Text

Simulator Certification Submittal.
	ML18151A220
Person / Time
Site:	Surry
Issue date:	11/30/1988
From:	; VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	;
Shared Package
ML18151A221	List: ML18151A220; ML18152B308;
References
	NUDOCS 8812150137
	Download: ML18151A220 (299)
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NRC 474 U.S. NUCLEAR Rl!GULATOIIY COMMIUION

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FORM 110,861 Aei.w-""OM*

10CFR \55.*Slbl, 1 55.* and 5.5 SIMULATION FACILITY CERTIFICATION ~31.<<I

~RUCTIONS. This form is to be filed for initial cenification, recertification (if required I, and for any change to a simulation facility performance testing plan r.. a<le after initial submittal of such a Plan. Provide the following information, and check the appropriate box to indicate rlllSOn for submittal.

FACILITY IDOCKET NUMBER SURRY POWER STATION so. 280 n-,_,.,

LICENSEE ID.ATE VIRGINIA ELECTRIC AND POWER COMPANY Th;,,. ,a centfv lllai: 1. 11'141 -

m00t1 !1M1 qute11ne1 con- in ANSI/ANS 3.5, 191111, u _ . . , NRC I I ~ Guidi 1.141; llld3.

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NAME /orothridffltifiation/ AND LOCATION OF SIMULATION FACILITY

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. 10/14/88

~ o f 10 CFII '111,.S: 2.11111..,._ IKMY tarNIIC-in--10CFll 111.4111111. II _ _ _

1 SURRY UNIT 2 SIMULATOR. SURRY POWER STATION. SURRY. VIRGINIA AT THE END OF STATE ROUTE F.'i?

j SIMULATION FACILITY PERFORMANCE TEST ABSTRACTS ATTACHED. (For,-ri-rant:ondur:r<<lin m.,-iod-ing *th tMdlr.of thiu:mifiratlonl DESCRIPTION OF PERFORMANCE TESTING COMPLETED (Attach additioMJ ,,.,_1,1 u - , y , 1nt1_idffltify t/Nitmi .--;prion Ming t:ominu<>rl-taa,,_ .,_for th* fou,.,-,,.,;oo commtmt:intt with th* dlt* of thi1 cff'tifiution. J DESCRIPTION OF PERFORMANCE TESTING TO BE CONDUCTED (Af!1t:h 1ddition,/ p,g,/1/ G'*-"f, 1111d idffltif'I tM itllffl dat:riprion t>>ing,:onrinu<<I/

SEE ATTACHED DOCUMENT j PERFORMANCE TESTING PLAN CHANGE. (Foran., modification to, ,-rio,,,,.nc.inring p/1111 IUbmitt<<I on, ,inwou, t:wrif/ation/

DESCRIPTION OF PERFORMANCE TESTING PLAN CHANGE (Attat:h 1ddit1on,/ p,p(,J 1 1 1 ~ . lllldidffltif'I th*itm, deiaiprion t.ingcontinwdJ NOT APPLICABLE AT THIS TIME IAtllch RECERTIF ICA TION (Dnt:rilM conw:riw ~iom ,,..,,, 1ttKh IWUlr, of compl.r<<I 1ddition,1..-1,1 u _ _ , , *nd 1dMltifv th* 1tllffl deeriorton Mino conrinuod./

,,.-fonNtfl rming in <<:Cordi- *th 10 CFR § 55.45(b/(5JM.

NOT APPLICABLE AT THIS TIME

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Any false s1u1m1nt 01 o'iJ;,*on ,'f.,nis ~men1, ,nctuding attachmenll, may be subiKt 10 civil and criminal sanctions . I cart1fy under penalty of perjury 1Nt the inlormauon ,n 1n,1
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IDATE SIGNA~r~P,P.ESENTATIVE !TITLE
. ~ - R. CARTWRIGHT VICE-PRESIDENT-NUCLEAR II - '2.3-88 In accordance with 10 CFr~ !S5.5, Communications. this form shall be submined to the NRC as follows:
BY MAIL ADDRESSED TO: Director, Offica of Nuclur Reactor R99Ulation BY DELIVERY IN PERSON U.S. NuclNr Regulatory Commission TO THE NRC OFFICE AT: 7920 Norfolk Avenue Wahington, DC 20555 Bethadl, MD
SURRY UNIT 1 SIMULATOR CERTIFICATION SUBMITTAL
Surry Unit 1 Simulator Certification Submittal This Surry Unit 1 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 ControlrProcedure (Attachment 9)
The ANSI 3~5 -- 1985 checklist will address each item and it's status~ -The overrides features are net 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 instructor console features will be listed. A list of current initial condition sets is included in Appendix 3 of this Attachment. 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 resµlts will be presented.
1
2
The simulator test schedule will be attached.
tests to be conducted are divided in such a manner as to ensure 25% of the tests required are performed each year thereby ensuring all testing is completed within the four The year time frame specified.
The simulator Physical Fidelity Report will be a listing of all current discrepancies and a scheduled date for resolution with priority indicated as appropriate.
The simulator facility arrangement and reference plant control room arrangement will be presented.
Virginia Power is currently conducting a systematic review and upgrade of each plant system to ensure the system 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 will be included as 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. The schedule will be revised as necessary to reflect needed modifications due to plant changes or changing training requirements.
The Virginia Power simulator configuration control procedure is included for your reference .
VIRGINIA POWER SIMULATOR SUPPORT GROUP SURRY uNIT i SIMULATOR ATTACHMENT 1 CERTIFICATION CHECKLIST
ATTACHMENT 1 Page 1 of 3
SURRY SIMULATOR CERTIFICATION CHECK LIST SIMULATOR CAPABILITIES Normal Plant Evolutions Normal evolutions listed in ANSI/ANS-3.5-1985 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 on the attached SMR listing.
Plant Malfunctions 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
/2-t-/l All simulated panel dimensions and arrangements 0 have been reyiewed to ensure they do no detract from training.
Obtained latest revision copy Surry control room floor plan. Floor plan is available for inspection.
Compared differences between the Surry control room floor plan and the Surry simulator control room floor plan. A list of differences is attached.
Compared lighting in the plant and simulator control rooms. Differences are indicated on the attached list.
Communication systems available in the plant and simulator control rooms have been compared.
Differences are indicated on the attached list.
Furnishings in the plant and the simulator have
been reviewed. A list of differences is attached .
ATTACHMENT 1 Page 2 of 3
Pictures of the Surry main control boards have been taken. They are available for inspection.
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 The simulator possesses the capability for storage of 40 initialization conditions. A current listing is attached.
Random selection 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.
Random selection testing has been conducted to validate the operability of the Malfunction Processor and its capability of simulating simultaneous and/or sequential malfunctions .
Random selection testing has been conducted to validate the operability of the Plant Equipment Display System (PEDS). Problems identified have either been corrected or are identified on the attached list.
Special features available on the Surry simulator are indicated on the attached list.
PERFORMANCE CRITERIA 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.
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 .
ATTACHMENT 1 Page 3 of 3
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.
A Simulator Limits Exceeded alarm has been incorporated to avoid negative training by progressing beyond plant design limits or model capabilities.
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.
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.
Random selection testing has been conducted to validate the operability of the Setpoint Override Processor. Problems identified have either been corrected or are identified on the attached list.
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.
Random selection testing has been conducted to validate the operability of the Meter Override Processor. Problems identified have either been corrected or are identified on the attached list .
VIRGINIA POWER SIMULATOR SUPPORT GROUP SURRY UNIT 1 SIMULATOR ATTACHMENT 2 INSTRUCTOR CONSOLE FEATURES AND OVERVIEW
ATTACHMENT 2 Page 1 of 51
INSTRUCTOR CONSOLE DESCRIPTION The instructor console is depicted in Figure 1. It 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
D.
This terminal is used to display the status of malfunctions and overrides entered by the instructor.
TOUCH SCREEN 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 panel receives instructor command inputs via pushbuttons, and computer acknowledgement of these commands via lamp indicators, with information displayed on the CONSOLE TERMINAL .
ATTACHMENT z
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ATTACHMENT 2 Page 3 of 51
1.
DETAILED INSTRUCTOR PROCEDURES 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 specific 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 until a new function is activated.
e. Interlocks are provided which prevent any adverse impact on simulator training due to inadvertent 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 conditions for initiation are displayed in green.
(2) Malfunctions/Overrides timing down to initiation are displayed in yello~.
(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 to process 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 "ii'"sO" is entered,
ATTACHMENT 2 Page 4 of 51
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.
i. In the event of CONSOLE PANEL failure, a message will 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 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 INDEX, PAGE FORWARD or PAGE EACK pushbutton lights 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 modcomp computer. When the link between these two computers fails, an indication (LEOF DATA LINK FAILURE) lights up on the instructor console to inform the instructor of the SPDS simulation failure. To restart the simulation, reboot of the modcomp is required .
ATTACHMENT 2 Page 5 of 51
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 specific function.
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 .
ATTACHMENT 2
_Page 6 of 51
Procedure INDEX Page 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 30 Remote Off 30 Fast Time (N/A FUS) 31 Freeze 32 Normal Time (N/A FUS) 33 Alarm Acknowledge 34 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
ATTACHMENT 2 Page 7 of 51
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ATTACHMENT 2 Page a of 51
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ATTACHMENT 2 Page 9 of 51
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 .
ATTACHMENT 2 Page 10 of 51
START UP
Description:
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 CONSOLE TERMINAL. When the startup function is complete, a confirming message is displayed on the CONSOLE TERMINAL and FREEZE, MALF TIMER STOP, REMOTE OFF, NORMAL TIME, MALF PROC OFF, ALARM OVERRIDE PROC OFF, LAMP OVERRIDE PROC OFF, SWITCH OVERRIDE PROC OFF, METER OVERRIDE PROC OFF and SETPOINT OVERRIDE PROC OFF function lights light up.
Procedure:
1. Push STARTUP.
2. Perform IC RECALL procedure .
ATTACHMENT 2 Page 11 of 51
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.
2. Push SINGLE SAVE .
ATTACHMENT 2 Page 12 of 51
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.
Procedure:
1. Push FREEZE
2. Push SINGLE RESTORE.
3. Follow procedure fur IC CHECK ..
ATTACHMENT 2 Page 13 of 51
CORE AGING (NAPS
Description:
& SPS ONLY)
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 Processor will automatically deactivate when it has either:
1. Successfully completed Core Aging OR
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) setpoint potentiometer to value specified on the CONSOLE TERMINAL .
ATTACHMENT 2 Page 14 of 51
Note:
1*
The instructor should expect a change in power range delta flux indication for:
Fuel distribution change with core life.
2. Xenon distribution change depending on specified p*ower history and delta flux .
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) identified by the Instructor.
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 16 characters long).
2. Description of scenerio.
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 containing name and description of all existing files is maintained in the Instructor booth.
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 go to step 18.
2. Check in 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.
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
c.
d.
e.
Name of Instructor.
Name of students (up to 6).
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 .
1 0. 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 monitor file to be modified and push enter.
14. Type in number corresponding to the item to be modified and push ENTER.
15. Type in 4 (corresponding to Save Monitor) and push ENTER.
16. Type in (corresponding to Start Monitor) and push ENTER.
17. Type Yin response to "Monitor File exists. Replace Y/N" and push ENTER.
NOTE: At this time the screen will clear and TPM ACTIVE push button will light up .
l.
ATTACHMENT 2 Page 17 of 51
18. To stop the monitor:
a.
b.
Push TPM push button.
Type in 2 (corresponding to Stop Monitor) and push enter.
NOTE: The TPM ACTIVE light will go off .
ATTACHMENT 2 Page 18 of 51
COMPUTER AIDED EXERCISE (CAE)
Description:
The Computer Aided Exercise (CAE) function allows the use of a prebuilt exercise, or the building of a new exercise.
Computer Aid Exercise is controlled by three (3) pushbuttons:
1. COMPUTER AIDED EXERCISE - used to activate/
deactivate the CAE function
2. COMPUTER 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.
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 exercise.
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.
d. Push CAE.
e. Push LOG ON/HOLD.
f. Proceed with the exercise.
NOTE: All buttons, and the sequence in which they are pushed on the CONSOLE PANEL are recorded.
If an instructor CONSOLE PANEL function is not desired to be recorded:
1. Push LOG ON/HOLD To recommence recording:
1. Push LOG ON/HOLD
ATTACHMENT 2 Page 19 of 51
g.
h.
i.
j .
At the end of exercise guide, push LOG ON/HOLD Push CAE.
Type in 4 and push ENTER.
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.)

......,.....------------:: __c::cc:

ATTACHMENT 2 Page 20 of 51
IC STORE
Description:
The IC Store function permits the Instructor to store the present simulator condition.
There are 40 different IC's. -~ 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
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 .
ATTACHMENT 2 Page 22 of 51
PLANT VARIABLES
Description:
The Plant Variable function permits the instructor to monitor blocks 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 .
ATTACHMENT 2 Page 23 of 51
SIMLOCH (INTENDED 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.
4.
Type in desired data base variables.
Use the following commands as necessary:
a. $F - Delete data base description of variables from display
b. $F10 - Display data base description of variables.
c. $F11 - Rearrange variables from column to row format.
d. ~X - Exchange left and right sets of 20 variables for display
e. $R - Rearrange variables in alphabetical/
numerical order.
f. $8 - Save variables displayed (give file name after $S).
g. $I - Clear screen of all variables.
h. $T.1 - Obtain maximum update rate of variables.
i. $P - Store/print displayed variables at a certain interval (give time in seconds after $P). To print the variables one time, use $P without any time and then exit the SIMLOCH. The file will get printed on printer .
ATTACHMENT 2 Page 24 of 51
j.
k.
$G - Display variables (give file name after
$P).
X - Exit SIMLOCH.
5. To terminate the SIMLOCH function:
a. Push SIMLOCH
ATTACHMENT 2 Page 25 of 51
IC RECALL
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.
Procedure:
1. Push FREEZE.
2. Exit from all MALFUNCTION/OVERRIDE functions.
3. Push IC RECALL.
4. Select desired IC and push ENTER.
5. Follow procedure for IC CHECK.
NOTE: IC number for current session is displayed on the top right corner of the CONSOLE TERMINAL .
ATTACHMENT 2 Page 26 of 51
BACK TRACK RECALL
Description:
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 of the 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 .
ATTACHMENT 2 Page 27 of 51
REPLAY
Description:
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 .
ATTACHMENT 2 Page 28 of 51
FAST TIME SETUP (NAPS
Description:
& SPS ONLY)
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.
g. Boron Mixing - Future.
Once the FAST TIME MODE is setup, it can be started at any 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 ENTE~.
3. Type in the new rate and push ENTER.
4* Type .in N and push ENTER.
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.
NOTE: If there is a communication problem with I/0 (COMERR=TRUE) then the simulator will not go to run. A message will be displayed on the console terminal that the I/0 is not functional .
ATTACHMENT 2 Page 30 of 51
MALF TIMER
Description:
The Malf Timer function permits the instructor to control the timer for malfunction and override initiation.
The time displayed on the Malfunction/Override Terminal for instructor entered malfunctions and overrides are updated continuously while the Malf Timer Run function is active.
Once a Malfunction/Override is active, the time displayed is the total time elapsed since activation, and will continue to count irrespective of Malf Timer status.
Procedure:
1. To start the malfunction timer:
a. Push MALF TIMER RUN.
2. To stop the malfunction timer:
b. Push MALF TIMER STOP .
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:
1. To activate the Remote Console:
a. Push REMOTE ON.
2. To deactivate the Remote Console:
a. Push REMOTE OFF .
ATTACHMENT 2 Page 32 of 51
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 pushbutton can be used to start the fast rate operation.
During fast rate operation the FAST TIME light comes on.
Procedure:
1. Push FAST TIME push button .
ATTACHMENT 2 Page 33 of 51
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 .
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 .
ATTACHMENT 2 Page 35 of 51
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
ATTACHMENT 2 Page 36 of 51
ROD STEP COUNTER ENABLE (NAPS
Description:
& SPS ONLY)
The ROD STEP COUNTER ENABLE function permits the instructor to calibrate the rod step counters to the value stored in, the IC.
This function must be initiated after performing an IC Recall or Backtrack, but before completing an IC Check.
Until the rods have counted to the desired value, the simulator should not be put in Run.
Procedure:
1. Push ROD STEP COUNTER ENABLE .

