ML20199F740

Rev 9 to ANO-1 Simulator Operability Test,Year 9 (First Cycle)

ML20199F740
Person / Time
Site:	Arkansas Nuclear
Issue date:	11/16/1998
From:	Cotton S ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20199F708	List: 1CAN019901, Forwards Rev 8 to ANO-1 Simulator Performance Testing Rept. All Performance Issues Identified During Operability Testing Have Been Corrected.New Malfunctions Were Tested & Incorporated Into Continuing Testing ML20199F721 ML20199F740
References
NUDOCS 9901220037
Download: ML20199F740 (104)

Text

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ARKANSAS NUCLEAR ONE UNIT 1 SIMULATOR OPERABILITY TEST YEAR 9 (First Cycle)

REVISION 9.0 November 9,1998 DATE COMMENCED:

DATE COMPLETED:

PREPARED BY:

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DATE

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APPROVAL:

e SUPVQqlMULATOR TQlNG iDATE lw f (&

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/DIR..TRNG AND EMERd. PLANNING DATE l

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9901220037 990114 l

PDR ADOCK 05000313 P

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t UNIT 1 OPERABILITY TEST O

FORWARD The Simulator Operability Test will be performed annually. The collected data will be evaluated, discrepancies, if any, explained and attached to the Annual Simulator Report.

i The Operability Test will provide the data to document satisfactory simulator response i

on an ongoing basis. It is required that all malfunctions listed in ANS-3.5,1995,3.1.2 and the operation test be tested every 4 years and a minimum of 25% tested each year.

The lists provided are suggested and should be followed. In the event that specific conditions warrant a change in the events / malfunctions being performed, the Supervisor, Simulator Training will be informed of the necessary changes or revision to ensure that the changes are re-incorporated to meet the aforementioned requirements of ANS 3.5,1995.

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OPERABILITY TEST November 9,1998 1

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b eN TABLE OF CONTENTS t

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A. SIM U LATOR REAL TIM E TEST............................................................................... 4 B. N O R M AL O P E RATIO N S TE ST................................................................................ 9 NORMAL OPERATING PROCEDURES

......................................... 17 PROCEDURE STEPS THAT WERE NOT COMPLETED 18 C. STEADY STATE O P ERATIO N S TEST.................................................................. 19 40% RATED POWER

..... 26 66% RATED POWER..

........... 27 100% RATED POWER

. 28 D. S U RV El L LA N C E T E S T.......................................................................................... 29 COMPLETED SURVEILLANCE TESTS.....

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PROCEDURE STEPS TIIAT WERE NOT COMPLETED....................................

38 SURVEILLANCE PROCEDURES......

39 E. T RA N S 1 E N T T E S T................................................................................................

MAN UAL REA CTOR TRIP..

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I SIMULTANEOUS TRIP OF ALL FEEliWATER PUMPS

............................. 50 SIMULTANEOUS CLOSURE OF BOTE MSIVs..........

........ 51 SIM ULTANEO US TRIP O F ALL RCPs....

................................. 52 i

TRIP O F O N E R CP...............................

................................ 53 MAIN TURBINE TRIP AT 40% POWER WITHOUT A REACTOR TRIP 54 MAXIM UM RATE POWER RAMP

.... 55 MAXIMUM SIZE RCS RUPTURE AND LOSS OF OFFSITE POWER

........... 56 r

l MAXIMUM SIZE UNISOLABLE MAIN STEAM LINE BREAK

...................................... 57

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I SLOW PRIMARY SYSTEM DEPRESSURIZATION TO SATURATION....................

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TIME IN LIFE TEST

.......... 59 F. M AL F U N CTIO N TE S T............................................................................................ 6 0 MALFUNCTION CAUSE AND EFFECTS LISTING 89 G. RETEST ITEMS FROM LAST OPERABILITY TEST............................................ 90 REFERENCES.............................................................................................................91 LIST OF POINTS RECORDED DURING TRANSIENT TEST USING OTI.........

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LIST OF POINTS RECORDED DURING TRANSIENT TEST USING OT2..

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LIST OF POINTS RECORDED DURING TRANSIENT TEST USING OT3.

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1 LIST OF POINTS RECORDED DURING TRANSIENT TEST USING OT4.................

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LIST OF POINTS RECORDED DURING TRANSIENT TEST USING OT5................

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DRLOG........................................................................................................................97

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i SU BJ ECT M ATER EXPERT EXPERIENCE SU M M ARY............................................. 98 C H RO N O LOG I C A L LOG............................................................................................. 99 DELOGGIN G HISTORICAL DATA LOG S................................................................. 100 O P E RA BI LITY TE S T S TA F F..................................................................................... 1 01 4

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A. SIMULATOR REAL TIME TEST i

r 1.0 DISCUSSION The purpose of this test is to assure that the Simulator is running in real time.

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Real-time calculations may be performed on-line by load module RTTEST which resides on the RSX. It calculates a real-time ratio by continually dividing elapsed simulator time by elapsed real time.

l This test will also gather CPU spare cycle time statistics for normal, transient,

.and emergency operations.

2.0 REFERENCE (S) a 2.1 ANS-3.5,1995 A3.1, ANS NPP Simulator for Operator Training.

1 2.2 ANO Unit-1 instructor Station User Guide.

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2.3 REALTIME program 3.0 EQUIPMENT t

3.1 ANO-1 Simulator 4.0 INITIAL CONDITIONS 4.1 100% Power, IC-2 r

5.0 ACCEPTANCE CRITERIA l

5.1 REAL-TIME ratio will be greater than 99% for all test cases.

5.2 CPU spare cycle time will be greater than 0% for all test cases.

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6.0 NON-ACCEPTANCE OF SIMULATOR RESULTS

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i 6.1 if the Simulator REAL-TIME ratio or spare cycle time do not meet the acceptance criteria in 5.0, adjustments will be made before the Simulator is used for routine training.

7.0 PROCEDURE - NORMAL OPS INIT 7.1 Initialize to 100% Rated Power (IC-2).

Place Simulator in RUN.

TSM>lMODE ONRA 7.2 Using Z:CPUSP obtain the CPU spare cycle time for the RSX 1 by entering the following at the TSM prompt:

t 7.2.1 TSM>! ACTIVATE Z:CPUSP 7.3 Obtain data from printer and record the minimum spare cycle times here.

CPU 7.4 On a RSX terminal, type TSM>RT. After 2 minutes, place simulator in FREEZE. Record here the final displayed value of RTRATIO.

REALTIME RATIO MODELXC

=

REALTIME RATIO MODELXI

=

REALTIME RATIO MODELXM

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REALTIME RATIO MODELXK

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REALTIME RATIO MODELXL

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AVG REAL TIME RATIO

=

OPERABILITYTEST November 9,1998 5

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8.0 PROCEDURE -TRANSIENT OPERATION O

INIT V

8.1 Initialize to 100% Rated Power (IC-2). Place simulater in RUN. Trip the reactor.

8.2 Using Z:CPUSP obtain the CPU spare cycle time for the RSX by entering the following at the TSM prompt:

8.2.1 TSM>! ACTIVATE Z:CPUSP 8.3 Record the minimum spare times here.

CPU.

8.4 On a RSX terminal, type TSM>RT. After 2 minutes, place simulator in FREEZE. Record here the final displayed value of RTRATIO.

REALTIME RATIO MODELXC

=

REALTIME RATIO MODELX1

=

REALTIME RATIO MODELXM

=

q REALTIME RATIO MODELXK

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V REALTIME RATIO MODELXL

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AVG REAL TIME RATIO

=

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l 9.0 PROCEDURE - EMERGENCY OPERATION i

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9.1 Initialize the 100% Rated Power (10-2). Place simulator in RUN. Activate malfunction for a 100%

MSLB outside containment on A OSTG.

l 9.2 Using Z:CPUSP obtain the CPU spare cycle times for the RSX by entering the following at the TSM prompt:

9.2.1 TSM>! ACTIVATE Z:CPUSP I

9.3 Record the minimum spare cycle times here.

l CPU 9.4 On a RSX terminal, type TSM>RT. - After 2 minutes, place Simulator in FREEZE. Record here the final displayed value of RTRATIO.

lp REALTIME RATIO MODELXC

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REALTIME RATIO MODELXI

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REALTIME RATIO MODELXM l

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REALTIME RATIO MODELXK

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REALTIME RATIO MODELXL

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AVG REAL TIME RATIO

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FINAL CONDITIONS i

10.1 Data has been recorded and saved verifying computer Real Time during normal, transient, and emergency situations.

10.2 Spare cycle times exceed 0% for all cases recorded.

10.3 Real-Time ratios exceed 99% for all cases recorded.

10.4 List any DISCREPANCIES on Attachment A-1.

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ATTACHMENT A-1 REAL-TIME TEST l-DISCREPANCY LIST STEP UUMBER DESCRIPTION D.R. #

t NONE NONE NONE l

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1.0 DISCUSSION Normal operations are performed to demonstrate the ability to operate the Simulator in accordance with reference plant operating procedures.

i Normal operations will be tested by. splitting the normal operations test into four segments, one of which will be tested each year.

2.0 REFERENCE (S) 2.1 ANS 3.5,1995,3.1.1, ANS NPP Simulator for Operator Training.

2.2 ANO Unit 1 Operating Procedures, Attachment B-1.

j 3.0 EQUIPMENT 3.1 Stop watch.

l 4.0 INITIAL CONDITIONS l,Q

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4.1 Initial plant conditions will be as stated in Section 7.0.

5.0 ACCEPTANCE CRITERIA l

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 referenced plant.

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6.0 NON ACCEPTANCE OF SIMULATOR RESULTS 6.1 Non acceptance is the inability of the Simulator to perform reference plant normal operations using only operator actions normal to the reference plant or performance that distracts from training.

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

7.0 PROCEDURE l

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

The test will be split as follows:

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a.

In veer one.1999, the plant will be initialized at 100% power and will be brought to hot standby power by plant procedures and this l

test procedure. (Step 7.1.1) b.

In vear two. 2000. the simulator will be initialized at 25% power and i

will be brought to cold shutdown condition using plant procedures l

and this test procedure. (Step 7.1.2) l c.

In year three. 2001. the simulator will be initialized in cold l

shutdown, a plant heatup/startup to hot standby power will be done j

using plant procedures and this test procedure. (Step 7.1.4) Also, perform 70% power steady state with 3 RCPs to hot shutdown and

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return to 70% power. (Step 7.1.3) j d.

In year four. 2002, of the cycle, the simulator will be initialized at 100% Power and tripped, then recovered to 100% as directed by plant procedures. (Step 7.1.5)

NOTE:

Procedures are to be initiated / signed as i

appropriate.

NOTE:

All procedure steps that cannot be simulated shall be marked NS. These steps are to be listed on Attachment B-2 and explained. The steps of the l

procedure that are marked N/A as allowed by the l

procedure are not to be listed on Attachment B-2.

l NOTE:

Initial Conditions (ICs) will be stored as designated.

NOTE:

Use Fast Time for Xenon and Pressurizer Heatup as appropriate.

OPERABILITY TEST November 9,1998

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1 INIT 7.1.1 100% Power to Hot Standby (Year One,1999) 1.

Recall 100% power, Equil Xe, MOL.

2.

Establish the following ICs while reducing power to 20%.

IC-5 80% 4 RCP TRANS XE lC-6 50% 2 MFP TRANS XE l

l lC-7 35% 1 MFP TRANS XE l

IC-8 25% 1 MFP TRANS XE 3.

Using plant procedure, OP1102.004, reduce power to 20%. Do not exceed 30%/ hour rate of change.

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4.

Using plant proce' dure OP1102.010, shut down I

the plant to hot standby.

5.

Put all signed procedures, and required forms into a binder marked for this evolution. Do not l r include any surveillances; completed surveillances

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will be placed into a' separate binder.

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i INIT O

7.1.2 25% to Cold Shutdown (Year Two,2000) 1.

Recall 25% power, equil Xenon.

2.

Establish the following ICs while shutting down:

I 10-9 290 Cooldown in Progress IC-10 CSD stm in Pzr,DH cooling t

3.

Using plant procedure OP1102.010, shutdown I

and cooldown the plant to cold shutdown.

4.

Put all signed procedures, and required forms into a binder marked for this evolution. Do not l

include any surveillances; completed surveillances will be placed into a separate binder.

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l 7.1.3 70% Power Steady State with 3 RCPs to Hot INIT O

s"etee m eme aeterm ie 70* ee er. < veer r"<ee. 2004) 1.

Recall 100% power, equil XE, MOL. (IC-2) 2.

Using plant procedure OP1102.004, reduce power to < 60%.'

