ML20067C930

Simulator Certification Rept for Prairie Island Plant Simulation Facility

ML20067C930
Person / Time
Site:	Prairie Island
Issue date:	02/01/1991
From:	NORTHERN STATES POWER CO.
To:
Shared Package
ML20067C928	List: ML20067C926 ML20067C930
References
NUDOCS 9102120254
Download: ML20067C930 (128)

Text

1 PRAIRIE ISLAND SIMUL.ATOR CERTIFICATION REPORT 1990 SIMULATOR CERTIFICATION REPORT FOR THE PRAIRIE ISLAND PLANT SIMULATION FACILITY Drafted Ily: ', --

Date: A,3/'f/

Certification Review Panel Review:

A !' 9i

~

Reviewed By: -Abdt Date:

Reviewed By 2( Date: 0\'\9\

Reviewed B Date:

W Approved 13y: * -

Date: L!/ /

Page 1 of 10 pitc/ reports 910212o254 91020s PDR AnocK05cogrg2 P

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d PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1990 TABLE OF CONTENTS Iltle Page Simulator Certificat bn Report Cover Page . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . - 1 Tab l e o f C o n t en t s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . -2 1

A p pe n d i c e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 i

1. I NTR O D U CTI O N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 i

A . Facili ty I n fo rmati o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

. 4 II. Cont rol Room I n formation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 C . I n st ru c t or 's I n t erface . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 i

D. Op:: rating l'roced ures for the Reference Plant . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 E. C h an ges f e nce the Last Report . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 II S I M U L A% ) R D ES I G N D ATA . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 III . _ SIM ULaTO R TESTING . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .................-8

- A. . Simulator Pertoruumce Testing . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8' 13 ; Simulator Operability Testing . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8-C . Testing Results R eview . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 IV. CONFIG UllATION M AN AG EMENT SYSTEM . . . . . . . . . . . . . . . . . . . . . . . . . . . 9-Page 2 of 10 pitc/ reports

i PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1990 APPENDICES  !

Appendix- 1 Evaluation of Simulator Physical Fidelity and Differences Iletween Plants and Simulator FIGURE 1 A Plant Control Room Layout FIGURE 111 Simulator Layout Appendix 2 Instructors Interface Capabilities Appendix 3 Instructors Interface Capabilities TABLE 3A Cross Reference Between ANS 3.5 Requirements and PI ,

Simulator Malfunctions TABLE 3B Simulator Initial Conditions TABLE 3C Simulator Operating Limits Appendix 4 Certification Review Panel Members Appendix 5 Four Year Testing Schedule

-Appendix 6 Annual Testing Abstracts TABLE 6A Simulator Certification Testing Critical Parameter List Appendix 7 Malfunction Test Procedure Sample Appendix 8- _ Malfunction Testing Abstracts Appendix 9 LER Testing Abstracts l Appendix 10 Evaluation of the Prairie Island Simulator Configuration Management

! Program Against the ANS/ ANSI 3.5-1985 Requirements Appendix 11 Documents Available for Training Use on the Simulator l

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PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1990

1. INTRODUCTION The purpose of the Prairic Island Simulator Certification 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 hereby certified for the Prairie Island Plant Units 1 and 2.

This report will be issued annually .with the initial report issued in February 1991. The first report will describe the simulator as it was delivered, plus any changes made up to the report issue date. Subsequent reports will describe any changes since the last report. A summary of the testing and resolution of discrepancies will be included in each report. <

A. Facility Information Prairic Island Unit 1 Docket Number 50-282 License Number DPR-42 Prairic Island Unit 2 Docket Number 50-306 License Number DPR-60 Licensee: Northern States Power Company Simulation Facility:

Owner / Operator Northern States Power Co.

Manufacturer Singer-Link (presently S-3 Technologies)

Date Available for Training February 6,1984 Type of Report Initial _ Certification B. Control Room-Information Figure 1 A is a layout of the plant Control Room and Figure IB 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 I half of the control room plus the necessary portions of the shared systems on Panel A and additionally certain Unit 2 systems with crosstic capability with Unit 1. The differences between the simulator and the plant control room physical arrangement, communications systems, audible environment, lighting, control panels, and systems are presented in Appendix 1.

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PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1990-C. Instructors Interface ,

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

The control panel and remote device functions are as follows:

Control Panel Remote Device

1. Emergency Power Off 1. Freeze

2. Recorder Powcr Off 2. Reset /Run

3. Computer Fault / Alarm Silence 3. Switch 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 Selection

11. Record Keys

12. Replay

13. Backtrack

~ 14. Forward

, 15. Reverse

16. Annunciator Sound Silence

17. Annunciator Lamp Acknowledge

18. Annunciator Reset

19. ERCS Fault / Override

20. Plant Page Hand Set

21. - Simulator Operating Limits / Override The functions available on the keyboard are presented ;n appendix 2. An evaluation of the instructor interface func.tions available against the requirements in ANS/ ANSI 3.5-1985 is presented in Appendix 3.

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r PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1990-D. Operating Procedures for the Reference Plant Controlled copics of the Prairic Island Nuclear Generating Plant (PINOP)

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 Procedures are used on the Prairic Island Simulator. Occasionally i draft revisions to selected procedures will be used to validate the procedure revisions prior to use in the plant or to provide the operations personnel training on significant Control Room modifications prior to installation in the plant. The period of use of draft procedures on the simulator is limited to the minimum necessary to provido 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 differences being the individual component identification numbers. Some procedures are currently " shared" procedures, with component numbers for both units included in the steps. In these cases  :

the Unit #2 component numbers are enclosed in brackets ([ ]) to separate them from the Unit #1 component numbers. During the normal review / revision process the procedures are being separated to provide individual unit specific procedures. 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 -his are the procedures which are kept in the Shift Supervisor's office in the plant. These procedures (eg. Startup Checklists, System Descriptions and Special Operating Procedures) are kept in locations on the simulator convenient to the operators. The appearance of the procedures is duplicated by using the same binders as those used in the plant control room.

Administrative procedures and references provided in the Unit #1 control I room are also available in the simulator area. Appendix 11 contains a list of I the documents which are available on the simulator.

J E. Changes Since Last Report None - Initial Certification Report Page 6 of 10 pite/ reports v -w w y+4 w - -w- w

L PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1990-

11. SIMULATOR DESIGN DATA A. 'ihe simulator design database is composed of three parts:

1. The initial database consists of the documents and data sent to Singer-Link which were used to design, construct and test the simulator.

This consisted of required plant drawings, technical manuals and collected plant data (control board pictures, plant process computer printouts, startup test results, etc.). This data was archived following receipt of the simulator and completion of the final acceptance testing. Lists of these documents are available at the Prairic Island Training Center on microfilm. Following delivery of the simulator a review was performed to determine which plant modifications had been included in the design data base.

2. Modifications and additions to the simulator database, as changes are '

made on 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 liardware Drawings Simulator Procedures Simulator Correspondence  ;

Simulator Performance Tests Simulator Design Review Committee Meeting Minutes Simulator Change Index ModifF ion Tracking Log Discrepancy Reports Simulator Improvement Requests -

Initial Condition Updates Form Benchmarking Files Simulator Work Requests

3. Several of the documcatation files included in each simulator change l '

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 documentation files (DAADS).

The accumulation of all. these records plus the current plant drawings and technical manuals (essentially updates of the original information which was sent to Singer-Link) composes the current simulator desiga database.

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l PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1990 l

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HI, SIMULATOR TESTING  !

l A. Simulator Performance Testing A Factory . Acceptance Test was conducted at the vendor facilities (Singer-Link)_ of the completed simulator from 8/83 until 11/83. Much of this test was repeated on site from 1/84 until 2/6/84. This test verified accurate modeling of all included plant systems and also verified correct performance of all available malfunctions. This testing was conducted by Prairic Island licensed personnel and produced a large number of discrepancies which were largely corrected by Singer-Link. All discrepancies resulting from this testing have been corrected or determined to not be significant to training, i

Simulator Procedure #11 addresses Performance Testing -and requires that  ;

performance testing be repeated if simulator changes result in significant simulator configuration or performance variations, i: B. Simulator Operability Testing 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 5 and abstracts of the annual test procedures are included as Appendix 6. The first annual test was completed in 1989 and will be completed annually.

This test includes 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 5 contains the schedule ~of testing for the next four year cycle. Note that this schedule may change slightly due to additions or deletions of malfunctions.

For this initial certification all malfunction- tests were completed during 1989 and 1990. Abstracts of these completed malfunction tests are included as Appendix 8 and samples of the malfunction test procedures are included as Appendix 7. Also included in Appendix _8 is a list of malfunctions which failed their test. The failure of these tests does not adversely affect certification of the simulator since all malfunctions required in ANSI /ANS 3.5-1985 are available. All simulator instructors Page 8 of 10 pitc/ reports l

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1990 are informed of these test failures, and the details of the simulator responso are available for review prior to conducting training.

Simulator operability testing requirements are included in Simulator Procedure #20. This procedure spells out the requirement for continuous testing of malfunctions over a four year cycle and the annual testing requirements.

In addition to the testing required by ANS/ ANSI 3.5-1985 we have determined that testing of all plant Licensee Events is a prudent practice.

An index of Licensee Event testing completed is included in Appendix 9.

C. Testing Results Review Results from all testing completed for simr 'r certification were reviewed by a panel of experts for agreement with u.e expected results listed in the procedure and with the results recorded du-ing testing. A list of the experts included in this panel and their qualifications is included as Appendix 4.

IV. CONFIGURATION MANAGEMENT SYSTEM A. The Configuration Management System for the Prairic Island simulator has five basic objectives:

1. Maintain a current simulator database.

2. Track, resolve and test identified simulator discrepancies.

3. Evaluate, implement and track simulator design enhancements.

4. Identify, track, evaluate, implement and test simulator configuration changes due to reference plant modifications or operating experience.

5. Verify - that the current simulator configuration complies with the functional and physical fidelity specifications - described in the design database.

B. These objectives are met using a database system based on dBase III+ and extensive documentation of changes made to the simulator hardware or software. The process for tracking, resolution and testing of identified changes to the simulator consists of the following parts:

1. A description of the simulator design database is included in Section II of-this submittal.

2. Simulator discrepancies are tracked, resolved and tested following the process spelled out in the simulator procedures. The tracking is performed using s database based on dBase III+. Resolution and testing Page 9 of 10 pitc/ reports l

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1990 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 design database.

3. Evaluation of proposed simulator design enhancement is performed by the Simulator Design Review Committee which is made up 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 discrepancies.

4. Plant modifications are tracked using the plant modification database.

This database is downloaded, from the computer system it resides in, to a Simulator Group PC and then compared against the tracking database maintained. All changes and additions are identified and tracking forms initiated. The tracking database is then updated to match the current plant database. 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 turnover to operations or a closcout), the Simulator Design Review Committee reviews this modification to determine if it requires changes to the simulator. If simulator changes are required a simulator change is initiated and tracked the same as all other simulator changes.

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

5. Verification that the current simulator configuration complies with the functional and physical fidelity specifications described in the design database was accomplished by completion of final acceptance testing after delivery of the simulator from Singer-Link. Continuing verification is accomplished by testing of each simulator change prior to use for training, verification of each discrepancy report against plant documents prior to making simulator changes, and testing as required for Simulator Certification.

Included in the testing for Certification are comparisons against the plant physical configuration (using photographs of the plant controls) periodically during the four year testing cycle.

An evaluation of the Configuration Management requirements included in ANS/ ANSI 3.5-1985 as compared to the procedural controls used for the Prairic Island simulator is included in Appendix 10.

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PRAIRIE ISLAND SIMUIATOR CERTIFICATION REPORT 1990 APPENDIX 1 Evaluation of Simulator Physical Fidelity and Differences Between Plants and Simulator 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 modelling is referenced to Prairie Island Unit 1.

The differences between the simulator and each unit are identified and justification is presented for all differences which do not adversely affect training. 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 1A and 1B the physical arrangement of the simulator duplicates the Prairie 7sland Unit 1 control room with the fo] lowing exceptions:

a. The Shift Supervisor's office is similar in appearance from the outside but is used on the simulator for the instructor's booth. None of the equipment located in the plant Shift Supervisor's office is included on the simulator. The manuals located in the plant Shift Supervisor's office are located in a bookshelf against the wall outside the SS office area on the simulator. The stairway leading to the Shift Supervisor's office is located in a different position in the simulator than in the plant.

l b. The carpetting in the simulator is a different color than in the plant control room. Additionally the plant' flooring consists of carpeted tiles with a black plastic edging while the simulator carpetting 1 does not have this black edging,

c. The simulator room has a flashing red light mounted l

in the ceiling which will alarm when the Halon fire protection system is actuated. The plant control room does not have this equipment.

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l PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1990

-I APPENDIX 1

d. The simulator room has three ceiling mounted cameras enclosed-in black plastic " bubbles" which are used during training to record the trainees-responses.

This equipment does not exist in the plant control room.

The following differences also exist between the Unit 2 control room physical arrangement and the simulatort

a. Unit 2 control room is a mirror image of the Unit 1 control room. Simulator duplicates the Unit 3 control room.

None of these differences will affect performance of any o normal, abnormal or emergenc operating procedures.

' None of these differences wi{.1 lead to operation or judgement errors on the part of a student during responses to a malfunction or emergency. None of these differences affects any task on the Shift Manager /Supv or Control Room Operator tasklists.

These' differences have been reviewed by the Simulator Design Review-Committee and are considered minor. The requireme: ts of ANSI /ANS 3.5-1985 Section 3.2.3 are ratisfied.

2. Communications Systems

'The communications systems available in the plant control room are available and--functional on the simulator to the

extent that the simulator instructor can communicate over.the

. appropriate system when acting as a remote operator or.other support personnel with the following exceptions:

a. The plant radio system is not included on the simulator however a pair of portable radios are available-for use which are similar-in appearance and function to'the portable radios available in l -the plant.

L None of'these differences will affect performance of any L abnormal or emergency operating procedures. None of normal,ifferences these d will lead to operation or judgement errors on'the part of a student during responses to a malfunction or emergency. None of these differences affects any-task on the-Shift Manager /Supv or Control Room Operator tasklints.

i These differences have been reviewed by the Simulator Design

!. Review Committee and are-considered minor. The requirements of ANSI /ANS 3.5-1985 Section 3.2.3 are satisfied.

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PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1990 APPENDIX 1

3. Audible Environment The simulator duplicates the plant control room audible environment as far as noise levels, control rod step counter noise,ing follow differences: flow integrator noises, and annunciator horns with the

a. Turbine noise ~is not specifically simulated. A partial simulation is included when the door to the Turbine Room is opened on the simulator. However this noise simulation is presently not functioning.

This discrepancy is being tracked with DR# 89D-112.

b. Control rod step counter noise is similar to the plant step counter noise; however since the step-counters on the simulator have been replaced with electronic LCD counters (in anticipation of the plant modification) the step counter noise is slightly different on the simulator. This difference is being tracked with plant modification # 88L-054.

None of these differences will affect-performance of any  !

normal,-abnormal or emergency operating procedures. None of these differences will lead to operation or judgement-errors on the part of a student.during responses to a malfunction or emergency. None of-these differences affects any task on the Shift Manager /Supy or Control Room Operator tasklists.

I-These differences have been reviewed by the Simulator Design Review Committee and are considered minor. The requirements

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

c. The general noise level on the simulator is' i approximately twice as loud (3dB higher) as the noise level in the plant Control Room. Additionally, the frequencies of noise are different on the simulator since most of the simulator noise!is from electronic power supplies whereas the plant Control Room noise is mostly turbine noise. Tais difference is being tracked with DR# 90D-242.

L d. The change in noise. level due to a start of the L

Control-Room Air Handlers is not simulated.--This difference is being tracked by DR# 91I-002.

These are considered exceptions to the requirements of

' ANSI /ANS 3.5-1985 Section.3.2.3. These exceptions will not _*

affect performance of any normal abnormal or emergency

operating procedures. Neither w111 these exceptions lead to 1 l operation or judgement errors on the part of a student during ]

responses to a malfunction or emergency. These differences o do not affect any task on the Shift Manager /Supv or Control j Page 3 1

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t  ;

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PRAIRIE- ISLAND SIMULATOR CERTIFICATION REPORT 1990 APPENDIX 1 Room Operator tasklists. These exceptions have been reviewed by the Simulator Design Review Committee and an investigation into the options for correction of these exceptions to improve the training environment on the simulator has been requested. This investigation will be completed and returned to the SDRC by 12/91.

4. Lighting

a. The simulator light levels are approximately 50%

higher than the plant control room light levels.

This discrepancy is being tracked with discrepancy report DR# 90D-241.

b. The emergency lighting equipment on the simulator does not match the emergency lighting equipment in the plant control room. This difference is being tracked with DR# 90I-081.

These are considered exceptions to the requirements of .

ANSI /ANS 3.5-1985 Section 3.2.3. These exceptions will not I affect performance of any normal, abnormal or emergency I operating procedures. Neither will these exceptions lead to I operation or judgement errors on the part of a student during i responses to a malfunction or emergency. These differences do not affect any task on the Shift Manager /Supv or Control i Room Operator tasklists. These exceptions have been reviewed l

. by the Simulator Design Review Committee and an investigation

! into the options available for correction of these exceptions to improve the training environment on the sinulator has been requested. This investigation will be completed and returned to the SDRC by 12/91.

B. Control Panels The Prairie Island simulator contains sufficient operational panels to provide the controls, instrumentation, alarms and other man-machine interfaces to perform the normal plant evolutions specified in ANSI /ANS 3.5-1985 Section 3.1.1 and L to respond to the malfunctions specified in Section 3.1.2 for l

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. The following panels are simulated:

a. NIS Panel

b. Panel F

c. Panel E Page 4 l

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' PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1990 APPENDIX 1

d. Panel D

e. Panel C

f. Panel B

g. Panel A

h. B Train Radiation Monitoring

1. A Train Hot Shutdown Panel

j. B Train Hot Shutdown Panel

k. Rod Drive' System Lift Disconnect Switch Box

1. Plant Process Computer Console (RO Station)

m. Panel G

n. Fire Protection Panel

o. Incore Instrumentation Panel The Prairie Island' simulator also models part of the A Train Radiation Monitoring Panel and portions of the local Auxiliary Feedwater Pump controls. In-addition portions of the Unit 2 Panel A are modelled to the extent necessary to provide the interactions between units for selected crosstied systems (eg. Cooling Water).

The following panels are located in the plant control room but are not included-in the simulator:

l a. Seismic Annunciator Panel - located behind Unit 2

[ control board.

b. Instrumentation Racks -located behind the control board on both Units, j

l

c. Electrical Relay Panel - located behind the Shift l Supervisor office.

d. Portions of the A Train Radiation Monitoring Panel -

Located behind the Unit 2 control board.

Following is-a-list of differences between the Prairic Island simulator and Prairie Island Unit 1 and Unit 2 control rooms:

I. - Prairie Island Unit 1

1. NIS rack opening above N43 is covered with a blank plate on simulator. This opening is used by I&C Page 5 ym1 -

PRAIR2E ISLAND SIMULATOR CERTIFICATION REPORT 1990 APPENDIX 1 technicians for placement of portable test equipment.

2. Control panels A, B, E and F include a set of four pushbutton switches for control of the motorized >

overhead T-Bar containing ERCS displays. These pushbuttons are not present on the simulator and the simulator T-Bar is not motorized.-

3. The workstation containing the ERCS printers in the simulator is different from the plant due 'to differences in the simulator room. In addition to this the hold card system printers which are located on this workstation in the plant are not included in the simulator.

4. Several meter. scales on the simulator have been revised as part of a plant project standardizing meter scales. Until the plant completes this project the simulator meter scales will be different from the plant meter scales in that the instrument number is printed on the new scale and some minor changes were made in some meter ranges.

5. The manuals and' proceduras normally kept in the Shift Supervisor's office-area are kept on a bookshelf ,

against the outside wall of the instructor's booth '

on the simulator.

6. The plant Hot Shutdown Panels are located remote from the Control Room. On the. simulator-these panels are located behind the Control Board. Only the Unit 1 portions of these panels are_ fully simulated.. The thiit 2= portions of these. panels are visually -

simulated.

7.- The steam generator power operated relief valve controllers located on the side of the Hot Shutdown Panel are not located in-a sheet metal enclosure on the simulator.:

8. The control rod drive system step counterc have been-replaced with electronic LCD counters on the simulator. The_ plant project to replace the mechanical step counters with electronic LCD step counters is scheduled to be completed in 1991.

9. -The portion of the A Train Radiation Monitoring Panel L which is-included on the simulator is located near L

the B Train Radiation Monitoring Panel. In'the plant the A' Train Rad Monitoring Panel is located behind the Unit 2 control board.

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FRAIRIE ISLAND SIMULATOR CERTZFICATION REPORT 1990 APPENDIX 1

10. The Hotwell and Condensate Storage Tank makeup integrators are not included on the simulator. These integrators are located behind the control board in the plant.

11. Several control switch handles are colored red in the plant but are black in the simulator. Red handles for these control switches are not available.

12. The plant has a MIDAS (Meteorological and Dose Assessment System) terminal located behind the Shift Supervisor office. ;his terminal is not included on the simulator.

13. The plant has moved the page system speaker previously located below annunciator cabinet 47024 to a location above the ceiling grids. This speaker is still located below annunciator cabinet 47024 on the simulator.

II. Unit 2 All differences listed for Unit 1 above also apply to Unit 2. Additionally the following differences exist:

1. The Unit 2 control panels are arranged in a modified mirror image of the Unit 1 control panels. The simulator panels match the layout of the Unit 1 control panels.

2. The Unit 2 annunciators for the intake screenhouse are not' included on the simulator. Conversely, the substation alarm included on the simulator does not exist on the Unit 2 annunciators.

3. Component numbering in the simulator does not match the Unit 2 component numbers. In most cases the component numbers differ in only one digit (eg. 1PT-485 vs. 2PT-485 or 47001 vs. 47501).

The four portions of operating panels which are not included l in the simulator are not considered significant to training i

since either no operator actions are expected using these panels or these operator actions are simulated using instructor controls with comi. iication with the student in a manner similar to that used in the plant control room. None of the differences ?4~ted between the simulator and Unit 1 or between the simu.' n' Unit 2 are considered significant since these diffs  ! 11 not affect performance of any normal, abnormal aacy operating procedures nor will any of these dif ,

lead to operation or judgement errors on the pa student during responses to a malfunction or en, .

Difference (11) will affect the Page 7 l

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method used by the Shift Manager to determine affected zones

-in the process of filling out the emergency notification form, however this function of the Shift Manager is normally-included in Emergency Plan Training which is conducted in-the EOF using an available MIDAS terminal. These differences do not affect any other task on the Shift Manager /Supv_or Control Room Operator tasklists.

These differences have been reviewed by the simulator Design Review Committee with the conclusion that none of these differences significantly affect training. The requirements of ANSI /ANS 3.5-1985 Section 3.2.3 are satisfied.

C. Systems Simulated and Degree Of completion All systems which are controlled from the control room are simulated. The completeness of the modelling 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 and integrated system response.

The systems which are operated from outside-the control room are simulated to the degree necessary to perform the reference plant normal evolutions and malfunctions listed in

' ANSI /ANS 3.5-1985 Sections 3.1'.1-and 3.1.2. The trainee is able to interface with the remote activities in a manner similar to the reference plant.

The requirementc of ANSI /ANS 3.5-1985 Section 3.2.1 are satisfied.

D. Significant Modifications The following significant modification has been performed on Prairie Island Unit 2 but has not been performed on Unit 1 or on the simulator:

1. Balance Of Plant Annunciator Modification This modification was performed on Unit 2 in September 1990-and is scheduled to be completed on Unit 1 in-June 1991m The simulator is scheduled to be modified in May 1991.

~

Plant policy nas been that significant plant modifications to I the control board are performed on the simulator first '.o allow operator training prior to implementation in the plant.

This policy effectively maintains the simulator current with L

the major plant modifications.

t Page 8

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..g Prairie Island Simulator Certification Report Appendix I Figure IA ,

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, l PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1990 .

