ML20133A231

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Ferm 2 CR Simulator Four Yr Rept
ML20133A231
Person / Time
Site: Fermi DTE Energy icon.png
Issue date: 12/19/1996
From:
DETROIT EDISON CO.
To:
Shared Package
ML20133A230 List:
References
NUDOCS 9612300132
Download: ML20133A231 (25)
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Text

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THE DETROIT EDISON COMPANY l

) FERMI 2 NUCLEAR POWER PLANT 1

l CONTROL ROOM SIMULATOR i 1

4 YEAR REPORT 1

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J 9612300132 961219 PDR ADOCK 05000341 R pop

TABLE OF CONTENTS Section Eagc i

Four Year Report 1.0 Purpose 3 2.0 References 3 3.0 Rcquirements 3 4.0 Compliance With Requirements A. Uncorrected Performance Test Failures and Schedule for Correction 4 B. Exceptions to ANSI /ANS 3.5 -1985 5  :

C. Testing Performed In Last 4 Year Period

1) Computer Real Time Test 5
2) Steady State and Normal Operations Test 6
3) Normal Operations Test 6
4) Transient and Malfunction Testing 7
5) Initial Conditions Performance Test 7 D. Description of New Performance Tests to be -

Conducted During the Subsequent Four Year 1 Period 8  !

l E. Schedule for the Conduct of Performance Tests for the Subsequent Four Year Period 8

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Simulator Certification Teat Performance Attachment 1 l

l Simulator Certification Test Schedule Attachment 2  !

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e THE DETROIT EDISON COMPANY FERMI 2 SIMULATOR CERTIFICATION FOUR YEAR REPORT 1.0 Purpose The Fermi 2 Simulator is certified to meet the requirements of 10CFR55.45 as a valid tool for conducting the simulator portion of NRC license examinations, and for meeting the licensed operator initial, upgrade, and requalification training objectives ,

of Fermi 2. In accordance with 10CFR55.45, every four years on the anniversary of the certification application, a repon must be submitted to the Commission.

The purpose of this report is to satisfy this reporting requirement for the Fermi 2 Control Room Simulator.

2.0 References A. Title 10, Code of Federal Regulations, Part 55, " Operator Licenses", Subpart E, Section 45. I B. U.S. Nuclear Regulatory Commission, Regulatory Guide 1.149 " Nuclear Power Plant Simulation Facilities for Use In Operator License Examinations." ,

1 C. ANSI /ANS 3.5-1985," Nuclear Power Plant Simulators for Use In Operator Training." l 3.0 Requirements A.10CFR55.45 requires the following be contained within this renort:

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1) Subpart E, Section 55.45 (b)(5)(ii) - Identification of any uncorrected performance test failures and a schedule for correction of such performance failures.
2) Subpart E, Section 55.45 (b)(5)(vi) - A description of performance testing 4 completed for the simulation facility. ,

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3.0 Requirements continued:

3) Subpart E, Section 55.45 (b)(5)(vi)- A description of the performance tests, if different, to be conducted on the simulation facility during the subsequent four -

year period.

4) Subpart E, Section 55.45 (b)(5)(vi)- A schedule for the conduct of approximately 25 percent of the performance tests per year for the subsequent 4 years.

4.0 Fermi 2 Compliance with Requirements A. Uncorrected performance test failures at Fermi 2 and schedule for l

correction

1) DR 94-1363: Response to reactor water level changes appears slightly slow when operating with the Startup Level Control Valve in service and feedmg l with a Reactor Feedpump. i Scheduled completion date for correction: 12/20/96
2) DR 95-1084: Several discrepancies exist concerning radiation transport during transients.

Scheduled completion date for correction: 12/31/97

3) DR 95-0512: Rod Block Monitor response not correct following cessation of rod movement.

Scheduled completion date for correction: 12/20/96

4) DR 96-0139: Turbine Bypass Valves do not respond exact y as e(pected following a pressure regulator failure. .

Scheduled completion date for correction: 12/TV96  !

5) DR 96-0403: Level decrease in condenser slight,y > ss than expected during level control system failure malfunction.

Scheduled completion date for correction: 12/20/96

6) DR 96-0404: Hotwell low level trip is occurring sooner than expected.

Scheduled completion date for correction: 12/20/96

7) DR 96-0714: RPV level doesn't increase to expected floodup value following a feed line rupture in the drywell (appmximately 10% too low).

Scheduled completion date for correction: 12/,0/96

8) DR 96-0730: EDG Trouble annunciator for EDG 14 unexpectedly received during loss ofelectrical bus, and MWe oscillated following loading.

Scheduled completion date for correction: 12/20/96.

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.- *O B. Exception to ANSI /ANS 3.5 - 1985

~ 1) Section 3.3.1 of ANSI /ANS 3.5-1985, titled " Systems Controlled from the Control Room", requires that simulation be to the extent necessary to perform reference plant evolutions required for Normal Plant Evolutions and i Plant Malfunctions. Contrary to this requirement, DR's 93-0468 and 94- i 0528 identify discrepancies and unincorporated modifications associated with i the Plant Process Computer (PPC) in the simulator. Correction of the j identified discrepancies was always expected to occur in conjunction with  !

procurement and installation of a PPC upgrade in the power plant, which was originally projected to occur as early as 1991. Since the simulator PPC consists of a limited model, and the training impact is minimal, I unincorporated modifications and discrepancies have been allowed to accumulate. It is currently anticipated that the PPC upgrade in the plant and i the simulator will occur by the end of 1999.

2) During Steady State Testing, Turbine First Stage Pressure is measured versus  :

Turbine Steam Flow (as noted in the original certification package).

