Text

Simulator Certification Submittal.
	ML18057A261
Person / Time
Site:	Palisades
Issue date:	06/11/1990
From:	Hoffman D; CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	;
Shared Package
ML18057A260	List: ML18057A259; ML18057A261;
References
	NUDOCS 9006140497
	Download: ML18057A261 (160)
	v • d • e

NRC FORM 474 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB:' NO. 3150-0138 (1-110) EXPIRES: 9-30-92 10 CFR 55.45(b),

55.4 and 55.5 ESTIMATED BURDEN PER REsPONSE TO COMPLY WITH THIS INFORMATION COLLECTION REQUEST: 120 HRS. FORWARD SIMULATION FACILITY CERTIFICATION COMMENTS REGARDING BURDEN ESTIMATE TO THE INFOR-MATION AND RECORDS MANAGEMENT BRANCH (MNBB 7714),

U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555. AND TO THE PAPERWORK REDUCTION PROJECT (315G-0138), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.

INSTRUCTIONS. This for,; is to be filed for initial certification, recertification (if required), and for any change to a simulation facility performance testing plan made* after initial submittal of such a plan. *Provide the following information, and*check the appropriate box to indicate reason'for submittal.

FACILITY -. jDOCKET NUMBER PALISADES NUCLEAR PLANT 50- 255 LICENSEE jDATE CONSUMERS POWER COMPANY ~

- .. 6/11/90 This is to certify that:

1. The above named facility licensee is using a simulation facility consisting solely of a.plant-referenced simulator that meets the requirements of 10 CFR 55.45.

2. Documentation is available for NRC review in accordance with 10 CFR 55.45(b).

3. This simulation facility meets the guidance contained in ANSI/ANS 3.5, 1985, as endorsed by NRC Regulatory Guide 1.149.

If there are any exceptions* to the certification of this item, check here [ l and describe fully on additional pages as necessary.

NAME (or other identification} AND LOCATION OF SIMULATION FACILITY MIDLAND TRAINING CENTER -

3249 E GORDONVILLE ROAD MIDLAND, MI 48640 XI SIMULATION FACl-LITY PERFORMANCE TEST ABSTRACTS ATTACHED. (For performance tests conducted in the period ending with the date of th.is certification}

DESCRIPTION OF PERFORMANCE TESTING COMPLETED (Attach additional page(s} as necessary, and identify the item description being continued}.

SEE ATTACHED: REAL TIME, STEADY STATE, NORMAL OPERATION, TRANSIENT AND MALFUNCTION TEST ABSTRACTS XI SIMULATION FACILITY PERFORMANCE TESTING SCHEDULE ATTACHED. (For the conduct of approximately 2,5% of performance tests per year for the four year period commencing with the date of this certification.} .

DESCRIPTION OF PERFORMANCE TESTING TO BE CONDUCTED. (Attach additional paga(s} as necessary, and identify t/Je item description being Continued}

~

SEE ATTACHED PERFORMANCE TEST SCHEDULE -*-

XI PERFORMANCE TESTING PLAN CHANGE. (Fo~any.modificati;n to a perf~;,ance testing plan submitt~ on a previous certification}

DESCRIPTION OF PERFORMANCE TESTING .PLAN-CHANGE (Attach additional page(s} as necessary, and identify the item description being continued}

NOT APPLICABLE XI RECERTIFICATION (Describe comJCtivuctions taken, llttJlch results of completed performance testing in accordance with 10 CFR § 55.45(b}(5JlvJ.

Attach additional page(s} as n8Ce$$8ry, snd identify th11 itllm descriprlon being continued.}

NOT APPL I CABLE - 1 .,

9006140497 900611 I PDR ADOCK 05000255 ..... PDC F' *- ~. - --

. *****--*-*- ~--

Any false statement or omiuion in this document, including attachments, may be subject to civil and criminal sanctions. I certify under penalty of perjury that the information in this document and attachments is true and correct.

~IGN~I> REPRESENTATIVE

. . l

... - 11 1- "'I' -

.jTITLE

-v~ ~-Ylv~~DATEIC.:11-'Jo In accordance with 10 CF~ 55.lS, Communications, this form shall be submitted to ti!& NRC as follows: ;

BY MAIL ADDRESSED TO: Dinictor, Office of Nuclear. Ructor Regulation BY DE1.IVERY IN PERSON One White Flint North

,; U.S. Nuclear Regulatory Cominlsslon 10 THE NRC OFFICE AT: 11665 Rockwille Pike

' Wahlngt0n, DC 20665 Rockwllle, MO

- NRC FORM 474 (1-801

Nuclear Training Center - 3249 East Gordonville Road, Midland. Ml 48640

PALISADES

. *SIMULATOR CERTIFICATION.

SUBMITTAL

CONSUMERS POWER COMPANY PALISADES SIMULATOR CERTIFICATION REfORT TABLE OF CONTENTS

ANS-3. 5-1985 RELATIONSHIP A. CERTIFICATION OF PALISADES SIMULATION FACILITY

1. NRC FORM 474

2. EXCEPTIONS TO ANSI/ANS-3.5-1985 B. GENERAL INFORMATION

1. PALISADES SIMULATOR/PLANT ..*.........*.....*.. Al.l

2. SIMULATOR DESIGN DATA ....*......*.......*..... A2.

3. CONTROLLED OPERATING PROCEDURES .*..*....*..... Al.4 C. CONTROL ROOM COMPARISON ..*.....*...*..***........ Al.2

1. PHYSICAL ARRANGEMENT, PANELS, ENVIRONMENT ..... 3.2

~ . REQUIRED SYSTEMS ..* .*.............**......*.... 3.3 D. INSTRUCTOR INTERFACE ............................. . Al.3

1. INITIAL CONDITIONS ......... *...*..**..*.....*..

2.. MALFUNCTIONS .** -*...***..****.*****.*..**....*.

3 . REMOTE FUNCTIONS *..*......*......*..*..*......

4 . ADDITIONAL FEATURES ..***..**...****...*.**.***

3.4.1 3.4.2 3.4.4 4.3 &

3.4.3 E. SIMULATOR PERFORMANCE TEST ABSTRACTS ********.***. A3. 4.4

1. REAL TIME TESTS (RTOl. ~ RT05) ...*.....**. ~ .... A3.1

- 2. STEADY STATE TEST (N007) ..*......**..**......* A3.2 4.1 B2 .1.

3. NORMAL OPERATION TESTS (NOOl - N006, NOOS) ... ; A3.2 3 .1.1

4. TRANSIENT TESTS (TOOl - TOlO) ....*..*.*..*.... *A3.3 4.2 B2.2

5. MALFUNCTION TESTS (MOOl - M221) .*.. ~ ..........

AJ.4. 3 .1. 2 F. CONFIGURATION CONTROL .****...****.**.****...**. * .* A4. 5.

1. CONFIGURATION MANAGEMENT

SUMMARY

2. SIMULATOR OPEN ITEMS REPORT (PALTRACK LISTING)

G. PERFORMANCE TESTING SCHEDULE

~*

)

page i of i

.~ .~-

SECl'ION A CERTIFICATION OF PAIJSADES

SIMULATION FACILITY

NRC FORM 474 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 315CM:l138 (1-80) EXPIRES:_ 9-3().82 10 CFR 65.46(b),

55,4 ond 65.15 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH *THIS INFORMATION COLLECTION REQUEST: 120 HRS. FORWARD SIMULATION FACILITY CERTIFICATION COMMENTS REGARDING BURDEN ESTIMATE TO THE INFOR*

MATION AND RECORDS MANAGEMENT BRANCH (MNBB 7714).

U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20566, AND TO THE PAPERWORK REDUCTION PROJECT (3160-0138), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC20503.

INSTRUCTIONS. This form is to be filed for initial certification, recertification (if required), and for any change to a simulation facility performance testing plan made after initial submittal of such a plan. Provide the following information, and check the appropriate box to indicate reason for submittal.

FACILITY IDOCKET NUMB~l1 Palisades Nuclear Plant 50- 255 LICENSEE IDATE Consumers Power Company 6/1/90 This is to certify that:

1. The above named facility licensee is using a simulation facility consisting solely of a plant-referenced simulator that meets the requirements of 10 CFR 55.45.

2. Documentation is available for NRC review in accordance with 10 CFR 55.45(b).

3. Thissimulation facility meets the guidance contained in ANSI/ANS 3.5, 1985, as endorsed by NRC Regulatory Guide 1.149.

If there are any excePtions to the certification of this item, check here [XI and describe fully on additional pages as necessary.

NAME (orotheridt111tlfication) AND LOCATION OF SIMULATION FACILITY Midland Training Center 3249 E Gordonville Rd Midl..,nd MT b..Af..b..n xi SIMULATION FACILITY PERFORMANCE TEST ABSTRACTS ATTACHED. (For performance testlconducted in the period ending with thedsteofthi1CMtiflcationJ DESCRIPTION OF PERFORMANCE TESTING COMPLETED (Attach edditional pag11(1) a nllCtl#llry, and idt111tify the item dllSICription being continued) .

See attached: Real Time, Steady State, Normal Operation, Transient and Malfunction Test Abstracts I SIMULATION FACILITY PERFORMANCE TESTING SCHEDULE ATTACHED. (For the conduct of approxim8tely 2~ of performance test1 per yeer for th* four ytltlr period commencing with the date of thi1 Cflrfificatlon.J

SCRIPTION OF PERFORMANCE TESTING TO BE CONDUCTED. (Attach lldditlonal pag11(1)., , _ r y , and idt111tify the item dllSICriptlon beingconrinuBd)

See attached Performance Test Schedule I

XI PERFORMANCE TESTING PLAN CHANGE. (For any modification to a performanct1 tnting plan rubmitted on 1 prevlotn Cflrtificatlon)

DESCRIPTION OF PERFORMANCE TESTING PLAN CHANGE (Attach lldditlonal pag11(1)., ,_ry, and ldt111tify the it1m dllS!Cription being continued)

Not applicable XI RECERTIFICATION (Ottsl:rlbeconecriv911ctionl ru1111,mach multrofcompl1ted plrformanct1 t81tlnglnaccordlnce with to CFR § 55.45(b}(5JlvJ.

Attach additional paf11(1J 11 ,_ry, Ind lc#ntlfy thll Item dflscrlptlon being continued.)

Not* applicable Ally falsa statement or omlaion In this document, Including ettachments, may be subJect to tlvll and criminal sanctions. I certify under penaltV of perjury that the Information in th~ document and lltUchments 11 true and cornet.

NATURE - AUTHORIZED REPRESENTATIVE ITITLE. IDATE In acco~ with 10 CFR § 65.5, Communications, thlt form shall be submitted to tl)e NRC u follows:

BY MAIL ADDRESSED TO: DINctor, Offlm of Nuclur Rac:lllr Regulltlon BY DELIVERY IN PERSON One Whlla Flint North U.S. N..._ R~ Coalmlalon . TO THE NRC OFFICE AT: 11111111 Rocbllle Plb WllhlallOn, DC 2GIU Rodmlll,llD NRC FORM 474 (1<<11

EXCEPTIONS TO ANSI/ANS-3.5-1985

1. Section 3.1.1 Normal Plant Evolutions This section states "The minimum evolutions that the simulator shall be capable of performing, using only operator action normal to the reference plant, are as follows:"

"(7) startup, shutd.own and power operations with less than full reactor coolant flow;"

RESPONSE

Operating the plant with less than all 4 primary coolant pumps is NOT a normal plant evolution at Palisades. The plant does not allow startup and power operations with

less than.full primary coolant flow {reference Technical Specification T.S. 3.1). If this evolution becomes*a part of our Standard Operating Procedures {SOP), a normal operations test will be developed to verify the simulator is capable of performing this SOP. This evolution was not tested.

2. Section 3.1.1 Normal Plant Evolutions This section states "The minimum evolutions that the simulator shall be capable of performing, using only operator action normal to the reference plant, are as follows:"

"{10) Operator conducted surveillance testing on safety-related equipment or systems."

RESPONSE

All of the operator conducted surveillance testing on safety related equipment or systems are not included in the simulator performance test. Only the surveillance tests that are conducted entirely in the control ro.om are included. The numerous other tests have data taken remotely, and are trained on as outlined in our Systematic Approach to Training {SAT) process *

A.2

EXCEPTIONS TO ANSI/ANS-3.5-1985

*3. section 3.l.2 Plant Malfunctions This section states "The malfunctions listed below shall be included:"

"(12) Control rod failure including stuck rods, uncoupled rods, drifting rods, rod drops, and misaligned rods;"

RESPONSE

The :Palisades simulator does not have specific malfunctions for "uncoupled rods" or "drifting rods", but our present capabilities in the area .of rod malfunctions are adequate to provide the operators with the necessary training related to rod operation (reference page D.8 for control rod malfunctions). The control panel indications and alarms, and the operating procedures utilized for our existing control rod malfunctions, would be the same as those for "uncoupled rods" and "drifting rods".

4. Section 3.2.2 Controls on Panels This section states "The controls on panels and consoles that are simulated shall be designed to duplicate the size, shape, color, and configuration of the functionally simulated hardware of the reference* plant."

nAll functionally simulated and visually simulated hardware shall replicate that in the reference plant control room."

RESPONSE

All of the meter$1, recorders., switches, annunciators, controllers, etc. that function during normal, abnormal, and emergency evolutions are included in the simulator, as verified during the performance testing. However, during a detailed picture comparison made between the simulator and plant controls, numerous (approx. 100) differences in color, shape, location or size of controls on the panels were discovered.

This comparison also revealed many (approx. 300) differences in the instruments that are simulated. All of these items and other differences (ex. bezels, tags, annunciator windows, position dots, indicating lights, hole covers, screws, etc.) have been documented and are being tracked on a computerized database .

The sign~f icance of these items on an individual basis is very minor. This is supported by the lack of licensed A. 3

EXCEPTIONS TO ANSI/ANS-3.5-1985 operator identification or complaints of physical fidelity in the 7 years of simulator usage. It is also supported by the favorable responses obtained on operator surveys during 1990 requalification training, regarding the physical fidelity of the simulator.

However, because of the numerical magnitude of differences, each of these items will be evaluated by the simulator's Technical Support Group (TSG), and recommendations will be presented to the Operations Curriculum Committee (OCC) regarding which items should be corrected. The occ will make the final disposition of these items. The TSG will correct the differences as determined by the occ. This process is proceduralized in the Midland Training Center (MTC) Local Instruction MTC 17.0, "SIMULATOR CERTIFICATION CONTROL PROGRAM".

Note: The occ is responsible for determining the curricula for the Palisades plant operator training program. Individuals from the Operations Department, Simulator Training and Technical Support Group attend occ meetings.

5. Section 3.3.2 Systems Operation or Functions Controlled

Outside of the.Control Room This section states "The systems that are operated outside the control room or that provide some input to the simulation models and are necessary to perform reference plant evolutions described in 3.1.1 (Normal

Plant Evolutions) .** shall be simuiated."

RESPONSE

This criteria was met for all of the performance testing conducted on Normal Plant Evolutions. However, because not all surveillance testing is conducted at the simulator, not all systems operated outside the control room, that are necessary to perform surveillance tests, are simulated. This exception relates directly to exception 2 *

A.4

SECl'ION B GENERAL INFORMATION

GENERAL INFORMATION PALISADES SIMULATOR AND PLANT

1) owner: Sheridan Leasing Corporation One American Plaza Evanston, Illinois 60201 Operator: Consumers Power Company 212 w. Michigan Avenue Jackson, Michigan 49201 Manufacturer:*The Singer Company Link Division, Silver Spring Operation 11800 Tech Road Montgomery Industrial Park Silver Spring, Maryland 20904

2) Reference Plant: Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, Michigan

49043 Type: Circulation - Pressurized Water Reactor (PWR)

NSSS - Combustion Engineering (CE)

Turbine - Westinghouse (WE)

Rating: Net Demonstrated capacity - 777 MW (3-18-87)

Turbine Nameplate * * - 811. 7 MW

3) Date. Available for Training: February 24, 1983

4) Type of Report: Initial

B.l

GENERAL INFORMATION SIMULATOR DESIGN DATA The Palisades Simulator was built approximately 10 years after the Palisades Plant was operational. Actual plant information was utilized in the design and development of the Palisades simulator.

Updates to the simulator since delivery have also been based on actual plant information whenever available. The simulator is on distribution for selected plant information and any plant documents/information used in a simulator modification are listed in the simulator's Final Design Specification (FDS). This process is proceduralized in the Midland Training Center's (MTC) Local Instructions MTC 6.0

and MTC 9.0.

-* B.2

_J_. GENERAL INFORMATION CONTROLLED OPERATING PROCEDURES The operating procedures utilized at the Palisades Simulator are a "controlled copy" of the operatii:ig procedures utilized at the Palisades Plant. Also, the same document control procedure governing the issuance of the operating procedures is used (PALISADES NUCLEAR PLANT ADMINISTRATIVE PROCEDURE 10.43, "DOCUMENT DISTRIBUTION AND CONTROL") to ensure the procedures .at the simulator are updated at the same time as those at the plant.

-*

B. 3

SECl'ION C CONTROL ROOM

COMPARISON

PALISADES SIMULATOR vs PALISADES CONTROL ROOM PANEL.ARRANGEMENT AND ENVIRONMENT The following two diagrams of the Palisades Control Room and the Palisades Simulator.Floor Plans are intended to show differences in layout and are not necessarily to scale. The dimensions shown are accurate within one inch.

DEGREE OF PANEL SIMULATION:

LAYOUT: The simulated control room panels and their layout give the appearance of being in the actual plant control room. The major differences are the rear of panels C12 and C13 are not simulated, C47, C47A and C115 are not simulated and the width of panels C04 and COG is narrower. These deviations have minimal impact on training and the panels simulated do provide the controls, instrumentation, alarms and other man-machine interfaces necessary to conduct the.Normal Plant Evolutions and respond to the Plant Malfunctions.

CONTROL ROOM ENVIRONMENT:

FLOORING: The flooring at the simulator is carpet of the same color as

that at the Palisades plant

CEILING: The ceiling in the simulator is significantly higher to accommodate the overhead viewing gallery.

OBSTRUCTIONS: The simulator has the Liebert air conditioner that is an additional obstruction behind panel Cl3. The simulator is lacking cabinets behind C07, C27, C106, C126 and C125. The operators furniture and its location is similar to that in the actual plant. The face-front area of the control panels conta~n the same obstructions.

LIGHTING: The simulator lighting is brighter than that of the plant control room. However, all of the control panel instruments are easily seen with no degrading shadows _or glare.

NOISE: Simulated noise is provided in the simulator environment. The nuclear startup channels are provided with an audio count rate, the turbine generator noise is simulated, the atmospheric steam dump valves and the secondary code relief valve noises are simulated.

COMMUNICATION: The operator- communicates with th*e s*ame *communication* --- --- ------

.systems at the simulator as at the plant; These include telephone (with identical telephone numbers), radios and direct. Instructors don hard hats with labeled job titles to represent desired individuals for direct communications *

C.1

PALISADES

SIMULATOR FLOOR PLAN Liebert OJtside 02/23/90 51" abino i

."A.IC .

105" 1.

C12 .

Computer . );

Room ~

. .\ C02 C06 47'

. , desk I~ lc!I desk I C07 lsi C27

,~@

I_'°_

M1sc Rooms

~

I 62"-

table CllA 67" desk Main 51-1/2" 60" '* 1Entrance L::====::::::::boo:k:s:~:w:e::::========::!!!!!!~====!::::==============::::!Jl

~.,...------------- 46' 6 u - - - - - - - - - - 1 *

C.2

PALISADES

CONTROL ROOM FLOOR PLAN 02/23/90 35*

I

). .. **

.. . .. *~ i

i

..** C12

..***** C04!

- - ....... 42" 34" !

- - -**ji 36" f :

C02 C06i j I! I I

i i 46'3" I desk I1lc!I desk C07

Main Entrance desk wall case CllA -

C.3

~

REQUIRED J

!!I SYSTEMS .'

r f.

0 . .J

REQUIRED SYSTEMS ~

Based on Simulator Training Scenario Listing.

Simulator Documentation used:

1) simulator Module Final Design Specification (FDS),

2) Simulator FORTRAN code, and.

3) Physical inspection of the simulator facility during evaluation.

PLANT SYSTEMS SIMULATED REQUIRED NOTES

===================== ========= ======== ==============

1) Primary Coolant system Full Yes 2A) Chemical and Volume Sys Partial Yes Boric Acid Heat Charging and Letdown; Trace not simulated; Concentrated Boric Acid Heat Trace controls not in Control Room .

. . . . . . . . . . . . .. . . . . . . . . . . .. . ~ ................................... ' ...........

28) Chemical and Volume Partial. Yes Manual valves and Control Sys - Purif ica- chemical additive tion and Chem Injection pumps not simulated.

3) Safety Injection and Full Yes Shutdown Cooling System

4) Containment Spray and Full Yes Iodine Removal System

5) Containment Air Cooling Partial Yes Hydrogen recombining and Hydrogen Recombining controls not in Control Room (C.R.).