APPENDIX 2 -

INSTRUCTORS INTERFACE CAPAlllLITIES Simulation Options llacktrack Fast Time Slow Time Instrument Noise Trainer liardware Test (DOI).T)

Switch Check Misalignments Display Initial Conditions Selection Snapshot Selection Itacktrack Time Selection Replay Rate Selection Malfunction Control Simulator Operating Limits Display Self Triggered Malfunctions Control I/O Override Control Meteorological Data Control System Overrides

!!ON10  !!G Tl!MI' XIMR IT200 CONDFLW XIMR FW201 CDSR llW XIMR FW202 II A FW Ll!VI!!, XIMR FW203 12A FW 1,1!VI!L XIMR FW3M 1111 l'W l.IIVl!L XIMR FW20$ 1211 FW 1,11VI!L XIMR FW206 13A FW Ll!Vi!L XIMR FW2G7 1311 FW Ll! Vill Kl'MR FW208 ISA FW Ll!VI!!, XIMR FW20) 1511 FW L11Vlit, XIMR MS200 til MS 1.liVill, Xi'MR MS201 111 MS I,1!V111, XIMR MS202  ; A MS 1.!! Vill;XIMR MS203 M MS LIIVP.1, XIMR MS34 til RilDT LilVlit, XIMR MS205 211 KilDT Ll!Vi!L XIMR MS206- 1 A RilDT 1.l!VI!!, XIMR MS207 2A RilDT L11Vlib XIMR i MS208 til FilDT 1.11Vi!L XIMR MS209 2il RIIDT Ll! Vill, Kl'MR MS210 1A RilDT Ll!VI!L XIMR MS211 2A RilDT LliVill, FI'MR l

pite/ reports Fage i

j PRAIRIE ISI AND SIMUL.ATOR CERTii'ICATION REPORT 1990 APPENDIX 2 System Overrides (Cont'd)

N130 Dl!!,TA 1 OUTI'UT N41 NI201 DlillrA I OU'll'UT N42 N1312 Dl!LTA 1 OUTl'UT N43 N f 313 DlILTA I OUTI'UT N44 Rll30 Ril 171DW XIMR RX30 RCS l'RESSURl! XIh1R RX201 RCS l'RI!SSURl! XThiR RX312 RCS l'RI!SSURI! XIhtR RX30 RCS l'RiiSSURli XIMR RX2nl l'RZR LVI, XIhiR RX205 l'RZR LVL XIhiR RX316 SO 1,liVl!L XIhiR RX207 SO I,liVi!!, XIh(R RX208 AUCTIONI!!!RiiD TAyo RX39 ItW 121DW XIhiR RX210 l'W FIDW XIMR RX211 FW 17 LOW KlhiR RX212 17W P1,0W XIhilt RX213 11/12 hts l'RI!SSURll KlhiR RX214 11 MS I*RiiSSURl! XTh1R RX215 11 hts l'RI!SSURii XThiR RX216 12 MS l'Ri!SSURI! KlhiR RX217 12 MS l'RilSSURl! XIMR RX218 IST STAGli l'RilSS XfMR RX219 11 MS FLOW XIMR RX220 11 MS lilDW XIMR RX221 12 hts I !DW XTMR RX222 12 MS l'IDW XIMR RX223 11 STM FI,0W KlhiR RX224 12 STM FI,0W XIhiR RX225 11 Fl!ED FIDW XIhiR RX226 12 l'I!!!D FI,0W XIMR RX227 11 Flil!D TEMI' XITR RX228 12 Fl!!!D Tl!MI' Kl'lK RX229 FW llDR l'RiiSSUR11 XIhtR RX230 FW llDR l'RESSUR11 XIMR RX231 11 SG WR LEVlil, XiliR RX232 12 SG WR I,1!VI!!, XIMR VC30 VC l'RESSURE XTMR VC201 VC TEMI'FRA'IURl! XIMR VC202 VC F1,0W XIMR VCND VC Fl OW XTMR plic/ reports Page 2

PRAIRIE ISLAND SIMULATOR CERTil'ICATION REPORT 1990 APPENDIX 2 l l

1 Variable Setpolnis l

CilNO Cil I CNMT 111 PRl!SS Cl!Xil Cl! !! CNMT 111 l'Rl!SS l CilX12 Cil IV CNMT lit l'RI!SS CllXO Cil 11 CNMT 111111 l'RilSS i CilN4 Cil 111 CNMT 111111 PRiiSS l Cl!30$ Cil IV CNMT 111111 PRi!SS l CilX6 Cll I CNMT 11111! I'RilSS Cl!Xl7 Cil 11 CNMT 111111 PRl!SS CIIXH Cll IV CNMT !!Illi PRl!SS l CllND Cil il CNMT 111111 l'RIISS l Cil310 Cll 111 CNMT lilill PRilSS 1 Cll311 Cll IV CNMT 111111 PRiiSS l MSVK) 11 SG SAFil'lY MSN)! 11 SO sal'l!'lY MSX12 11 SG sal'll'IY MSNO 11 SG SAFli'lY MSV4 11 SO SAFirlY MS30$ 12 SG SAFirlY MSN6 12 SG SAFI!'IY MSN17 12 SG SAFFllY MSXA9 12 SG SAFirIY MSX9 12 SG SAFil'IY NINO IR N35 PWR APOVi! P-6 N1301 1R N36 l'WR AllOVI! P-6 N1302 PR N41 PWR ABOVi! P-8 N1303 l'R N42 PWR AllOVli P-8 NIN4 l'R N43 PWR AllOVi! P-8 N1305 l'R N44 PWR AllOVI! P-8 N1306 Pit N41 PWR ADOVli P-9 N1307 PR N42 l'WR AllOVI! I'-9 NINL8 PR N43 l'WR AllOVi! P-9 NIXD l'R N44 l'WR ADOVI! P-9 N1310 PR N41 PWR ADOVi! P-10 N1311 PR N42 PWR ABOVli P-10 N1312 PR N43 PWR AllOVl! P-13 N1313 PR N44 l'WR AllOVli P-10 NI314 SR N31111 FI.UX TRIP N1315 SR N32 til Fl.UX TRIP ND16 IR N35 til Fl.UX TRIP NI317 IR N36111 Fl.UX TRIP N1318 PR N411.0 RNO lil FLUX TRIP NI319 PR N421,0 RNG 111 Fl.UX TRIP NI320 PR N431.0 RNG 11I Fl.UX TRIP N1321 PR N44 LO RNO III FI UX TRIP N1322 PR N41111 RNG 111 Fl.UX TRIP pite/ reports Page 3

PRAIRIE ISLAND SIMULATOR CERTirlCATION REPORT 1990 APPENDIX 2 Variable Setpoints (Cont'd)

N1323 l'R N42111 RNG 111 FLUX TRIP N1324 l'R N43 Ill RNG 111 FLUX TRIP N1325 PR N44 til RNG 111 FLUX TRIP N1326 PR N41 IOS RATE TRIP N1327 PR N42 IOS RATE TRIP N1328 PR N43 IOS RATE TRIP NI329 PR N44 IOS RATE TRIP

, Nf330 PR N41 NEG RATE TRIP N1331 l'R N42 NEO RATE TRIP N1332 PR N43 NEG RATE TRIP N1333 PR N44 NEG RATE TRIP RCNO PRZR SAFli'IY RC301 PRZR SAFE'lY RPN0 Cll 2 P-7 TURI) I'RESS RP301 Cil 3 P-7 TURil PRESS RP302 AUTO ROD %TPilDRAWAL llLOCK P-2 RPNG llUS 11 UV TRIP RP3al llUS 12 UV TRIP s RP305 11US 11 UP TRIP RI'306 IlUS 12 UP TRIP RIG 07 A 1DOP Cil 1 RC LO FLOW TRIP RP308 A LOOP Cil 11 RC LO FLOW TRIP R1909 A IDOP Cil Ill RC ID l LOW TRIP RI'310 111D01' CII I RC ID FIDW TRil' RI911 11 IDOP Cil III RC ID FI,0W TRIP RP312 11 LOOP Cil IV llc ID FIDW TRIP Rl913 Cil 1 PRZR ID PRESS TRIP RP314 Cll 11 PRZR LO PRESS TRIP RP315 Cil 111 PRZR LO l'RESS TRIP RP316 Cll IV PRZR LO PRESS TRIP RIU17 Cil 1 PRZR 111 PRESS TRIP RP318 Cil 11 PRZR 111 PRESS TRIP RP319 Clt 111 PRZR 111 PRESS TRIP RP320 Cll 1 PRZR I.O PRESS S1 RP321 Cil 11 PRZR LO PRESS SI RP322 Cll III PRZR ID PRESS Si RP323 Cli I PRZR 111 LVL TRIP Rl'324 Cll 11 PRZR 111 LVL TRIP Rl925 Cil !!I PRZR 111 LVL TRIP R1926 IDOP A Cil 1 SG LOLO LVL TRIP RP327 LOOP A Cll 111 SG I OLO LVL TRIP RP328 LOOP A Cll IV SG LOLO LVL TRIP Rl929 LOOP 11 Cil i SG LOLO LYL TRIP RP330 IDOP 11 Cil 11 SG LOLO LVL TRIP RP331 LOOP 11 Cll IV SG LOID INL TRIP 1

l plic/ reports Page 4

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1990 APPENDIX 2 Variable Setpoints (Cont')

l RlWO IDOP A Cll 111D10 TAvo STM LN ISol,

RlW1 IDOP A CII IV IDID TAvo STM LN ISOL

RIN2 IDOP 11 Cll I IDID T yo A STM LN ISOL RlW3 IDOP !! Cil !!! LOID TAyo STM LN ISOL RlW4 IDOP A Cl! I SG 111 S'IM FIDW RIW5 IDOP A Cil 11 SG 111 STM FIDW 4 RIN6 IDOP 11 Cl! Ill SG 111 STM FIDW RlW7- IDOP 11 Cil IV SO 111 STM FIDW l RIW8 IDOP A Cil 1 SG 111-111 STM FLOW RlW9 IDOP A CII 11 SG 111-111 STM FIDW RP350 LOOP 11 Cll !!! SG !!I-ill STM FLOW R1951 IDOP 16 CII IV SG 111-111 S'IM FIDW RIG 52 IDOP A Cil i SG IDID STM PRESS St R1953 IDOP A Cll 11 SG LOID S'IM PRESS Si

RP354 IDOP A Cil 111 SG IDI,0 STM PRESS St Rl955 IDOP A CII I SG LOID STM PRESS SI RP356 IDOP 11 Cil til SG IDID STM PRESS Si Rl957 IDOP 11 Cil IV SG 1.0L0 STM PRl!SS SI RXXO PRZR III PRESS PCV-430 INTI.K RX301 PRZR III PRESS l'CV-431 INTLK RXN12 LOAD REJ STM DUMP 111 TAvo RX303 LOAD R11J STM DUMP 111111 TAvo RX3N TURIl TRIP STM DUMP 111/111111 TAve MASTER PRZR PRESS CONT S11TI0lNT RXX)5 TC300 INIT 'IURIl CV IOS Malfunctions and Remote Functions Cornponent Cooling Systern CC01 COMIONENT COOLING WATER PUMP TRIP CCO2 COMPONIINT COOLING PUMP Fall.S 'lO START AUTOMATICALLY CCN COMIONENT COOLING WATER SUPPLY VALV11 TO RCP FAILS Cl,OSED CC05 COMIONENT COOLING WATliR SYST11M PIPING RUITURE CCo6 CCW VALV11 Fall,URl! TO OPEN RIIR lil!AT 11XCIIANGER AUTO ON PUMP START CCOS COMIONENT COOLING SURGE TANK AUTO MAKEUP FAILURE CC(9 S!!AL WATl!R llEAT EXCIIANGER LEAK CC100 - RCP CCW SUPPLY ISOL A :

CC101 RCP CCW SUPPLY ISOL 11 CC102 UNIT 1 - UNIT 2 CCW X CONNECT l plic/ reports Page 5 l _ . . _ _ _ . . _ _ _ - . . _ _ _ _ _ _ _ . . - . _ _ __ _ . . _ . _ __ ._ _ _ _. _ ,. -

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1990 1

APPENDIX 2 Malfunctions and Remote Functions (Cont'd)

Component Cooling System (Con't) i CC103 CC OUTLET TEMP CONTROLLER SETPOINT CC104 11 RCP COMP CLNT INLT/OU'IL IlKR CC105 12 RCP COMP CLNT INLT/OUTL BKR CC106 11 RCP llRO CLO WIR AETRN CC107 12 RCP llRO CLO WIR RETRN Containment /HVAC System I

C1101 CONTAINM11NT PRESSURE TRANSMrITER PAILURE Cll100 POST LOCA 112 CONTROL VENT

! Cll101 POST LOCA 112 CONTROL IA SUPPLY Cll102 11/13 CONT l'AN COIL DAMPER Cil103 12/14 CONT FAN COIL DAMI'ER <

CII1N CONT l'UROE CONTROL Cil105 121 CONT l'UROH CONTROL Cil106 CNTMT 111 PRESS II/S PC-945A Cil107 CNTMT III PRESS II/S IC-949A Cll108 CNTMT III PRESS NR IC-947A Cil109 - CNTMT 111-111 l'RESS B/S PC-946A CII110 CNTMT 111-111 PRESS II/S PC-948A i- Cll111 CNTMT III-III PRESS II/S IC-950A Cll112 CNTMT 111-111 PRESS II/S PC-94511 l Cill13 CNTMT lil-III PRESS II/S 1 0 -94611 i C11114 CNTMT 111-111 PRESS B/S 1 0 -9471)

Cill15 CNTMT 111-111 PRESS II/S 10-94811 -

CIll16 CNTMT 111-111 PRESS II/S 10-94911

, CIll17 CNTMT 111-111 PRESS II/S PC-950ll Cil118 121 LAUNDRY / LOCKER / FILTER ROOM EXIIAUST FANS Cill19- CNMT CillLL WATER SYSTEM Clll20 CAT I ANNUNCIATORS Cill21 FIRE DETECTION ALARMS Cill22 l' IRE DETECTION ALARMS Cll123 FIRE DETECTION ALARMS Clll24- FIR 11 DETECTION ALARMS .;

Cil125 FIRIl DETECTION AIARMS Cill26 121/122 CR WPR ClllLLER XOVER VLVS C11127 RAD WASTE IILDO VENT Cill28 11/12 CRDM COIL SUPPLY / RETURN VLVS CII129 UI CONTAINMENT ENTRY Cill30 U1 CONTAINMENT EXfP Cill31 11-14 CNTMT FCU COND COLL TK DRN pite/ reports Page 6

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 3990  ;

APPENDIX 2 Malfunctions and Remote Functions (Cont'd)

Cooling Water Systern Cllli COOLING WATER PUMP CIE2 DIESEL COOLING WATER PUMP FAILS TO START AU'!OMATICALLY CIIG 121 COOLING WATER PUMP FAILS TO START AUTOMATICALLY CI14 DIESEL COOLING WATER PUMP TRIP CII6 SAFEGUARDS COOLINO WATER SUPPLY PIPING RUI'!URE CIA 7 COOLING WATER SYSTEM TURillNE IlUILDING PIPE RUI'IURI!

Cila COOLING WATER LEAK INSIDE CONTAINMENT CL100 TURin OIL COOLER OUTL TEMP CONTRL SE'11'OINT CL101 CL-M-1 TRN A SFORDS CL WATER MAN VIN CL102 2CL-M-1 TRN !! SFORDS CL WATER MAN VLV CL103 11/13 FCU CLO %TR RTN ORF 11P VLV IDCAL CS i CLl(M 11/13 FCU CLO WIR RTN ORF IIP VIN LOCAL CS

, CL105 12/14 FCU CID WrR RTN ORF llP VLV IDCAL CS CL1(6 12/14 FCU CID WrR RTN ORF llP VIN IOCAL CS CL107 12 DSL CID WrR PUMP IDCAL STOP CL1(* 22 DSL CLO WrR PUMP IDCAL STOP l

r Reactor Core Systern CR01 FUEL CLADDING PAILURl!

CR02 GROSS FUEL FAILURE

, CR03 REACTOR COOLANT SYSTEM CRUD llURST CR(M FUEL CLADDING FAILURE Containtnent Spray Systern CS01 CONTAINMENT SPRAY PUMP TRIP CS02 CAUSTIC ADDirlON VAIN!! FAILURE TO OPEN IN AUTOMATIC CS03 CONTAINMENT SPRAT' PUMP FAILS TO START AUTOMATICALLY CSl(0 11 CS SUCTION FROM RilR llRR CS101 12 CS SUCTION FROM RilR llKR CS102 CAUSTIC ADD TO 11 CS PUMP ISOL CS103 CAUSTIC ADD TO 12 CS PUMP ISOL l l

i plic/ reports Page 7

, 4 -. . .m..y...-. e -. -...,-e...--, : ..-,,w.. .-,,,,,,,.m .m.,em,.,.. .,em._,.,,,.~,w..-,e--~4-w-, ,,a- - + or m v

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1990 APPENDIX 2 Malfunctions and Remote Functions (Cont'd)

Circulating Water System

. CWOI - CONDENSER 'IUllE LEAK CWO2 CIRCULATING WATER l'UMI' TRIP CW(0 CIRCUIEI1NG WATER l' UMP llEARING FAILURE CWN CONDIINSER TULLES l' LUGGED i CWO$ CONDliNSER tulle RUl4URE CWT 16 TRAVELING SCRE!!N lilDCKAGE ON Al'PROAcil CANAL CWO7 CONDENSER ITT FIDOD CWl(0 RIVER WATER TEMI'ERATUR11 p CW101 DYl' ASS G ATES MANUAL CONTROL Electrical Distribution System

, 11D01 IDSS OF OFFSITl! IOWER ED(G LOSS Ol' OFFSITE IOWi!R IIDN FAUllr IN UNIT 1 M TRANSFORMER-AUTO TRANSFER

!! DOS FAUllr IN UNIT 1 M TRANSPORMl!R-Wrrl! DELAYED TRANSFER ED06 FAUllr IN UNIT SUllSTATION TRANSFORMER ED07 IDSS OF 125 VDC UUS ED08 IDSS OF 120 VAC INSTRUMENT 11US

!!D(D IDSS OF 4160V 110S

!!DIO IDSS OF 480 VAC llUS i EDil 110S 15 IDAD RIUECrlON-RESTORATION SEQUENCE TIMER FAILURE

!!D12 IlUS 16 IDAD RIUECI10N-RESTORATION SEQUENCE TIMER FAILURE EDl3 VOLTAGl! RESTORING SCIII!MI! SEQUl!NCER Fall,URE EDl4 LOSS OF ALL AC ED15 DEGRADED GRID VOllrAGE ED16 Dl!GRADilD GRID FREQUENCY 11D100 STA AUX MN XFORMER 20KV DISCONNECTS ED101 10 IIANK TO ITUS Cr12 ED102 1Cr TO IlUS Cril-11D1(0 161 KV llUS 1 TO 10 BANK EDIN SI' RING CR1111K 161 KV TO 161 KV DUS 1 l 11D105 RED ROCK LIN!! 2/IlYRON 345 KV LINE l

l pitc/ reports Page 8

i PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1990 1 APPENDIX 2 Malfunctions and Remote Functions (Cont'd)

Electrical Distribution Systern (Cont'd)

ED106 IlYRON N5 KV IJNE TO 345 KV llUS 2 ED107 UNrr 2/IILUE LAKE NS KV LINE ED108 RED ROCK 345 KV LINE 1 TO 345 KV BUS 2 ED109 SUBSTATION ALARM ANNUNCIA'IDR RESET ED110 1R-Y AUX TRANSFMR IlUS TIE IlKR 1RYllT ED111 2R-Y AUX TRANSFMR BUS TIE IIKR 12RYllT ED112 1R-X/2R-X llUS TIE IlKR 12 RX11T ED113 1R-X BUS DISCONNECT ED114 1R-Y llUS DISCONNECT ED115 2R-X llUS DISCONNECT l ED116 2R-Y llUS DISCONNECT i ED117 480V IlUS 130/140 IlUS TIE IlKR INilT ED118 480V BUS 150/160 IlUS T1E BKR 15611T ED119 480V BUS 190/290 llUS TIE IIKR 192911T ED120 480V llUS 130 SUPP!,Y llKR 13M ED121 480V BUS 140 SUPPLY llKR 14M ED122 480V BUS 150 SUPPLY llKR 1>M ED123 480V 11US 160 SUPPLY llKR 16M

!!D124 480V llUS 190 SUPPLY llKR 19M ED125 4.16KV IlUS SUPPLY llKR CT11-1 ED126 4.16KV BUS SUPPLY llKR CT12-7 ED127 - 4.15KV CLNG 'IWR 110S TIE BKR CT-IIT112 ED128 480V MCC IT1 ALTERNATE SOURCE i

ED129 480V MCC 1T2 AllrERNATE SOURCE ED130 4.16KV BUS 11 IM XFMR 11KR 11-4 ED131 4.16KV llUS 121M XFMR IlKR 12-4 ED132 4.16KV llUS 131M XFMR llKR 13-9 ED133 4.16KV IlUS 141M XFMR llRR 14-9 EDIN 4.16KV IlUS 151M XFMR BKR 15-7 ED135 4.16KV llUS 13 PUMP OVERLOAD RELAYS RESET ED136 4.16KV IlUS 14 PUMP OVERIDAD RELAYS RESET Electrical Generation Systern EG01 GENERATOR OUTPUT llREAKER FAILS TO OPEN FOLLOWING TURillNE

- TRIP EG02 LOSS GENERATOR IIYDROGEN COOLING EG03 IDSS OF OFFStrE POWER EGOS GENERATOR VOLTAGE REGULATOR FAILURE EG06 GENERATOR FAUIlr EG07 GENERATOR LOSS OF EXCfrATION pitc/ reports Page 9

l l

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1990 APPENDIX 2 Malfunctions and Hernote Functions (Cont'd)

Electrical Generation System (Cont'd)

EGOS LOSS OF EMiiRGENCY DIESEL Gl!N!!RATOR EG(0 EMERGIINCY DIESEL GENERATOR FAILS TO START EG10 EMERGI!NCY Dil!Slil GENERATOR OUTPUT llRiiAKER FAILS OPEN I!Gil EMiiRGENCY DIESEL GENERATOR 1,OAD 1.lMir FAILURE liG1(O GliN!!RATOR 112 SUI' PLY EG101 GENERATOR CO2SUI' PLY I!G102 GENERATOR G AS VENT E G103 IIYDitOGEN SIDE SEAL OIL PUMP EG1(M AIR SIDE SEAL OIL PUMP EG106 D1 IDCAL MCA/SilUTDOWN RESET Pil

!!G107 D2 LOCAL MCA/SIIUTDOWN RESliT Pil I!G108 OliN XFMR .'u5 KV DISCONNECTS EGl(n MAIN GENIiRATOR OUTPUT DISCONNECT LINKS liG110 AIR SIDIl SliAL OIL BACKUP PUMP EGill AIR Sil)E SEAL OIL llACKUP PUMP EG112 M-lG/86-1GT RESET 110113 Di MECilANICAL LINKAGE TO FUEL RACKS RESliT 110 114 D2 MECilANICAl, LINKAGE TO FUEL, RACKS RESET EG115 D1 LOCAL ANNUNCIATOR SILENCE Pil 1:0 116 D2 LOCAL ANNUNCIATOR SILENCI!

!!G117 D1 LCCAL PANEL CS EG118 D2 IDCAl, PANEL CS Condensate and Feedwater System FW01 CONDENSATE PUMP TRIP FWO2 13 CONDENSATli PUMP FAILS TO START AUTOMATICALLY FWO3 LOSS OF CONDENSER VACUUM FWOS CONDENSATE PUMP RECIRC VAINE FAILS OPEN FWO6 CONDENSATE PUMP RECIRC VALVE FAILS CLOSED FWO7 CONDl!NSATE Il01WELL MAKEUP VALVE Fall S OPliN FWOS CONDENSER llOTWELL MAKEUP VALVE FAILS CLOSED FWCD 1.P FEEDWATER IIEATER llYPASS VAINE FAILS OPEN FW10 CONDENSER llOTWELI, LEVEL TRANSMr!TER FAILS 111011 FW11 CONDENSER llO1WEl.1, TRANSMrITER FAILS LOW FW13 MAIN FEEDWATER PUMP TRIP FW15 FEEDWATER llP llEATER 111011 LEVEL FW16 FEEDWATER LP llEATER 111011 LEVEL FWl7 FEEDWATER IIP llEATER LEAK FW18 FEEDWATER LP llEATER LEAK FW19 FEEDWATER SYSTEM RUl'rURE INSIDE CONTAINMENT plic/ reports Page 10

1 PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1990 APPENDIX 2 Malfunctions and Remote Functions (Cont'd)

Ccmdensate and Feedwater System (Cont'd)

IAV20 FEEDWATER SYSTEM LEAKAGE INSIDE CONTAINMENT FW21 FEEDWATER SYSTEM RUI'lVRE INSIDE CONTAINMl!NT UPSTRl!AM OF CIIECK VALVE FW22 FEEDWATER SYSTEM RUI'IURE OU'ISIDE CONTAINMENT FW23 FEEDWATER SYSTEM LEAKAGE OUTSIDE CONTAINMENT ITV24 FEEDWATER PUMP COMMON DISCl!ARGE IIEADER RUI'IURE FW25 FliEDWATER FIDW CONTROL VALVE FAILS TO CLOSl! ON ISV ISOLATION SIGNAL FW26 FilllDWATER FIDW CONTRGts VALVE FAIIS OPEN FW27 FEEDWATER FIDW CONTROL VALVE falls CLOSED FW28 IIEATER DRAIN PUMP TRIP FW29 IIEATER DRAIN TANK LEVEL TRANSMrlTER FAILS 111 0 11 FW30 I! EATER DRAIN TANK LEVEL, TRANSMITrliR FAILS LOW FW31 IIEATER DRAIN PUMP falls TO MINIMUM FW32 AUXILIARY FEEDWATER PUMP TRIP, MOTOR FW33 AUXILIARY FEEDWATER PUMP TRIP, TURillNE 13V34 AUXILIARY Fl!EDWATER PUMP FAILS TO START AUTOMATICALLY FW35 INADEQUATE CONDENSATE TO AUXILIARY FEEDWATER PUMP SUCTION FW36 AUXILIARY FEEDWATER DISCilARGE I.lNE RUI'IURE INSIDE CONTAINMENT FW37 AUXILIARY PEEDWATER DISCl!ARGli LINE RUI'IURE OUTSIDE CONTAINMENT FW38 AUXILIARY FEi!DWATER CONTROL VALVII FAILS IN POSrl10N FW39 FEEDWATER LINE RUI'IURli UPSTREAM UF FW REG VALVES FW40 COMMON FEl!DWATER PUMP SUCTION LINE IlLOCKAGE FW41 FEEDWATER FLOW CONTROL VALVI! LEAKAGE FW100 11-12-13 LP FW IITR llYPASS FW101 TDAFWP IA ISOL TO CV-31998 ITV102 CST XCONNECT 1%V103 AFW TO 11 SG CNMT ISO BKR FWIN AFW TO 12 SG CNMT ISO llKR FW105 11A-12A-13A FW 1rrR ISOL ITV106 1111- 1211- 1311 ITV IITR ISOL FW107 14A FW 1rIR ISOL FW108 141) ITV lilR ISOL FW109 14A FW 1rFR BYPASS FW110 14tl FW 1rrR BYPASS 13V111 COND MAKEUP MANUAL llYPASS FW112 15A IIIR ISOL FW113 1511 FW 1rrR ISOL i

pitc/ reports Page 11

l PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1990 APPENDIX 2 Malfunctions and Remote Functions (Cont'd)

Condensate and Feedwater Systern (Cont'd)

FW114 15A FW llTR IlYPASS IW115 151% llTR llYl' ASS FW116 15A TO 14A IITR RESET Pil FW117 1511 TO 1411 llTR RESET Pil FWil8 COND l'Ol.lSil SYS 11YPASS FW119 CONDENSER SPRAY SYSTEM FW120 11 FW PUMP RECIRC VIN FW121 12 FW PUMP RECIRC VIN Condensate and Fredwater System (Cont'd)

FW122 COND llYPASS TO CW STANDPIPl!, CD-19-1 FW123 1A ISOL _1 FW PUMP RECIR VIN FW124 IA ISOL 12 FW l' UMP RECIR VIN FW125 11 AFW PUMI' RESET Pil FW126 11 FV PMP DSCilO VIN CONTROL SW FW127 12 F% PMP DSCllG VLV CONTROL SW IrW12fl 11 F% PMP DSCilG VIN CLOSE IDCAL Pil FW129 11 FW PMP DSCilG VIN OPEN LOCAL Pil-FW130 -12 FW PMP DSCllO VIN Cl,OSE IDCAL Fil FW131 12 FW PMP DSCllO VIN OPEN LOCAL l'Il FW132 MDAFWP IDW PRESSURE TRIPS OVRD l'W133 21 MDAFW PUMP & CROSS-CONNECT VAINES FW131 11 AFW PUMP TO 1A STM GEN, MV-32238 l'W135 11 AFW PUMP TO 111 STM GEN, MV-32239 Cornpressed Air Sys!ern IA01 LOSS OF SERVICE AIR llEADER IA02 IDSS OF INSTRUMENT AIR IIEADER IA(0 IDSS OF AIR COMPRESSOR IA100 ' ICLIS!! AIR TO STATION AIR IA101 l'OLISil AIR TO INST AIR IA102 121 FILTER DRYER llYPASS RESET IA103 122 FILTER DRYER llYPASS RESET Main Stearn Systern MSol MAIN STEAM 1.INE RUI'IURE INSIDE CONTAINMENT UPSTREAM OF MSIV MS02 MAIN STEAM LINE RUI'!URE OUTSIDE CONTAINMENT UPSTREAM OF MSIV pitc/ reports Page 12

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1990 APPENDIX 2 '

Ms! functions and Remote Functions (Cont'd)

Main Stearn Systern (Con't)

MS03 MAIN STEAM LINE RUITURE OUTSIDE CONTAINMENT DOWNSTREAM OF MSIV MSO4 MAIN STEAM LINE LEAK I MS05 MAIN STEAM SAFETY val.VE STICKS OPEN MS06 GLAND SEAL S11iAM REGULATINO VALVE FAILS CLOSED MS07 MOISTURE SEPARATOR - REllEATER tulle LEAK MS08 - MOISTURE SEPARATOR - REllEATER RELIEF VALVES FAILURE MSO9 MAIN STEAM LINE I.EAK INSIDE CONTAINMIINT MS10 MAIN STEAM LINE IIREAK ON COMMON SUPPLY LINE TO AFW MS11 STEAM DUMP VALVE Fall,S IN lOSrt10N MS100 11 SG IORV 150L MS101 12 SG IORY ISOL MS102 11 SG ATMOS STM DUMP ISOL 1 MS103 11 SG ATMOS STM DUMP ISOL MSIN 12 SG ATMOS STM DUMP ISOL MS105 12 SG ATMOS STM DUMP ISOL MC106 COND S1M DUMP ISOL MS107 COND STM DUMP llYPASS ISOL MS108 1A MSR STM SUP ISOL MS109 111 MSR STM SUP ISOL MS110 2A MSR STM SUP ISOL MS111 211 MSR STM SUP ISOL MS112 11 SG VENT MS113 12 SG VENT MSil4 1A MSR CV llYPASS MS115 til MSR CV llYPASS MS116 2A MSR CV BYPASS MS117 211 MSR CV llYPASS MS118 MSR STOP CK AND CV-310M RESET MS119 LIP TURil!NE BLADING REMOVED MS120 1.P TURillNE IILADING REMOVED MS121 1A SG IORV LOCAL CONTROL MS122 1A SG IORV LOCAL CNTRI, VI V IOSil10N MS123 111 SG IORV LOCAL CONTROL MS124 111 SG IORY LOCAL CNTRL VIN IOSTIlON MS125 IIllATING STM SUPPLY TO AUX MAIN STM Nuclear instrurnentation Systern .

