ML20202J771

Simulator Certification Rept for Prairie Island Plant Simulation Facility,1998 Annual Rept

ML20202J771
Person / Time
Site:	Prairie Island
Issue date:	02/04/1999
From:	NORTHERN STATES POWER CO.
To:
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ML20202J762	List: ML20202J756 ML20202J771
References
NUDOCS 9902090239
Download: ML20202J771 (94)

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PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT

.1998 SIMULATOR CERTIFICATION REPORT FOR THE PRAIRIE ISLAND FLANT SIMULATION FACILITY l

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1998 ANNUAL REPORT  !

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Drafted By: . .d Date:

Certification Review Panel Review: .

I Reviewed By. m, Y1 Date: 2 f I Reviewed By: # Date: f/' 99 Reviewed B M ate: [r9 Approved By: I Date: '/ f 1

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l PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT  :-

1998  :

i l TABLE OF CONTENTS i Title Page  :

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i Simulator Certification Report Cover Page .............. . . . .. . .. ... . ........ .. . . ..... ...1 Table of Contents .......... ...... ........................................................................2 l

l List of Ap pe nd ices . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 l l

1. I NTR O D U CTl O N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . .. . .. . . . . . . . . . . . . . . . . . . . . 4 i j

A. Fa cility i nfo rmation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . 4 -

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l B. Control Room Information . . . .. . . . .. ... . .. . .. . . . . . . . .. ... .. ..... . . . ..... . . . . . . . . . . .. ... . . . . . . . 4 C . Instructor's Interface .. .. . .. . .. . . . .. . .. .. .. ... . . . . .. . .. . ..... ... .. . . . . . . . .. . . . . .. . . . . . 5 .

. D.- Operating Procedures for the Reference Plant .. .. .... ...... .. .......... .. .... . .. .. 6 i t

E. Changes Since Last Report ...... .. . ................ ....... .. .. .......... ... . . .. .. .......7 '

F. Cu rrent C hanges in Prog ress. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . .. . . . . . 7 i ll . SI M U LATOR DESIG N DATA ... .. ... .. . .. . . . . . . .. .. . . .. . . . . . .. . . . .. . . . . . . .. . . . . .. . ... . .. . . . . . . . 8 Ill . SIM U LATO R DOC U M E NTATIO N . . ........... .... ... ........ ......... ....... ..... . ....... .. . . ... 8  !

i IV. S I M U LATO R TE STI N G . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 1 1

t A. Simulator Performance Testing . . ...... ... ....... ...... . ..... ... . .... . . ............. .. 8 )i l

B. Simulator Operability Testing ................. ......... .. .......... .. ..... ...... .......... ... 9 l

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! C.- Testing Results Review .. .. . . . . .. .. . ... . .... .. . .. . .. .. . . . . ... .. .. . .. . . . ... ... . . . . .. ... . . . 10 i i 1 V. CONFIGURATION MANAGEMENT SYSTEM.... . .... ..... ..... ........... ............ 10 -

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PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT

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l LIST OF APPENDICES Appendix 1 Simulator Physical Fidelity Update FIGURE 1A Plant Control Room Layout FIGURE 1B Simulator Layout 1

l l Appendix 2 Instructors Interface Capabilities - Changes Table 2A Simulator Protected initial Conditions 1 Appendix 3 Certification Review Panel Members 1 l

Appendix 4 Four Year Testing Schedule Table 4A 1995 Testing Summary Table 4B 1996 Testing Summary  :

Table 4C 1997 Testing Summary 1 Table 4D 1998 Testing Summary  ;

l Appendix 5 AnnualTesting Abstracts Table SA Simulator Certification Testing Critical Parameter List Appendix 6 Malfunction Testing Abstracts l

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l , o l PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT l 1998

1. INTRODUCTION The purpose of the Prairie Island Simulator Certification Annual Report is to document the l performance of the Prairie Island simulator in accordance with the requirements provided in 10CFR55.45, Regulatory Guide 1.149 and ANS/ ANSI 3.5-1985. This report is divided l into several different sections including information describing the facility, hardware,  !

procedures used, performance testing completed arid the configuration management program for the simulation facility certified 'or the Prairie Island Plant Units 1 and 2. This :

repM;s issued annually - the initial report was issued in January 1991 and this is the l eighth annual update. This annual update is the final update for the second four year l cycle following initial certification. Therefore, this report will describe all changes and I testing completed since the 1994 certification report.

A. Facility Information Facility Name Docket / License Type Rating 1 Prairie Island Unit 1 Docket Number 50-282 Westinghouse PWR 560 MWE License Number DPR-42 I

Prairie Island Unit 2 Docket Number 50-306 Westinghouse PWR 560 MWE I License Number DPR-60 I icensee: Northern States Power Company I Simulation Facility:

Owner / Operator Northern States Power Company Manufacturer Singe.-Link (presently part of GSE inc.)

Hardware and Software Upgrades General Physics (1995)

CAE Electronics Ltd. (1996)

Date Available for Training February 6,1984 Type of Report Periodic Update Initial Certification Date February 7,1991 B. Control Room Information i Figure 1 A (Appendix 1) is a layout of the plant Control Room and Figure 1B is a layout of l the simulator area. As can be seen from these figures, the two units have a common Control Room with a Shift Supervisor's office in the center. The controls for each unit are Page 4 of 11 l

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PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1998 1

separate except for some shared syste'ns on Panel A. The simulator duplicates the Control Room for Unit 1 plus the necessary portions of the shared systems on Panel A as l well as certain Unit 2 systems with crosstie capability with Unit 1. An update on the simulator physical fidelity, including all changes in the differences between the simulator and the plant control room physical arrangement, communications systems, audible environment, lighting, control panels and systems, is presented in Appendix 1.

l C. Instructor's Interface i The Instructor's Station provides the interface necessary to control and monitor a training session. The major components consist of a CRT with a keyboard and a control panel. A remote device is also provided which allows the instructor to perform selected functions while not at the Instructor's Station.

The control panel and remote device functions are as follows:

Control Panel Remote Device

1. Emergency Power 1. Freeze

2. Recorder Power Off 2. Reset

3. Computer Fault / Alarm Silence 3. Switch Check Override

4. Step Counter Override 4. Snapshot

5. Freeze 5. Backtrack

6. Reset / Ready 6. Forward

7. Switch Check Override 7. Reverse

8. Snapshot 8. Replay i

9. Fast Time 9. Annunciator Sound Silence

10. Slow Time 10. Ten Malfunction / Remote Function

11. Record Selection Keys

12. Replay

13. Backtrack

14. Forward

15. Reverse

16. Annunciator Sound Silence

17. Annunciator Lamp Acknowledge

18. Annunciator Reset

19. ERCS Fault / Override

20. Plant Page Hand Set ,

21. Simulator Operating Limit Override i

The functions available on the keybosrd were listed in the Initial Certification Report and an updated list is included in Appendix 2. All malfunction, system override and variable Page 5 of 11 l

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PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1998 setpoint tests are included in Appendix 6," Malfunction Testing Abstracts" The changes to the available malfunctions, variable setpoints, system overrides and remote functions have been compared against the requirements in ANS/ ANSI 3.5-1985 to verify that these requirements are still met.

l D. Operating Procedures for the Reference Plant Controlled copies of the Prairie Island Nuclear Generating Plant (PINGP) Operating j Procedures for Unit 1, including Integrated Operations Procedures, System Operations Procedures, Surveillance Procedures, Plant Figures and Curves, System Checklists, j l Startup Checklists, Abnormal Operating Procedures and Emergency Operations '

Procedures are used on the Prairie Island simulator. Occasionally, draft revisions to selected procedures have been used on the simulator to " prove" the procedure revisions prior to use in the plant or to provide the operations personnel training on significant ,

Control Room or procedure modifications prior to installation in the plant. The period of use of draft procedures on the simulator is limited to the minimum necessary to provide the training desired by the plant operations personnel in order to maintain control of the simulator configuration.

Unit 2 operating procedures are maintained nearly identical to the Unit 1 procedures, with the major difference being the individual component identification numbers. Efforts are made to maintain the procedures identical during all revisions with the only exception behg the unique component identification and/or modifications made to one unit and not the other.

Most operating procedures are located on the same shelves in the simulator as they are in the plant Control Room. The exceptions to this are the procedures which are kept in the Shift Supervisor's office in the plant. These procedures (eg. Startup Checklists, System Descriptions and Special Operating Procedures) are kept in locations on the simulator convenient to the operators. The appearance of the procedures is duplicated by using the same binders as those used in the plant Control Room.

Administrative procedures and references provided in the Unit 1 Control Room are also available in the simulator area.

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', o PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1998 E. Changes Since Last Report

1. Malfunctions, Remote Functions, Variable Setpoints and System Overrides Many changes have been made, including addition of malfunctions and remote functions, renaming of malfunctions and remote functions (eg. DG system), and deletion of malfunctions and remote functions. Appendix 2 contains a list of the current Instructor's Station capabilities.

2. Annual and Operability Testing Appendix 5 includes the Annual Test Abstracts, and Appendix 6 includes the Malfunction Test Abstracts.

3. Physical Fidelity Appendix 1 contains an updated evaluation of the physical fidelity differences between the simulator and the plant Control Room.

4. Simulator Software The Core and Primary System models were replaced during 1994-1995 to provide more extensive training capabilities. The model installation was i completed with little impact on training's use of the simulator, and testing l was completed to verify that the simulator modeling functioned correctly

following the change. A selected set of certification test procedures was  ;

used to benchmark simulator performance before the change and to verify correct performance following the change.  !

l 5. 1/0 System Component Replacements l

l The Master Conkoller, Subcontrollers, and Analog Chassis were replaced in D98. i F. Current Changes in Progress l

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1. Currently in the Acceptance Test Procedure phase of the project to upgrade the Simulator Operating Platform to OpenSim NT. This will allow use of standard industry software products and off-the-shelf PC-based computer hardware.

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PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1998

2. Currently in the Acceptance Test Procedure phase of the project to upgrade instructor's Station to OpenSim IS. This will provide the instructors with a graphical interface and will expand the capabilities of the Instructor's Station.

II. SIMULATOR DESIGN DATA The simulator design database is composed of two parts:

1. The initial database consists of the documents and data sent to Singer-Link which were used to design, construct and test the simulator. This consisted of required plant drawings, technical manuals and collected plant data (control board pictures, plant process computer printouts, startup test results, etc.). This data was archived l following receipt of the simulator and completion of the final acceptance testing. Lists I of these documents are available at the Prairie Island Training Center on microfilm.

Following delivery of the simulator, a review was performed to determine which plant modifications had been included in the design data base.

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2. Current plant documents including drawings, technical manuals, plant process computer data, startup and operations reports, etc. are used to maintain and update the simulator. The accumulation of the original design data and these records comprise the current simulator design database.

Ill. SIMULATOR DOCUMENTATION Simulator specific documentation is maintained in order to effectively manage the simulator configuration. This documentation includes the simulation diagrams (which provide documentation of the scope of simulation), the Final Design Specification (which includes the math model descriptions, design assumptions and simplifications, and the source code documentation), completed testing results (including procedure used and results), and the simulation hardware drawings and wire lists.

IV. SIMULATOR TESTING A. Simulator Performance Testing The simulator core and primary system models were replaced during 1994-l 1995, with the objective of improving and expanding modeling performance.

! Release to training occurred in 1996. Performance test sections affected by the model changes were conducted and verified against actual and empirical data.

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o PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1998 B. Simulator Operability Testing The simulator operability testing consists of two basic parts: the Sim'.iator Annual Test and the malfunction testing.

1. Simulator Annual Test An outline of the annual simulator testing is included in Appendix 4, and abstracts of the 1998 annual test procedures are included as Appendix 5. The annual real-time test will be deferred to the 1999 test timeframe as part of the Acceptance Test Plan for the new simulator operating platform. This group of tests include all testing required for simulator certification except for the required malfunction testing.

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2. Simulator Malfunction Testing a) Malfunction testing includes testing of all available malfunctions (with two exceptions which have been determined to be inappropriate for training use) over a four year period. Appendix 4 contains the schedule of testing for the current four year cycle. Note that this schedule may change slightly due to additions or deletions of malfunctions.

, Tables 4A -D list all malfunctions which were tested during 1995-1998, respectively.

b) Appendix 6 contains abstracts of all the malfunction tests along with the date of the initial test approval, the date of the first four year cycle retest approval and the date of the most recent retest approval. Due to the testing of malfunctions affected by simulator modifications, some malfunctions may be retested more than one time during the four year cycle. These retests will be included in the tables following Appendix 4.

c) 43 of a planned 78 malfunctions scheduled for testing in 1998 to complete this four-year cycle have been delayed due to installation of l

the new simulator operating platform. Implementation delays have impacted our ability to complete the testing of these malfunctions in l accordance with the original schedule. We have determined that the i

most prudent course of action is to test these malfunctions on the new platform following the Acceptance Plan Testing. Therefore, the 1999 testing will include these 43 tests plus the malfunctions included in the normal rotation for compliance with ANS 3.5-1985.

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l PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1998 l

C. Testing Results Review Results from all testing completed for simulator certification were reviewed by a panel of experts for agreement with the expected results contained in the procedure and that those results are correct for the test performed. A list of the experts included in this panel and their qualifications is included as Appendix 3.

V. CONFIGURATION MANAGEMENT SYSTEM The Configuration Management system used to maintain the simulator configuration is tracked on a Microsoft Access database. The major elements of this process for tracking, resolution and testing of identified changes to the simulator include:

1. Simulator discrepancies are tracked, resolved and tested following the l process spelled out in the simulator procedures. The tracking is performed using a database based on Microsoft Access. Resolution and testing of j these discrepancies is tracked on this database. Documentation of the

! resolution and testing is included in the simulator change package which becomes part of the simulator documentation.

l 2. Evaluation of proposed simulator design enhancements is performed by j the Simulator Design Review Committee (SDRC), which is composed of l representatives from Plant Operations, Operations Training, and the Simulator Group. Tracking anc. testing is the same as used for l

discrepancies. The SDRC meets at least once a year.

3. Plant modifications are tracked using the plant modification databases.

All changes and additions are identified and tracking forms initiated. In this way, progress on plant modifications and alterations can be tracked and j current status can be easily determined. Once the plant modification is completed on Unit 1 (identified by a closeout date), the SDRC reviews this modification to determine if it requires changes to the simulator. If simulator I changes are required, a simulator change is initiated and tracked the same as all other simulator changes.

Changes due to plant operating experience or plant procedure changes are identified by the Request for Training Material Review process. These changes are further reviewed by the SDRC, and if simulator changes are required, they are initiated and tracked the same as all other simulator changes.

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l 4. Verification that the current simulator configuration matches the plant 1 l Control Room configuration is accomplished by testing of each simulator change prior to use for training, verification of each discrepancy report  ;

against plant documents prior to making simulator changes, and testing as  !

required for simulator certification. j included in the testing for certification are comparisons against the plant i physical configuration (using photographs of the plant controls) periodically  !

during the four year cycle. These photographs were compared with the i plant control board during 1998. All differences identified have been corrected or are being tracked for correction at a future time.

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PJ.AIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1998 APPENDIX 1 Simulator Physical Fidelity Summary: The Prairie Island simulator is used for training the operators for both Prairie Island Unit 1 and Unit 2.' Due to the similarities in plant construction, nearly identical operating procedures, identical Technical Specifications and single operator's license for both units, the Prairie Island simulator is considered a plant specific simulator for both Prairie Island units. Simulator physical design and modeling is referenced to Prairie Island Unit 1.

The differences between the simulator and each unit were identified and justification was presented for all differences which do not adversely affect training in the Initial Certification Report. This update includes only changes to the initial report. Differences 3

which are identified and whic, will be corrected are listed with the Simulator Change Request number for tracking purposes.

A. Control Room Environment

1. Physical Arrangement l I

As shown in Figures 1 A and 1B, the physical arrangement of the simulator closely duplicates the Prairie Island Unit 1 Control Room.

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2. Audible Environment i

The simulator duplicates the plant Control Room audible environment as far as noise levels, control rod step counter noise, flow integrator noises, and annunciator horns. All exceptions have been identified in previous reports.

3. Lighting

] a. Comparison of light level measurements between the plant Control Room and the simulator show that the light levels are generally higher in the Simulator than in the Control Room. These differences were reviewed by

' the Certification Review Panel and judged to not impact training.

The requirements of ANSI /ANS 3.5-1985 Section 3.2.3 are satisfied.

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PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1998 APPENDIX 1 B. Control Panels

-The Prairie Island simulator contains sufficient operational panels to provide the controls,

~ instrumentation, alarms and other man-machine interfaces to perform the normal plant evolutions specified in ANSI /ANS 3.5-1985 Section 3.1.1 and to respond to the malfunctions specified in Section 3.1.2 for both Prairie Island Unit 1 and Unit 2. The control panels and consoles are designed to duplicate the size, shape, color and

. configuration of the simulated plant hardware.' Modification of the simulator control board to reflect a new turbine are in progress and expected be completed in early 1999.

C. Systems Simulated and Degree Of Completion All systems which are controlled from the Control Room are simulated. The completeness of the modeling is sufficient to perform the normal reference plant evolutions and to respond to the reference plant malfunctions listed in ANSI /ANS 3.5-1985 Sections 3.1.1 and 3.1.2. This includes system interactions and provides an integrated system response.

The systems which are operated from outside the Control Room are simulated to the

' degree necessary to perfcean the reference plant normal evolutions and malfunctions listed in ANSI /ANS 3.5-1985 Sections 3.1.1 and 3.1.2. The trainee is able to interface ,

with the remote activities in a manner similar to the reference plant. l The requirements of ANSI /ANS 3.5-1985 Section 3.2.1 are satisfed. l D. Significant Modifications Installation of replacement models for the RCS, Steam Generators, and portions of the j Main Steam system thermohydraulics, and for the Core neutronics and therrnohydraulics .

has been recently completed. These new models provide the capability to train and test l further into the EOP's including shutdown conditions with the RCS partially drained. l Additionally, these new models provide the capability to more frequently update the core  !

model whenever the plant reload response significantly deviates from the simulator l l . response. These systems have been extensively tested prior to their use for training.  !

All plant modifications are reviewed periodically and necessary simulator changes are identified within one year of completion. These simulator changes are then incorporated '

into the simulator within one year.

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O Prairie Island Simulator Certification Report 2/96 Appendix I Figure IA Plant Control Room Layout

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I PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1998 APPENDIX 2 Instructor's Interface Capabilities Following is a list instructor's interface capabilities. Many changes have been completed in this area of the simulator. In general these have included addition of new malfunctions, remote functions and addition of new capabilities. These changes have been reviewed to verify that the requirments in ANSI /ANS 3.5-1985 are still met.

1 Simulation Options Backtrack Fast Time Slow Time Instrument Noise Trainer Hardware Test (DORT)

Switch Check Misalignments Display Initial Conditions Selection Snapshot Selection Backtrack Time Selection Replay Rate Selection Malfunction Control I/O Override Control Plant Process Computer Input Override I System Override / Remote Activation Control Simulator Operating Limits Display Meteorological Data Control i Annunciator System AN01 NSSS ANNUNCIATOR SYSTEM FAILURE AN02 BOP ANNUNCIATOR SYSTEM FAILURE ANO3 BOP DISTRIBUTED ANNUNCIATOR PCB OUTPUT CHIP FAILURE AN100 UNIT 2 ANNUNCIATOR AUTO ACKNOWLEDGE  !

Component Cooling System CC01 COMP COOLING WTR PUMP TRIP CC02 COMPONENT COOLING PUMP FAILS TO START AUTOMATICALLY CC03 11 RCP RETURN LINE CC PIPE RUPTURE l CC04 COMPONENT COOLING WATER SUPPLY VALVE TO RCP FAILS CLOSED l CC05 COMPONENT COOLING WATER SYSTEM PIPING RUPTURE CC06 CCW VALVE FAILURE TO AUTO OPEN TO RilR liEAT EXCil ANGER ON PUMP START

!~ CC08 COMPONENT COOLING SURGE TANK AUTO MAKEUP FAILURE l Page 1 l 1

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PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT I 1998

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l APPENDIX 2- 1 CC09 SEAL WATER HuAT EXCHANGER LEAK CC100 RCP CCW SUPPLY ISOL A I

. CC101 - RCP CCW SUPPLY ISOL B CC102 UNIT 1 - UNIT 1 uCW X CONNECT CC104 11 RCP COMP CLNTINLT/OUTL BKR CC105 12 RCP COMP CLNTINLT/OUTL BKR CC106 11 RCP BRG CLG WTR RETURN CC107 12 RCP BRG CLG WTR RETURN CC108 SURGE TANK XTIE ISOL VLV CC109 Il CC 11X OUTL TEMP CNTLR TC 26331 SP CCI10 12 CC llX OUTL TEMP CNTLR TC 26332 SP CClli 11 CC liX OUTL TCV CV-31381 TRVL STOP

. CCll2 12 CC liX OUTL TCV CV-31411 TRVL STOP CCll3 11 CC llX OUTL TCV CV-313813-WAY VLV CCll4 12 CC HX OUTL TCV CV-314113-WAY VLV CCI15 11 CC PMP SUCT MV-32200 BREAKER (lKi-B4)

CC116 ' 12 CC PMP SUCT MV-32201 BREAKER (lKA2-E2)

CCI17 21 CC PMP SUCT MV-32211 BREAKER (2Kl-B4)

CCI18 22 CC PMP SUCT MV-32212 BREAKER (2KA2-A2)

Containment / HVAC System

. CH01 CONTAINMENT PRESSURE TRANSMITTER FAILURE CH100 POST LOCA H2 CONTROL VENT .

l- Cil101 Ul CATI ANNUNCIATORS CH102 U2 CATI ANNUNCIATORS

, CH103 121 CNTMT PURGE SUPPLY FAN CH104 - ~ CONT PURGE CONTROL

, Cll105 121 CONT PURGE EXHAUST FAN CH106 CNTMT HI PRESS B/S PC-945A CH107 CNTMT Hi PRESS B/S PC-949A Cil108 CNTMT HI PRESS B/S PC-947A ,

CH109 .. CNTMT 111-111 PRESS B/S PC-946A Clfl10 - CNTMT lil-HI PRESS B/S PC 948A CliliI CNTMT 111-HI PRESS B/S PC-950A Cill12 CNTMT III-HI PRESS B/S PC-945B CH113 CNTMT HI-HI PRESS B/S PC-946B CH114 CNTMT lli-HI PRESS B/S PC-947B

Clll15 CNTMT HI-ill PRESS B/S PC-948B CHI 16 CNTMT lil-HI PRESS B/S PC-949B CHI 17 CNTMT HI-lil PRESS B/S PC-950B CHil8 121 LAUNDRY / LOCKER / FILTER ROOM EXHAUST FANS CHil9 CNMT CHILL WATER SYSTEM CH121 FIRE DETECTION ALARMS CH122 flRE DETECTION ALARMS CH123 FIRE DETECTION ALARMS CH124 Fir E DETECTION ALARMS l CH125 FIRE DETECTION ALARMS Clll26 121/122 CR CHILLER XOVER VLVS

{ CH127. RAD WASTE BLDG VENT Page 2 l .- - .- - - - .. .

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PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1998 APPENDIX 2 Cill28 11/12 CRDM COLL SUPPLY / RETURN VLVS CH129 Ul CONTAINMENT ENTRY i Clll30 UI CONTAINMENT EXIT Cill31 11-14 CNTMT FCU COND Colt TK DRN C11132 11 FCU DISCH TO CNTMT GAP / DOME DAMPERS CH133 12 FCU DISCH TO CNTMT GAP / DOME DAMPERS Clil34' 13 FCU DISCH TO CNTMT GAP / DOME DAMPERS Clll35 14 FCU DISCH TO CNTMT GAP / DOME DAMPERS Cill36 11 FCU DISCli TO CNTMT GAP / DOME DAMPERS l CH137 12 FCU DISCH TO CNTMT GAP / DOME DAMPERS CH138 13 FCU DISCH TO CNTMT GAP / DOME DAMPERS CH139 14 FCU DISCH TO CNTMT GAP / DOME DAMPERS Cll300 Clll CNMT 111 PRESS PC-945A Cll30) CH2 CNMT HI PRESS PC-949A CH302 CH4 CNMT 111 PRESS PC-947A I CH303 Cil2 CNMT IIIH1 PRESS PC-946A CH304 CH3 CNMT Hi PRESS PC-948A Cil305 CH4 CNMT HIH1 PRESS PC-950A Cll306 CIll CNMT111111 PRESS PC-945B CH307 Cil4 CNMT Hilli PRESS PC-947B CH308 Cll2 CNMT HlHI PRESS PC-949B CH309 CH2 CNMT HlHI PRESS PC-946B CH310 Cll3 CNMT HIHI PRESS PC-948B Cll311 CH4 CNMT HIH1 PRESS PC-950B Cooling Water System l CL01 COOLING WATER PUMP TRIP CLO2 DIESEL COOLING WATER PUMP FAILS TO START AUTOMATICALLY l CLO3 121 COOLING WATER PUMP FAILS TO START AUTOMATICALLY CLO4 DIESEL COOLING WATER PUMP 1 RIP CLO6 SAFEGUARDS COOLING WATER SUPPLY PlPING RUPTURE CLO7 COOLING WATER SYSTEM TURBINE BUILDING PIPE RUPTURE CLOS COOLING WATER LEAK INSIDE CONTAINMENT CL100 TURB OIL COOLER OUTL TEMP CONTROL SETPOINT CL101 CL-36-1 TRN A SFGRDS CL WATER MANUAL VLV CL102 2CL-36-1 TRN B SFGRDS CL WATER MANUAL VLV CL103 11/13 FCU CLG WTR RTN ORIFICE BP VLV LOCAL CS CL104 11/13 FCU CLG WTR RTN ORIFICE BP VLV LOCAL CS CL105 12/14 FCU CLG WTR RIN ORIFICE BP VLV LOCAL CS CL106 12/14 FCU CLG WTR RTN ORIFICE BP VLV LOCAL CS CL107 12 DSL CLG WTR PUMP LOCAL STOP CL108 22 DSL CLG Wl'R PUMP LOCAL STOP I CL109 121 COOLING WATER PUMP SOURCE ALIGNMENT CLi10 121 COOLING WATER PUMP BKR 25-01 CL111 121 COOLING WATER PUMP BKR 26-17 CLI12 TURB BLDG COOLING WATER HEADER CROSSTIE VLV  ;

CLI13 TURB BLDG COOLING WATER HEADER CROSSTIE VLV l CLI14 121 COOLING WATER PUMP DISCilARGE VALVE CL-39-3 CL115 11 FCU CLG WTR RETURN LINE, CL-22-1 Page 3 l 1

', o PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1998 APPENDIX 2 CL116 12 FCU CLG '.VTR RETURN LINE, CL-22-2 CLI17 13 FCU CLG WFR PITURN LINE, CL-22-3 I CLI18 14 FCU CLG WTR RETURN LINE, CL-22-4 l CL119 11 AUX BLDG CL RTRN llDR MV-32332 BKR (1K1-F3) j CL120 11 AUX BLDG CL RTRN HDR MV-32334 BKR (2K2-B3 j Reactor Core System l

CR01 FUEL CLADDING FAILURE CR03 CR04 REACTOR COOLANT SYSTEM CRUD BURST l FUEL CLADDING FAILURE  !

