ML20245A531
| ML20245A531 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 09/13/1988 |
| From: | Cartwright W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML20245A509 | List: |
| References | |
| NUDOCS 8906220052 | |
| Download: ML20245A531 (290) | |
Text
{{#Wiki_filter:__ NRCPOnuosa no ass U.S. NUCLE AR REQULATORY svoweCO.heMaassON ar.".m"'" APPr ' } SIMULATION FACILITY CERTIFICATION l%'b
- RUCTIONS. Th form is to be f ated for mitias certification, racertification of reovireal, and for any change to a semulation facehty performance testmg pian t..co af tet mittal submittal of tuch a plan. Provios the followmg information and check the 3DDroDriate boM to encicate reason for submittal.
F ACILIT y [OOCKE T NUMBER NORTH ANNA POWER STATION LICENSE E
' so 338 IDATE VIRGINIA ELECTRIC AND POWER COMPANY l 08/10/88 un ..ri e, , #n. - e s .-. _ .
e-
. ee e.= nc n Misen...te. - -
.e
... . e ..r e. .n.s.ua.us
.a .. a t.n.m..m _ _n..Oenem.--nae
- e. ,c . ._ .i.ie .no a. - .e .- nac - - -ia is cen ss mim. e = = saw NAME for orner.u.;cer,o,,p ANO LOCATION OF SAMULATION F ACILITY NORTH ANNA UNIT 1 SIMULATOR, NORTH ANNA POWER STATION, MINERAL. VA AT THE END OF STATE ROUT T
, l $1MULAflON 7 ACILITY PE R70RMANCE TEST ABSTR ACTS ATTACHEO. Iror oerformsere tears canauereo m the osrod enomy . era ene aere et rius certistcorsons 700 DE SCRIPTION OF PE R FORMANCE TESTING COMPLETED (Atraca ocorrsonas, espess/ as nees w esso scontary the eram orncrrorson semy centsauces SEE ATTACHMENT 3 0F ENCLOSED DOCUMENT
$ l ftemmento*er work one care et enor terrrtoestnort IbiMUL A f lON & ACsLa T y PE R FC RMANCE T EST4NG SCHEDULE A T T ACHEO. If or tne conauer of eco ossme DE$CRiPTION OF PERF0RMANCE TESTING TO 8E CONDUCTED IArreca nadirsonas paperst es necessery ano scenreer the trem osectrarson eerny continue #A SEE ATTACHMENT 4 0F ENCLOSED DOCUMENT O
PE R F0RU ANCE TESTING PL AN CH ANGE IFor one moorfwetoon to e certurmance testungnoen submarted sus e orewesa certofwetoont OESCR6PTlON OF PE R F 0RM ANCE TEST lNG PLAN CH ANGE LArseca ecoutsoner ongets) es necesaary, and ooent19y rhe otem anacrootron some continunot NOT APPLICABLE AT THIS TIME f A rraen ornrrow conroer es neernserv ent* rewornfer une ***m or.~rworme e emo rentmno.tr og H ECE H t sF scat son soescroce correcrnre actoorin recen arteen venurts or NOT APPLICABLE AT THIS TIME DT , ! v any s ne uaiemene or eruvie.on6n in.epocument mceuemq euecnments, may am suoiece to ci.e ano crimmai unct.ons a ceruev unaev ponerav oe pereurv met tne miermet.on en ansa neum.no ano estacnenpin as /,e an#irrece bNA 'A M R ESENTATIVE Dart lTsTLE W. R. CARTWRIGHT VICE-PRESIDENT-NUCLEAR 3 in accoraance min to C/'n t 55.D. Communications. inis form snait be suomittee to tne NHC as tonows-B Y Mall A00RESSED TO. Director. Office of Nuclear Reactor Requiation BY DELf vE R Y IN PE RSON U.S. Nuclear Regu6atory Comm.ssion TO 5 HE NRC OFFICE AT: Washmgton DC 20555 7920 Norfolk Avenue Bethasoa, MO
0 NORTH ANNA UNIT 1 SIMULATOR CERTIFICATION SUBMITTAL O Y O
North Anna Unit 1 Simulator Certification Submittal l This North Anna Simulator Certification Submittal consists of.the following sections:
. ANSI 3.5 -- 1985 Checklist and Exceptions (Attachment 1)
. Simulator Instructor Console Features and Overview (Attachment 2)
. Simulator Test Results (Attachment 3)
. Simulator Test Schedule (Attachment 4)
. Simulator Physical Fidelity Report (Attachment 5)
. Control Room / Simulator Panel.and Environment Comparison (Attachment 6)
. Simulator Upgrade Schedule (Attachment 7)
. Simulator Discrepancy Backlog and Resolution Schedule (Attachment 8) )
. Simulator Configuration Control Procedure (Attachment 9) ,
)
. The simulator instructor console features will be listed. Any exceptions will be noted.
]
Each test deemed to be a requirement of ANSI 3.5 - 1985 ; as modified by Reg Guide 1.149 in accordance with 10 CFR 55 issued March 1987 will be briefly reviewed. A synopsis of each test.and associated results will be pressnted. The simulator test schedule will be attached.- The' tests to be conducted are divided- in such a manner aus ' to ensure 25% of the tests required.are performed each yearL thereby ensuring all testing is completed within the four year time frame specified. , The simulator Physical Fidelity Report will be- a ;I listing of all current discrepancies and a scheduled date for resolution with priority indicated as appropriate.
l 2 The ANSI 3.5 -- 1985 checklist will address each item and it's status. The overrides features are not specifically tested by procedure, however credit is taken for day to day training activities which utilize these features constantly. If a problem arises, the particular point or component is immediately evaluated, and repaired as appropriate, utilizing instructor feedback and the discrepancy resolution system established. No exceptions have been identified and taken to ANS-3.5-1985 or its appendices. The simulator facility arrangement and reference plant control room arrangement will be presented. Virginia Power is currently conducting a systematic g review and upgrade of each plant system to ensure the system W is properly simulated on the simulator from a hardware and a software viewpoint. During the review, all current design change packages will be reviewed as well as physical fidelity comparison results, engineering work requests, the control room design review and resultant modifications to ensure the simulator properly replicates the reference plant control room to meet the required training objectives. The simulator discrepancy backlog and the simulator discrepancy resolution schedule vill be included as O currently envisioned for the next four years. The simulator discrepancy schedule is based upon the upgrade schedule currently in progress. The upgrade is based upon a systematic approach and is designed to 1) reduce the large backlog of discrepancies which has built up over the past few years and 2) to ensure all modifications are incorporated into the simulator which have not been thus far. Any system not appearing on the schedule has been reviewed and upgraded as appropriate, and is now being maintained by the normal maintenance scheduling. The Upgrade is scheduled to be completed by June 1989. As part ! of the annual report the schedule will be revised to reflect needed modifications due to plant changes or changing training requirements. The Virginia Power simulator configuration control procedure is included for your reference. O
~
1 l l i i 4 VIRGINIA POWER l' SIMULATOR SUPPORT GROUP i j l l 1 NORTH ANNA UNIT 1 SIMULATOR O ATTACHMENT 1 CERTIFICATION CHECKLIST I 1
'I i
- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ i
ATTACHMENT ' Page 1 ofL3-
) NORTH ANNA SIMULATOR CERTIFICATION CHECK LIST SIMULATOR CAPABILITIES Normal Plant Evolutions
~/fzZ4' Normal evolutions listed in ANSI /ANS-3.5-1995 section 3.1.1 and mentioned in Appendix A have been conducted on the simulator. The tests have been reviewed by the Simulator Support Group (SSG). . Problems identified have either been corrected or are identified (ni the attached SMR listing.
Plant Malfunctions
/2db'( All simulated malfunctions were' tested. Those malfunctions listed in ANSI /ANS-3.5-1985 section 3.1.2 were checked to ensure their inclusion among the tests. The tests have been reviewed by the SSG. Problems identified have either been corrected or are identified on the attached malfunction listing.
SIMULATOR ENVIRONMENT 274MP All simulated panel dimensions and arrangements have been reviewed'to ensure they do no detract from training. 474'/ f Obtained latest revision copy ~ North Anna control room floor plan. Floor plan is available.for inspection.
. t?46t' Compared differences between the North Anna control room floow plan and the North Anna simulator control room floor plan. A list-of differences is attached.
29'z2/'
~
Compared lighting in the plant and simulator control rocms. Differences are indicated on the-attached list. x2dc4' Communication systems available in the plant and simulator control rooms have been compared. Differences are indicated on the attached list. e7z2/r ' Furnishings in the plant and the simulator have L been reviewed. A list of differences is attached. 1 O
ATTACHMENT 1 Page 2 of 3-( A746V ' Pictures of the North Anna main control boards have been taken. They are available for inspection.
/94M' All the controls and indications on panels and consoles were reviewed'to ensure they duplicate
~
the reference plant. A Physical Fidelity Report identifies all differences and is attached. SIMULATOR TRAINING CAPABILITIES 226M/ The simulator possesses the capability for storage of 40 initialization conditions. A current listing is attached. 22#xV ' Random selecti'on testing has been conducted to validate the capability of interfacing with remote activities. Problems identified have either been corrected or are identified in the attached list. 222%/' ' Random selection testing has been-conducted to validate the operability of the Malfunction Processor and its capability of simulating simultaneous and/or sequential malfunctions. d26M Random selection testing has been conducted to O' ' validate the operability of the Plant Equipment Display System (PEDS). Problems identified have either been corrected or are identified on the j attached list. ) i dZdW' Special features available on the North Anna l simulator are indicEted on the-attached list. 1 PERFORMANCE CRITERIA e94&/( Simulator stability performance test have been conducted to validate simulator accuracies. Problems identified have either been corrected or are identified on the attached list. The tests are available for inspection. 69224' Transients listed in Appendix B of ANSI /ANS-3.5-1985 have been conducted on the simulator. The tests have been reviewed and problems identified have either been corrected or are identified on the attached list. The tests are available for inspection. ([]) i
ATTACHMENT 1 Page 3 of 3 X26M' ~ The simulator response time corresponds to real time during normal and transient operations. All performance tests were reviewed by the SST to verify response times. (Z#A/' A Simulator Limits Exceeded alarm has been incorporated to avoid negative training by progressing beyond plant design limits or model capabilities. d?49( Random selection testing has been conducted to validate the operability of the alarm Override Processor. Problems identified have either been corrected or are identified on the attached list. (286( Random selection testing has been conducted to validate the operability of the Lamp Override Processor. Problems identified have either been corrected or are identified on the attached list. 49'484' Random selection testing has been conducted to validate the operability of the Setpoint Override Processc*. Problems identified have either been corrected or are identified on the attached list. 49%%/( Random selection testing has been conducted to validate the operability of the Switch Override Processor. Problems identified have either been corrected or are identified on the attached list. t9%64I Random selection testing has been conducted to i validate the operability of the Meter Override Processor. Problems identified have either been l corrected or are identified on the attached list. I O
.j I
O i;
.l 1
)'
VIRGINIA POWER SIMULATOR SUPPORT GROUP ! l 1 l l
.)
i NORTH ANNA UNIT 1 SIMULATOR ATTACHMENT 2 INSTRUCTOR CONSOLE FEATURES AND OVERVIEW 1 O
ATTACHMENT 2 Page 1 of 51 O INSTRUCTOR CONSOLE DESCRIPTION i The instructor console is depicted in Figure 1. It I consists of five components, as follows from left to right.
- a. INSTRUCTOR / DIAGNOSTIC TERMINAL
- b. CONSOLE TERMINAL
- c. MALFUNCTION / OVERRIDE TERMINAL
- d. TOUCH SCREEN
- e. CONSOLE PANEL A. INSTRUCTOR /DIANOSTIC TERMINAL:
This terminal is used by the instructor for ( monitoring simulation variables or simulator equipment diagnostics. B. CONSOLE TERMINAL This terminal is used to display menus and instructions for various functions. : C. MALFUNCTION / OVERRIDE TERMINAL i This terminal is used to display the status of l malfunctions and overrides entered by the l instructor. l l D. TOUCH SCREEN 1 This terminal is used to display system drawings and to provide the instructor control of plant equipment via the TOUCH SCREEN. E. CONSOLE PANEL: This p _.1 receives instructor command inputs via pushbuttons, and computer acknowledgement of these commands via lamp indicators, with information displayed on the CONSOLE TERMINAL. O
- FIGURE 1 o \
touch ] SCR650 O
/// ,
i w " w 1Ii ii O g3-
l i ATTACHMENT 2 Page 3 of 51 DETAILED INSTRUCTOR PROCEDURES j
- 1. GENERAL REMARKS:
- a. This manual contains detailed instructions for each of the Instructor Console functions. The pushbutton numbers shown in-Figure 2 correspond to the page numbers which describe the Instructor Console functions.
- b. Each function has a specifte menu displayed on the CONSOLE TERMINAL and provides instructions to follow.
- c. In general, the status of an Instructor Console function is indicated by the lighting of the lamp indicator for that function. Some lights will flash while a function is in progress.
- d. After completion, information related to the last performed function remains on the CONSOLE TERMINAL l until a new function is activated.
- e. Interlocks are provided which prevent any adverse impact on simulator training due to in& # vertent
- misoperation of the Instructor Console.
- f. A color code has been assigned for differentiation of the status of malfunctions / overrides displayed.
on the MALFUNCTION / OVERRIDE' TERMINAL: (1) Malfunctions / Overrides awaiting a set of l conditions for initiation are displayed in green. (2) Malfunctions / Overrides timing down to initiation are displayed in yellow. (3) Malfunctions / Overrides initiated and ramping in degradation are displayed in blue. (4) Malfunctions / Overrides which are fully implemented are displayed in red.
- g. All Malfunctions / Overrides relating toLprocess instrumentation (i.e., instrumentation malfunctions, controller setpoint potentiometer overrides and meter. overrides are implemented-with the same philosophy. (i.e., no Malfunction /
Override is implemented when "50" is entered,
ATTACHMENT'2 Page-4 of.51 O full downscale when~"0" is entered, of full upscale when "100" is entered. Values entered other than "50", "0" or "100" will yield a response indicative of instrument'" drift".)
- h. The' overridden value-for.the equipment is shown on the screen.
- 1. In the event of CONSOLE PANEL failure, a message vill be displayed on the CONSOLE TERMINAL'and all' control will be transferred'to the INSTRUCTOR / DIAGNOSTIC TERMINAL. In case of a suspected console panel failure, the Instructor Console can be operated from a terminal.
(Appendix 1)
- j. If it is desired to terminate-a mode of operation,.
prior to its completion, push the respective function pushbutton. Note: Care must be used when this is done while I performing " core aging" as response of simulator may be unstable when early exiting is performed.
- k. Times entered for all malfunctions / overrides are in SECONDS.
- 1. Degradation for all malfunctions / overrides are in.
percent. These can be in decimal form if. desired (i.e., 84.6% would be entered as 84.6).
- m. It is possible for more information to be displayed on the Console Terminal and-Malfunction / Override Terminal than a single screen can accomodate. When this occurs, the DISPLAY .
l INDEX, PAGE FORWARD or PAGE.BACK pushbutton li. hts N up to. indicate which direction can be followed on menu.
- n. At Surry and North Anna, SPDS system is simulated using a line between the Gould computer and 3 modcomp computer. When the link between these two i computers' fails ~ an indication (LEOF DATA LINK FAILURE) lights.up on the instructor console to .
inform the instructor of the SPDS simulation l failure. To restart the simulation, reboot of the i modcomp is required. .) l
ATTACHMENT 2' Page 5 of.51 O o. At Surry'and North' Anna, an indication (SIMULATION LIMIT EXCEEDED) is provided to satisfy the'ANS 3.5 requirements. This modification. lights up when one or more of the critical parameters exceed their. boundary.
- 2. Use of ENTER-Pushbutton:
The ENTER pushbutton is-used for transmitting any alphanumeric character (s) required by a.specif1c j function. a
- 3. Use of.the. BACKSPACE Pushbutton:
This pushbutton is used to-correct mistyped character (s).
- 4. Use of SPACE Pushbutton:
This pushbutton is used to enter a SPACE between characters. i
)
l 1 l
.i
- )
i d l
ATTACHMENT 2 Page 6 of 51 l0 INDEX Page Procedure No. Shutdown 8 Startup 9 Single Save 10 Single Restore 11 Core Aging (N/A FUS) 12 Trainee Performance Monitor 14 Computer Aided Exercise 17 Computer Hold /GO 17 Log Hold /GO 17 IC Store 19 IC Transfer 20 Plant Variable 21 SIMLOCH 22 IC Recall 24 Back Track Recall 25 Replay 26 Fast Time Setup (N/A FUS) 27 Run 28 Malf Timer Run (N/A FUS) 29 Malf Timer Stop (N/A FUS) 29 Remote On O Remote Off Fast Time (N/A FUS) 30 30 3.1 Freeze 32 Normal Time (N/A FUS) 33 Alarm Acknowledge 34 l Rod Step Counter Enable (N/A FUS) 35 ! Trip Review Disable 36 Disable Horn 37 Print Screen 38 IC Check 39 Recover Comm Network 40 Diagnose and Recover (N/A SPS) 41 Development Mode 42 Control Room Diag 43 Instructor Console Diag 44 Malfunction Processor 45 Alarm Override Processor 46 Lamp Override Processor 47 Switch Override Processor 48 Meter Override Processor 49 Setpoint Override Processor 50 Console Panel Failure Appendix 1 Training Performance Review Appendix 2 O
i ATTACHMENT 2-Page 7 of 51 Shutdown Startup Single Single Core Trainee Computer Control Save Restore Aging Perform- Aided Display mance Exercise Index (N/A FUS) Monitor IC IC plant Simloch Computer page Store . Transfer Variable Hold /GO Back IC Back Replay Fast Time Log page Recall Track Set Up Hold /Go Forward Recall (N/A FUS) 16' 17 18 19 Run Malf Remote Fast Timer On Time Run (N/A FUS) Freeze Mn1f Remote Normal Timer Off Time , Stop (N/A FUS) . 22 23 24 25 26 27' Alarm Add Step Trip Disable Print IC ACK Counter Review Horn Screen. Check Enable Disable
---_-----.. 1NLB EWEL ----_- -_--_---- --------_ ------_-_
a
- s ( ) --
O A B C D E F
--------- a ------ --------- --------- ---------
I J K L M N Q R S T U V Y Z
-~_ __
ATTACHMENT 2 Page 8 of 51 EOF Samulation' Data Link Limtt ( Failure Exceeded
. .1N49_EWEL.1N10.EW31.
as as Overide Recover Diagnose Malf Display Display Come and I Index Index Network Recover _______30 Malf Override TPM Develop-Page page Back Active ment Back _________1..5ede 3 32 Malf Override page Page Control Instructor Forward Room Consolo Forward Diagnos- Diagram ties 34 35 36 37 34 33 Lamp Switch Meter Setpoint Malf Alarm Proc Override Override Override Override Override On Proc On Proc On proc On Proc On Proc On 37 _______38 33 34 ________35 36 . Lamp Switch Meter Set point Malf Alarm , 1 Proc Override Override Override Override Override 1 Off Proc Off Proc Off Proc Off Proc Off Proc Off _______g._______g_________4__________g _-_y________ g_ Alarm Lamp Switch Meter Setpoint Malf Active Override Override Override Override Override Active Active Active Active Active 1 l _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ j l H 1 2 3 Backspace G P 4 5 6 Space O ________ _ _ _ _ _ - ________. j I 8 9 Enter C W X 7 ( _________ _________ _________ __________ . . _ _ _ _ _ _ _ _ _ _ _ - - O
. I
ATTACHMENT 2 Page 9 of 51 O SHUTDOWN
Description:
The Shutdown function permits the Instructor to shutdown the simulator. The Shutdown function cannot be activated unless the simulator is in freeze and all other functions are off. After the Shutdown function is complete, a confirming message appears on the MALFUNCTION / OVERRIDE TERMINAL and TOUCH SCREEN. All indicators on the CONSOLE PANEL and the Control Room Panels are deactivated. Procedure:
- 1. Push SHUTDOWN.
O l l O
i
'l ATTACHMENT 2~
Page'10 of 51 O START UP j
Description:
l The Startup' function permits the Instructor to'startup the simulator. After the startup function pushbutton has been depressed, '! Simulator startup in progress message will appear on the j CONSOLE TERMINAL. When the startup function is complete, a l confirming message is displayed on the CONSOLE TERMINAL and l FREEZE, MALF TIMER STOP, REMOTE OFF, NORMAL TIME, MALF PROC 1 OFF, ALARM OVERRIDE PROC'OFF, LAMP OVERRIDE PROC OFF, SWITCH j OVERRIDE PROC OFF, METER OVERRIDE PROC OFF and SETPOINT OVERRIDE PROC OFF function lights light up. Procedure: i
- 1. Push STARTUP.
2.- Perform IC RECALL procedure. (::) l i i i l I l i i k O s
ATTACHMENT 2 Page 11 of 51 O SINGLE SAVE
Description:
The Single Save function permits the Instructor to store the current simulator condition temporarily. When this function is activated, any previously stored Single Save is deleted. Procedure:
- 1. Push FREEZE.
l l 2. Push SINGLE SAVE. 1 O O
ATTACHMENT 2 Page 12 of 51 O SINGLE RESTORE
Description:
The Single Restore function permits the instructor to restore the last Single Save stored by the Single Save function. As soon as the function is completed, the status of the out of position ANALOG and DIGITAL signals is displayed on the CONSOLE TERMINAL, and the PRODAC CRT. l Procedure: l l 1. Push FREEZE l
- 2. Push SINGLE RESTORE.
- 3. Follow procedure for IC CHECK.
l O
.. i ATTACHMENT 2 Page 13 of 51 CORE AGING (NAPS & SPS ONLY)
Description:
The Core Aging function permits the instructor to modify any IC (1 thru 40) to:
- 1. Any time in core life
- 2. Any power history
- 3. Any axial xenon distribution Fuel, Xenon and boron concentrations are automatically adjusted, as necessary, to achieve the new conditions specified by the instructor. Other parameters, such as the delayed neutron fraction, rod worth and power defect are also adjusted.
Core Aging, in cases where extreme changes in parameters are specified by the instructor, can take approximately five (5) minutes to complete. Also, for these extreme cases, the odds for successful completion are approximately 90%. Therefore, it is recommended that Core Aging be performed prior to its need for a training session and then stored using the IC Store procedure. The Core Aging Frocessor will automatically deactivate when it has either:
- 1. Successfully completed Core Aging QR
- 2. Detected an unsuccessful attempt at Core Aging Procedure:
- 1. Select the desired IC to be aged using the IC Recall procedure.
- 2. Push CORE AGING.
- 3. Follow instructions on the CONSOLE TERMINAL.
- 4. Adjust FC-113 (boric acid flow controller) l setpoint potentiometer to value specified on the CONSOLE TERMINAL.
ATTACHMENT 2 Page 14 of 51 r ( ) Note: The instructor should expect a change in power range delta flux indication for:
- 1. Fuel distribution change with core life.
- 2. Xenon distribution change depending on specified power history and delta flux.
l l 1 O l l 1 i l i l 0 I
ATTACHMENT 2 Page 15:of 51 TRAINEE PERFORMANCE MONITOR
Description:
The Training Performance Monitor (TPM) function provides a capability to monitor.the performance of trainees during.a training session. The TPM monitors the following:
- 1. Parameters-(up to 40)Jidentified by the
-Instructor s
- 2. Malfunctions active.during the session.
- 3. Overrides active during the session.
- 4. Switch or setpoint manipulation by trainees.
To use the'TPM, Instructor has-to setup a monitor file that containes the following information:
- 1. Name of the: file (up to 16Echaracters long).
- 2. Description of scenerlo.
- 3. Name of students (up to 6)
- 4. Name of Instructor.
- 5. Name of monitored variables (parameters) (up to 40).
Once this file is setup, it can be used again and again but if reused, it writes over the old data. A TPM~ file log 5 containing name and description of all existing files is maintained in the Instructor booth. i 1 The TPM can be started and stopped anytime during the ! session. ! The data recorded by TPM can be reviewed using Training-Performance Review (Appendix 2). Procedure: ,
- 1. To start the monitor go to. step 2. To stop the' monitor l go to step 18. .'
- 2. Check da the TPM log book if a monitor file for the current session already exists.
- 3. If the monitor file already exists go to step 11.
- 4. Define the following to create a new file.
I
- a. Name of monitor file (up to 16' characters).
- b. Description of scenerio (up to 2 lines) (40 characters each).
ATTACHMENT 2 Page 16 of 51 O c. Name of Instructor.
- d. Name of students (up to 6).
- e. Name of monitored variables (up to 40 from database last).
- f. Scam rate for each variable (in seconds).
- 5. Push the Training Performance Monitor button.
NOTE: A list of possible commands and format of the monitor file will appear on the screen.
- 6. Type in 3 (corresponding to Modify Monitor setup) and push ENTER.
- 7. Type in number corresponding to the item to be entered and push ENTER.
NOTE: a. These items were defined in step 4.
- b. To go to a different item or command menu push ENTER.
- 8. Continue step 7 until all items are entered.
- 9. Type in 4 (corresponding to Save Monitor) and push ENTER.
- 10. Go to step 16 to run the monitor.
- 11. If no changes are required in the existing monitor file, go to step 16 to run the monitor.
- 12. Type in 5 (corresponding to Use Monitor) and push ENTER.
- 13. Type in the name of the monito file to be modified and push enter.
- 14. Type in number cor esponding to the item to be modified and push ENTER.
- 15. Type in 4 (corresponding to Save Monitor) and push i ENTER.
- 16. Type in 1 (corresponding to Start Monitor) and push ENTER.
- 17. Type Y in response to " Monitor File exists. Replace Y/N" a.I push ENTER.
NOTE: At this time the screen vill clear and TPM ACTIVE push button will light up. O
I ATTACHMENT 2 .l Page 17 of 51 ) i l O 18. To stop the monitor: lI
- a. Push TPM push button.
- b. Type in 2 (corresponding to Stop Monitor) and push l enter.
NOTE: The TPM ACTIVE light will go off. i I O i i I O 1 a - _ - - - - - _ _ _ - . _ _ _ _ . l
1 ATTACHMENT 2 - Page 18 of 51L 'l i COMPUTER AIDED EXERCISE (CAE)
Description:
4 The Computer Aided Exercise (CAE) function allows the use of a prebuilt exercise, or the building.of a new exercise. )1 Computer Aid Exercise is controlled by three (3) pushbuttons:
- 1. COMPUTER _ AIDED EXERCISE - used to activate /
deactivate the CAE function l 2. COMPUTLR HOLD /GO - used to stop and continue the progression of CAE ]
- 3. LOG HOLD /GO - used to'stop and continue recording of the data entered by the instructor on the CONSOLE PANEL )
Procedure: A. Using a prebuilt exercise guide: _.
- a. Push CAE.
- b. Type in 1 and push ENTER.
qq c. Type in the name of exercise guide to~be used and push ENTER.
- d. Push CAE.
- e. Push COMPUTER HOLD /GO to start the exerc'ise.
B. Building a new exercise guide:
- a. Push CAE.
- b. Type in 2 and push ENTER.
- c. Type in the name of exercise guide to be built and !
. push ENTER. j
- d. Push CAE.
- e. Push LOG ON/ HOLD.
- f. Proceed with the exercise.
-1 NOTE: All buttons, and the sequence in which they are pushed on the CONSOLE PANEL are recorded.
If an instructor CONSOLE PANEL function is l not desired to be recorded: l
- 1. Push LOG ON/ HOLD To recommence recording:
- 1. Push LOG ON/ HOLD-O
_ )
i ATTACHMENT 2 Page 19 of 51 ym
- g. At the end of exercise guide, push LOG ON/ HOLD
- h. Push CAE.
- 1. Type in 4 and push ENTER.
- j. Push CAE.
Note: 1. Exercise is now stored for future use per "A" above.
- 2. New exercise guide can also be built without using Simulator time.
(Check with Lead Instructor.) O l
\
ATTACHMENT 2 Page 20 of 51 O IC STORE
Description:
The IC Store function permits the Instructor to store the present simulator condition. There are 40 different IC's. 1 thru 15 are controlled by the simulator staff. 16 thru 40 are for Instructor use. After pushing the IC Store function button, a list of all IC's 16 thru 40 is displayed on the screen. Procedure:
- 1. PUSH FREEZE.
- 2. Push IC STORE.
- 3. Follow instructions displayed on the Console Terminal.
CAUTION: Insure that the IC number to be used for storing the IC is not needed by another instructor as it will be deleted and replaced () \,,/ by the new IC. To terminate the IC STORE function prior to completion:
- 1. Push IC STORE i
i l
ATTACHMENT 2 Page 21 of 51 IC TRANSFER
Description:
The IC Transfer function-is restricted to simulator staff use. 'It is used to transfer one of IC's 16 thru.40 to any IC 1 thru 15. This function is restricted and requires a password to complete. Procedure:
- 1. Push IC TRANSFER.
- 2. Follow instructions displayed on the CONSOLE TERMINAL.
m U O
ATTACHMENT 2 Page 22 of 51 l 1 Ch ^ PLANT VARIABLES
Description:
i The Plant Variable function permits the instructor to monitor blockr, of predefined simulator variables (up to 20 variables per block). To use this function the INSTRUCTOR / DIAGNOSTIC TERMINAL must not be in use. Procedure:
- 1. Push PLANT VARIABLE.
- 2. Follow instructions on the CONSOLE TERMINAL.
1 l l 1 ji
ATTACHMENT 2 Page 23 of 51-O SIMLOCH (INTENTED FOR SIMULATOR STAFF USE ONLY)
Description:
The SIMLOCH function activates the Simulation Look and Change program for monitoring / changing simulator variables. To use this function the Instructor / Diagnostic Terminal should either be in TSM wait state or not logged on by a user. When this function is activated, SIMLOCH light comes on. First, SIMLOCH is' displayed on the Instructor / Diagnostic Terminal, then " command >". CAUTION: Use only " Break" Key to obtain subsequent
" Command" modes.
Procedure:
- 1. Plug the portable keyboard, into the INSTRUCTOR /
DIAGNOSTIC TERMINAL.
- 2. Push SIMLOCH.
- 3. Type in desired data base variables.
- 4. Use the following commands as necessary:
- a. SF - Delete data base description of variables from display b.
$F10 - Display data-base description of variables.
- c. SF11 - Rearrange variables from column to row format.
. d. SX - Exchange left and.right sets of 20 variables for display
- e. -SR - Rearrange variables in alphabetical /
numerical order.
- f. SS - Save. variables displayed (give file name after SS).
g.- $I Clear screen of'all variables.
- h. $T.1 - Obtain maximum update rate of variables.- -
- i. SP - Store / print displayed variables at a certain interval.(give time in seconds after $P). To print the variables one time, use.SP without any time and then exit the SIMLOCH. The file will get printed on printer.
ATTACHMENT 2 Page 24 of 51 O j. SG - Display variables (give file name after SP).
- k. X - Exit SIMLOCH.
- 5. To terminate tha SIMLOCH function:
- a. Push SIMLOCH O
O
ATTACHMENT 2 Page 25 of 51 1 IC RECALL ; i
Description:
The IC Recall function permits the instructor to recall any of the 1 thru 40 presaved Initial Conditions. The Simulator must be in FREEZE mode to use this function. i Procedure: I I
- 1. Push FREEZE. l 1
- 2. Exit from all MALFUNCTION / OVERRIDE functions. i
- 3. Push IC RECALL.
- 4. Select desired IC and push ENTER.
- 5. Follow procedure for IC CHECK.
NOTE: IC number for current session is I I displayed on the top right corner of the CONSOLE TERMINAL. l l i I l O
. ATTACHMENT?2
'Page 26-of.'51 l
BACK TRACK RECALLi Descr'iption: '- The Back Track' Recall function recalls'the' simulator'to a previous condition in one minute increments, up to 60 minutes back.- While.the simulator.is in run,'the condition ofLthe simulator is stored every minute:up to 60 minutes. After 60 minutes, it deletes the oldest condition'and stores the-present. Procedure:
- 1. Push FREEZE.
- 2. Push BACK-TRACK RECALL.
- 3. Select desired back track'and push ENTER.
- 4. Follow procedure for IC CHECK.
l O l s
~
l i-H _ b
b l ATTACHMENT 2 Page 27 of 51 O REPLAY
Description:
l The Replay function is used to replay parameter and equipment status on Control Room instrumentation and lights. It operates similar to the replay of a video tape in that it displays previous conditions and neither operator nor instructor actions have an effect on simulation. Replay will'stop when it has completed the preselected time interval. Procedure:
- 1. Push FREEZE.
- 2. Push REPLAY.
- 3. Follow instruction on the CONSOLE TERMINAL.
l l 1 0
'l
-- j ATTACHMENT 2 1 Page 28 of.51 l p.
U FAST TIME SETUP (NAPS & SPS ONLY)
Description:
The Fast Time Setup function provides the capability to setup the.following operations to process at a rate of up.to 50 times faster than real time:
- a. Plant heatup.
- b. ~ XENON Transient - Implemented.in CORE AGING function.
- c. Core Aging Implemented in CORE AGING function.
- d. Turbine Rotor Heatup -Future.
- e. . Containment Vacuum - Future.
- f. Condenser Vacuum - Future. O
- g. Boron Mixing - Future. !
Once the FAST TIME MODE is setup, it can be started at.any .i time by pushing FAST TIME button. NORMAL TIME button can be used to go back to normal rate. Procedure:
- 1. Push FAST TIME SETUP button.
- 2. Type in operation number and push ENTER.
( 3. Type in the new rate and push ENTER.
- 4. Type in N and push ENTER.
o _ _ _ _ _ _ _ _ _ a
ATTACHMENT 2 Page 29 of 51 RUN
Description:
The RUN function permits the Instructor to take the simulator out of Freeze. Procedure:
- 1. Push RUN.
l NOTE: If there is a communication problem with I/O (COMERR=TRUE) then the simulator will not go to run. A message will be displayed.on the console terminal that the I/O is not functional. t i l 1 l l 1 i i a O ) 4 1 _____ - - - _ _ - _ _ . . _ l
I ATTACHMENT 2 l Page 30 of 51 l l (~h G MALF TIMER
Description:
The Malf Timer function permits the instructor to control j the timer for malfunction and override initiation. j The time displayed on the Malfunction / Override Terminal for instructor entered malfunctions and overrides are updated j continuously while the Malf Timer Run function is active. ; i Once a Malfunction / Override is active, the time displayed is I the total time elapsed since activation, and will continue to count irrespective of Malf Timer status. 1 i Procedure: , I
- 1. To start the malfunction timer:
- a. Push MALF TIMER RUN.
I
- 2. To stop the malfunction timer: '
l b. Push MALF TIMER STOP. 1 l 4 I I l 1 j () i
ATTACHMENT 2 Page 31 of 51 REMOTE
Description:
This function permits the instructor to activate / deactivate the Remote Console (hand held). While the Remote Console is activated, all functions of the Console Panel remain functional. Procedure: q
- 1. To activate the Remote Console:
- a. Push REMOTE ON. i 4
- 2. To deactivate the Remote Console:
- a. Push REMOTE'0FF.
i l l i I 1 l I l i 4
i ATTACHMENT 2 Page 32 of 51 (D U FAST TIME (N/A FUS)
Description:
This function in conjunction with_the FAST TIME SETUP function provides the capability to perform certain operations at a faster rate than normal. This function can be used at any time during the training session. Once the fast rate conditions have been setup, FAST TIME p*ushbutton can be used to start the fast rate operation. During fast rate operation the FAST TIME light comes on. I l Procedure: 1 '
- 1. Push FAST TIME push button.
l i l'J' s_ l l l l l O d
ATTACHMENT 2 Page 33 of 51 V FREEZE
Description:
The FREEZE function permits the Instructor to put the simulator in the FREEZE mode. All simulation is stopped while in the Freeze mode. Note: Any switch or controller potentiometer which is adjusted while in the Freeze mode will only become evident when the simulator is subsequently placed in Run mode. Therefore, changing the status of equipment while in Freeze should be avoided. Procedure:
- 1. Push FREEZE.
o V l
/
O 1
ATTACHMENT 2 Page 34 of 51 NORMAL TIME (N/A FUS)
Description:
This function provides the capability to switch back to normal rate from fast rate at anytime. When in normal rate mode, NORMAL TIME light in on. Procedure:
- 1. Push NORMAL TIME button.
I i i m I O
ATTACHMENT 2 Page 35 of 51 h ALARM ACK
Description:
The Alarm Ack function permits the Instructor to acknowledge all of the annunciators in the control room. This function also silences all audible alarms. Procedure:
- 1. Push ALARM ACK.
I 1 o . l l l l l 0 l l w_-_________-_
ATTACHMENT 2 Page 36 of 51 i
\/ ROD STEP COUNTER ENABLE (NAPS & SPS ONLY) l
(
Description:
.i The ROD STEP COUNTER ENABLE function permits the instructor- !
to calibrate the rod step counters to the value stored in ' the IC. - l This function must be initiated after performing an IC f Recall or Backtrack, but before completing an IC Check. i Until the rods have counted to the desired value, the simulator should not be put in Run. Procedure:
- 1. Push ROD STEP COUNTER ENABLE.
l
)
l 1 e 4 i U
ATTACHMENT 2 Page 37.of 51 1 0 TRIP REVIEW DISABLE '! i
Description:
(Future) Procedure: (Future) 1 l O :
)
l I l
l 1 ATTACHMENT 2 j Page 38 of 51 I f~ DISABLE HORN
Description:
The DISABLE HORN function permits the intructor to disable all audible alarms. When this function is active, the annunciator lights will operate normally, but the horn will not sound. Procedure:
- 1. To disable the audible alarm:
- a. Push DISABLE HORN.
- 2. To enable the audible alarm:
- a. Push DISABLE. HORN.
L I i
)
l l 1 1 J I l _ _ _ _ _ _ _ _ . _ _ _ _ _ __ a
1 , ATTACHMENT 2 L Page 39 of 51 1 PRINT SCREEN
Description:
The Print Screen function permits the instructor to print l the current information en the CONSOLE TERMINAL and i MALFUNCTION / OVERRIDE TERMINAL. This information is then retrieved from the line printer. Procedure:
- 1. Push PRINT SCREEN.
- 2. Proceed to line printer:
- a. Push OFF LINE.
- b. Push TOP OFF FORM three (3) times.
- c. Push OFF LINE (verify-green light on pushbutton lit).
- 3. Tear off printed data sheet.
/~ NOTE: To print PLANT PARAMETER or SIMLOCH information l on INSTRUCTOR / DIAGNOSTICS TERMINAL, use SP command of SIMLOCH function.
i l I 1 J _ - - - - u
ATTACHMENT 2 Page 40 of 51
~
IC CHECK
Description:
The IC CHECK function is used to indicate the proper setup of the control room panel switches and controller potentiometers. Out of position switches are indicated by a blinking light in the vicinity of the switch. Out of position potentiometers are indicated by a solid light in the vicinity of the potentiometer. After IC RECALL, BACKTRACK or SINGLE RESTORE functions are activated, the out of position Pots and Switches are f displayed on the CONSOLE TERMINAL and "Prodac CRT" (SPS & NAPS). Procedure: ,
- 1. Complete equipment setup.
- 2. Push IC CHECK.
a i I
.r k !
1
ATTACHMENT 2 Page 41 of 51 l3 s- RECOVER COMM NETWORK (NAPS & FUS ONLY)
Description:
The Recover Comm Network permits the instructor to manually recover from most card failures in the cages. If the instructor suspects that some switches, lights or meters are not responding in the control room, the instructor can try to solve the problem by activating this function. If this function does not correct the problem notify the simulator staff. Procedure:
- 1. Push FREEZE. ,
- 2. Push RECOVER COMM NETWORK.
- 3. Push RUN (if applicable).
t 4 l l i s_ i l
ATTACHMENT 2. Page 42 of 51 DIAGNOSE & RECOVER (FUS & NAPS ONLY)
Description:
The DIAGNOSE & RECOVER functicn serves to reinitialdze control room cage problems automatically. When this function is active, if any of the microprocessor cards in the cages misoperate:
- a. The function light starts flashing to inform the instructor that one of the cards did not respond
- b. The problem is automatically corrected NO7 5 This function becomes active (by default) when simulator is started up.
Procedure:
- 1. Push DIAGNOSE & RECOVER. l i
- 2. If the light is f.?: Shing:
- a. Push DIAGNOSE & RECOVER (light will go solid)
() b. Push DIAGNOSE & RECOVER again (light will go off)
- c. Push DIAGNOSE & RECOVER once more (light will ;
come on solid)
- 1. If the light does not go solid, but ,
flashes again, perform steps "a" and "b" l agair.
- 2. If light still will ,1ot go solid, but flashes, it indicates a failure which will require maintenance action. Inform the simulator staff as necessary.
l 4 ____-__--______._a
i ; 1 L ATTACHMENT 2 Page 43 of 51 I
)
(~h l (-,)- DEVELOPMENT MODE: (INTENDED FOR SIMULATOR STAFF USE ONLY) l
Description:
The Development Mode function activates developme..t simulation models during Simulator STARTUP. During this mode only the following tasks are different:
- a. Model Task
- b. Automatic State Parameter initialization program Procedure:
- 1. Push DEVELOPMENT MODE.
1
- 2. Push STARTUP.
[\-)~ k
. ATTACHMENT 2 ,
Page144:of 51
~ CONTROL ROOM DIAG: (INTENDED FOR-SIMULATOR STAFF USE ONLY-)'
Description-
~The Control Room Diag function is used-to check out the-control room hardware.
This function permits individual diagnostic checks on:
- 1. Lights (Digital outputs)-
- 2. Meters (Analog outputs) I
- 3. Setpoints (Analog' inputs)'
- 4. Switches (Digital inputs)
To use this function:
- a. Simulator must be in Freeze mode l
- b. INSTRUCTOR / DIAGNOSTIC TERMINAL should either befin -
Wait State or not logged on by a user I When this function is active, instructions are displayed on () the INSTRUCTOR / DIAGNOSTIC TERMINAL. Procedure: 4
- 1. Push FREEZE.
- 2. To activate Control' Room Diagnostic function: !
- a. Push CONTROL ROOM DIAG ,
- 3. Use INSTRUCTOR / DIAGNOSTIC TERMINAL keyboard to proceed with diagnostics.
- 4. To deactivate Control Room Diagnostic function:
- a. Push CONTROL ROOM DIAG or
'l
- b. Type X on the INSTRUCTOR / DIAGNOSTIC TERMINAL i keyboard.
l l () l u
I ATTACHMENT 2 l Page 45 of 51 l r'N l s INSTRUCTOR CONSOLE DIAG:
Description:
The Instructor Console Diag function permits the instructor ; to check the operability of the CONSOLE PANEL. I I When this function is activated:
- a. All lights,on the console light one by one Procedure:
- 1. To activate the Instructor Console Diagnostic: l I
a, Push INSTRUCTOR CONSOLE DIAG
- 2. To deactivate the Instructor' Console Diagnostic: !
- a. Push INSTRUCTOR CONSOLE DIAG NOTE: If the CONSOLE PANEL does not respond, inform a member of the Simulator Staff. l d
O ,
ATTACHMENT 2 Page 46'of 51
-< MALF PROC:
Description:
The Malfunction Processor function permits the instructor to-either set-up or delete malfunctions. Two types'of malfunctions are provided:
- 1. .Rampable (1'.e.,. leaks,-instrument failures, etc.l
- 2. Go/no go (i.e., breaker trips, large LOCAS, etc.)~ I
'All. malfunctions can be initiated after an instructor determined time delay (in seconds). This delay start is !
initiated by:
- 1. Going to RUN on the Malfunction Timer 2r
- 2. Satisfying the instructor specified " Trigger" and "1" above.
Note: " Triggers" are provided'by the simulator staff.
~
The status of all entered malfunctions is displayed on the MALFUNCTION / OVERRIDE TERMINAL as'follows:
- I
- 1. Green - malfunction awaiting a specified " Trigger" J for start of delay time ~
- 2. i*ellow - malfunction not initiated but in a time down sequence to initiation
- 3. Blue - malfunction is initiated but in a ramp status i l
- 4. Red - malfunction fully completed Procedure:
- 1. To activate the Malfunction Processor: ;
- a. Push MALF PROC ON.
- b. Follow instructions on the CONSOLE TERMINAL.
j
- 2. To deactivate the Malfunction Processor: 1
- a. Push MALF PROC OFF. i O ;
1 i
h ATTACHMENT 2 Page'47 of 51L O ALARM OVERRIDE PROCESSOR
Description:
The Alarm Override Processor function permits the. instructor to override any annunciator. L Annunciators may be overridden:
- 1. ON_- result:is essentially that which'would occur-i if.a bad annunciator-input existed'(i.e., the annunciator will light and~the audible alarm will sound).
- 2. - OFF - result is essentially that which would occur if the specific annunciator window light-bulbs were burned outT(1.e., the annunciator.
will not light but the audible' alarm will sound). All Alarm Overrides can be initiated.after.an' instructor determined time delay (in-seconds). -This delay start is initiated by:
- 1. Going to RUN on the Malfunction Timer O e
- 2. Satisfying the instructor specifiedL" Trigger" and "1" above.
Note: " Triggers" are provided by the simulator staff. Procedure:
- 1. To activate the Alarm Override Processor:
- a. Push ALARM OVERRIDE PROC ON.
- b. Follow instructions on the CONSOLE TERMINAL.
- 2. To deactivate the Alarm Override Processor:
- a. Push ALARM OVERRIDE PROC OFF.
_--_-_.-__.._______m.. - I .
2..
~
ATTACHMENT 2 Page 48-of 51: O LAMP OVERRIDE PROCESSOR
Description:
The Lamp Override Processor function permits the instructor-
'to override any lamp (excluding annunciators).
Lamps may be overridden:
- 1. On - result is essentially that which;would occur if an independent power supply were connected to the lamp. (i.e., the loss of normal-power to'the lamp will not turn if.off. Therefore,-
this override should be used with: caution).
- 2. Off - result is essentially that which would occur.
if the lamp socket were1 defective. All Lamp Overrides-can be initiated after an instructor determined time delay (in. seconds).- This delay start is-initiated by:
- 1. Going to RUN on the-Malfunction Timer j or
() 2. Satisfying the-instructor specified " Trigger" and "1" above.- Note: " Triggers" are provided by the simulator staff. Procedure:
- 1. To activate the Lamp OverridefProcessor:.
. a. Push LAMP OVERRIDE PROC ON.
b.- Follow instructions on the CONSOLE TERMINAL.
- 2. To deactivate the Lamp Override Processor:
- a. Push LAMP OVERRIDE PROC OFF.
l L I L O
ATTACHMENT 2 "
-Page 491of 51' LO SWITCH' OVERRIDE' PROC ON'
Description:
l The Switch Overr.ide Processor' function. permits _the i- instructor to override'any switch position, 1 Switches may be overridden: L
- 1. ON - result is essentially that which would occur if the switch contact were toistick on. A single override of a multi-position switch will not'effect the operation of-the remaining contacts.
- 2. OFF - result is essentially that which would occur if the wires to that specific switch contact were to break.
All Switch Overrides can be initiated ~after an instructor ! I determined time. delay (in seconds).. This' delay start is l initiated by: j
- 1. ' Going to RUN on the Malfunction Timer 1 k
O 2. Satisfying the instructor specified " Trigger" and ;
"1" above.
Note: " Triggers" are provided by ,the simulator- 1 staff.. Procedure:
- 1. To activate the Switch Override Processor:
- a. Push SWITCH OVERRIDE PROC ON.
- b. Follow instructions on'the CONSOLE TERMINAL. i
- 2. To deactivate the Switch Override Processor:
- a. Push SWITCH. OVERRIDE. PROC OFF. ;
i
'l ATT..CHMENT 2- j Page 50 Eof.51 METER OVERRIDE PROCESSOR
Description:
The Meter Override Processor function permits the instructor to override any meter or recorder with-the exception of: )
.i
- 1. Main generator syncroscope
- 2. Diesel generator syncroscopes 'I q
l
- 3. R'eactor Coolant pump vibration meters Meters (and recorders) may be overridden:
- 1. Upward (50 to 100);- result;is essentially that which would occur if the signal conditioning card, 4 in the process or control racks, were to drift upward.
- 2. Downward (50 to 0) - result is essentially that which would occur if the' signal conditioning card, .
in the process or control racks, were to drift l downward. All Meter (or recorder) Overrides can be initiated after'an instructor determined time delay (in seconds). This delay . start is initiated by: l t
- 1. Going to RUN on the Malfunction Timer OE
- 2. Satisfying the instructor specified " Trigger" and!
"1" above.
I Note: " Triggers" are provided by th'e simulator I staff. I 1 Procedure:
- 1. To activate the Meter Override Processor: I
- a. Push METER OVERRIDE PROC ON.
l
- b. Follow instructions on the. CONSOLE TERMINAL. ]
- 2. To deactivate the Meter Override Processor:
- a. Push METER OVERRIDE PROC OFF. j i
I i i _ _ _ . _ _ . _ _ . _ . _ _ _ _ . _ . . . _ _ . _ _ . .J
l ATTACHMENT 2-- l Page-51 of 51-q I O SETPOINT OVERRIDE PROCESSOR ;
Description:
1 The Setpoint' Override. Processor function permits the-instructor to override any. controller setpoint potentiometer. 3
)
Setpoints may be overriden: I Upward (50 to 100) - result is essentially'that1 1. which would occur.if the signal. conditioning card, in the process or control racks, were to drift ' upward (raising.setpoint).
- 2. Downward (50 to 0) - result is' essentially that-which vould occur if the signal conditioning card, in the process or control racks, were to drift downward'(lowering setpoint).
