ML20244B632

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Rev 2 to ERC892154, Arkansas Nuclear One Unit II Simulator Operability Test
ML20244B632
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 04/19/1989
From: Danni Smith
ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML20244B597 List:
References
ERC892154, NUDOCS 8906130194
Download: ML20244B632 (67)
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- ERC892154':.

Rev. 04/17/891 I

a ARKANSAS NUCLEAR ONE UNIT - II 4.

SIMULATOR OPERABILITY TEST >. 'i REVISION'2.0.

APRIL 19, 1989 j

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1 DATE PERFORMED:

PERFORMED BY:

I APPROVAL:  % .e O 2, [@

. . . . SIMULATOR TRAINING SUPERVISOR-

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DATE

/ 5-n43 SIMULATd@ SUPPO SUPERVISOR DATE OPS TRAINING SUPERINTENDENT

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8904130194 890531' 4 PDR ADOCK 05000368 ,

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ERC892154 R2v. 04/17/89-UNIT 2 OPERABILITY TEST-I:

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!' FOREWORD The Simulator OperabilityLTest'will.be performed annually. TheLeollected data-will be evaluated,' discrepancies, if any,' explained and attached to the Annual' Simulator Report.

.An Operability. Test is not'a Performance. Test; The Performance Test demonstrated the Simulator's ffdelity by. comparing simulator calculated values to actuallor

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predicted plant data and' demonstrated ability.to comply with ANS-3.5,.1985. LThe-ANO-Training Administrative Guideline: . Simulator Modification Control is designed to maintain the Simulator's fidelity. The Operability Test will provide-theEdata to document satisfactory simulator: performance.

It is required that all malfunctions-listed in ANS-3.5,' 1985, 3.1.2 and the operation test be tested every 4 years and a minimum of 25% tested each year.

The lists provided are suggested and do not have to be followed, however, the aforementioned requirement must be met. The operation test is ran to ensure that the requirement of' proving model-integration fidelity is maintained, i

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l-ERC892154

- Rev. 04/17/89-TABII 0F CONTENTS .

SECTION A Real-Time' Test: T  !

.i SECTION B Normal Operations Test .

SECTION C: Steady: State Operations' Test 3 SECTION D Surveillance Test.

- SECTION E. Transient Test; SECTION F' 'Malfunctio'n Test.

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ERC892154 Rev. 04/17/89 A. COMPUTER REAL TIME TEST 1.0 DISCUSSION The purpose of this test is to ensure that the Simulator is running in Real Time. To ensure Real Time operation, 2-evolutions are to be performed. First, the computer clock frequency will be measured to ensure operations at 60 Hertz (or multiples of 60 Hertz). The second operation is a calculation of the actual time required for execution of 60 l simulator cycles. This calculation is performed in model BMDN and is accessible thru Simulator Development Aid (2:SDA).

2.0 REFERENCE (S) 2.1 ANS-3.5, 1985 A3.1, ANS NPP Simulator for Operator Training.

2.2 ANO Unit-II User Gtdde for Simulation Development Aide.

2.3 ANO Unit-II Simulator Model BMDN 3.0 EQUIPMENT 3.1 Timer / Counter, Fluke 1952A or equivalent.

3.2 Two development terminals (any system).

4.0 INITIAL CONDITIONS l

4.1 100% Power.

l 5.0 ACCEPTANCE CRITERIA 5.1 The Simulator computer clock will be 60 0.025 Hertz, 16.666 1 0.0069 msec, or 1201 0.05 Hertz, 8.333 1 0.0034.

5.2 Real-Time Ratio (RTRATIO) shall equal 100 1 3% for normal, abnormal and emergency conditions.

6.0 NON-ACCEPTANCE OF SIMULATOR RESULTS 6.1 If the acceptance criteria in 5.0 are not met, adjustments will be made before the Simulator is used for routine training.

the Simulator is used for routine training.

7.0 PROCEDURE 7.1 Initialize to 100% Rated Power (IC-1).

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ERC892154-Rsv. 04/17/89

.7.2 Using the Timer / Clock described in Section 3.0, measure computer-clock time (back plane. pins P1A-31 for each system).

Clock Time

. System A-

-Syst'em B System C.

7.3 Normal Operation 7.3.1- Use a' datapool monitorL to- display the -value of: RTRATIO

-(real-time ratio).with a format of F14.4..

7.3.2 Initialize to 100% power (IC1). Place simulator in RUN.

7.3.3. .Use Z:SDA to set the value of RT: FLAG = true. RTRATIO will-now = $.S.

7.3.4 About -1 minute later,,- record the value of RTRATIO.

RTRATIO =

7.4 Abnormal Operation 7.4.1 Use a datapool monitor to display the value of RTRATIO (real-time ratio) with a format of F14.4.

7.4.2 Initialize to 100% power (IC1). ' Place simulator in RUN.

7.4.3 Use Z:SDA to set the value of RT: FLAG = true. RTRATIO will now = $.S.

7.4.4 Within 5 seconds, manually trip the reactor.

7.4.5 About I minute later, record the value of RTRATIO.

RTRATIO =

7.5 Emergency Operation 7.5.1 Use a datapool monitor to' display the value of RTRATIO (real-time ratio) with a format of F14.4.

7.5.2 Initialize to 100% power (101). Place simulator in RUN.

7.5.3 Use Z:SDA to set the value of RT: FLAG = true. RTRATIO will' now = p.p. s 7.5.4 Within 5 seconds, initiate a 100% hot leg LOCA.

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ERC892154 Rev. 04/17/89 i

7.5.5 About 1 minute later, record the value of RTRATIO.

RTATIO.= -

8.0 Final Conditions Real-time ratios have been recorded for normal, abnormal, and emergency conditions.

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ERC892154-Rev. 04/17/89 B. NORMAL OPERATION TEST 1.0 DISCUSSION Normal operations are performed to demonstrate the ability to operate the Simulator in accordance with reference plant operating procedures.

. Normal operations will be' tested;by' splitting the performance operations test into four segments, one of which.will be tested each year.

2.0 REFERENCE (S)

'2.1ANS-3.5, 1985, 3.1.1, ANS NPP Simulator'for Operator Training.

'2.2 ANO Unit 2 Operating Procedures, 2102 Series.

3.0 EQUIPMENT 3.1 None 4.0 INITIAL CONDITIONS 4.1 Initial Conditions (ICs).will be'as stated in procedure..

5.0 ACCEPTANCE CRITERIA 5.1 The Simulator will perform,.without distraction'from training, reference plant normal operations.