N101 INCORRECT SOURCE RANGE CIIANNEL RESIONSE '

NIO2 SOURCE RANGE CllANNEL SPIKES N103 INTERMEDIATE RANGE CllANNEL IMPROPER RESIONSE NIN INTERMEDIATE RANGE CIIANNEL IMPROPER COMPENSATION

- N105 IMPROPER IOWER CIIANNEL RESIONSE plic/ reports Page 13

i PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1990 APPENDIX 2 Malfuncilons and Remote Funcilons (Cont'd) ,

Nuclear Instnanentation Systern (Cont'd)

N106 IOWER RANGE UI'I'liR Cll ANNEL IMPROl'ER RESI'ONSE N107 IOWER RANGE LOWER CilANNEL IMI' ROPER RRESIONSE Nil (0 CilANNEL 1 IWR RNO 1110 - til F ll/S Nil 01 Cil ANNUI,2 IWR RNO Ill 0 - til l' il/S Nil 02 CilANNEL 3 IWR RNG ll! 0 - til F ll/S nil (0 CilANNEL 4 PWR RNO 1110 - 111 P 11/S Nilot CllANNEL 1 PWR RNG ID 0 - !!! P ll/S Ni105 CilANNEL 2 IWR RNG ID 0 - 111 l'II/S N1106 CilANNEl,3 PWR RNO ID 0 - til F ll/S N!!07 CilANNEL 4 IWR RNO ID 0 - 111 F ll/S N!!08 CilANNEL 1 INT RNO lit l' il/S N1109 CilANNEl,2 INT RNO 111 F ll/S Nil 10 CllANNEL 1 SOURCl! RNG lli F ll/S N1111 CilANNEL 2 SOURCE RNG 111 F ll/S Nill 2 IOWER RANGE l'-10 II/S NC-41 M Nill 3 IOWER RANGli l'-10 II/S NC-42 M Niil4 IOWER RANGE P-1011/S NC-43 P Nil 15 IOWER RANGE l'-10 ll/S NC-44 M i

Nill 6 IOWPR RANG 11 P-8 II/S NC-41 N Nil 17 IOWl R RANGE l'-8 II/S NC-42 N l Nill 8 IOWIIR RANGE P-8 II/S NC-43 N l N1119 IOWER RANGE P-8 II/S NC-44 N l Nil 20 INTERM RANGI! P-6 II/S NC-35 D l

nil 21 INTERM RANGE P-6 II/S NC-36 D Nil 22 CilANNEL 1 IOSITIVE RATE II/S Nil 23 Cll ANNEL 2 IOSITIVE RATE II/S Nil 24 CilANNEL 3 IOSITIVE RATE II/S Nil 25 CllANNEL 4 IOSITIVE RATE II/S Nil 26 CllANNEl,1 NEGATIVE RAT 13 II/S Nil 27 CilANN!!L 2 NEGATIVE RATE II/S Nil 28 Cll ANN!!L 3 NEG ATIVE RATE II/S Nil 29 CilANNEL 4 NEGATIVI! RATE II/S N1130 CllANNEL 1/2 SOURCIL RANGE 111 FI,UX AT SD Slrl'lOINT Nil 31 CilANNEl,119 B/S N1132 CilANNEL 219 II/S

- N!!33 CilANNEL 319 II/S NILM C11ANNEL 419 II/S Nil 35 CilANNEL 1 INT RNG ROD IILOCK ll/S NC-3511

, nil 36 CilANNEL 2 INT RNO ROD BLOCK B/S NC-36E l

N1137 CilANNEL 1 PWR RNG ROD IlLOCK B/S NC-41L CilANNEL 2 PWR RNO ROD llLOCK ll/S NC-42L

~

N1138 Nil 39 CilANNI!L 3 PWR RNO ROD llLOCK ll/S NC-43L Nil 40 CilANNEL 4 PWR RNG ROD llLOCK II/S NC-44L plic/ reports Page 14

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

PRAIRIE ISLAND SIMULATOR CERTIFICATION REFORT ,

1990 j APPENDIX 2 l Malfunctions and Remote Functions (Cont'd)

Plant Process Computer System 1001 ERCS CPU Fall,URl!

1C02 ERCS DATA CONCENTRATOR LINK TO CI'U FAILURE 1003 ERCS ALRM DISPLAY Fall,URE ICN ERCS SAS DISI' LAY FAILURE 1005 ERCS CONTROL ROOM PRINTER FAILURI!

IC(6  !!RCS DISK A Fall,URE Reactor Coolant System RC01 REAC'IOR COOLANT l' UMP TRIP i RCO2 REACTOR COOLANT PUMP LOCKED ROTOR j RC03 Rl! ACTOR COO! ANT PUMP SilAIT SilEAR RCN REACTOR COOLANT l' UMP SilAIT SilEAlt RC05 REACTOR COO! ANT PUMP litiARING FAILURi!

RC06 1,OSS OF COOI. ANT ACCIDl!NT - IlOT LEO )

"C07 1,OSS OF COOLANT ACCIDl!NT - COLD LI!G RCP SUCTION RC08 IDSS OF COO! ANT ACCIDENT - Col,D 1.EG RCP DISCIIARG11 RC09 1 OSS OF COOLANT ACCID 11NT, PRESSURIZI!R STIIAM SPACE i RCIO IDSS OF COOLANT ACCIDl!NT l'RESSURIZER WATER SPACl!

1(Cl) IOSS OF COOLANT ACCIDENT-RTD llYPASS LOOP COLD 1,1!O M ANIFOLD RCl2 1,OSS OF COOLANT ACCIDENT-RTD IlYPASS LOOP Rlrl' URN 1.EG l'IPING RCl3 1,OSS OF COOLANT ACCIDl!NT - RI! ACTOR llEAD VENT RCl4 REACTOR COO! ANT SYSTliM Ll!AKS RCO REACTOR COOLANT SYSTEM 1.EAKS RC16 PRESSURIZER POWi!R OPERATIID RI!!,IEF VALVE Fall S Cl,OS11D RC17 PRESSURIZER 111011 OAS CONCl!NTRATION IN VAIOR SPACil RC18 l'RESSURIZER SAFETY VAINE RC-10-1 FAILS OPEN RC19 PRESSURIZER SAFirIY VALVE SEAT LI!AKS RC20 _ REACTOR COOi, ANT PUMP 011,l EAK, UITER RESERVOIR RC21 REACTOR VESSEL O-RING 1,I!AKAGli RC22 PR11SSURIZER LOWER OPERATilD REl.lEF VAINE LilAKAGil RC23 STEAM OENI!RATOR TULLES PLUGGED RC24 PRESSURIZliR SPRAY VALVE Fall,S IN IOSITION RC100 PRT PRilSSURE CONTROLLER SirPICINT RC101 LOOP 11 DRAIN RC102 REFUELING WATER LEVEL IND ,

RC103 PRZR SPRAY llYPASS LOOP 11 RCIN PRZR SPRAY llYPASS LOOP A RCK15 IDOP A RTD llYPASS ISOI, pite/ reports Page 15

]

! PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT l- 1990 l APPIMDIX 2 l

. Malfunctions and Remote functions (Cont'd)

Reactor Coolant System (Con't) l RCl(6 IDOP ll R1D llYPASS ISOL l i RC107 RX VESSliL INNER SEAL LEAKOFF l RC108 RX VESSEL OUTliR SEAL 1.EAKOFF  ;

j RC110 PRZR STEAM SPACE SAMPLE l RCit! COLD LEO LliVEL ISOIErlON VALVES i

Control Rod Drb'e System RD01 CONTROLLING ROD llANK FA!!S TO MOVE IN MANUAL RD02 CONTROLLING ROD llANK FAIIS TO MOVi! IN AUTO RD03 UNCONTROLI,ED CONTINUOUS ROD WITilDRAWAL OF CONTROLLING l  ;

ilANK l

', RDN UNCONTROLLED CONTINUOUS ROD INSERTION OF CONTROLLING l I .

IIANK l I RDOS CONTROL ROD MISALIONMENT  !

j RD(6 S'IUCK ROD 1

! RD07 DROPPED ROD RD08 CONTROL ROD O-3 PJECTED RD(y> ROD POSrl10N INDICATION FAIIS l RD10 INCORRECT ROD SPliED i RD100 11 ROD DRIVE MG 4 RD101 12 ROD DRIVII MO RD102 RPI SUPI'LY FRM INV 15/FRM PNL 117 L RD103 IIANK D ROD llLOCK ll/S TC-40$K RDIN . SET CONTROL IIANK A P/A CONV RD105 Si1T CONTROL IIANK 11 P/A CONV l RDK6 SET CONTROL 11ANK C P/A CONV i

RD107 SET CONTROL llANK D P/A CONV RD113 INV 115/ PANEL,117, CKT 13 POWER TO IRPI STACKS Residual Heat Rernoval System i Ril01 RESIDUAL llEAT REMOVAL l' UMP TRIP

, R1102 RESIDUA.,llEAT REMOVAL PUMP FAILS TO START AUTOMATICALLY R1103 RilR llEAT EXCilANOER END llELL LEAKAGE TO ATMOSPIIERE RilN RilR llEAT EXCilANOER llYPASS VALVE falls OPEN R1105 RIIR llEAT EXCil ANGER IlYPASS VALVII PAILS CLOSED Ril06 Rl! CIRCULATION SUMP SUCTION LIN!!S IILOCKED i

i pitcheports Page 16 l

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1990 APPENDIX 2 Malfunctions and Remote Functions (Cont'd)

Residual Heat Rernoval Systern (Cont'd)

R1107 RIIR SYSTEM LEAKAGE RIl08 RilR PUMP SEAL Pall,URE RIIO9 RESIDUAL llEAT REMOVAL RELIEF VALVE FAILURE Rill (0 11 RIIR IIX INI,ET X-CONN, Ril-2-4 Ril101 12 RilR llX INLET X-CONN, Ril-2-3 Ril102 11 R11R llX OUTLET X-CONN, Ril-2-6 Ril103 12 RilR llX OUTLET X-CONN, Ril-2-5 Ril1N 1,00P A 110T LEO MV-32164 IIKR Ril105 1,00P 11 llOT LEO MV-32230 IIKR Ril106 12 RilR PMP DSCilO TO SUMP Ril107 IDOP H RET ISO HKR Pil108 11 RilR IIEAT EXCil ANGER INLET ISL Ril-1-4 Ril109 12 RIIR IIEAT 11XCll ANGER INLET ISL RIl-1-3 Rill 10 11 RilR (CV-31235) MECil ANICAL STOP Rill 11 12 RilF (CV-31236) MECilANICAL STOP Ritt12 11 RilR PUMP SUCTION VALVE Ril113 12 RilR PUMP SUCTION VALVE Rill 14 RIIR TO CVCS LETDOWN LINE Rilll5 IOOP A IlOT LEO MV-32165 llKR Ril116 LOOP 11 IlOT LEO MV-32231 IlKR Reactor Protection Systern (Cont'd)

RI'01 REACTOR TRIP RI'02 Fall,URl! OF AUTOMATIC REACTOR TRIPS RI'03 FAILURE OF SAFETY SYSTEMS TO ACTUATE RI'N INADVERTENT ACTUATION OF Tile SAFETY INJECTION SYSTEM RIOS FAILURE OF CONTAINMENT ISOLATION l'IIASE A TO ACTUATE RI'06 Fall,URE OF MSIV'S TO ISOLATE R197 MECilANICAL FAILURE OF REACTOR TRIP llREAKERS RI'08 FAILURE OF SAFEOUARDS ACTUATION RP100 - REACTOR TRIP llYPASS IIKR TRN A RP101 REACTOR TRIP llVPASS IIKR TRN B RP102 1 IDW RC FIDW A LOOP D/S PC-411 RP103 - 2 IDW RC FLOW A LOOP ll/S FC-412 RPIN 3 LOW RC FIDW A LOOP U/S FC-413 l RP105 1 IDW RC FLOW 11 LOOP H/S FC-414 RP106 3 LOW RC FLOW H LOOP B/S FC-415 RP107 4 LOW RC FLOW 11 LOOP B/S FC-416 l RP108 - CllANNEL 1 RCP llKR OPEN B/S L. RP1(9 Cil ANNEL 2 RCP llKR OPEN ll/S RP110 1 PRZR PRESSURE III II/S PC 429A RP111 1 PRZR PRESSURE St II/S PC-429C i

plic/ reports Page 17 l

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

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1990 APPENDIX 2 Malfunctions and Remote Functions (Cont'd)

Reactor Protection System (Cont'd)

RP112 1 PRZR PRESSURE SI UN11LDCK ll/S IC-429D RP113 1 PRZR PRESSURE ID IVS IC-429E RP114 11 STM LOOP ID-ID PRESS II/S IC-468A RP115 11 STM IDOP ID-ID PRESS IVS IC-469A RP116 11 S1M IDOP ID-LO PRESS IVS IC-482A RP117 1 PRZR 111011 LVL IVS ID-426A RP118 2 PRZR 111011 LVL IVS IE-427A RP119 - 3 PRZR 111011 LVL ll/S LC-428A RP120 3 PRZR PRESSUR11 Ill ll/S IC-431A RP121 3 PRZR PRESSURE SI B/S 10-4310 RP122 3 PRZR PRESSURE SI UNillDCKED ll/S PC-4311 RP123 3 PRZR PRESSURE ID ll/S 10-431J

- RP124 4 PRZR PRESSURE ID IVS IC-449A RP125 1 S/O LO-ID LVL ll/S LC-46111

. RP126 1 S/O ID-ID LVL ll/S LC-472A >

RP127 11 STM OEN ID PRESS B/S 10-46811 RP128 - 1 S/O 111 INL IVS IC-461 A RP129 1 S/O 111 LVL B/S LC-47211 RP130 2 S/O LO-ID LVL ll/S LC-473C RP131 11 STM OEN ID PRESS II/S 10-46911 RP132 2 S/O Ill LVL B/S LC-473D RP133 3 S/O 1D-ID LVL IVS LC-462A RP134 11 S'IM OEN ID PRESS II/S 10-48211 RP135 3 S/O Ill LVL ll/S LC-46211 RP136 12 STM OEN ID PRESS II/S 10-47811 RP137 11 S1M OEN ID PRESS II/S 10-47911 RP138 12 S1M OEN ID PRESS B/S PC-48311 RP141 1 Ill S1M FLOW FC-4MA RP142 1 111-111 S'IM FIDW FC-4 Mil RP143 3 !!I S'IM FIDW FC-474A RP144 3 III-III STM FIDW FC-474B RP148 AMSAC lilDCK SWITCil RP149 AMSAC ACTUATION SiONAL RESET RP152 CllANNEL 1 IlUS 11 UNDERVOLTAGE II/S j RP153 Cil ANNEL 2 BUS 11 UNDERVOLTAGE IVS RP154 - Cl!ANNEL 3 IlUS 12 UNDERVOLTAGE B/S RP155 CilANNEL 4 BUS 12 UNDERVOLTAGE IVS RP156 12 S'IM LOOP ID-ID PRESS B/S PC-483A RP157 12 STM LOOP LO-ID PRESS IVS IC-478A pite/ reports Page 18

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

PRAIRIE ISIAND SIMULATOR CERTIFICATION REPORT 1990 APPENDIX 2 Malfunctions and Remote Functions (Cont'd)

Reactor Protection Systern (Cont'd)

RP158 12 STM IDOP ID-LO PRESS II/S PC-479A RP159 2 RC IDOP OP DELTA T ll/S TC-406A RP160 2 RC IDOP OP DELTA T ll/S TC-40611 RP161 2 RC IDOP OT DELTA T ll/S TC-406C RP162 2 RC LOOP OT DELT; T B/S TC-4(6D RP163 1 RC LOOP ID TAvo 10 *1C-401F RPIM 1 RC IDOP LD-ID TAyo B/S TC-401D RP165 2 RC LOOP LO TAvo II/S TC-402F RP166 2 RC IDOP ID-ID TAvo ll/S TC-402D RP167 OPPS 111 PRESSURE II/S PC-419D RP168 OPPS 111 PRESSURE II/S IC-420D RP169 1 RC IDOP OP DELTA T B/S TC-405A

' RP170 1 RC LOOP OP DEllrA T ll/S TC-40511 RPl71 1 RC !DOP OT DEI!rA T II/S TC-405C RPl72 1 RC IDOP OT DE!!TA T ll/S TC-40$D RP181 2 TURIllNE POWER P-7 II/S PC-485A RP182 3 TURillNil POWER P-711/S PC-486A RP183 11 IlUS UNDERFREQUENCY ll/S RP184 11 BUS UNDERI'REQUENCY B/S RP185 12 IlUS UNDERPREOUENCY ll/S RP186 1211US UNDERFREQUENCY B/S RP187 2 PRZR PRESSURE 111 B/S IC-430A RP188 2 PRZR PRESSURE SIII/S PC-430E RP189 2 PRZR PRESSURE SI UNillDCK B/S PC-430F RP190 2 PRZR PRESSURE ID 11/S 10-43011 RP191 4 S/O ID-ID LVL B/S LC-463C RP192 4 S/G I!! INL B/S LC-463D RP193 2111 S'IM FLOW FC-465A RP194 2 111-111 STM FLOW FC-465B RP195 4111 S1M FLOW PC-475A RP196 4 Ill-III S1M FLOW FC-47511 RP199 3 RP IDOP OP DELTA T ll/S TC-407A I RP200 3 RC IDOP OP DEllrA T ll/S TC-40711

RP201 3 RC LOOP OT DELTA T B/S TC-407C RP202 3 RC LOOP OT DELTA T B/S TC-407D RP2(0 4 RC IDOP OP DELTA T B/S TC-408A RP2N 4 RC LOOP OP DELTA T B/S TC-40811 RP205 4 RC LOOP OT DEllrA T ll/S TC-408C RP206 4 RC IDOP OT DELTA T B/S TC-40RD RF207 3 RC LOOP LO TAya II/S TC-403F RP208 3 RC IDOP LO-lD TAyo II/S TC-403D plic/ reports Page 19

- r , . . . - , s -.m,,,-,, .my. ..-,,-mm.,,m, emi- - . . . - - - 4,,., s.. . , . , ,.-- .- ., ,..a.. , - . , _ . , , . . . . - - , .- ~ , - m.-,e -- --n.r

l PRAIRIE ISLAND SIMULATOR CERTil'ICATION REPORT 1990 APPENDIX 2 Malfunctions and Remote Functions (Cont'd)

Reactor Protection System (Cont'd)

RI'2(0 4 RC IDOL' ID TAyo ll/S TC-4NF RP210 4 RC LOOP ID-LO TAyo ll/S TC-4ND RF211 4 S/G LO-lO INI,ll/S LC-47111 RF212 4 S/G lil INL E/S ID-471A Reactor Control System RX01 l'RESSURIZliR SPRAY VAINE Pall,S OPEN RX02 PRiiSSURIZI!R SPRAY VALVES PCV-431 A & 11 FAIL Cl OSED RXCD l'RESSURIZi!H 11 EATERS FAIL ON RX(M l'RESSURIZER llEATERS Fall OIT (Al.L)

RX05 REACTOR LOOLANT IDOP TH TRANSMilTER l' AILS 111011 RXO6 REACTOR COOLANT 1D01' TH TRANSMrITER falls LOW RXO7 REACTOR COOLANT Tc TRANSMrlTliR falls 111011 RXO8 REAC'!OR COOLANT IDOP Tc TRANSMrlTER falls 1,0W RXO9 PRESSURIZER 1 EVEL NARROW RANGE TRANSMrlTER FAILS 1110 11 RX10 PRESSURIZER 1.EVEL NARROW RANGE TRANSMllTI!R falls LOW RXil PRESSURIZER PRESSURE TRANSMrlTER falls 1110 11 RX12 PRESSURIZER PRESSURE TRANSMitTliR falls 1.OW RX13 REACTOR COOLANT SYSTEM WIDE RANGli l'RESSURE TRANSMrlTER Pall,S lilGil RX14 REACTOR COOLANT SYSTEM WIDE RANGE PRESSURli TRANSMrlTER FAILS LOW RX15 STEAM GENERATOR LEVEL TRANSMrlTliR falls 111011 RX16 STEAM GENERATOR LEVEL TRANSMITFER FA!!S LOW RX17 STEAM GENERATOR PRESSURE Til ANSMrITER FA!!S 111011 RX18 STEAM GENERATOR PRl!SSURil TRANSMrtTER l' AILS LOW RX19 MAIN STEAM 1.IN!! STEAM FI,0W TilANSMITTER falls 1110 11 RX20 MAIN STEAM LINE STEAM FLOW TRANSMrITER falls IDW RX21 MAIN STEAM llEADER PRiiSSURE TRANSMrlTliR FAILURl!

RX22 FEEDWATl!R CONTROLLER OUTPUT Fall URE RX23 PEEDWATER LINE FLOW TRANSMrlTl!R Falls 111011 RX24 FEEDWATER LINE FIDW TRANSMITTER falls 1 OW RX25 TURillNE FIRST STAGE PRl!SSURE TRANSMITTER falls 111011 RX26 TURillNE FIRST STAGE PRESSURE TRANSMITTER FAILS 1,0W RX27 STM GEN FEEDWATER INLETTliMPERATURE TRANSMrlT11R falls 111011 RX28 STM OEN FEEDWATER INLET TEMPERATURE TRANSMITIT:R falls 1,0W RX29 FEEDWA'lTR llEADliR PRESSURE TRANSMITI'ER falls 111011 RX30 PEEDWATER llEADliR PRESSURE TRANSMITTER falls 1 OW RX31 STEAM GENERATOR WIDE RANGE LEVEL TRANSMrITER falls 111011 RX32 STEAM GENERATOR WIDE RANGE LEVEL TRANSMrlTER FAILS LO'W l

pitc/ reports Page 20

PRAIRIE ISLAND SIMULATOR CERTiriCATION RF? ORT l 1990 APPENDIX 2 Malfunctions and Remote Functions (Cont'd)

Reacto' Ccmtrol System (Con't)

RX33 STEAM GENERNIOR FEEDWATliR CONTROL, SYSTIIM falls'IO MANUAL RX34 ADFCS MAIN FLOW CONTROL VAINE OUTPUT CARD FAILURE RX35 ADFCS IlYPASS FLOW CONTROL VAIN!! OUTPUT CARD FAILURl!

RXI(O PRZR IITR GROUP 11 l RX101 IMI' PRESS ROD lilDCK II/S PC-485C RX102 IMP PRiiSS STM DUMP ll/S PC-4MC RX103 1 PRZR lit l'RESS PORV 11/S T/P-42911 RX1(M 2 l'RZR 111 PRESS LORY ll/S PC-430ll RX105 3 PRZR 111 PRESS IORY ll/S PC-43111 RX106 4 l'RZR 111 PRESS IORY ll/S T/P-44911 RX107 PRZR ID PRiiSS II/U IITRS 11/s PC-431E RX108 ADFCS SIGNAL SEl.l!CTOR IDO !C RESET RX1(D ADFCS IDSS OF WIDE RANGE LEVill LOGIC RESET Stearn Generator Systern c SC01 STEAM GEN!!RATOR tulle 1.EAK S002 STEAM OEN!!RA'IOR TUlll! RUI'lVRl!

