ML20078N953

Simulator Certification Rept for Prairie Island Plant Simlation Facility 1994 Annual Rept

ML20078N953
Person / Time
Site:	Prairie Island
Issue date:	01/26/1995
From:	NORTHERN STATES POWER CO.
To:
Shared Package
ML20078N938	List: ML20078N935 ML20078N953
References
NUDOCS 9502160204
Download: ML20078N953 (189)

Text

A PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1994 SIMULATOR CERTIFICATION REPORT FOR THE PRAIRIE ISLAND PLANT SIMULATION FACILITY 1994 ANNUAL REPORT l

i Drafted By: kW kf Date: # ,/.2 c ,/ 9 s-3 7

Certification Review Panel Review:

Reviewed By: Date: / 26 (  ;

Reviewed By: h4L Date: //2/r/95 Reviewed By: M '

Date: (!267[

]; Approved By: bb Date: //2.c/7s l

Page 1 of 11 AD K 05000 82 P PDR

i f

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1994 TABLE OF CONTENTS Title Page Simulator Certification Report Cover Page . .... ............... .. ...... ......................... 1 i

Ta bl e of C o nt e nt s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

List of Appendices ... . .. .... .... . . . .. . . ....... . . . .... ....... ..... ... .. .... ........... .. ... 3

1. I N T R O D U CT I O N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

1 A. F acility I nformation . . . . . . . . . . . . . . . . . . . .. . . . . . . . .. . .. . . . . . . . . . . . . . . . . . ... .. .. . . . . . . . . . ... 4 l B. Control Room information... . . . . . ... .. . ... ....... ... . .. .............. ...... ... 4 C. Instructor's Interface . . . . . . . . . . .. .... . ... ... ...... ..... .. . ........ ........ .. ... 5 D. Operating Procedures for the Reference Plant.. ....... .. .. .... ....... .. . ...... 6 E. Changes Since the Last Report.... . ............... ...... .. .... . . ........ .. ....... 7

11. S IM U LATO R D E S IG N DATA . . . . . .. . . . .. . .. . ... . . . . .. . ... ... .. . ....... . . . . . . ... ... 7 4 l

111. SIMU LATO R DO C UM ENTATIO N . . . . . . . ... . .. . . .. . .. . . . . ... . ... . .. .. . ... . ... ....... . 8 IV. S IMU LATO R T E STI N G . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . .. . . . . . ... . . .. . . . . . . . . . . ... . . . 8 A. Simulator Performance Testing... . .. ..............................................8 B. Simulator Operability Testing..... . ... ..... ..... ......... .. .... . .. .. ... ... .... .. 9 1

C . Te sti ng Result s Review . . . . . . . . . . . . . . . . . . . . . .. . . .. ... . . . . . . . ... ... . ... . .. .. . .. . .. . . .. . .. .. . 10 V. CO NFIGU RATIO N MANAGEMENT SYSTEM . . ... ........ . ....... ....................... 10 Page 2 of 11

1 PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1994 LIST OF APPENDICES l Appendix 1 Simulator Physical Fidelity Update l FIGURE 1 A Plant Control Room Layout l FIGURE 1B Simulator Layout Appendix 2 Instructors Interface Capabilities - Changes Table 2A Simulator Protected initial Conditions ,

Appendix 3 Certification Review Panel Members  ;

Appendix 4 Four Year Testing Schedule Table 4A 1991 Testing Summary Table 4B 1992 Testing Summary Table 4C 1993 Testing Summary I

Table 4D 1994 Testing Summary Appendix 5 Annual Testing Abstracts Table SA Simulator Certification Testing Critical Parameter List ,

I I

Appendix 6 Malfunction Testing Abstracts Appendix 7 LERTesting Abstracts ,

1 Page 3 of 11 l

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1994 j

l. INTRODUCTION The purpose of the Prairie Island Simulator Certification Annual Report is to document the 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 in several different sections including information describing the facility, hardware, procedures used, performance testing completed and configuration management program for the simulation facility certified for the Prairie Island Plant Units 1 and 2. ,

This report is issued annually - the initial report was issued in January 1991 and this is the fourth annual update. This annual update is the final update for the first four year cycle following initial certification. Therefore, this report will describe all changes and testing completed since the initial certification report.

A. FACILITY INFORMATION i

Facility Name Docket / License Type Ratina l Prairie Island Unit 1 Docket Number 50-282 Westinghouse PWR 560 MWE License Number DPR-42 Prairie Island Unit 2 Docket Number 50-306 Westinghouse PWR 560 MWE License Number DPR-60 Licensee: Northern States Power Company Simulation Facility: 1 Owner / Operator Northern States Power Company Manufacturer Singer-Link (presently part of GSE Inc.)

Date Available for Training February 6,1984 Type of Report Periodic Update initial Certification Date February 7,1991 B. CONTROL ROOM INFORMATION Figure 1 A is a layout of the plant Control Room and Figure 1B is a layout of 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 separate except for some shared systems on Panel A. The simulator duplicates the Unit 1 half of the Control Room plus the necessary portions of the shared systems on Panel A as well as certain Unit 2 systems with crosstie capability with Unit 1. An Page 4 of 11

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1994 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.

C. INSTRUCTORS INTERFACE The Instructor 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 Instructors 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

9. Fast Time 9. Annunciator Sound Silence

10. Slow Time 10. Ten Malfunction / Remote Function Selection Keys

11. Record

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 The functions available on the keyboard were listed in the initial Certification Report and an updated list is included in Appendix 2. All malfunction, system override and l variable setpoint tests are included in Appendix 6, " Malfunction Testing Abstracts" The changes to the available malfunctions, variable setpoints, system overrides and Page 5 of 11

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1994 remote functions have been compared against the requirements in ANS/ ANSI 3.5-1985 to verify that these requirements are still met.

A recent audit of the simulator identified that one malfunction type required by ANSI /ANS 3.5-1985 was not included on the simulator - specifically an uncoupled rod malfunction. This issue was reviewed by the Simuistor Design Review Committee which determined that this malfunction was not needed for training since the instructor has tho ability to simulate the observable effects of an uncoupled rod with the current

'nstructor Station capabilities, and this malfunction would seldom be used for training.

D. OPERATING PROCEDURES FOR THE REFERENCE PLANT Controlled copies of the Prairie Island Nuclear Generating Plant (PINGP) Operating Procedures for Unit 1, including Integrated Operations Procedures, System Operations Procedures, Surveillance Procedures, Plant Figures and Curves, System Checklists, Startup Checklists and Emergency Operations ProcMWas are used on the Prairie Island simulator. Occasionally, draft revisions to selected pro::edures have been used to " prove" the procedure revisions prior to use in the plant or !c provide the operations personnel training on significant Control Room or procedu:e modifications prior to installation in the plant. The period of use of draft proce Jures 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 ccmponent identification numbers. Efforts are made to maintain the procedures identical during all revisions with the only exception being the unique component identification.

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. Tne 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.

Page 6 of 11

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT

! 1994 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, renarning of malfunctions and remote functions (eg. DG system), and deletion of malfunctions and remote functions. Appendix 2 contains a list of the current Instructor 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.  !

l

4. Simulator Hardware The simulator computer system was replaced during 1993 to provide more current capabilities and pavide for future model improvements. The computer replacement was completed without impacting training use of the simulator, and testing 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.

ll SIMULATOR DESIGN DATA The simulator design database is corrposed 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 trard pictures, plant process computer printouts, startup test results, etc.). This 1

dr.a was archived following receipt of the simulator and completion of the final i a: cuptance testing. Lists of these documents are available at the Prairie Island Training Center on microfilm. Following delivery of the simulator, a review was l

1 performed to determine which plant modifications had been included in the design data base.

Page 7 of 11

PRAIRid ISLAND SIMULATOR CERTIFICATION REPORT 1994

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 Modifications and additions to the simulator are documented in the simulator records. The simulator record files contain the following documents:

Simulator Change Packages Modification Reviews Setpoint Change Reviews Simulator Hardware Drawings Simulator Procedures Simulator Correspondence Simulator Performance Tests Simulator Design Review Committee Meeting Minutes Simulator Change Index Modification Tracking Log Discrepancy Reports Simulator improvement Requests initial Condition Updates Form Benchmarking Files Simulator Work Requests

3. Several of the documentation files included in each simulator change package are kept updated as living documents. These include the Final Design Specification, which includes the model source code, all design assumptions, and the system simulation drawings; wire lists, and several system specific doc.imentation files.

IV. SIMULATOR TESTING i A. Simulator Performance Testina Simulator procedure #11 addresses Performance Testing and requires that performance testing be repeated if simulator changes result in significant simulator configuration or performance variations. The simulator computer system was replaced during 1993, with release to Page 8 of 11

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT

, 1994 training in November. As part of this project, a representative sample of the operability tests were completed and compared to previous results with the objective of completing this replacement with no change in modeling performance. Since this change was completed without significant simulator configuration or performance variations, it did not require a repeat of the performance test.

l B. Simulator Operability Testina The simulator operability testing consists of two basic parts: the Simulator 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 1994 annual test procedures are included as Appendix 5. This group of tests include all testing required for simulator certification except for the required malfunction testing.

2. Simulator Malfunction Testing 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. Table 4A lists all malfunctions which i were tested during 1991, Table 48 lists all malfunctions which were tested during 1992, Table 4C lists all malfunctions which were tested during 1993 and Table 4D lists all malfunctions which were tested during 1994.

Appendix 6 contains abstracts of all the malfunction tests along with the date of the initial test approval and the date of the most recent retest approval. Due to the testing of malfunctions affected by simulator modifications and retesting of any malfunctions which failed the original testing (or were held pending additional data),

some malfunctions may have been retested more than one time during the four year cycle. These retests are included in Tables 4A,48,4C and 4D. j in addition to the testing required by ANS/ ANSI 3.5 - 1985, we a

have determined that testing of all applicable plant Licensee Events is a prudent practice. An index of Licensee Event testing completed is included in Appendix 7.

Page 9 of 11

4 L

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1994 i

C. Testina Results Review Results from all tesung completed for simulator certification were i reviewed by a panel of experts for agreement with the expected results l listed in the procedure and with the results recorded during testing. A list of the experts included in this panel and their qualifications is included as 3 Appendix 3.

V. CONFIGURATION MANAGEMENT SYSTEM The Configuration Management system used to maintain the simulator configuration has not been changed since the initial report, however the database used for this system has been changed from dBase to Microsoft Access. 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 process spelled out in the simulator procedures. The tracking is ,

performed using a database based on Microsoft Access. Resolution and l I

testing of 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.

1

2. Evaluation of proposed simulator design enhancements is performed by the Simulator Design Review Committee (SDRC), which is composed of representatives from Plant Operations, Operations Training, and the Simulator Group. Once these proposed changes are evaluated, they are entered into the tracking system. Further tracking and testing is the same as used for diserepancies. 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 current status can be easily determined. Once the plant modification is completed (identified by a closecut date), the SDRC reviews this modification to determine if it requires changes to the simulator. If simulator changes are required, a simulator change is initiated and  !

i tracked the same as all other simulator changes.

j l 1 I l Changes due to plant operating experience or plant procedure changes k are identified by the Request for Training Material Review process.

These changes are further reviewed by the SDRC, and if simulator Page 10 of 11 I

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1994 changes are required, they are initiated and tracked the same as all other ,

I simulator changes. .

4. Verification that the current simulator configuration matches the plant Control Room configuration is accomplished by testing of each simulator change prior to use for training, verification of each discrepancy report j against plant documents prior to making simulator changes, and testing as required for simulator certification.  ;

l Included in the testing for certification are comparisons against the plant  :

physical configuration (using photographs of the plant controls) l periodically during the four year cycle. These photographs were last taken during 1991 and the comparison was completed during 1992. All of (

the differences identified have been corrected. The next set of i photographs has been taken and comparison and correction of any l discrepancies identified will be completed during 1995. l 4

i t

i i

Page 11 of 11 l

f

-y -

w rr-r

l i

)

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1994 APPENDIX 1 Simulator Physical Fidelity l 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 which are identified and which will be corrected are listed with the Discrepancy Report number for tracking uses.

A. Control Room Environment

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

a. Many of the manuals which are located in the Shift Supervisor's office in the plant Control Room are located in a small office area adjacent to the simulator instructor's booth. Some of the frequently used manuals are located on a shelf behind the lead operator's station. Reference Figure 1B for this office and shelf location.

b. Identified in the Initial Certification Report was a difference in the carpeting between the simulator and the plant Control Room. The simulator flooring has been replaced and now matches the plant control room flooring.

2. Audible Environment 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 with the following exceptions:

a. Turbine noise is not simulated. A partial simulation was previously included when the door to the Turbine Room was opened on the PLge 1

PRAIRIE ISLAND SIMUIATOR CERTIFICATION REPORT 1994 APPENDIX 1 simulator. This noise simulation has been disabled since it was determined that this additional noise interfered with effective training.

Background noise is already higher on the simulator than in the plant Control Room, and this increased noise interferes with communications to a greater extent on the simulator than it does in the plant.

b. Control Rod step counter noise is slightly different from the plant step counter noise since the simulator step counters have been replaced with electronic LCD counters.

c. Simulator background noise levels are higher than the plant Control Ro m background noise levels.

d. The change in noise level due to the start of the Control Room Air Handlers is not simulated.

The Simulator Design Review Committee has reviewed these differences and determined that they are minor in nature and do not adversely impact training. The requirements of ANSI /ANS 3.5-1985 Section 3.2.3 are satisfied.

3. Lighting

a. The plant Control Room lighting was modified, resulting in an increase in light levels in the Control Room. Comparison of light level measurements between the plant Control Room and the simulator show that the light levels match reasonably close in most areas. One area in i the simulator is dimmer than the plant Control Room due to the lack of l light from the Unit 2 side of the Control Room in the simulator. This is not i considered significant and was judged not to impact training by the Certification Review Panel.

b. The emergency lighting system on the simulator has been modified to match the emergency lighting in the plant Control Room.

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

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 Page 2

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT j 1994 APPENDIX 1 l

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. Attached is a Control Room layout for the Prairie Island plant. i Following are the changes to the list of differences included in the Initial Certification Report:

a. The meter scales identified in the initial report, which haJ been modified in the simulator but had not yet been modified in the plant, have Deen completed in the plant Control Room.

b. The page system speaker previously located below annunciator cabinet 47024 has been relocated above the ceiling grids in the simulator to match the plant location.

c. A MIDAS (Meteorological and Dose Assessment System) terminal has been

• added to the simulator but is located in a different location than in the plant Control Room. 1 C. Systems Simulated snd Degree Of Completion l All systems which are controlled from the Control Room are simulated. The ,

I 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 ais :implated to the degree necessary to perform the reference plant normal evobtions and malfunctions listed in ANSI /ANS 3.5-1985 Sections 3.1.1 and 3.1.2. The trs! nee is able to interfaw with the remote activities in a manner similar to the reference plant The requirements of ANSI /ANS 3.5-1985 Section 3.2.1 are satisfied.

I 1

D. Significant Modifications o Several plant core reloads have been completed, resulting in changes in the  !

plant parameters without modifications to the simulator models incorporating Page 3 l l

I l

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1994 APPENDIX 1 l

these changes. The impact of these changes have been reviewed by the Simulator Design Review Committee and determined not to affect training use of l

I the simulator. Simulator model replacements are in progress and oxpected to be completed during 1995 which will incorporate these changes and also make future changes related to core reloads simpler to complete. No other significant plant modifications have been completed which have noi also been incorporated on the simulator. All plant modifications are reviewed periodically and necessary simulator changes are identified within one year of installation.

These simulator changes are then incorporated into the simulator within one year.

1 i

Page 4

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1994 APPENDIX 2 Instructor's Interface Capabilities Many changes have been completed in the instructors' interface area of the simulator. In general these have included addition of new malfunctions, remote functions and addition of new  :

capabilities (for example override of plant process computu .. puts). Following is a list l instructor's interface capabilities. These changes have been reviewed to verify that the requirements in ANSI /ANS 3.5-1985 are still met. (Note that an audit of the simulator identified one malfunction type required by ANS/ ANSI 3.5-1985 which is not available on the simulator -

specifically the Uncoupled Rod malfunction. Review of this malfunction by the Simulator Design Review Committee resulted in the determination that this malfunction was not needed for training and if desired by the instructor could be produced using available instructor controls.) 1 Simulation Options Backtrack Fast Time Slow Time Instrument Noise i

Trainer Hardware Test (DORT) 1 Switch Check Misalignments Display l

l Initial Conditions Selection Snapshot Selection Backtrack Time Selection Replay Rate Selection Malfunction Control Plant Process Computu Liput Override Simulator Operating Limits Display I/O Override Control Meteorological Data Control l

System Overrides EG200 EG TEMP TRANSMITTER FW200 COND FLW TRANSMITTER FW201 CDSR HW TRANSMITTER FW202 11 A FW LEVEL TRANSMITTER FW203 12A FW LEVEL TRANSMITTER FW204 1IB FW LEVEL TRANSMITTER FW205 12B FW LEVEL TRANSMITTER FW206 13 A FW LEVEL TRANSMITTER FW207 13B FW LEVEL TRANSMITTER FW208 15 A FW LEVEL TRANSMITTER Page 1 i

.1

PRAIRIE ISLAND SIMUIATOR CERTIFICATION REPORT 1994 APPENDIX 2 FW209 ISB FW LEVEL TRANSMITTER MS200 IB MS LEVEL TRANSMITTER MS201 2B MS LEVEL TRANSMITTER MS202 1 A MS LEVELTRANSMITTER MS203 2A MS LEVEL TRANSMITFER RH200 RH FLOW TRANSMITTER RX200 RCS PRESSURE TRANSMTITER RX201 RCS PRESSURE TRANSMITTER RX202 RCS PRESSURE TRANSMITTER RX203 RCS PRESSURE TRANSMITTER RX204 PRZR LVL TRANSMITTER RX205 PRZR LVL TRANSMITTER RX206 SG LEVEL TRANSMITTER RX207 SG LEVEL TRANSMITTER RX208 AUCTIONEERED TAVG RX209 FW FLOW TRANSMITTER RX210 FW FLOW TRANSMITTER RX211 FW FLOW TRANSMITTER RX212 FW FLOW TRANSMITTER RX213 11/12 MS PRESSURE TRANSh0TTER RX214 11 MS PRESSURE TRANSMITTER RX215 11 MS PRESSURE TRANSMITTER RX216 12 MS PRESSURE TRANSMITTER RX217 12 MS PRESSURE TRANSMITTER RX218 1ST STAGE PRESS TRANSMITTER RX219 11 MS FLOW TRANSMITTER RX220 11 MS FLOW TRANSMITTER RX221 12 MS FLOW TitANSMITTER RX222 12 MS FLOW TRANSMITTER RX223 11 STM FLOW TRANSMITTER RX224 12 STM FLOW TRANSMITTER RX225 11 FEED FLOW TRANSMITTER RX226 12 FEED FLOW TRANSMITTER RX227 11 FEED TEMP TRANSMITTER RX228 12 FEED TEMP TRANSMITTER RX229 FW HDR PRESSURE TRANSMITTER RX230 FW HDR PRESSURE TRANSMITTER RX231 11 SG WR LEVEL TRANSMITTER RX232 12 SG WR LEVEL TRANSMITTER RX233 PZR LEVEL LOCAL CONTROL VC200 VC PRESSURE TRANSMITTER VC201 VC TEMPERATURE TRANSMITTER VC202 VC FLOW TRANSMITTER VC203 VC FLOW TRANSMITTER VC204 VCT LEVEL TRANSMITTER VC205 VCT LEVEL TRANSMITTER Variable Setpoints Page 2 4

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1994 APPENDIX 2 Cli300 CHI CNMT HI PRESS PC-945A CH301 CH2 CNMT HI PRESS PC-949A CH302 CH4 CNMT HI PRESS PC-947A CII303 CH2 CNMT HIHI PRESS PC-946A CH304 CH3 CNMT HI PRESS PC-948A CH305 CH4 CNMT HIH1 PRESS PC-950A CH306 CHI CNMTlilHI PRESS PC-945B CH307 CH4 CNMT HIHI PRESS PC-947B Cll308 CH2 CNMT HIHI PRESS PC-949B CH309 CH2 CNMT HIHI PRESS PC-946B C11310 Cll3 CNMT HIHI PRESS PC-948B CH311 CH4 CNMT HIHI PRESS PC-950B MS300 11 SG SAI'ETY 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 MS308 12 SG SAFETY VALVE MS309 12 SG SAFETY VALVE N1300 IR N35 PWR ABOVE P-6 N1301 IR 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 N41.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 i N1311 PR N42 PWR ABOVE P-10 N1312 PR N43 PWR ABOVE P-10 N1313 PR N44 PWR ABOVE P-10 NI314 SR N3i HI FLUX TRIP N1315 SR N32 HI FLUX TRIP N1316 IR N35 HI FLUX TRIP N1317 IR N36 HI FLUX TRIP N!318 PR N41 LO RNG HIFLUX TRIP N1319 PR N42 LO RNG HIFLUX TRIP NI320 PR N43 LO RNG HI FLUX TRIP N1321 PR N44 LO RNG HIFLUX TRIP N1322 PR N41 HI RNG HI FLUX TRIP N1323 PR N42 HI RNG HIFLUX TRIP N1324 PR N43 HI RNG HI FLUX TRIP N1325 PR N44 HI RNG HI FLUX TRIP Page 3 i

l l

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1994 l

APPENDIX 2 N1326 PR N41 POS RATE TRIP N1327 PR N42 POS RATE TRIP N1328 PR N43 POS RATE TRIP NI329 PR N44 POS RATE TRIP N1330 PR N41 NEG RATE TRIP N1331 PR N42 NEG RATE TRIP r N1332 PR N43 NEG RATE TRIP PR N44 NEG RATE TRIP N1333  !