Containment Spray System  ;

CS01 CONTAINMENT SPRAY PUMP TRIP I CS02 CAUSTIC ADDITION VALVE FAILURE TO OPEN IN AUTOMATIC l CS03 CONTAINMENT SPRAY PUMP FAILS TO START AUTOMATICALLY CS100 11 CS SUCTION FROM Rilk BKR CS101 12 CS SUCTION FROM RilR BKR  !

CS102 CAUSTIC ADD TO 11 CS PUMP ISOL l CS103 CAUSTIC ADD TO 12 CS PUMP ISOL CS104 RWST TO 11 CS PUMP SUCTION MV 32098 BKR (1K1-F2) I CS105 RWST TO 12 CS PUMP SUCTION MV 32099 BKR (1KA2-C4) i Circulating Water System j CWO2 CIRCULATING WATTER PUMP TRIP CWO3 CIRCULATING WATER PUMP BEARING FAILURE CWO4 CO'NDENSER TUBES PLUGGED CWOS CONDENSER TUBE RUPTURE CWO6 TRAVELING SCREEN BLOCKAGE ON APPROACH CANAL CWO7 CONDENSER PIT FLOOD CW100 RIVER WATER TEMPERATURE CW102 INTAKE SCREENHOUSE BYPASS GATES MANUAL CONTROL CW103 CT PUMP / CW PUMP INTERLOCK BYPASS CW104 121 COOLING TOWER PUMP CW105 122 COOLING TOWER PUMP CW106 123 COOLING TOWER PUMP CW107 124 COOLING TOWER PUMP CW108 121 SLUICE GATE POSITION -5' CW109 122 SLUlCE GATE POSITION -6' CW110 123 SLUICE GATE POSITION -7' CW1Ii 124 SLUICE G ATE POSITION -5' CW112 121 RECYCLE CANAL GATE POSITION CW113 122 RECYCLE CANAL GATE POSITION CW114 123 RECYCLE CANAL GATE POSITION CWI15 124 RECYCLE CANAL GATE POSITION CW116 121 COOLING TOWER FAN CW117 122 COOLING TOWER FAN CW118 123 COOLING TOWER FAN CWil9 124 COOLING TOWER FAN CW120 121 COOLING TOWER FAN DIRECTION CW121 122 COOLING TOWER FAN DIRECTION Page 4 l

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• PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT l 1998 ,

i l APPENDIX 2  !

L  ;

j CW122 123 COOLING TOWER FAN DIRECTION l CW123 124 COOLING TOWER FAN DIRECTION  !

CW124 121 COOLING TOWER BYPASS GATE !OSITION l- ' CW125 122 COOLING TOWER BYPASS GATE POSITION CW126 123 COOLING TOWER BYPASS GATE POSITION CW127 124 COOLING TOWER BYPASS GATE POSITION l Emergency Diesel Generator  :

l DG01 LOSS OF EMERGENCY DIESEL GENERATOR DG02 EMERGENCY DIESEL GENERATOR FAILS TO START  ;

DG03 EMERGENCY DIESEL GENERATOR LOAD LIMIT FAILURE  :

DG04 EMERGENCY DIESEL GENERATOR OUTPUT BREAKER FAILS OPEN l DG05 ELECTRONIC GOVERNOR FAILURE DG06 24VDC SPLY FOR ELECTRONIC GOVERNOR FAILS DG07 DIESEL GENERATOR EMERGENCY START FAILURE i DG100 Di LOCAL SHUTDOWN RELAY RESET PB DG101 DI LOCAL 86 LO RELAY RESET DG102 DI LOCAL ANNUNCIATOR SILENCE PB DG103 DI MECilANICAL LINKAGE TO FUEL RACKS RESET l DG104 D1 LOCAL PANEL STOP CS DG105 D2 LOCAL SHUTDOWN RELAY RESET PB DG106 D2 LOCAL 86 LO RELAY RESET DG107 D2 LOCAL ANNUNCIATOR SILENCE PB

- DG108 D2 MECHANICAL LINKAGE TO FUEL RACKS RESET DG109 D2 LOCAL PANEL STOP CS DG110 DS LOCAL 86 LO RELAY RESET DGl13 - D5 LOCAL PANEL STOP CS .

DGI14 - DS LOCAL GOVERNOR CONTROL DGI15 D6 LOCAL 86 LO RELAY RESET DGl18 D6 LOC / ', PANEL STOP PB DG119 D6 LOCH GOVERNOR CONTROL DG120 D5 LOCAL FAIL TO START RELAY RESET DG121 D6 LOCAL FAIL TO START RELAY RESET DG122 D1 VOLTAGE RESET LOCAL PB DG123 D1 EXCITER SHUTDOWN LOCAL PB DG124 D2 VOLTAGE RESET LOCAL PB DG125 D2 EXCITEtt RESET LOCAL PB Electrical Distribution System  !

t ED01 LOSS OF OFFSITE POWER TO 161 KV BUS

[ ED02 4.16 KV 1R TRANSFORMER BKR FAILS TO AUTO CLOSE FOLLOWING GEN LO ED03 LOSS OF POWER TO CT TRANSFORMERS

, . ED04 FAULT IN UNIT 1 M TRANSFORMER - AUTO TRANSFER ED05 FAULT IN UNIT 1 M TRANSFORMER - DELAYED AUTO TRANSFER ED06 FAULT IN UNIT SUBSTATION TRANSFORMER ED07 LOSS OF 125 VDC BUS j ED08 LOSS OF 120 VAC INSTRUMENT BUS

l. ED09 LOSS OF 4160V BUS ED10 LOSS OF 480 VAC BUS

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V y, .. l PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1998 APPENDIX 2

~ . EDI1, FAILURE OF BATTERY' CHARGER ED12 LOAD SEQUENCER REJECTION FAILURE l EDl3 LOAD SEQUENCER RESTORATION FAILURE

! ED14 LOSS OF ALL OFFSITE AC POWER EDl5 DEGRADED GRID VOLTAGE ED16 DEGRADED GRID FREQUENCY EDl'I FAILURE OF $2Z LOAD SEQUENCER RELAY ED18 FAULTIN 1R TRANSFORMER l EDl9 FAULTIN CTI1 TRANSFORMER

~ ED20 FAULTIN CT12 TRANSFORMER

' ED100 ' STA AUX MAIN TRANSFORMER 20KV DISCONNECTS

, ED101 - 10 BANK TO BUS CT12 l ED102 ICT TO BUS CTil ED103 161 KV BUS 1TO 10 BANK i ED104 SPRING CREEK 161 KV TO 161 KV BUS 1 l

ED105 RED ROCK 2 345 KV LINE TO 345 KV BUS 1 j ED106 RED ROCK 2 / BYRON 345 KV LINE

ED107 BYRON 345 KV LINE TO 345 KV BUS 2 l ED108 UNIT 2 345 KV TO 345 KV BUS I ED109 UNIT 2 / BLUE LAKE 345 KV LINE EDI10 BLUE LAKE 345 KV LINE TO 345 KV BUS 2 EDI11 RED ROCK 345 KV LINE 1 TO 345 KV BUS 2 l EDil2 BUS 1345 KV TO 2RS TRANSFORMER MOD EDI13 BUS 2 345 KV TO 10 BANK TRANSFORMER MOD EDil4 2RS TRANSFORMER TO 2RY TRANSFORMER EDI15 2RS TRANSFORMER TO 2RX TRANSFORMER EDil6 SUBSTATION ALARM ANNUNCIATOR RESET l EDI17 1R-Y AUX TRANSFORMER BUSTIE BKR 1RYBT l ED!!8 2R-Y AUX TRANSFORMER BUS TIE BKR 2RYBT l ED119 - IR-Y/2R-Y BUS TIE BKR 12RYBT l ED120 1R-X/2R-X BUS TIE BKR 12RXBT l ED121 1R-X BUS DISCONNECT ED122 1R-Y BUS DISCONNECT ,

ED123 2R X BUS DISCONNECT l ED124 2R-Y BUS DISCONNECT l l

ED125 480V BUS 130/140 BUS TIE BKR 134BT ED126 480V BUS 150/160 BUS TIE BKR 156BT ED127 - 480V BUS 190/290 BUS TIE BKR 1929BT

!- ED128 4.16KV BUS SUPPLY BKR CTil-1

( ED129 4.16KV BUS SUPPLY BKR CT12-7 l

. ED130 4.16KV CLNG TWR BUS TIE BKR CT-BTil2 ED131 4.16KV BUS 11 IM XFMR BKR 11-4 ED132 4.16KV BUS 121M XFMR BKR 12-4 ED133 4.16KV BUS 13 IM XFMR BKR 13-9 -l ED134 4.16KV BUS 14 IM XFMR BKR 14-9 i o ED135 4.16KV BUS 13 PUMP OVERLOAD RELAYS RESET )

, ED136 4.16KV BUS 14 PUMP OVERLOAD RELAYS RESET 1 i EDl37 480V BUS 111 SUPPLY BKR 111M 4  :

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• s PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1998 APPENDIX 2 i

ED138 480V BUS 112 SUPPLY BKR ll2M ED139 480V BUS 121 SUPPLY BKR 121M i

EDl40 480V BUS 122 SUPPLY BKR 122M ED141 4.16KV BUS 25 SOURCE TO BUS 111/112 BKR 25-15 l ED142 4.16KV BUS 26 SOURCE TO BUS 121/122 BKR 26-03 480V BUS 111 SUPPLY BKR 111 A ED143 ED144 . 480V BUS 112 SUPPLY BKR ll2A ED145 480V BUS 121 SUPPLY BKR 121 A EDl46 480V BUS 122 SUPPLY BKR 122A-ED147 480V BUS 130 SUPPLY BKR 13M ED148. 480V BUS 140 SUPPLY BKR 14M ED149 480V BUS 150 SUPPLY BKR95M ED150 480V BUS 160 SUPPLY BKR 16M l ED151 480V BUS 190 SUPPLY BKR 19M -  !

ED152 480V MCC 1 ABI SUPPLY TRANSFER SWITCll ED153 480V MCC 1 AB2 SUPPLY TRANSFER SWITCli ED154 480V MCC ITI SUPPLY TRANSFER SWITCH ED155 480V MCC IT2 SUPPLY TRANSFER SWITCil ED156 4.16KV CLNG TWR BT CT-BTil2 AUTO. MAN SWITCil ED157 1R TRANSFORMER 86 LOCKOUT RELAY RESET ED158 1R - 161KV DISCONNECT

ED159 480V MCC 1 mal SUPPLY TRANSFER SWITCll j ED160 480V MCC 1MA2 SUPPLY TRANSFER SWITC11 l Electrical Generation System EG01 GENERATOR OUTPUT BREAKER FAILS TO OPEN FOLLOWING TURBINE TR]P EG02 LOSS OF GENERATOR llYDROGEN COOLING t

EG03 GENERATOR OUTPUT BREAKERS FAIL OPEN i

! EG04 GENERATOR VOLTAGE REGULATOR ADJ FAILURE l EG05 GENERATOR VOLTAGE REGULATOR FAILURE  !

l EG06 GENERATOR FAULT l EG07 GENERATOR LOSS OF EXCITATION l EG08 LOSS OF GENERATOR BUS DUCT COOLER BLOWER

, EG100 GENERATOR 112 SUPPLY l EG101 GENERATOR CO2 SUPPLY EG102 GENERATOR GAS VENT EG103 liYDROGEN SIDE SEAL OIL PUMP EG104 AIR SIDE SEAL OIL PUMP l EG105 GEN XFMR 345 KV DISCONNECTS EG106 MAIN GENERATOR OUTPUT DISCONNECT LINKS

! EG107 AIR SIDE SEAL OIL BACKUP PUMP STOP EG108 AIR SIDE SEAL OIL BACKUP PUMP START EG109 86-1G/86-lGT RESET EGI10 ' PREFERRED GEN BUS DUCT COOLER BLOWER (5983004)

EG200 EG TEMP TRANSMITTER Condensate and Feedwater System l FWOI CONDENSATE PUMP TRIP FWO2 13 CONDENSATE PUMP FAILS TO START AUTOMATICALLY j Page 7 3

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l PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1998 '

APPENDIX 2 l FWO3 LOSS OF CONDENSER VACUUM FWO5 CONDENSATE PUMP RECIRC VALVE FAILS OPEN FWO6 CONDENSATE PUMP RECIRC VALVE FAILS CLOSED FWO7 CONDENSATE HOTWELL MAKEUP VALVE FAILS OPEN FWO8 CONDENSER HOTWELL MAKEUP VALVE FAILS CLOSED FWO9 LP FEEDWATER HEATER BYPASS VALVE FAILS OPEN FW10 11 TD AFW PUMP LOW PRESSURE TRIP FW11 12 MD AFW PUMP LOW PRESSURE TRIP FW13 MAIN FEEDWATER PUMP TRIP i FWl7 FEEDWATER llP HEATER LEAK I FW18 FEEDWATER LP llEATER LEAK FW19 FEEDWATER SYSTEM RUPTURE INSIDE CONTAINMENT I FW20 FEEDWATER SYSTEM LEAKAGE INSIDE CONTAINMENT FW21 FEEDWATER SYSTEM RUPTURE INSIDE CONTAINMENT UPSTREAM OF CHECK VALVE  ;

FW22 FEEDWATER SYSTEM RUPTURE OUTSIDE CONTAINMENT  !

FW23 FEEDWATER SYSTEM LEAKAGE OUTSIDE CONTAINMENT l FW24 FEEDWATER PUMP COMMON DISCHARGE IIEADER RUPTURE l FW25 FEEDWATER FLOW CONTROL VALVE FAILS TO CLOSE ON FW ISOLATION SIGNAL I FW26 FEEDWATER FLOW CONTROL VALVE FAILS OPEN FW27 FEEDWATER FLOW CONTROL VALVE FAILS CLOSED FW28 HEATER DRAIN PUMP TRIP FW29 HEATER DRAIN TANK LEVEL TRANSMITTER FAILS 111G11 FW30 HEATER DRAIN TANK LEVEL TRANSMIITER FAILS LOW FW31 IlEATER DRAIN PUMP FAILS TO MINIMUM FW32 - AUXILIARY FEEDWATER PUMP TRIP - MOTOR FW33 AUXILI ARY FEEDWATER PUMP TRIP - TURBINE FW34 AUXILIARY FEEDWATER PUMP FAILS TO START AUTOMATICALLY l FW35 INADEQUATE CONDENSATE TO AUXILIARY FEEDWATER PUMP SUCTION FW36 AUXILIARY FEEDWATER DISCHARGE LINE RUPTURE INSIDE CONTAINMENT FW37 AUXILIARY FEEDWATER DISCHARGE LINE RUPTURE OUTSIDE CONTAINMENT l FW38 AUX 1LIARY FEEDWATER CONTROL VALVE FAILS IN POSITION j FW39 FEEDWATER LINE RUPTURE UPSTREAM OF FW REG VALVES l FW40 COMMON FEEDWATER PUMP SUCTION LINE BLOCKAGE i FW41 FEEDWATER FLOW CONTROL VALVE LEAKAGE  ;

FW100 11 12-13 LP FW HTR BYPASS  !

FW101 TDAFWP 1A ISOL TO CV-31998 )

FW102 CST XCONNECT FW103 AFW TO 11 SG CNMTISO BKR FW104 AFW TO 12 SG CNMTISO BKR FW105 11 A-12A-13A FW HTR ISOL i FW106 11B-12B-13B FW llTR ISOL l FW107 14A FW HTR ISOL ,

FW108 14B FW HTR ISOL FW109 14A FW HTR BYPASS FWil0 14B FW HTR BYPASS FWill COND MAKEUP MANUAL BYPASS FWil2 15A HTR ISOL FW113 ISB FW llTR ISOL  ;

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PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1998 APPENDIX 2 FW114 ISA FW HTR BYPASS FWil5 ISD HTR BYPASS FWil8 COND POLISH SYS BYPASS FW119 CONDENSER SPRAY SYSTEM FW120 11 FW PUMP RECIRC VLV FW121 12 FW PUMP RECIRC VLV FW122 COND BYPASS TO CW STANDPIPE, CD-19-1 FW123 1A ISOL 11 FW PUMP RECIR VLV FW124 I A ISOL 12 FW PUMP RECIR VLV FW125 11 AFW PUMP RESET PB FW126 11 FW PMP DSCHG VLV CONTROL SW FW127 12 FW PMP DSCHG VLV CONTROL SW FW128 11 FW PMP DSCHG VLV CLOSE LOCAL PB FW129 i FW PMP DSCHG VLV OPEN LOCAL PB FW130 12 FW PMP DSCHG VLV CLOSE LOCAL PB FW131 12 FW PMP DSCHG VLV OPEN LOCAL PB FW132 MDAFWP LOW PRESSURE TRIPS OVRD FW133 21 MDAFW PUMP & CROSS-CONNECT VALVES FW134 11 AFW PUMP TO 1 A STM GEN, MV-32238 FW135 11 AFW PUMP TO 1B STM GEN, MV-32239 FW136 12 MDAFW PUMP TO 1 A STM GEN, MV 32381 FW137 12 MDAFW PUMP TO 1B STM GEN, MV 32239 FW138 11 CONDENSATE RECYCLE PUMP FW139 11/21 CST LEVEL ADJUSTMENT FW200 COND FLW TRANSMITTER FW201 CDSR HW TRANSMITTER FW202 1I A FW LEVEL TRANSMITTER FW203 12A FW LEVEL TRANSMITTER FW204 11B FW LEVEL TRANSMITTER FW205 12B FW LEVEL TRANSMITFER FW206 13A FW LEVEL TRANSMITFER FW207 13B FW LEVEL TRANSMITTER FW208 15A FW LEVEL TRANSMITTER FW209 15B FW LEVEL TRANSMITTER Compressed Air System 1A01 LOSS OF SERVICE AIR HEADER IA02 LOSS OF INSTRUMENT AIR HEADER ,

IA03 LOSS OF AIR COMPRESSOR IA100

)

POLISH AIR TO STATION AIR IA101 POLISH AIR TO INST AIR IA102 121 FILTER DRYER BYPASS RESET JA103 122 FILTER DRYER BYPASS RESET j IA104 124 STATION AIR COMPRESSOR LOCAL CS (58151) l IA105 125 STATION AIR COMPRESSOR LOCAL CS (58152)

Main Steam System MS01 M AIN STEAM LINE RUPTURE INSIDE CONTAINMENT UPSTREAM OF MSIV MS02 MAIN STEAM LINE RUPTURE OUTSIDE CONTAINMENT UPSTREAM OF MSIV l Page 9 i

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, a-PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1998 APPENDIX 2 MS03 MAIN STEAM LINE RUPTURE OUTSIDE CONTAINMENT DOWNSTREAM OF MSIV MSO4 MAIN STEAM LINE LEAK MS05 - MAIN STEAM SAFETY VALVE STICKS OPEN MS06 GLAND SEAL STEAM REGULATING VALVE FAILS CLOSED MS07 MAIN STEAM SAFETY VALVE FAILURE MS08 MOISTURE SEPARATOR - RE11 EATER RELIEF VALVES FAILURE MSO9 MAIN STEAM LINE LEAK INSIDE CONTAINMENT MS10 - MAIN STEAM LINE BREAK ON COMMON SUPPLY LINE TO AFW MSII STEAM DUMP VALVE FAILS IN POSITION MS100 11 SG PORV ISOL.

MS101 12 SG PORV ISOL MS102 11 SG ATMOS STM DUMP ISOL MS103 - 11 SG ATMOS STM DUMP ISOL MS104 12 SG ATMOS STM DUMPISOL MS105 12 SG ATMOS STM DUMP ISOL MS106 - COND STM DUMP ISOL MS107 M ANUAL POSITIONING OF CONDENSER STEAM DUMP (CV-31100)

MS108 1 A MSR STM SUP ISOL MS109 IB MSR STM SUPISOL MS110 2A MSR STM SUP ISOL MSill 2B MSR STM SUPISOL MSil2 11 SAFETY VALVE 11DR VENT MSil3 12 SAFETY VALVE IIDR VENT MSil4 1 A MSR CV BYPASS MSil5 IB MSR CV BYPASS MSil6 2A MSR CV BYPASS MSil7 - 2B MSR CV BYPASS MSil8 MSR TO 11 HTR DRAIN TANK STOP CV RESET PB MS119 11P TURBINE BLADING REMOVED MS120 LP TURBINE BLADING REMOVED MS121 1 A SG PORV IA ISOL MS122 1 A SG PORV LOCAL CNTROL VLV POSITION MS123 1B SG PORV 1A ISOL MS124 IB SG PORV LOCAL CNTROL VLV POSITION MS125 liEATING STM SUPPLY TO AUX MAIN STM MS126 R11TR DRN TNKTO 15 FW IITR CV RESET PB MS127 1 A MSIV BYPASS MV-32045 BREAKER (IL1-D3)

MS128 IB MSIV BYPASS MV-32047 BREAKER (ILA2-D4 MS129 11 SG ATM STM DUMP CV 31086 POSITION 0-100%

MS130 11 SG ATM STM DUMP CV-31085 POSITION 0-100%

MS131 12 SG ATM STM DUMP CV-31090 POSITION 0-100%

MS132 12 SG ATM STM DUMP CV-31091 POSITION 0-100%

MS133 IA SUPPLY TO COND STM DUMP CV-3100

. MS134 1A SUPPLY TO 11 SG ATM STM DUMP CV-31086 MS135 IA SUPPLY TO 11 SG ATM STM DUMP CV-31085 MS136 IA SUPPLY TO 12 SG ATM STM DUMP CV-31090 MS137 IA SUPPLY TO 12 SG ATM JTM DUMP CV-31091 MS200 IB MS LEVEL TRANSMITTER Page 10 l

q PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1998 APPENDIX 2 MS201 2B MS LEVEL TRANSMITTER MS202 1 A MS LEVEL TRANSMITTER

_ MS203 2A MS LEVEL TRANSMITTER MS300 11 SG SAFETY VALVE

\ MS301 11 SG SAFETY VALVE

}

MS302 11 SG SAFETY VALVE MS303 11 SG SAFETY VALVE MS304 11 SG SAFETY VALVE MS305 12 SG SAFETY VALVE MS306 12 SG SAFETY VALVE MS307 12 SG SAFETY VALVE i MS308 12 SG SAFETY VALVE t MS309 12 SG SAFETY VALVE I Nuclear Instrumentation System 1- N!01 INCORRECT SOURCE RANGE CHANNEL RESPONSE N102 SOURCE RANGE CHANNEL SPIKES N103 INTERMEDIATE RANGE CHANNEL IMPROPER RESPONS8: ,

N104 INTERMEDIATE RANGE CHANNEL IMPROPER COMPENSATION NIOS IMPROPER POWER CHANNEL RESPONSE N106 POWER RANGE UPPER CIIANNEL IMPROPER RESPONSE N107 POWER RANGE LOWER CifANNEL IMPROPER RESPONSE nil 00 CllANNEL 1 PWR RNG HI Q - HI F B/S N!!01 CHANNEL 2 PWR RNG HI Q - HI F B/S N1102 CilANNEL 3 PWR RNG 111 Q -III F B/S N1103 CHANNEL 4 PWR RNG 111 Q - HI F B/S N1104 CHANNEL 1 PWR RNG LO Q - HI F B/S N1105 CHANNEL 2 PWR RNG LO Q - 111 F B/S N1106 CHANNEL 3 PWR RNG LO Q - Hi F B/S N1107 CHANNEL 4 PWR RNG LO Q - 111 F B/S N1108 CHANNEL l INT RNG HI F B/S N1109 CHANNEL 2 INT RNG HI F B/S Nil 10 CHANNEL 1 SOURCE RNG HI F B/S nil 11 CHANNEL 2 SOURCE RNG Hi F B/S N!!12 POWER RANGE P-10 B/S NC-41 M Nil 13 POWER RANGE P-10 B/S NC-42 M NII14 POWER RANGE P-10 B/S NC-43 M Nll15 POWER RANGE P-10 B/S NC-44 M Nil 16 POWER RANGE P-8 B/S NC-41 N nil 17 POWER RANGE P-8 B/S NC-42 N Nil 18 POWER RANGE P-8 B/S NC-43 N Nil 19 POWER RANGE P-8 B/S NC-44 N Nil 20 INTERM RANGE P-6 B/S NC-35 D Nil 21 INTERM RANGE P-6 B/S NC-36 D Nil 22 CHANNEL 1 POSITIVE RATE B/S NJ123 CHANNEL 2 POSITIVE . RATE B/S Nil 24 CHANNEL 3 POSITIVE RATE B/S Nil 25 CHANNEL 4 POSITIVE RATE B/S Nil 26 CHANNEL 1 NEGATIVE RATE B/S Page 11

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PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1998 APPENDIX 2  :

Nil 27 CilANNEL 2 NEGATIVE RATE B/S Nil 28 CilANNEL 3 NEGATIVE RATE B/S Nil 29 CHANNEL 4 NEGATIVE RATE B/S Nil 30 CHANNEL 1/2 SOURCE RANGE HI FLUX AT SD SETPOINT Nil 31 CHANNEL 1 P9 B/S Nil 32 CHANNEL 2 P9 B/S NI133 CHANNEL 3 P9 B/S -

Nil 34 CHANNEL 4 P9 B/S Nil 35 CHANNEL 1 INT RNG ROD BLOCK B/S NC-35B N1136 CilANNEL 2 INT RNG ROD BLOCK B/S NC-36B NI137 CliANNEL 1 PWR RNG ROD BLOCK B/S NC--4iL Nil 38 CHANNEL 2 PWR RNG ROD BLOCK B/S NC-42L Nil 39 CilANNEL 3 PWR RNG ROD BLOCK B/S NC-43L Nil 40 CliANNEL 4 PWR RNG ROD BLOCK B/S NC-44L

{

Nil 41 N41 DETECTOR GAIN ADJUSTMENTS Nil 42 N42 DETECTOR GAIN ADJUSTMENTS Nil 43 N43 DETECTOR GAIN ADJUSTMENTS Nil 44 N44 DETECTOR GAIN ADJUSTMENTS N1300 IR N35 PWR ABOVE P-6 NI301 1R N36 PWR ABOVE P-6 N1302 PR N41 PWR ABOVE P-8 N1303 PR N42 PWR ABOVE P-8 N1304 PR N43 PWR ABOVE P-8 N1305 PR N44 PWR ABOVE P-8 N1306 PR N4i PWR ABOVE P-9 N1307 PR N42 PWR ABOVE P-9 N1308 PR N43 PWR ABOVE P-9 N1309 PR N44 PWR ABOVE P-9 N1310 PR N41 PWR ABOVE P-10 l N1311 PR N42 PWR ABOVE P-10  !

