BYPASS/OPERATE SWTCH LPRM 32-41B BYPASS/OPERATE SWTCH November 16, 1994 Page 40 of 51 ID APPENDIX C ATTACHMENT C-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING SYSTEM DESCRIPTION NIS-078 NIS-079 NIS-080 NIS-081 NIS-082 NIS-083 NIS-084 NIS-085 NIS-086 NIS-087 NIS-088 NIS-089 NIS-090 NIS-091 NIS-092 NIS-093 NIS-094 NIS-095 NIS-096 NIS-097 NIS-098 NIS-099 NIS-100 NIS-101 NIS-102 NIS-103 NIS-104 NIS-105 NIS-106 NIS-107 NIS-108 NIS-109 NIS-110 NIS-111 NIS-112 NIS-113 NIS-114 NIS-115 NIS-116 NIS-117 NIS-118 NIS-119 NIS-120 NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NISLPRM 32-41D BYPASS/OPERATE SWTCH LPRM 32-49A BYPASS/OPERATE SWTCH LPRM 32-49C BYPASS/OPERATE SWTCH LPRM 32-49D BYPASS/OPERATE SWTCH LPRM 32-57B BYPASS/OPERATE SWTCH LPRM 32-57C BYPASS/OPERATE SWTCH LPRM 32-57D BYPASS/OPERATE SWTCH LPRM 40-09B BYPASS/OPERATE SWTCH LPRM 40-09C BYPASS/OPERATE SWTCH LPRM 40-09D BYPASS/OPERATE SWTCH LPRM 40-17A BYPASS/OPERATE SWTCH LPRM 40-17C BYPASS/OPERATE SWTCH LPRM 40-17D BYPASS/OPERATE SWTCH LPRM 40-25A BYPASS/OPERATE SWTCH LPRM 40-25B BYPASS/OPERATE SWTCH LPRM 40-25D BYPASS/OPERATE SWTCH LPRM 40-33A BYPASS/OPERATE SWTCH LPRM 40-33B BYPASS/OPERATE SWTCH LPRM 40-33C BYPASS/OPERATE SWTCH LPRM 40-41B BYPASS/OPERATE SWTCH LPRM 4041C BYPASS/OPERATE SWTCH LPRM 40-41D BYPASS/OPERATE SWTCH LPRM 40-49A BYPASS/OPERATE SWTCH LPRM 40-49C BYPASS/OPERATE SWTCH LPRM 40-49D BYPASS/OPERATE SWTCH LPRM 40-57A BYPASS/OPERATE SWTCH LPRM 40-57B BYPASS/OPERATE SWTCH LPRM 40-57D BYPASS/OPERATE SWTCH LPRM 48-09B BYPASS/OPERATE SWTCH LPRM 48-09C BYPASS/OPERATE SWTCH LPRM 48-09D BYPASS/OPERATE SWTCH LPRM 48-17A BYPASS/OPERATE SWTCH LPRM 48-17B BYPASS/OPERATE SWTCH LPRM 48-17C BYPASS/OPERATE SWTCH LPRM 48-25A BYPASS/OPERATE SWTCH LPRM 48-25B BYPASS/OPERATE SWTCH LPRM 48-25D BYPASS/OPERATE SWTCH LPRM 48-33A BYPASS/OPERATE SWTCH LPRM 48-33C BYPASS/OPERATE SWTCH LPRM 48-33D BYPASS/OPERATE SWTCH LPRM 48-41B BYPASS/OPERATE SWTCH LPRM 48P1C BYPASS/OPERATE SWTCH LPRM 48-41D BYPASS/OPERATE SWTCH November 16, 1994 Page 41 of 51 APPENDIX C ATTACHMENT C-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID NIS-121 NIS-122 NIS-123 NIS-124 NIS-125 NIS-126 NIS-127 NIS-128 NIS-129 NIS-130 NIS-131 NIS-132 NIS-133 NIS-134 NIS-135 OED-001 OED-002 OED-003 OGS-001 OGS-002 OGS-003 OGS-004 OGS-005 OGS-006 OGS-007 0GS-008 0GS-009 OGS-010 OGS-011 OGS-012 OGS-013 OGS-014 OGS-015 OGS-016 OGS-017 OGS-018 OGS-019 0GS-020 0GS-021 OGS-022 OGS-023 OGS-024 OGS-025 SYSTEM NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS OED OED OED OGS OGS OGS OGS OGS OGS OGS OGS OGS OGS OGS OGS OGS OGS OGS OGS OGS OGS OGS OGS OGS OGS OGS OGS OGS DESCRIPTION LPRM 48-49A BYPASS/OPERATE SWTCH LPRM 48-49B BYPASS/OPERATE SWTCH LPRM 48-49C BYPASS/OPERATE SWTCH LPRM 56-17A BYPASS/OPERATE SWTCH LPRM 56-17B BYPASS/OPERATE SWTCH LPRM 56-17C BYPASS/OPERATE SWTCH LPRM 56-25B BYPASS/OPERATE SWTCH LPRM 56-25C BYPASS/OPERATE SWTCH LPRM 56-25D BYPASS/OPERATE SWTCH LPRM 56-33A BYPASS/OPERATE SWTCH LPRM 56-33C BYPASS/OPERATE SWTCH LPRM 56-33D BYPASS/OPERATE SWTCH LPRM 56-41A BYPASS/OPERATE SWTCH, LPRM 5641B BYPASS/OPERATE SWTCH LPRM 56-41D BYPASS/OPERATE SWTCH 115 KV LINE MAN DISC SWITCH 230 KV STARTUP BKR-CB-TRS BPA RELAY 86/LR STATUS OG-V-4B RECOMBINER AIR PURGE OG-V-4A RECOMBINER AIR PURGE GY-V-80A GLYCOL SUP OG-HX-10A GY-V-80B GLYCOL SUP OG-HX-10B GY-V-99A GLYCOL SUP OG-HX-31A GY-V-99B GLYCOL SUP OG-HX-31B OG-V-42 MOIST SEP SEAL WTR FILL OG-V-35 CLR COND SEAL WTR FILL OG-V-30 HOLDUP LN SEAL FILL OG-V-51A INLET ISOL TO OG-HX-11A OG-V-51B INLET ISOL TO OG-HX-11B OG-V-51C INLET ISOL TO OG-HX-11C OG-V-51D INLET ISOL'TO OG-HX-11D OG-V-102A DRYER CH LOOP SEAL FIL OG-V-102B DRYER CH LOOP SEAL FIL AR-V-18 GLND SEAL STM COND PRESS MS-PC-11A S JAE A CTRL A/M SEL MS-PC-11A S JAE A CTRL AUTO SETPT MS-PC-11B SJAE B CTRL A/M SEL MS-PC-11B SJAE B CI'RL AUTO SETPT MS-PC-16A S JAE A CTRL A/M SEL MS-PC-16A S JAE A CTRL AUTO SETPT MS-PC-16B S JAE B CTRL A/M SEL MS-PC-16B S JAE B CTRL AUTO SETPT MS-PC-17A S JAE A CTRL A/M SEL November 16, 1994 Page 42 of 51 APPENDIX C ATTACHMENT C-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID OGS-026 OGS-027 OGS-028 OGS-029 OGS-030 0GS-031 OGS-032 0GS-033 OGS-034 0GS-035 OGS-036 OGS-037 OGS-038 OGS-039 OGS-040 OGS-041 OGS-042 OGS-043 OGS-044 OGS-045 OGS-046 OGS-047 OGS-048 OGS-049 OGS-050 OGS-051 OGS-052 OGS-053 OGS-054 OGS-055 OGS-056 OGS-057 PCN-001 PCN-002 PCN-003 PCN-004 PCN-005 PCN-006 PCN-007 PCN-008 PCN-009 PCN-010 PCN-011 SYSTEM OGS OGS OGS OGS OGS OGS OGS OGS OGS OGS OGS OGS OGS OGS OGS OGS OGS OGS OGS OGS OGS OGS OGS OGS OGS OGS OGS OGS OGS OGS OGS OGS PCN PCN PCN PCN PCN PCN PCN PCN PCN PCN PCN DESCRIPTION MS-PC-17A S JAE A CTRL AUTO SETPT MS-PC-17B S JAE B CI'Iu.A/M SEL MS-PC-17B SJAE B CTRL AUTO SETPT OG DRYER A STATUS OG DRYER B STATUS OG DRYER C STATUS OG DRYER D STATUS DRYER HEATER OG-DY-7A MODE DRYER HEATER OG-DY-7B MODE AR-EX-1A 0/C RESET'R-EX-1B 0/C RESET AR-P-1A 0/C RESET AR-P-1B 0/C RESET GY-P-1A 0/C RESET GY-P-1B 0/C RESET GY-P-1C 0/C RESET OG-BL-lA 0/C RESET OG-BL-1B 0/C RESET OG-V-41A PRE-FILTER OUTLET MS-PC-11A S JAE A CTRL MAN OUTPUT MS-PC-11B SJAE B CI RL MAN OUTPUT MS-PC-16A S JAE A CTRL MAN OUTPUT MS-PC-16B S JAE B CIRL MAN OUTPUT MS-PC-17A S JAE A CTRL MAN OUTPUT MS-PC-17B S JAE B CIA MAN OUTPUT OG-RC-5A 0/C RESET OG-RC-5B 0/C RESET OG-RF-20A 0/C RESET OG-RF-20B 0/C RESET OG-RF-20C 0/C RESET OG-DY-7A 0/C RESET OG-DY-7B 0/C RESET CSP-V-90 CONTAIN PURGE SUPPLY CMS-P-1303 0/C RESET CMS-P-1403 0/C RESET CRA-FN-1A1 0/C RESET CRA-FN-1A2 0/C RESET CRA-FN-1B1 0/C RESET CRA-FN-1B2 0/C RESET CRA-FN-1C1 0/C RESET CRA-FN-1C2 0/C RESET CRA-FN-2A1 0/C RESET CRA-FN-2A2 0/C RESET November 16, 1994 Page 43 of 51 APPENDIX C ATTACHMENT C-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACHONS LISTING ID PCN-012 PCN-013 PCN-014 PCN-015 PCN-016 PCN-017 PCN-018 PCN-019 PCN-020 PCN-021 PCN-022 RCC-001 RCC-002 RCC-003 RCC-004 RCC-005 RCC-006 RCC-007 RCC-008 RCC-009 RCC-010 RCC-011 RCC-012 RCC-013 RCC-014 RCC-015 RCC-016 RCC-017 RCC-018 RCC-019 RCC-020 RCC-021 RCC-022 RCC-023 RCC-024 RCC-025 RCI-001 RCI-002 RCI-003 RCI-004 RCI-005 RCI-006 RCI-007 SYSTEM PCN PCN PCN PCN PCN PCN PCN PCN PCN PCN PCN RCC RCC RCC RCC RCC RCC RCC RCC RCC RCC RCC RCC RCC RCC RCC RCC RCC RCC RCC RCC RCC RCC RCC RCC RCC RCI RCI RCI RCI RCI RCI RCI DESCRIPTION CRA-FN-2B1 0/C RESET CRA-FN-2B2 0/C RESET CRA-FN-3A 0/C RESET CRA-FN-3B 0/C RESET CRA-FN-3C 0/C RESET CRA-FN-4A 0/C RESET CRA-FN-4B 0/C RESET CRA-FN-5A 0/C RESET CRA-FN-5B 0/C RESET CRA-FN-5C 0/C RESET CRA-FN-5D 0/C RESET RCC-V-13A CRD-P-1A CLG WTR IN RCC-V-13B CRD-P-1B CLG WTR IN RCC-V-79A CRD-P-1A BRG CLG OUT RCC-V-79B CRD-P-1B BRG CLG OUT RCC-V-2A RCC-P-1A DISCH VLV RCC-V-2B RCC-P-1B DISCH VLV RCC-V-2C RCC-P-1C DISCH VLV RCC-V-3A RCC-HX-1A INLET VLV RCC-V-3B RCC-HX-1B INLET VLV RCC-V-3C RCC-HX-1C INLET VLV RCC-V-9A FPC-HX-1A INLET ISOL RCC-V-9B FPC-HX-1B INLET ISOL RCC-V-10A FPC-HX-1A OUTLET RCC-V-10B FPC-HX-1B OUTLET RCC-V-45A RWCU-P-1A CLG WTR IN, RCC-V-45B RWCU-P-1B CLG WTR IN RCC-V-8 RWCU HX OUTLET RCC-V-643A RWCU-P-1A CLR WTR OTL RCC-V-643B RWCU-P-1B CLR WTR OTL RCC-V-104 MAN OPEN RCC-V-21~OPEN RCC-V-5 MAN OPEN RCC-P-1A 0/C RESET RCC-P-1B 0/C RESET RCC-P-1C 0/C RESET RCIC-V-708 PS-9A ISOLATED RCIC-V-709 PS-9B ISOLATED RCIC-V-623D XTIE TO SLC RCIC OVERSPEED TRIP RESET RCIC-P-2 0/C RESET" RCIC-P-3 0/C RESET RCIC-P-4 0/C RESET November 16, 1994 Page 44 of 51
APPENDIX C ATTACHMENT C-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID RFC-001 RFC-002 RFC-003 RFC-004 RHR-001 RHR-002 RHR-003 RHR-004 RHR-005 RHR-006 RHR-007 RHR-008 RHR-009 RHR-010 RHR-011 RHR-012 RHR-013 RHR-014 RHR-015 RHR-016 RHR-017 RHR-018 RHR-019, RMS-001 RMS-002 RMS-003 RMS-004 RRP-001 RRP-002 RRP-003 RRP-004 RRP-005'RP-006 RRP-007 RRP-008 RRP-009 RRP-010 RRP-011 RRP-012 RRP-013 RRP-014 RRS-1 RWB-001 SYSTEM RFC RFC RFC RFC RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RMS RMS RMS RMS RRP RRP RRP RRP RRP RRP RRP RRP RRP RRP RRP RRP RRP RRP RRS RWB DESCRIPTION HY-P-A1 0/C RESET'Y-P-A2 0/C RESET HY-P-B1 0/C RESET'HY-P-B2 0/C RESET RHR-V-72A FLUSH LINE ISOLATION LPCS/RHR REMOVABLE SPOOLPIECE RHR-V-71A FLUSH LINE ISOL PMP SN RHR-V-67 LOOP C CROSS TIE&CONDF RHR-V-106 FLUSH SUPPLY RHR-V-104 RHR TO FPC INTERTIE EDR-V-176 DRAIN TO FDR-R-1 RHR-V-70 FLUSH LINE TO FLOOR DRN RHR-V-71B FLUSH LINE ISOLATION RHR-V-72B FLUSH LINE ISOLATION RHR-V-40 RHR DRAIN TO RW 0-100%RHR-V-49 RHR DRAIN TO RW 0-100%RHR-V-42A INJECT MAN OPEN 0-100%RHR-V-42B INJECT MAN OPEN 0-100%RHR-V-42C INJECT MAN OPEN 0-100%RHR-P-3 0/C RESET RHR-P-2A 0/C RESET RHR-P-2B 0/C RESET RHR-P-2C 0/C RESET WRA-FN-28 FAN STOP/START WRA-FN-31 FAN STOP/START TRA-FN-29 FAN STOP/START RRA-FN-30 FAN STOP/START RRC-P-1A VIBRATION ALARM RESET RRC-P-1B VIBRATION ALARM RESET RRC-V-8A SEAL PURGE ISOL VLV RRC-V-8B SEAL PURGE ISOL VLV RRC-FC-2A SEAL PURGE FLW CNTRL RRC-FC-2B SEAL PURGE FLW CNTRL SPARE SPARE PWR INTRLCK BYP SW RRC-RMS-118A PWR INTRLCK BYP SW RRC-RMS-118B FW LW FLOW BYP SW RRC-RMS-119A FW LW FLOW BYP SW RRC-RMS-119B RRC-P-1A 0/C RESET RRC-P-1B 0/C RESET REACTOR VESSEL HEAD FDR-V-187/COLL TK DISCH TO RIVER November 16, 1994 Page 45 of 51
APPENDIX C ATTACHMENT C-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID RWB-002 RWB-003 RWB-004 RWB-005 RWB-006 RWB-007 RWB-008 RWB-009 RWB-010 RWB-011 RWB-012 RWB-013 RWB-014 RWB-015 RWB-016 RWB-017 RWB-018 RWB-019 RWB-020 RWB-021 RWB-022 RWB-023 RWB-024 RWB-025 RWU-001 RWU-002 RWU-003 RWU-004 RWU-005 RWU-006 RWU-007 RWU-008 RWU-009 RWU-010 RWU-011 RWU-012 RWU-013 RWU-014 RWU-015 RWU-016 RWU-017 RWU-018 RWU-019 SYSTEM RWB RWB RWB RWB RWB RWB RWB RWB RWB RWB RWB RWB RWB RWB RWB RWB RWB RWB RWB RWB RWB RWB RWB RWB RWU RWU RWU RWU RWU RWU RWU RWU RWU RWU RWU RWU RWU RWU RWU RWU RWU RWU RWU DESCRIPTION FDR-V-474/COLL TK DISCH TO COND EDR-V-161/EDR TK DISCH TO FDR EDR-V-158B/EDR TK DISCH TO CST WOA-V-51A/¹1 REMOTE INTAKE ISOL WOA-V-51B/¹2 REMOTE INTAKE ISOL WOA-V-52A/¹1 REMOTE INTAKE ISOL WOA-V-52B/¹2 REMOTE INTAKE ISOL WEA-AD-52 IN DAMP TO WMA-AH-52A WEA-FN-1A 0/C RESET WEA-FN-1B 0/C RESET WEA-FN-1C 0/C RESET WEA-FN-51 0/C RESET WEA-FN-53A 0/C RESET WEA-FN-53B 0/C RESET WMA-FN-51A 0/C RESET WMA-FN-51B 0/C RESET WMA-FN-52A 0/C RESET WMA-FN-52B 0/C RESET WMA-FN-53A 0/C RESET WMA-FN-53B 0/C RESET WMA-FN-54A 0/C RESET WMA-FN-54B 0/C RESET WOA-FN-1A 0/C RESET WOA-FN-1B 0/C RESET RWCU-V-266A AUTO MANUAL RWCU-V-266B AUTO MANUAL RWCU-V-266A AUTO FLW SETPT V266A RWCU-V-266B AUTO FLW SETPT V266B RWCU-V-266A MANUL CNTRL VLV 266A RWCU-V-266B MANUL CNTRL VLV 266B RWCU-V-206A RWCU DEMN A INLT VLV RWCU-V-206B RWCU DEMN B INLT VLV RWCU-V-005A PMP A SUCT ISOL VLV RWCU-V-005B PMP B SUCT ISOL VLV RWCU-V-013A PMP A DISCH ISOL VLV RWCU-V-013B PMP B DISCH ISOL VLV RWCU-V-105 REGEN HX INLT ISO VLV CRD-FCV-512A RWCU-P-1A MTR PURGE CRD-FCV-512B RWCU-P-1B MTR PURGE RWCU-V-266A SEAL-IN RESET RWCU-V-266B SEAL-IN RESET RWCU-P-1A 0/C RESET RWCU-P-1B 0/C RESET November 16, 1994 Page 46 of 51 APPENDIX C ATTACHMENT C-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID SCN-001 SCN-002 SCN-003 SCN-004 SCN-005 SCN-006 SCN-007 SCN-008 SCN-009 SCN-010 SCN-011 SCN-012 SCN-013 SCN-014 SCN-015 SCN-016 SCN-017 SCN-018 SCN-019 SCN-020 SCN-021 SCN-022 SCN-023 SCN-024 SCN-025 SCN-026 SCN-027 SCN-028 SCN-029 SCN-030 SCN-031 SCN-032 SCN-033 SCN-034 SCN-035 SCN-036 SCN-037 SCN-038 SCN-039 SCN-040 SCN-041 SCN-042 SCN-043 SYSTEM SCN SCN SCN SCN SCN SCN SCN SCN SCN SCN SCN SCN SCN SCN SCN SCN SCN SCN SCN SCN SCN SCN SCN SCN SCN SCN SCN SCN SCN SCN SCN SCN SCN SCN SCN SCN SCN SCN SCN SCN SCN SCN SCN DESCRIPTION REA-FN-15 ANALYZER RM 1B RRA-FN-16 ACCESS AREA FDR-P-1A RX BLDG FDR SUMP 1 PUMP FDR-P-1B RX BLDG FDR SUMP 1 PUMP FDR-P-2 RX BLDG FDR SUMP 2 PUMP FDR-P-3 RX BLDG FDR SUMP 4 PUMP FDR-P-4A RX BLDG FDR SUMP 3 PUMP FDR-P-4B RX BLDG FDR SUMP 3 PUMP REA-V-F21 FIRE PROT FOR FU-2B REA-V-Fl1 FIRE PROT FOR FU-2A RRA-FN-8 MAIN STEAM TUNNEL FAN RRA-FN-9 MAIN STEAM TUNNEL FAN EDR-P-5 0/C RESET FDR-P-1A 0/C RESET FDR-P-1B 0/C RESET FDR-P-2 0/C RESET FDR-P-3 0/C RESET FDR-P-4A 0/C RESET FDR-P-4B 0/C RESET REA-FN-1A 0/C RESET REA-FN-1B 0/C RESET REA-FN-2A 0/C RESET REA-FN-2B 0/C RESET REA-FN-15 0/C RESET ROA-FN-1A 0/C RESET ROA-FN-1B 0/C RESET ROA-P-1A 0/C RESET ROA-P-1B 0/C RESET RRA-FN-1 0/C RESET RRA-FN-2 0/C RESET RRA-FN-3 0/C RESET RRA-FN-4 0/C RESET RRA-FN-5 0/C RESET RRA-FN-6 0/C RESET RRA-FN-8 0/C RESET RRA-FN-9 0/C RESET RRA-FN-10 0/C RESET RRA-FN-11 0/C RESET RRA-FN-12 0/C RESET RRA-FN-13 0/C RESET RRA-FN-14 0/C RESET RRA-FN-15 0/C RESET RRA-FN-16 0/C RESET November 16, 1994 Page 47 of 51 APPENDIX C ATTACHMENT C-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID SCN-044 SCN-045 SCN-046 SCN-047 SCN-048 SCN-049 SCN-050 SCN-051 SCN-052 SCN-053 SCN-054 SCN-055 SLC-001 SLC-002 SLC-003 SLC-004 SLC-005 SLC-006 SLC-007 SLC-008 SLC-009 SLC-010 SSW-001 SSW-002 SSW-003 SSW-004 SSW-005 SSW-006 SSW-007 SSW-008 SSW-009 SSW-010 SSW-011 SSW-012 SSW-013 SSW-014 SSW-015 TBS-001 TBS-002 TBS-003 TBS-004 TBS-005 TBS-006 SYSTEM SCN SCN SCN SCN SCN SCN SCN SCN SCN SCN SCN SCN SLC SLC SLC SLC SLC SLC SLC SLC SLC SLC SSW SSW SSW SSW SSW SSW SSW SSW SSW SSW SSW SSW SSW SSW SSW TBS TBS TBS TBS TBS TBS DESCRIPTION RRA-FN-17 0/C RESET RRA-FN-19 0/C RESET RRA-FN-20 0/C RESET SGT-FN-1A-1 0/C RESET SGT-FN-1A-2 0/C RESET SGT-FN-1B-1 0/C RESET SGT-FN-1B-2 0/C RESET RRA-FN-21 0/C RESET SGT-EHC-1A1 0/C RESET.,SGT-EHC-1A2 0/C RESET SGT-EHC-1B1 SGT-EHC-1B2 0/C RESET SLC-V-16 SYS CIRC TEST VLV SLC-V-31 TEST TANK OUTLET VALVE SLC-RV-29B REMOVED/CONN TO RCIC SLC-RV-29A REMOVED/CONN TO RCIC SLC-V-2A SLC PUMP 1A SUCTION VLV SLC-V-2B SLC PUMP 1B SUCTION VLV SLC-P-1A LOCAL START/STOP SLC-P-1B LOCAL START/STOP SLC-P-1A 0/C RESET SLC-P-1B 0/C RESET RHR-V-14A HX A MAN ISOL RHR-V-14B HX B MAN ISOL SW-V-165A SPRAY RING BYPASS SW-V-165B SPRAY RING BYPASS SW-V-170A SPRAY RING ISOL SW-V-170B SPRAY RING ISOL SW-V-71A SPRAY XOVER A-B SW-V-72A SPRAY XOVER B-A SW-P-2A LOOP A KEEP FILL PMP SW-P-2B LOOP B KEEP FILL PMP SW-P-1A 86 LOCKOUT RELAY RESET SW-P-1B 86 LOCKOUT RELAY RESET HPCS-P-2 0/C RESET SW-P-2A 0/C RESET SW-P-2B 0/C RESET TURB BLDG OUTSIDE AIR SPLY FAN1A TURB BLDG OUTSIDE AIR SPLY FAN1B TURB BLDG OUTSIDE AIR SPLY FAN2A TURB BLDG OUTSIDE AIR SPLY FAN2B'URB BLDG EXHAUST AIR FAN1A TURB BLDG EXHAUST AIR FAN1B November 16, 1994 Page 48 of 51 APPENDIX C ATTACHMENT C-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID TBS-007 TBS-008 TBS-009 TBS-010 TBS-011 TBS-012 TBS-013 TBS-014 TBS-015 TBS-016 TLO-001 TLO-002 TLO-003 TLO-004 TLO-005 TLO-006 TSW-001 TSW-002 TSW-003 TSW-004 TSW-005 TSW-006 TSW-007 TSW-008 TSW-009 TSW-010 TSW-011 TSW-012 TSW-013 TSW-014 TSW-015 TSW-016 TSW-017 TSW-018 TSW-019 TSW-020 TSW-021 TSW-022 TSW-023 TSW-024 TSW-025 TSW-026 TSW-027 SYSTEM TBS TBS TBS TBS TBS TBS TBS TBS TBS TBS TLO TLO TLO TLO TLO TLO TSW TSW TSW TSW TSW TSW TSW TSW TSW TSW TSW TSW TSW TSW TSW TSW TSW TSW TSW TSW TSW TSW TSW TSW TSW TSW TSW DESCRIPTION TURB BLDG EXHAUST AIR FAN1C TURB BLDG EXHAUST AIR FAN1D TEA-FN-1A 0/C RESET TEA-FN-1B 0/C RESET TEA-FN-1C 0/C RESET TEA-FN-1D 0/C RESET TOA-FN-lA 0/C RESET TOA-FN-1B 0/C RESET TOA-FN-2A 0/C RESET TOA-FN-2B 0/C RESET OIL COOLER SELECI'A/1B TO-EX-1 0/C RESET TO-P-BLP 0/C RESET TO-P-BOP 0/C RESET TO-P-EOP 0/C RESET TO-P-SOBP 0/C RESET TSW-V-63A RCC-HX-1A INLET VLV TSW-V-63B RCC-HX-1B INLET VLV TSW-V-63C RCC-HX-1C INLET VLV TSW-V-46 TSW-TCV-4 BYPASS TSW-V-21 TSW-TCV-8 BYPASS TSW-V-29 TSW-TCV-9 BYPASS TSW-V-10A TSW-TCV-14B BYPASS TSW-V-10B TSW-TCV-14A BYPASS TSW-F-1A TSW LUBE WTR FLTR ON TSW-F-1B TSW LUBE WTR FLTR ON TSW-V-78 TSW RTN ISOL CW BASIN TSW-V-38 AIR SIDE S CLR TSW IN TSW-V-39 H2 SIDE S CLR TSW IN TSW-V-40 AIR SIDE S CLR TSW OUT TSW-V-41 H2 SIDE S CLR TSW OUT TSW-V-42A BUS DCl'LR A TSW IN TSW-V-42B BUS DCT CLR B TSW IN TSW-V-43A BUS DCT CLR A TSW OUT TSW-V-43B BUS DCT CLR B TSW OUT TSW-V-230 TSW SU LUBE WTR SUP TSW-V-45B TCV-4 ISOLATION TSW-V-9D TCV-14A ISOLATION TSW-V-9B TCV-14B ISOLATION TSW-V-20B TCV-8 ISOLATION TSW-V-28B TCV-9 ISOLATION TSW-V-33 TCV-11 BYPASS TSW-V-32B TCV-11 ISOLATION November 16, 1994 Page 49 of 51 APPENDIX C ATTACHMENT C-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID TSW-028 TSW-029 TSW-030 TSW-031 TSW-032 TSW-033 TSW-034 TSW-035 TSW-036 TSW-037 TSW-038 TSW-039 TSW-040 TSW-041 TSW-042 TSW-043 TSW-044 TSW-045 TSW-046 TSW-047 TSW-048 TSW-049 TSW-050 TSW-051 TSW-052 TSW-053 TSW-054 TSW-055 TSW-056 TSW-057 TSW-058 TSW-059 TSW-060 TSW-061 TSW-062 TSW-063 TSW-064 TSW-065 TSW-066 TUR-001 TUR-002 TUR-003 TUR-004 SYSTEM TSW TSW TSW TSW TSW TSW TSW TSW TSW TSW TSW TSW TSW TSW TSW TSW TSW TSW TSW TSW TSW TSW TSW TSW TSW TSW TSW TSW TSW TSW TSW TSW TSW TSW TSW TSW TSW TSW TSW TUR TUR TUR TUR DESCRIPTION TSW-V-44 PCV-20 BYPASS TSW-V-48B PCV-20 ISOLATION CJW-P-1A JACKET WATER CIRC PUMP CJW-P-1B JACKET WATER CIRC PUMP CJW-V-201 TO TSW DISCH HEADER CJW-V-5 TCV INLET ISOLATION CJW-V-12 TCV-1 INLET ISOLATION CJW-V-18 TCV-1 BYPASS CJW-V-9 TCV-1 BYPASS CJW-V-16A CAS-C-1A OUTLET ISOL CJW-V-16B CAS-C-1B OUTLET ISOL TSW-V-684 INLET TO CJW-HX-1B TSW-V-685 INLET TO CJW-HX-1A TSW-V-687 OUTLET FROM CJW-HX-1B TSW-V-688 OUTLET FROM CJW-HX-1A CJW-V-751 FPS CONNECTION TSW-V-237,243,244 FPS CONNECTION TSW-V-69 TSW SUPPLY CW FILL CJW-V-16C CAS-C-1C OUTLET ISOL TSW-V-695 FIREWATER TO TSW CJW-V-22A CJW-HX-1A OUTLET ISOL CJW-V-22B CJW-HX-1B OUTLET ISOL TSW-F-2A FLTR CIRC WTR LUBE WTR TSW-F-2B FLTR CIRC WTR LUBE WTR TSW-V-94A FLTR TSW-F-2A ISOL VLV TSW-V-94B FLTR TSW-F-2B ISOL VLV TSW-V-683 CJW HTX COMMON ISOL TSW-P-lA 86 LOCKOUT RELAY RESET TSW-P-1B 86 LOCKOUT RELAY RESET CJW-P-1A 0/C RESET CJW-P-1B 0/C RESET TSW-V-140A OUTLET FROM TO-HX-2A TSW-V-140B OUTLET FROM TO-HX-2B TSW-V-140C OUTLET FROM TO-HX-2C TSW-V-140D OUTLET FROM TO-HX-2D TSW-V-5A INLET TO TO-HX-2A TSW-V-5B INLET TO TO-HX-2B TSW-V-5C INLET TO TO-HX-2C TSW-V-5D INLET TO TO-HX-2D SS-V-49F SS-PCV-4F BYP VLV SS-V-48F SS-PCV-4F ISOL VLV SS-V-49E SS-PCV-4E BYP VLV SS-V-48E SS-PCV-4E ISOL VLV November 16, 1994 Page 50 of 51 APPENDIX C ATTACHMENT C-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID TUR-005 TUR-006 TUR-007 TUR-008 TUR-009 TUR-010 TUR-011 TUR-012 TUR-013 TUR-014 TUR-015 TUR-016 TUR-017 TUR-018 TUR-019 TUR-020 TUR-021 TUR-022 TUR-023 TUR-024 TUR-025 TUR-026 SYSTEM TUR TUR TUR TUR TUR TUR TUR TUR TUR TUR TUR TUR TUR TUR TUR TUR TUR TUR TUR TUR TUR TUR DESCRIPTION RESET UTl'ON SS-V-49D SS-PCV-4D BYP VLV SS-V-48D SS-PCV-4D ISOL VLV SS-V-49C SS-PCV-4C BYP VLV SS-V-48C SS-PCV-4C ISOL VLV SS-V-49B SS-PCV-4B BYP VLV SS-V-48B SS-PCV-4B ISOL VLV SS-V-49A SS-PCV-4A BYP VLV SS-V-48A SS-PCV-4A ISOL VLV SS-V43B SS-PCV-2B BYP VLV SS-V-42B SS-PCV-2B ISOL VLV SS-V-43A SS-PCV-2A BYP VLV SS-V-42A SS-PCV-2A ISOL VLV SS-V-25 SS-PCV-126 BYPASS VLV SS-V-24 SS-PCV-126 ISOL SS-V-46 SS-PCV-3 BYP VLV SS-V47 SS-PCV-3 ISOL VLV AS-BLR-1 AUX BOILER HV-V-28A,HV-V-29A BYPASS HV-V-28B,HV-V-29B BYPASS HEATER EXT NON-RETURN VLV TG-M-TG LOCAL START PUSHB TG-M-TG 0/C RESET TOTAL COUNT: 2172 November 16, 1994 Page 51 of 51 APPENDIX C ATTACHMENT C-3 WASHINGTON PUBLIC POWER SUPPLY SYSTEM MALFUNCTIONS LISTING ID ADS-1 CAS-1 CAS-1A CAS-1B CAS-1C CAS-2 CAS-2A CAS-2B CAS-2C CAS-2D CAS-3 CAS-4 CFW-1 CFW-10 CFW-10A CFW-10B CFW-10C CFW-10D CFW-10E CFW-10F CFW-10G CFW-10H CFW-10I CFW-10J CFW-10K CFW-10L CFW-10M CFW-10N CFW-100 CFW-10P CFW-1A CFW-1B CFW-1C CFW-2 CFW-3 CFW4 CFW-5 CFW-6 CFW-7 CFW-8 CFW-8A CFW-8B CFW-9 SYSTEM ADS CAS CAS CAS CAS CAS CAS CAS CAS CAS CAS CAS CFW CFW CFW CFW CFW CFW CFW CFW CFW CFW CFW CFW CFW CFW CFW CFW CFW CFW CFW CFW CFW CFW CFW CFW CFW CFW CFW CFW CFW CFW CFW DESCRIPTION ADS LOGIC FAILURE COMPRESSOR LUBE OIL LEAK AP,C A COMPRESSOR LUBE OIL LEAK B COMPRESSOR LUBE OIL LEAK C COMPRESSOR LUBE OIL LEAK CTL AIR HDR LK DNSTRM CAS-V-15 CI'L AIR HDR LK DNSTRM CAS-V-151 CTL AIR HDR LK DNSTRM CAS-V-152 CI'L AIR HDR LK DNSTRM CAS-V-153 CTL AIR HDR LK DNSTRM CAS-V-155 SERV AIR HDR LK DNSTRM SA-PCV-2 LEAK DNSTRM OF CAS DRYER A/8 CONDENSER TUBE LEAK FEEDWATER HEATER TUBE RUPTURE FEEDWATER HEATER 1A TUBE RUPTURE FEEDWATER HEATER 1B TUBE RUPTURE FEEDWATER HEATER 1C TUBE RUPTURE FEEDWATER HEATER 2A TUBE RUPTURE FEEDWATER HEATER 2B TUBE RUPTURE FEEDWATER HEATER 2C TUBE RUPTURE FEEDWATER HEATER 3A TUBE RUPTURE FEEDWATER HEATER 3B TUBE RUPTURE FEEDWATER HEATER 3C TUBE RUPTURE FEEDWATER HEATER 4A TUBE RUPTURE FEEDWATER HEATER 4B TUBE RUPTURE FEEDWATER HEATER 4C TUBE RUPTURE FEEDWATER HEATER 5A TUBE RUPTURE FEEDWATER HEATER 5B TUBE RUPTURE FEEDWATER HEATER 6A TUBE RUPTURE FEEDWATER HEATER 6B TUBE RUPTURE CONDENSER TUBE LEAK EAST END CONDENSER TUBE LEAK MIDDLE CONDENSER TUBE LEAK WEST END LK IN CST SUPPLY HDR TO COND CONDENSER AIR LEAK LEAK IN COMMON COND PUMP DISCH FEED LINE LEAK IN TURBINE BLDG LEAK IN COMMON CBP DISCHARGE LEAK AT RFP SUCTION FEED LINE LEAK IN STEAM TUNNEL FEED LINE LEAK IN STEAM TUNNEL A FEED LINE LEAK IN STEAM TUNNEL B FEED LINE LEAK IN DRYWELL November 16, 1994 Page1of27 APPENDIX C ATTACHMENT C-3 WASHINGTON PUBLIC POWER SUPPLY SYSTEM MALFUNCTIONS LISTING ID CFW-9A CFW-9B CIA-1 CIA-2 CIA-3 CIA-3A CIA-3B CRD-1 CRD-1A CRD-1AA CRD-1AB