RC300 PZR SAFETY '

RC301 PZR SAFETY i

RP300 Cil 2 P-7 TURB PRESS RP301 Cil 3 P-7 TURB PRESS l RP302 AU10 ROD WITIIDRAWAL BLOCK P-2 RP303 BUS 11 UV TRIP RP304 BUS 12 UV TRIP RP305 BUS 11 UF TRIP J

RP306 BUS 12 UF TRIP RP307 A LOOP Cil 1 RC LOW FLOW TRIP RP308 A LOOP Cli 2 RC LOW FLOW TRIP RP309 A LOOP Cll 3 RC LOW FLOW TRIP RP310 B LOOP C111 RC LOW FLOW TRIP RP311 B LOOP Cli 3 RC LOW FLOW TRIP RP312 B LOOP Cl{ 4 RC LOW FLOW TRIP RP313 Cil 1 PRZR LO PRESS TRIP RP314 Cil 2 PRZR LO PRESS TRIP RP315 Cil 3 PRZR LO PRESS TRIP RP316 Cil 4 PRZR LO PRESS TRIP RP317 Cl{ l PZRIII PRESS TRIP RP318 Cil 2 PZR III PRESS TRIP RP319 Cil 3 PZRlil PRESS TRIP RP120 Cli 1 PRZR LO PRESS SI RP321 Cil 2 PRZR LO PRESS S1 I RP322 Cli 3 PRZR LO PRESS SI RP323 Cil 1 PRZRlil LVL TRIP RP324 Cil 2 PRZRlil LVL TRIP RP325 Cll 3 PRZR111 LVL TRIP RP326 LOOP A Cil 1 SG LOLO LVL TRIP RP327 LOOP A Cil 3 SG LOLO LVL TRIP RP328 LOOP A Cll 4 SG LOLO LVL TRIP RP329 LOOP B Cil 1 SG LOLO LVLTRIP RP330 LOOP B Cll 2 SG LOLO LVL TRIP RP331 LOOP B Cil 4 SG LOLO LVL TRIP RP340 LOOP A LOLO TAVG STM LN ISOL/III STM FLOW RP341 LOOP A LOLO TAVG STM LN ISOL RP342 LOOP B LOLO TAVG STM LN ISOL RP343 LOOP B LOLO TAVG STM LNISOL RP344 LOOP A 111 STM FLOW RP345 LOOP A 111 STM FLOW Page 4

PPAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1994 APPENDIX 2 RP346 LOOP B HI STM FLOW RP347 LOOP B lil STM FLOW RP348 LOOP A SG HI-HI STM FLOW RP349 LOOP A SO HI-H1 STM FLOW RP350 LOOP B SG HI-HI STM FLOW RP351 LOOP B SG Hi-HI STM FLOW RP352 LOOP A CH I SG LOLO STM PRESS SI RP353 LOOP A CH 2 SG LOLO STM PRESS SI RP354 LOOP A Cil 3 SG LOLO STM PRESS SI RP355 LOOP B CII 1 SG LOLO STM PRESS SI RP356 LOOP B CH 3 SG LOLO STM PRESS SI RP357 LOOP B CH 4 SG LOLO STM PRESS S1 RX300 PRZR PORV SETPOIMT RX302 LOAD REJECT STM DUMP HI TAVG RX303 LOAD REJECT STM DUMP HIHI TAVG RX304 TURBINE TRIP STM DUMP Hl/HIHITAVG RX305 M ASTER PRZR PRESS CONT STFT TC300 INIT TURB CV POS Annunciator System AN01 NSSS ANNUNCIATOR SYSTEM FAILURE AN100 UNIT 2 ANNUNCIATOR AUTO ACKNOWLEDGE Component Cooling System CC01 COMP COOLING WTR PUMP TRIP CCO2 COMPONENT COOLING PUMP FAILS TO START AUTOMATICALLY CC04 COMPONENT COOLING WATER SUPPLY VALVE TO RCP FAILS CLOSED CC05 COMPONENT COOLING WATER SYSTEM PIPING RUITURE CC06 CCW VALVE FAILURE TO AUTO OPEN TO RIIR HEAT EXCHANGER ON PUMP START CC08 COMPONENT COOLING SURGE TANK AUTO MAKEUP FAILURE CC09 SEAL WATER IIEAT EXCIIANGER LEAK CC100 RCP CCW SUPPLY ISOL A CC101 RCP CCW SUPPLY ISOL B CC102 UNIT I -UNIT 2 CCW X CONNECT CC103 CC OUTLET TEMP CONTROLLER SETPOTNT CC104 11 RCP COMP CLNT INLT/OUTL BKR CC105 12 RCP COMP CLNT INLT/OUTL BKR CC106 11 RCP BRG CLG WTR RETURN CC107 12 RCP BRG CLG WTR RETURN j l l i CC108 SURGE TANK XTIE ISOL VLV Containment / IIVAC System CII01 CONTAINMENT PRESSURE TRANSMITTER FAILURE Cll100 POST LOCA 112 CONTROL VENT Cll101 Ul CATI ANNUNCIATORS t ClI102 U2 CATI ANNUNCIATORS i

Cil103 121 CNTMT PURGE SUPPLY FAN Cil104 COh7 PURGE CONTROL CH105 121 CONT PURGE EXHAUST FAN Page 5

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1994 APPENDIX 2  ;

CH106 CNTMT HI PRESS B/S PC-945A CH107 CNTMT HI PRESS B/S PC-949A j CH108 CNTMT HI PRESS B/S PC 947A j CH109 CNTMT HI H1 PRESS B/S PC-946A CH110 CNTMT HI-HI PRESS B/S PC-948A CHI 11 CNTMT HI-HI PRESS B/S PC-950A Gil12 CNTMT HI-H1 PRESS B/S PC-945B CH113 CNTMT HI-HI PRESS B/S PC-946B CHI 14 CNTMT HI HI PRESS B/S PC-947B CH115 CNTMT HI-H1 PRESS B/S PC-948B CHI 16 CNTMT HI-HI PRESS B/S PC-949B Clll17 CNTMT HI-HI PRESS B/S PC-950B Clil18 121 LAUNDRY / LOCKER / FILTER ROOM EXHAUST FANS CHil9 CNMT CHILL WATER SYSTEM CH121 FIRE DETECTION ALARMS CH122 FIRE DETECTION ALARMS CH123 FIRE DETECTION ALARMS CH124 FIRE DETECTION ALARMS Clll25 FIRE DETECTION ALARMS CH126 121/122 CR CHILLER XOVER VLVS Gil27 RAD WASTE BLDG VENT Cill28 11/12 CRDM COIL SUPPLY / RETURN VLVS CH129 U1 CONTAINMENT ENTRY CH130 U1 CONTAINMENT EXIT CH131 11-14 CNTMT FCU COND COIL TK DRN CH132 11 FCU DISCH TO CNTMT GAP / DOME DAMPERS CH133 12 FCU DISCH TO CNTMT GAP / DOME DAMPERS CH134 13 FCU DISCH TO CNTMT GAP / DOME DAMPERS CH135 14 FCU DISCH TO CNTMT GAP / DOME DAMPERS CH136 11 FCU DISCH TO CNTMT GAP / DOME DAMPERS 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 C0oling Water System CL01 COOLING WATER PUMP TRIP CLO2 DIESEL COOLING WATER PUMP FAILS TO START AUTOMATICALLY CLO3 121 COOLING WATER PUMP FAILS TO START AUTOMATICALLY CLO4 DIESEL COOLING WATER PUMP TRIP CLO6 S AFEGUARDS COOLING WATER SUPPLY PIPING RUPTUPJi CL67 COOLING W ATER SYSTEM TURBINE BUILDING PIPE RUPTURE CLOS COOLING WATER LEAv. Id3?DE 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 RTN ORIFICE BP VLV LOCAL CS CL106 12/14 FCU CLG WTR RTN ORIFICE BP VLV LOCAL CS Page 6

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1994 APPENDIX 2 CL107 12 DSL CLG WTR PUMP LOCAL STOP CL108 22 DSL CLG WrR PUMP LOCAL STOP CL109 121 COOLING WATER PUMP SOURCE ALIGNMENT l CLI10 121 COOLING WATER PUMP BKR 25-01 f CLI11 121 COOLING WATER PUMP BKR 26-17 CLI12 TURB BLDG COOLING WATER HEADER CROSSTIE VLV CLI13 TURB BLDG COOLING WATER LEADER CROSSTIE VLV Reactor Core System CR01 FUEL CLADDING FAILURE CR02 GROSS FUEL FAILURE CR03 REACTOR COOLANT SYSTEM CRUD BURST CR04 FUEL CLADDING FAILURE Containment Spray System CS01 CONTAINMENT SPRAY PUMP TRIP CS02 CAUSTIC ADDITION VALVE FAILURE TO OPEN IN AUTOMATIC CS03 CONTAINMENT SPRAY PUMP FAILS TO START AUTOMATICALLY 11 CS SUCTION FROM RHR BKR CS100 CS101 12 CS SUCTION FROM RHR BKR CS102 CAUSTIC ADD TO 11 CS PUMP ISOL CS103 CAUSTIC ADD TO 12 CS PUMP ISOL Circulating Water System CWO2 CIRCULATING WATTER PUMP TRIP CWO3 CIRCULATING WATER PUMP BEARING FAILURE CWO4 CONDENSER TUBES PLUGGED CWO5 CONDENSER TUBE RUPTURE CWO6 TRAVELING SCREEN BLOCKAGE ON APPROACH CANAL CWO7 CONDENSER PIT FLOOD CW100 RIVER WA' ERTEMPERATURE CW101 BYPASS GATES MANUAL CONTROL CW102 CT EQUIPMENT HOUSE LOCAL ALARM RESET Emergency Diesel Generator 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 DG05 ELECTRONIC GOVERNOR FAILURE DG06 24VDC SPLY FOR ELECTRONIC GOVERNOR FAILS DG07 DIESEL GENERATOR EMERGENCY START FAILURE DG100 D1 LOCAL SHUTDOWN RELAY RESET PB DG101 D1 LOCAL 86 LO RELAY RESET DG102 D1 LOCAL ANNUNCIATOR SILENCE PB DG103 D1 hECHANICAL LINKAGE TO FUEL RACKS RESET DG104 D1 LOCAL PANEL STOP CS DG105 D2 LOCAL SIRTFDOWN RELAY RESET PB DG106 D2 LOCAL 86 LO RELAY RESET DG107 D2 LOCAL ANNUNCIATOR SILENCE PB Page 7

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1994 APPENDIX 2 DG108 D2 MECHANICAL LINKAGE TO FUEL RACKS RESET DG109 D2 LOCAL PANEL STOP CS DG110 D5 LOCAL 86 LO RELAY RESET DG112 D5 OVERSPEED DETECTOR RESET - FLYBALL hECH DG113 D5 LOCAL PANEL STOP CS DG114 D51,0 CAL GOVERNOR CONTROL DG115 D6 LOCAL 86 LO RELAY RESET DGl17 D6 OVERSPEED DETECTOR RESET - FLYBALL hECH DG118 D6 LOCAL PANEL STOP CS DG119 D6 LOCAL GOVERNOR CONTROL DG120 DS 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 EXCITER RESET LOCAL PB Electrical Distribution System 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 I M TRANSFORhER - DELAYED AUTO TRANSFER ED06 FAULT IN UNIT SUBSTATION TRANSFORMER ED07 LOSS OF 125 VDC BUS ED08 LOSS OF 120 VAC INSTRUMENT BUS ED09 LOSS OF 4160V BUS ED10 LOSS OF 480 VAC BUS ED12 LOAD SEQUENCER REJECTION FAILURE ED13 LOAD SEQUENCER RESTORATION FAILURE ED14 LOSS OF ALL OFFSITE AC POWER ED15 DEGRADED GRID VOLTAGE ED16 DEGRADED GRID FREQUENCY ED17 FAILURE OF 52Z LOAD SEQUENCER RELAY ED100 STA AUX MAIN TRANSFORhER 20KV DISCONNECTS ED101 10 BANK TO BUS CT12 ED102 ICT TO BUS CTil i ED103 161 KV BUS 1 TO 10 BANK i ED104 SPRING CREEK 161 KV TO 161 KV BUS 1 ED105 RED ROCK 2 345 KV LINE TO 345 KV BUS 1 ED106 RED ROCK 2 / BYRON 345 KV LINE ED107 BYRON 345 KV LINE TO 345 KV BUS 2 ED108 UNIT 2 345 KV TO 345 KV BUS 1 ED109 UNIT 2 / BLUE LAKE 345 KV LINE i EDI10 BLUE LAKE 345 KV LINE TO 345 KV BUS 2 EDI11 RED ROCK 345 KV LINE I TO 345 KV BUS 2 ED112 BUS 1345 KV TO 2RS TRANSFORhER MOD 4

EDI13 BUS 2 345 KV TO 10 BANK TRANSFORMER MOD ED114 2RS TRANSFORMER TO 2RY TRANSFORhER Page 8

i PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT  ;

1994 4

APPENDIX 2 ED115 2RS TRANSFORMER TO 2RXTRANSFORMER EDil6 SUBSTATION ALARM ANNUNCIATORRESET EDI17 1R-Y AUX TRANSFORMER BUSTIE BKR 1RYBT ED118 2R-Y AUX TRANSFORMER BUS TIE BKR 2RYBT ED119 iR-Y/2R-Y BUS TIE BKR 12RYBT ED120 1R-X/2R-X BUS TIE BKR 12RXBT ED121 1R X BUS DISCONNECT i ED122 1R-Y BUS DISCONNECT ED123 2R-X BUS DISCONNECT ED124 2R Y BUS DISCONNECT 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 7 ED128 4.16KV BUS SUPPLY BKR CTIl-1  :

ED129 4.16KV BUS SUPPLY BKR CT12-7 ED130 4.16KV CLNG TWR BUS TIE BKR CT-BT!!2 ED131 4.16KV BUS 11 IM XFMR BKR 11-4 ED132 4.16KV BUS 12 IM XFMR BKR 12-4 ED133 4.16KV BUS 13 IM XFMR BKR 13 9 ED134 4.16KV BUS 14 IM XFMR BKR 14-9 ED135 4.16KV BUS 13 PUMP OVERLOAD RELAYS RESET ED136 4.16KV BUS 14 PUMP OVERLOAD RELAYS RESET ED137 480V BUS 111 SUPPLY BKR IIIM ED138 480V BUS 112 SUPPLY BKR 112M ,

l ED139 480V BUS 121 SUPPLY BKR 121M ED140 480V BUS 122 SUPPLY BKR 122M ED141 4.16KV BUS 25 SOURCE TO BUS 111/112 BKR 25-15 ED142 4.16KV BUS 26 SOURCE TO BUS 121/122 BKR 26-03 ED143 480V BUS 111 SUPPLY BKR 1II A ED144 480V BUS 112 SUPPLY BKR 112A ED145 480V BUS 121 SUPPLY BKR 121 A ED146 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 BKR 15M ED150 480V BUS 160 SUPPLY BKR 16M ED151 480V BUS 190 SUPPLY BKR 19M ED152 480V MCC 1 ABI SUPPLY TRANSFER SWITCH ED153 480V MCC 1 AB2 SUPPLY TRANSFER SWITCH ED154 480V MCC ITI SUPPLY TRANSFER SWITCH ED155 480V MCC IT2 SUPPLY TRANSFER SWITCH ED156 4.16KV CLNG TWR BT CT-BTil2 AUTO. MAN SWITCH Electrical Generation System EGO 1 GENERATOR OUTPUT BREAKER FAILS TO OPEN FOLLOWING TURBINE TRIP EG02 LOSS OF GENERATOR HYDROGEN COOLING j EG03 GENERATOR OUTPUT BREAKERS FAIL OPEN EGOS GENERATOR VOLTAGE REGULATOR FAILURE EG06 GENERATOR FAULT Page 9 1

- , _-_ 0

PFAIRIE ISLAND SU"JIATOR CERTIFICATION REPORT 1994 APPENDIX 2 EG07 GENERATOR LOSS OF EXCITATION EG100 GENERATOR H2 SUPPLY EG101 GENERATOR CO2 SUPPLY EG102 GENERATOR GAS VENT EG103 HYDROGEN SIDE SEAL OIL PUMP EG104 AIR SIDE SEAL OIL PUMP EG108 GEN XFMR 345 KV DISCONNECTS EG109 MAIN GENERATOR OUTPUT DISCONNECT LINKS EGl10 AIR SIDE SEAL OIL BACKUP PUMP EGl11 AIR SIDE SEAL OIL BACKUP PUMP EGil2 86-lG/86-lGT RESET Condensate and Feedwater System FWOI CONDENSATE PUMP TRIP FWO2 13 CONDENSATE PUMP FAILS TO START AUTOMATICt.LLY f WO3 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 FW13 MAIN FEEDWATER PUMP TRIP FW17 FEEDWATER HP HEATER LEAK FW18 FEEDWATER LPIEATER LEAK FW19 FEEDWATER SYSTEM RUPTURE INSIDE CONTAINhENT FW20 FEEDWATER SYSTEM LEAKAGE INSIDE CONTAINhENT FW21 FEEDWATER SYSTEM RUPTURE INSIDE CONTAINMENT UPSTREAM OF CHECK VALVE FW22 FEEDWATER SYSTEM RUPTURE OUTSIDE CONTAlh%ENT FW23 FEEDWATER SYSTEM LEAKAGE OUTSIDE CONTAINhENT FW24 FEEDWATER PUMP COMMON DISCHARGE HEADER RUPTURE FW25 FEEDWATER FLOW CONTROL VALVE FAILS TO CLOSE ON FW ISOLATION SIGNAL FW26 FEEDWATER FLOW CONTROL VALVE FAILS OPEN FW27 FEEDWATER FLOW CONTROL VALVE FAILS CLOSED FW28 IEATER DRAIN PUMP TRIP FW29 HEATER DRA!N TANK LEVEL TRANSMITTER FAILS HIGH FW30 IEATER DRAIN TANK LEVEL TRANSM11TER FAILS LOW FW31 IEATER DRAIN PUMP FAILS TO MINIMUM FW32 AUXILI ARY FEEDWATER PUMP TRIP - MOTOR FW33 AUXILIARY FEEDWATER PUMP TRIP - TL1tBINE FW34 AUX 1LIARY FEEDWATER PUMP FAILS TO START AUTOMATICALLY FW35 INADEQUATE CONDENSATE TO AUXILIARY FEEDWATER PUMP SUCTION FW36 AUXILIARY FEEDWATER DISCHARGE LINE RUPTURE INSIDE CONTAINMENT FW37 AUXILIARY FEEDWATER DISCHARGE LINE RUlrFURE OUFSIDE COhTAINhENT FW38 AUXILI ARY FEEDWATER CONTROL VALVE FAILS IN POSITION FW39 FEEDWATER LINE RUPTURE UPSTREAM OF FW REG VALVES FW40 COMMON FEEDWATER PUMP SUCTION LINE BLOCKAGE FW41 FEEDWATER FLOW CON 1' .0L VALVE LEAKAGE Page 10

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1994 APPENDIX 2 FW100 11-12-13 LP FW HTR BYPASS FW101 TDAFWP 1A ISOL TO CV 31998 FW102 CST XCONNECT FW103 AFW TO 11 SG CNMT ISO BKR FW104 AFW TO 12 SG CNMTISO BKR FWIO5 11 A 12A-13A FW HTR ISOL FW106 11B-128-13B FW HTR ISOL FW107 14A FW HTR ISOL FW108 14B FW HTR ISOL FW109 14A FW HTR BYPASS FW110 14B FW HTR BYPASS FWI11 COND MAKEUP MANUAL BYPASS FW112 15A HTRISOL FW113 15B FWllTRISOL FW114 15A FW HTR BYPASS FWil5 15B HTR BYPASS FWil6 15A TO 14A IITR RESET PB FWil7 15B TO 14B HTR RESET PB FW118 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-191 FW123 IA ISOL 11 FW PUMP RECIR VLV FW124 1A 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 11 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 IB STM GEN, MV-32239 FW136 12 MDAFW PUMP TO 1 A STM GEN, MV 32381 FW137 12 MDAFW PUMP TO IB STM GEN, MV 32239 FW138 11 CONDENSATE RECYCLE PUMP FW139 11/21 CST LEVEL ADJUSTMENT

, Compressed Air System IA01 LOSS OF SERVICE AIR HEADER IA02 LOSS OF INSTRUMENT AIR HEADER IA03 LOSS OF AIR COMPRESSOR f IA100 POLISH AIRTO STATION AIR j IA101 POLISil AIRTOINST AIR IA102 121 FILTER DRYER BYPASS RESET IA103 122 FILTER DRYER BYPASS RESET Page 11 l

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1994 APPENDIX 2 Main Steam System MS01 MAIN STEAM LINE RUPTURE INSIDE CONTAINMENT UPSTREAM OF MSIV MS02 MAIN STEAM LINE RUPTURE OUTSIDE CONTAINMENT UPSTREAM OF MSIV 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 MS08 MOISTURE SEPARATOR - REHEATER RELIEF VALVES FAILURE MSO9 MAIN STEAM LINE LEAK INSIDE CONTAINMENT MS10 MAIN STEAM LINE BREAK ON COMMON SUPPLY LINE TO AFW MSil STEAM DUMP VALVE FAILS IN POSITION MS100 11 SG PORV ISOL i MS101 12 SG PORV ISOL MS102 11 SG ATMOS STM DUMP ISOL MS103 11 SG ATMOS STM DUMP ISOL MS104 12 SG ATMOS STM DUMP ISOL MS105 12 SG ATMOS STM DUMPISOL MS106 COND STM DUMP ISOL MS107 COND STM DUMP BYPASS ISOL MS108 I A MSR STM SUP ISOL MS109 IB MSR STM SUP ISOL MSil0 2A MSR STM SUP ISOL MSill ,

2B MSR STM SUP ISOL MSil2 11 SAFETY VALVE IIDR VENT MSI13 12 SAFETY VALVE IIDR VENT MSil4 1 A MSR CV BYPASS MSil5 IB MSR CV BYPASS MSil6 2A MSR CVi3YPASS MSil7 2!! MSR CV BYPASS MSils MSR TO 11 liTR DRAIN TANK STOP CV RESET PB MSI10 IIP TURBINE BLADING REMOVED MS120 LP TURBINE BLADING REMOVED MS121 1 A SG IORV 1A ISOL MS122 1 A SG PORV LOCAL CNTROL VLV POSITION

