ML17291A569

Simulator Facility Certification.

ML17291A569
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Site:	Columbia
Issue date:	12/07/1994
From:	WASHINGTON PUBLIC POWER SUPPLY SYSTEM
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Download: ML17291A569 (316)

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WNP-2 SIMULATORCERTIFICATION 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 SIMULATORCERTIFICATION WASHINGTON PUBLIC POWER SUPPLY SYSTEM

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1. INTRODUCTION 1 1

~ Certification Approach 1.2 Simulator Application SIMULATORINFORMATION 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. SIMULATORDESIGN 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 10 4.2.1 Annual Testing 4.2.2 Quadrennial Testing

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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) 12 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 13 APPENDIX A - SIMULATORSCOPE DIAGRAMS A-1WNP-2 Simulator Scope APPENDIX B - SIMULATOR CRITICALPARAMETERS 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 - SIMULATORACCEPTANCE 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 - QUADRENNIALTESTING 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 the Supply System's commitment to quality training. It is the Supply System's intent as'ubstantiate to fully support its training program by making the most effective use of the simulator.

2.0 SIMULATORINFORMATION 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:

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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 willbe 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.

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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.

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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.

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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.

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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

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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.

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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

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using the guidance of Section 4. - Performance Criteria, of the Standard.

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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.

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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 willbe 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 Alloutstanding 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.

AllTR's willbe 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.

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APPENDIX A WASHINGTON PUBLIC POWER SUPPLY SYSTEM SIMULATORSCOPE DIAGRAMS Figure A-1 WNP-2 Simulator Scope

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C 750-GDS].T p TOUCH PAD DISPLAY P600 PROCESS RADIATIONMONITORS C750-GDS1-CRT CATH9DE RAY TUBE DISPLAY P601 BENCHBOARD BD-RAD-24 BD-RAD-22 C70-GDS2-Tp TOUCH PAD DISPLAY P602 BENCHBOARD BD-RAD-23 C70GDS2-CRT CATHODE RAY TUBE DISPLAY P603 BENCH BOARD BD 'Y'D BD 'GIP VT2 TO VT5 PPCRS COLOR GRAPHIC TERMINALS P604 PROCESS RADIATIONMONITORS P606 R PS-A / RADIATION MONITO

'V'835 F831 BD P833- a PPCRS-A1 &A2 PPCRS ALARM PRINTERS a BD 'Gl' BD 'P-. 'T'832 H22.P100 P607 TIP CONTROL & MONITOR REMOTE SHUTDOWN P841 P842 C61-P001 P608 POWER RANGE NEUTRON MONITOR REMOTE SHUTDOWN ARC-A RELAY CABINET P609 TRIP SYSTEhl 'A'pS CMSCP BD 'M'D'P'301 CMS Cp 1401 RC-1 RELAY CABINET

'U TPJp SYSTEM B RPS BD'KII'D'R'D'H'D'J'828 RC-B RELAY CABINET F611 ARC-A F824 00

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~ P P811 P812 P818 P814 RC-B ARC-B RELAY CABINET I

F612 PROC<<SI W'620A II II II BD F821 BD 'N'827 I I ARC-B RC-2 3 659 RELAY CABINET R D SEQU C CO 0 S 8 I F614 pROCE SS MISC. MONOITORS F825 ooo ]- P620B P628 P607B P607D C750-GD2 C750-MP1 DISPLAY TERMINAL2 MATRIX PRINTER OL POS D RC-2

'O C750.MP2 MATRIXPRINTER P618 DIVISION 8 RHR PUMPS 'B' 'C' P82 g 522 51]

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BD 'L Q K 0-CO]25] P607A P607C P 607 E FRTP-1 RRE REMOTE TRANSFER PANEL .P BD I- 0 co aa BENCHBOARD F621 REACTOR CORE ISOLATION COOLANT BOARD'A'OARD'B'OARD'C'OARD'D'RAPHIC BENCHBOARD P622 INBOARD ISOLATION VALVES MP 452 O BENCHBOARD P623 OUTBOARD ISOLATION VALVES o g P608 P607 P TEMPERATURESCANNER F625 HIGH PRESSURE CORE SPRAY 222 BOA O GEN& RANS PRO E ON F626 DIV. I FUEL POOL COOLING FPC-1 CONTAINMENTVENT & PURGE F627 DIV. II FUEL POOL COOIJNG FPC-2

'D'A P627 BOARD'H'OARD'J'OARD'KI'OARD CONTAINMENTMONITOR SYSTEM F628 AUTOMTC DEPRESSURIZATION SYSTEM SGT TRAIN A & CAC DIV 1 F629 I LPCI & RHR

'A'IVISION P609 P606 P1 P2 P3 F633 F611 a F631 PUMP'A'UTOMTC DEPRESSURIZATION SYSTEM SGT TRAIN B & CAC DIV 2 STRONG MOTION RECORDR/MET RECD P632 I LEAK DETECTION

'B'IVISION F626 0250 TMU / COOLING TOWER SYSTEMS P633 RPS-B / RADIATIONMOMTOR P62 P619 P622 'Kll'OARD'L'OARD'M'OARD'N'OARD'P'OARD'R'OARD'S'OARD RCC/SW SYSTEMS P634 RECIRCULATION CONTROL a CONTROL ROOM HVAC P642 DIVISION II LEAK DETECTION P629 P628 F632 P642 P618 REACTOR / RADWASTE BLDG HVAC F650 ATWS (AUTOMATICTRIP WITHOUT SCRAM)

P623 P613 P 631 ISOLATION VALVE& STAT LT DSPLY P672 OFF GAS T FEEDER WTR & HTRBYPASS DSPLY F673 AREA RADIATIONMONITORING MNSTREAM LEAKAGECRNTL SYSTEM. CNTRLS. RFT GOV 1A,B REACTOR FEED PUMP TURB CNTRL PNL F673 WETWELL MONITOR FCP RRE CONTROL PANEL

u. P612 P672 BOARD'W'OARD'V'OARD'Y'OARD'Gl'NALOG) BOARD RRE PROTECTION CABINET P614 P604 P600 P625 P FEEDWATER HTR LVLCONTOL FD P65 ARS ALTERNATE REMOTE SHUTDOWN PANEL (ATWS)

MP2 I A OG Cp-1301 H2/02 MONITOR

'S'601 V24A 002 A2 Cp-1401 H2/02 MONITOR FCP-2 VT4B MP1 A1 RRE CONTROL PANEL CONS LE FOP'D

'FCP'CP-1 DRWNG ]2%~ NI]5h]'hzmQam ANSTEC FILES SRO OPER.

APERTURE DESK VT2B CARO SHIFT RO H22.P100 MANAGER RO OPER. F602 Also Available on OFRCE OPER. DESK C61-P001 Aperture Card

+VTS DESK FRTP-1 ARS P603 BD 'C'800 BD 'B'820 BD 'A'840 GOY 1A LEGEND:

GOY 1B PARTIAL PANEL SIMULATED FULL SCOPE SIMULATION 920436.2 DECEMBER 1994 Figure A-1 2

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APPENDIX B WASHINGTON PUBLIC POWER SUPPLY SYSTEM STEADY STATE OPERATlON Attachment B-1 Critical Parameter Listing

APPENDIX B ATTACHMENTB-1 WASHINGTON PUBLIC POWER SUPPLY SYSTEM CRITICALPARAMETERS LISTING

~D~crigtjgn w arne P evince RPV FUEL ZONE LMS:044A MS-LR-615R APRM POWER CH A SNISAM'R(1) APRM-LI-603A APRM POWER CH B SNISAMTR(2) APRM-LI-603B APRM POWER CH C SNISAIvHR(3) APRM-LI-603C APRM POWER CH D SNISAMTR(4) APRM-LI-603D APRM POWER CH E SNISAIvKR(5) APRM-LI-603E APRM POWER CH F SNISAMTR(6) APRM-LI-603F GENERATOR LOAD TG;00MW DEH-RI-M06 IvMNTURB 1SI'TG PRESS PMS:020B MS-PI-20B TOTALSTEAM FLOW WFWCST RFW-FR-607R TOTAL FEED FLOW WFWCFT RFW-FR-607G STEAM FLOW LINE A PRF:803A RFW-FI-603A STEAM FLOW LINE B PRF:803B RFW-FI-603 B STEAM FLOW LINE C PRF:803C RFW-FI-603 C STEAM FLOW LINE D PRF:803D RFW-FI-603 D RPV NR LEVEL PRF:004A RFW-LR-608 RPV WR LEVEL BRRS51AR MS-LRPR623A RPV WR LEVEL BRRS51BR MS-LRPR623B RP PRESSURE WR PMS:005 RFW-PI-605 TOTAL CORE FLOW WRRS 613 MS-FR-613R RECIRC LOOP A FLOW WNISFA(1) RRC-FR-614R RECIRC LOOP B FLOW WNISFB(1) RRC-FR-614G RECIRC LOOP A SUCT TEMP TRR:023A RRC-TR-650R RECIRC LOOP B SUCI'TEMP TRR:023B RRC-TR-650G DRYWELLPRESSURE NR PCM:007 CMS-PR-1R DRYWELLPRESSURE NR PCM:008 CMS-PR-2R DRYWELLPRESSURE WR PCM:001 CMS-PR-1G DRYWELLPRESSURE WR PCM:002 CMS-PR-2G DRYWELLAVE TEMP WR TPCNDSUM(1) CMS-TR-5-110 DRYWELLAVE TEMP WR TPCNDSUM(2) CMS-TR-6-128 SUPPRESSION POOL LVLWR LCM:006A CMS-LR-3G SUPPRESSION POOL LVLWR LCM:006B CMS-LR-4R 1 of 3

APPENDIX B ATTACHMENTB-1 WASHINGTON PUBLIC POWER SUPPLY SYSTEM CRITICALPARAMETERS LISTING

~Descri rion Software Name Device SUPPRESSION POOL TEMP TPCNI41R CMS-TI-41AR SUPPRESSION POOL TEMP TPCNI43R CMS-TI-43R SUPPRESSION POOL PRESS PCM:004 CMS-PR-4R SUPPRESSION POOL PRESS PCM:003 CMS-PR-3R CONDENSER VACUUM PMS:008A MS-PI-8A CONDENSER VACUUM PMS:008B MS-PI-8B CONDENSER VACUUM PMS:008C MS-PI-8C REACTOR PRESSURE NR PMS:808 MS-PR/FR-609 AVION TURB GOV VLVPOS RDEHGV(1) MS-V-GV/1 MAINTURB GOV VLVPOS RDEHGV(2) MS-V-GV/2 MAINTURB GOV VLVPOS RDEHGV(3) MS-V-GV/3 MAINTURB GOV VLVPOS RDEHGV(4) MS-V-GV/4 MAINTURBINE SPEED MTG:00SD DEH-RI-M05 RFP SPEED MFT:001A RFT-SI-1A RFP SPEED MFT:001B RFT-SI-1B RFP SUCT PRESSURE PCD:028A COND-PI-28A RFP SUCT PRESSURE PCD:028B COND-PI-28B RFP DISCH PRESSURE PRF:001A RFW-PI-1A RFP DISCH PRESSURE PRF:001B RFW-PI-1B CBP DISCH PRESSURE PCD:016 COND-PI-16 MAINSTEAM LINE RAD ERMS JMI(1) MS-RIS-601A MAINSTEAM LINE RAD ERMS JMI(2) MS-RIS-601B MAINSTEAM LINE RAD ERMS JMI(3) MS-RIS-601C 1VL4dN STEAM LINE RAD ERMS JMI(4) MS-RIS-601D MSIV VLVPOSITION RMSH022A MS-V-22A MSIV VLVPOSITION RMSH022B MS-V-22B MSIV VLVPOSITION RMSH022C MS-V-22C MSIV VLVPOSITION RMSH022D MS-V-22D MSIV VLVPOSITION RMSH028A MS-V-28A MSIV VLVPOSITION RMSH028B MS-V-28B MSIV VLVPOSITION RMSH028C MS-V-28C MSIV VLVPOSITION RMSH028D MS-V-28D 2of3

APPENDIX B ATTACHMENTB-1 WASHINGTON PUBLIC POWER SUPPLY SYSTEM CRITICALPARAMETERS LISTING

~Descri tion Software Name Device SCRAM DISCH VOLUME LRD:012A CRD-LI-601A SCRAM DISCH VOLUME LRD:P12B CRD-LI-601B SCRAM DISCH VOLUME LRD:012C CRD-LI-601C SCRAM DISCH VOLUME LRD:012D CRD-LI-601D RX BLDG VENT HI RAD ERMSAPMI(2) REA-RIS-609A RX BLDG VENT HI RAD ERMSAPMI(3) REA-RIS-609B RX BLDG VENT HI RAD ERMSAPMI(4) REA-RIS-609 C RX BLDG VENT HI RAD ERMSAPMI(5) 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 SMULATORINITIALCONDITIONS RPV POWER CORE IC PRESS (%) DESCRIPTION AGE (degf)

(psig) 01 EOC 150 ATMOS Ready For Startup - XE Free 02 BOC 150 ATMOS SRM Ready for Startup - XE Free 03 BOC ATMOS 5 Rods Fm Critical 04 BOC 150 ATMOS 1-2 Heatup In Progress 05 BOC 340 100 1-2 Heatup In Progress 06 BOC 480 1-2 Heatup In Progress 07 BOC 535 920 1-2 Heatup In Progress 08 BOC TSAT PSAT 15 Turbine Ready To Latch 09 BOC TSAT PSAT 20 Turbine @ 1800 RDY To SYNC 10 BOC TSAT PSAT Ready to Shift RFW-FCV-10A/8 BOC TSAT PSAT 32 Ready To Xfer RRP to 60HZ 12 BOC TSAT PSAT 100% Rod Line Q 50% Core Flow 13 BOC TSAT PSAT 100 100% Power/Flow 14 BOC TSAT PSAT 100 100% Equilibrium Power/Flow 15 BOC TSAT PSAT 40 RDY To Xfer RRC Pumps to 15HZ 16 BOC TSAT PSAT 20 S/D In Progress 17 BOC TSAT 850 S/D In Progress - AllRods In 18 BOC 350 120 C/D In Progress 19 BOC ATMOS S/D Cooling In Progress 20 BOC 520 800 S/U In Progress @ PK Xenon 21 BOC 280 32 Ready to Start S/D Cooling 22 BOC ATMOS S/D Cooling In Progress-Low XE BOC 260 20 Ready To Start S/D Cooling BOC 100 ATMOS Cold S/D - Most Systems Secured 25 MOC 100 ATMOS Cold S/D - Most Systems Secured Page 1 of2

APPENDIX C ATTACHMENTC-1 WASHINGTON PUBLIC POWER SUPPLY SYSTEM SMULATORINITIALCONDITIONS continued RPV POWER CORE TEMP IC PRESS (%) DESCRIPTION AGE (d f)

(psig) 26 MOC 540 1000 100 100% Equilibrium Power/Flow 27 EOC 100 ATMOS Cold S/D - Most Systems Secured 28 EOC 540 1000 100 100% Equilibrium Power/Flow 29 EOC 125 ATMOS Refueling In Progress 30 EOC TSAT -1000 -95 105% Core Age - Coastdown 31 EOC 120 ATMOS 0 105% Core Age - Ready For S/U XE Free 32 EOC TSAT 850 S/D In Progress- AllRods In 33 EOC 467 500 S/D To HSD with MSIV's Closed 34 MOC 540 975 Heatup In Progress 35 MOC 150 ATMOS Ready To Startup - XE Free Page 2 of 2

APPENDIX C ATTACHMENTC-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID SYSTEM DESCRIPTION CAC-001 CAC CAC-FN-1A 0/C RESET CAC-002 CAC CAC-FN-1B 0/C RESET CAC-003 CAC CAC-EHC-1A 0/C RESET CAC-004 CAC CAC-EHC-1B 0/C RESET CAS-001 CAS CAS-V-152 AIR ISOL TO SERV BLDG CAS-002 CAS CAS-V-153 AIR ISOL TO TUR BLDG CAS-003 CAS CAS-V-154 AIR ISOL TO TUR BLDG CAS-004 CAS CAS-V-155 AIR ISOL TO RW BLDG CAS-005 CAS CAS-V-151 AIR ISOL TO RX BLDG CAS-006 CAS CAS-V-210 N2 ISOL TO VAC BKR CAS-007 CAS AIR DRYER SELECT A/B CAS-008 CAS CAS-V-97-55 CAS ISOL TO VAC BKR CAS-009 CAS CAS-C-1A RESET CAS-010 CAS CAS-C-1B RESET CAS-011 CAS CAS-C-1C RESET CAS-012 CAS SA-C-1 COMPRESSOR START/STOP CAS-013 CAS CAS-C-1A 0/C RESET CAS-014 CAS CAS-C-1B 0/C RESET CAS-015 CAS CAS-C-1C 0/C RESET CAS-016 CAS SA-C-1 0/C RESET CAS-017 CAS CN-V-761A BYPASS FOR CN-SPV-61 CAS-018 CAS CN-V-761B ISOL FOR CN-SPV-61 CAS-019 CAS CN-V-761C ISOLATIONBOTl LE CON.

CAS-020 CAS CN-V-765A BYPASS FOR CN-SPV-65 CAS-021 CAS CN-V-765B ISOL FOR CN-SPV-65 CAS-022 CAS CN-V-765C ISOL FOR BOTI'LE CON.

CFW-001 CFW COND-V-674 COND PCV-105 ISOL VLV CFW-002 CFW COND-V-672 COND-PCV-105 BYP VLV CFW-003 CFW COND-V-108 GS COND INLETVLV CFW-004 CFW COND-V-154 GS COND OUTLET VLV CFW-005 CFW COND-V-1062 FIRE WATER CROSS TIE CFW-006 CFW COND-V-107A CND PMP 1A DISCH VLV CFW-007 CFW COND-V-107B CND PMP 1B DISCH VLV CFW-008 CFW COND-V-107C CND PMP 1C DISCH VLV CFW-009 CFW COND-V-120A CND BST PMP DIS VLV CFW-010 CFW COND-V-120B CND BST PMP DIS VLV CFW-011 CFW COND-V-120C CND BST PMP DIS VLV CFW-012 CFW COND-V-161A SS-EV-1A LCV BP VLV CFW-013 CFW COND-V-161B SS-EV-1B LCV BP VLV CFW-014 CFW COND-V-76 CND DEMINBP VLV CFW-015 CFW COND-V-12A CST-1A FILLVLVOPEN CFW-016 CFW COND-V-12B CST-1B FILLVLVOPEN CFW-017 CFW COND-V-131 CND-LCV-1ABP VLV November 16, 1994 Page 1 of 51

APPENDIX C ATTACHMENTC-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID SYSTEM DESCRIPTION CFW-018 CFW COND-V-170 CND-LCV-1C BP VLV CFW-019 CFW COND-V-612 CND-LCV-11 BP VLV CFW-020 CFW COND-V-147A FW PMP 1A SUCl'LV CFW-021 CFW COND-V-147B FW PMP 1B SUCT VLV CFW-022 CFW COND-V-15A CST-A DISCH ISOL CFW-023 CFW COND-V-15B CST-B DISCH ISOL CFW-024 CFW COND-V-28 RHR C FLUSH CONN CFW-025 CFW COND-P-3 RB COND SUPPLY PMP ON CFW-027 CFW NUMBER OF DEMINERALIZERS CFW-028 CFW AR-V-3A,3B,3C COND VAC BRKRS CFW-029 CFW COND-P-1A 0/C RESET CFW-030 CFW COND-P-1B 0/C RESET CFW-031 CFW COND-P-1C 0/C RESET CFW-032 CFW COND-P-3 0/C RESET CFW-033 CFW COND-P-AOP1A 0/C RESET CFW-034 CFW COND-P-AOP1B 0/C RESET CFW-035 CFW COND-P-AOP1C 0/C RESET CFW-036 CFW MD-M-1A0/C RESET CFW-037 CFW MD-M-1B 0/C RESET CFW-038 CFW COND-V-9A COND-TK-1AISOLATION CFW-039 CFW COND-V-9B COND-TK-1B ISOLATION CFW-040 CFW COND-P-2A 0/C RESET CFW-041 CFW COND-P-2B 0/C RESET CFW-042 CFW COND-P-2C 0/C RESET CIA-001 CIA CIA-V-728 N2 INERT ISOL VLV CIA-002 CIA REFILL REMOTE STAT 1A CIA-TK-20A CIA-003 CIA REFILL REMOTE STAT 1B CIA-TK-20B CIA-004 CIA CIA-V-104AN2 BOTI'LE DISCH CIA-005 CIA CIA-V-104B N2 BOTI'LE DISCH CIA-006 CIA CIA-V-740 SUP HDR DNSM BLEED ISO CIA-007 CIA CIA-V-741 SUPPLY HDR BLEEDOFF CIA-008 CIA CIA-V-739 SUP HDR UPSM BLEED ISO CIA-009 CIA CAS-V-98-88 CAS SUPPLY TO CIA CRD-001 CRD CRD-FCV-2A LOCALVAR CTRL CRD-002 CRD CRD-FCV-2B LOCALVAR CIRL CRD-003, CRD CRD-FCV-2A M/A SELECTOR SWITCH CRD-004 CRD CRD-FCV-2B M/A SELECTOR SWITCH CRD-005 CRD CRD-V-4 DRV WTR PRESS STA BYP CRD-006 CRD CRD-V-13A P-1A SUCTION CRD-007 CRD CRD-V-13B P-1B SUCTION CRD-008 CRD CRD-V-14A P-1A DISCHARGE CRD-009 CRD CRD-V-14B P-1B DISCHARGE CRD-010 CRD CRD-V-20A DRV WTR FLTR 3A INLET November 16, 1994 Page 2 of 51

APPENDIX C ATTACHMENTC-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID SYSTEM DESCRIPTION CRD-011 CRD CRD-V-20B DRV WTR FLTR 3B INLET CRD-012 CRD CRD-V-21A DRV WTR FLTR 3A OUTLET CRD-013 CRD CRD-V-21B DRV WTR FLTR 3B OUTLET CRD-014 CRD CRD-V-34 CHARGING WTR HDR ISOLET CRD-015 CRD CRD-V-46A FCV-2A INLET ISOL VLV CRD-016 CRD CRD-V-46B FCV-2B INLET ISOL VLV CRD-017 CRD CRD-V-47A FCV-2A OUTLET ISOL VLV CRD-018 CRD CRD-V-47B FCV-2B OUTLET ISOL VLV CRD-019 CRD CRD-V-61 DRV WTR PRESS CNTRL OUT CRD-020 CRD CRD-V-95 SCRAM AIR HDR ISOL VLV CRD-021 CRD CRD-V-520 RWCU PMP MTR PURGE ISO CRD-022 CRD CRD-V-114 PMP SUCT FTR 10A OUTLT CRD-023 CRD CRD-V-115 PMP SUCT FTR 10A INLT CRD-024 CRD CRD-V-116 PMP SUCI'TR 10B OUTLT CRD-025 CRD CRD-V-117 PMP SUCT FLT 10B INLET CRD-026 CRD CRD-V-729 PI-13 ISOLATION CRD-027 CRD CRD-PI-13 VENT PLUG REMOVED CRD-028 CRD CRD-V-102 CR 1803 WD LINE VENT CRD-029 CRD CRD-V-102 CR 2203 WD LINE VENT CRD-030 CRD CRD-V-102 CR 2603 WD LINE VENT CRD-031 CRD CRD-V-102 CR 3003 WD LINE VENT CRD-032 CRD CRD-V-102 CR 3403 WD LINE VENT CRD-033 CRD CRD-V-102 CR 3803 WD LINE VENT CRD-034 CRD CRD-V-102 CR 4203 WD LINE VENT CRD-035 CRD CRD-V-102 CR 1407 WD LINE VENT CRD-036 CRD CRD-V-102 CR 1807 WD LINE VENT CRD-037 CRD CRD-V-102 CR 2207 WD LINE VENT CRD-038 CRD CRD-V-102 CR 2607 WD LINE VENT CRD-039 CRD CRD-V-102 CR 3007 WD LINE VENT CRD-040 CRD CRD-V-102 CR 3407 WD LINE VENT CRD-041 CRD CRD-V-102 CR 3807 WD LINE VENT CRD-042 CRD CRD-V-102 CR 4207 WD LINE VENT CRD-043 CRD CRD-V-102 CR 4607 WD LINE VENT CRD-044 CRD CRD-V-102 CR 1011 WD LINE VENT CRD-045 CRD CRD-V-102 CR 1411 WD LINE VENT CRD-046 CRD CRD-V-102 CR 1811 WD LINE VENT CRD-047 CRD CRD-V-102 CR 2211 WD LINE VENT CRD-048 CRD CRD-V-102 CR 2611 WD LINE VENT CRD-049 CRD CRD-V-102 CR 3011 WD LINE VENT CRD-050 CRD CRD-V-102 CR 3411 WD LINE VENT CRD-051 CRD CRD-V-102 CR 3811 WD LINE VENT CRD-052 CRD CRD-V-102 CR 4211 WD LINE VENT CRD-053 CRD CRD-V-102 CR 4611 WD LINE VENT November 16, 1994 Page 3 of 51

APPENDIX C ATTACHMENTC-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID SYSTEM DESCRIPTION CRD-054 CRD CRD-V-102 CR 5011 WD LINE VENT CRD-055 CRD CRD-V-102 CR 0615 WD LINE VENT CRD-056 CRD CRD-V-102 CR 1015 WD LINE VENT CRD-057 CRD CRD-V-102 CR 1415 WD LINE VENT CRD-058 CRD CRD-V-102 CR 1815 WD LINE VENT CRD-059 CRD CRD-V-102 CR 2215 WD LINE VENT CRD-060 CRD CRD-V-102 CR 2615 WD LINE VENT CRD-061 CRD CRD-V-102 CR 3015 WD LINE VENT CRD-062 CRD CRD-V-102 CR 3415 WD LINE VENT CRD-063 CRD CRD-V-102 CR 3815 WD LINE VENT CRD-064 CRD CRD-V-102 CR 4215 WD LINE VENT CRD-065 CRD CRD-V-102 CR 4615 WD LINE VENT CRD-066 CRD CRD-V-102 CR 5015 WD LINE VENT CRD-067 CRD CRD-V-102 CR 5415 WD LINE VENT CRD-068 CRD CRD-V-102 CR 0219 WD LINE VENT CRD-069 CRD CRD-V-102 CR 0619 WD LINE VENT CRD-070 CRD CRD-V-102 CR 1019 WD LINE VENT CRD-071 CRD CRD-V-102 CR 1419 WD LINE VENT CRD-072 CRD CRD-V-102 CR 1819 WD LINE VENT CRD-073 CRD CRD-V-102 CR 2219 WD LINE VENT CRD-074 CRD CRD-V-102 CR 2619 WD LINE VENT CRD-075 CRD CRD-V-102 CR 3019 WD LINE VENT CRD-076 CRD CRD-V-102 CR 3419 WD LINE VENT CRD-077 CRD CRD-V-102 CR 3819 WD LINE VENT CRD-078 CRD CRD-V-102 CR 4219 WD LINE VENT CRD-079 CRD CRD-V-102 CR 4619 WD LINE VENT CRD-080 CRD CRD-V-102 CR 5019 WD LINE VENT CRD-081 CRD CRD-V-102 CR 5419 WD LINE VENT CRD-082 CRD CRD-V-102 CR 5819 WD LINE VENT CRD-083 CRD CRD-V-102 CR 0223 WD LINE VENT CRD-084 CRD CRD-V-102 CR 0623 WD LINE VENT CRD-085 CRD CRD-V-102 CR 1023 WD LINE VENT CRD-086 CRD CRD-V-102 CR 1423 WD LINE VENT CRD-087 CRD CRD-V-102 CR 1823 WD LINE VENT CRD-088 CRD CRD-V-102 CR 2223 WD LINE VENT CRD-089 CRD CRD-V-102 CR 2623 WD LINE VENT CRD-090 CRD CRD-V-102 CR 3023 WD LINE VENT CRD-091 CRD CRD-V-102 CR 3423 WD LINE VENT CRD-092 CRD CRD-V-102 CR 3823 WD LINE VENT CRD-093 CRD CRD-V-102 CR 4223 WD LINE VENT CRD-094 CRD CRD-V-102 CR 4623 WD LINE VENT CRD-095 CRD CRD-V-102 CR 5023 WD LINE VENT CRD-096 CRD CRD-V-102 CR 5423 WD LINE VENT November 16, 1994 Page 4 of 51

APPENDIX C ATTACHMENTC-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID SYSTEM DESCRIPTION CRD-097 CRD CRD-V-102 CR 5823 WD LINE VENT CRD-098 CRD CRD-V-102 CR 0227 WD LINE VENT CRD-099 CRD CRD-V-102 CR 0627 WD LINE VENT CRD-100 CRD CRD-V-102 CR 1027 WD LINE VENT CRD-101 CRD CRD-V-102 CR 1427 WD LINE VENT CRD-102 CRD CRD-V-102 CR 1827 WD LINE VENT CRD-103 CRD CRD-V-102 CR 2227 WD LINE VENT CRD-104 CRD CRD-V-102 CR 2627 WD LINE VENT CRD-105 CRD CRD-V-102 CR 3027 WD LINE VENT CRD-106 CRD CRD-V-102 CR 3427 WD LINE VENT CRD-107 CRD CRD-V-102 CR 3827 WD LINE VENT CRD-108 CRD CRD-V-102 CR 4227 WD LINE VENT CRD-109 CRD CRD-V-102 CR 4627 WD LINE VENT CRD-110 CRD CRD-V-102 CR 5027 WD LINE VENT CRD-111 CRD CRD-V-102 CR 5427 WD LINE VENT CRD-112 CRD CRD-V-102 CR 5827 WD LINE VENT CRD-113 CRD CRD-V-102 CR 0231 WD LINE VENT CRD-114 CRD CRD-V-102 CR 0631 WD LINE VENT CRD-115 CRD CRD-V-102 CR 1031 WD LINE VENT CRD-116 CRD CRD-V-102 CR 1431 WD LINE VENT CRD-117 CRD CRD-V-102 CR 1831 WD LINE VENT CRD-118 CRD CRD-V-102 CR 2231 WD LINE VENT CRD-119 CRD CRD-V-102 CR 2631 WD LINE VENT CRD-120 CRD CRD-V-102 CR 3031 WD LINE VENT CRD-121 CRD CRD-V-102 CR 3431 WD LINE VENT CRD-122 CRD CRD-V-102 CR 3831 WD LINE VENT CRD-123 CRD CRD-V-102 CR 4231 WD LINE VENT CRD-124 CRD CRD-V-102 CR 4631 WD LINE VENT CRD-125 CRD CRD-V-102 CR 5031 WD LINE VENT CRD-126 CRD CRD-V-102 CR 5431 WD LINE VENT CRD-127 CRD CRD-V-102 CR 5831 WD LINE VENT CRD-128 CRD CRD-V-102 CR 0235 WD LINE VENT CRD-129 CRD CRD-V-102 CR 0635 WD LINE VENT CRD-130 CRD CRD-V-102 CR 1035 WD LINE VENT CRD-131 CRD CRD-V-102 CR 1435 WD LINE VENT CRD-132 CRD CRD-V-102 CR 1835 WD LINE VENT CRD-133 CRD CRD-V-102 CR 2235 WD LINE VENT CRD-134 CRD CRD-V-102 CR 2635 WD LINE VENT, CRD-135 CRD CRD-V-102 CR 3035 WD LINE VENT CRD-136 CRD CRD-V-102 CR 3435 WD LINE VENT CRD-137 CRD CRD-V-102 CR 3835 WD LINE VENT CRD-138 CRD CRD-V-102 CR 4235 WD LINE VENT CRD-139 CRD CRD-V-102 CR 4635 WD LINE VENT November 16, 1994 Page 5 of 51

APPENDIX C ATTACHMENTC-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID SYSTEM DESCRIPTION CRD-140 CRD CRD-V-102 CR 5035 WD LINE VENT CRD-141 CRD CRD-V-102 CR 5435 WD LINE VENT CRD-142 CRD CRD-V-102 CR 5835 WD LINE VENT CRD-143 CRD CRD-V-102 CR 0239 WD LINE VENT CRD-144 CRD CRD-V-102 CR 0639 WD LINE VENT CRD-145 CRD CRD-V-102 CR 1039 WD LINE VENT CRD-146 CRD CRD-V-102 CR 1439 WD LINE VENT CRD-147 CRD CRD-V-102 CR 1839 WD LINE VENT CRD-148 CRD CRD-V-102 CR 2239 WD LINE VENT CRD-149 CRD CRD-V-102 CR 2639 WD LINE VENT CRD-150 CRD CRD-V-102 CR 3039 WD LINE VENT CRD-151 CRD CRD-V-102 CR 3439 WD LINE VENT CRD-152 CRD CRD-V-102 CR 3839 WD LINE VENT CRD-153 CRD CRD-V-102 CR 4239 WD LINE VENT CRD-154 CRD CR 4639 WD LINE VENT 'RD-V-102 CRD-155 CRD CRD-V-102 CR 5039 WD LINE VENT CRD-156 CRD CRD-V-102 CR 5439 WD LINE VENT CRD-157 CRD CRD-V-102 CR 5839 WD LINE VENT CRD-158 CRD CRD-V-102 CR 0243 WD LINE VENT CRD-159 CRD CRD-V-102 CR 0643 WD LINE VENT CRD-160 CRD CRD-V-102 CR 1043 WD LINE VENT CRD-161 CRD CRD-V-102 CR 1443 WD LINE VENT CRD-162 CRD CRD-V-102 CR 1843 WD LINE VENT CRD-163 CRD CRD-V-102 CR 2243 WD LINE VENT CRD-164 CRD CRD-V-102 CR 2643 WD LINE VENT CRD-165 CRD CRD-V-102 CR 3043 WD LINE VENT CRD-166 CRD CRD-V-102 CR 3443 WD LINE VENT CRD-167 CRD CRD-V-102 CR 3843 WD LINE VENT CRD-168 CRD CRD-V-102 CR 4243 WD LINE VENT CRD-169 CRD CRD-V-102 CR 4643 WD LINE VENT CRD-170 CRD CRD-V-102 CR 5043 WD LINE VENT CRD-171 CRD CRD-V-102 CR 5443 WD LINE VENT CRD-172 CRD CRD-V-102 CR 5843 WD LINE VENT CRD-173 CRD CRD-V-102 CR 0647 WD LINE VENT CRD-174 CRD CRD-V-102 CR 1047 WD LINE VENT CRD-175 CRD CRD-V-102 CR 1447 WD LINE VENT CRD-176 CRD CRD-V-102 CR 1847 WD LINE VENT CRD-177 CRD CRD-V-102 CR 2247 WD LINE VENT CRD-178 CRD CRD-V-102 CR 2647 WD LINE VENT CRD-179 CRD CRD-V-102 CR 3047, WD LINE VENT CRD-180 CRD CRD-V-102 CR 3447 WD LINE VENT CRD-181 CRD CRD-V-102 CR 3847 WD LINE VENT CRD-182 CRD CRD-V-102 CR 4247 WD LINE VENT November 16, 1994 Page 6 of 51

APPENDIX C ATTACHMENTC-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACHONS LISTING ID SYSTEM DESCRIPTION CRD-183 CRD CRD-V-102 CR 4647 WD LINE VENT CRD-184 CRD CRD-V-102 CR 5047 WD LINE VENT CRD-185 CRD CRD-V-102 CR 5447 WD LINE VENT CRD-186 CRD CRD-V-102 CR 1051 WD LINE VENT CRD-187 CRD CRD-V-102 CR 1451 WD LINE VENT CRD-188 CRD CRD-V-102 CR 1851 WD LINE VENT CRD-189 CRD CRD-V-102 CR 2251 WD LINE VENT CRD-190 CRD CRD-V-102 CR 2651 WD LINE VENT CRD-191 CRD CRD-V-102 CR 3051 WD LINE VENT CRD-192 CRD CRD-V-102 CR 3451 WD LINE VENT CRD-193 CRD CRD-V-102 CR 3851 WD LINE VENT CRD-194 CRD CRD-V-102 CR 4251 WD LINE VENT CRD-195 CRD CRD-V-,102 CR 4651'WD LINE VENT CRD-196 CRD CRD-V-102 CR 5051 WD LINE VENT CRD-197 CRD CRD-V-102 CR 1455 WD LINE VENT CRD-198 CRD CRD-V-102 CR 1855 WD LINE VENT CRD-199 CRD CRD-V-102 CR 2255 WD LINE VENT CRD-200 CRD CRD-V-102 CR 2655 WD LINE VENT CRD-201 CRD CRD-V-102 CR 3055 WD LINE VENT CRD-202 CRD CRD-V-102 CR 3455 WD LINE VENT CRD-203 CRD CRD-V-102 CR 3855 WD LINE VENT CRD-204 CRD CRD-V-102 CR 4255 WD LINE VENT CRD-205 CRD CRD-V-102 CR 4655 WD LINE VENT CRD-206 CRD CRD-V-102 CR 1859 WD LINE VENT CRD-207 CRD CRD-V-102 CR 2259 WD LINE VENT CRD-208 CRD CRD-V-102 CR 2659 WD LINE VENT CRD-209 CRD CRD-V-102 CR 3059 WD LINE VENT CRD-210 CRD CRD-V-102 CR 3459 WD LINE VENT CRD-211 CRD CRD-V-102 CR 3859 WD LINE VENT CRD-212 CRD CRD-V-102 CR 4259 WD LINE VENT CRD-213 CRD CRD-V-101 CR 1803 HCU INSERT ISO CRD-214 CRD CRD-V-101 CR 2203 HCU INSERT ISO CRD-215 CRD CRD-V-101 CR 2603 HCU INSERT ISO CRD-216 CRD CRD-V-101 CR 3003 HCU INSERT ISO CRD-217 CRD CRD-V-101 CR 3403 HCU INSERT ISO CRD-218 CRD CRD-V-101 CR 3803 HCU INSERT ISO CRD-219 CRD CRD-V-101 CR 4203 HCU INSERT ISO CRD-220 CRD CRD-V-101 CR 1407 HCU INSERT ISO CRD-221 CRD CRD-V-101 CR 1807 HCU INSERT ISO CRD-222 CRD CRD-V-101 CR 2207 HCU INSERT ISO CRD-223 CRD CRD-V-101 CR 2607 HCU INSERT ISO CRD-224 CRD CRD-V-101 CR 3007 HCU INSERT ISO CRD-225 CRD CRD-V-101 CR 3407 HCU INSERT ISO November 16, 1994 Page 7 of 51