5.2 Reference plant normal operations can be performed on the Simulator using only operator action normal to the reference plant and/or  ;

those actions denoted that prevent exceeding Simulator operating i limits. j

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6.0 NON-ACCEPTANCE OF SIMULATOR RESULTS 6.1 Non-acceptance is the inability of the Simulator to perform reference i plant normal operations using only operator actions. normal to the j reference plant and/or those actions denoted that prevent exceeding '

Simulator operating limits or performance that distracts from  ;

training. .j 6.2 Non-acceptance of Simulator performance shall halt the routine. j training involving such operations. Discrepancies shall be recorded, l models enhanced,-and retested as required.  ;

I 7.0 PROCEDURE l J

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ERC892154'

.Rev. 04/17/89 i

'4 7.1 Using the' latest revision of the reference plant procedure, perform the following operations:

.The test will be split'as follows:

a. 'In year one of the cycle, the' simulator will'be initialized at.

hot standby. power:and as directed.and by. plant < procedures will-be brought:to 100% power. (Steps.7.1.6 thru 7.1.7)-

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b. In year two, the plant will1be initialized at 100% power and-will be brought to hot standby power-by plant procedures and.

this test procedure. -(Steps 7.1.1 thru.7.1.3)

c. ,In year three, the simulator will be initialized in' cold; shutdown and a,heatup.and plant.startup to hot standby, power will be done.using plant procedures and this test procedure. (Step 7.1.5)
d. In year four, the' simulator will.be initialized at hot standby power and will be brought to a. cold shutdown-condition using plant procedures and this test procedure.

(step 7.1.4)

NOTE: Procedures are to be initialled / signed as appropriate, areas of non-simulation and Simulator specific operations are to.

be noted, and the procedure will be added to this test as-Attachment B-1.

NOTE: Initial Conditions (IC's)~will be stored as designated.

NOTE: Ensure PMS Trending Groups are established to store on IC Snaps / Stores.

NOTE: Use Fast Time for Xenon and Heatup as appropriate.

7.1.1 100% Steady State Operations-(OP 2102.04)-

7.1.1.1 Establish the following IC:

7.1.1.1.1 IC-1 100% FP, EQXE, MOL 7.1.2 100% - 20% Rated Power (OP2102.04) 7.1.2.1 Establish following IC:

l 7.1.2.1.1 IC-4 20% FP IAWP MOL 7.1.3 20% - HTSBY (OP2102 10).

7.1.3.1 Establish following JCs:

7.1.3.1.1 IC-5.HTSBY after S/D MOL.

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' 7.1 '. 4 HTSBY - Cold S/D (OP2102.02) .

7.1.4.1 Establish the following ICs:

7.1.4.1.1 IC-7 305'F/370 PSIA, MOL', (Thru Step 9.20)  !

-7.1.4.1.2 IC-10 150*F/50 PSIA, SDC, MOL i, 7.1.5- . Cold S/D HTSBY (OP.2102.10)~ '

7,1.5.1. . Establish.the following'IC:

7.1.5.1.1 IC-9 270'F/250 PSIA, SDC, MOL:

,7.1.5.1.2-IC-12 190*F/315' PSIA' 2RCP's,:LTOP's'

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inse'rvice, MOL, (Thru Step 11.2) 7.1.5.c.3 IC-18 490'F/2250 PSIA, 3RCP's, MOL (Thru

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step'11.22);

7.1.6 HTSBY-to 20% (OP 2102.02) 7.1.6.1 -Establish the following-IC:

7.1.6.1.1 IC-15.545'/2250 PSIA HTSBY,.MOL 1

7;1.6.1.2 IC-17 2%FP, No MFWP, 2P7B' MOL (Thru Step'.

13.5) t 7.1.7 20% to 100% FP (OP 2102.02) 7.1.7.1 Establish the following IC:

7.1.7.1.1 IC-19 50% FP, IMFWP, MOL (Thru Step 9.2.16)-

i 7.1.7-.1.2 IC-20 80% FP IAWP, MOL'(Thru Step 9.~2.19) l 8.0 FINAL CONDITIONS 1 8.1 Normal operations are completed, signed and attached. IC's i have been established and stored. '

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l' ERC892154 Rev. 04/17/89 ATTACHMENT B-1 NORMAL OPERATING PROCEDURES i

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ERC892154

Rev. 04/17/89 C. STEADY STATE OPERATIONS TEST 1.0 DISCUSSION

. Stability of.the Simulator is to be demonstrated by' establishing a. steady.

state condition and monitoring parameter variation with respect to time.  ;

Simulator computed ' values are also -to' be. compared to reference, plant data 1

at.various power levels.

2.0 . REFERENCE (S)'

'2.1iANS-3.5.,i 1985, 4.1, A3.2 ANS NPP Simulators for.OperatorITraining.

i 2.2' ANO-Unit-II Instructor Station; User Guide.

3.0 EQUIPMENT-3.1 None 4.0 INITIAL CONDITIONS 4'.1 Initial Conditions (ICs) will be as stated in' procedure.

5.0 ACCEPTANCE CRITERIA 5.1 At 100% Rated Power, Simulator computed values shall not vary more than 12% over a 60 minute period. -)

5.2 Simulator computed values of critical parameters shall agree with the reference plant within i2% and shall not detract from training.

5.3 Simulator computed values of non-critical parameters sha11' agree with )

the reference plant within 10% and shall not detract from training. l 6.0 NON-ACCEPTANCE OF SIMULATOR RESULTS i

1 6.1 Non-acceptance is defined as numerous Simulator computed. values outside  !

the range set'forth in Section 5.0.

l 6.2' Non-acceptance shall halt the routine training involving such operations. I Discrepancies shall be recorded, models enhanced,-and retested, -j as required. l 7.0 PROCEDURE i 7.1 Obtain Data 7.1.1 Initialize to 20% rated power (IC-4)- l 7.3.2 Increase and Stabilize Power at 30%

7.1.3 Start data log #3 7.1.4 Record problem time from instructor station screen i 7.1.5 Run for 20 minutes Stop l l

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Rev. 04/17/89 lJ 7.1.6 Secure data log 7.1.7 Initialize to 50% rated power (IC-9)  !