CRD-1AC CRD-1AD CRD-1AE CRD-1AF CRD-1AG CRD-1AH CRD-1AI CRD-1AJ CRD-lAK CRD-1AL CRD-1AM CRD-1AN CRD-1AO CRD-1AP CRD-1AQ CRD-1AR CRD-1AS CRD-1AT'RD-1AU CRD-1AV CRD-1AW CRD-1AX CRD-1B CRD-lc CRD-1D CRD-1E CRD-1F CRD-1G CRD-1H CRD-1I CRD-1J CRD-1K SYSTEM CFW CFW CIA CIA CIA CIA CIA CRD CRD CRD CRD CRD CRD CRD'RD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD DESCRIPTION FEED LINE LEAK IN DRYWELL A FEED LINE LEAK IN DRYWELL B CONTAINMENT INSTRUMENT AIR LEAK LEAK IN CIA LINE DNSTRM CIA-V-21 LK CIA LINE DNSTRM CIA-V-31A/8 LK IN SUPP LINE TO SRV-4A/4B/5B LK IN SUPP LINE SRV-3D/4C/4D/5C HCU ACCUMULATOR TROUBLE HCU ACCUMULATOR TROUBLE HCU ACCUMULATOR TROUBLE HCU ACCUMULATOR TROUBLE HCU ACCUMULATOR TROUBLE HCU ACCUMULATOR TROUBLE HCU ACCUMULATOR TROUBLE HCU ACCUMULATOR TROUBLE HCU ACCUMULATOR TROUBLE HCU ACCUMULATOR TROUBLE HCU ACCUMULATOR TROUBLE HCU ACCUMULATOR TROUBLE HCU ACCUMULATOR TROUBLE HCU ACCUMULATOR TROUBLE HCU ACCUMULATOR TROUBLE HCU ACCUMULATOR TROUBLE HCU ACCUMULATOR TROUBLE HCU ACCUMULATOR TROUBLE HCU ACCUMULATOR TROUBLE HCU ACCUMULATOR TROUBLE HCU ACCUMULATOR TROUBLE HCU ACCUMULATOR TROUBLE HCU ACCUMULATOR TROUBLE HCU ACCUMULATOR TROUBLE HCU ACCUMULATOR TROUBLE HCU ACCUMULATOR TROUBLE HCU ACCUMULATOR TROUBLE HCU ACCUMULATOR TROUBLE HCU ACCUMULATOR TROUBLE HCU ACCUMULATOR TROUBLE HCU ACCUMULATOR TROUBLE HCU ACCUMULATOR TROUBLE HCU ACCUMULATOR TROUBLE HCU ACCUMULATOR TROUBLE HCU ACCUMULATOR TROUBLE HCU ACCUMULATOR TROUBLE November 16, 1994 Page 2 of 27 APPENDIX C ATTACHMENT C-3 WASHINGTON PUBLIC POWER SUPPLY SYSTEM MALFUNCTIONS LISTING ID CRD-1L CRD-1M CRD-1N CRD-10 CRD-1P CRD-1Q CRD-1R CRD-1S CRD-1T CRD-1U CRD-1V CRD-1W CRD-1X CRD-1Y CRD-1Z CRD-2 CRD-3 CRD4 CRD-5 CRD-6 CRD-7 CRD-7A CRD-7B CSS-1 CSS-2 CSS-3 CSS-4 CSS-5 CSS-6 CSS-7 CWS-1 CWS-1A CWS-1B CWS-1C CWS-1D CWS-1E CWS-1F CWS-2 CWS-3 CWS-3A CWS-3B CWS-3C CWS-4 SYSTEM CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CSS CSS CSS CSS CSS CSS CSS CWS CWS CWS CWS CWS CWS CWS CWS CWS CWS CWS CWS CWS DESCRIPTION HCU ACCUMULATOR TROUBLE HCU ACCUMULATOR TROUBLE HCU ACCUMULATOR TROUBLE HCU ACCUMULATOR TROUBLE HCU ACCUMULATOR TROUBLE HCU ACCUMULATOR TROUBLE HCU ACCUMULATOR TROUBLE HCU ACCUMULATOR TROUBLE HCU ACCUMULATOR TROUBLE HCU ACCUMULATOR TROUBLE HCU ACCUMULATOR TROUBLE HCU ACCUMULATOR TROUBLE HCU ACCUMULATOR TROUBLE HCU ACCUMULATOR TROUBLE HCU ACCUMULATOR TROUBLE CONTROL ROD DRIVE SEALS WORN CRD HYD LINE BREAK AT INLET PORT CRD HYD LINE BREAK OUTLET PORT RUPTURE IN CRD AIR HEADER RUPTURE IN CRD WATER HEADER HYDRAULIC ATWS HYDRAULIC ATWS EAST SDV HYDRAULIC ATWS WEST SDV HPCS HEADER BREAK LPCS HEADER BREAK LPCS SUCTION LINE LEAK AT PUMP HPCS DISCHARGE LINE LEAK AT PUMP HPCS DISCH LN BRK DNSTRM FI-603 HPCS LOGIC FAILURE LPCS/LPCI-A LOGIC FAILURE CW TOWER ICING CW TOWER 1A ICING CW TOWER 1B ICING CW TOWER 1C ICING CW TOWER 2A ICING CW TOWER 2B ICING CW TOWER 2C ICING CW SYS RUPTURE AT COMMON DISCH CW SYS RUPTURE CONDENSER INLET CW SYS RUPTURE CONDENSER A INLET CW SYS RUPTURE CONDENSER B INLET CW SYS RUPTURE CONDENSER C INLET CW SYS RUPTURE AT CONDSER OUTLET November 16, 1994 Page 3 of27 APPENDIX C ATTACHMENT C-3 WASHINGTON PUBLIC POWER SUPPLY SYSTEM MALFUNCTIONS LISTING ID CWS-4A CWS-4B CWS-4C CWS-5 CWS-5A CWS-SB CWS-5C CWS-5D CWS-5E CWS-5F CWS-6 DEH-1 DEH-10 DEH-10A DEH-10B DEH-10C DEH-10D DEH-11 DEH-11A DEH-11B DEH-11C DEH-11D DEH-12 DEH-12A DEH-12B DEH-12C DEH-12D DEH-12E DEH-12F DEH-12G DEH-12H DEH-12I DEH-12J DEH-12K DEH-12L DEH-13 DEH-13A DEH-13B DEH-13C DEH-13D DEH-2 DEH-3 DEH-4 SYSTEM CWS CWS CWS CWS CWS CWS CWS CWS CWS CWS CWS DEH DEH DEH DEH DEH DEH DEH DBH DEH DBH DBH DEH DEH DEH DEH DEH DEH DEH DEH DBH DEH DEH DEH DEH DEH DEH DEH DEH DEH DEH DEH DEH DESCRIPTION CW SYS RUPTURE AT CNDSR A OUTLET CW SYS RUPTURE AT CNDSR B'OUTLET CW SYS RUPTURE AT CNDSR C OUTLET CW SYS RUPT AT EACH COOLING TOWR CW SYS RUPTURE AT CLG TOWER 1A CW SYS RUPTURE AT CLG TOWER 1B CW SYS RUPTURE AT CLG TOWER 1C CW SYS RUPTURE AT CLG TOWER 2A CW SYS RUPTURE AT CLG TOWER 2B CW SYS RUPTURE AT CLG TOWER 2C TMU RUPTURE IN 3.5 MILE M/U LINE MAIN TURBINE TRIP/PAIL TO TRIP TURBINE THROTILE VALVE FAILURE TURBINE THROTILE VALVE¹1 FAIL TURBINE THROTTLE VALVE¹2 FAIL TURBINE THROVE,E VALVE¹3 FAIL TURBINE THROVE.E VALVE¹4 FAIL TURBINE GOVERNOR VALVE FAILURE TURBINE GOVERNOR VALVE¹1 FAIL TURBINE GOVERNOR VALVE¹2 FAIL TURBINE GOVERNOR VALVE¹3 FAIL TURBINE GOVERNOR VALVE¹4 PAIL INTERCEPT AND STOP VALVE FAILURE INTERCEPT/STOP VALVE FAIL L-1IV INTERCEPT/STOP VALVE FAIL L-1RV INTERCEPT/STOP VALVE FAIL L-2IV INTERCEPT/STOP VALVE FAIL L-2RV INTERCEPT/STOP VALVE PAIL L-3IV INTERCEPT/STOP VALVE PAIL L-3RV INTERCEPT/STOP VALVE PAIL R-1IV INTERCEPT/STOP VALVE FAIL R-1RV INTERCEPT/STOP VALVE PAIL R-2IV INTERCEPT/STOP VALVE PAIL R-2RV INTERCEPT/STOP VALVE FAIL R-3IV INTERCEPT/STOP VALVE PAIL R-3RV TURBINE BYPASS VALVE FAILURE TURBINE BYPASS VALVE¹1 FAILURE TURBINE BYPASS VALVE¹2 FAILURE TURBINE BYPASS VALVE¹3 FAILURE TURBINE BYPASS VALVE¹4 FAILURE RUPTURE IN COMMON DEH DISCHARGE EH OIL LEAK AT PUMP DISCHARGE DEH STM PRESS INPUT AMP OSCIL November 16, 1994 Page 4 of 27 APPENDIX C ATTACHMENT C-3 WASHINGTON PUBLIC POWER SUPPLY SYSTEM MALFUNCTIONS LISTING ID DEH-4A DEH-4B DEH-5 DEH-6 DEH-7 DEH-7A DEH-7B DEH-8 DEH-9 DGN-1 DGN-1A DGN-1B DGN-1C DGN-2 DGN-2A DGN-2B DGN-2C DGN-3 DGN-3A DGN-3B DGN-3C DGN-4 DGN-4A DGN-4B DGN-4C DGN-5 DON-5A DGN-5B DGN-5C EPS-1 EPS-1A EPS-1B EPS-1C EPS-1D EPS-1E EPS-1F EPS-1G EPS-1H EPS-1I EPS-1J EPS-2 EPS-2A EPS-2B SYSTEM DEH DEH DEH DEH DEH DEH DEH DEH DEH DGN DGN DGN DGN DGN DGN DGN DGN DGN DGN DGN DGN DGN DGN DGN DGN DGN DGN DGN DGN EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS EPS DESCRIPTION DEH STM PRESS A INPUT AMP OSCIL DEH STM PRESS B INPUT AMP OSCIL DEH PRESS CONTROLLER OUTPUT FAIL DEH COMPUTER FAILURE DEH ANALOG CONTROLLER FAILURE DEH ANALOG CONTROLLER FAIL-BPV'S DEH ANALOG CONTROLLER FAIL-GV'S GOV VALVE LOW SIGNAL SELECT FAIL TURB ACCELERATION CNTRL FAILURE DG FAIL TO AUTO START-INCOMP SEQ DG1 FAIL AUTO START-INCOMPL SEQ DG2 FAIL AUTO START-INCOMPL SEQ DG3 FAIL AUTO START-INCOMPL SEQ DG TRIP-HI DIFFERED IAL CURRENT DG1 TRIP-HIGH DIFF CURRENT DG2 TRIP-HIGH DIFF CURRENT DG3 TRIP-HIGH DIFF CURRENT DG GOVERNOR FAILURE-SPEED/LOAD DG1 GOVERNOR FAIL-SPEED/LOAD DG2 GOVERNOR FAIL-SPEED/LOAD DG3 GOVERNOR FAIL-SPEED/LOAD DG VOLT REG FAIL-OSCILLATION DG1 VOLT REG FAIL-OSCILLATION DG2 VOLT REG FAIL-OSCILLATION DG3 VOLT REG FAIL-OSCILLATION DG HIGH VIBRATION DG1 HIGH VIBRATION DG2 HIGH VIBRATION DG3 HIGH VIBRATION 4160 VAC BUS OVERCURRENT-GROUND 4160 VAC BUS OVRCUR/GND SM1 4160 VAC BUS OVRCUR/GND SM2 4160 VAC BUS OVRCUR/GND SM3 4160 VAC BUS OVRCUR/GND SM4 4160 VAC BUS OVRCUR/GND SM75 4160 VAC BUS OVRCUR/GND SM85 4160 VAC BUS OVRCUR/GND SM7 4160 VAC BUS OVRCUR/GND SM8 4160 VAC BUS OVRCUR/GND SM72 4160 VAC BUS OVRCUR/GND SM82 480 VAC BUS OVERCURRENT
-GROUND 480 VAC BUS OVRCUR/GND SL11 480 VAC BUS OVRCUR/GND SL21 November 16, 1994 Page 5 of 27 ID APPENDIX C ATTACHMENT C-3 WASHINGTON PUBLIC POWER SUPPLY SYSTEM MALFUNCTIONS LISTING t SYSTEM DESCRIPTION EPS-2C EPS-2D EPS-2E EPS-2F EPS-2G EPS-2H EPS-2I EPS-2J BPS-2K EPS-2L EPS-3 EPS-3A EPS-3B EPS-3C EPS-3D EPS-3B EPS-3F EPS-3G EPS-4 EPS-4A EPS-4B EPS-4C EPS-5 EPS-5A EPS-5B FPC-1 FPC-2 FPC-3 FPS-1 FPT-1 FPT-1A FPT-1B FPT-2 FPT-2A FPT-2B FPT-3 FPT-3A FPT-3B FPT-4 FPT-4A FPT-4B FPT-5 FPT-5A EPS EPS EPS BPS EPS BPS EPS EPS EPS EPS EPS EPS EPS BPS EPS EPS EPS BPS EPS EPS BPS EPS EPS EPS EPS FPC FPC FPC FPS FPT FPT FPT FPT FPT FPT FPT FPT FPT FPT FPT FPT'PT 480 VAC BUS OVRCUR/GND SL31 , 480 VAC BUS OVRCUR/GND MC4A 480 VAC BUS OVRCUR/GND SL51-SL52 480 VAC BUS OVRCUR/GND SL53 480 VAC BUS OVRCUR/GND SL61-SL62 480 VAC BUS OVRCUR/GND SL63 480 VAC BUS OVRCUR/GND SL71 480 VAC BUS OVRCUR/GND SL73 480 VAC BUS OVRCUR/GND SL81 480 VAC BUS OVRCUR/GND SL83 GROUNDED DC BUS GROUNDED DC BUS DP-SO-1A GROUNDED DC BUS DP-SO-IB GROUNDED DC BUS DP-S1-1 GROUNDED DC BUS DP-S1-2 GROUNDED DC BUS DP-S 1-7 GROUNDED DC BUS DP-S1-HPCS GROUNDED DC BUS DP-S2-1 UPS STATIC SWITCH FAILURE UPS STATIC SWITCH FAILURE-IN1 UPS STATIC SWITCH FAILURE-IN2 UPS STATIC SWITCH FAILURE-IN3 6900 VAC BUS OVERCURRENT-GROUND 6900 VAC BUS OVRCUR/GND SH5 6900 VAC BUS OVRCUR/GND SH6 LEAK IN SPENT FUEL POOL RUPTURE IN FPC PUMP SUCHON LINE DROPPED SPENT FUEL BUNDLE IN SFP FIRE MAIN HEADER BREAK TO-TK-3A/3B LUBE OIL LEAK TO-TK-3A LUBE OIL LEAK TO-TK-3B LUBE OIL LEAK RFPT TRIP/FAIL TO TRIP RFPT-A TRIP/FAIL TO TRIP RFPT-B TRIP/FAIL TO TRIP RFPT LOSS OF LUBE OIL RFPT-A LOSS OF LUBE OIL RFPT-B LOSS OF LUBE OIL RFPT GOVERNOR FAILURE RFPT-A GOVERNOR FAILURE RFPT-B GOVERNOR FAILURE RFPT HIGH VIBRATION RFPT-A HIGH VIBRATION November 16, 1994 Page 6 of 27
APPENDIX C ATTACHMENT C-3 WASHINGTON PUBLIC POWER SUPPLY SYSTEM MALFUNCTIONS LISTING ID FPT-5B FPT-6 FPT-6A FPT-6B FWC-1 FWC-2 FWH-1 FWH-lA FWH-1B FWH-1C FWH-1D FWH-1E FWH-1F FWH-1G FWH-1H FWH-1I FWH-1J FWH-2 FWH-2A FWH-2B FWH-2C FWH-2D FWH-2E FWH-2F FWH-2G FWH-2H FWH-2I FWH-2J FWH-2K FWH-2L FWH-2M GEA-1 GBA-1A GEA-1B GEA-2 GEA-3 GEA-3A GEA-3B GEAR GEA-5 GEN-1 GEN-2 GEN-3 SYSTEM FPT FPT FPT FPT FWC FWC FWH FWH FWH FWH FWH FWH FWH FWH FWH FWH FWH FWH FWH FWH FWH FWH FWH FWH FWH FWH FWH FWH FWH GEA GEA GEA GEA GEA GEA GEA GEA GEA GEN GEN GEN DESCRIPTION RFPT-B HIGH VIBRATION STM LK RFP SUPPLY BETWEEN SV/GOV STM LK RFP-A SUP BETWEEN SV/GV STM LK RFP-B SUP BETWEEN SV/GV STEAM FLOW TOTALIZER FAILURE FEED FLOW TOTALIZER FAILURE DRAIN LINE LEAK TO MSR DRAIN TK DRAIN LINE LEAK TO HD-TK-1A DRAIN LINE LEAK TO HD-TK-1B DRAIN LINE LEAK TO HD-TK-2A DRAIN LINE LEAK TO HD-TK-2B DRAIN LINE LEAK TO HD-TK-2C DRAIN LINE LEAK TO HD-TK-2D DRAIN LINE LEAK TO HD-TK-3A DRAIN LINE LEAK TO HD-TK-3B DRAIN LINE LEAK TO HD-TK-3C DRAIN LINE LEAK TO HD-TK-3D FW HTR DRAIN LK BETWEEN DUMP VLV FW HTR DR LK BETWEEN DUMPS HTR2A FW HTR DR LK BETWEEN DUMPS HTR2B FW HTR DR LK BETWEEN DUMPS HTR2C FW HTR DR LK BETWEEN DUMPS HTR3A FW HTR DR LK BETWEEN DUMPS HTR3B FW HTR DR LK BETWEEN DUMPS HTR3C FW HTR DR LK BETWEEN DUMPS HTR4A FW HTR DR LK BETWEEN DUMPS HTR4B FW HTR DR LK BETWEEN DUMPS HTR4C FW HTR DR LK BETWEEN DUMPS HTR5A FW HTR DR LK BETWEEN DUMPS HTR5B FW HTR DR LK BETWEEN DUMPS HTR6A FW HTR DR LK BETWEEN DUMPS HTR6B RUPTURE OF GEN SEAL OIL FILTERS RUPT OF AIR SIDE SEAL OIL FILTER RUPT OF HYDROGEN SEAL OIL FILTER H2 LEAK IN SUPPLY LINE TO GEN SCC PUMPS SUCTION LINE LEAK SCC-A PUMP SUCTION LINE LEAK SCC-B PUMP SUCTION LINE LEAK GEN CLG WATER HIGH CONDUCTIVITY STATOR CLG WTR LEAK IN MAIN GEN MAIN GENERATOR TRIP/FAIL TO TRIP GENERATOR VOLTAGE REG FAILURE TRANSFORMER LOCKOUT TR-Nl November 16, 1994 Page 7 of 27 APPENDIX C ATTACHMENT C-3 WASHINGTON PUBLIC POWER SUPPLY SYSTEM MALFUNCTIONS LISTING ID GENP GEN-5 GEN-5A GEN-5B GEN-6 GEN-7 GEN-7A 6 EN-7B GEN-8 GEN-8A GEN-8B GEN-8C NIS-1 NIS-1A NIS-1B NIS-1C NIS-1D NIS-2 NIS-2A NIS-2B NIS-2C NIS-2D NIS-2E NIS-2F NIS-26 NIS-2H NIS-3 NIS-3A NIS-3B NIS-3C NIS-3D NIS-4 NISAA NISPB NISPC NISCD NISSE NISPF NISQG NIS-4H NIS-5 NIS-5A NIS-5B SYSTEM GEN GEN GEN GEN GEN GEN GEN GEN GEN GEN GEN GEN NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS DESCRIPTION TRANSFORMER LOCKOUT TR-N2 500KV BREAKER TRIP 500KV ASHE BKR¹1 (4885)TRIP 500KV ASHE BKR¹2 (4888)TRIP MWTI'AILURE MAIN GEN POTENTIAL XPMR FAILURE GEN INST POTENTIAL XPMR 62 FAIL VOLT REG POTENTIAL XFMR G3 FAIL MAIN TRANSFORMER LOCKOUT MAIN TRANSFORMER TR-M1 LOCKOUT MAIN'IRANSPORMER TR-M2 LOCKOUT MAIN TRANSFORMER TR-M3 LOCKOUT SRM INSTR FLR HI-LO-ERRAT-INOP SRM INSTR FLR HI-LO-ERRAT-INOP A SRM INSTR FLR HI-LO-ERRAT-INOP B SRM INSTR FLR HI-LO-ERRAT-INOP C SRM INSTR FLR HI-LO-ERRAT-INOP D IRM INSTR FLR HI-LO-ERRAT-INOP IRM INSTR FLR HI-LO-ERRAT-INOP A IRM INSTR FLR HI-LO-ERRAT-INOP B IRM INSTR FLR HI-LO-ERRAT-INOP C IRM INSTR FLR HI-LO-ERRAT-INOP D IRM INSTR FLR HI-LO-ERRAT-INOP E IRM INSTR FLR HI-LO-ERRAT-INOP F IRM INSTR PLR HI-LO-ERRAT-INOP G IRM INSTR FLR HI-LO-ERRAT-INOP H SRM DT DR FAIL-STCK,CIR FAIL.SRM DT DR FAIL.-STCK,CIR PAIL A SRM DT DR FAIL-STCK,CIR FAIL B SRM DT DR FAIL-STCK,CIR FAIL C SRM DT DR FAIL-STCK,CIR FAIL D IRM DT DR FAIL-STCK,CKT FAIL.IRM DT DR FAIL-STCK,CKT FAIL A IRM DT DR PAIL-STCK,CKT FAIL B IRM DT DR PAIL-STCK,CKT PAIL C IRM DT DR FAIL-STCK,CKT PAIL D IRM DT DR FAIL-STCK,CKT FAIL E IRM DT DR FAII STCK,CKT FAIL F IRM DT DR FAIL-STCK,CKT FAIL G IRM DT DR FAIL-STCK,CKT FAIL H APRM FAILURE-DWNSCL/UPSCL flNOP APRM-A FAILURE-DWNSCL/UPS CL/INOP APRM-B FAILURE-DWNSCL/UPSCL flNOP November 16, 1994 Page 8 of 27 APPENDIX C ATTACHMENT C-3 WASHINGTON PUBLIC POWER SUPPLY SYSTEM MALFUNCTIONS LISTING ID NIS-5C NIS-5D NIS-5E NIS-5F NIS-6 NIS-6A NIS-6B NIS-6C NIS-6D NIS-7 NIS-7A NIS-7B NIS-7C NIS-7D NIS-7E NIS-7F NIS-7G NIS-7H NIS-8 NIS-8A NIS-8AA NIS-8AB NIS-8AC NIS-8AD NIS-8AE NIS-8AF NIS-8AG NIS-8AH NIS-8AI NIS-8AJ NIS-8AK NIS-8AL NIS-8AM NIS-8AN NIS-8AO NIS-8AP NIS-8AQ NIS-8AR NIS-8AS NIS-8AT NIS-8AU NIS-8AV NIS-8AW SYSTEM NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS DESCRIPTION APRM-C FAILURE/DWNSCL/UPSCL/INOP APRM-D FAILURE-DWNSCL/UPSCL/INOP APRM-E FAILURE/DWNSCL/UPSCL/INOP APRM-F FAILURE/DWNSCL/UPSCL/INOP APRM FLOW UNIT FAILURE APRM FLOW UNIT A FAIL APRM FLOW UNIT B FAIL APRM FLOW UNIT C FAIL APRM FLOW UNIT D FAIL SRM-IRM INADEQUATE OVERLAP SRM-IRM A INADEQUATE OVERLAP SRM-IRM B INADEQUATE OVERLAP SRM-IRM C INADEQUATE OVERLAP SRM-IRM D INADEQUATE OVERLAP SRM-IRM E INADEQUATE OVERLAP SRM-IRM F INADEQUATE OVERLAP SRM-IRM G INADEQUATE OVERLAP SRM-IRM H INADEQUATE OVERLAP LPRM FAILURE UPSCALE/DOWNSCALE LPRM FAILURE UPSCALE/DOWNSCALE LPRM FAILURE UPSCALE/DOWNSCALE LPRM FAILURE UPSCALE/DOWNSCALE LPRM FAILURE UPSCALE/DOWNSCALE LPRM FAILURE UPSCALE/DOWNSCALE LPRM FAILURE UPSCALE/DOWNSCALE LPRM FAILURE UPSCALE/DOWNSCALE LPRM FAILURE UPSCALE/DOWNSCALE LPRM FAILURE UPSCALE/DOWNSCALE LPRM FAILURE UPSCALE/DOWNSCALE LPRM FAILURE UPSCALE/DOWNSCALE LPRM FAILURE UPSCALE/DOWNSCALE LPRM FAILURE UPSCALE/DOWNSCALE LPRM FAILURE UPSCALE/DOWNSCALE LPRM FAILURE UPSCALE/DOWNSCALE LPRM FAILURE UPSCALE/DOWNSCALE LPRM FAILURE UPSCALE/DOWNSCALE LPRM FAILURE UPSCALE/DOWNSCALE LPRM FAILURE UPSCALE/DOWNSCALE LPRM FAILURE UPSCALE/DOWNSCALE LPRM FAILURE UPSCALE/DOWNSCALE LPRM FAILURE UPSCALE/DOWNSCALE LPRM FAILURE UPSCALE/DOWNSCALE LPRM FAILURE UPSCALE/DOWNSCALE November 16, 1994 Page 9 of 27 APPENDIX C ATTACHMENT C-3 WASHINGTON PUBLIC POWER SUPPLY SYSTEM MALFUNCTIONS LISTING ID NIS-8AX NIS-8AY NIS-8AZ NIS-8B NIS-8BA NIS-8BB NIS-88C NIS-8BD NIS-8BE NIS-8BF NIS-8BG NIS-8BH NIS-8C NIS-8D NIS-8E NIS-8F NIS-8G NIS-8H NIS-8I NIS-8J NIS-8K NIS-8L NIS-8M NIS-8N NIS-80 NIS-8P NIS-8Q NIS-8R NIS-8S NIS-8T NIS-8U NIS-8V NIS-8W NIS-8X NIS-8Y NIS-8Z NSF-1 NSF-1A NSF-1B OED-1 OED-2 OED-3 OGS-1 SYSTEM NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS NIS EPS EPS EPS OED OED OED OGS DESCRIPTION LPRM FAILURE UPSCALE/DOWNSCALE LPRM FAILURE UPSCALE/DOWNSCALE LPRM FAILURE UPSCALE/DOWNSCALE LPRM FAILURE UPSCALE/DOWNSCALE LPRM FAILURE UPSCALE/DOWNSCALE LPRM FAILURE UPSCALE/DOWNSCALE LPRM FAILURE UPSCALE/DOWNSCALE LPRM FAILURE UPSCALE/DOWNSCALE LPRM FAILURE UPSCALE/DOWNSCALE LPRM FAILURE UPSCALE/DOWNSCALE LPRM FAILURE UPSCALE/DOWNSCALE LPRM FAILURE UPSCALE/DOWNSCALE LPRM FAILURE UPSCALE/DOWNSCALE LPRM FAILURE UPSCALE/DOWNSCALE LPRM FAILURE UPSCALE/DOWNSCALE LPRM FAILURE UPSCALE/DOWNSCALE LPRM FAILURE UPSCALE/DOWNSCALE LPRM FAILURE UPSCALE/DOWNSCALE LPRM FAILURE UPSCALE/DOWNSCALE LPRM FAILURE UPSCALE/DOWNSCALE LPRM FAILURE UPSCALE/DOWNSCALE LPRM FAILURE UPSCALE/DOWNSCALE LPRM FAILURE UPSCALE/DOWNSCALE LPRM FAILURE UPSCALE/DOWNSCALE LPRM FAILURE UPSCALE/DOWNSCALE LPRM FAILURE UPSCALE/DOWNSCALE LPRM FAILURE UPSCALE/DOWNSCALE LPRM FAILURE UPSCALE/DOWNSCALE LPRM FAILURE UPSCALE/DOWNSCALE LPRM FAILURE UPSCALE/DOWNSCALE LPRM FAILURE UPSCALE/DOWNSCALE LPRM FAILURE UPSCALE/DOWNSCALE LPRM FAILURE UPSCALE/DOWNSCALE LPRM FAILURE UPSCALE/DOWNSCALE LPRM FAILURE UPSCALE/DOWNSCALE LPRM FAILURE UPSCALE/DOWNSCALE POWER SUPPLY FAILURE-FUSE BLOWN P/S FAILURE-FUSE CB7A BLOWN P/S FAILURE-FUSE CB7B BLOWN TRANSFORMER LOCKOUT TR-S LOSS OF ALL OFFSITE POWER TRANSFORMER LOCKOUT TR-B SYSTEM LEAK CATALYTIC RECOMBINER November 16, 1994 Page 10 of 27 APPENDIX C ATTACHMENT C-3 WASHINGTON PUBLIC POWER SUPPLY SYSTEM MALFUNCTIONS LISTING ID 0GS-lA OGS-1B OGS-2 OGS-3 0GS-3A OGS-3B OGS-4 OGS-5 OGS-5A OGS-5B PCN-1 PCN-2 PCN-2A PCN-2B PCN-2C PCN-2D PCN-2E PCN-2F PCN-2G PCN-2H PCN-2I PCN-2J PCN-2K PCN-2L PCN-2M PCN-2N PCN-20 PCN-2P PCN-2Q PCN-2R PCN-3 PCN-3A PCN-3B PCN-3C PCN-3D PCN-4 PCN-5 PCN-5A PCN-5B PCR-1 PCR-10 PCR-2 PCR-3 SYSTEM OGS OGS OGS OGS OGS OGS OGS OGS OGS OGS PCN PCN PCN PCN PCN PCN PCN PCN PCN PCN PCN PCN PCN PCN PCN PCN PCN PCN PCN PCN PCN PCN PCN PCN PCN PCN PCN PCN PCN PCR PCR PCR PCR DESCRIPTION SYSTEM LEAK RECOMBINER OG-RC-5A SYSTEM LEAK RECOMBINER OG-RC-5B SYSTEM LEAK PREFILTER AREA SYSTEM LEAK IN CHARCOAL ADSORBER SYSTEM LEAK IN ADSORBER TRAIN A SYSTEM LEAK IN ADSORBER TRAIN B DEACITVATED STM LEAK IN BACH S JAE ROOM STM LEAK IN S JAE ROOM A STM LEAK IN SJAE ROOM B LK IN CONT DWNSTRM OF CEP-V-1A/B RUPT TAILPIP ABOVE SUPP POOL LVL RUPT MS-RV-1A TAILPIP ABV SP LVL RUPT MS-RV-2A TAILPIP ABV SP LVL RUPT MS-RV-3A TAILPIP'ABV SP LVL RUPT MS-RV-4A TAILPIP ABV SP LVL RUPT MS-RV-1B TAILPIP ABV SP LVL RUPT MS-RV-2B TAILPIP ABV SP LVL RUPT MS-RV-3B TAILPIP ABV SP LVL RUPT MS-RV-4B TAILPIP ABV SP LVL RUPT MS-RV-5B TAILPIP ABV SP LVL RUPT MS-RV-1C TAILPIP ABV SP LVL RUPT MS-RV-2C TAILPIP ABV SP LVL RUPT MS-RV-3C TAILPIP ABV SP LVL RUPT MS-RV-4C TAILPIP ABV SP LVL RUPT MS-RV-5C TAILPIP ABV SP LVL RUPT MS-RV-1D TAILPIP ABV SP LVL RUPT MS-RV-2D TAILPIP ABV SP LVL RUPT MS-RV-3D TAILPIP ABV SP LVL RUPT MS-RV-4D TAILPIP ABV SP LVL HI GAS CONCENTRATION IN PRI CONT HI H2 CONCENTRATION IN DRYWELL HI 02 CONCENTIMTION IN DRYWELL HI H2 CONCENTRATION IN WETWBLL'I 02 CONCENTRATION IN WETWELL HYDROGEN IGNITION CEP LEAKAGE CEP LEAKAGE (DRYWELL)CEP LEAKAGE (WETWELL)PLACE HOLDER PLACE HOLDER PLACE HOLDER PLACE HOLDER November 16, 1994 Page II of 27 APPENDIX C ATTACHMENT C-3 WASHINGTON PUBLIC POWER SUPPLY SYSTEM MALFUNCTIONS LISTING ID PCR-4 PCR-5 PCR-6 PCR-7 PCR-8 PCR-9 RBM-1 RBM-1A RBM-1B RCC-1 RCC-10 RCC-10A RCC-10B RCC-10C RCC-2 RCC-3 RCC-4 RCC-5 RCC-SA RCC-5B RCC-6 RCC-7 RCC-7A RCC-7B RCC-8 RCC-8A RCC-8B RCC-9 RCI-1 RCI-2 RCI-3 RCI-4 RCI-5 RCI-6 RCI-7 RCI-7A RCI-7B RCX-1 RCX-2 RCX-3 RCX-4 RCX4A RCX-4AA SYSTEM PCR PCR PCR PCR PCR PCR RBM RBM RBM RCC RCC RCC RCC RCC RCC RCC RCC RCC RCC RCC RCC RCC RCC RCC RCC RCC RCC RCC RCI RCI RCI RCI RCI RCI RCI RCI RCI RCX RCX RCX RCX RCX RCX DESCRIPTION PLACE HOLDER PLACE HOLDER PLACE HOLDER PLACE HOLDER PLACE HOLDER PLACE HOLDER ROD BLOCK MONITOR FAILURE RBM-A FAILURE RBM-B FAILURE RCC LK IN SUPPLY HDR IN PRI CONT RUPT DW COOLING LN INLET/OUTLET RUPT DW COOLING LN CRA-CC-1A/B/C RUPT DW COOLING LN TO CRA-CC-2B RUPT DW COOLING LN FRM CRA-CC-2B RCCW RETURN HDR LK IN PRI CONT RCCW LEAK AT PUMP SUCTION RCCW LK IN SUPPLY HDR TO OFF GAS LOSS RCCW COOLING TO RECIRC PUMP LOSS OF RCCW COOLING TO RRC-P-1A LOSS OF RCCW COOLING TO RRC-P-1B RCCW LK DOWNSTREAM OF RCC-FT-29 RCCW LK CRD PUMP BEARING COOLER RCCW LK AT CRD-P-1A BRNG COOLER RCCW LK AT CRD-P-1B BRNG COOLER LOSS RCCW FLOW CRD PMP BRNG CLR LOSS RCCW FLOW CRD-P-1A BRNG CLR LOSS RCCW FLOW CRD-P-1B BRNG CLR LOSS RCCW FLOW TO DW EDR COOLER RCIC TURBINE TRIP/PAILS TO TRIP RUPTURE STM SUPPLY TO RCIC IN PC RCIC TUR EXH DIA RUPTURE IN RB RUPT IN STM LN DWNSTRM RCIC-V-45 RUPTURE TURB EXH LINE IN RX BLDG STEAM LINE BREAK AT RCIC TUIUSINE RCIC LOGIC FAILURE RCIC LOGIC FAILURE DIVISION 1 RCIC LOGIC FAILURE DIVISION 2 CLAD PERFORATION GROSS CLAD FAILURE HIGH ROD WORTH SKEWED FLUX DISTRIBUTION SKEWED FLUX DISTRIBUTION SKEWED FLUX DISTRIBUTION Novembn 16, 1994 Page 12of27 APPENDIX C ATTACHMENT C-3 WASHINGTON PUBLIC POWER SUPPLY SYSTEM MALFUNCTIONS LISTING ID RCX-4AB RCX-4AC RCXPAD RCX-4AE RCX-4AF RCX-4AG RCX-4AH RCX-4AI RCX-4AJ RCX-4AK RCX4AL RCX4AM RCX-4AN RCXPAO RCX4AP RCX-4AQ RCX-4AR RCX-4AS RCX-4AT RCX4AU RC XIV RCX-4AW RCX-4AX RCX-4B RCX-4C RCX4D RCX-4E RCX-4F RCX4G RCX-4H RCX-4I RCX-4J RCX-4K RCX-4L" RCX-4M RCX-4N RCXPO RCX-4P RCX-4Q RCX-4R RCX-4S RCX-4T RCXPU SYSTEM RCX RCX RCX RCX RCX RCX RCX RCX RCX RCX RCX RCX RCX RCX RCX RCX RCX RCX RCX RCX RCX RCX RCX RCX RCX RCX RCX RCX RCX RCX RCX RCX RCX RCX RCX RCX RCX'CX RCX RCX RCX RCX RCX DESCRIPTION SKEWED FLUX DISTRIBUTION SKEWED FLUX DISTRIBUTION SKEWED FLUX DISTRIBUTION SKEWED FLUX DISTRIBUTION SKEWED FLUX DISTRIBUTION SKEWED FLUX DISTRIBUTION SKEWED FLUX DISTRIBUTION SKEWED FLUX DISTRIBUTION SKEWED FLUX DISTRIBUTION SKEWED FLUX DISTRIBUTION SKEWED FLUX DISTRIBUTION SKEWED FLUX DISTRIBUTION SKEWED FLUX DISTRIBUTION SKEWED FLUX DISTRIBUTION SKEWED FLUX DISTRIBUTION SKEWED FLUX DISTRIBUTION SKEWED FLUX DISTRIBUTION SKEWED FLUX DISTRIBUTION SKEWED FLUX DISTRIBUTION SKEWED FLUX DISTRIBUTION SKEWED FLUX DISTRIBUTION SKEWED FLUX DISTRIBUTION SKEWED FLUX DISTRIBUTION SKEWED FLUX DISTRIBUTION SKEWED FLUX DISTRIBUTION SKEWED FLUX DISTRIBUTION SKEWED FLUX DISTRIBUTION SKEWED FLUX DISTRIBUTION SKEWED FLUX DISTRIBUTION SKEWED FLUX DISTRIBUTION SKEWED FLUX DISTRIBUTION SKEWED FLUX DISTRIBUTION SKEWED FLUX DISTRIBUTION SKEWED FLUX