APPENDIX C ATTACHMENTC-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID SYSTEM DESCRIPTION CRD-226 CRD CRD-V-101 CR 3807 HCU INSERT ISO CRD-227 CRD CRD-V-101 CR 4207 HCU INSERT ISO CRD-228 CRD CRD-V-101 CR 4607 HCU INSERT ISO CRD-229 CRD CRD-V-101 CR 1011 HCU INSERT ISO CRD-230 CRD CRD-V-101 CR 1411 HCU INSERT ISO CRD-231 CRD CRD-V-101 CR 1811 HCU INSERT ISO CRD-232 CRD CRD-V-101 CR 2211 HCU INSERT ISO CRD-233 CRD CRD-V-101 CR 2611 HCU INSERT ISO CRD-234 CRD CRD-V-101 CR 3011 HCU INSERT ISO CRD-235 CRD CRD-V-101 CR 3411 HCU INSERT ISO CRD-236 CRD CRD-V-101 CR 3811 HCU INSERT ISO CRD-237 CRD CRD-V-101 CR 4211 HCU INSERT ISO CRD-238 CRD CRD-V-101 CR 4611 HCU INSERT ISO CRD-239 CRD CRD-V-'101 CR 5011 HCU INSERT ISO CRD-240 CRD CRD-V-101 CR 0615 HCU INSERT ISO CRD-241 CRD CRD-V-101 CR 1015 HCU INSERT ISO CRD-242 CRD CRD-V-101 CR 1415 HCU INSERT ISO CRD-243 CRD CRD-V-101 CR 1815 HCU INSERT ISO CRD-244 CRD CRD-V-101 CR 2215 HCU INSERT ISO

'RD-245 CRD CRD-V-101 CR 2615 HCU INSERT ISO CRD-246 CRD CRD-V-101 CR 3015 HCU INSERT ISO CRD-247 CRD CRD-V-101 CR 3415 HCU INSERT ISO CRD-&8 CRD CRD-V-101 CR 3815 HCU INSERT ISO CRD-249 CRD CRD-V-101 CR 4215 HCU INSERT ISO CRD-250 CRD CRD-V-101 CR 4615 HCU INSERT ISO CRD-251 CRD CRD-V-101 CR 5015 HCU INSERT ISO CRD-252 CRD CRD-V-101 CR 5415 HCU INSERT ISO CRD-253 CRD CRD-V-101 CR 0219 HCU INSERT ISO CRD-254 CRD CRD-V-101 CR 0619 HCU INSERT ISO CRD-255 CRD CRD-V-101 CR 1019 HCU INSERT ISO CRD-256 CRD CRD-V-101 CR 1419 HCU INSERT ISO CRD-257 CRD CRD-V-101 CR 1819 HCU INSERT ISO CRD-258 CRD CRD-V-'101 CR 2219 HCU INSERT ISO CRD-259 CRD CRD-V-101 CR 2619 HCU INSERT ISO CRD-260 CRD CRD-V-101 CR 3019 HCU INSERT ISO CRD-261 CRD CRD-V-101 CR 3419 HCU INSERT ISO CRD-262 CRD CRD-V-101 CR 3819 HCU INSERT ISO CRD-263 CRD CRD-V-101 CR 4219 HCU INSERT ISO CRD-264 CRD CRD-V-101 CR 4619 HCU INSERT ISO CRD-265 CRD CRD-V-101 CR 5019 HCU INSERT ISO CRD-266 CRD CRD-V-101 CR 5419 HCU INSERT ISO CRD-267 CRD CRD-V-101 CR 5819 HCU INSERT ISO CRD-268 CRD CRD-V-101 CR 0223 HCU INSERT ISO November 16, 1994 Page 8 of 51

APPENDIX C ATTACHMENTC-2, WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING SYSTEM DESCRIPTION CRD-269 CRD CRD-V-101 CR 0623 HCU INSERT ISO CRD-270 CRD CRD-V-101 CR 1023 HCU INSERT ISO CRD-271 CRD CRD-V-101 CR 1423 HCU INSERT ISO CRD-272 CRD CRD-V-101 CR 1823 HCU INSERT ISO CRD-273 CRD CRD-V-101 CR 2223 HCU INSERT ISO CRD-274 CRD CRD-V-101 CR 2623 HCU INSERT ISO CRD-275 CRD CRD-V-101 CR 3023 HCU INSERT ISO CRD-276 CRD CRD-V-101 CR 3423 HCU INSERT ISO CRD-277 CRD CRD-V-101 CR 3823 HCU INSERT ISO CRD-278 CRD CRD-V-101 CR 4223 HCU INSERT ISO CRD-279 CRD CRD-V-101 CR 4623 HCU INSERT ISO CRD-280 CRD CRD-V-101 CR 5023 HCU INSERT ISO CRD-281 CRD CRD-V-101 CR 5423 HCU INSERT ISO CRD-282 CRD CRD-V-101 CR 5823 HCU INSERT ISO CRD-283 CRD CRD-V-101 CR 0227 HCU INSERT ISO CRD-284 CRD CRD-V-101 CR 0627 HCU INSERT ISO CRD-285 CRD CRD-V-101 CR 1027 HCU INSERT ISO CRD-286 CRD CRD-V-101 CR 1427 HCU INSERT ISO CRD-287 CRD CRD-V-101 CR 1827 HCU INSERT ISO CRD-288 CRD CRD-V-101 CR 2227 HCU INSERT ISO CRD-289 CRD CRD-V-101 CR 2627 HCU INSERT ISO CRD-290 CRD CRD-V-101 CR 3027 HCU INSERT ISO CRD-291 CRD CRD-V-101 CR 3427 HCU INSERT ISO CRD-292 CRD CRD-V-101 CR 3827 HCU INSERT ISO CRD-293 CRD CRD-V-101 CR 4227 HCU INSERT ISO CRD-294 CRD CRD-V-101 CR 4627 HCU INSERT ISO CRD-295 CRD CRD-V-101 CR 5027 HCU INSERT ISO CRD-296 CRD CRD-V-101 CR 5427 HCU INSERT ISO CRD-297 CRD CRD-V-101 CR 5827 HCU INSERT ISO CRD-298 CRD CRD-V-101 CR 0231 HCU INSERT ISO CRD-299 CRD CRD-V-101 CR 0631 HCU INSERT ISO CRD-300 CRD CRD-V-101 CR 1031 HCU INSERT ISO CRD-301 CRD CRD-V-101 CR 1431 HCU INSERT ISO CRD-302 CRD CRD-V-101 CR 1831 HCU INSERT ISO CRD-303 CRD CRD-V-101 CR 2231 HCU INSERT ISO CRD-304 CRD CRD-V-101 CR 2631 HCU INSERT ISO CRD-305 CRD CRD-V-101 CR 3031 HCU INSERT ISO CRD-306 CRD CRD-V-101 CR 3431 HCU INSERT ISO CRD-307 CRD CRD-V-101 CR 3831 HCU INSERT ISO CRD-308 CRD CRD-V-101 CR 4231 HCU INSERT ISO CRD-309 CRD CRD-V-101 CR 4631 HCU INSERT ISO CRD-310 CRD CRD-V-101 CR 5031 HCU INSERT ISO CRD-311 CRD CRD-V-101 CR 5431 HCU INSERT ISO November 16, 1994 Page 9 of 51

APPENDIX C ATTACHMENTC-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID SYSTEM DESCRIPTION CRD-312 CRD CRD-V-101 CR 5831 HCU INSERT ISO CRD-313 CRD CRD-V-101 CR 0235 HCU INSERT ISO CRD-314 CRD CRD-V-101 CR 0635 HCU INSERT ISO CRD-315 CRD CRD-V-101 CR 1035 HCU INSERT ISO CRD-316 CRD CRD-V-101 CR 1435 HCU INSERT ISO CRD-317 CRD CRD-V-101 CR 1835 HCU INSERT ISO CRD-318 CRD CRD-V-101 CR 2235 HCU INSERT ISO CRD-319 CRD CRD-V-101 CR 2635 HCU INSERT ISO CRD-320 CRD CRD-V-101 CR 3035 HCU INSERT ISO CRD-321 CRD CRD-V-101 CR 3435 HCU INSERT ISO CRD-322 CRD CRD-V-101 CR 3835 HCU INSERT ISO CRD-323 CRD CRD-V-101 CR 4235 HCU INSERT ISO CRD-324 CRD CRD-V-101 CR 4635 HCU INSERT ISO CRD-325 CRD CRD-V-101 CR 5035 HCU INSERT ISO CRD-326 CRD CRD-V-101 CR 5435 HCU INSERT ISO CRD-327 CRD CRD-V-101 CR 5835 HCU INSERT ISO CRD-328 CRD CRD-V-101 CR 0239 HCU INSERT ISO CRD-329 CRD CRD-V-101 CR 0639 HCU INSERT ISO CRD-330 CRD CRD-V-101 CR 1039 HCU INSERT ISO CRD-331 CRD CRD-V-101 CR 1439 HCU INSERT ISO CRD-332 CRD CRD-V-101 CR 1839 HCU INSERT ISO CRD-333 CRD CRD-V-101 CR 2239 HCU INSERT ISO CRD-334 CRD CRD-V-101 CR 2639 HCU INSERT ISO CRD-335 CRD CRD-V-101 CR 3039 HCU INSERT ISO CRD-336 CRD CRD-V-101 CR 3439 HCU INSERT ISO CRD-337 CRD CRD-V-101 CR 3839 HCU INSERT ISO CRD-338 CRD CRD-V-101 CR 4239 HCU INSERT ISO CRD-339 CRD CRD-V-101 CR 4639 HCU INSERT ISO CRD-340 CRD CRD-V-101 CR 5039 HCU INSERT ISO CRD-341 CRD CRD-V-101 CR 5439 HCU INSERT ISO CRD-342 CRD CRD-V-101 CR 5839 HCU INSERT ISO CRD-343 CRD CRD-V-101 CR 0243 HCU INSERT ISO CRD-344 CRD CRD-V-101 CR 0643 HCU INSERT ISO CRD-345 CRD CRD-V-101 CR 1043 HCU INSERT ISO CRD-346 CRD CRD-V-101 CR 1443 HCU INSERT ISO CRD-347 CRD CRD-V-101 CR 1843 HCU INSERT ISO CRD-348 CRD CRD-V-101 CR 2243 HCU INSERT ISO CRD-349 CRD CRD-V-101 CR 2643 HCU INSERT ISO CRD-350 CRD CRD-V-101 CR 3043 HCU INSERT ISO CRD-351 CRD CRD-V-101 CR 3443 HCU INSERT ISO CRD-352 CRD CRD-V-101 CR 3843 HCU INSERT ISO CRD-353 CRD CRD-V-101 CR 4243 HCU INSERT ISO CRD-354 CRD CRD-V-101 CR 4643 HCU INSERT ISO November 16, 1994 Page 10 of 51

APPENDIX C ATTACHMENTC-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID SYSTEM DESCRIPTION CRD-355 CRD CRD-V-101 CR 5043 HCU INSERT ISO CRD-356 CRD CRD-V-101 CR 5443 HCU INSERT ISO CRD-357 CRD CRD-V-101 CR 5843 HCU INSERT ISO CRD-358 CRD CRD-V-101 CR 0647 HCU INSERT ISO CRD-359 CRD CRD-V-101 CR 1047 HCU INSERT ISO CRD-360 CRD CRD-V-101 CR 1447 HCU INSERT ISO CRD-361 CRD CRD-V-101 CR 1847 HCU INSERT ISO CRD-362 CRD CRD-V-101 CR 2247 HCU INSERT ISO CRD-363 CRD CRD-V-101 CR 2647 HCU INSERT ISO CRD-364 CRD CRD-V-101 CR 3047 HCU INSERT ISO CRD-365 CRD CRD-V-101 CR 3447 HCU INSERT ISO CRD-366 CRD CRD-V-101 CR 3847 HCU INSERT ISO CRD-367 CRD CRD-V-101 CR 4247 HCU INSERT ISO CRD-368 CRD CRD-V-101 CR 4647 HCU INSERT ISO CRD-369 CRD CRD-V-'101 CR 5047 HCU INSERT ISO CRD-370 CRD CRD-V-101 CR 5447 HCU INSERT ISO CRD-371 CRD CRD-V-101 CR 1051 HCU INSERT ISO CRD-372 CRD CRD-V-101 CR 1451 HCU INSERT ISO CRD-373 CRD CRD-V-101 CR 1851 HCU INSERT ISO CRD-374 CRD CRD-V-101 CR 2251 HCU INSERT ISO CRD-375 CRD CRD-V-101 CR 2651 HCU INSERT ISO CRD-376 CRD CRD-V-101 CR 3051 HCU INSERT ISO CRD-377 CRD CRD-V-101 CR 3451 HCU INSERT ISO CRD-378 CRD CRD-V-101 CR 3851 HCU INSERT ISO CRD-379 CRD CRD-V-101 CR 4251 HCU INSERT ISO CRD-380 CRD CRD-V-101 CR 4651 HCU INSERT ISO CRD-381 CRD CRD-V-101 CR 5051 HCU INSERT ISO CRD-382 CRD CRD-V-101 CR 1455 HCU INSERT ISO CRD-383 CRD CRD-V-101 CR 1855 HCU INSERT ISO CRD-384 CRD CRD-V-101 CR 2255 HCU INSERT ISO CRD-385 CRD CRD-V-101 CR 2655 HCU INSERT ISO CRD-386 CRD CRD-V-101 CR 3055 HCU INSERT ISO CRD-387 CRD CRD-V-101 CR 3455 HCU INSERT ISO CRD-388 CRD CRD-V-101 CR 3855 HCU INSERT ISO CRD-389 CRD CRD-V-101 CR 4255 HCU INSERT ISO CRD-390 CRD CRD-V-101 CR 4655 HCU INSERT ISO CRD-391 CRD CRD-V-101 CR 1859 HCU INSERT ISO CRD-392 CRD CRD-V-101 CR 2259 HCU INSERT ISO CRD-393 CRD CRD-V-101 CR 2659 HCU INSERT ISO CRD-394 CRD CRD-V-101 CR 3059 HCU INSERT ISO CRD-395 CRD CRD-V-101 CR 3459 HCU INSERT ISO CRD-396 CRD CRD-V-101 CR 3859 HCU INSERT ISO CRD-397 CRD CRD-V-101 CR 4259 HCU INSERT ISO November 16, 1994 Page 11 of 51

APPENDIX C ATTACHMENTC-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID SYSTEM DESCRIPTION CRD-398 CRD CRD-V-102 CR 1803 HCU WD HDR ISO CRD-399 CRD CRD-V-102 CR 2203 HCU WD HDR ISO CRD-400 CRD CRD-V-102 CR 2603 HCU WD HDR ISO CRD-401 CRD CRD-V-102 CR 3003 HCU WD HDR ISO CRD 402 CRD CRD-V-102 CR 3403 HCU WD HDR ISO CRD 403 CRD CRD-V-102 CR 3803 HCU WD HDR ISO CRD-404 CRD CRD-V-102 CR 4203 HCU WD HDR ISO CRD-405 CRD CRD-V-102 CR 1407 HCU WD HDR ISO CRD 406 CRD CRD-V-102 CR 1807 HCU WD HDR ISO CRD 407 CRD CRD-V-102 CR 2207 HCU WD HDR ISO CRD 408 CRD CRD-V-102 CR 2607 HCU WD HDR ISO CRD409 CRD CRD-V-102 CR 3007 HCU WD HDR ISO CRD-410 CRD CRD-V-102 CR 3407 HCU WD HDR ISO CRD 411 CRD CRD-V-102 CR 3807 HCU WD HDR ISO CRD 412 CRD CRD-V-102 CR 4207 HCU WD HDR ISO CRD 413 CRD CRD-V-102 CR 4607 HCU WD HDR ISO CRD 414 CRD CRD-V-102 CR 1011 HCU WD HDR ISO CRD 415 CRD CRD-V-102 CR 1411 HCU WD HDR ISO CRD-416 CRD CRD-V-102 CR 1811 HCU WD HDR ISO CRD-417 CRD CRD-V-102 CR 2211 HCU WD HDR ISO CRD-418 CRD CRD-V-102 CR 2611 HCU WD HDR ISO CRD 419 CRD CRD-V-102 CR 3011 HCU WD HDR ISO CRD420 CRD CRD-V-102 CR 3411 HCU WD HDR ISO CRD 421 CRD CRD-V-102 CR 3811 HCU WD HDR ISO CRD 422 CRD CRD-V-102 CR 4211 HCU WD HDR ISO CRD-423 CRD CRD-V-102 CR 4611 HCU WD HDR ISO CRD-424 CRD CRD-V-102 CR 5011 HCU WD HDR ISO CRD-425 CRD CRD-V-102 CR 0615 HCU WD HDR ISO CRD-426 CRD CRD-V-102 CR 1015 HCU WD HDR ISO CRD 427 CRD CRD-V-102 CR 1415 HCU WD HDR ISO CRD-428 CRD CRD-V-102 CR 1815 HCU WD HDR ISO CRD-429 CRD CRD-V-102 CR 2215 HCU WD HDR ISO CRD-430 CRD CRD-V-102 CR 2615 HCU WD HDR ISO CRD-431 CRD CRD-V-102 CR 3015 HCU WD HDR ISO CRD-432 CRD CRD-V-102 CR 3415 HCU WD HDR ISO CRD 433 CRD CRD-V-102 CR 3815 HCU WD HDR ISO CRD 434 CRD CRD-V-102 CR 4215 HCU WD HDR ISO CRD 435 CRD CRD-V-102 CR 4615 HCU WD HDR ISO CRD-436 CRD CRD-V-102 CR 5015 HCU WD HDR ISO CRD437 CRD CRD-V-102 CR 5415 HCU WD HDR ISO CRD438 CRD CRD-V-102 CR 0219 HCU WD HDR ISO CRD439 CRD CRD-V-102 CR 0619 HCU WD HDR ISO CRD-440 CRD CRD-V-102 CR 1019 HCU WD HDR ISO November 16, 1994 Page 12 of 51

APPENDIX C ATTACHMENTC-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID SYSTEM DESCRIPTION CRDM1 CRD CRD-V-102 CR 1419 HCU WD HDR ISO CRD-442 CRD CRD-V-102 CR 1819 HCU WD HDR ISO CRD-443 CRD CRD-V-102 CR 2219 HCU WD HDR ISO CRD 444 CRD CRD-V-102 CR 2619 HCU WD HDR ISO CRD-445 CRD CRD-V-102 CR 3019 HCU WD HDR ISO CRD-446 CRD CRD-V-102 CR 3419 HCU WD HDR ISO CRD-447 CRD CRD-V-102 CR 3819 HCU WD HDR ISO CRD-448 CRD CRD-V-102 CR 4219 HCU WD HDR ISO CRD-449 CRD CRD-V-102 CR 4619 HCU WD HDR ISO CRD-450 CRD CRD-V-102 CR 5019 HCU WD HDR ISO CRD 451 CRD CRD-V-102 CR 5419 HCU WD HDR ISO CRD-452 CRD CRD-V-102 CR 5819 HCU WD HDR ISO CRD-453 CRD CRD-V-102 CR 0223 HCU WD HDR ISO CRD-454 CRD CRD-V-102 CR 0623 HCU WD HDR ISO CRD 455 CRD CRD-V-102 CR 1023 HCU WD HDR ISO CRD-456 CRD CRD-V-102 CR 1423 HCU WD HDR ISO CRD 457 CRD CRD-V-102 CR 1823 HCU WD HDR ISO CRD-458 CRD CRD-V-102 CR 2223 HCU WD HDR ISO CRD-459 CRD CRD-V-102 CR 2623 HCU WD HDR ISO CRD 460 CRD CRD-V-102 CR 3023 HCU WD HDR ISO CRD 461 CRD CRD-V-102 CR 3423 HCU WD HDR ISO CRD462 CRD CRD-V-102 CR 3823 HCU WD HDR ISO CRD-463 CRD CRD-V-102 CR 4223 HCU WD HDR ISO CRD-464 CRD CRD-V-102 CR 4623 HCU WD HDR ISO CRD-465 CRD CRD-V-102 CR 5023 HCU WD HDR ISO CRD-466 CRD CRD-V-102 CR 5423 HCU WD HDR ISO CRD467 CRD CRD-V-102 CR 5823 HCU WD HDR ISO CRD-468 CRD CRD-V-102 CR 0227 HCU WD HDR ISO CRD 469 CRD CRD-V-102 CR 0627 HCU WD HDR ISO CRD 470 CRD CRD-V-102 CR 1027 HCU WD HDR ISO CRD 471 CRD CRD-V-102 CR 1427 HCU WD HDR ISO CRD 472 CRD CRD-V-102 CR 1827 HCU WD HDR ISO CRDP73 CRD CRD-V-102 CR 2227 HCU WD HDR ISO CRD 474 CRD CRD-V-102 CR 2627 HCU WD HDR ISO CRD-475 CRD CRD-V-102 CR 3027 HCU WD HDR ISO CRD 476 CRD CRD-V-102 CR 3427 HCU WD HDR ISO CRD 477 CRD CRD-V-102 CR 3827 HCU WD HDR ISO CRD 478 CRD CRD-V-102 CR 4227 HCU WD HDR ISO CRD 479 CRD CRD-V-102 CR 4627 HCU WD HDR ISO CRDP80 CRD CRD-V-102 CR 5027 HCU WD HDR ISO CRD-481 CRD CRD-V-102 CR 5427 HCU WD HDR ISO CRD-482 CRD CRD-V-102 CR 5827 HCU WD HDR ISO CRD-483 CRD CRD-V-102 CR 0231 HCU WD HDR ISO November 16, 1994 Page 13 of 51

APPENDIX C ATTACHMENTC-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACHONS LISTING ID SYSTEM DESCRIPTION CRD 484 CRD CRD-V-102 CR 0631 HCU WD HDR ISO CRD-485 CRD CRD-V-102 CR 1031 HCU WD HDR ISO CRD-486 CRD CRD-V-102 CR 1431 HCU WD HDR ISO CRD 487 CRD CRD-V-102 CR 1831 HCU WD HDR ISO CRD488 CRD CRD-V-102 CR 2231 HCU WD HDR ISO CRD489 CRD CRD-V-102 CR 2631 HCU WD HDR ISO CRD-490 CRD CRD-V-102 CR 3031 HCU WD HDR ISO CRD 491 CRD CRD-V-102 CR 3431 HCU WD HDR ISO CRD 492 CRD CRD-V-102 CR 3831 HCU WD HDR ISO CRD 493 CRD CRD-V-102 CR 4231 HCU WD HDR ISO CRD 494 CRD CRD-V-102 CR 4631 HCU WD HDR ISO CRDP95 CRD CRD-V-102 CR 5031 HCU WD HDR ISO CRD 496 CRD CRD-V-102 CR 5431 HCU WD HDR ISO CRD-497 CRD CRD-V-102 CR 5831 HCU WD HDR ISO CRD 498 CRD CRD-V-102 CR 0235 HCU WD HDR ISO CRD 499 CRD CRD-V-102 CR 0635 HCU WD HDR ISO CRD-500 CRD CRD-V-102 CR 1035 HCU WD HDR ISO CRD-501 CRD CRD-V-102 CR 1435 HCU WD HDR ISO CRD-502 CRD CRD-V-102 CR 1835 HCU WD HDR ISO CRD-503 CRD CRD-V-102 CR 2235 HCU WD HDR ISO CRD-504 CRD CRD-V-102 CR 2635 HCU WD HDR ISO CRD-505 CRD CRD-V-102 CR 3035 HCU WD HDR ISO CRD-506 CRD CRD-V-102 CR 3435 HCU WD HDR ISO CRD-507 CRD CRD-V-102 CR 3835 HCU WD HDR ISO CRD-508 CRD CRD-V-102 CR 4235 HCU WD HDR CRD-509 CRD CR 4635 HCU WD HDR ISO ISO'RD-V-102 CRD-510 CRD CRD-V-102 CR 5035 HCU WD HDR ISO CRD-511 CRD CRD-V-102 CR 5435 HCU WD HDR ISO CRD-512 CRD CRD-V-102 CR 5835 HCU WD HDR ISO CRD-513 CRD CRD-V-102 CR 0239 HCU WD HDR ISO CRD-514 CRD CRD-V-102 CR 0639 HCU WD HDR ISO CRD-515 CRD CRD-V-102 CR 1039 HCU WD HDR ISO CRD-516 CRD CRD-V-102 CR 1439 HCU WD HDR ISO CRD-517 CRD CRD-V-102 CR 1839 HCU WD HDR ISO CRD-518 CRD CRD-V-102 CR 2239 HCU WD HDR ISO CRD-519 CRD CRD-V-102 CR 2639 HCU WD HDR ISO CRD-520 CRD CRD-V-102 CR 3039 HCU WD HDR ISO CRD-521 CRD CRD-V-102 CR 3439 HCU WD HDR ISO CRD-522 CRD CRD-V-102 CR 3839 HCU WD HDR ISO CRD-523 CRD CRD-V-102 CR 4239 HCU WD HDR ISO CRD-524 CRD CRD-V-102 CR 4639 HCU WD HDR ISO CRD-525 CRD CRD-V-102 CR 5039 HCU WD HDR ISO CRD-526 CRD CRD-V-102 CR 5439 HCU WD HDR ISO November 16, 1994 Page 14of51

APPENDIX C ATTACHMENTC-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID SYSTEM DESCRIPTION CRD-527 CRD CRD-V-102 CR 5839 HCU WD HDR ISO CRD-528 CRD CRD-V-102 CR 0243 HCU WD HDR ISO CRD-529 CRD CRD-V-102 CR 0643 HCU WD HDR ISO CRD-530 CRD CRD-V-102 CR 1043 HCU WD HDR ISO CRD-531 CRD CRD-V-102 CR 1443 HCU WD HDR ISO CRD-532 CRD CRD-V-102 CR 1843 HCU WD HDR ISO CRD-533 CRD CRD-V-102 CR 2243 HCU WD HDR ISO CRD-534 CRD CRD-V-102 CR 2643 HCU WD HDR ISO CRD-535 CRD CRD-V-102 CR 3043 HCU WD HDR ISO CRD-536 CRD CRD-V-102 CR 3443 HCU WD HDR ISO CRD-537 CRD CRD-V-102 CR 3843 HCU WD HDR ISO CRD-538 CRD CRD-V-102 CR 4243 HCU WD HDR ISO CRD-539 CRD CRD-V-102 CR 4643 HCU WD HDR ISO CRD-540 CRD CRD-V-102 CR 5043 HCU WD HDR ISO CRD-541 CRD CRD-V-102 CR 5443 HCU WD HDR ISO CRD-542 CRD CRD-V-102 CR 5843 HCU WD HDR ISO CRD-543 CRD CRD-V-102 CR 0647 HCU WD HDR ISO CRD-544 CRD CRD-V-102 CR 1047 HCU WD HDR ISO CRD-545 CRD CRD-V-102 CR 1447 HCU WD HDR ISO CRD-546 CRD CRD-V-102 CR 1847 HCU WD HDR ISO CRD-547 CRD CRD-V-102 CR 2247 HCU WD HDR ISO CRD-548 CRD CRD-V-102 CR 2647 HCU WD HDR ISO CRD-549 CRD CRD-V-102 CR 3047 HCU WD HDR ISO CRD-550 CRD CRD-V-102 CR 3447 HCU WD HDR ISO CRD-551 CRD CRD-V-102 CR 3847 HCU WD HDR ISO CRD-552 CRD CRD-V-102 CR 4247 HCU WD HDR ISO CRD-553 CRD CRD-V-102 CR 4647 HCU WD HDR ISO CRD-554 CRD CRD-V-102 CR 5047 HCU WD HDR ISO CRD-555 CRD CRD-V-102 CR 5447 HCU WD HDR ISO CRD-556 CRD CRD-V-102 CR 1051 HCU WD HDR ISO CRD-557 CRD CRD-V-102 CR 1451 HCU WD HDR ISO CRD-558 CRD CRD-V-102 CR 1851 HCU WD HDR ISO CRD-559 CRD CRD-V-102 CR 2251 HCU WD HDR ISO CRD-560 CRD CRD-V-102 CR 2651 HCU WD HDR ISO CRD-561 CRD CRD-V-102 CR 3051 HCU WD HDR ISO CRD-562 CRD CRD-V-102 CR 3451 HCU WD HDR ISO CRD-563 CRD CRD-V-102 CR 3851 HCU WD HDR ISO CRD-564 CRD CRD-V-102 CR 4251 HCU WD HDR ISO CRD-565 CRD CRD-V-102 CR 4651 HCU WD HDR ISO CRD-566 CRD CRD-V-102 CR 5051 HCU WD HDR ISO CRD-567 CRD CRD-V-102 CR 1455 HCU WD HDR ISO CRD-568 CRD CRD-V-102 CR 1855 HCU WD HDR ISO CRD-569 CRD CRD-V-102 CR 2255 HCU WD HDR ISO November 16, 1994 Page 15 of 51

0 APPENDIX C ATTACHMENTC-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID SYSTEM DESCRIPTION CRD-570 CRD CRD-V-102 CR 2655 HCU WD HDR ISO CRD-571 CRD CRD-V-102 CR 3055 HCU WD HDR ISO CRD-572 CRD CRD-V-102 CR 3455 HCU WD HDR ISO CRD-573 CRD CRD-V-102 CR 3855 HCU WD HDR ISO CRD-574 CRD CRD-V-102 CR 4255 HCU WD HDR ISO CRD-575 CRD CRD-V-102 CR 4655 HCU WD HDR ISO CRD-576 CRD CRD-V-102 CR 1859 HCU WD HDR ISO CRD-577 CRD CRD-V-102 CR 2259 HCU WD HDR ISO CRD-578 CRD CRD-V-102 CR 2659 HCUWD HDR ISO CRD-579 CRD CRD-V-102 CR 3059 HCU WD HDR ISO CRD-580 CRD CRD-V-102 CR 3459 HCU WD HDR ISO CRD-581 CRD CRD-V-102 CR 3859 HCU WD HDR ISO CRD-582 CRD CRD-V-102 CR 4259 HCU WD HDR ISO CRD-583 CRD CRD-V-103 CR 1803 HCU DRV ISOL CRD-584 CRD CRD-V-103 CR 2203 HCU DRV ISOL CRD-585 CRD CRD-V-.103 CR 2603 HCU DRV ISOL CRD-586 CRD CRD-V-103 CR 3003 HCU DRV ISOL CRD-587 CRD CRD-V-103 CR 3403 HCU DRV ISOL CRD-588 CRD CRD-V-103 CR 3803 HCU DRV ISOL CRD-589 CRD CRD-V-103 CR 4203 HCU DRV ISOL CRD-590 CRD CRD-V-103 CR 1407 HCU DRV ISOL CRD-591 CRD CRD-V-103 CR 1807 HCU DRV ISOL CRD-592 CRD CRD-V-103 CR 2207 HCU DRV ISOL CRD-593 CRD CRD-V-103 CR 2607 HCU DRV ISOL CRD-594 CRD CRD-V-103 CR 3007 HCU DRV ISOL CRD-595 CRD CRD-V-103 CR 3407 HCU DRV ISOL CRD-596 CRD CRD-V-103 CR 3807 HCU DRV ISOL CRD-597 CRD CRD-V-103 CR 4207 HCU DRV ISOL CRD-598 CRD CRD-V-103 CR 4607 HCU DRV ISOL CRD-599 CRD CRD-V-103 CR 1011 HCU DRV ISOL CRD-600 CRD CRD-V-103 CR 1411 HCU DRV ISOL CRD-601 CRD CRD-V-103 CR 1811 HCU DRV ISOL CRD-602 CRD CRD-V-103 CR 2211 HCU DRV ISOL CRD-603 CRD CRD-V-103 CR 2611 HCU DRV ISOL CRD-604 CRD CRD-V-103 CR 3011 HCU DRV ISOL CRD-605 CRD CRD-V-103 CR 3411 HCU DRV ISOL CRD-606 CRD CRD-V-103 CR 3811 HCU DRV ISOL CRD-607 CRD CRD-V-103 CR 4211 HCU DRV ISOL CRD-608 CRD CRD-V-103 CR 4611 HCU DRV ISOL CRD-609 CRD CRD-V-103 CR 5011 HCU DRV ISOL CRD-610 CRD CRD-V-103 CR 0615 HCU DRV ISOL CRD-611 CRD CRD-V-103 CR 1015 HCU DRV ISOL CRD-612 CRD CRD-V-103 CR 1415 HCU DRV ISOL November 16, 1994 Page 16 of 51

APPENDIX C ATTACHMENTC-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING DESCRIPTION ID SYSTEM CRD-613 CRD CRD-V-103 CR 1815 HCU DRV ISOL CRD-614 CRD CRD-V-103 CR 2215 HCU DRV ISOL CRD-615 CRD CRD-V-103 CR 2615 HCU DRV ISOL CRD-616 CRD CRD-V-103 CR 3015 HCU DRV ISOL CRD-617 CRD CRD-V-103 CR 3415 HCU DRV ISOL CRD-618 CRD CRD-V-103 CR 3815 HCU DRV ISOL CRD-619 CRD CRD-V-103 CR 4215 HCU DRV ISOL CRD-620 CRD CRD-V-103 CR 4615 HCU DRV ISOL CRD-621 CRD CRD-V-103 CR 5015 HCU DRV ISOL CRD-622 CRD CRD-V-103 CR 5415 HCU DRV ISOL CRD-623 CRD CRD-V-103 CR 0219 HCU DRV ISOL CRD-624 CRD CRD-V-103 CR 0619 HCU DRV ISOL CRD-625 CRD CRD-V-103 CR 1019 HCU DRV ISOL CRD-626 CRD CRD-V-103 CR 1419 HCU DRV ISOL CRD-627 CRD CRD-V-103 CR 1819 HCU DRV ISOL CRD-628 CRD CRD-V-103 CR 2219 HCU DRV ISOL CRD-629 CRD CRD-V-103 CR 2619 HCU DRV ISOL CRD-630 CRD CRD-V-103 CR 3019 HCU DRV ISOL CRD-631 CRD CRD-V-103 CR 3419 HCU DRV ISOL CRD-632 CRD CRD-V-103 CR 3819 HCU DRV ISOL CRD-633 CRD CRD-V-103 CR 4219 HCU DRV ISOL CRD-634 CRD CRD-V-103 CR 4619 HCU DRV ISOL CRD-635 CRD CRD-V-103 CR 5019 HCU DRV ISOL CRD-636 CRD CRD-V-103 CR 5419 HCU DRV ISOL CRD-637 CRD CRD-V-103 CR 5819 HCU DRV ISOL CRD-638 CRD CRD-V-103 CR 0223 HCU DRV ISOL CRD-639 CRD CRD-V-103 CR 0623 HCU DRV ISOL CRD-640 CRD CRD-V-103 CR 1023 HCU DRV ISOL CRD-641 CRD CRD-V-103 CR 1423 HCU DRV ISOL CRD-642 CRD CRD-V-103 CR 1823 HCU DRV ISOL CRD-643 CRD CRD-V-103 CR 2223 HCU DRV ISOL CRD-644 CRD CRD-V-103 CR 2623 HCU DRV ISOL CRD-645 CRD CRD-V-103 CR 3023 HCU DRV ISOL CRD-646 CRD CRD-V-103 CR 3423 HCU DRV ISOL CRD-647 CRD CRD-V-103 CR 3823 HCU DRV ISOL CRD-648 CRD CRD-V-103 CR 4223 HCU DRV ISOL CRD-649 CRD CRD-V-103 CR 4623 HCU DRV ISOL CRD-650 CRD CRD-V-103 CR 5023 HCU DRV ISOL CRD-651 CRD CRD-V-103 CR 5423 HCU DRV ISOL CRD-652 CRD CRD-V-103 CR 5823 HCU DRV ISOL CRD-653 CRD CRD-V-103 CR 0227 HCU DRV ISOL CRD-654 CRD CRD-V-103 CR 0627 HCU DRV ISOL CRD-655 CRD CRD-V-103 CR 1027 HCU DRV ISOL November 16, 1994 Page 17 of 51

APPENDIX C ATTACHMENTC-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID SYSTEM DESCRIPTION CRD-656 CRD CRD-V-103 CR 1427 HCU DRV ISOL CRD-657 CRD CRD-V-103 CR 1827 HCU DRV ISOL CRD-658 CRD CRD-V-103 CR 2227 HCU DRV ISOL CRD-659 CRD CRD-V-103 CR 2627 HCU DRV ISOL CRD-660 CRD CRD-V-103 CR 3027 HCU DRV ISOL CRD-661 CRD CRD-V-103 CR 3427 HCU DRV ISOL CRD-662 CRD CRD-V-103 CR 3827 HCU DRV ISOL CRD-663 CRD CRD-V-103 CR 4227 HCU DRV ISOL CRD-664 CRD CRD-V-103 CR 4627 HCU DRV ISOL CRD-665 CRD CRD-V-103 CR 5027 HCU DRV ISOL CRD-666 CRD CRD-V-103 CR 5427 HCU DRV ISOL CRD-667 CRD CRD-V-103 CR 5827 HCU DRV ISOL CRD-668 CRD CRD-V-103 CR 0231 HCU DRV ISOL CRD-669 CRD CRD-V-103 CR 0631 HCU DRV ISOL CRD-670 CRD CRD-V-103 CR 1031 HCU DRV ISOL CRD-671 CRD CRD-V-103 CR 1431 HCU DRV ISOL CRD-672 CRD CRD-V-103 CR 1831 HCU DRV ISOL CRD-673 CRD CRD-V-103 CR 2231 HCU DRV ISOL CRD-674 CRD CRD-V-103 CR 2631 HCU DRV ISOL CRD-675 CRD CRD-V-103 CR 3031 HCU DRV ISOL CRD;676 CRD CRD-V-103 CR 3431 HCU DRV ISOL CRD-677 CRD CRD-V-103 CR 3831 HCU DRV ISOL CRD-678 CRD CRD-V-103 CR 4231 HCU DRV ISOL CRD-679 CRD CRD-V-103 CR 4631 HCU DRV ISOL CRD-680 CRD CRD-V-103 CR 5031 HCU DRV ISOL CRD-681 CRD CRD-V-103 CR 5431 HCU DRV ISOL CRD-682 CRD CRD-V-103 CR 5831 HCU DRV ISOL CRD-683 CRD CRD-V-103 CR 0235 HCU DRV ISOL CRD-684 CRD CRD-V-103 CR 0635 HCU DRV ISOL CRD-685 CRD CRD-V-103 CR 1035 HCU DRV ISOL CRD-686 CRD CRD-V-103 CR 1435 HCU DRV ISOL CRD-687 CRD CRD-V-103 CR 1835 HCU DRV ISOL CRD-688 CRD CRD-V-103 CR 2235 HCU DRV ISOL CRD-689 CRD CRD-V-103 CR 2635 HCU DRV ISOL CRD-690 CRD CRD-V-103 CR 3035 HCU DRV ISOL CRD-691 CRD CRD-V-103 CR 3435 HCU DRV ISOL CRD-692 CRD CRD-V-103 CR 3835 HCU DRV ISOL CRD-693 CRD CRD-V-103 CR 4235 HCU DRV ISOL CRD-694 CRD CRD-V-103 CR 4635 HCU DRV ISOL CRD-695 CRD CRD-V-103 CR 5035 HCU DRV ISOL CRD-696 CRD CRD-V-103 CR 5435 HCU DRV ISOL CRD-697 CRD CRD-V-103 CR 5835 HCU DRV ISOL CRD-698 CRD CRD-V-103 CR 0239 HCU DRV ISOL November 16, 1994 Page 18 of 51