3.

Using plant procedure OP1103.006, stop the C reactor coolant pump.

4.

Using plant procedure OP1102.004, increase power to 70%.

6.

Use fast time Xenon on the lA console to equalize and stabilize Xenon for 70% reactor power.

6.

Establish IC-4 at 70% reactor power with 3 RCPs running.

7.

Using plant procedure OP1102.004, reduce power to 20%.

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8.

Using plant procedure OP1102.010, reduce power to hot shutdovm.

9.

Using plant procedure OP1102.002, startup the plant to 20%.

10.

Using plant procedure OP1102.004, increase power to 70%.

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Put all signed procedures, and required forms into a binder marked for this evolution. Do not include any surveillances; completed surveillances will be placed into a separate binder.

OPERABILITY TEST November 9,1998 13

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INIT 7.1.4 Cold Shutdown to 2% Power. (Year Three,2001) i 1.

Recall cold shutdown; no Xenon.

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Using plant procedure OP1102.02, heatup/startup the plant to 20% power.

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3.

Establish the following ICs while starting up:

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IC-11 CSD 225# Steam in Pressunzer l

IC-12 420 F 720# HU in Progress IC-13 537 F Group One Out l

lC-14 537* F Safeties Out IC-15 Reactor Critical at 10E-8 Amps IC-16 2% From Startup AFW Pump On 4.

Put all signed procedures, and required forms j

into a binder marked for this evolution. Do not i

include any surveillances; completed surveillances I

will be placed into a separate binder.

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7.1.5 Reactor Trip Recovery from 100% Power INIT 2% Power to 100% Power (Year Four,2002) 1.

Recall IC-2,100% Power 2.

Manually trip the reactor.

3.

Carry out all required steps of EOP 1202.01 Reactor Trip.

4.

Verify the reactor is stable at Hot Shutdown.

5.

Establish IC-19, Hot Shutdown Post Trip.

6.

Calculate the value of Xenon 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> post trip.

7.

Use fast time Xenon and establish new Xenon concentration for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> post trip.

8.

Establish IC-20, Hot Shutdown 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> post trip.

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Complete OP1102.006, Reactor Trip / Outage Recovery.

10.

Using plant procedure OP1102.002, start up the plant to 20%.

11.

Establish the following ICs while increasing reactor power to 20%.

IC-13 535 F Group 1 rods out IC-14 535 F Safety rods out IC-15 Reactor Critical at 1E-8 amps IC-16 2% from startup IC-17 7% from startup IC-18 15% from startup 12.

Using plant procedure OP1102.004, increase power to 100%.

13.

Put all signed procedures, and required forms OPERABILITY TEST November 9,1998 15

into a binder marked for this evolution. Do not include any surveillances; completed surveillances will be placed into a separate binder.

8.0 FINAL CONDITIONS The normal power operations are completed. All required ICs are established.

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OPERABILITY TEST November 9,1998 16 m,

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ATTACHMENT B-1 NORMAL OPERATING PROCEDURES t

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ATTACHMENT B-2 PROCEDURE STEPS THAT WERE NOT COMPLETED PROCEDURE:

STEP #

REASON FOR NON-COMPLETION l

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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 at various power levels.

i 2.0 REFERENCE (S) 2.1 ANS 3.5,1995,4.1, A.3.2, ANS NPP Simulators for Operator Training.

3.0 EQUIPMENT 3.1 Stop Watch 3.2 Personal computer setup as a plant computer terminal and spreadsheet software.

4.0 INITIAL CONDITIONS 4.1 initial Plant Conditions will be as stated in this procedure.

5.0 ACCEPTANCE CRITERIA 5.1 The simulator computed values for steady state, full power operation with the reference plant control system configuration shall be stable and not vary more than +/- 2% of the initial values over a 60 minute period.

5.2 Simulated computed values of critical parameters shall agree' with the reference plant within +/- 2% of the instrument range and shall not detract from training.

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5.3 Simulator computed values of non-critical parameters shall agree with the reference plant within +/- 10% of the instrument range and shall not detract from training.

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9 NOTE:

The OTSG Operate range levels are not to be considered as critical

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p parameters due to the dynamic nature of a B&W OTSG. The levels i

change at the reference plant due to fouling and efficiency that are not readily identified and have no effect on training within the small band the level changes. The levels indicated on the data sheets are taken from March 1993 control room logs.

6.0 NON ACCEPTANCE OF SIMULATOR RESULTS 6.1 Non acceptance is defined as any critical parameter value outside the range set forth in Section 5.0.

6.2 Non acceptance shall halt the routine training involving such operations. Discrepancies shall be recorded, models enhanced, and

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retested, as required.

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NOTE:

if evaluation of collected simulator data is unsatisfactory, rerun appropriate portions of data collection after adjustments are completed.

NOTE:

Non-critical parameters will be compared by Operator observation only and will not be saved.

7.0 PROCEDURE i

7.1 Obtain Simulator Data for 40% Power INIT

-(These steps are repeated for 66 and 100%)

7.1.1 Recall the desired power with equilibrium xenon.

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7.1.2 Verify steady state conditions.

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l 7.1.3 Start the Archive process on the PC acting as I

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a plant computer use GD OT5 (depress F6) 40 66 100 7.1.4 Start the stop watch to measure >20 minutes.

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At >20 minutes, stop data collection.

40 66 i

7.1.5 Start the stop watch to measure >60 minutes.

At >60 minutes,stop data collection.

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7.4 e riaimi" e t 8eet 18 i<ei'e. T8 s>=#ieter i

data collected must be between the max and min 40 66 100 limits listed on each data point. The cause of 1

any point not being between the m'ax and min shall be determined and corrected. The test shall be repeated to prove performance at steady state.

7.1.7 Delogging the Data File refer to

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Attachment R9.

40 66 100 7.1.8 Attach all graphs and the data printouts to

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1 Attachment C-1, C-2 or C-3 as appropriate.

40 66 100 7.2 Obtain Simulator Data for 66% power.

7.2.1 Repeat steps 7.1.1 through 7.1.10 for 66 % power.

l 7.3 Obtain Simulator Data for 100% power.

7.3.1 Repeat steps 7.1.1 through 7.1.10 for 100% power.

Data shall be run >60 minutes at 100% power.

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OPERABILITY TEST November 9,1998 21

7.4 Delogging Simulator Data pg 7.4.1 40% rated power Reference Plant Simulator D:scription Tag Actual Min Max Min Value Max Value Reactor Power Nil 5 40.0 39.2 40.8 Core Thermal Megewetts QCORE 1027 1006 1047 Generred Watts J1 GEN 300 280 320 Teve 1000TMP1 579 577 581 A OTSG Pressure P2618A 900 878 922 Pressurizer Level L1001B 220 214 226 B OTSG Steam Temperature T2631 590 577 603 B OTSG Pressure P2617A 900 878 922 Pressurtzer Water Temperature T10018 647 633 661 j

RCS Pressure P1020 2155 2095 2215 A OTSG Steam Temperature T2681 595 583 607 A Main Feedwater Temperature T2629 370 360 380 Main Feedwater Flow F2627 2.184E6 2.06E6 2.304E6

.oop A Cold Leg Temperature T1016 569 567 571 Loop A Hot Leg Temperature T1011NR 589 587 591 Group 7 Rod Position Z7 AVG 90 88 92

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B Main Feedwater Temperature T2679 370 360 380 B Main Feedwater Flow F2677 2.184E6 2.06E6 2.304E6 Loop B Cold Leg Temperature T1045 569 567 571 Loop B Hot Leg Temperature T1039NR 589 587 591 I

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OPERABILITY TEST November 9,1998 22

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' 4.2 66% Rated Power Reference Plant Simulator Description Tag Actual Min Max

. Min Value Max Value Reactor Power Nil 5 66 63.5 68.5 Core Thermal Megawatts QCORE 1695 1631 1759 Generated Watts J1 GEN 555 535 575 Tave 1D00TMP1 579 577 581 A OTSG Pressure P2618A 905 883 927 Pressurtzer Levet L1001B 220 214 226 B OTSG Steam Temperature T2631 600 588 612 B OTSG Pressure P2617A 905 883 927 Pressurtzer Water Temperature T1001B 647 633 661 RCS Pressure P1020 2155 2095 2215 A OTSG Steam Temperature T2681 600 588 612 A Main Feedwater Temperature T2629 420 410 430 A Main Feedwater Fkw F2627 3.604E0 3.48E6 3.72E6 Loop A Cold Leg Temperature T1016 564 562 566

-.r. A Hot Leg Temperature T1011NR 595 593 597 Group 7 Rod Position Z7 AVG 90 88 92 B Main Feedwater Temperature T2679 420 410 430 B Main Feedwater Flow F2677 3.3E6 3.18E6 3.42E6 Loop B Cold Leg Temperature T1045 564 562 566 Loop B Hot Leg Temperature T1039NR 595 593 597 fl OPERABILITY TEST November 9,1998 LJ 23

' 4.3 100% Rated Power

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Reference Plant Simulator Description Tag Actual Min Max Min Value Max Value Reactor Power N115 100 97.5 102.5 Core Thermal Megawatts QCORE 2568 2503 2632 Generated Watts J1 GEN 890 870 910 Tave 1D00TMP1 579 577 581 A OTSG Pressure P2618A 900 876 924 Pressurtzer Level L10018 216 210 222 B OTSG Steam Temperature T2631 593 579 607 8 OTSG Pressure P2617A 900 876 924 Pressurtzer Water Temperature T1001B 647 633 661 RCS Pressure P1020 2155 2095 2215 A OTSG Steam Temperature T2681 567 573 601 A Main Feedwater Temperature T2629 454 444 464 A Main Feedwater Flow F2627 5.46E6 5.34E6 5.58E6 Loop A Cold Leg Temperature T1016 559 545 573

-5 A Hot Leg Temperature T1011NR 602 589 615 Group 7 Rod Positen Z7 AVG 90 88 92 B Main Feedwater Temperature T2679 454 444 464 B Main Feedwater Flow F2677 5.46E6 5.34E6 Sf,8E6 Loop B Cold Leg Temperature T1045 559 545 573 Loop B Hot Leg Temperature T1039NR 602 589 615 (9

OPERABILITY TEST November 9,1998 L) 24 9

l 7.4.4 Attach Simulator Data O

Attachment C-1,40% Rated Power Data Attachment C-2,66% Rated Power Data Attachment C-3,100% Rated Power Data 8.0 FINAL CONDITIONS t

Steady State tests for 40%,66% and 100% are completed. All required Simulator data points are delogged from historical data, printed out to hard copy

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and saved to a computer. All printouts are attached to the appropriate Attachment C-1, C-2, or C-3.

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OPERABILITY TEST November 9,1998 25

ATTACHMENT C-1 O

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ATTACHMENT C-2 66% RATED POWER l

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I ATTACHMENT C-3 100% RATED POWER l

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D. SURVEILLANCE TEST O

1.0 DISCUSSION I

The Surveillance Test is performed to demonstrate the ability to perform Normal l

Operations surveillances in accordance with reference plant procedures. The j

following criteria was used to select which surveillances will be run:

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Safety.related and routinely performed by operations Requires control room manipulations i

l Provide training value 3

Some surveillances have been deleted or added due to the changing needs of l

Operator training. The symbol A99 will be used to indicate the addition of a new i

surveillance during 1999, and D99 to indicate deleting a surveillance. (Use A9X and Deleted 9X for future years) 2.0 REFERENCE (S) 2.1 ANS-3.5,1995,3.1.1, ANS NPP Simulators for Operator Training.

2.2 ANO Unit 1 Surveillance Test Procedures, 1102,1103,1104,1105,1106,-

1304,1305 Series.

-i 3.0 EQUIPMENT i

3.1 Stop Watch 4.0 INITIAL CONDITIONS 4.1 Plant Conditions will be as required by Attachment D-1.

4.2 When possible, the surveillance may be completed during normal operations tests.

5.0 ACCEPTANCE CRITERIA 5.1 The Simulator will perform, without distraction from training, reference plant surveillance procedures.

OPERABILITY TEST November 9,1998 29

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5.2 The simulator shall satisfactorily perform each surve'illance. If the Q,s surveillance requires a Job Order to correct the reference plant, then the Test Director shall write a DR to correct the simulator response.

6.0 NON ACCEPTANCE CRITERIA l

6.1 Non acceptance is defined as the inability to perform surveillance tests, or those that detract from training.

l 6.2 Non acceptance shall halt routine training involving such operations.

Discrepancies shall be recorded on a DR and logged on attachment R-8 i

DR log, models enhanced, and retested, as required.