6) Reactor .

Control System .

Full Yes

7) Main Steam System Partial Yes S/G blowdown recirc.

incomplete. S/G Blow down pump controls not in Control Room.

8) Main Turbine and Genera- Partial Yes Generator Bus dis-ting Systems connect links not modeled. To be added after pending plant modification.

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

10) Extraction and Heater Fuli Yes Drain system

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

C.4

REQUIRED SYSTEMS LIST PLANT SYSTEMS SIMULATED REQUIRED . .

NOTES .

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

11} Condensate System Full Yes

**----------------------------------------------------~-----------

12} Feedwater System Full Yes 13} Air Ejector, Gland Steam Full Yes condenser and Condenser Vacuum Pump . - .

14} Circulating Water and Partial Yes Warm water recirc.

Chlorination Systems not modeled. Contrls not in Control Room.

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

15) Service Water System . Partial Yes Manual throttle of service water from ccw Hx not modeled.

16) Component Cooling Water Partial Yes dPC 0909 not modeled 17A) Clean Radioactive waste Partial No Only Engineering Safeguards Rm sumps 17B) Dirty Radioactive Waste are model.ed; other pumps, filters and receivers assumed fully operable.

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

18A) Radioactive Waste-Gas No No All gaseous & solid

lSB) Radioactive Waste Sys waste facilities are 18C} Radioactive Waste-solid assumed fully 180} Spent_ Resin Handling operable *

19) Instrument Air System .Partial *Yes No malfunctions or remote functions are provided for Inst.

Air Driers **. not controled from C.R.;

I/O overrides allow Instr. to simulate.

symptoms of failures

20) High-Pressure Control Partial Yes Compressors assumed Air system for Air- always in AUTO; Opera ted Valves Failure of 1 or more on loss of A-C power not modeled.

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

C.5

- PLANT SYSTEMS REQUIRED SYSTEMS

==========================~

21) Fire Protection Sys SIMUIATED

=

Partial

~

.REQUIRED

==

Yes NOTES

========

Interfaces with SW provided; no o.ther fire loads modeled.

Alarm panel in C.R.

not simulated.

22) Emergency Diesel Partial Yes Infinite Fuel Supply Generator assumed.

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

23) Plant Heating system No No

24) Ventilation and A~r Partial Yes Only evolutions con-Conditioning System trolled from C.R.are modeled; balance of system continuously operating.

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

25) Domestic Water System No No

26) Makeup System Partial Yes Storage tank fill valves simulated.

Sources of makeup continuously operable

27) Fuel Pool System Partial Yes C.R. controls simu-lated; Spent Fuel pool modeled as constant temp heat load/sink~

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

28) Fuel Handling system No No.

29) Shield Cooling System Full Yes

30) Station Power Partial Yes Bkrs/loads not cont-rolled from C.R.;

Assume normal unless malfunction imposed; Removal of main Gen.

Bus-links not simu-lated; ,Use of emerg-ency reserve trans-formers not simulated

31) Plant Liqnting and Partial Yes D.C. lighting not -

communications simulated; C.R. A-C lights on 1 circuit.

C.6

REQUIRED SYSTEMS LIST PLANT SYSTEMS SIMULATED REQUIRED NOTES

_::;:::_===================== ========= ======== ===============

32) 345 KV Switchyard Partial Yes Main Gen. Bus.links not simulated; not all potential fail-ures modeled.

33) Compressed Gas System Partial Yes Gas supplies assumed continuously aval.

34) Data Logger System Partial Yes Not all console.com-mands are simulated.

35) Neutron Monitoring Sys Partial Yes Provision to manual-ly read incore NI's not simulated.

36) Reactor Protective Sys Full Yes

37) Process Liquid Monitor Partial Yes Only representative System samples of C.R. in-

. . . . . . . . . . . . . . . . . . . . . . . . .. . . . struments are simul-ated; simulated ins-

38) Gaseous Process Monitor- truments representa-ing System tive of various mon-itors are consolida-ted on single panels

. 39) Area Radiation Monitor- in simulator; not ing System all monitors with control/alarm funct-ions are simulated.

40) Annunciators Partial Yes All C.R. panel alarm windows simulated, but not all are functional, based on training value.

Functional windows can be tripped/bloc-ked via malfunctions or override *

C.7

SEC'I'ION D INSTRUCTOR INTERFACE

INSTRUCTOR INTERFAcE The following indices of Initial Conditions, Malfunctions*

and Remote Functions represent the interfaces that were available at the time *the performance test was initially conducted during the last quarter of 1988 and

the first quarter of 1989.. Changes to these interfaces continue to occur as conditions warrant.

D.1

INITIAL CONDITIONS

PALISADES SIMULATOR INDEX O~ INITIAL CONDITIONS BORON CONCEN TIME IN

IC NUMBER PLANT OPERATING CONDITIONS IN PPM CORE LIFE ICOl END OF REFUELING OUTAGE, PRESSURIZER DRAINED AND 1720 BOL VENTED TO CONTAINMENT ATMOSPHERE. READY TO COM-MENCE PLANT HEATUP.

IC02 PLANT HEATUP IN PROGRESS FROM COLD SHUTDOWN. 1759 BOL PRESSURIZER SOLID, SHUTDOWN COOLING IN SERVICE.

NO PCPs RUNNING.

IC03 CONTINUATION OF PLANT HEATUP. PRESSURIZER SOLID 1772 BOL AND READY TO DRAW BUBBLE. 3 PCPs IN SERVICE. "A" HPSI PUMP IN SERVICE; AFW FLOW CONTROLLERS AT 165 GPM.

IC04 PRIMARY AT NOP/NOT. SECONDARY COLD WITH MSIVs 1185 BOL AND BYPASSES SHUT. READY TO PERFORM REACTOR AND PLANT STARTUP.

Ico5 PLANT AT NOP/NOT. PCS AT CRITICAL BORON CONCEN- 1089 SOL TRATION. SHUTDOWN AND PART LENGTH RODS WITHDRAWN *.

MSIV BYPASS VALVES THROTTLED; VACUUM ESTABLISHED.

IC06 REACTOR AT POWER IN PREPARATION FOR TURBINE ROLL. 1074* . BOL TURBINE METAL TEMPERATURE> 300 DEG*F. "A" MFWP

IGO?

IC08 IN MANUAL, FRV BYPASSES.IN MANUAL

MAIN TURBINE-GENERATOR ON LINE.

ESCALATION.

READY FOR POWER PLANT AT 41% POWER, EQUILIBRIUM XENON. READY FOR 2ND MFW PUMP START (CHEMISTRY HOLD COMPLETE).

1073 861 BOL BOL IC09 PLANT AT 73% POWER, EQUILIBRIUM XENON. 792 BOL IClO PLANT AT FULL POWER, EQUILIBRIUM XENON. 727 BOL ICll. READY FOR REACTOR STARTUP. SECONDARY HOT WITH MSIV 799 MOL BYPASSES THROTTLED. TURBINE COLO, ~ENON HAS DE-CAYED TO NEGLIGIBLE VALUE. ON AUXILIARY FEEDWATER.

IC12 NOT USED IC13 NOT USErr .

IC14 PLANT STABLE AT 30% POWER FOLLOWING STARTUP FROM 660 MOL XENON FREE CONDITION. HAVE HELD POWER AT 30% FOR.

2 HOURS WHILE CLEANING UP SECONDARY CHEMISTRY.

XENON CONCENTRATION -1.3% dK/K AND .INCREASING.

D.2

PALISADES SIMULATOR INDEX O~ INITIAL CONDITIONS

IC NUMBER IC15 PI.ANT OPERATING CONDITIONS PLANT STABLE AT FULL POWER FOLLOWING RAPID POWER EXCALATION FROM APPROXIMATELY 20%. XENON CONCEN-BORON CONCEN IN PPM 592 TIME IN CORE LIFE MOL .

TRATION 1.23% dK/K AND DECREASING. (IT WILL DE~

CREASE TO@ 1.14% dK/K BEFORE BUILDING BACK IN).

IC16 FULL POWER, EQUILIBRIUM XENON CONDITIONS. . 442 MOL IC17 READY FOR REACTOR STARTUP, XENON FREE CONDITION. 451 EOL Ms'Ivs CLOSED. -BYPASSES THROTTLED.

IC18 PLANT AT 91% POWER FOLLOWING NORMAL CYCLE 7 POWER 193 EOL INCREASE FROM XENON FREE SHUTDOWN. XENON C:ONCEN-TRATION 2.30% dK/K~

IC19 READY TO GO WITH RAS - SI ACTIVE (FROM LARGE BREAK 1669 EOL LOCA), SIRWT LEVEL 28%, CONTAINMENT SUMP LEVEL 94%.

IC20 PLANT STABLE AT FULL POWER, :XENON EQUILIBRIUM CON- 99 EOL DITION.

D.3

MALFUNCTIONS

PALISADES SIMULATOR INDEX O~ MALJ'OHCTIONS

(G) =GENERIC - select the option [(A),(B),etc] or [1,2,etc]

(V) = VARIABLE - select the severity (0-100%)

- the severity defaults to 100% if not selected (GV) = GENERIC and VARIABLE BLANK = No selectable options for this malfunction

0.4

PALISADES SIMULATOR INDEX OP MAI3UNCTIONS ANNUNCIATORS 1AHl. SYSTEM ANOl(G) Kll-C13 AUXILIARY SYSTEMS (1-72]

AN02(G) Kl3-C13 SAFEGUARD SAFTY INJECT & ISOL (1-78]

AN03(G) K21-C13 SIS SEQUENCE DISPLAY - LEFT (1-20]

AN04(G) K22-C13 SIS SEQUENCE DISPLAY - RIGHT (1-20)

AN05(G) K07-C12 PRIMARY SYS VOLUMN LVL PRESSURE [1-72)

AN06(G) K09-C12 PRIM COOL PMP ST GEN & ROD DR [l-72)

ANO? (G) KOl-Cll TURBINE CONDENSER & FEEDWATER [1-72]

ANOS(G) K03-Cll GENERATOR [1-36]

AN09(G) K05-Cll ELECTRICAL AUX & DIESEL GEN [1-60]

ANlO(G) C06A RPS CHANNEL A [1-8)

ANll(G) C06B RPS CHANNEL B [l-8]

AN12 (G) C06C RPS CHANNEL C [l-8]

AN13(G) C06D RPS CHANNEL D [1-8]

AN14(G) C106 COOLING TOWER MASTER SUPERVISORY [l-40]

AN15(G) Cl26 CT PPS, OIL PPS AND IODINE REMOVAL [1-35]

AN16(G) Cl25 H&V [1-12] .

AN17(G) LOSS OF POWER [(A)KOl (B)K02 (C)K03 (D)K05 (E)C06A (F)C06B (G)C06C (H)C06D {I)K07 (J)K09 (K)Kll (L)K13 (M)Cl06 (N)C125 (O)C126]

COMPONENT COOLING ~ SYSTEM CCOl LOS$ CC WATER TO ALL PRIMARY COOLANT PUMPS CC02(G) LOSS CC WATER PUMP P52 [(A)A (B)B (C)C]

CC03 (V) LEAKAGE FROM CC WATER SYSTEM [0-100%]

CONTAINMENT CHOl (G)

CH02(G)

CH03(G)

~ SYSTEM CONTAIN SPRAY MANUAL INITIATION SIG FAIL CHANNEL [(A)LEFT (B)RIGHT]

FALSE CONTAIN SPRAY INITIATION CHANNEL [(A)LEFT (B)RIGHT]

CONTAIN AIR COOL FAN FAIL [(A)V-1 (B)V-2 (C)V-3 (D)V-4] [(A)A (B)B]

CH04 . DELETED .

CH05(G) AUTO INITIATION FAILURE OF CONTAIN SPRAY CHANNEL [(A)LEFT (B)RIGHT]

CH06(G) CONTROL ROOM HVAC FAN FAILURE [(A)TRAIN A (B)TRAIN B]

CHO? CONTAINMENT H2 (100% = 20% H2)

CHEMICAL k VOLUME COHTROL ~ SYSTEM CVOl (V) LETDOWN LINE LEAK INSIDE CONTAINMENT [0-100%]

CV02(V) LETDOWN LINE LEAK INSIDE AUX BUILDING [0-100%]

CV03(G) CHARGING PUMP TRIP P-55 [(A)A (B)B (C)C]

CV04(V) CHARGING PUMP P-55A FLUID DRIVE FAILURE [0-100%]

CV05 LOSS LETDOWN PRES CONTROL HIGH CV06 LOSS LETDOWN PRES CONTROL LOW CV07(V) LETDOWN HEAT EXCHAGER TUBE RUPTURE [0-100%]

cvo8

LOSS OF CC WATER TO LETDOWN HEAT EXCHANGER

. CV09 PURIFICATION FILTER F-54A HIGH DP CVlO PRIMARY COOL SYS INADVERTENT DILUTION CVll PRIMARY COOL SYS INADVERTENT BORATION CV12 MAKEUP CONTROL FAILURE IN ALL MODES EXCEPT MANUAL

0.5

PALISADES SIMULATOR INDEX or MALJ'UNCTIONB CHEMICAL k VOLUME CONTROL ~ SYSTEM (continued)

CV13(V)

CV14 CV15 (V)

CV16(V)

VOLUME CONTROL TANK LEVEL CONTROL FAILURE [0-100%]

DELETED ACCIDENTAL RELEASE OF RADIOACTIVE LIQUID [0-100%]

LEAK ON CHARGING LINE INSIDE CONTAINMENT (0-100%]

COOLING *WATER i.Qlil SYSTEM CWOl(G) LOSS OF COOLING TOWER PUMP P39 [(A)A (B)B]

CW02(G) LOSS OF COOLING TOWER FAN 30 [(A)A (B)B] [(A)l (B)2 (C)i7 (D)18]

ELECTRICAL DISTRIBUTION l.filll. SYSTEM EDOl LOSS OF ALL OFF SITE POWER ED02 LOSS OF R BUS ED03 (G) LOSS OF 4160V BUS 1-((A)A (B)B (C)F (D)G]

ED04 (G) LOSS OF 2400V BUS 1-((A)C (B)D (C)E]

EDOS(G) LOSS OF 480V BUS [(A)ll (B)12 (C)l3 (D)l4 (E)19 (F)20 (G)71 (H)72 (I)13 (J)74 (K)75 (L)76 (M)77 (N)78 (0)90 (P)91 (Q)200]

ED06(G) LOSS OF MOTOR CONTROL CENTER [(A) 1 (B) 2 (C) 7 (D) 8 * (E) 21 & 23 (F)22 & 24 (G)25 (H)26 (I)79 (J)80 (K)Sl (L)82]

ED07 LOSS OF INSTRUMENT A-C BUS ED08 (G) LOSS OF PREFERRED A-C BUS [(A) 1 °CB) 2 (C) 3 (D)4]

ED09(G) LOSS OF 240V AC BUS [(A) 1 (B) 2]

EDlO (G) LOSS OF 125V DC BUS D-[ (A) 10 (B) 11 (C) 20 (D) 21 (E)54 (F) 55 (G) 201

'(H) 205 (I) 2li]

EDll(G) DIESEL GEN BREAKER FAILURE 1-((A)l (B)2]

ED12(G) DIESEL GEN FAILURE TO AUTO START 1-((A)l (B)2]

ED13 (G) SI AUTO INITIATION SIGNAL FAILURE CHANNEL [(A)LEFT (B)RIGHT]

ED14(G) DIESEL GEN FAILURE TO START.1-((A)l (B)2]

ELECTRICAL GENERATION ~ SYSTEM EGOl MAIN GENERATOR TRIP EG02 CHANGED TO TC13 EG03 LOSS OF MAIN GENERATOR EXCITER

.EG04 MAIN GEN AUTOMATIC VOLTAGE REGULATOR FAILURE EGOS. ABNORMAL GENERATOR HYDROGEN PRESSURE FEEPPUMP TURBINE lFl1 SYSTEM FTOl (G) "STEAM GEN FW PUMP TRIP P-1 [(~)A (B) BJ FEEDWhTER ..LDil. SYSTEM FWOl(V) LOSS OF CONDENSER VACUUM [0-1QO%]

FW02(V) HOTWELL LEVEL CONTROL FAILURE (0-100%]

FW03(V) CONDENSER TUBE LEAK [0-100%]

D.6

PALISADES SIMULATQR INPBX OP MALPPNCTIONS FEEDWATER l.flil SYSTEM (continued)

FW04(G) CONDENSATE PUMP TRIP P-2 [(~)A (B)B]

FWOS CONDENSATE FILTER DEMINERALIZER HIGH DIFF PRES FW06(GV) STEAM GEN FEED REGULATING VALVE FAIL CV-[(A)0701 (B)0703] [0-100%]

FW07(G) LOSS OF HEATER DRAIN PUMP P-10 [(A)A (B)B]

FWOB(GV) STARTUP STEAM GEN LEVL CONTROLLER FAIL LC-[(A)0734 (B)0735] [0-100%]

FW09(V) FW LINE NO. 1 RUPTURE INSIDE CONTAINMENT [0-100%]

FWlO(V) FW LINE NO. 2 RUPTURE OUTSIDE CONTAINMENT [0-100%]

FWll(V) FW LINE RUPTURE AT FW PUMP SUCTION CROSSOVER PIPE [0""'100%]

FW12(GV) HIGH PRESS FW HEATER TUBE FAILURE E-6 [(A)A (B)B] [0-100%]

FW13(GV) . LOW PRESS FW HEATER TUBE FAILURE E-1 [(A)A (B)B] (0-100%]

FW14(G) LOSS OF AFW PUMP SUCTION SUPPLY FROM.T-2 FW15(V) REDUCED AUXILIARY FEEDWATER FLOW TO E-50A (0-100%]

FW16(G) FAILURE OF AFW PUMP P-8 [(A)A (B)B (C)C]

FW17(V) AFW PUMP P-BA BEARING FAILURE [0-100%]

FW18(G) AFW TO STEAM GEN SUPPLY CONTROL VALVE INADVERTENT COLOSURE CV-[(A)737A (B)736A (C)749 (D)727]

FW19(GV) AFW PUMP DISCHARGE LINE RUPTURE [(A/B)A (C)B] [0-100%]

FW20 DELETED INSTRUMENT AIR 1.IAl SYSTEM IAOl(V) LOSS OF INSTRUMENT AIR [0-100%]

IA02 LOSS OF NITROGEN BACKUP STATION 1 AUX FW IA03 LOSS OF NITROGEN BACKUP STATION 2 FW & MS

MAIN STEAM lMfil. SYSTEM MSOl(G) STEAM GEN ISOLATION VALVE FAILS TO SHUT CV-[(A)0510 (B)0501]

MS02(G) STEAM GEN ISOLATION VALVE INADVERTENT CLOSURE CV-[(A)0510 (B)0501]

MS03(GV) MAIN STEAMLINE RUPTURE INSIDE CONTAINMENT [(A)l (B)2] (0-100%]

MS04 MAIN STEAMLINE RUPTURE OUTSIDE OF CONTAINMENT MSOS(V) STEAMLINE LEAK OUTSIDE OF CONTAINMENT [0-100%]

MS06(GV) MAIN STEAM RE~I~F VALVE LEAKAGE RV-[(A)0706 (B)0711] [0-100%]

MS07 ATMOSPHERIC DUMP VALVE CV-0781 FAILED OPEN MSOB ATMOSPHERIC DUMP VALVES FAILED CLOSED MS09 TURBINE BYPASS VALVE CONTROLLER FAILURE MSlO* ATMOSPHERIC DUMP ANO TURBINE. BYPASS VALVE INADVERTENTLY OPEN MSll TURBINE BYPASS VALVE INADVERTENT OPENING MS12 CHANGED TO RX15 MS13 GLAND SEAL SUPPLY REGULATOR CV-0514 FAILURE MS14 MAIN TURBINE GLAND SEAL HIGH PRESSURE PROCESS COMPUTER ~ SYSTEM PCOl(G) COMPUTER FAILURE [(A)PRIMARY VARIAN REACTOR DATA LOGGER (B)FW PURITY DATA LOGGER (C)CRITICAL FUNCTION MONITOR]

PC02(G) THERMAL MARGIN MONITOR POWER FAIL ON CHANNEL [(A)A (B)B (C)C (D)D]

D.7

PALISADES SIMVLATOR INDEX OJI MALl'UlfCTIONS

PRIMARY COOLANT RCOl RC02 RC03(V)

RC04(V)

RC05

~ SYSTEM HOT LEG RUPTURE COLD LEG RUPTURE SMALL UNISOLATABLE PCS COOLANT LEAK [O-lOOGPM]

UNISOLATABLE PRIMARY GOOLANT SYSTEM LEAK IN CONTAINMENT [O~lOOOGPM]

CORE BARREL FAIL RC06(G) PRIMARY COOLANT PUMP TRIP P-50 [(~)A (B)B (C)C (D)D]

RC07 PRIMARY COOLANT PUMP P-50A SHAFT BREAK RCOS PRIMARY COOLANT PUMP P-50B SEIZED ROTOR RC09(G) PRIMARY COOLANT PUMP LOSS OF LUBE OIL P-50 [(A)A (B)B (C)C (D)D]