------ -------- - =-=---=-----~~--------------------------------

ATTACHMENT 2 Page 37 of 51
TRIP REVIEW DISABLE
Description:
(Future)
Procedure:
(Future)
ATTACHMENT 2 Page 38 of 51
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 .
ATTACHMENT 2 Page 39 of 51
PRINT SCREEN
Description:
The Print Screen function permits the instructor to print the current information on the CONSOLE TERMINAL and 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 on INSTRUCTOR/DIAGNOSTICS TERMINAL, use $P command of SIMLOCH function .
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*
displayed on the CONSOLE TERMINAL and "Prodac CRT" (SPS &
NAPS).
Procedure:
1. Complete equipment setup.
2. Push IC CHECK .
ATTACHMENT 2 Page 41 of 51
RECOVER COMM NETWORK (NAPS
Description:
& FUS ONLY)
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) .
ATTACHMENT 2 Page 42 of 51
DIAGNOSE & RECOVER (FUS & NAPS ONLY)
Description:
The DIAGNOSE & RECOVER function serves to reinitialize 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 NOTE: This function becomes active (by default) when simulator is started up.
Procedure:
1. Push DIAGNOSE & RECOVER.
2. If the light is flashing:
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" again.
2. If light still will not go solid, but flashes, it indicates a failure which will require maintenance action. Inform the simulator staff as necessary .
ATTACHMENT 2 Page 43 of 51
DEVELOPMENT MODE:
Description:
(INTENDED FOR SIMULATOR STAFF USE ONLY)
The Development Mode function activates development 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.
2. Push STARTUP .
ATTACHMENT 2 Page 44 of 51
CONTROL ROOM DIAG:
Description:
(INTENDED FOR SIMULATOR STAFF USE ONLY)
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)
3. Setpoints (Analog inputs)
4. Switches (Digital inputs)
To use this function:
a. Simulator must be in Freeze mode
b. INSTRUCTOR/DIAGNOSTIC TERMINAL should either be in Wait State or not logged on by a user When this function is active, instructions are displayed on the INSTRUCTOR/DIAGNOSTIC TERMINAL.
Procedure:
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
b. Type X on the INSTRUCTOR/DIAGNOSTIC TERMINAL keyboard .
ATTACHMENT 2 Page 45 of 51
INSTRUCTOR CONSOLE DIAG
Description:
The Instructor Console Diag function permits the instructor to check the operability of the CONSOLE PANEL.
When this function is activated:
a. All lights on the console light one by one Procedure:
1. To activate the Instructor Console Diagnostic:
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 .
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 (i.e., leaks, instrument failures, etc.)
2. Go/no go (i.e., breaker trips, large LOCAS, etc.)
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 or
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*:
1. Green - malfunction awaiting a specified "Trigger" for start of delay time
2. Yellow - malfunction not initiated but in a time down sequence to initiation
3. Blue - malfunction is initiated but in a ramp status
4. Red - malfunction fully completed Procedure:
1. To activate the Malfunction Processor:
a. Push MALF PROC ON.
b. Follow instructions on the CONSOLE TERMINAL.
2. To deactivate the Malfunction Processor:
a. Push MALF PROC OFF.
ATTACHMENT 2 Page 47 of 51
ALARM OVERRIDE PROCESSOR
Description:
The Alarm Override Processor function permits the instructor to override any annunciator.
Annunciators may be overridden:
1. ON - result is essentially that which would occur 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 out (i.e., the annunciator will not light but the audible alarm will soundr.-
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 or
2. Satisfying the instructor specified "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 .
ATTACHMENT 2 Page 48 of 51
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 were 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 or
2. Satisfying the instructor specified "Trigger and "1" above.
Note: "Triggers" are provided by the simulator staff.
Procedure:
1. To activate the Lamp Override Processor:
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 .
ATTACHMENT 2 Page 49 of 51
SWITCH OVERRIDE PROC ON
Description:
The Switch Override Processor function permits the instructor to override any switch position.
Switches may be overridden:
1. ON - result is essentially that which would occur if the switch contact were to stick 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 instr~ctor determined time delay (in seconds). This delay start is initiated by:
1* Going to RUN on the Malfunction Timer
2.
Note:
"1" above.
or Satisfying the instructor specified "Trigger" and "Triggers" are provided by the simulator staff.
Procedure:
1. To activate the Switch Override Processor:
a. Push SWITCH OVERRIDE PROC ON.
b. Follow instructions on the CONSOLE TERMINAL.
2. To deactivate the Switch Override Processor:
a. Push SWITCH OVERRIDE PROC OFF .
ATTACHMENT 2 Page 50 of 51
METER OVERRIDE PROCESSOR
Description:
The Meter Override Processor function permits the instructor to override any meter or recorder with the exception of:
1. Main generator syncroscope
2. Diesel generator syncroscopes
3. Reactor Coolant pump vibration meters Meters (and recorders) may be overridden:
1. Upward (SO to 100) - result is essentially that which would occur if the signal conditioning card, in the process or control racks, were to drift upward.
2. Downward (SO to O) - result is essentially that which would occur if the signal conditioning card, in the process or control racks, were to drift downward *
All Meter (or recorder) 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 or
2. Satisfying the instructor specified "Trigger" and 11 1 11 above.
Note: "Triggers" are provided by the simulator staff.
Procedure:
1. To activate the Meter Override Processor:
a. Push METER OVERRIDE PROC ON.
b. Follow instructions on the CONSOLE TERMINAL.
2. To deactivate the Meter Override Processor:
a. Push METER OVERRIDE PROC OFF .
ATTACHMENT 2 Page 51 of 51
SETPOINT OVERRIDE PROCESSOR
Description:
The Setpoint Override Processor function permits the instructor to override any controller setpoint potentiometer.
Setpoints may be overriden:
1. Upward (SO to 100) - result is essentially that which would occur if the signal conditioning card, in the process or control racks, were to drift upward (raising setpoint).
2. Downward (SO to O) - result is essentially that which would 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).
~his delay start is initiated by:
1*
2.
Going to RUN on the Malfunction Timer or Satisfying the instructor specified "Trigger" and "1" above.
Note: "Triggers" are provided by the simulator staff.
Procedure:
1. To activate the Setpoint Override Processor:
a. Push SETPOINT OVERRIDE PROC ON.
b. Follow instructions on the CONSOLE TERMINAL.
2. To deactivate the Setpoint Override Processor:
a. Push SETPOINT OVERRIDE PROC OFF .
ATTACHMENT 2 APPENDIX 1 Page 1 of 3
CONSOLE PANEL FAILURE
Description:
This procedure describes how to use the INSTRUCTOR/
DIAGNOSTIC TERMINAL to operate the simulator in case of 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.
Simulator can be operated by using either the function codes for pushbuttons (FUNCTION MODE) or the legend on the pushbuttons (COMMAND MODE) without any spaces.
Procedure:
1. Log off the INSTRUCTOR/DIAGNOSTIC TERMINAL as soon 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 .
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ATTACHMENT 2 APPENDIX 2 Page 1 of 2
TRAINING PERFORMANCE REVIEW DESCRIPTION:
The Training Performance Reivew (TPR) function provides the capability to review the data collected during the TPM (Training Performance Monitor) function. This 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.
2. By reviewing the printed strip charts of monitored variables. These printed strip charts provide the following information:
a. Date of Scenerio
b. Name of Students
c. Name of Instructor
d. 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 return.
NOTE: A list of possible terminal choices will 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.
NOTE: Monitor-name is the name defined during TPM .
ATTACHMENT 2 APPENDIX 2 Page 2 of 2
5. Follow instructions as they appear on screen 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, after STOP TIME is 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 isntructions to 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:
(i) Push down the LOAD button.
(ii) Align the paper with the mark on bottom left (iii)Push the LOAD button again to release it .
NOTE:
b.
The paper will be pulled down by static charge.
Push down and hold the CALL button until it beeps and then release it.
NOTE: The plotter should start plotting at this time.
c. To remove the paper from the plotter (i) Push down the LOAD button.
(ii) Remove the paper.
(iii)Push the LOAD button again to release it .
ATTACHMENT 2 APPENDIX 3 Page 1 of 1
1.
INITIAL CONDITIONS 100 PERCENT CB 558 7000MWD DA220 09/11/88
2. 70 PERCENT CB 632 7000MWD DA190 09/11/88
3. 50 PERCENT CB 679 7000MWD DA158 09/11/88
4. 30 PERCENT CB 788 7000MWD DA164 SU 09/11/88
5. 15 PERCENT CB 575 7000MWD ON DUMPS TURBINE 1800RPM 09/11/88
6. 1E5 AMP CB 843 700MWD DA109 XE FREE 09/11/88
7. 1E8 AMP CB 574 7000MWD DA111 3HRS SINCE 100 PERCENT TRIP 09/11/88
8. HSD CB 575 7000MWD ARI 2HRS SINCE 100 PERCENT TRIP 09/11/88
9. HSD CB 575 7000MWD SB OUT 2.5HRS SINCE 100 PERCENT TRIP 09/11/88
10. ISO CB 1365 350F RHR BUBBLE FW PMP IN TEST 09/11/88
11. CSD CB 1361 280F RHR BUBBLE 09/11/88
12. CSD CB 1368 190F RHR BUBBLE 09/11/88
16. TRANSFER 09/11/88
25. SAVE HM OE2 08/24/88
27. 100 PER ANSI HSD IOO TEST 08/19/88
28. LORP 884SM1 JACKSON 05/19/88
29. LORP886SM1 JACKSON 07/28/88
30. LORP 885SM1 JACKSON 07/14/88 31 SAVE HM (STATIC MSLB) CONFIDENTIAL 08/22/88
32. SAVE HM (STATIC LOCA) CONFIDENTIAL 08/15/88 34~ 74 PER (BOB) 08/17/88
35. NEW RQ885SM2 07/01/88
38. SAVE HM (STATIC STARTUP) CONFIDENTIAL 08/15/88
VIRGINIA POWER SIMULATOR SUPPORT GROUP SURRY UNIT 1 SIMULATOR
ATTACHMENT 3 SIMULATOR TEST RESULTS
ATTACHMENT 3 Page 1 of 87
SIMULATOR TEST RESULTS Since delivery in 1978, 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 training 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 Surry simulator is acceptable for licensed operator training and retraining.
The following are brief synopses of the results of the tests conducted, which include Performance Integrated Operation Tests, Transient Tests, Malfunction Tests, Unique Tests, and Surveillance Tests.
Additional information concerning malfunctions can be obtained by referring to the Malfunction Cause and Effects index .
ATTACHMENT 3 Page 2 .of 87
VIRGINIA POWER SIMULATOR SUPPORT GROUP SURRY UNIT 1 SIMULATOR MALFUNCTION INDEX
ATTACHMENT 3 Page 3 of 87
*MALF NO.
MALFUNCTION DESCRIPTIO:t,T MASTER CROSS INDEX GENERIC DEGRADATION
( 0%) RAMP MCA01 INSTRUMENT AIR YES 0-1.00% NO HEADER LEAK.
MCA02 CNTMNT INSTRUMENT YES NONE NO AIR COMPRESSOR TRIP MCA04 CNTMNT INSTRUMENT NO 0-100% NO AIR HEADER LEAK t1CA08
INSTRUMENT AIR YES NONE NO COMPRESSOR OVERLOAD TRIP MCC01 LOSS OF CC WATER YES 0-100% YES SW THROUGH cc*
HX'S MCC03 LOSS OF COMP.* YES NONE NO COOL. WATER PUMPS MCC04 LOSS OF CC TO NO 0.-1 00% YES NON-REGEN HEAT EXCH MCCOS* THERMAL BARRIER YES . 0-1 00% YES LEAK TO CC SYSTEM MCH.01 LEAK IN LETDOWN NO 0-lOO%
YES LINE INSIDE CONTAINMENT MCH02 LTDN LEAK OUTSIDE NO 0-100% YES CNTMENT (0-60 GPM)
MCH03 CHG LINE LK NO. 0-100% YES DWNSTRM FCV-122 (OUTSIDE CNT)
MCH05 LOSS OF CHARGING YES NONE NO PUMP
ATTACHMENT, 3 Page 4 of 87
MALF NO.
MCH06 MALFUNCTION DESCRIPTION NON REGEN HX OUTLET TEMP GENERIC NO DEGRADATION
( 0%)
0-100%
RAMP YES CONTROLLER FAILURE MCH11 RCP SEAL INJ YES 0-100% YES PRESS XMTR FAILS MCH12 RCP SEAL WTR RTN NO 0-100% YES HOR TEMP XMTR 133 FAILS MCH13 LEAK IN NON-REGEN NO 0-100% YES HX MCH17 SEAL WATER RETURN NO NONE NO FILTER CLOGS MCH19 VCT LVL NO 0-100% YES CONTROLLER 112A FAILS MCH20 , CORE ACTIVITY NO 0-100% YES RELEASE MALF MCH21 VCT LEVEL XMTR YES 0-100% YES FAILS MCH22 VCT PRESS XMTR NO *0-100% YES 1 1 7 FAILS MCH23 VCT TEMP XMTR NO 0-100% YES 1 1 6 FAILS MCH24 BORIC ACID FLOW NO 0-100% YES CONTROLLER 113 FAILS MCH25 PRIMARY WATER NO 0-100% YES FLOW CONTROLLER 114 FAILS MCH28 CHG LINE FLOW NO 0-100% YES CONTROLLER 122A FAILS MCH29 CHRG LINE FLOW NO 0-100% YES XMTR 122 FAILS
ATTACHMENT 3 Page 5 of 87
MALF NO.
MCH31 MALFUNCTION DESCRIPTION REGEN HX CHRG OUTLT TEMP XMTR GENERIC NO DEGRADATION
( 0%)
0-100%
RAMP YES 123 FAILS MCH35 LP LETDOWN LINE NO 0-100% YES FLOW XMTR 150 FALLS MCH36 LP LETDOWN LINE NO 0-100% YES PRESS CONTROLLER 145 FAILS MCH37 LP LETDOWN LINE NO 0-100% YES PRESS XMTR 145 FAILS MCH38 REGEN HX LETDOWN NO 0-100% YES TEMP XMTR 140 FAILS MCH39 LETDOWN LINE NO 0-100% YES REL LINE TEMP
MCH40 MCH41 XMTR 141 FAILS LP LETDOWN LINE TEMP XMTR 143 FAILS NON REGEN HX NO NO 0-100%
0-100%
. YES YES OUTLT TEMP XMTR 144 FAILS MCN01 LOSS OF YES NONE NO CONDENSATE PUMP MCN02 AIR LEAKAGE INTO YES 0-100% YES MAIN CONDENSER CN-SC-1A/B BOOT MCN03 HOTWELL LVL NO 0-100% YES CONTROLLER FAILS MCN05 CN SYS LEAK NO 0-100% YES BETWEEN CN-114
& FCV-CN-107 MCN08 LOSS OF LOOP YES 0-100% YES FOR AIR EJECTORS 1 A/B
ATTACHMENT 3 Page 6 of 87
MALF NO.
MEL01 MALFUNCTION DESCRIPTION LOSS OF OFFSITE POWER GENERIC NO DEGRADATION
( 0 %)
NONE RAMP NO MEL02 MAIN GENERATOR NO NONE NO TRIP MELO? LOSS OF 4160V YES NONE NO STATION SERVICE BUS MEL08 LOSS OF YES NONE NO SCREENWELL TRANSFORMER MEL09 LOSS OF EMERGENCY YES NONE NO DIESEL GENERATOR MEL12 LOSS OF 480V YES NONE NO EMERGENCY SWITCHGEAR MEL13 LOSS OF 480V YES NONE NO EMERGENCY MCC'S MEL14 LOSS OF SEMI NO NONE NO VITAL BUS MEL17 LOSS OF 125V DC YES NONE NO BUS MEL18 LOSS OF 480V YES NONE NO SWITCHGEAR MEL19 LOSS OF 480V YES NONE NO MOTOR CONTROL CENTER MEL20 LOSS OF AC VITAL YES NONE NO BUS SUPPLY BREAKER MEL21 LOSS OF 4160V YES NONE NO EMERGENCY BUS MFW01 MAIN FEED PUMP YES NONE NO RECIRC VALVES FAIL
ATTACHMENT 3 Page 7 of 87
MALF NO.
MFW02*
MALFUNCTION DESCRIPTION MAIN FEED REG VALVES FAIL SHUT.
GENERIC YES DEGRADATION
( 0%)
NONE RAMP NO MFW04 LOW LUBE OIL YES 0-100% YES PRESSURE FOR MAIN FW PMPS MFWOS MN FEEDWATER BRK YES 0-100% YES UPSTREAM OF FLOW TRANSMITTER MFW07 AUX FW PMPS YES NONE NO FW-P-3A/B TRIP:
OVER-CURRENT MFW08 AUX FW TURBN WON'T NO NONE NO STOP: PCV-MS-102B OPEN MFW10 AUX FEED WTR PMP YES NONE . NO CHECK VLV STICKS OPEN
MFW12 MFW13 MAIN FEEDWATER PMPS SUCTION LINE BREAKS S/G LEVEL CH
. FAILS YES YES 0-100%
0-100%
YES YES MFW14 AUX FEED LINE YES 0-100% YES BREAK DOWNSTRM FLOW XMTRS MFW15 MN FEED LINE BRK YES 0-100% YES BET CHK VALVE &
CNTMNT MFW16 MN FEED LINE YES 0-100% YES BREAK INSIDE CONTAINMENT MFW17 DEGRADATION OF MN YES 0-100% YES FW PP, IMPELLER CRACK MFW18 S/G MAIN FEED YES 0-100% YES FLOW XMTRS FAIL
ATTACHMENT 3 Page 8 of 87
MALF NO.
MFW19 MALFUNCTION DESCRIPTION S/G MAIN FEED FLOW CONTROLLER GENERIC YES DEGRADATION
( 0 %)
0-100%
RAMP YES FAIL MFW20 S/G WIDE RNG LVL YES 0-100% YES.
XMTR FAIL MFW21 S/G AUX FEED YES 0-100% YES FLOW XMTR FAIL MFW22 MN FEED HOR YES 0-100 YES XMTR FAIL MFW23 TOTAL LOSS OF NO NONE NO FEEDWATER MMI03 INCREASE IN NO 0-100% NO CONTAINMENT PRESSURE MMI04 FAILURE OF RX YES NONE NO PB ON BENCH
MMSOl MMS03 RUPTURE OF MAIN STM LINE AT HEADER MAIN STEAM LINE RUPTURE, UPSTREAM YES YES 0-100%
0-100%
YES YES OF FE MMS04 RUPTURE OF MAIN YES 0-100% YES STM LINE BEFORE TRIP VV MMS06 MAIN STEAM TRIP YES NONE NO VALVE FAILS AS IS MMS07 SG SFTY VLV STICKS YES 0-100% YES OPEN (IMMEDIATELY)
MMSOB S/G STEAM FLOW YES 0-100% YES CH FAILS MMS09. MAIN STEAM TV YES NONE NO FAILS SHUT
ATTACHMENT 3 Page 9 of 87
MALF NO.
MMS10 MALFUNCTION DESCRIPTION FAILURE OF AUTO STEAM DUMP AS IS GENERIC NO DEGRADATION
( 0 %)
NONE RAMP NO MMS11 MAIN STEAM HEADER YES 0-100% YES PRESSURE XMTR FAILS MMS13 S/G PRESSURE YES 0-100% YES XMTR FAILURE MMS14 TURBINE FIRST YES 0-100% YES STAGE PRESS.
XMTR FAILURE MMS15 SG PORV CONTROLLER YES 0-100% YES FAILURE MNIO 1 SOURCE RANGE YES 0-100% YES CHANNEL FAILS MNI02 SOURCE RANGE YES 0-100% YES DETECTOR FAILURE
MNI03 MNI04 INTERMED RANGE CHANNEL UNDERCOMPENSATION INTERMEDIATE RANGE YES YES 0-100%
0-100%
YES YES OVERCOMPENSATION MNIOS INTERMED RANGE YES 0-100% YES CHANNEL FAILS MNI06 FAILURE OF IR TO NO NONE NO ALLOW SR BLOCK MNI07 LOSS OF INST YES NONE NO POWER TO POWER RANGE CH MNI08 POWER RANGE YES 0-100% YES CHANNEL UPPER DETECTOR FAILS
ATTACHMENT 3 Page 10 of 87
MALF NO.
MNI09 MALFUNCTION DESCRIPTION POWER RANGE CHANNEL LOWER
.GENERIC YES DEGRADATION
( 0%)
0-100%
RAMP YES DETECTOR FAILS MNI10 POWER RANGE YES 0-100% YES CHANNEL FAILS MRC01 RCS COLD LEG PIPE YES NONE NO RUPTURE MRC02 RCS HOT LEG-PIPE YES NONE NO RUPTURE MRCQ3 RCS SUCTION LEG YES NONE NO PIPE RUPTURE MRC04 RCS LEAK NO 0-100% YES NONISOLABLE (0-600 GPM)
MRCOS RCP BRKR GND YES NONE NO OVERCURRENT TRIP MRC07 RTD FAILURE IN YES 0-100% YES HOT LEG (PROTECTION)
MRC08 RTD FAILURE IN YES 0...:.100% YES COLD LEG (CONTROL)
MRC11 RTD FAILURE IN YES 0-100% YES COLD LEG (PROTECTION)
MRC14 FAILURE OF RCP YES 0-100% YES SEAL #3 MRC15 PRESSURIZER YES. 0-100% YES PRESS. CONTROL FAILURE MRC16 PRZR REL/SFTY VV YES 0-100% YES LINE TEMP.XMTR FAILURE MRC17 PRESSURIZER LEVEL NO 0-100% YES CONTROL FAILURE
ATTACHMENT 3 Page 1 1 of 87
MALF NO.
MRC20 MALFUNCTION DESCRIPTION PRZR SPRAY GENERIC YES DEGRADATION
( 0%)
NONE RAMP NO VALVE FAILS SHUT MRC21 PRZR SAFETY VALVE YES 0-100% YES FAILS OPEN MRC22 PRZR SPRAY VALVE YES NONE NO FAILS OPEN MRC24 STE~M GENERATOR YES 0-100% YES TUBE RUPTURE MRC25 PRESSURIZER YES NONE NO HEATERS GROUP FAIL ON MRC26 SHEARED REACTOR YES NONE NO COOLANT PUMP.SHAFT MRC30 LOSS OF SEAL YES 0-100% YES INJECTION TO RCP
MRC31 MRC34 RC* LOOP FLOW XMTR FAILURE RCS WIDE & NARROW RANGE PRESS XMTR FAILURE YES YES 0-100%
0-100%
YES YES MRC37 PRZR RELIEF TANK NO 0-100% YES PRESS XMTR FAILURE MRC38 LEAK FLOW OF CC YES 0-100% YES WTR FRM RCP CLS INLET MRC40 PRESSURIZER PORV YES 0-100% YES LEAKAGE MRC42 PRESSURIZER TEMP YES 0-100% YES XMTR FAILURE MRC45 PRZR RELIEF TANK NO 0-100% YES TEMP XMTR FAILURE MRC46 RX VESSEL LKOFF NO 0-100% YES TEMP XMTR FAILURE
ATTACHMENT 3 Page 12 of 87
MALF NO.
MRC48 MALFUNCTION DESCRIPTION PRZR PRESS XMTR FAILURE GENERIC YES DEGRADATION
( 0 %)
0-100%
RAMP YES MRC49 PRZR LVL XMTR YES 0-100% NO FAILURE MRCSO PRZR RELIEF TANK NO 0-100% YES LVL XMTR FAILURE MRD01 CONTINUOUS ROD NO *NONE YES WITHDRAWL, MOR A MRD02 CONTINUOUS ROD NO NONE YES INSERTION, MOR A MRD03 LOGIC FAILURE, A NO NONE NO
& C BANKS MOVE TOGETHER MRD04 AUTO & MANUAL NO NONE NO ROD CONTROL INOPERABLE MRDOS CONT BANKS IN NO UP TO 72 YES SPEED FAIL TO STEPS/MIN 72 SPM MRD06 CONT BANKS IN NO UP TO 8 YES SPEED FAIL TO 8 STEPS/MIN SPM MRD07 CONT BANKS W/D NO UP TO 72 YES SPEED FAIL TO 72 STEPS/MIN SPM MRD08 CONT BANKS W/D NO UP TO 8 YES SPEED FAIL TO 8 STEPS/MIN SPM MRD09 CONT BANK MOVES NO NONE NO OUT WHEN IN DEMANDED MRD10 CONT BANK MOVES NO NONE NO IN WHEN OUT DEMANDED MRD12 DROPPED RCCA YES NONE NO
ATTACHMENT 3 Page 13 of 87
MALF NO.
MRD13 MALFUNCTION DESCRIPTION EJECTED CONTROL ROD GENERIC NO DEGRADATION
( 0%)
0-100%
RAMP YES MRD15 RX TRIP BREAKERS YES NONE NO OPEN DUE TO UV COIL FAILURE MRD16 IRPI FAIL YES 0-100% YES MRD18 FAIL OF AUTO TRIP NO NONE NO TO SCRAM RX
MRD1 9 FAIL OF ALL ROD NO NONE NO STOPS TO BLOCK ROD MOVE MRD20 STUCK ROD YES NONE NO MRH01 RHR SYSTEM LEAK YES 0-100% YES MRH02 LOSS OR RESIDUAL NO NONE NO HEAT REMOVAL PUMP MRH04 HCV-1758 NO 0-100% YES CONTROLLER OUTPUT FAILURE MRH05 RHR FLOW NO 0-100% YES CONTROLLER FC-1605 OUTPUT FAILS MRH06 RHR RELIEF VALVE NO NONE NO FAILS OPEN MRM01 AREA RADIATION YES 0-100% YES MONITOR FAILURE MRM02 PROCESS RADIATION YES NONE NO MONITOR FAILURE MRS06 OUTSIDE RECIRC YES NONE NO SPRAY. PUMP LOCKOUT
ATTACHMENT 3 Page 14 of 87
MALF NO.
MRS07 MALFUNCTION DESCRIPTION INSIDE RECIRC GENERIC YES DEGRADATION
( 0 %)
NONE RAMP NO SPRAY PUMP LOCKOUT MRS08 CONT SPRAY PUMP YES NONE NO LOCKOUT MSI03 HOT LEG FLOW YES 0-100% YES XMTR FAILURE MSI04 SI HOR TOTAL YES 0-100% YES FLOW XMTR FAILURE MSIOS LHSI PUMP FLOW YES 0-100% YES XMTR FAILURE MSI06 COLD LEG FLOW YES 0-100% YES XMTR FAILURE MSI07 ACCUM TANK XMTR YES 0-100% YES FAILURE MSIOB FAIL SI RESET YES NONE NO TIMER MSI10 LHSI PUMP YES 0-100 YES IMPELLER DEGRAD.
MTU01 TURBINE TRIP NO NONE NO MTU04 FAILURE OF MANUAL YES NONE NO TURBINE TRIP MTU13 FAILURE OF NO NONE NO AUTOMATIC TURBINE RUN BACK MWD01 DROPPED FUEL ASBY NO NONE NO IN SPENT FUEL PIT MWD03 ACCIDENTAL YES NONE NO RELEASE FROM RADIOACTIVE GAS
ATTACHMENT 3 Page 15 of 87 VIRGINIA POWER SIMULATOR SUPPORT GROUP SURRY UNIT 1 SIMULATOR
PERFORMANCE TEST RESULTS
ATTACHMENT 3 Page 16 of 87
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 calctilations in real time by comparing the model execution rate to real time .
ATTACHMENT 3 Page 17 of 87
STEADY STATE STABILITY This test was conducted on 08/20/88 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 ~econds. before the actual data collection commenced. This allowed any perturbations to
. reach equilibrium conditions. Data was collected in several forms.
Computer printout with a one minute resolution,
~imulator 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 within the two percent tolerance limit of the reference plant. This was done by comparing values at the beginning and ertd of the test and against steady state log readings .
ATTACHMENT 3 Page 18 of 87
FULL POWER TRIP AND RECOVERY This test was conducted on 08/20/88 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 via operator action. Actual plant procedures were used to stabilize 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 steps are also included in the data package.
Test results were compared to actual plant data and no significant differences were found .
ATTACHMENT 3 Page 19 of 87
RAMP FROM 100% TO HOT SHUTDOWN CONDITIONS This certification test was conducted -On 08/24/88 Uting the current plant operating procedures. Data was collected in several forms, ie, computer printouts, and pen chart recorders. The test run commenced with steady state IC conditions at 100% reactor power. This test ran for 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .
A power reduction was started at a rate of .3 percent per minute and maintained during the ramp. Boration, rods, and the turbine were used to control plant temperature until stable Hot Shutdown conditions were reached .
ATTACHMENT 3 Page 20 of 87
LOAD CHANGES This certification test was conducted on 08/20/88 in accordance with NSI/ 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 used during the test run to ensure that all control room actions were reproducible.
The first load change consisted of- a 5%/min 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 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. A step load change from ~00%
to SO% at a rate of 200%/min was implemented. 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 There were no problems encountered during this test .
ATTACHMENT 3 Page 21 of 87
PLANT HEATUP FROM COLD SHUTDOWN TO INTERMEDIATE SHUTDOWN This certification test was conducted on 09/15/88 in accordance with ANSI/ANS-3.5~1985 section 3.1. It was a te~t to validate the simulator performance from conditions at 195 degrees F Cold Shutdown to Intermediate Shutdown to conditions of 350 degrees F and 450 psig.
Actual plarit procedures were used during the test /run to ensure that all control room actions were reproducible.
The procedures are included in the test data package. The test was secured when stable Intermediate Shutdown conditions existed.
Various parameters were monitored and recorded for 7.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months . The expected results were obtained. 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
ATTACHMENT 3 Page 22 of 87
PLANT HEATUP FROM INTERMEDIATE SHUTDOWN TO HOT SHUTDOWN This certification test was conducted on 09/16/88 in accordance with ANSI/ANS-3.5-1985 section 3. 1 .
It was a test to validate the simulator performance from Intermediate Shutdown* conditions at 350 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 all control room actions were reproducible.
The procedures are included in the test data package. The test was. setured when. stable Hot Standby conditions existed.
Various parameters were monitored and recorded for 7.75 hours8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months . The expected results were obtained. Data collection con~isted of the following as appropriate:
o A hard copy printout of forty parameters*
o Actual simulator trend charts
ATTACHMENT 3 Page 23 of 87
PLANT COOLDOWN FROM HOT SHUTDOWN TO INTERMEDIATE SHUTDOWN This certification test was conducted on 09/20/88 in accordance with ANSI/ANS~3.5-1985 section 3.1. It was a test to validate the simulator performance from Hot Shutdown conditions at 547 degrees F to Intermediate Shutdown conditions of 350 degrees F.
Actual plant procedures were used during the test run to ensure that all control room actions were reproducible.
The procedures are included in the test data package. The test Wa$ secured when stable Intermediate Shutdown conditions existed.
Various parameters were monitored and recorded for 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months . The expected results were obtained. 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
ATTACHMENT 3 Page 24 of 87
PLANT COOLDOWN FROM INTERMEDIATE SHUTDOWN TO COLD SHUTDOWN This certification test was conducted on 09/21/88 in accordance with ANSI/ANS-3.5-1985 section 3.1. It was. a test to validate the simulator performance from Intermediate Shutdown conditions at 350 degrees F to Cold Shutdown
.conditions of 195 degrees F.
Actual plant procedures were used during the test run to ensure that all control room actions were reproducible.
The procedures are included in the test data package. The test was secured. when stable Cold Shutdown conditions existed.
Various parameters were monitored and recorded for 3.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months . Data collection consisted of the followirig as appropriate:
o A hard copy printout of forty parameters o Actual simulator trend charts o Thermal charts of sixteen parameters The expected results were obtained, however, during cooldown an increase in steam generator mass was identified. (All
supply sources were secured). This problem is being evaluated for a solution under Surry Simulator Discrepancy#
8809221130 .
ATTACHMENT 3 Page 25 of 87
PLANT STARTUP FROM HOT SHUTDOWN TO FULL POWER CONDITIONS This performance test was conducted on 08/18/88 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 a~d included as port of the data package. Data was collected in several forms; computer printouts of a one minute resolution, and simulator trend charts. The test was conducted for seven hours until rated full power was achieved.
A known deficiency between current load cycle graphs and modeled core cycle was reidentified. The core model is currently planned for upgrade by December 2, 1988 according to the simulator upgrade schedule .
ATTACHMENT 3 Page 26 of 87 VIRGINIA POWER SIMULATOR SUPPORT GROUP SURRY UNIT 1 SIMULATOR
TRANSIENT TEST RESULTS
ATTACHMENT 3 Page 27 of 87
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 FEEDWATER PUMPS With simulator initial conditions of 100% power steady state, a simultaneous trip of all* feedwater pumps was activated using malfunction MFW23. 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.
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 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.
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 MRCOS. 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 ~ere stable. No problems were encountered during the test .
ATTACHMENT 3 Page 28 of 87
TRIP OF ANY SINGLE REACTOR COOLANT PUMP With simulator initial conditions of 100% power steady state, a tri~ of "A" loop reactor coolant pump was activated using malfunction MRCOS. 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 condi~ions 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%, momentar~ly 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 concluded 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 wa~ activated using malfunctions MRC01 and MEL01. 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 minrites of run time when plant conditions were stable. No problems were encountered during the test .
ATTACHMENT 3 Page 29 of 87
UNISOLABLE MAIN STEAM LINE RUPTURE With simulator initial conditions of 100% steady state power, a maximum size unisolable A" main steam line rupture was activated using malfunction MMS03. 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.
LOCA TO SATURATION CONDITIONS With the simulator initial conditions at steady state 100% power a slow primary system depressurization was started. This was implemented by opening one of the pressurizer power operated relief valves. Prevention of ECCS activation was accomplished by use of SIMLOCH Instructor Variables. 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 at saturated conditions.
No problems were encountered during the t~st .
ATTACHMENT 3 Page 30 of 87 VIRGINIA POWER SIMULATOR SUPPORT GROUP SURRY UNIT 1 SIMULATOR
MALFUNCTION TEST RESULTS
ATTACHMENT 3 Page 31 of 87
MALFUNCTION TEST RESULTS MCA01 INSTRUMENT AIR HEADER LEAK-The Instrument Air Header Leak malfunction was conducted on 08/08/88 at 100 % power, steady state conditions. The leak was ramped from zero leakage to full leakage over a 30 second time frame to demonstrate the degradation feature. The malfunction was degraded to it's maximum severity. Various parameters were monitored and recorded to show flows and mass balances of the Instrument Air system. The test ran for 275 seconds until stable conditions existed. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancies noted during the test.
MCA02 CONTAINMENT INSTRUMENT AIR COMPRESSOR TRIP The Containment Instrument Air Compressor Trip malfunction was conducted on 08/23/88 at 100 % power, steady state conditions. Various parameters were monitored ~nd recorded for 450 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected res0lts. There ~ere no discrepancies noted during the test.
MCA04 CONTAINMENT INSTRUMENT AIR HEADER LEAK The Containment Instrument Air Header Leak malfunction was conducted on 08/23/88 at 100 % power, steady state conditions. The leak was ramped from zero leakage to full leakage over a 30 second time frame to demonstrate the degradation feature. The malfunction was degraded to it's maximum severity. Various parameters were monitored and recorded to show flows and mass balances of the Containment Instrument Air system. The test ran for 240 seconds until stable condftions existed. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancies noted during the test .
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MCA08 INSTRUMENT AIR COMPRESSOR OVERLOAD TRIP The Instrument Air Compressor Overload Trip malfunction was conducted on 08/28/88 at 100 % power, steady state conditions. Various parameters were monitored and recorded for 200 seconds and the expected results were obtained.
Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancies noted during the test.
MCC01 LOSS OF CC WATER SW THROUGH CC HEAT EXCHANGERS The Loss of CC ~ater SW Through CC Heat Exchangers malfunction was conducted on 08/08/88 at 100 % power, steady state conditions. The leak was ramped from full Service Water flow to zero Service Water Flow over a 30 second time frame to demonstrate the degradation feature. The malfunction was degraded to it's maximum severity. Various parameters were monitored and reporded to show flows and mass balances of the Service Water system. The test ran for
200 seconds until stable conditions existed. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancies noted during the test. ,
MCC03 LOSS OF ALL COMPONENT COOLING WATER PUMPS The Loss Of All Component Cooling Water Pumps malfunction was conducted on 08/09/88 at 100 % power, steady state conditions. Various parameters were monitored and recorded for 60 seconds and the expected results were obtained. Data was collected in the fo~m of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancies noted during the test .
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MCC04 LOSS OF CC TO NON - REGENERATIVE HEAT EXCHANGER The Loss Of CC to Non - Regenerative Heat Exchanger malfunction. was conducted on 08/26/88 at 100 %_power, steady state conditions. The failure was ramped from zero flow to full flow over a 30 second time frame to demonstrate the degradation feature. The malfunction was degraded to it's maximum severity. Various parameters were monitored and recorded to show flows and mass balances of the Component Cooling Water system. The test ran for 180 seconds until stable conpitions existed. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancies noted during the test.
MCCOS THERMAL BARRIER LEAK TO CC SYSTEM The Thermal .Barrier Leak to CC system malfunction was conducted on 08/23/88 at 100 % power, steady state conditions. The leak* was ramped from zero* leakage to full leakage over a 30 second time frame to demonstrate
the degradation feature. The malfunction was to it's maximum severity. Various parameters monitored and recorded to show flows and mass balances of the Component Cooling Water system. The test ran for 240 seconds until stable conditions existed. Data was collected in the form of computer printouts. This data degraded were consists of model and plant variable points that verified the expected . results. There were no discrepancies noted during the test.
MCH01 ISOLABLE LETDOWN LINE LEAK IN CONTAINMENT The Isolable Letdown Line Leak in Containment malfunction was conducted on 12/28/87 at 100 % power, steady state conditions. The leak was ramped from zero leakage to full leakage over a 30 second time frame to demonstrate the degradation feature. The malfunction was degraded to it's maximum severity. Various parameters were monitored and recorded to show flows and mass balances of the eves system.
The test ran for 209 seconds until stable conditions existed. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discr~pancies noted during the test .
ATTACHMENT 3 Page 34 of 87
MCH02 LETDOWN LEAK OUTSIDE CONTAINMENT The Letdown Leak Outside Containment malfunction .was conducted on 12/28/87 at 100 % power, steady state conditions. The leak was ramped from zero leakage to full leakage over a 30 second time frame to demonstrate the degradation feature.*The malfunction was degraded to it's maximum severity. Various parameters were monitored and recorded to show flows and mass balances of the eves system.
The t~st ran for 208 seconds until stable conditions existed. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancies noted during the test.
MCH03 CHARGING LINE LEAK DOWNSTREAM OF FCV-1122 (OUTSIDE CONTAINMENT)
The Charging Line Leak Downstream of FCV-1122 malfunction was conducted on 03/16/88 at 100 % power, steady state conditions. The leak was ramped from zero leakage to full leakage over a 30 second time frame to demonstrate the degradation feature. The malfunction was degraded to it's maximum severity. Various parameters were monitored and recorded to show flows and mass balances of the eves system.
The test ran for 220 seconds until stable conditions existed. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancies noted during the test.
MCHOS LOSS OF CHARGING PUMP The Loss of Charging Pump malfunction was conducted on 12/28/87 at 100 % power, steady state conditions. Various parameters were monitored and recorded for 100 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results.
There were no discrepancies noted during the test .
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MCH06 NON REGEN. HEAT EXCHANGER OUTLET TEMP. CONTROLLER FAILURE The Non Regen. HX Outlet Temp. Controller Failure malfunction was conducted on 12/28/87 at 100 % power, steady state conditions. The failure was tested in the high and low directions. The malfunction was ramped over a 30 second time frame to demonstrate the degradation feature. The malfunction was degraded to it's maximum severity. Various parameters were monitored and recorded for 204 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results.
There were no discrepancies noted during the test.
MCH 11 RCP SEAL INJECTION PRESSURE TRANSMITTER FAILURE The RCP