All Setpoint Overrides can be initiated after an instructor determined time delay (in seconds). This delay start is initiated by:
- 1. Going to RUN on the Malfunction Timer-EE
- 2. Satisfying the instructor specified " Trigger"'and "1" above.
Note: " Triggers" are provided by the. simulator D staff. l
. Procedure:
J
- 1. To activate the Setpoint. Override. Processor:
- a. Push SETPOINT OVERRIDE PROC ~0N. ;
- b. Follow instructions on the CONSOLE TERMINAL.-
1 D "
- 2. To deactivate the Setpoint Override Processor:
- a. Push SETPOINT OVERRIDE PROC OFF. !
O i 1
' ATTACHMENT 2 APPENDIX-1 Page'liof 3-
-CONSOLE PANEL FAILURE
Description:
i This procedure describes how to use the INSTRUCTOR /' l DIAGNOSTIC TERMINAL'to operate the simulator in case:of l . CONSOLE PANEL failure. ' In most cases, as soon as CONSOLE PANEL starts-malfunctioning:
- 1. A message is displayed on the CONSOLE TERMINAL.
- 2. If no user-is logged on the INSTRUCTOR / DIAGNOSTIC TERMINAL, control is automatically transferred to the INSTRUCTOR / DIAGNOSTIC TERMINAL, otherwise~it waits for the user to log-off and then transfers the control.
If CONSOLE PANEL failure is suspected and control is not' transferred to INSTRUCTOR / DIAGNOSTIC terminal, it can be-done by setting CONSOLE-FAILED = T through SIMLOCH;or'by using the TYICIN macro. y Simulator can be operated by using.either.the functionicodes. i for'pushbuttons (FUNCTION MODE) or the legendLon the O pushbuttons.(COMMAND MODE) without any spaces. i Procedure:
- 1. Log off the INSTRUCTOR / DIAGNOSTIC TERMINAL as'soon-l as console failed message is noticed on the CONSOLE TERMINAL.
- 2. Enter function code or command in response to command or FUNCTION CODE) and hit return. Type in
? in response to prompt to see the valid command' and function codes.
NOTE: To use TYICIN macro, in TSM type in R TYICIN and hit return. Follow instructions provided on screen.
.1 i
ATTACHMENT 2 APPENDIX 1 i l Page 2 of 3 j s 201 200 Startup l Shutdown i 207 208 211 212 ---_ 215 134 8 ' Single Single Coro Trainee Computer Control Restore Aging perform- Aided Display Save mance Exercise Index Monitor { Plant Simloch Computer Control IC IC page Store Transfer Variable Hold /GO _ Esch -- gg ----- ggg ----- g g ----___g_ IC Back Replay Fast Time Log Control Recall Track Set Up Hold /Go page Recall Forward Run Malf Remote Fast Timer On Time Run
----___-- ) / -------_. -_ ------
i 180 129 132 130 ! 1 \ Freeze Malf Remote Normal : Off Time I Timer Stop Add Step Trip Disable print IC Alarm ACM Counter Review Horn Screen Check Enable Disable 36 94 40 41 95 42
$ ^ ( ) __
e 65 66 67 64 69 70 A B C D E F 73 74 75 76 77 78 I J K L M N
----_-~_- --------- --------- ----- ---------
81 SR 83 64 ---_85 66 Q R S T U V (~' 89 90 Y Z
ATTACHMt.NT 2 APPENDIX 1 Page-3 of 3 EOF Sim. Data Limit [ Link Exceeded
\- Failure (N/A FUS (N/A FUS)
Malf Overide Recover Diagnose Display Display Comm and Index Index Network Recover Malf Override TPM Develop-Page Page Active ment __Each___ _Each____ _________ _________ _ _ _ _ _ _ _ _ _ . Mede______ 141 142 153 144 Malf Override Control Instructor Page page Room Console Forward Forward Diagnos- Diagram tics i i 218 219 220 221 222 223 Malf Alarm Lamp Switch Meter Setpoint Proc Override Override Override Override Override On Proc On Proc On Proc On Proc On Proc On . s
\ 224 225 226 227 228 229 Malf Alarm Lamp Switch Meter Setpoint Proc Override Override Override Override Override Off Proc Off Proc Off Proc Off Proc Off Proc Off Malf i Alarm Lamp Switch Meter Setpoint Active Override Override Override Override Override Active Active Active Active Active j
_________ _________ _________ _________ _________ __________ I
)
G H 1 2 3 Backspace 79 80 52 53 54 32
- . O P 4 5 6 Space gN W X 7 8 9 Enter
( _________ _________ _________ _________ _________ __________ 46 44
._ O
-i ATTACHMENT 2 APPENDIX ~2
)
Page 1 of 2 q 1- . TRAINING PERFORMANCE REVIEW -i DESCRIPTION:
~
The Training Performance Reivev (TPR) function provides the capability to review the data collected during the ._ TPM (Training Performance Monitor) function. This j l review can be performed in two ways. !
- 1. By reviewing the chronological log of the following items on the screen.
- a. Monintored Variables
- b. Malfunction / Override Monitor Status
- c. Malfunction Status
- d. Override Status
- e. Operator.(trainee) actions on control board- ,
- f. All of the above parameters, i
- 2. By reviewing the printed strip charts of monitoredi variables. These printed strip charts provide the following information:
- a. Date of Scenerio
- b. Name of Students i O c.
d. Name of Instructor Up to 6 colored strip charts for monitored Variables. ' The TPR can be used any time after TPM has been. stopped for the desired scenerio. Plotter should be on line before starting the TPR. PROCEDURE:
- 1. Sign on the computer.
- 2. Type in R TPR NU in response to TSM) and hit j return.
NOTE: A list of possible terminal choices.will I be displayed on the screen.
- 3. Type in index number of the terminal being used and hit return.
- 4. Type in ^(TPM) monitor-name and hit return.
.j NOTE: Monitor-name'is the name defined during TPM.
i
-i
. 1
-ATTACHMENT ~2-APPENDIX 2 Page 2 of 2~
- 5. Follow instructions as they appear onfscreen'to see chronological log-.or. print strip chart.
NOTE: 1. To exit chronological log'in the middle, push space bar'in response to " ENTER'CR FOR'MORE".
- 2. While getting the strip chart,
.af ter STOP TIMEfis entered the :TPR goes to sleep mode for:a few seconds. During this-period it is developing the strip chart. After it wakes up,-it provides further isntructionsLto get'a hard copy'of the strip chart.
- 6. .To get the hard copy from the plotter:
- a. Load the' paper on plotter as'follows:
1 (1) - -Push. down the LOAD, button. (ii) Align.the paper with'the mark on bottom left ] (iii) Push the LOAD button againsto release : it. l NOTE: .The paper will be pulled /down by: static O charge.
- b. Push down and hold the CALL button until;it teeps and then. release it.
NOTE:' The plotter should start. plotting at this time.
- c. To remove'the paper from the-plotter (1) Push down the LOAD button.
.(11) Remove the paper. ~
(iii) Push the LOAD button'again to release it. l l i L 1
- w. -
. ._= - 1
x ATTACHMENT 2. APPENDIX 3' Page 1 of 2-O INITIAL CONDITIONS
- 1. MODE 1 (100 PEC 4000 EFPD) ARO 03/23/88'
- 2. MODE 1-( 50 PEC 4000 EFPD) 814 PPM 07/30/87
- 3. MODE 1 ( 30 PEC 4000 EFPD) 811 PPM 07/30/87
- 4. MODE 1 ( 8 PEC. 4000 EFPD) 793 PPM 07/30/87
- 5. MODE 2 (4 PCT) TURB 1800 RPM GEN. SECURED 12/18/87
( 6HR L AGO : TRIP HFP )
- 6. MODE 2 ( D BANK AT 0 STEPS-) ECP AT'140 STEPS 07/30/87
- 7. MODE 3 ( CONTROL BANKS INSERTED ) ECP 144 07/30/87
- 8. MODE 3 ( STABLE ) AT STEP ~4.4 IN 1_OP_3.3 07/30/87
- 9. MODE 3 ( STABLE ) AT STEP 4.13 IN 1_OP_3.3 07/30/87
- 10. SPARE 08/18/87
- 11. SPARE 10/07/87 ,
- 12. SPARE 02/25/88 j
- 13. SPARE 08/27/87 ,
- 14. SPARE 08/27/87
- 15. SPARE 08/27/87
- 16. BEGINNING OP_3.4 COME BACK 07/31/87 1 '7 . 440F_ COOLING _DOWN 10/29/87
- 18. COOLDOWN336DEF 1222 PPM 500 PPM RHR DCF 01/28/88
- 19. SOLID 150 F 50 PSI STEP 4.21 IN:OP_5.1 02/11/88 !
STABLE 2 11 88 *** l
- 20. EARLY CRITICALITY 1RSTEPS D BNK 954RMP ECP144 D BNK 03/04/88
- 21. IC_1 AFTER 1 HOUR STEADY RUN (ANN DEFEATED) WFS 04/27/88' ,
- 22. 143 STEPS 10E8 AMPS 1089 PPM XE FREE 08/07/87 .
- 23. 2 PCT 151 STEPS START OF OP_2'.1 08/07/87 10: ;
ATTACHMENT 2-APPENDIX ~3 Page 2 of=2 0 24. 415DEG SGTR C SG 01/28/88 , 25 - *EARLY CRIT (112C BK) NO XE(0 STEP A BK)922' PPM 02/09/88 STABLE
- SAVE -(
- 26. SOL'ID 151 F 50PSIG STEP 4.21 OP_5.1 08/07/87 l
- 27. . PREP'TO DRAW BUBBLE OP_1.1 STEP 4.23(304 F PZR)- -08/07/87- l 190 TAVG
- 28. LORP_CYC_6_SEG_2 06/28/88 I
- 29. 195F 300 LBS OP_3.3 COMPLETED SAVE SDD 01/28/88
- 30. 185'F 4DS IN PZR OP_1.1 STEP 4.23 DRAWING BUBBLE 01/28/88 SAVE SDD
- 31. MODE 1(50 PCT) EQUIL XE(176 D BK) 942 PPM
- 02/09/88 STABLE
- SAVE **
- 32. MODE .2 (4 PCT) TURB 1800 RPM GEN SECURED 12/16/87 (6HR AGO TRIP HFP)
- 33. ICI AFTER 3 HOURS STEADY STATE DCF 02/15/88 O 34. SOLID STABLE 195 F DRAWING A-BUBBLE (410 F PZR)'* SAVE ****
02/11/88
- 35. START UP 100 STEPS C BANK (140 D.ECP) 10/07/87
-36. LORP_CYC_5_SEG_2 06/21/88
- 37. LORP_CYC_6_SEG_1 06/28/88
- 38. 25 PCT 157 STEP D BK SAVE NEEDS TO SETTLE 12/02/87 OUT **SAVE*****
- 39. LORP_ CYCLE _4_SEG_1 06/24/88
- 40. SPDS* TEST 04/15/88 I
i
)
I
l' VIRGINIA POWER' SIMULATOR SUPPORT GROUP NORTH ANNA-UNIT 1 SIMULATOR ATTACHMENT 3 .i
' SIMULATOR TEST RESULTS-s e
e [
\
O e i i
ATTACHMENT 3-Page 1,of 85 ) O SIMULATOR-TEST'RESULTS Since_ delivery in September 1983, when a comprehensive Final. Acceptance Test Program . was completed, many ! modifications have been made- and tested to verify proper. operation. All necessary testing which verified. simulator fidelity acceptable for trainf*.cg and certification has .been-completed. All discrepancies uncovered are expected to be resolved in'accordance with the maintenance schedule. which has been included. Based upon the testing conducted, the North Anna simulator is acceptable for licensed operator training and retraining. The following are brief synopses of the results of the tests conducted, which include Performance Intergrated l Operation Tests, Transient Tests, Malfunction Tests, Unique Tests, and Surveillance Tests. Additional information concerning' malfunctions can. be q obtained by refering to the Malfunction Cause and Effects index. O
.I l
l i i l d l i
ATTACHMENT 3 Page 2 of 85 i
)
l l O l l i l VIRGINIA POWER SIMULATOR SUPPORT GROUP l NORTH ANNA UNIT 1 SIMULATOR MALFUNCTION INDEX O
ATTACHMENT 3 Page 3 of 85 MASTER CROSS INDEX MALF MALFUNCTION DEGRADATION NO DESCRIPTION GENERIC % RAMP MCA01 CONT IA COMPRESSOR ~YES .NONE NO FAILS DUE TO MOTOR OVERLOAD MCA02 CONTNMNT IA SYS LEAK NO 0-100 CFM YES DUE TO PIPE BREAK BETWEEN CMPRSR DISCH
& CHECK VLV MCA04 IA LEAK YES 0-100 CFM YES IN ONE OF SEVERAL HEADERS l
MCC02 CC PUMP FAILS TO START YES NONE NO TRIPS ON OVERLOAD DUE TO UNDERSIZED FUSES INSTALLED 1 MCC03 CC FLOW XHTR FAILS YES 0-MAX GPM NO
/N.
( ,) .MCC04 CC DISC PRESS XMTR NO 0-MAX PSIG YES FAILS MCC05 RCP THERMAL BARRIER YES' NONE NO LEAK DUE TO A TUBE LEAK MCC06 COMPONENT COOLING YES NONE NO WATER PUMP SHAFT
, SHEARS DUE TO FATIGUE FAILURE MCH01 ISOL LTDN LEAK IN NO 0-100 GPM YES ,
IN CONT BETWEEN LTDN ' i ORIFICES & THE CONTAINMENT WALL l MCH02 ISOL LTDN LEAK OUT NO 0-100 GPM ' YES CONT BETWEEN TV-1204
& THE CONTAINMENT WALL MCH03 ISOL CHG LEAK OUT CONT NO 0-150 GPM YES BETWEEN THE HEADER AND MOV-1289B
AT1ACHMENT 3 Page 4 of 85 O MALF MALFUNCTION DEGRADATION NO DESCRIPTION GENERIC % RAMP MCH04 LTDN PRESS XMTR FAILS NO 0-100 % YES MCH05 BLNDR BORATES IN NCR NO NONE NO M/U DUE TO SWITCH MALFUNCTION MCH06 LOSS OF CC TO LTDN HX NO NONE NO DUE TO PEEDBACK LINKAGE ON CC VLV BREAKS MCH07 CHG FLOW.CONTROLR NO 0-100 % YES FAILS INTO THE AUTO' MODE MCH08 CHG FLOW XMTR FAILS NO 0-100'% NO MCH09 REACTOR MAKEUP NO NONE NO DILUTION IN AUTO MODE I MCH11 B. A. TO BLNDR PLUGGED NO 0-100 %' YES DUE TO FAILED HT
,o BETWEEN BLENDER &
FCV-1113A {} l MCH12 VCT LEVEL XMTR FAILS YES 0-100 %. YES MCH13 NONREGEN'HX TUBE NO 0-50 GPM -YES o RUPTURE l l MCH15 BLNDR CONTRL FAILS TO NO NONE NO l OP DUE TO A LOSS OF
. POWER MCH16 CHARGING PUMP FAILS YES NONE NO DUE TO A BREAKER OVERLOAD MCH18 PCV-1145 FAILS OPEN NO 0-100 % YES IN AUTO (MAN IS OPERABLE) ,
l MCH21 CHARG1NG PUMP CHECK .O N NONE NO' l ' VALVE STICKS OPEN MCN01 LOSS OF CONDENSER M/U NO NONE NO DUE TO LC-CN-109 FAILING HIGH O 1 l 1
ATTACHMENT 3' Page 5.of 85 MALF MALFUNCTION DEGRADATION NO. DESCRIPTION GENERIC % RAMP MCN07 LCV-CN-107 FAILS OPEN NO NONE NO DUE TO FEEDBACK LINKAGE FAILING OFF MCN14 CONDENSATE PUMP NO NONE NO DISCHARGED CHECK VALVE STICKS OPEN MCN16 ' CONDENSER AIR IN NO 0-190 CFM 'YES-LEAKAGE.VIA LP TURBINE RUPTURE DISCS ~ MCV01 CONT PRESS INC SLOWLY NO 0-2500 CFM NO DUE TO LM VLV ON A QS PUMP LEFT OPEN MELO1 LOSS OF OFFSITE POWER NO NONE NO DUE TO SYSTEM GRID VOLTS OR FREQ DEGRADATION (~ MELO3 LOSS OF 4160 EMERG YES NONE NO BUS DUE TO A ELECTRICAL SHORT IN THE NOR SUPPLY BREAKER MELO4 . LOSS OF 4160 STA SER YES NONE' NO BUS DUE TO A GROUND FAULT IN THE XFMR MELOS LOSS OF 125V DC BUS YES NONE NO DUE TO A GROUND MELO6 LOSS OF 480V EMERG YES NONE NO BUS DUE TO THE SUPPLY BREAKER OPENING ON AN ELECTRICAL FAULT MELO7 LOSS OF 480V STA SER YES NONE NO' BUS DUE TO TRANSFORMER BLOWING UP MELO8 LOSS OF EMERG DIESEL YES NONE NO GEN DUE TO EXCITER FAILURE O .
ATTACHMENT 3 Page 6 of 35 7-~ MALF MALFUNCTION DEGRADATION NO DESCRIPTION GENERIC % RAMF MEL11 MAIN GENERATOR TRIP NO NONE NO DUE TO MN XFMR LOCKOUT AS T&E TESTING WRONG 86 RELAY MEL12 LOSS OF SEMI VITAL YES NONE NO BUS DUE TO SHORT-MEL13 LOSS OF VITAL BUS YES NONE ,NO DUE TO LOSS OF INVERTER MEL15 LOSS OF 480V NO NONE NO . EMERGENCY MCC HELIG LOCS OF 480 VOLT NO NONE NO STATION SERVICE MCC -I MEL17 PRI PROC RACK BKR YES NONE NO TRIPS DUE TO ELECTRICIAN ERROR MFWOI SG LVL TRANSMITTER YES 0-100 % YES FAILS MFWO2 SG LVL PRESS COMP YES 0-100 % YES LOST DUE TO LOSS OF TURB 1ST STAGE COMPENSATION SIGNAL MFWO4 MN FW PUMP LO OIL YES NOR-0 PSIG YES DUE TO CLOGGED OIL FILTER MFWOS MN FW REG VLV FAIL YES NONE NO CLOSE DUE TO THE IA SUPPLY LINE BREAKING MFWO6 TOTAL LOSS OF NO NONE NO
- l. FEEDWATER DUE TO l
SABOTAGE OF PUMP BREAKERS AND STEAM TO AUX FW TURB ISOLATED lO
?
s ATTACHMENT 3 Page.7 of 85 ~ l O MALF MALFUNCTION GENERIC DEGRADATION
% RAMP i
O N_O, DESCRIPTION MFWO8 LOSS OF STEAM YES" NONE NO j GENERATOR LEVEL i ERROR SIGNAL j i
~
MFWO9 AUX FD PUMP FAILS YES NONE NO - DUE TO OVERSPEED j MFW10 AUX FD PP CHECK VLV YES 0-MAX GPM .NO j OPEN FOLLOWING 1 SURVEIL. TEST 1 MFW11 AUX FD PF IMPELLER YES 0-100 % YES FAILS DUE TO A - CASTING DEFECT MFW12 MN FD FLOW XMTR FAILS YES 0-MAX.LBH YES i MFW13 FW.BRK AT FLW XMTR YES 0-100 % YES j REG VV BETWEEN REG VLV & XMTR MFW14 AFW BRK DWNSTRM YES NONE YES BETWEEN FLOW XMTR O AND CHECK VALVE MFW15 MFW BRK DWNSTRM OF YES 0-100 % 'YES CHECK VALVE OUTSIDE 3 OF CONTNMNT , l MFW16 MFW BRK IN YES 0-100 % YES CONTAINMENT . MFW17 MN FD PUMP DEGRADES YES 0-100 % YES l DUE TO A CASTING FLAW j IN THE IMPELLAR NO j MFW18 MN FW REG VLV FAILS YES NONE OPEN DUE TO A l I FEEDBACK LINKAGE FAILURE i MFW19 FEEDLINE BREAK BETWEEN YES 0-100 % YES FE AND CHECK VALVE MFW21 MAIN FEEDWATER PUMP YES 0-100 % YES SUCTION BREAK O
ATTACHMENT 3-Page 8 of 85 MALF MALFUNCTION DEGRADATION NO DESCRIPTION GENERIC 4 RAMP MFW23 AUX FEED PUMPS TRIP YES NONE NO ON OVERCURRENT MGWOI WGDT RUPTURES DUE TO YES 0-100% YES EXPLOSIVES BY SABOTEURS MMS 01 SG STM FLOW XMTR YES NOR-MAX LBH YES FAILS MMS 02 TUR 1ST PRES XMTR YES 0-MAX PSIG YES FAILS MMS 08 MN STM BREAK IN YES 0-3.8E+6 LBH YES CONTNMNT BEFORE THE FLOW XMTR MMSO9 MN STM BREAK AFTER YES 0-3.8E+6 LBH YES. NRV IN SAFEGUARDS AREA MMS 10 MN STM BREAK BEFORE YES 0-3.8E+6 LBH YES f' TV IN SAFEGUARDS AREA MMS 11 STEAM DUMPS FAILS AS NO NONE NO IS DUE TO CONTROL CIRCUIT FAILURE MMS 12 MN STM REL VLV OPEN YES 0-100 % YES DUE TO CONTROLLER FAILURE MMS 13 MN STM TV FAILS YES NONE NO AS IS BUT INDICATES PROPERLY MMS 14 MN STM SAFETY VLV YES 0-100 % NO OPEN DUE TO METAL l FATIGUE OF THE VLV SPRING
- i
ATTACHMENT 3 Paga 9 of 85 O MALF MALFUNCTION DEGRADATION NO DESCRIPTION GENERIC % RAMP MMS 15 MS DUMP VV STUCK OPEN YES NONE NO DUE TO TIGHT PACKING MMS 16 STM PRESS CNTRL FAILS NO 0-100 % YES LO DUE TO TRANSMITTER FAILURE MNIO1 PWR RANGE UP DET FAILS YES 0-MAX AMPS YES MNIO2 PWR RANGE LOW DET YES 0-MAX AMPS YES FAILS MNIO3 PWR RNGE CNTRL FUSE YES NONE NO FAILS MNIO4 PWR RANGE INST FUSE YES NONE NO FAILS I MNIO6 SR DET FAILS (DISC. YES 0-MAX VOLTS NO ERR) IMPROPER DISCFIM VOLT SETTING MNIO8 INT RNG BAD YES 0-MAX VOLTS YES l COMPENSATION DUE 1 TO I&C TECH ERROR MNIO9 INT RANGE DET FAILS YES 0-100 % YES DUE TO AMPLIFIER FAILURE MNII0 SOURCE RANGE CH YES 0-100 % YES FAILURE DUE TO EITHER 4 A BAD LOG LEVEL AMP 'I OR AMPLIFIER MNI13 POWER RANGE CH FAILS YES NONE NO DUE TO LOSS OF PWR' I SUPPLY MQS01 CONTAIN SPRAY PUMP YES NONE NO 4 TRIPS DUE TO UNDERSIZED FUSES INSTALLED DURING MAINTENANCE ' i MQS03 SPRAY FAILS TO NO NONE NO INITIATE DUE TO SETPOINT SET TOO l HIGH BY I&C TECHS
ATTACHMENT 3 Pcga 10 of 85 g l 0 MALF NO MALFUNCTION DESCRIPTION GENERIC DEGRADATION
% RAMP MQS06 SPURIOUS CONTAINMENT NO NONE NO SPRAY ACTUATION MRC01 RCS COLD LEG RUPTURE YES NONE NO BETWEEN RX VESSEL &
LOOP STOP VALVE MRC02 RCS HOT LEG RUPTURE YES NONE NO BETWEEN RX VESSEL & LOOP STOP VALVE MRC03 RCS SUCT LEG RUPTURE YES NONE NO BETWEEN PUMP SUCTION ' 4
& S/G OUTLET MRC04 RCS LEAK NONISOLABLE NO 0-600 GPM YES OUE TO'B COLD LEG RTD q l
FAILURE MRC05 RCP OVERCURRENT TRIP YES NONE NO MRC07 PRZR PRESS XMTR FAILS YES MON-MAX PSIG YES j DUE TO LOSS OF BALANCE I {~ SEAL ON THE REF. LEG MRC08 PRZR LVL XMTR FAILS YES 0-100% LVL NO MRC11 RC FLOW XMTR FAILS YES MIN-MAX % YES MRC14 RCP NO.3 SEAL FAILS YES 0-10 GPM YES MRC15 CNTRL COID LEG RTD YES MIN-MAX DEGF YES FAILS MRC17 PROT HOT LEG RTD YES MIN-MAX DEGF YES FAILS MRC18 PROT COLD LEG RTD YES MIN-MAX DEGF YES FAILS MRC19 PRZR RELF VLV STUCK YES NONE NO OPEN-EFFECTIVE WHEN VLV OPENS
ATTACHMENT 3 Page 11 of 85 v MALF MALFUNCTION' DEGRADATION NO DESCRIPTION GENERIC % RAMP MRC20 PRZR SPRAY VV STUCK YES NONE 'NO OPEN DUE TO FEEDBACK LINKAGE BREAKING MRC21 PRZR SAFETY.VV STUCK YES. 0-100 % YES OPEN EFFECTIVE WHEN VLV-OPENS MRC22 H BUS PRZR HEATERS ~ NO NONE NO FAIL'ON DUE TO TRIP CIRCUIT CONTROL PWR FUSES WERE INSTALLED IMPROPERLY MRC23 J BUS PRZR HEATERS NO NONE NO FAIL ON DUE TO A TRIP CIRCUIT MALFUNCTION MRC24 STM GEN TUBE RUPTURE YES 0-1100 GPM YES MRC25 PRZR SPRAY VVS FAIL NO NONE NO , SHUT DUE TO IA LINES O MRC26 TO E/P BEING CLOGGED RCP SHEARED SHAFT NO NONE NO MRC29 PRZER PRESS CNTRL NO 0-100 % YES FAILS MRC31 FUEL LEAK NO 0-100 % YES MRC32 PCV-456 SEAT LEAKAGE NO 0-100 % YES MRC33 PT-402 WIDE RANGE NO 0-100 % YES PRESSURE TRANSMITTER j FAILURE-MRC34 PT-403 WIDE RANGE NO 0-100 % YES PRESSURE TRANSMITTER FAILURE MRC35 PRT LEVEL TRANSMITTER NO 0-100 4 YES , FAILURE MRC36 PRT PRESSURE NO 0-100 % YES TRANSMITTER FAILURE I (])
ATTACHMENT 3 i Page-12 of 85 MALF MALFUNCTION DEGRADATION NO DESCRIPTION GENERIC % RAMP MRC37 RCS VESSEL FLANGE LEAK NO '0-100 % YES TEMP. DETECTOR FAILURE MRC38 LOSS OF CC WATER TC YES 0-400 GPM NO RCP DUE TO CASTING LEAK AT THE STATOR COOLER INLET MRC40 PZR SURGE LINE TEMP NO 0-100 % YES TRANSMITTER FAILURE i MRC41 RCS SPRAY LINE TEMP NO 0-100 % YES ' TRANSMITTER FAILURE MRC42 PRESSURIZER LIQUID / NO 0-100 4 YES VAPOR TEMPERATURE TRANSMITTER FAILURE MRC43 PRESSURIZER PORV LINE NO 0-100 % YES TEMP. TRANSMITTER FAILURE MRC44 O i PRESSURIZER SAFETY LINE TEMP. TRANSMITTER FAILURE NO 0-100 % YES MRC45 PRT LIQUID TEMP. NO 0-100% YES TRANSMITTER FAILURE MRC46 PRESSURIZER SPRAY NO 0-100 % YES CONTROLLER FAILS MRD01 IRPI FAILURE DUE TO YES NONE NO LINEAR VARIABLE DIFFERENTIAL XFMR FAILING MRD06 CONTINUOUS WITHDRAWAL NO NONE NO DUE TO ROD CONTROL LOGIC FAILURE MRD07 CONTINUOUS ROD NO NONE NO INSERTION DUE TO ROD CONTROL LOGIC FAILURE MRD08 RODS MOVE AT MAX SPEED NO NONE NO DUE TO FAILURE IN THE SPEED CONTROL CIRCUIT O
ATTACHMENT 3 Paga 13 of.85 MALF MALFUNCTION DEGRADATION NO, DESCRIPTION GENERIC % RAMP MRD09 RODS MOVE AT MIN SPEED NO NONE NO-DUE TO FAILURE IN THE SPEED CONTROL CIRCUIT MRD10 RODS REVERSE DIRECTION NO NONE NO IN AUTO ROD CONTROL MRD11 RODS REVERSE DIRECTION YES NONE NO. IN MANUAL MRD13 B&D BANKS MOVE NO NONE NO TOGETHER DUE TO FAULTY BK SELECT SWITCH OR SLAVE' CYCLER MRD14 RODS DONT MOVE IN NO NONE NO i AUTO DUE TO SUMMER s ERROR FAILING TO ZERO MRD15 NO ROD MOTION IN NO NONE NO MAN /GRP DUE TO LOGIC 1 s CABINET PHASE FAILURE
]
MRD16 DROPPED ROD DUE TO YES NONE NO
. STATIONARY COIL FAILURE MRD21 EJECTED CONTROL ROD YES NONE NO DUE TO ROD MECHANISM HOUSING RUPTURING j MRD26 STUCK CONTROL ROD DUE YES NONE NO TO LIFT COIL FAILURE MRD31 RODS CNTRL TEMP > NO NONE- NO SETPT DUE TO TAVE CNTRL SUMMER FAILURE 1 MRD32 AUTO TRIP WONT TRIP NO NONE NO !
RX DUE TO BREAKER SABOTAGE MRD33 ROD STOPS DONT STOP NO NONE NO ' RODS DUE TO SIGNAL FAILURE TO ROD CONTROL SYSTEM _ _ _ _ _ _ _ _ _ _ _ _ i
l 1 l l l ATTACHMENT-3 I Page 14 of 85 l () MALF MALFUNCTION DEGRADATION ! NO DESCRIPTION GENERIC % RAMP MRD34 RX TRIP BREAKERS OPEN YES NONE NO
'DUE TO UNDERVOLTAGE COIL FAILURE l
MRD36 LOSS OF NI SIGNAL TO NO NONE NO RODS FROM N-44 i MRD38 MANDAL RX TRIP FAILS NO NONE NO DUE TO FAILURE OF UNDERVOLTAGE SHUNT TRIP COILS MRH01 RHR SYSTEM LEAK DUE NO 0-1000 GPM YES TO B PP RELIEF VALVE FLANGE LEAK MRH02 RHR FLOW XMTR FAILS NO 0-100 % YES MRH03 CC SUPPLY LEAK TO RHR NO 0-1000 GPM YES HX DUE TO A HX CC INLET FLANGE LEAK MRH05 LOSS OF RHR PUMP YES NONE NO I ( DUE TO UNDERSIZE FUSES BEING INSTALLED IN BREAKER MRH06 RELIEF VALVE STUCK YES NONE NO i OPEN-EFFECTIVE WHEls OPEN MRM01 AREA RAD MON FAILS YES MIN-MAX ACT NO DUE TO CIRCUIT DEGRADATION l MRM02 PROCESS RAD MON FAILS YES MIN-MAX ACT NO DUE TO CIRCUIT DEGRADATION MRS01 OS RS PUMP FAILS DUE YES NONE NO TO UNDERSIZED FUSES INSTALLED DURING MAINT. l MRS02 INS RS PUMP FAILS YES NONE NO DUE TO UNDERSIZED FUSES INSTALLED DURING MAINT. (
ATTACHMENT 3. Pago 15 of 85 MALF MALFUNCTION DEGRADATION NO DESCRIPTION GENERIC % RAMP MSIO3 LO HD SI PUMP YES 0-100 % YES DEGRADES DUE TO CLOGGED STRAINER MSIO5 SPURIOUS SI (1 OR 2 YES NONE NO TRNS) DUE TO I & C ERROR MSIO6 FAILURE OF'SI TO NO NONE ' NO '
' RESET DUE TO STUCK RELAYS IN THE SAFEGUARDS RACK MSIO7 1 TRN OF SI FAILS TO YES NONE NO ACT DUE TO. LOSS OF POWER MSIO8 ANY SI SIGNAL WONT ACT NO NONE NO SI DUE TO SABOTAGE MSWOI SERVICE WATER PUMP YES NONE NO TRIP OM OVERLOAD DUE i rs TO BAD OVERCURRENT
( SETTINGS i MTU01 TURBINE OVERSPEED NO NONE NO TRIP CUE TO OVERSPEED ELECT. CIRCUIT FAILURE MTUO2 MAN TURB TRIP FAILS NO NONE NO DUE TO SOLENOID AST-1 FAILURE MTUO3 AUTO TURB TRIP FAILS NO NONE NO-DUE TO LOSS OF CONTROL POWER ( MTU12 AUTO TURB RUNBACK NO NONE NO i FAILS DUE TO RUNBACK l CONTROL CIRCUIT I FAILURE MTU13 SPURIOUS TURBINE NO .NONE NO RUNBACK DUE TO TIMER CIRCUIT FAILURE ; MTU14 REHEATER SV STUCK YES NONE NO OPEN-EFFECTIVE WHEN f- OPEN I I l
ATTACHMENT-- 3 Page.16 of 85 l
-i O
VIRGINIA POWER SIMULATOR SUPPORT GROUP-NORTH' ANNA UNIT'1 SIMULATOR. PERFORMANCE TEST RESULTS O
- )
ATTACHMENT'3 Page 17 of 85 SIMULATOR REAL TIME TEST The Simulator Real Time Test was a continuous check of simulator response during'the performance testing phase of the simulator. certification process.- All; certification tests, which include. Steady State, Normal, Transient and. Malfunction Tests were monitored for proper' sequencing, durations, rates and accelerations. Each test verified that the software _and hardware-dynamic responses replicated those of the reference plant. The computer complex was verified to be executing model calculations in real time'by comparing the model execution rate to real time.
'1 I
u () 1 l l l l l l O I 1
ATTACHMENT 3 Page 18 of_85 l ( STEADY STATE STABILITY l This test was conducted on June 7, 1988 in compliance with ANS-3.5-1985 section 3.1. It was a test to validate the simulator performance of a 60 minute, 100% power steady state run. Initial conditions of 100% reactor power was established for 200 seconds before the actual data 1 collection commenced. This allowed any perturbations to J reach equilibrium conditions. Data was collected in several forms. Computer printout . with a one minute- resolution, simulator trend charts, and thermal. trend charts. The simulator computer values were checked to ensure they did not drift.more than two percent and that they were i within the two percent tolerance limit of the. reference plant. This was done by comparing-values at the beginning { i and end of the test and against steady state log readings. '] 1 3' f~ V O
ATTACHMENT 3 Page 19 of185 ' O FULL POWER TRIP AND RECOVERY This test was conducted on June 7, 1988 in compliance with ANS-3.5-1985 section 3.1. It was a test to validate the simulator performance of a Full Power manual reactor trip and recovery. Initial conditions of 100% reactor power was established.for several minutes when a manual reactor trip was implemented iva operater action. Actual plant procedures were used to stablize the plant at 547 degrees F. in Hot Shutdown. conditions. The plant was then returned to .- hot standby conditions using plant procedures. It was maintained in this condition until proper operation of the steam dumps was confirmed. Data was collected in several forms. Computer printout with a one minute resolution, simulator trend charts, and thermal trend charts. The procedures used in the stes are also included in the data package. Test results were compaired to actual plant data and no - significant differences were found. O O
ATTACHMENT 3 Page 20 of 85 1 RAMP FROM 100% TO COLD SHUTDOWN CONDITIONS This certification test was conducted using the current plant operating procedures. Data was collected in several forms, ie,' computer printouts, thermal recorders, and ' pen chart recorders. The test run commenced with steady state IC conditions at 100% reactor power. A power reduction was started at a rate of one percent per minute and maintained during the ramp._ Boration, . rods, and the turbine were used to control plant temperature.until low power conditions were reached. At approximately fifteen percent power, operator error caused.a reactor trip to occur due to a low steam generator level. A Backtrack Recall was performed to just two minutes prior to the trip ~and corrective operator. action was taken. The simulator was then cooled down tc cold shutdown conditions of less than'two hundred degrees and on Residual Heat Removal cooling. No problems were encountered during this test. O I t i l 1
)
l i
ATTACHMENT 3
.Page 21 of 85.
('~) f
\_/ 1 LOAD CHANGES l
This certification test was conducted in accordance
~
with ANSI / ANS-3.5-1985- section 3.1. It was a test to validate the simulator performance for various load changes { from 100% steady state power. Actual plant procedures were i used during the test run to ensure that all control room actions were reproducible. i The first load change. consisted of a 5%/mir. ramp .from 100% to approximately 85% power. When conditions stabilized-an up power ramp to 100% was implemented. . This portion' of the test was concluded when stable conditions existed at 100% power. The initial 100% steady state conditions were- recalled-I and run for five minutes. A step load change of 10%, from 100% to 90% was implemented. After the unit stabilized- a ! step load change from 90% to 100%'was started. Power was > stabilized at 100%. The initial 100% steady state conditions were recalled again and run for ten minutes. At this a step load . change )' from 100% to 50% at a rate of 200%/ min was implemented. i (~} kJ Power was stabilized at 50%. Data collection consisted of the following: o A hard copy printout of forty parameters o Actual simulator trend charts o Thermal charts of sixteen parameters j l There were no problems encountered during this test. O i i 4
I ATTACHMENT 3 Page 22 of 85 PLANT STARTUP l This certification test was conducted .in accordance with ANSI / ANS-3.5-1985 section 3.1. It was a test to i validate the simulator performance from cold conditions at -( ' 195 degrees F to Hot Standby conditions of 547 degrees F and zero power level. Actual plant procedures were used during the test run to ensure that a'11 control room actions were . reproducible. These procedures are included in the test data package. The test was conducted for eight and one half hours and was ; secured when stable hot standby conditions existed, ie. l steam pressure controlled by the Steam Dumps. l Data collection consisted of the following as appropriate: o A hard copy printout of. forty parameters o Actual simulator trend charts o Thermal charts of sixteen parameters Problems encountered during the test were the development of a severe electrical storm which created network trouble with the Hand Control Stations on i Benchboard One and Two. Several " Start Requests" were necessary to restore the stations to operation. This however had no impact on actual test results. I 1 l l i i l k wJ w__________:_____-__-__-_-_-__---__-_- _ _ _ _ _ _ - - _ _ . _ _ _ . _ _ _ _ ___ ._ _ _ .
ATTACHMENT 3 Page 23 of 85 PLANT STARTUP FROM HOT SHUTDOWN TO FULL POWER CONDITIONS This performance test was conducted on May 28, 1988 in compliance with ANS-3.5-1985 section 3.1. The test was a plant startup from Hot Shutdown conditions to rated full power which included a Turbine startup and Generator synchronization. Initial conditions of 547 degrees F. and zero power level was established. Actual plant procedures were used and included as port of the data package. Data was collected in several forms; computer printouts of a one minute resolution, simulator trend charts, and thermal trend charts. The test was conducted until rated full power was achieved. A known deficiency between current load cycle graphs and modeled core cycle was reidentified. This produced errors in the ECP calculations. The core model is currently planned for upgrade by December 2, 1988 according to the simulator upgrade schedule. O O
ATTACHMENT 3 Page 24'of 85 O 1 VIRGINIA POWER SIMULATOR SUPPORT GROUP 4 l l 1 I 1 NORTH ANNA USTIT 1 SIMULATOR TRANSIENT TEST RESULTS I t O
ATTACHMENT 3 Page 25 of 85 MANUAL REACTOR TRIP With simulator initial conditions of 100% power steady state, a manual reactor trip was conducted with no operator followup action. Forty parameter points were monitored and ' recorded versus time with a resolution.of one half second. The test was concluded after approximately ten minutes of run time when plant conditions were stable. No problems were encountered.during the test. SIMULTANEOUS TRIP OF ALL FFEDWATER PUMPS With simulator initial conditions of 100% power steady state, a simultaneous trip of all feedvater pumps was activated using malfunction MFWO6. No operator followup action was taken. Forty parameter points were monitored and recorded-versus time with a resolution of one half second. The test was concluded.after approximately ten minutes of run time when plant conditions were stable. No problems were encountered during the test. f- SIMULTANEOUS CLOSURE OF ALL MAIN STEAM ISOLATION VALVES ' With simulator initial conditions of 100% power steady state, a simultaneous closure of all main steam isolation valves was implemented via operator action. No operator i followup action. was taken. Forty parameter points were monitored and recorded versus time with a resolution of one i half second. The test was concluded after approximately. ten J minutes of run time when plant conditions were stable. No problems were encountered during the test. SIMULTANEOUS TRIP OF ALL REACTOR COOLANT PUMPS With simulator initial conditions of 100% power steady state, a simultaneous trip of all reactor coolant pumps was activated using malfunction MRC05. No operator followup action was taken. Forty parameter points were monitored and , recorded versus time with a resolution of one half second. The test was concluded after approximately ten minutes of run time when plant conditions were stable. No problems i were encountered during the test. O
l l ATTACHMENT 3 Page 26 of 85 I i
\_
TRIP OF ANY SINGLE REACTOR COOLANT PUMP 1 With simulator initial conditions of 100% power steady state, a trip of "B" loop reactor coolant pump was activated using malfunction MRC05. No operator followup action was taken. Forty parameter points were monitored and recorded versus time with a resolution of one half second. The test-was concluded after approximately ten minutes of run time when plant conditions were stable. No problems were encountered during the test. MAIN TURBINE TRIP With the simulator initial conditions at approximately 10% power, a manual turbine trip was implemented via operator action. No operator followup action was taken. Forty parameter points were monitored and recorded versus time with a resolution of one half second. The test was concluded after approximately ten minutes of run time when plant conditions were stable. No problems were encountered during the test.
) MAXIMUM RATE POWER RAMP With the simulator initial conditions at steady state 100% power, a ramp rate of 5%/ min was started. Power was reduced to approximately 75%, momentarily stopped and then increased back to 100% at the rate of 5%/ min. No operator followup action was taken. Forty parameter points were monitored and recorded versus time with a resolution of one half second. The test was concitded after approximately ten minutes of run time when plant conditions were stable. No problems were encountered during the test.
LOCA WITH LOSS OF ALL OFFSITE POWER With simulator initial conditions of 100% steady state power, a maximum size reactor coolant system rupture combined with a loss of all offsite power was activated using malfunctions MRC01 and MELO1. No operator followup action was taken. Forty parameter points were monitored and recorded versus time with a resolution of one half second. The test was concluded after approximately ten minutes of run time when plant conditions were stable. No problems were encountered during the test. 4
l l , . ATTACHMENT 3 l Pago 27 of 85 .j
.( \ UNISOLABLE MAIN STEAM LINE RUPTURE l With simulator initial conditions. of 100% steady state power, a maximum size unisolable "C" main steam line rupture was activated using malfunction MMS 08. No operator followup action was taken. Forty parameter points- were i
monitored and recorded versus time with a resolution of. one i half second. The test was concluded after approximately ten minutes of run time when plant conditions were stable. No l problems were encountered during the test. l LOCA TO SATURATION CONDITIONS With the simulator initial conditions at steady state 100% power a slow primary system depressurization was started. This was implemented by1 opening one of the pressurizer power operated relief valves. Activation' of ECCS was accomplished by using malfunction MSIO8. No operator followup action was taken. Forty parameter points I I were monitored and recorded versus time with a resolution of one half second. The test was concluded after approximately ten minutes of run time when plant conditions were stable at 1 saturated conditions. No problems were encountered during I~
- the test. i d
l 4 k l l l
l-l 1 ATTACHMENT 3 1 Page 28 of 85 I O L l i 1 l 1 \ l ) l VIRGINIA POWER , 1 i SIMULATOR SUPPORT GROUP \ l l i l O NORTH ANNA UNIT 1 SIMULATOR ' MALFUNCTION TEST RESULTS 1 l i l
.I i
- O 1
ATTACHMENT 3 Page 29 of 85
/~
( l MALFUNCTION TEST RESULTS MCA01 FAILURE OF CONTAINMENT INSTRUMENT AIR COMPRESSOR The Failure of Containment Instrument Air Compressor I malfunction was tested on 05/11/88. It was conducted from , the initial conditions of. steady state normal. full power. ! The duration of the test was 30 seconds. This time was long enough to verify that all expected actions did occur. Data was collected in the form.of computer printouts. This data consisted of model and plant variable points that -verified the expected results. There were no discrepancies noted . during the duration of the test. MCA02 i CONTAINMENT INSTRUMENT AIR LEAK l l The Containment Instrument Air Leak malfunction . was i tested on 05/11/88. It was conducted from the initial conditions of steady state normal full power. The malfunction was ramped over a 30 seconds time frame to demonstrate the degradation feature. The malfunction was degraded to its maximum severity. The duration of the test Os was 351 seconds. This time was long enough to verify that all expected actions did occur. -Data was collected in the form of computer printouts. This data consisted of model J and plant variable points that verified the expected j results. There were no discrepancies noted during the ! duration of the test. i MCA04 INSTRUMENT AIR LEAK The Instrument Air Leak malfunction was' tested on 05-11-88. It was conducted from the initial conditions of steady state normal full power. The malfunction was ramped over a 30 seconds time frame to demonstrate the degradation i' feature. The malfunction 'was degraded to its maximum severity. The duration of the test was 379 seconds. .This time was long enough to verify that all expected actions did occur. Data was collected in- the form of computer printouts. This data consisted ~of model and plant variable points that verified the expected results. There were no discrepancies noted during the duration of the test.- O
ATTACHMENT 3 - Page 30 of 85 (::) MCC02 Ij COMPONENT COOLING PUMP FAILS.TO START The Component Cooling Pump sta:rt failure malfunction was conducted on 12/06/87 at 100% power, steady state- i conditions. The running pump .was tripped due- to an: electrical fault. This called upon the standby pump to start. Various pump indications were monitored to confirm the expected response. The duraticn of .the test was ~ 40 l seconds. Data was collected in the form of computer printouts. This data consisted of model and plant . variable i points that verified the expected results. There were no l discrepancies noted during the test. MCC03 j COMPONENT COOLING TRANSMITTER FAILURE i The Component Cooling Transmitter Failure malfunction was conducted on 12/06/87 at 100% power, steady state i conditions. Each transmitter was tested in.the high and low j conditions. The malfunction was degraded to- its maximum j severity. Major indications were monitored for 50 seconds l l and the expected results were obtained and stable conditions
/
l existed. Data was collected in the . form of computer i printouts. This data consisted of model and plant variable ! points that verified the expected result. There were no I discrepancies noted during the test. i L I MCC04 ) 1 l COMPONENT COOLING DISCHARGE PRESSURE TRANSMITTER FAILURE
- The Component Cooling Discharge Pressure Transmitter l 1 Failure malfunction was conducted on 12/06/87 at 100% power.
The failure was tested in the-high and low directions.- The malfunction was ramped over a 30 seconds time frame to demonstrate the degradation feature. The malfunction 'was . degraded to its maximum severity. Various system parameters and indications were monitored for 50 seconds and' the expected results were obtained. Data was collected in the- 3 l form of computer printouts. This data consisted of model and plant variable points that verified the' expected. i results. There were no discrepancies noted during the test. l 4
ATTACHMENT.3 Page 31 of 85 O MCC05 RCP THERMAL BARRIER LEAK The RCP Thermal Barrier Leak malfunction was conducted-on 12/06/87 at 100% power, steady state conditions. Various system and pump parameters were monitored for 130 seconds and the expected results were obtained. Data was collected. in the form of computer printouts. This data consisted of model and plant variable points that verified _the expected results. This is a generic malfunction, therefore, each pump thermal barrier was tested. There were no discrepancies noted during the test. MCC06 COMPONENT COOLING PUMP SHAFT SHEARS l The Component Cooling Pump Shaft Shear malfunction was. conducted on 12/06/87 at 100%- power, steady state conditions. Various system and component indications were-monitored for 108 seconds and the expected results were obtained. Data was collected in- the form of computer printouts. This data consisted of model and plant variable , points that verified the expected result. This is a generic ! O malfunction, therefore, both pumps were tested. no discrepancies noted during the test. There were MCH01 i LETDOWN LEAK IN CONTAINMENT The Letdown Leak in the Containment malfunction was conducted on 11/01/87 at 100% power, steady state l conditions. The leak was ramped from zero. leakage to full 1' - leakage over a 30 seconds time frame to demonstrate the degradation feature. The malfunction was degraded to its maximum severity. Various parameters were monitored and recorded to show flows and mass balances of the CVCS system.. The test was run for 134 seconds until stable conditions existed. Data was collected. in the form. of computer printouts. This data consisted of model and plant variable points that verified the expected results. There were no discrepancies noted during the test. . j
7 ATTACHMENT 3 Page 32 of 85 (a MCH02 LETDOWN LEAK OUTSIDE CONTAINMENT The Letdown Leak Outside Containment malfunction- was conducted on 11/01/87 at full reactor power, steady state conditions. The' leak was ramped from zero leakage'to full leakage over a 30 seconds time frame to demonstrate the degradation feature. The malfunction was degraded to its maximum severity. Various plant parameters and indications were monitored and recorded that would show the expected flow and alarms. The test was run for 120 seconds until stable condition's existed. Data- was collected in the form of computer- printouts. This data consisted- of model and plant variable points that verified the expected results. ; There were no discrepancies during the test. . i MCH03 4 NORMAL CHARGING LEAK OUTSIDE CONTAINMENT The Normal Charging Leak Outside the Containment 3 malfunction was conducted on 11/01/87 at full reactor power ' and normal charging flow conditions. The leak was ramped from zero leakage to full leakage over a 30 seconds time frame to demonstrate the degradation -The O' feature. malfunction was degraded to its maximum severity. plant parameters and indications were monitored for 114 Various seconds until stable plant conditions existed. Data was collected in the form of computer printouts. This data consisted of. mode) and plant variable points that verified j the expected results. There were no discrepancies' noted ! during the test. MCH04 LETDOWN PRESSURE TRANSMITTER FAILURE The Letdown Pressure Transmitter Failure malfunction was conducted on 11/01/87 at full reactor power-with normal charging and letdown flows. 'The transmitter.was failed over a 30 seconds time frame to demonstrate the degradation feature. The malfunction was degraded to 'its maximum-severity. Various parameters and indication were- monitored for 82 seconds and the expected results were obtained. Test data was collected in the form of computer printouts.- This data consisted of model and plant variable points that-verified the expected results. There were no discrepancies noted during the test.