RClO PRIMARY COOLANT PUMP P-50B AC & DC HIGH PRESSURE LIFT PUMPS FAILURE RCll P~IMARY COOLANT PUMP P-50A HIGH LUBE OIL LEVEL DUE TO CCS LEAKAGE RC12 (G) PRIMARY COOLANT PUMP LOWER MECH SEAL FAIL P-50 [(A)A (B)B (C)C (D)D]

RC13(G) PRIMARY COOLANT PUMP MIDDL MECH SEAL FAIL P-50 [(A)A (B)B (C)C (D)D]

RC14(G) PRIMARY COOLANT PUMP UPPER MECH SEAL FAIL P-50 [(A)A (B)B (C)C (D)D]

RC15(G) PRIMARY COOLANT PUMP VAPOR SEAL FAIL P-50 [(A)A (B)B (C)C (D)D]

RC16(G) HIGH VIBRATION ON PRIMARY COOLANT PUMP P-50 ((A)A (B)B (C)C (D)D]

RC17(V) PRESSURIZER SPRAY VALVE FAILURE CV-1057 (0-100%)

RC18(V) PRESSURIZER SPRAY VALVE FAILURE CV-1059 (0-100%]

RC19(V) PRESSURIZER PWR OPERATED RELIEF VALVE LEAK PRV-1042 (0-100%)

RC20 (V) PRESSURIZER PWR OPERATED RELIEF VALVE LEAK PRV-1043 (0-100%]

RC2l(V) PRESSURIZER SAFETY RELIEF VALVE LEAKAGE RV-1040 (0-100%]

RC22 (V) FAILED.FUEL ELEMENT (0-100%]

CONTROL RODS .!.Bill. SYSTEM

RDOl

. RD02 RD03 RD04(G)

FAILURE OF AUTOMATIC WITHDRAWL PROHIBIT (AWP) TO INITIATE FAILURE OF REGULATOR GROUP LIMIT SWITCHES TO BLOCK SHUTDOWN GROUP ROD INSERTION FAILURE OF SHUTDOWN GROUP LIMIT SWITCHES TO BLOCK REGULATING GROUP ROD WITHDRAWL UNCONTROLED GROUP WITHDRAWL [(A) SHUTDOWN GROUP A (B) SHUTDOWN GROUP B (C)REGULATING GROUP 1 (D)REGULATING GROUP 2 (E)REGULATING GROUP 3 (F)REGULATING GROUP 4 (G)POWER SHAPING GROUP FAILURE RD05(G) UNCONTROLED GROUP.INSERTION [(A)SHUTDOWN GROUP A (B)SHUTDOWN GROUP B (C)REGULATING GROUP 1 (D)REGULATING GROUP 2 (E)REGULATING GROUP 3 (F)REGULATING GROUP 4 (G)POWER SHAPING GROUP FAILURE RD06(G) UNCONTROLLED WITHDRAWL OF AN INDIVIDUAL CROM (1-45)

RD07 (G) UNCONTROLLED INSERTION OF AN INDIVIDUAL CROM (1-45]

ROOS CONTROL RODS FAIL TO MOVE ON DEMAND IN ANY MANUAL MODE RD09(G) CONTROL ROD MAI.OPERATION (SINGLE CROM CONTROLS) (1-45]

. RDlO (G) STUCK CONTROL ROD (UNTRIPABLE) (1-45] .

RDll(G) FAILURE OF CONTROL ROD DRIVE MECHANISM TO MOVE ON DEMAND [1-45)

RD12 (G) DROPPED CO~OL Rao* (1.,..45]

RD13 (G) - ROD (PIP) POSITION INDICATION FAILURE (l-45]

RD14 (G) EJECTED ROD ACCIDENT (1-45]

D.8

PALISADES SIMULATOR INDBX 0., !(ALJ'UNCTIOHS RADIATION MONITORING iBHl. SYSTEM

RMOl RM02 RM03 RM04(V)

RM05 (G) .

RM06(G)

CHANGED TO RC22 DELETED CHANGED TO CV15 ACCIDENTAL RELEASE OF GASEOUS WASTE HI CONTAIN RADIATION CHANNEL A RE-[(A)l805 (B)l806 (C)l807 (D)l808]

AREA MONITOR HI RADIATION:

(A)RIA-2300 EAST ENG. SAFEGUARDS RM (M)RIA-2312 LUNCH ROOM (B) RIA-2301. RADWASTE SER. CORRIDOR (N) RIA-2313 SPENT FUEL POOL RM (C)RIA-2302 RADWASTE CONTROL AREA (O)RIA-2314 AIR ROOM (D)RIA-2303 2.4KV SW. GR. RM (P)RIA-2315 AIR LOCK (E)RIA-2304 CONTROLLED LAB CORRIDOR (Q)RIA-2316 FUEL HANDLING AREA (F)RIA-2305 ACCESS CONTROL STATION * (R)RIA-1805* CONTAIN BLDG EL 590 (G)RIA-2306 ELEVATOR EL. 607 (S)RIA-1806 CONTAIN BLDG EL 590 (H)RIA-2307 CONTAIN PURGE, UNIT RM (T)RIA-1807 CONTAIN BLDG EL 590 (I)RIA-2308 RADWASTE DEMIN. RM (U)RIA-1808 CONTAIN BLDG EL 590 (J)RIA-2309 CORRIDOR - EL. 625 (V)RIA-5711 RADWASTE ADD VENT (K)RIA-2310 MAIN CONTROL RM ENTRANCE (W)RIA-5712 FUEL HANDLING AREA (L)RIA*2311 TURBINE OPER. FLOOR RADWASTE VENTILATION MONITOR RM07(GV) PROCESS MONITOR HIGH RADIATION [(A)-(T) see below] (O-IOO%]

RM08(G) PROCESS MONITOR LOW RADIATION [(A)-(R) see below]

(A)RIA-0631 CONDENSER OFF GAS (K)RIA-1049 RADWASTE DISCHARGE (B)RIA-1113 WASTE GAS (L)RIA-1323 CIRCULATING WATER (C)RIA-2318 STACK GAS (M)RIA-2320 BLOWDOWN TANK VENT (D)RIA-2319 STACK GAS* (N)RIA~5211 TURBINE BLDG SUMP (E)RIA-1817 CONTAIN BLDG GAS (O)RIA-0202A eves (F)RIA-1809 RADWASTE VENTILATION . (P)RIA-0202B eves .

(G)RIA-0915 ENG SAFEGUARDS RM VENT (Q)RIA-2323 MAIN STEAM (H)RIA-0707 STEAM GEN SLOWDOWN (R)RIA-2324 MAIN STEAM (I)RIA-0833 SER WATER DISCHARGE (S)RIA-2321 CONTAINMENT GAMMA (J)RIA-0915 COMPONT COOLING WATER (T)RIA-2322 CONTAINMENT GAMMA REACTOR PROTECTION l.Bfl SYSTEM RPOl(G) NOISY STARTUP RANGE CHANNEL [(A) l (B) 2]

RP02 (G) STARTUP RANGE HI VOLTAGE FAILURE CHANNEL [(A)l (B)2]

RP03(G) STARTUP RANGE PRE-AMP MODULE FAILURE CHANNEL [(A)l (B)2]

RP04 (G) STARTUP RANGE HI RATE OF CHANGE OUTPUT CHANNEL [(A) l (B) 2]

RP05(G) STARTUP RANGE OUTPUT LEVEL FAILS UPSCALE CHANNEL [(A) 1 (B) i]

RP06(G) LOGARITHMIC HI VOLTAGE POWER SUPPLY FAILURE CHANNEL [(A)3 (B)4]

RP07(G) LOGARITHMIC LOW (RELATIVE) OUTPUT SIGNAL CHANNEL [(A)3 (B)4]

RP08 (G) LOGARITHMIC HI RATE OF CHANGE OUTPUT CHANNEL [(A)3 (B)4]

RP09(G) LOGARITHMIC OUTPUT LEVEL FAILS UPSCALE CHANNEL [(A)3 (B)4]

RPlO(G) LOGARITHMIC LOWER LIMIT CUT-OFF FAILURE CHANNEL [(A)3 (B)4]

RPll(G) POWER RANGE SAFETY DETECTOR HIGH.VOLTAGE POWER SUPPLY FAILURE

CHANNEL [(A)5 (B)-6 (C)7 (D)8]

RP12 (G) POWER RANGE SAFETY SUBCHANNEL "A" FAILURE DOWNSCALE CHANNEL [(A)5 (B)6 (C)7 (D)8]

RP13(G) POWER RANGE SAFETY SUBCHANNEL "B" FAILURE DOWNSCALE: CHANNEL [(A)5 (B) 6 (C) 7 (D) 8]

RP14 (G) POWER RANGE SAFETY SUMMED POWER SIGNAL FAILS UPSCALE CHANNEL [(A)5 (B)6 (C)7 .(D)8]

D.9

PALISADES SIMULATOR INDEX OJ' MALJ'UNCTIONS REACTOR PROTECTION 1Rf1. SYSTEM (continued)

RP15. POWER RANGE SAFETY CHANNEL COMPARATOR AVERAGER OUTPUT FAILS LOW RP16 POWER RANGE SAFETY CHANNEL COMPARATOR AVERAGER OUTPUT FAILS HIGH RP17 (G) POWER RANGE CONTROL OUTPUT FAILS HIGH CHANNEL [(A)9 (B)lO]

RP18 (G) POWER RANGE CONTROL OUTPUT FAILS LOW CHANNEL [(A)9 (B)lO]

RP19 FAILURE OF AUTOMATIC REACTOR TRIP RP20 FAILURE OF MANqAL

REACTOR TRIP RP2l(G) LOSS OF REACTOR PROTECTION SYSTEM CHANNEL [(A)l (B)2 (C)3 (D)4]

RP22(GV) HOT LEG #1 RTD FAILURE TE-0122H-[(A)A (B)B (C)C (D)D] [0-100%]

RP23(GV) HOT LEG #2 RTD FAILURE TE-0122H-[(A)A (B)B (C)C (D)D] [0-100%]

RP24(GV) COLD LEG #1 RTD FAILURE TE-0112C-((A)A (B)B (C)C (D)D] [0-100%]

RP25(GV) *COLD LEG #2 RTD FAILURE TE-0112C-((A)A (B)B (C)C (D)D] [0-100%]

RP26(GV) P~SSURIZER PRESSURE SAFETY CHANNEL TRANSMITTER FAILS HIGH PT-0102-( (A)A (B)B (C)C (D)D] [0-100%]

RP27(GV) STEAM GENERATOR. #1 PROTECTION CHANNEL LEVEL TRANSMITTER FAILURE LT-0751-((A)A (B)B (C)C (D)D] [O-l00%]

RP28(GV) STEAM GENERATOR #2 PROTECTION CHANNEL LEVEL TRANSMITTER FAILURE LT-0752-( (A)A (B)B (C)C (D)D] [0-100%]

RP29(G) STEAM GENERATOR PRESSURE TRANSMITTER OUTPUT FAILURE HIGH

[(A)PT-0751 (B)PT-0752] [(A)A (B)B (C)C (D)D]

RP30(G) STEAM GENERATOR PRESSURE TRANSMITTER OUTPUT FAILURE LOW

[(A) PT-0751 (B) PT-0752] [(A) A (B) B (C) C (D)D]

REACTOR BEGUI.ATION 1.mil. SYSTEM RXOl(V) HOT LEG #1 CONTROL CHANNEL RTD FAILURE TE-OlllH [0-100%]

RX02(V)

RX06(G)

RX07(G)

RXOS(G)

HOT LEG #2 CONTROL CHANNEL RTD FAILURE TE-Ol21H [0-100%]

RX03(GV) COLD LEG #1 CONTROL CHANNEL RTD FAILURE TE-0111-[(A)A (B)B] (0-100%]

RX04(GV) COLD LEG #2 CONTROL CHANNEL RTD FAILURE TE-0121-[(A)A (B)B] (0-100%)

RX05(G) PRESSURIZER PRESSURE CONTROL FAILS IN HI DIRECTN PT-0101 [(A)A (B)B]

PRESSURIZER PRESSURE CONTROL FAILS IN LO DIRECTN PT-0101 [(A)A. (B)B]

PRESSURIZER LEVEL CONTROL UPSCALE DEMAND LT-0101 [(A)A (B)B]

PRESSURIZER LEVEL CONTROL DOWNSCALE DEMAND LT-0101 [(A)A (B)B]

RX09 . LOSS OF PRESSURIZER LEVEL CONTROL SIGNAL TO eves RXlO(GV) STEAM GENERATOR LEVEL CONTROL TRANMITTER FAILURE LT-[(A)0701 (8)0702 (C) 0703 (D) 0704] [0-100%]

RXll (G) FEED REGULATING VALVE ERRATIC OPERATION FRV-CV-[(A)0701 (B)0703]

RX12(G) PRESSURIZER HEATER GROUPS FAIL OFF [(A)PROPORTIONAL GROUP l (B)PROPORTIONAL GROUP 2 (C)BACKUP GROUP l (D)BACKUP GROUP 2 (E)BACKUP GROUP 3 (F)BACKUP GROUP 4]

RX13 PRESSURIZER PROPORTIONAL HEATER GROUP l REDU~ED CAPACITY RX14(GV). FEED WATER FLOW TRANSMITTER FAILURE FT~[(A)0701 (B)0703] [0-100%]

RX15(GV) MAIN STEAM FLOW TRANSMITTER FAILURE FT-[(A)0702. (B)0704] [0-100%]

STEAM GENERATOR ~ SYST~

SGOl(GV) STEAM GENERATOR TUBE RUPTURE [(A)l (B)2] (0-100%]

D.10

PALISADES SIMULATOR INDEX or MALFUNCTIONS SAFETY INJECTION 1..§.Il. SYSTEM

SIOl(G)

SI02(G)

SI04(G)

SI05(G)

SI06 HI PRESSURE SAFETY INJECT PUMP FAILURE P-66 [(A)A (B)B (C)C]

LO PRESSURE SAFETY INJECT PUMP FAILURE P-67 [(A)A (B)B]

SI03(G) . CONTAINMENT SPRAY PUMP FAILURE*P-54 [(A)A (B)B (C)C]

LOW SAFETY INJECT TANK PRESSURE FAILURE T-82 [(A)A (B)B (C)C (D)D]

LOW SAFETY INJECT TANK LEVEL CHANGED TO ED13 FAILURE T-82 [(A)A (B)B (C)C (D)D]

SI07 (G) SAFTY INJECT MANUAL INITIATION SIGNAL FAIL CHANEL [(A)LEFT (B)RIGHT]

SI08 (G) FALSE SAFETY INJECTION INITIATION CHANNEL [(A)LEFT (B)RIGHT]

SI09 CHANGED TO CH05 '

SilO(G) FAILURE OF AUTOMATIC CHANGEOVER TO ACTUATE CHANEL [(A)LEFT (B)RIGHT]

Sill (GV) SHUTDOWN COOLING HEAT EXCHANGER TUBE LEAK E-60 [(A)A (B)B] [0-100%]

SI12 (G) INCREASING SAFETY INJECTION TANK LEVEL T-82 [(A)A (B)B (C)C (D)D]

SI13 SHUTDOWN COOLING RELIEF VALVE RV-0401 FAILS OPEN SERVICE WATER l.fil!l SYSTEM SWOl LOSS OF TURBINE LUBE OIL COOLING SW02 LOSS OF SERVICE WATER TO GENERATOR HYDROGEN COOLERS SW03 DELETED SW04(G) LOSS OF SERVICE WATER PUMP P-7 [(A)A (B)B (C)C]

SWOS(G) COMPONENT COOLING HEAT EXCHANGER SERVICE WATER OUTLET VALVE FAILURE SHUT [(A)E-54A & CV-0821 (B)E-54B & CV-0822)

SW06(V) SERVICE WATER HEADER "A" PIPING RUPTURE [0-100%]

SW07(V) SERVICE WATER HEADER "B" PIPING RUPTURE [0-100%]

TURBINE CONTROL 1.l'.Sl. SYSTEM.

TCOl MAIN TURBINE TRIP TC02 FAILURE OF TURBINE AUTOMATIC TRIP ACTUATION TCOJ(G) TURBINE CONTROL VALVE FAILURE OPEN CV-[(A)l (B)2 (C)3 (D)4]

TC04 (G) TURBINE CONTROL VALVE FAILURE SHUT CV-[(A)l (B)2 (C)3. (D)4]

TCOS(G) TURBINE CONTROL VALVE FAILS AS IS CV-[(A)l (B)2 (C)3 (D)4]

TC06 . DELETED TC07 DELETED TC08(V) MAIN.TURBINE SPEED CONTROL FAILURE [0-190%]

TC09 MAIN TURBINE FIRST STAGE PRESSURE TRANSMITER (INPUT TO EHC) FAILS HI TClO MAIN TURBINE FIRST STAGE PRESSURE TRANSMITER (INPUT TO EHC) FAILS LO TCll LOAD-POWER MISMATCH (JUMPER AT PLANT DISABLED)

TC12(G) ELECTROHYDRAULIC CONTROL FLUID PUMP FAILURE [(A)A (B)B]

TC13 (V) LOAD REJECTION [0-100%]

TURBINE .!l'.ID. SYSTEM .

TUOl(V) MAIN TURBINE HIGH VIBRATION [0-100%]

TU02 TURBINE EXHAUST HOOD SPRAY INOPERABLE TU03 (V) LOSS OF MAIN TURBINE LUBE OIL [0-100%]

TU04* LOSS OF EMERGENCY BEARING OIL PUMP TU05 MAIN TURBINE TURNING GEAR 'FAILURE

D.11

REMOTE FUNCTIONS

PALISl\DBS SIMULATOR INPBX O~ RBMOTB J'UNCTIOHS RANGE STATUS

COMPONENT COOLING. CCC) SXSTEM ccoa PUMP P52A NORMAL RACKO UT CC09 .PUMP P52C NORMAL RACKO UT CClO PUMP P52C NORMAL RACKO UT CONTAINMENT CCHl SYSTEM CHlO PURGE EXHAUST Vl806 NORMAt DISABLE CORE CCR) SXSTEM CROl INCREASE/DECREASE EXCESS REACTIVITY OFF ON CR02 REACTIVITY METER -1% to +1% DK/K . (value)

CHEMICAL & VOLUME CONTBOL CCV) SYSTEM CV21 MIXED BED DEMIN BORON SATURATION N/SATUR SATUR CV22 BORIC ACID TANK T-53A BORON CONCENT 0 to 2000 ppm (value)

CV23 BORIC ACID TANK T-53B BORON CONCENT 0 to 2000 ppm (value)

CV24 BORIC ACID TANK T-53A LEVEL CHANGE INACTIVE ACTIVE CV25 BORIC ACID TANK T-53B LEVEL CHANGE INACTIVE ACTIVE CV26 WASTE DISTILLATE WATER TO TANK T-90 OUT SERV IN SERV CV27 DEMIN WATER TO T-939,0R T-2,0R T-81 OUT SERV IN SERV CV28 SIRW MAKEUP FILL LINE, V2157 *CLOSED OPEN CV29 SPOOL PIECE HOOKUP AND VALVES OPS DIS CONN CONNECT CV30 H2 SUPPLY TO VCT CLOSED OPEN CV31 N2 SUPPLY TO VCT CLOSED OPEN CV32 CHARGING PUMP P-55A RACKOUT NORMAL RACKO UT G\733 CHARGING PUMP P-55B RACKOUT NORMAL RACKO UT CV34 CHARGING PUMP P-55C RACKOUT NORMAL RACKO UT CV35 CONCENT BORIC ACID PUMP P-56A RACKOUT NORMAL RACKO UT CV36 CONCENT BORIC ACID PUMP P-56B RACKOUT NORMAL RACKO UT CV37. CHARGING PUMP DISCHARGE HEADER V2195 OPEN CLOSED CV38 SERVICE OF DEBORATION EXCHANGER T-52 CLOSED OPEN CV39

VOLUME CONTROL TANK T54 BORON CONCENT 0 to 2000 ppm (value)

CV40 BORONOMETER RANGE SELECTION NO.l 0 to 550 ppm INACTIVE ACTIVE CV41 BORONOMETER RANGE SELECTION N0.2 500 to 1050 ppm INACTIVE ACTIVE CV42 BORONOMETER RANGE SELECTION N0.3 1000 to 1550 ppm INACTIVE ACTIVE CV43 BORONOMETER RANGE SELECTION N0.4 1500 to 2050 ppm INACTIVE ACTIVE CV44 DOMESTIC WATER USAGE INACTIVE ACTIVE CV45 DELETED CV46 CHG .PUMP P-SSB POWER BUS NORMAL ALTRNTE CV47 CHG PUMP P-SSC POWER BUS NORMAL ALTRNTE CV48 P~sss & c ALTERNATE POWER BREAKER OPEN CLOSE

-- - - -=--*

~-- -- . -

D.12

PALISAQES SIMULATOR INDEX or REMOTB llJNCTIONS RAHGE STATUS

COOLING WATER Ccw> SYSTEM CW07 SLOWDOWN LINE VALVE (7-712 CWS) OPEN CLOSED cwoa SLOWDOWN LINE VALVE (7-714 CWS) OPEN CLOSED CW09 PUMP P39A RACKOUT NORMAL RACKOUT CWlO PUMP P39B RACKOUT NORMAL RACKO UT CWll PUMP P40A RACKOUT NORMAL RACKO UT CW12 PUMP P40B RACKOUT NORMAL RACKO UT CW13 VACUUM PRIMING SYS LINE UP FOR OFF ON EAST WATER BOX, MAIN COND CW14 VACUUM PRIMING SYS LINE UP FOR OFF ON WEST WATER BOX, MAIN COND CW15 LAKE WATER TEMPERATURE 35 to 80 Deg F (value)

CW16 AMBIENT AIR TEMPERATURE (OUTDOOR) o to 100 Dg F (value)

CW17 CIRCULATING WATER PH 5 to 9 Ph (value)

CW18 CIRCULATING WATER CONDUCTIVITY 10 to 1000 UMHO (value)

ELECTRICAL DISTRIBUTION CEDl SYSTEM ED18 SHUT AND OPEN MOD 26H5 OPEN CLOSE ED19 CHANGE GRID FREQUENCY o to 100% (value)

ED20 CHANGE GRID VOLTAGE -10 to +10 KV (value)

ED21 4160V BUS lF ALT SUPPLY BKR RACKOiJT .RACKIN ED22 4160V BUS lG ALT SUPPLY BKR RACKOUT . RACKIN ED23 CROSS-TIE BUS 11 THRU BUS 12 OPEN CLOSE ED24 CROSS-TIE BUS 12 THRU BUS 11 OPEN CLOSE E025 CROSS-TIE BUS 13 THRU BUS 14 OPEN CLOSE ED26 CROSS-TIE BUS 14 THRU BUS 13 .OPEN CLOSE ED27 D/G 1-1 TROUBLE ALARM C~ NORMAL CLEAR ED27 DEFEAT UNDERVOLTAGE RELAY LEFT CHANNEL NORMAL CLEAR ED28 D/G 1-2 TROUBLE ALARM CLEAR NORMAL .

