ML20204D524
| ML20204D524 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 03/31/1999 |
| From: | CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20204D488 | List: |
| References | |
| NUDOCS 9903240237 | |
| Download: ML20204D524 (140) | |
Text
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BRUNSWICK STEAM ELECTRIC PLANT l
UNIT 2 l
l SIMITLATOR CERTIFICATION ,
I QUADRENNIAL REPORT l MARCH 1999 CAROLINA POWER & LIGHT COMPANY SOUTHPORT, NORTH CAROLINA '
l jsA '3881328s7g{
o 1 l
CPEL BRUNSWICK UNIT TWO SINULATOR CERTIFICATION TABLE OF CONTENTS j i INTRODUCTION .................................................. 3 l General Information .................................... . 3 Simulator Configuration Control Board .................... 3 j Exceptions to ANSI /ANS 3.5 ............................... 4 1
I. GENERAL DESCRIPTION ................................... .. 8 A. Owner ................................................. 8 B. Re f e r enc e P l an t . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 C. Ready for Training Date ............................... 8 D. Type of Report ........................................ 8 II. CONTROL ROOM COMPARISON .................................. 9 l A. Physical Arrangement ....... .......................... 9 B. Panels and Equipment ................................. 10 C. Systems .............................................. 13 D. Environment .......................................... 13 III. Instructor Interface .................................... 15 A. General Description .................................. 15
. :B . Simulator Initial Conditions ......................... 15 C. Simulator Malfunction Selection ...................... 16 D. Simulator Overrides .................................. 16 E. Controls Outside Control Room ........................ 17 F. Parameter and Equipment Monitoring ................... 17 G. Simulator Special Features ............... ........... 18 1
IV. Procedure Analysis .................. .................. .20 V. Simulator Changes Since Last Report ..................... 20 A. Plant Modifications .................................. 20 B. Simulator Upgrades .................................. 20 C. Other_ Upgrades ....................................... 21 VI. . Simulator Design Data Base .......... .................. 21 VII. Simulator Discrepancy Resolution and Upgrading Programs . 21 j A. Simulator Service Request Program .................... 21 !
D. Plant Modification Implementation .................... 22 !
C. Simulator Configuration Management System ............ 22 l 1
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CPEL BRUNSWICK UNIT TWO SIMULATOR CERTIFICATION TABLE OF CONTENTS VIII. Simulator Tests ......................................... 23 A. Certification Test Schedule .......................... 23 A.1. Annual Operability Tests ........................ 23 A.2. Malfunction Tests ............................... 23 B. Certification Test Schedule 1995-1998 ................ 24 C. Certification Test Schedule 1999-2002 ................ 25 Appendix A Brunswick Simulator Annual Operability Tests Index ............................................ 26 1
Appendix B Brunswick Simulator Malfunction Test ............. 27 Appendix C New Malfunctions Added To The Certified Malfunction Listing .............................. 31 Appendix D 1995-1998 Completed Test Schedules ............... 34 l
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CPEL BRUNSWICK UNIT TWO SIMULATOR CERTIFICATION INTRODUCTION General Information The Brunswick Steam Electric Plant Simulator Certification Quadrennial Report is provided to demonstrate compliance with the requirements of 10 CFR 55.45(b) including compliance with ANSI /ANS-3.5-1985 as implemented by NRC Regulatory Guide 1.149 Rev 1, 1987. The subject simulator facility consists solely of a plant referenced full scope simulator, which is the primary vehicle for providing positive, practical license training and examination. The documentation provided herein is intended to constitute sufficient basis for-the retention of the )'
certification of the Brunswick Simulator. The last renewal was submt.tted on March 21,1995.
1 Simulator Configuration Control Board
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One means of evaluation and review of the simulator operations is the Simulator Configuration Control Board (SCCB). The SCCB is tasked with the review and a training value assessment of proposed non-routine changes in design or scope to the simulation facility, simulator discrepancies that impact simulator training, and recent operating experience lessons learned that may be applied to the simulator. The SCCB also reviews the status of simulator certification testing to ensure compliance with the Test Schedule.
The SCCB is comprised of the Manager of Operations, Manager of Training, Superintendent-Operator Training, Team-Leader Licensed Operator Continuing Training (LOCT), Team-Leader Operator Initial Training (OIT),and Supervisor-Computer and Simulation Technology.
Other training and plant personnel may also participate in SCCB meetings as a function of the topics to be addressed.
The SCCB also reviews and accepts, through training value assessments, differences between the simulator and the plant to l ensure they do not impact the actions taken by the operator or l detract from training. Minutes of board meetings are maintained to serve as a record of SCCB decisions.
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CP&L BRUNSWICK UNIT TWO SIMULATOR CERTIFICATION Exceptions to ANSI /ANS 3.5 The exceptions listed below were identified at the time of the initial certification or the certification renewal of the Brunswick Simulator through certification testing or the review / analysis of ANSI /ANS 3.5. Each exception was previously reviewed and approved by the SCCB to ensure that they did not adversely impact the license operator training program and did not prevent 10 CFR 55 compliant simulator examinations (operating tests) from being conducted. The exceptions identified in this section are listed by ANSI /ANS 3.5 reference and subject. Each specific exception taken and associated justification is addressed individually and still applies to this submittal.
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- 1. ANS Section 3.1.1 - Normal Plant Evolutions (4) Reacto:' Trip Followed by Recovery to Rated Power.
The test that was conducted recovered the plant to 1% !
power, or the point of adding heat (POAH), not full power. Since the objective of this test is to mainly ensure that the positive reactivity of the control' rods can overcome the negative reactivity added by peak Xenon following a scram from high power, continuation of this evolution past the POAH is unnecessary, as the results will be the same as the startup from a cold shutdown condition. Additionally this evolution is not part of the training program. In today's environment, with event and root cause investigations, and the i Maintenance Rule impact, it is highly unlikely that a reactor startup would commence such that operator would be withdrawing control rods at the time of peak Xenon !
(12 to 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> after shutdown / scram). !
- 2. ANS Section 3.1.2 - Plant Malfunctions (la) Significant PWR Steam Generator Tube Leaks.
This is a Pressurized Water Reactor (PWR) specific transient'and not related to Boiling Water Reactors (BWR),
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(12) Misaligned Control Rods.
An exception is'taken to " malfunctions for misaligned control rods" as this is PWR specific'and not an independent malfunction for a BWR. On a BWR, any one of the other malfunctions (stuck rod, uncoupled rod, drifting rod, and rod drop) or operator error will l cause a misaligned rod condition, but a misaligned rod is not a malfunction in itself. On a PWR since control rods'are moved in banks, failure of one or more rods in l a bank to latch and move with the rest of the bank can cause a misaligned condition and be a malfunction in i' itself for a misaligned control rod. With a BWR moving only one rod at a time a misaligned condition would be i caused by one or more of the other malfunctions (stuck l
rod, uncoupled rod, drifting rod, and rod drop)-
occurring.
l (18) Failure of Reactor Coolant Pressure and Volume Control l Systems.
This is a PWR' specific transient and not related to
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BWRs.
i j (22) Process Instrumentation, Alarms, and Control System
! Failures. 1 l
l_ No malfunctions exist strictly for " Alarm Failures". A failure of alarms will occur when other malfunctions occur such as loss of logic power or control system failures. However, each annunciator window can be overridden with an Input / output override by the instructor to provide no alarm (alarm window overridden l
off), false alarm (alarm window overridden on) ni random actuating alarms (alarm window overridden on/c t) to simulate failures. Also the joystick for responding to alarms can be overridden to any position. Override features that affect the Input / output devices at the man-machine interface and do not alter the normal operation of simulated instrumentation within the model are not considered to na a malfunctions in accordance with ANS/ ANSI 3.5, and do not require testing.
Therefore, an exception is taken to the standard in Section 3.l.2 (22) requiring malfunctions for the failure of alarms.
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CPEL BRUNSWICK UNIT TWO SIMULATOR CERTIFICATION l 3. ANS Section 3.2.1 - Degree of Panel Simulation-l The plant Control Room is a two Unit Control Room, while the simulator is a single unit control room referenced to Unit 2
, for panels, labels, identifiers, controls, instrumentation, I alarms, and other man-machine interfaces. The differences between the simulator.and Unit 2 control boards (front panels), which are minor and mainly cosmetic in nature, are l discussed in Section II.B, Panels and Equipment. Plant l
l modifications implemented on Unit 2 are usually implemented on the simulator along with or prior to the plant installation, but in no caso does the time frame from the plant operability date to simulator implementation date l exceed one year.
An exception is taken on the simulatar back panels. They do not match the reference plant in number, location, size, shape, or overall configuration. A training value assessment and task analysis was previously conducted to analyze the scope of simulation needed to support training. As a result of this assessment and analysis, the back panels were upgraded to their current scope of simulation. The present configuration was then determined to meet training needs and was approved as a difference by the SCCB. All the back panels that are simulated though, are referenced to Unit 2 l for controls, instrumentation, labels, identifier', and I
other man-machine interfaces. The differences between the Unit 2 panels and the back panels that are simulated are limited and are discussed in Section II.B, Panels and Equipment.
- 4. ANS Section 3.2.3 - Control Room Environment 1
Exceptions are taken to the environmental differences that exist between the simulator control room and the plant control room. The primary differences are in the locations of' doors and windows, the shape and size of the room, physical 1.ayout of furniture, audio / video and fire suppression equipment, communication systems, and alarm sounds. All of these differences were reviewed and accepted by the SCCB as to not impact the actions taken by the L operator or to detract from training. Refer to Section II.A, Page 6 Rev 0 L
'CPEL BRUNSWICK UNIT TWO SIMULATOR CERTIFICATION Physical Arrangement, and Section II.D, Environment, for further details and discussion of these differences.
- 5. ANS Section 4.3 (4) - Reactor Coolant System. pressure versus temperature relationship indicative of gross core voiding, This is not a Simulator Operating Limit for a BWR and is considered specific to a PWR. A BWR has voiding by design and a PWR does not. Therefore gross core voiding in a PWR would be considered an-event beyond the implemented models or known plant behavior.
Steady state performance test at 25% power proved to be of no value. At this power level the turbine could be on or off line, second stage reheat could be in or out of service, and '
feed water beatin, may or may not be stabilized, thus making data hard to interpret. Since 'NSI/ANS-3.5-1,44, Appendix B, states to record the data at power levels for '< ch dera is normally available or record the data at approxtarcely 354, 75% and 100% rated thermal power, an exception is tar.;. -
use 50%, 75%, and 100% normally available data instead of the 25%,75% and 100% data. ,
- 7. ANS Section Appendix B2 - PWR Simulator Operability Test This item is specifically related to PWR and not applicable to BWRs.
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p-CP&L BRUNSWICK UNIT TWO SIMULATOR CERTIFICATION i
l I. GENERAL DESCRIPTION A. Owner The Brunswick Simulator is owned by Carolina Power and Light (CP&L) Company. The Simulator is located at the Brunswick Steam Electric Plant, about 2.5 miles north of Southport, North Carolina. CP&L has its headquarters in Raleigh, North Carolina about 135 miles northwest of .
the city of Southport.
B. Reference Plant The Brunswick Simulator simulates the Brunswick Unit 2 Control Room. Brunswick site consists of two, 895 Mwe, 2558 MWTH(UPRATED), General Electric Boiling Water Reactors.
. l C. Ready for Training Date The Simulator was built by Electronics Associates, Inc.
(EAI) of West Long Branch, New Jersey. The contract !
for the Simulator was signed August of 1980. EAI j delivered the Simulator to the site and training was '
started in February of 1984. From 1988 to present, ;
major modeling and executive system upgrades have been '
performed by EXITECH Corporation of Maryville, Tennessee. j l
D. Type of Report Quadrennial (4 Year) Report i
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i II. CONTROL ROOM COMPARISON A. Physical Arrangement l
There are three major exceptions taken to the Plant Control Room physical arrangement or layout. All of the below listed exceptions were reviewed and accepted by the SCCB as to not impact the actions taken by the operators or to detract from training.
The first exception is the. location of the Shift Technical Advisor (STA) desk, which is placed approximately five feet away from where it is located j in the Plant Control Room. This is due to access / egress '
requirements for the door in the simulator. Since the STA is rarely at his desk during training sessions, this change hes no impact on training.
The second exc eption is the location of the Shif t Supervisor / Communicator table. In the reference control room this table is located near the end of the P601 panel; however, due to constraints in the simulator for access to doorways, the desk is located near the XU-5 panel. Since this desk is rarely used during normal training (it is normally only used during plant Emergency Plan exercises for communications with the Technical Support Center and Operations Support Center), this location change has no impact on training, j The third exception is the location of the Senior Reactor Operator platform. This raised section of flooring is located approximately one foot further away from the P601 panel than in the reference control room.
It has been verified by Operations and Training that this difference does not affect the ability to see items on the Reactor' Turbine Gauge Board, therefore it has no impact on training. There are also minor spatial differences due to the Simulator Control Room not conforming exactly to Plant Control Room dimensions.
l These differences do not adversely affect training.
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CPfL BRUNSWICK UNIT TWO SINULATOR CERTIFICATION B. Panels and Equipment All control room (front) panels and controls are included in the simulation and are modeled after Unit
- 2. This consists of the following panels:
- 1. Emergency Core Cooling System panel (P601).
- 2. Reactor control panel (P603).
- 3. Main Turbine / Generator control panel (XU-1).
- 4. Feed pump / Diesel Generator control panel (XU-2).
- 5. Turbine / Balance. of Plant control panel (XU-3).
- 6. Turbine /Balar e of Plant recorder panel (XU-4).
- 7. Switchyard control panel (XU-5).
- 8. Primary Cratainment vent / purge panel (XU-51).
- 9. Steam Jet. Air Ejector /Off-Gas panel (XU-80). ,
j There are Fome differences between the simulator and i Unit 2 control room panels. These differences were capte;ed during the hardware verification process and were reviewed and accepted by the SCCB as to not impact
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tha action to be taken by the operators or detract from training. The notable' differences are summarized below.
The official list with the SCCB approval is not included as part of this report but is maintained available on-site.
