ML17289A928

WNP-2 Simulator Certification NRC Form 474 Supporting Documentation.

ML17289A928
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Issue date:	06/24/1992
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WNP-2 SIMUlATOR CERTIFICATION NRC FORM 474 SUPPORTING DOCUMENTATION WASHINGTON P VBLIC POWER SUPPLY SYSTEM DOCKET NO. 50-397 JUNE 24, 1992 9210210210 921021 PDR 'ADOCK 05000397 V PDR

VIP-2 SVvfULATOR CERTIFICATION NRC FORM 474 SUPPORTING DOCUMENTATION

l. INTRODUCTION 1.1 Certification Approach 1.2 Simulator Application

2. BACKGROUND 2.1 History 2.2 Replacement Simulator Procurement 2.3 Simulator Upgrades 1988 - 1990 24 Plans

3. SIMULATORINFORMATION 3.1 General Infotmation 3.1.1 Owner/Operator/Manufacturer 3.1.2 Reference Plant/ape/Rating 3.1.3 Date Available for Training 3.1 4 Type of Certification Report 3.2 Control Room Physical Fidelity 3.2.1 Control Room Physical Arrangement 3.2.2 Panels 8c Equipment 3.2.3 Simulator Control Room Environment 3.2,4 Systems 3.3 Instructor Control Features 10 3.3.1 Initial Conditions 3.3.2 Malfunctions 3.3.3 Items Outside the Control Room 3.3.4 Additional Special Instructor/I'raining Features 3.4 Operating Procedures for Reference Plant 12

4. SIMULATORDESIGN DATA 4.1 Design Basis 13 4.2 Update Information 13 4.3 Simulator Discrepancy Resolution and Upgrading 13

5. PERFORMANCE VERIFICATION 5.1 Simulator Tests 15 5.1.1 Computer Real Time Verification 5.1.2 Normal Plant Evolutions 5.1.3 Steady State Operation 5.1.4 Transient Performance 5.1.5 Plant Malfunctions 5.2 Training/Evaluation Scenarios 17 5.3 Quadrennial Test Schedule 18 5.3.1 Annual Testing 5.3.2 Quadrennial Testing

6. COMPLIANCE 6.1 10 CFR 55.45 Regulatory Requirements 20 6.2 Regulatory Guide 1.149 20 6.3 Exceptions to ANSIIANS-33 (1985) 21 63.1 Simulator Capabilities 6.3,2 Simulator Environment 63.3 Systems Simulated and the Degree of Completeness 6.3.4 Simulator Training Capabilities 6.3.5 Simulator Design Control 6.4 Upgrades and Corrections

APPENDIX A - SIMULATORSCOPE DIAGRAMS A-1 Gould (current) Simulator Scope A-2 Westinghouse (new) Simulator Scope A-3 Gould Simulator Layout APPENDIX B - SIMULATOR ENVIRONMEiVI'-1 Panels Not Simulated B-2 Partially Simulated Panels B-3 Fully Simulated Panels B-4 Controls On Panels B-5 Control Room Enviromnent APPENDIX C - INSTRUCTOR INTERFACES C-1 Initial Conditions C-2 Local Operator Actions .

APPENDIX D - SIMULATORACCEPTANCE TESTS D-1 ANSI/ANS-33 (1985) Retpurements Versus Simulator Acceptance Tests D-2 Computer Real-Time Test Abstract D-3 Normal Plant Evolution Test Abstracts DWSteady State Operation Test Abstracts Transient Performance Test Abstracts

'-5 D-6 Plant Malfunction Test Abstracts APPENDIX E - ADDITIONALTRAPGNG MALFUNCTIONTESTS E-1 Training Malhxnction Tests List E-2 Training Malfunction Tests Abstracts APPENDIX F - QUADRENNIALTESTING

I. INTRODUCTION This report is submitted in accordance with Title 10, Code of Federal Regulations, part 55.45 and Regulatozy Guide 1.149. Thc xcpozt provides the information prescribed by Appendix A of the American National Standards Institute/Amezican Nuclear Society Standard, ANSI/ANS-3.5 (1985), "Nuclear Power Plant Simulators for Use in Operator Training". Its purpose is to provide supporting documentation to substantiate our submittal of NRC Foxm 474 "Simulation Facility Ceztification" for thc Washington Public Power Supply System's (Supply System) Nuclear Plant No.2 (WNP-2) Operator Traixzing Simulator.

I.I Certification Approach This certification submittal documents the pezfozmancc of the simulator now in use at thc Supply System. This facility is a plant-zcfcrenccd simulator which has been effective in meeting near-texm training objectives and in supporting operator licensing examinations. To meet it's long-term need to enhance operator training and to more effectively comply with current standazds, the Supply System has determined to replace the existing simulator. The new or "replacement" simulator, now under construction, was specified and designed to meet all Rnown and anticipated requirements. Its design documentation and configuration control system will also pcxznit the Supply System to maintam 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 diffexcnces are delineated in this submittal. The Supply System has assessed thc impacts of these diffezcnces in meeting its training objectives and examinations requirements. This has resulted in a continuing pxogram of upgrades for'difference that affect the value of training. Thc Supply System has also used compensatory training to augment its simulator training and used alternate functions (ic. device ovemdes) within the simulator's capabilities to achieve required examination scenarios.

Thc ddferences in correlation between the simulator and reference plant were determined to be of two categories:

1. Exceptions to thc ANSI/ANS-3.5 (1985) Standard - these dBezcnces are founded in the limited physical scope of thc simulator hardware and the range of simulated system operation. Exceptions'that, affect'training are to be reconciled by the expanded scope of the new simulator. Near-term training plans have accommodated these exceptions aud xmxximized any impacts to an acceptable level.

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2. Upgrades and Corrections - these diffezences represent aQ 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 cozrection consistent with the requirements of 10 CFR 55.45 (b)(4)(i).

It is thc Supply System's intent to provide a Gdl set of cemfication documentation with its certi6cation of the new simulator. Since the new simulator wiQ fully replace the cuzzent simulator it willbe a new facility and cemfied accordingly. The simulator is expected to be replaced during an appropriate transition period in late 1993 or early 1994.

12 Simulator Applicatioa The training program administrative procedures and technical support procedures are intended to ensure that licensee examinations and associated training are fully compliant with 10 CFR SS 45 requizements and associated guidelines. The scope, design, and operation of the simulator arc for the specific support of the training tasks used on the WNP-2 simulator for license operator tralI11ng and testmg.

Simulator training is structured around scenarios that include clearly defined leamiug objectives based on job task analysis. Training material based on those requirements are systematically compaxed to plant modifications, Licensee Event Reports, Significant Operating Experience Reports and changes to pzoceduzes.

The simulator's performance during recent operator examinations indicates no major Qaws in its support of its mission. The Supply System's continued resolution of identi6ed problems and planning for its use to achieve training and examination scenarios as required has made the simulator an effective tool.

The new simulator is intended to fully meet all known or anticipated requirements as well as substantiate the Supply System's commitment to quality training. It is the Supply System's intent to fully support its training program by making the most cffectivc use of its current simulator while preparing to provide the extensive additional capabilities afForded by its new simulator.

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2. BACKGROUND This section is provided to create an understanding of the Supply System's efforts to provide high-quality simulator pezfozmance to meet both its near-term as well as long-tenn Licensed Operator Training Program requirements.

2.1 History The original simulator for the Supply System's WNP-2 nuclear plant was contracted in September 1980 when the Nuclear Regulatory Commission (NRC) did not require plant speci6c training simulators. In April 1981, the NRC issued Regulatory Guide 1.149<">, which endorsed ANSI/

ANS 3.5. This standard placed full responsibility for verifying simulator acceptability on simulator ownexs.

The Supply System took delivexy of the WNP-2 simulator in 1983, after the vendor's contract was terminated. No acceptance test or baseline test was pezfozmetL Me design basis was not well-documented or was not pzovidetL Numerous features wexe known to be inoperative and the simulator as delivered did not zefiect recent changes in the plant's design. Supply System management decided to upgrade the simulator software and hardware and correct de6ciencies using in-house staff. Concuzxent to its upgrade/xetrofit, the simulator was pressed into service for training, significantly complicating the Supply System's ability to perform the required upgrades.

The inczeasing zequixements for simulator fidelity and sophistication, coupled with ongoing use of the cuzzent simulator for training, put certification of the cuxxent Supply System simulator in question. Duzing the summer of 1988, representatives of the Institute of Nuclear Power Operations indicated that the WNP-2 simulator had modeling and fidelity problems that reduced its training effectiveness. These included:

~ Several equipment differences between the plant and simulator equipment.

~ Some confiicting indications between simulated systems

~ Unrealistic transient responses under many conditions.-'

'ignificant problems with core, thexmal-hydraulic, and feedwater/condensate models.

During NRC Senior Reactor Operator licensing examinations. conducted on the WNP-2 simulator during the fall of 1988; several problems were noted:

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'The simulator continues to display fidelity problems to the extent that comprehensive NRC operating examinations cannot be administered without a thorough prevalidation of the intended scenario malfunctions and evolutions."

The Supply System's evaluation recognized the full scope of the deficiencies and the effort required to meet the cuzrent aad expected future levels of required performance. The simulator's plant model software, development tools, instructor iatezface and configuration control werc assessed. It was found that: more hardware simulation was'necessary to fully address the instnnnentation observed by thc licensed operators, thc simulation models needed significant enhancement to expand the scope of trainu~ into the Emergency Operating Procedures, software documentation needed ulxlating, deficiencies in documentation of design data and the backlog of plant changes as well as the conduct of performance tests were required. Because of these conccms about the simulator as a training and examining tool, the Supply System initiated action to provide a simulator that could be certifie to fully meet regulatory requirements.

'L2 Replacement Simulator Procurement The Supply System considered two alternatives to meeting simulator requirements:

Alternative l - Factory construction of a new simulator. In this alternative, we would elect to build a new, state-of-the-azt simulator. Thc cuzzeat simulator would then be replaced when the new one was complete. All testing to validate, verify and certify the new simulator would be completed at the vendor's facility prior to its installation.

Alternative 2 - Upgrade the current simulator for full certification. The existing panels, instrumentation and I/O hardware would be retained with new software and panels added to the machine. The backlog of plant changes would be incorporated in the simulator. A new computer architecture would be established and configuration control would be brought up to the level of the requirements.

Factors that affected our decision iucludcth Lost Training Time - A new. simulator would allow a minimum amount of disruption to training classes and examinations. being conducted in thc present facility. To reduce an upgrade's impact, work would be performed on off shifts. However, major panel modificazion would cause unavoidable confiicts.

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Schedule - The constraints of access to the current machine compared with completion of a new simulator, yielded a schedule differential of less than six months. It was uncertain that either alternative could be completed by the May 1991 certi6cation deadline.

Additional Hardware - Upgrading the present simulator would require new or additional computers to handle modern software, a new process computer, other costly instnzmentation changes in the plant control room, and the addition of panels not within the current simulator's scope.

Cost - A new simulator was the more costly alternative. It was difBcult to assess the indirect costs of performing an upgrade to the simulator including, lost training time, detailed project management requirements, and the availability cost of quali6ed contractors.

Con6guration Management - Over the years, only limited documentation was prepared for simulator hardware and software modifications. The upgrade of design documentation and preparation and conduct of performance tests was expected to be equal or greater than that required for design of a new simulator.

Risk - The risk to the Supply System was considered to be greater for the upgrade alternative. Procurement of a new simulator would allow the Supply System, via the contract, to share the risk of schedules and certification. A new, state~f-the-azt simulator was also expected to exceed the minimum functional and fidelity zequizements.

Thus in the summer of 1988, Supply System management chose to replace the current simulator.

The risk to the Supply System's Licenced Operator Training Program was the driving factor. The need to train opezatozs and conduct examinations would continue during a major upgrade, jeopardizing both programs.

The i~C was advised of the Supply System's plans to replace the existing WNP-2 simulator with a new simulator by summer 1991 to meet regulatory requirements. The commission agreed that our plan was an adequate long-term solution. The Supply System also pzesented its intentions to perform limited upgrades to the misting simulator to address major Gdelity problems for near-term training.

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22 Simulator Upgrades 1988 - 1990 Without other action, the conditions that led to the decision to replace the WNP-2 simulator would continue to aKect the quality of our training program until receipt of the new simulator.

Because of the need to use the current simulator for continued training, the Supply System elected to provide incremental improvement to better support abnoxmal conditions and emergency operatzng procedures traznIIlg.

In 1988 the operational fidelity of the cuzrent simulator was sufficient to support most of the normal operating procedures duxing startup, power maneuvering arid shutdown, In addition, many of the operating procedures for off-noxxnal conditions resulting from equipment malfimctions could be simulated. However, emergency operating procedures used under accident conditions were not effectively supported by the existing simulator. Those accident conditions fxequently required instructor intervention which is detrimental to operator training and testing. Accidents that could not be run without instructor intexvention included loss of coolant, loss of core Bow, loss of normal feedwater, and ATWS.

With the decision to procure a new simulator, the Supply System initiated a review of the present simulator's deficiencies. In parallel with this more detailed assessment, the Supply System's Training department reviewed the simulator's deficiencies to identify the improvements required to meet training needs over the expected remaining life of the simulator.

The Nuclear License Training Department's assessment looked at the current and planned training sessions and its then cuxrent set of simulator problem reports. Plant modifications that had an important impact on training wexe assessed from a cost/benefit point-of-view. The assessment resulted in a prioxitized set of limited upgrades to the cuxrent simulator. For the simulator models, the boiler model would be replaced and the condensate and feedwater, main steam and primary containment models would first be modified (upgraded). Other plant system models that interfaced with these key models would also require some improvements. These included such systems as the feedwater heaters, turbines and recirculation systems. The Training department's assessment also recommended that the plant process computer display system, a key control room feature, be incozporated into the simulator.

The Supply System presented its intent to make improvements to the current simulator to the NRC in December 1988. The detailed:assessment that established the scope and priorities for the limited upgrades was performed in the first quazter of 1989. The goal was to complete and test improvements to the simulator in time to support annual operator requalifications examinations scheduled for February 1990.

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Work plans were separated into three phases: the first phase, discussed above, was the assessment of the scope of limited upgrades that could reasonably be perfoxmed. The second phase was to develop a new boiler model and to upgrade the main steam header model including steam Bow calculations (from the vessel), condensate and feedwater hydxaulics model, and the containment model. Woxk also began to install the new plant process computer and displays in the simulator.

These activities were completed in mid-summer 1989. The xemaixung work and third phase of the improvements were installing the new boiler model and revising and refining the major models that interface with the new boiler model.

Model integration testing commenced in late November 1989. 'IMs checkout of the limited upgrades foctzsed on the simulator's ability to perfozm noxmal evolutions and selected transient conditions directly in support of planned examixtation scenarios. Integration testing of the models and the simulator plant computer display system continued to mid January 1990. During this time significant improvements were made to the simulator's performance and on January 25th 1990, a new training set was established for the license examixuztion.

2.4 Plans Following the program of upgrades, the Supply System's focus since January 1990 has been to direct its support of the cuxxent simulator to the conduct of the Licensed Operator Training Program. Ongoing upgrades and improvement to the simulator's pexfoxmance have been to support the conduct of training sessions and evaluations. This focus is to allow the most effective use of the sixztulator over its remaining useful life.

The simulator is expected to be xeplaced by the new simulator during a change over pexiod in late 1993 or early 1994. 'Ihe new simulaxor, on receipt, will have a backlog of plant changes to implement. We are cuxzently assessing the level of changes to implement prior to pressing the new simulator fully into service. One option being considexed will be to operate both simulators simultaneously for a period of several months. This will avoid any schedule confiicts and allow better access for Supply System staff to pexfozm upgrades. The certification submittal for the new simulator will be provided when the Supply System declaxes it "ready for training" and puts the simulator into service. Planned upgrades will be fully documented as part of the certification submittal.

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3.0 SIMULATORVIFORiVIATION This section of the WNP-2 Simulator Ccrtilication provides general information about the WNP-2 simulator and reference plant, summarizes the comparison made between the simulator and reference plant's physical attributes, instmmentation, and environment and discusses the available instructor interface features. Thc use of the reference plant's operating procedures in the simulator is also addressed.

3.1 General Information The foHowing general information is provided as reference and for familiarization with thc WNP-2 simulator.

3.1.1 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. 'Ihe simulator is located at the Supply System's Plant Support Facility, approximately one mile ft0m thc reference plant. The Supply System address is:

Washington Public Power Supply System P.O. Box 968 3000 George Washington Way Richland, WA 99352-0968 I I Thc WNP-2 simulator was originally manufactured by Gould Simulation Systems Division of Melville, Long Island, New York.

3.1.2 Reference Plantf7ype/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 iMark II containment. WNP-2 began commercial operations in December 1984.

3.12 Date Available For 'Inning The simulator was available for operator training in September 1983.

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3.1A 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.

32 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 fmnt panel devices fully funcnonal. 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.

3~ 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-1, "Gould Simulator Scope".

For comparison, Figure A-2, "Westinghouse Simulator Scope" in Appendix A, depicts the full range of simulator scope that will be included in the replacement simulator. Both figures also provide equipment lists which identify major panels and items on panels included in each simulator's respective scope of simulation.

The existing simulator has for those panels in its current scope retained a one-to-one relationship except as noted in the exceptions per Section 6 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 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 of all plant procedures as well as the trainees'bility ta monitor all of the contmls within the area of operator resoonsibility addressed as part of this assessment.

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3.22 Panels and Equipment Physical fidelity of the controls and simulated panels per ANSI/AVS 3.5 Section 3.2.2 has been verified against current photographs taken in March, 1992 of actual panels in the WNP-2 control room. Attachment B-4 of Appendix B suxnmarizcs the results of the comparison of the controls on panels in the simulator and the reference plant. Design changes which physically affect the simulator have been identified in an ongomg process where changes which affect simulated panels and controls are classified as to their trainmg impact. Difference between the simulator and the reference plant axe cataloged, entexed and tracked in the simulator's configuration management system.

322 Simulator Control Room Environment The verificatio of the simulator's fidelity to the WNP-2 control room included a comparison of the physical environment. The environment compared includes color, console arrangement, physical furnishings, lighting as well as the audible background. Figure A-3 in Appendix A shows the physical location of the simulated panels. Attachment B-5 summarizes the results of the comparison of the simulator's to the refexence plant control room environment. Deficiencies in the category are assessed in the same manner for training impact.

3.2.4 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, by plant procedure, be observed and/or controlled by plant operators are not simulated or are simulated partially duc to the limitations of simulated panels or controls. Simulator performance testing has identified discrepancies in simulated systems responses which are included as either changes to be pcxf'oxmed or exceptions.

32 Instructor Control Features The WNP-2 instxuctor interface consists of instructor control and monitoring equipment located in an elevated station overlooking the simulator Hoor. The room pexmits viewing of the main simulator control axca through tinted windows. Observation is further enhanced by use of audio/

video equipment which provides the capability to.record activities at the panels. Thc current instxuctor station has a full set of features summarized as follows:

IO of ~A

32.1 Initial Conditions This simulator can support fifty (50) initial coaditions or "snapshots" of plant conditions. Twenty (20) initial conditions (IC's) are xescrvcd for training usc and arc password protected. An additional 18 IC's arc for general use and 12 IC's are for usc with the "backtrack" feature. The IC's include a variety of operatiag conditions and fission product poison concentrations.

Attachment C-1 of Appendix C is a list of the cuxxent IC's used in the simulator.

332 Malfunctions Foxty (40) malfizactioas 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 ascent times to final value of such a range to xcpxesent the plant malfunction condition. Malfunctions may be activated as groups or individually. They can be activated by remote device, time delay trigger, console keyboard or by a combination of simulator events called a Boolean trigger. 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.

333 Items Outside the Controi Room The simulator provides realism as required for training in selected'operator interfaces to systems and components outside thc control room. The simulator includes a communications system which allows instxuctoxs to communicate with trainees just as control mom operators would communicate with equipment operators using telephones, radios and the PAX. Thc simulator also includes a xemote shutdown panel, located separately from the simulator. There are 335 remote operator actions available via the instructor station console. These "Local Operator Actions" are listed as Atta'chment C-2 of Appendix C.

3D.4 Additional Special InstructorfFraining Features Thc WNP-2 simulator includes capabilities to freeze simulation, xun simulation in slower than real time, fast time, and backtrack The "fast" &action can be used to change the rate of xenon buildup or. turbine warm-up by a factor'fzom 1. to 10 times real time. Parameters identified for performance testing are obtainable in hard copy either as plots or pzintouts. Plots are available through either the Simulator Perfonnance Vexification System at a resolution of up to model calculation rates or from a strip chazt 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 aud when simulator operating limits are exceeded a message is provided to the instructor. The simulator instructor has additional features available including audio/video recording and other controls to assist the conduct of training and evaluation sessions.

3.4 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. Simulator certi6cation tests have been conducted using current revisions of procedures. Documentation in the simulator also includes all top tier (blue line) plant drawings and all plant drawings on aperture (micro6lm) cards. Revisions which include reference plant modi6cations are accounted for by License Training instructors in the conduct of planned training or evaluation scenarios.

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4. 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).

4.1 Design Basis Information used as the basis for the simulator's design includes the WNP-2 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 con6guration and performance.

These documents axe controlled by the plant.

Simulator design documentation refiects the configuration of the simulator. This documentation includes computer software and model documentation, simulator hardware and physical configuration information. updated design, data, and completed changes to the simulator.

42 Update Information Update information are changes to the plant con6guration that are reviewed for applicability to the simulator. When changes occur in the plant configuration, they must be reviewed for impact on simulator training. Simulator modifications in process are also tracked.

At the time of this submittal, all plant modifications completed through April 1, 1992 have been input into the design change process and assessed for potential training impact.

The simulator's design basis is established, maintained, and tracked by use of the simulator's configuration management system (CMS). Design basis and update/status information is available through the CMS system. Documents identified in the CMS are available in hardcopy.

42 Simulator Discrepancy Resolution and Upgrading The simulator-has been maintained, since its delivexy, on a basis of evaluating plant change packages, making a detetmm'ation of a change's effect on the conduct of training, incorporating changes where appropriate, then maintaining this change in the simulator's scope. Information 13 of 24

about planned or implemented engineering changes to the plant axe subjected to review using established criteria and processes. Required modifications to the simulator arc documented as Change Requests (CR's) and are used as the basis for all simulator updates and modification.

Other sources that may result in simulator Change Requests include feedback from students and instructors, certification testing, malfunction testing and other information such as industry events.

Outstanding CR's are prioritized and assigned for resolution. Completed CR's are checked and validated, by testing. Each is initiated and processed through analysis, implementation and validation by established instructions.

In 1988, when the Supply System made its detezznination to replace its simulator, there was a significant backlog of outstanding Change Requests, refiecting both plant modifications and deficiencies identified Rom the simulator's use. Thc upgrades made to the simulator in 1989, as dcscribcd in Section 2.3 of this report, addressed many of thc simulator's most serious performance shortcomings.

Following the decision to procure a new simulator, outstanding dcficiencies requiring increases in the physical scope of simulation, major capital invcsunent or added computational capacity werc deferzcd. Allsimulator affecting plant modi6cations and outstanding CR's.affecting the simulator, whether active or deferred, continue to be tracked and were reviewed as part of this certification.

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 CR process in advance of this submittal or are represented by outstanding CR's.

As indicated above, as part of this certification, the Supply System has brought its review of the effect of plant changes on thc cuzrent simulator up-to-date. All outstanding CR's have also been reviewed, xeasscssed for resolution priority and are automatically tracked in the simulator configuration management system. The disposition of the identified set of discxepancies is discussed in Section 5 of this report which addresses compliance to the applicable requirements.

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5. PERFORMANCE VERIFICATION The entire set of tests described in this section were performed for this initial ceztification. The simulator performance tests are divided into four recommended categories in Appendix A of ANSI/ANS-3.5 (1985). This suggested fozznat is followed with a further sub-division in the second of thc categories:

(1) Computer Real-Time Vezification (2) Steady State and Normal Operations a) Normal Plant Evolutions b) Steady State Operation (3) Transient Perfonnance (4) Plant Malfunctions The range of malfunctions currently used for training were also tested as part of this ccztification.

These additional tests are presented to substantiate the simulator's performance where it is used.

These additional tests also demonstrate the Supply System's undexstanding of the cuzzent simulator's limitations and the effective use, including compensatory training whcrc necessary, of thc current simulator's capabilities.

5.1 Simulator Tests The pezfozznancc tests conducted for certification were developed to address thc specifi requirements of ANSI/ANS-3.5 (1985). To assure that the tests provided adequate coverage of the requirements, a cross refexencc between the tests and requirements was prepared. 'IMs cross-index is provided in Appendix C, Attachment C-I. As noted in Section 5.2, additional malfunction tests were exercised to validate thc malfunctions used by License Training to support training and evaluation scenarios.

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, thc source of evaluation data and test results. They are provided as Attachments C-2 thxough C-6 in. Appendix C.

Where appropriate, the pexformance tests selected for certificatio are supported by analysis data which includes the plant response recorded from spccific events and evolutions, engineering 15 of 24

analyses, the WNP-2 Final Safety Analysis Report as well as other supporting information. This baseline information is cross-indexed to the supported test procedures and is available on 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 certi6cation report. Allidenti6ed discrepancies from these perfonnance tests have been evaluated for potential impact to simulator training and perfonnance evaluations. The disposition of the certification performance test results are provided in Section 6A of this zepozt.

5.1J, 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 duzing the conduct of its assigned training and evaluation scenarios. His test is intended to verify ANSI/ANS-33 (1985) requirements for real-time operation. The abstract for this test is given as Attachment D-2 of Appendix D.

5.1 ~ Normal Plant Evolutions This series of tests demonstrates the simulator's ability to be operated over the full operating range fxom fizll power to cold shutdown and back to full power. The tests are based dizectly on WNP-2 operating procedures. All indicatozs, computer zeadouts, alarms and other man-machine interfaces used during the plant evolution are veri6ed in the simulator.

This category of tests also veri6es the nuclear characteristics of the simulated core model. The coze's response is verified against the WNP-2 cycle 1 mid-life core. Flux profiles, thezmal perfozmance and fiux response to core Bow are also checked.

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 gives the abstracts of these tests.

5.12 Steady State Operation The purpose of the tests in this category-are 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 pezfozmance is compared for key parameters as identified in ANSI/ANS 16 of 24

- 3.5 (1985) Appendix B 1.1 Steady State Performance. Steady state stability is also verified here.

Abstracts of these tests'esults are Attachment DA, Appendix D.

~nsient 5.1.4 Performance This series of tests are to verify that the %NP-2 simulator performs in accord with the criteria of ANSI/ANS - 33 (1985) Appendix B 1.2 Transient Perfozmance. Selected transients are introduced into a stable operating condition and the effects observed and recorded. Response of the simulator is expected to be consistent with the expected response of the plant under similar conditions. See Attachment C-5 of Appendix C for abstracts of these tests.

5.1S Plant Malfunctions This series of tests were performed to verify the proper response of the simulator to abnormal and emergencyevents including ma16mctions available in the simulator. These tests are intended to verify the inherent plant response as predicted or known for the panicular type of failuze. The test procedures are written to specifically address each of the malfunctions listed per ANSI/ANS - 3.5 (1985) Sections 3.1.2 (1) through 3.1.2 (25). Specific tests were also selected to validate the simulator to known plant responses as substantiated by operating experience or analysis.

Appendix D, Attachment D-6 gives the abstracts for these tests.

5.2 Training/Evaluation Scenarios The Supply System's decision to procure a new simulator was predicated in part due to shortcomings in model perfonnance compounded by older, simplified models. These concerns with fidelity also led to pezfozming the upgrades discussed in Section 2.3 as well as the exercise of care in the preparation and use of the simulator for training and evaluation. That care is exhibited in the development and vezification of simulator scenarios, tracking of known discrepancies and establishing work arounds or alternate training to compensate for these shortcomings.

The Supply System uses a preestablished inventory of simulator scenarios for training sessions.

An additional set of Emergency Operating Procedure (EOP) scenarios are used for EOP training and evaluation. The objective has been to focus efforts to address identified discrepancies that affect cuzrent and planned training for the remainder of the simulator's useful life. Consistent with this emphasis, the certification testing has had. the additional objective. with verifying the simulator peziozmance to the ANSI/ANS-3.5 (1985) requirements, to validate the malfuncnons now in use for training scenarios. Appendix E lists these additional tests that were conducted and provides abstracts of their results.

17 of 24

52 Quadrenniai Test Schedule Consistent with this certification, thc Supply System wB1 conduct continued testing in accordance with Regulatory Guide 1.149, Section C3. Selected performance tests are planned to be repeated annually with others over the 4-year period allowing more than 25% of the total to be conducted each year.

The Supply System also plans to test or validate each malfunction that may be added to the current training/evaluation repertoire. The cuxtent scope of malfunctions have been incorporated into the test program for this initial certificatio. Although the Supply System anticipates delivery, installation, and certification of its new simulator within 18 months of the date of this certificatio, test plans are provided for a four-year pexiod in accord with requirements.

52.l Annual Testing Annual testing willinclude:

1. Computer Real-Time Verification Test No. 14.5.4 Simulator Real Time

2. Steady-State Operation Tests Test No. 14.43.1 - 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. 14.43.1 - 100% Heat Balance Test iVo. 14.4.5.4- 100% Mass Balance Benchmaxk 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 oi AllRecirculation Pumps Test No. 14.4.9.24.34 - Recirculation Pump B Trip Test No. 14.4.9.24.31A - Main Turbine Trip fxom LT 30%

18 of 24

Test No. 14.4.8 4- Power Ramp Rom 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 Insoluble MSL Rupture Test No. 14.4.10.10 - MSIV ISOL with SRV Full Open 522 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 F. 'Ipse schedules represent performance of approximately 25 percent of the total tests requited for certification per year. Any deletions or changes in scope or to ANSI/ANS-33 (1985) acceptance criteria related to these tests willbe addressed by the refiling of Form 474 to refiect changes in the Supply System's plans.

19 of ~A

6. COMPLIANCE The following section summarizes the fidelity of thc simulator with respect to the applicable requirements and the endorsed Standard. The Supply System's ceztification submittal follows the recommended guidance of ANSI/ANS-33 (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 pezfozmance has been vezificd.

6.1 10 CFR 55.45 Regulatory Requirements The Supply System takes no exception to the requirements of 10 CFR 55.45 - Operating Tests. It should bc noted that this certification is being submitted at a later date than that rcqizized by this Regulation. This late subminal was allowed through the Nuclear Regulatory Commission's approval of the Supply System's request for an extension to the submission deadline. Specific reference to these communications is provided as part of our cover letter of transmittal for this certification.

6.2 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 spccific guidance contained thezcin.

The evaluations conducted in accord to this guidance have documented a number of deficiencies with resect to the ANSI/ANS - 3D (1985) Standard endorsed by Regulatory Guide 1.149. "

Since the Supply System is in process of having a ncw simulator constructed, selected identified deficiencies are not planned for cozrection in the current simulator. These de6cicncies are taken as permanent exceptions to requirements of ANSI/ANS - 3.5 (1985) for thc current simulator..

The following subsections pzovide a summary of the limitations of the cuzzcnt simulator to thc certification requirements.

20 of 24

63 Exceptions to ANSI/ANS-3w (1985)

Exceptions to ANSQANS-33 (1985) not plaaned to be coxrected on the current simulator are summarized here. The identified exceptions that affect training are to be reconciled by the expanded scope of the new simulator.

Our assessment of identified discrepancies also considered other factors in detczznixting their disposition. Whether training or evaluations could bc conducted using job pexfozmance measures in the reference plant contxol room as an alternative to simulator training was one factor. Near tezm training plans wezc a second factor, if an identifie discrepancy was not within the cuxrent purview of training emphasis, its correction might be defexzcd until receipt of the new simulator.

The cost to correct discrepaacies on a simulator with a limited xcmaiaing life was also considezed.

The addition of major capital equipmeat investment in the current simulator was not desired.

The followiag summary is provided to paralle1 applicable xequizcxneats of ANSI/ANS-3.5 (1985).

62.1 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 pezfozmed and the results assessed using the guidance of Section 4. - Performance Cxitcria, of the Standard.

All Boiling Water Reactor (BWR) related capabilities weze evaluated during thc course of certification testing. Only one exception is taken in the conduct of tests per Section 3.1-Simulator Capabilities and Appendix B.l BWR Simulator Operability Tests of the Standard. That is, Plant Malfunction 3.1.2 (5) which addresses the loss of condenser level control: Thc simulator does not have the condenser hotweH level controller as cuxzcntly implemented in the refexcnce plant. The ability to adequately evaluate this mal&mction is limited since the controller is required to initiate corrective action.

62.2 Simulator Environment The degree of panel simulation is shown on Figure A-l, "Gould 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 bc iacoxporated iato thc simulator. for one or mozc of the following reasons: 1) a similar or redundant panc1 for another division is simulated, 2) operator actions on these panels are routine, 21 of 24

or 3) compensatory classroom or on-the-job training is utilized for panel manipulation instruction.

Appendix B-1 provides a listing of thc panels detezmined to have minor training impact that are not included on the current simulator. This information is available Rom the simulator configuration management system.

The simulator also has ll partially simulated panels. For two panels, the lack of full simulation was assessed to have no training impact. The remaining nine paztially simulated panels determined to have minor training impact are listed in Appendix B-2. For reference, a listing of the fully simulated panels is pzovided as Attachment B-3 in Appendix B.

A detailed comparison for each instrument and control on each simulator panel was also made with each matching rcfezencc plant control room item. Appendix BA provides a summary of the disczepancies identified by comparing thc simulated instruments and controls with the reference plant'control room. The Supply System takes exception for several key instrumentation systems including the Rod Worth Mhumizer, Leak Detection Equipment, Wide Range Neutron Monitoring System and the Condenser Hotwcll Level Control System which are not planned for implementation in the simulator. The simulator control room environment assessment identified no discrepancies that have any training impact.

623 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 suppozt 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 perfozm the reference plant evolutions described in ANSI/ANS-3.5 (1985) Sections 3.1.1 (Nozmal Plant Evolutions) and 3.12 (Plant Malfunctions) has been assessed as part of the test program.

62.4 Simulator Waining Capabilities The core model available in the simulator does not include the capability to allow selection of initial conditions at various times in the coze life. With this exception, the cuzzent instructor station has all the capabilities required by Section 3.4 of ANSI/ANS-3.5 (1985).

22 of 24

629 Simulator Design Control The Supply System takes no exceptions to the zequirements of Sections 5.1 Simulator Design Data and 5.2 Simulator Update Design Data of ANSI/ANS-33 (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. The Supply System takes exception to the requirement of Section 5.3, Simulator Modifications, of the Standard, in that modifications on the existing simulator willbe limited.

Outstanding and current Plant Modifications Records (PMRs) were assessed for this certification.

Each PMR was evaluated individually to detezznine if the corresponding modification should be made on the simulator. Theze are cuzzently 123 modifications that have been completed in the reference plant, detezznined to impact either the simulator hardware or software, and not yet incorporated in the simulator.

Those PMR's detezznined to impact scheduled training have had CR's written and will be corrected. The PMR or its subsequently written Change Request was "deferred", ifit had little to no impact on training. It was also deferred if the modification was not determined to be cost effective, and the changes are scheduled to be incorporated on the replacement simulator, and other training materials (on-the-job tzaining, classroom etc.) provide adequate coverage of this infozmation.

6.4 Upgrades and Corrections Alloutstanding Change Requests (CR's) were evaluated as to their impact on current training and the cost of making the modification to the existing simulator. The zelative benefit of making a change was considered for the reznaizzing expected life of the simulator. This evaluation resulted in categorizing the CR's as either "open", on "hold" or "defezred".

"Open" Change Requests are planned to be implemented on the current simulator 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 CR's include many discrepancies identified Qom certification testing and reviews.

Change Requests in the "dezezred" category represent identified discrepancies that aze not planned to be implemented in the current simulator. These include exceptions summarized in Section 5.3 of this submittaL CR's in this category, although having an impact on training, either 23 of ~M

1) require excessive resources or materials to implement and other training measures are used to compensate or 2) the CR has minor or no impact on current and planned training.

A third category was established to allow for changes in training emphasis and priorities of required corrections. CR's on "hold" will be reevaluated quartedy to determine if they should be reassigned to the "open" category and implemented.

24 of 24

WNP-2 SIMUlATOR CERTIFICATION APPENDIX A SIMULATOR SCOPE DIAGRAMS Figure A-1 Gould (current) Simulator Scope Figure A-2 Westinghouse (new) Simulator Scope Figure A-3 Gould Simulator Layout

Q 9

~ ~ ~ ~

C75~DS1-TP TOUCH PAD DISPLAY C75%GDS1~RT CATHODE RAY TUBE DISPLAY 8 MAD-24 C70GDS2-Tp -'... TOUCH PAD XSPLAY BD-RAD-23 C704IDS2&RT .-.CATHODE RAY TUBE DISPLAY,- ',.",", .',;; .--,;=- -- .'-

Vl"To VTS; . PPCRS COLOR GRAPHIC

' T pPCRS A~M PRINTERS TERMIIIALS'-PPCRS-A1SA2

- ' .BOAIID..F':.--"'-~".,~

P842 BOARD 832 H22-PI00:.-

REMOTESHUTDOWN,.

-'EMOTESHUTDOWN":--.-: .. -.

~

C61-P001 BD 'M'D'P' BDKII ~ ~

BDR'DH ~ ~

BDJ~ ~

C750402 GRAPHIC DISPLAY TERMINAL2

,J P826 BD P811 P812 P813 P814 Q

BD 'lt!P N

'IQ'D P827 I II I II I II "C7504l P2 MATRIXPRINTER,"-'-,"

MATRIXPRINTER

'750.MP1',-

'.'- --~." .--

FRTP -

FIRE REMOTETRANSFER PANEL -".;."-'

RELAY CAB "

F825

."BOARD 'A': =

BENCHBOARD ~

RC-1 RELAY CAB. BOARD B' 'BENCHBOARD F823 RC-2 SI BOARD%' BENCHBOARD BD'L GGF APERTURE BOARD'H',. -:,=,--'ONTAINMENTVENTSPURGE -.:.:="-'.- -'~

C~RD BOARD'J- ' CONTAINQENTMONITORSYSTEM -'",;:~

BOARD'Q'.. -- "SGT TRAINA SCAC DIV1 -=..':.= '."

SGTTRAINBSCACDIV2-'-".;. ..--'.'-.',.;=,"-'

P61 0 Also Available On BOARD  %'MU BOARD'Kll'~.

BOARD Yl' -'CCISW I COOLING TOWER SYSTEMS-SYSTEMS =":;,.i; .- .-,

Aperture Card BOARD 'P'.'ONTROL ROOM HVAC" BOARD 'R'EACTOR I RADWASTE BLDG HVAC P606 BOARD 'S', ISOLATIONVAI.VES STAT UGHT DISPLAY, BOARD V' FEEDER WATER 6 HEATERBYPASS DISPLAY;.'

VI'AINSTREAM BOARD P660,"

P601 -

.. LEAKAGECONTROL SYS. CONTROLS.

PROCESS RADIATIONMONITORS BENCHBOARD P602, BENCHBOARD P603 .. BENCH BOARD =

• P6CS:-;=

P607 PROCESS RADIATIONMONITOR RPS-AIRADIAQONMONITORS ~

TIP CONTROLMOMTOR --='-'650

.'604,:.*,

P814 P604 F600 (ATW8) C

~, VT4A GD2 LEGEND.

FCP 2 VT4B P614 OCESS MISC MONITORS MP1 A1 RE CONTRO P6 P851 PARTIAL PANEL SIMULATED PANEL FCP FCP-1 FCP~

LLSCOPE SIMULATION P632 " I LEAKDETECTION SRO P634 P650 RECIRCULATION CONTROL

~ UTOMATICTRIP VmHOUT SCRAM),

P672 OFF GAS OPER.; P873 RADIATIONMONITORING DESK VT2B Fcp CONTROL PANEL SHIFT Ro BD BAD@3 MONITOR CONTROL BOARD

~ ~

MANAGER Ro OPER. ~ ~ ~ BD.RAm4 RELEASE RAD MONITOR OFHCE OPER. DESK DESK H22.pl 00 BD BD 'B'820 BD

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q pROCESS RADIATIONMONITORS 4'00 C7~DS1-Tp TOUCH PAD DISPLAY BD-RAD-24 Cpu) DS1 ART CATHODE RAY TUSE DISPLAY g60I 8 ENCHBOARD BD-RAD-22 C70Q~.TP TOUCH PAD DISPLAY 8 D-RAD-23 C704 IMZCRT CATHODE RAY TUSE DISPULY

- = "- pROCESS

-,'D'Y'D'V'835 BDT BD VTZTD VT5 PPCR!'A1 4LAZ PPCRS COLOR GRAPHIC TERMINALS PPCRS AULRM PRINTERS

$ 604" "F606 'PSJL I RADIATIONMONITORS RADIATIONMONITOR"

"; -'..'D-'F .P831 j)D'Gf-. .

-- "'.';. PIf42 H22-Pj00 REMOTE SHUTDOWN F607 4 T)p CONTROLS MOMTOR P841; -

C81-'PIC) REMOTE SHUTDOWN 9608 pOWER RANGE NEUTRON MONITOR ~

',,=..L'~..'.:,.'--

'GII'RC-A

=

CMS+P. ARC-A RELAY CABINET lB609 TRlp SYSTEM'A'RPS CMSer - 'R'D 'H'D BD78'D'P'301 14017 BD'Kll'826 BD 'J'812 RC-1 RCJ)

REULY CABINET RELAY CABINET P611 8

TRIP SYSTEM >'PS BD P813 P814 o '" ."

ARCJ) RELAY CABINET .,%1 ";- ROCKS/.

I II I ll I II BD VIP F821 BD 'N'827 ARC-8 RC-2, REULY CABINET

-R F G P614 pROCESS MISC. MONOITORS ='= ":=-.=".

C-1 P825 oo CO P6208 628 P6078 D C7~)DZ C750.) IPI GRAPHIC DISPLAYTERMINALZ MATRIXPRINTER r'T .r RC-2 .

PS AAC g uS C750.) Ip2 MATRIXPPJNTER P618 DMSIONII RHR PUMPS'8'4LW BD 'L m AA.G4CnAO 6 0 P607A P607C P607E FRTP-A RRE REMOTE TRANSFER PANEL -,i,-...A3 4 BOD ) CA. S OO 8 OAR I) BENCHBOARD P621-- REACTOR CORE ISOULllON COOULNT.; .~:-.'--

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BENCHBOARD P622- INBOARDISOLATIONVALVES',"--; -': -D.-L -';.. "'-

1)'OARI)

BENCHBOARD f623 OUTBOARD ISOULTION VALVES '-:-":-";-'IGH

'C'OARI)'D'BA TEMPERATURESCANNER P625 PRESSURE CORE SPRAY'.

G 0 P626- DIV, I FUEl POOl COOUNG FPC.1

~o o BOARI)

CONTAINMENTVENT 84 PURGE P627-'.

DIV. Il FUEL POOL COOLING FPC4 ..-'-. =: --':.-; '-;,

P627

'H'OARI)

CONTAINMENTMONITOR SYSTEM P628,"=.- AUTOMTC DEPRESSURIZATION SYSTEM 'A';

'J'OARII,'KI'OARD SGT TRAIN A 8I CAC DIV 1 P629 DMSION I LPCI IL RHR PUMP'A"." - = ~

TA. P609 P606 Pl P2 P3 Xlf SQT TRAIN 8 84 CAC DIV 2 P631 AUTOMTC DEPRESSURIZATION SYSTEM'8'MSION P626 STRONG MOTION RECORDR/MET RECD P632 I LEAKDEfECTION:,-~; .- .

OTTO BOARD'L'OARD'M'OAR TMU I COOUNG TOWER SYSTEMS P633 IIPB.BI RADIATIONMONITOR,-:,'; ',- .:. ':

- P621 P619 P622 I) RCCISWSYSTEMS- F634 ~

" RAOIR ODLATION COIIIIIOL

'N'OARI)

CONTROL ROOM HVAC P642 DMSIONIILEAKDEfECTION P 629 P628 P642 P616 P REACTOR I RADWASTE BLDG HVAC PS50 ATWS (AUTOMATICTRIP WITHOLITSCRAM)

'P'OARI}

P613 P 631 BOARI) T

'R'OARI)'S',

I ISOLATION VALVE STAT LT DSPLY FEEDER WTR 8 HTRBYPASS DSPLY.;,-

P672 P873 OFF GAS AREA RADIATIONMOXITORINGT-;'*-

BOARD 'W'- MNSTREAM LEAKAGECRNTL SYSTEM. CNTRLS. RFT GOV 1A,B REACTOR FEED PUMP TURB CNTRL PNL P634 P673 AI.,F6'IZ ~

(ATWS)

P672 I P614 P604 MP2 P600 P625 TA.

BOARII O:Glf 7

R,'Ql'-

'Y' V'OARII WETWELL MONITOR FEEDWATER HTR LVLCONTOL LOG FCP FD ARS CP-1301 RRE CONTROL PANEL BOARD RRE PROTECTION CABINET ALTERNATEREMOTE SHUTDOVIN PANEL H2IO2 MOMTOR

~A PANEL'FCP'CP-1 774A DDT AA CP 1401 H2/02 MOMTOR 44 FCP-2 VT48 MP1 A1 FIRE CONTROL p851 SAS CONS LE FCP4 BD DRWNQ P601 R ~

8LES SRO OPER.

DESK VT28 SHIFT RO MANAGER OPER. HZZJB100 OFFICE RO OPER. DESK SI DESK C81 P001 APERTURE FRTP-1 7'

CARD:;.

ARS BDW BD BD'A'--- A~)4bie Oe.

P800

'8'820 P840 APeWoee ~qg GOY 1A GOY 18 LEGEND:

PARTNL PANEL SIML!ULTED FULL SCOPE SIMULATION QZIDZiDZ(d-~K 920436.2 JUNE 1992> ~

Figure A-2

44 v

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1 lb OK 4

li I

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PL Q

BB i 0 4

~ ~ ~ ~ 4 NEHL. uxsmza&OI PULY C75aGDS1-TP TOUCH PAD C7504BOS1&RT CATHODE RAYTlIBEDISPLAY C704052-TP TOUCH PAD OISPlAY C706082RT CATHODE RAY TUBE DISPLAY VT2 TO,VT5 PPCRS COLOR GRAPHIC TERMINALS PPCRS-A18A2 PPCRS ALARMPRINTERS H22.P1CO REMOTE SHUTDOWN C61-P001 REMOTE SHUTDOWN BOER C7504'02 OlSPLAY TERMINAL2 BD BAD-23 C7504IP1 MATRIXPRINTER C750+IP2 MATRIXPRINTER FRTP.1 l FIRE REMOTE TRANSFER PANEL BOARD A'OARD.'8'OARD,C'RAPHIC BENCHBOARD BD BENCHBOARD P628 RAD-24 BENCHBOARD F61 0 P842 (BD'F)

',, ~: =-' F631 F832 '."4C~HOV~P'.8'.;-==;- P619 CONTAINMENTVENT 84 PURGE P609 P611 CONTAINMEN1'ONITORSYSTEM

-'GROUP:A;,.=: SGT TRAIN A 8 CAC DIV 1 SGT TRAIN 8 Ei CAC OIV 2 TMU I COOUNG TOWER SYSTEMS BD 'M'D'P' D 'KII 80 'R'0 'H'D BOARD,'H'OARD.'J'OARD'KI'OARD'KII'OARD'M'OARD'N'OARD,'P'OARD'R'OARD,'8'OARDS%'OARD%I'soo RCC I SW SYSTEMS CONTROL ROOM HVAC P826 80 REACTOR I RAOWASTE BLDG HVAC

'J'811 P812 P813 P814 BD ISOlATION VALVE8 STAT UGHT DISPLAY Rc-1 P821 BD 'N'827 RC-2 FEEDER WATER 6 HEATERBYPASS DISPLAY F825 MAINSTREAMLEAKAGECONTROL SYS. CONTROLS.

PROCESS RADIATIONMONiTORS P601 BENCHBOARD BBB P602 BENCHBOARD BD 41

'L'823 lEGEND: P603 BENCH BOARD P604 PROCESS RADIATIONMONITOR F606 R PS-A I RADIATIONMONITORS P673 II~~",:~ PARTIAL PANEL SIMUlATED P607 TIP CONTROL MONITOR P614 P604 P600 -',,rPO)V A-RANG Ng RONM NITOR"4:~r-P 634 P 650 P672 FULI. SCOPE SIMULATION ':, 'TRIIl4SYSTEI4('44'-,'RPS -"',-~

P609,-.~ .; ".:;-,.

VT4A FCP-2 BB 'B'T4B P614 PROCESS MISC MONITORS

'o oz RE CONTR 0 MP1 A1 P619-4;. ~...,.

i 4,- '"4)FTr,U4. I I415 O,;,- ..-~.,.v:.;

PANEL P851 4 R 44

'FCP'CP-1 P632 DIVISION I LEAK DETECTION I

rh Ol FOP'RWNG ~ ~ ~ ~ P634 RECIRCULATION CONTROL P650 ATWS (AUTOMATICTRIP WITHOUTSCRAM)

VT3 OFF GAS FILES SRO OPER. AREA RADIATIONMONITORING DESK VT28 E~XE --'.'--

FCP RRE CONTROI. PANEL BD.RA043 RAD MONITOR CONTROL BOARD SHIFT RO 4

H22-F100 BD.RAD44 BLDG RELEASE I'hatt RAD MONITOR MNGR RO OPER.

OFFICE OPER. DESK DESK C61-P001 FRTP-1 SI APERTURE 80 'C'800 BD '8'820 BD 'A'840

'CARS AiSO AVER~>re0@

A'Pd TYB '6&

920436.3 JUNE 1992 Figure A-3 Pzzoz/dzid -88'

0 WNP-2 SIMULATOR CERTIFICATION APPENDIX B SIMULATOR ENVIRONMENT Attachment B-1 Panels and Panel Sections Not Simulated Attachment B-2 Partially Simulated Panels -3 Fully Simulated Panels Attachment BA Controls on Panels Attachment B-5 Control Room Environment

WNP-2 SIMULATOR CERTIFICATION ATTACHMENT&4 CONTROLS ON PANELS The following is a suznmazy of the compazison made for each insmmient and control on each simulator panel with each matching refezence plant control room item. Detailed information on each identified discrepancy is available in the configuration management system. In this area, the assessment identified a number of deficiencies, some of them redundant (e.g. an incorrect instrument with an incorrect label), with most detezmined to have no or minimal impact to training:

Ann ciato 4 - The identi6ed annunciator de6ciencies were primarily due to engraving errors. Exrors involving incorrect word order or incozzect color when illuminated (white vs, amber etc.), weze determined not to impact training.