DEFEAT ED28 DEFEAT UNDERVOLTAGE RELAY RIGHT CHANNEL NORMAL DEFE~T FEEDPYMP TURBINE CFTl SYSTEM FT0.6 FEEDWATER TURBINE-K7A RESET o to 30 psig (value)

FT07 FEEDWATER TURBINE-K7B RESET o to*30 psig (value) .

FEEDWATER CFWl SYSTEM FW24 HOGGING- AIR EJECTOR INLE~ . OPEN CLOSE VALVE 106AE/CV-0633 FW25 MAIN AIR EJECTOR INLET OPEN CLOSE VALVE 640AE/114AE FW26 HEATER ISOLATION VALVES 0720CD & NORMAL BYPASS 0725CD / BYPASS VALVE 0722CD FW27 HEATER ISOLATION VALVES 0721CD & NORMAL BYPASS 0726CD / BYPASS VALVE 0724CD

D.13

PALISADBS SIMULATQR INDEX or BBMOTB FUNCTIONS RAHGE . STATUS

FEEDWATER ( FWl SYSTEM (continued)

FW28 FEEDWATER REGUIATING VALVE CLOSE OPEN BYPASS VALVE 0707FW FW29 FEEDWATER REGUIATING VALVE CLOSE OPEN BYPASS VALVE 0705FW FW30 HEATER E-6A ISOIATION AND BYPASS NORMAL BYPASS 115FW & 0706FW

FW31 HEATER E-6B ISOIATION AND BYPASS NORMAL BYPASS 114FW & 0708FW FW32 CONDENSATE PUMPS DISCHARGE OPEN CLOSE VALVE:* 102/103CD FW33 CONDENSATE PUMP P-2A BREAKER RACKOUT NORMAL RACKO UT FW34 CONDENSATE PUMP P-2B BREAKER RACKOUT NORMAL RACKO UT FW35 HEATER DRAIN PUMP P-lOA BREAKER RACKOUT NORMAL RACKOUT FW36 HEATER DRAIN PUMP P-lOB BREAKER RACKOUT. NORMAL RACKO UT FW37 SUCTION SUPPLY TO.AFW P-SA AND B CST(T-2) FIREPRT FW38 SUCTION SUPPLY TO AFW P-SC CST(T-2) SERVWTR FW39 S/G DIFF PRESS SENSOR BYPASS CHANNEL A NORMAL BYPASS FW40 S/G DIFF PRESS SENSOR BYPASS CHANNEL*B . NORMAL BYPASS FW41 STM GEN A LEVEL LOW SENSOR BYPASS NORMAL BYPASS FW42 STM GEN B LEVEL LOW SENSOR BYPAsS NORMAL BYPASS FW43 AFAS SUBSYSTEM ARMED RESET FW44 FOGG SUBSYSTEM ARMED/RESET. ARMEP RESET FW45 KS PCV-0521A BYPASS (MV-150FW) CLOSE OPEN FW46 CONDENS~R VACUUM PUMP P-910 OFF ON MS18 ADV AIR SUPPLY ISOIATION VALVE CLOSE OPEN (S/G B) CA-0779 MS19 ADV AIR SUPPLY ISOIATION VALVE CLOSE OPEN (S/G B) CA-0780 MS20 ADV AIR SUPPLY ISOLATION VALVE CLOSE OPEN (S/B A) CA-0781 MS21 ADV AIR SUPPLY ISOLATION VALVE CLOSE OPEN (S/G A) CA-0782 MS22 DRAIN VALVES CV-0515, 0517, 0518; CLOSE OPEN 0519, 0523, 0532, 0520

MS23 GLAND STEAM CONDENSER EXHAUSTER C-lA STOP START MS24 GLAND STEAM CONDENSER EXHAUSTER C-lB *sTOP START MS25 MSIV SOLENOID VALVES RELATCH TRIPPED LATCHED MS26 AUX BOILER STEAM SUPPLY . OUTSERV INSERV MS27 MSIV BYPASS VLV M0-0510 MANUAL OPER CTL-ROOM MANUAL MS28 MSIV BYPAsS VLV M0-0510 MANUAL POS o to 100% (value)

MS29 MSIV BYPASS VLV M0-0501 MANUAL OPER CTL-ROOM MANUAL MS30 MSIV BYPASS VLV M0-0501 MANUAL POS o to 100% (value)

D.14

PALISAPES SIMULATOR INDEX or REMOTJ JUHCTIONS

PROCESS COMPUTER CPCl SYSTEM . RAHGE STATUS PC03 CHAN A/ CHAN C BEING DISPIAYED CHAN A CHAN C PC04 CHAN B / CHAN D BEING DISPIAYED CHAN B CHAN D PC05 CHANGE TMM (A) BIAS. (delta T) -10% to +10% (value)

PC06 CHANGE TMM (B) BIAS (delta T) -10% to +10% (value)

PC07 CHANGE TMM (C) BIAS (delta T) -10% to +10% (value)

PCOS CHANGE TMM ( D) BIAS (delta T) -10% to +10% (value)

PRIMARY COOLANT CBC) SYSTEM RC26 ACTUAL BORON CONCENTRATION 1772.1 (ACT)

RC27 PRESSURIZER/REACTOR VESSEL/PC LOOPS 0 to 2000 PPM (value)

BORON CONCENTRATION .

RC2S *.PRESSURIZER VENT VALVE OPEN CLOSE RC30 PCP-SOA RACKOUT NORMAL RACKO UT

. RC31 PCP-SOB RACKOUT NORMAL RACKOUT RC32 PCP-SOC RACKOUT NORMAL RACKO UT RC33 PCP-SOD BACKOUT NORMAL RACKO UT REACTOR PROTECTION CRPl SYSTEM RP3S REACTOR BREAKER TO CLUTCH PWR BREAKER NORMAL RESET RP36 HIGH VOLT FOR START-UP RANGE CHANNELS OFF ON RP37 C-lSO NI CABINENT FUSES OUT IN

.REACTOR REGUIATION CRXl SYSTEM Rx17 LTOP SET POINTS (A) PSIA S75 RX18 LTOP SET POINTS (B) PSIA 575 STEAM GENEBATOR CSGl SYSTEM SG06 *OVERRIDE FOR FLASH TANK LEVEL HIGH OUT IN TRIP CV-0738, 0739, 0770 & 0771 .

. SAFETY

. INJECTION CSil SYSTEM SI16 V3225 SHUTDOWN HX TO SIRW TANK CLOSE OPEN SI17 DELETED SI18 . V3231 DISCHARGE OF CONTAINMENT CLOSE OPEN SPRAY PUMP P-54A SI19 V3221 DISCHARGE OF CONTAINMENT CLOSE OPEN SPRAY PUMP P-54B SI20 V3203 DISCHARGE OF CONTAINMENT *CLOSE OPEN SPRAY PUMP P-54C SI21 CONTAINMENT SPRAY ISOIATION CLOSE OPEN VALVES 3258,3259 SI22 DELETED

D.lS*

PALISADES SIMULATOR INDEX OP REMOTE FUNCTIONS

.SAFETY INJECTION (SI) SYSTEM (continued) RANGE STATUS SI23 RACKOUT HP PUMP 66A NORMAL RACKO UT SI24 RACKOUT HP PUMP 66B NORMAL RACKO UT SI25 DELETED SI26 RACKOUT LP PUMP 67A NORMAL RACKO UT SI27 RACKOUT LP PUMP 67B NORMAL RACKO UT SI28 RACKOUTrCS PUMP 54A NORMAL RACKO UT SI29 RACKOUT CS PUMP .54B NORMAL RACKO UT SI30 RACKOUT CS PUMP 54C NORMAL RACKO UT SI31 HP PUMP 66A RECIRC TO SIRWT VLV 3188 OPEN CLOSE SI32 HP PUMP 66B RECIRC TO SIRWT VLV 3179 OPEN CLOSE SI33 OPEN BREAKERS52-167 & 52-271 NORMAL OPEN SI34 LP PUMP 67A RECIRC TO SIRWT VLV 3203 OPEN CLOSE SI35 LP PUMP 67B RECIRC TO SIRWT VLV 3194 OPEN CLOSE SI36 CS PUMP 54A RECIRC TO SIRWT VLV 3232 OPEN CLOSE SI37 CS PUMP 54B RECIRC TO .SIRWT VLV 3222 OPEN CLOSE SI38 CS PUMP 54C RECIRC TO SIRWT VLV 3210 OPEN CLOSE SI39 DISABLE CV3006 HX BYPASS VALVE OPEN NORMAL OPEN' SI40 VLV 3234 SI TANK DRAIN TO SIRWT OPEN CLOSE SI41 RACKOUT SI TANK 82A DISCHG VLV M0-3041 NORMAL RACKO UT SI42

RACKOUT SI TANK 82B DISCHG VLV M0-3045 NORMAL RACKOUT SI43 RACKOUT SI TANK 82C DISCHG VLV M0-3049 NORMAL RACKO UT SI44 RACKOUT SI TANK 820 DISCHG VLV M0-3052 NORMAL RACKOUT SI45 SI TANK 82-A STEP LEVEL CHANGE O to 1 (xl00%) (value)

SI46 SI TANK 82-B STEP LEVEL CHANGE o to 1 (xlOO%) (value)

SI47 SI TANK 82-C STEP LEVEL CHANGE o to 1 (xlOO%) (value)

SI48 SI TANK 82-D STEP LEVLE CHANGE o to 1 (xlOO%) (value)

, SI49 NAOH TANK T-103 DISCHARGE VLVS ENERG DEENG CV;...0438A, B SI50 HYDRAZINE TANK T-102 ISOLATION OPEN CLOSE VALVES 3354, 3355 SERVICE WATER (SW) SYSTEM SW12 FIRE PROTECTION TO SW HOR A VALVE CLOSED OPEN SW13 FIRE PROTECTION TO SW HOR B VALVE CLOSED OPEN SW14 PUMP *P7A RACKOUT NORMAL RACKO UT SW15 PUMP P7B RACKOUT NORMAL RACKOUT SW16 PUMP P7C RACKOUT NORMAL RACKOUT SW17 FIRE PROTECTION TO AIR COMP COOLERS CLOSED OPEN

SW18 HOR C ISOLATION VLV BYPASS SWlOl CLOSED OPEN SW19 PUMP P-9A STOP NORMAL STOP TURBINE CONTROL (TC) SYSTEM TC17 EH PANEL ALARM BYPASS (VPL & MAN) NORMAL BYPASS

. TC18 RESET RELAYS 386P AND 386C NORMAL RESET I.

TURBINE (TU) S:XSTEM TUlO LUBE OIL VAPOR EXTRACTOR FAN 1 FAN 2 D.16 .

ADDITIONAL FEATURES

PAUSADES SIMULATOR ADDITIONAL INSTRUCTOR/TRAINING FEATURES

1. Ability t.o st.ore 40 initial conditions with the additional ability t.o "protect" any number of them from accidental destruction. Currently there are 20 IC's prot.ect.ed, and these are list.ed in the "Index of Initial Conditions".

2. Ability t.o take snapshots of simulat.or operating scenarios. We currently have the ability to st.ore 20 different snapshots without affecting protect.ed IC's.

3. Ability to invoke fast time(@ 1 - 60 times real time, depending on variable) for selected p,arameters. *

4. Ability to invoke slow time(@ 1/3 real time) for all simulation. *I

5. Ability t.o backtrack up t.o 60 minut.es of simulation (in 1 minut.e increments) and then proceed again from<*that point.

6. Ability t.o record up t.o 20 minut.es of a scenario and replay the events that t.ook place at 1/3 real. time.

7. Ability t.o freeze simulation, inCluding visual indication on the control panels via the radio call light. *

8. Ability t.o give notification when the simulat.or exceeds operating limits. When the simulation exceeds the limits of the following parameters, the simulator aut.omatically goes int.o freeze, and a light flashes on the instruct.ors console. It is then possible t.o det.ermine the paramet.er and the limit exceeded.

PARAMETER DESIGN RANGE* REFERENCE LIMITS c.B. Press. -3_ to +55 psig USAR 5.8 +10 to +107.1 psia C.B. Rad* Up to 3.22 E5 Rlhr SEPAppxB; 1 E-2 to 3.3 E5 Rlhr USAR Tab 11-1

C.B. Temp 50 to 283 deg F USAR 5.8 32 to 289 deg F CVCSCB 0 to 17,IDO ppm USAR Tab 9-2 0 to 17,544 ppm Condenser FWPCDR press Up to 5 psig W. I.L.1250-159 0 to 20.4 psia PC Boron *. 0 tO 1700 ppm USAR Tab 9-20 Oto4908ppm PCS Mass 10,900 cu ft vol USAR 4.2 0 to 702,758 lbs Pzr Mass 1,500 cu ft vol USAR 4.2 0 to 96,084 lbs Pzr Press Up to 2,500 psia ATWS Analysis 10 to 3188 psia

D.17

PALISADES SIMULATOR ADDITIONAL INSTRUCTOR/TRAINING FEATURES

I

\*

PARAMETER* DESIGN RANGE REFERENCE LIMITS Rx Power Up to 2650 MWt 0 to 3312.5 MWt SIG Mass 0 to 571,400 lbs USAR4.3 582,828 lbs SIG Press Up to 1000 psia USAR4.3 0 to 1061 psia Turbine Speed 0 to 1980 r/min USAR5.5.2 0 to 3764 r/min NOTE: Parameters may be added to this list as necessacy.

~*

D.18

SECl'ION E SIMULATOR PERFORMANCE TEST ABSTRACTS

SIMULATOR TEST RTOl ABSTRACT

1. NAME AND DESCRIPTION OF TEST RTOl is a simulator real time test that involves the operation of the control rods. Rod #1 was timed to record the amount of time required to withdraw it from 8 inches to 100 inches withdrawn.

2. ANSI/ANS-3.5-1985 RELATIONSHIP 3.1.1 PARTIAL - (Real Time)

3. TEST DATES RTOl was conducted in March, 1989.

4. INITIAL. CONDITIONS Initial condition was IC4, plant at hot shutdown condition, with all rods in.

5. FINAL CONDITION~/DORATION OF TEST Final condition was plant at hot shutdown with control rod #1 withdrawn to 100 inches.

This test required approximately 20 minutes to complete

6 *. BASELINE DATA The baseline data is from .control rod drive mechanism (CROM) design data where the ramp rate is stated for the rod drives.

7. DEFICIENCIES None.

8. EXCEPTIONS TO ANSI/ANS-3.5-1985 No exceptions taken *

E.l

SIMULATOR TEST RT02 ABSTRACT

2. ANSI/ANS-3.5-1985 RELATIONSHIP 3.1.1 PARTIAL - (Real Time) 3* TEST DATES RT02 was conducted in March, 1989.

4. INITIAL CONDITIONS Initial condition was IC6, plant at hot standby condition, at 5% reactor power. Turbine speed at o. rpm~

. 5 it FINAL CONDITIONS/DURATION OF TEST

Final condition was plant at hot standby with turbine speed at 1100 rpm~

This test required approximately 20 minutes to complete.

6. BASELINE DATA The baseline data is the calculated amount of time *required to increase turbine speed 1000 rpm at an acceleration rate of 50 rpm.

7. DEFICIENCIES None.

8. EXCEPTIONS TO ANSI/ANS-3.5-1985 No exceptions taken.-

E.2

SIMULATOR TEST RT03 ABSTRACT

. 1. NAME AND DESCRIPTION OF TEST RT03 is a simulator real time test that involves a volume change of the chemical and volume control system (CVCS). In particular, the level change of the volume control tank was measured and timed under controlled conditions.

2. ANSI/ANS-3.5-1985 RELATIONSHIP 3.1.1 PARTIAL - (Real Time):

3* TEST DATES RT03 was conducted in March, 1989.

4. INITIAL CONDITIONS Initial condition was IClO, plant at full power condition, with volume control tank at.80% level.

5. FINAL CONDITIONS/DURATION OF TEST Final condition was plant at full power with volume control tank at 70% level.

6.

This test.required approximateiy 30 minutes to complete

BASELINE.DATA The baseline data is the calculated amount of time required to decrease the level of the volume control tank 10% at a flow rate of 40. gpm.

7. DEFICIENCIES The following simulator deficiency was noted during performance of this test:

A. FLOW RATE OF eves vs LEVEL CHANGE IN THE VCT SDR-89-055 This.simulator deficiency report (SDR) is scheduled to be corrected as indicated in the enclosed "Paltrack" report listing.

8. EXCEPTIONS TO ANSI/ANS-3 *.5-1985 No exceptions taken *

E.3

. SIMULATOR TEST RT04 ABSTRACT

1. NAME AND DESCRIPTION OF TEST RT04 is a simulator real time test.that involves the turbine/generator loading rate. The rate of change for generator loading was selected at 0.1% per minute and initiated. The elapsed time was then recorded for a 2% load change.

2. ANSI/ANS-3.5-1985 RELATIONSHIP 3.1.1 PARTIAL - (Real Time) 3* TEST DATES RT04 was conducted in March, 1989.

4. INITIAL CONDITIONS Initial condition was IClO, plant at full power condition.

5. FINAL CONDITIONS/DURATION OF TEST Final condition was plant at 2% less thari initial condition of full power and generator output *

6.

This test required approximately 30 minutes to complete.

BASELINE DATA '1P-The baseline data is the calculated amount of time required to change the load 2% at a rate of change equal to 0.1% per minute.

7. DEFICIENCIES The following simulator deficiency was noted during performance of this test:

A. GENERATOR* LOADING/UNLOADING RATE TOO SLOW SDR-89-051 This simulator deficiency report (SOR) is scheduled to be corrected as indicated in the enclosed "Paltrack" report listing.

8. EXCEPTIONS. TO ANSI/ANS-3.5-1985 No exceptions taken *

E.4

SIMULATOR TEST RT05 ABSTRACT

1. NAME AND DESCRIPTION OF TEST RT05 is a simulator real time test. This timing test is based on interval timers set by various simulation programs. The smallest resolution of these timers is 0.1 second.

The test of real time operation is performed as part of our normal Training Load Save process, after the*new software has been accepted. The simulator is run for a period of 10 minutes and counters for each software module keep track of the number of times the module was completely executed. These results are then compared to predicted values. This technique provides a 0.2% resolution for modules running 1 time/second and up to 0.02% .for-modules running 10 times/second. *

2. ANSI/ANS-3.5-1985 RELATI~NSBIP 3.1.1 PARTIAL - (Real Time)

3. TEST DATES This test was last conducted in January, 1990, and is repeated 3 to 4 .times each year following Training Load Saves .

- 4 *. INITIAL CONDITIONS Initial condition was IClO, 80% plant power, for the January, 1990 test.

5. FINAL CONDITIONS/DURATION OF TEST The simulation is allowed to run approximately 10 minutes without operator intervention *. The 10 minute interval is then timed with a stop watch. The January 1990 performance level

.achieved was 100% of the expected frames being executed.