SG03 STEAM O!!NERA'IOR liLDWDOWN CONTROL VAINE falls OPEN S 0 102 11 SG IlD SAMP1.I! ISO VIN IDCAL CS SO101 11 SG llD SAMPLE ISO VIN IDCAI, CS l 3- SGIN- 12 SG llD SAMPLE ISO VIN IDCAL CS SO105 12 SO IID SAMPLE ISO VIN IDCAL CS ,

l Safety injection Systern SIOl llOTil llORIC ACID TANK VAINES FAIL'lO OPEN IN AUTO

-S102 SI LOOP A COLD LEO INJ CllECK VAINE Fall URli l S103 IlORIC ACID TANK VAINil FAILS TO Cl.OSE ON IDW-LOW Ll!VI!L .,

IN TIIE PRESELECfED llORIC ACID TANK IN AUTO SIN SAFETY INJECTION PUMP TRIPS S105 SAFE *1Y INJECTION PUMP falls 'IO START AUTOMATICALLY I

S106 St ACCUMULATOR LEAKAGE S107 St ACCUMULATOR CllECK VAINE LEAKAGE SIGR. St ACCUMULA'IDR RlilIEF YAINil LEAKAGE Sl(9 SI COLD LEO INJ LINE RUI' PURL! INSIDE OF Tile ANNULUS Sil00 11/121 !!AST SUPPLY TO SIS S!!01 SI T ilS T 1.I N E S1102  !!A IlLENDER 'lO RWST Sil(0 11/12 St PMP DISCilO X-CONN ,

- SilN 11 SI PUMP DISCilARGE VIN l S1105 12 St PUMP DISC 11ARGE VIN plic/ reports Page 21 I

PPSRIE ISLAND SIMULATOR CERTIFICATION REPORT 1990 APPENDIX 2 Malfunctions and Remote Functions (Cont'd)

Safety injectiort Systern (Con't)

Sil06 IIA SPLY TO SI PMPS (320fG) IIKR S1107 11 SI SUC110N FROM RilR llKR S1108 12 SI SUCTION FROM RilR llKR Sil09 SI TO COLD LEGS CNMT ISO I!KR Sil10 SI 'IO LOOP 11 COLD LEG llKR I Silti St TO I,00P A CO!,D LEO IlKR Sill 2 11 ACCUM OUTL VLV IIKR Sil13 12 ACCUM OUlt VLV IIKR Sill 4 St PUMP SUCrrON VALVE, S1-15-5

'Dirbine Control Systern TC01 TURIIINE STOP VALVII PAILS TO CLOSE WIIEN REQUIRED TCO2 TURIIINE STOP VAINE FAILS CLOSED TC03 TURillNE CONTROL SYSTEM CYCLING OUTPUT TCN TURillNI! CONTitOL VAINE FAILS OPEN TC05 TURillNE CONTROL VALVE FAILS CLOSED TC06 REACTOR PROTl!CTION SYSTEM PAILS TO TRIP TURillNil TC07 TURilINil CONTROL INTERCill'T VAINE FAILS CLOSED

'1008 TURillNE CONTROL FAILURE DURING TURilIN!! ROLL TC09 TURillNE CONTROL FAILURE CAUSING TURilINE RUNilACK TC10 TURillNE CONTROL FAILURE CAUSING AN INCRl!ASl! IN IOWER WTrilOUT DEMAND -

'1011 COMPLETl! TURillNE TRIP FAILURi!

TCl2 TURillNE TRIP TC13 III.ECTRICAL IlYDRAULIC CONTROL PUMP. TRIP TCl4 TURUINE CONTROL VAINE FAILS IN IOSil10N TC100 TURilINE PEDESTAL TRIP TC101 CllANNEL 2 TURil AUTO STOP ll/S TC102 CilANNEL 3 TURIl AUTO STOP ll/S TC103 CilANNEL 4 TURil AUTO STOP ll/S TCIN TURillNE LEFT STOP VIN CLOSl!D ll/S TC105 TURilINE RIGIIT STOP VLV CLOSED ll/S

Turbine Systern TUO! LOSS OF TURBINE LUllE OIL SUPPLY TUO2 TURillNE GENERATOR VillRATION

. plic/ reports Page 22 i

L

_. . . . ~ _ __ . . _ . _ _ . . _ _ _ _ _ _ _ _ . . . . . . . . , _ . , _ . . _ . . _ . . __ _ . . ._

PRAIRIE iSIAND SIMULATOR CERTIFICATION REPORT 1990 APPENDIX 2 Malfunctions and Remote Functions (Cont'd)

Chemical and Volume Control System VC01 REACTOR COOLANT PUMP #1 SEAL FAILURE VCO2 REACTOR COOLANT PUMP #2 SEAL FAILURE VC04 POStrIVE DISPLACEMENT CllAROING PUMP TRIP 5 VC05 STUCK OPEN CIIAROING PUMP RELIEF VALVE VCOG REGENERATIVE !! EAT EXCIIANGER LEAKAGE VC07 LETDOWN llEAT EXCilANGER LEAKAGE TO ATMOSPIIERE VC08 LETDOWN IIEAT EXCilANGER tulle RUI'IURE TO CCW SYSTEM VC09 LETDOWN LINE LEAKAGE INSIDE CONTAINMENT VC10 CIIARGING PUMP COMMON C ,CIIARGE IIEADER RUI'rURE VC11 CilAROING LINE LEAKAGE INSIDE CONTAINMENT VCl2 EMERGENCY 110 RATION VALVE STUCK OPEN VC13 LETDOWN LINE RELIEF VALVE FAILURE VCl4 VOLUME CONTROL TANK RELIEF VALV11 FAILURE VC19 I,OSS OF AIR TO CllARGING PUMP SPEED CONTROLLER VC20 CCW RETURN l' ROM Ll!TDOWN llEAT llXCIIANGER FAILS CLOSED VC21 REACTOR COOLANT PUMP TIIERMAL IIARRIER tulle FAILURE VCR0 11 RCP SilAL INJ TIIROTILE VLV VC101 12 RCP SEAL INJ TIIROTILE VLV VC102 11 RCP STANDPIPE FILL VC103 12 RCP STANDPII'E FILL VCIN 11/12 MI) DEMIN INLET VC105 11 IIAST 110RON CONCENTRATION VC107 11/12 DEllORATING DEMIN VC108 RWST PUMP SUCTION SELECTOR VClw MANUALllORATE FROM RWST VC110 IILENDLIR llYPASS VC111 VCT PURGE 'ID 1110 11 LVL LOOP VC112 RMU TO Clio PUMP SUCTION VC113 - 11 CllO PUMP SPEED REMOTE VCll4 12 CIIO PUMP SPEED REMOTE VC115 13 CllO PUMP SPEED REMOTE VC116 11/12 LETDOWN FILTER OUTLET VC117 110RON CONCENTRATION VC118 LETDOWN FILTERS BYPASS VC119 112 TO VCT VC120 SEAL WTR RTRN ISOL '

VC121 11 IIAST LEVEL VC122 121 UAST LEVEL VC123 11 RX MAKEUP TK FILL ISOL VC124 12 RX MAKEUP TK FILL ISOL pile / reports-- Page 23

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1990 i APPENDIX 2 '

Malfunctions and Remote Functions (Cont'd)

Chemical and Volume Control System (Cont'd)

VC125 11 MIX BED IX IORON CONC VC126 12 MIX HED IX IORON CONC VC127 11 DEIORATE IX 10RON CONC VC128 12 DEIORATE IX 10RON CONC VC129 EMERGENCY IORATION VALVE VC130 Cl!ARGING TO LP B ll-P VC131 11 RCP LEAKOFF FIDW XMTITER B-P VC132 12 RCP LEAKOFF FLOW XMTITER ll-P VC133 11 RCP SEAL ll-P VC134 12 RCP SEAL ll-P Waste Disposal System WD100 ANN SMP PMP DScil VLV 'lO CN1MT MV-32228 WD101 ANN SMP PMP DSCil VLV TO CNTMT MV-32228 WD102 CONT SMP A PMP DSClf VLV 'IO ARTD SMP TK WD103 CONT SMP A PMP DSCII VLV TO ARTD SMP TK WDIN 11 RIIR PIT SMP PMP DSCil VLV WL-87 WD105 12 RIIR PIT SMP PMP DSCil VLi WL-87-2 WD106 LOCAI, RESET PH 54700-08 WD107 RCDT FI!!rER INLET AND ll-P VLYS WD108 PURIFICATION JUMPER ISOL VLVS J

L L

pite/ reports Page 24

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< PRAIRIE ISLAND SIMUIATOR CERTIFICATION REPORT 1990 APPENDIX 3 INSTRUCTOR INTERFACE CAPhBILITIES EVALUATION 4

10CFR 55.45, Regulatory Guido 1.149 and ANS/ ANSI 3.5-1985 woro reviewed to determino all requirements for certification of a plant referenced simulator. Following are all the requirements related to simulator capabilitics and a discussion of the capabilities of the Prairio Island simulator which moots this requirement.

A. Normal Operations capability:

"The simulator shall be capable of simulating continuously, and in real time, plant operations of the referenco plant." (ANS-3.5-1985 3.1.1)

The Prairio Island simulator is capable of simulating normal plant operations using the reference plant proceduros. This capability is tested during the annual test section 2.1. Those operations are verified to be simulated in real timo during the annual test coction 3.

D. Minimum Normal Evolution capability:

"The minimum evolutions that the simulator shall be capable of performing, using only operator action normal to the reference plant, are as follows: "

(ANS-3.5-1985 3.1.1)

" Plant startup - cold to hot standby. The starting conditions shall be cold shutdown conditions of temperaturo and pressure. Removal of the reactor vossol head is not a required condition for simulation." (ANS-3.5-1985 3.1.1.1)

" Nuclear startup from hot standby to rated power."

(ANS-3.5-1985 3.1.1.2)

Turbino startup and generator synchronization. "

(ANS-3.5-1985 3.1.1.3)

"hoactor trip followed by recovery to rated power."

(ANS-3.5-1985 3.1.1.4)

" Operations-at hot standby."

(ANS-3.5-1985 3.1.1.5)

" Load changes." (ANS-3.5-1985 3.1.1.6) l Page 1

l

! PRAlRIE ISIAND SIMU1ATOR CERTIFICAT10N RRPO!(T 4 1990

APPENDIX 1 L " Plant shutdown from rated power to hot standby and

! cooldown to cold shutdown conditions."

l [ANS-3.5-1985 3.1.1.8)

"Coro performance testing such as plant heat  :

balance, determination of shutdown margin, and I and measurement of reactivity coefficients anil -

control rod worth using using permanently installed ,

instrumentation."

(ANS-3.5-1985 3.1.1.9)

" Operator conducted surveillance testing on safety related equipment or systems."

(ANS-3.5-1985 3.1.1.10] ,

l I

The Prairio Island simulator is capabic of the listed normal operations using plant procedures and t operator action normall

plant; with all outplan'y performed in the referencet actions normally perform t

in the reference plent, performed by the instructor. Those normal operations are verified  ;

during the annual test section 2.1.

"Startup shutdown and power operations with loss

, than full reactor coolant flow.

9 [ANS-3.5 *1985 3.1.1.7) j This evolution is not allowed by Prairie Island procedures and operations above 10% power tiith losu than full Reactor Coolant flow are not possible.

Thorofore this capability does not apply to tho Prairio Island plant or the Prairie Island -

! simulator. The Prairie Island simulator accurately simulates the plant response to loss of Renator t Coolant. flow.

L C. Plant Malfunction Capabilitiest "Tho simulator shall be capable of simulating in real~ time, abnormal and emergency events l including malfunctions to demonstrate inherent plant response and automatic plant centrol-functions."

The Prairie Island simulator is capab1w of simulating, using malfunctions, abnormal and omergency.svents which demonstrate plant responso

- and automatic control functions. These are verified to be simulated in real timo during the annual test section 3.

I L

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PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1990 APPENDIX 3 "Whore operator actions are a function of the degree of severity of the malfunction ... the simulator shall have adjustablo ratos for the malfunction of such a range to represent the plant malfcanction conditions The Prairie Island simulator has many malfunctions W i th variable severities. The range of those gilablo malfinctions has been chosen to allow colection by tl3 i tstru: tor to mimic postulated plant malfunction conditions.

"The remaining events shall consist of a variety of malfunctions associttoi vilh the electrical, auxiliary, engineorei s"foty features systems, steam systems, reactor wict.e system, and instrumentation and cont.*ol syotems."

"The rnalfunctions listah below shall bo includodt" (ANS-3.5-2C 1.1.2)

(1) L/ c 1 -

Coolani (a) signiticde.b PWR steam generator leaks (di 1: Lido and outsido primary containment (c) 1argo and small reactor coolant breaks

' including demonstration of saturation conditions (d) failure o# oalaty and relief valvos (2) Loss of inet2.umons air to the extent that the whole syncem u individual headers can loso pressure and 9ffect the plant's static or dynamic f)eformanco (3) Loss or degraded floctrical power to the station, including loss of offsite power, loss of omergency power, loss of amargency generators, loss of power to the plant's electrical diatribution buse.<a and loss of power to the individual instrumentation bucos pcwor (AC a0 well is ?ag. asroom pol DC)dicationthat in pro ido

plant cone.rol functions affecting the paant's ror21)onso

~

(4) Dass of forced coo ant flow due to single oc multiple pump fa duro (5) Lons of condonsor vac rgn including loss of condonsor level controf~

Page 3 sn&w--

l

}

PRAIRIE ISLAND SIMULATOR CERTIFICATION El' PORT 1990 APPENDIX 3 (6) Loss of service wa';er or cooling to individual components (7) Loss of shutdown cooling (8) Loss of component cooling system or cooling to individual components (9) Loss of normal feedwater or normal feodwater system failure (10) Loss of all feedwater (normal and emergency)

(11) Loss of protective system channel (12) Control rod failure including stuck rods, uncoupled rods, drifting rods, rod drops, and misaligned rods (13) Inability to drive control rods (14) Fuel cladding failure resulting in high activity in reactor coolant ... and the associated high radiation alarms (15) Turbino trip I (16) Generator trip (17) Failure in automatic control systems that affect reactivity and core heat removal (18) Failure of reactor coolant pressure and volume control systems (PWR)

(19) Reactor trip (20) Main steam line as well as main feed line break (both insido and outsido containment)

(21) Nuclear instrumentation failures (22) Process instrumentation, alarms, and control system failures (23) Passive malfunctions in systems, such as engineered safety featurcs emergency feedwater systems Page 4

PRA*.RIE l' LAND SIMULATOR CERTIFICATION REPORT 1990 APPENDIX 3 (24) Failure of the automatic reactor trip system (25) Reactor pressure control system failure including turbine bypass failure (BWR)

Table 3A contains a cross reference between these requirements and the specific Prairie Island simulator malfunction numbers. Note that malfur.chion requirement #25 ic specific for BWR plar.cs al'd therefore not applicable for Prairie Island. Additionally the events required in ANS-3.5-1985 Appendix B Section B.2.2 are tested annually.

"Rhere applicable to the malfunction the simulator shall provide to the operator the capability of taking action to recover the plant, mitigate the consequences, or both." (ANS-3.5-1985 3.1.2)

The Prairie Island simulator allows the operator to take any action normally perforred in the reference plant from the Control Room to recover the plant or mitigate the consequences of a malfunction. Most outplant actions procedurally directed to respond to a malfunction are also supported through the use of remote functions by the instructor. Some malfunctions are not recoverable, however normal actions for these malfunctions would attempt to mitigate their consequences.

D. Modelling Extent "The simulation shall be capable of continuing until such time that a stable controllable and safe condition is attained which can be continued to cold shutdown conditions, or until the simulator operating limits ... are reached."

[.TNS-3.5-1985 3.1.2]

Provided the simulation does not exceed the established operating limits, the Prairie Island simulation can continue to a stable, controllable and safe condition which can be continued to cold shutdown conditions. This capability is tested during the annual test Section 2.2 as part of the test procedure for the required transient tests.

Page 5

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PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1990 APPENDIX 3 "The simulator shall contain sufficient operational panels to provide the controls instrumentation, alarms, and other man-machine Interfaces to conduct the normal plant evolutions of 3.1.1 ... and respond to the malfunctions of 3.1.2 ... "  %

(ANS-3.5-1985 3.2.1)

The Prairie Island simulator includes all of the panels in the Prairie Island Unit 1 control Room plus a portion of the Unit 2 Control Room (selected panels which contain shared equipment). Also included are selected Control Room back panels plus selected outplant panels (eg. Hot Shutdown Panels .

Additional Control Room back panel capabilities ar)e provided to the instructor using remote functions (eg. Generator lockout reset). All panels on the Unit 1 Control Room are operational and the Unit 2 panels provided are operatior.a1 as far as their effect on Unit 1. As such,-sufficient controls, instrumentation, alarms and other man-machine interfaces are available to perform the required normal evolutions and to respond to the required malfunctions. This capability is verified during the annual test Sections 2.1 and 2.2.

"The inclusion of systems of the reference plant and the degree of simulation shall be to the extent necessary to perform the reference plant evolutions described in 3.1.1 ... and the malfunctions described in 3.1.2. It shall be possible to perform these control manipulations and observe plant response as in the reference plant. This shall include system interactions with other simulated systems and shall provide total system integrated response." {ANS-3.5-1985 3.3.1)

The Prairie Island simulation includes sufficient systems and degree of simulation to perform the required normal plant evolutions, to respond to the required malfunctions and to observe and control i

pla.it response as in the reference plant. This includes system interactions and provides correct integrated plant response. This is verified during the annual test Sections 2.1 and 2.2. 9 "The systems that are operated outside the control room or that provide some input to the simulation models and are necessary to perform reference plant evolutions described in 3.1.1 ... and malfunctions described in 3.1.2 ... shall be simulated. The simulator trainee shall be able to

, Page 6 I

I

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

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1990 APPENDIX 3 interface with the remote activity in a similar manner as in the reference plant." i (ANS-3.5-1985 3.3.2)

The systems operated outside the Control Room which are necessary as inputs to the simulation model or are necessary for performance of the normal plant evolutions or malfunctions rewired are simulated.

Outplant actions are performed by the instructor using remote functions available from the instructor's console CRT. Trainee interface with these outplant actions is through use of the telephone system arranged to be-as similar to the normal plant interface as possib. .

E. Instructor Interface-

"The simulator shall possess a minimum capability for storage of 20 initialization conditions.

...and shall include a variety of plant operating conditions, fission product poison concentrations, and various times in core life."

-(ANS-3.5-1985 3.4.1] i Table.3B includes a list of the 26 permanent initial conditions (password protected and kept updated by the simulator support group). In addition to these the Prairie Island simulator has 14 initial conditions which are password protected to be use.d for exam scenarios and Emergency Plan scenarios (but not kept updated when the software is changed). Also the Prairie ' Island simulator has 60 initial conditions which are temporary (not password-protected nor kept updated) to be used for short term.saving of conditions of interest or for discrepancy identification for correction. Of these last 60, four initial conditions do not have corresponding. plant process computer initial condition sets.

As can be determined from the attached' list, the 26 permanent initial conditions consist of a. variety of plant conditions, core lives LZBC, BOC, MOC, EOC CDC) and fission product (Xenon free, equilibrium Xenon, peak Xenon) poisons .

"It shall be possible to conveniently insert and terminate the plant malfunctions specified in 3.1.2 ... The simulator shall be-capable of simulating simultaneous or sequential malfunctions, Page 7

l PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT l

1990 APPENDIX 3 or both, ... The introduction of a malfunction shall not alert the operator to the impending malfunction in any manner other than would occur in the reference plant. Provisions shall be made for incorporating auditional malfunctions ... not included in 3.1.2 ... "

(ANS-3.5-1985 3.4.2]

Malfunctions on the Prairie Island simulator are entered, severity changed, and terminated (when allowed by the specific malfunction) on a dedicated screen on the instructor's console CRT (screen MFS). Up to 16 malfunctions may be entered in any order desired (simultaneously or sequentially) and may be initiated immediately, initiated at a preset time, or initiated by a programmed function key on the remote control unit. Removal of a malfunction has all the options available to initiation of a malfunction. Additionally, variable malfunctions may be ramped up to the selected severity by entering a ramp time. Initiation of a malfunction does not alert the trainee in any manner different from the response of the reference plant.

Additional malfunctions have been added and will continue to be added as identified as desirable by the administrative process in place for this determination.

"The simulator shall have the capability of freezing simulation. ... consideration should be given to incorporation of fast time, slow time, backtrack, and snapshot capabilities."

(ANS-3.5-19ES 3.4.3]

The Prairie Island simulator has the capability of freezing simulation, slow time (several choices of slow time rates - 1/2, 1/4, and 1/8 normal),

backtrack (up to sixty backtrack intervals -

backtrack interval is usually set to once per minute but can be adjusted between 1 ano 10 minutes), and snapshots (total of 100 snapshots 60 of which are for general use). Certain parameters can also be run in fast time. The selected parameters are: xenon transients, condenser evacuation, turbine metal temperature, reactor heatup, reactor cooldown, and decay heat.

Page 8

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1990 APPENDIX 3 "The capability shall be provided for the instructor to act in the capacity of auxiliary or other operators remote from the control room."

[ANS-3.5-1985 3.4.4)

This capability is provided to the instructor on the Prairie Island simulator using remote functions. All remote functions required to be used during the normal operations procedures and during the emergency operating procedures are available to the instructor. As additional required or desirable remote functions are  ;

identified or requested, they are reviewed and incorporated into the software according to the administrative determination. process in place for this F. Simulator Operating Limits "In order to avoid negative training which could result from simulator operation during such events, administrative controls or other means shall be provided to alert the instructor when certain parameters approach values indicative of events beyond the implemented model or known plant behavior." (ANS-3.5-1985 4.3]

l l The Prairie Island simulator has operating-limits l which are monitored by the software and, when l exceeded, the instructor is alerted by an audible

! alert. a flashing light on the instructor's console and oy the simulator entering freeze. The instructor can then call up a screen on the instructor's station CRT -(SOL) which identifies which limit (s) was exceeded. The instructor can then override the operating limits and continue from that point. Administrative guidance allows training beyond these limits provided that the response of the simulator is not adversely l affecting the training being conducted. These l limits are not normally overridden. The specific parameters monitored as operating limits are included in Table 3C. These parameters are revised as determined necessary using the administrative l

process in place for this determination.

Page 9

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1990 APPENDIX 3 G. Monitoring "It shall be possible to obtain hardcopy transient data in the form of either plots or printouts for critical parameters during the evolutions of 3.1.1 ...and the malfunctions of 3.1.2 ... This monitoring capability shall provide sufficient parametric and time resolution to determine compliance with the performance criteria of Section 4." (ANS-3.5-1985 4.4)

The Prairie Island simulator has several different monitoring programs available for differing requirements (eg. Emergency Plan data, hardcopy printout, graphical capabilities). The major system specifically incorporated for certification testing is a software package developed by EPRI and modified for use on our system (SATAR). It collects data duritig a simulator run, then downloads this data to a personal computer for analysis and graphing. This syrtem meets the parametric and time resolution re@irements and has been used extensively for collection, analysis, graphing and presentation of certification testing data.

" Simulator performance shall be established by preparing a simulator performance test, conducting the tests, and comparing the simulator's performance with the simulator design data within the requirenents of Section 4 ...

" Testing shall be conducted and a re for each of the following occasions: port prepared (1) Completion of initial construction (2) If simulator design changes result in significant simulator configuration or performance variations."

(ANS-3.5-1985 5.4.1)

The Prairie Island simulator was built by Singer Company and was ready for training in February 1984. As part of the contract with Singer the simulator underwent extensive testing including Factory Acceptance Tests (ATP). The ATP (Acceptance Test Procedure) met most of the listed requirements (eg. all systems were completely tested and all malfunctions were tested) however Page 10

l PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1 1990 APPENDIX 3 since the standard-(ANS-3.5-1985) was not yet issued the acceptance criteria included in the standard was not included in the ATP. Since completion of the ATP all changes have included  ;

limited testing to verify correct system and malfunction response for the portions of the software which were changed.. This level of testing meets the intent of the requirements listed in ANS-3.5-1985.

4 4

i e

i i

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.. _ _ _ _ _ _ _ _ . - _, . . _ _ J

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT _;

1990 APPENDIX 3 TABLE 3A CROSS REFERENCE BETWEEN ANS 3.5 REQUIREMENTS AND E SIMULATOR MALFUNCTIONS 2.2 PLANT MALFUNCTIONS 2.2.1 LOSS OF COOLANT 2.2.1.1 STEAM GENERATOR LEAKS

a. SG01 A,B

b. SG02 A,B 2.2.1.2- INSIDE CONTAINMENT

a. RC06 A,B

b. RC07 A,B

c. RC08fA,B

- d.: RC09

e. RC10

f. RC11 A,B

g. RC12 A,B

h. RC13

1. RC14

j. RC15

k. RC21

1. RD08

m. VC09 2.2.1.3 OUTSIDE CONTAINMENT

a. RH03

b. RH07

c. RH08

d. VC07 2.2.1.4 LARGE AND SMALL BREAKS INCLUDING _ .