N1312 PR N43 PWR ABOVE P-10 N1313 PRN44 PWR ABOVE P-10 N1314 SR N31 HI FLUX TRIE l NI315 SR N32 HI FLUX TRIP ,

N!316 IR N35 Hi FLUX TRIP  !

N1317 IR N36 HI FLUX TRIP N1318 PR N41 LO RNG 111 FLUX TRIP N1319 PR N42 LO RNG 111 FLUX TRIP '

N1320 PR N43 LO RNG HI FLUX TRIP NI321 PR N44 LO RNG HI FLUX TRIP N1322 PR N41 H2 RNG HI FLUX TRIP NI323 PR N42 HI RNG lil FLUX TRIP N1324 PR N43111 RNG HI FLUX TRIP N1325 PR N44 HI RNG lil FLUX TRIP N1326 PR N41 POS RATE TRIP  !

N1327 PR N42 POS RATE TRIP '

N1328 PR N43 POS RATE TRIP NI329 PR N44 POS RATE TRIP Page 12

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. i PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT i 1998 APPENDIX 2 i N1330 PR N41 NEG RATE TRIP 3 N133i PR N42 NEG RATE TRIP  !

Nf332 PR N43 NEG RATE TRIP N1333 PR N44 NEG RATE TRIP ' l Plant Process Computer System i PC01 . ERCS CPU FAILURE l PC03 ERCS ALA'RM DISPLAY FAILURE ,

PC04 ERCS SAS DISPLAY FAILURE PC05- . ERCS CONTROL ROOM PRINTER FAILURE PC100- ACKNOWLEDGE UNIT 2 ERCS ALARMS l Reactor Coolant System RC01 REACTOR COOLANT PUMP TRIP

RC02 REACTOR COOLANT PUMP LOCKED ROTOR l RC03 REACTOR COOLANT PUMP SilAFT SHEAR (SElZED IMPELLER)

' RC04 REACTOR COOLANT PUMP SIIAFT SilEAR RC05 REACTOR COOLANT PUMP BEARING FAILURE j RC06 LOSS OF COOLANT ACCIDENT- HOT LEG i RC07 LOSS OF COOLANT ACCIDENT- COLD LEG RCP SUCTION RC08 LOSS OF COOLANT ACCIDENT- COLD LEG RCP DISCHARGE RC09 LOSS OF COOLANT ACCIDENT PRESSURIZER STEAM SPACE RC10 LOSS OF COOLANT ACCIDENT PRESSURIZER WATER SPACE RCl1 LOSS OF COOLANT ACCIDENT - RTD BYPASS LOOP COLD LEG MANIFOLD RCl2 LOSS OF COOLANT ACCIDENT- RTD BYPASS LOOP RETURN LEG PIPING i RCl3 LOSS OF COOLANT ACCIDENT- REACTOR llEAD VENT l RCl4 REACTOR COOLANT SYSTEM LEAKS RCIS REACTOR COOLANT SYSTEM LEAKS RC16 - PRESSURIZER POWER OPERATED RELIEF VALVE FAILS CLOSED RCI8 PRESSURIZER SAFETY VALVE RC-10-1 FAILS OPEN RC19 PRESSURIZER SAFETY VALVE SEAT LEAKS RC20 REACTOR COOLANT PUMP OIL LEAK UPPER RESERVOIR RC21 REACTOR VESSEL O-RING LEAKAGE RC22 PRESSURIZER POWER OPERATED RELIEF VALVE LEAKAGE RC24 PRESSURIZER SPRAY VALVE FAILS IN POSITION RC100 PRT PRESSURE CONTROLLER SETPOINT RC101 LOOP B DRAIN RC102 REFUELING WATER LEVEL IND RC103 PRZR SPRAY BYPASS LOOP B RC104 PRZR SPRAY BYPASS LOOP A RC105 LOOP A RTD BYPASS ISOL RC106 LOOP B RTD BYPASS ISOL i RC107 RX VESSEL INNER SEAL LEAKOFF RC108 RX VESSEL OUTER SEAL LEAKOFF i

RC109 LOOP A 110T LEG DRAIN TO RCDT RCl10 PRZR STEAM SPACE SAMPLE 4

RCl11 COLD LEG LEVEL ISOLATION VALVES

?

RCil2 11 STM GEN TUBES PLUGGED RCll3 12 STM GEN TUBES PLUGGED

Page 13 l

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I PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1998

-APPENDIX 2 RCI14 ' SHUTDOWN PURIFICATION TO RCDT RCI15 PRZR SPRAY LOOP ISOL RCI16 - LOOP A COMMUNICATION LINE '

RCl17 RCGV IIEAD VENT ORIFICE BYPASS RCl18 ENABLE ULTRASONIC LEVEL INDICATING SYSTEM RCI19 PRT NITROGEN ISOLATION VALVE RC120 RCS LOOP A NITROGEN SUPPLY  !

RCl21 RCS LOOP B NITROGEN SUPPLY l RCl22 REACTOR HEAAD VENT MANUAL VENT VALVE (RC-8-31)

RCl23 PRESSURIZER MANUAL VENT VALVE (RC-8-32)

RCl24 PRT VENT (REMOVE 1LT-442 TOP TAP VALVE)

RC300 PZR SAFETY RC301 PZR SAFETY Control Rod Drive System RD01 CONTROLLING ROD BANK falls TO MOVE IN MANUAL RD02 ' CONTROLLING ROD BANK FAILS TO MOVE IN AUTO RD03 . UNCONTROLLED CONTINUOUS ROD WITHDRAWAL OF CONTROLLING BANK RD04 UNCONTROLLED CONTINUOUS ROD INSERTION OF CONTROLING BANK I RDOS CONTROL ROD MISALIGNMENT l RD06 STUCK ROD

' RD07 DROPPED ROD RDOS CONTROL ROD G-3 EJECTED ,

RD09 ROD POSITION INDICATION FAILS i RD10 INCORRECT ROD SPEED '

l RD100 11 ROD DRIVE MG RD101 12 ROD DRIVE MG RD102 RPI SUPPLY FRM INV 15/FROM PNL 117 RD103 BANK D ROD BLOCK B/S TC-40$K RD104 SET CONTROL BANK A P/A CONV RD105 SET CONTROL BANK B P/A CONV RD106 SET CONTROL BANK C P/A CONV RD107 SET CONTROL BANK D P/A CONV RD113 INV 115/ PANEL 117, CKT 13 POWER TO IRPl STACKS Residual Heat Removal System RII01 RESIDUAL HEAT REMOVAL PUMP TRIP RH02 RESIDUAL llEAT REMOVAL PUMP FAILS TO START AUTOMATICALLY RH03 RHR llEAT EXCHANGER END BELL LEAKAGE TO ATMOSPHERE RH04 RHR HEAT EXCHANGER BYPASS VALVE FAILS OPEN RHOS RHR HEAT EXCHANGER BYPASS VALVE FAILS CLOSED RH06 RECIRCULATION SUMP SUCTION LINES BLOCKED RH07 RHR SYSTEM LEAKAGE

. RHOS RHR PUMP SEAL FAILURE RH09 RESIDUAL REAT REMOVAL RELIEF VALVE FAILURE RH100 11 RHR HX INLET X-CONN, RH-2-4 RH101 12 RHR HX INLET X-CONN, Ril-2-3 RH102 11 RHR llX OUTLET X-CONN, RH-2-6 RH103 12 RHR HX OUTLET X-CONN, RH-2-5 Page 14 I

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PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1998 APPENDIX 2 RH104 LOOP A HOT LEG MV-32164 BKR RH105 LOOP B llOT LEG MV-32230 BKR Ril106 12 RHR PMP DSCilG TO SUMP RH107 LOOP 11 RET ISO BKR Ril108 11 RHR llEAT EXCilANGER INLET ISOL Ril-1-4 RH109 12 RIIR HEAT EXCHANGER INLET ISOL RH-1-3 Rlil10 11 RHR (CV-31235) MECHANICAL STOP Ril111 12 RHR (CV-31236) MECHANICAL STOP RHI12 11 RHR PUMP SUCTION VALVE Rill 13 12 RHR PUMP SUCTION VALVE Rill 14 RHR TO CVCS LETDOWN LINE Rlli15 LOOP A IlOT LEG MV-32165 BKR RIi116 LOOP B HOT LEG MV-32231 BKR Rlli17 R11R TO LETDOWN MV 32234 BREAKER RH118 RiiR BORON CONCENTRATION (DISPLAY ONLY) PPM Ril200 Rif FLOW TRANSMITTER Radiation Monitoring System RM01 RADIATION MONITOR MISCAllBRATION Reactor Protection System RP01 REACTOR TRIP RP02 FAILURE OF AUTOMATIC REACTOR TRIPS RP03 FAILURE OF SAFETY SYSTEMS TO ACTUATE RPO4 INADVERTENT ACTUATION OF THE SAFETY INJECTION SYSTEM RP05 FAILURE OF CONTAINMENT ISL. ATION PilASE A TO ACTUATE RP06 FAILURE OF MSIV'S TO ISOLATE RP07 MECil ANICAL FAILURE OF REACTOR TRIP BREAKERS RP08 FAILURE OF SAFEGUARDS ACTUATION RP100 REACTOR TRIP BYPASS BKR TRN A RP101 REACTOR TRIP BYPASS BKR TRN B RP102 1 LOW RC FLOW A LOOP B/S FC-411 RP103 2 LOW RC FLOW A LOOP B/S FC-412 RP104 3 LOW RC FLOW A LOOP B/S FC-413 RP105 1 LOW RC FLOW D LOOP B/S FC-414 RP106 3 LOW RC FLOW D LOOP B/S FC-415 RP107 4 LOW RC FLOW B LOOP B/S FC-416 RP108 CliANNEL 1 RCP BKR OPEN B/S RP109 CHANNEL 2 RCP BKR OPEN B/S RPI10 1 PRZR PRESSURE HI B/S PC,-429A RPl11 1 PRZR PRESSURE St B/S PC-429C RPI12 1 PRZR PRESSURE SI UNBLOCK B/S PC-429D j RPl13 1 PRZR PRESSURE LO B/S PC-429E RPil4 11 STM LOOP LO-LO PRESS B/S PC-468A I RPl15 11 STM LOOP LO-LO PRESS B/S PC-469A l

RPI16 11 STM LOOP LO-LO PRESS B'S PC-482A RPI17 1 PRZR HIGH LVL B/S LC-426A RPI18 2 PRZR lilGH LVL B/S LC-427A RPI19 3 PRZR lilGil LVL B/S LC-428A Page 15

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I PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT

• 1998 APPENDIX 2 f RP120 3 PRZR PRESSUPE 111 B/S PC-431 A I RP121 3 PRZR PRESSURE SI B/S PC-431G RP122 3 PRZR PRESSURE SI UNBLOCKED B/S PC-431L

. RP123 3 PRZR PRESSURE LO B/S PC-431J PP124 4 PRZR PRESSURE LO B/S PC-449A RP125 11 S/G LO-LO LVL B/S LC-461B RP126 12 S/G LO-LO LVL B/S LC-472A RP127 11 STM GEN LO PRESS B/S PC-468B RP128 11 S/G lil LVL B/S LC-461 A RP129 12 S/G HI LVL B/S LC-472B RP130 12 S/G LO-LO LVL B/S LC-473C RP131 11 STM GEN LO PRESS B/S PC-469B RPl32 12 S/G lil LVL B/S LC-473D RP133 11 S/G LO-LO LVL B/S LC-462A RP134 11 STM GEN LO PRESS B/S PC-482B '

RP135 11 S/G HI LVL B/S LC-462B RPl36 12 STM GEN LO PRESS B/S PC-478B RP137 12 STM GEN LO PRESS B/S PC-479B RP138 12 STM GEN LO PRESS B/S PC-483B RP141 1 HI STM FLOW FC-464A RP142 1 HI-HI STM FLOW FC-464B RP143 3 HI STM FLOW FC-474A RP144 3 HI-H1 STM FLOW FC-474B RP148 AMSAC BLOCK SWITCH RP152 CHANNEL 1 BUS 11 UNDERVOLTAGE B/S RP153 CHA Gt 12 BUS 11 UNDERVOLTAGE B/S RPl54 C!! OmLL 3 BUS 12 UNDERVOLTAGE B/S RPl55 CHANid.L 4 BUS 12 UNDERVOLTAGE B/S RP156 12 STM LOOP LO-LO PRESS B/S PC-483A RP157 12 STM LOOP LO-LO PRESS B/S PC-478A RP158 12 STM LOOP LO-LO PRESS B/S PC-479A RP159 2 RC LOOP OP DELTA T B/S TC-406A RP160 2 RC LOOP OP DELTA T B/S TC-406B RP161 2 RC LOOP OT DELTA T B/S TC-406C RPl62 2 RC LOOP OT DELTA T B/S TC-406D RP163 1 RC LOOP LO TAVG B/S TC-401F RPl64 1 RC LOOP LO-LO TAVG B/S TC-401D RP165 2 RC LOOP LO TAVG B/S TC-402F RPl66 2 RC LOOP LO-LO TAVG B/S TC-402D RPl67 OPPS HI PRESSURE B/S PC-419D RP168 OPPS 111 PRESSURE B/S PC-420D RP169 1 RC LOOP OP DELTA T B/S TC-405A RPl70 1 RC LOOP OP DELTA T B/S TC-405B RPl71 1 RC LOOP OT DELTA T B/S TC-405C RPl72 1 RC LOOP OT DELTA T B/S TC-405D RP181 2 TURBINE POWER P-7 B/S PC-485A RPI82 3 TURBINE POWER P-7 B/S PC-486A RP183 11 BUS UNDERFREQUENCY B/S Page 16 l

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PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1998 APPENDIX 2 RP184 11 BUS UNDERFREQUENCY B/S RP185 12 BUS UNDERFREQUENCY B/S l RP186 12 BUS UNDERFREQUENCY B/S RP187 2 PRZR PRESSURE 111 B/S PC-430A RP188 2 PRZR PRESSURE SI B/S PC-430E RP189 2 PRZR PRESSURE SI UNBLOCK B/S PC-430F RP190 2 PRZR PRESSURE LO B/S PC-43011 RPl91 11 S/G LO-LO LVL B/S LC-463C RP192 11 S/G 111 LVL B/S LC-463D RP193 2111 STM FLOW FC-465A RP194 2 '11-111 STM FLOW FC-465B RP195 4111 STM FLOW FC-475A RP196 4 lil-HI STM FLOW FC-475B RP199 3 RP LOOP OP DELTA T B/S TC-407A RP200 3 RC LOOP OP DELTA T B/S TC 407B RP201 3 RC LOOP OT DELTA T B/S TC-407C RP202 3 RC TOOP OT DELTA T B/S TC-407D RP203 4 RC LOOP OP DELTA T B/S TC-408A RP204 4 RC LOOP OP DELTA T B/S TC-408B RP205 4 RC LOOP OT DELTA T B/S TC-408C RP206 4 RC LOOP OT DELTA T B/S TC-408D RP207 3 RC LOOP LO TAVG B/S TC-403F RP208 3 RC LOOP LO-LO TAVG B/S TC-403D RP209 4 RC LOOP LO TAVC B/S TC-404F RP210 4 RC LOOP LO-LO TAVG B/S TC-404D RP211 12 S/G LO-LO LVL B/S LC-471B RP212 12 S/G 111 LVL B/S LC-471 A RP300 CH 2 P-7 TURB PRESS RP301 CH 3 P-7 TURB PRESS RP302 AUTO ROD WIT 11DRAWAL BLOCK P-2 RP303 BUS 11 UV TRIP RP304 BUS 12 UV TRIP RP305 BUS 11 UF TRIP RP306 BUS 12 UF TRIP RP307 A LOOP CH I RC LOW FLOW TRIP RP308 A LOOP CH 2 RC LOW FLOW TRIP RP309 A LOOP CH 3 RC LOW FLOW TRIP RP310 B LOOP Cil 1 RC LOW FLOW TRIP RP311 B LOOP C113 RC LOW FLOW TRIP RP312 B LOOP CH 4 RC LOW FLOW TRIP RP313 Cil 1 PRZR LO PRESS TRIP RP314 CH 2 PRZR LO PRESS TRIP RP315 CH 3 PRZR LO PRESS TRIP RP316 Cli 4 PRZR LO PRESS TRIP RP317 C111 PZR 111 PRESS TRIP RP318 CII 2 PZR 111 PRESS TRIP RP319 Cll 3 PZR 111 PRESS TRIP RP320 CH 1 PRZR LO PRESS S1 Page 17

t

• PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1998 APPENDIX 2 RP321 CH 2 PRZR LO PRESS S1 RP322 Cil 3 PRZR LO PRESS S1 RP323 CH 1 PRZR 111 LVL TRIP j RP324 CH 2 PRZR 111 LVL TRIP '

RP325 CH 3 PRZR HI LVL TRIP l RP326 LOOP A CH I SG LOLO LVL TRIP RP327 LOOP A CH 3 SG LOLO LVL TRIP  ;

RP328 LOOP A Cli 4 SG LOLO LVL TRIP RP329 LOOP B Cil 1 SG LOLO LVL TRIP RP330 LOOP B Cll 2 SG LOLO LVL TRIP RP331 LOOP B Cli 4 SG LOLO LVL TRIP RP340 LOOP A LOLO TAVG STM LN ISOL/lil STM FLOW l RP341 LOOP A LOLO TAVG STM LN ISOL  !

RP342 LOOP B LOLO TAVG STM LN ISOL RP343 LOOP B LOLO TAVG STM LN ISOL RP344 LOOP A 111 STM FLOW 1 RP345 LOOP A Ill STM FLOW l RP346 LOOP B HI STM FLOW l RP347 LOOP B Hi STM FLOW RP348 LOOP A SG HI-H1 STM FLOW RP349 LOOP A SG 111-111 STM FLOW RP350 LOOP B SG lil-HI STM FLOW RP351 LOOP B SG 111-111 STM FLOW RP352 LOOP A CH I SG LOLO STM PRESS Si l RP353 LOOP A Cil 2 SG LOLO STM PRESS SI  ;

RP354 LOOP A CH 3 SG LOLO STM PRESS SI l RP355 LOOP B Cil 1 SG LOLO STM PRESS SI l RP356 LOOP B CH 3 SG LOLO STM PRESS Si l RP357 LOOP B CH 4 SG LOLO STM PRESS SI  !

Reactor Control System I RX01 PRESSURIZER SPRAY VALVE FAILS OPEN l RX02 PRESSURIZER SPRAY VALVES PCV-431 A & B FAIL CLOSED RX03 PRESSURIZER HEATERS FAIL ON RX04 PRESSURIZER HEATERS FALLOFF (ALL)

RX05 REACTOR COOLANT LOOP Til TRANSMITTER FAILS IllGli RX06 REACTOR COOLANT LOOP Til TRANSMITTER FAILS LOW RX07 REACTOR COOLANT LOOP TC TRANSMITTER FAILS HIGH RXO8 REACTOR COOLANT LOOP TC TRANSMITTER FAILS LOW RX09 RCS WIDE RANGE PRESSURE TRANSMITTER FAILS HIGli RX10 RCS WIDE RANGE PRESSURE TRANSMITTER FAILS LOW RX11 FEEDWATER CONTROLLER OUTPUT FAILURE RX12 TURBINE FIRST STAGE PRESSURE TRANSMITTER FAILS lilGli RX13 TURBINE FIRST STAGE PRESSURE TRANSMITTER FAILS LOW '

RX14 STEAM GENERATOR FEEDWATER CONTROL SYSTEM FAILS TO MANUAL RX15 ADFCS MAIN FLOW CONTROL VALVE OUTPUT CARD FAILURE

! RX16 ADFCS BYPASS FLOW CONTROL VALVE OUTPUT CARD FAILURE RX100 PRZR HTR GROUP B RX101 IMPULSE PRESS ROD BLOCK B/S PC-485C Page 18 i

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i PRAIRIE ISIJLND SIMULATOR CERTIFICATION REPORT -

l 1998 APPENDIX 2 RX102 IMPULSE PRESS STM DUMP B/S PC-486C RX103 i PRZR 111 PRESS PORV B/S T/P-429B RX104 2 PRZR lil PRESS PORV B/S PC-4308 RX105 3 PRZR111 PRESS PORV B/S PC-431B RX106 4 PRZR111 PRESS PORV B/S T/P-449B RX107 PRZR LO PRESS BU HTRS B/S PC-431E

, RX108 ADFCS SIGNAL SELECTOR LOGIC RESET RX109 ADFCS LOSS OF WIDE RANGE LEVEL LOGIC RESET i' RX200 RCS PRESSURE TRANSMITTER PT429 RX201 RCS PRESSURE TRANSMITTER PT430 i RX202 RCS PRESSURE TRANSMITTER PT431 I RX203 RCS PRESSURE TRANSMITTER PT449 RX204 PRZR LVL TRANSMITTER LT426 I RX205 PRZR LVL TRANSMITTER LT427 l RX206 PRZR LVL TRANSMITTER LT428 RX207 11 FW FLOW TRANSMITTER FT466 RX208 11 FW FLOW TRANSMITTER FT467 RX209 11 FW FLOW TRANSMITTER FT495 l RX210 12 FW FLOW TRANSMllTER FT476 RX211 12 FW FLOW TRANSMITTER FT477 l

l RX212 12 FW FLOW TRANSMITTER IT497  !