The duration of .the test is approximately 25 minutes.

6. BASELINE DATA The baseline data is our objective to maintain simulator performance above 99.5%, that is, to skip less than 0.5% of the frames expected to be executed over the 10 minute period (the simulator is expected to run 10 frames/second). In March of 1989, the simulator was operated at 99% and no perceptible differences were detected when events were timed in the simulated control room.

E.5

SIMULATOR TEST RT05 ABSTRACT

7. DEFICIENCIES None.

8. EXCEPTIONS TO ANSI/ANS-3.5-1985 No exceptions taken *

E.6

STEADY STATE TE-ST

====================================================

ANS-3.5-1985 CPCO PAGE RELATIONSHIP TEST NUMBER 4.1 and N007 E.8 - E.9 3.1.1 (9) PARTIAL-(HEAT BALANCE)

====================================================

- STEADY STATE TESTS ACCEPTANCE CRITERIA A. CRITICAL PARAMETERS The following critical parameters must agree with plant data within +/-2% and not vary from their initial values by more than +/-2% over a one hour period :

MegaWatts Thermal(MWt)

MegaWatts Electrical (MWe)

Cold Leg Temperature (Tc)

Hot Leg Temperatut.e (Th)

FeedWat.er Flow (FWF)

St.earn Generator Pressure (SGP)

Primary Coolant Flow (PCF)

Pressurizer Pressure (Pzr Press)

B. NON:.CRITICAL PARAMETERS All other parameters must agree with plant data within +/-10%, and not detract from training .

C. PERCENT DEVIATION (SimulatDr Value) - (Plant Value) X 100%

(Range of Instrument)_*

If no range is available, such as LED displays, the instrument loop range is used...

E.7

SIMULATOR TEST N007 ABSTRACT

l. NAME AND DESCRIPTION OF TEST N007 is a simulator performance test that compares thermal power to generated electrical power, reactor coolant system temperature to steam generator pressure, feedwater flow to reactor thermal power, a mass balance of the pressurizer and a mass balance of a steam generator at three discrete. power levels. They are 99.7%, 75% and 50% of full power. The .

simulator was stabilized for 60 minutes. at each power level with data collection occurring at least 3 times within this period. These tests were accomplished following applicable Palisades' general operating procedures.

2. ANSI/ANS-3.5-1985 RELATIONSHIP 3 .1.1 (9) PARTIAL - (Heat Balance) 4.1

3. TEST DATES N007 was conducted in March, 1990.

4. TESTED PARAMETERS The parameters and their ranges monitored by strip chart, with a resolution of 0.5 seconds, are as follows:

Parameter Instrumentation Ranges A. PRESSURIZER LEVEL 0-100%

B. #1 HOT LEG TEMP. 0-615 DEG F.

C. #1 COLD LEG TEMP. 0-600 DEG F.

D. THERMAL POWER 0-100%

E. GROSS ELECTRIC OUTPUT 0-1000 MWe F. NET ELECTRIC OUTPUT 0-1000 MWe G. #2 HOT LEG TEMP. 0-615 DEG F.

H. #2 COLD LEG TEMP. 0-600 DEG F.

I. PRESSURIZER PRESSURE 1500-2500 PSIA.

J. STM. GEN. PRESS. E-50 A 0-1000 PSIA.

K. STM. GEN. LEVEL E-50 A 0-100%

L. WIDE RANGE LOG ( #3) (NI) 1. OE ... 8%. TO 125% FULL POWER M. STEAM FLOW E-50 A 0 TO 5.76E+6 LB PER HOUR N. FEED FLOW E-50 A 0 TO 5.76E+6 LB PER HOUR O. STM. GEN. PRESS. E-50 B 0-1000 PSIA.

P .. STM. GEN. LEVEL E-50 B 0-100%

Q. STEAM FLOW E-50 B 0 TO 5.76E+6 LB PER HOUR R. FEED FLOW E-50 B 0 TO 5.76E+6 LB PER HOUR S. T-AVERAGE 0-625 DEG F.

T. PRESSURIZER WATER TEMP. 0-1000 DEG F.

- In addition to the parameters listed above, the following items were also tested to verify simulator stability and accuracy*.

E.8

SIMULATOR TEST N007 ABSTRACT A. PCP AMPERES B. PRESSURIZER HEATER TRANSFORMER AMPERES C. CHARGING AND LETDOWN FLOW D. CHARGING AND LETDOWN TEMPERATURE E. STEAM FLOW F. FEEDWATER FLOW G. STEAM TEMPERATURE H. POWER LEVEL

5. INITIAL CONDITIONS Initial conditions were:

IClO, plant at full power, then stabilized at 99.7% full power, IClO, plant at full power, then stabilized at 75.0% full power, IC8, plant at 50% full power. -

6. STABILITY PERIOD/DURATION OF TEST The simulator was stabilized for a minimum of 60 minutes at each power level.

This test required approximately 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months to complete.

7. BASELINE DATA The baseline data is from Palisades plant operating procedures

GOP12; actual plant log s~eets dated May 3, 4, and 5, 1988, CFMS full power log, plant log dated May 15, 1988 (99.7% full power), CFMS 75% full power log, plant log sheets dated February 7, 1990, CFMS 50% full power log, plant strip charts dated May 3, 1988; plant documentation Technical Data Book (the steam generator pressure was compared in each case to the plant performance curve), the instrument index M-675; and subject matter experts.

8. DEFICIENCIES The following simulator deficiencies were noted during performance of this *test.

A. MAIN FEEDWATER FLOW A/B STM. GENERATOR SDR-89-085 B. STEAM PRESSURE A/B STM. GENERATOR SDR-86-017 C. LETDOWN TEMPERATURE FROM PCS SDR-89-009 D. PRESSURIZER HEATER AMPERES SDR-87-093 E. ELECTRICAL OUTPUT INDICATION (GROSS & NET) SDR-90-030 F. PRESSURIZER LEVEL OSCILLATIONS SDR-90-035 The simulator deficiency report SDR-89-009 has been corrected; the remaining SDR's are scheduled to be corrected as indicated in the "Paltrack" report listing.

EXCEPTIONS TO ANSI/ANS-3.5-1985

9.

No exceptions taken.

E.9

NORMAL OPERATION TESTS

================================================================

ANS-3.5-1985 CPCO PAGE RELATIONSHIP TEST NUMBER 3 .1.1 (1) NOOl E.11 - E.12 3 .1.1 {2) & (3) N002 E.13 - E.14 3 .1.1 (4) &: (9) N003 E.15 - E.16 3 .1.1 (5) N004 B.17 - B.19 3 .1.1 (6) NOOS E.19 E.20 3 .1.1 (8) N006 E.21 - E.22 3.1.1 (10) N009 B.23 - B.24 3 .1.1 (7) EXCEPTION 1. A.2

====================================================

NQte: CPCO test N007 is a steady state test. It's abstract is on pages B.9 - B.9.

\ .

'~

NORMAL OPERATIONS TESTS ACCEPTANCE CRITERIA A. If applicable, parameters must meet acceptance criteria of plant Startup Tests.

B. Parameter values must change in same* direction as expected for same transient on the plant, and not _violate physical laws .

C. Alarms and Auto Actioris must occur only as expected for the same transient on the plant. *

- - ElO

'.~

t NOOl PLANT STARTUP (COLD TO HOT STANDBY)

ANS-3.5-1985 RELATIONSHIP 3.1.1 (1)

SIMULATOR TEST NOOl ABSTRACT

. , 1. NAME AND DESCRIPTION OF T~ST Nooi is a simulator performance test that involves a normal plant startup from a cold shutdown condition to a hot standby condition. This evolution was accomplished following applicable Palisades' general operating procedures.

2. ANSI/ANS-3.5-1985 RELATIONSHIP

. 3.1.1 (1)

3. TEST DATES NOOl was conducted in March, 1989.

4. TESTED PARAMETERS The parameters and their ranges monitored by strip chart, with a resolution of 0.5 seconds, are as follows:

Parameter Instrumentation Ranges

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

A. PRESSURIZER LEVEL 0-100%

B. #1 HOT LEG TEMP. 0-615 DEG F.

C. #1 COLD LEG TEMP. 0-600 DEG F.

D.

E.

F.

G.

H.

I.

PCS FLOW CONTAINMENT PRESSURE CONTAINMENT TEMP.

2 HOT LEG TEMP.

2 COLD LEG TEMP.

PRESSURIZER PRESSURE 0-100%

0-100 PSIA.

0-400 DEG F.

0-615 DEG F.

0-600 DEG F.

1500-2500 PSIA.

J. STM. GEN. PRESS. E-50 A 0-1000 PSIA.

K. STM. GEN. LEVEL E-50 A 0-100%

L. WI.DE RANGE LOG ( #3) (NI) l.OE-8% TO 125% FULL POWER M. STEAM FLOW E-50 A . 0 TO 5.76E+6 LB PER HOUR N. FEED FLOW E-50 A 0 TO 5.76E+6 LB PER HOUR

0. STM. GEN. PRESS. E-50 B 0-1000 PSIA.

P. STM. GEN. LEVEL E-50 B 0-100%

Q. STEAM FLOW E-50 B 0 TO 5.76E+6 LB PER HOUR R. FEED FLOW E-50 B 0 TO 5.76E+6 LB PER HOUR S. T-AVERAGE 0-625 DEG F.

T. PRESSURIZER WATER TEMP *. 0-1000 DEG F.

In addition to the parameters listed above, the following items were also tested to verify simulator stability and accuracy.

A. SERVICE WATER SYSTEM B. COMPONENT COOLING WATER SYSTEM C. LOW TEMP. OVERPRESSURE PROTECTION EQUIP.

D. CONTAINMENT BUILDING VENTILATION SYSTEM E. RADWASTE VENTILATION SYSTEM F. FUEL HANDLING AND RADWASTE SYSTEM E.11

SIMULATOR TEST NOOl ABSTRACT

G.

H.

I.

J.

K.

L.

M.

ENGINEERED SAFEGUARDS ROOMS VENTILATION EQUIPMENT SAFETY INJECTION SYSTEM CONTAINMENT SPRAY SYSTEM CHEMICAL AND VOLUME CONTROL SYSTEM SHUTDOWN COOLING SYSTEM PRIMARY COOLANT SYSTEM MAIN STEAM SYSTEM N. STEAM GEN. BLOWDOWN SYSTEM O. CIRCULATING AND DILUTION WATER SYSTEMS P. CONDENSATE SYSTEM Q. PRESSURIZER PRESSURE AND LEVEL CONTROL EQUIPMENT R. TURBINE TURNING GEAR EQUIPMENT S. CONTROL ROD DRIVE MECHANISMS EQUIPMENT T. NUCLEAR INSTRUMENTATION .

U. AUXILIARY FEED WATER SYSTEM

5. INITIAL CONDITIONS Initial condition was ICl, plant at cold shutdown condition.

6. . F.INAL CONDITIONS/DURATION OF TEST The simulator was methodically changed from the cold shutdown condition to the hot standby condition.

This test required approximately thirteen hours to complete.

BASELINE DATA The baseline data is from plant procedures SOPl, SOP2, SOP3, SOP7, SOP14,

SOP~6, SOP24, GOP2 and GOP3; actual pla.nt data Test T-187 dated 2/26/86 and 5/24/86; and subject matter experts.

8. DEFICIENCIES The following simulator deficiencies were noted during performance of this test.

A. PRIMARY COOLANT PUMP AMPERES SDR-89-057 B. PRESSURIZER PRESSURE SDR-89-059 C. CONDENSATE PUMP AMPERES SDR-89-058 D. COOLING TOWER PUMP BASIN LEVEL SDR-89-003 E. PRESSURIZER LEVEL SDR-87-120 F. VOLUME CONTROL TANK LEVEL SDR-89-055/056 The simulator deficiency report SDR-89-003. has been corrected;

~he remaining SDR's are open and are scheduled to be corrected as indicated in the "Paltrack" report listing.

9. EXCEPTIONS TO ANSI/ANS-3.5-1985

. No exceptions taken.

E.12

N002 NUCLEAR STAR TUP.

FROM HOT STANDBY TO.

RATED POWER and TURBINE STARTUP AND

GENERATOR SYNCHRONIZATION ANS-3.5-1985 RELATIONSHIP 3.1.1 (2) & (3)

SIMULATOR TEST N002 ABSTRACT

1. NAME AND DESCRIPTION OF TEST N002 is a simulator performance test that involves a normal plant startup from hot standby to full power, including turbine startup and generator synchronization. This evolution was accomplished by following applicable Palisades' general operating procedures.

2. ANSI/ANS-3.5-1985 RELATIONSHIP 3.1.1 (2) 3.1.1 (3)

3. TEST DATES N002 was conducted in March, 1989.

4. TESTED PARAMETERS The parameters and their ranges monitored by strip chart, with a ~esolution of 0.5 seconds, are as follows:

PARAMETER INSTRUMENTATION RANGES A. PRESSURIZER LEVEL 0-100%

B.

C.

D.

E.

F.

-G.

1 HOT LEG TEMP .

1 COLD LEG TEMP.

PCS FLOW CONTAINMENT PRESSURE CONTAINMENT TEMP.

2 HOT LEG TEMP.

0-615 DEG F.

0-600 DEG F.

0-100%

0-100 PSIA.

0-400 DEG_ F.

0-615 DEG F.

H. #2 COLD LEG TEMP. 0-600 DEG F.

I. PRESSURIZER PRESSURE 1500-2500 PSIA.

J. STM. GEN. P~SS{JlIB E-50 A 0-1000 PSIA.

K. STM. GEN. LEVEL E-50 A 0-100%

L. WIDE RANGE LOG ( #3) (NI) 1. OE-8% TO 125% FULL POWER M. STM. FLOW E-50. A o~5.76E+6 LB PER HR.

N. FEED FLOW E-50 A 0-5.76E+6 LB PER HR.

O. STM. GEN. PRESSURE E-50 B 0-1000 PSIA.

P. STM. GEN* _LEVEL E-50 B . 0-100%

Q. STM. FLOW E-50 B 0-5.76E+6 LB PER HR.

R. FEED FLOW E 50 B 0-5.76E+6 LB PER HR.

S. T-AVERAGE 0-625 DEG F.

T. PRESSURIZER WATER TEMP. 0-1000 DEG F.

In addition to the parameters listed above, the following items were also tested to verify simulator stability and accuracy.

A. MAIN STM. SYSTEM

B.

C.

D.

FEED WATER SYSTEM DIESEL GENERATORS

-TURBINE GENERATOR SYSTEM E.13

SIMULATOR TEST N002 ABSTRACT

E.

F.

G.

H.

I.

CONDENSATE SYSTEM CIRCULATING WATER SYSTEM CHEMICAL AND VOLUME CONTROL SYSTEM CONTROL ROD DRIVE MECHANISMS SWITCHYARD, STATION POWER AND START-UP POWER SYSTEMS S. INITIAL CONDITIONS The initial condition for this test was IC6, plant at hot standby condition.

6. FINAL CONDITIONS/DURATION OF TEST The simulator was methodically changed from the hot standby condition to full power, including turbine startup and generator synchronization. - -

This test took approximately six hours to complete.

7. BASELINE DATA.

Baseline data is from plant procedures SOP30, GOP4, GOP5 and GOP12; and subject matter experts.

8* DEFICIENCIES

The following deficiency was noted during performance-of this*

test:

DIESEL GENERATOR STATUS LIGHTS This simulator deficiency report ~SOR)

SDR-89-007 has been corrected.

9. EXCEPTIONS TO ANSI/ANS-3.5-1985 No exceptions t_aken.

E.14

N003 REACTOR TRIP FOLLOWED BY RECOVERY TO RATED POWER an.d CORE PERFORMANCE TESTING ANS-3.5-1985 RELATIONSHIP 3.1.1 (4) & .(9)

SIMULATOR TEST N003 ABSTRACT NAME. AND DESCRIPTION OF TEST N003 is a simulator performance test that involves a full power reactor trip, followed by trip recovery and return to full power. The trip recovery and return to full power was accomplished using applicable Palisades' plant procedures.

2. ANSI/ANS-3.5*1985 RELATIONSHIP 3.1.1 (4) 3 .1.1 (9) PARTIAL :- (Heat Balance, Control Rod Worth and Estimated Critical Prediction)

3. TEST DATES N003 was conducted in March,- 1989.

4. TESTED PARAMETERS The parameters; and their ranges monitored by strip chart, with a resolution of 0.5 seconds, are as follows:

PARAMETER INSTRUMENTATION RANGES A. PRESSURIZER LEVEL . 0-100%

B. #1 HOT LEG TEMP. 0-615 DEG*F.

C. #1 COLD LEG TEMP. 0-600 DEG F ..

D. PCS FLOW 0-100%

E. CONTAINMENT PRESSURE 0-100 PSIA.

F. CONTAINMENT TEMP. 0-400.DEG F.

G. #2 HOT LEG TEMP. 0-615 DEG F.

H. #2 COLD LEG TEMP~ 0-600 DEG F.

I. PRESSURIZER PRESSURE 1500-2500 PSIA.

J. STM. GEN. PRESSURE E-50 A. .0-1000 PSIA.

K. STM. GEN. LEVEL E-50 A 0-100%

L. WIDE RANGE LOG (#3) (NI) 1.0E-8% TO 125% FULL POWER M. STM. FLOW E-50 A 0-5.76E+6 LB PER HOUR N. FEED FLOW E-50 A 0-5.76E+6 LB PER HOUR O~ STM. GEN. PRESSURE E-50 B 0-1000 PSIA.

P. STM. GEN. LEVEL E-50 B 0-100%

Q. STEAM FLOW E-50 B 0-5.76E+6 LB PER HOUR R. FEED FLOW E-50 B 0-5.76E+6: LB PER HOUR S. T-AVERAGE 0-625 DEG F.

T. PRESSUR~ZER WATER TEMP. 0-1000 DEG F.

In addition to the parameters listed above, the following it~ms were also tested to verify simulator stability and accuracy.

-* A.

B.

C.

D.

REACTOR AND TuRBINE TRIP INDICATIONS STATION POWER, STARTUP POWER AND ELECTRICAL DISTRIBUTION DIESEL GENERATORS MAIN FEED WATER SYSTEM E.15

SIMULATOR TEST N003 ABSTRACT E. MAIN STEAM SYSTEM F. CHEMICAL AND VOLUME CONTROL SYSTEM G. MAIN TURBINE SYSTEM H. CONTROL ROD DRIVE EQUIPMENT I. AUX. FEEDWATER SYSTEM

5. INITIAL CONDITIONS The initial condition for the test was IClO, plant at full power.

6. FINAL CONDITIONS/DURATION OF TEST A full power reactor trip followed by trip recovery and return to full power.

This test took approximately seven hours to complete.

7. BASELINE DATA The baseline data is from Palisades plant operating procedures SOP30, GOP12, and EOPl; actual plant data PTR 2 dated July, 1980; and subject matter experts.

s. DEFICIENCIES

The following deficiencies were noted during performance of this test:

A. STEAM GEN. LEVEL RECORDER LR0701 AND LR0703 B. DIESEL GEN. INDICATING LIGHTS (K6B)

SDR-89-062 SDR-89-007 The simulator deficiency report SDR-89-007 has been corrected and SDR-89-062 is scheduled to be corrected as indicated in the "Paltrack" report listing.

9. EXCEPTIONS TO ANSI/ANS-3.5~1985 No exceptions taken.

E.16

N004 OPERATIONS AT HOT STANDBY

ANS-3.5-1985 RELATIONSHIP 3.1.1 (5)

SIMULATOR TEST N004 ABSTRACT

1. NAME AND DESCRIPTION OF TEST N004 is a simulator performance test that involves operations at hot standby under steady state conditions. These operations were accomplished by following applicable Palisades' operating procedures.

2 *. ANSI/ANS-3.5-1985 RELATIONSHIP 3.i.l (5)

3. TEST DATES N004 was conducted in March, 1989.

4. TESTED PARAMETERS The parameters and their ranges*monitored by strip chart, with

a resolution of 0.5 seconds, are as follows:*

PARAMETER INSTRUMENTATION RANGES A. PRESSURIZER LEVEL 0-100%

B. #1 HOT LEG TEMPERATURE 0-.615 DEG. F.

C.. #1 COLD LEG TEMPERATURE 0-600 DEG. F.

D. PCS FLOW E. CONTAINMENT PRESSURE F. CONTAINMENT TEMPERATURE

G. #2 HOT LEG TE.MPERATURE H. #2 COLD LEG TEMPERATURE I. PRESSURIZER PRESSURE 0-100%

0-100 PSIA.

0-400 DEG. F.

0-615 DEG. F.

0-600 DEG. F.

1500-2500 PSIA.

