ML20202F790
| ML20202F790 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 01/25/1999 |
| From: | NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML20202F788 | List: |
| References | |
| NUDOCS 9902040180 | |
| Download: ML20202F790 (111) | |
Text
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l Docket Number: 50-263 4
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1999 FOUR YEAR SIMULATOR CERTIFICATION REPORT MONTICELLO NUCLEAR GENERATING PLANT SIMULATION FACILITY I
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- Prepared By: u %< Mb Date: 22 T4 99 e iorTech'nicalInstructor Reviewed By: d[8 _ Date: /- er - f r sbgtendenpSimulatorJfa'ining Approved By: s A -
Date: I (- 9 9 Training Mafager
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L L Monticello.Nucl::ar Gen rating Plant - -
l 1999 Four Year Simulator Certification Report L TABLE OF CONTENTS l
- A.1 Purpose......................................................................................................... 3
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B. Facility........................................................................................................... 3 C . S im u l ati on Fa cility. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .3. . . . .
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D. Control Room / Simulation Facility Arrangement............................................ 4 r
E. I n stru ctor i nte rface . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . -4 F. Operating Procedures For The Reference Pb nt.................. ........................ 5 G. Changes Since The 1995 Four Year Report................................................. .6 1.
H . S imu lato r Desig n D ata . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .8- :
- 1. Simulator Docu me ntation.. . . . . .. . . .. . .. . . . . . .. . . . . . . . . . . . . .. . . . . . .. . . . . . . . . . . . .. . . . .. . . . .. . . . . . . . . . . . . 8
. J . S i m u la to r Te sting . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .9. . . . . .
K. C onfig u ration Ma nagement System.. . ................. . .... ... .. ..... . . . . .. .......... ...... .. ..
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- L. Exceptions to the ANSI /ANS-3.5-1985 Sta nd a rd . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 Appendix 1 : Scope of Sim ulation. . . . . . . . . . . . . . . i .. . . . . . . ...... . ......... . .. . . . ... . ..... .. .... ... . .. 11 . ,
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' Ap'p endix 2: Simulator Control Room Reference Manuals and Procedures....... . 17 Appendix'3: Simulator Four Year Testing Schedule (1999-2002)...................... 19:
LAppendix 4: Certified Malfunction Testing Schedule.......................................... 21 i :
, Appendix 5: Remote Function List.. . .. . . . . . . . . . . . . . . . . ... ........... . .... . . . .... ............. .... 33
[ Appendix 6: CertifiGKi Malfunction List. .. ...... ... ... ... .......................................... 44 ,
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! ' Appendix' 7: Protected initial Conditions.. . .. . ... .. . ... .................... . ...................... 56 L ; Appendix' 8: Certification Test Abstracts... ... ... ... ........................ ..................... 57 L , Page 2 of 111 )
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Monticello Nucl:ar G::ndrating Plant 1999 Four Year Simulator Certification Report A. PURPOSE This report documents the performance of the Monticello plant-specific simulator in accordance with the requirements specified in 10 CFR 55.45, Regulatory Guide 1.149 (Rev.1), and ANSI /ANS-3.5-1985.
' The report and appendices:
- 1. Describe the facility, instructor interfaces, reference plant Control Room versus simulator facility fidelity, and remote function and certified malfunction .
capabilities.
- 2. Identify the references and operating procedures utilized for the conduct of ~
simulator training.
3.' Detail the objectives and methodologies associated with certification testing conducted over the period 1995 through 1998.
- 4. ' Establish the schedule for the conduct of certification testing' activities for the period 1999 through 2002.
- 5. ' Summarize the changes to the simulation facility and certification testing
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- program since the submittal of the January 1995 certification report.
- The initial certification report for the Monticello simulator was issued January 1991 and the subsequent four year certification report was issued in January 1995. <
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- B. FACILITY. '
Monticello Nuclear Generating Plant
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b ' Unit 1 GE BWR 1775MWth' Docket Number: 50-263 Licensee: Northern States Power Company _
C. SIMULATION FACILITY.
4 Owner / Operator: Northern States Power Company Location: Monticello Training Center Manufacturer: ..
Singer-Link Company
~ Date Available For Training: February 24,' 1984 Initial Certification Datei January 31,1991
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Monticello Nuclear Gan rating Plant :
1999 Four Year Simulator Certification Report D. CONTROL ROOM / SIMULATION FACILITY ARRANGEMENT l l
The simulator Control Room closely duplicates the reference plant Control Room. The layout of the plant Control Room, simulation facility, scope of simulation, and <
differences between the plant Control Room and the simulator Control Room are presented in Appendix 1.
E. INSTRUCTOR INTERFACE ,
- The simulator instructor Station is located on an elevated platform at the rear of the simulator Control Room. It consists of two redundant instructor consoles each providing the interface necessary to control and monitor simulator training activities.
Each instructor console employs a PC-based graphical operating environment utilizing standard AutoCad format drawings of all major plant systems. The activation of remote functions via the instructor console is used to simulate the operation of systems outside
. of the Control Room. Various equipment,' system, and environmental malfunctions are activated via'the instructor console to simulate plant events and operational challenges.
'A harsdheld remote device is utilized to perform selected simulator operational functions from locations away from the instructor station but within the simulator Control Room.
This enables the instructor to closely monitor training activities while also maintaining the capability to freeze the simulator or activate pre-loaded remote functions,-
malfunctions, and panel overrides.
. The video recording system located at the simulator Instructor Station provides the capability to utilize audio and video equipment installed in the simulator Control Room
- for the taping of training activities. This equipment includes three cameras and an array of microphones located throughout the simulator Control Room front panel area.
' Telephones at the Instructor Station support communications during simulator training between students and the simulator operator. This interface is utilized to support communications for the simulation of operating evolutions normally performed by in-plant operators.-
- The Instructor Station console and remote device functional capabilities include:
- 1. ' Instructor console hardware switches
- a. ; Emergency Power Off y ;
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~ Monticello Nucl2 r Gen:rcting P!::nt 1999 Four Yerr Simulator C:rtification R: port
- b. Recorder' Power Off ~
. c. Annunciator Sound Silence.
' d. Annunciator Lamp Acknowledge
. e. - Simulator Operating Limit Alarm
- f. Simulator Frane/Run
- 2. Instructor console graphical operating display a.+ Simulator Freeze /Run .
- b. Initial Conditions (0-200)
Lc. Backtrack Points (0-60)
- d. Quick Snapshot to IC "0".
- e. t Malfunction, Remote Function, and Override Total Lists
, f.- Malfunction, Remote Function, and Override Summary-
- g. Graphic System Display
- h. Data Collection System (DCS);
- i. Expert Mode Commands J. Simulator Operating Limit Status -
. k. Event Trigger Program .
~ 1.; Parameter Monitor Program.
- 3. Handheld remote device
- a. Simulator Freeze /Run -
- b. ' Simulator IC Reset
- c. Switch Check Override
- d. Annunciator Sound Silence'
- e./ Remote Triggers (1-10) .
' All malfunctions and remote functions have been validated for compliance with the requirements of ANS/ ANSI 3.5-1985.
Remote functions that simulate those activities performed by in-plant operators and are
, . necessary to accomplish simulated in-plant evolutions are listed on Appendix 5.
! Protected, simulator initial conditions are identified on Appendix 7. The protection of initial conditions facilitates the maintenance of simulator versus reference plant-
, operational fidelity. These initial conditions may be changed to support simulator training needs or to incorporate changes to the reference plant operating configuration.
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Monticello Nuclear Gsn:rcting PI:nt .
1999 Four Year Simulator Certification Report a
j F. OPERATING PROCEDURES FOR THE REFERENCE PLANT Controlled copies of the Monticello Nuclear Generating Plant operating procedures, mechanical drawings, logic prints, administrative directives, and other plant references are maintained in the simulator Control Room. These materials are controlled and updated in the same manner and timeliness as the corresponding materials available in the plant Control Room per the plant document control process.
The location, availability, and appearance of th'ese materials are similar to that of the plant Control Room.
i Copies of single use procedures and plant surveillance tests are stored in the simulator Control Room versus the Shift Supervisor Office and document control files at the plant.
This ensures that these materials are readily available to support training activities.
Appendix 2 is a listing of the procedures and reference materials located in the simulator Control Room.
G. CHANGES SINCE THE 1995 FOUR YEAR REPORT ;
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- 1. Simulation Computer The simulator Encore RSX computer system has been replaced by an ALR Dual Processor Pentium Pro-based system running under the OPENSIM NT operating system. The replacement and testing of this system was completed without ;
impacting training utilization of the simulator facility.
- 2. Instructor Station Console The original vendor provided instructor station has been replaced with two parallel (redundant capability) PC-based instructor consoles each connected to the simulation computer via an Ethernet network. Each console utilizes a graphical user interface for simulator operation, remote function activation, malfunction initiation, and simulator operating parameter monitoring.
Up to 200 Initial Conditions can be saved via the instructor station consoles to the simulation computer with the capability of saving additional initial conditions directly to magnetic storage media. Consolo installation and testing was completed without impacting traliiing utilization of the simulator facility.
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1999 Four Year Simulator Certification Report 1
- 3. Simulator Master Controller and Sub-Controllers The original simulator master controller and sub-controllers have been replaced
- as part of the simulation computer replacement project.
- 4. Simulation Certified Malfunctions The following certified malfunctions have been added:
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- a. CH23 CRDH pump low suction pressure trip
- b. RH07 Containment spray valve failure to auto close ;
- c. .TC11 Turbine runback failure
- e. AP07 Inadvertent ADS timer actuation Appendix 6 is a listing of all current certified malfunctions. Adjustable initiation
. rates are identified where applicable.
- 5. Simulation Remote Functions The following remote functions have been added:
- a. CW45 Circulating Water pump knife switch 9/305.
- b. CW46 Circulating Water pump knife switch 9/405.
- c. ED81 4160V breaker 152-308 knife switch 3/308.
Appendix 5 is a listing of all current remote functions.
- 6. Certified Malfunction Testing The list of certified malfunctions previously identified by the February 24,1997 submittal letter, has been updated to reflect the subsequent addition and deletion of certified malfunctions. All malfunctions have been validated in accordance with the certification testing schedule.
.c Appendix 4 is the testing schedule for certified malfunctions for the period 1999 through 2002.
- 7. Simulator Process Computer The simulator process computer utilized for operation of the Safety Parameter Display System (SPDS) has been upgraded to a Mini-Vax 4000.
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1999 Four Year Simulator Certification Report !
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- 8. Simulator Shift Supervisor Office
- A Shift Supervisor Office located adjacent to the simulator Control Room has been established to enhance the simulator training environment. A display panel in the office replicates Panel C-295 installed in the plant Shift Supervis,or Office.
The panel enables shift supervision in training to monitor and assess simulator crew activities. An intercom and telephone similar in appearance and function to
' that installed in the plant Shift Supervisor Office are provided to facilitate communications between the two locat'sas. !
- 9. A.Iternate Shutdown System Panel '
The Altemate Shutdown System Panel C-292 bench board has been relocated from the simulator Control Room to the simulator computer room to enhance !
operational realism when performing actions at C-292.
- 10. Plant Re-Rate
.The simulator has been modified to reflect Monticello plant re-rate condMions.-
- 11. Plant Modifications -
All' applicable reference plant modifications have been evaluated, installed, and !
- tested in accordance with the plant modification process and simulation :
configuration control procedures. ;
.H. SIMULATOR DESIGN DATA
" The initial simulator design database consists of those documents and reference :
materials provided to the simulator manufacturer for use in the design, construction, and testing of the simulator. This data includes plant drawings, logic prints, technical manuals, control board photographs, plant performance information, and plant process computer printouts.
J Following simulator delivery and the completion ~of acceptance testing, the initial design database was archived and remains available in a retrievable microfilm format.
)The current design database is the compilation of the original design data and that data subsequently added to reflect simulator hardware and software updates, simulator ;
facility changes,' and the incorporation of reference plant modifications. [
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+ Monticello Nuclerr Gan:rcting Pl:nt 1999 Four Year Simulator Certification Report
- 1. SIMULATOR DOCUMENTATION - l l
All records associated with simulator facility operation, modification, testing, and certification are maintained as controlled documents in secordance with site .
' administrative control procedures. lThese records include:
-1. Simulator Modification Review Committee Minutes
- 2. Simulator Modification Packages ,_
. 3. Completed Simulator Discrepancy Reports
- 4. Simulator Performance Tests ,
- 5. Protected initial Conditions Summary )
- 6. Simulator. Malfunction'Cause and Effect Records_
- 7. Completed Simulator Media Update Forms
- 8. - Completed Set Point Change Review Forms j
- 9. Simulator Certification Reports
- 10. Simulator Annual Certification Reports
- 11. Simulator Four Year Certification Reports J.- SIMULATOR TESTING l ' Simulator operability testing consists.of steady state and transient performance, normal plant evolution, malfunction, and facility environment testing. Appendix 8 is the compilation of test abstracts and results associated with simulator certification testing l for the period 1995 through 1998.
' Appendices 3 and 4 are the four year certification test schedules for the period 1999 through 2002; K. CONFIGURATION MANAGEMENT SYSTEM The simulator Configuration Management system provides the mechanism for initiating, tracking, resolving, and testing changes to the simulator. The major elements of the system include:
- 1. Simulator Discrepancy Reports (DR)-
Deficiencies associated with the simulator facility are identified via the DR process.L Each DR is tracked, resolved, and acceptance tested in accordance with simulator process proceiures. A PC-bar,ed database is utilized for tracking
. of the DR process. Once complete'd, each DR is retained in the simulator documentation file.
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. . 1999 Four Year Simulator Certification Report
- 2. Simulator Modification Review Committee (SMRC) ,
All ' reference plant modifications are evaluated for applicability to the simulator in accordance with the plant modification process. An evaluation of applicable -
plant modifications, proposed simulator modifications and design enhancements, and simulator facility changes is performed by the SMRC. The SMRC is composed of representatives from the Simulator and Operations Training groups.
Changes and modifications approved for implementation by the SMRC are installed and tested in accordance with simulator process procedures.
Completed modification packages are retained in the simulator documentation
- file.
- 3. Physical Configuration Verification in accordance with simulator process procedures, physical configuration control
- of the simulator is accomplished by comparing photographs of the plant Control .:
Room and simulator Control Room panels. The photographs are updated as -
, necessary to reflect current plant Control Room panel configurations.
~ Changes to' plant Control Room labeling and the installation of operator aids and -
information tags on_ plant control panels are assessed for simulator applicability in accordance with plant administrative control procedures. If applicable, additional copies of labels, aids, and tags are provided by plant personnel for installation on the simulator.
t
'L.1 EXCEPTIONS TO THE ANSI /ANS-3.5-1985 STANDARD
- l. ' No' exceptions have been taken with respect to the reference standard.
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Monticello Nucle:r G:nzrcting Pl:nt 1999 Four Year Simulator Certification Report Appendix 1: Scope of Simulation
- 1. Equipment providing full-scope simulation of the reference plant Control Room:
- a. Area and Process Radiation Monitoring CO2
- b. Reactor Core Cooling Panel C03
- c. Cleanup and Cooling Panel - C04
- d. Reactor Control Panel C05
- e. Feedwater and Condensate Panel C06
- f. Turbine and Generator Control Panel C07
- g. - Auxiliary Electrical Control Panel C08
- h. Area Radiation Panel C11
- 1. Nuclear Steam Supply Temperature Recording C21 J. Single Rod Scram Test Panel C16
. k. Remote Shutdown Panel C292
- 1. - Off-Gas Storage C252A
- m. Off-Gas Recombiner System A C252B
- n. Off-Gas Recombiner System B C252C
- o. Miscellaneous Process Section C252D
. p. Nitrogen inerting System Panel C26
- q. Combustible Gas Control Panel A C291A
- r. Combustible Gas Control Panel B C291B
- s. Standby Gas Treatment System A C24A
- t. Standby Gas Treatment System B C24B Page 11 of 111
Monticello Nucle r Gen:rcting Plant .
1999 Four Year Simulator Certification Report Appendix 1: Scope of Simulation
- u. Drywell Cooling System Panel C25
- v. HVAC and Feedwater heater Control Panel C20
- w. Wide Range Gas Monitor Channel A C257
- y. Operators Desk- C01
- 2. Equipment providing partial-scope simulation of the reference plant Control Room:
- a. Process Radiation Monitor Panel C10
- 1) Reactor Building Plenum Radiation Monitors (Channel 1 only)
- 2) Fuel Pool Radiation Monitors (Channel A only)
- 3) Discharge Canal Radiation Monitors (Channel A only)
- b. Reactor Protection Div.1 Relay Panel (MSIV Low-Low Reactor Water Level Bypass key locked switches only) C15
- c. Reactor Protection DP/. 2 Relay Panel (MSIV Low-Low i Reactor Water Level Bypass key locked switches only) C17
- d. Startup Range Neutron Monitor Panel (Source Range l' Channel 21 and Intermediate Range Channel 11 only) C36
- e. Power Range Neutron Monitor Panel (Average Power Range Channel 4 and Local Power Group 1 only) C37
- f. Traversing incore Probe Panel (Single TIP Machine utilized
- to sim~ulate' Channels 1,2, and 3) C13
- g. Generator Protection & Monitoring Panel (Relays not
. physically simulated) ~ C31 ;
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1999 Four Year Simulator Certification Report i
~
Appendix 1: Scope of Simulation J
3 ' Equipment not simulated:
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- a. Seismic Monitoring Cabinet
- b. Fire Detection Cabinet C300
- c. Wide Range Gas Monitor Channel B C258 l
- e. Emergency Filtration Training Control Panels C263 l l
f.' Operator's Desk dedicated (Giatronics) plant paging station
'4. Simulation modeldesign assumptions:
The system-specific design assumptions are detailed in the Simulator Final Design Specification. The generalized assumptions used for all modeled systems include: ;
i
- a. Containments, vessels, piping and other systems do not fail due to exceeding the design press or temperature.
- b. - Systems operate in a ideal manner (i.e. valves do not leak, check valves do not permit reverse flow, and fuel is not damaged unless acted on by a malfunction).