7.1.8 Increase and stabalize power at 60%. ]

7.1.9 Start data log #2-  !

7.1.10 Record problem time from instructor station screen )

7.1.11 Run for 20 minutes Stop i 7.1.12 Secure data log 7.1.13 Initialize to 100% rated power (IC-1)

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7.1.14 Stabilize power j 7.1.15 Start data log #1 (

7.1.16 Record problem time from instruction station screen j 7.1.17 Run for 70 minutes Stop 7.1.18 Secure data log 7.1.19 Freeze simulator 1 1

7.2 Delogging Data l

7.2.1 30% Rated Power I

7.2.1.1 Establish the following Delog Tableaux (

7.2.1.2 Print and plot each tableau at 26 second in- 1 tervals for 20 minutes I 7.2.1.3 Attach data l i

I TABLEAU 1 - 30%

ACCEPTANCE l

CRITERIA j i

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  1. Tag # Actual Min Max Description Simulated Values Min Max I 46 21R-9624 231.9 211.9 251.9 MV Gross 66 #CV-5993 29.6 27.6 31.6 Core Thermal Power 87 #T-4611-2 545.4 542.6 548.2 Loop A T C '

86 #T-4611-1 547.2 544.4 550 Loop B T C i 85 #T-4610-1 563.7 560.7 566.7 Loop A TH 94 #T-4717-B 555.5 545.5 565.5 Tav 82 #T-1023 345.3 335.3 355.3 FW Temp 36 2PI-4624-2 2243 2183 2303 Pzr Press J

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ERC892154 Rev. 04/17/89 i

TABLEAU 2 - 30%

i ACCEPTANCE CRITERIA l

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  1. Tag # Actual Min Max Description Simulated Values  !

Min Max 35 2LI-4627-1 46.3 44.3 48.3 Pzr Level 89 #T-4622 655.3 641.3 669.3 Pzr Temp 65 #CRAVG6 150 147 150 GR6 Rod Et.

I 2LI-1031-1 70.2 68.2 72.2 S/G Lv1.  !

2 2PI-1041-1 944.2 924 2 968.2 S/G Press.

47 2TR-0200 538.8 522.8 554.8 S/G Temp.

5 2FR-1029 1724K 1584K 1864K Stm Flow I 6 2FR-1030 1736K 1596K 1876K FW Flow l

7.2.2 60 % Rated Power 7.2.2.1 Establish the following Delog Tableaux -

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7.2.2.2 Print and plot each tableau at 26 second intervals 1 for 20 minutes {

7.2.2.3 Attach data 'I i

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ERC892154

- R:v. 04/17/89 TABLEAU 1 - 60%

ACCEPTANCE CRITERIA I

  1. Tag # Actual Min Max Description Simulated Values Min Max 46 21R-9624 524.11 500.1 548.1 MW Gross 66 #CV-5993 60.32 58.32 62.32 Core Thermal Power 87 #T-4611-2 549.6 546.8 552.4 Loop A T C 86 #T-4611-1 550.6 547.8 553.4 Loop B T C

85 #T-4610-1 582.9 579.9 585.9 Loop A T H

94 #T-4717-B 566 562 570 Tav 82 #T-1023 402.6 392.6 412.6 FW Temp 36 2PI-4624-2 2247 2227 2267 Pzr Press TABLEAU 2 - 60%

ACCEPTANCE CRITERIA

  1. Tag # Actual Min Max Description Simulated Values Min Max 35 2LI-4627-1 52.7 50.7 54.7 Pzr Level 89 #T-4622 656.8 642.8 670.8 Pzr Temp 65 CRAVG 6 141 138 144 GR6 Rod Ht. _

1 2LI-1031-1 70.2 68.2 72.2 S/G Level 2 2PI-1041-1 931.1 907.1 955.1 S/G Press 47 2TR-0200 535.9 519.9 551.9 S/G Temp 5 2FR-1029 3606K 3466K 3746K FW Flow 6 2FR-1030 3634K 3494K 3774K Stm Flow 14

ERC892154 Rev. 04/17/89 7 . ;< *; 100% Rated Power q 7.2.3.1 Establish the following Delog Tableaux l 7.2.3.2 Print and plot each tableau at 80 second intervals i for 60 minutes 7.2.3.3 Attach data l

TABIIAU 1 - 100%

ACCEPTANCE CRITERIA

  1. Tag # Actual Min Max Description Simulated Values Min Max 46 '21R-9624 928.01 908 948 MW Gross 66 #CV-5993 100 98 102 Core Thermal Power 87 #T-4611-2 552.04 549.2 554.8 Loop A T C 86 #T-4611-1 553.6 550.8 556.4 Loop B TC -

85 #T-4610-1 606.7 603.7 609.7 Loop A TH 94 #T-4717-B 580' 576 584 Tav 82 #T-1023 447.9 437.9 457.9 FW Temp 36 2PI-4624-2 2249 2189 2309 Pzr Press l

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Rev. 04/17/89- -

,, TABLEAU 2 - 100%~

ACCEPTANCE.

CRITERIA -

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  1. Tag # Actual. . ._ Min - Max- .

Description:

~ Simulated Values '1 Min Max  !

l35 '2LI-4627-1 '60 '58 62 .Pzr Level H 89- #T-4622- 654.88 640.8 668.8 .Pzr Temp-65, #CRAVG 6- 147- 144- "150; GR6. Rod Ht 1 -2LI-1031-1 70.0 '68 ~72 S/!iLeval: ,  ?

.2 2PI-1041-11 918. 894: 942 A /0 Press 47 2TR-0200 530- '514 546 S/0 Temp; 5 2FR-1029- 6306K- 6166K 6446K. FW flew-6 2FR-1030 -6305K' 6165K 6441K.- Stm D ow 1

7.3. Tape Save 7.3.1 Record Tape Serial..No(s) 1

.j 8.0 FINAL CONDITIONE l Steady State data is collected, tape saved, and data attached to this  !

procedure. -

I NOTES: i

.l. 30% data taken at 0100 on 09/17/86 from computer 1ogs.

2. 60% data' taken at 0700 on~ 09/23/86--from computer -logs.
3. 100% data taken on' 11/18/87 from computer logs 4

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'ERC892154 Rev. 04/17/89 -1 i

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ATTACIDfENT C-1 30% RATED POWER DATA i

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ERC892154 Rev. 04f37jgg ATTACKHENT C~2 60% RATED POWER DATA l

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ERC892154 Rev. 04/17/89 ATTACHMENT C-3 100% RATED POWER DATA s

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ERC893154 Rev. 04/17/89~  ;

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, H D. SLM'EILLANCE TEST  !

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.1.0 DISCUSSION' Surveillance. Tests are. performed to demonstrate the ability to perform Normal Operation surveillance in accordance with reference plant procedures.

The following criteria was.used'to select.which surveillance will be runt

  • ~ Safety related and routinely performed by Operations.
  • Require Control Room Manipulations. .
  • Provide training-value.

.I 2.0 REFERENCE (S) 2.1 ANSI-3.5, 1985, 3.1.1, ANS NPP Simulators for Operator Training j 2.2 ANO Unit 2 Surveillance Test Procedures 3.0 EQUIPMENT-3.1 None , H 4.0 INITIAL CONDITIONS 4.1 Initial Conditions (ICs) will be at'.IC-1 (100%), unless otherwise; note 6.