Seal Injection Pressure Transmitter Failure malfunction was conducted on 12/29/87 at 100 % power, steady state conditions. The failure was tested in the high and low directions. The malfunction was ramped over a 30 second time frame to demonstrate the degradation feature. The malfunction was degraded to it's maximum severity. Various parameters were monitored and recorded for 40 seconds and the expected results were obtained. Data was collected in the form. of computer printouts. This data consists of model and plant variable points that verified the expected results.
There were no discrepancies noted during the test.
MCH12 RCP SEAL WATER RETURN TEMPERATURE TRANSMITTER FAILURE.
The RCP Seal Water Return Temperature Transmitter Failure malfunction was conducted on 12/29/87 at 100 %
power, steady state conditions. The failure was tested in the high and low directions. The malfunction was ramped over a 30 second time frame to demonstrate the degradation feature. The malfunction was degraded to it's maximum severity. Various parameters were monitored and recorded for 30 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancies noted during the test .
ATTACHMENT 3 Page 36 of 87
The Leak in MCH13 LEAK IN NON-REGENATIVE HEAT EXCHANGER the Non~Regenative Heat Exchanger malfunction was conducted on 12/29/87 at 100 % power, steady state conditions. The leak was ramped from zero leakage to full leakage over a 30 second time frame to demonstrate the degradation feature. The malfunction was degraded to it's maximum severity. Various parameters were monitored and recorded to show flows and mass balances of the eves system.
The test ran for 40 seconds until stable conditions existed.
Data was colJected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results~ Ther~ were no discrepancies noted during the test.
MCH17 SEAL WATER RETURN FILTER CLOGS The Seal Water Return Filter Clogs malfunction was conducted on 03/31/88 at 100 % power, steady state conditions. Various parameters were monitored and recorded for ~900 seconds and the expected results were
obtained. Data was collected in the form of computer printouts. This variable points data consists of that verified model.
the expected There were no discrepancies noted during the test.
MCH19 and plant results.
VCT LEVEL CONTROLLER 112A FAILURE The VCT Level Controller 112A Failure malfunction was conducted on 08/09/88 at 100 % power, steady state conditions. The failure was tested in the high and low directions._ The malfunction was ramped over a 30 second time frame to demonstrate the degradation feature. The malfunction was degraded* to it's maximum severity.
Various parameters were monitored and recorded for 200 seconds and the expected results were obtained. Data was collected in th~ form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancies noted during the test .
ATTACHMENT 3 Page 37 of 87
MCH20 CORE ACTIVITY RELEASE MALFUNCTION The Core Activity Release malfunction was conducted. on 12/29/88 at 100 % power, steady state conditions. The activity release was ramped from zero release to maximum activity release over a 30 second time frame to demonstrate the degradation feature. The malfunction was degraded to it's maximum severity. Various parameters were monitored and recorded to show the activity levels of various systems. The test ran for 65 seconds until stable conditions existed.
Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the exp~cted results. There were no discrepancies noted during the test.
MCH21 VCT LEVEL TRANSMITTER FAILURE The VCT Level Transmitter Failure malfunction was conducted on 12/29/87 at 100 % power, steady state conditions. The failure was tested in the high and low directions. The malfunction was ramped over a 30 second
time frame to demonstrate the degradation feature.
malfunction was degraded to it's maximum was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were The severity~
Various parameters were monitored and recorded for 75
~econds and the expected results were obtained. Data no discrepancies noted during the test.
MCH22 VCT PRESSURE TRANSMITTER FAILURE The VCT Pressure Transmitter Failure malfunction was conducted on 12/29/88 at 100 % power, steady state conditions. The failure was tested in the high and low directions. The malfunction was ramped over a 30 second time frame to demonstrate the degradation feature. The malfunction was degraded to it's maximum severity.
Various par~meters were monitored and recorded for 55 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancie~ noted during the test .
ATTACHMENT 3 Page 38 of 87
MCH23*
VCT TEMPERATURE TRANSMIT~ER FAILURE The VCT Pressure Transmitter Failure malfunction ,was conduct~d on 12/29/88 at 100 % power, steady state conditions. The failure was tested in the high and low directions. The malfunctiori was ramped over a 30 second time frame to demonstrate the degradation. feature. The malfunction was degraded to it.'s maximum severity.
Various parameters were monitored and recorded for 40 seconds and the expect~d results ~ere obtained. Data was collected in the form of computer printouts. This data consists of model and plant ~ariable points that verified. the expected
results. There
were
no discrepancies noted during the test.
MCH24 BORIC_ ACID FLOW CONTROLLER 113 FAILS rhe B6r~c Acid Flow Controlier 113 Fails malfunction was conducted on 12/29/87 at 100 % power, steady state conditions. The failure wa~ tested in. the high arid low directions. The malfunction was ramped over a 30 second time
frame, to demonstrate the degradation
feature.
malfunction was* degraded to it's maximum severity. Various parameters were monitored and recorded for 45 seconds arid the eipected res~lts were obtained. Data was collected in the form of computer printouts. This data corisists of model and plant variable points that verified the expected results.
There were no discrepancies noted during the test.
The MCH25 PRIMARY WATER FLOW CONTROLLER 114 FAILS The Primary Water Fl6w Controller 114 Fails malfunction was conduct~d on 12/29/87 at
100 % power, steady state conditions. The failute was tested in the high and. low directions. The malfuriction was ramped over a 30 second time frame to demonstrate the degradation featu~e. The malfunction was degraded to it's maximum severity. Various parameters were monitored and recorded for 50 seconds and the expected results were obtained. Data was colle.cted in the form of computer printouts~ This data consists of model and plant variable points that verified the expected results.
There were no discrepancies noted during the test .
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MCH28 CHARGING LINE FLOW CONTROLLER 122A FAILS The Charging Line Flow Controller 122A malfunction was conducted on 01/09/88 at 100 % power, steady state conditioris. Th~ failure was tested in the high and low directions. The malfunction was ramped over a - 30 second time frame to demonstrate the degradation feature. The malfunction was degraded to it's maximum severity.
Various parameters were monitored and recorded for 100 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that
.ver~fied the expected results. There were no discrepanci~s noted during the test.
MCH29 CHARGING LINE FLOW TRANSMITTER 122 FAILS The Charging Line Flow Transmitter 122 Fails malfunction was conducted on 01/09/88 at 100 % power, steady state conditions. The failure was tested in the high and low directions. The malfunction was ramped over a 30 second time
frame to demonstrate the degradation feature. The malfunction was degraded to it's maximum severity. Various paramet~rs were monitored and recorded for 110 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results.
There were no discrepancies noted during the test.
MCH31 REGENERATIVE HEAT EXCHANGER CHARGING OUTLET TEMPERATURE TRANSMITTER 123 FAILS The Regenerative Heat Exchanger Charging Outlet Temperature Transmitter 123 Fails malfunction was conducted on 01/09/88 at 100 % power, steady state conditions. The failure was tested in the high and low directions. The malfunction was ramped over a 30 second time frame -to demonstrate the degradation feature. The malfunction was degraded to ~t's maximum severity. Various parameters were monitored and recorded for 35 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. Th~re were no discrepancies noted during the test .
ATTACHMENT 3 Page 40 of 87
MCH35 LOW PRESSURE LETDOWN LINE FLOW TRANSMITTER 150 FAILS The Low Pressure Letdown Line Flow Trans~itter *150 Fails malfunction was conducted on 01/09/88 at 100 % power, steady state conditions. The failure was tested in the high and low directions. The malfunction was r~mped over a 30 second time frame to demonstrate the degradation feature~
The malfunction was degraded to it's maximum s~verity.
Various parameters were monitored and iecorded for 45 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancies noted during the test.
MCH36 LOW PRESSURE LETDOWN LINE PRESSURE CONTROLLER 145 FAILS The Low Pressure Letdown Line Pressure Controller
.malfunction was conducted on 01/09/88 at 100 % power, steady state conditions. The failur~ was tested in the high and lo~
direction&. The malfunction was ramped over a 30 second time frame to demonstrate the degradation feature. The malfunctibn was degraded to it's maximum severity. Various parameters were monitored and recorded for iOO .seconds and the expected results were obtained. Data was collected in the form of computer printouts. This-data consists of model and plant variable points that verified the expected results.
There were no discrepancies noted during the test.
MCH37 LOW PRESSURE LETDOWN LINE PRESSURE TRANSMITTER 14~ FAILS The Low Pressure Letdown Line Pressure Transmitter 145 Fails malfunction was conducted ori 01/09/88 at 100 % power, steady state conditions. The failure was tested in the high and low directions. The malfunction was ramped over a - 30 second time frame to demonstrate the degradation feature ..
The malfunction was degraded to it's maximum severity.
Various parameters were monitored and recorded for 100 seconds and the expected results were* obtained. Data was collected in th~ form of computer printouts. This data consists of model and plant variabie points that verified the expected results. There were no discrepancies noted during the test .
ATTACHMENT 3 Page 41 of 87
MCH38 REGENERATIVE HEAT EXCHANGER LETDOWN TEMPERATURE TRANSMITTER 140 FAILS The Regenerative Heat Exchanger Letdown Temperature Transmitter 140 Fails malfunction was conducted on 01/09/88 at 100 % power, steady state conditions. The failure was tested in the high and low directions. The malfunction was ramped over a 30 second time frame to demonstrate the degradation feature. The malfunction was degraded to it's maximum severity. Various parameters were monitored and recorded for 35 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancies noted during the test.
MCH39 LETDOWN LINE RELIEF LINE TEMPERATURE TRANSMITTER 141 FAILS The Letdown Line Relief Line Temperatur~ Transmitter 141 Fails malfunction was conducted on 01/09/88 at 100 %
power, steady state conditions. The failure was tested in the high and low directions. The malfunction was ramped over a 30 second time frame to demonstrate the degradation feature. The malfunction was degraded to it's maximum severity. Various parameters were monitored and recorded for 35 seconds and the expected res~lts.were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancies noted during the test.
MCH40 LOW PRESSURE LETDOWN LINE TEMPERATURE TRANSMITTER 143 FAILS The Pressure Letdown Line Temperature Transmitter 143 Fails malfunction was conducted on 01/09/88 at 100 % power, steady state conditions. The failure was tested in the high and low directions. The malfunction was ramped over a 30 second time frame to demonstrate the degradation feature.
The malfunction was degraded to it's maximum severity.
Various parameters were monitored and recorded for 45 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancies noted
during the test .
ATTACHMENT 3 Page 42 of 87
MCH41 NON-REGENERATIVE HEAT EXCHANGER OUTLET TEMPERATURE TRANSMITTER 144 FAILS The Non-Regenerative Heat Exchanger Outlet Temperature Transmitter malfunction was conducted on 01/09/88 at 100 %
power, steady state conditions. The failure was tested in the high and low directions. The malfunction was ramped over a 30 second time fra~e to demonstrate the degradation feature. The malfunction was degraded to it's maximum severity. Variou~ parameters were monitored and recorded for 45 seconds and the expected results were obtained. Data was
.collected in the form of computer printouts. This data consists of model and plant variable
points that verified the expected results. There were no discrepancies noted during the test.
MCN01 LOSS OF CONDENSATE PUMP The Loss of Cond~nsate Pump malfunction was conducted on 04/26/88 at 100 % power, steady state conditions .. Various parameters were moni~ored and recorded for 120 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results.
There were no discrepancies noted during the test.
MCN02 AIR LEAKAGE INTO MAIN CONDENSER CN-SC-1A/B BOOT The Air Leakage Into Main Condenser CN-SC-1A/B Boot malfunction was conducted on 09/13/88 at 100 % power, steady state conditions. The leak ~as ramped from zero leakage to full leakage over a 30 second time frame to demonstrate the degradation feature. The malfunction was* degraded to it's maximum severity. Various parameters were monitored and recorded to show flows and mass balances of the Condensate system. The test ran for 240 seconds until stable conditions existed. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results.
There were no discrepancies noted during the test .
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MCN03 HOTWELL LEVEL CONTROLLER FAILS The Hotwell Level Controller Fails malfunction *was conducted on 08/10/88 at 100 % power, steady state conditions. The failure was tested in the high and low directions. The malfunction was ramped over a 30 second time frame to demonstrate the degradation feature. The malfunction was degraded to it's maximum severity.
Various parameters were monitored and recorded for 180 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancies noted during the test.
MCN05 CONDENSATE LEAK BETWEEN CN-114 & FCV-CN-107 The Condensate Leak Between CN-114 & FCV-CN-107 malfunction was conducted on 04/26/88 at 100 % power, steady state conditions. The leak was ramped from zero leakage to full leakage over a 30 second time frame to demonstrate the degradation feature. The malfunction was degraded to it's maximum severity. Various parameters were monitored and recorded to show flows and mass balances of the Condensate system. The test ran for 280 seconds until stable conditions existed. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancies noted during the test.
MCN08 LOSS OF LOOP SEAL FOR AIR EJECTORS 1A/B The Loss of Loop Seal For Air Ejectors 1A/B malfunction was conducted on 04/26/88 at 100 % power, steady state
conditions. The leak was ramped from zero leakage to full loss of seal over a 30 second time frame to demonstrate the degradation feature. The malfunction was degraded to it's maximum severity. Various parameters were monitored and recorded to show flows and mass balances of the Condensate system. The test ran for 400 seconds until stable conditions existed. Data was collected in the form of
computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancies noted during the test .
ATTACHMENT 3.
Page 44 of 87
MEL01 LOSS OF OFFSITE POWER The Loss Of Offsite Power malfunction was conducted on 05/31/88 at 100 % power, steady state conditions. Various parameters were monitored and recorded for 65 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results.
There were no discrepancies noted during the test.
MEL02 MAIN GENERATOR TRIP The Main Generator Trip malfunction was conducted on 08/28/88 at 108 % power, steady state conditions. Various parameters were monitored ind recorded for 60 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results.
There were no discrepancies noted during the test.
MEL07
LOSS OF 4160V STATION SERVICE BUS The Loss of 4160V Station Service Bus malfunction was conducted on 05/31/88 at 1QO % power, steady conditions. Various parameters were monitored and recorded for 60 seconds and the expected results were obtained. Data state was collected in the form of computer printouts. This data consists of model and plant Variable points that verified the expected results. There were no discrepancies noted during the test.
MELDS LOSS OF SCREENWELL TRANSFORMER The Loss of Screeriwell Transformer malfun~tion was conducted on 05/31/88 at 100 % power, steady state conditions. Various parameters were monitored and recorded for 60 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results.
There were no discrepancies noted during the test .
ATTACHMENT 3 Page 45 of 87
MEL09 LOSS OF EMERGENCY DIESEL GENERATO~
The Loss of Emergency Diesel Generator malfunction was conducted on 09/22/88 at 100 % power, steady state conditions. Various parameters were monitored and recorded for 140 seconds and the expected results were obtained.
Data was collected in the form of computer printouts. This data consisti of model and plant variable points that verified the expected results. There were no discrepancies noted during the test.
MEL12 LOSS OF 480V EMERGENCY SWITCHGEAR The Loss of 480V Emergency Switchgear malfunction was conducted on 07/31/88 at 100 % power, steady state conditions. Various parameters were monitored and recorded for 60 seconds and the expected results were obtained. Data was collected in the for~ of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancies noted during the test .
MEL13 LOSS OF 480V EMERGENCY MCC'S The Loss of 480V Emergency MCC's malfunction was conducted on 07/31/88 at 100 % power, steady state conditions. Various parameters were monitored and recorded for 120 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expect~d results.
There were no discrepancies noted during the test.
MEL14 LOSS OF SEMI VITAL BUS The Loss of Semi Vital Bus malfunction was conducted on 08/23/88 at 100 % power, steady state conditions. Various parameters were monitored and recorded for 195 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancies noted during the test.
A review of the semi-vital bus loads is currently in progress via Surry SMR# 8801081200 .
ATTACHMENT 3 Page 46 of 87
MEL17 LOSS OF 125V DC BUS The Loss of 125V DC Bus malfunction was conducted on 08/26/88 at 100 % power, steady state conditions. Various parameters were monitored and recorded for 120 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results.
Current loads are being revised to reflect the updated plant load list. Surry smr# 8808262100 has been issued to resolve this problem.
MEL18 LOSS OF 480V SWITCHGEAR The Loss of 480V Switchgear malfunction was coriducted on 07/31/88 at 100 % power, steady state conditions. Various parameters were monitored and recorded for 30 seconds and the expected results were obtained. Data was collected ~n the form of computer printouts. This data consists of model and plant variable points that verified the expected results.
There were no discrepancies noted during the test .
MEL 1-9 LOSS OF 480V MOTOR CONTROL CENTER The Loss of 480V Motor Control Center malfunction was conducted on 07/31/88 at TOO % power, steady state conditions. Various parameters were monitored and recorded for 30 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results.
There were no discrepancies noted during the test.
MEL20 LOSS OF AC VITAL BUS SUPPLY BREAKE_R The Loss of AC Vital Bus Supply Breaker malfunction was conducted on 08/26/88 at 100 % power, steady state conditions. Various parameters were monitored and recorded for 120 seconds and the expected results were obtained.
Data was collected in the form of computer printouts. This data consists of model and piant variable points that verified the expected results. A recent plant design change is being implemented which revises load distribution .
ATTACHMENT 3 Page 47 of 87
MEL21 LOSS OF 4160V EMERGENCY BUS The Loss *of 4160V Emergency Bus malfunction was conducted on 07/31/88 at 100 % power, steady state conditions. Various parameters were monitored and recorded for 180 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results.
There were no discrepancies noted during the test.
MFW01 MAIN FEED PUMP RECIRC VALVES FAIL OPEN The Main Feed Pump Recirc Valves Fail Open malfunction was conducted on 06/07/88 at 100 % power, steady state conditions. Various parameters were monitored and recorded for 180 seconds and the expected results were obtained.
Data was collected in the form of computer prLnt6uts. This data consists of model and plant variable points that verified the expected results. There were no tiiscrepancies noted during the test .
MFW02 MAIN FEED REGULATING VALVES FAIL SHUT The Main Feed Regulating Valves Fail Shut malfunction was conducted on 03/01/88 at 100 % power, steady state conditions. Various parameters were monitored and recorded for 65 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancies noted during the test .
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MFW04 LOW LUBE OIL PRESSURE FOR MAIN FEED WATER PUMPS The Low Lube Oil Pressure for Main Feed Water Pumps malfunction was conducted on 03/01/88 at 100 % power, steady state conditions. The leak was ramped from zero leakage to full leakage over a 30 second time frame to demonstrate the degradation feature. The malfunction was degraded to it's maximum severity. Various parameters were monitored and recorde*d to show flows and mass balances of th-e Feed Water system. The test ran for 160 seconds until stable conditions existed. Data was collected in the form of computer printouts. This data consists of model and pla.nt variable points that verified the expected results. There were no discrepancies noted during the test.
MFWOS MAIN FEED WATER BREAK UPSTREAM OF FLOW TRANSMITTERS The Main Feed water Break Upstream of Flow Transmitters malfunction was conducted on 09/14/88 at 100 % power, steady state conditions. The leak was ramped from zero
leakage to full leakage over a 30 second time frame to demonstrate the degradation feature. The malfunction was degraded to it's maximum severity. Various parameters were monitored and recorded to show flows and mass balances of the Feed Water system. The test ran for 200 seconds until st~ble conditions existed.
Data was collected in the form of computer printouts.
This data consists of model and plant variable points that verified the expected results. There were no discrepancies noted during the test.
MFW07 AUXILIARY FEED WATER PUMPS FW-P-3A/B OVERCURRENT TRIP The Auxiliary Feed Water Pumps FW-P-3A/B Overcurrent Trip malfunction was conducted on 03/01/88 during post reactor trip conditions. Various parameters were monitored and recorded for 80 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no disCrepancies noted during the test .
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Feed MFW08 AUXILIARY FEED WATER TURBINE WON'T STOP, PCV-MS-102B OPEN The Auxiliary Water Turbine Won't Stop, PCV-MS-102B Open malfunction was conducted on 03/01/88 at 100 % power, steady state conditions. Various parameters were monitored and recorded for 500 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancies noted during the test.
MFW1 0 AUXILIARY FEED WATER PUMP CHECK VALVE STICKS OPEN The Auxiliary Feed Water Pump Check Valve Sticks Open malfunction was conducted on 06/10/88 at 100 % power, steady state conditions. Various parameters were monitored and recorded for 180 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancies noted during the test .
MFW12 MAIN FEED WATER PUMPS SUCTION LINE BREAKS The Main Feed Water Pumps Suction Line Breaks malfunction was conducted on 08/10/88 at 100 % power, steady state conditions. Various parameters were rnonito~ed and recorded for 220 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancies noted during the test.
MFW13 STEAM GENERATOR LEVEL CHANNEL FAILS The Stearn Generator Level Channel Fails malfunction was conducted on 03/16/88 at 100* % power, steady state conditions. The failure was tested in the high and low directions. The malfunction was ramped over a 30 second time frame to demonstrate the degradation feature. The malfunction was degraded to it's maximum severity. Various parameters were monitored and recorded for 45 seconds and the expected results were obiained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results.
There were no discrepancies noted during the test.
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MFW14 AUXILIARY FEED LINE BREAK DOWNSTREAM OF FLOW TRANSMITTERS The Au~iliary Feed Line Break Downstream of Flow Transmitters malfunction ~as conducted on 06/09/88 at 106 %
po~er, steady state conditions. The leak was ramped from zero leakage to full leakage over a-30 second time fra~e to demonstrate the degradation feature. The malfunction was degraded to it's maximum severity. Various* parameters were monitored and recorded to show flows and mass balances of
the Feed Water system. The test ran for 580 seconds until stable conditions existed. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancies noted during the test.
MFW15 MAIN FEED LINE BREAK BETWEEN CHECK VALVE AND CONTAINMENT The Mairi Feed Line Break Between Check Valve and Containment malfunction was conducted on 03/16/88 at 100 %
power, steadi state conditions. The leak was ramped trom zero leakage to full leakage over a 30 second ti~e frame to demonstrate the degradation feature. The malfunction was degraded to it's maximum severity. Various parameters were monitored and recorded to show flows and mass balances of the Feed Water sysiem. The test ran for 100 seco~ds ~ntil stable conditions existed. Data was colle6ted in the form of computer printouts. This data consists of model and* plant variable points that verified the expected results. There were no discrepancies noted durini the test.
MFW16 MAIN FEED LINE BREAK INSIDE CONTAINMENT The Main Feed Line Break Inside Containment malfunction
was conducted on 03/17/88 at 100 % power, steady _state conditions. The leak was ramped from zero leakage to full leakage over a 30 second. time frame to demonstrate the*
degradation feature. The malfunction was degraded to it's maximum severity. Various parameters were monitored: and recorded to show flows and mass balances of the Feed Wat~r system. The test ran for 130 seconds until stable conditions existed. Data was collected- in the *form of computer printouts. This data consists of model and plant variable points that verified the expected result~. There were no discrepancies noted during the test .
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MFW17 DEGRADATION OF MAIN FEED WATER PUMP IMPELLER CRACK The Degradation of Main Feed Water Pump Impeller C~ack malfunction was conducted on 03/17/88 at 100% steady state conditions. The impeller was ramped from zero failure to full failure over a 30 second time frame to demonstrate the degradation feature. The malfunction was degraded to it's maximum severity. Various parameters were monitored and recorded to show flows and mass balances of the Feed Water syst~rn. The test ran for 150 seconds until stable conditions existed. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results.
There were no discrepancies noted during the test.
MFW18 STEAM GENERATOR MAIN FEED FLOW TRANSMITTERS FAIL The Stearn Generator Main Feed Flow Transmitters Fail malfunction was conducted on 03/17/88 at 100 % power, steady state conditions. The failure was tested in the high and low directions. The malfunction was ramped over a 30 second time
frame to demonstrate tha degradation feature.
malfunction was degraded to it's maximum severity. Various parameters were monitored and recorded for 40 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results.
There were no disdrepancies noted during the test.
The MFW19 STEAM GENERATOR-MAIN FEED FLOW CONTROLLERS FAIL The Stearn Generator Main Feed Flow Controllers Fail malfunction was conducted on 03/17/88 at 100 % power, steady state conditions. The failure was tested in the high and low directions. The malfunction was ramped over a 30 second .time frame to demonstrate the degradation feature. The malfunction was degraded to it's maximum severity. Various parameters were monitored and recorded for 160 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results.
There were no discrepancies noted during the test .
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MFW20 STEAM GENERATOR WIDE RANGE LEVEL TRANSMITTER FAIL The Steam Generator Wide Range Level Transmitter Fail malfunction was conducted on 03/17/88 at 100 % power, steady state conditions. The failure was tested in the high and low directions. The malfunction was ramped over a 30 second time frame to demonstrate the degradation feature. The malfunction was degraded to it's maximum severity. Various parameters were monitored and recorded for 40 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results.
There were no discrepancies noted during the test.
MFW21 STEAM GENERATOR AUXILIARY FEED FLOW TRANSMITTER FAILS The Steam Generator Aux~liary Feed Flow Transmitter Fail malfurrction was conducted on 03/17/88 ,post trip conditions. The failure was tested in the high and low directions. The malfunction was ramped over a 30 second time frame to demonstrate the 'degradation feature. The
malfunction was degraded to it's maximum severity. Various parameters were monitored and recorded for 50 seconds and the expected results were obtained. Data was coll~cted in the form of computer printouts. This data consists of model and plant variable points that verified the expected results.
There were no discrepancies noted during the test.
MFW22 MAIN FEED HEADER TRANSMITTER FAIL The Main Feed Header Transmitter Fail malfunction was conducted on 03/17/88 at 100 % power, steady state conditions. The failure was tested in the high and low directions. The malfunction was ramped over a 30 second time frame to demonstrate the degradation feature. The malfunction was degraded to it's maximum severity.
Various parameters were monitored and recorded for 40 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists - of model and plant variable points that verified the expected results. There were no discrepancies noted during the test .
ATTACHMENT 3*
Page 53 of.87
MFW23 TOTAL LOSS OF FEEDWATER The Total Loss of Feedwater malfunction was conducted on 08/26/88 at 10.0 % power, steady state conditions. Various parameters were monitored and recorded for 425 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results.
The~e were no discrepancies noted during the test.
MMI03 INCREASE IN CONTAINMENT PRESSURE The Increase in Containment Pressure malfunction was cond~cted on . 08/28/88 at ~00 % power, steady state conditiorts. The leak *was ramped from zero leakage to full leakage over a 30 second time frame to demonstrate the degradation feature. The malfunction was degraded to. it's maximum severity. Various parameters were monitored and recorded. The test ran for 500 seconds until stable conditions existed. Data was ~ollected in the form of computer printouts. This data. consists of model and plant variable points that verified the
-expected results.* There were no discr~pancies noted during the test.
MMI04 FAILURE OF REACTOR TRIP PUSH BUTTON 0~ BENCH BOARD
The Failure of Reactor Trip Push Button on Bench Board
malfunction was conducted on 07/31/88 at 100 % power, .steady state conditions. Various parameters were monitored- and recorded for 60 seconds and the expected results were obtained. Data was collected in the form of computer
~rintouts. This data* consists 6f model and plant variable points that verified the expected results. There were no discr~pancies noted during the test .
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The Rupture of MMS01 RUPTURE OF MAIN STEAM LINE AT HEADER the Main Steam Line at Header malfunction was conducted on 11/23/87 at 100 % power, steady state conditions. The leak was ramped from zero leakage to full leakage over a 30 second time frame to demonstrate the degradation feature. The malfunction was degraded to it's maximum severity. Various parameters were monitored and recorded to show flows and mass balances of the Main Steam system~ The test ran for 100 seconds until stable conditions existed. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancies noted during the test.
MMS03 RUPTURE OF MS LINE UPSTREAM OF FE The Rupture of MS Line Upstream of FE malfunction was conducted on 11/23/87 at 100 % power, steady state conditions. The leak was ramped from zero leakage to full leakage over a 30 second time frame to demonstrate the
degradation feature .. The malfunction was degraded to it's maximum severity. Various parameters were monitored and recorded to show flows and mass balances of the Main Steam system. The test ran for 120 computer printouts. This data plant variable points that seconds until conditions existed. Data was collected in the form of consists of model verified the stable and expected results. There were no discrepancies noted during the test.
MMS04 RUPTURE OF THE MAIN STEAM LINE BEFORE THE TRIP VALVE The Rupture of the Main Steam Line Before the Trip Valve malfunction was conducted on 11/23/87 at 100 % power, steady state conditions~ The leak was ramped from zero leakage to full leakage over a 30 second time frame to demonstrate the degradation feature. The malfunction was degraded to it's maximum severity. Various parameters were monitored and recorded to show flows and mass balances of the Main Steam system. The test ran for 100 seconds until stable conditions existed. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancies noted dur~ng the test .
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MMS06 MAIN STEAM TRIP VALVE FAILS ~SIS The Main Steam T~ip Valve Fails AS Is malfunction *was conducted on 11/24/B7 at 100 % power, steady state conditions in conjunction with a Main Steam Line Break malfunction Various parameters were monitored and recorded for 100 seconds and the expected 'results were obtained. Data was collected in tne form of computer printouts. This data, ~onsists of model and pl~nt variable points that verified- the expected results. There were no discrepancies noted during the test.
MMS07 STEAM GENERA~OR SAFETY VALVE FAILS O~EN Tha Steam Generator Safety Valve Fails Open malfunction.
was conducted on 12/02/87 at 100 % power, steady state conditions. The valve was ramped from closed to full open position over a 30 second time frame to demonstrate the degradatioti feature. The malfunctibn was degraded to it's maximum severity. Various parameters were monitored and recorded to show flows and mass balances of the Main Steam
system. The test r~n for 200 second~ until stable conditions existed. D~ta was collected in the* form of c6mputer printouts. This data consists of model, and plant Variable points that verified the expected results. There were ~o discrepancies noted during the test.
MMS08 STEAM 'GENERATOR STEAM FLOW TRANSMITTER FAILURE The Steam Generator Steam Flow Transmitter Failure malfunction was conducted on 09/14/88 at 100 % power, steady state conditions. The failure was tested in the high and low directions. The malfunction was ramped over a 30 second time frame to demonstrate the degradation feature. The malfunction was d~graded to it's, maiimum severity. Various parameters were,monitored and recorded for 120 seconds until the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and, plant variable points that* verified the
expected results. There were no discrepancies not~d during the test .
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MMS09 MAIN STEAM TRIP VALVE FAILS SHUT The Main Steam Trip Valve Fails Shut malfunction was conducted on 12/02/87 at 100 % power, steady state conditions. Various parameters were monitored and recorded for 50 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancies noted during the test.
MMS10 FAILURE OF AUTO STEAM DUMP AS IS The Failure of Auto Steam Dump As Is malfunction was conducted on 12/02/87 at 100% reactor power. The first test was a Reactor Trip initiation followed by the malfunction being implemented. The second test was with the Malfunction implemented followed by a Reactor Trip. Various parameters were monitored and recorded for 100 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancies noted during the test.