APPENDIX C ATTACHMENTC-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID SYSTEM DESCRIPTION CRD-699 CRD CRD-V-103 CR 0639 HCU DRV ISOL CRD-700 CRD CRD-V-103 CR 1039 HCU DRV ISOL CRD-701 CRD CRD-V-103 CR 1439 HCU DRV ISOL CRD-702 CRD CRD-V-103 CR 1839 HCU DRV ISOL CRD-703 CRD CRD-V-103 CR 2239 HCU DRV ISOL CRD-704 CRD CRD-V-103 CR 2639 HCU DRV ISOL CRD-705 CRD CRD-V-103 CR 3039 HCU DRV ISOL CRD-706 CRD CRD-V-103 CR 3439 HCU DRV ISOL CRD-707 CRD CRD-V-103 CR 3839 HCU DRV ISOL CRD-708 CRD CRD-V-103 CR 4239 HCU DRV ISOL CRD-709 CRD CRD-V-103 CR 4639 HCU DRV ISOL CRD-710 CRD CRD-V-103 CR 5039 HCU DRV ISOL CRD-711 CRD CRD-V-103 CR 5439 HCU DRV ISOL CRD-712 CRD CRD-V-103 CR 5839 HCU DRV ISOL CRD-713 CRD CRD-V-103 CR 0243 HCU DRV ISOL CRD-'714 CRD CRD-V-103 CR 0643 HCU DRV ISOL CRD-715 CRD CRD-V-103 CR 1043 HCU DRV ISOL CRD-716 CRD CRD-V-103 CR 1443 HCU DRV ISOL CRD-717 CRD CRD-V-103 CR 1843 HCU DRV ISOL CRD-718 CRD CRD-V-103 CR 2243 HCU DRV ISOL CRD-719 CRD CRD-V-103 CR 2643 HCU DRV ISOL CRD-720 CRD CRD-V-103 CR 3043 HCU DRV ISOL CRD-721 CRD CRD-V-103 CR 3443 HCU DRV ISOL CRD-722 CRD CRD-V-103 CR 3843 HCU DRV ISOL CRD-723 CRD CRD-V-103 CR 4243 HCU DRV ISOL CRD-724 CRD CRD-V-103 CR 4643 HCU DRV ISOL CRD-725 CRD CRD-V-103 CR 5043 HCU DRV ISOL CRD-726 CRD CRD-V-103 CR 5443 HCU DRV ISOL CRD-727 CRD CRD-V-103 CR 5843 HCU DRV ISOL CRD-728 CRD CRD-V-103 CR 0647 HCU DRV ISOL CRD-729 CRD CRD-V-103 CR 1047 HCU DRV ISOL CRD-730 CRD CRD-V-103 CR 1447 HCU DRV ISOL CRD-731 CRD CRD-V-103 CR 1847 HCU DRV ISOL CRD-732 CRD CRD-V-103 CR 2247 HCU DRV ISOL CRD-733 CRD CRD-V-103 CR 2647 HCU DRV ISOL CRD-734 CRD CRD-V-103 CR 3047 HCU DRV ISOL CRD-735 CRD CRD-V-103 CR 3447 HCU DRV ISOL CRD-736 CRD CRD-V-103 CR 3847 HCU DRV ISOL CRD-737 CRD CRD-V-103 CR 4247 HCU DRV ISOL CRD-738 CRD CRD-V-103 CR 4647 HCU DRV ISOL CRD-739 CRD CRD-V-103 CR 5047 HCU DRV ISOL CRD-740 CRD CRD-V-103 CR 5447 HCU DRV ISOL CRD-741 CRD CRD-V-103 CR 1051 HCU DRV ISOL November 16, 1994 Page 19 of 51

APPENDIX C ATTACHMENTC-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID SYSTEM DESCRIPTION CRD-742 CRD CRD-V-103 CR 1451 HCU DRV ISOL CRD-743 CRD CRD-V-103 CR 1851 HCU DRV ISOL CRD-744 CRD CRD-V-103 CR 2251 HCU DRV ISOL CRD-745 CRD CRD-V-103 CR 2651 HCU DRV ISOL CRD-746 CRD CRD-V-103 CR 3051 HCU DRV ISOL CRD-747 CRD CRD-V-103 CR 3451 HCU DRV ISOL CRD-748 CRD CRD-V-103 CR 3851 HCU DRV ISOL CRD-749 CRD CRD-V-103 CR 4251 HCU DRV ISOL CRD-750 CRD CRD-V-103 CR 4651 HCU DRV ISOL CRD-751 CRD CRD-V-103 CR 5051 HCU DRV ISOL CRD-752 CRD CRD-V-103 CR 1455 HCU DRV ISOL CRD-753 CRD CRD-V-103 CR 1855 HCU DRV ISOL CRD-754 CRD CRD-V-103 CR 2255 HCU DRV ISOL CRD-755 CRD CRD-V-103 CR 2655 HCU DRV ISOL CRD-756 CRD CRD-V-103 CR 3055 HCU DRV ISOL CRD-757 CRD CRD-V-103 CR 3455 HCU DRV ISOL CRD-758 CRD CRD-V-103 CR 3855 HCU DRV ISOL CRD-759 CRD CRD-V-103 CR 4255 HCU DRV ISOL CRD-760 CRD CRD-V-103 CR 4655 HCU DRV ISOL CRD-761 CRD CRD-V-103 CR 1859 HCU DRV ISOL CRD-762 CRD CRD-V-103 CR 2259 HCU DRV ISOL CRD-763 CRD CRD-V-103 CR 2659 HCU DRV ISOL CRD-764 CRD CRD-V-103 CR 3059 HCU DRV ISOL CRD-765 CRD CRD-V-103 CR 3459 HCU DRV ISOL CRD-766 CRD CRD-V-103 CR 3859 HCU DRV ISOL CRD-767 CRD CRD-V-103 CR 4259 HCU DRV ISOL CRD-768 CRD CRD-V-101 CR 1803 INS LINE VENT CRD-769 CRD CRD-V-101 CR 2203 INS LINE VENT CRD-770 CRD CRD-V-101 CR 2603 INS LINE VENT CRD-771 CRD CRD-V-101 CR 3003 INS LINE VENT CRD-772 CRD CRD-V-101 CR 3403 INS LINE VENT CRD-773 CRD CRD-V-101 CR 3803 INS LINE VENT CRD-774 CRD CRD-V-101 CR 4203 INS LINE VENT CRD-775 CRD CRD-V-101 CR 1407 INS LINE VENT CRD-776 CRD CRD-V-101 CR 1807 INS LINE VENT CRD-777 CRD CRD-V-101 CR 2207 INS LINE VENT CRD-778 CRD CRD-V-101 CR 2607 INS LINE VENT CRD-779 CRD CRD-V-101 CR 3007 INS LINE VENT CRD-780 CRD CRD-V-101 CR 3407 INS LINE VENT CRD-781 CRD CRD-V-101 CR 3807 INS LINE VENT CRD-782 CRD CRD-V-101 CR 4207 INS LINE VENT CRD-783 CRD CRD-V-101 CR 4607 INS LINE VENT CRD-784 CRD CRD-V-101 CR 1011 INS LINE VENT November 16, 1994 Page 20 of 51

APPENDIX C ATTACHMENTC-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID SYSTEM DESCRIPTION CRD-785 CRD CRD-V-101 CR 1411 INS LINE VENT CRD-786 CRD CRD-V-101 CR 1811 INS LINE VENT CRD-787 CRD CRD-V-101 CR 2211 INS LINE VENT CRD-788 CRD CRD-V-101 CR 2611 INS LINE VENT CRD-789 CRD CRD-V-101 CR 3011 INS LINE VENT CRD-790 CRD CRD-V-101 CR 3411 INS LINE VENT CRD-791 CRD CRD-V-101 CR 3811 INS LINE VENT CRD-792 CRD CRD-V-101 CR 4211 INS LINE VENT CRD-793 CRD CRD-V-101 CR 4611 INS LINE VENT CRD-794 CRD CRD-V-101 CR 5011 INS LINE VENT CRD-795 CRD CRD-V-101 CR 0615 INS LINE VENT CRD-796 CRD CRD-V-101 CR 1015 INS LINE VENT CRD-797 CRD CRD-V-101 CR 1415 INS LINE VENT CRD-798 CRD CRD-V-101 CR 1815 INS LINE VENT CRD-799 CRD CRD-V-101 CR 2215 INS LINE VENT CRD-800 CRD CRD-V-101 CR 2615 INS LINE VENT CRD-801 CRD CRD-V-101 CR 3015 INS LINE VENT CRD-802 CRD CRD-V-101 CR 3415 INS LINE VENT CRD-803 CRD CRD-V-101 CR 3815 INS LINE VENT CRD-804 CRD CRD-V-101 CR 4215 INS LINE VENT CRD-805 CRD CRD-V-101 CR 4615 INS LINE VENT CRD-806 CRD CRD-V-101 CR 5015 INS LINE VENT CRD-807 CRD CRD-V-101 CR 5415 INS LINE VENT CRD-808 CRD CRD-V-101 CR 0219 INS LINE VENT CRD-809 CRD CRD-V-101 CR 0619 INS LINE VENT CRD-810 CRD CRD-V-101 CR 1019 INS LINE VENT CRD-811 CRD CRD-V-101 CR 1419 INS LINE VENT CRD-812 CRD CRD-V-101 CR 1819 INS LINE VENT CRD-813 CRD CRD-V-101 CR 2219 INS LINE VENT CRD-814 CRD CRD-V-101 CR 2619 INS LINE VENT CRD-815 CRD CRD-V-101 CR 3019 INS LINE VENT CRD-816 CRD CRD-V-101 CR 3419 INS LINE VENT CRD-817 CRD CRD-V-101 CR 3819 INS LINE VENT CRD-818 CRD CRD-V-101 CR 4219 INS LINE VENT CRD-819 CRD CRD-V-101 CR 4619 INS LINE VENT CRD-820 CRD CRD-V-101 CR 5019 INS LINE VENT CRD-821 CRD CRD-V-101 CR 5419 INS LINE VENT CRD-822 CRD CRD-V-101 CR 5819 INS LINE VENT CRD-823 CRD CRD-V-101 CR 0223 INS LINE VENT CRD-824 CRD CRD-V-101 CR 0623 INS LINE VENT CRD-825 CRD CRD-V-101 CR 1023 INS LINE VENT CRD-826 CRD CRD-V-101 CR 1423 INS LINE VENT CRD-827 CRD CRD-V-101 CR 1823 INS LINE VENT November 16, 1994 Page 21 of 51

APPENDIX C ATTACHMENTC-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID SYSTEM DESCRIPTION CRD-828 CRD CRD-V-101 CR 2223 INS LINE VENT CRD-829 CRD CRD-V-101 CR 2623 INS LINE VENT CRD-830 CRD CRD-V-101 CR 3023 INS LINE VENT CRD-831 CRD CRD-V-101 CR 3423 INS LINE VENT CRD-832 CRD CRD-V-101 CR 3823 INS LINE VENT CRD-833 CRD CRD-V-101 CR 4223 INS LINE VENT CRD-834 CRD CRD-V-101 CR 4623 INS LINE VENT CRD-835 CRD CRD-V-101 CR 5023 INS LINE VENT CRD-836 CRD CRD-V-101 CR 5423 INS LINE VENT CRD-837 CRD CRD-V-101 CR 5823 INS LINE VENT CRD-838 CRD CRD-V-101 CR 0227 INS LINE VENT CRD-839 CRD CRD-V-101 CR 0627 INS LINE VENT CRD-840 CRD CRD-V-101 CR 1027 INS LINE VENT CRD-841 CRD CRD-V-101 CR 1427 INS LINE VENT CRD-842 CRD CRD-V-101 CR 1827 INS LINE VENT CRD-843 CRD CRD-V-101 CR 2227 INS LINE VENT CRD-844 CRD CRD-V-101 CR 2627 INS LINE VENT CRD-845 CRD CRD-V-101 CR 3027 INS LINE VENT CRD-846 CRD CRD-V-101 CR 3427 INS LINE VENT CRD-847 CRD CRD-V-101 CR 3827 INS LINE VENT CRD-848 CRD CRD-V-101 CR 4227 INS LINE VENT CRD-849 CRD CRD-V-101 CR 4627 INS LINE VENT CRD-850 CRD CRD-V-101 CR 5027 INS LINE VENT CRD-851 CRD CRD-V-101 CR 5427 INS LINE VENT CRD-852 CRD CRD-V-101 CR 5827 INS LINE VENT CRD-853 CRD CRD-V-101 CR 0231 INS LINE VENT CRD-854 CRD CRD-V-101 CR 0631 INS LINE VENT CRD-855 CRD CRD-V-101 CR 1031 INS LINE VENT CRD-856 CRD CRD-V-101 CR 1431 INS LINE VENT CRD-857 CRD CRD-V-101 CR 1831 INS LINE VENT CRD-858 CRD CRD-V-101 CR 2231 INS LINE VENT CRD-859 CRD CRD-V-101 CR 2631 INS LINE VENT CRD-860 CRD CRD-V-101 CR 3031 INS LINE VENT CRD-861 CRD CRD-V-101 CR 3431 INS LINE VENT CRD-862 CRD CRD-V-101 CR 3831 INS LINE VENT CRD-863 CRD CRD-V-101 CR 4231 INS LINE VENT CRD-864 CRD CRD-V-101 CR 4631 INS LINE VENT CRD-865 CRD CRD-V-101 CR 5031 INS LINE VENT CRD-866 CRD CRD-V-101 CR 5431 INS LINE VENT CRD-867 CRD CRD-V-101 CR 5831 INS LINE VENT CRD-868 CRD CRD-V-101 CR 0235 INS LINE VENT CRD-869 CRD CRD-V-101 CR 0635 INS LINE VENT CRD-870 CRD CRD-V-101 CR 1035 INS LINE VENT November 16, 1994 Page 22 of 51

APPENDIX C ATTACHMENTC-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID SYSTEM DESCRIPTION CRD-871 CRD CRD-V-101 CR 1435 INS LINE VENT CRD-872 CRD CRD-V-101 CR 1835 INS LINE VENT CRD-873 CRD CRD-V-101 CR 2235 INS LINE VENT CRD-874 CRD CRD-V-101 CR 2635 INS LINE VENT CRD-875 CRD CRD-V-101 CR 3035 INS LINE VENT CRD-876 CRD CRD-V-101 CR 3435 INS LINE VENT CRD-877 CRD CRD-V-101 CR 3835 INS LINE VENT CRD-878 CRD CRD-V-101 CR 4235 INS LINE VENT CRD-879 CRD CRD-V-101 CR 4635 INS LINE VENT CRD-880 CRD CRD-V-101 CR 5035 INS LINE VENT CRD-881 CRD CRD-V-101 CR 5435 INS LINE VENT CRD-882 CRD CRD-V-101 CR 5835 INS LINE VENT CRD-883 CRD CRD-V-101 CR 0239 INS LINE VENT CRD-884 CRD CRD-V-101 CR 0639 INS LINE VENT CRD-885 CRD CRD-V-101 CR 1039 INS LINE VENT CRD-886 CRD CRD-V-101 CR 1439 INS LINE VENT CRD-887 CRD CRD-V-101 CR 1839 INS LINE VENT CRD-888 CRD CRD-V-101 CR 2239 INS LINE VENT CRD-889 CRD CRD-V-101 CR 2639 INS LINE VENT CRD-890 CRD CRD-V-101 CR 3039 INS LINE VENT CRD-891 CRD CRD-V-101 CR 3439 INS LINE VENT CRD-892 CRD CRD-V-101 CR 3839 INS LINE VENT CRD-893 CRD CRD-V-101 CR 4239 INS LINE VENT CRD-894 CRD CRD-V-101 CR 4639 INS LINE VENT CRD-895 CRD CRD-V-101 CR 5039 INS LINE VENT CRD-896 CRD CRD-V-101 CR 5439 INS LINE VENT CRD-897 CRD CRD-V-101 CR 5839 INS LINE VENT CRD-898 CRD CRD-V-101 CR 0243 INS LINE VENT CRD-899 CRD CRD-V-101 CR 0643 INS LINE VENT CRD-900 CRD CRD-V-101 CR 1043 INS LINE VENT CRD-901 CRD CRD-V-101 CR 1443 INS LINE VENT CRD-902 CRD CRD-V-101 CR 1843 INS LINE VENT CRD-903 CRD CRD-V-101 CR 2243 INS LINE VENT CRD-904 CRD CRD-V-101 CR 2643 INS LINE VENT CRD-905 CRD CRD-V-101 CR 3043 INS LINE VENT CRD-906 CRD CRD-V-101 CR 3443 INS LINE VENT CRD-907 CRD CRD-V-101 CR 3843 INS LINE VENT CRD-908 CRD CRD-V-101 CR 4243 INS LINE VENT CRD-909 CRD CRD-V-101 CR 4643 INS LINE VENT CRD-910 CRD CRD-V-101 CR 5043 INS LINE VENT CRD-911 CRD CRD-V-101 CR 5443 INS LINE VENT CRD-912 CRD CRD-V-101 CR 5843 INS LINE VENT CRD-913 CRD CRD-V-101 CR 0647 INS LINE VENT November 16, 1994 Page 23 of 51

APPENDIX C ATTACHMENTC-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID SYSTEM DESCRIPTION CRD-914 CRD CRD-V-101 CR 1047 INS LINE VENT CRD-915 CRD CRD-V-101 CR 1447 INS LINE VENT CRD-916 CRD CRD-V-101 CR 1847 INS LINE VENT CRD-917 CRD CRD-V-101 CR 2247 INS LINE VENT CRD-918 CRD CRD-V-101 CR 2647 INS LINE VENT CRD-919 CRD CRD-V-101 CR 3047 INS LINE VENT CRD-920 CRD CRD-V-101 CR 3447 INS LINE VENT CRD-921 CRD CRD-V-101 CR 3847 INS LINE VENT CRD-922 CRD CRD-V-101 CR 4247 INS LINE VENT CRD-923 CRD CRD-V-101 CR 4647 INS LINE VENT CRD-924 CRD CRD-V-101 CR 5047 INS LINE VENT CRD-925 CRD CRD-V-101 CR 5447 INS LINE VENT CRD-926 CRD CRD-V-101 CR 1051 INS LINE VENT CRD-927 CRD CRD-V-101 CR 1451 INS LINE VENT CRD-928 CRD CRD-V-101 CR 1851 INS LINE VENT CRD-929 CRD CRD-V-101 CR 2251 INS LINE VENT CRD-930 CRD CRD-V-101 CR 2651 INS LINE VENT CRD-931 CRD CRD-V-101 CR 3051 INS LINE VENT CRD-932 CRD CRD-V-101 CR 3451 INS LINE VENT CRD-933 CRD CRD-V-101 CR 3851 INS LINE VENT CRD-934 CRD CRD-V-101 CR 4251 INS LINE VENT CRD-935 CRD CRD-V-101 CR 4651 INS LINE VENT CRD-936 CRD CRD-V-101 CR 5051 INS LINE VENT CRD-937 CRD CRD-V-101 CR 1455 INS LINE VENT CRD-938 CRD CRD-V-101 CR 1855 INS LINE VENT CRD-939 CRD CRD-V-101 CR 2255 INS LINE VENT CRD-940 CRD CRD-V-101 CR 2655 INS LINE VENT CRD-941 CRD CRD-V-101 CR 3055 INS LINE VENT CRD-942 CRD CRD-V-101 CR 3455 INS LINE VENT CRD-943 CRD CRD-V-101 CR 3855 INS LINE VENT CRD-944 CRD CRD-V-101 CR 4255 INS LINE VENT CRD-945 CRD CRD-V-101 CR 4655 INS LINE VENT CRD-946 CRD CRD-V-101 CR 1859 INS LINE VENT CRD-947 CRD CRD-V-101 CR 2259 INS LINE VENT CRD-948 CRD CRD-V-101 CR 2659 INS LINE VENT CRD-949 CRD CRD-V-101 CR 3059 INS LINE VENT CRD-950 CRD CRD-V-101 CR 3459 INS LINE VENT CRD-951 CRD CRD-V-101 CR 3859 INS LINE VENT CRD-952 CRD CRD-V-101 CR 4259 INS LINE VENT CRD-953 CRD CRD-P-1A 0/C RESET CRD-954 CRD CRD-P-1B 0/C RESET CSS-001 CSS-002 CSS CSS LPCS-V-5 INJ LINE VLV ~

HPCS-V-4 INJ LINE VLVMAN OPEN OPEN November 16, 1994 Page 24 of 51

APPENDIX C ATTACHMENTC-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID SYSTEM DESCRIPTION CSS-003 CSS HPCS-V-51 IN CI'MT MANUALSHUTOFF CSS-004 CSS LPCS-V-51 IN CI'MT MANUALSHUTOFF CSS-005 CSS HPCS-P-1 0/C RESET CSS-006 CSS HPCS-P-3 0/C RESET CSS-007 CSS LPCS-P-2 0/C RESET CSS-008 CSS LPCS-P-1 0/C RESET CWS-001 CWS CBD-LCV-1 CIRC WTR BLOWDOWN VLV CWS-002 CWS CBD-V-2 CBD-LCV-1 ISOL VLV CWS-003 CWS CBD-V-3 CBD-LCV-1 BYPASS VLV CWS-004 CWS TMU-V-4TMU S/U LUB WTR SUP VLV CWS-005 CWS TMU-V-5 TMU-LCV-2AISOL VLV CWS-006 CWS TMU-V-9TMU-LCV-2ABYP VLV CWS-007 CWS TMU-V-10ASPRAY POND FILL CWS-008 CWS TMU-V-10B SPRAY POND FILL CWS-009 CWS TMU-V-103AWEIR BOX SLUICE GATE CWS-010 CWS TMU-V-103B WEIR BOX SLUICE GATE CWS-011 CWS CW-FN-1 0/C RESET CWS-012 CWS CW-FN-2 0/C RESET CWS-013 CWS CW-FN-3 0/C RESET CWS-014 CWS CW-FN-4 0/C RESET CWS-015 CWS CW-FN-5 0/C RESET CWS-016 CWS CW-FN-6 0/C RESET CWS-017 CWS CW-FN-7 0/C RESET CWS-018 CWS CW-FN-8 0/C RESET CWS-019 CWS CW-FN-9 0/C RESET CWS-020 CWS CW-FN-10 0/C RESET CWS-021 CWS CW-FN-11 0/C RESET CWS-022 CWS CW-FN-12 0/C RESET CWS-023 CWS CW-FN-13 0/C RESET CWS-024 CWS CW-FN-14 0/C RESET CWS-025 CWS CW-FN-15 0/C RESET CWS-026 CWS CW-FN-16 0/C RESET CWS-027 CWS CW-FN-17 0/C RESET CWS-028 CWS CW-FN-18 0/C RESET CWS-029 CWS CW-FN-19 0/C RESET CWS-030 CWS CW-FN-20 0/C RESET CWS-031 CWS CW-FN-21 0/C RESET CWS-032 CWS CW-FN-22 0/C RESET CWS-033 CWS CW-FN-23 0/C RESET CWS-034 CWS CW-FN-24 0/C RESET CWS-035 CWS CW-FN-25 0/C RESET CWS-036 CWS CW-FN-26 0/C RESET CWS-037 CWS CW-FN-27 0/C RESET November 16, 1994 Page 25 of 51

APPENDIX C ATTACHMENTC-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID SYSTEM DESCRIPTION CWS-038 CWS CW-FN-28 0/C RESET CWS-039 CWS CW-FN-29 0/C RESET CWS-040 CWS CW-FN-30 0/C RESET CWS-041 CWS CW-FN-31 0/C RESET CWS-042 CWS CW-FN-32 0/C RESET CWS-043 CWS CW-FN-33 0/C RESET CWS-044 CWS CW-FN-34 0/C RESET CWS-045 CWS CW-FN-35 0/C RESET CWS-046 CWS CW-FN-36 0/C RESET CWS-047 CWS TMU-P-1A 0/C RESET CWS-048 CWS TMU-P-1B 0/C RESET CWS-049 CWS TMU-P-1C 0/C RESET DEH-001 DEH DEH PRESS CONTROLLER A OR B SEL DEH-002 DEH MANTURBINE TRIP AT FRONT STNDRD DEH-003 DEH DEH-P-1A 0/C RESET DEH-004 DEH DEH-P-1B 0/C RESET DEH-005 DEH DEH-FN-1A 0/C RESET DEH-006 DEH DEH-FN-1B 0/C RESET DGN-001 DGN BKR DG1-7 RACKED OUT DGN-002 DGN BKR DG2-8 RACKED OUT DGN-003 DGN BKR 4-DG3 RACKED OUT DGN-004 DGN BKR 4-DG3 DG3 BREAKER CONTROL DGN-005 DGN BKR DG1-7 DG1 BREAKER CONTROL DGN-006 DGN BKR DG2-8 DG2 BREAKER CONTROL DGN-007 DGN DG1 MODE SELECl'EY SWITCH DGN-008 DGN DG2 MODE SELECT KEY SWITCH DGN-009 DGN DG3 MODE SELECT SWITCH DON-010 DGN DGl LOCKOUT RLY & OVR SPD RESET DGN-011 DGN DG2 LOCKOUT RLY & OVR SPD RESET DGN-012 DGN DG3 LOCKOUT RLY & OVR SPD RESET DGN-013 DGN DG1 EMERGENCY STOP PUSHBUTTON DGN-014 DGN DG2 EMERGENCY STOP PUSHBVITON DGN-015 DGN DG3 EMERGENCY STOP PUSHBVITON DGN-016 DGN DG-1 LOCAL START PUSHBUTI'ON DGN-017 DGN DG-2 LOCAL START PUSHBUTI'ON DGN-018 DGN DG-3 LOCALSTART PUSHBUITON DGN-019 DGN DG1 ENGINE CONTROL SELECT DGN-020 DGN DG2 ENGINE CONTROL SELECT DGN-021 DGN DG1 EMERGENCY BYPASS SELECT DGN-022 DGN DG2 EMERGENCY BYPASS SELECT DGN-023 DGN DG1 EXCITATIONMODE SELECTOR DGN-024 DGN DG2 EXCITATIONMODE SELECTOR DGN-025 DGN DG3 GOVERNOR DROOP SWITCH November 16, 1994 Page 26 of 51

APPENDIX C ATTACHMENTC-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID SYSTEM DESCRIPTION DGN-026 DGN DG1 ENGINE SPEED SELECI'OR DGN-027 DGN DG2 ENGINE SPEED SELECI'OR EPS-001 EPS BATI'ERYBO-1A DISC EPS-002 EPS BATI'ERYBO-1A FUSE EPS-003 EPS BATTERY BO-1B DISC EPS-004 EPS BATI'ERYBO-1B FUSE EPS-005 EPS BATI'ERYBO-2A DISC EPS-006 EPS BATI'ERYBO-2A FUSE EPS-007 EPS BATI'ERYBO-2B DISC EPS-008 EPS BATI'ERYBO-2B FUSE EPS-009 EPS BATTERY B 1-1 DISC EPS-010 EPS BATl'ERYB 1-1 FUSE EPS-011 EPS BATl'ERYB 1-2 DISC EPS-012 EPS BATI'ERYB 1-2 FUSE EPS-013 EPS BATI'ERYB 1-3 OUTPUT BKR 0/C EPS-014 EPS BATI'ERYB 1-7 DISC EPS-015 EPS BATl'ERY B 1-7 FUSE EPS-016 EPS BATI'ERYB2-1 DISC EPS-017 EPS BATI'ERYB2-1 FUSE EPS-018 EPS BKR 52-1-11 0/C RESET EPS-019 EPS BKR 52-1-500S 0/C RESET EPS-020 EPS BKR 52-1-7 0/C RESET EPS-021 EPS BKR 52-11-1 0/C RESET EPS-022 EPS BKR 52-2-21 0/C RESET EPS-023 EPS BKR 52-2-4 0/C RESET EPS-024 EPS BKR 52-21-11 0/C RESET EPS-025 EPS BKR 52-21-2 0/C RESET EPS-026 EPS BKR 52-3-31 0/C RESET EPS-027 EPS BKR 52-3-8 0/C RESET EPS-028 EPS BKR 52-31-21 0/C RESET EPS-029 EPS BKR 52-31-3 0/C RESET EPS-030 EPS BKR 52-5-53 0/C RESET EPS-031 EPS BKR 52-6-63 0/C RESET EPS-032 EPS BKR 52-CTA 0/C RESET EPS-033 EPS BKR 52-CTB 0/C RESET EPS-034 EPS BKR 52N1-1 0/C RESET EPS-035 EPS BKR 52N1-2 0/C RESET EPS-036 EPS BKR 52N1-3 0/C RESET EPS-037 EPS BKR 52N2-5 0/C RESET EPS-038 EPS BKR 52N2-6 0/C RESET EPS-039 EPS BKR 52S-1 0/C RESET EPS-040 EPS BKR 52S-2 0/C RESET EPS-041 EPS BKR 52$ -3 0/C RESET November 16, 1994 Page 27 of 51

0 APPENDIX C ATTACHMENTC-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID SYSTEM DESCRIPTION EPS-042 EPS BKR 52S-5 0/C RESET EPS-043 EPS BKR 52$ -6 0/C RESET EPS-044 EPS BKR CB-4-2 0/C RESET EPS-045 EPS BKR CB-4-41 0/C RESET EPS-046 EPS BKR CB-LF1A 0/C RESET EPS-047 EPS BKR CB-LF1B 0/C RESET EPS-048 EPS BKR CB-LF2A 0/C RESET EPS-049 EPS BKR CB-LF2B 0/C RESET EPS-050 EPS BKR CB-RPT-3A 0/C RESET EPS-051 EPS BKR CB-RPT-3B 0/C RESET EPS-052 EPS BKR CB-RPTAA 0/C RESET EPS-053 EPS BKR CB-RPT-4B 0/C RESET EPS-054 EPS BKR CB-RRA 0/C RESET EPS-055 EPS BKR CB-RRB 0/C RESET EPS-056 EPS BKR CS-3-500S 0/C RESET EPS-057 EPS BKR CS-7-1 0/C RESET EPS-058 EPS BKR CS-7-71 0/C RESET EPS-059 EPS BKR CS-7-73 0/C RESET EPS-060 EPS BKR CS-7-75/1 0/C RESET EPS-061 EPS BKR CS-7-DG1 0/C RESET EPS-062 EPS BKR CS-75-72 0/C RESET EPS-063 EPS BKR CS-8-3 0/C RESET EPS-064 EPS BKR CS-8-81 0/C RESET EPS-065 EPS BKR CS-8-83 0/C RESET EPS-066 EPS BKR CS-8-85/1 0/C RESET EPS-067 EPS BKR CS-8-DG2 0/C RESET EPS-068 EPS BKR CS-85-82 0/C RESET EPS-069 EPS BKR CS-B-7 0/C RESET EPS-070 EPS BKR CS-B-8 0/C RESET EPS-071 EPS CHARGER CO-1A INPUT BKR 0/C EPS-072 EPS CHARGER CO-1A OUTPUT BKR 0/C EPS-073 EPS CHARGER CO-1B INPUT BKR 0/C EPS-074 EPS CHARGER CO-1B OUTPUT BKR 0/C EPS-075 EPS CHARGER CO-2A INPUT BKR 0/C EPS-076 EPS CHARGER CO-2A OUTPUT BKR 0/C EPS-077 EPS CHARGER CO-2B INPUT BKR 0/C EPS-078 EPS CHARGER CO-2B OUTPUT BKR 0/C EPS-079 EPS CHARGER C 1-1 FUSE EPS-080 EPS CHARGER C 1-1 INPUT BKR 0/C EPS-081 EPS CHARGER Cl-1 INPUT DISC EPS-082 EPS CHARGER Cl-1 OUTPUT BKR 0/C EPS-083 EPS CHARGER Cl-1 OUTPUT DISC EPS-084 EPS CHARGER Cl-2 FUSE November 16, 1994 Page 28 of 51

APPENDIX C ATIACHMENT C-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACI'IONS LISTING ID SYSTEM DESCRIPTION EPS-085 EPS CHARGER Cl-2 INPUT BKR 0/C EPS-086 EPS CHARGER Cl-2 INPUT DISC EPS-087 EPS CHARGER Cl-2 OUTPUT BKR 0/C EPS-088 EPS CHARGER Cl-2 OUTPUT DISC EPS-089 EPS CHARGER Cl-7 FUSE EPS-090 EPS CHARGER Cl-7 INPUT DISC EPS-091 EPS CHARGER C 1-7 OUTPUT DISC EPS-092 EPS CHARGER Cl-HPCS INPUT BKR 0/C EPS-093 EPS CHARGER Cl-HPCS OUTPUT BKR 0/C EPS-094 EPS CHARGER C2-1 FUSE EPS-095 EPS CHARGER C2-1 INPUT BKR 0/C EPS-096 EPS CHARGER C2-1 INPUT DISC EPS-097 EPS CHARGER C2-1 OUTPUT BKR 0/C EPS-098 EPS CHARGER C2-1 OUTPUT DISC EPS-099 EPS IN1 KIRKKEY EPS-100 EPS IN1 MAINTENANCESW EPS-101 EPS IN1 STATIC SWITCH EPS-102 EPS INl-CB1 MC-7A NORM INPT AC 0/C EPS-103 EPS IN1-CB2 DP-S2-1 NORM DC 0/C EPS-104 EPS IN1-CB3 INV OUTPUT 0/C EPS-105 EPS IN1-CB4 ALT AC OUT 0/C EPS-106 EPS IN1-MIS MAINTBYPASS 0/C EPS-107 EPS IN2 MANUALXFER SWITCH EPS-108 EPS IN2 STATIC SWITCH EPS-109 EPS IN2-CB1 lN2 NORM DC BKR 0/C EPS-110 EPS IN3 MANUALXFER SWITCH EPS-111 EPS IN3 STATIC SWITCH EPS-112 EPS IN3-CB1 IN3 NORM DC BKR 0/C EPS-113 EPS MC-1A DISC DEH-P-1A EPS-114 EPS MC-1A DISC HY-P-A2/3 EPS-115 EPS MC-1A DISC HY-P-B2/3 EPS-116 EPS MC-1A DISC TO-BOP-1 EPS-117 EPS MC-1A DISC TO-EX-1A EPS-118 EPS MC-1A DISC TO-SOBP-1 EPS-119 EPS MC-1B DISC RFT-MOP-1A EPS-120 EPS MC-1B DISC RFT-TNG-1A EPS-121 EPS MC-1E DISC HD-V-15A EPS-122 EPS MC-2B DISC COND-V-135C EPS-123 EPS MC-2C DISC DEH-P-1B EPS-124 EPS MC-2C DISC RFW-V-112B EPS-125 EPS MC-2D DISC SCW-P-2 EPS-126 EPS MC-2D DISC TO-EX-4 EPS-127 EPS MC-2P DISC CAS-C-1 c November 16, 1994 Page 29 of 51

APPENDIX C ATTACHMENTC-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID SYSTEM DESCRIPTION EPS-128 EPS MC-2P DISC RFT-MOP-18 EPS-129 EPS MC-2P DISC RFT-TNG-1B EPS-130 EPS MC-2R DISC BF-1B EPS-131 EPS MC-2R-A DISC COND-V-1408 EPS-132 EPS MC-3A DISC COND-V-140A EPS-133 EPS MC-38 DISC BF-1A EPS-134 EPS MC-38 DISC TG-TNG-1 EPS-135 EPS MC-3C DISC AR-EX-1A EPS-136 EPS MC-3C DISC TG-ASOP-1 EPS-137 EPS MC-4A DISC HPCS-P-3 EPS-138 EPS MC-4A BKR HPCS-V-1 RACKOUT EPS-139 EPS MC-4A BKR HPCS-V-15 RACKOUT EPS-140 EPS MC-4A BKR HPCS-V-4 RACKOUT EPS-141 EPS MC-5L DISC CW-FN-21 EPS-142 EPS MC-5M DISC CW-FN-23 EPS-143 EPS MC-5N DISC FP-P-2A EPS-144 EPS MC-5P DISC CW-FN-25 EPS-145 EPS MC-SQ DISC CW-FN-29 EPS-146 EPS MC-5R DISC CW-V-7 EPS-147 EPS MC-68 DISC TR-68-E EPS-148 EPS MC-6L DISC CW-FN-2 EPS-149 EPS MC-6M DISC CW-FN-14 EPS-150 EPS MC-6N DISC FP-P-28 EPS-151 EPS MC-6P DISC CW-FN-7 EPS-152 EPS MC-6Q DISC CW-FN-11 EPS-153 EPS MC-6R DISC CW-V-4 EPS-154 EPS MC-7A BKR MC-7A-A0/C EPS-155 EPS MC-7A DISC CAS-C-1A EPS-156 EPS MC-7A DISC IN1 NORM AC EPS-157 EPS MC-7A DISC RFW-V-65A EPS-158 EPS MC-7A DISC RFW-V-658 EPS-159 EPS MC-7A DISC RPS-MG-A EPS-160 EPS MC-7A DISC SW-V-12A EPS-161 EPS MC-7A DISC SW-V-2A EPS-162 EPS MC-7A DISC TR-7A EPS-163 EPS MC-7A DISC TR-7A-C EPS-164 EPS MC-7A-A DISC SW-V-4A EPS-165 EPS MC-78 DISC CIA-V-20 EPS-166 EPS MC-78 DISC CIA-V-30A EPS-167 EPS MC-78 DISC CRA-FN-1A-1 EPS-168 EPS MC-78 DISC CRA-FN-2A-2 EPS-169 EPS MC-78 DISC LPCS-P-2 EPS-170 EPS MC-78 DISC RCIC-P-3 November 16, 1994 Page 30 of 51