DISTRIBUTION SKEWED FLUX DISTRIBUTION SKEWED FLUX DISTRIBUTION SKEWED FLUX DISTRIBUTION SKEWED FLUX DISTRIBUTION SKEWED FLUX DISTRIBUTION SKEWED FLUX DISTRIBUTION SKEWED FLUX DISTRIBUTION SKEWED FLUX DISTRIBUTION SKEWED FLUX DISTRIBUTION November 16, 1994 Page 13 of 27 APPENDIX C A%I ACHMENT C-3 WASHINGTON PUHLIC POWER SUPPLY SYSTEM MALFUNCTIONS LISTING ID RCX-4V RCX-4W RCX-4X RCX-4Y RCXCZ RCX-5 RCX-5A RCX-5B RFC-1 RFC-2 RFC-3 RFC-3A RFC-3B RFC-4 RFC-4A RFC-4B RFC-4C RFC-4D RFC-5 RHR-1 RHR-2 RHR-3 RHRP RHRQA RHR-4B RMC-1 RMC-1A RMC-1AA RMC-1AB RMC-1AC RMC-1 AD RMC-lAERMC-lAF RMC-1AG RMC-1 AH RMC-1AI RMC-1AJ RMC-1AK RMC-1AL RMC-1AM RMC-1AN RMC-1AO RMC-1AP SYSTEM RCX RCX RCX RCX RCX RCX RCX RCX RFC RFC RFC RFC RFC RFC RFC RFC RFC RFC RFC RHR RHR RHR RHR RHR RMC RMC RMC RMC RMC RMC RMC RMC RMC RMC RMC RMC RMC DESCRIPTION SKEWED FLUX DISTRIBUTION SKEWED FLUX DISTRIBUTION SKEWED FLUX DISTRIBUTION SKEWED FLUX DISTRIBUTION SKEWED FLUX DISTRIBUTION POWER OSCILLATIONS PWR OSCILL,GLOBAL gN PHASE)PWR OSCILL,REGION (OUT OF PHASE)RUPT IN HYD LN AT RRC-V-60B ACT RUPT IN HYD LN AT RRC-V-60A ACT FAIL IN FEEDBACK LOOP-VLV POS FAIL IN VLV POS FB RRC-M/A-611A FAIL IN VLV POS FB RRC-M/A-611B HPU FAILURE-LEAD/BACKUP SYSTEM HPU A SYS 1 FAILS-HY-HP-Al HPU B SYS 1 FAILS-HY-HP-Bl HPU A SYS 2 FAILS-HY-HP-A2 HPU B SYS 2 FAILS-HY-HP-B2 DEACIIVATED LINE BREAK AT RHR-P-2A SUCTION LINE BREAK AT RHR-HX-1B S/D COOLING LINE BRK IN SEC CONT LPCI LOGIC FAILURE-A, B, AND C LPCI LOGIC FAILURE A LPCI LOGIC FAILURE B AND C HCU TRANSPONDER FAILURE HCU TRANSPONDER FAILURE HCU TRANSPONDER FAILURE HCU'IRANSPONDER FAILURE HCU TRANSPONDER FAILURE HCU TRANSPONDER FAILURE HCU TRANSPONDER FAILURE HCU TRANSPONDER FAILURE HCU TRANSPONDER FAILURE HCU TRANSPONDER FAILURE HCU TRANSPONDER FAILURE HCU TRANSPONDER FAILURE HCU'IRANSPONDER FAILURE HCU TRANSPONDER FAILURE HCU TRANSPONDER FAILURE HCU TRANSPONDER FAILURE HCU TRANSPONDER FAILURE HCU TRANSPONDER FAILURE November 16, 1994 Page 14 of 27 APPENDIX C ATTACHMENT C-3 WASHINGTON PUBLIC POWER SUPPLY SYSTEM MALFUNCTIONS LISTING ID RMC-lAQ RMC-1AR RMC-1AS RMC-1 AT RMC-lAU RMC-1AV RMC-1AW RMC-1AX RMC-lAY RMC-1AZ RMC-1B RMC-1BA RMC-1BB RMC-1BC RMC-1BD RMC-1BE RMC-1BF RMC-1BG RMC-1BH RMC-1C RMC-1D RMC-1E RMC-1F RMC-1G RMC-1H RMC-1I RMC-1J RMC-1K RMC-1L RMC-1M RMC-1N RMC-10 RMC-1P RMC-1Q RMC-1R RMC-1S RMC-1T RMC-1U RMC-1V RMC-1W RMC-1X RMC-1Y RMC-1Z SYSTEM RMC RMC RMC RMC RMC RMC RMC RMC, RMC RMC RMC RMC RMC RMC RMC RMC RMC RMC RMC RMC RMC RMC RMC RMC RMC RMC RMC RMC RMC RMC RMC"RMC RMC RMC RMC RMC RMC RMC RMC RMC RMC RMC RMC DESCRIPTION HCU TRANSPONDER FAILURE HCU TRANSPONDER FAILURE HCU TRANSPONDER FAILURE HCU TRANSPONDER FAILURE HCU TRANSPONDER FAILURE HCU TRANSPONDER FAILURE HCU TRANSPONDER FAILURE HCU TRANSPONDER FAILURE HCU TRANSPONDER FAILURE HCU, TRANSPONDER FAILURE HCU TRANSPONDER FAILURE HCU TRANSPONDER FAILURE HCU TIMNSPONDER FAILURE HCU TRANSPONDER FAILURE HCU TRANSPONDER FAILURE HCU TRANSPONDER FAILURE HCU TRANSPONDER FAILURE HCU'IRANSPONDER FAILURE HCU TRANSPONDER FAILURE HCU TIMNSPONDER FAILURE HCU TRANSPONDER FAILURE HCU TRANSPONDER FAILURE HCU TRANSPONDER FAILURE HCU TRANSPONDER FAILURE HCU TRANSPONDER FAILURE HCU TRANSPONDER FAILURE HCU'IRANSPONDER FAILURE HCU'IRANSPONDER FAILURE HCU TRANSPONDER FAILURE HCU TRANSPONDER FAILURE HCU TRANSPONDER FAILURE HCU TRANSPONDER FAILURE HCU TRANSPONDER FAILURE HCU TRANSPONDER FAILURE HCU TRANSPONDER FAILURE HCU TRANSPONDER FAILURE HCU TRANSPONDER FAILURE HCU TRANSPONDER FAILURE HCU TRANSPONDER FAILURE HCU TRANSPONDER FAILURE HCU TRANSPONDER FAILURE HCU TRANSPONDER FAILURE HCU TRANSPONDER FAILURE November 16, 1994 Page 15 of 27 APPENDIX C ATTACHMENT C-3 WASHINGTON PUBLIC POWER SUPPLY SYSTEM MALFUNCTIONS LISTING ID RMC-2 RMC-3 RMC-4 RMC-4A RMC-4AA RMC-4AB RMC-4AC RMC-4AD RMC-4AE RMC-4AF RMC-4AG RMC-4AH RMC-4AI RMC-4AJ RMC-4AK RMC-4AL RMC-4AM RMC-4AN RMC-4AO RMC-4AP RMC-4AQ RMC-4AR RMC-4AS RMC-4AT RMC-4AU RMC-4AV RMC-4AW RMC-4AX RMC-4AY RMC-4AZ RMC-48 RMC-4BA RMC-4BB RMC-4BC RMC-4BD RMC-4BE RMC-4BF RMC-4B6 RMC-4BH RMC-4C RMC-4D RMC-4E RMC-4F SYSTEM RMC RMC CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD DESCRIPTION ROD POSITION INDICATION FAILURE RDCS FAILURE ROD DRIFTS IN/OUT ROD DRIFTS IN/OUT ROD DRIFTS IN/OUT ROD DRIFTS IN/OUT ROD DRIFTS IN/OUT ROD DRIFTS IN/OUT ROD DRIFTS IN/OUT ROD DRIFTS IN/OUT ROD DRIFTS IN/OUT ROD DRIFTS IN/OUT ROD DRIFTS IN/OUT ROD DRIFTS IN/OUT ROD DRIFTS IN/OUT ROD DRIFTS IN/OUT ROD DRIFTS IN/OUT ROD DRIFTS IN/OUT ROD DRIFTS IN/OUT ROD DRIFTS IN/OUT ROD DRIFTS IN/OUT ROD DRIFTS IN/OUT ROD DRIFTS IN/OUT ROD DRIFTS IN/OUT ROD DRIFTS IN/OUT ROD DRIFTS IN/OUT ROD DRIFTS IN/OUT ROD DRIFTS IN/OUT ROD DRIFTS IN/OUT ROD DRIFTS IN/OUT ROD DRIFTS IN/OUT ROD DRIFTS IN/OUT ROD DRIFTS IN/OUT ROD DRIFTS IN/OUT ROD DRIFTS IN/OUT ROD DRIFTS IN/OUT ROD DRIFTS IN/OUT ROD DRIFTS IN/OUT ROD DRIFTS IN/OUT ROD DRIFTS IN/OUT ROD DRIFTS IN/OUT ROD DRIFTS IN/OUT ROD DRIFTS IN/OUT November 16, 1994 Page 16 of 27 APPENDIX C ATTACHMENT C-3 WASHINGTON PUBLIC POWER SUPPLY SYSTEM MALFUNCTIONS LISTING ID RMC-4G RMC-4H RMC-4I RMC-4J RMC-4K RMC-4L RMC-4M RMC-4N RMC-40 RMC-4P RMC-4Q RMC-4R RMC-4S RMC-4T RMC-4U RMC-4V RMC-4W RMC-4X RMC-4Y RMC-4Z RMC-5 RMC-5A RMC-5AA RMC-SAB RMC-SAC RMC-SAD RMC-5AE RMC-SAP RMC-SAG RMC-5AH RMC-SAI RMC-5AJ RMC-SAK RMC-SAL RMC-SAM RMC-5AN RMC-5AO RMC-SAP RMC-SAQ RMC-SAR RMC-5AS RMC-5AT RMC-SAU SYSTEM CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD DESCRIPTION ROD DRIFTS IN/OUT ROD DRIFTS IN/OUT ROD DRIFTS IN/OUT ROD DRIFTS IN/OUT ROD DRIFTS IN/OUT ROD DRIFTS IN/OUT ROD DRIFTS IN/OUT ROD DRIFTS IN/OUT ROD DRIFTS IN/OUT ROD DRIFTS IN/OUT ROD DRIFTS IN/OUT ROD DRIFTS IN/OUT ROD DRIFTS IN/OUT ROD DRIFTS IN/OUT ROD DRIFTS IN/OUT ROD DRIFTS IN/OUT ROD DRIFTS IN/OUT ROD DRIFTS IN/OUT ROD DRIFTS IN/OUT ROD DRIFTS IN/OUT STUCK ROD STUCK ROD STUCK ROD STUCK ROD STUCK ROD STUCK ROD STUCK ROD STUCK ROD STUCK ROD STUCK ROD STUCK ROD STUCK ROD STUCK ROD STUCK ROD STUCK ROD STUCK ROD STUCK ROD STUCK ROD STUCK ROD STUCK ROD STUCK ROD STUCK ROD STUCK ROD November 16, 1994 Page 17 of 27 APPENDIX C ATTACHMENT C-3 WASHINGTON PUBLIC POWER SUPPLY SYSTEM MALFUNCTIONS LISTING ID RMC-SAV RMC-SAW RMC-SAX RMC-5AY RMC-SAZ RMC-5B RMC-SBA RMC-SBB RMC-SBC RMC-SBD RMC-5BE RMC-5BF RMC-5BG RMC-5BH RMC-SC RMC-SD RMC-SE RMC-SF RMC-5G RMC-SH RMC-SI RMC-SJ RMC-5K RMC-SL RMC-SM RMC-5N RMC-50 RMC-SP RMC-SQ RMC-SR RMC-SS RMC-ST RMC-SU RMC-SV RMC-SW RMC-SX RMC-SY RMC-SZ RMC-6 RMC-6A RMC-6AA RMC-6AB RMC-6AC SYSTEM CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD , CRD CRD CRD CRD CRD CRD CRD CRD DESCRIPTION STUCK ROD STUCK ROD STUCK ROD STUCK ROD STUCK ROD STUCK ROD STUCK ROD STUCK ROD STUCK ROD STUCK ROD STUCK ROD STUCK ROD STUCK ROD STUCK ROD STUCK ROD STUCK ROD STUCK ROD STUCK ROD STUCK ROD STUCK ROD STUCK ROD STUCK ROD STUCK ROD STUCK ROD STUCK ROD STUCK ROD STUCK ROD STUCK ROD STUCK ROD STUCK ROD STUCK ROD STUCK ROD STUCK ROD STUCK ROD STUCK ROD STUCK ROD STUCK ROD STUCK ROD UNCOUPLED ROD UNCOUPLED ROD UNCOUPLED ROD UNCOUPLED ROD UNCOUPLED ROD November 16, 1994 Page 18 of 27 APPENDIX C ATTACHMENT C-3 WASHINGTON PUBLIC POWER SUPPLY SYSTEM MALFUNCTIONS LISTING ID RMC-6AD RMC-6AE RMC-6AF RMC-6AG RMC-6AH RMC-6AI RMC-6AJ RMC-6AK RMC-6AL RMC-6AM RMC-6AN RMC-6AO RMC-6AP RMC-6AQ RMC-6AR RMC-6AS RMC-6AT RMC-6AU RMC-6AV RMC-6AW RMC-6AX RMC-6AY RMC-6AZ RMC-6B RMC-6BA RMC-6BB RMC-6BC RMC-6BD RMC-6BE RMC-6BF RMC-6B6 RMC-6BH RMC-6C RMC-6D RMC-6E RMC-6F RMC-6G RMC-6H RMC-6I RMC-6J RMC-6K RMC-6L RMC-6M SYSTEM CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD DESCRIPTION UNCOUPLED ROD UNCOUPLED ROD UNCOUPLED ROD UNCOUPLED ROD UNCOUPLED ROD UNCOUPLED ROD UNCOUPLED ROD UNCOUPLED ROD UNCOUPLED ROD UNCOUPLED ROD UNCOUPLED ROD UNCOUPLED ROD UNCOUPLED ROD UNCOUPLED ROD UNCOUPLED ROD UNCOUPLED ROD UNCOUPLED ROD UNCOUPLED ROD UNCOUPLED ROD UNCOUPLED ROD UNCOUPLED ROD UNCOUPLED ROD UNCOUPLED ROD UNCOUPLED ROD UNCOUPLED ROD UNCOUPLED ROD UNCOUPLED ROD UNCOUPLED ROD UNCOUPLED ROD UNCOUPLED ROD UNCOUPLED ROD UNCOUPLED ROD UNCOUPLED ROD UNCOUPLED ROD UNCOUPLED ROD UNCOUPLED ROD UNCOUPLED ROD UNCOUPLED ROD UNCOUPLED ROD UNCOUPLED ROD UNCOUPLED ROD UNCOUPLED ROD UNCOUPLED ROD November 16, 1994 Page 19 of 27 APPENDIX C ATTACHMENT C-3 WASHINGTON PUBLIC POWER SUPPLY SYSTEM MALFUNCTIONS LISTING ID RMC-6N RMC-60 RMC-6P RMC-6Q RMC-6R RMC-6S RMC-6T RMC-6U RMC-6V RMC-6W RMC-6X RMC-6Y RMC-6Z RMC-7 RMC-7A RMC-7AA RMC-7AB RMC-7AC RMC-7AD RMC-7AE RMC-7AF RMC-7AG RMC-7AH RMC-7AI RMC-7AJ RMC-7AK RMC-7AL RMC-7AM RMC-7AN RMC-7AO RMC-7AP RMC-7AQ RMC-7AR RMC-7AS RMC-7AT RMC-7AU RMC-7AV RMC-7AW RMC-7AX RMC-7AY RMC-7AZ RMC-7B RMC-7BA SYSTEM CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD CRD RPS RPS RPS RPS RPS RPS RPS RPS RPS RPS RPS RPS RPS RPS RPS RPS RPS RPS RPS RPS RPS RPS RPS RPS RPS RPS RPS RPS RPS RPS DESCRIPTION UNCOUPLED ROD UNCOUPLED ROD UNCOUPLED ROD UNCOUPLED ROD UNCOUPLED ROD UNCOUPLED ROD UNCOUPLED ROD UNCOUPLED ROD UNCOUPLED ROD UNCOUPLED ROD UNCOUPLED ROD UNCOUPLED ROD UNCOUPLED ROD SINGLE ROD SCRAM SINGLE ROD SCRAM SINGLE ROD SCRAM SINGLE ROD SCRAM SINGLE ROD SCRAM SINGLE ROD SCRAM SINGLE ROD SCRAM SINGLE ROD SCRAM SINGLE ROD SCRAM SINGLE ROD SCRAM SINGLE ROD SCRAM SINGLE ROD SCRAM SINGLE ROD SCRAM SINGLE ROD SCRAM SINGLE ROD SCRAM SINGLE ROD SCRAM SINGLE ROD SCRAM SINGLE ROD SCRAM SINGLE ROD SCRAM SINGLE ROD SCRAM SINGLE ROD SCRAM SINGLE ROD SCRAM SINGLE ROD SCRAM SINGLE ROD SCRAM SINGLE ROD SCRAM SINGLE ROD SCRAM SINGLE ROD SCRAM SINGLE ROD SCRAM SINGLE ROD SCRAM SINGLE ROD SCRAM November 16, 1994 Page 20 of 27 APPENDIX C ATTACHMENT C-3 WASHINGTON PUBLIC POWER SUPPLY SYSTEM MALFUNCTIONS LISTING ID RMC-7BB RMC-7BC RMC-7BD RMC-7BE RMC-7BF RMC-7BG RMC-7BH RMC-7C RMC-7D RMC-7E RMC-7F RMC-7G RMC-7H RMC-7I RMC-7J RMC-7K RMC-7L RMC-7M RMC-7N RMC-70 RMC-7P RMC-7Q RMC-7R RMC-7S RMC-7T RMC-7U RMC-7V RMC-7W RMC-7X RMC-7Y RMC-7Z RMC-8 RMC-8A RMC-8AA RMC-8AB RMC-8AC RMC-8AD RMC-8AE RMC-8AF RMC-8AG RMC-8AH RMC-8AI RMC-8AJ SYSTEM RPS RPS RPS RPS RPS RPS RPS RPS RPS RPS RPS RPS RPS RPS RPS RPS RPS RPS RPS RPS RPS RPS RPS RPS RPS RPS RPS RPS RPS RPS RPS RMC RMC RMC RMC RMC RMC RMC RMC RMC RMC RMC RMC DESCRIPTION SINGLE ROD SCRAM SINGLE ROD SCRAM SINGLE ROD SCRAM SINGLE ROD SCRAM SINGLE ROD SCRAM SINGLE ROD SCRAM SINGLE ROD SCRAM SINGLE ROD SCRAM SINGLE ROD SCRAM SINGLE ROD SCRAM SINGLE ROD SCRAM SINGLE ROD SCRAM SINGLE ROD SCRAM SINGLE ROD SCRAM SINGLE ROD SCRAM SINGLE ROD SCRAM SINGLE ROD SCRAM SINGLE ROD SCRAM SINGLE ROD SCRAM SINGLE ROD SCRAM SINGLE ROD SCRAM SINGLE ROD SCRAM SINGLE ROD SCRAM SINGLE ROD SCRAM SINGLE ROD SCRAM SINGLE ROD SCRAM SINGLE ROD SCRAM SINGLE ROD SCRAM SINGLE ROD SCRAM SINGLE ROD SCRAM SINGLE ROD SCRAM REED SWITCH FAILURE REED SWITCH FAILURE REED SWITCH FAILURE REED SWITCH FAILURE REED SWITCH FAILURE REED SWITCH FAILURE REED SWITCH FAILURE REED SWITCH FAILURE REED SWITCH FAILURE REED SWITCH FAILURE REED SWITCH FAILURE REED SWITCH FAILURE November 16, 1994 Page 21 of 27 APPENDIX C ATTACHMENT C-3 WASHINGTON PUBLIC POWER SUPPLY SYSTEM MALFUNCTIONS LISTING ID RMC-8AK RMC-SAL RMC-SAM RMC-8AN RMC-8AO RMC-SAP RMC-8AQ RMC-8AR RMC-8AS RMC-SAT RMC-SAU RMC-SAV RMC-8AW RMC-8AX RMC-8AY RMC-SAZ RMC-8B RMC-8BA RMC-8BB RMC-SBC RMC-8BD RMC-8BE RMC-8BF RMC-8BG RMC-88H RMC-8C RMC-SD RMC-8E RMC-SF RMC-8G RMC-8H RMC-SI RMC-SJ RMC-8K RMC-8L RMC-SM RMC-SN RMC-80 RMC-8P RMC-8Q RMC-8R RMC-8S RMC-8T SYSTEM RMC RMC RMC RMC RMC RMC RMC RMC RMC RMC RMC RMC RMC RMC RMC RMC RMC RMC RMC RMC RMC RMC RMC RMC RMC RMC RMC RMC RMC RMC RMC RMC RMC RMC RMC RMC RMC RMC RMC RMC RMC RMC RMC DESCRIPTION REED SWITCH FAILURE REED SWITCH FAILURE REED SWITCH FAILURE REED SWITCH FAILURE REED SWITCH FAILURE REED SWITCH FAILURE REED SWITCH FAILURE REED SWITCH FAILURE REED SWITCH FAILURE REED SWITCH FAILURE REED SWITCH FAILURE REED SWITCH FAILURE REED SWITCH FAILURE REED SWITCH FAILURE REED SWITCH FAILURE REED SWITCH FAILURE REED SWITCH FAILURE REED SWITCH FAILURE REED SWITCH FAILURE REED SWITCH FAILURE REED SWITCH FAILURE REED SWITCH FAILURE REED SWITCH FAILURE REED SWITCH FAILURE REED SWITCH FAILURE REED SWITCH FAILURE REED SWITCH FAILURE REED SWITCH FAILURE REED SWITCH FAILURE REED SWITCH FAILURE REED SWITCH FAILURE REED SWITCH FAILURE REED SWITCH FAILURE REED SWITCH FAILURE REED SWITCH FAILURE REED SWITCH FAILURE REED SWITCH FAILURE REED SWITCH FAILURE REED SWITCH FAILURE REED SWITCH FAILURE REED SWITCH FAILURE REED SWITCH FAILURE REED SWITCH FAILURE November 16, 1994 Page 22 of 27 APPENDIX C ATTACHMENT C-3 WASHINGTON PUBLIC POWER SUPPLY SYSTEM MALFUNCTIONS LISTING ID RMC-8U RMC-8V RMC-8W RMC-8X RMC-8Y RMC-8Z RPS-1 RPS-1A RPS-1B RPS-1C RPS-1D RPS-1E RPS-1F RPS-1G RPS-1H RRP-1 RRP-1A RRP-1B RRP-1C RRP-1D RRP-2 RRP-2A RRP-2B RRS-1 RRS-lA RRS-1B RRS-2 RRS-2A RRS-2B RRS-2C RRS-2D RRS-2E RRS-2F RRS-2G RRS-2H RRS-2I RRS-2J RRS-3 RRS-3A RRS-3B RRS-3C RRS-3D RRS-4 SYSTEM RMC RMC RPS RPS RPS RPS RRP RRP RRP RRP RRP RRP RRP RRP RRS RRS RRS RRS RRS RRS RRS RRS RRS RRS RRS RRS RRS RRS RRS RRS RRS RRS RRS RRS DESCRIPTION REED SWITCH FAILURE REED SWITCH FAILURE REED SWITCH FAILURE REED SWITCH FAILURE REED SWITCH FAILURE REED SWITCH FAILURE RPS SCRAM GROUP FUSES BLOWN RPS SCRAM FUSE BLOWN-GPl F18A RPS SCRAM FUSE BLOWN-GP1 F18B RPS SCRAM FUSE BLOWN-GP2 F18E RPS SCRAM FUSE BLOWN-GP2 F18F RPS SCRAM FUSE BLOWN-GP3 F18C RPS SCRAM FUSE BLOWN-GP3 F18D RPS SCRAM FUSE BLOWN-GP4 F18G RPS SCRAM FUSE BLOWN-GP4 F18H RECIRCULATION PUMP SEAL FAILURE RRC-P-1A LOWER SEAL FAILURE RRC-P-1B LOWER SEAL FAILURE RRC-P-1A UPPER SEAL FAILURE RRC-P-1B UPPER SEAL FAILURE RECIRCULATION PUMP HI VIBRATION RRC-P-1A HIGH VIBRATION RRC-P-1B HIGH VIBRATION HIGH REACTOR WATER CONDUCTIVITY HI RX WATER COND VIA RWCU-DM-A HI RX WATER COND VIA RWCU-DM-B JET PUMP FAILURE FAILURE JET PUMPS 1 AND 2 FAILURE JET PUMPS 3 AND 4 FAILURE JET PUMPS 5 AND 6 FAILURE JET PUMPS 7 AND 8 FAILURE JET PUMPS 9 AND 10 FAILURE JET PUMPS 11 AND 12 FAILURE JET PUMPS 13 AND 14 FAILURE JET PUMPS 15 AND 16 FAILURE JET PUMPS 17 AND 18 FAILURE JET PUMPS 19 AND 20 MN STM LN BRK AFTER FLOW RSTRCTR MN STM LN A BRK AFT FLOW RSTRCIR MN STM LN B BRK AFT FLOW RSTRCI'R MN STM LN C BRK AFT FLOW RSTRCIR MN STM LN D BRK AFT FLOW RSTRCTR RECIRC LN RUPT-PMP A/B SUCT/DISC November 16, 1994 Page 23 of 27 APPENDIX C ATTACHMENT C-3 WASHINGTON PUBLIC POWER SUPPLY SYSTEM MALFUNCTIONS LISTING ID RRS-4A RRS-4B RRSPC RRS-4D RRS-5 RRS-5A RRS-5B RRS-5C RRS-5D RRS-5E RRS-5F RRS-6 RRS-6A RRS-6B RRS-6C RRS-6D RRS-7 RRS-7A RRS-7B RRS-7C RRS-7D RRS-7E RRS-7F RRS-7G RRS-7H RRS-8 RRS-8A RRS-8B RRS-8C RRS-8D RRS-9 RRS-9A RRS-9B RRS-9C RRS-9D RSC-1 RWB-1 RWB-2 RWB-2A RWB-2B RWM-1 RWU-1 RWU-lA SYSTEM RRS RRS RRS RRS RRS RRS RRS RRS RRS RRS RRS RRS RRS RRS RRS RRS RRS RRS RRS RRS RRS RRS RRS RRS RRS RRS RRS RRS RRS RRS RRS RRS RRS RRS RRS RSC RWB RWB RWB RWB RWM RWU RWU DESCRIPTION RECIRC LINE RUPT-RRC-P-1A SUCT RECIRC LINE RUPT-RRC-P-1B SUCT RECIRC LINE RUPT-RRC-P-1A DISCH RECIRC LINE RUPT-RRC-P-1B DISCH INSTRUMENT LINE VARIABLE LEG BRK INST VAR LN BRK-PENETRATION 12A INST VAR LN BRK-PENETRATION 12B INST VAR LN BRK-PENKZViTION 12C INST VAR LN BRK-PENEl'RATION 12D INST VAR LN BRK-PENETRATION 13A INST VAR LN BRK-PENETRATION 13B MAIN STM LN BREAK IN STM TUNNEL MSL-A BREAK IN THE STEAM TUNNEL MSL-B BREAK IN THE STEAM TUNNEL MSL-C'BREAK IN THE STEAM TUNNEL MSL-D BREAK IN THE STEAM TUNNEL INST LINE REFERENCE LEG BREAK INST LN BRK BTW RPV&CU4A IN CONT INST LN BRK BTW RPV&CU4B IN CONT INST LN BRK BTW RPV&CU4C IN CONT INST LN BRK BTW RPV&CU4D IN CONT INST LN BRK DOWNSTRM PI-EFC-X114 INST LN BRK DOWNSTRM PI-EFC-X109 INST LN BRK DOWNSTRM PI-EFC-X112 INST LN BRK DOWNSTRM PI-EFC-X106 MN STEAM LN BRK IN TURBINE BLDG MSL-A BREAK IN TURBINE BUILDING MSL-B BREAK IN TUIU3INE BUILDING MSL-C BREAK IN TURBINE BUILDING MSL-D BREAK IN TURBINE BUILDING MN STM LN BRK BEFORE FLW RSTRCTR MN STM LN A BRK BFR FLOW RSTRCIR MN STM LN B BRK BFR FLOW RSTRCIR MN STM LN C BRK BFR FLOW RSTRCIR MN STM LN D BRK BFR FLOW RSTRCIR RSCS FAILURE EARTHQUAKE RADWASTE TANK LEAKS RADWASTE TANK EDR-TK-2 LEAK RADWASTE TANK FDR-TK-6 LEAK RWM FAILURE RWCU LEAK IN PUMP ROOM LEAK IN RWCU PUMP ROOM-A November 16, 1994 Page 24 of27 APPENDIX C ATTACHMENT C-3 WASHINGTON PUBLIC POWER SUPPLY SYSTEM MALFUNCTIONS LISTING ID RWU-1B RWU-2 RWU-3, RWU-4 RWU-5 RWU-5A RWU-5B SCN-1 SCN-1A SCN-18 SLC-1 SSW-1 TLO-1 TLO-2 TLO-2A TLO-2B TLO-2C TLO-2D TLO-3 TLO-3A TLO-38 TLO-3C TLO-3D TLO-3E TLO-3F TLO-3G TLO-3H TLO-3I TLO-3J TLO-3K TSI-1 TSI-1A TSI-1B TSI-1C TSI-1D TSI-1E TSI-1F TSI-1G TSI-1H TSI-1I TSI-1J TSI-1K TSI-2 SYSTEM RWU RWU RWU=RWU RWU RWU RWU SCN SCN SCN SLC SSW TLO TLO TLO TLO TLO TLO TLO TLO TLO TLO TLO TLO TLO TLO, TLO TLO TLO TLO TSI TSI TSI TSI TSI TSI TSI TSI TSI TSI TSI TSI TSI DESCRIPTION LEAK IN RWCU PUMP ROOM-B RWCU LEAK IN RETURN LINE RWCU LEAK IN DRYWELL SUCT LINE RWCU LEAK IN HEAT EXCHANGER AREA RWCU DEMNERALIZER PLUGGED RWCU DEMN-A PLUGGED RWCU DEMN-B PLUGGED RUPTURE IN SGT FILTER UNITS RUPT IN SGT FILTER UNIT-TRAIN A RUPT IN SGT FILTER UNIT-TRAIN B RUPTURE IN SLC COMMON PUMP DISCH LEAK BETWN SW-V-2B AND FI-602B TO-TK-2 TANK LEAK TURBINE LUBE OIL SYSTEM LEAK TURBINE LUBE OIL SYSTEM LEAK A TURBINE LUBE OIL SYSTEM LEAK B TURBINE LUBE OIL SYSTEM LEAK C TURBINE LUBE OIL SYSTEM LEAK D RESTRICTED BEARING OIL PATH RESTRICTED OIL PATH BEARING¹1 RESTRICTED OIL PATH BEARING¹2 RESTRICTED OIL PATH BEARING¹3 RESTRICTED OIL PATH BEARING¹4 RESTRICTED OIL PATH BEARING¹5 RESTRICTED OIL PATH BEARING¹6 RESTRICTED OIL PATH BEARING¹7 RESTRICTED OIL PATH BEARING¹8 RESTRICTED OIL PATH BEARING¹9 RESTRICTED OIL PATH BEARING¹10 RESTRICTED OIL PATH BEARING¹11 HIGH TURBINE/GEN BEARING TEMP.HIGH TG TEMPERATURE BEARING¹1 HIGH TG TEMPERATURE BEARING¹2 HIGH TG TEMPERATURE BEARING¹3 HIGH TG TEMPERATURE BEARING¹4 HIGH TG TEMPERATURE BEARING¹5 HIGH TG TEMPERATURE BEARING¹6 HIGH TG TEMPERATURE BEARING¹7 HIGH TG TEMPERATURE BEARING¹8 HIGH TG TEMPERATURE BEARING¹9 HIGH TG TEMPERATURE BEARING¹10 HIGH TG TEMPERATURE BEARING¹11 HIGH THRUST BEARING WEAR November 16, 1994 Page 25 of 27 APPENDIX C ATTACHMENT C-3 WASHINGTON PUBLIC POWER SUPPLY SYSTEM MALFUNCTIONS LISTING ID TSI-3 TSI-3A TSI-3B TSI-3C TSI-3D TSI-3E TSI-3F TSI-3G TSI-3H TSI-3I TSI-3J TSI-3K TSI-4 TSI-5 TSI-5A TSI-5B TSW-1 TSW-2 TSW-3 TSW-4 TSW-5 TUR-1 TUR-1A TUR-1B TUR-2 TUR-2A TUR-2B TUR-2C TUR-2D TUR-2E TUR-2F TUR-3 TUR-3A TUR-3B TUR-4 TUR-4A TUR-4B TUR-4C TUR-4D TUR-4E TUR-4F TUR-4G TUR-4H SYSTEM TSI TSI TSI TSI TSI TSI TSI TSI TSI TSI TSI TSI TSI TSI TSI TSI TSW TSW TSW TSW TSW TUR TUR TUR TUR TUR TUR TUR TUR TUR TUR TUR TUR TUR TUR TUR TUR TUR TUR TUR TUR TUR TUR DESCRIPTION TURBINE GEN.HIGH VIBRATION'TG HIGH VIBRATION BEARING¹1 TG HIGH VIBRATION BEARING¹2 TG HIGH VIBRATION BEARING¹3 TG HIGH VIBRATION BEARING¹4 TG HIGH VIBRATION BEARING¹5 TG HIGH VIBRATION BEARING¹6 TG HIGH VIBRATION BEARING¹7 TG HIGH VIBRATION BEARING¹8 TG HIGH VIBRATION BEARING¹9 TG HIGH VIBRATION BEARING¹10 TG HIGH VIBRATION BEARING¹11 HIGH ECCENTRICITY HIGH DIFFERENTIAL EXPANSION HIGH DIFF EXPANSION-GOV END HIGH DIFF EXPANSION-GEN END TSW LEAK AT COMMON PUMP DISCHRGE TSW LEAK IN REACI'OR BLDG.TSW LEAK DOWNSTRM OF TSW-PCV-20 LOSS OF TSW TO BUS DUCT COOLERS LOSS OF TSW TO H2 SEAL OIL CLRS DRAIN LINE LEAK HD-TK-SA(B)
DRN LINE LEAK HD-TK-5A DRN LINE LEAK HD-TK-5B MSR LN BRK BETWN INCEPT/STOP VLV MSR LN BRK DOWNSTRM OF MS-V-166A MSR LN BRK DOWNSTRM OF MS-V-166B MSR LN BRK DOWNSTRM OF MS-V-166C MSR LN BRK DOWNSTRM OF MS-V-163A MSR LN BRK DOWNSTRM OF MS-V-163B MSR LN BRK DOWNSTRM OF MS-V-163C STM LEAK AT EA MOIST SEPARATOR STEAM LEAK AT A MSR STEAM LEAK AT B MSR RUPTURE IN STEAM SEAL HEADER RUPTURE IN STM SEAL MAIN HEADER RUPTURE IN STEAM SEAL HDR RFT-1A RUPTURE IN STEAM SEAL HDR RFT-1B RUPT SEAL STM HDR NEAR BRG1 RUPT SEAL STM HDR NEAR BRG2 RUPT SEAL STM HDR NEAR BRG3 RUPT SEAL STM HDR NEAR BRG4, RUPT SEAL STM HDR NEAR BRG5 November 16, 1994 Page 26 of 27 ID APPENDIX C ATTACHMENT C-3 WASHINGTON PUBLIC POWER SUPPLY SYSTEM MALFUNCTIONS LISTING SYSTEM DESCRIPTION TUR-4I TUR-4J TUR-4K TUR-5 TUR-6 TUR-6A TUR-6B TUR-6C TUR-7 TUR-7A TUR-7B TUR-7C TUR-7D TUR-8 TUR TUR TUR TUR TUR TUR TUR TUR TUR TUR TUR TUR TUR TUR RUPT SEAL STM HDR NEAR BRG6 RUPT SEAL STM HDR NEAR BRG7 RUPT SEAL STM HDR NEAR BRG8 STEAM LEAK AFTER STEAM CHESTS STEAM LEAK IN LOW PRESS TURBINE STEAM LEAK IN LP TURBINE-A STEAM LEAK IN LP TURBINE-B STEAM LEAK IN LP TURBINE-C REHEATER TUBE RUPTURE 1ST STGE RHTR A TUBE BUNDLE RUPT 2ND STGE RHTR A TUBE BUNDLE RUPT 1ST STGE RHTR B TUBE BUNDLE RUPT 2ND STGE RHTR B TUBE BUNDLE RUPT LEAK AT TURBINE BYPASS MANIFOLD TOTAL COUNT: 1132 November 16, 1994 Page 27 of 27 APPENDIX C ATTACHMENT C-4 WASHINGTON PUBLIC POWER SUPPLY SYSYTEM COMPONENT LEVEL FAILURES LISTING The following component level failures are.provided via touch screen selection, of the associated plant system and Equipment Piece Number (EPN)for the specific device.A.Remotely Controlled Circuit Breakers: 1)Spurious breaker txip due to internal failure in the trip logic.2)Spurious breaker closure due to internal failure in the closing logic.3)Failure of breaker automatic trip logic.Manual trip circuitry is unaffected.