MMS11 MAIN STEAM HEADER PRESSURE TRANSMITTER FAILURE The Main Steam Header Transmitter Failure malfunction was conoucted on 12/02/87 at 100 % power, steady state conditions. The failure was tested in the high and low directions. The malfunction was ramped over a 30 second time frame to demonstrate the degradation feature. The malfunction was degraded to it's maximum severity. Various parameters were monitored and recorded for 35 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results.
There were no discrepancies noted during the test~
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The Steam Generator MMS13 STEAM GENERATOR PRESSURE TRANSMITTER FAILURE Pressure Transmitter Failure malfunction was conducted on 12/03/87 at 100 % power, steady state conditions. The failure was tested in the high and low directions. The malfunction was ramped over a 30 second time frame to demonstrate the degradation feature. The malfunction was degraded to it's maximum severity. Various parameters were monitored and recorded for 40 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results.
There were no discrepancies noted during the test.
MMS14 TURBINE FIRST STAGE PRESSURE TRANSMITTER FAILURE The Turbine First Stage pressure Transmitter Failure malfunction was conducted on 03/16/88 at 100 % power, steady state conditions. The failure was tested in the high and low directions. The malfunction was ramped over a 30 second time frame to demonstrate the degradation feature. The malfunction was degraded to it's maximum severity. Various parameters were monitored and recorded for 40 seconds and the expected results were* obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results.
There were no discrepancies noted during the test.
MMS15 STEAM GENERATOR PORV CONTROLLER FAILURE The Steam Generator PORV Controller Failure malfunction was conducted on* 06/19/88 at 100 % power, steady state conditions. The failure was tested in the high and low directions. The malfunction was ramped over a 30 second time frame to demonstrate the degradation feature. The malfunction was degraded to it's maximum severity. Various parameters were monitored and recorded for 180 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results.
There were no discrepancies noted during the test .
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The Source MNIO 1 SOURCE RANGE CHANNEL FAILS Range _Channel Fails malfunction .was conducted on 01/10/88 at Hot Shutdown, steady state conditions. The. failure was tested in the high and low directions. The malfunction was ramp~d over a 30 second time frame to demonstrate the degradation feature. Th~
malfuhction was degraded to it's maximum severity. Various parameters were monitored and recorded for 40 seconds and the expected results were obtained. Data was. collected *in the f6rm of domputer printouts. Th!s data consists of model and plant variable points that verified the ~xpected results.
Thete were no*disdrepancie~ noted during_the test.
MNI02 SOURCE RANGE DETECTOR FAILURE The Source Range Detector Failure malfunction was conducted on 08/28/88 at* Hot Shutdown, steady state conditions. The detector wa£ ramped from minimum to maximum severity over a 30 second time frame to demonstrate the
degradation feature. Various I parameter~ were monitored and recorded for 60 s~conds. and the expected results were obtained Data wa~ collected in the foim of computer printouts. This data consists of model* and plant var~able points that verified the exp~cted results. There were nd discrepancies noted during the test.
MNI03 INTERMEDIATE RANGE CHANNEL UNDERCOMPENSATION The .Intermediate Range Channel Undercompensation malfunction was conducted on 01/10/88- at Hot Shutdown, steady state conditions. The*channel was' ramped from* zero uridercompensation to full under- compensation over a_ 30
~econd time frame to demonstrate the degradation* feattire.
The malfunction was degraded to it's maximum severity.
Various parameters were monitored *and recorded 270 seconds and the expected results _were obtained. Data-was collected in the form of computer printouts. This data consists of model and plant variable ~oints that verified the expected results. There were n6 discrepancies noted during the t~st .
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The Intermediat~
MNI04 INTERMEDIATE RANGE CHANNEL OVERCOMPENSATION Range Channel Overcompensation malfunction was conducted -on 01/10/88 at Hot Shutdown, steady state conditions. The channel was ramped from zero overcompensation to full over- compensation over a 30 second time frame to demonstrate the degrad~tion feature. The malfunction was degraded to it's maximum severity. Various parameters were monitored and recorded 290 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results.
There were no discrepancies noted during the test.
MNI05 INTERMEDIATE RANGE CHANNEL FAILS The Intermediate Range Channel Fails malfunction was conducted on 01/10/88 at Hot Shutdown, steady state conditions. The failure was tested in the high and low directions. The malfunction was ramped over a 3~ second time frame to demonstrate the degradation feature. The malfunction was degraded to it's maximum severity. Various parameters were monitored and recorded for 60 seconds and the expected results were obtained. Data was collected -in the form of computer printouts. This data consists of m6~el and plant variable points that verifie~ the expected results.
There were no discrepancies noted during the test.
MNI06 FAILURE OF IR TO ALLOW SR BLOCK The Failure of Intermediate Range to allow Source Range Block malfunction was conducted on 01/10/88 at Hot Shutdown, plant startup conditions. Various parameters were monitored and recorded for 190 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancies n9ted during the test .
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MNI07
.LOSS OF INSTRUMENTATION POWER TO POWER RANGE CHANNEL The Loss of Instrumentation Power to Power R~nge Channel malfunction was conducted on 01/10/88 at 100 %
power, steady state* conditions. Various parameters were monitored and recorded for 120 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancies noted during the test.
MNI08 PO~ER RANGE CHANNEL UPPER DETECTOR FAILS The Power Range Channel Upper Detector Fails malfunction was conducted on 01/10/88 at 100 % power, steady state conditions. The failure was tested in the high and low directions~ The malfunction was ramped over a 30 second time frame to demonstrate the degradation feature. The malfunction was degraded to it's maximum severity. Various parameters were monitored and recorded for 180 seconds and the ~xpected results were obtained. Data was collected in
the form of computer printouts. This data consists of model and plant variable points that verified the expected resulti.
There were no discrepancies noted during the test.
MNI09 POWER RANGE CHANNEL LOWER DETECTOR FAILS The Power Range Channel Lower Detector Fails malfunction was conducted on 01/10/88 at 100 % power, steady state conditions. The failure was tested in the high and low d~rections. The malfunction was ramped over a 30 secortd time frame to demonstrate the degradation feature. The malfunction was degraded to it's maximum ~everity. Various parameters were monitored and recorded for 180 seconds and the expe~ted results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results.
There were no discrepancies noted during the test .
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MNI10 POWER RANGE CHANNEL FAILS The Power Range Channel Fails malfunction was conduqted on 01/10/88 at 100 % power, steady state conditions. The failure was tested in the high and low directions. The malfunction was ramped over a 30 second time frame to demonstrate the degradation feature. The malfunction was degraded to it's maximum severity. Various parameters were monitored and recorded for 180 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancies noted during the test.
MRC01 RCS COLD LEG PIPE RUPTURE The RCS Cold Leg Pipe Rupture malfunction was conducted on 06/07/88 it 100 % power, steady state conditions. Various parameters were monitored and recorded for 580 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists 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 RCS Hot Leg Pipe Rupture malfunction was conducted on 06/08/88 at 100 % power, steady state conditions. Various parameters were monitored and recorded for 600 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results.
There were no discrepancies noted during the test .
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MRC03 RCS SUCTION LEG PIPE RUPTURE The RCS Suction- Leg Pipe Rupture malfunction was conducted on 06/08/88 at 100 % power, steady state conditions. Various parameters were monitored and recorded for 600 seconds and the expected results were obtained.
Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancies noted during the test.
MRC04 RCS LEAK NONISOLABLE The RCS Leak Nonisolable malfunction was conducted on 06/08/88 at 100 % power, steady state conditions. Various parameters were monitored and recorded for 400 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results.
There were no discrepancies noted during the test.
MRCOS RCP OVERCURRENT TRIP The RCP Overcurrent Trip malfunction was conducted on 10/20/87 at 100 % power, steady state conditions. Various parameters were monitored and recorded for 280 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results.
There were no discrepancies noted during the test.
MRC07 RTD FAILURE IN HOT LEG (PROTECTION)
The RTD Failure in Hot Leg (Protection) malfunction was conducted on 11/02/87 at 100 % power, steady state conditions. The failure was tested in the high and low directions. The malfunction ias r~mped over a 30 second time frame to demonstrate the degradation feature. The malfunction was degraded to it's maximum severity. Various parameters were monitored and recorded for 100 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results.
There were no discrepancies noted during the test .
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MRC08 RTD FAILURE IN COLD LEG (CONTROL)
The RTD Failure ih Cold Leg (Control) malfunction' was conducted on 12/12/87 at 100 % power, steady state conditions. The failure was tested in the high and low directions. The malfunction was ramped over a 3 0 second tim,e frame to demonstrate the degradation feature. The malfunction was degraded to it's maximum severity. Various parameters were monitored and recorded for 40 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results.
There were no discrepancies noted during the test.
MRC11 RTD FAILURE IN COLD LEG (PROTECTION)
The RTD Failure in Cold Leg (Protection) malfunction was conducted on 12/07/87 at 100 % power, steady state conditions. The failure was tested in the high and low directions. The malfunction was ramped over a 30 second time frame to demonstrate the degradation feature. The malfunction was degraded to it's maximum severity. Various parameters were monitored and recorded for 45 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plarit variable points that verified the expected results.
There were no discrepancies noted during the test.
MRC14 FAILURE OF RCP SEAL# 3 The Failure of RCP Seal # 3 malfunction was conducted on 11/05/87 at 100 % power, steady state conditiohs. The leak was ramped from zero failure to full failure over a 30 second time frame to demonstrate the degradation feature.
The malfunction was degraded to it's maximum severity.
Various parameters were monitored and recorded to show flows and mass balances of the Reactor Coolant system. The test ran for 100 seconds until stable conditions existed. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no .discrepancies noted during the test .
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MRC15 PRESSURIZER PRESSURE CONTROiLER FAILURE The Pressurizer Pressure Controller Failure malfunction was conducted on 07/31/88 at 100 % power, steady state conditions. The failure was tested in the high and low directions. The malfunction was ramped over a 30 second time frame to demonstrate the degradation feature. The malfunction was degraded to it's maximum severity. Various
parameters were monitored and recorded for 180 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results.
There were no discrepancies noted during the test.
MRC16 PRESSURIZER REL/SAF VV LINE TEMPERATURE TRANSMITTER FAILURE The Pressurizer Relief/Safety Valve Line Temperature Transmitter Failure malfunction was conducted on 11/05/87 at 100 % power, steady state conditions. The failure was tested in the high and low directions. The malfunction was ramped over a 30 second time frame to de~onstrate the degradation feature. The malfunction was degraded to it's maximum severity. Various parameters were ~onitored and recoided, for 60 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. Ttere were no discrepancies noted during the test.
MRC17 PRESSURIZER LEVEL CONTROLLER FAILURE The Pressurizer Level Controller Failure malfunction was conducted on 11/05/87 at 100 % power, steady state conditions. The failure was tested in the high and low directions. The malfunction was ramped over a 30 second time frame to demonstrate the degradation feature.* The malfunction was degraded to it's maximum severity. Various parameters were monitored and recorded for 1856 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of_ model and ~lant variable points that verified the expected results.
There were no discrepancies noted during the test .
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MRC20 PRESSURIZER SPRAY VALVE FAILS SHUT The Pressurizer Spray Valve Fails Shut malfunction .was conducted on 11/05/87 at 100 % power, steady state conditions. Various parameters were monitored and recorded for 70 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable. points that verified the expected results. There were no discrepancies noted during the test.
MRC21 PRESSURIZER SAFETY VALVE FAILS OPEN The Pressurizer Safety Valve Fails Open malfunction was conducted on 11/05/87 at 100 % power, steady state conditions. The leak w'as ramped from zero failure to full failure over a 30 second time frame to demonstrate the degradation feature. The malfunction was degraded to it's maximum severity. Various parameters were monitored and recorded to show flows and mass balances of the Reactor Coolant system. The test ran for 100 seconds until stable conditions existed. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancies noted during the test.
MRC22 PRESSURIZER SPRAY VALVE FAILS OPEN The Pressurizer Spray Valve Fails Open malfunction was conducted on 11/05/87 at 100 % power, steady state conditions. Various parameters were monitored and recorded for 250 seconds and the expected results were obtained.
Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results .. There were no discrepancies noted during the test .
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MRC24 STEAM GENERATOR TUBE RUPTURE The Steam Generator Tube Rupture malfunction *Was conducted on 11/11/87 at 100 % power, steady state conditions. The leak was ramped from zero leakage to full leakage over a 30 second time frame to demonstrate the degradation feature. The malfunction was degraded to it's maximum severity. Various parameters were monitored and recorded. The test ran for 261 seconds until stable conditions existed. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancies noted during the test.
MRC25 PRESSURIZER HEATERS GROUP FAIL ON The Pressurizer Heaters Group Fail On malfunction was conducted on 11/11/87 at 100 % power, steady state conditions. Various parameters were monitored and recorded for 180 seconds and the expected results were obtained.
Data was collected in the form of computer printouts. This
data consists of model and plant variable points that verified the expected results. There were no discrepancies noted during the test ..
MRC26 SHEARED REACTOR COOLANT PUMP SHAFT The Sheared Reactor Coolant Pump Shaft malfunction was conducted on 11/11/87 at 100 % power, steady state conditions. Various parameters were monitored and recorded for 150 seconds and the expected results were obtained.
Data was collected in the form of computer printouts. This data consists* of model and plant variable points that verified the expected results. There were no discrepancies noted during the test .
ATTACHMENT 3 Page 67 of 87
MRC30 LOSS OF SEAL INJECTION TO RCP The Loss of Seal Injection to RCP malfunction was conducted on 09/22/88 at 100 % power, steady state conditions. The malfunction was ramped from normal flow to zero flow over a 30 second time frame to demonstrate the degradation feature. The malfunction was degraded to it's maximum severity. Various parameters were monitored and recorded to show flows and mass balances of the Reactor Coolant system. The test ran for 120 seconds until stable conditions existed. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancies noted during the test.
MRC31 REACTOR COOLANT LOOP FLOW TRANSMITTER FAILURE The Reactor Coolant Loop Flow Transmitter malfunction was conducted on 11/24/87 at 100 % power, steady state conditions. The failure was- tested in the high and low directions. The malfunction was ramped over a 30 second time
f~ame to demonstrate the
degradation feature.
malfunction was degraded to it's maximum severity.
The Various
~arameters were monitored and recorded for 45 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that veiified the expected results.
There were no discrepancies noted during the test.
MRC34 RCS WIDE & NARROW RANGE PRESSURE TRANSMITTER FAILURE The RCS Wide & Narrow Range Pressure Transmitter Failure malfunction was conducted on 11/25/87 at 100 %
power, ~teady state conditions. The failure was tested in the high and low directions. The malfunction was ramped over a 30 second time frame to demonstrate the degradation feature. The malfunction was degraded to it's maximum severity. Various parameters were monitored and recorded for 40 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancies noted during the test .
ATTACHMENT 3 Page 68 of 87
MRC37 PRESSURIZER RELIEF TANK PRESSURE TRANSMITTER FAILURE The Pressurizer Relief Tank Pressure Transmitter Failure malfunction was conducted on 11/25/87 at 100 %
power, steady state conditions. The failure was tested in the high and low directions. The malfunction was ramped over a 30 second time frame to demonstrate the degradation feature. The malfunction WqS- degraded to it's maximum severity. Various parameters were monitored and recorded for 41 seconds and the expected r~sults were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancies noted during the test.
MRC38 LEAK FLOW OF CC WATER FROM RCP COOLER INLET The Leak Flow *of CC Water From RCP Cooler Inlet malfunction was conducted on 08/10/88 at 100 % power, steady
-state conditions. The leak was ramped from zero leakage to full leakage over a 30 second time frame to demonstrate the degradation feature. The malfunction was degraded to it's maximum severity. Various parameters were monitored and recorded to show flows and mass balances of the Component Cooling Water system. The test ran for 120 seconds until stable conditions existed. Data was collected in the form of computer printouts. This data consists of model and _plant variable.points that verified the expected results. There were no discrepancies noted during the test.
MRC40 PRESSURIZER PORV LEAKAGE The Pressurizer PORV Leak~ge malfunction was conducted on 11/25/87 at 100 % power, steady state cohditions. The leak was ramped from zerb leakage to full leakage over a 30 second time-frame to demonstrate the degradation feature.
The malfunction was degraded* to it's maximum severity.
Various parameters were monitored and recorded to show flows and mass balances of the Reactor Coolant system. The test ran for 120 seconds until stable conditions existed. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. Thete were no discrepancies noted during the test .
ATTACHMENT 3 Page 69 of 87
MRC42 PRESSURIZER TEMPERATURE TRANSMITTER FAILURE The Pressurizer Temperature Transmitter Failure malfunction was conducted on 11/25/87 at 100 l power, steady state conditions. The failure was tested in the high and low directions. The malfunction was ramped over a 30 second time frame to demonstrate the degradation feature. The malfunction was degraded to it's maximum severity. Various parameters were monitored and recorded for 40 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results.
There were no discrepancies noted during the test.
MRC45 PRESSURIZER RELIEF TANK TEMPERATURE TRANSMITTER FAILURE The Pressurizer Level Startup Transmitter Failure malfunction was conducted on 11/25/87 at 100 % power, steady
~tate conditions. The failbre was tested in the high and low directions. The malfunction was ramped over a 30 second time frame to .demonstrate the degradation feature. The malfuriction was degraded to it's maximum severity. Various parameters were monitored and recorded for 40 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant 'variable points that verified the expected results.
There were no discrepancies noted during the test.
MRC46 REACTOR VESSEL LEAKOFF TEMPERATURE TRANSMITTER FAILURE The Reactor Vessel Leakoff Temperature Transmitter Failure malfunction was conducted on 11/25/87 at 100 %
power, steady state conditions. The failure was tested in the high and low directions. The malfunction was ramped over a 30 second time frame to demonstrate the degradation feature. The malfunction was degraded to it's maximum severity. Various parameters were monitored and recorded for 40 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancies noted during the test .
A.TT ACHMENT 3 Page 70 of 87
The Pressurizer MRC48 PRESSURIZER PRESSURE TRANSMITTER FAILURE Pressure Transmitter Failure malfunction was conducted on 12/07/87 at 100 % power, st~ady state conditions. The failure was tested in the high and low directions. The malfunction was ramped over a 30 second time frame to demonstrate the degradation feature. The malfunction was degraded to it's maximum severity. Various parameters were monitored* and recorded for 45 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results.
There were no discrepancies noted during the test.
MRC49 PRESSURIZER LEVEL TRANSMITTER FAILURE The Pressurizer Level Transmitter Failure malfunction was conducted on 11/25/87 at 100 % power, steady state conditions. The failure. was tested in the high and low directions. The malfunction was ramped over a 30 second time frame to demonstrate the degradation feature. The
malfunction was degraded to it's maximum severity. Various parameters were monitored and recorded for 40 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results.
There were no discrepancies noted during the test.
MRC50 PRESSURIZER RELIEF TANK LEVEL TRANSMITTER FAILURE The Pressurizer Relief Tank Level Transmitter Failure malfunction was conducted on 11/25/87 at 100 % power, steady state conditions. The failure was tested in the high and low directions. The malfunction was ramped over a 30 second time frame to demonstrate the degradation feature. The malfunction was degraded to it's maximum ~everity. Various parameters were monitored and recorded for 40 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results.
There were no discrepancies noted during the test .
ATTACHMENT 3 Page 71 of 87
MRD01 CONTINUOUS ROD WITHDRAWAL, MANUAL OR AUTO The Continuous Rod Withdrawal, Manual or ~uto malfunction was conducted on 08/26/88 at 5~ % power, steady state conditions. Various parameters were monitored and recorded for 600 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results .. This test was performed in both "Auto and Manual" modes. There were no discrepancies noted during the test.
MRD02 CONTINUOUS ROD INSERTION, MANUAL OR AUTO The Continuous Rod Insertion , Manual or Auto malfunction was conducted on 08/26/88 at 100 % power, steady state conditions. Various parameters were monitored and recorded for 600 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancies noted during the test.
MRD03 LOGIC FAILURE A & C BANKS MOVE TOGETHER The Logic Failure A & C Banks Move Together malfunction was conducted on 08/28/88 at 100 % power, steady state conditions. Various parameters were monitored and recorded for 65 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancies noted during the test .
ATTACHMENT 3 Page 72 of 87
MRD04 AUTO & MANUAL ROD CONTROL INOPERABLE The Auto & Manual Rod Control Inoperable malfunction was conducted on 07/16/88 at 100 % power, steady state conditions. Various parameters were monitored and recorded for 300 seconds and the expected results were obtained.
Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancies noted during the test.
MRDOS CONTROL BANKS IN SPEED FAIL TO 72 STEPS PER MINUTE The Control Banks In Speed Fail To 72 Steps Per Minute malfunction was conducted on 07/16/88 at 100 % power, steady state conditions. The speed was ramped from normal speed to sev~nty two ~teps per minute over a 30 second time frame to demonstrate the degradation* feature. The malfunction was degraded to it's maximum severity. The test ran for 80 seconds until stable conditions existed. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancies noted during the test.
MRD06 CONTROL BANKS IN SPEED FAIL TO 8 STEPS PER MINUTE The Control Banks In Speed Fail To 8 Steps Per Minute malfunction was conducted on 07/16/88 at 100 % power, steady.
state conditions. The speed was ramped from normal speed to eight steps per minute over a 30 second time frame to demonstrate the degradation feature. The malfunction was degraded to it's maximum severity. The test ran for 140 seconds until stable conditions existed. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancies noted during the test .
ATTACHMENT 3 Page 73 of 87
MRD07 CONTROL BANKS WITHDRAWAL SPEED FAIL TO 72 STEPS PER MINUTE The Control Banks Withdrawal Speed Fail To 72 Steps Per Minute malfunction was conducted on 07/16/88 at 100 % power, steady state conditions. The speed was ramped from normal speed to seventy two steps per minute over a 30 second time frame to demonstrate the - degradation feature. The malfunction was degraded to it's maximum severity. The test ran for 65 seconds until stable conditions existed. Da\a was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancies noted during the test.
MRD08 CONTROL BANKS WITHDRAWAL SPEED FAIL TO 8 STEPS PER MINUTE The Control Banks Withdrawal Speed Fail To 8 Steps Per Minute malfunction was conducted on 07/16/88 at 100 % power, steady state conditions. The spee9 was ramped from normal speed to eight steps per minute ovet a 30 second time frame
to demonstrate the degradation feature. The malfunction- was degraded to it's maximum severity. The test ran for 180 seconds until stable conditions existed. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancies noted during the test.
MRD09 CONTROL BANK MOVES OUT WHEN IN DEMANDED The Control Bank Moves Out When In Demanded malfunction was conducted on 07/16/88 at 100 % power, steady state conditions. Various parameters were monitored and recorded for 300 seconds and the expected results were obtained.
Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancies noted during the test .
ATTACHMENT 3 Page 74 of 87
MRD10 CONTROL BANK MOVES IN WHEN OUT DEMANDED The Control Bank Moves In When Out Demanded malfunction was conducted on 07/16/88 at 100 % power, steady state conditions. Various parameters were monitored and recorded for 240 seconds and the expected results were obtained.
Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancies noted during the test.
MRD12 DROPPED ROD The Dropped Rod malfunction was conducted at 100 %
power, steady state conditions. Various parameters were monitored and recorded for 114 seconds and the. expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancies noted during the test .
MRD13 EJECTED CONTROL ROD The Ejected Control Rod malfunction was conducted on 08/28/88 at 100 % power, steady state conditions. Various parameters were monitored_ and recorded for 60 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results.
There were no discrepancies noted during the test.
MRD15 RX TRIP BKRS OPEN DUE TO UV COIL FAILURE The RX Trip Breakers Open Due to UV Coil Failure malfunction was conducted on 08/26/88 at 100 % power, steady state conditions. Various parameters were monitored and recorded for 120 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancies noted during the test .
ATTACHMENT 3 Page 75 of 87
MRD16 IRPI FAILURE The IRPI Failure malfunction was conducted on 08/28/88 at 100 % power, steady state conditions. Various parameters were monitored and recorded for 180 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancies noted during the test.
MRD18 FAILURE OF AUTO TRIP TO SCRAM REACTOR The Failure of Auto Trip to Scram Reactor malfunction was conducted on 07/16/88 at 100 % power, steady state conditions. Various parameters were monitored and recorded for 180 seconds and the expected results were obtained.
Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There.were no discrepancies noted during the test.
MRD19 FAILURE OF ALL ROD STOPS TO BLOCK ROD MOVEMENT The Failure of All Rod Stops To Block Rod Movement malfunction was conducted on 07/16/88 at 100 % power, steady state conditions. Various parameters *were monitored and recorded for 240 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There .were no discrepancies noted during the test .
ATTACHMENT 3 Page 76, of 87
MRD20 STUCK ROD Th~ Stuck Rod malfuriction was conducted on 08/28/88 at 100 % power, steady state conditions. Various parameters were monitored and recorded for 60 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancies noted during the test.
MRH01 RHR SYSTEM LEAK The RHR System Leak malfunction was conducted on 08/26/88 at cold shutdown, steady state conditions. The leak was ramped from zero leakage to full leakage over a 30 second time frame to demonstrate the degradation feature.
The malfunction was degraded to it's maximum severity.
Various parameters were monitored and recorded to show flows and mass balances of the RHR system. The test ran for 100 seconds until stable conditions existed. Data. was collected in the form of computer printouts. This data consists of
model and plant variable points that verified the expected results. There were no discrepancies noted during the test .
. MRH02 LOSS OF RESIDUAL HEAT-REMOVAL PUMP The Loss of Residual Heat Removal Pump malfunction was conducted on_ 08/26/88 at Cold Shutdown, steady state conditions. Various parameters were monitored and recorded for 120 seconds and the expected results were obtained.
Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancies noted during the test .
ATTACHMENT 3 Page 77 of 87
MRH04
.HCV-1758 CONTROLLER OUTPUT FAILS The HCV-1758 Controller Output Fail malfunction was conducted on 09/14/88 at Cold Shutdown, steady state conditions. The failure was tested in the high and low directions. The malfunction was ramped over a 30 second time frame to demonstrate the degradation feature. The malfunction was degraded to it-'s maximum severity. Various parameters were monitored and recorded for 240 seconds and the exp~cted results we~e obtained. Data *was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancies n6ted during the test.
MRHOS RHR FLOW CONTROLLER FC-1605 OUTPUT FAILS The RHR Flow Controller FC-1605 Output Fails malfunction was conducted on 09/14/88 at Cold Shutdown, steady state conditions. The_ failure was tested in the high and low directions. The malfunction was ramped over a 30 second time frame to demonstrate the degradation feature.
The malfunction was degraded to it's maximum severity.
Various parameters were monitored and recorded for 120 seconds and the expected results were _obtained. Data was collected in the form of computer printouts. Th~s data consists of model and plant variable points that verified the expected results. There were no discrepancies noted
-during the t~st.
MRH06 RHR RELIEF VALVE FAILS OPEN The RHR Relief Valve Fails Open malfunction was conducted on 09/14/88 at 300 PSI and 300 degrees Fahrenheit, steady state conditions. Various parameters were monitored and recorded for 200 seconds until the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancies noted during the test .
ATTACHMENT 3 Page 78 of 87
MRM01 AREA RADIATION MONITOR FAILURE The Area Radiation Monitor failure malfunction was conducted on 08/26/88 at 100 % power, steady state conditions. The failure was tested in the high and low directions. The malfunction was ramped over a 30 second time frame to demonstrate the degradat~on feature. The
-malfunction was degraded to it's maximum severity.
Various parameters were monitored and recorded for 35 seconds and the expected results were obtained. *Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. RI-RMS-153 caused an alarm when failed low. S~rry smr# 8808261900 was issued. -This problem was resolved on 09/14/88.
MRM02 PROCESS RADIATION MONITOR FAILURE The Process Radiation Monitor Failure malfunction was conducted on 08/28/88 at 100 % power, steady state conditions. The failure was tested in the high and low directions. The malfunction was ramped over a 30 second time frame to demonstrate the degradation feature. The malfunction was degraded to it's maximum severity.
Various parameters were monitored and recorded for 35 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data
consists of model and plant variable points that verified the expected results. There were no discrepancies noted during the test.
MRS06 OUTSIDE RECIRC SPRAY PUMP LOCKOUT The Outside Recirc Spray Pump Lockout malfunction was conducted on 08/10/88 during a large break LOCA malfunction.
Various parameters were monitored and recorded for 120 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results~ There were no discrepancies noted during the test .
ATTACHMENT 3 Page 79 of 87
MRS07 INSIDE RECIRC SPRAY PUMP LOCKOUT The Inside Recirc Spray Pump Lockout malfunction was conducted on 08/10/88 during a*large break LOCA malfunction.
Various parameters were monitored and recorded for 120 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancies noted during the test.
MRS08 CONT SPRAY PUMP LOCKOUT The_ Cont Spray Pump Lockout malfunction was conducted on 08/10/88 during a large break LOCA malfunction. Various parameters were monitored and recorded for 290 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results.
There were.no discrepancies noted Quring the test.
MSI03 HOT LEG FLOW XMTR FAILURE The Hot Leg Flow XMTR Failure malfunction was conducted on 05/21/88 during a large break LOCA malfunction. The failure was tested in the high and low directions. The malfunction was ramped over a 30 second time frame to demonstrate the degradation feature. The malfunction was degraded to it's maximum severity. Various parameters were monitored and recorded for 45 seconds and the* expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verifLed the expected results. There were no discrepancies noted during the test .
ATTACHMENT 3 Page 80 of 87
MSI04 SI HDR TOTAL FLOW XMTR FAILURE The SI HDR Total Flow XMTR Failure malfunction *Was conducted on 05/21/88 during a large break LOCA malfunction.
The failure was tested in the high and low directions. The malfunction was ramped over a 30 second time frame to demonstrate the degradation feature. The malfunction was degraded to it's maximum severity. Various parameters were monitored and recorded for 40 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancies noted during the test.
MSI05 LHSI PUMP FLOW XMTR FAILURE The LHSI Pump Flow XMTR Failure malfunction was conducted on 05/21/88 during a large break LOCA malfunction.
The failure was tested in the high and low directions. The malfunction was ramped over a 30 second tirn'e fl'.'.ame to demonstrate the degradation feature. The malfunction was degraded to it's maximum severity. Various parameters were monitored and recorded for 40 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancies noted during the test.
MSI06 COLD LEG FLOW XMTR FAILURE The Cold Leg Flow XMTR Failure malfunction was conducted on 05/21/88 during a large break LOCA malfunction.
The failure was tested in the high and low directions. The malfunction was ramped over a 30 second time frame to demonstrate the degradation feature. The malfunction was degraded to it's maximum severity. Various parameters were monitored and recorded for 40 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were rio discrepancies noted during the test .