APPENDIX C ATTACHMENTC-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID SYSTEM DESCRIPTION EPS-171 EPS MC-78 DISC SLC-P-1A EPS-172 EPS MC-78-A DISC LPCS-V-1 EPS-173 EPS MC-78-A DISC LPCS-V-5 EPS-174 EPS MC-78-A DISC PP-7A-Z EPS-175 EPS MC-78-A DISC RCC-V-5 EPS-176 EPS MC-78-A DISC RHR-FCV-64A EPS-177 EPS MC-78-A DISC RHR-V-24A EPS-178 EPS MC-78-A DISC RHR-V-27A EPS-179 EPS MC-78-A DISC RHR-V-42A EPS-180 EPS MC-78-A DISC RHR-V-4A EPS-181 EPS MC-78-A DISC RHR-V-53A EPS-182 EPS MC-78-A DISC RHR-V-538 EPS-183 EPS MC-78-A DISC RHR-V-6A EPS-184 EPS MC-78-8 DISC RHR-V-3A EPS-185 EPS MC-78-8 DISC SGT-FN-1A-1 EPS-186 EPS MC-78-8 DISC SGT-FN-18-1 EPS-187 EPS MC-78-8 DISC SGT-V-3A-1 EPS-188 EPS MC-7C DISC RRA-FN-8 EPS-189 EPS MC-7C DISC RRC-V-67A EPS-190 EPS MC-7C-A DISC CN-V-51 EPS-191 EPS MC-7C-8 DISC TSW-V-64A EPS-192 EPS MC-7E DISC WEA-FN-lA EPS-193 EPS MC-7F DISC IN1 ALTSUPP EPS-194 EPS MC-7F DISC WEA-FN-53A EPS-195 EPS MC-7F DISC WMA-FN-51A EPS-196 EPS MC-7F DISC WMA-FN-53A EPS-197 EPS MC-7F DISC WMA-FN-54A EPS-198 EPS MC-7R/MC-8R DISC PP-78 EPS-199 EPS MC-8A BKR MC-8A-A0/C EPS-200 EPS MC-8A DISC CAS-C-18 EPS-201 EPS MC-8A DISC CJW-P-18 EPS-202 EPS MC-8A DISC RPS-MG-2 EPS-203 EPS MC-8A DISC SW-V-128 EPS-204 EPS MC-8A DISC SW-V-28 EPS-205 EPS MC-8A DISC TR-8A EPS-206 EPS MC-8A-A DISC SW-V-48 EPS-207 EPS MC-88 DISC CRA-FN-18-1 EPS-208 EPS MC-88 DISC CRA-FN-18-2 EPS-209 EPS MC-88 DISC CRA-FN-28-1 EPS-210 EPS MC-88 DISC CRA-FN-28-2 EPS-211 EPS MC-88 DISC PP-8A-Z EPS-212 EPS MC-88 DISC RHR-P-3 EPS-213 EPS MC-88 DISC SLC-P-18 November 16, 1994 Page 31 of 51

APPENDIX C ATTACHMENTC-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID SYSTEM DESCRIPTION EPS-214 EPS MC-8B-A DISC RCIC-V-63 EPS-215 EPS MC-8B-A DISC RHR-V-16B EPS-216 EPS MC-8B-A DISC RHR-V-17B EPS-217 EPS MC-8B-A DISC RHR-V-24B EPS-218 EPS MC-8B-A DISC RHR-V-27B EPS-219 EPS MC-8B-A DISC RHR-V-42B EPS-220 EPS MC-8B-A DISC RHR-V-42C EPS-221 EPS MC-8B-A DISC RHR-V-4B EPS-222 EPS MC-8B-A DISC RHR-V-4C EPS-223 EPS MC-8B-A DISC RHR-V-64B EPS-224 EPS MC-8B-A DISC RHR-V-64C EPS-225 EPS MC-8B-A DISC RHR-V-6B EPS-226 EPS MC-8B-A DISC RHR-V-9 EPS-227 EPS MC-8B-A DISC RWCU-V-1 EPS-228 EPS MC-8B-B DISC RHR-V-3B EPS-229 EPS MC-8B-B DISC SGT-FN-1A-2 EPS-230 EPS MC-8B-B DISC SGT-FN-1B-2 EPS-231 EPS MC-8B-B DISC SGT-V-3A-2 EPS-232 EPS MC-8C BKR RWCU-P-1A RACKOUT EPS-233 EPS MC-8C BKR RWCU-P-1B RACKOUT EPS-234 EPS MC-8C DISC HY-P-Al/3 EPS-235 EPS MC-8C DISC RRA-FN-9 EPS-236 EPS MC-8C DISC RRC-V-23A EPS-237 EPS MC-8C-A DISC HY-P-B1/3 EPS-238 EPS MC-8C-B DISC TSW-V-64B EPS-239 EPS MC-8C-B DISC TSW-V-64C EPS-240 EPS MC-8E DISC WEA-FN-1B EPS-241 EPS MC-8E DISC WEA-FN-1C EPS-242 EPS MC-8F DISC WEA-FN-53B EPS-243 EPS MC-8F DISC WMA-FN-51B EPS-244 EPS MC-8F DISC WMA-FN-53B EPS-245 EPS MC-8F DISC WMA-FN-54B EPS-246 EPS MC-S1-1D DISC RCC-V-6 EPS-247 EPS MC-S1-1D DISC RCIC-V-10 EPS-248 EPS MC-S1-1D DISC RCIC-V-68 EPS-249 EPS MC-S1-1D DISC RCIC-V-8 EPS-250 EPS MC-S1-2D DISC CAC-V-11 EPS-251 EPS MC-S2-1A DISC RCIC-P-4 EPS-252 EPS MC-S2-1A DISC RCIC-V-1 EPS-253 EPS MC-S2-1A DISC RCIC-V-13 EPS-254 EPS MC-S2-1A DISC RCIC-V-45 EPS-255 EPS MC-S2-1A DISC RHR-V-8 EPS-256 EPS MC-S2-1A DISC RWCU-V-4 November 16, 1994 Page 32 of 51

APPENDIX C ATTACHMENTC-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID SYSTEM DESCRIPTION EPS-257 EPS MC-S2-1B DISC RFT-EOP-1A EPS-258 EPS MC-S2-1B DISC RFT-EOP-1B EPS-259 EPS MC-S2-1B DISC TG-ASOBP-1 BPS-260 EPS MC-S2-1B DISC TO-P-1 EPS-261 EPS PP-7A DISC C0-1A,1B EPS-262 EPS PP-7A DISC IN-3 EPS-263 EPS PP-8A DISC C0-2A,2B BPS-264 EPS PP-8A DISC IN-2 EPS-265 BPS RPS-CB-2A RPS-A TRIP SYS BKR 0/C EPS-266 EPS RPS-CB-2B RPS-B TRIP SYS BKR 0/C EPS-267 EPS RPS-CB-3A PWR RNG DIV 1 BKR 0/C EPS-268 BPS RPS-CB-3B PWR RNG DIV 2 BKR 0/C EPS-269 EPS RPS-CB-5A NS4 INBD BKR 0/C EPS-270 EPS RPS-CB-5B NS4 OTBD BKR 0/C EPS-271 EPS RPS-CB-6A PRM DIV 1 BKR 0/C EPS-272 EPS RPS-CB-6B PRM DIV2 BKR 0/C EPS-273 EPS RPS-CB-7A NS4 OTBD BKR 0/C EPS-274 EPS RPS-CB-7B NS4 INBD BKR 0/C EPS-275 EPS RPS-CB-CB1 ALTSUP BKR 0/C EPS-276 EPS RPS-CB-MG1 MG-A OUTPT BKR 0/C EPS-277 EPS RPS-CB-MG2 MG-B OUTPT BKR 0/C EPS-278 EPS RPS-EPA-3A RPS-A EPA-3A 0/C EPS-279 EPS RPS-EPA-3B RPS-B EPA-3B 0/C EPS-280 EPS RPS-EPA-3C RPS-A EPA-3C 0/C EPS-281 EPS RPS-EPA-3D RPS-B EPA-3D 0/C EPS-282 EPS RPS-EPA-3E ALTRPS BPA-3E 0/C BPS-283 EPS RPS-EPA-3F ALTRPS EPA-3F 0/C EPS-284 EPS RPS-MS-1 RPS-MG-A START SW EPS-285 EPS RPS-MS-2 RPS-MG-B START SW EPS-286 EPS S 1-1 DISC DP-Sl-1A EPS-287 EPS S 1-1 DISC MC-S 1-1D EPS-288 EPS S1-2 DISC MC-S 1-2D EPS-289 EPS S1-3 DISC 4KV BKR CONTROL S004 EPS-290 EPS S1-7 DISC DP-Sl-2C EPS-291 EPS S2-1 DISC IN-1 EPS-292 EPS S2-1 DISC MC-S2-1A EPS-293 EPS S2-1 DISC MC-S2-1B EPS-294 EPS SH-05 BKR 5-53 RACKOUT EPS-295 EPS SH-05 BKR CTA RACKOUT EPS-296 EPS SH-05 BKR N2-5 RACKOUT EPS-297 EPS SH-05 BKR RRA RACKOUT EPS-298 EPS SH-05 BKR S-5 RACKOUT EPS-299 EPS SH-05 PT FUSE SH-5 November 16, 1994 Page 33 of 51

APPENDIX C ATTACHMENTC-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID SYSTEM DESCRIPTION EPS-300 EPS SH-06 BKR 6-63 RACKOUT EPS-301 EPS SH-06 BKR CTB RACKOUT EPS-302 EPS SH-06 BKR N2-6 RACKOUT EPS-303 EPS SH-06 BKR RRB RACKOUT EPS-304 EPS SH-06 BKR S-6 RACKOUT EPS-305 EPS SH-06 PT FUSE SH-6 EPS-306 EPS SH-09 BKR RPT-3A RACKOUT EPS-307 EPS SH-10 BKR RPT-3B RACKOUT EPS-308 EPS SH-ll BKR RPT-4A RACKOUT EPS-309 EPS SH-12 BKR RPT-4B RACKOUT EPS-310 EPS SH-13 BKR LF-2A RACKOUT EPS-311 EPS SH-14 BKR LF-2B RACKOUT EPS-312 EPS SL-11 BKR 11-1 RACKOUT EPS-313 EPS SL-11 BKR AR-P-1A RACKOUT EPS-314 EPS SL-21 BKR 21-11 RACKOUT EPS-315 EPS SL-21 BKR 21-2 RACKOUT EPS-316 EPS SL-21 BKR AR-P-1B RACKOUT EPS-317 EPS SL-31 BKR 31-21 RACKOUT EPS-318 EPS SL-31 BKR 31-3 RACKOUT EPS-319 EPS SL-31 BKR MC-SC 0/C EPS-320 EPS SL-51 BKR MC-5M 0/C EPS-321 EPS SL-'S2 BKR MC-5Q 0/C EPS-322 EPS SL-53 BKR WOA-FN-1A RACKOUT EPS-323 EPS SL-61 BKR MC-6M 0/C EPS-324 EPS SL-62 BKR MC-6Q 0/C EPS-325 EPS SL-63 BKR WOA-FN-1B RACKOUT EPS-326 EPS SL-71 BKR MC-7A-B 0/C EPS-327 EPS SL-71 BKR MC-7B 0/C EPS-328 EPS SL-71 BKR MC-7C 0/C EPS-329 EPS SL-71 BKR RCC-P-1A RACKOUT EPS-330 EPS SL-71 BKR REA-FN-1A RACKOUT EPS-331 EPS SL-73 BKR MC-7A 0/C EPS-332 EPS SL-73 BKR MC-7E 0/C EPS-333 EPS SL-73 BKR MC-7F 0/C EPS-334 EPS SL-73 BKR ROA-FN-1A RACKOUT EPS-335 EPS SL-81 BKR MC-8B 0/C EPS-336 EPS SL-81 BKR MC-8C 0/C EPS-337 EPS SL-81 BKR RCC-P-1B RACKOUT EPS-338 EPS SL-81 BKR RCC-P-1C RACKOUT EPS-339 EPS SL-83 BKR MC-8A 0/C EPS-340 EPS SL-83 BKR MC-8E 0/C EPS-341 EPS SL-83 BKR MC-8F 0/C EPS-342 EPS SL-83 BKR REA-FN-1B RACKOUT November 16, 1994 Page 34 of 51

APPENDIX C ATTACHMENTC-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID SYSTEM DESCRIPTION EPS-343 EPS SL-83 BKR ROA-FN-1B RACKOUT EPS-344 EPS SM-1 BKR 1-11 RACKOUT EPS-345 EPS SM-1 BKR 1-500S RACKOUT EPS-346 EPS SM-1 BKR 1-7 RACKOUT EPS-347 EPS SM-1 BKR C1A RACKOUT EPS-348 EPS SM-1 BKR CB2A RACKOUT EPS-349 EPS SM-1 BKR CW1A RACKOUT EPS-350 EPS SM-1 BKR LF-1A RACKOUT EPS-351 EPS SM-1 BKR Nl-1 RACKOUT EPS-352 EPS SM-1 BKR S-1 RACKOUT EPS-353 EPS SM-1 PT FUSE SM-1 EPS-354 EPS SM-2 BKR 2-21 RACKOUT EPS-355 EPS SM-2 BKR 2-4 RACKOUT EPS-356 EPS SM-2 BKR C1B RACKOUT EPS-357 EPS SM-2 BKR CB2B RACKOUT EPS-358 EPS SM-2 BKR CW1B RACKOUT EPS-359 EPS SM-2 BKR Nl-2 RACKOUT EPS-360 EPS SM-2 BKR S-2 RACKOUT EPS-361 EPS SM-2 PT FUSE SM-2 EPS-362 EPS SM-3 BKR 3-31 RACKOUT EPS-363 EPS SM-3 BKR 3-500S RACKOUT EPS-364 EPS SM-3 BKR 3-8 RACKOUT EPS-365 EPS SM-3 BKR C1C RACKOUT EPS-366 EPS SM-3 BKR CB2C RACKOUT EPS-367 EPS SM-3 BKR CW1C RACKOUT EPS-368 EPS SM-3 BKR LF-1B RACKOUT EPS-369 EPS SM-3 BKR Nl-3 RACKOUT EPS-370 EPS SM-3 BKR S-3 RACKOUT EPS-371 EPS SM-3 PT FUSE SM-3 EPS-372 EPS SM-4 BKR 4-2 RACKOUT EPS-373 EPS SM-4 BKR 4P1 RACKOUT EPS-374 EPS SM-4 BKR HPCS RACKOUT EPS-375 EPS SM-7 BKR 7-1 RACKOUT EPS-376 EPS SM-7 BKR 7-71 RACKOUT EPS-377 EPS SM-7 BKR 7-73 RACKOUT EPS-378 EPS SM-7 BKR 7-75/1 RACKOUT EPS-379 EPS SM-7 BKR 7-75/2 RACKOUT EPS-380 EPS SM-7 BKR 7-DG1 RACKOUT EPS-381 EPS SM-7 BKR B-7 RACKOUT EPS-382 EPS SM-7 BKR CRD-1A RACKOUT EPS-383 EPS SM-7 BKR LPCS RACKOUT EPS-384 EPS SM-7 BKR RHR-2A RACKOUT EPS-385 EPS SM-7 BKR SW-1A RACKOUT November 16, 1994 Page 35 of 51

APPENDIX C ATTACHMENTC-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID SYSTEM DESCRIPTION EPS-386 EPS SM-72 BKR TMU-1ARACKOUT EPS-387 EPS SM-75 BKR 75-72 RACKOUT EPS-388 EPS SM-75 BKR TSW-lA RACKOUT EPS-389 EPS SM-8 BKR 8-3 RACKOUT EPS-390 EPS SM-8 BKR 8-81 RACKOUT EPS-391 EPS SM-8 BKR 8-83 RACKOUT EPS-392 EPS SM-8 BKR 8-85/1 RACKOUT EPS-393 EPS SM-8 BKR 8-85/2 RACKOUT EPS-394 EPS SM-8 BKR 8-DG2 RACKOUT EPS-395 EPS SM-8 BKR B-8 RACKOUT EPS-396 EPS SM-8 BKR CRD-1B RACKOUT EPS-397 EPS SM-8 BKR RHR-2B RACKOUT EPS-398 EPS SM-8 BKR RHR-2C RACKOUT EPS-399 EPS SM-8 BKR SW1B RACKOUT EPS-400 EPS SM-82 BKR TMU-1B RACKOUT EPS-401 EPS SM-85 BKR 85-82 RACKOUT EPS-402 EPS SM-85 BKR TSW-1B RACKOUT EPS-403 EPS TMU-1C BKR RACKOUT EPS-404 EPS TMU-1C BUS SELECT EPS-405 EPS IN1-BTB MAINTBYPASS 0/C EPS-406 EPS IN1-MBP MAINTBYPASS 0/C EPS-407 EPS RRC-M-1A1 0/C RESET EPS-408 EPS RRC-M-1B1 0/C RESET EPS-409 EPS RPS-MG-1 0/C RESET EPS-410 EPS RPS-MG-2 0/C RESET EPS-411 EPS BKR 7-75/2 EPS-412 EPS BKR 8-85/2 EPS-413 EPS MC-8AADISC MS-V-146 EPS-414 EPS E-RMS-7FDA, IN-3 POWER EPS-415 EPS E-RMS-8FDA, IN-2 POWER FPC-001 FPC FPC-V-148 CONDENSER RETURN FPC-002 FPC FPC-V-114 PUMP X CONN FPC-003 FPC FPC-V-115A HX BYPASS FPC-004 FPC FPC-V-115B HX BYPASS FPC-005 FPC FPC-V-116A HX INLET ISOL FPC-006 FPC FPC-V-116B HX INLET ISOL FPC-007 FPC FPC-V-118A HX OUTLET ISOL FPC-008 FPC FPC-V-118B HX OUTLET ISOL FPC-009 FPC FPC-V-143 RX WELL RECIRC FPC-010 FPC FPC-V-141 X-TIE TO RHR FPC-011 FPC FPC-V-131 GATE DRAIN FPC-012 FPC FPC-V-105 WELL DRAIN FPC-013 FPC FPC-V-130 SURGE TANKDRAIN November 16, 1994 Page 36 of 51

APPENDIX C ATTACHMENTC-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID SYSTEM DESCRIPTION FPC-014 FPC FPC-V-142 FP RECIRC FPC-015 FPC FUEL POOL PLUG POSITION FPC-016 FPC FPC-V-147 WETWELL CLEANUP ISOL FPC-017 FPC FPC-P-1A 0/C RESET FPC-018 FPC FPC-P-1B 0/C RESET FPC-019 FPC FPC-P-3 0/C RESET FPS-001 FPS FP-P-1 DIESEL FIRE PUMP FPS-002 FPS FP-P-2A ELECTRIC FIRE PUMP FPS-003 FPS FP-P-2B ELECTRIC FIRE PUMP FPS-004 FPS FP-P-3 JOCKEY PUMP FPS-005 FPS FP-P-110 DIESEL FIRE PUMP FPS-006 FPS FP-P-111 JOCKEY PUMP FPS-007 FPS FP-P-111 0/C RESET FPS-008 FPS FP-P-2A 0/C RESET FPS-009 FPS FP-P-2B 0/C RESET FPS-010 FPS FP-P-3 0/C RESET FPS-011 FPS FP-P-1 0/C RESET FPS-012 FPS FP-P-110 0/C RESET FPT-001 FPT TO-V-62A RFPT A LO CLR SEL 2A/B FPT-002 FPT TO-V-62B RFPT B LO CLR SEL 2C/D FPT-003 FPT RFT-P-AOPA 0/C RESET FPT-004 FPT RFT-P-AOPB 0/C RESET FPT-005 FPT RFT-P-EOPA 0/C RESET FPT-006 FPT RFT-P-EOPB 0/C RESET FPT-007 FPT RFT-P-MOPA 0/C RESET FPT-008 FPT RFT-P-MOPB 0/C RESET FPT-009 RFT-TNG-1A 0/C RESET FPT-010 FPT RFT-TNG-1B 0/C RESET FPT-011 FPT TO-EX-3A 0/C RESET FPT-012 FPT TO-EX-3B 0/C RESET FPT-013 FPT WEDGE REMOVED/INSTALLRFT-TNG-1A FPT-014 FPT WEDGE REMOVED/INSTALLRFT-TNG-1B FWH-001 FWH HV-V-2D BYP HV-V-23D STRTUP VNT FWH-002 FWH HV-V-2C BYP HV-V-23C STRTUP VNT FWH-003 FWH HV-V-2HBYP HV-V-23H STRTUP VNT FWH-004 FWH HV-V-2G BYP HV-V-23G STRTUP VNT FWH-005 FWH HV-V-2LBYP HV-V-23LSTRTUP VNT FWH-006 FWH HV-V-2KBYP HV-V-23KSTRTUP VNT FWH-007 FWH HV-V-2IBYP HV-V-23I STRTUP VNT FWH-008 FWH HV-V-2J BYP HV-V-23J STRTUP VNT FWH-009 FWH HV-V-35ABYP HV-V-37ASTRTUP VNT FWH-010 FWH HV-V-35B BYP HV-V-37B STRTUP VNT FWH-011 FWH HV-V-2ABYP HV-V-23ASTRTUP VNT November 16, 1994 Page 37 of 51

APPENDIX C ATTACHMENTC-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID SYSTEM DESCRIPTION FWH-012 FWH HV-V-2B BYP HV-V-23B STRTUP VNT FWH-013 FWH HV-V-2E BYP HV-V-23E STRTUP VNT FWH-014 FWH HV-V-2F BYP HV-V-23F STRTUP VNT FWH-015 FWH HV-V-34ABYP HV-V-36ASTRTUP VNT FWH-016 FWH HV-V-34B BYP HV-V-36B STRTUP VNT FWH-017 FWH MSR HD-TKS NON-RETURN VLVRESET GEA-001 GEA SO-V-232 SEAL OIL TANKISOL GEA-002 GEA SCW-F05 HX 2 OUTLET GEA-003 GEA SCW-V406 HX 1 OUTLET ISOLATION GEA-004 GEA SCW-V-407 HX 2 INLET GEA-005 GEA SCW-F08 HX 2 INLET ISOLATION GEA-006 GEA SCW-V409 HX 1 INLET GEA-007 GEA H2-V-7 H2 ISOLATIONVALVE GEA-008 GEA SCW-P-1A PUMP AUTO/START/STOP GEA-009 GEA SCW-P-1B PUMP AUTO/START/STOP GEA-010 GBA TG-HSOP H2 SEAL OIL PUMP 6EA-011 GEA TG-ASOP AIR SIDE SEAL OIL PUMP GEA-012 GEA TG-ASOBP AIR SIDE SO B/U PUMP GEA-013 GBA H2-V-52 H2 SUPPLY VALVE GEA-014 GEA H2-V-34 H2 VENT VALVE GEA-015 GEA C02-V-60 C02 SUPPLY VALVE GEA-016 GEA C02-V-6 C02 ISOLATION GEA-017 GEA IBD-AD-13B FRESH AIR INTAKE GEA-018 GEA IBD-AD-2VENT TO ATMOSPHERE GEA-019 GEA IBD-AD-13AFRESH AIR INTAKE GEA-020 GEA STATOR CLG WTR DEMINA IN SERV GEA-021 GEA STATOR CLG WTR DEMINB IN SERV GEA-022 GEA SO-V-231 SEAL OILTANKDRAIN GEA-023 GEA SCW-V-424 DEMINBYPASS 6EA-024 GBA IBD-FN-1A 0/C RESET GEA-025 GEA IBD-FN-1B 0/C RESET 6EA-026 GEA SCW-P-1A 0/C RESET GEA-027 GBA SCW-P-1B 0/C RESET GEA-028 GEA TG-ASOP 0/C RESET GEA-029 GEA TG-ASOBP 0/C RESET GEA-030 GEA TG-HSOP 0/C RESET GEA-031 GEA TO-EX-4 0/C RESET 6 EN-001 GEN MOD BANK89-P 1/P3 GEN-002 GEN E-MO-DIS189 ¹1 MTR OP DISC GEN-003 GEN E-MO-DIS189 ¹2 MTR OP DISC GEN-004 GEN E-MO-DIS289 ¹1 MTR OP DISC GEN-005 GEN E-MO-DIS289 ¹2 MTR OP DISC GEN-006 GEN GRID BUS SELECT November 16, 1994 Page 38 of 51

APPENDIX C ATTACHMENTC-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID SYSTEM DESCRIPTION GEN-007 GEN MAINGENERATOR DISCONNECT LINK GEN-008 GEN BKR 4885 500KV BKR ¹1 LOCAL CONT GEN-009 GEN BKR 4888 500KV BKR ¹2 LOCAL CONT LDS-001 LDS LPDS SINGLE INPUT (SPURIOUS)

LDS-002 LDS LPDS SUSTAINED INPUT MSL-001 MSL MSLC-V-11 AIR INLET MSL-002 MSL MSLC-V-12 AIR INLET MSL-003 MSL MSLC-FN-1 0/C RESET MSL-004 MSL MSLC-FN-2 0/C RESET NIS-001 NIS APRM A GAIN ADJ FACTOR 0-10 NIS-002 NIS APRM B GAIN ADJ FACTOR 0-10 NIS-003 NIS APRM C GAIN ADJ FACTOR 0-10 NIS-004 NIS APRM D GAIN ADJ FACTOR 0-10 NIS-005 NIS APRM E GAIN ADJ FACI'OR 0-10 NIS-006 NIS APRM F GAIN ADJ FACl OR 0-10 NIS-007 NIS LPRM 08-17A BYPASS/OPERATE SWTCH NIS-008 NIS LPRM 08-17C BYPASS/OPERATE SWTCH NIS-009 NIS LPRM 08-17D BYPASS/OPERATE SWTCH NIS-010 NIS LPRM 08-25A BYPASS/OPERATE SWTCH NIS-011 NIS LPRM 08-25B BYPASS/OPERATE SWTCH NIS-012 NIS LPRM 08-25D BYPASS/OPERATE SWTCH NIS-013 NIS LPRM 08-33A BYPASS/OPERATE SWTCH NIS-014 NIS LPRM 08-33B BYPASS/OPERATE SWTCH NIS-015 NIS LPRM 08-33C BYPASS/OPERATE SWTCH NIS-016 NIS LPRM 0841B BYPASS/OPERATE SWTCH NIS-017, NIS LPRM 0841C BYPASS/OPERATE SWTCH NIS-018 NIS LPRM 0841D BYPASS/OPERATE SWTCH NIS-019 NIS LPRM 08-49A BYPASS/OPERATE SWTCH NIS-020 NIS LPRM 08-49C BYPASS/OPERATE SWTCH NIS-021 NIS LPRM 0849D BYPASS/OPERATE SWTCH NIS-022 NIS LPRM 16-09B BYPASS/OPERATE SWTCH NIS-023 NIS LPRM 16-09C BYPASS/OPERATE SWTCH NIS-024 NIS LPRM 16-09D BYPASS/OPERATE SWTCH NIS-025 NIS LPRM 16-17A BYPASS/OPERATE SWTCH NIS-026 NIS LPRM 16-17B BYPASS/OPERATE SWTCH NIS-027 NIS LPRM 16-17C BYPASS/OPERATE SWTCH NIS-028 NIS LPRM 16-25A BYPASS/OPERATE SWTCH NIS-029 NIS LPRM 16-25B BYPASS/OPERATE SWTCH NIS-030 NIS LPRM 16-25D BYPASS/OPERATE SWTCH NIS-031 NIS LPRM 16-33A BYPASS/OPERATE SWTCH NIS-032 NIS LPRM 16-33C BYPASS/OPERATE SWTCH NIS-033 NIS LPRM 16-33D BYPASS/OPERATE SWTCH NIS-034 NIS LPRM 16-41B BYPASS/OPERATE SWTCH November 16, 1994 Page 39 of 51

APPENDIX C ATTACHMENTC-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID SYSTEM DESCRIPTION NIS-035 NIS LPRM 16-41C BYPASS/OPERATE SWTCH NIS-036 NIS LPRM 16-41D BYPASS/OPERATE SWTCH NIS-037 NIS LPRM 1649A BYPASS/OPERATE SWTCH NIS-038 NIS LPRM 1649B BYPASS/OPERATE SWTCH NIS-039 NIS LPRM 1649C BYPASS/OPERATE SWTCH NIS-040 NIS LPRM 16-57A BYPASS/OPERATE SWTCH NIS-041 NIS LPRM 16-57B BYPASS/OPERATE SWTCH NIS-042 NIS LPRM 16-57D BYPASS/OPERATE SWTCH NIS-043 NIS LPRM 24-09A BYPASS/OPERATE SWTCH NIS-044 NIS LPRM 24-09B BYPASS/OPERATE SWTCH NIS-045 NIS LPRM 24-09D BYPASS/OPERATE SWTCH NIS-046 NIS LPRM 24-17A BYPASS/OPERATE SWTCH NIS-047 NIS LPRM 24-17B BYPASS/OPERATE SWTCH NIS-048 NIS LPRM 24-17C BYPASS/OPERATE SWTCH NIS-049 NIS LPRM 24-25B BYPASS/OPERATE SWTCH NIS-050 NIS LPRM 24-25C BYPASS/OPERATE SWTCH NIS-051 NIS LPRM 24-25D BYPASS/OPERATE SWTCH NIS-052 NIS LPRM 24-33A BYPASS/OPERATE SWTCH NIS-053 NIS LPRM 24-33C BYPASS/OPERATE SWTCH NIS-054 NIS LPRM 24-33D BYPASS/OPERATE SWTCH NIS-055 NIS LPRM 2441A BYPASS/OPERATE SWTCH NIS-056 NIS LPRM 24-41B BYPASS/OPERATE SWTCH NIS-057 NIS LPRM 24-41D BYPASS/OPERATE SWTCH NIS-058 NIS LPRM 24-49A BYPASS/OPERATE SWTCH NIS-059 NIS LPRM 24-49B BYPASS/OPERATE SWTCH NIS-060 NIS LPRM 24-49C BYPASS/OPERATE SWTCH NIS-061 NIS LPRM 24-57B BYPASS/OPERATE SWTCH NIS-062 NIS LPRM 24-57C BYPASS/OPERATE SWTCH NIS-063 NIS LPRM 24-57D BYPASS/OPERATE SWTCH NIS-064 NIS LPRM 32-09A BYPASS/OPERATE SWTCH NIS-065 NIS LPRM 32-09B BYPASS/OPERATE SWTCH NIS-066 NIS LPRM 32-09D BYPASS/OPERATE SWTCH NIS-067 NIS LPRM 32-17A BYPASS/OPERATE SWTCH NIS-068 NIS LPRM 32-17C BYPASS/OPERATE SWTCH NIS-069 NIS LPRM 32-17D BYPASS/OPERATE SWTCH NIS-070 NIS LPRM 32-25B BYPASS/OPERATE SWTCH NIS-071 NIS LPRM 32-25C BYPASS/OPERATE SWTCH NIS-072 NIS LPRM 32-25D BYPASS/OPERATE SWTCH NIS-073 NIS LPRM 32-33A BYPASS/OPERATE SWTCH NIS-074 NIS LPRM 32-33B BYPASS/OPERATE SWTCH NIS-075 NIS LPRM 32-33C BYPASS/OPERATE SWTCH NIS-076 NIS LPRM 32-41A BYPASS/OPERATE SWTCH NIS-077 NIS LPRM 32-41B BYPASS/OPERATE SWTCH November 16, 1994 Page 40 of 51

APPENDIX C ATTACHMENTC-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID SYSTEM DESCRIPTION NIS-078 NIS LPRM 32-41D BYPASS/OPERATE SWTCH NIS-079 NIS LPRM 32-49A BYPASS/OPERATE SWTCH NIS-080 NIS LPRM 32-49C BYPASS/OPERATE SWTCH NIS-081 NIS LPRM 32-49D BYPASS/OPERATE SWTCH NIS-082 NIS LPRM 32-57B BYPASS/OPERATE SWTCH NIS-083 NIS LPRM 32-57C BYPASS/OPERATE SWTCH NIS-084 NIS LPRM 32-57D BYPASS/OPERATE SWTCH NIS-085 NIS LPRM 40-09B BYPASS/OPERATE SWTCH NIS-086 NIS LPRM 40-09C BYPASS/OPERATE SWTCH NIS-087 NIS LPRM 40-09D BYPASS/OPERATE SWTCH NIS-088 NIS LPRM 40-17A BYPASS/OPERATE SWTCH NIS-089 NIS LPRM 40-17C BYPASS/OPERATE SWTCH NIS-090 NIS LPRM 40-17D BYPASS/OPERATE SWTCH NIS-091 NIS LPRM 40-25A BYPASS/OPERATE SWTCH NIS-092 NIS LPRM 40-25B BYPASS/OPERATE SWTCH NIS-093 NIS LPRM 40-25D BYPASS/OPERATE SWTCH NIS-094 NIS LPRM 40-33A BYPASS/OPERATE SWTCH NIS-095 NIS LPRM 40-33B BYPASS/OPERATE SWTCH NIS-096 NIS LPRM 40-33C BYPASS/OPERATE SWTCH NIS-097 NIS LPRM 40-41B BYPASS/OPERATE SWTCH NIS-098 NIS LPRM 4041C BYPASS/OPERATE SWTCH NIS-099 NIS LPRM 40-41D BYPASS/OPERATE SWTCH NIS-100 NIS LPRM 40-49A BYPASS/OPERATE SWTCH NIS-101 NIS LPRM 40-49C BYPASS/OPERATE SWTCH NIS-102 NIS LPRM 40-49D BYPASS/OPERATE SWTCH NIS-103 NIS LPRM 40-57A BYPASS/OPERATE SWTCH NIS-104 NIS LPRM 40-57B BYPASS/OPERATE SWTCH NIS-105 NIS LPRM 40-57D BYPASS/OPERATE SWTCH NIS-106 NIS LPRM 48-09B BYPASS/OPERATE SWTCH NIS-107 NIS LPRM 48-09C BYPASS/OPERATE SWTCH NIS-108 NIS LPRM 48-09D BYPASS/OPERATE SWTCH NIS-109 NIS LPRM 48-17A BYPASS/OPERATE SWTCH NIS-110 NIS LPRM 48-17B BYPASS/OPERATE SWTCH NIS-111 NIS LPRM 48-17C BYPASS/OPERATE SWTCH NIS-112 NIS LPRM 48-25A BYPASS/OPERATE SWTCH NIS-113 NIS LPRM 48-25B BYPASS/OPERATE SWTCH NIS-114 NIS LPRM 48-25D BYPASS/OPERATE SWTCH NIS-115 NIS LPRM 48-33A BYPASS/OPERATE SWTCH NIS-116 NIS LPRM 48-33C BYPASS/OPERATE SWTCH NIS-117 NIS LPRM 48-33D BYPASS/OPERATE SWTCH NIS-118 NIS LPRM 48-41B BYPASS/OPERATE SWTCH NIS-119 NIS LPRM 48P1C BYPASS/OPERATE SWTCH NIS-120 NIS LPRM 48-41D BYPASS/OPERATE SWTCH November 16, 1994 Page 41 of 51

APPENDIX C ATTACHMENTC-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID SYSTEM DESCRIPTION NIS-121 NIS LPRM 48-49A BYPASS/OPERATE SWTCH NIS-122 NIS LPRM 48-49B BYPASS/OPERATE SWTCH NIS-123 NIS LPRM 48-49C BYPASS/OPERATE SWTCH NIS-124 NIS LPRM 56-17A BYPASS/OPERATE SWTCH NIS-125 NIS LPRM 56-17B BYPASS/OPERATE SWTCH NIS-126 NIS LPRM 56-17C BYPASS/OPERATE SWTCH NIS-127 NIS LPRM 56-25B BYPASS/OPERATE SWTCH NIS-128 NIS LPRM 56-25C BYPASS/OPERATE SWTCH NIS-129 NIS LPRM 56-25D BYPASS/OPERATE SWTCH NIS-130 NIS LPRM 56-33A BYPASS/OPERATE SWTCH NIS-131 NIS LPRM 56-33C BYPASS/OPERATE SWTCH NIS-132 NIS LPRM 56-33D BYPASS/OPERATE SWTCH NIS-133 NIS LPRM 56-41A BYPASS/OPERATE SWTCH, NIS-134 NIS LPRM 5641B BYPASS/OPERATE SWTCH NIS-135 NIS LPRM 56-41D BYPASS/OPERATE SWTCH OED-001 OED 115 KV LINE MAN DISC SWITCH OED-002 OED 230 KV STARTUP BKR - CB-TRS OED-003 OED BPA RELAY 86/LR STATUS OGS-001 OGS OG-V-4B RECOMBINER AIR PURGE OGS-002 OGS OG-V-4A RECOMBINER AIR PURGE OGS-003 OGS GY-V-80A GLYCOL SUP OG-HX-10A OGS-004 OGS GY-V-80B GLYCOL SUP OG-HX-10B OGS-005 OGS GY-V-99A GLYCOL SUP OG-HX-31A OGS-006 OGS GY-V-99B GLYCOL SUP OG-HX-31B OGS-007 OGS OG-V-42 MOIST SEP SEAL WTR FILL 0GS-008 OGS OG-V-35 CLR COND SEAL WTR FILL 0GS-009 OGS OG-V-30 HOLDUP LN SEAL FILL OGS-010 OGS OG-V-51A INLET ISOL TO OG-HX-11A OGS-011 OGS OG-V-51B INLET ISOL TO OG-HX-11B OGS-012 OGS OG-V-51C INLET ISOL TO OG-HX-11C OGS-013 OGS OG-V-51D INLET ISOL'TO OG-HX-11D OGS-014 OGS OG-V-102A DRYER CH LOOP SEAL FIL OGS-015 OGS OG-V-102B DRYER CH LOOP SEAL FIL OGS-016 OGS AR-V-18 GLND SEAL STM COND PRESS OGS-017 OGS MS-PC-11A S JAE A CTRL A/M SEL OGS-018 OGS MS-PC-11A S JAE A CTRL AUTO SETPT OGS-019 OGS MS-PC-11B SJAE B CTRL A/M SEL 0GS-020 OGS MS-PC-11B SJAE B CI'RL AUTO SETPT 0GS-021 OGS MS-PC-16A S JAE A CTRL A/M SEL OGS-022 OGS MS-PC-16A S JAE A CTRL AUTO SETPT OGS-023 OGS MS-PC-16B S JAE B CTRL A/M SEL OGS-024 OGS MS-PC-16B S JAE B CTRL AUTO SETPT OGS-025 OGS MS-PC-17A S JAE A CTRL A/M SEL November 16, 1994 Page 42 of 51