ATTACHMENT'3 Page 33 of 85 A L) MCH05 BLENDER BORATES IN NORMAL MAKE-UP This Blender Borates in Normal Make-up malfunction was conducted on 11/01/87 under normal, full power, steady state conditions. Various parameters ;and indications were monitored for. 46 seconds until the expected results- were obtained and.all affected systems became stabilized. . With the malfunction implemented,.the mass of the_VCT was reduced' to cause an automatic. makeup to occur. Data was 1 collected: in the form of computer printouts. This data consisted of: model and plant variable points that verified the expected j results. There were no discrepancies noted during the test. MCH06 LOSS OF CC.TO LETDOWN. HEAT EXCHANGER .; The Loss of Cooling to'the Letdown Heat Exchanger , malfunction was conducted on 11/01/87.at full power, with~ normal charging and letdown flows. Various parameters and , indications were monitored for 144 seconds to show the :) system response and to obtain the expected results. Data was collected in the form of computer printouts. This data (~ consisted of model and plant variable points.that verified (_T / the expected results. There were no discrepancies noted during the test. MCH07 CHARGING FLOW CONTROLLER FAILS IN AUTO ) The Charging Flow Controller- Failure' malfunction was l conducted on 11/01/87 at full steady state power. The
. malfunction was ramped over a 30 seconds time . frame to J demonstrate the degradation feature. The malfunction was ,
degraded to its maximum severity. Various plant parameters and indications were monitored for 1460 seconds to show the , expected response. Data was collected. until the expected : responses were verified and stable conditions were reached. Data was. collected until all affected systems became- , ! stabilized. There were no discrepancies noted during the. test.
-s v
ATTACHfENT 3 Pago 34 of 85 j
,. m \
MCH08 CHARGING FLOW TRANSMITTER FAILURE i The Charging Flow Transmitter Failure malfunction was I conducted on 11/01/87 at normal full power, steady state i conditions. It was ramped to fail over a 30 sect. ids time ! interval in both the high and low directions. The l malfunction was degraded to its maximum severity. Various j parameters, indications and alarms were monitored for 172 ; seconds until the expected results were obtained. Data was j collected in the form of computer printouts. This data 1 consisted of model and plant variable points that verified j the expected results. There were no discrepancies noted j during the performance of the test. MCH09 REACTOR MAKEUP DILUTION IN AUTO MODE i The Reactor Makeup Dilution in the Auto Mode i malfunction was conducted on 11/01/87 with the plant at j normal full power, steady state conditions. Specific ( variables were monitored for 76 seconds to verify that the correct flows and concentrations were added to the Reactor )
/N Coolant system to obtain the desired response from the i
(_) malfunction. Various valve positions vere monitored to ensure the flow line up was correct for the current malfunction. Data was collected in the form of computer printouts. This data consisted of model and plant variable points that verified the expected results. No discrepancies were noted during the test. MCH11 I BORIC ACID LINE TO THE BLENDER PLUGGED j l The Plugged Boric Acid Line malfunction was conducted l on 11/01/87 at normal operating conditions. A ramp feature i was used to demonstrate the variable degradation over time, I in this case 30 seconds. The malfunction was degraded to ) its maximum severity. Various model variables and plant j parameters and indication were monitored for 91 seconds to j verify the results of the test. Data was collected An the l form of computer printouts. This data consisted of 'model , and plant variable points that verified the expected j resuJts. No discrepancies were noted during the test. l l [
\
. _ - _ - _ -___A
ATTACHMENT 3 Page 35 of 85 Q MCH12 VCT LEVEL TRANSMITTER FAILURE' The VCT Level Transmitter Failure was conducted on 11/01/87 at normal full power conditions. A ramp feature of 30 seconds was used to demonstrate the degradation, feature. The malfunction was tested in both the high and low .
. directions. There are two redundant channels of level, l therefore both channels were tested. The malfunction was degraded to its maximum severity. Various parameters and indications were monitored for 65 seconds to verify the correct response. Data was collected in the form' of computer printouts. This data consisted of model and plant variable points that. - verified the expected results. No discrepancies were noted during the test.
MCH13 j TUBE RUPTURE IN THE NONREGENERATIVE HEAT EXCHANGER The Nonregenerative Heat Exchanger Tube Rupture malfunction was conducted on 11/01/87 at 100% power steady state conditions. It was ramped over a 30 seconds time I frame to demonstrate the degradation feature. The ) ( malfunction was degraded to its maximum severity. Various ! model variables and plant indications were monitored for 212 seconds to confirm the expected plant response. Data was collected in the form of computer printouts. This data consisted of model and plant variable points that verified the expected results. There were no discrepancies noted during the test. MCH15 LOSS OF REACTOR MAKEUP CONTROL The Loss of Reactor Makeup Control malfunction was conducted on 11/01/87 under normal operating ' conditions. Various plant parameters and indications were monitored for 200 seconds to ensure that the expected results were obtained. Data was collected in the form of computer printouts. This data consisted of model and plant variable points that verified the expected results. No discrepancies were noted during the test. O
ATTACHMENT 3 Page 36 of 85 MCH16 LOSS OF1 CHARGING PUMP The Loss of Charging Pump malfunction.was conducted on 11/01/87 during normal operation. The malfunction was implemented on the running pump. Various charging system variables and indications were monitored for 20 seconds to verify the expected results on the system.and overall plant. Data was collected in the form of computer printouts. This data consisted of model and plant variable points that' verified the expected results. No discrepancies were noted during the test. MCH18 LETDOWN PRESSURE CONTROL VALVE FAILS The Letdown Pressure Control Valve Failure malfunction was conducted on 11/01/87 at normal operating ' conditions. l The malfunction was. ramped over a 30 second time frame in both the high and low directions to demonstrate the degradation feature. The malfunction was degraded to its maximum severity. The major model and system parameters were monitored for 70 seconds to verify correct response of O the malf' unction. Data vac collected in the form of computer printouts. This data consisted of model and plant variable points that verdfied the expected results. There were no discrepancies noted during the test. MCH21 CHARGING PUMP CHECK VALVE STICKS OPEN The Charging Pump Check Valve malfunction was tested on 11/01/87 under normal operating conditions.. This generic malfunction tested all three discharge check valves. Specific variables and plant indications were monitored for 84 seconds to verify correct malfunction and plant response. Data was collected in the form of computer printouts. This data consisted- of model and plant variable points that verified the expected results. There were no discrepancies noted during the test. l l O
ATTACHMENT 3 Page.37 of 85 MCN01 LOSS OF CONDENSATE MAKEUP The Loss of Condensate Makeup malfunction was performed. on 08/01/87 during normal operating steady state conditions. Various models and parameters of the systems affected .were monitored for 1090 seconds to verify that the expected results were obtained. Data was collected in the form of computer printouts. This data consisted of model and plant variable points that verified the expected results. There were nd' discrepancies found during this test. MCN07 HOTWELL LEVEL CONTROL FAILS HIGH The Hotwell Level Control malfunction was conducted on 08/02/87 under normal operating full power conditions. The malfunction was implemented with the condensate system steady state. Specific -model variables and system parameters were monitored for 155 seconds to verify correct response. Data was collected in the form of computer' printouts. This data consisted of model and plant variable points that verified the expected results. There were no discrepancies noted during the test. MCN14 CONDENSATE PUMP DISCHARGE CHECK VALVE STICKS OPEN The Condensate Pump Discharge Check Valve . failure malfunction was conducted on 10/25/87 at full . power conditions. Each check valve was tested by implementing the malfunction then securing its respective condensate pump and verifying reverse flow. Specific system variables and , overall plcnt variables were monitored for 70 seconds to 1 insure proper response. Data was collected in the form of l computer printouts. This data consisted of model and plant ] variable points that verified the expected results. There were no discrepancies noted during the test'. 3
d i ATTACHMENT 3 Page 38 of 85- 1 1 ([]) MCN16 - i CONDENSER AIR IN-LEAKAGE - 1 The Condenser Air In-Leakage malfunction was conducted on 04/14/88 at normal full power conditions. It was. ramped over a 30 seconds time frame to. demonstrate the degradation feature. The malfunction was degraded to its maximum severity. Specific malfunction variables and plant system variables were monitored to verify proper response. The test was run for 93. seconds and the expected response .va s obtained. Data- was collected in the form of computer ! printouts. This data consisted of model and plant variable points that verified the expected results. There were no discrepancies noted during the test. MCV01 GRADUAL INCREASE IN CONTAINMENT PRESSURE The Increase In Containment Pressure malfunction was conducted on 04/14/88 under normal full power conditions. The malfunction was degraded to its maximum severity. Specific malfunction variables and containment parameters were monitored to verify correct response. The test was run O for 610 seconds until the expected responses.were obtained. Data was collected in the form of computer printouts. data consisted of model and plant variable points that This verified the expected results. There were no discrepancies noted during the test. MELO1 LOSS OF OFFSITE POWER The Loss of Offsite Power malfunction was conducted on 08/02/87 at full power steady state conditions. Data was collected at half second resolution on specific breaker variables. These variables were used to verify the correct response of the malfunction. The test was run for 45 seconds and the expected system responses were obtained. Data was collected in the-form of computer printouts.- This data consisted of model and plant variable points that verified the expected results. There were no discrepancies noted during this test. o
ATTACHMENT 3 Page 39 of 85 l MELO3 l LOSS OF 4160 EMERGENCY BUS The Loss of the 4160 _ Emergency Bus malfunction was conducted on 08/23/87 under' normal steady state conditions. Each emergency bus was tested. Specific breaker and bus variables were monitored for 45 seconds to insure the correct malfunction respqnse. Test data was collected at half second resolution until the expected response was obtained. Data was collected in the form of computer printouts. This data consisted of model and plant variable points tha verified the expected results. There were. no discrepancies noted during the test. HELO4 , LOSS OF 4160 STATION SERVICE BUS The Loss of the 4160 Station Service Bus malfunction was conducted on 08/23/87 at normal full power conditions. This generic malfunction tested each station service bus. Specific breaker and bus variables were monitored for ,15 l seconds to verify the correct response of the malfunction.
,, Data was collected in the form _of computer printouts. This t data consisted of model and-plant variable points _ that ]
\m} - verified the expected results. No discrepancies were noted '
during the test. MELOS LOSS OF 125V DC BUS The Loss of 125V DC Bus malfunction was conducted' on 08/23/87 under normal operating conditions. Each bus was i tested and it's respective load list was verified to ensure ' that all of the modeled loads were deenergized. Data was collected that verified the loss of bus voltage and the response of some selected indication. The duration of the , test was 15 seconds. Data was collected in the form of i computer printouts. This data consisted of model and plant variable points that verified the expected results. There 3 were no discrepancies noted during the test. I I I 1 ______ - _ - - 1
ATTACHMENT'3 Page 40 of 85 : 1 . (~~S O MELO6 LOSS OF 480V EMERGENCY BUS The Loss of the. 480V Emergency Bus malfunction was conducted on 08/23/87' under normal full power conditions. Each emergency bus was tested with it's respective loads verified to deenargize. Data was collected to verify that bus voltage was lost and some indications were monitored to 4 show the response of that bus. The duration of the test.was 15 seconds. Data was collected in the form of computer printouts. This data consisted of model and plant variable points that verified the expected results. There were no discrepancies noted during the test.- i i MELO7 j i LOSS OF 480V STATION SERVICE BUS The Loss of 480V Station Service Bus malfunction was j conducted on 08/23/87 under normal operationg conditions. ' Each bus was tested and their respective loads verified to ensure proper deenergization. Data was collected that .! monitored various voltages, flags, and indications to verify { proper response. . Data was collected in the form of computer 1 Q k)m printouts. The duration of the test was 15 seconds. were no discrepancies noted during the test. There ' MELO8 LOSS OF EMERGENCY DIESEL GENERATOR The Loss of Emergency Diesel Generator malfunction was conducted on 08/23/87 under normal full power conditions. A Safety Injection was given that started the Emergency Diesel. After a time delay the malfunction was implemented causing the diesel under testing to trip off., Data was collected with the varables to show the loss of the diesel and it's respective bus. Data was collected'in the form of 4 computer printouts. The duration of the test was 15 seconds. There were no decerepancies noted during the test. MEL11 MAIN GENERATOR TRIP The Main Generator- Trip malfunction was conduct-d on 08/23/87 .at normal full power- conditions. Data was collected to verify proper response, alarms and indict <. ions. The duration of the test was 15 seconds. Data was co;.lected in the form of computer printouts. This data consis*ed of' model and plant variable points that verified the expected-results. There were no discrepancies noted during the test.
ATTACHMENT 3 Pago 41 of.85 MEL12 LOSS OF SEMI-VITAL BUS The Loss of Semi-Vital Bus malfunction was conducted on 08/23/87 during normal full power conditions. Each bus was tested and verified that all loads were deenergized. Various bus parameters and indications were monitored for 15 seconds to ensure proper response. Data was collected in the form of computer printouts. This data consisted of model and plant variable points that verified the expected , results. There were no discrepancies noted during the test. j MEL13 LOSS OF VITAL BUS ! The loss of Vital Bus malfunction was performed on 08/23/87 under normal full power conditions. Each of the four buses were tested and all modeled loads check to ensure they were deenergized. The duration of the test was 5 seconds. Data was collected in the form of computer ( printouts. This data consisted of model and plant variable points that verified the expected results. There were no discrepancies identified during this test. A () MELIS LOSS OF 480V EMERGENCY BUS The Loss of 480V Emergency Bus malfunction was ! conducted on 08/23/87 at normal full power conditions. Each i emergency bus was tested and verified for the correct response. All loads were checked for proper response. The ' duration of the test was 10 minutes. Data was collected in the form of computer printouts. This data consisted of model and plant variable points that verified the expected results. There were no discrepancies noted during the test. MEL16 i LOSS OF 480V STATION SERVICE BUS The Loss of 480V Station Service Bus malfunction was conducted n 08/23/87 under normal operating conditions. Each of the 480V buses were tested. Various bus parameter were monitored to ensure proper bus response and all loads were checked to verify proper power supplies. The duration of the test was 10 seconds. Data was collected in the form of computer printouts. This data consisted of model and plant variable points that verified the expected results. There were no discrepancies noted during the test. (m
I l q ATTACHMENT 3 Page 42 of 85
. 1 MEL17 ,
R LOSS OF PRIMARY PROCESS RACK 1 The Loss of Primary . Process Rack malfunction wa s " , conducted on 08/23/87 at normal operating cinditions. Each of the process racks were tested. All loads from there l 4 respective buses were verified for correct response. .. The 4 duration of the test was 10 seconds. Data was collected in 'I the form of computer printouts. This data consisted of model and plant variable points that verified the expected results. There were no discrepancies noted during the test. H MFWD1 STEAM GENERATOR LEVEL TRANSMITTER FAILS The Steam Generator Level Transmitter Failure was conducted on 07/11/87 at normal full power conditions. Each l 1evel Transmitter was tested in the failed high and failed low conditions. Data was collected over the ramp over-a 30 sconds time frame to demonstrate the degradation feature of tne malfunction. The' malfunction was degraded to its maximum severity. Various parameters were monitored to- , verify correct malfunction. response. The duratien of the ' test was 300 seconds. Data was collected in the form of O computer printouts. This data consisted of model and plant variable points that verified the expected results. There were no discrepancies noted during the test. MFWO2 STEAM GENERATOR PRESSURE COMPENSATION FAILURE. The Steam Generator . Pressure Compensation Failure malfunction was conducted on 07/11/87 under normal operation conditions. Each level' channel was given a loss'of pressure compensation due to a loss of turbine- first stage compensation. Data was collected over the 30 seconds ramp time to demonstrate the degradation feature. The malfunction was degraded to its maximum severity. Various parameters and indications were monitored to ensure proper malfunction response. The duration of the test was 210 seconds. Data was- collected in the form of computer-printouts. .This data consisted of model and plant -variable points that verified the expected results. There were no discrepancies noted during the test.
l t-ATTACHMENT 3 Page 43 of 85 MFWO4 MAIN FEED PUMP LOW LUBE OIL PRESSURE The Main Feed Pump Low Lube 011 Pressure. malfunction was tested on 07/12/87. It was conducted from the initial conditions of- steady state normal full power. The malfunction was ramped. over a 30 seconds time frame to demonstrate the degradation feature. The malfunction was degraded to its maximum severity. The duration of-the test was.60 seconds. This time was long enough to verify that all expected actions did occur. Data was collected in the form of computer printouts. This data consisted of. model and plant variable. points that verified the expected results. There were no discrepancies noted during the ! duration of the test. I MFWOS MAIN FEEDWATER REGULATING VALVE FAILS CLOSED The Main Feedwater Regulating Valve Fails Closed malfunction was tested on 07/12/87. It was conducted from the initial conditions of steady state normal full power. The duration of the test was 60 seconds. This time was long enough to verify.that all expected actions did occur., Data was collected in the form of computer printouts. This data consisted of model and plant variable points that verified the expected results. There were no discrepancies noted I during the duration of the test. l MFWO6 TOTAL LOSS OF FEEDWATER ! The Total Loss of Feedwater malfunction was tested on 07/12/87. It was conducted from the initial conditions of steady state normal full power. The duration of the test was 123 seconds. This time was long enough to verify that all expected actions did occur. Data was collected in the form of computer printouts. This data consisted of model and plant variable points that verified- the expected results. There were no discrepancies' noted during the i duration of the test.- ~ O .
ATTACHMENT 3 Page 44 of 85 O MFWO8 LOSS OF LEVEL ERROR SIGNAL TO STEAM GENERATOR LEVEL CONTROL The Loss of Level Error Signal to Steam Generator Level Control malfunction was tested on 07/19/87. It was conducted from the initial conditions of steady state normal full power. The duration of the test was 800 seconds. This time was long enough to verify that all expected actions did occur. Data was collected in the form of computer printouts. This data consisted of model and plant variable points that verified the expected results. There were no discrepancies noted during the duration of the test. MFWO9 OVERSPEED TRIP OF AUXILIARY STEAM GENERATOR FEED PUMP The Overspeed Trip of Auxiliary Steam Generator Feed Pump malfunction was tested on 07/19/87. It was conducted from the initial conditions of steady state normal full power. The duration of the test was 60 seconds. This time , was long enough to verify that all expected actions did i occur. Data was collected in the form of computer G I printouts. This data consisted of model and plant variable ; points that verified the expected results. There were no 1 discrepancies noted during the duration of the test. MFW10 AUXILIARY FEED PUMP CHECK VALVE OPEN The Auxiliary Feed Pump Check Valve Open malfunction was tested on 07/26/87. It was conducted from the initial conditions of steady state normal full power. The malfunction was degraded to its maximum severity. TF-duration of the test was 240 seconds. This time was _ , l enough to verify that all expected actions did occur. Data 1 was collected in the form of computer printouts. This data consisted of model and plant variable points that verified the expected results. There were no discrepancies noted during the duration of the test. O
ATTACHMENT 3 Page 45 of 85 i rm
%s MFW11 1
AUXILIARY FEED PUMP IMPELLER DEGRADATION The Auxiliary Feed Pump Impeller Degradation l malfunction was tested on 07/24/87 It was conducted from l the initial conditions of steady state normal full power. I The malfunction was ramped over a 30 seconds time frame to demonstrate the degradation feature. The malfunction was degraded to its. maximum severity. The duration of the test was 70 seconds. This time was long enough to verify that all expected actions did occur. Data was collected in the form of computer printouts. This data consisted of model ) i and plant variable points that verified the expected results. There were no discrepancies noted during the duration of the test. MFW12 l MAIN FEED FLOW TRANSMITTER FAILURE ' The Main Feed Flow Transmitter Failure malfunction was tested on 07/24/87. It was conducted from the initial conditions of steady state normal full power. The malfunction was ramped cver a 30 seconds time frame to r'% demonstrate the degradation feature. The malfunction was ( ',) degraded to its maximum severity. The duration of the test was 126 seconds. This time was long enough to verify that all expected actions did occur. Data was collected in the form of computer printouts. This data consisted of model and plant variable points that verified the expected results. There were no discrepancies noted during the duration of the test. MFW13 MAIN FEEDWATER BREAK BETWEEN REG VALVE AND FLOW TRANSMITTER The Main Feedwater Break Between Reg Valve and Flow Transmitter malfunction was tested on 07/26/87. It was conducted from the initial conditions of steady state normal full power. The malfunction was ramped over a 30 seconds time frame to demonstrate the degradation feature. The malfunction was degraded to its maximum severity. The l duration of the test was 82 seconds. This time was long enough to verify that all expected actions did occur. Data
'was collected in the form of computer printouts. This data consisted of model and plant variable points that verified the expected results. There were no discrepancies noted during the duration of the test. /3
i l ATTACHMENT 3 l Page 46 of 85 ) MFW14 AUXILIARY FEEDWATER BREAK DOWNSTREAM OF FLOW TRANSMITTER AND CHECK VALVE The Auxiliary Feedwater Break Downstream of Flow i Transmitter snd Check Valve malfunction was tested on ! 07/26/87. It was conducted from the initial conditions of steady state normal full. power. The duration of the test was 175 seconds. This time was long enough to verify that all expected actions did occur. Data vas collected in the form of computer printouts. This data consisted of model and plant variable points that verified the expected results. There were no discrepancies noted- during the-duration of the test. MFW15 MAIN FEEDWATER BREAK DOWNSTREAM OF CHECK VALVE OUTSIDE CONTAINMENT The Main Feedwater Break Downstream of Check Valve Outside Containment malfunction was tested on 07/26/87. It was conducted from the initial conditions of steady state normal full power. The malfunction was ramped over a 30 / seconds. time frame to demonstrate the degradation feature.. (, The malfunction was degraded to its maximum severity. The duration of the test was 300. seconds. This. time'was long enough to verify that all expected actions did occur. Data was collected in the form of. computer printouts. This data consisted of model and plant variable points that verified the expected results. There were no discrepancies noted during the duration of the test. MFW16 MAIN FEEDWATER BREAK IN CONTAINMENT The Main Feedwater Break in Containment malfunction was tested on 07/26/87. It was conducted from the initial conditions of steady . state normal full power.- The malfunction was ramped over a 30 seconds tina frame to demonstrate the degradation feature. . The malfunction was-degraded to its maximum severity. The duration of the test was 227 seconds. This time was long enough to verify that all expected actions.did occur. Data was collected in. the-form of computer prantouts. This data consisted of model and plant variable points that- verified' the expected results. There were no discrepancies noted during the duration of the test. O
ATTACHMENT 3 Page 47 of 85 9 MFW17 DEGRADATION OF MAIN FEED PUMP The Degradation of Main Feed Pump malfunction was tested on 07/26/87. It was conducted from the initial conditions of steady state normal full power. The malfunction was ramped over a 30 seconds time frame to demonstrate the degradation feature. The malfunction was degraded to its maximum severity. The duration of the test was 106 seconds. This time was long enough to verify that all expected actions did occur. Data was collected in the form of computer printouts. This data consisted of model and plant variable points that verified the expected results. There were no discrepancies noted during the duration of the test. MFW18 MAIN FEEDWATER REGULATING VALVE FAILS OPEN The Main Feedwater Regulating Valve Fails Open malfunction was tested on 07/26/87. It was conducted from the initial conditions of steady state normal full power. The duration of the test was 230 seconds. This time was long enough to verify that all expected actions did occur. G Data was collected in the form of computer printouts. data consisted of model and plant variable points that This verified the expected results. There were no discrepancies noted during the duration of the test. MFW19 FEEDLINE BREAK BETWEEN FE AND CHECK VALVE The Feedline Break Between FE and Check Valve malfunction was tested on 11/03/87. It was conducted from the initial conditions of steady state normal full power. The malfunction was ramped over a 30 seconds time frame to demonstrate the degradation feature. The malfunction was degraded to its maximum severity. The duration of the test was 95 seconds. This time was long enough to verify that all expected actions did occur. Data was collected in the l form of computer printouts. This data consisted of model I and plant variable points that verified the expected results. There were no discrepancies noted during the duration of the test. O
ATiACHMENT 3~ Page 48 of 85 MFW21 MAIN FEEDWATER PUMP SUCTION BREAK The Main Feedwater Pump Suction Break malfunction was tested on 11/22/87. It was conducted from the initial conditions of steady state normal full power. The malfunction was ramped over a 30 seconds time frame to demonstrate the degradation feature. The malfunction was degraded to its maximum severity. The duration of the test was 118 seconds. This time was long enough to verify that all expected actions did occur. Data was collected in- the form of computer printouts. This data consisted of model and plant variable. points that verified the expected' results. There were no discrepancies noted during the duration of the test. MFW23 AUXILIARY FEED PUMPS TRIP ON OVERCURRENT The Auxiliary Feed Pumps Trip- on Overcurrent malfunction was tested on 11/03/87. It was conducted from the initial conditions of steady state normal full power. The duration of the test was 20 seconds. This time was long enough to verify that all expected actions did occur. Data O' was collected in the form of computer printouts. This data consisted of model and plant variable points that verified the expected results. There were no discrepancies during the duration of the test. noted MGWO1 - ACCIDSNTAL RELEASE OF RADIOACTIVE GAS The Accider.tal Release of Radioactive Gas malfunction was tested on 06/10/88. It was conducted from the initial conditions of steady state normal. full power. malfunction was ramped over a 30 seconds time frame The to demonstrate the degradation feature. The malfunction was degraded to its maximum severity. The duration of the test was 312 seconds. This time was long enough to verify -that all expected actions did occur. Data was collected in the form of computer- printouts. This data consisted of model and plant variable points that verified the results. There were no discrepancies noted during. the expected duration of the test. r~'h
ATTACHMENT 3 Page 49 of 85 , O MMS 01 STEAM GENERATOR STEAM FLOW TRANSMITTER FAILURE The Steam Generator Steam Flow Transmitter- malfunction power level was tested on 11/22/87 in the failed high and failed low directions. The test was conducted using Channel l III as the controlling channel and Channel IV as a 1 non-controlling channel. The intent of the test was to show results of a failed controlling channel. and of a failed I non-controlling channel. The failure was ramped over a 30 seconds. time interval and continued .until the expected results were obtained. The malfunction was degraded to. its maximum severity. Data was gathered at five second intervals. The duration of the test was 93 seconds. Data was collected in the form of computer printouts. This data consisted of model and plant variable points that verified the expected results. There were no discrepancies noted during this test. MMS 02 TURBINE FIRST STAGE PRESSURE TRANSMITTER FAILURE The Turbine First Stage Pressure . Transmitter (g r-j malfunction power level was tested on 11/22/87 in the failed high and failed low directions. The test was conducted l using Channel III as the controlling channel and Channel IV as the non-controlling channel.' The intent of the test was to show results of a failed controlling channel and non-controlling channel. The failure was ramped over a 30 l seconds time interval. The malfunction was degraded to' its maximum severity. Data was gathered at five second .) intervnis. The duration of the test was 80 seconds. . Data ( was collected in the form of computer printouts. This' data l consisted of model and plant variable points that verified ' the expected results. There were no discrepancies noted i during the test. l l 9 I
ATTACHMENT 3 Page 50 of 85-O MMS 08 RUPTURE OF MAIN STEAM LINE IN CONTAINMENT BEFORE THE FLOW TRANSMITTER The Rupture of' Main Steam Line in Containment Before the Flow Transmitter malfunction was tested on 11/22/87.- It was conducted.from the initial conditions of steady state normal full power. The malfunction was ramped over a 30 seconds time frame to demonstrate the degradation feature.- The malfunction.was degraded to its maximum severity. The duration of the test was 125 seconds. This time was long enough to verify that all expected actions did occur. Data was collected in the form of computer printouts. This data. consisted of model and plant variable points that verified the expected results. There were no discrepancies noted during the duration of the test. MMSO9 RUPTURE OF MAIN STEAM LINE AFTER THE NON-RETURN VALVE The Rupture of Main Steam Line After-the Non-return Valve malfunction was tested on 11/22/87. It was ' conducted from the initial conditions of steady state normal full power. The malfunction was ramped over a 30 seconds time (_, ts/ frame to de'onstrate m the degradation feature. The malfunction was degraded to. Its maximum severity. .The q duration of the test was 115 seconds. This time was long : enough to verify that all expected actions did occur. Data-was collected in the form of computer printouts. -{ This data consisted of model and plant variable points that- verified the expected results. There were no discrepancies noted during the duration of the test. l MMS 10 ; RUPTURE OF MAIN STEAM LINE BEFORE THE TRIP VALVE The Rupture of Main Steam Line Before the Trip- Valve ! malfunction was' tested on 11/22/87. It was conducted from j the initial conditions of steady state. normal full power. 1 The malfunction wac ramped over a 30 seconds time frame 'to ! demonstrate the degradation feature. The malfunction was-degraded to its maximum severity. The duration of the test was 120 seconds. This time was long enough to verify that-all expected actions'did occur. Data was collected in the ; form of computer printouts. This data consisted of model and plant variable points that- verified the. expected results. There. were no discrepancies .noted during the duration of the test. [
ATTACHMENT 3 Page 51 of 85 O MMS 11 FAILURE OF STEAM DUMP CONTROL AS IS The Failure of Steam Dump Control As Is malfunction was tested on 11/22/87. It was conducted from the initial conditions of steady state normal full power. The duration of the test was 170 seconds. This time was long enough to verify that all expected actions did occur. Data was collected in the form of computer printouts. This data consisted of model and plant variable points that verified the expected results. There were no discrepancies noted during the duration of the test. MMS 12 ATMOSPHERIC STEAM RELIEF VALVE STUCK OPEN The Atmospheric Steam Relief Valve Stuck Open malfunction was tested on 12/18/87. It was conducted from the initial conditions of steady state normal full power. The malfunction was ramped over a 30 seconds time frame to demonstrate the degradation feature. The malfunction was degraded to its maximum severity. The duration of the test was 556 seconds. This time was long enough to verify that 9 all expected actions did occur. Data was collected in the form of computer printouts. This data consisted of model and plant variable points that verified the expected results. There were no discrepancies noted during the duration of the test. MMS 13 MAIN STEAM TRIP VALVE FAILS AS IS The Main Steam Trip Valve Fails AS Is malfunction was tested on 05/20/87. It was conducted from the initial conditions of steady state normal full power. The duration of the test was 30 seconds. This time was long enough to verify that all expected actions did occur. Data was collected in the form of computer printouts. This. data consisted of model and plant variable points that verified the expected results. There were no discrepancies noted during the duration of the test. i
l 1 ATTACHMENT 3 ) Page 52 of-85 C\ V MMS 14 MAIN STEAM SAFETY VALVE STUCK OPEN The Main Steam Safety Valve Stuck.Open malfunction was .j tested on 05/20/87. It was conducted from the initial '4 conditions of steady. state normal full power. The ' malfunction was ramped over a 30 seconds time frame to demonstrate the degradation feature. .The malfunction was' degraded to its maximum severity. The duration of the test 4 j was 145 seconds. This time was long enough to verify that i all expected actions did occur. Data was collected in the form of computer printouts. This data consisted of .model and plant variable points that verified. the- expected results. There were no discrepancies noted during the duration of the test. MMS 15 l STEAM DUMP VALVE STUCK OPEN The Steam Dump Valve Stuck Open malfunction was tested 4 on 05/20/87. It was conducted from the initial conditions 1 of steady state normal full power. The' duration of the test was 169 seconds. This time was.long enough to. verify that all expected actions did occur. i Data was collected form of computer printouts. This data consisted of model in .the and plant . variable points that verified the expected. ' results. There were no discrepancies noted during the duration of the test. MMS 16 FAILURE OF STEAM HEADER PRESSURE CONTROL (0-1004) l The Failure of Steam Headel Pressure Control (0-100%) malfunction was tested on 05/20/87. It was conducted from the initial conditions of steady state normal full power. The malfunction was ramped over a 30 seconds time frame to demonstrate the degradation feature. The malfunction was 1 degraded to its maximum severity. The duration of the test was 94 seconds. This time was long. enough to verify that-all expected actions did occur. Data was collected in the form of computer printouts. This data consisted of model and plant variable points that verified the expected results. There were no discrepancies noted during the i j duration of the test. l
/ .
N.,/
, l 1
1 1
ATTACHMENT 3 Page 53'of 85 m MNIO1 POWER RANGE UPPER DETECTOR FAILURE The Power Range Upper Detector Failure malfunction was tested on 11/17/87. It was conducted from the initial conditions of steady. state normal full power. The malfunction was ramped over a 30 seconds time frame to demonstrate the degradation feature. The malfunction was degraded to its maximum severity. The duration of the- test was 47 seconds. This time was long enough to verify that all. expected actions dio occur. Data was coll 9cted in the form of computer printouts. This data . consisted of model and plant variable. points that. verified the expected results. There were no discrepancies noted during the duration of the test. MNIO2 POWER RANGE LOWER DETECTOR FAILURE The Power Range Lower Detector Failure malfunction was tested on 11/17/87. _It was conducted from the initial conditions of steady state normal. full power. The malfunction was ramped over a 30 seconds time frame to r% demonstrate the degradation feature. The ma* function was (' degraded to its maximum severity. The duration of the test was 46 seconds. This time was long enough to verify that all expected actions did occur. Data was collected in the form of computer printouts. This data consisted of model and plant variable points -that verified the expected results. There were no discrepancies noted during the duration of the test. MNIO3 BLOWN POWER RANGE CONTROL FUSE The Blown Power Range Control Fuse malfunction was tested on '11/17/87. It was conducted from the initial conditions of steady state normal full power. The duration of the test was 20 seconds. This time was long enough to verify that all expected actions did occur. Data was collected in the form of computer printouts. This data consisted of model and plant variable points that verified the expected results. There were-no discrepancies noted during the duration of the test. v
s- . On .y
. ATTACHMENT 3!
'Page 54 of 85 p
MNIO4 BLOWN. POWER RANGE. INSTRUMENT FUSE i
. . The Blown Power Range Instrument. Fuse malfunction; was i tested on 11/17/87. It was conducted from' the' initial conditions of. steady state. normal full power.- .The -duration l of the test.was 15 seconds. This time vas long enough. to.
verify that all expected actions. did occur. Data'. was collected'in tho' form of computer printouts.- .This- data 3 consisted of modellandt plant variable points'that verified ' the expected results. There. were no discrepancies noted during.the duration of the test. -
~{
MNIO6 s; SOURCE RANGE DETECTOR FAILURE-(DISCRIMINATOR ERROR) The Source Range Detector. Failure (Discriminator' Error) I malfunction was tested on- 05/11/87. It.was conducted from. the initial conditions. of steady state normal full;' power.. The malfunction was degraded; to its maximum severity.- The duration-of the test was 100 seconds. This time was 'long enough to verify that,all expected actions did. occur.. Dataj was collected inLthe form of computer printouts. . This data
/~T consisted of-model and plant _ variable points'that- verified ~ . the expected .results. There- were no discrepancies noted during the duration of the test.
MNIO8 INTERMEDIATE RANGE IMPROPERLY COMPENSATED The Intermediate Range Improperly. . Compensated malfunction was tested on 11/17/87. It was conducted from the initial conditions of steady state- normal full- power. j The malfunction was ramped over a 30 seconds time frame to demonstrate the. degradation feature. The malfunction .was degraded to.its maximum severity. The duration of the test was 445 seconds. This time twas long enough to. verify that q all expected actions did occur. ' Data was collected in the 1 form of computer printouts. This data' consisted of. model. j and. plant variable' points that verified the expected. R results. 'There were no discrepancies noted..during- the-duration:of the test. 1
-'l' I i
O - c l
l ATTACHMENT 3 l Page 55'of 85 ) MNIO9 INTERMEDIATE RANGE DETECTOR FAILURE ] The Intermediate Range Detector Failure malfunction was tested on 11/22/87. It was conducted from the initial I conditions of steady state normal full power. The malfunction was ramped over a 30 seconds-time frame to - demonstrate the degradation feature. The malfunction was ! degraded to its maximum severity. The duration of the test i was 164 seconds.' This time was long enough to verify that all expected actions did occur. Data was collected in the ] form of computer printouts. This data consisted of model and plant variable points that verified the expected results. There were no discrepancies noted during the duration of the test. MNII0 SOURCE RANGE CHANNEL FAILURE The Source Range Channel Failure malfunction was tested on 11/22/87. It was conducted from the initial conditions of steady state normal full power. The malfunction was { ramped over a 30 seconds time frame to demonstrate the ' degradation feature. The malfunction was degraded to its ; (--)
\-
maximum severity. The duration of the test was 100 seconds. This time was long enough to verify that all expected actions did occur. Data was collected in the form of computer printouts. This data consisted of model and plant variable points that verified the expected results. There were no discrepancies noted during the duration of the test. i MNI13 POWER RANGE CHANNEL FAILURE The Power Range Channel Failure malfunction was tested on 05/20/88. It was conducted.from the initial conditions of steady state normal full power. The duration of the test was 15 seconds. .This time was long enough to verify that all expected actions did occur. Data was collected in the form of computer printouts. .This data consisted of model and plant variable points that verified the expected results. There were no discrepancies noted during the duration of the test. I \ (_.
ATTACHMENT 3 Paga 56 of 85 MQS01 LOSS OF' QUENCH SPRAY PUMP The Loss of Quench Spray Pump malfunction was tested on 12/10/87. It was conducted from the initial conditions of steady state normal full power. The duration of the test was 45 seconds. This time was long enough to verify that all expected actions did occur. Data was collected in the form of computer printouts. This data consisted of model and plant variable points that verified the expected results. There were no discrepancies noted .during the duration of the test. MQS03 FAILURE OF CONTAINMENT HIGH PRESSURE TO INITIATE SPRAY The Failure of Containment Hi Pressure to Initiate Spray malfunction was tested on 12/gh10/87. It was conducted from the initial conditions of- steady state normal full power. The duration of the test was 50 seconds. This time was long enough to verify that all expected actions did occur. Data was collected in the form of computer fs printouts. This data consisted of model and plant variable e points that verified the expected results. There were no discrepancies noted during the duration of the test. MQS06 l SPURIOUS CONTAINMENT SPRAY ACTUATION The Spurious Containment Spray Actuation malfunction was tested on 12/10/87. It was conducted from the initial conditions of steady state normal full power. The duration of the test was 271 seconds. This time was long enough to verify that all expected actions did -occur. Data was collected in the form of computer printouts. This data consisted of model and plant variable points that verified the expected results. There were no discrepancies noted during the duration of the test. O 9
ATTACHMENT 3 Page 57.of 85-MRC01 RCS COLD LEG PIPE RUPTURE The Reactor Coolant System Cold Leg Pipe Rupture Malfunction test was on 08/30/87 implemented at 100% reactor power and tested on each of the three reactor loops. Major RCS and containment parameters were monitored along with injection flows, major alarms, and- various meter indications. .The duration of the test was 113 seconds. This time was long enough to verify safety systems were actuated and containment pressure decreased from.its peak pressure. Data. was collected in the form of computer printouts. This data consisted of model and plant variable points that verified the expected results. There were no discrepancies noted during the test. MRC02 RCS HOT LEG PIPE RUPTURE The Reactor Coolant System Hot Leg Pipe Rupture Malfunction test was implemented on 08/30/87 at 100% reactor power and tested on each of the three reactor. loops. . Major RCS and Containment parameters were monitored along- with injection flows, mojor -alarms, and. Various meter O. - indications. The duration of the test was 96 seconds. This time was long enough to verify safety systems.to actuated and containment pressure decreased from its. peak pressure. Data was collected in the form of computer printouts. This data consisted of model and plant variable points that verified the expected results.- There were no discrepancies noted during the test. MRC03 RCS SUCTION LEG PIPE RUPTURE The Reactor Coolant System Suction Leg Pipe Rupture Malfunction test was implemented on 08/30/87 at 100% reactor power and tested on each of the three reactor loops. Major RCS and Containment Parameters were monitored along with injection flows, major alarms-, and various meter indications. 'The duration of the test was 92 seconds. time was long enough to verify safety systems' actuated This and containment pressure decreased from peak pressure. Data was collected in the form of computer printouts. .This- data consisted of model and plant variable points that verified the expected results. There were no discrepancies noted during the test. O
\- / ,
j ATTACHMENT 3 j Page 58 of 85 ; 1 4
/~
k _}s s MRC04 RCS PRESSURE BOUNDARY The Reactor Coolant System Pressure Boundary Leak Malfunction test was . performed on 08/30/87 at 100% power. - The malfunction was ramped over a 30 seconds t1me frame 'to demonstrate the degradation feature. The leak was degraded i from zero leakage to a 600 gpm leak over a 30 seconds time-period. Major containment-and reactor coolant parameters were monitored along with various alarms and indications. Data'was collected at five second intervals until safeguard features actuated and stablized. The duration of the- test was 263 seconds. Data was collected in the form of computer printouts. This data consisted of model'and plant variable points that verified the expected results. No discrepancies were noted during the performance of this test. MRC05 REACTOR COOLANT PUMP OVERCURRENT TRIP The Reactor Coolant Pump Overcurrent Trip Malfunction test was conducted on 08/30/87 at 100% reactor power. Each of the three coolant pumps was tested while monitoring major ("' primary and secondary parameters along.with.various alarms 5 and meter indications. Data was collected until RCS flows and temperatures stablized. . The duration of the' test was 38 seconds. Data was collected in the form of computer printouts. This data consisted of model and plant variable points that verified the expected results. No discrepancies were noted during the test. MRC07
, PRESSURIZER PRESSURE TRANSMITTER FAILURE The Pressurizer Pressure Transmitter Failure Malfunction test was performed on 08/30/87 at 100% reactor power. The malfunction was ramped over a 30 seconds time frame to demonstrate the degradation feature. The malfunction was degraded to its maximum severity. Each of the five pressurizer pressure transmitters were tested in i the failed High and failed Low condition. Major pressurizer parameters were monitored along with control features. and respective meter indication. The duration of the test was 520 seconds and stable plant conditions were reached. Data was collected in the form of computer printouts. This data consisted of model and plant variable points that verified the expected results. No discrepancies were found during the test. /~'i V
ATTACHMENT ~3 Page 59 of 85 O MRC08 PRESSURIZER LEVEL TRANSMITTER FAILURE The Pressurizer Level Transmitter Failure Malfunction test was conducted on 08/30/87 at 100% reactor power. Each of the four level transmitters were. failed in the High and Low condition. The malfunction was degraded to its maximum severity. Data was collected until the expected response was obtained or stable plant conditions existed. Major pressurizer parameters were monitored along with various alarms and controlling features. The duration of the test was 97 seconds. Data was collected in the form of computer l printouts. This data consisted of model and plant variable points that verified the expected results. No discrepancies: were noted during the test. MRC11 RCP FLOW TRANSMITTER FAILURE The Reactor Coolant Flow Transmitter Failure Malfunction test was conducted on 08/30/87 at 100% reactor power. The malfunction was ramped over a 30 seconds time frame to demonstrate the degradation feature. The malfunction was degraded to its maximum severity. Each of i O the nine transmitters was tested in the' failed High and failed Low direction. The respective meter and alarms for each transmitter were monitored until the full failed condition was reached. Data was collected in the' form -of computer printouts. This data consisted of model and' plant variable points.that verified the expected results. There were no discrepancies noted during the test. MRC14 FAILURE OF RCP NUMBER 3 SEAL l The Reactor Coolant Pump Number Three Seal Failure Malfunction test was conducted on 09/12/87-at 100% reactor power. The malfunction was ramped over a 30 seconds time frame to demonstrate the degradation feature. The malfunction was degraded to its maximum severity. .Each reactor coolant pump was tested monitoring it respective standpipe alarm, along with major containment parameters. The duration of the test was 147 seconds. Data was collected in the form of computer printouts. This data consisted of model and plant variable points that verified the expected results. No discrepancies were noted during-the test. O
q
. ATTACHMENT'3 l
1 Page 60 of 85 j
.O
.V MRC15 !
l RCS. COLD LEG RTD (CONTROL) FAILURE i The RCS Cold Leg RTD Failure Malfunction was tested on 'l 09/12/87at 100% reactor power.' Each of the thre9 . reactor ) loops control RTO were tested in the High and Low directions. .The failure was ramped over.a 30' seconds time , frame .to demonstrate ~the degradation feature. The j malfunction was , degraded to its maximum severity. Various j temperature indications and alarms were: monitored along.with major control parameters. Data.was collected until expected results were obtained. The' duration of the test . wa s' 55 i seconds. Data was collected in the form of computer l printouts. This data consisted of model and plant ' variable l points that verified the expected results. There were no ! discrepancies noted during the test. 1 MRC'17 I RCS HOT LEG RTD (PROTECTION) FAILURE The RCS Hot Leg RTD Failure Malfunction test was conducted on 09/12/87 at 100% reactor power. Each of the three reactor ' loops : protection RTDS were tested in the failed High and failed Low- directions. The.' failure was
,O ramped over a 30 seconds time frame to demonstrate the degradation feature. The malfunction was degraded to its l
i maximum severity. The failed . channel's respective temperature indicators were monitored' along with their associated alarms. . Data was collected until the expected ; results were obtained.. The duration of the test- was 60 seconds. Data was collected in the form of computer I printouts. This data consisted of model and plant variable l points that verified the expected results'. There-were no discrepancies noted during the test. MRC18 RCS COLD LEG RTD (PROTECTION) FAILURE The RCS Cold Leg RTD Failure Malfuntion test ~was conducted on 09/12/87 at 100% reactor power. Each of the three reactor loops Protection RTDS were tested. in the failed High and failed Low directions. The failure was ramped over a 30 seconds time frame to demonstrate the degradation feature.- The malfunction was degraded to; its maximum severity. The failed channel's respective temperature indicators were monitored. along with'their ' associated alarms. . Data was collected until the expected results were obtained. The duration of the test was 60 i ! seconds. Data wa s - collected. in the- form of computer ! printouts. This data consisted.of model and plant . variable (- points that verified .the expected results. There were no discrepancies noted during the test. 1
ATTACHMENT 3 Page 61 of 85 [
\ '
MRC19 PRESSURIZER RELIEF VALVE STUCK OPEN The Pressurizer Relief Valve Stuck Open Malfunction ; Each test was conducted on 09/14/87 at 100% reactor power. relief valve was tested. Various reactor coolant system. parameters and component parameters were monitored along with major alarms. Data was collected until a safety injection actuated and flows stablized. The duration of the test was 96 seconds. Data was collected in the form of computer printouts. This data consisted of model and plant variable points that verified the expected results. No discrepancies were noted during the test. , I MRC20 PRESSURIZER SPRAY VALVE STUCK OPEN The Pressurizer Spray Valve Stuck Open Malfunction test was conducted on 09/14/87 at 100% reactor power. Each ; spray valve was tested. Major parameters were monitored i along with RCS control features. Data was collected until a reactor trip and safety injection occurs. The duration of the test was 196 seconds. Data was collected in the form of g computer printouts. This data consisted of model and plant ; i < variable points that verified the expected results. There 1
\- / were no discrepancies noted during this test.
MRC21 PRESSURIZER SAFETY VALVE STUCK OPEN The Pressurizer Safety Valve Stuck Open malfunction was tested on 09/17/87. It was conducted from the initial conditions of steady state normal full power. The malfunction was ramped over a 30 seconds time frame to demonstrate the degradation feature. The malfunction was degraded to its maximum severity. The duration of the test was 100 seconds. This time was long enough to verify that all expected actions did occur. Data was collected in the form of computer printouts. This data consisted of model and plant variable points that verified the expected results. There were no discrepancies noted during the duration of the test. D.
) %,/
~ ATTACHMENTS 3?
Page 62 of 85 O
\"'
MRC22 PRESSURIZER HEATERS FAIL ON (H BUS) The Pressurizer Heaters Fail On.(H Bus) malfunction was tested on 09/14/87. It was conducted from' the . initial conditions of steady state . normal f ull; power. The duration of-the test was:308-. seconds. This. time,was long enough to
~ verify that .all expected _ actions;:did occur. Data was collected in the' form- of computer printouts. This data-consisted of model'and- plant variable points that verified the expected- results. -There .were nci discrepancies noted-during the duration of the. test.
MRC23 J BUS PRESSURIZER HEATERS FAIL ON The J Bus Pressurizer Heaters Fail On malfunction was tested on' 09/14/87. It. was conducted from the initial conditions of steady-stateLnormal full power. The: duration: of-the test was 388 seconds. This time was long enough Hto verify that all -expected.. actions did occur. ~ Data;'was collected in the form of. computer: printouts. This dataf consisted of model and plant' variable points that verified. p) ( the expected results. There were'no ; discrepancies during the duration of the test. noted-MRC24
-STEAM GENERATOR TUBE RUPTURE The Steam Generator Tube Rupture malfunction was' tested on 09/14/87. It was conducted from the initial conditions of steady state normal full .: power. The -malfunction: was ramped over. a 30. seconds ' time frame to demonstrate- the degradation feature. The malfunction'was degraded to.'its maximum severity. The duration of the test wasf145 seconds.