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7.0 PROCEDURE 7.1 Using the latest revision of the referenced plant operating procedures, perform the surveillances for the indicated year as listed in Attachment D-1.

7.2 Each surveillance shall be filled out completely. There shall be no blanks that are not filled.

A 7.3 The Test Director shall sign as the Shift Supervisor and Operations V

Management.

7.4 All steps that can not be completed shall be explained on Attachment D-2.

Completed Attachment D-2 forms will be placed in the binder for Attachment D-2.

7.5 Any surveillance that is found as unsatisfactory shall be repeated after the simulator is corrected. The failed surveillance shall be retained and remain with the satisfactory surveillance test.

7.6 Completed surveillance forms will be placed in the binder for Attachment D-1 and the Test Director shall initial the surveillance listing, Attachment D-1, as sat or unsat.

8.0 FINAL CONDITIONS Surveillance tests are completed and recorded on the index of Attachment D-1.

All surveillance forms are in the Attachment D-1 binder. All steps that can't be completed are recorded on attachment D-2.

(]

OPERABILITY TEST November 9,1998 v

30 l

ATTACHMENT D-1 COMPLETED SURVEILLANCE TESTS Required Year Plant of Surveillance Description Condition Initials Cvele 1015.02 Att A Verification of DH Removal CSD 1

and "LTOP" When RCS is (SaUUnsat) 5300 F 1015.02 Att F Verification of DH System CSD 2

Alignment (SaVUnsat) 1102.01 Supp 1 RCS High Point Vent Note 1 3

Operability Check (SaVUnsat) 1104.04 Supp 6 DH Suct Isol Vivs CV-1050 &

Note 2 4

CV-1410 Leak Test (SaVUnsat)

(~}

1102.01 Supp 3 Main Steam & MFW lsol Note 3 1

t/

Valve Test (SaVUnsat) 1102.10 Supp 1 Low Temp Overpressure Note 5 2

Protection Alarm Test (SaVUnsat) 1103.05 Supp 1 Exercising of Pzr Electromatic CSD 3

Relief Viv (PSV-1000)

(SaVUnsat) 1103.13 Supp 1 RCS Leak Rate Determine Power Ops 4

When RCS Leakage is Not Being (SaVUnsat)

. Returned to RCS 1104.01 Supp 1 Core Flood Check Vive Test Note 4 1

(CF-1 A, CF-1B, DH-14A, (SaVUnsat)

DH-14B) 1104.02 Supp 1 RCS Loop A HPl MOV Power Ops 2

Quarterly Test (SaVUnsat)

(

OPERABILITY TEST November 9,1998 31 l

l

. = _

d l

' ATTACHMENT D-1, (CONTINUED) l r

COMPLETED SURVEILLANCETESTS i

Required Year Plant of L

Surveillance Description Condition initials Cy_9.lt l

1104.02 Supp 2 RCS Loop B HPI MOV Power Oos 3

i Quarterly Test (Sat /Unsat) i i

1104.02 Supp 3 HPl Pump P-36A Test -

Power Oos 4

i (Sat /Unsat) l 1104.02 Supp 4 HPl Pump P-36B Test Power Oos 1

(Sat /Unsat) 1 1104.02 Supp 5 HPl Pump P-36C Test Power Oos 2

(Sat /Unsat) f 1104.02 Supp 6 RCP Seal Bleedoff CV Note 6 3

l Stroke Test (Sat /Unsat) 1104.02 Supp 7 HPI Flow Path Verification CSD 4

(Sat /Unsat) 1104.02 Supp 8 MU & P System Check Valve CSD 1

and CV Stroke Test (Sat /Unsat) 1104.04 Supp 1 LO Press Inj (DH) Pump P-34A Power Oos 2

& Components Quarterly Test (Sat /Unsat) l 1104.04 Supp 2 LO Press inj (DH) Pump P-348 Power Oos 3

& Components Quarterly Test (Sat /Unsat) 1104.04 Supp 3 DH Suct MOV & Injection CSD 4

Check Valve Stroke Test (Sauunsat) 1104.05 Supp 2 RB Spray NAOH Addition Power Ocs 1

Valves Quarterly Test (Sat /Unsat)

OPERABILITY TEST November 9,1998 32 i

lg ATTACHMENT D-1, (CONTINUED) i COMPLETED SURVEILLANCE TESTS i

l l

Required Year l

Plant of Surveillance Description Condition initials Cvele

~

1104.05 Supp 3 RB Spray Pump P-35'A Power Ops 2

Quarterly Test (SaVUnsat) l 1104.05 Supp 4 RB Spray Block (CV-2400 &

Power Oos 3

CV-2401) Stroke Test (SaUUnsat) 1104.05 Supp 5 RB Spray Pump P-35B Power Oos 4

Quarterly Test (SaVUnsat) i 1104.29 Supp 1 Service Water Pump P-4A Test Power Oos 1

(SaVUnsat) 1104.29 Supp 2 Service Water Pump P-4B Test Power Oos 2

(SaVUnsat) 1104.29 Supp 3 Service Water Pump P-4C Test Power Oos 3

(Sat /Unsat) 1104.31 Supp 1 Hydrogen Sampler C178 Test Any 4

(SaVUnsat) 1104.31 Supp 2 Hydrogen Sampler C179 Test Any 1

(Sat /Unsat) 1104.31 Supp 3 Hydrogen Recombiner M55A Note 7 2

'l Functional Test (SaVUnsat) i 1104.31 Supp 4 Hydrogen Recombiner M55B Note 7 3

Functional Test (Sat /Unsat) l l

33 N

l

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ATTACHMENT D-1, (CONTINUED)

U COMPLETED SURVEILLANCE TESTS l

Required Year Plant of Surveillance Descriotion Condition Initials Cycle 1104.31 Supp 5 M55A Heatup Test Power Oos

.4 l

(SaVUnsat) 1104.31 Supp 6 M55B Heatup Test Power Ops 1

(Sat /Unsat) 1104.33 Supp 3 Monthly RB Cooling Unit Test Any 2

(SauUnsat) 1104.33 Supp 4 RB Purge System Test CSD 3

(SaUUnsat) 1104.33 Supp 5 RB Cooling Units VCC-2C &

Power Oos 4

VCC-2D Flow Test (SaVUnsat) 1104.33 Supp 6 RB Cooling Units VCC-2A, Power Oos 1

VCC-2B Flow Test (SaUUnsat) 1104.36 Supp 1 DG1 Monthly Test Any 2

(SaVUnsat) 1104.36 Supp 2 DG2 Month'ly Test Any 3

(SaVUnsat) 1104.36 Supp 9 DG1 Endurance & Load Reject Any 4

Test (SaVUnsat) 1104.36 Supp 10 DG2 Endurance & Load Reject Any 1

Test (SaVUnsat) 1104.43 Supp 1 Penetration Room Ventilation Any 2

Lead System Monthly Test (SaVUnsat)

OPERABILITY TEST November 9,1998 34

i ATTACHMENT D-1, (CONTINUED)

O COMPLETED SURVEILLANCE TESTS

- Required Year Plant of Surveillance Descriotion Condition Initials Cycle i

1104.43 Supp 2 Penetration Room Ventilation Any 3

- Standby Monthly Test (SaVUnsat) i 1104.43 Supp 3 Penetration Room Ventilation Any 4

Sys 18 Month Surveillance Test (Sat /Unsat) 4 1105.05 Supp 2 EFIC Functional Test CSD 1

(SauUnsat) 1105.09 Supp 1 Absolute & Relative Position Power Oos 2

indication Comparison (SaVUnsat)

-1106.06 Supp 1 Electric Emergency FWP (P-7B) Power Oos 3

1 Test (Monthly)

(Sat /Unsat) 1106.06 Supp 2 Steam Driven Emergency'FWP Power Oos 4

(P-7A Test (Monthly)

(SaVUnsat) 1106.06 Supp 3 Emergency FW Valve Stroke Power Ops 1

Test (SaVUnsat)-

1106.06 Supp 4 EFW Flow Path & Automatic CSD 2

Actuation Verification.

(Sat /Unsat) 1106.09 Supp 1 Turbine Overspeed Trip Test 20% Power 3

(Sat /Unsat) 1305.06 Integrated ES System Check CSD 4

(SaVUnsat) 1305.07 Supp 1 Normal Operation Valve Stroke Power Oos 1

Times (SaVUnsat)

OPERABILITY TEST November 9,1998 35

.. _ _. _._ _ _.m l

ATTACHMENT D-1, (CONTINUED)

O COMPLETED SURVEILLANCE TESTS Required Year Plant of l

Surveillance Description Condition initials Cycle 1

1305.07 Supp 2 Cold Shutdown Valve Stroke CSD 2

Times (Sat /Unsat) 1305.07 Supp 3 Monthly Misc Safety Systems Power Oos 3

Status Verification (Sat /Unsat) 1305.16 Supp 2 Monthly Safe Shutdown Inst Power Oos 4

l Channel Checks (Sat /Unsat) 1 1305.29 Refueling Off-Site Power CSD 1

Surveillance (Sat /Unsat) l t

OPERABILITY TEST November 9,1998 36 9

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' q ATTACHMENT D-1, (CONTINUED)

V COMPLETED SURVEILLANCE TESTS l.

NOTE:

1.

Plant in Cold Shutdown, RCS Pressure 100 to 200 PSIG I

2.

Heatup from CSD, RCS Pressure 1200, < 300 PSIG l

3.

Heatup from CSD, RCS Temperature 1270, < 280 F 4.

RCS Cooldown, RCS Pressure > 900 PSIG 5.

Highest Tcold temperature <304* F i

l 6.

RCS pressure >150 PSIG.

l

7. '

The hydrogen recombiner tests should be modified to take data on a less

. frequent intental. The test should be run during some other event that will allow for a steady 5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> run time It is important to test the initial and finial

/

temperatures and the approximate rate of change during this test. The ability of k

recording of data on short intervals is not being tested.

l l

l OPERABILITY TEST November 9,1998 37 k

4 e

i ATTACHMENT D-2 PROCEDURE STEPS THAT WERE NOT COMPLETED PROCEDURE:

STEP #

REASON FOR NON-COMPLETION i

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1 OPERABILITY TEST November 9,1998 38

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E. TRANSIENT TEST O

i 1.0 DISCUSSION l

. The intent of the Transient Test is to verify simulator performance. Transients must be capable of continuing until such time that a stable, controllable and l

safe condition is attained which can be continued to a Cold Shutdown condition or until the Simulator operating limits are exceeded.

2.0 REFERENCE (S) 2.1 ANO-3.5,1995,4.2.1,4.3, A3.3 ANS NPP Simulators For Operator Training i

3.0 EQUIPMENT 3.1 Stop Watch 3.2 Personal computer setup as a plant computer and spreadsheet software.

j 4.0 INITIAL CONDITIONS 4.1 All transients commence at 100% Rated Power, unless othenvise noted.

5.0 ACCEPTANCE CRITERIA 5.1 Observable changes in the parameters correspond in direction to those expected from plant data or best estimate data and do not violate the physical laws of nature.

6.0 NON ACCEPTANCE OF SIMULATOR RESULTS 6.1 Simulator results that would detract from positive training and those declared unacceptable by evaluation based on acceptance criteria, will not be used for routine training.

OPERABILITY TEST November 9,1998 40

-=

7.0 PROCEDURE fb NOTE:

After initiation of transient, Operators are to take only the actions as directed by this test document.

I NOTE:

All transients are to be carried to a stable plant condition.

7.1 Test Director shall brief the crew as to their expected actions to ensure the accuracy and repeatability of these tests.

7.2 Perform the following transients:

7.2.1 Manual Reactor Trip INIT 1.

Recall 100% power.

2.

Start OT1 on Group Display.

3.

Wait 30 seconds, depress Reactor Trip PB 4.

Minimize letdown.

5.

Adjust pzr level setpoint to 100".

6.

Stabilize the plant at hot shutdown.

l 7.

Verify proper actuation of all systems &

carry out all required actions s

8.

Collect data for 5 minutes and name file d

MNRXTP.PRN

~

9.

Delog data by following the instructions in Step 7.3.

7.2.2 Simultaneous Trip of all Feedwater Pumps 1.

Recall 100% power.

i 2.

Start OT1 on Group Display.

3.

Block EFW pump operation.

4.

Wait 30 seconds, trip both MFW pumps.

I 5.

Minimize letdown.

l 6.

Adjust pzr level setpoint to 100".

i 7.

Stabilize the plant at hot shutdown.

8.

Verify proper actuation of all systems i

i and carry out all required actions 9.

Collect data for 5 minutes and name file NOFEED.PRN 10.

Delog data by following the instructions in Step 7.3.