5.0 ACCEPTANCE CRITERIA-5.1 The simulator will perform, without distraction from training, j

. reference plant surveillance procedures. j 6.0 NON ACCEPTANCE CRITERIA 6.1 Non acceptance is defined as the inability to perform surveillance i tests, or those that detract from training. ij

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6.2 Non acceptance shall halt routine training involving'such' operations. D Discrepancies shall be recorded,-models enhanced, and retested, as' l required.  !

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g ERC892154 Rev. 04/17/89 7.0' PROCEDURE 7.1 Using the. latest-revision of the' reference plant surveillance procedures. perform.the following operations-as indicated for the' current yearL(year 1 in; thel current .

test' cycle = A, Year'2.=JB: ETC).

A7 1.1 PRZR LVL Response OP2103.05lSupp. 1 .

-A7.1.2~ Qtrly. SI TK VLV Stroke- 'OP2104.01 Supp. 2 A7.1.3 Cont. Atmos.~ Conditions- 0P2103.33 Supp.'4-A7.1. 4 ' 2DG1 Monthly' OP2104.36'Supp.:1' A7.1.5 2DG2-Monthly. . OP2104.36 Supp. 2 A7.1.6 -Semiannual'H2 Recomb'- _0P2104.44 Supp.12' A7.1.7 Excore NI Safety _Chan -OP2105.15 Supp. LIB >

A7.1.8 2P7A Monthly- ;0P2106.06 Supp.'I?

A7.1.9 2P7B Monthly OP2106.06.Supp. 2:!'

B7.1.10: :Qtrly EFW VLV-Stroke OP2106.06 Supp.'3-

-B7.1.11 EFW A Train Flow. OP2106.06 Supp.;4' B7.1.12 EFW B Train Flow .

1OP2105.06 Supp. 5 B7.1.13 MFWPT.Stop VLV OP2106.07.Supp. 1, B7.1.14 Turb. Overspeed Trip '0P2106.092Att..D B7.1.15 T/G CV Stroke OP2106.09'Att. F B7.1.16 'T/G CV Stroke .OP2106.09LAtt. G B7.1.17 MSIV Qtrly Stroke:

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, 0P2106.16 Supp. 1 B7.1.18 Elect. Sys. Brkr Align ' OP2107.01 Supp.-4 C7.1.19 ESF SWGR RM. EXH Fan OP2107.02 Supp.-1, C7.1.20 2P89A Monthly. 10P2104;29 Supp. 1-C7.1.21 2P89B Monthly .OP2104.39.Supp. 2 C7.1.22 2P60A Monthly OP2104.40lSupp. 1 C7.1.23 2P6bB Monthly .0P2104.40 Supp. 2 C7.1.24 2P35A Monthly OP2304.05'Supp. 1:

C7.1.25 2P35B Monthly .0P2104.05 Supp. 2 C7.1.26 18 Month Press Interlock. .0P2104.01 Supp.,3 4 C7.1.27 2P36A Monthly '0P2104.02 Supp. 1 l D7.1.28 2P36B Monthly .OP2104.02 Supp. 2 ,

D7.1.29 2P36C Monthly OP2104.02 Supp. 3-  !

D7.1.30 2P39A Monthly- CP2104.03 Supp 1 .

D7.1.31 2P39B Monthly OP2104.03~Supp. 2 ,

D7.1.32 SDC Viv Interlock OP2104.40 Supp.;6 l D7.1.33 Rx TCB OP2105.09:Supp. 1 l D7.1.34 Relief VLV Monitor 'OP2105.11'Supp. 1

D7.1.35 Heat Balance Calc OP2103.16 j D7.1.36 . Moderator Temp. Coeff. ~0P2302.09

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8.0 FINAL CONDITIONS  !

1 8.1 Surveillance procedures are completed, initialed and. attached. . .l

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ERC892154 Rtv. 04/17/89 ATTACIDIE.NT D-1 SURVEILLANCE PROCEDURES I

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1 ERC892154 Rev.' 04/_17/89.

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,E._ TRANSIENT TEST i

J 1.0 DISCUSSION l

- 1 The intent of the TransientLTest is_to verify Simulator-performance.  ;

Transients must be capable of continuing until such time that;a stable,:' j controllable and safe condition'is' attained'which can be continued to-'

i-- ~l a: Cold' Shutdown condition or until the Simulator operating limits are exceeded. These tests will be performed each year.  !

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-2.0 REFERENCE (S) 2.1. ANS-3.5, 1985, 4.2.1, 4.3, A.3.3'ANS NPP Simulators for Operator 1 Training. .{

3.0 EQUIPMENT.

l 3.1 None 4.0 INITIAL CONDITIONS 4.1 Initial Conditions (ICs) will be as stated in procedure.

5.0 ACCEPTANCE CRITERIA' l I

5.1 Observable changes in tae parameters correspond in' direction to )

those expected from plant data or best estimate data and'do not.  !

violate the physical laws of nSture. .d I

6.0 NON-ACCEPTANCE OF SIMULATOR RESULTS 6.1 Simulator results do not have to parallel source' data, however, ,

observable differences, those that would detract from positive l training and those declared unacceptable by evaluation based'on  ;

acceptance criteria, will not be used for routine training. -i l

7.0 PROCEDURE NOTE 1: After initiation of transient, Operators are.to take appropriate actions as directed by plant procedures.

NOTE 2: All problem times should begin at'00:00:00 with a 1 minute delay ')

to the malfunction.

NOTE 3: All transients are to be carried to a stable plant condition.

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'7.1 Perform the following transients -

7.1.1 -Turbine trip / Reactor trip, High MSR Level'(LER 86-11).

7.1.1.1 Initialize tofl00% (IC-1)

-7.1.1.2 Start data log-#4 7.1.1.3 Insert Malfunction SSV0417 = 0 and SSV0418 = 0

-7.1.1.4 Record Data for 10 Minutes 7.1.1.5: When stable conditions are reached,-freeze simulator 7.1.2 "A".MSIV Closure-(2CV-1010-1) 7.1.2.1 ' Initialize to 100% (IC-1) 7.1.2.2 Start Data log #5' 7.1.2.3 ' Insert Malfunction SHV1010 = 0 7.1.2.4 Record Data'for 10 minutes 17.1.2.5- When stable conditions are reached, freeze simulator.