- 5. Simulator Control Room environment:
- a. The simulator room environment is similar in appearance to the actual Control Room. The features incorporated to enhance plant Control Room environment fidelity include:
- 1) The furniture and appointments are identical. Duplicate items from the same supplier were procured and installed.
- 2) Annunciator sound characteristics and levels are identical.
- 3) The floor and wall coverings are similar in color and material.
- 4) The lighting levels are maintained at a similar level.
- 5) Identical emergency lighting is installed.
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Monticello Nucirr G:nsrcting Plant 1999 Four Ye:r Simulator C:rtification R: port Appendix 1: Scope of Simulation
- 6) Communications equipment is the same style and color.
- 7) The ambient sound levelis similar.
- b. Physical differences between the simulator and the plant Control Room:
- 1) The ceiling height in the simulator is 24 inches higher than the plant Control E
Roorn.
- 2) The Instructor Station in the simulator room occupies the corresponding plant Control Room kitchen and rest room area.
- 3) The reference print and drawing racks in the simulator are of a different style and maintained in a different location than those in the Control Room.
- 4) The Automated Traversing incore Probe system is not installed on the simulator. The originally installed Traversing Incore Probe system, similar in appearance and function, remains utilized.
5)' The storage cabinet utilized for Emergency Operating Procedure flowcharts is of a different design in the simulator Control Room versus the plant Control Room to support the increased utilization of the enclosed materials.
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Monticello Nuclerr G:ner: ting PI:nt i 1999 Four Ycir Simul; tor Certification Report Appendix 1: Scope of Simulation l
- 6. Plant Control Room configuration PLANT CONTROL ROOM i
- c. C15 C16 - C17 C21 C11 C10 CO2 CHANNEL A PROT' CHANNEL B NSSS AREA PROCESS AREA & PROT PROTECT SYS SYS TEST, PROTECT SYS TEMP REC MON MON! TOR MONITOR l
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Monticello Nucle:r Generating Plent 1999 Four Year Simulator Certification R: port
- Appendix 1: Scope of Simulation
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[ 1999 Four Year Simulator Certification Report l
l Appendix 2: Simulator Control Room Reference Manuals and Procedures
! 1. . The reference manuals and documents utilized for operator training are controlled L and maintained current per the Monticello Document Control Administrative Work Instruction 4-awl-02.01.01. I i
1
- 2. ' The' reference manuals and documents utilized for the conduct of plant operations !
and maintained in the plant Control Room are similarly maintained in the simulator )
. Control Room. I
- 3. Reference manuals and documents maintained in the simulator Control Room
- a. Technical Specifications
- b. . Technical Specifications Interpretation Manual
- c. Volume A - Emergency Plan (Volumes 1 through 3)
- d. Volume B - System Operating Procedures
- e. Volume C - Integrated Operating Procedures
- 1) C.1 - Startup
- 2) C.2 - Power Operation
- 3) C.3-Shutdown
- 4) C.4 - Abnormal Operating Procedures
- 5) C.5 - Emergency Operating Procedures
- 6) C.6 - Annunciator Response Procedures
- f. Volume D - Refueling Procedures
- g. Volume E - Electrical Procedures
- h. Emergency Operating Procedure Flowcharts
- i. Plant Drawings (P & ID's)
J. Administrative Controls Manuals Page 17 of 111
Monticello Nucis r Gcn:rcting Plant '
1999 Four Year Simulator C::rtifica. tion Report Appendix 2: Simulator Control Room Reference Manuals and Procedures
. k. System Controlled Drawings .
- l. Lighting and Power Panel Schedules
- m. 480 Volt MCC Load Manual ,
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- n. Operations Memos
. w.-Volume F (Temporary Changes) Manual-
- x. Pre-Fire Strategies
- y. T Operator Aids
- z. Emergency Plan Implementing Procedures aa. Emergency Action Level Reference Manual ,
bb. Chemical Response Guides. [
cc. Contingency Plan Implementing Procedures dd. Operations Work Instructions
- ee.NUREG 1022 Event Reporting Guidelines L ,
. ff. : Severe Nccident Management Guidelines l.
gg. Selected plant single use procedures and surveillance tests applicable to the simulator. training venue - ,
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1 Monticello Nucle r Gener ting PI:nt 1999 Four Year Simulator Certification Report '
' Appendix 3: Simulator Four Year Test Schedule (1999-2002) !
- 1. Normal Plant Evolution (NPE) testing, per Section 3.1.1 of ANSI /ANS 3.5-1985, will be performed on an annual basis and will include: 4
- a. NPE01 - Plant Startup (Cold to Hot Standby)
- b. NPE02 - Plant Startup (Hot Standby to Rated Power)'
- c. NPE03 -Turbine Startup and Generator Synchronization
- d. NPE04 - Reactor Trip Followed by Recovery to Rated Power
- e. NPE05 - Operations in Hot Standby
- f. NPE06 - Generator Load Changes
- g. NPE07 - Power Operation at Less Than Full Coolant Flow.
j
- h. NPE08 - Plant Shutdown from Rated Power to Hot Standby and Cool Down to Cold Shutdown Conditions
- i. NPE09 - Heat Balance Data at 25%,50%,75%, and 100% Power J. NPE10 - Operator Conducted Surveillance Testing on Safety-Related Equipment and Systems
- 2. Steady-state performance testing, per Section 4.1 and Appendix B of ANSI /ANS-3.5 of 1985, will be conducted on an annual basis and include:
- a. US01 - 100% Stability
- b. US02 - Steady State Performance at 25%,50%,75%, and 100% Power Levels
- 3. - Transient Performance testing, per Section 4.2.1 and Appendix B of ANSI /ANS-3.5 of 1985, will be conducted on an annual basis and include:
- a. TZ01 - Manual Scram
- b. TZ02 - Simultaneous Trip of All Feedwater Pumps
- c. TZO3 - Simultaneous Closure of All MSIVs Page 19 of 111
I Monticello Nucl:ar Gan:rcting Plant 1999 Four Year Simulator Certification Report
. Appendix 3: Simulator Four Year Test Schedule (1999-2002)
- d. TZ04 - Single Reactor Recirculation Pump Trip
- e. TZO5 - Simultaneous Trip of Both Reactor Recirculation Pumps
- f. TZ06 - Main Turbine Trip (Maximum Power with No Screm)
- g. ' TZ07 - Maximum Rate Power Ramp.(100%
- 75%
- 100%)
- h. TZO8 - Design Basis LOCA Coincident with a Loss of Offsite Power
- 1. TZ09 - Maximum Size Unisolable Main Steam Line Rupture J. ' '.10 - SORV Open, MSIV lsolation, and HP ECCS Inhibited
- 4. Certified malfunction testing, per Section 3.1.2 of ANSI /ANS-3.5 of 1985, will be performed in the manner such that approximately 25% of certified ,
malfunctions as detailed on Appendix 4 of this report are completed annually, in the event the list of certified malfunctions changes, the testing schedule will ;
be modified as necessary to assure all malfunctions are tested during the four-year period. ,
- 5. Computer real time testing, per Section 3.1.1 of ANSI /ANS-3.5 of 1985, will be performed on an annual basis per XX-01 Simulator Real Time Test.
- 6. Simulator environment and physical fidelity testing, per Section 3.2.1 through ,
3.2.3 of ANSI /ANS-3.5 of 1985, will be completed during the four year period -
and include:
~a . XX Simulator / Control Room Lighting
- b. XX Simulator / Control Room Audible ;
- c. XX Simulator / Control Room Physical Fidelity l l
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Monticello Nuclear Gen:stting Plant
-1999 Four Year Simulator Certification Report Appendix 4: Certified Malfunction Testing Schedule l
For the period 1999-2002 certified malfunction testing, per Section 3.1.2 of ANSI /ANS-3.5 of 1985, will be completed as follows:
MALF TITLE 1999 2000 2001 2002 :
AN01 - ANNUNCIATOR FAILURE X AP01 SAFETY RELIEF VALVE Fall OPEN X
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AP02 INADVERTANT ADS ACTUATION X 1
AP03 SAFETY RELIEF VALVE LEAK X AP04 SRV FAILURE TO LIFT- SAFETY MODE X APOS SRV FAILURE TO RESEAT X AP06 ADS AUTOMATIC INITIATION FAILURE X
-AP07 SPURIOUS ADS ACTUATION X-CH01 CONTROL ROD DRIFTS OUT X CH02 CONTROL ROD STUCK X CH03 CONTROL ROD UNCOUPLED X CH04 CRD ACCUMULATOR TROUBLE X CH05 CONTROL ROD SCRAM X CH07 CRD FLOW CONTROL VALVE FAILURE X CH08 CRD PUMP BREAKER TRIP X
- t CH11 RMCS TIMER FAILURE X CH12 CONTROL ROD FAILURE TO DE-SELECT X Page 21 of 111
Monticello Nuclerr G:n r; ting Pisnt 1999 Four Yerr Simulator C:rtificttion Report Appendix 4: Certified Malfunction Testing Schedule i MALF TITLE 1999 2000 2001 2002 CH13 FAILURE OF RX MANUAL CONTROL X CH16 FAILURE TO SCRAM X CH18 ATWS FAILURE - ARI VALVE FAILURE X CH19 MULTIPLE STUCK RODS X _
CH22 SDV VENT / DRAIN VALVES Fall OPEN X CH23 CRDH PUMP LOW SUCTION PRESS. TRIP X CS01 CORE SPRAY PUMP NO.11 (12) TRIP X CS02 CORE SPRAY OTBD VLV FAILS SHUT X
- CWO2 CIRC WATER PUMP TRIP X CWO4 CIRC WTR PUMP NO.11 (12) PIT FLOOD X CWO8 CONDENSER PIT FLOOD X DG01 DIESEL GENERATOR TRIP X DG02 DG #11(12) FAILURE TO START X DG04 NO.13 DIESEL GENERATOR TRIP X ED04A LOSS OF MAIN TRANSFORMER X ED04B LOSS OF 1AR TRANSFORMER X 1
ED04C LOSS OF 1R TRANSFORMER X ED04D LOSS OF 2R TRANSFORMER X EDO4E LOSS OF 2RS TRANSFORMER X Page 22 of 111 4
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Monticello Nuclerr G:n:rcting PI:nt 1999 Four Year Simulator Certification Report l
Appendix 4: Certified Malfunction Testing Schedule l l
l MALF TITLE 1999 2000 2001 2002 ED04F LOSS OF 1ARS TRANSFORMER X
- ED05A 4160V BUS LOCKOUT NO.11 X j 1
ED05B 4160V BUS LOCKOUT NO.12 X j l
ED05C 4160V BUS LOCKOUT NO.13 X ED05D 4160V BUS LOCKOUT NO.14 X l
ED05E 4160V BUS LOCKOUT NO.15 X ED05F 4160V BUS LOCKOUT NO.16 X ED06A LOSS OF LOAD CENTER 101 X l l
ED06B LOSS OF LOAD CENTER 102 X l l
l ED06C LOSS OF LOAD CENTER 103 X l
ED06D LOSS OF LOAD CENTER 104 X l ED06G LOSS OF LOAD CENTER 109 X ED07A LOSS OF 250 V DC DIV I BATTERY X ED07B LOSS OF 250 V DC DIV 11 BATTERY X ED08A LOSS OF 125 V DC DIV I BATTERY X ED08B LOSS OF 125 V DC DIVil BATTERY X ED09A LOSS OF 24 V DC BATTERY NO.15 X ED098 LOSS OF 24 V DC BATTERY NO.14 X ED10A LOSS OF UPS Y10 X Page 23 of 111
Monticello Nuclear G:ntrcting Plant -
1999 Four Year Simul: tor Certificr. tion Report
. Appendix 4: Certified Malfunction Testing Schedule MALF TITLE 1999 2000 2001 2002 ED10B LOSS OF UPS Y30 X
- f. ED10C LOSS OF UPS Y70 X
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ED10D LOSS OF UPS Y80 X ED11A LOSS OF INST AC DISTRIBUTION Y-20 .X ED11B LOSS OF INST AC DISTRIBUTION Y-25 X ED11C LOSS OF INST AC DISTRIBUTION Y-26 X ED12 LOSS OF OFF-SITE POWER X ,
-ED16 2R TRANSFORMER COOLING FAN FAILURE X ED20 Y91 INVERTER FAILURE X
. REM' OPEN 3N4 @ POWER (2R SUPPLYING X i
'ED06 HOUSE LOADS) (REMOTE FUNCTION)
EG01 LOSS OF STATOR WATER COOLING X EG02 STATOR COOLING PUMP TRIP X EG03 GENERATOR LOCKOUT X EG08 GENERATOR HYDROGEN LEAKAGE X EG07 GENERATOR MAX EXCITATION X FWO3 - CONDENSATE PUMP TRIP X FWO4 CONDENSATE PUMP HIGH VIBRATION X FWO6 COND RECIRC VALVES FAIL OPEN/ CLOSED - X Page 24 of 111
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, Monticello Nucle:r Gen: rating PI:nt 1999 Four Year Simulator Certification Report Appendix 4: Certified Malfunction Testing Schedule MALF TITLE 1999 .2000 2001 2002 FWO8 CONDENSATE DEMIN HIGH D/P X FW10 DEMIN RESIN RETENTION FAILURE X FW11 EXHAUST HOOD SPRAY FAILS CLOSED X FW14 LP FEEDWATER HEATER TUBE LEAK X
-FW15 REACTOR FEED PUMP HIGH BEARING X TEMP FW16 REACTOR FEED PUMP TRIP X FW17 RX FEEDPUMP RECIRC VLV FAILURE X FW19 HIGH PRESS FW HEATER TUBE LEAK X
'FW20 FWRV LOSS OF AIR X FW21 FAIL FEED REG VLV M/A CONTROLLER X FW23 - Fall OF DFC SHIFT SINGLE ELEMENT X FW24 FAIL OF FW FLOW TRANS FT-6-50-A X 1
FW25 FW PIPE A(B) BREAK OUTSIDE PC X FW26 - FW LOOP A(B) BREAK INSIDE PC X ,
HP01 HPCI AUTO INITIATION X
- R- CLOSES CHECK VALVE HP-10 X HP01.
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' HP02 HPCI AUTO-START FAILURE X HP03 HPCI TURBINE TRIP X Page 25 of 111 E
Monticello Nuclear G:n: rating Pirnt -
1999 Four Year Simulator Certification Report Appendix 4: Certified Malfunction Testing Schedule i
MALF TITLE 1999 2000 2001 2002 HPO4; HPCI SPEED CNTRL FAILS HIGH (LOW) X HP05 HPCI AUTO ISOLATION (GROUP 5) X-HP06 - LOSS OF COOLING TO HPCI GLAND SEAL. X CONDENSER AND L.O. COOLER HP07 HPCI STEAM LINE LEAK X IA01 SERVICE AIR COMPRESSOR TRIP X
'IA02 SERVICE AIR ISOLATION X.
lA03 AIR COMP Fall TO LOAD (UNLOAD) X IA04 INST AIR HDR FAILURE - RX BLDG X IA06 DECREASING SERVICE AIR PRESSURE X MC01 LOW PRESSURE CONDENSER TUBE LEAK X l RMC01 ADJUST MS-24-1 TO ALTER A/E STM FLOW X MC03 CONDENSER AIR IN-LEAKAGE X MC05 AIR EJECTOR SUCTION VALVES CLOSURE X MS01 MSIV 80-A(B,C,D) INBD FAILS CLOSED X ,
1 MS02 MSIV 86-A(B,C,D) OTBD FAILS CLOSED X MS03 MSL "B" RUPTURE IN TUNNEL X MSO4 MSL RUPTURE IN DRYWELL X
. MS05- MSIV 80-A(B,C,D) INBD FAIL TO CLOSE X Page 26 of 111
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Monticello Nuclear Gener: ting Plant 1999 Four Year Simulator Certification Report )
I Appendix 4: Certified Malfunction Testing Scliedule j l
l MALF TITLE 1999 2000 2001 2002 l MS06 MSIV 86-A(B,C,D) OTBD Fall TO CLOSE X MS07 MSIV DISC SEPARATION FROM STEM X MS08 TURBINE STEAM SEAL FAILURE X ;