OPERABILITY TEST November 9,1998 41 l

i 7.2.3 Simultaneous Closure of all Main Steam isolation Valves 1.

Recall 100% power.

2.

Start OT1 on Group Display 3.

Wait 30 seconds, shut both Main Steam Isolation Valves.

4.

Minimize letdown.

5.

Adjust pzr level setpoint to 100".

6.

Stabilize the plant at hot shutdown.

7.

Verify proper actuation of all systems and carry out all actions required by the appropriate procedures.

8.

Collect data for 5 minutes and name file MSIV.PRN 9.

Delog data by fnllowing the instructions in Step 7.3.

7.2.4 Simultaneous Trip of all Reactor Coolant Pumps l

/3 1.

Recall 100% power.

O 2.

Start OT1 on Group Display.

3.

Wait 30 seconds, step all 4 RCPs.

4.

Minimize letdown.

5.

Adjust pzr level setpoint to 100".

6.

Stabilize the plant at hot shutdown.

7.

Verify proper actuation of all systems and carry out all actions required by the appropriate procedures.

8.

Collect data for 5 minutes and name file i

NORCP.PRN 9.

Delog data by following the instructions in Step 7.3.

1 l

l OPERABILITY TEST November 9,1998 42 i

l i

7.2.5 Trip of any Single Reactor Coolant Pump 1.

Recall 100% power.

2.

Start OT2 on Group Display.

3.

Wait 30 seconds, trip "C" RCP.

4.

Minimize letdown.

5.

Adjust pzr level setpoint to 100".

6.

Stabilize the plant at hot shutdown.

7.

Verify proper actuation of all systems and carry out all actions required by the appropriate procedures.

8.

Collect data for 5 minutes and name file TRPRCP.PRN 9.

Delog data by following the instructions in Step 7.3.

l 7.2.6 Main Turbine Trip (Maximum Power That Does Not Cause an immediate Reactor Trip) l l

1.

Recall 50% power.

l (

2.

Start OT1 on Group Display.

3.

Reduce power to 40%.

4.

Wait 30 seconds, trip the main turbine l

5.

Use the ERV and pressurizer spray to control RCS pressure while the ICS runs reactor power back.

6.

Stabilize the plant at power less than 15%.

7.

Verify proper actuation of all systems and carry out all actions required by I

the appropriate procedures.

j 8.

Collect data for 5 minutes and name file TURTRIP.PRN 9.

Delog data by following the instructions in Step 7.3.

l i

]

OPERABILITY TEST November 9,1998 43 l

. - =

l INIT lq g

7.2.7 Maximum Rate Power Ramp (100% Down to 75%

and Back Up to 100%)

1.

Recall 100% power.

2.

Start OT1 on Group Display 3.

Wait 30 seconds, set ICS rate demand to 10%/ minute.

4.

Set ULD to approximate value for j

75% power.

5.

Reduce power to 75%.

6.

Reduce the rate when approaching 75%

power to reduce undershoot.

7.

Adjust the ULD for 100% power and set i

the rate limit for 10%/ minute.

8.

Increase power to 100%.

9.

Stabilize the plant at 100%.

j 10.

Verify proper actuation of all systems l

and carry out all actions required by 1

l the appropriate procedures.

l l

11.

Collect data for 5 minutes and name file A1007510.PRN O

12.

Delog data by following the instructions j

in Step 7.3.

j l

7.2.8 Maximum Size RCS Rupture Combined with a Loss of Offsite Power l

l 1.

Recall 100% power.

l 2.

Start OT3 on Group Display l

3.

Wait 30 seconds, add malfunction l

ED183 for loss of offsite power and 2

add malfunction RC005 at 8.5 ft.

4.

Minimize letdown.

l 5.

Adjust pzr level setpoint to 100".

l 6.

Terminate the test when the RCS l

leakage and the HPl/LPI are equal and I

the CETs are stable at approximately 200 F.

O OPERABILITY TEST November 9,1998 i

V u

INIT 1 O 7.

Verify proper actuation of all systems and carry out all actions required by the appropriate procedures.

8.

Collect data for 5 minutes and name file i

LOCA.PRN I

9.

Delog data by following the instructions in Step 7.3.

7.2.9 Maximum Size Un-isolable Main Steam Line Rupture 1

i l

\\

l 1.

Recall 100% power.

l 2.

Start OT3 on Group Display.

3.

Wait 30 seconds, add malfunction MS131 2

at 3.14 ft, inside RB.

i 4.

Minimize letdown.

l 5.

Adjust pzr level setpoint to 100".

l 6.

Stabilize the plant at hot shutdown.

7.

Verify proper actuation of all systems and carry out all actions required by the appropriate procedures.

8.

Collect data for 5 minutes and name file

\\

MSLI.PRN 9.

Delog data by following the instructions in Step 7.3.

)

l l

OPERABILITY TEST November 9,1998 45 l

l i

l l

l INIT I

i 7.2.10 Slow Primary System Depressurization to Saturation Condition Using ERV j

i 1.

Recall 100% power.

j 2.

Block HPl valves shut.

CV1219; CV1220; CV1228; CV1227 CV1278; CV1279; CV1284; CV1285 3.

Start OT4 on Group Display.

4.

Wait 30 seconds, open ERV block valve and ERV.

j 5.

After the reactor trips, reduce l

letdown.

l 6.

Stop all RCPs when SCM < 30' F.

7.

Adjust pzr level setpoint at 100".

8.

Stabilize the plant at hot shutdown.

9.

Verify proper actuation of all systems and carry out all actions required l

by the appropriate procedures.

j 10.

Collect data for 10 minutes and name file O

ERV.PRN 11.

Delog data by following the instructions in Step 7.3.

I 7.3 Delog the Data File. Refer to Attachment R-9 r

OPERABILITY TEST November 9,1998 d

46

i INIT (m)

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8.0 TIME IN LIFE VERIFICATION TEST 8.1 Time in Life Verification Test Beginning of Life i

1.

Recall 1E-8 Amp Power BOL.

2.

Fail CV6687 and CV6689 shut using component override.

3.

Start OT2 on Group Display 1

4.

Open the turbine bypass valves 50%.

5.

Collect data for 20 minutes and name file BOL.PRN l

6.

Delog data by following the instructions in Step 7.3.

i 8.2 Time in Life Verification Test Middle of Life 1.

Recall 1E-8 Amp Power MOL.

2.

Fail CV6687 and CV6689 shut using component override.

3.

Start OT2 on Group Display s/

4.

Open turbine bypass valves 50%.

5.

Collect data for 20 minutes and name file MOL.PRN 6.

Delog data by following the instructions in Step 7.3.

8.3 Time in Life Verification Test End of Life 1.

Recall 1E-8 Amp Power EOL.

2.

Fail CV6687 and CV6689 shut using component override.

3.

Start OT2 on Group Display 4.

Open turbine bypass valves 50%.

5.

Collect data for 20 minutes and name file EOL.PRN 6.

Delog data by following the instructions in Step 7.3.

OPERABILITY TEST November 9,1998 u

47 l

l l

l

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f ~3.

8.4 Graph the following parameters, place all three time

()

in lives on the same graph.

j 1.

Loop A TCOLD.

l l

2.

NI-5 Power Range.

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f L

8.5 Place graphs in Attachment E-11.

l l

9.0 FINAL CONDITIONS l

9.1 Graph each parameter that is required by ANS 3.5, Appendix B.2.2.1 through B.2.2.10. Print a graph for 4

each required paranieter showing both actual simulator i

response and predicted response. Attach the transient spreadsheet and graphs to the appropriate attachment i

i E-1 through E-10.

Transients Tests have been run. Evaluations have been made and l

j appropriate problems, if any, noted by Discrepancy Reports. Any Transient Test that requires a DR to correct the simulator response shall be repeated until successful or listed as an exception to ANSI /ANS 3.51995. All data points have been delogged, printed to hard copy, saved to a computer, and

,j p included in the appropriate Attachment E-1 through E-11. All critical data

' d points are graphed against the predicted response and previous Operability test results, and evaluated to be satisfactory; graph included in the appropriate Attachment E-1 through E-11 and the spreadsheet printed and placed with graphs.

1 i

i l

l I

OPERABILITY TEST November 9,1998 48 I

i

S.

ATTACHMENT E-1 O

4 1

TRANSIENT TEST MANUAL REACTOR TRIP TRANSIENT B2.2 (1) 4.

Transient Reviewed by:

Date:

Simulator Training 4-t O

e 4

OPERABILITY TEST November 9,1998 49

=

_....- ~.. -

ATTACHMENT E-2 O

TRANSIENT TEST SIMULTANEOUS TRIP OF ALL FEEDWATER PUMPS TRANSIENT B2.2 (2) t Transient Reviewed by:

Date:

Simulator Training O

l i

OPERABILITY TEST November 9,1998 50

l ATTACHMENT E-3 O

TRANSIENT TEST SIMULTANEOUS CLOSURE OF BOTH MSIVs TRANSIENT 82.2 (3)

Transient Reviewed by:

Date:

Simulator Training O

4 4

OPERABILITY TEST November 9,1998 51 I

ATTACHMENT E-4 TRANSIENT TEST SIMULTANEOUS TRIP OF ALL RCPs TRANSIENT B2.2 (4)

Transient Reviewed by:

Date:

Simulator Training O

O OPERABILITY TEST November 9,1998 52 i

i ATTACHMENT E-5

~

O TRANSIENT TEST TRIP OF ONE RCP TRANSIENT B2.2 (5)

Transient Reviewed by:

Date:

Simulator Training l

O I

J e

OPERABILITY TEST November 9,1998 53 4

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ATTACHMENT E-6 O

TRANSIENT TEST l

MAIN TURBINE TRIP AT 40% POWER WITHOUT A REACTORTRIP

]

l TRANSIENT B2.2 (6)

. Transient Reviewed by:

Date:

Simulator Training O

OPERABILITY TEST November 9,1998 1

54

1 ATTACHMENT E-7 O

TRANSIENT TEST MAXIMUM RATE POWER RAMP 100% TO 75% TO 100%

i TRANSIENT B2.2 (7) l l

Transient Reviewed by:

Date:

Simulator Training l

f i

O OPERABILITY TEST November 9,1998 55

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ATTACHMENT E-8 O

TRANSIENT TEST r

MAXIMUM SIZE RCS RUPTURE AND LOSS OF OFFSITE POWER TRANSIENT B2.2 (8)

I Transient Reviewed by:

Date:

1 Simulator Training O

OPERABILITY TEST November 9,1998 56 4

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7 I

ATTACHMENT E-9 TRANSIENT TEST i

i MAXIMUM SIZE UNISOLABLE MAIN STEAM LINE BREAK l

TRANSIENT B2.2 (9) 2 3

1 Transient Reviewed by:

Date:

Simulator Training 4

l r

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I OPERABILITY TEST November 9,1998

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ATTACHMENT E-10 0

TRANSIENT TEST SLOW PRIMARY SYSTEM DEPRESSURIZATION TO SATURATION USING THE ERV WITHOUT HPl TRANSIENT B2.2 (10)

Transient Reviewed by:

Date:

Simulator Training O

4 S

OPERABILITY TEST November 9,1998 58

)

l l

t ATTACHMENT E-11

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O i

TRANSIENT TEST TIME IN LIFE TEST Transient Reviewed by:

Date:

Simulator Training O

OPERABILITY TEST November 9,1998 59 O

r I

F. MALFUNCTION TEST s

l

'1.0 DISCUSSION i

A.

All malfunctions that are required by either 10CFR55.59.C.3.i or ANS 3.5 1995 Section 3.1.2 and are not tested during the transient testing portion of the performance test shall 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.

Some malfunctions have been deleted or added due to the changing needs of Operator training. The symbol A99 will be used to indicate the addition of a new malfunction during 1999, and D99 to indicate deleting a malfunction.

(Use A9X D9X for future years)

B.

The following assumptions have been utilized in preparing this section:

1)

The simulator shall 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 attempt to define every possible alarm or Q

response in the Malfunction cause and effect document, only the major V

items are listed.

2)

The anticipated plant response is described in the Unit 1 Malfunction Cause and Effects Document.

C.

The following termination criteria will be used during malfunction testing:

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. (i.e., RCS leakage > T.S. but <HPl capacity.)

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 EOP.

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 - i.e., during a dropped control rod from power malfunction, it is not necessary to withdraw the control rod.

OPERABILITY TEST November 9,1998 60

i 4)

The malfunction has failed to perform correctly.

O D.

The following process will be used to conduct and document each malfunction test:

t 1)

The Test Director will review the malfunction, AOP, EOP, and anticipated plant respons.e with the test personnel prior to each malfunction test.