ATTACHMENT 3 Page 81 of 87
MSI07 ACCUM TANK XMTR FAILURE The Accum Tank XMTR Failure malfunction was conducted on 05/21/88 at 100 % power, steady state conditions. The failure was tested in the high and low directions. The malfunction was r~mped over a 30 second time frame to demonstrate the degradation feature. The malfunction was degraded to it's maximum severity. Various parameters were monitored and recorded for 45 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant vari~ble points that verified the expected results. There were no discrepancies noted during the test.
MSI08 FAIL SI RESET TIMER The Fail SI Reset Timer malfunction was conducted on 05/21/88 during safety injection conditions. Various parameters wer~ monitored and recorded for 180 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model
and plant variable points that verified the expected results .
There were no discrepancies noted during the test.
MSI10 LHSI PUMP IMPELLER DEGRADATION The LHSI Pump Impeller Degradation malfunction was conducted on 06/09/88 during a large break LOCA malfunction.
The malfunction was ramped from zero failure to full failure over a 30 second time frame to demonstrate the degradation feature. The malfunction was degraded to it's maximum severity. Various parameters were monitored and recorded to show flows and mass balances of the safety injection system.
The test ran for 120 seconds until stable conditions existed. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancies noted during the test .
ATTACHMENT 3 Page 82 of 87
MTU01 TURBINE TRIP The Turbine Trip malfunction was conducted on 09/14/88 at 100 % power, steady state conditions. Various parameters were monitored and recorded for 100 seconds until the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results.
There were no discrepancies noted during the test.
MTU04 FAILURE OF MANUAL TURBINE TRIP The Failure of Manual Turbine Trip malfunction was conducted on 06/09/88 at 100 % power, steady state conditions. Various parameters were monitored and recorded for 30 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data con~ists of model and plant variable points that verified the expected results. There were no* discrepancies noted during the test.
MTU13 FAILURE OF AUTOMATIC TURBINE RUN BACK The Failure of Automatic Turbine Run Back malfunction was conducted on 06/09/88 at 100 % power, steady state conditions. Various parameters were monitored and recorded for 120 seconds and the expected results were obtained.
Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There were no discrepancies noted during the test .
ATTACHMENT 3 Page 83 of 87
MWDOl DROPPED FUEL ASSY IN SPE~T FUEL PIT The Dropped Fuel Assy In Spent Fuel Pit malfunction*was conducted on 08/26/88 at 100 % power, steady state conditions. Various parameters were monitored and recorded for 60 seconds and the expected results were obtained. Data was collected in the form of computer printouts. This data consists of model and plant variable points that verified the expected results. There. were no discrepancies noted during the test.
MWD03 ACCIDENTAL RELEASE FROM RADIOACTIVE GAS The Accidental Release From Radioactive Gas malfunction was conducted on 09/14/88 at 100 % power, steady state conditions. Various parameters were monitored and recorded for 60 seconds and the expected results were obtained. Data was collected in the -form of computer printouts. This data consists of model and plant variable points that verified the expected results.
There were no discrepancies noted during the test .
~'"-,
ATTACHMENT 3 Page 84 of 87 VIRGINIA POWER SIMULATOR SUPPORT GROUP
SURRY UNIT 1 SIMULATOR UNIQUE TESTS RESULTS
ATTACHMENT 3 Page 85 of 87
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 revi~wed for impact. An SMR was generated to create a malfunction to reproduce this event.
A generic malfunction, MFW12, was developed and tested on 09/22/88 for 305 seconds to ensure the sequence of events matched as* much as posiible those which occurred in the plant. "C" Main Steam Trip Valve was failed closed to initiate the event in order to fully duplicate the event as it occurred in the station. There were no discrepancies noted during the tests.
TUBE RUPTURE A tube rupture event at North Anna generated a test review of malfunction MRC24. This test was conducted on 09/22/88 for 360 seconds. The results were compared to LER 87-017 and subsequent reports. The test results indicated good response in comparison to the North Anna event.
However, due to Sur~y plant design differences in the steam generator, the steam pressure response was different and was judged acceptable for the purpose of this test. No other discrepancies were noted during the test .
REACTOR COOLANT LOOP- STOP VALVE FAILURE On May 16, 1987, the "A" loop hot leg isolation valve (1-RC-MOV-1590) stem failed. The test report of 5 June 1987 was reviewed. The test was conducted on 09/22/88 for 600 seconds. The test results indicated good response. No other discrepancies were noted during the test .
ATTACHMENT 3 Page 86 of 87 VIRGINIA POWER SIMULATOR SUPPORT GROUP SURRY UNIT 1 SIMULATOR SURVEILLANCE TEST RESULTS
ATTACHMENT 3 Page 87 of 87
SURVEILLANCE TESTS The Periodic Tests listed below were conducted on the Surry 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.
The major discrepancy noted during the tests was the inability of the plant computer to support. all of the necessary *aspects of the tests. The plant computer is currently scheduled for upgrade by 02/28/89.
1-PT-6.0 Control Rod*~{sembly Partial Movement 1-PT-10.0 Reactor Coolant Leakage 1-PT-14.2 Main Steam Trip Valves and Main Steam Non-Return Valves 1-PT-14.3 CSD Testing of Blowdown Trip Valves 1-PT-15.1C Turbine Driven Auxiliary Feedwater Pump 1-PT-17.3 Containment Outside Recirculation Spray Pumps 1-PT-18.6 Monthly Testing of Safety related MOV's 1-PT-18.6A Quarterly Testing of Safety-Injection MOV's and HCV's 1-PT-18.6B Quarterly Testing of Misc. Containment Trip Valves 1-PT-18.6C CSD Testing of Charging and Safety Injection MOV's and Check Valves 1-PT-18.6D CSD Testing of MOV-1373 and MOV-1381 1-PT-19.1 RWST Chemical Addition Tank and Containment Spray System MOV's 1-PT-25.1 Quarterly Test of CW & SW System Valves 1-PT-25.2 Testing of Service Water Valves to Recirc. Spray Heat Exchangers 1-PT-26.1 Radiation Monitoring Equipment Check 1-PT-29.1 Turbine Inlet Valve Test 1-PT-30.2 RHR System MOV Cycling 1-PT-35.0 Reactor Power Calibration Using Feed Flow (P-250 problem) 1-PT-35.1 Reactor Power Calibration Using Feed Flow (Computer out of service) 1-PT-35.2 Reactor Power Calibration Using Steam Flow (P-250 problem) 1-PT-35.3 Reactor Power Calibration Using CALCALC Computer Program (P-250 problem) 1-PT-36 Instrument Surveillance
VIRGINIA POWER SIMULATOR SUPPORT GROUP SURRY UNIT 1 SIMULATOR ATTACHMENT 4 SIMULATOR TEST SCHEDULE I
ATTACHMENT 4 Page 1 OF 5
SIMULATOR PERFORMANCE TEST SCHEDULE The performance test schedule to be conducted over the next four years will consist of the following test&. The Transient Performance Tests of ANS-3.5-1985.
Appendix B section B.2.2 will be conducted annually.
November 1988 - October 1989 Integrated Tests Plant Heatup from Cold Shutdown to Intermediate Shutdown.
Plant Heatup from Intermediate Shutdown to Hot Shutdown.
Malfunction Tests MCA01 INSTRUMENT AIR LEAK MCA02 LOSS OF CONTAINMENT INSTRUMENT AIR COMPRESSOR MCA04 CONTAINMENT INSTRUMENT AIR LEAK MCAOB INSTRUMENT AIR COMPRESSOR *ovERLOAD TRIP MCC01 COMPONENT COOLING HEAT EXCHANGER LEAK MCC03 OVERLOAD TRIP OF COMPONENT COOLING WATER PUMP MCC04 LOSS OF COMPONENT COOLING TO NON-REGENERATIVE HEAT
MCCOS MCHO 1 MCH02 MCH03 MCHOS MCH06 EXCHANGER RCP THERMAL BARRIER LEAK ISOLABLE LETDOWN LINE LEAK IN CONTAINMENT ISOLABLE LETDOWN LINE OUTSIDE CONTAINMENT ISOLABLE CHARGING LINE LEAK OUTSIDE CONTAINMENT LOSS OF CHARGING PUMP NON-REGENATIVE HEAT EXCHANGER OUTLET TEMPERATURE
.CONTROLLER FAILURE MCH11 SEAL WATER INJECTION PRESSURE TRANSMITTER FAILURE MCH12 RCP SEAL WATER RETURN HEADER TEMPERATURE MCH13 TUBE RUPTURE IN THE NON-REGENERATIVE HEAT EXCHANGER MCH17 SEAL WATER RETURN FILTER CLOGS MCH19 VCT LEVEL CONTROLLER FAILURE MCH20 CORE ACTIV~TY RELEASE MCH21 VCT LEVEL TRANSMITTER FAILURE MCH22 VOLUME CONTROL TANK PRESSURE TRANSMITTER FAILURE MCH23 VOLUME CONTROL TANK TEMPERATURE TRANSMITTER FAILURE MCH24 BORIC ACID FLOW CONTROLLER 113 FAILURE MCH25 PRIMARY WATER FLOW CONTROLLER 114 FAILURE MCH28 FAILURE OF CHARGING FLOW CONTROLLER MCH29 FAILURE OF CHARGING FLOW TRANSMITTER MCH31 REGENERATIVE HEAT EXCHANGER OUTLET TEMPERATURE TRANSMITTER CH-TE-123 FAILS MCH35 LOW PRESSURE LETDOWN FLOW TRANSMITTER FAILURE MCH36 LETDOWN PRESSURE CONTROLLER (PC-1145) FAILURE MCH37 LOW PRESSURE LETDOWN LINE PRESSURE TRANSMITTER 145 FAILURE
ATTACHMENT 4 Page 2 OF 5
MCH38 MCH39 REGENERATIVE HEAT EXCHANGER LETDOWN TEMPERATURE TRANSMITTER FAILURE LETDOWN LINE RELIEF LINE TEMPERATURE TRANSMITTER FAILURE MCH40 LOW PRESSURE LETDOWN LINE TEMPERATURE TRANSMITTER FAILURE MCH41 NON-REGENERATIVE HEAT EXCHANGER OUTLET TEMPERATURE TRANSMITTER FAILURE MCN01 LOSS OF MAIN CONDENSATE PUMP MCN02 CONDENSER AIR IN LEAKAGE.
McN03 HOTWELL LEVEL CONTROLLER FAILURE MCNOS CONDENSATE LINE LEAK BEFORE FCV-CN-107 MCN08 LOSS OF AIR E~ECTOR LOOP SEAL MELO 1 LOSS OF ALL OFFSITE POWER MEL02 MAIN GENERATOR TRIP November *1999 - October 1990 Integrated.Tests Unit start up operations (Hot Shutdown to full power).
Malfunction Tests MEL07 LOSS OF 4160V STATION BUS MEL08 LOSS OF SCREENWELL TRANSFORMER MEL09 LOSS OF EMERGENCY DIESEL GENERATOR MEL12 LOSS OF 480V EMERGENCY SWITCHGEAR.
MEL13 LOSS OF 480V EMERGENCY MOTOR CONTROL CENTER MELl4 LOSS OF SEMI-VITAL BUS MEL17 LOSS OF 125V D.C. BUS MEL18 LOSS OF. 480V STATION SWITCHGEAR MEL19 LOSS OF 480V MOTOR.CONTROL CENTER MEL20 LOSS OF AC VITAL BUS MEL21 LOSS OF 4160V EMERGENCY BUS MFW01 MAIN FEEDWATER PUMP RECIRC VALVE FAILS OPEN MFW02 MAIN FEEDWATER REGULATING VALVE FAILS CLOSED MFW04 MAIN FEED PUMP LOW LUBE OIL PRESSURE MFWOS MAIN FEEDWATER BREAK UPSTREAM OF FLOW TRANSMITTER MFW07 AUX FEED PUMPS FW-P-3A/B TRIP : OVERCURRENT MFW08 AUX FEED PUMP TURBINE WON'T STOP; PCV-MS-102B OPEN MFW10 AUXILIARY FEED PUMP CHECK VALVE OPEN MFW1 *2 MAIN FEED PUMP SUCTION LINE BREAK MFW13 STEAM GENERATOR LEVEL TRANSMITTER FAILURE (0-100%)
MFW14
AUXILIARY FEEDWATER BREAK DOWNSTREAM OF FLOW TRANSMITTER AND 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 STEAM GEN MAIN FEED FLOW TRANSMITTER FAILURE MFW19 STEAM GEN MAIN FEED FLOW CONTROLLER FAILURE MFW20 STEAM .GEN WIDE RANGE LEVEL TRANSMITTER*FAILURE
ATTACHMENT 4
Page 3 OF 5
MFW21 MFW22 MFW23 MMI03 MMI04 STEAN GEN AUX FEED FLOW TRANSMITTER FAILURE STEAM GEN MAIN FEED HEADER PRESSURE TRANSMITTER FAILURE TOTAL LOSS OF FEEDWATER GRADUAL INCREASE IN CONTAINMENT PRESSURE FAILURE OF REACTOR TRIP BUTTON MMS01 RUPTURE OF MAIN STEAM LINE AT HEADER MMS03 RUPTURE OF MAIN STEAM LINE UPSTREAM OF FLOW ELEMENT MMS04 RUPTURE OF MAIN STEAM LINE BEFORE THE TRIP VALVE MMS06 MAIN STEAM TRIP VALVE FAILS AS IS MMS07 MAIN STEAM SAFETY VALVE FAILS OPEN MMS08 STEAM GEN STEAM FLOW TRANSMITTER FAILURE MMS09 MAIN STEAM TRIP VALVE FAILS SHUT MMS10 FAILURE OF AUTO STEAM DUMP AS IS MMS11 MAIN STEAM HEADER PRESSURE TRANSMITTER FAILURE Novembe~ 1990 - October 1991 Integrated Tests Decreasing power from 100% power level to Hot Shutdown conditions.
Computer Real Time Test.
Malfunction Tests
MMS13 MMS14 MMS15 MNIO 1 MNI02 MNI03 STEAM GEN PRESSURE TRANSMITTER FAILURE TURBINE FIRST STAGE PRESSURE TRANSMITTER FAILURE SG PORV CONTROLLER FAILURE SOURCE RANGE CHANNEL FAILURE SOURCE RANGE DETECTOR FAILURE (DISCRIMINATOR ERROR)
INTERMEDIATE RANGE CHANNEL UNDERCOMPENSATION MNI04 INTERMEDIATE RANGE CHANNEL OVERCOMPENSATION MNI05 INTERMEDIATE RANGE CHANNEL FAILURE MNI06 FAILURE OF IR TO ALLOW SR BLOCK MNI07 LOSS 'OF INSTRUMENT POWER TO POWER RANGE CHANNEL MNI08 POWER RANGE CHANNEL UPPER DETECTOR FAILURE MNI09 POWER RANGE CHANNEL LOWER DETECTOR FAILURE MNI10 POWER RANGE CHANNEL FAILS MRC01 REACTOR COOLANT SYSTEM COLD LEG PIPE RUPTURE MRC02 REACTOR COOLANT SYSTEM HOT LEG PIPE RUPTURE MRC03 REACTOR COOLANT SYSTEM SUCTION LEG PIPE RUPTURE MRC04 REACTOR COOLANT SYSTEM NONISOLABLE LEAK MRC05 RCP OVERCURRENT TRIP MRC07 RTD FAILS HIGH IN THE HOT LEG (PROTECTION)
MRC08 RTD FAILS HIGH IN THE COLD LEG (CONTROL)
MRC11 RTD FAILURE IN COLD LEG (PROTECTION)
MRC14 FAILURE OF RCP SEAL #3 MRC15 PRZR PRESSURE CONTROLLERS FAILURE MRC16 PRZR REL/SFTY VV LINE TEMPERATURE TRANSMITTER FAILURE MRC17 PRESSURIZER LEVEL CONTROL FAILURE MRC20 BOTH PRZR SPRAY VALVES FAIL SHUT
ATTACHMENT 4 Page 4 OF 5
MRC21 MRC22 MRC24 MRC25 MRC26 PRESSURIZER SAFETY VALVE FAILS OPEN PRZR SPRAY VALVE FAILS OPEN STEAM GENERATOR TUBE RUPTURE PRESSURIZER HEATERS GROUP FAIL ON RCP SHAFT SHEARS MRC30 LOSS OF SEAL INJECTION FLOW TO RCP MRC31 REACTOR COOLANT LOOP FLOW TRANSMITTER FAILURE MRC34 RCS WIDE AND NARROW RANGE PRESSURE TRANSMITTER FAILURE MRC37 PRESSURIZER RELIEF TANK PRESSURE TRANSMITTER FAILURE MRC38 LOSS OF COMPONENT COOLING WATER TO RCP MRC40 PRESSURIZER PORV LEAKAGE MRC42 PRESSURIZER TEMPERATURE TRANSMITTER FAILURE MRC45 PRESSURIZER RELIEF TANK TEMPERATURE TRANSMITTER FAILURE MRC46 REACTOR VESSEL LEAKOFF TEMPERATURE TRANSMITTER FAILURE MRC48 PRESSURIZER PRESSURE TRANSMITTER FAILURE November 1991 - October 1992 Integrated Tests Unit cooldown from Hot Shutdown to Intermediate Shutdown.
Unit cooldown from Intermediate Shutdown to Cold Shutdown .
Malfunction Tests MRC49 PRESSURIZER LEVEL TRANSMITTER FAILURE MRCSO PRESSURIZER RELIEF TANK LEVEL TRANSMITTER FAILURE MRDOl CONTINUOUS ROD WITHDRAWAL; MANUAL OR AUTO MRD02 CONTINUOUS ROD INSERTION MANUAL OR AUTO MRD03 LOGIC FAILURE CAUSING BANK A AND C TO MOVE AT THE SAME TIME MRD04 AUTO AND MANUAL ROD CONTROL INOPERABLE MRDOS CONTROL BANKS IN SPEED FAIL TO 72 SPM MRD06 CONTROL BANKS IN SPEED FAIL TO 8 SPM MRD07 CONTROL BANKS OUT SPEED FAIL TO 72 SPM MRD08 CONTROL BANKS OUT SPEED FAIL TO 8 SPM MRD09 CONTROL BANK MOVES OUT WHEN IN DEMANDED MRDlO CONTROL BANK MOVES IN WHEN OUT DEMANDED MRD12 DROPPED CONTROL ROD MRD13 EJECTED CONTROL ROD MRD15 RX TRIP BREAKERS OPEN DUE TO UV COIL FAILURE MRD16 INDIVIDUAL ROD POSITION INDICATION FAIL MRD18 FAIL OF AUTO TRIP TO SCRAM RX MRD19 FAILURE OF ALL ROD STOPS TO BLOCK ROD MOVEMENT MRD20 STUCK ROD MRHO 1 RESIDUAL HEAT REMOVAL SYSTEM LEAK MRH02 LOSS OF RESIDUAL HEAT REMOVAL PUMP MRH04. HCV-1758 CONTROLLER OUTPUT FAILS HIGH MRHOS RHR FLOW CONTROLLER FC-1605 FAILS HIGH
ATTACHMENT 4 Page 5 OF 5
MRH06 MRM01 MRM02 RELIEF VALVE FAILS OPEN ON RESIDUAL HEAT REMOVAL SYSTEM AREA RADIATION MONITOR FAILS PROCESS RADIATION MONITOR FAILURE.
MRS06 LOSS OF OUTSIDE RECIRC SPRAY PUMP ON START MRS07 LOSS OF INSIDE RECIRC SPRAY PUMP ON START MRS08 LOSS OF CONTAINMENT SPRAY PUMP MSI03 SAFETY INJECTION HOT LEG FLOW TRANSMITTER FAILURE MSI04 SAFETY INJECTION TOTAL FLOW TRANSMITTER FAILURE MSIOS LHSI PUMP FLOW TRANSMITTER FAILURE MSI06 SAFETY INJECTION COLD LEG FLOW TRANSMITTER FAILURE MSI07 SAFETY INJECTION ACCUMULATOR LEVEL TRANSMITTER FAILURE MSI08 FAILURE OF SAFETY INJECTION RESET TIMER MSI10 LOW HEAD SAFETY INJECTION PUMP IMPELLER DEGRADATION MTU01 TURBINE TRIP DUE TO .SOLENOID FAILURE MTU04 FAILURE OF MANUAL TURBINE TRIP
. MTU1 3 FAILURE OF AUTOMATIC TURBINE RUNBACK MWD01 DROPPED SPENT FUEL ASSEMBLY IN THE SPENT FUEL PIT MWD03 ACCIDENTAL RELEASE OF RADIOACTIVE GAS
VIRGINIA POWER
. SIMULATOR SUPPORT GROUP SURRY UNIT 1 SIMULATOR
ATTACHMENT 5 PHYSICAL FIDELITY REPORT
ATTACHMENT 5 Page 1 of 58
SURRY PHYSICAL FIDELITY COMPARISON REPORT APRIL 1988 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 April 1988.
A prioritized corrective maintenance program has been initiated and work is being accomplished based upon an item by item evaluation and parts availability. This report includes identification of all currently outstanding Simulator Control Panel discrepancies; indicating work to be performed based on training impact, cost effectiveness, and other comments as appropriate. Generic Control Room/Panel differences have been identified as necessary.
The Plant Control Room photos are arranged panel by- panel and sequentially numbered. 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 ~ssociated Photo# and lists each discrepancy of
the simulator from the plant .
This report is organized in two 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.
~riority 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; ie, software, plant ops, etc., generally within 90-120 days.
3. Minimal training impact correctable as part of the Control Room Design Review (CRDR) or system upgrade.
These items are periodically re-evaluated for training impact/cost effectiveness .
ATTACHMENT 5 Page 2 of 58
Status codes indicate:
N/S N/A Not started Not applicable w Work in progress Description indicates:
Item, name, location or identifier of Simulator discrepancy or difference from plant control rdom with photo reference where applicable. ie. (V2-175 = Vertical Board 2- photo
/t 1 7 5 )
Panel codes used: BB1 - BENCH BOARD :/t BB2 - BENCH BOARD :/t 2 V1 - VERTICAL BOARD :/t V2 - VERTICAL BOARD :/t 2 LW - LIQUID WASTE PANEL BR - BORON RECOVERY PANEL RM - RADIATION MONITOR PANEL DJ - DIESEL GEN "J" PANEL DH - DIESEL GEN "H" PANEL TS - TURBINE SUPERVISORY PANEL
IC AMS CHR ASD CC INCORE PANEL ACCOUSTICAL MONITORING SYSTEM (VALVE MONITORING) PANEL
- CONTAINMENT HIGH RANGE RADIATION MONITORING (VICTOREEN) PANEL
- AUXILIARY SHUT DOWN PANEL.
- COMPONENT COOLING WALL MOUNTED PANELS BC - BEARING COOLING PANEL CW - CIRCULATING WATER PANEL FP - .FIRE PROTECTION PANEL SY - SWITCH YARD PANEL SS - SHIFT SUPERVISOR CONSOLE PD - PRODAC CONSOLE CR - ANY OTHER CONTROL ROOM EQUIPMENT Comment indicates:
Action, applicability, impact, due date, etc; information relative to resolution or disposition of the indicated items.
The list that follows will give the photo numbers that cover a designated panel .
ATTA_CHMENT 5 Page 3 of 58
PHOTO NO PANEL SEQUENCE FOR PHOTOS PANEL 1-18 Radiation Monitoring 19-33 Waste Disposal 34-38 High Range Gaseous Effluent RAP 3 9 Ambient Temperature Monitoring 42-64 BOron Recovery 65-83 Incore 84-103 Nuclear Instrumentation 104-109 Containment High Range Radiation Monitor 110-117 Intake Structure 118-121 Gas Turbine* Generators 122-126 Emergency Diesel Generator No.1 127-132 Switch Yard Status 133-138 Load Frequency and Heat Tracing Monitor for Unit 1 and 2 139-144 Heating and Ventilation 145-151 Emergency Diesel Generator No.3 152-158 Turbine Supervisory 159-162 RCP Vibration and Flood Control Monitor 163-164 Steam Generator Chemistry 165-168 Control Room View 169-174 Post Accident Moni to_r 175-2{3 Bench Board 1
_215-265 Bench Board 2 266-280 Vertical Boards and Auxiliary Ventilation Annunciator Panels 281-324 Vertical Board 1 325-386 Vertical Board 2 387-403 Auxiliary Ventilation 404-410 Supervisors Console 411-425 *Auxiliary Shutdown
ATTACHMENT 5 Page 4 of 58
1988 PHYSICAL FIDELITY The following list of discrepancies were found to be no impact o~
training in the 1987 report. Therefore these discrepancies will.
not be covered in this report.
ANNUNCIATOR WINDOWS
1) Windows with different spacing, but they read the same.
2) Windows with different letter sizes.
PANELS
1) Panels that are made different.
2) Panels without molding or different molding.
3) Paint for system separation that is laid out a little different, but includes all of the proper components.
4) Drawer handles that are a different size or style.
RECORDERS
1) With or without Logo.
2) That are a slightly different style.
INTEGRATORS OR COUNTERS
1) With slightly different reset buttons.
2) With different color letters or wheels.
ELECTROSWITCH LABELS
1) With wording that is straight across instead of at an angle.
SETPOINT STATIONS
1) With different color trim or cover plate .
ATTACHMENT 5 Page 5 of 58
METERS 1) 2)
With bolder legends or scales.
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 .
ATTACHMENT 5 Page 6 of *59
PRIORITY STATUS ITEM/DESCRIPTION GENERIC COMMENT COMMENTS NEW STYLE OT2 SWITCHES WERE INSTALLED VERSUS OLD STYLE IN 258 LOCATIONS, BECAUSE THE OLD STYLE IS*
NOT AVAILABLE FOR INSTALLATION.
RAD MON PNL PHOTO# 1 2 1. ALL ANNUNCIATOR Due 12/88 WINDOWS ARE LAID OUT DIFFERENT. THE LETTERS SHOULD BE LARGER AND THE WORDS SPACED DIFFERENT. THE WINDOWS ON THE SIMULATOR MATCH THE ESK WINDOW LAYOUT .
THE PLANT WINDOWS READ THE SAME BUT THEY ARE ABBREVIATED DIFFERENT.
PHOTO# 5 Due 12/88 2 w 1. LIGHT LENS CAP SHOULD BE GREEN INSTEAD OF RED Parts ordered FOR PUMP ON/OFF FILTER FEED ON RC-GW-101.
2 w 2. LIGHT LENS CAP Due 12/88 SHOULD BE GREEN Parts ordered INSTEAD OF RED FOR PUMP ON/OFF FILTER FEED ON RC-VG-103.
PHOTO# 6 2 w 1. SELECTOR SWITCH FOR Due 12/88 RI-CC106 IS A Parts ordered DIFFERENT STYLE.
PHOTO# 7 2 w 1. INDICATING LIGHT FOR Due 12/88 1-SW-P-6A IS Parts ordered MISSING.
ATTACHMENT 5 Page 7 of 58
PRIORITY STATUS RAD MON PNL ITEMLDESCRIPTION COMMENTS PHOTO# 7 2 w 2. INDICATING LIGHT FOR Due 12/88 1-SW-P-6B IS Parts ordered MISSING.
2 w 3. INDICATING LIGHT FOR Due 12/88 1-SW-P-6C IS MISSING. Parts ordered 2 w 4. INDICATING LIGHT FOR Due 12/88 1-SW-P-6D IS MISSING. Parts ordered PHOTO# 1 4 2 w 1. SELECTOR SWITCH FOR Due 12/88 RI-RMS-163 IS A Parts ordered DIFFERENT STYLE.
PHOTO# 1 6 2 N/S 1. FILTER FEED PANEL IN Due 12/88 THE PLANT HAS BEEN REPLACED WITH A NEW STYLE PANEL.
2 w 2. SELECTOR SWITCH FOR Due 12/88 RI-RMS-159 IS A Parts ordered DIFFERENT STYLE.
2 w 3. SELECTOR SWITCH FOR Due 12/88 RI-RMS-160 IS A Parts ordered DIFFERENT STYLE.
PHOTO# 1 7 2 w 1. LIGHT LENS CAP FOR Due 12/88 RC-VG-109 SHOULD BE Parts ordered GREEN INSTEAD OF RED.
PHOTO# 1 8 N/A N/A 1. TV MONITOR FOR THE CONTROL ROOM ANNEX IS MISSING - ON HOLD FOR FUTHER EVALUATION IN 1989.
NLS 2. SONALERT BRACKET NEEDS TO BE PAINTED.
Due 10/88
ATTACHMENT 5 .
Page 8*of 58
PRIORITY STA'l'US RAD MON PNL ITEM/DESCRIPTION COMMENTS WASTE DISPOSAL PANEL PHOTO# 19 w 1~ SOUND POWERED PHONE Parts*ordered JACK IS MISSING. ' 08/05/88 THE JACK IS UNDER Due 10/88 THE CATALYTIC RECOMBINER TEMP~
RECORDER.
PHOTO# 21
_._1_ w 1. INDICATOR FOR LI-529 Due 12/88
. IS MISSING. THE* Parts* ordered
. HOLE HAS NOT BEEN CUT YET .. THE SCALE SHOULD BE 0-100% .AND THE MARGIN SHOULD READ: PERCENT
2 w 2. INDICATOR FOR TI-LW-112 IS MISSING THE SCALE IS 0-200 DEGREES FAHRENHEIT Due 12/88 Systematic upgrade Parts ordered*
AND THE MARGIN SHOULD READ LW EFFLUENT.
PHOTO# 25 2 w 1. INDICATOR Due*12/88 PI-GW-102A SCALE Systematic upgrade IS DIFFERENT. THE Parts ordered SCALE SHOULD. BE 0-225 INSTEAD OF 0.,..150.
2 w 2. . INDICATOR Due 12/88 PI-GW-102B SCALE Systematic upgrade IS DIFFERENT. THE Parts ordered SCALE SHOULD BE 0-225 INSTEAD OF 0-150 .
ATTACHMENT 5 Page 9 of 58
PRIORITY STATUS WASTE DISPOSAL PANEL ITEM[DESCRIPTION COMMENTS PHOTO# 25 2 w 3. INDICATOR Due 12/88 PI-GW-102C SCALE Systematic upgrade IS DIFFERENT. THE Parts ordered SCALE SHOULD BE 0-225 INSTEAD OF 0-150.
2 w
--- 4* INDICATOR Due 12/88 PI-GW-102D SCALE Systematic upgrade IS DIFFERENT. THE Parts ordered SCALE SHOULD BE 0-225 INSTEAD OF 0-150.
PHOTO# 29 2 w 1. SWITCH LW-P-SA IS A Due 12/88 DIFFERENT TYPE. THE Systematic upgrade SWITCH SHOULD BE 3 Parts ordered 3 POSITION, WITH SPRING RETURN TO CENTER.
2 w 2. SWITCH LW-P-5B IS Due 12/88 A DIFFERENT TYPE. Systematic upgrade THE SWITCH SHOULD Parts ordered BE A 3 POSITION WITH SPRING RETURN TO CENTER.
PHOTO# 31 2 w 1. SWITCH FCV-GW-160 Due 12/88 IS DIFFERENT. THE Systematic upgrade SWITCH SHOULD BE A Parts ordered 2 POSITION MAINTAINED.
2 w 2. SWITCH FCV-GW-260 IS Due 12/88 DIFFERENT. THE SWITCH Systematic upgrade SHOULD BE A 2 Parts ordered POSITION MAINTAINED.
2 w 3. SWITCH RING LABEL Due 12/88 FOR HCV-GW-106 IS Systematic upgrade DIFFERENT. THE Parts ordered LABEL SHOULD READ:
CLOSE/\OPEN .
ATTACHMENT 5 Page 1o*ot 58
PRIORITY STATUS WASTE DISPOSAL PANEL ITEM/DESCRIPTION COMMENTS PHOTO # 31 2 w 4. ( W) OT2 TWO Due 12/88 POSITION Parts ordered MAINTAINED SWITCH HAS BEEN INSTALLED BETWEEN FCV-GW-101 AND RL-P-1B.
2 w 5. SWITCH RL-P-1A IS Due 12/88 DIFFERENT. THE SWITCH Systematic,upgrade SHOULD BE A 3 Parts ordered POSITION SPRING RETURN TO CENTER.
PHOTO# 32 2 w 1. SWITCH 1-LW-P-100A Due 12/88 HAS BEEN CHANGED Systematic upgrade IN THE PLANT: THE Parts ordered NEW SWITCH IS A 3 POSITION MAINTAINED WITH OCTOGONAL SHAPED RETAINING RING.
2 w 2. SWITCH 1-LW-P-100B Due 12/88 HAS BEEN CHANGED Systematic upgrade IN THE PLANT. THE Parts ordered NEW SWITCH IS A 3 POSITION MAINTAINED WITH OCTAGONAL SHAPED RETAINING RING.
2 w 3. SWITCH HCV-LW-511 Due 12/88 HAS BEEN CHANGED Systematic upgrade IN THE PLANT. THE Parts ordered NEW SWITCH HAS A OCTAGONAL SHAPED RETAINING RING AND A PISTOL GRIP HANDLE .
ATTACHMENT 5.
Page 11 of 58
PRIORITY STATUS WASTE DISPOSAL PANEL ITEM/DESCRIPTION COMMENTS PHOTO# 32 w 4. RED AND GREEN Due 12/88 LIGHTS HAVE BEEN Parts ordered ADDED AT THE PLANT BETWEEN SWITCHES 1-LW-P-100A AND B.
THE LIGHTS ARE FOR FCV-LW-525.
PHOTO# 33 w 1. A SWITCH FOR LW~P-4 Due 12/88 HAS BEEN INSTALLED AT Systematic upgrade THE PLANT. THE NEW Parts ordered SWITCH IS ( W ) OT2 3 POSITION MAINTAINED.
w 2. RED AND GREEN ( W ) Due 12/88 MINI LIGHTS NEEDS TO Systematic upgrade
2 w 3.
BE INSTALLED FOR SWITCH LW-P-4.
SWITCH RING LABEL NEEDS TO BE INSTALLED FOR SWITCH LW-P-4.
THE RING LABEL Parts ordered Due 12/88 Systematic upgrade Parts ordered SHOULD READ:
HAND/OFF\AUTO 2 w 4. SWITCH LW-P-8 HAS Due 12/88*
BEEN CHANGED IN THE Systematic upgrade PLANT. THE NEW Parts ordered SWITCH IS A ( W ) OT2 3 POSITION MAINTAINED.
2 w 5. A SWITCH HAS BEEN Due 12/88 INSTALLED FOR Systematic upgrade 1-FVC-LW-160 AT Parts ordered THE PLANT. THE NEW SWITCH IS A ( W ) OT2 2 POSITION MAINTAINED.
2 w 6. RED AND GREEN ( W ) Due 12/88 MINI LIGHTS NEED-TO Systematic upgrade BE INSTALLED for Parts ordered 1-FCV-LW-160 .
ATTACHMENT 5 Page 12 of 58
PRIORITY STATUS WASTE DISPOSAL PANEL ITEM/DESCRIPTION COMMENTS PHOTO.# 33 2 w 7. SWITCH RING LABEL FOR Due 12/88 1-FCV-LW-160 NEEDS TO Systematic upgrade BE INSTALLED. THE RING Parts ordered
LABEL SHOULD READ:
CLOSE/\OPEN HI RAD EFFLUENT PANEL PRIORITY. STATUS ITEM/DESCRIPTION COMMENTS PHOTO# 34 N/A N/A 1. THE PANEL IS A DIFFERENT No training impact, STYLE.
N/A N/A 2.* A VALIDYNE MUX IS No training impact MISSING AT THE BOTTOM OF THE PANEL.
HI RAD EFFLUENT *MON PHOTO# 35 2 w 1. RECORDER CHANNEL LABEL Due 12/88 IS MISSING FOR Parts ordered RR-RMS-132 .
2 w . 2. RECORDER CHANNEL LABEL Due 12/88 IS MISSING FOR Parts ordered RR-RMS-133.
PHOTO# 38 2 w 1. INDICATING LIGHT FOR Due 12/88 EFFLUENT MON .LO TEMP Systematic upgrade IS MIS.SING. Parts ordered 2 w 2; PB SWITCH FDR TEST Due 12/88 SHOULD HAVE AN OCTOGONAL Systematic upgrade SHAPED RETAINING RING. Parts ordered 2 w 3. SWITCH RING LABEL FOR TEST Due 12/88 IS BLANK AND IT IS A Systematic upgrade DIFFERENT STYLE. THE RING Parts ordered LABEL SHOULD READ: TEST
ATTACHMENT 5 Page 13 of 58
PRIORITY STATUS_
HI RAD EFFLUENT MON ITEM[DESCRIPTION COMMENTS
PHOTO # 38 2 w 4. SWITCH RING LABEL FOR ACK Due 12/88 IS BLANK, THE WRONG. COLOR Systematic upgrade AND IT IS A DIFFERENT Parts ordered STYLE. THE RING LABEL SHOULD BE RED IN COLOR AND READ: ACK 2 w 5. SWITCH RING LABEL FOR Due 12/88 SILENCE IS BLANK, THE Systematic upgrade WRONG COLOR AND IT IS Parts ordered A DIFFERENT STYLE. THE RING LABEL SHOULD BE RED IN COLOR AND READ:
SILENCE 2 N[S 6. THE TEST P.B. SWITCH IS Due 11/88 IN THE WRONG LOCATION.
IT SHOULD BE MOVED 2.5 INCHES TO THE LEFT.
2 N[S 7* THE ACK P.B. SWITCH IS Due 11/88 IN THE WRONG LOCATION.
IT SHOULD BE MOVED 2.5 INCHES TO THE LEFT.
2 N[S 8. THE SILENCE P.B. SWITCH Due 11/88 IS IN THE WRONG LOCATION.
IT SHOULD BE MOVED 2.5 INCHES TO THE LEFT.
N[S 9. LAMACOID LABEL FOR Due 11/88 FI-MS-200 IS IN THE Systematic upgrade WRONG LOCATION. IT SHOULD BE LOCATED BELOW THE METER.
N[S 1 0. COUNTER FTO-MS-200 IS Due 11/88 MOUNTED TOO CLOSE TO Systematic upgrade FI-MS-200. THIS IS WHY THE LABEL WILL NOT FIT UNDER THE METER.
N[S
11 . LAMACOID LABEL FO~ Due 11/88 FI-MS-100 IS IN THE Systematic upgrade WRONG LOCATION IT SHOULD BE LOCATED BELOW THE METER.
ATTACHMENT 5 I
Page 14 of 58 I
I i
AMB TEMP MON PANEL PRIORITY STATUS ITEM/DESCRIPTION *COMMENTS PHOTO# 38 N/S. 12. COUNTER FTO-MS-100 IS Due 11/88 MOUNTED TOO CLOSE TO Systematic upgrade FI-MS-100. THIS IS WHY THE LABEL WILL NOT FIT UNDER THE METER.
PHOTO# 41 w 1. BLANK PLATE FOR RONAN ANN. Due 12/88 WINDOW 2~5 IS MISSING ON Parts ordered TRAIN B.
BO:RON-REC PANEL PHOTO*# 42
1. SPARE HAGAN RECORDER No training impact LOCATED NEXT TO ANN. PNL
1- w 2.
IS NOT INSTALLED. THE PLANT DOES NOT USE THIS RECORDER, BUT IT IS STILL THERE.
SOUND POWERED PHONE JACK UNDER THE L & N RECORDER-Due 10/88 Parts ordered
.IS MISSING. 08/05/88 -
PHOTO# 46 2 1. RtD AND GREEN LIGHTS AND Due 10/88 LABEL FOR 1~BR-P-1A SHOULD BE MOVED DOWN
- 1 . 5 INCHES.
2 2. RED AND GREEN LIGHTS AND .Due 10/88 LABEL FOR 1-BR-P-1B SHOULD BE MOVED DOWN 2 INCHES .
ATTACHMENT 5 Page 15 of 58
PRIORITY STATUS BORON REC PANEL ITEM/DESCRIPTION COMMENTS PHOTO# 47 2 N/S 1. SWITCH BR-P-7A HAS A Due 12/88 DIFFERENT STYLE 4 POSITION MAINTAINED SWITCH OPERATOR.
2 N/S 2. SWITCH BR-P-7B HAS A Due 12/88 DIFFERENT STYLE 4 POSITION MAINTAINED SWITCH OPERATOR.
2 N/S 3. SWITCH BR-C-1A HAS A Due 12/88 DIFFERENT STYLE 4 POSITION MAINTAINED SWITCH OPERATOR. IT APPEARS TO BE AN ALLEN BRADLY SWITCH.
2 N/S 4. SWITCH BR-C-1B HAS A Due 12/88
DIFFERENT STYLE 4 POSITION MAINTAINED SWITCH OPERATOR.
APPEARS TO BE AN IT ALLEN BRADLY SWITCH.
PHOTO# 48 2 N/S 1. PRINTED FLOW DIAGRAM Due 12/88 SHOULD BE 11448-FM-79A Hold for evaluation INSTEAD OF 79B. may be a difference in drawing revision level PHOTO# 53 2 N/S.
1 . SWITCH BR-P-4A HAS A Due 12/88 DIFFERENT STYLE 4 POSITION MAINTAINED SWITCH OPERATOR. IT.
APPEARS TO BE AN ALLEN BRADLEY SWITCH.
2 N/S 2. SWITCH BR-P-4B HAS A Due 12/88 DIFFERENT STYLE 4 POSITION MAINTAINED SWITCH OPERATOR. IT APPEARS TO BE AN ALLEN BRADLEY SWITCH.
ATTACHMENT 5 Page 16 of 58
PRIORITY STATUS BORON REC PANEL ITEM/DESCRIPTION COMMENTS PHOTO :/t 54 2 1. RECORDER TR-BR~120 IN Due 12/88 THE PLANT HAS BEEN Systematic upgrade REPLACED WITH AN LAND N RECORDER. THE SIMULATOR STILL HAS A HONEYWELL.
PHOTO :/t 59 2 1. SWITCH WITH RED AND GREEN Due 12-/88 LIGHTS ARE MISSING FOR Systematic upgrade HCV-BR-112-B. THE SWITCH Parts ordered IS ( W ) 2 POSITION MAINTAINED, LIGHTS ARE
( W ) MINI-. THE SWITCH RING LABEL SHOULD READ:
CLOSE - OPEN 2 w 2. SWITCH FOR PCV-BR-1 IS Due 12/88
MISSING. THE SWITCH IS Systematic upgrade
( W ) 2 POSITION Parts ordered MAINTAINED. THE SWITCH RING LABEL SHOULD READ:
OPEN/ \ CLOSE PHOTO :/t 62 2 w 1. METER PI-BR-109B HAS THE Due 12/88 WRONG SCALE. THE SCALE Systematic upgrade SHOULD READ: 0-45 PSIA Parts ordered INCORE PANEL PHOTO :/t 66 2 1. A DETECTOR POSITION Due 12/88 DISPLAY HAS BEEN CHANGED IN THE PLANT. THE DISPLAY IS NOW A LCD AND NOT NIXIE TUBE.
PHOTO# 67
1. PANEL LOGO SHOULD BE Due 10/88 PAINTED OVER .
ATTACHMENT 5 Page 17 of 58
PRIORITY STATUS INCORE PANEL ITEMLDESCRIPTION COMMENTS PHOTO :/t 68 2 NLS 1. B DETECTOR POSITION Due 12/88 DISPLAY HAS BEEN CHANGED
. IN THE PLANT. THE DISPLAY IS NOW A LCD AND NOT NIXIE TUBE.
PHOTO :/t 69 NLs- 1. PANEL LOGO SHOULD BE Due 10/88 PAINTED OVER.
PHOTO :/t 70 w 1. SOUND POWERED PHONE JACK Due 10/88
-IS MISSING. Parts ordered 08/05/88 2 NLS 2. RECORDER IS MISSING Due 12/88 INKING SYSTEM.
PHOTO :/t 71 NLA NLA 1. FUEL BLDG TELEVISION SURVEILLANCE SYS PANEL On hold for IS MISSING. THIS PANEL futher evaluation IS INSTALLED IN PLACE in 1989 OF THE PICOAMPERE SOURCE PANEL. THE NEW PANEL TAKES UP .HALF THE SPACE, THEREFORE, A BLANK PLATE WAS INSTALLED TO COVER THE LEFTOVER SPACE.
2 w 2. LAMACOID LABEL MISSING Due 11/88 FOR FUEL BLDG TELEVISION Label ordered SURVEILLANCE SYS. 07/15/88 PHOTO :/t 73
. NLS 1. PANEL LOGO SHOULD BE Due 10/88 PAINTED OVER .
ATTACHMENT 5 Page 18 of 58
PRIORITY STATUS INCORE PANEL ITEM/DESCRIPTION COMMENTS PHOTO# 74 2 1. BRACKET FOR INK Due 12/88 CARTRIDGES IS MISSING.
PHOTO# 75
1. VIDEO DISPLAYS MONITORS ARE. MISSING. THESE On hold for MONITORS ARE FOR THE futher evaluation FUEL BLDG SURVEILLANCE in 1989 SYS.
PHOTO# 77 2 1. C DETECTOR POSITION Due 12/88 DISPLAY IS A DIFFERENT STYLE. IN THE PLANT THEY HAVE REPLACED THE NIXIE TUBE DISPLAY
1.
WITH A LCD .
PHOTO# 78 PANEL LOGO SHOULD BE PAINTED OVER.
Due 10/88 PHOTO# 79 2 1. D DETECTOR POSITION Due 12/88 DISPLAY IS A DIFFERENT STYLE. IN THE PLANT THEY HAVE REPLACED THE NIXIE TUBE DISPLAY WITH A LCD.
PHOTO# 80 2 1. RECORDER INKING SYSTEM Due 12/88 IS MISSING.
2. PANEL LOGO SHOULD BE Due 10/88 PAINTED OVER .
ATTACHMENT 5 Page 19 of 58
PRI-ORITY STATUS INCORE PANEL ITEM/DESCRIPTION COMMENTS*
PHOTO. # 81 2 1*. E DETECTOR POSITION Due 12/88 DISPLAY IS A DIFFERENT STYLE. IN THE PLANT THEY HAVE REPLACED THE NIXIE TUBE DISPLAY WITH A LCD.
PHOTO# 82 1.~ PANEL LOGO SHOULD BE Due 10/88 PAINTED OVER.
PHOTO# 83 2 1. RECORDER INKING SYSTEM Due 12/88 IS MISSING.
2 N/S. 2. THE HOLDER FOR THE FLUX Due 10/88 THIMBLE LABELS IS MISSING
1*.
PHOTO# 88 NI PANEL SPARE STATUS WINDOW FOR.
N41A SHOULD BE BLANK.*
. No training impact PHOTO # 93 .
N/A 1. SPARE STATUS WINDOW FOR No training impact N42A SHOULD BE BLANK.
PHOTO# 96 w 1. CORE STATUS BOARD SHOULD Due 10/88 aE MADE TO MATCH THE Parts ordered PLANT.
PHOTO# 97
1. SPARE STATUS WINDOW FOR No training impact N43A SHOULD.BE BLANK.
PHOTO# 102
1. *SPARE STATUS WINDOW FOR No training impact i N44A SHOULD BE BLANK.
ATTACHMENT 5 Page 20 of 58
PRIORITY STATUS CTMT HI RNG RAD MON ITEM/DESCRIPTION PHOTO# 105 COMMENTS
1. THE PANEL IS HALF THE No training impact WIDTH AS THE ONE IN THE PLANT. THIS IS DUE TO TWO THINGS. 10 ALL ITEMS ON THE LEFT SIDE OF THE PANEL ARE UNIT 2 AND NOT SIMULATED. 2) THE PANEL HAD TO BE SMALLER TO ACCOMMODATE THE DOOR INTO THE SIMULATOR.
2. THE TWO PANEL TAGS AT THE No training impact TOP OF THE PANEL ARE PLACED ABOVE THE UNIT 1 INSTRUMENTS. THIS IS DUE TO THE PANEL SIZE.
PHOTO# 106
2 2 N/s*
1.
1.
THE IPAC SIGNAL ISOLATOR IS MISSING FOR RI-RMS-1270.
PHOTO# 108 THE IPAC SIGNAL ISOLATOR IS MISSING FOR RI-RMS-128 P; Due 12/88 Due 12/88 INTAKE PANEL PHOTO # 111
1. PANEL LOGO IS DIFFERENT. No training impact THE LABEL SHOULD BE GE INSTEAD OF BOEING.
PHOTO# 113 3 1. THE DIGITAL DISPLAY IS Due 12/88 A DIFFERENT STYLE.
PHOTO# 114 2 1. KNOB FOR SCAN MODE Due 12/88 SWITCH IS DIFFERENT .
ATTACHMENT 5 Page 21 of 58
PRIORITY *sTATUS ITEM/DESCRIPTION PHOTO# 1 1 4 INTAKE PANEL COMMENTS 2 N/S 2. LIGHT LENS *cAP FOR Due 12/88 STATION OFF SCAN SHOULD BE RED INSTEAD OF GREEN.
2 N/S 3. WHITE RESET P.B. MISSING Due 12/88 ON ALARM INSERT.
1 N/S 4. HAND WRITTEN ALARM STATUS Due 1 0/88 BOARD IS MISSING BETWEEN THE ALARM AND CONTROL.
INSERTS.
N/S 5. THE RED TAPE ON THE SCAN Due 10/88 MODE SWITCH IS MISSING.
PHOTO# 1 1 5
- 2 N/S 1. STATUS LIGHT A1-C IS Due 12/88 MISSING "BUS 2G". THE
2 N/S 2.
LIGHT SHOULD READ:
4160V SUPPLY/BKR-BUS-2G STATUS LIGHT A1-D SHOULD BE 1G INSTEAD OF 1G1. THE LIGHT SHOULD READ:
4160V SUPPLY/BKR-BUS-1G-1 Due 12/88 2 N/S 3. STATUS LIGHT A2-A SHOULD Due 12/88 NOT HAVE BUS-2G ON IT.
THE LIGHT SHOULD READ:
1-GWP-1A/BKR 1 N/S 4. STATUS LIGHT A4-D SHOULD Due 12/88 BE BLANK INSTEAD OF FUTURE.
2 N/S 5. STATUS LIGHT AS-C SHOULD Due 12/88 READ ALARM1IND/TEST INSTEAD OF FUTURE.
1 N/S 6. STATUS LIGHT A5-D SHOULD Due 12/88 BE BLANK INSTEAD OF FUTURE .
ATTACHMENT 5 Page 22 of 58
PRIORITY STATUS INTAKE PANEL ITEM/DESCRIPTION COMMENTS PHOTO# 117 2 1. INSERT# 3C IS MISSING Due 12/88 6 ALARM STATUS LIGHTS.
,2 2. ALARM STATUS 3C-A SHOULD Due 12/88 READ CO2/TROUBLE/LOCKOUT CO2/ALERT.
2 3. ALARM STATUS 3C-F SHOULD .Due 12/88 READ LAMP/TEST.
GAS TURB PANEL PHOTO #s 118-121 3 1. ALL INSTRUMENTATION AND Verify removal LABELS ARE MISSING ON completed by THIS PANEL. PANEL'S 12/88
COMPONENTS ARE BEING REMOVED BY THE STATION PHOTO# 123 EMERG GEN NO.
2 w 1. METER FOR XFER BUS F AMPS Due 12/88 HAS A DIFFERENT LINEARITY Parts ordered ON THE SCALE.
2 w 2. METER FOR EMERG BUS 1H Due 12/88 AMPS HAS A DIFFERENT Parts ordere.d LINEARITY ON THE SCALE.
2 w 3. METER SCALE FOR AC Due 12/88 KILOWATTS SHOULD BE Parts ordered 0-5000 INSTEAD OF 0-5.
2 w 4. METER SCALE FOR KILOVARS Due 12/88 SHOULD BE -2000 -+3000 Parts ordered INSTEAD OF +3.
2 w 5. METER SCALE FOR INCOMING Due 12/88 VOLT HAS A DIFFERENT Parts ordered LINEARITY .
2 w 6. METER SCALE FOR RUNNING VOLT HAS A DIFFERENT LINEARITY.
Due 12/88 Parts ordered
ATTACHMENT 5 Page 23 of 58
PRIORITY STATUS EMERG GEN NO.
ITEM/DESCRIPTION COMMENTS PHOTO# 123 2 w 7. METER SCALE FOR EMERG Due 12/88 BUS lH VOLTS HAS A Parts ordered DIFFERENT LINEARITY.
2 w 8. SWITCH RING LABEL FOR Due 12/88 EMERG GEN NO. 1 ENGINE Parts ordered START IS A DIFFERENT STYLE.