RX213 11 MS PRESSURE TRANSMITTER PT468 RX214 11 MS PRESSURE TRANSMITTER PT469 RX215 11 MS PRESSURE TRANSMITTER PT482 RX216 12 MS PRESSURE TRANSMITTER PT478 l RX217 12 MS PRESSURE TRANSMITTER PT479 '

RX218 12 MS PRESSURE TRANSMITTER PT483 RX219 11 MS FLOW TRANSMITTER FT464  ;

RX220 11 MS FLOW TRANSMITTER FT465  ;

RX221 12 MS FLOW TRANSMITTER FT474 RX222 12 MS FLOW TRANSMITTER FT475 RX223 11 STM FLOW TRANSMITTER FT494 RX224 12 STM FLOW TRANSMITTER FT496 RX225 11/12 MS PRESSURE TRANSMITTER PT484 RX226 IST STAGE PRESS TRANSMITTER PT485 RX227 11 FEED TEMP TRANSMITTER TT498 RX228 12 FEED TEMP TRANSMITTER TT499 RX229 FW 11DR PRESSURE TRANSMITTER PT450 RX230 FW IIDR PRESSURE TRANSMITTER PT451 i RX231 11 SG WR LEVEL TRANSMITTER LT502 ,

RX232 12 SG WR LEVEL TRANSMITTER LT503 l RX233 PZR LEVEL LOCAL CONTROL LC428F RX234 SG LEVEL TRANSMllTER LT461 RX235 SG LEVEL TRANSMITTER LT462.

l RX236 SG LEVEL TRANSMITTER LT463 i RX237 SG LEVEL TRANSMITTER LT471

'. RX238 SG LEVEL YRANSMITTER LT472 i RX239 SG LEVEL TRANSMITTER LT473 Page 19 l ,

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PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1998 APPENDIX 2 RX240 AUCTIONEERED TAVG RX300 PRZR PORV SETPOINT RX302 LOAD REJECT STM DUMP 111 TAVG RX303 LOAD REJECT STM DUMP HIHI TAVG RX304 TURBINE TRIP STM DUMP Hl/HIHI TAVG RX305 MASTER PRZR PRESS CONT ST; 2 Steam Generator System SG01 STEAM GENERATOR TUBE LEAK SG02 STEAM GENERATOR TUBE RUPTURE SG03 STEAM GENERATOR BLOWDOWN CONTROL VALVE FAILS OPEN SG100 SG BLOWDOWN DISCHARGE SG101 SG BLOWDOWN RESET SG102 11 SG BD SAMPLE ISOL VLV LOCAL CS CLOSE SG103 11 SG BD SAMPLE ISOL VLV LOCAL CS OPEN SG104 12 SG BD SAMPLE ISOL VLV LOCAL CS CLOSE SG105 12 SG BD SAMPLE ISOL VLV LOCAL CS OPEN Safety Injection System S101 BOTH BORIC ACID TANK VALVES FAIL TO OPEN IN AUTO SIO2 SI LOOP A COLD LEG INJ CHECK VALVE FAILURE S103 BA TNK VLV FAILS TO CLOSE ON LO-LO LVL IN THE SELECTED BA TNK IN AUTO S104 SAFETY INJECTION PUMP TRIPS S105 SAFETY INJECTION PUMP FAILS TO START AUTOMATICALLY S106 SI ACCUMULATOR LEAKAGE S107 SI ACCUMULATOR CHECK VALVE LEAKAGE S108 SI ACCUMULATORIELIEF VALVE LEAKAGE S109 SI COLD LEG INJ LINE RUPTURE INSIDE OF THE ANNULUS S1100 11/121 BAST SUPPLY TO SIS S1101 Si TEST LINE S1102 BA BLENDER TO RWST S1103 11/12 S1 PMP DISCHG X-CONN SIl04 11 SI PUMP DISCHARGE VLV Sil05 12 S1 PUMP DISCHARGE VLV SI106 BA SPLY TO SI PMPS (32083) BKR S1107 11 SI SUCTION FROM RHR BKR Sil08 12 SI SUCTION FROM RHR BKR S1109 SI TO COLD LEGS CNMT ISO BKR SIl10 SI TO LOOP B COLD LEG BKR Silli S1 TO LOOP A COLD LEG BKR Sill 2 11 ACCUM OUTL VLV BKR Sill 3 12 ACCUM OUTL VLV BKR Sil14 Si PUMP SUCTION VALVE, SI-15-5 S1115 RWST LEVEL ADJUSTMENT Turbine Control System TC01 TURBINE STOP VALVE FAILS TO CLOSE WHEN REQUIRED TC02 TURBINE STOP VALVE FAILS CLOSED TC03 TURBINE CONTROL SYSTEM CYCLING OUTPUT TC04 TURBINE CONTROL VALVE FAILS OPEN Page 20

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PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT

! 1998

?

APPENDIX 2  ;

TC05 TURBINE CONTROL VALVE FAILS CLOSED  ;

i -TC06 REACTOR PROTECTION SYSTEM FAILS TO TRIP TURBINE TC07 TURBINE CONTROL INTERCEPT VALVE FAILS CLOSED TC08 TURBINE CONTROL FAILURE DURING TURBINE ROLL i TC09 TURBINE CONTROL FAILURE CAUSING TURBINE RUNBACK

'TC10 ~. TURBINE CONTROL FAILURE CAUSING AN INCREASE IN POWER WITHOUT DEMAND TCl1 TURBINE TRIP FAILURE  !

TCl2 TURBINETRIP l TCl3 ELECTRICAL HYDRAULIC CONTROL PUMP TRIP TCl4 TURBINE CONTROL VALVE FAILS IN POSITION TC100 TURBINE PEDESTAL TRIP .

TC101 CilANNEL 2 TURB AUTO STOP B/S TC102 CHANNEL 3 TURB AUTO STOP B/S TC103 CilANNEL 4 TURB AUTO STOP B/S .

TC104 TURBINE LEFT STOP VLV CLOSED B/S TC105 . TURBINE RIGilT STOP VLV CLOSED B/S TC300 INIT TURB CV POS Turbine System TU01 ' LOSS OF TURBINE LUBE OIL SUPPLY TUO2 TURBINE GENERATOR VfBRATION Chemical and Volume Control System 1 VC01 REACTOR COOLANT PUMP #1 SEAL FAILURE VC02 REACTOR COOLANT PUMP #2 SEAL FAILURE 1 VC04 POSITIVE DISPLACEMENT CHARGING PUMP TRIP VC05 STUCK OPEN CHARGING PUMP RELIEF VALVE VC06 REGENERATIVE IIEAT EXCHANGER LEAKAGE VC07 LETDOWN llEAT EXCHANGER LEAKAGE TO ATMOSPHERE VC08 LETDOWN llEAT EXCHANGER TUBE RUPTURE TO CCW SYSTEM

' VC09 LETDOWN LINE LEAKAGE INSIDE CONTAINMENT VCIO CHARGING PUMP COMMON DISCIIARGE HEADER RUPTURE VCl1 CHARGING LINE LEAKAGE INSIDE CONTAINMENT VCl2 EMERGENCY BORATION VALVE STUCK OPEN VCl3 LETDOWN LINE RELIEF VALVE FAILURE VCl4 VOLUME CONTROL TANK RELIEF VALVE FAILURE VC19 LOSS OF AIR TO CliARGING PUMP SPEED CONTROLLER VC20 CCW RETURN FROM LETDOWN HEAT EXCilANGER FAILS CLOSED VC21 . REACTOR COOLANT PUMP TIIERMAL BARRIER TUBE FAILURE VC100 1I RCP SEAL INJ TilROTTLE VLV VC101 12 RCP SEAL INJ THROTTLE VLV

' VC102 11 RCP STANDPIPE FILL VC103 12 RCP STANDPIPE FILL VC104 11/12 MB DEMIN INLET VC105 11 BAST BORON CONCENTRATION j VC107 11/12 DEBORATING DFMiN  :

VC108 RM STORAGE TANK PUMP SUCTION SELECTOR  !

l.

,- VC109 MANUAL BORATE FROM RWST i r VCl10 BLENDER BYPASS Page 21

e s PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1998 APPENDIX 2 VCili VCT PURGE TO HIGH LVL LOOP VCll2 RMU TO CilG PUMP SUCTION VCl13 11 CllG PUMP SPEED REMOTE <

VCl14 12 CilG PUMP SPEED REMOTE VC)15 13 CHG PUMP SPEED REMOTE VCl16 11/12 LETDOWN FILTER OUTLET i VC117 BORON CONCENTRATION l VCll8 LETDOWN FILTER.S BYPASS I VC119 H2 SUPPLY TO VCT I VCl20 SEAL WTR RTRN ISOL l VCl21 11 BAST LEVEL l VC!22 121 BAST LEVEL VCl23 11 RX MAKEUP TK FILL ISOL VCl24 12 RX MAKEUP TK FILL ISOL )

VCl25 11 MIX BED IX BORON CONC VCl26 12 MIX BED IX BORON CONC VCl27 11 DEBORATE IX BORON CONC VCl28 12 DEBORATE IX BORON CONC VC129 EMERGENCY BORATION VALVE VCl30 LOOP B CHARGING LINE BYPASS VCl31 11 RCP LEAKOFF FLOW TRANSMITTER B-P VCl32 12 RCP LEAKOFF FLOW TRANSMITTER B-P VCl33 11 RCP SEAL B-P VCl34 12 RCP SEAL B-P VCl35 11 BA XFER PUMP DISCH TO BLENDER VCl36 12 BA XFER PUMP DISCH TO BLENDER VCl37 11 CVCS HOLDUP TANK LEVEL VC200 VC PRESSURE TRANSMITTER VC201 VC TEMPERATURE TRANSMITTER VC202 VC FLOW TRANSMITTER VC203 VC FLOW TRANSMITTER VC204 VCT LEVEL TRANSMrITER VC205 VCT LEVEL TRANSMITTER WASTE DISPOSAL SYSTEM WD100 ANN SMP PMP DSCH VLV TO CNTMT MV-32228 WD101 ANN SMP PMP DSCH VLV TO CNTMT MV-32228 WD102 CONT SUMP A PMP DSCH VLV TO ARTD SUMP TK WD103 CONT SUMP A PMP DSCH VLV TO ARTD SUMP TK WD104 11 RHR PIT SUMP PMP DSCll VLV WL-87-1 WD105 12 RHR PIT SUMP PMP DSCH VLV W1.-87-2 WD106 LOCAL RESET PB 54700-08 WD107 RCDT FILTER INLET AND B-P VLVS WD108 PURIFICATION JUMPER ISOL VLVS

, WD109 11 REFUELING WATER PURIFICATION PUMP l WD110 WL-34-4/WL-95-1 RCDT VENT AND VACUUM BKR WDill ll/12 RCDT PUMP DISCHARGE (WL-40-1/2)

WDil2 WL-34-3 RCDT TO GAS ANALYZER ISOL VLV WDll3 WL-31-6 RCDT TO WASTE GAS VENT HDR ISOL VLV Page 22 l

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i PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1998 APPENDIX 2

, Table 2A shows the current set of protected initial conditions used for training. These 26 initial conditions are password protected from inadvertent modification and are kept updated as the simulation models are modifiert. An additional 19 initial conditions are password protected to provide security for exam scenarios and for certification testing purposes. The remaining 55 initial conditions are provided for temporary storage of conditions useful for current training or for identification and correction of simulator discrepancies. New initial conditions matching the desired plant conditions will be built as needed to support training.

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PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1998 .

APPENDIX 2 TABLE 2A 2/3/1999 ,

TEU%yjsc wmsiWi(Ji.ATORiRROTECTED!1NITIALCONDITIONSMTMMcWCG han2MuwlmumenMmimnx:imi&G;.:LiAlaswxaarswnumswna&dMMaMwass.u&1ama&LM&amb 1.C. TIME IN DATE BORON ROD XENON TAVG PZR PWR REMARKS CYCLE SIIOT CONC llEIGIIT PRESS I ZBC 12/12/97 2107 SDO NONE 363 384 120 CPS IlU IN PROGRESS / PZR BUBBLE 2 CDC 12/26/97 1711 ARI NONE I13 13 400 CPS COLD SID,3% S/D,30% PZR LVL 3 CDC 12/26/97 1688 ARI NONE 115 15 400 CPS COLD S/D,3% S/D, RCS SOLID 4 ZBC 12/30/97 2096 SDO NONE 349 460 120 CPS IIEATUP IN PROGRESS, READY TO REMOVE RIIR 5 BOC 11/26/97 1701 SDO NONE 549 2265 650 CPS IlOT S/D, ECC:1701 PPM @ 47 STEPS ON D 6 BOC 11/25/97 1701 D@61 INC 554 2269 6 % PRIOR TO ROLLING TURBINE 7 BOC 11/25/97 1701 D @ 61 INC 553 2266 6 % PRIOR TO SYNCIIRONIZING GENERATOR 8 BOC 11/25/97 1471 D @ 195 EQUIL 553 2265 50 % ONE IIDT, COND, AND FW PUMP IN SERVICE 9 BOC 11/25/97 1356 D @ 218 EQUll 560 2264 100 % 100% TARGET DELTA I = +0.6 10 MOC 11/25/97 813 D @ 218 EQUll 560 2265 100 % 100% TARGET DELTA l = -0.9 11 EOC 11/25/97 156 D @ 218 EQUIL 560 2264 100 % 100% TARGET DELTA I = -1.4 12 EOC 11/26/97 182 D @ 165 INC 554 2264 60 % PWR REDUCTION TO 60% FROM 100% AT 1% / MIN PRIOR TO SECURING MFWP 13 EOC i1/26/97 175 D @ 66 INC 549 2264 22 % PRIOR TO SEPARATING UNIT 113 MWE 14 EOC 11/26/97 461 SDO NONE 549 2264 3200 CPS BORATED TO ECC DORON, VACUUM IN COND ECC:461 PPM @ 47 STEPS ON D 15 CDC 12/26/97 1038 ARI INC 341 325 500 CPS C/D IN PROGRESS, PRIOR TO PLACING RIIR IN-SERVICE. AT COLD S/D BORON CONC 16 MOC 11/25/97 1164 D @ ll4 INC 548 2264 11 % LOAD INCREASE 17 CDC 11/26/97 0 D @ 228 EQUIL 555 2264 96 % COASTDOWN AT EOC 18 MOC 12/2/97 1110 D @ 45 NONE 550 2265 1.0E-08 PLANT STARTUP IN PROGRESS 19 MOC 11/25/97 1132 D @ 184 INC 551 2264 50 % LOAD INCREASE; 2 COND, ilDT, MFW PUMPS 20 MOC 12/2/97 832 SDO INC 550 2264 1000 CPS 24 IIRS FOLLOWING RX TRIP FROM 100% PWR.

ECC: 909 PPM @ 47 STEPS ON D 21 MOC 11/25/97 812 D @ 205 PEAK 558 2266 89 % LOAD DECREASE: XENON PEAKED - DECREASING 22 MOC i1/26/97 832 SDO PEAK 550 2265 850 CPS 10 !!RS FOLLOWING RX TRIP FROM 100% PWR ECC: 703 PPM @ 47 STEPS ON D 23 MOC 11/25/97 800 D@170 PEAK 553 2264 52 % 611RS FOLLOWING LOAD REDUCTION FROM 100%

POWER 24 BOC 11/25/97 1445 D @ 207 DEC 556 2264 77 % LOAD INCREASE FROM 50%

25 MOC 11/25/97 834 D @ 193 INC 555 2264 70 % LOAD DECREASE 26 7BC 12/22/97 1853 D @ 47 NONE 546 2264 1.0E-8 POSITIVE ITC, STARTUP IN PROGRESS Time In Core Life 7BC BOC MOC EOC CDC MWD / MTU 0 1,000 10,000 18,000 20,470 L.- _ __

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1998 APPENDIX 3 Certification Review Panel Members The Certification Review Panel makeup is spelled out in Simulator Procedure #20. This panel consists of the Superintendent, Technical Training / Simulator Engineering, one member from the Plant Operations group, one member from the Operations Training group and one member from the Simulator Support group. The current membership and their qualifications follow:

1 Superintendent, Simulator Engineering - Donald C. Fricke  ;

Educational

Background:

Bachelor of Science in Chemical Engineering University ofNorth Dakota,1977 Experience: Eight years as a Quality Engineer at the Prairie Island Nuclear Plant j Three years as the Superintendent Materials Engineering l Three years as the Project Manager, Strategic Information System l i

One year as the Senior Nuclear Consultant, Primergy Merger Team Two years as the Superintendent Technical Training / Simulator Engineering ;

I Certifications: Prairie Island Senior Reactor License 6/12/86 (Changed to SRO Certification in 1987) j PE License MN 15509 Plant Operations - Mark Johnson, transfer from Plant Equipment Operator to Instructor Educational

Background:

High School Diploma Experience: 19 years at Prairie Island in operations as a union operator.

One year as Technical Instructor - Operations Training Certifications: Prairie Island Reactor Operator License 1988 Prairie Island Senior Reactor Operator License 1995.

Operations Training - Jim Lash, Senior Technical Instructor - Operations Training Educational

Background:

Bachelor of Science - Corporate Training Idaho State University - 1993 Experier.a: 6.5 years as PINGP Operations Instructor 3 years simulator instructor DOE Test Reactor 2 years simulator instructor General Electric 8.5 years US Navy Nuclear Power Certifications: NSP Training Specialist Certification Prairie Island Senior Reactor Operator License 1994 Page1 i

r . .

1 PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1998 APPENDIX 3 l Simulator Support Group - Michael Gardzinski, Senior Technical Instructor

! Educational

Background:

High School Diploma Two years post secondary education Experience: Thirty two years nuclear plant experience i

Nine and one half years US Navy Nuclear Plant Operator / Instructor One and one half years Nuclear Plant Chemistry Tech - D C Cook Plant Five years WPPSS NuclearInstructor l Fifteen years instructor at Prairie Island Certifications: NSP Advanced Instructor Certification (allowed to lapse 1/93)

Prairie Island Senior Reactor Operator License (Changed to SRO Certification in 1/1992) i Page 2 ;

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I PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT

1998 i Appendix 4 Table 4A l MALFUNCTION

SUMMARY

- 1995 TESTING f i

TEST TITLE TESTDATE APPROVAL ,

DATE j CC0I - Component Cooling Water Pump Trip 5/5/95 3/14/96 l i'

CC02 Component Cooling Pump Fails To Start Automatically 5/5/95 3/14/96 CC04- CCW Supply Valve To RCP Fails Closed 5/5/95 3/14/96-  !

CCG5 CCW System Piping Rupture 3fg/96 3/29/96 i

CC06 CCW Valve Failure To Open To RHR Heat Exchanger 3n/96 3/14/96 Automatically - l CC08 Component Cooling Surge Tank Auto Makeup Failure 5/8/95 2/22/96 CC09 Seal Water lleat Exchanger Leak 3D/96 3/29/96 C1101 Containment Pressure Transmitter Failure 3fg7/95 11/29/95

)

Cll300 Containment Hi and Ili-lii Pressure Actuation Setpoints 3/14/95 11/29/95 CR01 Fuel Cladding Failure -

11/8/95 11/29/95 CR03 Reactor Coolant System CRUD Burst 3/6/96 3/14/96 CS01 Containment Spray Pump Trip 3/17/95 11/29/95 CS02 - Caustic Addition Valve Failure to Open in Automatic 3/17/95 11/29/95 CS03 Containment Spray Pump Fails to Start Automatically 3/17/95 11/29/95 CWO2 Cirettlating Water Pump Trip 3/20/95 11/29/95 CWO3 Circulating Water Pump Bearing Failure 3/22/95 11/29/95 CWO4 Condenser Tubes Plugged 11/29/95 4/19/95 CWO5 Condenser Tube Rupture 4/28/95 3/14/96 CWO6 Traveling Screen Blockage On Approach Canal 4/28/95 3/14/96 CWO7. . Condenser Pit Flood 3/8/96 3/29/96 MS01 ' Main Steam Line Rupture Inside Containment 12/5/95 2/2/96 MS02 Main Steam Line Rupture Outside Containment Upstream Of 12/5/95 2/2/96 MSIV MS03 - Main Steam Line Rupture Outside ContPment Downstream 11/20/95 2/2/96 Of MSIV -

MS04 . Main Steam Line Leak 11/20/95 1/25/96 MS05 - Main Steam Safety Valve Sticks Open 11/15/95 2/2/96 MS06 Gland Steam Regulation Valve Failure 12/13/95 1/25/96 MS08 Moisture Seperator - Reheater Relicf Valve Failure 10/18/95 2/22/96 l

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. . 1 PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1998 i Appendix 4 Table 4A MSO9 Main Steam Line Leak inside Containment 10/23/95 1/25/96 I MS10 Main Steam Line Break Outside Containment 11/22/95 2/2/96 MSI1 Steam Dump Valve Failsin Position i1/15/95 2/2/96 MS200 1B Main Steam Level Transmitter 10/22/95 11/29/95 I r

MS201 2B Main Steam Level Transmitter 10/22/95 11/29/95 MS202 1 A Main Steam Level Transmitter 10/22/95 11/29/95 MS203  :

2A Main Steam Level Transmitter 10/22/95 11/29/95 MS300 11/12 Steam Generator Safety Valve Setpoints 10/22/95 2/2/96 RC01 ' Reactor Coolant Pump Trip 9/28/95 3/14/96 RC02 Reactor Coolant Pump Locked Rotor 9/28/95 3/29/96 l t

RC04 - Reactor Coolant Pump Shaft Shear 9/28/95 3/14/96 r RCOS Reactor Coolant Pump Bearing Failure 12/13/95 3/29/96 l RC06 Loss Of Coolant Accident - Hot Leg 12/11/95 2/9/96 RC07 Loss Of Coolant Accident - Cold Leg RCP Suction 12/11/95 3/29/96  !

g RC08 Loss Of Coolant Accident - Cold Leg RCP Discharge 10/14/95 2/22/96 RC09 Loss of Coolant Accident - Pressurizer Steam Space 11/12/95 2/9/96 RCIO Loss of Coolant Accident - Pressurizer Water Space 2/14/96 2/22/96 RC11 Loss Of Coolant Accident - RTD Bypass Loop Cold Leg 12/7/95 3/14/96 Manifold RCl2 - Loss Of Coolant Accident - RTD Bypass Loop Return Retum 10/15/95 3/14/96 Leg Piping RCl3 Loss Of Coolant Accident - Reactor Head Vent 10/15/95 2/9/96 RCl4 Reactor Coolant System Leaks 12/20/95 3/29/96 RCIS Reactor Coolant System Leaks 10/16/95 2/9/96

RC16 Pressurizer Power Operated Relief Valve Fails Closed 2/12/96 2/22/96 RCl8 Pressurizer Safety Valve RC-10-1 Fails Open 2/8/96 2/22/96 RC19 Pressurizer Safety Valve Seat Leaks 12/14/95 1/25/96 RC20 Reactor Coolant Pump Oil Leak - Upper Reservoir 1/8/96 1/25/96 P.C21 Reactor Vessel 0-Ring Leakage 12/16/95 1/25/96

. RC22 Pressurizer Power Operated Relief Valve Leakage 12/16/95 1/25/96 RC24 Pressurizer Spray Valve Fails in Position 1/8/96 1/25/96 RD01 Controlling Pod Bank Fails To Move in Manual 10/9/95 1/25/96 4

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PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT

, 1998 Appendix 4 Table 4A RD02 Controlling Rod Bank Fails To Move in Automatic 10/9/95 1/25/96

'RD03 Continuous Rod Withdrawal Of Controlling Bank 10/9/95 2/9/96 RD04 Uncontrolled Continuous Rod Insertion Of Controlling Bank 10/9/95 1/25/96 RDOS ControlRod Misalignment 3/8/96 3/29/96 RD06 Stuck Rod 3/8/96 3/29/96 RD07 Dropped Rod 12/17/95 2/9/96 RD08 Control Rod G-3 Ejected 12/18/95 2/9/96 i RD09. Rod Position Indication Fails 3/8/95 3/29/96 l RDIO Incorrect Rod Speed 10/23/s5 3/29/96 RH01 Residuallieat RemovalPump Trip 10/10/95 2/9/96 R1102 Residual lleat Removal Pump Fails To Start Automatically 10/10/95 2/9/96 RH03_ RHR lleat Exchanger End Bell Leakage 10/10/95 2/22/96 RH04 RHR 11 eat Exchanger Bypass Valve Fails Open 12/18/95 1/25/96 RiiOS . Rif R Heat Exchanger Bypass Valve Fails Closed 1/8/96 2/9/96 RH06 Recirculation Sump Suction Lines Blocked 1/3/96 2/9/96 RH07 RHR System Leakage 10/12/95 2/9/96 R1108' RilR Pump Seal Failure 1/4/95 2/9/96 I RH09 Residual Heat Removal Relief Valve Failure 2/14/95 2/22/96 RH200 RH Flow Transmitter 23060 10/22/95 2/9/96 SG01 Steam Generator Tube Leak 10/22/95 2/9/96 SG02 Steam Generator Tube Rupture 10/13/95 3/29/96 SG03 Steam Generator Blowdown Control Valve Fails Open 10/22/95 2/9/96 l

ALSO:

CLO4 Diesel Cooling Water Pump Trip 3/17/95 11/29/95 l-CLO6 Safeguards Cooling Water Supply Piping Rupture 2/1/96 2/22/96 CLO7 Codng Water System Turbine Building Pipe Ruture 2/1/96 2/22/96 CLO8 Cooling Water Leak inside Containment 4/21/95 3/14/96 i ED03 Loss Of Power To CT Transformers 5/9/95 2/22/96 FWl9 -

Feedwater System Rupture inside Containment 2/15/96 2/22/96 t

FW20 Feedwater System Leakage Inside Containment 10/24/95 2/2/96 1

FW21.~ Feedwater System Rupture Inside Contairment 11/28/95 2/2/96 i

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PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1998 Appendix 4 Table 4A 1995 ANNUAL TEST

SUMMARY

~ TEST Ti1LE TEST DATE APPROVAL DATE 1.1 100% POWER STEADY STATE 2/29/96 3/14/96  ;

1.2 75% POWER STEADY STATE 3/18/96 3/29/96 1.3 25% POWER STEADY STATE 3/16/96 3/29/96 2.1.1 UNIT STARTUP 6/25/95 4/8/96 2.1.2 UNIT SliUTDOWN 10/25/95 4/8/96 2.1.3 REACTOR TRIP WITH RECOVERY 2/26/96 3/14/96 2.1.4 CORE PERFORMANCE 3/27/96 3/29/96 2.1.5 OPERATOR SURVEILANCE 12/18/95 3/14/96 2.2.1 MANUAL REACTOR TRIP 12/4/95 2/2/96 2.2.2 TRIP OF ALL FEEDWATER PUMPS I1/28/95 1/25/96 2.2.3 CLOSURE OF MSIV'S 12/4/95 2/2/96 2.2.4 TRIP OF ALL RCP'S 11/29/95 3/29/96 2.2.5 TRIP OF ONE RCP 11/2995 1/25/96 2.2.6 MAIN 'IURF,1NE TRtP 2/18,96 3/14/96 2.2.7 MAX MUM RATL POWER RAMP 11/29/95 2/2/96 2.2.8 MAXIMUM LOCA WITH LOOP 11/29/95 2/2/96 2.2.9 MAXIMUM STEAM BREAK I1/29/95 1/25/96 2.2.10 SBLOCA THRU PORV/NO S1 PUMPS 11/29/95 1/25/96 2.2.11 LOSS OF LOAD 2/21/96 3/14/96 3.1 COMPUTER REAL TIME 3/7/96 3/29/96 l