- 1. Panel XU-1: Generator Primary Lockout, Generator Backup Lockout, Reactor Protection System Scram Test switches, and the Scram Channel Power Indicatiag Lamps are located on the back of panel XU-1 in the simulatcr and are not located there in the plant. This is due to Panels XU-8, P609, and P611, where these controls are actually located in
-the plant, are not simulated and it was determined these controls were i needed for manipulation and training i purposes.
- 2. Panel XU-2: The vertical section of the metal l panel in the simulator is flush with L the rest of the panels. In the plant i Unit 2 has a raised metal plate Page 10 Rev 0 l
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i installed over the panel for meter support. Also condensate conductivity i
recorder, CO-CR-24, is not the same model as the one in the plant due to there being no room currently to l
install a recorder of that size without replacing the entire vertical panel section. The Emergency Response Facility Information System (ERFIS) monitor in the plant fits flush with the panel. In the simulator an adjustable bezel was used to fill the gap around the monitor.
- 3. Panel XU-51:The vertical section of the metal i panel in the plant is flush with the
- rest of the panels. The simulator has a raised metal plate installed over the panel for meter support.
Selected back panels and controls are also included in i
^ the simulation and are modeled after Unit 2. A task analysis was conducted in March of 1990 to determine the scope of back panel simulation needed to support the required tasks. Plant Modification 91-031 was I developed and completed in December 1995, adding new l panels and upgrading some existing panels to meet these training requirements. The present configuration was then determined to meet training needs and approved as a difference, even though the simulated back panels (which are listed below) do not match the plant in physical dimensions, number, location, or configuration.
- 1. Source and Intermediate Range Monitoring / Radiation Monitoring panel (P606).
- 2. Traversing In-core Probe (TIP)/ Rod Worth Minimizer I panel (P607: partial panel-one of four Tip machines modeled). !
- 3. Average Power Range Monitoring (APRM) and Rod l l
Block Monitoring (RBM)/ Flow Unit panels (P608: '
partial panels-two of five panels modeled with all hardware, photos).
- 4. Steam Leak Detection / Temperature Recorder / Drain sump timer pane.' (P614).
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i j' 5. Reactor Building Ventilation Radiation monitoring panel (XU-55).
- 6. Drywell Radiation monitoring panel (XU-61).
l 7. Electro-Hydraulic Control First Hit panel (P644).
- 8. Process Radiation Monitor panel (P604).
- 9. Process Radiation Monitor / Post Accident Sampling System (PASS) panel ( XIc' -
! 10. Process Radiation Mon 4' 'kSSpanel (XU-79).
- 11. Select Rod Insert (SI p- el (P610),
- 12. Area Radiation Monito. 1 (P600).
- 13. Digital Feed Water panel (. 312: partial model of field bus modules, control processor, and power supplies),
l There are also some differences between the simulator and the Unit 2 back panels which are simulated. These differences were also captured during the hardware verification process and were reviewed and accepted by the SCCB as'to not impact the action to be taken by the operators or detract from training. The notable differences are summarized below. The official list with SCCB approval is not included with this report but is also available on-site.
- 1. Panel P608: On three of the five APRM/RBM Pe.nels, all of the panel internals are not modeled. Only two of the five, one in each trip channel, are modeled with I applicable switches, meters, and photographs to replicate the actual panels.
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- 2. Panel P607: Only one of four TIP Machines is modeled in the simulator. This partial simulation causes the RWM to be located in a different area of the panel in the simulator than in the plant. Also the X-Y Plot Recorder and j the Flux Probing Monitor do not l exactly inatch the ones in the plant.
l Since the TIP Machines are no. longer operated by the Operators, these differences do not impact training.
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CPKL BRUNSWICK UNIT TWO SIMULATOR CERTIFICATION
- 3. Panel P612: The simulator only partially models the field bus modules (FBM),the control i processors (CP) , and the power supplies l for Digital Feed Water, with all of the components located inside of panel 4
P612. The modules on Unit 2 are open
-to the outside of the cabinet, and have redundant components for each.
C. Systems l
L The Brunswick Simulator systems were modeled to L replicate the Unit 2 plant systems as' closely as data i
was available to support. However, several differences exist which requires the operator to operate the ]
Simulator in a different manner than the reference plant. The differences are as follows:
Installation of EOP jumpers in contro'. room equipment cabinets is done by remote function in the simulator.
Bypassing Local Power Range Monitor (LFRM) cards is done by remote function for APRMs A,B,E, and F.
For APRMs'C and D the bypass switches are modeled.
Bypassing the APRM flow units and resetting alarms is done by remote function for flow units A and B.
l For flow units C and D the switches are modeled.
Placing the APRM Flow Control Trip Reference (FCTR) cards in single loop /two loop and normal / setup conditions is done by remote functions for APRMs A,B,E, and F. For APRMs C and D the single loop /two loop switches and the normal / setup push buttons are modeled.
Reports to and from Unit 1 staff are done by the simulator operator.
D. Environment The environmental differences that exist between the Simulator and the Plant Control Room are summarized Page 13 Rev 0
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i below. All of these differences were determined not to j' impact the actions taken by the operator or to detract from training and were approved by the SCCB.
4 The actual shape, size, and walls of the simulator control room does not match the plant control room. The-
- Simulator contains Unit 2 only and has a white board on l -
one wall, while the plant has a dual unit control room l with no white board.
l I -The plant Unit 2 work request counter / window is fully enclosed with an entrance to the control room at the end of panel XU-5. The simulator has a entrance / exit door by the work request counter and another double l door by panel P601 that the plant does not have.
l The annunciator alarms produce a difference in sound 1 l between the Unit 1 and Unit 2 systems. The alarms for i l the Unit 2 Emergency Core Cooling System.(ECCS) panels i has a distinctly different sound from Unit'1. The sound of Unit 2's-alarms could not be replicated; therefore,
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m Unit l's sound was used for modeling the simulator. -j j
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The Simulator Control Room lighting and configuration approximates the Plant Control Room lighting as close as possible. Plant Control Room carpet color and arrangement as well as panel paint color have also been matched as close as possible. The carpet in the simulator does not exactly match the shade of the carpet in the plant; however, the colors and the layout of the dark and light carpet is the same.
The Simulatct ?ontrol Room has video cameras with microphones permanently installed in the ceiling and a
, Halon Fire Protection system with nozzles protruding-i from the ceiling, none of which are in the plant.
The. simulator has a-Public Address (PA) station on the j . wall by panel-XU-80. The plant does not have a PA in l, this location. This PA is connected to the actual plant l PA system instead of the simulator PA system and can be j activated for use during Emergency Plan Drills. It is i- not used during normal training. 1 j
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r CPTL BRUNSWICK UNIT TWO SIMULATOR CERTIFICATION III. Instructor Interface A. General Description The Brunswick Simulator has an instructor booth (or station) that is separated from the simulatos control Room and visually out of sight (one way mir cu :d glass) from the operators view. The instructor is able to observe the actions of the operator in the Simulator Control Room from the booth. A multiple camera audio / video system is provided in the simulator facility to allow better analysis of operator activity.
The audio / video system has been reviewed and accepted by the SCCB to not impact the actions taken by the operators or to detract from training.
The instructor has the capability of operating the simulator from the instructors booth or from a remote console on the simulator control room floor. Hand held remote operating controls are also available for inserting pre-planned simulation functions.
B. Simulator Initial Conditions The simulation device has storage for up to 300 Initial Condition (IC) sets. A controlled set of ICs(30)are stabilized and re-snapped after each major simulator modification / upgrade period but prior to training restart.
The ICs contain a minimum of four different times in core life; Beginning Of Life (BOL), Middle Of Life (MOL),
End Of Life (EOL), and EOL Coastdown For Final Feed Water Temperature Reduction (FFWTR), with different power levels to satisfy training objectives. These 30 ICs are password protected and can only be re-snapped by a qualified individual authorized by Training.
Twenty one IC slots are utilized for exam purposes only and are security protected such that they can neither be reset to or snapped without a password.
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CPEL BRUNSWICK UNIT TWO SIMULATOR CERTIFICATION C. Simulator Malfunction Selection.
The simulator contains the capability to insert any number of discrete malfunctions individually or in combination. The selection of malfunctions may be accomplished through command line entry or menu selection.
Malfunction severity, time to activation, and time to reach selected severity may be entered through the
' instructor station and modified as training objectives dictate.
Any number of malfunctions may be active at the same time. Malfunctions may also be initiated based on specific plant conditions. Deactivation and time delayed deactivation of malfunctions are also
~ facilitated.
The current status, such as delay times, severity
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rates, ramp times, and deactivation times, of any selected malfunction is readily available to the instructor through use of a summary display.
D. Simulator Overrides The instructor has the ability to override any simulated device (Input / Output devices) on the control room panels. For example, a meter may be driven to any value, a light may be turned on or off, or a switch may be failed to any position. These overrides may also be inserted with a time delay for activation and deactivation, and analog values may be ramped in over a specified time band.
The selection of overrides may be accomplished through command line entry, through a menu of available i overrides, or through a graphic display of the panel mimics. The current status of any selected override is readily available to the instructor through use of a summary display.
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CPtL BRUNSWICK UNIT TWO SINULATOR CERTIFICATION E. Controls Outside Control Room l
Plant procedures were reviewed to identify the local operator actions (Remote Functions) that were required to be performed in the field in order to accomplish the reference plant evolutions described in ANSI /ANS 3.5, SECTION 3.1.1 Normal Plant Evolutions and SECTION 3.1.2 Plant Malfunctions, including Emergency Operating Procedures. The identified local operator actions were then incorporated into the instructor station under
" Remote Functions". The instructor can simulate performing the required actions when directed by the operator through the activation of these remote l functions.
l Additional local operator actions are added to the scope of simulation as they are identified by training as being needed for execution of simulator tasks.
These local operator actions are available through the j
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same selection methods as malfunctions and overrides and their current status is also readily available to the instructor through use of a summary display.
F. Parameter and Equipment Monitoring The simulator instructor station has the capability of graphically monitoring the computer simulation through dynamic panel mimics.
l The instructor station system has the capability of monitoring and producing a trend plot of various system parameters simultaneously versus time. There is also the capability of obtaining a hard copy transient data in the form of data printouts through a program that resides in the computer for the system models.
Both the trend plots and the data printouts are capable of recording these multiple test parameters simultaneously versus time with a resolution of 0.5 i seconds or less. l l
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i CP&L BRUNSWICK UNIT TWO SIMULATOR CERTIFICATION G. Simulator Special Features Industry standard capabilities are available in the areas of switch check status, switch check override, run, freeze, backtrack, snapshot, fast time for certain
. parameters, and computer aided exercises.
Backtrack capabilities allow for four hours of storage at two minute intervals. The time between snaps of backtracks can be changed to lengthen or shorten this time.
The computer aided exercise feature of the Simulator allows the selection of preprogrammed lesson scenarios which will automatically step the simulator through a set of predefined operations and controls. This feature minimizes the setup time and manipulations required by the instructor, and provides standard, repeatable, and
. pre-planned exercises on the Simulator.
The Fast Time feature of the Simulator allows the instructor to accelerate through some plant evolutions that are not training intensive to a point where more training intensive evolutions can be given their proper attention. When FAST TIME is selected by the instructor, the dynamics of the selected plant i parameters will speed up while all other parameters I remain at real time. The following list of plant evolutions can be selected from the FAST TIME menu.
- Xenon Concentration
- Core Decay Heat
- Reactor Coolant Heat Up l
- Turbine Heat Up
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In accordance with ANSI /ANS 3.5 section 4.3, the l simulator will alert the instructor, by way of a message displayed on the instructor station screen, if I certain operating limits are exceeded which could lead
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to negative operator training or indicate that the simulator is proceeding beyond the limits of the implemented model or known plant behavior. The limits I
used to alert the instructor are the following: i Page 18 Rev 0
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! (1) Primary Containment Integrity Limit Exceeded > 93 ,
PSIG - This message is indicative of possible I primary containment structural failure. In accordance with UFSAR data, the primary containment was designed to maintain its functional integrity at 1.5 X the design pressure l limit (62 PSIG). The model is capable of further simulation, the limit is based on known plant behavior I l
(2) Reactor Pressure Safety Limit Exceeded > 1325 PSIG l - This message is indicative of exceeding the Reactor Coolant Pressure Safety Limit. In accordance with Technical Specifications, section
- 2.0, Safety Limits, the pressure limit is set high such that no foreseeable circumstances can cause the system pressure to rise to this limit. The model is capable of further simulation. The limit is based on known plant behavior.
(3) Gross Fuel Failure Probable - Fuel Temperature >
l _. 2780" F - This message is indicative of probable {
gross fuel failure. In accordance with Nuclear i Engineering And Science, SANDIA National Labs, Hydrogen Generation During Fuel / Coolant I Interactions, this fuel temperature limit is the onset of fuel meltdown and gross cladding failure.
The Zirc-Water reaction becomes auto-catalytic at clad temperatures of ~ 2700 F. The model is capable of further simulation. The limit is based on known plant behavior.
(4) Suppression Pool Unstable Condensation Limit -
Temperature > 200 F - This message is indicative of the onset of unstable steam condensation in the suppression chamber. In accordance with NUREG-0783, Suppression Pool Temperature Limits for BWR Containments, this is the maximum water temperature allowable at which condensation l
instability is known not to occur. The limit is based on known plant behavior.
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1 IV. Procedure Analysis 1
The procedures in the Simulator Control Room are controlled l copies of the procedures used in the Brunswick Steam Electric Plant Unit 2 Control Room therefore, no discrepancies exist.
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V. Simulator Changes Since Last Report A. Plant Modifications i All plant modifications continue to be reviewed for simulator impact. Numerous modifications have occurred to the plant since the last submittal. Those which affected the simulator have all been incorporated, with the more significant ones being listed below.
(1) Power Uprate to 105% power (2) Unit Auxiliary Transformer Backfeed Ability (3) Replace HPCI/RCIC GEMAC Controllers with Yokogawa Programmable Microprocesser-based Controllers (4) Removal Of Main Steam Line Radiation Monitors from i Reactor Protection and Containment Isolation j (5) Thermal Hydraulic Instability Option ElA-Added l Period Based Detection Circuitry and Flow Mapping l to APRM Rod Block and Scram Setpoints i B. Simulator Upgrades Three major model upgrades have occurred since the last submittal. Each upgrade was followed by a specific series of performance tests prior to being turned over to training. The following is the list of upgrades.