4)Failuxe of breaker automatic closing logic.Manual closing logic is unaffected.
5)Mechanical seizuxe of the breaker in its current position.6)Blown fuse in circuit breaker control power circuit resulting in loss of position indication as well as failure of the breaker in its current position.7)Failuxe of breaker spring charging motor.Breaker will trip but cannot be re-closed.
B.Motored Operated Valves: I)Blown fuse in valve control power circuit resulting in loss of valve position indication as well as inability to electrically position the valve.2)Spurious valve opening due to electrical failure in valve motor contractor closing circuit.Valve ramps normally to full closed position.If valve closure is attempted (manually or automatically),'valve will close, but will reopen as soon as the closing signal clears.3)Spurious valve closure due to electrical failure in valve motor contractor closing circuit.Valve ramps normally to full open position.If valve opening is attempted (manually or automatically), valve will open, but will re-close as soon as the opening signal cleaxs.4)Automatic open signal failure.Valve may be opened manually but automatic open signals have no effect.5)Automatic close signal failure.Valve may be closed manually but automatic close signals have no effect.6)Mechanical seizure of valve in its current position, resulting in thermal overload activation if valve movement is attempted or in progress.1 of 5 APPENDIX C ATTACHMENT C-4 WASHINGTON PUBLIC POWER SUPPLY SYSYTEM COMPONENT LEVEL FAILURES LISTING 7)Open limit/torque switch failure.Valve control circuit does not de-energize when valve reaches the open limit switch position or the open mechanical torque, potentially resulting in mechanical stall of the actuator motor when the valve reaches mechanical end of travel and activation of electrical protection devices.8)Closed limit/torque switch failure.Valve control circuit does not de-energize when valve reaches the closed limit switch position or the closed mechanical torque, potentially resulting in mechanical stall of the actuator motoi'hen the valve reaches mechanical end of travel and activation of electrical protection devices.C.Centrifugal Pumps: 1)Break in shaft between pump impeller and prime mover.Prime mover operates normally at no load condition.
Impeller is free to"windmill" in fluid stream.2)Rapid seizure of pump impeller.Prime mover is stopped with the pump.l 3)Variable degradation of pump developed head for a given value of impeller speed and flow.D.Positive Displacement Pumps: 1)Break in shaft between pump and prime mover.Prime mover operates normally at no load condition.
2)Rapid seizure of pump.Prime mover is stopped with the pump.3)Variable degradation of pump flow for a given discharge head due to internal leakage (seals, internal bypass valves).H.Mixed Flow Pumps: 1)Break in shaft between pump impeller and prime mover.Prime mover operates normally at no load condition.
Impeller is&ee to"windmill" in fluid stream.2)Rapid seizure of pump impeller.Prime mover is stopped with the pump.3).Variable degradation of pump developed head for a given value of impeller speed and flow.20f5 APPENDIX C ATTACHMENT CA WASHINGTON PUBLIC POWER SUPPLY SYSYTEM COMPONENT LEVEL FAILURES LISTING F.Heat Exchangers:
1)Variable severity fouling of tube side.Overall Heat transfer coefficient and hydraulic admittance of tubes are both affected.2)Variable severity leakage between tube and shell sides.Leakage shall affect conductivity and activity of fluids as applicable in addition to mass/energy inventory and heat exchanger performance.
3)Variable severity tube rupture.Same as e.2 above except severity is related to number of tubes ruptured.G.Air Operated Valves: 1)Positioner (or pilot valve)failure;valve ramps to full open position and will not respond to electrical control.2)Positioner (or pilot valve)failure;valve ramps to full closed position and will not respond to electrical control.3)Fault in valve position indication circuitry; valve functions normally but valve position indication is lost.4)Valve mechanically seizes in current position.H.Major Check Valves: 1)Check valves open seizure;check valve seizes at full open position when moved to that position by fluid flow while this failure is active.2)Check valves closed seizure;check valve seizes at full closed position when moved to that position by fluid flow while this failure is active.3)Variable severity valve leakage;valve leakage during back-seat condition is a function of failure severity value.I.Major Mechanically Activated Safety and Relief Valves: 1)Variable severity valve setpoint drift;valve nominal opening setpoint increases or decreases by percentage severity value (+or-)entered.2)Variable severity leakage;valve seat leakage is a function of failure severity value.3 of 5
APPENDIX C ATTACHMENT C-4 WASHINGTON PUBLIC POWER SUPPLY SYSYTEM COMPONENT LEVEL FAILURES LISTING 3)Valve open failure;valve trips to full open position when failure is activated and remains at that position independent of system pressure while failure is active.4)5)Valve closure failure;valve remains in full closed position independent of system pressure while failure is active.Variable valve performance; mass How rate through open valve is a function of failure severity level.J.Local Process Controllers (i.e, external to Simulatox Control Room): Variable controller failure;output signal is set equal to the severity value, If no severity is entered, controller output remains at the value in existence just priox to the failure initiation.
2)Variable severity controller instability; controller output oscillates in a periodic manner.Magnitude of oscillation is a function of failure severity;period of oscillation is determined by separate model constant for each type of local process controller.
K.Control Room Process Control Hardwaxe: Variable device failure;output signal is set equal to the severity value.If no severity is entered, device output remains at the value in existence just prior to the failure initiation.
This failuxe shall apply to controllers, ratio stations, bias stations, and automatic/manual stations and shall affect all station opexating modes.2)3)Variable device failure-automatic mode.Identical to K.labove except affects only the automatic (and, if applicable, cascade)mode output of controllers and automatic/manual stations.The device functions normally in the manual mode.Variable severity controller instability; controller automatic (and, if applicable, cascade)oscillates in periodic manner.The magnitude of oscillation is a function of failure severity;the period of oscillation is determined by separate model constant for each type of process controller.
L.Electronic Bistables:
2)Bistable fail to trip;bistable output signal fails to change to trip state for any value of the monitored variable parameter.
Bistable spurious trip;bistable output maintained in the tripped state for any value of the monitored variable parameter.
4 of 5
APPENDIX C ATTACHMENT CR WASHINGTON PUBLIC POWER SUPPLY SYSYTEM COMPONENT LEVEL FAILURES LISTING 3)Variable severity bistable setpoint drift;bistable nominal trip setpoint increases or decreases by percentage severity value (+or-)entered.M.Reactor Protection System Relays and Engineered Safety Features System Relays.1)Relay coil failure;coil develops an open circuit, relay contracts move to coil de-energized state and fail to respond when the coil is energized.
2)Relay armature failure;armature is mechanically stuck in position existing just prior to failure activation.
N.Process Transmitters (including radiation monitoring system detectors):
1)Variable severity transmitter failure;transmitter output set equal to severity value in percent of span.If no severity value is entered, the transmitter output is frozen at the value in existence just prior to failure activation.
2)Variable severity transmitter offset;transmitter output is offset from the process value by a constant percentage equal to the severity value (+or-)entered.O.Resistance temperature detectors (RTD): 1)Open circuit on the sensor (resistance element)side of the RTD.2)Variable severity transmitter onset;RTD output is ofFset from the process temperature value by a constant percentage equal to the severity value (+or-)entered.P.Process Loop Power Supplies: 1)Power supply output fails to zero volts, (open circuit)5of5 APPENDIX D WASHINGTON PUBLIC POWER SUPPLY SYSTEM SIMULATOR ACCEPTANCE TESTS Attachment D-1 ANSI/ANS-3.5 (1985)Requirements Versus Simulator Acceptance Test Procedures Attachment D-2 Computer Spare Capacity Test Abstract Attachment D-3 Normal Plant Evolutions Test Abstracts Attachment D-4 Steady State Operation Test Abstracts Attachment D-5 Transient Performance Test Abstracts Attachment D-6 Plant Malfunction Test Abstracts APPENDIX D ATTACHMENT D-1 WASHINGTON PUBLIC POWER SUPPLY SYSYTEM ANSI/ANS-3.5 (1985)REQUIREMENTS VERSUS SIMULATOR ACCEPTANCE TEST PROCEDURES General Requirements 3.1 Simulator Capabilities 3.1.1 Normal Plant Evolutions 3.1.1(1)3.1.1(2)3.1.1(3)3.1.1(4)3.1.1(5)3.1.1(6)3.1.1(8)3.1.1(9)3.1.1(10)Plant Startup 14.4.7.1-Normal Plant Operations Nuclear Startup 14.4.7.2.1
-Startup from Hot Shutdown to Rated Pressure Turbine Startup and Gen Synchronization 14.4.7.1-Normal Plant Operations Reactor SCRAM/Recovery to 100%Power 14.4.7.2.1
-Startup from Hot Shutdown to Rated Pressure Operations at Hot Standby 14.4.7.2.3
-SD to HSD Load Changes 14.4.7.1-Normal Plant Operations Plant S/D from Rated Power to Cold S/D 14.4.7.1-Normal Plant Operations Core Performance Testing 14.4.6.1-Core Reactivity/Shutdown Margin 14.4.6.3-Fission Product Poison Test 14.4.6.5-SRM/IRM vs.Control Rod Motion Operator Conducted Surveillance Testing (Safety Eq.)07.04.00.05.06
-EDR, FDR, RRC, MS 8 RRC Valve Ops 07.04.00.05.13
-Reactor Vx&Trip Valve Operability 07.04.00.05.15
-CIA Valve Operability 07.04.00.05.18
-HPCS Service Water Operability/Demo 07.04.01.03.01.01
-Scram Discharge Volume Vent 8 Drain Valve Operability 07.04.01.03.01.02
-Control Rod Exercise 07.04.03.01.01.22
-Manual SCRAM Function Test 07.04.03.06.09
-SDV Bypass Rod Block 07.04.03.07.04.01
-Remote Shutdown Panel Channel Check Page 1 of 6 07.04.03.08.02.01
-Monthly Turbine Valve Tests 07.04.04.07
-MSIV Closure Test 07.04.05.01.05
-LPCS Valve Lineup/Ads Inhibit CFT 07.04.05.01.06
-HPCS Valve Uneup 07.04.05.01.11
-HPCS System Operability Test 07.04.06.01.04.02A
-MSIV Valve Operability 07.04.06.02.02.01
-RHR Valve Position Verification 07.04.06.03.03
-Containment Isolation Valve Operability 07.04.06.04.01.02
-Suppression Chamber-Dry Well Vacuum Breaker Operability 07.04.06.05.02.01
-Reactor Building Ventilation Isolation Valve Operability 07.04.06.05.03.01A
-Standby Gas Treatment Operability Test 07.04.06.05.03.04A
-Standby Gas Treatment Manual initiation Bypass Damper 8 Heater Test 07.04.07.01.01.02
-Standby Service Water Loop B valve Position Verification 07.04.07.09.01
-Weekly Bypass Valves Test 07.04.08.01.01.01.02
-18 Month Manual 8 Auto XFR Test, Start-Up to Backup Station Power 07.04.08.01.01.02.01
-Diesel Generator P1-Operability Test 07.04.08.01.01.02.06
-HPCS Diesel Generator-Loss of Power Test 07.04.08.01.01.02.11
-Diesel Generator%-Operability Test 07.04.08.01.01.02.12
-HPCS Diesel Generator-Operability Test Plant Malfunctions 3.1.2(1)Loss of Coolant 3.1.2(1)(a)Large and Small Reactor Coolant Breaks 14.4.9.18.3
-instrument Line Break (Ref)14.4.9.18.6-instrument Line Break (Var)14.4.10.7-Maximum Size Reactor Coolant System Rupture w/Loss of Offsite Power 3.1.2(1)(b)
Failure of Safety and Relief Valves 14.4.9.24.27
-Main Steam Safety Relief Valve Fails Open 14.4.9.25.14
-SRV's-Fail Closed 14.4.10.10-MSIV ISOL with SRV FO 3.1.2(2)Loss of Instrument Air 14.4.9.4.4
-Leak Downstream Control Air Dryer Page2of6 0
Loss or Degraded Electrical Power 14.4.9.8.3
-4160 Vac Bus Sm-8 Overcurrent 14.4.9.8.3A
-41 60 Vac Bus Sm-7 Overcurrent 14.4.9.8.3B
-Overcurrent SM-1 14.4.9.8.4
-S1-2 DC Ground 14.4.9.8.5
-6900 Vac Bus SH-6 OL-GND 14.4.9.8.7-Loss of All Offsite Power 14.4.9.8.8
-DG-2 Trip High Diff.Current 14.4.9.24.15
-S1-1 DC Ground 14.4.9.24.15A
-S1-1 Trip 14.4.9.24.18
-RPS B MG Set Trip 14.4.9.24.56
-Battery Charger C1-1 Trip 14.4.10.2-Loss of All AC Power-Station Blackout Loss of Forced Coolant Flow Due to Pump Failure 14.4.9.24.34
-Recirculation Pump B Trip 14.4.10.6-Trip of all Recirculation Pumps Loss of Cond Vacuum/Loss of Cond Lvl Control 14.4.9.2.2-Condenser Air Leak 14.4.9.24.86
-COND-LIC-1 Fails Condenser Level Low Loss of Service Wtr or Cooffng to lndiv.Comp 14.4.9.24.5
-SW Pump A Trip 14.4.9.24.64
-TSW Pump A Trip 14.4.9.25.15-RCC-P-1 A-Trip Loss of Shutdown Cooling 14.4.9.24.5
-SW Pump A Trip Loss of Comp Cooling Sys or Cool to Indiv.Comp 14.4.9.24.5
-SW Pump A Trip 14.4.9.24.73
-SW-V-2B Falls Closed 14.4.9.24.64
-TSW Pump A Trip Loss of Normal Feedwater or System Failure 14.4.9.2.9
-RFPT A Trip 14.4.9.24.2-COND-P-2A Shaft Break 14.4.9.24.48
-COND-P-1 B Trip 14.4.10.1-Loss of All Feedwater Loss of All Feedwater (Nor and Emer)14.4.10.16-Loss FW with Emergency Depressurization 14.4.10.40-Loss of Normal and Emergency FW Loss of Protective System Channel 14.4.9.16.4
-HPCS Logic Failure 14.4.9.21.1
-ADS Logic Failure 14.4.9.24.78
-ATWS/ARI Failure Page 3 of 6 3.1.2(12)3.1.2(13)3.1.2(14)3.1.2(15)3.1.2(16)3.1.2(17)3.1.2(19)3.1.2(20)3.1.2(21)3.1.2(22)14.4.9.24.80
-RPS Fails to SCRAM Control Rod Failure 14.4.9.3.1
-Rod Drift 14.4.9.3.2-Stuck Rod 14.4.9.3.3
-Uncoupled Rod 14.4.9.3.4
-Single Rod SCRAM 14.4.9.3.12
-Hydraulic ATWS 14.4.9.3.13
-Dropped Rod Inability to Drive Rods 14.4.9.3.6
-RDCS Failure Fuel Cladding Failure 14.4.9.7.1
-Small Clad Fall 14.4.9.7.2
-Gross Clad Fail Turbine Trip 14.4.9.24.31
-Main Turbine Trip 14.4.9.24.31A
-Main Turbine Trip From LT 30%14.4.10.13-Mn Turbine Trip W/0 Bypass Valves Generator Trip 14.4.9.13.1
-Main Generator Trip Failure in Auto Cont Sys Affect React/Heat Removal 14.4.9.23.3-DEH Press Reg.Output Failure High 14;4.9.23.3A
-DEH Press Reg.Output Fails Low 14.4.9.24.40
-BPV-1 Failure Reactor Trip 14.4.9.24.33
-Manual Scram Main Steamiine/Main Feed Line Breaks 14.4.9.2.3
-Feed Line Break in DW 14.4.9.2.8
-FW Rupture in Turbine Bldg.14.4.9.21.4-MS Break in DW Dwnstrm of Flow Restrict 14.4.9.21.5A MS Rupture In Turbine Bldg.14.4.9.21.6
-RCIC Steam Line Break at Turbine Nuclear Instrumentation Failures 14.4.9.14.1
-SRM A Failure-Low 14.4.9.14.2
-APRM Failure 14.4.9.14.5
-IRM Failure-High 14.4.9.14.8
-LPRM Failure-Downscale Process Inst, Alarms, Cont Sys Failures 14.4.9.9.4A
-RCIC Turbine Trip Due to RCIC-V-8 Closure 14.4.9.24.43
-Annunciator Failure 14.4.9.24.67-RPV/L Trip Channel Failure Hl 14.4.9.24.67B
-RFW-L1-606B
-Fails Low Pagc4of 6 0 0 3.1.2(23)3.1.2(24)3.1.2(25)14.4.9.24.67C
-RFW-L1-606B Fails High Passive Maif in Sys (ESF, Emer Feedwater) 14.4.9.3.10
-Rod Worth Minimizer Fails 14.4.9.9.2-LPCS Suet Line Break at Pump 14.4.9.24.37
-HPCS-V-4 Falls Thermal Overload 14.4.9.25.2-RHR-P-2B Shaft Shear 14.4.9.25.5
-RHR-P-2A Trip Failure of Auto Reactor Trip System 14.4.9.3.12
-Hydraulic ATWS 14.4.9.24.80-RPS Fails to SCRAM 14.4.9.25.19
-RPS Spurious Scram A 14.4.10.11
-100%Hydraulic ATWS Reactor Press Cont Sys Failure (BWR)14.4.9.23.3-DEH Press Reg.Output Failure High 14.4.9.23.3A
-DEH Press Reg.Output Falls Low 14.4.9.24.27-Main Steam Safety Relief Valve Fails Open 14.4.9.24.40
-BPV-1 Failure 14.4.9.24.63
-DEH Pump 1A Trip Performance Criteria 4.1 Steady-State Operation 14.4.4.1-100%SS Accuracy 14.4.4.2-66%SS Accuracy 14.4.4.3-40%SS Accuracy 14.4.4.4-Cold Shutdown-BOC 14.4.5.1-100%Heat Balance Page5of6 t APPENDIX A of ANSI/ANS-3.5 Requirements A3.1 Computer Spare Capacity Test 14.5.2 Computer Spare Capacity Test APPENDIX B of ANSI/ANS.3.5 Requirements, B.1 BWR Simulator Operability Test B1.1 Steady-State Performance B1.1(1)Primary Plant 14.4.3.1.1
-1 Hour Stability 14.4.3.1.2-Initial Condition Stability B1.1(2)Secondary Plant 14.4.3.1.1
-1 Hour Stability 14.4.3.1.2-Initial Condition Stability B1.2 Transient Performance B1.2(1)Manual SCRAM 14.4.9.24.33 Manual Scram B1.2(2)Simultaneous Trip of All Feedwater Pumps 14.4.10.5-Simultaneous Trip of AII RFP's B1.2(3)Simultaneous Closure of AII Main Steam Isolation Valves 14.4.10.3-Closure of All Main Steam Isolation Valves B1.2(4)Simultaneous Trip of All Recirculation Pumps 14.4.10.6-Trip of All Recirculation Pumps B1.2(5)Single Recirculation Pump Trip 14.4.9.24.34
-Recirculation Pump B Trip B1.2(6)Main Turbine Trip (No Immediate Reactor SCRAM)14.4.9.24.31A
-Main Turbine Trip from LT 30%B1.2(7)Maximum Rate Power Ramp (100%-75%-100%)
14.4.8.4-Power Ramp from 100%PWR to 75%to 100%B1.2(8)DBA LOCA with Loss of AII Off-site Power 14.4.10.7-Maximum Size Reactor Coolant System Rupture w/Loss of Offsite Power B1.2(9)DBA Steamline Rupture 14.4.10.9-Maximum Size Unisolatable MSL Rupture B1.2(10)Simultaneous Closure of All MSIVs with Single Stuck-Open Safety/Relief Valve (Inhibit High Press ECCS)14.4.10.10
-MSIV ISOL with SRV Failed Open Page 6 of 6 APPENDIX D ATTACHMENT 0-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM COMPUTER SPARE CAPACITY ABSTRACT OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Computer Spare Capacity TEST No.14.5.2 REV.4 TITLE: COMPUTER SPARE CAPACITY D Ee Duty Cycle is evaluated during conduct of DBA LOCA and is verified not to exceed 75%for CPU's, IPU's and Compute Node.Additionally during the transient which is allowed to run for one (I)hour the Simtime is evaluated against clock time and a maximuin differential of 5 seconds was verified.INI'HAL CONDITIONS:
IC-14 100%Power with Equilibrium Xenon.FINAL CONDITIONS:
Post DBA LOCA.SOURCE OF COMPARISON DATA: PLANT DATA SET g ENGINEERING EVALUATION FSAR SUER/LER OPERATIONALASSESSMENT TEST RESULTS: TESTRESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES PX TEST RESULTS SATISFACI'DRY WITHOUT DISCREPANCIES APPENDIX D ATTACHMENT D-3 WASHINGTON PUBLIC POWER SUPPLY SYSTEM NORMAL PLANT EVOLUTION TEST ABSTRACTS 0
OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Normal Operations TEST No.14.4.7.1 REV.4 TITLE: NORMAL PLANT OPERATIONS D IREDRE P N E: This test was performed to verify simulator response to a shutdown from rated power conditions to CSD and subsequent startup to rated conditions.
The applicable steps of PPM 3.2.1,Normal SD to CSD (Attachment A), PPM 3.1.2 Reactor Plant Cold Startup (Attachment B)and PPM 7.4.4.6.1.1, HU/CD Log (Attachment C)were completed.
All applicable steps for PPM 3.2.1 Normal SD to CSD, PPM 3.1.2 Reactor Plant Cold Startup and PPM 7.4.4.6.1.1 HU/CD Log were tested and verified.INII'IAL CONDITIONS:
IC-14 100%Power Equilibrium Xenon.FINAL CONDITIONS:
100%Power Xenon Concentration Increasing to Equilibrium.
SOURCE OF COMPARISON DATA: X PLANT DATA SEI'NGINEERING EVALUATION FSAR SOER/LBR X OPERATIONAL ASSESSMENT PLANTSD DATASET SHUTDOWN.DOC START.DO SU99109.DOC CY6STARTUP1 CY6START P2 TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES X TEST RESULTS SATISFACTORY WITH DISCREPANCIES Q TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES
~'f' OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Normal Operations TEST No.14,4.7,2,1 REV.4 TITLE: PLAlVT OPERATION TESTS-STARTUP FROM HOT SHUTDOWN TO RATED PRESSURE D IREDR P N E: This test is performed to verify simulator response to a startup from the HSD condition at 4-8 hours after the initial SCRAM from rated power conditions with Equilibrium Xenon present.The applicable steps of PPM 3.1.3, SU from HSD (Attachment A)were completed.
Qmggzafz.Reactor SU from HSD discontinued at rated RPV/P due to previous data evaluation during normal operations for the Startup to 100%power.Xenon burn resulted in Reactor Power increase from 1%to 3%.INI'GAL CONDITIONS:
IC-20-0%Power Ready for Startup, or HSD IC-0%Power Ready for Startup.FINAL CONDITIONS:
Reactor Critical, RPV/P Control via MT bypass valves, at Rated Pressure.SOURCE OF COMPARISON DATA: PLANT DATA SBT ENGINEERING EVALUATION FSAR SOER/LBR g OPERATIONAL ASSESSMENT TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACI'ORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Normal Operations TEST No.14.4.7.2.3 REV.4 TITLE: PLANT OPERATION TESTS-SD FROM RATED RPVlP TO HSD D IREDRE P N This test is performed to verify the minimum evolutions that the simulator shall be capable of performing, using only operator action normal to the reference plant for operations at hot shutdown.The applicable steps of PPM 3.2.2, SD to HSD (Attachment A)and PPM 7.4.4.6.1.1 (Attachment B)should be completed.
INITIAL CONDITIONS:
IC-16, Shutdown in progress, 14%Power, 920 psig.FINAL CONDITIONS:
Reactor is Shutdown and Plant is in Hot Shutdown.SOURCE OF COMPARISON DATA: g PLANT DATA SEI'NGINEERING EVALUATION FSAR SOER/LER X OPERATIONAL ASSESSMENT C cle 6 Shutdown Data TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES X TEST RBSULTS SATISFACTORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST No.14.4.6.1 REV.4 TITLE: CORE PERFORMANCE TESTS-CORE REACTIVI'IY and SHUTDOWN MARGIN REDRE P N E: BOC Shutdown Margin verified to be within Technical Specification 3/4.1.2 requirements.
BOC, MOC and EOC 100%power equilibrium Xenon Control Rod Patterns verified to match target rod pattern cal-culations.
Additionally, the BOC, MOC, and EOC Critical Control Rod Patterns evaluated for Cold Clean Xenon free conditions against calculated Critical Rod Patterns.The SDM, 100%Rod Patterns and Critical Rod Positions were verified to match predicted conditions.
Proper reactivity response eval-uated during approach to critical and through the point of adding heat.INITIAL CONDITIONS:
Multiple IC's for BOC, MOC and ROC.SOURCE OF COMPARISON DATA: PLANT DATA SET ENGINEERING EVALUATION FSAR SOER/LER g OPERATIONAL ASSESSMENT TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES QZ TEST RESULTS SATISFACI'ORY WITHOUT DISCREPANCIES
OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY;Normal Operations TEST No.14.4.63 REV.3 TITLE: CORE PERFORMANCE TESTS-FISSION PRODUCT POISON TEST DESIRED RESPONSE: This test was performed to demonstrate proper Xenon response to Rx Power transients.
Power ramp from 100 to 75%with Xe placed in fast time to verify time interval to maximum value and subsequent equilibrium conditions.
Power subsequently ramped to 100%and Xe minimum valve and time to equilibrium verified.Lastly a Reactor SCRAM initiated with evaluation of time to peak and subsequent decay to minimum verified.INITIAL CONDITIONS:
IC-14, 100%Power with Equilibrium Xenon.FINAL CONDITIONS:
Reactor Scrammed with minimum CSD Xe conditions.
SOURCE OF COMPARISON DATA: PLANT DATA SET X BNGINBERING EVALUATION FSAR SOBR/LER g OPERATIONAL ASSESSMENT NEDE-24 1 Vol.1 TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES X TEST RESULTS SATISFACI'ORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Normal Operations TEST No.14.4.G.5 REV.3 TITLE: CORE PERFORMANCE TESTS-SRMIIRM REPONSE TO CONTROL ROD MOTION TEST D IREDRE P N E: This test was performed to demonstrate the pxoper SRM/IRM response to control rod motion.The SRM's and IRM's adjacent to control xods being withdrawn are verified to respond more dramatically than they do when other control rods are withdrawn.
The SRM response includes a verification of the Prompt Jump and subcritical multiplication effects as demonstrated by the associated plots of SRM response.The SRM and IRM response to control rod motion wexe tested and verified., INITIAL CONDITIONS:
'C-3 Startup in progress approaching criticality.