J. STM GEN. PRESSURE E-50 A 0-1000 PSIA.

K. STM GEN. LEVEL E-50 A *0-100%

L. WIDE RANGE LOG (#3) (NI) 1.0E-8% TO 125% FULL POWER M. STEAM FLOW E-50 A 0-5.76E+6 LB PER HOUR N. FEED FLOW E-50 A 0-5.76E+6 LB PER HOUR

0. STM GEN. PRESSURE E-50 B 0-1000 PSIA.

P. STM GEN. LEVEL E-50 B 0-100%

Q.* STEAM FLOW E-50 B 0-5.76E+6 LB PER HOUR R. FEED FLOW E-50 B 0-5.76E+6 LB PER HOUR S. T-AVERAGE 0-625 DEG. F.

T. PRESSURIZER WATER TEMP. 0-1000 DEG. F.

In addition to the parameters listed in above,_ the following items were also tested to verify*simulator stability and accuracy.

A. STM. GEN. PRESSURE B. TURBINE BYPASS VALVE OPERATION C. AUX. FEEDWATER FLOW D. STEAM GEN. LEVELS E.17

SIMULATOR TEST N004 ABSTRACT INITIAL CONDITIONS The initial condition for this test was IC6, plant at hot standby condition.

6. STABILITY PERIOD/DURATION OF TEST The simulator was stabilized for a 60 minute period in a: hot standby condition.

This test took approximately two hours to complete.

7. BASELINB DATA The baseline data is from actual plant calorimetric data, and subject matter experts.

8. DEFICIENCIES The following deficiency was noted during performance of this test:

AUX. FEED FLOW 0727 0749 SDR-89-040 This simulator deficiency repo_rt (SOR) has been corrected.

EXCEPTIONS TO ANSI/ANS-3.5-1985

No exceptions taken *

E.18

N005 LOAD CHANGES

ANS-3.5-1985 RELATIONSHIP 3.1.1 (6)

SIMULATOR TEST N005 ABSTRACT

1. NAME AND DESCRIPTION OP TEST N005 is a simulator performance test that involves load changes greater than or equal to 10% of load/power. Turbine valve testing was also included.in this test. The test begins at full power, then was adjusted to 93.9% of turbine load* with all applicable equipment in service per standard operating procedures. The.load was reduced to 84.5%, then was further reduced to completely close #4 governer valve, at which time turbine valve testing was performed (reactor power at this time was 74.5%). All of the steps were performed using control rods and/or dilution. The evolutions performed were accomplished by following applicable Palisades' operating procedures.

2. ANSI/ANS-3.5-1985 RELATIONSHIP 3.1.1 (6)

3. TEST DATES N005 was conducted in March, 1989.

4. TESTED PARAMETERS The parameters and their.ranges monitored by strip chart, with a resolution of Q.5 seconds, are as follows:

PARAMETER INSTRUMENTATION RANGES A. PRESSURIZER LEVEL 0-100%

B. #1 HOT LEG TEMPERATURE 0-615 DEG .* F.

C. #1 COLD LEG TEMPERATURE 0-600 DEG. F.

D.* PCS FLOW 0-100%

E. CONTAINMENT PRESSURE 0-100 PSIA.

F. CONTAINMENT TEMPERATURE 0-400 DEG. F.

G. #2 HOT LEG TEMPERATURE 0-615 DEG. F.

H. #2 COLD LEG TEMPERATURE 0-600 DEG. F.*

I. PRESSURIZER PRESSURE 1500-2500 PSIA.

J. STM. GEN *. PRESSURE E-50 A 0-1000 PSIA.

K. STM. GEN. LEVEL E-50 A 0-100%

L. WIDE RANGE LOG (#3) (NI) l.OE-8% TO 125% FULL POWER M*. STM. FLOW E-50 A 0-5.76E+6 LB PER HOUR N. FEED FLOW E-50 A 0-5.76E+6 LB PER.HOUR O. STM. GEN. PRESSURE E-50 B 0-1000 PSIA.

P. STM. GEN. LEVEL E-50 B 0-100%

Q. STM. FLOW E-50 B 0-5.76E+6 LB PER HOUR R. FEED FLOW E-50 B 0-5.76E+6 LB PER HOUR S. T-AVERAGE 0-625 DEG. F.

T. PRESSURIZER WATER TEMP. 0-1000 DEG. F *

E.19

SIMULATOR TEST NOOS ABSTRACT

In addition to the parameters listed on the previous page, the following items were also tested to verify simulator stability and accuracy.

A. TURBINE CONTROL VALVE POSITION VALVES 1,2,3,4.

B. TURBINE CONTROLS AND INDICATIONS.

5. INIT.IAL CONDITIONS The initial condition for this test was IClO, plant at full power. ,*

6. FINAL CONDITIONS/DURATION OF TEST The load was reduced to 74.5%, at which time turbine valve testing was performed. Then the power level was raised to the initial value.

This test took approximately two hours to complete.

7. BASELINE DATA The baseline data is from General Operating Procedures (GOP) 6 and 7, Standard Operating Procedure (SOP) a, Alarm Response

. Procedures (ARP) 1 and 2, and subject matter experts.

a. DEFICIENCIES The following deficiency was noted during performance of this test:

MAIN GENERATOR POWER METER SDR-89-063 This simulator deficiency report (SOR) is scheduled to be corrected as indicated in the "Paltrack" report listing.

9. EXCEPTIONS TO ANSI/ANS"."'3. 5-1985' No exceptions taken *

E.20

N006 PLANT SHUTDOWN FROM RA TED POWER TO

HOT STANDBY AND COOLDOWN TO COLD SHUTDOWN.

CONDITIONS ANS-3.5-1985 RELATIONSHIP 3.1.1 (8)

SIMULATOR TEST N006 ABSTRACT

,. 1. NAME AND DESCRIPTION OF TEST N006 is a simulator performance test. that involves a normal controlled shutdown from full power to a cold shutdown condition. This evolution was accomplished following applicable Palisades' general operating procedures.

2. ANSI/ANS-3.5-1985 RELATIONSHIP 3.1.1 (8)

3. TEST DA'rES N006 was conducted in March, 1989.

4. TESTED PARAMETERS The parameters and thei+ ranges .monitored by strip chart, with a resolution of 0.5 seconds, are as follows:

Parameter Instrumentation Ranges A. PRESSURIZER LEVEL. 0-100%

B. #1 HOT LEG TEMP. 0-615 DEG F.

C. #1 COLD LEG TEMP. 0-600- DEG F.

D.

E.

F.

G.

H.

I.

PCS FLOW CONTAINMENT PRESSURE CONTAINMENT TEMP.

2 HOT LEG TEMP.

2 COLD LEG TEMP.*

PRESSURIZER PRESSURE 0-100%

0-100 PSIA.

0-400 DEG F.

0-615 DEG F.

0-600 DEG F.

1500-2500 PSIA.

J. STM. GEN. PRESS. E-50 A 0-1000 PSIA.

K. STM. GEN. LEVEL E-50 A 0-100%

L .. WIDE RANGE. LOG ( #3) (NI) l *. OE-8% TO 125% FULL POWER M. STEAM FLOW E-50 A 0 TO 5.76E+6 LB PER HOUR N. FEED FLOW' E-50 A 0 TO 5.76E+6 LB PER HOUR O. STM. GEN. PRESS. E-50 B 0-1000 PSIA.

P. STM. GEN. LEVEL E-50 B 0-100%

Q. STEAM*FLOW E-50 B 0 TO 5.76E+6 LB PER HOUR R. FEED FLOW E-50 B 0 TO 5.76E+6 LB PER HOUR S. T-AVERAGE 0-625 DEG F.

T. PRESSURIZER WATER TEMP. 0-1000 DEG F.

In addition to the parameters listed above, the following items were also tested to verify simulator stability and accuracy.

A. eves CONTROLS AND INDICATIONS B. TURBINE CONTROLS C. MAIN FEEDWATER SYSTEM D. DIESEL GENERATORS E. AUX. FEEDWATER SYSTEM F. ATMOSPHERIC STEAM DUMP VALVES E.21

SIMULATOR TEST N006 ABSTRACT

s.

G. PRIMARY GOOLANT SYSTEM H. SHUTDOWN COOLING SYSTEM INITIAL CONDITIONS Initial condition was IClO, plant at full power.

6. FINAL CONDITIONS/DURATION OF TEST The simulator was methodically changed from full power to a cold shutdown condition.

This test required approximately nine hours to complete.

7. BASELINE DATA The* baseline data is from Palisades plant operating procedures SOPl, SOP6, SOP7, SOP12, GOP5, and EOP2; plant drawing E256, sheet 3, revision 7; and subject matter experts.

8. DEFICIENCI~S The following simulator deficiencies were noted during performance of this test.

A. DIESEL GEN. STATUS LIGHTS SDR-89-007 B. ATMOSPHERIC STEAM .DUMP VALVE IND. LIGHTS SDR-89-064 C. PRIMARY COOLANT FLOW .SDR-89-055 D. SHUTDOWN COOLING FLOW.INDICATION SDR-87-010 The simulator deficiency report SDR-89-007 has been corrected; SDR-89-064, SDR-89-055 and SDR-87-010 are scheduled.to be corrected as indicated in the "Paltrack" report listing.

9. EXCEPTIONS TO ANSI/ANS-3.5-1985 No exceptions taken *

E.22

N007 (is a steady state test. It's abstract is on pages E.8 - E.9 )

NOOS OPERA TOR CONDUCTED SURVEILLANCE TESTING ON SAFETY-RELATED EQUIPMENT OR

SYSTEMS ANS-3.5-1985 RELATIONSHIP 3.1.1 (10)

SIMULATOR TEST N008 ABSTRACT

1. NAME AND DESCRIPTION OF TEST NOOS is a simulator performance test that involves technical specification surveillance tests normally conducted by the control room operators. These tests were accomplished following applicable Palisades' general operating procedures.

The tests that were conducted are as follows:

A. REACTOR PROTECTION SYSTEM (R~S) MATRIX LOGIC TESTS (M03)

B. POWER DEPENDANT INSERTION LIMIT (PDIL) AND CONTROL RODS OUT OF SEQUENCE ALARMS TESTING (MOS)

2. ANSI/ANS-3.5-1985 RELATIONSHIP 3.1.1 (10)

3. TEST DATES NOOS consists of three sections. -Sections 1 and 2 of NOOS were conducted in March, 1989. Section 3 was conducted in March, 1990.

4. TESTED PARAMETERS

The parameters and their ranges monitored by strip chart, with a resolution of o.5 seconds, are as follows:

Parameter A. PRESSURIZER LEVEL Instrumentation-Ranges 0-100%

B. #1 HOT LEG TEMP. 0-615 DEG F.

C. #1 COLD LEG TEMP. 0-600 DEG F.

D. PCS-FLOW 0-100%

E. CONTAINMENT PRESSURE o-1oo*PsIA.

F. CONTAINMENT TEMP. 0-400 DEG F.

G *. #2 HOT LEG TEMP. 0-615 DEG F.

H. #2 COLD LEG TEMP. 0-600 DEG F.

I: PRESSURIZER PRESSURE 1500-2500 PSIA.

J. STM. GEN. PRESS. E-50 A 0-1000 PSIA *.

K. STM. GEN. LEVEL E-50 A 0-100%

L *.WIDE RANGE LOG (#3) (NI) l.OE-8% TO 125% FULL POWER M. STEAM FLOW E-50 A 0 TO 5.76E+6 LB PER HOUR N. FEED FLOW E-50 A 0 TO 5.76E+6 LB PER HOUR O. STM. GEN. PRESS. E-50 B 0-1000 PSIA.

P. STM. GEN. LEVEL E-50 B 0-100%

Q. STEAM FLOW E-50 B 0 TO 5.76E+6 LB PER HOUR R. FEED FLOW E-50 B 0 TO 5.76E+6 LB PER HOUR S. T-AVERAGE 0-625 DEG F.

T. _PRESSURIZER WATER TEMP

0-1000 DEG F.

E.23

SIMULATOR TEST N008 ABSTRACT

In addition to the parameters listed on the previous page, the following items were also tested to verify simulator stability and accuracy.

A. RPS TEST SWITCHES AND INDICATIONS (TRIP LIGHTS)

B. PDIL OUT OF SEQUENCE ALARMS (PIP)/(.PRIMARY DATA LOGGER)

5. INITIAL CONDITIONS Initial condition was IClO, plant at full power.

6. FINAL CONDITIONS/DURATION OF TEST The simulator was maintained at full power for the duration of the test.

This test required approximately five hours to complete.

7. BASELINE DATA The baseline data is from plant surveillance test procedures M03 and MOS; and subject matter experts.

a. DEFICIENCIES

The following simulator deficiencies were noted during performance of this test.

A. RPS AC.AND DC INDICATION LAMPS B. PIP WOULD NOT ALLOW SECTION 3 OF TEST NOOS TO BE COMPLETED. .

SDR-89-065 SDR-89-046 C. PPDIL & PDIL HORNS DO NOT ACTUATE AS REQUIRED SDR-90-049 The simulator deficiency report SDR-89-046 has been corrected, SDR-89-065 and SDR~90-049 are scheduled to be corrected as indicated in the "Paltrack" report listing.

9. EXCEPTIONS TO ANS.I/ANS-3. 5-1985 All of the operator conducted surveillance testing on safety related equipment or systems are not included in the simulator performance testing. These two technical specification (TS) surveillance tests are the only ones that are conducted entirely in the control room. The numerous other TS surveillance tests are performed by starting and stopping equipment from the control room, then taking data locally *

E.24

TRANSIENT TESTS

================================================================

ANS-3.5-1985 CPCO PAGE RELATIONSHIP TEST NUMBER B2.2 (1) TOOl E.26 - E.27 B2.2 (2) T002 E.28 - B.29 B2.2 (3) T003 E.30 - E.31 B2.2 (4) T004 E.32 - E.33 B2.2 (5) TOOS E.34 - E.35 82.2 (6) T006 E.36 - E.37 82.2 (7) T007 E. 38 - E.39 B2.2 (9) TOOS E.40 - E.41 B2.2 (8) T009 E.42 - E.43 B2.2 {10) & TOlO E.44 - B.45 3 .1.2 (10)

====================================================

TRANSIENT TESTS ACCEPTANCE CRITERIA A If applicable, parameters must meet acceptance criteria of plant Startup Tests.

B. Parameter values must change in same direction as expected for same transient on the plant, and not violate physical laws .

- C. Alarms and Auto Actions must occur only as expected for the same transient on the plant .

TOOl MANUAL REACTOR TRIP ANS-3.5-1985

RELATIONSHIP

- B2.2 (1)

SIMULATOR TEST TOOl ABSTRACT

1. NAME AND DESCRIPTION OF. TEST T001 is a simulator performance test that involves a manual reactor trip transient, an uncomplicated reactor trip from full power. This evolution was accomplished following applicable Palisades' standard operating procedures (SOP) and emergency operating procedures (EOP). The normal plant equipment was simulated to be in service and/or operable per SOP's.

2. ANSI/ANS-3.5-1985 RELATIONSHIP Appendix B, B2.2(1)

3. *TEST DATES TOOl was conducted in April, 1990.

4. TESTED PARAMETERS The parameters and their ranges monitored by strip ~hart, with a resolution of 0.5 seconds, are as follows:

Parameter Instrumentation Ranges A. PRESSURIZER LEVEL 0-:.100%

B. #1 HOT LEG TEMP. 0-615 DEG F.

C. #1 COLD LEG TEMP. 0-600 DEG F.

D. PCS FLOW 0-100%

E. CONTAINMENT PRESSURE 0-100 PSIA.

F. CONTAINMENT TEMP. 0-400 .DEG F.

G. #2 HOT LEG TEMP. 0-615 DEG F.

H. #2 COLD LEG TEMP. 0-600 DEG F.

I. PRESSURIZER PRESSURE 1500-2500 PSIA.

J. STM. GEN. PRESS. E-50 A 0-1000 PSIA.

K. STM. GEN. LEVEL E-50 A 0-100%

L. WIDE RANGE LOG (#3) (NI) 1.0E-8% TO 125% FULL POWER

~. STEAM FLOW E-50 A 0 TO 5.76E+6 LB PER HOUR N. FEED FLOW E-50 A 0 TO 5.76E+6 LB PER HOUR O. STM. GEN. PRESS. E-50 B 0-1000 PSIA.

P. STM.. GEN. LEVEL E-50 B 0-100%

Q. STEAM FLOW E-50 B 0 TO 5.76E+6 LB PER HOUR R. FEED FLOW E-50 B 0 TO 5.76E+6 LB PER HOUR S. T-AVERAGE 0-625 DEG F.

T. PRESSURIZER WATER TEMP. 0-1000 DEG F.

In addition to the parameters listed above, the following items were also tested to verify simulator stability and accuracy.

A. REACTOR TRIP ALARM B. CONTROL ROD POSITION INDICATION C. POWER LEVEL (NI 03 AND 04) AND START UP RATE D. RPS CLUTCH POWER SUPPLY INDICATION E.26

SIMULATOR TEST TOOl ABSTRACT

E. FEEDPUMP HIGH AND LOW PRESSURE THROTTLE AND TRIP VALVE INDICATION-F. FEEDPUMP SPEED G. TURBINE STOP AND GOVERNOR H. STATION POWER AND START-UP POWER INDICATION I. DIESEL GENERATOR STATUS/INDICATION J. S/G LEVEL K. PRESSURIZER HEATER INDICATION L. SUBCOOLDED MARGIN MONITOR M. PRESSURIZER PRESSURE AND LEVEL N. AUX FEEDPUMP STATUS, FLOW AND PRESSURE

0. BUS lC AND lD VOLTAGE AND ALARMS P. DC VOLATAGE ALARMS Q. SERVICE WATER PUMPS STATUS, PRESSURE R. COMPONENT COOLING WATER PUMPS STATUS, PRESSURE & TEMPERATVRE S. COMPRESSED AIR STATUS T. PCS DIFFERENTIAL TEMPERATURE AND AVERAGE TEMPERATURE U. CONTAINMENT BLDG INTEGRITY: PRESSURE, TEMPERATURE AND RADIATION

5. INITIAL CONDITIONS Initial condition was IClO, plant at full power condition.

6. FINAL CONDITIONS/DURATION OF TEST

7.

Final condition was plant at hot shutdown .

This test required approximately 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to complete.

BASELINE DATA The baseline data is from actual Plant Trip Report dated July 2, 1980; Palisades plant operating procedure EOPl; and subject matter experts.

8. DEFICIENCIES The following simulator deficiency was noted during performance of this test.

A. DIESEL. GENERATOR STATUS LIGHTS SDR-89-007 This simulator deficiency report (SOR) has been corrected.

9. EXCEPTIONS TO ANSI/ANS-3.5-1985 No exceptions taken.

-* E.27

\.* *'

T002 SIMULTANEOUS TRIP OF ALL FEEDW ATER

PUMPS ANS-3.5-1985

RELATIONSHIP B2.2 (2)

SIMULATOR TEST T002 ABSTRACT NAME AND DESCRIPTION OF TEST T002 is a simulator performance test that involves a feedwater

pump transient, a full power reactor trip initiated by low steam generator level, which resulted from .the loss of both S/G feed pumps. This evolution was accomplished following applicable Palisades' standard operating procedures (SOP) and emergency operating procedures (EOP). The normal plant equipment was simulated to be in service and/or operable per SOP's.

2. ANSI/ANS-3.5-1985 RELATIONSHIP Appendix B, B2.2(2)

3. TEST DATES T002 was conducted in March, 1989.

4. TESTED PARAMETERS The parameters and their ranges monitored by strip chart, with a resolution of 0.5 seconds, are as follows:

Parameter Instrumentation Ranges

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

A. PRESSURIZER LEVEL 0-100~

B. #1 HOT LEG TEMP .. 0-615 DEG F.

C. #1 COLD LEG TEMP. 0-600 DEG.F.

D. PCS FLOW 0-100%

E. CONTAINMENT PRESSURE 0-100 PSIA.

F. CONTAINMENT TEMP. 0-400 DEG F.

G. #2 HOT LEG TEMP. 0-615 DEG F.

H_. #2 COLD LEG TEMP. 0-600 DEG F.

I. PRESSURIZER PRESSURE 1500-2500 PSIA.

J. STM. GEN. PRESS. E-50 A 0-1000 PSIA.

K. STM. GEN. LEVEL E-50 A 0-100%

L. WIDE RANGE LOG (#3) (NI) 1.0E-8% TO 125% FULL POWER M. STEAM FLOW E-50 A 0 TO 5.76E+6 LB PER HOUR N. FEED FLOW E-50 A 0 TO 5.76E+6 LB PER HOUR

0. STM. GEN. PRESS. E-50 B 0-1000 PSIA.

P. STM. GEN. LEVEL E-50 B 0-100%

Q. STEAM FLOW E-SO B O TO 5.76E+6 LB PER HOUR R. FEED FLOW E-50 B 0 TO 5.76E+6 LB PER HOUR S. T-AVERAGE 0-625 DEG F.

T. PRESSURIZER WATER TEMP. 0~1000 DEG F.

In addition to the parameters listed above, the following items were also tested to verify simulato~ stability and accuracy.