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PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1998 Appendix 4 Table 4B MALFUNCTION

SUMMARY

- 1996 TESTING  ;

TEST TITLE TEST DATE APPROVAL DATE CLO1 COOLING WATER PUMP TRIP 9/20/96 1/14/97 CLO2 DIESEL COOLING WATER PUMP FAILS TO START 9/20/96 1/14/97 AUTOMATICALLY CLO3 121 COOLING WATER PUMP FAILS TO START 9/20/96 1/14/97 AUTOMATICALLY CLO4 DIESEL COOLING WATER PUMP TRIP 9/20/96 1/14/97 CLO6 SAFEGUARDS COOLING WATER SUPPLY PIPING 10G1/96 1/24/97 RUPTURE CLO7 COOLING WATER SYSTEM TURBINE BUILDING 10/31/96 1/24/97 PIPE RUPTURE CLOS COOLING WATER LEAK INSIDE CONTAINMENT 10S 1/96 1/24/97 DGO1 LOSS OF EMERGENCY DIESEL GENERATOR 10/3/96 1/14/97 DG02 EMERGENCY DIESEL GENERATOR FAILS TO 10/3/96 1/14/97 START DG03 EMERGENCY DIESEL GENERATOR LOAD LIMIT 10/30/96 1/24/97 FAILURE DG04 EMERGENCY DIESEL GENERATOR OUTPUT 10/3/96 1/14/97 BREAKER FAILS OPEN DG05 ELECTRONIC GOVERNOR FAILURE 10/3/96 1/14/97 1 DG06 24VDC SPLY FOR ELECTRONIC GOVERNOR FAILS 10/3/96 1/14/97 DG07 DIESEL GENERATOR EMERGENCY START FAILURE 10/3/96 1/14/97 ED01 LOSS OF OFFSITE POWER 9/19/96 1/14/97 I ED02 1R TRANSFORMER BREAKER FAILS TO CLOSE 9/26/96 1/14/97 ED03 LOSS OF OFFSITE POWER 10/3/96 1/14/97 ED04 FAULT IN UNIT I M TRANSFORMER - AUTO 09/18/96 1/14/97 TRANSFER ED05 FAULT IN UNIT 1 M TRANSFORMER - DELAYED 09/18/96 1/14/97 l AUTO TRANSFER ED06 FAULT IN UNIT SUBSTATION TRANSFORMER 09/18/96 1/14/97 ED07 LOSS OF 125 VDC BUS 9/18/96 1/14/97 ED08 LOSS OF 120 VAC INSTRUMENT BUS 9/26/96 1/14/97 ED09 LOSS OF 4160V BUS 9/20/96 1/14/97 ED10 LOSS OF 480 VAC BUS 9/19/96 1/14/97 EDI1 BUS 15 LOAD REJECTION-RESTORATION Malfunction Deleted SEQUENCE TIMER FAILURE ED12 BUS 16 LOAD REJECTION-RESTORATION 10/4/96 1/14/97 SEQUENCE TIMER FAILURE Page1

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PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1998 l

Appendix 4 Table 4B ED13 VOLTAGE RESTORING SCliEME SEQUENCER 10/4/96 1/14/97 FAILURE EDl4 LOSS OF ALL AC 9/27/96 1/14/97 ED15 DEGRADED GRID VOLTAGE 9/27/96 1/14/97 -

ED16 DEGRADED GRID FREQUENCY 10/29/96 1/14/97 ED17 FAILURE OF $2Z LOAD SEQUENCER RELAY 10/4/96 1/24/~,7 ED18 FAULT IN 1R TRANSFORMER 9/19/96 1/14/97 EG01 GENERATOR OUTPUT BREAKER FAILS TO OPEN 10/30/96 1/14/97 FOLLOWING TURBINE TRIP j EG02 LOSS OF GENERATOR liYDROGEN COOLING jfyj97 gfy4f97 j EG03 LOSS OF OFFSITE POWER 10/30/96 t/24/97 EG05 GENERATOR VOLTAGE REGULATOR FAILURE 10/30/96 1/24/97 l

EG06 GENERATOR FAULT 10/30/96 1/24/97 EG07 GENERATOR LOSS OF EXCITATION 9/27/96 1/14!97 EG200 EG TEMP TRANSMITTER 9/27/96 1/14/97 IA01 LOSS OF SERVICE AIR HEADER 10/31/96 1/24/97 IA02 LOSS OF INSTRUMENT AIR llEADER 10/31/96 2/4/97 1A03 LO3S OF AIR COMPRESSOR 10/18/96 1/14/97 RM01 RADIATION MONITOR MISCALIBRATION 9/16/96 1/14/97  !

RP01 REACTOR TRIP 10/16/96 1/14/97 RP02 FAILURE OF AUTOMATIC REACTOR TRIPS 10/18/96 1/14/97 RP03 FAILURE OF SAFETY SYSTEMS TO ACTUATE 10/16/96 1/14/97 RP04 INADVERTENT ACTUATION OF THE SAFETY 10/18/96 1/17/97 INJECTION SYSTEM  ;

RP05 FAILURE OF CONTAINMENT ISOLATION PHASE A 10/18/96 1/17/97 TO ACTUATE ,

RP06 FAILURE OF MSIV'S TO ISOLATE 10/18/96 1/17/97 RP07 MECHANICAL FAILURE OF REACTOR TRIP 10/22/96 1/17/97 BREAKERS RP08 FAILURE OF SAFEGUARDS ACTUATION 10/18/96 1/17/97 RP300 / P-7 TURB PRESS / TURBINE IST STAGE PRESSURE 10/25/96 1/17/97 RX226 RP302 AUTO ROD WITHDRAWAL BLOCK P-2 10/25/96 1/17/97 RP303 BUS 11/12 UV TRIP 10/31/96 1/24/97 l RP305 BUS 11/12 UF TRIP 11/31/96 1/17/97 Page 2

I es PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1998 Appendix 4 Table 4B l

RP307 / RC LOW FLOW TRIP / REACTOR COOLANT PUMP 10/31/96 1/24/97 i RC03 SilAFT SHEAR l RP313 / PRZR LO PRESS TRIP / SI 10/31/96 1/24/97 RP320 RP317 / PZR 111 PRESS TRIP / PRESSURIZER SAFETIES 10/25/96 1/24/97 RC300 RP323 PRZR HI LVL TIUP 10/31/96 1/24/97

^

RP326 SG LOLO LVL TRIP 11/1/96 1/24/97 RP340 / LOLO TAVG STM LN ISOL /Ill STM FLOW 11/1/96 1/24/97 RP344 RP348 SG Hi-lil STM FLOW 10/31/96 1/24/97 RP352 SG LOLO STM PRESS SI 11/1/96 1/24/97 TC01 TURBSE STOP VALVE FAILS TO CLOSE WiiEN

' 10/23/96 1/17/97 REQUIRED TCO2 TURBINE STOP VALVE FAILS CLOSED 10/23/96 1/17/97 TCO3 TURBINE CONTROL SYSTEM CYCLING OUTPUT 10/25/96 1/24/97 TC04 TURBINE CONTROL VALVE FAILS OPEN 1025/96 2/4/97 TC05 TURBINE CONTROL VALVE FAILS CLOSED 10/23/96 1/17/97 TC06 REACTOR PROTECTION SYSTEM FAILS TO TRIP 10/23/96 1/17/97 TURBINE TC07 TUREINE CONTROL INTERCEPT VALVE 10/23/96 1/17/97 TC08 TURBidE CONTROL FAILURE DURING TURBINE 10/25/96 1/17/97 ROLL TC09 TURBINE CONTROL FAILURE CAUSING TURBINE 10/25/96 1/17/97 RUNBACK l TC10 TURBINE CONTROL FAILURE CAUSING AN 10/25/96 1/17/97 I INCREASE IN POWER WITilOUT DEMAND TCI1 COMPLETE TURBINE TRIP FAlLURE 10/23/96 1/17/97  !

TC12 TURBINE TRIP 10/25/96 I 1/17/97 TCl3 ELECTRICAL llYDRAULIC CONTROL PUMP TRIP 10/23/96 1/17/97 TCl4 TURBINE CONTROL VALVE FAILS IN POSITION 10/25/96 1/17/97 TC300 INIT TURB CV POS 10/25/96 1/17/97 TUDI LOSS OF TURBINE LUBE OIL SUPPLY 10/23/96 1/17/97 l

TUO2 TURBINE GENERATOR VfBRATION 10/25/96 1/17/97 4 l

l Light LevelMeasurements 1/14/97 2/4/97 Sound Level Measurements 1/15/97 1/24/97 I

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(n 1 PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT -

i 1998. 5 Appendix 4 - Table 4B l 1996 ANNUALTEST

SUMMARY

l- TEST TITLE TEST DATE APPROVAL l DATE 1.1 100% POWER STEADY STATE 11/08/96 2/4/97 1.2 75% POWER STEADY STATE I1/8/96 2/4/97 l 13 25% POWER STEADY STATE 11/8/96- 2/4/97 2.1.1 ' UNIT STARTUP I/9/97 -- 2/4S7 -

2.1.2 UNIT SHUTDOWN 10/3/96 2/4/97

! 2.13 REACTOR TRIP WITH RECOVERY I10/96 2/4/97 2.1.4 - CORE PERFORMANCE - 12/9/96 2/4/97 2.1.5. OPERATOR SURVEILANCE 10/3/96 2/4/97 j 2.2.1 MANUAL REACTOR TRIP 11/5/96 1/24/97 1

22.2 TRIP OF ALL FEEDWATER PUMPS 12/17/96 1/24/97 2.23 CLOSURE OF MSIV'S 11/5/96 2/4/97 2.2.4 -- TRIP OF ALL RCP'S 11/5/96 2/4/97 l 2.2.5 TRIP OF ONE RCP 11/5/96 2/4/97

.=

22.6- MAIN TURBINE TRIP 11n/96 2/4/97 2.2.7 MAXIMUM RATE POWER RAMP 1In/96 2/4/97 2.2.8- MAXIMUM LOCA WITH LOOP 11/6/96 2/4/97 2.2.9 MAXIMUM STEAM BREAK 11/25/96 2/4/97  !

2.2.10- SBLOCA THRU PORV/NO SI PUMPS 11/6/96 2/4/97 2.2.11 LOAD REJECTION FROM i00% POWER 11/6/96 2/4/97 3.1 COMPUTER REAL TIME 1/6/97 1/24/97 i.

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se PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1998 Appendix 4 Table 4C MALFUNCTION

SUMMARY

- 1997 TESTING TEST TITLE TEST DATE APPROVAL DATE AN01 NSSS ANNUNCIATOR SYSTEM FAILURE 4/8/97 8/26/97

~

NIO1 INCORRECT SOURCE RANGE CilANNEL RESPONSE 4/8/97 8/26/97

~

N102 SOURCE RANGE CHANNEL SPIKES 4/8/97 8/26/97

~

N103 INTERMEDIATE RANGE CHANNEL IMPROPER 4/8/97 8/26/97

RESPONSE

N104 INTERMEDIATE RANGE CHANNEL IMPROPER 4/8/97 8/26/97 COMPENSATION N105 IMPROPER POWER CHANNEL RESPONSE 4/8/97 8/26/97 N106 POWER RANGE UPPER CHANNEL IMPROPER 4/8/97 9/26/97

RESPONSE

N107 POWER RANGE LOWER CHANNELIMPROPER 4/9/97 9/26/97

RESPONSE

N1300 1R PWR ABOVE P-6 4/21/97 8/26/97 N1302 1R PWR ABOVE P-8 4/8/97 8/26/97 N1306 IR PWR ABOVE P-9 4/9/97 8/26/97 N1310- IR PWR ABOVE P-10 4/11/97 9/26/97 N1316 IR 111 FLUX TRIP 4/23/97 9/26/97 N1318 FIELO RNG 111 FLUX TRIP 4/11/97 9/26/97 N1322 PR HI RNG HI FLUX TRIP / POS RATE TRIP / 4/11/97 9/26/97 NEG RATE TRIP PC01 ERCS CPU FAILURE 10/3/97 11/13/97 PC03 ERCS ALARM DISPLAY FAILURE 10/5/97 11/13/97 PC04 ERCS SAS DISPLAY FAILURE 10/3/97 11/13/97 PC05 ERCS CONTROL ROOM PRINTER FAILURE 10/29/97 11/13/97 RX01 PRESSURIZER SPRAY VALVE FAILS OPEN 5/6/97 9/26/97 RX02 PRESSURIZER SPRAY VALVES PCV-431 A & B FAIL 5/6/97 9/26/97 CLOSED RX03 PRESSURIZER HEATERS Fall ON 5/6/97 9/26/97 RX04 PRESSURIZER HEATERS Fall OFF(ALL) 5/6/97 9/26/97 RX05 REACTOR COOLANT LOOP TH TRANSMITTER 5/6/97 10/20/97 FAILS HIGli Page1 l

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PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1998 Appendix 4 . Table 4C RX06 REACTOR COOLANT LOOP TH TRANSMITTER 5/6/97 10/20/97 FAILS LOW RXO7 REACTOR COOLANT TC TRANSMITTER FAILS 5/6/97 10/20/97' lilGH -

RX08 REACTOR COOLANT LOOP TC TRANSMITTER 5/6/97 10/20/97 FAILS LOW RXO9 REACTOR COOLANT SYSTEM WIDE RANGE 12/31/97 1/27/98 3

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PRESSURE TRANSMITTER FAILS lilGH RX10 REACTOR COOLANT SYSTEM WIDE RANGE -

10/29/97 1/27/98

• ~~

PRESSURE TRANSMITTER FA!LS LOW RX11 FEEDWATER CONTROLLER OUTPUT FAILURE 10/28/97 11/13/97 RX12 TURBINE FIRST STAGE PRESSURE TRANSMITTER 10/20/97 11/13/97

' FAILS HIGH RX 13 - TURBINE FIRST STAGE PRESSURE TRANSMITTER 10/20/97 11/13/97 FAILS LOW RX14 STEAM GENERATOR FEEDWATER CONTROL 10/20/97 11'13/97 SYSTEM FAILS TO MANUAL RXIS ADFCS MAIN FLOW CONTROL VALVE OUTPUT 10/20/97 11/13/97 CARD FAILURE RX16 ADFCS BYPASS FLOW CONTROL VALVE OUTPUT 10/20/97 11/13/97 CARD FAILURE RX200 RCS PRESSURE TRANSMllTER PT429

$/6/97 10/20/97

!- RX201. RCS PRESSURE TRANSMITTER PT430 4

5/E97 10/20/97 RX202 RCS PRESSURE TRANSMITTER PT431 5/6/97 10/20/97 RX203 RCS PRESSURE TRANSMllTER PT449 5/6/97 10/20/97 RX204 PRZR LVL TRANSMITTER LT426 4 10/28/97 1/27/98' f

RX205 PRZR LVL TRANSMITTER LT427 10/27/97 11/13/97 RX206 PRZR LVL TRANSMllTER LT428 10/24/97 11/13/97 RX207 FW FLOW TRANSMITTER FT466 10/24/97 11/13/97 RX208 FW FLOW TRANSMITTER FT467 10/24/97 11/13/97 '

i RX209 FW FLOW TRANSMITTER FT495 10/28/97 1/27/98 RX210 FW FLOW TRANSMITTER FT476 1/27/98 10/28/97 RX211 - FW FLOW TRANSMITTER FT477 10/23/97 11/13/97 RX212 FW FLOW TRANSMITTER FT497 10/20/97 11/13/97 RX213 11 MS PRESSURE TRANSMITTER PT468 12/8/97 1/27/98 i RX214 11 MS PRESSURE TRANSMITTER PT469 12/8/97 1/27/98 RX215 11 MS PRESSURE TRANSMITTER PT482 12/8/97 1/27/98 RX216 12 MS PRESSURE TRANSMITTER PT478 9/25/97 10/20/97 RX217 12 MS PRESSURE TRANSMllTER PT479 9/25/97 10/20/97 Page 2

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PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT

-1998 Appendix 4 Table 4C L

RX218 12 MS PRESSUPI TRANSMITTER PT483 12/8/97 1/27/98 RX219 11 MS FLOW TRANSMITTER FT464 10/98 1/27/98 RX220 11 MS FLOW TRANSMITTER FT465  !

in/98 1/27/98 RX221 12 MS FLOW TRANSMITTER FT474 10/98 1/27/98 RX222 12 MS FLOW TRANSMITTER FT475 10/98 1/27/98 RX223 11 STM FLOW TRANSMITTER IT494 10/98 1/27/98

~

1 RX224 12 STM FLOW TRANSMITTER FT496 10/98 1/27/98  :

RX225 11/12 MS PRESSURE TRANSMITTER PT484 12/9/97 1/27/98 RX227 11 FEED TEMP TRANSMllTER TT498 12/9/97 1/27/98 RX228 12 FEED TEMP TRANSMITTER TT499 12/9/97 1/27/98 RX229 FW llDR PRESSURE TRANSMITTER PT450 12/31/97 1/27/98 RX230 FW IIDR PRESSURE TRANSMITTER PT451 12/31/97 1/27/98 RX231 11 SG WR LEVEL TRANSMITTER LT502 10/98 1/27/98 RX232 12 SG WR LEVEL TRANSMITTER LT503 In/98 1/27/98 RX233 PZR LEVEL 1,0 CAL CONTROL LC428F 9/25/97 10/20/97 I RX234 11 SG LEVEL TkddSMITTER LT461 12/31/97 1/27/98 l

RX235 11 SG LEVEL TRANSMITTER LT462 12/31/97 1/27/98 RX236 11 SG LEVEL TRANSMITTER LT463 12/31/97 1/27/98 RX237 12 SG LEVEL TRANSMITTER LT471 12/31/97 1/27/98 RX238 12 SG LEVEL TRANSMITTER LT472 12/31/97 1/27/98 RX239 12 SG LEVEL TRANSMITTER LT473 '

12/31/97 1/27/98 Ri240 AUCTIONEERED TAVG 12/31/97 1/27/98

~RX300 PRZR PORV SETPOINT 12/29/97 1/27/98 RX302 LOAD REJECT STM DUMP Hl/Ill-HI TAVG 6/19/97 11/13/97 RX305 MASTER PRZR PRESS CONT STPT 6/19/97 10/20/97 i

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.,u, PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1998 Appendix 4 Table 4C ALSO:

FW01 CONDENSATE PUMP TRIP 3/3/97 9/26/97 FW17 FEEDWATERllP11 EATER LEAK 3/3/97 9/26/97 FW18 FEEDWATER LPIIEATER LEAK 1/31/97 9/26/97 FWl9 FEEDWATER SYSTEM RUPTURE INSIDE 8/28/97 9/26/97 CONTAINMENT FW20 FEEDWATER SYSTEM LEAKAGE INSIDE 8/28/97 9G6/97 CONTAINMENT FW28 11 EATER DRAIN PUMP TRIP 3/3/97 9/26/97 FW31 11 EATER DRAIN PUMP FAILS TO MINIMUM (SPEED) 9/5/97 9/26/97 FW36 AUXILIARY FEEDWATER DISCilARGE LINE 9/5/97 9/2997 RUPTURE INSIDE CONTAINMENT FW37 AUXILIARY FEEDWATER DISCilARGE LINE 9/5/97 9/26/97 RUPTURE OUTSIDE CONTAINMENT MS07 MAIN STEAM SAFETY VALVE FAILURE 6/16/97 8/26/97 MSI1 STEAM DUMP VALVE FAILS IN POSITION 8/26/97 9/26/97 RP300/ Cil 2 P-7 TURBINE PRESSURE - MALFUNCTION /IST 10/23/97 11/13/97 STAGE PRESS XMTR(PSIG)- REMOTE Page 4

. . - . - . - . ~ . . . . . . ~ . . - . ~ . - . _ . - . . - . - - . -

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PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT f' 1998 Appendix 4 Table 4C 'l l

1997 ANNUALTEST

SUMMARY

-l i

TEST TITLE TEST DATE APPROVAL  ;

DATE  :

1.1 100% POWER STEADY STATE 10/17/97 2/5/98  !

I 1.2 75% POWER STEADY STATE 11/5/97 2/6/98  !

13 25% POWER STEADY STATE 11/5/97 2/5/98 l 2.1.1 UNIT STARTUP 11/21/97 2/5/98 i

2.1.2 UNIT SHUTDOWN 11/17/97 2/5/98  !

2.13 REACTOR TRIP WITil RECOVERY 10/22/97' 2/5/98 2.1.4 CORE PERFORMANCE 11/11/97 2/5/98 2.1.5 OPERATOR SURVEILLANCE 12/29/97 1/27/98 }

2.2.1 ' MANUAL REACTOR TRIP 9/19/97 11/13/97 ,

i 2.2.2 TRIP OF ALL FEEDWATER PUMPS 8/29/97 2/5/98 2.23 CLOSURE OF MSIV'S 9/19/97' 11/13/97 j 2.2.4 ' TRIP OF ALL RCP'S 9/19/97 11/13/97  !

t 2.2.5 TRIP OF ONE RCP 9/19/97 11/2I/97 li 2.2.6 MAIN 1URBINE TRIP 9/19/97 2/5/98 )

t 2.2.7 - MAX 1 MUM RATE POWER RAMP 9/19/97 11/21/97 j 2.2.8 MAXIMUM LOCA WITH LOOP 9/19/97 11/21/97 l

2.2.9 MAXIMUM STEAM BREAK 9/19/97 2/5/98  !

2.2.10 SBLOCA THRU PORV/NO SI PUMPS 9/19/97 11/21/97 I

2.2.11 LOAD REJECTION FROM l'00% POWER 9/19/97 2/6/98 3.1 COMPUTER REAL TlME ' i1/20/97 - 2/5/98 I

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PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1998 Appendix 4 Table 4D MALFUNCTION

SUMMARY

- 1998 TESTING TEST TITLE TEST DATE APPROVAL DATE FW01 CONDENSATE PUMP TRIP 1/10/99 2/2/99 FWO2 13 COND. PUMP FAILS TO START 1/10/99 2/2/99 ,

FWOS COND. RECIRC VALVE FAILS OPEN 1/10/99 2/2/99 FWO7 CNDSR HW MU VALVE FAILS OPEN 1/10/99 2/2/99 FW25 FDWTR FLOW CV FAILS TO CLOSE 1/16/99 2/2/99 FW28 HTR DRN puled TRIP 1/16/99 2/2/99 FW32 AFW PUMP TRIP - MOTOR I/10S9 2/2/99 FW33 AFW PUMP TRIP- TURBINE 1/10/99 2/2/99 FW34 nFW PUMP FAILS TO START AUTO 1/10/99 2/2/99 FW38 AFW FLOW MV FAILS IN POSITION 1/15/99 2/2/99 FW201 CDSR11W XTMR 1/10/99 2/2/99 S101 BOT 11 BA TNK VLVS FAIL TO OPEN 1/10/99 2/2/99 S102 LOOP A COLD LEG INJECTION CHECK VALVE FAILURE 1/16/99 2/2/99 S103 BA TANV. VALVE FAILS TO CLOSE ON LOW LOW LEVEL 1/16/99 2/2/99 IN THE. . . :.LECTED BAT IN AUTO '

S104 S1 PUMP TRIP 1/10/99 2/2/99 S105 SAFETY INJECTION PUMP FAILS TO START 1/16/99 2/2/99 AUTOMATICALLY S106 l SI ACCUMULATOR LEAKAGE 1/16/99 2/2/99 S107 SI ACCUMULATOR CHECK VALVE LEAKAGE 1/16/99 2/2/99 S108 SI ACCIIMULATOR RELIEF VALVE LEAKAGE 1/16/99 2/2/99 S109 SI COLD LEG INJECTION LINE RUPTURE INSIDE OF TIIE 1/16/99 2/2/99 ANNULUS VC04 CHARGING PUMP TRIP 1/10/99 2J2/99 VC07 LETDOWN HEAT EXCilANGER LEAKAGE TO 1/17/99 2/2/99 ATMOSPHERE VC09 LETDOWN LINE LEAKAGE INSIDE CONTAINMENT 1/17/99 2/2/99 i

, VC10 CilARGING PUMP COMMON DISCll. IIEADER RUPTURE 1/17/99 2/2/99 VCl1 CHARGING LINE LEAKAGE INSIDE CONTAINMENT 1/17/99 2/2/99 VCl4 VOLUME CONTROL TANK RELIEF VALVE FAILURE 1/17/99 2/2/99 VC20 - CCW RETURN FROM LTDWN ilEAT EXCit FAILS CLOSED 1/17/99 2/2/99 Page1

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PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT l 1998 j Appendix 4 Table 4D 1998 ANNUAL TEST

SUMMARY

l TEST TITLE TEST DATE APPROVAL l DATE l l

1.1 100% POWER STEADY STATE 5/13/98 2/4/99 1.2 75% POWER STEADY STATE 1/15/99 2/4/99 l 1.3 25% POWER STEADY STATE 5/13/98 2/4/99 l

2.1.1 UNIT STARTUP 5/l1/98 2/4/99 '

2.1.2 UNIT SilUTDOWN 5/8/98 2/4/99 2.1.3 REACTOR TRIP WITil RECOVERY 5/12/98 2/4/99

)

2.1.4 CORE PERFORMANCE I/12/99 2/4/99 2.1.5 OPERATOR SURVEILLANCE 2/3/99 2/4/99 2.2.1 MANUAL REACTOR TRIP 5/12/98 1/15/99 2.2.2 TRIP OF ALL FEEDWATER PUMPS 5/29/98 1/15/99 2.2.3 CLOSURE OF MSIV'S 5/6/98 1/15/99 2.2.4 TRIP OF ALL RCP'S 5/6/98 1/15/99 2.2.5 TRIP OF ONE RCP 5/6/98 1/15/99 2.2.6 MAIN TURBINE TRIP 1/13/99 2/4/99 2.2.7 MAXIMUM RATE POWER RAMP 1/27/99 2/2/99 2.2.8 MAXIMUM LOCA WITH LOOP 5/6/98 1/15/99 2.2.9 MAXIMUM STEAM BREAK 1/27/99 2/2/99 2.2.10 SBLOCA TilRU PORV/NO S1 PUMPS 5/6/98 1/15/99 2.2.1 i LOAD REJECTION FROM 100% POWER 5/7/98 1/15/99 3.1 COMPUTER REAL TIME Deferred Deferred l

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PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT j 1998 1 APPENDIX 5  :

ANNUAL OPERABILITY TES11NG ABSTRACT l STEADY STATE TEST- 100% POWER  !

l

Description:

The purpose of this test was to measure certain plant parameters and compare'those I parameters to data measured on the simulator. Prairie Island Simulator data is compared to - 1

both PINGP units. In addition the parameters measured on the simulator are evaluated for  !

stability over a one hour time period.