SOURCE OF COMPARISON DATA: PLANT DATA SBI'NGINEERING EVALUATION FSAR SUER'/LER g OPERATIONAL ASSESSMENT TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCRBPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Normal Operations TEST No.07.04.00.05.06 REV.10 TITLE: EDR, FDR, RRC, MS&RCC VALVE OPER4BILI7T DESIRED RESPONSE: This test was performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures.
Proper valve stroking 8c timing were tested and verified.INITIAL CONDITIONS:
In accordance with the testing requirements of the specific Surveillance.
FINAL CONDITIONS:
In accordance with the testing requirements of the specific Surveillance.
SOURCE OF COMPARISON DATA;PLANT DATA SEI'NGINEERING EVALUATION FSAR SUER/LER OPERATIONAL ASSESSMENT TSS 7.4.0.5.6 TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES Z TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES
OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Normal Operations TEST No.07.04.00.05.13 REV.9 TITLE: PI-VX&TIP VALVE OPERABILIXY DESIRED RESP NSE: This test was performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures.
Proper valve stroking 8c timing were tested and verified.INITIAL CONDITIONS:
In accordance with the testing requirements of the specific Surveillance.
t FINAL CONDITIONS:
In accordance with the testing requirements of the specific Surveillance.
SOURCE OF COMPARISON DATA: PLANT DATA SET g ENGINEERING EVALUATION FSAR SOBR/LER OPERATIONAL ASSESSMENT TSS 7.4.0.5.13 TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES TBST RESULTS SATISFACTORY WITHOUT DISCRBPANCIBS OPERATIONAL REVIEW
SUMMARY
TEST No.07.04.00.05.15 REV.8 TITLE: CIA VALVE OPERABILIZT DE IREDR P N E: This test is performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures.
Proper valve stroking 8c timing were tested and verified.INITIAL CONDITIONS:
In accordance with the testing requirements of the specific Surveillance.
t FINAL CONDITIONS:
In accordance with the testing requirements of the specific Surveillance.
SOURCE OF COMPARISON DATA: PLANT DATA S EI'NGINEERING EVALUATION FSAR SOBR/LER OPERATIONAL ASSES SMBNT TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACI'ORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Normal Operations TEST No.07.04.00.05.18 REV.11 TITLE: HPCS SERVICE WATER OPERABILITY DEMONSTRATION D IREDRE N E'his test is performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures.
Proper valve stroking&timing were tested and verified.The systems capabilities were verified for delivery of required cooling to system loads.Valve stroke timing is taken to verify valve operability.
Proper system flow balance is verified.INITIAL CONDITIONS:
In accordance with the testing requirements of the specific Surveillance.
FINAL CONDITIONS:
In accordance with the testing requirements of the specific Surveillance.
SOURCE OF COMPARISON DATA: PLANT DATA SEI'ENGINEERING EVALUATION FSAR SOER/LER OPERATIONAL ASSESSMENT TSS 7.4.0.5.18 TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES
OPERATIONAL REVIEW
SUMMARY
TEST No.07.04.01.03.01.01A REV.1 TITLE: SCRAM DISCHARGE VOLUME VENT&DRAIN VALVE OPERABII ITY RD EP NE'his test is performed to demonstrate Shnulator System Operability in accordance with approved Plant Surveillance Procedures.
INITIAL CONDITIONS:
In accordance with the testing requirements of the specific Surveillance.
FINAL CONDITIONS:
In accordance with the testing requirements of the specific Surveillance.
SOURCE OF COMPARISON DATA: PLANT DATA SEI'ENGINEERING EVALUATION FSAR SOER/LER OPERATIONAL ASSESSMENT T A.l..l.l TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES 0
OPERATIONAL REVIEW
SUMMARY
TEST No.07.04.01.03.01.02 REV.14 TITLE: CONTROL ROD EXERClSE D IREDR P N E'his test was performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures.
Proper valve stroking&timing were tested and verified.INITIAL CONDITIONS:
In accordance with the testing requirements of the specific Surveillance.
FINAL CONDITIONS:
In accordance with the testing requirements of the specific Surveillance.
SOURCE OF COMPARISON DATA: PLANT DATA SET g ENGINEERING EVALUATION FSAR SOER/LER OPERATIONAL ASSESSMENT 50.59 Review TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Normal Operations TEST No.07.04.03.01.01.22 REV.8 TITLE: MANUAL SCRAM FUNCTIONAL TEST E EDRE P N E: This test was performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures.
INI'rlAL CONDITIONS:
IC-14, Plant operating at 100%power or less.FINAL CONDITIONS:
IC-14, Plant operating at 100%power or less.SOURCE OF COMPARISON DATA: PLANT DATA SET g ENGINEERING EVALUATION FSAR SUER/LER OPERATIONAL ASSESSMENT 5.5 Review TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES Z TEST RESULTS SATISFACI'ORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Normal Operations TEST No.07.04,03.06.09 REV.5 TITLE: SDV BFPASS ROD BLOCK DESIRED RESPONSE: This test was performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures.
The SDV High Water Level Bypass switch functionality with Mode Switch in REFUEL was verified.INITIAL CONDITIONS:
IC-2.FINAL CONDITIONS:
IC"2.SOURCE OF COMPARISON DATA: PLANT DATA SBT Q ENGINEERING EVALUATION FSAR SOER/LER OPERATIONAL ASSES SMBNT T.Table 4.3.6-1.5.A TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES X TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Normal Operations TEST No.07.04.03.07.04.01 REV.0 TITLE: REMOTE SHUTDOWN PANEL CHANNEL CHECIC RED E N E'his test is performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures.
The RSDP instrumentation is verified.INITIAL CONDITIONS:
Plant operating at 80%power or less.SOURCE OF COMPARISON DATA: PLANT DATA SET g ENGINEERING EVALUATION FSAR SOER/LER OPERATIONAL ASSESSMENT TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACI'ORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST No.07.04.03.08.02.01 REV.0 TITLE: MONTHLY TURBINE VALVE TEST DESIRED RESPONSE: This test is pexformed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures.
This stroking of all tuxbine steam valves was conducted to verify valve operability.
INITIAL CONDITIONS:
Plant operating at 80%power or less.SOURCE OF COMPARISON DATA: PLANT DATA SBI'ENGINEERING EVALUATION FSAR SOER/LER OPERATIONAL ASSESSMBNT T.S.4.3.8.2 TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES X TEST RESULTS SATISFACTORY WITHOUT DISCRBPANCIES
OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Normal Operations TEST No.07.04.04.07 REV.11 TITLE: MSIV CLOSURE TEST DESIRED RESP NSE: This test is pexfolmed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures.
MSIV Fast closure stroke times were measured and validated against timing requirements.
Opening Stroke times were also measured.INITIAL CONDITIONS:
Plant operating at power LE 80%.FINAL CONDITIONS:
Plant operating at power LE 80%.SOURCE OF COMPARISON DATA: PLANT DATA SET g ENGINEERING EVALUATION FSAR SOER/LER OPERATIONAL ASSESSMENT T.S.4.4.7 TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCRBPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Normal Operations TEST No.07.04.05.01.05 REV.1 TITLE: I,PCS VAL VZ LINEUP D IRD E NE'his test is performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures.
This test verifies that LPCS valves are in their correct position for a normal standby lineup.INITIAL CONDITIONS:
100%Power.FINAL CONDITIONS:
100%Power, SOURCE OF COMPARISON DATA: PLANT DATA SET g ENGINEERING EVALUATION FSAR SOER/LER OPERATIONAL ASSESSMENT TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Normal Operations TEST No.07.04.05.01.06 REV.1 TITLE: HPCS VALVE LINEUP IRED RE E'his test is performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures.
Tlus test verifies that the HPCS valves are in their correct position for a normal standby lineup.INITIAL CONDITIONS:
IC-14 100%Power.FINAL CONDITIONS:
IC-14 100%Power.SOURCE OF COMPARISON DATA: PLANT DATA SEI'BNGINBERING EVALUATION FSAR SOBR/LER P OPERATIONAL ASSESSMENT T.S.4.5.1.A.2 TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES PX TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES
OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Normal Operations TEST No.07.04.05.01.11 REV.0 TITLE: HPCS SYSTEM OPERABILITY TEST D IREDRE P N E: This test is performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures.
HPCS flow testing from CST to CST was performed and valve stroke timing measurements were taken.INITIAL CONDITIONS:
IC-14 100%power, equiliberium Xenon.SOURCE OF COMPARISON DATA: Q PLANT DATA SEI'ENGINBERING EVALUATION FSAR SOER/LER OPERATIONAL ASSESSMENT T.S.4.5.1.b.3 TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES X TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Normal Operations TEST No.07.04.06.01.04.02A REV.1 TITLE: MSIV VALVE QUARTERLY OPERABILI1T SURVEILLAlVCE D IREDRE P N E: This test is pexformed to demonstrate MSIV Leakage Control System Operability in accordance with approved Plant Surveillance Procedures.
Proper valve stroking 2 timing were tested and verified.INITIAL CONDITIONS:
Plant shutdown.and depressurized, or IC-14.FINAL CONDITIONS:
Plant shutdown and depressurized or IC-14.SOURCE OF COMPARISON DATA: P PLANT DATA SEI'ENGINEERING EVALUATION FSAR SOER/LER OPERATIONAL ASSESSMENT TEST RESULTS: TEST RBSULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RBSULTS SATISFACI'DRY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST No.07.04.06.02.02.01 REV.0 TITLE: RHR SFSTI" M VAJ VI" POSITION VERIFICATION IREDR N E This test is pexfoxmed to demonstrate Simulator System Operability in accoxdance with appxoved Plant Surveillance Procedures.
This test is done to verify RHR valve positions to confirm system operability.
INITIAL CONDITIONS:
N/A FINAL CONDITIONS:
N/A SOURCE OF COMPARISON DATA: P PLANT DATA SEI'ENGINEERING EVALUATION FSAR SUER/LER OPERATIONAL ASSESSMENT TEST RESULTS: TEST RESULTS UNSATISPACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES
OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Normal Operations TEST No.07.04.06.03.03 REV.9 TITLE: CSP&CEP CONTAINMENT ISOLATION VALVE OPERABILITF DE IREDRESP N E'his test is performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures.
Proper valve stroking 8c timing were tested and verified.INITIAL CONDITIONS:
In accordance with the testing requirements of the specific Surveillance.
FINAL CONDITIONS:
In accordance with the testing requirements of the specific Surveillance.
SOURCE OF COMPARISON DATA: PLANT DATA SET g ENGINBERING EVALUATION FSAR SOBR/LBR OPERATIONAL ASSESSMBNT TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES PX TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Normal Operations TEST No.07.04.06.04.01.02 REV.12 TITLE: SUPPRESSION CHAMBER DRY WELL VACUUM BREAKER OPERABILIIY D IREDR P N E This test is performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures.
This test demonstrates the operability of each suppression chamber and drywell vacuum breaker.INITIAL CONDITIONS:
In accordance with the testing requirements of the specific Surveillance.
SOURCE OF COMPARISON DATA: PLANT DATA SBT g ENGINEERING EVALUATION FSAR SOER/LER OPERATIONAL ASSESSMENT TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RBSULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACI'ORY WITHOUT DISCRBPANCIBS OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Normal Operations TEST No.07.04.06.05.02.01 REV.8 TITLE: REACTOR BUILDING ISOL4TION VALVE OPERABILI2T D IREDRE N E: Tliis test is performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures.
Proper valve stroking&timing were tested and verified.Valve operability and stroke times were checked and verified to meet procedure requirements.
INITIAL CONDITIONS:
IC-14 100%Pwr/Flow RB HVAC In Service.SOURCE OF COMPARISON DATA: PLANT DATA SEI'ENGINEERING EVALUATION FSAR SUER/LER OPERATIONAL ASSESSMENT 5.5 TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES X TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Normal Operations TEST No.07.04.06.05.03.01A REV 2 TITLE;STANDBY GAS TREATMENT SI'STEM OPERABILITY TEST DESIRED RESPONSE: This test is performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures.
Proper valve stroking&timing were tested and verified.Valve operability and stroke times were checked and verified to meet procedure requirements.
INITIAL CONDITIONS:
Any IC SGT in STBY.FINAL CONDITIONS:
Any IC SGY in STBY.SOURCE OF COMPARISON DATA: PLANT DATA SEI'ENGINEERING EVALUATION FSAR SUER/LER OPERATIONAL ASSESSMENT TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES II TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES
OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Normal Operations TEST No.07.04.07.01.01.02 REV.15 TITLE: STANDBX SERVICE WATER LOOP B VALVE POSITION VI;RIP'ICATlON D IREDRE P N E This test was performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures.
Proper valve stroking 8c timing were tested and verified.The systems capabilities were verified for delivery of required cooling to system loads.Valve stroke timing was taken to verify operability.
Proper system flow balance was verified.INITIAL CONDITIONS:
N/A FINAL CONDITIONS:
N/A SOURCE OF COMPARISON DATA: PLANT DATA SET g ENGINEERING EVALUATION FSAR SOER/LER OPBRATIONALASSESSMENT 50.5 Review TEST RESULTS: TESTRESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES P~TBSTRESULTS SATISFACTORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Normal Operations TEST No.07.04.07.09.01 REV.10 TITLE: WZZra,rarmSS VmVZS rZSr IREDRE P SE: This test was performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures.
Proper valve stroking was tested and verified.Tins stroking of all turbine steam valves was conducted to verify valve operability.
INITIAL CONDITIONS:
IC-14 100%Pwr/Flow.FINAL CONDITIONS:
IC-14 100%Pwr/Flow.SOURCE OF COMPARISON DATA: PLANT DATA SET X ENGINEERING EVALUATION FSAR SOER/LER OPERATIONAL ASSESSMENT 50.59 Review TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACI'ORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Normal Operations TEST No.07.04.08.01.01.01.02 REV.6 TITLE: l8 MONTH MANUAL&AUTO TRANSFER TLi"ST/STARTUP TO BACKUP STATION POWER D IRED RE This test was performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures.
Manual and auto transfers for breakers B7&B8 to SM-7 and SM-8 were conducted.
INITIAL CONDITIONS:
IC-14 100%Power/Flow.FINAL CONDITIONS:
IC-14 100%Power/How.SOURCE OF COMPARISON DATA: PLANT DATA SEI'ENGINEERING EVALUATION FSAR SOER/LBR OPERATIONAL ASSESSMENT TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES X TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Normal Operations TEST No.07.04.08.01.01.02.01 REV.23 TITLE: DG-I MONTHLY OPERABILIZT DESIRED RESPONSE: This test was performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures.
Proper valve stroking 8c timing were tested and verified.This test verifies the load carrying capability of the Diesel Generator.
INITIAL CONDITIONS:
N/A FINAL CONDITIONS:
N/A SOURCE OF COMPARISON DATA: PLANT DATA SEI'ENGINEERING EVALUATION FSAR SOER/LER OPERATIONAL ASSESSMENT 5.5 Review TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Normal Operations TEST No.07.04.08.01.01.02.06 REV.7 TITLE: HPCS DIESEL GENER4TOR-LOSS OIi POWER TEST DESIRED RESPONSE;This test was performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures.
Proper timing was tested and verified.This test required the diesel to auto start, come up to speed and voltage auto close onto the respective bus, with a prescribed time, with minimum specified drop in voltage and frequency.
INITIAL CONDITIONS:
IC-14 100%Pwr/Flow.FINAL CONDITIONS:
IC-14 100%Pwr/Flow.SOURCE OF COMPARISON DATA: PLANT DATA SET X ENGINEERING EVALUATION FSAR SOER/LER OPERATIONAL ASSESSMENT TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES I TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Normal Operations TEST No.07.04.08.01.01.02.11 REV.22 F TITLE: DG-2 MONTHLY OI'I."RABILITY This test was performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures.
Proper valve stroking 8c timing were tested and verified.This test verifies the load carrying capability of the Diesel Generator.
INITIAL CONDlTIONS:
N/A FINAL CONDITIONS:
N/A SOURCE OF COMPARISON DATA: PLANT DATA SET X BNGINBERING EVALUATION FSAR SOER/LER OPERATIONAL ASSESSMENT
.5 Review TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES 1 TEST RESULTS SATISFACTORY WITH DISCREPANCIES M TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Normal Operations TEST No.07.04.08.01.01.02.12 REV.25 lt TITLE: HPCS DIESEL GENERATOR MONTHLY OPERABII ITX TES2'ED R P N E'his test was performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures.
Proper valve stroking 8c timing were tested and verified.This test verifies the load carrying capability of the Diesel Generator.
INITIAL CONDITIONS:
N/A FINAL CONDITIONS:
N/A SOURCE OF COMPARISON DATA: PLANT DATA SEI'ENGINEERING EVALUATION FSAR SOER/LER OPERATIONAL ASSESSMENT 50.59 Review TEST RESULTS: TEST RESULTS UNSATISPACTORY WITH DISCREPANCIES X TEST RESULTS SATISFACTORY WITH DISCREPANCIES Q TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES APPENDIX D ATTACHMENT 0-4 WASHINGTON PUBLIC POWER SUPPLY SYSTEM STEADY STATE OPERATION TEST ABSTRACTS OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Steady State Operation TEST Noh 14.43.1.1 REV.6 TITLE: INITIAL CONDITION STABILITY TEST D I ED Ee The Initial Condition Stability Test is performed to verify simulator critical parameters do not vary by more than g 2%over a period of one hour.Additionally, selected simulator non-critical parameters were verified to not vary by more that,+2%over the same one hour period.The Critical and selected Non-Critical parameters were recorded for each minute and plotted for the one hour period.INITIAL CONDITIONS:
IC-14, 100%Power Equilibrium Xenon.SOURCE OF COMPARISON DATA: X PLANT DATA SEI'NGINBERING EVALUATION FSAR SUER/LER X OPERATIONAL ASSESSMENT o PWRD T TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES M TEST RESULTS SATISFACI'ORY WITHOUT DISCRBPANCIBS lt 4~
OPERATI NAL REVIEW
SUMMARY
TEST CATEGORY: Steady State Operation TEST No.14 4 3 1 2 REV.6 TITLE: INITIAL CONDITION STABILIXY-4-HOUR STABILIZT DESIRED RESPONSE: The Initial Condition Stability Test is performed to verify shnulator critical parameters do not vary by more than p 2%over a period of one hour.Additionally, selected simulator non-critical parameters were verified to not vary by more that, g 2%over the same one hour period.The Critical and selected Non-Critical parameters were recorded for each minute and plotted for the one hour period.INITIAL CONDITIONS:
IC-14, 100%Power Equilibrium Xenon.FINAL CONDITIONS:
IC-14, 100%Power Equilibrium Xenon.SOURCE OF COMPARISON DATA: X PLANTDATASEI'NGINEERING EVALUATION FSAR SOER/LER X OPERATIONALASSESSMENT I 0 o PWRDATA TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TBSTRBSULTS SATISFACTORYWITH DISCREPANCIES PX TESTRESULTS SATISFACTORY WITHOUT DISCREPANCIES N~
OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Steady State Operation TEST No.14.4.3.1.2 TITLE: INITIAL CONDITION STABILITY-4-HOUR STABILI1T REV.6 DESIRED RESPONSE: The Initial Condition Stability Test is performed to verify simulator critical parameters do not vary by more than+2%over a period of one hour.Additionally, selected simulator non-critical parameters were verified to not vary by more that,+2%over the same one hour period.The Critical and selected Non-Critical parameters were recorded for each minute and plotted for the one hour period.INITIAL CONDITIONS:
IC-14, 100%Power equilibrium Xenon.FINAL CONDITIONS:
IC-14, 100%Power Equilibrium Xenon.SOURCE OF COMPARISON DATA: X PLANT DATA SBT ENGINBBRING EVALUATION FSAR SOER/LER g OPERATIONAL ASSESSMENT 1 o P DATA TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Steady State Operation TEST No.14.4.4.1 REV.3 TITLE: STEADY-STATE ACCURACY TESTS-l00 PERCENT POWER AND FLOWP EQ XE DESIRED RESPONSE: This test is performed to verify that the computed values of simulated plant parameters at 100 per-cent power, Equilibrium Xenon correspond to plant parameters, to within the accuracy requirements of ANSI/ANS-3.5-1985, Nuclear Power Plant Simulators for use in Operator Training.Simulator is run for one hour and then data is taken.Critical Parameters monitored included but were not limited to the following categories:
RPV LEVEL's, APRM PWR's, GENERATOR LOAD, MN TURB 1ST STAGE PRESS, STEAM FLOW's, FEED FLOW's, RPV PRESS's, CORE FLOW's, RECIRC LOOP FLOW's, DRYWELL PRESS's, DRYWELL TEMP's, SUPPRESSION POOL LVL's, SUP-PRESSION POOL TEMP's, CONDENSER VACUUM's, MAIN TURB GOV VLV POS's, MAIN TURB SPEED, RFP SPEED's, RFP PRESS's, and as listed.Values were within specifications or identified fox correction.
B tlTIAL CONDITIONS:
IC-14 100%Power with Equilibrium Xenon.FINAL CONDITIONS:
IC-14 100%Power with Equilibrium Xenon.SOURCE OF COMPARISON DATA: PLANT DATA SET ENGINEERING EVALUATION FSAR SOER/LER g OPERATIONAL ASSESSMENT 100 PWR Jan 22 1 PWR Jan 1 TEST RESULTS: TBST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACI'ORY WITHOUT DISCREPANCIES P~,
OPERATIONAL REVIEW
SUMMARY
t TEST CATEGORY: Steady State Operation TEST No.14.4.4.1 REV.3 TITLE: STEADY-STATE ACCURACY TESTS-l00 PERCENT POWER AND FLOWp EQ XE DESIRED RESPONSE: This test is performed to verify that the computed values of simulated plant parameters at 100 per-cent power, Equilibrium Xenon correspond to plant parameters, to within the accuracy requirements of ANSI/ANS-3.5-1985, Nuclear Power Plant Simulators for use in Operator Training.Simulator is run for one hour and then data is taken.Critical Parameters monitored included but were not limited to the following categories:
RPV LEVEL's, APRM PWR's, GENERATOR LOAD, MN TURB 1ST STAGE PRESS, STEAM FLOW's, FEED FLOW's, RPV PRESS's, CORE FLOW's, RECIRC LOOP FLOW's, DRYWELL PRESS's, DRYWELL TEMP's, SUPPRESSION POOL LVL's, SUP-PRESSION POOL TEMP's, CONDENSER VACUUM's, MAIN TUI&GOV VLV POS's, MAIN TURB SPEED, RFP SPEED's, RFP PRESS's, and as listed.Values were within specifications or identified for correction.
INITIAL CONDITIONS:
IC-14 100%Power with Equilibrium Xenon.SOURCE OF COMPARISON DATA: g PLANT DATA SEI'NGINEERING EVALUATION FSAR SOER/LER g OPERATIONAL ASSESSMENT 100 PWR Jan 22 1 PWR Jan 18 TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES I TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES h
OPERATI NAL REVIEW
SUMMARY
REV.4 TITLE: STEADY-STATE ACCVRACY TESTS-66 PERCENT POWER DESIRED RESPONSE: This test is performed to verify that the computed values of simulated plant parameters at 66 per-cent power, correspond to plant parameters, to within the accuracy requirements of ANSI/ANS-3.5-1985, Nuclear Power Plant Simulators for use in Operator Training.Simulator power is reduced to 66%allowed to run for one hour and then data is taken.Critical Parameters monitored included but were not limited to the following categories:
RPV LEVEL's, APRM PWR's, GEN-ERATOR LOAD, MN TURB 1ST STAGE PRESS, STEAM FLOW's, FEED FLOW's, RPV PRESS's, CORE FLOW's, RECIRC LOOP FLOW's, DRYWELL PRESS's, DRYWELL TEMP's, SUPPRESSION POOL LVL's, SUPPRESSION POOL TEMP's, CONDENSER VAC-UUM's, MAIN TURB GOV VLV POS's, MAIN TURB SPEED, RFP SPEED's, RFP PRESS's, and others as listed.Values were within specifications or identified for correction.
e INITIAL CONDITIONS:
IC-14, Adjusted power to 66%.FINAL CONDITIONS:
66%Power SOURCE OF COMPARISON DATA: g PLANT DATA SBT ENGINEERING EVALUATION FSAR SOER/LER X OPERATIONAL ASSESSMENT P Mar 1 TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES X TEST RBSULTS SATISFACI'ORY WITHOUT DISCRBPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Steady State Operation TEST No.j.4.4.4.2 REV.4 TITLE: STEADY-STATE ACCURACY TESTS-66 PERCENT POWER DESIRED RESPONSE: This test is performed to verif'y that the computed values of simulated plant parameters at 66 per-cent power, correspond to plant parameters, to within the accuracy requirements of ANSI/ANS-3.5-1985, Nuclear Power Plant Simulators for use in Operator Training.Simulator power is" reduced to 66%allowed to run for one hour and then data is taken.Critical Parameters monitored included but were not limited to the foHowing categories:
RPV LEVEL's, APRM PWR's, GEN-ERATOR LOAD, MN TURB 1ST STAGE PRESS, STEAM FLOW's, FEED FLOW's, RPV PRESS's, CORE FLOW's, RECIRC LOOP FLOW's, DRYWELL PRESS's, DRYWELL TEMP's, SUPPRESSION POOL LVL's, SUPPRESSION POOL TEMP's, CONDENSER VAC-UUM's, MAIN TURB GOV VLV POS's, MAIN TURB SPEED, RFP SPEED's, RFP PRESS's, and others as listed.Values were within specifications or identified for correction.
INITIAL CONDITIONS:
IC-14, Adjusted power to 66%.FINAL CONDITIONS:
66%Power SOURCE OF COMPARISON DATA: g PLANT DATA SEI'NGINEERING EVALUATION FSAR SOBR/LER g OPERATIONAL ASSESSMENT 6 PWR Mar 1 TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES QX TBST RESULTS SATISFACTORY WITHOUT DISCREPANCIES
/U' OPERATIONAL REVIEW
SUMMARY
e TEST CATEGORY: Steady State Operation TEST No, 14.4.4.3 TITLE: STEADY-STATE ACCURACY TESTS-40 PERCENT POWER REV.3 DESIRED RESPONSE: This test is performed to verify that the computed values of simulated plant parameters at 40 per-cent power, correspond to plant parameters, to within the accuracy requirements of ANSI/ANS-3.5-1985, Nuclear Power Plant Simulators for use in Operator Training.Simulator is allowed to run for one hour and then data is taken.Critical Parameters monitored included but were not lim-ited to the following categories:
RPV LEVEL's, APRM PWR's, GENERATOR LOAD, MN TURB 1ST STAGE PRESS, STEAM FLOW's, FEED FLOW's, RPV PRESS's, CORE FLOW's, RECIRC LOOP FLOW's, DRYWELL PRESS's, DRYWELL TEMP's, SUPPRESSION POOL LVL's, SUPPRESSION POOL TEMP's, CONDENSER VACUUM's, MAIN TURB GOV VLV POS's, MAIN TURB SPEED, RFP SPEED's, RFP PRESS's, and others as listed.Values were within specifications or identified for correction.
FINAL CONDITIONS:
40%Power SOURCE OF COMPARISON DATA: g PLANT DATA SEI'NGINEERING EVALUATION FSAR SOER/LER X OPERATIONAL ASSESSMENT 40PWRA r20 TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES X TEST RESULTS SATISFACTORY WITHOUT DISCRBPANCIES I~'f V g p$~8 PERATIONAL REVIEW
SUMMARY
t TEST CATEGORY: Steady State Operation TEST No.14.4.4.3 TITLE'TEADY-STATE ACCURACY TESTS-40 PERCENT POWER REV.3 DESIRED RESPONSE: This test is performed to verify that the computed values of simulated plant parameters at 40 per-cent power, correspond to plant parameters, to within the accuracy requirements of ANSI/ANS-3.5-1985, Nuclear Power Plant Simulators for use in Operator Training.Simulator is allowed to run for one hour and then data is taken.Critical Parameters monitored included but were not lim-ited to the following categories:
RPV LEVEL's, APRM PWR's, GENERATOR LOAD, MN TURB 1ST STAGE PRESS, STEAM FLOW's, FEED FLOW's, RPV PRESS's, CORE FLOW's, RECIRC LOOP FLOW's, DRYWELL PRESS's, DRYWELL TEMP's, SUPPRESSION POOL LVL's, SUPPRESSION POOL TEMP's, CONDENSER VACUUM's, MAIN TURB GOV VLV POS's, MAIN TURB SPEED, RFP SPEED's, RFP PRESS's, and others as listed.Values were within specifications or identified for correction.
INITIAL CONDITIONS:
IC-62 40%Power FINAL CONDITIONS:
40%Power SOURCE OF COMPARISON DATA: I PLANT DATA SET ENGINBBRING EVALUATION FSAR SUER/LER X OPERATIONAL ASSESSMENT 40PWRA r20 TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES X TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Steady State Operation TEST No.14.4.4.4 REV.4 TITLE: STEADY-STATE ACCURACF TESTS-COLD SHUTDOWN)BOC DESIRED RESPONSE: This test is performed to verify that compiled values of plant parameter at COLD SHUTDOWN, correspond with plant parameters, to within the accuracy reuirements of Nuclear Plant Simulators for use in Operator Training.Valves were within specifications or identified for correction.
INITIAL CONDITIONS:
IC-24, Cold Shutdown FINAL CONDITIONS; Cold Shutdown SOURCE OF COMPARISON DATA: PLANT DATA SET ENGINEERING EVALUATION FSAR SOER/LER g OPERATIONAL ASSESSMENT TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCRBPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Steady State Operation TEST No.14.4.4.4 REV.4 TITLE: STEADY-STATE ACCURACY TESTS>>COLD SHUTDOWN>BOC DESIRED RESPONSE: This test is performed to verify that compiled values of plant parameter at COLD SHUTDOWN, correspond with plant parameters, to within the accuracy reuirements of Nuclear Plant Simulators for use in Operator Training.Valves were within specifications or identified for correction.
INITIAL CONDITIONS:
IC-24, Cold Shutdown FINAL CONDITIONS:
Cold Shutdown SOURCE OF COMPARISON DATA: PLANT DATA SET ENGINEERING EVALUATION FSAR SUER/LER X OPERATIONAL ASSESSMENT TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITHOUT DISCRBPANCIBS OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Steady State Operation TEST No.14.4.5.1 REV.4 TITLE: HEAT AlVD MASS BALAlVCE TESTS-l00 PERCENT POWER HEAT BAL4NCE D IRED RESPONSE: This test is performed to verify that the principal mass and energy balances are satisfied as required by ANSI/ANS-3,5.-1985, Nuclear Power Plant Simulators for Use in Operator Training.Simulator is run for at least thirty minutes and then data is taken.Data is collected and recorded for Attachment A, 100%Heat Balance Control Board Data.Calculations were performed as indicated in Attachment B.Data is evaluated against the Acceptance Criteria of section 5.0, as applicable.
QQ~This test can be run with 100%Steady-State Accuracy Test, 14.4.4.1.INITIAL CONDITIONS:
IC-14 100%Power with Equilibrium Xenon.FINAL CONDITIONS:
IC-14 100%Power with Equilibrium Xenon.SOURCE OF COMPARISON DATA: PLANT DATA SET ENGINEERING EVALUATION FSAR SUER/LER g OPERATIONAL ASSESSMENT TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACI'ORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Steady State Operation TEST No.14.4.5.1 REV.4 TITLE: HEAT AND MASS BALANCE TESTS-100 PERCENT POWER HEAT BALANCE DESIRED RESPONSE: This test is performed to verify that the principal mass and energy balances are satisfied as required by ANSI/ANS-3.5.-1985, Nuclear Power Plant Simulators for Use in Operator Training.Simulator is run for at least thirty minutes and then data is taken.Data is collected and recorded for Attachment A, 100%Heat Balance Control Board Data.Calculations were performed as indicated in Attachment B.Data is evaluated against the Acceptance Criteria of section 5.0, as applicable.
ATE This test can be run with 100%Steady-State Accuracy Test, 14,4.4.1.INITIAL CONDITIONS:
IC-14 100%Power with Equilibrium Xenon.FINAL CONDITIONS:
IC-14 100%Power with Equilibrium Xenon.SOURCE OF COMPARISON DATA: PLANT DATA SET ENGINEERING EVALUATION FSAR 0 SOBR/LER OPERATIONALASSESSMENT TEST RESULTS: TBST RBSULTS UNSATISFACTORY WITH DISCRBPANCIBS TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES APPENDIX D ATTACHMENT D-5 WASHINGTON PUBLIC POWER SUPPLY SYSTEM TRANSIENT PERFORMANCE TEST ABSTRACTS
OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Transients TEST No.14.4.8.4 REV.4 TITLE: INDUCED TRANSIENT TESTS-POWER RAMP FROM loo PERCENT POWER TO 75 PERCENT TO l00 PERCENT D IREDRE P N E: This test is performed to evaluate the tuning of the feedwater system.Using the RRC FCV's power is ramped down from 100 percent to 75 percent in 10 seconds.After stabilizing Rx level, power is xamped from 75 percent to 100 percent in 10 seconds.Proper response of the induced transient was tested and verified.INITIAL CONDITIONS; IC-14 100%Power Equilibrium Xenon.FINAL CONDITIONS:
100%Power.SOURCE OF COMPARISON DATA: PLANT DATA SEI'NGINEERING EVALUATION FSAR X SOER/LBR X OPERATIONAL ASSESSMENT 84-124 12/03/84 84-125 11 27 84 TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES X TEST RBSULTS SATISFACTORY WITHOUT DISCREPANCIES W
OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Transient TESTNo.144101 REV.5 TITLE: LOSS OF AJ L REACTOR FEEDWATER DESIRED RESPONSE: RFW Turbines'A'nd'B'nd RCIC Trip.Followed by Reactor SCRAM on Low RPV/L.RRC FCV RunBack and Pump Downshift to 15 Hz verified.Simulated Operator actions include: MT Trip, Reactor Mode Switch being placed in Shutdown and HPCS Manual Ini-tiation.HPCS-V-4 Auto Closure at RPV/L 8 (54.5")is verified.Proper Control Board Indications and annunciation verified throughout transient.
INITIAL CONDITIONS:
IC-14, 100%Power Equilibrium Xenon.FINAL CONDITIONS:
Reactor Scrammed.RPV/L Restored via HPCS.MSIV's isolated with RPV/P slowly increasing after termination of HPCS Flow.SOURCE OP COMPARISON DATA: PLANT DATA SBT ENGINEERING EVALUATION FSAR SOER/LBR OPERATIONAL ASSESSMENT TEST RESULTS: TEST RBSULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES X TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Transient TEST No.14.4.10.2 REV.4 TITLE: LOSS OF ALL AC STATION BLACKOUT DESIRED RESPONSE: Loss of All AC with exception of DG-3.Subsequent NS4 Isolations with RPV/P Control via SRV's with HPCS and RCIC Initiation at 30 seconds to restore and control RPV/L.Primary Containment heatup verified for proper direction and trend for associated vari-ables.HPCS and RCIC Operation for RPV/L Control on isolated RPV verified.INITIAL CONDITIONS:
IC-14, 100%Power Equil Xenon FINAL CONDITIONS:
Shutdown with DGN-3 supplying HPCS;RCIC Operation controlling RPV/L.SOURCE OF COMPARISON DATA: PLANT DATA SET ENGINEERING EVALUATION FSAR SOER/LBR II OPERATIONAL ASSESSMENT TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES
OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Transients TEST No.14.4.103 REV.4 TITLE: MSIV ISOL4TION This test was performed to verify the Simulators response to an MSIV Isolation.