This time was long 'enough to verify. that all expected actions did occur. Data was collected- in the' form of computer printouts. This data consisted of modeliandt plant: variable points that verified the expected results... There were no discrepancies noted during the. duration of the test. [}
' ATTACHMENT 3 Paga 63 of-85 O- MRC25 BOTH PRESSURIZER SPRAY VALVES FAIL CLOSED The Both Pressurizer Spray Valves Fail Closed malfunction was tested on 09/14/87. It_was conducted from the initial conditions of steady state normal full power.
The duration of the test was 508 seconds. This time was long enough to verify that all expected actions did occur. Data was collected in'the form of computer printouts. This data consisted of model and plant variable points that verified the expected results. There were no dicerepancies noted during the duration of the test. MRC26 l RCP SHEARED SHAFT The RCP Sheared Shaft malfunction was- tested on 09/14/87. It was conducted from the initial conditions of steady state normal full power. The duration of the ' test i was 33 seconds. This time was long enough to verify that l all expected actions did occur. Data was collected in the form of computer printouts. This data consisted of model and plant variable points that verified the expected results. There were no discrepancies noted during the O duration of the test. MRC29 PRESSURIZER PRESSURE CONTROL FAILS The Pressurizer Pressure Control Fails malfunction was tested on 04/14/88. It was conducted .from the initial conditions of steady state normal full power. The malfunction was ramped over a 30 seconds time frame to' demonstrate the degradation feature. The malfunction was i l degraded to its maximum severity. The duration of the test l was 137 seconds. This time was long enough to verify that 1 d11 expected actions did occur. Data was collected in the 'l form of computer printouts. This data consisted of model and plant variable points that verified the expected results. There were no discrepancies noted during the duration of the test. . I i
ATTACHMENT 3
.Page 64 of 85 O MRC31 FUEL LEAK The Fuel Leak malfunction was tested on 06/01/88. It was conducted from the initial conditions of steady state normal full power. The malfunction was ramped over a 30 seconds time frame to demonstrate the degradation feature.
The malfunction was. degraded to its maximum severity. The
' duration of the test was 338 seconds. This time was long enough to verify that all expected. actions did occur. Data was collected in the form of computer printouts. This data consisted of.model and plant variable points that verified the expected results. .There were-no discrepancies noted during the duration of the test.
MRC32 PCV-456 SEAT LEAKAGE The PCV-456 Seat Leakage malfunction was tested on 11/01/87. It was conducted from the initial conditions of steady state normal full power. The malfunction was ramped over a 30 seconds time frame to demonstrate the degradation feature. The malfunction was degraded to its -maximum severity. The duration of the test was 180 seconds. O time was long enough to verify that.all expected actions did-occur. Data was collected in the form. of computer This printouts. This data consisted of model and plant variable points that verified the expected results. 'There were no discrepancies noted during the duration of the test. MRC33 PT-402. WIDE RANGE PRESSURE TRANSMITTER FAILURE The PT-402 Wide Range Pressure Transmitter Failure malfunction was tested on 11/01/87. It was conducted from the initial conditions of steady state normal full power. The malfunction was ramped over a 30 seconds time frame to demonstrate the degradation feature. The malfunction was degraded to its maximum severity. The duration of the test was 35 seconds. This time was-long enough to verify that all expected actions did occur. . Data was collected in..the I i form of computer printouts. This data consisted of model j and plant variable points that verified the' expected i results. There were no discrepancies noted during . the . - duration of the test. H l I
.- _ _ a
ATTACHMENT.3 Page 65 of 85 MRC34 PT-403 WIDE RANGE PRESSURE TRANSMITTER FAILURE The PT-403 Wide Range Pressure Transmitter Failure malfunction was tested on 11/01/87. It was conducted from the initial conditions of steady state normal full power. The malfunction was ramped over a 30 seconds time frame to demonstrate the degradation feature. The malfunction was degraded to its, maximum severity. The duration of the test was 42 seconds. This time was long enough to verify that all expected actions did occur. Data was collected in the form of computer printouts. This data consisted of model and plant variable points that verified the expected results. There were no discrepancies noted during the duration of the test. MRC35 l PRT LEVEL TRANSMITTER FAILURE The PRT Level Transmitter Fa12ure malfunction was a tested on 11/01/87. It was conducted from the initial conditions of steady state normal full power. { The malfunction was ramped over a 30 seconds'timeL frame to ! demonstrate the degradation feature. The malfunction -was degraded to its maximum severity. The duration of the test was 40 seconds. This time was long enough to verify that all expected actions did occur. Data was collected in the form of computer printouts. This data consisted of model i' i and plant variable points that verified -the expected results. There were no discrepancies noted during the duration of the test. MRC36 PRT PRESSURE TRANSMITTER FAILURE The PRT Pressure Transmitter Failure malfunction was i tested on 11/01/87. It was conducted from the initial i conditions of steady state normal full power. The malfunction was ramped over a 30 seconds time' frame to demonstrate the degradation feature. The malfunction was degraded to its maximum severity. The duration of.the test was 37 seconds. This time was long enough to verify that all expected actions did occur. Data was collected in the form of computer printouts. This data consisted of model and plant variable points that verified the expected results. There were no discrepancies noted during the l duration of the test. l r i
l l ATTACHMENT 3 Page 66 of 85 MRC37 RCS VESSEL FLANGE LEAK TEMPERATURE DETECTOR FAILURE The RCS Vessel Flange Leak Temperature Detector Failure l malfunction was tested on 11/01/87. It was conducted from the initial conditions of steady state normal full power. I The malfunction was ramped over a 30 seconds time frame to demonstrate the degradation feature. The malfunction was
. deg raded to its maximum severity. The duration of the test was 40 seconds. This time was long enough to verify that all expected actions did occur. Data was collected in the form of computer printouts. This data consisted of model and plant variable points that verified the expected results. There were no discrepancies noted during the duration of the test.
MP.C38 LOSS OF COMPONENT COOLING WATER TO RCP The Loss of Component Cooling Water to RCP malfunction was tested on 06/07/88. It was conducted from the initial conditions of steady state normal full power. The malfunction was ramped over a 30 seconds time frame to 73 demonstrate the degradation feature. The malfunction was K/ I degraded to its maximum severity. The duration of the test was 311 seconds. This time was long enough to verify that all expected actions did occur. Data was collected in the j form of computer printouts. This data consisted of model 1 and plant variable points that verified the expected results. There were no discrepancies noted during the { duration of the test. ' MRC40 ! PRZ SURGE LINE TEMPERATURE TRANSMITTER FAILURE The PZR Surge Line Temperature Transmitter Failure malfunction was tested on 11/01/87. It was conducted from ! 1 the initial conditions of steady state normal full power. . ! The malfunction was ramped over a 30 seconds time frame to demonstrate the degradation feature. The malfunction was degraded to its maximum severity. The duration of the test was 40 seconds. This time was long enough to verify that all expected actions did occur. Data was collected in the form of computer printouts. This data consisted of model and plant variable points that verified the expected ; results. There were no discrepancies noted during the duration of the test.
' .,Y
]
. ATTACHMENT Page.67 of 85 MRC41 RCS SPRAY LINE TEMPERATURE TRANSMITTER FAILURE ;
W The RCS Spray LineL Temperature Transmitter Failure malfunction was tested on 11/01/87. It wasl conducted from , the initial conditions .of steady state normal full power. ' The malfunction was. ramped overi a 30. seconds time frame' to demonstrate the. degradation. feature.- The malfunction .was degraded to its maximum severity. . LThe duration of the ' test was_40: seconds. This time was long__-enough to verify.-that all expected actions did occur. _ Data was collected in' the form of computer printouts. _This data' consisted of model and plant variable- points' that.Lverified- the- ' expected-results. There were no ' discrepancies .noted. during: the
- ~
duration of the test. MRC42 PRESSURIZER LIQUID / VAPOR TEMPERATURE TRANSMITTER FAILURE The Pressurizer Liquid / Vapor Temperature Transmitter Failure malfunction was tested on 11/01/87. . It ;was conducted from the. initial conditions ofl steady state normal-full power. The malfunction was ramped over a.30 seconds L time frame to demonstrate the degradation feature.; The '-g malfunction was degraded to .its maximum severity.. The duration of the test was 40 seconds.1 This time was -long enough to verify that all expected actions did occur. Data l was collected in the form of computer printouts. This data l consisted of model and -plant variable points that verified-the expected results. There were no discrepancies noted during the duration of the test. l MRC43
* }n PRESSURIZER PORV LINE TEMPERATURE TRANSMITTER FAILURE f
' The Pressurizer PORV. Line Temperature' Transmitter Failure. malfunction was tested- on 11/01/87. - -It was-l conducted from the initia1Lconditions of steady state normal-i full power. The malfunction was ramped over a'30 . seconds time frame to demonstrate the degradation feature.- The j malfunction was degraded to its maximum severity. The i duration of the test was 40 seconds. This ' time was long i enough to verify that all expected actions did occur. ' Data l was collected in the= form of computer printouts. This : data a consisted of model and plant variable points that verified the expected results. There vere no discrepancies noted-during the duration of the test. l O , l 1
, I i
ATTACHMENT.3 Page 68 of 85' ; O MRC44 PRESSURIZER SAFETY LINE TEMPERATURE TRANSMITTER FAILURE The Pressurizer Safety Line Temperature Transmitter Failure malfunction was tested on. 11/01/87.~ It was conducted from the initial conditions of steady state normal full power. The malfunction was ramped over a 30 seconds time frame to demonstrate the degradation feature. The malfunction was degraded to its maximum severity. The duration of the test was 40 seconds. This time was long enough to verify that all expected actions did occur. Data was collected in the form or computer printouts. This data' t consisted of model and plant variable points that verified ; the expected results. There were no discrepancies noted during the duration of the test. 1 MRC45 PRT LIQUID TEMPERATURE TRANSMITTER FAILURE The PRT Liquid Temperature Transmitter Failure malfunction was tested on 10/25/87. It was conducted from i' l the initial conditions of steady state normal full power. i The malfunction was ramped over a 30 seconds time frame to I demonstrate the degradation feature. The malfunction was ! degraded to its maximum severity. The duration of the test . was 41 seconds. This time was long enough to verify that l l all expected actions did occur.- Data was collected in the form of computer printouts. This data consisted of model l and plant variable points that verified the expected results. There were no discrepancies noted' during- the duration of the test. . I MRC46 : PRESSURIZER SPRAY CONTROLLER FAILS The Pressurizer Spray Controller Fails malfunction was ! tested on 10/25/87. It was conducted from the initial conditions of steady state normal full power. . The malfunction was ramped. over a 30 seconds time frame to demonstrate the- degradation feature. The malfunction was degraded to its maximum severity. The duration of the . test was 257 seconds. This time was long enough to verify that-all expected actions did occur. Data was collected in the form of computer printouts. This data consisted of model and plant variable points that verified the expected results. There were no discrepancies noted during the duration of the test. 1 d : l e
l ATTACHMENT 3 Page 69 of 85 I ) 1 MRD01 ROD POSITION INDICATOR FAILURE , j
)
The Rod Position Indicator Failure malfunction was tested on 12/13/87. It was conducted from the initial 3 conditions of steady state normel full power. The duration j of the test was 47 seconds. This time was long enough to verify that all expected- actions did occur. Data was collected in the form of computer printouts. This data i consisted of model and plant variable points that verified the expected results.- There were no . discrepancies noted ] during the duration of the test. MRD06 i UNCONTROLLED CONTINUOUS ROD WITHDRAWAL IN AUTO AT MAXIMUM SPEED 1 The Uncontrolled Continuous Rod Withdrawal in Auto at i Maximum Speed malfunction was tested on 12/13/87. It was , conducted from the initial conditions of steady state normal j full power. The duration of the test was 65 seconds. This time was long enough to verify that all expected actions did occur. Data was collected in the form of computer
/' printouts. This data consisted of model and plant variable points that verified the expected results. There were no discrepancies noted during the duration of the test.
MRD07 UNCONTROLLED CONTINUOUS ROD INSERTION (AUTO) AT MAXIMUM SPEED l The Uncontrolled Continuous Rod Insertion (Auto) at Maximum Speed malfunction was tested on 12/13/87. It was , conducted from the initial conditions of steady state normal ; full power. The duration of the test was 65. seconds. This time was long enough to verify that all expected actions did ; occur. Data was collected in the form of computer printouts. This data consisted of model and plant variable points that verified the expected results. There were no discrepancies noted during the duration of the test.. i l
,-~ :
\_, <
c
ATTACHMENT 3 Page 70 of 85 O MRD08 CONTROL RODS MOVE AT MAXIMUM SPEED testedThe on Control Rods Move 12/13/87. It at Maximum Speed malfunction was was conducted from the initial conditions of of the test was steady state normal full power. The duration r verify that all 73 seconds. This time L expected collected in the form of computer actions did occur. enough to was long Data was printouts. This consisted of model and plant variable points that the expected results. data There were no discrepanciesverified during the duration of the test. noted MRD09 (} CONTROL RODS MOVE AT MINIMUM SPEED testedThe on Control Rods Move 12/13/87. It at Minimum Speed malfunction was was conducted from the conditions of steady state normal full power. initial The duration of the test verify thatwas 110 seconds. This time was long enough to all expected collected in the form of computer printouts. actions did occur. Data was consisted the expectedof model and plant variable points that This data O results. There during the duration of the test.were no discrepancies noted verified MBD10 REVERSE DIRECTION IN AUTO ROD CONTROL The Reverse Direction in Auto Rod Control Was tested on 12/13/87. It malfunction of the test wasconditions of steady state normal fullThe initial power.was conducted from the verify that 85 seconds. This time was long enough duration all expected to actions did occur. collected in the form of computer printouts. Data was consisted the expectedof model and plant variable points that This data results. There verified during the duration of the test.were no discrepancies noted
~
MRD11 RODS REVERSED DIRECTION IN MANUAL testedThe on Rods Reversed Direction 12/13/87. It in Manual malfunction was was conducted from the initial conditions of of the test was steady state normal full power. The duration verify that all 96 seconds. This time expected was long enough to collected in the form of actions did occur. computer printouts. Data was O consisted the expectedof model and results. plant variable There during the duration of the test.were no This data points that verified discrepancies noted
i
.l 1
ATTACHMENT 3' { Page 71 of 85 4
'~) MRD13 ROD CONTROL FAILURE CAUSING B 5 D BANKS TO MOVE TOGETHER 1
The Rod Control. Failure Causing B&D Banks to Move Together malfunction was tested on 12/13/87. It was conducted from the initial conditions of steady state normal j full power. 'The duration of the test was 120 seconds. This i time was long enough to verify that all expected actions did occur. Data was collected in the form of computer
)
{
- printouts. This data consisted'of model and plant variable 1 points that verified the expected results. There were no discrepancies noted during the duration of the test.
MRD14 1 RODS FAIL TO MOVE ON DEMAND IN AUTO i
. l The Rods Rail to Move on Deuand in Auto malfunction was tested on 12/13/87. 'It was conducted- from the initial j conditions of steady state normal full power. The duration- '
of the test was 90 seconds. This time was long enough to ! verify that all expected actions did occur. Data was collected in the form of computer printouts. This data j consisted of model and plant variable points that verified ! the expected results. There were no discrepancies noted during the duration of the test. MRD15 RODS FAIL TO MOVE ON DEMAND IN MANUAL OR BANK SELECT The Rods Fail to Move on Demand in Manual or .Benk i l Select from the malfunction was tested on 12/13/87. It was conducted
' initial conditions- of steady state normal full power. The duration of the test was 100 seconds. .This time I was long enough to verify that all expected actions did
, occur. Data was collected in the form ~of computer printouts. This data consisted of model and plant variable points that verified the expected results. There were no discrepancies noted.during the duration of the test. l 1 i vO
ATTACHMENT 3 Page 72 of 85 t' MRD16 DROPPED ROD The Dropped Rod malfunction was tested on 12/13/87. It was conducted from the initial conditions of steady state normal full power. The duration of the test was.15 seconds. This time was long enough to verify that all expected actions did occur. Data was collected in the form of computer printouts. This data consisted of model and plant variable points that verified the expected results. There were no discrepancies noted during the duration of the test. MRD21 EJECTED CONTROL ROD The Ejected Control Rod malfunction was tested on 12/13/87. It was conducted from the initial conditions of steady state normal full power. The duration of the test was 122 seconds. This time was long enough to verify that all expected actions did occur. Data was collected in the form of computer printouts. This data consisted of model and plant variable points that verified the expected results. There were no discrepancies noted during the duration of the test. STUCK CONTROL ROD The Stuck Control Rod malfunction was tested. on 12/13/87. It was conducted from the initial conditions of i steady state normal full power. The duration of the test was 59 seconds. This time was long enough to verify that all expected actions did occur. Data was collected in the ; form of computer printouts. This data consisted of model i and plant variable points that verified the expected results. There were no discrepancies noted during the i duration of the test. I MRD31 ' AUTO ROD CONTROL CONTROLS TEMPERATURE ABOVE SETPOINT 1 The Auto Rod Control Controls Temperature' Above Setpoint malfunction was tested on 12/13/87. It was ! conducted from the initial conditions of steady state normal j full power. The duration of the test was 145 seconds. This time was long enough to verify that all expected actions did i occur. Data was collected in the form of computer printouts. This data consisted of model and plant variable points that verified the expected results. There were no () discrepancies noted during the' duration of the test.-
]
ATTACHMENT 3 Page 73 of 85 1 f~ MRD32 FAILURE OF AUTO TRIP TO TRIP REACTOR ANY TIME The Failure of Auto Trip to Trip Reactor Any Time malfunction was tested on 12/13/87. It was conducted from-the initial conditions of steady state normal full power. The duration of the test was 360 seconds. This time was , long enough to verify that all expected actions did occur. Data was collected in the form of computer printouts. This i data consisted of model and plant variable points that ' verified the expected results. There were no discrepancies noted during-the duration of the test.
)
MRD33 FAILURE OF ALL ROD STOPS TO BLOCK ROD MOTION The Failure of All Rod Stops to Block Rod Motion malfunction was tested on 12/18/87. It was conducted from the initial conditions of steady state. normal full. power. The duration of the test was 312 seconds. This time was. long enough to verify that all expected actions did' occur. 4 ( Data was collected in the form of computer printouts. data consisted of model and plant variable points This that I fx verified the expected results. There were no discrepancies j t I noted during the duration of the test.
%.J 1 MRD34 REACTOR TRIP BREAKERS OPEN j
The Reactor Trip Breakers Open malfunction was tested i on 12/18/87. It was conducted from t!sa initial conditions of steady state normal full power. was 72 seconds. The duration of the test This time was long enough to verify that , all expected actions did occur. Data _was collected in the ! form of computer printouts. This data consisted of model and plant variable points that verified the expected i results. There were no discrepancies noted_ during the ! i duration of the test. 1 l i MRD36 LOSS OF NUCLEAR INSTRUMENT SIGNAL.TO ROD CONTROL' ' s The-Loss of Nuclear Instrument Signal to Rod Control malfunction was tested on 12/18/87. It was conducted from the initial conditions of steady state normal full power. The duration of the test vac 52 seconds. This' time was long enough to verify that all expected actions did occur. Data ; was collected in the form of computer printouts. This data f- consisted of model and plant variable points that verified ; [ the expected results. There were no discrepancies noted during the duration of the test.
l1 ATTACHMENT 3 Paga 74 of 85 j \
-) MRD38 {
j FAILURE OF REACTOR TRIP ON MANUAL DEMAND The Failure of Reactor Trip on Manual Demand malfunction was tested on 12/18/87. It was conducted from l the initial conditions of steady state normal full power. ; The duration of the test was 50 seconds. This time was long ) enough to verify that all expected actions did occur. Data was collected in the form of computer printouts. This data ; consisted of model and plant variable points that verified j the expected results. There were no discrepancies noted during the duration of the test. j c MRH01 RESIDUAL HEAT REMOVAL SYSTEM LEAK The Residual Heat Removal System Leak malfunction was tested on 11/22/87. It was conducted from the initial conditions of steady state normal full power. The malfunction was ramped over a 30 seconds time frame to demonstrate the degradation feature. The malfunction was i degraded to its maximum severity. The duration of the test was 282 seconds. This time was long enough to verify that x all expected actions did occur. Data was collected in the ( \ -) form of computer printouts. This data consisted of model and plant variable points that verified the expected results. There were no discrepancies noted during the duration of the test. MRH02 RESIDUAL HEAT REMOVAL FLOW TRANSMITTER FAILURE ! i The Residual Heat Removal Flow Transmitter Failure j malfunction was tested on 11/22/87. It was conducted from j the initial conditions of steady state normal full power. l The malfunction was ramped over a 30 seconds time frame to I demonstrate the degradation feature. The malfunction was degraded to its maximum severity. The duration of the test was 156 seconds. This time was long enough to verify that all expected actions did occur. Data was collected in the ; form of computer printouts. This data consisted of model ! and plant variable points that verified the expected l results. There were no discrepancies noted during the duration of the test. (3 (-
AT*ACHMENT 3 Page 75 of.85 O MRH03 LOSS OF COMPONENT COOLING TO RESIDUAL HEAT REMOVAL The Loss of Component Cooling to Residual Heat . Removal malfunction was tested on 11/22/87. It was conducted from the initial conditions of steady state normal full power. . The malfunction was ramped over a 30 seconds time. frame to i demonstrate the degradation feature. The malfunction was degraded to its, maximum severity. The duration of the test was 137 seconds. This time was long enough to verify that all expected actions did occur. Data was collected in the form of computer printouts. This data consisted of model and plant variable points that verified the expected results. There were no discrepancies noted during the duration of the test. { I MRH05
)
LOSS OF RESIDUAL HEAT REMOVAL PUMP The Loss of Residual Heat Removal Pump malfunction was tested on 11/22/87. It was conducted from the_. initial conditions of steady state normal full power. .The duration of the test was 43 seconds. This time was long enough to verify that all expected actions did occur. Data- was O collected in the form of computer printouts. consisted of model and plant variable points that verified the expected results. There were no discrepancies noted This data l I during the duration of the test. MRH06 RELIEF VALVE STUCK OPEN ON ; RESIDUAL HEAT REMOVAL SYSTEM ' The Relief Valve Stuck Open on Residual Heat Removal System malfunction was tested on 11/22/87. It was conducted from the initial conditions of steady state normal full power. The duration of the test was 120 seconds. This time was long enough to verify that all expected actions did occur. Data was collected in the form of computer printouts. This data consisted of model and plant variable points that verified the expected results. There were no discrepancies noted during the duration of the test. O'
ATTACHMENT 3 Page 76 of 85 C\ MRM01 AREA RADIATICN MONITOR FAILURE The Area Radiation Monitor Failure malfunction was tested on 06/01/88. It was conducted from the initial conditions of steady state normal full power. The malfunction was degraded to its maximum severity. The duration of the test was 43 seconds. This time was long enough to verify that all expected actions did occur. Data i was collected in the form of computer printouts. This data consisted of model and plant variable points that verified the expected results. There were no discrepancies noted during the duration of the test. l MRM02 I PROCESS RADIATION MONITOR FAILURE ' The Process Radiation Monitor Failure malfunction was , tested on 06/01/88. It was conducted from the initial conditions of steady state normal full power. The malfunction was degraded to its maximum severity. The duration of the test was 41 seconds. This time was long enough to verify that all expected actions did occur. Data f- was collected in the form of computer printouts. This data I]s k consisted of model and plant variable points that verified the expected results. There were no discrepancies noted a during the duration of the test. MRS01 LOSS OF OUTSIDE RECIRC SPRAY PUMP ON START The Loss of Outside Recirc Spray Pump on Start malfunction was tested on 12/10/87. It was conducted from the initial conditions of steady state normal full power. The duration of the test was 249 seconds. This time was long enough to verify that all expected actions did occur. Data was collected in the form of computer printouts. This data consisted of model and plant variable points that verified the expected results. There were no discrepancies noted during the duration of the test. 1 O N ,]
ATTACHMENT 3. Page~77 of 85 l l lD l MRS02 LOSS OF INSIDE RECIRC-SPRAY PUMP ON START l The Loss of Inside- Recirc- Spray Pump on Start malfunction was tested on. 12/10/87. . It vas conducted from the initial conditions of steady state normal full power. 1 The duration of the test was 262 seconds. This time was long enough to verify that all expected actions did occur. l 1 Data was. collected in the form of computer printouts. This data consisted. of model and plant variable points that verified the expected results. There were no discrepancies noted during the duration of the test. l MSIO3 LOW HEAD SI PUMP SUCTION SCREEN. CLOGS l The Low Head SI Pump Suction Screen Clogs malfunction I was tested ~on 11/22/87. It was conducted from the. initial ! conditions of steady state normal full power. The malfunction was ramped over a 30 seconds time frame -to ] demonstrate the degradation feature. The malfunction ~ was degraded to its maximum severity. The duration of the test f j was 130 seconds. This time was long enough'to verify. that j g- all expected actions did occur. Data was collected in the form of computer printouts. This data consisted of model and plant variable points. that verified the. -expected results. There were -no discrepancies noted during the duration of the test. MSIOS SPURIOUS SAFETY INJECTION i ' The Spurious Safety Injection malfunction was tested on 1 11/22/87.It was conducted from ti.s initial conditions of-eteady state normal full power. .The duration'of the ' test
.:A 60 cM onds. This- time was long enaugh to verify that dil expedbed actions did occur. Data was collected in the i
form of computer printouts. This data co1sisted of model and plant variable points that verif1Gd the expacted results. There were no discrepancies noted during the duration of the test. ; I _ _ _ = - _ _ _ _ _ _ . --_---_ 1
ATTACi! MENT;3 Page.78 ofi85.< O-MSIO6 FAILURE OF SAFETY' INJECTION TO RESET The Failure of Safety Injection to Reset malfunction was tested on 1.1/22/87. It was conducted.from the initial conditions of' steady. state normal full power. Tha duration of the test was.141 seconds. This time wasflong enough Lto Lverify that all expected actionsL did occur. Data was collected in the form. of computer printouts. ..This.-data consisted of model and. plant variable points that.: verified the expected results. There were no discrepancies noted during the duration of the test.. ' MSIO7 FAILURE OF ONE SAFETY INJECTION TRAINLTO-ACTIVATE The Failure of One_ Safety Injection Train to Activate malfunction was tested on 11/22/87. It was conducted .from the initial conditions .of steady state normal full : power. The duration of the test was'44 seconds. .This time was long enough to verify that all expected actions did occur ~ . Data. was collected in the form of computer: printouts. .This. data consisted of model and plant variable points that. verified the expected results. There were no discrepancies noted () during the duration of the test. MSIO8 FAILURE OF ANY-SAFETY INJECTION SIGNAL TO CAUSE SAFETY INJECTION The Failure of Any Safety Injection Si Cause Safety injection malfunction. was tested on : 11/gnal 22/87.to It.was
- conducted from the initial conditions of steady state;normi full power. The duration of the test was 33. seconds. This time was long enough-to verify that all expected actions'did' occur. Data.was collected in the form :of' computer.
printouts. This data consisted of model and plant Lvariable points that verified the expected results. There were. no discrepancies noted during the duration of_.the test. MSWO1 ,
^
LOSS OF SERVICE WATER PUMP L The Loss of Service Water Pump,-malfunction was performed _on 05/28/88.during normal operating steady. state. conditions. .Various parametersLof the model and systems; affected were monitored to verify that the expected. results
~
were obtained. . Data was collected in the form of. computer-printouts. There- were no ' discrepancies noted () duration of the test. during the
ATTACHMENT 3 Page 79 of 85 r~s MTU01 TURBINE TRIP DUE TO OVEKSPEED The Turbine- Trip Due to Overspoed malfunction ~ vas I tested on 12/06/87. It was conducted from the initial conditions of steady state normal full.poeer. The duration of the test was 20 seconds. This time wac long enough to verify that all expected actions did occur. Data was collected in the form of computer printouts. This data consisted of model and plant variable points that verified the expected results.- There ~were no discrepancies noted during the duration of the test. MTUO2 FAILURE OF MANUAL TRUBINE TRIP TO FUCTION ON DEMAND The Failure of Manual' Turbine Trip to : Function on Demand malfunction was tested on 12/06/87. It was conducted from the initial conditions of steady state normal full i power. The duration of the test was 54 seconde. This time was long enough to verify that all expected actions did occur. Data was collected in the form of computer printouts. This data consisted of model and plant variable ; points that verified the expected results. There were- no gO discrepancies noted during the duration of the test. MTUO3 l 1 FAILURE OF AUTO TURBINE TRIP TO FUNCTION ON DEMAND I The Failure of Auto Turbine Trip to Function on Demand' i malfunction was tested on 12/06/87. It was conducted from i the initial conditions. of steady state normal full power. j The duration of the test was 226 seconds. This time .was i long enough to verify that all expected actions did occur. I Data was collected in the form of computer printouts. This data consisted of model and plant variable points that verified the expected results. There were no' discrepancies noted during the duration of the test. I
ATTACHMENT 3 Page 80 of 85
\-
MTU12 FAILURE OF AUTO TURBINE RUNBACK The Fe!. lure of Auto Turbine Runback malfunction was ' tested on 12/06/87. . It was conducted from the initial conditions of steady state normal full power. The duration 3 of the test was 60 seconds. This time was long enough to ( verify that all expected actions did occur. Data was collected in the form of computer printouts. This data consisted of model and plant variable points that verified the expected results. There were no discrepancies noted 3= during the duration of the test. 1 MTU13 SPURIOUS TURBINE RUNBACK The Spurious Turbine Runback malfunction was tested on 12/06/87. It was conducted from the initial conditions of steady state normal full power. The duration of the test 'I was 88 seconds. This time was long enough to verify that all expected actions did occur. Data was collected in the form of computer printouts. This data consisted of model and plant variable points that verified the expected f~s results. There were no discrepancies noted during the ( ) duration of the test. w/ MTU14 REHEATER SAFETY VALVE STUCK OPEN The Reheater Safety Valve Stuck Open malfunction was tested on 12/06/87. It was conducted from the initial conditions of steady state normal full power. The duration of the test was 96 seconds. This time was long enough to verify that all expected actions did occur. Data was collected in the form of computer printouts. This data consisted of model and plant variable points that verified the expected results. There were no discrepancies noted during the duration of the test. l (~ (
l ATTACHMENT 3 Page 81 of 85 O V VIRGINIA POWER SIMULATOR SUPPORT GROUP NORTH ANNA UNIT 1 SIMULATOR UNIQUE TESTS RESULTS
' ATTACHMENT.3 Page 82 of-85 O SIMULATOR RELIABILITY TEST A special reliability test was conducted in' November '1987 and in March 1988. ..These tests demonstrated-the operability and reliability of the simulator complex following hardware- or modifications. The first test- followed the software incorporation of shared memory between-the Gould 87 and 27 computers. The second test followed repairs and modifications to the LSI and Gould data link interface.
is Each test consisted of a test run in which The theLsimulator.the availability.of used under normal training- conditions. simulator must be greater than or equal to 95% in order to be an acceptable test. Test procedures were completed-to document the tests. There were no discrepancies noted during the tests. CHARGING PUMP CHECK VALVE STUCK OPEN An event occurred in the reference plant in which .the discharge check valve.of a charging pump being secured stuck open. Operations personnel had not experienced this event before and determined that training in this area is required. /~ LER 87-002 was reviewed for impact and SMR_# 8703251535-'was produced. The SMR created a malfunction MCH21, which replicated the sequence of events of _the reference plant. The malfunction is generic and ~a ll three pumps were tested. There were no discrepancies noted during the tests. FEEDWATER LINE BREAK An event occurred at.Surry Power Station'in which personnel were fatally injured. NRC. Information Notice 86-106 and LER 86-020 were reviewed for impact. An SMR was generated to Lcreate a malfunction to reproduce this event. A generic malfunction, MFW21, was developed and tested'to ensure the sequence of events matched as much as possible those which' occurred:in the sister plant. There were no discrepancies noted during the tests. O
^l ATTACHMENT 3 Page 83 of'85 )
f i i TUBE RUPTURE i I A tube rupture event at North Anna generated a test review i of malfunction MRC24. The results were compared'to LER 87-017 j and subsequent reports. This test .resulted in a minor modification to the steam generator- model-to match the- response of the simulator to the. reference plant. No other discrepancies ) were noted during the test. SINGLE MSTV CLOSURE An event. occurred at North Anna power station in which a ) single main steam line trip valve closed at rated full power. l The resulting LER, LER 86-00C, was reviewed and tested. l A discrepancy was noted: between -the simulator 'and the 'I I reference plant. The reference plant received 'a reactor trip ! safety injection due to high steam flows,. the simulator received 1 a reactor trip due to low steam. generator level. Since' no i previous data existed on the event questions were raised as- to l the proper response of the reference plant. The simulator 'will replicate the reference plant after some adjustments. Currently the correct response is still under review. s-. q I 1 l 9
_3 ATTACHMENT 3: Page~84 of 85-4 LVIRGINIA POWER-SIMULATOR SUPPORT GROUP NORTH. ANNA UNIT 1 SIMULATOR SURVEILLANCE TEST RESULTS ,)
.i 1
q I i z j O a _ _ _ _ _ _ _ _ _ __________ _ _ _ w
l ATTACHMENT 3' Page 85 of 85- 4 (~) N/-- . SURVEILLANCE TESTS q The Periodic Tests listed below were conducted on the North Anna Simulator. These Periodic Tests support the RO/SRO License Program. Each test used actual plant periodic test . procedures. Only those portions of the test that require control room operator action or a local- action that is simulated were performed. All identified problems have either.been-repaired or scheduled into the Simulator Modification Report (SMR) system. 1 The major discrepancy noted during the tests the inability of the plant computer to support all of the . was ncessary ; aspects of the tests. The plant computer is currently scheduled for upgrade by 02/28/89. j i 1-PT-10 Determination of Shutdown Margin i 1-PT-10.1 At Power-Shutdown Margin Determination ! 1-PT-17.1 Control Rod Operability i 1-PT-23 Quadrant Power Tilt Ratio 1-PT-24 Hand Calorimetric 1-PT-24.1 Computer Calorimetric 1-PT-34.3 Turbine Valve Freedow Test ! 1-PT-52.1 Measurement of Controlled Leakage 1-PT-52.2 Reactor Coolant System Leak Rate e~g 1-PT-60.2 Containment Air Temperature
'j 1-PT-71.1 Steam Driven Aux Feed Pump and Valve Test 1-PT-82H 1H Emergency Diesel Generator Slow Start Test 1-PT-82J 1J Emergency. Diesel Generator Slow Start Test ;
1 O . 1
'I l
l j 1 I l VIRGINIA POWER i i SIMULATOR SUPPORT GROUP { J
'l l
l i NORTH ANNA UNIT 1 SIMULATOR O ATTACHMENT 4-l SIMULATOR TEST SCHEDULE ! i
ATTACHMENT 4 Paga 1 OF 5-
~
[ ( SIMULATOR PERFORMANCE TEST SCHEDULE The performance test schedule to be conducted over the- next four years will consist of the following tests. The . Transient Performance Tests of.ANS-3.5-1985 Appendix B section B.2.2 will be conducted annually. August 1988 - July 1989 Integrated Tests Unit Startup from Cold Shutdown Condition (Mode 5) < 200 deg. F l L with a solid pressurizer to Cold Shutdown Condition (Mode 5) at < 200 deg. F. Unit Startup from Cold Shutdown Condition (Mode 5) to Hot Shutdown Condition (Mode 4) less than or equal to 350 deg. F. Malfunction Tests MCA01 FAILURE OF CONTAINMENT INSTRUMENT AIR COMPRESSOR I
/ MCA02 CONTAINMENT INSTRUMENT AIR LEAK
- l. (_j)/ MCA04 INSTRUMENT AIR LEAK MCC02 FAILURE OF COMPONENT COOLING PUMP TO START MCC03 COMPONENT COOLING FLOW TRANSMITTER FAILURE MCC04 COMPONENT COOLING PRESSURE TRANSMITTER FAILURE MCC05 RCP THERMAL BARRIER LEAK MCC06 COMPONENT COOLING PUMP SHEARED SHAFT MCH01 ISOLABLE LETDOWN LINE LEAK IN CONTAINMENT MCH02 ISOLABLE LETDOWN LINE LEAK OUTSIDE CONTAINMENT MCH03 ISOLABLE CHARGING LINE LEAK OUTSIDE CONTAINMENT MCH04 LETDOWN PRESSURE TRANSMITTER FAILURE MCH05 REACTOR MAKEUP CONTROL BORATES IN THE AUTO MODE MCH06 LOSS OF COMPONENT COOLING TO NRHX MCH07 FAILURE OF CHARGING FLOW CONTROLLER l MCH08 FAILURE OF CHARGING FLOW TRANSMITTER MCH09 REACTOR MAKEUP DILUTION IN AUTO MODE MCH11 BORIC ACID LINE TO THE BLENDER PLUGGED MCH12 VCT LEVEL TRANSMITTER FAILURE 4 MCH13 TUBE RUPTURE IN THE NONREGENERATIVE HEAT EXCHANGER MCH15 LOSS OF REACTOR MAKEUP CONTROL MCH16 LOSS OF CHARGING PUMP 1 MCH18 LETDOWN PRESSURE CONTROL VALVE FAILS OPEN j MCH21 CHARGING PUMP CHECK VALVE STICKS OPEN MCN01 LOSS OF CONDENSATE MAKEUP MCN07 HIGH LEVEL DIVERT VALVE LCV-CN-107 FAILS OPEN i MCN14 CONDENSATE PUMP DISCHARGE CHECK VALVE STICKS OPEN MCN16 CONDENSER AIR IN LEAKAGE O MCV01 NELO1 MELO3 GRADUAL INCREASE IN CONTAINMENT PRESSURE LOSS OF ALL OFFSITE POWER LOSS OF 4160V EMERGENCY BUS i 1 <
j
ATTACHMENT 4 Page 2 OF 5 I 'N MELO4 LOSS OF 4160V STATION BUS
\~- MELOS LOSS OF 125V D.C. BUS MELO6 LOSS OF 480V EMERGENCY BUS MELO7 LOSS OF 480V STATION BUS MELO8 LOSS OF EMERGENCY DIESEL GENERATOR MEL11 MAIN GENERATOR TRIP MEL12 LOSS OF SEMI-VITAL BUS MEL13 LOSS OF AC VITAL BUS INVERTER MELIS LOSS OF 480V EMERGENCY MCC j MEL16 LOSS OF 480V STATION SERVICE MCC MEL17 LOSS OF PRIMARY PROCESS RACK POWER SUPPLY i August 1989 - July 1990 l
Integrated Tests Unit Startup from Hot Shutdown Condition (Mode 4) to Hot Standby Condition (Mode 3 at 547 deg. F. Unit Startup from Hot Standby Condition (Mode 3) to Startup i Condition (Mode 2) with Reactor critical at less than or equal to 5% power. I Malfunction Tests j MFWO1 STEAM GENERATOR LEVEL TRANSMITTER FAILURE (0-100%) f' gy MFWO2 LOSS OF STEAM PRESS. COMPENSATION TO S/G LEVEL CONTROL MFWO4 MAIN FEED PUMP LOW LUBE OIL PRESSURE
\ >; MFWO5 MAIN FEEDWATER REGULATING VALVE FAILS CLOSED MFWO6 TOTAL LOSS OF FEEDWATER MFWO8 LOSS OF LEVEL ERROR SIGNAL TO S/GLEVEL CONTROL MFWO9 OVERSPEED TRIP OF AUXILIARY S/G FEED PUMP MFW10 AUXILIARY FEED FUMP CHECK VALVE OPEN )
MFW11 AUXILIARY FEED PUMP IMPELLER DEGRADATION MFW12 MAIN FEED FLOW TRANSMITTER FAILURE MFW13 MAIN FEEDWATER BREAK UPSTREAM OF FLOW TRANSMITTER MFW14 AUX FEEDWATER BREAK DOWNSTREAM BETWEEN FLOW TRANS & CHECK VALVE MFW15 MAIN FEEDWATER BREAK DOWNSTREAM OF CHECK VALVE OUTSIDE CONTAINMENT MFW16 MAIN FEEDWATER BREAK IN CONTAINMENT MFW17 DEGRADATION OF MAIN FEED PUMP MFW18 MAIN FEEDWATER REGULATING VALVE FAILS OPEN MFW19 MAIN FEEDWATER BREAK BETWEEN FLOW ELEMENT AND CHECK VALVE l MFW21 MAIN FEEDWATER PUMP SUCTION PIPE BREAK MFW23 AUXILARY FEEDWATEK PUMP TRIPS ON OVERCURRENT MGWO1 ACCIDENTAL RELEASE OF RADIOACTIVE GAS MMS 01 STEAM FLOW TRANSMITTER FAILURE MMS 02 TURBINE FIRST STAGE PRESSURE TRAN'SMITTER FAILURE MMS 08 RUPTURE OF MAIN STEAM LINE IN CONTAINMENT BEFORE THE FLOW TRANSMITTER 1 1
ATTACHMENT 4 Page 3 OF 5 O MMS 09 RUPTURE OF MAIN STEAM LINE AFTER THE NON-RETURN VALVE MMS 10 RUPTURE OF MAIN STEAM LINE BEFORE THE TRIP VALVE MMS 11 FAILURE OF STEAM DUMP CONTROL AS IS MMS 12 ATMOSPHERIC STEAM RELIEF VALVE STUCK OPEN MMS 13 MAIN STEAM TRIP VALVE FAILS AS IS MMS 14 MAIN STEAM SAFETY VALVE STUCK OPEN MMS 15 STEAM DUMP VALVE STUCK OPEN MMS 16 FAILURE OF STEAM HEADER PRESSURE CONTROL (0-100%) MNIO1 POWER RANGE UPPER DETECTOR FAILURE MNIO2 POWER RANGE LOWER DETECTOR FAILURE MNIO3 BLOWN POWER RANGE CONTROL FUSE MNIO4 BLOWN POWER RANGE INSTRUMENT FUSE MNIO6 SOURCE RANGE DETECTOR FAILURE (DISCRIMINATOR ERROR) MNIO8 INTERMEDIATE RANGE IMPROPERLY COMPENSATED MNIO9 INTERMEDIATE RANGE DETECTOR FAILURE MNIl0 SOURCE RANGE CHANNEL FAILURE MNI13 POWER RANGE CHANNEL FAILURE August 1990 - July 1991 Integrated Tests Unit Power Operation, Mode 2 to Mode 1 (to include heat balance performance test). Unit Power Operation, Mode 1 to Mode 2. Computer Real Time Test. Malfunction Tests MQS01 LOSS OF QUENCH SPRAY PUMP MQS03 FAILURE OF CONTAINMENT HIGH PRESSURE TO INITIATE SPRAY MQS06 SPURIOUS CONTAINMENT SPRAY ACTUATION MQS07 DEGRADATION OF INSIDE RECIRC SPRAY PUMP MQS08 RECIRC SPRAY NOZZLES CLOG MQSO9 TUBE LEAK IN RECIRC SPRAY HEAT EXCHANGER MRC01 REACTOR COOLANT SYSTEM COLD LEG PIPE RUPTURE MRC02 REACTOR COOLANT SYSTEM HOT LEG PIPE RUPTURE MRC03 REACTOR COOLANT SYSTEM PUMP SUCTION LEG PIPE RUPTURE l MRC04 REACTOR COOLANT SYSTEM NONISOLABLE LEAK l MRC05 RCP OVERCURRENT TRIP MRC06 FAILURE OF REACTOR VESSEL LEVEL TRANSMITTER i MRC07 PRESSURIZER PRESSURE TRANSMITTER FAILURE l MRC08 PRESSURIZER LEVEL TRANSMITTER FAILURE- l MRC11 REACTOR COOLANT FLOW TRANSMITTER FAILURE MRC14 FAILURE OF RCP NO. 3 SEAL MRC15 CONTROL RTD FAILURE IN COLD LEG MRC17 PROTECTION RTD FAILURE IN HOT LEG MRC18 PROTECTION RTD FAILURE IN COLD LEG MRC19 PRESSURIZER RELIEF VALVE FAILS-OPEN 9 MRC20 MRC21 PRESSURIZER SPRAY VALVE STUCK OPEN PRESSURIZER SAFETY VALVE STUCK OPEN j
ATTACHMENT 4 1 Pago 4 OF 5 l MRC22 RPESSURIZER HEATERS FAIL ON (H BUS) MRC23 J BUS PRESSURIZER HEATERS FAIL ON l MRC24 STEAM GENERATOR TUBE RUPTURE MRC25 BOTH PRESSURIZER SPRAY VALVES FAIL CLOSED MRC26 RCP SHEARED SHAFT )' MRC29 PRESSURIZER PRESSURE CONTROL FAILS MRC31 FUEL LEAK MRC32 PCV-456 SEAT LEAKAGE MRC33 PT-402 WIDE RANGE PRESSURE TRANSMITTER FAILURE MRC34 PT-403 WIDE RANGE PRESSURE TRANSMITTER FAILURE MRC35 PRT LEVEL TRANSMITTER FAILURE i MRC36 PRT PRESSURE TRANSMITTER FAILURE l MRC37 RCS VESSEL FLANGE LEAK TEMPERATURE DETECTOR FAILURE I MRC38 LOSS OF COMPONENT COOLING WATER TO RCP l MRC40 PZR SURGE LINE TEMPERATURE TRANSMITTER FAILURE q MRC41 RCS SPRAY LINE TEMPERATURE TRANSMITTER FAILURE MRC42 PZR LIQUID / VAPOR TEMPERATURE TRANSMITTER FAILURE MRC43 PRESSURIZER PORV TEMPERATURE TRANSMITTER FAILURE i MRC44 PZR SAFETY LINE TEMPERATURE TRANSMITTER FAILURE j MRC45 PRT LIQUID TEMPERATURE TRANSMITTER FAILURE August 1991 - July 1992 Integrated Tests [~) (_/ Unit Shutdown from Startup Condition with Power less equal to 5% (Mode 2) to Hot Standby Condition (Mode than
- 3) at or 547 j
deg. F. ] { l Unit Shutdown from Hot standby Condition (Mode 3) to Hot Shutdown l Condtion (Mode 4) at less than 350 deg. F. Unit Shutdown from Hot Shutdown Condition (Mode 4) to Cold I Shutdown Condition (Mode 5) at less than or equal to 200 deg. F. Malfunction Tests MRC46 PRESSURIZER SPRAY CONTROLLER FAILS MRD01 ROD POSITION INDICATOR FAILURE MRD06 UNCONTROLLED CONTINUOUS ROD WITHDRAWAL IN AUTO AT MAXIMUM SPEED MRD07 UNCONTROLLED CONTINUOUS ROD INSERTION (AUTO) AT MAXIMUM SPEED MRD08 CONTROL RODS MOVE AT MAXIMUM SPEED MRD09 CONTROL RODS MOVE AT MINIMUM SPEED MRD10 REVERSEDIRECTION IN AUTO ROD CONTROL MRD11 RODS REVERSED DIRECTION IN MANUAL MRD13 ROD CONTROL FAILURE CAUSING B & D BANKS TO MOVE TOGETHER MRD14 RODS FAIL TO MOVE ON DEMAND IN AUTO i MRD15 RODS FAIL TO MOVE ON DEMAND IN MANUAL OR BANK SELECT i
,.m U
ATTACHMENT'4 Pago.5 OF.5 MRD16 DROPPED ROD MRD21 EJECTED CONTROL ROD j MRD26 STUCK CONTROL ~ ROD MRD31 AUTO ROD CONTROL CONTROLS TEMPERATURE ABOVE SETFOINT MRD32 FAILURE OF AUTO TRIP TO TRIP REACTOR ANY TIME MRD33 FAILURE OF ALL ROD STOPS TO BLOCK ROD MOTION . MRD34 REACTOR TRIP BREAKERS OPEN-MRD36 LOSS OF NUCLEAR INSTRUMENT SIGNAL TO ROD CONTROL-MRD38 FAILURE OF REACTOR TRIP ON MANUAL' DEMAND MRH01 RESIDUAL HEAT REMOVAL SYSTEM LEAK' l MRH02 RESIDUAL HEAT REMOVAL FLOW TRANSMITTER FAILURE MRH03 LOSS OF COMPONENT COOLING TO RESIDUAL HEAT REMOVAL MRH05 LOSS OF RESIDUAL HEAT REMOVAL PUMP MRH06 RELIEF VALVE STUCK OPEN ON RESIDUAL HEAT REMOVAL SYSTEM MRM01 AREA RADIATION MONITOR FAILURE MRM02 PROCESS RADIATION MONITOR FAILURE MRS01 LOSS OF OUTSIDE RECIRC SPRAY PUMP ON START 4 I MRS02 LOSS OF INSIDE RECIRC' SPRAY. PUMP ON START MSIO3 LOW HEAD SI PUMP SUCTION SCREEN CLOGS MSIO5 SPURIOUS SAFETY INJECTION MSIO6 FAILURE OF SAFETY INJECTION TO RESET l MSIO7 FAILURE OF ONE SAFETY INJECTION TRAIN TO ACTUATE , MSIO8 FAILURE OF ANY SAFETY INJECTION SIGNAL TO CAUSE l SAFETY INJECTION O MSWO1 MTU01 MTUO2 SERVICE WATER PUMP TRIP TURBINE TRIP DUE TO OVERSPEED FAILURE OF MANUAL TURBINE TRIP TO FUNCTION ON DEMAND MTUO3 FAILURE OF AUTO TURBINE TRIP TO FUNCTION ON DEMAND MTU12 FAILURE OF AUTO TURBINE RUNBACK MTU13 SPURIOUS TURBINE RUNBACK MTU14 REHEATER SAFETY VALVE STUCK OPEN l l I i i i l 1
1 i O 4 1 VIRGINIA POWER SIMULATOR SUPPORT GROUP 1 I NORTH ANNA UNIT 1 SIMULATOR ATTACHMENT 5 PHYSICAL FIDELITY REPORT l I l 1 l i i O
k
. ATTACHMENT'5' Page 1 of 46 1 i
5 i NORTH ANNA PHYSICAL FIDELITY COMPARISON REPORT ' APRIL 1988 ) i g This Physical Fidelity Report is an item by item ~ simulator control room comparison to a series of Plant Control Room Unit #1 photographs taken in February 1988. A priortized corrective maintenance program has been initiated and work is being accomplished based upon an item by item j evaluation and parts availability. This report includes { identification of all- unresolved. Simulator Control Panel I discrepancies; indicating work to be performed based on training 4 impact, cost effectiveness, and other comments as appropriate. Also included are discrepancies identified as requiring no action at this time. Generic Control Room / Panel differences have been-identified as necessary. The Plant Control Room photos are arranged panel by panel and l I sequentially numbered. Discrepancy duplications due to photo overlap are so indicated by reference to the earliest photo { ' sequence appearance. Discrepancy item identifications are written as descriptive as possible but a complete review of referenced photos in conjunction with this report may be required to determine ( the exact difference (s). This report references each panel with associated Photo # and lists each discrepancy of ' the simulator from the plant. This report is organized in t"o sections: .No Impact: those items previously identified as "no impact" on the 1987 report. The actual comparison then follows based upon 1988 photographs and is arranged panel by panel and sequentially numbered for each panel grouping. Each line item is identified by priority, status, description, and comment. Priority codes indicate:
- 1. Items impacting training, that are to be corrected as soon as possible, generally within 30-60 days.