7.1.3 Main Turbine Runback 7.1.3.1 Initialize to 100% (IC-1).

7.1.3.2- Start Data Log #61 7.1.3.3 Insert malfunction X:SW7800 7.1.3.4 At 2 minutes after runback commences remove malfunction X:SW7800 '

7.1.3.5 Record Data for 10 minutes 7.1.3.6 When stable' plant conditions are reached, freeze-simulator.

7.1.4 Loss of Main Circulating Vater 7.1.4.1 Initialize to 100% power (IC-1) 7.1.4.2 Maneuver to 67%' power 7.1.4.3 Start Data log #7 7.1.4.4 Insert malfunction X:CR3101 and X:CR3102 7.1.4.5 Record Data'for 10 minutes 7.1.4.6 When stable plant conditions are reached, freeze simulator.

7.1.5 Reactor Trip, "D" RCP Trip (LER 86-7) 7.1.5.1 Initialize to 100% (IC-1) 7.1.5.2 Start Data Log #8 7.1.5.3 Insert Malfunction X:RQ0604 7.1.5.4- Record Data for 10 minutes l 7.1.5.5 ' When stable plant conditions are reached, freeze simulator.

24 L - ___-- _____ __ __ .

?" ERC892154-Rev.'04/17/89 7.1.6 Reactor Trip,'"A'" S/G Level Low J7.1. 6 ' 1

. ~ Initialize to.100% (IC-1) 7.1.6.2 Start' data log #9 7 1.6.3 Place both MFRV'in manual' 7.1.6.4  ; Slowly close "B" MFRV 7.1.6.5 hhen stable plant conditions are reached,Lfreeze the

-simulator 7.1.7 Partial Loss of Off-Site Power (Natural Circulation)-

7.1.7.1 ' Initialize,to 100% (IC-1)'

7.1.7.2- Start data. log #10 . .

7.1.7.3 Place 6900 volt aux. loads'on S/U XFMR #3:

7.1.7;4 Place 4160 volt aux. loads on Aux.' XFMR 7.1. 7 . 5 ' Insert malfunction X:EA8902 7.1.7.6 Record dat'a for 10 minutes 7.1.7.7 When stable conditions'are~ reached, freeze simulator

'7.1.8 Steam Line Break (100%)

7.1.8.1 Initialize to 100%L(IC-1) 7.1.8.2 Start ~ data log fil .

7.1.8.3 Insert malfunction XRSG3701 or XRSG3702 - 100%

7.1.8.4 Record data for 10 minutes 7.1.8.5. When stable conditions'are; reached, freeze simulator 7 1.9 LOCA (100%)

7.1.9.1 Initialize to 100% (IC-1) 7.1.9.2 Start data. log #12 7.1.9.3 Insert malfunction XRRC0301, XRRC0302, XRRC0303,-

or XRRC0304 (100%)

7.1.9.4 Record data for 10 minutes.

7.1.9.5 When stable conditions are reached,; freeze simulator 7.2 Delogging Data 7.2.1 - Print out required parameter values at 1 second' intervals 7.2.2 Plot required parameters 7.2.3 Compare simulator computed values to plant.or predicted.

-values.

7.3 Data Tableaux 7.3.1 Establish tableaux for transient data y.

o 25

,[- J1

' .i' .,'l ERC892154.

l Rev.'04/17/89 7.3.111L LTurbine Trip / Reactor. trip, High MSR. Level (Log'4).

.g. Tag # Min  : Max Description 1

35- ~2LI-4627 0- , -100 Pzr Level j 36 2PI-4624-2. 1500 -2500" Prz Pressure- j

~'

85 #T-4610-1 525 625 Loop A T 17 2JR-9005-1 0 110- Neutronflux.(%):

il- 2LI-1031-1, 'O- :100- "A" S/G Level 2 2PI-1041-1 0~ . 1200: "A" S/G Pressure 1 86 .#T-4611-1 525 625 Loop B T 'l C

87. -#T-4611-2' 525 :625 - Loop A T  !

C 7.3.1.2- "A" MSIV Closesure (Log 5);

-l

( Tag'# Min.

' Max Description j

I 35 2LI-4627-1 0 100' Pzr Level?

36 2PI-4624-2 1500 2500 .Pzr Pressure-85 #T-4610-1 525 625 Loop A TH 90 #T-4710-1 525' '625 Loop.B TH 86 #T-4611-1 525 625 Loop B T i 87 #T-4611-2 525 625 Loop"A T*

17 2JR-9005-1 0- 110- Neutron. flux (%)

1 2LI-1031-1 0 '100 "A" S/G Level 3 '2LI-1131-1 0- 100.. "B" S/G Level 2 2PI-1041-1 :0 1200 "A" S/G Pressure; i 4 2PI-1141 0 ;1200 "B"_S/G Pressure i

7.3.1.3 Main Turbine Runback (Log 6) l f Tag # Min' Max Description' 35 2LI-4627-1 0 '100 Pzr Leveli j 36 2PI-4624-2 1500 2500. Pzr Pressure.  !

85 #T-4610 525 '625- Loop'A T .l 17 2JR-9005-1 0 110 Neutronflux-(%) '

1 2LI-1031-1 0 1100 "A" S/G Level 2 2PI-1041-1 0 1200 -S/G Pressure

86. #T-4611 525 625 Loop B;T C

87 #T-4611 525 625- ' Loop A'T 7.3.1.4 Loss of Main Circulating Water (Log:7) l l

g Tag # Min Max' Description' i 35 2LI-4627-1 0 100 PzrLLevel I 36 2PI-4624-2 1500 2500 Pzr Pressure: '

85 #T-4610-1 525 * % 625. Loop A T' -l 17 2JR-9005-1 .0, 110 NeutronM1ux(%) l 1 2LI-1031-1 0 100 "A" S/G Level ')

2 2PI-1041-1 0 1200 "A" S/G Pressure i 86 2PI-1041-1 525 625 Loop'B'T  !

100 2PIS-0605 0- 15 Condensor vacuum l 26

~

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4 i

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',o' ERC892154' "Rev.-04/17/89- '

i 7 -. 3.1. 5 !ReactorTrip,"D"RCP.TRIPL(Log 8)l
  1. . Tag #- . Mini Max' Description 1 q

35: :2LI-4627-1 0' 100 LPzr Level 36 '2PI-4624-2L - 1500: '2500. 1Pzr Pressure I 85 #T-4610-1 525 1 625' Loop A.T' 90: - #T-4710-1 -- 525 625'; Loop B TH .

86J '#T-4611-1 525! .625, LoopiB"TH.