A majority of the deficiencies were identi6ed for the annunciator windows on the Fire Control panels. These de6ciencies resulted from a plant modification which edited the wording on these windows. This change has mininial impact on training, and cozrection is defezred with these discrepancies documented for training purposes. In addition, annunciator windows associated with defezred modifications are also defezred and will be separately identified for training.

Disczepancies determined to impact current training, resulting from plant modifications, incorrect wording, or windows that have been "blanked" in the plant have been incorporated as Change Requests to be corrected.

~gtzgQm - Only 3 controllers on the simulated panels were identified as having discrepancies.

One discrepancy due to minor labeling error had no impact on training. The other two disczepancies result ftom the Condenser Hotwell level control modi6cation, which has been defezzed based on mizmnal training impact and operator fanuliazity with these controls.

Dem cation Lines - The deficiencies in this category result Qom the zeplacement of control room recorders or panels that have been partially simulated. Since the demarcation lines are correct for the existing simulator configuration, these lines have no impact on training.

Qgg@aggp - We majority of discrepancies in this, category are minor errors in switch labels which do not impact operation of the associated control (i.e. use of "NORIVP vs. "NOR" etc.).

Disczepancies related to plant modifications (Containment ventilation fans and Turbine Oil exhauster) detezmined to impact training will be cozrected via Change Requests.

1 of3

.Tb' g I* d' dl, lych .p 1'*.

control room Rznishings, labels on this equipment etc. The majority of these items do not impact training as they aze not used by operations. Approximately 25% of these discrepancies have nzinimal impact on training (including the replacement of the Turbine Supervisory system equipment) and are deferred until the replacement simulator, but will be identified for training puzposes. Those discrepancies with more significant impact on training (new Rod Worth Miniznizer, Leak Detection equipment, Wide Range Neutron'Monitoring system) have been identified with Change Requests and will be fuzther evaluated for incorporation into the exi>~g simulator on a quarterly basis. Items considered as part of the control room environm'ent, e,g.

furnishings etcare discussed in Section 5.3.3 to follow.

/~cia .> - Only one zelay that is simulated was identified as a discrepancy. It is on the panel in the simulator but not the plant. This discrepancy has negligible training impact but will be identified for training purposes. Note that a number of relays are not simulated and were included in that category below.

- This category identifies lights associated with control functions that have improper engraving or a removed in the actual control room. Approximately half represent only minor changes that do not impact training. Those that affect operation of the plant, including significant engraving errozs or have been removed from the control room panels have been identified and willbe corrected through the Change Request process.

hhg~ - This category identifies meters with improper scales or labeling, metezs that have been replaced or removed etc. Approximately 25% of these represent only minor differences in size of characters or brand name labeling and do not impact training. 'IIzose discrepancies that are defezzed include meters associated with equipment whose change is defezzed until the replacement simulator, including the Turbine Supervisory system, and recorder replacement on P601. These discrepancies are all identified for training purposes.

Th simulated. This pzimarily includes; control room panels and furnishings, electrical relays, computer tezminals, copier equipment and the label tags associated with this equipment. Each tag, associated with a device not simulated,has been separately identified but is considered to have no impact on training, since the device itself has also been evaluated for impact. The.items'in this category that are being defezred consist of panels and relays that are not simulated.

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Th / I

• d qp

• g . d*l p room panels that disagree with or are not simulated. Those identified as no impact on training include those on the TIP panels which are not used by operators, and on equipment that will be removed &om the simulator based on plant modifications. Those that impact operations have been identified for correction through the Change Request process.

~Eti~P~ane - This category identifies panels that are of the incoxzect color or are only partially simulated. Each of the items in this categozy have been defezxed until the xeplacement simulator and are identified for training puxposes.

ging - 'Ibis category identifies disczepancies associated with the lines that mimic system Qowpaths etc. A majority of those identified include improper or nonexistent mimicking and will be coxxected though the Change Request process.

j~cgf~ - 'Ibis category identifies discrepancies associated with control room recorders, Most of these discrepancies axe the result of an ongoing plant control room modification to replace recorders. The majoxity of these recorder changes are being defezzed until the replacement simulator based on the operators fxequent use and fanuliazity of these in the control room. Those recorders that have been removed or have incozzect labeling will be corrected though the Change Request process.

~w' - Discrepancies concerning switches result from items that are no longer in the plant or have a diffezent appearance than those in the control room. Those with minor differences such as the shape of the xzng behind the switch, have no impact on training. The discrepancies associated

, with switches that were zemoved with the replacement of the Leak Detection System equipment have been identi6ed with a Change Request and will be further evaluated for incorporation into the existing simulator on a quarterly basis. Those switches with incoxxect labels or that are related to a plant modification which has not been defezred in the simulator willbe cozzected through the Change Request process.

T~ - Tag deficiencies identified are primarily due to engraving errors or.tags that are missing or need to be removed. Those tags associated with devices previously identified in other categories as an item to be defezzed or with no training impact wexe evaluated as no impact to training. Those tags which had only minimal impact on training were defezxed and identified for training purposes. Tags,associated. with.equipment that has been altered by a plantmodificatioxz or have an impact on device idennfication or opexation wiQ be cozxected through the Change Request px'ocess.

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WNP-2 SIMOLATOR CERTIFICATION ATTACHMENTB-5 CONTROL ROOM ENVIRONMENT The discxepancies that our assessment identiffed are suzamarized as follows:

Qj~ugigga - The simulated control room has thc same operational ffoor space available as in the refczeacc plant control room. The dimensions of the simulator control room extend to the location of the teanination cabiaets on the north, south and west walls of the refexence plant control room.

The simulated control room has been truncated approxiznately 20 feet short of thc actual control room, with a temporary wall at the end opposite of the main contml panels (east wall of reference plant control room). The simulated control room's ceilings and Qoors match the reference plant control room.

F~aciTiti - The simulator includes a patdaUy simulated replica of the shift manager sof'gce which is outfftted with plant proceduxes as contained in the reference plant control room. Other items such as logs and furnituxe in the shift maaagexs oiiicc axe not zeplicatetl The double door airlock access to the plant contml zoom is also not duplicated.

~ - It should be noted that the panels in the reference plant contml room are now being repainted a different color. The new simulator has incorporated this change into its design. 'Ihe current simulator panels do not match the new color which is an exception to the Standard.

~lg - The main control panel layouts on the simulated control room Qoor are identical to thc main control boards in the reference plant. Back panel locations on thc simulator Qoor dier fmm

~ \

the plant. Figure A-3 in Appendix A shows the location of the simulator's control panels.

Fuzoit~u - The stationary control room furniture including thc reactor operator's desks and consoles, the senior reactor operator's desk, drawing cabinets aad procedures storage cabiaets are identical to the zefcrencc plant. Some movable furniture located in the plant control room along the walls or in back locations along the east wall are not included.

P ceduze an rator Ai - As noted previously, plant procedures used in the reference plant control room are also included and contmlled in the simulator. Contmlled operator aids in the control room arc located identically on.panels..Discrepancies in this category are. summarized in Section 5.3.2.

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BBackBoouunndd - All lighting responses m the reference plant ste available for simulation.

Annunciator audible indications, horns and emergency tones are all simulated. The instructors have all communications systems available for simulated actions including radio and telephone communications. Control room background noises and plant noises ate not simulated.

The discrepancies in the control room environment as compared to the reference plant control room weze determined not to have a cost bene6t to their training impact to correct for the remaining expected life of the simulator.

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WNP-2 SIMULATOR CERTIFICATION APPENDIX C INSTRUCTOR INTERFACES Attachment C-1 Simulator Initial Conditions Attachment C-2 Local Operator Actions

WNP-2 SIMULATOR CERTIFICATION ATTACHMENTC-1 SIMULATOR INITIALCONDITIONS 0% 14.71 0% Cold Shutdown 0% 14.70 0% Ready for S/U 0% 7.50 0% Almost Critical 0% 7.54 0% Point of Adding Heat 1% 136.82 0% Heat Up e 135¹ 12% 519A4 0% Heat Up e 520¹ 10% 866.97 .01 Heat Up e 865¹ 21% .01 Ready to Synch Main Tur 39% 953.39 .03 Ready for 60 Hz Operations 56% 963.00 80% Rod Line 96% 994.97 .06 95% Min Xenon 100% 100197 1.03 100% PWR EQ Xenon

- 59% 965.35 1.17 "'hutdown e 60% Power 14% 940.41 1.67 Shutdown e 14% Power 2% 933.72 1.96 AllRods In 1% 73.31 2.74 C/D e 75¹ 0% 34.97 2.71 C/D 6" 35¹ 0% 14.70 2.87 SDC In Progress

WNP-2 SIMULATOR CERTIFlCATION ATTACHMENTC-2 LOCAL OPERATOR ACTlONS 001 APIM-AGAF APRM A GAIN ADJ FACTOR 0-2 FW 0 TO 2.0 002 APRM-B GAF APRM B GAIN ADJ FACIQR 0-2 FW OTOo 0 APRM-C GAF APRM C GAIN ADJ FACIOR 0-2 OTO'7 0 APRM-D GAF APRM D GAIN ADJ FACTOR 0-2 0 TO 2.0 APRM-E GAF APRM E GAIN ADJ FACI'OR 0-2 0 TO 2.0 006 APRM-F GAF APRM F GAIN ADJ FACTOR 0-2 0 TO 2.0 007 AS-BLR-1 AU2GLARYBOILER - ON LB 008 CAS-V<53 CAS-V<53 1=AIR 2~N2 OTO2 009 CAS-C-lA FIRE WTR FOR CAS COMPR. LB 010 CAS-C-1A CAS COMPRESSOR RESET LB 011 CIA/CAS XHE (N2=7; CAS=F) LB 012 COMPUTER COMPUTER RESEI'FT PWR LOSS LB 013 COND LEG COND NOR SYS LKG (0-1E7) FW 0.0 TO 1M 014 COND-V-1062 FIRE WATER X-HZ OPEN LB 015 COND-V-107A COND PMP1A DISCH VLV0-1.0 FW 0.0 TO 1.0 016 COND-V-107B COND PMPlB DISCH VLV0-1.0 FW 0.0 TO 1.0 017 COND-V-107C COND PMPlC DISCH VLV0-1.0 FW 0.0 TO 1.0 018 COND-V-120A COND BOOST PMPA DIS,7LV 0-1 0.0 TO 1.0 019 COND-V-120B COND BOOST PMPB DIS VLV0-1 0.0 TO 1.0 020 COND-V-120 C COND BOOST PMPC DIS VLV0-1 0.0 TO 1.0 COND-V-161A SS-EV-1A LCV BP VLV0-1.0 0.0 TO 1.0 022 COND-V-161B SS-EV-1B LCV BP VLV0-1.0 0.0 TO 1.0 023 COND DEMINS COND DEMINS ON LINE 0-5 OTO5 024 COND-V-76 COND DEMIN B/P CYIR SW- LB 025 COND-V-76 COND DEMIN B/P RST SW LB 026 COND-V-12A CST 1A FILL VLVOPEN LB 027 COND-V-12B CST 1B FILLVLVOPEN LB 028 COND-V-131 CND-LCV-1ABP VLV0'-1.0 0.0 TO 1.0 029 COND-V-170 CND-I.CV-1C BYP VLV0-1.0 0.0 TO 1.0 030 COND-V-612 CND-LCV-11 BP VLV0-1.0 0.0 TO 1.0 031 COND-FC-11 CND-FCV-11 IN CASCADE 1 of10

032 COND-V-147A FW PMP1A SUCT VLV0-1.0 0.0 TO 1.0 033 COND-V-147 B FW PMP1B SUCT VLV0-1.0 0.0 TO 1.0 034 CW-LCV-1 CIRC WTR BLOWDOWN 0-1.0 OTO I 035 ROD ¹ RMCS ROD BYPASS 1-185 1 TO 185 036 ROD 0-185 1ST ROD ¹ BYPASSED BY RSCS 0 TO 185 037 ROD 0-185 2ND ROD ¹ BYPASSED BY RSCS 0 TO 185 038 ROD 0-185 3RD ROD ¹ BYPASSED BY RSCS 0 TO 185 039 ROD 0-185 4TH ROD ¹ BYPASSED BY RSCS 0 TO 185 040 ROD 0-185 5TH ROD ¹ BYPASSED BY RSCS 0 TO 185 041 ROD 0-185 6IHROD ¹ BYPASSED BYRSCS 0 TO 185 042 ROD 0-185 7TH ROD ¹ BYPASSED BY RSCS 0 TO 185 043 ROD 0-185 8TH ROD ¹ BYPASSED BY RSCS 0 TO 185 044 CRD-FCV-2AlB CRD-FCV-2A LOCALSEL SW 045 CRD-V47A CRD-FCV-2A ISOL VLVOPEN 046 CRD-V-47B CRD-FCV-2B ISOL VLVOPEN LB 047 SCRAM AIR HDR VENT PLUG LB 048 SCRAM AIR HDR ISO VLVV-95 049 CHG LINE ISO VALVEV-34 LB 050 CRD-V-14A CRD-P-1A DIS VLV0-1.0 0.0 TO 1.0 051 CRD-V-14B CRD-P-1B DIS VLV0-1.0 0.0 TO 1.0 052 CRD-V-501 A PURGE SUPPLY TO RWCU-P-1A 053 CRD-V-501 B PURGE SUPPLY TO RWCU-P-1B 054 CRD-FCV-512A PURGE FCV TO RWCU-P-1A 0.0 TO 1.0 055 CRD-FCV-512B PURGE FCV TO RWCU-P-1B 0.0 TO 1.0 056 BUS Sl-l Cl-1 TO Sl-l BKR CLOSED 057 BUS S1-2 Cl-2 TO Sl-2 BKR CLOSED 058 BUS S1-3 Cl-3 TO Sl-3 BKR CLOSED LB 059 BUS SI< Cl-4 TO S1-4 BKR CLOSED 060 BUS S1-7 Cl-7 TO S1-7 BKR CLOSED 061 BUS S2-1 CZ-1 TO S2-1 BKR CLOSED 062 Sl-l GND AN.'IUNRESET LB 063 Sl-2 GND ANNUNRESET 064 S1-3 GND ANNUN RESET 065 SIN GND ANNUNRESET 2of10

066 S2-1 GND ANI'IUNRESET LB 067 HPCS GND ANNUNRESET LB 068 DEH-V-11 DEH OIL CLR SEL HX 1A LB 069 DG1 EXClT SEL DG-1 IN PARIVJ.LEL LB 070 DG2 EXCIT SEL DG-2 IN PARRALLEL 071 DG3 EXCTT SEL DG-3 IN PARRALLEL 072 DG1 DG1 IN MAINTENANCE 073 DG2 DG2 IN MAINTENANCE 074 DGI DG 1 LCKOUTRELAYRESET 075 DG2 DG 2 LCKOUTRELAYRESET 076 DG3 DG 3 LCXOUTRELAY RESET 077 DG-1 IN IDLE 078 DG-2 IN IDLE 079 DG3 DG3 EMERGENCY STOP 080 PP-8A BKR MC4A TO PEA CLOSED 081 SM-1 LOAD ASHE LOAD ON SM-1 0-100AMP 0 TO 100 082 SM-3 LOAD ASHE LOAD ON SM-3 0-100 AMP 0 TO 100 083 MC-7C/TE MC-7C/7E BKR RESET 084 MC4C/SE MC-SC/SE BKR RESEI'DR 085 86/7-DGl 7-DGI O.C. LKOTRESET 086 86/8-DG2 FDR 8-DG2 O.C. LKOTRESET L3 087 KBKR-1-11 BKR 1/11 0/C LKOTRESET 088 BKR-1-7 BKR 1P 0/C CXOT RESET LB 089 BKR-2-21 BKR 2/21 0/C LKOTRESET LB 090 BKR-2A BKR 2/4 0/C LKOTRESET LB 091 BKR-3-31 BKR 3/31 0/C LKOTRESET LB 092 BKR-3-8 BKR 3/8 0/C LKOTRESET LB 093 3KR-7-1 BKR 7/1 0/C LKOTRESET 094 BKR-75-72 BKR 75/72 0/C LKOTRESET L3 095 BKR-7-75 BKR 7P5 0/C LKOTRESET LB 096 BKR-8-3 BKR 8/3 0/C LKOT RESET 097 3KR-85-82 BKR S5/82 0/C LKOTRESET LB 098 3KR-8-85 BKR 8/85 0/C LKOTRESET 099 BKR-B7 BKR B7 0/C LKOTRESET 3 of IO

100 BKR-B8 BKR B8 0/C LKOTRESET 101 BKR-CI'A BKR CI'A 0/C LKOTRESET 102 BKR~ BKR CZB 0/C LKOT RESEI'KR 103 BKR-Nl-1 Nl/1 0/C LKOTRESET 104 BKR-Nl-2 BKR Nl/2 0/C LKOTRESET 105 BKR-Nl-3 BKR Nl/3 0/C LKOTRESET 106 BKR-N2-5 BKR N2/5 0/C LKOTRESET BKR-N24 BKR N2/6 0/C LKOTRESET 108 BKR-Sl BKR Sl 0/C LKOTRESET 109 BERE BKR S2 0/C LKOT RESEEl'KR 110 BKR$3 S3 0/C LKOTRESET BKR-S5 BKR S5 0/C LKOTRESET 112 BKRQ6 BKR S6 0/C LKOT RESEI'RE 113 FIRE PROT LK SYSTEM LEAKAGE0-1E7 0.0 TO 0.0E7 114 HRE PMPS MANSTOP OF ALLFIREPUMPS LB 115 GEN MOD'S MOD 89 STATUS - CLOSED LB 116 GRID FREQ GRID FREQ. 59.9M.I HZ 59.9 TO 60.1 117 GRID VOLT GRID VOLT 450-550KV 450K TO 550 118 GRID BUS SEL BUS SEL NO 2 SO~I NO BUS& 0T02 119 H2%02 H2 SUPPLY VLV52 OPEN 120 IN1-CR3 IN-I, NOR AC BKR CLOSED 121 INl-CBl IN-.IPtOR DC BKR CLOSED IN1-CB5 IN-l, ALTAC BKR CLOSED LB 123 IN1 STAT SW IN1 ST SW I~NOR 2 INV 3~ALT TB 1T03 124 INl KIRKKEY IN-1, KIRKKEY'IO IN-1 LB INZ-CB1 INS NOR DC BKR CLOSED L3 126 IN2 IN-2 INVERTOR TO LOAD LB 127 IN2 IN-2 MANXFER SW IN ALTAC LB 128 IN2 IN-2 ALTAC BKR CLOSED LB 129 IN3-CBl IN3 NOR DC BKR CLOSED LB 130 IN3 IN-3 MANXFER SW IN ALT AC 131 IN3 IN-3 ALTAC BKR CLOSED 132 IN3 IN-3 INVEIGQR TO LOAD 133 LPCSQ15 LPCS D/G TEST SW S15 NORMM.

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LPCS-RX-86 LPCS 86 LOCKOUT RESET LB 135 LPRM 08<ID LPRM BYPASS SW IN BYPASS LB 136 LPRM 2449B LPRM BYPASS SW IN BYPASS LB 137 LPRM 1649C LPRM BYPASS SW IN BYPASS LB 138 LPRM 32-17A LPRM BYPASS SW IN BYPASS LB 139 LPRM 48-17C LPRM BYPASS SW IN BYPASS'PRM LB LPRM 40-17D BYPASS SW IN BYPASS LB 141 LPRM 32-25B LPRM BYPASS SW IN BYPASS LB 142 LPRM 16-25D LPRM BYPASS SW IN BYPASS LB 143 LPRM 40-33B LPRM BYPASS SW IN BYPASS LB 144 LPRM 56-33C LPRM BYPASS SW IN BYPASS LB 145 LPRM 24-33D LPRM BYPASS SW IN BYPASS LB 146 LPRM 40<ID LPRM BYPASS SW IN BYPASS LB 147 LPRM 24-49A LPRM BYPASS SW IN BYPASS LB LPRM 08<9C LPRM BYPASS SW IN BYPASS LB 149 LPRM 16-57A LPRM BYPASS SW IN BYPASS LB 150 AMB TEMP e 45 FI'0-100 FW 0 TO 100 151 MET-TR-1(R) AMBIENTTEMP AT 33 FT 0-100 0 TO 100 152 MEI'-HUMIDITY AMBIENT% REL HUMID 10-95 FW 10 TO 95 153 MET-WDR-4(B) WIND DIR e 245'-540 FW 0 TO 540 154 MEI'-WDRA(R) WIND DIR e 33'-100 FW 0 TO 540 155 MET-WSR~) WIND SPD e 245" 0-100 FW 0 TO 100 156 MET WSR-4(R) WIND SPD e 33'-100 FW 0 TO 100 157 iVIEHWNOISE FLOW INDICATORS/RCDRS 0-100 EW 0.0 TO 100.0 158 MEIZR NOISE PRESS INDICATOR/RCDRS 0-100 EW 0.0 TO 100.0 159 MEIZR NOISE RAD(ARM)INSTRUMEN'ZS 0-100 EW 0.0 TO 100.0 160 VaaER NOISE WIND SPEED RCDR 0-100 0.0 TO 100.0

, 161 MEIER NOISE WIND DIRECTION RCDR 0-100 0.0 TO 100.0 162 METER NOISE SRM PERIOD INDICATORS 0-100 0.0 TO 100.0 163 MEI'ER NOISE SRM COUNT MEHHVRCDRS 0-100 0.0 TO 100.0 164 METER NOISE IRM RECORDERS 0-100 0.0 TO 100.0 165 MEIER NOISE LPRM MEIZRS 0-1'00'"'RP 0.0 TO 100.0 166 iVII'ERNOISE 10 NOISE COYIROL 0-100 0.0 TO 100.0 167 METER NOISE GRP,11 NOISE CONTROL 0-100 0.0 TO 100.0 5of10

169 ME~ NOISE GRP 13 NOISE CONTROL 0-100 0.0 TO 100.0 170 METER NOISE GRP 14 NOISE CONTROL 0-100 0.0 TO 100.0 17I METER NOISE GRP 15 NOISE CORIROL 0-100 0.0 TO 100.0 172 GY-V-99BIRSOA OPFGAS GLY TRN A IN SERV 173 GY-V-99A8NOB OPFGAS GLY TRN B IN SERV 174 OGV90AAIIOA DRYER ~UN A ON LINE 175 OGV90B85110B DRYER TAN B ON LINE 176 OG-V-15A OFFGAS CLR A INLET OPEN 177 OG-V-51B OFFGAS CLR B INLET OPEN 178 OG-V-5IC OFFGAS CLR C INLET OPEN 179 OG-V-51D OFFGAS CLR D INLET OPEN 180 REA-RIS~B DIV2 Z4IG RESET 181 RCC-V-13A CRD-P-IA CLG WTR IN VLV0-1 0.0 TO 1.0 182 RCC-V-79A CRD-P-IA DRF CL OUT VLV0-1 0.0 TO 1.0 183 RCC LKG RCC SYSTEM LKG (0-IE7) 0.0 TO 1.0E7 184 RCC-V-2A RCC-P-IA DIS VLV0-1.0 0.0 TO 1.0 185 RCC-V-2B RCC-P-IB DIS VLV0-1.0 0.0 TO 1.0 186 RCC-V-2C RCC-P-IC DIS VLV0-1.0 0.0 TO 1,0 187 RCC-V-3A RCC-HX-IAIN VLV0-1.0 0.0 TO 1.0 188 RCC-V-3B RCC-HX-IB IN VLV0-1.0 0.0 TO 1.0 189 RCC-V-3C RCC-HX-IC IN VLV0-1.0 0.0 TO 1.0 190 RCC-V-9A FPC-HX-IA IN ISOL 0-1.0 0.0 TO 1.0 191 RCC-V-9B PPC-HX-7B IN ISOL 0-1.0 0.0 TO 1.0 192 RCC-V-10A PPC-HX-IA OUT ISOL VLVOPEN 193 RCC-V-10B PPC-HX-IB OUT ISOL VLVOPEN 194 RCC-V<5A RWCU-P-lA CL WTR IN ISO 0-1 0.0 TO 1.0 195 RCC-V-105A TWCU-P-IA CL WT OUT ISO O-l 0.0 TO 1.0 196 RCC-V&5B RWCU-P-1B CL WTR IN ISO 0-1 0.0 TO 1.0 197 RCC-V~3A RWCU-P-IA CLG WTR OUT V 0.0 TO 1.0 198 RCC-V-643 B RWCU-P-1B CLG WTR OUT V 0.0 TO 1.0 199 RCC-V-8 RWCU HX OUT ISOL'-1.0 0.0 TO 1.0 200 RCIC-V-59 RCIC PLW TST. ISO VLV0-1.0 0.0 TO 1.0 201 RCIC 0/S RCIC OVERSPEED TRIP RESET 202 RHR-VMA RHR-VMABREAKER CLOSED 6of10

203 RHR-VWB RHR-VMB BREAKER CLOSED LB RHR-S70 RHR D/G TEST SW S70 NORMAL LB 205 RHR-V-14A RHR-HX-ASW IN VLV0-1.0 FW 0.0 TO 1.0 206 RHR-V-14B RHR-HX-B SW IN VLV0-1.0 FW 0.0 TO 1.0 RHR-VA RHR-VM MANOPEN TO 25%

RHR-V-71A RHR-P-2A SUC LN DRAIN OPEN 209 RHR-V-72A RHR-P-'2A DISCH LN DRAIN OPE 210 RIVER-LPK COLUMBIARIVLVL20'O 20'O 30'OL 30'3.0 211 RIVER-'IKVP RIVER WTW TEMP 33 TO 80 TO 80.0 212 RPS-MG-A MG-A OUTPUT BKR RESET

~ 213 RPS-MG-B MG-B OUTPUT BKR RESET 214 RPS ALTBKR RPS ALTSUPPLY BKR RESET 215 RPS JUMPER NON-COIN SCRAM JMP REMOVED 216 RWCU-V-103 RWCU-V-103 OPEN 217 RWCU-V-5,13 RWCU-P-1A ISOL VLVS 218 RWCU-V-5,13 RWCU-P-1B ISOL VLVS 219 RWCU-V-266A RWCU-V-266A CONTROL IN AUTO 220 RWCU-V-266B RWCU-V-266B CONTROL IN AVIO RWCU-V-206A RWCU DEMN A INLETVLVOPEN RWCU-V-206B RWCU DEMINB INLETVLVOPEN RWCU-V-266A AUTO FLOW SETFT V266A 0-300 0.0 TO 300.0 RWCU-'V-266B AUTO FLOW'SETFI'266B 0-300 0.0 TO 300.0 RWCU-V-266A MANCONRL VLV266A POS 0-1. 0.0 TO 1.0 RWCU-V-266B MANCNTROL VLV266B POS 0-L 0.0 TO 1.0 RWM SEQUENCE RWM SEQUENCE B SELECTED 228 RRC-P-lA 60HZ PWR L/0 RLY-ARESET 229 RRC-P-18 60HZ PWR L/0 RLY-B RESET 230 LFMG-A LFMG A LKTRELAYRESET LB 231 LFMG-B LFMG B LET RELAYRESET LB 232 RRC-P-lA PWR INTLKKEYSW S118 A 233 RRC-P-1B PWR I%ILKKEY SW S118 B LB U4 RRC-P-lA FW LO FLO KEYSW S119 'A 235 RRC-P-lB FW LO FLO KEYSW S119 B 236 'RRC-P-lA LO DT KEYSW S120 A 7 of 10

RRC-P-IB LO DT KEYSW S120 B TG-HSOP H2 SEAL OIL PUMP ON TG-ASOP AIR SIDE SEAL OIL PMP ON SS<<VP3A SS-PCV-2A BYP VLVSL1 0-1.0 0.0 TO 1.0 241 SS-V-43B SS-PCV-2B BPY VLVSL20-1.0 0.0 TO 1.0 242 SS-V<9A SS-PCVAA BYP VLVSL3 0.0 TO 1.0 0-1.0'S-PCVAB SS-V-49B BYP VLV-SL4 0-1.0 0.0 TO 1.0 SS-V<9C SS-PCV~ BYP VLVSL5 0-1.0 0.0 TO 1.0 SS-VA9D SS-PCVAD BYP VLVSL60-1.0 0.0 TO 1.0 SS-V-49E SS-PCVAE BYP VLVSL7 0-1.0 0.0 TO 1.0 SS-V<9F SS-PCV4F BUP VLV-SL8 0-1.0 0.0 TO 1.0 248 STATOR COOL STATOR CLG DEMIN IN SERVICE LB 249 SCC-P-1A SCC PMP A OFF& SBY~I RUN~2 OTO2 250 SCC-P-IB SCC PMP B OFF=4 SBY~I RUN~2 OTO2 251 SW-V-71A&8 SPRAY POND XOVER A-B CLOSED SW-V-72A&B SPRAY POND XOVER B-A CLOSED SW-V-179A SW-A DISH PIPE DR VLV0-1.0 0.0 TO 1.0 SW-V-179B SW-B DISH PIPE DR VLV0-1.0 0.0 TO 1.0 TMU-POWER TMU-P-IC PWR SEL BUS $2 TiiU-V-5 TMU-LCV-2AISOL VLVOPEN 257 Ti%-V-9 'IlrGJ-LCV-2ABYPASS 0-1.0 FW 0.0 TO 1.0 TMU-V4 TMU S/U LUB WTR SUP VLVOPE LB TSW-V-63A RCC-HX-'lA IN VLV0-1.0 FW 0.0 TO 1.0 260 TSW-V-63B RCC-HX-IB IN VLV0-1.0 FW 0.0 TO 1.0 261 TSW-V<3 C RCC-HX-1C IN VLV0-1.0 FW 0.0 TO 1.0 262 TSW-VM TSW-TCV< BYP 0-1.0 FW 0.0 TO 1.0 263 TSW-V-21 TSW>>TCV4 BYP 0-1.0 FW 0.0 TO 1.0 264 TSW-V-29 TSW-TCV-9 BYP 0-1.0 FW 0.0 TO 1.0 265 TSW-V-10A TSW-TCV-14A BYP 0-1:0 FW 0.0 TO 1.0 266 TSW-V-10B TSW-TCV-14B BYP 0-1.0 0.0 TO 1.0 267 TSW'-F-1A TSW LUBE WTR FLT ON LB 268 TSW-F-1B TSW LUBE WTR FLT ON 269 TSW-F-2A CW LUBE WTR FLT ON 270 TSW-F-2B CW LUBE WTR FLT ON LB S of10

TSW-V-17A MNLO CLRATSW IN ISO 0-1 0.0 TO 1.0 TSW-V-17B MN LO CLR B TSW IN ISO 0-1 0.0 TO 1.0 TSW-V-18A MN LO CLR A TSW OUT ISO 0-1 0.0 TO 1.0 TSW-V-18B MNLO CLR B TSW OUTTSO 0-1 0.0 TO 1,0 TSW-V-94A TSW-F-2A ISOL 0-1.0 0.0 TO 1.0 TSW-V-94B TSW-F-2B ISOL 0-1.0 0.0 TO 1.0 TSW-V-78 TSW RTN ISOL-CW BSN 0-1.0 0.0 TO 1.0 TSW-V-140A RFPT A CLR A TSW OUT 0-1.0 0.0 TO 1.0 TSW-V-140B RFPT A CLR B TSW OUT 0-1.0 0.0 TO 1.0 280 TSW-V-140C RFPT B CLR C TSW OUT 0-1.0 0.0 TO 1.0 281 TSW-V-140D RFPT B CLR D TSW OUT 0-1.0 0.0 TO 1.0 TSW-V-5A RFPT A OIL CLR A TSW IN 0-1 0.0 TO 1.0 TSW-V-5B RFPT A OIL CLR B TSW IN 0-1 0.0 TO 1.0 TSW-V-5C RFPT A OIL CLR C TSW IN 0-1 0.0 TO 1.0 TSW-V-5D RFPT B OIL CLR D TSW IN 0-1 0.0 TO 1.0 TSW-V-13A CAS-HX-2A CL WT IN ISOL 0-1 0.0 TO 1.0 TSW-V-13B CAS-HX-2B CL WT IN ISOL 0-1 0.0 TO 1.0 TSW-V-13C CAS-HX-2C CL WT IN ISOL 0-1 0.0 TO 1.0 TSW-V-15A CAS-HX-2A CL WT OUT ISO 0-1 0,0 TO 1,0 290 TSW-V-15B CAS-HX-2B CL WT OUT ISO 0-1 0.0 TO 1.0 291 TSW-V-15C CAS-HX-2C CL WT OUT ISO 0-1 0.0 TO 1.0 292 TSW-V-110A CAS-C-1A CLG WTR IN BP CLOS 293 TSW-V-110B CASK-IB CLG WTR IN BP CLOS 294 TSW-V-110C CASW-1C CLG WTR IN BP CLOS 295 TSW-V-23A DEH OIL CLR A TSW INL 0-1.0 0.0 TO 1.0 296 TSW-V-23B DEH OIL CLR B TSW INL0-1.0 0.0 TO 1.0 297 TSW-V-24A DEH OIL CLR A OUT VLV0-1.0 0 TO 1.0 298 TSW-V-24B DEH OIL CLR B OUT VLV0-1.0 0.0 TO 1.0 299 TSW-V-25A GEN H2 CLR A TSW INL 0-1.0 0.0 TO 1.0 300 TSW-V-25E GEN H2 CLR A TSW OUT 0-1.0 0.0 TO 1.0 301 TSW-V-38 AIR SIDE S CLR TSW IN 0-1 0.0 TO 1.0 302 TSW-V-39 H2SIDES CLRTSWINO-'1'IR 0.0 TO 1.0 303 TSW-V-40 SIDE S CLR TSW OUT 0-1 0.0 TO 1.0 304 TSW-V&1 H2 SIDE S CLR TSW OUT 0-1 0.0 TO 1.0 9of10

305 TSW-V-42A BUS DCT CLR A TSW IN 0-1 0.0 TO 1,0 306 TSW-V42B BUS DCI'LR B TSW IN 0-1 0.0 TO 1.0 307 TSW-V43A BUS DCI'LR A TSW OUT 0-1 0.0 TO 1.0 308 TSW-V43B BUS DCI'LR B TSW OUT 0-1 0.0 TO 1.0 309 TSW-V-50A STIR WTR CLR A TSW IN 0-1 0.0 TO 1.0 310 TSW-V-50B STIR WTR CLR B TSW IN 0-1" 0.0 TO 1.0 311 TSW-V-51A SITR WTR CLR A TSW OUT 0-1 0.0 TO 1.0 312 TSW-V-51B STTR WTR CLR B TSW OUT 0-1 0.0 TO 1.0 313 TSW-V-104 TSW PIRDJP LUB WTR SUP OPEN 314 TO-V-62A RFPT A LO CLR SEL 2A 315 TO-V-62B RFPT B LO CLR SEL 2C 316 TURB OIL HX MAINTURB OIL CLR SEL HX-1A 317 TO-P-2 TO-P-2 CS IN AUTO 318 HPCS-V-23 HPCS OVERIDE 319 LPCS-V-12 LPCS OVERIDE 320 RHR-V-21 RHR C OVERIDE 321 RHR-V48A RHR A OVEIRIDE LB 322 RHR-V48B RHR B OVEIUDE 323 PPM 5.5:6 MSIVLOW LVLBYPA 324 PPM 59.12 MSIV BYPASS 325 PPM 5.5.12 MS DRAIN BYPASS LB 326 MS-V-20 EMERG OVERIDE FOR MS-V-20 FW 0.0 TO 1.0 327 LD-RMS-S1B TEST SW LB 328 LD-RMS42B 329 LD-RMS-S3C TEST SW 330 LD-RMS<3D TEST SW 331 LD-RMS-S4B 'INST SW 332 LD-RMS-S5B TEST SW I;B'B 333 MM-F20-F17A PULL FUSE CRD-V-9/182 334 CRD-FCV-2A/B MANUALLOADER STATION OMAN LB 335 CRD-FCV-2A/B FCV POSITION FROM MAN LOAD FW 0.0 TO 100.0 10 of.10

0 WNP-2 SiMULATOR CERTIFICATION APPENDIX D SIMULATOR ACCEPTANCE TESTS -1 ANSI/ANSI'.5 (1985) Requirements Versus Simulator Acceptance Test Procedures Attachment D-2 Computer Real-Time Test Abstract Attachment D-3 Normal Plant Evolutions Test Abstracts Attachment DA Steady State Operation Test Abstracts Attachment D-5 Transient Performance Test Abstracts Attachment D-6 Plant Malfunction Test Abstracts

WNP-2 SIMULATOR CERTIFICATION ATTACHMENTD-1 ANSI/ANS-3.5 (1985) REQUIREMENTS VERSUS SIMULATOR ACCEPTANCE TEST PROCEDURES Gen eral Requfrements 3.1 Simulator Capabilltfes 3.1.1 Normal Plant Evolutfons 3.1.1(1) Plant Startup 14.4.7.1 - Normal Plant Operations 3.1.1(2) Nuclear Startup 14.4.72.1 - Startup from Hot Shutdown to Rated Pressure 3.1.1(3) Turbine Startup and Gen Synchronization 14.4.7.1 - Nolmal Plant Operations 3.1.1(4) Reactor SCRAM/Recovery to 1 00/o 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 Operatfons 3.1.1(7) S/U, S/D, Power OPS with 1 Recfrc Pump 14.4.72.4- S/U, S/D, Power OPS with 1 Recfrc Pump 3.1.1(8) Plant S/D from Rated Power to Cold S/D 14.4.7.1 - Normal Plant Operations 3.F 1(9) Core Performance Testfng 14.4.6.1 - Shutdown Margfn 14.4.6.2 - Core Reactivity Coefficient 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, FOR, RRC, MS & RRC Valve Ops 07.04.00.05.13- Reactor Vx & Trip Valve Operability 07.04.00.05.15- CIA Vafve Operability 07.04.00.05.18 - HPCS Service Water Operability/Demo 07.04.01.03.01.01 - Scram Discharge Volume Vent & Drafn Valves Operability 07.04.01.03.01.02- Control Rod Exercise 07.04.01.04.02.01 - RSCS Operability Prior to Start-Up 07.04.03.01.01.22- Manual SCRAM Function Test 07.04.03.06.09 - SDV Bypass Rod Block Page I of 6

07.04.03.07.04.01 - Remote Shutdown Panel Channel Check 07.04.03.08.02.01 - Monthly Turbine Valve Tests 07.04.04.02.01.01 - Safety Relief Valve Acoustic Monitor CC 07.04.04.07- MSIV Closure Test 07.04.05.01.04- LPCI Flow Path Verification 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 - Reactar Building Ventilation Isolation Valve Operability 07.04.06.05.03.01 - Standby Gas Treatment Operability Test 07.04.06.05.03.04- Standby Gas Treatment Manual Initiation Bypass Damper & Heater Test 07.04.07.01.01.02- Standby Service Water Loop B valve PosNon Verification 07.04.07.01.01.03 - HPCS Service Water Valve Position VerNcatlon 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 ¹1 - Operability Test 07.04.08.01.01.02.06 - HPCS Diesel Generator - Loss of Power Test 07.04.08.01.01.02.08 -'PCS Diesel Generator - LOCA Test 07.04.08.01.01.02.11 - Diesel Generator ¹2- Operability Test 07.04.08.01.01.02.12 - HPCS Diesel Generator - Operability Test Plan t Malfunctions 3.1. 2(1) Loss of Coolant 3.1.2(1)(c) Large and Small Reactor Coolant Breaks 14.4.9.18.3 - instrument Une Break (Ref) 14.4.9.18.6 - Instrument Line Break (Var) 3.1.2(1) (d) Failure of Safety and Relief Valves 14.4.9.24.27 - Main Steam Safety Relief Valve Fails Open 14.4.9.25.14 - Sos - Fall Closed 14.4.9.25.14A - SRV-4C Simmering 144;10.10- MSIV ISOL with SRV FO Page2of6

Loss of Instrument Air 14.4.9.4.4- Leak Downstream Control Air Dryer Loss or Degraded Electrical Power 14.4.9.8.3A - 4160 Vac Bus Sm-7 Overcurrent 14.4.9.8.3B - Oveenrent SM-1 14.4.9.8A - S1-2 DC Ground 14.4.9.8.5.- 6900 Vac Bus SHW OL-GND 14.4.9.8.7- Loss of All Offsite Power 14.4.9.8.8 - DG-2 Trfp High Diff. Current 14.4.924.15 - S1-1 DC Ground 14.4.924.15A - S1-1 Trip 14.4.924.18 - RP S B MG Set Trip 14.4.9.24.56 - Battery Charger C1-1 Trip Loss of Forced Coolant Flow Due to Pump Failure 14.4.924.34- Recirculation Pump B Trfp 14.4.10.6- Trip of all Recfrculatlon Pumps Loss af Cond Vacuum/Loss of Cond Lvl Control 14.4.9.22- Condenser Air Leak Loss of Service Wtr or Cooling to Indlv. Comp 14.4.9.24.5- SW Pump A Trfp 14.4.9.24.64- TSW Pump A Trfp 14.4.9.24.64A - TSW Pump B Trfp 14.4.9.25.15- RCC-P-1A - Trip Loss of Shutdown Cooling 14.4.9.24.5- SW Pump A Trip 14.4.9243 - Loss of RHR SDC due to RHR-P-2B Trip Loss of Comp Cooling Sys or Cool to Indlv. Comp 14.4.9.24.5- SW Pump A Trfp 14.4.924.73- SW-V-2B Fails Closed 14.4.9.24.64 - TSW Pump A Trfp 14.4.924.64A - TSW Pump B Trip Loss of Normal Feedwater or System Failure 14.4.9.2.9 - RFPT A Trfp 14.4.9.2.9A - RFPT B Trfp 14,4.9.24.2 - COND-P-2A Trip 14.4.9.24A8A - COND-P-1A Trip Loss of All Feedwater (Nor and Emer) 14;4.10.40- Loss of'Normal and Emergency FW Lass of Protective System Channel 14.4.9.16.4 - HPCS Logic Failure Page 3 of 6

14.4.9.21.1 - ADS Logic Failure 14.4.9.24.78 - ATWS/ARI Failure 14.4.9.24,80- RPS Falls to SCRAM 14.4.924.80A - RPS Fails to SCRAM (AUTO) 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 3.1.2(13) Inability to Drfve Rods 14.4.9.3.6- RDCS Failure 3.1.2(14) Fuel Cladding Failure 14.4.9.7.1 - Small Clad Fail 14.4.9.7.2- Gross Clad Fall 3.1.2(15) Turbine Trip 14.4.9.24.31 - Main Turbine Trip 14.4.9.24.31 A - Main Turbine Trfp From LT 30%

3.1.2(16) Generator Trip 14.4.9.13.1 - Main Generator Trfp 3.1.2(17) Failure ln Auto Cont Sys Affect React/Heat Removal 14.4.9.23.3 - DEH Press Reg. Output FaHure High 14.4.923.3A - DEH Press Reg. Output Fails Low 14.4.9.24.40 - BPV-1 Failure 14.4.9.24.40A - BPV-2 Faf lure 14.4.9.24.40B - BPV-3 Failure 14.4.9.24.40C - BPV-4 Failure 3.1.2(19) Reactor Trfp 14.4.9.24.33 - Manual Scram 3.1.2(20) Main Steamf Inc/Main Feed Une Breaks 14.4.9.2.3 - Feed Une Break in DW 14.4.9.2.8 - FW Rupture in Turbfne Bldg.

14.4.9.21.4A - MS Rupture In DW.

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 ) Nucfear Instrumentation Failures t4.4.9.14.1 - SRM A Failure - Low 14.4.9.14.2 - APRM Failure 14.4.9.14.5 - IRM Failure - Hfgh 14.4.9.14.8 - LPRM Failure - Downscale Page 4 of 6

3.1.2(22) Process Inst, Alarms, Cont Sys Failures 14.4.9.9.4A - RCIC Turbine Trip Due to RCIC-V-8 Closure 14.4.9.9.48 - RCIC Turbine Trip (High Exh. Pressure) 14.4.9.24A3 - Annunciator Failure 14.4.924.678- RFW-L1 4068- Falls Low 14.4.9.24.67C - RFW-L1-6068 Falls High 3.1.2(23) Passive Malf In Sys (ESF, Emer Feedwater) 14.4.9.3.10- Rod Worth Minimizer Fails 14.4.9.9.4C - RCIC Turbine Trip - (Mechanical Overspeed) 14.4.924.37A - HPCS-VA Fails to Open 14.4.9252- RHR-P-28 Shaft Shear 14.4.925.5 - RHR-P-2A Trip 3.1.2(24) Faf lure of Auto Reactor Trip System 14.4.9.3.12- Hydraulfc ATWS 14.4.924.80- RPS Fails to SCRAM 14.4.9.24.80A - RPS Falls to SCRAM (AUTO) 14.4.9'.19- RPS Spurious Scram A 14.4.9.25.20 - RPS Spurfous Scram 8 3.1.2(25) Reactor Press Cont Sys Failure (BWR) 14,4.923.3- DEH Press Reg. Output Failure Hfgh 14.4.9.23.3A - DEH Press Reg, Output Falls Low 14.4.9.24.27- Main Steam Safety Relfef Valve Fails Open 14.4.924AO - BP V-1 Failure 14.4.9.24AOA - BPV-2 Failure 14.4.9.24.408- BPV-3 Failure 14.4.9Z4AOC - BPVA Faf lure 14.4.9.24.63 - DEH Pump 1A Trip 4 Performance Crfteria 4.1 Steady&tate Operation 14.4.4.1 - 100% SS Accuracy 14.4.4.2 - 66% SS Accuracy 14.4.4.3 - 40% SS Accuracy 14.4.5.1 - 100/o Heat Balance 14.4.5.4- 100% Mass Balance Page 5 of 6

APPENDIX A of ANSI/ANS-3,5 Requirements A3.1 Computer Real Time Test 14.5.4 Computer Real-Time APPENDIX 8 of ANSVANS.3,5 Requirements 8.1 BWR Simulator Operability Test 81.1 Steady<tate Performance 81.1(1) Primary Plant 14.4.3.1 - 1 Hour Stability 81.1(2) Secondary Plant 14.4.3.1 - 1 Hour Stability 81.2 Transient Performance 81.2(1) Manual SCRAM 14.4.9.24.33 Manual Scram 81.2(2) Simultaneous Trip of All Feedwater Pumps 14.4.10.5- Simultaneous Trip of All RFP's 81.2(3) Simultaneous Closure of All Main Steam Isolation Valves 14.4.10.3- Closure of All Main Steam Isolation Valves 81.2(4) Simultaneous Trip of All Redrculatlon Pumps 14.4.10.6 - Trip of All Redrculation Pumps 81.2(5) Single Recirculation Pump Trip 14.4.9.24.34- Redrcuiatlon Pump 8 Trip 81.2{6) Main Turbine Trip (No Immediate Reactor SCRAM) 14.4.9.24.31 A - Main Turbine Trip from LT 30%

81.2(7) Maximum Rate Power Ramp (100/~75/~100%)

14.4.8.4- Power Ramp from 100'/o PWR to 75'/o to 100%

81.2{8) DBA LOCA with Loss of All Off-site Power 14.4.10.7 - Maximum Size Reactor Coolant System Rupture w/Loss of Offsite Power 81.2(9) DBA Steamllne Rupture 14.4.10.9 - Maximum Size Insoluble MSL Rupture 81.2(10) Simultaneous Closure of All MSIVs with Single Stuck&pen Safety/Relief Valve (Inhibit High Press ECCS) 14.4.10.10- MSIV ISOL with SRV Failed Open Page 6 of 6

WNP-2 SIMULATOR CERTIFICATION ATTACHMENTD-2 COMPUTER REAL-TiMETEST ABSTRACT

NAL RE TEST CATEGORY: Real Time Test TEST No. 143.4 REV. 0 TITLE: REAL TIME TEST PROCEDURE OVERVIEW.

This test is designed to provide assurance that thc simulator is running with sufhcient spare time that it will perform all model calculations in real time. The measurements are taken while the simulator is in RUN and the models are executing. The amount of time consumed by each processor is measured and checked to see ifthere is any spare time left over. Data is recorded and the totals arc calculated and then compared to the maximum allowed time for each frame.

INI'ITALCONDITIONS: IC-12 100% power FINAL CONDITIONS: 100% power SOURCE OF COMPARISON DATA:

PLANT DATASEI' ENGINEERING EVALUATION FSAR SOER / LER OPERATIONAL ASSESSMENT TEST RESULTS:

Q TEST RESULTS UNSATISFACI'ORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITH DISCREPANCIES Q TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

WNP-2 SIMULATOR CERTIFICATION ATI'ACHMENTD-3 NORMAL PLANT EVOLUTION TEST ABSTRACTS

0 N RE TEST CATEGORY: iVotmal Operations TEST No. 14.4.6.1 REV. 0 TITLE: CORE PERFORMANCE 7ZSTS - CORE ZEACTIVIZT 0VERVQ.W:

This test was performed to verify simulator response demonstrate the capability to determine the shutdown margin of the reactor core, provide a method of checking for possible reactivity anoma-lies as the core reactivity changes with exposure per Technical Speci6cation 4.1.2 while in mode 1 and to compare simulator performance against reference plant data in order to detezmine acceptable accuracy in computing the critical point. The three evaluations described above were tested and ver-i6ed.

K'ITALCONDITIONS: IC-2 Ready for startup; IC -12 100% Power with Etluilbrium Xenon FINALCONDITIONS: N/A I

SOURCE OF COMPARISON DATA:

g PLANT DATA CY4PPM7411 EVALUATION SEI':ENOINEIEUNO FSAR STATEPOINTS SUER / LER g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACI'ORY WITH DISCREPANCIES H TEST RESULTS SATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Normal Operations TEST No. 14.4.6.2 REV. 0 TITLE: CORE PERFORMANCE TESTS - CORE REACTlVITTCOEFFICIENTS TEST OVERVIEW.

This test was performed to demonstrate that the moderator temperature, void and fuel temperature (doppler) reactivity coefEcients approximate reference plant coefBcients in order of magnitude. The magnitutdhs for the reactivity coefBcients were tested and veri6ed.

INI;ITALCONDITIONS: IC-2 Ready for startup FINAL CONDITIONS: N/A SOURCE OF COMPARISON DATA:

g PLANT DATASET CY4 CRPATTEIW ENOINIEEUNO EVALUATION ANF PERIOD C FSAR TIVI'IVDATA SOER/LER CY4SAOLETREP I OPERATIONAL ASSESSMENT TEST RESULTS:

Q TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES QX TEST RESULTS SATISFACTORY WITH DISCREPANCIES Q TEST RESULTS SATISFACI'ORY WITHOUTDISCREPANCIES

TEST CATEGORY: Normal Operations TEST No. 14.4.63 REV. 0 TITLE: CORE PERI'ORKhYCE TESTS - SRM/IRM REPONSE TO CONTROL ROD MOTION TEST OVERVIEW:

This test was performed to demonstrate the proper SRM/IRM response to control rod motion. The SRM's and IRM's adjacent to control rods being withdrawn are verifled to respond more dramatically than they do when other control rods are withdrawn. The SRM response includes a veriflcation 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 were tested and verified.