2)

Plant response will be compared to the Malfunction Cause and Effects i

Document.

j 3)

Deviations will be annotated in the expected plant response section of the Cause and Effects Document. A DR shall be written to correct simulator response and the Cause and Effect Document edited to include all correct plant response not contained in the Cause and Effect.

1 4)

If the acceptance criteria in section 5.0 have been met, the Test Director will sign off the malfunction on the Malfunction Verification List as being accepted. (Attachment F-1) j i

2.0 REFERENCE (S) t 2.1 ANS-3.5,1995, 3.1.2, 4.2.2, and A3.4.

1 2.2 10CFR55.59.C.3.i.A through AA.

3.0 EQUIPMENT 3.1 None 4.0 INITIAL CONDITIONS 4.1 initial Plant Conditions will be as stated in the Malfunction Cause and Effects Document in the Malfunction Test Condition.

1 5.0 ACCEPTANCE CRITERIA 5.1' Observable that change in the parameter correspond in direction to actual plant data or to that expected from best estimate and not violate the physical laws of nature.

OPERABILITY TEST November 9,1998 61

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5.2 The simulator 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 i

trip.

6.0 NON ACCEPTANCE OF SIMULATOR RESULTS 6.1 Simulator results that would ' detract from positive training and those declared unacceptable by evaluation based on acceptance criteria, will not be used for routine training.

i 7.0 PROCEDURE 7.1 Test each malfunction in accordance with the test plan in the Malfunction Cause and Effects document.

7.1.1. Using Attachment F-1 of this procedure, select malfunction to be tested during this " year of cycle".

1)

Recall the IC as indicated on the Malfunctions Cause and Effects, Attachment F-2.

2)

Enter the malfunction being tested on the IA terminal using the severity and magnitude indicated on the Cause and Effects document.

3)

The only operator actions allowed are listed on the Malfunction Cause and Effects document. All safety systems will be verified.

Any automatic actuation or system response that does not occur as an indirect result of this malfunction will D.gt be cause for unsatisfactory status of this malfunction. A DR will be written for all improper responses.

4)

The malfunction must perform as indicated on the Malfunction Cause and Effects document. Deviations must be resolved before the malfunction can be determined satisfactory. The Cause and Effects document shall be updated to reflect actual results.

OPERABILITY TEST November 9,1998 62 l

~

5)

When the plant has reached a steady state status, hot shutdown or some new steady power, the test can be terminated -

satisfactorily.

6)

If the Simulator Operating Limit (SOL) is reached, the validity of

{

the alarm must be verified and a determination made that the simulation has not caused a failure of one of the models.

7)

After verifying the malfunction has correctly functioned and all corrections to the Cause and Effects document have been hand written on the test copy, the Test Director shall sign the satisfactory performance block of Attachment F-1.

l 8)

Continue to the next malfunction.

~8.0 FINAL CONDITIONS All malfunctions have been tested and the Malfunction Verification List has been signed by the Test Director. If problems have been identified a Discrepancy Report has been written to initiate corrective action. The malfunction will be tested again and when satisfactory, the Test Director will sign for the satisfactory performance.

O OPERABILITY TEST November 9,1998 63 I

O O

O ATTACHMENT F-1 MALFUNCTION VERIFICATION LIST Name Description ANSI Year Date DR No.

Unsat Date Satisfactory 3.5 Of ifApp Init Retest Performance Test Signature RC001 OTSG A TUBE RUPTURE

.1A 1

RC003 RC HOT LEG LEAK (LOOP A)

.1 C 1

RC006 RC COLD LEG LEAK (LOOP B)

.1 B 1

RC011 LOSS OF RCP LO. P32A

.4 1

CV018 SEAL NO.1 FAILURE P32D

.18 1

CV022 SEAL NO.2 FAILURE P32D

.1B 1

CV023 SEAL NO.3 FAILURE P32A

.1 B 1

CV027 R32A SHAFT LEAKAGE

.1 B 1

RC030 RCP LOCKED ROTOR P32D

.4 1

RCO34 RCP SHEARED SHAFT P32D

.4 1

RC041 PSV 1002 UFT& RESET PRESS DRIFT

.1 D 1

TROSS PZR TT 1002 FAILURE

.18 1

CV062 FAllMAKEUP PMP 36B(OPEN CKT)

.18 1

CV066 LEAK IN MAKEUP PUMP 36C SUCTION

.18 1

i FWO71 P2A MOTOR BEARING HEATUP

.9 1

OPERABILITY TEST November 9,1998 64

t O

O O

ATTACHMENT F-1 l

MALFUNCTION VERIFICATION LIST Name Description ANSI Year Date DR No.

Unsat Date Satisfactory 3.5 Of ifApp init Retest Periv0rierice t

Test Signature FWO75 FW PUMP 1B FAILURE

,9 1

FWO76 STEAM DRIVEN EFWP FAILURE

.23 1

j FWO81 FW PMP SUCT PRESS OSCIL ACTION None 1

FWO82 P3A MOTOR BEARINGS HEATUP

.5 1

FWO86 P8A MOTOR BEARINGS HEATUP

.9 1

[

4 FWO93 TUBE LEAK FW HTR ESA

.9 1

l CV097 P36C MOTOR BEARINGS HEATUP

.18 1

FW102 FW LINE BRK OUTSIDE RX BLDG LP B

.20 1

i FW108 Flowpath "W Onfice screen fails FWP "A"

.22 1

j FW113 MFW PUMP TRIP STATUS FAILS

.9 1

(

SW121 P4A MOTOR BEARINGS HEATUP

.6 1

l MS134 MSL B RUPTURE OUTSIDE THE RX BLD

.20 1

i TU136 TURB LO. LOSS (CLR DISCH CLSD)

.15 1

MS140 GLAND SEAL FAILURE

^

.5 1

MS143 GHlFTIN PSV 2686 LIFT & RESET

.20 1

i OPERABILITY TEST November 9,1998 f;

l t

65

[

i

,em

. m,

,e y G

ATTACHMENT F-1 MALFUNCTION VERIFICATION LIST Name Description ANSI Year Date DR No.

Unsat Date Satisfactory 3.5 Of ifApp Init Retest Performance Test Signature TU147 IV CV6825 FAILS CLOSED

.22 1

TU153 NO.1 GOVERNOR VALVE FAILS

.22 1

RH161 LEAK IN DISCHARGE OF DHR PMP 34A

.7 1

RH165 LEAK IN DHR COOLER E35A

.7 '

1 RM169 FUELCLADDING MECH. FAILURE

.14 1

IA170 IA LEAK DOWNSTREAM OF IA 68

.2 1

EG171 FAILURE OF MAIN GENERATOR EXCITER

.16 1

i

.3 1

DG174 DG 2 FAILURE ED178 MN TRANSFORMER FAILURE PHASE B

.3 1

ED182 UA XFMR FAILURE

.3 1

ED186 LOSS OF 4.16 KV BUS A2

.3 1

ED190 LOSS OF 480 V BUS B2

.3 1

ED194 LOSS OF 480 B BUS B6

.3 1

ED199 LOSS OF 125 VDC BUS D02

.3 1

RC204 LEAK IN RCP OilCOOLER P32D

.4 1

j OPERABILITY TEST November 9,1998 66 m

O

- O O

ATTACHMENT F-1 MALFUNCTION VERIFICATION LIST Namc Description ANSI Year Date DR No.

Unsat Date Satisfactory 3.5 Of IfApp init Retest Paferinance Test Signature N1234 NI-3 OVER COMPENSATED

.21 1

N1238 NI-7 FAILS LO

.21 1

N1242 NI-7 FAILS Hi

.21 1

RP244 FALSE RXTRIP

.19 1

RP247 REACTOR TRIP RELAY KE2 FAILS

.24 1

RD250 UNABLE MANUAL ROD INSERTION

.13 1

ES251 FALSE ACTUATION OF ES CHANNEL 1

.22 1

ES255 FALSE ACTUATION OF ES CHANNEL 5

.22 1

f ES259 ES CHANNEL 1 FAILS TO ACTUATE

.11 1

l ES263 ES CHANNEL 5 FAILS TO ACTUATE

.11 1

ES267 ES CHANNEL 9 FAILS TO ACTUATE

.11 1

RD271 LOSS OF SEQUENCE ENABLE

.12 1

RD276 DROP ROD C11 (GR3-ROD 1 )

.12 1

RD310 EJECT ROD B8 (GR6-ROD 1 )

.1 B 1

[

RD351 STUCK ROD C11 (GR3-ROD 1 )

.12 1

L OPERABILITY TEST November'9,1998 i

i

im em U

b p

V ATTACHMENT F-1 MALFUNCTION VERIFICATION LIST Name Description ANSI Year Date DR No.

Unsat Date Satisfactory 3.5 Of ifApp init Retest Performance Test Signature RD388 -

DEGRDED MOTION ROD E9 GR4-ROD 1

.12 1

RD424 FAILURE OF CRD B DC HOLD P/S

.12 1

RD428 DROP GROUP 7 RODS

.12 1

TR449 LOOP BTC (TT1048)

.22 1

ED450 LOSS OF NNIX POWER

.3 1

EG454 LEAK IN RCP COOLER E25A

.1 B 1

ED460 B5114 GEN OUTPUT BKR FAILS

.3 1

RC462 RCS LEAK DOWNSTREAM MU45A

.1 B 1

RD446 Stuck Rod on Reactor Trip Gp1 Rd 3 @ 5 inches

.22 1

RC467 P32A Anti Reverse Rotation Device Failure

.4 1

TR553 SG A MAIN FW START UP (PDT2626)

.22 1

TR557 SG B MAIN FW START UP (PDT2676)

.22 1

TR561 GENERATED MW SIGNAL (TWC)

.22 1

TRS65 LOOP A TH (TT1011)

.22 1

TR569

'A' OTSG LEVEL OPER (LT2660)

.22 1

OPERABILITY TEST November 9,1998 68

3 n

m ATTACHMENT F-1 MALFUNCTION VERIFICATION LIST Name Description ANSI Year Date DR No.

Unsat Date Satisfactory 3.5 Of ifApp Init Retest Performance Test Signature TR573

'A' OTSG LEVEL S/U (LT2653)

.22 1

TR577

'A' OTSG PRESS (PT2653)

.22 1

TR581

'B' HDR THROTTLE PRESS (PT2633)

.22 1

TR585

'B' OTSG MAIN FW TEMP (TT2679)

.22 1

TR589 LOOP A TC (TT1015)

.22 1

RX593 TURB. A-1 BYP CNTRL VLV (IC23.8)

.22 1

RX597 TURB. B-2 BYP CNTRL VLV(IC23.10)

.22 1

RX601 STARTUP FW VLV 'B' (FW23.12)

.22 1

RX605 DEC. TURBINE POSITION (IC18.3D)

.22 1

FW608 CH.A SGB PRESS INITIATE BISTABLE

.23 1

RD625 CRD Motor heat up Group 6 Rod 3

.22 1

TR622 BWST LEVEL INSTRUMENT LT1411 FAILS

.22 1

TR626 B CFT LEVEL INSTRUMENT LT2418 FAILS

.22 1

ED642 Breaker A106 Fails to Latch

.3 1

RC002 OTSG B TUBE RUPTURE

.1A 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 OPERABILITY TEST November 9,1998 69

o o

o 1

ATTACHMENT F-1 MALFUNCTION VERIFICATION LIST Name Description ANSI Year Date DR No.

Unsat Date Satisfactory 3.5 Of ifApp init -

Retest Performance Test Signature I

RC004 RC HOT LEG LEAK (LOOP B)

.1 C 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RC012 LOSS OF RCP LO. P328

.4 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 CV015 SEAL NO.1 FAILURE P32A

.1 B 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 CV019 SEAL NO.2 FAILURE P32A

.1 B 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 i

CV024 SEAL NO.3 FAILURE P32B

.1 B 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RCO27 RCP LOCKED ROTOR P32A

.4 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 CV028 P328 Shaft Leakage

.1 b 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 i-RC031 RCP SHEARED SHAFT P32A

.4 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RC042 PSV 1000 LEAKING

.1 D 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 l

RC045 PZR STEAM SPACE LEAK

.18 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 TR049 PZR LT 1001 FAILURE

.18 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 CV063 FAllMAKEUP PMP 36C(OPEN CKT)

.18 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 l

CV067 LEAK IN MAKEUP PMP 36A DISCHARGE

.18 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 FWO72 P2B MOTOR BEARING HEATUP

.9 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99

[

CWO83 P3B MOTOR BEARINGS HEATUP

.5 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 i

OPERABILITY TEST November 9,1998 70 w

,\\

N O

N.)