- 2. Items requiring additional support for completion; ~ 1e' ,
software, plant ops, etc., generally within 90-120 days. :
- 3. Minimal training impact correctable as part ofL the .!
Control Room Design Review (CRDR) or system upgrade. These items are periodically re-evaluated for training l l impact / cost effectiveness. '
ATTACHMENT 5 Paga 2 of 46 Vo Status codes indicate: j N/S - Not started
.I I
N/A - Not applicable W - Work in progress , i Done, corrected or completed- ! D - Description indicates: -) 1 discrepancy. 1 Item, name,' location or identifier-of. Simulator or difference from plant control room with photo reference where applicable. le. (V2-175 ' = Vertical Board 2- photo
#175) l Panel-codes used: BB1 - BENCH BOARD # 1 i BB2 - BENCH BOARD #'2 j V1 - VERTICAL BOARD # 1 V2 - VERTICAL BOARD # 2 LW - LIQUID WASTE PANEL ,
BR - BORON RECOVERY PANEL 1 RM - RADIATION MONITOR' PANEL l DJ - DIESEL GEN "J" PANEL f l DH - DIESEL GEN "H" PANEL TS - TURBINE SUPERVISORY PANEL IC - INCORE PANEL AMS - ACCOUSTICAL MONITORING SYSTEM-(VALVE MONITORING) PANEL CHR - CONTAINMENT HIGH RANGE RADIATION MONITORING (VICTOREEN) PANEL ASD - AUXILIARY SHUT DOWN PANEL CC - COMPONENT COOLING WALL MOUNTED PANELS BC - BEARING COOLING PANEL CW - CIRCULATING WATER PANEL FP - FIRE PROTECTION PANEL SY - SWITCH YARD PANEL SS - SHIFT SU?EFVISOR CONSOLE i PD - PRODAC CONSCLE l CR - ANY OTHER CONTROL ROOM EQUIPMENT. Comment indicates: Action, applicability, impact, due date, etc; information relative to resolution or disposition of the indicated items. 1 O ' l E____1_______________ . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ .
ATTACHMENT 5 Paga 3 of 46 O 1988 PHYSICAL FIDELITY The following list of discrepancies.were found to have- no impact on training in'the 1987 report. Therefore these types of discrepancies will;not be covered in this report. l l ANNUNCIATOR WINDOWS
- 1) Windows with different spacing,:but they read.the same.
- 2) Windows with different: letter sizes.-
l PANELS 1). Panels that are built differently.
- 2) ' Panels'without-molding or different molding.
- 3) Paint for system separation that .is laid out a .little l different and does not detract. from training.
(components are within the proper. colored segment as in the station). () 47 5)
' Drawer handles that are a different size or style.
With or without Logo.-
- 6) Screws, bolts,.and nuts missing or not-the same-type.
- 7) Minor physical spacing differences and physical- panel dimensions.
RECORDERS
- 1) With or without Logo.
- 2) With or without correct Logo.
- 3) That are a'slightly different style.
INTEGRATORS OR COUNTERS
- 1) With slightly different reset buttons.
- 2) With different color letters or wheels.
SETPOINT STATIONS
- 1) With different color trim or cover plate.
O
1 l
- ATTACHMENTS 5' Paga ' 4 ' of .' 4 6-X METERS.
- 1) With bolder-legends or scales..
-2) With different style or-size lettering.
- 3) With different color or style pointer.
- 4) With different color trim.
~
- 5) With more or less division marks,.but-the scale:is the same.
LABELS
- 1) With different size letters.
- 2) With bolder or lighter letters.
- 3) That are' spaced'different,.but read the same.
- 4) Labels that are cracked.
4 1 1 4 O
'l
_ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . . _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ __ _ _ _ 1
ATTACHMENT 5 Pcgs 5.of 46 (m) OVERALL CONTROL ROOM ITEMS ] { Priority Status Description Comments i N/A N/A 1. LOCATION OF AUX SHUTDOWN Located'for convenience ! VITAL BUS TRANSFER no impact from a j SWITCHES IS DIFFERENT training stand point j l N/A N/A 2. THERE IS NO HATHAWAY High cost equipment is l EVENT RECORDER not located in the 4 control room N/A N/A 3. THERE IS NO KAMAN DATALOGGER Used by HP personnel only ! N/A N/A 4. THE ROBERTSHAW FIRE Not cost effective PROTECTION SYSTEM IS high labor - minimal NOT FUNCTIONAL training value N/A N/A 5. VG 112 & 113 VENT STACK Located here for B RAD MONITORS ARE LOCATED convenience & space ON THE UNIT 2 BACKBOARD IN consideration no THE REAL CONTROL ROOM. ON further action THE SIMULATOR THEY'RE scheduled LOCATED ON THE UNIT 1 ( RADIATION MONITORING PANEL
\ AT THE SAME LEVEL N/A N/A 6. THE SOUND POWERED HEADPHONE No training value SYSTEM IS NOT WIRED UP.
N/A N/A 7. THERE IS NO SIESMIC Training evaluation MONITORING EQUIPMENT indicates not cost l SIMULATED (COMMON TO effective at this time BOTH UNITS) periodically revaluated N/A N/A 8. THERE IS NO MET TOWER EQUIP Training evaluation SIMULATED (COMMON TO BOTH indicates not cost UNITS) effective at this timo periodically revaluated N/A N/A 9. THERE IS NO LOOSE PARTS Training evaluation MONITORING EQUIP. SIMULATED. indicates not cost i (COMMON TO BOTH UNITS) effective at this time periodically revaluated i
)
i (~/'i N.- i _ _ _ _ _ _ _ - _ . . _ _ . . _ _ _ b
ATTACHMENT 5 Pcgo 6 of 46 [ fiority Status Description Comments N/A N/A 10. THE LIGHTING / CEILING IN THE Evaluation determines SIMULATOR IS DIFFERENT. THE cost too high MAIN CONTROL ROOM USES currently to revise CONTINOUS LIGHT DIFFUSION PANELS AND FLOURESCENT LIGHTING. THE SIMULATOR ONLY HAS DIFFUSION PANELS UNDER EACH LIGHT FIXTURE AND THE FIXTURES ARE MUCH CLOSER TO THE DIFFUSION PANELS. N/A N/A 11. THERE ARE NO CALIBRATION No training value STICKERS AFFIXED TO ALL SIMULATOR METERS, CONROLS,ETC N/A N/A 12. MAGNA-HELIC PDI'S NOT No training value SIMULATED AT THIS TIME PERIODICALLY RE-EVALUATED FOR TRAINING IMPACT. N/A N/A 13. WATT HOUR AND RELAY DEVICE No training value INTERNALS ARE NOT PROVIDED. f'\N/A N/A 14. NEW FORMAT, PLANT SUPPLIED (_/ LABELS HAVE BEEN INSTALLED ON SIMULATOR BUT NOT ON PLANT BY THE TIME PHOTO'S WERE TAKEN. CRDR RELABEL UNDERWAY IN PLANT. WILL PERIODICALLY VERIFY CONTROL ROOM LABELS ARE INSTALLED. N/A N/A 15. THE CARPETING IN THE No training value SIMULATOR IS NOT LIKE THE high cost - runners PLANT. THE PILE IS THICKER may be installed IN THE PLANT AND A DIFFERENT after upgrade SHADE OF BROWN. THERE ARE ALSO PROTECTIVE RUNNERS UNDER VERTICAL BOARD THAT PROTECT CARPETING FROM INK STAINS. 3 N/S 16. AREA RADIATION MONITOR Parts on order 08/08/88 DETECTOR & METER FOR CONTROL ROOM AREA IS NOT INSTALLED. LOCAL INDICATION ON SIDE OF i VERT 1 O O
ATTACHMENT 5' Paga 7'of 46 O v Priority Status Description Comments 3 N/S 17. NEW VICTOREEN RATE METER Systematic upgrade NOT INSTALLED'(ITS'FOR ! SERVICE WATER) ! l N/S 18. ALL MARK # TAGS (FOR CRDR review underway 3 J METERS) AT SIMULATOR ARE may reengrave all- 1 WHITE W/ BLACK LETTERS & labels & tags in plant CONTROL ROOM IS BLACK i W/ WHITE LETTERS 1 W 19. GAITRONICS WAS CHANGED IN Due by 08/88 PLANT TO CUT DOWN ON- l BACKGROUND NOISE IN THE CONTROL ROOM. NOW YOU CAN ONLY CALL CONTROL ROOM ON CHANNEL 5. (THE ONLY CHANNEL THEY CAN HEAR PAGING
.INSIDE THE CONTROL ROOM) 3 N/S 20. THE SIMULATOR WAS NOT Low training value- y SUPPLIED WITH NON-GLARE scheduled for 1 ON THE METER CASES, THE completion by 12/88 PLANT WAS 3 N/S 21. THE LOGOS AT THE END.0F THE Complete'by 12/88 CONTROL ROOM AND ON TIIE S/S CONSOLE ARE MISSING 2 W 22. THE FILE CABINETS FOR Ordered, PROCEDURES ARE NO LONGER Complete by 09/88 SINGLE DRAWER TYPE CABINETS, THEY ARE LATERAL FILE l C?5INETS IN THE MAIN CONTROL ROOM !
i 3 N/S 23. VERTICAL BOARD #1 CRT-17 IS Systematdc l A COLOR TERMINAL BUT LACKS upgradt l SOFTWARE TO DRIVE IT OTHER l THAN MONOCHROMATIC 2 W 24. POWER SOURCE INDICATORS, Complete by 08/88 ROUND COLORED DOTS, VARY IN SHAPE & HUE FROM PLANT-i l O
ATTACHMENT 5 Pcgo 8 of 46 1
,r-(.Priority Status Description Comments ;
1 W 25. BACKGROUND COLOR OF Complete by 08/88 ILLUMINATED WINDOWS HAS NOT BEEN VERIFIED DUE TO THIS DETAIL MISSING FROM COLOR PHOTOGRAPHS & TIME REQUIRED TO VERIFY CONTROL ROOM DOCUMENTATION FOR ANNUNCIATORS )
-1 SPECIFIC COMPARISON {
ANNUNCIATOR PANEL 1-EI-CB-21P (70) 3 N/S 1. WINDOW D3 - DASH BETWEEN Due 12/88
...AT-POWER..." IS MISSING ANNUNCIATOR PANEL 1-El-CB-21A (71) 1 W 1. WINDOW G7 BLANK ON SIMULATOR Due 08/88 PLANT: "EMER. DIESEL GEN 7s 1H IN LOCAL CONTROL ss ANNUNCIATOR PANEL 1-EI-CB-218 (72) 1 W 1. BLACK ON YELLOW LETTER Due 08/88 l DESIGNATOR FOR PANEL COLUMN "F" MISSING".
1 W 2. WINDOW F3 IS BLANK IN PLANT Due 08/88 PHOTO. SIMULATOR: RCS MARGIN:.." l 1 W 3. WINDOW E5 IS BLANK ON Due 08/88 j SIMULATOR. PLANT: E5 "EMER DIESEL GEN BATTERY VOLTAGE TROUBLE" l ANNUNCIATOR PANEL f 1-EI-CD-21C 173) 1 N/S 1. WINDOWS Al & A4 REVERSED Due 08/88 f PLANT: A1 "...L-115", 1 A4 "...L-112" l l SIM: A1"...L-112", ; A4"...L-115"
ATTACHMENT 5 Paga 9 of 46 ority Status Description Comments j 1 N/S 2. 7.- 1 NEEDS TO BE MADE & Due 08/88 SOFTWARE IMPLEMENTED ! I 1 W 3. A-4 NEEDS TO BE MADE & Due 08/88 SOFTWARE IMPLEMENTED 3 W 4. WINDOWS F5 & F6 Due 12/88 l PLANT: "RC LOOP..." SIM: "RCP LOOP..." ANNUNCIATOR PANEL 1-EI-CB-21D (74) l 3 N/S 1. WINDOWS C1 & C2 DIFFER CRDR relabel i PLANT: " ...HI 0-HI..." (SPACE BETWEEN HI 0) SIM: ...HIO-HI..." (NO SPACE BETWEFN HIO) i 3 W 2. WINDOW C7 1ST WORD Due 12/88 PLANT: "MOTR"..." SIM: " MOTOR..." ( "'s 1 W 3. WINDOW El LAST CHARACTER Due 08/88 x / PLANT: " .. 50%"
'~
SIM: "
.. 30%"
ANNUNCIATOR P1NEL 1-EI-CB-21G (77) 1 W 1. WINDOW C2 IS BLANK ON' Due 08/88 SIMULATJR i PLANT: "G BUS j LOAD SHED" 3
- ~ ~
N/S 2. WINDOW CG CRDR relabel PLANT: " .. 100ABCD..." l SIM: .. 100 ABCD..." ! 1 2 W 3. WINDOW D8 IS BLANK Due 08/88 i PLANT: "SI CDA LOAD SHEDDING l AUTO START BLOCKING IN TEST" ANNUNCIATOR PANEL 1-EI-CB-21H (78) 3 N/S 1. SIMULATOR HAS NO SPACE CRDR relabel BETWEEN 4 & KV ON THE FOLLOWING WINDOWS: [ ] D8, F3, FS, F6, F7, F8, G5, L/ G7, G8, H4, H5, H7, H8 i _______-_--__D
n
. ATTACHMENT.5 Paga 10 ofL46'
. . )
Priority Status Description Comments { ANNUNCIATOR PANEL 1-El-CB-21J (79) . 1 W 1. WINDOW B2 Due 08/88 ~ - PLANT:."RWST CHEM ADD. TANK , SIM: HI/LO LEVEL" "RWST CHEM ADD TK ] LO LEVEL .l 3 N/S 2. WINDOW H6-DIFFERS FROM CRDR relabel' PLANT BUT MODIFIED BY PEN & INK
... OP" " DELTA" ADDED 3 N/S 3. D-3 SHOULD HAVE A (.) CRDR relabel PERIOD,AFTER 1-P1A, BUT IS MISSING 3 N/S 4. E-4 SHOULD HAVE A (.) CRDR relabel ~
PERIOD, AFTER L-P4,. BUT IS MISSING (~') ANNUNCIATOR PANEL l () 1-EI-CB-21K (80) l 1 W 1. WINDOW G7 IS BLANK ON Due 08/88 SIMULATOR PLANT: " START-UP LOAD SHED TEST" BENCH BOARD 1-EI-CB-01 (BB1-1-34) 3 W 1. N16 MONITOR PANEL (INR) IS Complete by 11/83 MISSI.NG (BB1-1,2)
-3_ N/S 2. LABEL "NI-43B PWR-RNG3" HAS CRDR relabel A DISTORTED "W" IN'"PWR" (BB1-7) i 1 W 3. METER "RNG 2, NI-32B IS Due 08/88 l MISSING TOP SCREW COVER PLATE (BB1-7) !
l l 4
ATTACHMENT 5 Paga 11 of 46
~
%.,j' Priority Status Description Comments 3 N/S 4. TAG " MANUAL SPRAY ACTUATION" CRDR relabel NOT LIKE PLANT, INCLUDES SUBSCRIPTS "2/2 1/1C1PBA1" (BB1-18) , 3 N/S 5. SAFETY COVERS FOR SPRAY Complete by 12/88 ACTUATION AND RESET AND PHASE A ISOLATION ARE ; MISSING (BB1-18) l 3 N/S 6. TAG IS WRONG SHOULD BE CRDR tag may be 36.1 AND 36.10 SIMULATOR reengraved in plant , HAS NO DECIMAL POINT i (BB1-18) 3 N/S 7. PORV PUSHBUTTON MOUNTING Complete by 12/88 4 PLATES ARE WHITE RATHER
^
THAN YELLOW AS IN PLANT / (BB1-19, 24) { 1 N/A N/A 8. LABEL " SAFETY SYSTEM No training value ]' TRIP / RESET" IS DIFFERENT SIZE (LONGER) THAN PLANT f~'} (BB1-18,22) %.J 1 2 W 9. LABELS "LO TAVE... & Complete by 08/88 LO PRZ..." (4) DIFFER FROM PLANT IN SPACING & 1 COLOR DOT LOCATION ! (BB1-22) 3 N/S 10. SIMULATOR: PRODAC Systematic upgrade i PUSHBUTTON SAYS 1
" VITAL PARAMETER" PLANT: " FLASH EVAP2" (BB1-23,27)
N/A N/A 11. SPDS SELECTOR SWITCH IS No impact on training 3 INCHES FURTHER TO LEFT value ON SIM (BB1-23,27) 3 N/S 12. LABEL "CRT DISPLAY CONTROL" CRDR relabel DIFFERS FROM PLANT " CONT" (BB1-27) () t_-
7] d
' ATTACHMENT 5' Paga 121of146
)
( ' Description Comments ipr 10rity Statu s - 1 W- 13. LABELS "HCV-1586, HCV-1201, Due 08/88 HCV-1137, LCV-1115A.& _HCV-1389 DIFFER:FROM NEW PLANT SUBSCRIPTS (BB1-26) 2 N/S 14. SWITCH' HANDLE FOR "TCV-1143" iDue 09/88
' DIFFERS FROM' PLANT (BB1-30) 1 W 15. LABEL "TV-CC-116C" DIFFERS -Due 08/88
'FROM NEW" PLANT LABEL 3 SUBSCRIPTS (BB1-32,33) ]
2 N/S 16. METER' LABELS FOR-RCPP- Due 09/88-B & C ARE INCORRECT SHOULD BE: "1-RC-P-1B" j
< "1-RC-P-1C" (BB1-31) 3 N/S 17. LABEL ABOVE THUMBWHEEL Due 10/88 SWITCHES ON CRT DISPLAY.
CONT DIFFERS FROM' PLANT: " ...LIN SEL" I SIM: "
...LIN SELECT" f
\-- 2 N/S 18. SWITCH PLATE FOR "HCV-1389" Due-09/88 'l SHOULD READ: "VCT P.D.TK" l' (BB1-30) 2 N/S ' 19. SWITCH PLATE:FOR""HCV-1244" Due'09/88 4
SHOULD READ: "VCT IX" (BB1-16) 2 N/S 20. SWITCH PLATE FOR " NORM / DEGAS" Due-09/88 SHOULD READ: " NORMAL DEGAS" RATHER THAN: '" NORM..." l l BENCH BOARD 1-EI-CB-02-(BB2-35-67) N/A N/A 1. LABEL " CALL HP IF OPERATED" Training staff, ', MISSING 3 PLACES ABOVE responsibility! l PCV -MS 101 A, B ' & ' C ( BD2-37 ) 1 W 2. LABEL " EMERGENCY - Due-08/88 l STATION FIRE..." DIFFERS FROM PLANT'(BB2-37): , e u
'I J
'l
ATTACHMENT 5. Pega113 ofE46,
.I VPriority Status Description Comments 2 N/S 3.- LABELS, NEW ON SIMULATOR- See Overall
- DIFFER FROM OLD ON PLANT Comment # 14 l (BB2-37,38,39) l "NRV-MS-101A NRV-MS-101B L NRV-MS-101C "NRV-MS-103A NRV-MS-103B 1 NRV MS-103C "PCV-MS-101A PCV-MS-101B PCV-MS-101C "MOV-FW-154A MOV-FW-154B l MOV-FW-154C" "FCV-1478 FCV-1488 FCV-1498' 2 N/S- 4. LABELS, NEW ON SIMULATOR See Overall DIFFER FROM OLD ON PLANT Comment # 14 (BB2-40,41,42)
MOV-FW-150A MOV-FW-150B MOV-FW-150C 1-FW-P-1A1 1-FW-P-1B1 1-FW-P-1C1 l 1-FW-P-1A2 1-FW-P-1B2 1-FW-P-1C2 0- 1-SD-P-1A 1-SD-P-1C 1-SD-P-2A-1-SD-P-1B 1-SD-P-2B 1-WT-P-3A 1-WT-P-3B FCV-SD101A FCV-SD101B FCV-SD101C MOV-AS-101 1-MS-TV-111A 1-MS-TV-111B .) 1-FW-MOV-100D 1-FW-MOV-100A 1-WT-P-12A 2 N/S 5. LABELS NEW ON SIMULATOR See Overall 3 DIFFER FROM OLD PLANT Comment # 14 l (BB2-45,46,47) l MOV-FW-100D) ] MOV-FW-100A) Same as #9 l 1-Wi-P-12A ) MOV-FW-100B ! 1-WT-P-1A 1-WT-P-1B' MOV-FW-100C HCV-FW-100C R i 1-FW-P-3B 1-FW-P-3A 1-WT-P-2B 1-WT-P-12B l
ATTACHMENT 5' Pago.14 of 46 Piority Status Description Comments 2 N/S 6. SWITCH COVERS (2) MISSING Due'09/88' FROM BOTH PHASE B ISOLATION RESET SWITCHES-(BB2-43)' 2 N/S- 7. LABELS (2)-NEW ON SIMULATOR See Overall "F/W BYPASS' VALVE RESET" Comment # 14 DIFFER FROM OLD ON PLANT (BB2-43) 2 N/S 8. LABELS NEW ON SIMULATOR See Overall DIFFER FROM OLD IN PLANT Comment # 14 (BB2-45,46,47) 1-CD-P-2A. 1-CD-P-3A 1-CC-P-1A MOV-CW-102A MOV-CW-101A 1-VP-P-2A 2 N/S 9. LABELS NEW ON SIMULATOR See Overall DIFFER FROM OLD IN PLANT Comment # 14 ! (BB2-48) 1-CD-P-2A). I 1-CD-P-3A) Same as #21 O- 1-CC-P-1A) 1-CD-P-2B 1-CD-P-3B 1-CC-P-1B FCV-CN-107 2 N/S 10. SWITCH PLATE ETCHINGS IN Due 09/88 PLANT ARE "OFF-ON" WHILE 1-CD-P-3A LEGEND SIM SAYS: CLOSE OPEN 1-CP-P-3B LEGEND SIM SAYS: CLOSE OPEN (BB2-48) l 2 N/S 11. LABELS NEW ON SIMULATOR See Overall l DIFFER FROM PLANT Comment # 14 ' (BB2-49,50) 1-BC-P-1A 1-BC-P-1B MOV-CW-102A,102B,102C,102D MOV-CW-101A,101B,101C,101D 2 N/S 12. LABELS NEW ON SIMULATOR See Overall i DIFFER FROM PLANT (BB2-51) ' Comment'#'14 ' 1-WT-P-12B (same as.#11) ! 1-VP-P-2A (same as #21) l 1-VP-P-2B 1-VP-P-1A 1-VP-P-1B i _ _ _ _ _ _ _ _ _ - - _ - - - _ - - - - i
Pago 15 of 46- f Il J k. Pfiority Status Description Comments 1
'2 N/S 13. LABELS NEW ON SIMULATOR See Overall .f DIFFER FROM PLANT Comment # 14 1 (BB2-53,60) 3 "RSS TO BUS 1A' AMPS" j "RSS TO BUS 1B AMPS" "RSS TO BUS 1C AMPS" ,
"STA SER 1A AMPS" 1
" REG BAL VOLTS" l
" EXCITER VOLTS"
" EXCITER AMPS" "STA SER 1A VOLTS" 2 N/S 14. SWITCHPLATE FOR "1-TM-P-2" Due 09/88
'SHOULD BE " MAN - OFF - AUTO" AS IN PLANT
]
2 N/S 15. SWITCH PLATES FOR 1-VP-P-1A,. Due 09/88 1B,1C DOES NOT HAVE A HYPHEN BETWEEN BACK & UP (BB2-50,51,56) 1 W 16. E H TURBINE CONTROL Systematic upgrade
" MAINTENANCE & OVERSPEED PROTECTION" TEST ~LEDS DO I NOT WORK, ON ALL THE TIME (BB2-59) 1 J
3 N/S 17. LENSE COVER OF " VALVE Due 12/88 TEST LEFT" DIFFERENT THAN PLANT (BB2-59) i PLANT: 1IL - OPEN j IIL --CLOSED SIMULATOR: 11RL - OPEN i IIRL - CLOSED 3 N/S 18. LENSE COVERS OF " VALVE TEST Due .12/88 RIGHT" DIFFERENT THAN PLANT (BB2-59) PLANT: lIR - OPEN 11R - CLOSED-2IR - OPEN 2IR - CLOSED SIM: 1IRR - OPEN IIRR - CLOSED ' 2IRR - OPEN 2IRR - CLOSED O . - - - ~ - - - - _ _ . _ - _ - _ . - . . _ _ - - - . _ - - . . . . . _ . _ _ _ _ _ . _ _ . _ _ -
l ATTACHMENT'5' - d Page 16 of 46 1 I l Priority Status Description Comments' l 3 N/S 19. LABELS NEW ON SIMULATOR See Overall , DIFFER.FROM PLANT Comment # 14 (BB2-54,55,56) )
"1-CN-P-1A 1-CN-P-1B 1-CN-P-1C" "MOV-HS-100" .
"1-GM-P-1 1-GM-P-5" I "1-TM-P-5" "1-GM-P-8 1-GM-P-2 !
1-GM-P-10" "MOV-MS-103 MOV-MS-104" i "MOV-MS-105 MOV-MS-106" "1-TM-P-3 1-TM-P-4" "1-VP-P-1B 1-VP-P-1C" 3 N/S 20. LABELS NEW ON SIMULATOR See Overall' .)' DIFFER.FROM PLANT Comment # 14 (BB2-60,61)
"STA SER 1B AMPS.
STA SER 1C AMPS" "STA SER.1B VOLTS . STA SER 1C VOLTS"
" GEN AMPS PHASE A" 1,
l O " GEN AMPS PHASE B"
" GEN AMPS PHASE C"
" GENERATOR NEUT. VOLTMETER" l
3 N/S 21. LABELS NEW ON SIMULATOR See Overall DIFFER FROM PLANT Comment # 14 (BB2-62,63,64)
"ACB-15A2 ACB-15B2 ACB-15C2"
" SYNCHRONIZING -
ACB-15A2 ACB-15B2 ACB-15C2" -i "4KV STA TRANS-A,B,C - VOLTS" :
- "ACB-15A1 ACB-15B1 ACB-15C1" l
"ACB-ASD1 ACB-15El ACB-15F1"
" GEN NEUT VOLTAGE..."
3 N/S 22. LABELS NEW ON SIMULATOR See Overall DIFFER FROM PLANT Comment # 14 (BB2-65,66,67)
" MAIN GEN BKR'SW-1-G12" .!
" MAIN CEN BKR SYNC SW 25-G12"
" MAIN GEN BKR... 43-G12"
" EXCITER FIELD ACB" l
" GENERATOR VOLTS" -!
g q
L. ATTACHMENT 5. Page 17 of 46 l
^ ' Priority Status Description Comments 1 W 23. LENSE COVER " AMBER" DIFFERS Due 08/88:
FROM " WHITE IN PLANT ABOVE
" VOLTAGE REGULATOR CONTROL" (BB2-66) 2 N/S 24. LABELS NEW ON SIMULATOR . Sc3 Overall DIFFER FROM PLANT Comment # 14 i "34.5KV SHUNT l
~ REACTOR NO.1..." l L "34.5KV. SHUNT REACTOR NO.2..."
"34.5KV SHUNT REACTOR NO.3..."
"34.5KV SHUNT REACTOR NO.4..."
"34.5KV SHUNT i REACTORS 1 & 2..."
"34.5KV SHUNT REACTORS 3 & 4..." j J
1 N/S 25. REMOVABLE SYNCHRONIZING l SWITCH HANDLE (SYNC KEY) 1 PLANT HAS PIECE WELDED ONTO Install by 08/88 ] SYNC KEY AND ALL THOSE
\ PIECES WERE TAKEN OFF OF j
. SWITCHES'BECAUSE ONE FELL OFF THE SWITCH AND DOWN INTO {
THE BOARD WHICH COULD HAVE CAUSED A TRIP (BB2-65) VERTICAL BOARD #1 NIS (VB-68-79) l 3 N/S 1. SOURCE RANGE DRAWERS N31 & CRDR relabel N32 SWITCH LABELS ARE WHITE (LETTERS) ON BLACK (BACKGROUND) WHERE AS PLANT HAS BLACK ON WHITE , (VB-71,74) j 2 N/S 2. LABEL "118V.2A,AC AUDIO Due 09/88 CHANNEL POWER" ON SIMULATOR IS MISSING ON PLANT PHOTO (VB-78) 3 N/S 3. BLACK ON WHITE LABELS FOR CRDR relabel
" SUPPORT HEATERS" DIFFER FROM PLANT WHICH ARE WHITE ON BLACK (V1-80)
O E___._________________ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _._ _ . _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _j
. . =-
ATTACHMENT SJ ~ o L Paga:18.off46 I l
" Comments Priority Status Description
'1 N/S 4. SWITCH PLATES'FOR "NIS REC Due 08/88 ;
SEL RED / BLUE PEN" ARE-( REVERSED FROM PLANT SIM: DELTA F IV ON 1/N 45 DELTA F III.ON 2/N 45 (V1-84) ; 1 W 5. LABEL BELOW FUSES ON-N43B Due 08/88
" POWER RANGE B" SAYS
" CONTROL" SHOULD BE: "118V.5A.AC INSTR POWER" 1 1/8" X 3 1/8" WHITE ON BLACK (V1-75) 3 N/S 6. BLACK ON WHITE LABELS ON CRDR relabel "RCS TMP - LOOP A,B & C METERS DIFFER FROM WHITE- ] '
ON BLACK. LABELS ~AS THE' - PLANT. SAME DIFFERENCE I NOTED ON: " BORIC ACID"
" LEAK OFF TEMP" "RCS PRS"
" PRESSURE PROT" O'" " PRESS CONTROL" & !
" LEVEL" METERS (V1-87-89) i I
1 W 7. BLACK ON WHITE LABEL "PCP Due 08/88 INLET HDR" IS MISSING ; (VB1-109)- N/A N/A. 8. GRAY FRONT DOOR OF N/A
"#1 SEAL C1 LEAK-OFF" RECORDER DIFFERS FROM PLANTS BLACK FRONT (V1-128) 3 N/S 9. BLACK ON WHITE LABEL IN CRDR relabel WINDOW OF " REACTOR ~ COOLANT.
PUMP" RECORDER DIFFERS FROM WHITE ON. BLACK LABEL IN > I PLANT (V1-132) 1 N/G 10. "VV PIT SUMP PUMP 1-DAP6A" Due 08/88 LABEL ON SIMULATOR IS 1 MISSING FROM PLANT PHOTO 1 V1-123) ! i
ATTACHMENT :5
- Page 19_of 46 q O'iority Pr Status Description Comments 1 W 11. '"L1-1112-1" METER LABEL'IS Due 08/88 MISSING (V1-114) 3 N/S 12. TAG FCV-GN100 SIMULATOR Due 12/88 HAS' HYPHEN BETWEEN GN & 1001 2 N/S 13. RECORDER SCALE FOR." BLENDER- Due 09/88' FLOW" IS 0-10 WHICH DIFFERS FROM-PLANT THAT-IS 0-20 (V1-122) THIS WILL REQUIRE SOFTWARE CHANGE & TAG. CHANGE SHOULD FOLLOW VERTICAL BOARD'#2 1-El-CB-04 (V2-134-184) 2 N/S' 1'. "HTX RTN TMP" "A" LABEL IS Due 09/88-l IN PLACE BUT NOT IN PLANT !
PHOTO (V2-135) ) 1 N/,S 2. LABEL "STM GEN WIDE RANGE Due 08/88.
'LVL" IS LOCATED ON RECORDER DOOR.RATHER THANJABOVE-RECORDER'AS IN.THE PLANT L -
; (V2-152) 1 N/S 3. LABEL'" TREND RECORDER'B"'IS Due 08/88:
MISSING FROM FRONTiOF RECORDER DOOR'(V2-143) , l 2 N/S 4. LABEL "1-NS-LCV-101" NEW ON See'Overall. 1 ! SIMULATOR DIFFERS FROM OLD -Comment # 14 1 , IN PLANT: "LCV-NS101" j (V2-141) l 3 N/S 5. LABELS "MOV-CC100A & CRDR relabel MOV-CC100B" HAVE SPACE : l BETWEEN "CC" & "100" l (V2-145) , i 1 N/S 6. BLACK ON WHITE LETTER Due 09/88 i SPACING & SIZE OF "DRLIN"
. SWITCH LABELS DOES NOT MATCH PLANT LABELS (V2-178)-
PLANT: MOV-SD-100A SIM: MOV-SD-100A 1H1-1B3 <-- SIZE -----> MOV-SD100B MOV-SD-100B ! ETC. THRU: MOV-SD102D MOV-SD-102D
l 1 ATTACHMENT 5 Paga 20 of 46
]q l
I (~y () Priority Status Description Comments 4 3 N/S 7. ALL MOV SD 100 & 102 CRDR relabel l SERIES TAGS HAVE HYPHENS. j
~
TAGS HAVE NO SPACE BETWEEN NO & 1, 2, 3, 4 ) ETC. (V2-178) 3 N/S 8. ALL TV ES 100 & 102/103 CRDR relabel SERIES VALVES HAVE UYPEEN BETWEEN ES & 100/102/103 1 (V2-179) . 1 N/S 9. PR-MS-102 MAIN STEAM PRESS Due 09/88 RECORDER SCALE 0-150 j SHOULD BE 0-1500 IN J INCREMENTS OF 300 LINEAR ! (V2-166) 1 N/S 10. PI LO 100 HAS TAG AT Due 09/88 ! SIMULATOR NONE IN PLANT l 1 N/S 11. SIMULATOR: HAS SINGLE SCALE Due 09/88 ON STEAM GEN RECORDERS I CONTROL ROOM: HAS DUAL SCALE, BUT BOTH ARE 0-5 (V2-154) ("N N/A N/A 12- SIMULATOR CH III & IV BLUE & No training impact YELLOW DOTS ARE NOT AS LARGE l (V2-156,157) l l N/A N/A 13. RIGHT OF "LCV-CN-104 Complete via upgrade SIMULATOR DOES NOT HAVE for system 1f SQUARE HERE. applicable or as DCP is incorporated 3 N/S 14. BLACK ON WHITE LETTERING OF CRDR relabel "MOV-ES-101-104" SW3TCH LABELS DOES NOT MATCH PLANT LABELS PLANT: MOV-ES101A & B MOV-ES102A & B MOV-ES103A & B MOV-ES104A & B SIM: MOV-ES-101A & B MOV-ES-102A & B MOV-ES-103A & B MOV-ES-104A & B (V2-167) l I o
ATTACHMENT 5 Pago 21 of 46 f NE1ority Status Description Comments N/A N/A 15. BLACK ON WHITE " UNIT 1 LOAD CRDR relabel RECORDER" TAG IS WHITE LETTERING ON BLACK IN PLANT (V2-175) 1 N/S 16. LABELS "COND PRESS" & MAIN Due 08/88 STEAM TEMP" ARE MOUNTED ON RECORDER DOOR RATHER THAN ABOVE RECORDER IN PLANT (V2-153,165) 3 N/S 17. BLACK ON WHITE LABEL CRDR relabel "TR-MS101-1..." RECORDER ID. IS WHITE LETTERS ON BLACK IN PLANT (V2-165) N/A N/A 18. SIMULATOR RECORDER FOR No training impact MEGAWATTS IS A NEW IMPROVED MODEL L & N (V2-175) VERTICAL BOARD 3A/B 1-El-CB-05 (V3-185-2391 1 W 1. TOP END METER COVER MISSING Parts on order j FROM PI-LM 110A (V2-191 ) j 1 1 N/S 2. ZONE BANDING ON " ACCUMULATOR Due 08/88 I A,B, & C LVL" METERS L1-1920, { L1-1924 & L1-1928 ARE NOT l ON PLANT METERS (V2-191, 192) ' i N/A N/A 3. SIMULATORS LAMP NOT No training value INSTALLED IN PLATE l FOR "MOV-1890A" i (V2-195) 2 W 4. LhbELS OLD ON SIMULATOR See Overall DIFFER FROM NEW IN PLANT: Comment # 14 (V2-198-200)
"H1C-1947" "TV-BD-100A TV-BD-100C TV-BD-100E" "TV-CV-150A TV-CV-150C" "TV-SI-101" "TV-DA-100A" "TV-LM-100A TV-LM-100C TV-LM-100E" l
i __ _ - _ _ _ _ _ _ _ _ _ _ _ - _ _ _ -
i 7. ATTACHMENT'5 Paga 22 of-:46' 1 Priority , Status Description ' Comments "TV-LM-100G TV-LM-101 A &'C" "TV-VG-100A"'
"TV-MS-110A" "TV-RM-100A- TV-RM-100B" "TV-SI-100A"'
"TV-MS-109A" "TV-1859" "TV-SS-100A TV-SS-101A TV-SS-102A" "TV-SS .104A TV-SS-106A "TV-SS-104A- TV-SS-106A TV-SS-112A' "TV-1519A "TV-MS-101A-1 TV-MS-113A-1"-
"SOV-1-2-1" N/A N/A 5.. SPACING FOR INDICATOR LfMPS No training value FOR."MOV-1890A & MOV-1869A" IS.LESS THAN 1/26 AS IS'THE PLANTS'(V2-195) , '
1 W 6. LABEL "FI-1943-1" IS MISSING. Due_08/88
- l. FROM METER- (V2-201 )
1'
\ 2 W 7. BLACK ON WHITE " SERVICE'WTR' Due 09/88 PP1A"' LABEL ~DOES1NOT' MATCH PLANT LABEL.
PLANT:~" SERVICE WATER PUMP 1A"' SIM: SERVICE WTR PP1A - 1 W 8. " SERVICE WATER PUMP 1A"r Due108/88-LABELS ARE PAPER & NEED-TO l BE REPLACED: V2-202-204 l PI-SW112A PI-SW114A. PI-SW116A PI-SW118A FI-SW110A~ PI-SW108A N/A -N/A 9. SIMULATOR DOES NOT HAVE .No training value: LIGHT MOUNTED IN SQUARE - PLATE OF MOV-1865A,B,C 1 W 10. LABEL'"RS'HX A & C" DIFFERS Due 08/88: FROM PLANT PLANT: "RS HX A & D SIM:~ RS HX A & C-(V2-206) O
/
ATTACHMENT 5 { Pago 23 of 46 l rh Priority Status Description Comments Due 08/88 j 1 W 11. LABELS & SCALES DIFFER FROM PLANT FOR METERS: j PLANT: TI-SW-100D ! FI-SW-100D 1 SIM: TI-SW-100C l FI-SW-100C l (SWAPPING METERS BETWEEN 3A
& B PANELS CAN CORRECT THIS PROVIDED SOFTWARE HAS BEEN CHANGED) l 2 N/S 12. LABELS OLD ON SIMULATOR Due 09/88 DIFFER FROM NEW IN PLANT l BY WORDING AND FORMAT "HCV-1850A HCV-1850C" "HCV-1850D"
~
1 N/S 13. LABELS HAVE "B" HDR ETCHED Due 08/88 i WHILE WRITTEN ON PLANT FOR: j "MOV-SW-101C" !
"MOV-SW-105A" J N/S ' 14. LABELS HAVE "A" HDR ETCHED Due 08/88 j WHILE WRITTEN ON PLANT FOR: ;
f.-).1
\-- "MOV-SW-101A" i "MOV-SW-105C" 3 N/S 15. LABELS "PI-LM., 110B HAS NO CRDR relabel SPACE BETWEEN 110 & B WHILE PLANT DOES (V2-218) 3 N/S 16. LABEL "LI-DA-110B" HAS CRDR relabel HYPHEN BETWEEN DA & 110B WHILE PLANT DOES NOT (V2-216) 3 N/S 17. LABEL "LI-DA-111B" HAS CRDR relabel HYPHEN DA & 111B WHILE PLANT DOES NOT (V2-216) 1 N/S 18. FI-CV-150 SIMULATOR SAYS Due 08/88 ISO (V2-223)
N/A N/A 19. UNLABELED COUNTER LEFT OF No training value METER FI-CV-150 HAS SCREWS MISSING (V2-222,223) p
ATTACHMENT 5 . Paga 24 ofi46-j . .O Pfiority Status- Description Comments . s [ j N/A N/A- 20. .TV-SV-103 PUSHBUTTONS LNo training value [ " SPARE-TEST" ENGRAVED AT. I SIMULATOR, LABEL MAKER WAS, 1 USED IN MAIN CONTROL ROOM . (V2-225) 1 N/S 21. . LABEL "TV-1884B" OLD ON Due 08/88-
. SIMULATOR DIFFERS FROMJ
.NEW IN PLANT-(V2-222) 1 1 N/S 22. . LABEL " HIC-LM-101B" OLD ON Due 08/88 SIMULATOR DIFFERS-FROM NEW i IN PLANT (V2-223) j N/A N/A 23. LAMP " VALVE MONITOR #1" NOT No training value MOUNTED ON PLATE AS IS PLANT (V2-222) 1 W 24. LABELS OLD ON SIM DIFTER Due 08/88 FROM NEW IN' PLANT: 3 "TV-BD 100B TV-BD-100D '{
TV-BD100F" d "HCV-1936 -j "TV-DA-100B" "TV-DG-100B" "TV-LM-100B TV-LM-100D" "TV-LM-100F TV-LM-100H" "TV-LM-1016&D" "TV-LM-100B&D" "TV-MS-110" .
"TV-RM-100C 'TV-RM-100D" "TV-1204" "TV-SI-100B" "TV-MS-109" "TV-1849" "TV-SS-100B TV-SS-101B TV-SS-102B "TV-SS-103B TV-SS-104B TV-SS-106B" "TV-SS-112B" "TV-MS-101A-2 TV-MS-113A-2"
...SI-RESET" "TV-MS-1-1B-2 TV-MS-113B-2" "TV-SV-103" "TV-MS-101C-2 TV-MS-113C-2" D
ATTACHMENT 5 Page 25 of 46
\
Pflority Status Description Comments 1 N/S 25. SWITCH PUSH BUTTON Due 08/88 "HCV-1936" DIFFERS FROM PLANT: OPEN PERM SIM: PERM (SIMULATOR LABEL PAPER) (V2-224) N/A N/A 26. SWITCH PUSH BUTTONS No training value "TV-SV-103" ARE ETCHED
" SPARE - TEST" WHILE PLANT USE LABEL TAPE (V2-225)
N/A N/A 27. DIGITAL READOUTS No training value "PL-LM1D1B1 & 2" ARE NOT PLATE MOUNTED AS IN PLANT (V2-223) 1 N/S 28. LABEL " HIC-LM-101B" Due 08/88 DIFFERS FROM NEW PLANT LABEL BY WORDING AND FORMAT (V2-2?3) W " SERVICE WATER" LABEL Due 08/88 01 29. DIFFERS FROM PLANT:
" SERVICE WATER PUMP 1B" SIM: " SERVICE WATER PP1B" (V2-226-228) 1 N/S 30. LABEL " INST AIR COMP PRS" IS Due 08/88 ENGRAVED SAME AS PLANT BUT PLANT HAS " CONTAINMENT" PEN / INKED IN (V2-227) 1 W 31. LABEL MISSING FROM 0-1000 Due 08/88 METER "FI-1940-1" WHICH IS IN REVERSED LOCATION WITH "FI-1943" 0-10 METER l (V2-226,227)
N/A N/A 32. SPACING BETWEEN "FI-1963" & No training impact "FI-1943" (UNLABELED "FI-1940-1) DIFFERS FROM PLANT (V2-226,227) 1 W 33. LABELS "HDR 1B1 PR & Due 08/88 HDR 1B2 PR" MODIFIED BY PAPER LABEL (V2-226-228) O
ATTACHMEN'T'S-Paga 26 of.46 i ' ^
- (Pilority
) Status ' Description Comments 1 W 34. LABELS MISSING (NOW'IN PAPER) Due 08/88 "PI-SW113B" "PI-SW115B" "PI-SW117B" "PI-SW119B" "FI-SW104B"
'"TI-SW107B" "TI-SW1093" "FI-SW111B" "PI-SW109B" l
(V2-228) \ 3 N/S 35. LABEL DIFFERS CRDR relabel' ; PLANT: "LI-DA113B SIM: "LI-DA-113B 1 W 36. LABEL "RS HX B & D" DIFFERS Due 08/88 FROM PLANT PHOTO WHICH. READS "RS HX B & C (V2-230) i 1 W 37. LABELS DIFFER FROM Due 08/88 PLANT: "TI-SW-100C" "FI-SW-100C"
,Q SIM: "TI-SW-100D"
! (_/ "FI-SW-100D" (V2-230) 1 W 38. LABEL SCALES OF METERS Due'08/88 DIFFER FROM: PLANT FOR: ' " 1 "TI-SW-100D" "FI-SW-100D" (BOTH REFERENCE'"C" RATHER THAN "D")-(V2-230) N/A N/A 39. BLANK PANEL MISSING No training' impact BETWEEN METERS "LI-DA113B & LI-SW-101B" i (V2-231) 3 N/S 40. SWITCH PLATES " RESET" Due 08/88 l MISSING (2)-FOR."51/CDA 1 LOAD SHED" PUSHBUTTONS ; l 1 N/S 41. LABELS DIFFER BY WORDING Due 08/88 AND FORMAT'FROM-PLANT "MOV-SW-101B" "MOV-SW-101D" "MOV-SW-105B" "MOV-SW-105D" ;
ATTACHMENT 5 Pago 27 of 46 '! l i-m . 1 Priority Status Description Comments 3 N/S 42.- LABEL DIFFERENCE CRDR relabel H PLANT: " ...VV" . l MOV-QS101B SIM: " ...W" 1 j MOV-QS-101B . 3 N/S 43. LABEL DIFFERENCE CRDR relabel PLANT: " ...VV" MOV-QS-1008 SIM: " ...W" MOV-QS-100B 3 N/S 44. LABEL DIFFERS CRDR-relabel PLANT: " ...VV MOV-RS156B SIM: ...W" MOV-RS-156B 3 N/S 45. LABEL DIFFERENCE CRDR relabel PLANT: " ...VV" MOV-RS 155B SIM: "
...W" MOV-RS-155B 3 N/S 46. LABEL DIFFERS CRDR relabel PLANT: LI-DA110B' SIM LI-DA-110B 3 N/S 47. LAB'EL DIFFERS CRDR relabel j PLANT: LI-DA111B '
SIM: LI-DA-111B VERTICAL BOARD #2 ! P.A.M. (V2-234-239) ' 1 N/S 1. ALL SWITCH LABELS DIFFER Due 08/88 FROM PLANT BY NOT INCLUDING < VARIABLE DESIGNATION, COLOR l POWER SOURCE l 1 W 2. BLACK OUTLINE MATERIAL OF Due 08/88 REACTOR VESSEL DOES NOT i ENCOMPASS SWITCHES & R INDICATORS FOR TV-HC101A & l TV-HC102A (V2-236,237) l ( } i
.s ATTACHMENT 5 l Page 28 of 46 '
I' )
'\ /
l) Priority Status Description Comments 1 N/S 3. POWER ON INDICATOR LABEL Due 08/88 1 "TV-HC 100A...ETC." ARE 1 MISSING (V2-239) 1 1 N/S 4. METAL SWITCH LABELS "CLOSE Due 09/88 1 I OPEN" ARE MISSING FROM HI RAD SAMPLE SWITCHES 1 N/S 5. MISSING HORIZONTAL BLUE Due 08/88 OUTLINE MATERIAL CONNECTING ! SWITCHES TV-HC108A & TV-HC108B . LIQUID WASTE 1-EI-CB-12 (LW 1-18) 2 W 1. L & N 2500 RECORDER To be installed (ASSOCIATED WITH N16 MONITOR in conjunction i PANEL) IS MISSING AI@NG WITH with N16 monitor APPROPRIATE LABELS 3 N/S 2. HAGAN RECORDER "LW-FR-104" Due 12/88 ) IS MOUNTED INCORRECTLY l (~D SHOULD BE BELOW TOP RIGHT l l \- RECORDER (LW-1) ) l 1 W 3. TOP LEFT RECORDER Due 08/88 ;
"LW-FR-109..." EXTRA SCALE !