Date Conducted: 5/13/1998 i CRP Approval Date: 2/4/99

' Initial Conditions: 100% Power, Beginning of Cycle 1 1

Duration oftest: One Hour i

l i

Data Collected: Data was collected for the parameters listed in Table SA using the SATAR l

(Simulator Automated Testing And Reverification) program. Additionally, RCS leakrate, various process computer logs and secondary calorimetric (heat balance) data was collected.

Description of Baseline Data Used: Plant data is collected using the plant process computer archival retrieval functions.

Deficiencies identified: Several parameters differed from the plant values by more than 2%. Most of these parameters are variable based on desired plant modes of operation and vary from day to day (eg. generator vars is adjusted to the desired grid conditions which vary from hour to hour). Some differences were determined to be due to plant maintenance problems (eg.

leaking check valve) which are undesirable to model. All differences were reviewed by the Certification Review Panel and determined to be insignificant to training. 1 1

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PRAIRJE ISLAND SIMULATOR CERTIFICATION REPORT 1998 APPENDIX 5 ,

A'NNUAL OPERABILITY TESTING ABSTRACT [

STEADY STATE TEST- 75% POWER .

t

Description:

The purpose of this test was to measure certain plant parameters and compare those ,

parameters to data measured on the simulator. Prairie Island Simulator data is compared to  ;

both PINGP units. In addition the parameters measured on the simulator are evaluated for l stability over a one hour time period. l I

I Date Conducted: 1/21/1999 CRP Approval Date: 2/4/99 Initial Conditions: 78% Power, Middle of Cycle. Power level is stabilized at approximately 75%

Efforts are mad to match the plant power level for which data is available as closely as  !

possible.

Duration of Test: One Hour Data Collected: Data was collected for the parameters listed in Table SA using the SATAR (Simulator Automated Testing And Reverification) program. Additionally, RCS leakrate, various process computer logs and secondary calorimetric (heat balance) data was collected.

I l

Description of Baseline Data Used: Data is collected using the plant process camputer archival retrieval functions. Data points to be collected were determined from a review of ANS/ ANSI 3.5-1985 and a survey performed by General Physics Corporation.

i Deficiencies Identified: Several parameters differed from the plant values by more than 2%. Most of these parameters are variable based on desired plant modes of operation and vary from day to day (eg. generator vars is adjusted to the desired grid conditions which vary from hour to hour). Some differences were determined to be due to plant maintenance problems (eg.

leaking check valve) which are undesirable to model. All differences were reviewed by the Certification Review Panel and determined to be insignificant to training.

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PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1998 APPENDIX 5 ANNUAL OPERABILITY TESTING ABSTRACT STEADY STATE TEST-25% POWER

Description:

The purpose of this test was to measure certain plant parameters and compare those parameters to data measured on the simulator. Prairie Island Simulator data is compared to both PINGP units. In addition the parameters measured on the simulator are evaluated for stability over a one hour time period.

Date Conducted: 5/13/1998 CRP Approval Date: 2/4/99 Initial Conditions: 20% Power, End of Cycle. Power level is stabilized at approximately 25%.

Efforts are made to match the plant power level for which data is available as closely as possible.

i Duration oftest: One 11our Data Collected: Data was collected for the parameters listed in Table 5A using the SATAR  ;

(Simulator Automated Testing And Reverification) program.

l l

l Description of Baseline Data Used: Data is collected using the plant process computer archival retrieval functions. Data points to be collected were determined from a review of ANS/ ANSI 3.5-1985 and a survey performed by General Physics Corporation.

Deficiencies identified: Several parameters differed from the plant values by more than 2%. Most of these parameters are variable based on desired plant modes ofoperation and vary from day  !

to day (eg. generator vars is adjusted to the desired grid conditions which vary from hour to hour). Some differences were determined to be due to plant maintenance problems (eg.

leaking check valve) which are undesirable to model. All differences were reviewed by the i Certification Review Panel and determined to be insignificant to training. I i

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PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT i 1998 APPENDIX 5 .

ANNUAL OPERABILITY TESTING ABSTRACT TRANSIENT OPERATION TESTING - NORMAL PLANT EVOLUTIONS i UNIT STARTUP

Description:

The purpose of this test is to ensure the PITC Simulator simulates operations from  ;

cold shutdown conditions to 100% power operations. This procedure will use the normal plant operating procedures and surveillances for operating guidance. The simulator is expected to simulate all control board evolutions and some required supporting out plant tasks.

]

l Date Conducted: 5/11/98 l

l CRP Approval Date: 2/4/99 Initial Conditions: Cold Shutdown, Beginning of Cycle.

l 4 Final Conditions: Simulator in stable 100% power conditions.

Data Collected: Controlled procedures were used for all plant evolutions. Completed copies of all procedures used were collected.

Description of Baseline Data Used: Controlled plant procedures are used for all steps of this shutdown. Copies of all completed procedures and urveillances are included as records.

Ability to correctly complete controlled plant procedures and to achieve stable 100% power conditions indicates acceptable simulator performance.

Deficiencies identified During This Testing: None Page 4

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PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT l 1998 )

APPENDIX 5  :

ANNUAL OPERABILITY TESTING ABSTRACT I

TRANSIENT OPERATION TESTING - NORMAL PLANT EVOLUTIONS UNIT SIIUTD0%W

Description:

The pmpose of this test is to ensure the PITC Simulator simulates operations from 100% power operations conditions to cold shutdown conditions. This procedure will use the normal plant operating procedures and surveillances for operating guidance. The simulator is expected to simulate all control board evolutions and some required supporting out plant tasks.

Date Conducted: 5/8/98 CRP Approval Date: 2/4/99 i

. Initial Conditions: 95% Power, End of Life Conditions l

)

Final Conditions: Simulator m stable Cold Shutdown conditions.

Data Collected: Controlled procedures were used for all plant evolutions. Completed copies of all procedures used were collected.

Description of Baseline Data Used: Controlled plant procedures are used for all steps of this shutdown. copies of all completed procedures and surveillances are included as records.

Abilitt to correctly complete controlled plant procedures and to achieve stable cold shutdown condinons indicates acceptable simulator performance.

Deficiencies Identified During This Testing: None l

1 Page 5

l PRAIRIE ISLAND SIMl'LATOR CERTIFICATION REPORT 1998 APPENDIX 5 ANNUAL OPERABILITY TESTING ABSTRACT l

TRANSIENT OPERATION TESTING - NORMAL PLANT EVOLUTIONS REACTOR TRIP WITH RECOVERY

Description:

The purpose of this procedure is to test the response of the Prairie Island Simulator,  !

during the sequence of events of a reactor trip, subsequent restart of the reactor and load I increase to rated power. It is not the intent that other malfunctions be interjected, but to  ;

simulate operations under nomial conditions. Other portions of the testing program will l measure the malfunction abilities of the simulator. This test is designed to meet the l requirements of ANSI 3.5 section 3.1.l(4) " Reactor trip followed by recovery to rated power".

The acceptance criteria of ANSI 3.5 section 4.2.1 Transient operation (b) and (c) is followed.

l i

i Date Conducted: 5/12/98 i i

CRP Approval Date: 2/4/99 j Initial Conditions: 100% Power, Beginning of Cycle Final Conditions: 100% Power with stable plant conditions.

Data Collected: Controlled procedures were used for all plant evolutions. Completed copies of all procedures used were collected.

Description of Baseline Data Used: Controlled plant procedures are used for all steps of this shutdown. Copies of all completed procedures, checklists and surveillances are included as records. Ability to correctly complete controlled plant procedures and to achieve stable 100% ,

power conditions indicates acceptable simulator performance. 1 I

Deficiencies identified During This Testing

None l

l Page 6 l

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PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1998 APPENDIX 5 ANNUAL OPERABILlTY TESTING ABSTRACT i

TRANSIENT OPERATION TESTING - NORMAL PLAN T EVOLUTIONS CORE PERFORMANCE TESTING

Description:

The purpose of this test is to verify that the performance of the Prairie Island Simulator core model matches the plant core performance. This test will measure the plant heat balance (calorimetric), will calculate the shutdown margin at several power levels and will perform Zero Power Physics testing to measure total control rod worth, critical baron concentration and is thermal temperature coefficient at beginning oflife. This test is designed to meet the requirements of ANSI 3.5 section 3.1.1.9 "Nomtal Plant Evolutions". The I acceptance criteria was developed from the plant surveillance test procedures (SP 1005, D30, j D32).

Date Conducted: 1/21/99 j CRP Approval Date: 2/4/99

)

l Initial Conditions: Several for separate pans of the test: i 100% Power Middle of Cycle  !

50% Power Middle ofCycle 20% Power End of Cycle  ;

Hot Shutdown Beginning of Cycle Final Conditions: Measurements completed. I Data Collected: Measurements of Control Rod Worth, Critical Boron Concentration, Isothennal Temperature Coefficient, Shutdown Margin along with Calcrimetric (heat balance) data.

Description of Baseline Data Used: Plant predicted core data and results from low power physics testing during stanup.

1 Deficiencies Identified During This Testing: None Page 7 i

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L :. -

l PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT

~1998 APPENDIX 5 l

l ANNUAL OPERABILITYTESTING ABSTRACT l ' TRANSIENT OPERATION TESTING - NORMAL PLANT EVOLUTIONS OPERATOR SURVEILLANCE TESTS

Description:

The purpose of this test is verify that the PINGP safety-related surveillances are able to be completed an the Prairie Island Simulator. This test is designed to meet the requirements of ANSI 3.5 section 3.1 " Normal Plant Evolutions", subsection 3.1.1.10 " Operator conducted surveillance testing on safety-related equipment or systems. The surveillances tested are .

selected from the PINGP control room lists of surveillances. All surveillances on diis list

< which are completed largely from the Control Room are tested. The criteria for acceptable

. simulator response was the ability to complete the surveillance as outlined in the test procedure, and all control board responses were within the procedure acceptance criteria.

l Date Conducted: 2/3/99 CRP Approval Date: 2/4/99 Initial Conditions: Various depending on the surveillance procedure requirements.

Final Conditions: Completion of the surveillance procedure.

Data Collected: Completed copies of all surveillance procedures determined to be appropriate for use on the simulator.

Description of Baseline Data Used: Controlled copies of the plant surveillance procedures with )

their prescribed acceptance criteria.

1 Deficiencies Identified During This Testing: Two surveillance procedures were found to have i minor problems, Simulator Change Requests were written to investigate and correct the l problems -  !

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P PRAIRIE ISLAND SIMULATOR CER'11FICATION REPORT j L

1998 APPENDIX 5 l

ANNUAL OPERABILITY TESTING ABSTRACT

, TRANSIENT OPERATION TESTING - TRANSIENT TESTS MANUAL REACTOR TRIP

Description:

The purpose of this test is to test the ability of the Prairie Island Simulator to match  ;

PINGP conditions,'during a manual reactor trip. It is not the intent that other malfunctions be i interjected, but to only simulate operations under reactor trip conditions. Other portions of the

- testing program will measure the malfunction ability of the simulator. This test is designed to meet the requirements ofANSI 3.5 Appendix B section B.2.2 - Transient Performance

" Manual reactor trip". The acceptance criteria of ANSI 3.5 Appendix B - B.2.2.1, and 4.2.1 -

Transient operation (b) and (c) is followed.

Date Conducted: 5/12/1998 i

CRP Approval Date: 1/15/1999 l

1

. Initial Conditions: 100% Power, Middle of Cycle Final Conditions: Tave stabilizes at or trends to 547 degrees, NIS source ranges are energized, steam generator narrow range levels are on scale and increasing.

Data Collected: Data was collected for selected parameters from the list in Table SA using the SATAR (Simulator Automated Testing And Reverification) program.

Description of Baseline Data Used: Judgment of the Certification Review Panel. Makeup and qualifications of this panel are identified in Appendix 4 of this report.

Deficiencies Identified During This Testing: None 4

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g .e PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1998 i APPENDIX 5 1

l

' ANNUAL OPERABILITY TESTING ABSTRACT  !

) '

TRANSIENT OPERATION TESTING - TRANSIENT TESTS l

TRIP OF ALL FEEDWATER PUMPS l

Description:

The purpose of this test is to test the ability of the Prairie Island Simulator to match .

PINGP conditions, during a loss of all feedwater event. It is not the intent that other

malfunctions be interjected, but to only simulate operations under loss of feedwater. Other portions of the testing program will measure the malfunction ability of the simulator. This test )

is designed to meet the requirements of ANSI 3.5 Appendix B section B.2.2 - Transient  !

Perfonnance " Simultaneous trip of all feedwater pumps". The acceptance criteria of ANSI 3.5 Appendix B - B2.2.1, and 4.2.1 Transient operation (b) and (c) is followed.

l Date Conducted: 5/29/1998  :

l CRP Approval Date: 1/15/1999 l

' l l

i Initial Conditions: 100% Power End of Cycle i

Final Conditions: RCS pressure reaches the setpoint of the pressurizer power operated relief valves and the pressurizer PORV's lift.

i

! Data Collected: Data was collected for selected parameters from the list in Table 5A using the l 1 SATAR (Simulator Automated Testing And Reverification) program.

! Description of Baseline Data Used: Ju.lgment of the Certification Review Panel. Makeup and qualifications of this panel are identified in Appendix 4 of this report.

Deficiencies' Identified During This Testing: None

Page 10 L

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PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT ,

I 1998 APPENDIX 5 ANNUAL OPERABILITY TESTING ABSTRACT TRANSIENT OPERATION TESTING - TRANSIENT TESTS i

CLOSURE OF MAIN STEAM ISOLATION VALVES

Description:

The purpose of this test is to test the ability of the Prairie Island Simulator to match PINGP conditions, during a inadvertent closure of both main steam isolation valves while at 100% reactor power. It is not the intent that other malfunctions be interjected, but to only simulate operations under MSIV closure conditions. Other portions of the testing program will measure the malfunction ability of the simulator. This test is designed to meet the requirements of ANSI 3.5 Appendix B section B.2.2 - Transient Perfom1ance " Simultaneous closure of all Main Steam Isolation Valves". The acceptance criteria of ANSI 3.5 Appendix B

- B.2.2.1, and 4.2.1 Transient operation (b) and (c) is followed.

Date Conducted: 5/6/1998 CRP Approval . .: 1/15/1999 Initial Conditions. ; 00% Power, Middle of Cycle Final Conditions: RCS Tavg stabilizes at approximately 552 degrees or steam generator pressure PORV's maintain pressure at 1050 psig.

1 Data Collected: Data was collected for selected parameters from the list in Table 5A using the SATAR (Simulator Automated Testing And Reverification) program.

Description of Baseline Data Used: Judgment of the Certification Review Panel. Makeup and qualifications of this panel are identified in Appendix 4 of this report.

1 I

Deficiencies identified During This Testing: None Page 11 L _

PRA!RIE ISLAND SIMULATOR CERTIFICATION REPORT 1998 APPENDIX 5 l

ANNUAL OPERABILITY TESTING ABSTRACT  :

TRANSIENT OPERATION TESTING - TRANSIENT TESTS TRIP OF ALL REACTOR COOLANT PUMPS 1

Description:

The purpose of this test is to test the ability of the Prairie Island Simulator to j approximate PINGP conditions, during a simultaneous trip of both unit # 1 RCP's, which l causes a reactor trip. It i., not the intent that other malfunctions be interjected, but to only l simulate operations under reactor trip conditions. Other portions of the testing program will measure the malfunction ability of the simulator. This test is designed to meet the requirements of ANSI 3.5 Appendix B section B.2.2 -Transient Performance " Simultaneous trip of all reactor coolant pumps " The acceptance criteria of ANSI 3.5 Appendix B - B.2.2.1, and 4.2.1 Transient operation (b) and (c) is followed.

Date Conducted: 5/6/1998 i

CRP Approval Date: 1/15/1999 Initial Conditions: IC-11 (100% Power Middle of Cycle)

Final Conditions: RCS Tave stabilizes at approximately 547 degrees and natural circulation is verified.

Data Collected: Data was collected for selected parameters from the list in Table 5A using the SATAR (Simulator Automated Testing And Reverification) program.

Description of Baseline Data Used: Judgment of the Certification Review Panel. Makeup and qualifications of this panel are identified in Appendix 4 of this report. .

l Deficiencies identified During This Testing: None l

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PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1998 APPENDIX 5 ANNUAL OPERABILITY TESTING ABSTRACT TRANSIENT OPERATION TESTING - TRANSIENT TESTS TRIP OF ANY REACTOR COOLANT PUMP ]

Description:

The purpose of this test is to test the ability of the Prairie Island Simulator to match PINGP conditions, during a trip of 11 RCP, which causes a reactor trip. It is not the intent that )

other malfunctions be interjected, but to only simulate operations under reactor trip conditions. I Other portions of the testing program will measure the malfunction ability of the simulator.

This test is designed to meet the requirements of ANSI 3.5 Appendix B section B.2.2

-Transient Performance " Trip of any single reactor coolant pump". The acceptance criteria of l

ANSI 3.5 Appendix B - B.2.2.1, and 4.2.1 Transient operation (b) and (c) is followed. j Date Conducted: 5/6/1998 CRP Approval Date: 1/15/1999 l

l Initial Conditions: 100% Power Middle of Cycle l

Final Conditions: RCS Tave stabilizes at approximately 547 degrees.

I Data Collected: Data was colle.ted for selected parameters from the list in Table 5A using the SATAR (Simulator Automated Testing And Reverification) program.

Description of Baseline Data Used: Judgment of the Certification Review Panel. Makeup and qualifications of this panel are identified in Appendix 4 of this report.

Deficiencies Identified During This Testing: None l

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PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1998 APPENDIX 5 ANNUAL OPERABILITY TESTING ABSTRACT r TRANSIENT OPERATION TESTING - TRANSIENT TESTS MAIN TURBINE TRIP

Description:

The purpose of this test is to test the ability of the Prairie Island Simulator to approximate PINGP conditions, during a main turbine trip (from maximum power level that does not result in immediate reactor trip). It is not the intent that other malfunctions be interjected, but to only simulate operations under main turbine trip conditions. Other portions l of the testing program will measure the malfunction ability of the simulator. This test is designed to meet the requirements of ANSI 3.5 Appendix B section B.2.2 - Transient Performance " Main turbine trip". The acceptance criteria of ANSI 3.5 Appendix B - B.2.2.1, and 4.2.1 Transient operation (b) and (c) is followed.

Date Conducted: 1/13/98 CRP Approval Date: 2/4/99 Initial Conditions: 5% Power, Beginning of Cycle  !

1 Final Conditions: RCS Tavg stabilizes at approximately 552 degrees.

Data Collected: Data was collected for selected parameters from the list in Table 5A using the SATAR (Simulator Automated Testing And Reverification) program.

Description of Baseline Data Used: Judgment of the Certification Review Panel. Makeup and qualifications of this panel are identified in Appendix 4 of this report.

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Deficiencies Identified During This Testing: None Page 14 t

1 PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1998 APPENDIX 5 ANNUAL OPERABILITY TESTING ABSTRACT TRANSIENT OPERATION TESTING - TRANSIENT TESTS i

MAXIMUM RATE POWER RAMP  ;

Description:

The purpose of this test is to test the ability of the Prairie Island Simulator to match PINGP conditions, during a maximum rate power ramp from 100% power down to approximately 75% power and back to 100% power. It is not the intent that other malfunctions be interjected, but to only simulate operations under maximum rate power ramp conditions.

Other portions of the testing program will measure the malfunction ability of the simulator. ,

This test is designed to meet the requirements of ANSI 3.5 Appendix B section B.2.2 - )

Transient Performance " Maximum rate power ramp". The acceptance criteria of ANSI 3.5 j Appendix B - B.2.2.1, and 4.2.1 Transient operation (b) and (c) is followed.  !

Date Conducted: 1/27/1999 l CRP Approval Date: 2/2/1999 Initial Conditions: 100% Power Middle of Cycle Final Conditions: RCS Tavg, pressurizer pressure and pressurizer level stabilize.

I Data Collected: Data was collected for selected parameters from the list in Table SA using the SATAR (Simulator Automated Testing And Reverification) program.

l l

Description of Baseline Data Used: Judgment of the Certification Review Panel. Makeup and qualifications of this panel are identified in Appendix 4 of this report.

Deficiencies identified During This Testing: None l

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PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1998 I l

1' APPENDIX 5 l

ANNUAL OPERABILITY TESTING ABSTRACT I

' TRANSIENT OPERATION TESTING - TRANSIENT TESTS }

MAXIMUM LOCA WITH LOSS OF OFFSITE POWER l

Description:

The purpose of this test is to test the ability of the Prairie Island Simulator to match i PINGP conditions, during a maximum break LOCA with a loss of offsite power. It is not the I intent that other malfunctions be interjected, but to only simulate operations under these conditions. Other portions of the testing program will measure the other malfunction abilities of the simulator. This test is designed to meet the requirements of ANSI 3.5 Appendix B >

section B.2.2 - Transient Performance " Maximum size reactor coolant system rupture l combined with loss of all offsite power". The acceptance criteria of ANSI 3.5 Appendix B - )

B.2.2.3, and 4.2.1 Transient operation (b) and (c) is followed.

l Date Conducted: 5/6/1998 l

CRP Approval Date: 1/15/1999 Initial Conditions: 100% Power, Middle of Cycle Final Conditions: RCS pressure stabilizes, containment pressure trends down and SI pumps lose suction due to low RWST level.

l Data Collected: Data was collected for selected parameters from the list in Table 5A using the  ;

SATAR (Simulator Automated Testing And Reverification) program. ,

Description of Baseline Data Used: Judgment of the Certification Review Panel. Makeup and l l

qualifications of this panel are identified in Appendix 4 of this report.

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Deficiencies Identified During This Testing: None l Page 16

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PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT ,

1998 l

APPENDIX 5 ANNUAL OPERABILITY TESTING ABSTRACT TRANSIENT OPERATION TESTING - TRANSIENT TESTS i

MAXIMUM STEAM LINE BREAK i

Description:

The purpose of this test is to test the ability of the Prairie Island Simulator to match PINGP conditions, during a maximum steam line break inside containment. It is not the intent ,

that other malfunctions be interjected, but to only simulate opemtions under these conditions. 1 Other portions of the testing program will measure the other malfunction abilities of the i simulator. This test is designed to meet the requirements of ANSI 3.5 Appendix B section i B.2.2 - Transient Performance " Maximum size unisolable main steam line rupture". The acceptance criteria of ANSI 3.5 Appendix B - B.2.2.3, and 4.2.1 Transient operation (b) and (c) is followed.

Date Conducted: 1/27/1999 CRP Approval Date: 2/2/1999 l Initial Conditions: 100% Power, Middle of Cycle l

Final Conditions: RCS pressure recovers, the non-faul.ted steam generator level recovers and containment pressure trends down. l Data Collected: Data was collected for selected parameters from the list in Table SA using the SATAR (Simulator Automated Testing And Reverification) program.

Description of Baseline Data Used: Judgment of the Certification Review Panel. Makeup and qualifications of this panel are identified in Appendix 4 of this report.

Deficiencies Identified During This Testing: Some changes were noted and reviewed. The steam break flow was unstable shortly after the malfunction actuation, a Simulator Change Request has been written to investigate this problem and a letter describing the problem was sent to the simulator operators recommending that the main steam breaks not be used.

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PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT l 1998 APPENDIX 5 ANNUAL OPERABILITY TESTING ABSTRACT I f

TRANSIENT OPERATION TESTING - TRANSIENT TESTS i

SMALL BREAK LOCA TIIROUGH PRESSURIZER PORV WITil NO S1 PUMPS l l

Description:

The purpose of this test is to test the ability of the Prairie Island Simulator to match l PINGP conditions, during a depressurization due to a stuck open PORV along with both SI  :

pumps disabled. It is not the iment that other malfunctions be interjected, but to only simulate operations under these conditions. Other portions of the testing program will measure the other malfunction abilities of the simulator. This test is designed to meet the requirements of i ANSI 3.5 Appendix B section B.2.2 - Transient Performance " Slow primary system  ;

depressurization to saturated conditions using pressurizer reliefor safety valve stuck open.