ATTACHMENT F-1 MALFUNCTION VERIFICATION LIST Name Description ANSI Year Date DR No.

Unsat Date Satisfactory 3.5 Of IfApp init Retest Performance Test Signature FWO87 P8B MOTOR BEARINGS HEATUP

.9 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 FWO94 TUBE LEAK FW HTR ESB

.9 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 FWO99 FW LINE BRK INSIDE RX BLDG LP A

.20 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 FW107 Flowpath *A" Orifice screen fails FWP "A"

.22 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 FW117 MN FW A CNTL VLV(CV2625) LEAKS

.22 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 SW122 P48 MOTOR BEARING HEATUP

.6 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 SW127 SW LOOP l LEAK IN RX BUILDING

.6 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 MS131 MSL A RUPTURE INSIDE THE RX BLD

.20 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 MS135 STM LINE BREAK BTWN HP&LP TURB

.20 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 TU136 TURB L.O. LOSS (CLR DISCH CLSD)

.15 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 MS137 STEAM SUPPLY LINE RUPTURE TO P7A

.20 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 MS144 SHIFT IN PSV 2687 LIFT & RESET

.20 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 1

MS145 PSV2684 MSSV Fails open

.20 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 TU148 i V CV6828 FAILS CLOSED

.22 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 TU154 NO.2 GOVERNOR VALVE FAILS

.22 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 OPERABILITY TEST November 9,1998 71

O O

O ATTACHMENT F-1 MALFUNCTION VERIFICATION LIST Name Description ANSI Year Date DR No.

Unsat Date Satisfactory 3.5 Of ifApp init Retest Performance Test Signature

{

t RH162 LEAK IN DISCHARGE OF DHR PMP 348

.7 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 j

RH166 LEAK IN DHR COOLER E35B

.7 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RM169 FUELCLADDING MECH. FAILURE

.14 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 IA170 lA LEAK DOWNSTREAM OF lA 68

.2 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 EG172 MAIN GEN VOLTAGE REG FAILS

.16 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 DG175 DG 1 FAILS TO AUTO START

.3 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 ED179 MN TRANSFORMER FAILURE PHASE C

.3 2

N/A 99 N/A 99 N/A 99

~ N/A 99 N/A 99 t

ED183 LOSS OF OFF SITE POWER

.3 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 ED187 LOSS OF 4.16 KV BUS A3

.3 2

N/A 99 N/A 99 N/A 99 N/A99 N/A 99 l

ED191 LOSS OF 480 V BUS B3

.3 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 ED195 LOSS OF 480 V BUS B7

.3 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 l

i RC201 LEAKIN RCP OIL COOLER P32A

.4 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 l

CW215 PLUGGED CNDNSR TUBE SHEET E11A

.5 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 I

4 i

EG225 LOSS OF GEN HYD COOUNG(CV4018)

.8 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 N1235 NI-4 OVER COMPENSATED

.21 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 OPERABILITY TEST November 9,1998

.L h

72 t

b

.m

0,a

,y N.)

ATTACHMENT F-1 MALFUNCTION VERIFICATION LIST Name Description ANSI Year Date DR No.

Unsat Date Satisfactory 3.5 Of IfApp init Retest Performance Test Signature NI239 NI-8 FAILS LO

.21 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 N1243 NI-8 FAILS HI

.21 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RP244 FALSE RX TRIP

.19 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RP248 RX TRIP RELAY KE3 FAILS (CRPS)

.24 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RD250 UNABLE MANUAL ROD INSERTION

.13 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 l

ES252 FALSE ACTUATION OF ES CHANNEL 2

.22 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 ES256 FALSE ACTUATION OF ES CHANNEL 6

.22 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 i

ES.260 ES CHANNEL 2 FAILS TO ACTUATE

.11 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 I

ES264 ES CHANNEL 6 FAILS TO ACTUATE

.11 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 ES268 ES CHANNEL 10 FAILS TO ACTUATE

.11 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RX272 DEFEAT ROD DEMAND (ICS TO CRD)

.12 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RD277 DROP ROD D4 (GR7-ROD 8)

.12 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RD312 EJECT ROD (GRS-ROD 12 )

.1 B 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RD352 STUCK ROD D4 (GR7-ROD 8)

.12 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RD389 DEGRDED MOTION ROD D4 (GR7-ROD 8)

.12 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 OPERABILITY TEST November 9,1998 73 l

l 1

O O

O i

ATTACHMENT F-1 MALFUNCTION VERIFICATION LIST i

Name Description ANSI Year Date DR No.

Unsat Date Satisfactory 3.5 Of ifApp init Retest Performance Test Signature RD425 FAILURE OF CRD AUXILIARY P/S

.12 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RD448 Stuck Rod on Reactor Trip Gp6 Rd 1 @ 5 inches

.22 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 ED451 LOSS OF NNIY POWER

.3 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RC455 LEAKIN RCP COOLER E258

.1 B 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 r

TR458 PT1021, RCS PRESS TRANSMITTER

.22 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RC463 RCS LEAK DOWNSTREAM MU45B

.1 B 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RC468 P32C Anti Reverse Rotation Device Failure

.4 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 r

TR550 SG A SHELL WATER TEMP (TT2664)

.22 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 TR554 SG B SHELL WATER TEMP (TT2614)

.22 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 TR558

• B' OTSG FW FLOW (MAIN)(PDT2677)

.22 2

N/A 99 N/A 99 N/A 99 N/A 99' N/A 99 TR562 RC FLOW LOOP A (PDT1028)

.22 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 TR566 LOOP B TH (TT1042)

.22 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 TR570

• B' OTSG LEVEL OPER (LT2609)

.22 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 TR574

'B' OTSG LEVEL S/U (LT2614)

.22 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 TR578

'B' OTSG PRESS (PT2602)

.22 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 t

OPERABILITY TEST November 9,1998 74 p

O O

O 4

l ATTACHMENT F-1 MALFUNCTION VERIFICATION LIST

[

Name Description ANSI Year Date DR No.

Unsat Date Satisfactory f

3.5 Of ifApp init Retest Performance Test Signature TR582

.'A' OTSG MAIN FW TEMP (TT2630)

.22 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 l

f TR586

'A' MFW DELTA P FAILURE

.22 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 TR590 LOOP A TC (TT1018)

.22 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RX599 A MFW SPD SIGNAL FROM ICS TO U

.22 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 i

RX602 A LL CONTROL VLV FAILS, CV2622

.22 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RX606 WITHDRAW RODS COMMAND

.12 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 i

FW609 CH.A SGA LEVEL INITIATE BISTABLE

.23 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 FW612 FALSE ACTUATION OF TRAIN A EFW

.22 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 i

FW617 P78 ELEC. EFW PMP FAILS TO ACTU.

.23 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 FW618 EFIC FALSE VECTOR CL SIG CV2648

.22 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 j

TR623 BWST LEVEL INSTRUMENT LT1421 FAILS

.22 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99

[

f RD626 CRD Motor heat up Group 7 Rod 5

.22

-2 N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 TR627 B CFT LEVEL INSTRUMENT LT2419 FAILS

.22 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 f

ED643 Breaker A210 Fails to Latch

.3 2

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 j

i RC001 OTSG A TUBE RUPTURE

.1A 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 l

i OPERABILITY TEST November 9,1998 l

^

75

G' L)

G ATTACHMENT F-1 MALFUNCTION VERIFICATION LIST Name Description ANSI Year Date DR No.

Unsat Date Satisfactory 3.5 Of IfApp Init Retest Performance Test Signature RC003 RC HOT LEG LEAK (LOOP A)

.1C 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RC013 LOSS OF RCP L.O. P32C

.4 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 CVO16 SEAL NO.1 FAILURE P32B

.1 B 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 CV020 SEAL NO.2 FAILURE P328

.1 B 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99

' CV025 SEAL NO.3 FAILURE P32C

.1 B 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RCO28 RCP LOCKED ROTOR P328

.4 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 CV029 P32C Shaft Leakage

.1 b 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RCO32 RCP SHEARED SHAFT P32B

.4 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RC039 PSV 1000 LIFT & RESET PRESS DRIFT

.1D 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RC043 PSV 1001 LEAKING

.1D 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RC046 ALL PZR HEATERS FAllON

.18 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 TR050 PZR LT 1002 FAILURE

.18 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 TR054 PZR TT 1000 FAILURE

.18 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 CV058 LETDOWN CO'JLER E29A TUBE LEAK

.18 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 CV064 LEAK IN MAKEUP PUMP 36A SUCTION

.18 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 OPERABILITY TEST November 9,1998 76

i O

O O

i ATTACHMENT F-1 MALFUNCTION VERIFICATION LIST l

f Name Description ANSI Year Date DR No.

Unsat Date Satisfactory 3.5 Of IfApp Init Retest Performance Test Signature l

CV068 LEAK IN MAKEUP PMP 368 DISCHARGE

.18 -

3 N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 l'

l FWO73 P2C MOTOR BEARING HEATUP

.9 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 TR586 FW BLK VLV TMTR PDT 2700 Fall LO

.22 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 f

CWO84 P3C MOTOR BEARINGS HEATUP

.5 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 i

FWO91 CONDENSATE LINE A LEAK

.9 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 CV096 P368 MOTOR BEARINGS HEATUP

.18 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 t

FW100 FW LINE BRKINSIDE RX BLDG LP B

.20 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 FW111 A MFP CONTROL OIL PRESS FAILURE

.17 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 FW118 MN FW B CNTL VLV(CV2675) LEAKS

.22 3

N/A 99 N/A 99 N/A 99 N/A 99 ~

N/A 99 l

f SW123 P4C MOTOR BEARINGS HEATUP

.6 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 t

MS132 MSL B RUPTURE INSIDE THE RX BLD

.20 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 i

TU136 TURB LO. LOSS (CLR DISCH CLSD)

.15 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 I

MS138 A MAIN STEAM LINE RUPTURE TO P7A

.20 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 i

i TC139 TURBINE HI VIBRATION None 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 f

MS141 SHIFTIN PSV 2696 LIFT & RESET

.20 3

N/A 99 ~

N/A 99 N/A 99 N/A 99 N/A 99 i

OPERABILITY TEST November 9,1998 l

77 i

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O ATTACHMENT F-1 MALFUNCTION VERIFICATION LIST Name Description ANSI Year Date DR No.

Unsat Date Satisfactory 3.5 Of ifApp Init Retest Perfom1ance Test Signature TU149 i V CV6829 FAILS CLOSED

.22 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 TU155 NO.3 GOVERNOR VALVE BINDS

.22 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RH163 LEAKIN SUCTION OF DHR PUMP 34A

.7 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RM169 FUEL CLADDING MECH. FAILURE

.14 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 IA170 IA LEAK DOWNSTREAM OF lA 68

.2 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 EG171 FAILURE OF MAIN GENERATOR EXCITR

.16 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A99 DG176 DG 2 FAILS TO AUTO START

.3 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 ED180 NO.1 START UP XFMR FAILURE

.3 3

N/A 99 N/A 99 N/A 99 N/A S9 N/A 99 ED184 LOSS OF 6.9 KV BUS H1

.3 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 ED188 LOSS OF 4.16 KV BUS A4

.3 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 ED192 LOSS OF 480 V BUS B4

.3 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 ED196 LOSS OF 125 VDC BUS D01

.3 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99

{

RC202 LEAK IN RCP OIL COOLER P32B

.4 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 SW220 SW Bay "A" Strainer failure F118A

.8 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 CW216 PLUGGED CNDNSR TUBE SHEET E118

.5 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 OPERABILID' TEST November 9,1998 t

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Unsat Date Satisfactory 3.5 Of if App init Retest Performance Test Signature EG226 LEAK IN GENERATOR HYD COOLER

.8 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 N1228 NI-1 FAILS LO

.21 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 NI232 NI-3 UNDER COMPENSATED

.21 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 N1236 NI-5 FAILS LO

.21 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 NI240 NI-5 FAILS HI

.21 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 J

RP244 FALSE RX TRIP

.19 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 TC245 MSTR TRIP SOL FAILS (TURB TRIP)

.23 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RP249 REACTOR TRIP RELAY KE4 FAILS

.24 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RD250 UNABLE MANUAL ROD i:!3ERTION

.13 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 ES253 FALSE ACTUATION OF ES CHANNEL 3

.22 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 ES257 FALSE ACTUATION OF ES CHANNEL 7

.22 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 ES261 ES CHANNEL 3 FAILS TO ACTUATE

.11 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 ES265 ES CHANNEL 7 FAILS TO ACTUATE

.11 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RD269 UNCONTROLLED ROD WITHDRAWL

.12 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RD273 DROP ROD 88 (GRG-ROD 1 )

.12 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 OPERABILITY TEST November 9,1998 l

l 79

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ATTACHMENT F-1 MALFUNCTION VERIFICATION LIST Name Description ANSI Year Date DR No.