0-100 LABEL DOTS NOT COLORED l WRONG CHART SHOULD BE 0-10 ONLY (LW-1) 1 W 4. MID RECORDER "LW-PR-118..." Due 08/88 EXTRA SCALE 0-150 SCALE DIFFERENT 0-200 PLANT: 0-140 & 0-120 LABEL MOUNTED INCORRECT (LW-1) 1 W 5. TOP RIGHT RECORDER Due 08/88 "GW-FR-101..." LABEL DIFFERS FROM PLANT SCALE 0-3 DIFFERENT GRADUATION 3 EXTRA SCALE 0-150 (LW-1) 78 v)
ATTACHMENT SJ Page 29 of 46: Piiority Status Description Comments 1 W 6. BOTTOM LEFT' RECORDER Due 08/88 "GW-02R-102..." i LABEL DIFFERS FROM PLANT SCALE 0-5 MISSING 2ND' SCALE 0-100 WRONG q CHART 0-10 SHOULD BE: .i 0-5 LINEAR (LW-1) } N/A N/A 7. COUNTERS DIFFER IN COLOR & No training'value MOUNTING FROM PLANT: 1-BD-FTD-101 1-HV-FTD-1212A 1-LW-FTD-104 ! 1-GW-FTD-108 (LW-2) :{ i 2 N/S 8. IPAC COUNTER FRONTS DIFFER Due 09/88 FROM PLANT & LABELS MOUNTED ABOVE RATHER THAN ON COUNTER AS IN THE PLANT (LW-2) 3 N/S 9. LABEL "TR-GW-101..." ON -Due-12/88 RECORDER DOOR.NOT IN t PLANT. NO CHART AS RECORDER-O J
' UNUSED (LW-3,4) l1 3 N/S 10. LABEL FOR RECORDER POINTS Due 12/88 MISSING FROM "TR-LW-101..."
NO CHART AS RECORDER UNUSED RECORDER FRONT GREY WHILE i BLACK IN PLANT 1 W 11. METER SCALES Due 08/88 "1-GW-PI-109A-109D" DIFFER FROM PLANT IN THAT SCALES READ 0-150 & 0-120 WHERE AS PLANTS READ 0-250 & 0-200 g ( LW 8 )
]
1 W 12. OPERATOR AID TAGS MISSING Ordered tags l
" FILLING" Due 08/88- !
"RECIRCING" 1
. "ON SERVICE" I " TANK ON HOLDUP" l "ON SERVICE" "DO NOT PUMP"
]
l () i
- 1 1
' ATTACHMENT SP PagaL30 of,46 a
4 xP ority Status Description Comments ') 2 W 13. WINDOWS GW-E2,E4 Due 08/88 , BLANK IN PLANT: ) CATALYTIC WASTE GAS -l RECOMBINER DECAY TANK j OUTLET SIDE H1-02 .j H1-H2 j (LW-9) 2' N/S 14. WINDOW H4'" REACT COOL SYS DueLO8/88 UNITS-1-2..." NOT IN PLANT 3- N/S 15. RECOMB PREHTR CONTROLLERS- Due 12/88 AND: LABELS DIFFER FROM PLANT BY. MANUFACTURER, APPEARANCE, AND. TYPE
" TIC-GW-102"
" TIC-GW-103"- .
j
" TIC-GW-104" (LW-13,14)
J 2 N/S 16. SWITCH PUSHBUTTON Due 09/88 "1-GW-FCV-101" ETCHED " CLOSED" WHILE , PLANT IS ETCHED'" MODULATE" O (LW-18), ,
.j BORON RECOVERY 1-EI-CB-13 (BR-19-36) !
3 N/S 1. BLACK ON WHITE LABEL- . CRDR relabel' b "1-EI-CB-13" DIFFERS FROM
' PLANT WHICH IS WHITE ON BLACK 1 W 2. WINDOWS B-F2, G3 Due 08/88 J DIFFER FROM PLANT' PLANT:-PRIM DRAIN XFER FLTR :
DIFF PRESS J SIM: FLTR. UNIT 1- -) HI DIFF PRESS , I PLANT: ... UNIT 2 HI DIFF PRESS SIM: " BLANK" 3. N/A N/A SETPOINT POT MISSING FROM Not used in plant' j 1-BR-PCV-118B i l ' - ([) l l
ATTACHMENT 5' ! Page'31 of 46 j 4 i 3r (P lority Status Description Comments 1 N/S 4. SWITCH LABELSL1-BR-EV-1A. Due 08/88 1
&11B DIFFERS FROM' PLANT (2 LABELS NEARLY SAME. 1 j
UNDER DIFFERENT SWITCHES- ' PUMP & MODE SELECT) 2 N/S 5. SWITCH LABEL TV-BR121C DIFFERS FROM PLANT WHICH- See'Overall~
.IS OLD LABEL Comment'#'14' 3 N/S 6. ' INDICATOR MISSING:.FROM Due 12/88 MICROPHONE PANEL-(BR-19) 3 N/S 7. MICROPHONE PANEL LABEL- Due 12/88
" UNIT 1 (UNIT 2)..."
DIFFERS FROM PLANT (BR-19). 1 N/S 8. RECORDER LABELS DIFFER Due 08/88 FROM PLANT. DOTS ARE NOT COLORED i 1 N/S 9. TOP LEFT RECORDER OLD SIM Due'08/88 f O LABEL DIFFERS FROMLNEW PLANT LABEL, SCALE NOT IN MIDDLE OF. CHART WINDOW 0-100 (BR-21) 1 N/S 10. TOP RIGHT RECORDER NEW-LABEL' Due.08/86 DIFFERS FRO:4 OLD BLACK PLANT, SCALE 0-300 GRADUATIONS DIFFER SCALE NOT IN MIDDLE OF CHART WINDOW (BR-21) 0-100 N/A N/A 11. COUNTER "1-BR-FTO-110" No training value DIFFERENT COLOR & MOUNTED DIFFERENTLY (BR-32) 3 N/S 12. TEMP RECORDER SCALE Systematic upgrade DIFFERENT GRADUATIONS, COLOR & NO. CHART BUT-IS NOT USED (BR-36) RADIATION MONITOR 1-EI-CV-49C,A,B(RM-37-40) 1 N/S 1. RAD MONS DO NOT RESPOND Due 08/88 PROPERLY WHEN PLACED IN
" PULSE CAL" O
^ ATTACHMENT 5 Page 32 of 46.
O Priority . Status Description Comments 2 N/S 2. FUZE HOLDERS ARE INSTALLED Due 09/88 ] IN " LIQUID MONITOR 1-RM-SW-109 OF SIM:'BUT REMOVED IN PLANT PHOTO (RM-39) N/A N/A 3. BOTTOM BLANK PANELS'OF No training value SIMULATOR MISSING THESE SCREWS IN 16 PLACES (RM-40,44) - 3 N/S 4. THIS AGASTAT TIMER DOES- Do via system upgrade NOT WORK IN AUTO CONTROL ] MANUAL IS OK, ALSO SIMULATOR SAYS OMRON INSTEAD OF AGhSTAT (RM-38) i 1 N/S 5. LABEL'(ILLEGIBLE, WHITE ON Due 08/88 BLACK) IS MISSING FROM RIGHT SIDE OF " AREA MONITOR - SPARE, RMS 165" (RM-41,42) 1 N/S 6. " SPARE - AIR PARTICLE Due 08/88 O \/ MONITOR" RACK IS MOUNTED BELOW RR100 RECORDER RATHER I THAN ABOVE 1-RM-CH-12 RACK AS IN THE PLANT. A BLANK PANEL IS MOUNTED BELOW RECORDER IN PLANT (RM-43,44) 1 W 7. RACKS MOUNTED BELOW RECORDER Due 08/88 RR100 ARE " AIR PARTICLE MONITOR" & UNIT 2 VENT STACK MONITOR WHILE IN THE PLANT IS A BLANK & SMALL ELECTRONIC l PANEL (RM-43,44)- I 1 N/S 8. LABELS MISSING FROM Due 08/88
" VENT STACK "B" PANEL "1-RM-VG-113"
" VENT STACK "B" INPUTS..." ;
" LAMP #3451019" "FOR NORMAL OPERATION START BOTH-PUMPS SIMULTANEOUSLY" "RM-VG-112..."
"SCINT" (RM-44)
O
ATTACHMENT 5' Pago 33 of 46 Priority Status Description Comments 3 N/S 9. AGASTAT FACINGS'ARE Systematic upgrade DIFFERENT THAN PLANT (RM-43) 3- N/S 10. LONG. LABEL ABOVE AGASTATS No training value DOES NOT SHOW IN PLANT PHOTO (RM-43) VENTILATION PANEL 1-EI-CB-07 (VP-45-50) . 1 N/S 1. AREA PIPING (BLACK & WHITE Due 08/88 STRIPE & RED /& WHITE STRIPE) DOES NOT APPEAR IN PLANT PHOTO, EXCEPT AROUND
" AUX", " FUEL", ETC. .
(VP-45,46) 1 N/S 2. LABEL "GE-327 23V... DOES Due 08/88 NOT APPEAR IN PLANT PHOTO I (VP-45) l s 1 N/S 3. AREA PIPING AROUND " SERVICE Due 08/88 WATER..." SWITCH IS NOT IN PLANT (RED / WHITE) (VP-46) 1 N/S 4. SWITCH PLATE'FOR Due 08/88 "1-CC-TV-115A,B,C" IS NOT PAINTED GREEN (VP-46) 1 N/S 5. LABEL "1-HV-F-8A" DIFFERS- Due 08/88' FROM PLANT PHOTO (VP-47) '. I 1 N/S 6. LABEL "1-HV-MOV-111A/113A" Due 08/88 DIFFERS FROM PLANT PLANT: ".. 0UTLET VALVE..." ) SIM: "... OUTLET VLV..." (VP-48) 2 N/S 7. NEW LABEL "1-HV-F-57A" See Overall VERBAGE DIFFERS FROM OLD Comment # 14 PLANT (VP-50) 2 N/S 8. NEW LABEL "1-HV-F-57B" See Overall J VERBAGE DIFFERS FROM OLD Comment i 14 i PLANT (VP-50.) H l j
ATTACHMENT 5' Paga 34 of~46
.Fr'iority Status Description Comments 2 N/S 9. NEW LABEL "1-HV-F-57B" See Overall VERBAGE DIFFERS FROM OLD Comment # 14 PLANT (VP-50) 2 N/S 10. NEW LABEL "1-HV-F-57D" See Overall VERBAGE DIFFERS FROM OLD Comment # 14 PLANT (VP-50) 2 N/S 11. NEW LABEL "1-HV-E-3B" See Overall DIFFERS FROM OLD PLANT' Comment # 14 (VP-50)
EMERGENCY GENERATOR 1J 1-EI-CB-08B (DJ-51-55) 1 N/S 1. LABELS "PO1 & PO2" ARE NOT Due 08/88 LOCATED ALONGSIDE INDICATORS AS IN PLANT PHOTO (DJ-51) 1 N/S 2. START INSTRUCTION - LABEL Due 08/88 DIFFERS IN VERBAGE & APPEARANCE FROM PLANT PHOTO (DJ-53) ( )1 N/S 3. LABEL " SHUTDOWN RELAY Due 08/88
. STATUS LIGHT" DIFFERS FROM PLANT PHOTO (DJ-53) 1 N/S 4. LOCKOUT RELAY NEEDS TO'BE Due 08/88 MADE FUNCTIONAL (DJ-54,55) 1 N/S 5. LABEL FOR " MOTOR OPERATED- Due 08/88 POTENTIOMETER DEFEAT SWITCH" NOT IN PLANT. SWITCH PLATE .)
ETCHED "STOP - START" WHEREAS PLANT: " MANUAL - AUTO" (DJ-54) N/A N/A 6. INTERNAL ASSEMBLIES ARE No training value MISSING FROM "DIFF RELAY - PHASE A,B &.C"
...OVER CURRENT RELAY'- '
PHASE A,B,C" (DJ-55) a a = - - _ - - _ - _ _ _ _ _ - _
]
ATTACHMENT 5 Pago 35 of 46 b Pilority Status Description Comments TURBINE SUPERVISORY I 1-EI-CB-10-(TS-56-60) ] N/A N/A 1. IN REAL CONTROL ROOM WHEN Lov training value IURBINE ANNUNCIATOR COMES IN A LOUD RELAY CLICKS IN THAT CAN BE HEARD THROUGHOUT THE-CONTROL ROOM. SIMULATOR DOES NOT HAVE THIS FEATURE 1 N/S 2. LABEL " MULTIPLY TURBINE Due 08/88 SPEED SCALE BY.0.5 IS LOCATED IN WRONG POSITION ALONG SIDE RATHER THAN BELOW (TS-59) 2 N/S 3. . LABELS " REC /SGV SHAFT SPEED See.Overall-
& GOV VV POSITION" & " REC /RP Comment #'14 ROTOR POSITION DO NOT APPEAR IN PLANT PHOTO (TS-59) 3 N/S 4. " SPEED, VIBRATION & Minor training value ECCENTRICITY" METER FACE CRDR relabel LABELING DIFFERENT THAN PLANT BY WORDING. (TS-59,60) 1 N/S 5. " ADDITIVE VALVE POSITION" Due 08/88 ;
SWITCH " SPEED / VALVE, SPEED ONLY" HAS BEEN REMOVED IN PLANT (TS-60) EMERGENCY GENERATOR 1H 1-EI-CB-OBA (DH-61-65)
.i 2 N/S 1. SMALL LABEL" -EMER GEN 1H See Overall i
" DOES NOT. APPEAR IN PLANT Comment # ' 14 PHOTO i 1
2 N/S 2. LABEL "4160V EMER GEN See Overall . SUPPLY... SYNCHRONIZING Comment # 14 1 15H2" NEW ON SIM DIFFERS - FROM OLD IN PLANT (DH-62) 1 N/S 3. LABEL "4160V EMER BUS Due 08/88 1H.. 15H2" OLD ON SIM DIFFERS FROM NEW IN PLANT- 3 (DH-62) ' i
ATTACHMENT 5 Page 36 of 46 (-)/ (Priority Status Description Comments 1 N/S 4. METAL LABEL WITH DIESEL Due 08/88 RESTART INSTRUCTIONS DIFFERS FROM PLANT LABEL VERBAGE (DH-63) 2 N/S 5. LABEL " SHUTDOWN RELAY STATUS See Overall LIGHT" DIFFERS FROM PLANT Comment # 14 PHOTO OLD LABEL (DH-64) 1 N/S 6. SWITCH PLATE ETCHED "ON-OFF" Due 08/88 WHILE PLANT: " MANUAL - AUTO" FOR " MOTOR OPERATED POTENTIOMETER... SWITCH" VALVE MONITORING 1-EI-CB-190 (YMS-66-67)
.N/A N/A 1. VALVE MONITORING RACKS No training value "SV-1551A THRU PORV 1456" & l SV-2551A THRU PORV 2456" ARE MISSING (VMS-66) 3 N/S 2. CHANNEL SELECTOR KNOBS ON Minimal training value
[__ SWITCH PANEL DIFFER FROM PLANT ,
\ (VMS-67) l N/A N/A 3. GAIN KNOBS ARE MISSING FROM No training value j SPEAKER PANEL. SONALERTS ARE i NOT WIRED NOR FUNCTIONAL ON SPEAKER PANEL (VMS-67)
N/A N/A 4. MISSING NEW TEC VALVE No training value l i MONITORS "1-VMS-Y-200A,B, & C" VICTOREEN 1-EI-CV-49D (CHR-68-71) 3 N/S 1. SELECTOR KNOBS OF EACH Minimal training value VICTOREEN ASSEMBLY DIFFER FROM PLANT 2 N/S 2. LABELS NEW ON SIM DIFFER See Overall l FROM OLD PLANT LABELS FOR: Comment # 14 l
"2-RM-RMS-265" "1-RM-RMS-165" "2-RM-RMS-266" "1-RM-RMS-166" I')
(_/ I l C-___ --
\
ATTACHMENT 5 Page 37 of-46 4 Priority Status Description Comments l 3 N/S 3. RECORDER DOOR FASTENING Minimal training value KNOBS MISSING FROM "RR-RMS 265(0)".&
"RR-RMS-266 (P) l FIRE PROTECTION -l 1-EI-CB-97 (FP-74-78) I 1 . 1 2 N/S 1. SWITCH PLATES ARE ETCHED Due 09/88 1
" START" RATHER THAN " SPRAY" FOR:
" MAIN TRANS A"
" MAIN TRANSLB"
" MAIN TRANS C" "SS TRANS A" "SS TRANS B" "SS TRANS C" (FP-75)
I 3 N/S 2. LABEL FOR " SPRINKLER-HEATING 1 ALR ROOM"-(FP-74) ) PLANT SHOULD BE BLR FOR CRDR' relabel. BOILER BUT IS ALR minor training value (~ SOMEONE CROSSED OUT A & WROTE IN B IN SIMULATOR j 3 N/S 3. "HALON-EMERGENCY-SWGR. ROOM"' Minor training value ACTUATOR (INSIDE COVER) ' NOT THE SAME SIZE AS THE REST OF THE ACTUhTORS L LENSE COVERS AR" NOT ETCHED AS IN PLANT: RED "SYS7'i.1 hC'ilM ION" YELLOW "T. %i1L? 'FP-75) 2 N/S 4. FAR RIGHT LENSE COVER FOR Due 09/88 "BCW TWR" CELL 1A & 1B" ARE NOT ETCHED NON CORRECT COLOR AS PLANT: ETCHING ; ILLEGIBLE IN PLANT PHOTO I (FP-75) BEARING COOLING 1-EI-CB-80-(BC-79-81) 2 N/S 1. LABEL "1-BC-FCV-111" NEW ON See Overall SIM DIFFERS FROM OLD IN Comment # 14 PLANT: "PHC BC 111 FCV BC111" (BC-80)
ATTACHMENT 5 Page 38 of.46 Priority _ Status Description Comments 2 N/S 2. LABEL "1-BC-LCV-123" NEW See Overall ON SIM DIFFERS FROM OLD IN- Comment # 14 PLANT: "LCV BC'123" CIRCULATION WATER 1-EI-CB (CW-82-86) 1 N/S 1. UPPER LABEL." BUS 1GA Due 08/88 "UNDERVOLTAGE" BLACK LETTERING ON WHITE DIFFERS FROM. PLANT WHICH IS WHITE ON BLACK (CW-83) 2 N/S 2. LABEL "1G/2G GROSS TIE See Overall SYNCHRONIZING 15G10" NEW Comment # 14 ON SIM DIFFER FROM OLD IN PLANT & SHOULD BE~
..." CROSS"... (CW-83) 2 N/S 3. " CAUTION' LA'EL'DOES NOT See Overall APPEAR IN PLANT PHOTO Comment # 14 ABOVE KEY SWITCHES (CW-86A) i 1 W 4. KEYS HAVE TAGS HANGING Due 08/31/88 FROM THEM (CW-86A) 2 N/S 5. SWITCH PLATE OF Due 09/88 1-CW-MOV-103 IS ETCHED l ,
"CLOSE-AUTO-OPEN"~
WHEREAS PLANT IS "CLOSE-INTER-OPEN" LOAD FREQUENCY PANEL 1-EI-CB-17A (LF-90-93) N/A N/A 1. BELLS ON TOP OF UNIT ARE N/A j MOUNTED FRONT FLUSH WITH- ) CABINET WHERE AS PLANT BELLS l PROTRUDE AS THE MOUNTING BRACKET IN FRONT IS FLUSH & PAINTED BLACK (LF-90) 1 1 N/A N/A 2. ALARMS AREN'T HOOKED UP No training value j N/A N/A 3. L & N TAG MISSING No training value i (LF-90,91) ; a l
1 ATTACHMENT'5 1 Page 39 of 46 l 9iority Status Description' Comments N/A N/A 4. SIMULATOR DOES NOT HAVE No training impact ' SAME TYPE OF RECORDER (LF-91) 1 N/S 5. GAITRONICS. PHONE MOUNT IS Due 08/88 DIFFERENT FROM THE PLANT' (RED LABEL IS MISSING)
"USE CHANNEL 5 FOR-CONT./EMER.
YOU ARE AT BOX 15H31C" 1 1/2" X 3" WHITE ON RED (LF-93) VIBRATION MONITOR PANEL 1-EI-CB-11/16 (VM-94-96) s 1 N/S 1. LABELS FOR " UNIT 2...MWH" & Due 08/08 "RCP... VIBRATION... LIMITS... { 1-AP-9" ARE NOT LOCATED AS I IN PLANT (VM-94) J N/A N/A 2. " VIBRATION MONITOR - PATCH No training impact ] PANEL" K0 - TEST JACKS ARE ) WHITE WHILE PLANTS ARE tO YELLOW (VM-95) 1 N/S 3. METER LABELS DIFFER FROM Due 08/88 PLANT , PLANT: " UNIT"X" GEN l GROSS GEN SIM: " GEN UNIT NO"X" GROSS GEN AXIAL POWER DISTRIBUTION MONITORING SYSTEM N/A N/A 1. NOTE: THIS EQUIPMENT IS POWERED DOWN & NOT REQUIRED ] IN* PLANT. LIKEWISE ON THE i SIMULATOR ALL IO CARDS ARE SPARED BUT CABINETS STILL WIRED < i INCORE 1-EI-CB-96 A,B,C,D (IC-1-16) i l 1 N/S 1. BLACK DISK UNDER " PATH Due 08/88 SELECTOR" SWITCHES.ARE MISSING FROM EACH DETECTOR l CONTROL PANEL ! o
ATTACHMENT 5 Page 40 of 46 r~%, Pr ority Status Description Comments 3 N/S 2. CABINET LABELS DIFFER FROM CRDR relabel PLANT (4) PLACES PLANT: "1-EI-CB-96"X" SIM: "EI-CB-96"X" N/A N/A 3. " WESTINGHOUSE: NAMEPLATE IS N/A MISSING I 3 N/S 4. "PICOAMMETER" RACK / CHASSIS Due 12/88 INSTALLED IN SIMULATOR BUT NOT IN PLANT THIS EQUIPMENT IS NOT FUNCTIONAL. USED DURING STARTUP LOW POWER PHYSICS TESTING N/A N/A 5. SCREWS ARE MISSING FROM No training value
" COMMON GROUP" THUMBWHEEL l
SWITCHES SN " DETECTOR l CONTROL A & B" PANELS 1 3 N/S 6. LIMIT ENCODERS NEED TO BE Do via system upgrade SET UP PROPERLY & IC'S [^} v RESHOT 3 N/S 7. SI.MULATOR SCALE SAYS Due 09/88 MICROAMPERES ON ALL !
" DETECTOR READ OUT" AMMETERS 3 N/S 8. SIMULATOR RECORDERS DO NOT Minor training impact HAVE AN AUTO CHART DRIVE POSITION THEY WERE WIRED UP !
SUCH THAT ON = AUTO & THERE IS NO CONTINOUS ON POSITION l N/A N/A 9. SIMULATOR SAYS TRACOR No training impact l WESTRONICS ON RECORDERS
- 1-A11, 1-A14 & 1A19 1
N/A N/A 10. SCREWS MISSING & NOT No training impact REQUIRED ON SIM " SWITCH OVER PANEL" BUT ARE IN THE PLANT N/A N/A 11. SWITCH HANDLE DIFFERS IPOM No training impact PLANT ON " COMMON CONTROLS- 1 INSERT-WITHDRAW" SWITCH N
ATTACHMENT 5~ Pags-41 of 46. i
?r k-
. Priority Status Description Comments 1 N/S 12. SCREW HEAD BROKEN OFF ON- Due 08/88
" POWER DISTRIBUTION - DRYER CIRCUIT BREAKER" N/A N/A 13. PAPER LABEL'OF PEN No training impact <
DESIGNATIONS FOR RECORDER l 1-A14 IS MISSING 1 N/S 14. OPERATOR AID, " DETECTOR Due 08/88 ! PLATEAU DATA SHEET" IS I MISSING FROM BLANK PANEL' ABOVE RECORDER 1-A19 N/A N/A 15. SIMULATOR HAS MORE SCREWS No training impact , INSTALLED ON BLANK PANEL 1 ABOVE RECORDER A19 THAN DOES PLANT ! AUX SHUTDOWN PANEL 1-EI-CB-06A (AS-97-100) )
.I 1 N/S 1. SIMULATOR LABELS ARE BLACK Due 09/88 LETTERING ON WHITE WITH-COLORED DOT TO INDICATE -f PARTICULAR SYSTEM WHEREAS PLANT.HAS PRIMARILY METER LABELS - WHITE ON BLACK EWITCHES - BLACK LETTERING AND THE PLANT USED A COLORED TAG SCHEME FOR SYSTEM N/A N/A 2. THE PANEL IS GREY IN THE Color is low training PLANT, GREEN IN THE value, size is lov SIMULATOR. THE SIMULATOR training value, since PANEL IS PHYSICALLY A a11' instruments _are' DIFFERENT SIZE, AND THERE same arrangement as IS AN EXTRA PANEL BETWEEN station. No training THEM FOR A RADIO value for' extra panel TRANSMITTER / RECEIVER N/A N/A 3. CONTROLLER "HCV-FW-100A" No training impact HAS WHITE FRONT WHERE AS PLANT HAS BLACK FRONT (AS-99) 1 N/S 4. GAITRONICS PHONE PANEL IS Due 08/88 DIFFERENT (AS-99)
O
ATTACHMENT 5 Page 42'of 46' Priority Status Description Comments 1 N/S 5. " HOURS" COUNTER IS MISSING Due 08/88 (AS-100) 3 N/S 6. LABELS DIFFER FROM PLANT CRDR relabel BY HYPHEN SIM: PLANT: HIC-FW-100A-2 HIC-FW100A-2 HIC-FW-100B-2 HIC-FW-100B-2 HIC-FW-100C-2 HIC-FW-100C-2 HCV-FW-100A HCV-FW100A HCV-FW-100B HCV-FW100B TV-MS-111A TV-MS111A TV-MS-111A(R-L) TV-MS111 AIR-L) MOV-HV-118-1 MOV-HV118-1' MOV-HV-118-2 MOV-HV118-2 PDI-HV-101 PDI-HV101 j (AS-100) 2 N/S 7. LABEL " REMOTE LOCAL,_ Plant label fell HCV-1200A" ON SIM IS NOT off and should I I IN PLANT ABOVE " CIRCUIT B" be replaced JACK (AS-100)
/~') 1 N/S 8. GREEN TAPE LABEL " LOG START / Due 08/88
(_/ STOP" IS MISSING'FROM ABOVE "1-HV-F-42" INDICATORS (AS-100) 3 N/S 9. SIMULATOR HAS GAITRONICS Due.12/88 HANDSET AND SWITCH BUT NO BOX. RED DOT MISSING ON . NUMERAL 5. SWITCH IS IN THE WRONG PLACE I N/A N/A 10. SINULATOR HAS COILED CORD No training value ON HEADSET-CORD (AS-100) N/A N/A 11. SIMULATOR DOESN'T HAVE A Low training value SHELF TO PUT PROCEDURES ON , N/A N/A 12. HEADPHONES MISSING No training value 1 N/S 13. LABEL MISSPELLED " REMOTE Due 08/88 , LOCAL PZR HTR PWL NO 4" SHOULD BE "PNL'" (AS-98) ' 1
ATTACHMENT 5: Page 43 of~46-O Priority Status Description Comments -i N/A N/A 14. HAMMER TO BREAK GLASS IS No training value HERE STILL. KEY IS KEPT. Glass is a safety ~ INSIDE PANEL ON SIMULATOR concern q AUX SHUTDOWN PANEL I 1-EI-CB-06B (AS-101-104) 3 N/S 1. LABELS DIFFER FROM' PLANT BY CRDR relabel HYPHEN SIM: PLANT: PCV-MS-101A(S) PCV-MS101A PCV-MS-101B(S) .PCV-MS101B q PCV-MS-101C(S) PCV-MS101C !. PCV-MS-101A(C) .PCV-MS101A PCV-MS-101B(C) .PCV-MS101B. ]' PCV-MS-101C(C) PCV-MS101C l TV-MS-11B TV-MS11B- l TV-MS-11B(R-L) TV-MS11B MOV-FW-100A MOV-FW100A 1 J MOV-FW-100B MOV-FW100B MOV-FW-100C MOV-FW-100C MOV-FW-100D MOV-FW100D MOV-FW-100A(R-L) MOV-FW-100A O MOV-FW-100B(R-L) MOV-FW100B MOV-FW-100C(R-L) MOV-FW100C
'MOV-FW-100D(R-L) MOV-FW100D
.(AS-101-104 3 N/S 2. SIMULATOR SAYS NORMAL CRDR relabel INSTEAD OF NORM IN 4 PLACES "MOV-FW-100A"- ;
THRH "D" SWITCH PLATES (AS-104) ! 1 N/A N/A 3. SIMULATOR HAS SIMILAR Minor training value. ;j' SWITCH HANDLES BUT NOT IDENTICAL IN 4 PLACES j (THIS TYPE SWITCH HANDLE ; IS NO LONGER AVAILABLE)
" REMOTE LOCAL MOV-FW-100A" THRU "D" SWITCHES (AS-104) l TRANSFER SWITCH ~ BOXES (109,110)
N/A N/A 1. NO' PHOTOS AVAILABLE 0F Obtaining new j BOXES 1 & 2 photos ! 1 N/S 2. BOX 3.NOT STENCILED " VITAL Due 08/88 .r% BUS. 1-III TRANSFER SWITCH"
l ATTACHMENT 5 i Paga 44 of 46 l 1 ority Status Description Comments j 2 N/S 3. BOX 4 NOT STENCILED " VITAL Due 08/88 BUS. 1-IV TRANSFER SWITCH" l LABELS MODIFIED WITH TAPE ] 1 LABEL TO INDICATE "SW4" Du6 08/88 1 N/S 4. DIFFERS FROM PLANT CASING 1 COOLING PANELS 1-EI-CV-156A I (CC-111-115) 1-EI-LB-156B I 2 N/S 5. PANELS ARE GREY RATHER THAN Due 09/88 I GREEN AS IN THE PLANT l (CC-111-115) i i 1 N/S 6. PANELS USE LABELS RATHER THAN Due-08/88 STENCILLED AS LANT:
" BOTTLED AIR CASING COOLING ,
SYSTEM 1-EI-CB-156A" OR "B" I (CC-111,114,115) l N/A N/A 7. NO GROUND STRAP No training value 1 1 N/S 8. LABELS USED COLORED DOT Due 08/88 i RATHER THAN ORANGE OR ! ( VIOLET LABEL AS IN l (_)) PLANT: MOV-RS101B MOV-RS100A 1-RS-P-3A i MOV-RS101A ! (CC-113,114,115) ! UNIT 2 MUX 50 (105-108)
)
1 N/S 1. KAMEN- Due 08/88 RECORDERS ARE NOT USED NOR CONNECTED. LABELS FOR RECORDER POINTS ARE MISSING \ 1 W 2. TAPE LABELS (RED) ARE Due 08/88 MISSING (6)
" PROCESS VENT HI" AND "...LO"
" VENT STACK A HI" AND "...LO"
" VENT S" 3.CK B HI" AND " . . . LO" N/A N/A 3. CABINET & MOUNTING OF KAMEN No training impact DIFFERS FROM PLANT WHICH IS RAIL MOUNT r ~s wY L_ __
ATTACHMENT 5 Page 45 of 46 9fority Status Description Comments N/A N/A 4. NO PHOTOS AVAILABLE ON No training impact UNIT 2 CONTROLS, INDICATORS & LABELS i SIMULATED BY UNIT 2 ) CABINETS j SHIFT SUPERVISOR CONSOLE (118-124) 2 N/S 1. CONSOLE IS BEIGE WHERE AS Due 09/88 l PLAT CONSOLE IS GREEN j 1 N/A N/A 2. PHONE OR RADIO PANELS No training value HANGING ON SIDE OF CONSOLE TOWARD VERTICAL BOARD ARE MISSING (2) N/A N/A 3. "MX CTL 1" BOX IS MISSING No training value FROM ALONG SIDE TERMINAL 1 N/S 4. RED DOT MISSING FROM Due 08/88 "GAITRONICS-UNIT "1 & 2" SELECT 5" POSITION g)3 ( 1 N/S 5. LABEL "USE CHANEL 5 FOR Due 08/88 CONT./EMER..." IS MISSING FROM GAITRONICS PHONE PANEL
--~
3 N/S 6. STATION UNITS 1 & 2 PHONES Due 12/88 DO NOT WORK, BUT GAITRONICS DOES. PUSHBUTTON SWITCHES ARE NOT LABELED TO INDICATE CALLED STATION 1 N/S 7. RED INDICATOR ABOVE " SPARE" Due 09/88 PHONE IS MISSING N/A N/A 8. KEY BOARD, TERMINAL AND No training value "MX CTL 2" ARE MISSING FOR UNIT 2 i W 9. TOGGLE SWITCH & LABELS: Due 08/88 "CHAN.5 ONLY NORMAL OP'S" ARE MISSING & NOT OPERATIONAL FROM UNIT 2 GAI-TRONICS PANEL PRODAC .ONSOLE (125-128) N/A N/A 1. DESK TOP IS WHITE WHILE N/A g- PLANT IS SIMULATED WOOD V
ATTACHMENT 5 Page 46 of 46 P1'iority Status Description Comments 2 W 2. READ OUT HOUSINGS ARE Due 09/88 MISSING FROM PRODAC PANEL DIGITAL READ OUTS (2) 1 N/S 3. KEY CHAIN IS MISSING FROM Due 08/88 PRODAC SWITCH PANEL N/A N/A 4. PRINTER IS MISSING FROM See Overall CABINET RIGHT PRODAC PANEL Comment # 14 2 N/S 5. TERMINAL HOUSING IS BROWN Due 09/88 WHERE AS PLANT HOUSING IS GREEN (WHOLE CABINET) 2 N/S 6. KEYBOARD (CTC) NOT PLACED Due 09/88 HERE & CRT9 & KPD 14 TAGS MISSING COLOR IS WRONG, SHOULD BE GREEN REM RADS , 2 N/S 1. ENCLOSURES ARE PAINTED Due 09/88 BEIGE WHICH DIFFERS FROM (' PLANT WHICH ARE GREY
\ (116-117)
N/A N/A 2. SIMULATOR SPACING (PHYSICAL Minimal training value LOCATION) DIFFERS FROM PLANT IN THAT UNIT 2 REM RADS ARE i INCLUDED IN CLUSTER ! N/A N/A 3. ENCLOSURE JACK / CABLE No training value INTERCONNECTIONS DIFFER FROM PLANT WHICH HAS 4 JACKS WHILE SIMULATOR j HAS 1 CABLE (116) ) 2 N/S 4. LABELS NEW ON SIMULnTOR See Overall DIFFER FROM PLAN 1 WHICH Comment # 14 ONLY HAS ID # ie "RI-VG-174" (117) i l l i I OO 1 1 _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ - - 1
1~ l l l l r' l l l VIRGINIA POWER SIMULATOR SUPPORT GROUP j l i
)
\
l 1 NORTH ANNA UNIT 1 SIMULATOR l ATTACHMENT 6 s NORTH ANNA UNIT 1 CONTROL ROOM / SIMULATOR PANEL AND ENVIRONMENT COMPARISON O
D
' ATTACHMENT 6 PAGE 1 OF 16 O NORTH ANNA CONTROL ROOM AND SIMULATOR! COMPARISON OF PANEL LAYOUT AND ENVIRONMENT This report is a comparisonEbetween the control room panels (Figure 1 of this attachment) and simulator panels 1 (Figure 2 of this attachment), their layout, and the general surrounding environment. The report is in two parts, part "A" covers equipment panels, and part "B" discusses the j environment.
]l Each panel will be reviewed individually. Information )
will'be given, such as name, location, function and ') associated units. Each panel is also, reviewed for its training value. The major areas of the environment thatzare covered are, lighting, noise, and color scheme. Minor differences ' will be noted and all areas will be in reference to its training value. l This comparison is not intended to be the definite simulator Physical Fidelity Comparison Report. The Physical Fidelity Comparison Report is contained in Attachment 4. O : I l
)
l i 1 i
^
y ATTACHMENT 6 PAGE-2 OF 16- I SIMULATED ~ PANELS NRC RADIATION MONITORING KAMEN RADIATION MONITORING PANEL ; LIQUID WASTE PANEL i BORON RECOVERY PANEL RADIATION MONITORING PANEL j VENTILATION PANEL IJ EMERGENCY DIESEL PANEL ~ TURBINE SUPERVISORY PANEL 1H EMERGENCY DIESEL PANEL PRESSURIZER SAFETY VALVE MONITORING PANEL HIGH RANGE RADIATION MONITORING (VICTOREENS) ROBERT SHAW FIRE PROTECTION PANEL STATION FIRE PROTECTION PANEL. BEARING COOLING PANEL CIRCULATING WATER PANEL I SWITCHYARD DISTRIBUTION PANEL LOAD FOLLOW FANEL REACTOR COOLANT PUMP VIBRATION PANEL AXIAL POWER FLUX DISTRIBUTION MONITORING SYSTEM PANEL INCORE NUCLEAR INSTRUMENTATION PANEL VITAL BUS TRANSFER SWITCHES MAIN ANNUNCIATOR PANELS 1 VERTICAL BOARD #1 O VERTICAL BOARD #2 SAFEGUARD PANEL #1 SAFEGUARD PANEL #2 POST ACCIDENT MONITORING PANEL UNIT 2 EQUIPMENT PANEL (SIMULATOR) BENCHBOARD #1 BENCHBOARD #2 AUXILIARY SHUTDOWN PANEL P-250 STATION SHIFT SUPERVISOR DESK (INCLUDE COMMUNICATION EQUIPMENT)
)
( ) 3
i
~
ATTACHMENT 6 PAGE 3 OF 16 O NON-SIMULATED PANELS - FANELS SPECIFIC TO UNIT 2 OPERATION NRC RADIATION MONITORING BEARING COOLING PANEL , AXIAL POWER FLUX DISTRIBUTION MONITORING l CIRCULATING WATER PANEL-INCORE NUCLEAR INSTRUMENTATION PANEL FIRE PROTECTION PANEL 2H EMERGENCY DIE _"EL GENERATOR PANEL TURBINE SUPERVISING PANEL 2J EMERGENCY DIEEEL GENERATOR PANEL VENTILATION PANEL l RADIATION MONITORING-OPERATORS CONSOLE SPDS CONSOLE BENCHBOARD #1 BENCHBOARD #2~ VERTICAL BOARD #1 VERTICAL BOARD #2 j' SAFEGUARD PANEL #1 SAFEGUARD PANEL #2 P-250 STATION AUXILIARY SHUTDOWN PANEL O l l l l
' ATTACHMENT 6' PAGE 4 OF 16 ,
f I r~ (_)) l' NON-SIMULATED PANELS - COMMON TO BOTH UNITS These panels have not been simulated because of the. relative minor training value received from'them oridue to , their inoperable status in the reference plant. l AMBIENT TEMPERATURE-MONITORING PANEL -~No training value METEOROLOGICAL PANEL - Little training value STATION AND DIESEL BATTERY MONITORING PANEL - No training ^ value l SEISMIC PANEL - Little training value I SPILLWAY SUPERVISORY PANEL - Non-operational .] , 1 I
'l 0
D E.M% 3-0: s h
>y>MnO1'5 s
't t .@
l L t T e ! t w pA . PTC
= .
R4 -
~U =
eRU
.sI E2 e.
< l T W9 T1 o
< 7 1ED.S 0 N c,
I
. 5N FMtE xB l
e2 2
. E(AOp f V54 I
. W l
HsfTaPE 2 afreEP FW3sLBA pt I
= . . , ,. ..
l t 334s87 _ S333333 _ l si l e s 0I I 3D m d 1 I n H9M 4 I LI EtV JsFNVA IED _ l
= WEG S W f A s. R g
r V . e TR3lt tt fs i NE3EEa EB1D _.O m VETEPC _D l 5N70303333 2 u j
=
'd p 5 4 . _ _
l 3
=
8 1N Y r 2 l E i l
= e. 10 MOtHD 9
g# 4 4
.!-1
= W. OE i_
= wDDp AAfg ue ,.
= .t
.a E l
DR uC C
=IIDD . ,
O. "D"!s i i n 0IE 0I 0G912 I BAA I lRD Am 5 4 T. 2 T t f M O O 1 1 I B T,A VE _ 0HO- - l 3CC19 : . R
= . . . . .
9t254 2 :4
- L 2S2E3 4 S O R 1 ll Ot S 'E R nI'o l E T m,U VS E'
E" l N e O r L eEa 5 C u A B P L l l l g 0O _ 131 S S 1 L1E E99W E I Ai s N AD I R N NF N _ l PASD RRET A f f - r L A _ l9GS A c i E - u 1
=
V39I f si 2
- H T
l r e700. t351 r r L R _ A i i w C O _ e D t e I T N ._ i r l T R E s C V i U f f J _ l R E 2 4 TT V 4-SWfBFN E r# I IE 1
. tPGSS t
l e I B I - i aER t E D _ l E fREMl f E I3M B T ei 3FE E N . l i i I8948. I13I1 k% % E.^= D I. C l CA L. A. e 4 . r T,h S O P A.
% 0*
3 1_ L
. LE l
nILEf vB EI fA eOgAP
=i l MAP P T
= TA TCAW i _T A2WL
.StsLL
. ?e22 0LI I
rsEPW eESS i y .
. . 9 l
7SS1 T.
,U
- e n
e g I D m e o c
- s E 2
l mpfT e t I AsET t
.O ctHN WES m l eeTIf eD
.O l
= neJcfF ugoAA r nO e
8
- 234S
.O
0 ATTACHMENT 6 PAGE 6 OF 16 o i Isl I l- i 1 - l [ i i g R
? I i il iiisisi s
, s
; , ,ii ,
llillI ligg l 4 o ll8 i . i
.!_!_!_!_!_ \
, -g s
- C
\ E i h. -
+
_iii !!
- ll
~
==aI!:l i ll !
e, l-
-,,I ill ll1
_ II l' I'~ la U:- til ____
- u, 11 lo l
l L____________________
ATTACHMENT'6 ' PAGE 7 OF 16 O- PART A PANELS l NRC RADIATION MONITORS l The High REnge Effluent Monitoring system panels are located in-the north west corner of the main control room. These panels. provide indications and alarms for radiological releases from effluent. steam paths. The effluent monitoring panels of the reference plant, j Unit-1,:are fully simulated and located in a similar position in the simulator control room. The Unit 2 panels are not simulated. These panels provide training in determining.the status of radiological releases.thru effluent flow paths. l KAMEN RADIATION MONITORING PANELS The High Range Effluent Monitoring Panels are' located on the Unit 2 side west of the backboard panels. This panel provides indication and diagnostic features for radiological releases from various flowpaths. Only the reference plant,- Unit 1, portion of the panel is simulated. The location of the simulator panel is in'an approximate position of the reference panel,.i.e. on the Unit 2 side of the back panels. Th- Janel provides minimal training value, due to operuulonal data being displayed. Diagnostic information is not simulated. LIQUID WASTE PANEL The Liquid Waste Panel is a backboard panel located on the Unit 2 side of centerline in the main control room. It is a common panel belng shared by both Unit 1 and Unit 2. The panel contains controls, indications-and alarms for various systems shared by both units. The Liquid Waste panel is fully simulated and-located identically to the ' i reference plant. It provides valuable training in the operation and control of common systems and coordination between backboard 1 and control board operations. ) i y O i l i
- - _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ - - _ - _ - _ _ - --. _ . - :__ _ -_ a
i ATTACHMENT 6 PAGE 8 OF 16 1 i BORON RECOVERY PANEL The Baron Recovery Panel is a backboard panel located on the Unit 1 side of centerline in the main control room. 1 It is a common panel sharing systems of both units. It , contains controls, indications and alarms for the Boron ! Recovery and Primary Grade water systems. This panel is fully simulated and located identical to the reference plant. It provides significant training in the operation of boron recovery components and systems. .It also develops coordination between the backboard operator and the control room operator. RADIATION MONITORING PANEL The Radiation Monitoring Panels are backboard panels l located on the Unit 1 side. These panels provide control, ! indication and alarms for. process and area radiation detectors on common and respective unit systems.- Only the I common and Unit 1 monitors are simulated. The Unit 2 systems have no training value and are not simulated. The panels are located exactly as in the reference plant and provide significant training in monitoring and analyzing the radiological status of plant systems.
)
l VENTILATION PANELS , a The Ventilation Panels are located on their respective units backboards. Each contain controls for ventilation i equipment for their unit and some equipment separated for relability. The Unit 1 ventilation panel is. fully simulated and located as in the reference plant. The Unit 2 ventilation panel is partially simulated with control features to ensure the reference plant system is complete. The Unit 2 ventilation panel is located in the approximate position to the actual panel. ; The panels provide training in plant systems and components. It also develops coordination between the l backboard operator and the control room operator. EMERGENCY DIESEL PANELS The Emergency Diesel Panels are located among their respective units backboard pat.als. They provide all the necessary control and indication to operate the diesel generators. Only the reference plant (Unit 1) panels are l
1 ATTACHMENT 6 PAGE 9 OF 16 simulated. Each panel, H and J, is fully simulated and. l provides significant training in the operation of electrical l generators. l TURBINE SUPERVISORY PANEL The Turbine Supervisory Panel is a backboard panel that provides indications and alarms for various turbine control systems. The reference plant: (Unit 1) panel is fully simulated and located similar to the reference plant. The Unit 2 panel provides no training value and is not simulated. This panel provides training in the monitoring of main turbine parameters and turbine control. systems, i PRESSURIZER SAFETY VALVE MONITORING PANEL The~ Pressurizer Safety Valve Monitoring Panel is a backboard panel located on the Unit 1 side in the main control room. The panel monitors and indicates the. safety valve flow conditions via acoustical monitors for both Units 1 and 2 and gives associated alarms. Only the Unit 1 portion is fully simulated, with the Unit 2 portion simulated to show power to the monitors. The panel provides () minimal training value other than indications. CONTAINMENT RADIATION MONITORS The Containment Radiation Monitoring Panelfis located j along the backboards next to the main control room entrance. 1 The panel contains controls and indications for both Unit 1 1 and 2 containment radiation conditions. Both units monitors I are functional, however, only Unit 1 (reference plant) is i fully simulated. The panel provides valuable training j during accident conditions by displaying containment , conditions. ROBERT SHAW FIRE PROTECTION PANEL l i The Robert Shaw Fire Protection Panel is located on the i Unit 1 side of the main control room backboard panels next ; I to the entrance door. It displays the status of numerous fire zones and smoke detectors. The panel is only simulated to the extent of having the hardware installed. () a l u_ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - . _ _ _ _ __ __ . _ _ _ _ _ __ _ _ _ _ _ _ _ _ -i
ATTACHMENT 6-PAGE 10 OF 16 ., O STATION FIRE PROTECTION PANEL The Station Fire Protection Panel-is located on the east side of the main control room backboard panels. It monitors and displays the status of fire supression systems in various locations. Major plant areas common to both units are also displayed.- The Fire Protection panel is - fully. simulated to give the proper indication and alarms - when called upon by the simulator instructor. " BEARING COOLING PANEL
)
The Bearing Cooling Panel is a backboard panel located in the east section of the main control room. It contains the controls and indications for the operations-of the. bearing cooling system. It also contains the ambient temperature monitor panels. The Bearing Cooling Panel is fully simulated. Its location in the simulator' control room-is identical to the main control room. CIRCULATING WATER PANEL The Circulating Water Panel is a backboard panel located on the east side of the control room. The Unit 2 o O- circulating water panel is on the west side of the main . . control room. The Unit 2 panel is not simulated. .The Unit 1 1 panel is fully simulated to include circulating water pump ! controls switches, valve control, and indication. It also includes indication for bus power. This panel provides significant training on system operation. SWITCHYARD DISTRIBUTION PANEL The Switchyard Distribution Panel is a backboard panel located on the east side of the main control room. It is a common panel shared between both units. It contains a mimic-bus and necessary indications to monitor the electrical switchyard breaker and line voltage status. This panel is fully simulated logicly and dynamically. 1 LOAD FOLLOW PANEL The Load Follow Control Panel is a backboard panel , located on the east side of the main control room. It is a common panel shared by both units. It is a non-functioning l panel at this time with no plans of becoming operational. 1 1 i
ATTACHMENT 6 PAGE 11 OF 16 r3 It contains a frequency recorder, load follow controls and a phone system. This panel is simulated to the extent of the systems that are operational in the main control room panel. RCP VIBRATION MONITORING PANEL The Reactor Coolant Pump Vibration Monitoring Panel is a backboard panel located on its respective units side of the main control room. The Unit 1 panel contains some equ.4pment common to both units and some specific for Unit 2, specifically the watt. meter integrators. The watt meter-integrators are not functional in the simulator. The RCP vibration monitoring panel however is fully simulated in that it provides the calculated vibration indication under normal and abnormal conditions. AXIAL POWER FLUX DISTRIBUTION MONITORING PANEL (APDMS) The APDMS panel is a backboard panel located on the respective units side of the main control room. Only the reference plant (Unit 1) panel is simulated. Currently the main control room panel is not required by plant operations. _s Therefore, this panel is physically incorporated but not simulated. It provides no training value and is maintained (A /) only for simulator appearance. INCORE FLUX DISTRIBUTION PANEL The Nuclear Instrumentation Incore Flux Distribution Panel is located on the respective units side of the main ' control room. This panel is fully simulated.for the reference plant. It contains the controls and indicative used for the incore system operations under normal and abnormal indication. This panel provides training on the operation of the incore flux drive system and in diagnosing changes in neutron flux patterns. VITAL BUS TRANSFER SWITCHES The Vital Bus Transfer Swltchs are individual panels located in the main control room behind the main control ; panels. Only the Unit 1 panels are simulated. The panels provide the ability to transfer the power sources of the l vital buses. These panels are fully simulated and provide l the same ability as in plant. They are located behind the ! main control boards in the approximate location as in the main control room. b("N
ATTACHMENT 6 PAGE 12 OF 16 i . ET.N ANNUNCIATOR PANEL The Main Annunciator Panels are located above the main' control board vertical sections. There are fifteen panels. each consisting'of sixty four " windows".. The panels provide indication of circuit status, permissives, and alarms contitions. Each annunciator window is simulated to the-ninimum extent of being able to activate the alarm. For systems that are fully modeled there associated alarms are also fully modeled. The only. physical difference between the control room and simulator room involve minor items such as letter size-and or wording. These have been identified'by the annual physical fidelity review. The annunciator system is the major component _in proper operator training and must be simulated to the maximum extent possible. MAIN VERTICAL BOARD #1 The Main Control Room Vertical Board Number 1 is located on the left hand portion of the main control boards. It contains all of the equipment necessary for operating and
- monitoring of the Nuclear Instrumentation system and various primary plant systems. This Unit 1 panel'is fully simulated and located in the identical position in the simulator control rocm and provides operator training in the' control and monitoring of the Excore Nuclear Instrumentation System and primary plant systems.