DEMONSTRATION OF SATURATION CONDITIONS

a. Several listed above at various severities 2.2.1.5 FAILURE OF SAFETY / RELIEFS

a. RC18

b. RC19 c.-RC22 d.-RH09

e. VC13

f. VC14 2.2.2 LOSS OF INSTRUMENT AIR

a. IA01

b. IA02 t

Page 12 l

v#-' p- m -m,w -

PRAIRIE-ISLAND SIMULATOR CERTIFICATION REPORT 1990-APPENDIX 3 TABLE 3A

-2.2.3 LOSS OR DEGRADED ELECTRICAL POWER ,

a. ED01

b. ED03

c. ED04

d. EDOS

e. ED06

f. ED07 A,B

g. ED08 A,B,C,D,E,F,G,H

h. ED09 A,B,C,D,E,F,G,H

1. ED10 A,B,C,D,E,F,G,H,I,J

j. ED13

k. ED14

1. ED15

m. ED16

n. EG03

o. EG06

p. EG08

2. 2. 4 - LOSS OF FORCED COOLANT FLOW

a. RC01

b. RCO2

c. RCO3 d.-RC04 2 . 2 . 5 .- LOSS OF CONDENSER VACUUM

a. FWO3

b. CWO2 2.2.6 LOSS OF COOLING TO COMPONENTS

a. CLO6

b. CLO7

c. CLO8 2.2.7 LOSS OF SHUTDOWN COOLING

a. CC05 b.-CC01 A,B l c. RH01 A,B L d. RH06 2.2.8- LOSS OF-COMPONENT COOLING l

l

a. CC01 A,B

b. CC04 A,B:

c. CC05

d. CC06 l

2. 2. 9. ' LOSS OF NOPMAL FEEDWATER

a. FWO1 A,B,C

b. FW13 A,B

c. FWO2.

d. FWOS-

e. FWO6 Page 13 n - . ,

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1990 APPENDIX 3 TABLE 3A

f. FWO9

g. FW15 A,B

h. FW16 A,B,C,D,E,F

i. FW17 A,B

j. FW18 A,B,C,D,E,F,G,H

k. FW19 A,B

1. FW20 A,B

m. FW21 A,B

n. FW22 A,B

o. FW23 A,B

p. FW24

q. FW25 A,B

r. FW26 A,B

s. FW27 A,B

t. FW28 A,B,C

u. FW29

v. FW30 W. FW31 A,B,C

x. FW39 A,B

y. FW40

z. FW41 A,B 2.2.10 LOSS OF ALL FEEDWATER This malfunction will be a combination of the normal feedwater malfunctions listed above and the emergency feedwater malfunctions following:

a. FW32

b. FW33

c. FW34 A,B

d. FW36

c. FW37 2.2.11 LOSS OF PROTECTIVE SYSTEM CHANNEL

a. CH01 A,B,C,D,E,F

b. NIO5 A,B,C,D

c. NIO6 A,B,C,D

d. NIO7 A,B,C,D

e. RP08 A,B

f. RP02 A,B

g. RXOS A,B,C,D

h. RXO6 A,B,C,D

1. RXO7 A,B,C,D

j. RXOB A,B,C,D  ;

k. RXO9 A,B,C

1. RX10 A,B,C

m. RX11 A,B,C,D

n. RX12 A,B,C,D

o. RX15 A,B,C,D,E,F

p. RX16 A,B,C,D,E,F

q. RX17 A,B,C,D,E,F Page 14

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1990 APPENDIX 3 TABLE 3A

r. RX18 A,B,C,D,E,F

s. RX19 A,B,C,D

t. RX20 A,Bec.D

u. RX23 A,E,C,D

v. RX24 A,B,C,D

- w. RX25 A,B

x. RX26 A,B

2. 2.12 CONTROL ROD FAILURES

a. RDOS 1,2,3,4,5,6,7,8,9,10,11,12,13, 14,15,1G,17,18,19,20,21,22,23, 24,25,26,27,28,29

'b. RD06 A,B,C,D,E,F,G,H,I,J,K,L

c. RD07 A,B,C,D,E,F,G,H,I,J,K,L 2.2.13 INABILITY TO DRIVE CONTROL RODS

a. RD01

b. RD02

c. RD03 d . -- RD0 4 2.2.14 FUEL CLADDING FAILURE

'a. CRO1 2'2.15 TURBINE TRIP

. 1

a. TC12 b.-TC13 A,B 2.2.16 GENERATOR TRIP

a. EG06

.b. EG07 2.2.17 FAILURE OF AUTOMATIC CONTROL SYSTEMS a.'MS11 A,B,C,D,E

b. RD01

c. RD02

d. RD03

e. RD04 f.-RD10

g. RX05 A,B,C,D

h. RXO7 A,B,C,D L 1. RX15 A,B,C,D

j. RX16 A,B,C,D

'k. RX17 A,B,C,D,E,F

1. RX18 A,B,C,D,E,F

m. RX19 A,B,C,D E n.~RX20 A,B,C,D

o. RX21

p. RX22 A,B

q. RX23 A,B,C,D

r. RX24 A,B,C,D Page 15

i PRAIRIE ISLAND- SIMULATOR CERTIFICATION REPORT 1990 APPENDIX 3 TABLE 3A

s. RX25 A,B

t. RX26 A,B 2.2.18 FAILURE OF RCS PRESSURE AND VOLUME A. Pressure

a. RC16 A,B

b. RC24 A,B

c. RX01 A,B

d. RXO2

e. RXO3

f. RXO4 g.-RX11 A.B,C,D

h. RX12 A,B,C,D '

B. Volume

a. VC19

b. RXO9 A,B,C

c. RX10 A,B,C

d. RX05 A,B,C,D 2.2.19 REACTOR TRIP

a. RP01 2.2.20 MAIN' FEED / STEAM LINE BREAK A. Main Steam Line Break

1. Inside Containment

a. MS01 A,B

', b. MSO9 A,B '

2. Outside Containment

a. MSO2 A,B

b. MSO3 A,B

c. MSO4

. d. MS10

.B. Main Feedwater Line Break

1. Inside Containment

.a. FW19 A,B b.:.FW20 A,B

c. FW21 A,B

2. Outside Containment

a. FW22 A,B

b. FW23 A,B

c. FW24

d. FW39 A,B

2. 2.21 NUCLEAR INSTRUMENTATION FAILURE

.a. NIO1 A,B

b. NIO2 A,B

c. NIO3 A,B

~d. NIO4 A,B e, NIOS A,0,C,D

f. NIO6 A,B,C,D

g. NIO7 A,B,C,D Page 16

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1990 APPENDIX 3 TABLE 3A 2.2.22 PROCESS INSTRUMENT ALARM / CONTROL SYSTEM FAILURE-a._CC06 A,B

b. CC08

c. EG02 d.-EGOS e.=EGil f._FWOS

g. FWO6

h. FWO7 1.-FWO8

j. FWO9

k. FW10

1. FW11

m. FW15 A,B

-n. FW16 A,B,C,D,E,F

o. FW25 A,B

p. FW26 A,B q._FW27 A,B

r. FW29

s. FW30

t. FW31

u. MS06 V. RD09

w. RH04

x. RHOS i

y. RP03-A,B,C,D,F.,F,G,H

z. RPO4~ J aa. RP05 ab RP06 ac. RP08 A,B ad.-RX13-A,B ae. RX14 A,B af. SG03 A,B,C,D ag. TCO3 ah. TC08 ai'. TC09-aj. TC10 ak TC11

'al. TC01 am.-TCO2 an. TC04 ao. TC05 ap. TC06 aq. TC07 ar. VC20 2.2.23 PASSIVE MALFUNCTIONS-ESF/AFW

-a. CCO2 A,B-

b. CC06 A,B Page 17 Ifituaarii e uinii . _.. .

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PRAIRIE ISLAND SIMULATOR CERTIFICATION-REPORT

-1990 APPENDIX 3 TABLE 3A '

c. CLO2 A,B

d. CLO3 A,B

e. CSO2.A,B

f. CS03~A,B

g. EG09 A,B

.h. EGil A,B

1. FW34 A,B j -RH02 A,B

k. RP03 A,B,C,D,E,F.,G,H

1. RP05

m. RP06 - -'

n. RP07 -

o. RP08 A,B

p. RP02 A,B q SIO1 r..SIO3 A,B

s. SIO5 A,B 2.2.24 FAILURE OF AUTO REACTOR TRIP SYSTEM

a. RP02 A,B

b. RP07 i

j r

+

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PRAIRIE ISLAND SInULATOR'CERTIFICATf0N REPORT < I i' APPENDIX 3 TABLE 38 iSIMULATOR PR0ittiw INITIAL CONDITIONS ,

TIME IN ~DATE BORON ROD PZR~ RX- i I . C. CYCLE SHOT CONC' - EIGHT XENON TENG DRESS PWR REMARKS -

. i 1- ZBC 12/09/90 2150 MI NONE' 110' 26 30 CPS TEST IC'  !

2 BOC 12/09 C 1599 RRI- NOE 133 16 .30 CPS COLD S/D, 3% 5/D  !

. 3 MOC -12/09/90 '1448 ARI NONE 132- 14 . 30 CPS COLD S/0, 3% S/D.- [

4 BOC :12/09/90- l1604" 500 NOE 322 390 30 CPS- E ATUP IN PROGRESS  !

i 5 BOC :12/09/90 1339 500 NOE 546 2272 100 CPS HOT S/0,'ECC:1339 PPM 8 100'5TEPS ON D :f i

6 BOC. 12/09/90. 1339 D 8 116 INC- 551 2255 5 %' PRIOR TO ROLLING TURBIE l 7 BOC 12/09/90 1342 D 8 119 INC 551 2242 5% PRIOR TO SYNCMONIZING GEERATOR {

l 8 BOC' 12/09/90 1072 0 8 203 EQUIL 552' 2220 51 % OE ET,' COW, Am FW PUrP IN SERVICE  !

.9 BOC 12/09/90 950 D 8 215 EQUIL. 560 2243 100 % 100% TN GET DELTA I = +0.6  !

10 .MOC 12/09/90 -503 D 8 218 EQUIL 560 2242 100 % 100% TARGET DELTA I : -0.9 ,

11 -EOC- 12/09/90- 210 D 8 218 EQUIL 560 2246 100 % 100% TNGET DELTA I : -1.4 -i i 12 EOC 12/09/90: 221 0 0 155 INC 554 2249 62 % PWR REDUCTION TO 60% FROM 100% AT

.o 1%/ MIN PRIOR TO SECURING FFWP  !

r 3* 13 14 EOC EOC 12/09/90 12/09/90-192 D 8 65:

550 500 INC.

NOE --

548 2237 22 % PRIOR TO SEPERATING UNIT 547. 2277 200 CDS BOWATED TO ECC BORON, VAC IN CO M ENSER j t y ECC:550 PPM 8 100 STEPS ON D  ;

15 EOC 12/09/90 952 ' 500 . NONE 346 352 70 CPS 'C/D IN PROGRESS, PRIOR TO PLACING RIR IN  ;

SERVICE. AT COLD 5/D BORON CONC ,

i 16 MOC '12/09/90 868 D 2 160- INC 547 2276 11 % LORD INCRERSE  !

17 CDC 12/09/90 0 0 8 228- EQUIL- 557 2241 95 %- COASTDOWN AT EOC  !

18 HOC 12/09/90- 868 D'8 118' NONE 547 2274 1.0E-8 PLANT STARTUP IN PROGRESS 19 MOC 12/09/90- 677 D 8 183 INC' 552 2242 52 % LOAD INCREASE; 2 COND,' WT, PFN PUrF5 20 MOC 12/09/90 488: 500 INC. 547 2251 200 CPS 2 MS FOLLOWING RX TRIP FROM 100% PlR. . l

, ECC:488 PPM E 100 STEPS ON D ,

21 MOC 12/09/90 507 D 8 210' DEC 558 2237 90 % LOAD INCREASE '

22- EOC 12/09/90 117. 5D0 PEAK 548 2265 300 CPS 10 HRS FOLLOWING RX TRIP' FROM 100% PWR ECC:117 PPM 8 100 STEPS ON D 23 MOC 12/09/90L 502 D 8 188. . PEAK 552 2236 52 % 6 M S FOLLOWING LOAD REDUCTION FROM.  ;

100% POWER 1 24 BOC !12/09/90 1054 D'8 210. DEC- 557 2255 78 % LOAD INCREASE TO 100% ~

25 MOC 12/09/90 513 0 8 183 INC- 555 2247 71:% . LOAD DECRERSE  !

.l 26 .ZBC '12/09/90 1402 D E 95L -NONEl 547 '2274 1.0E-8 POSITIVE ITC, STARTUP IN PROGRESS .!

1 .

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PRAIETE ISLAND SIMULATOR CERTIFICATION REPORT 1990 APPENDIX 3 TABLE 3C Simulator Operating Limits

1. RCS Pressure >3107 psig (Tech Spec 2.2 basis)

2. Containment Pressure >46 psig (FSAR Section 5.2.1.1)

3. Containment 'twrporature >268 F (FSAR Section 5.2.1.1)

4. Primary to Secondary dP >2485 pai (FSAR Section 4.3.2.2)

5. Secondary to Primary dP >1100 psi (FSAR Section 4.3.2.2)

6. NDT Limit Brittle Fracture - RCS pressure and temperature outside of brittle fracture region of curve in Tech Spec 3.1 (Figure 3.1-1)

7. Steam Cooling / Two Phase Flow parameters:

- Hot leg flow below natural circulation and

- Rx vessel level below hot leg and No SI flow and

- No RHR flow

8. Steim Bubble In Rx Head

- Pzr steam space flow (out of Pzr) and

- Rx Vessel upper plenum water enthalpy above saturation l

9. Rx Vessel Lower Plenum Temperature Limit

- Temperature in lower plenum should be above core region boiling temperature These nine conditions will be monitored using the identified l parameters and when these conditions are exceeded the SOL alarm will be set. For simple conditions (eg. RCS Pressure)

L the SOL page on PCM will display the value once the limit is exceeded. However for the complicated conditions the SOL page will only display "TRUE".

Note that considerable time and effort has been expended to enable the model to respond in a correct manner outside of several of these limits (specifically with a steam bubble in the reactor head and with early stages of steam cooling),

Page 20 1

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PRAIRIE' ISLAND' SIMULATOR CERTIFICATION REPORT 1990' APPENDIX 3 TABLE 3C however since the model-has some limitations in responding to these effects, these operating limits ~must be incorporated.

These operating limits can be~ overridden to allow training during these plant conditions. This enables training on use

. of some procedures as long as the simulator response is

-judged to not adversely affect the training being conducted.

The simulator operating limits are not overridden unless these conditions are expected or reached.

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PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1990 APPENDIX 4 Certification Review Panel Members The certification Review Panel makeup is spelled out in Simulator Procedure #20. This panel consists of the Lead Simulator Engineer, 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:

Lead Simulator Engineer - Michael Johnson Educational

Background:

Bachelor of Electrical Engineering University of Minnesota 1979 Experience: Eight years as a plant Systems Engineer at the Prairie Island Nuclear Plant Three years as the Lead Simulator Engineer for the Prairie Island Plant Simulator Certifications: Prairie Island Senior Reactor License 4/30/85 (License allowed to lapse 12/31/88 due to company decision)

Plant Operations - Robert Held Educational

Background:

High School Diploma Navy Nuclear Power Training Experience: Twenty-six years nuclear plant experience Fourteen years as Shift Supervisor at Prairie Island One year as Operations Liaiuon with Production Training Certifications: Prairie Island Reactor Operator License 1974 Prairie Island Senior Reactor Operator License 1977 NSP Basic Instructor Certification Page 1

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1990 APPENDIX 4 Operations Training - David Reynolds Educational

Background:

High School Diploma Two years Post Secondary Education Experience: Twenty-two years nuclear plant experience Over fifteen years training experience Five and one half years as Operations Training Supervisor 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 Educational

Background:

High School Diploma Two-years post secondary education Experience: Eleven years US Navy Nuclear Plant Operator / Instructor One and one half years Nuclear Plant Chemistry Tech Five years WPPSS Nuclear Instructor Eight and on half years instructor at Prairie Island Certifications: NSP Advanced Instructor Certification Prairie Island Senior Reactor Operator License Page 2 l-

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1990 APPENDIX 5 FOUR YEAR TESTING SCHEDULE A. Annual Testing - Following is an outline of the testing to be completed annually:

PART 1 -

STEADY STATE OPERATION REFERENCE ANSI 3.5 1.1 100% POWER - IC-9 BOL B2.1 1.2 75% POWER - IC-24 MOL ad:Iusted to ~75% B2.1 1.3 25% POWER - IC-13 EOL ad:lusted 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 .1.1 ( 1 )

2.1.1.2 OPERATIONS AT llOT 3.1.1(5)

SHUTDOWN 2.1.1.3 REACTOR STARTUP 3.1.1(2) 2.1.1.4 TURBINE / GENERATOR 3.1.1(3)

STARTUP 2.1.1.5 IAAD INCREASE 3 .1.1 ( 6 )

(0% TO 100%)

2.1.2 UNIT SHUTDOWN 2.1.2.1 PIANT SHUTDOWN 3 .1.1 ( 8 )

(HSD TO CSD) 2.1.2.2 LOAD DECREASE 3.1.1(6)

(100% TO 0%)

2.1.3 REACTOR TRIP WITH RECOVERY 3 .1.1 ( 4 )

2.1.4 CORE PERFORMANCE TESTING 3.1.1(9) 2.1.4.1 CALORIMETRIC 2.1.4.2 SHUTDOWN MARGIN CALCULATION 2.1.4.3 PHYSICS TESTING 2.1.5 OPERATOR SURVEILLANCE TESTS 3.1.1(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 D2.2 2.2.7 MAXIMUM RATE POWER RAMP B2.2 2.2.8 MAXIMUM LOCA WITH LOSS OF OFFSITE POWER B2.2 2.2.9 MAFIMUM STEAM BREAK B2.2 2.2.10 SBLOCA THRU PORV WITH NO SI PUMPS B2.2 2.2.11 LOAD REJECTION FROM 100% (Draft) B3.2 PART 3 COMPUTER REAL TIME TEST A3.1 PAGE 1

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PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1990- l APPENDIX 5 I

FOUR YEAR TESTING SCHEDULE B. Periodic Testing - The following testing-will be completed over a four_ year period from 1/1/91 through 12/31/94.

1. Malfunction Tests - A total of 339 tests are currently-included.- This number will be revised as  ;

^

malfunctions are-added, deleted or modified. One qut.'ter of_these tests

' completed each calendaryear. (presently 85 +/-4)_will be

2. Physical-Fidelity Comparisons - The-comparisons of-the simulator to the plant control room, although not specifically-included as tests, will be-repeated once every four year cycle. This-includes the comparison of photographs of the plant control room to the

- simulator, light level measurements and noise level measurements. Present plans are to complete these comparisons =during 1994.

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PRAIRIE ISLAND SIMULATOR' CERTIFICATION REPORT APPENDIX 6 1990 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. PITC 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: 1/11/90 CRP Approval Date: 2/1/91 Initial Conditions: IC-9 (100% Power Beginning of Cycle)

Duration of Test: One Hour Data Collected: Data was collected for the parameters listed in-Table 6A using the SATAR (Simulator Automated Testing ,

program And and Reverification)imetric Secondary Calor (heat balance) Additionally, dataRCS wasLeakrate collected.

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

Deficiencies. Identified:-Several parameters differed.from the plant values by more than 2%. Most of these parameters are variable based on desired plant modes of operation and vary-from day to day (eg. Generator vars is adjusted to the desired grid conditions which vary from hour to.

hour). Some differences were~ determined to be due to plant maintenance problems (eg. leaking check valve) which are undesirable to model. All differences were reviewed by the Certification Review Panel and determined to be. insignificant to training.

1 Page 1

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT APPENDIX 6 1990 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. PITC 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: 1/16/91 CRP Approval Date: 2/1/91 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 6A using the SATAR (Simulator Automated Testing program. Additionally, RCS Leakrate And Reverification)imetric and Secondary Calor (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 2

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT APPENDIX 6 1990 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. PITC 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: 1/18/91 CRP Approval Date: 2/1/91 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 parameters listed in Table 6A using the SATAR (Simulator Automated Teating program. Additionally, RCS Leakrate And Reverification)imetric and Secondary Calor (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 l

l PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT APPENDIX 6 1990

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

Description:

The purpose of this test'is to ensure the PI*C Simulator simulates operations from cold shutdown '

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

Date Conducted: 8/21/90 through 11/20/90 CRP Approval Dater 1/31/91 Initial Conditions: IC 2 (Cold Shutdown, Beginning Of Cycle)

Final-Conditions: Simulator in stable 100% Power conditions. .

Data Collected:- Controlled procedures were used for all plant-evolutions, completed copies of all procedures used were collected.-

Description of: Baseline Data Used: Controlled plant procedures are-used-for all steps of this shutdown.

Copies:of all completed procedures and-surveillances are included as records. Ability to correctly complete controlled plant procedures and'to achieve stable 1001 power conditions indicates acceptable simulator o performance.

Deficiences Identifjed During This Testing: None '

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d PRAIR7.E ISLAND SIMULATOR' CERTIFICATION REPORT APPENDIX 6~ 1990 ]

I ANNUAL OPERABILITY TESTING ABSTRACT TRANSIENT OPERATION TESTING - NORMAL PLANT EVOLUT10FS

. UNIT SHUTDOWN

Description:

The purpose of-this test is to ensurn the PITC Simulator simulates operations-from 100% power

~ operations conditions.to cold shutdown conditions. This precedure will use the normal plant-operatiag procedures and surveillances-for operating. guidance. Th9= simulator is expected to simulate all control board evolutions ano some required supporting.out plant tasks..

Date Conducted: 11/20/90 through 11/21/90 CRP Approval Date: 2/1/91 Initisl condit. ions: IC-17 (95% Power. Coastdown Cont.litions)

'Finhl Conditions: Simulator in stable Cold Chutdown conditions.

= Data Collected: Controlled procedures were used -for all plant evolutions.- Completed copies of all procedures L

used were collected.

LDescription of Baseline Data Used:. Controlled plant procedures are used for all'stepo of-this shutdown.

l- Copies- of Jall-' completed ' procedures: and csurveillances are

,- included as records. Ability to correctly complete L controlled plant procedures.and to achieve stable cold shutdown conditions indicates acceptable simulator performance.

-Deficiencen Id'entified During This Testing: None 1;

L Pago 5

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, PRAIRIE ISLAND GIMULATOR CERTIFICATION AEPORT l APPENDIX-6 1990 ANNUAL b9EMBIL(7'i 'fL%7NG ABSTRACT TRANSIENT OPER CION TFSTIVa - MOfLVL PLANT EV0 LOTIONS RL'CTOR TRIP W1W ItEc0VERY

Description:

The purpose of this procedure is to test the response of thn PITC 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 1 portions of the testing program will measure the malfunction abilitics of Qua- simulator. This test la designed to meet the requirements of AdSI 3.5 section -

3.1.1(4) " Reactor trip followed by recovery to rated power". The acceptance ct'iteria of ANSI 3.5 section 4,2.1 Tranzient operation (b) and (c) is followed.

Date Condursed: 12/19/90 CRP Approval Date: 1/31/91 initial Conditions: Ic-9-(200% Power.Beginning of Cycle) l-Final Conditions: 100% Powar Stable plant-conditions.

Data Collected: contro]le.d p'rocedures were used for all plant evoJutloas, completed coolosaof all procedures used were collected.

Description'of Baseline Date Used: Controlled plant procedures-are.uted for all steps-of this shutdown.

Copies of all cou3leted. procedures, checklists and surucillances aru' included as records. Ability to correctly conplete controlled pinnt' procedures and to achieve-stab).e 100% power conditions indicates acceptable simulator performance.

Deficiences Identified .htring This 'Tosting: None p

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4

-PRAIRIE ISLAND SIMULC10R CERTIFICATION REPORT  !

APPENDIX 6 1990 {

6

.{

ANNUAL OPERABILITY TESTING ABSTRACT TRANSIENT OPERATION TESTING - NORMAL' PLANT EVOLUTIONS CORE Peri'ORMANCE TESTING l

Description:

The purpose of this test-is to verify that the performance of the Prairie Island Gimulator core model matches . the plant core performanus. This test will ,

messure the plant heat balance ; tale.~imetric), will-  !

calculate the shutdown mariin at several power-levels und W11] 'Nrt@r0 Zsro Power Physics testing to measure -

total cor.ttpl rqd worth, c'iti;al S boron concentration-and lonthermal"teniperat 9 cSofficient at beginning of 1 life. T^2 s tast is dtvour ed to meet the requirements of 1RSY 3.1. Section 3.1.1.s'% Norma 2 Plant Evolutions". The acceptance critoriataLt developed from the plant  !

orrveillanco test >rocedures (SP loci, n30, D32). 1 i

, Date Conducted: 1/1/91 CRP hpproval Date: 2/1/91 Initial Cc ndLtions: ' Several fte 9eperate parts of tha t.cer:- l IC-o (100k Pc:rer Beq.tyLig c of Cycle)

IC-19 (53% Power dxddle et Cycle)

IC-13 (2G% Power End of Cycle r

7C-5 (Hot Shutdown Beginning u) f Cycle)

Final Conditions: Heasureme;ts completed.

Data Collected:' Measurements of: Control Rod Worth, Critic 11 Doron Concentration,' Isothermal 1 Temperature Coefficient,

' Shutdown Mal in along with Calorimetric (heat balance)-

-data, i

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 incor orated'into the simulator.- These-differences have been udged by the Certification Review Panel to not be -

signi icant to training. The simulator core model will be updated to mctch'the plant predicted core data once the plaut has achieved the goal of 18 month cycles Page 7 i,

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1 I PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT APPENDIX 6 1990 l

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 designed to meet the requirements of ANSI 3.5 section 3.1 hNormal Plant Evolutisns", sub;oction 3.1.1.10

" Operator conducted surveillance testing on safety-related equipment or systems. The surveillances tested are selected from the PINGP control room lists of csrveillances. All surveillances on this list whicn arn completed largely from the control Room are tested. Th.

criteria for acceptable simulator response was the ability to complete the surveillance as outlined in the test procedure, and all control board res within the procedure acceptance criteria.ponses were Date Conductedt Various Dates between 11/13/90 and 11/21/90.

CRP Approval Date 1/31/91 Injtial Conditionst Various depending on the Surveillance procedure requirements.

Final conditions: Completion of the surveillance procedure.

Data Collected: Completed copies of all Surveillance Procedures detemined to he appropriate for use on the L simulator.

l-Description of Baseline Data Used: Controlled copies of the plant surveillance procedures with their proscribed acceptance criteria.

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Doriciences Identified During This Testingt None Page 8

PRAIRIE ISLAND SIMUMTOR CERTIFICATION REPORT APPENDIX 6 1990 ANNUAL OPERABILITY TESTING ABSTRACT TRANSIENT OPERATION TESTING - TRANSIENT TESTS I

MANUAL REACTOR TRIP

Description:

The purpose of this test is to test the ability of the PITC simulator to match PINGP conditions, during a manual reactor trip. It is not the intent that other malfunctions bo intorjected. but to only simulato operations under reactor trip conditions. Other portions of the testing program will measure the malfunction ability of t3e 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 critoria of ANSI 3.5 Appendix B -

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

Dato Conductod 12/19/90 CRP Approval Dato: 1/31/91 Initiel Conditions: IC-10 (100% Power Middle of Cycle)

Final Conditions: Tavo stabilizes at or trends to 547 degreco, NIS sourco ranges are onorgized, steam generator narrow range levels are on scale and increasing.

Data Collected: Data was collected for selected paramotors from the list in Table 6A using the SATAR Automated Testing And Roverification) progr(Simulator am.

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

l Doficiences Identified Daring This Testing None l

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1 PRAIRIC ISLAND SIMULATOR CERTIFICATION REPORT APPENDIX 6 1990 1

ANNUAL OPERABILITY TESTING ABSTRACT TRANSIENT OPERATION TESTING - TRANSIENT TESTS '

l TRIP OF ALL FEEDWATER PUMPS Description The purpose of this test is to test the ability

, of the PITC simulator to estch PINGP conditions, during a loss of all feedwater event. It is not the intent that other malfunctions be interjected, buc to only simulate operations under loss of feedwater. Other portions of Lie 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 ANPI 3.5 Appendix B ~B2.2.1, and 4.2.1 Transient operation (b) and (c) is followed.