Unsat Date Satisfactory 3.5 Of ifApp init Retest Performance Test Signature RD313 -

EJECT ROD C9 (GR3-ROD 1 )

.1 B 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RD348 STUCK ROD B8 (GR6-ROD 1 )

.12 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RD385 DEGRDED MOTION ROD B8 (GRG-ROD 1)

.12 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RD422 DEFEAT SEL GROUP (IN MANUAL)

.12 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RD426 DROP GROUP 5 RODS

.12 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RD450 Stuck Rod on Reactor Trip Gp5 Rd 12 @ 10 inch

.22 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 ED452 LOSS OF ICS POWER

.3 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 EG454 GENERATOR STATOR GROUND

.16 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RC456 LEAK IN RCP COOLER E25C

.1 B 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 ED461 B5118 GEN OUTPUT BKR FAILS

.22 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 ED462 Loss of Bus H2

.3 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RC464 RCS LEAK DOWNSTREAM MU45C

.1 B 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 i

RC469 P32C Anti Reverse Rotation Device Failure

.4 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 TR551 SG A SHELL WATER TEMP (TT2665)

.22 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 TR555 SG B SHELL WATER TEMP (TT2615)

.22 3

N/A 99 N/A 99 N/A 99

! N/A 99 N/A 99 l

i OPERABILITY TEST November 9,1998 l

80

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ATTACHMENT F-1 MALFUNCTION VERIFICATION LIST i

^i Name Description ANSI Year Date DR No.

Unsat Date Satisfactory

[

3.5 Of ifApp init Retest Performance

[

Test Signature f

TR559 NEUTRON POWER

.22 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 TR563 RC FLOW LOOP B (PDT1034)

.22 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 f

i TR567 LOOP B TH (TT1039)

.22 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 TR571

• B' OTSG LEVEL OPER (LT2610)

.22 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 f

TR575

'B' OTSG LEVEL S/U (LT2613)

.22 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 TR579

'B' OTSG PRESS (PT2603)

.22 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 i

TR583

'A' OTSG MAIN FW TEMP (TT2629)

.22 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 TR587

• B' OTSG FW STOP VLV P (PDT2701)

.22 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 i

TR591 LOOP B TC (TT1044)

.22 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RX599 FWP B SPEED CHNG DEMAND

.22 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RX603 LOW LOAD FW VLV'B'

.22 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RX607 INSERT RODS COMMAND

.12

~3 N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 i

FW610 EFIC CH.A LOSS OF POWER

.23 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99

[

t FW614 EFIC FALSE VCTR. CL SIG. CV2620

.22 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 t

t FW619 FALSE ACTUATION TRAIN B MSLI

.22 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99

[

l OPERABILITY TEST November 9,1998 81 t

O O

O ATTACHMENT F-1 MALFUNCTION VERIFICATION LIST Name Description ANSI Year Date DR No.

Unsat Date Satisfactory 3.5 Of IfApp init Retest Performance Test Signature FW621 CH.A,B,D INITIATE MDL OUTUT Fall

.23 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 TR624 A CFT LEVEL INSTRUMENT LT2415 FAILS

.22 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 ED640 Breaker A112 Fails to Latch

.3 3

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RC002 OTSG B TUBE RUPTURE

.1A 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RC004 RC HOT LEG LEAK (LOOP B)

.1 C 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 f

RC005 RC COLD LEG LEAK (LOOP A)

.1 B 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 CWOO7 FAILURE OF DARDANELLE DAM -

.6 4

N/A 9.9 N/A 99 N/A 99 N/A 99 N/A 99 RC014 LOSS OF RCP LO. P32D

.4 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 CV017 SEAL NO.1 FAILURE P32C

.1 B 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 CV021 SEAL NO.2 FAILURE P32C

.18 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 CV026 SEAL NO.3 FAILURE P32D

.18 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RCO29 RCP LOCKED ROTOR P32C

.4 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 CV030 P32D Shaft Leakage

.1 b 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RCO33 RCP SHEARED SHAFT P32C

.4 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RC040 PSV 1001 LIFT & RESET PRESS DRIFT

.1 D 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 OPERABILITY TEST November 9,1998 82

~

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O ATTACHMENT F-1 i

MALFUNCTION VERIFICATION LIST Name Description ANSI Year Date DR No.

Unsat Date Satisfactory 3.5 Of ifApp init Retest Performance Test Signature RC044 PSV 1002 LEAKING

.1 D 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RC047 ALL PZR HEATERS FALLOFF

.18 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 CV059 LETDOWN COOLER E29B TUBE LEAK

.1 B 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 CV061 FAllMAKEUP PMP 36A(OPEN CKT)

.18 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 CV065 LEAKIN MAKEUP PUMP 36B SUCTION

.18 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 CV069 LEAK IN MAKEUP PMP 36C DISCHARGE

.18 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RC070 LETDOWN LINE LEAK IN AUX BLDG 1B 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 FWO74 FW PUMP 1 A FAILURE

.9 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 FWO78 LOSS OF INST AIR TO K2B

.2 4

N/A 99 N/A 99 N/A 99 N/A 99 '

N/A 99 TR080 FW BKL VLV TMTR PDT 2701 FAllLO

.22 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 CWO85 P3D MOTOR BEARINGS HEATUP

.5 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 MC088 CONDENSER VACUUM LEAK

.5 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 FWO92 CONDENSATE LINE B LEAK

.9 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 CV095 P36A MOTOR BEARING HEATUP-

.18 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 FW101 FW LINE BRK OUTSIDE RX BLDG LP A

.20 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 OPERABILITY TEST November 9,1998 83 i

o o

o ATTACHMENT F-1 MALFUNCTION VERIFICATION LIST Name Description ANSI Year Date DR No.

Unsat Date Satisfactory 3.5 Of ifApp Init Retest Performance Test Signature FW112 B MFP CONTROL PRESS FAILURE

.17 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 SW128 SW LOOP 11 LEAK IN RX BUILD

.6 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 MS133 MSL A RUPTURE OUTSIDE THE RX BLD

.20 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 TU136 TURB LO. LOSS (CLR DISCH CLSD)

.15 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 i

MS142 SHIFT IN PSV 2697 LIFT & RESET

.20 4

N/A 99 N/A 99 N/A 99' N/A 99 N/A 99 TU146 I V CV6822 FAILS CLOSED

.22 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RX150 FREEZE ICS SIG TO EHC(CURR VAL)

.22 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 TU151 GOV.VLV OSC (EHC AUTO CNTL)

.22 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 TU156 NO.1 THROTTLE VALVE BINDS

.22 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RH164 LEAKIN SUCTION OF DHR PUMP 34B

.7 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99

[

RM169 FUEL CLADDING MECH. FAILURE

.14 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 A1170 IA LEAK DOWNSTREAM OF IA 68

.2 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 EG172 MAIN GEN VOLTAGE REG FAILS

.16 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 GN173 DG 1 FAILURE

.3 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 ED177 MAIN XFMR FAILURE PHASE A

.3 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 l

t OPERABILITY TEST November 9,1998 i

I l

84

O O

O ATTACHMENT F-1 MALFUNCTION VERIFICATION LIST Name Description ANSI Year Date DR No.

Unsat Date Satisfactory 3.5 Of ifApp init Retest Performance Test Signature ED181 NO.2 START UP XFMR FAILURE

.3 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 ED185 LOSS OF 4.16 KV BUS A1

.3 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 ED189 LOSS OF 480 V BUS B1

.3 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 ED193 LOSS OF 480 V BUS B5

.3 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 ED197 LOAD REJECTION

.3 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RC203 LEAK IN RCP OIL COOLER P32C

.4 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 SW221 SW Bay "C" Strainer failure F118C

.8 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 MC227 RUPT OF COND XFER DWNSTRM CS189

.8 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 N1229 N!-2 FAILS LO

.21 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 N1233 NI-4 UNDER COMPENSATED

.21 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 N1237 NI-6 FAILS LO

.21 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 NI241 NI-6 FAILS HI

.21 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RP244 FALSE RX TRIP

.19 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RP246 REACTOR TRIP RELAY KE1 FAILS

.24 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RD250 UNABLE MANUAL ROD INSERTION

.13 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 i

OPERABILITY TEST November'9,1998 85

---

- a-

--e-,

ATTACHMENT F-1 MALFUNCTION VERIFICATION LIST l

Name Description ANSI Year Date DR No.

Unsat Date Satisfactory 3.5 Of ifApp init Retest Performance Test Signature ES254 FALSE ACTUATION OF ES CHANNEL 4

.22 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 ES258 FALSE ACTUATION OF ES CHANNEL 8

.22 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 ES262 ES CHANNEL 4 FAILS TO ACTUATE

.11 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 L

ES266 ES CHANNEL 8 FAILS TO ACTUATE

.11 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 l

RD270 UNCONTROLLED ROD INSERTION

.12 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RD275 DROP ROD F6 (GR6-ROD 8 )

.12 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RD314 EJECT ROD D4 (GR7-ROD 8)

.1 B 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RD350 STUCK ROD C7 (GRS-ROD 12 )

.12 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 i

RD387 DEGRDED MOTION ROD C7 GR5-ROD 12

.12 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RD423 FAILURE OF CRD A DC HOLD P/S

.12 4

N/A 99 N/A 99 N/A 99 N/A 99 '

N/A 99 RD427 DROP GROUP 6 RODS

.12 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RD451 Stuck Rod on Reactor Trip Gp3 Rd 1 @ 15 inch

.22 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 ED453 LOSS OF SPDS (A & B)

.3 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RC457 LEAK IN RCP COOLER E25D

.1 B 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 TR459 PT1038, RCS PRESS TRANSMITTER

.22 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 OPERABILITY TEST November 9,1998 86

--u

-w

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O ATTACHMENT F-1 MALFUNCTION VERIFICATION LIST Name Description ANSI Year Date DR No.

Unsat Date Satisfactory 3.5 Of IfApp init Retest Performance Test Signature RC465 RCS LEAK DOWNSTREAM MU45D

.1 B 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 ED466 FAILURE OF SU#1 TO A2 AUTOTRIP

.3 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RC466 P32A Anti Reverse Rotation Device Failure

.4 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 TR552 SG A MAIN FLOW (PDT2628)

.22 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 TR556 SG B MAIN FLOW (PDT2678)

.22 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 TR564 LOOP A TH (TT1014)

.22 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 TR568

'A' OTSG LEVEL OPER (LT2659)

.22 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 i

TR572

'A' OTSG LEVEL S/U (LT2664)

.22 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 TR576

'A' OTSG PRESS (PT2652)

.22 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 I

TR580

'A' HDR THROTTLE PRESS (PT2683)

.22 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 TR584

'B' OTSG MAIN FW TEMP (TT2680)

.22 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 TR588

'A' OTSG FW FLOW MAIN (PDT2627)

.22 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 RX600 STARTUP FW VLV 'A'

.22 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 TR600 RCS Wide Range Pressure PT-1041 Failure

.22 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 i

RX604 INC. TURBINE POSITION

.22 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 OPERABILITY TEST November 9,1998 i

87 I

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O

^

ATTACHMENT F-1 MALFUNCTION VERIFICATION LIST Name Description ANSI Year Date DR No.

Unsat Date Satisfactory 3.5 Of IfApp init Retest Performance Test Signature FW611 EFIC LOSS OF FILL RATE CONTROL

.23 4

N/A99 N/A 99 N/A 99 -

N/A 99 N/A 99 FW620 FALSE ACTUATION TRAIN B A MSLI 22 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 TR625 A CFT LEVEL INSTRUMENT LT2416 FAILS

.22 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 4

ED641 Breaker H24 Fails to Latch

.3 4

N/A 99 N/A 99 N/A 99 N/A 99 N/A 99 e

9 i

r OPERABILITY TEST November 9,1998 l

~

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3=- p & a &M6er&O & M &am4 awe,o4Emse 0,,a4.uWh>aA 4mM 4a6Asimnni AAnH H&a 4 mHE. 4se O 6M M m L,M k md4M 4 pa b a i

ATTACHMENT F-2 MALFUNCTION CAUSE AND EFFECTS LISTING I

FOR MALFUNCTIONS TO BE TESTED l

I l

November 9,1998 OPERABILITY TEST 89

-u a,,,

,e g.,

G. RETEST ITEMS FROM LAST OPERABILITY TEST 1.0 DISCUSSION The intent this section is to silow the closure of the annual operability test with some outstanding items remaining. This section will be used to list the items remaining from the last operability test that must be tested this year. This section is not intended to allow violation of the intent of the operability test, but to allow problems to be carried over to the next year and close last years test.