INI'ITALCONDITIONS: IC-3 Startup in progress approaching criticality.

FINAL CONDITIONS: N/A SOURCE OF COMPARISON DATA:

Q PLANT DATA EVALUATIONI SEI'NGINEEIUNG FSAR SUER/LER g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACI'ORY WITHOUTDISCREPANCIES

TEST CATEGORY: Normal Operations TEST No. 14.4.7.1 REV. 0 TITLE: NORMALPLANT OPEK4TIONS OVERVIEW:

This test was performed to very simulator response to a shutdown ftom rated power conditions to CSD and subsequent startup to rated conditions. The applicable steps of PPM 3.2.1P'ormal SD to CSD (Attachment A), PPM 3.1.2 Reactor Plant Cold Startup (Attachment 8) and PPM 7.4.4.6.1.1, HU/CD Log (Attachment C) were completed. AQ applicable steps for PPM 3.2.1 Notmal 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.

INDI'IALCONDITIONS: IC-12 100% Power Equilibrium Xenon, FINAL CONDITIONS: 100% Power Xenon Concentration Incteasing to Equilibrium SOURCE OF COMPARISON DATA:

X PLANT DATASEI' PLANTSD DATASET SHUTDOWN.DOC ENGINEERING EVALUATION FSAR SOER / LER SU99109.DOC g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES H TEST RESULTS SATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Normal Operations TEST No. 14.4.7.2.1 REV. 0 TITLE: PLANT OPERATION TESTS - STARTUP FROM O'OT SHUTDOWN TO RATED PRES-SURE OVERVII.:W:

This test was performed to verify simulator response to a startup from the HSD condition at 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> after the initial SCR,QvI from rated power conditions with equiTibrium Xenon present. The applicable steps of PPM 3.1.3, SU from HSD (Attachment E, 7.5.1) and PPM 7.4.4.6.1.1, HU/CD Log (Attachment E, 7.52) were completed.

INZIIALCONDITIONS: IC 0% Power Ready for Startup FINAL CONDITIONS: Reactor Critical, RPV/P Control via MT bypass valves, at Rated Pressure SOURCE OF COMPARISON DATA:

PLANT DATA SET ENGINEERING EVALUATION FSAR S DER I LEE g OPERATIONAL ASSESSMENT TEST RESULTS'EST RESULTS UNSATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACIORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Normal Operations TEST No. 14.4.7.2.3 REV. 0 T1TLE'LANTOPERATION TESTS - SD FROM RATED RPVIP TO HSD 0VERVII:7It'his test was performed to verify the minimum evolutions that the simulator shall be capable of performing, usmg only operator action normal to the ref'erence plant for operations at hot standby.

The applicable steps of PPM 3.2.2, SD to HSD (Attachment A) and PPM 7.4.4.6.1.1 (Attachment B) were completed.

INI'ITALCONDITIONS: IC-14, Shutdown in progress, e14% Power.

FINAL CONDITIONS: Reactor is Shutdown and Plant is in Hot Shutdown.

SOURCE OF COMPARISON DATA:

g PLANT DATA ce td wn Data SEI'NGINEERING EVALUATION FSAR

[7 SOER ( LER g OPERATIONAL ASSESSMEKI' TEST RESULTS:

TESI'ESULTS UNSATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITHOUTDISCREPANCIES

TEST CATEGORY: Normal Operations TEST No. 14.4.7.2A REV. 0 TITLE: STriRTUPp SHUTDOWN AND POWER OPER4TIONS WITE ONE RRC PUMP OVERVIEW'his test was pexformed to verify simulator response to a shutdown from rated power conditions to Single RRC Loop conditions, to CSD and subsequent startup to rated conditions for Single Loop Operations. The applicable steps of PPM 3.2.1Ptormal SD'o CSD (Attachment A), PPM 3.1.2 Reactor Plant Cold Startup (Attachment B), PPM 7.4.4.6.1.1, HU/CD Log (Attachment C), and PPM 2.2.1 RRC System Ops were completed. All applicable steps for PPM 3.2.1 Normal SD to CSD, PPM 3.1.2 Reactor Plant Cold Startup, PPM 2.2.1 RRC System Ops and PPM 7.4.4.6.1.1 HU/CD Log were tested and veri6ecL INITIALCONDITIONS: lC-12 100% Power Equilibrium Xenon FINALCONDITIONS: 60% Power Xenon Concentration Increasing to Equilibrium SOURCE OF COMPARISON DATA:

g PLANT DATA PLANTSD DATASEI'HUTDOWN.DOC SEI'NGINEIEUNG EVALUATION STARTUP.DOC Q

Q SOERI LEE SU99109.DOC g OPERATIONAL ASSESSMENT PAT30B TEST RESULTS:

TEST RESULTS UNSATISFACI'ORY WITH DISCREPANCIES H TESI'RESULTS.SATISFACTORY WITH DISCREPANCES Q TEST RESULTS SATISFACIORY WITHOUT DISCREPANCIES

TEST CATEGORY: Normal Operations TEST No. 07.04.00.05.06 REV. 0 TTILE: EDR, FDRP RRC, MS & RCC VALVEOPERABIL11Y OVERVIEW:

This test was performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures. Proper valve stroking 8h timing were tested and verified.

INTIVALCONDITIONS: In accordance with the testing requirements of the specific Suxveillance.

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

SOURCE OF COMPARISON DATA:

PLANT DATASEr g ENGINEEIUNG EVALUATION FSAR SUER/LER OPERATIONALASSESSMENT TEST RESULTS:

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

TEST CATEGORY: Normal Operations TEST No. 07.04.00.05.13 REV. 0 PI-VX & TIP VALVEOPERABILITY OVERVII.:W:

This test was performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures. Proper valve strolling 8h timing were tested aud verified.

INI'IDEALCONDITIONS: In accordance with the testing requirements of the specific Surveillance.

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

SOURCE OF COMPARISON DATA:

PLANT DATA SEI' ENGINEERING EVALUATION FSAR SOER/LER OPERATIONALASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS. SATISFACTORY WITH DISCREPANCIES H TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Normal Operations TEST No. 07.04.00.05.15 REV. 0 TITLE: CIA VALVEOPERABILITY OVERVIEW:

This test was performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures. Proper valve stroking R timing weze tested and verified.

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

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

SOURCE OF COMPARISON DATA:

PLANT DATASET g ENGINEERING EVALUATION FSAR Q SUER HLER Q OPERATIONAL ASSESSMENT TEST RESULTS:

[g TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES Q TEST RESULTS SATISFACI'ORY WITH DISCREPAiVCKS Q TEST RESULTS SATISFACTORY WITHOUTDISCREPANCIES

TEST CATEGORY: Normal Operations TEST No. 07.04.00.05.18 REV. 0 TITLE: HPCS SERVICE WATER OPER4BILITYDEMONSTRATION 0VERVII:W:

This test was performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures. Proper valve stroking 8h timing weze tested and verified.

The systems capabilities weze verifie for delivery of required cooling to system loads. Valve stroke timing was taken to verify valve operabBity. Proper system fiow balance was verified.

INDIIALCONDITIONS: In accordance with the testing requirements of the specific SurveiHance.

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

SOURCE OP COMPARISON DATA:

Q PLANT DATASEI' ENGINEERING EVALUATION Q FSAR SOER/LER

'PERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITH DISCREPANCIES Q TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

PERA N TEST CATEGORY: Normal Operations TEST No. 07.04.01.03.01.01 REV. 0 TITLE: SC2tVf DISCHARGE VOLUME VENT'c DRAIN VALVEOPERABII I1Y This test was performed to demonstrate Simulator System OperabiTity in accordance with approved Plant Surveillance Procedures. Proper valve stroking 8h timing were tested and verified.

INDIIALCONDITIONS: 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:

Q PLANT DATASET g ENGINEIBUNG EVALUATION Q FSAR SUER / LER OPERATIONAL ASSESSMENT TEST RESULTS:

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

TEST CATEGORY: Normal Operations TEST No. 07.04.01.03.01.02 REV. 0

'ITIVE: COhTROL ROD EXERCISE 0VERVIPV This test was performed to demonstrate Simulator System OperabiTity in accordance with approved Plant Surveillance Procedures. Proper valve stroking 8c timing were tested and verified.

INI'IIALCONDITIONS: In accordance with the testing reqttirements of the specific Surveillance.

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

SOURCE OF COMPARISON DATA:

PLANT DATA SEI' ENGINEEIUNG EVALUATION FSAR SOER / LER OPERATIONAL ASSESSMIB1T TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES Q TEST RESULTS SATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Normal Operations TEST No. 07.04.01.04.02.01 REV. 0 TITLE: RSCS OPERABILlTY PRIOR TO STARTUP 0VERVII:W:

This test was performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures. RSCS Operability demonstration performed to ensure proper rod sequence adherence enforced.

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

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

SOURCE OF COMPARISON DATA:

PLANT DATASEI' ENGINEERING EVALUATION FSAR SUER/LER OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPAiVCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Normal Operations TEST No. 07.04.03.01.01.22 REV. 0 TITLE: MANUALSCRAM FUNCTIONALTEST OVERVIEW:

This test was performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures. Proper valve stroking 4 timing were tested and veri6ed.

This stroking of all turbine steam valves was conducted to verify valve operability.

INITIALCONDITIONS: Plant operating at 80% power or less.

HNALCONDITIONS: Plant operating at 80% power or less.

SOURCE OF COMPARISON DATA:

PLANT DATA SET g ENGINEERING EVALUAHON FSAR SOER / LER OPERATIONAL ASSESS~iNT TEST RESULTS:

TESI'ESULTS UNSATISFACTORY WITH DISCREPANCIES Q TEST RESULTS SATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

N RE TEST CATEGORY: Normal Operations TEST No, 07.04.03.06.09 REV. 0 TITLE: SDV BYPASS ROD BLOCK 0VERVII:W:

This test was performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures. The SDV Bypasss switches functionality was veri6ed.

This stroking of all turbine steam valves was conducted to verif'y valve operability.

INZIIALCONDITIONS: Plant operating at 80% power or less.

FINALCONDITIONS: Plant operating at 80% power or less.

SOURCE OF COMPARISON DATA:

PLANT DATASEI' ENGINEERING EVALUATION'SAR SUER / LER OPERATIONAL ASSESS~iNT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Normal Operations TEST No. 07.04.03.07.04.01 REV. 0 TITLE: RE>MOTE SHUTDOR'LV PANEL CEKAÃlVELCBECZ OVERVH..W:

This test was performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures. The RSDP instrumentation was veri6ed.

This strolling of all turbine steam valves was conducted to verify valve operability.

INMXALCONDITIONS: Plant operating at 80% power or less.

FINALCONDITIONS: Plant operating at 80% power or less.

SOURCE OF COMPARISON DATA:

PLANT DATASEI' ENGINEEIUNG EVALUATION FSAR SUER / LER OPERATIONAL ASSESSMENT TEST RESULTS:

TESI'ESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACI'QRY WITH DISCREPANCIES g TEST RESULTS SATISFACI'ORY WITHOUT DISCREPANCIES

N TEST CATEGORY: Normal Operations TEST No. 07.04.03.08.02.01 REV. 0

'ITTLE: MONTHLYTURBINE VALVETEST OVERVII.:W:

This test was performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures.Proper valve stroktng 4 timing were tested and veri6etL This stroking of all turbine steam valves was conducted to verify valve operability.

INEQUAL CONDITIONS: Plant operating at 80% power or less.

FINAL CONDITIONS: Plant operating at 80% power or less.

SOURCE OF COMPARISON DATA:

PLANT DATASET g ENGINEEIUNG EVALUAUON FSAR SUER / LER OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSAUSFACTORY WITH DISCREPMVCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUTDISCREPANCIES

TEST CATEGORY: Normal Operations TEST No. 07.04.04.02.01.01 REV. 0

'IITLE: SRV ACOUSTIC MON1TOR CHAHNZI, CHECE 0VERVH.:%:

This test was performed to demonstrate Simulator System OperabBity in accordance with approved Plant Surveillance Procedures. Proper valve strolang & timing were tested and verified.

Each SRV was operated to verify the detection capability of the tail pipe tetnperature monitoring and accoustlc moQltormg systems.

INFIXALCONDITIONS: Plant Operation at GT 25% power.

FINAL CONDITIONS: Plant Operation at GT 25% power.

SOURCE OF COMPARISON DATA:

PLANT DATA SET g ENGINEEIUNG EVALUATION

[7 FSAR SOER / LER OPERATIONAL ASSESSiiIENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUTDISCREPANCIES

TEST CATEGORY: Normal Operations TEST No. 07.04.04.07 REV. 0 THI.E: MSIVCLOSURE TEST 0VERVIIDV; 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.

Fast closure stroke times are tested and validated against timing requirements.

INZIIALCONDITIONS: Plant operating at power LE 80%.

FINAL CONDITIONS: Plant operating at power LE 809o.

SOURCE OF COMPARISON DATA:

PLANT DATA SEI' ENGINEERING EVALUATION

[7 F SAR Q SOER I LER

[7 OPERATIONAL ASSESSMENr TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPAiVCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TI AL VH:Vf TEST CATEGORY: Normal Operations TEST No. 07.04.05.01.04 REV. 0 TITLE: LPCI FLOW PATE VFREFICATION 0VERVIIPR This test was performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures. Proper valve stroking 8h timing were tested and vexi6etL RHR Bow testing for various modes of system operation is tested. Valve stroke timing and operabil-ity for key parameters was tested.

INZITALCONDZIIONS:

FINAL CONDITIONS:

SOURCE OF COMPARISON DATA:

PLANT DATA SEI' 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

TEST CATEGORY: Normal Operations TEST No. 07.04.05.01.05 REV. 0 TITLE: LPCS VALVELPfZUP /ADS INHIBITCFT 0VERVIE%;

This test was performed to demonstrate Simulator System OperabiTity in accordance with approved Plant Surveillance Procedures. Proper valve stroking 8h timing were tested and verified.

LPCS full Bow testing, valve stmke timing, and operabiTity for key parameters was tested.

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

PLANT DATA SET Q ENGINEEIUNG EVALUATION FSAR SUER / LER OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES .

g TEST RESULTS SATISFACI'ORY WITHOUT DISCREPANCIES

TEST CATEGORY: Normal Operations 'INST No. 07.04.05.01.06 REV. 0 TTILE: &PCS VALVELINEUP OVERVIE7It'his test was performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedutes. Proper valve strolang 4 timing were tested and verified.

HPCS full Bow testing is performed. Valve stroke timimg and operability for key parameters was tested.

IPG'TIAL CONDZIIONS: N / A FINAL CONDITIONS: N/A SOURCE OF COMPARISON DATA:

PLANT DATA SEI' ENGINEERING EVALUATION FSAR SOERI LER OPERATIONAL ASSESSMENT TEST RESULTS:

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

TEST CATEGORY: Normal Operations TEST No. 07.04.05.01.11 REV. 0 TELE: HPCS SYSTEM OPER4BIL1TF TEST OVERVIEW:

This test was performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures. Proper valve stroking 4 timing were tested and veri6ed.

HPCS full Qow testing is performed. Valve stroke timimg and operability for key parameters was tested.

INITIALCONDITIONS: IC-12 100% power, equilibezium Xenon FINAL CONDITIONS: IC-12 100% power, equiliberium Xenon SOURCE OF COMPARISON DATA:

Q PLANT DATASET g ENGINEERING EVALUATION FSAR Q SOER.I LEE Q OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES

[g TEST RESULTS SATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Normal Operations TEST No. 07.04.06.01.04.02A REV. 0 TITLE: MSIV VALVEQUARTERIP OPER4BILITF SURVEILLAiYCE 0VERVll:W:

This test was performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures. Proper valve stroking & timing were tested and vexi6ed.

MSIV leakage control is tested to insure its capability for processing leakage past the valve discs.

INlTIALCONDITIONS: Plant shutdown and depressurized.

FlNAL CONDITIONS: Plant shutdown and depressurized.

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 SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Normal Operations TEST No. 07.04.06.02.02.01 REV. 0 TITLE: RPR SYSTEM VALVEPOSITION VERII'ICATION OVERVIE%:

This test was performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Pmcedures. Proper valve stroking & timing were tested and verilied.

RHR Bow testing for various modes of system operation is tested. Valve stroke timing and operabil-ity for key parameters was tested.

INH~ CONDITIONS: N/A FINALCONDZITONS: N /A SOURCE OF COMPARISON DATA:

Q PLANT DATA SET g ENGINEERING EVALUATION Q

SOER / LER Q OPERATIONAL ASSESSMENT TEST RESULTS:

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

NAL TEST CATEGORY: Normal Operations TEST No. 07.04.06.03.03 REV. 0 TITLE: CSP <<k CEP CONTAIlVMEhTISOLATIONVALVEOPERABILlTP OVERVQ W:

This test was performed to demonstrate Simulator System Operability in accordance with approved Plant SurveQlance Procedures. Proper valve strolang 4 timing were tested and verifie.

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

I LANTDATASET g ENGINEIEUNG'EVALUATION SOER / LER OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES

[g TEST RESULTS SATISFACI'ORY WITH DISCREPANCIES 0 TEST RESULTS SATISFACTORY WITHOUT DISCREPANCES

TEST CATEGORY: Normal Operations TEST No. 07.04.06.04.01.02 REV. 0 TITLE: SUPRESSION CHAMBER DRY WELL VACUUMBRE/iZER OPERABILITY OVERVIEW:

This test was performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures. Proper valve stroking 8'c timing werc tested and veri6ed.

INITIALCONDITIONS: In accordance with the testing requirements of the speci6c SurveB1ance FINAL CONDITIONS: In accordance with the testing requirements of the speci6c Surveillance SOURCE OF COMPARISON DATA:

[7 PLANT DATA SET g ENGINEERING EVALUATION FSAR SOER / LER OPERATIONAL ASSESSiiENT TEST RESULTS:

TEST RESULTS UNSATISFACI'ORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUTDISCREPANCIES

TEST CATEGORY: Normal Operations TEST No. 07.04.06.05.02.01 'EV. 0 TITLE: REACTOR BUILDINGISOLATIONVALVEOPERABILITY OVERVIIVV:

This test was pczfozmed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures. Proper valve stroking & timing were tested and veriGetL Valve operability and stroke times werc checked and ved6ed to meet procedure requirements.

INFIXALCONDITIONS: Minimize time that the RB HVAC is out of sezvice to prelude system isolations on high temperature.

FINALCONDITIONS: Miznmizc time that the RB HVAC is out of service to prelude system isolations on high temperature.

SOURCE OF COMPARISON DATA:

PLANT DATA SEI' ENGINEERING EVALUATION FSAR

[7 SOER I LEE OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES

[g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Normal Operations TEST No. 07.04.06.05.03.01 REV. 0 TITLE: STANDBYGAS TRTEATMENTSYSTEM% OPER4BLLIZY TZST OVERVIEW:

This test was performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures. Proper valve stroking 4 timing were tested and verified.

Valve operability and stroke times were cheched and veri6ed to meet procedure requirements.

INZIIALCONDITIONS: Does not impact other plant systems.

FINALCONDITIONS: System has capacity to meet procedure requirements for a pmlonged period of time.

SOURCE OF COMPARISON DATA:

PLANT DATA SET g ENGINEERING EVALUATION FSAR

[7 SOERI LEE OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS IINSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACI'ORY WITHOUTDISCREPANCIES

TEST CATEGORY: Normal Operations TEST No. 07.04.06.05.03.04 REV. 0 TIII.E: STANDBY GAS TZK4TMENTSYSTEM I MANUALIN1TIATION,BYPASS DAMPER & HEATER TEST OVERVIEW'his test was performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures. Proper valve stmking 8c timing were tested and verified.

Valve operability and stroke times were checked and verifie to meet procedure requirements.

INITIALCONDITIONS: Does not impact other plant systems.

FINAL CONDITIONS: System has capacity to meet procedure requirements for a prolonged period of time.

SOURCE OF COMPARISON DATA:

PLANT DATA SEI'g ENGINEERING EVALUASTON FSAR SUER/LER Q OPERATIONAL ASSESSMENT TEST RESULTS:

[7 TEST RESULTS UNSATISFACI'ORY, WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACI'ORY WITHOUTDISCREPANCIES

TEST CATEGORY: Normal Operations TEST No. 07.04.07.01.01.02 REV. 0 TITLE: STANDBYSERVICE HATER I.OOP B VALVEPOSITION VERIFICATION

'VERVII:W:

This test was performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Pmcedures. Pmper valve stroking & timing were tested and verified.

Thc systems capabilities were verified for delivery of required cooling to system loads. Valve stroke timing was taken to verify operability. Proper system Qow balance was verified.

4 INHTALCONDITIONS: N /A FINAL CONDrrrONS: N/A SOURCE OF COMPARISON DATA:,

PLANI DATASET g ENGINEERING EVALUATION FSAR SUER HLER OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACI'ORY WITH DISCREPANCIES

[g TEST RESULTS SATISFACI'ORY WITHOUT DISCREPANCIES

0 TEST CATEGORY: Nozma1 Operations TEST No. 07.04.07.01.01.03 REV. 0 TITLE: HPCS SERVICE WATER VALVEPOSITION VERLFICATiON OVERVIEW This test was performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures. Proper valve stroking 8h timing were tested and vezified.

The systems capabilities weze vezified for delivery of required cooling to system loads. Valve stroke timing was taken to verif'y operability. Proper system fiow balance was verified.

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

PLANT DATASET g ENGINEERING EVALUATION FSAR SOER HLER OFERAIIONALASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES

[g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Normal Operations TEST No. 07.04.07.09.01 REV. 0 TITLE: WEEZLYBY PASS FAJ'ZS TEST OVERVIEW:

This test was performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures. Proper valve stroking 8h timing were tested and veri6ed.

This stroking of all turbine steam valves was conducted to verify valve operability.

INI'ITALCONDITIONS: Plant operating at 809o power or less FINALCONDI7IONS: Plant operating at 80%%uo power or less SOURCE OF COMPARISON DATA:

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

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFA'CTORY WITH DISCREPANCIES g TEST RESULTS SATISFACI'ORY WITHOUT DISCREPANCIES

TEST CATEGORY: Normal Operations TEST No. 07.04.08.01.01.01.02 ~ 0 TITLE: l8 MONTHMANUAL& AUTO TR4NSFER TEST/ STARTUP TO BACZUP STA17ON POWER OVERVIEW This test was performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures. Proper valve stroking 88 timing werc tested and verified.

Breaker alignments were checked and vcrified for a normal station lineup and auto power seeking transfer tests werc conducted to verify correct operability.

INITIALCONDITIONS: N/A FINAL CONDITIONS; N/A SOURCE OF COMPARISON DATA:

PLANT DATASEI' ENGINEEIUNG'EVALUATION

'SAR SOER / LER OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCES TEST RESULTS SATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Normal Operations TEST No. 07.04.08.01.01.02.01 REV. 0

'ITTLE: DG-l MONTHLY0PERABLUTY 0 VERVET."W:

This test was performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures. Proper valve stroking & timing were tested and verified.

This test verifies the load carrying capability of the Diesel Generator.

INI'I1ALCONDITIONS: N/A FINAL CONDITIONS: iV/A SOURCE OF COMPARISON DATA:

PLANT DATA SET g ENGINEERING EVALUATION FSAR SUER HLER OPERATIONAL ASSESSMENT TEST RESULTS:

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

TEST CATEGORY: Normal Operations 'TEST No. 07.04.08.01.01.02.06 REV 0 TITLE'PCS DIESEI. GEiVERATOR - LOSS OF POWER TEST 0VERVGVV:

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 required the diesel to auto start, come up to speed and voltage auto close onto the respec-tive bus, with a prescribe time, with nnuimum specified drop in voltage and frequency.

INZITALCONDITIONS: N/A HNAL CONDITIONS: N/A SOURCE OF COMPARISON DATA:

PLANT DATA SET g ENGINEEKNG EVALUATION FSAR SOER/LER OPERATIONAL ASSESS'iiIENT THST RESULTS:

TEST RESULTS UNSATISFACI'ORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

N TEST CATEGORY: Normal Operations TEST No. 07.04.08.01.01.02.08 REV 0 TTI'LE: HPCS DIESEL GENER4TOR LOCA TEST OVERVIEW'his test was performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures. Proper valve stzohng dh timmg were tcstcd and veri6ed.

This test demonstrates the DG's ability to auto start, come up to speed and voltage, auto dose onto the bus and energize loads within thc prescribed limits of time, frequency and voltage.

I>KIIALCONDITIONS: N/A FINALCONDITIONS: N/A SOURCE OF COMPARISON DATA:

PLANT DATA SET g ENGINEIEUNG EVALUATION Q

SUER/LER OPERATIONAL ASSESSMIPlT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Normal Operations TEST No. 07.04.08.01.01.02.011 REV. 0 TRIKE: DG-2 MOiVTFLYOPER4B1L/TY OVERVIEW:

This test was performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures. Proper valve stroking 8h timing were tested and veri6ed.

This test veri6es the load carrying capability of the Diesel Generator.

INTEL CONDITIONS: N/A FINAL CONDITIONS: N/A SOURCE GF COMPARISON DATA:

[7 PLANTDATASET g ENGINEERING EVALUATION FSAR SOER/LER OPERATIONAL ASSESSmNT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Normal Operations TEST No. 07.04.08.01.01.02.012 REV. 0 TITLE: HPCS DIESEL GENERATOR MONTHLYOPERABILQT'EST OVERVIEW:

This test was performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures. Proper valve stroldng 8h timing were tested and verified.

This test verifies the load carrying capability of the Diesel Generator.

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

PLANT DATASEI' ENGINEEIUNG EVALUATION FSAR SUER / LER OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES 4

TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

WNP-2 SIMUIATOR CERTIFICATION ATTACHMENTD-4 STEADY STATE OPERATION TEST ABSTRACTS

Yj: N REVIEWS TEST CATEGORY: Steady State Operation TEST No. 14.4.4.1 REV. 0 TITLE: STEADFNTATE ACCURACT 1ZSTS -100 PERCENT POWZR AND FLOW, EQ XE OVERVIEW:,

'Ibis test was performed to verify that the computed values of simulated plant parameters at 100 percent power, Eqmlibrium Xenon correspond to plant p'arameters, to within the accu-racy requirements of ANSIJ'ANS-33-1985, Nuclear Power Plant Simulators for use in Operator Training. Simulator was run for one hour and then data was taken. Critical Param-eters monitored included but were not limited to the following categories: RPV LEVEL's, APRM PWR's, GENERATOR LOAD, MN TURB 1ST STAGE PRESS, S'IEAM FLOW's, FEED FLOW's, RPV PRESS's, CORE FLOW's, RECIRC LOOP FLOW's, DRYWELL PRESS's, DRYWALL 'IEMP's, SUPPRESSION POOL LVL's, SUPPRES-SION POOL TEMP's, CONDENSER VACUUM's, MAIN TURB GOV VLV POS's,

%VAN TK& SPEED, RFP SPEED's, RFP PRESS's, and as listed. Values were within specifications or identified for correction.

INEQUAL CONDITIONS: IC-12 100% Power with Equilibrium Xenon FINAL CONDITIONS: IC-12 1009o Power with Equilibrium Xenon SOURCE OF COMPARISON DATA:

100 PWR Jan 22 g PLANT DATA 1 WRJ SEI'NGINEERING EVALUATION FSAR g SOERiLER g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Steady State Operation TEST No. 14.4.4.2 REV. 0 TITLE: STEADY-STATE ACCURACY TESTS - 66 PERCENT POWER OVERVIEW:

This test was performed to verify that the computed values of simulated plant parameters at 66 percent power, correspond to plant parameters, to within the accuracy retirements of ANSI/ANS-3.5-1985, Nuclear Power Plant Simulators for use in Operator Training.

Simulator power was reduced to 66% allowed to run for one hour and then data was taken.

Critical Parameters monitored included but were not limited to the following categories:

RPV LEVEL's, APRM PWR's, GENEIVZOR LOAD, MNTURB'IST STAGE PRESS, STEAM FLOW's, FEED FLOW's, RPV PRESS's, CORE FLOW's, RECIRC LOOP FLOW's, DRYWELL PRESS's, DRYWELL 'IEMP's, SUPPRESSION POOL LVL's, SUPPRESSION POOL TEMP's, CONDENSER VACUUM's, AUD TURB GOV VLV POS's, hQQN TURB SPEED, RFP SPEED's, RFP PRESS's, and others as listed. Values were within specifications or identified for correction.

INI~CONDITIONS: IC-12, Adjusted power to 66~o.

FINALCONDITIONS: 66% Power SOURCE OF COMPARISON DATA:

g PLANT DATA SEI'NGINEERING EVALUATION FSAR Q SUER/LER g OPERATIONAL ASSESSMENT TEST RESULTS:

Q TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITH DISCREPANCIES Q TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Steady State Operation TEST No. 14.4.4.3 REV. 0 TITLE: STK4DP-STATE ACCURACY TESTS AO PERCENT POWER OVERVIEW This test was performed to verify that the computed values of simulated plant parameters at 40 percent power, correspond to plant parameters, to within the accuracy requirements of ANSI/ANS-35-1985, Nuclear Power Plant Simulators for use in Operator Training.

Simulator was allowed to run for one hour and then data was taken. Critical Parameters monitored included but were not limited to the following categories: RPV LEVEL's, APRM PWR's, GENERATOR LOAD, MN TURB 1ST STAGE PRESS, STEAM FLOW's, FEED FLOW's, RPV PRESS's, CORE FLOW's, RECIRC LOOP FLOW's, DRYWELL PRESS's, DRYWELL TEMP's, SUPPRESSION POOL LVL's, SUP-PRESSION POOL TEMP's, CONDENSER VACUUM's, hVdN TURB GOV VLV POS's, MAINTURB SPEED, RFP SPEED's, RFP PRESS's, and others as listed. Val-ues were within speci6cations or identified for correction.

INITIALCONDITIONS: IC-9 40% Power FINAL CONDITIONS: 40% Power SOURCE OF COMPARISON DATA:

g PLANT DATASET 40 PWR A r 20 ENGINEEIUNG EVALUATION FSAR SOER / LER g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Steady State Operation TEST No. 14.4.5.1 REV. 0 TITLE: HEATArVDrVVSS BAJANCE TESTS -100 PERCE1VT POWER HEAT BALANCE OVERVH:W:

This test was performed to verify that the principal mass and energy balances are satis6ed as required by ANSIJ'ANS-33.-1985, Nuclear Power Plant Simulators for Use in Operator Training. Simulator was run for at least thirty minutes and then data was taken. Data was collected and recorded for Attachment A, 100% Heat Balance Control Board Data, and for Attachment B, 100% Heat Balance Computer Point Data Calculations were performed as indicated in Attachments CQg, and F. Data was evaluated against the Acceptance Criteria of section 5.0, as applicable.

NOTE 'IMs test should be run with 100% Steady-State Accuracy Test, 14.4.4.1.

INI'GALCONDITIONS: IC-12 100% Power with Equilibrium Xenon FINALCONDITIONS: IC-12 100% Power with Equilibrium Xenon SOURCE OF COMPARISON DATA:

PLANT DATASET ENGINEERING EVALUATION FSAR SUER / LER

[g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACI'ORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Steady State Operation TEST No. 14.4.5.4 REV. 0 1TILE:HEATAND BALA1VCETESTS - IOO PERCENT POWER MASS BALhVCE OVERVIIPV:

This test was performed to evaluate the SIMULATORMASS BALANCE for a period of one hour. Twenty Plant Performance Parameters IAW Attachment A were set to zero.

Reactor level and condenser levels were maintained constant. Proper response of the CST levels was tested and veri6ed.

INK'IALCONDlTIONS: IC-12 1009o Power with Equilibrium Xenon.

FINALCONDITIONS IC-12 1009o Power with Equilibrium Xenon.

SOURCE OP COMPARISON DATA:

PLANT DATA SET ENOINEERINO EVALUATION FSAR Q SOERI LEE g OPEIIATIONALASSESSMIPIT Q TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES Q TEST RESULTS SATISFACI'ORY WITH DISCREPANCIES g TEST RESULTS SATISFACI'ORY WITHOUT DISCREPANCIES

TEST CATEGORY: Steady State Operation TEST No. 14A.3,1 REV. 0 TITLE: INITIALCONDITIONSTABII.ITTTEST OVERVIIVV:

The Initial Condition Stability Test was performed to verify simulator critical parameters do not vary by more than+ 2% over a period of one hour. Additionally, selected simulator non~tical parameters were verified to not vary by mote that, + 10% 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.

INDIIALCONDITIONS: IC-12, 100% Power Equilibrium Xenon.

FINAL CONDITIONS: IC-12, 100% Power Equilibrium Xenon.

SOURCE OF COMPARISON DATA:

g PLANT DATA 1 DP DA SEI'NGINEEIUNG EVALUATION Q FSAR Q SUER <LEE g OPERATIONAL ASSESSMENT TEST RESULTS:

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

WNP-2 SIMULATOR CERTIFICATION ATTACHMENTD-5 TRANSIENT PERFORMANCE TEST ABSTRACTS

TEST CATEGORY: Transients TEST No. 14.4.9.24.33 REV. 0

'ITTLE: MANUALSCRAM OVERVIEW:

This test was performed to demonstrate the functionality of the MAMJALSCIVQvf 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/AP1Q4Rbm & Rbm/

APRM/Flow Status lamps indicated downscale, Lvl Setpoint/Setdown light lit, and CRD-V-(10/

180,11/181) closed. The response of multiple (meters, recorders, & devices) was IAW the test pro-cedure coxzect. Multiple annunciators listed in the test alarmed coaectly. Simulator Data Set 9 33 was compared to Plant Data Set SCRAM LER 89-35. Proper response on activation of the MANUALSCR.AM malRnction was tested and veri6ed.

INITIALCONDITIONS: IC-12, Adjusted How to 67% using FCV's FINAL CONDITIONS: Reactor Scrammed, BOP shutdown in progress.

SOURCE OF COMPARISON DATA:

g PLANT DATASEZ ENGINEERING EVALUATION FSAR SUER/LER 90-021 85-016 g OPERATIONAL ASSESSMENT TEST RESULTS:

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

OP TEST CATEGORY: Transients TEST No. 14.4.103 REV. 0 TITLE: SIMULTANEOUS TRIP OF ALLRFP'S OVERVIl.W:

This test was perfoxmcd to verify the Simulators response to a simultaneous trip of all RFP's. The RRC FCV runback at RPV/L 4 with coincident RFP trip was vexi6ed. Reactor Scram and RRC pump trip to 15 hz was veri6ed at RPV/L 3. The Scram induced RPV/P reduction with Mode

, Switch in run was vexi6ed 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 offwere veri6ed and evaluated. HPCS-V-4 and RCIC-V45 closure at RPV/

L 8 and subsequent reopening of HPCS-VA at RPV/L 2 wexe veri6ed. No operator actions were taken as speci6ed in ANS 3d Attachment B, item B1.2. ANS 3d item B1.2.1 variables were plotted and evaluated at.5 sec resolution as specified. Note: Scram details evaluated in detail in 14.4.9.2433, 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 Brcak in DW.

INZITALCONDITIONS: IC-12 100% Power Exluilibxium 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:

g PLAFIT DATASET SCRMLER84.114 ENGINEEIUNG EVALUATION FSAR g SOERI LEE g OPERATIONAL ASSESSMIDIT TEST RESULTS:

TESI'ESULTS UNSATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITHOUTDISCREPANCIES

TEST CATEGORY: Transients TEST No. 14.4.10.3 REV. 0 TITLE: MS'SOLATION OVERVIEW'his test was perfoxmed to very the Simulators response to an MSIVIsolation. Thc MSIV isolation was vexified to cause a RPV/P increase 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 and reopening at RPV/

L 2. The SRV How decrease was verified as RPV Decay Heat decreased. The relationship between decay heat generation, RPV/P, SRV Flow, HPCS and RCIC Bow (at LT saturated conditions) werc evaluated. No operator actions were taken as specified in ANS 33 Attachment B, item B1.2. ANS 3.5 item 31.2.1 variables wexe plotted and evaluated at .5 sec resolution as specified.

INIIIALCOND1TIONS: IC-12 100% Power Equilibrium Xenon HNALCONDITIONS: 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:

g PLANT DATASET SCRMLER88.03 ENGINEERING EVALUATION, FSAR g SUER I LEE LER 88-03 g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACI'ORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITH DISCREPANCIES Q TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Transients TEST No. 14.4.10.6 REV. 0 TITLE: SIMULTAlVZOUST2UP OF ALLRECLRCULA27ON PUMPS 0VERVIIPiV:

This test was performed to vexify the Simulators response to a trip of all Recirculation Pumps. Core Power was verified to decrease due to the Core Bow reduction to Natural Circulation. No operator actions were taken as specified in ANS 3.5 Attachment B, item B1,2. ANS 35 item B1.2.2 vari-ables were plotted and evaluated at 5 sec resolution as specified.

INITIALCONDITIONS: IC-IO, adjusted to 75% Power, 100% Core Flow.

FINAL CONDITIONS: 25% Power and 25% Core Flow SOURCE OF COMPARISON DATA:

g PLANT DATASEI' ENGINEERING EVALUATION FSAR SUER /LER g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

N RE TEST CATEGORY: Transients TEST No. 14.4.9.24.34 REV. 0 TITLE: RECIRCUL4TIONPUMP B ZZIP OVERVIEW:

This test was performed to demonstrate the functionality of the RECIRCULATIONPUMP B TRIP Malfunction. Pump Motor overcturent due to electrical fault. System responses included: Multiple JP meter response IAW test procedure, RRC B Loop JP Qow decreased to zero and then increased as reverse Qow, RRC A Loop JP Qow increased as RRC B loop entered reverse Qow, appropriate annunciators alarmed, and total core Qow 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. Simulator Data was collected and evaluated as SPVS File 14.4.9.24.34, RRC B PUMP TRIP. Proper response on activation of the Recirculation Pump B Trip malfunction was tested and veriQed.

INfI'IALCONDITIONS: IC-12 1009o Power with EtluiiibriumXenon FINALCONDITIONS: Reactor Plant in Single Loop at reduced power SOURCE OF COMPARISON DATA:

g PLANT DATA PAT30A SEI'NOINEIEUNO'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 SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Transients TEST No. 14.4.9.24.31A REV. 0 TITLE: MAIlVTURBIlVETRlP FROM LT 30%

0VERVIEVIt'his test was performed to demonstrate the functionality of the hQQN TURBINE TRIP FROM LT 30% malfunction. System responses included: IVV'ENERATOR tripped, 5QQN TURBINE tripped, Multiple meter responses on P603, F840, F820, DEH Turbine Control, DEH Valve Test, BWR Control, TG-TR-SMT, and P800 occurred IAW with requirements listed in this test proce-dure. MT Bypass valves opened to control RPV/P. Multiple annunciators alarmed as listed in this test procedure. The reqtnred heater dump valves opened and the required extraction non-rein valves closed. The Turbine auxiliaries functioned properly during Turbine coastdown. Simulator Data was collected and evaluated as SPVS File 9-24-31. Proper response on activation of the Main Turbine Trip From LT 30% malfunction was tested and veri6ed.

NOTE Generator Trip evaluated in 14.4.8.1, Main Generator Trip evaluated in 14.4.9.13.1 INFIXALCONDIIIONS: IC-9, Adjusted Power to -28%.

FINAL CONDITIONS: Main Turbine has tripped, DEH controlling pressure on the Bypasses SOURCE OF COMPARISON DATA:

g PLANT DATASET PLANTSD.DOC ENGINEERING EVAL'UATION g FSAR 15.2.3 Q .SOERILER g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACI'ORY WITH DISCREPANCIES g TEST RESULTS SATISFACI'QRY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

N TEST CATEGORY: Transients TEST No. 14 4 8 4 REV. 0 TITLE: INDUCED TRANSLENT TESTS - PO7FER RAMP FROM 100 PERCENT POR'ER TO T5 PERCENT TO 100 PERCENT OVERVII..W:

This test was performed to evaluate the tuning of the feedwater system. Using thc RRC FCV's power was ramped down Rom 100 percent to 75 percent in 10 seconds. After stabilizing Rx level, power was aunped from 75 percent to 100 percent in 10 seconds. Proper response of the induced transient was tested and verified.

INI'IDEALCONDITIONS: IC-12 1009o Power Equilibrium Xenon FINAL CONDITIONS: 1009o Power SOURCE OF COMPARISON DATA:

Q PLANT DATA SEI'NOHIEERINU EVALUAHON FSAR 84-124 12/03/84

[g SUER y LER g OPERATIONAL ASSESSMENT TEST RESULTS:

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

TEST CATEGORY: Transients TEST No. 14.4.10.7 REV. 0 TITLE: MA'&MUMSIZZ DBA LOCA RVTH LOSS OEFSITE POR'ER OVERVIEW This test was perfoaned 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 bz via RPV/L 3 signals was verified. The initiation of the RPV/L 2 NS4 isolation, HPCS initiation, RCIC initiation, and RRC pumps tripping to offwere verified and evaluated. Div 1 and Div 2 DG's and ECCS initiation were verified. DW/P response and subsequent WW/P response are verifed as the DW/P overcomes downcomer submergence. No operator actions were taken as specified in ANS 33 Attachment B, item B1.2. ANS 3.5 item B1,2.3 variables were plotted and evaluated at 3 sec resolution as specified. 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.

INITIALCONDITIONS: IC-12 100% Power Equilibrium Xenon FINAL CONDITIONS: Reactor Shutdown with RPV/L being controlled GT Two-Thirds Core Height via ECCS Div 1-3 injection. Primary Containment Isolation complete via NS4 isolations.

SOURCE OF COMPARISON DATA:

PLANT DATASET g ENGINEERING EVALUATION FSAR g SUER SLEE Z OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITH DISCREPANCIES Q TEST RESULTS SATISFACI'ORY WITHOUTDISCREPANCIES

TEST CATEGORY: Transients TEST No, 14.4.10.9 REV. 0

'ITIVE: MAX'IMUMSlZE MAINSTEAMLINERUPTURE OVERVIEW:

This test was pezfozmed to veridy the Simulators response to a Maximum size MSL Break.. The DW/P increase initiation of Reactor Scram, NS4 Isolation and RRC FCV lockup werc vczifled; The RRC pump trip to 15 hz via RPV/L 3 signals was veri6ed. The initiation of the RPV/L 2 NS4 isola-tion, HPCS initiation, RCIC initiation, and RRC pumps tripping to off were vcrified and evaluated.

Div 3 DG and HPCS initiation werc verified. DW/P response and subsequent WW/P response arc verifed as the DW/P overcomes downcomer submergencc. CBP injection and subsequent RPV/L restoration, with DW cooling via brcak vezified. No operator actions were taken as specified in ANS 3.5 Attachment B, item B1.2. ANS 3D item B1.23 variables were plotted and evaluated at 3 sec resolution as spccifictL Note: Scram details evaluated in detail in 14.4.9.24.33, MT Trip details evaluated in 14.4.9.2431, Main Gen Trip details evaluated in 14.4.9.13.1, NS4 Isolation at RPV/L, INITIALCONDTTIONS: IC-12 100% Power E~brium Xenon FINAL CONDITIONS: Reactor Shutdown with RPV/L GT the MSL 110 inches. Primary Contaizunent Isolation complete via NS4 isolations.

SOURCE OF COMPARISON DATA:

PLANT DATASET ENGINEEIUNG EVALUATION g FSAR 15.6.5 6.2.1.13.b SOER/LER g OPERATIONAL ASSESSMENT TEST RESULTS:

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

TEST CATEGORY: Transients TEST No. 14.4.10.10 REV. 0 TITLE: MSIVISOLATIONTV7TH SRV FAILED OPEN (HP ECCS INHIBITED) 0VERVIIPiV:

This test was performed to verify the Simulators response to an MSIV Isolation with a SRV failed open. The MSIV isolation with SORV was veriQed to cause a RPV/P reduction with a subsequent injection by the Condensate Booster Pumps at approximately 630 psig. The SRV Qow decrease was veriQed as RPV/P decreased. The relationship between decay heat generation, RPV/P, SRV How, and Condensate Booster Pump Qow (at LT saturated conditions) were evaluated. No operator actions were taken as speciQed in ANS 3.S Attachment B, item Bl.2. ANS 35 item B1.2,3 vari-ables were plotted and evaLuated at 3 sec resolution as speciQed.

INITIALCONDEMNS: IC-12 100% Power Equilibrium Xenon HNAL CONDITIONS: Reactor Shutdown and deptessurized with CBP injection and RPV/L GT the ASS lines resulting in liquid Qow via the SORV.

SOURCE OF COMPARISON DATA:

g PLANT DATASEI' SCRMLER 8.03 ENGINEERING EVALUATION FSAR g SUER ILER g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFAC1'ORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

WNP-2 SIMULATOR CERTIFICATION ATTACHMENTDW PLANT MALFUNCTIONTEST A8STRACTS

TEST CATEGORY: Plant Malfunction TEST No. 14.4.9.2,2 REV. 0 TCILE: CONDENSER AIR LKiE OVERVII.W:

This test was performed to demonstrate the functionality of the CONDENSER AGU.EAK Mal-function. Metal fatigue causes a crack in the condenser shell. System responses included: Control Room indications showed decreasing main condenser vacuum, off gas Bow increased, appropriate annunciators alarmed, and Generator load was decreasing. The TURBINE GENERATOR tripped on low vacuum and caused a reactor SCABS. As vacuum continued to decrease an NSSSS isola-tion occurred and the Main Steam isolation valves closed. Proper response on activation of the CONDENSER AIR LEAKma15mction was tested and ved6ed. NOTE:Turbine Trip covered 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 INZIIALCONDITIONS: IC-12 100% Power with Equilibrium Xenon FINALCONDITIONS: Reactor Shutdown, RPV/P control via SRV operation, RPV/L deczeaseing towards RPV/L 2.

SOURCE OF COMPARISON DATA:

PLANT DATASET Q ENGINEERING EVALUATION g FSAR g SUER I LER g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITH DISCREPANCIES

[7 TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Plant Malfunction TEST No. 14 4.9.2.3 REV. 0 TITLE: FFZDWATER LllVEBRZAEINDRFWZLL OVERVII:W:

This test was performed to verify the Simulators response to a Feedwatcr Line Break in the DW upstream of thc inboani check valves. The DW/P response was verified to initiate a Reactor Scram with subsequent NS4 and ECCS initiations. The RRC pump'rip to 15 hz via RPV/L 3 signals was veri6ed. 'Ihe isolation of the MSIV's was verified to occur on low RPV/P. The subsequent RPV/P increase was vcrified to txip the RRC pumps off via ATWS logic. Thc SRV's werc verified to con-trol RPV/P at setpoint. The RFP's were vcrified to coast down as HP and LP steam sources expended. HPCS-VA was verified to auto close at RPV/L 8. Condensate Flow was verificd to con-tinue with a subsequen DW/P reduction as FWff decreased. Note: Scram details evaluated in detail in 14.4.9.24.33, hfT Trip details evaluated in 144.9,24.31, Main Gen Trip details evaluated in 14.4.9.13.1, MSIV Isolation details evaluated in 14.4.10.3. Proper Atmunciation response was veri-fied.

INITIALCONDITIONS: IC-12 100% Power Equilibrium Xenon FINALCONDITIONS: Reactor Shutdown with RPV/P control via SRV's with the Primary Containment isolation complete. Condensatc Flow contintxing via the break cooling the DW.

SOURCE OF COMPARISON DATA:

PLANT DATA SEI'NGINEERING EVALUAHON FSAR SOERI LEE g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITH DISCREPANCIES P TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Plant Malftxnction TEST No. 14.4,9.2.8 REV. 0 TITLE: FEEDWATER LINE BRE4E IN TURBINE BUILDING OVERVll:W:

This test was performed to verify the Simulators response to a Feedwater Line Break in the Turbine Building. 'Ihe RRC pump trip to 15 hz and the Reactor Scram via RPV/L 3 signals was verifled.

The isolation of the MSIV's was verifled to occur on low RPV/P. The Leak Detection system response was verifled.The subsequent RPV/P incxease was vezified to tzip the RRC pumps to off'via ATWS logic. The SRV's wexe verifled to control RPV/P at setpoint. The Auto initiation of HPCS and RCIC at RPV/L 2 was vezified. The NS4 isolatiion at RPV/L 2 was also verified. 'Ihe closure of HPCS-V-4 and RCIC-V45 at RPV/L 8 and the subsequent reopening of HPCS-v-4 at RPV/L 2 was veri6ed. Note: Scram details evaluated in detail in 14.4.9.2433, 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. The details of the NS4 isolation were vezified in 14.4.9.2.3 FW'ine Break in the Dzy-well. Proper Annunciation response was vezified.

INZIIALCONDITIONS: IC-12 1009o Power Bpxilibxium Xenon FINAL CONDITIONS: Reactoz'hutdown with RPV/P control via SRV's with RPV/L control via HPCS-V-4 cycling open and closed at RPV/L 2 and RPV/L 8 xespectively.

SOURCE OF COMPARISON DATA:

PLANT DATASET Q ENGINEIEUNG EVALUATION g FSAR 5. .6 SUER /LER g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Plant Mauunction TEST No. 14.4.9.2.9 REV. 0 TITLE: RFPTA TRIP OVERVIEW:

This test was performed to demonstrate the functionality of the RFPT A 'IRIP Malfunction, Circuit failuze causes RFW-DT-1A trip. System responses included the following alazzns: 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 Recizc Flow Control Runback occuzzed and the Reactor did not Scram. Proper response on activa-tion of the RFPT A TRIP malfunction was tested and verified.

INITIALCONDITIONS: IC-12 100% Power Equilibrium Xenon FINAL CONDITIONS: Reciic Flow Control valves have zunbacic, RFPT B has increased Qow to maxi-mum, Reactor is at approx. 68 to 72% Power.

SOURCE OF COMPARISON DATA:

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

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES.