(1) Thermal Hydraulics Model for the Core, Nuclear Boiler, and Reactor Recirculation system (2) Main Steam Model (3) Core Neutronics Model with current Unit 2 Reload Page 20 Rev 0
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CP&L BRUNSWICK UNIT TWO SIMULATOR CERTIFICATION C. Other Upgrades The plant computer group is in the process of replacing )
the ERFIS System Digital Equipment Corporation (DEC) '
8600 computers in the plant and in the simulator with DEC 4000 systems. Also the simulator group will rehost from the current Silicon Graphics Incorporated (SGI) computer system in the simulator to Windows NT based j Pentium computers. Both upgrades are being done to become Y2K compliant by mid 1999.
VI. Simulator Design Data Base The original simulator design data base consisted of plant reference drawings and system test results which were sent to the simulator vendor for simulator construction. This set of reference documents constitutes the as-built data base and was entered into the Configuration Management System (CMS) by document name and revision number. The current simulator data base was developed from the original data base and updated with plant modification data. The data base is now kept current with plant data. I VII. Simulator Discrepancy Resolution and Upgrading Programs A. Simulator Service Request Program Discrepancies noted in the simulator during testing or training sessions are documented in the Simulator Problem Report Book. The Problem Reports are then used by the simulator staff to generate Simulator Service i Requests (SSRs) to evaluate the problem and to identify I the corrective actions. SSRs are also used to request additions, deletions, or other changes that would make for more effective training or simulator improvement.
Documentation used to research the problems is attached to the SSR for inclusion into the CMS as part of the i Simulator Update Design Data Base. I i
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i CPtsL BRUNSWICK UNIT TWO SIMULATOR CERTIFICATION B. Plant Modification Implementation All Plant Modifications / Engineering Service Requests (ESR), prior to final approval for implementation, are reviewed by the training staff concurrent with the plant review for applicability and impact to the simulator and existing training material. Plant Modifications which are within the current simulator scope and have an effect on the simulator are assigned a Simulator Modification Request (SMR) number. Plant Modifications which are outside the current scope of ,
the simulator but which may have an impact on training j are reviewed by the SCCB for possible implementation on '
the simulator. If a decision is made to implement the Plant Modification on the simulator, an SMR is generated to perform and document the work.
l Plant Modification related SMRs are scheduled to be completed no later than one year after the modification is declared operable in the plant. If the SCCB determines that the SMR has significant training value,
'~
it may be implemented prior to its completion in the plant in order that the operators may be trained on its operation prior to actual plant turn over. The completed SMR package is maintained as part of the Simulator Update Design Data Base. j C. Simulator Configuration Management System
'l The simulator CMS is a PC-based management and design control system used to track simulator consistency with the plant, performance or certification testing, modifications, and maintenance. This system is used for recording and tracking SMRs and SSRs. Based on the relative importance of the modification or severity of the problem, a four level priority system is applied to determine work scheduling. When all work is completed, the status of the item is updated in the CMS computer.
The CMS computer is also used to provide necessary reports to management on the status of outstanding SMRs and SSRs.
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CPEL BRUNSWICK UNIT TWO SIMULATOR CERTIFICATION VIII. Simulator Tests A. Certification Test Schedule l The simulator certification testing is carried out in l accordance with the Simulator Certification Test l Schedule. The testing is typically accomplished by SRO certified individuals using approved test procedures.
The-tests are based on Brunswick Steam Electric Plant data, similar plant data, engineering best estimate l analysis, or a panel of experts. The selection of I
simulator performance tests topics were based on ANSI /ANS 3.5-1985 requirements. The Simulator 4 Operability Testing (Refer to Appendix A of this submittal) is based on the requirements of ANSI /ANS 3.5-1985, Appendix B as stated in Section 5.4.2 and as endorsed by Section C.6lof Regulatory Guide 1.149 ;
Revision 1, 1987. The Malfunction Testing (Refer to I Appendix B of this submittal) is based on the requirements of Regulatory Guide 1.149 Revision 1, 1987 .
as stated in Section C.5 for malfunctions identified in 4 l ANSI /ANS 3.5 1985 Section 3.1.2.
- 1. Annual Operability Tests l
The annual operability tests include the simulator Operating Limits Test, computer Real Time Test, simulator Repeatability Test, the Steady State Stability and Comparison Tests, and Transient Tests. Appendix A of this submittal lists the tests which currently make up the Brunswick Annual Operability Test Schedule along with a cross reference to the applicable ANSI /ANS 3.5 reference ,
section. This test schedule differs from the '
previous submittal test schedule as discussed in Section VIII.C of this submittal.
- 2. Malfunction Tests Malfunctions available on the simulator and incorporated in the operator training program have l been formally tested by an individual performance, l typically at the time of inclusion. In addition Page 23 Rev 0
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p l CP&L BRUNSWICK UNIT TWO SIMULATOR CERTIFICATION i malfunctions included in the simulation to meet l the requirements of ANSI /ANS 3.5-1985 Section 1 3.1.2, are tested on a periodic basis. These tests are scheduled such that approximately 25 percent
- of these required malfunctions are tested each year. The number of performance tests will be'
' adjusted as malfunctions are added or deleted from the certification test program as dictated by operator training program requirements. These additions and/or deletions will be noted in subsequent quadrennial reports, however, the test I program will be maintained in compliance with ANSI /ANS 3.5-1985. Appendix B of this submittal lists the malfunctions which are currently certified and the schedule for terting over the next four years. The malfunction t.ests are divided in such a manner that most plant systems are tected each year. Appendix B also contains a cross-reference to the applicable ANSI /ANS 3.5 reference section. i B. Certification Test Schedule 1995-1998 All tests for the 1995-1998 certification period were performed in accordance with the test plan submitted with the 1995 Quadrennial Certification Renewal Report.
In addition, due to plant modifications, simulator upgrades, plant operating experience reports, and changes to the training task lists, twenty six new malfunction tests and three operator conducted surveillance tests were added and tested. See Appendix C of this submittal for a list of the tests added, reason'for the addition, and a cross reference to the applicable ANSI /ANS 3.5 section.
All tests conducted for the 1995-1998 test plan were completed satisfactorily. Refer to Appendix D of this submittal for a summary of the 1995-1998 completed test schedule, which includes a list of the test performed each year, dates performed, test status, and retest date if applicable. Also in Appendix D, following the l
completed test schedules, are the abstracts for the new
[ tests that were conducted during the 1995-1998 period.
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.CPEL BRUNSWICK UNIT TWO SIMUIATOR CERTIFICATION C. Certification Test Schedule 1999-2002 The certification test schedule for 1999-2002 is composed of both the Annual Operability Tests and the Quadrennial Malfunction Tests. The quadrennial rest schedule.for malfunctions is similar to the previously submitted certification test schedule except for the addition of twenty six new malfunctions that were added in the 1995-1998 test years. Appendix B of this submittal is the list of these malfunctions and the schedule for testing them during 1999-2002 test period.
The Annual Operability Test schedule is quite different from the previous submittal. The Ncrmal Plant Evolutions Tects, Core Performance Tests, and Operator
, Conducted Surveillance Tests, are no longer a part of the Annual Operability Test schedule. In accordance with ANSI /ANS 3.5 1985 Appendix B and Regulatory Guide 1.149 Revision 1, 1987 Section C.6, these tests are not required'to be part of the Annual Operability Tests schedule. Also during the previous eight years of testing, these tests seldom detected a problem and consequently were adding no value to the test program by performing them annually. These tests will still remain a part of the simulator over all Performance Test Plan as described in ANSI /ANS 3.5-1985 Section 5.4.1 but will not be a part of the Annual Operability Tests as described in AMSI/ANS 3.5-1985 Section 5.4.2.
These tests will now only be performed as needed for post maintenance testing of systems / components when limited changes are made to the software or following significant configuration changes, such as new co.a models or computer rehosting. Appendix A of this submittal is the list of Annual Operability Tests to be performed during the 1999-2002 test period.
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Appendix A Brunswick Simulator Annual Operability Tests Index j
l BRUNSWICK SIMULATOR FOUR YEAR CERTIFICATION SCHEDULE 4
('
Note: The following Simulator Test Procedures should be performed with a frequency of once per calendar year I. SIMULATOR OPERATING LIMITS TEST l STP-OL-001 Simulator Operating Limits Test (4.3)
!!. COMPUTER REAL TIME TEST STP RT-001 Simulator Peal Time Test (Appendix A A3.(1))
STP-RP 001 Simulator Repeatability Test (N/A)
!!!. STEADY STATE l
STP-SS-002' 501 Power Steady State Comparison (4.1)
STP-SS 003 75% Power Steady State Comparison (4,1)
STP SS-004 1001 Power Steady State Comparison (4.0 IV. TRANSIENTS STP-TN-001 Manual Scram .
Appendix B Bl.2 STP-TN-002 . Simultaneous Trip All Feedwater Pumps Appendix B BL 2 STP-TN-003 - Simultaneous Closure of All MSIVs Appendix B Bl.2 STP-TN 004 Simultaneous Trip Of Both Rectre. Pumps Appendix B Bl.2 STP-TN-005 Single Recirc Pump Trip Appendix B Bl.2 STP TN-006 Turbine Trip Does lot Result In An Immediate Rx SCRAM (Unit 2) Appendix B Bl.2 STP TN-006.1 Turbine Trip Does Not Result In An imediate Rx SCRAM (Unit 1) Appendix B Bl.2 STP-TN-007 . Max Rate Power Ramp-Recirc Flow Controller in Manual (1001 751 1002) Appendix B Bl.2 STP-TN-008 DB LOCA in Conjunction With loss Of Offsite Power Appendix B Bl.2 .
STP TN-009 Maximum Size Unisolable MSL Rupture Appendix B Bl.2 STP-TN-010 MSIV Closure With 1 Stuck Open SRV With High Pressure ECCS Inhibited Appendix B Bl.2 l
-STP-TN-011. Inadvertert HPCI Initiation Appendix A A3.3 i l
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c Appendix B Brunswick Simulator Malfunction Tests BRUNSWICK SIMULATOR FOUR YEAR CERTIFICATION SCHEDULE Note: The following Malfunction Simulator Test Procedures should be performed in their entirety not less than every four years, approximately 253 per year (Reg Guide 1.149 C.S.) (Frequency of once per four calendar years):
V. MALFUNCTIONS YEAR ONE STP-MA 001 NB 140 Recirc Pump A Suction Line Rupture 0-100* 0 60 min 3.1.2(1)(b)&(c)
STP-MA-008 MS 154 MSL Break In Steam Tunnel 0-1003 0 60 min 3.1.2(1)(b)&(c)(20)
STP MA-012 AI 349 Instr Air Rupt Destr of Dryers 0-100% 0-60 min 3.1.2(2)
STP-MA-021 DG 311 Loss Of Substation E8 None None 3.1,2(3)b STP-MA-028 EE 395 Irdividual Bus failures (Partial) None None 3.1.2(3)d STP-MA-031 EE 345 Loss of 4160 Bus None None 3.1.2(3)d STP-MA-035 RL 115 Recire knp MG Set Fid Bkr Trip None None 3.1.2(4)
STP MA-041 CW 247 Nuc SW Hdr Rupture 0-100* 0-60 min 3.1.2(6)
STP-MA-042 CA 255 Loss Of RBCCW To DW Coolers None None 3.1.2(8)
STP-MA-054 CF 212 Cond Xfer Sys Rupture None lione 3.1 2(5)
STP-MA-055 CN 190 Loss Of Condenser vacuum 0-+1E6#/HR 0-60 min 3.1.2(5)
STP MA-062 RH 284 RHRT Pump Trip None Ncne 3.1.2(7)
STP-MA-063 CF 200 Condensate Pump Sheared Shaft None None 3.1.2(9)
STP MA-065 CF 200 Cond Bstr Pmp Sheared Shaft None None 3.1.2(9)
STP-MA-071 CF 221 Feedwater Pump Sheared Shaft None None 3.1.2(9)
STP-MA 088 RD 001 Control Rod slow insertion Drift None None 3.1.2(12)c STP-MA 090 XX 012&016 Control Rod Drop None None 3.1.2(12)d STP-MA 091 RD 017 CRD FCV 'A' Fails Closed None None 3.1.2(13)
STP MA-099 MS 169 Main Turbine Trip (Unit 2) None None 3 1.2(15)
STP-MA-099.1 MS 169 Main Turbine Trip (Unit 1) None None 3.1 2(15)
STP-MA-103 ES 269 RCIC Turbine Speed Control Failure None None 3 1.2(17)&(22)
STP-MA-105 RP 045 Spurious Scram None None 3.1.2(19)
STP-MA-108 NI 130 Rec /APRM Flow Inst Fails Dnsci None None 3.1.2(21)&C22)
STP-MA-109 NI 046 SRM Frils Hi None None 3.1.2(21)&(22)
STP-MA-112 NI 058 IRM Fails Hi None None 3.1.2(21)&(22)
STP-MA 115 NI 076 APRM Fails Hi None None 3.1.2(21)&f22)
STP-MA.118 N1 092 LPRM Fails High None None 3.1.2(21)&(22)
STP-MA-126 NB 236 RX Lvl Xmitter B21-N004 Fails 0-100* 0-60 min 3.1.2(22)
STP-MA-127 DG 320 DG Auto Start Failure None None 3.1.2(23)
STP-MA-128 ES 113 ADS Logic Failure None None 3.1.2(23)&(22)
STP-MA-130 ES 261 HPCI Logic Bus A Auto Start Fails None None 3.1.2(23)
STP-MA 136 MS 162 EHC Pressure Regulator Fails High None None 3.1.2(25)&(22)
STP MA 141 MS 181 All Turb BPV #1 Fails Open None None 3.1.2(25)
STP-MA-147 CF 147 Feedwater Line Break In Drywell 0-100* 0-60 min 3.1.2(20)
STP-MA-152 RP 111 Manual Scram Defeat None None 3.1.2(23)
STP-MA 231 RW 231 RWCU Break In Triangle Room 0-1002 0-60 min 3 1.2(1)(b)
STP-MA-264 ES 264 HPCI Hydraulic Failure None None 3.1 2(22)&(23)
STP-MA 276 RH 276 'A' RHR Inj Viv F015 Stuck Closed None None 3.1 2(17) 51P-MA-292 RH 292 RHR Heat Exchanger Bypass Valve Trip None None 3 1.2(17)
STP-MA 298 EE 298 Auto Voltage Reg. Failure None None 3 1.2(3)&(22)
STP-MA-309 EE 309 Main Transformer Cooling System Failure None None 3.1.2(3)&(B)
STP MA 409 EE 409 Station Blackout None None 3.1.2(3)
STP-MA-415 DG 415 DG #3 AVR Trip None None 3.1.2(3)ca(22)
STP-MA-416 DG 416 DG #4 AVR Trip None None 3.1.2(3)t&(22)
STP MA-420 NB 420 Core Region To Downcomer Leak 0 1002 0-60 min 3.1.2(d)
STP-MA-A25 MS 425 EHC Pump Fails To AUTO Stirt None None 3.1.2(25)
STP MA-426 RC 426 Recirc Pump Runback To Limiter 1 None None 3.1.2(17)
STP-MA-431 CF 431 Scram Discharge Volume Rupture 0-100* 0-60 min 3.1.2(1)(b)
STP-MA-435 NB 435 Pen X49A Line Break None None 3.1.2 (22)
STP-MA-439 ES 439 E41 F002 FAILURE TO AUTO CLOSE .ONE NONE 3.1.2 (22)& (23)
STP-MA-446 N1 446 APRM FCTR CARD INOP NONE NONE 3.1.2 (21)& (22)
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p Appendix B Brunswick Sinclator Halfunction Tests BRUNSWICK SIM)LATOR FOUR YEAR CERTIFICATION SCHEDULE
. Note: The followirg Malfunction Simulator Test Prcadures should be performed in their entirety not less than every four years.