SWITCHYARD PANEL PHOTO# 127 2 N/S 1. METER FOR GEN N0.2 500KV Due 12/88 IS A DIFFERENT STYLE.
2 N/S 2. METER FOR FUTURE IS A Due 12/88 DIFFERENT STYLE .
2 2
N/S N/S 3.
4.
METER FOR FUTURE IS A DIFFERENT STYLE.
METER FOR 500KV LINE 557 IS A DIFFERENT STYLE.
Due 12/88 Due 12/88 2 N/S 5. METER FOR 500KV LINE Due 12/88 531 IS A DIFFERENT STYLE.
2 N/S 6. METER FOR 500KV LINE Due 12/88 562 IS A DIFFERENT STYLE.
PHOTO # 128 2 N/S 1. METER FOR XFMR NO . 1 Due 12/88 230KV IS A DIFFERENT STYLE.
2 N/S 2. METER FOR XFMR N0.2 Due 12/88 230KV IS A DIFFERENT STYLE .
ATTACHMENT 5 Page 24 of 58
PRIORITY STATUS SWITCHYARD PANEL ITEM[DESCRIPTION COMMENTS PHOTO # 128 2 N[S 3. METER FOR GEN NO. 1 Due 12/88 230KV IS A DIFFERENT STYLE.
2 N[S 4. METER FOR 230KV LINE 214 Due 12/88 IS A DIFFERENT STYLE.
2 N[S 5. METER FOR 230KV LINE 226 Due 12/88 IS A DIFFERENT STYLE.
2 N[S 6. METER FOR 230KV LINE 290 Due 12/88 IS A DIFFERENT STYLE.
PHOTO# 129 2 N[S 1. METER FOR 230KV LINE 240 Due 12/88 IS A DIFFERENT STYLE.
2 N[S 2. METER FOR 230KV LINE 212 Due 12/88 IS A DIFFERENT STYLE~
2 N[S 3. METER FUTURE IS A Due 12/88 DIFFERENT STYLE.
2 N[S 4. METER FOR 230KV LINE 223 Due 12/88 IS A DIFFERENT STYLE.
2 N[S 5. METER RSSA 4.16KV IS A- Due 12/88 DIFFERENT STYLE.
2 N[S 6. METER RSSB 4;16KV IS A Due 12/88 DIFFERENT STYLE.
2 N[S 7. METER RSSC 4.16KV IS A Due 12)88 DIFFERENT STYLE.
PHOTO# 132 w 1. RED AND GREEN LIGHTS ARE Due 12/88 MISSING FOR C.B . L402/5. Parts ordered
ATTACHMENT 5 Page 25 of 58
PRIORITY STATUS LOAD FREQ PANEL/HEAT TRACING ITEM/DESCRIPTION COMMENTS PHOTO# 134 3 1. RECORDER SHOULD HAVE A Due 12/88 FELT TIP INKING SYSTEM.
PHOTO# 138 2 w 1. SWITCH FOR HTP-7 IS Due 12/88 MISSING. THE SWITCH IS Parts ordered GE WITH OCTAGONAL SHAPED RETAINING RING.
2 w 2. SWITCH RING LABEL FOR Due 12/88 SWTICH HTP-7 IS MISSING. Lamacoid ring label THE RING LABEL IS BLACK ordered 08/16/88 LAMACOID WITH WHITE Parts ordered LETTERS AND IT SHOULD READ: OFF/ AUTO \ON 2 w 3. SWITCH IS MISSING FQR Due 12/88 HTP-6. THE SWITCH IS Parts ordered G.E. WITH AN OCTAGONAL SHAPED RETAINING RING.
2 w 4. SWITCH RING LABEL FOR Due 12/88 SWITCH HTP-6 IS MISSING Lamacoid ring label THE RING LABEL IS BLACK ordered 08/16/88 LAMACOID WITH WHITE Parts ordered*
LETTERS AMD IT SHOULD READ: OFF/AUTO\ON VENT PANEL PHOTO# 141 2 w 1. SWITCH RING LABEL FOR Due 12/88 1-VS-F4A IS A DIFFERENT Parts ordered STYLE AND THE ENGRAVING IS WRONG. THE RING LABEL SHOULD BE A _GE XL AND READ: STOP : START
ATTACHMENT 5 Page 26 of 58
PRIORITY STATUS VENT PANEL ITEM/DESCRIPTION COMMENTS
. PHOTO :# 1 41 2 w 2. SWITCH RING LABEL FOR Due 12/88 1-VS-F4B IS A DIFFERENT Parts ordered STYLE AND THE ENGRAVING IS WRONG. THE RING LABEL SHOULD BE A GE XL AND READ: STOP I START 2 w 3. SWITCH RING LABEL FOR Due 12/88 CTMT PURG EXH FLOW IND Parts ordered SELIS A DIFFERENT STYLE AND THE ENGRAVING IS WRONG. THE RING LABEL SHOULD BE GEXL AND READ:
UNIT 1 l UNIT 2 2 w 4. SWITCH RING LABEL FOR Due 12/88 AOD-VS-103A IS A DIFFERENT Parts ordered STYLE AND THE ENGRAVING IS WRONG. THE RING LABEL SHOULD BE GEXL AND READ:
FILTER I UNFILTER
.2 w 5. SWITCH RING LABEL FOR Due 12/88 AOD-VS-103B IS A DIFFERENT Parts ordered
. STYLE AND THE ENGRAVING IS WRONG. THE RING LABEL SHOULD BE GEXL AND READ:
FILTER I UNFILTER 2 w 6. SWITCH FOR CTMT PURGE Due 12/88 EXH FLOW IND SELIS A Parts ordered DIFFERENT STYLE. THE SWTICH SHOULD BE G.E.
INSTEAD OF ( W ).
2 w 7. SWITCH FOR AOD-VS-103A IS Due 12/88 A DIFFERENT STYLE. THE Parts ordered SWITCH SHOULD BE G.E.
INSTEAD OF ( W ).
2 w 8. SWITCH FOR AOD-VS-103B IS Due 12/88 A DIFFERENT STYLE. THE Parts ordered SWITCH SHOULD BE G.E.
INSTEAD OF ( W) .
ATTACHMENT 5 Page 27 of 58
PRIORITY STATUS VENT PANEL ITEM/DESCRIPTION COMMENTS PHOTO# 142 2 w 1. SWITCH RING LABEL FOR Due 12/88 1-VS-HV-1A IS A DIFFERENT Parts ordered STYLE AND THE ENGRAVING IS WRONG. THE RING LABEL SHOULD BE GEXL AND READ:
STOP I START 2 w 2. SWITCH RING LABEL FOR Due 12/88 1*-VS-F-8A IS A DIFFERENT Parts ordered STYLE AND THE ENGRAVING IS WRONG. THE RING LABEL SHOULD BE GEXL AND READ:
STOP l START
. i 2 w 3. SWITCH RING LABEL FOR Due 12/88 1-VS-F-8B IS A DIFFERENT Parts ordered STYLE AND THE ENGRAVING IS WRONG. THE RING LABEL
2 w 4.
SHOULD BE GEXL AND READ:
STOP I START SWITCH RING LABEL FOR 1-VS-F-9A IS A DIFFERENT STYLE AND THE ENGRAVING IS WRONG. THE RING LABEL Due 12/88 Parts ordered SHOULD BE GEXL AND READ:
STOP I START 2 w 5. SWITCH RING LABEL FOR Due 12/88 1-VS-F-9B IS A DIFFERENT Parts ordered STYLE AND THE ENGRAVING IS WRONG. THE RING LABEL SHOULD BE GEXL AND READ:
STOP l START 2 w 6. SWITCH RING LABEL FOR Due 12/88 1-VS-HV-1B IS A DIFFERENT Parts ordered STYLE AND THE ENGRAVING IS WRONG. THE RING LABEL SHOULD BE GEXL AND READ:
STOP I START
ATTACHMENT 5 Page 28 of 58
PRIORITY STATUS VENT PANEL ITEM/DESCRIPTION COMMENTS PHOTO# 142 2 w 7. SWITCH RING LABEL FOR Due 12/88 MOD-VS-100B IS A DIFFERENT Parts ordered STYLE AND THE ENGRAVING IS WRONG. THE RING LABEL SHOULD BE GEXL AND READ:
FILTER I UNFILTER 2 w 8. SWITCH RING LABEL FOR Due 12/88 MOD-VS-200B IS A DIFFERENT Parts ordered STYLE AND THE ENGRAVING IS WRONG. THE RING LABEL SHOULD BE GEXL AND READ:
FILTER I UNFILTER 2 w 9. SWITCH RING LABEL FOR Due 12/88 AOD-VS-109 A AND BIS Parts ordered A DIFFERENT STYLE AND THE ENGRAVING IS WRONG .
2 w 10.
THE RING LABEL SHOULD BE A GEXL AND READ:
FILTER I UNFILTER SWITCH RING LABEL FOR 1-VS-F-59A IS A DIFFERENT STYLE AND THE ENGRAVING Due*12/88 Parts ordered IS WRONG. THE RING LABEL SHOULD BE GEXL AND READ:
STOP I START 2 w 11. RED AND GREEN ( W )MINI Due 12/88 LIGHTS ARE MISSING FOR Parts ordered SWITCH 1-VS-F-59.
2 w 12. SWITCH AOD-VS-109 A/B Due 12/88 IS A DIFFERENT STYLE. Parts ordered THE SWITCH SHOULD BE G.E.
INSTEAD OF ( W ) .
ATTACHMENT 5 Page 29 of 58 VENT PANEL ITEM/DESCRIPTION COMMENTS PRIORITY STATUS PHOTO# 143
1. SWITCH RING LABEL FOR Due 12/88 2 w Parts ordered 1-VS-F-6 IS A DIFFERENT STYLE AND THE ENGRAVING IS WRONG. THE RING LABEL SHOULD BE A GEXL AND SHOULD READ:
STOP l START
2. SWITCH RING LABEL FOR Due 12/88 2 w Parts ordered 1-VS-F-39 IS A DIFFERENT STYLE AND THE ENGRAVING I~ WRONG. THE RING LABEL SHOULD BE A GEXL AND SHOULD READ:
STOP l START
3. SWITCH RING LABEL FOR Due 12/88 2 w Parts ordered AOD-VS-101 A AND B IS A DIFFERENT STYLE AND THE ENGRAVING IS WRONG. THE RING LABEL SHOULD BE A GEXL AND SHOULD READ: STOP l START
4. SWITCH AOD-VS-101 IS A Due 12/88 2 w Parts ordered DIFFERENT STYLE. THE SWITCH SHOULD BE A GE TWO POSITION MAINTAINED INSTEAD OF A ( W ).
5. SWITCH RING LABEL FOR Due 12/88 2 w Parts ordered 1-VS-F-7A IS A DIFFERENT STYLE AND THE ENGRAVING IS WRONG. THE RING LABEL SHOULD BE A GEXL AND READ:
STOP l START
6. SWITCH RING LABEL FOR Due 12/88 2 w Parts ordered 1-VS-F-7B IS A DIFFERENT STYLE AND THE ENGRAVING IS WRONG. THE RING LABEL SHOULD BE A GEXL AND READ:
STOP l START
ATTACHMENT 5 Page 30 of 58
PRIORITY STATUS VENT PANEL ITEM/DESCRIPTION COMMENTS PHOTO# 143 2 w 7. SWITCH RING LABEL FOR Due 12/88 1-VS-HV-5 IS A DIFFERENT Parts ordered STYLE AND THE ENGRAVING IS WRONG. THE RING LABEL SHOULD BE A GEXL AND READ:
STOP I START 2 w 8. SWITCH RING LABEL FOR Due 12/88 AOD-VS-104 IS A DIFFERENT Parts ordered STYLE AND THE ENGRAVING IS WRONG. THE RING LABEL SHOULD BE A GEXL AND READ:
FILTER I UNFILTER 2 w 9. SWITCH AOD-VS-104 IS A Due 12/88 DIFFERENT STYLE. THE Parts ordered SWITCH SHOULD BE A GE TWO POSITION MAINTAINED
2 w 10.
INSTEAD OF A ( W ).
SWITCH RING LABEL FOR 1-VS-F-56A IS A DIFFERENT STYLE AND THE ENGRAVING IS WRONG. THE RING LABEL SHOULD BE A GEXL AND READ:
Due 12/88 Parts ordered STOP I START 2 w 11. SWITCH RING LABEL FOR Due 12/88 1-VS-F-56B IS A DIFFERENT Parts ordered STYLE AND THE ENGRAVING IS WRONG. THE RING LABEL SHOULD BE A GEXL AND READ:
STOP I START PHOTO# 144 2 w 1 . . SWITCH RING LABEL FOR Due 12/88 1-VS-F-40A IS A DIFFERENT Parts ordered STYLE AND THE ENGRAVING IS WRONG. THE RING LABEL SHOULD BE A GEXL AND READ:
STOP I START
ATTACHMENT 5 Page 31 of 58
PRIORITY STATUS VENT PANEL ITEM/DESC~IPTION COMMENTS PHOTO # 144 2 w 2. SWITCH RING LABEL FOR Due 12/88 MOV-VS-100A IS A DIFFERENT Parts ordered STYLE AND THE ENGRAVING IS WRONG. THE RING LABEL SHOULD BE A GEXL AND READ:
FILTER I UNFILTER 2 w 3. SWITCH RING LABEL FOR Due 12/88 1-VS-HV-4 IS A DIFFERENT Parts ordered STYLE AND THE ENGRAVING IS WRONG. THE RING LABEL SHOULD BE A GEXL AND SHOULD READ:
STOP I START 2 w 4~ SWITCH.RING LABEL FOR Due i2/88 1-VS-F-408 IS A DIFFERENT Parts ordered STYLE AND THE ENGRAVING IS WRONG. THE RING LABEL* SHOULD BE A GEXL AND SHOULD READ:
STOP I START 2 w 5. SWITCH RING LABEL FOR Due 12/88 2-VS-F-40A IS A DIFFERENT Parts ordered STYLE AND THE ENGRAVING IS WRbNG. THE RING LABEL SHOULD BE A GEXL AND SHOULD READ: STOP I START 2 w 6. SWITCH RING LABEL FOR Due 12/88 MOD-VS-200A' IS A DIFFERENT Parts ordered STYLE AND THE ENGRAVING IS WRONG. THE RING LABEL SHOULD BE A GEXL AND READ:
FILTER I UNFILTER 2 7. SWITCH RING LABEL FOR *Due12/88 2-VS-HV-4 IS A DIFFERENT Par:ts ordered STYLE ANO THE ENGRAVING IS WRONG. THE RING LABEL SHOULD BE A GEXL AND SHOULD READ:
STOP I START
ATTACHMENT 5 Page 32 of 58
PRIORITY STATUS VENT PANEL ITEM/DESCRIPTION COMMENTS PHOTO# 144 2 w 8. SWITCH RING LABEL FOR Due 12/88 2-VS-F-40B IS A DIFFERENT Parts ordered STYLE AND THE ENGRAVING IS WRONG. THE RING LABEL SHOULD BE A GEXL AND SHOULD READ:
STOP I START EMERG GEN NO. 3 PHOTO# 146 2 w 1. METER SCALE FOR XFER BUS Due 12/88 DAMPS HAS A DIFFERENT Parts ordered LINEARITY.
2 w 2. METER SCALE FOR INCOMING Due 12/88 VOLT HAS A DIFFERENT Parts ordered LINEARITY.
2 w 3. METER SCALE FOR RUNNING Due 12/88 VOLT HAS A DIFFERENT Parts ordered LINEARITY.
PHOTO# 148 2 w 1. METER SCALE FOR EMERG BUS Due 12/88 lJ VOLTS HAS A DIFFERENT Parts ordered LINEARITY.
PHOTO# 150 2 w 1. KEY SWITCH FOR NO. 3 EDG Due 12/88 TO UNIT 2 IS A DIFFERENT Parts ordered STYLE.
TURB SUP INST PANEL PHOTO# 155 2 w 1. P.B. SWITCH FOR ACK IS Due 12/88 A DIFFERENT STYLE AND Parts ordered IT SHOULD BE BLACK .
ATTACHMENT 5 Page 33 of 58
PRIORITY STATUS COND/STM GEN CHEM PANEL ITEM/DESCRIPTION COMMENTS PHOTO# 159 N/A N/A 1. THE RECORDER AT THE No training impact PLANT LOCATED UNDER CR-SS-110 WAS REMOVED.
A BLANK BLACK PLATE WAS INSTALLED IN ITS PLACE.
THE SIMULATOR DID NOT HAVE THIS RECORDER.
RCP VIB /FLOOD CONP PANEL PHOTO# 160 2 N/S 1. FLOW DIAG IS WRONG. Due 12/88 IT SHOULD BE FOR Hold for 11448-FM-84A INSTEAD reevaluation due OF 11448-FKS-1 0-11. to revision difference
2 w 1.
PHOTO# 162 PRESS TO TEST P.B.
IS MISSING FOR LS-DA-116A.
Due 12/88 Parts ordered 2 w 2. PRESS TO TEST P.B. Due 12/88 IS MISSING FOR Parts ordered LS-DA-117A.
2 w 3. PRESS TO TEST P.B. Due 12/88 IS MISSING FOR Parts ordered LS-DA-118A.
2 w 4. PRESS TO TEST P.B. Due 12/88 IS MISSING FOR Parts ordered LS-DA-119A.
2 w 5. PRESS TO TEST P.B. Due 12/88 IS MISSING FOR Parts ordered LS-DA-120A.
2 w 6. PRESS TO TEST P.B. Due 12/88 IS MISSING FOR Parts ordered LS-DA-121A.
2 w 7. PRESS TO TEST P.B. Due 12/88 IS MISSING FOR Parts ordered LS-DA-110A.
ATTACHMENT 5 Page 34 of 58
PRIORITY STATUS RCP VIB /FLOOD CONP PANEL ITEM/DESCRIPTION COMMENTS PHOTO# 162 2 w 8. PRESS TO TEST P.B. Due 12/88 IS MISSING FOR Parts ordered LS-DA-111A.
2 w 9. PRESS TO TEST P.B. Due 12/88 IS MISSING FOR *Parts ordered LS-DA-112A.
2 w 1 0. PRESS TO TEST P.B. Due 12/88 IS MISSING FOR Parts ordered LS-DA-113A.
2 w 11. PRESS TO TEST P.B. Due 12/88 IS MISSING FOR Parts ordered LS-DA-114A.
2 w 12 . PRESS TO TEST P.B. Due 12/88 IS MISSING FOR Parts ordered
2 w 13 .
LS-DA-115A .
ALL THE LAMACOID.LABELS FOR THE P.B.s ARE IN THE WRONG LOCATION.
P.A.M. PANEL Due 12/88 Parts ordered PHOTO# 169 2 w 1* ALL SWITCHES ON THE Due 12/88 PANEL HAVE OCTAGONAL Parts ordered SHAPED RETAINING RINGS.
(24 SWITCHES TOTAL)
PHOTO# 170 2 w 1. RED AND GREEN LIGHT Due 12/88 LENS CAPS FOR SWITCH Parts ordered TV-GW-111A SHOULD BE TRANSLUCENT .
ATTACHMENT 5 Page 35 of 58
'PRIORITY STATUS P.A.M. PANEL ITEMLDESCRIPTION COMMENTS PHOTO -# .170 2 w 2. RED AND GREEN LIGHT Due 12/88 LENS CAPS FOR SWITCH Parts ordered TV-GW-111B SHOULD BE TRANSLUCENT.
2 w 3. RED AND GREEN LIGHT Due 12/88 LENS CAPS FOR SWITCH Parts ordered TV-GW-112A SHOULD BE TRANSLUCENT.
2 w 4. RED AND GREEN LIGHT Due 12/88 LENS CAPS FOR SWITCH Parts ordered TV-GW-112B SHOULD BE TRANSLUCENT.
2 w 5. WHITE LIGHT LENS CAP Due 12/88 FOR SWITCH TV-G.W-111.A Parts ordered SHOULD BE OFFWHITE TO AMBERISH IN COLOR.
2 w 6. WHITE LIGHT LENS CAP Due 12/88 FOR SWITCH TV-GW-111B Parts ordered SHOULD BE OFFWHITE TO AMBERISH IN COLOR.
2 w 7. WHITE LIGHT LENS CAP Due 12/88 FOR SWITCH TV-GW-112A Parts ordered SHOULD BE OFFWHITE TO AMBERISH IN COLOR.
2 w 8. WHITE LIGHT LENS CAP Due 12/88 FOR SWITCH TV-GW-112B Parts ordered SHOULD BE OFFWHITE TO AMBERISH IN COLOR.
PHOTO-# 1 7 1 2 w . 1 .. RING LABEL MISSING FOR Due 12/88 SWITCH SOV-RC-100A-2 Parts ordered GE STYLE XL "CLOSE II OPEN"
ATTACHMENT 5 Page 36 of 58
PRIORITY STATUS P.A.M. PANEL ITEM[DESCRIPTION PHOTO# 1 7 1 COMMENTS 2 w 2. RING LABEL MISSING FOR Due 12/88 SWITCH SOV-RC-lOOB-2 Parts ordered GE STYLE XL "CLOSE II OPEN" 2 w 3. RING LABEL MISSING FOR Due 12/88 SWITCH SOV-RC-lOlA-2 Parts ord.ered GE STYLE XL "CLOSE II OPEN" 2 w 4. RING LABEL MISSING FOR Due 12/88 SWITCH SOV-RC-lOlB-2 Parts ordered GE STYLE XL "CLOSE II OPEN" 2 w 5. RING LABEL MISSING FOR Due 12/88 SWITCH SOV-RC-lOOA-1 Parts ordered GE STYLE XL "CLOSE II OPEN" 2 w 6. RING LABEL MISSING FOR Due 12/88 SWITCH SOV-RC-lOOB-1 Parts ordered GE STYLE XL "CLOSE II OPEN" 2 w 7. RING LABEL MISSING FOR Due 12/88 SWITCH SOV-RC-lOlA-1 Parts ordered GE STYLE XL "CLOSE II OPEN" 2 w 8. RING LABEL MISSING FOR Due 12/88 SWITCH SOV-RC-lOlB-1 Parts ordered GE STYLE XL "CLOSE II OPEN" PHOTO# 173 2 w 1. RING LABEL MISSING FOR Due 12/88 SWITCH TV-DA103B. Parts ordered GE STYLE XL "CLOSE II OPEN"
ATTACHMENT 5 Page 37 of 58
PRIORITY STATUS P.A.M. PANEL ITEM/DESCRIPTION COMMENTS PHOTO :/t 173 2 w 2. RING LABEL MISSING FOR Due 12/88 SWITCH TV-DA-103A Parts ordered GE STYLE XL "CLOSE I OPEN" 2 w 3. FOUR WHITE LIGHT LENS Due 12/88 CAPS ABOVE SWITCH XFER Parts ordered CKT SHOULD BE OFFWHITE TO AMBERISH IN COLOR.
2 .w 4. RING LABEL MISSING FOR Due 12/88 SWITCH XFER CKT. Parts ordered GE STYLE XL "UNIT 1 I UNIT 2 11 PHOTO :/t 174 w
2 1. RING LABEL MISSING FOR Due 12/88 SWITCH TV-GW-101 Parts ordered GE STYLE XL "CLOSE I OPEN" 2 w 2. RING LABEL MISSING FOR Due 12/88 SWITCH TV-GW-102 Parts ordered GE STYLE XL "CLOSE I OPEN" 2 w 3. RING LABEL MISSING FOR Due 12/88 SWITCH TV-GW-104 Parts ordered GE STYLE XL "CLOSE I OPEN" 2 w 4. RING LABEL MISSING FOR Due 12/88 SWITCH TV-GW-106 Parts ordered GE STYLE XL "CLOSE I OPEN"
.2 w 5. RING LABEL MISSING FOR Due 12/88 SWITCH TV-GW-101 Parts ordered GE STYLE XL "CLOSE I OPEN" 2 w 6. RING LABEL MISSING FOR Due 12/88 SWITCH TV-GW-103 Parts ordered GE STYLE XL "CLOSE I OPEN"
ATTACHMENT 5 Page 38 of 58
PRIORITY STATUS P.A.M. PANEL ITEM/DESCRIPTION COMMENTS PHOTO# 174 2 w 7. RING LABEL MISSING FOR Due 12/88 SWITCH TV-GW-107 Parts ordered GE STYLE XL "CLOSE I OPEN" 2 w 8. RING LABEt MISSING FOR Due 12/88 SWITCH TV-GW-105 Parts ordered GE STYLE XL "CLOSE I OPEN" 2 w 9. WHITE LIGHT LENS CAP Due 12/88 FOR VB1-1-29 SHOULD Parts ordered BE OFFWHITE TO AMBERISH IN COLOR.
2 w 10. WHITE LIGHT LENS CAP Due 12/88
. FOR VB1-11-30 SHOULD Parts ordered BE OFFWHITE TO AMBERISH IN COLOR.
2 w 11. WHITE LIGHT LENS CAP Due 12/88 FOR VB-1-111-29 SHOULD Parts ordered BE OFFWHITE TO AMBERISH IN COLOR.
2 w 12. WHITE LIGHT LENS CAP Due 12/88 FOR VB-1-lV-32 SHOULD Parts ordered BE OFFWHITE TO AMBERISH IN COLOR.
B B 1 PHOTO# 176 2 w 1. LEFT P.B. SWITCH FOR Due 12/88 RMT SYS TR "A" IS A Parts ordered DIFFERENT STYLE.
2 w 2. RIGHT P.B. SWITCH FOR Due 12/88 RMT SYS TR "A" IS A Parts ordered DIFFERENT.STYLE.
2 w 3. P.B. SWITCH FOR TR "A" Due 12/88 RESET IS A DIFFERENT Parts ordered STYLE .
ATTACHMENT 5 Page 39 of 58
PRIORITY STATUS B B 1 ITEM[DESCRIPTION COMMENTS PHOTO=# 176 2 w 4* WHITE AND AMBER LIGHTS Due 12/88 FOR SWITCH TR "A" RESET Parts ordered ARE A DIFFERENT STYLE.
2 w 5. LEFT P.B. SWITCH FOR Due 12/88 RMT SYS TR "B" IS A Parts ordered DIFFERENT STYLE.
2 w 6. RIGHT P.B. SWITCH FOR Due 12/88 RMT SYS TR "B" IS A Parts ordered DIFFERENT STYLE.
2 w 7. P.B. SWITCH FOR TR "B" Due 12/88 RESET IS A DIFFERENT Parts ordered STYLE.
2 w 8. WHITE AND AMBER LIGHTS Due 12/88 FOR SWITCH TR "B" RESET Parts ordered
2 w 1.
ARE A DIFFERENT STYLE .
PHOTO=# 177 KEY SWITCH FOR MOV-1869A IS A DIFFERENT STYLE.
Due 12/88 Parts ordered 2 w 2. KEY SWITCH FOR MOV-1869B Due 12/88 IS A DIFFERENT STYLE. Parts ordered 2 N[S 3. FOUR POSITION SWITCH Due 12/88 1-CS-P-2A IS A DIFFERENT STYLE.
2 N/S 4. FOUR POSITION SWITCH Due 12/88
. 1 -CS-P-2B IS A DIFFERENT STYLE.
PHOTO #178 2 w 1. KEY SWITCH FOR MOV-1890A Due 12/88 IS A DIFFERENT STYLE. Parts ordered 2 w 2. KEY SWITCH FOR MOV-1890B Due 12/88 IS A DIFFERENT STYLE. Parts ordered
ATTACHMENT 5 Page 40 of 58
PRIORITY STATUS B B 1 ITEMLDESCRIPTION COMMENTS PHOTO# 184 2 w 1. SWITCH MOV~CS-103D IS A Due 12/88 DIFFERENT STYLE. Parts ordered 2 w 2. SWITCH MOV-CS-103C IS A Due 12/88 DIFFERENT STYLE. Parts ordered 2 w 3. SWITCH MOV-CS-103B IS A Due _12/88 DIFFERENT STYLE. Parts ordered 2 w 4. SWITCH MOV-CS-103A IS A Due 12/88 DIFFERENT STYLE. Parts ordered PHOTO# 186 3 NLS 1. BRASS SWITCH COVER IS Station is MISSING FOR SWITCH evaluating new MOV~CW-106A. . covers 3 NLS 2. .BRASS SWITCH COVER rs Station is MISSING FOR SWITCH evaluating new MOV-CW-106B. covers 3 NLS 3. BRASS SWITCH COVER IS Station is MISSING FOR SWITCH evaluating new MOV-CW-106C. covers 3 NLS 4. BRASS SWITCH COVER IS Station is MISSING FOR SWITCH evaluating new MOV-CW-106D. covers PHOTO# 189 2 w
--* 1. FOUR POSITION SWITCH FOR Due 12/88 1-V-P-P-lA IS A DIFFERENT Parts ordered STYLE. THE SWITCH APPEARS TO BE A CUTLER
. HAMER WITH A OCTAGONAL RETAINING RING AND A PISTOL GRIP HANDLE.
PHOTO# 1 91 2 w 1. P.B. SWITCH FOR ACK Due 12/88 IS A DIFFERENT STYLE . Parts ordered
ATTACHMENT 5 Page 41 of 58
PRIORITY STATUS B B 1 ITEM/DESCRIPTION COMMENTS PHOTO# 210 2 w 1. ELECTRO SWITCH PLATE Due 12/88 LABEL FOR 1-CH-P-1B Parts ordered IS MISSING AUTO FOR THE CENTER POSITION.
PHOTO# 213 2 w 1. SWITCH RING LABEL FOR Due 12/88 label SOV-SI-102A1 IS A ordered 08/16/88 DIFFERENT STYLE AND SHOULD READ:
CLOSE-AUTO-OPEN 2 w 2. SWITCH RING LABEL FOR Due 12/88 label SOV-SI-102B1 IS A ordered 08/16/88 DIFFERENT STYLE AND SHOULD READ:
CLOSE-AUTO-OPEN
2 w 3. SWITCH RING LABEL FOR SOV-SI-102A2 IS A DIFFERENT STYLE AND SHOULD READ:
CLOSE-AUTO-OPEN Due 12/88 label ordered 08/16/88 2 w 4. SWITCH RING LABEL FOR Due 12/88 SOV-SI-102B2 IS A Parts ordered DIFFERENT STYLE AND SHOULD READ:
CLOSE-AUTO-OPEN B B 2 PHOTO# 220 2 w 1. FOUR POSITION SWITCH Due 12/88 FOR 1-CH-P-2A IS A Parts ordered DIFFERENT STYLE. THE SWITCH. SHOULD BE CUTLER HAMER WITH AN OCTAGONAL RETAINING RING.
2 w 2. FOUR POSITION SWITCH Due 12/88 FOR 1-CH~P-2B IS A Parts ordered DIFFERENT STYLE. THE SWITCH SHOULD BE CUTLER HAMER WITH AN OCTAGONAL RETAINING RING.
ATTACHMENT 5 Page 42 of 58
PRIORITY STATUS B B 2 ITEMLDESCRIPTION COMMENTS PHOTO# 220 2 w 3. SWITCH RING LABEL FOR Due 12/88 Label TI-PG-1-1B IS A DIFFERENT ordered 08/16/88 STYLE AND SHOULD READ HAND OFF AUTO PHOTO # 223 NLA NLA 1. STEP COUNTER FOR No training impact CONT BANK C TRIM SHOULD BE PAlNTED BEIGE.
PHOTO# 224 NLA NLA 1. STEP COUNTER FOR No training impact SHUTDOWN BANK A SHOULD BE PAINTED BEIGE .
2 NLS 1.
PHOTO# 225 METER LEGEND FOR N1-1-41C SHOULD HAVE
% INSTEAD OF j_j,_ O.
Due 12/88 2 NLS 2. METER LEGEND FOR Due 12/88 N1-1-42C SHOULD HAVE
% INSTEAD OF j_j,_ O.
2 NLS 3. METER LEGEND FOR Due 12/88 N1-1-43C SHOULD HAVE
% INSTEAD OF j_j,_ O.
2 N/S 4. METER LEGEND FOR Due 12/88 N1-1-44C SHOULD HAVE
% INSTEAD OF j_j,_ 0.
PHOTO# 231 2 w 1. SWITCH RING LABEt FOR Due 12/88 ROD CONT SYS START UP Parts ordered RESET IS A DIFFERENT STYLE .
ATTACHMENT 5 Page 43 of 58
PRIORITY STATUS B B 2 ITEM/DESCRIPTION COMMENTS PHOTO# 234 2 w 1. P.B. SWITCH FOR ACK IS A Due 12/88 DIFFERENT STYLE. THE Parts ordered SWITCH SHOULD BE CUTLER HAMER WITH AN OCTAGONAL RETAINING RING.
PHOTO# 241 2 w 1. SWITCH NORM/DEFEAT IS A Due 12/88 DIFFERENT STYLE. THE Parts ordered SWITCH SHOULD BE A CUTLER HAMER WITH A PLASTIC SWITCH COVER ON IT.
2 w 2. RED AND GREEN MINILIGHTS Due 12/88 FOR MOV-CP-100 ARE DIFFERENT Parts ordered STYLE. THE LIGHTS SHOULD HAVE LENS CAP THAT SCREWS TO OUTSIDE OF THE ASSEMBLY .
PHOTO# 249 2 w 1. SWITCH SOV-MS-102A IS A Due 12/88 DIFFERENT STYLE. THE Parts ordered SWITCH SHOULD BE AN
-ELECTRO SWITCH SERIES 20, TYPE PR-20 WITH A GRAY TEE SWITCH HANDLE.
2 2. SWITCH MOV-AS-101 IS A Due 12/88 DIFFERENT STYLE.
PHOTO# 257 2 .w 1. METER SCALE IS MISSING Due 12/88 DIVISION MARKS BETWEEN Parts ordered 500 AND 1000V FOR STA SERV lA VOLT METER.
PHOTO# 265 2 w 1. ELECTRO SWITCH FOR Due 12/88 34.5 KV BUSS 5 HAS A Parts ordered DIFFERENT STYLE COVER PLATE. THE PLATE SHOULD
~E BLANK WITH A WHITE POINTER.
ATTACHMENT 5 Page 44 of 58
PRIORITY STATUS B B 2 ITEMLDESCRIPTION COMMENTS PHOTO# 265 2 w 2. P.B. SWITCH COVERS FOR Due 12/88 RSST LTC SHOULD BE Parts ordered SCRIBED. THE SWITCH COVERS SHOULD READ:
UNIT 1 RESET, UNIT 2 RESET, 1 & 2 V B PHOTO# 285 2 w 1. KEY SWITCH FOR MOV-186A Due 12/88 IS A DIFFERENT STYLE. Parts ordered
2 w 2. KEY SWITCH FOR MOV-1865B Due 12/88 IS A DIFFERENT STYLE . Parts ordered
2 w 1.
PHOTO# 286 METER*FI-1-960 HAS A DIFFERENT SCALE. IN THE PLANT THE SCALE IS 0-600 GPM SQUARE ROOT.
Due 12/88 Parts ordered PHOTO #"289 2 w 1 RED AND GREEN P.B. Due 12/88 SWITCH/LIGHTS FOR Parts ordered TV-IA-101A ARE A DIFFERENT STYLE.
PHOTO# 292 2 w 1. RED AND GREEN P.B. Due 12/88 SWITCH/LIGHTS FOR Parts ordered TV-IA-101B ARE A DIFFERENT STYLE.
PHOTO# 295 2 w 1. RWST LVL RECORDER IS Due 12/88 MISSING THE SCALE FOR Parts ordered PEN 2.POINT-LR-CS-102.
THE SCALE SHOULD.BE DUAL WITH 0-100 AND 9~0-10.0.
ATTACHMENT 5 Page 45 of 58
PRIORITY STATUS V B 1 ITEM[DESCRIPTION COMMENTS PHOTO :/t 295 2 w 2. THE SCALE FOR METER Due 12/88 LI-CW-101 IS DIFFERENT. Parts ordered THE SCALE SHOULD BE 15-30 FT.
2 w 3. THE SCALE FOR METER Due 12/88 FI-SW-105A IS DIFFERENT. Parts ordered THE SCALE SHOULD BE 0-160 X 100 GPM SQUARE ROOT.
2 w 4. THE SCALE FOR METER Due i2/88 FI-SW-105B IS DIFFERENT. Parts ordered THE SCALE SHOULD BE 0-160 X 100 GPM SQUARE ROOT.
PHOTO :/t 297
2 2
w w
1.
2.
KEY SWITCH OPERATOR IS A DIFFERENT STYLE FOR 11 A11 STM GEN BD TV.
KEY SWITCH OPERATOR IS A DIFFERENT STYLE FOR 11B11 STM GEN BD TV.
Due 12/88 Due 12/88 2 w 3* KEY SWITCH OPERATOR IS Due 12/88 A DIFFERENT STYLE FOR II C II STM GEN BD TV.
PHOTO :/t 299 2 w 1. METER SCALE IS DIFFERENT Due 12/88 FOR LI-DA-110A. THE SCALE Parts ordered SHOULD BE 4.5-26.5 INCHES.
2 w 2. METER SCALE IS DIFFERENT Due 12/88 FOR LI-DA-110B. THE SCALE* Parts ordered SHOULD BE 4.5-26.5 INCHES .
ATTACHMENT 5 ,
Page 46 of 58
PRIORITY STATUS V B 1 ITEM/DESCRIPTION COMMENTS PHOTO :/t 301
1. INDICATING LIGHTS FOR Due 11/88 SWITCH 1-IA-C-4A AND 1-IA-C-4B SHOULD BE SPACED FURTHER APART.
THE SWITCHES, LIGHTS AND LABELS FOR 1-IA-C-4A, SOV-SA-175, PCV-1456 &
PVC-1455C SHOULD BE RELOCATED APPROXIMATELY 2 INCHES TO THE LEFT.
2 w 2. INDICATING LIGHTS FOR Due 12/88 SWITCH 1-IA-C-4A ARE A Parts ordered DIFFERENT STYLE.
2 w 3. INDICATING LIGHTS FOR Due 12/88 SWITCH 1-IA-C-4B ARE A Parts ordered DIFFERENT STYLE .
2 2
w w
4.
5.
SWITCH 1-IA-C-4A IS A DIFFERENT STYLE.
SWITCH 1-IA-C-4B IS A DIFFERENT STYLE.
Due 12/88 Parts ordered Due *12/88 Parts ordered PHOTO# 302 2 1. 20" X 20" FLOW DIAG IS Due 12/88 MISSING. THE DIAG IS A On hold due to ON METAL FOR CONTAINMENT reevaluation of INSTRUMENT AIR SYSTEM. revision differences PHOTO :/t 306 2 w 1. RECORDER SCALE FOR FR1-154A Due 12/88 IS WRONG. THE SCALE AND Parts ordered PAPER SHOULD BE 0-6 INSTEAD OF 0-100
ATTACHMENT 5 Page 47 of 58
PRIORITY STATUS V B 1 ITEM/DESCRIPTION COMMENTS PHOTO :/t 322 2 w 1. RECORDER SCALE AND PAPER Due 12/88 IS DIFFERENT FOR Parts ordered FR-1-113. THE SCALE SHOULD BE DUAL: 0-10 AND 0-150. THE PAPER SHOULD MATCH THE SCALE.
PHOTO :/t 324 w 1. EIGHT SOUND POWERED PHONE Due 10/88 Parts JACKS ARE MISSING AT THE ordered 08/05/88 BOTTOM OF THE PANEL.
V B 2.
PHOTO :/t 327 2 1. TRIP STATUS LIGHT J-1 HAS Due 12/88
2 2.
AN EXTRA LINE THAT READS HI PRESS. THIS LINE SHOULD BE REMOVED AND THE REMAINING LINES SHOULD BE SPACED DIFFERENTLY.
TRIP STATUS LIGHT J-2 HAS Due 12/88 AN EXTRA LINE THAT READS HI PRESS.
2 3. TRIP STATUS LIGHT J-3 HAS Due 12/88 AN EXTRA LINE THAT READS HI PRESS.
PHOTO :/t 329 w 1 .. TREND RECORDER STATUS Due 12/88 BOARD IS MISSING. Parts ordered PHOTO :/t 332 2 w 1. OT2 SWITCH WITH RED AND Due 12/88 GREEN LIGHTS ARE MISSING Parts ordered FOR MOV-ES-22.
2 w 2. OT2 SWITCH WITH RED AND Due 12/88 GREEN LIGHTS ARE MISSING Parts ordered FOR MOV-ES-67.
ATTACHMENT 5 Page 48 of 58
PRIORITY STATUS V B 2 ITEM/DESCRIPTION COMMENTS PHOTO# 332 2 w 3. OT2 SWITCH WITH RED AND Due 12/88 GREEN LIGHTS ARE MISSING Parts ordered FOR MOV-ES-58.
2 w 4. OT2 SWITCH WITH RED AND Due 12/88 GREEN LIGHTS ARE MISSING Parts ordered FOR MOV-ES-95.
2 w 5. OT2 SWITCH WITH RED AND Due 12/88 GREEN LIGHTS ARE MISSING Parts ordered FOR MOV-ES-86.
2 N/S 6. OT2 SWITCH WITH RED AND Due 12/88 GREEN LIGHTS ARE MISSING FOR MOV-ES-100.
PHOTO# 333
2 2
N/S N/S 1.
2.
PERM STATUS LIGHT A-1, LINE 3 SHOULD READ <35%
INSTEAD OF <SO%.
PERM STATUS LIGHT B-3, LINE 3 IS MISSING THE Due 12/88 Due 12/88 WORD "AMPS I I .
2 N/S 3. PERM STATUS LIGHT C-2, Due 12/88 LINE 3 SHOULD BE WHITED OUT.
PHOTO# 336 2 w 1. METER PI-1-402 SCALE Due 12/88 SHOULD BE 0-3000 PSI Parts ordered INSTEAD OF 0-30 X100 PSIG.
PHOTO# 341 2 N/S SWITCH "SPARE" STILL Due 12/88 HAS THE CONTROLS FOR MOV-ES-100 WIRED TO IT.
ONCE MOV-ES-100 SWITCH IS INSTALLED IN ITS NEW
LOCATION WE CAN TRANSFER THE WIRING TO IT.
ATTACHMENT 5 Page 49 of 58
PRIORITY STATUS V B 2 ITEM/DESCRIPTION COMMENTS PHOTO-# 343 N/S 1. METER FI-BD-103A IS Due 10/88 MISSING BLUE AND YELLOW SCALE BANDING.
N/S 2. METER FI-BD-1 04A I.S Due 10/88 MISSING BLUE AND YELLOW SCALE BANDING.
N/S 3. METER FI-BD-103B IS Due 10/88 MISSING BLUE AND YELLOW SCALE BANDING.
4~ METER FI-BD-104B IS Due 10/88 MISSING BLUE AND YELLOW SCALE.BANDING.
PHOTO-# 346
2 1.
2.
SWITCH RING LABEL IS MISSING FOR TV-MSlOlA,B,C EMERG I GE STYLE XL CLOSE I NORMAL RECORDER CR-SS-100 SHOULD Due 12/88 Parts ordered Due 10/88 BE REMOVED. AT THIS TIME THE PLANT STILL HAS A HOLE WHERE THE RECORDER WAS TAKEN OUT.
PHOTO-# 353
1. SIGMA METERS LI-CN-100 No training impact AND 101 ARE IN THE WRONG LOCATION. THEY NEED TO BE MOVED APPROXIMATELY 4.5 INCHES TO THE RIGHT.
2 2. METER LI-CN-100 OPERATES Due 12/88 DIFFERENT FROM THE PLANT.
THE RED INDICATION SHOULD ILLUMINATE FROM TOP TO BOTTOM INSTEAD OF BOTTOM TO TOP.
2 3. METER LI-CN-101 OPERATES DIFFERENT FROM THE PLANT.
Due 12/88
AT'I_'ACHMENT 5 Page 50 of 58
PRIORITY STATUS .
V B 2 ITEMLDESCRIPTION COMMENTS PHOTO :/t 359 2 NLS 1. RING DOWN PHONE IS Due 12/88 MISSING. (GROWLER)
PHOTO :/t 361 w 1. 02 RECORDER HAS BEEN Due 10/88 REPLACED WITHAL & N 3 POINT RECORDER.
PHOTO :/t 363 2 N/S 1. RECORDER CR-CC-101 HAS Due 12/88 BEEN REPLACED WITH A NEW STYLE.
PHOTO :/t 367 w
1. METER FI-FW-100B IS MISSING Due 10/88 A WHITE CHANNEL DOT. Parts ordered PHOTO :/t 370 2 w 1. METER H2I-HG-101 SCALE IS Due 12/88 WRONG. THE SCALE SHOULD Parts ordered BE 50-100.
PHOTO :/t 374 2 w 1. METER FI-1-100A SCALE IS Due 12/88 LAID OUT WRONG. THE Parts ordered DIVISIONS DO NOT REPRESENT THE SAME SQUARE ROOT SCALE AS THE PLANT.
2 w 2. METER FI-1-100B SCALE IS Due 12/88 LAID OUT WRONG. THE Parts ordered DIVISIONS DO NOT REPRESENT THE SAME SQUARE ROOT.SCALE AS THE PLANT.
2 w 3. METER 1-cc-.:P-1A SCALE IS Due 12/88 DIFFERENT. THE BOTTOM Parts ordered 20% OF THE SCALE SHOULD BE NON LINEAR .
ATTACHMENT 5 Page 51 of 58 *
PRIORITY STATUS V B 2 ITEM/DESCRIPTION COMMENTS PHOTO# 374 2 w 4. METER 1-CC-P-lB SCALE IS Due 12/88 DIFFERENT. THE ~OTTOM Parts ordered 20% OF THE SCALE SHOULD BE NON LINEAR.
PHOTO# 382 2 w 1. SWITCH RING LABEL FOR Due 12/88 1-SW-P-4A IS LAID OUT Parts ordered DIFFERENT. IT SHOULD READ: HAND OFF AUTO 3 2. LAMACOID LABEL FOR Due 10/88 1-CD-P-2A SHOULD BE LOCATED UNDER THE SWITCH AND NOT OVER THE SWITCH.
DUE TO THE LOCATION OF THE LIGHTS FOR SWITCH
2 w 3.
1-CD-P-2B THE LABEL- WILL NOT FIT UNDER THE SWITCH.
SWITCH RING LABEL FOR 1-CD-P-3A IS LAID OUT DIFFERENT. IT SHOULD READ: HAND OFF AUTO Due 12/88 Parts ordered AUX VENT PANEL PHOTO# 387 2 1. DIGITAL CLOCK IS MISSING. Due 12/88 May be able to use NAPS clock which may be replaced
2. THE TWO SECURITY VIDEO Due 12/88 MONITORS ARE MISSING. THESE On hold for MONITORS SHOULD BE MOUNTED futher evaluation ON EITHER SIDE OF THE ANN. in 1989 PANEL. DUE TO THE DIMENSIONS OF THE PANEL THE MONITORS WILL NOT FIT IN THE PANEL.
3. THE UNIT TWO RECORDERS No training impact ARE MISSING.
ATTACHMENT 5 Page 52 of 58
PRIORITY STATUS AUX VENT PANEL ITEM/DESCRIPTION COMMENTS,*
PHOTO# 387
4. ANN P.B. SWITCHES FOR TEST, No training impact ACK, AND SILENCE HAVE BEEN Due to only unit 1.
RELOCATED TO THE RIGHT modeled --
SIDE OF THE PANEL~
5. ANN PANEL IS OFFSE~ No training impact APPROXIMATEtY ONE FOOT TO Due to only unit~
THE RIGHT. modeled *
6. UNIT ONE RECORDERS ARE No training impact OFFSET APPROXIMATELY TWO Due to only unit 1 INCHES TO THE LEFT TO modeled ACCOMMODATE THE ANN P.B.'s.
7. FLOW DIAG WILL BE LOCATED No *training impact ON THE RIGHT SIDE OF THE Due to- only unit 1 P~NEL INSTEAD OF THE LEFT modeled
8. THE PANEL TS SMALLER IN WIDTH DUE.TO NO UNIT TWO RECORDERS AND TO ACCOMMODATE THE SPACE NEEDED TO PUT THE PANEL IN. THIS DOES NOT EFFECT THE LAYOUT OF INSTRUMENTS No training impact Due to only unit 1 modeled
ON THE PANEL EXCEPT FOR-THE ITEMS LISTED ABOVE.
PHOTO# 392
1.
BLACK MOUNTING CASE Due 11/88 COVER IS MISSING FOi PIC/FI-VS-1*17A
2. BLACK MOUNTING CASE Due 11/88 COVER IS ~ISSING FOR
_ PIC/FI-VS-11 7B
3. THE METERS AND SETPOINT Due 11/88 STATION FOR PIC/FI-VS-117B HAVE TO SWAP LOCATIONS. THE SETPOINT STATION SHOULD BE UNDER THE LEFT HAND METER .
ATTACHMENT 5 Page 53 of- 58
PRIORITY STATUS AUX VENT PANEL ITEMLDESCRIPTION COMMENTS PHOTO# 395 2 w 1. SWITCH RING LABEL FOR Due 12/88 CTMT EXH IS A DIFFERENT Parts ordered STYLE AND IT IS BLANK.
THE RING LABEL SHOULD BE A GE XL AND READ:
FILTER II ISOLATE PHOTO# 396 2 w 1. SWITCH RING LABEL FOR Due 12/88 AUX BLDG IS A DIFFERENT Parts ordered STYLE AND IT IS BLANK.
THE RING LABEL SHOULD BE A GE XL AND READ:
FILTER II UNFILTER 2 w 2. SWITCH RING LABEL FOR Due 12/88 SOV-VS-101A IS A DIFFERENT Parts ordered STYLE AND IT IS BLANK .
THE RING LABEL SHOULD READ: RESET 2- w 3. SWITCH RING LABEL .FOR Due 12/88 SOV-VS-101B IS A DIFFERENT Parts ordered STYLE AND IT IS BLANK.
THE RING LABEL SHOULD READ: RESET 2 w 4. SWITCH RING LABEL FOR Due 12/88 SOV-VS-201A IS A DIFFERENT Parts ordered STYLE AND IT IS BLANK.
THE RING LABEL SHOULD READ: RESET 2 w 5. SWITCH RING LABEL FOR Due 12/88 SOV-VS-201B IS A DIFFERENT Parts ordered STYLE AND IT IS BLANK.
THE RING LABEL SHOULD READ: RESET PHOTO# 398 2 NLS 1. 30" X 30" FLOW DIAG IS Due 12/88 MISSING FOR AUX VENT SYS. Reevaluate due to revision
differences
ATTACHMENT 5 Page 54 of 58
PRIORITY STATUS AUX VENT PANEL ITEMiDESCRIPTION COMMENTS PHOTO# 399 2 w 1. SWITCH RING LABEL FOR Due 12/88 AOD-VS-113 IS A DIFFERENT Parts ordered STYLE AND IT IS BLANK.
THE RING LABEL SHOULD BE A GE XL AND READ:
CLOSE I I OPEN 2 w 2. SWITCH RING LABEL FOR Due 12/88 AOD-VS-112A IS A DIFFERENT Parts ordered STYLE AND IT IS BLANK.
THE RING LABEL SHOULD BE A GE XL AND READ:
CLOSE I OPEN I
2 w 3. SWITCH RING LABEL FOR Due 12/88 AOD-VS-112B IS A DIFFERENT STYLE AND IT IS BLANK.
THE RING LABEL SHOULD BE A GE XL AND READ:
CLOSE OPEN PHOTO# 401 2 w 1. SWITCH RING LABEL FOR Due 12/88 TEST IS A DIFFERENT Parts ordered STYLE AND IT IS BLANK.
THE RING LABEL SHOULD READ: TEST 2 w 2. SWITCH RING LABEL FOR Due 12/88 ACKNOWLEDGE IS A DIFFERENT Parts ordered STYLE AND IT IS BLANK.
THE RING LABEL SHOULD READ:
ACKNOWLEDGE 2 w 3. SWITCH RING LABEL FOR Due 12/88 SILENCE READS ACK. THE Parts ordered RING LABEL SHOULD READ:
SILENCE PHOTO# 403 2 NiS 1. FLOW DIAGRAM MISSING FOR Due 12/88 AIR COOLING AND PURGING Hold for re-
SYS . evaluation due to revision concerns
ATTACHMENT 5 Page 55 of 58
PRIORITY STATUS SUPERVISOR CONSOLE ITEM/DESCRIPTION PHOTO :/t 405 COMMENTS 2 w 1. TOGGLE SWITCH MISSING FOR Due 12/88 THE FIRST AID ALARM. Parts ordered PHOTO :/t 407 3 1. THE SPARE PHONE SHOULD BE Due 12/88 REMOVED AND A ZERROM MODEL 15 MULTIFORMAT ENCODER INSTALLED IN ITS PLACE.
PHOTO :/t 409
1. MOTOROLA COMMUNICATION Install by 10/88 PANEL IS MISSING. Done but need facia plates to finish PHOTO :/t 410
1. MOTOROLA COMMUNICATION PANEL IS MISSING.
AUX SHUTDOWN Install by 10/88 Done but need facia plates to finish PHOTO :/t 414 2 1. METER PI-1-444 A IS MISSING Due 12/88 PSIG ON THE SCALE.
2 2. METER PI-464 BIS MISSING Due 12/88 X100 PSIG ON THE SCALE.
2 3. METER PI-1-122 B SCALE Due 12/88 SHOULD BE SQUARE ROOT INSTEAD OF LINEAR.
PHOTO :/t 415 2 1. LAMACOID LABEL FOR Due 12/88 PI-MS-101C IS MISSING.
THE LABEL SHOULD READ:
MAIN STM. LINE PRESS/
PI-MS-101C
ATTACHMENT 5 Page 56 of 58
PRIORITY STATUS SUPERVISOR CONSOLE ITEM/DESCRIPTION COMMENTS PHOTO :/t 417 2 N/S 1. ELECTRO SWITCH COVER PLATE Due 12/88 LABEL FOR 1-FW-P-3A IS WRONG. THE LABEL READS:
TRIP. /AUTO\ CLOSE IT SHOULD READ:
STOP /AUTO\ START 2 N/S 2. GRAY COVER PLATE IS Due 12/88 MISSING FOR SOV-MS-102. THE SWITCH IS A ELECTROSWITCH SERIES 20.
2 N/S 3. CLOSE AND OPEN LAMACOID Due 12/88 LABELS ARE MISSING FOR SOV-MS-102.
2 N/S 4. ELECTROSWITCH COVER PLATE Due 12/88 FOR 1-CH-P-1A IS WRONG.
THE LABEL SHOULD READ:
STOP /AUTO\ START INSTEAD OF TRIP /AUTO\ CLOSE 2 N/S 5* ELECTRO SWITCH COVER PLATE Due 12/88 FOR 1-CH-P-1C IS WRONG.
THE LABEL SHOULD READ:
STOP /AUTO\ START INSTEAD OF TRIP /AUTO\ CLOSE PHOTO :/t 418 2 N/S 1. LAMACOID LABEL FEEDWATER Due 12/88 PRESSURE SWITCH FOR SOV-MS-102B IS MISSING.
THIS LABEL WILL NOT FIT ON THE PANEL WHERE IT IS SUPPOSE TO. THIS IS DUE TO THE DIFFERENT STYLE MINI LIGHTS .
ATTACHMENT 5 Page 57 of 58
PRIORITY STATUS AUX SHUTDOWN ITEM[DESCRIPTION COMMENTS PHOTO :ft 418 2 N[S 2. LAMACOID LABEL FOR Due 12/88 SOV-MS-102B rs MISSING.
2 N[S 3. ELECTRO SWTICH COVER Due 12/88 PLATE FOR 1-FW-P-3B IS WRONG. THE LABEL SHOULD READ STOP/AUTO\START INSTEAD OF TRIP/AUTO\CLOSE 2 N[S 4. ELECTRO SWITCH COVER PLATE Due 12/88 FOR 1-CH-P-lB IS-WRONG.
THE LABEL SHOULD READ STOP/AUTO\START INSTEAD OF TRIP/AUTO\CLOSE.
PHOTO :ft 423 2 N[S 1. LAMACOID LABELS CONT RM Due 12/88
2 N[S 2~
& S/V PANEL ARE MISSING FOR FCV-122 SWITCH.
ELECTRO SWITCH COVER PLATE FOR GROUPE IS WRONG. THE LABEL SHOULD READ:
STOP/AUTO\START Due 12/88 2 N[S 3. BARREL WITH COVER PLATE IS Due 12/88 MISSING FOR MOV-1350.
2 N[S 4. LAMACOID LABELS SHUT AND Due 12/88 OPEN ARE MISSING FOR MOV-1350.
PHOTO :ft 424 2 N[S 1. SWTICH COVER PLATE FOR Due 12/88 HCV-MS-104 rs MISSING.
THE PLATE rs GRAY ELECTRO SWITCH SERIES 20.
2 N[S 2. ELECTRO SWITCH COVER PLATE Due 12/88 FOR GROUP A IS WRONG. THE LABEL SHOULD READ STOP/AUTO\START INSTEAD OF TRIP/AUTO\CLOSE .
ATTACHMENT 5
.Page 58 of 58
PRIORITY STATUS AUX SHUTDOWN ITEM[DESCRIPTION COMMENTS PHOTO :/t 425 2 NiS 1. SWITCH COVER PLATE FOR Due 12/88 RC 100A AND l01A IS MISSING.
THE LABEL SHOULD READ:
DISABLE II ENABLE 2 N[S 2. SWITCH COVER PLATE FOR Due 12/88 RC 1455C IS MISSING.
THE LABEL SHOULD READ:
DISABLE II ENABLE 2 NiS 3. SWITCH COVER PLATE FOR Due 12/88 1480A IS MISSING.
THE LABEL SHOULD READ:
DISABLE II ENABLE 2 N/S 4. SWITCH COVER PLATE FOR Due 12/88 RC 100B AND 101B IS MISSING.
THE LABEL SHOULD READ:
2 N[S 5.
DISABLE II ENABLE SWITCH COVER PLATE FOR RC 1456 IS MISSING.
THE LABEL SHOULD READ:
DISABLE II ENABLE Due -12/88 2 N[S 6. SWITCH COVER PLATE FOR Due 12/88 1137 IS MISSING.
THE LABEL SHOULD READ:
DISABLE II ENABLE
VIRGINIA POWER SIMULATOR SUPPORT GROUP SURRY UNIT 1 SIMULATOR
ATTACHMENT 6 CONTROL ROOM/SIMULATOR PANEL AND ENVIRONMENT COMPARISON
ATTACHMENT 6 PAGE 1 OF 15
SURRY 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, furiction and associated uni ts. - - 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 definitive simulator Physical Fidelity Comparison Report. The Physical Fidelity Comparison Report is contained in Attach~ent 4 .
ATTACHMENT 6 PAGE 2 OF 15
SIMULATED PANELS VICTOREEN RADIATION MONITORING PANELS LIQUID WASTE PANEL AMBIENT TEMPERATURE MONITOR PANEL KAMEN HIGH RANGE RADIATION MONITORING PANEL BORON RECOVERY PANEL INCORE FLUX DISTRIBUTION MONITORING SYSTEM PANEL NUCLEAR INSTRUMENTATION PANEL CONTAINMENT HIGH RANGE RADIATION MONITORING PANEL INTAKE STRUCTURE PANEL EMERGENCY DIESEL #1 PANEL.
EMERGENCY DIESEL #3 PANEL SWITCHYARD DISTRIBUTION PANEL
LOAD FREQUENCY AND HEAT TRACING PANEL VENTILATION PANEL
TURBINE SUPERVISORY PANEL REACTOR COOLANT PUMP VIBRATION*PANEL' SECONDiRY CHEMISTRY MONITORING PANEL MAIN ANNUNCIATOR PANEL VERTICAL BOARD #1 VERTICAL BOARD #2 POST ACCIDENT MONITORING PANEL BENCHBOARD #1