~ 87  :#T-4611-2 ~525- 625 -Loop'A T C 1 -2LI-'1031-11 04 '

1100, . "A"S/Gfevel-2 '2PI-1041 -0 1 1200/ "A" S/G Pressure 7 2 -- .#CV-9199 '0 ;13E7 ' Loop'A RCS' Flow 73: -#CV-9200: ' 0" .13E7 l Loop B RCS Flowf 74 .#CV-9201'  : 0- .33E7 Loop C~RCS Flow 75' #CV-9202 'O .13E7  : Loop.D RCS Flow-

- 17 '2JR-9005-1 0 110: Neutron Flux.(%)

'3 ~ '2LI-1131 0 -100 ' ?'B": S/G . Level 4 .2PI-1141-1 ;O .1200: "B" S/G Pressurei 7.3.1.6 Reactor Trip, "A" S/G Level (Log 9)>

  1. ' Tag-# = Min -Max- Description 35 2LI-4627-1 0: 100- -Pzr Level ~

36 2PI-4624-2" 1500- -2500- Pzr Pressure 85 #T-4610-1 525J :625 Loop A.T 3 2LI-1131-1 0' 100 '"B"~S/Glevel-1 2LI-1031 .0 100- "A":S/G Level-2 2PI-1041-1 - 0' i1200- '."A"-S/G Pressure 86 #T-4611 _525 625 Loop;B T-17 2JR-9005 110  : Neutron flux (%):

6 2FR-1029/30 -0 6.500,000 A S/G Feed Flow 8 2FR-1329/30 'O' 6,500,000 B S/G Feed Flow -

l g

27 2_ __ .:

ERC892154L

'Rev. 04/17/89 .;

7 3.1.7 PARTIAL Loss of.Offsite' Power (Natural-Circulation).-

(Log 10)

  1. - . Tag #l Min ~  : Max Description.

35 12LI-4627-1 0 100 .Pzr Level " -

h 36 2PI-4624-2 1500 2500 Pzr Pressure: i 4: 2PI-1141-1 0, 1200. S/G B Pressure  :

3- .2LI-1131-1 '0-100' ' 'S/G B Level' 1 2LI-1031-1 0 100 S/G A Level' 2 2PI-1041-1 O. 1200; S/G A Pressure 85 #T-4610-1 525- 625 Loop A T_g 90 #T-4710-1 '525 625 Loop'B T-H 72 #CV-9199 -0 .13E7- Loop A RCS Flow.

73 ~#CV-9200 0' .13E7 Loop B RCS Flow 74 #CV-9201 0 .13E7 Loop C RCS Flow-75 #CV-9202- 0 .13E7 Loop D RCS Flow 17 2JR-9005-1 0 110 Neutron Fluz (%)

86 #T4611-1: 525' 625 . Loop'B T"'

87 -#T-4611-2 525 625 Loop'A T c

7.3.1.8 Steam Line Break (100%) (Log 11).

  1. ' Tag # Min. ' tiax Des cription .-

36 2PI-4624-2 900 2300' Pzr Pressure '

2 2PI-1041-1 0' 1200 S/G A' Pressure 4 2PI-1141 O. .1200 S/G B Pressure 35 2LI-4627-1 0 100 Pzr L-vel' 85 #T-4610-1 350 625 Loop A T 90 #T-4710-1 350 625 Loop.B :l 57 2PI-5602-2 0 60~ Cont;. Pressure-58 2TI-5664-2 0 300 Cont. Temperature 7.3.1.9 LOCA (100%) (Log 12)

  1. Tag # . Min  : Max Description-57 2PI-5602-2 0 60 Cont. Pressure 58 2TI-5664-2 0 300 . Cont. Temperature .;

36 2PI-4624-2 0 2400 Pzr Pressure 1 2 2PI-1041-1 0 1200 S/G A~ Pressure.

4 2PI-1141-1 0 1200 -S/G A. Pressure 35 2LI-4627-1 0 100 Pzr Level- .,

85 #T-4610 350 625 Loop A T  !

H 90 #T-4710-1 350 625 Loop B T H

~l o  :

28 a

p ERC892154 R:v. 04/17/89 7.4 Tape Save 7.4.1- Record Tape Serial No(s) 8.0 FINAL CONDITIONS Transient tests have been-.run, data collected, attached, and saved.

29

.i i'

ERC892154 R v. 04/17/89

\

ATTACIDEM E~  !

TURBINE TRIP / REACTOR TRIP /HIGH MSR LEVEL DATA l

l 3

1 1

1 l

e 30

ERC892154 R:v. 04/17/89 L

ATTACHMENT E-2 "A" MSIV CLOSURE. DATA I

4 I

i 1

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l 5

l 31

ERC892154 Rev. 04/17/89 ATTAClefENT E-3 MAIN TURBINE RUNBACK DATA j

I 32

ERC892154 R::v. 05/17/89 ATTACIDfENT E-4 LOSS OF MAIN CIRC VATER DATA I

.g 33

ERC892156 Rev. 04/17/89 ATTACHMENT E-5 "D" RCP TRIP DATA 1

J l

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i 4 1

]

34 1

i

ERC892156 Rev. 04/17/89 ATTACHMENT E-6 RX TRIP "A" S/G LEVEL DATA

.l i

l l m 35

1 l

~ERC892156 Rev. 04/17/89 ATTACHMENT E-7 LOSS OFF SITE POWER / NATURAL CIRCULATION DATA l

~

i "6.,

36

ERC892154 R:v. 04/177g9 ATTACIIMENT E-8 STEAM LINE BREAK (100%) DATA

-l

'l 37

l ERC892154 R v. 04/17/89 _q l

ATTACHMENT E-9 LOCA (200%) DATA J

1 i

i I

(

l -

1

s.  ;

1 38

ERC892154 Rev. 04/17/89 F. MALFUNCTION TEST 1.0 DISCUSSION A. Approximately 25% of the malfunctions that are required by either 10CFR55.59.C.3.1 or ANS 3.5.1985 Section 3.1.2 and are not tested during the transient testing portion of the performance test will be tested by this section. Additionally, any other malfunction to be used as a part of operator training shall be tested by this section.

A minimum of 25% of the malfunctions used by training will be tested each year.

B. The following assumptions have been utilized in preparing this section:

1) The simulator will be operated in accordance with approved plant procedures. Symptoms, automatic actions.and plant response described in these procedures will be used to evaluate simulator performance and there is no need to attempt to define every possible alarm or response in the Malfunction test body.
2) The " Anticipated Plant Response", detailed on the APR form gives initial plant response. These responses were obtained by discussion between training and operations department personnel and have been approved by licensed representatives of each group.

Subsequent action will be as required by normal system response (i.e. if pressurizer level decreases initially during a malfunc-tion the APR will indicate such, but the plant will be expected to respond properly, which for this example would be letdown flow decreasing and if necessary backup charging pump (s) starting).

C. The following termination criteria will be used during malfunction testing- I i

1) For malfunctions that do not result in a plant trip but do require a shutdown, terminate the malfunction test when the ,

shutdown is initiated. (ie. RC leak > T.S. but < CCP capacity) I

2) For malfunctions that result in a plant trip (automatic or manual) terminate the malfunction test when the plant is being controlled in accordance with the appropriate section of the E0P.
3) For malfunctions not covered by 1 or 2 above terminate the malfunction test when the plant reaches stable conditions but it is not necessary to recover - ie. during a dropped CEA from power malfunction, it is not necessary to withdraw the CEA.