~

(Inhibit activation of high pressure Emergency Core Cooling Systems)". The acceptance criteria of ANSI 3.5 Appendix B - B.2.2.4, and 4.2.1 Transient operation (b) and (c) is i followed. 1 Date Conducted: 5/6/1998 CRP Approval Date: 1/15/1999 Initial Conditions: 100% Power, Middle of Cycle Final Conditions: RCS pressure reaches saturation conditions as indicated by ICCM and ERCS displays.

Data Collected: Data was collected for selected parameters from the list in Table 5A using the SATAR (Simulator Automated Testing And Reverification) program.

Description of Baseline Data Used: Judgment of the Certification Review Panel. Makeup and qualifications of this panel are identified in Appendix 4 of this report.

Deficiencies Identified During This Testing: None Page 18 1 i

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PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT  !

1998 APPENDIX 5 ANNUAL OPERABILITY TESTING ABSTRACT TRANSIENT OPERATION TESTING - TRANSIENT TESTS i

~ LOAD REJECTION FROM 100% POWER  :

t

Description:

The purpose of this test is to test the ability of the Prairie Island Simulator to match PINGP conditions, during a load rejection from 100% power. It is not the intent that any  ;

malfunctions be interjected, but only to simulate operations under maximum loss ofload conditions. Other portions of the testing program will measure the malfunction ability of the simulator. This test was designed to meet the requirements of 1990 draft of ANSI 3.5 Appendix B section B3.2.1 - Transient Performance " Load rejection from 100% power". The acceptance criteria of 1900 draft of ANSI 3.5 Appendix B - B3.2.2, and 4.1.3.3 Normal Evolutions were followed.

Date Conducted: 5/7/1998 CRP Approval Date: 1/15/1999  ;

I Initial Conditions: 100% Power, Middle of Cycle  !

Final Conditions: RCS Tavg, pressurizer pressure and pressurizer level stabilize.

l Data Collected: Data was collected for selected parameters from the list in Table 5A using the  ;

SATAR (Simulator Automated Testing And Reverification) program. l Description of Baseline Data Used: Judgment of the Certification Review Panel. Makeup and qualifications of this panel are identified in Appendix 3 of this report.

Deficiencies identified During This Testing: None Page 19

l l PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1998 l

APPENDIX 5 ANNUAL OPERABILITY TESTING ABSTRACT COMPUTER REAL TIME TEST

Description:

The purpose of this test is to test the ability of the Prairie Island Simulator to perform in real time. Real time is defined (in ANS 3.5) as "... dynamic perfomiance in the same time base relationships, sequences, durations, rates and accelerations as the dynamic performance of the reference plant." To verify real time perfonnance this test verifies that the four executive programs have spare time in all frames to ensure that all frames have time to complete (and therefore frames never are skipped). This verifies real time performance since all the software assumes that the modules run at their allocated frequency. Additionally, four specific tasks, chosen to ensure that each of the four executive programs are tested, are performed and timed to be compared to plant values for task completion time. Finally a selected list of plant surveillance tests are completed all of which time the performance of some plant equipment.

These surveillance test results are then compared to the plant results to verify agreement.

Date Conducted: Deferred - This test will be conducted on the new simulation platform during Acceptance Test Plan and thereby will demonstrate the OpenSim NT capability to run in real time during 1999 simulation use. This test was conducted in 1995,1996, and 1997 with no deficiencies identified.

Initial Conditions: Various depending on the surveillance test requirements.

Final Conditions: Completion of the computer timing test, selected operations and selected surveillance procedures.

Data Collected: Completed surveillance test procedures, completed computer timing test including calculations of spare time and timed simulator response for selected manipulations.

Description of Baseline Data Used: Minimum of five percent spare time in each computer from the computer timing test, selected operations compared to system design values, surveillance results compared to acceptance criteria provided in the surveillance test procedure.

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PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1998 Appendix 5 Table 5A  !

Simulator Certification Testing Critical Parameter List Datapool Parameter Title Units Variable

'~  !

Loop Flow Loop A  % RCF0400A l Loop B  % RCF0420A Hot Leg Temperature Loop A F RCT450 Loop B F RCT451 Cold Leg Temperature Loop A F RCTCLDA Loop B F RCTCLDB l Average RCS Temperature - Auct Hi F RXTAVGN Steam Flow Loop A #/s MSFMSLA Loop B #/s MSFMSLB Normal Feedwater Flow Loop A #/s FWFFWSGA Loop B #/s FWFFWSGB Aux Feedwater Flow SG A #/s FWFAFSGA l SG B #/s FWFAFSGB l Steam Generator Blowdown Flow SG A gpm SGF0409A j SG B gpm SGF0429A Core Thermal Power watts RCQRXPWR  !

Neutron Flux N41  % NIN0049A  ;

N42  % NIN0050A l N43  % NIN0051A  !

N44  % NIN0052A Source Range Monitor N31 DKCPS NIN0031A N32 DKCPS NIN0032A Intermediate Range Monitor N35 Amps NIN0035A N36 Amps NIN0036A Delta I N41  % NIQPDIA N42  % NIQPDIB N43  % NIQPDIC N44  % NIQPDID ,

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? ,e; PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT I 1998  !

i- Appendix 5 Table SA Simulator Certification Testing Critical Parameter List

.i I

Datapool Parameter Title Units Variable Control Rod Bank Positions l

Shutdown A Steps RDSSDA Shutdown B Steps RDSSDB Control A Steps RDC0100A Control B Steps RDC0101A  !

Control C Steps RDC0102A l' Control D Steps RDC0103A Wide Range RCS Pressure (this parameter is used instead psig RCPI709 of Pressurizer Pressure because of scale limitations) -

Pressurizer Level  % RCLPZR Pressurizer Temperature Liquid F RCT0480A Steam F RCT0481A Pressurizer Surge Line Temperature F RCT0482A

_RVLIS Level Upper Head  % RCLO452A Wide Range  % RCLO454A -  ;

y Dynamic Head  % RCLO456A I Generator Watts MW EGQO340A -!

Vars MVars EGYO346A Voltage -

volts EGV0341A 345 KV Bus 2 Voltage KV EDV0330A q 4160 V Voltage Bus 15 volts EDV0347A

( l Bus 16 volts EDV0348A' I 4160 V Frequency Bus 15 Hz EDFBUS15 l Bus 16 Hz EDFBUS16 480 V Safeguards Bus Voltage Bus 111 volts EDEB111 Bus 112 volts EDEBil2 j Bus 121 volts EDEB121 Bus 122 volts EDEB122 l instrument AC Status Pnl111 Bool ED:B0111 l Pnl112 Bool ED:B0112  !

l Pnl113 Bool ED:B0113 L Pnl114 Bool ED:B0114 l Pnl117 Bool ED:B0117 Pnl118 Bool ED:B0ll8 l 4 .

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' PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1998 Appendix 5 Table SA Simulator Certification Testing Critical Parameter List Datapool Parameter Title Units Variable 125 VDC Voltage Pnl 11 Volts EDEBATI1 Pnl12 volts EDEBAT12 Containment Pressure psig CHP1005A  !

Containment Temperature F CHTCONT 4 Steam Generator Pressure SG A - psia IGPS468 SG B psia RXPS478 Wide Range Steam Generator Level - SG A  % RXLO409A ,

SG B  % RXLO429A Narrow Range Steam Generator Level SG A  % RXLO405A SG B  % RXLO425A Safeguards Actuation Signal Train A - Bool RP:SISA Train B Bool RP:SISB

~~

Pressurizer Relief Valve Status Bool RCY9201D ,

9 Safety injection Flow 11 SIP gpm SIF0922A  !

, 12 SIP gpm SIF0923A I RWST Level  % SILRWSTP Component Cooling Pump Pressure 11 Header psig CCPHDR11 l 12 Header psig CCPHDR12 Cooling Water Header Pressure Loop A psig CLP41504 Loop B psig CLP41505 CVCS Chargmg Flow gpm VCF0128A Boron Concentration ppm RCB Subcooling Margin Train A F RCTSUBCA

, Train B F RCTSUBCB Note that variables are not listed for Steam Generator Temperature or Pressurizer Relief Valve Flow. i These values are not available to the operator and are not easily available on the simulator. For Pressurizer Relief Valve Flow a status point is listed since this is available to the operator. In addition, RCS Wide Range Pressure is listed in place of Pressurizer Pressure. This value is available to the )

operator and is scaled from zero to 2500 psig versus 1700 to 2500 for Pressurizer Pressure. Therefore RCS Wide Range Pressure is more appropriate for transients in which RCS pressure drops below 1700 psig.

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PRAIRIE ISLAND CERTIFICATION REPORT 1998 APPENDIX 6 MALFUNCTIONTESTING ABSTRACT Following is a list of the malfunction tests indicating the date the initial certification testing was completed, the date the testing was completed for the first four year cycle, and the date the testing was completed for the second four year cycle. As was done for the initial certification testing, all tests with discrete options (type D) had all options tested. For those tests with variable severity capabilities (type V, VS - Variable Setpoints or SO - System Overrides) three severities were tested for each discrete option (with a few exceptions where three severities were not reasonable). Generally, the three severities chosen included the minimum and maximum of the available range. The initial conditions for each of these tests were chosen from the available protected IC sets to enable the most appropriate testing. Some tests involved several initial conditions in order to test the range of simulator response. All listed tests were reviewed by the Certification Review Panel listed in Appendix 3 l

Initial Cycle 1 Cycle 2 Test Title Type Approval Approval Approval Number Date Date Date Annunciator System ,

AN01 NSSS ANNUNCIATOR SYSTEM FAILURE D NEW 01/06/94 08/26/97 l AN02 BOP ANNUNCIATOR SYSTEM FAILURE D NEW NEW NEW )

AN03 BOP DISTRIBUTED ANNUNCIATOR PCB D NEW NEW NEW OUTPUT CHIP FAILURE Component Cooling System CC01 COMP COOLING WTR PUMP TRIP D - 03/02/90 12/13/91 03/14/96 CC02 COMPO'NENT COOLING PUMP FAILS TO D 03/12/90 12/13/91 03/14/96 STARTAUTOMATICALLY CC04 COMPONENT COOLING WATER SUPPLY D HOLD 01/31/92 03/14/96 VALVE TO RCP FAILS CLOSED CC05 - COMPONENT COOLING WATER SYSTEM V 06/06/90 10/11/91 03/29/96 PIPING RUPTURE CC06 CCW VALVE FAILURE TO AUTO OPEN TO D 03/03/90 10/11/91 03/14/96 I l

RHR HEAT EXCHANGER ON PUMP START CC08 COMPONENT COOLING SURGE TANK D 05/09/90 05/09/91 02/22/96 AUTO MAKEUP FAILURE l CC09 SEAL WATER HEAT EXCHANGER LEAK V 05/09/90 05/08/91 03/29/96 Containment / HVAC System CH01 CONTAINMENT PRESSURE TRANSMITTER V 03/02/90 10/11/91 11/29/95 FAILURE CH300' CNMT Hl/H1-HI PRESS VS 07/24/90 06/21/91 11/29/95 Ce ung Water System CL01 COOLING WATER PUMP TRIP D 03/02/90 12/13/91 01/14/97 i CLO2- DIESEL COOLING WATER PUMP FAILS TO D 03/02/90 12/13/91 01/14/97 i START AUTOMATICALLY  ;

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t ..e PRAIRIE ISLAND CERTIFICATION REPORT 1998 APPENDIX 6 Initial Cycle l Cycle 2 Test Title Type Approval Approval Approval Number Date Date Date CLO3 121 COOLING WATER RUMP FAILS TO D 03/02/90 10/28/92 01/14/97 START AUTOMATICALLY CLO4 DIESEL COOLING WATER PUMP TRIP D 03/02/90 10/11/91 01/14/97 CLO6 SAFEGUARDS COOLING WATER SUPPLY V FAILED 01/23/92 01/24/97 PIPING RUPTURE CLO7 COOLING WATER SYSTEM TURBINE V 06/06/90 01/17/92 01/24/97 BUILDING PIPE RUPTURE CLO8 COOLING WATER LEAK INSIDE V 06/06/90 05/08/91 01/24/97 CONTAINMENT Reactor Core System CR01 FUEL CLADDING FAILURE V 02/13/91 06/21/91 11/29/95 CR03 REAL FOR COOLANT SYSTEM CRUD V 02/13/91 10/11/91 03/14/96 BURST Containment Spray System CS01 CONTAINMENT SPRAY PUMP TRIP D 03/02/90 10/11/91 11/29/95 CS02 CAUSTIC ADDITION VALVE FAILURE TO D 03/02/90 10/11/91 11/29/95 OPENIN AUTOMATIC CS03 CONTAINMENT SPRAY PUMP FAILS TO D 03/02/90 10/11/91 11/29/95 START AUTOMATICALLY Circulating Water System

- CWO2 CIRCULATING WATTER PUMP TRIP D 01/31/91 10/11/91 11/29/95 CWO3 CIRCULATING WATER PUMP BEARING D 05/09/90 06/21/91 11/29/95 FAILURE CWO4 CONDENSER TUDES PLUGGED V 06/06/90 06/21/91 11/29/95 CWOS CONDENSER TUBE RUPTURE V 06/06/90 12/20/91 03/14/96 CWO6 TRAVELING SCREEN BLOCKAGE V 06/06/90 06/21/91 03/14/96 ONAPPROACH CANAL CWO7 CONDENSER PIT FLOOD V 06/06/90 12/13/91 03/29/96 Emergency Diesel Generator DG01 LOSS OF EMERGENCY DIESEL D 06/06/90 10/28/92 01/14/97 GENERATOR DG02 EMERGENCY DIESEL GENERATOR FAILS D 07/24/90 10/28/92 01/14/97 TO START DG03 EMERGENCY DIESEL GENERATOR LOAD D NEW 12/15/94 01/24/97 LIMIT FAILURE DG04 EMERGENCY DIESEL GENERATOR D 08/20/90 10/28/92 01/14/97 OUTPUT BREAKER FAILS OPEN Page 2 4

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PRAIRIE ISLAND CERTIFICATION REPORT 1998 APPENDIX 6 Initial Cycle 1 Cycle 2 Test Titic Type Approval Approval Ap[$roval Number Date Date Date DG05 ELECTRONIC GOVERNOR FAILURE D NEW 12/15/94 01/14/97 DG06 24VDC SPLY FOR ELECTRONIC D NEW 12/15/94 01/14/97 GOVERNOR FAILS DG07 DIESEL GENERATOR EMERGENCY START D NEW 11/30/94 01/14/97 FAILURE Electrical Distribution System ED01 LOSS OF OFFSITE POWER D 09/25/90 10/28/92 01/14/97 ED02 1R TRANSFORMER BREAKER FAIIR TO D NEW 09/28/94 01/14/97 CLOSE ED03 LOSS OF OFFSITE POWER D 09/25/90 10/28/92 01/14/97 ED04 FAULT IN UNIT 1 M TRANSFORMER - D 09/25/90 06/21/91 01/14/97 AUTO TRANSFER ED05 FAULT IN UNIT 1 M TRANSFORMER - D 09/25/90 05/08/91 01/14/97 DELAYED AUTO TRANSFER ED06 FAULT IN UNIT SUBSTATION D 10/16/90 01/05/93 01/14/97 TRANSFORMER ED07 LOSS OF 125 VDC BUS D 01/21/91 01/23/92 01/14/97 ED08 LOSS OF 120 VAC INSTRUMENT BUS D 01/28/91 12/20/91 01/14/97

-ED09 LOSS OF 4160V BUS D 09/25/90 01/05/93 01/14/97 ED10 LOSS OF 480 VAC BUS D FAILED 10/28/92 01/14/97 ED12 LOAD SEQUENCER REJECTION FAILURE V 10/16/90 10/28/92 01/14/97 ED13 LOAD SEQUENCER RESTORATION D 10/16/90 10/28/92 01/14/97 FAILURE ED14 LOSS OF ALL AC D 10/16/90 12/09/93 01/14/97 ED15 DEGRADED GRID VOLTAGE V FAILED 10/28/92 01/14/97 ED16 DEGRADED GRID FREQUENCY V 10/16/90 10/28/92 01/14/97 ED17 FAILURE OF 52Z LOAD SEQUENCER D NEW 12/15/94 01/24/97 RELAY EDl8 FAULT IN 1R TRANSFORMER D NEW NEW 01/14/97 ED19 FAULT IN CTI1 TRANSFORMER D NEW NEW NEW ED20 FAULTIN CT 12 TRANSFORMER D NEW NEW NEW Electrical Generation System EG01 GENERATOR OUTPUT BREAKER FAILS TO D 06/06/90 12/13/91 01/14/97 OPEN FOLLOWING TURBINE TRIP EG02 ~ LOSS OF GENERATORIIYDROGEN D 07/24/90 10/11/91 01/24/97 COOLING EG03 LOSS OF OFFSITE POWER D 08/20/90 10/11/91 01/24/97 Page 3

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h" l PRAIRIE ISLAND CERTIFICATION REPORT ';

1998 '

i APPENDIX 6  ;

i Initial . Cycle 1 Cycle 2 l Test Title - Type Approval Approval Approval {

l Number - Date Date Date l

)

EG04 GENERATOR VOLTAGE REGULATOR V NEW NEW NEW  !

EG05 GENERATOR VOLTAGE REGULATOR V HOLD 01/23/92- 01/24/97  :

FAILURE  !

EG06 GENERATOR FAULT D 06/06/90 10/11/91 01/24/97 l EG07. . GENERATOR LOSS OF EXCITATION D 06/06/90 10/11/91- 01/14/97  !

EG200 EG TEMP TRANSMITTER SO 08/20/90 05/08/91 01/14/97 )

Condensate and Feedwater System . l FWOI CONDENSATE PUMP TRIP D 03/02/90 01/29/93 2/2/99 )

F W O2' 13 CONDENSATE PUMP FAILS TO START D 03/02/90 01/29/93 2/2/99 )

AUTOMATICALLY . l FWO3 LOSS OF CONDENSER VACUUM V FAILED 01/05/93 Deferred l FWOS CONDENSATE PUMP RECIRC VALVE D 08/20/90 10/28/92 2/2/99 FAILS OPEN FWO6 CONDENSATE PUMP RECIRC VALVE D 08/20/90 10/28/92 Deferred

- Fall,S CLOSED ,

FWO7 - CONDENSATE HOTWELL MAKEUP VALVE D 03/02/90- 01/29/93 2/2/99 i FAILS OPEN l FWO8 CONDENSER HOTWELL MAKEUP VALVE D 06/06/90 10/28/92 Deferred j FAILS CLOSED FWO9 LP FEEDWATER HEATER BYPASS VALVE D 06/06/90 10/28/92 Deferred

-FAILS OPEN -

FW10 CONDENSER HOTWELL LEVEL D 10/16/90 02/08/93 Deferred TRANSMITTER FAILS HIGH FW11 CONDENSER HOTWELL TRANSMITTER D 01/21/91 02/08/93 Deferred FAILS LOW FW13 - MAIN FEEDWATER PUMP TRIP D 06/06/90 01/29/93 Deferred FW15 FEEDWATER HP HEATER HIGH LEVEL D 04/12/90 08/12/92 Deferred FW16 - FEEDWATER LP HEATER HIGH LEVEL D 04/12/90 10/28/92 Deferred FW17 - FEEDWATER HP HEATER LEAK V 07/24/90 10/28/92 09/26/97 FW18 FEEDWATER LP HEATER LEAK V 01/15/91 01/29/93 09/26/97 FW19 FEEDWATER SYSTEM RUPTUREINSIDE V 01/08/91 10/28/92 09/26/97 CONTAINMENT FW20 FEEDWATER SYSTEM LEAKAGE INSIDE V 09/25/90 01/29/93 09/26/97

! CONTAINMENT FW21. FEEDWATER SYSTEM RUPTUREINSIDE V 01/08/91 01/29/93 02/02/96 l

l CONTAINMENT UPSTREAM OF CHECK l VALVE

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PRAIRIE ISLAND CERTIFICATION REPORT l 1998 l f APPENDIX 6 i Initial Cycle 1 Cycle 2 Test Title Type Approval Approval Approval Number Date Date Date FW22 FEEDWATER SYSTEM RUPTURE OUTSIDE V 01/15/91 01/29/93 Deferred CONTAINMENT i FW23 FEEDWATER SYSTEM LEAKAGE OUTSIDE V 09/25/90 01/05/93 Deferred ]

CONTAINMENT  !

FW24 FEEDWATER PUMP COMMON DISCHARGE V 01/21/91 01/29/93 Deferred HEADER RUP"URE FW25 F"EDWATG FLOW CONTROL VALVE D 07/24/90 08/12/92 2/2/99 l FAILS 10 CLOSE ON FW ISOLATION SIGNAL FW26 FEEDWATER FLOW CONTROL VALVE V 01/31/91 01/29/93 Deferred FAILS OPEN ,

FW27 FEEDWATER FLOW CONTROL VALVE D 09/25/90 01/29/93 Deferred FAILS CLOSED FW28 HEATER DRAIN PUMP TRIP D 03/02/90 01/29/93 2/2/99 FW29 HEATER DRAIN TANK LEVEL D 09/25/90 10/28/92 Deferred TRANSMITFER FAILS HIGH FW30 HEATER DRAIN TANK LEVEL D 09/25/90 01/0.i/93 Deferred TRANSMITTER FAILS LOW FW3I HEATER DRAIN PUMP FAILS TO MINIMUM D 09/25/90 10/28/92 09/26/97 FW32 AUXILIARY FEEDWATER PUMP TRIP - D 03/02/90 01/29/93 2/2/99 MOTOR I FW33 AUXILIARY FEEDWATER PUMP TRIP - D 03/02/90 01/29/93 2/2/99 I l TURBINE l

FW34 ' AUXILIARY FEEDWATER PUMP FAILS TO D 03/02/90 02/04/93 2/2/99 START AUTOMATICALLY FW35 INADEQUATE CONDENSATE TO V 01/15/90 01/29/93 Deferred AUXILIARY FEEDWATER PUMP SUCTION FW36 AUXILIARY FEEDWATER DISCHARGE V 01/21/91 01/29/93 09/26/97 LINE R'UPTURE INSIDE CONTAINMENT FW37 AUXILIARY FEEDWATER DISCHARGE V 01/08/91 10/28/92 09/26/97 ,

LINE RUPTURE OUTSIDE CONTAINMENT FW38 AUXILIARY FEEDWATER CONTROL D 03/02/90 01/29/93 2/2/99 VALVE FAILS IN POSITION

! FW39 FEEDWATER LINE RUPTURE UPSTREAM V 09/25/90 08/12/92 Deferred l OF FW REG VALVES l FW40 COMMON FEEDWATER PUMP SUCTION V 01/28/91 01/29/93 Deferred l LINE BLOCKAGE i Page 5 i

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PRAIRIE ISLAND CERTIFICATION REPORT  ;

1998 APPENDIX 6 i

Initial Cycle 1 Cycle 2 Test Title Type Approval Approval Approval l Number Date Date Date FW41 FEEDWATER FLOW CONTROL VALVE V 01/15/91 01/05/93 ~ Deferred i LEAKAGE l FW200 COND FLW TRANSMITTER SO 07/24/90 10/28/92 Deferred l FW201 CDSR HW TRANSMITTER SO 07/24/90 08/12/92 2/2/99 i FW202 11 A FW LEVEL TRANSMITTER SO 07/24/90 08/12/92 Deferred 9 FW203 12A FW LEVEL TRANSMITTER SO 07/24/90 08/12/92 Deferred FW204 11B FW LEVEL TRANSMITTER SO 07/24/90 08/12/92- Deferred FW205 12B FW LEVEL TRANSMITTER SO 07/24/90 08/12/92 Deferred FW206 13A FW LEVEL TRANSMITTER SO 07/24/90 08/12/92 Deferred I FW207 13B FW LEVEL TRANSMITTER SO 07/24/90 08/12/92 Deferred l FW208 15A FW LEVEL TRANSMITTER SO 07/24/90 08/12/92 Deferred FW209 15B FW LEVEL TRANSMITTER SO 07/24/90 08/12/92 Deferred Compressed AirSystem IA01 LOSS OF SERVICE AIR HEADER V 10/16/90 02/08/93 01/24/97 IA02 LOSS OF INSTRUMENT AIR HEADER V 01/28/91 01/06/94 02/04/97 l 1A03 LOSS OF AIR COMPRESSOR D 03/02/90 02/08/93 01/14/97 l Main Steam System l MS01 MAIN STEAM LINE RUPTURE INSIDE V 01/21/91 12/09/93 02/02/96 l CONTAINMENT UPSTREAM OF MSIV l MS02 MAIN STEAM LINE RUPTURE OUTSIDE V 01/15/91 01/29/93 02/02/96 CONTAINMENT UPSTREAM OF MSIV MS03 MAIN STEAM LINE RUPTURE OUTSIDE V 09/25/90 01/29/93 02/02/96 CONTAINMENT DOWNSTREAM OF MSIV MS04 MAIN STEAM LINE LEAK V 09/25/90 01/29/93 01/25/96 MS05 MAIN STEAM SAFETY VALVE STICKS D 05/09/90 01/29/93 02/02/96 OPEN MS06 GLAND SEAL STEAM REGULATING D 09/25/90 01/29/93 01/25/96 i

l VALVE FAILS CLOSED MS07 MAIN STEAM SAFETY VALVE FAILURE V NEW NEW 08/26/97 ,

MSO8 MOISTUIE SEPARATOR -IEHEATER D 01/08/91 01/29/93 02/22/96 l RELIEF VALVES FAILURE l MSO9 MAIN STEAM LINE LEAKINSIDE V 01/21/91 02/04/93 01/25/96 l

, CONTAINMENT  ;

l MS10 MAIN STEAM LINE BREAK ON COMMON V HOLD 01/29/93 02/02/96 )

. SUPPLY LINE TO AFW MSI1 STEAM DUMP VALVE FAILS IN POSITION D 01/31/91 01/29/93 09/26/97 MS200 . IB MS LEVEL TRANSMITTER SO 08/20/90 01/05/93 11/29/95 Page 6 l

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PRAIRIE ISLAND CERTIFICATION REPORT 1998  :

APPENDIX 6 ]

l Initial Cycle 1 Cycle 2 Test Title Type Approval . Approval Approval l Number Date Date Date l

MS201 2B MS LEVEL TRANSMITTER SO 08/20/90 01/05/93 11/29/95 MS202 1 A MS LEVEL TRANSMITTER SO 07/24/90 01/05/93 11/29/95 MS203 2A MS LEVEL TRANSMITTER SO 07/24/90 01/05/93- 11/29/95 MS300 SG SAFETY VALVES VS 01/21/91 01/29/93 02/02/96 Nuclear Instrumentation System NIOl INCORRECT SOURCE RANGE CHANNEL V 05/09/90 01/06/94 08/26/97 1 RESPONSE  !