APPENDIX C ATTACHMENTC-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID SYSTEM DESCRIPTION OGS-026 OGS MS-PC-17A S JAE A CTRL AUTO SETPT OGS-027 OGS MS-PC-17B S JAE B CI'Iu. A/M SEL OGS-028 OGS MS-PC-17B SJAE B CTRL AUTO SETPT OGS-029 OGS OG DRYER A STATUS OGS-030 OGS OG DRYER B STATUS 0GS-031 OGS OG DRYER C STATUS OGS-032 OGS OG DRYER D STATUS 0GS-033 OGS DRYER HEATER OG-DY-7A MODE OGS-034 OGS DRYER HEATER OG-DY-7B MODE 0GS-035 OGS AR-EX-1A 0/C RESET OGS-036 OGS 'R-EX-1B 0/C RESET OGS-037 OGS AR-P-1A 0/C RESET OGS-038 OGS AR-P-1B 0/C RESET OGS-039 OGS GY-P-1A 0/C RESET OGS-040 OGS GY-P-1B 0/C RESET OGS-041 OGS GY-P-1C 0/C RESET OGS-042 OGS OG-BL-lA0/C RESET OGS-043 OGS OG-BL-1B 0/C RESET OGS-044 OGS OG-V-41A PRE-FILTER OUTLET OGS-045 OGS MS-PC-11A S JAE A CTRL MAN OUTPUT OGS-046 OGS MS-PC-11B SJAE B CI RL MANOUTPUT OGS-047 OGS MS-PC-16A S JAE A CTRL MANOUTPUT OGS-048 OGS MS-PC-16B S JAE B CIRL MANOUTPUT OGS-049 OGS MS-PC-17A S JAE A CTRL MAN OUTPUT OGS-050 OGS MS-PC-17B S JAE B CIA MANOUTPUT OGS-051 OGS OG-RC-5A 0/C RESET OGS-052 OGS OG-RC-5B 0/C RESET OGS-053 OGS OG-RF-20A 0/C RESET OGS-054 OGS OG-RF-20B 0/C RESET OGS-055 OGS OG-RF-20C 0/C RESET OGS-056 OGS OG-DY-7A 0/C RESET OGS-057 OGS OG-DY-7B 0/C RESET PCN-001 PCN CSP-V-90 CONTAIN PURGE SUPPLY PCN-002 PCN CMS-P-1303 0/C RESET PCN-003 PCN CMS-P-1403 0/C RESET PCN-004 PCN CRA-FN-1A1 0/C RESET PCN-005 PCN CRA-FN-1A2 0/C RESET PCN-006 PCN CRA-FN-1B1 0/C RESET PCN-007 PCN CRA-FN-1B2 0/C RESET PCN-008 PCN CRA-FN-1C1 0/C RESET PCN-009 PCN CRA-FN-1C2 0/C RESET PCN-010 PCN CRA-FN-2A1 0/C RESET PCN-011 PCN CRA-FN-2A2 0/C RESET November 16, 1994 Page 43 of 51

APPENDIX C ATTACHMENTC-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACHONS LISTING ID SYSTEM DESCRIPTION PCN-012 PCN CRA-FN-2B1 0/C RESET PCN-013 PCN CRA-FN-2B2 0/C RESET PCN-014 PCN CRA-FN-3A 0/C RESET PCN-015 PCN CRA-FN-3B 0/C RESET PCN-016 PCN CRA-FN-3C 0/C RESET PCN-017 PCN CRA-FN-4A 0/C RESET PCN-018 PCN CRA-FN-4B 0/C RESET PCN-019 PCN CRA-FN-5A 0/C RESET PCN-020 PCN CRA-FN-5B 0/C RESET PCN-021 PCN CRA-FN-5C 0/C RESET PCN-022 PCN CRA-FN-5D 0/C RESET RCC-001 RCC RCC-V-13A CRD-P-1A CLG WTR IN RCC-002 RCC RCC-V-13B CRD-P-1B CLG WTR IN RCC-003 RCC RCC-V-79A CRD-P-1A BRG CLG OUT RCC-004 RCC RCC-V-79B CRD-P-1B BRG CLG OUT RCC-005 RCC RCC-V-2A RCC-P-1A DISCH VLV RCC-006 RCC RCC-V-2B RCC-P-1B DISCH VLV RCC-007 RCC RCC-V-2C RCC-P-1C DISCH VLV RCC-008 RCC RCC-V-3A RCC-HX-1A INLET VLV RCC-009 RCC RCC-V-3B RCC-HX-1B INLET VLV RCC-010 RCC RCC-V-3C RCC-HX-1C INLET VLV RCC-011 RCC RCC-V-9A FPC-HX-1A INLET ISOL RCC-012 RCC RCC-V-9B FPC-HX-1B INLET ISOL RCC-013 RCC RCC-V-10A FPC-HX-1A OUTLET RCC-014 RCC RCC-V-10B FPC-HX-1B OUTLET RCC-015 RCC RCC-V-45A RWCU-P-1A CLG WTR IN, RCC-016 RCC RCC-V-45B RWCU-P-1B CLG WTR IN RCC-017 RCC RCC-V-8 RWCU HX OUTLET RCC-018 RCC RCC-V-643A RWCU-P-1A CLR WTR OTL RCC-019 RCC RCC-V-643B RWCU-P-1B CLR WTR OTL RCC-020 RCC-021 RCC-022 RCC RCC RCC RCC-V-21 ~

RCC-V-104 MAN OPEN OPEN RCC-V-5 MAN OPEN RCC-023 RCC RCC-P-1A 0/C RESET RCC-024 RCC RCC-P-1B 0/C RESET RCC-025 RCC RCC-P-1C 0/C RESET RCI-001 RCI RCIC-V-708 PS-9A ISOLATED RCI-002 RCI RCIC-V-709 PS-9B ISOLATED RCI-003 RCI RCIC-V-623D XTIE TO SLC RCI-004 RCI RCIC OVERSPEED TRIP RESET RCI-005 RCI RCIC-P-2 0/C RESET "

RCI-006 RCI RCIC-P-3 0/C RESET RCI-007 RCI RCIC-P-4 0/C RESET November 16, 1994 Page 44 of 51

APPENDIX C ATTACHMENTC-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID SYSTEM DESCRIPTION RFC-001 RFC HY-P-A1 0/C RESET RFC-002 RFC 0/C RESET 'Y-P-A2 RFC-003 RFC HY-P-B1 0/C RESET RFC-004 RFC 'HY-P-B2 0/C RESET RHR-001 RHR RHR-V-72A FLUSH LINE ISOLATION RHR-002 RHR LPCS/RHR REMOVABLESPOOLPIECE RHR-003 RHR RHR-V-71A FLUSH LINE ISOL PMP SN RHR-004 RHR RHR-V-67 LOOP C CROSS TIE &CONDF RHR-005 RHR RHR-V-106 FLUSH SUPPLY RHR-006 RHR RHR-V-104 RHR TO FPC INTERTIE RHR-007 RHR EDR-V-176 DRAINTO FDR-R-1 RHR-008 RHR RHR-V-70 FLUSH LINE TO FLOOR DRN RHR-009 RHR RHR-V-71B FLUSH LINE ISOLATION RHR-010 RHR RHR-V-72B FLUSH LINE ISOLATION RHR-011 RHR RHR-V-40 RHR DRAINTO RW 0-100%

RHR-012 RHR RHR-V-49 RHR DRAINTO RW 0-100%

RHR-013 RHR RHR-V-42A INJECT MANOPEN 0-100%

RHR-014 RHR RHR-V-42B INJECT MAN OPEN 0-100%

RHR-015 RHR RHR-V-42C INJECT MAN OPEN 0-100%

RHR-016 RHR RHR-P-3 0/C RESET RHR-017 RHR RHR-P-2A 0/C RESET RHR-018 RHR RHR-P-2B 0/C RESET RHR-019, RHR RHR-P-2C 0/C RESET RMS-001 RMS WRA-FN-28 FAN STOP/START RMS-002 RMS WRA-FN-31 FAN STOP/START RMS-003 RMS TRA-FN-29 FAN STOP/START RMS-004 RMS RRA-FN-30 FAN STOP/START RRP-001 RRP RRC-P-1A VIBRATIONALARMRESET RRP-002 RRP RRC-P-1B VIBRATIONALARMRESET RRP-003 RRP RRC-V-8A SEAL PURGE ISOL VLV RRP-004 RRP RRC-V-8B SEAL PURGE ISOL VLV RRP-005 RRP RRC-FC-2A SEAL PURGE FLW CNTRL

'RP-006 RRP RRC-FC-2B SEAL PURGE FLW CNTRL RRP-007 RRP SPARE RRP-008 RRP SPARE RRP-009 RRP PWR INTRLCKBYP SW RRC-RMS-118A RRP-010 RRP PWR INTRLCKBYP SW RRC-RMS-118B RRP-011 RRP FW LW FLOW BYP SW RRC-RMS-119A RRP-012 RRP FW LW FLOW BYP SW RRC-RMS-119B RRP-013 RRP RRC-P-1A 0/C RESET RRP-014 RRP RRC-P-1B 0/C RESET RRS-1 RRS REACTOR VESSEL HEAD RWB-001 RWB FDR-V-187/COLL TK DISCH TO RIVER November 16, 1994 Page 45 of 51

APPENDIX C ATTACHMENTC-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID SYSTEM DESCRIPTION RWB-002 RWB FDR-V-474/COLL TK DISCH TO COND RWB-003 RWB EDR-V-161/EDR TK DISCH TO FDR RWB-004 RWB EDR-V-158B/EDR TK DISCH TO CST RWB-005 RWB WOA-V-51A/¹1 REMOTE INTAKEISOL RWB-006 RWB WOA-V-51B/¹2 REMOTE INTAKEISOL RWB-007 RWB WOA-V-52A/¹1 REMOTE INTAKEISOL RWB-008 RWB WOA-V-52B/¹2 REMOTE INTAKEISOL RWB-009 RWB WEA-AD-52 IN DAMP TO WMA-AH-52A RWB-010 RWB WEA-FN-1A 0/C RESET RWB-011 RWB WEA-FN-1B 0/C RESET RWB-012 RWB WEA-FN-1C 0/C RESET RWB-013 RWB WEA-FN-51 0/C RESET RWB-014 RWB WEA-FN-53A 0/C RESET RWB-015 RWB WEA-FN-53B 0/C RESET RWB-016 RWB WMA-FN-51A0/C RESET RWB-017 RWB WMA-FN-51B 0/C RESET RWB-018 RWB WMA-FN-52A0/C RESET RWB-019 RWB WMA-FN-52B 0/C RESET RWB-020 RWB WMA-FN-53A0/C RESET RWB-021 RWB WMA-FN-53B 0/C RESET RWB-022 RWB WMA-FN-54A0/C RESET RWB-023 RWB WMA-FN-54B 0/C RESET RWB-024 RWB WOA-FN-1A 0/C RESET RWB-025 RWB WOA-FN-1B 0/C RESET RWU-001 RWU RWCU-V-266A AUTO MANUAL RWU-002 RWU RWCU-V-266B AUTO MANUAL RWU-003 RWU RWCU-V-266A AUTO FLW SETPT V266A RWU-004 RWU RWCU-V-266B AUTO FLW SETPT V266B RWU-005 RWU RWCU-V-266A MANULCNTRL VLV266A RWU-006 RWU RWCU-V-266B MANULCNTRL VLV266B RWU-007 RWU RWCU-V-206A RWCU DEMN A INLTVLV RWU-008 RWU RWCU-V-206B RWCU DEMN B INLTVLV RWU-009 RWU RWCU-V-005A PMP A SUCT ISOL VLV RWU-010 RWU RWCU-V-005B PMP B SUCT ISOL VLV RWU-011 RWU RWCU-V-013A PMP A DISCH ISOL VLV RWU-012 RWU RWCU-V-013B PMP B DISCH ISOL VLV RWU-013 RWU RWCU-V-105 REGEN HX INLT ISO VLV RWU-014 RWU CRD-FCV-512A RWCU-P-1A MTR PURGE RWU-015 RWU CRD-FCV-512B RWCU-P-1B MTR PURGE RWU-016 RWU RWCU-V-266A SEAL-IN RESET RWU-017 RWU RWCU-V-266B SEAL-IN RESET RWU-018 RWU RWCU-P-1A 0/C RESET RWU-019 RWU RWCU-P-1B 0/C RESET November 16, 1994 Page 46 of 51

APPENDIX C ATTACHMENTC-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID SYSTEM DESCRIPTION SCN-001 SCN REA-FN-15 ANALYZERRM 1B SCN-002 SCN RRA-FN-16 ACCESS AREA SCN-003 SCN FDR-P-1A RX BLDG FDR SUMP 1 PUMP SCN-004 SCN FDR-P-1B RX BLDG FDR SUMP 1 PUMP SCN-005 SCN FDR-P-2 RX BLDG FDR SUMP 2 PUMP SCN-006 SCN FDR-P-3 RX BLDG FDR SUMP 4 PUMP SCN-007 SCN FDR-P-4A RX BLDG FDR SUMP 3 PUMP SCN-008 SCN FDR-P-4B RX BLDG FDR SUMP 3 PUMP SCN-009 SCN REA-V-F21 FIRE PROT FOR FU-2B SCN-010 SCN REA-V-Fl1 FIRE PROT FOR FU-2A SCN-011 SCN RRA-FN-8 MAINSTEAM TUNNEL FAN SCN-012 SCN RRA-FN-9 MAINSTEAM TUNNEL FAN SCN-013 SCN EDR-P-5 0/C RESET SCN-014 SCN FDR-P-1A 0/C RESET SCN-015 SCN FDR-P-1B 0/C RESET SCN-016 SCN FDR-P-2 0/C RESET SCN-017 SCN FDR-P-3 0/C RESET SCN-018 SCN FDR-P-4A 0/C RESET SCN-019 SCN FDR-P-4B 0/C RESET SCN-020 SCN REA-FN-1A 0/C RESET SCN-021 SCN REA-FN-1B 0/C RESET SCN-022 SCN REA-FN-2A 0/C RESET SCN-023 SCN REA-FN-2B 0/C RESET SCN-024 SCN REA-FN-15 0/C RESET SCN-025 SCN ROA-FN-1A 0/C RESET SCN-026 SCN ROA-FN-1B 0/C RESET SCN-027 SCN ROA-P-1A 0/C RESET SCN-028 SCN ROA-P-1B 0/C RESET SCN-029 SCN RRA-FN-1 0/C RESET SCN-030 SCN RRA-FN-2 0/C RESET SCN-031 SCN RRA-FN-3 0/C RESET SCN-032 SCN RRA-FN-4 0/C RESET SCN-033 SCN RRA-FN-5 0/C RESET SCN-034 SCN RRA-FN-6 0/C RESET SCN-035 SCN RRA-FN-8 0/C RESET SCN-036 SCN RRA-FN-9 0/C RESET SCN-037 SCN RRA-FN-10 0/C RESET SCN-038 SCN RRA-FN-11 0/C RESET SCN-039 SCN RRA-FN-12 0/C RESET SCN-040 SCN RRA-FN-13 0/C RESET SCN-041 SCN RRA-FN-14 0/C RESET SCN-042 SCN RRA-FN-15 0/C RESET SCN-043 SCN RRA-FN-16 0/C RESET November 16, 1994 Page 47 of 51

APPENDIX C ATTACHMENTC-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID SYSTEM DESCRIPTION SCN-044 SCN RRA-FN-17 0/C RESET SCN-045 SCN RRA-FN-19 0/C RESET SCN-046 SCN RRA-FN-20 0/C RESET SCN-047 SCN SGT-FN-1A-1 0/C RESET SCN-048 SCN SGT-FN-1A-2 0/C RESET SCN-049 SCN SGT-FN-1B-1 0/C RESET SCN-050 SCN SGT-FN-1B-2 0/C RESET SCN-051 SCN RRA-FN-21 0/C RESET SCN-052 SCN SGT-EHC-1A1 0/C RESET SCN-053 SCN .,SGT-EHC-1A2 0/C RESET SCN-054 SCN SGT-EHC-1B1 SCN-055 SCN SGT-EHC-1B2 0/C RESET SLC-001 SLC SLC-V-16 SYS CIRC TEST VLV SLC-002 SLC SLC-V-31 TEST TANKOUTLET VALVE SLC-003 SLC SLC-RV-29B REMOVED/CONN TO RCIC SLC-004 SLC SLC-RV-29A REMOVED/CONN TO RCIC SLC-005 SLC SLC-V-2A SLC PUMP 1A SUCTION VLV SLC-006 SLC SLC-V-2B SLC PUMP 1B SUCTION VLV SLC-007 SLC SLC-P-1A LOCAL START/STOP SLC-008 SLC SLC-P-1B LOCALSTART/STOP SLC-009 SLC SLC-P-1A 0/C RESET SLC-010 SLC SLC-P-1B 0/C RESET SSW-001 SSW RHR-V-14A HX A MANISOL SSW-002 SSW RHR-V-14B HX B MANISOL SSW-003 SSW SW-V-165A SPRAY RING BYPASS SSW-004 SSW SW-V-165B SPRAY RING BYPASS SSW-005 SSW SW-V-170A SPRAY RING ISOL SSW-006 SSW SW-V-170B SPRAY RING ISOL SSW-007 SSW SW-V-71A SPRAY XOVER A-B SSW-008 SSW SW-V-72A SPRAY XOVER B-A SSW-009 SSW SW-P-2A LOOP A KEEP FILLPMP SSW-010 SSW SW-P-2B LOOP B KEEP FILL PMP SSW-011 SSW SW-P-1A 86 LOCKOUT RELAY RESET SSW-012 SSW SW-P-1B 86 LOCKOUT RELAY RESET SSW-013 SSW HPCS-P-2 0/C RESET SSW-014 SSW SW-P-2A 0/C RESET SSW-015 SSW SW-P-2B 0/C RESET TBS-001 TBS TURB BLDG OUTSIDE AIR SPLY FAN1A TBS-002 TBS TURB BLDG OUTSIDE AIR SPLY FAN1B TBS-003 TBS TURB BLDG OUTSIDE AIR SPLY FAN2A TBS-004 TBS TURB BLDG OUTSIDE AIR SPLY FAN2B TBS-005 TBS 'URB BLDG EXHAUST AIR FAN1A TBS-006 TBS TURB BLDG EXHAUST AIR FAN1B November 16, 1994 Page 48 of 51

APPENDIX C ATTACHMENTC-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID SYSTEM DESCRIPTION TBS-007 TBS TURB BLDG EXHAUST AIR FAN1C TBS-008 TBS TURB BLDG EXHAUST AIR FAN1D TBS-009 TBS TEA-FN-1A 0/C RESET TBS-010 TBS TEA-FN-1B 0/C RESET TBS-011 TBS TEA-FN-1C 0/C RESET TBS-012 TBS TEA-FN-1D 0/C RESET TBS-013 TBS TOA-FN-lA0/C RESET TBS-014 TBS TOA-FN-1B 0/C RESET TBS-015 TBS TOA-FN-2A 0/C RESET TBS-016 TBS TOA-FN-2B 0/C RESET TLO-001 TLO OIL COOLER SELECI'A/1B TLO-002 TLO TO-EX-1 0/C RESET TLO-003 TLO TO-P-BLP 0/C RESET TLO-004 TLO TO-P-BOP 0/C RESET TLO-005 TLO TO-P-EOP 0/C RESET TLO-006 TLO TO-P-SOBP 0/C RESET TSW-001 TSW TSW-V-63A RCC-HX-1A INLET VLV TSW-002 TSW TSW-V-63B RCC-HX-1B INLET VLV TSW-003 TSW TSW-V-63C RCC-HX-1C INLET VLV TSW-004 TSW TSW-V-46 TSW-TCV-4 BYPASS TSW-005 TSW TSW-V-21 TSW-TCV-8 BYPASS TSW-006 TSW TSW-V-29 TSW-TCV-9 BYPASS TSW-007 TSW TSW-V-10A TSW-TCV-14B BYPASS TSW-008 TSW TSW-V-10B TSW-TCV-14A BYPASS TSW-009 TSW TSW-F-1A TSW LUBE WTR FLTR ON TSW-010 TSW TSW-F-1B TSW LUBE WTR FLTR ON TSW-011 TSW TSW-V-78 TSW RTN ISOL CW BASIN TSW-012 TSW TSW-V-38 AIR SIDE S CLR TSW IN TSW-013 TSW TSW-V-39 H2 SIDE S CLR TSW IN TSW-014 TSW TSW-V-40 AIR SIDE S CLR TSW OUT TSW-015 TSW TSW-V-41 H2 SIDE S CLR TSW OUT TSW-016 TSW TSW-V-42A BUS DCl'LR A TSW IN TSW-017 TSW TSW-V-42B BUS DCT CLR B TSW IN TSW-018 TSW TSW-V-43A BUS DCT CLR A TSW OUT TSW-019 TSW TSW-V-43B BUS DCT CLR B TSW OUT TSW-020 TSW TSW-V-230 TSW SU LUBE WTR SUP TSW-021 TSW TSW-V-45B TCV-4 ISOLATION TSW-022 TSW TSW-V-9D TCV-14A ISOLATION TSW-023 TSW TSW-V-9B TCV-14B ISOLATION TSW-024 TSW TSW-V-20B TCV-8 ISOLATION TSW-025 TSW TSW-V-28B TCV-9 ISOLATION TSW-026 TSW TSW-V-33 TCV-11 BYPASS TSW-027 TSW TSW-V-32B TCV-11 ISOLATION November 16, 1994 Page 49 of 51

APPENDIX C ATTACHMENTC-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID SYSTEM DESCRIPTION TSW-028 TSW TSW-V-44 PCV-20 BYPASS TSW-029 TSW TSW-V-48B PCV-20 ISOLATION TSW-030 TSW CJW-P-1A JACKET WATER CIRC PUMP TSW-031 TSW CJW-P-1B JACKET WATER CIRC PUMP TSW-032 TSW CJW-V-201 TO TSW DISCH HEADER TSW-033 TSW CJW-V-5 TCV INLET ISOLATION TSW-034 TSW CJW-V-12 TCV-1 INLET ISOLATION TSW-035 TSW CJW-V-18 TCV-1 BYPASS TSW-036 TSW CJW-V-9 TCV-1 BYPASS TSW-037 TSW CJW-V-16A CAS-C-1A OUTLET ISOL TSW-038 TSW CJW-V-16B CAS-C-1B OUTLET ISOL TSW-039 TSW TSW-V-684 INLETTO CJW-HX-1B TSW-040 TSW TSW-V-685 INLETTO CJW-HX-1A TSW-041 TSW TSW-V-687 OUTLET FROM CJW-HX-1B TSW-042 TSW TSW-V-688 OUTLET FROM CJW-HX-1A TSW-043 TSW CJW-V-751 FPS CONNECTION TSW-044 TSW TSW-V-237,243,244 FPS CONNECTION TSW-045 TSW TSW-V-69 TSW SUPPLY CW FILL TSW-046 TSW CJW-V-16C CAS-C-1C OUTLET ISOL TSW-047 TSW TSW-V-695 FIREWATER TO TSW TSW-048 TSW CJW-V-22A CJW-HX-1A OUTLET ISOL TSW-049 TSW CJW-V-22B CJW-HX-1B OUTLET ISOL TSW-050 TSW TSW-F-2A FLTR CIRC WTR LUBE WTR TSW-051 TSW TSW-F-2B FLTR CIRC WTR LUBE WTR TSW-052 TSW TSW-V-94A FLTR TSW-F-2A ISOL VLV TSW-053 TSW TSW-V-94B FLTR TSW-F-2B ISOL VLV TSW-054 TSW TSW-V-683 CJW HTX COMMON ISOL TSW-055 TSW TSW-P-lA 86 LOCKOUT RELAY RESET TSW-056 TSW TSW-P-1B 86 LOCKOUT RELAY RESET TSW-057 TSW CJW-P-1A 0/C RESET TSW-058 TSW CJW-P-1B 0/C RESET TSW-059 TSW TSW-V-140A OUTLET FROM TO-HX-2A TSW-060 TSW TSW-V-140B OUTLET FROM TO-HX-2B TSW-061 TSW TSW-V-140C OUTLET FROM TO-HX-2C TSW-062 TSW TSW-V-140D OUTLET FROM TO-HX-2D TSW-063 TSW TSW-V-5A INLETTO TO-HX-2A TSW-064 TSW TSW-V-5B INLETTO TO-HX-2B TSW-065 TSW TSW-V-5C INLETTO TO-HX-2C TSW-066 TSW TSW-V-5D INLET TO TO-HX-2D TUR-001 TUR SS-V-49F SS-PCV-4F BYP VLV TUR-002 TUR SS-V-48F SS-PCV-4F ISOL VLV TUR-003 TUR SS-V-49E SS-PCV-4E BYP VLV TUR-004 TUR SS-V-48E SS-PCV-4E ISOL VLV November 16, 1994 Page 50 of 51

APPENDIX C ATTACHMENTC-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM LOCAL OPERATOR ACTIONS LISTING ID SYSTEM DESCRIPTION TUR-005 TUR SS-V-49D SS-PCV-4D BYP VLV TUR-006 TUR SS-V-48D SS-PCV-4D ISOL VLV TUR-007 TUR SS-V-49C SS-PCV-4C BYP VLV TUR-008 TUR SS-V-48C SS-PCV-4C ISOL VLV TUR-009 TUR SS-V-49B SS-PCV-4B BYP VLV TUR-010 TUR SS-V-48B SS-PCV-4B ISOL VLV TUR-011 TUR SS-V-49A SS-PCV-4A BYP VLV TUR-012 TUR SS-V-48A SS-PCV-4A ISOL VLV TUR-013 TUR SS-V43B SS-PCV-2B BYP VLV TUR-014 TUR SS-V-42B SS-PCV-2B ISOL VLV TUR-015 TUR SS-V-43A SS-PCV-2A BYP VLV TUR-016 TUR SS-V-42A SS-PCV-2A ISOL VLV TUR-017 TUR SS-V-25 SS-PCV-126 BYPASS VLV TUR-018 TUR SS-V-24 SS-PCV-126 ISOL TUR-019 TUR SS-V-46 SS-PCV-3 BYP VLV TUR-020 TUR SS-V47 SS-PCV-3 ISOL VLV TUR-021 TUR AS-BLR-1 AUXBOILER TUR-022 TUR HV-V-28A,HV-V-29ABYPASS TUR-023 TUR HV-V-28B,HV-V-29BBYPASS TUR-024 TUR HEATER EXT NON-RETURN VLVRESET TUR-025 TUR TG-M-TG LOCAL START PUSHB UTl'ON TUR-026 TUR TG-M-TG 0/C RESET TOTAL COUNT: 2172 November 16, 1994 Page 51 of 51

APPENDIX C ATTACHMENTC-3 WASHINGTON PUBLIC POWER SUPPLY SYSTEM MALFUNCTIONS LISTING ID SYSTEM DESCRIPTION ADS-1 ADS ADS LOGIC FAILURE CAS-1 CAS COMPRESSOR LUBE OIL LEAKAP,C CAS-1A CAS A COMPRESSOR LUBE OIL LEAK CAS-1B CAS B COMPRESSOR LUBE OIL LEAK CAS-1C CAS C COMPRESSOR LUBE OIL LEAK CAS-2 CAS CTL AIR HDR LK DNSTRM CAS-V-15 CAS-2A CAS CI'L AIR HDR LK DNSTRM CAS-V-151 CAS-2B CAS CTL AIR HDR LK DNSTRM CAS-V-152 CAS-2C CAS CI'L AIR HDR LK DNSTRM CAS-V-153 CAS-2D CAS CTL AIR HDR LK DNSTRM CAS-V-155 CAS-3 CAS SERV AIR HDR LK DNSTRM SA-PCV-2 CAS-4 CAS LEAKDNSTRM OF CAS DRYER A/8 CFW-1 CFW CONDENSER TUBE LEAK CFW-10 CFW FEEDWATER HEATER TUBE RUPTURE CFW-10A CFW FEEDWATER HEATER 1A TUBE RUPTURE CFW-10B CFW FEEDWATER HEATER 1B TUBE RUPTURE CFW-10C CFW FEEDWATER HEATER 1C TUBE RUPTURE CFW-10D CFW FEEDWATER HEATER 2A TUBE RUPTURE CFW-10E CFW FEEDWATER HEATER 2B TUBE RUPTURE CFW-10F CFW FEEDWATER HEATER 2C TUBE RUPTURE CFW-10G CFW FEEDWATER HEATER 3A TUBE RUPTURE CFW-10H CFW FEEDWATER HEATER 3B TUBE RUPTURE CFW-10I CFW FEEDWATER HEATER 3C TUBE RUPTURE CFW-10J CFW FEEDWATER HEATER 4A TUBE RUPTURE CFW-10K CFW FEEDWATER HEATER 4B TUBE RUPTURE CFW-10L CFW FEEDWATER HEATER 4C TUBE RUPTURE CFW-10M CFW FEEDWATER HEATER 5A TUBE RUPTURE CFW-10N CFW FEEDWATER HEATER 5B TUBE RUPTURE CFW-100 CFW FEEDWATER HEATER 6A TUBE RUPTURE CFW-10P CFW FEEDWATER HEATER 6B TUBE RUPTURE CFW-1A CFW CONDENSER TUBE LEAK EAST END CFW-1B CFW CONDENSER TUBE LEAKMIDDLE CFW-1C CFW CONDENSER TUBE LEAKWEST END CFW-2 CFW LKIN CST SUPPLY HDR TO COND CFW-3 CFW CONDENSER AIR LEAK CFW4 CFW LEAKIN COMMON COND PUMP DISCH CFW-5 CFW FEED LINE LEAKIN TURBINE BLDG CFW-6 CFW LEAKIN COMMON CBP DISCHARGE CFW-7 CFW LEAKAT RFP SUCTION CFW-8 CFW FEED LINE LEAKIN STEAM TUNNEL CFW-8A CFW FEED LINE LEAKIN STEAM TUNNEL A CFW-8B CFW FEED LINE LEAKIN STEAM TUNNEL B CFW-9 CFW FEED LINE LEAKIN DRYWELL November 16, 1994 Page1of27

APPENDIX C ATTACHMENTC-3 WASHINGTON PUBLIC POWER SUPPLY SYSTEM MALFUNCTIONSLISTING ID SYSTEM DESCRIPTION CFW-9A CFW FEED LINE LEAKIN DRYWELLA CFW-9B CFW FEED LINE LEAKIN DRYWELLB CIA-1 CIA CONTAINMENTINSTRUMENT AIR LEAK CIA-2 CIA LEAKIN CIA LINE DNSTRM CIA-V-21 CIA-3 CIA LK CIA LINE DNSTRM CIA-V-31A/8 CIA-3A CIA LKIN SUPP LINE TO SRV-4A/4B/5B CIA-3B CIA LK IN SUPP LINE SRV-3D/4C/4D/5C CRD-1 CRD HCU ACCUMULATORTROUBLE CRD-1A CRD HCU ACCUMULATORTROUBLE CRD-1AA CRD HCU ACCUMULATORTROUBLE CRD-1AB CRD HCU ACCUMULATORTROUBLE CRD-1AC CRD HCU ACCUMULATORTROUBLE CRD-1AD CRD HCU ACCUMULATORTROUBLE CRD-1AE CRD HCU ACCUMULATORTROUBLE CRD-1AF HCU ACCUMULATORTROUBLE

'RD CRD-1AG CRD HCU ACCUMULATORTROUBLE CRD-1AH CRD HCU ACCUMULATORTROUBLE CRD-1AI CRD HCU ACCUMULATORTROUBLE CRD-1AJ CRD HCU ACCUMULATORTROUBLE CRD-lAK CRD HCU ACCUMULATORTROUBLE CRD-1AL CRD HCU ACCUMULATORTROUBLE CRD-1AM CRD HCU ACCUMULATORTROUBLE CRD-1AN CRD HCU ACCUMULATORTROUBLE CRD-1AO CRD HCU ACCUMULATORTROUBLE CRD-1AP CRD HCU ACCUMULATORTROUBLE CRD-1AQ CRD HCU ACCUMULATORTROUBLE CRD-1AR CRD HCU ACCUMULATORTROUBLE CRD-1AS CRD HCU ACCUMULATORTROUBLE CRD-1AT'RD-1AU CRD HCU ACCUMULATORTROUBLE CRD HCU ACCUMULATORTROUBLE CRD-1AV CRD HCU ACCUMULATORTROUBLE CRD-1AW CRD HCU ACCUMULATORTROUBLE CRD-1AX CRD HCU ACCUMULATORTROUBLE CRD-1B CRD HCU ACCUMULATORTROUBLE CRD-lc CRD HCU ACCUMULATORTROUBLE CRD-1D CRD HCU ACCUMULATORTROUBLE CRD-1E CRD HCU ACCUMULATORTROUBLE CRD-1F CRD HCU ACCUMULATORTROUBLE CRD-1G CRD HCU ACCUMULATORTROUBLE CRD-1H CRD HCU ACCUMULATORTROUBLE CRD-1I CRD HCU ACCUMULATORTROUBLE CRD-1J CRD HCU ACCUMULATORTROUBLE CRD-1K CRD HCU ACCUMULATORTROUBLE November 16, 1994 Page 2 of 27

APPENDIX C ATTACHMENTC-3 WASHINGTON PUBLIC POWER SUPPLY SYSTEM MALFUNCTIONS LISTING ID SYSTEM DESCRIPTION CRD-1L CRD HCU ACCUMULATORTROUBLE CRD-1M CRD HCU ACCUMULATORTROUBLE CRD-1N CRD HCU ACCUMULATORTROUBLE CRD-10 CRD HCU ACCUMULATORTROUBLE CRD-1P CRD HCU ACCUMULATORTROUBLE CRD-1Q CRD HCU ACCUMULATORTROUBLE CRD-1R CRD HCU ACCUMULATORTROUBLE CRD-1S CRD HCU ACCUMULATORTROUBLE CRD-1T CRD HCU ACCUMULATORTROUBLE CRD-1U CRD HCU ACCUMULATORTROUBLE CRD-1V CRD HCU ACCUMULATORTROUBLE CRD-1W CRD HCU ACCUMULATORTROUBLE CRD-1X CRD HCU ACCUMULATORTROUBLE CRD-1Y CRD HCU ACCUMULATORTROUBLE CRD-1Z CRD HCU ACCUMULATORTROUBLE CRD-2 CRD CONTROL ROD DRIVE SEALS WORN CRD-3 CRD CRD HYD LINE BREAK AT INLET PORT CRD4 CRD CRD HYD LINE BREAK OUTLET PORT CRD-5 CRD RUPTURE IN CRD AIR HEADER CRD-6 CRD RUPTURE IN CRD WATER HEADER CRD-7 CRD HYDRAULICATWS CRD-7A CRD HYDRAULICATWS EAST SDV CRD-7B CRD HYDRAULICATWS WEST SDV CSS-1 CSS HPCS HEADER BREAK CSS-2 CSS LPCS HEADER BREAK CSS-3 CSS LPCS SUCTION LINE LEAKAT PUMP CSS-4 CSS HPCS DISCHARGE LINE LEAKAT PUMP CSS-5 CSS HPCS DISCH LN BRK DNSTRM FI-603 CSS-6 CSS HPCS LOGIC FAILURE CSS-7 CSS LPCS/LPCI-A LOGIC FAILURE CWS-1 CWS CW TOWER ICING CWS-1A CWS CW TOWER 1A ICING CWS-1B CWS CW TOWER 1B ICING CWS-1C CWS CW TOWER 1C ICING CWS-1D CWS CW TOWER 2A ICING CWS-1E CWS CW TOWER 2B ICING CWS-1F CWS CW TOWER 2C ICING CWS-2 CWS CW SYS RUPTURE AT COMMON DISCH CWS-3 CWS CW SYS RUPTURE CONDENSER INLET CWS-3A CWS CW SYS RUPTURE CONDENSER A INLET CWS-3B CWS CW SYS RUPTURE CONDENSER B INLET CWS-3C CWS CW SYS RUPTURE CONDENSER C INLET CWS-4 CWS CW SYS RUPTURE AT CONDSER OUTLET November 16, 1994 Page 3 of27