1 MS09 STM PACKING EXH BLOWER MTR TRIP X MS10 Fall OF MS FLOW TRANS 6-51 A X MS11 MSL RUPTURE IN TURBINE BLDG X !
N101 SRM FAILS DOWNSCALE X NIO2 SRM FAILS FULL SCALE X --
N103 SRM INOP X i
NIO5 IRM DOWNSCALE X NIO6 IRM FULLSCALE X ,
l NIO7 IRMINOP X N109 IRM CHANNEL SPURIOUS INDICATION X N112 APRM DOWNSCALE X N113 APRM FAILS FULLSCALE X N114 APRM INOP X N115 RBM DOWNSCALE X
- N116 RBM UPSCALE X N117 RBMINOP X Page 27 of 111
l Monticello Nucle rG n rating Plant . ,
1999 Four Year Simulator Ctrtification R: port I Appendix 4: Certified Malfunction Testing Schedule l
MALF TITLE 1999 2000 2001 2002 ]
J l
OG07 RECOMB TRN LOW STM FLOW SD X OG30 CLOSES "B" RECOMB. STEAM (REMOTE) X PC01 SBGT EXH FAN V-EF-17A(B) TRIP X PC02 SPURIOUS SEC. CONTAINMENT ISOLATION X RPC05 OPEN TORUS DRAIN (REMOTE) X PC07 TORUS TO DRYWELL VACUUM BREAKER X PC09 SRV RV2-71 A (B-H) LINE BREAK X PC11 RX BLDG DP POSITIVE X POO1 SPDS FAILURE X PP01 LOSS OF RPS MG SET A (B) X PP03 RPS SUBCHANNEL FAILURE X REM MSL HIGH FLOW SETPOINT X PPO3 (VARIABLE SETPOINT)
PPO4 RPS SUBCHANNEL AUTO SCRAM X PP05 SPURIOUS GP 1 ISOL SUBCHAN TRIP X PP06 FAILURE OF MODE SW TO SCRAM X OVR MANUAL SCRAM PUSHBUTTON FAILURE X RC01 RCIC AUTO-START FAILURE X RC02 RCIC AUTO INITIATION X
!. Page 28 of 111
.: Monticello Nuclear Gener ting Plant 1999 Four Ye r Simulator Certification Report Appendix 4: Certified Malfunction Testing Schedule MALF TITLE 1999 2000 2001 2002 RC02 RCIC OVERSPEED SETPOINT ADJUSTMENT X RC03 RCIC TURBINE TRIP X RC03- CLOSE RCIC PUMP SUCTION (REMOTE) X RC04 RCIC ISOLATION SIGNAL X RC05 RCIC SPEED CONTROL FAILURE X RC06 RCIC LUBE OIL COOLER LOW SUPPLY X
-RC07 RCIC STEAM LINE LEAK X RC08 FAILURE OF GROUP 5 ISOLATION X RH01 RHR PUMP TRIP X RH02 RHR SYS 11(12) HEAT EXC TUBE LEAK X l l
RH03 FAILURE OF LPCI (INBD) INJ VALVE X l
l RHOS RHR MIN FLOW VALVE FAILS OPEN X j RH04 RHR SD COOLING SUPPLY ISO SIGNAL X RH06 RHR PUMP MIN FLOW VALVE FAILS SHUT X RH07 - CNTMT SPRAY VLV ISOL FAILURE X RM01 PROCESS RADIATION MONITOR UPSCALE X RM02 PROCESS RADIATION MONITOR DWNSCL X RM03 AREA RADIATION MONITOR HIGH X RRO1 A- RX RECIRC LOOP A BREAK (SMALL) X Page 29 of 111
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Monticello Nuclerr Gen:rcting Plant -
1999 Four Ye:r Simulator C:rtification R: port Appendix 4: Certified Malfunction Testing Schedule MALF TITLE 1999 2000 2001 2002 RR01B RX RECIRC LOOP B BREAK (SMALL) X :
RR02 RECIRC JET PUMP RISER BREAK X RR03A RX RECIRC LOOP A BREAK (LARGE) X RR03B RX RECIRC LOOP B BREAK (LARGE) X RR04 INST LINE RUPTURE INSIDE DRYWELL X RR05A RX RECIRC PUMP A LOCKOUT X RR05B RX RECIRC PUMP B LOCKOUT X RR06A RX RECIRC PUMP A SElZURE X RR06B RX RECIRC PUMP B SElZURE X RR07 RECIRC PUMP MTR BEARING TEMP HIGH X RR09 RX RECIRC PUMP RUN AWAY X RR10 RECIRC MG FIELD BREAKER TRIPS OPEN X RR11 RX REClRC PMP INCOMPLETE START X SEQUENCE l RR13 RECIRC MG MANUAL SCOOP TUBE X ADJUSTMENT (REMOTE)
RR13 RECIRC SPEED CONTROL SIGNAL FAILURE X RR15 RX RECIRC SYS TOTAL FLOW INST X ;
FAILURE I RR16 RECIRC PUMP LOWER SEAL FAILURE X Page 30 of 111
Monticello Nucl:ar Gen:: rating Pl::nt 1909 Four Year Simulator Certification Report Appendix 4: Certified Malfunction Testing Schedule MALF TITLE 1999 2000 2001 2002 RR17 RECIRC PUMP UPPER SEAL FAILURE X RR18 INSTRUMENTED JET PUMP FAILURE -X RR19 NON-INSTRUMENTED JET PUMP FAILURE X '
RR20 SPURIOUS ATWS TRIP X RR22 RECIRC LUBE OIL PUMP TRIP X RR23 ATWS FAILURE: RECIRC MG FIELD BKRS X Fall TO TRIP RR25 FAILURE OF NR LEVEL TRANS. (LT-6-52A/B) X RR27 RCP MANUAL SPEED CNTRL Fall LOW X RR28 RPV LEVEL VARIABLE LINE BREAK X RUO1 RWCU PUMP TRIP X RUO3 NON-REGEN HEAT EXCH HIGH OUTLET X TEMPERATURE RUO7 RWCU SUCTION PIPE BREAK X RWO1 RWM EQUIPMENT FAILURE: CONTINUOUS - X ROD BLOCK RWO2 ROD WORTH MINIMlZER LPSP FAILURE X RX01 FUEL FAILURE X RXO3 REACTOR CORE POWER OSCILLATIONS X SLO 1 SBLC PUMP TRIP X Page 31 of 111
Monticillo Nucle:r Gcn: rating Plant .
1999 Four Year Simulator Certification Report
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Appendix 4: Certified Malfunction Testing Schedule MALF TITLE 1999 2000 2001 2002 SLO 3 SBLC SQUlB VALVE FAILS CLOSED X SWO1 RBCCW PUMP TRIP X SWO2 - RBCCW LEAK IN DRYWELL X SWO3 SERVICE WTR PMP TRIP X SWO4 ESW/ EFT ESW PUMP TRIP X SWO5 : RHRSW PUMP TRIP X TC02 TURBINE MASTER TRIP X TC04 ELEC PRESS REGULATOR FAILURE X TC05- MECH PRESS REGULATOR OSCILLATIONS X ,
TC06 TURBINE BYPASS VLV STUCK X TC07 TURBINE BYPASS VALVE FAILURE X TC08 TURBINE CONTROL VALVE FAILURE X TC09 TURBINE STOP VALVE FAILS CLOSED X TC10 TURBINE FAILURE TO TRIP X TC11 TURBINE GENERATOR RUNBACK FAILURE X TUO1 EPR OIL PUMP TRIP X TUO3 TURBINE BEARING HIGH VIBRATION X TUO5 LOSS OF TURBINE BEARING OIL X PRESSURE-Page 32 of 111-
Monticello Nucl:ar Gancrating Plant 1999 Four Ye:r Simulator Certification Report Appendix 5: Remote Function List REMOM STATUSI DESCRIPTION RANGE FUNCTION VALUE CGO1 CGCS DIV l INLET, MO-4043A OP/OF/CL !
CGO2 CGCS DIV ll lNLET, MO-40438 OP/OF/CL CGO3 CGCS DIV I RECIRC, MO-4044A 0-100 %
CGO4- CGCS DIV ll RECIRC, MO-4044B 0-100 %
CGO5 CGCS DIV l CONTROL SWITCH OF/OP CGO6 CGCS DIV ll CONTROL SWITCH OF/OP CH01 XR-21, CRD MAN ISOL VALVE (N.C.) CUOP CH02 FR-11, CRD SEAL FLOW REG - 11 RX 5GPM CH03 FR-12, CRD SEAL FLOW REG - 12 RX 0-5GPM CH04 CRD-1, CRD PUMP SUCT FRM CST N.0 CUOP CH05 CRD-68, PMP SUC SUPP FRM COND CUOP CH06 CRD-24, BYPASS MO-3-20, DRIVE WT T CUOP CH07 CRD-27, BYPASS MO-3-22, COOL WTR T CL/OP CH08 CRD-30, CRD STOP ISOL VLV-RWCU CUOP l CH09 CRD WTR FILT 3-17A/3-17B IN/OUT A/B IN/OUT I CH10 #12 CRD PUMP SUC STNDBY FILTER OUT/IN I CH11 CRD PP SUC FIL A-IN,B-IN,C-OUT A/B/C IN/OUT CH12 CRD-5-1, CRD PUMP #11, DISCH.VLV T CUOP CH13 CRD-5-2, CRP PUMP #12, DISCH.VLV ' T CUOP CH14 CRD-8 PMP TEST BYPASS T CUOP CH15 CR (XX-YY) ELEC DIRM (121) DRD/ ARM l
. CH16 A F.C. STA CRD-16-1/CRD-18-1 CUOP l l- CH17 - B F.C. STA CRD-16-2/CRD-18-2 _
CUOP L CH18 - TRIP PUSHBUTTON #11 CRD PMP NRMUTRI BREAKER u
CH19 CLOSE PUSHBUTTON #11 CRD PMP NRMUCLO BREAK CH2O TRIP PUSHBUTTON #12 CRD PMP NRML/TRI BREAKER CH21 CLOSE PUSHBUTTON #12 CRD PMP NRMUCLO BREAK i CH22 CRD-14, ACC CHRG WTR TCUOP NRMUCLO l CH23 CRD FLOW CNTRL CV3-19A LO MAN CN 1.4-100 CH24 CRD FLOW CNTRL CV3-19B LO MAN CN 1.4-100 CH25. CRD PMP 11 ECCS LD SD BY14A-Kl7A OUT/IN CH26 CRD PMP 12 ECCS LD SD BY14A-Kl7B OUT/IN
- - CWO1 #11 COOLING TWR FAN E STP/STRT CWO2 #11 COOLING TWR FAN C STP/STRT CWO3 #11 COOLING TWR FAN A STP/STRT CWO4 #12 COOLING TWR FAN P STP/STRT Page 33 of 111 d
Monticello Nucl=r G:nnrating Plant 1999 Four Year Simulator Certification Report Appendix 5: Remote Function List RMOTE DESCRIPTION RANGE STAWS/
FUNCTION VALUE CWO5 #12 COOLING TWR FAN M STP/STRT CWO6 #12 COOLING TWR FAN K STP/STRT -
CWO7 - #11 COOLING TWR FAN TRIP RESET NRMURES CWO8 412 COOLING TWR FAN TRIP RESET NRMURES CWO9 #11 COOLING TWR PUMP STP/STRT CW10- #12 COOLING TWR PUMP -
STP/STRT -
CW11 CW-MO-1154 CW COND OTLT VLV CLOSE AUTO /OPN CW12 CW-MO-1155 CW COND OTLT VLV CLOSE AUTO /OPN :
CW13 CW-MO-1156 CW COND INLT VLV CUOP CW14 CW-MO-1157 CW COND INLT VLV CUOP CW15 #11 CLOSED CYCLE MAKEUP PUMP STP/STRT CW16 #12 CLOSED CYCLE MAKEUP PUMP STP/STRT CW17 lNTAKE ISOLATION GATE MO-1976 CUOP CW18 INTAKE ISOLATION GATE MO-1977 - CUOP CW19 INTAKE ISOLATION GATE MO-1978 CUOP CW20 INTAKE ISOLATION GATE MO-1979 CUOP CW21 - #11 TOWER SLUICE GATE MO-1899 TCUOP CW22 #12 TOWER SLUICE GATE MO-1900 TCUO? !
CW23 #11 CT PMP SLUICE GATE MO-1873 T CUOP CW25 WATERBOX SCAVENGING PUMP P-50A STP/STRT CW26 - WATERBOX SCAVENGING PUMP P-50B STP/STRT CW27 CW-16, DE ICING VLV T CL./OP CW28 AIR /WTR F A=0/37,B=40/60,C=90/8 A/B/C CW29 CW RDWST VLV CV-3374/3376/3377 CUOP CW30 CW INTAKE SYSTEM TROUBLE NRMUACK
- CW31 #11 COOLING TOWER FAN G STP/STRT CW32 #11 COOLING TOWER FAN J STP/STRT CW33 #11 COOLING TOWER FAN B STP/STRT CW34 #11 COOLING TOWER FAN D STP/STRT i CW35 #11 COOLING TOWER FAN F STP/STRT
~ CW36 #11 COOLING TOWER FAN H STP/STRT CW37 #12 COOLING TOWER FAN R STP/STRT .
CW38 #12 COOLING TOWER FAN T STP/STRT CW39 #12 COOLING TOWER FAN L STP/STRT !
CW40 #12 COOLING TOWER FAN N STP/STRT CW41 #12 COOLING TOWER FAN Q STP/STRT CW42 #12 COOLING TOWER FAN S STP/STRT CW43 #11 CT RISER VALVES, CW-3-1/4-1 CUOP CW44 #12 CT RISER VALVES, CW-3-2/4-2 CUOP '
DG04 - Y91 INVERTER TROUBLE ANN RESET NRMURES Page 34 of 111
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Monticello Nuclear G:nnrating Plant 1999 Four Year Simulator C:rtification Report Appendix 5: Remote Function List REMOTE DESCRIPTION RANGE STAWSI FUNCTION VALUE DG05 Y93 MAINTENANCE BYPASS SWITCH NRMUALT DG06 52-704 480V Y93 MBS SUP BKR OP/CL ;
DG07 52-804 480V Y91 SUP BKR OP/CL i
, DG08 52-710 480V #13 D OUTPUT BRK OP NRMUOP DG09 #13 DIESEL GENERATOR STP/STRT ED01 345 KV BUS VOLTAGE ~
311-379 ED02 345 KV/115 KV YARD TROUBLE ANNUN NRMUACK
. . ED03 345 KV BKR 8Nll CUOP l ED04 345 KV DISC 8NIO CUOP l ED05 2RS XFMR PRI DISC CUOP ED06 - 2R XFMR PRI SUPPLY BKR 3N4 CUOP ED07 2R XFMR ANN PANEL ACKNOWLEGE NRMUACK ED08 IAR XFMR PRI SUPPLY BKR 1N2 CUOP ED09 1AR XFMR PRI SUPPLY BKR IN6 CUOP ED10 1ARS XFMR PRI DISC CUOP ED11 1ARS XFMR PRI SUPPLY SOURCE 10/345KV i ED12 #8 XFMR PRI SUPPLY BKR IN4 CUOP ED13 #7 XFMR PRI SUPPLY BKR IN7 CUOP ED14 MAIN GENERATOR DISCONNECT CUOP ED18 RACK OT BKRS 152-101,201,301,4,01 NRMUOUT ED19 TRIP PUSHBUTTON-ACB 152-101 NRML/TRI
< ED20 CLOSE PUSHBUTTON ACB 152-101 NRMUCL ED21 TRIP PUSHBUTTON ACB 152-102 NRML/TRI ED22- CLOSE PUSHBUTTON ACB 152-102 NRMUCLO ED23 TRIP PUSHBUTTON ACB 152-201 NRML/TRI ED24 CLOSE PUSHBUTTON ACB 152-201 NRMUCLO ED25' TRIP PUSHBUTTON ACB 152-202 NRML/TRI m ED26 CLOSE PUSHBUTTON ACB 152-202 NRMUCLO
- ED27 TRIP PUSHBUTTON ACB 152-301 NRMUTRI ED28 CLOSE PUSHBUTTON ACB 152-301 NRMUCLO
, ED29 TRIP PUSHBUTTON-ACB 152-302 NRMUTRI ED30 CLOSE PUSHBUTTON ACB 152-302 NRMU C
- ED31 TRIP PUSHBUTTON ACB 152-401 NRML/ TRI ED32 CLOSE PUSHBUTTON ACB 152-401 NRMUL F i ED33 TRIP PUSHBUTTON ACB 152-402 NRMUCLU '
ED34 - CLOSE PUSHBUTTON ACB 152-402 NRMUTRI ED35 TRIP PUSHBUTTON - ACB 152-308 - 13-15 NRMUTRI ED36- CLOSE PUSHBUTTON - ACB 152-308 NRMUCLO ED37 TRIP PUSHBUTTON - ACB 152-408 14-16 NRMUTRI ED38 CLOSE PUSHBUTTON - ACB 152-408 NRMUCLO Page 35 of 111 4 .
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Monticello Nucl:ar Gantrating Plant f 1999 Four Yecr Simulator Csrtification Rrport Appendix 5: Remote Function List REMOTE STAWS/ j DESCRIPTION ' RANGE VALUE FUNCTION ED39 TRIP PUSHBUTTON - ACB 152-511 1 AR-15 NRMUTRI !
ED40 CLOSE PUSHBUTTON - ACB 152-511 NRMUCLO l ED41 TRIP PUSHBUTTON - ACB 152 610 1 AR-16 NRML/TRI ED42 CLOSE PUSHBUTTON - ACB 152-610 NRMUCLO l ED43 BUS 17/18 X-TIE - ACB 152-703 CUOP ED44 BUS 17 SUPPLY DISC X7B CUOP ED45 BUS 18 SUPPLY DISC X8B CUOP ED52 480 VAC LC 105 BKR 52-501 CUOP-ED53 480 VAC LC 105 ALT BKR 52-502 CL/OP ED54 480 VAC LC 106 PRI BKR 52-601 CUOP ED55 480 VAC LC 106 ALT BKR 52-602 CUOP ED56 480 VAC LC 107 PRI BKR 52-701 NRMUCLO ED57 480 VAC LC 107/108 BKR 52-711 NRMUOP ED58 480 VAC LC 108 PRI BKR 82-801 NRMUCLO ED59 480 VAC LC 107 PRI BKR 52-701 NRMUOP ED60 480 VAC LC 107/108 BKR 52-711 NRMUCLO -
ED61 480 VAC LC 108 PRI BKR 52-801 NRMUOP ED69 REST NON-ES MCC 131,132,141,142B NRMURES ED70 480 VAC MCC 131 SUP BKR 52-302 OP/CL ED71 480 VAC MCC 132 SUP BKR 52-303 OP/CL ED72 480 VAC MCC 133A SUP BKR 52-304 OP/CL ED73 480 VAC MCC 134 SUP BKR 52-308 OP/CL ED74 480 VAC MCC 141 SUP BKR 52-402 OP/CL ED75 480 VAC MCC 142A SUP BKR 52-403 OP/CL ED76 480 VAC MCC 142B SUP BKR 52-4231 OP/CL ED77- 480 VAC MCC 143A SUP BKR 52-404 OP/CL ED78 480 VAC MCC 144 SUP BKR 52-408 OP/CL ED79 SWING BUS TRANSFER BKR 52-3300 NRMUCL ED80 SWING BUS TRANSFER BKR 52-4300 NRMUCL -
ED81 LPCl SWING BUS MANUAL RESET NRMURES ED82 480 VAC MCC 133B SUP BKR 52-307 NRML/CL ED83 480 VAC MCC 143B SUP BKR 52-407 NRMUCL
. ED86 DIV i INVERT Y71 TRBLE ANN RESET NRMURES ,
ED87 DIV ll lNVERT Y81 TRBL ANN RESET NRMURES ED88 INST AC BUS YlO DISC SWITCH Y74 CUOP ED89 INST AC BUS Y20 AUTO XFER SWITCH NRMUEME ED90 INST AC BUS Y30 DISC SWITCH Y84 CUOP ED91- INST AC BUS Y70 DISC SWITCH Y75 CUOP ED92 INST AC BUS Y80 DISC SWITCH Y85- CUOP ED93 INST AC MANUAL BYPASS SWITCH Y73 NRMUALT Page 36 of 111
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Monticello Nucinar G:n rating Plant l 1999 Four Year Simulator Certification Report l l
l
- Appendix 5: Remote Function List REMOTE STAWSI DESCRIPTION RANGE FUNCTION VALUE ED94 INST AC MANUAL BYPASS SWITCH Y83 NRMUALT EG01 GENERATOR HYDROGEN PURITY 0-100 EG02 GENERATOR COND MON RESET NRMURES )
L EG03 GENERATOR HYDROGEN PRESSURE 0-60 l' EG04 Y-07, STATOR COOLING TEMP ADJUST 0-100 l
EG05 #1 GEN H2 SYSTEM TROUBLE ALARM NRMUACK EG06 REG V/HZ HIGH RELAY RESET VHZ NRMUTRI EG07 REG LOW GEN VOLT RELAY RESET 62NHZ NRMllTRI FP01 TRANSFORMER DELUGE RESET NRMURES FP02 DIESEL FIRE PUMP HAND SWITCH OFF AUTO / MAN FW01 FW-7-1 CON PMP DISCHARGE VALVE TCUOP FWO2 FW-7-2 CON PMP DISCHARGE VALVE TCUOP FWO3 FW-32 CON RECIR CV BYPASS (NC) TCUOP L FWO4 CONDENSATE DEMIN A OUT/lN l FWO5 CONDENSATE DEMIN B - OUT/IN i
FWO6 CONDENSATE DEMIN C OUT/IN FWO7 CONDENSATE DEMIN D OUT/IN FWO8 CONDENSATE DEMIN E OUT/lN FWO9 CON F/D SYS Hi DP/FLO BAL OVRD NRMURES FW10 AO-1740, CON FILT DEMIN BYPS VLV TCUOP FW11 FW-39 REJECT CV BYPASS (NC) TCUOP !