C. Description of performance testing performed in the last four year pe'riod ANS/ ANSI 3.5-1985 Appendix A, section A.3 describes certification testing requirements. Four separate categories are identified, and tested as follows:

1) Computer Real Time Test
a. This test validates that the simulation is being presented in real time. In addition, the test validates that an alarm is received at the Instructor.

Station if the simulation is not being present' e d in real time. Verification of simulator spare computing capacity is also performed. The Real Time Test validates the functionality of real time monitoring by forcing the simulation out of real time and verifying actuation of the alarm.

b. This test also verifies that simulator Operating Limits are being monitored, and that a warning (parameter over-range alarm) is actuated at the j Instructor Station console to alent the instructor when any one of these limits is exceeded. Each of the monitored parameters is forced to its  !

corresponding high and/or low limit and actuation of the alarm is verified.

Attachment I lists the specific date that computer real time testing was  ;

performed. This test is currently performed one time during the 4 year testing period.

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4 f 2) Steady State Test 1

Steady State Testing is composed of three separate activities:

a. Steady state performance testing is performed to evaluate and benchmark i the degree of agreement between the simulator and the Fermi 2 plant for

, mass and energy balance parameters at three steady state power levels.

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b. Stability performance is performed to evaluate and benchmark simulator l dynamic stability (simulator drift) at 100% power.
c. Simulator instrument error is verified to be no greater than the Fermi 2 plant while operating at 100% power.

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- Attachment I lists the specific dates that steady state performance testing was performed.  !
3) Normal Operations Test  :
a. This testing validates the capability to perform the normal plant evolutions i- of ANSI /ANS-3.5-1985, Section 3.1.1 by performing the relevant General Operating Procedures, System Operating Procedures, and Surveillance Procedures (and/or procedure sections).

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b. In addition, Emergency Operating, Abnormal Operating, and Alarm f Response Procedures (or portions of those procedures) are performed as J necessary to validate the capability for operators to respond to the specific r malfunction events required by ANSI /ANS-3.5-1985, Section 3.1.2 and  :

the transient events listed in ANSI /ANS-3.5-1985, Appendix B, Section J B l .2.

c. Regulatory Guide 1.149, Revision 1, April 1987 requires that the normal plant evolutions of ANSI /ANS-3.5-1985, Section 3.1.1 be performed periodically (at the rate of approximately 25% per year) to verify- ,

continuing integrity of the simulator models.

Attachment I lists the dates that the specific Normal Operations Tests were performed.

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4) Transient and Malfunction Testing .

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a. Testing is performed to evaluate agreement between the simulator response and predicted responses for malfunction events. The testing validates dynamic and logical fidelity for the event without regard to i operator action.

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b. The set of malfunctions events validated consists of the events of l ANSI /ANS-3.5-1985, Section 3.1.2 and Appendix B, Section Bl.2. This I is performed periodically to meet the periodic testing requirements of

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ANSI /ANS-3.5-1985 and Regulatory Guide 1.149, Revision 1, April l 1987. '

4 Attachment I lists the dates that the specific Transient and Malfunction Tests l were performed.

4 (In addition to the four categories of certification testing required by ANS/ ANSI 3.5-1985 Appendix A, section A.3, the Initial Conditions Performance Test l described below is also performed at Fenni 2.)  ;

5) Initial Conditions Performance Test i
a. The Initial Conditions performance testing is performed to i validate that the administratively controlled simulator initial conditions (IC's) satisfy their intended use in support of simulator training. This test also validates the ANSI /ANS-3.5-1985 requirement that a minimum of ten IC's are operational which include a variety of plant operating conditions, fission product poison concentrations, and various times in core life.

Attachment I lists the dates that the specific Initial Conditions Performance Tests were performed.

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D. Description of performance tests,if different, to be conducted on the simulation facility during the subsequent four year period.

1) New tests to be performed during the next four year period and added to the performance test schedule include:
a. MFE135: Reactor Scram with Gland Seal System In Manual
b. MFE136: Loss of Feedwater due to False L8 Signal
c. Surveillance Test 24.408.04 - Division 2 Primary Containment Monitoring System Valve Operability and Position Indication Verification Test
2) Tests being deleted from those contained on the previous test schedule include:

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a. Surveillance Test 44.010.149 - Rod Block Monitor Channel "A" Functional Test is being deleted from the test schedule as the major portion of this test is m !onger performed in the Control Room.
b. Surveillance Test 44.010.150 - Rod Block Monitor Channel"B" Functional Test is being deleted from the test schedule as the major portion of this test is no longer performed in the Control Room.

E. Schedule for the conduct of approximately 25 percent of the performance tests per year for the subsequent 4 years.

1) Attachment 2 provides the schedule for certification testing to be performed over the next four year period. Approximately 25% of all malfunction testing is performed annually.

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ATTACHMENT 1 I

FERMI 2 SIMULATOR CERTIFICATION TEST PERFORMANCE This attachment provides information relative to certification performance testing of the Fermi 2 Control Room Simulator. This testing has been performed in accordance with requirements as stated in ANS/ ANSI 3.5-1985 and Regulatory Guide 1.149 Revision 1, April 1987.

Deviations From Original Certification Test Schedule There was one deviation from the test schedule submitted in the original certification report. The Steady State Operations Performance Test portion of 1994 cenification ,

testing was not performed during cslendar year 1994 due to the unavailability of actual steady state plant data. This was a result of the extended plant shutdown caused by the December 25,1993 Turbine Failure Event at Fermi 2. Upon completion of plant run time at high power conditions during 1995, plant data was obtained and SCM 6 steady state testing was performed. ,

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1. COMPUTER REAL TIME TEST - This test is performed as described in the l applicable Simulator Cenification Maintenance Procedure, SCM 5 - Operating Limit  ;

and Real Time Test. The test was collectively completed on the following date: l Test Completion: November 11,1993 (this test performed only once during 4 year cycle.)