l approximately 252 per year (Reg Guide 1.149 C.S.) (Frequency of once per four calendar years):
l l V. . MALFUNCTIONS YEAR TWO l- STP-MA-002 NB 141 Recirc Pump A Disch Line Rupture 0-100% 0-60 min 3.1.2(1)(b)&(c) l STP MA 009 MS 155 MSL Break In Turbine Building 0-100% 0-60 min 3.1.2(1)(b)&(c)(20)
STP-MA 013 AI 365 Service Air Rupture. None None 3.1.2(2) i STP-MA 025- DG 331 DG Governor Failure High None None 3.1.2(3)c STP-MA-026 EE 297 Main Xfmr Sud Press Dev Actuates . None None 3.1.2(3)d STP-HA 028' EE 395 Individual Bus Failures (Partial) None None 3.1.2(3)d l STP.MA-032 DG 333 UPS Failure .
None None 3.1.2(3)e l STP-MA-036 RC 117 Recirc Pmp MG Set Bus Bkr Trip None None 3.1.2(4)
STP-MA 043 CW 252 _ TBCCW Hx Plugged 0 100* 0-60 min 3.1.2(6) i STP-MA 050 XY 317 Stator C1g Temp Controller Fails None None 3.1.2(8)&(22) j STP-MA 051 MS 191 MTLO Temp Cntrlr Fails None None 3.1.2(8)&(22) 1 STP-MA-053 CF 194 H/W Rej Viv Falls Closed None None 3.1.2(8)&(22)
STP-MA-057 CN 242 CW Pmp Disc viv Fails Closed None None 3.1.2(5) '
[ STP-MA-061 CW 286 RHR SW Pump Breaker Fault None None 3.1.2(7)
STP-MA-068 CF 216 LP FW Heater 28 Tube Leak 0 500Kf/HR 0 60 min 3.1.2(9)
STP MA-077 CF 234 RFP Low Suction Press None None 3.1.2(9)
STP-MA-083 RP 108 . RPS MG Set trip None None 3.1.2(11)
STP-MA 087 RD 005 Control Rod withdrawal Drift None . None 3.1.2(12)c STP-MA-092 RD 018 CRD Pump Suction Filter Plugged None None 3.1.2(13) J
,, STP-MA 094 RD 398 RWM Loss Of Power None None 3.1.2(13) I
- STP-MA-100 EE 299 Main Generator Trip None None 3.1.2(16)
STP-MA 102 ES 263 HPCI Power Supply Failure None None 3.1.2(17) i STP MA 107 NI 103 SRM/IRH Drive Mtr Power Failure None
' None 3.1.2(21)
STP-MA 110' NI 047 SRM Fails to None None 3.1.2(21)&(22)
- STP MA 114 NI 059 IRM Fails As is None None 3.1.2(21)
STP MA-119 NI 093 LPRM Fails to None None 3.1.2(21)&(22)
STP MA-122 N1 100 SRM CH A Stuck Detector None None 3.1.2(21)
STP-MA-131 - ES 267 HPCI Logic Bus B Auto Start fails None None 3.1.2(23)
STP-MA 132 XY 393 DEFEAT OF GROUP 2 ISOLATION LOGIC Nono None 3.1.2(23)
STP-MA-137 MS 163 EHC Pressure Regulator fails Low None None 3.1.2(25)&(22)
STP MA-145 ES 156 ADS Valve Fails Open None None 3.1.2(1)(d)
STP MA 148 ES 138 HPCI Steam Brk HPCI Room 0-1002 0 60 min 3.1.2(1)(b)(c)&t20)
STP-MA-151 RC 121 'A' Recire Pump fl Seal Failure 0-1001 0-60 min 3.1.2(1)(b)(c)
. STP-MA 155 RW 149 ' RWCU Resin Injection into tactor Vessel None- None 3.1.2(non specif tc)
-STP-MA-167 MS 167 MSIV Failure To Auto Close None None 3.1.2(23)
STP-MA 304 EE 304 Grid Load Increase None None 3.1.2(3)
STP-MA-354 Al 354 2D Air Comp Fails To Load None None 3.1.2(2)
STP-MA-361 RM 361 Rx Building vent Monitor fails Downscale- None None 3.1.2(22)
STP-MA-367. AI 367 Rx Bldg Air Receiver Leak 0-375sefm0-60 min 3.1.2(2) !
STP-MA 369 CA 369 58GT Inadvertent initiation None None 3.1.2(22) j STP MA 403 CF 403 C32-FTN002(Feed Flow) Failure 0 1001 0-60 min 3.1.2(22)
STP-MA-410 ES 410 HPCI Auto Start Failure None None 3.1.2(17)&(22)
STP-MA-413 ES 413 'A' RHR Failure To Auto Start None None 3.1.2(17)&(22)
STP-MA 417 DG 417 DG AVR Fails High - None None 3.1.2(3)c&(22)
STP-MA 421 NB 421 Isolation Of Condensing Pot D004A None None- 3.1.2(22)
STP.MA-427 RC 427 ' Recirc Pump Runback To limiter 2 Nr.,ne
)
None 3.1.2(17) {
STP-MA-429 MS 429 Failure of Turbine Auto Trip Ckt None None 3.1.2(22)
STP MA-432 ES 432 ' Core Spray Suction Strainer Plugging 50 802 0-60 min 3.1.2(23) j STP-MA-436 NB 436 Pen X49B Line Break None None 3.1.2(22) l l STP-MA-440 ES 440- E41.F003 FAILURE TO AUTD CLDSE NONE NONE 3.1.2 (22)&(23) ;
i STP-MA 443 NB 443 LASALLE TRANSIENT THI NONE NONE 3.1.2 (a) (e) l:
l.
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Appendix B Brunswick Simulator Halfunction Tests i
BRUNSWICK SlHULATOR FOUR YEAR CERTIFICATION SCHEDULE Note: The following Malfunction Simulator Test Procedures should be performed in their entirety not less than every four years, approximately 253 per year (Reg Guide 1.149 C.S.) (Frequency of once per four calendar years):
V. HALFUNCTIONS YEAR THREE l
STP-MA 006 ES 274 RCIC Steam Break- South RHR 0-1002 0 60 min 3 1.2(1)(b)&(c) i STP-MA 011 ES 161 SRV B21-F013E Setpt Drift Low None None 3.1.2(1)(d)
STP-MA-017 Al 368 Pneumatic Leak in The Drywell 0-100scfm0 60 min 3.1.2(2)
STP-MA-018 EE 305 Loss Of Offsite Power None None 3.1.2(3)a STP-MA 022 DG 334 Loss Of Substation E7 None None 3.1.2(3)b STP-MA 024 DG 330 DG Governor Failure Lew None None 3.1.2(3)c&(22) l STP MA 028 EE 395 Individual Bus Failures (Partial) None None 3.1.2(3)d I STP-MA 033 EE 336 Loss Of 250v DC Bus A None None 3.1.2(3)e STP M 037 RC 126 Recirc Pmp Shaft Seizure None None 3.1 2(4)
STP.MA-040 CW 248 Cony SW Hdr Rupture 0-100% 0 60 min 3.1.2(6)
STP-MA 045 MS 173 Exh Hood Spr Viv Fails Closed Fixed 5-50 min 3.1.2(8)
STP-MA-046 CW 249 RBCCW Pmp Suct Hdr Rupture 3-100% 0 60 min 3.1.2(6)
STP MA-059 CN 324 Loss Of SJAE None None 3.1.2(5)
STP MA 064 CF 203 Condensate Pump Locked Rotor None None 3.1.2(9)
STP-MA-073 CF 224 RFP 28 Turbine Overspeed None None 3.1 2(9)
STP-MA 080 CF 239 RFP Min Flow Viv Fails Open None None 3.1 2(9)
STP MA-081 CF 234,261.267 Loss Of All Feedwater dormal& Emerg None None 3.1.2(10)
STP MA-082 RP 107 RPS Channel Failure None None 3.1.2(11) !
STP MA-085 RD 012 Stuck Control Rod None None 3.1.2(12)a 1
~ STP MA-089 RD 031 Control Rod Fast Insertion Delft None None 3.1.2(12)c STP-MA-095 RD 042 Rod Block Monitor A Fails Downscale None None 3 1.2(13)&(22) l STP-MA 098 NB 143 Fuel Failure 0-1001 0-60 min 3.1.2(14)
STP MA-101 ES 259 CS Valve F005 Fails To Open None None 3.1.2(17)
STP-MA-106 CF 225 FW Htr f5 Outlet Line Rupture 0-100% 0 60 min 3 1.2(20)
STP-MA-111 NI 048 SRM Fails As is None None 3.1.2(21)
STP-MA-ll3 NI 061 IRM Fails Lo None None 3.1.2(21)&(22)
STP.MA 116 NI 077 APRM Fails lo None None 3.1.2(21)&(22)
STP-MA 121 NI 098 LPRM Erratic Operation None None 3.1.2(21) j STP-MA 125 NI 105 APRM C Inconsistent With Others None None 3.1.2(21) l STP-MA 133 RP '96 S/D Cing Hi Rx Press Perm fails None None 3.1.2(23)&(22)
STP-MA-138 MS 168 EHC Pressure Regulator Oscillation 0 100% 0 60 min 3.1.2(25)&(22)
STP MA 139 MS 180 Turb BPV #1 Fails Open None None 3.1.2(25)
STP-MA-143 CA 350 DW CLG Fan Damper Failure None None 3.1.2(8) j STP MA-153 RC 123 Rectre Pump Seal #2 Fails 0-100% 0-60 min 3.1.2(1)(b)(c) 1 STP MA 164 RM 164 MSL Rad Monitor Fatis Downscale None None 3.1.2(22)
STP-MA-182 MS 182 Loss Of Turbine Bearing 011 Pressure None None 3.1.2(15)
STP MA 232 RW 232 RWCU Brea In Return Line 20' 0 1002 0 60 min 3 1.2(1)(b)
STP MA 250 RW 250 RBCCW HI Rad 0-100% 0-60 min 3.1.2(8)
STP-MA 251 CW 251 RBCCW HX/SW Tube Leak 0 1002 0 60 min 3.1.2(8)
STP-MA-328 NB 328 Small recirc Suction Line Rupture 0-1002 0-60 min 3 1. 2(1 ) < b)&lc )
STP-MA 362 RM 362 Rx Building Vent Monitor falls Upscale None None 3.1.2(22)
STP-MA 405 CA 405 Broken Downcomer Quadrant 1 0 100% 0-60 min 3 1 2(23)
STP MA 412 ES 412 *B' Core Spray Failure to Aut) Start None None 3.1.2(17)&(22)
STP.MA-418 DG 418 DG AVR Falls low None None 3.1.2(3)c&t22)
STP-MA-422 NB 422 Isolation Of Condensing Pot D004B None None 3.1.2(22) ;
STP-MA-428 RC 428 Recirc Pump Auto Trip failure None None 3.1.2(17) i STP-MA 430 CF 430 Isolable FW Line Break in Drywell 0 1003 0 60 min 3.1.2( W STP MA 434 ES 434 RCIC FIC CPU Failure None None 3.1.2(, )&(22)
STP.MA 437 RW 437 G31-F001 FAILURE TO AUTO CLOSE NONE NONE 3.1.2 (22)&(23)
STP MA 441 ES 441 E51 F007 FAILURE TO AUTOCLOSE NONE NONE 3.1.2 (22)&(23) l STP-MA-444 NB 444 UNIT 1 LOCA NONE NONE 3.1.2 (Non Specific)
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Appendix B Brunswick Simulator Malfunction Test:
BRUNSWICK SIMULATOR FOUR YEAR CERTIFl".ATION SCHEDULE Note: The following Malfunction Simulator Test Procedures should be performed in their entirety not less than every four years, approximately 253 per year (Reg Guide 1.149 C.S.) (Frequency of once per four calendar years):
V. MALFUNCTIONS YEAR FOUR STP-MA 003 NB 139 Instrument Rack Ref Leg Drain None None 3.1.2(22)
STP-MA-004 NB 153 MSL 0 BRK Before Flow Restrictor 0-1003 0-60 min 3.1.2(1)(b)&(c)(20) !