FW12 FW-38 MAN BL VLV/RE CV-1093A/B - TCUOP FW13 FW-44 MAKEUP CV BYPASS (NC) TCUOP FW14 FW-42 MAN BL VLV/RE CV1094A/B TCUOP FW15 FW-MO-1088 A BLK VLV LP HTR TCUOP FW16 FW-MO-1089 B BLK VLV LP HTR TCUOP FW17 FW-58-1 A BL V OTLT LP HTR TCUOP FW18 FW-58-2 B BL V OTLT LP HTR TCUOP FW19 FW-82-1 LOW FLO FW-CV DISCH VLV CUOP FW20 FW-82-2 LOW FLO FW-CV DIGCH VLV CUOP FW21 FW-88-1 CLNUP RCRC CNDSR FR LOOP T CUOP l FW22 FW-88-2 CLNUP RCRC CNDSR B LOOP TCUOP FW23 FW-88-3 CLNUP RCRC TO MAIN COND TCUOP FW24 FW-MO-1614 FW FR A HP HTRS BLK V TCUOP
- j. FW25 FW-MO-1615 FW-FR B HP HTRS BLK V TCUOP FW26 FW-98-1 REACTOR INJECTION VALVE UNULKOP FW27 FW-98-2 REACTOR INJECTION VALVE UNULKOP i FW28 COND STOR TNK CONDUCTIVITY CHNGE 0.1/10 l FW29 COND SERV WTR PMP #11 ST/ START
- FW30 COND SERV WTR PMP #12 ST/ START L
l Page 37 of 111 L
1 Monticello Nucirr Gan:rcting Plant l 1999 Four Yctr Simulator Cartification R:: port j Appendix 5: Remote Function List !
l REMOTE STATUS /
DESCRIPTION RANGE VALUE FUNCTION FW31 CST-89 SHTDWN COOL SUCT FIL IN V T CUOP FW32 CST-91 B LOOP LPCI RTN FIL LN V TCUOP FW33 CST-93 B LP CONT SPRAY FIL LN V TCUOP FW34 CST-95 A LP LPCI RTN FIL IN VLV T CUOP FW35 CST-83 PCV-2992 BYPASS VALVE CUOP FW36 CST-101-1 PCV-2458 BYPASS VALVE CUOP FW37 CST-101-2 PCV-2459 BYPASS VALVE CUOP FW38 DEMIN WATER TRANSFER PUMP #11 ST/ START FW39 DEMIN WATER TRANSFER PUMP #12 ST/ START FW40 COND DEMIN SYS TROUBLE ACK NRMUACK FW41 FILL CST FROM WASTE SAMPLE TANK CUOP FW42 DFCS INITIALIZATION OR RESTART NRMUINI FW43 FW LOW FLOW CV6-13 LOCAL MAN CN 1-100/0 FW44 FW REG.VLV CV6-12A LOCAL MAN CN 1-100/0 FW45 FW REG VLV CV6-12B LOCAL MAN CN 1-100/0 ,
HV01 V-EF-10 SMPLE HOOD EX FAN OFF/ON HV02 V-EF-24A/24B MAN TRANSFER SWITCH 24B/24A HV03 V-EF-24A/24B RX BLDG EX FAN CN OFF/ON
, HV04 V-EF-28 REFUELING POOL EXHAUST OFF/ON HV05 V-AC-10A RX BLDG SUP FAN OFF/ON HV06 V-AC-10B RX BLDG SUP FAN OFF/ON HV07 V-AH-4A REFUEL FLR SUP FAN OFF/ON HV08 V-AH-4B REFUEL FLR SUP FAN OFF/ON HV09 V-EF-11 TURBINE BLDG EX FAN OFF/ON HV10 V-EF-26 TURBINE BLDG EX FAN OFFION HV11 V-MX-1 SWITCH GEAR AREA FAN ST/ START HV13 V-MZ-5 COND AREA SUPPLY AIR ST/ START HV14 V-MZ-6 TURB BLDG SUPPLY AIR ST/ START "
HV15 V-EF-20 MAIN EXHAUST FAN HAND OFF/ AUTO HV16 V-EF-21 MAIN EXHAUST FAN HAND OFF/ AUTO HV17 V-EF-22 MAIN EXHAUST FAN HAND OFF/ AUTO HV18 V-EF-200R 22 LEAD FAN HANDSWITCH 20/22 HV19 C1004A/B RECOMB BLDG EXHAUST FAN 4A OFF/4B HV20 V-FU-3A FILTER UNIT FAN HAND OFF/ AUTO
, HV21 V-FU-3B FILTER UNIT FAN HAND OFF/ AUTO lA01 #11 AIR COM DUAL CNTRL SELECTOR HAND OFF/ AUTO IA02 #12 AIR COM DUAL CNTRL SELECTOR HAND OFF/ AUTO lA03 #11 COMPRESSOR MODE SWITCH HAND OFF/ AUTO lA04 #12 COMPRESSOR MODE SWITCH HAND OFF/ AUTO ,
lA05 #13 COMPRESSOR MODE SWITCH HAND OFF/ AUTO Page 38 of 111
~~ .. . -. - - .-. .- - ..- - - - - - -. - - - ..-.. .
Monticello Nucirr G::nerating Plant 1999 Four Yecr Simul: tor Certification Report Appendix 5: Remote Function List l
REMOTE STATUSI FUNCTION DESCRIPTION RANGE VALUE ;
IA06 CNTRL PNL SEQ SEL SWITCH 1/2/3 C-A-B ACB/BCA j l lA07 Al-38 INSTR AIR MAN ISOL VLV CUOP '
l lA08 Al-41 INSTR AIR MAN ISOL VLV CUOP lA09 #11 SERVICE AIR COMPRESSOR RE/ LOCAL lA10- #12 SERVICE AIR COMPRESSOR RE/ LOCAL IA11 AIR NITROGEN SELECTOR FOR DW AIR NTGN/ AIR I lA12 #11 COMP ECCS LD SHED BPS 14A/17A OUT/IN
, lA13 #12 COMP ECCS LD SHED BPS 14A/17B OUT/IN l
lA14 #13 COMP ECCS LD SHED BPS 14A/19B OUT/IN l MC01 MS-24-1 #11 AIR EJ PCV BYP NC 0-100 MC02 MS-24-2 #12 AIR EJ PCV BYP NC 0-100 i
MC03 MS-22-1/MS-23-1 #11 SJAE PCV INL CUOP ,
MC04 MS-22-2/MS-23-2 #12 SJAE PCV INL CUOP '
MC05 MAIN COND ROTARY VAC PMP P-3 STP/STRT '
MC06 MEC VAC PM SUC V OG-22-1/OG-22-2 0-100 MC07 #11 SJAE 1ST EL PRl/SEC GAS /STM CUOP MC08 #11 SJAE 2ND EL PRl/SEC GAS /STM CUOP MC09 #12 SJAE 1ST EL PRl/SEC GAS /STM CUOP MC10 #12 SJAE 2ND EL PRl/SEC GAS /STM CUOP !
MC11 OG-20/OG-21 LP SEAL DRAIN SJAE CUOP l
MS01 TSS-1 PRI STM/STMSEAL SYS IS VLV- CUOP MS02 CV-3133 MOIS SEP #11 D TNK #11 -6.5/24
- MS03 CV-1002 MOIS SEP #12 D TNK #12 -6.5/24 MSO4 CV-1004 MOIS SEP #13 D TNK #13 -6.5/24 l MS05 CV-3134 MOIS SEP #14 D TNK #14 -6.5/24 MS06 - CV-3127 MOIS SEP #11 D TNK #11 -6.5/24 l
MS07. CV-1001 MOIS SEP #12 D TNK #12 -6.5/24 MS08 CV-1003 MOIS SEP #13 D TNK #13 -6.5/24 MS09 CV-3132 MOIS SEP #14 D TNK #14 -6.5/24 MS10 INBOARD DC BYPASS JUMPER 16A-K69 OUT/IN MS11 INBOARD AC BYPASS JUMPER 16A-K70 OUT/IN MS12 OUTBOARD DC BYPS JUMPER 16A-K67 OUT/IN MS13 OUTBOARD AC BYPS JUMPER 16A-K68 N101 BYPASS LPRM A,B,C,D (XX-YY)(96) BYP/OPRT
- N105 SRM CHANNEL #24 GAIN ADJUSTMENT 0.5-1.5 N106 IRM CHANNEL #11 GAIN ADJUSTMENT 0.5-1.5 N107 IRM CHANNEL #12 GAIN ADJUSTMENT 0.5-1.5 N108 IRM CHANNEL #13 GAIN ADJUSTMENT 0.5-1.5 l
Page 39 of 111
Monticello Nucisar G:ntrating Plant 1999 Four Year Simulator Certification Report Appendix 5: Remote Function List REMOTE STAWS/
DESCRIPTION RANGE VALUE FUNCTION N109 IRM CHANNEL #14 GAIN ADJUSTMENT 0.5-1.5 N110 lRM CHANNEL #15 GAIN ADJUSTMENT 0.5-1.5 N111 IRM CHANNEL #16 GAIN ADJUSTMENT 0.5-1.5 N112 IRM CHANNEL #17 GAIN ADJUSTMENT 0.5-1.5 N113 IRM CHANNEL #18 GAIN ADJUSTMENT 0.5-1.5 N114 APRM CHANNEL #1 GAIN ADJUSTMENT 0.5-1.5 N115 APRM CHANNEL #2 GAIN ADJUSTMENT 0.5-1.5 N116 APRM CHANNEL #3 GAIN ADJUSTMENT 0.5-1.5
- N117 APRM CHANNEL #4 GAIN ADJUSTMENT 0.5-1.5 N118 APRM CHANNEL #5 GAIN ADJUSTMENT 0.5-1.5 N119 APRM CHANNEL #6 GAIN ADJUSTMENT 0.5-1.5 N120 TIP MACHINE SELECT 11 12/13 OG01 PCV-7496A BYP IN OV PRESS C VLV 0-30 OG02 PCV-74968 BYP IN OV PRESS C VLV .5-30.5 OG03 OG-52-1 EDUCTOR PRESS RELIEF IS T CUOP OG04 OG-52-2 EDUCTOR PRESS RELIEF IS T CUOP OG05 OG-50 'I RECOMB GAS INLT ISOL VLV T CUOP OG06 OG-50-2 RECOMB GAS INLT ISOL VLV T CUOP OG07 OG-55-1 RECOMB COND GAS OTLT VLV TCUOP OG08 OG-55-2 RECOMB COND GAS OTLT VLV T CUOP OG09 AT-7731A H2 ANALYZER OFF/ON OG10 AT-7731B H2 ANALYZER OFF/ON OG11 AT-7553A H2 ANALYZER OFF/ON OG12 AT7553B H2 ANALYZER OFF/ON OG13 - AT-7552A H2 ANALYZER OFF/ON OG14 AT-7552B H2 ANALYZER OFF/ON OG15 F-2801 A GAS COMPR SUCT FILTER OUT/IN OG16 F-2801B GAS COMPR SUCT FILTER OUT/IN OG17 OG-124-1 GAS COMPR INLT ISOL CUOP OG18 OG-124-2 GAS COMPR INLT ISOL CUOP OG19- OG-74-1 GAS COMPR OTLT ISOL CUOP OG20 OG-74-2 GAS COMPR OTLT ISOL- CUOP OG21 C-1002A COMPR COOL WTR CHILLER ST/ START OG22 C-1002B COMPR COOL WTR CHILLER ST/ START OG23 OG-90 FCV-7676 BYPASS VLV T CUOP OG24 OG-88 FCV-7676 ISOL VLV CUOP OG27 PC-7497A SETPOINT ADJUST 0-350 OG28 PC-74978 SETPOINT ADJUST 0-350 OG29. MS-51-1 MAN STM ISOL TO RECOMB T CUOP OG30 MS-51-2 MAN STM ISOL TO RECOMB T CUOP Page 40 of 111
-. - - __. _- .- - . - --- -.. - ~ . - . - - . . . _ _ - . -.. . _
. Monticello Nucl::r G:nnrating Plant 1999 Four Ye:r Simulator Certification Report Appendix 5: Remote Function List REMOTE STAWSI DESCRIPTION RANGE FUNCTION VALUE OG31 MS-53-1 STM TO RECOMB PREHEATER T CUOP OG32 MS-53-2 STM TO RECOMB PREHEATER TCUOP OG33 AO-2562A COND DRIP TANK VLV CUOP OG34 AO-2562B COND DRIP TANK VLV CUOP OG35 RADWASTE ALARM NRMUACK PC01 DWV-13 N2 GAS SUPPLY VALVE T CUOP PC02 ROOTS BLOWER #1 ST/ START PC03 ROOTS BLOWER #2 ST/ START PC04 02 ANALYZER SYSTEM OUT/IN PC05 N2-1 ROOTS BLWR MAN IS VLV-DRYWL CUOP PC06 DWV-14 N2 VPRZR GAS DISCH VLV CUOP PC07 DWV-29 N2 VPRZR LIQ INLT VLV TCUOP PC08 PRIM CONT OXYGEN SAMPLING DRYTTOR PC09 VENT ISOL SIG BYPASS INLOCK-JUMP REM / INST PC10 DRYWELL CAM TROUBLE ANNUNCIATOR NRMUACK PC11 SGTS TRAIN A AUTO INIT BYPSS R1A REM / INST PC12 SGTS TRAIN B AUTO INIT BYPSS R1B REM / INST PC13 GROUP 11 ISOLATION BYPASS REM / INST PC14 MSIV CLOSURE /COND VAC SCRAM REM / INST BYPASS PC15 GROUP 11 ISOLATION BYPASS TORUS DR REM / INST PP01 SET A BKR CN1 A-CU2A,1A-OP/2A-CL NRMUALT PP02 SET B BKR C1B-CU28,18-OP/28-CL NRMUALT PP03 RX LO-LO WTR LVL ISOL RLY JUMPER REM / INST PPO4 RPS MG SET A LOCAT RESET NRML/TRI PP05 RPS MG SET B LOCAL RESET NRMUTRI RC01 RCIC MECH OVERSPEED TRIP NRMURES RC02 RCIC-10 RCIC ST/CHCK VLV POS ADJ 0-100 RC03 RCIC-32 RCIC PMP SUCTION VALVE CUOP RC04 RCIC MO-2075,2076,2078 AUTO /OP B REM / INST RH01 S/D CL SUP INBD ISOL V MO-20298R CUOP RH02 S/D CL SUP INBD ISOL V MO-20291N OUT/IN RH03 S/D CL SUP lNBD ISOL V MO-2030lN OUT/IN RH04. COND SUP-RHR IS VLV RH-18-1 LC ULK/LKCL RH05 COND SUP-RHR IS VLV RH-18-2 LC ULK/LKCL RH06 RHR SW-RHR LPCI S V RHR-SW-12/14 CUOP l RH07 #11 RHR HX IN/OT I V RHR-4-1/5-1 CUOP
. RH08 #12 RHR HX IN/OT I V RHR-4-2/5-2 CUOP RH09 #11 RHR HX CORROSION 0-15 RH10 #12 RHR HX CORROSION 0-15 i
Page 41 of 111
Monticello Nucitar Gennrating Plant 1999 Four Yecr Simulator Certification Raport Appendix 5: Remote Function List i l
REMOM STAWSI DESCRIPTION RANGE j FUNCTION VALUE <
RH11 RHR-WST-23 IS V MO-2032 BRK 4211 OP/CL i
RM01 SJAE SAMPLING SYSTEM A OUT/IN RM02 SJAE SAMPLING SYSTEM B OUT/IN RR01 RX RECIRC DC OIL PUMP #11 STOP NRMUSTA RR02 RX RECIRC DC OIL PUMP #12 STOP NRMUSTA RR03 #11 RX RECIRC GEN CK RELAY RESET NRML/TRI RR04 #12 RX RECIRC GEN LK RELAY RESET NRML/TRI RR05 #11 RX RECIRC AUX LK RELAY RESET NRMUTRI RR06 #12 RX RECIRC GEN AUX LK RLY RES NRMUTRI RR09 #11 RX RECIRC SC TUBE PWR SWITCH OFF/ON RR10 #12 RX RECIRC SC TUBE PWR SWITCH OFF/ON RR11 SLC BORON MIX CONCENTRATION 0-100 RR12 #11 SCOOP TUBE MAN ADJUSTMENT 0-100 RR13 #12 SCOOP TUBE MAN ADJUSTMENT 0-100 RR14 TRIP PUSHBUTTON #11 REC DR MTR NRML/TRI BRKR RR15 CLOSE PUSHBUTTON #11 RE DR MTR NRMUCL BRKR RR16 TRIP PUSHBUTTON #12 RE DR MTR NRML/TRI BRKR RR17 CLOSE PUSHBUTTON #12 RE DR MTR NRMUCLO BRKR RUO1 #11 RWCU FIL DEMIN FLOW CONTROL 0-100 RUO2 #12 RWCU FIL DEMIN FLOW CONTROL 0-100 RUO3 #11 RWCU FILTER DEMIN OUT/IN RUO4 #12 RWCU FILTER DEMIN OUT/IN RUO5 CLEANUP FILTER DEMIN ALARM NRMUACK RUO6 RC-103 RWCU HX BYPASS VALVE T CUOP RUO7 RC-102 RWCU REGEN HX BYPASS VLV TCUOP RUO8 RC-101 RWCU REGEN HX OUTLET VLV T CUOP RUO9 BREAKER 3201 FOR MO-2401 OP/CL RWO1 ROD WORTH MIN CNTL ROD SEQ A/B SEA /SEB RWO2 RW MINIMlZER INITIALIZED NO/YES RWO3 RWM SYSTEM DIAGNOSTIC OFF/ON PUSHBUTTON SLO 1 SBLC LEVEL CALIBRATION . 0.5-1.5 SLO 2 A=X P-10 P, DM 56C LS/X P-1 C LS,DM 560P B A/B SWO1 SW46-2 TURB L OIL CLR MAN IS VLV 0-100 POS SWO2 SW145/147 EM WTR-COND A HTWL MAN CUOP SWO3 DM-111 DEMIN MKP-RBCCW SURGE TNK POS CUOP Page 42 of 111
Monticello Nucle r G:n: rating Plant 1999 Four Ye:r Simul tor C:rtific: tion Report Appendix 5: Remote Function List REMOTE STATUS /
DESCRIPTION RANGE FUNCTION - VALUE SWO4 SW125-1 OTLT FROM 11 MGST OlL CO 0-100 i
SWO5 SW125-2 OTLT FROM 12 MGST OIL CO 0-100 POS SWO6 RBCC-26 RBCCW SRG .TNK DRAIN VLV CL/OP SWO7 RHR-SW PMP11 ECCS LD SD BYPS14A OUT/IN l SWO8 RHR-SW PMP12 ECCS LD SD BYPS14A - OUT/IN SWO9 RHR-SW PMP13 ECCS LD SD~BYPS14A OUT/IN SW10 RHR-SW PMP14 ECCS LD SD BYPS14A OUT/IN SW11 SW PUMP #11 ECCS LD SD BYPS14A OUT/IN SW12 SW PUMP #12 ECCS LD SD BYPS14A OUT/IN SW13 RBCCW PMP11 ECCS LD SD BYPS14A OUT/IN l SW14 RBCCW PMP12 ECCS LD SD BYPS14A OUT/IN TUO1 #11 EPR OIL PUMP STOP/RUN
-TUO2 #12 EPR OIL PUMP STP/ AUTO TUO3 MAIN TUR LUB OIL RES LEVEL ADJ 1-10000 TUO4 SET TURB METAL TEMP TO OP IN VLV 80-600 TU0S MAIN TURB AUX OIL PUMP LOCKOUT NRML/RES Page 43 of 111
Monticsilo Nucinar G:nnrating Plant '
1999 Four Year Simulator Certification Report Appendix 6: Certified Malfunction List ;
l MALF TITLE ADJUSTABLE RATE !