2. STEADY STATE TEST - This test is performed as described in the applicable i Simulator Certification Maintenance Procedure, SCM 6 - Steady State Operations  !

Performance Test. This test encompasses the following:

A. Low Power Data Comparison B. Mid Power Data Comparison i C. Full Power Data Comparison D. Full Power Stability Verification E. Full Power Panel Indicator Verification Test Completion:

E - December 29,1993 M - June 29,1995 (see note in deviations from original test schedule above)

M - October 5,1995 M - June 5,1996 Page1

Attachment I a .

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3. NORMAL OPERATIONS TEST - This test is performed as described in the applicable Simulator Certification Maintenance Procedure, SCM 7 - Operations l Procedures Performance Test:  ;

1993 Normal Onerations Test Test Completion: December 29,1993 l This test consisted of:

A.1993 Normal Plant Evolutions:

1) Startup From Cold Shutdown to Hot Standby - GOP NPP 22.000.02 " Plant

, Startup to 25% Power", through completion of" Reactor Pressure and Temperature Monitoring During Heatup"(with the MSIV's closed).

. B.1993 Surveillance Test Procedures for Safety Related Equipment  !

i 1) 24.000.02 Shiftly, Daily, Weekly and Situation Required Surveillances

2) 24.106.02 CRD Coupling Integrity Verification l
3) 24.107.03 SBFW Pump and Valve Operability and Lineup Verification Test l
4) 24.129.01 Station and Control Air System Valve Operability and Position
Indication Verification Test  !
5) 24.137.15 MSIV Leakage Control System Functional Test l
6) 24.138.04 Recirculation Sample System Isolation Valve Operability Test l
7) 24.202.02 HPCI Flow Rate Test at 165 PSIG Reactor Steam Pressure  !
8) 24.203.04 Core Spray Valve Operability and Position Verification Test
9) 24.204.06 Div. II LPCI and Suppression Pool Cooling / Spray Pump and Valve Operability Test j
10) 24.205.08 Div. I RHR Cooling Tower Fan Operability and RHRSW EESW j Valve Line-up Verification l
11) 24.206.04 RCIC Flow Rate Test at 150 PSIG l
12) 24.207.07 EECW/EESW Actuation Functional Test
13) 24.402.01 Drywell and Suppression Chamber Vacuum Breaker Operability Test
14) 24.404.04 Division II SGTS Filter and Secondary Containment Isolation Damper 1 Operability Test  :
15) 24.409.03 Division II Post LOCA Thermal Recombiner System Valve Operability '

Test

16) 24.608 Rod Worth Minimizer Functional Test
17) 24.630 Remote Shutdown Instrument Channel Checks
18) 24.800.04 Alternate Coolant Circulation and Decay Heat Removal Standby Lineup Operability Verification Page 2

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Attachment 1

, 1993 Normal Operations Test continued: )

C.1993 Plant Malfunctions and Transients - Procedures used to respond to these events were validated.

1) 001 Loss of FW Flow Signal"A" l
2) 005 Spurious Main Steam Isolation I
l. 3) 006 Recire. Pump Speed Increase upon Automatic Reset of #1 Limiter l
4) 008 Reactor Manual Scram
5) 011 HPCI System Spurious Initiation j j 6) 013 Recire. Pump "A" Trip
7) 014 Loss of Both Recirculation Pumps .
8) 017 Spurious Scram
9) 023 Earthquake  !
10) 028 Control Rod Drift In
11) 033 Loss of 4160V Bus 69J
12) 037 Loss of Offsite Power
13) 043 Feed Pump Min. Flow Recire. Valve Fails Open
14) 045 Steam Line Rupture in the Drywell
15) 048 LPRM 16-49-ID Fails Fullscale .)
16) 052 Loss ofFeed l
17) 053 Main Turbine Trip at 25%  ;
18) 054 Master Flow Control Transient
19) 055 Recire. Loop Rupture With Loss of Offsite Power
20) 056 MSIV Closure with Stuck Open SRV, Failed Closed SULCV and Failure of HPCI/RCIC
21) 059 Reactor Power Oscillations
22) 063 Off Gas Explosion
23) 067 RPS/NSSS Drywell Pressure Transmitter Failure i
24) 107 Main Turbine Trip Without Bypass Valves
25) 121 Reactor Scram Subsequent to Resetting a Scram Due to Failure to Bypass High Scram Discharge Volume Level Scram 1994 Nor==I Operations Test Test Completion: December 7,1994 J

This test consisted of:

A.1994 Normal Plant Evolutions:

Startup from Hot Standby to Rated Power, including:

1) NPP-22.000.02 " Plant Startup to 25% Power", Section 5 beginning with the step " opening MSIV's" (includes Section 8.0).
2) NPP-22.000.02 " Plant Startup to 25% Power", Section 6 "RPV Pressurization".
3) NPP-22.000.02 " Plant Startup to 25% Power", Section 7.0 " Main Turbine Startup and Power Increase to 25%".

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i Attachment 1 Ii 1994 Normal Operations Test continued:

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4) NPP 22.000.03 " Power Operation 25% to 100% to 25%", Section 4.0

" Power Increase".

5) Demonstrated ability to operate above the 100% load line.  !
6) Demonstrated abilit, to operate in single Recire. Loop Operation.