A. VARIOUS STATION POWER SUPPLY BREAKER TRIP/UNDERVOLTAGE ALARMS B. PRESSURIZER HEATER STATUS INDICATION C. FEEDPUMP SUCTION PRESSURE E.28

SIMULATOR TEST T002 ABSTRACT

D. FEEDPUMP HIGH PRESSURE/LOW PRESSURE THROTTLE & TRIP VALVE INDICATION E. GENERATOR BREAKER STATUS F. STATION POWER AND START-UP POWER BREAKER STATUS INDICATION G. DIESEL GENERATOR STATUS INDICATION H. POWER LEVEL AND START-UP RATE I. AUX FEEDPUMP STATUS, FLOW AND PRESSURE J. STEAM GENERATOR LEVEL K. PRESSURIZER LEVEL AND PRESSURE L. PCS/CORE DELTA TEMPERATURE AND AVERAGE TEMPERATURE M. CONTROL ROD POSITION INDICATION N. C AND D BUS VOLTAGE O. BATTERY CHARGERS TROUBLE ALARM P. 125V DC BUS UNDERVOLTAGE/TROUBLE ALARM Q. SERVICE WATER PRESSURE AND PUMP INDICATION R. COMPONENT COOLING WATER PRESSURE, TEMPERATURE AND PUMP INDICATION S. COMPRESSED AIR STATUS T. SUBCOOLED MARGIN MONITOR U. CONTAINMENT INTEGRITY: PRESSURE, TEMPERATURE AND RADIATION

s. INITIAL CONDITIONS Initial condition was IClO, plant at full power condition.

6* FINAL CONDITIONS/DURATION OF TEST Final condition was plant at hot shutdown.

This test required approximately 1/2 hour to complete.

7. BASELINE DATA The baseline data is from actual Plant Trip Report dated October, 28, 1982; Palisades plant operating procedure EOPl; and subject matter experts.

8. DEFICIENCIES The following simulator deficiencies were noted during performance of this test.

A. DIESEL GENERATOR STATUS LIGHTS SDR-89-007 B. PRESSURIZER PRESSURE SDR-89-047 C. STEAM GENERATOR LEVEL SDR-89-040 The simulator deficiency reports SDR-89-007 and SDR-89-040 have been corrected; SDR-89-047 is scheduled to be co.rrected as indicated in the "Paltrack" report listing.

9. EXCEPTIONS TO ANSI/ANS~3.S-1985

No exceptions taken.

E. 29

T003 SIMULTANEOUS CLOSURE OF ALL MAIN STEAM ISOLATION VALVES

ANS-3.5-1985 RELATIONSHIP B2.2 (3)

SIMULATOR TEST T003 ABSTRACT NAME AND DESCRIPTION OF TEST T003 is a simulator performance test that involves the closure of all main steam isolation valves transient, a full power

reactor trip resulting from a loss of heat sink, (MSIVs closed without a turbine trip). This evolution was accomplished following applicable Palisades' standard operating procedures (SOP) and emergency operating procedures (EOP). The normal plant equipment was simulated to be in service and/or operable per SOP'S.

2. ANSI/ANS,-3.5-1985 RELATIONSHIP Appendix B, B2.2(3)

3. TEST DATES T003 was conducted in March, 1989.

4. TESTED PARAMETERS The parameters and their ranges monitored by strip chart, with.

a resolution of 0.5 seconds, are as follows:

Parameter Instrumentation Ranges

A.

B.

C.

D.

E.

F.

PRESSURIZER LEVEL

1 HOT LEG TEMP.

1 COLD LEG TEMP.

PCS FLOW.

CONTAINMENT PRESSURE CONTAINMENT TEMP.

0-100%

0-615 DEG F.

0-600 DEG F.

0-100%

0-100 PSIA.

0-400 DEG F.

G. #2 HOT LEG TEMP. 0-615 DEG F.

H. #2 COLD LEG TEMP. 0-600 DEG F.

I. PRESSURIZER PRESSURE 1500-2500 PS;I:A.

J. STM. GEN. PRESS. E-50 A 0-1000 PSIA.

K. STM. GEN. LEVEL E-50 A 0-100%

L. WIDE RANGE LOG (#3) (NI) 1.0E-8% TO 125% FULL POWER M. STEAM FLOW E-50 A .o TO 5.76E+6 LB PER HOUR N. FEED FLOW E-50 A 0 TO 5.76E+6 LB PER HOUR O. STM. GEN. PRESS. E-50 B 0-1000 PSIA.

P. STM. GEN. LEVEL E-50 B 0-100%

Q. STEAM FLOW E-50 B 0 TO 5.76E+6 LB PER HOUR R. FEED FLOW E-50 B 0 TO 5.76E+6 LB PER HOUR S. T-AVERAGE 0-625 DEG F.

T. PRESSURIZER WATER TEMP. 0-1000 DEG F.

In addition to the parameters listed above, the following items were also tested to verify simulator stability and accuracy .

A. MSIV POSITION INDICATION B. STEAM GENERATOR PRESSURE AND LEVEL E.30

SIMULATOR TEST T003 ABSTRACT

c. PCS TEMPERATURE D. PRESSURIZER LEVEL E. REACTOR TRIP ALARM

F. CONTROL ROD POSITION .

G. REACTOR POWER. AND START-UP RATE INDICATION H. RPS CLUTCH POWER SUPPLY INDICATION I. FEEDPUMP HIGH PRESSURE AND LOW PRESSURE TRIP AND THROTTLE VALVE POSITION J. FEEDPUMP SPEED INDICATION .

K. TURBINE STOP AND CONTROL VALVE POSITION INDICATION L. GENERATOR BREAKER INDICATION M. STATION POWER/START-UP POWER BREAKER INDICATION N. DIESEL GENERATOR STATUS LIGHTS AND FREQUENCY INDICATION

o. PRESSURIZER HEATER INDICATION P. SUBCOOLED MARGIN MONITOR INDICATION Q. AUX FEEDWATER PUMP STATUS, PRESSURE AND FLOW INDICATION S. INITIAL CONDITIONS Initial condition was IClO, plant at full power condition.

6. FINAL CONDITIONS/DURATION OF TEST Final condition was plant at hot shutdown.

7.

This test required approximately 3/4 hour to complete .

BASELINE DATA The *baseline data is from actual Plant Trip Report dated May*

19, 1986; and subject matter experts.

8. DEFICIENCIES The following simulator deficiency was noted during performance of this test:

A. DIESEL GENERATOR STATUS LIGHTS SDR-89-007 This simulator deficiency report (SOR) has been corrected.

9. EXCEPTIONS TO ANSI/ANS-3.5-1985 No exceptions taken .

E.31

T004 SIMULTANEOUS TRIP OF ALL REACTOR COOLANT PUMPS ANS-3.5-1985 RELATIONSHIP B2.2 (4)

, I

SIMULATOR TEST T004 ABSTRACT

1. NAME AND DESCRIPTION OF TEST T004 is a simulator performance test that involves a primary coolant pumps trip transient; a full"power reactor trip initiated by a lo~ flow condition resulting from the simultaneous trip of all four primary coolant pumps. This evolution was accomplished following applicable Palisades' standard operati~g procedures (SOP) and emergency operating procedures (EOP). The normal plant equipment was simulated to be in service and/or operable per SOP's.

2. ANSI/ANS-3.5-1985 RELATIONSHIP Appendix B, B2.2(4)

3. TEST DATES T004 was conducted in March, 1989.

4. TESTED PARAMETERS The parameters and their ranges monitored by strip chart, with

a resolution of 0.5 seconds, are as follows:

Parameter Instrumentation Ranges

A.

B.

C.

D.

E.

PRESSURIZER LEVEL

1 HOT LEG TEMP.

1 COLD LEG TEMP.

PCS FLOW CONTAINMENT PRESSURE 0-100%

0-615 DEG F.

0-600 DEG F.

0-100%

0-100 PSIA.

F. CONTAINMENT TEMP. 0-400 DEG F.

G. #2 HOT LEG TEMP. 0-615 DEG F.

H. #2 COLD LEG TEMP. 0-600 DEG F.

I. PRESSURIZER PRESSURE 1500-2500 PSIA.

J. STM. GEN. PRESS. E-50 A 0-1000 PSIA.

K. STM. GEN. LEVEL E-50 A 0-100%.

L. WIDE RANGE LOG (#3) (NI) l.OE-8% TO 125% FULL POWER M. STEAM FLOW E-50 A 0 TO 5.76E+6 LB PER HOUR N. FEED FLOW E-50 A O TO 5.76E+6 LB PER HOUR

0. STM. GEN. PRESS. E-50 B 0-1000 PSIA.

P. STM. GEN. LEVEL E-50 B 0-100%

Q. STEAM FLOW E-50 B 0 TO 5.76E+6 LB PER HOUR R. FEED FLOW E-50 B 0 TO 5.76E+6 LB PER HOUR S. T-AVERAGE 0-625 DEG F.

T. PRESSURIZER WATER TEMP. 0-1000 DEG F.

In addition to the parameters listed above, the following items were also tested to verify simulator stability and accuracy *

A. R BUS STATUS INDICATION AND SWITCHYARD ALARMS B.. COOLING TOWER AND CONDENSER STATUS AND ALARMS E.32

SIMULATOR TEST T004 ABSTRACT

C. REACTOR TRIP ALARM D. CONTROL ROD STATUS (POSITION INDICATION)

E. RPS STATUS (POWER SUPPLY INDICATION)

F. REACTOR POWER LEVEL G. PRIMARY COOLANT PUMP STATUS, ON/OFF INDICATION AND AMPS H. GENERATOR FIELD BREAKER STATUS I. DIESEL GENERATOR STATUS J. CONTROL ROOM LIGHTING K. BUS lA AND lB STATUS, BREAKER INDICATION AND VOLTAGE L. NATURAL CIRCULATION VERIFICATION: CORE EXIT THERMOCOUPLES, PCS T/COLD AND SUBCOOLING INDICATION

5. INITIAL CONDITIONS Initial condition was IClO, plant at full-power condition.

6. FINAL CONDITIONS/DURATION OF TEST Final condition was plant at hot shutdown.

This test required approximately 3/4 hour to complete.

7. BASELINE DATA The baseline 4ata is from Emergency Operating Procedures (EOP)

a.

1 and 8, Alarm Response Procedures (ARP) 4 and 5, and subject matter experts.

DEFICIENCIES The following simulator deficiency was noted during performance of this test.

A. DIESEL GENERATOR STATUS LIGHTS SDR-89-007 This simulator deficiency report (SOR) has been corrected.

9. EXCEPTIONS TO ANSI/ANS-3.5-1985 No exceptions taken.

E.33

TOOS TRIP OF ANY SINGLE REACTOR COOLANT PUMP ANS-3.5-1985

RELATIONSHIP .

B2.2 (5)

SIMULATOR TEST T005 ABSTRACT

1. NAME AND DESCRIPTION OF TEST T005 is a simulator performance test that involves a primary coolant pump transient; a full power reactor trip initiated by a low flow condition resulting from the trip of a single primary coolant pump. This evolution was accomplished following applicable Palisades' standard operating procedures (SOP) and emergency operating procedures (EOP). The normal plant equipment was simulated to be in service and/or operable per SOP's.

2. ANSI/ANS-3.5-1985 RELATIONSHIP Appendix B, B2.2(5)

3. TEST DATES T005 was conducted in March, 1989.

4. TESTED PARAMETERS The parameters and the1r ranges monitored by strip chart, with a resolution of 0.5 seconds, are as follows:

Parameter Instrumentation Ranges

A.

B.

C.

D.

E.

PRESSURIZER LEVEL

1 HOT LEG TEMP.

1 COLD LEG TEMP.

PCS FLOW CONTAINMENT PRESSURE 0-100%

0-615 DEG F.

0-600 DEG F *.

0-100%

0-100 PSIA.

F. CONTAINMENT TEMP. 0-400 DEG F.

G. #2 HOT LEG TEMP. 0-615 DEG F~

H. #2 COLD LEG TEMP. 0-600 DEG F.

I. PRESSURIZER PRESSURE. 1500..-2500 PSIA.

J. STM. GEN. PRESS. E~5o A 0-1000 PSIA.

K. STM. GEN. LEVEL E-50 A 0-100%

t. WIDE RANGE LOG (#3) (NI) 1.0E-8% TO 125% FULL POWER M. STEAM FLOW E-50 A 0 TO S.76E+6 LB PER HOUR N. FEED FLOW E-50 A 0 TO 5.76E+6 LB PER HOUR O. STM. GEN. PRESS. E-50 B 0-1000 PSIA.

P. STM. GEN. LEVEL E-50 B 0-100%

Q. STEAM FLOW E-50 B 0 TO 5.76E+6 LB PER HOUR R. FEED FLOW E-50 B 0 TO 5.76E+6 LB PER HOUR S. T-AVERAGE 0-625 DEG F.

T. PRESSURIZER WATER TEMP. 0-1000 DEG F.

In addition to the parameters listed above, the following items were alsotested to* verify simulator stability and accuracy *

A. PCP STATUS INDICATION: LIGHTS AND AMPERES B. RPS TRIP INDICATION E.34

SIMULATOR TEST TOOS ABSTRACT C. REACTOR TRIP ALARM D. AUX FEEDWATER FLOW E. STEAM GENERATOR LEVEL F. PCS/PRESSURIZER LEVEL AND PRESSURE G. SAFETY INJECTION SYSTEM/PUMPS, VALVES AND ALARMS H. SERVICE WATER.PUMPS STATUS I. COMPONENT COOLING WATER PUMPS STATUS

s. INITIAL CONDITIONS Initial condition was IClO, plant at fu~l power condition.

6. FINAL CONDITIONS/DURATION OF TEST Final condition was plant at hot shutdown.

This test required approximately 1/2 hour to complete.

7. BASELINE DATA The baseline data is from actual Plant Trip Report dated February 1, 1979 and Zero Power Test Report - 7; and subject matter'experts.

8. DEFICIENCIES

The following simulator deficiencies were noted during performance of this test.

A. RPS TRIP LIGHTS SDR-89-049 B. STEAM GENERATOR LEVEL INDICATION SDR-89-050 These simulator deficiency reports (SOR) are scheduled to be .*

corrected as indicated in the "Paltrack" report listing.

9. EXCEPTIONS TO ANSI/ANS-3.5-1985 No exceptions taken *

E. 35

T006 MAIN TURBINE TRIP (MAXIMUM POWER LEVEL WHICH DOES NOT RESULT IN IMMEDIATE REACTOR TRIP)

ANS-3.5-1985

RELATIONSHIP B2.2 (6)

SIMULATOR TEST T006 ABSTRACT

~* 1. NAME AND DESCRIPTION OF TEST T006 is a simulator performance test that involves a turbine trip without a.direct reactor trip transient; a full power trip of the main turbine generator without a direct trip of the reactor. This evolution was accomplished following applicable Palisades' standard operating procedures (SOP) and emergency operating procedures (EOP). The normal plant equipment was simulated to be in service and/or operable per SOP's.

2. ANSI/ANS-3.5-1985 RELATIONSHIP Appendix B, B2.2(6)

3. TEST DATES T006 was conducted in March, 1989.

4. TESTED PARAMETERS The parameters and their ranges monitored by strip chart, with a resolution of 0.5 seconds, are as follows:

Parameter* Instrumentation Ranges A. PRESSURIZER LEVEL 0-100%

B. #1 HOT LEG TEMP. 0-615 DEG F~

C. #1 COLD LEG TEMP. 0-600 DEG F.

D. PCS FLOW 0-100%

E. CONTAINMENT PRESSURE 0-100 PSIA.

F. CONTAINMENT TEMP. 0-400 DEG F.

G. #2 HOT LEG TEMP. 0-615 DEG F.

H. #2 COLD LEG TEMP. 0-600 DEG F.

I. PRESSURIZER PRESSURE 1500-2500 PSIA.

J. STM. GEN. PRESS. E-50 A 0-1000 PSIA.

K. STM. GEN. LEVEL E-5o*A 0-100%

L. WIDE RANGE LOG (#3) (NI) l.OE-8% TO 125% FULL POWER M. STEAM FLOW E-50 A 0 TO 5.76E+6 LB PER HOUR N. FEED FLOW E-50 A 0 TO 5.76E+6 LB PER HOUR

0. STM. GEN. PRESS. E-50 B 0-1000 PSIA.

P. STM. GEN. LEVEL E-50 B 0-100%

Q. STEAM FLOW E-50 B 0 TO 5.76E+6 LB PER HOUR R. FEED FLOW E-50 B 0 TO 5.76E+6 LB PER HOUR S. T-AVERAGE 0-625 DEG F.

T. PRESSURIZER WATER TEMP. 0-1000 DEG F.

In addition to the parameters listed above, the following items were also tested.to verify simulator stability and accuracy.

A. STEAM GENERATOR LEVEL B. PCS TEMPERATURE C. PRESSURIZER LEVEL AND PRESSURE E.36

SIMULATOR TEST T006 ABSTRACT D. RPS. STATUS E. CONTROL ROD POSITION F. AUX FEEDWATER FLOW

s. INITIAL CONDITIONS Initial condition was IClO, plant at full p*ower condition.

6. FINAL CONDITIONSjDURATION OF TEST Final condition was plant at hot shutdown.

This test required approximately 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to complete.

7. BASELINE DATA The baseline data is from actual Plant Trip Report dated January 26, 1983 and a Transient Analysis of full load rejection without a direct reactor trip (ref. A-NT-88-02).

8.

DEFICIENCIES The following simulator deficiency was noted during performance of this test. '

9.

A. PRESSURIZER PRESSURE SDR-89-047 This simulator deficiency report (SOR) is scheduled to be corrected as indicated in the "Paltrack" report listing.

EXCEPTIONS TO ANSI/ANS-3.5-1985 No exceptions taken.

~-

E.37

'i

T007 MAXIMUM RA TE POWER RAMP (lOOo/o DOWN TO APPROXIMATELY 75%AND BACK UP TO 100%)

ANS-3.5-1985 .

RELATIONSHIP B2.2 (7)

SIMULATOR TEST TOO? ABSTRACT

1. NAME AND DESCRIPTION OF TEST TOO? is a simulator performance test that involves a maximum rate load change transient; beginning at full power, ramping down to 75% full power at a rate of 200% per minute, then ramping up to full power. This evolution was accomplished following applicable Palisades' standard operating procedures (SOP) and emergency operating procedures (EOP). The normal plant equipment was simulated to be in service and/or operable per SOP's.

2. ANSI/ANS-3.5-1985 RELATIONSHIP Appendix B, B2.2(7)

3. TEST DATES T007 was conducted in March, 1989~

4. TESTED PARAMETERS The parameters and their ranges monitored by strip chart, with a resolution of 0.5 seconds, are as follows:

Parameter Instrumentation Ranges

A. PRESSURIZER LEVEL B. #1 HOT LEG TEMP.

C. #1 COLD LEG TEMP.

D. PCS FLOW E. CONTAINMENT PRESSURE 0-100%

0-615 DEG F.

0-600 DEG F.

0-100%

0-100 PSIA.

F ** CONTAINMENT TEMP. 0-400 DEG.F.

G. #2 HOT LEG TEMP. 0-615 DEG F.

H. #2 COLD LEG TEMP. 0-6oo*DEG F.

I. PRESSURIZER PRESSURE 1500-2500 PSIA.

J. STM. GEN. PRESS. E-50 A 0-1000.PSIA.

K. STM. GEN. LEVEL E-50 A 0-100%

L. WIDE RANGE LOG (#3) (NI) 1.0E-8% TO 125% FULL POWER M. STEAM FLOW E-50 A OTO 5.76E+6 LB PER HOUR N. FEED FLOW E-50*A 0 TO 5.76E+6 LB PER HOUR O. STM. GEN. PRESS. E-50 B 0-1000 PSIA.

P. STM. GEN. LEVEL E-50 B 0-100%

Q. STEAM FLOW E-50 B 0 TO 5.76E+6 LB PER HOUR R. FEED FLOW E-50 B 0 TO 5.76E+6 LB PER HOUR S. T-AVERAGE 0-625 DEG F.

T. PRESSURIZER WATER TEMP. 0-1000 DEG F.

In addition to the parameters listed above, the following items were also tested to verify simulator stability and accuracy .

A. PCS.TEMPERATURE B. PRESSURIZER PRESSURE AND LEVEL E~38

SIMULATOR TEST T007 ABSTRACT C. STEAM GENERATOR LEVEL AND PRESSURE D. REACTOR POWER

s. INITIAL CONDITIONS Initial condition was IClO, plant at full power condition.

6. FINAL CONDITIONS/DURATION OF TEST The final conditions for this test was the plant at full power with normal plant equipment in service and/or operable.

This test required approximately 1/2 hour to complete.

7* BASELINE DATA The baseline data is actual plant 60% Power Test Report - 9.

8. DEFICIENCIES

.None.

9. EXCEPTIONS TO ANSI/ANS-3.5-1985 No exceptions taken .

E.39

TOOS MAXIMUM SIZE UNISOLABLE

MAIN STEAM LINE RUPTURE

ANS-3.5-1985 RELATIONSHIP B2.2 (9)

SIMULATOR TEST TOO& ABSTRACT

1.. NAME AND DESCRIPTION OF TEST T008 is a simulator performance test that.involves a*main steam line break transient; beginning at full power and invoking an unisolable main steam line break. This evolution was accomplished following applicable Palisades' standard operating procedures (SOP) and emergency operating procedures (EOP). *The normal plant equipment was simulated to be in service and/or operable per SOP's.