AN01 ANNUNCIATOR FAILURE NO i
AP01 SAFETY RELIEF VALVE Fall OPEN NO I AP02 INADVERTANT ADS ACTUATION NO l AP03 SAFETY RELIEF VALVE LEAK 0 - 100,000 lbm APO4 SRV FAILURE TO LIFT - SAFETY MODE NO AP05 SRV FAILURE TO RESEAT NO 1
AP06 ADS AUTOMATIC INITIATION FAILURE NO l AP07 SPURIOUS ADS ACTUATION NO l
CH01 CONTROL ROD DRIFTS OUT NO CH02 CONTROL ROD STUCK NO CH03 CONTROL ROD UNCOUPLED NO CH04 CRD ACCUMULATOR TROUBLE NO CH05 CONTROL ROD SCRAM NO CH07 CRD FLOW CONTROL VALVE FAILURE NO CH08 CRD PUMP BREAKER TRIP NO CH11 RMCS TIMER FAILURE NO l CH12 CONTROL ROD FAILURE TO DE-SELECT NO CH13 FAILURE OF RX MANUAL CONTROL NO
.CH16 FAILURE TO SCRAM NO Page 44 of 111
Montic:llo Nucl ar G:n:r;1 ting Plant 1999 Four Ye:r Simulator Certification Report Appendix 6: Certified Malfunction List MALF TITLE ADJUSTABLE RATE CH18 AW/S FAILURE - ARI VALVE FAILURE NO CH19 MULTIPLE STUCX RODS NO CH22 SDV VENT / DRAIN VALVES Fall OPEN NO CH23 CRDH PUMP LOW SUCTION PRESS. TRIP NO CS01 CORE SPRAY PUMP NO.11 (12) TRIP NO CS02 CORE SPRAY OTBD VLV FAILS SHUT NO CWO2 CIRC WATER PUMP TRIP NO CWO4 CIRC WTR PUMP NO.11 (12) PIT FLOOD NO CWO8 CONDENSER PIT FLOOD NO DG01 DIESEL GENERATOR TRIP NO DG02 DG #11(12) FAILURE TO START NO DG04 NO.13 DIESEL GENERATOR TRIP NO ED04A LOSS OF MAIN TRANSFORMER NO ED048 LOSS OF 1 AR TRANSFORMER NO ED04C LOSS OF 1R TRANSFORMER NO ED04D LOSS OF 2R TRANSFORMER NO EDO4E LOSS OF 2RS TRANSFORMER NO ED04F LOSS OF 1 ARS TRANSFORMER NO ED05A 4160V BUS LOCKOUT NO.11 NO Page 45 of 111
_J
Monticello Nucl:tr G:nnrcting PI:nt 1999 Four Year Simulator Certification R: port Appendix 6: Certified Malfunction List MALF TITLE ADJUSTABLE RATE ED058 4160V BUS LOCKOUT NO.12 NO ED05C 4160V BUS LOCKOUT NO.13 NO ED05D 4160V BUS LOCKOUT NO.14 NO ED05E 4160V BUS LOCKOUT NO.15 NO
-EDOSF 4160V BUS LOCKOUT NO.16 NO ED06A LOSS OP LOAD CENTER 101 NO ED06B LOSS OF LOAD CENTER 102 NO ED06C LOSS OF LOAD CENTER 103 NO ED06D LOSS OF LOAD CENTER 104 NO ED06G LOSS OF LOAD CENTER 109 NO ED07A LOSS OF 250 V DC DIV I BATTERY NO ED078 LOSS OF 250 V DC DIV ll BATTERY NO ED08A LOSS OF 125 V DC DIV I BATTERY NO ED08B LOSS OF 125 V DC DIVil BATTERY NO ED09A LOSS OF 24 V DC BATTERY NO.15 NO I
ED09B LOSS OF 24 V DC BATTERY NO.14 NO J l
ED10A LOSS OF UPS Y10 NO ED10B LOSS OF UPS Y30 NO ED10C LOSS OF UPS Y70 NO Page 46 of 111
l Monticello Nucirr G n: rating Pl:nt 1999 Four Year Sirnulator Certification Report Appendix 6: Certified Malfunction List l MALF TITLE ADJUSTABLE RATE
, ED10D LOSS OF UPS Y80 NO l
ED11A LOSS OF INST AC DISTRIBUTION Y-20 NO ED118 LOSS OF INST AC DISTRIBUTION Y-25 NO 1
)
l ED11C LOSS OF INST AC DISTRIBUTION Y-26 NO '
l ED12 LOSS OF OFF-SITE POWER NO I i
l ED16 2R TRANSFORMER COOLING FAN FAILURE NO I
ED20 Y91 INVERTER FAILURE NO ED06 OPEN 3N4 @ POWER (2R SUPPLYING HOUSE NO l
LOADS) (REMOTE FUNCTION)
EG01 LOSS OF STATOR WATER COOLING NO EG02 STATOR COOLING PUMP TRIP NO EG03 GENERATOR LOCKOUT NO EG08 GENERATOR HYDROGEN LEAKAGE 0 - 100 %
EG07 GENERATOR MAX EXCITATION NO FWO3 CONDENSATE PUMP TRIP NO
~IWO4 CONDENSATE PUMP HIGH VlBRATION NO FWO6 COND RECIRC VALVES Fall OPEN/ CLOSED NO FWO8 CONDENSATE DEMIN HIGH D/P NO FW10 DEMIN RESIN RETENTION FAILURE 100% = 50% of demin resin Page 47 of 111
Montic:;llo Nucl2ar G:n: rating Plant 1999 Four Year Simulator Certification Report Appendix 6: Certified Malfunction List MALF TITLE ADJUSTABLE RATE FW11 EXHAUST HOOD SPRAY FAILS CLOSED NO FW14 LP FEEDWATER HEATER TUBE LEAK 100% = 150% normal drain flow FW15 REACTOR FEED PUMP HIGH BEARING TEMP 100% = 200 deg increase FW16 REACTOR FEED PUMP TRIP NO FW17 RX FEEDPUMP RECIRC VLV FAILURE NO FW19 HIGH PRESS FW HEATER TUBE LEAK 100% = 100% normal drain flow FW20 FWRV LOSS OF AIR NO FW21 FAIL FEED REG VLV M/A CONTROLLER NO FW23 FAIL OF DFC SHIFT SINGLE ELEMENT NO FW24 FAIL OF FW FLOW TRANS FT-6-50-A 0 - 100%
FW25 FW PIPE A(B) BREAK OUTSIDE PC 100% = 10 inch break FW26 FW LOOP A(B) BREAK INSIDE PC 100% = 14 inch break HP01 HPCI AUTO INITIATION NO R- CLOSES CHECK VALVE HP-10 NO HP01 HP02 HPCI AUTO-START FAILURE NO HP03 HPCI TURBINE TRIP NO HPO4 HPCI SPEED CNTRL FAILS HIGH (LOW) NO I
l Page 48 of 111 l
[ l
I i
Monticello Nucle:r G:n:rcting Plant 1999 Four Year Simulator Certification Report
^
Appendix 6: Certified Malfunction List MALF TITLE ADJUSTABLE RATE '
j HP05 NO HPCI AUTO ISOLATION (GROUP 5)
- - HP06 LOSS OF COOLING TO HPCI GLAND SEAL NO i CONDENSER AND L.O. COOLER HP07 HPCI STEAM LINE LEAK 100% = 4 inch break IA01 SERVICE AIR COMPRESSOR TRIP NO IA02 SERVICE AIR ISOLATION NO lA03 AIR COMP FAllTO LOAD (UNLOAD) NO IA04 INST AIR HDR FAILURE - RX BLDG 0 = 100%
IA06 DECREASING SERVICE AIR PRESSURE NO MC01 LOW PRESSURE CONDENSER TUBE LEAK 100% = 500 gpm MCO2 ADJUST MS-24-1 TO ALTER A/E STM FLOW 0 = 100%
MCO3 CONDENSER AIR IN-LEAKAGE 100% = 2000 scfm MC05 AIR EJECTOR SUCTION VALVES CLOSURE NO MS01 MSIV 80-A(B,C,D) INBD FAILS CLOSED NO MS02 MSIV 86-A(B,C,D) OTBD FAILS CLOSED NO MS03 MSL "B" RUPTURE IN TUNNEL 0 = 100% pipe break MSO4 MSL RUPTURE IN DRYWELL small 100% = 3 inch large 100% = 18 inch MS05 - MSIV 80-A(B,C,D) INBD FAIL TO CLOSE NO
- MS06 MSIV 86-A(B,C,D) OTBD Fall TO CLOSE NO Page 49 of 111
4 Menticello Nuclasr G:nsrating Plant 1999 Four Year Simulator Certification Report Appendix 6: Certified Malfunction List MALF TITLE ADJUSTABLE RATE MS07 MSIV DISC SEPARATION FROM STEM NO MS08 TURBINE STEAM SEAL FAILURE NO MSO9 STM PACKING EXH BLOWER MTR TRIP NO MS10 Fall OF MS FLOW TRANS 6-51 A 0 - 100 %
~
- MS11 MSL RUPTURE IN TURBINE BLDG 100% = 10 inch break N101 SRM FAILS DOWNSCALE .NO ,
l N102 SRM FAILS FULL SCALE. NO N.103 SRM. INOP NO NIO5 IRM DOWNSCALE NO N106 IRM FULLSCALE NO N107 IRM INOP NO N109 IRM CHANNEL SPURIOUS INDICATION NO
. N112 APRM DOWNSCALE NO N113 - APRM FAILS FULLSCALE NO
^
N114 APRMINOP NO ,
I N115 RBM DOWNSCALE NO l
- N116 RBM UPSCALE NO l
N117 RBMINOP NO l OG07 RECOMB TRN LOW STM FLOW SD NO j l
Page 50 of 111-l
Monticello Nucirr Gen: rating Plant 1999 Four Year Simulator Certification Report
~
l Appendix 6: Certified Malfunction List MALF TITLE ADJUSTABLE RATE 1
! OG30 CLOSES "B" RECOMB. STEAM (REMOTE) NO l
i PC01 SBGT EXH FAN V-EF-17A(B) TRIP NO PC02 SPURIOUS SEC. CONTAINMENT ISOLATION NO !
PCOS OPEN TORUS DRAIN (REMOTE) NO PC07 TORUS TO DRYWELL VACUUM BREAKER NO I
PC09 SRV RV2-71 A (B-H) LINE BREAK NO PC11 RX BLDG DP POSITIVE NO POO1 SPDS FAILURE NO PP01 LOSS OF RPS MG SET A (B) NO PP03 RPS SUBCHANNEL FAILURE NO PPO2 MSL HIGH FLOW SETPOINT 80 - 101 % ,
(VARIABLE SETPOINT)
PPO4 RPS SUBCHANNEL AUTO SCRAM NO-PP05 SPURIOUS GP 1 ISOL SUBCHAN TRIP NO t DP06 FAILURE OF MODE SW TO SCRAM NO OVR MANUAL SCRAM PUSHBUTTON FAILURE NO RC01 RCIC AUTO-START FAILURE NO RC02 RCIC AUTO INITIATION NO RC02 RCIC OVERSPEED SETPOINT ADJUSTMENT 4000 - 6200 rpm Page 51 of 111
. . . - . - - .. . . . _ . . - - .. - - - - . - - _= . . .. - . - . - - . .
Monticello Nuciser G:n rating Plant -
1999 Four Year Simulator Certification Report Appendix 6: Certified Malfunction List MALF TITLE ADJUSTABLE RATE RC03 RCIC TURBINE TRIP NO RC03 CLOSE RCIC PUMP SUCTION (REMOTE) NO RC04 RCIC ISOLATION SIGNAL NO I
RC05 RCIC SPEED CONTROL FAILURE NO RC06 RCIC LUBE OIL COOLER LOW SUPPLY NO RC07 RCIC STEAM LINE LEAK 100% = 2 inch break RC08 FAILURE OF GROUP 5 ISOLATION NO RH01 RHR PUMP TRIP NO
- RH02 RHR SYS 11(12) HEAT EXC TUBE LEAK NO RH02 FAILURE OF LPCI (INBD)INJ VALVE NO RHOS RHR MIN FLOW VALVE FAILS OPEN NO.
RH04 RHR SD COOLING SUPPLY ISO SIGNAL- NO RH06 RHR PUMP MIN FLOW VALVE FAILS SHUT NO RH07 CNTMT SPRAY VLV ISOL FAILURE NO RM01 PROCESS RADIATION MONITOR UPSCALE 0 - 100% full scale !