B.1994 Surveillance Test Procedures for Safety Related Equipment: ,

1) 24.000.03 Mode 5 Shiftly, Daily, and Weekly Surveillances l 2) 24.106.04 Scram Discharge Volume Vent and Drain Valve Operability Test

! 3) 27.109.01 Turbine Steam Valves Test

4) 24.137.01 Main Steam Line Isolation Channel Functional Test
5) 24.137.16 MSIV Leakage Control System Monthly Operability Test  ;

j 6) 24.138.06 Jet Pump Operability Test i 7) 24.202.05 ' HPCI System Cold Shutdown Valve Operability Test l 8) 24.204.01 Div.1 LPCI and Suppression Pool Cooling / Spray pump and Valve

! Operability Test

9) 24.204.08 Non-Divisional RHR Local Valve and Position Verification Test
10) 24.205.10 Div. 2 RHR Cooling Tower Fan Operability and RHRSW EESW Valve Line-up Verification d
11) 24.207.04 RBCCW/EECW Miscellaneous Valve Operability Test
12) 24.208.02 Division 1 EESW Pump and Valve Operability Test

.'! 13) 24.402.07 Drywell to Suppression Chamber Vacuum Breaker Closed Verification Test

14) 24.406.01- Nitrogen Inerting System Valve Operability Test i_ '15) 24.413.03 Control Room Emergency Filter Monthly Operability Test
16) 24.610.01 RPS - Manual Scram Functional Test
17) 24.630.01 Remote Shutdown Panel Control Circuit and Switch Test
18) 44.010.149 Rod Block Monitor (RBM) Channel A Functional Test C.1994 Plant Malfunctions and Transients - Procedures used to respond to these events were validated:
1) 002 Fuel Cladding Failure
2) 005 Spurious Main Steam Isolation
3) 007 Loss of Normal Feedwater with Failure of HPCI, RCIC, and SBFW
4) 008 Reactor Manual Scram
5) 012 Spurious Main Steam Isolation With Failure of RPS Auto Scram Logic
6) 013 Recire. Pump "A" Trip
7) 014 Loss of Both Recirculation Pumps
8) 018 Main GeneratorTrip
9) 024 120V AC Bus Trip H11-P900
10) 029 Control Rod Drop
11) 034 Condenser Air Leak
12) 038 Loss of 4160 Volt ESF Bus 64C Page 4

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Attachment 1 1994 Normal Operations Test continued:

13) 044 Loss of RPS Channel
14) 045 Steam Line Rupture in the Drywell
15) 050 Annunciator Failure
16) 052 Loss of Feed
17) 053 Main Turbine Trip at 25%
18) 054 Master Flow Control Transient
19) 055 Recire. Loop Rupture with Loss of Offsite Power
20) 056 MSIV Closure with Stuck Open SRV, Failed Closed SULCV, and Failure of HPC1/RCIC
21) 060 Loss of 4160 Volt ESF Bus 64B
22) 064 Loss of Gland Seal Exhauster
23) 071 SRM ChannelFailure
24) 111 General Service Water Pump Trip  ;
25) 131 Recire. Pump Speed Increase on Scoop Tube Reset i

1995 Nor==I Onerations Test Test Completion: November 27,1995 l This test consisted of: i A.1995 Normal Plant Evolutions:

Plant Shutdown from Rated Power to Hot Standby, and Cooldown to Cold Shutdown Conditions, including:

1) NPP-22.000.03 " Power Operation 25% to 100% to 25%", Section 5.0

" Power Decrease".

2) NPP-22.000.04 " Plant Shutdown From 25% Power", Section 4.0 " Load Reduction".
3) NPP-22.000.04 " Plant Shutdown From 25% Power", Section 5.0 " Reactor Shutdown, Cooldown, and Depressurization (MSIV's Open)".
4) NPP 22.000.04 " Plant Shutdown From 25% Power", Section 6.0 ' Plant i Shutdown". l B.- 1995 Surveillance Test Procedures for Safety Related Equipment
1) 24.000.05 Monthly Continuity Light and Channel Check j
2) 24.106.% Scram Discharge Volume Vent and Drain Valves Scram Operability Test
3) 24.109.02 Turbine Bypass Valve Operability Test
4) 24.137.03 Main Steam Line Valve Operability Test
5) 24.137.18 Main Steam Line Drain Isolation Valve Operability Test 6)'24.144.01 TWMS Valve Operability and Valve Position Indication Verification Test
7) 24.203.02 Division I CSS Pump and Valve Operability and Automatic Actuation.

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, ,. . l Attachment 1 1995 Normal Operations Test continued:

8) 24.204.02 RHR Valve Lineup and System Filled Verification
9) 24.205.05 Division I RHRSW Pump and Valve Operability Test
10) 24.206.01 RCIC System Pump and Valve Operability Test ,
11) 24.207.05_ EECW Valve Operability Test 12) 24.208.03 Division 11 EESW I Pump and Valve Operability Test I I
13) 24.404.02 Division I SGTS Filter and Secondary Containment Isolhtion Damper Operability Test
14) 24.408.01 Primary Containment Monitoring System Valve Operability and Position Indication Verification Test.
15) 24.415 Drywell Cooling Fan 1 and 2 Operability Test
16) 24.610.02 RPS - Mode Switch In Shutdown Functional Test
17) 24.702.01 Miscellaneous Systems Valve Operability Test
18) 44.010.150 Rod Block Monitor (RBM) Channel Functional B Functional Test C. 1995 Plant Malfunctions and Transients - Procedures used to respond to these events were validated:
1) 003 Main Turbine Trip
2) 005 Spurious Main Steam Isolation
3) 008 Reactor Manual Scram .
4) 009 Main Steam Line Rupture in the Steam Tunnel
5) 013 Recire. Pump"A" Trip
6) 014 Loss of Both Recirculation Pumps
7) 015 RPV Lvl Xmtr Fail- Floodup B21-N027
8) 019 Recirculation Loop Rupture "A" Large
9) 026 Control Rod (XX-YY) Uncoupled
10) 031 CRD Flow Control Valve "A" Fails Shut
11) 035 Stator Water Cooling High Temperature
12) 040 Recireplation Loop Rupture A (Small) l
13) 045 Steam Line Rupture in the Drywell
14) 046 Excessive Cooldown Rate During Shutdown Cooling
15) 052 LossofFeed
16) 053 Main Turbine Trip at 25%
17) 054 Master Flow Control Transient  ;