TEST CATEGORY: Plant Malsmction TEST No. 14.4.9.2,9A REV. 0 TITLE: RFPTB TRlP OVERVIEW:

This test was performed to demonstrate the functionality of the RFPT B TRIP Malftmction. Circuit failure causes RFW-DT-1B trip. System responses included the following alarms: TUR B TRIP,,

TUR B COHEIR OIL PRESS LOW, and RFW PMP B DISCH FLOW LOW, Reactor water level decreased on all control room instruments and the RPV LEVEL HIGH/LOW ALERT alarmed. A Recixc Flow Contxol Runback occuxxed and the Reactor did not Scram. Proper response on activa-tion of the RFPT B TRIP malhmction was tested and vexi6ed.

INYIIALCONDITIONS: IC-12 100% Power Equilibrium Xenon FINAL CONDITIONS: Recirc Flow Contxol valves have runback, RFPT A has incxeased Bow to maxi-mum, Reactor is at approx. 68 to 72% Power.

SOURCE OF COMPARISON DATA:

PLANT DATA SEI'NGINEERING EVALUATION

[7 FSAR g SUER I LEE g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCKS TEST RESULTS'SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

N TEST CATEGORY: Plant Malfunction TEST No. 14.4.9.3.1 REV. 0 TlTLE: ROD DRlFT OVERVIEW:

This test was written to demonstrate the functionality of the ROD DRIFT Malfunction. A rod drifts in due to HCU 4 Valve Manifold Failure. System responses included: P603-A7-5-7 ROD DRIFT alarmed, the zed Drift light on the full coze display illuminated, P603-A7-5-7 ROD DRIFT alarm cleared when the rod is selected, the rod changed position on the four-rod display and thc Rod Drift alarm annunciated when thc next odd reed switch was activated, LPRM strings indicated a power decrease on the 4 Rod Display, APRM's indicated a slight decrease iu power, and the full coze dis-play illuminated 00 when thc rod reach its final position. Proper response on activation of the ROD DRIFT malfunction was tested and verified, INITIALCONDITIONS: IC-12 1009o Power with Equilibrium Xenon.

FINALCONDITIONS: IC-12 1009o Power with Equilibrium Xenon.

SOURCE OF COMPARISON DATA:

g PLANI'ATA PowerPlex Data SEI'NGINEERING EVALUATION Q FSAR SUER / LER g OPERATIONAL ASSESSMENT TEST RESULTS:

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

TEST CATEGORY: Plant Malfunction TEST No. 14.4.9.3.2 REV. 0 TITLE: STUCK ROD OVERVQ"W; This test was 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 was illu-minated and the blue background was on for the selected rod on the four rod display. The INSERT, WITHDRAW, and SEITLE lights illuminated normally when attempting to withdraw a rod. Sys-tem responses includaL indicated drive How equaled 2 gpm, 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 malftmction was tested and verified.

INZIXALCONDITIONS: IC-3, 1% Power FINALCONDITIONS: IC-3, 1% Po~er SOURCE OF COMPARISON DATA:

[J PLANT DATASZr ENGINEERING EVALUATION FSAR SUER (LER g OPERATIONAL ASSESSMI2iT TEST RESULTS:

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

TEST CATEGORY: Plant Malfunction TEST No. 14.4.9.3.3 REV. 0 TITLE: UNCOUPLED ROD OVERVIEW:

This test was 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. Proper Annunciation was veri6ed.

INHTALCONDITIONS: IC-5 FINAL CONDITIONS: IC-5 SOURCE OF COMPARISON DATA:

PLANT DATA SEI'NGINEERING EVALUATION SOERI LEE g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES Q TEST RESULTS SATISFACTORY. WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Plant Malfunction TEST No. 14.4.9.3.4 REV. 0 TITLE: SINGLE ROD SCRAM OVERVIEW:

This test was performed to demonstrate the functionality of the SINGLE ROD SCRAM Malfunc-tion. Blown fuse causes a single rod SCRAM. System responses included: F603-A7-&7 ACCU-MULATOR TROUBLE alarmed, F603-A7-5-7 ROD DRIFT alarmed, APRM's indicated a decrease in power, the scram light for the rod illuminated on the full 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 rod was blank while the malfunction was active. The LPRM strings surrounding the rod showed a noticeable decrease in Qux levels. Proper response on activation of the SINGLE ROD SCRAM malfunction was tested and verified.

INEQUAL CONDITIONS: IC-12 100% Power with Equilibrium Xenon FINAL CONDITIONS: Power is less than 100% and iVEE are less than 1150

~ SOURCE OF COMPARISON DATA:

g PLANT DATA PowerPlex Data SEI'NGINEERING EVALUATION FSAR g SO~I~

I OPEIIATIONALASSESSMENT TEST RESULTS:

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

TEST CATEGORY: Plant Malfunction TEST No. 14.4.9.3.6 REV. 0 TITLE: RDCS FAILURE OVERVIEW:

This test was performed to demonstrate the functionality of the RDCS FAILURE Malfunction. A rod select module generates a channel disagreement. System responses included: F603-A7-2-8 ROD DRIVE.CONTROL SYS INOP alarmed, the ACI'IVITYCONTROLS DISAGREE light illu-minated, the INSERT BLOCK and WTTHDRAW BLOCK lights illuminated on Reactor Control Console, and the ROD OUT BLOCK P603-A7-2-7 alarmed. Proper response on activation of the RDCS FAILURE malfunction was tested and verified INK'IALCONDITIONS: IC-4 Point Of Adding Heat FINAL CONDITIONS: ICA Point Of Adding Heat SOURCE OF COMPAluSON DATA:

PLANT DATA SEI'NOINEEREIO EVALUATION.

FSAR SUER / LER g OPERATIONAL ASSESSMENT TEST RESULTS:

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

TEST CATEGORY: Plant Malfunction TEST No. 14.4.9.3.12 REV. 0 TITLE: HYDRAULICATWS OVERVIEW:

This test was 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-12 1009o Power with Eqtniibrium Xenon.

FINAL CONDITIONS: IC-12 1009o Power with Equilibrium Xenon.

SOURCE OF COMPARISON DATA:

PLANT DATASET ENGINEEIUNG EVALUATION Q FSAR SUER HLER g OPERATIONAL ASSESSiilENT TEST RESULTS:

TEST RESULTS UNSATISFACI'ORY WITH DISCREPANCIES

[7 TEST RESULTS SATISFACI'ORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Plant Malfunction TEST No. 14.4.9.4.4 REV. 0 TITLE: LEAZDOWNSTREAM OF CONTROL AIR DRYER OVERVIEW:

This test was performed to demonstrate the functionality of thc LEAKDOWNSTREAM OF CON-TROL AIR DRYER Malfunction. Leak occurs in the control air line between the dryezs and the after 6lters. System responses includetL control room indic'ation 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 dtiNng in, and the Reactor SCRAM occurred Rom SDV/L scram stpt. Sig-ni6cant 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 DOWNSTRE QVl OF CONTROL AIR DRYER malhlnction was tested and veri6ed.

INIITALCONDITIONS: IC-12 100% Power with Equilibrium Xenon FINAL CONDITIONS; Reactor SCRAM with signi6cant systems and valves in loss of air failed posltxous SOURCE OF COMPARISON DATA:

PLANT DATASET ENGINEIEUNG EVALUATION FSAR Q SOERi LEE g OPERATIONAL ASSESS'iiIENT TEST RESULTS:

Q TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITH DISCREPANCIES Q TEST RESULTS SATISFACI'ORY WITHOUTDISCREPANCES

TEST CATEGORY: Plant Malfunction TEST No. 14.4.9.7.1 REV. 0 TULE: CLADDINGPERFOK4TION OVERVIEW'his test was performed to demonstrate the functionality of the CLADDINGPERFORATION Mal-function. The fuel rods of numerous fuel bundles experience cladding preformation fxom PCI. Sys-tem responses included: radiation levels on log radiation monitors for the main steam lines increased, a 30 second period where nothing else occurs, counts on the off gas pre-treatment moni-tor increased, radiation level on carbon adsorber vault monitor increased, and the off gas post-treat-ment recorder increased. Proper response on activation of the CLADDING PERFORATION malfunction was tested and verifie.

INZIIALCONDITIONS: IC-12 100% Power with Ecpulibrium Xenon FINAL CONDITIONS: IC-12 100% Power with Ecpulibrium Xenon SOURCE OF COMPARISON DATA:

PLANT DATA SET ENGINEIEUNG EVALUATION FSAR SOER/LER g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACI'ORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITH DISCREPANCIES Q TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Plant Malfunction TEST No. 14.4.9.7.2 REV. 0 TITLE: GROSS CLADIiAIIURE OVERVIEW:

This test was performed to demonstrate the functionality of the GROSS CLAD FAILURE Mtlfunc-tion. An operating condensate Qlter demin ruptures and resin trap then breaks, resin is injected into the vessel causing clad failure. System responses included: OG-RR-604 off gas pretreatment radia-tion incxeased, CONDSR RAD HI-HI alaxmed at 1800mr/hr, CONDSR RAD HIGH alarmed at 2300 mrIthr, OFFGAS POST TREAT RAD HIGH alxmed at 1700 cpm, OG-V<5 closed, and OG-V-51M,CP opened. P603-A8-24 MSL RAD HIGH KP alarmed causing a half SCRAM and half MSL isolation. F603-A7-2A MSL RAD HIGH TRIP alarmed causing a half SGVJd and half MSL isolation. With the second MSL RAD HIGH TRIP a RX SCRAM and MSIV isolation occuxxecL NOTE: Details of the reactor SCR AM detailed in test 14.4.9.24.33@etails of the Turbine Trip are in test 14.4.9.24.31 INITIALCONDITIONS: IC-12 100% Power with EquQibxxum Xenon, OG-V<5 switch in BYPASS and then AUTO. OG-V-51AQ,C,D shut, OG-V45 is open FINAL CONDlTIONS: Reactor SCRAM and MSIV isolation have occuxxed SOURCE OF COMPARISON DATA:

PLANT DATASET ENGINEERING EVALUATION FSAR SUER I LEE g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITH DISCREPANCIES 0 TEST RESULTS SATISFACI ORY WITHOUTDISCREPANCIES'

N TEST CATEGORY: Plant Malfunction TEST No. 14.4.9.8,3A REV. 0 TJ.'ILE: 4160 VAC BUS SM-7 OVERCURRENT OVERVIEW:

This test was perfozmed to demonstrate the functionality of the 4160 VAC BUS SM-7 OVERCURRZNT - GRND Malfunction. Electrical insulation failure causes a ground and ovezcuzrent on SM-7. System zesponses included: aplmpziate annunciatozs alarmed, bkr 7-1 tripped open and was locked out, bkr B-7 open, 7-DGl open, (volt and amp) meters on SM-7 and her daughter buses indicated zero zeadings, DG-1 auto-started and was running unloaded without SW cooling, TSW-P-1B started on low pzessuze, and RPS bus A half-SCIVJVl occuzzed. Proper zesponse to the loss of motive power provided by SM-7 and her daughter busses was tested and verified. Proper response to the loss of control and indica-tion power provided by SM-7 and her daughter busses was tested and verdied INK'IALCONDITIONS: IC-12 100% Power with Equilibrium Xenon FINALCONDITIONS: 100% Power, 1/2 Scram A channel SOURCE OF COMPARISON DATA:

PLANT DATASEr ENGINEERING EVALUATION FSAR Q SOERI LEE g OPERATIONAL ASSESSMENT TEST RESULTS:

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

TEST CATEGORY: Plant Malfunction TEST No. 14.4.9.8.3B REV. 0 TITLE: OVERCURRENT SM-1 OVERVIIVV:

This test was performed to demonstrate the functionality of the 4160 VAC BUS SM-1 OVERCUR-RENT Ma16mction. Overcurrentk Lockout Condition of Bus SM-1. System responses included:

appropriate annunciators alarmed, bkr Nl-1 tripped open and was locked out, bkr l-ll 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 was mnning unloaded, bkr B-7 closed and supplied SM-7. Proper response to the loss of motive power provided by SM-1 was tested and verified. NOTE: LOSS OF BUS SM-7 is evaluated in 14.4,9.8.3%

INI'ITALCONDlTIONS: IC-12 100% Power with Equilibrium Xenon FINAL CONDITIONS: One third of thc Condensatc system capacity has been lost and will cause a subsequent reactor SCRAM.

SOURCE OF COMPARISON DATA:

PLANT DATA SEI'7 ENGINEERING EVALUATION FSAR.

Q SOar.HLER g OPERATIONAL ASSESSM1DIT TEST RESULTS:

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

TEST CATEGORY: Plant Malfunction TEST No. 14.4.9.8.4 REV. 0 THI E: GROUNDED DC BUS - DP-Sl-2 OVERVII:W:

.This test was performed to demonstrate the functionality of the GROUNDED DC BUS - DP S1-2 TRIP Mal6mction. Electrical insulation failure causes a ground. System responses included:

Appropriate Annunciator alarms, applicable BISI panel alaxms, IN-2 shifted to the alternate ac source, ampmeters (AM-B1-2 0 AM-C1-2) indicated zero, and VM41-2 indicated zero. Proper response to the loss of motive power provided by DP-Sl-Zwas tested and vexi6ed for the following loads: RCIC-V-113 and CAC-V- (11,13,15,17). Proper response to the loss of control and indication power provided by DP-S1-2 was tested and veri6ed INITIALCONDITIONS: IC-12 100Vo Power with Equilibrium Xenon FINAL CONDITIONS: RCIC and CAC systems OOS, numerous indications OOS.

SOURCE OF COMPARISON DATA:

PLANT DATA SET ENGINEERING EVALUATION FSAR SUER I LEE g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPAiVCIES g TEST RESULTS SATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Plant Malfunction TEST No. 14.4.9.8.5 REV. 0 TITLE: 6900 VAC BUS SHA OVERCURREiVT - GND OVERVIEW'his test was performed to demonstrate thc loss of power to Bus SH-6 using malfunction 6900 VAC BUS SH-6 OVERCUtu&NT - GRND. Proper response to the loss of motive power provided by SH-6 and hcr daughter busses was tested and verified. Proper response to the loss of control and indication power provided by SH-6 and her daughter busses was tested and verified INITLQ.CONDITIONS: IC-12 100% Power with Equilibrium Xenon FINAL CONDITIONS: Bus SH-6 has tripped, RRC-P-13 has tripped, Rx is in single loop with fmal fecdaow and steam flow greater than 45%

SOURCE OF COMPARISON DATA:

PLANT DATA SET Q ENGINEERING EVALUATION Q FSAR SOER/LER g . OPERATIONAL ASSESSMENT TEST RESULTS:

TESI'ESULTS UNSATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITH DISCREPANCIES Q TEST RESULTS SATISFACTORY WITHOUTDISCREPANCIES

TEST CATEGORY: Plant Malfunction TEST No. 14.4.9.8.7 REV. 0

'ITTLE: LOSS OF ALLOFF- SITE POWER OVERVIEW:

This test was performed to demonstrate the functionality of the LOSS OF ALLOFFQITE POWER Malfunction. A tornado destroys all outside transznission lines to the plant. Simulator was frozen at six seconds for evaluation; system responses include<<L appropziatc annunciators alarmed, multiple A.C. Amp meters indicated zero, multiple A.C. Volt meters indicated zero, the Reactor had scramzned, the Turbine had tzzplmd, thc MSIV'S were closed, and the SRV's were controlling pres-sure. All major electrical breakers tripped opened as listed. Emergency dicsels werc running unloaded and DC pumps had started. Simulator was restarted and zun for twenty scc. Proper response to the loss of motive power provided by all major A.C. Busses and their daughter busses was tested and veri6e<<L Proper response to the loss of control and indication power provided by major A.C. Busses and their daughter busses was tested and veri6ed INDIIALCONDITIONS: IC-12 100% Power with Equilibrium Xenon FINAL CONDITIONS: Reactor Scrammed, all major AC Busses dc~crgized, Vital AC Busses pow-ered by EDG's, pzessuze controlled by SRV's SOURCE OF COMPARISON DATA:

PLANT DATA SEI'NGINEERING EVALUATION g FSAR SUER/LER g OPERATIONAL ASSESSMENT TEST RESULTS:

TESI'ESULTS UNSASISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITH DISCREPANCIES

[7 TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Plant Malfunction TEST No. 14.4.9.8.8 REV. 0 TITLE: DG 2 TRLP - HIGH DIFFERE1VTIALCURRElVT OVERVII..W:

This test was performed to demonstrate thc functionality of thc DG 2 TRIP - HIGH DIFFEREN-TIALCURRENT Malfunction. Defective electrical insulation causes high phase-to-phase difcren-tial current. System responses included: appropriate 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 was tested and verified.

NOTE Response to the loss of motive, control, and indication power provided by SM-8 axe evalu-ated in Test No. 14.4.9.8.3 (LOSS OF POWER TO SM-8) and 14.4.9.8.10 (LOSS OF PWR to SL-81).

INHTALCONDITIONS: IC-12 1009o Power with Etpilibrium Xenon FINALCONDITIONS: SM-8 is de-energized and "a half scram has occurred on RPS-B SOURCE OF COMPARISON DATA:

[7 PLANT DATA SET ENGINEERING EVALUATION PSAR SUER / LER g OPERATIONAL ASSESSMENT TEST RESUI.TS:

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

TEST CATEGORY: Plant Malfunction TEST No. 14.4.9.9.4A REV. 0 TITLE: RCIC TURBINE ZZEP OVERVIEW:

This test was performed to demonstrate the functionality of the RCIC TURBINE TRIP DUE TO RCIC-V-8 CLOSURE Ma16mction. The RCIC turbine tripped due to RCIC -V-8 failing closed.

System xesponses included: RCIC-V-8 closed, RCIC TURBINE TRIP alaxmed, Turbine (speed, exhaust pressure, How, suction press, and discharge pxess) decreased, RCIC-V-(1 and 19) indicated closed, RCIC WATER LEG PUMP DISCH PRESSURE LOW, and RCIC LUBE OIL CLR WATER PRESSURE HIGH/LOW annunciators alarmed and cleared. Proper response on activation of the RCIC TURBINE TRIP due to RCIC-V-8 closure ma16zction was tested and verified.

~W'IALCONDITIONS: IC-12 100% Power with Ettuilibrium Xenon@CIC placed in Full Flow Test Mode CST to CST FINALCONDITIONS: IC-12 100% Power, RCIC TURBINE has tripped.

SOURCE OF COMPARISON DATA:

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

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Plant Malfunction TEST No. 14.4.9.9.4B REV. 0 TITLE: RClC TURBENE TRlP (EFIGH'EXPAUST PRESSURE)

OVERVH..W:

This test was performed to demonstrate the functionality of the RCIC TURBINE TRIP (HIGH E2CHAUST PRESSURE) Malfunction. The RCIC turbine tripped due to RCIC -VM stichng shut, System responses included: RCIC Exhaust Pressure increased, F601-A4-2-8 EXH PRESS HIGH alarmed, P601-A4-1-S RCIC TURBINE TRIP alarmed, 'Ihrbine (speed, exhaust pzessure, How, and discharge press) decreased, RCIC-V-(1 and 19) indicated closed, RCIC WATER LEG PUMP DISCH PRESSURE LOW, and RCIC LUBE OIL CLR WATER PRESSURE HIGH/LOW annunci-ators alarmed and cleared. Proper response on activation of the RCIC TURBINE TRIP due to high exhaust pressure malfunction was tested and vexi6ed.

INITIALCONDITIONS: IC-12 100% Power with Equilibrium Xenon@CIC placed in Full Flow Test Mode CST to CST FINAL CONDITIONS: IC-12 100% Power, RCIC TKU3INE has tripped.

SOURCE OF COMPARISON DATA:

PLANT DATA SEI'NGINEIEUNG EVALUATION FSAR SOER / LER g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITH DISCREPANCIES Q TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Plant Malfunction TEST No. 14.4.9.9.4C REV. 0 TITLE'CIC TURBINE TRlP (MZCHAMCALOVERSPEED)

OVERVIEW:

This test was performed to demonstrate the functionality of the RCIC 'I'URBINE TRIP (MECHANICALOVERSPEED) Malfunction. The RCIC turbine tripped due to mechanical over-speed. System responses included: P601-A4-1-5 RCIC 'I UIU3INE TRIP alarmed, Turbine (speed, exhaust pressure, flow, and discharge press) decreased, RCIC-V-(1 and 19) indicated closed, RCIC WATER LEG PUMP DISCH PRESSURE LOW, and RCIC LUBE OIL CLR WATER PRESSURE HIGH/LOW annunciators alarmed and cleared. Mal6mction was deactivated, attempted to open RCIC-V-I, RCIC-V-l would not open. Proper response on activation of the RCIC TURBINE TRIP due to mechanical overspeed malfunction was tested and verified INH'IALCONDITIONS: IC-12 100% Power with Equilibrium Xenon@CIC placed in Full Flow Test Mode CST to CST FINAL CONDEMNS: IC-12 100% Power, RCIC TURBINE has tripped,and RCIC-V-1 could not be opened from control room.

SOURCE OF COMPARISON DATA:

[7 PLANT DATA SET ENGINEEIUNG EVALUATIGN

[7 FSAR SOER /LER g OPERATIONAL ASSESSMEIIT TEST RESULTS:

TESI'ESULTS UNSATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY W1TH DISCREPANCIES TEST RESULTS SATISFACI'ORY WITHOUT DISCREPANCIES

TEST CATEGORY Plant Malhinctions TEST No. 14.4.9.13.1 REV. 0 TITLE BLALlÃGENERATOR TRIP OVERVIEW:

This test was performed to demonstrate the functionality of the MAIN GENERATOR TRIP Malfunction, The 86 lockout tzip 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 Trip, and Oscillograph Started. System responses included: Recirc Pumps transferred to LFMG's, TO-P-BOP started, Trip Circuit Available light illuminated, (throttle, governor, reheat stop, and intercept) valves closed, turbine speed decreased, generator output read zero, bypass valves controlled DEB pressure, turbine drains opened, MSR temperature controls shut, (86XU, 86XIU, 8h 86G)tripped, Generator output bkrs opened, N bkr's opened, S bkr's shut, Generator parameters werc sat, non-return valves closed, and dump valves opeaed. Proper response on activation of the Main Generator Trip malf was tested aad verified.

INI'IIALCONDITIONS: IC-12 100% Power with Equilibrium XEnon

/

FINAL CONDITIONS: Main Generator tripped, Reactor Scrainmed.

NOTE: Refer to 14.4.9.24.33 for SCRAM details.

SOURCE OF COMPARISON DATA:

PLANT DATA SEI'NOINEEIUNO EVALUATION g FSAR 15.2.2 g SOERI LEE 85-002,85-003 g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACI'ORY WITH.DISCREPANCIES g TEST RESULTS SATISFACTORY WITH DISCREPA'NCIES TEST RESULTS SAHSFACTORY WITHOUTDISCREPANCIES

TEST CATEGORY: Plant Malfunction TEST No. 14.4.9.14.1 REV. 0

'ITIVE: SRM A FAILURE -

LOS'VERVIE7It'his test was performed to demonstrate the functionality of the SRM A FAILURE - LOW Malfimction. Proper response on activation of SRM-A failing low was tested and veri6ed.

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

PLANT DATA SEI'NOINEEREIO EVALUATION Q FEAR

[7 SOER HLER g OPERAIIONALASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Plant Malfunction TEST No. 14.4.9.14.2 REV. 0 TITLE: APKVD FAILS UPSCALE OVERVI1:W:

This test was perfoancd to demonstrate the functionality of the APRM D FAILS UPSCALE Malfunction. Malfunction in the averaging circuit. Alarm responses included: APRM UPSCALE, APRM BDF UPSCL TRIP or INOP, ROD OUT BLOCK, NEVIRON MONITOR SYSTEM TRIP, and 1/2 SCRAM SYSTEM B. APRM D UPSC TR OR INOP and UPSC ALAIM lights illuminated on P603. System responses included: APRM D read upscale on IRM-LR-603B, APRM D was upscale on P608, UPSCI. (Therm Trip, Alarm, Neut Trip, Neut First) lights illuminated on P608, RPS B logic scram group solenoid lamps extinguished on F603, RPS B SCRAM GP 1<

solenoid cncrgy. lamps extinguished on F611, and the Bachzp Scram Valve Solenoid Lights for RPS B logic illuminated. Proper response on activation of APRM D Fails Upscale malfunction was tested and verified.

INITIALCONDITIONS: IC-12 1009o Power with Equilibrium XEnon.

FINALCONDITIONS: 1009o Power, 1/2 SCRAM RPS B 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 SATISFACI'ORY WITHOUT DISCREPANCIES

TEST CATEGORY: Plant Malfunction TEST No. 14,4.9.14.5 REV. 0 TXTLE: LRMINSTR UMEAYFAILURE - HIGH 0VERVH:VIt'his test was performed to demonstrate the functionality of the IRM INSTR. FAILURE-HIGH Malfunction. IRM output amp shorted. The following annunciators alarmed: IRM ACEG UPSCL TRIP OR INOP, IRM MONITORS UPSCALE, ROD OUT BLOCK, NEUTRON MONITOR SYS'lKVl TRIP, and 1/2 SCRUB SYSTEM A. System responses included: IRM A indicated upscale on IRM-LR-603A, IRM A UPSC TR OR INOP light illuminated, IRM A UPSC AVBN light illuminated F603, IRM A upscale on IRM A drawer, UPSCALE ALARMlight illunnnated on F606. RPS A logic SCIVQvl group solenoid lamps extinguished. Bachip SCRAM valve solenoid lights for RPS A logic illuminated. Proper response on activation of IRM Instr. Failure - High was tested and veritied.

INI'ITALCONDITIONS: IC-5 FINALCONDITIONS: Half Scram System A and accompanying alarms SOURCE OF COMPARISON DATA:

PLANT DATASEP ENGH IEHRING EVALUATION FSAR SUER HLER g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DIS CREPANCES

[g TEST RESULTS SATISFACI'ORY WITHOUT DISCREPANCIES

NAL TEST CATEGORY: Plant Malfunction TEST No. 14 4.9.14.8 REV. 0 TTIT.E: LPRM FAILURE- DOWlVSCALZ OVERVIEW'his test was performed to demonstrate the functionality of the LPRM FAILURE - DOWNSCALE Malfunction. The LPRM Bux amplifier fails. System responses included. P603-A8-5-6 LPRM DOWN SCALE alarmed,24-33a DNSC light illuminated on the full coze display, and LPRM%

HEAT FLUX meter ( bottom zt, A level) indicated downscale when zod 22-35 was selected. Proper zesponse on activation of the LPRM FAILURE - DOWNSCALE malfunction was tested and verified.

INI'ITALCONDITIONS: IC-12 100% Power with Equilibrium Xenon FINALCONDITIONS: IC-12 100% Power with Equilibrium Xenon SOURCE OF COMPARISON DATA:

PLANT DATASET ENGINEERING EVALUATION FSAR SUER)LER g OPERATIONAL ASSESSMENT TEST RESULTS:

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

TEST CATEGORY: Plant Malfunction TEST No. 14.4.9.16 4 REV. 0 TITLE: HPCS LOGIC FAILURE OVERVIEW:

This test was perfomed to demonstrate the functionality of the HPCS LOGIC FAILURE Malfunction. Inadvertent HPCS Initiation. System responses included: P601-Al-1-6 HPCS ACTUATED alarmed, P601-Al-6-1 DIESEL ENGINE RUNNING alarmed., HPCS-P-(1832) auto started, RPV LEVA. HIGH/LOW ALERT alarmed, RPV INJECIION HPCS-VP auto opened, RFW -LIC-600 Qow decreased, and RFW-FR-607 developed a Sow mismatch. Proper response on activation of the HPCS LOGIC FAILURE Malfunction was tested and verifie.

KNXITALCONDlTIONS: IC-12 100% Power with Equilibrium Xenon FINAL CONDITIONS: 100% Power with HPCS injection in progress.

SOURCE OF COMPARISON DATA:

PLANT DATA SEI'NGINEIEUNG EVALUATION g FSAR 15.5.1 SOER / LER g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACI'ORY WITH DISCREPANCIES TEST RESULTS SATISFACI'ORY WITH DISCREPANCIES g TEST RESULTS SATISFACI'ORY WITHOUT DISCREPANCIES

TEST CATEGORY: Plant Malfunction TEST No. 14.4.9.18.3 REV. 0 TITLE: INSTRUMEiVTREFERENCE LINEBREAE D004A (PENXll4)

OVERVIEW:

This test was performed to demonstrate the functionality of the INSTRUMENT REF LINE BREAK D004A (PENX114). Rupture of INST Line between REACTOR and CONDENSATE POT for DOO4A (PENX114). Apparent level incxeased MS-LIS-100A, P601-Al-2-6 Injection Vlv Closure RPV LEVEL HIGH +54.5" alarmed, and HPCS-VA remained shut. Apparent level increased RFW-DFF4A, RFW-LR-609 and RFW-LL 606A indicated upscale high. REACTOR VESSEL HIGH LEVELA SEAL light illuminated and RFWffUIUPINERPV LEVEL HIGH 'IHIP alarm activated. Manual transfer to level control Ch B prevented low level actual scram. Leak was allowed to xun and caused dxywell pressure to increase. DRYWELL PRESS HIGH/Low Alert alarmed followed by the Drywell Pxess High Trip. Proper response on activation of INST REF LINE break DOO4A was tested and vexified27OTE: Details of Reactor Scram evaluated in test 14.4.9.2433, DBA in14.4.9.18.S.

INEQUAL CONDITIONS: IC-12 100% Power with Equilibrium Xenon FINAL CONDITIONS: Reactor has scxanuned on Hi Drywell pressure.

SOURCE OF COMPARISON DATA:

PLANT DATASET ENGINEEIUNG EVALUATION g FSAR g SUER ILER g OPEILATIONALASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITH DISCREPANCIES Q TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Plant Malnmction TEST No. 14.4.9.18.6 REV. 0

'ITTLE: INSTRUMENT VAREABLEIZG LINEBRZAExll5 OVERVIEW:

This test was performed to demonstrate the functionality of the INSTRUMENT VAIGABLELEG LINE BREAK xl15 Malfunction. System responses included: PI-EFC-X115 changed position ftom open to closed, apparent loss of level as indicated by MS-LR/PR-623A downscale, HPCS INIT RPV LEVEL LOW -50"alarmed, HPCS system initiated, N4S ISOL RPV LEVEL LOW-50"alarmed, MSIV Half Trip System A, and RC-1 HALF TRIP annunciated. Proper response on activation of the INSTRUMENT VARIABLELEG LINE BREAK XI15 malfunction was tested and vcri6ed.

INFIXALCONDITIONS: IC-12 100Fo Power with BtuilibriumXenon FINAL CONDITIONS: 1009o Power, HPCS system ltntiated, RC-1 HALF TRIP alarmed.

SOURCE OF COMPARISON DATA:

PLANT DATA SET Q ENGINEERING EVALUATION g FEAR 15.6.2 SOER / LER g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCES TEST RESULTS SATISFACTORY WITH DISCREFANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES'

TEST CATEGORY: Plant Malfunction TEST No. 14.4.9.21.1 REV. 0

'ITCLE: ADS LOGIC FAILURE (INADVERTENTINITIATIO1V)

OVERVllVV:

This test was performed to demonstrate the functionality of the ADS LOGIC FAILURE (INAD-VERTENT INITIATION)Malfunction. A surveillance being performed results in an advertent ini-tiation of the ADS. System responses included: Applicable annunciator's alarmed, after 105 seconds elapsed time the seven ADS valves indicated open and their respective acoustic monitor alarm lights illunnnated, suppression pool temperatures increased, and Reactor pressure decreased rapidly. RPV/L increased due to swell with resultant RPV/LS Trip of Main Turbine and RFP's which in tumed caused a leve1 three Reactor Scram and the RRC pumps to shift to slow speed.

Proper response on activation of ADS Logic Failure (Inadvertent Initiation) malfunction was tested and verified.

B KH'ALCONDITIONS: IC-12 1009o Power Equilibrium Xenon FINAL CONDITIONS: Reactor Scr'untned on lvl three, level two NSSSS isolation occurred and the MSIV'S shut.

SOURCE OF COMPARISON DATA:

[7 PLANTDATA SEI'NGINEEIUNG EVALUATION'SAR SUER / LER X OPERATIONAL ASSESSMENT TEST RESULTS:

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

N RE TEST CATEGORY: Plant Malfunction TEST No. 14.4.9.21.4A REV. 0

'ITILE: MA1NSTEAM RUPTURE IF DRYWELL OVERVIEW:

This test was performed to verify the Simulators response to a Main Steam Line Rupture in the DrywelL The DW/P increase initiation of Reactor Scram, NS4 Isolation and RRC FCV lockup were veri6ed. The RRC pump trip to 15 hz via RPV/L 3 signals was vexi6ecL The initiation of the RPV/L 2 NS4 isolation, HPCS initiation, RCIC initiation, and RRC pumps tripping to o8'were ver-i6ed and evaluated. Div 3 DG and HPCS initiation wexe veri6ed. DW/P response and subsequent WiV/P response axe vexifed as the DW/P overcomes downcomer submexgence. CBP injection and subsequent RPV/L restoration, with DW cooling via break vexi6ed. 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 evalu-ated 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 vexi6ed.

INI'TIALCONDITIONS: IC-12 100% Power Eqmlibxium Xenon FINAL CONDITIONS: Reactor Shutdown with RPV/L GT the MSL 110 inches. Primary Containment Isolation complete via NS4 isolation SOURCE OF COMPARISON DATA:

PLANT DATA SEI'NGINEEIUNG EVALUATION g FSAR 15.6.5 6.2.1.1.3.b SUER / LER QX OPERATIONAL ASSESSMENT TEST RESULTS:

[7 TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES X TEST RESULTS SATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACI'ORY WITHOUTDISCREPANCIES

TEST CATEGORY: Plant Malfunction TEST No. 14.4.9.21.5A REV. 0 TITLE: MAlNSTKhM RUZTUREIN TURBIlVEBUILDlNG 0VERVIIDV:

This test was performed to verify thc Simulators response to a Main Stcam Line Rupture in the Tur-bine Building, The RRC pump trip to 15 hz and Reactor Scram initiation via RPV/L 3 signals was verifi. The isolation of the MSIV's was verified to occur on low RPV/P. The subsequent RPV/P increase was verified to tzip the RRC pumps to o8'ia ATWS logic. The SRV's were verifie to control RPV/P at setpoint.. Note: Scram details evaluated in detail in 14.4.9.24.33, MT Trip details evaluated in 14.4.9.24.31, 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.

INI'IIALCONDITIONS: IC-12 100% Power Equilibrium Xenon FINAL CONDITIONS: Reactor Shutdown with RPV/P control via SRV's with RPV/L decreasing towards RPV/L 2 SOURCE OF COMPARISON DATA:

Q PLANT DATASET ENGINEERING EVALUATION' FSAR 15.6.4 SUER /LER g OPERATIONAL ASSESSiVNNT TEST RESULTS:

Q TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES QX TEST RESULTS SATISFACI'ORY WITH DISCREPANCIES Q TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Plant Malfunction TEST No. 14.4.9.2L6 REV. 0 TITLE: RCIC STEAMLlNEBREAKAT TURBINE OVERVIEW:

This test was performed to demonstrate the functionality of the RCIC STEPJvtLINE BREAK AT TMINEMa5mction. RCIC Steam Line break between RCIC-V4 and RCIC-VMS valves. Sys-tem responses included: (RCIC TURBINE TRIP, RCIC STEAM LINE INTEGRITY DP HIGH, RCIC DIVI OUT OF SERVICE, RCIC TURBINE STEAM SUPPLY PRESS LOW, and others) alarmed, RCIC-V/8, 63, 1) closed, and Turbine Coasts to a stop. RCIC room radiation levels increased, RCIC room temperatures increased, and Reactor Bldg. Exhaust radiation levels increased with a time delay. Proper response on activation of the RCIC STEAMLINEBREAK AT TURBINE malfunction was tested and vedfied.

INITIALCONDITIONS: IC-12 100% Power Ecluilibrium Xenon FINALCONDITIONS: RCIC Turbine Tripped, Reactor at 100% Power SOURCE OF COMPARISON DATA:

PLANT DATA SEI'NGINEEIUNG EVALUATION g FSAR SUER / LER g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITHOUTDISCREPANCIES.

TEST CATEGORY: Plant Malfunction TEST No. 14.4.9.23.3 REV. 0 TITLE: DEH PRESS REGULATOR OUTPUT FAILUREHIGH 0VERVII:W:

This test was performed to demonstrate the functionality of thc DEH PRESS REGULATOR OUT-PUT FAILURE HIGH Malfunction. Circuit failure cause controller high signal select circuit to fail high. System responses included: governor valves full open, Generator output increased, Bypass valves went full open, and Reactor press decreased rapidly. The following annunciators alarmed:

MSL PRESS LOW, MSIV HALF TRIP SYSTEM B, MSIV HALF TRIP SKI'EM A, and MSL ISOL VLVS CLOSURE TRIP. Mc 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 INITIALCONDEMNS: IC-12 100% Power Eqmlibrium Xenon FINALCONDITIONS: Reactor Scrams on MSIVclosuxe.

SOURCE OF COMPARISON DATA:

g PLANT DATA PAT 22 SEI'NGINEERING EVALUATION g FSAR 15.1.3 SUER /LER QX OPERATIONAL ASSESSMENT TEST RESULTS TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACI'ORY W1TH DISCREPANCIES Q TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Plant Malfunction TEST No. 14.4.9.23.3A REV. 0 DZH PRESS REGULATOR OUTPUT FAILURE LOR'VERVKW'his test was perfozmed to demonstrate the functionality of the DEH PRESS REGULATOR OUT-PUT FAILURE LOW Ma16xnction. Circuit failure cause PRESS REGULATOR OUTPUT to go low, due to HSS Circuit internal failure. System responses included: governor valves are full shut,-

Turbine/Generator trips off-line, bypass valves aze full closed, reactor pressure is increasing, appro-priate alarms occur, Rx scrams on high pzemzze, and SRV's control pressure. Proper response on activatrion of the DEH Press Regulator Output Failure Low was tested and verified.

INTIALCONDITIONS: IC-12 100% Power Equilibrium Xenon FINAL CONDITIONS: REACTOR SCRAMS on either High Pressure or HI APRM Trips.

SOURCE OF COMPARISON DATA:

PLANT DATA SEI'NGINEERING EVALUATION

'SAR 85-024 g SOER/LER g OPERATIONAL ASSESSMENT TEST RESULTS:

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

TI N TEST CATEGORY: Plant Malfunction TEST No. 14.4.9.24A REV. 0 TRIKE: LOSS OF RBR SDC DUE TO RHR-P-2B TRIP OVERVH..W:

This test was performed to demonstrate the functionality of the LOSS OF RHR SDC DUE TO RHR-P-2B TRIP Malfunction. The following annunciators alarmed: RHR B PUMP TRIP, RHR B PUMP OVERLOAD RHR B/C PUMP RUNNING, RHR B OOS, and RHR BISI CB-RHR2B OUT OF SERVICE Bluminated. Reactor Coolant showed a slow increase in temperature as indi-cated on RRC-TR-650 88 RRC-TRS-601. Proper response on activation of the Loss of SDC Due to RHR-P-23 Trip malfunction was tested and verified.

INITIALCONDITIONS: IC-1 Cold Shutdown FINAL CONDITIONS: IC-1 Cold Shutdown SOURCE OF COMPARISON DATA:

PLANT DATA SET ENGINEERING EVALUATION FSAR

[7 SUER I LEE g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACI'OKY'WITHDISCREPANCIES TEST RESULTS SATISFACI'ORY WITHOUT DISCREPANCIES

TEST CATEGORY: Plant Malfunction TEST No. 14.4.9.24.2 REV. 0 TITLF'ONDENSATEBOOSZZR PU>MP 2A TRlP OVERVII W:

This test was performed to demonstrate the functionality of the CONDENS~ BOOSTER PUMP 2A TRIP Malfunction. Electrical Malftmction causes pump trip. System responses included:

booster motor amps decreased, appropriate alarms occur, booster pump discharge HDR pressure decreases, RFW pump suction pressure decreases, and RFW pumps trip. Proper response on activa-tion of thc CONDENSATE BOOSTER PUMP 2A Trip was tested and verified. NOTE: RFPT'IHIP evaluated per 14.4.9.2.9, REACTOR SCRAM evaluated per 14.4.9.2433, MT/GEN TRIP evalu-ated per 14.4.9.2431, MSIVISOLATIONevaluated per 14.4.103, LOSS OF ALLRFW evaluated pcr 14.4.10.1 INITIALCONDITIONS: IC-12 1009o Power Equilibrium Xenon FINALCONDITIONS: RFW pumps have tripped, Reactor has scrammed.

SOURCE OF COMPARISON DATA:

PLANT DATASET ENOINEERINO EVALU>ZrON FSAR g SUER / LER - 24 g OPERATIONAL ASSESSMENT TEST RESULTS:

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

P TIO TEST CATEGORY: Plant Malfunction TEST No. 14.4.924.5 REV. 0 TITLE: SR PUMP A TRIP OVERVIEW:

This test was performed to demonstrate the functionality of the SW PUMP A TRIP Malfunction.

Electrical fault initiates Motor Overload/Ground. System responses included: Service water Qow decreased, SW PMP A MOTOR OL/GND alaxmed, applicable Service Water Qow annunciators alarmed, and multiple BISI lights Blumittated from systems affected by a loss of Service water Qow.

Proper response on activation of the SW PUMP A TRIP malhntction was tested and vexified INZIIALCONDITIONS: IC-12 100% Power Equilibrium Xenon FINAL CONDITIONS: IC-12 100% Power Equilibrium Xenon SOURCE OF COMPARISON DATA:

PLANT DATA SET ENGINEERING EVALUATION FSAR SOER / LER g OPEIMIIONALASSESSMENT TEST RESULTS:

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

TEST CATEGORY: Plant Malfunction TEST No. 14.4.9.24.15 REV. 0 ITTLE: Sl-I DC GROUND OVERVG:W; This test was performed to demonstrate the functionality of thc Sl-l DC GROUND Malfunction.

Ground on Bus Sl-l, duc to water in the DC control panel. 'Ibis resulted in a ground annunciator on the bus and deBection on thc ground detector meter. The battery charger output amps increased

, until at 400 amps the charger output fuse blew followed-by the battery output fuse and a loss of the bus. System responses included: multiple annunciators, multiple BISI lights illuminated indicating systems out of service, and IN-3 shifted to the altematc A.C. source. AM-B1-1, AM-C1-1, and VM41-1 indicated zero. Motive power was lost to the following loads: CAC-V-(2,6,4,8), RCIC-V-(31, 10, 46, 110, 8, 68), RCC-V-6, RHR-V-40, and MS-V-19. Proper response to the loss of Control and Indication power provided by Sl-l was tested and verified INI'IIALCONDITlONS: IC-12 100% Power Equilibrium Xenon FINAL CONDITIONS: Bus Sl-l de-energized, IN-3 shifted to alternate A.C. power.

SOURCE OF COMPARISON DATA:

Q PLANT DATA SEI'NOINEERINO EVALUATION FSAR (7 SUER HLER g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITH DISCREPi4VCIES TEST RESULTS SATISFACI'ORY WITHOUT DISCREPANCIES

TEST CATEGORY: Plant Malfunction TEST No. 14.4.9.24.15A REV. 0 TITLE: Sl-I TRP OVERVIEW; This test was performed to dcmonstratc thc functionality of the Sl-l TRIP Malfunction. DC Bus S 1-1 Trip. Proper response to the loss of Control and Indication power provided by Sl-l was tested and vcri6ed IAW Attachment EMOTE: All final control board indications and annunciators acti-vated are identical to test 14.4.9.24.15, S1-1 DC GROUND, with the exception of no battery ground annunciator and no ground detection meter deBection.

INITIALCONDITIONS: IC-12 100% Power Equilibrium Xenon FINAL CONDITIONS: Bus S 1-1 de~ergized SOURCE OF COMPARISON DATA:

PLANT DATA SET

[7 ENGINEEIUNG EVALUATION FSAR SOER/LER g OPERATIONAL ASSESSMPNI'EST RESULTS; Q TEST RESULTS UNSATISFACTORY WITH'DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACI'ORY WITHOUT DISCREPANCIES

TEST CATEGORY: Plant Malfunction TEST No. 14.4.9.24.18 REV. 0 TZI7 E: RPS B MG SET TZ/P OVERVII:W:

.This test was performed to demonstrate the functionality of thc RPS B MG SET TRIP Malfunc-tion. 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$ ,3,k4 extinguished, BU Scram amber lights iilutnittated, RPS Bus B power available light extinguished, and APRM groups B,D, and F indicated downscale. An NSSSS inboard and outboard isolation occurred.; Group's 1,2,4,%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 was tested and verified IAW attachment E Proper response on activation of thc RPS B MG SET'IRIP malfunction was tested and verified INK'IALCONDITIONS: IC-12 1009o Power Ettuilibrium Xenon

~ALCONDITIONS: RPS Bus B de~neqpzed, NSSSS inboard and outboard isolation present.

SOURCE OF COMPARISON DATA:

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

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES Q TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Plant Malfunction TEST No. 14.4.9.24.27 REV. 0

'IITLE: MAINSTEAM SAFE2T RELIEF VALVEFAILS OPEN OVERVIEW'his test was performed to demonstrate the functionality of the AN STEAM SAFETY RELIEF VALVE FAILS OPEN Malamction. Mechanical setpoint adjusnnent out of adjustment. System responses included: SRV MS-RV-IA opened, F601-A2-54 SRV OPEN, SRV ACCOUSTICAL VALVEMON DRAWER (MS-RV-1A) SRV cards alarmed and the Bow card indicated 100 percent How. Steamline A How dropped as indicated on RFW-Fl-603A. At the DEB panel, Generator Out-put MW's droIxped. An attetnpt 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 veri6ed.

INIIIALCONDITIONS: IC-12 100% Power Equilibrium Xenon FINALCONDITIONS: 100% Power, SRV open, reduced MW's from Generator SOURCE OF COMPARISON DATA:

PAT SRVTEST g PLANT DATA SEI'NGINEERING EVALUATION g FSAR 15.1.4 SOER / LER g OPERATIONAL ASSESSMENT TEST RESULTS:

Q TEST RESULTS UNSATISFACI'ORY WITH'DISCREPANCIES g TEST RESULTS SATISFACI'ORY WiTH DISCREPANCIES Q TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Plant Malfunctions TEST No. 14.4.9.24.31 REV. 0

'III'LE: bQLlN TURBINE TRIP 0VERVII.W:

This test was performed to demonstrate the functionality of the hQQN TURBINE TRIP malfunc-tion. Electronic malfunction. System responses included: SPAIN GENERATOR tripped, 5QQN TURBINE tripped, Reactor Scrammed with RRC Pumps tripping to 15 Hz. Multiple meter responses on P603, F840, F820, 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 Turbine auxiliaries Rnctioned properly during Turbine coastdown. NOTE: Manual Scram evaluated in 14.4.9.24.33, Generator Trip in 14.4.8.1, MainGen-erator Trip evaluated in 14.4.9.13.1 INGLE. CONDITIONS: IC-1,2 1009o Power with Equilibrium Xenon FINAL CONDITIONS: Reactor has Scrammed, Main turbine has tripped SOURCE OF COMPARISON DATA:

PLANT DATA SEI'NGINEEIUNG EVALUATION g FSAR .2 85-002, 01/01/85 QX SUER I I.ER X OPERATIONAL ASSESSMENI' TEST RESULTS:

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

TEST CATEGORY: Plant Malfunction TEST No. 14.4.9.24.34 REV. 0 TITLE: RECIRCULATIOlVPUMP 8 TRlP OVERVIEW This test was performed to demonstrate the functionality of the RECIRCULATION PUMP B TRIP Malfunction. Pump Motor ovezcuzrent due to electrical fault. System responses included: Multiple JP meter response IAW test procedure, RRC B Loop JP Qow deczeased to zero and then increased as zevezse Qow, RRC A Loop JP Qow increased as RRC B loop entered reverse Qow, appropziate annunciators alarmed, and total coze Qow and core DP decreased as indicated on MS-DPR/FR413.

Reactor power decreased as indicated on IRM/APRM recorders. RPV level increased as indicated on RFW-LR-608. Simulator Data was collected and evaluated as SPVS File 14.4.9.24.34, RRC B PUMP TRIP. Proper response on activation of the Recirculation Pump B Trip malfunction was tested and veriQed.

INITIALCONDITIONS: IC-12 100% Power with Equilibrium Xenon FINAL CONDITIONS: Reactor Plant in Single Loop at reduced power SOURCE OF COMPARISON DATA:

g PLAPIT DATA SEI'NGINEERING EVALUATION 15.3.1 g FSAR S GER / LER g OPERATIONAL ASSESSMENT TEST RESULTS:

TESI'ESULTS UNSATISFACI'ORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACI'ORY WITHOUT DISCREPANCIES

TEST CATEGORY: Plant Mal6mction TEST No. 14.4.9.24.37A REV. 0 TITLE: HPCS-V-4 FAILS OPEN OVERVIEW:

This test was performed to demonstrate the functionality of the HPCS-V4 FAILS OPEN Malfunc-tion. Thermal binding results in valve seizure. HPCS system was initiated. Once HPCS-V4 was open the malfimction was initiated. System response included: HPCS-V4 did not close after plac-ing 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-V4 Fails Open was tested and vai-Ged.

INI'ITALCONDITIONS: IC-12 100% Power Equilibrium Xenon FINALCONDITIONS: IC-12 100% Power EquiTibrium Xenon SOURCE OF COMPARISON DATA:

PLANT DATA SEI'NGINEERING EVALUATION SUER HLER g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACI'ORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WTI'HOUT DISCREPANCIES

TEST CATEGORY: Plant Mauunction TEST No. 14.4.9.24.40 REV. 0 TITLE: 27JRBIiYE BYPASS VALVE(BPV-I) FAILURE OVERVH:W:

This test was performed to demonstrate thc functionality of the TURBINE BYPASS VALVE(BPV-

1) FAILURE Malfunction. 'Ihennal binding results in valve seizure. Test was activated by going to BPV MANUAL and depressing the BPV RAISE at the 'BWR DEH panel on P820. System responses included: BPV TRACK increased, BPV-1 position remained at zero; BPV-(2),4) opened, MWE on DEH TURBINE CONTROL decreased, BPV-(2P,4) open lights energized, and BPV-1 closed light remained eneqpzed. The Govcmor valve additive position decreased and the GV's closed to maitrtain sctpoint pressure.

INZITALCONDZTIONS: IC-12 100% Power Etpilibrium Xenon FINALCONDITIONS: BPV's(2$ ,4) arc open, BPV-1 is shut, MWE has decreased by approximately 21%.