RM02 PROCESS RADIATION MONITOR DWNSCL NO RM03 AREA RADIATION MONITOR HIGH 0 - 100% full scale RR01A RX RECIRC LOOP A BREAK (SMALL) 100% = 3 inch break RR01B RX RECIRC LOOP B BREAK (SMALL) 100% = 3 inch break Page 52 of 111
Monticello Nucisar G:n: rating Plant l
1999 Four Year Simulator Certification Report j
Appendix 6: Certified Malfunction List MALF TITLE ADJUSTABLE RATE l
RR02 RECIRC JET PUMP RISER BREAK 100% = 10 inch break RR03A RX RECIRC LOOP A BREAK (LARGE) 1 - 100% = 10 - 28 inch break RR03B RX RECIRC LOOP B BREAK (LARGE) 1 - 100% = 10 - 28 inch break RR04 INST LINE RUPTURE INSIDE DRYWELL NO RR05A RX RECIRC PUMP A LOCKOUT- NO RR05B RX RECIRC PUMP B LOCKOUT NO RR06A RX RECIRC PUMP A SElZURE NO RR06B RX RECIRC PUMP B SElZURE NO RR07- RECIRC PUMP MTR BEARING TEMP HIGH 100% = 100 deg F rise RR09 RX RECIRC PUMP RUN AWAY NO RR10 RECIRC MG FIELD BREAKER TRIPS OPEN NO RR11 RX RECIRC PMP INCOMPLETE START NO SEQUENCE RR13. RECIRC MG MANUAL SCOOP TUBE 0 - 100%
ADJUSTMENT (REMOTE)
'RR13 RECIRC SPEED CONTROL SIGNAL FAILURE NO
, RR15 RX RECIRC SYS TOTAL FLOW INST FAILURE NO RR16- REClRC PUMP LOWER SEAL FAILURE 100% = 1.1 gpm Page 53 of 111
Monticello Nucl:ar Gannrating Plant 1999 Four Year Simulator Certification Report Appendix 6: Certified Malfunction List MALF TITLE ADJUSTABLE RATE RR17 RECIRC PUMP UPPER SEAL FAILURE 100% = 1.1 gpm RR18 INSTRUMENTED JET PUMP FAILURE NO RR19 NON-INSTRUMENTED JET PUMP FAILURE NO RR20- SPURIOUS ATWS TRIP NO RR22 RECIRC LUBE OIL PUMP TRIP NO RR23 ATWS FAILURE: RECIRC MG FIELD BKRS Fall NO TO TRIP RR25 FAILURE OF NR LEVEL TRANS. (LT-6-52A/B) 0 - 100% full scale RR27 RCP MANUAL SPEED CNTRL FAIL LOW NO RR28 RPV LEVEL VARIABLE LINE BREAK 100% = 5 gpm RUO1 RWCU PUMP TRIP NO RUO3 . NON-REGEN HEAT EXCH HIGH OUTLET 100% = no cooling TEMPERATURE RUO7. RWCU SUCTION PIPE BREAK 100% = 4 inch break RWO1 RWM EQUIPMENT FAILURE: CONTINUOUS ROD NO BLOCK RWO2 ROD WORTH MINIMlZER LPSP FAILURE NO RX01 FUEL FAILURE 100% = 100 rem increase RX03 REACTOR CORE POWER OSClLLATIONS NO SLO 1- SBLC PUMP TRIP NO Page 54 of 111
Monticello Nuclear G::n=rcting Pl:nt 1999 Four Yccr Simul: tor Certification Report
- l. Appendix 6: Certified Malfunction List l
l l- MALF TITLE ADJUSTABLE RATE i SLO 3 SBLC SQUlB VALVE FAILS CLOSED NO 1
SWO1 RBCCW PUMP TRIP NO l
SWO2 RBCCW LEAK IN DRYWELL 100% = 5 gpm l- SWO3 SERVICE WTR PMP TRIP NO l
SWO4 ESW/ EFT ESW PUMP TRIP NO SWO5 RHRSW PUMP TRIP NO TC02 TURBINE MASTER TRIP NO
-TC04 ELEC PRESS REGULATOR FAILURE NO
.TC05 MECH PRESS REGULATOR OSCILLATIONS NO TC06 TURBINE BYPASS VLV STUCK NO l l
TC07 TURBINE BYPASS VALVE FAILURE 100% = full open TC08 TURBINE CONTROL VALVE FAILURE 100% = full open TC09 TURBINE STOP VALVE FAILS CLOSED NO TC10 TURBINE FAILURE TO TRIP NO TC11 TURBINE GENERATOR RUNBACK FAILURE NO TUO1 EPR OIL PUMP TRIP NO TUO3 TURBINE BEARING HIGH VIBRATION 0 - 10% = 3.3 mils TUO5 LOSS OF TURBINE BEARING OIL PRESSURE 100% = 150 deg F increase l
Page 55 of 111
Monticello Nucl:ar Generating Plant -
1999 Four Year Simulator Certification R: port Appendix 7: Protected initial Conditions R DESCRIPTION APRM LOAD PRESS CORE
%PWR MWE (PSIG) LIFE 101 READY FOR S/U - MOST SYSTEMS SECURED 0 0 0 MOL 102 READY FOR CONTROL ROD WITHDRAWAL 0 0 0 MOL 103 READY FOR CONTROL ROD WITHDRAWAL 0 0 0 EOL 104 REACTOR STARTUP- NEAR CRITICAL 0 0 0 BOL 105 - REACTOR STARTUP - NEAR CRITICAL 0 0 0 EOL 106 HEATUP IN PROGRESS - 195 degrees 0.1 0 7 BOL 107 HEATUP IN PROGRESS -475 degrees 2.5 0 552 BOL 108 PRIOR TO MODE SWITCH TO RUN 6.2 0 903 BOL 109 READY TO ROLL TURBINE 16.5 0 924 BOL
-110 READY TO LOAD GENERATOR 17.9 0 927 BOL 111 100% ROD PATTERN - MIN RECIRC FLOW 64- 372 945 BOL 112 100% POWER - POWER ASCENTION COMPLETE 100 625 1003 BOL 113 100% POWER - FALL - XE CONC. INCREASING 100 626 1003 BOL 114 100% POWER-WINTER CONDITIONS 100 637- 1000 MOL 115- 100% POWER- FALL- EQUILIBRIUM XE 100 622 1000 EOL 116 100% POWER - REQUAL TRAINING SPECIFIC 100 622 1000 EOL 117. 75% POWER - SPRING / FALL 75 459 956 EOL 118 S/D IN PROGRESS - MIN RECIRC FLOW 59 355 940 EOL-119 S/D IN PROGRESS - RODS IN SEQUENCE 37 204 922 EOL 120 '100% POWER - BACKUP REQUAL CONDITIONS 100 625 1000 EOL-121 REQUALIFICATION DEVLOPMENT IC 69' 416 965 BOL
'122 STARTUP - 145 PSIG BYPASS VALVE at 80% 2.0 0 145 EOL l
Page 56 of 111 !
l
Monticello Nucl:ar Gan: rating Plent 1999 Four Year Simulator Certification Report Appendix 8: Certification Test Abstracts
- TEST TITLE:
,- -Plant Startup (Cold to Hot Standby), Test NPE01 revision 8 DESCRIPTION:-
A normal reactor startup was performed per C.1 Plant Startup.
TEST FREQUENCY:
Test performed annually 1995 - 1998
REFERENCE:
ANSI /ANS 3.5 Section 3.1.1 - Normal Plant Evolutions INITIAL CONDITIONS:
- The simulator was in cold shutdown condition ready for control rod withdrawal.
DATA COLLECTION METHOD (S):
Simulator data was recorded on the Startup Checklist 2167 (checklist not filed with test) l l
TEST PROCEDURE:
- 1. Perform a reactor startup to ready to roll turbine condition in accordance with C.1_ Plant Startup and Startup Checklist #2167.
- 2. Note any discrepancies in the Comments section of this test.
FINAL CONDITIONSIDURATION OF TEST:
The reactor is at rated temperature and pressure ready for turbine roll.
BASELINE REFERENCE DATA: ,
C.1 Plant Startups C.2 Power Operation Startup Checklist 2167 i
Page 57 of 111
Monticello Nuclear G:n rating Plant 1999 Four Year Simulator Certification Report Appendix 8: Certification Test Abstracts TEST DEFICIENCIES / CORRECTIVE ACTIONS:
, None EXCEPTIONS TO ANSI /ANS-3.5-1985 TAKEN:
None l'
.s Page 58 of 111
' Monticello Nucl=r G:ntrating PI:nt L 1999 Four Year Simulator Certification Report Appendix 8: Certification Test Abstracts TEST TITLE:
Plant Startup (Hot Standby to Rated Power), Test NPE02 revision 8 DESCRIPTION:
A normal reactor startup was continued from test NPE03 per C.1 Plant Startup, C.2 Power Operations and Startup Checklist 2167 from cold shutdown to rated power.
TEST FREQUENCY:
Test performed annually 1995 -1998 p
REFERENCE:
- ANSI /ANS 3.5 Section 3.1.1 - Normal Plant Evolutions E . INITIAL CONDITIONS:
L l The reactor at rated temperature and pressure with the generator on line at L minimum load.
DATA COLLECTION METHOD (S):
1 Simulator data was recorded on the Startup Checklist 2167 (checklist not filed L with test).
l
!' - TEST PROCEDURE:
- 1. Continue the plant startup from test NPE03 with generator on line to 100%
rated power.
1
- 2. Note any discrepancies in the Comments section of the test.
FINAL CONDITIONS / DURATION OF TEST:
l The simulator was at 100% of rated power.
BASELINE REFERENCE DATA:
C.1 Plant Startup L
[ Page 59 of 111 L
Monticello Nucl:ar G:n rating Plant 1999 Four Yo:r Simulator Certification R: port Appendix 8: Certification Test Abstracts C.2 Power Operation TEST DEFICIENCIES / CORRECTIVE ACTIONS:
None EXCEPTIONS TO ANSI /ANS-3.5-1985 TAKEN:
None a
l Page 60 of 111
L Monticello Nuclear Gen: rating Pitnt l 1999 Four Yecr Simulator Ctrtification R: port Appendix 8: Certification Test Abstracts TEST TITLE:
l Turbine Startup to Generator Synchronization, Test NPE03 revision 8 DESCRIPTION:
A normal reactor startup was continued from test NPE01 per C.1 Plant Startup and C.2 Power Operations. .
L TEST FREQUENCY:
Test performed annually 1995 - 1998
REFERENCE:
ANSI /ANS 3.5 Section 3.1.1 - Norrnal Plant Evolutions INITIAL CONDITIONS:
The reactor is at rated temperature and pressure ready for turbine roll.
DATA COLLECTION METHOD (S):
l Simulator data was recorded on the Startup Checklist 2167 (checklist not filed with test).
1 TEST PROCEDURE: l I
- 1. Perform a turbine startup and synchronize the generator to the grid.
- 2. Note any discrepancies in the Comments section.
FINAL CONDITIONS / DURATION OF TEST:
The generator was on line at minimum load.
BASELINE REFERENCE DATA:'
C.1 Plant Startup C.2 Power Operation Page 61 of 111 4
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L None EXCEPTIONS TO ANSI /ANS-3.5-1985 TAKEN:
None f
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Page 62 of 111 r.4 , -
, . Montissilo Nucirr G:nsrating Plant l 1999 Four Yerr Simulator Certification Report Appendix 8: Certification Test Abstracts TEST TITLE:
Reactor Trip Followed by Recovery to Rated Power, Test NPE04 revision 8
! DESCRIPTION:
l l The Reactor was scrammed from 100% power with all immediate and subsequent scram actions performed per C.4-A, Reactor Scram. A reactor startup to Hot Standby was performed per C.1 Plant Startup; subsequently, reactor power was increased to 100% of rated conditions.
TEST FREQUENCY:
Test performed annually 1995 - 1998
REFERENCE:
ANSI /ANS 3.5 Section 3.1.1 - Normal Plant Evolutions INITIAL CONDITIONS:
100% Reactor power, all conditions normal.
DATA COLLECTION METHOD (S):
The test was conducted in accordance with approved plant procedures; no data collection was necessary.
TEST PROCEDURE:
- 1. Initiate a manual reactor scram; perform allimmediate and subsequent scram actions per C.4-A Reactor Scram.
- 2. Perform a reactor startup per C.1 Plant Startup and bring the reactor to the hot standby condition.
- 3. Increase reactor power to rated per C.1 Plant Startup & C.2 Power Operations.
- 4. Note any discrepancies in the Comments section of this test.
~
Page 63 of 111
Monticello Nuclear G::n: rating Plant 1999 Four Yc::r Simulator C:rtification Report Appendix 8: Certification Test Abstracts FINAL CONDITIONS / DURATION OF TEST:
The reactor was at 100% of rated conditions.
BASELINE REFERENCE DATA:
'C.4A Reactor Scram C.1 Plant Startup F C.2 Power Operations TEST DEFICIENCIES / CORRECTIVE ACTIONS:
.None EXCEPTIONS TO ANSI /ANS-3.5-1985 TAKEN:
None ,
Page 64 of 111
1
' Monticello Nucle:r G:nerating Pl:nt ..
1999 Four Yc r Simulator Ccrtification R: port Appendix 8: Certification Test Abstracts TEST TITLE:
Operations in Hot Standby, Test NPE05 revision 8
, DESCRIPTION: '
l The simulator was initialized to the hot standby condition and maintained stable for 30 minutes.
TEST FREQUENCY:
Test performed annually 1995 - 1998
REFERENCE:
]
l ANSI /ANS 3.5 Section 3.1.1 - Normal Plant Evolutions . I
- IN'TIAL I CONDITIONS:
Reactor in' hot standby with the Main Condenser available.
DATA COLLECTION METHOD (S):
l No data collected.
P TEST PROCEDURE:
- 1. Place the simulator in the hot standby condition and allow parameters to stabilize.
i
- 2. Verify parameters temain stable for 30 minutes.
- 3. Note any discrepancies in the Comments section.
FINAL' CONDITIONSIDURATION OF TEST:
l' The reactor was in the Hot Standby condition with all parameters stable.
L -
l.i BASELINE REFERENCE DATA:
- C.1 Plant Startup.
i
- C.3 Plant Shutdown j J' - Page 65 of 111
1 Monticello Nucitar Gun: rating Plant -
l 1999 Four Year Simulator Certification Report !
Appendix 8: Certification Test Abstracts TEST DEFICIENCIESICORRECTIVE ACTIONS:
None EXCEPTIONS TO ANSIIANS-3.5-1985 TAKEN:
None-l l
Page 66 of 111
i Monticello Nucle:r G:n rating Pl:nt
' 1999 Four Year Simul tor Certification Report
^
Appendix 8: Certification Test Abstracts ,
LTEST TITLE:
Generator Load Changes, Test NPE06 revision 8 DESCRIPTION:
Power adjustments were performed on the simulator in accordance with C.2 Power Operations and C.4F Rapid Power Reduction.
TEST FREQUENCY:
Test performed annually 1995 - 1998
REFERENCE:
ANSI /ANS 3.5 Section 3.1.1 - Normal Plant Evolutions INITIAL CONDITIONS:
100% power, all conditions normal.
DATA COLLECTION METHOD (S):
No data collected. :
TEST PROCEDURE:
- 1. Ramp reactor power from 100% to 75% and back to 100% utilizing recirculation flow.
- 2. Verify plant parameters respond as expected for normal power changes.
- 3. Note any discrepancies in the Comments section.
FINAL CONDITIONSIDURATION OF TEST:
Reactor at 100% rated power.
BASELINE REFERENCE DATA:
C.2 Power Operations
~
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Montic:llo Nucl:ar G:n: rating Plant 1999 Four Yecr Simulator Csrtification R port Appendix 8: Certification Test Abstracts TEST DEFICIENCIESICORRECTIVE ACTIONS:
None EXCEPTIONS TO ANSIIANS-3.5-1985 TAKEN:
None
- {'
Page 68 of 111
l -
Monticello Nucl cr G:ntrating Plant l l 1999 Four Year Simul:, tor Certification Rtport l l- \
L' Appendix 8: Certification Test Abstracts !
l-TEST TITLE:
Power Operation at Less Than Full Coolant Flow, Test NPE07 revision 8 l .
l DESCRIPTION:
Operation with one and both reactor recirculation pumps secured was performed l in accordance with approved plant procedures. A subsequent start of the l secured reactor recirculation pumps was then performed.
TEST FREQUENCY:
l Test performed annually 1995 - 1998 l
REFERENCE:
1 ANSI /ANS 3.5 Section 3.1.1 - Normal Plant Evolution INITIAL CONDITIONS-1 1
L
- 100% power, all conditions normal.
DATA COLLECTION METHOD (S):
No data collected.
. TEST PROCEDURE:
- 1. Manually trip one recirculation pump performing all immediate and subsequent operator actions per C.4-B.1.4.A.
- 2. Perform a manual start of the tripped reactor recirculation pumps and return to 100% power. l l
- 3. Manually trip both reactor recirculation pumps and perform all operator actions in accordance with C.4-B.1.4.B.
l 4. Perform a manual start of both reactor recirculation pumps and return the
! reactor to 100% power. !
t 1
- 5. Verify plant parameters respond as expected during the power 1 hanges.
- 6. Note any discrepancies in the Comments section. j Page 69 of 111 )
i
Monticello Nuclsar G:nnrating Plant -
1999 Four Ye:r Simulator Certification Report Appendix 8: Certification Test Abstracts FINAL CONDITIONSIDURATION OF TEST:
The reactor was at 100% of rated power.
BASELINE REFERENCE DATA:
C.4-B.1.4.A Trip of One Recirculation Pump C.4-B.1.4.B Trip of Two Recirculation Pumps TEST DEFICIENCIES / CORRECTIVE ACTIONS:
None EXCEPTIONS TO ANSI /ANS-3.5-1985 TAKEN:
None 1
1 l
l l
l i
Page 70 of 111 l
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l Monticello Nucl:cr Gen: rating Plant 1999 Four Yerr Simulator Ctrtification Report Appendix 8: Certification Test Abstracts TEST TITLE:-
Plant Shutdown from Rated Power to Hot Standby and Cool Down to Cold
' Shutdown Conditions, Test NPE08 revision 8 DESCRIPTION: -
g E plant shutdown was performed from 100% of rated power to hot standby i followed by complete reactor shutdown and cooldown to the cold shutdown !
L condition.
TEST FREQUENCY: ;
1 Test performed annually 1995- 1998
REFERENCE:
I-
- ANSI /ANS 3.5 Section 3.1.1 - Normal Plant Evolutions INITIAL CONDITIONS:
100% reactor power, all conditions normal.
DATA COLLECTION METHOD (S):
L Completed Shutdown Checklist 2204 (checklist not filed with test).
l l TEST PROCEDURE:
1.' Perform a reactor shutdown and cooldown from 100% power to cold shutdown conditions (<212 deg) per C.3 Plant Shutdown and relevant Operations Manual system operations procedures.
- 2. Note any discrepancies in the Comments section.
FINAL CONDITIONS / DURATION OF TEST:
Reactor in the cold shutdown condition.
BASELINE REFERENCE DATA:
'i ,
C.3 Plant Shutdown
(
l l Page 71 of 111
Monticslio Nucinar Gen rating Plant 1999 Four Year Simulator Certification Report Appendix 8: Certification Test Abstracts TEST DEFICIENCIESICORRECTIVE ACTIONS:
None EXCEPTIONS TO ANSI /ANS-3.5-1985 TAKEN:
None i
k l-l 1
I Page 72 of 111 i
I Monticello Nuclear Gan:: rating Plant 1999 Four Year Simulator Certification Report
' Appendix 8: Certification Test Abstracts I
TEST TITLE:
Heat Balance Data at 25%,50%,75% and 100% Power, Test NPE09 revision 8 DESCRIPTION:
Four heat balance runs were completed on the simulator at the specified power levels of 25%,50%,75% and 100% for the years 1995 - 1997. The plant '
implemented rerate conditions in November 1998 without going to the shutdown condition therefore actual plant data at rerate conditions is not available for 1998 for power levels < 75%. Additional tests were performed with data taken during plant rerate testing at power levels between 84% and 100% of rated power.
l
' TEST FREQUENCY:
Test performed annually 1995- 1998
REFERENCE:
ANSI 3.5 Section 3.1.1 INITIAL CONDITIONS:
Reactor power levels required for the specific test. All conditions normal.