, MS123 IB SG PORV 1A ISOL l MS124 IB SG PORV LOCAL CNTROL VLV POSITION MS125 lil!ATING STM SUPPLY TO AUX MAIN STM MS126 RiiTR DRN TNK TO 15 FW llTR CV RESET PB Nuclear Instrumentation System N101 INCORRECT SOURCE RANGE CilANNEL RESIONSE N102 SOURCE RANGE CllANNEL SPIKES N103 INTERMEDI ATE RANGE CIIANNEL IMPROPER RESPONSE N104 INTERMEDIATE RANGE CllANNEL IMPROPER COMPENSATION N105 IMPROPER POWER CilANNEL RESPONSE N106 POWER RANGE UPPER CilANNEL IMPROPER RESPONSE N107 POWER RANGE LOWER CIIANNEL IMPROPER RESPONSE NI100 CllANNEL I PWR RNG 111 Q- HI F B/S Page 12

I PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT (

1994 APPENDIX 2 N1101 CHANNEL 2 PWR RNG HI Q -HI F B/S N1102 CHANNEL 3 PWR RNG HI Q -111 F B/S N1103 CHANNEL 4 PWR RNG HI Q -HI F B/S nil 04 CHANNEL 1 PWR RNG LO Q - HI F B/S N1105 CHANNEL 2 PWR RNG LO Q - HIF B/S nil 06 CllANNEL 3 PWR RNG LO Q - HI F B/S Nil 07 CHANNEL 4 PWR RNG LO Q -HIF B/S N1108 CHANNEL 1 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 Nill 2 POWER RANGE P-10 B/S NC-41 M Nil 13 POWER RANGE P-10 B/S NC-42 M Nil 14 POWER RANGE P-10 B/S NC-43 M Nil 15 POWER RANGE P-10 B/S NC-44 M nil 16 POWER RANGE P-8 B/S NC-41 N N1117 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 Nil 23 CHANNEL 2 POSITIVE RATE B/S NI124 CHANNEL 3 POSITIVE RATE B/S N1125 CilANNEL 4 POSITIVE RATE B/S Nil 26 CHANNEL 1 NEGATIVE RATE B/S NI127 CHANNEL 2 NEGATIVE RATE B/S Nil 28 CHANNEL 3 NEGATIVE RATE B/S NI129 CHANNEL 4 NEGATIVE RATE B/S NI130 CHANNEL 1/2 SOURCE RANGE HI FLUX AT SD SETPOlhT nil 31 CHANNEL 1 P9 B/S NI132 CHANNEL 2 P9 B/S Nil 33 CllANNEL 3 P9 B/S Nil 34 CilANNEL 4 P9 B/S NI135 CilANNEL 1 INT RNG ROD BLOCK B/S NC-35B nil 36 CHANNEL 2 INT RNG ROD BLOCK B/S NC-36B N1137 CHANNEL 1 PWR RNG ROD BLOCK B/S NC--41L nil 38 CHANNEL 2 PWR RNG ROD BLOCK B/S NC-42L Nll39 CHANNEL 3 PWR RNG ROD BLOCK B/S NC-43L Nil 40 CHANNEL 4 PWR RNG ROD BLOCK B/S NC-44L Plant Process Computer System PC01 ERCS CPU FAILURE PC03 ERCS ALARM DISPLAY TAILURE PC04 ERCS SAS DISPLAY FAILURE i PCOS ERCS CONTROL ROOM PRINTER FAILURE I PC100 ACKNOWLEDGE UNIT 2 ERCS ALARMS Reactor Coolant System Page 13

f PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1994 APPENDIX 2 RC01 REACTOR COOLANT PUMP TRIP j RCO2 REACTOR COOLANT PUMP LOCKED ROTOR  :

i RC04 REACTOR COOLANT PUMP SHAFT SIIEAR RC05 REACTOR COOLANT PUMP BEARING FAILURE .

RC06 LOSS OF COOLANT ACCIDENT- HOT LEG RC07 LOSS OF COOLANT ACCIDENT - COLD LEG RCP SUCTION  !

LOSS OF COOLANT ACCIDENT - COLD LEG RCP DISCHARGE RC08 i

RC09 LOSS OF COOLANT ACCIDENT PRESSURIZER STEAM SPACE RC10 LOSS OF COOLANT ACCIDENT PRESSURIZER WATER SPACE [

RCll LOSS OF COOLANT ACCIDENT - RTD BYPASS LOOP COLD LEG MANIFOLD  ;

RCl2 LOSS OF COOLANT ACCIDENT - RTD BYPASS LOOP RETURN LEG PIPING j RCl3 LOSS OF COOLANT ACCIDENT - REACTOR HEAD VENT RCl4 REACTOR COOLANT SYSTEM LEAKS j

RCIS REACTOR COOLANT SYSTEM LEAKS PRESSURIZER POWER OPERATED RELIEF VALVE FAILS CLOSED {

RC16 RCIS PRESSURIZER SAFETY VALVE RC-10-1 FAILS OPEN RC19 PRESSURIZER SAFETY VALVE SEAT LEAKS RC20 REACTOR COOLANT PUMP OIL LEAK UPPER RESERVOIR i

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 LEVELIND RC193 PRZR SPRAY BYPASS LOOP B RCibt PRZR SPRAY BYPASS LOOP A RC10$ LOOP A RTD BYPASS ISOL RC106 LOOP B RTD BYPASSISOL RC107 RX VESSEL INNER SEAL LEAKOFF RC108 RX VESSEL OUTER SEAL LEAKOFF ,

RC109 LOOP A HOT LEG DRAIN TO RCDT RCl10 PRZR STEAM SPACE SAMPLE RCI11 COLD LEG LEVELISOLATION VALVES RCl12 11 STM GEN TUBES PLUGGED RCl13 12 STM GEN TUBES PLUGGED RCI14 SHUT 9OWN PURIFICATION TO RCDT RC115 PRZR SPRAY LOOP ISOL RCl16 LOOP A COMMUNICATION LINE f RCl17 RCGV llEAD VENT ORIFICE BYPASS RCl18 ENABLE ULTRASONIC LEVEL INDICATING SYSTEM RCI19 PRT NITROGEN ISOLATION VALVE RCl20 RCS LOOP A NITROGEN SUPPLY RC121 RCS LOOP B NITROGEN SUPPLY Control Rod Drive System RD01 CONTROLLING ROD BANK FAILS 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 Page 14

- PRAIRIE ISLAND SIMUIATOR CERTIFICATION REPORT 1994 APPENDIX 2 RDOS CONTROL ROD MISALIGNMENT RD06 STUCK ROD RD07 DROPPED ROD RD08 CONTROL ROD G-3 EJECTED RD09 ROD POSITION INDICATION FAILS ,

RD10 INCORRECT ROD SPEED P4100 11 ROD DRIVE MG kd101 12 ROD DRIVE MG RD102 RPI SUPPLY FRM INV 15/FROM PNL i17 RD103 BANK D ROD BLOCK B/S TC-405K RD104 SET CONTROL BANK A P/A CONV '

RD105 SET CONTROL BAMK B P/A CONV RD106 SET CONTROL BANK C P/A CONV i

RD107 SET CONTROL BANK D P/A CONV RD113 INV i15/ PANEL 117, CKT 13 POWER TO IRPI STACKS Residual Heat Removal System ,

l RH01 RESIDUALIIEAT REMOVAL PUMP TRIP R1102 RESIDUAL lEAT REMOVAL PUMP FAILS TO START AUTOMATICALLY l R1103 RHR lEAT EXCHANGER END BELL LEAKAGE TO ATMOSPHERE RH04 RHR IEAT EXCHANGER BYPASS VALVE FAILS OPEN l RH05 RIIR lEAT EXCilANGER BYPASS VALVE FAILS CLOSED RH06 RECIRCULATION SUMP SUCTION LINES BLOCKED RIIR SYSTEM LEAKAGE j R1107 I

RH08 RifR PUMP SEAL FAILURE .

R1109 RESIDUAL REAT REMOVAL RELIEF VALVE FAILURE Ril100 11 RHR HX INLET X-CONN, RH-2-4 l Ril101 12 RHR HX INLET X-CONN, RH-2-3 RH102 11 RHR HX OUTLET X-CONN, RH 2-6 Ril103 12 RHR HX OUTLET X-CONN, RH-2 5 Ril104 LOOP A HOT LEG MV-32164 BKR RH105 LOOP B HOT LEG MV-32230 BKR Ril106 12 RHR PMP DSCHG TO SUMP RH107 LOOP B RETISO BKR RH108 11 RHR HEAT EXCHANGER INLET ISOL RH-1-4 RH109 12 RIIR IIEAT EXCHANGER INLET ISOL RH-1 3 Rlil10 11 RHR (CV-31235) MECHANICAL STOP RH111 12 RIIR(CV-31236) MECHANICAL STOP RH112 11 RHR PUMP SUCTION VALVE Rlil13 12 RHR PUMP SUCTION VALVE Rlil14 RHR TO CVCS LETDOWN LINE i RH115 LOOP A HOT LEG MV-32165 BKR Rlill6 LOOP B HOT LEG MV-32231 BKR RH117 RHR TO LETDOWN MV 32234 BREAKER Reactor Protection System RP01 REACIOR TRIP RP02 FAILURE OF ALTTOMATIC REACTOR TRIPS RP03 FAILURE OF SAFETY SYSTEMS TO ACTUATE Page 15

)

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1994 APPENDIX 2 RPO4 INADVERTENT ACTUATION OF THE SAFETY INJECTION SYSTEM RP05 FAILURE OF CONTAINMENT ISOLATION PHASE A TO ACTUATE RP06 FAILURE OF MSIVS TO ISOLATE RP07 MECHANICAL FAILURE OF REACTOR TRIP BREAKERS RPOR 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 B LOOP B/S FC-414 RP106 3 LOW RC FLOW B LOOP B/S FC-415 RP107 4 LOW RC FLOW B LOOP B/S FC-416 RP108 CHANNEL 1 RCP BKR OPEN B/S RP109 CHANNEL 2 RCP BKR OPEN B/S RPI10 1 PRZR PRESSURE HI B/S PC,-429A RPI11 1 PRZR PRESSURE SI B/S PC-429C RPI12 1 PRZR PRESSURE SI UNBLOCK B/S PC-429D RPI13 i PRZR PRESSURE LO B/S PC-429E RPI14 11 STM LOOP LO-LO PRESS B/S PC-468A RPI15 11 STM LOOP LO-LO PRESS B/S PC-469A RPI16 11 STM LOOP LO-LO PRESS B/S PC-482A RPI17 1 PRZR HIGH LVL B/S LC-426A RPl18 2 PRZR HIGH LVL B/S LC-427A RPI19 3 PRZR HIGH LVL B/S LC-428A RP120 3 PRZR PRESSURE HI B/S PC-431 A RP121 3 PRZR PRESSURE S1 B/S PC-43IG 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 SiG HI 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 RP132 12 S/G HI 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 RPl35 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 I RPl41 1 Ui STM FLOW FC-464 A l

RP142 i HI-HI STM FLOW FC-464B RP143 3 HI STM FLOW FC-474A RP144 3 lil-HI STM FLOW FC-474B Page 16 l

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1994 APPENDIX 2 RP148 AMSAC BLOCK SWITCH RP149 AMSAC ACTUATION SIGNAL RESET RP152 CIIANNEL 1 BUS 11 UNDERVOLTAGE B/S RP153 CHANNEL 2 BUS 11 UNDERVOLTAGE B/S RP154 CHANNEL 3 BUS 12 UNDERVOLTAGE B/S RP155 CHANNEL 4 BUS 12 UNDERVOLTAGE B/S RP156 12 STM LOOP LO-LO PRESS B/S PC-483 A 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 RP162 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-4010 RP165 2 RC LOOP LO TAVG B/S TC-402F RP166 2 RC LOOP LO-LO TAVG B/S TC-402D RP167 OPPS HI PRESSURE B/S PC-419D RPl68 OPPS HI 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-40-5B RPl71 1 RC LOOP OT DELTA T B/S TC-405C RPl72 1 RC LOOP OT DELTA T B/S TC-40-5D RP181 2 TURBINE POWER P-7 B/S PC-485A RPl82 3 TURBINE POWER P-7 B/S PC-486A RP183 11 BUS UNDERFREQUENCY B/S RP184 11 BUS UNDERFREQUENCY B/S RP185 12 BUS UNDERFREQUENCY B/S RP186 12 BUS UNDERFREQUENCY B/S RP187 2 PRZR PRESSURE HI B/S PC-430A RP188 2 PRZR PRESSURE SI B/S PC-430E RP189 2 PRZR PRESSUPI SI UNBLOCK B/S PC,-4 30F RP190 2 PRZR PRESSURE LO B/S PC-430H RP191 11 S/G LO-LO LVL B/S LC-463C RP192 11 S/G HI LVL B/S LC-463D RP193 2 HI STM FLOW FC-465A RP194 2 HI-HI STM FLOW FC-465B RP195 4 HI STM FLOW FC-475A RPl% 4 HI-H1 STM FLOW FC-475B RP199 3 RP LOOP OP DlILTA 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 t 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 Page 17

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1994 APPENDIX 2 f

RP208 3 RC LOOP LO-LO TAVG B/S TC-403D t RP209 4 RC LOOP LO TAVC B/STC-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 HI LVL B/S LC-471 A Reactor Control System RX01 PRESSURIZER SPRAY VALVE FAILS OPEN RX02 PRESSURIZER SPRAY VALVES PCV-431 A & B FAIL CLOSE9 RXO3 PRESSURIZER HEATERS FAIL ON RXO4 PRESSURIZER HEATERS FAIL OFF(ALL)

RX05 REACTOR COOLANT LOOP TH TRANSMITTER FAILS HIGH RXO6 REACTOR COOLANT LOOP TH TRANSMITTER FAILS LOW RXO7 REACTOR COOLANT LOOP TC TRANSMITTER FAILS HIGH RX08 REACTOR COOLANT LOOP TC TRANSMITTER FAILS LOW RXO9 PRESSURIZER LEVEL NARROW RANGE TRANSMITTER FAILS HIGH RX10 PRESSURIZER LEVEL NARROW RANGE TRANSMITTER LOW RXI1 PRESSURIZER PRESSURE TRANSMITTER FAILS HIGH RX12 PRESSURIZER PRESSURE TRANSMTITER FAILS LOW RX13 RCS WIDE RANGE PRESSURE TRANSMITTER FAILS HIGli RX14 RCS WIDE RANGE PRESSURE TRANSMITTER FAILS LOW RX15 STEAM GENERATOR LEVEL TRANSMITTER FAILS HIGH RX16 STEAM GENERATOR LEVEL TRANSMITTER FAILS LOW RX17 STEAM GENERATOR PRESSURE TRANSMITTER FAILS HIGH RX18 STEAM GENERATOR PRESSURE TRANSMITTER FAILS LOW RX19 MAIN STEAM LINE STEAM FLOW TRANSMITTER FAILS HIGH RX20 MAIN STEAM LINE STEAM FLOW TRANSMITTER FAILS LOW RX22 FEEDWATER CONTROLLER OUTPUT FAILURE RX23 FEEDWATER LINE FLOW TRANSMITTER FAILS HIGH RX24 FEEDWATER LINE FLOW TRANSMITTER FAILS LOW RX25 TURBINE FIRST STAGE PRESSURE TRANSMTITER FAILS HIGH RX26 TURBINE FIRST STAGE PRESSURE TRANSMITTER FAILS LOW RX27 STM GEN FEEDWATER INLET TEMPERATURE TRANSMITTER FAILS HIGH RX28 STM GEN FEEDWATER INLET TEMPERATURE TRANSMITTER FAILS LOW RX29 FEEDWATER HEADER PRESSURE TRANSMITTER FAILS HIGH RX30 FEEDWATER HEADER PRESSURE TRANSMITTER FAILS LOW RX31 STEAM GENERATOR WIDE RANGE LEVEL TRANSMITTER FAILS HIGH RX32 STEAM GENERATOR WIDE RANGE LEVEL TRANSMITTER FAILS LOW RX33 STEAM GENERATOR FEEDWATER CONTROL SYSTEM FAILS TO MANUAL RX34 ADFCS MAIN FLOW CONTROL VALVE OUTPUT CARD FAILURE RX35 ADFCS BYPASS FLOW CONTROL VALVE OUTPUT CARD FAILURE

. RX100 PRZR HTR GROUP B RX101 IMPULSE PRESS ROD BLOCK B/S PC-485C l

i RX102 IMPULSE PRESS STM DUMP B/S PC-486C

! RX103 1 PRZR HI PRESS PORY B/S T/P-429B l RX104 2 PRZR HI PRESS PORV B/S PC-430B j f RX105 3 PRZR HI PRESS PORV B/S PC-431B 1 i

• I RX106 4 PRZR HI PRESS PORV B/S T/P-449B RX107 PRZR LO PRESS BU HTRS B/S PC-431E Page 18

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT ,

1994 APPENDIX 2 I

RX108 ADFCS SIGNAL SELECTOR LOGIC RESET RX109 ADFCS LOSS OF WIDE RANGE LEVEL LOGIC PISET Steam Generator System .

SG01 STEAM GENERATOR TUBE LEAK SG02 STEAM GENERATOR TUBE RUPTURE SG03 STEAM GENERATOR BLOWDOWN CONTROL VALVE FAILS OPEN l SG100 SG BLOWDOWN DISCHARGE  !

SG101 SG BLOWDOWN RESET l l

SG102 11 SG BD SAMPLE ISOL VLV LOCAL CS SG103 11 SG BD SAMPLE ISOL VLV LOCAL CS SG104 12 SG BD SAMPLE ISOL VLV LOCAL CS SG105 12 I'G BD SAMPLE ISOL VLV LOCAL CS .-

SaMy Ir,jection System .

S10 1 BOTH BORJC ACID TANK VALVES FAIL TO OPEN IN AUTO S102 SI LOOP A COLD LEG INJ CHECK VALVE FAILUPE SIO3 BA TNK VLV FAILS TO CLOSE ON LO-LO LVL IN THE SELECTED BA TNK IN AUTO ,

S104 SAFETY INJECTION PUMP TRIPS S10 5 SAFETY INJECTION PUMP FAILS TO START AUTOMATICALLY i S106 St ACCUMULATOR LEAKAGE SIO7 SI ACCUMULATOR CHECK VALVE LEAKAGE S108 St ACCUMULATOR RELIEF VALVE LEAKAGE S10 9 SI COLD LEG INJ LINE RUPTURE INSIDE OF THE ANNULUS Sil00 11/121 BAST SUPPLY TO SIS SI101 SITEST LINE S1102 BA BLENDER TO RWST l i

S1103 11/12 51 PMP DISCHG X-CONN SIl04 11 S1 PUluP DISCHARGE VLV S1105 12 St PUMP DISCHARGE VLV

, S1106 BA SPLY TO SI PMPS (32083) BKR  ;

S1107 11 SI SUCTION FROM RHR BKR S1108 12 SI SUCTION FROM RHR BKR SI109 S1TO COLD LEGS CNMTISO BKR Sil10 SI TO LOOP B COLD LEG BKR Sil11 Si TO LOOP A COLD LEG BKR S1112 11 ACCUM OUTL VLV BKR SI113 12 ACCUM OUTL VLV BKR Sil14 S1 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 ,

i TC04 TURBINE CONTROL VALVE FAILS OPEN TC05 TURBINE CONTROL VALVE FAILS CLOSED TC06 REACTOR PROTECTION SYSTEM FAILS TO TRIP TURBINE TC07 TURBINE CONTROL INTERCEPT VALVE FAILS CLOSED l TC08 TURBINE CONTROL FAILURE DURING TURBINE ROLL Page 19 I

I I

- - - -,-.y s ,% ., -w- -

l I

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1994 j APPENDIX 2 l TC09 TURBINE CONTROL FAILURE CAUSING TURBINE RUNBACK TC10 TURBINE CONTROL FAILURE CAUSING AN INCREASE IN POWER WITHOUT DEMAND TCl1 TURBINE TRIP FAILURE I TCl2 TURBINE TRIP TCl3 ELECTRICAL HYDRAULIC CONTROL PUMP TRIP TCl4 TURBINE CONTROL VALVE FAILS IN POSITION TC100 TURBINE PEDESTAL TRIP TC101 CIIANNEL 2 TURB AUTO STOP B/S j TC102 CHANNEL 3 TURB AUTO STOP B/S TC103 CllANNEL 4 TURB AUTO STOP B/S l TC104 TURBINE LEFT STOP VLV CLOSED B/S TC105 TURBINE RIGHT STOP VLV CLOSED B/S Turbine System 1001 LOSS OF TURBINE LUBE OIL SUPPLY TUO2 TURBINE GENERATOR VIBRATION Chemical and Volume Control System j REACTOR COOLANT PUMP #1 SEAL FAILURE j VC01 VCO2 REACTOR COOLANT PUMP #2 SEAL FAILURE VC04 POSITIVE DISPLACEMENT CHARGING PUMP TRIP VJ05 STUCK OPEN CHARGING PUMP RELIEF VALVE VC06 REGENERATIVE HEAT EXCHANGER LEAKAGE VC07 LETDOWN HEAT EXCHANGER LEAKAGE TO ATMOSPHERE LETDOWN HEAT EXCHANGER TUBE RUPTURE TO CCW SYSTEM  ;

VC08 VC09 LETDOWN LINE LEAKAGE INSIDE CONTAINMENT VC10 CHARGING PUMP COMMON DISCHARGE HEADER RUPTURE l l

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 CHARGING PUMP SPEED CONTROLLER VC20 CCW RETURN FROM LETDOWN HEAT EXCHANGER FAILS CLOSED VC21 REACTOR COOLANT PUMP THERMAL BARRIER TUBE FAILURE VC100 11 RCP SEAL INJ THROTTLE 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 VC107 11/12 DEBORATING DEMIN VC108 RM STORAGE TANK PUMP SUCTION SELECTOR VC109 MANUAL BORATE FROM RWST VCl10 BLENDER BYPASS VCl11 VCT PURGE TO HIGH LVL LOOP VCil2 RMU TO CHG PUMP SUCTION VCll3 11 CHG PUMP SPEED REMOTE VCll4 12 CHG PUMP SPEED REMOTE Page 20 l

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1994 APPENDIX 2 VCl15 13 CHG PUMP SPEED REMOTE VCl16 11/12 LETDOWN FILTER OUTLET VC117 BORON CONCENTRATION VCl18 LETDOWN FILTERS BYPASS VC119 H2 SUPPLY TO VCT VCl20 SEAL WTR RTRN ISOL VC121 11 BAST LEVEL VC122 12i BAST LEVEL VC123 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 DEBORATEIX BORON CONC VCl28 12 DEBORATEIX BORON CONC VCl29 EMERGENCY DORATION VALVE VC130 LOOP B CHARGING LINE BYPASS VC131 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 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 DSCH VLV WL-87-1 WD105 12 RHR FIT SUMP PMP DSCH VLV WL-87-2 WD106 LOCAL RESET PB 54700-08 WD107 RCDT FILTERINLET AND B-P VLVS WD108 PURIFICATION JUMPERISOL VLVS WD109 11 REFUELING WATER PURIFICATION PUMP WD110 RCDT VENT AND VACUUM BREAKER ISOLATION VALVES Table 2A shows the current set of protected initial conditions to be used for training. These 26 initial conditions are protected from inadvertent modification and are kept updated as the simulation models are modified. An additional 19 initial conditions are 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.