I8) 055 Recire Loop Rupture With Loss of Offsite Power l

19) 056 MSIV Closure With Stuck Open SRV, Failed Closed SULCV and Failure of HPC1/RCIC .  !
20) 057 Station Blackout
21) %1 Loss of 4160 Volt ESF Bus 65E j
22) %5 RPV Reference Leg Sensing Line Rupture
23) 088 RHR Service Water Pump Trip i
24) 118 Interruptible Air Header Rupture Page 6

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i Attachment 1 1996 Nor==I Operations Test Test Completion: August 4,1996 This test consisted of:

A.1996 Normal Plant Evolutions:

Reactor Trip Followed by Recovery to Rated Power, including:

1) NPP-20.000.21 " Reactor Scram".  ;
2) NPP-22.000.02 " Plant Startup to 25% Power", Section 4.0 "Precriticality".
3) NPP-22.000.02 " Plant Startup to 25% Power", Section 5.0 " Reactor '

Startup/Heatup",

4) NPP 22.000.02 " Plant Startup to 25% Power", Section 6.0 "RPV Pressurization". l
5) NPP 22.000.02 " Plant Startup to 25% Power", Section 7.0, " Main Turbine l

Startup and Power Increase to 25%". 1

6) NPP 22.000.03 " Power Operation 25% to 100% to 25%", Section 4.0

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" Power Increase".

l B.1996 Surveillance Test Procedures for Safety Related Equipment '

1) 24.106.01 Operable Control Rod Check
2) 24.107.01 Feedwater Reverse Flow Check Valve Operability and Position ,

Indication Verification Test 1

3) 24.110.05 RPS-Turbine Control and Stop Valve Functional Test
4) 24.137.11 Safety Relief Valve (SRV) Operability Test
5) 24.138.02 Reactor Recirculation Pumps Valve Operability Test
6) 24.202.01 HPCI Pump Time Response and Operability Test at 1025 PSI
7) 24.203.03 Division II CSS Pump and Valve Operability and Automatic Actuation.
8) 24.204.04 RHR Shutdown Cooling Valve Operability
9) 24.205.% Division II RHRSW Pump and Valve Operability Test
10) 24.206.02 RCIC Valve Operability Test
11) 24.207.06 EECW/EESW Actuation Functional Test-Division I
12) 24.324.01 Combustion Turbine Generator 11 Unit 1 Monthly Operability Check
13) 24.404.03 Standby Gas Treatment System Valve Operability Test
14) 24.409.02 Division I Post LOCA Thermal Recombiner System Valve Operability Test
15) 24.603.02 SRM/IRM APRM Overlap Verification
16) 24.623 Reactor Manual Control / Reactor Mode Switch / Refueling Platform-Refueling Interlocks
17) 24.707.01 Reactor Water Cleanup (RWCU) Valve Operability Test Page 7

Attachment 1 1996 Normal Operations Test continued:

C.1996 Plant Malfunctions and Transients - Procedures used to respond to these events were validated:

1) 004 Feedwater Line Rupture in the Steam Tunnel
2) 005 Spurious Main Steam Isolation
3) 008 Reactor Manual Scram
4) 010 Main Steam SRV "K" Fails Open
5) 013 Recire. Pump "A" Trip
6) 014 Loss of Both Recirculation Pumps  ;
7) 016 Rx. Recire. Pump "A" Runaway l
8) 022 Loss of DC Dist. Cabinet 2IAl-3 l
9) 027 Control Rod (XX-YY) Blade Stuck
10) 032 Pressure Regulator"A" Fails High
11) 036 Main Condenser Level Control System Failure 4
12) 042 Loss of Shutdown Cooling
13) 045 Steam Line Rupture in the Drywell
14) 047 Feed Line Rupture in the Drywell
15) 052 Loss ofFeed
16) 053 Main Turbine Trip at 25% 1
17) 054 Master Flow Control Transient
18) 055 Recire Loop Rupture With Loss of Offsite Power
19) 056 MSIV Closure With Stuck Open SRV, Failed Closed SULCV and Failure of HPCI/RCIC
20) 058 Spurious Single Control Rod Scram ,
21) 062 Loss of 4160 Volt ESF Bus 65F l
22) 066 RPV Wide Range Variable Leg Sensing Line Rupture
23) 093 HPCI Steamline Break in Reactor Building
24) 120 Loss of 4160 Volt Bus 65D
4. TRANSIENT AND MALFUNCTION TESTING - This test is performed as described in the applicable Simulator Certification Maintenance Procedure, SCM 8 -

Malfunction Event Performance Test.

1993 Transient and Malfunction Testing Test Completion: December 29,1993 This test consisted of:

A. 001 Loss of FW Flow Signal "A" B. 005 Spurious Main Steam Isolation C. 006 Recire. Pump SpecJ Increase upon Automatic Reset of #1 Limiter D. 008 Reactor Manual Scram E. 011 HPCI System Spurious Initiation Page 8

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Attachment 1 1993 Transient and Malfunction Testing continued:

- F. 013 Recire. Pump "A" Trip G. 014 Loss of Both Recirculation Pumps l H. 017 Spurious Scram i I. 023 Earthquake )

J. 028 Control Rod Drift In K. 033 Loss of 4160V Bus 69J l l L 037 Loss of Offsite Power M. 043 Feed Pump Min. Flow Recire. Valve Fails Open N. 045 Steam Line Rupture in the Drywell O. 048 LPRM 16-49-ID Fails Fullscale .