DATA COLLECTION METHOD (S):
Simulator Data Collection System utilized to collect required heat balance data.
TEST PROCEDURE:
NOTE: Tests are performed at power levels of approximately 25%,50%,75%,
100 %.
- 1. Initialize or place the simulator at the desired power level.
- 2. Collect data utilizing " HEAT BAL" from MONITOR.
l 3. Direct simulator software engineering to perform a manual heat balance L calculation.
- 4. Compare simulator data to plant data for acceptability. Simulator " Core Thermal Power" and " Net Plant Efficiency" will match actual plant data (if Page 73 of 111
Monticello Nucitar G:n: rating Plant -
1999 Four Year Simulator Certification Report Appendix 8: Certification Test Abstracts l
available) within +2% and best estimate values at power levels where plant
- data is not available. I
' FINAL CONDITIONS / DURATION OF TEST:
N/A BASELINE REFERENCE DATA:
Actual plant heat balance data collected during the current operating cycle following rerate implementation includes data at power levels >75% of rated conditions (1775 MWth). The 1998 tests for power levels of 25% and 50%
utilized plant data taken during startup following the 1998 refueling outage prior to rerate implementation. Plant power has not been less than 75% since rerate implementation in November 1998, therefore plant data is not available for test ,
comparison. Tests will be accomplished at rerate conditions when plant data is available.
. TEST DEFICIENCIES / CORRECTIVE ACTIONS:
None EXCEPTIONS TO ANSI /ANS-3.5-1985 TAKEN:
None
. Page 74 of 111
___ ____= -_
Monticello Nucl:ar G:n= rating Plant 1999 Four Year Simulator Certification Report Appendix 8: Certification Test Abstracts TEST TITLE:
Operator Conducted Surveillance Testing on Safety-Related Equipment and Systems, Test NPE10 revision 8 DESCRIPTION:
Operator conducted safety related equipment surveillance tests were performed and evaluated as required. The number of tests was increased during 1998 to increase the comprehensiveness of testing.
TEST FREQUENCY:
Surveillance tests performed annually 1995 - 1998
REFERENCE:
ANSI /ANS 3.5 Section 3.1.1 - Normal Plant Evolutions INITIAL CONDITIONS:
Various initial conditions as outlined in the specific test. I DATA COLLECTION METHOD (S):
Completed surveillance test procedure (surveillance procedures not filed with test).
TEST PROCEDURE:
- 1. Perform the following surveillances:
- 0010 REACTOR MANUAL SCRAM FUNCTIONAL
- 0016 REACTOR MODE SWITCH IN SHUTDOWN SCRAM
- 0045a RBM MONTHLY ROD BLOCK FUNCTIONAL
- 0070a OFF-GAS MONITOR FUNCTIONAL
L Monticello Nucinar Generating Plant - '
2 1999 Four Year Simulator Certification Report
' Appendix 8: Certification Test Abstracts i
- 0112. SAFETY RELIEF VALVES OPERABILITY 4 #0114 RCIC SYSTEM TESTS <150 PSIG
- 0143 DW/ TORUS MONTHLY VACUUM BREAKER CHECK AND INSTRUMENT AIR SYSTEM VALVE EXERCISE '
- 0160 MSIV EXERCISE TEST
- 0187-1 #11 STBY DIESEL GEN /ESW
- 0187-2 #12 STBY DIESEL GEN /ESW
- 0212: ROD WORTH MINIMlZER OPERABILITY.
- 0253-1 SBGT A TRAIN
- 0255-01-1A CRDH SYSTEM QUARTERLY VALVE EXERCISE
- 0255-3-1A-2A COLD SHUTDOWN VALVE OPERABILITY
- 0255-3-IA-1 ' CORE SPRAY SYSTEM TESTS
- 0255-4-IA-1 RHR PUMP AND VALVE TESTS
- 0255-6-IA-1 HPCI SYSTEM TESTS WITH REACTOR PRESSURE AT RATED CONDITIONS
- 0255-7-1 A-1 MAIN STEAM VALVE EXERCISE TESTS
- 0255-8-IA-1 RCIC SYSTEM TESTS WITH REACTOR PRESSURE AT RATED CONDITIONS - ;
- 0255-9-1 A RECIRCULATION SYSTEM VALVE OPERABILITY
- 0255-10-1 A-1 PRIMARY CONTAINMENT ISOLATION VALVE EXERCISE
- 0255-14-1A-1' RWCU VALVE OPERABILITY AND POSITION INDICATION 2
- 0289A SERVICE WATER EFFLUENT MONITOR FUNCTIONAL
- 0444B SUPPRESSION POOL TEMPERATURE MONITORING DURING SRV OPERATION
- 1227 ATWS-RPT ATWS-ARI, ASDS ROD INSERTION AND B/U SCRAM VALVE FUNCTIONAL
- 1415 PRIMARY CONTAINMENT HARD PIPE VENT VALVE EXERCISE l
- 1455 PLANT PROTECTION SYSTEM FUNCTIONAL l FINAL CONDITIONSIDURATION OF TEST:
Various plant conditions depending on the specific test. I BASELINE REFERENCE DATA:
Criteria outlined in the specific tests.
TEST DEFICIENCIESICORRECTIVE ACTIONS:-
Some surveillance tests have shown minor discrepancies such as incorrect valve timing and computer points not indicating appropriately., etc. These Page 76 of 111 1
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1999 Four Year Simulator Certifiention R port l
Appendix 8: Certification Test Abstracts .
l.
discrepancies are being corrected in accordance with the simulator discrepancy report process,
' EXCEPTIONS TO ANSlIANS-3.5-1985 TAKEN:
l None 1
l l
i 1
I 1
Page 77 of 111
l Monticello Nucirr G3n:: rating Pl:nt -
1999 Four Year Simulator Certification Report" t
, Appendix 8: Certification Test Abstracts TEST TITLE:
Manual Scram, Test TZ01 revision 8 DESCRIPTION:
A manual scram was actuated with no operator scram actions performed.
Automatic plant interlocks and actions were verified to occur as designed.
TEST FREQUENCY: ,
Test performed annually 1995 - 1998
REFERENCE:
' ANSI /ANS 3.5 Section 4.2.1 and Appendix B.1 INITIAL CONDITIONS:
100% power, all conditions normal.
i
, DATA COLLECTION METHOD (S):
l-Simulator Data Collection System utilized to collect required data.
TEST PROCEDURE:
- 1. Verify DCS is set to record "TRAN" file.
- 2. Verify FWLC in 3-element control.
- 3. Place the mode switch in S/D; Take no immediate operator actions.
- 4. Verify expected automatic actions occur per C.4-A, " Reactor Scram".
l 5. Observe the control panels during the test and note any unexpected l
- response in the comments section. 1
! l
- 6. Graph data points and compare to best estimate response. l FINAL CONDITIONSIDURATION OF TEST:
Reactor in the hot shutdown condition, all rods inserted.
Page 78 of 111
. . - .- - - ~ . . _ - . - . _ . - . .
. . Montic llo Nuclear Gen:: rating Plant i 1999 Four Ycar Simulator Certification Report I l \
~
Appendix 8: Certification Test Abstracts i
i
. BASELINE REFERENCE DATA.
l L-- 1. NSP Nuclear Analysis Department "Best Estimate" computer data (Dynode- l B).-
j 2. Actual plant scram data (TRA Graphs).
l
- 3. Table Top Discussion data.
I- TEST DEFICIENCIES / CORRECTIVE ACTIONS:
None EXCEPTIONS TO ANSIIANS-3.5-1985 TAKEN:
- None l
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Page 79 of 111 l
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Monticello Nuctrar Gennrating Plant .
1999 Four Yerr Simulator Cartification Report Appendix 8: Certification Test Abstracts TEST TITLE:
- Simultaneous Trip of All Feedwater Pumps, Test TZO2 revision 8 ,
DESCRIPTION:
I A dual feedwater pump trip was actuated from 100% power with no operator 2
action performed. All automatic plant actions and interlocks were verified to occur as designed.
TEST FREQUENCY:
Test performed annually
REFERENCE:
ANSI /ANS 3.5 Section 4.2.1 and Appendix B.1 INITIAL CONDITIONS:
100% power, all conditions normal.
DATA COLLECTION METHOD (S):
Simulator Data Collection System utilized to' collect required data.
TEST PROCEDURE:
- 1. Verify DCS is set to record "TRAN" file.
- 2. Actuate malfunctions FW16A & B simultaneously, take no operator action.
- 3. Verify expected automatic actions occur.
s
- 4. Observe the control panels during the test and not any unexpected response in the Comments section.
- 5. Stop the test when RPV level has recovered to +48".
- 6. Graph data points and compare to best estimate response.
Page 80 of 111 ,
Monticello Nucl:ar G::n:: rating Plant 1999 Four Year Simulator Certification Rsport Appendix 8: Certification Test Abstracts FINAL CONDITIONSIDURATION OF TEST:
Reactor in t he hot shutdown. condition, all rods inserted. Reactor level restored !
BASELINE REFERENCE DATA: l
- 1. NSP Nuclear Analysis Department "Best Estimate" computer data (Dynode-8).
- 2. Table top discussion data.
TEST DEFICIENCIESICORRECTIVE ACTIONS:
- None EXCEPTIONS TO ANSilANS-3.5-1985 TAKEN
- ,
None l~
i i
s
, Page 81 of 111
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- Monticello Nuclear G:n:: rating Plant .
1999 Four Year Simulator _Catification Report
- Appendix 8: Certification Test Abstracts TEST TITLE:
Simultaneous Closure of All MSIVs, Test TZO3 revision 8 DESCRIPTION:.
- All MSIVs were simultaneously closed resulting in a reactor scram and'-
. subsequent plant transient. All automatic' plant interlocks and actions were
. verified to' occur as designed.
TEST FREQUENCY:
Test Performed Annually 1995 - 1993
REFERENCE:
l ANSI /ANS 3.5 Section 4.2.1 and Appendix B.1 INITIAL CONDITIONS:
i-
'100% power, all conditions normal.
- DATA COLLECTION METHOD (S)
Simulator Data Collection System utilized to collect required data.
-TEST PROCEDURE:
' 1. Verify DCS is set to record "TRAN" file.
1
- 2. Verify FWLC is in 3-element control.
' 3. Actuate malfunctions PP05A & PP05C simultaneously; take no operator actions.
4.' Verify automatic actions occur per C.4-B.4.1.A.
? ~ 5.' Obselve the ~ cont.rol panels during the test and note any unexpected i response in the comments section.
1
<M 6. Graph data points and compare to best estimate response.
Page 82 of 111
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Monticello Nucle:r Gun: rating Plant
.1999 Four Year Simulator Certification Report 1 Appendix 8: Certification Test Abstracts i
FINAL CONDITIONS / DURATION OF TEST:
Reactor shutdown and isolated in the hot shutdown condition, all rods inserted.
. BASELINE REFERENCE DATA:
- 1. NSP Nuclear Analysis Department "Best Estimate" computer data (Dynode B).
- 2. Table top discussion data.
TEST DEFICIENCIES / CORRECTIVE ACTIONS:
None EXCEPTIONS TO ANSI /ANS-3.5-1985 TAKEN:
.None 4.
i Page 83 of 111
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)
1999 Four Year Simulator Certification Report !
l Appendix 8: Certification Test Abstracts l l
l TEST TITLE: l I
Single Reactor Recirculation Pump Trip, Test TZO4 revision 8 l l
DESCRIPTION: I A single recirculation pump was tripped from 100% power operation resulting in the plant operating in a single loop configuration. All automatic plant interlocks and actions were verified to occur as designed. ,
TEST FREQUENCY:
Test performed annually 1995 - 1998
REFERENCE:
ANSI /ANS 3.5 Section 4.2.1 and Appendix B.1 INITIAL CONDITIONS:
100% power, all conditions normal.
DATA COLLECTION METHOD (S):
Simulator Data Collection System utilized to collect required data.
- TEST PROCEDURE:
- 1. Verify DCS is set to record TRAN file. j l
- 2. Verify FWLC in 3-element control.
- 3. Trip one Reactor Recirculation Pump by manually opening the drive motor breaker; Close the tripped pumps discharge valve.
' 4. Observe the control panels during the tests and note any unexpected response in the' comments section.
- 5. Allow parameters to stabilize; graph data points and compare to best estimate response.
Page 84 of 111 j
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. Monticello Nucl::r G:n rcting Plant 1999 Four Year Simulator Curtification Report 4
Appendix 8: Certification Test Abstracts 4
FINAL CONDITIONS / DURATION OF TEST:
The reactor will be operating in a single loop configuration in accordance with
- approved plant operating procedures.
BASELINE REFERENCE DATA:
- 1. NSP Nuclear Analysis Department "Best Estimate" computer data (Dynode-B).
- 2. Table top discussion data.
TEST DEFICIENCIES / CORRECTIVE ACTIONS:
None 1
EXCEPTIONS TO ANSIIANS-3.5-1985 TAKEN:
- None d
(
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Monticello Nuclear Gan* rating Plant 1999 Four _ Year Simulator Cartification Report Appendix 8: Certification Test Abstracts I i
- TEST TITLE: I l
Simultaneous Trip of Both Recirculation Pumps, Test TZOS revision 8 DESCRIPTION:
A dual Reactor Recirculation Pump trip was effected from 100% power resulting
^
in the reactor operating in the natural circulation mode. All automatic plant l interlocks and actions were verified to occur as designed.
)
TEST FREQUENCY:
Test performed annually 1995 - 1998 i I
REFERENCE:
)
i ANSI /ANS 3.5 Section 4.2.1 and Appendix B.1 l I
INITIAL CONDITIONS:
100% power, all conditions normal. )
' DATA COLLECTION METHOD (S): l Simulator Data Collection System utilized to collect required data.
TEST PROCEDURE:
- 1. . Verify DCS is set to record TRAN file.
- 2. Verify FWLC in 3-element control. l l
- 3. Trip both reactor recirculation pumps by manually opening the drive motor breakers; close the tripped pumps discharge valve. l 1
- 4. Observe the control panels during the tests and note any unexpected I response in the comments section.
- 5. Al. low parameters to stabilize; graph data points and compare to best ;
estimate response. l 1
l Page 86 of 111
. Montic:llo Nuclear Gcnarating Plant 1999 Four Year Simulater Certification Report Appendix 8: Certification Test Abstracts FINAL CONDITIONS / DURATION OF TEST:
- The reactor will be operating in the natural circulation mode in accordance wv.h approved plant operating procedures.
~
BASELINE REFERENCE DATA:
1.- Actual Plant Data (TRA graphs). .
- 2. Table top discussion data.
3.- NSP Nuclear Analysis Department "Best Estimate" computer data (DynodeB).
TEST DEFICIENCIES / CORRECTIVE ACTIONS:
None
' EXCEPTIONS TO ANSI /ANS-3.5-1985 TAKEN:
None 1
i i
Page 87 of 111
Montic llo Nucl:ar Gensrating Plant I 1999 Four Year Simulator Certification Report l I
Appendix 8: Certification Test Abstracts l TEST TITLE:
l Main Turbine Trip (Maximum power with no scram), Test TZ06 revision 8 DESCRIPTION:
A Main Turbine trip was manually initiated with reactor power at the maximum point at which the trip did not directly cause a reactor scram. All automatic plant interlocks and actions were verified to occur as designed. ,
TEST FREQUENCY:
I Test performed annually 1995 - 1998 ,
REFERENCE:
ANSI /ANS 3.5 Section 4.2.1 and Appendix B.1 INITIAL CONDITIONS: ,
1
. Reactor power approximately 30% with annunciator 5-B-37 " TURBINE PRESS GEN REJECTION BYPASS" actuated and Main Turbine on line.
DATA COLLECTION METHOD (S):
Simulator Data Collection System utilized t'o collect required data.
TEST PROCEDURE:
- 1. Verify DCS is set to record "TRAN" file.
- 2. Manually trip the turbine from CO-7. Take no operator action.
- 3. Observe the control panels during the test and note any unexpected response in the comments section.
- 4. Allow parameters to stabilize; graph data points and compare to best estimate response FINAL CONDITIONSIDURATION OF TEST:
Reactor in the hot shutdown condition, all rods inserted. Pressure control maintained by the Turbine Bypass valves.
Page 88 of 111
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Montic:llo Nucl::r G:nnrcting Plant 1999 Four Ye r Simulator C rtification Report i
! Appendix 8: Certification Test Abstracts l
BASELINE REFERENCE DATA:
j
- 1. NSP Nuclear Analysis Department "Best Estimate" computer data (Dynode-B)
- 2. Table Top Discussion Data ;
1 TEST DEFICIENCIESICORRECTIVE ACTIONS:
1 None EXCEPTIONS TO ANSI /ANS-3.5-1985 TAKEN: !
- 1 None l
l l
Page 89 of 111
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Monticello Nuciscr Gen: rating Plcnt 1999 Four Year Simulator Certification Report Appendix 8: Certification Test Abstracts TEST TITLE: l Maximum Rate Power Ramp (100% - 75% -100%), Test TZ07 revision 8 DESCRIPTION:
Reactor power was adjusted from 100% to 75% and back to 100% at the maximum allowable rate utilizing the manual mode of reactor recirculation flow -
control.
TEST FREQUENCY:
Test performed annually 1995- 1998
REFERENCE:
ANSI /ANS 3.5 Section 4.2.1 and Appendix B.1 INITIAL CCNDITIONS:
100% power, all conditions normal.
DATA COLLECTION METHOD (S):
Simulator Data Collection System utilized to collect required data.
. TEST PROCEDURE:
- 1. Verify DCS is set to record "TRAN" file.
- 2. Verify FWLC in 3-element control.
- 3. Manually decrease reactor power to 75%, allow power to stabilize and return power to 100% using recirculation flow at the maximum ramp rate.
- 4. . Observe the control panels 'during the test and note any unexpected. '
response in the comments section.
- 5. Graph data points and compare to best estimate response.