Page 21

Table 2A M 104OM W O O O H Y 1 M W A i? % RXLU1;i ( *F WY! M  :

?

TIME IN DATE BORON ROD PZR 1.C. CYCLE SHOT CONC IEIGiff XENON TAVG PRESS PWR REMARKS 1 BOC 9/10S4 1610 SDO NONE 317 368 250 CPS HU IN PROGRESS / PZR BUBBIE ARI NONE 131 15 80 CPS COLD S/D 3% S/D,30% PZR LVL 2 '80C 6/25/93 1599 3 MOC %'ic,M 1550 ARI NONE 121 15 15 CPS COLD S/D,3% S/D,RCS SOLID 4 BOC 6/25/93 1610 SDO NONE 340 414 200 CPS IEATUPINPROGRESS S BOC 9/10S 4 1339 SDO NONE 546 2240 90 CPS HOT S/D.ECC:1339 PPM @ 100 STEPS ON D 6 BOC 9/10/94 1339 D @ l16 INC 548 2242 4% PRIOR TO ROU.ING TURBINE i 7 BOC 9/10/94 1342 D @ 119 INC 549 2243 4% PRIORTO SYNCHRONIZING GENERATOR 553 2240 52 % ONE IIDT,COND, AND FW PUMP IN SERVICE 8 BOC 9/10/94 1073 D @ 203 EQUIL 9 BOC 9/10S4 950 D @ 218 EQUIL 560 2240 ;00 % 100% TARGET DELTA I = +0.6 10 MOC 9/10/94 502 D @ 218 EQUIL $60 2MO 100 % 100% TARGET DELTA 1 = -0.9 11 EOC 9/10S4 210 D @ 218 EQUIL 560 2240 100 % 100% TARGET DELTA 1 = -1.4 12 EOC 9/1064 221 D @ 155 INC 553 2240 62 % PWR REDUCTION TO 60% FROM 100% AT 1%/ MIN PRIOR TO SECURING MFWP 13 EOC 9/10/94 187 D @ 65 INC 548 2240 22 % PRIOR TO SEPARATING UNIT. 90 MWE 550 SDO NONE 546 2240 200 CPS BORATED TO ECC BORON, VACUUM IN COND 14 EOC 9/10/94 ECC:550 PPM @ 100 STEPS ON D SDO NONE 352 337 50 CPS C/ DIN PROGRESS, PRIOR 10 PLACINO RHR 15 EOC 9/10/94 1235 IN-SERVICE. ATCOLDS/DBORONCONC 16 MOC 9/10/94 1 D @ 160 INC 547 2235 11 % LOAD INCREASE 17 CDC 9/10/94 0 D @ 228 EQUIL 557 2240  %% COASlDOWN AT EOC 18 MOC 9/10/94 868 D @ l14 NONE 546 2242 2E-09 PLANT STARTUP IN PROGRESS INC 553 2240 52 % LOAD INCREASE; 2 COND, HDT, MFW PUMPS 19 MOC 9/10/94 676 D @ 188 20 MOC 9/10S4 488 SDO INC 546 2240 200 CPS 2 IIRS FOLLOWING RX TRIP FROM 100% PWR.

ECC:488 PPM @ 100 STEPS ON D 559 2240 90 % LOAD DECREASE; XENON PEAKED - DECREASING 21 MOC 9/10/94 507 D @ 2to PEAK 22 EOC 9/10 S 4 117 SDO PEAK 546 2240 350 CPS 10 HRS FOLLOWING RX1 RIP FROM 100% PWR ECC:117 PPM @ 100 STEPS ON D 23 MOC 9/10/94 502 D @ 188 PEAK 553 2240 52 % 6 HRS FOLLOWING LOAD REDUCTION FROM 100% POWER 24 BOC 9/1064 1060 D @ 202 DEC 557 2241 78 % LOADINCREASE FROM 50%

25 MOC 9/10/94 512 D@ 189 INC 555 2240 71 % LOAD DECREASE 546 2240 1.0E-9 POSITIVE ITC, STARTUP IN PROGRESS 26 ZBC 9/10/94 1420 D @ 100 NONE NIS GAIN POT SETTINGS: N41 4.75 N43 4.76 N42 4.76 N44 4.78

i PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1994 APPENDIX 3 Certification Review Panel Members The Certification Review Panel makeup is spelled out in Simulator Procedure #20. This panel consists of the S sperintendent, 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:

Superintendent, Sinulator Engineering - Michael Johnson Educational

Background:

Bachelor of Electrical Engincering University of Minnesota 1979 Experience: Eight years as a plant Systems Engineei at the Prairie Island Nuclear Plant Six years as the Simulator Engineering Supervisor for the Prairie Island Plant Simulator Certifications: F rairie Island Senior Reactor License 4/30/85 (Allowed to lapse 12/31/88) l Plant Operations - John Reuter, Operations Shift Supervisor Educational

Background:

Over 3 years college education. Near completion of BS  !

degree in Applied Nuclear Science Experience: Over tv.u:4y-seven years nuclear power plant experience.

Seven years US Navy Nuclear program as machinist mate.

Twenty years at Prairie Island in operations, fifteen years as union operator and five years as Shift Supervisor.

Four years as Operations Liaison with Production Training.

Certifications: Prairie Island Reactor Operator License Prairie Island Senior Reactor Operator License l

Page 1

l l

l PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1994 1

APft.NDIX 3 l l

Operations Training - David Reynolds, Superintendent of Operations Training Educational

Background:

High School Diploma Two years post secondary education Experience: Over twenty-five years nuclear plant experience.

Over seventeen years training experience.

Nine and one half years as Superintendent Operations Training at Prairie Island Certifications: Prairie Island Senior Reactor Operator License 3/84 (allowed to lapse 1/90)

NSP Advanced Instructor Certification Simulator Support Group - Michael Gardzinski, Senior Technical Instructor Educational

Background:

High School Diploma Two years post secondary education Experience: Twenty-eight years nuclear plant experience 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 Nuclear Instructor Twelve years instructor at Prairie Island Certifications: NSP Advanced Instructor Certification (allowed to lapse 1/93)

Prairie Island Senior Reactor Operator License (allowed to lapse 1/92)

Page 2

PRAIRIE ISLAND SIMUIATOR CERTIFICATION REPORT 1994 APPENDIX 4 FOUR YEAR TESTING SCHEDULE A. Annual Testing - Following is an outline of the testing completed annually. This testing schedule has not been changed from the original certification submittal.

PART I - STEADY STATE OPERATION REFERENCE ANSI 3.5 1.1 100% POWER -IC-9 BOL B2.1 1.2 75% POWER -IC-24 MOL adjusted to ~75% B2.1 1.3 25% POWER -IC-13 EOL adjusted to -25% B2.1 PART 2 - TRANSIENT OPERATION 2.1 NORMAL PLANT EVOLUTIONS 2.1.1 UNIT STARTUP 2.1.1.1 PLANT HEATUP 3.1.l(1) 2.1.1.2 OPERATIONS AT HOT SHUTDOWN 3.1.l(5) 2.1.1.3 REACTOR STARTUP 3.1.l(2) 2.1.1.4 TURBINE / GENERATOR STARTUP 3.1.1(3) 2.1.1.5 LOAD INCREASE (0% TO 100%) 3.1.l(6) 2.1.2 UNIT SHUTDOWN 2.1.2.1 PLANT SHUTDOWN (HSD TO CSD) 3.1.l(8) 2.1.2.2 LOAD DECREASE (l00% TO 0%) 3.1.1(6) 2.1.3 REACTOR TRIP WITH RECOVERY 3.1.l(4) 2.1.4 CORE PERFORMANCE TESTING 3.1.l(9) 21.4.1 CALORIMETRIC 2.1.4.2 SHUTDOWN MARGIN CALCULATION 2.1.4.3 PHYSICS TESTING 2.1.5 OPERATOR SURVEILLANCE TESTS 3.1.l(10) 2.2 TRANSIENT PERFORMANCE TESTS 2.2.1 MANUAL REACTOR TRIP B2.2 2.2.2 TRIP OF ALL FEEDWATER PUMPS B2.2 2.2.3 CLOSURE OF MSIV's B2.2 2.2.4 TRIP OF ALL RCP's B2.2 2.2.5 TRIP OF ANY RCP B2.2 2.2.6 MAIN TURBINE TRIP B2.2

{

2.2.7 MAXIMUM RATE POWER RAMP B2.2 l'

2.2.8 MAXIMUM LOCA WITH LOSS OF OFFSITE POWER B2.2 j 2.2.9 MAXIMUM STEAM BREAK B2.2 1 2.2.10 SBLOCA THRU PORV WITH NO S1 PUMPS B2.2 2.2.11 LOAD REJECTION FROM 100% (Drafi) B3.2 I

PART 3 COMPUTER REAL TIME TEST A3.1 Page 1

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1994 APPENDIX 4 FOUR YEAR TESTING SCHEDULE B. Periodic Testing - The following testing was completed over a four year period from 1/1/91 through 1/31/95.

1. Malfunction Tests - A total of 323 tests are included. This number is revised as malfunctions are added, deleted or modified. Approximately one quarter of these tests (presently 81 +/-4) are completed each calendar year.

The following systems' testing was performed during 1991: CC, CH, CL, CR, CS, CW, ED, EG, RH, RP. This included a total of 83 tests. Sixteen additional tests were completed which had previously failed or been on hold. (Twenty-one tests had failed or were on hold in 1990 however five of these tests were due to be retested during 1991.)

The following systems' testing was performed during 1992: MS, FW, IA, RD. This included a total of 76 tests. In addition sixteen tests in systems CL, ED DG and TC were retested due to plant electrical system modifications. The DG system malfunctions were existing EG system malfunctions which were redesignated to system DG due to the expansion of this part of the plant electrical system.

The following systems' testing was performed during 1993: AN, NI, PC, RX, VC and selected tests from IA, RC and TC systems. This included a total of 81 tests. Three additional malfunction tests were completed which were new, had failed previously or for which additional data was obtained.

The following systems' testing was performed during 1994: RC, SG, SI, TC, TU and remaining tests from ED, DG, N1, RX and VC systems. This included a total of 83 tests. Three additional malfunction tests were completed for which additional data had been obtained.

2. Physical Fidelity Comparisons - The comparisons of the simulator to the plant control room, although not specifically included as tests, will be repeated during the four year cycles. This includes the mmparison of photographs of the plant control room to the simulator, light level measurements and noise level measurements. Comparisons of photographs of the plant Control Room panels to the simulator panels were completed during 1992 and all discrepancies found were documented and corrected.

Light level measurements were completed and compared to simulator light levels during 1993 with acceptable results. Noise level measurements were completed during January 1995 with acceptable results.

I j We plan to repeat the testing listed above during the next four year cycle.

Page 2

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT I

1994 Appendix 4 Table 4A MALFUNCTION

SUMMARY

- 1991 TESTING TEST TITLE TEST DATE APPROVAL DATE  !

CCW PUMP TRIP 9/27/91 12/13/91 CC01 CCW PUMP FAILS TO START 9/27/91 12/13/91 CC02 CCW SUPPLY TO RCP FAILS CLOSED 1/21/92 1/31/92 CC04 CCW PIPE RUFFURE 3/11/91 6/21/91 CC05 CCW TO RHRIDC VALVE FAILS TO OPEN 7/10/91 10/11/91 CC06 CCW AUTO MAKEUP FAILURE 3/12/91 5/9/91 CC08 SEAL WATERIIX LEAK 3/12/91 5/9/91 CC09 CONT. PRESSURE XTMR FAILURE 7/9/91 10/11/91 C1101 CH 1-4 CNMT PRESS XTMR SETPOINT 2/26/91 6/21/91 Cil300-311 9/26/91 12/13/91 CLO1 CL PUMP TRIP DIESEL CL PUMP FAILS TO START 9/27/91 12/13/91 CLO2 121 CL PUMP FA!LS TO START 9/27/91 12/13/91 CLO3 3/4/91 10/11/91 CLO4 DIESEL CL PUMP TRIP 1/17/92 1/23/92 CLO6 SAFEGUARDS CL PIPE RUPTURE TURBINE CL PIPE RUPTURE 12/30/91 1/17/92 CLO7 3/19/91 5/9/91 CLO8 CL LEAK 1.S. CONT.

FUEL CLAD FAILURE 3/15/91 6/21/91 CR01 8/1/91 10/11/91 CR03 REACTOR COOLANT CRUD BURST 7/9/91 10/11/91 CS01 CS PUMP TRIP 3/25/91 10/11/91 CS02 CA VALVE FAILURE TO OPEN 3/28/91 10/11/91 CS03 CS PUMP FAILS TO START - AUTO 6/13/91 10/11/91 CWO2 CW PUMP TRIP 3/15/91 6/21/91 CWO3 CW PUMP BEARING FAILURE 3/15/91 6/21/91 CWO4 CNDSR TUBE PLUGGED CNDSR TUBE RUPTURE 12/9/91 !2/30/91 CWO5 3/22/91 6/21/91 CWO6 TRAVELING SCREENS BLOCKAGE 9/22/91 12/13/91 CWO7 CONDENSER PIT FLOOD i

LOSS OF POWER TO 161 KV BUS 3/1/91 6/21/91 ED01 3/1/91 6/21/91 ED03 LOSS OF POWERTO CT TRANSF Page 1

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1994 Appendix 4 Table 4A ED04 FAULT IN IM TRANSF AUTO TRANSFER 3/1/91 6/21/91 ED05 FAULT IN 1M TRANSF DELAY TRANSFER 3/1/91 5/9/91 ED06 FAULTIN 1R SUBSTA TRANSF 7/3/91 10/11/91 ED07 LOSS OF 125 VDC BUS 1/18/92 1/23/92 ED08 LOSS OF 120 VAC INSTRUMENT BUS 5/8/91 12/20/91 ED09 LOSS OF 4160 BUS 3/20/91 10/11/91 ED10 LOSS OF 480 VAC BUS 1/20/92 1/23/92 ED11 BUS 15 LOAD REJ/RES TIMER FAILURE 3/1/91 6/21/91 ED12 BUS 16 LOAD REJ/RES TIMER FAILURE 3/1/91 10/11/91 ED13 LOAD SEQUENCER RESTORATION FAILS 9/27/91 12/13/91 ED14 LOSS OF ALL OFFSITE AC PONER 4/12/91 6/21/91 ED15 DEGRADED GRID VOLTAGE 1/15/92 1/23/92 ED16 DEGRAGED GRID FREQUENCY 9/27/91 12/13/91 EGO 1 MN GEN OUTPUT BKR FAILS TO OPEN 9/4/91 12/13/91 EG02 LOSS GEN ITYDROGEN COOLING 4/5/91 10/11/91 EG03 MN GEN OUTPUT BKR FAILS OPEN 4/5/91 10/11/91 EG05 GEN VOLT REGULATOR FAILURE 1/23/92 1/23/92 EG06 GENERATOR FAULT 4/5/91 10/11/91 EG07 GENERATOR LOSS OF EXCITATION 4/5/91 10/11/91 EG08 LOSS OF EM DIESEL GENERATOR 3/1/91 5/8/91 (DG01)

EG09 EM DIESEL GEN FAILS TO START 3/1/91 5/8/91 (DG02)

EG10 EM DIESEL, GEN OUTPlJF BKR OPENS 3/1/91 5/8/91 (DG04)

EGII EM DIESEL GEN LOAD LIMIT FAILS 7/3/91 10/11/91 (DG03)

EG200 EG TEMP XTMR SO 3/1/91 5/9/91 R1101 R11R PUMP TRIP 4/2/91 6/21/91 R1102 RIIR PUMP FAILS TO START 4/3/91 6/21/91 R1103 RIIR IIX LEAK TO ATMOSPlIERE 3/13/91 5/9/91 R1104 RIIR IIX B/P VALVE FAILS OPEN 3/15/91 6/21/91 R1105 RilR llX B/P VALVE FAILS CLOSED 4/23/91 5/9/91 Page 2

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1994 Appendix 4 Table 4A R1106 RiiR RECIRC SUMP SUCTION PLUGGED 4/26/91 6/21/91 R1107 RHR SYSTEM LEAK 3/15/91 6/21/91 RIIO8 RIIR PUMP SEAL FAILURE 7/2/91 10/11/91 RiiO9 RHR RELIEF VALVE FAILURE 5/3/91 10/11/91 RII200 RHR FLOW XTMR - SO 4/19/91 5/9/91 RP01 REACTOR TRIP 3/4/91 5/9/91 RP02 FAILURE OF AUTO REACTOR TRIPS 3/28/91 5/9/91 RP03 SAFETY SYSTEMS FAllTO ACTUATE 4/12/91 10/11/91 RPO4 INADVERTENT SI ACTUATION 5/14/91 6/21/91 RP05 CONT. ISO. FAILS - PHASE A 4/11/91 5/9/91 RP06 MSIV'S Fall TO ISOLATE 3/18/91 6/21/91 RP07 MECH. FAILURE OF RTB'S 3/22/91 6/21/91 RP08 FAILURE OF SAFEGUARDS ACTUATION 4/10/91 5/9/91 RP300-301 P-7 TURB PRESS - VS 4/12/91 5/9/91 RX218 RP302 AUTO ROD WITHDRAWAL BLOCK SETPNT 4/18/91 5/9/91 RP303-304 11/12 BUS UV TRIP SETPOINT 4/19/91 6/21/91 RP305-306 11/12 BUS UF TRIP SETPOIm 7/3/91 10/11/91 RP307-312 LOOP A/B LO FLOW TRIP SETPOINT 10/4/91 12/13/91 RC03 RP313 316 PRZR PRESS LO TRIP SETPOINT 9/27/91 12/13/91 RP320-322 PRZR PRESS LO - SI SETPOINT RP317-319 PRZR PRESS HI TRIP SETPOINT 4/25/91 6/21/91 RC300-301 PRZR SAFETY SETPOINT _.

RP323-325 PRZR HI LEVEL TRIP SETPOINT 4/24/91 5/9/91 RP326-331 A/B SG LOLO LEVEL TRIP SETPOINT 4/21/91 6/21/91 RP340-343 A/B LOOP LOLO TAVG STM LINE ISOL TRIP STPT 7/3/91 10/11/91 RP344-347 A/B SG 111 STM FLOW SETPOINT 10/11/91 l RP348-351 A/B SG HI-HI STM FLOW SETPOINT 7/1/91 RP352-357 A/B SG LOLO STM PRESS SI SETPOINT 5/3/91 6/21/91 LSO - SG03 (5/9/91), VC210 (1/11/91), RX208 (10/11/91), FWO3 (12/13/91), MS07 (12/13/91), PC03 (12/13/91), PC04 (12/13/91), PC05 (12/13/91), RX300 (12/13/91), MS10 (1/17/92), RC02 (1/17/92), RD07 (1/23/92), TCl1 (1/23/92), TUO! (1/23/92), RCl1 (1/23/92), TC04 (2/4/92), ED02 (3/7/91)

Page 3

I PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1994 Appendix 4 Table 4 A 1991 ANNUAL TEST

SUMMARY

TEST TITLE TEST DATE APPROVAL DATE 1.1 100% POWER STEADY STATE 6/13/91 1/2/92 1.2 75% POWER STEADY STATE 6/3/91 1/2/92 1.3 25% POWER STEADY STATE 6/3/91 1/2/92 2.1.1 UNIT STARTUP 7/11/91 1/2/92 2.1.2 UNIT SHUTDOWN 6/25/91 1/2/92 2.1.3 REACTOR TRIP WITH RECOVERY 6/11/91 1/2/92 2.1.4 CORE PERFORMANCE 8/2/91 1/2/92 2.1.5 OPERATOR SURVEILANCE 11/15/91 1/2/92 2.2.1 MANUAL REACTOR TRIP 6/4/91 1/2/92 2.2.2 TRIP OF ALL FEEDWATER PUMPS 6/14/91 1/2/92 2.2.3 CLOSURE OF MSIVS 6/14/91 1/2/92 2.2.4 TRIP OF ALL RCP'S 6/14/91 1/2/92 2.2.5 TRIP OF ONE RCP 6/14/91 1/2/92 2.2.6 MAIN TURBINE TRIP 6/15/91 1/2/92 2.2.7 MAXIMUM RATE POWER RAMP 6/15/91 1/2/92 2.2.8 MAXIMUM LOCA WITH LOOP 6/14/91 1/2/92 2.2.9 MAXIMUM STEAM BREAK 6/14/91 1/2/92 2.2.10 SBLOCA THRU PORV/NO S1 PUMPS 6/14/92 1/2/92 2.2.11 LOSS OF LOAD 6/14/91 1/2/92 3.I COMPUTER REAL TIME 8/1/91 1/2/92 l

1 Page 4

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1994 Appendix 4 Table 4B MALFUNCTION

SUMMARY

- 1992 TESTING TEST Tl"LE TEST DATE APPROVAL DATE FWOI CONDENSATE PUMP TRIP 6/15/92 1/29/93 FWO2 13 COND. PUMP FAILS TO START 6/15/92 1/29/93 FWO3 LOSS CNDSR VACUUM 3/20/92 1/20/93 FWOS COND. RECIRC VALVE FAILS OPEN 3/16/92 10/28/92 FWO6 COND. RECIRC VALVE FAILS CLOSED 3/16/92 10/28/92 FWO7 CNDSR HW MU VALVE FAILS OPEN 6/15/92 1/29/93 FWO8 CNDSR HW MU VALVE FAILS CLOSED 3/6/92 10/28/92 FW69 LP FDWTR HTR B/P VLV FAILS OPEN 3/6/92 10/28/93 FW10 CNDSR HW LEVEL XMTTR FAILS HIGH 6/15/92 2/8/93 FW11 CNDSR HW LEVEL XMITR FAILS LOW 6/15/92 2/8/93 FWl3 MAIN FEEDWATER PUMP TRIP 4/3/92 1/29/93 FWl5 FDWTR HP HTR HIGH LEVEL 4/3/92 8/12/92 .