NIO2 SOURCE RANGE CHANNEL SPIKES D 05/09/90 01/06/94 08/26/97 NIO3. INTERMEDIATE RANGE CHANNEL V 05/09/90 01/06/94 08/26/97 IMPROPER RESPONSE N104 INTERMEDIATE RANGE CHANNEL V 01/21/91 12/21/94 08/26/97 IMPROPER COMPENSATION NIO5 IMPROPER POWER CHANNEL RESPONSE V 10/16/90 01/20/95 08/26/97 I NIO6 POWER RANGE UPPER CHANNEL V 01/21/91 12/21/94 09/26/97 j IMPROPER RESPONSE I NIO7- POWER RANGE LOWER CHANNEL V 01/21/91 12/15/94 09/26/97 I IMPROPER RESPONSE i I

NI300 1R PWR ABOVE P-6 VS 01/25/91 01/06/94 08/26/97 N1302 . PR PWR ABOVE P-8 VS 09/25/90 01/20/94 08/26/97 N1306 PR PWR ABOVE P-9 VS 09/2J/90 01/20/94 08/26/97 N1310 PR PWR ABOVE P-10 VS 09/25/90 01/20/94 09/26/97 N1316 IR HI FLUX TRIP VS 09/25/90 01/20/94 09/26/97 NI318 PR LO RNG HI FLUX TRIP VS 09/25/90 01/20/94 09/26/97 NI322 PR HI RNG HI FLUX TRIP / POS RATE TRIP / VS 01/28/91 01/20/94 09/26/97 NEG RATE TRIP Plant Process Computer System PC01- ERCS CPU FAILURE D 09/25/90 01/06/94 11/13/97 PC03 ERCS ALARM DISPLAY FAILURE D FAILED 01/20/94 11/13/97 PC04 ERCS SAS DISPLAY FAILURE D FAILED 01/20/94 11/13/97 PCOS ERCS CONTROL ROOM PRINTER FAILURE D FAILED 01/20/94 11/13/97 l .

. Reactor Coolant System y

~

RC01 REACTOR COOLANT PUMP TRIP D 10/16/90 .01/06/95 03/14/96 j RCO2 REACTOR COOLANT PUMP LOCKED D HOLD 01/20/94 03/29/96 j ROTOR RC04 REACTOR COOLANT PUMP SHAFT SHEAR D 10/16/90 01/06/95 03/14/96 RC05 REACTOR COOLANT PUMP BEARING V 10/25/90 01/06/95 03/29/96 FAILURE

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PRAIRIE ISLAND CERTIFICATION REPORT -

1998 APPENDIX 6 l

)

Initial Cycle 1 Cycle 2 '

Test Title Type Approval Approval ' Approval Number Date Date Date RC06 LOSS OF COOLANT ACCIDENT- HOT LEG V 01/28/91 12/21/94 02/09/96 l RC07 LOSS OF COOLANT ACCIDENT- COLD LEG V 01/15/91 12/21/94 03/29/96 RCP SUCTION RC08 LOSS OF COOLANT ACCIDENT- COLD LEG V 01/28/91 12/21/94 02/22/96 RCP DISCHARGE =

RC09 LOSS OF COOLANT ACCIDENT V 01/25/91 10/06/94 02/09/96 PRESSURIZER STEAM SPACE l RC10 LOSS OF COOLANT ACCIDENT V 01/21/91 10/06/94 02/22/96 l PRESSURIZER WATER SPACE RC11 LOSS OF COOLANT ACCIDENT- RTD V FAILED 02/03/94 03/14/96 .

BYPASS LOOP COLD LEG MANIFOLD  !

RCl2 LOSS OF COOLANT ACCIDENT - RTD V 01/15/91 01/06/95 03/14/96 BYPASS LOOP RETURN LEG PIPING RC13 LOSS OF COOLANT ACCIDENT-IGACTOR V 01/31/91 01/06/95 02/09/96 HEAD VENT RCl4 REACTOR COOLANT SYSTEM LEAKS V 01/21/91 12/21/94 03/29/96 RC15 REACTOR COOLANT SYSTEM LEAKS V 01/15/91 12/15/94 02/09/96 RC16 PRESSURIZER POWER OPERATED RELIEF D 01/21/91 10/06/94 02/22/96 VALVE FAILS CLOSED RCl8 PRESSURIZER SAFETY VALVE RC-10-1 D 02/05/90 01/06/95 02/22/96 FAILS OPEN I RC19 PRESSURIZER SAFETY VALVE SEAi V 02/05/90 01/06/95 01/25/96 LEAKS RC20 REACTOR COOLANT PUMP OlL LEAK D 01/21/91 01/06/95 01/25/96 UPPER RESERVOIR RC21 REACTOR VESSEL O-RING LEAKAGE D 01/28/91 01/20/95 01/25/96 RC22 PRESSURIZER POWER OPERATED RELIEF V 10/25/90 01/20/95 01/25/96 VALVE LEAKAGE RC24 PRESSURIZER SPRAY VALVE FAILS IN D 10/25/90 01/06/95 01/25/96 POSITION Control Rod Drive System RD01 CONTROLLING ROD BANK FAILS TO D 03/02/90 01/29/93 01/25/96 MOVEIN MANUAL RDC2 CONTROLLING ROD BANK FAILS TO D 03/02/90 02/04/93 01/25/96 MOVEIN AUTO RD03 UNCONTROLLED CONTINUOUS ROD D 03/02/90 02/04/93 02/09/96 l

WITHDRAWAL OF CONTROLLING BANK Page 8

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PRAIRIE ISLAND CERTIFICATION REPORT 1998 APPENDIX 6 Initial Cycle 1 Cycle 2  :

Test Title Type Approval Approval Approval Number Date Date Date RD04 UNCONTROLLED CONTINUOUS ROD D 03/03/90 02/08/93 01/25/96  :

INSERTION OF CONTROLING BANK RDO5 ~ CONTROL ROD MISALIGNMENT D 01/21/91 02/04/93 03/29/96  !

RD06 STUCK ROD D 03/02/90 02/04/93 03/29/96  :

RD07 DROPPED ROD D 1IOLD 12/09/93 02/09/96 RD08 CONTROL ROD G-3 EJECTED D 01/21/91 01/29/93 02/09/96 ,

RD09 ROD POSITION INDICATION FAILS D 03/02/90 01/29/93 03/29/96 l RD10 INCORRECT ROD SPEED D 03/02/90 02/08/93 03/29/96 i Residual Heat Hemoval System RH01 RESIDUAL HEAT RFMO'i AL PUMP TRIP D 03/02/90 06/21/91 02/09/96 RH02 RESIDUAL HEAT PEMOVAL PUMP FAILS D 03/02/90 06/21/91 02/09/96 TO START AUTfAATICALLY RH03 RHR HEAT EXCHANGER END BELL V 08/20/90 05/08/91 02/22/96 LEAKAGE TO ATMOSPHERE RH04 RHR HEAT EXCHANGER BYPASS VALVE D 08/20/90 06/21/91 01/25/96 FAILS OPEN RH05 RHR HEAT EXCHANGER BYPASS VALVE D 09/20/90 05/08/91 02/09/96 FAILS CLOSED RH06 RECIRCULATION SUMP SUCTION LINES V 08/20/90 06/21/91 02/09/96 i BLOCKED RH07 RHR SYSTEM LEAKAGE V 10/16/90 06/21/91 02/09/96 RH08 RIIR PUMP SEAL FAILURE D 08/20/90 10/11/91 02/09/96 RH09 RESIDUAL REAT REMOVAL RELIEF D 08/20/90 10/11/91 02/22/96 VALVE FAILURE RH200 RH FLOW TRANSMITI'ER SO 07/24/90 05/08/91 02/09/96 Radiation Monitor System RM01 RADIATION MONITOR MISCALIBRATION V NEW NEW 01/14/97  ;

Reactor Protection System  !

RP01 REACTOR TRIP D 01/08/91 05/08/91 01/14/97 RP02 FAILURE OF AUTOMATIC REACTOR TRIPS D 08/20/90 05/08/91 01/14/97 RP03. FAILURE OF SAFETY SYSTEMS TO D 01/25/91 10/11/91 01/14/97 ACTUATE RP04 INADVERTENT ACTUATION OF TIIE D 01/08/91 06/21/91 01/17/97 SAFETY INJECTION SYSTEM

.RP05 FAILURE OF CONTAINMENTISOLATION D 01/25/91 05/08/91 01/17/97 l

l PHASE A TO ACTUATE

! RP06 FAILURE OF MSIV'S TO ISOLATE D 01/08/91 06/21/91 01/17/97

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4 ee PRAIRIE ISLAND CERTIFICATION REPORT 1998 APPENDIX 6 Initial Cycle 1 Cycle 2 Test Title Type Approval Approval Approval l Number Date Date Date i

RP07 MECIIANICAL FAILURE OF IEACTOR TRIP D 01/08/91 06/21/91 01/17/97 BREAKERS RP08 l FAILURE OF SAFEGUARDS ACTUATION D 01/25/90 05/08/91 01/17/97 '

IU'300 / P-7 TURB PRESS / TURBINE 1ST STAGE VS 01/25/91 05/08/91 01/17/97 RX226 PRESSURE RP302 AUTO ROD WITHDRAWAL BLOCK P-2 VS 08/20/90 05/08/91 01/17/97 RP303 BUS 11/12 UV TRIP VS 08/20/90 06/21/91 01/24/97 RP305 BUS 11/12 UF TRIP VS 08/20/90 10/11/91 01/17/97 l RP307 / RC LOW FLOW TRIP / REACTOR COOLANT VS 08/20/90 12/13/91 01/24/97 RC03 PUMP SHAFT SHEAR RP313 / PRZR LO PRESS TIUP / SI VS 01/25/91 12/13/91 01/24/97 IU'320 l

RP317/ PZR 111 PRESS TRIP / PRESSURIZER VS 01/25/91 06/21/91 01/24/97 i RC300 SAFETIES j RP323 PRZR HI LVL TRIP VS 09/25/90 05/08/91 01/24/97 RP326 SG LOLO LVL TRIP VS 09/25/90 06/21/91 01/24/97 RP340 / LOLO TAVG STM LN ISOL / HI STM FLOW VS 09/25/90 10/11/91 01/24/97 !

RP344 RP348 SG Hi-HI STM FLOW VS 09/25/90 10/11/91 01/24/97 RP352 SG LOLO STM PRESS SI VS 09/25/90 06/21/91 01/24/97 Reactor Control System RX01 PRESSURI7ER SPRAY VALVE FAILS OPEN V 03/02/90 11/24/93 09/26/97 RX02 PRESSURIZER SPRAY VALVES PCV-431 A & D 03/02/90 01/06/94 09/26/97 E FAIL CLOSED l RX03 PRESSURIZER HEATERS FAIL ON D 03/02/90 11/24/93 09/26/97 RX04 PRESSURIZER HEATERS FAIL OFF (ALL) D 03/02/90 11/24/93 09/26/97 RX05 REACTOR COOLANT LOOP TH D '

03/02/90 02/09/94 10/20/97 TRANSMITTER FAILS HIGH RX06 REACTOR COOLANT LOOP TH D 03/02/90 02/09/94 10/20/97 TRANSMITTER FAILS LOW RX07 REACTOR COOLANT TC TRANSMITTER D 03/02/90 02/09/94 10/20/97 FAILS HIGH RXO8 REACTOR COOLANT LOOP TC D 03/02/90 02/09/94 10/20/97 TRANSMITTER FAILS LOW l RX09 REACTOR COOLANT SYSTEM WIDE D 04/12/90 11/24/93 1/27/98 RANGE PRESSURE TRANSMITTER FAILS HIGH Page 10 r

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i / e' l PRAIRIE ISLAND CERTIFICATION REPORT 1998 APPENDIX 6 1

Initial Cycle 1 Cycle 2 Test Title Type Approval Approval Approval Number Date Date Date i

RX10 REACTOR COOLANT SYSTEM WIDE D 04/12/90 12/09/93 1/27/98 RANGE PRESSURE TRANSMITTER FAILS LOW RX11 FEEDWATER CONTROLLER OUTPUT V 04/12/90 12/02/93 11/13/97 l FAILURE RX12 TURBINE FIRST STAGE PRESSUIG D 03/02/90 12/07/94 11/13/97 i TRANSMITTER FAILS HIGH RX13 TURBINE FIRST STAGE PRESSURE D 03/02/90 12/07/94 11/13/97 TRANSMITTER FAILS LOW RX14 STEAM GENERATOR FEEDWATER D 03/02/90 12/07/94 11/13/97 l CONTROL SYSTEM FAILS TO MANUAL RX15 ADFCS MAIN FLOW CONTROL VALVE D 03/02/90 12/07/94 11/13/97 OUTPUT CARD FAILURE RX16 ADFCS BYPASS FLOW CONTROL VALVE D 04/12/90 12/02/93 11/13/97 OUTPUT CARD FAILURE RX200 RCS PRESSURE TRANSMITTER PT429 SO 01/08/91 12/02/93 10/20/97 l RX201 RCS PRESSURE TRANSMITTER PT430 SO 01/08/91 12/02/93 10/20/97 RX202 RCS PRESSURE TRANSMITTER PT431 SO 01/08/91 12/02/93 10/20/97 RX203 RCS PRESSURE TRANSMITTER PT449 SO 01/08/91 12/02/93 10/20/97 RX204 PRZR LVL TRANSMITTER LT426 SO 01/25/91 12/02/93 1/27/98 RX205 PRZR LVL TRANSMITTER LT427 SO NEW NEW l1/13/97 RX206 PRZR LVL TRANSMITIER LT428 SO 01/25/91 12/02/93 11/13/97 RX207 FW FLOW TRANSMITTER FT466 SO 01/08/91 12/02/93 11/13/97 RX208 FW FLOW TRANSMITTER FT467 SO 01/08/91 12/02/93 11/13/97 RX209 FW FLOW TRANSMITTFR FT495 SO 01/0 0 1 12/09/93 1/27/98 RX210 FW FLOW TRANSMITTER FT476 SO 01/08/91 12/02/93 1/27/98 RX211 FW FLOW TRANSMITTER FT477 SO 01/08/91 12/02/93 11/13/97 RX212 FW FLOW TRANSMITTER FT497 SO 01/08/91 12/09/93 11/13/97 RX213 11 MS PRESSURE TRANSMITTER PT468 SO 01/08/91 12/02/93 1/27/98 RX214 11 MS PRESSURE TRANSMITTER PT469 SO 01/08/91 12/09/93 1/27/98 RX215 11 MS PRESSURE TRANSMITTER PT482 SO NEW NEW 1/27/98 RX216 12 MS PRESSURE TRANSMITTER PT478 SO 01/08/91 12/09/93 10/20/97 RX217 12 MS PRESSURE TRANSMITTER PT479 SO 01/08/91 12/09/93 10/20/97 RX218 12 MS PRESSUIE TRANSMITTER PT483 SO NEW NEW 10/20/97 RX219 11 MS FLOW TRANSMITTER FT464 SO 01/08/91 12/09/93 1/27/98 RX220 11 MS FLOW TRANSMITTER FT465 SO 01/08/91 12/09/93 1/27/98 l RX221 12 MS FLOW TRANSMITTER FT474 SO 01/08/91 12/09/93 1/27/98 Page 11

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PRAIRIE ISLAND CERTIFICATION REPORT 1998 APPENDIX 6 Initial Cycle 1 Cycle 2 Test Title Type Approval Approval Approval Number Date Date Date RX222 12 MS FLOW TRANSMITTER FT475 SO 01/08/91 12/09/93 1/27/98 RX223 11 STM FLOW TRANSMITTER FT494 SO 01/08/91 12/09/93 1/27/98 RX224 12 STM FLOW TRANSMITTER FT496 SO 01/08/91 12/09/93 1/27/98 l RX225 11/12 MS PRESSURE TRANSMITTER PT484 SO 01/08/91 12/02/93 1/27/98 RX227 11 FEED TEMP TRANSMITTER TT498 SO 01/08/91 12/09/93 1/27/98 l RX228 12 FEED TEMP TRANSMITTER TT499 SO 01/08/91 12/09/93 1/27/98 I RX229 FW HDR PRESSURE TRANSMITTER PT450 SO 01/08/91 12/09/93 1/27/98 RX230 FW HDR PRESSURE TRANSMITTER PT451 SO 01/08/91 12/09/93 1/27/98 RX231 11 SG WR LEVEL TRANSMITTER LT502 SO 01/25/91 01/06/94 1/27/98 I RX232 12 SG WR LEVEL TRANSMITTER LT503 SO 01/25/91 01/06/94 1/27/98 RX233 PZR LEVEL LOCAL CONTROL LC428F SO NEW 02/03/94 10/20/97 RX234 11 SG LEVEL TRANSMITTER LT461 SO 01/08/91 01/06/94 1/27/98  ;

RX235 11 SG LEVEL TRANSMITTER LT462 SO NEW NEW 1/27/98 I RX236 11 SG LEVEL TRANSMITTER LT463 SO NEW NEW 1/27/98 RX237 12 SG LEVEL TRANSMITTER LT471 SO 01/08/91 01/06/94 1/27/98 RX238 12 SG LEVEL TRANSMITTER LT472 SO NEW NEW 1/27/98  ;

RX239 12 SG LEVEL TRANSMITTER LT473 SO NEW NEW 1/27/98 RX240 AUCTIONEERED TAVG SO FAILED 12/02/93 1/27/98 RX300 PRZR PORV SETPOINT VS FAILED 12/09/93 11/13/97 RX302 . LOAD REJECT STM DUMP HI/HI-HI TAVG VS 01/25/91 02/03/94 10/20/97 RX305 MASTER PRZR PRESS CONT STPT VS 01/25/91 01/20/94 10/20/97 Steam Generator System SG01 STEAM GENERATOR TUBE LEAK V 01/28/91 01/06/95 02/09/96 SG02 STEAM GENERATOR TUBE RUPTURE V 01/28/91 01/06/95 03/29/96 SG03 STEAM GENERATOR BLOWDOWN D FAILED 01/20/95 02/09/96 CONTROL VALVE FAILS OPEN Safety Injection System SIOl BOTH BORIC ACID TANK VALVES FAllTO D 10/25/90 02/04/93 2/2/99 OPEN IN AUTO SIO2 SI LOOP A COLD LEG INJ CHECK VALVE D 10/25/90 01/20/95 2/2/99 FAILURE S103 BORIC ACID TANK VALVE FAILS TO D 10/25/90 01/20/95 2/2/99 CLOSE ON LO-LO LEVEL IN THE PRESELECTED BORIC ACID TANK IN l AUTO S104 SAFETY INJECTION PUMP TRIPS D 03/02/90 02/08/93 2/2/99 Page 12 l

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PRAIRIE ISLAND CERTIFICATION REPORT 1998 1 APPENDIX 6 Initial Cycle 1 Cycle 2 Test Title Type Approval Apprt> val Approval Number Date Date Date S105 SAFETY INJECTION PUMP FAILS TO D 03/02/90 01/06/95 2/2/99 START AUTOMATICALLY  ;

SIO6 SI ACCUMULATOR LEAKAGE D 10/25/90 01/20/95 2/2/99 SIO7 SI ACCUMULATOR CHECK VALVE D 10/25/90 01/20/95 2/2/99 ,

LEAKAGE S108 SI ACCUMULATOR RELIEF VALVE D 10/25/90 01/20/95 2/2/99 LEAKAGE S109 SI COLD LEG INJ LINE RUPTURE INSIDE V 01/25/91 01/20/95 2/2/99 OF THE ANNULUS Turbine Control System TC01 TURBINE STOP VALVE FAILS TO CLOSE D 03/02/90 07/22/94 01/17/97 WHEN REQUIRED  ;

TC02 TURBINE STOP VALVE FAILS CLOSED D 03/02/90 07/22/94 01/17/97 )

TC03 TURBINE CONTROL SYSTEM CYCLING V 01/15/91 07/22/94 01/24/97 I OUTPUT TC04 TURBINE CONTROL VALVE FAILS OPEN D FAILED 01/20/94 02/04/97 TC05 TURBINE CONTROL VALVE FAILS CLOSED D 10/25/96 07/22/94 01/17/97 TC06 REACTOR PROTECTION SYSTEM FAILS TO D 03/02/90 07/22/94 01/17/97 TRIP TURBINE TC07 TURBINE CONTROL INTERCEPT VALVE D 03/02/90 07/22/94 01/17/97 TC08 TUIGINE CONTROL FAILURE DURING 1) 10/25/90 07/22/94 01/17/97 TURBINE ROLL TC09 TURBINE CONTROL FAILURE CAUSING D 01/15/91 07/28/94 01/17/97 l TURBINE RUNBACK TC10 TURBINE CONTROL FAILURE CAUSING D 10/25/90 07/22/94 01/17/97 i AN INCREASE IN POWER WITHOUT l DEMAND j TCl1 COMPLETE TURBINE TRIP FAILURE D FAILED 07/22/94 01/17/97 !

TCl2 TURBINE TRIP D 10/25/90 07/28/94 01/17/97 TCl3 ELECTRICAL HYDRAULIC CONTROL D 03/02/90 07/22/94 01/17/97 PUMP TRIP TCl4 TURBINE CONTROL VALVE FAILS IN D NEW 12/07/94 01/17/97 POSITION TC300 INIT TURB CV POS VS 01/03/91 01/06/94 01/17/97 i

Turbine System TU01 LOSS OF TURBINE LUBE OIL SUPPLY V HOLD 01/06/94 01/17/97 TUO2 TURBINE GENERATOR VIBRATION V 10/25/90 09/28/94 01/17/97 Page 13

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PRAIRIE ISLAND CERTIFICATION REPORT 1998 l APPENDIX 6 .

i Initial Cycle 1 Cycle 2 i Test Title Type Approval Approval Approval  !

Number Date Date Date Chemical and Volume Control System VC01 REACTOR COOLANT PUMP #1 SEAL V 01/28/91 02/03/94 Deferred FAILURE i VC02 IEACTOR COOLANT PUMP #2 SEAL D 01/25/91 01/20/94 Deferred FAILURE VC04 POSITIVE DISPLACEMENT CHARGING D 07/24/90 01/20/94 2/2/99 '

PUMP TRIP VC05 STUCK OPEN CHARGING PUMP RELIEF D NEW 07/22/94 Deferred VALVE VC06 REGENERATIVE HEAT EXCHANGER V 01/28/91 01/20/94 Deferred LEAKAGE VC07 LETDOWN HEAT EXCHANGER LEAKAGE V 01/25/91 09/28/94 2/2/99 TO ATMOSPHERE VC08 LETDOWN HEAT EXCHANGER TUBE D 01/15/91 07/28/94 Deferred RUPTURE TO CCW SYSTEM VC09 LETDOWN LINE LEAKAGE INSIDE V 01/08/91 09/28/94 2/2/99  !

CONTAINMENT VC10 CHARGING PUMP COMMON DISCHARGE V 01/15/91 09/28/94 2/2/99 l HEADER RUPTURE VCl1 CHARGING LINE LEAKAGE INSIDE V 01/28/91 11/30/94 2/2/99 CONTAINMENT VCl2 EMERGENCY BORATION VALVE STUCK D 01/28/91 09/28/94 Deferred OPEN VCl3 LETDOWN LINE RELIEF VALVE FAILURE D 01/15/91 07/28/94 Deferred VC14 VOLUME CONTROL TANK IELIEF VALVE D 01/28/91 09/28/94 2/2/99 FAILURE 4 VC19 LOSS OF AIR TO CHARGING PUMP SPEED D 01/28/91 07/28/94 Deferred CONTROLLER VC20 CCW RETURN FROM LETDOWN HEAT D 01/15/91 07/28/94 2/2/99 EXCHANGER FAILS CLOSED VC21 REACTOR COOLANT PUMP THERMAL V 01/28/91 09/28/94 Deferred BARRIER TUBE FAILURE VC200 VC PRESSURE TRANSMITTER SO 01/08/91 07/28/94 Deferred i

VC201 VC TEMPERATUIE TRANSMITTER SO FAILED 07/28/94 Deferred VC202 VC FLOW TRANSMITTER SO 01/25/91 07/28/94 Deferred VC203 VC FLOW TRANSMITTER SO 01/25/91 07/28/94 Deferred VC204 VCT LEVEL TRANSMITTER SO NEW 07/28/94 Deferred Page 14 I

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l PRAIRIE ISLAND CERTIFICATION REPORT 1998 APPENDIX 6 Initial Cycle 1 Cycle 2 Test Title Type Approval Approval Approval Number Date Date Date P

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