FINAL' CONDITIONS / DURATION OF TEST:
1The reactor will be at 100% power and all conditions normal.~ -
Page 90 of 111
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Monticello NuclearG:nsr ting Pl:nt '
1999 Four Ye:r Simulator C:rtificrtion Report
^
.; ' Appendix 8: Certification Test Abstracts
. BASELINE REFERENCE DATA:
- 1. NSP Nuclear Analysis Department "Best Estimate" computer data (2-D graphs).
- 2. Table Top Discussion Data.
TEST DEFICIENCIES / CORRECTIVE ACTIONS:
None EXCEPTIONS TO ANSIIANS-3.5-1985 TAKEN:
None i
Page 91 of 111 t,
Montic:llo Nuclear G:n rating Plant ,
1999 Four Yenr Simulator C:rtification Report !
l Appendix 8: Certification Test Abstracts TEST TITLE:
Design Basis LOCA Coincident with a Loss of Offsite Power, Test TZO8 revision 8
DESCRIPTION:
A design basis loss of coolant accident (LOCA) coincident with a loss of offsite power was actuated. All automatic plant interlocks and actions were verified to occur as designed.
TEST FREQUENCY:
Test performed annually 1995 - 1998
REFERENCE:
ANSI /ANS 3.5 Section 4.2.1 and Appendix B.1 INITIAL CONDITIONS:
100% reactor power, all conditions normal.
DATA COLLECTION METHOD (S):
Simulator Data Collection System utilized to collect required data.
TEST PROCEDURE:
- 1. Verify DCS is set to record "TRAN" file.
- 2. Actuate malfunctions RR03A at 100% severity and ED12 simultaneously.
Take no operator action.
- 3. Verify expected automatic actions occur as expected.
- 4. Observe the control panels during the test and note any unexpected response in the comments section.
- 5. Allow RPV water level to recover.
- 6. Graph data points and compare to best estimate response Page 92 of 111
Monticello Nucl::ar Gan:rcting Plant 1999 Four Year Simulator Certification Report Appendix 8: Certification Test Abstracts FINAL CONDITIONS / DURATION OF TEST:
Reactor shutdown, all rods inserted, and reactor water level restored.
BASELINE REFERENCE DATA:
- 1. NSP Nuclear Analysis Department "Best Estimate" computer data (2-D graphs). .
- 2. Table top Discussion Data.
TEST DEFICIENCIES / CORRECTIVE ACTIONS:
1 None EXCEPTIONS TO ANSilANS-3.5-1985 TAKEN:
None l
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I' l-l I
. Page 93 of 111 l
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Montic3llo Nucl:nr Gunsrating Plant 1999 Four Year Simulator Certification Report Appendix 8: Certification Test Abstracts TEST TITLE:
Maximum Size Uniso!able Main Steam Line Rupture, Test TZO9 revision 8 DESCRIPTION:
A maximum size unisolable Main Steam line break within the Drywell was affected. All automatic plant interlocks and actions were verified to occur as designed.
TEST FREQUENCY:
Test performed annually 1995- 1998
REFERENCE:
ANSI /ANS 3.5 Section 4.2.1 and Appendix B.1 INITIAL CONDITIONS:
100% reactor power, all conditions normal.
DATA COLLECTION METHOD (S):
Simulator _ Data Collection System utilized to collect required data.
TEST PROCEDURE: l
- 1. Verify DCS is set to record "TRAN" file.
- 2. Actuate malfunction MSO48@100% severity. Take no operator action.
- 3. Verify exmted automatic actions occur.
- 4. Observe the control panels during the test and note any unexpected response in the comments section. 4
- 5. Allow the test to run approximately 10 minutes. Graph data points and I' compare to best estimate response.
L Page 94 of 111 4
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I Monticello Nuciscr G:nnrating Plant l 1999 Four Year Simulator Certification Report j i
! Appendix 8: Certification Test Abstracts l FINAL CONDITIONSIDURATION OF TEST:
Reactor shutdown and all rods inserted. Primary Containment and reactor parameters stabilized.
BASELINE REFERENCE DATA:
~
- 1. NSP Nuclear Analysis Department "Best Estimate" computer data (2-D i
. graphs).
1
- 2. Table top discussion data.-
. TEST DEFICIENCIES / CORRECTIVE ACTIONS:
None EXCEPTIONS TO ANSIIANS-3.5-1985 TAKEN:
None 4
i Page 95 of 111
Monticello Nucl:ar Gen:: rating Plant 1999 Four Year Simul tor Certification Report Appendix 8: Certification Test Abstracts
~
' TEST TITLE:
SORV Open, MSIV isolation, and HP ECCS Inhibited, Test TZ10 revision 8 TEST FREQUENCY:
Test performed annually 1995 - 1998 DESCRIPTION:
A Group 1 isolation accompanied with a stuck open' safety relief valve and loss of all high pressure ECCS was actuated. lAll automatic plant interlocks and actions were verified to occur as designed.
4
REFERENCE:
ANSI /ANS 3.5 Section 4.2.1 and Appendix B.1 INITIAL CONDITIONS:
100% reactor power, all conditions normal.
DATA COLLECTION METHOD (S):
Simulator Data Collection System utilized to collect required data.
TEST PROCEDURE:
- 1. Verify DCS is set to record "TRAN" file.
- 2. Simultaneously actuate malfunctions PP05A, PP05C and AP01A.
- 3. Verify expected automatic' actions occur.
- 4. Observe the control panels during the test and note any unexpected l response in the comments section.
- 5. Allow test to run approximately 10 minutes. Graph data points and compare to best estimate response.
FINAL CONDITIONS / DURATION OF TEST: !
Reactor shutdown and slowly depressurizing due to the open safety relief valve.
l Page 96 of 111 i
l Monticallo Nuclear Gen: rating Plant l 1999 Four Yecr Simulator Ccrtification Report l
' l Appendix 8: Certification Test Abstracts I BASELIME REFERENCE DATA: l
- 1. NSP Nuclear Analysis Department "Best Estimate" computer data (2-D graphs). I l
l
- 2. Table top discussion data. .
l TEST DEFICIENCIES / CORRECTIVE ACTIONS:
None '
i EXCEPTIONS TO ANSI /ANS-3.5-1985 TAKEN:
I None'
]
l J
s Dage 97 of 111 as u I'-
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- - . . . .= . .. . .- .- . -- - . - - --.
Monticello Nucl:ar G:nnrating PI:nt 1999 Four Year Simulator Certification Report Appendix 8: Certification Test Abstracts TEST TITLE:
100% Stability, Test US01 revision 8 DESCRIPTION:
Simulator p( rformance data was collected at the beginning of the test and at the 60 minute point and evaluated for stability.
TEST FREQUENCY:
Test performed annually 1995 - 1998
REFERENCE:
ANSI /ANS 3.5 Appendix B.1.1 INITIAL CONDITIONS:
100% reactor power, all conditions normal.
DATA COLLECTION METHOD (S):
Simulator data was col!ected from panel indicators and the process computer (SPDS). The simulator data collection system is also utilized to collect and compare relevant data.
._ s PROCEDURE:
- 1. Initialize the simulator to 100% power.
- 2. Record initial data points on attachment #1.
- 3. Aliow the simulator to run for 60 minutes and record final data on test Attachment #1.
Note: The_ acceptable range is +2% for all parameters.
FINAL CONDITIONS / DURATION OF TEST:
Simulator conditions remained unchanged for the entire test.
Page 98 of 111
i- . Monticello Nucl :r G:nnrcting Plant
- j. 1999 Four Year Simulator C:rtification Report .
I- Appendix 8: Certification Test Abstracts .
BASELINE REFERENCE DATA:
l N/A. Simulator data only.
TEST DEFICIENCIES / CORRECTIVE ACTIONS:
!- None EXCEPTIONS TO ANSI /ANS-3.5-1985 TAKEN:
None t-1 l
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t J5 Page 99 of 111
Montic:llo Nucl:ar Gen: rating Plant 1999 Four Year Simulator Certification Report Appendix 8: Certification Test Abstracts TEST TITLE:
Steady State Performance at 25%,50%,75%, and 100% Power Levels, Test US02 A, B, C, D revision 8 DESCRIPTION: -
Simulator performance data was collected at power levels of 25%,50%,75%
and 100% from 1995 - 1997. The plant implemented rerate conditions in November 1998 without going to the shutdown condition therefore actual plant data at rerate conditions is not available for 1998 at power levels <75%.
TEST FREQUENCY:
Test performed annually 1995 - 1998
REFERENCE:
- ANSI /ANS 3.5 Appendix B.1.1 INITIAL CONDITIONS:
Initial conditions will reflect the individual test power level required.
DATA COLLECTION METHOD (S):
Data is read from the simulator panels and SPDS during performance of the i test.
TEST PROCEDURE:
- 1. Initialize and adjust the simulator to duplicate parameters as closely as possible to specific recorded plant reference conditions.
- 2. Record required data on attachment #1.
- 3. Compare simulator data to plant data.
Note: The acceptable range for critical parameters (*) is 12% and 110% for non-critical parameters of the 100% value or 100% normal range.
, Page 100 0f 111
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Monticello Nucl:ar Gnn: rating Plant 1999 Four Year Simulator Certification Report Appendix 8: Certification Test Abstracts FINAL CONDITIONS / DURATION OF TEST:
Simulator conditions remained essentially unchanged for the duration of the test for each power level.
BASELINE REFERENCE DATA:
Actual plant data collected during the current operating cycle following rerate implementation includes data at power levels >75% of rated conditions (1775 MWth). The 1998 tests for power levels of 25% and 50% utilized plant data taken during startup following the 1998 refueling outage when rated power was l 1670 MWth. Plant power has not been less tnan 75% since rerate implementation in November 1998 therefore plant data ls not available for test comparison. The steady state performance tests will be accomplished at rerate l conditions when plant data is available.
TEST DEFICIENCIES / CORRECTIVE ACTIONS:
None EXCEPTIONS TO ANSI /ANS-3.5-1985 TAKEN:
None 1
Page 101 of 111
Monticello Nucl::ar Gnn: rating Plant .
1999 Four Year Simulator Certific tion Report Appendix 8: Certification Test Abstracts TEST TITLE:
Computer Real Time Measurement, Test XX-01 revision 2 DESCRIPTION:
Verify the simulator computer operates simulation in real time.
TEST FREQUENCY:
Test performed annually 1995 - 1998
REFERENCE:
ANSI 3.5-1985 Section 3.1.1 INITIAL CONDITIONS:
100% power, all conditions normal DATA COLLECTION METHOD (S):
- Simulation computer MST frame time. :
-TEST PROCEDURE:
- 1. Initialize the simulator to normal 100% power conditions.
- 2. Start the stopwatch when the simulator is taken out of freeze.
- 3. Allow the simulator to run for approximately 30 minutes.
4; For the next 30 minutes of runtime, sequence various malfunctions active and allow the simulator to continue to run.
Note: Do not use malfunctions which will drive the simulator out of operating limits (i.e. Torus temperature, fuel temperature, etc.).
- 5. : Verify MST frame time is <50 msec during the final 30 minute run.
- 6. Verify total processor spare time is >30%.
' 7. Verify simulator operation appears normal from all panel indications.
Page 102 of 111 a
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Monticello Nucis:r G ncrating PI:nt 1999 Four Yerr Simulator Certification Report Appendix 8: Certification Test Abstracts
- 8. After running approximately one hour, stop the stopwatch and compare computer problem time to real time from the stopwatch. Verify times are reasonable.
FINAL CONDITIONS / DURATION OF TEST:
Spare time should be >30% and MST frame time shall be <S0 msec.
9
, BASELINE REFERENCE DATA:
None
-TEST DEFICIENCIES / CORRECTIVE ACTIONS:
Test Results were acceptable.
. EXCEPTIONS TO ANSI /ANS-3.5-1985 TAKEN:
None Page 103 of 111 i.
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Monticello Nuclear Gan rating Plant .
1999 Four Year Simulator Curtification Report J Appendix 8: Certification Test Abstracts !
l TEST TITLE:
Simulator / Control Room Lighting Test, Test XX-03 revision 2 DESCRIPTION-1 Comparison of plant control room lighting levels to simulator control room lighting l levels. <
TEST FREQUENCY: )
Simulator environment testing is performed on a four-year cycle ,
l REFERENCE.
ANS!/ANS 3.5 Section 3.2.3 Simuf 1 tor Environment INITIAL CONDITIONS:
N/A DATA COLLECTION METHOD (S):
Calibrated light meter, values recorded manually.
TEST PROCEDURE:
Light readings were taken at various locations in the plant Control Room using a i calibrated light meter. Light readings were then taken in the simulator at the )
approximate same locations and compared with the plant readings. The light switches and dimmer switches in the simulator were then adjusted to closely !
I match the lighting level recorded in the plant. The switches and dimmers for the simulator were then marked to indicate the correct position to correctly simulate l actual Control Room lighting.
FINAL CONDITIONS / DURATION OF TEST:
N/A '
- - BASELINE REFERENCE DATA:
Plant Control Room measured lighting levels.
Page 104 of 111
. Monticello Nuclear Gan rating Plant 1999 Four Ye r Simulator Cartification Report Appendix 8: Certification Test Abstracts
-TEST DEFlCIENCIES/ CORRECTIVE ACTIONS:
None
- EXCEPTIONS TO ANSI /ANS-3.5-1985 TAKEN:
None 1
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1 w
$ I Page 105 of 111
Monticello Nuclear Gnn:: rating Plant -
1999 Four Year Simulator Certification Report Appendix 8: Certification Test Abstracts TEST TITLE:
Simulator / Control Room Audible Test, Test XX-04 revision 2 DESCRIPTION:
Comparison of plant control room sound levels to simulator control room sound levels.-
TEST FREQUENCY:
Simulator environment testing is performed on a four-year cycle.
REFERENCE:
ANSI /ANS 3.5 Section 3.2.3 Simulator Environment INITIAL CONDITIONS:
N/A DATA COLLECTION METHOD (S):
N/A TEST PROCEDURE:
Th'e initial simulator certification sound level test' utilized a sound meter to
't : document sound levels in the simulator and plant control room. The environmen,t S in the plant control room and the simulator control room has not appreciably changed in the since the initial test. Verification of the ambient sound levels in 7
both the plant and the simulator were verified by ear noting such things as similar T panel power supply sounds, ventilation, etc.
FINAL CONDITIONS / DURATION OF TEST:
'N/A BASELINE REFERENCE DATA:
- Plant Control Room sound level measurements.
4 Page 106 of 111 4
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l-4 Monticello Nucle:r G:n rcting Pitnt 1999 Four Yecr Simulator Certific tion Report
, Appendix 8: Certification Test Abstracts l
l l
TEST DEFICIENCIESICORRECTIVE ACTIONS:
None EXCEPTIONS TO ANSI /ANS-3.5-1985 TAKEN:
l.
None I
i Page 107 of 111 l
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Montic llo Nuclear G:;nsrcting Plant -
1999 Four Year Simulator Certification Report i Appendix'8: Certification Test Abstracts TEST' TITLE:
Simulator / Control Room Physical Fidelity Test, Test XX-05 revision 3 DESCRIPTION:
2- This test verifies the simulator control panels are correctly simulated to match the -
. MNGP control panels.
TEST FREQUENCY:
Simulator physical fidelity testing is performed on a four year cycle.
REFERENCE:
ANSI /ANS 3.5-1985 Section 3.2.1 and 3.2.2 INITIAL CONDITIONS: .
NA DATA COLLECTION METHOD (S):
Photographs were taken of the Monticello Nuclear Generating Plant Control Room panels.
.- TEST PROCEDURE: ,
The process of verifying the simulator panels consisted of dating and sequentially numbering each of the reference plants panel's photographs and comparing
. these photographs to the actual simulator control room panels.
The MTC Simulator Photo Record contains information such as:
- 1. . Panel number, section of panel (upper / lower) ,
' 2. Number of photo, date of reference photo.
- 3. Date of simulator verification and verifying individual. ;
- 4. l Discrepancies will be documented and corrected per the simulator Discrepancy Report process.
[
- , n.
Page 108 of 111-4 s
..m, --e v s c n --- . , ,, - n < r .- - y , y.- s
, 'c
- Monticello Nuclear Gennrating Pitnt
- i. 1999 Four Yerr Simul: tor Cartification Report Appendix 8: Certification Test Abstracts ,
! I The test procedure for verification consisted of verifying each pane! with regard to labeling, recorders, indicators, lights, switches and mimic / demarcation lines. ;
l FINAL CONDITIONS / DURATION OF TEST:
NA
. BASELINE REFERENCE DATA: .
MNGP Control Room panel photographs a
- TEST DEFICIENCIES / CORRECTIVE ACTIONS
None
'l EXCEPTIONS TO ANSIIANS-3.5-1985 TAKEN:
None li T
Page 109 of 111
Monticello Nuclzr G:nnrating Plant .
1999 Four Year Simulator Cartification Report Appendix 8: Certification Test Abstracts TEST TITLE:
Certified Malfunction Tests, revision 3 DESCRIPTION:
A malfunction test was written and performed for each malfunction listed on the Certified Malfunction List (Appendix 4).
TEST FREQUENCY:
Approximately 25% of certified malfunctions were tested each year.
REFER 85NCE:
ANSI /ANS 3.5 Section 3.1.2, Plant Malfunctions
. INITIAL CONDITIONS: '
Initial conditions varied depending on the specific malfunction being tested.
DATA COLLECTION METHOD (S):
.The following methods are used to collect data when required:
- 1. Safety' Parameter Display System (SPDS)
- 2. Alarm Typer
?\
, 3. Simulator Data Collection System.
TEST PROCEDURE:
Each malfunction was tested using a customized malfunction test procedure with the specific malfunction cause and effects attached.
BASELINE REFERENCE DATA:
- 1. Malfunction Cause'& Effects
- 2. Controlled Monticello Plant Elementary Drawings
- 3. Monticello Nuclear Generating Plant Operations Manuals Page 110 of 111
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. .: ;- Monticello Nucl:ar G:n: rating Plant 1999 Four Year Simulator Cartificeiion Report Appendix 8: Certification Test Abstracts
- 4. Actual Plant Operating Experiences TEST DEFICIENCIESICORRECTIVE ACTIONS:
None c- EXCEPTIONS TO ANSI /ANS-3.5-1985 TAKEN:
None -
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Page 111 of 111