FW16 FDWTR LP HTR HIGH LEVEL 4/3/92 10/28/93 FWl7 FDWTR HP HTR LEAK 4/3/92 10/28/92 FW18 FDWTR LP HTR LEAK 4/3/92 1/29/93 1 1

FW19 FDWTR SYS RUPTURE I.S. CONT. 4/10/92 10/28/92 FW20 FDWrR SYS LEAK 1.S. CONT. 4/24/92 1/29/93 f l

FW21 FDWTR RUlrr. I S. CONT. U.S. CHK 4/24/92 1/29/93 FW22 FDWFR SYS RUPTURE O.S. CONT. 4/22/92 1/29/93 FW23 FDWTR SYS LEAK O.S. CONT. 5/1/92 1/20/93 FW24 FDWTR PUMP COMMON HDR RUPTURE 8/2/92 1/29/93 FW25 FDWTR FLOW CV FAILS TO CLOSE 7/27/92 8/12/92 FW26 FDWTR FLOW CV FAILS OPEN 5/1/92 1/29/93 I FW27 FDWrR FLOW CV FAILS CLOSED 11/13/92 1/29/93 FW28 HTR DRN PUMP TRIP 6/5/92 1/29/93 i

FW29 HTR DRN TNK LEVEL XMTR FAILS HI 7/27/92 10/28/92 l

FW30 HTR DRN TNK LEVEL XMTR FAILS LO 7/27/92 1/20/93 FW31 HTR DRN PUMP FAILS TO MIN 7/27/92 10/28/92 FW32 AFW PUMP TRIP - MOTOR 6/15/92 1/29/93 i Page 1

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1994 Appendix 4 Table 4B j FW33 AFW PUMP TRIP -TURBINE 6/15/92 1/29/93 FW34 AFW PUMP FAILS TO START- AUTO 6/15/92 2/4/93 FW35 LOSS SUCTION TO AFW PUMP 1/14/93 1/29/93 FW36 AFW RUPTURE 1.S. CONT. 8/3/92 1/29/93 FW37 AFW RUIYTURE O S. CONT. 7/27/92 10/28/92 FW38 AFW FLOW MV FAILS IN POSITION 6/15/92 1/29/93 FW39 FDWTR RUPTURE U.S. REG VALVE 7/27/92 8/12/92 FW40 COMMON FDWTR PUMP SUCTION BLOCK 1/3/93 1/29/93 FW41 FDWTR FLOW CV LEAKAGE 7/24/92 1/20/93  ;

FW200 COND FLOW XTMR 7/20/92 10/28/92 FW201 CDSRllW XTMR 7/20/92 8/12/92 FW202 11 A FW LEVEL XTMR 7/20/92 8/12/92 FW203 12A FW LEVEL XTMR 7/20/92 8/12/92 FW204 11B FW LEVEL XTMR 7/20/92 8/12/92 FW205 12B FW LEVEL XTMR 7/20/92 8/12/92 FW206 13 A FW LEVEL XTMR 7/20/92 8/12/92  ;

FW207 13B FW LEVEL XTMR 7/20/92 8/12/92 FW208 ISA FW LEVEL XTMR 7/20/92 8/12/92 FW209 15B FW LEVEL XTMR 7/20/92 8/12/92 IA01 LOSS OF SERVICE AIR HDR 1/27/93 2/8/93 IA02 LOSS OF INST AIR HDR HOLD DELAY IA03 LOSS OF AIR COMPRESSOR 6/15/92 2/8/93 MSO1 MS RUPTURE 1.S. CONT. U.S MSIV 10/20/92 FAILED MS02 MS RUPTURE O.S. CONT. U.S. MSIV 10/23/92 1/29/93 MS03 MS RUPTURE O.S. CONT. D S. MSIV 10/23/92 1/29/93 MSO4 MS LINE LEAK 111/5/92 1/29/93 MS05 MS SAFETY VALVE STICKS OPEN 11/5/92 1/29/93 MS06 GLND SL STM REG VLV FAIL CLOSED 11/5/92 1/29/93 ,

M508 MSR RELIEF VALVE FAILURE 11/6/92 1/29/93 MSO9 MS LEAK 1.S. CONT. I1/6/92 2/4/93 MS10 MS BREAK 'ID AFW PUMPS 11/6/92 1/29/93 Page 2

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1994 Appendix 4 Table 4B MSI1 STM DUMP VLV FAILS IN POSITION 11/6/92 1/29/93 MS200 IB MS LEVEL XTMR 11/6/92 1/20/93 MS201 2B MS LEVEL XTMR 11/6/92 1/20/93 MS202 1 A MS LEVEL XTMR 11/6/92 1/20/93 MS203 2A MS LEVEL XTMR 11/6/92 1/20/93 MS300-309 11/12 SG SAFETY SETPOINT 11/6/92 1/29/93 RD01 ROD BNK FAILS TO MOVE IN MANUAL 11/9/92 1/29/93 RD02 ROD BNK FAILS TO MOVE IN AUTO 11/9/92 2/4/93 RD03 CONTINUOUS ROD WITHDRAWAL 1/26/93 2/4/93 RD04 CONTINUOUS ROD INSERTION 11/9/92 2/8/93 RDOS CONTROL ROD MISALIGNMENT 11/5/92 2/4/93 RD06 STUCK ROD 11/9/92 2/4/93 RD07 DROPPED ROD HOLD DELAY RD08 CONTROL ROD G-3 EJECTION 12/31/92 1/29/93 RD09 IRIP FAILS 11/9/92 1/29/93 RD10 INCORRECT ROD SPEED 11/9/92 2/8/93 S10 1 BOTH BA TNK VLVS FAIL TO OPEN 11/6/92 2/ M 3 S104 SI PUMP TRIP 12/30/92 2/8/93 ALSO-CLO3 / DG01/ DG02 / DG04 / ED01/ ED02 / ED03 / ED13 / ED12 / EDl4 / ED15 ED16 / EDIO / ED06 /

ED09 / TCl4 i

i I

i

'i 4

Page 3 1

i PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1994 Appendix 4 Table 4B 1992 ANNUALTEST

SUMMARY

TEST TITLE TEST DATE APPROVAL DATE 1.1 100% POWER STEADY STATE 11/25/92 2/18/93 1.2 75% POWER STEADY STATE 11/30/92 2/18/93 1.3 25% POWER STEADY STATE I1/30/92 2/8/93 2.1.I UNIT STARTUP 11/20/92 2/8/93 2.1.2 UNIT SHUTDOWN 11/18/92 2/8/93 2.1.3 REACTOR TRIP WITH RECOVERY l1/19/92 2/8/93 2.1.4 CORE PERFORMANCE I1/30/92 2/18/93 2.1.5 OPERATOR SURVEILLANCE 12/8/92 1/20/93 2.2.1 MANUAL REACTOR TRIP 11/16/92 1/20/93 2.2.2 TRIP OF ALL FEEDWATER PUMPS 11/16/92 1/20/93 2.2.3 CLOSURE OF MSIVS 11/16/92 1/20/93 2.2.4 TRIP OF ALL RCP'S 11/16/92 1/20/93 2.2.5 TRIP OF ONE RCP 11/16/92 1/20/93 2.2.6 MAIN TURBINE TRIP 11/16/92 1/20/93 2.2.7 MAXIMUM RATE POWER RAMP 11/16/92 1/20/93 2.2 8 MAXIMUM LOCA WITH LOOP 11/16/92 1/20/93 2.2.9 MAXIMUM STEAM BREAK 12/9/92 1/20/93 2.2.10 SBLOCA THRU PORV/NO SI PUMPS 11/16/92 1/20/93 2.2.11 LOSS OF LOAD 11/16/92 1/20/93 3.1 COMPUTER REAL TIME 12/1/92 2/18/93 Page 4

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1994 Appendix 4 Table 4C MAIPJNCTION

SUMMARY

- 1993 TESTING TEST TITLE TEST DATE APPROVAL DATE AN01 NSSS ANNUNCIATORFAILURE 12/10/93 1/6/94 1A02 LOSS OF INSTRUMENT AIR HEADER 5/20/93 1/6/94 N101 INCORRECT SOURCE RANGE CHANNEL RESPONSE 12/9/93 1/6/94 N102 SOURCE RANGE CHANNEL SPIKES 11/3/93 1/6/94 NIO3 INTERMEDIATE RANGE CHANNEL IMPROPER 12/9/93 1/6/94

RESPONSE

NI300 IR N35/36 PWR ABOVE P-6 12/9/93 1/6/94 N1302 PR N41-44 PWR ABOVE P-8 12/9/93 1/20/94 NI306 PR N41-44 PWR ABOVE P-9 12/9/93 1/20/94 N1310 PR N41-44 PWR ABOVE P-10 12/9/93 1/20/94 N1316 IR N35-36 HI FLUX TRIP 12/9/93 1/20/94 N1318 PR N41-44 LO RNG HI FLUX TRIP 12/10/93 1/20/94 N1322 PR N41-44 HI RNG HI FLUX TRIP 1/13/94 1/20/94 PC01 ERCS CPU FAILURE 12/10/93 1/6/94 PC03 ERCS ALARM DISPLAY FAILURE 1/4/94 1/20/94 PC04 ERCS SAS DISPLAY FAILURE 12/28/93 1/20/94 PC05 ERCS CONTROL ROOM PRINTER 12/28/93 1/20/94 RCO2 REACTOR COOLANT PMP LOCKED ROTOR 1/12/94 1/20/94 RC11 LOCA -RTD B/P LOOP COLD LEG MANIFOLD 1/7/94 2/3/94 RX01 PRESSURIZER SPRAY VLV FAIL OPEN 10/28/93 11/24/93 RX02 PRESSURIZER SPRAY VLV FAIL CLOSED 7/23/93 <!/6/94 RX03 PRESSURIZER HEATERS FAIL ON 11/2/03 11/24/93 RX04 PRESSURIZER HEATERS FAIL OFF 10/11/93 11/24/93 RX05 RC LOOP TH TRANSMITTER FAILS hlGH 1/26/94 2/9/94 RXO6 RC LOOP TH TRANSMITTER FAILS LOW 1/27/94 2/9/94 RX07 RC TC TRANSMITTER FAILS HIGH 1/27/94 2/9/94 RXO8 RC LOOP TC TRANSMITTER FAILS LOW 1/27/94 2/9/94 RXO9 PRZR LVL TRANSMITTER FAILS HIGH 5/18/93 11/24/93 RX10 PRZR LVL TRANSMITTER FAILS LOW 7/8/93 11/24/93 Page 1

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1994 Appendix 4 Tabic 4C 6/3/93 11/24/93 RX11 PRZR PRESS TRANSMITTER FAILS HIGH 7/12/93 11/24/93 RX12 PRZR PRESS TRANSMITTER FAILS LOW 5/14/93 11/24/93 RX13 RCS WIDE RNG PRESS XMTR FAILS HIGH 5n/93 12/9/93 RX14 RCS WIDE RNG PRESS XMTR FAILS LOW 10/11/93 11/24/93 RX15 SG LEVEL TRANSMITTER FAILS HIGH 12/8/93 1/6/94 RX16 SG LEVEL TRANSMITTER FAILS LOW 7/30/93 11/24/93 RX17 SG T'1ESS TRANSMITTER FAILS HIGH 7/30/93 12/2/93 RX18 SG PRESS TRANSMITTERFAILS LOW Sn/93 12/2/93 RX22 FEEDWATER CNTLR OUTPUT FAILURE Sn/93 12/2/93 RX35 ADFCS BYPASS FLOW CNTRL VLV OUTPUT CARD FAILURE 5/14/93 12/2/93 RX200 RCS PRESSURE XMTR PT-429 5/21/93 12/2/93 RX201 RCS PRESSURE XMTR PT-430 5/21/93 12/2/93 RX202 RCS PRESSURE XMTR PT-431 l

5/21/93 12/2/93 RX203 RCS PRESSURE XMTR PT-449 5/21/93 12/2/93 RX204 PRZR LVL XMTR LT-426 5/21/93 12/2/93 RX205 PRZR LVL XMTR LT-428 10/29/93 1/6/94 RX206 SG LEVEL XMTR LT-461 10/29/93 1/6/94 RX207 SG LEVEL XMTR LT-471 7/23/93 12/2/93 RX208 AUCTIONEERED TAVG 7/30/93 12/2/93 RX209 FW FLOW XMTR FT-466 7/30/93 12/2/93 RX210 FW FLOW XMTR FT-467 7/30/93 12/2/93 RX211 FW FLOW XMTR FT-476 10/8/93 12/2/93 RX212 FW FLOW XMTR FT-477 7/23/93 12/2/93 RX213 11/12 MS PRESSURE XMTR PT-484 7/23/93 12/9/93 RX214 11 MS PRESSURE XMTR PT-468 7/23/93 12/9/93 RX215 11 MS PRESSURE XMTR PT-469 f 7/23/93 12/9/93 RX216 12 MS PRESSURE XMTR PT-478 h

7/23/93 12/9/93 k RX217 12 MS PRESSURE XMTR PT-479 7/23/93 12/9/93 RX219 11 MS FLOW XMTR FT-464 7/23/93 12/9/93 RX220 11 MS FLOW XMTR FT-465 7/23/93 12/9/93 RX221 12 MS FLOW XMTR FT-474 Page 2

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1994 Appendix 4 Table 4C RX222 12 MS FLOW XMTR FT-475 7/23/93 12/9/93 RX223 11 STM FLOW XMTR FT-494 8/13/93 12/9/93 RX224 12 STM FLOW XMTR IT-4% 8/13/93 12/9/93 RX225 11 FEED FLOW XMTR FT-495 8/13/93 12/9/93 RX226 12 FEED FLOW XMTR FT-497 8/13/93 12/9/93 RX227 11 FEED TEMP XMTRTT-498 8/13/93 12/9/93 RX228 12 FEED TEMP XMTR TT-499 8/13/93 12/9/93 RX229 FW HDR PRESS XMTR FT-500 8/13/93 12/9/93 RX230 FW HDR PRESS XMTR PT-501 8/13/93 12/9/93 RX231 11 SG WR LEVEL XMTR LT-502 12/10/93 1/6/94 RX232 12 SG WR LEVEL XMTR LT-503 12/10/93 1/6/94 RX233 PRZR LEVEL LOCAL CONTROL LC-428F 1/19/94 2/3/94 RX300 PRZR PORV SETPOINT PCV-430 10/13/93 12/9/93 RX302 LOAD REJECT STM DUMP HI SP 1/12/94 2/3/94

-303 LOAD REJECT STM DUMP lilH1 SP

-304 TURB TRIP STM DUMP Hl/HIH1 SP RX305 MASTER PRZR PRESS CONT SP 1/12/94 1/20/94 TC04 TURBINE CONTROL VALVE FAILS OPEN 1/4/94 1/20/94 TC300 INIT TURB CV POS 12/10/93 1/6/94 TU0I LOSS OF TURBINE LUBE OIL SUPPLY 12/6/93 1/6/94 VC01 REACTOR COOLANT PMP #1 SEAL FAIL. 1/7/94 2/3/94 VCO2 REACTOR COOLANT PMP #2 SEAL FAIL. 1/5/94 1/20/94 VC04 CHARGING PUMP TRIP 11/3/93 1/20/94 VC06 REGEN HEAT EXCHANGER LEAKAGE 12/27/94 1/20/94 ALSO - ED02,MSO1,RD07, AND LIGHT LEVELS - (12/9/93)

Page 3

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1994 1 Appendix 4 Table 4C l 1993 ANNUALTEST

SUMMARY

TEST TITLE TEST DATE APPROVAL DATE 1.1 100% POWER STEADY STATE 1/31/94 2/9/94 1.2 75% POWER STEADY STATE 12/3/93 2/9/94 1.3 25% POWER STEADY STATE 12/3/94 2/9/94 2.1.I UNIT STAREJP 11/21/93 2/9/94 2.1.2 UNIT SilUTDOWN 11/5/93 12/16/93 2.1.3 REACTOR TRIP WITil RECOVERY I1/18/93 2/9/94 2.1.4 CORE PERFORMANCE 12/3/93 2/9/94 2.1.5 OPERATOR SURVEILLANCE 1/20/94 2/3/94 2.2.1 MANUAL REACTOR TRIP 11/5/93 12/16/93 2.2.2 TRIP OF ALL FEEDWATER PUMPS 11/16/93 12/16/93 2.2.3 CLOSURE OF MSIVS 11/16/93 1/6/94 2.2.4 TRIP OF ALL RCP'S 11/16/93 12/16/93 2.2.5 TRIP OF ONE RCP 11/16/93 12/16/93 2.2.6 MAIN TURBINE TRIP 11/5/93 12/16/93 2.2.7 MAXIMUM RATE POWER RAMP 11/16/93 12/16/93 2.2.8 MAXIMUM LOCA WITil LOOF 11/5/93 12/16/93 2.2.9 MAXIMUM STEAM BREAK 2/1/94 2/9/94 2.2.10 SBLOCA TIIRU PORV/NO S1 PUMPS 11/5/93 12/16/93 2.2.11 LOSS OF LOAD 11/16/93 12/16/93 3.1 COMPUTER REAL TIME I1/30/93 1/6/94 k

i Page 4

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1994 Appendix 4 Table 4D MALFUNCTION

SUMMARY

- 1994 TESTING 1

TEST TITLE TEST DATE APPROVAL DATE ED02 4.16KV 1R XFMR BKR FAILS TO AUTO CLOSE 8/4/94 9/28/94 FOLLOWING GEN / GEN XFMR LOCKOUT ED17 FAILURE OF 52Z LOAD SEQUENCER RELAY 12/13/94 12/15/94 DG05 ELECTRONIC GOVERNOR FAILURE 12/1/94 12/15/94 l

DG06 24VDC SUPPLY FOR ELECTRONIC GOVERNOR 12/1/94 12/15/94 FAILS DG07 DIESEL GENERATOR EMERGENCY AUTO START 11/11/94 11/30/94 FAILURE N104 INTERMEDIATE RANGE CHANNEL IMPROPER I1/30/94 12/21/94 COMPENSATION N105 IMPROPER POWER RANGE CHANNEL RESPONSE 1/9/94 1/20/95 N106 POWER RANGE UPPER CHANNEL IMPROPER 12/7/94 12/21/94

RESPONSE

NIO7 POWER RANGE LOWER CHANNEL IMPROPER 12/13/94 12/15/94

RESPONSE

RC01 REACTOR COOLANT PUMP TRIP 12/29/94 1/6/94 RC04 REACTOR COOLANT PUMP SHAFT SHEAR 1/3/95 1/6/95 RC05 REACTOR COOLANT PUMP BEARING FAILURE 12/21/94 1/6/95 RCM LOCA - HOT LEG 12/9/94 12/21/94 RC07 LOCA - COLD LEG RCP SUCTION 12/9/94 12/21/94 RC08 LOCA - COLD LEG RCP DISCHARGE 12/9/94 12/21/94 RC09 LOCA - PRESSURIZER STEAM SPACE 9/27/94 10/6/94 RC10 LOCA - PRESSURIZER WATER SPACE 9/27/94 10/6/94 RC12 LOCA - RTD BYPASS LOOP PITURN LEG 12/27/94 1/6/95 RCl3 LOCA - REACTOR HEAD VENT 12/28/94 1/6/95 RC14 REACTOR COOLANT SYSTEM LEAKS (RHR-10 GPM) 12/6/94 12/21/94 RC15 REACTOR COOLANT SYSTEM LEAKS (RHR-500 12/12/94 12/15/94 GPM)

RC16 PRESSURIZER PORV FAILS CLOSED 9/26/94 10/6/94 Page 1 i

i

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1994 Appendix 4 Table 4D RC18 PRZR SAFETY VLV RC-10-1 FAILS OPEN 12/30/94 1/6/95 RC19 PRESSURIZER SAFETY VALVE SEAT LEAKS 12/19/94 1/6/95 RC20 RCP OIL LEAK - UPPER RESERVOIR 12/29/94 1/6/95 RC21 REACTOR VESSEL 0-RING LEAKAGE 1/6/95 1/20/95 RC22 PORV VALVE LEAKAGE 1/6/95 1/20/95  :

RC24 PRZR SPRAY VALVE FAILS IN POSITION 12/30/94 1/6/95 RX19 MAIN STM LINE FLOW TRANSMTITER FAILS HIGH 11/17/94 12/15/94 l