APPENDIX C ATTACHMENTC-3 WASHINGTON PUBLIC POWER SUPPLY SYSTEM MALFUNCTIONSLISTING ID SYSTEM DESCRIPTION CWS-4A CWS CW SYS RUPTURE AT CNDSR A OUTLET CWS-4B CWS CW SYS RUPTURE AT CNDSR B'OUTLET CWS-4C CWS CW SYS RUPTURE AT CNDSR C OUTLET CWS-5 CWS CW SYS RUPT AT EACH COOLING TOWR CWS-5A CWS CW SYS RUPTURE AT CLG TOWER 1A CWS-SB CWS CW SYS RUPTURE AT CLG TOWER 1B CWS-5C CWS CW SYS RUPTURE AT CLG TOWER 1C CWS-5D CWS CW SYS RUPTURE AT CLG TOWER 2A CWS-5E CWS CW SYS RUPTURE AT CLG TOWER 2B CWS-5F CWS CW SYS RUPTURE AT CLG TOWER 2C CWS-6 CWS TMU RUPTURE IN 3.5 MILEM/U LINE DEH-1 DEH MAINTURBINE TRIP/PAIL TO TRIP DEH-10 DEH TURBINE THROTILE VALVEFAILURE DEH-10A DEH TURBINE THROTILE VALVE¹1 FAIL DEH-10B DEH TURBINE THROTTLE VALVE¹2 FAIL DEH-10C DEH TURBINE THROVE,E VALVE¹3 FAIL DEH-10D DEH TURBINE THROVE.E VALVE¹4 FAIL DEH-11 DEH TURBINE GOVERNOR VALVEFAILURE DEH-11A DBH TURBINE GOVERNOR VALVE¹1 FAIL DEH-11B DEH TURBINE GOVERNOR VALVE¹2 FAIL DEH-11C DBH TURBINE GOVERNOR VALVE¹3 FAIL DEH-11D DBH TURBINE GOVERNOR VALVE¹4 PAIL DEH-12 DEH INTERCEPT AND STOP VALVEFAILURE DEH-12A DEH INTERCEPT/STOP VALVEFAILL-1IV DEH-12B DEH INTERCEPT/STOP VALVEFAILL-1RV DEH-12C DEH INTERCEPT/STOP VALVEFAIL L-2IV DEH-12D DEH INTERCEPT/STOP VALVEFAIL L-2RV DEH-12E DEH INTERCEPT/STOP VALVEPAIL L-3IV DEH-12F DEH INTERCEPT/STOP VALVEPAIL L-3RV DEH-12G DEH INTERCEPT/STOP VALVEPAIL R-1IV DEH-12H DBH INTERCEPT/STOP VALVEFAIL R-1RV DEH-12I DEH INTERCEPT/STOP VALVEPAIL R-2IV DEH-12J DEH INTERCEPT/STOP VALVEPAIL R-2RV DEH-12K DEH INTERCEPT/STOP VALVEFAILR-3IV DEH-12L DEH INTERCEPT/STOP VALVEPAIL R-3RV DEH-13 DEH TURBINE BYPASS VALVEFAILURE DEH-13A DEH TURBINE BYPASS VALVE¹1 FAILURE DEH-13B DEH TURBINE BYPASS VALVE¹2 FAILURE DEH-13C DEH TURBINE BYPASS VALVE¹3 FAILURE DEH-13D DEH TURBINE BYPASS VALVE¹4 FAILURE DEH-2 DEH RUPTURE IN COMMON DEH DISCHARGE DEH-3 DEH EH OIL LEAKAT PUMP DISCHARGE DEH-4 DEH DEH STM PRESS INPUT AMP OSCIL November 16, 1994 Page 4 of 27

APPENDIX C ATTACHMENTC-3 WASHINGTON PUBLIC POWER SUPPLY SYSTEM MALFUNCTIONS LISTING ID SYSTEM DESCRIPTION DEH-4A DEH DEH STM PRESS A INPUT AMP OSCIL DEH-4B DEH DEH STM PRESS B INPUT AMP OSCIL DEH-5 DEH DEH PRESS CONTROLLER OUTPUT FAIL DEH-6 DEH DEH COMPUTER FAILURE DEH-7 DEH DEH ANALOG CONTROLLER FAILURE DEH-7A DEH DEH ANALOG CONTROLLER FAIL-BPV'S DEH-7B DEH DEH ANALOG CONTROLLER FAIL-GV'S DEH-8 DEH GOV VALVELOW SIGNAL SELECT FAIL DEH-9 DEH TURB ACCELERATION CNTRL FAILURE DGN-1 DGN DG FAILTO AUTO START-INCOMP SEQ DGN-1A DGN DG1 FAIL AUTO START-INCOMPL SEQ DGN-1B DGN DG2 FAIL AUTO START-INCOMPL SEQ DGN-1C DGN DG3 FAIL AUTO START-INCOMPL SEQ DGN-2 DGN DG TRIP- HI DIFFERED IAL CURRENT DGN-2A DGN DG1 TRIP - HIGH DIFF CURRENT DGN-2B DGN DG2 TRIP - HIGH DIFF CURRENT DGN-2C DGN DG3 TRIP - HIGH DIFF CURRENT DGN-3 DGN DG GOVERNOR FAILURE - SPEED/LOAD DGN-3A DGN DG1 GOVERNOR FAIL - SPEED/LOAD DGN-3B DGN DG2 GOVERNOR FAIL - SPEED/LOAD DGN-3C DGN DG3 GOVERNOR FAIL - SPEED/LOAD DGN-4 DGN DG VOLT REG FAIL-OSCILLATION DGN-4A DGN DG1 VOLT REG FAIL - OSCILLATION DGN-4B DGN DG2 VOLT REG FAIL- OSCILLATION DGN-4C DGN DG3 VOLT REG FAIL - OSCILLATION DGN-5 DGN DG HIGH VIBRATION DON-5A DGN DG1 HIGH VIBRATION DGN-5B DGN DG2 HIGH VIBRATION DGN-5C DGN DG3 HIGH VIBRATION EPS-1 EPS 4160 VAC BUS OVERCURRENT- GROUND EPS-1A EPS 4160 VAC BUS OVRCUR/GND SM1 EPS-1B EPS 4160 VAC BUS OVRCUR/GND SM2 EPS-1C EPS 4160 VAC BUS OVRCUR/GND SM3 EPS-1D EPS 4160 VAC BUS OVRCUR/GND SM4 EPS-1E EPS 4160 VAC BUS OVRCUR/GND SM75 EPS-1F EPS 4160 VAC BUS OVRCUR/GND SM85 EPS-1G EPS 4160 VAC BUS OVRCUR/GND SM7 EPS-1H EPS 4160 VAC BUS OVRCUR/GND SM8 EPS-1I EPS 4160 VAC BUS OVRCUR/GND SM72 EPS-1J EPS 4160 VAC BUS OVRCUR/GND SM82 EPS-2 EPS 480 VAC BUS OVERCURRENT - GROUND EPS-2A EPS 480 VAC BUS OVRCUR/GND SL11 EPS-2B EPS 480 VAC BUS OVRCUR/GND SL21 November 16, 1994 Page 5 of 27

APPENDIX C ATTACHMENTC-3 WASHINGTON PUBLIC POWER SUPPLY SYSTEM MALFUNCTIONS LISTING t

ID SYSTEM DESCRIPTION EPS-2C EPS 480 VAC BUS OVRCUR/GND SL31 EPS-2D EPS ,

480 VAC BUS OVRCUR/GND MC4A EPS-2E EPS 480 VAC BUS OVRCUR/GND SL51-SL52 EPS-2F BPS 480 VAC BUS OVRCUR/GND SL53 EPS-2G EPS 480 VAC BUS OVRCUR/GND SL61-SL62 EPS-2H BPS 480 VAC BUS OVRCUR/GND SL63 EPS-2I EPS 480 VAC BUS OVRCUR/GND SL71 EPS-2J EPS 480 VAC BUS OVRCUR/GND SL73 BPS-2K EPS 480 VAC BUS OVRCUR/GND SL81 EPS-2L EPS 480 VAC BUS OVRCUR/GND SL83 EPS-3 EPS GROUNDED DC BUS EPS-3A EPS GROUNDED DC BUS DP-SO-1A EPS-3B EPS GROUNDED DC BUS DP-SO-IB EPS-3C BPS GROUNDED DC BUS DP-S1-1 EPS-3D EPS GROUNDED DC BUS DP-S1-2 EPS-3B EPS GROUNDED DC BUS DP-S 1-7 EPS-3F EPS GROUNDED DC BUS DP-S1-HPCS EPS-3G BPS GROUNDED DC BUS DP-S2-1 EPS-4 EPS UPS STATIC SWITCH FAILURE EPS-4A EPS UPS STATIC SWITCH FAILURE - IN1 EPS-4B BPS UPS STATIC SWITCH FAILURE - IN2 EPS-4C EPS UPS STATIC SWITCH FAILURE - IN3 EPS-5 EPS 6900 VAC BUS OVERCURRENT- GROUND EPS-5A EPS 6900 VAC BUS OVRCUR/GND SH5 EPS-5B EPS 6900 VAC BUS OVRCUR/GND SH6 FPC-1 FPC LEAKIN SPENT FUEL POOL FPC-2 FPC RUPTURE IN FPC PUMP SUCHON LINE FPC-3 FPC DROPPED SPENT FUEL BUNDLE IN SFP FPS-1 FPS FIRE MAINHEADER BREAK FPT-1 FPT TO-TK-3A/3B LUBE OIL LEAK FPT-1A FPT TO-TK-3A LUBE OIL LEAK FPT-1B FPT TO-TK-3B LUBE OIL LEAK FPT-2 FPT RFPT TRIP/FAILTO TRIP FPT-2A FPT RFPT-A TRIP/FAILTO TRIP FPT-2B FPT RFPT-B TRIP/FAILTO TRIP FPT-3 FPT RFPT LOSS OF LUBE OIL FPT-3A FPT RFPT-A LOSS OF LUBE OIL FPT-3B FPT RFPT-B LOSS OF LUBE OIL FPT-4 FPT RFPT GOVERNOR FAILURE FPT-4A FPT RFPT-A GOVERNOR FAILURE FPT-4B RFPT-B GOVERNOR FAILURE FPT'PT FPT-5 RFPT HIGH VIBRATION FPT-5A RFPT-A HIGH VIBRATION November 16, 1994 Page 6 of 27

APPENDIX C ATTACHMENTC-3 WASHINGTON PUBLIC POWER SUPPLY SYSTEM MALFUNCTIONS LISTING ID SYSTEM DESCRIPTION FPT-5B FPT RFPT-B HIGH VIBRATION FPT-6 FPT STM LK RFP SUPPLY BETWEEN SV/GOV FPT-6A FPT STM LKRFP-A SUP BETWEEN SV/GV FPT-6B FPT STM LKRFP-B SUP BETWEEN SV/GV FWC-1 FWC STEAM FLOW TOTALIZERFAILURE FWC-2 FWC FEED FLOW TOTALIZERFAILURE FWH-1 FWH DRAIN LINE LEAKTO MSR DRAINTK FWH-lA FWH DRAIN LINE LEAKTO HD-TK-1A FWH-1B FWH DRAIN LINE LEAKTO HD-TK-1B FWH-1C FWH DRAIN LINE LEAKTO HD-TK-2A FWH-1D FWH DRAIN LINE LEAKTO HD-TK-2B FWH-1E FWH DRAIN LINE LEAKTO HD-TK-2C FWH-1F FWH DRAIN LINE LEAKTO HD-TK-2D FWH-1G FWH DRAIN LINE LEAKTO HD-TK-3A FWH-1H FWH DRAIN LINE LEAKTO HD-TK-3B FWH-1I FWH DRAIN LINE LEAKTO HD-TK-3C FWH-1J FWH DRAIN LINE LEAKTO HD-TK-3D FWH-2 FWH FW HTR DRAIN LK BETWEEN DUMP VLV FWH-2A FWH FW HTR DR LK BETWEEN DUMPS HTR2A FWH-2B FWH FW HTR DR LK BETWEEN DUMPS HTR2B FWH-2C FWH FW HTR DR LK BETWEEN DUMPS HTR2C FWH-2D FWH FW HTR DR LK BETWEEN DUMPS HTR3A FWH-2E FW HTR DR LK BETWEEN DUMPS HTR3B FWH-2F FW HTR DR LK BETWEEN DUMPS HTR3C FWH-2G FWH FW HTR DR LK BETWEEN DUMPS HTR4A FWH-2H FWH FW HTR DR LK BETWEEN DUMPS HTR4B FWH-2I FWH FW HTR DR LK BETWEEN DUMPS HTR4C FWH-2J FWH FW HTR DR LK BETWEEN DUMPS HTR5A FWH-2K FWH FW HTR DR LK BETWEEN DUMPS HTR5B FWH-2L FWH FW HTR DR LK BETWEEN DUMPS HTR6A FWH-2M FWH FW HTR DR LK BETWEEN DUMPS HTR6B GEA-1 GEA RUPTURE OF GEN SEAL OIL FILTERS GBA-1A GEA RUPT OF AIR SIDE SEAL OIL FILTER GEA-1B GEA RUPT OF HYDROGEN SEAL OIL FILTER GEA-2 GEA H2 LEAKIN SUPPLY LINE TO GEN GEA-3 GEA SCC PUMPS SUCTION LINE LEAK GEA-3A GEA SCC-A PUMP SUCTION LINE LEAK GEA-3B GEA SCC-B PUMP SUCTION LINE LEAK GEAR GEA GEN CLG WATER HIGH CONDUCTIVITY GEA-5 GEA STATOR CLG WTR LEAKIN MAINGEN GEN-1 GEN MAINGENERATOR TRIP/FAILTO TRIP GEN-2 GEN GENERATOR VOLTAGE REG FAILURE GEN-3 GEN TRANSFORMER LOCKOUT TR-Nl November 16, 1994 Page 7 of 27

APPENDIX C ATTACHMENTC-3 WASHINGTON PUBLIC POWER SUPPLY SYSTEM MALFUNCTIONS LISTING ID SYSTEM DESCRIPTION GENP GEN TRANSFORMER LOCKOUT TR-N2 GEN-5 GEN 500KV BREAKER TRIP GEN-5A GEN 500KV ASHE BKR ¹1 (4885) TRIP GEN-5B GEN 500KV ASHE BKR ¹2 (4888) TRIP GEN-6 GEN MWTI'AILURE GEN-7 GEN MAINGEN POTENTIALXPMR FAILURE GEN-7A GEN GEN INST POTENTIALXPMR 62 FAIL 6 EN-7B GEN VOLT REG POTENTIALXFMR G3 FAIL GEN-8 GEN MAINTRANSFORMER LOCKOUT GEN-8A GEN MAINTRANSFORMER TR-M1 LOCKOUT GEN-8B GEN MAIN'IRANSPORMER TR-M2 LOCKOUT GEN-8C GEN MAINTRANSFORMER TR-M3 LOCKOUT NIS-1 NIS SRM INSTR FLR HI-LO-ERRAT-INOP NIS-1A NIS SRM INSTR FLR HI-LO-ERRAT-INOPA NIS-1B NIS SRM INSTR FLR HI-LO-ERRAT-INOPB NIS-1C NIS SRM INSTR FLR HI-LO-ERRAT-INOP C NIS-1D NIS SRM INSTR FLR HI-LO-ERRAT-INOP D NIS-2 NIS IRM INSTR FLR HI-LO-ERRAT-INOP NIS-2A NIS IRM INSTR FLR HI-LO-ERRAT-INOPA NIS-2B NIS IRM INSTR FLR HI-LO-ERRAT-INOPB NIS-2C NIS IRM INSTR FLR HI-LO-ERRAT-INOP C NIS-2D NIS IRM INSTR FLR HI-LO-ERRAT-INOP D NIS-2E NIS IRM INSTR FLR HI-LO-ERRAT-INOP E NIS-2F NIS IRM INSTR FLR HI-LO-ERRAT-INOP F NIS-26 NIS IRM INSTR PLR HI-LO-ERRAT-INOP G NIS-2H NIS IRM INSTR FLR HI-LO-ERRAT-INOP H NIS-3 NIS SRM DT DR FAIL-STCK,CIR FAIL.

NIS-3A NIS SRM DT DR FAIL.-STCK,CIR PAIL A NIS-3B NIS SRM DT DR FAIL-STCK,CIR FAILB NIS-3C NIS SRM DT DR FAIL-STCK,CIR FAILC NIS-3D NIS SRM DT DR FAIL-STCK,CIR FAILD NIS-4 NIS IRM DT DR FAIL-STCK,CKTFAIL.

NISAA NIS IRM DT DR FAIL-STCK,CKTFAILA NISPB NIS IRM DT DR PAIL-STCK,CKTFAILB NISPC NIS IRM DT DR PAIL-STCK,CKTPAIL C NISCD NIS IRM DT DR FAIL-STCK,CKTPAIL D NISSE NIS IRM DT DR FAIL-STCK,CKTFAIL E NISPF NIS IRM DT DR FAII STCK,CKT FAIL F NISQG NIS IRM DT DR FAIL-STCK,CKTFAIL G NIS-4H NIS IRM DT DR FAIL-STCK,CKTFAIL H NIS-5 NIS APRM FAILURE-DWNSCL/UPSCLflNOP NIS-5A NIS APRM-A FAILURE-DWNSCL/UPSCL/INOP NIS-5B NIS APRM-B FAILURE-DWNSCL/UPSCLflNOP November 16, 1994 Page 8 of 27

APPENDIX C ATTACHMENTC-3 WASHINGTON PUBLIC POWER SUPPLY SYSTEM MALFUNCTIONS LISTING ID SYSTEM DESCRIPTION NIS-5C NIS APRM-C FAILURE/DWNSCL/UPSCL/INOP NIS-5D NIS APRM-D FAILURE-DWNSCL/UPSCL/INOP NIS-5E NIS APRM-E FAILURE/DWNSCL/UPSCL/INOP NIS-5F NIS APRM-F FAILURE/DWNSCL/UPSCL/INOP NIS-6 NIS APRM FLOW UNIT FAILURE NIS-6A NIS APRM FLOW UNIT A FAIL NIS-6B NIS APRM FLOW UNIT B FAIL NIS-6C NIS APRM FLOW UNIT C FAIL NIS-6D NIS APRM FLOW UNIT D FAIL NIS-7 NIS SRM-IRM INADEQUATEOVERLAP NIS-7A NIS SRM-IRM A INADEQUATEOVERLAP NIS-7B NIS SRM-IRM B INADEQUATEOVERLAP NIS-7C NIS SRM-IRM C INADEQUATEOVERLAP NIS-7D NIS SRM-IRM D INADEQUATEOVERLAP NIS-7E NIS SRM-IRM E INADEQUATEOVERLAP NIS-7F NIS SRM-IRM F INADEQUATEOVERLAP NIS-7G NIS SRM-IRM G INADEQUATEOVERLAP NIS-7H NIS SRM-IRM H INADEQUATEOVERLAP NIS-8 NIS LPRM FAILURE UPSCALE/DOWNSCALE NIS-8A NIS LPRM FAILURE UPSCALE/DOWNSCALE NIS-8AA NIS LPRM FAILURE UPSCALE/DOWNSCALE NIS-8AB NIS LPRM FAILURE UPSCALE/DOWNSCALE NIS-8AC NIS LPRM FAILURE UPSCALE/DOWNSCALE NIS-8AD NIS LPRM FAILURE UPSCALE/DOWNSCALE NIS-8AE NIS LPRM FAILURE UPSCALE/DOWNSCALE NIS-8AF NIS LPRM FAILURE UPSCALE/DOWNSCALE NIS-8AG NIS LPRM FAILURE UPSCALE/DOWNSCALE NIS-8AH NIS LPRM FAILURE UPSCALE/DOWNSCALE NIS-8AI NIS LPRM FAILURE UPSCALE/DOWNSCALE NIS-8AJ NIS LPRM FAILURE UPSCALE/DOWNSCALE NIS-8AK NIS LPRM FAILURE UPSCALE/DOWNSCALE NIS-8AL NIS LPRM FAILURE UPSCALE/DOWNSCALE NIS-8AM NIS LPRM FAILURE UPSCALE/DOWNSCALE NIS-8AN NIS LPRM FAILURE UPSCALE/DOWNSCALE NIS-8AO NIS LPRM FAILURE UPSCALE/DOWNSCALE NIS-8AP NIS LPRM FAILURE UPSCALE/DOWNSCALE NIS-8AQ NIS LPRM FAILURE UPSCALE/DOWNSCALE NIS-8AR NIS LPRM FAILURE UPSCALE/DOWNSCALE NIS-8AS NIS LPRM FAILURE UPSCALE/DOWNSCALE NIS-8AT NIS LPRM FAILURE UPSCALE/DOWNSCALE NIS-8AU NIS LPRM FAILURE UPSCALE/DOWNSCALE NIS-8AV NIS LPRM FAILURE UPSCALE/DOWNSCALE NIS-8AW NIS LPRM FAILURE UPSCALE/DOWNSCALE November 16, 1994 Page 9 of 27

APPENDIX C ATTACHMENTC-3 WASHINGTON PUBLIC POWER SUPPLY SYSTEM MALFUNCTIONS LISTING ID SYSTEM DESCRIPTION NIS-8AX NIS LPRM FAILURE UPSCALE/DOWNSCALE NIS-8AY NIS LPRM FAILURE UPSCALE/DOWNSCALE NIS-8AZ NIS LPRM FAILURE UPSCALE/DOWNSCALE NIS-8B NIS LPRM FAILURE UPSCALE/DOWNSCALE NIS-8BA NIS LPRM FAILURE UPSCALE/DOWNSCALE NIS-8BB NIS LPRM FAILURE UPSCALE/DOWNSCALE NIS-88C NIS LPRM FAILURE UPSCALE/DOWNSCALE NIS-8BD NIS LPRM FAILURE UPSCALE/DOWNSCALE NIS-8BE NIS LPRM FAILURE UPSCALE/DOWNSCALE NIS-8BF NIS LPRM FAILURE UPSCALE/DOWNSCALE NIS-8BG NIS LPRM FAILURE UPSCALE/DOWNSCALE NIS-8BH NIS LPRM FAILURE UPSCALE/DOWNSCALE NIS-8C NIS LPRM FAILURE UPSCALE/DOWNSCALE NIS-8D NIS LPRM FAILURE UPSCALE/DOWNSCALE NIS-8E NIS LPRM FAILURE UPSCALE/DOWNSCALE NIS-8F NIS LPRM FAILURE UPSCALE/DOWNSCALE NIS-8G NIS LPRM FAILURE UPSCALE/DOWNSCALE NIS-8H NIS LPRM FAILURE UPSCALE/DOWNSCALE NIS-8I NIS LPRM FAILURE UPSCALE/DOWNSCALE NIS-8J NIS LPRM FAILURE UPSCALE/DOWNSCALE NIS-8K NIS LPRM FAILURE UPSCALE/DOWNSCALE NIS-8L NIS LPRM FAILURE UPSCALE/DOWNSCALE NIS-8M NIS LPRM FAILURE UPSCALE/DOWNSCALE NIS-8N NIS LPRM FAILURE UPSCALE/DOWNSCALE NIS-80 NIS LPRM FAILURE UPSCALE/DOWNSCALE NIS-8P NIS LPRM FAILURE UPSCALE/DOWNSCALE NIS-8Q NIS LPRM FAILURE UPSCALE/DOWNSCALE NIS-8R NIS LPRM FAILURE UPSCALE/DOWNSCALE NIS-8S NIS LPRM FAILURE UPSCALE/DOWNSCALE NIS-8T NIS LPRM FAILURE UPSCALE/DOWNSCALE NIS-8U NIS LPRM FAILURE UPSCALE/DOWNSCALE NIS-8V NIS LPRM FAILURE UPSCALE/DOWNSCALE NIS-8W NIS LPRM FAILURE UPSCALE/DOWNSCALE NIS-8X NIS LPRM FAILURE UPSCALE/DOWNSCALE NIS-8Y NIS LPRM FAILURE UPSCALE/DOWNSCALE NIS-8Z NIS LPRM FAILURE UPSCALE/DOWNSCALE NSF-1 EPS POWER SUPPLY FAILURE- FUSE BLOWN NSF-1A EPS P/S FAILURE - FUSE CB7A BLOWN NSF-1B EPS P/S FAILURE - FUSE CB7B BLOWN OED-1 OED TRANSFORMER LOCKOUT TR-S OED-2 OED LOSS OF ALLOFFSITE POWER OED-3 OED TRANSFORMER LOCKOUT TR-B OGS-1 OGS SYSTEM LEAK CATALYTICRECOMBINER November 16, 1994 Page 10 of 27

APPENDIX C ATTACHMENTC-3 WASHINGTON PUBLIC POWER SUPPLY SYSTEM MALFUNCTIONSLISTING ID SYSTEM DESCRIPTION 0GS-lA OGS SYSTEM LEAKRECOMBINER OG-RC-5A OGS-1B OGS SYSTEM LEAKRECOMBINER OG-RC-5B OGS-2 OGS SYSTEM LEAKPREFILTER AREA OGS-3 OGS SYSTEM LEAKIN CHARCOALADSORBER 0GS-3A OGS SYSTEM LEAKIN ADSORBER TRAINA OGS-3B OGS SYSTEM LEAKIN ADSORBER TRAINB OGS-4 OGS DEACITVATED OGS-5 OGS STM LEAKIN BACH S JAE ROOM OGS-5A OGS STM LEAK IN S JAE ROOM A OGS-5B OGS STM LEAKIN SJAE ROOM B PCN-1 PCN LKIN CONT DWNSTRM OF CEP-V-1A/B PCN-2 PCN RUPT TAILPIP ABOVE SUPP POOL LVL PCN-2A PCN RUPT MS-RV-1A TAILPIP ABVSP LVL PCN-2B PCN RUPT MS-RV-2A TAILPIP ABV SP LVL PCN-2C PCN RUPT MS-RV-3A TAILPIP'ABV SP LVL PCN-2D PCN RUPT MS-RV-4A TAILPIP ABVSP LVL PCN-2E PCN RUPT MS-RV-1B TAILPIP ABV SP LVL PCN-2F PCN RUPT MS-RV-2B TAILPIP ABV SP LVL PCN-2G PCN RUPT MS-RV-3B TAILPIP ABVSP LVL PCN-2H PCN RUPT MS-RV-4B TAILPIP ABV SP LVL PCN-2I PCN RUPT MS-RV-5B TAILPIP ABVSP LVL PCN-2J PCN RUPT MS-RV-1C TAILPIP ABV SP LVL PCN-2K PCN RUPT MS-RV-2C TAILPIP ABV SP LVL PCN-2L PCN RUPT MS-RV-3C TAILPIP ABV SP LVL PCN-2M PCN RUPT MS-RV-4C TAILPIP ABV SP LVL PCN-2N PCN RUPT MS-RV-5C TAILPIP ABV SP LVL PCN-20 PCN RUPT MS-RV-1D TAILPIP ABV SP LVL PCN-2P PCN RUPT MS-RV-2D TAILPIP ABVSP LVL PCN-2Q PCN RUPT MS-RV-3D TAILPIP ABVSP LVL PCN-2R PCN RUPT MS-RV-4D TAILPIP ABVSP LVL PCN-3 PCN HI GAS CONCENTRATION IN PRI CONT PCN-3A PCN HI H2 CONCENTRATION IN DRYWELL PCN-3B PCN HI 02 CONCENTIMTIONIN DRYWELL PCN-3C PCN HI H2 CONCENTRATION IN WETWBLL 'I PCN-3D PCN 02 CONCENTRATION IN WETWELL PCN-4 PCN HYDROGEN IGNITION PCN-5 PCN CEP LEAKAGE PCN-5A PCN CEP LEAKAGE(DRYWELL)

PCN-5B PCN CEP LEAKAGE(WETWELL)

PCR-1 PCR PLACE HOLDER PCR-10 PCR PLACE HOLDER PCR-2 PCR PLACE HOLDER PCR-3 PCR PLACE HOLDER November 16, 1994 Page II of 27

APPENDIX C ATTACHMENTC-3 WASHINGTON PUBLIC POWER SUPPLY SYSTEM MALFUNCTIONS LISTING ID SYSTEM DESCRIPTION PCR-4 PCR PLACE HOLDER PCR-5 PCR PLACE HOLDER PCR-6 PCR PLACE HOLDER PCR-7 PCR PLACE HOLDER PCR-8 PCR PLACE HOLDER PCR-9 PCR PLACE HOLDER RBM-1 RBM ROD BLOCK MONITOR FAILURE RBM-1A RBM RBM-AFAILURE RBM-1B RBM RBM-B FAILURE RCC-1 RCC RCC LK IN SUPPLY HDR IN PRI CONT RCC-10 RCC RUPT DW COOLING LN INLET/OUTLET RCC-10A RCC RUPT DW COOLING LN CRA-CC-1A/B/C RCC-10B RCC RUPT DW COOLING LN TO CRA-CC-2B RCC-10C RCC RUPT DW COOLING LN FRM CRA-CC-2B RCC-2 RCC RCCW RETURN HDR LKIN PRI CONT RCC-3 RCC RCCW LEAKAT PUMP SUCTION RCC-4 RCC RCCW LK IN SUPPLY HDR TO OFF GAS RCC-5 RCC LOSS RCCW COOLING TO RECIRC PUMP RCC-SA RCC LOSS OF RCCW COOLING TO RRC-P-1A RCC-5B RCC LOSS OF RCCW COOLING TO RRC-P-1B RCC-6 RCC RCCW LK DOWNSTREAM OF RCC-FT-29 RCC-7 RCC RCCW LK CRD PUMP BEARING COOLER RCC-7A RCC RCCW LK AT CRD-P-1A BRNG COOLER RCC-7B RCC RCCW LK AT CRD-P-1B BRNG COOLER RCC-8 RCC LOSS RCCW FLOW CRD PMP BRNG CLR RCC-8A RCC LOSS RCCW FLOW CRD-P-1A BRNG CLR RCC-8B RCC LOSS RCCW FLOW CRD-P-1B BRNG CLR RCC-9 RCC LOSS RCCW FLOW TO DW EDR COOLER RCI-1 RCI RCIC TURBINE TRIP/PAILS TO TRIP RCI-2 RCI RUPTURE STM SUPPLY TO RCIC IN PC RCI-3 RCI RCIC TUR EXH DIARUPTURE IN RB RCI-4 RCI RUPT IN STM LN DWNSTRM RCIC-V-45 RCI-5 RCI RUPTURE TURB EXH LINE IN RX BLDG RCI-6 RCI STEAM LINE BREAK AT RCIC TUIUSINE RCI-7 RCI RCIC LOGIC FAILURE RCI-7A RCI RCIC LOGIC FAILURE DIVISION 1 RCI-7B RCI RCIC LOGIC FAILURE DIVISION2 RCX-1 RCX CLAD PERFORATION RCX-2 RCX GROSS CLAD FAILURE RCX-3 RCX HIGH ROD WORTH RCX-4 RCX SKEWED FLUX DISTRIBUTION RCX4A RCX SKEWED FLUX DISTRIBUTION RCX-4AA RCX SKEWED FLUX DISTRIBUTION Novembn 16, 1994 Page 12of27

APPENDIX C ATTACHMENTC-3 WASHINGTON PUBLIC POWER SUPPLY SYSTEM MALFUNCTIONS LISTING ID SYSTEM DESCRIPTION RCX-4AB RCX SKEWED FLUX DISTRIBUTION RCX-4AC RCX SKEWED FLUX DISTRIBUTION RCXPAD RCX SKEWED FLUX DISTRIBUTION RCX-4AE RCX SKEWED FLUX DISTRIBUTION RCX-4AF RCX SKEWED FLUX DISTRIBUTION RCX-4AG RCX SKEWED FLUX DISTRIBUTION RCX-4AH RCX SKEWED FLUX DISTRIBUTION RCX-4AI RCX SKEWED FLUX DISTRIBUTION RCX-4AJ RCX SKEWED FLUX DISTRIBUTION RCX-4AK RCX SKEWED FLUX DISTRIBUTION RCX4AL RCX SKEWED FLUX DISTRIBUTION RCX4AM RCX SKEWED FLUX DISTRIBUTION RCX-4AN RCX SKEWED FLUX DISTRIBUTION RCXPAO RCX SKEWED FLUX DISTRIBUTION RCX4AP RCX SKEWED FLUX DISTRIBUTION RCX-4AQ RCX SKEWED FLUX DISTRIBUTION RCX-4AR RCX SKEWED FLUX DISTRIBUTION RCX-4AS RCX SKEWED FLUX DISTRIBUTION RCX-4AT RCX SKEWED FLUX DISTRIBUTION RCX4AU RCX SKEWED FLUX DISTRIBUTION RC XIV RCX SKEWED FLUX DISTRIBUTION RCX-4AW RCX SKEWED FLUX DISTRIBUTION RCX-4AX RCX SKEWED FLUX DISTRIBUTION RCX-4B RCX SKEWED FLUX DISTRIBUTION RCX-4C RCX SKEWED FLUX DISTRIBUTION RCX4D RCX SKEWED FLUX DISTRIBUTION RCX-4E RCX SKEWED FLUX DISTRIBUTION RCX-4F RCX SKEWED FLUX DISTRIBUTION RCX4G RCX SKEWED FLUX DISTRIBUTION RCX-4H RCX SKEWED FLUX DISTRIBUTION RCX-4I RCX SKEWED FLUX DISTRIBUTION RCX-4J RCX SKEWED FLUX DISTRIBUTION RCX-4K RCX SKEWED FLUX DISTRIBUTION RCX-4L RCX SKEWED FLUX DISTRIBUTION RCX-4M RCX SKEWED FLUX DISTRIBUTION RCX-4N RCX SKEWED FLUX DISTRIBUTION RCXPO RCX SKEWED FLUX DISTRIBUTION RCX-4P SKEWED FLUX DISTRIBUTION

'CX RCX-4Q RCX SKEWED FLUX DISTRIBUTION RCX-4R RCX SKEWED FLUX DISTRIBUTION RCX-4S RCX SKEWED FLUX DISTRIBUTION RCX-4T RCX SKEWED FLUX DISTRIBUTION RCXPU RCX 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 SYSTEM DESCRIPTION RCX-4V RCX SKEWED FLUX DISTRIBUTION RCX-4W RCX SKEWED FLUX DISTRIBUTION RCX-4X RCX SKEWED FLUX DISTRIBUTION RCX-4Y RCX SKEWED FLUX DISTRIBUTION RCXCZ RCX SKEWED FLUX DISTRIBUTION RCX-5 RCX POWER OSCILLATIONS RCX-5A RCX PWR OSCILL,GLOBALgN PHASE)

RCX-5B RCX PWR OSCILL,REGION (OUT OF PHASE)

RFC-1 RFC RUPT IN HYD LN AT RRC-V-60B ACT RFC-2 RFC RUPT IN HYD LN AT RRC-V-60A ACT RFC-3 RFC FAILIN FEEDBACK LOOP - VLVPOS RFC-3A RFC FAILIN VLVPOS FB RRC-M/A-611A RFC-3B RFC FAILIN VLVPOS FB RRC-M/A-611B RFC-4 RFC HPU FAILURE - LEAD/BACKUPSYSTEM RFC-4A RFC HPU A SYS 1 FAILS - HY-HP-Al RFC-4B RFC HPU B SYS 1 FAILS - HY-HP-Bl RFC-4C RFC HPU A SYS 2 FAILS - HY-HP-A2 RFC-4D RFC HPU B SYS 2 FAILS - HY-HP-B2 RFC-5 RFC DEACIIVATED RHR-1 LINE BREAK AT RHR-P-2A SUCTION RHR-2 RHR LINE BREAK AT RHR-HX-1B RHR-3 RHR S/D COOLING LINE BRK IN SEC CONT RHRP RHR LPCI LOGIC FAILURE-A,B, AND C RHRQA RHR LPCI LOGIC FAILURE A RHR-4B RHR LPCI LOGIC FAILUREB AND C RMC-1 RMC HCU TRANSPONDER FAILURE RMC-1A RMC HCU TRANSPONDER FAILURE RMC-1AA RMC HCU TRANSPONDER FAILURE RMC-1AB RMC HCU 'IRANSPONDER FAILURE RMC-1AC RMC HCU TRANSPONDER FAILURE RMC-1 AD RMC HCU TRANSPONDER FAILURE RMC-lAE RMC HCU TRANSPONDER FAILURE RMC-lAF RMC HCU TRANSPONDER FAILURE RMC-1AG RMC HCU TRANSPONDER FAILURE RMC-1 AH HCU TRANSPONDER FAILURE RMC-1AI RMC HCU TRANSPONDER FAILURE RMC-1AJ RMC HCU TRANSPONDER FAILURE RMC-1AK RMC HCU 'IRANSPONDER FAILURE RMC-1AL RMC HCU TRANSPONDER FAILURE RMC-1AM HCU TRANSPONDER FAILURE RMC-1AN HCU TRANSPONDER FAILURE RMC-1AO HCU TRANSPONDER FAILURE RMC-1AP HCU TRANSPONDER FAILURE November 16, 1994 Page 14 of 27

APPENDIX C ATTACHMENTC-3 WASHINGTON PUBLIC POWER SUPPLY SYSTEM MALFUNCTIONS LISTING ID SYSTEM DESCRIPTION RMC-lAQ RMC HCU TRANSPONDER FAILURE RMC-1AR RMC HCU TRANSPONDER FAILURE RMC-1AS RMC HCU TRANSPONDER FAILURE RMC-1 AT RMC HCU TRANSPONDER FAILURE RMC-lAU RMC HCU TRANSPONDER FAILURE RMC-1AV RMC HCU TRANSPONDER FAILURE RMC-1AW RMC HCU TRANSPONDER FAILURE RMC-1AX RMC, HCU TRANSPONDER FAILURE RMC-lAY RMC HCU TRANSPONDER FAILURE RMC-1AZ RMC HCU, TRANSPONDER FAILURE RMC-1B RMC HCU TRANSPONDER FAILURE RMC-1BA RMC HCU TRANSPONDER FAILURE RMC-1BB RMC HCU TIMNSPONDER FAILURE RMC-1BC RMC HCU TRANSPONDER FAILURE RMC-1BD RMC HCU TRANSPONDER FAILURE RMC-1BE RMC HCU TRANSPONDER FAILURE RMC-1BF RMC HCU TRANSPONDER FAILURE RMC-1BG RMC HCU 'IRANSPONDER FAILURE RMC-1BH RMC HCU TRANSPONDER FAILURE RMC-1C RMC HCU TIMNSPONDER FAILURE RMC-1D RMC HCU TRANSPONDER FAILURE RMC-1E RMC HCU TRANSPONDER FAILURE RMC-1F RMC HCU TRANSPONDER FAILURE RMC-1G RMC HCU TRANSPONDER FAILURE RMC-1H RMC HCU TRANSPONDER FAILURE RMC-1I RMC HCU TRANSPONDER FAILURE RMC-1J RMC HCU 'IRANSPONDER FAILURE RMC-1K RMC HCU 'IRANSPONDER FAILURE RMC-1L RMC HCU TRANSPONDER FAILURE RMC-1M RMC HCU TRANSPONDER FAILURE RMC-1N RMC HCU TRANSPONDER FAILURE RMC-10 "RMC HCU TRANSPONDER FAILURE RMC-1P RMC HCU TRANSPONDER FAILURE RMC-1Q RMC HCU TRANSPONDER FAILURE RMC-1R RMC HCU TRANSPONDER FAILURE RMC-1S RMC HCU TRANSPONDER FAILURE RMC-1T RMC HCU TRANSPONDER FAILURE RMC-1U RMC HCU TRANSPONDER FAILURE RMC-1V RMC HCU TRANSPONDER FAILURE RMC-1W RMC HCU TRANSPONDER FAILURE RMC-1X RMC HCU TRANSPONDER FAILURE RMC-1Y RMC HCU TRANSPONDER FAILURE RMC-1Z RMC HCU TRANSPONDER FAILURE November 16, 1994 Page 15 of 27