D. The following process will be used to conduct and document each l malfunction test: ~

1) The test director will review the malfunction, AOP, E0P and

" Anticipated Plant Response" with the test personnel prior to each malfunction test.

39

_ _ _ _ _ _ _ - _ . /

k ERC892154 Rev. 04/17/89

2) Test personnel and the test director will'. function as an operating crew using all applicable' procedures during each malfunction test.-
3) Plant response will be. compared to." Anticipated Plant Response".

. Actual ~ response will be'noted'on the'APR form next to the-anticipated. response.

4) Deviations .will be annot ated in- the results section' of the APR.
5) If:the acceptance criteriajin section 5.0 have been met, the Test Director will sign the APR form as being accepted.
6) Two 8-pen recorders will be.run during each malfunction test.

~

They.will be labled and_ collected after each test and maintained' with the APR forms' The- following points will normally, be assigned to the pen recorders.

Pzr Press Pzr Lvl Log Power Th Tc SG Press (A'&B)--

SG Lvl (A'&B)

MS Flow (A'&B) '

MF Finw (A'&B)

MW Cent Press Coat Temp These points can be changed by the. Test Director' to better monitor the specific malfunction.

2.0 REFERENCE (S) 21 ANS-3.5, 1985, 3.1.2, 4.2.2, and A3.4, 2.2 10 CFR 55.59.C.3.i.A through AA

-l I

3.0 EQUIPMENT 3.1 None i

l 4.0 INITIAL CONDITIONS j i

4.1 Initial Conditions (ICs) will be as stated in the Malfunction -l list in Attachment F-1. 'l l 5.0 ACCEPTANCE CRITERIA  %, j i

5.1 Observable change in the parameters correspond in direction to' actual l j' plant data or to that' expected from best estimate and not violate ~ l l- the physical laws of nature.

l 40 )

I i

, ERC892154 Rev. 06/17/89 5.2 The Simuistor shall not fail to cause an alarm or trip if the reference plant would have caused an alarm or trip.

5.3 The Simulator shall not alarm or trip if the reference plant would not alarm or trip.

6.0 NON-ACCEPTANCE OR SIMULATOR RESULTS 6.1 Simulator results do not have to parallel source data, however, observable differences, those that detract from positive training, those declared unacceptable by evaluation based on acceptance criteria, and those not tested, will not be used for routine training.

7.0 PROCEDURE 7.1 Test each malfunction in accordance with the Anticipated Plant Response sheets.

7.2 The malfunctions are split into four groups, with one group to be performed each year. The lists are identified by the test year number of the cycle in the column following'the description of the malfunction. These are in addition to the malfunctions which are required to be performed annually.

Annunciator malfunctions are handled identically, therefore, a small-portion will be tested each year.

Valve malfunctions are handled identically hence a small number of valve malfunctions will be tested each year.

7.2.1 Malfunction Test Schedule Year One Malf. Description Test Year 1

003 T Cold Leak 1 005 RCP Seal Fail 1 i

009 PRZR Back up Heaters Fail 1 010 RCP Start Perm Override 1 019 Degrade CEA Motion 1 020 Defeat Group Motion 1 022 Defeat Auto CEA Control 1 024 Reactor Trip 1 036 FW Heater Degradation 1 038 Steam Leak in MSR Shell 1 039 Turbine Trip 1 040 Turbine Loss of Lube Oil 1 047 Faulty EHC Control VLV Demand 1 051 Charging P? Discharge Leak 1 054 LPSI Suction Leak 1 058 Inadvertent SIAS Actuation 1 059 Inadvertent CIAS (Hi' Cont. Pres) 1 066 Loss of CCW to L/D Hx 1 41

'  ;" w b x. y ,.

E ERC892154 Rev. 04/17/89

. 4

.Malf. Description- . Test Year 067 Loss of-Chilled Wtr.LTo'ContainL .1

'071 Loss of SW PP- 'c 1 072. Loss of StatorLCooling Wtr. 1 1 075 Loss of Condensor Vacuum' 1-084 M Gen. L/0 Trip. .

, 1: ..m

085
'M Gen. Volt Reg.' Failure ~1 090. Loss of 500KV 1' 097. Log. Power Chan Failt 1 T02- Letdown Temp. Failures - 'l 7.2.2 - Malfunction Test Schedule, Year Two Mal" Description Te'st Year 001 - S/G Tube Rupture- 2 002- 'T Hot. Leak 2 004 RCP Lube.0il Loss 2 H 006- RCP Safety: Reset Press 2

-011 PRZP Safety Reset1Press 2 012 PRZR Safety Leak 2 013 PRZR Steam Leak 2

'015 DROP CEA 2 016 Eject Cea 2.

018 Group Vithdrawal 2' 028 NFW PP Trip- .2 030 Condensor Vacuum PP Fail 2' 091 Circulating Water PP Fault 1 2

'037 MS Leak In/Out Containment- -2 041 Turbine Trip-Fail. 2-044' MS Relief Reset Press 1 Change. 2 048 Letdown HX Tube Leak 2 053 LPSI PP Fault '2 055 LPSI Discharge-Leak 2' 060 Inadvertent CSAS .

2 068 Loss of ACW to Turb Lube Oil 2 076 FWC System Fail-(CV Open) 2 079 MFWPT Loss of Lube Oil- 2

'086 M Gen Exciter Failure ,

2

'091 . Grid' Degradation (Freq): 2 098 Start Up Chan Fail 2-T04 S/G Level control 12 l

1 s .

42

3 '$ , ,

ERC892154-Rev. 04/17/89 7.2.3 Malfunction Test Schedule Year Three

' Mal: Description. Test Year-005 RCP Seal.' Fail.(Hi, Mid, Lo) 3 i 007 RCP. Rotor _ Lock 3-

-014 Reactor: Vessel, Vent Leak 3 017 Drop Group of CEA's 3.'