BENCHBOAR°o # 2
PLANT COMPUTER P-250 OPERATOR STATION SHiFT ~UPERVISOR CONSOLE (INCLUbES COM~UNICATION EQUIPMENT)
. AUXILIARY SHUTr:iOWN PANEL AUXILIARY VENTILATION PANEL
ATTACHMENT 6 PAGE 3 OF 15
NON-SIMULATED PANELS - PANELS SPECIFIC TO UNIT 2 OPERATION VICTOREEN RADIATION MONITORING INCORE FLUX DISTRIBUTION PANEL NUCLEAR INSTRUMENTATION PANEL CONTAINMENT HIGH RANGE RADIATION MONITORING PANEL EMERGENCY DIESEL GENERATOR #2 PANEL EMERGENCY DIESEL GENERATOR #3 PANEL (UNIT 2 SIDE)
TURBINE SUPERVISORY PANEL REACTOR COOLANT PUMP VIBRATION PANEL SECONDARY CHEMISTRY MONITORING PANEL VERTICAL BOARD #1 VERTICAL BOARD #2 POST ACCIDENT MONITORING PANEL BENCHBOARD #1 BENCHBOARD #2 PLANT COMPUTER P-250 OPERATOR STATION RADIATION MONITORING PANELS
ATTACHMENT 6 PAGE 4 OF 15
NON-SIMULATED PANELS - COMMON TO BOTH UNITS The~e panels have not been simulated because of the relative minor training value received from them.
METEOROLOGICAL PANEL ROBERT SHAW FIRE PROTECTION PANELS STATION FIRE PROTECTION PANELS GAS TURBINE REMOTE CONTROL PANELS - Being spared out at station FLOOD CONTROL PANEL UNIT 2 VENTILATION PANEL
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4. DIOl8. DEN H 4 42 42. TURB SuPmYlSOAY
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2. FLOOD aJNTROL 2 44 44. RECORDERS I
t'CTURIUIIIICAL DATA V-2-1 V-1-S V-1-2 SURRY CONTROL ROOH PANELS LAY OUT
<NOT TO SCALE>
FIGURE V1 (J'I
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7. IIIOIION REaJVERY "* ~ J l
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4. UASTI: DllPOS.11.. 11. on E 17. JNUICE STRUCn.11£ Ill. IIA$ TURII ~
IS 17 18 Ill ID. DIDIO !;EN II za. svna1YARD 21 . LOAD fREQ & HT TRAC
22. VDfT PANEL BB-1-2 215. A.C. COOL 211. OIEMISlRY RECORDERS V-1-3 v-1-2 SURRY SIMULATOR CONTROL ROOM PANELS LAY OUT CNOT TD SCALE>
FIGURE 2 u, 0\
ATTACHMENT 6 PAGE 7 OF 15
PART A PANELS VICTOREEN RADIATION MONITORING PANEL The Victoreen Radiation Monitoring Panels are backboard panels located on the Unit 2 side of centerline. ~hese panels provide control, indication and alarms for process and area radiation detectors on common.and respective unit systems. Only the 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.
LIQUID WASTE PANEL The Liquid Waste Panel is a backboard panel located on the Unit 2 side of centerline iri the main control room. It is a common panel being 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 reference plant .
It provides valuable training in the operation and control of common systems and coordination between backboard and control.board operations.
AMBIENT TEMPERATURE MONITORING PANEL The Ambient Temperature Monitoring Panel is a backboard
panel located on the Unit 1 side of centerline in the main control room. It is a comm6n panel being shared with both Unit 1 and Unit 2 . The panel contains the controls, indications and alarms for various areas shared by both units. The Ambient Temperature Monitoring Panel is fully simulated with the exception that input to values of indicated temperature is performed via Instructor input from SIMLOCH.
It provides minimal training value due to the operation data being displayed .
ATTACHMENT 6 PAGE 8 OF 15
KAMEN HIGH RANGE RADIATION MONITORING PANELS The Kamen High Range Effluent Monitoring Panel is a backboard panel which is located at approximately centerline between both units. This panel provides indication and diagnostic features for raqiological releases from various flowpaths. Only the reference plant, Unit 1, portion of the panel is simulated.
The panel provides minimal training value, therefore, only operational data is displayed. Diagnostic information is not simulated.
BORON RECOVERY PANEL The Boron Recovery Panel is a backboard panel located on the Unit 1 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 watei systems.
This panel is fully simulated and located identical to the reference plant. It provides training in the operation of boron recovery systems and promotes improved coordination bet~een the backboard operator and the control room ope_rator.
INCORE FLUX DISTRIBUTION PANEL The Incore Flux Distribution Panel is a backboard panel located on the south rear wall of the main control room adjacient to the Boron Recovery panel. This panel is fully simulated for the reference plant. It contains the controls and indications used for the incore system operations under normal and abnormal conditions.
This panel provides training on the operation of the incore flux drive system and in diagnosing changes in neutron flux patterns .
ATTACHMENT 6 PAGE 9 OF 15
NUCLEAR INSTRUMENTATION PANEL The-Nuclear Instrumentation Panel ia a backboard located on the Unit 1 side in the main control room. It contains the controls, indications, and alarms which allow the operator to monitor the plants nuclear power level.
This panel is fully simulated and located identical to the reference plant. It provides significant training in the operation of the nuclear instrumentation system. It also deveiopes coordination between the backboard operator and the control room operator.
CONTAINMENT HIGH RANGE RADIATION MONITORING PANEL The Containment High Range Radiation Monitoring Panel is located along the backboards next to th~ Intake Stiucture Panel. The panel contains ~ontrols and indications for only
-unit 1 containment radiation
. conditions. Unit 1 monitors.
are functional and fully simulated. The Unit 2 panel provides no training value and is not simulated. The panel provides valuable training during accident conditions by displaying containment conditions .
INTAKE STRUCTURE PANEL The Intake Structure Panel is a backboard p~nel located on the south rear wall of the control room adjacent to the Containment High Range Radiation Monitor Panel. This is a common panel which 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.
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 simulated. Each panel, #1 and #3, is fully simulated and provides significant training in the operation of electrical generators .
ATTACHMENT 6 PAGE 10 OF 15
SWITCHYARD DISTRIBUTION PANEL The Switchyard Distribution Panel is a backboard panel located on the west side of the main control room.
common panel shaied between both units.
It is a 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 FREQUENCY AND HEAT TRACING PANEL The Load Frequency and Heat Tracing Panel is a backboard panel located on the west side of Unit 1 adjacent to the Switchyard Panel. This panel is simulated only to the extent of current scope of simulation, providing only minimal training value.
VENTILATION PANEL The Ventilation Panel is a backboard panel located on the west side of Unit 1 adjacient to the Load Frequency and Heat Tracing Panel. It contains controls for ventilation equipment for both Unit 1 and Unit 2. The Unit 1 ventilation equipment is fully simulated . The Unit 2 veDtilation equipment is partially simulated with c6ntroi features to ensure the reference plant system is complete.
The panel provides training in plant systems and components. It also develops coordination. between the backboard operator and the control room operator.
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.
RCP VIBRATION MONITORING PANEL The Reactor Coolant Pump Vibration Monitoring Panel is located on the north west side of the main control room adjacient to the Turbine Supervisory Panel. The RCP vibration monitoring panel ~s fully simulated for the reference plant in that it provides the calculated vibration
indication under normal and abnormal conditions .
ATTACHMENT 6 PAGE 11 OF 15
SECONDARY CHEMISTRY MONITORING PANEL The Secondary Chemistry Monitoring Panel is a backboard panel which is located on the west side of the control room.
This panel is presently undergoing major modifications due to design change in the reference plant and is not presently fully simulated at this time.
MAIN ANNUNCIATOR PANEL The Main Annunciator Panels are located ~bove the main control board vertical sections. There- are eleven panels each consisting of sixty four "windows", except panels "E" and "F" which have eighty "windows". The panels provide indication of circuit status, permissives, and ala~ms 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.
The only physical difference between the control room and simulator room involve mino~ items such as letter size and or wording. These have been identified by the annual physical fidelity review .
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 various safeguards and primary plant systems. This panel is fully simulated and located in the identical position in the simulator control room and provides operator training in the control and monitoring of the safeguards and primary plant systems .
ATTACHMENT 6 PAGE 12 OF 15
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 systems. Each of the systems monitored is fully simulated, therefore, the instrumentation and controls of this panel is fully simulat~d. 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 instrumentation in the operations and control of major plarit systems.
POST ACCIDENT MONITORING PANEL The Post Accident Monitoring Panel is located to the left of the bench board #1 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 simulation. The panel provid~s valuable training in past accident conditions in analysis and recovery and is located identical to the main control room.
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 simulat~d panel. Only the reference plant Unit 1 panel is simulated. This panel provides a major portion of operator simulator training.
Only minor cosmetic discrepancies are known and they are identified in the annual physical fidelity comparison report in Attachment 4.
BENCH BOARD #2 The Main Control Room Benchboard Number 2 is th~ 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, 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.
ATTACHMENT 6 PAGE 13 OF 15
PLANT COMPUTER P-250 OPERATOR STATION The Plant Computer P-250 Operator Station is located opposite the operators main control console. It is used to monitor plant st~tus ~nd 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 SUPERVISOR'S CONSOLE The Shift Supervisor's 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, have the hardware installed, but is not operational.
AUXILIARY SHUTDOWN PANEL
The Auxiliary Shutdown Panels are located in the emergency switchgear room of its respective unit. This panel provides independent remote control of vital system components for the safe shutdown of the plant. Only the reference plant Unit 1 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.
AUXILIARY VENTILATION PANEL The Auxiliary Ventilation Panel is located between Unit Vertical Board 2 and Unit 2 Vertical Board 1. It contains controls for ventilation equipment for both Unit 1 and Unit
2. The Unit 1 ventilation equipment is fully simulated.
The Unit 2 ventilation equipment is partially simulated with control features to ensure the reference-plant system is complete .
ATTACHMENT 6 PAGE 14 OF 15
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.
These differences have been reviewed and found to have no impact on training, and that the simulator is acceptable foi operator trainirig and testing.
The main control room florescent lighting is established with a continuous honey cone false ceiling panel which dispurses the light through out the room. The Simulator uses a solid tile false ceiling due to air conditioning requirements. This causes a different dispersion of the lighting. Overall the effect is that the simulator lighting appears*to be brighter.
The main control room has been recently recarpeted.
The carpet change is schedule for completion on the si~ulator by the end of 1988.
The main control room has recently replaced the chairs used by the operating staff with bnes that are a different color than those in the simulator .
. , The main control room has bracket type emergency lighting fixtures which can be redirected to enhance certain areas of the control room. The Simulator uses a stationary fixture which is set into the ceiling.
The control room has a digital clock installed over the Auxiliary Ventilation Panel which is not installed in the simulator.
Floor riser sections are installed on both the east and west ends of the bench .board which phys;cally raises the floor height approximately four inches with a sloping grade of 45 degrees. The simulator floor is level through out, but is schedule for modification by the end of 1988.
The control room has a bookcase provided next to the Containment High Range Radiation Monitoring Panel. Due to the location of the entrance way into the simulator space is not ava~lable fbr this bookcase. There is a substitute bookcase provided in the simulator on the east end of the benchboard .
ATTACHMENT 6 PAGE. 15 OF 15
There are television screens in the control room to monitor the movement and operation of personel in and around the Control Room Annex, Auxiliary Shutdown Panel and Fuel Building. These are not provided in the simulator, but are being evaluated for implementation on the simulator.
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 being evaluated for implementation on the simulator .
VIRGINIA POWER SIMULATOR SUPPORT GROUP
SURRY UNIT 1 SIMULATOR
. ATTACHMENT 7 SIMULATOR UPGRADE
ATTACHMENT 7 Page 1 of 1
System SIMULATOR UPGRADE SCHEDULE Phase A Phase B
1. Residual Heat Removal 10/31/87
04/15/88
2. Neutron Shield Cooling 10/31/87 06/26/88
3. Component Cooling Water 11/30/87 06/26/88
4. Recirc Spray 11/30/88 06/26/88
5. Spent Fuel Pit Cooling 11/30/87 07/21/88
6. Heating & Ventilation 12/31/87. 09/01/88 7 Main Generator 12/31/87 09/01/88
8. Rod Control 02/15/88 09/30/88
9. Instrument Air *02/29/8£ 1 0(1.S/8£ 1 0. Service Air 02/29/88 10/31/88 11* Circulating Water 03/31/88 11/15/88 12 . Extraction Steam 03/31/88 11/15/88 13 . Reactor 04/30/88 11/30/88 1 4. Steam Generator Blowdown 05/31/88 12/15/88 1 5. Bearing Cooling 05/31/88 12/31/88 16 Lube Oil 05/31/88 01/15/89 17 . Gland Steam 06/30/88 01/31/89 18 . Electro-hyraulic control 06/30/88 02/15/89 1 9. Plant Computer 07/15/88 02/28/89
20. Turbine 08/31/88 03/31/89
21. Boron Recovery 09/30/88 04/05/89
22. Liquid Waste 09/30/88 04/15/89
23. Hydrogen Control 10/30/88 04/30/89
24. Gaseous Waste 10/30/88 05/02/89
25. Station Vent (Air Ejectors) 11/15/88 06/05/89
26. Steam Drains 11/15/88 06/05/89
27. Gasified Drains 11/30/88 06/26/89 28 . Building Drains 12/15/88 06/26/89
VIRGINIA POWER SIMULATOR SUPPORT GROUP SURRY UNIT 1 SIMULATOR ATTACHMENT 8 DISCREPANCY BACKLOG/AND RESOLUTION SCHEDULE
ATTACHMENT 8 Page 1 of 23 The attached discrepancy list contains all currently open discrepancies (SMR's) excluding preventive maintenance and miscellaneous routine maintenance items. Each discrepancy has been assigned a priority in accordance with current Virginia Power simulator maintenance guidelines.
Each SMR also has ari assigned completion date and primary area of responsibility .
ATTACHMENT 8 Page 2 of 23
SMR NUMBER SYS AN DESCRIPTION MAKE THE NECESSARY SCHEDULED COMPLETION DATE 09/15/88 2 PRIORITY 8607171101 SOFTWARE CHANGES TO IMPLEMENT ANNUNCIATOR RESPONSE. ENSURE STATION HAS IMPLEMENTED PRIOR TO MAKING THIS MOD.
8809200948 AS WHEN TV-SV-102A IS 10/30/88 2 STROKED OPEN WITH NORMAL LINE UP (TV-SV-103 OPEN, TV-SV-102 OPEN)
CONTAINMENT PRESSURE DECREASES RAPIDLY AND MODEL GOES TO UNSTABLE CONDITIONS.
8706250859 BC NEED TO MODEL LOGIC FOR 12/31/88 3 LCV-BC-100 - VALVE IS CURRENTLY INSTRUCTOR CONTROLLED FROM SIMLOCH
- ONLY (VA-RIABLE -NAME -
VLBC 1000) SYSTEMATIC UPGRADE -- EVALUATE FURTHER.
8805240820 BC THE "A" BC PUMP 12/31/88 3 APPARENTLY DOES NOT DEVELOP DISCHARGE PRESSURE AS THE "B" BC PUMP STARTS AUTOMATICALLY ON LOW HEADER PRESSURE WITH THE "A" BC PUMP ON.
8808221258 BC BEARING COOLING HEAT 12/31/88 3 EXCHANGERS REPLACEMENT
-UPGRADE HEAT EXCHANGER RATING.
760030 BD S/G BLOWDOWN COOLING 12/15/88 3 SYSTEM MOD.
820026 BD SG BLOWDOWN TANK 12/15/88 3 REMOVAL
ATTACHMENT 8 Page 3 of 23
SMR NUMBER SYS DESCRIPTION SCHEDULED COMPLETION DATE PRIORITY 8602141535 BD SG ON-LINE CHEMISTRY 12/15/88 3 MONITORING SYSTEM UNIT 2.
WILL REQUIRE REMOVAL OF OLD RECORDERS AND INSTALLATION OF 2 NEW L & N SPEEDOMAX 1650 AND 1 NEW L & N SPEEDOMAX 100 RECORDER. BLANKS FOR UNUSED RECORDER HOLES WILL BE NECESSARY.
8703130104 BD DC 82-022 STEAM GENERATOR 12/15/88 3 BLOWDOWN TRIP VALVE REPLACEMENT (UNIT 1 & 2).
VERIFY CHANGE IN VALVE SIZE AND STROKE TIME HAS BEEN INCORPORATED VIA SCOPE REVIEW. (RETAIN DOCUMENT) 8803291115 BD THE BLOWDOWN COOLERS DO 12/i5/88 3 NOT INTERFACE WITH THE CONDENSATE SYSTEM. THE CN FLOW PROGRAM CALCULATES CNW234 AS FLOW THROUGH THE COOLERS AND SGBLDN CALCULATES AND USES SGW902 AS CN FLOW THROUGH COOLERS.
8705041004 CA PERMANENT INSTALLATION 10/31/88 2 OF 1-SA-TK-2 AND THE ATLAS-COPCO AIR COMPRESS-OR 1-SA-C-2.
8801081215 CH IT IS DIFFICULT TO CHANGE 11/15/88 2 SWITCH POSITIONS. THE SWITCH WAS DISASSEMBLED AND ADJUSTED. IT WORKS BETTER BUT IS STILL STIFF.
THE FOLLOWING SWITCH PARTS NEED TO BE ORDERED:
WESTING HOUSE OT2SA CAM 11 OPERATOR, OT1C CONTACT BLOCK DPDT. NOW THESE SWITCHES WERE REPLACED BY CUTTER HAMMER STYLE AS PER
PLANT. PTL 07/08/88 WILL ORDER SWITCH.
ATTACHMENT 8 Page 4 of 23
SMR NUMBER SYS DESCRIPTION SCHEDULED COMPLETION DATE PRIORITY 8806301616 CH THE CHARGING PUMPS OVER- 10/30/88 2 CURRENT LOGIC SHOULD BE REMOVED FROM F.LOADS AND MERGED INTO THE CH SYSTEM.
8803281942 cw NEED TO MODEL FLOW 11/15/88 2 THROUGH UNIT 2 CIRC WATER PUMPS 8805030902 cw CONTROL SWITCH FLIP UP 11/15/88 2 COVERS UNDER REVIEW AS OF 05/03/88.
8802180831 DA EVALUATE DA PUMP 09/23/88 CONTROL/SURRY -- UNITS 1 AND 2 ADDS TIME DELAY RELAY FOR 1-DA-P-38.
8809142117 ED NEED TO DEVELOP SPEED 11/30/88 2 DROOP CAPABILITIES FOR EDG .
8506211200 EH EHC CONTROL SYSTEM 09/16/88 1 RETURNED TURBINE TO 61%
AFTER REDUCING IT TO 50%
NO OPERATOR ACTION. LIMITER WENT FROM 70% TO 85% WHEN P25 WAS SOLID WITH LIQUID AND VAPOR TEMP= AS P25 LEVEL WAS SLOWLY DECREASED NO CHANGE IN PRESSURE WITH
-75% LEVEL. THEN PRESSURE.
8508151537 EH WHEN DROP LOW WORTH ROD 09/16/88 GET IRPI R/B (LOAD FIRST)
ONLY ... OK. BUT THE LIMITER IS REDUCING FIRST STAGE WELL BELOW THE 70% VALUE WHEN THE R/B IS SUPPOSED TO STOP GOING DOWN TO -40%.
THIS IS PROBABLY RELATED TO AN EARLIER SMR.
8608250820 EH IMPLEMENT PUMP 02/15/89 3 CHARACTERISTICS WHEN PUMPS HAVE BEEN INSTALLED AT STATION AS SCOPE OF
SIMULATION REQUIRES .
ATTA,CHMENT 8 Page 5 of 23
SMR NUMBER SYS DESCRIPTION SCHEDULED COMPLETION DATE PRIORITY 8707311451 EH THE SEMI-VITAL BUS POWER 02/15/89 3 FEEDS TO THE EH CONTROL SYSTEM NEED TO BE MODELED.
THESE ARE SEMI-VITAL BUS BREAKER #20 AND AC-DISTRIBUTION PANEL BREAKERS 12,13 AND 14.
8602141606 EL CURRENTLY ALL RECORDERS 01/31/89 3 CONTINUE TO OPERATE DURING LOSS OF POWER SIMULATION. PROVIDE HARDWARE AND SOFTWARE NECESSARY TO ACTUALLY DENERGIZE THE RECORDERS FOR PROPER SIMULATION.
RECORDER POWER SHOULD BE DEENERGIZED WHEN THE SIMULATOR IS SHUTDOWN.
8801081200 EL NEED TO VERIFY EACH AND J0/20/88 2 EVERY LOAD COMING OFF OF THE SEMI-VITAL BUS (SEE ATTACHMENTS FOR MORE INFO).
OPS NEEDS TO WORK WITH SOFTWARE ON IDENTIFYING ALL THE LOADS AND IF THEY ARE SIMULATED.
8804130951 .EL OP-2.1.1 HAS BEEN CHANGED 11/01/89 3 TO INCLUDE A STEP TO STARTUP THE MAIN XFMR COOLING SYS JUST PRIOR TO TURBINE S/U. THIS IS VISIBLE TO THE CRO BY THE ALARM KF2 CLEARING. NEED A FEDS BLOCK WHICH FAKES THE COOLING SYSTEM BY CONTROLLING THE ANNUNCIATOR.
8806280800 EL DECOMMISSIONING OF SUPV. 12/31/88 3 CONTROL MASTER STATION COMBUSTION TURBINE GENERATOR. ADDS "SPARE" LABLE TO PANEL .
ATTACHMENT 8 Page 6 of 23
SMR NUMBER 8808191346 SYS EL DESCRIPTION WITH 1H BUS DEENERGIZED SCHEDULED COMPLETION DATE 10/15/88 PRIORITY 2
(SEMIVITAL DEENERGIZED)
THEN TRIP UNIT, THE GEN MOTORING STATUS LIGHT CAME ON UNTIL OUTPUT BREAKERS OPENED.
THIS IS INCORRECT AS THE LIGHT IS POWERED FROM SV.
8808262100 EL UPDATE LOAD LISTS TO 09/10/88 REFLECT RECENT PLANT LOAD LIST CHANGE.
8808311555 EL WHEN OPEN BREAKER 15J1 09/30/88 FROM FED'S IT APPEARS LIKE POWER IS LIST TO THE "B" AFWP, THE CORRECT POWER SUPPLY IS 4160V.
8809200944 EL UPON LOSS OF VOLTAGE 10/30/88 2 TOH AND J BUS DUE TO EDG FAILURE IF POWER IS AVAILABLE VIA NORMAL SUPPLY - NEED TO MODEL 15H8, 15J8 CAPABILITY TO BE CLOSED ON DEAD BUS
- 15 SEE T/D.
770052 ES AUTOMATIC EXTRACTION 03/31/89 3 STEAM SHUTOFF 8805240943 ES NEED CAPABILITY TO 11/15/88 2 REMOVE/REINSTATE THE "SEAL IN CONTACTS" FOR MOV-ES-100, FROM PEDS.
8708271627 FP PROVIDE SW & HW FOR FIRE 10/31/88 2 PUMP SWITCHES FP-P-1 &
FP-P-2.
8804261206 FW NEED MALFUNCTION FOR LEAK 06/30/89 3 FROM AFW HEADERS.
8806301402 FW THE FEEDWATER PUMPS 11/30/88 2 OVERCURRENT LOGIC SHOULD BE MOVED FROM F.LOADS AND MERGED INTO THE FW SYSTEM .
ATTACHMENT 8 Page 7 of 23
SMR NUMBER 8809221130 SYS FW DESCRIPTION NEED TO UPDATE FW SYSTEM SCHEDULED COMPLETION DATE PRIORITY 10/30/88 2 SO AS NOT TO "CREATE" WATER
'AT THE FEED WATER FLOW NETWORK NODE NEXT TO STEAM GENERATORS. THIS WATER SHOWS UP IN SG AS A BIG "SWELL" IN SG LEVELS.
8804130832 GM OP-2.1.1 HAS BEEN CHANGED 10/31/88 TO REQUIRE THE OPERATOR TO OPEN THE MAIN GENERATOR MANUAL DISCONNECT AND CYCLE THE GENERATOR OUTPUT BREAKERS JUST PRIOR TO SYNCHRONIZATION TO GRID, NEED TO HAVE 2 DISCONNECT MODELED, ACCESSIBLE FROM PEDS.
8806021324 GM EPH ON LINE OVEREXCITATION 10/31/88 RELAYING MOD .
8806291300 GM THE PROCESS MODEL FOR EL 10/31/88 SYSTEM NEEDS TO BE UPGRADED TO COMPLETE THE SYSTEMATIC UPGRADE OF THE EL SYSTEM. ONLY LOGICS HAVE BEEN DONE UNTIL NOW.
840032 GW RADIACTIVE GAS HOLD-UP 10/30/88 2 TANK PRESS INST. CHANGES PI-GW-102 A,B,C AND D SCALES FROM 0-150 PSIG TO 0-225 PSIG.
8607170830 GW NO IMPACT, BUT TRACK AND 10/30/88 2 VERIFY WHEN INSTRUMENT HAS BEEN PROCURED UNDER A DCP FOR THE SIMULATOR THAT SIMULATOR RESPONSE IS UNAFFECTED. **NO INSTRUMENT (NEW) WAS PURCHASED UNDER THIS EWR. A DISAGREEMENT AS TO THE CLASSIFICATION (CAT I. VS. CAT II .
ATTACHMENT 8 Page 8 of 23
SMR NUMBER SYS DESCRIPTION SCHEDULED COMPLETION DATE PRIORITY 8607170900 GW MAKE THE NECESSARY CHANGES 10/30/88 2 AS INDICATED IN EWR. VERIFY THIS PROCEDURE HAS BEEN COMPLETED IN THE STATION PRIOR TO IMPLEMENTATION.
THIS EWR HAS NOT BEEN COMPLETED IN THE STATION AS PER PETE DEWITT (OPERATIONS).
THIS WILL BE ON HOLD PER BEN DELAMORTON.
8701012148 GW REVISION TO WASTE GAS 10/30/88 2 DECAY 02 ANALYZERS -
VERIFY OPERATION OF HIGH 02 CONCENTRATION ANNUNCIATION (WD-C9).
8712020951 GW WASTE GAS DECAY 02 10/30/88 2 ANALYZERS/SURRY/1&2 PROVIDE MEANS FOR ALARM TO BE DEFEATED IF 02 ANALYZERS ARE IN STAND BY.
8806301610 GW NEED TO CHECK THE 05/02/89 3 RESPONSE OF PROCESS VENTS BASED UPON INPUTS FROM THE GW SYSTEM.
8508121415 HV RESEARCH AND IMPLEMENT 10/31/88 2 (FOR VENT DYNAMICS)
(1) ACTUAL VOLUMES OF BUILDINGS, (2) HUMIDITY AFFECTS ON THE BUILDING AIR PRESSURES AND ENERGY BALANCE. (3) DIFFERENT COMPARTMENTS OF THE BUILDING FOR CORRECT OR RESPONSE OF LEANS.
8710141103 HV NEED FLAGS TO "OPEN 10/31/88 2 BREAKER" FOR FOLLOWING:
MOV100A,B,C,D; MOV102; MOV101 - THESE ARE ON VENT PNL & ARE CONTAINMENT PURGE RELATED .
ATTACHMENT 8 Page 9 of 23
SMR NUMBER SYS DESCRIPTION SCHEDULED COMPLETION DATE PRIORITY 8801081441 HV ADDITION OF CONTROL ROOM 12/31/88 2 02 ANALYZER. PERMANENT ANALYZERS NOT !~STALLED AS OF 05/19/88. NEED TO HAVE EWR INSTALL IN SIMULATION.
8803282141 HV NEED TO MODEL POWER 10/31/88 2 SUPPLY FOR A AND B HYDROGEN RECOMBINERS WHEN INSTALLED IN THE SIMULATOR.
86002 IA SERVICE AND INSTRUMENT 10/31/88 AIR COMPRESSORS 790053 IA EMERGENCY POWER SUPPLY 10/31/88 2 PORV NEED TO MODEL BOTTLED AIR TO PORV .
8601201050 IA INCORPORATE INTO IA SYSTEM PROGRAM INDIVIDUAL AIR BOTTLE RESERVOIRS FOR UNIT ONE PNEUMATIC VALVES AS PER ATTACHED LIST IN EWR 86-003.
10/15/88 2 8607071250 IA INCORPORATE THE VOLUME 10/15/88 2 CHANGES AS THE SCOPE OF SIMULATION FOR THE AIR SYSTEM REQUIRES.
8607171550 IA DURING INPLANT LOSS OF 09/30/88 2 IA, THE MSLTV's DID NOT CLOSE WITH IA PRESS>
30 PSIG, MFWRV's SHUT ABOUT 40 PSIG, FCV 113 AND 114B WERE FAILED<
30 PSIG, TV1204 SHUT ABOUT 60 PSIG. NEED TO EXAMINE/CHANGE SIMULATOR SOFTWARE AFTER EVALUATION OF PLANT DATA.
8511050901 IC NEED SUPERVISORS CONSOLE 09/30/88 2 COMMUNICATION SYSTEMS
HOOKED UP TO TALK TO INSTRUCTOR CONSOLE.
ATTACHMENT 8 Page 10 of 23
SMR NUMBER SYS DESCRIPTION SCHEDULED COMPLETION DATE PRIORITY 8512061515 IC NEED MALFUNCTION 12/31/89 3 CAPABILITY TO FAIL ANY MAJOR CONTROL-PROTECTION SYSTEM TRANSMITTER.
8512061519 IC NEED GENERIC CONTROL 12/31/89 3 SYSTEM MALFUNCTION CAPABILITY.
8512061523 IC NEED CAPABILITY TO PLACE 12/31/89 3 PROTECTION SYSTEM BISTABLES IN TRIP MODE.
8601300544 IC SEE ATTACHED PRINTED 12/31/88 3 SCREEN. THIS HAPPENS NOW AND THEN.
8602130945 IC MANY SYSTEM DESCRIPTORS 12/31/88 3 MISSING, C SG B/D PCV MISSING FROM PAGE 2 OF BO SYSTEM .
8801151200 IC MCU EXER DAC TEST SHOULD 12/31/88 3 BE SELECTED TO +10 OR OVDC-+lOVDC. WHEN I USE THIS NOW THE INDICATOR WILL DRIVE TO -lOVDC. THIS MAY POSSIBLY DAMAGE THE DEVICE.
750016 LO EMERGENCY TURBINE OIL 01/15/89 3 PUMP START ON LOSS OF AC POWER.
8805180833 LO REPLACEMENT OF L.O. 01/15/89 3 CONDITIONER. EVALUATE DURING SYSTEMATIC UPGRADE FOR CHANGES TO SCOPE OF SIMULATION.
76002 LW LIQUID WASTE TREATMENT 09/30/88 2 UTILIZING DISPOSABLE IX'S HOLD FOR LW UPGRADE.
800087 LW CONTAMINATED LAUNDRY 09/30/88 2 DRAIN TANK .