RX20 MAIN STM LINE FLOW TRANSMITTER FAILS LOW l1/17/94 12/15/94 RX23 FEEDWATER FLOW TRANSMITTER FAILS HIGH 11/17/94 12/15/94 RX24 FEEDWATER FLOW TRANSMITTER FAILS LOW l1/17/94 12/15/94 RX25 TURBINE FIRST STAGE PRESSURE TRANSMITTER 11/28/94 12/7/94 FAILS HIGH l RX26 TURBINE FIRST STAGE PRESSURE TRANSMITTER 11/28/94 12n/94 FAILS LOW RX27 FEEDWATER INLET TEMPERATURE TRANSMrlTER 11/28/94 12n/94 FAILS HIGH RX28 FEEDWATER INLET TEMPERATURE TRANSMITTER 11/28/94 12/7/94 FAILS LOW RX29 FEEDWATER HEADER PRESSURE TRANSMITTER 11/28/94 12n/94 FAILS HIGH RX30 FEEDWATER HEADER PRESSURE TRANSMITTER 11/28/94 12n/94 FAILS LOW RX31 STEAM GENERATOR WIDE RANGE LEVEL 11/28/94 12n/94 TRANSMITTER FAILS HIGH RX32 STEAM GENERATOR WIDE RANGE LEVEL 11/28/94 12n/94 t

TRANSMITTER FAILS LOW RX33 STEAM GENERATOR LEVEL CONTROL FAILS TO 11/28/94 12n/94 MANUAL RX34 STEAM GENERATOR MAIN FEEDWATER FCV 11/28/94 12n/94 ADFCS OlTTPUT CARD FAILURE SG01 STEAM GENERATOR TUBE LEAK 12/14/94 1/6/95 SG02 STEAM GENERATOR TUBE RUPTURE 12/15/94 1/6/95 Page 2

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1994 Appendix 4 Table 4D SG03 STEAM GENERATOR BLOWDOWN CONTROL 1/9/95 1/20/95 VALVE FAILS OPEN S102 LOOP A COLD LEG INJECTION CHECK VALVE 1/13/95 1/20/95 FAILURE SIO3 BA TANK VALVE FAILS TO CLOSE ON LOW-LOW 1/3/95 1/20/95 LEVEL IN THE PRESELECTED BATIN AUTO SIO5 SAFETY INJECTION PUMP FAILS TO START 12/30/94 1/6/95 AUTOMATICALLY S106 St ACCUMULATORLEAKAGE 1/13/95 1/20/95 S107 St ACCUMULATOR CHECK VALVE LEAKAGE 1/13/95 1/20/95 SIO8 St ACCUMULATOR RELIEF VALVE LEAKAGE 1/13/95 1/20/95 S109 St COLD LEG INJECTION LINE RUFTURE INSIDE OF 1/13/95 1/20/95 THE ANNULUS TC01 TURBINE STOP VALVE FAILS TO CLOSE WHEN 6/3/94 7/22/94 l REQUIRED TCO2 TURBINE STOP VALVE FAILS CLOSED 5/17/94 7/22/94 TC03 TURBINE CONTROL SYSTEM CYCLING OUTPUT (50 5/18/94 7/22/94 MW SWING)

TC05 TURBINE CONTROL VALVE FAILS CLOSED 5/27/94 7/22/94 TC06 RPS FAILS TO TRIP TURBINE 6/27/94 7/22/94 TC07 TURBINE CONTROL INTERCEPT VALVE FAILS 6/10/94 7/22/94 CLOSED TC08 TURBINE CONTROL FAILURE DURING TURBINE 6/10/94 7/22/94 ROLL TC09 TURBINE CONTROL FAILURE CAUSING TURBINE 7/12/94 7/28/94 RUNBACK TC10 TURBINE CONTROL FAILURE CAUSING AN 6/27/94 7/22/94 INCREASE IN POWER WITHOUT DEMAND TCl1 COMPLETE TURBINE TRIP FAILURE 5/20/94 7/22/94 TCl2 TURBINE TRIP 7/15/94 7/28/94 TC13 ELECTRO HYDRAULIC PUMP 7 RIP 6/3/94 7/22/94 TCl4 TURBINE CONTROL VALVE FAILS IN POSITION 11/28/94 12n/94 TUO2 TURBINE GENERATOR VIBRATION 7/26/94 9/28/94 Page 3

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1994 Appendix 4 Table 4D VC05 STUCK OPEN CilARGING PUMP RELIEF VALVE 5/26/94 7/22/94 VC07 LETDOWN IIEAT EXCl{ ANGER LEAKAGE TO 7/25/94 9/28/94 ATMOSPilERE VC08 LETDOWN IIEAT EXCilANGER TUDE RUFTURE TO 7/21/94 7/28/94 CCW SYSTEM VC09 LETDOWN LINE LEAKAGE INSIDE CONTAINMENT 8/22/94 9/28/94 VC10 CilARCING PUMP COMMON DISCl[ARGE IIEADER 8/15/94 9/28/94  :

RUPTURS VCl1 CllARCtNG LINE LEAKAGE INSIDE CONTAINMENT 10/11/94 11/30/94 VCl2 EMERGENCY BORATION VALVE STUCK OPEN 7/27/94 9/28/94 VC13 LETDOWN LINE RELIEF VALVE FAILURE 7/14/94 7/28/94 VCl4 VOLUME CONTROL TANK RELIEF VALVE FAILURE 7/27/94 9/28/94 VC19 LOSS OF AIR TO CIIARGING PUMP SPEED 7/15/94 7/28/94 COffrROLLER VC20 CCW RETURN FROM LETDOWN IIEAT EXCl{ ANGER 7/13/94 7/28/94 FAILS CLOSED VC21 REACTOR COOLANT PUMP TilERMAL BARRIER 7/26/94 9/28/94 TUBE FAILURE VC200 CVCS PRESSURE TRANSMITTER PT-21131 6/6/94 7/28/94 VC201 CVCS TEMPERATURE TRANSMITTER TE-15306 7/20/94 7/28/94 VC202 CVCS FLOW TRANSMITTER FT-23033 7/21/94 7/28/94 VC203 CVCS FLOW TRANSMITTER FT-23034 7/21/94 7/28/94 VC204 VCT LEVEL TRANSMITTERS LT-ll2,141 7/20/94 7/28/94

-205 ALSO - ED06, ED14, DG03(11/11/94), NOISE LEVEL TEST and all REMOTE FUNCTIONS.

Page 4

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1994 Appendix 4 Table 4D 1994 ANNUAL TEST

SUMMARY

TITLE TESTED APPR 1.1 100% POWER STEADY STATE 10n/94 11/30/94 1.2 75% POWER STEADY STATE 11/10/94 11/30/94 1.3 25% POWER STEADY STATE 11/3/94 11/30/94 1 2.1.1 UNIT STARTUP 10/19/94 11/30/94 2.1.2 UNIT SHUTI>0WN 10/18/94 11/30/94 2.1.3 REACTOR TRI? WITH RECOVERY 9/30/94 11/30/94 2.1.4 CORE PERFORMANCE I1/14/94 11/30/94 2.1.5 OPERATOR SURVEILLANCE 10/26/94 11/30/94 2.2.1 MANUAL REACTCR TRIP 9/23/94 11/30/94 2.2.2 TRIP OF ALL FEEDWATER PUMPS 9/23/94 11/30/94 2.2.3 CLOSURE OF MSIVS 9/19/94 9/28/94 2.2.4 TRIP OF ALL RCP'S 9/19/94 9/28/94 1

2.2.5 TRIP OF ONE RCP 9/20/94 9/28/94 j 2.2.6 MAIN TURBINE TRIP 9/20/94 9/28/94 2.2.7 MAXIMUM RATE POWERitAMP 9/22/94 9/28/94 2.2.8 MAXIMUM LOCA WITH LOOP 12/19/94 12/21/94 2 2.9 MAXIMUM STEAM BREAK 9/23/94 11/30/94 2.2.10 SBLOCA THRU PORV/NO S1 PUMPS 9/22/94 9/28/94 1

2.2.11 LOSS OF LOAD 10/3/94 10/6/94 3.1 COMPUTER REAL TIME 9/27/94 10/6/94 I

i l

t i

I l

Fage 5 l l

i I

PRAIRIE ISLAND SIMUIAToR CERTIFICATION REPORT l 1994 APPENDIX 5 ANNUAL OPERABILITY TESTING ABSTRACT STEADY STATE TEST - 100% 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: 10/7/94 CRP Approval Date: 11/30/94 Initial Conditions: IC-9 (100% Power Beginning of Cycle)

Duration of Test: One 11our Data Collected: Data was collected for the parameters listed in Table S A using the SATAR (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 difTerences 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.

Page 1

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1994 APPENDIX 5 ANNUAL OPERABILITY TESTING ABSTRACT STEADY STATE TEST- 75% 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: 11/10/94 CRP ApprovalDate: 11/30/94 Initial Conditions: IC-24 (78% Power Middle of Cycle). Power level is stabilized at approximately 75% Efforts are made 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.

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 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 Resiew Panel and determined to be insignificant to training.

Page 2

PRAIRIE ISLAND SIMUIAToR CERTIFICATION REPORT 1994 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: 11/3/94 CRP ApprovalDate: 11/30/94 Initial Conditions: IC-13 (20% Power End of Cycle). Power level is stabilized at approximately 28%. Efforts are made 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 paramete rs listed in Table SA using the SATAR (Simulator Automated Testing And Reverificction) program. Additionally, RCS leakrate, various process computer logs and secondary calorimetric (heat balance) data was collected.

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 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.

Page 3

PRAIRIE ISLAND SIMUIATOR CERTIFICATION REPORT 1994 ,

APPENDIX 5 t

i ANNUAL OPERABILITY TESTING ABSTRACT .

TRANSIENT OPERATION TESTING - NORMAL PLANT EVOLUTIONS l UNIT STARTUP

Description:

The purpose of this test is to ensure the PITC Simulator simulates opcations from cold shutdown conditions to 100% power operations. This procedure will use the normal plant operating precedures and surveillances for operating guidance. The si.nulator is expected to simulate all control board evolutions and some required supponing ont plant tasks.

Date Conducted: 8/29/94 to 9/6/94 CRP ApprovalDate:11/30/94 Initial Conditions: IC 2 (Cold Shutdown, Beginning Of Cycle)

Final Conditions: Simulator in stable 100% power conditions. l Date. Collected: Controlled procedures were used for all plant evolutie:is. Completed copies of all procedures used were collected.

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

i indicates acceptable simulator performance.

i-Deficiencesidentified During This Testing: None Page 4

r PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1994 APPENDIX 5 ANNUAL OPERABILITY TESTING ABSTRACT TRANSIENT OPERATION TESTING - NORMAL PLANT EVOLUTIONS UNIT SHUTDOWN

Description:

The purpose 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: 8/29/94 to 9/6/94 i

CRP Approval Date: 11/30/94 Initial Conditions: IC-17 (95% Power Coastdown Conditions)

Final Conditions: Simulator in 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. Ability to correctly complete controlled plant procedures av , achieve stab".e cold shutdown conditions indicates acceptable simulator performance.

Deficiences identified During This Testing: None 1

Page 5 i

4 m., w

PPAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1994 APPDIDIX 5 l

ANNUAL OPERABILITY TESTING ABSTRACT 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 increase to rated power. It is not the intent that other malfunctions be interjected, but to simulate operations under normal conditions. Other portions of the testing program will measure the malfunction abilities of the simulator. This test is designed to meet the requirements of ANSI 3.5 section 3.1.l(4) " Reactor trip followed by recovery to rr.ted power" The acceptance criteaa of ANSI 3.5 section 4.2.1 Transient operation (b) and (c) is followed.

Date Conducted: 9/30/94 CRP ApprovalDate: 11/30/94 Initial Conditions: IC-9 (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.

Deficiences Identified During This Testing: None Page 6 I

I 1

PRAIRIE ISLAND SIMUIAToR CERTIFICATION REPORT 1994 APPENDIX 5 ANNUAL OPERABILITY TESTING ABSTRACT TRANSIENT OPERATION TESTING - NORMAL PLANT 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 boron 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 " Normal Plant Evolutions" The acceptance criteria was developed from the plant surveillance test procedures (SP 1005, D30, D32).

Date Conducted: 11/14/94 CRP Approval Date: 11/30/94 Initial Conditions: Several for seperate parts of the test:

IC-9 (100% Power Beginning of Cycle)

IC-19 (50% Power Middle of Cycle)

IC-13 (20% Power End of Cycle)

IC-5 (Hot Shutdown Beginning of Cycle)

Final Conditions: Measurements completed.

Data Collected: Measurements of Control Rod Worth, Critical Boron Concentration, Isothermal Temperature Coeflicient, Shutdown Margin along with Calorimetric (heat balance) data.

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

Deficiences identified During This Testing: Measurements of total Control Rod Worth differed from the plant predicted values by more than 10%. This difference is due to plant core modifications which have not been incorporated into the simulator. These differences have beenjudged by the Certification Review Panel to not be significant to training. The simulator core model is planned to be updated to match the plant predicted core data in 1995.

Page 7

I 6

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1994  :

APPENDIX 5  ;

ANNUAL OPERABILITY TESTING ABSTRACT .

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 on the Prairie Island Simulator. This test is d esigned 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. Tlie surveillances tested are selected from the PINGP control room lists of surveillances. All surveillances on this 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. ,

Date Conducted: 9/27/94 ,

-l CRP Approval Date: 11/30/94 Initial Conditions: Various depending on the surveillance procedure requirements.

Final Conditions: Completion of the surveillance procedure.

Data Collected: Completed copies of all surveillance procedures detemined 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.

Deficiences identified During This Testing: None Page B j I

q:-

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1994 APPENDIX 5 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 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 of ANSI 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 fo!! owed.

Date Conducted: 9/23/94 CRP ApprovalDate: 11/30/94 l l

Initial Conditions: IC-10 (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: Judgement of the Certification Review Panel. Makeup and qualifications of this panel are identified in Appendix 4 of this report.

Deficiences Identified During This Testing: None l

t 8

Page 9 N _ - - _ _ - _ - _ _ _ - _ _ - _ _

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1994 APPENDIX 5 ANNUAL OPERABILITY TESTING ABSTRACT TRANSIEi TT OPERATION TESTING - TRANSIENT TESTS TRIP OF ALL FEEDWATER PUMPS

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 Performance " 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.

Date Conducted: 9/23/94 CRP Approval Date: 11/30/94 Initial Conditions: IC-11 (100% Power End of Cycle)

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

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

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

Deficiences Identified During This Testirg: Nane i

Page 10 l

i

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1994 APPENDIX 5 ANNUAL OPERABILITY TESTING ABSTRACT TRANSIENT OPERATION TESTING - TRANSIENT TESTS I

CLOSURE OF MAIN STEAM ISOLATION VALVES Descriptior' 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 i

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 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: 9/19/94 ,

CRP Approval Date: 9/28/94 Initial Conditions: IC-11 (100% Power End of Cycle)

Final Conditions: RCS Tavg stabilizes at approximately 552 degrees or steam generator pressure PORV's maintain pressure at 1050psig.

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

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

Deficiences Identified During This Testing: None Page 11

-. = -- -- . . _ .

1

~

PRAIRIE ISLAND SI!fJIATOR CERTIFICATION REPORT 1994 APPENDIX 5

)

ANNUAL OPERABILITY TESTING ABSTRACT i l

TRANSIENT OPERATION TESTING - TRANSIENT TESTS  :

Tf~ )F ALL REACTOR COOLANT PUMPS 1

4

Description:

The purpose of this test is to test the ability of the Prairie Island Simulator to appeaximate PINGP conditions, during a simultaneous trip of both unit #1 RCP's, which causes a reactor trip. It is not the intent that other malfunctions be 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 of ANSI 3.5 Appendix B section B.2.2 -Transient Performance

" Simultaneous trip of all reactor coolant pumns " The acceptance criteria of ANSI 3.5 Appendix B - B.2.2.1, and 4.2.1 Transient operation (b) and (c)is followed. l Date Conducted: 9/19/94 CRP Approval Date: 9/28/94 i

Initial Conditions: IC-11 (100% Power End of Cycle)

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

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

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

Deficiences Identified During This Testing: None Page 12 l

_ _ _ _ . __ ... . _ . __ __. . . - . . .m ._ _ . _. .. ... _ _

l l

1

- PRAIRIE ISIAND SIMUIAToR CERTIFICATION REPORT 1 1994 APPENDIX 5 l

ANNUAL OPERABILITY TESTING ABSTRACT f i

TRANSIENT OPERATION TESTING - TRANSIENT TESTS a

TRIP OF ANY REACTOR COOLANT PUMP

Description:

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

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 i trip conditions. Other portions of the testing program will measure the malfimetion 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 j acceptance criteria of ANSI 3 5 Appendix B - B.2.2.1, and 4.2.1 Transient operation (b) and (c)is followed.

1 Date Conducted: 9/20/94 i CRP Approval Date: 9/28/94  ;

I Initial Condition:: IC-11 (100% Power End of Cycle)

Fmal Conditions: RCS Tave stabilizes at approximately 547 degrees.

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

1 l

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

Deficiences Identified During This Testing: None Page 13 l

1

PRAIRIE ISL AND 9MULATOR CERTIFICATION REPORT 1994 APPENDIX 5 ANNUAL OPERABILITY TESTING ABSTRACT TRANSIENT OPERATION TESTING - TRANSIENT TESTS MAIN TURBINE TRIP

Description:

The purpow of this test is to test the ability of the Prairie Island Simulator to approximate PINGl conditions, during a main turbine trip (from maximum power level that does act result in immediate reactor trip). It is not the intent that other malfunctions be interjerted, but to only simulate operations under main turbine 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 " 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: 9/20/94 CRP Approval Date: 9/28/94 Initial Conditions: IC-7 (5% Power Beginning of Cycle) i l

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

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

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

Deficiences Identified During This Testing: None Page 14 l

, -,- . _ - - . - . . . . - - - . - - - - =- _- . .- . -. . . . . - -

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1 1994 i APPENDIX 5 i

ANNUAL OPERABILITY TESTING ABSTRACT j TRANSIENT OPERATION TESTING - TRANSIENT TESTS 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 :ection B.2.2 - Transient Performance " Maximum rate power ramp" The acceptance criteric of ANSI 3.5 Appendix B - B.2.2.1, and 4.2.1 Transient operation (b) and (c)is followed.  ;

i i

Date Conducted: 9/22/94 ,

CRP Approval Date: 9/28/94 i

Initial Conditions: IC-10 (100% Power Middle of Cycle)  !

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

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: Judgement of the Certification Review Panel. Makeup and qualifications of this panel are identified in Appendix 4 of this report.

Deficiences Identified During This Testing: None 4

j Page 15 j

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1994 APPENDIX 5 ANNUAL OPERABILITY TESTING ABSTRACT TRANSIENT OPERATION TESTING - TRANSIENT TESTS MAXIMUM LOCA WITH LOSS OF OFFSITE POWER

==

Description:==

The purpose of this test is to test the ability of the Prairie Island Simulator to match PINGP conditions, during a maximum break LOCA with a loss of offsite power. It is not the 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 te::: is designed to meet the requirements of ,

ANSI 3.5 Appendix B section B.2.2 - Transient Performance " Maximum size reactor .

coolant system rupture combined with loss of all offsite power". The acceptance criteria of l ANSI 3.5 Appendix B - B.2.2.3, and 4.2.1 Transient operation (b) and (c)is followed. )

i Date Conducted: 12/7/94 CRP Approval Date: 12/21/94 l Initial Conditions: IC-11 (100% Power End of Cycle)

Final Conditions: RCS pressure stabilizes, containment pressure trends down and SI pumps lose suction due to low RWST level.

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: Judgement of the Certification Review Panel. Makeup and qualifications of this panel are identified in Appendix 4 of this report.

Deficiences Identified During This Testing: None Page 16

PRAIRIE ISLAND SIMUIAToR CERTIFICA"oN REPORT 1994 APPENDIX 5 ANNUAL OPERABILITY TESTING AB5 TRACT TRANSIENT OPERATION TESTING - TRANSIENT TESTS MAXIMUM STEAM LINE BREAK

==

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 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 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: 9/23/94 CRP Approval Date: 10/30/94 Initial Conditions: IC-11 (100% Power End of Cycle)

Final Conditions: RCS pressure recovers, the non-faulted steam generator level recovers and containment pressure trends down.

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: Judgement of the Certification Review Panel. Makeup and qualifications of this panel are identified in Appendix 4 of this report.

Deficiences Identi6ed During This Testing: None Page 17

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1994 APPENDIX 5 ANNUAL OPERABILITY TESTING ABSTRACT TRANSIENT OPERATION TESTING - TRANSlENT TESTS SMALL BREAK LOCA THROUGH PRESSURIZER PORV WITH NO SI PUMPS

==

Description:==

The purpose of this test is to test the ability of the Prairie Island Simulator to match PINGP conditions, during a depressurization due to a stuck open PORV along with both SI pumps disabled. It is not the intent that other malfunctions be interjected, but to only simulate operations under these cor.ditions. 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 " 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 Transieni operation 1 (b) and (c)is followed.

Date Conducted: 9/22/94 CRP Approval Date: 9/28/94 j Initial Conditions: IC-11 (100% Power End 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 l SATAR (Simulator Automated Testing And Reveriscation) program.

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

Deficiences Identified During This Testing: None Page 18

k PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1994 APPENDIX 5 j 1

ANNUAL OPERABILITY TESTING ABSTRACT TRANSIENT OPERATION TESTING - TRANSIENT TESTS l LOAD REJECTION FROM 100% POWER

==

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 rnaximum 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 1990 draft of ANSI 3.5 Appendix B - B3.2.2, and 4.1.3.3 Normal Evolutions were followed.

Date Conducted: 9/23/94 CRP Approval Date: 10/6/94 Initial Conditions: IC-10 (100% Power Middle of Cycle)

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

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: Judgement of the Certification Review Panel. Makeup and qualifications of this panel are identified in Appendix 3 of this report.

Deficiences Identified During This Testing: None Page 19

I PRAIRIE ISIAND SIMU1AToR CERTIFICATION REPORT 1994 APPENDIX 5 f i

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 performance in the same time base relationships, see,.sences, durations, rates and accelerations as the dynamic performance of the reference plant." To verify real time performance 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 mn 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.

l Date Conducted: 9/27/94 i CRP Approval Date: 10/6/94 l

Initial Conditions: Various depending on the surveillance test requirements.

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

Data Collected: Completed surveillance test procedures, completal 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.