MAIN VERTICAL BOARD #2 The Mcin Control Room Vartical Board Number 2 is located approximately right of the center of the. vertical boards. The panel contains indication for various plant ' l secondary systems.- Each of the systems monitored is fully simulated, therefore, the instrumentation and controls of this panel is fully simulated. Some minor cosmetic discrepancies are known.and have been identified in the annual fidelity report. Only.the Unit 1 reference plant is simulated and its location is identified as in the main control' room. This panel provides vital 1 instrumentation in the operations and control of major plant systems. O r_-_____-_______________-____ - _ . i
1 ATTACHMENT 6 PAGE 13 OF 16
)
<b
~.
SAFEGUARD PANELS #1 b i l The Safeguard Panels are located to the right of the vertical boards. This panel contains the indications and i controls for numerous components of the primary, secondary and safeguard systems. All indications and control features are fully simulated logically and dynamically. The I simulated panels are located and layed out identical to the main control room. These panels provide valuable training in the operation and control of vital plant systems. j 1 1 POST ACCIDENT MONITORING PAsEL The Post Accident Monitoring Panel is located to the right of the safeguard panel. It contains instrumentation and controls for systems affecting containment environment. 1 Only the reference plant (Unit 1) is simulated. The panel is fully operational. All valve logics are modeled and the i l instrumentation is modeled to the required scope of simulation. The panel provides valuable training in past accident conditions in analysis and recovery and is located identical to the main control room. UNIT 2 EQUIPMENT PANEL (SIMULATOR) b[i The Unit 2 Equipment Panel, located in the simulator i control room, along the south wall, contains indications and controls used to enhance simulator training. The equipment simulated are components of systems that are shared between the units. This equipment is located in the main control specifically on Unit 2 panels, and is simulated only to the extent to allow training to be conducted on systems that require actions to be taken at Unit 2 locations. BENCH BOARD #1 The Main Control Room Benchboard Number 1 is located on the left of the operator console. This panel contains the indications and controls.for components of various primary l systems. Each system and its features are fully modeled making the panel a completely simulrJed pinel. Only the l reference plant is simulated. This panel provides a major l portion of operator simulator training. Only minor cosmetic j discrepancies are known and they are identified in the annual physical fidelity comparison report in Attachment 4.
/'~N O
1 ATTACHMENT 6 i I PAGE 14 OF 16 n V BENCH BOARD #2 The Main Control Room Benchboard Number 2 is the right hand portion of the operators console. This panel contains the indications and controls of components for various secondary and electrical systems. The panel is " fully simulated panels with only the reference plant (Unit 1) panel simulated. This panel is used in a major portion of the operator training program. Only minor cosmetic differences are known between the refere, ice plant and the simulator panels. AUXILIARY SHUTDOWN PANEL f The Auxiliary Shutdown Panels are located in the j emergency switchgear room of its respective plant. This panel provides independent remote control of vital system components for the safe shutdown of the plant. Only the reference plant auxiliary shutdown panel is simulated. This panel is fully simulated, however it is located in a manner .j different from the reference plant. The simulator auxiliary 1 shutdown panel is located within the simulator control room l but out of the line of sight of control room operators. The ; placement of the panel adequately simulates the remote
N conditions of the actual panel.
(b PLANT COMPUTER STATION The Plant Computer Station is located opposite the operators main contr<,1 console. It is used to monitor plant ( status and gather information for specific tasks. The 1 reference plant computer station is fully simulated with the exceptions of some tasks that are beyond the scope of simulation. It is located identical to the reference plant. i SHIFT SUPERVISORS CONSOLE The Shift Supervisors Console is located between the main control boards of both plants. It acts as the central control station for supervisory plant operation. it contains the necessary communication and information systems needed for decision making. This console is not fully simulated. Some systems, such as the station radio system, and inter-state communication system are not completely functional. Only systems vital to the operator training program have been incorporated. O O
ATTACHMENT 6 PAGE 15 OF 16 PART B ENVIRONMENTAL DIFFERENCES There are certain environmental differences between the simulator and control room. The most noticable of these is that the dual unit control rooms panel layout are mirror images of each other with some minor equipment differences existing which is compensated for by the use of a " Unit Two equipment panel" in the simulator. These differences have been reviewed and found to have no impact on training, and that the simulator is acceptable for operator training and testing. The main control room florescent lighting is placed in a north and south configuration while the simulator lighting is run east to west. This causes a different dispersion of the lighting. Overall the effect is that the simulator lighting appears to be brighter and produces more gJare upon the meter faces. A meter lens replacement project is underway to procure and replace the VX252 style meter lens. The replacement is scheduled for completion by the end of 1988. The main control room has been recently recarpeted. f The carpet change has not yet been incorporated into the I T simulator. V There are four Virginia Power logos applied in places in the main control room that are not in the simulator. The Reactor Operators console is laminated with a wood veneer that is not incorporated in the simulator. Freestanding national and company flags have been added te, the main control room that are not in the simulator. The national flag has been placed in the simulator. The Shift Supervisor console contains a site radio and company page system that is not yet incorporated into the simulator. The hardware has i:aen installed, but is not operational. Noises that accompany operation of various systems or equipment adjacent to the main control room are not simulated. The local control room radiation monitor detector and read ut with alarm is not included in the simulator, but is scheduled for installation in accordance with the discrepancy resolution schedule. k-1 _ _ - - - - - - _ - - - - -- 1
ATTACHMENT'6 PAGE 16 OF 16 t' (w Some minor painting schemes are not current in the simulator, i.e. NRC radiation panels and panel lettering. Imitation potted plants were procured by the station. ! The same plants have been ordered as used in unit 1 control ! room and have been installed in the simulator. I l l
's.
VIRGINIA POWER SIMULATOR SUPPORT GROUP NORTH ANNA UNIT 1 SIMULATOR ATTACHME T 7 SIMULATOR. UPGRADE l 1 I O
ATTACHMENT 7 Page'1 of 1 l l SIMULATG3 UPGRADE SCHEDULE System Phase A Phase B
- 1. Chilled Water 08/31/87 03/15/68
- 2. Safety Injection 09/30/87 04/15/88-
- 3. Residual Heat Removal 10/31/87 04/15/88
- 4. Neutron Shield Cooling 10/31/87 06/26/88
- 5. Component Cooling Water 11/30/87 06/26/88
- 6. Recirc Spray 11/30/88 06/26/88
- 7. Containment Spray 11/30/87 07/21/88
- 8. Spent Fuel Pit Cooling 11/30/87 07/21/88
- 9. Heating & Venti 3ation 12/31/87 09/01/88 10 Main Generator 12/31/87 09/01/88
- 11. Radiation Monitoring 02/15/88 09/30/88
- 12. Rod Control 02/15/88 09/30/88
- 13. Instrument Air 02/29/88 10/15/88
- 14. Service Air 02/29/88 10/31/88
- 15. Circulating Water 03/31/88- 11/15/88
- 16. Extraction Steam .03/31/88 11/15/88
- 17. Reactor 04/30/88 11/30/88
- 18. Steam Generator Blowdown 05/31/88 12/15/88
- 19. Bearing Cooling 05/31/88 12/31/88 20 Lube Oil 05/31/88 01/15/89 )
- 21. Gland Steam 06/30/88 01/31/89
- 22. Electro-hyraulic control 06/30/88 02/15/89
( 23. Plant Computer 07/15/88 02/28/89
\~- 24. Turbine 08/31/88 03/31/89
- 25. Boron Recovery 09/30/88 04/05/89
- 26. Liquid Waste 09/30/88 04/15/89
- 27. Hydrogen Control 10/30/88 04/30/89
- 28. Gaseous Waste 10/30/88 05/02/89
- 29. Station Vent (Air Ejecters) 11/15/88 06/05/89
- 30. Steam Drains 11/15/88 06/05/89
- 31. Gasified Drains 11/30/88 06/26/89
- 32. Building Drains 12/15/88 06/26/89 i
I l 1 l 1 s
)
(G) VIRGINIA POWER SIMULATOR SUPPORT GROUP l i NORTH ANNA UNIT 1 SIMULATOR ATTACHMENT 8 DISCREPANCY BACKLOG /AND RESOLUTION SCHEDULE I 1 I l i l l r ( l l
ATTACHMENT 8L
.Pags 1:of 24.:
O The attached ' discrepancy. list.contains.all currently-open discrepancies, (SMR's). Each discrepancy. has- been: assigned'a priority .in.accordance with. current Virginia Power. simulator maintenance guidelines. Each SMR.alsohas-an assigned completion 'date and primary. area- .of responsibility.. O r.< O W N__-.-_-__-.-__. _ _ -a ";
ATTACHMENT-8 Paga 2 of^24 I O DISCREPANCY BACKLOG /AND RESOLUTION SCHEDULE f 1 SCHEDULED COMPLETTON SMR NUMBER SYS DESCRIPTION DATE PRIORITY I l 8706231104 AM REMOVE S/G SUPPORT HTR 01/31/89- 3 j INDICATION FROM MCV. ALSO VERIFTY SUPPOPT HEATERS EFFECT REMOVED l FROM RCS & CONTAINMENT MODELS. 8605162000 AN NEED TO ADD ANNUNCIATOR 08/15/88 1
]
HORN, SILENCE,- J 1 ACKNOWLEDGE & TEST PUSHBUTTONS TO UNIT 2 f PANEL. 8610141015 AN 4KV & 480V EMER BUS 08/15/88 1' 2 OVERVOLT. 480 VOLT EMER BUS OVERVOLTAGE PROTECTION & ALARM, ANNUNCIATOR WINDOW () 8704101030 AN AS R DCP WIRE LIST WAS FOUND.TO BE 08/15/88 1-INCORRECT & NO WIRING DIAGRAM NOR SCHEMATIC TO INDICATE MX804202 CHAN'S 1-8 ANNUNCIATOR - SILENCE, TEST, ACKNOWLEDGE, FIRST OUT RESET, STATION-EVAC, FIRE, ALERT, C. EVAC. 8707271126 AN RELOCATE VARIOUS 08/15/88 1 i ANNUNCIATOR WINDOWS. 4 8703180107 BC EWR 83-110 MODIFY .12/31/88- 3
-DRAWINGS'TO REFLECT AS' BUILT PIPING - VERIFY THIS IS INCORPORATED AS i SCOPE REQUIRED DURING UPGRADE.
l 8710291400 BC BC TOWER OUftET TEMP 08/15/88 1 (T1-BC-120) READS HIGHER THAN THE BC-TOWER INLET l TEMP T1-BC-121. ,
1
~
-ATTACHMENT 8 Pago 3 of 24 1 1
'l
() SCHEDULED COMPLETION SMR NUMBER SYS DESCRIPTION- PATE PRIORITY 8711131026 BC THE FM DRAWINGS & LOCAL 12/15/88 3 INSTRUMENT LISTS SHOULD BE REVISED. VERIFY AS SCOPE OF SIMULATION ) i REQUIRES. l 9 8804261527 BC 1-BC-P-1A DID NOT AUTO 12/15/88 3 i START WHEK STARTING UP SYSTEM (PLACED IN AUT0) HOWEVER AT 100% LOWER IC IT OPERATES CORRECTLY. 81038 BD SG BLOWDOWN RECOVERY SYS 12/15/88 3 ) 1 8705061021 BD CHANGE LOW SETPOINTS FOR 12/15/88 3
-STEAM GENERATOR " STEAM GENERATOR BLO*iDOWN CHEMISTRY Tis 0BLE" ANN. j TO 7.1 PH FOR '1 1-PHA-101-A,B, & C. ]
(~T 8501211101 BR VERIFY LOGICS CORRECT 09/30/88 2 (/ FOR ALL LW & BR SYSTEMS l PUMPS WHICH HAVE SWITCHES OF THE TANKA, NORM, TANKB' TYPE. SEE ROGER FOR DETAILS. I 8602271000 BR MODIFY BR LOGIC FOR 09/30/88 2 i ANNUNCIATOR PER REVISION TO LOOP BOOK PAGE BR-106 1 REVISION DATE 12/02/85. 8609161100 BR INCORPORATE ALL CHANGES 04/05/89 3 INDENTIFIED AS SCOPE OF SIMULATION REQUIRES. 8610071105 BR DELETE INCREMENTS OF 50 09/30/88 2 ON SCALE BORON RECOVERY BOARD TRBR-103A SCALE HAGAN SHOULD BE O 100 200 300. 8610071200 BR IR-BR-103B SCALE WRONG. 09/30/88 2 SHOULD BE NO INCREMENTS' 0F 50. 0 100 200' 300
-=-._________-__-____-__-_-______-___-_---_
ATTACHMENT 8' Page 4 of 24 SCHEDULED
' COMPLETION SMR NUMBER SYS DESCRIPTION .DATE PRIORITY 8610071205 BR TR BR 111B SCALE WRONG. . 09/30/88 2 SHOULD BE IN INCREMENTS OF 40. 0 40 80 120 160 200 (HAGAN) ,
8610071210 BR TR-BR-100 SCALE INCORRECT. 09/30/88 2 SHOULD BE. INCREMENTS OF
- 50. .0 50 100 150 200 250 300 400. L & N.
SPEEDOMAX H. 8612290912 BR INVESTIGATE CAUSE OF 10/26/88 2 UNUSUAL HIGH TEMP IN .l' GAS STRIPPER. 8706230922 BR CHANGE THE' LOW ALARM 09/30/88 2 SETPOINT FOR-LSL-BR-114-2 { FROM'42" TO 30" IAW j' SETPOINT CHANGE REQUEST SP85-40. COMPLETE IAW SYSTEM UPGRADE. 8805121015 CA' BREAK OUT MCA0401 TO MAKE 12/30/88 3~ IT MCA03. MAKE'MCA0402 ] INTO MCA04. ; 8709031045 CC COMPONENT COOLING WATER 08/30/88 1-SURGE TANK LEVEL ALARM : (V2GA1-W) HAS WRONG SETPOINTS. CORRECT AS SER' SP DOCUMENT. 8710241143 CC CCL730 DOES NOT INCREL4E, 08/30/88 1 CCM700 DOES INCREASE. VERIFY SURGE TANK LEVEL CHANGES. 8704101105 CH MKS03123 CHAN'S 14,15 68/15/88 1 ACTIVATE YIC COUNTERS 13,14 ARE SUPPOSED TO ACTIVATE & 15,16 ARE SUPPOSED TO RESET. 8710261010 CH MCH-19'HAS NO TRAINING 10/26/88 2
.VALUE & IS NOT FEASIBLE GIVEN.
l' l
ATTACHMENT 8 Page'5 of 24 SCHEDULED' 'I COMPLETION~ SMR NUMBER SYS' DESCRIPTION- DATE PRIORITY l 8803311115 CN CURRENT BORON CONC. 08/15/88' 1 DELETE MALF. MCH-19 FROM-
'I DATABASE. CONDENSER VACUUM DOESN"T CHANGE WHEN STEAM.TO AIR EJECTCRS IS STOPPED. .)
1 8803311120 CN CONDCILER VACUUM DOESN'T 10/10/88 '2 l l CHANGE ON A-LOSS OF CN / FLOW (NO COOLING TO AIR EJECTOR CONDENSERS) , d E711041424 CV CONTAINMENT PRESSURE 08/30/88 1 ) CHART MECORDER SCALE l SHOULD BE.0-180 PSIG d NOT 0-100 PSIG. .j (RED PEN; P-LM 110B) i
.I 8709241040 CW CHANGING THE CWLOGC 08/31/88 1 I
l ROUTINE FOR MOV-CW-101A/B/C/D,& () 81059 EL MOV-CW-102A/B/C/D. . NORMAL TO EMERG BUS TIE. 08/30/88 1 1 I l 82002 EL ADD LOAD SHED TEST 08/30/88 11 l SWITCHES.. 82004 EL 34. SKV RC TRIP, LTC & 08/30/88 1
]
LOAD SHED. l l 8311180845 EL BACKPLATE FOR MOP SWITCH 08/30/88 ,1 SHOULD DE AS SHOWN. ; l. 8412031145 EL SOFTWARE REQUIRES CHANGE. 08/15/88 1 NEW' ANALYZER HAS 3 RANGES. R1-0-100% CO2 IN AIR, R2-0-100% CO2 IN H2', R#-75-100% H2 IN AIR. l J l 3
. _ _ _ - - . _ . - - - _______2 . _ _ - - - .______-___-_____-:__-
ATTACHMENT 8' ; I Page 61of 24 SCHEDULED COMPLETION-SMR NUMBER SYS DESCRIPTION DATE PRIORITY 8602141602 EL CURRENTLY ALL RECORDERS 12/31/88 3 CONTINUE TO OPERATE ) DURING LOSS OF POWER-SIMULATION. PROVIDE HARDWARE & SOFTWARE NECESSARY TO ACTUALLY DEENERGIZE THE RECORDERS ? FOR PROPER SIMULATION. y RECORDER POWER SHOULD BE DEENERGIZED WHEN THE SIMULATOR IS SHUTDOWN. r 8805131315 EL ADD INSTR. VAR. TO LOGIC . 09/20/88 2 .] FOR V2HC3 W & V2HC4 W TOO KEEP ALARMS FALSE-UNTIL SET TO TRUE (ELPATCH H19 & ELPATCH H27) BLACK BOARD PROGRAMT l I 8701301600 FP INSTALL ALARM BELLS ON 10/15/88 2 FIRE PROTECTION PANEL TO
/ FUNCTION WITH ALARM , \ SIGNALS & INTERIOR HOSE ALARM. j l
8704101007 FP NO INDICATION WAS NOTED 09/30/88 2
]
USING SIMLOCH FOR.THE FOLLOWING POINTS: MX409051 CHAN'S'7,8 MONITOR PANEL, 7= MONITOR
- AUDIBLE 8 = MONITOR-R j i
8610071045 FW MOV-FW-100A,B,C,D. BACK 08/30/88 1 PLATES SHOULD_ READ NORM INSTEAD OF NORMAL-(AUX. SHUTDOWN PANEL). 8703041700 FW THE ENERGY BALANCE OF THE 08/15/88 1 , FW HEATERS IS NOT CORRECT. 4 AFTER TURBINE TRIPS-HEATERS ARE NOT ABLE TO , l GENERATE ANY HEAT TRANSFER ! CAUSING THE FEEDWATER TEMP TO DROP FROM' APPROX l 450 DEG. F TO APPROX 75 DEG..F IN.A FEW SECONDS.
'(
L R _ _ _ _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ . _
O
--4 ATTACHMENT 8.
Page 7 7 of'24 ye .
%._ /
SCHEDULED COMPLETION SMR NUMBER - SYS DESCRIPTION DATE PRIORITY ~ 87041101135 FW RAISE / LOWER SWITCHES . 08/15/88 1 REVERSED FOR MX404116,17. 8802081147 FW CONVERSION FACTOR- 10/31/88 2' TGGCONV_K FOR BTU /HR TO HP CONVERSION SHOULD BE EQUAL TO 3.929E-4 (PRESENTLY EQUAL TO 2545.1 ) CHANGING CONSTANT WILL AFFECT FW-P-2 OPERATION. 8608141025 GM EWR.84-497-LOOP BOOK 09/01/88 1 DRAWING REVISIONS TO GM SYSTEM PAGE GM 001. 8405021305 GW FLOW FROM CONTAINMENT : 10/30/88 2 VACUUM PUMPS NOT INCLUDED INTO GASEOUS WASTE PROCESS VENT FLOW (FT-GW-108). VACUUM PUMP FLOW TIES INTO' PROCESS VENT SYSTEM. ! I \ UPSTREAM OF CHARCOAL FILTERS
\w / (THESE REDUCE ACTIVITY SIMULAR TO THAT DONE BY VENTILATION SYSTEM FILTERS)
AND j 8502070907 GW SINCE THE WASTE GAS' 1'0/30/88 2 CATALYTICS RECOMBINER IS l NOT IN USE AT NORTH ANNA, THIS EWR 84-929 DISABLES ALL ALARMS ASSOCIATED WITH THE RECOMBINER. MODIFY NECESSARY PROGRAMS l TO COMMENT OUT THESE LOGICS. l (THEY MAY BE USED IN THE FUTURE SO'NEED TO BE RETAINED). AND 8510031030 GW WASTE GAS DECAY TANK 10/30/88 2 INSTRUMENTATION i MODIFICATION. i i M M&n w --____ L.-, _ - _ _ _ _ _ - - --z------_-------- - - n - 1 - - - - - =
. s aa a-
ATTACHMENT 8 Pago 8 of 24 SCHEDULED COMPLETION SMR NUMBER SYS DESCRIPTION DATE PRIORITY 8602281220 GW MODIFY SCALE TO 10/30/88 2 PI-GW-109A, 109B, 109C, 109D IN ACCORDANCE WITH LOOP BOOK PAGES GW-010, 011,012, & 013. SEE DCP - 84-46 FOR FURTHER ! INFORMATION. l 8703101537 GW INSTALL HYDROGEN ANALYZER 10/30/88 2 SWITCHES ON SAFEGUARDS PANEL. DO VIA UPGRADE SCHEDULE. I 8703111102 GW EWR 83-540 CHANGE 10/30/88 2 H2A-GW-102 INDICATOR & RECORDER SCALES VERIFY THIS CHANGE HAS BEEN INCORPORATED. I 8704101205 GW MX806037 CHAN'S 4,5 LIST 10/30/88 2 i AS SPARE BY DBLOOK INDICATE WITH CONCURRENT OPEN ACTUATION TVGW103A-C, ( TVGW103B-C. 8805290805 GW MALFUNCTION SHOULD BE 10/30/88 2 DEGRADABLE & RAMPABLE. ' 8312132001 HC MAIN GENERATOR HYDROGEN 50/30/88 2 SYSTEM & ASSOCIATED COOLING, PRESSUPE, PURITY,
& TEMP INDICATION NOT l MODELED. '
8402081900 MC VERIFY PROPER RESPONSE OF 10/30/88 2 MAIN GEN H2 COOLER LEAK MALF (MBC02) WHEN H2 THERMAL MODEL TESTING IS COMPLETED. 1 8404181800 HC IMPLEMENT INTO MAIN 10/30/88 2 GENERATOR MODEL THE ADDITIONAL ALARM INPUT TO ANNUNCIATOR TSC1 W OF (SEE DRAWING ATTACHED) I
- )
1 .O]
\~
' ATTACHMENT ~8 Page.9 of 24 SCHEDULED
. COMPLETION i SMR NUMBER SYS DESCRIPTION DATE PRIORITY I
{ 8703191050 HC. ECAO.O REQUIRES OPERATORS 10/30/88 2.- TO VENT OFF U2 IN' MAIN GENERATOR, UNABLE TO DO. 3 MODIFY WITH A VENT VALVE TO 1 DEPRESSURIZE (SEVERAL OTHER J PROCEDURES ALSO.HAVE.YOU l PERFORMED THIS EVOLUTION!). J 8704152120 HC THE FOLLOWING VALVE .09/30/88 2 LOGICS-WILL NOT GIVE l CLOSE INDICATION WHEN i SWITCH.IS PLACED.FROM OPEN l TO CLOSE.'TV-HC-105A&B,
- TV-HC-106A&B,'TV-HC-107A&D.-
3312132000 HV - VERIFY VENTILATION FLOW 09/01/88 1 PROPERLY DISPLAYED ON. STACK FLOW RECORDERS, l WHEN RECORDER OPERATIONAL. I 8411081235 HV- IMPLEMENT METHOD-TO ALLOW 12/31/88 '3 [~T FOR DYNAMIC RESPONSE OF.
\,_/ MAGNEHELIC METERS. -]
8702201400 HV VENT FLOW ON CHART 09/01/88. 1 RECORDER FR-HV-1212A H DOES NOT REFLECTLACTUAL FAN CONFIGURATION NEITHER' ) DOES FR-HV-1212B. l
. . I 8710221300 IA FROM.ICI WITH IA= .
10/15/88 2 j CONTAINMENT TU'S SHUT & i NO IA COMPRESSORS RUNNING ; IN THE CONTAINMENT, AIR ' PREESURE DOES NOT DECREASE. ! I UNDERSTAND THE-SYS*EM IN-I THE SIMULATOR DOES b " HAVE LEAKAGE. AIR LE: AGE i IS NORMAL IN ALLRAIR SYS'& :
'MUST BE SIMULATED WITH SOME l SMALL AMOUNT! y 4
it . 1 l f% l l '. i
, e o
[; g e
,t .-
+
1 y
ATTACHMENT'8-Page 10 of;24 O SCHEDULED COMPLETION SMR NUMBER SYS DESCRIPTION DATE PRIORITY-8610171520 IC STEAM DUMP CONTROLLER, 09/30/88 2 PZR MASTER CONTROLLER & OTHERS DO NOT RESPOND THE SAME AS IN.THE' PLANT WHEN SHIFTING FROM MANUAL TO AUTO. 8611131300 IC DETERMINE IF IT IS . 10/26/88 2 FEASIBLE TO INCORPORATE INSTRUCTOR CONSOLE DIAGNOSTICS ON NORTH ANNA PRODAC OPERATORS CONSOLE (BOTH UNITS ARE CTC DRIVEN.) NOTE
- WILL NOT AFFECT PRODAC OPERATION.
8704100950 IC REVERSED INDICATION WAS 11/30/88 3 NOTED.USING SMILOCH FOR THE FOLLOWING. POINTS: 2=DETA-BTM-LIM-18 SWITCH,4 8702201422 LW LIQUID WATER RECORDER. 09/30/88 2 FR-LW-104 DOES NOT SHOW FLOW WHEN PCV-LW-115 IS OPEN. 8802081800 LW ADD PCV-LW-118 TO THE 08/15/88' 1 AI LIST OF IC CHECK. 8806271403 LW VERIFY LOGICS-ARE CORRECT 04/15/89
~
3 ) FOR ALL LW SYSTEM PUMPS i WHICH HAVE SWITCHES OF THE TANKA NORM TANKB TYPE. THIS REFERENCES SMR #850121101. l 8608271512 MI FOR THE PROCEDURE: MODEL 09/30/88 2 TESTING AS A STAND ALONE TASK, STEP 1),'THE FILE F. , TEST PRESENTLY-MUST BE DIFFERENT FOR NORTH ANNA
& SURRY. THIS NEEDS TO BE CHANGED TO ALLOW ONLY ONE FILE.
=- -
ATTACHMENT 8 Pcgo 11 of 24. j
-l }
SCHEDULED COMPLETION SMR NUMBER SYS DESCRIPTION DATE PRIORITY 8609100811 MI METERS ON VERTICLE BOARD 12/31/88 3 HAVE TOO MUCH GLARE. l THEY ARE VERY DIFFICULT TO READ & HAVE LED TO MANY DIAGNOSTIC ERRORS. THIS IS A'VERY COMMON- l COMPLAINT AMONG OPERATORS
& INSTRUCTORS ALIKE.
8610061420 MI ELIMINATION-OF 08/15/88 1 UNNECESSARY CONTROL ROOM , NOISE. GAITRONICS CUTOUT. i SWITCH. INSTALL HARDWARE ON SHIFT SUPERVISORS DESK. ; 8610171543 MI SUBMIT WORK' ORDERS TO 12/30/88- 3- 1 HAVE SHIFT SUPERVISORS DESK PAINTED TO MATCH CONTROL ROOM.-ALSO.HAVE j LOGOS' APPLIED TO DESK &. 1 I WALLS TO MATCH CONTROL. ROOMS. 8612010800 MI AT PRESENT THE' INSTRUCTOR 08/15/88 1 CONSOLE RESPONSE IS SLOW I
& CPU SPARE TIME IS ONLY
~
7%. INVESTIGATE & PROVIDE MORE COMPUTATIONAL POWER TO PROVIDE MORE CPU TIME & INSTRUCTOR CONSOLE RESPONSE. 8703041331 MI IF.YOU SPECIFY A VARIABLE 12/30/88 3 NAME & GIVE IT A RECORD TYPE TO LOOK INTO, DBLOOK TAKES YOU THERE. THIS GETS YOUR LINKS CORRUPTED. DBLOOK SHOULD SET THE RECORD TYPE BACK TO ORIGINAL IF NOT FOUND. S 8703110948 MI EWR 83-468 CEILING TILE 12/31/88 3 REPLACEMENT IN CONTROL ; ROOM. ! l . l :
mp u ATTACHMENT 8 Paga 12 of 24 l
-l O SCHEDULED.
COMPLETION SMR NUMBER SYS DESCRIPTION DATE PRIORITY 8704101040 MI NO INDICATION WAS NOTED 08/15/88 1 USING SIMLOCH FOR THE FOLLOWING POINTS: MX804235 CHAN'S 1-11 ACCELERATION RATE, ANNUNCIATOR RESET. 8704130940 MI MXA07016 CHAN 3'WL-7950 09/30/88 2 SHEET 9 NOT WIRED TO ITEM 4 AS SHOWN ON WIRE LIST. GAITRONICS-M VU METER. 8705070815 MI FORTRAN SEES CLOSE AS A 12/31/88 3 KEYWORD 1F IT IS USED AS A CALL.TO A SUB-ROUTINE (OR AN ARRAY), BUT OTHERWISE ITS JUST
~ANOTHER VARIABLE. HOWEVER, SIMPR6 SOMEHOW PASSES THE VARIABLE CLOSE AS A KEYWORD g ) & INCORRECTLY PASSES THE L./ REST OF-THE LINE OF CODE..
8709031220 MI GAITRONICS MODIFICATION 08/15/88 1-
'10 ALLOW CONTROL ROOM CONTROL OF CHANNEL . PAGING.
IMPLEMENT WHEN EWR HAS BEEN IMPLEMENTED IN STATION. 8709291020 MI "N" KEY ON INSTRUCTOR 09/30/88 2 CONSOLE REPEATS NNNNNNNN. 8712210910 MI QUARTERLY P.M. RUN DISK' 08/30/88 1 DIAGNOSTIC WHILE RUNNING CN. BATCH 8780.- 8802251431 MI SIMULATION PREPARATION / -12/31/88 3 REPAIR 8802251433 MI SIMULATOR BENCH TEST / 12/31/887 3 REPAIR 8802251438 MI ' SIMULATOR MISC. TRAVEL- 12/31/88 3 CLEANING ROUTING CABLES. ETC. O
ATTACHMENT 8 Page 13'of 24 SCHEDULED COMPLETION SMR NUMBER SYS' DESCRIPTION DATE- . PRIORITY 8803251301- MI WHILE USING SIML6 SCREEN- 12/30/88 3 FORMAT "$F10": 1. USER IS-UNABLE TO PROPERLY
"$ RESTORE" IC.(CAUSES GLOBAL MEMORY TO BE CORRUPTED), 2. ALSO, DUPLICATE VARIABLES DO NOT-SHOW SAME DEFINITION.
8804071100 MI. RESOLVE PHYSICAL FIDELITY 09/30/88 2 DIFFERENCES BETWEEN SIMULATOR CONTROL ROOM
& UNIT 1 CONTROL ROOM.
'8804111300 MI TO REDUCE CONFUSION, NEED 08/31/88 1 TO DELETE MOST OF THE OLD REVISIONS OF ALL THE FILES ON THE LSI WINCHESTER DISK (SEE ATTACHED LOGS).
8804181220 MI INCORPORATE POWER SUPPLY -08/30/88 1
, TEST POINTS EXTERNAL TO
\ DECLSI'S FOR.P.M. PURPOSES, GROUND, SV & 12V.
8804290813 MI PERFORM DAILY BACKUP FOR 08/31/88- 1 THE MONTH OF AUGUST. CAREFULLY CHECK THE BACKUP LISTING FOR ANY ERROR AND CORRECT THEM AS REQUIRED. 8805080840 MI PERFORM MONTHLY BACKUP 08/31/88 .1 USING SOFTWARE APPLICATION PROCEDURE S1.3. CAREFULLY CHECK THE BACKUP LISTINGS FOR ANY ERRORS AND CORRECT
, THEM AS NECESSARY. CHECK OUT DISKS CAREFULLY ALSO..
8805250839 MI INVEST 1 GATE TPM FEATURE '10/31/88 2-TO ELIMINATE DUPLICATION OF.INFORMATION. (SEE' ATTACHED PRINTOUT). O r
_ _ = _ _ _ - _ _ - _ _ _ - - _ - _ _ l '- '1 t ATTACHMENT 8' Page 14 of.24 i 1 1 - SCHEDULED j COMPLETION ! SMR NUMBER SYS DESCRIPTION DATE PRIORITY l 8806240950. MI REVISE SIMULATOR PANEL 12/31/89 3 j DRAWINGS TO' REFLECT ! CURRENT AS/ BUILT l CONDITION TO ENHANCE i FUTURE H/W DOCUMENTATION ]
& PHYSICAL FIDELITY l REVIEWS.
- l. 8808010000 MI PERFORM COMPUTER POWER 08/31/88 1 SUPPLY P.M. FOR AUGUST 8808010001 MI PERFORM I/O POWER 08/31/88 1 l SUPPLY P.M. FOR AUGUST 8808010002 MI . PERFORM DISK DRIVE POWER 08/31/88 1 SUPPLY P.M. FOR AUGUST 8808010003 MI PERFORM FILTER CLEANING 08/31/88 1 P.M. FOR AUGUST 8808050841 MI PERFORM WEEKLY BACKUPS 08/31/88 1 l
USING SOFTWARE APPLICATION PROCEDURE S1.2. CAREFULLY-CHECK THE BACKUP LISTINGS FOR ANY ERRORS AND CORRECT THEM AS NECESSARY (MONTH OF AUGUST). 8802041215 MS STEAM DUMP ARMING SIGNAL 08/15/88 1-C-7 SHOULD CLEAR AFTER A ! TIME DELAY FROM FAILING 1 447 TO ZERO. SEE BACK OF l ATTACHED SMR.- 8806060840 MS SIMULATION SHOWS AN 12/01/88 3 EXCESSIVE LOAD DECREASE. WHEN MAIN STEAM INTERCEPT
&. REHEAT STOP VALVES ARE CLOSED. THE SIMULATION SHOWS 130 MW' DECREASE. IT SHOULD BE AROUND A 40.MW DECREASE.
8709041011 NS UPGRADE NS SYSTEM AS 08/30/88 1 i REQUIRED BY SCOPE. (] - 1 V i e g . n. l y
ATTACHMENT 8 Pago 15 of 24 O SCHEDULEQ COMPLETIO,N
~
SMR NUMBER SYS DESCRIPTION DATE PRIORITY 8404301515 PC VERIFY PRODAC MODEL 12/15/88 3 MEETS ITEMS ADDRESSED IN ATTACHED LETTER. 8406211850 PC STEAM GENERATOR FEED FLOW i2/31/88 3 TO PRODAC EVIDENTLY IS DERIVED FROM PROCESS l VARIABLE. SHOULD COME l FROM TRANSMITTER (WHICH IS THE CASE FOR ALL PRODAC AI POINTS). 8410121352 FC VALVES DISPLAYED BY 12/31/88 3 PRODAC ARE ERONEOUS--TOO MANY TO LIST. NEED TO DO FULL VERIFICATION OF ALL DATA / DISPLAYS TO ENSURE l' PROPER VALVES ARE BEING USED/ DISPLAYED. s 8410121503 PC USE DC 81-201 (ATTACHED) 12/15/88 3 [ AS A GUIDE FOR INSTALLATION OF SHIFT SUPERVISORS CONSOLE & ASSOCIATED.SPDS & COMMUNICATION SYSTEMS. j
**BEYOND SCOPE OF :
SIMULATION - ALLAN KOZAK 01/27/88** 8411081155 PC PRODAC NEEDS FEATURE SUCH 12/15/88 3 THAT WHEN AN INCORE THERMOCOUPLE IS SELECTED, AT THE INCORE PANEL A MESSAGE IS PRINTED ON THE ALARM TYPEWRITER. 8411081159 PC TEST /DEGUB/ IMPLEMENT 12/31/88 3 BEARING TEMPERATURE PROGRAM F.BRGTEM. 8506051500 PC TIME OUTSIDE AXIAL FLUX 12/30/88 3 BAND WHEN LESS THAN 50% POWER SHOULD ACCUMULA2E PENALTY MINUTES: ONE j PENALTY MINUTE FOR EACH 1 2 MINUTES OUTSIDE THE l BAND NOT ONE FOR ONE. WHEN j >50% IT IS ONE FOR ONE.
- 1
.i ATTACHMENT 8 Pago 16 of 24 ~
SCHEDULED z COMPLETION j SMR Nt1MDER SYS DESCRI,PTION DATE PRIORITY ) 8509121534 PC ANYTIME CORE IS AGED TO 12/30/88 3 EOL CONDITIONS THE AFD , ALARM COMES IN & CREATES i UNNECESSARY PROBLEMS. IT APPEARS WHEN YOU AGE THE CORE IT STILL LOOKS AT THE BOL TARGET & THUS CREATES ] THIS PROBLEM. **THIS i SITUATION NEEDS TO BE l CORRECTED PRIOR TO NRC J EXAMS. l 8610062037 PC ADD TO P-250 COMPUTER 12/30/88 3 l INPUT THE START & STOP l OF CONTAINMENT SUMPS PUMPS. 8702201217 PC COMPUTER (P-250) POINT 12/30/88 3 i L28000 WILL NOT ALARM I OR DISPLAY WHEN ! CONTAINMENT SUMP PUMPS N. CYCLE. , 8702201424 PC P-250 CRT DOES NOT HAVE 12/30/88 3 MORE THAN ONE COLOR FOR j INFORMATION. PLANT CRT j HAS RED, WHITE, YELLOW
& GREEN.
8702201428 PC P-250 DOES NOT GIVE 12/30/88 3 AUDIBLE BELL ALARM WHEN ALARM IS RECOGNIZED BT P-250. i 8704302000 PC COMPUTER POINT L28000 IS 12/30/88 '3 NOT ACTIVATING WHEN CONTAINMENT SUMP PUMPS TURN ON. 8705121214 PC PROVIDE COMPUTER POINT 12/30/88 3 FOR LI-DG-101 & 201 IMPLEMENT ON P-250 DURING UPGRADE.
ATTACHMENT 8 Pcg3 17 of 24
^l\ :
2 1 j SCHEDULED COMPLETION SMR NUMBER SYS DESCRIPTION DATE PRIORITY , 1 8802011452 PC UPDATE P-250 VARIABLE TO 12/30/88 3 i REFLECT THE INDICATIONS SEEN AT THE OUTPUT OF THE TRANSMITTER OA ANY GIVEN ! COMPUTER POINT. 8802031247 PC PRODAC POINTS VO413, 08/30/88 1 ; V0433, VO453 NOT FUCTIONAL i 8501252300 PG CHECK PG-P-1A & B& 08/31/88 1 ! PG-P-2A & B PUMP CHARACTERISTICS & i VERIFY CONSISTENCY TO ! TO PUMP HEAD CURVES. ! l PUMP DISCHARGE PRES 3URE SEEMS TO DECREASE MORE THAN IT SHOULO. l 8704130900 RC RAISE / LOWER WIRING 08/30/88 1 7- g REVERSAL FOR FOLLOWING l t i POINTS: MX803220,21
'd WL11-7934 SH 26 CHAN'S ,
4,5,6,9,10,11 ) MX803218,19 WL 1 8707271040 RC REPLACE PZR HTR PISTOL 09/30/88 2 GRIP SWITCHES WITH OVAL , TYPE SWITCHES. i 8710070157 RC MRC38 DOES NOT CAUSE RCP. 08/15/88 1 STATOR MOTOR TEMP TO INCREASE. 8711090900 RC UPON LOSS OF RC-P-1B & 08/30/88 1 RC-P-1C (UV ON THEIR l BUSSES), CHANNEL B TAVG ' PROJECTIONS & CONTROL l TRACKED DOWN WITH CHANNEL i C.TAVG CONTROL, BUT CHANNEL C TAVG PROTECTION DROPPED LOW QUICKER. 8805211305 RC COULD NOT START A 3RD RCP, 08/30/88 1 TRIPS ON OVERCURRENT WHEN LESS 250 DEGREES. l l- b) ()
ATTACHMENT 8 i Paga 10 of 24 1 O SCHEDULED COMPLETION 1 l SMR NUMBER SYS DESCRIPTION DATE PRIORITY
.8405160850 RD DURING RECOVERY OF ROD, 09/30/88 2 j
IN BANK SELECT C, DROVE ROD BANK IN (WITH MALF' l ACTIVE)'& REACTOR TRIPPED 1 ON HIGH POWER (SPIKE). l THIS ACTION RESULTS IN NO l ACTUAL ROD MOTION & THEREFORE NO REACTIVITY CHANGE. I.E. POWEP. SPIKED
& SHOULD NOT HAVE. 1 8508130847 RD RESEARCH & IMPLEMENT ROD 09/30/88 2 URGENT FAILURE ALARM &
LOGIC FOR AUTOMATIC ROD CONTROL MODE. 8705011535 RD INCLUDE SHUTDOWN BANK 09/30/88 2 RODS FOR MALFUNCTIONS MRD-21; MRD-26; & MRD-27. 8706100830 RD OCONE SIMULATOR HAD 09/30/88 2 l DIFFICULTIES WITH (O_/ MECHANICAL STEP COUNTERS MALFUNCTIONING UNTIL THEY PROGRAMMED THEM TO QUICK STEP (20SEC TO 228 STEP)
& THE STAFF ALLOWED THEM TO COUNT UP ON-IC CHECK. i i
THIS PREVENTED JAMMING THE STOPS & RESULTED ON WEAR O 8712120959 RD ALARM V1AD4_W WAS NOT 09/30/88 2 RECEIVED WHEN RODS WERE
>12 STEPS OUT.
8803280816- RD PLEASE INVESTIGATE _THE 08/15/88 1 j IMPLEMENTATION OF THE j ROD DRIVE MALFUNCTIONS. ! AT PRESENT IT SEEMS ONLY l ONE MALF PER GROUP CAN BE IMPLEMENTED. 8806221935 RD CONTROL BANK "C" ONLY 08/15/88 1 , PULLS TO 200 STEPS THEN STOPS. SHOULD PULL TO l 228 STEPS. l f'~N A L
ATTACHMENT 8 Paga 19 of 24 (D SCHEDULED COMPLETION l SMR NUMBER SYS DESCRIPTION DATE PRIORITY 8806300822 RD CHANGE RD METER OVERRIDE 08/15/98 1 DESCRIPTIONS AS PER ATTACHED LISTING. 8503082200 RM PRESENTLY BOTH GAS & 08/15/88 1 PARTICULATE ACTIVITY, FROM DECON BLDG, TO B STACK (RMR 017, 018) STICKS WHEN AOO-HV-113 IS POSITIONED TO FLOW l THROUGh FILTER, WITH FILTER l VALVES CLOSED. IN THIS CONDITION, THE OTHER VENTILATION FLOWS SHOULD i DILUTE (DECREASE) THESE l ACTIVITIES BECAUSE THEY i HAVE NO ACTIVITY. l 8609291220 RM (1) THE VICTOREEN MODULES 08/15/88 1 ' ARE NOT COMPLETELY ) FUNCTIONAL. IN SOME j MODULES THE ALERT DOESN'T s. s WORK, IN THE OTHER CHECK SOURCE DOES NOT WORK & IN THE OTHER ONE THE HI ALARM DOES NOT WORK. IT IS INCONSISTENT.
'2) THE DOCUMENTATION FOR VICTOREEN NOT PRE 8704100959 RM NO INDICATION WAS NOTED 08/15/88 1 i USING SIMLOCH FOR THE FOLLOWING POINTS: l MX808149 CHAN'S 1-16 VERT STACK MONITOR B.
8704101010 RM NO INDICATION WAS NOTED 08/15/88 1 USING SIMLOCH FOR THE FOLLOWING POINTS: MX809116 CHAN'S 11,12 ALERT-SAFE / RESET MX809117 CHAN'S 11,12 ALERT-SAFE / RESET. 8704231235 RM UPDATED CONVERSION 12/31/89 3 FACTORS FOR RADIATION MONITORS. O
ATTACHMENT 8 ) Pago 20 of 24 l SCHEDULED COMPLETION SMR NUMBER SYS DESCRIPTION DATE PRIORITY 8712141002 RM WHEN PERFORMING A FLUX 08/15/88 1 l MAP ON INCORE DETECTORS INCORE INSTRUMENT ROOM AREA MONITOR SHOULD GO q INTO SATURATION (FULL J SCALE) BUT DOESN'T SHOW ANY CHANGE. 8802171142 RM MODIFY PWR SUPPLIES TO 08/15/88 1 , RM-VG-112 & 113 PUMPS l FROM 1Al-1; CONTROL , FROM 14J-4. i 8805131244 RM N-16 RAD MON. SYSTEM 12/30/88 3 (NEW SYSTEM). 8806210830 RM INSTALL SERVICE WATER 08/15/88 1 RAD MONITOR 1-RM-SW-109 VICTOREEN MODEL 942A. (BAY 6) ,1 8807071000 RM INSTALL CONTROL ROOM AREA 08/30/88 1 RAD MONITOR 8610071059 RP REACTOR TRIP SWITCH BACK 08/30/88 1 PLATE SHOULD READ TRIP NOT TRI BENCH 1. 8712100215 RS THE OVERLOAD ALARM 08/30/88 1 (V2JC6 & V2JG6) DOES NOT ACTIVATE. 8406211921 RX MULTIPLE ROD EJECTIONS 11/30/88 2 HAVE ESSENTIALLY NO EFFECT ON CORE REACTIVITY (I.E. ROD WORTH DECREASES ' VERY LITTLE). 8510151120 RX REVISE SIMULATOR ECP DATA 11/30/88 2 TO REFLECT NEW INFORMATION CONCERNING SOMARIUM 149
& PLUTORIUM 239.
8603141446 RX UPDATE SIMULATOR TO 11/30/88 2 , REFLECT CHANGES IN l LICENSE ADMENDMENT 73 & 59 (OPERATION WITH A POSITIVE M.T.C.)
ATTACHMENT 8 Pago 21 of 24 i l SCHEDULED I COMPLETION SMR NUMBER SYS DESCRIPTION DATE PRIORITY 8607311530 RX THE MALFUNCTIONS MRD38, 11/30/88 2 i I MRD32 ARE NOT IMPLEMENTED AS PER THE CAUSE GIVEN IN I THE CAUSE & EFFECTS DOCUMENT. A T.R.W. OF.THE REACTOR TRIP & BYPASS BREAKERS IS NEEDED TO ACCURATELY REFLECT THE ESKs
& CORRECTLY IMPLEMENT THESE MALFUNCTIONS.
8801130945 RX IN ^(NAMODELS)F.ICCM, 11/30/88 2 THE INDEX 51 OF RKT360 IS BEING USED FOR BOTH THERMOCOUPLE N-6 & P-7. IN FACT, N-6 SHOULD BE USING INDEX 24 AS PER ATTACHMENT. I 8708311030 SD CHANGE SETPOINT FOR LEVEL 11/15/88 3 SWITCH LS-SD-148A & E. ( 8709031230 SD REPLACEMENT OF STH PT 11/15/88 3 HTRS & DRAIN COOLERS INSURE ENGINEERING DATA & , SETPOINTS ARE MODIFIED AS j NECESSARY WHEN THE DCP HAS BEEN IMPLEMENTED AT THE STATION. 8606300915 SS INCORPORATE NEW RECORDERS, 09/30/88 2 MAKE SOFTWARE CHANGES TO BEARING COOLING, ELECTRICAL
& ANY OTHER SYSTEM AS SCOPE OF SIMULATION REQUIRES. l 8609300914 SS CONDUCTIVITY SETPOINT 12/31/88 3 CHANGE INCORPORATED INTO MODELS AS SCOPE REQUIRES.
l 8705111015 SS PROVIDE SETPOINTS OF 1 12/30/88 3 PPB FOR NAR-SS 101, 102
& 7 PPB FOR NAR-SS-103 VERIFY SETPOINTS HAVE BEEN CHANGED PRIOR TO IMPLEMENTING THIS CHANGE.