~-----~~- - -~-

ATTACHMENT 8 Page 11 of 23
SMR NUMBER 830058 SYS LW DESCRIPTION CONTAMINATED LAUNDRY SCHEDULED COMPLETION DATE 04/19/89 PRIORITY 3
FACILITY - PIPING MODIFICATION TO CONNECT LW, CDT, LAUNDRY DRAINS TANK.
8602121610 LW VERIFY THAT DRAIN FLOW 09/30/88 2 FROM BORIC ACID TANKS CH-TK-1A AND CH-TK-1B
( CVW4 1 1 ( 1 ) & ( 2 ) GOES TO HI LEVEL WASTE ORN TANKS.
8606061510 LW MAKE NECESSARY S/W 09/30/88 2 CHANGES TO INCORPORATE RANGE, SETPOINTS AND DENSITY CHANGES AS APPROPRIATE.
8707301212 LW REMOVAL OF CHECK VALVE 09/30/88 2 1-LW-339. RE-EVALUATE DURING SYSTEMATIC UPGRADE.
8709091112 LW EVALUATE CALIBRATION OF 09/30/88 2 LOST LEVEL INDICATION.
VERIFY DURING SYSTEMATIC UPGRADE.
8709091315 LW EVALUATION OF LW PIPING - 09/30/88 2 REMOVES CHECK VALVE TO ALLOW TRANSFER BETWEEN BR-TK-2A, 2B AND 1-LW-TK-3A, 3B 8806301611 LW NEED TO CHECK THE 04/15/89 3 RESPONSE OF RM-LW-108 MONITOR BASED UPON THE INPUTS FROM LW SYSTEM.
8809121324 LW UPDATE DATA BASE AND 09/30/88 SOFTWARE FOR MX401100, BITS 5 AND 6, VARIABLE NAMES W00115 AND W00116.
740015 MI FLOODING CONTROL OF 12/31/88 2 SAFETY RELATED
ATTACHMENT 8 Page 12 of 23
SMR NUMBER SYS MI DESCRIPTION APPENDIX R EMERGENCY SCHEDULED COMPLETION DATE 12/31/88 PRIORITY 2
84002 COMMUNICATIONS 8508221314 MI WE NEED TO INVESTIGATE 12/31/88 3 THE FEASIBILITY OF REARRANGING THE DATA BASE TO MAKE IT LOGICAL; ANSWERING THE FOLLOWING QUESTIONS: (1) SCOPE OF WORK, (2) IMPACT, (3) TIME REQUIRED, (4) STRUCTURE OF NEW DB<- DESIGN TIME.
8604081602 MI REVISE MALFUNCTION NAMES 12/31/88 3 TO CONFORM TO STANDARD NAMING CONVENTION, I.E.
SYSTEM DESIGNATOR, EQUIPMENT, ETC.
8605081230 MI USEFUL INFORMATION 12/31/88 3 RELATING TO BISTABLE TRIP SWITCHES. USE AS NEEDED IN APPLICABLE CONTROL PROGRAMS. WHERE USED BE SURE TO REFERENCE THIS EWR IN DOCUMENTATION. WHEN NEEDED INFORMATION IMPLEMENTED, COMPLETE THIS SMR.
8607310920 MI CURRENTLY SPRING R~TURN 12/31/88 3 TYPE SWITCHES ARE NOT CHECKED IN IC CHECK.
INCORPORATION OF THESE SWITCHES INTO IC CHECK WOULD MAKE HARDWARE CHECK FASTER AND EASIER THAN USING CONTROL ROOM DIAGNOSTICS DI MONITOR TEST .
ATTACHMENT 8 Page 13 of 23
SMR NUMBER SYS DESCRIPTION SCHEDULED COMPLETION DATE PRIORITY 8703130108 MI DC 82-028A SHORT TERM 09/23/88 LOOSE PARTS MONITORING SYSTEM (UNIT 1) VERIFY THIS ALARM HAS BEEN INCORPORATED VIA SCOPE REVIEW FOR DC AND STEAM GENERATOR.
8801291400 MI THE RAMCARDS FILE NEEDS 12/31/88 2 TO BE REDONE TO CORRECTLY REFLECT OUR CURRENT I/0 CONFIGURATION, SPECIFICALLY, ALL OF THE MUX NAMES NEED TO BE CHANGED TO REFLECT THE PROPER AND CURRENT I/0 NAMING CONVENTION.
8801291515 MI MODIFY THE MCU SOFTWARE 12/31/88 2 (FORMAT, RAMBLD, AND PNLPOOL) AS NECESSARY TO PROVIDE FOR HANDLING OF THE AO IN THE SAME MANNER AS THE DI's AND DO's. (I.E.
SO EACH AO POINT DOES NOT HAVE TO BE IN THE RAMCARDS FILE).
8801291520 MI SINCE AI CARDS HAVE 64 12/31/88 2 POINTS ON THEM, ALL 64*
OF THESE POINTS SHOULD BE IN THE DB AS WELL AS IN RAMCARDS. THE AI POINTS ADDED AS SPARES SHOULD BE NAMED AS AICOMN SP1 ...
8803301300 MI WHEN PLACING FAILED 10/01/88 2 INSTRUMENT CHANNELS IN TRIP NEED CAPABILITY TO SET ANNUNCIATOR DES SIMILAR TO HOW WE HANDLE THE RACK DOOR ALARMS.
8805270900 MI RAM DATA FAILED WHEN SIM 12/31/88 3 STARTS UP. TROUBLE SHOOTING AND REWORK ARE REQUIRED .
~ - - - - - - - - - - - - ~ - - - - - - --~- - - - - - - --
ATTACHMENT 8 Page 14 of 23
SMR NUMBER SYS DESCRIPTION SCHEDULED COMPLETION DATE PRIORITY 8808291442 MI VERIFY STROKE RATES FOR 09/10/88 THE VALVES FOR THE PT'S LISTED ON THE ATTACHED LIST.
8809281529 MI LIBRARY FUNCTION RPPI 11/30/88 2 NEEDS TO INCLUDE POWER SUPPLY DEPENDENCY FOR SECTION WHICH SIMULATED LOCAL CONTROLLERS (CONTROLLER INDEX >=70).
8809291400 MI INSTALL ESD PANEL JACKS 10/15/88 ON 87 COMPUTER SYSTEM.
AND THE 27 SYSTEM.
8809291430 MI IMPLEMENT SHARED MEMORY 10/31/88 INSTALLATION SPS BETWEEN 8780 AND 2750 COMPUTER SYSTEMS .
8809292050 MI UPDATE SPS BIT BOOKS 12/31/88 2 FOR DO'S TO REFLECT J1 AND J2 CONNECTORS.
8809292051 MI UPDATE SPS BIT BOOK FOR 12/31/88 2 DI'S TO REFLECT J1 AND J2 CONNECTORS.
8809292052 MI UPDATE SPS BIT BOOKS 12/31/88 2 FOR AO'S AND AI'S TO REFLECT J1 AND J2 CONNECTORS.
8809292053 MI GENERATE SPS BIT BOOK 12/31/88 2 AMMENDMENT TO EXPLAIN NUMBERING SCHEME/SYSTEM FOR DATA-BASE VIA BIT BOOKS.
8810031212 MI RESOLVE PHYSICAL 12/30/88 FIDELITY DIFFERENCES BETWEEN SIMULATOR CONTROL ROOM ANNUNCIATORS AND UNIT 1 CONTROL.
ATTACHMENT 8 Page 15 of 23
SMR NUMBER SYS DESCRIPTION SCHEDULED COMPLETION DATE PRIORITY 8810042145 MI REVISE SIMULATOR PANEL 12/31/89 3 DRAWINGS TO REFLECT AS/BUILT CONDITIONS TO ENHANCE FUTURE H/W DOCUMENTATION AND PHYSICAL FIDELITY 8508201320 NI EXCORE NEUTRON FLUX 09/29/88 MONITOR SYSTEMS.
8705041026 NI EXCORE NEUTRON FLUX 09/23/88 MONITOR SYSTEM MODIFICATION TO ENSURE ONE TRAIN OF NI's IS AVAILABLE FOLLOWING A FIRE.
75001 PC ADD DELTA FLUX ALARMS 11/30/88 2 TO P250 COMPUTER.
8509181310 PC WHEN P-250 IS INOPERABLE 09/15/88 2 ANN. GB5 COMPUTER PRINTOUT ROD CONTROL SYS SHOULD NOT BE COMING IN. THE LOGIC FOR THIS ANNUNCIATOR SHOULD REALLY BE IN THE PRODAC SUBROUTINES.
8808081545 PC THE ADDRESS WINDOWS, 09/15/88 2 (DIGITAL DISPLAY) ON THE PRODAC CONSOLE ARE NOT WORKING PROPERLY. WINDOW ONE ALWAYS HAS A "V" IN IT.
WINDOW SIX IS ALWAYS BLANK.
WINDOW FOUR DISPLAYS A 'B' OVERLAYED WITH THE ADDRESS VALVE.
8808181100 PC LEOF DATA LINK DOES NOT 09/15/88 WORK, ALL DATA ARE ZERO.
8808241001 PC PERFORM UPGRADE OF PRODAC 11/15/88 2 P250 SIMULATION.
840067 RC PRESSURE SAF VLV LOOP 12/31/88 2 SEAL INSULATION .
ATTACHMENT 8 Page 16 of 23
SMR NUMBER SYS DESCRIPTION SCHEDULED COMPLETION DATE PRIORITY 8805171425 RC INSTALLATION OF 10/31/88 SHUTDOWN COOLING LEVEL INDICATION.
8806301601 RC THE REACTOR COOLANT PUMPS 11/30/88 2 OVERCURRENT LOGIC SHOULD BE MOVED FROM F.LOADS AND MERGED INTO THE RC SYSTEM.
N82-44 RC PI-1458 (RCS NARROW RANGE 08/31/88 PRESSURE) DIFFERS BY 50 PSIG BETWEEN PI 1-145 (LOW PRESSURE LETDOWN LINE PRESSURE) WHEN PLANT 84008 RD AUTO ACTUATION OF RX 10/31/88 TRIP BREAKER SHUNT -
ADDS RX TRIP BREAKER INDICATION.
840052 RD CONTROL ROD GUIDE TUBE 12/31/88 2 REFURBISHMENT 8710211324 RD WHEN DO SYSTEMATIC 10/31/88 UPGRADE OF ROD CONTROL SYSTEM, NEED TO MODEL URGENT FAILURES ON EACH POWER CABINET AND THE LOGIC CABINET.
8803280815 RD ALL MALF IN THE ROD 10/31/88 DRIVE PROGRAM SEEM TO ONLY SEE ONE MALF PER GROUP. PLEASE INVESTIGATE THE IMPLEMENTATION OF THESE MALFUNCTIONS.
8803300809 RD WHEN DO SYSTEMATIC 10/31/88 UPGRADE ON IRPI SYSTEM, INCLUDE A DEPENDENCE OF IRPI ON TEMPERATURE.
OBSERVED IN PLANT WITH RODS AT 225 STEPS, IRPI INDICATED 185 STEPS, TAVE WAS 345 DEGREES .
ATTACHMENT 8 Page 17 of 23
SMR NUMBER SYS DESCRIPTION SCHEDULED COMPLETION DATE PRIORITY 8508281315 RH TO PROPERLY SET THE 10/16/88 INITIAL RHR BORON CONCENTRATION, A CALCULATION SHOULD BE ADDED TO CORE AGE TO SET RHR [CS] TO CSD BORON (OR A LITTLE ABOVE) PER CURVE BOOK PP20. FOR CORE AGE= 0.0%, RHR BORON=
1500.0 PPM. FOR CORE AGE=
100.0% RHR BORON= 800.0 8712110800 RH THE P250's DISPLAY OF 10/16/88 RHR FLOW IS IMPROPERLY SCALED. IT INDICATES 2200 GPM WHEN THE VERTICAL BOARD INDICATED 4100 GPM. LOOKS LIKE SQUARE ROOT NOT BEING TAKEN .
8712110801 8712110803 RH RH RHR HXCH CC OUTLET TEMP.
RESPONDS VERY SLOWLY.
NEED BULLET ON PEDS RHR SCREEN FOR POWER (BREAKER) TO MOV1720A & B.
10/16/88 10/16/88 8807121104 RH MODEL RHR VORTEXING 10/16/88 WITHIN SCOPE OF ATTACHED EVALUATION DATA INCLUDING CHANGE IN RVLIS INDICATION TO CHANGE IN RCS INVENTORY.
8809081340 RH NEED TO RESET.THE GAS 10/16/88 MASS IN UPPER PLEUNUM TO ZERO. TAKE AWAY THE GAS MOVEMENT IN RCS.
PUT THE GAS MASS OF UPPER PLEUNUM INTO PRESSURIZER.
ALL THIS TO BE DONE WITH MINIMUM OR NO PRESSURE OR LEAD TRANSIENT.
8508281237 RM DURING TESTING OF RADDYN 09/23/88 2 AND NEW CUBORN IN SUPPORT OF ADV. RCS COULD NOT
TEST FLOW PATHS TO PROCESS MODEL. SEE ATTACHED.
~~-~~-- - - - ~ - - - ------- ~-~~ -~
ATTACHMENT 8 Page 18 of 23
SMR NUMBER SYS DESCRIPTION SCHEDULED COMPLETION DATE PRIORITY 8806020202 RM DEVELOP A 3X4 COLUMN/ROW 10/30/88 2 SCHEME TO DRIVE THE KAMAN KEYBOARDS. EXISTING KEYBOARDS WILL NOT FUNCTION FOR AN EXTENDED PERIOD OF TIME.
8808300800 RM PROCUR AND INSTALL 12/31/88 3 COMPONENTS FOR CONTROL ROOM RAD MON DETECTOR AND DISPLAY.
780036 RS RECIRC SPRAY AND LHSI 12/31/88 2 NPSH MOD.
800020 RS SERVICE WATER 10/10/88 TEMPERATURE RELIEF #1 NPSH DESIGN CHANGES.
760039 RX TC INSTALLED IN RV - 11/30/88 2 "VERIFY THERMOCOUPLE LOCATIONS MODELLED DURING SYSTEMATIC UPGRADE.
820050 RX INCORE THERMOCOUPLE 11/30/88 2 REPLACEMENT UNIT 1 8605131110 RX IMPLEMENT PROMPT-TO- 11/30/88 2 DELAYED NEUTRON RATIO FOR REACTIVITY BALANCE AS IT HAS BEEN IMPLEMENTED AT NORTH ANNA IN F.RKFLUX.
SEE ATTACHMENT 8607141220 RX RESEARCH AND IMPLEMENT 11/30/88 2 LOGIC FOR REACTOR TRIP BYPASS BREAKERS. ALSO PROVIDE THEIR CONTROL ON FEDS.
8608061005 RX IMPLEMENT THIS CHANGE 11/30/88 2 FOLLOWING ICCM DELIVERY IF NEEDED. ASSIGNMENT OF INCORE THERMOCOUPLE FOR CORE COOLING MONITOR .
~- -~--~ --- --- -~--- ~
- - --- ~ -- ---
ATTACHMENT 8 Page 19 of 23
SMR NUMBER SYS DESCRIPTION SCHEDULED COMPLETION DATE PRIORITY 8608251120 RX MAKE CHANGE IN 11/30/88 2 THERMOCOUPLE ASSIGNMENT IF SCOPE OF SIMULATION REQUIRES.
8612031600 RX INCORE FLUX MAPPING 11/30/88 2 SYSTEM HAS MULTIPLE PROBLEMS. NO RECORDERS OPERATE, DETECTOR E LIGHTS FLASH AND NO DETECTOR VOLTAGE ADJUST OPERATE PROPERLY.
8702121257 RX EVALUATE ROD WORTHS 11/30/88 2 DURING CORE MODEL UPGRADE TO INSURE PROPER VALUES PROVIDED FOR NORMAL OPERATION AND MALFUNCTION CONDITIONS.
8712161240 RX NEED TO CORRECT 11/30/88 2 THERMOCOUPLE AND RVLIS INPUTS TO ICCMS TO BE CONSISTANT WITH PLANT DATA.
880328.2146 RX NEED TO MODEL POWER 11/30/88 2 SUPPLIES FOR INCORE DRIVE DETECTORS FROM THEIR RESPECTIVE 480V EMERG MCC's.
8610020949 SA ADDITION OF SA COMPRESSOR 10/31/88 2 (1-SA-C-2B) NEED TO ADD TO SCOPE OF SIMULATION A SERVICE AIR COMPRESSOR (1-SA-C-2) WITH CAPACITY OF 346, 546 FT3/MIN. THIS WILL ALOW PROPER SIMULATION OF 1-SA-C-2 A & B. ALSO REQUIRE FAULT ON THIS COMPRESSOR TO ACTUATE ANN B-E-5.
8701261441 SA INCREASED RESERVOIR 10/31/88 2 CAPACITY ON THE SERVICE AIR SYSTEM - INSURE AIR
IS IN SCOPE FOR UNIT 1 .
ATTACHMENT 8 Page 20 of 23
SMR NUMBER SYS DESCRIPTION SCHEDULED COMPLETION DATE PRIORITY 84001 SD UNIT 1 HPHD PIPING MODS. 12/31/88 2 840019 SD MOISTURE-SEPARATER 06/05/89 3 REHEATER REPLACE NEED TO MODEL NEW REHEAT SYSTEM.
8503200002 SD SECURED LP HEATER DRAIN 11/15/88 2 PUMPS COULDN'T RESTART.
MAY BE SCALING PROBLEM BETWEEN WHAT LEVEL CONTROL LOOKS AT COMPARED TO PROCESS MODEL SUPPLIED.
SAME GOES FOR HP HEATER DRAIN PUMPS. RE-EVALUATE 11/17/86.
8602071030 SD HIGH PRESSURE HEATER 11/15/88 3 DRAIN PUMP HIGH PRESSURE TRIP.
8610021007 SD NEED TO CALIBRATE OR 09/23/88 RENORMALIZE THE NORMAL OPERATING LEVEL OF HP HTR DRAIN TANK LI-SD-111 SHOULD BE APPROX. 62%,
ALSO NEED TO RESET LOW LEVEL ALARM SETPOINT OF ANN. K-A-3 TO 51%.
8701301528 SD REQUIRE ADDITION OF 11/15/88 2 SIMULATION OF MANUAL DISCHARGE VALVES ON A AND B HIGH PRESSURE DRAIN PUMPS - FOR 1-SD-P-1A VALVE IS 1-SD-15, FOR 1-SD-P-1B VALVE .IS 1-SD-6.
8805200846 SD HP HTR DRAIN TANK LEVEL 09/23/88 2 GOES TO 100% WHEN PUMP IS SECURED. NEED TO VERIFY MODELING OF HIGH LEVEL DIVERT VALVE.
8805241442 SD 3A/3B AND 4A/4B FW HEATER 06/05/89 .3 HI LEVEL ALARMS CYCLE ON AND OFF (JC1, JD1, JE1, JF1 ). THE DIVERT VALVES
SHOULD MODULATE/CYCLE TO PREVENT THIS.
ATTACHMENT 8 Page 21 of 23
SMR NUMBER SYS DESCRIPTION SCHEDULED COMPLETION DATE PRIORITY 8808311600 SD MALFUNCTION PARTITION 06/05/89 3 SD SHOULD HAVE DESCRIPTION "SECONDARY DRAINS" VICE "STEAM DUMPS".
8804271521 SI NEED TO IMPLEMENT NEW 09/26/88 3 MALF MSI11 - PIPE LEAK AT PRESSURE NODE SIP401, DEGRADABLE 0-100% WITH 100% SIMULATING PIPE RUPTURE 100% FLOW TO CONTAINMENT.
8805240935 SI MOV1869B AND MOV1890A 11/30/88 2 PRESENTLY ARE 3 POSITION MAINTAINED SWITCHES.
THESE SHOULD BE 3 POSITION SPRING RETURN TO MID-POSITION .
8806071516 SI REVISE THE RMT VARIABLES USED IN SILOGC TO USE THE NEW VARIABLE NAMES, USING THE CS SYSTEM DESIGNATION - NOT SP.
06/01/89 3 820013 ss CONT RM HAB CHLORINE 03/31/89 3 DETECTOR 820014 ss CONT RM HAB SODIUM 03/31/89 3 ANALYZERS 8602101455 ss REPLACE CONDUCTIVITY 10/31/88 RECORDERS ON VERTICAL BOARD - 2 8703261525 sv AIR EJECTOR VAPOR/AIR 10/31/88 2 FLOW GOES AND STAYS NEGATIVE FOLLOWING A/ERM ALARM AND CLOSURE OF TV-SV-102A, EVEN AFTER REOPENING TV-SV-102A.
800054 SW ADDITION OF CHG PUMP LUBE 10/31/88 2 OIL REG VALVES (AOV) .
~---~
ATTACHMENT 8 Page 22 of 23
SMR NUMBER SYS DESCRIPTION SCHEDULED COMPLETION DATE PRIORITY 8509260932 SW THE CONTROLS/INDICATIONS 10/31/88 FOR THE RM SW PUMPS ARE INCORRECT. SEE PHOTOGRAPHS.
PUMPS 1-SW-P-6A --> 6D, 1-SW-P-SA--> SD. THIS HARDWARE EXTRA AND MISSING.
SAI (SUDIR) IS DOING S/W AS PART OF UPGRADE.
8803231015 SW NEED TO INSTALL HARDWARE 10/31/88 2 FOR SW-P-6A,B,C,D TO ALLOW SIMULATION OF THESE PUMPS AS PRESENTLY USED IN PLANT.
8803282138 SW NEED TO MODEL POWER 09/23/88 SUPPLIES FOR 1-SW-P-5A, B,C,D RAD MONITOR SAMPLE PUMPS WHEN INSTALLED IN SIMULATOR.
8806031324 SW NEED TO MODEL PROPER 09/23/88 2 POWER SUPPLY FOR 1-SW-P-5A,B,C,D.
8810031001 SW ADDS NEW B INCH SW 01/31/89 3 LINES FOR CHG PUMP SW PUMP SUPPLY - ,.
EVALUATE SCOPE OF SIMULATION.
8706250907 TU EXHAUST HOOD SPRAY 03/31/89 3 PRESENTLY MODELED IN CONDENSATE SYSTEM - HAS NO EFFECT ON L.P. TURBINE EXHAUST TEMP. SYSTEMATIC UPGRADE.
8805191227 TU WHEN OPEN GENERATOR 10/30/88 OUTPUT BREAKERS, TURBINE SPEED INCREASES RAPIDLY, SOMETIMES TO >2500 RPM.
SPEED SHOULD REMAIN APPROXIMATELY CONSTANT AT 1800 RPM. ELECTRICAL OUTPUT IS UNSTABLE ALSO .
ATTACHMENT 8 Page 23 of 23
SMR NUMBER SYS DESCRIPTION SCHEDULED COMPLETION DATE PRIORITY 8805241331 TU JF6, TURB ZERO SPEED 09/23/88 2 "BLIPS" IN WHEN INITIALLY ACCELERATING THE TURBINE DURING S/U.
8611241222 VP NEED TO SIMULATE 1-VP-1 12/30/88 3 AND 1-VP-2 CONDENSER HOGGER SUCTIONS - NOT PRESENTLY MODELED.
8602261026 VV WHEN AN MOV LOSES 12/31/88 3 ELECTRICAL POWER IT CAN STILL BE OPERATED LOCALLY, SIMILAR TO LOCAL VALVES. NEED TO PROVIDE EITHER PEDS CONTROL OF MOV's (PREFERRED) OR PLANT EQUIPMENT FILES MADE (ALTERNATIVE) TO ALLOW INSTRUCTOR CONTROL OF MOV's .
VIRGINIA POWER SIMULATOR SUPPORT GROUP SURRY UNIT 1 SIMULATOR ATTACHMENT 9 CONFIGURATION MANAGEMENT OVERVIEW DOCUMENT
ATTACHMENT 9 SSG 2.0 05/13/88 Revision 0 Page 1 of 10 SIMULATOR CONFIGURATION MANAGEMENT OVERVIEW 1 .o 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.
0 Develop and implement a plan for validation of the simulators which meets NRC and INPO requirements.
o Represent Virginia Power on, and participate in activities of, appropriate industry 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.
o Prepare responses to audits by INPO, NRC, Virginia Power, or other agencies .
ATTACHMENT 9 SSG 2.0 05/13/88 Revision O
o 0 Provide technical assistance to the supervisor and other groups within the simulator support group~
Support the Supervisor in the evaluation of Page 2 of 10 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.
o Assist the training center instructors in their use of the simulator by defining capabilities and limitations of the simulator to perform certain simulator exercises.
o Represent Virginia Power on, and participate in the activities of, appropriate industry related committees and professional societies.
0 Develop and perform tests to insure simulator response to be within or exceeds requirements 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.
o Document all simulator hardware changes.
o Review and approve procedures pertaining to hardware and software on the simulator.
o Coordinate hardware portion of NRC simulator certification.
o Assist in setting priorities for hardware section work as a function of plant changes and simulator availability.
o Direct the activities of the hardware section personnel .
ATTACHMENT 9 SSG 2.0 05/13/88 Revision 0 Page 3 of 10 2.4 Engineering Software Analyst (Simulator) o Provide inputs for software, hardware maintenance and upgrades.
o Document all simulator software changes.
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.
2.5 Administrative Assistant o Administer the handling and maintenance of records.
o Prepare, compile, and verify reports and project authorization .
0 o
Maintain documentation according to company standards.
Develop and maintain record keeping procedures.
o Assign, distribute, and coordinate typing and computer output requests.
o Direct the activities of the administration section personnel.
3.0 Definitions 3.1 Integrated Plant Test - A real time test of the response of the simulator. The specific function of this test is to monitor the inherent plant response with particular attention to system interfaces.
3.2 Malfunction Test - A real time test of the response of the simulator to normal and emergency conditions resulting from the malfunction. The specific function of this test is to verify inherent plant response and the functioning of automatic plant controls as established in the
Simulator Cause and Effects Document .
ATTACHMENT 9 SSG 2.0 05/13/88 Revision 0
Page 4 of 1 O 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 - Establishes the boundaries of Hardware and Software simulation to provide a detailed modeling of a system of the reference plant with which the operator interfaces with from the control room.
3.5 Simulator Data Base - A collection of documents that describe the current performance and standards chosen as simulator boundaries.
3.6 Simulator Modifications Report (SMR) - A report that identifies and tracks deviations in simulator performance or appearance from the current design specifications.
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 .
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.
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.
4.0 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 .
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 basis in 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 respective 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 the 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 .
ATTACHMENT 9 SSG 2.0 05/13/88 Revision 0 Page 6 of 10 4.4.3 Operating Events - NRC bulletins, notices, INPO reports, LER's and Training Impact Reports should be reviewed for possible impact on the Scope of Simulation.
4.5 Simulator Modification Planning/ Implementation 4.5*1 Reports - ln order to allow for an efficient planning of work to be performed, 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 Six Month SMR Report - Lists all the outstanding SMR's which are scheduled to be completed during the next six months. This allows for advance planning of jobs requiring large amount of time for software development or ordering of necessary hardware parts or development of testing procedures.
(Updated monthly) 4.6 Planning Meetings 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 documerited via telephone conversations or the modification report .
ATTACHMENT 9 SSG 2.0 05/13/88 Revision O
0 Page 7 of 10 Engineering Design Review Meetings - Meetings 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 software person(s) developing the modification to consider as a minimum the following:
0 Digital Input Loops 0 Analog Input Loops 0 Control Room Diagnostic Checks 0 Instructor Overrides 0 Malfunctions 0 Remote functions (PEDS) 0 Monitored Paramete~s 0 Logic Response 0 Dynamic Response 0 Steady State Response 0 Transient Response
ATTACHMENT 9 SSG 2.0 05/13/88 Revision 0 Page 8 of 10 4.7.4 Operations developes any test procedures which may be required.
4.7.5 Once the modification has been prepared, reviewed, and revised the change is then transferred to the site and installed in the development mode for initial testing.
4.7.6 Upon successful completion of the test in 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 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 generate the update package or the accuracy of the update package and associated documentation cannot be assured. It is the responsibility of the 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 being closed. A hard copy of the completed SMR is filed with the system changed by the modification .
ATTACHMENT 9 SSG 2.0 05/13/88 Revision 0 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 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 .O 6.0 Files/Procedures 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 Group to find information in the files with system designators given by other members of the group.
Simulator Support Guideline 4.6 gives further details on the filing system.
6.2 Informat~on 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 .
ATTACHMENT 9 SSG 2.0 05/13/88 Revision 0
Page 1 0 of 1 0 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 .
NRC FORM 474 U.S. NUCLEAR REGULATOIIY COMMIUION 110,861 Aeer- a,, OMI 5 5 1
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SIMULATION FACILITY CERTIFICATION f::i'&- 31 . .
~RUCTIONS. This form ,s to be filed for initial cenification, recenification (if required), and for any change to a simulation facility performance testing plan
,.... de after initial submittal of such a plan. Provide the following information, and check the appropriate box to indicltl reason for submittal.
FACILITY DOCKET NUMBER SURRY POWER STATION ~ 281 LICENSEE DATE VIRGINIA ELECTRIC AND POWER COMPANY con- it-2-. -
Thia 1110 c-""1: I. t h * - - t a c i l i l v - . .
m-1 the guocsance in ANSI/ANS 3.6. Isa. 11 -
11ceo1-. 10 the cemficl1- ot IWe O u---fully----*-*
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NIIC _ i n _ _ 10 CFll '1511* *111. II llw8 - -
NAME (ororhwidfflrifiurion/ AND LOCATION OF SIMULATION FACILITY SURRY UNIT 1 SIMULATOR, SURRY POWER STATION, SURRY, VIRGINIA AT THE END OF STATE ROUTE 652 X SIMULATION FACILITY PERFORMANCE TEST ABSTRACTS ATTACHED. /For,-rl- ,_,t:ondut:tedin rM,-iodMtlin, llllirh fMdlttof thi1e.nifit:11tlonl DESCRIPTION OF PERFORMANCE TESTING COMPLETED /Att<<:11 lddirioMl ,,_,,./1/ a , - , , , , *nd_ idlnrify tMitlffl da:riprion 1-in,t:ominu<<I/
SEE ATTACHMENT 3 OF ENCLOSED DOCUMENT X SIMULATION FACILITY PERFORMANCE TESTING SCHEDULE ATTACHED. (Forth1t:ondut:rol1ppro,c1m1fll'f 25"ofperf-raa,ur.,_forth1four-,-Pfflod eommt1nt:in with th* dltl of this t:errifiation. J DESCRIPTION OF PERFORMANCE TESTING TO BE CONDUCTED IAf!<<h 1ddirioMl ,,.,,_/1/ a 1111:-f'f, 111d idffltif'f thl iflffl dlcriprion being ,:ominUldl SEE ATTACHMENT 4 OF ENCLOSED DOCUMENT PERFORMANCE TESTING PLAN CHANGE. /Foran-, modifiarion to* -'onNnt:1 tffling p/M wbmittld on* prwi01A t:1rtifiurionl DESCRIPTION OF PERFORMANCE TESTING PLAN CHANGE (AttM:h *dditiOM/ f)lgl(I) .. ,,..,_,.,, Mid idenrif-, th* itlffl t/lxripriar being t:ontinUftlJ NOT APPLICABLE AT THIS TIME NOT APPLICABLE AT THIS TIME I certify undlf penalty of perjury thllt tt11 infor11111tton ,n 11111 TITLE DATE CARTWRIGHT VICE-PRESIDENT-NUCLEAR 11-23 *66 In accordance wit 10 CF ij 5 . Communications, this form shall be submitted to the NRC as follows:
BY MAIL ADD ESSED TO: Director, Offica of Nuclear Ructor R11JUlation BY DELIVERY IN PERSON
U.S. Nucla, R1g11latory Commitsion TO THE NRC OFFICE AT: 7920 Norfolk Avenue Washington, DC 20555 Bethesda, MD
SURRY UNIT 2 SIMULATOR CERTIFICATION SUBMITTAL
Suriy Unit 2 Certification Submittal This Surry 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)
VIRGINIA POWER SIMULATOR SUPPORT GROUP
SURRY UNIT 2 SIMULATOR ATTACHMENT 1 CONTROL ROOM/SIMULATOR PANEL AND ENVIRONMENT COMPARISON
ATTACHMENT 1 Page 1 of 7
Surry Unit 2 Certification Submittal Control Room Panel Comparison Report The Surry 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 to the operator in order to maintain an overall balanced appearance of the control room. Some minor differences exist with secondary equipment controls. These are 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 Envirohment Comparison Report, Attachment 6, of the Surry Unit 1 Simulator Certification Submittal which has been included for your convenience.
As a result of this comparison report, the Surry Unit 1 Simulator meets all Unit 2 training needs .
ATTACHMENT 1 Page 2 of 7
Control Panels Specific to Unit Two Operation Containment High Range Radiation Monitoring Panel Incore Flux Distribution Panel Nuclear Instrumentation Panel Ventilation Panel Emergency Diesel Generator #2 Panel Turbine Supervisory Panel Emergency Diesel Generator #3 Panel (Unit 2 side)
Vi6toreen Radiation Monitoring Panels SPDS Control Console Plant Computer ~-250 Operator's Cons6le Benchboard #1 Benchboard #2 Vertical Board #1 Vertical Board #2 Post Accident Monitoring Panel Secondary Chemistry Monitoring Panel Kamen Radiation Monitoring Panels
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ATTACHMENT 1 Page 4 of 7
Containment High Range Radiation Monitors The Containment High Range Radiation Monitoring Panel.
is. located along the backboards next to the Intake Structure Panel. The panel contains control~ and indications for otily Unit 2 containment radiation conditions. Unit 1 monitors are functional and fully simulated. The Unit 2 panel is identical to Unit 1 and therefore is not simulated. The panel provides valuable training during accident conditions by displaying containment conditions.
Incore Flux Distribution Panel The Incore Flux Distribution Panel contains the controls and indications used for the Incore Flux Distribution Monitoring 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.
Nuclear Instrumentation Panels The Nuclear Instrumentation Panels for thei~ respective units are identical in their appearance and controls. Only the reference plant unit one panel was simulated .
Ventilation Panel This panel contains controls and indications common to Unit 1 and Unit 2 Control Room Environment. These components are presently considered to be beyond the scope of simulation and provide very little training value.
Emergency Diesel #2 Panel The #2 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 and appearance. Therefore only the reference plant, unit one, is simulated .
ATTACH~ENT 1 Page 5 of 7
Emergency Diesel Generator #3 Panel The #3 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 plant panel is simulated.
Victoreen Radiation Monitoring Panels The Victoreen Radiation Monitoring 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) Console The SPDS,Console contain the CRT Monitor and keyboard functions to monitor the respective unit~ vital parameters.
Their operations are identical, therefore only the reference plant unit one console is simulated.
Plant Computer P~250 Console The Plant Computer P-250 Operator Cohsole for each unit is identical to each other in their features and controls.
Only the reference plant unit one computer console is modeled .
ATTACHMENT 1 Page 6 of .7
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.
Benchboard :/t2 The main control room Benchboard Number Two contains the controls ~nd indications of components for various secondary and el~ctrical systems. The unit one and unit two benchboard number two are identical except for the following:
0 Unit one board contains seven additional electrical switches for control of common components.
o Unit one board contains four switches for control of common redundant components.
These differences have no training impact and therefore only the reference plant unit one benchboard is simulated.
Main Vertical Board #1 The Main Control Room Vertical Board Number is located on the left hand portion of the main control boards.
It contains all of the ~quipment necessary for operating and monitoring of the various safeguards and primary plant systems. The Unit 2 panel is identical to the Unit 1 panel except for the following items:
0 The Unit 1 board contains one additional switch, one additional hand control station, and four additional lamp indications for components of common systems.
The Unit 1 panel is fully simulated and located in the idential position in the simulator control room and provides operator training in the control ~nd monitoring of the safefguards and primary plant systems .
ATTACHMENT 1 Page 7 of 7
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 systems. Each of the systems monitored is fully simulated, therefore~ the instrumentation and controls of this panel is fully simulated. The Unit 2 panel is identical to the Unit 1 panel. Only the Unit 1 reference plant is simulated atid it's location is the same as in the main control room. This
panel provides vital instrumentation in the operations and control of major plant systems.
Post Accident Monitoring Panel The Post Accident Monitoring Panel contains the controls for systems affecting the containment environment.
These panels are identical in their configuration.
Therefore only the reference plant unit one panel is simulated.
Secondary Chemistry Monitoring Panel The Secondary Chemistry Monitoring Panel is a backboard panel located on the east side of the control room. This panel is presently undergoing major modifications due to a design change in the reference plant and is not fully simulated at this time. Unit 1 and Unit 2 Secondary Chemistry Monitoring Panels are identical in design and operation. Only the reference plant (Unit1) is simulated.
Kamen Radiation Monitoring Panels The Kamen High Range Effluent Monitoring Panel is a backboard panel which is located at approximately centerline between both units. This panel provides indication and diagnostic features for radiological releases from various flowpaths. Unit 2 and Unit 1 panel sections are* identical in layout. Only the reference plant, Unit 1, portion of the panel is simulated .
VIRGINIA POWER SIMULATOR SUPPORT GROUP SURRY UNIT 2 SIMULATOR
ATTACHMENT 2 UNIT 1 CONTROL ROOM/SIMULATOR PANEL AND ENVIRONMENT COMPARISON
ATTACHMENT 2 PAGE 1 OF 15
SUR~Y UNIT 1 CONTROL ROOM AND SIMULATO~ 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 giv~ri, such a~ name, location, function and associated units. Each pariel 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 ~ts training value.
This comparison is not intended to be the definitive simulator Physical Fidelity Comparison Report. The Physical Fidelity Comparison Report is conta~ned in Attachment 4 .
ATTACHMENT 2 PAGE 2 OF 15
SIMULATED PANELS VICTOREEN RADIATION MONITORING PANELS LIQUID WASTE PANEL AMBIENT TEMPERATURE MONITOR PANEL KAMEN HIGH RANGE RADIATION MONITORING PANEL BORON RECOVERY PANEL INCORE FLUX DISTRIBUTION MONITORING SYSTEM PANEL NUCLEAR INSTRUMENTATION PANEL CONTAINMENT HIGH RANGE RADIATION MONITORING PANEL INTAKE STRUCTURE PANEL EMERGENCY DIESEL #1 PANEL EMERGENCY DIESEL #3 PANEL SWITCHYARD DISTRIBUTION PANEL LOAD FREQUENCY AND HEAT TRACING PANEL VENTILATION PANEL TURBINE SUPERVISORY PANEL REACTOR COOLANT PUMP VIBRATION PANEL SECONDARY CHEMISTRY MONITORING PANEL MAIN ANNUNCIATOR PANEL VERTICAL BOARD #1 VERTICAL BOARD #2 . i POST ACCIDENT MONITORING PANEL BENCHBOARD #1 BENCHBOARD #2 .
PLANT COMPUTER P-250 OPERATOR STATION SHIFT SUPERVISOR CONSOLE (INCLUDES COMMUNICATION EQUIPMENT)
AUXILIARY SHUTDOWN PANEL AUXILIARY VENTILATION PANEL
.ATTACHMENT 2 PAGE .3 OF 1 5
.*NON-SIMULATED PANELS - PANELS. SPECIFIC TO UNIT. 2 OPERATION VICTOREEN RADIATION MONITORING INCORE FLUX DISTRIBUTION PANEL NUCLEAR INSTRUMENTATION PANEL CONTAINMENT HIGH RANGE RADIATION MONITORING PANEL EMERGENCY DIESEL GENERATOR #2 PANEL EMERGENCY DIESEL GENERATOR #3*PANEL (UNIT 2 SIDE).
TURBINE SUPERVISORY PANEL REACTOR COOLANT PUMP VIBRATION PANEL SECONDARY CHEMISTRY MONITORING PANEL VERTICAL BOARD #1 ..
VERTICAL ~OA~D #2 POST ACCIDENT MONITORING PANEL
.BENCHBOARD # 1 BENCHBOARD #2 PLANT COMPTUER P-250 OPERATOR STATION RADIAT~ON MONITORING PANELS
ATTACHMENT 2 PAGE 4 OF 15
NON-SIMULATED PANELS - COMMON TO BOTH UNITS These panels have not been simulated because of the
relative minor training value received from them.
METEOROLOGICAL PANEL ROBERT SHAW FIRE PROTECTION PANEL STATION FIRE PROTECTION PANELS GAS TURBINE REMOTE CONTROL PANEL - Being spared out at station FLOOD CONTROL PANEL UNIT 2 VENTILATION PANEL
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ATTACHMENT 2 PAGE 7 OF 15
PART A PANELS VICTOREEN RADIATION MONITORING PANEL
. The Victoreen Radiation Mori~toring Panels are backboard panels located on the Unit 2 *side of centerline .. These panels provide control, indic~tion and alarms for process and area radiation detectors on common and respective unit sistems. O~ly the common and Unit 1 monitots are simulated.
The Unit 2 systems have no training value ~nd are not simulated. The panels are 16cated exactly as in the reference plant and provide significant training in monitoring and analyzing .the radiological ~tatus of plarit systems.
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 being shared by both Unit 1 and Unit 2.
The panel contains co.ntrols ,* indications and alarms for various systems shared by both units. The Liquid .Waste
'panel is fully simulated and Iodated identically to the reference plant.
It provides valuable training in the operation and control of common systems and coordination between. backbo.ard and control b.oard operations.
AMBIENT TEMPERATURE MONifORING PANEL The Ambient Temperature Monitoring Panel is a backboard panel located on the Unit 1 side of cente~line ih the main control room. It is a comm6n panel being shared with both Unit. 1 and Unit 2 . . The panel contai*ns t.he controls, indic~tions arid alar~s fqr various are~s shared by both units; The Ambient Temperature Monitoring Panel is fully simulated with the exception that input to values of indicated temperature is performed via Instructor input from SIMLOCH.
It provides minimal .training value due to the operation data being displayed .
ATTACHMENT 2 PAGE 8. OF 1 5
KAMEN HIGH RANGE RADIATION MONITORING PANELS The Kamen High Range Effluent Monitoring Panel is a backboard panel which is located at approximately centerline between both units. This panel provides indication and
diagnostjc features foi radiological releases from variou~
fl6wpaths. Onl~ the reference plant, Unit 1, portion of the panel is* simulated.
The panel provides minimal training value, therefore, only operation~l data is displayed. Diagnostic information is not simulated.
BORON RECOVERY PANEL The Boron Recovery Pa~el is a backboard panel located on the Vnit l side of centerline in the main control room.
It is a common panel sharing sistems of both units. It cont~i~s controls, ~ndications arid alarms for the Boron Recovery and Primary Grade water systems.
This pan~l is fully simtilated and located i~en~ical to the referende plant. It provides training in the operation of boron recovery systems, and promotes improved
coordination between the backboard operator and the control room operator.
INCORE FLUX DISTRIBUTION PANEL The Incore Flux Distiibtition Panel i~ a backboard panel located on the south rear.wall of the main control room adjacient to the Boron Recovery panel. Th~~ panel is fully simulated for the refer~nce plant. It contains the coritrols
~nd indications used for.the incore syste~ operations under normal a~d abnormal conditions.
This panel provides training on the operation of the inccir~ flux drive system and in diagnosing changes in
neutron flux patterns. .
ATTACHMENT.2 PAGE. 9 OF 15
NUCLEAR INSTRUMENTATION PANEL The Nucleai Instrumentation Panel ia ~ backboard located on the Unit 1 sid~ in the ~ain control room. It contains the controls, indications, and alarms which.allow the operator to monitor the plants nuclear power level._
This pa~el is fully simulated and located identical to the reference plant. It provides significant training in the operation of the nuclear instrumentation system. It also d~velopes coordination between the backboard operator ~nd the control room o~erator. *
CONTAINMENT HIGH RANGE RADIATION MONITORING PANEL Th~ Containment High ~ange Radiation Monitoring Panel is located along the backboards next to'the Ihtake Structure Panel. The panel contains contr6ls and indications .for only Unit 1 contairiment radiati6n conditi6ns. Unit 1 monitors are functional and fully sim_ulated. The Unit 2 panel provides no training value. and is not . simulated. The. pa*nel provides valuable training during accident conditions by displaying containment conditions .
INTAKE STRUCTURE PANEL The Intake StructGre Panel is a backboard panel located on the south rear wall of the*control room.adjacent*to the Containment High Range Radiation Monitor Panel. This is* a common panel which is*fully simulated to include circulating water pump coritrols switches, valve c6ntrol, and indication.
It also include~ indication for bus power. This panel provides significant training on system operation .
. 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. Orily the ~e1erence plant (Unit 1) panels are simulated. Each panel, #1 and #3, is fully simulated and provides significant training in the operation of el~ctrical
generators. *
ATTACHMENT 2 PAGE 10 OF 15
SWITCHYARD DISTRIBUTION PANEL The Switchyard Distribution Panel is a backboard panel located on the west side of the main control room. rt 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 FREQUENCY AND HEAT TRACING PANEL The Load Frequency and Heat Tracing Panel is a backboard panel located on the west side of Unit 1 adjacent to the Switchyard Panel. This panel is simulated to the
extent of current scope of simulation, providing only minimal training value.
VENTILATION PANEL The Ventilation Panel is a backboard panel located on the west side of Unit 1 adjacient to the Load Frequency and Heat Tracing Panel. It contains controls for ventilation equipment for both Unit 1 and Unit 2. The Unit 1 ventilation equipment is fully simulated . The Unit 2 ventilation equipment is partially simulated with control features to ensure the reference plant system is complete.
The panel provides training in plant systems and components. It also develops coordination between the backboard operator and the control room operator.
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.
RCP VIBRATION MONITORING PANEL The Reactor Coolant Pump Vibration Monitoring Panel is located on the north west side of the main control room adjacient to the Turbine Supervisory Panel. The RCP vibration monitoring pariel is fully simulated for the reference plant in that it provides the calculated vibration
. indication under normal a~d abnormal conditions.
ATTACHMENT 2 PAGE 11 OF 15
SECONDARY CHEMISTRY MONITORING PANEL The Secondary Chemistry Monitoring Panel is a backboard panel which is located on the west side of the control room.
This panel is presently undergoing major modifications due to design change in the reference plant and is not presently fully simulated at this time.
MAIN ANNUNCIATOR PANEL The Main Annunciator Panels are located above the main control board vertical sections. There are eleven panels each consisting of sixty four "windows", except panels "E" and "F" which have eighty "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.
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 .
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 various safeguards and primary plant systems. This panel is fully simulated and located in the identical position in the simulator control room and provides operator training in the control and monitoring of the safeguards and primary plant systems .
ATTACHMENT 2 PAGE 12 OF 15
MAIN VERTICAL BOARD #2 The Main Control Room Vertical Board Number 2 is located approximately right of th~ center of the vertical boards. The panel contains indication for various plant 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 instrumentation in the operatjons and control of major plant systems.
POST ACCIDENT MONITORING PANEL The Post Accident Monitoring Panel is located to the left of the bench board #1 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 simulation. The panel provides valuable training in past accident conditions in analysis and
recovery and is located identical to the main control room .
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 co~ponents of various primary systems. Each system and its features are fully modeled making the panel a completely simulated panel. Only th~
reference plant Unit 1 panel is simulated. This panel provides a major pottion of operator simulator training.
Only minor cosmetic discrepancies are known and they are identified in the annual physical fidelity comparison report in Attachment 4.
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, 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.
ATTACHMENT 2 PAGE 13 OF 15
PLANT COMPUTER P-250 OPERATOR STATION The Plant Computer P-250 Operator Station is located opposite the operators main control console. It is used to monitor plant status and gather infor~atiori for specific tasks~ The r~ference plant computer ~tation 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 SUPERVISOR'S CONSOLE The Shift Supervisor's 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, have the hardware installed, but is not operational.
AUXILIARY SHUTDOWN PANEL
.The Auxiliary Shutdown Panels are located in the emergency switchgear room of its respective unit.* This panel provides independent remote control of vital system components for the safe shutdown of the plant. Only the reference plant Unit 1 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.
AUXILIARY VENTILATION PANEL The .Auxiliary Panel is located between Unit 1 Vertical Board 2 and Unit 2 Vertical Board 1. It contains controls for ventilation equipment for both Unit 1 and Unit 2. The*
Unit i ventilation equipment is fully simulated. The Unit 2 ventilation equipment is partially simulated with control features to ensure the reference plant system is complete .
ATTACHMENT 2 PAGE 14 OF 15
PART B ENVIRONMENTAL DIFFERENCES There are ceitain 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.
These differences have been reviewed and found to have no impact on training, and that the simulator is acceptabl~ for operator training and testing. -
The main control room florescent lighting is established with a continuous honey cone false ceiling panel which dispurses the light through out the ro6m. The Simulator us~s a solid tile false ceiling due to air conditioning requirements. Th~s c~uses a different dispersion of the lighting. Overall the effect is that the simulator lighting appears to be brighter.
-The main control room has been recently recarpeted.
The carpet change is schedule for completion on the simulator by the end of 1988.
The main control room ha~ recently replaced~he chairs used by the operating staff with ones that are a different color than those in the simulator.
The main control room has b_racket type emergency lighting fixtures which can be redirected to enhance certain areas of the control room. The Simulator uses a stationary fixture which is set i~to the ceiling.
The control room has a digital clock.installed over the Auxiliary Ventilation Panel which is not installed in the simulator.
Floor riser sections are installed on both the east and west ends of the bench board which physically raises the floor height approximately four inches with a sloping grade of 45 degrees. The simulator floor is level through out, but is schedule for modification by the end of 1988.
The control room has a bookc~se provided bext- to the Containment High Range Radiation Monitoring Panel. Due to the location of the entrance way into the simulator space is not available for this-bookcase. There is a substitute bookcase provided in the simulate~ on the east end of the benchboard. -
ATTACHMENT 2 PAGE 1 5. OF 1 5 There are television screens in the control room to monitor the movement and operation of personel in and around the Control Room Annex, Auxiliary Shutdown Panel and Fuel Building. These are not provided in the simulator, but are being evaluated for *1~plementation on the simulator.
Noises that accompany operation of VarioU~ 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 being evaluated for implementation on the simulator .

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