Date Conductedt 12/10/90 CRP Approval Date! 1/31/91 Initial Conditions: IC-11 (100% Power End of Cycle)

Final Conditions: RCS prersure reaches the setpoint of the

. pressurizer power operated relief valves and the 4

pressurizer PORV's 13.f t.

. Data Collected: Date was collected'for selected parameters

-from the list in-Table 6A 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 10 4

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PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT APPENDIX 6 1990 AMNUAL OPERABILITY TESTING ABSTRACT TRANS.'.ENT OPERATION TESTING - TRANSIENT TESTS CIASURE OF MAIN STEAM ISOLATION VALVES

Description:

The purpose of this test is to test the ability of the FITC simulator to match PINGP conditions, during a inadvertent closure of both main steam isolation valves vhile at 100% reactor power. It is not the intent that other malfunctions be interjected, but to only simulate operations under MSIV closure conditions.

Other portions of the testing program will measure the malfunction ability of the simulator. This test is designed to meet the requirements of ANSI 3.5 Appendix B section B.2.2 - Transient Performance " Simultaneous closure of all "ain Steam Isolation Valves". The acceptance criteria of ANSI 3.5 Appenoix B - B.2.2.1, and 4.2.1 Transierit operation (b) and (c) is followed.

Date Conducted: 12/10/90 CRP Approval Date: 1/31/91 Initial Conditions: IC-11 (1004 Power End of Cycle)

Final Conditions: RCS Tavg stabilizes at approximately 552 degrees or steam pressure at 1050psig. generator pressure PORV's maintain Data Collected: Data was collected for selected parameters from the list in Table 6A 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 11

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT APPENDIX 6 1990 .

1 l

ANNUAL OPERABILITY TESTING ABSTRACT TRANSIENT OPERATION TESTING - TRANSIENT TESTS TRIP OF ALL REACTOR COOLANT PUMPS Description The purpose of this test is to test the abilit of the PITC simulator to approximate PINGP conditions, y during a simultaneous trip of both unit #1 RCP'P, 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 t1e simulator. This test.is designed to meet the requirements of ANSI 3.5 Appendix B section B.2.2 -Transient Performance " Simultaneous trip of all Reactor coolant pumps ". The acceptance criteria '

of ANSI 3.5 Appendix B -B.2.2.1, and 4.2.1 Transient operation (b) and (c) is followed.

Date Conductedt 11/27/90 CRP; Approval Datet 1/31/91 Initial Conditionst IC-11 (100% Power End of Cycle)

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

Data collected: Data was collected for selected parameters from the list in Table 6A 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 ideratified in Appendix 4 of this report.

Deficiences Identified During This Testing: None Page 12 i

e

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT APPENDIX 6 1990 ANNUAL OPERABILITY TESTING ABSTRACT TRANSIEHf OPERATION TESTING - TRANSIENT TESTS TRIP OF ANY REACTOR COOLANT PUMP

==

Description:==

The purpose of this test is to test the ability of the PITC simulator to match PINGP cotiditions, during a trip of 11 RCP, which causes a reactor trip. It is not the intent that other malfunctions be interjected, but to only simulate operations under reactor trip conditions. Other portions of the testing program will measure the malfunction ability of the simulator. This test is designed to meet the requirements of ANSI 3.5 Appendix B section B.2.2 -Transient Performance " Trip of any single ; .ctor coolant pump". 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: 12/10/90 CRP Approval Date: 1/31/91 Initial Conditions: IC-11 (100% Power End of Cycle)

Final Conditions: RCS Tave stabilizes at approximately 547 degrees.

Data Collected: Data was collected for selected parameters from the list in Tabic 6A 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 1

Page 13 )

4 s

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PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT j APPENDIX 6 1990 ANNUAL OPERABILITY TESTING ABSTRACT j TRANSIENT OPERATION TESTING ** TRANSIENT TESTS

! MAIN TURBINE TRIP a

5-

Description:

The purpose of this test is to test the abilit of the PITC simulator to ap during a Main turbine tripfrom (proximate maximum power p1NGP conditions, level that y i does not result in immediate-reactor trip). It is not i

the intent that other malfunctions be interjected but i to only simulate operations under tain turbine tr1p '

conditiona. Other portions of the testing program will i 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)  !

l and (c) is followed.

Date Conductedt 11/6/90 l CRP Approval Datet 1/31/91 Initial conditions: IC-7 ($4 Power Beginning of cycle) i Final Conditionst RCS Tavg stabilizes at approximately 552 ,

degrees.

Data' Collected: Data was collected for selected from the list in Table 6A using the SATAR (parameters Simulator' j 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 i 9

Page 14

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3-4- PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT

. APPENDIX 6 1990

[ ANNUAL OPERABILITY TESTING ABSTRACT l

TRANSIENT OPERATION TESTING - TRANSIENT TESTS

, MAXIMUM RATE POWER RAMP

Description:

The purpose of this test-is to test the ability of the PITC 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 l 4

power ramp conditions. Other portions of the testing i L program will measure the malfunction ability of the simulator. This test is designed to meet the requirements of ANSI 3.5 Appendix B section B.2.2 -

+

Transient Performance " Maximum rate power ramp". The

acceptance criteria of ANSI 3.5 Appendix B - B.2.2.1, and- 4.2.1 Transient operation (b) and -(c) is followed, i

Date Conducted: 12/10/90 CRP Approval Date: 1/31/91 j Initial conditions ' IC-10 (100% Power Middle .? Cycle) f

! Final Conditions: RCS Tavg pressurizerlevelstab11$ressurizerpressureand ze.

Data. collected: Data was collected for selected parameters from the :'.st in Table 6A using-the SATAR' Automated Testing And Reverification) progr(Simulator am.- I 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 i report.

Deficiencos' Identified During This Testing None 4

Page 15 4

1 w-<---..-- -- , .-m.a. ,n, ,p-

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT APPENDIX 6 1990 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 PITC simulator to match PINGP conditions, during a maximum break LOCA with a loss of offsite power. It is not the intent that other nalfunctions be interjected, but to only simulate operations under these conditions. Other portions of the testing program will measure the other malfunction abilities of the simulator. This test is designed to meet the requirements of ANSI 3.5 Appendix B section B.2.2 -

Transient Performance " Maximum size reactor coolant system rupture combined with loss of all offsite power".

The acceptance criteria of ANSI 3.5 Appendix B -B.2.2.3, and 4.2.1 Transient operation (b) and (c) is followed.

Date Conducted: 12/10/90 CRP Approval Date: 1/31/91 Initial Conditions: IC-11 (100% Power End of Cycle)

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

Data Collected: Data was collected for selected parameters from the list in Table 6A using the SATAR (Simulator Automated Testing And Reverification) program.

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

Deficiences Identified During This Testing: None Page 16

i e

j

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT

, APPENDIX 6 1990 1

ANNUAL OPERABILITY TESTING ABSTRACT l

{ TRANSIENT OPERATION TESTING - TRANSIENT TESTS MAXIMUM STEAM LINE BREAK 2

Description:

The purpose of this test is to test the ability of the PITC 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.

t l: Date Conductedt 12/11/90 CRP Approval Datet 1/31/91 Initial Conditions: 10-11 (100% Power End of Cycle) t Final Conditions: RCS pressure recovers, the non-faulted 1 steam generator level recovers and containment pressure trends down.

d Data Collected:- Data was collected for selected paramoters F from the list in Table 6A using the SATAR Automated Testing And Reverification).progr(Simulator am.

i Description of Baseline Data Used: Judgement of the Certification Review Panel. Makeup and qualifications L

~

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

Deficiences Identified-During This Testing: None J

J f' Page 17 L

l

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT APPENDIX 6 1990 ANNUAL OPERABILITY TESTING ABSTRACT TRANSIENT OPERATION TESTING - TRANSIENT TESTS SMALL BREAK LOCA THROUGH PRESSURIZER PORV WITH NO SI PUMPS

Description:

The purpose of this test is to test the ability J of the PITC simulator to match PINGP conditions, during I 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 conditions. Other portions of tae testing program will measure the other malfunction abilities of the simulator. This test is designed to 1 meet the requirements of ANSI 3.5 Appendix B section  !

B.2.2 - Transient Ferformance " Slow primary system l depressurization to saturated conditions using-  !

pressurizer relief or safety valve stuck open. lInhibit activation of high pressure Emergency Core Cool:ng Systems)". The acceptance criteria of ANSI 3.5 Appendix B - B.2.2.4, and 4.2.1 Transient operation (b) and (c) l is followed.

l Date Conducted: 12/11/90 l CRP Approval Date: 1/31/91 Initial Conditions: 1C-11 (100% Power End of Cycle)

Final Conditions: RCS pressure reaches saturation conditions as indicated by ICCM and ERCS displays.

L Data Collected:-Data waJ collected for selected paraueters i from the list in Table 6A using the SATAR Automated Testing And feverification) progr(Simulator am.

l Description of' Baseline Data Used: Judgement of the i 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 l

i PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT APPENDIX 6 1990 ANNUAL OPERABILITY TESTING ABSTRACT TRANSIENT OPERATION TESTING - TRANSIENT TESTS LOAD REJECTION TROM 100% POWER

Description:

The purpose of this test is to test the ability of the PITC simulator to match PINGP conditions, during a load rejection from 100% power. It is not the intent that any malfunctions be interjected, but only to simulate operations under maximum loss of load conditions. Other portions of the testing program will measure the malfunction ability of the simulator. This test is designed to meet the requirements of 1990 drcft 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 are followed.

Date Conducted: 12/11/90 CRP Approval Datet 1/31/91

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

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

Data Collected: Data was collected for selected paramotors from the list in Table 6A 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 19

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT l APPENDIX 6 1990 ANNUAL OPERABILITY TESTING ABSTRACT COMPUTER REAL TIME TEST l

==

Description:==

The purpose of this test is to test the a allity of t7e PITC simulator to perform in real time.

Real time is defined (in ANS 3.5) as "... dynamic performance in the same time base relationships, sequences, 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 therefore that frames all frames haveare never timeskippod).

to completeThis ver(and ifies real time performance since all the software assumes that the modules run at their allocated frequency. Additionally, four specific tasks, chosen to ensure that each of the four executive programs are tested, are performed and timed to be compared to plant values for task completion time. Finally a selected list of plant surveillance tests are completed all of which time the performance of some plant equipment. These surveillance test results are taen compared to the plant results to verify agreement.

Date Conducted: 6/28/90 & 12/31/90 CRP Approval Date: 1/31/91 Initial conditions: Various depending on the surveillance test requirements.

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

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

Description of Baseline Data Used: Minimum of five percent spare time in each frame 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 Page 20

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT APPENDIX 6 1990 TABLE 6A SIMULATOR CERTIFICATION TESTING CRITICAL PARAMETER LIST Datapool Parameter 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 Foodwater Flow Loop A W/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 vatts RCQRXPWR Neutron Flux N41  % NIN0049A N42  % HIN0050A N43  % NIN0051A N44  % NIN0052A Source Range Monitor N31 DKCPS NIN0031A N32 DKCPS NIN0032A Intermediate Range Monitor N35 mea NIN0035A N36 mcA HIN0036A Delta I N41  % HIQPDIA N42  % NIQPDID 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 RCT0483A RVLIS Level Upper Head  % RCLO452A Wide Range  % RCLO454A Dynamic Head  % RCLO456A Generator Watts MW EGQO340A Generator Vars MVars EGYO346A Generator Voltage volts EGV0341A 345 KV Bus 2 Voltage KV EDV0330A Page 21 l

_-____ _ _ _ _ _ _ _ _ ____ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ = _ _ _

PRAIRIE ISLAND SIMULATOR CERTIFICATION PEPORT APPENDIX 6 1990 TABLE 6A SIMULATOR CERTIFICATION TESTING CRITICAL PARAMETER LIST Datapool i

Paramotor Title Units Variablo 4160 V Voltago Bus 15 volts EDV0347A Bus 16 volts EDV0348A 4160 V Frequency Bus 15 Hz EDFBUS15 Bus 16 Hz EDFBUS16 400 V Safeguardo Bus 110 Voltage volts EDEB110 Bus 120 Voltage volts EDEB120 Instrumont AC Statun Pnl 111 Bool EDtB0111 Pnl 132 Bool EDtB0112 Pnl 113 Bool EDtB0113 Pnl 114 Bool EDtB0114 Pnl 117 Bool EDtB0117 Pnl 118 Bool EDtB0118 125 VDC Voltage Pn1 11 volts EDEBAT11 Pnl 12 volts EDEBAT12 Containment Pressure psig CHP1005A Containment Temperature F CHTCONT Steam Generator Pressure SGA psia RXPS468 SGB psia RXPS478 Wide Range Steam Generator Level SGA  % RXLO409A 3GB  % RXLO429A Narrow Range Steam Generator Lovel SGA  % RXLO4 05A SGB  % RXLO425A Safeguards Actuation Signal Train A bool RP SISA Train B Bool RPtSISB Pressurizer Relief Valvo Status Bool RCY9201D Safety Injection Flow 11 SI Pump gpm SIF0922A 12 SI Pump gpm SIF0923A RWST Lovel  % SILRWSTP Component Cooling Pump Pressure 11 Header psig CCPHDR11 12 Header psig CCPHDR12 Cooling Water Header Pressure Loop A psig CLP43504 Loop B psig CLP41505 CVCS Charging Flow gpm VCF0128A Boron Concentration ppm RCD Subcooling Margin Train A F RCTSUBCA Train B F RCTSUBCD i

Note that variables are not listed for Steam Genrtator Temperattire or Pressurizer Relief Valvo Flow. These values are not available to the operator and are not easily available on the simulator. For Pressurizer Relief Valve Flow a status point is listed since this is available to the operator.

Page 22 l

{

PRAIRIE ISLAND SIMULATok CERTIFICATION REPORT l 1990 APPENDIX 7 MALFUNCTION TEST PROCEDURE SAMPLE Following are two samples of malfunction test procedures.

Two different formats are followed; the first format unos the parts of the updated Acceptance Test Proceduro along with the cause and Effects pagos which describe the detailu of the malfunction being tested, the second format is a cortpletely rewritten test proceduro specifically for cortification testing of malfunctions. During the next four years wo intend to rewrito all test procedures to follow the second format and to replace the malfunction testing section of the Acceptance Test Procedure with those procedures.

Page 1

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l

PITC ANNUAL SIMULATOR OPERABILITY TEST PROCEDURE b

l MALFUNCTION TEST - REACTOR COOIANT SYSTEM

{

MALFUNCTION RC01 I

. PROCEDURE APPROVALt Revision 0 Prepared by: Nbb Approved by: M/ /l ,

f 7IG/DATF '

5 OVERVIEWr

i. The purpose of this test is to monitor the control L board response resulting from the insertion of a

Reactor Coolant Pump Trip malfunction. This. test i will compara expected response with simulator control board response. A satisfactory test will i be-confirmed if all responses are as expected and L are within the bounds described in the malfunction j cause and effects manual for a " REACTOR COOLANT PUMP TRIP - RC01".

l EXPECTED RESULT The simulator will respond to this malfunction as described in the Cause and Effects and in the

-Acceptance Test Procedure (both attached).

r PROCEDURE:

Test this malfunction as described in the Cause and Effects and in.the Acceptance Test Procedure (both attached).

TEST DATE l

l MALFUNCTION TEST RC01 - REV O PAGE 1

RA RIE 3SLAND MALFUNCTION CAUSE AND EFFECTS 4ALF N0. MALFUNCT!cN TITLE /RANSE/CAUSE t EFFECTS RCD 1 REACTOR COOLANT PUMP TRIP MALF - A - 11 RCP ,

MALF 12 RCP TYPEtGENERIC CAUSE FAULTY 86 RELAY ACTUATION PLT STA 100% REACTOR POWER EFFECTS THE WHITE AND G#EEN LAMPS WILL ENERGI!E AND THE RED LAMP WILL DEENERGIIE ON THE SCEAKER INDICATION FOR THE SELECTED REACTOR COOLANT PUMP. FLOW THP0 UGH THE AFFECTED LOOP WILL DECREASE TO ZERO IN ADPROXIMATELY 60 SECONDS. REVERSE FLOW THROUGH THE AFFECTED LOOP WILL OCCUP DUE TO TWE DELT A P ACROSS *HE CORE DEVELOPED SY THE OPERATING REACTOR COOLANT PUMP.

A REACTOR TRIP 001 TO REACTOR COOLANT PUMP BREAKE#

OPENING WILL OCCUR. PRES $UDIIER PRES $VRE AND LEVEL WILL INCREASE INITIALLY DUE TO THE DECREASED HEAT TRANSFER FROM THE REACTOR COOLANT SYSTEM. THE REACTOR COOLANT SVSTEA WILL REACH STEADY STATE HOT SHUTDOWN CONDITIONS WITH DECAY HEAT BEING REMOVED BY THE OPERAELE REACTOR COOLANT LOOP.

MALFUNCTION REMOVAL WILL RESET AND RESTORE THE LOCK 0UT RELAY TO NORMAL OPERATION.

PRAIRIE !$ LAND 4.13.1 RZACT08 COOLANT-AALF R 01 0$/it/t9 j ACCEPTANCE TECT PD0!!DURI Pa$l i TEST RI$ ULT 5

$TEP PANIL TAJ NUM!iR- $2D TAS NVM5CR PAN!L INIT D.R.

0000- FILENAME X49413 MALF RC01 RC RCP TRI#

0001 PCM IC09 YP INITIALIZE TO ICO? PLAht AT 100% 50WEP A

P ........

0002 PCM RCJ14 RC 47012-0101 C-1 ........_

47012-0!01 C-1 46255 C-1 INSERT MALF RC01A 11 RCP LOCKED OUT ALARM ACTUATEC, 11 RC LOOD LOW FLOW OR $<R OPEN ALARM ACTUATES, AND WHITE LAM 8 ILLUSINATES 47017-0301 0-1 F04030 PPC-ONE LOOP LOW FLOW OR RCP BKR OPEN RX TRIP ALARM-

-ACTUATESJ'A RX-TRIP - TUR3 TRIP-OCCUR $

41072 C-1 41121 C-1 E -- 11 RC LOOP AND RTD BYPASS LOOP FLOWS DECREASE TO ZERO IN APPROX 60 3ECONDS (REVERS!

PRAIR!! ISLAND A.13.1 RIACTOR C0CLANi+'ALF Rtoi 05/16/69 ACCESTANCE it$T PPO!!DJRt PA$f  ?

T!$T P.[$ULi; STEP PANEL TAG NUMEIR $!D 1A3 NU'k!R DANEL INIT D.R.

FL0h THRU LOOD 0 CUDS) 47012-050) C-1 RC RTD LOOPS Ttw.P PY8 LOW FLCw ALARM ACTUAft$

42042 C-1 4?059 C-1 11 RC LOOP COLD LES TEMP

[ OVA LIZIL WIT 4 HDT LES TE*P

(!'A 6L >!LTA T)I DECAY HEAT n!LL ?E *EF0/10 BY 12 *C LOCP/$S A

E ...... .

i 0003 C-1 4625$ AC 47:12-01 1 C-1 ,,,,,,,,

4625! C-1 PLACE 11 RCP CONTROL ALARM CLEA'$r WHITE LA*P SWITCH IN STOP DEEht*3:2!$

A ,,,,,,,,

B ........

l l

l

. _ ___ _ _ _ _ _ _ _ ~ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ .

PRA!RIE 2SLAND 4.1}.1 RLACTOR COOLANT-MALF DC01 35/i!/69 l l

ACCEPTANT! TEST PROCEDJRE PAGE 3 TEST RE$UL'S )

$TEP PANEL TAG NVMEER  ?!D TA3 NUwa!R PAN!L )

- INIT D.R.

0004 C-1 46257 #C ____....

C-1 40255 F. C

$ TART 11 RCP OL PUNF THEN 11 RCF EKR CLOSE! THEN ATTEMPT TO $ TART 11 RCP IMPEDIATELY LOCK OUT TRID$

A b ........

0305 PCM RC31A rC _______.

C-1 46255 PC REMOVE mal.f RC01A, RISIT 11 ACP $ T A *. T $

AND START 11 RCD a ........

l ........

0036 PCM RC013 RC ,,,,,..,

C-1 4e250 FC C-1 462f6 FC PERFORM STEPS =.13.1.1 EXP!CTED RESULTS S!P:LAR THRU 4.13.1.5 FOR MALF RC010 F04 12 RCD

PITC ANNUAL SIMUIATOR OPERABILITY TEST PROCEDURE TEST

SUMMARY

AND EVALUATION:

1. Evaluate data and complete a summary report for this test.

SIGNATURE /DATE

.s TEST APPROVAtt

1. The test results are approved and any recommended corrective actions have been entered into the Simulator Change process.

SIGNATURE /DATE e

MALFUNCTION TEST RC01 - REV O PAGE 2

l PITC ANNUAL SIMULATOR OPERADILITY TEST PROCEDURE MALFUNCTION TEST - COMPONENT COOLING WATER SYSTEM CC05 PROCEDURE APPROVAL: Sg71. ton 0 Prepared by ~

pprovedbys/2 Ik 16f ejc

" I V \s ' SIG /pATE OVERVIEW:

The purpose of this test is to monitor the control board response resulting from the insertion of a CCW System Piping Rupture malfunction. This test will compare expected response with simulator control board response. A satisfactory test will be confirmed if all responses are as expected and are within the bounds described in the malfunction cause and effects manual for a "CCW SYSTEM PIPING RUPTURE CC05".

EXPECTED R_ESULT

1. The malfunction will cause the system to respond as if a piping failure occurred at vent CC 39. This malfunction has a variable severity, the effects will depend on the severity. At low severities the surge tank level will decrease and automatic makeup will refill and attempt to maintain a level in the tank. At higher severities the tank level will not be maintained, system flows and pressures will decrease, and temperatures will increase. A severity of 100% equals 4000 gpm at 100 psig.

2. The effects of a loss of component cooling to related equipment will be; increased temperatures and possible loss of flow to them, when proper response is taken.

3. The malfunction can be removed and the system will return to normal operation.

4. This procedure will review the effects of related remote functions CC100 and CC101 for proper operation.

MALFUNCTION TEST CC05 - REV 1 PAGE 1

I J PITC ANNUAL SIMULATOR OPERABILITY TEST PROCEDURE 3- i

.l TEST STEPS

~

TEST DATE i i

1. ENTER SATAR TEST DATA REQUIRED FOR THIS TEST INTO THE 4

SATAR PC. TEST NUMBER FOR THIS TEST IS _014 ,0_q 001.

INITIAT,

2. SELECT IC-07 (6% POWER, BOC), RESET SIMULATOR TO IC-07 AND ALI4W THE SIMULATOR TO INITIALIZE.

WHEN THE READY LIGHT COMES ON, THE SIMULATOR /PC SHOULD BE READY FOR THE NEXT TEST ENTERED INTO THE SATAR PC. .

INITIAL

3. INSERT MALFUNCTION CC05, AT A SEVERITY OF 1% (ABOUT 40 GPM), ON A TIME DELAY OF ONE MINUTE. PLACE SIMULATOR IN RUN MODE AND CHECK PARAMETERS STABLE.

INITIAL i

4. MONITOR THE FOLI4 WING INDICATIONS FOR THE EXPECTED RESPONSEt CC SUMP HIGH LEVEL ALARM (47019:0603) ACTUATES.

11 CC SURGE TANK LEVEL DECREASES AT APPROXIMATELY 1 IN/ MIN ON INDICATOR 41007, AND ON ERCS 1L2703A.

11 CC SURGE TANK- LO LEVEL AIARM 47020:0602 ACTUATES WHEN LEVEL DECREASES TO -6 INCHES,-CV-31432 WILL ALSO OPEN AT THIS LEVEL.

LEVEL WILL INCREASE-TO O INCHES AND CV-31432 WILL

__ C I 4 S E .

INITIAL l

l' MALFUNCTION TEST CCOS - REV 1 PAGE 2

l PiTC ANNUAL SIMULATOR OPERABILITY TEST PROCEDURE .

5. (TESTING FOR REMOTE FUNCTICN CC100.) PLACE CS-46037 FOR 12 CC PUMP IN PULLOUT. USE CS-46032 TO CLOSE MV-32121. MONITOR THE FOLi.cWING INDICATIONS FOR THE EXPECTED RESPONSE:

12 COMPONENT COOLING WATER PUMP DISCHARGE HEADER 14W PRESSURE ALARM 47019 0402 ACTUATES.

12 CONTAINMENT SPRAY PUMP CC WATER LOW FLOW AIARM 47019 0402 ACTUATES.

12 SI PUMP CC WATER LOW FI4W AIARM 47018 0402 ACTUATES.

12 RHR PUMP CC WATER LOW FLOW ALARM 47016:0403 ACTUATES.

INITIAL

6. USE REMOTE CC100 TO CICSE MV-32266, CC TO RCP'S.

FIDW INDICATION 4127601 AND 4127701 WILL GO TO ZERO, COMPONENT COOLING WATER RCP ICOP 11 ISOLATION VALVE SHUT ALARM 47020:0403. RE-OPEN MV-32266 WITH REMOTE CC100.

INITIAL

7. OPEN UNIT 1 TO UNIT 2 CC CROSSCONNECT VALVES UCING REMOTE CC102. THE LEVEL DECREASE SHOULD SIDW TO APPROXIMATELY 0.5 INCHES PER MINUTE, AS INDICATED ON 41007, 41506 AND 1L2703A. THE 11 AND 21 SURGE TANK LEVEL ALARMS WILL ACTUATE AT -6 INCHES AND CLEAR ABOVE -6 INCHES (47020:0602 AND 47520:0606).

INITIAL

8. CLOSE THE UNIT 1 TO UNIT 2 CC CROSSCONNECTS USING REMOTE CC102. THEN INCREASE SEVERITY TO 2%.

1NITIAL

9. LEVEL IN 11 CC SURGE TANK (41007 AND 1L2703A)) WILL DECREASE FASTER DOWN TO -6 INCHES, AND WILL CONTINUE DOWN. MAKEUP FLOW IS LESS THAN RUPTUkE FLOW.

INITIAL MALFUNCTION TEST CC05 - REV 1 PAGE 3

[

1 PITC ANNUAL SIMULATOR OPERABILITY TEST PROCEDURO

10. 11 CC HEAT EXCHANGER OUTLET TLOW INCREAFES (41008-

, 03).

j' *INITIAN i.

l 11. INCREASE CC05 MALFUNCTION-SEVERITY TO 100%.