The MSIV isolation was verified to cause RPV/P incxease and subsequent SRV operation followed by the initiation of HPCS and RCIC at-50 inches.SRV operation at setpoint was verified in conjunction with RCIC-V-45 closure and HPCS-V-4 closure and subsequent cycling closed at RPV/L 8.The SRV flow decxease was verified as RPV Decay Heat decreased.
The relationship between decay heat genera-tion, RPV/P, SRV Flow, HPCS and RCIC flow (at LT saturated conditions) were evaluated.
No oper-ator actions were taken as specified in ANS 3.5 Attachment B, item B1.2.ANS 3.5 item B1.2.1 variables were plotted and evaluated at.5 sec resolution as specified.
INITIAL CONDITIONS:
IC-14 100%Power Equilibrium Xenon.FINAL CONDITIONS:
Reactor Shutdown with SRV Operation controlling RPV/P at setpoint and periodic HPCS injection controlling RPV/L between RPV/L 8 and RPV/L 2.SOURCE OF COMPARISON DATA: X PLANTDATASET ENGINEERING EVALUATION FSAR X SOER/LER X OPERATIONAL ASSESSMENT SCRMLER88.03 LER 88-03 TEST RESULTS: TESTRESULTS UNSATISFACTORY WITH DISCREPANCIES
\TEST RESULTS SATISFACTORY WITH DISCREPANCIES PX TBST RESULTS SATISFACTORY WITHOUTDISCRBPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Transients TEST No.14.4.10.5 REV.4 TITLE: SIMULTANEOUS TRlP OF ALL RFP'S-SLF: FPT 2A and FPT 2B D IREDRE P N E: This test is performed to verify the Simulators response to a simultaneous trip of all RFP's.The RRC FCV xunback at RPV/L 4 with coincident RFP txip is vexified.Reactox Scram and RRC pump trip to 15 hz is verified at RPV/L 3.The Scram induced RPV/P reduction with Mode Switch in run is verified to cause a MSIV isolation.
The subsequent SRV operation with resultant inventory loss and initiation of the RPV/L 2 NS4 isolation, HPCS initiation, RCIC initiation, and RRC pumps tripping to o6'were vexified and evaluated.
HPCS-V-4 and RCIC-V-45 closure at RPV/L 8 and subsequent reopening of HPCS-V-4 at RPV/L 2 were verified.No operator actions were taken as specified in ANS 3.5 Attach-ment B, item B1.2.ANS 3.5 item B1.2.1 variables were plotted and evaluated at.5 sec resolution as.specified.
Note: Scxam details evaluated in detail in 14.4.9.24.33, MT Trip details evaluated in 14.4.9.24.31, Main Gen Trip details evaluated in 14.4.9.13.1, NS4 Isolation at RPV/L 2 evaluated in 14.4.9.2.3 RFW Break in DW.INITIAL CONDITIONS:
IC-14, 100%Power Equilibrium Xenon.FINAL CONDITIONS:
Reactor Shutdown with SRV Operation controlling RPV/P at setpoint and periodic HPCS injection controlling RPV/L between RPV/L 8 and RPV/L 2.SOURCE OF COMPARISON DATA: X PLANT DATA SET ENGINBERING EVALUATION FSAR X SOBR/LER X OPERATIONAL ASSESSMENT SCRMLER84.114 LE 4-4 TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACI'ORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Transients TEST No.14.4.10.6 t REV.4 TITLE: SIMULTANEOUS TRIP OF ALL RECIRCULATION PUMPS-SLF: EPS 43&EPS 44 ED ESP E This test is performed to verify the Simulators response to a trip of all Recirculation Pumps.Core Power is verified to decrease due to the Core flow reduction to Natural Circulation.
Activation of mechanistic power oscillations on entry to Region A of power to flow map, verified.No operator actions were taken as specified in ANS 3.5 Attachment B, item B1.2.ANS 3.5 item B1.2.2 variables were plotted and evaluated at.5 sec resolution as specified.
INITIAL CONDITIONS:
IC-14, 100%Power Equilibrium Xenon.SOURCE OF COMPARISON DATA: g PLANT DATA SEI'ENGINEERING EVALUATION FSAR SUER/LER X OPERATIONAL ASSESSMENT PAT OB TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES PX TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Transients TEST No.14.4.10.7 REV.4 TITLE: MAXIMUM SIZE DBA LOCA WITH LOSS OEFSITE POWER SLF: RRS 4 and OED2 ED P E'his test was performed to verify the Simulators response to a Maximum size DBA LOCA with LOP.The DW/P increase initiation of Reactor Scram, NS4 Isolation and RRC FCV lockup were verified.The RRC pump trip to 15 Hz via RPV/L 3 signals is verified.The initiation of the RPV/L 2 NS4 isolation, HPCS initiation, RCIC initiation, and RRC pumps tripping to oK were verified and evaluated.
Div 1 and Div 2 DG's and ECCS initiation were verified.DW/P response and subsequent WW/P response are verified as the DW/P overcomes downcomer submergence.
No operator actions were taken as specified in ANS 3.5 Attachment B, item B1.2.ANS 3.5 item B1.2.3 variables were plotted and evaluated at.5 sec resolution as specified.
Note: Scram details evaluated in detail in 14.4.9.%.33, MT Trip details evaluated in 14.4.9.24.31, Main Gen Trip details evaluated in 14.4.9.13.1, NS4 Isolation at RPV/L 2 evaluated in 14.4.9.2.3 RFW Break in DW.INITIAL CONDITIONS:
IC-14 100%Power Equilibrium Xenon.t FINAL CONDITIONS:
Reactor Shutdown with RPV/L being controlled GT'Avo-Thirds Core Height via E<CCS Div 1-3 Injection.
Primary Containment Isolation complete via NS4 Isolations.
SOURCE OF COMPARISON DATA: PLANT DATA SEI'ENGINEERING EVALUATION FSAR SOER/LER X OPERATIONAL ASSESSMENT ANF LOCA ANALY IS TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST No.144 10 9 TEST CATEGORY: Transients TITLE: MAXIMUM SIZE MAIN STEAMI.INE RUPTURE REV.0 IRED RESP N E: This test is performed to verify the Simulators response to a Maximum size MSL Break.The DW/P increase initiation of Reactor Scram, NS4 Isolation and RRC FCV lockup were verified.The RRC pump trip to 15 Hz via RPV/L 3 signals is verified.The initiation of the RPV/L 2 NS4 isolation, HPCS initiation, RCIC initiation, and RRC pumps tripping to off were verified and evaluated.
Div 3 DG and HPCS initiation were verified.DW/P response and subsequent WW/P response are verified as the DW/P overcomes downcomer submergence.
CBP injection and subsequent RPV/L restoration, with DW cooling via break verified.No operator actions were taken as specified in ANS 3.5 Attachment B, item B1.2.ANS 3.5 item B1.2.3 variables were plotted and evaluated at.5 sec resolution as specified.
Note: Scrain details evaluated in detail in 14 4.9.24.33, MT Trip details evaluated in 14.4.9.24.31, Main Gen Trip details evaluated in 14.4.9.13.1, NS4 Isolation at RPV/L 2 evaluated in 14.4.9.2.3 RFW Break in DW.INITIAL CONDITIONS:
IC-14 100%Power Equilibrium Xenon.FINAL CONDITIONS:
Reactor Shutdown with RPV/L GT the MSL 110 inches.Primary Containment Isolation complete via NS4 isolations.
SOURCE OF COMPARISON DATA: PLANT DATA SET ENGINEERING EVALUATION g FSAR SOER/LER g OPERATIONAL ASSESSMENT 15.6.5 6.2.1.1.3.b TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES
OPERATIONAL REVIEW
SUMMARY
t TEST CATEGORY: Transients TEST No.14.4.10.10 TITLE: MSlV ISOLATION WITH SRV FAILED OPEN REV.4 D IREDR P N E'his test is performed to verify the Simulators response to an MSIV Isolation with a SRV failed open.The MSIV isolation with SORV is verified to cause a RPV/P reduction with a subsequent injection by the Condensate Booster Pumps at approx-imately 630 psig.The SRV flow decrease is verified as RPV/P decreased.
The rela-tionship between decay heat generation, RPV/P, SRV Flow, and Condensate Booster Pump flow (at LT saturated conditions) were evaluated.
No operator actions were taken as specified in ANS 3.5 Attachment B, item B1.2.ANS 3.5 item B1.2.3 variables were plotted and evaluated at.5 sec resolution as specified.
INITIAL CONDITIONS:
IC-14 100%Power Equilibrium Xenon.FINAL CONDITIONS:
Reactor Shutdown and depressurized with CBP injection and RPV/L GT the MS lines resulting in liquid How via the SORV.SOURCE OF COMPARISON DATA: X PLANT DATA SEI'NGINEERING EVALUATION FSAR X SUER/LER X OPERATIONAL ASSESSMENT SCRMLER88.03 TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RBSULTS SATISFACI'ORY WITHOUT DISCRBPANCIES OPERATIONAL REVIEW
SUMMARY
TEST No.14.4.10.16 REV.4 TITLE: LOSS EW WITH EMERGENCY DEPRESS URlZATION DESIRED RESPONSE: Loss of Normal RFW and HP Injection, followed by Emergency Depressurization when RPV/L decreases to Top of Active Fuel.RPV/L, RPV/P and Core Flow as weH as signifi-cant Primary Containment variables evaluated during conduct of test.The NS4 Isolation is subsequently reset and plant placed in the Shutdown Cooling Alignment followed Emer-gency Depressurization and RPV Level Restoration with Low Press ECCS.INH'IAL CONDITIONS:
IC-14 100%Power and Flow with Equilibrium Xenon.t FINAL CONDITIONS:
Plant SD with RHR B in the Shutdown Cooling Alignment and RHR B in Suppression Pool Cooling.SOURCE OF COMPARISON DATA: PLANT DATA SEI'NGINEERING EVALUATION FSAR SOER/LER X OPERATIONAL ASSESSMENT TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES X TEST RESULTS SATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACI'ORY WITHOUT DISCREPANCIES APPENDIX D ATTACHMENT D-6 WASHINGTON PUBLIC POWER SUPPLY SYSTEM PLANT MALFUNCTION TEST ABSTRACTS OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Plant Malfunction TEST No.14.4.9.18.3 REV.6 TITLE: INSTRUMENT REFERENCE LINE BREAK D004C (PENXII2)-SLF: RRS7C D I EDR P NE'his test is performed to demonstrate the functionality of the, INSTRUMENT REF LINE BREAK D004C (PENX112).
Rupture of INST Line between REACTOR and CONDENSATE POT for DOO4C (PENX112).
Apparent level increased MS-LIS-100B, P601-A1-'2-6 Injection Vlv Closure RPV LEVEL HIGH+54.5" alarmed, and HPCS-V-4 remained shut.Apparent lev'el increased RFW-DPT-4C, MS-LI-604 and RFW-LI 606C indicated upscale high.REACI'OR VESSEL HIGH LEVEL C SEAL light illuminated and RFW/I'URBINE RPV LEVEL HIGH TRIP alarm activated.
Leak is allowed to run and caused drywell pressure to increase.DRYWELL PRESS HIGH/LOW ALERT alarmed followed by the Drywell Press High Trip.Proper response on activation of INST REF LINE break DOO4C was tested and verified.~+<~: Details of Reactor Scram evaluated in test 14.4.9.24.33, DBA LOCA evaluated in test 14.4.10.7.
INITIAL CONDITIONS:
IC-14 100%Power with E<quilibrium Xenon FINAL CONDITIONS:
Reactor has Scrammed on Hi Drywell pressure.SOURCE OF COMPARISON DATA'LANT DATA SET ENGINEERING EVALUATION g I SAR g SOER/LER g OPERATIONAL ASSESSMENT 15..2 5-5 0 4 5 TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACI'ORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Plant Malfunction TEST No.14.4.9.16.4 REV.3 TITLE: HPCS LOGIC FAILURE-SLF: CSS>>6 DE IREDRE P N E'his test is performed to demonstrate the functionality of the'"HPCS LOGIC FAILURE Malfunction.
HPCS Initiation Failure to automaticaHy respond.System responses include: P601-A1-6.8, HPCS SYSTEM OUT OF SERVICE, HPCS-BISI-HPCS LOGIC PWR FAIL, failure of HPCS Injection valve V-4 to automatically close when RPV level is GT+54" and minimum flow Bypass valve V-12 to automatically open or close on HPCS flow.INITIAL CONDITIONS; IC-12 100%Power with Equilibrium Xenon.FINAL CONDITIONS:
100%Power with HPCS injection in progress.SOURCE OF COMPARISON DATA;PLANT DATA SKI'NGINEERING EVALUATION g FSAR C]SOER/LER g OPERATIONAL ASSESSMENT 15.5.1 TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW UMMARY TEST CATEGORY: Plant Malfunction TEST No.14.4.9.18.6 REV.5 TITLE: INSTRUMENT VARIABLE LEG LINE BREA'111-SLF'RRS SC RED E P E: This test is performed to demonstrate the functionality of the INSTRUMENT VARIABLE LEG LINE BREAK Xlll SLF.System responses included: PI-EFC-Xlll changed position from open to closed, apparent loss of level as indicated by MS-LR/PR-623B downscale, NS4 ISOL RPV LEVEL LOW-50"alarmed, MSIV Half Trip System B, and RC-2 HALF TRIP annunciated.
Proper response on activation of the INSTRUMENT VARjlABLE LEG LINE BREAK Xll 1 malfunction was tested and verified.INITIAL CONDITIONS:
IC-14 100%Power with Equilibrium Xenon t FINAL CONDITIONS:
Reactor Scrammed, RRC Pumps Off, RCIC-V-45 Oscillating with RPV/L 8 controlling RPV/L.SOURCE OF COMPARISON DATA: PLANT DATA SBT ENGINEERING EVALUATION g FSAR SOERiLBR g OPERATIONAL ASSESSMENT 15.6.2 TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACI'ORY WITHOUT DISCRBPANCIES OPERATIONAL REVIEW
SUMMARY
TEST No.14.4.9.24.27 REV.3 TITLE: MAIN STEAM SAFETY RELIEF VALVE FAILS OPEN-CLF: RRS l STPT DRIFT ED RE P SE: This test is performed to demonstrate the functionality of the MAIN STEAM SAFETY RELIEF VALVE STPT DRIFT Component Level Failure.Mechanical setpoint adjustment out of adjustment.
System responses included: SRV MS-RV-1A opened, P601-A2-5-8 SRV OPEN, SRV ACOUSTICAL VALVE MON DRAWER (MS-RV-1A)
SRV cards alarmed and the flow card indicated 100 percent flow.Steam-line A flow dropped as indicated on RFW-FI-603A.
At the DEB panel, Generator Output MW's dropped.An attempt to use the manual control switch for MS-RV-1A had no effect.Proper response on activation of the Main Steam Safety Relief Valve Fails Open malfunction was tested and verified.INITIAL CONDITIONS:
IC-14 100%Power Equilibrium Xenon FINAL CONDITIONS:
100%Power, SRV open, reduced MW's from Generator SOURCE OF COMPARISON DATA: X PLANT DATA SEI'NGINEERING EVALUATION QX FSAR SUER/LER g OPERATIONAL ASSESSMENT 15.1A TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DIS CRBPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Plant Malfunction TEST No.14 4.9.25.14 REV.1 TITLE: SRV'S-FAIL CLOSED-CLF: RRS 12-RRS l8 (OPTION 4)E IRED E N E This test is performed to demonstrate the functionality of the SRV's FAIL CLOSED Malfunction.
SRV's fail closed due to electrical fault.Malfunction is selected on seven ADS valves.Attempts were then made to open the SRV's: Manually from P601, arming and depressing DIV I ADS push-buttons, Key switches to open on F628 and F631 none of the SRV's opened.Proper response on activation of the individual malfunctions were tested and verified INI'GAL CONDITIONS:
IC-14 100%Power with Equilibrium Xenon.FINAL CONDITIONS:
IC-14 100%Power with Equilibrium Xenon.SOURCE OF COMPARISON DATA: PLANT DATA SET ENGINEERING EVALUATION P FSAR 0 SOER/LER g OPERATIONAL ASSESSMENT TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACP DRY WITHOUT DISCRBPANCIBS OPERATIONAL REVIE%
SUMMARY
TEST CATEGORY: Transients TEST No.X4.4.X0.X0 TITLE: MSIV ISOLATION WITH SRV FAILED OPEN REV.4 D IREDRE N E'his test is performed to verify the Siinulatoxs response to an MSIV Isolation with a SRV failed open.The MSIV isolation with SORV is verified to cause a RPV/P reduction with a subsequent injection by the Condensate Booster Pumps at approx-imately 630 psig.The SRV flow decxease is verified as RPV/P decreased.
The rela-tionship between decay heat generation, RPV/P, SRV Flow, and Condensate Boostex Pump flow (at LT saturated conditions) were evaluated.
No operator actions were taken as specified in ANS 3.5 Attacliment B, item B1.2.ANS 3.5 item B1.2.3 variables were plotted and evaluated at.5 sec resolution as specified.
INITIAL CONDITIONS:
IC-14 100%Power Equilibrium Xenon.FINAL CONDITIONS:
Reactor Shutdown and depressurized with CBP injection and RPV/L GT the MS lines resulting in liquid flow via the SORV.SOURCE OF COMPARISON DATA: X PLANT DATA SET ENGINEERING EVALUATION FSAR X SOER/LER X OPERATIONAL ASSESSMENT SCRMLER88.03 TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST No.14.4.9.4.4 REV.3 TITLE: LEAIC DOWNSTREAM OF CONTROL AIR DRYER-SLF: CAS-4 D IREDR P N E'his test was performed to demonstrate the functionality of the LEAK DOWNSTREAM OF CON-TROL AIR DRYER Malfunction.
Leak occurs in the control air line between the dryers and the after filters.System responses included: control room indication showed decreasing air pressure, standby air compressors started at 90 psig, applicable annunciators alarmed, service air header iso-lation valve (SA-PCV-2) shut at 80 psig, SCRAM VALVE PILOT AIR HDR PRESS LOW alarmed at 65 psig, rods started drifting in, and the Reactor SCRAM occurred from SDV/L scram stpt.Sig-nificant BOP responses included: condenser water level increased, Feedwater Heater level control valves failed open, Rx bldg.supply and return valves shut, REA and ROA fans tripped, and RB pressure increased.
Valves and systems failed IAW Attachment E.Proper system response on acti-vation of the LEAK DOWNSTREAM OF CONTROL AIR DRYER malfunction was tested and verified.INITIAL CONDITIONS:
IC-14 100%Power with Equilibrium Xenon.FINAL CONDITIONS:
Reactor SCRAM with significant systems and valves in loss of air failed positions.
SOURCE OF COMPARISON DATA: PLANT DATA SEI'NGINBBRING EVALUATION FSAR SOER/LER g OPERATIONAL ASSESSMENT TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Plant Malfunction TEST No.14.4.9.8.3 REV.3 TITLE: 4l60 VAC BUS SM-8 OVERCURRENT
-SLF: BOP'PS)EPS lII D IRED E P N E This test is performed to demonstrate the functionality of the 4160 VAC BUS SM-8 OVERCUR-RENT-GRND Malfunction.
Electrical insulation failure causes a ground and overcurrent on SM-8.System responses included: appropriate annunciators alarmed, bkr 8-3 tripped open and was locked out, bkr B-8 open, 8-DG2 open, (volt and amp)meters on SM-8 and her daughter buses indicated zero readings, DG-2 auto-started and was running unloaded without SW cooling, TSW-P-1A started on low pressure, and RPS bus B half-SCRAM occurred.Proper response to the loss of motive power provided by SM-8 and her daughter busses was tested and verified.Proper response to the loss of contxol and indication power provided by SM-8 and her daughter busses were tested and verified INITIAL CONDITIONS:
IC-14 100%Power with Equilibrium Xenon.FINAL CONDITIONS:
100%Power, 1/2 Scram B Channel.SOURCE OF COMPARISON DATA: PLANT DATA SET ENGINEERING EVALUATION FSAR SOER/LER X OPERATIONAL ASSESSMENT TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACI'ORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Plant Malfunction TEST No.14.4.9.8.3A REV.0 TITLE: 4160 VAC BUS SM-7 OVERCURRENT
-SLF: BOP)EPS)EPS IG DESIRED RESPONSE: This test is performed to demonstrate the functionality of the 4160 VAC BUS SM-7 OVER-CURRENT-GRND Malfunction.
Electrical insulation failure causes a ground and overcurrent on SM-7.System responses included: appropriate annunciators alarmed, bkr 7-1 tripped open and was locked out, bkr B-7 open, 7-DG1 open, (volt and amp)meters on SM-7 and her daugh-ter buses indicated zero readings, DG-1 auto-started and was running unloaded without SW cooling, TSW-P-1B started on low pxessuxe, and RPS bus A half-SCRAM occurred.Proper xesponse to the loss of motive powex provided by SM-7 and her daughter busses was tested and verifie.Proper response to the loss of control and indication power provided by SM-7 and her daughter busses was tested and vexified INITIAL CONDITIONS:
IC-14 100%Power with LIquilibrium Xenon.FINAL CONDITIONS:
100%Power, 1/2 Scram A channel.SOURCE OF COMPARISON DATA: PLANT DATA SEI'NGINBERING EVALUATION FSAR SOER/LER X OPERATIONAL ASSESSMENT TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACI'ORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Plant Malfunction TEST No.14.4.9.8,3B REV.1 TITLE: OVERCURRENT SM-1-SLF: EPS 1A IRED R P E: This test is performed to demonstrate the functionality of the 4160 VAC BUS SM-1 OVERCURRENT Malfunction.
Overcurrent 8c Lockout Condition of Bus SM-1.System responses included: appropriate annunciators alarmed, Bkr Nl-1 tripped open and is locked out, Bkr 1-11 tripped and locked out, Bkrs (1-7,7-1,11-1) tripped, (volt and amp)meters on SM-1 indicated zero readings, DG-1 auto-started and is running unloaded, Bkr B-7 closed and supplied SM-7.Proper response to the loss of motive power provided by SM-1 is tested and verified.NOTE: LOSS OF BUS SM-7 is evaluated in 14.4.9.8.3.A INITIAL CONDITIONS:
IC-14 100%Power with Equilibrium Xenon.FINAL CONDITIONS:
One third of the Condensate system capacity has been lost and will cause a subsequent reactor SCRAM.SOURCE OF COMPARISON DATA: PLANT DATA SEI'NGINEERING EVALUATION FSAR SOBR/LBR X OPERATIONAL ASSESSMENT TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Plant Malfunction TEST No.14.4.9.8.4 REV.3 TITLE: GROUNDED DC BUS-DP-Sl-2-SLF: EPS 3D D IREDR P N E: This test is, performed to demonstrate the functionality of the GROUNDED DC BUS-DP S1-2 TRIP Malfunction.
Electrical insulation failure causes a ground.System responses included: Appropriate Annunciator alarms, applicable BISI panel alarms, IN-2 shifted to the alternate AC source, ampmeters (AM-B 1-2 8c AM-Cl-2)indicated zero, and VM-S 1-2 indicated zero.Proper response to the loss of motive power provided by DP-S1-2 is tested and verified for all loads.Proper response to the loss of control and indication power provided by DP-S1-2 was tested and verified INITIAL CONDITIONS:
IC-14 100%Power with Equilibrium Xenon.FINAL CONDITIONS:
RCIC and CAC systems OOS, numerous indications OOS.SOURCE OP COMPARISON DATA: PLANT DATA SET ENGINEERING EVALUATION FSAR P SOBRIr ER g OPERATIONAL ASSESSMBNT TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES
-g TEST RESULTS SATISFACTORY WITH DISCREPANCIES P TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES
'I OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Plant Malfunction TEST No.14.4.9.8.5 REV.3 TITLE: 6900 VAC BUS SH-6 OVERCURRENT
-GND-BOP)EPS)EPS-5B DESIRED RESPONSE: This test is performed to demonstrate the loss of power to Bus SH-6 using malfunction 6900 VAC BUS SH-6 OVERCURRENT
-GRND.Proper response to the loss of motive power provided by SH-6 and her daughter busses was tested and verified.Proper response to the loss of control and indication power pro-vided by SH-6 and her daughter busses was tested and verified INITIAL CONDITIONS:
IC-14 100%Power with Equilibrium Xenon.FINAL CONDITIONS:
Bus SH-6 has tripped, RRC-P-1B has tripped, Rx is in single loop with final feedflow and steam flow greater than 45%.SOURCE OF COMPARISON DATA: PLANT DATA SEI'NGINEERING EVALUATION FSAR SOER/LBR g OPERATIONAL ASSESSMENT TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RBSULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Plant Malfunction TEST No.14.4.9.8.7 REV.3 TITLE: LOSS OF ALL OFF-SITE POWER-SLF: OED 2 D EDR P This test is pexformed to demonstrate the functionality of the LOSS OF ALL OFF-SITE POWER Malfunction.
A tornado destroys all outside transmission lines to the plant.Simulator is fxozen at six seconds for initial evaluation.
Simulator is then placed in RUN again.System responses included: appxopxiate annunciatoxs alarmed, multiple A.C.Amp meters indicated zero, multiple A.C.Volt metexs indicated zexo, the Reactor had scrammed, the'Ibxbine had tripped, the MSIV'S were closed, and the SRV's were controlling pressure.All major electrical breakers tripped opened as listed.Emergency diesels are.running unloaded and DC pumps have started.Simulator is restarted and runs for twenty sec.Proper xesponse to the loss of motive power pxovided by all major A.C.Busses and their daughter busses was tested and verified.Proper response to the loss of control and indication power provided by major A.C.Busses and their daughter busses wexe tested and verified INITIAL CONDITIONS:
IC-14 100%Power with Equilibrium Xenon.FINAL CONDITIONS:
Reactor Scrammed, all major AC Busses de-energized, Vital AC Busses powered by EDG's, pressure controlled by SRV's.SOURCE OF COMPARISON DATA: PLANT DATA SET ENGINEERING EVALUATION QX FSAR SOBR/LER X OPERATIONAL ASSESSMENT TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TBSTRBSULTS SATISFACTORY WITHOUTDISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Plant Malfunction TEST No.14.4.9.8.8 REV.3 TITLE: DG 2 TRIP-HIGH DIFFERENTIAL CURRENT-SJ F: BOP'GNP DGN 2P DGN 2B DESIRED RESPONSE::
This test is performed to demonstrate the functionality of the DG 2 TRIP-HIGH DIFFERENTIAL CURRENT Malfunction.
Defective electrical insulation causes high phase-to-phase differential current.System responses included: appropxiate annunciators alarmed, CB-8DG2 tripped, Bkr DG2-8 tripped, and EDG2 control room indications failed to zero.Proper response on activation of High Differential Current on DG2 and attendant loss of power to SM-8 is tested and verified.NOTE: Response to the loss of motive, contxol, and indication power pxovided by SM-8 are evaluated in Test No.14.4.9.8.3 (LOSS OF POWER TO SM-8).INITIAL CONDITIONS:
IC-14 100%Power with Equilibrium Xenon.FINAL CONDITIONS:
SM-8 is De-Energized and a half scram has occurred on RPS-B.SOURCE OF COMPARISON DATA: PLANTDATA SET ENGINEERING EVALUATION FSAR SOER/LER M OPERATIONAL ASSESSMENT TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TBSTRBSULTS SATISFACTORY WITH DISCREPANCIES PX TEST RESULTS SATISFACI'DRY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Plant Malfunction TEST No.14.4.9.24.15 TITLE: DC BUS TRIP LOAS'S LPS80 and EPS009 REV.3 DESIRED RESPONSE: This test was performed to demonstrate the functionality of the Sl-1 Charger and Battery Breaker LOA's.Proper response to the loss of Control and Indication power provided by Sl-l was tested and verified.All control board indications and annunciators verified to be correct.~t'ontrol Power Verification and response is tested in 14.4.9.&.56, BATIERY CHARGER Cl-1 TRIP Test.INITIAL CONDITIONS:
IC-14 100%Power Equilibrium Xenon.FINAL CONDITIONS:
Bus Sl-1 de-energized.
SOURCE OF COMPARISON DATA: PLANT DATA SEI'NGINEERING EVALUATION FSAR SOER/LER g OPERATIONAL ASSESSMENT TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES QZ TEST RBSULTS SATISFACTORY WITHOUT DISCREPANCIES e e (~
OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Plant Malfunction TITLE: Sl-l TRIP-SLF: EPS 3C TEST No.14.4.9.24.15A REV.1 E EDR This test was performed to demonstrate the functionality of the S1-1 TRIP Malfunction.
DC Bus Sl-l Trip.Proper response to the loss of Control and Indication power provided by S 1-1 was tested and verified IAW Attachment E.NOTE: All final control board indications and annunciators activated are identical to test 14.4,9.24.15, Sl-1 DC GROUND, with the exception of no battery ground annunciator and no ground detection meter defiection.
ARRAiBRI-14.4.9.94.66, BATII!RT CHARGER Cl-I TRIP 4 I PL ,C Power and Loss Control Board indication, therefore evaluation not performed in this test.INI'HAL CONDITIONS:
IC-14 100%Power Equilibrium Xenon FINAL CONDITIONS:
IC-14 100%Power with BUS Sl-1 De-Energized SOURCE OF COMPARISON DATA: PLANT DATA SET BNGINEERING EVALUATION FSAR SOER/LBR g OPERATIONAL ASSBSSMBNT TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RBSULTS SATISFACTORY WITH DISCREPANCIES X TEST RESULTS SATISFACTORY WITHOUT DISCRBPANCIES
OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Plant Malfunction TEST No.14.4.9.24.18 REV.3 TITLE: RPS 8 MG SET TMP-LOA: BOP'PS, EPS-279>OPEN ED P N E'liis test is performed to demonstrate the functionality of the RPS B MG SET TRIP Malfunction.
RPS-EPA-3B breaker opens.System responses included: Multiple annunciators associated with a total loss of RPS Bus B, Scram Group Solenoid lights for Gps 1,2,3,8>4 extinguished, BU Scram amber lights illuminated, RPS Bus B power available light extinguished, and APRM groups B, D, and F indi-cated downscale.
An NSSSS inboard and outboard isolation occurred.Group's 1,2,4,8c 7 (inboard and outboard)valves closed and could not be opened, MSIV's remained open (half isolation).
Proper response to the loss of control and indication power provided by RPS-PP-001-B is tested and verified IAW attachment E.Proper response on activation of the RPS B MG SET TRIP malfunction was tested and verified INITIAL CONDITIONS:
IC-14 100%Power Equilibrium Xenon.SOURCE OF COMPARISON DATA: PLANT DATA SET ENGINEERING EVALUATION FSAR X SOER/LER X OPERATIONAL ASSESSMENT 7-014 TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES
OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Plant Malfunction TEST No.14.4.9.24.56 REV.3 TITLE: BATTERY CHARGER Cl-l TMP-LOA: BOP, FPS)EPS-081 IRED RESP NSE: This test is performed to demonstrate the functionality of the BALI'ERY CHARGER Cl-1 TRIP Malfunction.
Activated spurious breaker trip.System responses included: CHARGER Cl-1 TROUBLE alarm, other appropriate alarms, dropping DC voltage, AM-Cl-1 indicates zero amps, AM-Bl-1 indicates about 100 amps.Proper response on activation of Battery Charger Cl-1 Trip was tested and verified.INITIAL CONDITIONS:
IC-14 100%Power Equilibrium Xenon.FINAL CONDITIONS:
IC-14 100%Power Equilibrium Xenon.SOURCE OF COMPARISON DATA: PLANT DATA SET ENGINEERING EVALUATION P FSAR SOER/LBR g OPERATIONAL ASSBSSMBNT TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RBSULTS SATISFACTORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Transient TEST No.14.4.10.2 REV.4 TITLE: LOSS OF ALL AC STATION BLACKOUT DESIRED RESPONSE: Loss of All AC with exception of DG-3.Subsequent NS4 Isolations with RPV/P Control via SRV's with HPCS and RCIC Initiation at 30 seconds to restore and control RPV/L.Primary Containment heatup verified for proper direction and trend for associated vari-ables.HPCS and RCIC Operation for RPV/L Control on isolated RPV verified.INITIAL CONDITIONS:
IC-14, 100%Power Kquil Xenon t FINAL CONDITIONS:
Shutdown with DGN-3 supplying HPCS;RCIC Operation controlling RPV/L.SOURCE OF COMPARISON DATA: PLANT DATA SET ENGINEERING EVALUATION FSAR SOER/LBR X OPERATIONAL ASSESSMENT TEST RESULTS: TEST RBSULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCRBPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Transients TESTNo.144 92434 TITLE: RECIRCULATION PUMP 8 TRIP-CLF, NSSS)RRP, PMP SHAFT SHEAR D IREDR P N E: This test is performed to demonstrate the functionality of the RECIRCULATION PUMP B TRIP Malfunction.
Pump Motor will trip on overcurrent due to shaft seizure.System responses included: Multiple JP meter response IAW test procedure, RRC B Loop JP flow decreased to zero and then increased as reverse flow initiated, RRC A Loop JP flow increased as RRC B loop entered reverse flow, appropriate annunciators alarmed, and total core flow and core DP decreased as indicated on MS-DPR/FR-613.
Reactor power decreased as indicated on IRM/APRM recorders.
RPV level increased as indicated on RFW-LR-608.
Proper response on activation of the Recirculation Pump B Trip malfunction is tested and verified.INI'HAL CONDITIONS:
IC-14 100%Power with Equilibrium Xenon.FINAL CONDITIONS:
Reactor Plant in Single Loop at reduced power.SOURCE OF COMPARISON DATA: g PLANT DATA SET ENGINEERING EVALUATION g FSAR SOER/LER g OPERATIONAL ASSESSMENT PAT30A 15.3.1 TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY, WITH DISCREPANCIES g TEST RESULTS SATISFACI'ORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST No.14.4.10.6 REV.4 TITLE'IMULTAlVEOUS TRlP OF ALL RECIRCUL4TION PUMPS-SLF: EPS 43 d'c EPS 44 I ED EP NE'his test is pexfoxmed to verify the Simulators response to a txip of all Recirculation Pumps.Core Power is verified to decxease due to the Core flow reduction to Natural Circulation.