APPENDIX C ATTACHMENTC-3 WASHINGTON PUBLIC POWER SUPPLY SYSTEM MALFUNCTIONS LISTING ID SYSTEM DESCRIPTION RMC-2 RMC ROD POSITION INDICATIONFAILURE RMC-3 RMC RDCS FAILURE RMC-4 CRD ROD DRIFTS IN/OUT RMC-4A CRD ROD DRIFTS IN/OUT RMC-4AA CRD ROD DRIFTS IN/OUT RMC-4AB CRD ROD DRIFTS IN/OUT RMC-4AC CRD ROD DRIFTS IN/OUT RMC-4AD CRD ROD DRIFTS IN/OUT RMC-4AE CRD ROD DRIFTS IN/OUT RMC-4AF CRD ROD DRIFTS IN/OUT RMC-4AG CRD ROD DRIFTS IN/OUT RMC-4AH CRD ROD DRIFTS IN/OUT RMC-4AI CRD ROD DRIFTS IN/OUT RMC-4AJ CRD ROD DRIFTS IN/OUT RMC-4AK CRD ROD DRIFTS IN/OUT RMC-4AL CRD ROD DRIFTS IN/OUT RMC-4AM CRD ROD DRIFTS IN/OUT RMC-4AN CRD ROD DRIFTS IN/OUT RMC-4AO CRD ROD DRIFTS IN/OUT RMC-4AP CRD ROD DRIFTS IN/OUT RMC-4AQ CRD ROD DRIFTS IN/OUT RMC-4AR CRD ROD DRIFTS IN/OUT RMC-4AS CRD ROD DRIFTS IN/OUT RMC-4AT CRD ROD DRIFTS IN/OUT RMC-4AU CRD ROD DRIFTS IN/OUT RMC-4AV CRD ROD DRIFTS IN/OUT RMC-4AW CRD ROD DRIFTS IN/OUT RMC-4AX CRD ROD DRIFTS IN/OUT RMC-4AY CRD ROD DRIFTS IN/OUT RMC-4AZ CRD ROD DRIFTS IN/OUT RMC-48 CRD ROD DRIFTS IN/OUT RMC-4BA CRD ROD DRIFTS IN/OUT RMC-4BB CRD ROD DRIFTS IN/OUT RMC-4BC CRD ROD DRIFTS IN/OUT RMC-4BD CRD ROD DRIFTS IN/OUT RMC-4BE CRD ROD DRIFTS IN/OUT RMC-4BF CRD ROD DRIFTS IN/OUT RMC-4B6 CRD ROD DRIFTS IN/OUT RMC-4BH CRD ROD DRIFTS IN/OUT RMC-4C CRD ROD DRIFTS IN/OUT RMC-4D CRD ROD DRIFTS IN/OUT RMC-4E CRD ROD DRIFTS IN/OUT RMC-4F CRD ROD DRIFTS IN/OUT November 16, 1994 Page 16 of 27

APPENDIX C ATTACHMENTC-3 WASHINGTON PUBLIC POWER SUPPLY SYSTEM MALFUNCTIONS LISTING ID SYSTEM DESCRIPTION RMC-4G CRD ROD DRIFTS IN/OUT RMC-4H CRD ROD DRIFTS IN/OUT RMC-4I CRD ROD DRIFTS IN/OUT RMC-4J CRD ROD DRIFTS IN/OUT RMC-4K CRD ROD DRIFTS IN/OUT RMC-4L CRD ROD DRIFTS IN/OUT RMC-4M CRD ROD DRIFTS IN/OUT RMC-4N CRD ROD DRIFTS IN/OUT RMC-40 CRD ROD DRIFTS IN/OUT RMC-4P CRD ROD DRIFTS IN/OUT RMC-4Q CRD ROD DRIFTS IN/OUT RMC-4R CRD ROD DRIFTS IN/OUT RMC-4S CRD ROD DRIFTS IN/OUT RMC-4T CRD ROD DRIFTS IN/OUT RMC-4U CRD ROD DRIFTS IN/OUT RMC-4V CRD ROD DRIFTS IN/OUT RMC-4W CRD ROD DRIFTS IN/OUT RMC-4X CRD ROD DRIFTS IN/OUT RMC-4Y CRD ROD DRIFTS IN/OUT RMC-4Z CRD ROD DRIFTS IN/OUT RMC-5 CRD STUCK ROD RMC-5A CRD STUCK ROD RMC-5AA CRD STUCK ROD RMC-SAB CRD STUCK ROD RMC-SAC CRD STUCK ROD RMC-SAD CRD STUCK ROD RMC-5AE CRD STUCK ROD RMC-SAP CRD STUCK ROD RMC-SAG CRD STUCK ROD RMC-5AH CRD STUCK ROD RMC-SAI CRD STUCK ROD RMC-5AJ CRD STUCK ROD RMC-SAK CRD STUCK ROD RMC-SAL CRD STUCK ROD RMC-SAM CRD STUCK ROD RMC-5AN CRD STUCK ROD RMC-5AO CRD STUCK ROD RMC-SAP CRD STUCK ROD RMC-SAQ CRD STUCK ROD RMC-SAR CRD STUCK ROD RMC-5AS CRD STUCK ROD RMC-5AT CRD STUCK ROD RMC-SAU CRD STUCK ROD November 16, 1994 Page 17 of 27

APPENDIX C ATTACHMENTC-3 WASHINGTON PUBLIC POWER SUPPLY SYSTEM MALFUNCTIONS LISTING ID SYSTEM DESCRIPTION RMC-SAV CRD STUCK ROD RMC-SAW CRD STUCK ROD RMC-SAX CRD STUCK ROD RMC-5AY CRD STUCK ROD RMC-SAZ CRD STUCK ROD RMC-5B CRD STUCK ROD RMC-SBA CRD STUCK ROD RMC-SBB CRD STUCK ROD RMC-SBC CRD STUCK ROD RMC-SBD CRD STUCK ROD RMC-5BE CRD STUCK ROD RMC-5BF CRD STUCK ROD RMC-5BG CRD STUCK ROD RMC-5BH CRD STUCK ROD RMC-SC CRD STUCK ROD RMC-SD CRD STUCK ROD RMC-SE CRD STUCK ROD RMC-SF CRD STUCK ROD RMC-5G CRD STUCK ROD RMC-SH CRD STUCK ROD RMC-SI CRD STUCK ROD RMC-SJ CRD STUCK ROD RMC-5K CRD STUCK ROD RMC-SL CRD STUCK ROD RMC-SM CRD STUCK ROD RMC-5N CRD STUCK ROD RMC-50 CRD STUCK ROD RMC-SP CRD STUCK ROD RMC-SQ CRD STUCK ROD RMC-SR CRD STUCK ROD RMC-SS CRD STUCK ROD RMC-ST CRD STUCK ROD RMC-SU CRD STUCK ROD RMC-SV CRD STUCK ROD RMC-SW CRD STUCK ROD RMC-SX , CRD STUCK ROD RMC-SY CRD STUCK ROD RMC-SZ CRD STUCK ROD RMC-6 CRD UNCOUPLED ROD RMC-6A CRD UNCOUPLED ROD RMC-6AA CRD UNCOUPLED ROD RMC-6AB CRD UNCOUPLED ROD RMC-6AC CRD UNCOUPLED ROD November 16, 1994 Page 18 of 27

APPENDIX C ATTACHMENTC-3 WASHINGTON PUBLIC POWER SUPPLY SYSTEM MALFUNCTIONS LISTING ID SYSTEM DESCRIPTION RMC-6AD CRD UNCOUPLED ROD RMC-6AE CRD UNCOUPLED ROD RMC-6AF CRD UNCOUPLED ROD RMC-6AG CRD UNCOUPLED ROD RMC-6AH CRD UNCOUPLED ROD RMC-6AI CRD UNCOUPLED ROD RMC-6AJ CRD UNCOUPLED ROD RMC-6AK CRD UNCOUPLED ROD RMC-6AL CRD UNCOUPLED ROD RMC-6AM CRD UNCOUPLED ROD RMC-6AN CRD UNCOUPLED ROD RMC-6AO CRD UNCOUPLED ROD RMC-6AP CRD UNCOUPLED ROD RMC-6AQ CRD UNCOUPLED ROD RMC-6AR CRD UNCOUPLED ROD RMC-6AS CRD UNCOUPLED ROD RMC-6AT CRD UNCOUPLED ROD RMC-6AU CRD UNCOUPLED ROD RMC-6AV CRD UNCOUPLED ROD RMC-6AW CRD UNCOUPLED ROD RMC-6AX CRD UNCOUPLED ROD RMC-6AY CRD UNCOUPLED ROD RMC-6AZ CRD UNCOUPLED ROD RMC-6B CRD UNCOUPLED ROD RMC-6BA CRD UNCOUPLED ROD RMC-6BB CRD UNCOUPLED ROD RMC-6BC CRD UNCOUPLED ROD RMC-6BD CRD UNCOUPLED ROD RMC-6BE CRD UNCOUPLED ROD RMC-6BF CRD UNCOUPLED ROD RMC-6B6 CRD UNCOUPLED ROD RMC-6BH CRD UNCOUPLED ROD RMC-6C CRD UNCOUPLED ROD RMC-6D CRD UNCOUPLED ROD RMC-6E CRD UNCOUPLED ROD RMC-6F CRD UNCOUPLED ROD RMC-6G CRD UNCOUPLED ROD RMC-6H CRD UNCOUPLED ROD RMC-6I CRD UNCOUPLED ROD RMC-6J CRD UNCOUPLED ROD RMC-6K CRD UNCOUPLED ROD RMC-6L CRD UNCOUPLED ROD RMC-6M CRD UNCOUPLED ROD November 16, 1994 Page 19 of 27

APPENDIX C ATTACHMENTC-3 WASHINGTON PUBLIC POWER SUPPLY SYSTEM MALFUNCTIONS LISTING ID SYSTEM DESCRIPTION RMC-6N CRD UNCOUPLED ROD RMC-60 CRD UNCOUPLED ROD RMC-6P CRD UNCOUPLED ROD RMC-6Q CRD UNCOUPLED ROD RMC-6R CRD UNCOUPLED ROD RMC-6S CRD UNCOUPLED ROD RMC-6T CRD UNCOUPLED ROD RMC-6U CRD UNCOUPLED ROD RMC-6V CRD UNCOUPLED ROD RMC-6W CRD UNCOUPLED ROD RMC-6X CRD UNCOUPLED ROD RMC-6Y CRD UNCOUPLED ROD RMC-6Z CRD UNCOUPLED ROD RMC-7 RPS SINGLE ROD SCRAM RMC-7A RPS SINGLE ROD SCRAM RMC-7AA RPS SINGLE ROD SCRAM RMC-7AB RPS SINGLE ROD SCRAM RMC-7AC RPS SINGLE ROD SCRAM RMC-7AD RPS SINGLE ROD SCRAM RMC-7AE RPS SINGLE ROD SCRAM RMC-7AF RPS SINGLE ROD SCRAM RMC-7AG RPS SINGLE ROD SCRAM RMC-7AH RPS SINGLE ROD SCRAM RMC-7AI RPS SINGLE ROD SCRAM RMC-7AJ RPS SINGLE ROD SCRAM RMC-7AK RPS SINGLE ROD SCRAM RMC-7AL RPS SINGLE ROD SCRAM RMC-7AM RPS SINGLE ROD SCRAM RMC-7AN RPS SINGLE ROD SCRAM RMC-7AO RPS SINGLE ROD SCRAM RMC-7AP RPS SINGLE ROD SCRAM RMC-7AQ RPS SINGLE ROD SCRAM RMC-7AR RPS SINGLE ROD SCRAM RMC-7AS RPS SINGLE ROD SCRAM RMC-7AT RPS SINGLE ROD SCRAM RMC-7AU RPS SINGLE ROD SCRAM RMC-7AV RPS SINGLE ROD SCRAM RMC-7AW RPS SINGLE ROD SCRAM RMC-7AX RPS SINGLE ROD SCRAM RMC-7AY RPS SINGLE ROD SCRAM RMC-7AZ RPS SINGLE ROD SCRAM RMC-7B RPS SINGLE ROD SCRAM RMC-7BA RPS SINGLE ROD SCRAM November 16, 1994 Page 20 of 27

APPENDIX C ATTACHMENTC-3 WASHINGTON PUBLIC POWER SUPPLY SYSTEM MALFUNCTIONS LISTING ID SYSTEM DESCRIPTION RMC-7BB RPS SINGLE ROD SCRAM RMC-7BC RPS SINGLE ROD SCRAM RMC-7BD RPS SINGLE ROD SCRAM RMC-7BE RPS SINGLE ROD SCRAM RMC-7BF RPS SINGLE ROD SCRAM RMC-7BG RPS SINGLE ROD SCRAM RMC-7BH RPS SINGLE ROD SCRAM RMC-7C RPS SINGLE ROD SCRAM RMC-7D RPS SINGLE ROD SCRAM RMC-7E RPS SINGLE ROD SCRAM RMC-7F RPS SINGLE ROD SCRAM RMC-7G RPS SINGLE ROD SCRAM RMC-7H RPS SINGLE ROD SCRAM RMC-7I RPS SINGLE ROD SCRAM RMC-7J RPS SINGLE ROD SCRAM RMC-7K RPS SINGLE ROD SCRAM RMC-7L RPS SINGLE ROD SCRAM RMC-7M RPS SINGLE ROD SCRAM RMC-7N RPS SINGLE ROD SCRAM RMC-70 RPS SINGLE ROD SCRAM RMC-7P RPS SINGLE ROD SCRAM RMC-7Q RPS SINGLE ROD SCRAM RMC-7R RPS SINGLE ROD SCRAM RMC-7S RPS SINGLE ROD SCRAM RMC-7T RPS SINGLE ROD SCRAM RMC-7U RPS SINGLE ROD SCRAM RMC-7V RPS SINGLE ROD SCRAM RMC-7W RPS SINGLE ROD SCRAM RMC-7X RPS SINGLE ROD SCRAM RMC-7Y RPS SINGLE ROD SCRAM RMC-7Z RPS SINGLE ROD SCRAM RMC-8 RMC REED SWITCH FAILURE RMC-8A RMC REED SWITCH FAILURE RMC-8AA RMC REED SWITCH FAILURE RMC-8AB RMC REED SWITCH FAILURE RMC-8AC RMC REED SWITCH FAILURE RMC-8AD RMC REED SWITCH FAILURE RMC-8AE RMC REED SWITCH FAILURE RMC-8AF RMC REED SWITCH FAILURE RMC-8AG RMC REED SWITCH FAILURE RMC-8AH RMC REED SWITCH FAILURE RMC-8AI RMC REED SWITCH FAILURE RMC-8AJ RMC REED SWITCH FAILURE November 16, 1994 Page 21 of 27

APPENDIX C ATTACHMENTC-3 WASHINGTON PUBLIC POWER SUPPLY SYSTEM MALFUNCTIONS LISTING ID SYSTEM DESCRIPTION RMC-8AK RMC REED SWITCH FAILURE RMC-SAL RMC REED SWITCH FAILURE RMC-SAM RMC REED SWITCH FAILURE RMC-8AN RMC REED SWITCH FAILURE RMC-8AO RMC REED SWITCH FAILURE RMC-SAP RMC REED SWITCH FAILURE RMC-8AQ RMC REED SWITCH FAILURE RMC-8AR RMC REED SWITCH FAILURE RMC-8AS RMC REED SWITCH FAILURE RMC-SAT RMC REED SWITCH FAILURE RMC-SAU RMC REED SWITCH FAILURE RMC-SAV RMC REED SWITCH FAILURE RMC-8AW RMC REED SWITCH FAILURE RMC-8AX RMC REED SWITCH FAILURE RMC-8AY RMC REED SWITCH FAILURE RMC-SAZ RMC REED SWITCH FAILURE RMC-8B RMC REED SWITCH FAILURE RMC-8BA RMC REED SWITCH FAILURE RMC-8BB RMC REED SWITCH FAILURE RMC-SBC RMC REED SWITCH FAILURE RMC-8BD RMC REED SWITCH FAILURE RMC-8BE RMC REED SWITCH FAILURE RMC-8BF RMC REED SWITCH FAILURE RMC-8BG RMC REED SWITCH FAILURE RMC-88H RMC REED SWITCH FAILURE RMC-8C RMC REED SWITCH FAILURE RMC-SD RMC REED SWITCH FAILURE RMC-8E RMC REED SWITCH FAILURE RMC-SF RMC REED SWITCH FAILURE RMC-8G RMC REED SWITCH FAILURE RMC-8H RMC REED SWITCH FAILURE RMC-SI RMC REED SWITCH FAILURE RMC-SJ RMC REED SWITCH FAILURE RMC-8K RMC REED SWITCH FAILURE RMC-8L RMC REED SWITCH FAILURE RMC-SM RMC REED SWITCH FAILURE RMC-SN RMC REED SWITCH FAILURE RMC-80 RMC REED SWITCH FAILURE RMC-8P RMC REED SWITCH FAILURE RMC-8Q RMC REED SWITCH FAILURE RMC-8R RMC REED SWITCH FAILURE RMC-8S RMC REED SWITCH FAILURE RMC-8T RMC REED SWITCH FAILURE November 16, 1994 Page 22 of 27

APPENDIX C ATTACHMENTC-3 WASHINGTON PUBLIC POWER SUPPLY SYSTEM MALFUNCTIONS LISTING ID SYSTEM DESCRIPTION RMC-8U RMC REED SWITCH FAILURE RMC-8V RMC REED SWITCH FAILURE RMC-8W REED SWITCH FAILURE RMC-8X REED SWITCH FAILURE RMC-8Y REED SWITCH FAILURE RMC-8Z REED SWITCH FAILURE RPS-1 RPS SCRAM GROUP FUSES BLOWN RPS-1A RPS SCRAM FUSE BLOWN - GPl F18A RPS-1B RPS SCRAM FUSE BLOWN - GP1 F18B RPS-1C RPS SCRAM FUSE BLOWN - GP2 F18E RPS-1D RPS SCRAM FUSE BLOWN - GP2 F18F RPS-1E RPS RPS SCRAM FUSE BLOWN - GP3 F18C RPS-1F RPS RPS SCRAM FUSE BLOWN - GP3 F18D RPS-1G RPS RPS SCRAM FUSE BLOWN - GP4 F18G RPS-1H RPS RPS SCRAM FUSE BLOWN - GP4 F18H RRP-1 RRP RECIRCULATION PUMP SEAL FAILURE RRP-1A RRP RRC-P-1A LOWER SEAL FAILURE RRP-1B RRP RRC-P-1B LOWER SEAL FAILURE RRP-1C RRP RRC-P-1A UPPER SEAL FAILURE RRP-1D RRP RRC-P-1B UPPER SEAL FAILURE RRP-2 RRP RECIRCULATION PUMP HI VIBRATION RRP-2A RRP RRC-P-1A HIGH VIBRATION RRP-2B RRP RRC-P-1B HIGH VIBRATION RRS-1 RRS HIGH REACTOR WATER CONDUCTIVITY RRS-lA RRS HI RX WATER COND VIARWCU-DM-A RRS-1B RRS HI RX WATER COND VIARWCU-DM-B RRS-2 RRS JET PUMP FAILURE RRS-2A RRS FAILURE JET PUMPS 1 AND 2 RRS-2B RRS FAILURE JET PUMPS 3 AND 4 RRS-2C RRS FAILUREJET PUMPS 5 AND 6 RRS-2D RRS FAILURE JET PUMPS 7 AND 8 RRS-2E RRS FAILURE JET PUMPS 9 AND 10 RRS-2F RRS FAILUREJET PUMPS 11 AND 12 RRS-2G RRS FAILUREJET PUMPS 13 AND 14 RRS-2H RRS FAILUREJET PUMPS 15 AND 16 RRS-2I RRS FAILURE JET PUMPS 17 AND 18 RRS-2J RRS FAILURE JET PUMPS 19 AND 20 RRS-3 RRS MN STM LN BRK AFTER FLOW RSTRCTR RRS-3A RRS MN STM LN A BRK AFT FLOW RSTRCIR RRS-3B RRS MN STM LN B BRK AFT FLOW RSTRCI'R RRS-3C RRS MN STM LN C BRK AFT FLOW RSTRCIR RRS-3D RRS MN STM LN D BRK AFT FLOW RSTRCTR RRS-4 RRS RECIRC LN RUPT-PMP A/B SUCT/DISC November 16, 1994 Page 23 of 27

APPENDIX C ATTACHMENTC-3 WASHINGTON PUBLIC POWER SUPPLY SYSTEM MALFUNCTIONSLISTING ID SYSTEM DESCRIPTION RRS-4A RRS RECIRC LINE RUPT- RRC-P-1A SUCT RRS-4B RRS RECIRC LINE RUPT- RRC-P-1B SUCT RRSPC RRS RECIRC LINE RUPT- RRC-P-1A DISCH RRS-4D RRS RECIRC LINE RUPT- RRC-P-1B DISCH RRS-5 RRS INSTRUMENT LINE VARIABLELEG BRK RRS-5A RRS INST VAR LN BRK- PENETRATION 12A RRS-5B RRS INST VAR LN BRK- PENETRATION 12B RRS-5C RRS INST VAR LN BRK- PENKZViTION 12C RRS-5D RRS INST VAR LN BRK- PENEl'RATION 12D RRS-5E RRS INST VAR LN BRK- PENETRATION 13A RRS-5F RRS INST VAR LN BRK- PENETRATION 13B RRS-6 RRS MAINSTM LN BREAK IN STM TUNNEL RRS-6A RRS MSL-ABREAK IN THE STEAM TUNNEL RRS-6B RRS MSL-B BREAK IN THE STEAM TUNNEL RRS-6C RRS MSL-C'BREAKIN THE STEAM TUNNEL RRS-6D RRS MSL-D BREAK IN THE STEAM TUNNEL RRS-7 RRS INST LINE REFERENCE LEG BREAK RRS-7A RRS INST LN BRK BTW RPV&CU4A IN CONT RRS-7B RRS INST LN BRK BTW RPV&CU4B IN CONT RRS-7C RRS INST LN BRK BTW RPV&CU4C IN CONT RRS-7D RRS INST LN BRK BTW RPV&CU4D IN CONT RRS-7E RRS INST LN BRK DOWNSTRM PI-EFC-X114 RRS-7F RRS INST LN BRK DOWNSTRM PI-EFC-X109 RRS-7G RRS INST LN BRK DOWNSTRM PI-EFC-X112 RRS-7H RRS INST LN BRK DOWNSTRM PI-EFC-X106 RRS-8 RRS MN STEAM LN BRK IN TURBINE BLDG RRS-8A RRS MSL-ABREAK IN TURBINE BUILDING RRS-8B RRS MSL-B BREAK INTUIU3INE BUILDING RRS-8C RRS MSL-C BREAK IN TURBINE BUILDING RRS-8D RRS MSL-D BREAK IN TURBINE BUILDING RRS-9 RRS MN STM LN BRK BEFORE FLW RSTRCTR RRS-9A RRS MN STM LN A BRK BFR FLOW RSTRCIR RRS-9B RRS MN STM LN B BRK BFR FLOW RSTRCIR RRS-9C RRS MN STM LN C BRK BFR FLOW RSTRCIR RRS-9D RRS MN STM LN D BRK BFR FLOW RSTRCIR RSC-1 RSC RSCS FAILURE RWB-1 RWB EARTHQUAKE RWB-2 RWB RADWASTE TANKLEAKS RWB-2A RWB RADWASTE TANKEDR-TK-2 LEAK RWB-2B RWB RADWASTE TANKFDR-TK-6 LEAK RWM-1 RWM RWM FAILURE RWU-1 RWU RWCU LEAKIN PUMP ROOM RWU-lA RWU LEAKIN RWCU PUMP ROOM -A November 16, 1994 Page 24 of27

APPENDIX C ATTACHMENTC-3 WASHINGTON PUBLIC POWER SUPPLY SYSTEM MALFUNCTIONS LISTING ID SYSTEM DESCRIPTION RWU-1B RWU LEAKIN RWCU PUMP ROOM -B RWU-2 RWU RWCU LEAKIN RETURN LINE RWU-3, RWU RWCU LEAKIN DRYWELLSUCT LINE RWU-4 =

RWU RWCU LEAKIN HEAT EXCHANGER AREA RWU-5 RWU RWCU DEMNERALIZERPLUGGED RWU-5A RWU RWCU DEMN-APLUGGED RWU-5B RWU RWCU DEMN-B PLUGGED SCN-1 SCN RUPTURE IN SGT FILTER UNITS SCN-1A SCN RUPT IN SGT FILTER UNIT- TRAIN A SCN-18 SCN RUPT IN SGT FILTER UNIT- TRAIN B SLC-1 SLC RUPTURE IN SLC COMMON PUMP DISCH SSW-1 SSW LEAKBETWN SW-V-2B AND FI-602B TLO-1 TLO TO-TK-2 TANKLEAK TLO-2 TLO TURBINE LUBE OIL SYSTEM LEAK TLO-2A TLO TURBINE LUBE OIL SYSTEM LEAKA TLO-2B TLO TURBINE LUBE OIL SYSTEM LEAKB TLO-2C TLO TURBINE LUBE OIL SYSTEM LEAKC TLO-2D TLO TURBINE LUBE OIL SYSTEM LEAKD TLO-3 TLO RESTRICTED BEARING OIL PATH TLO-3A TLO RESTRICTED OIL PATH BEARING ¹1 TLO-38 TLO RESTRICTED OIL PATH BEARING ¹2 TLO-3C TLO RESTRICTED OIL PATH BEARING ¹3 TLO-3D TLO RESTRICTED OIL PATH BEARING ¹4 TLO-3E TLO RESTRICTED OIL PATH BEARING ¹5 TLO-3F TLO RESTRICTED OIL PATH BEARING ¹6 TLO-3G TLO, RESTRICTED OIL PATH BEARING ¹7 TLO-3H TLO RESTRICTED OIL PATH BEARING ¹8 TLO-3I TLO RESTRICTED OIL PATH BEARING ¹9 TLO-3J TLO RESTRICTED OIL PATH BEARING ¹10 TLO-3K TLO RESTRICTED OIL PATH BEARING ¹11 TSI-1 TSI HIGH TURBINE/GEN BEARING TEMP.

TSI-1A TSI HIGH TG TEMPERATURE BEARING ¹1 TSI-1B TSI HIGH TG TEMPERATURE BEARING ¹2 TSI-1C TSI HIGH TG TEMPERATURE BEARING ¹3 TSI-1D TSI HIGH TG TEMPERATURE BEARING ¹4 TSI-1E TSI HIGH TG TEMPERATURE BEARING ¹5 TSI-1F TSI HIGH TG TEMPERATURE BEARING ¹6 TSI-1G TSI HIGH TG TEMPERATURE BEARING ¹7 TSI-1H TSI HIGH TG TEMPERATURE BEARING ¹8 TSI-1I TSI HIGH TG TEMPERATURE BEARING ¹9 TSI-1J TSI HIGH TG TEMPERATURE BEARING ¹10 TSI-1K TSI HIGH TG TEMPERATURE BEARING ¹11 TSI-2 TSI HIGH THRUST BEARING WEAR November 16, 1994 Page 25 of 27

APPENDIX C ATTACHMENTC-3 WASHINGTON PUBLIC POWER SUPPLY SYSTEM MALFUNCTIONS LISTING ID SYSTEM DESCRIPTION TSI-3 TSI TURBINE GEN. HIGH VIBRATION TSI-3A TSI 'TG HIGH VIBRATIONBEARING ¹1 TSI-3B TSI TG HIGH VIBRATIONBEARING ¹2 TSI-3C TSI TG HIGH VIBRATIONBEARING ¹3 TSI-3D TSI TG HIGH VIBRATIONBEARING ¹4 TSI-3E TSI TG HIGH VIBRATIONBEARING ¹5 TSI-3F TSI TG HIGH VIBRATIONBEARING ¹6 TSI-3G TSI TG HIGH VIBRATIONBEARING ¹7 TSI-3H TSI TG HIGH VIBRATIONBEARING ¹8 TSI-3I TSI TG HIGH VIBRATIONBEARING ¹9 TSI-3J TSI TG HIGH VIBRATIONBEARING ¹10 TSI-3K TSI TG HIGH VIBRATIONBEARING ¹11 TSI-4 TSI HIGH ECCENTRICITY TSI-5 TSI HIGH DIFFERENTIALEXPANSION TSI-5A TSI HIGH DIFF EXPANSION - GOV END TSI-5B TSI HIGH DIFF EXPANSION - GEN END TSW-1 TSW TSW LEAKAT COMMON PUMP DISCHRGE TSW-2 TSW TSW LEAKIN REACI'OR BLDG.

TSW-3 TSW TSW LEAK DOWNSTRM OF TSW-PCV-20 TSW-4 TSW LOSS OF TSW TO BUS DUCT COOLERS TSW-5 TSW LOSS OF TSW TO H2 SEAL OIL CLRS TUR-1 TUR DRAIN LINE LEAKHD-TK-SA(B)

TUR-1A TUR DRN LINE LEAKHD-TK-5A TUR-1B TUR DRN LINE LEAKHD-TK-5B TUR-2 TUR MSR LN BRK BETWN INCEPT/STOP VLV TUR-2A TUR MSR LN BRK DOWNSTRM OF MS-V-166A TUR-2B TUR MSR LN BRK DOWNSTRM OF MS-V-166B TUR-2C TUR MSR LN BRK DOWNSTRM OF MS-V-166C TUR-2D TUR MSR LN BRK DOWNSTRM OF MS-V-163A TUR-2E TUR MSR LN BRK DOWNSTRM OF MS-V-163B TUR-2F TUR MSR LN BRK DOWNSTRM OF MS-V-163C TUR-3 TUR STM LEAKAT EA MOIST SEPARATOR TUR-3A TUR STEAM LEAKAT A MSR TUR-3B TUR STEAM LEAKAT B MSR TUR-4 TUR RUPTURE IN STEAM SEAL HEADER TUR-4A TUR RUPTURE IN STM SEAL MAINHEADER TUR-4B TUR RUPTURE IN STEAM SEAL HDR RFT-1A TUR-4C TUR RUPTURE IN STEAM SEAL HDR RFT-1B TUR-4D TUR RUPT SEAL STM HDR NEAR BRG1 TUR-4E TUR RUPT SEAL STM HDR NEAR BRG2 TUR-4F TUR RUPT SEAL STM HDR NEAR BRG3 TUR-4G TUR RUPT SEAL STM HDR NEAR BRG4, TUR-4H TUR RUPT SEAL STM HDR NEAR BRG5 November 16, 1994 Page 26 of 27

APPENDIX C ATTACHMENTC-3 WASHINGTON PUBLIC POWER SUPPLY SYSTEM MALFUNCTIONS LISTING ID SYSTEM DESCRIPTION TUR-4I TUR RUPT SEAL STM HDR NEAR BRG6 TUR-4J TUR RUPT SEAL STM HDR NEAR BRG7 TUR-4K TUR RUPT SEAL STM HDR NEAR BRG8 TUR-5 TUR STEAM LEAKAFTER STEAM CHESTS TUR-6 TUR STEAM LEAKIN LOW PRESS TURBINE TUR-6A TUR STEAM LEAKIN LP TURBINE-A TUR-6B TUR STEAM LEAKIN LP TURBINE-B TUR-6C TUR STEAM LEAKIN LP TURBINE-C TUR-7 TUR REHEATER TUBE RUPTURE TUR-7A TUR 1ST STGE RHTR A TUBE BUNDLE RUPT TUR-7B TUR 2ND STGE RHTR A TUBE BUNDLE RUPT TUR-7C TUR 1ST STGE RHTR B TUBE BUNDLE RUPT TUR-7D TUR 2ND STGE RHTR B TUBE BUNDLERUPT TUR-8 TUR LEAKAT TURBINE BYPASS MANIFOLD TOTAL COUNT: 1132 November 16, 1994 Page 27 of 27

APPENDIX C ATTACHMENTC-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. Ifvalve closure is attempted (manually or automatically),'valve willclose, but willreopen 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. Ifvalve opening is attempted (manually or automatically), valve willopen, but willre-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 ifvalve movement is attempted or in progress.

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APPENDIX C ATTACHMENTC-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 ATTACHMENTCA 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.

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APPENDIX C ATTACHMENTC-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) Valve closure failure; valve remains in full closed position independent of system pressure while failure is active.

5) 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, Ifno 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. Ifno 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) Variable device failure - automatic mode. Identical to K.labove except affects only the automatic (and, ifapplicable, cascade) mode output of controllers and automatic/manual stations. The device functions normally in the manual mode.

3) 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:

Bistable fail to trip; bistable output signal fails to change to trip state for any value of the monitored variable parameter.

2) Bistable spurious trip; bistable output maintained in the tripped state for any value of the monitored variable parameter.

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APPENDIX C ATTACHMENTCR 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 If value in percent of span. 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 SIMULATORACCEPTANCE 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 ATTACHMENTD-1 WASHINGTON PUBLIC POWER SUPPLY SYSYTEM ANSI/ANS-3.5 (1985) REQUIREMENTS VERSUS SIMULATORACCEPTANCE TEST PROCEDURES General Requirements 3.1 Simulator Capabilities 3.1.1 Normal Plant Evolutions 3.1.1(1) Plant Startup 14.4.7.1 - Normal Plant Operations 3.1.1(2) Nuclear Startup 14.4.7.2.1 - Startup from Hot Shutdown to Rated Pressure 3.1.1(3) Turbine Startup and Gen Synchronization 14.4.7.1 - Normal Plant Operations 3.1.1(4) Reactor SCRAM/Recovery to 100% Power 14.4.7.2.1 - Startup from Hot Shutdown to Rated Pressure 3.1.1(5) Operations at Hot Standby 14.4.7.2.3 - SD to HSD 3.1.1(6) Load Changes 14.4.7.1 - Normal Plant Operations 3.1.1(8) Plant S/D from Rated Power to Cold S/D 14.4.7.1 - Normal Plant Operations 3.1.1(9) 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 3.1.1(10) 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

14.4.9.24.80 - RPS Fails to SCRAM 3.1.2(12) 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 3.1.2(13) Inability to Drive Rods 14.4.9.3.6 - RDCS Failure 3.1.2(14) Fuel Cladding Failure 14.4.9.7.1 - Small Clad Fall 14.4.9.7.2 - Gross Clad Fail 3.1.2(15) 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 3.1.2(16) Generator Trip 14.4.9.13.1 - Main Generator Trip 3.1.2(17) 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 3.1.2(19) Reactor Trip 14.4.9.24.33 - Manual Scram 3.1.2(20) 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 3.1.2(21) 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 3.1.2(22) 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

14.4.9.24.67C - RFW-L1-606B Fails High 3.1.2(23) 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 3.1.2(24) 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 3.1.2(25) 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 ATTACHMENT0-2 WASHINGTON PUBLIC POWER SUPPLY SYSTEM COMPUTER SPARE CAPACITYABSTRACT

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'HALCONDITIONS: 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 ATTACHMENTD-3 WASHINGTON PUBLIC POWER SUPPLY SYSTEM NORMALPLANT EVOLUTIONTEST ABSTRACTS

0 OPERATIONAL REVIEW

SUMMARY

TEST CATEGORY: Normal Operations TEST No. 14.4.7.1 REV. 4 TITLE: NORMALPLANT 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'IALCONDITIONS: IC-14 100% Power Equilibrium Xenon.

FINAL CONDITIONS: 100% Power Xenon Concentration Increasing to Equilibrium.

SOURCE OF COMPARISON DATA:

X PLANT DATA PLANTSD DATASET SEI'NGINEERING SHUTDOWN.DOC EVALUATION START .DO FSAR SU99109.DOC SOER/LBR X OPERATIONALASSESSMENT 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: PLAlVTOPERATION 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'GALCONDITIONS: IC 0% Power Ready for Startup, or HSD IC-0% Power Ready for Startup.

FINALCONDITIONS: 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 OPERATIONALASSESSMENT 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.

INITIALCONDITIONS: IC-16, Shutdown in progress, 14% Power, 920 psig.

FINALCONDITIONS: Reactor is Shutdown and Plant is in Hot Shutdown.

SOURCE OF COMPARISON DATA:

g PLANT DATA C cle 6 Shutdown Data SEI'NGINEERING EVALUATION FSAR SOER/LER X OPERATIONALASSESSMENT 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'IYand 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.

INITIALCONDITIONS: Multiple IC's for BOC, MOC and ROC.

SOURCE OF COMPARISON DATA:

PLANT DATASET 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.

INITIALCONDITIONS: IC-14, 100% Power with Equilibrium Xenon.

FINALCONDITIONS: Reactor Scrammed with minimum CSD Xe conditions.

SOURCE OF COMPARISON DATA:

PLANT DATA SET X BNGINBERING EVALUATION NEDE-24 1 Vol. 1 FSAR SOBR/LER g OPERATIONALASSESSMENT 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 - SRMIIRMREPONSE 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.,

INITIALCONDITIONS: '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 VALVEOPER4BILI7T 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.

INITIALCONDITIONS: In accordance with the testing requirements of the specific Surveillance.

FINALCONDITIONS: In accordance with the testing requirements of the specific Surveillance.

SOURCE OF COMPARISON DATA; PLANT DATA SEI'NGINEERING EVALUATION TSS 7.4.0.5.6 FSAR SUER/LER OPERATIONAL ASSESSMENT 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 VALVEOPERABILIXY 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.

INITIALCONDITIONS: In accordance with the testing requirements of the specific t Surveillance.

FINAL CONDITIONS: In accordance with the testing requirements of the specific SOURCE OF COMPARISON DATA:

Surveillance.