STP-MA-005 RC 335 Recirc Pump A Dual Seal Failure None None 3.1.2(1)(b)&(c)
STP MA-010 ES 159/160 SRV Not Properly Seated 0-1001 0-60 min 3.1.2(1)(d)
STP-MA 016 RD 114 Loss Of Cntrl Air To the Scram N %100% 0-60 min 3.1.2(2)
STP-MA 020 : EE 338 Unit 2 SAT Relay failure s one None 3.1.2(3)a STP-MA 023 DG 326 DG Output Breaker Trip Nt 'e None 3.1.2(3)c STP-MA-027 EE 331 4KV Common Bus B Trip Nons None 3.1.2(3)d STP MA-028 EE 395 Individual Bus Failures (Partial) None None 3.1.2(3)d j
STP-MA 038 RC 132 Recirc HG Se'. woling Water Loss None None 3 1.2(8)
STP-MA-039 CN 246 Total Loss Of CW Pump Seal Water None None 3.1.2(5)&(8)
STP-MA-044 - CW 381 TBCCW lx Disch Hdr Rupture 0-100* 0-60 min 3.1.2(6)
STP.MA 047 RD 019 CR0 Drive Water Filter Plugged None None 3.1.2(8)&(13)
STP-MA 048 RW 151 RWCU N/R Hx Hi Outlet Temp None None 3.1.2(8)
STP-MA 049 XY 314 Gen Mr Clg TCv Fails Closed None None 3.1.2(8)&(22)
STP-MA-052 CF 193 H/W Make-up Viv Fails Closed None None 3.1.2(8)&(22)
STP MA 060 MS 189 Turb Steam Seal Reg Fails Closed None None 3.1.2(5)
STP-MA 070 CF 218 HP f Heater 48 Tube Leak 0 920Kf/HR 0-60 min 3.1.2(9) j STP-MA-072' CF 223- RFP 2A Lube Oil Leak 1000 gal 30 min 3.1.2(9)
STP-MA 076 CF 233 S/U Lvl Cont Viv Fails Closed None None 3.1.2(9)
STP-MA-084 RP 112 RPS SCRAM Group slown Fuse None None 3.1.2(11)
STP MA 086 RD 016 Control Rod Uncoupled None None 3.1.2(12)b STP.MA-097 RD 044 Rod Motion Timer Failure None None 3.1.2(13)&C22)
STP-MA-117 NI 078 APRM Fails As is None None 3.1.2(21)
STP MA 120 'NI 094 LPRM Fails As Is None None 3.1.2(21)
STP MA-123 NI 101 IRM Stuck Detector None None .3.1.2(21)
STP-MA 124 NI 104 SRM/IRM Overlap Incorrect None None 3.1.2(21)
'STP-MA-129 ES 392 HPCI Inject Viv Fails To Auto Open None None 3.1.2(23)
STP MA 134 RP 382 ATWS Fixed None 3.1.2(24)
STP-MA-135 'RP 110 Auto Scram Defeat None None 3.1.2(24)
STP-MA-140 .MS 180A Turb BPV #1 Fails Closed None None 3.1.2(25) i STP-MA-142 MS 181A All Turb BPV #1 Fails Closed None None 3.1.2(25) 1 STP-MA-144 CA 357 DW CLG Fan failure None None 3.1.2(8)
STP-MA-146 ES 146 HPCI S Mam Line Break - MiniStm Tunnel 0-1005 0 60 min 3.1.2 (1)(b):(c)&t20)
STP MA-150 NI 099 LPRM Bypass None None 3.1.2(2t)
STP-MA 154 RC 144 Recirc Pump MG Set Scoop tube Failure None None 3.1.2(17)(22)
STP-MA-188 . RW 188 . RWCU Break in Heat Exchanger Room 0-100* 0-60 min 3.1.2(1)(b)
STP MA 268' ES 268 RCIC Turbine Trip None None 3.1.2(22)
STP MA-271- ES 271 RCIC Inadvertent Start None None 3.1.2(17)&(22)
STP-MA 275 ES 275- RCIC Injection Valve Overload None None 3.1.2(17)
.STP MA 306 EE 306 230KV Transmission Line trip None None 3.1.2(3)
STP-M-399 RM 399 MSL Rad Monitor 'B' Fails Upscale None None 3.1.2(22)
STP-MA 406 CA 406 SRV Ta11 pipe Rupture' None None 3.1.2(23)
STP-MA-411 ES 411 RCIC Fall to Auto Start None None 3.1.2(17)&(22) l STP-MA 419 .DG 419 DG Differential Fault None None 3.1.2(3)c STP-MA-423 CW 423 CW Screen HI Delta P Fixed 1-60 min 3.1.2(5)
STP MA-424 RH 424 ' RHR Suction Strainer Clogging 50-802 0-60 min 3.1.2(7)&(23)
STP-MA 433 ES 433 HPCI FIC CPU Failure None None 3.1.2(17)&(22)
'STP-MA-438 RW 438 G31 F004 FAILURE TO AUTO CLOSE NONE NONE 3.1.2 (22)&(23)
STP MA;442 ES 442 E51-F008 FAILURE TO AUTO CLOSE NONE NONE 3.1.2 (22.1 & (23)
STP-MA 445 RC 445 RECIRC PUMP LIMITER 2 FAILURE NONE NONE 3.1.2 (17)
STP-MA 447- NI 447 RBM POWER SUPPLY FAILURE NONE NONE 3.1.2 (21)& (22)
Page 30 Rev 0
Appendix C NEW MALFUNCTIONS ADDED TO THE CERTIFIED MALFUNCTION LISTING 1995-1998 Certification TEST MALF S ANSI /ANS 3.5. NEW MALFUNCTION NUMBER NUMB Y 1985 TITLE REASON FOR ADDITION ER S - CROSS REFERENCE STP-MA- 367 Al 3.1.2 (2) RX BLDG AIR Previously non-certified malfunction convertea to 367 RECEIVER LEAK certifled malfunction _
STP-MA- 426 R 3.1.2 (17) RECIRC PUMP SMR-95-0080. Malfunction added at instructors 426 C RUNBACK TO request to cause Recin: pumps to runback to # 1 LIMITER 1 limiter STP-MA- 427 R 3.1.2 (17) RECIRC PUMP SMR-95 -0081 Malfunction added at instructors 427 C RUNBACK TO request to cause Recirc pumps to runback to #2 l
, LIMITER 2 limiter i STP-MA- 428 R 3.1.2 (17) RECIRC PUMP A . TO SMR-95 0082 Malfunction added at instructors 428 C TRIP FAILURE request to cause Recire pump auto trip failure STP-MA- 420 N 3.1.2(d) CORE REGION 10 SMR 93-0318. Malfunction added at management 120 B DOWNCOMER LEAK request due to cracking in plant shroud for demonstration purposes. Made certified in 1995 STP MAi 4?9 M 3.1.2(22) FAILURE OF SMR 95-0077 Malfunction added at instructors 429 S TURBINE AUTO TRIP request to cause a main turbine auto trip failure.
CKT STP-MA- 430 C 3.1.2(20) ISOLABLE SMR 95-0251, Malfunction added at instructors 430 F FEEDWATER LINE request to have break in drywell that is isolable.
BREAK IN DRYWELL STP-MA- 431- R 3.1.2(1)(b) SCRAM DISCHARGE SMR 95-0250. Malfunction added a nstructors 431 D VOLUME RUITURE request to have a leak from SDV to . . ndary containment that stops when scram . reset.
STP MA- 432 E 3.1.2(23) CORE SPRAY SMR 95-0368. Added due to industry events I 432 S SUCTION STRAINER dealing with potential loss of ECCS systems due {
PLUGGING - to clogged suctions. NRC Info Notice 93 34 STP MA- 433 E 3.1.2(17)(22) IIPCI FIC CPU SMR 95-0226 (PM 92-080) Malfunction added as 433- S FAILURE most likely failure mode for new microprocessor j based programmable controller that replace l GEMAC ilow controller i STP-MA- 434 E 3.1.2(17)(22) RCIC FIC CPU SMR 95-0226 (PM 92-080) Malfunction added as 434 S FAILURE most likely failure mode for new microprocessor based programmable controller that replace GEMAC flow controller STP-MA- 139 N 3.1.2(22) INSTRUMENT RACK Previously non-certified malfunction converted to 003 B REF LEG DRAIN certified malfunction STP-MA. 435 N 3.1.2(22) rr:N X49A LINE SMR96-0359 Malfunction added as 435 B BREAK recommendation from ANSI 3.5 Self Assessment Audit Page 31 Rev 0
I Appendix C l
J NEW MALFUNCTIONS ADDED TO THE CERTIFIED MALFUNCTION LISTING !
l 1995-1998 Certification TEST MALF SY , ANSI /ANS 3.5, NEW MAITJNCTION NUMBER NUMB S 1985 TITLE REASON FOR ADDITION ER CROSS REFERENCE' STP RP- N/A N/ N/A SIMULATOR Added to test schedule as recommendation from Of ' A REPEATABILilY ANSI 3.5 Self Assessmant Audit TEST STP-MA- 436 NB 3.1.2(22) PEN X49B LINE SMR96-0359 Malfunction added as 436 BREAK recommendation from ANSI 3.5 Self Assessment Audit STP-MA- 437 RW 3.1.2 (22)&t23) G31-F001 FAILURE SMR 97-0224 CONVERTED FROM REMOTE 437 TO ALTTO CLOSE FUNCTION TO MALFUNCTION STP-MA- 438 RW- 3.1.2 (22)&l23) G31-F004 FAILURE SMR-97-0224 CONVERTED FROM REMOTE 438 TO ALTTO CLOSE FUNCTION TO MALFUNCTION 1
STP-MA- 439 ES 3.1.2 (22)&(23) E41 F002 FAILURE SMR-97-0224 CONVERTED FROM REMOTE 1 439 TO ALTTO CLOSE FUNCTION TO MALFUNCTIGN STP-MA- 440 ES - 3.1.2 (22)&(23) E41-F003 FAILURE SMR-97-0224 CONVERTED FROM REMOTE 440 TO AlfrO CLOSE FUNCTION TO MALFUNCTION STP-MA- 441 ES 3.1.2 (22)&t23) E51 F007 FAILURE SMR-97-0224 CONVERTED FROM REMOTE 441 TO AUTO CLOSE FUNCTION TO MALFUNCTION STP MA- 442 ES 3.1.2 (22)&(23) E51-F008 FAILURE SMR-97-0224 CONVERTED FROM REMOTE 442 TO ALTTO CLOS'd FUNCTION TO MALFUNCTION STP-MA- 443 NB 3.1.2 (a)(c) LASALLE TRANSIENT SMR-97-0221 CONVERIED FROM REMOTE 443 THI FUNCTION TO MALFUNCTION STP-MA- 444 NB 3.1.2 (Non UNIT-1 LOCA. SMR-97-0221 CONVERTED FROM REMOTE 444 Specific) FUNCTION TO MALFUNCTION STP MA- 445 RC 3.1.2 (17) RECIRC PUMP SMR-07-0222 CONNERTED FROM REMOTE 445 LIMITER #2 FAILURE FUNCTION TO MALFUNCTION STP-MA- 446 NI 3.1.2 (2!)&t22) APRM FCTR CARD SMR-97-0314 MALFUNCTION ADDED TO 446' INOP SIMULATE SELF TEST FAILURE OF DIGITAL FCTR CARD FOR THI STP-MA- 447 NI 3.1.2 (21)&(22) RBM POWER SUPPLY SMR-98-0201 MALFUNCTION ADDED TO 447 FAILIRE SIMULATE EVENT FROM PLANT AND GE SIL NO. 599 Page 32 Rev 0 4.
1 I
i
- Appendix C l
4, s PLANT PERIODIC TESTS ADDED TO OR DELETED LfF 1995-1998 Certification PLANT !
SIMULATOR 1 PERIODIC TEST PERIODIC TEST TITLE TEST NUMBER PROCEDURE REASON FOR ADDITION OR DE
}
-f- 217-15,4 STP-MV- !
752 SECONDARY CONTAINMENT INTEGRrlY <
ADDED TO VERIFY SBGT ABILTIY TO MA OPT-15.8 STP-MV. IN VAC AT 3000 SCFM IAW TECH SPEC 753 POST ACCIDENT SAMPLING VALVE OPERABILITY TEST ADDED TO VERIFY ASSOCIATED VALV Dirr 24.4 STP-MV- DATA MATCHES REFERENCE PLANT DAT 754 SERVICE WATER SYSTEM VALVE OPERABILl1Y TEST ADDED TO VERIFY ASSOCIATED VALV DATA MATCHES REFERENCE PLANT DAT}
i s
l Page 33 Rev 0 l
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c-l TEST ABSTRACTS FOR NEW TESTS ADDED DURING 1995-1998 TESTING t-l SCHEDULE ARE ATTACHED TO THIS REPORT FOLLOWING THIS PAGE l
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PERFORMANCE TEST ABSTRACT PTA-MA-367 1.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE-1.1 STP-MA-367, Rx Bldg Air Compressor Leak 1.2 ANSI /ANS 3.5 1985, Section 3.1.2 Plant Malfunctions,
-(2) Loss of Instrument Air 2.0 AVAILABLE OPTIONS 2.1 This malfunction allows selection of either 2A and/or 2B Rx Bldg Air Compressors.
3.0 TESTED OPTIONS 3.1 MALFUNCTION NUMBER): 367 3.2 MALFUNCT!JN SYMBOL.:MAIO10F (MAIOO7F) 3.3 MALFUNCTION MENU...:AI 3.4 SELECTED Air Compressor: 2A 2B 4.0 INITIAL CONDITIONS 4.1 The simulator is operating at approximately 300% steady state reactor power.
4.2 A recording device is setup to record the following test parameters simultaneously versus time with a resolution of 0.5 seconds or less:
i 4.2.1 Rx Bldg Div I Air Pressure...........AIPRXA 4.2.2 Rx Bldg Div II Air Pressure..........AIPRXB 4.2.3 Drywell Div I Air Header Pressure. .AIPNID1 4.2.4 Drywell Div II Air Header Pressure..AIPNID2 5.0 TEST DURATION 5.1 The recording device will be stopped after the effects of the malfunction have stabilized.
l 6.0 BASE LINE DATA l
6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power Plant Training Simulator, latest Revision.
I 7.0 DATE PERFORMED: 8-26-95 SSP
-PTAMA367 REV 0
8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES.
NONE 9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION.
NONE SSP PTAMA367 REV 0
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l PERFORMANCE TEST ABSTRACT PTA-MA-426 I 1
1-. 0 PROCEDURE TITLE / ANSI 3.5 REFEP.ENCE l~ . l ' .STP-MA-426, Recirc Pump Runback To Limiter 1 1.2 ANSI /ANS 3.5 1985, Section 3.1.2 Plant Malfunctions, (17) Failure in automatic control systems that affect reactivity
~2.0. AVAILABLE OPTIONS 2.1 This malfunction allows selection of either 2A and/or 2B Reactor Recirculation Pumps.