P. 052 Loss ofFeed Q. 053 Main Turbine Trip at 25% I R. 054 Master Flow Control Transient S. 055 Recire. Loop Rupture With Loss of Offsite Power. .

T. 056 MSIV Closure with Stuck Open SRV, Failed Closed SULCV and Failure of l HPCI/RCIC U. 059 Reactor Power Oscillations V. 063 OffGas Explosion W. 067 RPS/NSSS Drywell Pressure Transmitter Failure X.107 Main Turbine Trip Without Bypass Valves l Y 12 -

>ctor Scram Subsequent to Resetting a Scram Due to Failure to Bypass High l Scram Discharge Voh me Level Scram 1994 Transient and Malfunction Testina Test Completion: December 7,1994 This test consisted of:

A. 002 Fuel Cladding Failure B. 005 Spurious Main Steam Isolation 1 C. 007 Loss of Normal Feedwater with Failure of HPCI, RCIC, and SBFW D. 008 Reactor Manual Scram E. 012 Spurious Main Steam Isolation With Failure of RPS Auto Scram Logic F. 013 Recire. Pump "A" Trip G. 014 Loss of Both Recirculation Pumps H. 018 Main GeneratorTrip I. 024 120V AC Bus Trip H11-P900 J. 029 Control Rod Drop K. 034 Condenser Air Leak L. 038 Loss of 4160 Volt ESF Bus 64C M. 044 Loss of RPS Channel N. 045 Steam Line Rupture in the Drywell O. 050 AnnunciatorFailure Page 9

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Attachment 1 1994 Transient and Malfunction Testing continued:

P. 052 Loss of Feed Q. 053 Main Turbine Trip at 25%

R. 054 Master Flow Control Transient S. 055 Recire. Loop Rupture with Loss of Offsite Power T. 056 MSIV Closure with Stuck Open SRV, Failed Closed SULCV, and Failure of HPCI/RCIC l U. 060 Loss of 4160 Volt ESF Bus 64B V. 064 Loss of Gland Seal Exhauster W. 071 SRM Channel Failure

X. I11 General Service Water Pump Trip Y.131 Recire. Pump Speed Increase on Scoop Tube Reset
1995 Transient and Malfunction Testing Test Completion
November 27,1995

. This test consisted of:

A. 003 Main Turbine Trip B. 005 Spurious Main Steam Isolation C. 008 Reactor Manual Scram D. 009 Main Steam Line Rupture in the Steam Tunnel E. 013 Recire. Pump "A" Trip F. 014 Loss of Both Recirculation Pumps G. 015 RPV Lvl Xmtr Fail- Floodup B21-N027 H. 019 Recirculation Loop Rupture "A" Large I. 026 Control Rod (XX-YY) Uncoupled J. 031 CRD Flow Control Valve "A" Fails Shut K. 035 Stator Water Cooling High Temperature L. 040 Recirculation Loop Rupture A (Small)

M. 045 Steam Line Rupture in the Drywell N. 046 Excessive Cooldown Rate During Shutdown Cooling O. 052 Loss of Feed P. 053 Main Turbine Trip at 25%

Q. 054 Master Flow Control Transient R. 055 Recire Loop Rupture With Loss of Offsite Power S. 056 MSIV Closure With Stuck Open SRV, Failed Closed SULCV and Failure of HPCI/RCIC T. 057 Station Blackout U. 061 Loss of 4160 Volt ESF Bus 65E V. 065 RPV Reference Leg Sensing Line Rupture W. 088 RHR Service Water Pump Trip X. I18 Interruptible Air Header Rupture Page 10

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1 , y i Attachment 1 l 1996 Transient and Malfunction Testine ~

Test Completion: July 9,1996 l 1

! This test consisted of:

A. 004 Feedwater Line Rupture in the Steam Tunnel B. 005 Spurious Main Steam Isolation

]

C. 008 Reactor Manual Scram D. 010 Main Steam SRV "K" Fails Open E. 013 Recire. Pump "A" Trip

, F. 014 Loss of Both Recirculation Pumps G. 016 Rx. Recire. Pump "A" Runaway i H. 022 Loss of DC Dist. Cabinet 21Al-3 I. 027 Control Rod (XX-YY) Blade Stuck

J. 032 Pressure Regulator"A" Fails High K. 036 Main Condenser Level Control System Failure L. 042 Loss of Shutdown Cooling 3

M. 045 Steam Line Rupture in the Drywell

! N. 047 Feed Line Rupture in the Drywell O. 052 Loss of Feed P. 053 Main Turbine Trip at 25%

Q. 054 Master Flow Control Transient R. 055 Recirc Loop Rupture With Loss of Offsite Power S. 056 MSIV Closure With Stuck Open SRV, Failed Closed SULCV and Failure of HPCI/RCIC T. 058 Spurious Single Control Rod Scram U. 062 Loss of 4160 Volt ESF Bus 65F V. 066 RPV Wide Range Variable Leg Sensing Line Rupture ,

W. 093 HPCI Steamline Break in Reactor Building X.120 Loss of 4160 Volt Bus 65D '

5. INITIAL CONDITIONS PERFORMANCE TEST - This test is performed as described in the applicable Simulator Certification Maintenance Procedure, SCM 9 -

Initial Conditions Performance Test. This test encompasses:

A. Validation that the controlled initial conditions (IC's) satisfy their intended use in support of simulator training.

B. A minimum of ten IC's are operational and include a variety of plant operating conditions, fission product poison concentrations, and various periods in core life.

Test Completion:

1991-November 25,1993 1993 - December 9,1994 1925- October 4,1995 1926 - June 4,1996 Page11

o

,- r )

l I

l -

l ATTACHMENT 2 FERMI 2 SIMULATOR CERTIFICATION TEST SCHEDULE This attachment provides the Fermi 2 Control Room Simulator Certification Test schedule through the year 2000. This test schedule has been modified from the initial j certification submittal to include new malfunctions and delete obsolete surveillance tests.