SOURCE OF COMPARISON DATA:

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

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

TEST CATEGORY: Plant Malfunction TEST No. 14.4.9.24.40A REV. 0 TITLE: TURBINE BYPASS VALVE(BPV-2) FAIL,URE OVERVIEWt This test was performed to demonstrate the fitnctionality of the TURBINE BYPASS VALVE(BPV-

2) FAILURE Malfunction. Thermal binding results in valve seizure. Test was activated by going to BPV MANUAL and depressing the BPV RAISE at the B.WR DEH panel on P820. System responses included: BPV TRACK increased, BPV-2 position remained at zero, BPV-(1),4) opened, MWE on DEH TURBINE CONTROL decreased, BPV-(1$ ,4) open lights energized, and BPV-2 dosed light tentained energized. The Governor valve additive position decreased and the GV's closed to maintain setpomt pressure. Proper response on activation of Turbine Bypass Valve (BPV-2) Failure was tested and verified.

INTIIALCONDITIONS: IC-12 100% Power Equilibrium Xenon FINAL CONDITIONS: BPV's-(13,4) are open, BPV-2 is shut, MWE has decreased by approximately 21%.

SOURCE OF COMPARISON DATA:

PLANT DATASEE ENOINEERINO EVALUATION FSAR g SUER HLER 84-056 84-044,84-104 g OPERATIONAL ASSESSMENT TEST RESULTS:

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

TEST CATEGORY: Plant Malfunction TEST No. 14.4.9.24.40B REV. 0 TITLE: TURBINE BYPASS VALVE(BPV-3) FAILURE OVERVIEW:

This test was performed to demonstrate the functionality of the TURBINE BYPASS VALVE(BPV-

3) FAILURE Ma16mction. Thermal binding results in valve seizure. Test was'activated by going to BPV MANUAL and depressing the BPV RAISE at the B.WR DEB panel on P820. System responses included: BPV TRACK increased, BPV-3 position remained at zero, BPV-(IP,4) opened, MWE on DEB TURBINE COYIROL decreased, BPV-(1$ ,4) open lights energized, and BPV-3 closed light remained energized. The Governor valve additive position decreased and the GV's closed to maintain setpoint pressure.

INI'TIALCONDITIONS: IC-12 100% Power Ecpnlibrium Xenon F1NAL CONDITIONS; BPV's-(1,2,4) arc open, BPV-3 is shut, MWE has decreased by approximately 21%.

SOURCE OF COMPARISON DATA:

PLANT DATASET ENGINEERING EVALUATION Q FSAR g SORRY LER 84-056 84-044 84-104 g OPERATIONAL ASSESSMENT TEST RESULTS:

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

TEST CATEGORY: Plant Malfunction TEST No. 14.4.9.24.40C REV. 0 TZILE: TURBINE BYPASS VALVE(BPVA) FAILURE OVERVIEW This test was perfoaned to demonstrate the functionality of the 'I'URBINE BYPASS VALVE(BPV-

4) FAILURE Malfunction. 'Ihermal binding results in valve seizure. Test was activated by going to BPV MANUAL and depressing the BPV RAISE at the 'B.WR DEH panel on F820. System responses included: BPV TRACK increased, BPV-4 position remained at zero, BPV-(1$ ,3) opened, MWE on DEB TUI&INECONTROL decreased, BPV-(1+,3) open lights energized, and BPV< dosed light remained energized. The Govcmor valve additive position decreased and the GV's closed to maintain sctpoint pressure INITIALCONDITIONS: IC-12 1009o Power Ecpilibrium Xenon FINALCONDITIONS: BPV's-(14,3) are open, BPV-4 is shut, MWE has decreased by approximately 21'.

II SOURCE OF COMPARISON DATA:

PLANT DATA SEI' ENGINEERING EVALUATION FSAR g SUER'ER OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES Q TEST RESULTS SATISFACTORY WITH DISCREPANCIES.

TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Plant iVlalfunction TEST No. 14.4.9.24,43 REV. 0 TITLE: AiViVUlVCIATORFAILURE OVERVII:W:

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. The failure to Annunciate Malfunction was cleared and the False Annunciation nudfunction is activated. The Annunciator is verified to activate, INITIALCONDITIONS: IC-12 100% Power Equilibrium Xenon FINAL CONDITIONS: IC-12 100% Power Equilibrium Xenon SOURCE OF COMPARISON DATA:

Q PLANT DATA SET ENGINEERING EVALUATION Q PSAR SUER / LER g OPERATIONAL ASSESS'iiIENT TEST RESULTS:

Q TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISPACI'ORY WITHOUT DISCREPANCIES

TEST CATEGORY: Plant Malfunction TEST No. 14.4.9.24.48A REV. 0 TITLE: COND-P-IA TRP OVERVIEW:

This test was pezfozmed to demonstrate thc functionality of the COND-P-IA TRIP Malfunction.

Electrical Malfunction'causes pump trip. System responses included: Cond Pump A motor amps decreased, Cond Pumps B 8c C amps inczeased, appropziatc 'alarms occurred, condensate pump dis-charge header pzessuze deczeased, Booster and RFW pump suction pzessuzes deczeased, and RFW pumps tripped. Proper response on activation of the COND-P-1A HIP was tested and vezi6ed.

NOTE:RFPT TRIP evaluated per 14.4.9.2.9, REACTOR SCIL@ evaluated per 14.4.9.24.33, MT/

GEN TRIP evaluated pcr 14.4.9.24.31, MSIVISOLATIONevaluated per 14.4.10.3, LOSS OF ALL RFW evaluated per 14.4.10.1 INITIALCONDITIONS: IC-12 100% Power Btuilibzium Xenon FINAL CONDITIONS: RFW pumps tripped, Reactor has scratnmcd SOURCE OF COMPARISON DATA:

[7 PLANT DATASET ENGINEERING EVALUATION FSAR SUER / LER H OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACI'ORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUTDISCREPANCKS

TEST CATEGORY: Plant Malfunction TEST No. 14.4.9.24.56 REV. 0 TITLE: BAZTERYCEK4RGER Cl-l TRlP OVERVII."VIt'his test was performed to demonstrate the functionality of the BAITERYCHARGER Cl-1 TRIP Malsmction. Activated spurious breaker trip. System responses included: CHARGER C1-1 TROUBLE alarm, other appropriate alarms, dropping DC voltage, AM-C1-1 indicates zero amps, AM-B1-1 indicates about 100 amps. Proper response on activation of Battery Charger C1-1 Trip was tested and verified.

INDI~CONDITIONS: IC-12 100~o Power Equilibrium Xenon FINAL CONDZIIONS: IC-12 1009o Power Equilibrium Xenon SOURCE OF COMPARISON DATA:

PLANT DATA SHI'NGINEERING'EVALUATION FSAR SOER / LER g OPERATIONAL ASS ESSiiIENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Plant Malfunction TEST No. 14.4.9.24.63 REV. 0

'IITLE'EHI'UMP IA TRLP 0VERVIEVIt'his test was performed to demonstrate the functionality of the DEH PUMP IATRIP Malfunction.

Spurious breaker trip. System responses included: DEH-P-IA triI~d, DEH HDR pressure decreased, appropriate annunciators alarmed, and the standby DEH-P-IB auto started at 1800 psig.

Proper response on activation of the DEH-P-1A trip was tested and vcri6ed.

INI'ITALCONDITIONS: IC-12 100% Power EquBibrium Xenon FINALCONDITIONS: Standby DEH-P-1B is running, plant is still at 100% Power SOURCE OF COMPARISON DATA:

PLANT DATA SET ENGINEERING EVALUATION FSAR g SOER I LER H OPERATIONAL ASSESSMENT TEST RESULTS:

TESI'ESULTS UNSATISFACTORY WITH DISCREPANCIES g TESI'ESULTS SATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Plant Malfunction TEST No. 14.4.9.24.64 REV. 0 TITLE: TSW PUMP A TMP OVERVIEW:

.This test was performed to demonstrate thc functionality of the TSW PUMP A TRIP Malfunction.

A piece of the impeller separates from the impeller and wedges between the impeller and the cas-ing. System responses included: TSW-P-IA motor cuxzent increased, TSW-P-lA tripped, appropri-ate alaxms occuxxed, TSW-P-1B staxtcd at less than or equal to 80 psig, TSW-V-53A closes, and TSW'-V-53B opens. The followingTSW Loads responded as follows: TCV's held temperatuxes rel-atively constant, RFP A8cB oil cooler outlet temperature incxcased, Main turbine oil cooler outlet temperature increased, turbine lube oil temperatures increased as indicated on TG-'IRK and TG-TR-144. Dxywell temperanxxe and Containment pressure increased. Proper response on activation of the TSW pump trip was tested and veri6ed.

INITIALCONDITIONS: IC-12 1009o Power Equilibrium Xenon FINAL CONDITIONS: 1009o Power but with higher temperatures on all the loads cooled with TSW SOURCE OF COMPARISON DATA:

PLANT DATASET ENGINEERING EVALUATION PSAR SOER / LER g OPERATIONAL ASSESSMENT TEST RESULTS; TEST RESULTS UNSATISPACI'ORY WITH DISCREPANCIES TEST RESULTS SATISPACTORY WITH DISCREPANCIES P TEST RESULTS SATISPACI'ORY WITHOUT DISCREPANCIES

TEST CATEGORY: Plant Malfunction TEST No. 14.4.9.24.64A REV. 0 TITLE: TSW PUMP B TRlP OVERVIEW:

This test was performed to demonstrate the functionality of the TSW PUMP B TRIP Malfunction, A piece of the impeller separates from the impeller and wedges between the. impeller and the cas-ing. System responses inciudeL TSW-P-1B motor current increased, TSW-P-1B tripped, appropri-ate alarms occurred, TSW-P-1A started at less than or equal to 80 psig, TSW-V-53B closes, and TSW-V-53A opens. The followmg TSW Loads responded as follows: TCV's held temperatures rel-atively constant, RFP ARB oil cooler outlet temperature incteascd, Main turbine oil cooler outlet temperature increased, turbine lube oil temperatures mcreased as indicated on TG-TRES and TG-TR-144. Drywell temperature and Containment pressure increased. Proper response on activation of the TSW pump trip was tested and verifie INI'ITALCONDITIONS: IC-12 100% Power Equilibrium Xenon FINALCONDITIONS: 100% Power but with higher temperantres on all the loads cooled with TSW SOURCE OF COMPARISON DATA:

PLANT DATASET ENGINEERING EVALUATION FSAR SOER HLER Q OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACI'ORY WITH DISCREPMVCIES g TEST RESULTS SATISFACTORY WITH DISCREPANCIES Q TEST RESULTS SATISFACTORY WITHOUTDISCREPANCIES

TEST CATEGORY: Plant Malfunction TEST No. 14.4.9.24.67B REV. 0 TAT.E: RF8'-LI406B FAILS LOW OVERVIEW This test was performed to demonstrate the functionality of the RFW-LI-606B FAILS LOW Mal-function. Level Sensor C34-N004B Fails low. System responses included: RFW-LIM6B indicated downscale, P603-A8-2-8 RFW TURB Control Signal or Level Channel failure alarmed, and FWC sensor A was automatically selectecL The RPV Level Control Channel was manually selected to Channel A and P603-A8-2-8 cleared. Proper response on activation of the RFW-LII06B FAILS LOW malfunction was tested and veri6ed.

INK'IALCONDITIONS: IC-12 100% Power Equilibrium Xenon FINAL CONDITIONS: IC-12 100% Power Equilibrium Xenon SOURCE OF COMPARISON DATA:

PLANT DATA SET ENOINEERINO EVALUATION FSAR g SUER HLER g OPERATIONAL ASSESS~iT TEST RESULTS:

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

TEST CATEGORY: Plant Malfunction TEST No. 14.4.9.24.67C REV. 0

'ITTLE: RFW-LI<06B FAILS HIGH OVERVIEW:

This test was performed to demonstrate the functionality of the RFW-LI-606B FAILS HIGH Mal-function. Level Sensor C34-N004B Fails high. System responses included: RPV Level HIGH/

LOW ALERT alarmed, RPV, high level channel B seal in amber light Qlurninated, RFW/TURBINE RPV level high Trip alarmed, RFW-LI-606B indicated upscale, and RFW-LR-608 indicated upscale. RFW Level Control System, (RFW-LIC-600, RFW4C-601A 8h 601B output demands decreased) causing both RFW Turbines to decrease in speed causing feedwater Qow to decrease to less than steam Sow and RPV/L to drop. At RPV level 3 a Rx SCRAM occurred. Proper response on activation of the RFW-LI-606B FAILS HIGH mal6jnction was tested and vezi6ed XNXITALCONDITIONS: IC-12 100% Power Bpdlibzium Xenon FINAL CONDITIONS: Reactor Scramxned on actual low level.

SOURCE OF COMPARISON DATA:

PLANT DATA SET ENGINEEIUNG EVALUATION:

FSAR SUER HLER g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES Q TEST RESULTS SATISFACTORY WITH DISCREPANCIES .

g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

N VGA TEST CATEGORY: Plant Malfunction TEST No. 14.4.9.24.73 REV. 0 TITLE: SW-V-2B FA1'LS CLOSED OVERVIEW:

This test was performed to demonstrate the functionality of the SW-V-2B FAILS CLOSED Mal-function. Internal electrical failure in the autosyn logic circuit. RHR-P-2B was started using con-trol switch. System responses included: SW-V-2B PUMP DISCHARGE did not open, SW-P-2B DISCH PRESS SW-PI-2B indicated zero, SW-Fl-9B did not increase, and SW-P-2B Amp Ind was less than rated amps for normal operation. Proper response on activation of the SW-V-2B FAILS CLOSED Malfunction was tested and veri6ed.

INITIALCONDITIONS: IC-12 100% Power Equilibrium Xenon FINALCOND1TIONS: IC-12 100% Power Equilibrium Xenon SOURCE OF COMPARISON DATA:

PLANT DATA SET

[7 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 DISCREPANCIES

TEST CATEGORY: Plant Malfunction TEST No. 14.4.9.24.78 REV. 0 TZII.E: ATWSIARIFAILURZ OVERVIEW:

This test was performed to demonstrate the functionality of the ATWS/ARI FAILURE Malfunc-tion. Electrical Malfunction. The ATWS-ABI SYS AAB switches were placed in trip. System responses included: ATWS-ARI TRIP did not alarm, 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 valves indicated closed. Proper response on activation of the ATWS/ARI FAILURE malfunction was tested and verified.

INITIALCONDITIONS: IC-12 1009o Power BImlibrium Xenon FINALCONDITIONS: IC-12 1009o Power BIuilibriumXenon SOURCE OF COMPARISON DATA:

PLANT DATA EVAL'DATION SEI'NGINEEIUNG FSAR

[7 SOERI LEE g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Plant Malfunction TEST No. 14.4.9.24,80 REV. 0

'ITIVE: RPS FAILS TO SCRAM OVERVIEW:

.This test was performed to demonstrate the functionality of the RPS FAILS TO SCRAM Malfunc-tion. The relay armature mechanically seizes. A manual scram was initiated. System alarms that did not initiate included: REACI'OR SCRAM Al AND B 1 LOGIC, I/J2 SCRAM SYSTEM A, REAC-TOR SCRAM A2 AND 32 LOGIC, and lg SCIBQrf SYSTEM B. Allof the SCIVJVl Group Sole-noid lights remained illuminated. 'Ihe Backup SCIVLM lights retnained extinguished. The SDV vent and drain valves remained open. Proper response on activation of the RPS FAILS TO SCRAM malfunction was tested and verified.

'NITIAL CONDlTIONS: IC-12 100% Power Equilibrium Xenon FINAL CONDITIONS: IC-12 100% Power Equilibrium Xenon SOURCE OF COMPARISON DATA:

PLANT DATA SEI'NOINEIEUNO EVALUATION Q FSAR SOER/LER g OPERATIONAL ASSESSiiIENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES T

Q TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Plant Malfunction TEST No. 14.4.9.24.80A REV. 0 TITLE: RPS FAILS TO SCRAM (AUTO)

OVERVII..W:

This test was performed to demonstrate the functionality of the RPS FAILS TO SCI4Qd (AUTO)

Malfunction. The relay atmatutes mechanically be seizing. A MT Trip was initiated. System alarms that did not initiate included: REACTOR SCRAM Al AND'Bl LOGIC, 1/2 SCRAM SYSTEM A, REACI'OR SCRAM A2 AND BZ LOGIC, and 1/2 SCR.AM SYSTEM B. The SCRAM Group Sole-noid lights retnained illuminated. The Backup SCR F84 lights retnained extinguished. The SDV vent and drain valves remained open. System responses included: MT Bypass valves and SRV OPERA-TION CONTROLLED RPV/P, RRC Pumps Tripped to 15Hz via RPT 'IRIP LOGIC, RPV/P HIGH 1037 psig did not hntiate REACI'OR SCRAM, and an ATVfS-ARI TRIP occurred at 1076 psig (causing all rods to scram, vent and drain valves to shut, and reactor to shutdown). Proper response on activation of the RPS FAILS TO SCRAM (AUTO) mal&mction was tested and verified.

INITIALCONDITIONS: IC-12 1009o Power Equilibrium Xenoa FINAL CONDITIONS: ATWS-ARITRIP induced SCRAM at 1076 psig., Reactor is shutdown, Bypasses controlling pressure at setpoint.

SOURCE OF COMPARISON DATA:

P~VI'ATASET ENOINEERINO EVALUATION

[7 FSAR SOER / LER g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPAiVCXES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCES

TEST CATEGORY: Plant Malfunctions TEST No. 14.4.9.25.2 REV; 0 TITLE: RHR-P-2B SE4FT SHEAR OVERVII..Vf:

This test was perfoaned to demonstrate the functionality of the RHR-P-2B SHAFT SHEAR Mal-function. RHR-P-23 Shak Shear break between motor and pump. System responses included:

RHR-P-2B motor amps decreased, RHR-P-2B discharge Qow decreased, disch'arge pressure decreased, and appropriate annunciators alarmed. Proper response on activation of RHR-P-23 Shaft Shear was tested and verified.

INITIALCONDITIONS: IC-12 100% Power with Equilibrium Xenon FINALCONDITIONS: IC-12 100% Power with Equilibrium Xenon, SOURCE OF COMPARISON DATA:

PLANT DATA SET ENGINEERING'VAL'UATION FSAR SUER / LER g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACI'ORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITH DISCREPANCIES P TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TI N RE TEST CATEGORY: Plant Malfunction TEST No. 14.4.9.25.5 REV. 0 TITLE: RHR-P-2A TRIP OVERVIEW:

This test was 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 indi-cated 0, RHR-P-2A Flow indicator approx 20 on RHR-FI-603A, RHR-P-2A Discharge Presstne indicated approximately 10 on RHR-PI-612A, switch lights indicated pump tripped, and appropri-ate annunciators alazmed. Proper response on activation of malfunction RHR-P-2A TRIP was tested and vezifietL M'IALCONDITIONS: IC-12 100% Power with Equilibrium Xenon, RHR-P-2A in Full Flow Test at rated Qow.

FINAL CONDITIONS: IC-12 100% 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 UNSATISFACI'ORY WITH DISCREPANCIES TEST RESULTS SATISFACI'ORY WITH DISCREPANCIES g TEST RESULTS SATISFACI'ORY WITHOUTDISCREPANCIES

TEST CATEGORY: Plant Malfunction TEST No. 14.4.9.25.14 REV. 0 TTTLE: SRV'S - FAIL CLOSED OVERVIEW:

This test was performed to demonstrate thc functionality of the SRV's FAILCLOSED Malfunction.

SRV'S M dosed due to electrical fault. Malftmction was selected on seven ADS valves. Attempts were then made to open the SRV's: Manually ftom P601, arming and depressing DIVI ADS push-buttons, Reyswitches to open on P628 and P631 none of the SRV's opened. Proper response on acti-vation of the individual of thc individual mal&mctions was tested and veriaed IC-12 1009o Power with Equilibrium Xenon FINALCONDITIONS: IC-12 1009o Power with Etpilibrium Xenon SOURCE OF COMPARISON DATA:

Q PLANP DATA SEP ENGINEERING EVALUATION FSAR SUER / LER g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Plant Malfunction TEST No. 14.4.9.25.14A REV. 0 TITLE: SRV~ SLMMERIlVG OVERVIEW:

This test was performed to demonstrate the functionality of the SRV~ SIMMERING Malfunc-tion. Malfunction simulates failure of SRV in such a manner that the valve opens and closes about every 5 seconds, due to mechanical setpoint drift. System rc'sponses included: SRVAC open/close lights cycled every 5 seconds, Acoustic monitor on P851 lit up, appropriate annunciators alatmed.

Manually closing SRV~ Control Switch did not stop thc cycling. Proper response on activation of the SRV~ SIMiMERINGmalf'unction was tested and verified IC-12 100% Power with Equilibrium Xenon FINALCONDITIONS: IC-12 100% Power with Equilibrium Xenon, cycling SRV, MWE small loss and cycling.

SOURCE OF COMPARISON DATA:

PLAIIT DATA SEI'NGINEERING EVALUATION FSAR SUER / LER g OPERATIONAL ASSESSMENT TEST RESULTS:

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

TEST CATEGORY: Plant Malfunction TEST No. 14.4.9.25.15 REV. 0 TITLE: RCC-P-IA, TRIP OVERVIEW'his test was performed to demonstrate the functionality of the RCC-P-IA TRIP malfunction.

RCC-P-lA Trips on Thermal OL due to electrical fault. System responses included: RCC-P-1A 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-IA TRIP ma16mction was tested and vexiiie INDILAL CONDITIONS: IC-12 100%%uo Power with Equilibrium Xenon RCC-P-lA and RCC-P-1B running.

FINAL CONDITIONS: IC-12 1009o Power with Equilibrium Xenon, RCC-P-1B and RCC-P-1C running.

SOURCE OF COMPARISON DATA:

[7 I LANI DATASET ENGINEEIUNG EVALUATION FSAR SUER / LER g OPERATIONAL ASSESSMENT TEST RESUI.TS:

TEST RESULTS UNSASISFACTORY WITH DISCREPANCIES Q TEST RESULTS SATISFACTORY WITH DISCREPANCIES

[g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Plant Malfunction TEST No. 14.4.9.25.19 REV. 0 TITLE: RPS SPURlOUS SCRAM A OVERVIEW This test was performed to demonstrate the functionality of the RPS SPURIOUS SCRAM A Mal-function. Spurious trip ofRPS CHW DIVI 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 annun-ciator alarmed, RPS A Logic Groups IP SCRAM lights on panels P603 and F609 extinguished, and backup SCRAM valve Solenoid lights for RPS A and RPS B Logic illuminate. Proper response on activation of the RPS SPURIOUS SCRAM A malfunction was tested and veri6ed.

INITIALCONDITIONS: IC-12 100% Power with Equilibrium Xenon FINAL CONDITIONS; IC-12 1009o Power with Equilibrium Xenon, 1/2 SCRAM ON RPS A SOURCE OF COMPARISON DATA:

PLANT DATA SEI'7 ENOINEEREIO EVALUATION FSAR SOER/LER g OPERATIONAL ASSESSMENT TEST RESULTS:

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

N RE TEST CATEGORY: Plant Malfunction TEST No. 14.4.9.25.20 REV. 0 TI'ILE: RPS SPUMOUS SCR4M B OVERVIEW:

This test was performed to demonstrate the functionality of the RPS SPURIOUS SCRAiVl B Mal-function. Spurious tzip of RPS CHAL DIVI I/2 SCRAM (due to trip of RPV HIGH PRESS switch).

System responses included: RPV PRESS HI trip annunciator alarmed, 11t2 SCRAM SYS B annun-ciator alarmed, RPS B Logic Groups 1< SCR Aevi lights on panels F603 and P611 extinguished, and backup SCRAM valve Solenoid lights for RPS A and RPS B Logic illuminate. Proper response on activation of the RPS SPURIOUS SCRAM B malfunction was tested and veri6ed.

INITIALCONDITIONS: IC-12 100% Power with Equilibrium Xenon FINALCONDITIONS: IC-12 100% Power with Equilibrium Xenon,l/Z SCIL ON RPS B SOURCE OF COMPARISON DATA:

PLAFIT DATA SEI'NGINEERING EVALUATION FSAR SOER I LEE g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACI'ORY W1TH DISCREPANCIES TEST RESULTS SATISFAC1'ORY WlTH DISCREPANCIES g TEST RESULTS SATISFACI'ORY WITHOUTDISCREPANCIES

TEST CATEGORY: Plant Malfunction TEST No. 14.4.10.40 REV. 0 TITLE: LOSS OF NORMALAND EMERGENCY FW'VERVIEW'his test was performed to verify the Simulators response to a LOSS OF ALL NORMAL and EMERGENCY FW. Thc Reactor Scram, NS4 isolation, RRC pump trip, Loss of normal ECCS and RCIC injection sources was veri6ed. RPV/P was vcri6ed to increase with the subsequent operation of SRV's to control RPV/P at setpoint following thc MSIV isolation. The RPV/L was veri6ed to slowly decrease as the Core is blowndown via SRV operation with no normal or emergency feedwater sources available. SRV operation was veri6ed to diminish as Core Decay heat decreased following the Scram.

Note: Scram details evaluated m 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 14.4.9.23 RFW Break in DW.

INITIALCONDITIONS: IC-12 100% Power Equilibzium Xenon FINAL CONDITIONS: Reactor Shutdown with RPV/P being controlled at setpoint via SRV operation resulting in the core slowly blowing down to the Suppression Pool.

SOURCE OF COMPARISON DATA:

PLANT DATA SEI'7 ENGINEERING EVALUATION FSAR SUER / LER g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES f

g TEST RESULTS SATISFACTORY WITH DISCREPANCIES Q TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

WNP-2 SIMULATOR CERTIFICATION APPENDIX E TRAINING MALFUNCTIONTESTS Attachment E-1 Training Malfunction Test List Attachment E-2 Training Malfunction Test Abstracts

WNP-2 SIMULATOR CERTIFICATION ATTACHMENTE-1 ADDITIONALTRAINING MALFUNCTIONTESTS 07.04.00.05.07- RHR, HPCS, LPCS, RCIC, PI-EFCX-Valve Operability/Shutdown 07.04.00.05.09- RWCU, RRC, RCC, RFW Valve Operability/Shutdown 07.04.00.05.14- CAC Valve Operability 07.04.00.05.16 - Standby Service Water Loop A Operability/Demo 07.04.00.05.17 - Standby Water Service Loop B Operability/Demo 07.04.03.07.05.01 - Accident Manltorfng Instrumentatlan - Channel Check 07.04.04.01.02- Jet Pump Operability 07.04.05.01.07- LPCS System Operability Test 07.04.05.01.08 - RHR Loop A Operability Test 07.04.05.01.10 - RHR Loop C Operability Test 07.04.07.01.01.01 - Standby Service Water Loop A Valve Posmon Vermcatlon 07.04.07.03.03A - RCIC Operability Test <150¹ 07.04.08.01.01.02.05C - Standby Diesel Generator DG2- Loss af Power Test 07.04.08.01.01.02.13- HPCS Diesel Generatar - Semi-Annual 07.04.08.03.02- AC/DC Weekly Breaker Alignment 14.4.9.2.1 - Condenser Tube Leak 14.4.9.2.9B - RFW Turb A - Loss af Control Signal 14.4.9.3.7- RSCS Failure 14.4.9.3.9- Rod Position indication Failure (Present Reed Switch) 14.4.9.3.9A - Rod PosNon Indication Failure (Odd Reed Switch) 14.4.9.3.10 - Rod Worth Minimizer Fails 14.4.9.3.11 - HCU Accumulator Trouble 14.4.9.8.1 - DG-1 Trfp After Auto Start 8 Supplying SM-7 14.4.9.8.1A - HPCS Trfp After Autostart 14.4.9.8.3 - 4160 Vac Bus SM4 OL-GND 14.4.9.8.3C - Overcurrent SM-3 14.4.9.8.4A - DP41-2 Trip 14.4.9.8.6 - Lockout TRS 14.4.9.8.6A - TR-N1 Lockout 14.4.9.8.6B - TR-N2 Lockout 14.4.9.8.6C - TR-M Lockout 14.4.9.8.6D - TR-B Lackout 14.4.9.8.8A - DG-1 Trip High Diff. Current 14.4.9.8.8B - HPCS-DG Trip High Diff. Cunent 14.4.9.8.8C - Output Bkr DG1/7 Fails to Auto Close Page 1 of4

14.4.9.8.8D - Output Bkr DG2/8 Fails to Auto Close 14.4.9.8.8E - DG-2 HI Vlbratfon 14.4.9.8.10 - 480 Vac Bus SL-81 OL-GND 14.4.9.9.4- RCIC Turbfne Trip 14.4.9.9.4D - RCIC Fail to Trip on HI Exh Press 14.4.9.9.4E - RCIC DIV 1 fsol Faifure 14.4.9.9.7- RHR A Supp. Pool Suet. Une Break 14.4.9.14.1A - SRM A Fails High 14.4.9.14.2A - APRM A Falls INOP 14.4.9.1423 - APRM C Fails INOP 14.4.9.14.2C - APRM D Fails INOP 14.4.9.14.5A - IRM A - Fails Downscale 14.4.9.14.58 - IRM 8 - Fails Upscale 14.4.9.14.5C - IRM F - Fafla Upscale 14.4.9.14.5D - IRM A - Fails INOP 14.4.9.14.5E - IRM E Erratic Operation 14.4.9.16.1 - RPS Scram Group Fuses Blown 14.4.9.16.1A - RPS Scram Group Fuses Blown 14.4.9.16.18 - RPS Scram Group Fuses Blown 14.4.9.16.1C - RPS Scram Group Fuses Blown 14.4.9.17.1 - RWCU Leak fn Suctfon Une 14.4.9.17.2A - Leak in RWCU DW Suet Une (W/I PCN) 14.4.9.17.28 - RWCU Demin 8 Plugged 14.4.9.18.2 - Jet Pump Failure 14.4.9.18.3A - instrument Ref. Line Break D0048 14.4.9.18.38 - Instrument Ref. Line Break D004C 14.4.9.18.3C - Instrument Ref. Line Break D004D 14.4.9.18.4- Recirculation Pump Seal Failure 14.4.9.18.68 - Instrument Varfabfe Leg Line Break 14.4.9.18.6C - Instrument Varfable Leg Line Break 14.4.9.18.6D - fnstrument Variable Leg Line Break 14.4.9.18.8- Hl Recirculation Pump A Miratfon 14.4.9.18.8A - Hl Recfrcufatfon Pump 8 Vlbratfon 14.4.9.24.2A - COND-P-28 Trip 14.4.9.24.28 - COND-P-2C Trfp 14.4.9.24.4- CRD A Pump Trfp 14.4.9.24.4A - CRD 8 Pump Trip 14.4.9.24.13 - 480 Vac MCC Trip 14.4.9.24.18A - RPS A MG Set Trip 14.4.9.24.23 - RHR A Pump Shaft Shear Page2of4

14.4.924.34A - Recirculation Pump A Trip 14.4.9.24.36- RHR-V42B Falls Closed 14.4.9.24.37 - HPCS-V< Falls As Is 14.4.9.24.37B - HPCS-VA Falls to Auto Open 14.4.9.24.38- LPCS-V-5 Fails Closed 14.4.924.44- LPCS-P-2 Shaft Shear 14.4.924.44A - LPCS-P-2 Trip 14.4.924.45 - RHR-P-3 Shaft Shear 14.4.9.24.47- HPCS Waterfeg Pump Shaft Shear (P-3) 14.4.924.48 - COND-P-1B Trfp 14.4.9.24 48B - COND-P-1C Trip 14.4.9.24.49 - Master FWLC Fails High 14.4.9.24.54- C1-7 Battery Charger Trfp 14.4.924.54A - CO-1A Charger Trfp 8 Batt. BO-1A Discharge 14.4.9.24.54B - C2-1 Charger Trfp 8 B2-1 Ofscharge 14.4.9.24.57- H2-Side SO Pump Trip 14.4.9.24.58 - Afr<fde SO Pump Trip 14.4.9.24.59- Shaft-Driven LO Pump Failure 14.4.9.24.60 - CRD-FCV-2 Falls Closed 14.4.9.24.63A - DEH Pump 1B Trip 14.4.9.24.67A - RFW-LI-606A Fails As Is 14.4.9.24.67D - RFW-LR06C Falls Hfgh 14.4.9.24.68 - RCIC-VN Fails Open 14.4.9.24.69- RCIC-V-8 Falls Open 14.4.924.72- SLC-P-1 B Fails to Start 14.4.9.24.85A - MS-V-22A - Fails to Close 14.4.924.85B - MS-V-28A - Fails to Close 14.4.9.24.85C - MS-V-28B - Fails to Close 14.4.9.24.85D - MSIV's - Falls to Close 14.4.9.24.85E - MS-V-22B - Fails to Close 14.4.924.85F - MS-V-22C - Fails to Close 14.4.9.24.856 - MS-V-28C - Fails to Close 14.4.9.24.85H - MS-V-28C fnadvertent Slow Closure 14.4.9.24.85I - MS-V-28D fnadvertent Slow Closure 14.4.924.85J - MS-V-28B Inadvertent Slow Closure 14.4.9.25.1 - LPCS-P-1 Shaft Shear 14.4.9.25.1A - LPCS-P-1 Trip 14.4.9.25.3 - RHR-P-2C Shaft Shear 14.4.9.25.4- HPCS-P-1 Shaft Shear 14.4.9.25.6- RHR-V42B Falls Closed Page3of4

14.4.9.25.7- RHR-VIV Fails Ctosed 14.4.925.8 - RHR-P-28 Tifp 14.4.9.25.9 - RHR-P-2C Trip 14.4.9Z5.10 - HPCS-P-1 Trip 14.4.9.25,11 - RHR-V-16A, 168, 17A, 178, Falls Closed 14.4.9.25.12- RCIC-V-13 Fafls to Open 14.4.925.13 - RCIC-VW Falls Ctosed 14.4.929.15A - RCC-P-1 8 Trfp 14.4.9.25.158 - RCC-P-1 C Trfp 14.4.9.25.1 6 - MC-88 Trip 14.4.9.25.18 - ARM/Process Monitor Failures 14.4.9.2521 - LPRM Fails Upscale 14.4.9.2522- RHR-V-42A Faifs Closed 14.4.9.25.23 - CAS-C-1A Loss of Cooling 14.4.92524- TG HP Rotor High Vibration 14.4.9.2526- Generator Hydrogen Pressure Control Failure 14.4.925.26 - RBM CHA Fails Upscale 14.4.9,25.27 - RPV NR Level Recorder Pen Stfcks 14.4.9.2548 - Hl Oxygen ln Containment 14.4.9.25.29 - FWH 1A Tube Rupture 14.4.9.25.30 - RFW Turbines Hl Vtbratfon 14.4.9.25.31 - 5A FWH Loss of Ext. Stm 14.4.9.25.32 - 6A FWH Loss of Ext. Stm 14.4.9.25.33 - RFW<CV-10 Controller Output Fails Low 14.4.9.25.33A - PWLC SU Level Control Falls Low 14.4.9.25.35 - Loss of Press Suppression Function 14.4.925.36;,RWCU Leak In,Equfpment Area 14.4.9.25.37- Hl Hydrogen In Containment 14.4.9.25.38 - BKR S1 Failure to Auto Close 14.4.9.25.39 - S2-1 DC Ground 14.4.9.25.40- RRC Loop A HPU Fuse TH5 Fails 14.4.9.25.41 - RRC-P-1 8 60 Hz Breaker Fails to Trip Page4of4

WNP-2 SIMULATOR CERTIFICATION ATTACHMENTE-2 TRAINING MALFUNCTIONTESTS ABSTRACTS

TEST CATEGORY: Malfunction Tests TEST No. 07.04.00.05.07 REV. 0 TTILE: RHRPHPCS~CSQCIC, PI-EFCX & TIP VALVZOPERABIL/1T - SHUTDOWN OVERVIE%'.

This test was performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures. Proper valve stroking 8h timing were tested and verified.

O'ZH'AL CONDITIONS: In accordance with the testing requirements of the specific Surveillance.

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

SOURCE OF COMPARISON DATA:

PLANT DATASEI' ENGINEERING EVALUATION FSAR SOER / LER OPERATIONAL ASSESSiiNT TEST RESULTS:

TEST RESULTS UNSATISFACI'ORY WITH DISCREPANCIES g TEST RESULTS SATISFACI'DRY WITH DISCREPANCIES Q TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Malfunction Tests TEST No. 07.04.00.05.09 REV. 0 TITLE: RWCU~CgCC etc RFW'ALVEOPERABILlTY- SHUTDOWN OVERVIEW This test was performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures. Proper valve stroking 8'c timing were tested and verified.

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

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

SOURCE OF COMPARISON DATA:

PLANT DATA SET g ENGINEERING EVALUATION'SAR SUER / LER OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSAGSFACI'ORY WITH DISCREPANCIES g TEST RESULTS SATISFACI'ORY WITH DISCREPANCIES Q TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Malfunction Tests TEST No. 07.04.00.05.14 REV. 0 CAC VALVEOPE2biBILITY OVERVIEW This test was performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedutes. Proper valve stroking 8h timing were tested and verificd.

INK'IALCONDITIONS: In accordance with the testing requirements of the specific SurveiHance.

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

SOURCE OF COMPARISON DATA:

I LANTDATASHr g ENGINEERING EVALUATION

'SAR SUER /LER OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUTDISCREPANCIES

TEST CATEGORY: Malfunction Tests TEST No. 07.04.00.05.16 REV. 0 TITLE: STANDBYSERVICE RATER Z,OOP A OPERABILITYDEMONSTRATION OVERVll:W:

This test was performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures. Proper valve stroking 8h timing were tested and verlfietL The systems capabilities were vezified for delivery ofrequired cooling to system loads. Valve stroke timing was taken to veziEy valve operability. Proper system Bow balance was verified.

INH'IALCONDITIONS: In accordance with the testing requirements of the specific Surveillance.

HNAL CONDITLONS: In accozdance with the testing requirements of the specific Surveillance.

SOURCE OF COMPARISON DATA:

PLANT DATA SEI' ENGIPIEERING EVALUATI6PI FSAR Q SUER ILER OPERATIONAL ASSESS'iiIENT TEST RESULTS:

TEST RESULTS UNSATISPACI'ORY WITH DISCREPANCIES g TEST RESULTS SATISFACI'ORY WIIZ'DISCREPANCIES TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Malfunction Tests TEST No. 07.04.00.05.17 REV. 0 TITLE: STANDBYSERVICE WATER LOOP B OPERABILITYDEMONSTRATION 0VERVII:W:

This test was performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures. Proper valve stroking 4 timing were tested and verifiecL The systems capabilities were verified for delivery of required cooling to system loads. Valve stroke timing was taken to verify valve operability. Proper system Bow balance was verified.

INK'IALCONDITIONS: In accordance with the testing requiretnents of the specific Surveillance.

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

SOURCE OF COMPARISON DATA:

Q PLANr DATA SET g ENGINEERING EVALUATION FSAR SUER/LER OPERATIONAL ASSESSi~T TEST RESULTS:

TFST RESULTS UNSATISFACI'ORYWITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES

[7 TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Malfunctioa Tests TEST No. 07.04.03.07.05.01 REV. 0 TITLE: ACCLDEiVTMONITORS INSTRUMEÃTCHA1VNEL CHECK OVERVIEW This test was performed to demonstrate Simulator System OperabiTity in accordance with approved Plant Surveillance Procedutes.The functionality of the Accident Monitoring Instrumentation was demonstrated.

'Ms stroking of all turbine steam valves was conducted to verify valve operability.

~~ CONDITIONS: Plant operating at 80% power or less.

FINALCONDITIONS: Plant operating at 809o power or less.

SOURCE OF COMPARISON DATA:

PLANT DATA SEP g ENGINEERING EVALUATION FSAR SUER I LEE OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY.WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

N TEST CATEGORY: Malfunction Tests TEST No. 07.04.04.0L02 REV. 0 TITLE: JET PUMP OPERABILITY OVERVIEW:

This test was performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures. Proper valve stroking 8h timing were tested and vexi6ed.

This test veri6es that the loop Bows aud jet pump Qows meet the comparison requirements to prove jet pump integrity.

INHTALCONDITIONS: Plant operating at 25% power.

FINAL CONDITIONS: Plant operating at 25% power.

SOURCE OF COMPARISON DATA:

PLANT DATASEI' ENGINEERING EVALUATION FSAR SUER / LER Q OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACI'ORY WITH DISCREPANCXES

[g TEST RESULTS SATISFACTORY WITH DISCREPANCIES P TEST RESULTS SATISFACI'ORY WITHOUT DISCREPANCIES

TEST CATEGORY: Mal&mction Tests TEST No. 07.04.05.01.07 REV. 0 TITLE: LPCS SYSTEM OPERABIIJTY'EST 0VERVII..W:

This test was performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures. Proper valve stroking 8h timing were tested and veri6ed.

HPCS full How testing is ped'ormetL Valve stroke timimg and operability for kcy parameters was tested.

INTIIALCONDITIONS' /A FINALCONDrTIONS: N/A SOURCE OF COMPARISON DATA:

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

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

TEST CATEGORY: Malfunction Tests TEST No. 07.04.05.01.08 REV, 0 TITLE: RPR LOOP A OPERABILlTF TEST OVERVIEW:

This test was performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures. Proper valve stroking dh timing wexe tested and vcri{ied.

RHR How testing for vaxious modes of system operation is tested. Valve stroke timing and operabil-ity for key parametexs was tested.

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

PLANT DATA SEI' EN GINE EIUNG'EVALUATION Q FSAR Q SUER HLER OPEIMIIONALASSESS~iNT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES Q TEST RESULTS SATISFACTORY WITH DISCREPANCIES Q TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Malfunction Tests TEST No. 07.04.05.0L10 REV. 0 TITLE RHR LOOP C OPERABLLI2T TEST OVERVII:W:

This test was performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures. Proper valve stroking 8c timing were tested and veri6ed.

RHR Bow testing for various modes of system operation is tested. Valve stroke timing and operabil-ity for key parameters was tested.

INI'ITALCONDITIONS: IC-12 100Vo power, etluiliberium Xenon FINAL CONDITIONS: IC-12 1009o power, equiliberium Xenon SOURCE OF COMPARISON DATA:

PLANT DATA SEI'g ENGINEERING EVALUATION Q FSAR SOER / LER OPERATIONAL ASSESSMENT TEST RESULTS:

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

ERA N RE TEST CATEGORY: Malfunction Tests TEST No. 07.04.07.01.0L01 REV. 0 TIVE: STANDBF SERVICE WATER LOOP A VALVEPOS1TION VERIFICATION OVERVQ.".7It'his test was performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures. Proper valve strohng 4 timing were tested and verified.

INI'?IALCONDITIONS: In accordance with the testing requirements of the specific Surveillance.

Surveillance.

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

PLANT DATASEI' ENGINEERING EVALUATION FSAR SOERi LER OPEIIATIONALASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Malfunction Tests TEST No. 07.04.07.03.03A REV. 0 TITLE: RCIC OPER48ILITT'PRlOR TO 150 pst'g.

0VERVH.:W:

This test was performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures. Proper valve stroking dh timing were tested and verifie.

Thc system was operated in the How test mode to verify system Bow and discharge pressure for both conditions. A quick start was also performed at rated pressure with parameters verifled to bc within requirements.

INDI'IALCONDITlONS: 1. Rated Pressure

¹

2. 150 Pressurizing FINAL CONDlTIONS: I. Rated Pressure

¹

2. 150 Pressurizing, some small amount of heat from RCIC.

SOURCE OF COMPARISON DATA:

Q FLANT DATA SEI' ENGINEERING EVALUATION Q FSAR SOER / LER OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES

[7 TEST RESULTS SATISFACTORY WITH DISCREPANCIES Q TEST RESULTS SATISFACI'ORY WITHOUT DISCREPANCIES

TEST CATEGORY: Malfunction Tests TEST No. 07.04.08.01.01.02.05C REV. 0 TlTLE: DIESEL GE1YER4TOR 0 2- LOSS OF POWER TEST OVERVIEW:

This test was performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures. Proper valve stroking 8h timing were tested and verified.

This test required the diesel to auto start, come up to speed and voltage auto close onto the respec-tive bus, with a prescribed time, with minimum specified drop in voltage and frequency.

INI'ITALCONDITIONS: N/A FINALCONDITIONS: N A SOURCE OF COMPARISON DATA:

Q PLANT DATA SEI' ENGINEERING EVALUATION FSAR SOER / LER

[7 OPERATIONAL ASSESSMENT TEST RESULTS:

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

TEST CATEGORY: Mal&mction Tests TEST No. 07.04.08.01.01.02.013 REV. 0 TITLE: PCS DIESEL GEiYER4TOR SEMI-AlVNUALOPERABLLITF TEST OVERVIEW This test was performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures. Proper valve stroking 8h timing were tested and verified.

This test verifie the load carrying capability of the Diesel Generator.

INZIIALCONDTITONS: N/A

'INAL CONDrrrONS: N/A SOURCE OF COMPARISON DATA:

PLANT DATA SET g ENGINIEEIUNG EVALUATION FSAR SOER /LER OPERATIONAL ASSESSMENT TEST RESULTS:

Q TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACI'ORY WITHOUT DISCREPANCIES.

TEST CATEGORY: Malfunction Tests TEST No. 07.04.08.03.02 REV. 0 TITLE: ACIDC WEEELEF BREAZER ALIG1VMENT OVERVIEW This test was performed to demonstrate Simulator System Operability in accordance with approved Plant Surveillance Procedures. Proper valve stroking 8c timing were tested and veriGed.

Breaker alignments were checked and verified for a normal station lineup and auto power seeking transfer tests were conducted to verify correct operability.

INZITALCONDITIONS: N/A FINALCONDITIONS: NIA SOURCE OF COMPARISON DATA:

PLANT DATASEI' ENGINEERING EVALUATION FSAR SUER / LER OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES Q TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Malfunction Tests TEST No, 14.4.9.2.1 REV. 0 TIVE: CONDENSER TUBE LZAZ OVERVIEW:

This test was performed to demonstrate the functionality of the CONDENSER TUBE LEAK Mal-function. Corrosion causes condenser tube leak. System responses included: Conductivity recorder CONDOR-1 indicated an increase in conductivity on some'f the points, 1 thru 14, P840-A345 MAINCONDSR CONDUCI'IGH alarmed at GE 9 micromhos, conductivity recorders RWCU-CR401 and RWCU-CR403 showed an increasing conductivity trend, and FILTER DEMN INFLUENT and EFFLUENT annunciators alarmed. Proper response on activation of the CON-DENSER TUBE LEAKmalfunction was tested and vexified.

2'lI'ITALCONDITIONS: IC-12 100% Power with Equilibrium Xenon FINAL CONDITIONS; IC-12 100% Power with Equilibrium Xenon SOURCE OF COMPARISON DATA:

PLANT DATASET ENGINEEIUNG EVA'L'UATION FSAR X SUER / LER g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES H TESI'RESULTS SATISFACTORY WITH.DISCREPAiVCIES TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

N TEST CATEGORY: Naif'unction Tests TEST No. 14A.9.2,9B REV. 0 TITLE: RFW TURB' - LOSS OF CONTROL SIGNAL OVERVIl.:W:

This test was performed to demonstrate the functionality of the RFW'I'URBINE A LOSS OF CON-TROL SIGNAL Malfunction. Circuit failure results in Loss of Control Signal to RFW TURB A.

System responses included: RFW-DT-1A LOSS OF CONTROL SIGNAL amber light illuminates and F603-A8-2.8 RFW TURB CONTROL, SIGNAL FAIL/ or LEVEL CH FAIL alaaned. REAC-TOR POWER was reduced to 90% with the following system responses: RFW TURB A SPEED and DISCH PRESSURE did not change, RFWQC-601A output did not change, RFW-SC401B output decreased with the decrease on RFW-LIC-600, and RFW/T B SPEED and DISCH PRESS decreased with the power decrease. Proper response on activation of RFW TUI&INEA LOSS OF COÃlROL SIGNAL malhmction was tested and vened.

INZIIALCONDITIONS: IC-12 1009o Power with Equilibrium Xenon FINAL CONDITIONS: 90% Power with RFW TURB A at constant speed and RFW TURB B at a slower speed controlling feed Qow.

SOURCE OF COMPARISON DATA:

PLANT DATASET ENGINEERING EVALUATION FSAR SUER / LER g OPERATIONAL ASSES SMART TEST RESULTS:

Q TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES H TEST RESULTS SATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

NAL TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.3.7 REV. 0 TXILE: RSCS BFPASS OVERVIEW:

This test was performed to demonstrate the functionality of the RSCS BYPASS Malfunction. The RSCS is completely BYPASSED using EOP 55.11 (installing a jumper). Inserting a Control Rod not in the selected group, system responses included: did n'ot initiate an insert block, Rod Block indication benchboard did not illuminate, and LPSP LED on Rod Sequence Controller Qluminated.

Proper response on activation of the RSCS BYPASS malfunction was tested and vexi6ed.

INITIALCONDlTIONS: IC-7 HEATUP AT 850¹ FINALCONDITIONS: IC-7 HEATUP AT 850¹ SOURCE OF COMPARISON DATA:

PLAiVTDATA SEI'NGINEERING EVALUATION FSAR Q SUER ILER g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITH'DISCREPANCIES Q TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: MalRnction Tests TEST No. 14.4.9.3.9 REV. 0

'IITLE'ROD POSITION INDlCATIONFAILURE(PRESENT REED SWITCH)

OVERVIEW:

This test was performed to demonstrate the fonctionality of the PRESENT REED SW FAILS TO OPEN malhtnction. Proper response in the form of withdraw and insert blocks were tested and ver-ified. The rod position indication was verified lost for the selected ROD on the four rod display.

INITIALCONDITIONS: IC-7 HEATUP AT 85(Q FINALCONDITIONS: IC-7 HEATUP AT 8SOO SOURCE OF COMPARISON DATA:

PLAiVl'ATASET ENGINEEIUNG EVALUATION Q FSAR SUER I LEE OPERATIONAL ASSESSMENT TEST RESULTS:

Q TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES

'7 TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

N TEST CAIZGORY: Malfunction Tests TEST No. 14.4.9.3.9A REV. 0 TJTLE:ROD POSITION INDICATIONFAILURE (ODD REED SRVTCH)

OVERVI1:W; This test was performed to demonstrate the functionality of the NAYREED S%'AILS TO CLOSE malfunction. Proper response in the form of withdraw and insert blocks were tested and verified. The rod position indication was verified lost for the selected ROD on the four rod display.