3.0 TESTED OPTIONS
)
3.1 MALFUNCTION NUMBER.:426 3.2 MALFUNCTION. SYMBOL.:MAIO24F (MAIO25F)
- 3.3 MALFUNCTION MENU.. :RC 3.4 SELECTED Recirc Pump: 2A 2B 4.0 INITIAL CONDITIONS 4.1 The simulator is operating at approximately 100% steady state reactor power.
4 .' 2 A recording device is setup to record the following test parameters simultaneously versus time with a resolution of 0.5 seconds or less:
4.2.1 2A Recirc Pump Flow.................NBWFLOW(10) 4.2.2 2B Recirc Pump Flow......... ......NBWFLOW(11) 4.2.3 Reactor Water. Level (150 - 210")... IARXLVL }
j 4.2.4 Reactor Power......... ............NIJAPRM l
l 5.0 TEST DURnTION
- 5. l' The recording device will be stopped after the effects of the' malfunction have stabilized.
6.0 BASE LINE DATA l 1
6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power Plant Training Simulator, latest Revision.
1 SSP j PTAMA426 REV 0
I 7.O DATE PERFORMED: 7-15-95 )
8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES.
NONE 9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION.
NONE SSP PTAMA426 REV 0
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i PERFORMANCE TEST ABSTRACT PTA-MA-427 l 1.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE 1.' l STP-MA-427, Recirc Pump Runback To Limiter 2 1.2 ANSI /ANS 3.5 1985, Section 3.1.2 Plant Malfunctions, (17) Failure in automatic control systems that affect reactivity-2.0 AVAILABLE OPTIONS 2.1 This malfunction allows selection of either 2A and/or 2B Reactor Recirculation Pumps.
3.0 TESTED OPTIONS 3.1 MALFUNCTION NUMBER.:427 3.2 MALFUNCTION SYMBOL.:MAIO26F (MAIO27F) 3.3 MALFUNCTION MENU. .:RC 3.4 SELECTED Recirc Pump: 2A 2B 4.0 INITIAL CONDITIONS 4.1 The simulator is operating at approximately 100% steady state-reactor power.
4.2 A recording device is setup to record the following test parameters simultaneously versus time with a resolution of 0.5 seconds or less:
4.2.1 2A Recirc Pump Flow......... ......NBWFLOW(10) 4.2.2 2B Recirc Pump Flow. ..............NBWFLOW(11) 4.2.3 Reactor Water Level (150 - 210")... IARXLVL 4.2.4 Reactor Power..... ........ .......NIJAPRM 5.0 TEST Dr. .N 5.1 The recording device will be stopped after the effects of the malfunction have stabilized.
6.0 BASE LINE DATA I 6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power Plant Training Simulator, latest Revision.
SSP PTAMA427 REV 0
7.0 DATE PERFORMED: 7-15-95 )
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8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES.
NONE 9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION.
NONE i
SSP PTAMA427 REV 0
PERFORMANCE TEST ABSTRACT PTA-MA-428 1.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE 1.1 STP-MA-428, Recirc Pump Auto Trip Failure 1.2 ANSI /ANS 3.5 1985, Section 3.1.2 Plant Malfunctions, (17) Failure in. automatic control systems that affect reactivity 2.0 AVAILABLE OPTIONS 2.1 This malfunction allows selection of either 2A and/or 2B Reactor Recirculation Pumps.
3.0 TESTED OPTIONS i 3.1 MALFUNCTION NUMBER.:428 3.2 MALFUNCTION SYMBOL.:MAIO28F (MAIO29F) 3.3 MALFUNCTION MENU...:RC 3.4 SELECTED Recirc Pump: 2A 2B 4.0 INITIAL CONDITIONS !
l 4.1 The simulator is operating at approximately 100% steady state reactor power.
1 5.0 TEST DURATION 5.1 The Simulator will be placed in FREEZE after the l effects of the malfunction have stabilized.
6.0 BASE LINE DATA 6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power Plant Training Simulator, latest Revision.
l L 7.0 DATE PERFORMED: 7-15-95 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES.
NONE 9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION.
NONE SSP PTAMA428 REV 0
p PERFORMANCE TEST ABSTRACT PTA-MA-429 1.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE 1.1 STP-MA-429, Failure of Turbine Auto Trip Ckt 1.2 ANSI /ANS 3.5 1985, Section 3.1.2 Plant Malfunctions, (22) Process instrumentation, alarms, control system failures.
2.0 AVAILABLE OPTIONS 2.1 None 3.0 ' TESTED OPTIONS 3.1 MALFUNCTION NUMBER.:429 3.2 MALFUNCTION SYMBOL.: MMS 052F 3.3 MALFUNCTION MENU...:MS i
'4 . 0 ' INITIAL CONDITIONS 4.1 The simulator is operating at approximately 100% steady state reactor power.
5.0 TEST DURATION 5.1 The Simulator will be placed in FREEZE after the )
effects of the malfunction have stabilized.
6.0 BASE LINE DATA 6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power l Plant Training Simulator, latest Revision.
7.0 DATE PERFORMED: 12-04-95 !
8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN l OR PLANNED, AND ASSOCIATED DATES.
NONE 9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION.
NONE i
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SSP PTAMA429 REV 0
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PERFORMANCE TEST ABSTRACT PTA-MA-420
1.0 PROCEDURE
TITLE / ANSI 3.5 REFERENCE 1.1 STP-MA-420, Core Region to Downcomer Leak.
1.2 . ANSI /ANS 3.5.1985, Section 3.1.2 Plant Malfunctions, (d)" Local Site. Considerations and. Plant Specific Operating Experience.
2.0 . AVAILABLE OPTIONS: l 2.1 . Severity of 0 to'100% break size, located inside the reactor above_the top guide.
.2.2 Severity Rate of 0 to 60 minutes 3.0. TESTED OPTIONS 3.1 MALFUNCTION NUMBER.:42C 3.2- MALFUNCTION SYMBOL.:MNB011F 3.3- MALFUNCTION MENU...:NB 3.4 This Malfunction is. tested with a severity of 100% and a severity rate of 0 minutes.
4.0 . INITIAL CONDITIONS 4.1 The simulator is operating _at approximately 100% steady state power.
4.2 A recording device is setup to record the following test; parameters simultaneously versus time with a resolution of 0.5 seconds or less:
4.2.1 2A Recirculation Pump Temperature..:NBTAV(20) 4.2.2 2B Recirculation Pump Temperature..:NBTAV(22) 4.2.3'2A Recirculation Loop Flow.........:NBWFLOW(10) 4.2.4 2B Recirculation Loop Flow.... ....:NBWFLOW(11) 4.2.5 Actual Core Flow....... ...........:NBWMIX(2) 4.2.6 Core Delta' Pressure................:NBDELTPT(21) 4.2.~7 Reactor Power........ .............:RXQNCORE 4.2.8 Generator Megawatts. ........... ..:EGJGMWE 5.0 TEST DURATION 5.1- -The recording device will be stopped after the effects of this malfunction have syabilized.
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6.0- BASE LINE DATA 6 .1. BWROG 94114 Operator Actions to detect potential core shroud cracks during normal operations
'6. 2 Malfunction Cause and Effect for Brunswick Unit 2 Power Plant Training Simulator, latest Revision.
SSP PTAMA420 REV 0 h
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7.0 DATE PERFORMED: 12-05-95 l
8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN i OR PLANNED, AND ASSOCIATED DATES.
NONE 9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION.
NONE SSP PTAMA420 REV 0
PERFORMANCE TEST ABSTRACT PTA-MA-430 1.0 ' PROCEDURE ~ TITLE / ANSI 3.5
REFERENCE:
1 ~.1 STP-MA-430, ISOLABLE FEEDWATER LINE BREAK IN DRYWELL 1.2 ANSI /ANS 3.5 1985, Section'3.1.2 Plant Malfunctions, (20)
Main Steam Line . as well as Main ~ Feed Line Break (both inside and outside containment) 2.0 AVAILABLE OPTIONS 2.1 Severity of 0 to .100% rupture of the selected feedwater line inside of the Drywell ' upstream of the check valve B21-F010 2.2 Severity. Rate of 0 to 60 min.
2.3 This Malfunction allows selection of either Feedwater Line A or:Feedwater Line B.
3.0 TESTED OPTIONS 3.1 MALFUNCTION NUMBER.:430
~
3.2 MALFUNCTION SYMBOL.:MCF050F, MCF051F 3.3. MALFUNCTION MENU...:CF 3.4 Component selected.. A B 3.5 This malfunction is tested with severity of 100% and a severity rate of 0 minutes.
4.0 INITIAL CONDITIONS 4.1 The simulator is operating at approximately 100% steady state power.
4.2 A recording device is setup to record.the following test parameters-simultaneously versus time with a resolution of 0.5 seconds or less:
4 2.1 .Rx Water Level (0 to 210").......:NBLEVELT(5) 4.2.2 ~Rx. Water Level (-150 to 150")....:NBLEVELT(7) '
4 2.3 A-Feedwater Line Flow (FT-N002A).:CFWlREAT 4.2.4 B Feedwater Line Flow (PT-N002B) :CFW1REBT 4.2.5 FW Fl:,w to RPV on Affected Line..:CFW1REA 4 9.E l CFW1 REB :
4'.2.6 Reactor Pressure (0 to 1500).. ..:NBPITAPT(31) 4.2.7 Drywell Pressure.................: CAP 0010
- 4.2.8 Suppression Pool Temperature.....
- CAT 2120 i 4.2.9 Suppression Chamber' Pressure.. ..: CAP 0020 SSP STPMA430 Rev 0
5.0 TEST DURATION 5 .1~ The recording device will be stopped after 10 minutes has elapsed or unit conditions have stabilized.
6 '. 0 BASE LINE' DATA 6.1 Malfunction-Cause and Effect for Brunswick Unit 2 Power Plant Training Simulator, latest revision.
7.0 DATE PERFORMED: 8-21-96 8.0 DEFICIENCIES FOUND DURING. TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES.
NONE 9.O EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION.
NONE SSP STPMA430 Rev 0
PERFORMANCE TEST ABSTRACT PTA-MA-431 1.0. PROCEDURE TITLE / ANSI 3.5 REFERENCE 1.1 STP-MA-431; Scram Discharge Volume Rupture 1.2 ANSI /ANS 3. 5' 1985, _Section- 3.1.2 Plant Malfunctions, (1) (B) Loss of Coolant outside primary containment.
2.0, AVAILABLE OPTIONS 2.1 Severity of 0 to 100% of an instantaneous line rupture on
.the scram discharge volume header on the south side of RX Bldg 20ft area overhead.
2.2 Severity rate of 0 to 60 minutes.
3.0 TESTED OPTIONS 3.1 MALFUNCTION NUMBER.:431 3.2 MALFUNCTION.-SYMBOL.:MRD045F 3.3 MALFUNCTION MENU...:RD 3.4 This Malfunction is tested with a' severity of 100% and a severity rate of 0 minutes..
4.0. INITIAL CONDITIONS 4.1 The simulator is operating at approximately 100% steady state power and a manual scram is inserted.
4.2 A recording device is setup to record the following test parameters simultaneously versus time with a resolution of 0.5 seconds or less:
4.2.1 Rx Bldg 20ft North Area Temp.....:HVT25765 4.2.2 Rx Bldg 20ft South Area Temp.....:HVT25767 4.2.3 Rx Bldg 50ft Area Temp...........:HVT25766 OR Rx Bldg 50ft Area Temp.... ......:HVT25768 l 4.2.4 Scram Discharge V,lume Level.....:RDLSDVLS 4.2.5 South Core Spray Sump Level.. ...:WDL10005 5.0 TEST DURATION 5.1 The recording device will be stopped after 10 minutes has elapsed or unit conditions have stabilized.
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6.0 BASE LINE DATA I
6.1 Malfunction Cause and'Effect for Brunswick Unit 2 Power Plant Training Simulator, latest revision.
7.0 DATE PERFORMED: 8-22-96 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES.
NONE ,
j 9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION.
NONF. )
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. PERFORMANCE TEST ABSTRACT PTA-MA-432 1.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE 1.1 .STP-MA-432,-CORE Spray Suction Plugging
'1.2 ANSI /ANS 3.5 1985, Section'3.1.2 Plant Malfunctions, (23) Passive Malfunctions:in systems, such as engineered safety features, emergency feedwater systems.
2.0 AVAILABLE OPTIONS l2 .1 Severity of 50% to 80% clogging of suction strainer.
2.2- Severity Rate of 0 to 60 minutes 2.3- Selectable to A or B Loop Suction Strainer 3 .' O TESTED OPTIONS 3.1 MALFUNCTION NUMBER.:432 3.2 MALFUNCTION SYMBOL.: MESO 49F.MES050F- i
. 3.3 MALFUNCTION MENU...:ES 3.4 COMPONENT SELECTED.: A B 3.5 This Malfunction is ' tested with a severity of 80% and a severity rate of 0 minute.
4.0~ INITIAL CONDITIONS 4.1 The simulator is operating with A (B) Loop of Core Spray in full flow test.
4.2 A recording device is setup to record the following test parameters simultaneously-versus time with a resolution of 0.5 seconds or less:
4.2.1 2A CS Pump Suction Pressure...: CSP 0001 OR 2B CS Pump Suction Pressure...: CSP 0021 4.2.2 CS Loop A. Flow................:CSW0002 Or CS Loop B Flow................:CSW0022 4.2.3 2A CS Pump Diacharge Tressure.: CSP 0002 3r 2B CS Pump Discharge Pressure.: CSP 0022 SSP PTAMA432 REV 0 g
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1 i 5.0 TEST DURATION 5.1 The recording device will be stopped after 10 minutes or unit conditions have stabilized.
6.0 BASE LINE DATA 6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power Plant Training Simulator, latest Revision.
7.0 DATE PERFORMED: 8-21-96 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN ,
OR PLANNED, AND ASSOCIATED DATES.
NONE 9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION.