Activation of mechanistic power oscillations on entry to Region A of power to flow map, verified.No operator actions were taken as specified in ANS 3.5 Attachment B, item B1.2.ANS 3.5 item B1.2.2 variables were plotted and evaluated at.5 sec resolution as specified.
INITIAL CONDITIONS:
IC-14, 100%Power E<quilibrium Xenon.FINAL CONDITIONS:
40%g 4%Power and 25%Core Flow.SOURCE OF COMPARISON DATA: g PLANT DATA SBT ENGINEERING EVALUATION FSAR SOER/LER X OPERATIONAL ASSESSMENT PAT 30B TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIBS X TEST RBSULTS SATISFACTORY WITHOUT DISCRBPANCIES
OPERATIONAL REVIEW
SUMMARY
t TEST CATEGORY: Plant Malfunction TEST No.14.4.9.2.2 TITLE: CONDENSER AIR LEAlC-SLP: CFW 3 REV.3 D IREDRE P N E'his test is performed to demonstrate the functionality of the CONDENSER AIR LEAK Malfunction.
Metal fatigue causes a crack in the condenser shell.System responses included: Control Room indications showed decreasing main condenser vacuum, off gas Qow increased, appropriate annunciators alarmed, and Generator load is decreasing.
The TURBINE GENERATOR tripped on low vacuum and caused a reactor SCRAM.As vacuum continued to decrease an NSSSS isolation occurred and the Main Steam isolation valves closed.Proper response on activation of the CONDENSER AIR LEAK malfunction was tested and verified.5QXE: Turbine Trip evaluated in test 14.4.9.24.31, Reactor Scram evaluated in test 14.4.9.24.33, MSIV Isolation evaluated in test 14.4.10.3 INITIAL CONDITIONS:
IC-14 100%Power with Equilibrium Xenon.e FINAL CONDITIONS:
Reactor Shutdown, RPV/P control via SRV operation, RPV/L decreasing towards RPV/L 2.SOURCE OF COMPARISON DATA: PLANT DATA SBT ENGINEERING EVALUATION g FSAR g SOER/LER g OPERATIONAL ASSESSMENT 4-125 TEST RESULTS: TEST RESULTS UNSATISPACTORY WITH DISCREPANCIES X TEST RESULTS SATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Plant Malfunction TEST No.14.4.9.24.86 REV.0 TITLE: COND-LIC-l FAILS CONDENSER LEVEL LOW DESIRED RESPONSE: Controller Input signal Fails High resulting in Condensate Dump valve opening and a subsequent Low Condenser Level.Level control was then changed to the LIC-2 position.COND-LIC-2 Output signal decreased.
Main Condsex Hotwell Level Low alarm cleared.INITIAL CONDITIONS:
IC-14, 100%Power Equilibrium Xenon, Hotwell Level Normal.SOURCE OF COMPARISON DATA: PLANT DATA SBT ENGINEERING EVALUATION FSAR SOER/LER X OPERATIONAL ASSESSMENT TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Plant Malfunction TEST No.14.4.9.24.5 REV.3 TITLE: SW PUMP B TRIP-CLF: SSW 3-OPT 1 DESIRED R P N E This test is performed to demonstrate the functionality of the SW PUMP A TRIP Malfunction.
Mechanical fault initiates Shaft Shear.System responses included: Service water flow decreased, applicable Service Water flow annunciators alarmed, and multiple BISI lights illuminated from systems affected by a loss of Service water flow.Proper response on activation of the SW PUMP B Shaft Shear component level failure was tested and verified The subsequent heatup of Reactor Coolant System due to Loss of SDC was verified.INITIAL CONDITIONS:
IC-19 SDC in Progress.FINAL CONDITIONS:
IC-19 SDC in Progress without SW IQow to RHR 8 HX.SOURCE OF COMPARISON DATA: PLANT DATA SET ENGINBERING EVALUATION FSAR SOER/LER X OPERATIONAL ASSESSMENT TEST RESULTS: P TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Plant Malfunction TEST No.14.4.9.24.G4 REV.3 TITLE: TSW PUMP TMP D IREDRE PON E'his test is performed to demonstrate the functionality of the TSW PUMP A TRIP Malfunction.
A piece of the impeller separates from the impeller and wedges between the impeller and the casing.System responses included: TSW-P-1A motor current increased, TSW-P-1A tripped, appropriate alarms occurred, TSW-P-1B started at less than or equal to 80 psig, TSW-V-53A closes, and TSW-V-53B opens.The following TSW Loads responded as follows: TCV's held temperatures relatively constant, RFP A8cB oil cooler outlet temperature increased, Main turbine oil coolex outlet temperature increased, tuxbine lube oil temperatures increased as indicated on TG-TR-48 and TG-TR-144.
Drywell tempexatuxe and Containment pressure incxeased.
Proper response on activation of the TSW pump trip was tested and verified.INITIAL CONDITIONS:
IC-14 100%Power Equilibrium Xenon.FINAL CONDITIONS:
100%Power but with higher temperatures on all the loads cooled with TSW.SOURCE OF COMPARISON DATA: Q PLANT DATA SEI'NGINEERING EVALUATION FSAR SUER/LBR QX OPERATIONAL ASSESSMENT TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES
OPERATIONAL REVIEW
SUMMARY
TEST No.14.4.9.25.15 REV.1 TITLE: RCC-P-lA TMP-CLF: RCC I D REDRE P N E'his test is performed to demonstrate the functionality of the RCC-P-1A TRIP malfunction.
RCC-P-1A Trips on Thermal OL due to electrical fault.System responses included: RCC-P-lA tripped, RCC Pump A Motor OL Trip annunciator alarmed, RCC-P-1C auto started, RCC HDR PRESS RCC-PI-3 decreased and then returned to normal, and RCC-V-6 remained open.Proper response on activation of the RCC-P-1A TRIP malfunction was tested and verified INITIAL CONDITIONS:
IC-14 100%Power with Equilibrium Xenon RCC-P-lA and RCC-P-1B running.t FINAL CONDITIONS:
IC-14 100%Power with Equilibrium Xenon, RCC-P-1B and RCC-P-1C running.SOURCE OF COMPARISON DATA: PLANT DATA SBT ENGINBERING EVALUATION FSAR SOER/LER QX OPERATIONAL ASSESSMBNT TEST RESULTS: TEST RBSULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Plant Malfunction TEST No.14.4.9.24.73 REV.3 TITLE: SW-V-28 FAILS CLOSED-OVERRIDE SWZV2BC IREDR P N E: This test is pexfonned to demonstrate the functionality of the SW-V-2B FAILS CLOSED Malfunction.
Internal electrical failure in the auto-open logic circuit.RHR-P-2B is started using contxol switch, with subsequent auto start signal for SW-P-1B.System responses included: SW-V-2B PUMP DISCHARGE did not open, SW-P-1B DISCH PRESS SW-PI-32B decreases to-25 psig, SW-FI-9B did not increase, and SW-P-1B Amp Ind is less than rated amps for normal operation.
Proper response on activation of the SW-V-28 FAILS CLOSED Malfunction was tested and verified.INITIAL CONDITIONS:
IC-14 100%Power Equilibrium Xenon.FINAL CONDITIONS:
IC-14 100%Power Equilibrium Xenon.SOURCE OF COMPARISON DATA: PLANT DATA SET ENGINEERING EVALUATION FSAR SOER/LER g OPERATIONAL ASSESSMENT TEST RESULTS: TEST RESULTS UNSATISFACTORY WITI I DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Plant Malfunction TEST No.14.4.9.2.9 REV.4 TITLE: RFPT A TRIP-SLF: FPT-2A IREDRE P N E This test is performed to demonstrate the functionality of the RFPT A TRIP Malfunction.
Circuit failure causes RFW-DT-1A trip.System responses included the following alarms: TUR A TRIP, TUR A CONTR OIL PRESS LOW, and RFW PMP A DISCH FLOW LOW.Reactor water level decreased on all control room instruments and the RPV LEVEL HIGH/LOW ALERT alarmed.A Recirc Flow Control Runback occurred and the Reactor did not Scram.Proper response on activation of the RFPT A TRIP malfunction was tested and verified.INITIAL CONDITIONS:
IC-14 100%Power Equilibrium Xenon t FINAL CONDITIONS:
Recirc Flow Control valves have runback, RFPT 8 has increased flow to maximum, Reactor is at approx.68 to 72%Power.SOURCE OF COMPARISON DATA: PLANT DATA SEI'NGINEERING EVALUATION FSAR g SOER/LBR g OPERATIONAL ASSESSMENT 84-TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACI'ORY WITHOUT DISCRBPANCIES a h N OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Plant Malfunction TEST No.14.4.9.24.2 REV.3 TITLE: CO1VDENSATE BOOSTER PUMP 2A TRIP-CLF: CFW 4p 2 D IREDRE P N E: This test is performed to demonstrate the functionality of the CONDENSATE BOOSTER PUMP 2A TRIP Malfunction.
Electrical Malfunction causes pump trip.System responses included: booster motor amps peg high and then decreased to zero, appropriate alarms occur, booster pump discharge header pressure decreases, RFW pump suction pressure decreases, and possible trip of one or both RFW pumps.Proper response on activation of the CONDENSATE BOOSTER PUMP 2A Trip is tested and verified.NOTE: RFPT TRIP evaluated per 14A.9.2.9, REACTOR SCRAM evaluated per 14.4.9.%.33, MT/GEN TRIP evaluated per 14.4.9.24.31, MSIV ISOLATION evaluated per 14.4.10.3, LOSS OF ALL RFW evaluated per 14.4.10.1 INITIAL CONDITIONS:
IC-12 100%Po>ver Equilibrium Xenon SOURCE OF COMPARISON DATA: PLANT DATA SET ENGINBERING EVALUATION FSAR g SOER/LER QX OPERATIONAL ASSESSMENT 86-024 TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Malfunction Tests TEST No.14.4.9.24.48 REV.3 TITLE: COND-P-l8 TNP D RDR P NE'his test was performed to demonstrate the functionality of the COND-P-1B TRIP Malfunction.
Electrical Malfunction causes pump trip.System responses included: Cond Pump B motor amps, decxeased, Cond Pumps A 8c C amps increase, appropriate alarms occurred, condensate pump discharge header pressure decreased, Booster and RFW pump suction pressures decreased, and RFW pumps tripped.Proper response on activation of the COND-P-1B TRIP was tested and verified.NOTE: RFPT TRIP evaluated pex 14.4.9.2.9, REACTOR SCRAM evaluated per 14.4.9.24.33, MT/GEN TRIP evaluated per 14.4.9.24.31, MSIV ISOLATION evaluated pex 14.4.10.3, LOSS OF ALL RFW evaluated pex 14.4.10.1.
INITIAL CONDITIONS:
IC-14, 100%Power with Equilibrium Xenon.FINAL CONDITIONS:
RFW Pumps tripped, Reactor has scrammed.SOURCE OF COMPARISON DATA: PLANT DATA SEI'NGINEERING EVALUATION FSAR SUER/LER QX OPERATIONAL ASSESSMENT TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Plant Malfunction TEST No.14 4 10 40 REV.4 TITLE: LOSS OF NORMAL AND EMERGENCY FW-Multiple D EDR P N E'his test is performed to verify the Simulators response to a LOSS OF ALL NORMAL and EMERGENCY FW.The Reactor Scram, NS4 isolation, RRC pump trip, Loss of normal ECCS and RCIC injection sources is verified.RPV/P is verified to increase with the subsequent operation of SRV's to control RPV/P at setpoint following the MSIV isolation.
The RPV/L is verified to slowly decrease as the,Core is blowndown via SRV operation with no normal or emergency feedwater sources available.
SRV operation is verified to diminish as Core Decay heat decreased following the Scram.Note: Scram details evaluated.in detail in 14.4.9.24.33, MT Trip details evaluated in 14.4.9.24.31,MSIV Isolation details evaluated in 14.4.10.3, NS4 Isolation at RPV/L 2 evaluated in 14.4.9.2.3 RFW Break in DW, RFP Trip is evaluated in 14.4.9.2.9.
INITIAL CONDITIONS; IC-14 100%Power Equilibrium Xenon.FINAL CONDITIONS:
Reactor Shutdown with RPV/P being controlled at setpoint via SRV operation resulting in the core slowly blowing down to the Suppression Pool.SOURCE OF, COMPARISON DATA: PLANT DATA SEI'NGINEERING EVALUATION FSAR SOER/LBR g OPERATIONAL ASSESSMENT TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES
OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Plant Malfunction TEST No.14.4.9.16.4 REV.3 TITLE: HPCS LOGIC FAILURE-SLF: CSS-6 D E This test is performed to demonstrate the functionality of the HPCS LOGIC FAILURE Malfunction.
HPCS manually initiated via activation of ARM/DEPRESS push-button and the failure to automatically start, verified.Subsequent manual start of HPCS-P-1 and manual opening of HPCS-V-4.System responses include: F601-A1-6.8, HPCS SYSTEM OUT OF SERVICE, HPCS-BISI-HPCS LOGIC PWR FAIL, failure of HPCS Injection valve V-4 to automatically close when RPV level is GT+54" and minimum flow Bypass valve V-12 to automatically open or close on HPCS flow.INITIAL CONDITIONS:
IC-14 100%Power with E<quilibrium Xenon.e FINAL CONDITIONS:
Reactor Scrammed with both RFW Turbines tripped on HIGH RPV/L with HPCS Injection ongoing.SOURCE OF COMPARISON DATA: PLANT DATA SBT ENGINEERING EVALUATION g FSAR SUER/LER g OPERATIONAL ASSESSMENT 15.5.1 TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RBSULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Plant Malfunction TEST No.14.4.9.21.1 REV.3 TITLE: ADS LOGIC FAILURE (INADVERTENT INITIATION)
-ADS l D IREDRE N E: Tlus test is performed to demonstrate the functionality of the ADS LOGIC FAILURE INADVERTENT INITIATION)
Malfunction.
A surveillance being performed results in an inadvertent initiation of the ADS.System responses included: Applicable annunciatox's alarmed, the seven ADS valves opened and their respective acoustic monitor lights illuminated, suppxession pool temperatures and pool level increased, and Reactor pressure decreased.
Steam flow to Main Turbine decxeased and Generator MWE output decreased followed by a Reactor power increase when feedwatex temperatuxe decreases.
The steam flow, feed flow mismatch errox to the level contxol system causes the RPV water level to be maintained at<30".DW Temperature, DW Pxessure as well as Wetwell Air Temperatuxe and Suppression Pool Temperature increasing.
Proper response on activation of ADS Logic Failure inadvertent Initiation) malfunction was tested and vexified.INITIAL CONDITIONS:
IC-14 100%Power Equilibrium Xenon FINAL CONDITIONS:
RPV pressure e-984 psig with 7 ADS valves open and Main Iturbine/Generator-60%load.Simulator placed in FREEZE prior to DW High Pressure activation SOURCE OF COMPARISON DATA: PLANT DATA SEI'NGINEERING EVALUATION FSAR SOBR/LBR X OPERATIONAL ASSBSSMBNT TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES QX TBST RESULTS SATISFACTORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Plant Malfunction TEST No.14.4.9.24.78 REV.3 TITLE: ATWS/ARI 8 LOGIC FAILURE-(See ATP for Listing)IREDR P N E'his test is performed to demonstrate the functionality of the ATWS/ARI FAILURE.The ATWS-ARI SYS A switch was placed in trip.ATWS-ARI SYS B Switch was overidden to AUTO TO PRECLUDE OPERATION and CRD-V-24B, 25B, 26B, 27B Failed As Is.Then ATWS-ARI-SYS B Switch placed to Trip.Subsequent System B response was noted.No ANN of F603-A8-3.1 and NO valves CRD-V-24B-27B changed position.P603-A7-3.1, ATWS-ARI SYS TRIP activated.
When ATWS-ARI-SYS A Switch placed in TRIP.System responses included: no scram lights were illuminated on the full core display, no rods had moved as indicated on the RSCS full core display, and all of the CRD ARI SYS B valves indicated closed.Proper response on activation of the ATWS/ARI FAILURE malfunction was tested and verified.INITIAL CONDITIONS:
IC-14 100%Power E<quilibrium Xenon.FINAL CONDITIONS:
IC-14 100%Power Equilibrium Xenon.SOURCE OF COMPARISON DATA: PLANT DATA SEI'NGINEERING EVALUATION FSAR SOER/LER g OPERATIONAL ASSESSMENT TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES pf OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Plant Malfunction TEST No.14.4.9.24.80 REV.3 TITLE: RPS FAILS TO SCRAM-CLF's: (RPS 25-RPS 32)D IRED RESP N E: This test is performed to demonstrate the functionality of the RPS FAILS TO SCRAM Malfunction.
The relay logic is shorted.A manual scram is initiated.
System alarms that did not initiate included: REACTOR SCRAM A1 AND B1 LOGIC, 1/2 SCRAM SYSTEM A, REACTOR SCRAM A2 AND B2 LOGIC, and 1/2 SCRAM SYSTEM B.All of the SCRAM Group Solenoid lights remained illuminated.
The Backup SCRAM lights remained extinguished.
The SDV vent and drain valves remained open.Proper response on activation of the RPS FAILS TO SCRAM malfunction was tested and verified.INITIAL CONDITIONS:
IC-14 100%Power Equilibrium Xenon.FINAL CONDITIONS:
IC-14 100%Power Equilibrium Xenon.SOURCE OF COMPARISON DATA: PLANT DATA SEI'NGINEERING EVALUATION FSAR 0 SOER/LBR g OPERATIONAL ASSESSMENT TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES
"~Ir~q OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Plant Malfunction TEST No.14.4.9.3.1 REV.3 TITLE: ROD DMFT-SLF: RMC4 CR 30-3l DRlFTS OUT IREDRE P N E: This test is written to demonstrate the functionality of the ROD DRIFT Malfunction.
A rod drifts out due to HCU 4 Valve Manifold Failure.System xesponses included: P603-A7-5-7 ROD DRIFT alarmed, the red Drift light on the full core display illuminated, F603-A7-5-7 ROD DRIFT alarm P603-A8-3.5, RBM UPSCL or INOP Alarms cleared when the rod is selected, the rod changed position on the four-rod display and the Rod Drift alarm annunciated when the next odd reed switch is activated, LPRM strings indicated a power increase on the 4 Rod Display, APRM's indicated an increase in power, and the full core display illuminated 48 when the xod xeach its final position.Pxoper response on activation of the ROD DRIFT malfunction was tested and verified.INITIAL CONDITIONS:
IC-14 100%Power with Equilibrium Xenon.FINAL CONDITIONS:
IC-14 100%Power with Equilibrium Xenon.SOURCE OF COMPARISON DATA: g PLANT DATA SET ENGINEERING EVALUATION FSAR SOER/LER g OPERATIONAL ASSESSMENT PowerPlex Data TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Plant Malfunction TEST No.14.4.9.3.2 REV.2 TITLE: STUCK ROD-SLF: RMC SA D IREDRE P N E This test is performed to demonstrate the functionality of the STUCK ROD Malfunction.
Air in the insert and withdraw lines of the CRD causes a stuck rod.The rod select matrix switch is illuminated and the blue background is on for the selected rod on the four rod display.The INSERT, WITH-DRAW, and SETTLE lights illuminated normally when attempting to withdraw a rod.System responses included: rod position remained constant, and rod did not change indicated position on the RDCS Four Rod display.Proper response on activation of the STUCK ROD malfunction was tested and verified.INITIAL CONDITIONS:
IC-14, 100%Power with Equilibrium Xenon.SOURCE OF COMPARISON DATA: PLANT DATA SBT BNGINBERING EVALUATION FSAR SOER/LER g OPERATIONAL ASSESSMENT TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES 0
OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Plant Malfunction TEST No.14.4.93.3 REV.3 TITLE: UNCOUPLED ROD-SLF: RMC 6A.D EDRE P E'his test is performed to demonstrate the functionality of the Uncoupled Rod Malfunction.
The coupling release handle for the rod becomes mechanically bound and the rod becomes uncoupled.
Subsequent control rod withdrawal is initiated resulting in the control rod being withdrawn to the overtravel position.System responses included: Proper response on activation of the STUCK ROD malfunction was tested and verified.Activation of F603-A7 8, ROD OVERTRAVEL and P603-A7-2.7, ROD OUT BLOCK verified.Proper RWM, RSCS and RDCS response verified.INITIAL CONDITIONS:
IC-3 approximately five (5)rods from critical.FINAL CONDITIONS:
IC-3 approximately five (5)rods from critical.SOURCE OF COMPARISON DATA: P PLANT DATA SET ENGINEERING EVALUATION FSAR SOER/LER g OPERATIONAL ASSESSMENT TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES QX TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES h II 1 0 OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Plant Malfunction TEST No.14.4.99.4 REV.4 TITLE: SINGLE ROD SCRAM-SLY: RMC 7A IREDRE P N E'his test is perfoxmed to demonstxate the functionality of the SINGLE ROD SCRAM Malfunction.
Blown fuses cause a single rod SCRAM (rod 34-31).System responses included: P603-A7-6-7 ACCUMULATOR TROUBLE alarmed, P603-A7-5-7 ROD DRIFT alarmed, APRM's indicated a decxease in power, the scram light for the rod illuminated on the Ml core display, the ACCUM light for the rod illuminated on the full core display, and the FULL IN light for the rod illuminated.
The RSCS full core display indicated 00 and the four rod display for the affected xod is blank while the malfunction is active.The LPRM strings surrounding the rod showed a noticeable decrease in flux levels.Proper response on activation of the SINGLE ROD SCRAM malfunction was tested and verified.INITIAL CONDITIONS:
IC-14 100%Power with Equilibrium Xenon.FINAL CONDITIONS:
Power is less than 100%and MWE<less than 1150.SOURCE OF COMPARISON DATA: g PLANT DATA SEI'NGINEERING EVALUATION FSAR SOER/LER X OPERATIONAL ASSESSMENT PowerPlex Data TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACI'ORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Plant Malfunction TEST No.14.4.9.3.12 REV.4 TITLE: M'DRAULIC ATWS-SLF: 7A&7B at 100%Severity DESIRED RESPONSE: This test is performed to demonstrate the functionality of the HYDRAULIC ATWS Malfunction.
Proper response on activation of a Manual SCRAM without Control Rod insertion was tested and verified INITIAL CONDITIONS:
IC-14 100%Power with Equilibrium Xenon.FINAL CONDITIONS:
IC-14 100%Power with Equilibrium Xenon.SOURCE OF COMPARISON DATA: PLANT DATA SET ENGINEERING EVALUATION FSAR SOER/LER g OPERATIONAL ASSESSMENT TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES
~'
OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Plant Malfunction gS TEST No.14.4.99.13 REV.0 TITLE: DROPPED ROD DESIRED RESPONSE: Activation of the Stuck Rod and Uncoupled Rod during Reactor Start-up with subsequent withdrawal of drive inechanism by operator.Later the Stuck Rod malfunction is cleared and the contxol rod drops out of core.Rod Overtravel Annunciation verified as well as proper NI Control Board Indications and alarms as the Control Rod Free Falls out of core.INI'GAL CONDITIONS:
IC-3 SU Ongoing.SOURCE OF COMPARISON DATA: PLANT DATA SET ENGINEERING EVALUATION FSAR SOBR/LER X OPERATIONAL ASSESSMENT TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES QX TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIBS OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Plant Malfunction TEST No.14.4.93.6 REV.3 TITLE: RDCS I'AILURL-SLF<: RMC 3 D IREDRE PON E'his test is performed to demonstrate the functionality of the RDCS FAILURE Malfunction.
A xod select module generates a channel disagreement due to timer A Failure.System responses included: the ACTIVITY CONTROLS DISAGREE light illuminates on Reactor Control Console, and random indication on activity Control Unit input to,ROD DRIVE CONTROL SYSTEM ANALYZER on Panel P616.Proper xesponse on activation of the RDCS FAILURE malfunction was tested and verifie INITIAL CONDITIONS:
IC-14 100%Power.FINAL CONDITIONS:
IC-14 100%Power.SOURCE OF COMPARISON DATA: PLANT DATA SET ENGINEERING EVALUATION FSAR SOER/LER g OPERATIONAL ASSESSMENT TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST No.14.4.9.7.1 REV.4 TITLE'LADDING PERP'ORATION
-SLF: RCX l P 40 PINS D E R P NE" This test is performed to demonstrate the functionality of the CLADDING PERFORATION Malfunction.
Forty fuel pins experience cladding failure from PCI.System responses included: radiation levels on log radiation monitors for the main steam lines increased, counts on the off gas pre-treatment monitor increased, radiation level on carbon adsorber vault monitor increased, and the off gas post-treatment recorder increased.'NITIAL CONDITIONS:
IC-14 100%Power with Equilibrium Xenon.SOURCE OF COMPARISON DATA: PLANT DATA S EI'NGINEERING EVALUATION P FSAR SOER/LBR g OPERATIONALASSBSSMENT TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Plant Malfunction TEST No.14.4.9.7.2 TITLE: GROSS CLAD FAILURE-SLF'CX l REV.4 D EDRE P NE:: This test is performed to demonstrate the functionality of the GROSS CLAD FAILURE Malfunction.
System responses included: OG-RR-604 off gas pretreatment radiation increased, SJAE CONDSR RAD HI-HI alarmed at 1800mr/hr, SJAE CONDSR RAD HIGH alarmed at 2300 mr/hr.P603-A8-2-4 MSL RAD HIGH TRIP alarmed causing a half SCRAM and half MSL isolation.
F603-A7-2.4 MSL RAD HIGH TRIP alarmed causing a half SCRAM and half MSL isolation.
With the second MSL RAD HIGH TRIP and RX SCRAM and MSIV isolation occurred.NOTE: Details of the reactor SCRAM detailed in test 14.4.9.24.33, Details of the Turbine Trip are in test 14.4.9.24.31 INITIAL CONDITIONS:
IC-14 100%Power with Equilibrium Xenon, OG-V-45 is open.SOURCE OF COMPARISON DATA: PLANT DATA SET ENGINEERING EVALUATION FSAR SUER/LBR g OPERATIONAL ASSESSMENT TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES X TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Plant Malfunctions TEST No.14.4.9.24.31 REV.5 TITLE: MAIN TURBINE TRIP-SLF DI" H I D IREDRE P N E: This test is performed to demonstrate the functionality of the MAIN TURBINE TRIP malfunction..
Electronic malfunction.
System responses included: MAIN GENERATOR tripped, MAIN TURBINE tripped, Reactor Scrammed with RRC Pumps tripping to OFF.Multiple meter responses on F603, P840, P820, DEH Turbine Control, DEH Valve Test, BWR Control, TG-TR-SMT, and P800 occurred IAW with requirements listed in this test procedure.
MT Bypass valves and SRV Gp 1 opened to control RPV/P, ATWS/ARI, RPV/P trip initiated.
Multiple annunciators alarmed as listed in this test procedure.
The required heater dump valves opened and the required extraction non-return valves closed.The Tur-bine auxiliaries functioned properly during Turbine coastdown.
NOTE: Manual Scram evaluated in 14.4.9.24.33, Main Generator Trip evaluated in 14.4.9.13.1 INITIAL CONDITIONS:
IC-14 100%Power with Equilibrium Xenon.FINAL CONDITIONS:
Reactor has Scrammed, Main'Ihrbine has tripped.SOURCE OF COMPARISON DATA: g PLANT DATA SEI'ENGINEERING EVALUATION X FSAR X SOER/LER X OPERATIONAL ASSESSMENT 15.2.85-002, 01/01/85 TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES PX TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES
OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Transients TEST No.14.4.9.24.31A
'EV.0 TITLE;MAIN TURBINE TRIP FROM LT 30%-SI F: DEH 1 ED EP This test is performed to demonstrate the functionality of the MAIN TURBINE TRIP FROM LT 30%malfunction.
System responses included: MAIN GENERATOR tripped, MAIN TURBINE tripped, Multiple meter responses on P603, P840, P820, DEH 7urbine Control, DEH Valve Test, BWR Control, TG-TR-SMT, and P800 occurred IAW with requirements listed in this test procedure.
MT Bypass valves opened to control RPV/P.Multiple annunciators alarmed as listed in this test procedure.
The required heater dump valves opened and the required extraction non-return valves closed.The Turbine auxiliaries functioned properly during 7urbine coastdown.
Proper response on activation of the Main 7urbine Trip From LT 30%malfunction was tested and verified.NOTE: Main Generator Trip evaluated in 14.4.9.13.1 INH'IAL CONDITIONS:
IC-10, Adjusted Power to 28%.FINAL CONDITIONS:
Main Turbine has tripped, DEB controlling pressure with Bypass valves.SOURCE OF COMPARISON DATA: g PLANT DATA SET ENGINEERING EVALUATION X FSAR SOBR/LBR g OPERATIONAL ASSESSMENT PLANTS D.DOC 15.2.3 TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES X TBSTRESULTSSATISFACTORYWITHOUTDISCRBPANCIBS OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Transient TEST No.14.4.10.13 REV.4 TITLE: MAIN TURBINE TRIP from RATED CONDITIONS WIO BXPASS VALVES DESIRED RESPONSE: Main Turbine Trip, ByPass Valves fail to OPEN with resultant RPV Pressurization limited by SRV operation.
RPT Trip of RRC Pumps to 15 Hz and subsequent trip to OFF via 1076 psig setpoint.MS-RV-1A Setpoint failed to 930 psig which will cycle to Control RPV Press.FW alignment made to FCV 10A/10B and RPV/L restored to normal.INI'GAL CONDITIONS:
IC-14-100%Power Equilibrium Xenon.e FINAL CONDITIONS:
Reactor SD, MS-RV-lA controlling RPV/P and SU LCV controlling level via RFP Turbine 1A.SOURCE OF COMPARISON DATA: X PLANT DATA SEI'NGINEERING EVALUATION FSAR SOER/LBR g OPERATIONAL ASSESSMENT SCRAM,LER 8-TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACI'ORY WITHOUT DISCREPANCIES PERATIONAL REVIEW
SUMMARY
TEST CATEGORY Plant Malfunctions TEST No.14.4.9.13.1 REV.4 TITLE: MAIN GENI" RAI'OR mlP-SLY: GEN-l D IREDRE P N E'his test is performed to demonstrate the functionality of the MAIN GENERATOR TRIP Malfunction, The 86 lockout trip is actuated.Alarm responses included: Turbine Throttle Vlv Closure, Turbine Gov Vlv Fast Closure, Scram, Turb Trip Sol Energ, Tg Auto Stop Trip, Unit Primary Lockout Trip, Main Gen Lockout Trip, Main Gen Exciter Field Bkr Txip, and Oscillograph Started.System responses included: Recirc Pumps tripped to OFF due to ATWS (high RPV pressure)condition, TO-P-BOP started, Trip Circuit Available light out, (throttle, governor, reheat stop, and intercept) valves closed, turbine speed decreased, generator MWE output is zero, bypass valves controlled DEB pressure, turbine drains opened, MSR temperature control valves shut, (86XU, 86XIU,&86G)tripped, Generator output bkxs opened, N bkr's opened, S bkr's shut, Generator parametexs were sat, non-xeturn valves closed, and dump valves opened.Proper response on activation of the Main Generator Trip malf was tested and verified.INI'GAL CONDITIONS:
IC-14 100%Power with Equilibrium Xenon FINAL CONDITIONS:
Main Generator tripped, Reactor Scrammed.NOTE: Refer to 14.4.9.24.33 for SCRAM details.SOURCE OF COMPARISON DATA: PLANT DATA SEI'NGINEERING EVALUATION g FSAR g SOER/LER g OPERATIONAL ASSESSMENT 15.2.2 85-002,85-003 TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACI'ORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Plant Malfunction TEST No.14.4.9.23.3 REV.5 TITLE;DEH PRESS REGULATOR OUTPUT FAILURE HIGH-SLF: DEH S D RED R P E: This test was performed to demonstrate the functionality of the DEH PRESS REGULATOR OUTPUT FAILURE HIGH Malfunction.
Circuit failure cause controller high signal select circuit to fail high.System responses included: governor valves full open, Generator output increased, and Reactor press decreased rapidly.The following annunciators alarmed: MSL PRESS LOW, MSIV HALF TRIP SYSTEM B, MSIV HALF TRIP SYSTEM A, and MSL ISOL VLVS CLOSURE TRIP.The MSIV's all closed.Proper response on activation of the DEH Press Regulator Output Failure Low was tested and verified.NOTE: Reactor Scram evaluated in 14.4.9.24.33 Turbine Trip evaluated in 14.4.9.24.31 INI'HAL CONDITIONS:
IC-12 100%Power Equilibrium Xenon FINAL CONDITIONS:
Reactor Scrams on MSIV closure.SOURCE OF COMPARISON DATA: g PLANT DATA SEI'NGINEERING EVALUATION g FSAR SUER/LER X OPERATIONAL ASSBSSMBNT PAT 22 15.1.3 TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCRBPANCIBS
OPERATIONAL REVlEW
SUMMARY
TEST CATEGORY: Plant Malfunction TEST No.14.4.9.23.3A REV.I TITLE: DEH PRESS REGULATOR OUTPUT FAILURE LOW-SLF: DEH 5 D I EDREP E This test is performed to demonstxate the functionality of the DEH PRESS REGULATOR OUTPUT FAILURE LOW Malfunction.
Circuit failure cause PRESS REGULATOR OUTPUT to go low, due to HSS Circuit internal failure.System responses included: governor valves go fuH shut, Turbine/Generator trips off-line, bypass valves are full closed, reactox pressure is increasing, appropriate alarms occur, Rx scxams on high Neutron Pwx, and SRV's control pressure.Proper response on activation of the DEH Press Regulator Output Failure Low was tested and verified.INITIAL CONDITIONS:
IC-14 100%Power Equilibrium Xenon SOURCE OF COMPARISON DATA: PLANT DATA SET ENGINEERING EVALUATION FSAR g SOBR/LBR QX OPERATIONAL ASSESSMENT TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACI'ORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Plant Malfunction TEST No.14.4,9.24.40 REV.3 TITLE: TURBINE BYPASS VALVE (BPV-l)FAILURE-SLF: DEH l3A D I D NE'his test is performed to demonstrate the functionality of the TURBINE BYPASS VALVE (BPV-1)FAILURE Malfunction.
Thermal binding results in valve seizure.Test is activated by going to BPV MANUAL and depressing the BPV RAISE at the BWR DEB panel on P820.System responses included: BPV TRACK decreased, BPV-1 position remained at zero, BPV-(2,3,4) opened, MWE on DEB TURBINE CONTROL decreased, BPV-(2,3,4) open lights energized, and BPV-1 closed light remained'energized.
The Governor valve additive position decreased and the GV's closed to maintain setpoint pressure.INITIAL CONDITIONS:
IC-14 100%Power Equilibrium Xenon.FINAL CONDITIONS:
BPV's-(2,3,4) are open, BPV-I is shut, MWE has decreased.