2.0 PROCEDURE The list in section 3.0 is from last year's operability test. Repeat the listed item and sign and date the appropriate box to indicate satisfactory completion. A note has been placed on last year's operability test explaining that the item (s) were deferred to this year's test.

3.0 ITEMS FOR RETEST 3.1 Real Time Test None 3.2 Normal Operations Test None 3.3 Steady State Test None 3.4 Surveillance Test None 3.5 Transient Test None 3.6 Malfunction Test l

None l

OPERABILITY TEST November 9,1998 90 1

A a,..4 Wad dMa.--

4.

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-4a&-ase4am.J REFERENCES I

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OPERABILITY TEST November 9,1998 91 l

l O

ATTACHMENT R-1 LIST OF POINTS RECORDED DURING TRANSIENT TEST USING OT1 Point ID Global Variable Description 1

N115 Reactor Power 2

1D00TMP1 Tave 3

1B00TMP1 Pressurizer Pressure 4

P1020 RCS Pressure 5

L1001B Pressurizer Level l

6 T1001B Pressurizer Water Temperature 7

1800TMP2 A OTSG Steam Flow 8

1801TMP1 B OTSG Steam Flow 9

F2627 A OTSG MFW Flow lO 10 F2677 B OTSG MFW Flow l

11 T1039H Loop B Thot 12 T1045 Loop B Tcold 13 P2617A B OTSG Pressure 14 L2609 B OTSG Operate Range Level l

15 L2614 B OTSG Startup Range Level l

l l

OPERABILITY TEST November 9,1998 92

ATTACHMENT R-2 l

LIST OF POINTS RECORDED DURING TRANSIENT TEST USING OT2 l

l Point ID Global Variable Description 1

N115 Reactor Power 2

T1011H Loop AThot 3

T1039H Loop B Thot 4

T1016 Loop A Tcold 5

T1045 Loop B Tcold 6

P2618A A OTSG Pressure 7

P2617A B OTSG Pressure 8

L2659 A OTSG OP Range Level 9

L2609 B OTSG OP Range Level 10 L2664 A OTSG SU Range Level 11 L2614 B OTSG SU Range Level 12 1800TMP2 A OTSG Steam Flow 13 1801TMP1 B OTSG Steam Flow 14 F2627 A OTSG Feedwater Flow 15 F2677 B OTSG Feedwater Flow l

l (3)

OPERABILITY TEST November 9,1998 93

1 ATTACHMENT R-3 I

LIST OF POINTS RECORDED DURING TRANSIENT TEST USING OT3 Point ID Global Variable Description l

1 1B00TMP1 Pressurizer Pressure

)

i 2

P1020 RCS Pressure j

3 L1001B Pressurizer Level l

4 P2405 Reactor Building Pressure 5

T2405 Reactor Building Temperature I

i OPERABILITY TEST November 9,1998 94

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l ATTACHMENT R-4 LIST OF POINTS RECORDED DURING TRANSIENT TEST USING OT4

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Point ID Global Variable Description 1

1801TMP2 ERV Flow to Quench Tank 2

1B00TMP1 Pressurizer Pressure 3

P1020 RCS Pressure 4

T10018 Pressurizer Water Temperature 5

1B02TMP1 Pressurizer Steam Temperature 6

L1001B Pressurizer Level 7

F1028 A RCS Loop Flow 8

F1034 8 RCS Loop Flow 9

T1009 Surge Line Temperature 10 T1011H Loop A Thot 11 N11SR Source Range Counts 12 1802TMP2 Reactor Vessel Level i

13 P1893 Margin to Saturation OPERABILITY TEST November 9,1998 95 9

l O

^TT^cs us~r a-s LIST OF POINTS RECORDED DURING TRANSIENT TEST l

USING OT5 Point ID Global Variable Description J

1 N115 NI-5 Rx Power 2

QCORE Core Power Thermal 3

J1 GEN Generator Watts 4

1D00TMP1 Tave 5

P2618A A OTSG Pressure 6

L1'001B Pressurizer Level 7

T2631 B OTSG Steam Temperature 8-P2617A B OTSG Pressure 9

T1001B Pressurizer Temperature 10 P1020 RCS Pressure 11 T2681 A OTSG Steam Temperature j

12 T2629 A MFW Temperature 13 F2627 A MFW Flow 14 T1016 Loop A Cold Leg Temp l

15 T1011H Loop A Hot Leg Temp 16 Z7 AVG Group Seven Position (ABS) 17 T2679 B MFW Temperature 18 F2677 B.MFW Flow 19 T1045 Loop B Cold Leg Temp 20 T1041 Loop B Hot Leg Temp OPERABILITY TEST November 9,1998 96 i

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O ATTACHMENT R-7 SUBJECT MATER EXPERT EXPERIENCE

SUMMARY

Subject Matter Education /

Years in the Years in Ops Years in Nuc NRC Operator Title Expert Degrees Plant Training Navy License F. Uptagrafft B.S.

5 14 8

SRO Senior Instructor, Ops Training D.E. Smith H.S.

8 16 6

SRO Senior instructor, Ops Training R.E. Stancliff H.S.

8 18 0

SRO Senior Instructor, Ops Training i

K.W. Canitz A.A.

5 15 6

SRO Senior Instructor, Ops Training C.N. Edwards H.S.

15 2

0 SRO Senior instructor, Ops Training 4

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i OPERABILITY TEST November 9,1998 ss i

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b ATTACHMENT R-8 CHRONOLOGICAL LOG l

DATE-l PAGE:

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i OPERABILITY TEST November 9,1998

ATTACHMENT R-9 DELOGGING HISTORICAL DATA LOGS To start OT group displays.

1. Type GD OT1 on the command line. A 20 point column display will appear and the values will be dynamic.

2. Depress the F6 key (Page Down Key) to activate the local archive. The data displayed on the screen is now being saved on the local computers hard drive. The hard drive light should be flashing slowly. A message will be displayed on the upper left corner of the screen saying "SDS Local Archive Activated".

3. When data collection is complete, type RUN LOCARC <> on the control line.

4. The computer will exit the SDS program and run a DOS program. This program will ask for the name of the report file. Enter a drive letter, directory and file name. The drive letter and directory is your choice. The file name and file extension is listed in the instructions for the transient test. Example: C:\\OTEST99\\ERV.PRN. This file will fit on a floppy disk. The file size is limited to about 1.1 meg. This is also about 4100 data updates with 20 data points per update.

5. When the program finishes converting the data from the SDS format to a DOS format a message will appear. " Press any key to continue". This will return the

/

computer to the SDS program.

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6. Start the Excel program PMSDELOG.XLS.

7. Verify the Title of Graph line 1 is:

UNIT ONE SIMULATOR OPERABILITY TEST 199X

8. Collect printouts and file. These are now part of the test package.

OPERABILITY TEST November 9,1998 100

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ATTACHMENT R-10 OPERABILITY TEST STAFF Position Name Title / License Test Director Test Director Test Director Operator i

Operator Operator Operator Operator i

Operator Operator

(

Operator Operator Simulator Support Staff Simulator Support Staff Simulator Support Staff Simulator Support Staff Simulator Support Staff Simulator Support Staff O)

OPERABILITY TEST November 9,1998 101 e

i Section 5 r

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ANO-1 New Malfunctions f

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ANO-1 New Malfunctions PMy b8lWWL?Pw"*h2WW Wk "W* W:em ' YM*

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CVS27 P32A RCP SHAFT LEAKAGE 1/2/98 CV928 P32B RCP SHAFT LEmKAGE 1/2/98 Cve20 P33C RCP SHAFT LEAKAGE 1/2/06 CVtae P32D RCP SHAFT LEAKAGE 1/2/08 CV967 MAKEUP TANK REFERENCE LEG LEAK 1/16/06 ED178 MAW TRANSFORMER FAILURE PHASE B 16/28/97 ED170 MAIN TRANSFORMER FAILURE PHASE C 10/28/97 ED482 LOSS OF BUS H2 1/24/07 ED640 FEEDER BREAKER 182-113 FAILS TO LATCH 1/34/98 ED841 FEEDER BREAKER 182 34 FAILS TO LATCH 1/30/08 ED642 MCC P2C BREAKER FAILS TO LATCH 1/30/08 ED643 MCC P3B BREAKER FAILS TO LATCH 1/30/06 ED644 MCC P34A BREAKER FAILS TO LATCH 1/3448 ED648 MCC PTB BREAKER FAILS TO LATCH 1/34/98 ED644 MCC P32C BREAKER FAILS TO LATCH 1/30/88 FW197 FLOWPATH "A" ORIFICE SCREEN FAILS FWP 'A" S 4/98 FW198 FLOWPATH "A" ORIFICE SCREEN FAILS FWP *B" S 4/08 FW111

• A* MFP CONTROL OIL PRESSURE FAILURE

$447 i

FW112

• B" MFP CONTROL OIL PRESSURE FAILURE 8 4/07 1

FW113 MFWP TRIP STATUS RELAY CONTACT FAILURE 1/2/98 MS137 8 TEAM SUPPLY LINE RUPTURE TO PTA 10/2847 MS138

• A* MAIN STEAM LINE RUPTURE TO PTA 10/2847 i

MS145 PSV-2884 MSSV FAILS OPEN 2/23/88 RC488 P32A ANTI REVERSE ROTATION DEVICE FAlLURE 3/26/97 RC487 P32B ANTI REVERSE ROTATION DEVICE FAILURE 3/2647 RC488 P32C ANTI REVERSE ROTATION DEVICE FAILURE 3/26/97 RC4e8 P320 ANTI REVERSE ROTATION DEVICE FAILURE 3/2647 RC471 HOT LEG LOOP 'A' HP VENT FAILS 7/1348

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RC4T2 HOT LEG LOOP "B" PF VENT F AA.S T/13/DB RC473 PRESSURIZER HP VENT FAILS 7/13/98 RC474 RK VESSEL HP VENT FAILS T/13/08 RD648 8 TUCK ROD ON REACTOR TRIP GRP 1 RD 3 g 8 W 1/36/98 RD448 STUCK ROO ON REACTOR TRIP GRP S RD 1 g 5 W 9/20/98 RD440 STUCK ROD ON REACTOR TRIP GRP S RD 12 $ te W S/2048 RD441 STUCK ROO ON REACTOR TRIP GRP 3 RD 18 il IN 9/2048

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RD824 CRD MOTOR HEATUP GRP S RD 3 1/1946 RD826 CRD MOTOR HEATUP GRP 7 RD 6 1/1648 RP271 FLUX / DELTA FLUK 1 FLOW TRIP FAILURE *A* CHANNEL 7 4/08 RPZ72 FLUK / DELTA FLUX / FLOW TRIP F ALLURE *B" CHANNEL 7448 RPIT3 FLUK i DELTA FLUX i FLOW TRIP FAlLURE *C" CHANNEL 7 4/98 RP274 FLUK / DELTA FLUK i FLOW TRIP FAILURE "D" CHANNEL T4/98 SW220 SW BAY *A* STRAINER FAILURE F114A 12/16/08 1

)

SW221 SW SAY *C* STRAMER FAILURE F118C 12/16/98 TResa SGA MtESS PTN18A e-1300 PSIG W18/06 Tree 8 SGA PRESS PT38108 e-1300 PSNB W14/98 TRete SOS PRESS PTN17A 4-1300 PSIG W16/ps Trees SOS PRESS PTN175 0-1300 PSee W144s TRN8 SGA LEVEL LTN18 e-100 M W16/06 Tree 7 SOS LEVEL LTN716180 W W16/06 Trest SGA LEVEL LTasse 8400 W Wieles i

TRSee SOS LEVEL LTNT3 6400 W W16/06 TRett RCS WIDE RANGE PRESSURE PT-1641 FAILURE 1/2647 1

TRs22 SWET LEVEL WSTRUMENT LT4411 FAILS 14/28/07 TRS23 SWET LEVEL NSTRUMENT LT4421 FAdLS 10/28/97 i

TR6N "A" CFT LEVEL WSTRUMENT LT-3414 FAILS 10/28/97 i

TRsN

• A* CFT LEVEL WSTRUMENT LT 3416 FAILS 10/28/97 TR$N

• S* CFT LEVEL NSTRUMENT LT4418 FAILS 14/20/07 l

TRS27

• B" CFT LEVEL IMSTRUMENT LT-3410 FAILS 10/28/97 TU148

1. 1 OOVERNOR VALVE SINDING 9/16/07 i

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