ATTACHMENT 8 Page 22 of 24
/)
N s! i SCHEDULED l COMPLETION l SMR NUMBER SYS DESCRIPTION DATE PRIORITY j 8802170910 SW CHANGE OUT METER FI-SW 08/15/88 1 203A ON UNIT 2 EQUIPMENT ! PANEL TO A PRESSURE METER ) LIKE (PISW 201A) & RELABEL IT (PI-SW-201B) REFER TO METER PI-SW-201A FOR COMPARISON, LOCATED ON 0-2 EQUIPMENT. 8805040936 SW TEMP & FLOW INDICATION 08/15/88 1 . l FOR RECIRC SPRAY HDRS "C" & "D" NEED TO BE l SWAPPED. TI-SW-100C BECOMES TI-SW-100D FI-SW-100C BECOMES FI-SW-100D IAW - PHYSICAL FIDELITY. 8806130805 SW WHILE CLOSING MOV-SW 11/01/88 2 103A-D, 104A-D SW WATER PARAMETERS BROKE INTO k\
/
/
OSCILLATIONS. SPECIFICALLY CLOSING MOV SW 104C,D LAS BROKE SW SYSTEM INTO OSCILLATION. 8807181431 SW UPDATE DOCUMENTS SHOWING 08/30/G8 1 SW MOV's CLOSED. AFFECTED IC's WILL BE RESHOT WITH VALVES IN CORRECT POSITION. ) 8610071046 TU TURNING GEAR SWITCH (BEND 08/30/88 1 BOARD 2) BACK PLATE SHOULD BE LABELED MAN-OFF-AUTO EXISTING SWITCH LABELED OFF MAN AUTO. 8703161312 TU EWR 83-264 IMPROVES 08/30/88 1 TURBINE GOVERNOR VALVE OPERATION - ENSURE THIS HAS NOT BEEN REVISED THEN l MAKE THE CHANGE. (RETAIN l STROKE CURVES). l 4
1 ATTACHMENT 8 j Pagn 23 of 24 l SCHEDULED i COMPLETION i SMR NUMBER SYS DESCRIPTION DATE PRIORITY l 8704101140 TU NO INDICATION WAS NOTED 08/30/88 1 USING SIMLOCH FOR THE i FOLLOWING POINTS: MX404130 CHANS 4-6, 6 WORKS NO WIRE LIST. I 8704101444 TU TURBINE SPEED IS INDICATED 08/15/88 1 AT 1845 RPM BEFORE CONDITIONS ARE RIGHT FOR GEN. SYNCH. TURBINE SPEED SHOULD BE AT APPROX. 1811 RPM. 8704131235 TU MALFUNCTION CAUSES TRIP, 08/15/88 1 I CYCLES TURBINE VALVES
& WILD PLANT RESPONSE.
SHOULD ONLY CAUSE LOW PRESSURE ALARM & START THE STBY. PUMP. VERIFE PROPER SETPOINTS PRIOR TO bND E 4/30/87. 8707011000 TU DURING TURBINE S/U THE 08/15/88 1 UPPER TO LOWER CASING (HP MUST BE <125 F ON i POINTS 3 TO 4 & 10 TO 11 ON TEMP RECORDER ON TS PANEL. 10 TO 11 IS OK, BUT
#3 =541 F, & #4 =320 F, i DURING SU FROM 1C6/IC7. I THIS PREVENTS TURBINE START UP (OR PROLONG IT UNTIL INSTRUCTOR TRAINS AROUND IT).
8711041502 TV WHEN PERFORMING TURBINE 09/15/88 2 TRIPS IN OP 15.1 THE PROCEDURE REQUIRES THE OPERATOR TO VERIFY TURBINE STOP VALVE CLOSED USING THE P-250. SPECIFICALLY, HE IS TO VERIFY VARIOUS ALARMS ARE RECEIVED ON THE ALARM (TYPEWRITTEN (OP 15.1 PAGE 9)). l
y 3 ATTACHMENT 8 l Paga 24 of 24 l
)
O SCHEDULED COMPLETION SMR NUMBER SYS DESCRIPTION DATE PRIORITY q 8602041850 VV USE ATTACHED GRAPH FOR- 12/31/88. 3 ENHANCING MOV MODEL. THIS. : GRAPH INDICATES MOTOR LOAD ! FCR OPENING VALVE. ) 8602261055 VV' WHEN A MOV LOSES 12/31/89 3 ELECTRICAL POWER, IT CAN STILL BE' OPERATED LOCALLY, :l SIMILAR TO LOCAL-VALVES. j NEED TO PROVIDE EITHER PEDS CONTROL OF MOVS-(PERFERRED) OR PLANT EQUIPMENT FILES. MADE (ALTERNATIVE) TO ALLOW INSTRUCTOR CONTROL OF MOVS. (SEE ALSO SURRY SMR () j i l ! 1 I l I
O VIRGINIA POWER SIMULATOR SUPPORT GROUP NORTH ANNA UNIT.1 SIMULATOR ATTACHMENT 9 CONFIGURATION MANAGEMENT OVERVIEW DOCUMENT O
ATTACHMENT 9 SSG 2.0 05/13/88 ; () Revisdon 0 Page 1 of 10 j SIMULATOR CONFIGURATION MANAGEMENT OVERVIEW 1.0 Purpose The purpose of this document is to describe the Simulator Configuration, performance criteria, and management system used to establish and maintain a sufficient degree of completeness and accuracy of simulation of the Virginia Power Nuclear Power Plants (North Anna and Surry). It is intended that in meeting !' the criteria of this document, the respective simulators will meet or exceed certification requirements of the Nuclear Regulatory Commission. 2.0 Responsibilities 2.1 Supervisor Training (Simulator) ; o Coordinate activities with training center and power station personnel to identify needed simulator changes and maintenance schedules. o Develop and implement a plan for validation f- of the simu3ators which meets NRC and INPO I requirements. o Represent Virginia Power on, and participate in activities of, appropriate industry )I related committees and societies. o Consulting with the Supervisor Training (Power Station Operations) to support < effective utilization of the simulator to , meet training objectives. ' 2.2 Simulator Support Coordinator o Independently research regulatory or occupational information and interface with station training staff to identify training requirements. o Act as subject matter expert to review training materials for technical accuracy and for determining scope of simulation. l l o Prepare responses to audits by INPO, NRC, l Virginia Power, or other agencies. l l
j ATTACHMENT 9 SSG 2.0 4 05/13/88 l Revisjon 0 ! Page 2 of 10 (- ) o Provide technical assistance to the supervisor and other groups within the simulator support group. o Support the Supervisor in the evaluation of work done by the vendors in support of simulator upgrade or design change activities. ; o Assist in obtaining and interpreting records of power station transients necessary to support simulator certification effort. , 1 o Assist the training center instructors in i their use of the simulator by defining ) capabilities and limitations of the simulator j to perform certain simulator exercises. ' o Represent Virginia Power on, and participate in the activities of, appropriate industry l related committees and profasedonal societies. o Develop and perform tests to insure simulator response to be within or exceeds requirements Is i of a certified simulator as established by
\-'# the Nuclear Regulatory-Commission.
2.3 Simulator Technician (Hardware) o Provide inputs for software, hardware maintenance and upgrades. f 1 o Document all simulator hardware changes. , 1 o Review and approve procedures pertaining to i hardware and software on the simulator. l 1 o Coordinate hardware portion of NRC simulator )' certification. o Assist in setting priorities for hardware . section work as a function of plant changes I and simulator availab'ility. ! o Direct the activities of the hardware section j l personnel. ; i gg NjY l
ATTACHMENT.9 SSG 2.0 ! 05/13/88 Revision 0
-() 2.4 Engineering Software Analyst (Simulator)
Page 3.of 10 o- Provide inputs for software,-hardware j maintenance and upgrades. o Document all simulator software changes. 't o- Review and approve procedures pertaining to hardware and software on the simulator.- o Coordinate the software' portion of NRC simulator certification. ,
?
o Assist in setting priorities for software ! section work as a function of plant changes and simulator availability. I 2.5 Administrative Assistant 'l l o- Administer the handling and maintenance of records.
)
o Prepare, compile, and verify reports and project authorization. () o Maintain documentatica according'to company-standards. I o Develop and maintain record keeping l< procedures. l 1 o Assign, distribute, and coordinate typing and I computer output requests. l] o Direct the activities of the administration ; section personnel. l 1 3.0 Definitions j J 3.1 Integrated Plant Test - A real time. test of:the l response of the simulator. The specific function ; of this test'is to monitor the inherent plant: j l response with particular attention to system ] interfaces. l j 4 3.2 Malfunction Test - A real. time test of the response;of.the simulator to normal and emergency l conditions resulting from the malfunction. The-l specific function.of this test is to verify , l inherent plant response and the functioning of l automatic plant controls as established in the ; Simulator Cause and Effects Document. ! km I I k . _ _ _ _ _ . _ _ _ _ _ _ _
l l ATTACHMENT 9 l SSG 2.0 i 05/13/88 ' Revision 0 Page 4 of 10 i 3.3 Planned Maintenance System - An organized, structured system used to periodically verify the operation and status of the simulator equipment, hardware and software, to minimize lost training time. 3.4 Scope of Simulation - Estab13shes the boundaries of Hardware and Software simulation to provide a detailed modeling of a system of the reference 1 plant with which the operator interfaces with from i the control room. 3.5 Simulator Data Base - A collection of documents l that describe the current performance and ! standards chosen as simulator boundaries.
)
1 3.6 Simulator Modifications Report (SMR) - A report ! that identifies and tracks deviations in simulator l performance or appearance from the current design { specifications. j 3.7 Simulator Support Guidelines (SSG) - A document which sets the detailed requirements and philosophy of approach to the performance and , duties of the Simulator Support Group. l 3.8 Simulator Modification Resolution Report - A report used to document to the training staff that a previously submitted SMR has been resolved and that the problem no longer exists on the simulator at that time. 1 3.9 System Test - A real time test of the response of the simulator to normal and abnormal conditions with particular emphasis on the reaction of the system being tested.
"! . 0 Simulator Configuration Management 4.1 All software and hardware modifications, upgrades, changes, etc. will be performed in accordance with the appropriate sections of the Simulator Support Guidelines.
4.2 Simulator Design Data Base - Baseline Data 4.2.1 Virginia Power simulators (North Anna and Surry) are presently established based on available data as of September 30, 1986. O
ATTACHMENT 9
-SSG 2.0 05/13/88
- Revision 0
. Page 5 of 10 4.2.2 During the month of January of each year a tape and' disc back up of current simulator software configuration shall be made and stored as a record of that year's base line date.
4.3 Simulator Design Data Base - Performance' Data. 4.3.1 ' Actual reference plant data-when available shall be used as the technical basis for the simulator. 4.3.2 In cases when simulator response is undocumentable,'i.e., no plant reference data is available for the event, operator experience and engineering evaluation is utilized to ensure that the response is acceptable. 4.3.3 Simulator performance tests shall be performed in a rotational.basiscin order-to insure continued simulator reliability and certification requirements.
. 4.4 Simulator Modifications 4.4.1 Operator Input - Feedback from Training Supervisors, Superintendents of-Operations, Shift Supervisors, Reactor-Operators and other trainees will be' evaluated and appropriate modifications will be made to the simulator.
o Initial evaluation of " Operator Inputs" shall be performed by the Senior Simulator Instructor for the recpective plant's simulator,. o The Senior.-Simulator Instructor will act as the point of contact for'all: feedback to plant personnel relating to-simulator modifications. 4.4.2 Plant Modifications - Plant modifications will normally be documented through thel use of Design Changes'or Engineering Work Requests.. These: changes shall;be reviewed' and implemented ~within a year or as'soon there after as possible of installation:of the change in the plant. O
l ATTACHMENT-9 3 SSG 2.0 l ~ 05/13/88 Revision.0 { ), .Page.6 of 10 4.4.3 Operating Events - NRC bulletins, notices, INPO reports, LER's and Training Impact- l Reports should be reviewed for possible l l impact on the Scope of Simulation. 4.5 Simulator Modification Planning /. Implementation 4.5.1 Reports - In order to allow for an efficient. planning of work to be perf ormed, the following : reports are provided to all of the. sections of the Simulator Support Group. o Weekly SMR Report - Lists all' outstanding SMR's which are scheduled to be. completed'during'that week. (Updated weekly).
- o. Monthly SMR Report - Lists all the outstanding SMR's which are scheduled to be completed during the next 30 days. ~This allows for the development of necessary software and installation' of any hardware required.. (Updated weekly)
O o Six Month SMR Report - Lists all the outstanding SMR's which are scheduled j to be completed during the next six ; months. This allows for advance i planning of jobs. requiring large amount I l of time for software development or. ordering of necessary hardware parts or ! development of testing procedures. l' 1 * (Updated monthly) 4.6 Planning Meetings i o Simulator Support Group Meetings - Normally held on a weekly basis.to discuss progress of the previous week, requirement to reestablish completion dates of scheduled SMR's and plan-work for upcoming week. - o Simulator Progress Meetings - Periodic meetings held with the simulator instructors at each station to discuss progress or areas of concern which may.not have been documented via telephone conversations or the ; modification report. I O ; i i
ATTACHMENT 9 SSG 2.0 05/13/88 Revision 0 () gs o Engineering Design Review Meetings - Meetings Page 7 of 10 held with Engineering and Construction during the development stages of design changes that affect the simulator. Normally held at the 30%, 70%, and 90% completion stages. 4.7 Modification Implementation 4.7.1 After an in-depth review and determination of the changes to the scope of simulation, the modification is approved and scheduled for implementation in the simulator. 4.7.2 Hardware coordinates and performs all alterations to the simulator physical fidelity ensuring hardware configuration control in all areas. 4.7.3 Software develops all software models and performs a stand alone test at prior to' transfer to the site. The test shall be designed to ensure that the modified simulator meets the requirements of the SMR. It is the responsibility of the
's software person (s) develcping the modification to consider as a minimum the following:
o Digital Input Loops o Analog Input Loops o Control Room Diagnostic Checks o Instructor Overrides o Malfunctions o Remote functions (PEDS) o Monitored Parameters o Logic Response o Dynamic Response o Steady State Response o Transient Response 1
ATTACHMENT 9-SSG 2.0 05/13/88 ROvision.0 O' 4.7.4 Operations developes any test procedures Page 8 of;10 which may be required. 4.7.5 Once the modification has-been prepared, reviewed, and revised the changeLis-then transferred to the site and' installed in the development mode for initial testing. 4.7.6 Upon successful completion of the test in 8 development, the Operations' Specialist-coordinates with the Training staff and allows the transfer of the modification to ~ the operational mode. 4.7.7 The Modification is then tested in the operational mode to verify proper response.. 4.7.8 The Operations Specialist.then submits a Simulator Modification Resolution Report to the' Senior Simulator Instructor informing him of.the changes which have , been performed on the simulator. 4.7.9 Documentation Upgrade - The intent of the O. updating process is'the ensure that the usefulness and accuracy of the documentation associated with the Simulator. It is necessary that the documentation employed to perform simulator modifications reflect the current training simulation. .All previous updates shall be incorporated in their final form on the documents'used to j generate the update package or the 1 accuracy of the update package and associated documentation cannct be , assured. It is the responsibility of'the l person (s).who develop the necessary changes for the simulator to insure that ; the documentation is' complete. 4.7.10 The SMR is completed and entered in'the SMR data base as b'eing closed. A hard copy of the completed SMR is filed with 'l the system changed by the modification. i O
ATTACHMENT 9 SSG 2.0 1 05/13/88
,~
< Revision 0 ;
1 {}s Page 9 of 10 { 5.0 Simulator Planned Maintenance System 5.1 To ensure the proper reliability of the simulator, it is necessary that a standard practice of performance checks, backups and maintenance be ] performed on each simulator. 5.2 For each of the items requiring preventive I maintenance, they shall be performed in accordance with the requirements set up in the Simulator Support Guidelines. 5.2.1 hardware - SSG-H 1.0 5.2.2 Software - SSG-S 1.0 l 6.0 Files / Procedures i 1 6.1 The Simulator Support Group's filing system is ! setup to conform to company policy as well as the system descriptions of the stations. The system affords a convenient method for the Administrative l Group to find information in the files with system j designators'given by other members of the group. I Simulator Support Guideline 4.6 gives further g-w)s g details on the filing system. l 6.2 Information kept in the files includes outstanding SMRs, closed SMRs, scope of simulation, and completed test procedures. Members of the administrative group are responsible for checking the files or original SMRs in and out of the file room. This information is kept on orange "out" cards at the front of each file drawer. Only members of Administrative Staff are allowed to use the files in the file room. The person who takes any information out of the files is held responsible for it once their name is on the card. , 6.3 The Simulator Support Group has guidelines and application procedures which are controlled manuals. These manuals are available at all of the training sites. The guidelines are used to understand how the group functions as a whole unit. 6.4 The application procedures are broken down into each of the three sections of the group and set forth how each group performs certain activities.. 4 4
l s ATTACHMENT 9 Li SSG 2.0 l 05/13/88 l [,~,') - Revision 0 l
\> Page 10 of 10 I 6.5 The Administrative Group is responsible for processing and making revisions to the guidelines and procedures. Since they.are a controlled document, revisions and additions are issued in a memo and the new or revised procedure attached.
l I l ("') s_- l 1 4 O
NLCFOp.sa74 ise ras itt U.S. alWCLEAR REOULATORY AfsP'esw ov CoasMeS8a
;i C.' "."* SIMULATION FACILITY CERTIFICATION IM& =
O "RUCTIOa'3. Thrs form is to Oe filea for inssiat certification, decertification lef reouiredi. and for any change to a simu6ation facility performance testing pian h oe after ms.at submittal of such a pian. Provice the foHovnng mformation and check the approprets box to inacate re for submittal. i F ACILIT Y ' DOCKE r NUMSER NORTH ANNA POWER STATION 50 n g ! LICEN5E E DATE VIRGINIA ELECTRIC AND POWER COMPANY - og /I n /R A
% . . n
. i.e . ia.
.a :
=.e.-
i ,a e a ass.u.=sn=a
.a a s inao .-
NAXE for orner #aunresceraanJ AND LOCAT40N OP SIMULATION P ACILITY a.ac :.,._ . o .u . i ... ra= _- .e e.mac si _ _== ==
.c.an.m . 3.e.w cra es.a.m.i.vse NORTH ANNA UNIT 2 SIMULATOR. NORTH ANNA POWER (;TATTON_ MTM7 RAT. VA AT TMF run nr c'mr* tmty i l SJMULATiON 7 ACILf TY PE RFORMANCE TEST ABSTR ACTS ATTACHEO. (for performance essrs canawtse m the amme ne.nr wr4 ene sure of ras el 700 DESCRIPT107, OF PER70PMANCE TESTING COMPLET ED (Aresca acomense payress as necess v.amr essemer rne # rem summerses aswer centsausurt I SEE ATTACHED DOCUMENT I
1 l $IMUL A IION F AclLli Y PE R*ORMANCE i ESTING SCHEQULL ATT ACHEO. af or ene consier or amorossmafory 255 orperteniserice restsper rear for ene tour rearpe'uos I eommeverme .e=en the sete of #nte correhearson 7 0F SCRIP TION OF PE R7ORMANCE TESTING TO 8 E CONOUCTED (Atraen acustsonas saperss as ner.smer, ans scisarrry rne nem osacrorma eseny roarenuses I i SEE ATTACHED DOCUMENT PE R FORM ANCE TESTING PL AN CHANGE. (For aar anodrfraren to a perfomware restav Adan subartreet on a prewtow terrs#merson# DESCRIPTION OF PE R50RM ANC E TESTING PLAN CHANGE (Artsen soorteenst seyevas as ascessary, ana eosersty rne trem essenpreon comy contenuscri NOT APPLICABLE AT THIS TIME ti a Hcreen t CE emr,rro., Rt 6F ICATmSON e an(D,
.,v esc,rsor ear sr acswructs.e,eersom ressa.r me n, eae ere,a wa me,na errscn resuers or comose enarm.
voen raurang cerr, ..- accarence u en 80 CF A $ 61e5tDif6Jte). e NOT APPLICABLE AT THIS TIME Aav sei.e siaisawas or 9mm orba ia.s cas. ament. .acsuo.at estacnmears. <r.., os suoieci io c.. ene crema. uncuou a cerus, uaoer owneerv os pe<sur, snet une maareneuen sa tais u m a. saa enoca,Pwe . fue ..uyerreev _NAT / ~ O/ZE(VR fPRJSENTATIVE cart l TITLE
/ /'
Mf W. R. CARTWRIGHT VICE-PRESIDENT-NUCLEAR in accorcant'E4tn 10 Cf R e $5.b. Communications, inis form snail De suomitted to tne N HC as tonows: 88 BY Mall ADDRESSED TO. Detector.Offace of Nucesor Reactor Reguutson BY DELfVERY IN PERSON U.S. Nuch Rogsta:Erv Commessen TO THE NRC OFFICE AT: Washmgton, DC 20555 7920 Norfolk Avenue Bethemos. MD l
i i I
-1
' ll j
l i l i i i NORTH ANNA UNIT 2 SIMULATOR C3 RATIFICATION SUBMITTAL 4 4
/n) 'u/ North Anna Unit 2 Certification Submittal This North Anna Simulator Certification Submittal consists of the following sections:
. Unit 2 Control Room / Simulator Panel and Environment Comparison (Attachment 1)
. Unit 1 Control Room / Simulator Panel and Environment Comparison (Attachment 2)
.Ot (.) 1
i Q VIRGINIA POWER SIMULATOR SUPPORT GROUP 1 l l 1 1 i I NORTH ANNA UNIT 2 SIMULATOR r ATTACHMENT 1 ( , CONTROL ROOM / SIMULATOR PANEL AND ENVIRONMENT COMPARISON l l l 1 O
r-l ATTACHMENT 1. 1 Page 1 of 8 . i l
.d' I
North Anna Unit 2~ Certification Submittal l Control Room Pane] .j Comparison Report i The North Anna Power Station is a two unit- station, operating from a common control room (Figure 1).- The respective unit control panels are identical in their configuration and layout with respect to the operator. A few auxiliary systems panels present a mirror image layout i to the operator in order to maintain an overall balanced i appearance of the control. room. Some . minor . differences i exist with secondary equipment controls. These are i discussed in more detail within this report. This report is a comparison between the unit one and unit two control room panel layout and component configuration. Each panel is discussed individually. Differences are identified and addressed. , Environmental differences and differences:between the ) simulator and the unit one control room'are discussed within ! the Control Room / Simulator Panel and Environment Comparison Report, Attachment 6, of the North' Anna Unit 1 Simulator. Certification Submittal which has been included for your O convenience. As a result of this comparison report, the North' Anna j Unit 1 Simulator. training requirements meets all Unit 2. training needs. ] l I i l i 1 1 i
ATTACHMENT 1
'Page 2 of 8 O Control Panels Specific to Unit Two Operation NRC Radiation' Monitoring Panels Bearir.q Cooling Panel-Axial Power Flux Distribution Monitoring Panel Incore Nuclear Instrumentation Panel Intake Structure Control Panel l Fire Prot'ection Panel 2H Emergency Diesel Generator Panel Turbine Supervisory Panel.
2J Emergency Diesel Generator Panel' Ventilation Panel Radiation Monitoring Panels SPDS Control Console O. P-250 Operator's Console Excore Nuclear Instrumentation Panels Benchboard #1 Benchboard #2 Vertical Board #1 Vertical Board #2 Safeguard Panel #1 Safeguard Pane] #2 Post Accident Monitoring Panel O _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ . _ _ _ _ _ _ _ - _ . _._._.__._______-.._._.______._.__________________.._._-.___.__.__.____..__2
1 y _ ATTACHMENT 1
- Page 3 of 8
~
R . 1 o l i !Ni!!i- I
+
,,,i,<<
W 2 % i !! 'k i (2E
...[gil a,
ggo 111151. al0 i
\ %
7 dididi %~\
- I 1 (( \
\\
/ g k"*I O i
g
-[ ... ~. ~. if d .. !a n:22: y ##if g
t!s _h
~
!E O ii Egl [E' 8 8
;g!!j E! t t
a
; }
l
+ 1111 h. : is T
E a u sz i l U li hf : g e assi i
=- =e==. . . . , .
, :j,-
3 g e 1i iiii T i {!
)g=g .s i hem *. .
s.:sse { - O -. i i , IoO 7 gk Io I l.:w e ss
ATTACHMENT 1 Pago 4 of 8 l i ( NRC Radiation Monitoring Panels The High Range Effluent Monitoring System Panels are located in the north west corner of the main control room. These panels provide indications and alarms for radiological releases from effluent steam paths. The unit one and unit two panels are identical in function and style, and are located next to each other. The reference plant panels, unit one, is fully simulated and located in a similar position in the sinulator control room. Therefore the unit two panels are not simulated. Bearing Cooling Panel The Bearing Cooling Panel contains the controls and indications for the operation of the Bearing Cooling Water System. The unit one and unit two panels are identical in function and configuration. Only the reference plant panel of unit one is simulated. Axial Power Flux Distribution Monitorine System (APDMS) Panel O The Axial Power Distribution Monitoring System Panel was used in conjunction with the Incore Nuclear Instrumentation System to perform flux mapping. It is no longer operable in the plant. Unit one and unit two panels are identical in function and switch configuration, therefore only the reference plant unit one is simulated. However the APDMS panel is physically simulated, but not modeled. 1 Incore Nuclear Instrumentation Panel The Nuclear Incore Flux Distribution Panel contains the controls and indications used for the Incore Instrumentation system. Both unit one and unit two panels are identical in function and switch configuration. Therefore only the unit one reference plant panel is simulated. This panel is fully _modeled, logically and dynamically. Intake Structure Control Panel The Intake Structure Control Panel contains the controls and indications for the Circulating Water System. ! unit one and unit two panels are identical in function and j 0
, switch configuration.
panel is simulated. Only the reference plant unit one This panel is fully modeled both logically and dynamically. i i l l l I
j ATTACHMENT 1 Paga 5 of 8 Fire Protection Panel The Fire Protection Panel monitors and displays the-status of fire suppression systems in various locations of the respective units. The unit one panel, contains indications of plant areas that.are common to both units. Unit two panel is more unit specific. Therefore the unit one panel is simulated to provide more overall plant training. 2H Emergency Diesel Panel The 2H Emergency Diesel Panel is located among the respective units' backboard panels and provides all the necessary control and indication to operate the Emergency Diesel Generator. The unit one and unit two panels are identical in function and switch configuration. Therefore only the reference plant unit one panel is simulated. Turbine Supervisory Panel The Turbine Supervisory Panel is a backboard panel that provides indications and alarms for various turbine control systems. Units one and two panels are identical in function O and appearance. Therefore only the reference plant, unit one, is simulated. 2J Emergency Diesel Generator Panel The 2J Emergency Diesel Generator Panel contains all the controls and indications- for the operation of the Emergency Diesel Generator. The unit one and unit two diesel panels are identical in their layout and , configuration. There are no differences in the operation ; between the units. Therefore only the unit one reference j plant panel is simulated. l 1 i Ventilation Panels l l The Ventilation Panels contain controls and indications l for each of the respective units' ventilation systems. Some l
~ systems controls which are common to both units.are shared i between the two panels. Since the ventilation systems are i identical for both units only_ the unit one reference- plant ventilation panel is' simulated. The unit two ventilation panel is partially simulated to contain the control features of the common shared systems. This panel is located in the same approximate position as the actual <
{} panel. __ m _ _ _ _ _ - _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ . . _ m.__- - . _ _ _ -. - ---
ATTACHMENT 1 Page 6 of 8 Radiation Monitoring Panels The Radiation Monitorirg Panels provide control, indication and alarms for the process and area radiation detectors for their respective systems. The unit one and unit two systems are identical. Therefore, only the reference plant unit one panels along with the common panels are simulated. Safety Parameter Display System (SPDS) Consols The SPDS Consoles contain the CRT Monitor and keyboard functions to monitor the respective units vital parameters. Their operations are identical, therefore only the reference plant unit one console is simulated. Plant Computer Console The Plant P-250 Computer for each unit are identical to each other in their features and controls. Only the reference plant unit one computer console is modeled. t Excore Nuclear Instrumentation Panels O The Excore Nuclear Instrumentation Panels for their respective units are identical in their appearance and controls. Only the reference plant unit one panel was , simulated. Benchboard #1 The main control room Benchboard Number One contains the indications and controls for components of various primary systems. The unit one and unit two number one benchboards are identical in control and configuration. Only the unit one reference plant benchboard is simulated. O
ATTACHMENT 1 Page 7 of 8 Benchboard #2-The main control room Benchboard Number Two contains the controls and indications of components for various secondary and electrical systems. The unit one and unit two j benchboard number two are identical except for the following: o Unit one board contains nine additional electrical switches for control of common components. o Unit one board contains three switches for control of common redundant components. These differences have no training impact and therefore only the reference plant unit one benchboard is simulated. Vertical Board #1 The main control room Vertical Board Number One
-contains all of the equipment necessary for operating and monitoring the nuclear instrumentation system and other various primary plant systems. The unic one and unit two vertical boards are identical in configuration with the-exception of the unit one board containing two additional O switches and an additional indicator for components of common systems.- These slight differences actually enhance training, therefore, only the reference plant unit one panel is simulated.
Vertical Board #2 The main control room Vertical Board Number Two contains the control and indications for various plant secondary systems. The unit one and unit two panels are identical in their configuration with the following exceptions: o The unit one board contains two additional-indicators for components of common systems. o The unit two board contains the controls for the common chilled water system mechanical -chiller. These controls are simulated on another panel. These differences are minor and have no ' training impact. Therefore only the reference plant unit one vertical board #2 is simulated. f I
ATTACHMENT 1 Page 8 of 8 Safeguard Panels 1 and 2 The Safeguard Panels contain the controls and indications for numerous components of the primary, secondary and safeguard systems. The unit .,e and unit two panels are identical in their configuration except for the following: o The unit two board contains additional switches for a minor system modification to the instrument air system. o The unit two board contains switches for the heat trace system for the cemmon hydrogen analyzers. These are minor differences and have no training impact. Only the reference plant unit one panels are simulated. Post Accident Monitoring Panel, The Post Accident Monitoring Panel contains the controls for systems affecting the containment environment. These panels are redundant in nature and identical in their configuration. Therefore only the reference plant unit one lll panel is simulated. O
VIRGINIA POWER SIMULATOR SUPPORT GROUP NORTH ANNA UNIT 2 SIMULATOR ATTACHMENT 2 NORTH ANNA UNIT 1 CONTROL ROOM / SIMULATOR PANEL AND ENVIRONMENT COMPARISON O I l i 1 i i O
sv ATTACHMENT 2 Page 1 of 16 NORTH ANNA CONTROL ROOM AND SIMULATOR' COMPARISON OF PANEL LAYOUT AND ENVIRONMENT This report is a comparison between the control ~ room panels (Figure'1 of this attachment) and simulator panels (Figure 2 of this attachment), their layout, and the general surrounding environment. The report is in two parts, part "A" covers equipment panels,-and part "B" discusses the environment. Each panel will be reviewed individually. Information. will be given, such as name, location, functionLand associated units. Each panel.is also reviewed for its training-value. The major areas-of the environment that are covered are, lighting, noise, and color scheme. Minor differences will be noted and all areas will-be in reference to its training value. This comparison is not intended to be the definite i simulator Physical Fidelity' Comparison' Report. The Physical Fidelity Comparison Report is contained in Attachment 4. O 4
)
i
- _- _ _-_ O
ATTACHMENT 2 Paga 2 ofL16
'( ~
SIMULATED PANELS NRC RADIATION MONITORING KAMEN RADIATION MONITORING PANEL LIQUID WASTE ~ PANEL BORON RECOVERY PANEL s ~ RADIATION MONITORING PANEL VENTILATION PANEL 1J EMERGENCY DIESEL PANEL TURBINE SUPERVISORY PANEL 1H EMERGENCY DIESEL PANEL PRESSURIZER SAFETY VALVE MONITORING PANEL HIGH RANGE RADIATION MONITORING (VICTOREENS) ROBERT SHAW FIRE PROTECTION PANEL STATION FIRE PROTECTION PANEL BEARING COOLING PANEL CIRCULATING WATER PANEL SWITCHYARD DISTRIBUTION PANEL LOAD FOLLOW PANEL REACTOR' COOLANT PUMP VIBRATION PANEL AXIAL POWER FLUX DISTRIBUTION MONITORING SYSTEM PANEL INCORE NUCLEAR INSTRUMENTATION PANEL VITAL BUS TRANSFER SWITCHES MAIN ANNUNCIATOR PANELS'
, VERTICAL BOARD #1 VERTICAL BOARD #2 O SAFEGUARD PANEL #1 SAFEGUARD PANEL #2 POST ACCIDENT MONITORING PANLL UNIT 2 EQUIPMENT PANEL (SIMULATOR)
BENCHBOARD #1 BENCHBOARD #2 AUXILIARY SHUTDOWN PANEL P-250 STATION SHIFT SUPERVISOR DESK (INCLUDE COMMUN' CATION EQUIPMENT) l O
ATTACHMENT 2. l Page 3 of 16 l ' NON-SIMULATED PANELS - PANELS SPECIFIC TO UNIT 2 OPERATION < NRC RADIATION MONITORING BEARING COOLING PANEL AXIAL POWER FLUX DISTRIBUTION MONITORING l CIRCULATING WATER PANEL' {' INCORE NUCLEAR INSTRUMENTATION PANEL FIRE PROTECTION PANEL 2H EMERGENCY DIESEL GENERATOR PANEL i TURBINE SUPERVISING PANEL l 2J EMERGENCY DIESEL GENERATOR PANEL- ! VENTILATION PANEL ! RADIATION MONITORING OPERATORS CONSOLE SPDS CONSOLE BENCHBOARD #1 BENCHBOARD #2 VERTICAL BOARD #1 VERTICAL BOARD #2 SAFEGUARD PANEL #1 SITEGUARD PANEL #2 P-250 STATION AUXILIARY SHUTDOWN PANEL j l O O I 1 _ - __-
ATTACHMENT 2 Page 4 of 16 Q- NON-SIMULATED PANELS - COMMON TO BOTH UNITS These panels have not been simulated because-of the. relative minor training value received from them or due to their inoperable status in the reference plant. AMBIENT TEMPERATURE MONITORING PANEL - No training value METEOROLOGICAL PANEL - Little training value STATION AND DIESEL BATTERY MONITORING PANEL - No training value SEISMIC PANEL - Little training value. SPILLWAY SUPERVISORY PANEL - Non-operational DRAWING O l l - O
ATTACHMENT 2 g g Page 5 of 16 Y O $ l' l l'ii'lll!! saaaaaa 4. 7 3 z!! 1 i l,ilill 1 Billii \ \ laota; r iiiiti-f \/ . i I s
$4 v l 11 l.E P ol al" 1
' g !! \\ . glll hg" s ....
si;anz
*i :1l a
U 4444 J w 0" 9 __ , Illlll ! i,-
. Will E iE
_ sag- g 5 BI!! f. I T
" z
-t' iiii Il n u
/f [
1" E g!5k g cg i silt! * . iiiii
- lT' la.5 iiii IIl!=
r - i
.. V $
l
- ssl*. .
a.:aan g 4 -
. I i
A
,o ; 5 g
D gk E y D
~-
.[:aaia
ATTACHMENT 2 Page 6 of 16 12J . _ _ I - i i illl I -
+ iilnl'h ;
iiesiti Y. l 7 i 2 sli ;
~
E l1I5l1 !~ O lloa a 2 inntil <<
< =. e_ _ _
\. g:,
<H I
8< is "
- a z a g lit l
11 Il b\s
\ n
[ll a
-1 II ...
anz n {_44444 ___ t=l ll IlB ll gD . -gg . IlaO
- ll 2,,
il O
ATTACHMENT 2 j Page 7 of-16 4 i PART A PANELS NRC RADIATION MONITORS
'i The High Range Effluent Monitoring system panels are located in the north west corner of'the main control room.
These panels provide indications and alarms for radiological releases from effluent steam paths. The effluent monitoring panels of the reference plant, : Unit 1,.are fully simulated and located in a similar position in the simulator control room. The Unit-2 panels are not simulated. These penels provide training in determining the status of radiological releases thru effluent flow paths. K A M E N R A D I A T I O N M O N I T O R I N G 'P A N E L S The High Range Effluent Monitoring Panels are located on the Unit 2 side west of the backboard panels. This panel provides indication and diagnostic features for radiological
. releases from various flowpaths. Only the reference plant, Unit 1, portion of the panel is simulated.-
b The location of the simulator panel is in an approximate position of the reference panel, i.e. on the Unit 2 side of the back panels. The panel provides minimal training value, due to operational data being displayed. Diagnostic information is not simulated. LIQUID WASTE PANEL i The Liquid Waste Panel is'a backboard panel located on ] the Unit 2 side of centerline in the main control room. It I is a common panel being shared by both Unit 1 and Unit 2. The panel contains controls, indications and alarms for i various systems shared by both units. The Liquid Waste i panel is fully simulated and located identically to the l reference plant. l i It provides valuable training in the operation and l control of common systems and coordination between backboard and control board operations. i l 1 O
q ATTACHMENT 2 Page 8 of 16 1 [ ' BORON RECOVERY PANEL
\
i The Boron Recovery Panel is a backboard panel located on the Unit I side of centerline in the main control room. It is a common panel sharing systems of.both units. It contains controls, indications and alarms for the Boron. Recovery and Primary Grade water systems. ; This panel is fully simulated and located identical to the reference plant. It provides significant training in the operation of boron recovery, components and systems. It also develops coordination between the backboard operator and the control room operator. RADIATION MONITORING PANEL 1 The Radiation Monitoring Panels are backboard panelt H located on the Unit 1 side. These panels provide control, i indication and alarms for process and area radiation i detectors on common and respective unit systems. Only the i common and Unit 1 monitors are simulated. The Unit 2 l systems have no training value and are not simulated.. The i panels are located exactly as in the reference plant and ! provide significant training in monitoring and analyzing the j radiological status of plant systems. j O VENTILATION PANELS The Ventilation Panels are located on their respective units backboards. Each contain controls for ventilation equipment for their unit and some equipment separated for . relability. The Unit 1 ventilation panel is fully simulated j and located as in the reference plant. The Unit 2 l Ventilation panel is partially simulated with control features to ensure the reference plant system.is complete. The Unit 2 ventilation panel is located in the approximate position to the actual panel. ! The panels provide training in plant systems and components. It also develops coordination between the l backboard operator and the control room operator. l
' EMERGENCY DIESEL PANELS The Emergency Diesel Panels are located among their ,
respective units backboard panels. They provide all the necessary control and indication to operate the diesel generators. Only the reference plant (Unit 1) panels are O
ATTACHMENT 2-Pago 9 of 16 simulated. Each panel, H and J, is fully simulated and provides significant training in the operation of electrical generators. TURBINE SUPERVISORY PANEL The Turbine Supervisory. Panel is a backboard panel that i provides indications and alar:as for various turbine control . systems. The reference plant (Unit 1) panel is fully simulated and located similar to the reference plant. The i Unit 2 panel provides no training value and is not simulated. This panel provides training-in the monitoring , of main turbine parameters and turbine control systems. PRESSURIZER SAFETY VALVE MONITORING PANEL The Pressurizer Safety Valve Monitoring Panel is a backboard panei located on the Unit 1 side in the main control room. The panel monitors and indicates the safety valve flow conditions via acoustical monitors for both Units 1 and 2 and gives associated alarms. Only the Unit 1-portion is fully simulated, with the Unit 2 portion simulated to show power-to the monitors. The panel provides j minimal training value other than indications. CONTAINMENT RADIATION MONITORS-The Containment Radiation Monitoring Panel is located along the backboards next to the main control room entrance. The panel contains controls and indications for both Unit 1 l and 2 containment radiation conditions. .Both units. monitors are functional, however, only Unit 1 (reference plant) .is fully simulated. The panel provides valuable training during accident conditions by displaying containment conditions. ROBERT SHAW FIRE PROTECTION PANEL l The Robert Shaw Fire Protection Panel is located on the l Unit 1 side of the main. control room backboard panels next to the entrance door. It displays the status of numerous
' fire zones and smoke detectors. The panel is only simulated to the extent of having the hardware installed.
l 0
ATTACHMENT 2 Page 10 of 16
,,~
(_ STATION FIRE PROTECTION PANEL The Station Fire Protection Panel is located on the east side of the main control room backboard panels. It monitors and displays the status of fire supression systems in various locations. Major plant areas common to both units are also displayed. The Fire Protection panel is fully simulated to give the proper indication and alarms when called upon by the simulator instructor. I BEARING COOLING PANEL The Bearing Cooling Panel is a backboard panel located in the east section of the main control room. It contains the controls and indications for the operations of the bearing cooling system. It also contains the ambient temperature monitor panels. The Bearing Cooling Panel is fully simulated. Its location in the simulator control room is identical to the main control room. CIRCULATING WATER PANEL The Circulating Water Panel is a backboard panel located on the east side of the control room. The Unit 2 ()
\-
circulating water panel is on the west side of the main control room. The Unit 2 panel is not simulated. The Unit 1 panel is fully simulated to include circulating water pump controls switches, valve control, and indication. It also includes indication for bus power. This panel provides significant training on system operation. SWITCHYARD DISTRIBUTION PANEL The Switchyard Distribution Panel is a backboard panel located on the east side of the main control room. It is a ! common panel shared between both units. It contains a mimic bus and necessary indications to monitor the electrical switchyard breaker and line voltage status. This panel is fully simulated logicly and dynamically. LOAD FOLLOW PANEL The Load Follow Control Panel is a backboard panel l located on the east side of the main control room. It is a common panel shared by both units. It is a non-functioning panel at this time with no plans of becoming operational. (3 N.J
l ATTACHMENT 12 1 Page 11 of 16 .j (} ( i It contains a frequency recorder, load follow controls and a phone system. This panelLis simulated to the extent of the _! systems that are' operational-in the main control room panel. ! I RCP VIBRATION MONITORING PANEL The Reactor Coolant Pump Vibration Monitoring Panel is I 1 a backboard panel located on its respective. units side of the main control room. The Unit 1 panel contains some equipment common to both units and some specific for Unit 2, specifically the watt meter _integrators. _The vatt meter integrators are not functional in the. simulator. The RCP. , vibration monitoring panel however is fully simulated in i that it provides the calculated-vibration indication'under normal and abnormal conditions. I AXIAL POWER FLUX DISTRIBUTION MONITORING PANEL (APDMS)
'The APDMS panel is a backboard panel located on the .
respective units side of the main control room. Only the ! ref erence plant (Unit .1 ) panel is simulated. Currently the l main control room panelHis not required by plant operations. Therefore, this panel is physically incorporated but not ; simulated. It provides no training'value and is maintained () only f or silaulator appearance. 1 INCORE FLUX DISTRIBUTION PANEL i The Nuclear Instrumentation Incore Flux Distribution i' Panel is located on the respective units side of the main control room. This panel is fully simulated for the reference plant. It contains the controls and indicative used for the incore system operations under normal and abnormal indication. This panel provides training on the operation of the incore-flux _ drive system and in diagnosing changes in neutron flux patterns. l i' VITAL BUS TRANSFER SWITCHES The Vital Bus Transfer Switchs are individual panels located in the main control room behind the main control
~ panels. Only the Unit 1 panels are simulated. The panels provide the ability to transfer the power sources of the vital buses. These panels are fully simulated and provide-the same ability as in plant. They are located behind the main control boards in the approximate location as in the main control room.
O r
ATTACHMENT 2 Page 12 of 16 l l MAIN ANNUNCIATOR PANEL The Main Annunciator Panels are located above the main control board vertical sections. There are fifteen panels I each consisting of sixty four " windows". The panels provide indication of circuit status, permissives, and alarms contitions. Each annunciator window is simulated to the minimum extent of being able_to activate the alarm. For' systems that are fully modeled there associated alarms are also fully modeled. I The only physical difference between the control room ) and simulator room involve minor items such as letter size ' and or wording. These have been identified by the annual physical fidelity review. The annunciator system is the major component _in proper i operator training and must be simulated to the maximum extent possible. I MAIN VERTICAL BOARD #1 i The Main Control Room Vertical Board Number 1 is located on the left hand portion of the main control boards. It contains all of the equipment necessary for operating and O,s monitoring of the Nuclear Instrumentation system and various primary plant systems. This Unit 1 panel is fully simulated and located in the identical position in the simulator I control room and provides operator training in the control and monitoring of the Excore Nuclear Instrumentation System and primary plant systems. MAIN VERTICAL BOARD #2 The Main Control Room Vertical Board Number 2 is . located approximately right of the center of the vertical , boards. The panel contains indication for various plant secondary systems. Each of the systems monitored is fully ; simulated, therefore, the instrumentation and controls of this panel is fully simulated. Some minor cosmetic discrepancy ' are known and have been identified in the ! annual fidelity report. Only the Unit 1 reference plant is simulated and its location is identified'as in the main control room. This panel provides vita) instrumentation in the operations and control of major plant' systems. O
ATTACHMENT 2 l Page 131of'16: y J l l O- SAFEGUARD PANELS #1 'l I The Safeguard Panels are located to the right of the' l vertical boards.. This panel contains the indications and' l controls for numerous components of the primary,' secondary and safeguard. systems. All indications and control features : are fully simulated logically and dynamically. The simulated panels are located and layed out. identical.to'the main control room. .These panels provide valuable training in the operation and control of vital plant systems. 1 POST ACCIDENT MONITORING PANEL The Post Accident Monitoring Panel is locatedito the right of the safeguard panel. It contains instrumentation and controls for systems affecting containment environment. Only the reference plant (Unit 1) is simulated. The panel is fully operational. All valve logics are modeled and the ; instrumentation is modeled to the required scope of 1 simulation. The panel provides valuable training in past accident conditions in analysis and recovery and is located identical to the main control room. UNIT 2 EQUIPMENT PANEL (SIMULATOR) O The Unit 2 Equipment Panel, located in the simulator control room, along the south-vall, contains indications and controls used to enhance simulator training. The equipment i simulated are components of systems that are shared between ! the units. This equipment is located in the main control specifically on Unit 2 panels, and is simulated only to the extent to allow training to be conducted on systems that require actions to be taken at Unit 2 locations.- , I BENCH BOARD #1 The Main Control Room Benchboard Number 1 is located on the left of the operator console. This panel contains the ; indications and controls for components of various primary ! systems. Each system and its features are fully modeled { making the panel a completely simulated panel. Only-the i ' reference plant is simulated. This panel provides a major
' portion of operator simulator training. Only minor cosmetic j discrepancies are known and they are identified in the-annual physical fidelity comparison report in Attachment 4. ,
l
ATTACHMENT 2 Page 14 of 16 BENCH BOARD #2 The Main Control Room Benchboard Number 2 is the right hand portion of-the operators console. This panel contains the indications and controls of components for various secondary and electrical systems. The panel is " fully)- simulated panels with only the reference plant (Unit 1 panel simulated. This panel is used in a major portion of the operator training program. Only minor cosmetic . differences are known between the. reference plant and the-simulator panels. AUXILIARY SHUTDOWN PANEL The Auxiliary Shutdown Panels are located in the. emergency switchgear room of its respective plant. .This panel provides independent remote contro11of vital system components for the safe shutdown of the plant.. Only the reference plant auxiliary shutdown panel is simulated.- This panel is fully simulated, however it is located in a manner different from the reference plant. The simulator auxiliary shutdown' panel is located within the simulator control room but out of the line of sight of control room operators. The placement of the panel adequately simulates the remote ( conditions of the actual panel. PLANT COMPUTER STATION The Plant Computer Station is located opposite the operators main control console. It is used to monitor plant status and gather information-for specific tasks. The reference plant computer station is fully simulated with the exceptions of some tasks that are beyond.the scope of simulation. It is located identical to the reference plant. SHIFT SUPERVISORS CONSOLE The Shift Supervisors Console is located between the main control boards of both plants. It acts as the central control station for supervisory plant operation. it contains the necessary communication-and information systems needed for decision making. This console is not fully.
' simulated. Some systems, such as the station radio system, and inter-state communication system are not completely functional. Only systems vital to the operator training program have been incorporated.
O
ATTACHMENT 2 Page 15 of 16 k PART B ENVIRONMENTAL DIFFERENCES There are certain environmental differences between the simulator and control room. The most noticable of these is that the dual unit control rooms panel layout are mirror images of each other with some minor equipment differences existing which is compensated for by the use of a " Unit Two equipment panel" in the simulator. These differences have been reviewed and found to have no impact on training, and that the simulator is acceptable for. operator training.and testing. ! The main control room florescent lighting is placed in a north and south configuration while the simulator lighting is run east to west. This causes a different dispersion of the lighting. Overall the effect is that the simulator lighting appears to be brighter and produces more glare upon the meter faces. A meter lens replacement project _is underway to procure and replace the VX252 style meter lens. The replacement is scheduled for completion by the end of 1988. The main control room has been recently.recarpeted. The carpet change has not yet been incorporated into the simulator, i There are four Virginia Power logos applied in places in the main control room that are not in the simulator. The Reactor Operators console is laminated with a. wood veneer that is not incorporated in the simulator. Freestanding national and company flags have been added to the main control room that are not in the simulator. The national flag has been placed in the simulator. The Shift Supervisor console contains a site radio and company page system that is not yet incorporated into the-simulator. The hardware has been installed, but is not operational. Noises that accompany operation of various systems or equipment adjacent to the main control room are not simulated. The local control room radiation monitor' detector and readout with alarm is not_ included in the simulator, but is scheduled for installation in accordance with the discrepancy resolution schedule.
ATTACHMENT 2 Page 16 of 16 I i l (3
'v/ Some minor painting schemes are not current in the I
simulator, i.e. NRC radiation panels and panel lettering. Imitation potted plants were procured by the station. The same plants have been ordered as used in unit 1 control room and have been insta11ea in the simulator. i
)
1 i I l [ 'N j I _ _ _ . _ _ _ _ _ _ _ _ _ _ _}}