INITIALCONDITIONS: IC-7 HEATUP AT 850¹ FINALCONDITIONS: IC-7 HE@IMP AT 850¹ SOURCE OF COMPARISON DATA:

[7 PLANT DATASET Q ENGINEERING EVALUATION FSAR SUER HLER g OPIBIAI'IONALASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WII'HDISCREPANCIES TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

OP NAL VH:W U TEST CATEGORY: Malfunction Test TEST No. 14.4,9.3.10 REV. 0 TITLE: ROD WORTP MI1VIMIZERFAILS OVERVIEW:

Th' f '

f KIH~PAILS Malfunction. A parity checlc error causes the RWM to go INOP. System responses included: P603-A7-2.7 ROD OUT BLOCK alarmed, INSERT BLOCK and WITHDRAWNBLOCK lights Blumi-nated on the (Reactor Control Console and on RWM Console). Proper response on activation of the Rod Worth Minimizer Fails malfunction was tested and verified.

INIITALCONDITIONS: IC-7 HEAT UP e 8500 FINALCONDITIONS: IC-7 HEAT UP 85%

SOURCE OF COMPARISON DATA:

[7 PLANT DATA SEr ENGINEERING EVALUATION FSAR SUER / LER g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST ~GORY: Malfunction Tests TEST No. 14.4.9.3.11 REV. 0 TITLE:HCU ACCUMULATORTROUBLE OVERVIEW:

This test was performed to demonstrate the functionality of the ROD 22-03 ACCUM malfunction. Proper response to low accumulator pressure was tested for multiple loca-tions and verified correct.

INI'ITALCONDITIONS: IC-12 100% Power with Equilibrium Xenon FINALCONDITIONS; IC-12 100% Power with Equilibrium Xenon SOURCE OF COMPARISON DATA:

PLANT DATA SET ENGINEERING EVALUATION FSAR SOER / LER g OPERATIONALASSESSMENT TEST RESULTS:

g TEST RESULTS UNSATISFACIORYWITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.8.1 REV. 0 TITLE: DG>>I TRIP AF1ZR AUTO START AND SUPPLYING SiM-7 OVERVIEW:

This test was performed to demonstrate the functionality of the DG-1 TRIP AFTER AUTO START and SUPPLYING SM-7 Malfunction. Clogged fuel lines cause trip. Bh CB-7/1 was opened, system responses included: DG-1 auto started and carried SM-7 for thirty seconds, DG-1 then tripped, SM-7 Voltage and Amp meters dropped to zero. Annunciators P800-Cl-(DG-1 BKR 7DG1 TRIP, BUS 7 UV 69% INSTANT TRIP, BUS 7 UV 87% DELAYTRIP, DG-1 LOCAL PA5IH. ALARM,BUS 75 UNDERVOLTAGE) alarmed. Proper response on activation of DG-1 TRIP after auto start malfunction was tested and verified.

INK'IALCONDITIONS: IC-12 100% Power with Equilibrium Xenon FINAL CONDITIONS: SM-7 de~nergized, 1/2 Scram on A system.

SOURCE OF COMPARISON DATA:

PLANT DATA SEI'NGINEEIUNG EVALUATION FSAR SUER iLER Q OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITH DISCREPANCIES Q TEST RESULTS'SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.8.1A REV. 0 TITLE:&PCS TREP AFTER AUTO START AND SUPPLY1NG SMA OVERVIEW'his test was performed to demonstrate the functionality of the HPCS TRIP AFTER AUTO START and SUPPLYING SMQ Malfunction. Clogged fuel lines cause trip. Bkr CB 4-2 was opened, system responses included: HPCS auto started and carried SMA for thirty secondsgiPCS DG then tripped, SMX Voltage and Amp meters dropped to zero. Annunciators P601-Al- (HPCS SYSTKd UND-ERVOLTAGE, DIESEL ENGINE TRIP, DG LOCAL PANEL ~EM, 480 V SYSTEM UNDER-VOLTAGE, HPCS WATER.EG PUMP DISCH PRESS LOW, 8h HPCS OUT OF SERVICE) alarmed. Proper response on activation of HPCS TRIP after auto start malf'unction was tested and verified.

INK'IALCONDITIONS: IC-12 100% Power with Equilibrium Xenon HNAL CONDITIONS: SMA dewnergized, 100% Power SOURCE OF COMPARISON DATA:

PLANT DATA SEI'NOINEERINO EVALUATION FSAR SUER / LER g OPERATIONAL ASSESSMRIT TEST RESULTS:

TEST RESULTS UNSATISFACI'ORY WITH DISCREPANCES g TESI'RESULTS SATISFACTORY.WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Malfunction Test TEST No. 14.4.9.8.3 REV. 0 TITLE: 4260 T AC BUS SiVN OVERCURRENT - GRND OVERVIEW:

This test was performed to demonstrate the functionality of the 4160 VAC BUS SM-8 OVERCUR-RENT - GRND Malfunction. Electrical insulation failure causes a ground and overcuzzent on SM-

8. System responses included: appropriate annunciatozs alarmed, bkr 8-3 tripped open and was locked out, bkr B-8 open, 8-DGZ open, (volt and amp) meters on SM-8 and her daughter buses indi-cated zero readings, DG-2 auto-started and was running unloaded without SW cooling, TSW-P-lA started on low pressure, RPS bus B half-SCRAM occuzzed, and with only RCC-P-lA running RCC heat loads increased in temperature. Proper response to the loss of motive power provided by SM4 and her daughter busses was tested and verified. Proper response to the loss of control and indica-tion power provided by SM-8 and her daughter busses was tested and verified INH'IALCONDITIONS: IC-12 100% Power with Equilibrium Xenon FINALCONDITIONS: 100% Power, 1/2 Scram B channel of RPS SOURCE OF COMPARISON DATA:

Q PLANT DATA SET ENGINEEIUNG EVALUATION FSAR SUER I LEE g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITH DISCREPANCIES Q TEST RESULTS SAHSFACI'ORY WITHOUT DISCREPANCIES

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.8.3C REV. 0 TITLE: OVERCURREiVT SIV-3 OVERVII..W:

This test was performed to demonstrate the functionality of the 4160 VAC BUS SM-3 OVERCUR-REN'I'alhmction. Overcunent 8h Lockout Condition of Bus SM-3 system, responses included:

appropriate annunciators alaxmed, bkr N1-3 tripped open and was locked out, bkr 3-31 tripped and locked out, bkrs (3-8,8-3@1-3) tripped, (volt and amp) meters on SM-3 indicated zero readings, bkr verified.

31-21 autmlosed to energize SL-31, DG-2 auto-started and was running unloaded, bkr B-8 closed and supplied SM-8. Proper response to the loss of motive power provided by SM-3 was tested and NOTE: LOSS OF BUS SM-8 is evaluated in 14.4.9.8.3.

AXIALCONDITIONS: IC-12 100% Power with Ettuilibrium Xenon FINAL CONDITIONS: One third of the Condensate system capacity has been lost and willcause a subsequent reactor SCRAM.

SOURCE OF COMPARISON DATA:

Q PLANT DATA SET ENGINEERING EVALUATION FSAR Q SUER/LER g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFAC1'ORY W1TH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Malfunction Test TEST No. 14.4.9.8.4A REV. 0 TITLE: SP<<SI-2 TRIP OVERVIEW:

This test was performed to demonstrate the functionality of the DP S1-2 TRIP Malfunction. Battery Bl-2 OOS with disconnect switch open simultaneous with'Battery Charger Cl-2 failure. System responses included: Appropriate Annunciator alarms, applicable BISI panel alarms, IN-2 shifted to the alternate ac source, ampmeters (AM-B1-2 4 AM-CI-2) indicated zero, and VM-S1-2 indicated zero. Proper response to the loss of motive power provided by DP-S1-Zwas tested and verifie for the following loads: RCIC-V-113 and CAC-V- (11,13,1S,17). Proper response to the loss of contml and indication power provided by DPQ1-2 was tested and verified.

INITIALCONDITIONS: IC-12 100% Power with Equilibrium Xenon FINALCONDITIONS: RCIC and CAC systems OOS, numerous indications OOS.

SOURCE OF COMPARISON DATA:

PLANT DATA SEI'NGINEERING EVALUATION Q SUER ILER g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACI'ORY WITH DISCREPANCIES.

Q TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.8.6 REV. 0 TITLE: T2bhVSFORMER LOCEOUT TRN OVERVIEW'his test was perfotmed to demonstrate the functionality of thc 'HVQCSFROMER LOCKOUT TR-S Malfunction. 86TS actuates on phase differential current. XFMR 'IRQ LOCKOUT TRIP alarmed and simulator was frozen at TW sec. System responses included: appropriate alaxms, multiple (amp 8h volt) meters indicated zero, and wattmeters WM-'IRS-(X,Y) indicated zero. The followmg break-ers opened: 500 KV bkts, N bkrs, Tie bkrs (1-7, 2A, 4-2, and 3-8), 2 sec later 7-1 and 8-3, Tie bkrs (1-11, 2-21, and 3-31), and Tie bkrs (75-72 and 85-82). Bkrs B-7 dh B-8 closed and RCC-P-lA and RCC-P-1B restarted. AT least onc TR4 differential phase relay tripped. Proper response to the loss of motive, control, and indication power was tested and verified or identified as previously tested and verified. Simulator was returned to run: EDG-(ldh2) ran unloaded and EDG-3 eneqjzed SM4 INH'IALCONDITIONS: IC-8, 20% Power FINALCONDITIONS: Major Electrical Busses de-energized, Reactor Scrammed.

SOURCE OF COMPARISON DATA:

PLANT DATA SEI'NGINEERING EVALUATION FSAR 87-018 6/26/87 g SOER(LER QX OPERATIONAL ASSESSMENT TEST RESULTS:

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

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.8.6A REV. 0 TITLE: TR-Nl LOCEOUT OVERVIEW This test was performed to demonstrate the functionality of the TR-Nl LOCKOUT Malfunction.

System responses included: XFMR TR-Nl LOCKOUTTRIP annunciated and Unit Prinuuy Lockout (86XU) and 86XlU actuatecL System responses included: 'Dubine Trip (20 AST), all N Supply Bkrs Tripped 4 Locked out, Supply Bkrs Closed, 500 KVBkrs Tripped, Exciter Qe1d Circuit Bkr Tripped, and Oscillograph started. Normal XFMR TR-(Nl 8h N2) Power meters read zero. Relay, 86TN1 Tripped, Flag 03, and white light extinguished. Proper response on activation of the V.-N1 LOCK-OUT malfunction was tested and veri6ed.

NOTE: Main TG Trip evaluated in 14.4.9.13.1 Main Gen Trip evaluated in 14.4.9.24.31 INEQUAL CONDITIONS: IC-12, 100% Power FINALCONDITIONS: Turbine Tripped, Reactor Scrammed SOURCE OF COMPARISON DATA:

PLANT DATA SEF ENGINEEIUNG EVALUASION FSAR SOER / LER g OPERATIONAL ASSESSMENT TEST RESULTS:

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

REVH:W TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.8.6B REV. 0 TITLE: TR-1V2 LOCKOUT OVERVII:W:

This test was performed to demonstrate the functionality of the TR-N2 LOCKOUT Malfunction.

System responses inciuded: XFMR TR-N2 LOCKOUT 1RIP annunciated and Unit Primary Lock-out (86XU) and 86XIU acmated. System responses included: Turbine Trip (20 AST), all N Supply Bkrs Tripped 8h Locked out, Supply Bkrs Closed, 500 KV Bkrs Tripped 2 Lockout, Exciter Beld Circuit Bkr Tripped, and OsciHograph started. Normal XFMR TR-(Nl dh N2) Power meters read zero. Relay, 86TN2 Tripped, Flag O3, and white light extinguished. Proper response on activation of the TR-NZ LOCKOUT nnQfunction was tested and verified.

NOTE: Main TG Trip evaluated in 14.4.9.13.1 Main Gen Trip evaluated in 14.4.9.24.31 INI1IALCONDITIONS: IC-12, 1009o Power FINAL CONDITIONS: Main Generator Tripped, Reactor Scranuned SOURCE OF COMPARISON DATA:

PLANT DATA SEI'NGINEERING EVALUATION FSAR SOER / LER g OPEIMTIONALASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WlTH DISCREPANCIES g TEST RESULTS SATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WlTHOUT DISCREPANCIES

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.8.6C REV. 0 TITLE:TR-cM LOCEOUT 0VERVQ":W:

Ms test was perfotmed to demonstrate the functionality of the TR-M LOCKOUT Malfunction.

hQ~ XFMR BANKLOCKOUT TRIP annunciated and Unit Primary Lockout (86XU) and 86XIU actuated. System responses included: Turbine Trip (20AST), all N Supply Bkrs Tripped and Locked out, Supply Bkrs Closed, 500 KV Bkrs Tripped, Exciter field Circuit Bkr Tripped, and Oscillograph started. TR-M Lockout Relay, 8KV4 trudged and white light extinguished. Proper response on acti-vation of the TR-M LOCKOUT mal6mction was tested and verified.

NOTE: Main TG Trip evaluated in 14.4.9.24,31 INDIIALCONDITIONS: IC-12, 100% Power FINALCONDITIONS: Main Generator Tripped, Reactor Scrammed SOURCE OF COMPARISON DATA:

PLANT DATA SEI' ENGINEERING EVALUATION FSAR SOER / LER g OPEIIATIONALASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCES g TEST RESULTS SATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.8.6D REV. 0 TITLE: TR-B LOCEOUT OVERVIEW This test was performed to demonstrate the functionality of the TR-B-I.OCKOUT Malfunction. TR-B LOCKOUT on sudden pressure. 2GMR TR-B LOCKOUT TRIP and XFMR TR-B UNDER VOLATAGE annunciated. BKRs (B78638) tripped and BACKUP XFMR BKR (B7, B8) 'IRIP annunciators alarmed. DG-1 started and closed in on Siif-7. DG-2 started and closed in on SM-8.

Appropriate annunciators ahumed and Oscillograph started. The following meters read zero: 'IR-B MEGAWAITS, TR-B KILOAMPS (OA,OB,OC), and BUS (7, 8) BACKUP FEEDER KVOLTS.

TR-B Lockout Relay, 8873 Tripped and the white light extinguished. Proper response on activation of the TR-B LOCKOUT malf'unction was tested and veri6ed.

NOTE: DG response and closure on to Bus 7 4 8 is covered in 14.4.9.8.7 INTIIALCONDITIONS: IC-12, 1009o Power FINALCONDITIONS: Reactor has Scrammed, Main Generator Tripped.

SOURCE OF COMPARISON DATA:

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

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACI'ORY WITH DISCREPANCIES 0 TEST RESULTS SATISFACI ORY WITHOUT DISCREPANCIES

TEST CATEGORY: Malfunction Test TEST No. 14.4.9.8.8A REV. 0 l

TITLE:DG TRIP - HIGH DIFFERENTIALC URRZ1VT OVERVIEW This test was performed to demonstrate the functionality of the DG 1 TRIP - HIGH DIFFEREN-TIALCURRENT Malfixction. Defective electrical insulation causes high phase-to-phase differen-tial current. System responses included: appropriate annunciators alarmed, CB-7DG1 tripped, Bkr DG1-7 tripped, and EDG1 control room indications failed to zero. Proper response on activation of High Differential Current on DG1 and attendant loss of power to SM-7 was tested and verified.

NOTE: Response to the loss of motive, control, and indication power provided by SM-7 are evaluated in Test No. 14.4.9.83A (LOSS OF POWER TO SM-7).

INTIIALCONDITIONS: IC-12 100% Power and Flow with Equilibrium Xenon FINAL CONDITIONS: SM-7 is de~nergized and a half scram has occurred on RPS-A SOURCE OF COMPARISON DATA:

PLANI'ATA SEI'NGINEEIUNG EVALUATION FSAR SOER / LER g OPERATIONAL ASSESSMENT TEST RESULTS:

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

P TEST CATEGORY: Malfunction Test TEST No. 14.4.9.8.8B REV. 0 TTILE: HPCS DG TRlP-HIGH D1FFERE1VTIAL CURRE1VT OVERVIEW:

This test was performed to demonstrate the functionality of thc HPCS DG TRIP- HIGH DIFFEREN-TIAL CURIKNT Malfunction. System responses included: P601-A1-3.3 DIESEL ENGINE VIP alarmed, Bkr CBADG3 trq~d, F601-A1-5.2 HPCS GENERATOR OVERCURRENT alarmed, READY FOR AUTOSTART light over thc Diesel Control Switch extinguished, and EDG3 control room indications failed to zero. Proper response on activation of High Ddferential Current on HPCS DG malfunction was tested and veri6ed.

I'll'GALCONDITIONS: IC-12 1009o Power and Flow with Etluilibrium Xenon FINAL CONDITIONS: SM-4 is de~ergizecL SOURCE OF COMPARISON DATA:

PLANT DATASEP

[7 ENGINEEIUNG EVALUATION Q

SOER/LER g OPERATIONAL ASSESSMENT TEST RESULTS:

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

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.8.8C REV 0 TITLE:DIESEL GENERATOR OUTPUT BREAZER DGI/7 FAILS TO AUTO CLOSE OVERVIEW:

This test was performed to demonstrate the functionality of the DIESEL GENERATOR OUTPUT BKR DGl/7 FAILS TO AUTO CLOSE Malfunction. Breaker DG1/7 fails to auto close when Diesel is started 8'c tries to load BUS 7. After BKR CB-7/1 was tripped, system responses included: DG-1 started, annunciators (BUS 7 LOSS OF VOLTAGE and BUS 7 DEGRADED VOLTAGE) alarmed, BUS 7 (volt and amp) meters read zero, and DGl/7 did not auto close. CB-DG1-7 sync. selector switch was placed in noanal and DG1/7 was manually shut. BUS 7 (volt and amp) indication indi-cated normal readmgs. Proper response on activation of the DG OUTPUT BKR DG1/7 FAILS TO AUTO CLOSE malfunction was tested and veri6ed.

INI'ITALCONDI,IIONS: IC-8 20% Power Ready for Synchronization, Bkr CB-B/7 in PTL to prevent TR-B from loading BUS 7.

FINALCONDITIONS: DG1 was manually paralleled to SM-7.

SOURCE OF COMPARISON DATA:

Q PLANT DATA SEI' ENGINEERING EVALUATION FSAR Q SO~i~

g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACI'ORY WITH DISCREPANCIES TESI'ESULTS SATISFACI'ORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

VIEW TEST CATEGORY: Malfunction Test TEST No. 14.4.9.8.8D REV. 0

'IITLE:DIESEL GENERATOR OUTPUT BREAEER DG2/8 FAILS TO AUTO CLOSE OVERVIEW

'IMs test was performed to demonstrate the functionality of the DIESEL GENEIVZOR OUTPUT BKR DG2/8 FAILS TO AUTO CLOSE Malfunction. Breaker DG2/8 fails to auto dose when Diesel is started 8h tries to load BUS 8. After BKR CB-8/2 was tripped, system responses included.'G-2 started, annunciators (BUS 8 LOSS OF VOLTAGE and BUS 8 DEGRADED VOLTAGE) alarmed, BUS 8 (volt and amp) meters read zero, and DG2/8 did not auto close. CB-DG2-8 sync. selector switch was placed in notmal and DG2/8 was manually shut. BUS 8 (volt and amp) indication indi-cated normal readings. Proper response on activation of the DG OUTPUT BKR DG2/8 FAILS TO AUTO CLOSE malfunction was tested and verified.

INITIALCONDITIONS: IC4 209o Power Ready for Synchronization, Bkr CB-B/8 in PTL to prevent TR-B from loading BUS 8.

FINAL CONDITIONS: DG-2 was manually paralleled to SM-8.

SOURCE OF COMPARISON DATA:

Q PLANT DATA SET ENGINEEIUNG 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

TEST CATEGORY: Malfunction Test TEST No. 14.4.9.8.8E REV. 0 TITLE:DG-2 Hl VIBER4TIOlV OVERVIlDV:

This test was performed to demonstrate the functionality of the DG-2 HI VIBRATIONMalfunction.

Mechanical fault induces DG-2 HI Vibration. System responses included: DG-2 VIB HI, F800-CS-4-1, and DG-2 LOCALPNL Al AZVf,P800-C5-3-1, annunciators alarmed. Proper response on acti-vation of the DG-2 HI VIBRATIONmalfimction was tested and veri6ed.

~GAL CONDITIONS: IC-12 100% Power with Equilibrium Xenon, DG-2 started FINALCONDITIONS: IC-12 100% Power with Equilibrium Xenon, DG-2 started SOURCE OF COMPARISON DATA:

PLANT DATA SEr ENGINEERING EVALUATION FSAR

[7 SOER< LEE g OPERATIONAL ASSESSMENT I

TEST RESULTS:

TEST RESULTS UNSATISFACTORY W1TH DISCREPANCIES

[7 TEsr RESULTS SATIsFAcroRY wrrH DISOREPANOIES g TEST RESULTS SATISFACTORY W1THOUT DISCREPANCIES

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.8.10 REV. 0 TITLE: 480 VAC BUS SL41 OVERCVRRZlVT- GRND OVERVIEW:

This test was pezfozmed to demonstrate the loss of power to Bus SL-81 using malfunction 480 VAC BUS SL-81 OVERCURRENT -GRND. Proper response to the loss of motive power provided by SL-81 and her daughter busses where tested and verified. Proper response to the loss of control and indication power provided by SL-81 and her daughter busses where tested and verifie.

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

FINALCONDITIONS: RWCU sys is offline, RCC temperatures throughout the plant are increasing, and dzywell pressure is slowly inczeasing.

SOURCE OF COMPARISON DATA:

PLANT DATA SEr ENGINEERING EVALUATION FSAR SUER/LER g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFAC1'ORY W1TH DISCREPANCIES Q TEST RESULTS SATISFACTORY W1THOUT DISCREPANCIES

N RE VGA TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.9.4 REV. 0 TITLE: RCIC TURBlNE TRIP OVERVIEW:

This test was performed to demonstrate the functionality of the RCIC TURBINE TRIP Malfunction.

The RCIC turbine trips on electrical overspeed due to misalignment of the overspeed sensor circuit.

System responses included: RCIC TURBINE TRIP alarmed, Turbine (speed, exhaust pressure, Qow, suction press, and discharge press) decreased, RCIC-V- (1 and 19) indicated dosed, RCIC WATER LEG PUMP DISCH PRESSURE LOW, and RCIC LUBE OIL CLR WATER PRESSURE HIGH/LOW annunciators alarmed. Proper response on activation of the RCIC 'I'URBINE TRIP malfunction was tested and vexi6ed.

INZIIALCONDITIONS: IC-12 100% Power with Equilibrium Xenon, RCIC placed in Full Flow Test Mode CST to CST FINALCONDITIONS: IC-12 100% Power, RCIC TURBINE has trippccL SOURCE OF COMPARISON DATA:

Q PLANT DATA SET

[7 ENGINEERING EVALUAIION FSAR g SUER HLER g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.9.4D REV. 0 TITLE:RCIC FALL TO TRLP ON HIEXP PRESS OVERVIEW This test was performed to demonstrate the functionality of the RCIC FAILTO TRIP ON HI EXH PRESS Malfunction. TURBINE EXH PRESS TRIP RELAY FAILURE inhibits the HI EXH PRESS TRIP. RCIC-V-68 EXHAUST KEYLOCK SWITCH was placed to closed, system responses included: RCIC E2QiAUST PRESSURE increased as indicated on RCIC-PI-603, RCIC TURBINE did not trip on HIGH KCHAUST PRESSURE, at 150 psig 1st RUPTURE DISC BLOWS initiating RCIC ISOLATION and TRIP, and appropriate annunciators alarmed. Proper response on activation of the RCIC FAILTO TRIP ON HI EXH PRESS malfunction was tested and verified.

INEQUAL CONDITIONS: IC-12 1009o Power with Equilibrium Xenon, RCIC placed in Full Flow Test Mode CST to CST.

FINAL CONDITIONS: IC-12 1009o Power, RCIC TURBINE has tripped due to RUPI'URE DISC blowing.

SOURCE OF COMPARISON DATA:

PLAPIT DATASET ENGINEERING EVALUATION FSAR SUER HLER g OPERATIONAL ASSESSMENT TEST RESULTS:

TESI'ESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACI'ORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUTDISCREPAiVCIES

YI AL VIEW TEST CATEGORY: Malhmction Test TEST No. 14.4.9.9.4E REV. 0 I

TITLE: RCIC DIV ISOL FAILURE OVERVIEW:

This test was performed to demonstrate the functionality of thc RCIC DIV I ISOL FAILURE Malfunction. RCIC K-15 RELAY (DIV 1 ISOL) mechanically jammed prevents DIV 1 ISOL and TURB TRIP. System responses included: RCIC-V-63 auto closed, applicable annunciators alarmed, RCIC -V-8 failed to dose, RCIC did not trip, RCIC-V-1 and RCIC-V-2 remain open, RCIC STEAM LINE PRESS decreased on RCIC-PI-602, RCIC SYS FLOW coasted down from 600 gpm to zero, RCIC-PI-601 decreased from rated to LT or less than keep fill pressure, and RCIC4I-2 SPEED decreased from rated to zero. Proper response on activation of thc RCIC DIV I ISOL FAILURE malf'unction was tested and verified.

~TALCONDITIONS: IC-12 100% Power with Equilibrium XEnon, RCIC in Full Flow Test to CST.

FINAL CONDlTIONS: IC-12 100% Power, RCIC coasted to zero speed without proper isolation, SOURCE OF COMPARISON DATA:

[7 PLANT DATA SET ENGINEERING EVALUATION FSAR SUER HLER g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

NAL REVUVVv TEST CATEGORY: Malfunction Test TEST No. 14.4,9.9.7 REV. 0 TITLE:RFR A SUPPRESSION POOL SUCTION LINE BRKiE OVERVIEW'his test was performed to demonstrate the functionality of the RHR A SUPPRESSION POOL SUC-TION LINE BREAK Malfunction. A break occurs in RHR-P-2A Suction Line just upstream of pump. System responses included: RHR A (How and pressure) decreased, RHR A motor amps became erratic, P601-A3-2-7 LEAKDEI'EACTOR BLDG Floor Sump R2 Leakage High alarmed, P602-A13-2-1 REACI'OR BLDG Floor Sump Rl Level Hi-Hi alarmed, and Suppression pool level decreased significantly with time. RHR A Pump Room Water Level High, SUPP POOL LEVEL HIGH/LOW, RHR A PUMP DISCH PRESS HIGH/LOW, and RHR A PUMP TRIP annunciated.

Sump Pump Out Timer FDR-TM-604A alarmed with indication of run time equal to STPT. Proper response on activation of RHR A Suppression Pool Suction Line Break was tested and verified.

INIIIALCONDITIONS: IC-12 100% Power with Equilibrium Xenon FINAL CONDITIONS: IC-12 100% Power with Equilibrium Xenon SOURCE OF COMPARISON DATA:

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

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITH DISCREPANCIES Q TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9. 14. 1A REV. 0 Tl'ILE: SRM A FAILS - HIGH OVERVIl.:W:

This test was performed to demonstrate the functionality of the SRM A FAILURE - HIGH Mal5mction. Proper response on activation of SRM-A failing high was tested and verified.

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

PLANT DATA SEI'NGINEERING EVALUAHON FSAR SUER / LER QX OPERATIONAL ASSESSMENT TEST RESULTS:

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

RE VIV TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.14.2A REV. 0

'ITTLE: APRM A FAILS IKON OVERVIEW:

This test was performed to demonstrate the functionality of the APRM A FAILS INOP Malfunc-tion. Malfunction in the count circuit with the output failing to zero. Alarm responses included:

APRM UPSCALE, APRM ACE UPSCL TRIP or INOP, ROD OUT BLOCK, NEVI'RON MONI-TOR SYSTEM TRIP, and Ig SCRAM SYSTEM A. APRM A UPSC TR OR INOP ALAI'ight illuminated on P603. System responses included: RPS A logic scram group solenoid lamps extin-guished on F603, RPS A SCRAM GP 1-4 solenoid eneqp lamps extinguished on P609, and the Backup Scram Valve Solenoid Lights for RPS A logic illumumted. Proper response on activation of APRM A Fails INOP malfunction was tested and verified.

INITIALCOND1TIONS: IC-12 100% Power with Eipuiibrium Xenon FINAL CONDITIONS: 1009o Power, 1/2 SCRAM RPS A SOURCE OF COMPARISON DATA:

PLANT DATA SEI'NGINEERING EVALUATION FSAR SUER / LER QX OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TESI'ESULTS SATISFACTORY WITH'DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.14.2B REV. 0 TTH.E: APRM C FAILS INOP OVERVQ:W:

This test was performed to demonstrate the functionality of the APRM C FAILS INOP Malftmc-tion. Malfunction in the count circuit with the output failing to zero. Alatm responses included:

APRM ACE UPSCL TRIP or INOP, ROD OUT BLOCK, NEUTRON MONITOR SYSTEM TRIP, and 1/2 SCRAM SYSTEM A. APRM C UPSC TR OR INOP ALUMlight Bluminated on P603.

System responses included: RPS A logic scram group solenoid lamps extinguished on P603, RPS A SCRAM GP IA solenoid energy lamps extinguished on P609, and the Backup Scram Valve Sole-noid Lights for RPS A logic iilununated on P603 4 F609. Proper response on activation of APRM C Fails INOP malfunction was tested and verified INZIIALCONDITIONS: IC-12 100fo Power with Equilibrium Xenon FINAL CONDITIONS: 1009o Power, 1/2 SCIL@ RPS A SOURCE OF COMPARISON DATA:

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

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

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.14.2C REV. 0 TITLE: APRM D FAILS PFOP OVERVIEW This test was performed to demonstrate the functionality of the APRM D FAILS INOP Malfunc-tion. Malfunction in the count circuit with the output failing to zero. Alarm responses included:

APRM BDF UPSCL TRIP or INOP, ROD OUT BLOCK, NEUTRON MONITOR SYSTEM TRIP, and 1/2 SCIVQVI SYSTEVI B. APRM D UPSC TR OR INOP ALA~light illuminated on P603.

System responses included: RPS B logic scram group solenoid lamps extinguished on P603, RPS B SCRAM GP 1< solenoid energ. lamps extinguished on P611, and the Backup Scram Valve Sole-noid Lights for RPS B logic illumittated. Proper response on activation of APRM D Fails INOP malfunction was tested and verifietL INITIALCONDITIONS: IC-12 100% Power with Equilibrium Xenon FINAL CONDITIONS: 100% Power, 1/2 SCRAM RPS B SOURCE OF COMPARISON DATA:

PLANT DATA SET Q ENGINEERING EVALUASTON Q FSAR SOER/LER X OPERATIONAL ASSESSMENT TEST RESULTS:

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

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.14.5A REV. 0 TITLE IBMA FAILS DO%'iVSCALE OVERVIEW; This test was performed to detnonstrate the functionality of the IRMA FAILS DOWNSCALE Mal-function. Proper response on activation of IRM A failing downscale was tested and verified.

INK'IALCONDITIONS: IC-5, following'POAH with IRM's on RG 8 or RG 9 HNALCONDITIONS: IC-5, following POAH with IRM's on RG 8 or RG 9 SOURCE OF COMPARISON DATA:

PLANT DATA SEI'NGINEERING EVALUASION FSAR SOER HLER QX OPERATIONAL ASSESSMENT TEST RESULTS:

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

N TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.14.5B REV. 0 TITLE: IRM C FAILS UPSCALZ OVERVIEW:

This test was performed to demonstrate the functionality of the IRM C FAILS UPSCALE Malfunc-tion. IRM output amp failure. The following annunciators alarmed. IRM ACEG UPSCL TRIP OR INOP, IRM MONITORS UPSCALE, ROD OUT BLOCK, NEVI'RON MONITOR SYSTEM TRIP, and 1/2 SCRAM SYSTEM A. System responses included: IRM C indicated upscale on IRM-LR-603C, IRM C UPSC TR OR INOP light illuminated, IRM C UPSC ALA~light illuminated P603, IRM C upscale on lRM C drawer, (UPSCAIZ ALARUM light and UPSC Trip light) Blumi-nated on P606. RPS A logic SCRAM group solenoid lamps extinguished. Backup SCK4V1 valve solenoid lights for RPS A logic illuminated. Proper response on activation of IRM C failing upscale was tested and veaiied.

INEQUAL CONDITIONS: IC-5 FINALCONDITIONS: IC-5, Half Scram System A and accompanying alarms SOURCE OF COMPARISON DATA:

PLANT DATA SEI'NGINEERING EVALUATION .

FSAR SOER/LER X OPERATIONAL ASSESSMENT TEST RESULTS:

Q TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACI'ORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUTDISCREPANCIES

N TEST CATEGORY: Malfunction Tests TEST No. 14.4.9. 14.5C REV. 0 TITLE: IRMF FAILS UPSCALZ OVERVIEW'his test was performed to demonstrate the functionality of the IRM F FAILS UPSCALE Malfunc-tion. IRM output amp shorted. The following annunciators alarmed: IRM BDFH UPSCL TRIP OR INOP, IRM MONITORS UPSCALE, ROD OUT BLOCK, NEU'IRON MONITOR SYSTEM TRIP, and 1/2 SCIVJVI SYSTEM B. System responses included: IRM F indicated upscale on IRN-LR-603D, IRM F UPSC TR OR INOP light illuminated, IRM F UPSC ALIBI light iHuminated F603, (UPSCALE ALAIMlight and UPSC Trip light) iHuminated on P606. RPS B logic SCR,AN group solenoid lamps extinguished. Backup SCRAM valve solenoid lights for RPS B logic iHumi-natecL Proper response on activation of IRM F failing upscale was tested and verified.

INHTALCONDITIONS: IC-5 FINALCONDITIONS: IC-S, Half Scram System B and accompanying alarms SOURCE OF COMPARISON DATA:

PLANT DATA Sar ENGINEERING EVALUATION FSAR SUER / LER g OPERATIONAL ASSESSMENT TEST RESULTS:

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

NAL TEST CATEGORY: Malfunction Tests TEST No. 14.4.9. 14.5D REV. 0 TITLE: IRr3f A FAILS 1K'VERVII:"W:

This test was performed to demonstrate the functionality of the IRM A FAILS INOP Malfunction.

IRM fails resulting in LO HV PWR SUPPLY VOLTAGE. The following annunciators alarmed:

IRM ACEG UPSCL TRIP OR INOP A, ROD OUT BLOCK, NEUTRON MONITOR SYSTEM TRIP, and IIJ2 SCRAM SYSTEM A. System responses included: IRM A indicated downscale on IRM-LR-603C, IRM A UPSC TR OR INOP light illunnnated. RPS A logic SCRAM youp sole-noid lamps extinguished. Baclmp SCIVQvf valve solenoid lights for RPS A logic illunnnated.

Proper response on activation of IRM A failing Inop was tested and vezi6ed INHTALCONDlTIONS: IC-5 FINAL CONDITIONS: IC-S, Half Scram System A and accompanying alarms SOURCE OF COMPARISON DATA:

[7 PLANT DATA Sar ENGINEERING EVALUATION FSAR Q SUER ILER QX OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACI'ORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUTDISCREPANCIES

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.14.5E REV. 0 TITLE: IRME ERRA17C OPERATION 0VERVII..W:

This test was performed to demonstrate the functionality of the IRM E ERRAIIC OPEIVZION Malfunction. Proper response on activation of IRM E failing erratic was tested and verified.

INITIIQ.CONDlTIONS: IC-5 FINALCONDlTIONS: IC-5 SOURCE OF COMPARISON DATA:

PLANT DATASET .

Q ENGINEERING EVALUATION FSAR Q SUER(LER X OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACI'ORY WITHOUTDISCREPANCIES

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.16.1 REV. 0 TITLE: RPS SCRAM GROUP FUSES BLOWN (CH A GROUP2 & CH B GROUP OVERVIEW:

This test was performed to demonstrate thc functionality of thc RPS SCRAM GROUP FUSES BLOWN (CH A GROUP 2 8h CH B GROUP 2) Malfunction. Proper response of the Group 2 Con-trol Rods listed on Attachment 7.1 including the Full Core Display Accumulator Lights and the Blue Scram lights were tested and veriiied. Proper response of the Group 2 solenoid lights for RPS A and RPS B were tested and veriiied. Simulator placed in FREEZE shortly after initiating the mal-function to inhibit a SDV/L High trip which would mask the results of the blown fuses.

INEQUAL CONDITIONS: IC-12 100% Power with Equilibrium Xenon FINALCONDITIONS: Group two rods have scrammed, Reactor power has been reduced signiiicantly.

SOURCE OF COMPARISON DATA:

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

TEST RESULTS UNSATISFACI'ORY WITH DISCREPANCIES Q TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

N TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.16.1A REV. 0 TITLE: RPS SCR4M GROUP FUSES BLOTCH (CH 2 GROUP 1 & CH B GROUP 1)

OVERVIEW:

This test was performed to demonstrate the functionality of the RPS SCRAM GROUP FUSES BLOWN (CH A GROUP 18'H B GROUP I) Malfunction. Proper response of the Group 1 Con-trol Rods listed on Attachment 7.1 including thc Full Core Display Accumulator Lights and the Blue Scram lights were tested and verifie. Proper response of the Group 1 solenoid lights for RPS A and RPS B were tested and verifie.Simulator placed in Ff&PZE shortly after initiating the mal-function to inhibit a SDV/L High trip which would mask the results of the blown 6xses.

INITIALCONDITIONS: IC-12 100% Power with BtuilibriumXenon FINAL CONDITIONS: Group one rods have scrammed, Reactor power has been rcduccd significantly.

SOURCE OF COMPARISON DATA:

PLANI'AI'ASEZ ENGINEEKNG EVALUATION FSAR SOER / LER g OPEIIAIIONALASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.16.1B REV. 0 TITLF'PS SCRAM GROUP FUSES BLOW'N (CH A GROUP 3 etc CH B GROUP 3)

OVERVII:W:

This test was performed to demonstrate the functionality of the RPS SCIVJul GROUP FUSES BLOWN (CH A GROUP 3A CH B GROUP 3) Malfunction. Proper response of the Group 3 Con-trol Rods listed on Attachment 7.1 including the Full Core Display Accumulator Lights and the Blue Scram lights were tested and verified. Proper response of the Group 3 solenoid lights for RPS A and RPS B were tested and verified..Simulator placed in FREEZE shortly after initiating the mal-function to inhibit a SDV/L High trip which would mask the results of the blown fuses.

INI'ITALCONDITIONS: IC-12 100% Power with Equilibrium Xenon FINALCONDlTIONS: Group three rods have scrammed, Reactor power has be:n reduced significantly.

SOURCE OF COMPARISON DATA:

PLANT DATA SEI'NGINEERING EVALUATION FSAR SOERi LEE g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

N REVIEW TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.16.1C REV. 0 TITLE: RPS SCR4M GROUP FUSES BLOWlV(CH A GROUP 4 ck CH B GROUP 4)

OVERVIEW:

This test was performed to demonstrate the functionality of the RPS SCRAM GROUP FUSES BLOWN (CH A GROUP 485 CH B GROUP 4) Malfunction. Proper response of the Group 4 Con-trol Rods listed on Attachment 7.1 including the Full Core Display Accumulator Lights and the Blue Scram lights were tested and verilied. Proper response of the Group 4 solenoid lights for RPS A and RPS B were tested and veriiied..Simulator placed in FREEZE shortly after initiating the mal-function to inhibit a SDV/L High trip which would mask the results of the blown fuses.

INIITALCONDITIONS: IC-12 1009o Power with Equilibrium Xenon FINAL CONDITIONS: Group four rods have scranuned, Reactor power has been reduced significantly.

SOURCE OF COMPARISON DATA:

PLANT DATASET ENGINEERING EVALUATION FSAR SOBR1LER g OPERATIONAL ASSESSMENT TEST RESULTS:

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

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.17.1 REV. 0 TITLE: RW'CU LZAEINSUCTION LINE OVERVII:W:

This test was performed to demonstrate the functionality of the RWCU LEAKIN SUCTION LINE Mal5mction. A break in the return line occurs betwee check valve RWCU-V-39 and Qow transmit-ter FT-41.System responses included: increasing pump suction Qow, decreasing pump discharge pressure, increased Qow through Qlter demin, increase in delta Qow indication, accompanying alarms, RWCU-V-1 and VA close, RWCU pump trips when RWCU-V-1 and VA enagim. Proper response on activation of the RWCU LEAKIN SUCTION LINE was tested and verified.

INDIIALCONDITIONS: IC-12 100% Power with Equilibrium Xenon FINAL CONDITIONS: RWCU system isolated, High sump levels Rx bldg, possible ARM alarms SOURCE OF COMPARISON DATA:

PLANI'ATASET ENGINEERING EVALUATION FSAR SOER / LER g OPERATIONAL ASSESSMENT TEST RESULTS:

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

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.17.2A REV. 0 TlTLE: RR'CU DENIMA FL UGGED OVERVIEW'.

This test was perfoaned to demonstrate the functionality of the RWCU DEIGN A PLUGGED Mal-function. Crud Buildup on Demin causes High Dp Isolation. System responses included: RWCU-H-609 Pump Suction Flow decreased, RWCU-H-605A decreased (to zero), P602-A5-6.7 CLEQ~ HLTER DEMIN FAILURE alarmed and later cleared when FD "A" isolated, and RWCU-PI-600 Pump Disch Pressure increased slightly. Proper response on activation of the RWCU DEMIN A PLUGGED malhmction was tested and vcri6cd.

INIIXALCONDITIONS: IC-12 100% Power with Equilibrium Xenon FINAL CONDITIONS: IC-12 100% Power with Equilibrium Xenon SOURCE OF COMPARISON DATA:

PLANI'ATASET ENGINEERING EVALUATION FSAR SUER / LER QX OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACI'ORY WITH DISCREPANCIES TESI'ESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS'SATISFACTORY WITHOUT DISCREPANCIES

NAL RE TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.17.23 REV. 0 TITLE: R7YCU DEMINB PLUGGED OVERVIEW

.This test was performed to demonstrate the functionality of the RWCU DEMIN B PLUGGED Malfunction. Crude Buildup on Demin causes High D.P. Isolation. System responses included:

RWCU-FI-609 Pump Suction Flow decreased, RWCU-H-605B decreased (to zero), P602-A5-6.7 CLF~KP FILTER DEMIN FAILURE alarmed and later cleared when FD "B" isolated, and RWCU-PI-600 Pump Disch Pressure increased slightly. Proper response on activation of the RWCU DEMINB PLUGGED malfunction was tested and veri6ed.

INZITALCONDZIIONS: IC-12 100% Power with Equilibrium Xenon HNAL CONDITIONS: IC-12 100Vo Power with Equilibrium Xenon SOURCE OF COMPARISON DATA:

PLANT DATA SET ENGINEIHUNG EVALUATION FSAR SUER / LER X OPERATIONAL ASSESSMENT TEST RESULTS:

TESI'ESULTS UNSATISFACTORY W1TH DISCREPANCIES TEST RESULTS SATISFACI'ORY WlTH DISCREPANCIES g TEST RESULTS 'SATISFACTORY W1THOUT DISCREPANCIES

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.18.2 REV. 0 TITLE: JET PUMP FAILURE OVERVIEW:

This test was performed to demonstrate the functionality of the JET PUMP FAILURE Malfunction.

Nozzle assembly becoming detached from the mixer assembly causes jet pump failure (15,16). Sys-tem responses included: Recirc loop How B increased as indicated on RRC-FR-614, Total core How decreased as indicated on MS-DPR/FR-613, Jet Pumps (15 8cl6) Sow decreased radically, Jet Pumps (11,12,13,14,17,18, 19@0) decreased slightly, and reactor power decreased as indicated on IRM-LR-603 (A,CPP). Proper response on activation of the JET PUMP FAILURE malfunction was tested and verifietL INI'ITALCONDITIONS: IC-12 100% Power with Equilibrium Xenon FINALCONDITIONS: Power has decreased, Associated Jet Pump Flows have decreased significantly and not affected Jet Pump How have decreased slightly SOURCE OF COMPARISON DATA:

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

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

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.18.3A REV. 0 1TTLE: INSTRUMENTREFERENCE LIEVE BREAE D004B (PENXI09)

OVERVIEW:

This test was performed to demonstrate the functionality of the INSTRUMENTREF LINE BRF~

D004B (PENX109). Rupture of INST Line between REACTOR and CONDENSATE POT for DOO4B (PENX109). Apparent level increased RFW-DPR-'4A, RFW-LI 606B indicated upscale high. REACTOR VESSEL HIGH LEVEL B SEAL light illuminated and RFW/TK&INERPV LEVEL HIGH TRIP alarm activated. System responses included: MS-LP/PR-623B (red pen) downscale, MS-LR/PR423B (black pen) going upscale high, RHR B/C INJECIION VLV OPEN permissive alarmed, MS-LI-10R upscale, and MS-PI-2 indicated downscle at RSD. Leak was 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 DOO4B was tested and verified. NOTE Details of Reactor Scram evaluated in test 14.4.9.24.33 and S/B Loca evaL 14.4.9.185.

INITIALCONDITIONS: IC-12 1009o Power with Equilibrium Xenon FINALCONDITIONS: Reactor has scrammed on Hi Drywell pressure.

SOURCE OF COMPARISON DATA:

PLANT DATASET ENGINEERING EVALUATION FSAR SUER / LER X OPERATIONAL ASSESSMENT TEST RESULTS:

TESI'ESULTS UNSATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITHOUTDISCREPANCIES

TEST CATEGORY: Mdfunction Tests TEST No. 14.4.9.18.3B REV. 0 TITLE: INSTRUMENTREFERENCE LINEBREAE D004C (MNXI12)

OVERVll:W:

This test was performed to demonstrate the functionality of the INSTRUMENTREF LINE BREAK D004C(PENX112). Ruptuxe of INST Line between REACI'OR and COND for DOO4C (PENX112). Appaxent level increased Ref-DPT-4C, RFW-LI 606C,8'cD indicated upscale high.

REACTOR VESSEL HIGH LEVEL C SEAL light Qluminatcd and RFW/TURBINE RPV LEVEL HIGH TRIP alaxm activated. System responses included: Injection Vlv Closure RPV LEVEL HIGH

+54.5 alarmed (HPCS-V4 remained closed), MS-LM04 indicated upscale P603, and FD How increased. Leak was allowed to continue. DRYS~L 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 verifie. NOTE Details of Reactor Scram evaluated in test 14.4.9.24.33, S/B Loca evaluated in 14.4.9.183. MT/GEN TRIP in 14.4.9.24.31, and High Level in 14.4.9.24.49 INITIALCONDITIONS: IC-12 100% Power with Ettuilibrium Xenon FINAL CONDITIONS: Reactor has scratnmed on Hi Drywcllpressuxe.

SOURCE OF COMPARISON DATA:

PLANT DATA SEI'NGINEERING EVALUATION FSAR SOER / LER X OPERATIONAL ASSESSidENT TEST RESULTS:

TEST RESULTS UNSATISFACI'ORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITH DISCREPANCIES Q TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

VH& U TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.18.3C REV. 0 TIME: INSTRUMENTREFERENCE LINEBREAKD004D (PENX106)

OVERVIEW'his test was performed to demonstrate the hnctionality of the INSTRUMIWTREF LINE BREAK D004D (PENZ106). Rupture of INST Line between REACTOR and CONDENSATE POT for DOO4D (PENX106). System responses included: RHR A INJECTION VLV OPEN pezznissive alarmed, LPCS INJECI1ON VLV OPEN permissive alarmed, Apparent level MS-LR-615 FUEL ZONE RPV level recorder remained upscale high, D/W Floor Drain Sump Bow increased, and Con-tainment temperatures increased. Leak was allowed to continue. DRYVI~LPRESS HIGH/Low Alert alarmed followed by the Drywell Press High Trip. Proper zesponsc on activation of INST REF LINE break DOO4D was tested and vezi6ed.NOTE: Details of Reactor Scram evaluated in test 14.4.9.24.33, S/B Loca evaluated in 14.4.9.18.5 MT/GEN TRIP in 14.4.9.24.31, and High Level in 14.4.9.24.49 INZIIALCONDITIONS: IC-12 100% Power with EquiTibzium Xenon FINAL CONDITIONS: Reactor has scrammed on Hi Drywell prcssure.

SOURCE OF COMPARISON DATA:

PLAIITDATASEI' ENGINEEIUNG 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

S TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.18.4 REV. 0 TITLE: RECLRCULATIONPUMP SEAL FAILURE OVERVIEW.

This test was performed to demonstrate the functionality of the RECIRCUI~ION PUMP SEAL FAILURE Malfunction. Improper reassembly on rebuilt results in RRC-P-1A upper and lower seal failure. System responses included: appropriate alarms, drop in pressure across lower seal, seal pressure decreasing to zero, dxywell Boor drain sump Bow increases, pump A number 1 and 2 seal cavity tempezatuxes increase, drywell pressure and temp increase. Proper response on activation of the Recirculation Pump Seal Failure was tested and vexifietL INEQUAL CONDITIONS: IC-12 100% Power with Equilibrium Xenon FINALCONDITIONS: RRC-P-lA seals have failed, large leak of coolant to drywell, pressure and tem-perature in dxywell are increasing.

SOURCE OF COhIPARISON DATA:

PLANT DATA SEP ENOINEERINO EVALUATION FSAR g SUER HLER t yet QX OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITH DISCREPANCIES

[7 TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.18.6B REV. 0 TITLE: INSTRUMENT VARL4BLELEG LINEB)PER xlll OVERVH.:W:

This test was performed to demonstrate the functionality of the INS'JUMENT VAKMBLELEG LINE BREAK xlll Malfunction. Rupture of Instrument Line Variable Leg, Xll1, outside Primary Containment. PI-EFC-X108 changed position from open to closed. Apparent -50" lvl responses included: RECIRC (A89) PUMP TRIP ATWS does not trip, ATWS-ARI 'IKPS did not annunci-ate, N4S ISOL RPV LEVEL LOW alarmed, MS-LR/PR-623B shifted to fast speed, and RC-2 Half Trip alarmed. Apparent -129" lvl responses included: RHR-P-2B 8h 2C autostarted, DG-2 AND SW-P-IB autostarted, RCIC Initiated, Main Turbine Tripped, Appropriate alarms occurred, and the Reactor Scrammed. Proper response on activation of the INSTRUMENT VAKM3LELEG LINE BREAK Xlll malfunction w as tested and veriliecLNOTE: Reactor Scram evaluated 14,4.9.24.33, MT/GEN Trip evaluated 14.4.9.24.31 INH1ALCONDITIONS: IC-12 100% Power with Etluilibrium Xenon FINALCONDITIONS: Reactor Scratnmed, MT/GEN Tripped, RHR BED started.