NONE l
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i SSP PTAMA432 REV 0
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PERFORMANCE TEST ABSTRACT PTA-MA-433 1.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE i
1.1 STP-MA-433, HPCI FIC CPU FAILURE.
1.2 ANSI /ANS 3.5 1985, Section 3.1.2 Plant Malfunctions,
( l'7 ) Failure in Automatic Conrol Sys. that affect reactivity and Core heat removal (22) Process instrumentation, alarms, and control system failures .
2.0 AVAILABLE OPTIONS NONE 3.0 TESTED OPTIONS 3.1 MALFUNCTION NUMBER.:433 3.2 MALFUNCTION SYMBOL.:MES051F 1 3.3 MALFUNCTION MENU...:ES )
4.O INITIAL CONDITIONS 1 4.1 HPCI system is operating and injecting to the vessel with an auto initiation signal present. For test purposes Malfunction #262 can be used to inadvertently initiate HPCI.
4.2 A recording device is setup to record the following test parameters simultaneously sersus time with a resolution of 0.5 seconds or less:
4.2.1 HPCI Pump Discharge Pressure. :HPP0003 4.2.2 HPCI Pump Flow....... . . .
.:HPFHPCI 4.2.3 HPCI Turbine Speed. . .. . .
- TMS5660S(4) 5.0 TEST DURATION 5.1 The recording device will be stopped after the affects of the malfunction have been verified.
6.0 BASE LINE DATA 6.1 Malfunction Causc and Effect for Brunswick Unit 2 Power Plant Training Simulator, latest Revision.
1 SSP PTAMA433 REV 0
7.0 DATE PERFORMED: 8-23-96 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES.
NONE 9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING
.TUSTIFICATION.
NONE l
SSP PTAMA433 REV 0
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i PERFORMANCE TEST ABSTRA21 PTA-MA-434
.l.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE 1.1 STP-MA-434, RCIC FIC CPU FAILURE.
1.2 ANSI /ANS 3.5 1985, Section 3.1.2 Plant Malfunctions, 1 (17) Failure in Automatic Conrol Sys. that affect i
reactivity and Core heat removal (22) Process !
instrumentation, alarms, and control system failures .
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2.0 AVAILABLE OPTIONS i
NONE 3.0 TESTED OPTIONS 3.1 MALFUNCTION NUMBER.:434 j 3.2 MALFUNCTION SYMBOL.:MES052F 3.3 MALFUNCTION MENU...:ES i
4.0 INITIAL CONDITIONS 4.1 RCIC system is operating and injecting to the vessel wi.th an auto initiation signal present. For test i purposes Malfunction #271 can be used to inadvertently initiate RCIC, i l
4.2 A recording device is setup to record the following test parameters simultaneously versus titue with a resolution of 0.5 seconds or less:
4.2.1 RCIC Pump Discharge Pressure..:RJP0002 4.2.2 RCIC Pump Flow... ..... . . .:RJFRCIC 4.2.3 RCIC Turbine Speed.. . .
..:TMS6660S(3) 5.0 TEST DURATION 5.1 The recording device will be stopped after the affects of the malfunction have been verified.
6.0 BASE LINE DATA 6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power Plant Training Simv'ator, latest Revision.
SSP PTAMA434 REV 0
7,0 UATE PERFORMED: 8-23-96 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES.
NONE '
9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION.
NONE SSP PTAMA434 REV 0
. PERFORMANCE TEST ABSTRACT PTA-RP-001 l
I 1.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE !
1.1 STP-RP-001, Simulator Repeatability Test 1.2 ' ANSI /ANS 3.5 1985 2;0 AVAILABLE OPTIONS 2.1. This test is performed by conducting two executions of I
at least two simulecor Transient Test Procedures.
3.0 TESTED OPTIONS 3.1 STP-TN- 003 and STP-TN- 004 1
! 4.0 INITIAL CONDITIONS NONE 5.0 TEST DURATION 5.1 Each execution of a transient test will be run for 10 minutes or until unit conditions have stabilized.
6.0 BASE LINE DATA NONE
, 7.0 DATE PERFORMED: 3-24-98 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES.
NONE _
l 9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION.
NONE l
l SSP IrfARP001 REVO l
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,, PERFORMANCE TEST ABSTRACT PTA-MA-435 1.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE 1.1 STP-MA-435, PEN X49A LINE BREAK 1.2 ANSI /ANS 3.5 1985, Section 3.1.2 Plant Malfunctions, (22) Process Instrumentation, Alarms, and Control System Failures.
2.0 AVAILABLE OPTIONS NONE 3.0 TESTED OPTIONS 3.1 MALFUNCTION NUMBER.:435 3.2 MALFUNCTION SYMBOL.:MNB014F 3.3 MALFUNCTION MENU. iNB 4.0 INITIAL CONDITIONS 4.1 The simulator is operating at approximately 100% steady state power.
5.0 TEST DOHATION 5.1 The simulator will be placed in the FREEZE mode after
, unit conditions have stabilized.
6.0 BASE LINE DATA 6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power Plant Training Simulator, latest Revision.
7.0 DATE PERFORMED: 10-22-96 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES.
NONE 9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION.
NONE SSP PTAMA435 1 REV 0
PERFORMANCE TEST ABSTRACT PTA-M1.-436 1.0 PROCEDURE TITLE / ANSI 3.5 REFERINCE 1.1 STP-MA-436, PEN X49B LINF BREAK 1.2 ANSI /ANS 3.5 1985, Sectie1 3.1.2 Plant Malfunctions, (22) Process Instrument . ion, Alarms, and Control System Failures.
2.0 AVAILABLE OPTIONS NONE 3.0 TESTED OPTIONS 3.1 MALFUNCTION NUMBER.:436 3.2 MALFUNCTION SYMBOL.:MNB015F 3.3 MALFUNCTION MENU., :NB 4 4.0. INITIAL CONDITIONS 4.1 The simulator is operating at approximately 100% steady state power.
5.0 TEST DURATION 5.1 The simulator will be placed in the FREEZE mode after unit conditions have stabilized.
6.0 BASE LINE DATA 6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power Plant Training Simulator, latest Revision.
7.0 DATE PERFORMED: 10-22-96 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES.
NONE 9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION.
NONE 1
SSP PTAMA436 1 REV 0 c.
, PERFORMANCE TEST ABSTRACT PTA-MA-003
.l.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE 1,1 STP-MA-003, INSTRUMENT RACK, REF LEG DRAIN 1.2 ANSI /ANS 3.5 1985, Section 3.1.2 Plant Malfunctions, (22) Process Instrumentation, Alarms, and Control System' Failures.
2.0 AVAILABLE OPTIONS NONE 3.0 TESTED OPTIONS 3.1 MALFUNCTION NUMBER.:139 3.2 MALFUNCTION SYMBOL.:MNB001F 3.3 MALFUNCTION MENU...:NB 4.0 INITIAL CONDITIONS 4.1 'The simulator is operating at approximately 100% steady state power.
5 ~. 0 TEST DURATION 5.1 The simulator will be placed in the FREEZE mode after unit conditions have stabilized.
6.0 BASE LINE DATA :
6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power Plant Training. Simulator, latest Revision.
7.0 DATE PERFORMED: 10-22-96 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES.
NONE 9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION.
- NONE l
SSP PTAMA003 1 REV 0 L: j
PERFORMANCE TEST ABSTRACT PTA-MA-437 1.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE 1.1 STP-MA-437, 031-F001 Failure To Auto Close. l 1.2 ANSI /ANS 3.5 1985, Section 3.1.2 Plant Malfunctions, (22) Process instrumentation, alarms, and control system failures AND (23) Passive malfunctions in systems, such as engineered safety features, emergency feed water systems.
2.0 AVAILABLE OPTIONS NONE 3.0 TESTED OPTIONS 3.1 MALFUNCTION NUMBER...:437 3.2 MALFUNCTION SYMBOL. :MRW015F 3.3 MALFUNCTION MENU. :RW 4.O INITIAL CONDITIONS 4.1 The Simulator is operating at 100% power with RWCU in service. A small break LOCA of sufficient severity to cause reactor level to decrease below LL2 will be initiated with malfunction #437 active.
4.2 A recording device is setup to record the following test parameters simultaneously versus time with a !
resolution of 0.5 seconds or less:
4.2.1 Reactor Water Level.. . .. :NBLEV26T(2) 4.2.2 G31-F001 Valve Position. .. . .:VMRW001 4.2.3 G31-F004 Valve Position. ... .:VMRWOO4 i
SSP PTAMA437
r-5.0 TEST DURATION 5.1 The recording device will be stopped after the affects of the malfunction have been verified.
6.0 BASE LINE DATA 6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power Plant Training Simulator, latest Revision.
l 7.0 DATE PERFORMED: 9-10-97 8.O DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES NONE 9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION.
NONE SSP PTAMA437 1
_ __ --_-_-_a
F.
PERFORMANCE TEST ABSTRACT PTA-MA-438 1.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE 1.1 STP-MA-438 G31-F004 Failure To Auto Close.
1.2 ANSI /ANS 3.5 1985, Section 3.1.2 Plant Malfunctions, (22) Process instrumentation, alarms, and control system failures AND (23) Passive malfunctions in systems, such as engineered safety features, emergency feed water systems.
2.0 AVAILABLE-OPTIONS j
NONE 3.0 TESTED OPTIONS 3.1 MALFUNCTION NUMBER.. :438 3.2 MALFUNCTION'SYi1BOL. .:MRW016 3.3 MALFUNCTION MENU. . ..:RW 4.0 INITIAL CONDITIONS I 4.1 The Simulator is operating at 100% power with RWCU in service. A small break LOCA of sufficient severity to cause reactor level to decrease below LL2 will be initiated with malfunctions #438 active. i 4.2 A recording device is setup to record the following test parameters simultaneously versus time with a !
resolution of 0.5 seconds or less: I 4.2.1 Reactor Water Level.. . ..
.:NBLEV26T(2) 4.2.2 G31-F004 Valve Position. .:VMRWOO4 4.2.3 G31-F00lValve Position. . . :VMRWOOl I
I SSP PTAMA438 REV 0
1 l
l l
l 5.0 TEST DURATION 5 , l' The recording device will be stopped after the affects of the malfunction have been verified.
6.0 BASE LINE DATA 6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power Plant Training Simulator, latest Revision.
7.0 DATE PERFORMED: 9-10-97 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES.
l NONE 1
9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION.
NONE 1
1 4
SSP l PTAMA438 REV 0 l
l l
PERFORMANCE TEST ABSTRACT PTA-HA-439 l.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE 1.1 STP-MA-439, E41-F002 FAILURE TO AUTO CLOSE 1.2 ANSI /ANS 3.5 1985, Section 3 l.2 Plant Malfunctions,
.(22) Process instrumentation, alarms, and control system failures AND (23) Passive malfunctions in systems, such as engineered safety features, emergency
-feed water systems.
2.0 AVAILABLE OPTIONS NONE 3.0 TESTED OPTIONS 3.1 MALFUNCTION NUMBER. :439 3.2 MALFUNCTION SYMBOL. .:ME3053F 3.3 HALFUNCTION MENU. :ES
)
- 4.0 INITIAL CONDITIONS 4.1 The Simulator is operating at 100% power with HPCI System in a standby lineup. For test purposes a HPCI line break in the HPCI Room (MALF
- 138) will be l initiated at 100% severity to cause an automatic I isolation signal to be generated with malfunction #439 active.
4.2 A recording device is setup to record the following i test parameters simultaneously versus time with a resolution of 0.5 seconds or less: l 4.2.1 HPCI Room Temperature (TE-N030A)..:HVT4030A 4.2.2 HPCI Room Temperature (TE-NO30B). :HVT4030B 4.2.3 E41-F002 Valve Position... . . :VTMS402 4.2.4 E41-F003 Valve Position.. .
.:VMMS403 1
l SSP PTAMA439 REV 0 I
5.0 TEST DURATION 5.1 The recording device will be stopped after the affects of the malfunction have been verified.
6.0 BASE LINE DATA 6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power Plant Training Simulator, latest Revision.
7.0 DATE PERFORMED: 9-10-97 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES.
NONE 9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION.
NONE SSP PTAMA439 REV 0
PERFORMANCE TEST ABSTRACT PTA-MA-440 1.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE 1.1 STP-MA-440 E41-F003 FAILURE TO AUTO CLOSE 1.2 ANSI /ANS 3.5 1985, Section 3.1.2 Plant Malfunctions.
(22) Process instrumentation, alarms, and control system failures AND (23) Passive malfunctions in systems, such as engineered safety features, emergency feed water systems.
2.0 AVAILABLE OPTIONS NONE 3.0 TESTED OPTIONS 3.1 MALFUNCTION NUMBER...:440 3.2 MALFUNCTION SYMBOL. .:MES054F 3.3 MAL' FUNCTION MENU. :ES 4.0 INITIAL CONDITIONS 4.1 The Simulator is operating at 100% power with HPCI System in a standby lineup. For test purposes a HPCI line break in the HPCI Room (MALF #138) will be initiated at 100% severity to cause an automatic isolation signal to be generated with malfunction #440 active.
4.2 A recording device is setup to record the following test parameters simultaneously versus time with a resolution of 0.5 seconds or less:
4.2.1 HPCI Room Temperature (TE-N030A) :HVT4030A 4 2.2 HPCI Room Temperature (TE-N030B) :HVT4030B 4.2.2 E41-F002 Valve Position. .:VTMS402 4.2.3 E41-F003 Valve Position... . :VTMS403 SSP PTAMA440 REV 0
l 5.0 TEST DURATION 5.1 The recording device will be stopped after the affects of the malfunction have been verified.
6.0 BASE LINE DATA 6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power Plant Training Simulator, latest Revision.
7,0 DATE PERFORMED: 9-10-97 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES.
NONE 9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION.
NONE SSP PTAMA440 REV 0 j 1
f I
PERFORMANCE TEST ABSTRACT PTA-MA-441 1.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE 1.1 STP-MA-441, E51-F007 FAILURE TO AUTO CLOSE 1.2 ANSI /ANS 3.5 1985, Section 3.1.2 Plant ' Malfunctions, (22) Process instrumentation, alarms, and control system failures AND (23) ~ Passive malfunctions in l systems, such as engineered safety features, emergency feed water systems.