L INITIAL -

12, MONITOR.THE FOLLOWING INDICATIONS FOR THE EXPECTED 4 RESPONSE i .- 11 CC SURGE TANK LEVEL DECREASES RAPIDLY CAUSING LO i' j LO LEVEL ALAPM (47020-0103) TO ACTUATE.

I 11 CC HEAT EXCHANGER OUTLET FLOW INCREASES (41008-03),.

i CC HEADER PRESSURE DECREASES ' (41008-01 AND r 1P2608A), RESULTING IN AN AUTOMATIC START OF 12 CC F

" PUMP (46037) . 12-CC HEAT EXCHANGER FLOW (41009-03)

AND PRESSURE (41009-01 AND 1P02609A) INCREASE ONLY '

SLIGHTLY.

11 AND 12 CC PUMPS WILL APPEAR TO BE CAVITATING, AS INDICATED BY THEIR OSCILLATING FLOWS AND PRESSURES.

AFTER FIVE MINUTES THEY WILL TRIP ON OVERLOAD j- (46036,46037 AND 47020:0101,47020:0102). -

RCP BEARING AND STATOR TEMPERATURES INCREASE AS i

t INDICATED ON RECORDERS'42003 AND 42023.

CVCS LETDOWN-TEMPERATURE INCREASES (41053-02), AND-r TCV130 OPENS FULLY (43025-02). THE LETDOWN FIDW (41050) AND PRESSURE (41056) WILL BEGIN TO CYCLE AS THE LETDOWN LIQUID FLASHES TO STEAM.

b

- LETDOWN - F14W HIGH TEMPERATORE ALARM (4701510408)

ACTUATES.

i.

i. WASTE DISPOSAL BORON RECYCLE PANEL TROUBLE ALARM (4701510101) ACTUATES. ,

L AUXILIARY. BUILDING SUMP HI LEVEL ALAkM (47019 0503)

ACTUATES.

7NITIAL L i..

j- MALFUNCTION TEST CC05 - REV 1 PAGE 4 4

PJTC ,MINUAL StMULETOR OPERABILITY TEST PROCEDURE 13 FREEZE 'lHE SIMULATOR, AND THEN RESET TO IC-07 AND ALLOW ThiU SIMULATOR TO INITIALIZE.

INITIAL .

14. INSER! MALFUNCTION CC05 AT 10% SEVERITY ON A ONE MINUTE TIME DELAY. PLACE THE SIMULATOR IN THE RUN MODE AND OD1ERVE THE CC SYSTEM OPERATION. WHEN THE CC SURGE TANK LEVEL IS BELOW -10 INCHES, REMOVE TIIE MALFUNCTIO!C CC05. THE SYSTEM WILL RETURN TO NORMAL OPERALON.

INITIAL

15. (TESTING TOR REMOTE CC101.) START 12 CC PUMP USING CS-46037, STOP 11 CC PUMP WIT){ CS-46036, AND PLACE IN PUL14UT. CLOSE MV-32120 WITH CS-46029. MONITOR THE FOLLOWING INDICATIONS FOR THE EXPECTED RESPONSE:

11 COMPONENT COOLING WATER PUMP DISCHARGE 14W PRESSURE ALARM 47020t0402 ACTUATES.

11 CONTAINMENT SPRAY PUMP CC WATER LOW FLOW ALARM 47019:0401 ACTUATES.

11 SI PUMP CC WATER LOW FLOW ALARM 4701810401 ACTUATES.

11 RHR PUMP CC WATER LOW F14W ALARM 4701610402 ACTUATES.

INIT.iAL

16. USE REMOTE CC101 *O CLOSE MV-32266, CC FLOW TO RCP'S, FLOW INDICATION 4127601 AND 4127701 WILL GO TO ZERO, AND COMPONENT COOLING WATER RCP LOOP 32 ISOLATION VALVE SHUT ALARM 47020:0404 ACTUATES. RE-OPEN MV-32266 WITH REMOTE CC101, INDICATED FLOW WILL RETURN TO NORMAL.

INITIAL MALFUNCTION TEST CC05 - REV 1 PAGE 5 I,

_._.__._____ .._._____-~-._m. . _ _ _ _ . . . _ . __ m..em _ - _ _-_a__ m-.____-__a-o.-_-- h

1 l PITC ANNUAL SIMULATOR OPERABILITY TEST PROCEDUPJ, TEST

SUMMARY

AND EVALUATION:

1. Evaluate data and complete a summary report for this test.

SIGHATURE/DATE 7pST APPROVAL:

1. The test results are approved and any recommended correctivo Change prococs.

actions have been ontored into the Simulator SIGNATURE /DAC MALFUNCTION TEST CC05 - RZy 1 I PAGE 6

Tost' Point F1100 Dick Filt Symbol (Array) Description

-01400000 CCPHDR11 (000,000,000) HFt. DER 11 PRESSURE 01400000 CCPHDR12 (000,000,000) HEADER 12 PRESSURE 01400000- - CC P1A13 (000,000,000) 11 CCP BREAKER STATUS 01400000 CCIP1A14 (000,000,000'l 11 CCP L.O. TRIP 01400000 CC:P2A13 (000,000,000 ) 12 OCP BREAKER STATUS 01400000 CC P2A14 (000,000,000 1 12 CCP L.O. TRIP ,

01400000 CC SV035 (000,000,000) CV31432 COMMAND STATUS 01400000 CCF0614A (000,000,000) 11 SL WTR HX CC OUT F 0140000C CCF0615A 01400000 CCF0617A (000,000,000))

000,000,000 11'LTDN HX CC'OUT FLOW 11 RCP CC OUTLET ' FLOW 01400000 CCF0618A 000,000,000!I 12 RCP CC OUTLET FLOW 01400000 CCFMF05 000,000,000 01400000 CCFMU 000,000,000)l LEAK MX-UP FLOW-DUE TO MJLF05 FROM RX MU 0 CCL2703A 000,000,000

,D,1400000 1401000 CCL2703A 11-CC SURGE TANK LEVEL 000,000,000 11 CC SURGE TANK LEVEL 01401000 CCISV035 000,000,000 CV31432 COMMAND STATUS 01401000 CCFMU 000,000,000 MK-UP FROM RX MU

?

4 y ,,p.. 1w - - '

i PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1990 APPENDIX 8 MALFUNCTION TESTING ABSTRACT

- The following list of malfunction tests were completed between January 1,1989 and February 1,1991. For all tests with discrete options (type D) all options were 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 Peview Panel listed in Appendix 4.

All tests passed .vith the exception of the following:

Trst NO. TITI E DR#

EGil EMERGENCY DIESEL GENERA 1DR IDAD LIMIT FAILURE 90D-184 PCO3 ERCS ALARM DISPLAY FAILURE 901-082 PC04 ERCS SAS DISPI iY FAILURE 901-082 PCOs - ERCS CORI1tOL ROOM PRIKrER FAILURE 901-082 ED15 DEGRADED GRID VOLTAGE 90D-181 SG03 STEAM GENERA 1DR BIDWDOWN CONTROL VLV FAIL 3 90D-200

'IEll COMPLETE TURBINE TRIP FAILURE 90D-192 C1.06 SFORDS COOLING WNIT!R SUPPLY PIPING RUI'IURE 90D-095 EDIO LOSS OF 480 V llUS 91D-016 RCll IDSS OF COOLANT ACCIDENT - RTD llYPASS LOOP 91D-028 RX208 AUCPIONEERED TAVG OVERRIDE 91D-035

• 1004 TURBINE CONTROL VALVE FAILS OPEN 90D-227 VC201 VC 111MPERATURE TRANSMITil!R 91D-015 RX300 PRESSURIZER PORV SirtTOIKrS 911-001 FWO3 - IDSS OF CONDENSJR VACUUM 90D-238 The following simulator certification tests have not been completed due to waiting for additional information on expected plant response:

TEST '

NO. TITI.E MS07 MOISTURE SEPARATOR - REllEATER TUDE LEAK MS10 MAIN S*IEAM LINE IIREAK ON COMMON AFW SUPPLY I,1NE TUO! LOSS OF TURUINE LUBE OIL SUPPLY CCat CC SUPPLY VALVE TO RCP FAILS CIDSED VC05 STUCK OPEN CilARGING PUMP RELIEF VALVE RD07 DROPPED ROD EGOS GENERATOR VOLTAGE REGULATOR FAlt,URE RCO2 REACIUR COOLANT PUMP LOCKED RCrIUR pitc/ reports Page 1 l

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1990 APPENDIX 8 b1ALFUNCTION TESTING ABSTRACTS The following simulator malfunctions were decided by the Simulator Design Review Committee to be excluded from the certified malfunctions since these malfunctions were designed for Emergency Plan drill use and are not realistic. Note that other fuel failure malfunctions which give realistic plant response are available:

CR02 Gross Fuel Failure CR04 Fuel Cladding Failure All tests which failed will be corrected and retested by 12/91. All tests waiting for additional plant response information will be completed by 12/91, B1ALFUNCTION TESTING Tent Approved Number Title Tme Date Comments Variable Setpointa E0200 UO TEMP XIMR SO 08/20/90 IN200 COND FLW KrMR SO 07/24/90 FW201 CDSR llW XTMR SO 07/24/90 FW202 IIA IN LEVEL XIMR SO 07/24/90-IW203 12A FW LEVEL XfMR SO 07/24/90 FW204 till FW LEVEL XTMR SO 07/24/90 FW205 12H FW LEVEL XFMR SO 07/24/90 FW206 13A FW IEVEL XTMR SO 07/24/90 FW207 13D FW IIVEL XFMR SO 07/24/90 IN208 ISA FW LEVEL ATMR SO 07/24/90 FW209 ISH FW LEVEL XfMR SO 07/24/00 MS200 IB MS LEVEL XfMR SO 08/20/90 MS201. 211 MS LilVEL KrMR SO 08/20/90 MS202 IA MS LEVEL XrMR SO 07/24/90 MS203 2A MS LEVEL KrMR SO 07/24/90 MS201 111 RilDT Lf! VEL XTMR SO 08/20/90-MS205 2B RilDT LEVEL XfMR SO 08/20/90 MS206 1 A RilDT LEVEL XTMR SO 08/20/90 MS207 2A RilDT 1EVEL XFMR SO 08/20/90 MS208 ID RilDT LEVEL XIMR SO 08/20/90 MS209 211 RtiOT LEVEL XrMR SO 08/20/90 MS210 1 A RilDT LEVEL XTMR SO 08/20/90 MS211 2A RilDT LEVEL XfMR SO 08/20/90 Ril:00 Ril FLOW XfMR SO 07/24/90 pitchepotts Page 2

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT - i 1990 APPENDIX 8 Test Approved Numl>er Title Tyne Date Comments RX200 RCS PRESSURE XTMR SO 01/08/91 RX201 RCS PRESSURE XFMR SO 01/08/91 RX202 RCS PRESSURE XTMR EO 01/08/91 RX203 RCS PRESSURE XINR 50 01/08/91 RX204 PRZR LVL XrMR SO 01/25/91 RX205 PRZR LYL XTMR SO 01/25/91 RX206 SO LEVEL XIMR SO 01/08/91 RX207 SO LEVEL XrMR SO 01/08/91 RX208 AUCTIONEERED TAyo SO 01/21/91 FAILED RX209 IM 11DW XFMR SO 01/08/91 RX210- IV FLOW XrMR SO 01/08/91 RX211 FW FLOW XfMR SO 01/08/91 RX212 FW 110W XTMR SO 01/08/91

- RX213 11/12 MS PRESSURE XTMR SO 01/08/91 RX214 11 MS PRESSURE XTMR SO 01/08/91 RX215 11 MS PRESSURE XIMR SO 01/08/91 RX216 12 MS PRESSURE XTMR SO 01/08/91 RX217 12 MS PRESSURE XTMR SO 01/08/91 RX219 11 MS FIDW KrMR SO 01/08/91 RX220 11 MS IIDW XTMR SO 01/08/91 RX221 12 MS FLOW XTMR SO 01/08/91

. RX222 12 MS 11DW XTMR SO 01/08/91 RX223 11 STM FLOW KrMR SO 01/08/91 RX224 12 STM FIDW XTMR SO 01/08/91 RX225 11 FEED IIDW XTMR SO 01/08/91 RX226 12 FEED FIDW XINR SO -01/08/91 RX227 11 FEED TEMP XFIR SO 01/08/91 RX228 12 FEED TEMP XITR SO 01/08/91

. RX229 FW llDR PRESSURE XTMR SO 01/08/91

! RX230 IN IIDR PRESSURE XTMR SO 01/08/91 RX231 11 SG WR LEVEL XTMR SO 01/25/91 RX232 12 SG WR LEVEL XTMR SO 01/25/91 VC200 VC PRESSURE XINR SO 01/08/91 VC201- VC TEMPERATURE XTMR SO 01/28/91 FAILED VC202 VC FLOW XIMR SO 01/25/91 VC203 VC 110W XrMR SO 01/25/91 Vertable Setpoints CII300- CNhrr III/111 til PRESS VS 07/24/90 MS300 SO SAFETY VALVES VS 01/21/91 pitc/ reports .Page 3

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT

1990 APPFEDIX 8 Test Approved Numlier Title Type Date Comments N1300 IR PWR AHOVE P-6 VS 01/25/91 N1302 PR PWR ADOVE P-8 VS 09/25/90 N1306 PR PWR ADOVE P-9 VS 09/25/9C N1310 PR PWR AllOVE P-10 VS 09/25/90 N1316 IR III FLUX TRIP VS 09/25/90 N1318 PR LD RNO 111 FLUX TRIP VS 09/25/90 N1322 PR 111 RNO 111 FLUX TRIP /POS RATE TRIP / VS 01/28/91 NEO RA'IT! 'IRIP RC300 PRZR SAFETY VS 01/25/91 RP300 P-7 TURD PRESS VS 01/25/91 RP302 AUTO ROD WITIIDRAWAL lllDCK P-2 VS 08/20/90

. RP303 IlUS 11/12 UV TRIP VS 08/20/90 RP305 IlUS 11/12 UF 'ITIIP VS- 08/20/90 RP313 PRZR LD PRESS TRIP /SI VS. 01/25/91 RP323 PRZR III LVL TRIP VS 09/25/90 RP326 SO IDLD 1,VL TRIP VS 09/25/90

- RP340 ' IDID TAVO STM IN 1S011111 SYM FIDW VS 09/25/90

' RP348 : 50 Ill-III STM FIDW VS 09/25/90 RP352 SO LotD STM PRESS SI VS 09/25/90 RX300 PRZR 111 PRESS PCV VS. .01/15/91 FAILED RX302 STM DUMP 111/111111 TAVO VS 01/23/91 RX305 MASTER PRZR PRESS CONT SETPOINT VS 01/25/91

'10300 _INIT TURI) CV POS VS 01/03/91 Malfunctions Component Cooling Sprim CC01 COMPONHKr COOLING WATER PUMP TRIP D 03/02/90

- CCO2. iCOMPONEKr COOLING PUMP FAILS 'IU D 03/12/90 START ALTIDMATICALLY CCat COMPONENT COOLINO WATT!R SUPPLY VALVE D IIOLD TO RCP FAILS CIDSED CC05 COMPONENT COOLING WATER SYSTEM V 06/06/90 PIPING RUI'ITJRE CC06 CCW VALVE 7 ' URE TO OPEN RIIR llEAT

, D 03/03/90 EXCIIANOT - JTO ON PUMP START CC08 COMPONENf COOLING SURGE TANK ALTID D 05/09/90 MAKEUP FAILURE CC09 SEAL WATER llEAT EXCIIANGER LEAK V 05/09/90 l

1 pitdreports Page 4

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT I 1990 APPENDIX 8 Test Approved Number Title Tme Date Comments Containment /1[VAC System C1101 CONTAINMilNT PRESSURE 'IRANSMITTER V 03/02/90 Fall,URE Cooling Water System CIDI COOL,1NO WATER PUMP D Fl/02/90 CIE2 DIESEL COOLING WATER PUMP FAILS TO D 0 itD100 START AlTIDMATICA11Y CID3 121 COOLINO WATER PUMP FAILS TO START D 03/02/90 AlTIDMATICAILY CIAl DIESEL COOLING WATER PUMP TRIP D 03/02/90 CID6 SAFEOUARDS COOLING WATER SUPPLY V 06/06/90 FAILED PIPING RUlvrURE CLO7 COOT.ING WATER SYSTEM TURIIINE IlUILDING V 06/06/90 PIPE RUI'rURE CID8 COOLING WATl!R LEAK INSIDE CONTAINMENT V 06/06/90 Re~ctor Gre System CR01 FUEL CLADDING FAILURE V CR03 REACIDR COOLANT SYSTEM CRUD BURST V Containment Spray System CS01 CONTAINMENT SPRAY PUMP TRIP D 03/02/90 CS02 CAUSTIC ADDITION VALVE FAILURE TO D 03/02/90 OPEN IN AlTIDMATIC CS03 CONTAINMENT SPRAY PUMP FAILS TO D 03/02/90 START AUTOMATICALLY Circulating Water System C%U1 CONDENSER TUBE LEAK V TO Bli DELE'IT!D CWU2 CIRCULATING WATER PUMP TRIP D 01/31/91 C%U3 CIRCULATING WATER PUMP UEARING D 05/09/90 FAILURE CWO4 CONDENSER TULLES PLUGOED V 06/06/90 CWO5 CONDENSER TUBE RUlvrURE V 06/06/90 CWO6 TRAVELING SCREEN llLOCKAGE ON V 06/06/90 APPROACil CANAL C%U7 CONDENSUR PIT FIDOD V 06/06/90 pite/ reports Page 5

l PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1990 APPENDIX 8 Tes! Approved Number Title Tme Date Comments Hectrical INstribution System ED01 LDSS OF OFFSITl! PO%T!R D 09/25/90

. ED03 IDSS OF OFFSITU PO%PR D 09/25/90 I!Dc4 FAULT IN UNIT 1 M TRANSFORMER-AUTO D 09/25/90  ;

111ANSFER 12D05 FAULT IN UNIT 1 M TRANSIORMER-WITil D 09/25/90 DELAYED TRANSf11R

. I!D06 FAULT IN UNIT SUllSTATION TRANSFORMI!R D 10/16/90 ED07 IDSS OF 125 VDC IlUS D 01/21/91 ED08 IDSS OF 120 VAC INSTRUMENT IlUS D 01/28/91 ED09 IDSS OF 4160V DUS D 09/25/90 ED10 IDSS OF 480 VAC 11US D 01/21/91 FAILED ED11 11US 15 IDAD RI3IUCTION-RES1DRATION V 10/16/90 SEQUENCE TIMER FAILURE ED12 -- I1US 16 LDAD REJEC110N-RUS'lORATION V 10/16/90 SEQUENCE TIMER FAILURE ED13 VOLTAGE RESTORING SCllEME SEOUIINCER D 10/16/90 FAILURt!

BD14' ' IDSS OF ALL AC D 10/16/90 ED15 DEGRADHD ORID VOLTAGE .V 10/16/90 FAILED ED16 Dl!ORADHD ORID IllEQUENCY V 10/16/90 Dectrical Generation System E001 GENERATOR OUTPUT IIREAKER FAILS TO D 06/06/90 OPEN FOLIDWING TURDINil TRIP 11002 IDSS GENERA 1DR IIYDROGEN COOLING D 07/24/90-E003 IDSS OF OFFSITU POWER D 08/20/90.

E005 GENERATOR VOLTAOll REOULATOR FAILURE -V IIOLD E006 OENERATOR FAUI.T D 06/06/90 E007. GENERA 1DR LDSS OF EXCITATION D 06/06/90 0008 -IDSS OF EMBROUNCY DIUSUL GENERATOR D 06/06/90 0009 EMBROUNCY DIESEL GENERATOR FAILS D 07/24/90 10 START

. B010 EMBROENCY DIESEL GENERATOR OUTPlTT D 08/20/90 EREAKER Fall,S OPEN EOll EMBROUNCY DIESI!L OENERATOR LOAD V 09/25/90 FAILED IJMIT FAILURE i-

' pite/ reports Page 6

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

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1990 l

APPENDIX 8 Test Approved Nun.ber Title Tyne Date Comments Condemate and Fredwater System TM01 CONDENSA1T! PUMP TRIP D 03/02/90 FWO2 13 CONDENSATE PUMP FAILS 10 START D 03/02/90 AU1DMATICA11Y IM03 ' IDSS OF CONDENSER VACUUM V 06/06/90 FAILED IMOS - CONDENSATE PUMP RECIRC VALVE FAILS D 08/20/90 OPl!N FWD 6 - CONDENSATE PUMP RECIRC VALVE FAILS D 08/20/90 CIDS!!D FWD 7 - CONDENSATE IlOlWE!L MAKUUP VAI.VE D 03/02/90 FAILS OPEN IN08 CONDI!NSER ilar%Till MAKEUP VALVE D 06/06/90 FAILS C1DSI!D 17 09 LP FEEDWATER lil!ATER llYPASS VALVE D 06/06/90 FAILS OPEN FW10 CONDENSER llOTWELL LEVI!L TRANSMITIT3R D 10/16/90 - '

FAILS 1110l! .

FWil CONDENSI3R 110TWHIL TRANSMrFTER D 01/21/91 FAILS IDW ITI's MAIN IT!!DWATER PUMP TRIP D 06/06/90 IV15 FEEDWNIT!R llP llEATER 111011 LEVEL D 04/12/90

'f W16 FUEDWATER LP llEATER !!!Oli LEVEL D 04/12/90 FW17 ITEDWATER 11P IIBATER LEAK V 07/24/90

- FW18 Fi!EDWATER LP llBATER LEAK V 01/15/91 IMl9 FUEDWATER SYSTEM RUPTURI3 INSIDE V -01/08/91

. CONTAINMENT IV20 FEEDWATER SYSTEM LEAKAGE INSIDE V 09/25/90 CONTAINMENT FW21- Fl!EDWATER SYSTEM RUI'TURE INSIDE V --

01/08/91

. CONTAINMENT UPSTREAM OF CllECK VALVE IM22 ' ITEDWN111R SYSTEM RUPTURE OIJTSIDE V 01/15/91 CONTAINMENT FW23 FEEDWATER SYSTEM LEAKAGE OUTSIDE V 09/25/90 l CONTAINMUKr IT24 ITEDWATER PUMP COMMON DISCliAROB V 01/21/91 IIEADER RUI'rURE IV25 . FEEDWATER FIDW-CONITIOL VALVE FAILS D 07/24/90 10 CLOSE ON FW ISOLATION SIONAL Iv26 ITEDWATER II.OW CONTROL val,VB FAILS V 01/31/91 OPEN

-1727 ~ FEEDWATT!R FLOW CONTROL VALVE FAILS - D 09/25/90 CIOSED FW28 - !! EATER DRAIN PUMP TRIP D 03/02/90 IM29 .Illl/.*ll!R DRAIN TANK LEVEL TRANSMITTER D 09/25/90 FAILS 1I1011

pitcIreports Page 7 l

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1990 APPENDIX 8 Test Approved Number Title Tme Date Comments FW30 llEATl!R DRAIN TANK LEVEL TRANSMrFil!R D 09/25/90 FAILS IDW FW31 IIEA'll!R DRAIN PUMP FAILS TO MINIMUM D 09/25/90 ,

Iv32 AUXILIARY ITEDWA*I1!R PUMP TRIP, MOTOR D 03/02/90 FW33 AUXILIARY FilEDWAh!R PUMP TRIP, TURlllNE D 03/02/90 FW34 AUXILIARY FEEDWATER PUMP FAILS TO D 03/02/90 START AtrIOMATICALLY Iv35 INADEOUATE CONDENSAT11 TO AUXILIARY V 01/15/90 ITEDWATER TUMP SUCTION FW36 . AUXILIARY FBI!DWAU!R DISCllAROB LINE V 01/21/91 RUI'rURI! INSIDE CONTAINMEKr TV37 AUXILIARY FEEDWATER DISCilAKOU LINI3 V 01/08/91 RUI'IURI! OtfrSIDE CONTAINMENT FW38 AUXILIARY FEEDWATER CONTROL val.VU D 03/02/90 Fall IN POSITION FW39 ITEDWAR!R LINE RUI'rURE UPSTREAM OF V 09/25/90 FW REO VALVES FW40 -COMMON FUEDWATER PUMP SUCTION 1.INil V 01/28/91 IllDCKAGE Iv41 ITI!DWATER FLOW CONTROL VAI.VE LEAKAO!! V 01/15/91 Compressed Air System IA01 IDSS OF SERVICE AIR llEADER V 10/16/90 1A02 LOSS OF INSTRUMEKr AIR llEADER V 01/28/91 IA03 LOSS OF AIR COMPRESSOR -D 03/02/90 Main Steam System

- MS01 - MAIN STEAM LINE RUI'FURE INSIDil V -01/21/91 CONTAINMENT UPSTREAM OF MSIV MS02 - MAIN STEAM LINE RUI'rURI! OUTSIDE V 01/15/91 CONTAINMEKr UPS11WAM OF MSIV MS03 MAIN STEAM LINE RUI'rURE OtTTSIDE V 09/25/90 CONTAINMEKr DOWNSTREAM OF MSIV MSN MAIN STEAM LINE L1!AK V 09/25/90 MSOS MAIN STEAM SAFLTY VALVE STICKS OPEN D 05/09/90 MS06 = OLAND SEAL STEAM REOULATING VALVE D 09/25/90 FAILS CIDSED MS07 MOISTURE SEPARATOR - REllEATER V llOLD tulle LEAK M508 MOISTURE SEPARATOR - RHilEATER RELIEF D 01/08/91 VALVES FAILURE 1

pitc/ reports Page 8 l

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT i 1990 APPENDIX 8 Test Approved Number Title Type Date Comments MSO9 MAIN STT!AM LINE LEAK INSIDE V 01/21/91 CONTAINMl!NT MS10 MAIN STEAM LINE IIREAK ON COMMON V IIOLD SUPPLY LINE TO AFW MSit STEAM DUMP VALVE FAILS IN POStr!ON D 01/31/91 Nuclear instrumentation System N101 INCORR11CT SOURCE RANGE CilANNEL V 05/09/90 RESPONSB N102 SOURCE RANGE CilANNEL SPIKES D 05/09/90 N103 IN111RMEDIATE RANGE CilANNEL IMPROPER V 05/09/90 RIISPONSB NIGl INI11RMEDIATE RANGE Cl! ANNE!IIMPROPER V 01/21/91 COMPENSATION N105 IMPROPER POWER CIIANNEL RESPONSE V 10/16/90 NIO6 l'OWER RANGE UPPER CilANNEL IMPROPER V 01/21/91

RESPONSE

N107' POWER RANGE LOWER CllANNEL IMPROPER V 01/21/91 RRESPONSE Plant l'rocess Computer System PC01 ERCS CPU FAILURE D 09/25/90 PCO2 URCS DATA CONCENTRATOR LINK TO D 09/25/90 FAILEDfro El3 DELETT!D CPU FAILURE PC03 ERCS ALRM DISPLAY FAILURE D 09/25/90 FAILED PCO's URCS SAS-DISPLAY FAILURE D 09/25/90 FAILED PCOS ERCS CON!1tOL ROOM PRINTER FAILURE D 09/25/90 FAILED PC06 ERCS DISK A FAILURE D G4/12/90 '10 EU DELETED IGactor Coolant System

RC01 REACTOR COOLANT PUMP TRIP D 10/16/90

~ RCO2 REACTOR COO! ANT PUMP IDCKED ROTOR D I101 D

. RC03 REACIDR COO! ANT PUMP SilAIT S!! EAR D 08/20/90 s RCal ' REACTOR COOLANT PUMP S!!AIT SilEAR D- 10/16/90 RC05 REACTOR COO! ANT PUMP EEARING FAILURE V 10/25/90-RC06 LDSS OF COOLANT ACCIDENT - IIOT LEO V 01/28/91 RC07 LOSS OF COOIANT ACCIDI!NT - COLD LEO - V 01/15/91 RCP SUCTION RC08 . LOSS OF COOLANT ACCIDENT - COLD LEO - V 01/28/91 RCP DISCilAROB pitc/ reports Page 9

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1990 APPENDIX 8

- Test Approved Numlier Title Tme Date - Comments RC09 LDSS OF COOLANT ACCIDENT, PRESSURIZER V 01/25/91 STEAM SPACI!