Testing performed meets criteria as specified in ANSI /ANS - 3.5 - 1985 and Regulatory Guide 1.149 Revision 1.

All malfunctions are scheduled to be completed on a four year rotation with approximately 25% performed annually. l Test Description Schedule Sintulator Real Time Test 1997 Normal Plant Evolutions

)

l Startup From Cold Shutdown to Hot Standby 1997 l

Startup From Hot Standby to Rated Power 1998  !

Plant Shutdown From Rated Power to Hot Standby 1999 l and Cooldown to Cold Shutdown l Reactor Trip Followed By Recovery To Rated Power 2000 Surveillance Test Procedures for Safety Related Eauipment I 24.000.02 Shiftly, Daily and Weekly, Required 1997 Surveillances 24.000.03 Mode 5 Shiftly, Daily, and Weekly Surveillances 1998 '

24.000.05 Monthly Continuity Light and Channel Check 1999 24.106.01 Operable Control Rod Check 2000 24.106.02 CRD Coupling Integrity Verification 1997 24.106.04 Scram Discharge Volume Vent and Drain Valve 1998 Operability Test 24.106.06 Scram Discharge Volume Vent and Drain Valves 1999 Scram Operability Test 24.107.01 Feedwater Reverse Flow Check Valve Operability 2000 and Position Indication Verification Test 24.107.03 SBFW Pump and Valve Operability and Lineup 1997 Verification Test 27.109.01 Turbine Steam Valves Test 1998 Page1

s (

Attachment 2 Certification Test Schedule Cont'd:

24.109.02 Turbine Bypass Valve Operability Test 1999 j 24.110.05 RPS-Turbine Control and Stop Valve Fur.ctional 2000 Test 24.129.01 Station and Control Air System Valve 1997

)

Operability and Position Indication l

VeriScation Test 1 24.137.01 Main Steam Line Isolation Channel Functional 1998 I Test 24.137.03 Main Steam Line Valve Operability Test 1999 24.137.11 Safety Relief Valve (SRV) Operability Test 2000 24.137.15 MSIV Leakage Control System Functional Test 1997 24.137.16 MSIV Leakage Control System Monthly 1998  ;

~

Operability Test l 24.137.18 Main Steam Line Drain Isolation Valve 1999 Operability Test 24.138.02 Reactor Recirculation Pumps Valve Operability 2000 Test j 24.138.04 Recirculation Sample System Isolation Valve 1997  ;

Operability Test l 24.138.06 Jet Pump Operability Test 1998 )

24.144.01 TWMS Valve Operability and Valve Position 1999 Indication Verification Test 24.202.01 HPCI Pump Time Response and Operability 2000 Test at 1025 PSI l 24.202.02 HPCI Flow Rate Test at 165 PSIG Reactor 1997 I Steam Pressure

)

24.202.05 HPCI System Cold Shutdown Valve Operability 1998 Test 24.203.02 Division I CSS Pump and Valve Operability and 1999 Automatic Actuation 24.203.03 Division II CSS Pump and Valve Operability and 2000 Automatic Actuation 24.203.04 Core Spray Valve Operability and Position 1997 Verification Test 24.204.01 Div. I LPCI and Suppression Pool Cooling / Spray 1998 Pump and Valve Operability Test 24.204.02 RHR Valve Lineup and System Filled Verification 1999 24.204.04 RHR Shutdown Cco!ing Valve Operability 2000 24.204.06 Div. II LPCI and Suppression Pool Cooling / Spray 1997 Pump and Valve Operability Test 24.204.08 Non-Divisional RHR Local Valve Position 1998 Indication Verification Test Page 2

. -~ - . - . - . . - . - - -- -.. . ... . . - . - -

6 *-

Attaclunent 2 l I Certification Test Schedule Cont'd: 1 24.205.05 Division I RHRSW Pump and Valve Operability 1999 )

Test i

24.205.06 Division 11 RHRSW Pump and Valve Operability 2000 l l1 Test l- 24.205.08 RHR Cooling Tower Fan Operability and 1997 RHRSW and EESW Valve Line-up Verification L 24.205.10 Div. II RHR Cooling Tower Fan Operability and 1998 RHRSW, EESW Valve Line-up Verification 24.206.01 RCIC System Pump and Valve Operability Test 1999 24.206.02 RCIC Valve Operability Test 2000 l 24.206 04 RCIC System Automatic Actuation and Flow Test 1997 1

24.207.04 RBCCW/EECW Miscellaneous Valve Operability 1998  !

Test 24.207.05 EECW Valve Operability Test 1999 24.207.06 EECW/EESW Actuation Functional Test-Div. I 2000 24.207.07 EECW/EESW Actuation Functional Test-Div. II 1997 24.208.02 Division I EESW Pump and Valve Operability 1998 1 Test l

24.208.03 Division II EESW Pump and Valve Operability 1999 ,

Test

]

24.324.01 Combustion Turbine Generator 11 Unit 1 2000 Monthly Operability Check 24.402.01 Drywell and Suppression Chamber Vacuum 1997 Breaker Operability Test 24.402.07 Drywell to Suppression Chamber Vacuum 1998 i Breaker Closed Verification Test 24.404.02 Division I SGTS Filter and Secondary 1999 Containment Isolation Damper Operability Test 24.404.03 Standby Gas Treatment System Valve 2000 Operability Test 24.404.04 Division II SGTS Filter and Secondary 1997 Containment Isolation Damper Operability Test 24.406.01 Nitrogen Inerting System Valve Operability Test 1998 24.408.03 Division 1 Primary Containment Monitoring 1999 System Valve Operability and Position Indication Verification Test H.408.04 Division 2 Primary Containment Monitoring 2000 System Valve Operability and Position Indication Verification Test 24.409.02 Division I Post LOCA Thermal Recombiner 1997 System Valve Operability Test 24.409.03 - Division II Post LOCA Thermal Recombiner 1998 System Valve Operability Test Page 3