PLANT DATASET g ENGINEERING EVALUATION TSS 7.4.0.5.13 FSAR SOBR/LER OPERATIONALASSESSMENT 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 VALVEOPERABILIZT 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.

INITIALCONDITIONS: In accordance with the testing requirements of the specific t

Surveillance.

FINAL CONDITIONS: In accordance with the testing requirements of the specific Surveillance.

SOURCE OF COMPARISON DATA:

PLANT DATAS EVALUATION EI'NGINEERING FSAR SOBR/LER OPERATIONALASSES 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 OPERABILITYDEMONSTRATION 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.

INITIALCONDITIONS: In accordance with the testing requirements of the specific Surveillance.

FINALCONDITIONS: In accordance with the testing requirements of the specific Surveillance.

SOURCE OF COMPARISON DATA:

PLANT DATA SEI' ENGINEERING EVALUATION TSS 7.4.0.5.18 FSAR SOER/LER OPERATIONALASSESSMENT 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 VALVEOPERABII ITY RD EP NE'his test is performed to demonstrate Shnulator System Operability in accordance with approved Plant Surveillance Procedures.

INITIALCONDITIONS: 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 DATASEI' ENGINEERING EVALUATION T A.l..l.l FSAR SOER/LER OPERATIONALASSESSMENT 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.

INITIALCONDITIONS: 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 50.59 Review 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. 07.04.03.01.01.22 REV. 8 TITLE: MANUALSCRAM FUNCTIONALTEST E EDRE P N E:

This test was performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures.

INI'rlALCONDITIONS: 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 5 .5 Review FSAR SUER/LER OPERATIONAL ASSESSMENT 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.

INITIALCONDITIONS: IC-2.

FINAL CONDITIONS: IC "2.

SOURCE OF COMPARISON DATA:

PLANT DATA SBT ENGINEERING EVALUATION T. Table 4.3.6 -1.5.A Q

FSAR SOER/LER OPERATIONAL ASSES SMBNT 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.

INITIALCONDITIONS: Plant operating at 80% power or less.

SOURCE OF COMPARISON DATA:

PLANT DATASET 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: MONTHLYTURBINE VALVETEST 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.

INITIALCONDITIONS: Plant operating at 80% power or less.

SOURCE OF COMPARISON DATA:

PLANT DATA SBI' ENGINEERING EVALUATION T.S. 4.3.8.2 FSAR SOER/LER OPERATIONALASSESSMBNT 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.

INITIALCONDITIONS: Plant operating at power LE 80%.

FINALCONDITIONS: Plant operating at power LE 80%.

SOURCE OF COMPARISON DATA:

PLANT DATASET g ENGINEERING EVALUATION T.S. 4.4.7 FSAR SOER/LER 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. 07.04.05.01.05 REV. 1 TITLE: I,PCS VALVZ 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.

INITIALCONDITIONS: 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 VALVELINEUP 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.

INITIALCONDITIONS: IC-14 100% Power.

FINAL CONDITIONS: IC-14 100% Power.

SOURCE OF COMPARISON DATA:

PLANT DATASEI' BNGINBERING EVALUATION T.S. 4.5.1.A.2 FSAR SOBR/LER P OPERATIONAL ASSESSMENT 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 OPERABILITYTEST 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.

INITIALCONDITIONS: IC-14 100% power, equiliberium Xenon.

SOURCE OF COMPARISON DATA:

Q PLANT DATASEI' ENGINBERING EVALUATION T.S. 4.5.1.b.3 FSAR SOER/LER 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. 07.04.06.01.04.02A REV. 1 TITLE: MSIV VALVEQUARTERLY 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.

INITIALCONDITIONS: Plant shutdown.and depressurized, or IC-14.

FINALCONDITIONS: 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.

INITIALCONDITIONS: N /A FINALCONDITIONS: N / A SOURCE OF COMPARISON DATA:

P PLANT DATASEI' ENGINEERING EVALUATION FSAR SUER/LER OPERATIONALASSESSMENT 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 CONTAINMENTISOLATION VALVEOPERABILITF 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.

INITIALCONDITIONS: In accordance with the testing requirements of the specific Surveillance.

FINALCONDITIONS: 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 VACUUMBREAKER 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.

INITIALCONDITIONS: In accordance with the testing requirements of the specific Surveillance.

SOURCE OF COMPARISON DATA:

PLANT DATA SBT g ENGINEERING EVALUATION FSAR SOER/LER OPERATIONALASSESSMENT 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 BUILDINGISOL4TION VALVEOPERABILI2T 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.

INITIALCONDITIONS: IC-14 100% Pwr/Flow RB HVAC In Service.

SOURCE OF COMPARISON DATA:

PLANT DATA SEI' ENGINEERING EVALUATION 5 .5 FSAR SUER/LER 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. 07.04.06.05.03.01A REV 2 TITLE; STANDBY GAS TREATMENTSI'STEM OPERABILITYTEST 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.

INITIALCONDITIONS: Any IC SGT in STBY.

FINALCONDITIONS: 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: STANDBXSERVICE WATER LOOP B VALVEPOSITION 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.

INITIALCONDITIONS: N /A FINALCONDITIONS: N / A SOURCE OF COMPARISON DATA:

PLANT DATA SET g ENGINEERING EVALUATION 50.5 Review FSAR SOER/LER OPBRATIONALASSESSMENT 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.

INITIALCONDITIONS: IC-14 100% Pwr/Flow.

FINALCONDITIONS: IC-14 100% Pwr/Flow.

SOURCE OF COMPARISON DATA:

PLANT DATASET X ENGINEERING EVALUATION 50.59 Review 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 CATEGORY: Normal Operations TEST No. 07.04.08.01.01.01.02 REV. 6 TITLE: l8 MONTHMANUAL& 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.

INITIALCONDITIONS: IC-14 100% Power/ Flow.

FINALCONDITIONS: 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 MONTHLYOPERABILIZT 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.

INITIALCONDITIONS: N/A FINALCONDITIONS: N/A SOURCE OF COMPARISON DATA:

PLANT DATA SEI' ENGINEERING EVALUATION 5 .5 Review 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. 07.04.08.01.01.02.06 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.

INITIALCONDITIONS: IC-14 100% Pwr/Flow.

FINAL CONDITIONS: IC-14 100% Pwr/Flow.

SOURCE OF COMPARISON DATA:

PLANT DATASET X ENGINEERING EVALUATION FSAR SOER/LER OPERATIONALASSESSMENT 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 MONTHLYOI'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.

INITIALCONDlTIONS: N/A FINAL CONDITIONS: N/A SOURCE OF COMPARISON DATA:

PLANT DATA SET X BNGINBERING EVALUATION .5 Review FSAR SOER/LER OPERATIONAL ASSESSMENT 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 MONTHLYOPERABII 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.

INITIALCONDITIONS: N/A FINALCONDITIONS: N/A SOURCE OF COMPARISON DATA:

PLANT DATA SEI' ENGINEERING EVALUATION 50.59 Review FSAR SOER/LER OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISPACTORY WITH DISCREPANCIES X TEST RESULTS SATISFACTORY WITH DISCREPANCIES Q TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

APPENDIX D ATTACHMENT0-4 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: INITIALCONDITION STABILITYTEST 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.

INITIALCONDITIONS: IC-14, 100% Power Equilibrium Xenon.

SOURCE OF COMPARISON DATA:

X PLANT DATA o PWRD T SEI'NGINBERING EVALUATION FSAR SUER/LER X OPERATIONAL ASSESSMENT 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: INITIALCONDITIONSTABILIXY- 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.

INITIALCONDITIONS: IC-14, 100% Power Equilibrium Xenon.

FINALCONDITIONS: IC-14, 100% Power Equilibrium Xenon.

SOURCE OF COMPARISON DATA:

X I 0 o PWRDATA PLANTDATASEI'NGINEERING EVALUATION FSAR SOER/LER X OPERATIONALASSESSMENT 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 REV. 6 TITLE: INITIALCONDITIONSTABILITY- 4-HOUR STABILI1T 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.

INITIALCONDITIONS: IC-14, 100% Power equilibrium Xenon.

FINAL CONDITIONS: IC-14, 100% Power Equilibrium Xenon.

SOURCE OF COMPARISON DATA:

X PLANT DATASBT 1 o P DATA ENGINBBRING EVALUATION FSAR SOER/LER g OPERATIONAL ASSESSMENT 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, DRYWELLPRESS's, DRYWELLTEMP's, SUPPRESSION POOL LVL's, SUP-PRESSION POOL TEMP's, CONDENSER VACUUM's, MAINTURB 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 tlTIALCONDITIONS: IC-14 100% Power with Equilibrium Xenon.

FINALCONDITIONS: IC-14 100% Power with Equilibrium Xenon.

SOURCE OF COMPARISON DATA:

100 PWR Jan 22 PLANT DATASET 1 PWR Jan 1 ENGINEERING EVALUATION FSAR SOER/LER g OPERATIONALASSESSMENT TEST RESULTS:

TBST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACI'ORY WITHOUT DISCREPANCIES

P

~,

t OPERATIONAL REVIEW

SUMMARY

TEST CATEGORY: Steady State Operation TEST No. 14.4.4.1 REV. 3 TITLE: STEADY-STATEACCURACY TESTS -l00 PERCENT POWER ANDFLOWp 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, DRYWELLPRESS's, DRYWELLTEMP's, SUPPRESSION POOL LVL's, SUP-PRESSION POOL TEMP's, CONDENSER VACUUM's, MAINTUI& GOV VLV POS's, MAIN TURB SPEED, RFP SPEED's, RFP PRESS's, and as listed. Values were within specifications or identified for correction.

INITIALCONDITIONS: IC-14 100% Power with Equilibrium Xenon.

SOURCE OF COMPARISON DATA:

100 PWR Jan 22 g PLANT DATA 1 PWR Jan 18 SEI'NGINEERING EVALUATION FSAR SOER/LER g OPERATIONAL ASSESSMENT 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 ACCVRACYTESTS - 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, MAINTURB GOV VLVPOS's, MAINTURB SPEED, RFP SPEED's, RFP PRESS's, and others as listed. Values were within specifications or identified for correction.

e INITIALCONDITIONS: IC-14, Adjusted power to 66%.

FINALCONDITIONS: 66% Power SOURCE OF COMPARISON DATA:

g PLANT DATASBT P Mar 1 ENGINEERING EVALUATION FSAR SOER/LER X OPERATIONAL ASSESSMENT 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-STATEACCURACY 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, MAINTURB GOV VLVPOS's, MAINTURB SPEED, RFP SPEED's, RFP PRESS's, and others as listed. Values were within specifications or identified for correction.

INITIALCONDITIONS: IC-14, Adjusted power to 66%.

FINALCONDITIONS: 66% Power SOURCE OF COMPARISON DATA:

g PLANT DATA 6 PWR Mar 1 SEI'NGINEERING EVALUATION FSAR SOBR/LER g OPERATIONALASSESSMENT 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 TITLE: STEADY-STATE ACCURACY TESTS -40 PERCENT POWER TEST No, 14.4.4.3 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, MAINTURB 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 40PWRA r20 SEI'NGINEERING EVALUATION FSAR SOER/LER X OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES X TEST RESULTS SATISFACTORY WITHOUT DISCRBPANCIES

I ~ ' V ~

f g p $

8

t PERATIONALREVIEW

SUMMARY

TEST CATEGORY: Steady State Operation TEST No. 14.4.4.3 REV. 3 TITLE'TEADY-STATEACCURACY TESTS -40 PERCENT POWER 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, MAINTURB GOV VLV POS's, MAINTURB SPEED, RFP SPEED's, RFP PRESS's, and others as listed. Values were within specifications or identified for correction.

INITIALCONDITIONS: IC-62 40% Power FINALCONDITIONS: 40% Power SOURCE OF COMPARISON DATA:

I PLANT DATA SET 40PWRA r20 ENGINBBRING EVALUATION FSAR SUER/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: Steady State Operation TEST No. 14.4.4.4 REV. 4 TITLE: STEADY-STATEACCURACF 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.

INITIALCONDITIONS: IC-24, Cold Shutdown FINALCONDITIONS; 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.

INITIALCONDITIONS: IC-24, Cold Shutdown FINAL CONDITIONS: Cold Shutdown SOURCE OF COMPARISON DATA:

PLANT DATASET 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: HEATAlVDMASS BALAlVCETESTS - l00 PERCENT POWER HEATBAL4NCE 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.

INITIALCONDITIONS: IC-14 100% Power with Equilibrium Xenon.

FINALCONDITIONS: IC-14 100% Power with Equilibrium Xenon.

SOURCE OF COMPARISON DATA:

PLANT DATASET ENGINEERING EVALUATION FSAR SUER/LER g OPERATIONALASSESSMENT 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: HEATAND MASS BALANCETESTS - 100 PERCENT POWER HEATBALANCE 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.

INITIALCONDITIONS: IC-14 100% Power with Equilibrium Xenon.

FINALCONDITIONS: 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 ATTACHMENTD-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.

INITIALCONDITIONS; IC-14 100% Power Equilibrium Xenon.

FINAL CONDITIONS: 100% Power.

SOURCE OF COMPARISON DATA:

PLANT DATA SEI'NGINEERING EVALUATION FSAR 84-124 12/03/84 X SOER/LBR 84-125 11 27 84 X OPERATIONALASSESSMENT 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.

INITIALCONDITIONS: IC-14, 100% Power Equilibrium Xenon.

FINALCONDITIONS: 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 ALLAC STATION BLACKOUT DESIRED RESPONSE:

Loss of AllAC 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.

INITIALCONDITIONS: IC-14, 100% Power Equil Xenon FINALCONDITIONS: Shutdown with DGN-3 supplying HPCS; RCIC Operation controlling RPV/L.

SOURCE OF COMPARISON DATA:

PLANT DATASET 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: MSIVISOL4TION 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.

INITIALCONDITIONS: IC-14 100% Power Equilibrium Xenon.

FINALCONDITIONS: 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 SCRMLER88.03 ENGINEERING EVALUATION FSAR X SOER/LER LER 88-03 X OPERATIONAL ASSESSMENT 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 ALLRFP'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.

INITIALCONDITIONS: IC-14, 100% Power Equilibrium Xenon.

FINALCONDITIONS: 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 SCRMLER84.114 ENGINBERING EVALUATION FSAR X SOBR/LER LE 4- 4 X OPERATIONALASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACI'ORY WITHOUT DISCREPANCIES

OPERATIONAL REVIEW

SUMMARY

t TEST CATEGORY: Transients TEST No. 14.4.10.6 REV. 4 TITLE: SIMULTANEOUS TRIP OF ALLRECIRCULATIONPUMPS - 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.

INITIALCONDITIONS: IC-14, 100% Power Equilibrium Xenon.

SOURCE OF COMPARISON DATA:

g PLANT DATASEI' PAT OB ENGINEERING EVALUATION FSAR SUER/LER X OPERATIONAL ASSESSMENT 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: MAXIMUMSIZE DBA LOCA WITHLOSS 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.

INITIALCONDITIONS: IC-14 100% Power Equilibrium Xenon.

t FINALCONDITIONS: Reactor Shutdown with RPV/L being controlled GT 'Avo-Thirds Core SOURCE OF COMPARISON DATA:

Height via E<CCS Div 1-3 Injection. Primary Containment Isolation complete via NS4 Isolations.

PLANT DATASEI' ENGINEERING EVALUATION ANF LOCA ANALY IS FSAR SOER/LER X OPERATIONALASSESSMENT 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. 144 10 9 REV. 0 TITLE: MAXIMUMSIZE MAINSTEAMI.INERUPTURE 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.

INITIALCONDITIONS: 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 DATASET ENGINEERING EVALUATION g FSAR 15.6.5 6.2.1.1.3.b SOER/LER g OPERATIONALASSESSMENT 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 TITLE: MSlV ISOLATION WITHSRV FAILED OPEN TEST No. 14.4.10.10 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.

INITIALCONDITIONS: 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 SCRMLER88.03 SEI'NGINEERING EVALUATION FSAR X SUER/LER X OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RBSULTS SATISFACI'ORY WITHOUTDISCRBPANCIES

OPERATIONAL REVIEW

SUMMARY

TEST No. 14.4.10.16 REV. 4 TITLE: LOSS EW WITHEMERGENCY 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'IALCONDITIONS: IC-14 100% Power and Flow with Equilibrium Xenon.

t FINALCONDITIONS: Plant SD with RHR B in the Shutdown Cooling Alignment and RHR B in SOURCE OF COMPARISON DATA:

Suppression Pool Cooling.

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 ATTACHMENTD-6 WASHINGTON PUBLIC POWER SUPPLY SYSTEM PLANT MALFUNCTIONTEST ABSTRACTS

OPERATIONAL REVIEW

SUMMARY

TEST CATEGORY: Plant Malfunction TEST No. 14.4.9.18.3 REV. 6 TITLE: INSTRUMENTREFERENCE LINEBREAKD004C (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.

INITIALCONDITIONS: 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 15..2 g SOER/LER 5-5 0 4 5 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: 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.

INITIALCONDITIONS; IC-12 100% Power with Equilibrium Xenon.

FINALCONDITIONS: 100% Power with HPCS injection in progress.

SOURCE OF COMPARISON DATA; PLANT DATA SKI'NGINEERING EVALUATION g FSAR 15.5.1 C] 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 UMMARY TEST CATEGORY: Plant Malfunction TEST No. 14.4.9.18.6 REV. 5 TITLE: INSTRUMENT VARIABLELEG LINE BREA'111 - SLF'RRS SC RED E P E:

This test is performed to demonstrate the functionality of the INSTRUMENT VARIABLELEG 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 VARjlABLELEG LINE BREAK Xll1 malfunction was tested and verified.

INITIALCONDITIONS: IC-14 100% Power with Equilibrium Xenon t FINALCONDITIONS: Reactor Scrammed, RRC Pumps Off, RCIC-V-45 Oscillating with RPV/L 8 SOURCE OF COMPARISON DATA:

controlling RPV/L.

PLANT DATA SBT ENGINEERING EVALUATION g FSAR 15.6.2 SOERiLBR g OPERATIONALASSESSMENT 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: MAINSTEAM SAFETY RELIEF VALVEFAILS OPEN - CLF: RRS l STPT DRIFT ED RE P SE:

This test is performed to demonstrate the functionality of the MAINSTEAM 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.

INITIALCONDITIONS: 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 15.1A SUER/LER g OPERATIONAL ASSESSMENT 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'GALCONDITIONS: 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 REV. 4 TITLE: MSIV ISOLATION WITHSRV FAILED OPEN 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.

INITIALCONDITIONS: 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 SCRMLER88.03 ENGINEERING EVALUATION FSAR X SOER/LER 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 No. 14.4.9.4.4 REV. 3 TITLE: LEAICDOWNSTREAM OF CONTROL AIR DRYER - SLF: CAS-4 D IREDR P N E'his test was performed to demonstrate the functionality of the LEAKDOWNSTREAM 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 VALVEPILOT 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.

INITIALCONDITIONS: IC-14 100% Power with Equilibrium Xenon.

FINALCONDITIONS: 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 INITIALCONDITIONS: IC-14 100% Power with Equilibrium Xenon.

FINALCONDITIONS: 100% Power, 1/2 Scram B Channel.

SOURCE OF COMPARISON DATA:

PLANT DATASET 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 INITIALCONDITIONS: IC-14 100% Power with LIquilibriumXenon.

FINALCONDITIONS: 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 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 INITIALCONDITIONS: 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 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-B1-2 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 INITIALCONDITIONS: 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 INITIALCONDITIONS: IC-14 100% Power with Equilibrium Xenon.

FINALCONDITIONS: 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 ALLOFF- SITE POWER - SLF: OED 2 D EDR P This test is pexformed to demonstrate the functionality of the LOSS OF ALLOFF-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. Allmajor 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 INITIALCONDITIONS: IC-14 100% Power with Equilibrium Xenon.

FINALCONDITIONS: 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 DIFFERENTIALCURRENT - 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).

INITIALCONDITIONS: 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:

PLANTDATASET 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 REV. 3 TITLE: DC BUS TRIP LOAS'S LPS80 and EPS009 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.

INITIALCONDITIONS: 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 TEST No. 14.4.9.24.15A REV. 1 TITLE: Sl-l TRIP -SLF: EPS 3C 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 Power and Loss Control Board indication, therefore evaluation not performed in this test.

,C INI'HALCONDITIONS: IC-14 100% Power Equilibrium Xenon FINALCONDITIONS: IC-14 100% Power with BUS Sl-1 De-Energized SOURCE OF COMPARISON DATA:

PLANT DATASET BNGINEERING EVALUATION FSAR SOER/LBR g OPERATIONALASSBSSMBNT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RBSULTS SATISFACTORY WITH DISCREPANCIES X TEST RESULTS SATISFACTORY WITHOUTDISCRBPANCIES

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 test is performed to demonstrate the functionality of the RPS B MG SET TRIP Malfunction.

E'liis 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 INITIALCONDITIONS: IC-14 100% Power Equilibrium Xenon.

SOURCE OF COMPARISON DATA:

PLANT DATASET ENGINEERING EVALUATION FSAR X SOER/LER 7-014 X OPERATIONAL ASSESSMENT 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: BATTERYCHARGER 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.

INITIALCONDITIONS: 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 ALLAC STATION BLACKOUT DESIRED RESPONSE:

Loss of AllAC 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.

INITIALCONDITIONS: IC-14, 100% Power Kquil Xenon t FINALCONDITIONS: Shutdown with DGN-3 supplying HPCS; RCIC Operation controlling RPV/L.

SOURCE OF COMPARISON DATA:

PLANT DATA SET ENGINEERING EVALUATION FSAR SOER/LBR X OPERATIONALASSESSMENT 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: RECIRCULATIONPUMP 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'HALCONDITIONS: 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 PAT30A ENGINEERING EVALUATION g FSAR 15.3.1 SOER/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 No. 14.4.10.6 REV. 4 TITLE'IMULTAlVEOUSTRlP OF ALLRECIRCUL4TION 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.

INITIALCONDITIONS: IC-14, 100% Power E<quilibrium Xenon.

FINALCONDITIONS: 40% g 4 % Power and 25% Core Flow.

SOURCE OF COMPARISON DATA:

g PLANT DATA SBT PAT 30B ENGINEERING EVALUATION FSAR SOER/LER X OPERATIONAL ASSESSMENT 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 TITLE: CONDENSER AIR LEAlC - SLP: CFW 3 D IREDRE P N TEST No. 14.4.9.2.2 REV. 3 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 LEAKmalfunction 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 INITIALCONDITIONS: IC-14 100% Power with Equilibrium Xenon.

e FINALCONDITIONS: Reactor Shutdown, RPV/P control via SRV operation, RPV/L decreasing towards RPV/L 2.

SOURCE OF COMPARISON DATA:

PLANT DATASBT ENGINEERING EVALUATION g FSAR g SOER/LER 4-125 g OPERATIONALASSESSMENT 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 LEVELLOW 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.

INITIALCONDITIONS: 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.

INITIALCONDITIONS: IC-19 SDC in Progress.

FINAL CONDITIONS: IC-19 SDC in Progress without SW IQow to RHR 8 HX.

SOURCE OF COMPARISON DATA:

PLANT DATASET 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.

INITIALCONDITIONS: IC-14 100% Power Equilibrium Xenon.

FINALCONDITIONS: 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 INITIALCONDITIONS: IC-14 100% Power with Equilibrium Xenon RCC-P-lA and t

RCC-P-1B running.

FINALCONDITIONS: IC-14 100% Power with Equilibrium Xenon, RCC-P-1B and RCC-P-1C running.

SOURCE OF COMPARISON DATA:

PLANT DATASBT 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.

INITIALCONDITIONS: IC-14 100% Power Equilibrium Xenon.

FINALCONDITIONS: IC-14 100% Power Equilibrium Xenon.

SOURCE OF COMPARISON DATA:

PLANT DATASET ENGINEERING EVALUATION FSAR SOER/LER g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITII 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.

INITIALCONDITIONS: IC-14 100% Power Equilibrium Xenon t FINAL CONDITIONS: Recirc Flow Control valves have runback, RFPT 8 has increased flow to SOURCE OF COMPARISON DATA:

maximum, Reactor is at approx. 68 to 72% Power.

PLANT DATA SEI'NGINEERING EVALUATION FSAR g SOER/LBR 84-g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACI'ORY WITHOUT DISCRBPANCIES

ah 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 ISOLATIONevaluated per 14.4.10.3, LOSS OF ALLRFW evaluated per 14.4.10.1 INITIALCONDITIONS: IC-12 100% Po>ver Equilibrium Xenon SOURCE OF COMPARISON DATA:

PLANT DATA SET ENGINBERING EVALUATION FSAR g SOER/LER 86-024 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: 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 ISOLATIONevaluated pex 14.4.10.3, LOSS OF ALLRFW evaluated pex 14.4.10.1.

INITIALCONDITIONS: 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 NORMALAND EMERGENCY FW - Multiple D EDR P N test is performed to verify the Simulators response to a LOSS OF ALLNORMAL E'his 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.

INITIALCONDITIONS; IC-14 100% Power Equilibrium Xenon.

FINALCONDITIONS: 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.

INITIALCONDITIONS: IC-14 100% Power with E<quilibrium Xenon.

e FINALCONDITIONS: Reactor Scrammed with both RFW Turbines tripped on HIGH RPV/L with HPCS Injection ongoing.

SOURCE OF COMPARISON DATA:

PLANT DATASBT ENGINEERING EVALUATION g FSAR 15.5.1 SUER/LER 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. 14.4.9.21.1 REV. 3 TITLE: ADS LOGIC FAILURE (INADVERTENTINITIATION)- 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 AirTemperatuxe and Suppression Pool Temperature increasing. Proper response on activation of ADS Logic Failure inadvertent Initiation) malfunction was tested and vexified.

INITIALCONDITIONS: 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/ARI8 LOGIC FAILURE - (See ATPfor Listing)

IREDR P N test is performed to demonstrate the functionality of the ATWS/ARI FAILURE. The E'his 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.

INITIALCONDITIONS: IC-14 100% Power E<quilibrium Xenon.

FINALCONDITIONS: 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.

INITIALCONDITIONS: 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.

INITIALCONDITIONS: IC-14 100% Power with Equilibrium Xenon.

FINAL CONDITIONS: IC-14 100% Power with Equilibrium Xenon.

SOURCE OF COMPARISON DATA:

g PLANT DATA SET PowerPlex Data ENGINEERING EVALUATION FSAR SOER/LER g OPERATIONALASSESSMENT 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.

INITIALCONDITIONS: IC-14, 100% Power with Equilibrium Xenon.

SOURCE OF COMPARISON DATA:

PLANT DATASBT BNGINBERING EVALUATION FSAR SOER/LER g OPERATIONALASSESSMENT 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.

INITIALCONDITIONS: 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 OPERATIONALASSESSMENT 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.

INITIALCONDITIONS: IC-14 100% Power with Equilibrium Xenon.

FINALCONDITIONS: Power is less than 100% and MWE< less than 1150.

SOURCE OF COMPARISON DATA:

g PLANT DATA PowerPlex Data SEI'NGINEERING 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. 14.4.9.3.12 REV. 4 TITLE: M'DRAULICATWS - SLF: 7A & 7B at 100% Severity DESIRED RESPONSE:

This test is performed to demonstrate the functionality of the HYDRAULICATWS Malfunction. Proper response on activation of a Manual SCRAM without Control Rod insertion was tested and verified INITIALCONDITIONS: IC-14 100% Power with Equilibrium Xenon.

FINALCONDITIONS: IC-14 100% Power with Equilibrium Xenon.

SOURCE OF COMPARISON DATA:

PLANT DATA SET ENGINEERING EVALUATION FSAR SOER/LER g OPERATIONALASSESSMENT 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. 14.4.99.13 REV. 0 gS 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'GALCONDITIONS: IC-3 SU Ongoing.

SOURCE OF COMPARISON DATA:

PLANT DATASET 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 INITIALCONDITIONS: 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'LADDINGPERP'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 DATAS EVALUATION EI'NGINEERING 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 REV. 4 TITLE: GROSS CLAD FAILURE - SLF'CX l 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 INITIALCONDITIONS: IC-14 100% Power with Equilibrium Xenon, OG-V-45 is open.

SOURCE OF COMPARISON DATA:

PLANT DATASET 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: MAINTURBINE 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, MAINTURBINE 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 INITIALCONDITIONS: IC-14 100% Power with Equilibrium Xenon.

FINAL CONDITIONS: Reactor has Scrammed, Main'Ihrbine has tripped.

SOURCE OF COMPARISON DATA:

g PLANT DATASEI' ENGINEERING EVALUATION X FSAR 15.2.85-002, 01/01/85 X SOER/LER X OPERATIONALASSESSMENT 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; MAINTURBINE TRIP FROM LT 30% - SI F: DEH 1 ED EP This test is performed to demonstrate the functionality of the MAINTURBINE TRIP FROM LT 30% malfunction. System responses included: MAINGENERATOR tripped, MAINTURBINE 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'IALCONDITIONS: IC-10, Adjusted Power to 28%.

FINALCONDITIONS: Main Turbine has tripped, DEB controlling pressure with Bypass valves.

SOURCE OF COMPARISON DATA:

g PLANT DATA SET PLANTS D.DOC ENGINEERING EVALUATION X FSAR 15.2.3 SOBR/LBR g OPERATIONALASSESSMENT 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: MAINTURBINE 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'GALCONDITIONS: IC 100% Power Equilibrium Xenon.

e FINAL CONDITIONS: Reactor SD, MS-RV-lAcontrolling RPV/P and SU LCV controlling level via RFP Turbine 1A.

SOURCE OF COMPARISON DATA:

X PLANT DATA SCRAM,LER 8-SEI'NGINEERING EVALUATION FSAR SOER/LBR g OPERATIONALASSESSMENT 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: MAINGENI"RAI'OR mlP - SLY: GEN-l D IREDRE P N E'his test is performed to demonstrate the functionality of the MAINGENERATOR 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'GALCONDITIONS: IC-14 100% Power with Equilibrium Xenon FINALCONDITIONS: 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 15.2.2 g SOER/LER 85-002, 85-003 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: Plant Malfunction TEST No. 14.4.9.23.3 REV. 5 TITLE; DEH PRESS REGULATOR OUTPUT FAILUREHIGH - 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'HALCONDITIONS: IC-12 100% Power Equilibrium Xenon FINALCONDITIONS: Reactor Scrams on MSIV closure.

SOURCE OF COMPARISON DATA:

g PLANT DATA PAT 22 SEI'NGINEERING EVALUATION g FSAR 15.1.3 SUER/LER X OPERATIONALASSBSSMBNT 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 FAILURELOW -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.

INITIALCONDITIONS: 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 MANUALand 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.

INITIALCONDITIONS: IC-14 100% Power Equilibrium Xenon.

FINALCONDITIONS: BPV's-(2,3,4) are open, BPV-I is shut, MWE has decreased.

SOURCE OF COMPARISON DATA:

PLANT DATASBT ENGINEERING EVALUATION FSAR X SOER/LER 4- 56 4-044 4-1 4 X OPERATIONALASSESSMENT 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: MANUALSCRAM REDR P N E'his test is performed to demonstrate the functionality of the MANUALSCRAM 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 33 is compared to Plant Data Set SCRAM LER 89-35. Proper response on activation of the MANUALSCRAM malfunction is tested and verified.

INK'IALCONDITIONS: IC44, Adjusted Aow to 100% using FCV's.

FINALCONDITIONS: Reactor Scrammed, BOP shutdown in progress.

SOURCE OF COMPARISON DATA:

g PLANT DATA SCRAMLER SEI'NGINEERING EVALUATION FSAR BOER/LBR 90-021 85-016 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: Plant Malfunction TEST No. 14.4.9.2.3 REV. 3 TITLE: FEEDWATER LINE BREAKIN 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, INITIALCONDITIONS: IC-14 100% Power Equilibrium Xenon FINALCONDITIONS: 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 OPERATIONALASSESSMENT 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. 14.4.9.2.8 REV. 5 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 LVL2 with subsequent HPCS and RCIC Auto Start and NS4 Isolation. Turbine Building temperatures increase.

Proper Annunciation response was verified.

INITIALCONDITIONS: IC-14 100% Power Equilibrium Xenon FINALCONDITIONS: Reactor has scrammed, Turbine Bldg. Temp. increases, RPV Level increases, LVL8 RCIC-V-45A & HPCS-V-14 shut.

SOURCE OF COMPARISON DATA:

PLANT DATASEI' ENGINEERING EVALUATION g FSAR SUER/LER g OPERATIONALASSESSMENT 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 REV. 5 TITLE: MAINSTEAM RUPTURE IN DRYWALL- SLY: RRS 3C (DOWNSTRFAM OF FLOW RES TRICTORS)

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.

INITIALCONDITIONS: IC-14 100% Power E<quilibrium Xenon FINALCONDITIONS: 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 15.6.5 6.2.1.1.3.b P SOER/LBR X OPERATIONALASSESSMENT 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: MAINSTEAM RUPTURE IN TURBINE BUIIDING - 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'IIALCONDITIONS: IC-14 100% Power Equilibrium Xenon.

FINALCONDITIONS: Reactor Shutdown with RPV/P control via SRV's.

SOURCE OF COMPARISON DATA; PLANT DATA SET ENGINEERING EVALUATION X FSAR 15.6.4 SOER/LBR X OPERATIONAL ASSESSMENT 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 STEAMLINEDOWlVSTRZAMRCIC-V 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.

INEHALCONDITION: 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 OPERATIONALASSESSMENT 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.

INITIALCONDITIONS: IC-3, 5 Rods from critical FINALCONDITIONS: IC-3, 5 Rods from critical SOURCE OF COMPARISON DATA:

Q PLANT DATASBT 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

+v q~, ",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 ALARMlights 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.

INITIALCONDITIONS: IC-14 100% Power with Equilibrium Xenon.

FINALCONDITIONS: 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: IRMINSTRUMENTFAILURE - HIGH - SLF: NIS 2A ES REDRE P E:

This test is performed to demonstrate the functionality of the IRM INSTR. FAILURE-HIGHMalfunction.

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 ALARMlight illuminated P603, IRM A upscale on IRM A drawer, UPSCALE ALARMlight 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.

INITIALCONDITIONS: IC-5 SOURCE OF COMPARISON DATA:

PLANT DATASET 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.

INITIALCONDITIONS: IC-14 100% Power with Equilibrium Xenon.

FINALCONDITIONS: 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/LOWannunciators alarmed and cleared.

Proper response on activation of the RCIC TURBINE TRIP due to RCIC-V-8 closure malfunction was tested and verified.

INITIALCONDITIONS: IC-14 100% Power with Equilibrium Xenon, RCIC placed in Full Flow Test Mode CST to CST.

FINALCONDITIONS: IC-14 100% Power, RCIC TURBINE has tripped.

SOURCE OF COMPARISON DATA:

PLANT DATASET 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: ANNUNCIATORFAILURE 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.

INITIALCONDITIONS: 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 CHAlVNFLFAILURE 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.

INITIALCONDITIONS: 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 OPERATIONALASSESSMENT 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'GALCONDITIONS: IC-14 100% Power Equilibrium Xenon FINALCONDITIONS: IC-14 100% Power Equilibrium Xenon SOURCE OF COMPARISON DATA:

PLANT DATA SEI'NGINEERING EVALUATION FSAR g SUER/LER 5- 16 QX OPERATIONAL ASSESSMENT 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.

INITIALCONDITIONS: IC-14 100% Power Equilibrium Xenon.

SOURCE OF COMPARISON DATA:

PLANT DATA SEI'NGINBERING EVALUATION FSAR SOER/LER g OPERATIONALASSESSMENT 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 MINIMIZERFAILS DESIRED RESPONSE:

This test is performed to demonstrate the functionality of the ROD WORTH MINIIVIIZERFAILS 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.

INITIALCONDITIONS: IC-9 HEAT UP e 850¹.

FINALCONDITIONS: 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 LEAEATPUMP 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'TIALCONDITIONS: IC-14 100 % 100% Power with Equilibrium Xenon, LPCS Pump in Full Flow test to Suppression Pool.

FINALCONDITIONS: IC-14 100 % 100% Power with Equilibrium Xenon, LPCS Pump Tripped and Low Suppression Pool Water Level.

SOURCE OF COMPARISON DATA:

PLANT DATASET ENGINEERING EVALUATION FSAR SOER/LER X OPERATIONALASSESSMENT 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 THERMALOVERLOAD- 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.

INITIALCONDITIONS: IC-14 100% Power Equilibrium Xenon.

FINALCONDITIONS: Reactor Scrammed, RFW and MT Tripped at RPV/L 8, DEH Controlling RPV/P via MT ByPass Valves.

SOURCE OF COMPARISON DATA:

PLANT DATASET 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 INITIALCONDITIONS: 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 OPERATIONALASSESSMENT 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.

INITIALCONDITIONS: IC-14 100% Power with Equilibrium Xenon, RHR-P-2A in Full Flow Test at rated How.

FINALCONDITIONS: IC-14 100% Power with Equilibrium Xenon, RHR-P-2A is tripped.

SOURCE OF COMPARISON DATA; PLANT DATASET 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.

INITIALCONDITIONS: IC-14 100% Power with Equilibrium Xenon.

SOURCE OF COMPARISON DATA:

PLANT DATASET 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% HYDRAULICATWS, WITHMSIVISOL4TION Ii DESIRED RESPONSE:

MSIV ISOLATIONwith 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.

INITIALCONDITIONS: 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 ANF ATWS Fl'nal fs ENGINEERING EVALUATION FSAR SUER/LER X OPERATIONALASSESSMENT 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.

INITIALCONDITIONS: IC-14 100% Power Equilibrium Xenon.

SOURCE OF COMPARISON DATA:

PLANT DATASET ENGINEERING EVALUATION FSAR g SUER/LBR 4-045 - 21 g OPERATIONALASSESSMENT 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 QUADRENNIALTESTING Attachment E Quadrennial Test Schedule

APPENDIX E Attachment E-1 WASHINGTON PUBLIC POWER SUPPLY SYSYTEM QUADRENNIALTESTING 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 AllRFP's Test No. 14.4.10.3 - Closure of AllMain Steam Isolation Valves Test No. 14.4.10.6 - Trip of AllRecirculation 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 QUADRENNIALTESTING 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 QUADRENNIALTESTING 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 Generator ¹2- 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 QUADRENNIALTESTING 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

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