Deficiences Identified During This Testing: None  ;

1 l

i Page 20

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1994 Appendix 5 Table SA Simulator Certification Testine Critical Parameter List Datapool Paranceter Title Units Variable

~

Loop Flow Loop A  % RCF0400A 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 Average RCS Temperature - Auct Hi F RXTAVGN Steam Flow Loop A #/s MSFSGA Loop B #/s MSFSGB Normal Feedwater Flow Loop A #/s FWFFWSGA Loop B #/s FWFFWSGB Aux Feedwater Flow SG A #/s FWFAFSGA SG B #/s FWFAFSGB Steam Generator Blowdown Flow SG A gpm SGF0409A SG B gpm SGF0429A Core Thermal Power watts RCORXPWR Neutron Flux N41  % NIN0049A N42  % NIN0050A 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 Control Rod Bank Positions SDA Steps RDSSDA SDB Steps RDSSDB A Steps RDC0100A B Steps RDC0101A C Steps RDC0102A D Steps RDC0103A Wide Range RCS Pressure psig RCPI709 Pressurizer Level  % RCLPZR Pressurizer Pressure psia RCPPZT Pressurizer Temperature Liquid F RCT0480A Steam F RCT0481A Pressurizer Surge Line Temperature F RCT0482A RVLIS Level Upper Head  % RCLO452A Wide Range  % RCLO454A Dynamic Head  % RCLO456A Page 1

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1994 Appendix 5 Table 5A Simulator Certification Testine Critical Parameter List Datapool Parameter Title Units Variable Generator Watts MW EGQ0340A Vars NVars EGYO346A Voltage volts EGV0341A 345 KV Bus 2 Voltage KV EDV0330A 4160 V Voltage Bus 15 volts EDV0347A Bus 16 volts EDV0348A 4160 V Frequency Bus 15 Hz EDFBUS15 Bus 16 Hz EDFBUS16 480 V Safeguards Bus Voltage Bus 111 volts EDEB111 Bus 112 volts EDEB112 Bus 121 volts EDEB121 Bus 122 volts EDEB122 Instrument AC Status Pnl 111 Bool ED:B0111 Pnl 112 Bool ED:B0112

~

Pnl 113 Bool ED:B0113

~

Pnl 114 Bool ED:B0114

~

Pnl 117 Bool ED:B0117 Pnl 118 Bool ED:B0118 125 VDC Voltage Pnl 11 Volts EDERAT11 Pnl 12 volts EDEBAT12 Containment Pressure psig CHP1005A Containment Temperature F CHTCONT Steam Generator Pressure SG A psia RXPS468 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 Safety Injection Flow 11 SIP gpm SIF0922A 12 SIP gpm SIF0923A RWST Level  % SILO 920A Component Cooling Pump Pressure 11 Header psig CCP2608A 12 Header psig CCP2609A Cooling Water Header Pressure Loop A psig CLP2601A Loop B psig CLP2602A CVCS Charging Flow gpm VCF0128A Boron Concentration ppm RCB Subcooling Margin Train A F RCTSUBCA j Train B F RCTSUBCB I Page 2

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1994 Appendix 5 Table SA Simulator Certification Testine Critical Parameter List Note that variables are not listed for S'eam Generator Temperature or Pressurizer Relief Valve Flow.

These values are not available to t h operator and are not easily available on the simulator. For Pressurizer Relief Valve Flow a ::tatus point is listed since this is available to the operator.

l Page 3

l l

l PRAIRIE ISLAND CERTIFICATION REPORT  ;

1994 l APPENDIX 6 MALFUNCTION TESTING ABSTRACT l Following is a list of the malfunction tests indicating the date the initial certification testing was completed and the date the testing was completed for the first 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. All tests which failed or were placed on hold (due to the need for additional information) during the initial certification testing have been corrected and retested with acceptable results. One additional test (MS01) had failed its retest due to additional information collected on the simulator which did not agree with the expected plant response. This response has also been corrected and retested satisfactorily.

All test procedures have been rewritten to follow the desired format and the malfunction testing section of the original simulator acceptance test procedure has been replaced with these procedures. i MALFUNCTION TESTING Initial Cycle 1 ,

Test Title Type Approval Approval Number Date Date System Overrides EG200 EG TEMPTRANSMITTER SO 08/20/90 05/08/91 FW200 COND FLW TRANSMITTER SO 07/24/90 10/28/92 FW201 CDSR HW TRANSMITTER SO 07/24/90 08/12/92 FW202 11 A FW LEVEL TRANSMITTER SO 07/24/90 08/12/92 FW203 12A FW LEVEL TRANSMITTER SO 07/24/90 08/12/92 i FW204 1IB FW LEVEL TRANSMITTER SO 07/24/90 08/12/92 FW205 12B FW LEVEL TR ANSMITTER SO 07/24/90 08/12/92 FW206 13A FW LEVEL TRANSMITTER SO 07/24/90 08/12/92 FW207 13B FW LEVEL TRANSMITTER SO 07/24/90 08/12/92 FW208 15A FW LEVEL TRANSMITTER SO 07/24/90 08/12/92 FW209 15B FW LEVEL TRANSMITTER SO 07/24/90 08/12/92 MS200 IB MS LEVEL TRANSMITTER SO 08/20/90 01/05/93 MS201 2B MS LEVEL TRANSMITTER SO 08/20/90 01/05/93 MS202 1 A MS LEVEL TRANSMITTER SO 07/24/90 01/05/93 MS203 2A MS LEVEL TRANSMITTER SO 07/24/90 01/05/93 Page 1 l

PRAIRIE ISLAND CERTIFICATION REPORT 1994 APPENDIX 6-Initial Cycle 1 Test Title Type Approval Approval Number Date Date System Overrides RH200 RH FLOW TRANSMITTER SO 07/24/90 05/08/91 RX200 RCS PRESSURE TRANSMITTER SO 01/08/91 12/02/93 RX201 RCS PRESSURE TRANSMITTER SO 01/08/91 12/02/93 RX202 RCS PRESSURE TRANSMITTER SO 01/08/91 12/02/93 RX203 RCS PRESSURE TRANSMITTER SO 01/08/91 12/02/93 RX204 PRZR LVL TRANSMITTER SO 01/25/91 12/02/93 RX205 PRZR LVL TRANSMITTER SO 01/25/91 12/02/93 RX206 SG LEVEL TRANSMITTER SO 01/08/91 01/06/94 RX207 SG LEVEL TRANSMITTER SO 01/08/91 01/06/94 RX208 AUCTIONEERED TAVG SO FAILED 12/02/93 RX209 FW FLOW TRANSMITTER SO 01/08/91 12/02/93 RX210 FW FLOW TRANSMITTER SO 01/08/91 12/02/93 RX211 FW FLOW TRANSMITTER SO 01/08/91 12/02/93 RX212 FW FLOW TRANSMITTER SO 01/08/91 12/02/93 RX213 11/12 MS PRESSURE TRANSMITTER SO 01/08/91 12/02/93 RX214 11 MS PRESSURE TRANSMITTER SO 01/08/91 12/09/93 RX215 11 MS PRESSURE TRANSMITTER SO 01/08/91 12/09/93 RX216 12 MS PRESSURE TRANSMITTER SO 01/08/91 12/09/93 RX217 12 MS PRESSURE TRANSMITTER SO 01/08/91 12/09/93 RX219 11 MS FLOW TRANSMITTER SO 01/08/91 12/09/93 RX220 11 MS FLOW TRANSMITTER SO 01/08/91 12/09/93 RX221 12 MS FLOW TRANSMITTER SO 01/08/91 12/09/93 RX222 12 MS FLOW TRANSMITTER SO 01/08/91 12/09/93 RX223 11 STM FLOW TRANSMITTER SO 01/08/91 12/09/93 RX224 12 STM FLOW TRANSMITTER SO 01/08/91 12/09/93 RX225 11 FEED FLOW TRANSMITTER SO 01/08/91 12/09/93 RX226 12 FEED FLOW TRANSMITTER SO 01/08/91 12/09/93 RX227 11 FEED TEMP TRANSMITTER SO 01/08/91 12/09/93 RX228 12 FEED TEMP TRANSMITTER SO 01/08/91 12/09/93 RX229 FW HDR PRESSURE TRANSMITTER SO 01/08/91 12/09/93 RX230 FW HDR PRESSURE TRANSMITTER SO 01/08/91 12/09/93 RX231 11 SG WR LEVEL TRANSMITTER SO 01/25/91 01/06/94 RX232 12 SG WR LEVEL TRANSMITTER SO 01/25/91 01/06/94 RX233 PZR LEVEL LOCAL CONTROL SO NEW 02/03/94 VC200 VC PRESSURE TRANSMITTER SO 01/08/91 07/28/94 Page 2

PRAIRIE ISLAND CERTIFICATION REPORT 1994 i APPENDIX 6 Initial Cycle 1 Test Title Type Approval Approval Number Date - Date System Overrides VC201 VC TEMPERATURE TRANSMITTER SO FAILED 07/28/94 VC202 VC FLOW TRANSMITTER SO 01/25/91 07/28/94 VC203 VC FLOW TRANSMITTER SO 01/25/91 07/28/94 W.204 VCT LEVEL TRANSMITTER SO NEW 07/28/94 Variable Setooints CH300 CNMT HI/HI-HI PRESS VS 07/24/90 06/21/91 MS300 SG SAFETY VALVES VS 01/21/91 01/29/93 NI300 IR PWR ABOVE P-6 VS 01/25/91 01/06/94 N1302 PR PWR ABOVE P-8 VS 09/25/90 01/20/94 NI306 PR PWR ABOVE P-9 VS 09/25/90 01/20/94 N1310 PR PWR ABOVE P-10 VS 09/25/90 01/20/94 NI316 IR HI FLUX TRIP VS 09/25/90 01/20/94 NI318 PR LO RNG HI FLUX TRIP VS 09/25/90 01/20/94 NI322 PR HI RNG HI FLUX TRIP / POS RATE TRIP / VS 01/28/91 01/20/94 NEG RATE TRIP RP300 P-7 TURB PRESS VS 01/25/91 05/08/91 RP302 AUTO ROD WITHDRAWAL BLOCK P-2 VS 08/20/90 05/08/91 RP303 BUS 11/12 UV TRIP VS 08/20/90 06/21/91 RP305 BUS 11/12 UF TRIP VS 08/20/90 10/11/91 RP307 RC LOW FLOW TRIP VS 08/20/90 12/13/91 RP313 PRZR LO PRESS TRIP /SI VS 01/25/91 12/13/91 RP317 PZR HI PRESS TRIP VS 01/25/91 06/21/91 RP323 PRZR HI LVL TRIP VS 09/25/90 05/08/91 RP326 SG LOLO LVL TRIP VS 09/25/90 06/21/91 RP340 LOLO TAVG STM LN ISOL/HI STM FLOW VS 09/25/90 10/11/91 RP348 SG HI-III STM FLOW VS 09/25/90 10/11/91 RP352 SG LOLO STM PRESS SI VS 09/25/90 06/21/91 RX300 PRZR Hi PRESS PCV VS FAILED 12/09/93 RX302 STM DUMP HI/HI-III TAVG VS 01/25/91 02/03/94 RX305 MASTER PRZR PRESS CONT STPT VS 01/25/91 01/20/94 TC300 INIT TURB CV POS VS 01/03/91 01/06/94 Page 3

PRAIRIE ISLAND CERTIFICATION REPORT 1994 APPENDIX 6 Test Initial Cyclel Number Title Type Approval Approval Date Date l

Malfunctions Annunciator System AN01 NSSS ANNUNCIATOR SYSTEM FAILURE D NEW 01/06/94 Component Cooling System CC01 COMP COOLING WTR PUMP TRIP D 03/02/90 12/13/91 CCO2 COMPONENT COOLING PUMP FAILS TO START D 03/12/90 12/13/91 AUTOMATICALLY CCO4 COMPONENT COOLING WATER SUPPLY VALVE TO D HOLD 01/31/92 RCP FAILS CLOSED CC05 COMPONENT COOLING WATER SYSTEM PIPING V 06/06/90 10/11/91 RUPTURE CC06 CCW VALVE FAILURE TO AUTO OPEN TO RHR D 03/03/90 10/11/91 HEAT EXCHANGER ON PUMP START CCO8 COMPONENT COOLING SURGE TANK AUTO D 05/09/90 05/09/91 MAKEUP FAILURE CCO9 SEAL WATER HEAT EXCHANGER LEAK V 05/09/90 05/08/91 Containment / IIVAC System CH01 CONTAINMENT PRESSURE TRANSMITTER FAILURE V 03/02/90 10/11/91 Cooling Water System CLOl COOLING WATER PUMP TRIP D 03/02/90 12/13/91 CLO2 DIESEL COOLING WATER PUMP FAILS TO START D 03/02/90 12/13/91 AUTOMATICALLY CLO3 121 COOLING WATER PUMP FAILS TO START D 03/02/90 10/28/92 AUTOMATICALLY CLO4 DIESEL COOLING WATER PUMP TRIP D 03/02/90 10/11/91 CLO6 SAFEGUARDS COOLING WATER SUPPLY PIPING V FAILED 01/23/92 RUPTURE CLO7 COOLING WATER SYSTEM TURBINE BUILDING PIPE V 06/06/90 01/17/92 RUPTURE CLO8 COOLING WATER LEAK INSIDE CONTAINMENT V 06/06/90 05/08/91 Reactor Core System CROI FUEL CLADDING FAILURE V 02/13/91 06/21/91 CRO3 REACTOR COOLANT SYSTEM CRUD BURST V 02/13/91 10/11/91 Containment Spray System CS01 CONTAINMENT SPRAY PUMP TRIP D 03/02/90 10/11/91 CS02 CAUSTIC ADDITION VALVE FAILURE TO OPEN IN D 03/02/90 10/11/91 AUTOMATIC Page 4

PRAIRIE ISLAND CERTIFICATION REPORT 1994 APPENDIX 6 CS03 CONTAINhENT SPF \Y PUMP FAILS TO START D 03/02/90 10/11/91 AUTOMATICALLY Circulating Water System CWO2 CIRCULAT1NG WATTER PUMP TRIP D 01/31/91 10/11/91 CWO3 CIRCULATING WATER PUMP BEARING FAILURE D 05/09/90 06/21/91 CWO4 CONDENSER TUBES PLUGGED V 06/06/90 06/21/91 CWOS CONDENSER TUBE RUPTURE V 06/06/90 12/20/91 CWO6 TRAVELING SCREEN BLOCKAGE ONAPPROACH V 06/06/90 06/21/91 CANAL CWO7 CONDENSER PIT FLOOD V 06/06/90 12/13/91 Emergency Diesel Generator DGO1 LOSS OF EMERGENCY DIESEL GENERATOR D 06/06/90 10/28/92 DGO2 EMERGENCY DIESEL GENERATOR FAILS TO START D 07/24/90 10/28/92 DG03 EhERGENCY DIESEL GENERATOR LOAD LIMIT D NEW 12/15/94 FAILURE DG04 EMERGENCY DIESEL GENERATOR OUTPUT D 08/20/90 10/28/92 BREAKER FAILS OPEN DG05 ELECTRONIC GOVERNOR FAILURE D NEW 12/15/94 DG06 24VDC SPLY FOR ELECTRONIC GOVERNOR FAILS D NEW 12/15/94 DG07 DIESEL GENERATOR EMERGENCY START FAILURE D NEW 11/30/94 Electrical Distribution System ED01 LOSS OF OFFSITE POWER D 09/25/90 10/28/92 ED02 1R TRANSFORMER BREAKER FAILS TO CLOSE D NEW 09/28/94 ED03 LOSS OF OFFSITE POWER D 09/25/90 10/28/92 .

ED04 FAULT IN UNIT 1 M TRANSFORhER - AUTO D 09/25/90 06/21/91 l TRANSFER ED05 FAULT IN UNIT I M TRANSFORhER - DELAYED D 09/25/90 05/08/91 AUTO TRANSFER ED06 FAULT IN UNIT SUBSTATION TRANSFORAER D 10/16/90 01/05/93 ED07 LOSS OF 125 VDC BUS D 01/21/91 01/23/92 ED08 LOSS OF 120 VAC INSTRUMENT BUS D 01/28/91 12/20/91 ED09 LOSS OF 4160V BUS D 09/25/90 01/05/93 ED10 LOSS OF 480 VAC BUS D FAILED 10/28/92 EDI1 BUS 15 LOAD REJECTION-RESTORATION V 10/16/90 06/21/91 SEQUENCE TIMER FAILURE ED12 BUS 16 LOAD REJECTION-RESTORATION V 10/16/90 10/28/92 SEQUENCE TIMER FAILURE ED13 VOLTAGE RESTORING SCHEhE SEQUENCER D 10/16/90 10/28/92 FAILURE EDl4 LOSS OF ALL AC D 10/16/90 12/09/93 ED15 DEGRADED GRID VOLTAGE V FAILED 10/28/92 Page 5

PRAIRIE ISLAND CERTIFICATION REPORT 1994 APPENDIX 6 I

ED16 DEGRADED GRID FREQUENCY V 10/16/90 10/28/92 l ED17 FAILURE OF 52Z LOAD SEQUENCER PELAY D NEW 12/15/94 ,

Electrical Generation System  !

EG01 GENERATOR OUTPUT BREAKER FAILS TO OPEN D 06/06/90 12/13/91 l FOLLOWING TURBINE TRIP EG02 LOSS OF GENERATOR HYDROGEN COOLING D 07/24/90 10/11/91 EG03 LOSS OF OFFSITE POWER D 08/20/90 10/11/91 EG05 GENERATOR VOLTAGE REGULATOR FAILURE V HOLD 01/23/92 EG06 GENERATOR FAULT D 06/06/90 10/11/91 EG07 GENERATOR LOSS OF EXCITATION D 06/06/90 10/11/91 Condensate and Feedwater System FW01 CONDENSATE PUMP TRIP D 03/02/90 01/29/93 FWO2 13 CONDENSATE PUMP FAILS TO START D 03/02/90 01/29/93 AUTOMATICALLY FWO3 LOSS OF CONDENSER VACUUM V FAILED 01/05/93 FW05 CONDENSATE PUMP RECIRC VALVE FAILS OPEN D 08/20/90 10/28/92 FWO6 CONDENSATE PUMP RECIRC VALVE FAILS CLOSED D 08/20/90 10/28/92 FWO7 CONDENSATE HOTWELL MAKEUP VALVE FAILS D 03/02/90 01/29/93 OPEN FWO8 CONDENSER HOTWELL MAKEUP VALVE FAILS D 06/06/90 10/28/92 CLOSED FWO9 LP FEEDWATER HEATER BYPASS VALVE FAILS D 06/06/90 10/28/92 OPEN FW10 CONDENSER HOTWELL LEVEL TRANSMITTER D 10/16/90 02/08/93 FAILS HIGH FW11 CONDENSER HOTWELL TRANSMITTER FAILS LOW D 01/21/91 02/08/93 FW13 MAIN FEEDWATER PUMP TRIP D 06/06/90 01/29/93 FW15 FEEDWATER HP HEATER HIGH LEVEL D 04/12/90 08/12/92 FW16 FEEDWATER LP HEATER HIGH LEVEL D 04/12/90 10/28/92 FW17 FEEDWATER HP HEATER LEAK V 07/24/90 10/28/92 FW18 FEEDWATER LP HEATER LEAK V 01/15/91 01/29/93 FW19 FEEDWATER SYSTEM RUPTURE INSIDE V 01/08/91 10/28/92 CONTAINMENT FW20 FEEDWATER SYSTEM LEAKAGE INSIDE V 09/25/90 01/29/93 CONTAINMENT FW21 FEEDWATER SYSTEM RUPTURE INSIDE V 01/08/91 01/29/93 CONTAINMENT UPSTREAM OF CHECK VALVE FW22 FEEDWATER SYSTEM RUPTURE OUTSIDE V 01/15i91 01/29/93 CONTAINMENT FW23 FEEDWATER SYSTEM LEAKAGE OUTSIDE V 09/25/90 01/05/93 i CONTAINhENT Page 6

PRAIRIE ISLAND CERTIFICATION REPORT 1994 APPENDIX 6 FW24 FEEDWATER PUMP COMMON DISCHARGE HEADER V 01/21/91 01/29/93 RUPTURE FW25 FEEDWATER FLOW CONTROL VALVE FAILS TO D 07/24/90 08/12/92 CLOSE ON FW ISOLATION SIGNAL FW26 FEEDWATER FLOW CONTROL VALVE FAILS OPEN V 01/31/91 01/29/93 FW27 FEEDWATER FLOW CONTROL VALVE FAILS D 09/25/90 01;29/93 CLOSED FW28 HEATER DRAIN PUMP TRIP D 03/02/90 01/29/93 FW29 HEATER DRAIN TANK LEVEL TRANSMITTER FAILS D 09/25/90 10/2PS2 HIGH FW30 HEATER DRAIN TANK LEVEL TRANSMITTER FAILS D 09/25/90 01/05/93 LOW FW31 HEATER DRAIN PUMP FAILS TO MINIMUM D 09/25/90 10/28/92 FW32 AUXILIARY FEEDWATER PUMP TRIP - MOTOR D 03/02/90 01/29/93 FW33 AUXILI ARY FEEDWATER PUMP TRIP - TURBINE D 03/02/90 01/29/93 FW34 AUXILIARY FEEDWATER PUMP FAILS TO START D 03/02/90 02/04/93 AUTOMATICALLY FW35 INADEQUATE CONDENSATE TO AUXILIARY V 01/15/90 01/29/93 FEEDWATER PUMP SUCTION RV36 AUXILIARY FEEDWATER DISCHARGE LINE V 01/21/91 01/29/93 RUPTURE INSIDE CONTAINMENT FW37 AUXILIARY FEEDWATER DISCHARGE LINE V 01/08/91 10/28/92 l RUPTURE OUTSIDE CONTAINMENT  !

FW38 AUXILIARY FEEDWATER CONTROL VALVE FAILS D 03/02/90 01/29/93 I IN POSITION  !