026- Reactor Trip Failure. '3~

'027- -Condensate PP Trip ._

3' W 032 Condensate Disch HDR Leak 3 034 Heater Drn. PP Fault '3-043 Glandseal Reg. Setpoint Drift. L3'~

045' EHC to Intercept Valves :3 l l- __052 Boric Acid PP. Fault 3. -

056' SDC HX Tube Leak 3 061 TCB Pair-Fail to Trip' 3 064' Loss.'of SW to SDC Hx1 3 q 070- No CCW to MFWP Lo Cooler '3 073 _SDBCS Fails to Open Valves '3 1 077 Loss of SW to D/G 3- l 080- Elect Bus Loss. l 081 Load Rejection 3-082 Station Blackout 3 088 Fall Unit Aux. Transformer '3 092 Cont. Spray PP Fault- 3' T01 2PRZR Level / Press. Cont. Fail' 3 T09 SPDS Update Failure 3

. Malfunction Test Schedule Year Four Mal Description Test Year i l

005 Steam Header Press: 4.

008 RCP Sh'ft a Broken? 4' 'i 021 Loss' Group W/D Sequence Perm. 4

.)

023 Uncontrolled CEA Motion -4  !

029 EFW PP Trip .

4 l

-033 Condensor Tube Leak' 4  ;

035 FW PP Disch Leak 4  !'

042 Turbine High Vibration 4 046 Freeze. Signal to Governor Valves 4 049 Charging PP_ Failure :4 ,

053 HPSI Fail to Start 4 1 l 057 False. Reactor Trip. 4- i l

062 No.ESAS Response'to ESF Actuat 4 063 Loss of CCW 4 063 Loss of CCW 4 i 065 Inhibit Brkr Status Change 4'  !

l 069 Loss of SW to CCW Loop 1 4' 069 Loss of SW t'o cCW Loop 2 4 ,

'I I

43-

1

^b

ERC892154 Rev.104/17/89 .

l Mal  : Description Test Year f

I C 074 Loss of ACW' . . _

4' .h D78 Loss ACW to Stator Cooling- I

'0&3' Loss,of Instrument' Bus .

4 ,

087 <

Loss of D/G Lube Oil / Start Air -4 ..

0891 Fail Start up Transformer. 4 093- Loss of.' Inst.. Air:(Leak): .4 094- Fail'ed' Fuel ~ 4-

-095- Linear Pwr Safety Channel Fail l4

} <

096. Linear'Pwr. Control'Chanel Fail; 4- 1 T02 ~. .VCT Lvl' Transmitter Fail' 4-7.3' Test the following malfunctions. annually at'BOL.and.EOL to- i evaluate inherent Core characteristics: .

l

2. Small Steam Leak
3. ' Dropped CEA
4. Loss of SDC Flow'
5. Loss of One MFWP .

i

  • 6. T/G Runback (Loss of ACW to SWC)
  • These malfunction will be recorded on tape,. saved,-plotted -'

and attached.~ (Attachment F-2)  !

A. Main Steam Line Break - Tape Serial-

1) BOL - Log-#13 (Start )(Stop );

^

2) EOL - Log #14-(Start-- )(Stop -)

B. T/G Runback

1) BOL - Log #15 (Start )(Stop- -)
2) EOL - Log #16 (Start ')(Stop. ). j 8.0 FINAL CONDITIONS 1 Malfunction has been tested and the Malfunction-Verification List has been ij signed by the appropriate person or problems have been identified and a .j Discrepancy Report written to initiate corrective action.

.l I

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44'  !

1 l

ERC892154. i Rev. 04/17/89 .!

ATTACHMENT F-1 j MALFUNCTION VERIFICATION. LIST

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NO 1 1 1 .

UM 4321 21 0987654321 4321 4321 2l 21 MP BO EN RE N

T llll1llllillllllllllll ll1lil l l RRRR RRRRRRRRRRRR RRRR RRRR RR SS CCCC CCCCCCCCCCCC CCCC CCCC CC //

PPPP PPPPPPPPPPPP PPPP GG CCCC l l TTTT LMULMULMULMU LLLL oooo lool TT r rrr o ip o ip o ip o ip oooo lll l tt uu iiii w dp w dp w dp w dp s s s s dddd bb pp pp edeedeedeede s sss LL ee rl rrlrrl rrl r LLLL ee P PPP e e e e LLLL eeee gg LL 3333 S SS SS SS S uuuu gggg '

ee 2222 eSeeSeeSeeSe bbbb LL aa M DCBA aeaaeaaeaaea eeee LLLL ee kk A l allall allal eeee a a L l l l l OOOO a aaa kk 22 F F FF FF FF F iiii kkkk EE U aFaaFaaFaaFa llll BA 22 N i aiiaiiaiiai DCBA 44 C l il li ll il li l PPPP BA T ul uul uuluul u 3333 I r ur r ur r urrur 2222 O ereereereere DCBA N e e e e P PP PP PP P D 3P33P33P33P3 E 232232232232 S D2DC2CB2BA2A C D C B A R I

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NO UM 54321 1 1 21 21 4321 21 4321 4321 MP

= - -

BO EN RE

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DDDDD R P PP SS RRRR PP. RRRR RRRR rrrrr V z zz aa CCCC zz CCCC CCCC ooooo ppppp r rr ff PPPP rr PPPP PPPP ppppp V ee -

e S SS t t IIII BB SSSS LLLL eeeee n t aa yy nnnn UU hhhh oooo ddddd t a ff t t t t aaaa cccc ee VV eeee HH ffff kkkk RRRRR L S t t l1 rrrr t t t ttt eeee ooooo e p yy vv llll rr -

dddd ddddd a a -

oooo BBBB k c VV PP cccc OO rrrr RRRR M 54321 e l1 rr kkkk- Nf oooo oooo. A 2 vv ee ss f kkkk t t t t. L R- L e

O0OO eeee oooo- F 1

a LL ee ss vvvv nnnn rrrr- U eeee N k aa R R' rrrr PPPP PPPP C kk ee rrrr 3333 3333 T 2 s s iiii 2222 2222 I T 22 ee dddd DCBA DCBA O 1 PP t t eeee N SS -

44 22 PPPP D 66 PP 3333 E 33 SS 2222 S 43 44 DCBA C 66 R 33 I 43 P 4 T I

7 O

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T ED SA TT EE D

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C NO 33333333322222222221 1 1 1 1 1 1 1 1 1 _

UM 87654321 0987654321 0987654321 09876 MP BO EN RE

- N T

llllllllllillllllllllllllllllllll l

- _ l DDDDDDDDDDDDDDDDDDDDDDDDDDDDDDDDD r rr rrrrrrrr rrrrrrrrrrrrrrrrr rrrr r ooooooooooooooooooooooooooooooooo ppppppppppppppppppppppppppppppppp ppppppppppppppppppppppppppppppppp eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee ddddddddddddddddddddddddddddddddd . .

~

R RRRRRRRRRRRRRRRRRRRRRRRRR RRRRRRR o ooooooooooooooooooooooooo ooooooo ddddddddddddddddddddddddddddddddd -

~

M 33333333322222222221 1 1 1 1 1 1 .1 l 1 9876 A 87654321 0987654321 098765432l 0 L

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