RC10 IDSS OF COO! ANT ACCIDENT PRESSURIZER V 01/21/91 WATER SPACE .

RCll IDSS OF COOLANT ACCIDENT-RTD IlYPASS V 01/21/91 FAILED IDOP COLD LEO MANIFOLD RCl2 IDSS OF COOIANT ACCIDENT-RTD DYPASS V 01/15/91 IDOP RETURN LEO PIPING RCl3 IDSS OF COOIANT ACCIDENT - REACIUR V 01/31/91 IIEAD VENT RCl4 - REACIDR COOLANT SYSTEM LEAKS V 01/21/91

' RC15 REACTOR COOLANT SYSTEM LEAKS V 01/15/91

_ RC16 - PRESSURIZER POWER OPERATED REIIEF D 01/21/91 u VALVE FAILS CIDSED RC17 PRESSURIZER 111011 OAS CONCENTRATION V 01/15/91 IN VAPOR SPACE RC18 PRESSURIZER SAFETY VALVE RC-10-1 D 12/05/90 FAILS OPEN RC19 ' PRESSURIZER SAFETY VALVE SEAT I EAKS V 12/05/90 RC20 REACIDR COOLAKr PUMP OIL LEAK, UPPER D 01/21/91 RESERVOIR RC21 REACIDR VESSEL O-RING LEAKAGE D 01/28/91 RC22 PRESSURIZER POWER OPERATED RELIEF V 10/25/90

(

L VALVE LEAKAOIl RC23 S111AM OENERATOR TUBES PLUGOED V 12/05/90 RC24 PRESSURIZER SPRAY VALVE FAILS -D 10/25/90 IN POStrlON Control Rod Drive System

~

! - RD01 CONTROILING ROD EANK FAILS TO MOVE D '03/02/90

-IN MANUAL RD02 CONTRO111NO ROD BANK FAIIS TO MOVE D 03/02/90 IN AUTO RD03 - UNCONTROLil!D CONrtNUOUS ROD V/fril- D 03/02/90 DRAWAL OF CONTROILING llANK

.RDal UNCONTROLLED CONTINUOUS ROD D 03/03/90-INSERTION OF CONTROLLING EANK RDOS CONTROL ROD MISALIONMENT D 01/21/91 RD06 STUCK ROD D 03/02/90 RD07 DROPPED ROD D IIOLD

' RD08 CONTROL ROD O-3 EJECTED D 01/21/91

~

RD09 ROD POSITION INDICATION FAILS D 03/02/90-RD10 INCORRECT ROD SPEED D 03/02/90 pitc/ reports Page 10 l .

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT i

1990 APPENDIX 8 Test Approved Number .

Title Type Date Comment s Residual lleat Removal System Ritol Rl!51 DUAL llEAT Ri!MOVAL PUMP TRIP D 03/02/90 R1102 RI'SIDUAI, !! EAT REMOVAL PUMP FAILS 'lO D 03/02190 START AtrIDMATICA11Y 111103 Ri!R llHAT EXCilANGER END lil!!L LEAKAGl! V 08/20/90 10 ATMOSPl!!!Rl!

Ril04 RiiR lil!AT IIXCilANGER llYPASS VALVE D 08/20/90 Fall,S OPl!N Ril05 ItllR llEAT llXCilANGER llYPASS VALVE D 08/20/90 Fall,S CIDS!!D Ril06 RECIRCU!ATION SUMP SUCTION 1,1N!!S V 08/20/90 I!LOCKUD 111107 RilR SYSTEM LEAKAGU V 10/16/90 R1108 RilR PUMP SEAL Fall,URH D 08/20/90 Ril09 RHSIDUAL llEAT RI!MOVAl, RELIEF VA1,VH D 08/20/90 FAILUltU Reactor l'rocerion System RP01 Rl! ACTOR TRIP D 01/08/91 IIP 02 FA!LUki! OF AUTOMATIC REACIUR TRIPS D 08/20/90 RP03 FAILURll OF SAFE'IY SYSTEMS 'ID ACTUATE D 01/25/91 RPGl INADVER'ITINr ACTUATION OF Tile SAFirlY D 01/08/91 INJECTION SYSTEM RP05 FAILURE OF CONTAINMENT ISOl ATION D 01/25/91 Pl! ASH A TO ACTUA'll!

ItP06 FAILURH OF MSIV'S 'lU ISOLATI! D 01/08/91 RI'07 MECilANICAL Fall.URt! OF REACIDR TitIP D 01/08/91 IlltEAKliRS RP08 FAILURE OF SAFilOUARDS ACTUATION D 01/25/90 Reactor Control System RX01 PRl!SSURIZER SPRAY VALVH FAILS OPEN V 03/02/90 RXD2 PRESSURIZLIR SPRAY VALVES PCV-431 D 03/02/90 A & 11 Fall C1.OS!!D RX03 PRESSURIZER IIBATERS FAIL ON D 03/02/90 RXat PRESSURIZult !! HATERS Fall, OFF (All) D 03/02/90 RXD5 llHACIUll COOLANT 100P TH TRANSMITrHR D 03/02/90 FAILS 111011 RXD6 REACTOR COOLANT IDOP TH 'DIANSMEITER D 03/02/90 Fall S 1,0W pite/ reports Page 11

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT l

1990 APPENDlX 8 Test Approved Number Title Tme Date Comments RXO7 REAcrOR COOIANT Tc TRANSMrFI11R D 03/02/90 falls 111011 RXO8 RI!ACIOR COOIANT IDOP TC TRANSMITil!R D 03/02/90 FAILS LDW RXO9 PRESSURIZi!R LI!VI!L NARROW RANGE D 04/12/90 TilANSMITil!R FAILS 1110 11 RX10 PRESSURIZER I.UVEL NARROW RANGE D Gl/12/90 TRANSMrITER FAILS LDW RX11 PRESSURIZER PRESSURE TRANSMrITER D 01/21/91 l' AILS 111011 RX12 PRl!SSURIZi!R PRESSURE TRANSMITI11R D 01/21/91 Fall.S IDW RX13 REACIDR COOLANT SYS'ITiM WIDE RANGE D 04/12/90 PRl!SSURI!'IRANSMFITER FAILS 111 0 11 RX14 REACTOR COOLANT SYSTEM WIDE RANGE D al/12/90 PRESSUR1! TRANSMITrl!R Fall.S IDW RXt5 STl!AM GEN 1!RAIDR LEVI!L TRANS- D 03/02/90 MITTER FAILS 1110 11 RX16 STEAM GENI!RA'lDR LEVI!L TRANS- D 03/02/90 MrlTER FAILS IDW RX17 STIIAM G11NERATOR PRf!SSURE TRANS- D 03/02/90 MITil!R FAILS 111011 RX18 STI!AM GIINERATOR PRESSUltI! TRANS- D 03/02/90 MITTER FAILS IDW RX19 MAIN S'11!AM LINE STEAM FIDW TRANS- D 03/02/90 MITTER FAILS 1110 11 RX20 MAIN STEAM l.INE STEAM FIDW TRANS- D 03/02/90 MITIT!R Fall.S IDW RX21 MAIN STEAM IIEADER PRESSURE TRANS- V nt/12/90 MITTER FAILURI!

RX22 FEEDWATER CONTRO1111R OltrPUT FAILURE V nt/12/90 RX23 FUEDWN111R LINE FIDW TRANSMrFT11R D 03/02/90 Fall.S 111011 RX24 FEEDWATI!R LINE FIDW TRANSMrrl11R D 03/02/90 FAII,5 LOW RX25 TURIllNE FIRST STAGli PRESSURE TRANS D 03/02/90 MITTI!R FAILS 1110 11 RX26 TURlilNU FIRST STAGE PRESSURE TRANS- D 03/02/90 MrfrER Fall.S IDW RX27 S'111 GEN FEEDWATER INI.ET 111MPI!RATl)Rll D 03/02/90 TRANSMITTER Fall.S 111011 pitc/ reports Page 12

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PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1990 APPENDIX 8 Tes! Approved -

Number Title Tme Date Comments RX28 STM GEN FEEDWATER INLET TEMPERATURE D 03/02/90

• IRANSMITI1!R FA!!3 II)W RX29 FEEDWATTIR I!EADER PRESSUR!l D 03/02/90

'IRANSMITTER FAILS 111 0 11 RX30 FEEDWA11!R IIEADER PRESSURE D 03/02/90 TRANSMITTER FAILS IDW

- RX31 S111AM OENERAIDR WIDE RANOB LEVEL D 03/02/90 1RANSMITI11R FAILS 1110 11 RX32 Sil!AM GENERATOR WIDE RANGE LEVEL D 03/02/90 1RANSMITTER FAILS LOW RX33 STEAM OENERATOR FEEDWATER COf(IROL D 03/02/90 SYSTEM FAILS TO MANUAL RX34 ADFCS MAIN 11.OW CO?(IROL VALVE OUTPlTT D 03/02/90 CARD FAILIIRE RX35 ADFCS BYPASS FLOW COffrROL VALVE D Gl/12/90 OLTTPLTF CALD FAILURE Steam Generator System SOO! STEAM OENERATOR TUBE LEAK V 01/28/91 SOO2 STEAM GENERATOR TUBE RUI'rURE V 01/28/91 SOO3 STEAM OENERATOR BLOWDOWN COffrROL D 10/25/90 FAILED VALVE FAILS OPEN Safety injection System S101 IK7Fil 110RIC ACID TANK VALVES FAIL D 10/25/90

'ID OPEN IN AUTO S102' SI IDOP A COLD LEO INJ CilECK VALVE D 10/25/90 FAILURE S103 IlORIC ACID TANK VALVII FAILS TO CLOSE ON D 10/25/90 LOW-LOW LEVEL IN Tile PRESELECTED IK)RIC ACID TANK IN ALTID Slat SAFETY INJECTION PUMP TRIPS D 03/02/90 SIO5 SAFLTY INJECrlON PUMP FAILS TO START D 03/02/90 AUTOMATICA11Y S106 Si isCCUMULATOR LEAKAGE D 10/25/90 S107 SI ACCUMULA1DR CilECK VALVE LEAKAGE D 10/25/90 SIO8 St ACCUMULAIDR RELIEF VALVE LEAKAGE D 10/25/90 SIO9- SI COLD Ll!O INJ LINE RUlvrURE INSIDE OF V 01/25/91 Tile ANNULUS

- pite/ reports Page 13

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1990.

APPENDIX 8 Test Approved Number Title Tme - Date Cornment s Turbine Control System 1C01 TURillNE STOP VALVil FAILS 'ID CIDSB WIIEN D 03/02/90 RllOUIRED 1C02 TURillNE STOP VALVE FAILS CIDSED D 03/02/90 TCO3 TURilINE CONIROL SYSTEM CYCLING OUTPUT V 01/15/91 1CGI TURIllNU CONTROL VALVE FAILS OPEN - D 01/25/91 FAILED 1005 TURillNE CORIROL VALVE FAILS CIDSED D 10/25/90 1C06 REACIDR PROTECrlON SYSTEM FAILS TO D 03/02/90 7 TRIP TURIl!NU TC07 TURIl! Nil CONTROL INIT!RCEPT VALVE D 03/02/90 FAILS CIDSED 1008 WRI11NE CONTROL PAILURil DURING D 10/25/90 WRillNE ROIL TC09 TURIllNE CONIROL FAILURE CAUSING D 01/15/91

. TURillNil RUNIlACK '

'ICIO TURBINE COVTROL FAILUR11 CAUSING AN D 10/25/90 INCREASE IN POWER WITilOUT DEMAND

- 1C11 COMPLETil TURHINE TRIP FAILURE D- 01/08/91 FAILED

-1012 WRBINE TRIP D 10/25/90 1C13 UIECTRICAL 11YDRAULIC CONTROL D 03/02/90 PUMP TRIP Turbine System TUO! IDSS OF TURil!NE LUllE OIL SUPPLY V llOLD TUO2 TUlullNE GENERA 1DR VillRATION V 10/25/90' Chemical and Volume Centrol System VC01- ' REACIVR COOLANT PUMP #1 SEAL FAILURE V 01/28/91

. VCO2 . REACTOR COOIANT PUMP #2 SEAL FAILURE D 01/25/91 VCGI POSITIVE DISPLACEMENT CllAROING D 07/24/90 PUMP TRIP VC05 STUCK OPEN CilARGINO PUMP RELIEF VALVE D  !!OLD VC06 REGUNERATIVE IIEAT EXCl! ANGER LEAKAGl! V 01/28/91 VC07 LETDOWN llEAT EXCIIANGER LEAKAOl! TO V 01/25/91 ATMOSPilERE VC08 1RfDOWN IIBAT EXCIIANGER tulle RUl"rURE D 01/15/91 1D CCW SYSTEM -

- VC09 LlrrDOWN LINE LEAKAGE INSIDE V 01/08/91 CONTAINMENT .

t

. pite/ reports - Page 14

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1990 APPENDIX 8 Test Apprmed l

M itt.ter Title Tme Date Comments VC10 CilARGING PUMP COMMON DISCilARGl! V 01/15/91 lil!ADl!R RUI'rVRl!

VCll CilAltGING l.IN!! 1.l!AKAGI! INSIDl! V 01/28/91 CONTAINMl!NI' VCl2 13MI!!(Gl!NCY llORATION VAI.Vi! STUCK OPl!N D 01/28/91 VC13 1.l!TI)OWN 1. int! RI!!.ll!!' val.VI! I'All.URI! D 01/15/91 VCl4 Vol.UMI! CONTROL TANK Rill.II!F val.Vil D 01/28/91 l'All.URI!

VC19 IDSS Ol' AIR 'lO CllARGING PUMP SPl!I!D D 01/28/91 CON 11tOI.1 i:R VC20 CCW RE! TURN l' ROM 1.!rrDOWN lil!AT D 01/15/91 I!XCilANGl!R l'All,S CIDS!!D VC21 Kl!ACIOR COOL. ANT PUMP Tlll!RMAl. V 01/28/91 11ARRil!R TUlti! I'All.URI!

pitc/ reports Page 15

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1990 APPENDIX 9 LER TESTING ABSTRACTS The following list of Licensee Event Reports (Reportable Events) and Significant Operating Events were tested on the Prairie Island Simulator between 1/1/91 and 1/20/91. 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, 4

remote functions, I/O 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 Test Number Title Date Comments P-RE-1-88-1 Procedure Inade@acy 1/19/91 Correct Covering Operation Of Response RHR-Pumps In Recirculation Mode P-RE-1-88-2 Autostart Of 12 And 22 1/19/91 Correct Cooling Water Pumps Due Response 4

To Air Binding Of 11 Cooling Water Pump P-SOE-1-88-10 Loss Of DC Power To 1/19/91 Correct 12 Circulating Water Responso Pump P-SOE-1-88-14 Loss Of Power To IRPI 1/19/91 Correct Stacks Response P-RE-1-89-15 Actuation Of 122 Control 1/14/91 Correct Room Clean-up Fan Response P-RE-2-89-2 Unit Trip Caused By 1/15/91 Correct

-AEH. System-Malfunction Response P-RE-1-89-8 Autostart Of Aux Building- 1/15/91 Correct

'Special Vent System Due To Response Rad Monitor 1R37 Spike P-RE-1-89-5 Autostart Of 12 AFW Pump 1/15/91 Correct Due To Loss Of Bus 12 DC Response Power 4

PAGE 1 e

PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1990 i APPENDIX 9 LER TESTING ABSTRACTS LER Test Number Title Date Comments P-SOE-2-89-1 Isolation Of Boric Acid 1/15/91 Correct Supply To The Charging Responso Pumps P-SOE-2-89-4 Trip Of 22 AFW Pump Due 1/15/91 Correct To Governor Valve Binding Response PAGE 2

1 PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT  !

1990- ,

APPENDIX 10 EVALUATION OF THE PRAIRIE ISLAND SIMULATOR CONFIGURATION ,

MANAGEMENT PROGRAM AGAINST THE ANS/ ANSI 3.5-1985 REQUIREMENTS Following are the requirements pertaining to a Configuration 1 Management process contained in ANS/ ANSI 3.5-1985 and the elements of the Prairie Island-Simulator Configuration Management process which meet those requirements:

A. Configuration Management-Requirements

" Reference plant modifications shall be reviewed at least once per-year and the simulator update design data shall-be revised as appropriate based on-engineering and training value assessment."

(ANS-3.5-1985 5.2)

Reference plant modifications are tracked by the Lead' Simulator Engineer using the plant Modification Index and i Alteration Index. As modifications / alterations are completed in the plant they are reviewed by the Simulator Design Review Committee. The-SDRC evaluates the effect of modifications on the-simulator design and determines which modifications are to be incorporated into the simulation based on an assessment of training value. The modifications to be incorporated into the simulator are- assigned Simulator Change numbers and are then tracked and completed similar to other simulator changes. _ Completed modifications / alterations are identified within one year and Simulator Changes which result from plant

modifications are completed within one year. Simulator design data is updated by revision of the controlled plant drawings and technico! manuals, and completion of the simulator change package.

"The simulator shall be modified as. required within 12 months following the annusl ... update design data ..."

-(ANS-3.5-1985 5.3)

Simulator changes initiated as the result of a plant modification are completed within 12 months of the date the -

modification was turned over to operations (or closed out if there is no operations turnover date). However, significant modifications to the Control Room Control Panels or control

. systems are frequently implemented-in the simulator prior to completion-in the plant in order to provide training prior to use for operations.

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PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1990 APPENDIX 10

"( ANSI /ANS-3. 5-198 5' Section 5.2 ... requires that reference plant modifications be reviewed-annually against thn simulator and that the simulator update design data be revised as appropriate. This should be taken to mean that the first such-annual review and update should take place within one-year following the licensee's certification ..."

(RG 1.149 C.4].  !

The first review of plant nodifications was performed following delivery of the simulator in 1983. These reviews have been ongoing since that date.

"The control panels and consoles that are simulated shall be-designed to duplicate the size shape, color, and configuration of the functionally simulated hardware of the referonce plant."

(ANS-3.5-1985 3.2.1)

"The controls on panels and consoles that are simulated shall be designed to duplicate the size, shape,. color, and configuration of.the functionally simulated hard-ware of-the reference plant."

(ANS-3.5-1985_3.2.2]

"All functionally simulated ... hardware shall replicate that in the reference plant control room."

(ANS-3.5-1985 3.2.2]

-The simulated control' panels and consoles, and the controls on-these panels and consoles, are designed to~ duplicate the size, bhape, color and configuration of the functionally

. simulated. hardware. 7%) ensure that this duplication is maintained pictures of1the plant control boards and consoles nre taken periodically and compared to the simulator. All exceptions to this replication are identified to the Simulator Design-Review Committee and' reviewed to-verify that they will not affect training. A list of these exceptions is is-available to the instructors and is included in Appendix A.-

" Plant information shall be displayed to the operator in the'same' form and units that are available in the reference plant." (ANS-3.5-1985'3.2.2)

All plant indications for use by the operators are provided in the sa:no form and units as are available in the reference plant. All meter scales match the reference plant meters and-L lthe plant process computer database matches the reference l plant.

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PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1990 APPENDIX 10

" Meters, recorders, switches, annunciators, controllers, plant computer interface hardware and other components or displays that would function during normal, abnormal and emergency evolutions shall be included in the simulator". (ANS-3.5-1985 3.2.2)

All meters, ret ders, switches, annunciators, controllers, and plant proce ; computer hardware on simulated panels are included in the simulation. Some components for the Unit 2 which are included on shared control panels are only partially simulated - these are simulated to the extent needed for Unit 1 operation. Some panels located in the control room behind the main control board are not included in the simulator. These panels are listed in the exceptions and have been determined to not affect training.

" Consideration should be given to simulating as much of the control room environment as is reasonable and practical, for example, turbine noise, control rod step counter noise, flooring, obstructions and lighting."

[ANS-3.5-1985 3.2.3)

Steam dump noises and some turbine noise effects are simulated. Control rod step counter noise is simulated.

flooring in simulator is different than flooring currently in the plant control room however plans to replace flooring in simulator (due to wear of simulator carpetting) are proceeding. Ventilation noise in simulator does not match the plant control room ventilation noises. Improvements to decrease the noise level in the simulator have been completed however the noise level is still higher than the plant control room. Lighting level in the simulator control room is different than the plant control room and the ceiling grids do not match the plant control room.

" Communications systems that a control room operator would use to communicate with an auxiliary operator or other support activities shall be operational to the extent that the simulator instructor, when performing those remote activities, shall be able to communicate over the appropriate communication system."

(ANS-3.5-1985 3.2.3)

The following communications systems are used in the plant to communicate with auxiliary operators and other support activities: l l Plant telephone system l Plant page (Gaitronics) l Sound powered phone system  !

Radio pagers l

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PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1990 APPENDIX 10 Plant radio system Intercom system Auto ring line to the system dispatcher All communications systems except the radio pagers and the plant radio system are operational in the simulator and allow the simulator instructor to act as the auxilia n operator.

Additionally, a pair of portable radios is available on the simulator to allow simulation of radio communication with "

auxilliary operators similar to the plant system.

" Simulators ... shall be based on actual or predicted plant configuration and performance "

(ANS-3.5-1985 5.0)

The simulator modelling is based on actual plant performance and controlled plant drawings and technical manuals. The reactor core modelling is based on predicted performance obtained from core design models. Results from testing performed for simulator changes or simulator certification are compared to actual plant performance, when available, or predicted plant performance.

"When a limited change is made a specific performance test on the affected systems and components shall be performed."

(ANS-3.5-1985 5.4.1)

All simulator changes (which are limited changes), which involve changes to the model, are tested prior to use for training.

B. Simulator Enhancement Requirements "The determination of the type and number of malfunctions to be simulated should ba nr.t of a systematic process for designing performance-based operator training curricula."

(ANS-3.5-1986 3.1.2)

Determination of the type of malfunctions to be modelled is performed by the Simulator Design Review Committee during review of new malfunction requests. New malfunctions are requested by instructors as they develop operator training curricula following a systematic performance based process.

The number of malfunctions to be simulated is limited only by the available computer resources and the manpower resources assigned to the simulator support.

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PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1990 APPENDIX 10 "The malfunction assessment process should utilize:

(a) Licensee Event Reports (b)Probabilistic Risk Assessment studies (c)NSSS and BOP manufacturer equipment availability / reliability data and technical information service bulletins (d) local site considerations and plant-specific operating experiences (e)NRC bulletins and circulars" (ANS-3.5-1985 3.1.2)

Many licensee event reports, NRC bulletins and circulars and plant specific operating experiences are utilized by the instructors during development of training curricula. To ensure that these items are evaluated for additions or modifications of simulator malfunctions, a process has been set up to ensure that these items are reviewed by the simulator support group. Probabilistic Risk Assessment NSSS and BOP manufacturer data and technical studies, informat ion will also be reviewed when these items are received.

" Student feodoack should be evaluated as part of the review process."

(ANS-3.5-1985 5.2]

Student foodback is evaluated as part of the training program review process. Simulator discrepancies which are identified.

by students are written up by the responsible instructor, d

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PRAIRIE ISLAND SIMULATOR CERTIFICATION REPORT 1990 l APPENDIX 11 DCCUMENTS AVAILABLE FOR TRAINING USE ON THE SIMULATOR Following is a list of the manuals and procedures available for training use on the Prairie Island Simulator. The proJedures and manuals wl.ich are controlled by the Prairie Island QA Progrum are indicated.

1.-Technical-Specifications Controlled

2. Technical Specification Interpretations Controlled-3.~ Administrative controlo-Manual (SACD & SlACD) Controlled

4. Administrative Work Instruction (SAWI & N1AWI) Controlled

5. Emergency Plan with Implementing Procedures Controlled G. Operations-Manual Volumes A, AB, B, C, D E F, Controlled

'G., H and-I'(C Manual-contains-the operating, procedures) 7.- Alarm Response Procedures (C Procedures) Controlled

, 8 '. Operations Temporary Memos and Special Orders

9. Flow Diagrams controlled

-10.1 Logic Diagrams Controlled 11 -

SPDS Manual Controlled

12. Surveillance Procedures (Control Room list) Controlled

13. Operations checklists controlled

14. NSP-- Power Production' Policies and Procedures

15. Foxboro Control System Drawings Controlled

-16.- Westinghouse ~ Logic Drawings-Controlled

17. Electrical Distribution Drawings, Load Centers List, Panel List

18. Prairie Island Tank Book p 19. Prairie Island Pump _ Curves Book L

20. Operations Section Work Instructions (SWI) Controlled

21. . Air Junction Box List

22. Boration / Dilution Tables l

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