SOURCE OF COMPARISON DATA: PLANT DATA SBT ENGINEERING EVALUATION FSAR X SOER/LER X OPERATIONAL ASSESSMENT 4-56 4-044 4-1 4 TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES OPERATlONAL REVIEW
SUMMARY
TEST CATEGORY: Transients TEST No.14.4.9.24.33 REV.5 TITLE: MANUAL SCRAM REDR P N E'his test is performed to demonstrate the functionality of the MANUAL SCRAM Malfunction.
Plant responses included: All control rods inserted as indicated by (Full Core Display, RSCS,&PPCRS), RPS (A&B)Scram Group Solenoid lights extinguished, Flow/APRM/Rbm
&Rbm/APRI+Vlow Status lamps indicated downscale, Lvl Setpoint/Setdown light lit, and CRD-V-(10/180,11/181) closed.The response of multiple (meters, recorders,&devices)is IAW the test procedure.
Multiple annunciators listed in the test alarmed correctly.
Simulator Data Set 9-24-33 is compared to Plant Data Set SCRAM LER 89-35.Proper response on activation of the MANUAL SCRAM malfunction is tested and verified.INK'IAL CONDITIONS:
IC44, Adjusted Aow to 100%using FCV's.FINAL CONDITIONS:
Reactor Scrammed, BOP shutdown in progress.SOURCE OF COMPARISON DATA: g PLANT DATA SEI'NGINEERING EVALUATION FSAR BOER/LBR g OPERATIONAL ASSESSMENT SCRAMLER 90-021 85-016 TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACI'ORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Plant Malfunction TEST No.14.4.9.2.3 REV.3 TITLE: FEEDWATER LINE BREAK IN DRFWELL-SLF: CFW 9A EDR P E This test is performed to verify the Simulators response to a Feedwater Line Break in the DW on Reactor Side of the inboard check valves.The DW/P response is verified to initiate a Reactor Scram with subsequent NS4 and ECCS initiations.
The RRC pump trip to 15 hz via RPV/L 3 signals is verified.The isolation of the MSIV's is verified to occur on low RPV/P.The subsequent RPV/P increase is verified to trip the RRC pumps oK via ATWS logic.The SRV's are verified to control RPV/P at setpoint.The RFP's are verified to coast down as HP and LP steam sources expended.HPCS-V-4 is verified to auto close at RPV/L 8.Condensate Flow is verified to continue with a subsequen DW/P reduction as FW/I'ecreased.
~: Scram details evaluated in detail in 14.4.9.24.33, MT Trip details evaluated in 14.4.9.24.31, Main Gen Trip details evaluated in 14.4.9.13.1, MSIV Isolation details evaluated in 14.4.10.3.
Proper Annunciation response was verified, INITIAL CONDITIONS:
IC-14 100%Power Equilibrium Xenon FINAL CONDITIONS:
Reactor Shutdown with RPV/P control via SRV's with the Primary Con-tainment isolation complete.Condensate Flow continuing via the break cooling the DW SOURCE OF COMPARISON DATA: PLANT DATA SEI'NGINEERING EVALUATION FSAR SUER/LER X OPERATIONAL ASSESSMENT TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACI'ORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
REV.5 TEST CATEGORY: Plant Malfunction TEST No.14.4.9.2.8 TITLE: FEEDWATER LINE BREAE IN TURBINE BUILDING-SLF: CF W 5 EDRE P N This test is performed to verify Simulator response to RFW line break in Turbine Building.RFW Header Pressure decreases, RPV/L decreases initiating Rx SCRAM and RRC Pump Trip to 15Hz.RFW pumps accelerate to runout conditions and trip on low suction pressure.Condensate Booster Pumps trip on low suction pressure when condenser level decreases such that condensate pumps cannot maintain CBP suction pressure.RPV Level decreases to RPV LVL 2 with subsequent HPCS and RCIC Auto Start and NS4 Isolation.
Turbine Building temperatures increase.Proper Annunciation response was verified.INITIAL CONDITIONS:
IC-14 100%Power Equilibrium Xenon FINAL CONDITIONS:
Reactor has scrammed, Turbine Bldg.Temp.increases, RPV Level increases, LVL 8 RCIC-V-45A
&HPCS-V-14 shut.SOURCE OF COMPARISON DATA: PLANT DATA SEI'ENGINEERING EVALUATION g FSAR SUER/LER g OPERATIONAL ASSESSMENT TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCRBPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Plant Malfunction TEST No.14.4.9.21.4 TITLE: MAIN STEAM RUPTURE IN DRYWALL-SLY: RRS 3C (DOWNSTRFAM OF FLOW RES TRICTORS)REV.5 DESIRED RESPONSE: This test was pexformed to vexify the Simulators xesponse to a Main Steam Line Rupture in the Drywell.The DW/P increase initiation of Reactor Scxam, NS4 Isolation and RRC FCV lockup were verified.The RRC pump txip to 15 Hz via RPV/L 3 signals was verified.The initiation of the RPV/L 2 NS4 isolation, HPCS initiation, and RRC pumps tripping to off were verified and evaluated.
DG 1, 2&3 and HPCS initiation were vexified.DW/P response and subsequent WW/P response are verified as the DW/P overcomes downcomer submergence.
CBP injection and subsequent RPV/L restoration, with DW cooling via break verified.Note: Scram details evaluated in detail in 14.4.9.24.33, MT Trip details evaluated in 14.4.9.24.31, Main Gen Trip details evaluated in 14.4.9.13.1, NS4 Isolation at RPV/L 2 evaluated in 14.4.9.2.3 RFW Break in DW.Proper Annunciation response was verified.INITIAL CONDITIONS:
IC-14 100%Power E<quilibrium Xenon FINAL CONDITIONS:
Reactor Shutdown with RPV/L GT the MSL 110 inches.Primary Containment Isolation complete via NS4 isolation SOURCE OF COMPARISON DATA: PLANT DATA SEI'NGINEERING EVALUATION X FSAR P SOER/LBR X OPERATIONAL ASSESSMENT 15.6.5 6.2.1.1.3.b TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES Q TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RBSULTS SATISFACI'ORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Plant Malfunction TEST No.14.4.9.21.5A REV.1 TITLE: MAIN STEAM RUPTURE IN TURBINE BUII DING-SLF: RRS SC DESIRED RESPONSE: This test is performed to verify the Simulators response to a Main Steam Line Rupture in the Turbine Building.The RRC pump trip to 15 Hz and Reactor Scram initiation via RPV/L 3 signals is verified.The isolation of the MSIV's is verified to occur on low RPV/P or MSL'IGH FLOW.The subsequent RPV/P increase or RPV/L decrease is verified to trip the RRC pumps to off via ATWS logic.The SRV's were verified to control RPV/P at setpoint.Note: Scram details evaluated in detail in 14.4.9.24.33, MT Trip details evaluated in 14.4.9.%.31, Main Gen Trip details evaluated in 14.4.9.13.1, MSIV Isolation details evaluated in 14.4.10.3.
Proper Annunciation response was verified.INI'IIAL CONDITIONS:
IC-14 100%Power Equilibrium Xenon.FINAL CONDITIONS:
Reactor Shutdown with RPV/P control via SRV's.SOURCE OF COMPARISON DATA;PLANT DATA SET ENGINEERING EVALUATION X FSAR SOER/LBR X OPERATIONAL ASSESSMENT 15.6.4 TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES 1 g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Plant Malfunction TEST No.14.4.9.21.6 REV.3 TITLE: RUPTURE IN STEAMLINE DOWlVSTRZAM RCIC-V-45-SLF RCI4 IRED E P N E'his test is performed to demonstrate the functionality of the RCIC STEAMLINE BREAK AT TURBINE.RCIC Steam Line break between RCIC-V-45 and RCIV-V-2.System xesponses included: (RCIC TURBINE TRIP, RCIC STEAM LINE INTEGRITY DP HIGH, RCIC DIV1 OUT OF SERVICE, RCIC TURBINE STEAM SUPPLY PRESS LOW, and others)alarmed, RCIC-V-(S, 63, 1)closed, and Turbine Coasts to a stop.RCIC xoom xadiation levels increased and RCIC room temperatures increased.
Propex response on activation of the RCIC STEAMLINE BREAK AT TURBINE malfunction was tested and verified.INEHAL CONDITION:
IC-14 100%Power Equilibrium Xenon, RCIC in II'ull Flow Test to CST.SOURCE OF COMPARISON DATA: PLANT DATA SEI'NGINEERING EVALUATION FSAR SOER/LER X OPERATIONAL ASSESSMENT TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TBST RESULTS SATISFACTORY WITH DISCREPANCIES X TEST RBSULTS SATISFACTORY WITHOUT DISCREPANCIES tl
OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Plant Malfunction TEST No.14.4.9.14.1 REV.2 TITLE: SRM A FAILURE-LOS'SLF: NIS lA D EDRE P E: Tliis test is performed to demonstrate the functionality of the SRM A FAILURE-LOW Malfunction.
SRM MONITOR DOWNSCALE, P603-A7-6.6 and ROD OUT BLOCK, F603-A7-2.7 verified.SRM count rate and period downscale indications verified on P603 and P609 on SRM DRAWER.Proper response on activation of SRM-A failing low was tested and verified.INITIAL CONDITIONS:
IC-3, 5 Rods from critical FINAL CONDITIONS:
IC-3, 5 Rods from critical SOURCE OF COMPARISON DATA: Q PLANT DATA SBT ENGINEERING EVALUATION FSAR SOER/LER g OPERATIONAL ASSESSMENT TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES
+vq~,",s<
OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Plant Malfunction TEST No.14.4.9.14,2 REV.3 TITLE: APRM D FAILS UPSCALE-SLF: NIS SA p OPT 2 D IREDR P N E;This test is performed to demonstrate the functionality of the APRM A FAILS UPSCALE Malfunction.
Malfunction in the averaging circuit.Alarm responses included: APRM UPSCALE, APRM ACE UPSCL TRIP or INOP, ROD OUT BLOCK, NEUTRON MONITOR SYSTEM TRIP, and 1/2 SCRAM SYSTEM A.APRM A UPSC TR OR INOP and UPSC ALARM lights illuminated on P603.System responses included: APRM A read upscale on IRM-LR-603B, APRM A is upscale on F608, UPSCL (Therm Trip, Alarm, Neut Trip, Neut First)lights illuminated on P608, RPS A logic scram group solenoid lamps extinguished on P603, RPS A SCRAM GP 1A Solenoid lights extinguished and the Backup Scram Valve Solenoid Lights for RPS A logic illuminated.
Proper response on activation of APRM A Fails Upscale malfunction is tested and verified.INITIAL CONDITIONS:
IC-14 100%Power with Equilibrium Xenon.FINAL CONDITIONS:
100%Power, 1/2 SCRAM RPS A.SOURCE OF COMPARISON DATA: PLANT DATA SEI'NGINEERING EVALUATION FSAR SOER/LER g OPERATIONAL ASSESSMENT TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES QX TEST RESULTS SATISFACI'ORY WITHOUT DISCREPANCIES OPERATlONAL REVIEW
SUMMARY
TEST CATEGORY;Plant Malfunction TEST No.14 4.9.14.5 REV.2 TITLE: IRM INSTRUMENT FAILURE-HIGH-SLF: NIS 2A ES REDRE P E: This test is performed to demonstrate the functionality of the IRM INSTR.FAILURE-HIGH Malfunction.
IRM output amp shorted.The following annunciators alarmed: IRM ACEG UPSCL TRIP OR INOP, IRM MONITORS UPSCALE, ROD OUT BLOCK, NEUTRON MONITOR SYSTEM TRIP, and 1/2 SCRAM SYSTEM A.System responses included: IRM A indicated upscale on IRM-LR-603A, IRM A UPSC TR OR INOP light illuminated, IRM A UPSC ALARM light illuminated P603, IRM A upscale on IRM A drawer, UPSCALE ALARM light illuminated on F606.RPS A logic SCRAM group solenoid lamps extinguished.
Backup SCRAM valve solenoid lights for RPS A logic illuminated.
Proper response on activation of IRM Instr.Failure-High was tested and verified.INITIAL CONDITIONS:
IC-5 SOURCE OF COMPARISON DATA: PLANT DATA SET ENGINEERING EVALUATION FSAR SOER/LER I OPERATIONAL ASSESSMENT TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST No.14.4.9.14.8 TITLE: LPRM FAILURE-DOWNSCALE-SLF: NIS 8AA IRED RE E'his test is performed to demonstrate the functionality of the LPRM FAILURE-DOWNSCALE Malfunction.
The LPRM flux amplifier fails.System responses included: P603-A8-5-6 LPRM DOWN SCALE alarmed,24-33a DNSC light illuminated on the Full Core display, and LPRM%HEAT FLUX meter (bottom rt, A level)indicated downscale when rod 22-35 is selected.Proper response on activation of the LPRM FAILURE-DOWNSCALE malfunction was tested and verified.INITIAL CONDITIONS:
IC-14 100%Power with Equilibrium Xenon.FINAL CONDITIONS:
IC-14 100%Power with Equilibrium Xenon.SOURCE OF COMPARISON DATA: PLANT DATA SEI'NGINEERING EVALUATION FSAR SOER/LER g OPERATIONAL ASSESSMENT TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES
OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Plant Malfunction TEST No.14.4.9.9.4A REV.1 TITLE: RCIC TURBINE TRIP-CLF: NSSS>RCI (RCI 26'PTION 2)(RCI 28'PTION 2)DESIRED RESPONSE: This test is performed to demonstrate the functionality of the RCIC TURBINE TRIP DUE TO RCIC-V-8 CLOSURE CLF.The RCIC turbine tripped due to RCIC-V-8 failing closed.System responses included: RCIC-V-8 closed, RCIC TURBINE TRIP alarmed, Turbine (speed, exhaust pressure, flow, suction press, and discharge press)decreased, RCIC-V-(1 and 19)indicated closed, RCIC WATER LEG PUMP DISCH PRESSURE LOW, and RCIC LUBE OIL CLR WATER PRESSURE HIGH/LOW annunciators alarmed and cleared.Proper response on activation of the RCIC TURBINE TRIP due to RCIC-V-8 closure malfunction was tested and verified.INITIAL CONDITIONS:
IC-14 100%Power with Equilibrium Xenon, RCIC placed in Full Flow Test Mode CST to CST.FINAL CONDITIONS:
IC-14 100%Power, RCIC TURBINE has tripped.SOURCE OF COMPARISON DATA: PLANT DATA SET ENGINEERING EVALUATION FSAR SOER/LER g OPERATIONAL ASSESSMENT TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES X TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Plant Malfunction TEST No.14.4.9.24.43 REV.3 TITLE: ANNUNCIATOR FAILURE REDR N E: This test was performed to demonstrate the functionality of the Annunciator Failure Malfunction.
The failure to Annunciate malfunction is initiated with a subsequent system condition establish to initiate the associated Annunciator and its failure to activate was verified.INITIAL CONDITIONS:
IC-14 100%Power Equilibrium Xenon.FINAL CONDITIONS:
IC-14 100%Power Equilibrium Xenon.SOURCE OF COMPARISON DATA: PLANT DATA SEI'NGINEERING EVALUATION FSAR 0 SUER/LER g OPERATIONAL ASSESSMENT TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES X TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: TEST No.14.4.9.24.67 REV.3 TITLE: RP'V/L TMP CHAlVNFL FAILURE HI: RRSI8 and RRS-2)DESIRED RESPONSE: This test is performed to demonstrate the functionality of the RRS malfunction type BST for MS-LIC-24B and MS-LIS-24D Option 2(trip).System responses included: RCIC-RLY-K68 (21/025)RCIC-V-45, ISOL RPV LEVEL HIGH energized and RCIC-V-45, Failed shut.Proper response on activation of the Malf (RRS18 and RRS 2)was tested and verified.INITIAL CONDITIONS:
IC-14 100%Power Equilibrium Xenon.FINAL CONDITIONS:
100%Power Equilibrium Xenon, RCIC-V-45 has Failed shut.SOURCE OF COMPARISON DATA: PLANT DATA SEI'NGINEERING EVALUATION FSAR SOER/LER X OPERATIONAL ASSESSMENT TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCRBPANCIBS TEST RESULTS SATISFACTORY WITH DISCREPANCIES X TEST RBSULTS SATISFACTORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Plant Malfunction TEST No.14.4.9.24.67B REV.1 TITLE: RFW-LI>>6068 FAILS DOWNSCALE-CLF: RRS<<83'PT 4)50%DESIRED RESPONSE: This test is performed to demonstrate the functionality of the RFW-LI-606B PAILS DOWNSCALE Malfunction.
Level Sensor C34-N004B Fails low.System responses included: RFW-LI-606B indicated downscale, P603-A8-2-8 RFW TURB Control Signal or Level Channel failure alarmed, and FWC sensor A is automatically selected.The RPV Level Control Channel is manually selected to Channel A.Proper response on activation of the RFW-LI-606B FAILS DOWNSCALE malfunction was tested and verified.INI'GAL CONDITIONS:
IC-14 100%Power Equilibrium Xenon FINAL CONDITIONS:
IC-14 100%Power Equilibrium Xenon SOURCE OF COMPARISON DATA: PLANT DATA SEI'NGINEERING EVALUATION FSAR g SUER/LER QX OPERATIONAL ASSESSMENT 5-16 TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RBSULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCRBPANCIBS l l OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Plant Malfunction TEST No.14.4.9.24.67C REV.1 TITLE: RFH'-DPTAB
-FAILS HIGH-CLF: RRS 83 EDRE P N E'his test is performed to demonstrate the functionality of the RFW-LI-606B PAILS HIGH Malfunc-tion.Level Sensor C34-N004B Fails high.System responses included: RPV Level HIGH/LOW ALERT alarmed, RPV high level channel B seal in amber light illuminated, RFWffURBINE RPV level high Trip alarmed, RFW-LI-606B indicated upscale, and RFW-LR-608 indicated upscale.RFW Level Control System, (RFW-LIC-600, RFW-SC-601A 8c 601B output demands decreased) causing both RFW Turbines to decrease in speed causing feedwater flow to decrease to less than steam flow and RPV/L to drop.At RPV level 3 a Rx SCRAM occurred.Proper response on activation of the RFW-LI-606B PAILS HIGH malfunction was tested and verifie.INITIAL CONDITIONS:
IC-14 100%Power Equilibrium Xenon.SOURCE OF COMPARISON DATA: PLANT DATA SEI'NGINBERING EVALUATION FSAR SOER/LER g OPERATIONAL ASSESSMENT TEST RESULTS: TEST RESULTS UNSATISPACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Malfunction Test TEST No.14.4.9.3.10 REV.3 TITLE: ROD WORTH MINIMIZER FAILS DESIRED RESPONSE: This test is performed to demonstrate the functionality of the ROD WORTH MINIIVIIZER FAILS Malfunction.
A parity check error causes the RWM to go INOP.System responses included: P603-A7-2.7 ROD OUT BLOCK alarmed, INSERT BLOCK and WITHDRAWN BLOCK lights illuminated on the (Reactor Control Console and on RWM Console).Proper response on activation of the Rod Worth Minimizer Fails malfunction was tested and verified.INITIAL CONDITIONS:
IC-9 HEAT UP e 850¹.FINAL CONDITIONS:
IC-9 HEAT UP e 850¹.SOURCE OF COMPARISON DATA: PLANT DATA SBT ENGINEERING EVALUATION FSAR SOER/LER QX OPERATIONAL ASSESSMENT TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Plant Malfunction TEST No.14.4.9.9.2 REV.3 TITLE: LPCS SUCT LINE LEAEAT PUMP DESIRED RESPONSE: LPCS SUCflON LINE BREAK results in RB FD R4 Level alarms, isolation of FDR-V-109, LPCS Room Hi Level'alarm, SP/L Low alarm, and'LPCS Pump Trip on overload when LPCS Pump Room Level shorts out pump, with assocaiated annunciation.
INI'TIAL CONDITIONS:
IC-14 100%100%Power with Equilibrium Xenon, LPCS Pump in Full Flow test to Suppression Pool.FINAL CONDITIONS:
IC-14 100%100%Power with Equilibrium Xenon, LPCS Pump Tripped and Low Suppression Pool Water Level.SOURCE OF COMPARISON DATA: PLANT DATA SET ENGINEERING EVALUATION FSAR SOER/LER X OPERATIONAL ASSESSMENT TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES X TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES
OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Plant Malfunction TEST No.14.4.9.24.37 REV.3 TITLE: HPCS-VA FAILS THERMAL OVERLOAD-CLF: CSS7-OPT 6 IREDRE P E'his test is performed to demonstrate the functionality of the HPCS-V-4 FAILS OPEN Malfunction.
Thermal binding results in valve seizure.HPCS system is initiated.
Once HPCS-V-4 is open the mal-function is initiated.
System response included: HPCS-V-4 did not close after placing manual switch in closed position and it did not close after receiving a close signal on a Reactor high level of 54.5".Proper response on activation of the HPCS-V-4 Fails Open was tested and verified.INITIAL CONDITIONS:
IC-14 100%Power Equilibrium Xenon.FINAL CONDITIONS:
Reactor Scrammed, RFW and MT Tripped at RPV/L 8, DEH Controlling RPV/P via MT ByPass Valves.SOURCE OF COMPARISON DATA: PLANT DATA SET ENGINEERING EVALUATION FSAR SOBR/LBR X OPERATIONAL ASSESSMENT TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIBS g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES II I t I It OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Plant Malfunction TEST No.14.4.9.25.2 REV.I TITLE: RHR-P-2B SHAFT SHEAR-CLF: NSSSP RHR DESIRED RESPONSE: This test is performed to demonstrate the functionality of the RHR-P-2B, Shaft Shear Malfunction.
System responses included: RHR-P-2B AMPS decreasing, RHR-P-2B Flow decreasing, RHR-P-2B Discharge Pressure decreasing and appropriate annunciators alarmed.Proper response on activation of malfunction RHR-P-2B Shaft Shear was tested and verified INITIAL CONDITIONS:
IC-14 100%Power with Equilibrium Xenon, RHR-P-28 in Full Flow Test at rated flow.FINAL CONDITIONS:
IC-14 100%Power with Equilibrium Xenon, RHR-P-2B sheared shaft.SOURCE OF COMPARISON DATA: PLANT DATA SET ENGINBBRING EVALUATION FSAR SOER/LER g OPERATIONAL ASSESSMENT TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACI'ORY WITH DISCREPANCIES g TEST RESULTS SATISFACI'ORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST No.14.4.9.25.5 REV.I TITLE: RHR-P-2A TRIP-Select CLF: NSSS, RHR MOTOR, RHR I IRED R P E This test is performed to demonstrate the functionality of the RHR-P-2A Malfunction.
RHR-P-2A Trip on overload due to electrical fault.System responses included: RHR-P-2A AMPS icreased to trip point and then decreased, RHR-P-2A Flow and Discharge Pressure decreased, switch lights indicated pump tripped, and appropriate annunciators alarmed.Proper response on activation of malfunction RHR-P-2A TRIP was tested and verified.INITIAL CONDITIONS:
IC-14 100%Power with Equilibrium Xenon, RHR-P-2A in Full Flow Test at rated How.FINAL CONDITIONS:
IC-14 100%Power with Equilibrium Xenon, RHR-P-2A is tripped.SOURCE OF COMPARISON DATA;PLANT DATA SET ENGINEERING EVALUATION FSAR SOER/LER g OPERATIONAL ASSESSMENT TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACI'ORY WITHOUT DISCRBPANCIES
OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Plant Malfunction TEST No.14.4.9.25.19 REV.1 TITLE: RPS SPURIOUS SCRAM A-CLF: D RD P E'his test is performed to demonstrate the functionality of the RPS SPURIOUS SCRAM A Malfunction.
Spurious trip of RPS CH.A DIV I 1/2 SCRAM (due to trip of RPV HIGH PRESS switch).System responses included: RPV PRESS HI trip annunciator alarmed, 1/2 SCRAM SYS A annunciator alarmed, RPS A Logic Groups 1-4 SCRAM lights on panels P603 and P609 extinguished, and backup SCRAM, System A and System B Solenoid lights illuminate.
Proper response on activation of the RPS SPURIOUS SCRAM A malfunction was tested and verified.INITIAL CONDITIONS:
IC-14 100%Power with Equilibrium Xenon.SOURCE OF COMPARISON DATA: PLANT DATA SET ENGINEERING EVALUATION FSAR SUER/LER QX OPERATIONAL ASSESSMENT TEST RESULTS: Q TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACI'ORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Transient TEST No.14.4.10.11 REV.3 TITLE: 100%HYDRAULIC ATWS, WITH MSIV ISOL4TION Ii DESIRED RESPONSE: MSIV ISOLATION with all rods remaining Full Out.RPV Level reduction due to steaming rate GT Feed rate due to RCIC.HPCS disabled per EOP directions.
SLC Injection at 60 seconds and RPV/L reduction jointly decrease Reactor Power to APRMS DOWNSCALE within 6 minutes in accordance with ANF ATWS Analysis.SRV Operation controls RPV/P with time interval between successive SRV LIFTS increasing with time due to power reduction.
INITIAL CONDITIONS:
IC-14 100%Power Equilibrium Xenon.FINAL CONDITIONS:
SD due to CSD BORON Weight Injected via SLC at 43 minutes.SOURCE OF COMPARISON DATA: g PLANT DATA SET ENGINEERING EVALUATION FSAR SUER/LER X OPERATIONAL ASSESSMENT ANF ATWS Fl'nal fs TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES X TEST RESULTS SATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES OPERATIONAL REVIEW
SUMMARY
TEST CATEGORY: Plant Malfunction TEST No.14.4.9.24.63 REV.3 TITLE: DEH PUMP TRIP-CLF: DEH-P-IA)SHAFT SEIZURE ED This test is performed to demonstrate the functionality of the DEH PUMP 1A TRIP Malfunction.
Spurious breaker trip.System responses included: DEH-P-1A tripped, DEH HDR pressure decreased, appropriate annunciators alarmed, and the standby DEH-P-1B auto started at 1800 psig.Proper response on activation of the DEH-P-1A trip was tested and verified.INITIAL CONDITIONS:
IC-14 100%Power Equilibrium Xenon.SOURCE OF COMPARISON DATA: PLANT DATA SET ENGINEERING EVALUATION FSAR g SUER/LBR g OPERATIONAL ASSESSMENT 4-045-21 TEST RESULTS: TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RBSULTS SATISFACI'ORY WITHOUT DISCREPANCIES APPENDIX E WASHINGTON PUBLIC POWER SUPPLY SYSYTEM QUADRENNIAL TESTING Attachment E-1-Quadrennial Test Schedule
APPENDIX E Attachment E-1 WASHINGTON PUBLIC POWER SUPPLY SYSYTEM QUADRENNIAL TESTING LT Computer Spare Capacity Verification Test No.14.5.2-Simulator Computer Spare Capacity Test Steady-State Operation Tests Test No.14.4.3.1-1 Hour Stability Test No.14.4.4.1-100%SS Accuracy Test No.14.4.4.2-66%SS Accuracy Test No.14.4.4.3-40%SS Accuracy Test No.14.4.4.4-Cold Shutdown-BOC Benchmark Transient Tests Test No.14.4.7.1-Normal Plant Operations Test No.14.4.9.24.33
-Manual Scram Test No.14.4.10.5-Simultaneous Trip of All RFP's Test No.14.4.10.3-Closure of All Main Steam Isolation Valves Test No.14.4.10.6-Trip of All Recirculation Pumps Test No.14.4.9.24.34
-Recirculation Pump B Trip Test No.14.4.9.24.31A
-Main Turbine Trip from LT 30%Test No.14.4.8.4-Power Ramp from 100%PWR to 75%to 100%Test No.14.4.10.7-Maximum Size Reactor Coolant System Rupture w/Loss of Offsite Power Test No.14.4.10.9-Maximum Size Unisolatable MSL Rupture Test No.14.4.10.10
-MSIV ISOL with SRV Full Open 1 of5 APPENDIX E Attachment E-l WASHINGTON PUBLIC POWER SUPPLY SYSYTEM QUADRENNIAL TESTING Year 1 Normal Plant Evolutions 07.04.00.05.13
-Reactor Vx 8 Trip Valve Operability 07.04.01.03.01.02-Control Rod Exercise 07.04.03.07.04.01
-Remote Shutdown Panel Channel Check 07.04.04.07
-MSIV Closure Test 07.04.05.01.11
-HPCS System Operability Test 07.04.06.03.03
-Containment Isolation Valve Operability 07.04.06.05.03.01A
-Standby Gas Treatment Operability Test 07.04.07.09.01
-Weekly Bypass Valves Test 07.04.08.01.01.02.06-HPCS Diesel Generator-Loss of Power Test Malfunction Tests 14.4.9.18.3
-Instrument Line Break (Ref)14.4.9.8.3B
-Overcurrent SM-1 14.4.9.8.7-Loss of All Offsite Power 14.4.9.24.56
-Battery Charger C1-1 Trip 14.4.9.2.2-Condenser Air Leak 14.4.9.24.48A
-COND-P-1A Trip 14.4.9.21.1
-ADS Logic Failure 14.4.9.3.1
-Rod Drift 14.4.9.3.13
-Dropped Rod 14.4.9.24.31
-Main Turbine Trip 14.4.9.24.40
-BPV-1 Failure 14.4.9.24.33
-Manual Scram 14.4.9.21.5A
-MS Rupture In Turbine Bldg.14.4.9.14.5
-IRM Failure-High 14.4.9.24.67C
-RFW-L1-606B Fails High 14.4.9.25.5
-RHR-P-2A Trfp 14.4.9.25.19-RPS Spurious Scram A 14.4.9.24.63
-DEH Pump 1A Trip 2of5 APPENDIX E Attachment E-I WASHINGTON PUBLIC POWER SUPPLY SYSYTEM QUADRENNIAL TESTING Year 2 Normal Plant Evolutions 14.4.7.2.1
-Startup from Hot Shutdown to Rated Pressure 14.4.7.2.3
-SD to HSD 14.4.6.1-Core Reactivity/Shutdown Margin 14.4.6.3-Fission Product Poison Test 07.04.00.05.15
-CIA Valve Operability 07.04.03.08.02.01
-Monthly Turbine Valve Tests 07;04.06.01.04.02-MSIV Leakage Control System 07.04.06.04.01.02-Suppression Chamber-Dry Well Vacuum Breaker Operability 07.04.06.05.03.04A
-Standby Gas Treatment Manual Initiation Bypass Damper 8 Heater Test Malfunction Tests 14.4.9.18.6
-Instrument Line Break (Var)14.4.10.10-MSIV ISOL with SRV FO 14.4.9.8.4
-S1-2 DC Ground 14.4.9.8.8
-DG-2 Trip High Diff.Current 14.4.9.24.64A
-TSW Pump B Trip 14.4.9.24.78
-ATWS/ARI Failure 14.4.9.2.9
-RFPT B Trip 14.4.9.3.2-Stuck Rod 14.4.9.3.6
-RDCS Failure 14.4.9.13.1
-Main Generator Trip 14.4.9.21.6
-RCIC Steam Line Break at Turbine 14.4.9.14.8
-LPRM Failure-Downscale 14.4.9.9.4C
-RCIC Turbine Trip-(Mechanical Overspeed) 14.4.9.3.12-Hydraulic ATWS 14.4.9.23.3-DEH Press Reg.Output Failure High 14.4.9.24.27-Main Steam Safety Relief Valve Fails Open 14.4.9.24.37A
-HPCS-V-4 Fails to Open 14.4.9.25.2
-RHR-P-2B Shaft Shear 3of5 APPENDIX E Attachment E-l WASHINGTON PUBLIC POWER SUPPLY SYSYTEM QUADRENNIAI TESTING Year 3 Normal Plant Evolutions 14.4.6.5-SRM/IRM vs.Control Rod Motion 07.04.00.05.18 HPCS Service Water Operability/Demo 07.04.03.01.01.22-Manual SCRAM Function Test 07.04.05.01.05
-LPCS Valve Lineup/Ads Inhibit CFT 07.04.06.01.04.02A
-MSIV Valve Operability 07.04.06.05.02.01
-Reactor Building Ventilation Isolation Valve Operability 07.04.07.01.01.02-Standby Service Water Loop B valve Position Verification 07.04.08.01.01.01.02-18 Month Manual&Auto XFR Test, Start-Up to Backup Station Power 07.04.08.01.01.02.11
-Diesel Generator¹2-Operability Test Malfunction Tests 14.4.9.24.27-Main Steam Safety Relief Valve Fails Open 14.4.9.4.4-Leak Downstream Control Air Dryer 14.4.9.24.15
-S1-1 DC Ground 14.4.9.24.15A
-S1-1 Trip 14.4.9.24.34
-Recirculation Pump B Trip 14.4.9.24.64
-TSW Pump A Trip 14.4.9.24.5
-SW Pump A Trip 14.4.9.2.9
-RFPT A Trip 14.4.10.40-Loss of Normal and Emergency FW 14.4.9.24.80
-RPS Fails to SCRAM 14.4.9.3.3
-Uncoupled Rod 14.4.9.7.1
-Small Clad Fail 14.4.9.23.3-DEH Press Reg.Output Failure High 14.4.9.2.8
-FW Rupture in Turbine Bldg 14.4.9.14.1
-SRM A Failure-Low 14.4.9.9.4A
-RCIC Turbine Trip Due to RCIC-V-8 Closure 14.4.9.24.43
-Annunciator Failure 4 of 5
APPENDIX E Attachment E-1 WASHINGTON PUBLIC POWER SUPPLY SYSYTEM QUADRENNIAL TESTING Normal Plant Evolutions 07.04.00.05.06-EDR, FDR, RRC, MS 8 RRC Valve Ops 07.04.01.03.01.01
-Scram Discharge Volume Vent 8 Drain Valves Operability 07.04.03.06.09
-SDV Bypass Rod Block 07.04.05.01.06
-HPCS Valve Lineup 07.04.06.02.02.01
-RHR Valve Position Verification 07.04.08.01.01.02.01
-Diesel Generator ff1-Operability Test 07.04.08.01.01.02.12-HPCS Diesel Generator-Operability Test Malfunction Tests 14.4.9.2.3
-Feed Line Break in DW 14.4.9.25.14
-SRV's-Fall Closed 14.4.9.8.3
-4160 Vac Bus Sm-7 Overcurrent 14.4.9.8.5
-6900 Vac Bus SH-6 OL-GND 14.4.9.24.18
-RPS B MG Set Trip 14.4.10.6-Trip of all Recirculation Pumps 14.4.9.25.15
-RCC-P-1A-Trip 14.4.9.24.73
-SW-V-2B Fails Closed 14.4.9.24.2-COND-P-2A Shaft Break 14.4.9.16.4
-HPCS Logic Failure 14.4.9.3.4
-Single Rod SCRAM 14.4.9.7.2
-Gross Clad Fail 14.4.9.23.3A
-DEH Press Reg.Output Fails Low 14.4.9.21.4A
-MS Rupture In DW 14.4.9.14.2
-APRM Failure 14.04.09.24.67B
-RFW-L1-606B
-Fails Low 5of5 0-