SOURCE OF COMPARISON DATA:

PLANT DATA SHI'NOINEERINO EVALUATION FSAR Q SOER(LER g OPERAIIONALASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITH DISCREPANCIES Q TEST RESULTS SATISFACI'ORY WITHOUTDISCREPANCIES

PERA N TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.18.6C REV. 0 TITLE: INSTRUME1VT VARIABLELEG LINEBREAE xlI3 OVERVIl.W:

This test was performed to demonstrate the Rnctionality of the INSTRUIVIENTVAKMBLELEG LINE BREAK x113 Malfunction. Rupture of Instrument Line Variable Leg, X113, outside Primary Containment. PI-EFC-X113 changed'position from open to closed. Appa'rent -50" lvl responses included: loss of leve1 as indicated on MS-LI404, HPCS system initiated with appropriate alarms, N4S ISOL RPV LEVEL LOW -50" alarmed, MSIV Half Trip System AP4S-LR/PR-623A shifted to fast speed, and RC-2 Half Trip alarmed. Proper response on activation of the INSTRUMENT VALUABLELEG LINE BREAK X113 malfunction was tested and veri6ed.

INITIALCONDITIONS: IC-12 100% Power with Ettuilibrium Xenon FINAL CONDITIONS: 100% Power, HPCS system initiated.

SOURCE OF COMPARISON DATA:

PLANT DATASET ENGINEERING EVALUATION FSAR SUER / LER QZ OPERATIONAL ASSESSiiENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES i

g TEST RESULTS SATISFACI'ORY WITH DISCREPANCIES Q TEST RESULTS SATISFACTORY WITHOUTDISCREPANCIES

N TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.18.6D REV. 0 TITLE: INSTRUMENT VA2K4BZEZEG ZINE BREAE xl08 OVERVQ:W:

This test was performed to demonstrate the functionality of the INSTRUMENT VARIABLELEG LINE BREAK xl08 Ma15mction. Rupture of Instrument Line Variable Leg, X108, outside Primary Containment. PI-EFC-X108 changed position from open to closed. Apparent -50" lvl responses included: RECIRC (A8$ ) PUMP TRIP ATWS does not trip, ATWS-ARI TRIPS did not annunci-ate, N4S ISOL RPV LEVEL LOW alarmed, MSIV Half Trip System B alarmed, and RC-1 Half Trip alarmed. Apparent -129" lvl responses included: LPCS/RHR A autostarted, DG-1 AND SW-P-lA autostarted, RCIC Initiated, Main Turbine Tripped, Appropriate alarms occurred, and the Reac-tor Scranuned. Proper response on activation of the INSTRUMENT VAKM3LE LEG LINE BREAK X108 malfunction was tested and vexi6eLNOTE: Reactor Scram evaluated 14.4.9.24.33, MT/GEN Trip evaluated 14.4.9.24.31 INITIALCONDITIONS: IC-12 100% Power with Equilibrium Xenon FINALCONDITIONS: Reactor Scrammed, MT/GEN Tripped, LPCS/RHR A started.

SOURCE OF COMPARISON DATA:

PLANT DATA SEI'NGINEEIUNG EVALUATION FSAR

[7 SOER HLER QX OPERATIONAL ASSESSMENT TEST RESULTS:

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

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.18.8 REV. 0 TTIT.E: HI RECIRCULATIONPUMP A VIBRATION OVERVIEW:

This test was performed to demonstrate the functionality of the HI RECIRCUl~~ION PUJMP A VIBRATION Malfunction. Impeller crachng causes recirculation pump high vibration. Proper response on activation of the Hi Recirculation Pump A Vibration was tested and verified.

INZITALCONDZTIONS: IC-12 100% Power with Equilibrium Xenon FINAL CONDlTIONS: IC-12 100% Power with Equilibrium Xenon SOURCE OF COMPARISON DATA:

PLANT DATASEr ENGINEEIUNG EVALUATION FSAR SUER I LER QX OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.18.8A REV. 0 TITLE: HIRECLRCULATIONPUMP B VLBRATlOH OVERVll.:W:

This test was performed to demonstrate the functionality of the HI RECIRCULATION PUMP B VIBRATION Malfunction. Impeller crachng causes recirculation pump high vibration. Proper response on activation of the Hi Recirculation Pump B ~iration was tested and verified.

INITIALCONDITIONS: IC-12 1009o Power with Eqmlibrium Xenon FINALCONDITIONS: IC-12 1009o Power with Equilibrium Xenon SOURCE OF COMPARISON DATA:

PLANT DATA SEI'NGINEERING EVALUATION Q FSAR

[7 SUER ILER X OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT.DISCREPANCIES

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.24.2A TITLE: CONDENSATE BOOSTER PVMP 2B TREP OVERVII:W:

This test was performed to demonstrate the functionality of the CONDENSATE BOOSTER PUMP 2B TRIP Malfunction. Electrical Malftmction causes pump trip. System responses included. booster motor amps decreased, appropriate alarms occur, booster pump discharge header pressure decreases, RFW pump suction pressure decreases, and RFW pumps trip. Proper response on activa-tion of the CONDENSATE BOOSTER PUMP 2B Trip was tested and verified. NOTE RFPT TRIP evaluated per 14.4.9.2.9, REACTOR SCRAM evaluated per 14.4.9.24.33, MT/GEN TRIP evaluated per 14.4.9.24.31, MSIV ISOLATION evaluated per 14.4.10.3, LOSS OF ALL RFW evaluated per 14.4.10.

INIIIALCONDITIONS: IC-12 1009o Power with Eqtnlibrium Xenon FINALCONDITIONS: RFW pumps have tripped, Reactor has scranunetL SOURCE OF COMPARISON DATA:

[7 PLANT DATASET ENGINEERING EVALUATION FSAR g SUER/LER 24 g OPERATIONAL ASSESSMENT TEST RESULTS:

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

ON RE TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.24.2B REV. 0

'ITIVE: CONDENSATE BOOSTER PUMP ZC TRlP OVERVIEW This test was performed to demonstrate the functionality of the CONDENSATE BOOSTER PUMP 2C TRIP Malbmction. Electrical Malfunction causes pump trip. System responses includctL booster motor amps decreased, appropriate alarms occur, booster pump discharge header pressure decreases, RFW pump suction pressure decreases, and RFW pumps trip. Proper response on activa-tion of the CONDENSATE BOOSTER PUMP 2C Trip was tested and verifie. NOTE: RFFI'RIP evaluated per 14.4.9.2.9, REACTOR S&4QVf evaluated per 14.4.9.24.33, MT/GEN TRIP evalu-ated pcr 14.4.9.24.31, MSIV ISOLATION evaluated per 14.4.10,3, LOSS OF ALLRFW evaluated per 14.4.10.1 INITIALCONDITIONS: IC-12 1009o Power with EttuiTibrium Xenon FINALCONDITIONS: RFW pumps have tripped, Reactor has scranuned.

SOURCE OF COMPARISON DATA:

PLANT DATA SEI'NGINEERING EVALUATION FSAR g SUER/LER - 24 g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACI'ORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.24.4 REV. 0 TITLE: CRD A PUMP TREP OVERVIEW'his test was perfoxmed to demonstrate the functionality of the CRD A PUMP TRIP Malfunction.

A piece of the impeller separates from the impeller and wedges between the impeller and the casing.

System responses included: CRD-P-lA trips, qpropriate alarms occur, CHARGING HEADER PRESSURE drops to zero, DRIVE HDR/RX DELTA P drops to zero, COOLING HDR/RX DELTA P drops to zero, DRIVE HEADER FLOW drops to zero, COOLING HDR FLOW drops to zero, SYSTEM FLOW drops to zero, and ROD ACCUMULATOR TROUBLE alarms occur, Proper response on activation of CRD A PUMP 'IRIP was tested and verifie.

INITIALCONDITIONS: IC-12 100% Power with Equilibrium Xenon FINALCONDITIONS: IC-12 100% Power with Equilibrium XEnonSame as above, and Multiple ROD ACCUMULATORTROUBLE alarms SOURCE OF COMPARISON DATA:

PLANT DATA SET ENGINEERING EVALUATION FSAR SOER / LER X OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACI'ORY WITH DISCREPANCIES

g. TEST RESULTS SATISFACTORY WITH DISCREPANCIES'EST RESULTS SATISFACTORY WITHOUT DISCREPANCIES.

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.24.4A REV. 0 TIILE: CRD B PUMP TR1P OVERVIEW'his test was performed to demonstrate the functionality of the CRD B PUMP TRIP Malfunction. A piece of the impeller separates Rom the impeller and wedges between the impeller and the casing.

System responses included: CRD-P-1B trips, appropriate alarms occur, CHARGING HEADER PRESSURE drops to zero, DRIVE HDR/RX DELTAP drops to zero, COOLING HDR/RX DELTA P drops to zero, DRIVE HEADER FLOW drops to zero, COOLING HDR FLOW drops to zero, SYSTEM FLOW drops to zero, and ROD ACCUMULATOR TROUBLE alarms occur. Proper response on activation of CRD B PUMP TRIP was tested and verifie.

INC'IALCONDITIONS: IC-12 100% Power with Equilibrium Xenon FINAL CONDITIONS: IC-12 100% Power with Equilibrium Xenon, and Multiple ROD ACCUMULA-TOR TROUBLE alarms SOURCE OF COMPARISON DATA:

PLANT DATASET ENGINEEIUNG EVALUATION FSAR SUER(LER g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACI'ORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITH DISCREPANCIES P TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

NAL RE TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.24.13 REV. 0 TTILE: 480 VAC MC-7B TZ/P OVERVIEW This test was performed to demonstrate the functionality of the 480 VAC MC-7B TRIP Mal-Rnction. Loss of MC-73, caused by tripping of its feeder breaker. Proper response to thc loss of motive power provided by MC-7B and hcr daughter busses was tested and verified. Proper response to the loss of control and indication power provided by MC-73 and her daughter bussses was tested and veri6ed.

Note: The pritnary purpose of this test is to check that MC-7B and her daughter busses pro-vide motive power, control power, and indication power to the correct loads. A mitnmum of a 10% sampling criteria is used. One hundred percent of thc motive loads are listed in the body of the procedure. Onc hundred percent of the control and indication loads are listed in attach-ment E.

INI'ITALCONDITIONS: IC-12 100% Power with Equilibrium Xenon FINAL CONDITIONS: Multiple motive, control, and indication loads have been dewnergized from bus MC-7B and her daughter busses.

SOURCE OF COMPARISON DATA:

PLANT DATA SEI'NGB IEERING EVALUATION Q FSAR Q SOER/LER X OPERATIONAL ASSESSMENT TEST RESULTS:

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

TEST CATEGORY: Malfuaction Tests TEST No. 14.4.9.24.18A REV. 0 TET.E: RPS A MG SET TRIP OVERVIEW:

This test was performed to demonstrate the functionality of the RPS A MG SET TRIP Malfunction.

RPS-EPA-3A breaker opens. System responses included: Multiple anaunciators associated with a total loss of RPS Bus A, Scram Group Solenoid lights for Gps 1$ ,3,24 extinguished, BU Scram amber lights illuminated, RPS Bus A power available light extinguished, Of gas valve AR-V-1 closed, aad APRM groups A,C, and E indicated downscale. An NSSSS outboard isolation occurred.; Group's 1,2,4/,6, 857 (outboard) valves closed and could not be opened, MSIV's remained open (half isolation only). Proper response to the loss of control aad indication power pro-vided by RPS-PP-001-A was tested and verified IAW'ttachment E. Proper response on activation of the RPS A MG SEI'TRIP malftmction was tested and verified.

INH'IALCONDITIONS: IC-12 100% Power with Equilibrium Xenon FINALCONDITIONS: RPS Bus A de~nergized, NSSSS outboard isolation present.

SOURCE OF COMPARISON DATA:

PLANT DATA SET ENGINEEIUNG EVALUATION FSAR g SUER.HLER QX OPERATIONAL ASSESSiiENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES H TEST RESULTS SATISFACTORY W!TH DISCREPANCIES 0 TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

NAL TEST CATEGORY: Malfunction Tests TEST No. 14.4.9,24.23 REV. 0 TEIDE: RHR A PUMP SHAFT SHEAR OVERVIEW:

This test was performed to demonstrate the functionality of the RHR A PUMP SHANTI'HEAR Malfunction. Metal fatigue causes the couplmg to break between the pump and thc prime mover.

RHR A in Full Flow Test, system responses included: RHR A Bow decreased to approximately 200 gpm as indicated on RHR-FI-603A, pressure decreased to approximately 20 psig on RHR-PI-612, RHR-P-2A motor amps dccteased, RHR-V-64A opened, and appropriate annunciators alarmed.

Proper response on activation of RHR A PUMP SHAFT SHEAR was tested and verified INH'IALCONDITIONS: IC-12 100% Power with Equilibrium Xenon FINALCONDITIONS: IC-12 100% Power with EquHbrium Xenon SOURCE OF COMPARISON DATA:

PLANT DATA SET ENGINEERING EVALUATION FSAR SOER / LER gX OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WII'KDISCREPANCIES TEST RESULTS SATISFACI'ORY WII'HOUTDISCREPANCIES

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.24.34A REV. 0 TH.'LE: RECLRCULATIONPUMP A TRIP OVERVII W'his test was performed to demonstrate the functionality of the RECIRCULATION PUMP A TRIP Malfunction. A piece of the impeller separates from the impeller and wedges between the impeller and the casing. System responses included: Multiple JP meter response IAW test procedure, RRC A Loop JP Qow decreased to rexo and then increased as reverse Qow, RRC B Loop JP Qow increased as RRC A loop entered reverse Qow, appropriate annunciators alarmed, and total core Qow 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. Simulator Data was collected and evaluated as SPVS File 14.4.9.24.34A, RRC A PUMP TRIP. Proper response on activation of the Reciredation Pump A Trip malfimction was tested and verified.

INHTALCONDITIONS: IC-12 1009o Power with Equilibrium Xenon FINALCONDITIONS: Reactor Plant in Single Loop at reduced power SOURCE OF COMPARISON DATA:

PLANT DATA P A SEI'NGINEERING EVALUATION g FSAR SOER / LER QX OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACI'ORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.24.36 REV. 0 TITLE: RPR-V42B FAIIS CLOSE 0VERVIE%'his test was performed to demonstrate the functionality of the RHR-V42B FAILS CLOSED Mal-function. Thermal binding results in valve seizure. An attempt to open the valve RHR-V42B using the switch was made; the valve would not open. Shifted Norm/Emerg switch RHR-V42B Rom Normal to Emergency; RHR-V-42B would not open. Proper response on activation of the RHR-V-42B Fails Closed malfunction was tested and veri6ed.

INITIALCONDITIONS: IC-12 100% Power with Equilibrium Xenon FINAL CONDITIONS: IC-12 100% Power with Equilibrium Xenon SOURCE OF COMPARISON DATA:

PLANT DATASET

[7 ENGINEERING EVALUATION FSAR SOER/LER OX OPERATIONAL ASSESSMENT TEST RESULTS:

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

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.24.37 REV. 0

'ITILE: PCS-V< FALLAS IS OVERViEW:

This test was performed to demonstrate the functionality of the HPCS-VA FAIL AS IS Malfunc-tion. Thermal bindiug results in valve seizure. System response included: HPCS valve did not move after receiving an open signaL Proper response on activation of the HPCS-VA Fail as Is was tested and veri6etL INITIALCONDITIONS: IC-12 100% Power with Equilibrium Xenon FINALCONDITIONS: IC-12 1009o Power with Equilibrium Xenon SOURCE OF COMP~ON DATA:

PLANT DATA SEI'NOINEERINO EYALUATION FSAR

[7 i SUER LER X OPERATIONAL ASSESSMENT TEST RESULTS:

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

TEST CATEGORY: Mal6mction Tests TEST No. 14.4.9.24.37B REV. 0 TETE: HPCS-VA FAKS TO AUTO OPEN OVERVIEW This test was performed to demonstrate the functionality of the HPCS-V-4 FAILS TO AUTO OPEN Malfunction. Thermal binding results in valve seizure. HPCS system was initiated, System response included: HPCS-P-1 auto started, HPCS-V-12 nnnimum How valve opened, HPCS-VA did not open, and HPCS-H-603 indicated zero Qow. HPCS-V-4 control switch was placed to the open posi-tion, system response included: . Proper response on activation of the HPCS-VA Fails to Auto Open was tested and verified.

INITIALCONDITIONS: IC-12 100% Power with Equilibrium Xenon FINALCONDITIONS: IC-12 1009o Power with Equilibrium Xenon SOURCE OF COMPARISON DATA:

PLANT DATASET Q ENGINEEIUNG EVALUATION

[7 FSAR SUER/LER g OI EIIATIONALASSESSMENT TEST RESULTS:

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

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.24.38 REV. 0 TITLE: LPCS-V-S FAILS CLOSED OVERVIEW:

This test was performed to demonstrate the functionality of the LPCS-V-5 FAILS CLOSED Mal-function. LPCS-V-5 control switch was placed to the open position; LPCS-V-5 did not open. Proper response on activation of the LPCS-V-5 Fails Closed malfunction was tested and veri6ed.

INZIIALCONDIIIONS: IC-1 COLD SHUTDOWN FINAL CONDITIONS: IC-1 COLD SHUTDOWN SOURCE OF COMPARISON DATA:

PLANT DATA SET ENOTNEERINO EVALUATION FSAR SUER HLER X OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACI'ORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.24 44 REV. 0 TITLE: LPCS - P 2 SK4ET SHEAR OVERVH.W:

This test was perfotmed to demonstrate the functionality of the LPCS-P-2 SHAFf SHEAR Mal-function. Metal fatigue causes the coupling to break between the pump and the prime mover. Sys-tem responses included: pressure as measured at LPCS-PI-3 and RHR-PI-612A decreased, appropriate alarms occurred, and normal red running light stiQ energized. Proper response on acti-vation of the LPCS-P-2 Shaft Shear was tested and verifie INEQUAL CONDEMNS: IC-12 100% Power with Equilibrium Xenon FINALCONDITIONS: IC-12 100% Power with Equilibrium Xenon SOURCE OF COMPARISON DATA:

PLANT DATASET Q ENGINEERING EVALUATION FSAR SOER/LER QX OPEIIAIIONALASSESSMENT TEST RESULTS:

TESI'ESULTS UNSATISFACTORY WITH DISCREPANCIES

[7 TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACI'ORY WITHOUT DISCREPANCIES

W TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.24.44A REV. 0 TITLE: LPCS -P-2 TRLP OVERVIEW.

His test was performed to demonstrate the functionality of the LPCS-P-2 TRIP Malfunction.

LPCS-P-2 Trips on thermal overload due to motor electrical fault. System responses included: pres-sure as measured at LPCS-PI-3 and RHR-PI-612A decreased, (LPCS PUMP DISCH PRESS HIGH/

LOW 8h RHR A PUMP DISCH PRESS HIGH/LOW) alarmed, applicable BISI lights illuminated, and (RHR A OUT OF SERVICE 8h LPCS OUT OF SERVICE) annunciators alarmed. Proper response on activation of the LPCS-P-2 Trip malfunction was tested and verifie.

INI'ITALCONDITIONS: IC-12 100%%uo Power with Equilibrium Xenon FINALCONDITIONS: IC-12 1009o Power with BlmlibriumXenon SOURCE OF COMPARISON DATA:

PLANT DATA SET ENGINEEIUNG EVALUATION

[7 F SAR SUER / LER g OPERATIONAL ASSESSMENT TEST RESULTS:

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

TEST CAIZGORY: Malfunction Tests TEST No. 14.4.9.24 45 REV. 0 TITLE: RPR-P-3 SE4FT SPEAR OVERVIEW:

This test was performed to demonstrate the functionality of the RHR-P-3 SHAFT SHEAR Malfunc-tion. Metal fatigue causes the coupling to break between the pump and the prime mover. System responses included: pressure as measured at RHR-P!-612B and RHR-PI-612C decreased, appropri-ate alarms occurred, and normal red running light was stiH energized. Proper response on activation of the RHR-P-3 Shaf't Shear was tested and verified.

INI'ITALCONDITIONS: IC-12 100% Power with Equilibrium Xenon FINAL CONDITIONS: IC-12 100% Power with Equilibrium Xeno'OURCE OF COMPARISON DATA:

PLANT DATA SEI'NOINEERINO EVALUATION Q PSAR SUER HLER g OPERATIONAL ASSESSIVIENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCES g TEST RESULTS SATISFACI'ORY WITHOUTDISCREPANCIES

N TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.24.47 REV. 0 TITLE: 8PCS TFATERLSG PUMP SZAF T SPEAR (8PCS-P-3)

OVERVIEW:

This test was performed to demonstrate the functionality of thc HPCS WATERLEG PUMP SHAFT SHEAR (HPCS-P-3) Malf'unction. Metal fatigue causes the coupling to break between the pump aud the prime mover. System responses included: pressure as measured at HPCS-P-601 decreased, appropriate alarms occurred, and normal red running light was still encqpzed. Proper response on activation of the HPCS Waterleg Pump Shaft Shear was tested and verified.

INEQUAL CONDITIONS: IC-12 100% Power with Equilibrium Xenon FINAL CONDITIONS: IC-12 100% Power with Equilibrium Xenon SOURCE OF COMPARISON DATA:

PLANT DATA SET ENGINEERING EVALUATION FSAR SUER(LER g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACIORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUTDISCREPANCIES

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.24.48 REV. 0 TITLE: COND-P-1B TRP OVERVIEW:

This test was perfoaned to demonstrate the functionality of the COND-P-1B VIP Malfunction.

Electrical Malfunction causes pump trip. System responses included: Cond Pump B motor amps decreased, Cond Pumps A dh C amps increase, appropriate alarms occurred, condensate pump dis-charge header ptessure 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 veri6ed.

NOTE: RFFI'TRIP evaluated per 14.4.9.2.9, REACI'OR SCI4QVI evaluated per 14.4.9.24.33, M'/

GEN TRIP evaluated per 14.4.9.2431, MSIV ISOLATIONevaluated per 14.4.10.3, LOSS OF ALL RFW evaluated per 14.4.10.1 INITIALCONDITIONS: IC-12 100% Power with Eqtulibzium Xenon FINALCONDITIONS: RFW pumps tripped, Reactor has scrammed.

SOURCE OF COMPARISON DATA:

PLANT DATA SEI'NGINEERING EVALUATION FSAR SOER/LER g OPERATIONAL ASSESSMENT TEST RESULTS:

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

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.24.48B REV. 0 TITLE: COiVD-P-1C TZP OVERVIEW; This test was performed to demonstrate the functionality of the COND-P-1C TRIP Malfunction.

Electrical Mal6mction causes pump trip. System responses included: Cond Pump C motor amps decreased, Cond Pumps A 8c B amps increased., appropziate alarms occuzzed, condensate pump dis-charge header pzessuze decreased, Booster and RFW pump suction pzessuzes decreased, and RFW pumps tripped. Proper response on activation of the COND-P-1C 'IKP was tested and verified.

NOTE: RFFI'TRIP evaluated per 14.4.9.2.9, REACIQR SCRAM evaluated per 14.4.9.24.33, MT/

GEN TRIP evaluated per 14.4.9.24.31, MSIVISOLATIONevaluated per 14.4.10.3, LOSS OF ALL RFW evaluated per 14.4.10.1 INDIIALCONDZTIONS: IC-12 1009o Power with Ettuilibzium Xenon FINAL CONDITIONS: RFW pumps txipIxxi, Reactor has scrammed.

SOURCE OF COMPARISON DATA:

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

TEST RESULTS UNSATISFACI'ORY WITH DISCREPAiVCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

REVE%

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9,24.49 REV. 0 TITLE: MASTER FWLC FAILS 87'VERVIEW'his test was performed to demonstrate the functionality of the Master FWLC failing high. The RFP speed controllers RFW-SC<01A (3) response to the high output signal from FRW-LIC400 was verified. The RFP speed, discharge pressure and Bow was verifed to be correct. The RFP's and MT tripped at RPV/L S as anticipated. The proper response for the Main Turbine Trip (14.4.9.24.31),

RFP Turbine Trip 14.4.9.2.9, Main Generator Trip (14.4.9.13.1), and Reactor Scram (14.4.9.24.33) previously verified in detail in the speci6ed test documents. Proper response on activation of Master FWLC fails High was tested and veri6ed.

INITIALCONDITIONS: IC 13, 50% Power, 75% Rod Line FINAL CONDITIONS: Post Scram, with RFP and MT tripped, MSIV and NS$ Isolation at RPV/L 2 with SRV operation controlling RPV/P at setpoint, and HPCS-V-4 opening at RPV/L 2 and cycling closed at RPV/L 8.

SOURCE OF COMPARISON DATA:

g PLANT DATA SEI'NOINEERINO EVALUATION FSAR Q S DER / LER g OPERATIONAL ASSESSMENT TEST RESULTS:

TESI'ESULTS UNSATISFACTORY WITH DISCREPANCIES g TESI'ESULTS SATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Malfunction Tests TEST No, 14.4.9.24.54 REV. 0 TITLE: BATTERYCHARGER Cl-7 TRfP OVERVIEW:

.This test was performed to demonstrate the functionality of the BAI'I'ERYCHARGER Cl-7 TRIP Malfunction. Loss of Charger Cl-7, due to output breaker trip. System responses included:

(CHARGER CI-7 TROUBLE, INVHG'ER IN-5 TROUBLE, and 125V LOSS BAITB 1-7 FAIL-URE) alarmed, AM-Cl-7decreased to zero, AM-Blincreased to approximate reading on AM-Cl-7 prior to initialization, VM-S1-7 indicated approximately 125vdc, and bus Sl-7 voltage decreased with time. Proper response on activation of Battery Charger Cl-7 Trip was tested and vezi6ed.

INITIALCONDITIONS: IC-12 100% Power with Equilibrium Xenon FINAL CONDITlONS: IC-12 100% Power with Equilibrium Xenon SOURCE OF COMPARISON DATA:

PLANT DATA SEI' ENGINEERING EVALUATION Q FEAR SUER(LER QX OPERATIONAL ASSESSMENT TEST RESULTS:

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

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.24.54A REV. 0 TITLE: CO-lA CE4RGER TRlP & BATTE2F BO-IADISCE4RGE OVERVIEW:

This test was performed to demonstrate the functionality of the CO-lA CHARGER TRIP dh BAT-TERY BO-lA DISCHARGE Malfunction. Loss of Charger.CO-lA due to output breaker trip. Sys-tem responses included: 24 VDC CHARGE CO-1A TROUBLE alarmed, AM-BO-1A increased to approximately same reading as was on AM-CO-lA prior to malfunction, VM40-IA indicated approximately 24 VDC and decrcascd with time. Proper response on activation of CO-lA Charger Trip 8h Battery BO-IA Discharge malfunction was tested and veri6ed.

INI'IIALCONDITIONS: IC-12 100% Power with Equilibrium Xenon FINALCONDITIONS: IC-12 100% Power with Equilibrium Xenon SOURCE OF COMPARISON DATA:

PLANT DATA SEI'NGINEERING EVALUATION

[7 F SAR SUER HLER OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Malfunction Tests TEST No. 14 4.924.54B REV. 0

'ITTLE: C2-l CHARGER TRlP &BATTERI B2-I DISCHARGE OVERVII:W:

This test was performed to demonstrate the functionality of the C2-1 CHARGER TRIP 0 BAT-TERY B2-1 DISCHARGE Malfunction. Loss of Charger C2-1 due to output breaker trip. System responses included: (250 VDC CHARGER C2-1 TROUBLE and RCIC DIV 1 OOS) annunciators alarmed, IN- 1 Auto Transferred to Alternate Source, AM C2-1 decreased to zero, and AM-B2-1 increased to approxitnately the same initial reading as indicated on AM C2-1. The annunciator 250 VDC LOSS BAITB2-1 PAIL alaxmed when voltage dropped to LT 220 VDC on S2-1 and VM42-1 indicated approximately 250 VDC initially and continued to decrease with time. Proper response on activation of C2-1 Charger Trip 8c Battery B2-1 Discharge was tested and verifie.

IRZIIALCONDITIONS: IC-12 100% Power with Equilibrium Xenon FINALCONDITIONS: IC-12 100% Power with Equilibrium Xenon SOURCE OF COMPARISON DATA:

PLANT DATASEr ENGIFIEEIUNG EVALUATION FSAR SOER /LER X OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITH DISCREPANCIES P TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.24.57 REV. 0 TITLE: H2<IDE SO PUMP TRLP OVERVIEW:

This test was perfoaned to demonstrate the functionality of the HZQIDE SO PUMP 'IRIP Malfunc-tion. A piece of the impeller separates Rom thc impeller and wedges between the impeller and the casing. System responses included: GEN SEAL OIL H2 SIDE PUMP OFF alarms, pressure meters TO-PI-24 and TO-DPI-23 do not change, Generator hydrogen pressure and purity decrease slowly over time. Pmper response on activation of tripping thc BRIDE SO PUMP was tested and veri-fied.

INI.'IIALCONDITIONS: IC-12 100% Power with Equilibrium Xenon FINALCONDITIONS: IC-12 100% Power with Equilibrium Xenon SOURCE OF COMPARISON DATA:

PLAiYTDATA SEI'NGINEERING EVALUATION FSAR SUER / LER QX OPERATIONAL ASSESSMENT TEST RESULTS:

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

N TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.24.58 REV. 0 TTKE: AIR-SIDE SO PUMP TR?P OVERVIIVV:

This test was performed to demonstrate the functionality of the AIRNIDE SO PUMP TRIP Mal-function. A piece of the impeller separates from the impeller and wedges between the impeller and the casing. System responses included: GEN SEAL OIL AIRCIDE PUMP OFF alarms, pressure meters TO-PI-S and TO-DPI-23 do not change. Proper response on activation of tripping the AIR-SIDE SO PUMP was tested and verified.

PRIMAL CONDITIONS: IC-12 100% Power with Bpilibrium Xenon FINALCONDITIONS: IC-12 100% Power with BpilibriumXenon SOURCE OF COMPARISON DATA:

PLANT DATASET

[7 ENOINEEIUNO EVALUATION

[7 FSAR SOER / LER X OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TIQN RE TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.2439 REV. 0 TXILE: SK4FT-DRlVEiVLO PUMP FAKURE 0VERVII.:W:

This test was performed to demonstrate the functionality of the SHAFT-DFD'EN LO PUMP FAIL-URE Malfimction. Metal fatigue causes the coupling to break between the pump and prime mover.

System responses included: TG BRG OIL EMERG PUMP ON alarm, TO-P-BOP pump has started, and TO-P-EOP emergency oil pump auto start. Proper response on activation of the SHAFT-DRIVEN LO PUMP FAILURE was tested and verified.

INITIALCONDITIONS: IC-12 100% Power with Ecpulibrium Xenon FINALCONDITIONS: IC-12 100% Power with Equilibrium Xenon SOURCE OF COMPARISON DATA:

PLANT DATASEI' ENGINEEIUNG EVALUATION Q FSAR SOER / LER QX OPERATIONAL ASSESSiilENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES Q TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACI'ORY WITHOUTDISCREPANCIES

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.24.60 REV. 0 TZILE: CRD-FCV-2 FAILS CLOSED OVERVIEW:

This test was pezfozzned to demonstrate the functionality of the CRD-FCV-2 FAILS CLOSED Mal-function. Electronic Malfunction. System responses included: CRD-P-IA MOTOR CUIEENT decreased, DRIVE HDR/RX DELTA P decreased, COOLING HDR/RX DELTA P decreased CRD-FCV-2A red and green position indication changed to all Green, cooling hdr Bow decreased, and CRD How deczeased. Proper response on activation of the CRD-FCV-2 FAILS CLOSED was tested and verified.,

INIIIALCONDITIONS: IC-12 1009o Power with EquBibzium Xenon FINALCONDITIONS: IC-12 1009o Power with Equilibrium Xenon, with increasing CRD temperatures.

SOURCE OF COMPARISON DATA:

PLANT DATA SET ENGINEERING EVALUATION FSAR SUER HLER g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACI'ORY WITHOUTDISCREPANCIES

TEST CATEGORY: Mauunction Tests TEST No. 14.4.9.24.63A REV. 0 TITLE: DER PUMP IB TRLP OVERVIEW This test was perfotmed to demonstrate the functionality of the DEH PUMP 1B TRIP Malfunction.

Spurious breaker txip. System responses included: DEH-P-1B trjqed, DEH HDR pressure decreased, appropriate annunciators alarmed, and the standby DEH-P-1A auto started at 1800 psig.

Proper response on activation of the DEH-P-IB trip was tested and veri6ed.

INZIIALCONDITIONS: IC-12 100% Power with Equilibrium Xenon FINALCONDITIONS: IC-12 100% Power with Eqmlibrium Xenon, with Standby DEB-P-1A 1S ZQIlIlHlg.,

SOURCE OF COMPARISON DATA:

PLANT DATA SEI'NGINEERING EVALUATION P FSAR g SUER / LER 84-046, 90-021 X OPERATIONAL ASSESSMENT TEST RESULTS:

Q TESI'RESULTS UNSATISFACI'ORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITHOUT DISCREPAiVCIES

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.24.67A REV. 0 TITLE: REF-LI<06A FAILSAS IS OVERVIEW:

This test was performed to demonstrate the functionality of the RFW-LI-606A FAILS AS IS Mal-function. Level Sensor C34-N004A Pails as is. Reactor Power was decreased to 90% using RRC FCV's 60A 0 60B. System responses included: RFW-LI-606A did not respond, RFW-LI-606B and RFW-LI-606C showed increasing RPV/L, RPV/L Hi/Lo Alarm F603-AS-3-7 did not alarm, and the response of Master Controller was sluggish. Power was decreased rapidly to 60%; system responses included: Stm Flow dh Rx Pwr decreased with RPV/L increasing due to RFW/F GT MS/F, RPV/L went to LVL 8 on RFW-LI-606B 4 RFW-Ll406C with RFW-LI-606A unchanged, MT tripped, and Reactor Scramtned. Proper response of RFW-LI-606A fails as is was tested and verified.

NOTE: RFW TURB TRIP evaluated in 14.4.9.2.9griT'IHIP evaluated in14.4.9.24.31, RX SCRAM evaluated in 14.4.9.24.33 INZITALCONDITIONS: IC-12 100% Power with Equilibrium Xenon FINAL CONDITIONS: Reactor is Scrammed, MT Tripped on high level.

SOURCE OF COMPARISON DATA:

Q PLANT DATASET ENOINEERINO EVALUATION FSAR SUER I LEE QX OPERATIONAL ASSESSM:NT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES

[g TEST RESULTS SATISFACI'ORY WITHOUTDISCREPANCIES

N RE TEST CATEGORY: Malfunction Tests TEST No. 14.4.9,24.67D REV. 0 TITLE: RFW-Ll406C FAILS HIGH OVERVll.W This test was performed to demonstrate the functionality of the RFW-LI-606C FAILS HIGH Mal-function. Level Sensor C34-N004C Fails high. System responses included: RFW-LI-606C and 606D indicated upscale, RPV high level channel C seal in amber light illutninated, and P603-A8W 7 RFW/I'URBINE RPV level high Trip alarmed. Proper response on activation of the RFW-LI-606C FAILS HIGH malftmction was tested and veri6ed.

INITIALCONDITIONS: IC-12 100% Power with Equilibrium Xenon FINALCONDITIONS: IC-12 100% Power with Equilibrium Xenon SOURCE OF COMPARISON DATA:

PLANT DATASET ENGINEERING EVALUATION

[7 FSAR SOER / LER X OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACI'ORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9,24.68 REV. 0 TITLE: RCIC-V<3 FALLS OPEN OVERVII.:W:

This test was performed to demonstrate the functionality of the RCIC-V-63 FAILS OPEN Malfunc-tion. Internal electrical failure in the auto-dose logic circuit. System responses included: placed the RCIC-V-63 Keyswitch to close, the STM SUPPLY LINE INBOARD ISOL did not close. Proper response on activation of the RCIC-V-63 Fails Open was tested and veriaed.

INZIIALCONDITIONS: IC-12 100% Power with EtgnTibzium Xenon FINALCONDITIONS: IC-12 100% Power with Equilibrium Xenon SOURCE OF COMPARISON DATA:

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

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACIORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.24.69 REV. 0 TITLE: RCIC-VN FAILS OPEN OVERVIEW'his test was performed to demonstrate the functionality of the RCIC-V-8 FAILS OPEN Malfunc-tion. Internal electrical failure in the auto-dose logic circuit. System responses included: ARM and DEPRESSED manual initiation push-button, RCIC-V-8 did not close, placed S'I EAM SUPPLY LINE OUTBOARD ISOL RCIC-V-8 control switch in close, valve did not close. Proper response on activation of the RCIC-V4 Fails Open was tested and veri6ed.

INITIALCONDITIONS: IC-12 100% Power with Equilibrium Xenon FINALCONDITIONS: IC-12 100% Power with Equilibrium Xenon SOURCE OF COMPARISON DATA:

PLANT DATA SEI'NGINEERING EVALUATION FEAR SOER/LER g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSAHSFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCES g TEST RESULTS SATISFACI'ORY WITHOUT DISCREPANCIES

P TI N TEST CATEGORY: Malfunction Tests TEST No. 14 4 9 24 72 REV. 0 TITLE: SLC-P-IB FAILS TO START OVERVIEW:

This test was performed to demonstrate the functionality of the SLC-P-1B FAILS TO START Mal-function. Internal electrical failure in the ant~pen logic circuit. Placed the key switch SLC-RMS-SIB, SLC SYSTEM B, to OPERATE. System responses included: SLC-P-IB did not start, no indi-cation of discharge pressure, and no indication of SLC flow. Proper response on activation of the SLC-P-1B FAILS TO START malfunction was tested and veri6ed.

INDI'IALCONDITIONS: IC-12 100% Power with Equilibrium Xenon FINALCONDITIONS: IC-12 100% Power with Equilibrium Xenon SOURCE OF COMPARISON DATA:

Q PLANT DATASET ENGINEERING EVALUATION FSAR Q SUER HLER g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TESI'ESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Malfunction Tests TEST No. 14,4.9.24.85A REV. 0 TTTLE: MS-V-'22A - FALLS TO CLOSE OVERVIEW:

This test was performed to demonstrate the functionality of the MS-V-22A-FAILSTO CLOSE Mal-function. MSIV fails to close due to mechanical seinue of disc. System responses included: all MSIV's closed with the exception of MS-V-22A, Reactor scrunmed, MT/GEN Tripped on reverse power, SRV's operated to control pressure, a manual attempt to close MS-V-22A did not shut the valve. Proper response on activation of the MS-V-22A Fails to Close ma5zction was tested and veriGed. NOTE: Reactor Scram evaluated in 14 4.9.24.33, MSIV Isolation evaluated in 14.4.10.3, MT Trip evaluated in 14.4.9.24.31 INZIIALCONDITIONS: IC-12 1009o Power with Equilibrium Xenon FINALCONDITIONS: Reactor Scram initiated due to initiation of MSIVNS4 signal with MS-V-22A failing open.

SOURCE OF COMPARISON DATA:

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

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACI'ORY WITH DISCREPANCIES g TEST RESULTS SATISFACI'DRYWITHOUT DISCREPANCIES

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.24.85B REV. 0 TITLE MS-V-28A- FAILS TO CLOSE OVERVII:W; This test was performed to demonstrate the functionality of the MS-V-28A-FAILSTO CLOSE Mal-function. MSIV fails to close due to mechanical seimre of disc. System responses included: all MSIV's closed with the exception of MS-V-28A, Reactor scratntned, MT/GEN Tripped on reverse power, SRV's operated to control pressure, a manual attempt to close MS-V-28A did not shut the valve. Proper response on activation of the MS-V-28A Fails to Close malfunction was tested and veri6eLNOTE: Reactor Scram evaluated in 14.4.9.24.33, MSIV Isolation evaluated in 14.4.10.3, MT Trip evaluated in 14.4.924.31 INITIALCONDITIONS: IC-12 100% Power with Equilibrium Xenon FINALCONDITIONS: Reactor Scram initiated due to initiation of MSIVNS4 signal with MS-V-28A faiTing open.

SOURCE OF COMPARISON DATA:

Q PLANT DATASEI' ENGINEEIUNG EVALUATION FSAR SOER / LER QX OPERATIONAL ASSESSMENT TEST RESULTS:

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

N TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.24.85C REV. 0 TTI'LE: MS-V-28B - FAILS TO CLOSE OVERVH W This test was performed to demonstrate the functionality of the MS-V-28B-FAILS TO CLOSE Mal-function. MSIV fails to close due to mechanical seizure of disc. System responses included: all MSIV's closed with the exception of MS-V-28B, Reactor scrammed, MT/GEN Tripped on teverse power, SRV's operated to control pressure, a manual attempt to close MS-V-28B did not shut the valve. Proper response on activation of the MS-V-28B Fails to Close malfunction was tested and verified. NOTE: Reactor Scram evaluated in 14.4.9.2433, MSIV Isolation evaluated in 14.4.10.3, MT Trip evaluated in 14.4.9.24.31 INITIALCONDITIONS: IC-12 100% Power with Equilibrium Xenon FINALCONDITIONS: Reactor Scram initiated due to initiation of MSIVNS4 signal with MS-V-28B

. failing open.

SOURCE OF COMPARISON DATA:

PLANT DATA SET ENOINEERINU EVALUATION FSAR Q SUER HLER QX OPERATIONAL ASSESSMENT TEST RESULTS:

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

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.24.85D REV. 0 T1TLE: MS1V's - FAILS TO CLOSE OVERVIl.:W:

This test was performed to demonstrate the functionality of the MSIV's - FAILS TO CLOSE Mal-function. MSIV's ALLmechanically Fail in the Open position. Manual and NS4 isolation push-but-ton attempts to shut the MSIV's with the ma16mction activated would not shut the valves. Proper response on activation of the MSIV's - Fails to Close malfunction was tested and verified. NOTE:

Complete MSIV evaluation evaluated in 14.4.10.3, NS4 Isolation Groups 2-8 are evaluated in 14.4.9.2.6.3 INITIALCONDITIONS: IC-12 100% Power with Equilibrium Xenon FINAL CONDITIONS: IC-12 100% Power with Ecpxilibrium Xenon SOURCE OF COMPARISON DATA:

Q PLANT DATA SEI'NGINEERING EVALUATION

[7 FSAR

[7 SUER <I.ER X OPERATIONAL ASSESSMENI'EST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUTDISCREPANCIES

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.24.85E REV. 0 TITLE: MS-V-22B - MLS TO CLOSE OVERVII:W:

This test was performed to demonstrate the functionality of the MS-V-22B-FAILS TO CLOSE Mal-function. MSIV fails to close due to mechanical seizure of disc. System responses included: all MSIV's closed with the exception of MS-V-22B, Reactor scrammed, MT/GEN Tripped on reverse power, SRV's operated to control pressure, a manual attempt to close MS-V-22B did not shut the valve. Proper response on activation of the MS-V-223 Fails to Close malfunction was tested and verifie. NOTE: Reactor Scram evaluated in 14,4,9.24.33, MSIV Isolation evaluated in 14.4.10.3, MT Trip evaluated in 14.4.9.24.31 INHTALCONDITIONS: IC-12 100% Power with Equilibrium Xenon FINAL CONDITIONS: Reactor Scram initiated due to initiation of MSIV NS4 signal with MS-V-223 failing open.

SOURCE OF COMPARISON DATA:

PLANT DATA SET ENGINEERING EVALUATION FSAR SUER/LER QX OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES H TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.24.85F REV. 0 TITLE: MS-V-22C - FAILS TO CLOSE OVERVIEW This test was performed to demonstrate thc functionality of the MS-V-22C-FAILS TO CLOSE Mal-function. MSIV fails to close due to mechanical seizure of disc. System responses included: all MSIV's closed with the exception of MS-V-22C, Reactor scranuned, MT/GEN Tripped on reverse power, SRV's operated to control pressure, a manual attempt to close MS-V-22C did not shut thc valve. Proper response on activation of thc MS-V-22C Fails to Close malfunction was tested and veri6ed. NOTE: Reactor Scram evaluated in 14.4.9.24.33, MSIV Isolation evaluated in 14.4.10.3, MT Trip evaluated in 14.4.9.24.31 INI'ITALCONDITIONS: IC-12 100% Power with Equilibrium Xenon FINALCONDITIONS: Reactor Scram initiated due to initiation of MSIV NS4 signal with MS-V-22C failing open.

SOURCE OF COMPARISON DATA:

PLANT DATA SEI'NGINEERING EVALUATION FSAR SOER / LER PX OPERATIONAL ASSESSMENT TEST RESULTS:

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

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.24.85G REV. 0 TITLE: MS-V-28C - FAES TO CLOSE OVERVIEW:

This test was performed to demonstrate the functionality of the MS-V-28C-FAILS TO CLOSE Mal-function. MSIV fails to dose due to mechanical seizure of disc. System responses included: all MSIV's closed with the exception of MS-V-28C, Reactor scratnmed, MT/GEN Tripped on reverse power, SRV's operated to control pressure, a manual attempt to close MS-V-28C did not shut the valve. Proper response on activation of the MS-V-28C Fails to Close malfunction was tested and veri6ed. NOTE: Reactor Scram evaluated in 14.4.9.2433, MSIV Isolation evaluated in 14.4.10.3, MT Trip evaluated in 14.4.9.24.31 INIIIALCONDITIONS: IC-12 100% Power with Equilibrium Xenon FINALCONDITIONS: Reactor Scram initiated due to initiation of MSIV NS4 signal with MS-V-28C failing open.

SOURCE OF COMPARISON DATA:

PLANT DATA SEI' ENGINEERING EVALUATION FSAR Q SOER HLER X OPERATIONAL ASSESSMENT TEST RESULTS:

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

TEST CATEGORY: Malsmction Tests TEST No. 14.4.9.24.85H REV. 0 TITLE: MS-V-2SC INADVERTENTSLOW CLOSURE OVERVIEW, This test was performed to demonstrate the functionality of the MS-V-28C - INADVERI'ENT SLOW CLOSURE Malftmction. Slow, inadvertent closure of MS-V-28C over approximately one minute. System responses included: MSIV-V-28C slow closed, was full shut at about 60 seconds, and Rx power and pressure stabilized approximately one minute later. The followmg Simulator Per-formance Verification System (SPV's) variables were plotted and evaluated: APRM (~), RPV/L NR, RPV/P NR, MSL (~,CQ) FLOW, AND MAINGEN MW ELECT. Proper response on acti-vation of the MS-V-28C -Inadvertent Slow Closure malfunction was tested and verified.

INITIALCONDITIONS: IC-12 100% Power with EcpuBbrium Xenon FINALCONDITIONS: IC-12 100% Power. with MS Lines AP, 8hD How indication upscale and RPV/P higher than initiaL SOURCE OF COMPARISON DATA:

PLANT DATA SEI'NGINEEIUNG EVALUATION FSAR SOER / LER X OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFAC1'ORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACI'ORY W1THOUT DISCREPANCIES'

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.24.85I REV. 0 TITLE: MS-V-28D I1VADVHTENTSLOW CLOSURE OVERVIEW:

This test was performed to demonstrate the functionality of the MS-V-28D - INADVERTENT SLOW CLOSURE Malfunction. Slow, inadvertent closure of MS-V-28D over approximately one minute. System responses included: MSIV-V-28D slow closed, was full shut at about 60 seconds, and Rx power and pressure stabilized approximately one minute later. The following Simulator Per-fonnance Veri6cation System (SPV's) variables were plotted and evaluated: APRM (A/3), RPV/L NR, RPV/P NR, MSL (~,C J3)FLOW, AND IVANGEN MW ELECT. Proper response on acti-vation of the MS-V-28D Inadvertent Slow Closure malfunction was tested and vai6ed.

INI'ITALCONDITIONS: IC-12 100Vo Power with Equilibrium Xenon FINALCONDITIONS: IC-12 100% Power. with MS Lines higher than initial.

~, 8'ow indication upscale and RPV/P SOURCE OF COMPARISON DATA:

PLANT DATA SET

[7 ENOINEERINO EVALUATION SOER / LER g OPERATIONAL ASSESSMENT TEST RESULTS:

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

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.24.85J REV. 0 TITLE: MS-V-28B -INADVERTENTSLOW CLOSURE OVERVIEW:

This test was performed to demonstrate the functionality of the MS-V-28B - INADVERTENT SLO7/'LOSURE Malfunction. Slow, inadvertent closure of MS-V-28B over approximately one minute. System responses included: MSIV-V-28B slow dosed, was full shut at about 60 seconds, and Rx power and pressure stabiTized approximately one minute later. The following Simulator'Per-fonnance Verification System (SPV's) variables were plotted and evaluated: APRM (AP), RPV/L NR, RPV/P NR, MSL (~,Cg))FLO%', AND MAINGEN MW ELECI'. Proper response on acti-vation of the MS-V-28B Inadvertent Slow Closure malfunction was tested and verified.

INITIALCONDITIONS: IC-12 1009o Power with Ettuilibrium Xenon FINAL CONDITIONS: IC-12 1009o Power. with MS Lines A,C, 8c D Sow indication upscale and RPV/P higher than initial.

SOURCE OF COMPARISON DATA:

PLANT DATASET ENGINEEIUNG EVALUATION FSAR Q SOER I LER g OPERATIONAL ASSESSMENT TEST RESULTS:

TESI'ESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACIORY WITHOUT DISCREPANCIES

TEST CATEGORY: Malfimction Tests TEST No. 14.4.9.25.1 REV, 0

'ITTLE: LPCS-P-I SHAET SHEAR OVERVII:W:

This test was performed to demonstrate the fitnctionality of the LPCS-P-1 SHAFT SHEAR Mal-fimction. LPCS-P-1 Shaf't Shear Break between motor and pump. System responses included:

LPCS-P-1 Motor Amps decreased, LPCS-P-1 Flow decreased to zero, Discharge pressure decreased to approx to 100 on LPCS-PI-3, and appropriate annunciator alarms. Proper response on activation of malhnction LPCS-P-1 SHAFT SHEAR was tested and verified.

INI'IIALCONDITIONS: IC-12 100% Power with Equilibrium Xenon FINALCONDITIONS: IC-12 100% Power with Equilibrium Xenon SOURCE OF COMPARISON DATA:

PLANT DATA SEI'NGINEERING EVALUATION SUER / LER g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES g TESI'RESULTS SATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.25.1A aZV. 0 TITLE: LPCS-P-I TNP 0

VERVET'his test was performed to demonstrate the functionality of the LPCS-P-1 TRIP Malfunction. Elec-tric fault causes overload trip. System responses included: LPCS-P-1 Amps decreased to zero,.Dis-charge Press LPCS-PI-3 decreased to approx 1@, LPCS How LPCS-FI-600 decreased to approx 200 GPM, and appropriate annunciators alarmed. Proper response on activation of mal&ntction LPCS-P-1 was tested and vexi6ed.