2.0 AVAILABLE OPTIONS NONE 3.0 TESTED OPTIONS 3.1 MALFUNCTION NUMBER.. :441 3.2 MALFUNCTION SYMBOL. :MES055F ,
3.3 MALFUNCTION MENU. :ES l 4.0 INITIAL CONDITIONS 4.1 The Simulator is operating at 100% power with RCIC System in a standby lineup. For test purposes a RCIC line break in' the SRHR Room (MALF #274) will be initiated at 100% severity to cause an automatic isolation signal to be generated with malfunction #441 4 active. !
I 4.2 A recording device is setup to record the following test parameters simultaneously versus time with a resolution of 0.5 seconds or less:
4.2.1 RCIC Steam Line Flow. . .. :MSW4E40 4.2.2 E51-F007 Valve Position. ... :VTMS507 4.2.3 E51-F008 Valve Position... :VMMS508 f SSP
{ PTAMA441 REV 0
5.0 TEST DURATION 5,1 The recording device wilt be stopped after the affects of rne r.ulfunction have been verified.
6.0 BASE LINE DATA 6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power Plant Training Simulator, latest Revision.
7.0 DATE PERFORMED: 9-10-97 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES.
NONE 9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION.
NONE SSP PTAMA441 REV 0
h PERFORMANCE-TEST ABSTRACT PTA-MA-442 1.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE 1.1 STP-MA-442, E51-F008 FAILURE TO AUTO CLOSE l 1.2 ANSI /ANS 3.5 1985, Section 3.1.2 Plant Malfunctions, l (22) Process instrumentation, alarms, and control system failures AND (23) Passive malfunctions in systems, such as engineered safety features, emergency feed water systems.
2.0 AVAILABLE OPTIONS NONE 3,0 TESTED OPTIONS 3.1 MALFUNCTION NUMBER. .:442 3.2 MALFUNCTION SYMBOL.. :MES056F 3.3 MALFUNCTION MENU. :ES 4.0 INITIAL CONDITIONS 4.1 The Simulator is operating at 100% power with RCIC System in a standby lineup. For test purposes a RCIC line break in the SRHR Room (MALF #274) will be initiated at 100% severity to cause an automatic isolation signal to be generated with malfunction #442 active.
4.2 A recording device is setup to record the following test parameters simultaneously versus time with a resolution of 0.5 seconds or less:
4.2.1 RCIC Steam Line Flow. .. . .. . :MSW4E40 4.2.2 E51-F007 Valve Position. . . :VTMS507 4.2.3 E51-F008 Valve Position. ... :VMMS508 l-SSP l PTAMA442 REV 0
5.0 TEST DURATION 5.1 The recording device will be stopped after the affects of the malfunction have been' verified.
6.0 BASE LINE DATA 6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power Plant Training Simulator, latest Revision.
7.0 DATE PERFORMED: 9-10-97 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES.
NONE 9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION.
NONE SSP PTAMA442 REV 0
f!
l PERFORMANCE TEST ABSTRACT i
i PTA-MA-443 1.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE 1.1 STP-MA-443 LASALLE TRANSIENT.THI 1.2 ANSI /ANS 3.5 1985, Section 3.1.2 Plant Malfunctions, (A) Licensee Event Reports (e) NRC bulletins and circulars.
2.0 AVAILABLE OPTIONS NONE l
l l
3.0 TESTED OPTIONS 3.1 MALFUNCTION NUMBER...:443 l 3.2 MALFUNCTION SYMBOL.. :MNB016F 3.3 MALFUNCTION MENU. .. :NB 4.0 INITIAL CONDITIONS
( 4.1 The Simulator is operating at 100% power when a duai recirc pump trip is experienced.
i 4.2 A recording device is setup to record the following test parameters simultaneously versus time with a resolution of 0.5 seconds or less:
4.2.1 Total Core Flow... ... .
- NBWFLOW(7) 4.2.2 Reactor Power.... .
- RXQCOREl 5.0 TEST DURATION 5.1 The recording device will be stopped when the reactor scrams on neutron flux.
6.0 BASE LINE DATA 6.1 Malfunction Cause and Effect for Branswick Unit 2 Power Plant Training Simulator, latest Revision.
7.0 I DATE PERFORMED: 9-10-97 SSP PTAMA443 REV 0
F-8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES.
NONE i
9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION.
NONE l
l l
SSP PTAMA443 REV 0
r
)
)
PERFORMANCE TEST ABSTRACT PTA-MA-444 l
1.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE 1.1 'STP-MA-444, UNIT 1 LOCA 1.2 ANSI /ANS 3.5 1985, Section 3.1.2 Non-Specific.
Plant Malfunctions.
1 2.0 AVAILABLE OPTIONS NONE l
3.0 TESTED OPTIONS 1
3.1- MALFUNCTION NUMBER.:444 1 3.2 MALFUNCTION SYMBOL.:MNB017F 3.3 MALFUNCTION MENU. :NB
\
4.0 INITIAL CONDITIONS 4.1 The simulator is operating at approximately 100% steady state power.
5.0 TEST DURATION l
5.1 The simulator will be placed in the FREEZE mode after j unit conditions have stabilized. l 6.0 BASE LINE DATA 5.1 Malfunction Cause and Effect for Brunswick Unit 2 Power l Plant Training Simulator, latest Revision.
l 7.0 DATE PERFORMED: 9-10-97 I
l SSP PTAMA444 1 REV 0 1.
8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES.
NONE 9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION.
NONE SSP PTAMA444 2 REV 0
f:
1 i
l PERFORMANCE TEST ABSTRACT PTA-MA-445 1.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE 1.1 STP-MA-445 RECIRC PUMP LIMITER 2 FAILURE.
1.2 ANSI /ANS 3.5 1985, Section 3.1.2 Plant Malfunctions,
-(17) Failure in Automatic Control Sys. that affect reactivity and Core heat removal.
2.0 AVAILABLE OPTIONS i NONE 3.0 TESTED OPTIONS l
3.1 MALFUNCTION NUMBER.. :445 i 3.2 MALFUNCTION SYMBOL. :MRC030F 3.3 MALFUNCTION MENU.. :RC 4.0 INITIAL CONDITIONS l l
4.1 The simulator is operating at 100% power when one reactor feed water pump is tripped.
4.2 A recording device is setup to record the following test parameters simultaneously versus time with a resolution of 0.5 seconds or less:
4.2.1 Reactor Water Level. :IARXLVL 4.2.2 A RFP Suction Flow. ... ... .:CFWlRFP(1) 4.2.3 B RFP Suction Flow... .
- CFWlRFP(2) 4.2.4 A Recirc Pump Flow. . .
- NBWFLOW(10) 4.2.5 B Recirc Pump Flow. ,.
- NBWFLOW(11) 5.0 TEST DURATION 5.1 The recording device will be stopped when the reactor scrams on neutron flux.
SSP PTAMA445 REV 0
3 6.0 BASE LINE DATA 6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power Plant Training Simulator, latest Revision.
I 7.0 DATE PERFORMED: 9-10-97 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES.
NONE 9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION.
NONE
(
l l
/
i I
SSP PTAMA445 REV 0
PERFORMANCE TEST ABSTRACT PTA-MA-445 l
1.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE 1.1 STP-MA-446 APRM FCTR CARD INOP.
l 1.2 ANSI /ANS 3.5 1985. Section 3.1.2 Plant Malfunctions.
l (21) Nuclear Instrumentation Failure (s) & (22) Process Instrumentation, Alarms, And Control System Failures.
2.0 AVAILABLE OPTIONS 2.1 This Malfunction causes the selected APRM FCTR card self test program to detect a bad EPROM checksum resulting in an APRM FCTR Card Inop signal.
2.2 This Malfunction allows selection of either A, B, C. D.
E, or F APRM 3.0 TESTED OPTIONS 3.1 MALFUNCTION NUMBER. :446 3.2 MALFUNCTION SYMBOL. :MNIO66F 3.3 MALFUNCTION MENU. . :NI 3.4 TESTED APRM(S) A, B, C, D. E. AND F ,
l 1
i 4.0 INITIAL CONDITIONS 4.1 The Simulator is operating at 100% power.
I 5.0 TEST DURATION l
i 5.1 The simulator will be placed in freeze after the cause I
& Effect has been verified.
6.0 BASE LINE DATA I 61 Malfunction Cause and Effect for Brunswick Unit 2 Power Plant Training Simulator, latest Revision.
i SSP l PTAMA446 REV 0 l
a 1
7.0 DATE' PERFORMED: 11-23-98 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES.
NONE 4
9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION.
NONE j
I i
I i
l l
SSP PTAMA446 REV 0
rv PERFORMANCE TEST ABSTRACT PTA-MA-447 1.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE 1.1 'STP-MA-447 RBM POWER SUPPLY FAILURE.
l.2 ANSI /ANS, 3.5 1985, Section 3.1.2 Plant Malfunctions, '
'(21) Nuclear Instrumentation Failure (s) & (22) Process Instrumentation, Alarms, And Control System' Failures.
2,0 AVAILABLE OPTIONS 211 This Malfunction causes the selected RBM 5 volt power supply to fail'due to fuse F29 blows when a control rod is selected. This results-in the LPRM selections to that RBM being frozen'and potentially allows the reactor operator ta) withdraw a control rod further than permit.ted by the design analysis.
2.2 I
' This Malfunction allows selection of either A or B RBM (
POWER SUPPLY FAILURE.
.3.0 TESTED OPTIONS 3.1 MALFUNCTION' NUMBER. ... . . ... :447 3.2 MALFUNCTION SYMBOL., . ..... . ....:MNIO72F 3.3 MALFUNCTION MENU.. .. ........... :NI 3.4 TESTED RBM POWER SUPPLY FAILURE.. A B
-4'0 INITIAL CONDITIONS 4.1 The Simulator is operating at 60% power with no rod selected.
4.2 A. recording device is setup to record the following i test parameters simultaneously versus time with a resolution of 0.5 seconds or less: ,
4.2.1 Upper Left LPRM Detector Meter A.... G2Cl2GlB ;
4 . 2 .' 2 . Upper Left LPRM Detector Meter B...- G2CllG1B l 4.2.3 Upper ~Left LPRM Detector Meter C... G2C10GlB 4.2.4 Upper Left LPRM Detector Meter D...: G2C09G1B 4.2.5 Lower Left LPRM Detector Meter A... G2C16G1B 4.2.6 Lower Left LPRM Detector Meter B.. : G2C15GlB 4.2.7 Lower Left LPRM Detector Meter C. .: G2C14GlB SSP PTAMA447 REV 0
l 4.2.8 Lower Left LPRM Detector Meter D. G2C13C1B 4.2.9 Upper Right LPRM Detector Meter A. G2C25G1B 4.2.10 Upper Right LPRM Detector Meter B. -
G2C24GlB 4.2.11 Upper Right LPRM Detector Meter C. G2C23GlB 4.2.12 Upper Right LPRM Detector Meter D. G2C22GlB 4.2.13 Lower Right LPRM Detector Meter A. -
G2C29GlB 4.2.14 Lower Right LPRM Detector Meter B. G2C28GlB 4.2.15 Lower Right LPRM Detector Meter C. G2C27GlB 4.2.16 Lower Right LPRM Detector Meter D. G2026G1B 4.2.17 RBM A Recorder Reading. .. . . . . G2928GlC 4.2.18 RBM B Recorder Reading. .. . . .. G2E0lGlD 5.0 TEST DURATION 5.1 The simulator will be placed in freeze after the Cause
& Effect has been verified.
6.0 BASE LINE DATA 6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power Plant Training Simulator, latest Revision.
7.0 DATE PERFORMED: 11-23-98 3.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES.
NONE 9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION.
NONE SSP PTAMA447 REV 0
PERFORMANCE TEST ABSTRACT PTA-MV-752 l _ l.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE 1.1 STP-MV- 752 .
Secondary Containment Integrity i
l l '. 2 PT- 15.4 1.3 ANSI /ANS 3.5 1985, Section 3.1.1 Normal Plant Evolutions, (10) Operator conducted surveillance testing on safety {'
related equipment or systems.
2.0 AVAILABLE OPTIONS 2.1 none 3.0 TESTED OPTIONS 3.1 none 4.0 INITIAL CONDITIONS l l
4.1 cold shutdown 5.0 TEST DURATION 5.1 2.5 hours 6.0 BASE LINE DATA I
6.1 PT 15.4 770 DATE PERFORMED: 9-8-95 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES.
NONE l 9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION.
NONE SSP PTAMV700. REV 6
PERFORMANCE TEST ABSTRACT PTA-MV-753 i
1.0 PROCEDURE TITLE / ANSI'3.5 REFERENCE l 1.1 STP-MV- 753 ,
Post Accident Sampling Valve Operability l
1.2 PT- 15.8 l 1.3 ANSI /ANS 3.5 1985, Section 3.1.1 Normal Plant Evolutions, I
(10) Operator conducted surveillance testing on safety related equipment or systems.
2.0 AVAILABLE OPTIONS I
2.1 none 3.0 TESTED OPTIONS 3.1 none 4.0 INITIAL CONDITIONS 4.1 cold shutdown 5.0 TEST DURATION i 5.1 2.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> 6.0 BASE LINE DATA !
6.1 PT 15.8 $
l 7.0 DATE PERFORMED: 9-B-95
. 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES.
NONE l
l 9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION SSP PTAMV700 REV 6 I i L j
F PERFORMANCE TEST ABSTRACT PTA-MV-754 1.0 PROCEDURE TITLE / ANSI, 3.5 REFERENCE 1.1 STP-MV- 754 Service Water Valve Operability Test 1.2 PT- 24.4 1.3 ANSI /ANS 3.5 1985, Section 3.1.1 Normal Plant Evolutions, l (10) Operator conducted surveillance testing on safety l related equipment or systems.
2.0 AVAILABLE OPTIONS 2.1 none 1
3.0 TESTED OPTIONS 3.1 none 4.0 INITIAL CONDITIONS 4.1 100% power 5.0 TEST DURATION ~
I 5.1 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 6.0 BASE LINE DATA 6.1 PT 15.8 j
7.0 DATE PERFORMED: 7-25-96 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES.
NONE 9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION.
NONE 1
I I l SSP PTAMV700 REV 6 1 i