RV39 FEEDWATER LINE RUPTURE UPSTREAM OF FW REG V 09/25/90 08/12/92 VALVES FW40 COMMON FEEDWATER PUMP SUCTION LINE V 01/28/91 01/29/93 i BLOCKAGE l FW41 FEEDWATER FLOW CONTROL VALVE LEAKAGE V 01/15/91 01/05/93 Compressed Air System IA01 LOSS OF SERVICE AIR HEADER V 10/16/90 02/08/93 IA02 LOSS OF INSTRUMENT AIR HEADER V 01/28/91 01/06/94 1A03 LOSS OF AIR COMPRESSOR D 03/02/90 02/08/93 Main Steam System l' MS01 MAIN STEAM LINE RUPTURE INSIDE V 01/21/91 12/09/93 CONTAINMENT UPSTREAM OF MSIV MS02 MAIN STEAM LINE RUPTURE OUTSIDE V 01/15/91 01/29/93 CONTAINMENT UPSTREAM OF MSIV MS03 MAIN STEAM LINE RUPTURE OUTSIDE V 09/25/90 01/29/93 CONTAINMENT DOWNSTREAM OF MSIV Page 7

l PRAIRIE ISLAND CERTIFICATION REPORT 1994 APPENDIX 6 MSO4 MAIN STEAM LINE LEAK V 09/25/90 01/29/93 MS05 MAIN STEAM SAFETY VALVE STICKS OPEN D 05/09/90 01/29/93 l

MS06 GLAND SEAL STEAM REGULATING VALVE FAILS D 09/25/90 01/29/93 CLOSED MS08 MOISTURE SEPARATOR - REHEATER RELIEF D 01/08/91 01/29/93 i VALVES FAILURE i MS09 MAIN STEAM LINE LEAK INSIDE CONTAINMENT V 01/21/91 02/04/93 MS10 MAIN STEAM LINE BREAK ON COMMON SUPPLY V HOLD 01/29/93 LINE TO AFW MSI1 STEAM DUMP VALVE FAILS IN POSITION D 01/31/91 01/29/93 Nuclear Instrumentation System l NIO1 INCORRECT SOURCE RANGE CHANNEL RESPONSE V 05/09/90 01/06/94 NIO2 SOURCE RANGE CHANNEL SPIKES D 05/09/90 01/06/94 l NIO3 INTERMEDIATE RANGE CHANNEL IMPROPER V 05/09/90 01/06/94  ;

RESPONSE  :

NIO4 INTERMEDIATE RANGE CHANNEL IMPROPER V 01/21/91 12/21/94 l COMPENSATION NIO5 IMPROPER POWER CHANNEL RESPONSE V 10/16/90 01/20/95 i NIO6 POWER RANGE UPPER CHANNEL IMPROPER V 01/21/91 12/21/94 [

RESPONSE

NIO7 POWER RANGE LOWER CHANNEL IMPROPER V 01/21/91 12/15/94 RESPONSE l Plant Process Computer System  ;

PC01 ERCS CPU FAILURE D 09/25/90 01/06/94 PC03 ERCS ALARM DISPLAY FAILURE D FAILED 01/20/94 l PC04 ERCS SAS DISPLAY FAILURE D FAILED 01/20/94 PC05 ERCS CONTROL ROOM PRINTER FAILURE D FAILED 01/20/94 Reactor Coolant System RC01 REACTOR COOLANT PUMP TRIP D 10/16/90 01/06/95 .

RC02 REACTOR COOLANT PUMP LOCKED ROTOR D HOLD 01/20/94 RC04 REACTOR COOLANT PUMP SHAFT SHEAR D 10/16/90 01/06/95 RC05 REACTOR COOLANT PUMP BEARING FAILURE V 10/25/90 01/06/95 i RC06 LOSS OF COOLANT ACCIDENT - HOT LEG V 01/28/91 12/21/94 RC07 LOSS OF COOLANT ACCIDENT - COLD LEG RCP V 01/15/91 12/21/94 SUCTION RC08 LOSS OF COOLANT ACCIDENT - COLD LEG RCP V 01/28/91 12/21/94 DISCHARGE RC09 LOSS OF COOLANT ACCIDENT PRESSURIZER V 01/25/91 10/06/94 STEAM SPACE RC10 LOSS OF COOLANT ACCIDENT PRESSURIZER V 01/21/91 10/06/94 WATER SPACE Page B I

i

PRAIRIE ISLAND CERTIFICATION REPORT 1994 APPENDIX 6 ,

I RC11 LOSS OF COOLANT ACCIDENT - RTD BYPASS LOOP V FAII.ED 02/03/94 l COLD LEG MANIFOLD l RC12 LOSS OF COOLANT ACCIDENT - RTD BYPASS LOOP V 01/15/91 01/06/95 RETURN LEG PIPING  !

RCl3 LOSS OF COOLANT ACCIDENT - REACTOR HEAD V 01/31/91 01/06/95  :

VENT )

RCl4 REACTOR COOLANT SYSTEM LEAKS V 01/21/91 12/21/94 RC15 REACTOR COOLANT SYSTEM LEAKS V 01/15/91 12/15/94 RC16 PRESSURIZER POWER OPERATED RELIEF VALVE D 01/21/91 10/06/94  ;

l FAILS CLOSED RCl8 PRESSURIZER SAFETY VALVE RC-10-1 FAILS OPEN D 02/05/90 01/06/95 RC19 PRESSURIZER SAFETY VALVE SEAT LEAKS V 02/05/90 01/06/95 RC20 REACTOR COOLANT PUMP OIL LEAK UPPER D 01/21/91 01/06/95 RESERVOIR RC21 REACTOR VESSEL O-RING LEAKAGE D 01/28/91 01/20/95 ,

RC22 PRESSURIZER POWER OPERATED RELIEF VALVE V 10/25/90 01/20/95 LEAKAGE RC24 PRESSURIZER SPRAY VALVE FAILS IN POSITION D 10/25/90 01/06/95 Control Rod Drive System RD01 CONTROLLING ROD BANK FAILS TO MOVE IN D 03/02/90 01/29/93 MANUAL RD02 CONTROLLING ROD BANK FAILS TO MOVE IN D 03/02/90 02/04/93 AUTO RD03 UNCONTROLLED CONTINUOUS ROD WITHDRAWAL D 03/02/90 02/04/93 l

OF CONTROLLING BANK RD04 UNCONTROLLED CONTINUOUS ROD INSERTION OF D 03/03/90 02/08/93 i CONTROLING bah % i RDOS CONTROL ROD MISALIGNMENT D 01/21/91 02/04/93 RD06 STUCK ROD D 03/02/90 02/04/93 RD07 DROPPED ROD D HOLD 12/09/93 RD08 CONTROL ROD G-3 EJECTED D 01/21/91 01/29/93 RD09 ROD POSITION INDICATION FAILS D 03/02/90 01/29/93 RD10 INCORRECT ROD SPEED D 03/02/90 02/08/93 1 Residual Heat Removal System RH01 RESIDUAL HEAT REMOVAL PUMP TRIP D 03/02/90 06/21/91 RH02 RESIDUAL HEAT REMOVAL PUMP FAILS TO START D 03/02/90 06/21/91 AUTOMATICALLY RH03 RHR HEAT EXCHANGER END BELL LEAKAGE TO V 08/20/90 05/08/91 1 I

ATMOSPHERE RH04 RHR HEAT EXCHANGER BYPASS VALVE FAILS D 08/20/90 06/21/91 OPEN Page 9

PRAIRIE ISLAND CERTIFICATION REPORT 1994 APPENDIX 6 RHO 5 RH.R HEAT EXCHANGER BYPASS VALVE FAILS D 09/20/90 05/08/91 CLOSED RIlO6 RECIRCULATION SUMP SUCTION LINES BLOCKED V 08/20/90 06/21/91 RHO 7 RHR SYSTEM LEAKAGE V 10/16/90 06/21/91 RHO 8 RHR PUMP SEAL FAILURE D 08/20/90 10/11/91 RHO 9 RESIDUAL REAT REMOVAL RELIEF VALVE D 08/20/90 10/11/91 FAILURE Reactor Protection System RP01 REACTOR TRIP D 01/08/91 05/08/91 RP02 FAILURE OF AUTOMATIC REACTOR TRIPS D 08/20/90 05/08/91 RP03 FAILURE OF SAFETY SYSTEMS TO ACTUATE D 01/25/91 10/11/91 RPO4 INADVERTENT ACTUATION OF THE SAFETY D 01/08/91 06/21/91 INJECTION SYSTEM RP05 FAILURE OF CONTAINMENT ISOLATION PHASE A D 01/25/91 05/08/91 TO ACTUATE RP06 FAILURE OF MSIV'S TO ISOLATE D 01/08/91 06/21/91 RP07 MECHANICAL FAILURE OF REACTOR TRIP D 01/08/91 06/21/91 BREAKERS RP08 FAILURE OF SAFEGUARDS ACTUATION D 01/25/90 05/08/91 Reactor Control System RX01 PRESSURIZER SPRAY VALVE FAILS OPEN V 03/02/90 11/24/93 RX02 PRESSURIZER SPRAY VALVES PCV-431 A & B FAIL D 03/02/90 01/06/94 CLOSED RX03 PRESSURIZER HEATERS FAIL ON D 03/02/90 11/24/93 RX04 PRESSURIZER HEATERS FAIL OFF (ALL) D 03/02/90 11/24/93 RX05 REACTOR COOLANT LOOP TH TRANSMITTER FAILS D 03/02/90 02/09/94 l

HIGH RXO6 REACTOR COOLANT LOOP TH TRANSMITTER FAILS D 03/02/90 02/09/94 LOW RX07 REACTOR COOLANT TC TRANSMITTER FAILS HIGH D 03/02/90 02/09/94 RXO8 REACTOR COOLANT LOOP TC TRANSMITTER FAILS D 03/02/90 02/09/94 LOW RX09 PRESSURIZER LEVEL NARROW RANGE D 04/12/90 11/24/93 TRANSMITTER FAILS HIGH RX10 PRESSURIZER LEVEL NARROW RANGE D 04/12/90 11/24/93 TRANSMITTER LOW RX11 PRESSURIZER PRESSURE TRANSMITTER FAILS D 01/21/91 11/24/93 HIGH RX12 PRESSURIZER PRESSURE TRANSMITTER FAILS LOW D 01/21/91 11/24/93 RX13 REACTOR COOLANT SYSTEM WIDE RANGE D 04/12/90 11/24/93 PRESSURE TRANSMITTER FAILS HIGH )

i Page 10 j

l PRAIRIE ISLAND CERTIFICATION REPORT 1994 APPENDIX 6 RX14 REACTOR COOLANT SYSTEM WIDE RANGE D 04/12/90 12/09/93 PRESSURE TRANSMITTER FAILS LOW RX15 STEAM GENERATOR LEVEL TRANSMITTER FAILS D 03/02/90 11/24/93 HIGH RX16 STEAM GENERATOR LEVEL TRANSMITTER FAILS D 03/02/90 01/06/94 j LOW j RX17 STEAM GENERATOR PRESSURE TRANSMITTER D 03/02/90 11/24/93 FAILS HIGH RX18 STEAM GENERATOR PRESSURE TRANSMITTER D 03/02/90 12/02/93 l

FAILS LOW RX19 MAIN STEAM LINE STEAM FLOW TRANSMITTER D 03/02/90 12/15/94  :

FAILS HIGH RX20 MAIN STEAM LINE STEAM FLOW TRANSMITTER D 03/02/90 12/15/94 FAILS LOW .

RX22 FEEDWATER CONTROLLER OUTPUT FAILURE V 04/12/90 12/02/93 l RX23 FEEDWATER LINE FLOW TRANSMITTER FAILS D 03/02/90 12/15/94 HIGH RX24 FEEDWATER LINE FLOW TRANSMITTER FAILS LOW D 03/02/90 12/15/94 RX25 TURBINE FIRST STAGE PRESSURE TRANSMITTER D 03/02/90 12/07/94 l FAILS HIGH RX26 TURBINE FIRST STAGE PRESSURE TRANSMITTER D 03/02/90 12/07/94 FAILS LOW RX27 STM GEN FEEDWATER INLET TEMPERATURE D 03/02/90 12/07/94 i TRANSMITTER FAILS HIGH l RX28 STM GEN FEEDWATER TEMPERATURE D 03/02/90 12/07/94 )

TRANSMITTER FAILS LOW RX29 FEEDWATER HEADER PRESSURE TRANSMITTER D 03/02/90 12/07/94 FAILS HIGH RX30 FEEDWATER HEADER PRESSURE TRANSMITTER D 03/02/90 12/07/94 FAILS LOW RX31 STEAM GENERATOR WIDE RANGE LEEL D 03/02/90 12/07/94 j TRANSMITTER FAILS HIGH RX32 STEAM GENERATOR WIDE RANGE LEVEL D 03/02/90 12/07/94 TRANSMITTER FAILS LOW RX33 STEAM GENERATOR FEEDWATER CONTROL D 03/02/90 12/07/94 SYSTEM FAILS TO MANUAL RX34 ADFCS MAIN FLOW CONTROL VALVE OUTPUT D 03/02/90 12/07/94 CARD FAILURE RX35 ADFCS BYPASS FLOW CONTROL VALVE OUTPUT D 04/12/90 12/02/93 CARD FAILURE Steam Generator System 1

Page 11

PRAIRIE ISLAND CERTIFICATION REPORT 1994 APPENDIX 6 SG01 STEAM GENERATOR TUBE LEAK V 01/28/91 01/06/95 SG02 STEAM GENERATOR TUBE RUPTURE V 01/28/91 01/06/95 SG03 STEAM GENERATOR BLOWDOWN CONTROL VALVE D FAILED 01/20/95 FAILS OPEN Safety Injection System SIOl BOTH BORIC ACID TANK VALVES FAIL TO OPEN IN D 10/25/90 02/04/93 AUTO SIO2 SI LOOP A COLD LEG INJ CHECK VALVE FAILURE D 10/25/90 01/20/95 SIO3 BORIC ACID TANK VALVE FAILS TO CLOSE ON LO- D 10/25/90 01/20/95 LO LEVEL IN THE PRESELECTED BORIC ACID TANK IN AUTO SIO4 SAFETY INJECTION PUMP TRIPS D 03/02/90 02/08/93 SIO5 SAFETY INJECTION PUMP FAILS TO START D 03/02/90 01/06/95 AUTOMATICALLY SIO6 SI ACCUMULATOR LEAKAGE D 10/25/90 01/20/95 SIO7 SI ACCUMULATOR CHECK VALVE LEAKAGE D 10/25/90 01/20/95 SIO8 SI ACCUMULATOR RELIEF V ALVE LEAKAGE D 10/25/90 01/20/95 S109 SI COLD LEG INJ LINE RUPTURE INSIDE OF THE V 01/25/91 01/20/95 ANNULUS Turbine Control Egtem TC01 TURBINE STCP 'v ALVE FAILS TO CLOSE WHEN D 03/02/90 07/22/94 REQUIRED TC02 TURBINE STOP VALVE FAILS CLOSED D 03/02/90 07/22/94 TC03 TURBINE CONTROL SYSTEM CYCLING OUTPUT V 01/15/91 07/22/94 TC04 TURBINE CONTROL VALVE FAILS OPEN D FAILED 01/20/94 TC05 TURBINE CONTROL VALVE FAILS CLOSED D 10/25/90 07/22/94 TC06 REACTOR PROTECTION SYSTEM FAILS TO TRIP D 03/02/90 07/22/94 TURBINE TC07 TURBINE CONTROL INTERCEPT VALVE D 03/02/90 07/22/94 TC08 TURBINE CONTROL FAILURE DURING TURBINE D 10/25/90 07/22/94 ROLL TC09 TURBINE CONTROL FAILURE CAUSING TURBINE D 01/15/91 07/28/94 RUNBACK TC10 TURBINE CONTROL FAILURE CAUSING AN D 10/25/90 07/22/94 INCREASE IN POWER WITHOUT DEMAhT) l TClI COMPLETE TURBINE TRIP FAILURE D FAILED 07/22/94 1 TCl2 TURBINE TRIP D 10/25/90 07/28/94 TC13 ELECTRICAL HYDRAULIC CONTROL PUMP TRIP D 03/02/90 07/22/94 TCl4 TURBINE CONTROL VALVE FAILS IN POSITION D NEW 12/07/94 Turbine System TU01 LOSS OF TURBINE LUBE OIL SUPPLY V HOLD 01/06/94 Page 12 1

PRAIRIE ISLAND CERTIFICATION REPORT 1994 APPENDIX 6 TUO2 TURBINE GENERATOR VIBRATION V 10/25/90 09/28/94 Chemical and Volume Control System VC01 REACTOR COOLANT PUMP #1 SEAL FAILURE V 01/28/91 02/03/94 c VC02 REACTOR COOLANT PUMP #2 SEAL FAILURE D 01/25/91 01/20/94 VC04 POSITIVE DISPLACEhENT CHARGING PUMP TRIP D 07/24/90 01/20/94 VC05 STUCK OPEN CHARGING PUMP RELIEF VALVE D NEW 07/22/94 VC06 REGENERATIVE HEAT EXCHANGER LEAKAGE V 01/28/91 01/20/94 VC07 LETDOWN HEAT EXCHANGER LEAKAGE TO V 01/25/91 09/28/94 ATMOSPHERE VC08 LETDOWN HEAT EXCHANGER TUBE RUPTURE TO D 01/15/91 07/28/94 CCW SYSTEM VC09 LETDOWN LINE LEAKAGE INSIDE CONTAINhENT V 01/08/91 09/28/94 VC10 CHARGING PUMP COMMON DISCHARGE HEADER V 01/15/91 09/28/94 RUPTURE VCl1 CHARGING LINE LEAKAGE INSIDE CONTAINAENT V 01/28/91 11/30/94 VCl2 EMERGENCY BORATION VALVE STUCK OPEN D 01/28/91 09/28/94 VC13 LETDOWN LINE RELIEF VALVE FAILURE D 01/15/91 07/28/94 VCl4 VOLUME CONTROL TANK RELIEF VALVE FAILURE D 01/28/91 09/28/94 VC19 LOSS OF AIR TO CHARGING PUMP SPEED D 01/28/91 07/28/94 CONTROLLER VC20 CCW RETURN FROM LETDOWN HEAT EXCHANGER D 01/15/91 07/28/94  :

FAILS CLOSED l VC21 REACTOR COOLANT PUMP THERMAL B ARRIER V 01/28/91 09/28/94 TUBE FAILURE l

Page 13 l

PRAIRIE ISIAND SIMULATOR CERTIFICATION REPORT 1994 APPENDIX 7 LER TESTING ABSTRACTS The following list of Licensee Event Reports were tested on the Prairie Island Simulator during the period from February 1991 to January 1995. The initial conditions for each test were chosen from the available protected IC sets and then manipulated to achieve the initial conditions which best matched the plant conditions in the event report.

Simulator malfunctions, remote functions,1/0 overrides and control manipulations were then used to recreate the event and the simulator response was compared to the plant response documented in the event report.

LER Title Test Date Results Number P-SOE No.12 DCLP Tripped On 11/25/91 Correct Response 90-004 Overspeed P-RE Reactor Trip Due To Bus Duct 1/30/92 Correct Response 90-017 Coolong System P-RE Auto Start Of One Train Of 1/30/92 Correct Response 90-014 Control Room Special Vent P-RE Reactor Trip Due To Rod Control 1/30/92 Correct Response 90-012 System Failure P-RE Inadvertant Operation A 1/30/92 Correct Response 010 Safeguard Logic Train Pushbutton P-RE Autostart Of A CC Pump During 1/24/95 Correct Response 90-009 Surveillance Test P-RE Auto Start Of A CC Pump While 1/24/95 Correct Response 90-008 Switching RHR Pumps P-RE Auto Start Of AFW Pump Due To 1/30/92 Correct Response 90-005 Failure To Follow Procedure P-RE Reactor Trip Due To Rod Control 1/30/92 Correct Response 90-004 System Failure With Substation 345KV Breaker Failure P-RE Auto Start Of 12 Diesel Cooling 1/30/92 Correct Response 90-003 Water Pump Page 1

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1994 APPENDIX 7 P-RE Reactor Trip While 1/30/92 Correct Response 90-003 Troubleshooting rod Control System P-R E Reactor Trip Due To Failed 1/30/92 Correct Response 90-002 Reactor Protection Logic Relay P-R E Reactor Trip And Generator 1/30/92 Correct Response 90-001 Lockout Due To Bus Duct Cooling System Failure 1-91-011 Unit 1 Trip As Result Of Rod 2/3/93 Correct Response Control System Failure 2-92-001 Unplanned Auto Start Of An 2/3/93 Correct Response Auxiliary Feedwater Pump Due To Personnel Error 2-92-003 Auto Start Of A Motor Driven 2/2/93 Correct Response Auxiliary Feedwater Pump Due To Personnel Error During Surveillance Testing 1-92-014 One Steam Generator Safety 2/3/93 Correct Response Valve Setpoint Found 3% Low 1-93-05 linit 1 Reactor Trip Caused By 1/20/94 Correct Response Bus 12 86 Lockout 1-93-08 Containment Isolation Valve 1/21/94 Correct Response Failed Closed 1-93-09 Unplanned closure Of A 1/21/94 Correct Response Containment Isolation Valve 2-93-01 22 Component Cooling Pump 1/4/93 Correct Response Auto Start 1-93-06 Auto Start Of 121 Cooling Water 1/31/94 Simulator did not Pump respond correctly.

Discrepancy report written to model correct response.

Page 2

e t

PRAIRIE ISIAND SIMUIATOR CERTIFICATION REPORT 1994 APPENDIX 7 1-94-01 121 Cooling Water Pump Auto 1/24/95 Identical LER to 1 Start

06. Simulator DR in progress.

1-94-02 Generator frip - Reactor Trip 1/26/95 Correct Response Caused by Failure of Fire Protection in Near Bus Duct 1-94-06 Letdown isola'ed When Charging 1/26/95 Correct Response i

1-94-12 Pump Tripped 2-94-03 Auto Start of One Train of ABSV 1/26/95 Correct Response on High Radiation - R30 Page 3