INIIIALCONDITIONS: IC-12 100% Power with Ettuilibrium Xenon FINAL CONDITIONS: IC-12 100% Power with BIuilibriumXenon, SOURCE OF COMPARISON DATA:

PLANT DATA SET ENOINEERINO EVALUATION FSAR SOER / LER g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY W1TH DISCREPANCIES

[g TEST RESULTS SATISFACTORY WITH DISCREPANCIES Q TEST RESULTS SATISFACTORY W1THOUT DISCREPANCIES

TEST CATEGORY: Malfunction Tests TEST No. 14 4 9~ 3 REV. 0 TITLE: RHR-P-2C SE4FT SHEAR OVERVIEW:

This test was performed to demonstrate the functionality of the RHR-P-2C SHAFT SHEAR Mal-function. RHR-P-2C Shaft Shear break between motor and pump. System responses included:

RHR-P-2C motor amps decreased, RHR-P-2C discharge How decreased, discharge pressure decreased, and appropriate annunciators alarmed. Proper response on activation of RHR-P-2C Shaft Shear was tested and verified.

INHTALCONDITIONS: IC-12 100% Power with BpiiibriumXenon FINALCONDITIONS: IC-12 100% Power with equilibrium Xenon SOURCE OF COMPAKPON DATA:

PLANT DATA SEI'NGINEERING EVALUASION FSAR SUER/LER X OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES

. TEST RESULTS SATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACI'ORY WITHOUT DISCREPANCIES

TEST CATEGORY: Malfunction Tests TESTNo. 1449254 REV. 0 TITLE: HPCS-P-I SHAFT SHEAR OVERVIEW:

This test was performed to demonstrate the functionality of the HPCS-P-1 SHAI'T SHEAR Mal-function. HPCS-P-1 Shaft Shear break between motor and pump. System responses included:

HPCS-P-1 motor amps decreased, HPCS-P-1 discharge Bow decreased, discharge pressure decreased, and appropriate aununciators alarmccL Proper response on activation of HPCS-P-1 Shaft Shear was tested and veri6ed.

INITIALCONDITIONS: IC-12 100% Power with Ecguiibrium Xenon J

FINALCONDITIONS: IC-12 100% Power with BIuilibriumXenon SOURCE OF COMPARISON DATA:

PLANT DATASET ENGINEERING EVALUATION FSAR SOER/LER QX OPIEIATIONALASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACI'ORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITHOUT DISCREPANCSES

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.25.6 REV. 0 THEE: RPR-V&2B FAILS CLOSED 4

OVERVII..W:

This test was performed to demonstrated the functionality of the RHR-V-423 FAILS CLOSED Malfunction. Fails closed duc to mechanical seizure. System responses included: RHR-3 initiated at L6Q DPI pressure, RHR-V423 did not open at 47@

Rx Press, there was no indicated system Bow on RHR-FI-603B, and RHR-V-423 would not open manually. Proper response on activation of RHR-V<23 FAILS CLOSED ma15mction was tested and verified.

INI'ITALCONDITIONS: IC-12 1009o Power with Bpilibrium XEnon, MEDIUMSIZE LOCA FINAL CONDITIONS: Reactor has scratnmed, LOCA in progress, no injection fmm RHR B system.

SOURCE OF COMPARISON DATA:

PLANT DATA SET

[7 ENOINEERINO EVALUATION FSAR SOER i LEE Q OPEIIATIONALASSESSMENT TEST RESULTS:

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

W TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.25.7 REV. 0 TZIT.E'FR-V-42C FAILS CLOSED OVERVIEW This test was performed to demonstrated the functionality of the RHR-VQZC FAILS CLOSED Malfunction. Fails closed due to mechanical seinue. System responses included: RHR-C initiated at L68¹ D/W pressure, RHR-V-42C did not open at 470¹ Rx Press, there was no indicated system Bow on RHR-FI-603C, and RHR-V42C would not open manually. Proper response on activation of RHR-V-42C FAILS CLOSED malftmction was tested and veri6ed.

INH'IALCONDITIONS: IC-12 1009o Power with Equilibrium XEnon, MEDIUMSIZE LOCA HNAL CONDITIONS: Reactor has scramxned, LOCA in progress, no injection from RHR C system.

SOURCE OF COMPARISON DATA:

PLANT DATA SEI'NGIPIEERING EVALUATION FSAR SOERI LEE g OPEIIAIIONALASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9,25.8 REV. 0 TITLE:EB-P-2B TRlP.

OVERVIEW'his test was performed to demonstrate the functionality of the RHR-P-2B Malfunction, RHR-P-23 Trip on overload due to electrical fault. System responses included: RHR-P-23 AMPS indicated 0, RHR-P-2B Flow indicator approx 200 on RHR-FI-6033, RHR-P-2B Discharge Pressure indicated approximately 10 psig on RHR-PI-612B, control switch indicating lights indicated pump tripped, and appropriate annunciators alarmetL Proper response on activation of malfunction RHR-P-2B TRIP were tested and vezi6etL INITIALCONDITIONS: IC-12 100% Power with Equilibrium XEnon, RHR-P-2B in Full Flow Test at rated liow.

FINAL CONDITIONS: IC-12 100% Power with Equilibrium XEnon, RHR-P-2B in Full Flow Test at rated How, except RHR-P-23 is tripped SOURCE OF COMPARISON DATA:

PLANT DATA SEI'NGINEERING EVALUATION FSAR SUER/LER g OPERATIONAL ASSESSMENT TEST RESULTS:

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

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.25.9 REV, 0 TITLE:RHR-P-2C TREP OVERVII.W:

This test was performed to demonstrate the functionality of the RHR-P-2C Malfunction.

RHR-P-2C Trip on overload due to electrical fault. System responses included: RHR-P-2C AMPS indicated 0, RHR-P-2 Flow indicated approx 20 on RHR-FI-603C, RHR-P-2C Dis-charge Pressuxe indicated approximately 10 psig on RHR-P!-612C, control switch indicating lights indicated pump tripped, and appropriate annunciators alarmed. Proper response on acti-vation of malfunction RHR-P-2C TRIP was tested and verified.

INITIALCONDITIONS: IC-12 1009o Power with Equilibrium XEnon, RHR-P-2C in Full Flow Test at rated Sow.

FINALCONDITIONS: IC-12 1009o Power with Equilibrium XEnon, RHR-P-2C in Full Flow Test at rated Qow, RHR-P-2C is tripped SOURCE OF COMPARISON DATA:

PLANT DATA SEI'NGINEERING EVALUATION

[7 FSAR SOER / LER g OPERATIONAL ASSESSMENT TEST RESULTS:

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

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.25.10 REV. 0 1TILE: 8PCS-P-1 TRIP OVERVIEW This test was performed to demonstrate the iunctionality of the HPCS-P-1 TRIP malsmction. Elec-trical fault causes HPCS-P-1 to trip. System responses. included: HPCS-P-1 AMPS indicated 0, HPCS-P-1 Qow indicated approx 200 on HPCS-FI-603, HPCS-P-1 discharge pressure indicated approximately 10 psig on HPCS-P-601, control switch indicating lights indicated pump tripped, and appropriate annunciators alarmed. Proper response on activation of HPCS-P-1 TRIP malfunction was tested and veri6e INITIALCONDITIONS: IC-12 1009o Power with Equilibrium Xenon, HPCS-P-1 in fall Sow system test.

FINAL CONDITIONS: IC-12 1009o Power with Equilibrium Xenon with HPCS-P-1 is tripped.

SOURCE OF COMPARISON DATA:

PLANT DATA SET ENGINEERING EVALUATION FSAR SUER / LER g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITH DISCREPANCIES Q TEST RESULTS SATISFACTORY WITHOUT DISCREPANCES

TEST CATEGORY: Mal&mction Tests TEST No. 14.4.9.25.11 REV. 0 TITLE RHR-V 16AP 16Br 17AP chic 17B FAILCLOSED OVERVIEW:

This test was performed to demonstrate the functionality of the RHR-V-16A, 16B, 17A, 0 17B FAIL CLOSED Malfunction. RHR-V-I6A, 16B, 17A, 17B mechanically bound in closed position.

Valves were cycled one at a time to insure they worked properly. Valve malfunctions were inserted for the valves one at a time, attempts were then made to open the respective valves. Proper response on activation of the individual valve malfimctions was tested and veri6ed.

INITIALCONDITIONS: IC-12 100% Power with Equilibrium Xenon, FINAL CONDITIONS: IC-12 100% Power with Equilibrium Xenon SOURCE OF COMPARISON DATA:

PLANT DATA SEI'NGINEERING EVALUATION FSAR Q SOER HLER Z OPERATIONAL ASSESSMENT TEST RESULTS:

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

TEST CATEGORY: Malfunction Tests TEST No. 144 925 12 REV. 0 TITLE: RCIC-V-I3 FALLS TO OPEN OVERVIEW:

This test was performed to demonstrate the functionality of the RCIC-V-13 FAILS TO OPEN Mal-function. RCIC-V-13 fails to open duc to electrical malfunction. Armed and Depressed RCIC initia-tion PB. System responses included: RCIC-V-2 opened, RCIC-V-13 did not open, RCIC Turbine (Speed, Exh Press, Pump Discharge Press) increased, RCIC-V-19 opened on low fiow, and RCIC system fiow remained at zero as indicated on RCIC-FI-600. RCIC-V-13 did not open when C/S was placed to open. Proper response on activation of thc RCIC-V-13 FAILS TO OPEN malfunction was tested and verified.

INfl'IALCONDEMNS: IC-12 100% Power with Equilibrium Xenon, FINALCONDITIONS: IC-12 100% Power with Equilibrium Xenon SOURCE OF COMPARISON DATA:

PLANT DATASET ENGINEERING EVALUATION Q FSAR SUER/LER X OPERATIONAL ASSESSMENT TEST RESULTS:

Q TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES Q TEST RESULTS SATISFACTORY WITH DISCREPAiVCIES g TEST RESULTS SATISFACI DRY WITHOUT DISCREPANCIES

NAL TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.25.13 REV. 0 TITLE: RCIC-V<5 FAILS CLOSED OVERVIEW:

This test was performed to demotu>trate the functionality of the RCIC-V45 FAILS CLOSED Mal-function. RCIC-V45 fails closed due to electrical fault. RCIC in FULL FLOW test, CST to CST.

System responses induded: RCIC-V45 dosed, RCIC-V-19 did not auto open with RCIC coast-down, RCIC Turbine (Speed, Exh Press, Discharge Press, System Flow) decreased; appropriate annunciators alarmed, and RCIC-FIC-600 output increased to maximum. RCIC-V45 failed to open when C/S was placed to open. Proper response on activation of the RCIC-V-45 FAILS CLOSED malfunction was tested and vea6ed.

INZIIALCONDITIONS: IC-12 100% Power with Equilibrium Xenon, FINALCONDITlONS: IC-12 100% Power with Equilibrium Xenon SOURCE OF COMPARISON DATA:

PLANT DATASET ENGINEEIUNG EVALUATION FSAR SOER / LER QX OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISPACI'ORY WITH DISCREPANCKS g TEST RESULTS SATISFACTORY WITH DISCREPANCIES

[7 TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Malfimction Tests TEST No. 14.4.9.25.15A REV. 0 TITLE: RCC-P-1B TRlP OVERVIEW:

This test was performed to demonstrate the functionality of the RCC-P-1B HIP malfizction. RCC-P-1B Trips on Thermal OL due to electrical fault. System responses included: RCC-P-1B tripped, RCC Pump B Motor OL Trip annunciator alarmed, RCC-P-1A auto started, RCC HDR PRESS RCC-PI-3 decreased and then returned to normal, and RCC-V4 renuuned open. Proper response on activation of the RCC-P-1B TRIP malfunction was tested and verified.

INITIALCONDlTIONS: IC-12 100% Power with Equilibrium Xenon, RCC-P-1B and RCC-P-IC running RCC-P-1A in stby.

FINALCONDITIONS: IC-12 100% Power with Equilibrium Xenon RCC-P-1A and RCC-P-1C running.

SOURCE OF COMPARISON DATA:

PLANT DATA SET Q ENGINEERING EVALUATION FSAR

[7 SOERi LEE X OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACI'ORY WITHOUTDISCREPANCIES

P TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.25.15B REV. 0 TITLE: RCC-P-1C 2KP OVERVIIVV:

This test was performed to demonstrate the functionality of the RCC-P-1C TRIP malfunction. RCC-P-1C Trips on Thexmal OL due to electrical fault. System responses included: RCC-P-1C tripped, RCC Pump C Motor OL Trip annunciator alarmed, RCC-P-1B 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-1C TRIP malfunction was tcstcd and verified.

INITIALCONDITIONS: IC-12 100% Power with Ecpxilibrium Xenon, RCC-P-1A and RCC-P-1C running RCC-P-IB in stby.

HNAL CONDITIONS: IC-12 100% Power with Epilibrium Xenon RCC-P-1A and RCC-P-1B amning.

SOURCE OF COMPARISON DATA:

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

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

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.25.16 REV. 0 TITLE: MCNAB TRlP OVERVlEV.

This test was performed to demonstrate the functionality of the MC-8B TRIP Malfunction. MC-8B BKR electrical fault in TRIPPING CXT. Proper response to the loss of motive power provided by MC-8B and her daughter busses MC-8B-A and MC-8B-B were tested and verified. Proper response to the loss of control and indication power provided by MC-8B and her daughter busses MC-8B-A and MC-8B-B were tested and vexi6ed.

1NIITALCONDITIONS: IC-12 100% Power with Eqmlibzium Xenon HNAL CONDITIONS: IC-12 100% Power with Equilibrium Xenon, loads on MCNAB and daughter busses de~eqpzed.

SOURCE OF COMPARISON DATA:

PLANT DATA SEP ENORIEERRIO EVALUATION FSAR SUER / LER g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.25.18 REV. 0

'ITILE: ARMS/PROCESS MONITOR FAILURES OVERVIEW This test was performed to demonstrate thc functionality of thc ARMS/PROCESS MONITOR FAILURES Malfunction. ARM CKT FAILURES causing associated ARM UPSCALE response.

Fifteen ARM-RIS->> s were checked individually. The following is an example of one test. ARM-RIS< malfunction was activated. System responses included: ARM-RISA meter indicated high, high setpoint light illuminated on instrument, and Annunciator P602-A5-3.1 Rx Bldg. Rad High alarmed at setpoint. Proper response on activation of the individual ARMS/PROCESS MONITOR FAILURES was tested and vcri6cd.

INDI'IALCONDlTIONS: IC-12 100% Power with Equilibrium Xenon FINALCONDEMNS: IC-12 100% Power with Equilibrium Xenon, SOURCE OF COMPARISON DATA:

PLANT DATASET Q ENGINEERING EVALUASION FSAR SUER / LER X OPERATIONAL ASSESSMENT TEST RESULTS:

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

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.25.21 REV. 0 TITLE: LPRM FAILS UPSCALE OVERVIEW:

This test was performed to demonstrate the functionality of the LPRM FAILS UPSCALE Malfunc-tion. System responses included: LPRM 24-25 Detector A Upscale light illununated on FULL CORE display and LPRM Upscale annunciator P603-AS-2-5 alarmed. Control Rod 26-23 was selected: Upper left LPRM group Detector A level% Heat Flux Meter indicated Upscale, APRM A recorder read slightly higher, and RBM A recorder read higher. Proper response on activation of the LPRM FAILS UPSCALE malfunction was tested and verified.

INI'ITALCONDITIONS: IC-12 100% Power with Equilibrium Xenon FINAL CONDITIONS: IC-12 100% Power with Equilibrium Xenon, SOURCE OF COMPARISON DATA:

[7 PLANTDATASET ENGINEERING EVALUATION FSAR SOER / LER QX OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPAiVCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Malfunction Tests TEST No. 14.4 9 25 22 REV. 0 TITLE: RHR-V<2A FAILS CLOSED OVERVIEW:

This test was performed to demonstrated the functionality of the RHR-V<2A FAILS CLOSED Malfunction. Fails closed post LOCA due to mechanical seizure. System responses included: RHR-A initiated at L68¹ D/W pressure, RHR-V-42A did not open at 470¹ Rx Press, there was no indi-cated system flow on RHR-FI-603A, and RHR-V-42A would not open manually. Proper response on activation of RHR-V-42A FAILS CLOSED malfunction was tested and verified.

INI'GALCONDITIONS: IC-12 1009o'Power with Equilibrium Xenon FINAL CONDITIONS: Reactor has scxanuned, LOCA in progress, no injection from RHR A system.

SOURCE OF COMPARISON DATA:

PLANT DATA SEI'NGINEEIUNG EVALUATION FSAR SOER(LER QX OPERATIONAL ASSESSi~NT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TESI'ESULTS SATISFACI'ORY WITH DISCREPANCIES TEST RESULTS SATISPACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Ma16znction Tests TEST iNo. 14.4.9.25.23 REV. 0 TXI'LE: CAS4-lA- LOSS OF COOLlNG OVERVH:W:

This test was performed to demonstzate the functionality of the CAS-C-IA - LOSS OF COOLING Malfunction. CAS-C-IA Loss of Cooling (ASubsequent Trip). System responses included: Air Compressor A discharge temperature high annunciator alazmed, Air Compressor A Motor Trip alarmed, CASK-1A LATCH RESEI'hite light extinguished, when stem pressure had dropped to approximate1y 90 psig the Standby Air Compressor and accompanying alazm came on. System air pressure began to rise and the AIR RECEDi'ER PRESS LO%'lazm did not come in. Proper response on activation of the CAS-C-lA LOSS OF COOLING iVhlfunction was tested and verified.

INITIALCONDITIONS: IC-12 1009o Power with Ettuilibzium Xenon FINAL CONDITIONS: IC-12 1009o Power with Equilibrium Xenon, CAS-C-1A compressor de-ener-gized, Standby compzessor mnning.

SOURCE OF COMPARISON DATA:

PLANT DATASHP ENGINEERING EVALUATION FSAR SUER / LER QX OPERATIONAL ASSESSMENT TEST RESULTS:

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

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.25.24 REV; 0 TITLE: TG HP ROTOR HIGH VIBERATION OVERVIEW This test was performed to demonstrate the functionality of the TG HP ROTOR HIGH VIBRA-TION MaKunction. Main 'Bubine HP Rotor VReratioin due to improper balancing. System responses included: Vibexation increased on TG-XR-VXCDpts 1852, RED lights Ol 8t2 illuminated on TG ~iration Monitor 01, P820-Bl-7-6 ROTOR MON 1 VIB HIGH annunciated at 7 mils as shown on TG-XR-VXCD pts 1852, and bearings 1882 indictated increased vibration on the DEH CRT (Display on Pg. 4). Proper response on activation of the TG HP ROTOR HIGH VIBRATION malfunction was tested and veri6ed.

1NZITALCONDITIONS: IC-12 100% Power with EtluilibriumXenon HNAL CONDITIONS: IC-12 100% Power with Ecpxilibrium Xenon SOURCE OF COMPARISON DATA:

PLANT DATA SEI'NGINEERING EVALUATION FSAR SUER / LER X OPERATIONAL ASSESSMENT TEST RESULTS:

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

TEST CATEGORY: Mal6mction Tests TEST No. 14 4.9 25 25 REV. 0 TITLE GENER4TOR HYDROGEN PRESSURE COiVTROL FAILURE 0VERVIE%'.

This test was performed to demonstrate the hmctionality of the GENERATOR HYDROGEN PRESSURE CONTROL FAILURE Malfunction. The malfunction simulates Hydrogen Pressure decrease with 100% severity. System responses included: GEN H2 PRESS LOW annunciated at LT 72 psig H2 press, GEN HZ TEMP HIGH annunciated at GT 48 degrees C gas temp as read on TG-TR-144, STATOR COIL WTR/HZ DP LOW annunciated at approx 55 psig press as read on H2-PI-1, GEN H2 PURXIY LT 90% annunciated at <90% purity as read on HZ-PU-1, and the white alarm light Bluminated on TG-TR-144. Proper response on activation of the Generator Hydrogen Pressure Control Failure malfunction was tested and veri6ed.

INITIALCONDlTIONS: IC-12 100% Power with Equilibrium Xenon FINALCONDITIONS: IC-12 100% Power with Equilibrium Xenon SOURCE OF COMPARISON DATA:

PLANI DATASET ENGINEERING EVALUATION FSAR SUER /LER QX OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES X TEST RESULTS SATISFACI'ORY WITH DISCREPAiVCIES Q TEST RESULTS SATISFACTORY WITHOUT DISCREPANCES

TEST CATEGORY: Malfunction Tests TEST No. 14A.9.25.26 REV. 0

'ITTLE: RBM CH A FALLS UPSCALE OVERVIEW:

S This test was performed to demonstrate the functionality of the RBM CH. A FAILS UPSCALE Malfunction. RBM A FAILS UPSCALE due to electrical fault in drawer. System responses included: RBM UPSCALE or INOP P603-A8-3-5 alarmed, RBM A indicated Upscale on IRM-LR-603C, RBM A UPSCALE light illuminated, ROD BLOCK OUT P603-A7-2-7 alarmed, and With-draw Block Light illuminated on P603. RBM BYPASS SWTTCH was positioned to A position:

RBM UPSCALE ALARMcleared, ROD OUT BLOCK cleared, RBM A UPSCALE light extin-guished, RBM A BYPASS light illuminated 8h WTTHDRAWNBLOCK P603 Benchboard clears.

Proper response on activation of RBM CH A FAILS UPSCALE malfunction was tested and veri-fied.

INTTIALCONDITIONS: IC-12 100% Power with BIuiiibriumXenon FINALCONDITIONS: IC-12 100% Power with Equilibrium Xenon SOURCE OF COMPARISON DATA:

PLANT DATA SEI' ENGINEEIUNG EVALUATION FSAR Q SOER(LER g OPERATIONAL ASSESSMENT TEST RESULTS:

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

TEST CATEGORY: Malfunction Tests TEST No. 14A.9,25.27 REV. 0

'ITTLE: RPV NR LFVEL RECORDER PEN STICES OVERVIEW:

This test was performed to demonstrne the functionality of the RPV NR LEVELRECORDER PEN STICKS Malfunction. Recorder Drive Cable breaks for NR Input on RFW-LR-608. Increased RPV LEVEL MASTER CONTROL RFW-LIC-600 Setpt to 39"; system responses included: RFW-LI-606(A33,C) increased to 39", RFW-LR-608 NR Black Pen did not change. Decreased RPV LEVEL MASTER CONTROL RFW-LIC400 Stpt to 31". RFW-LI-606 (~,C) RPV/L decreased to 31" and RFW-LR408 NR Black Pen did not change. The Red pen did follow the transient. Proper response on activation of RPV NR LEVEL RECORDER PEN sticking was tested and vexi6ed.

INITIALCONDZIIONS: IC-12'100% Power with Equilibrium Xenon FINAL CONDITIONS: IC-12 100% Power with Equilibrium Xenon SOURCE OF COMPARISON DATA:

PLANT DATASEP ENGINEERING EVALUAHON FSAR SOER / LER QX OPEIIATIONAL ASSESS'iiPWI'EST RESULTS:

TESP RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES lm TEST RESULTS SATISFACI'ORY WITHOUT DISCREPANCIES

TEST CATEGORY: Malfunction Tests TEST No. 14 4.9.25.28 REV. 0 TITLE: HI OZ1'GEN IN CONTAINMENT dd' R d d d 'd dd ldDXYGHNINCO ddldmddd Malfunction. Zirconium/Water Reaction is simulated to result in oxygen production. System responses included: CMS-02R-1 and CMS42R-2 indicated (02) increased to approximately 10%,

OXYGEN LEVELHIGH P814-J(142)-1-2 alarmed at 3.25%, and OXYGEN LEVEL HIGH P814-J(182)-5-2 alarmed at 3.7%. Proper response on activation of malfunction HI OXYGEN IN CON-TAlNMENTMalfunction was tested and vezi6ed.

INHTALCONDZTIONS: IC-12 100% Power with Equilibrium Xenon FINALCONDITIONS: IC-12 100% Power with Equilibrium Xenon SOURCE OF COMPARISON DATA:

PLANT DATASET ENGINEIEUNG EVALUATION FSAR SUER / LER QX OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACI'ORY WITH DISCREPANCIES

'd TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.25.29 REV. 0 TITLE: FWH 1A TUBE RUPTURE OVERVIEW:

This test was performed to demonstrate the functionality of the FWH 1A TUBE RUFI'URE Mal-function. Erosion and hydraulic stress result in multiple tube ruptures. System responses included:

LP HTR 1A LEVEL HIGH and HIGH TRIP alarms activated, BS-DV-1A opened, COND-V-123A and COND-V-134A closed and COND-V-141A opened, COND-DPI-17A indicated zero, STEVE DUMP VALVES not full closed alarmed, RFW-TI-5 indicated a decreased RPV Inlet FW/I; Reac-tor Power Increased slightly, and MN GEN Elect Generation decreased slightly. Proper response on activation of the FWH 1A TUBE RUPTUI& mal6mction was tested and verified.

INIIXALCONDITIONS: IC-12 1009o Power with Eqmlibrium Xenon FINAL CONDITIONS: IC-12 1009o Power with Equilibrium Xenon SOURCE OF COMPARISON DATA:

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

TESI'ESULTS UNSATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITH DISCREPANCIES .

TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

OP TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.25.30 REV. 0 TITLE: RFW TURBINES HI VZBRATlON This test was performed to demonstrate thc functionality of the RFW TURBINES HI VIBRATION Malfunction. Turbine imbalance results in a high vibration condition. System responses included:

RFW-T-1A VIBRATIONincreased to 2.2 as indicated on RFT-VBAM-1A, RFW-T-1B VIBRA-TION increased to 4.7 as indicated on RFT-VBAM-1B, and RFW-T-1B alarm TURB B VIB HIGH P840-A1-7.5 alarmed OXS mills. The severity of malfunction was increased. System responses included: RFT-T-1A VIBRATIONincreased to approx 4d, RFW-T-1A alarm TURB A VIB HIGH P840-A1-7.1 alarmed O25 mills. Recorders for both the A and B turbines indicated increased vib-eration. Proper response on activation of the RFW TURBINES HI VIBRATIONmalfunction was tested and verified.

INZI'IALCONDEMNS: IC-12 1009o Power with Equilibrium Xenon FINALCONDITIONS: IC-12 1009o Power with Equilibrium Xenon SOURCE OF COMPARISON DATA:

PLANT DATA SET Q ENGINEERING EVALUATION SUER / LER X OPERATIONAL ASSESSMENT TEST RESULTS:

Q TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITHOUT DISCREPANCKS

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.25.31 REV. 0 TI'ILE'A.FWH LOSS OF EXT STM OVERVH:W:

This test was performed to demonstrate the functionality of the 5A FWH LOSS OF EXT S'M Mal-function. ES NR and DUMP VALVE I.OGIC FAILURE initiates Loss of ES. System responses included: BS-V-5A aud BS-VAA indicated CLOSED, BS-'DV-5A mdicated open, STM DUMP valves not full closed P840-A2-9.6 alarmed, RPV INLETTEMP decreases on RFW-TI-5, APRMS

~,CQ@,8'ndicate 1-2% pwr increase, Gen MW Output decreased on DEH Turbine Control LED, and 5A FWH Press decreased on BS-PI-5A. Proper response on activation of the 5A FWH LOSS OF EXT STM malfunction was tested and verified.

INI'GALCONDITIONS: IC-12 100% Power with Equilibrium Xenon FINALCONDITIONS: IC-12 100% Power with Equilibrium Xenon SOURCE OF COMPARISON DATA:

PLANT DATA SEI'NGINEEIUNG EVALUATION FSAR Q SUER.HLER g OPERATIONAL ASSESSMENT TEST RESULTS:

Q TEST RESULTS UNSATISFACI'ORY WITH DISCREPAiVCIES g TEST RESULTS SATISFACI'ORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.25,32 REV. 0 TZILE: 6A FWB'OSS OF EST STM 0VERVH..W:

This test was performed to demonstrate the functionality of the 6A FWH LOSS OF EXT STM Mal-function. ES NR and DUMP VALVE LOGIC FAILURE initiates Loss of ES. System responses included: BS-V-7A and BS-V-6A indicated CLOSED, BS-DV-6A indicated open, STM DUMP valves not full closed F840-A2-9.6 alarmed, RPV INLETTEMP decreases on RFW-TI-5, APRMS

~,Cgg,~ indicate 1-2% pwr increase, Gen MW Output decreased on DEH Turbine Control LED, and 6A FWH Press decreased on BS-PICA. Proper response on activation of the 6A FWH LOSS OF EZT STM malfunction was tested and verified.

INH'IALCONDXHONS: IC-12 100% Power with Equilibrium Xenon FINALCONDITIONS: IC-12 100% Power with Equilibrium Xenon SOURCE OF COMPARISON DATA:

PLANT DATA SEI'NGINEERING EVALUATION FSAR SUER/LER g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITHOUTDISCREPANCIES

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.25.33 REV. 0 TITLE: REF-I.CV-10 CONTROLLER OUTPUT FAILS LOW OVERVIEW'his test was performed to demonstrate the functionality of the RFW-LCV-10 CONTROLLER OUTPUT FAILS LOW Malfunction. RFW-LCV-10 CONTROLLER OUTPUT FAILS LOW. Sys-tem responses included: RFW-LCV-10A/B shut, Flowindication on RFW-FI404A/B and RFW-FR-607 decreased to zero, RPV/L indication on RFW-LI-606',C decreased, RPV/L indication on RFW-LR408 decreased, RPV Level High/Low alert alarmed, SU Valve DP increased on RFW-DPIP, RFW Pump discharge press increase, RPV/L decreased to 13", and a Reactor SCRAM occurred. Proper response on activation of the RFW-LCV-10 CONTROLLER OUTPUT FAILS LOW ma16mction was tested and veri6ed INITIALCONDITIONS: IC-8, 21% Power, Ready for Synchronization FINALCOND1TIONS: Reactor Scratnmed

~

SOURCE OF COMPARISON DATA:

Q PLANT DATA SET ENGINEERING EVALUATION FSAR SOER / LER X OPERATIONAL ASSESSMENT TEST RESULTS:

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

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.25.33A REV. 0 TI'ILE: EWLC SU LEVEL CONTROL FAILS LOW OVERVIEW:

This test was performed to demonstrate the functionality of the FWLC SU LEVEL CONTROL FAILS LOW Malfunction. Inteznal Circuit Failure causes FWLC SU LEVEL CONTROL to fail low to minimum output. System zesponses included: RFW-LCV-10A/B shut, Flow indication on RFW-FI-604A/B and RFW-FR-607 decreased to zero, RPV/L indication on RFW-LIM6AJ,C deczeased, RPV/L indication on RFW-LR-608 decreased, RPV Level High/Low alert alarmed, SU Valve DP increased on RFW-DPI', RFW Pump discharge press increased, RPV/L decreased to 13", and a Reactor SCRAM occuzzed. Proper zesponse on activation of the FWLC SU ~/EL CONTROL FAILS LOW n~mction was tested and veri6ed.

INK'IALCONDITIONS: IC-8, 21% Power, Ready for Synchronization FINALCONDITIONS: Reactor Scrammed SOURCE OF COMPARISON DATA:

PLANT DATA SEI'NGINEERING EVALUATION FSAR SUER / LER g OPERATIONAL ASSESSMENT TEST RESULTS:

TESI'ESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES TEST RESULTS. SATISFACI'ORY WITHOUT DISCREPP+VCIES

TEST CATEGORY: Malfunction Tests TEST No. 144925 35 REV. 0 TITLE: LOSS OF PRESS SUPPRESSION FUNCTION OVERVIEW:

This test was performed to demonstzate the functionality of the LOSS OF PRESS SUPPRESSION FUNCIION Malfunction. Loss of Primary Containment Press Suppression Function (Drywell Hoor Failure) followed by a Main Steam Line Rupture. System responses includetL Drywell and Wetwell Pressure increased concurrently, Dzywell Pressure and Wetweli pressure tracked together and exceeded design pressure within a few minutes, appropriate annunciators alarmed, Dryweil temperature exceeded 280 degrees in approximately 8 minutes, and Wetwell water temperature and level did not increase appreciably. Reactor Scrammed at less than 2 psig Drywell pressure. Proper response on activation of the LOSS OF PRESS SUPPRESSION FUNCTION malfunction was tested and veri6ed.

O'KIIALCONDITIONS: IC-12 1009o Power with Ecpulibrium Xenon FINAL CONDITIONS: Reactor Scranuned.

SOURCE OF COMPARISON DATA:

PLANT DATA SEI'NGINEERING EVALUATION FSAR SOER / LER X OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACI'ORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPAiVCIES TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY; Malfunction Tests TEST No. 14.4 9 25 36 aSV. 0 TITLE: RWCU LEAJ/'N Eg,UIPMZlYTAREA OVERVlEW:

This test was performed to demonstrate the functionality of the RWCU LEAK IN EQUIPMENT AREA Malfunction. Rupture in the RWCU piping between the F/D suction isolation valve (V-2068) and the F/D. System responses included: F603-AS+7 CLASP HLTER DEMIN FAIL-URE alarmed, RWCU-FI-620 RWCU DIFF. FLOW increased and then decreased, RWCU-FI-609 PUMP SUCTION increased and then decreased, RWCU-FI-605B FILTER DEMIN FLOW decreased to zero, and RWCU-H- 605A HLTER DEMIN FLOW increased to approx 240 gpm.

Proper response on activation of the RWCU LEAK IN EQUIPMENT AREA malfunction was tested and veri6ed.

INK'IALCONDITIONS: IC-12 100% Power with Ecgnlibrium Xenon HNAL CONDITIONS: IC-12 100% Power with Ectuilibrium Xenon SOURCE OF COMPARISON DATA:

[7 PLANTDATASET ENGINEERING EVALUATION FSAR SOER / LER g OPERATIONAL ASSESSMENT TEST RESULTS:

tm TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES Q TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.25.37 REV. 0 TITLE: HIHYDROGEN 1N COlVTAlmE1VT OVERVIEVIt'his test was performed to demonstrate the functionality of the HI HYDROGEN IN CONTAIN-MENT Malfunction. Zerconium/water reaction is simulated to occur with resulting Hydrogen Pro-duction. System responses included: H2 increased to 8% on (CMS-H2R-I and CMS-H2R-2) and HYDROGEN level HIGH F814-J1-2.2 and P814-J2-2.2 alarmed at 3.S%. Proper response on acti-vation of the HI HYDROGEN in Containment malfunction was tested and verified.

INK'IALCONDITIONS: IC-12 100% Power with Equilibrium Xenon FINAL CONDITIONS: IC-12 100% Power with Equilibrium Xenon SOURCE OF COMPARISON DATA:

PLANT DATASET ENGINEERING EVALUATION FSAR Q SUER(LER g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DISCREPANCIES I

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

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.25.38 REV. 0 TITLE: BKR Sl FAILURE TO AUTO CLOSE OVERVIEW V:

This test was performed to demonstrate the functionality of the BKR Sl FAILURE TO AUTO CLOSE Malfunction. Failure of BUS S1 to Auto Close. Reactor was scrantmed, system responses included: P800-C3-2.1 BKR Nl-1 TRIP annunciated after Lockout Relays 86XU and 86XUOA tripped, BKR SI did not close, Power was lost to SM-1, BKR-B-7 shut and supplied SM-7, DG-1 started but did not close onto SM-7 Pmper response on activation of the BKR Sl Failure to Auto Close was tested and verifie. NOTE: Loss of SM-1 is evaluated in 14.4.9.8.3B INHTALCONDITIONS: IC-12 1009o Power with BtuilibriumXenon FINAL CONDITIONS: Reactor is scrammed, SM-1 is dewneqpzed SOURCE OF COMPARISON DATA:

PLANT DATA SET ENOINEEIUNO EVALUATION FSAR Q SOER QX OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UiiISATISFACTORYWITH DISCREPANCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.25.39 REV. 0 TITLE: S2-I DC GROUlVD OVERVIEW'his test was performed to demonstrate the functionality of the S2-1 DC GROUND Malfimction.

Simulates a zero resistance to ground on the bus duc to water in a DC control panel. This results in a ground annunciator on the bus and deQection on the ground detector meter. The battery charger amps increased until at 600 AMPS the output fuse blew and the charger was lost. Thc ground then resulted in the battery output fuse blowing and a loss of the SZ-1 bus. Motive Power was lost to the following loads: RCIC-V-(l, 4, 23, 13, 19, 22, 59, 45, 69), RHR-V-S, RCIC-P-(2, 4), TO-P-EOP, and RFT-EOP-(1A,lB). Proper response on activation of thc S2-1 DC GROUND malfunction was tested and verified.

INHTALCONDITIONS: IC-12 100% Power with Equilibrium Xenon FINALCONDEMNS: IC-12 100% Power with Equilibrium Xenon SOURCE OF COMPARISON DATA:

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

g TESI'ESULTS UNSATISFACTORY WITH DISCREPANCIES TESI'ESULTS SATISFACTORY WITH DISCREPANCIES Q TEST RESULTS SATISFACIORY WITHOUT DISCREPANCIES

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.25.40 REV. 0 TELE: RRC LOOP A BPU FUSE THS FAIL OVERVIEW This test was performed to demonstrate the functionality of the RRC LOOP A HPU FUSE TH5 FAILMalfunction. Loss of fuse TH5 in RC1 causing spurious closure of HV Isolation Valves with-out isolation signal present. The following valves changed status hn OPEN to CLOSED: HV-V-(17A, 18A, 19A, 20A, 33A, 34A, 35A, 36A). A manual attempt to reduce Bow in RRC Loop A on Flow Controller RRC-M'/A-611A did not cause RRC-FCV-60A to change position. Proper response on activation of the RRC LOOP A HPU FUSE TH5 FAILmalfunction was tested and verified.

INH'IALCONDITIONS: IC-12 100% Power with Ecpulibrium Xenon FINALCONDITIONS: IC-12 100% Power with Equilibrium Xenon SOURCE OF COMPARISON DATA:

PLANT DATA SEI'NGINEERING EVALUATION FSAR

[7 SOER>LER g OPERATIONAL ASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACI'ORY WITH DISCREPANCIES TEST RESULTS. SATISFACTORY WITH DISCREPANCIES g TEST RESULTS SATISFACTORY WITHOUT DISCREPANCIES

TEST CATEGORY: Malfunction Tests TEST No. 14.4.9.25.41 REV. 0

'ITIVE: RRC-P-IB 60 8 BROKER FriILS TO TRIP OVERVIEW:

This test was performed to demonstrate the failing functionality of the RRC-P-1B Hz BREAKER FAILS TO TRIP Malfunction. BKR RPT 3B Failliag to Trip when pump is started on 15 Hz. Pump was started IAWwith PPM 22.1, sytem responses included.Pump started to 60 Hz, MG-1B started, CB-RPT-3B did not Trip when pump reached GE 95% of 60Hz speed, and CB-LF-2B did not close because CB-RPT-3B had not tripped. Forty seconds later RPT-3B, 4B and LF-1B Tripped due to an incomplete start sequence. RRC-P-1B speed and Loop aud JP Flows delcayed back to reverse Flow Values. RRC-P-IB Incomplete Sectuence Annunciators activated. Proper response on activation of the RRC-P-1B 60 Hz BREAKER FAILS TO TRIP malftmction was tested and veri6ed.

INTIIALCONDITIONS: IC-8 39% Power Ready for 60 HZ FINALCONDITIONS: Power is reduced and Reactor is in Single Loop SOURCE OF COMPARISON DATA:

PLANI'ATASET ENGINEIEUNG EVALUATION FSAR SOER / LER g OPEIIATIONALASSESSMENT TEST RESULTS:

TEST RESULTS UNSATISFACTORY WITH DIS CREPAiVCIES TEST RESULTS SATISFACTORY WITH DISCREPANCIES g TMTRESULTS SATISFACTORY WIIIIOUTDISCREPANCIES

WNP-2 SIMULATOR CERTIFICATION APPENDIX F QUADRENNIALTESTING

WNP-2 SIMULATOR CERTiFICATION APPENDIX F QUADRENNIALTESTING Y~ea 1

1. Normal Plant Evolutions 07.04.00.05.13 - Reactor Vx Ijl 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 Opeabiffty 07.04.06.05.03.01 - Standby Gas Treatment OperabHlty Test 07.04.07.01.01.03- HPCS Service Water Valve Posion Verification 07.04.07.09.01 - Weekly Bypass Valves Test 07.04.08.01.01.02.06- HPCS Diesel Generator - Loss of Power Test

2. Malfunctfon Tests 14.4.9.18,3 - Instrument Une Break (Ref) l4.4.9.25.14A - SRV~ Slmmerfng

'l4.4.9.8.3B - Overcurrent SM-1 14.4.9.8.7- Loss of All Offsite Power 14.4.924.56- Battery Charger C1-1 Trip 14.4.9.22- Condenser Air Leak 14.4.9.24 48A - COND-P-1 A Trip 14.4.9.21.1 - ADS Logic Failure 14.4.9.3.1 - Rod Drfft 14.4.9.24.31 - Main Turbine Trip 14.4.9.24.40 - BP V-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 14.4.9.9.48 - RCIC Turbine Thp (High Exh. Pressure) 14.4.9.24.67C - RFW-Lt<06B Fails High 14.4.9.25.5 - RHR-P-2A Trip 14.4.9.25.19 - RPS Spurfous Scram A; 14.4.9.24.63 - DEH Pump 1A Trip 1 of 4

Normal Plant Evolutfons 14.4.72.1 - Startup from Hot Shutdown to Rated Pressure 14.4.72.3- SD to HSD 14.4.6.1 - Shutdown Margfn 14.4.62- Core Reactivity Coefficient Test 07.04.00.05.15- CIA Valve Operability 07.04.01.04.02.01 - RSCS Operability Prfor to Start-Up 07.04.03.08.02.01 - Monthly Turbine Valve Tests 07.04.05.01.04- LPCI Flow Path Verification 07.04.06.01.04.02- MSIV Leakage Control System 07.04.06.04.01.02- Suppression Chamber-Dry Well Vacuum Breaker Operability 07.04.06.05.03.04 - Standby Gas Treatment Manual Initiation Bypass Damper &

Heater Test

2. Malfunctfon Tests 14.4.9.18.6 - Instrument Une 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-2Trfp High Diff. Current 14.4.9.248 - Loss of RHR SDC due to RHR-P-2B Trip 14.4.9Z4.64A - TSW Pump B Trip 14.4.9Z4.78 - 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 - Mafn Generator Trfp 14.4.9.24.40A - BPV-2 Failure 14.4.9.21.6 - RCIC Steam Une 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 14.4.92929- RPS Spurious Scram B 2 of 4

Normal Plant Evolutfons 14.4.6.6- SRM/IRM vs. Control Rod Motion 07.04.00.06.18 HPCS Servfce Water Operability/Demo 07.04.03.01.01.22- Manual SCRAM Function Test 07.04.04.02.01.01 - Safety Relief Valve Acoustic Monitor CC 07.04.05.01.05 - LPCS Valve Lineup/Ads Inhibit CFT 07.04.06.01.04.02A - MSIV Valve Operability 07.04.06.06.02.01 - Reactor Building Ventiiaifon Isolatfon Valve Operability 07.04.07.01.01.02- Standby Service Water Loop B valve Position VerNcatfon 07.04.08.01.01.01.02- 18 Month Manual 8 Auto XFR Test, Start-Up to Backup Station Power 07.04.08.01.01.02.11 - Diesel Generator ff2- Operability Test Maffunctfon Tests 14.4.92427 - Main Steam Safety Relief Valve Fafls Open 14.4.9.4.4- Leak Downstream Control Alr Dryer 14.4.9.24.15 - S1-1 DC Ground 14.4.9.24.15A - S1-1 Tdp 14.4.9.24.34- Recfrcufatfon Pump B Trip 14.4.944.64 - TSW Pump A Trfp 14.4.9.24.6- SW Pump A Trfp 14.4.9.2.9 - RFPT A Trip 14.4.10.40 - Loss of Normal and Emergency FW 14.4.9Z4.80 - RPS Fails to SCRAM 14.4.9.3.3 - Uncoupled Rod 14.4.9,7.1 - Small Clad Faff 14.4.9.23.3 - DEH Press Reg. Output Failure High 14.4.9.24AOB - BP V-3 Failure 14.4.9.2.8 - FW Rupture ln Turbine Bldg 14.4.9.14.1 - SRM A Failure - I ow 14.4.9.9.4A - RCIC Turbfne Trip Due to RCIC-V-8 Closure 14.4.9.24.43 - Annunciator Failure 14.4.9.24.37A - HPCS-VA Fails to Open 14.4.9.23.3- DEH Press Reg. Output Failure High 3 of 4

Year 4

1. Normal Plant Evolutions 1 4.4.72.t - Startup from Hot Shutdown to Rated Pressure 14.4.7.2A - S/U, S/D, Power OPS with 1 Recfrc Pump 07.04.00,05.06- EDR, FDR, RRC, MS & RRC Valve Ops 07.04.01.03.01.01 - Scram Discharge Volume Vent & Drain Valves Operability 07.04.03.06.09 - SDV Bypass Rod Block 07.04.05.01.06- HPCS Valve Uneup 07.04.06.02.02.01 - RHR Valve Position Vetfffcatfon 07.04.08.01.01.02.01- Diesel Generator Ot - Operability Test 07.04.08.01.01.02.08- HPCS Diesel Generator - LOCA Test 07.04.08.01.01.02.12- HPCS Diesel Generator - Operability Test

2. Malfunction Tests 14.4.9.2.3 - Feed Line Break in DW 14.4.9.25.14- SRV's - Fail Closed 14.4.9.8.3- 4160 Vac Bus Sm-7 Overcurrent 14.4.9.8.5- 6900 Vac Bus SH-6 OLNND 14.4.924.18 - RPS B MC Set Trip 14.4.t0.6- Trip of all Reclrcuiatfon Pumps 14.4.9.25.15 - RCC-P-1 A - Trfp 14.4.9.24.73 - SW-V-2B waifs Closed 14.4.9.242- COND-P-2A Trfp 14.4.9.16.4 - HPCS Logic Failure 14.4.924.80A - RPS FaiLs to SCRAM (AUTO) 14.4.9.3.4- Single Rod SCRAM 14.4.9,7.2- Gross Clad Fafl 14.4.9.23.3A - DEH Press Reg. Output Fails Low 14.4.9Z1.4A - MS Rupture In DW 14.4.9.14.2 APRM Failure 14.04.09.24.67B - RPN-L1-606B - Fails Low 14.4.9.25.2- RHR-P-2B Shaft Shear 14.4.9,24.27- Main Steam Safety Relfef Valve Fails Open 4pf4

NAC FORM 474 U.S. NUCLEAR REGULATORY COMMISSION APPROVEO SV UMu: Nu. il~~I EXPIRES: 00002 I)4)0) 10 CF R 55.45(b),

55.4 end 555 ESTIMATED BURDEN PER RESPONSE TO COMP(.Y WITH THIS INFORMATION COLLECTION REGUEST( 120 NRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFOR.

SIMULATION FACILlTY CERTIFICATION M*TION ANO RECORDS MANAGEMENT BRANCH (MNSS 77)a),

Ug. NUCLEAR REGULATORY COMMISSION. WASHINGTON. OC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (3150 0)35), OFFICE OF MANAGEMENT AND SUDGET, WASHINGTON, DC 20503.

made after initial CTIONS, This form is to be filed for initial certification, recertification iifrequired), and for any change to a simulation facility performance testing plan sub <ttal of such a plan. Provide the following information, and check the appropriate box to indicate reason for subinittal, DOCKET NUMBER FACILITY.

Nuclear Plant No. 2 s0.397 LICENSEE DATE Hashington Public Power Supply System 6/24/92 This is to certify that:

1. The above named facility licensee is using a simulation facility consisting solely of a p)antccfcrcnccd simulator that meets the requirements of 10 CFR 55 45.

2. Documentation is available for NRC review in accordance whh 10 CF R 55.45ibj. See Section 6.-Compliance

3. This simulation facility meets the guidance contained in ANSI/ANS 35, 1985, as endorsed by NRC Regulatory Guide 1.149.

If there are any exceptions to the ccrtificationof this item, check here jx j and describe fully on additional pages as necessary Or f EXCepti OnS tO ANS 3. 5 NAME (or otheridenri%'carion J AND LOCATION OF SIMULATIONFACILITY Plant Support Facility MNP2 - Hanford Reservation Richland, HA. 99352 SIMULATIONFACILITYPE AFOAMANCETEST ABSTRACTS ATTACHED. (For performance tars conducted in the period ending wirh the dire of thk csnificirion/

D ESCA IPTION OF PERFORMANCE TESTING COMPLETED (A(lech addniona/page(s/ as rrccesseiy, indidsnrify the nem descriprion being continued/

See attached "Form 474 Supporting Documentation," 'Appendix D-Simulator Acceptance Tests and Appendix E-Additional Training Malfunction Tests Bi+i/LATIONFACILITYPE RFOA MANGE TESTING SCHEDULE ATTACHED. (For the conduct of ipproxinMtely 25% ofperformance tears pcr year for the four year pe M commencing wirh rhi dire of this certification./

IPTION OF PERFOAMANCE TESTING TO BE CONDUCTED. (Attach additions(Page(s J as necessary, andidcntlfy the ncm dcscriPt/on being cont/nucd J See attached "Form 474 Supporting Documentation" Section 5.3-quadrennial Test Schedule and Appendix F-guadrenniat Testing i

PERFORMANCE TESTING PLAN CHANGE. (For any modificsribn ro pinbnnsnce testing pfsn submirrad on a pnrribus car(if/caribn/

DESCAIPTION OF PERFORMANCE TESTING PLAN CHANGE fArrah addhionil page(sJ as necessary, ind identify the /rcm darer/pr/on being conrlnued/

Not Applicable RECERTI F ICATION (Describe correct(reactions tel(en, attach rcsu/rs of completed performance testing in accordance with 10 CF/f, 1'I 55 45(b/(5/(v/.

Arrach eddic(ons/ page(s/ as necessary, and /dent(fy the /rem descript/on being conrlnued J Not Applicable Any false statement or omhslon in this document, including attachments, may be subject to civil and criminal sanctions. I certify under penalty of perjury that the Information in his document cnd attachments h true and correct.

TURE AUTHOR) D REP NTATIVE TITLE DATE Deputy Managing Director 6/24/92 I accordance with 10 CFR jj 55/i, Commun)cat)ons, thh form shall be submitted to the NRC as follows:

BY MAILADDRESSED TOI D(rector, Office of Nuclear Reactor Regu)atbn BY DELIVERYIN PERSON One White F)int North UA. Nuclear Regu)story Commlsdon TO THE NRC OFFICE AT: 11556 Rockv94 Pike Waahksgton, DC 20666 Rockvil)e, MD NRC FORM 474 ((40)

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