  • 4*

i Attachment 2 Certification Test Schedule Cont'd:

24.413.03 Control Room Emergency Filter Monthly 1999 l Operability Test i 24.415 Drywell Cooling Fan 1 and 2 Operability Test 2000 )

! 24.603.02 SRM/IRM/APRM Overlap Verification 1997

, 24.608 Rod Worth Minimizer Functional Test 1998 24.610.01 RPS - Manual Scram Functional Test 1999 )

24.610.02 RPS - Mode Switch in Shutdown Functional Test 2000 '

24.623 Reactor Manual Control / Reactor Mode Switch / 1997 Refueling Platform - Refueling Interlocks l

24.630 Remote Shutdown Instrument Channel Checks 1998 '

24.630.01 Remote Shutdown Panel Control Circuit and 1999 Switch Test l 24.702.01 Miscellaneous Systems Valve Operability Test 2000 l 24.707.01 Reactor Water Cleanup (RWCU) Valve .1997 Operability Test 24.800.04 Alternate Coolant Circulation and Decay Heat 1998 Removal Standby Lineup Operability Verification Plant Malfunctions 001 Loss of FW Flow Signal"A" 1997 002 Fuel Cladding Failure 1998 003 Main Turbine Trip 1999 004 Feedwater Line Rupture in the Steam Tunnel 2000 006 Recire. Pump Speed Increase Upon Automatic 1997 Reset of Speed Limiter #1 007 Loss of Normal Feedwater with a Failure of HPCI, 1998 ,

RCIC, and SBFW  ;

009 Main Steam Line Rupture in the Steam Tunnel 1999 010 Main Steam SRV "K" Fails Open 2000 011 HPCI System Spurious Initiation 1997 012- Spurious Main Steam Isolation With Failure of 1998 RPS Auto Scram Logic 015 RPV Level Xmtr. Fail-Floodup B21-N027 1999 016 Rx. Recire. Pump "A" Runaway 2000 017 Spurious Scram 1997 018 Main Generator Trip 1998 019 Recirculation Loop Rupture "A" Large 1999 022 Loss of DC Dist. Cabinet 2IAl-3 2000 023 Earthquake 1997 024 120V AC Bus Trip H11-P900 1998 026 - Control Rod (XX-YY) Uncoupled 1999 Page 4

u ps

  • Attachment 2 Certification Test Schedule Cont'd:

027 Control Rod (XX-YY) Blade Stuck 2000 028 Control Rod Drift In 1997 I 029 Control Rod Drop 1998 i 031 CRD Flow Control Valve "A" Fails Shut 1999 032 Pressure Regulator"A" Fails High 2000

033 Loss of 4160 Volt Bus 69J 1997 l 034 Condenser Air Leak 1998

! 035 Stator Water Cooling High Temperature 1999-036 Main Condenser Level Control System Failure 2000

! 037 Loss of Offsite Power 1997 I 038 Loss of 4160 Volt ESF Bus 64C 1998

} 040 Recirculation Loop Rupture "A" (small) 1999 l 042 Loss of Shutdown Cooling 2000 l 043 Feed Pump Min. Flow Recire. Valve Fails Open 1997

! 044 Loss of RPS Channel 1998

046 Excessive Cooldown Rate During Shutdown Cooling 1999
047 Feed Line Rupture in the Drywell 2000 1 048 LPRM 16-49-1D Fails Fullscale 1997 1 050 Annunciator Failure 1998 057 Station Blackout 1999 058 Spurious Single Control Rod Scram 2000 059 Reactor Power Oscillations 1997 4

060 Loss of 4160 Volt ESF Bus 64B 1998 j 061 Loss of 4160 Volt ESF Bus 65E 1999 062 _ Loss of 4160 Volt ESF Bus 65F 2000

063 Off Gas Explosion 1997 5

064 Loss of Gland Seal Exhausters 1998 065 RPV Reference Leg Sensing Line Rupture 1999 066 RPV Wide Range Variable Leg Sensing Line Rupture 2000

%7 RPS/NSSS Drywell Pressure Transmitter Failure 1997 071 SRM Channel Failure 1998 088 RHR Service Water Pump Trip 1999 093 HPCI Steamline Break in the Reactor Building 2000 107 Main Turbine Trip With Failure of Bypass Valves 1997 111 General Service Water Pump Trip 1998 118 Interruptible Air Header Rupture 1999 a 120 Loss of 4160 Volt Bus 65D 2000 121 Reactor Scram Sub. to Resetting a Scram Due to Failure to Bypass High Scram Discharge Volume Level Scram 1997 131 Recire Pump Speed increase on Scoop Tube Reset 1998 135 Reactor Scram with Gland Seal System In Manual 1999 136 Loss of Feedwater due to False L8 Signal 2000 Page 5

a 6 m +- .

Attachment 2 ANNUAL OPERABILITY TEST SCHEDULE .

Initial Conditions Performance Test Steady State Performance Test Transient Events 005 Spurious Main Steam Isolation 008 Reactor Manual Scram 013 Recirculation Pump "A" Trip 014 Loss of Both Recirculation Pumps 045 Steam Line Rupture in the Drywell 052 Loss of Feed 053 Main Turbine Trip at 25% Power 054 Master Flow Control Transient 055 Recirculation Loop Rupture With Loss of Offsite Power 056 MSIV Closure With Stuck Open SRV, Failed Closed SULCV and Failure of HPCI/RCIC l

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