2. ANSI/AN~-3.5-1985 RELATIONSHIP 3.1.2 (15), (16), (19) and (2.0)

Appendix B, B2.2(9)

3. TEST DATES T008 was conducted in March, 1989.

4. TESTED PARAMETERS The parameters and their ranges monitored by strip chart, with a resolution of 0.5*seconds, are as follows:

Parameter Instrumentation Ranges A *. PRESSURIZER LEVEL 0-100%

B. #1 HOT LEG TEMP. 0-615 DEG F.

C. #1 COLD LEG TEMP. 0-600 DEG F.

D. CONTAINMENT SUMP LEVEL 0-66 INCHES E. CONTAINMENT PRESSURE 0-100 PSIA.

F. CONTAINMENT TEMP. 0-400 DEG F.

G. #2 HOT LEG TEMP. 0-615 DEG F.

H. #2 COLD LEG TEMP. *o-600 DEG F.

I. PRESSURIZER PRESSURE 1500-2500 PSIA.

J. STM. GEN. PRESS. E-50 A 0-1000 PSIA.

K. STM. GEN. LEVEL E-50 A 0-100%

L. WIDE RANGE LOG (#3) (NI) 1.0E-8% .TO 125% FULL POWER M. STM. GEN. "A" STEAM FLOW 0 TO 5.76E+6 LB PER HOUR N. CONTAINMENT WATER LEVEL 0-90 INCHES ABOVE 590' 4.25" O. STM. GEN. PRESS. E-50 B 0-1000 PSIA.

P. STM. GEN. LEVEL E-50 B 0-100%

Q. STM. GEN. "B" STEAM FLOW 0 TO 5.76E+6 LB PER HOUR R. SI.REFUELING WATER TANK LEVEL 0~100%

S. PRESSURIZER PRESSURE 0-2500 PSIA T. REACTIVITY RHO < 0.5 TO RHO > 0.5 In addition to the parameters listed above, the following items were also tested to verify simulator stability and accuracy.

A. REACTOR.POWER LEVEL B. AVERAGE TEMPERATURE/REFERENCE TEMPERATURE C. STEAM GENERATOR PRESSURE AND LEVEL E *.40

SIMULATOR TEST T008 ABSTRACT D. PRESSURIZER PRESSURE AND LEVEL E. MAIN FEEDWATER SYSTEM STATUS F. TURBINE CONTROLS G. DIESEµ GENERATOR CONTROLS AND STATUS H. eves CONTROLS AND STATUS I. SUBCOOLED MARGIN MONITOR

s. INITIAL CONDITIONS Initial condition was IC20, plant at full power condition~

6. FINAL CONDITIONS/DURATION OF TEST Final condition was plant at hot shutdown *

.This test required approximately 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to complete.

7. BASELINE DATA The baseline data is from General Operating Procedures (GOP) 5 and 6, Standard Operating Procedure (SOP) a, Alarm Response Procedures (ARP) 1 and 2, Off Normal Procedure (ONP) 9, and subject matter experts.

8* DEFICIENCIES

9.

None.

EXCEPTIONS TO ANSI/ANS-3.5-1985 No exceptions taken *

E.41

T009 MAXIMUM SIZE REACTOR COOLANT SYSTEM RUPTURE COMBINED Wl*TH .LOSS OF ALL OFFSITE POWER

- ANS-3.5-1985 RELATIONSHIP B2.2 (8)

SIMULATOR TEST T009 ABSTRACT NAME AND DESCRIPTION OF TEST T009 is a simulator- -performance test that involves a large break loss of coolant accident without standby power transient.

This evolution was accomplished following applic.able Palisades' standard operating procedures (SOP) and emergency operating procedures (EOP). The normal plant equipment was simulated to be in service and/or operable per SOP's.

2. ANSI/ANS-3.5-1985 RELATIONSHIP 3.1.2 (lb), (le), (3), (15), (16) and (19)

Appendix B, B2.2(8)

3. TEST DATES T009 was conducted in March, 1989.

4. TESTED PARAMETERS The parameters and their ranges monitored by strip chart, with a resolution of 0.5 seconds, are as follows:

Parameter Instrumentation Ranges

A.

B.

C.

D.

E.

F.

PRESSURIZER LEVEL

1 HOT LEG TEMP.

1 COLD LEG TEMP.

CONTAINMENT SUMP LEVEL CONTAINMENT PRESSURE CONTAINMENT TEMP.

0-100%

0-615 DEG F.

0-600 DEG F.

0-66 INCHES 0-100 PSIA.

0-400 DEG F.

G. #2 HOT LEG TEMP. 0-615 DEG F.

H. #2 COLD LEG TEMP. 0-600* DEG F *.

I. PRESSURIZER PIIB,SSURE 1500-2500 PSIA.

J. STM. GEN. PRESS. E-50 A 0-1000 PSIA.

K. STM.- GEN. LEVEL E-50 A 0-100%

L. WIDE RANGE LOG (#3) (NI) l.OE-8% TO 125% FULL POWER M. PCS ENTHALPY 0-1000. BTU PER POUND N. CONTAINMENT WATER LEVEL 0-90 INCHES ABOVE 590' 4.25" O. PRESSURIZER LIQUID TEMPERATURE 0-1000 DEG F.

P. PCS INLET FLOW 0~100%

Q. REACTOR WATER LEVEL 0-50 FEET R. SI REFUELING WATER TANK LEVEL 0-100%

S. SUBCOOLED MARGING MONITOR 0-500 DEG F.

T. RAD MONITOR (RIA 1805) l-10.0E+7 MR/HOUR In addition to the parameters listed above, the following items were also tested to verify simulator stability and accuracy *

A. SAFETY INjECTION SYSTEM TANK LEVELS, VALVE POSITION AND PUMP STATUS E.42

SIMULATOR TEST T009 ABSTRACT

- B. DIESEL GENERATOR STATUS: INDICATING LIGHTS, FREQUENCY AND VOLTAGE C. SWITCHYARD STATUS D. lC AND lD BUS VOLTAGE E. eves STATUS AND CHARGING PUMP INDICATION F. BORIC ACID PUMP STATUS G. SERVICE WATER PUMP STATUS H. COMPONENT COOLING WATER PUMP STATUS I. CONTAINMENT AIR COOLER STATUS J. CONTAINMENT SPRAY PUMP STATUS K. CONTAINMENT ISOLATION STATUS

5. INITIAL CONDITIONS Initial condition was IClO, plant at full power condition.

6. FINAL CONDITIONS/DURATION OF TEST Final condition was plant at hot shutdown.

This test required approximately 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to complete.*

7. BASELINE DATA The baseline data is from Palisades plant operating procedure

EOP4; plant electrical drawing E209; and subject matter experts.

8 *. DEFICIENCIES The following simulator deficiency was noted during performance of this test.

A. DIESEL GENERATOR STATUS LIGHTS SDR-89-007 This simulator deficiency report (SDR) has been corrected.

9. EXCEPTIONS TO ANSI/ANS-3.5-1985 No exceptions taken *

E.43

T010 SLOW PRIMARY SYSTEM DEPRESSUR-IZA TION TO SATURATED CONDI-TION USING PRESSURIZER RELIEF OR SAFETY VAL VE STUCK OPEN and LOSS OF ALL FEEDW ATER (NORMAL AND EMERGENCY)

ANS-3.5-1985 RELATIONSHIP B2.2 (10) and 3.1.2 (10)

SIMULATOR TEST T010 ABSTRACT NAMB AND DESCRIPTION OF TEST TOlO is a simulator performance test that involves a failed open pressurizer relief valve transient: a slow depressurization to saturation conditions, with no initial

. input from the high pressure safety injection pumps. This evolution was accomplished following applicable Palisades' standard operating procedures (SOP) and emergency operating procedures (EOP). The normal plant equipment was simulated to be in service and/or operable per SOP's.

2. ANSI/ANS-3.5-1985 RELATIONSHIP 3.1.2 (10)

Appendix B, B2.2(10) 3* TEST DATES TOlO was conducted in March, 1989.

4. TESTED PARAMETERS The parameters and their ranges monitored by_strip chart, with a resolution of o.5_seconds, are as follows:

Parameter A.

B.

C.

D.

PRESSURIZER LEVEL

1 HOT LEG TEMP.

1 COLD LEG TEMP.

CONTAINMENT SUMP LEVEL Instrumentation Ranges 0-100%

0:-615 DEG F.

0-600 DEG F.

0-66 INCHES E. CONTAINMENT PRESSURE 0-100 PSIA.

F. CONTAINMENT TEMP. 0-400 DEG F.

G. #2 HOT LEG TEMP. 0-615 DEG F.

H. #2 COLD LEG TEMP. 0-600 DEG F.

I. PRESSURIZER PRESSURE 1500-2500 PSIA.

J. STM.

GEN. "A" PRESSURE 0-1000 PSIA.

K. STM. GEN. "A" LEVEL 0-100%

L. REACTIVITY RHO = -0.5 TO RHO = +0.5 M. PCS VOIDS 0-1 N. STM. GEN. "B" LEVEL 0-100%

O. PRESSURIZER LIQUID TEMPERATURE 0-1000 DEG F.

P. PCS INLET FLOW 0-100%

Q. REACTOR WATER LEVEL 0-50 FEET R. AUDIBLE COUNTRATE INPUT 0-5000 CPS S. SUBCOOLED MARGIN MONITOR 0-500 DEG F.

T. PRESSURIZER MOV FLOW (1042/3) 0~1ao,ooo LB/HOUR In addition to the parameters listed above, the following items were also tested to verify simulator stability and accuracy .

A. HPSI PUMP STATUS B. PRESSURIZER POWER OPERATED RELIEF VALVES STATUS E.44

SIMULATOR TEST T010 ABSTRACT C. ELECTRO HYDRAULIC PUMP STATUS D. RPS REACTOR TRIP STATUS AND ALARM E. RPS PRESSURIZER HIGH PRESSURE PRE-TRIP AND TRIP ALARMS F. SAFETY VALVE AND/OR PRESSURE OPERATED RELIEF VALVE (PORV)

OPEN ALARM

5. INITIAL CONDITIONS Initial condition was IClO, plant at full power condition.

6. FINAL CONDITIONS/DURATION OF TEST Final condition was plant at hot shutdown.

This test required approximately 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to complete *

. 7. BASELINE DATA The baseline data is from the FSAR Section 14.17, Emergency Operating Procedures (EOP) 1 and 4, Alarm Response Procedures

.CEOP) 4 and 5, and subject matter experts. *

8. DEFICIENCIES None.

9. EXCEPTIONS TO ANSI/ANS-3. 5-1985 No exceptions taken~

E. 45

-., MALFUNCTION TESTS

====================================================

ANS-3.5-1995 CPCO PAGB RELATIONSHIP ~ NUMBER 3.1.2 (1) (a) M185 B.62 3.1.2 {l) {b} M024* B.49 3.1.2 (1) (c} M027* B.50 3.1.2 (1) (d) M117* B.57 3.1.2 (2) MOOl* E.47 3.1.2 (3) M002* B.47 3.1.2 (4) M006* B.48 3.1.2 (5) M043* B.51 3.1.2 (6) M197* B.62 3.1.2 (7) M196 B.62 3.1.2 (9) M017* B.49 3.1.2 (9) M063* B.53 3.1.2 (10) TOlO B.44 - B.45 3.1.2 (11) M057 B.52 3.1.2 (12) M124* E.58 3.1.2 (13) M129* B.58 3.1.2 (14) M120 B.58 3.1.2 (15) M045* B.51 3.1.2 (16) MOSS* B.53 3.1.2 (17) M071* B.54 3.1.2 (18) M181* B.61 3.1.2 (19) M066* B.53 3.1.2 (20) M088* B.55 3.1.2 (21) M140* B.59 3.1.2 (22) M205* B.63 3.1.2 (23) MllO* B.57 3.1.2 (24) M159 B.60 3.1.2 (25) N/A BWR

===========================================================?

Indicates there is more than one CPCO Malfunction Test that addresses the ANS-3.5-1985 requirement. For a complete

.)

listing, refer to reverse side.

~=========================================================

ANS-3.5-1985 CPCO E:BI1ATIQNSHI~ ~

. ~-*

3.1.2 (1) (a) M185 3.1.2 (1) (b) M024, M026, M027, M028, M032, M033, MOS2, MlOO, Ml20, T009 3.1.2 {1) {c) M024, M027, MOS2, MlOl, M102, M134, .T009 3.1.2 (1) (d) M117 I M118 3.1.2 (2) MOOl, M082, M201 3.1.2 (3) M002, MOOS, M009, M014, M04S-MOS6, MOS7.S, T009 3.1.2 (4) M006, M047, M104-M107 I M109, M114 3.1.2 (S) M043, M063 3.1.2 (6) MOOl, MOS?, M082, M197, Ml98, M200, M201-M203 3.1.2 (7) .M196 3.1.2 (8) MOOl, M017 I M019, MOS?, Ml09, M201 3.1.2 (9) M0~3, :M066, M068, M071, M072, M073, M075 3.1.2 (10) TOlO

. 3.1.2 (11) MOS?

3.1.2 (12) M1*24-M134 3.1.2 (13) M128, M130, M131 3.1.2 {14) M120 3.1.2 {lS) !(007, M043, M045, M046, M058, M059, M062, M063, M066, M071, M072, M073, M092, M204, 3.1.2 (16)

M205, M219, T008, T009 MOOS, M043, M045, M046, MOSS, MOS9, M062, ~*

M063, M066, M071-M073, M204, T008, T009 3.1.2 (17) MOlO, MOll, M036, M037, M057, Mb62, M071, M072, M073, MOSS, M122-M126, M191-Ml93 3.1.2 (18) M174-M178, M181, M182 3.1~2 (19) M006, M042, M045, M046, M052, MOSS, M059, M062, M066, M06S, M071-M073, M075, MOS2, M086, M088, M094, M102, M104, M106, M126, M160, M185, M204, M207, M215, TOOS, T009

. 3.1.2 (20) M071, M072, M073, MOSS, M088-M090, TOOS 3.1.2 (21) M140-M158 3~1.2 (22) M002, M005-M007, M010-M019, M022, M031, M032, M034, M035, M038, M039, M041-M044, M051-M053, M060-M062, M068-M070, M086, M091-M09S, M108, MllS, Mll6, M136-M139, M159-M184, M191-M193, M205-M208, M211-M213, M216 3.1.2 (23) M002-M004, M014, M020, M021, M025, M029, M030, M036, M037, M051-M053, M057, M076-M084, M103, M110-M114, M135, M186-M190, M194-M196, M20S, M215, M217-M221 3.1.2 (24) . M158 3.1.2* (25) N/A BWR

~==~==================================================

- MALFUNCTION TESTS ACCEPTANCE CRITERIA A. If applicable, parameters must meet acceptance criteria of plant Startup Tests.

B. Parameter values must change in same direction as expected for.

same transient on the plant, and not violate physical laws .

C. Alarms and Auto Actions must occur only as expected for the same transient on the plant .

E.46

SIMULATOR TESTS MOOl - M221 ABSTRACT.

1. HAMB AND DESCRIPTION O~ TEST MOOl through M221 are malfunction tests that test various aspects of all the malfunctions that were available on the Palisades simulator as of June, 1988. Malfunctions added after this date were tested and accepted in accordance with approved simulator modification procedures.

2. AHSI/AHS-3.5-1985 RELATIONSHIP 3.1.2 (1)-(9) and (11)-(2S). See Transient Test TOlO for (10).

3. TEST DATES MOOl - M221 were conducted between November 1988 and March 1989.

4. AVAILABLE OPTIONS A listing of the malfunctions available on the Palisades simulator-and the options available for each malfunction are identified in the "PALISADES SIMULATOR INDEX OF MALFUNCTIONS",

included with this submittal on pages D.4 - D.11.

5. TESTED OPTIONS Following is a list.of the Malfunction tests and the options that*

were tested~ The "OPTIONS TESTED" relate to the available options as listed in the "INDEX OF MALFUNCTIONS" on p~ges D.4 -

D.11.

ANSI-3.S OPTIONS TEST 3.1.2 ~. ~ TE STEP PABAMETERS/SXSTEMS MONITORED MOOl (2) 10 ANOl 1 *icoNT INSTRUMENT AIR PRESS" (6) 37 "SERVICE WATER PUMP TRIP"

.< 8) 72 "CCW SURGE TANK HI/LO LEVEL" M002 (23) 10 AN02 1 "SHIELD COOLING PUMPS TRIP" (3) 11 & 32 "SAFETY INJECTION BLOCK RELAX" (22) 78 "CONT ISOL & SI RIGHT SIDE CONTROL CIRCUIT UNDERVOLTAGE" M003 (23) 10 ANOJ 2 11 CONT COOLER RECIRC FAN V-4A" 12 "BORIC ACID GRAVITY FEED M0-2170" M004 (23) 10 AN04 3 "CHARGING PUMP PSS-A" 13 "HP SI PUMP P66-A" MOOS (22) *10 ANOS 1 "REGEN HX TUBE OUTLET HI TEMP" 36 "BORIC ACID CRITICAL HEAT TRACE SYSTEM TROUBLE" 72 "LOOP #2 HOT LEG HI TEMPERATURE"

- E.47

SIMULATOR TESTS M001 - M221 ABSTQCT ANSI-3.5 OPTIONS

ll.§..'.I M006 3 .1. 2 (4)

(22)

(19)

~

10

~

AN06 TESTED 1

36 72 PABAMETERS/SXSTEffS MONITORED "PCP P-SOA TRIP" "GROUP #3 POWER DEPENDENT INSERTION LIMIT" "REACTOR TRIP" M007 (15) 10 AN07 1 "TURBINE TRIP" (22) 36 . "DIRTY AND/OR CLEAN OIL STORAGE TANK HIGH LEVEL" 72 "MOISTURE SEPARATOR DRAIN TANK TS HIGH HP-LOW LEVEL" MOOS (16) 10 ANOS 1 "GENERATOR TRIP" (3) 15 "GENERATOR FIELD GROUND" 36 "SWITCHYARD ACB TRIP" Moog* (3) 10 AN09 l* "4160V BUS lA BKR 252-101 TRIP" 30 "START-UP TRANSFORMERS TROUBLE" 60 "D/G DAY TANK T-25 HIGH/LOW LEVEL" MOlO (22) 10 ANlO 1 "VARIABLE HIGH POWER LEVEL CHANNEL TRIP" (17) 8 "LOW LEVEL S/G l.CHANNEL PRE-TRIP" MOll (17) 10 ANll 1 "LOW LEVEL S/G 2 CHANNEL PRE-TRIP"

M012 (22)

(22) 10 AN12 8

3 8

"HIGH-PRESSURE PRESSURIZER CHANNEL PRE-TRIP" "LOSS OF LOAD CHANNEL TRIP" "LOW NEUTRON DETECTOR VOLTAGE (CHANNEL 3-8)

M013 (22) 10 AN13 1 "ZERO POWER MODE BYPASS" a* "NUCLEAR DELTA T POWER DEVIATION/

T-INLET OFF NORMAL/CALCULATOR TROUBLE CHANNEL D" M014 (3) 10 AN14 .1 "START-UP TRANSFORMER 1-3.PROTECTION CIRCUIT UNDERVOLTAGE" (22) 30 "COOLING TOWER E-30 B FIRE" (23) 40 "CONTROLS/INDICATION TRANSFERRED TO C-150/C-lSOA" M015 (22) 10 . AN15 1 "COOLING TOWER PUMP P39A HI TEMP OR OVERLOAD" 18 "DILUTION WATER PUMP P-40A TRIP" M016 (22) 10 AN16 1 "RADWASTE AREA LOW TEMP V-67 11 9 "MAIN STEAM PENETRATION ROOM HIGH TEMPERATURE"

E.48

SIMULATOR TESTS MOOl - M221 ABSTRACT ANSI-3.5 OPTIONS

~ 3 .1. 2 ~ ~ TESTED PARAMETERS/SYSTEMS MONITORED M017 (8) 10 CCOl "CV-0911 CCW CONTAINMENT ISOLATION (22) VALVE POSITION; PCP COOLING WATER LOW FLOW ALARM STATUS FOR EACH PUMP; PCP. TEMPERATURE INDICATION FOR EACH PUMP; PCP HIGH TEMPERATURE ALARM STATUS FOR EACH PUMP; PURIFI-CATION DEMINERALIZER ISOLATION VALVE CV-2023 POSITION INDICATION; BORONOMETER AND PROCESS RADIATION MONITOR VALVE CV-2014 POSITION INDICATION" M018 (22) 10 CC02 A "CCW SURGE TANK LEVEL INDICATION" M019 (8) 10 CC03 10%, 50% & "CCW SURGE TANK LEVEL INDICATION; (22) 100% CCW PUMP INDICATION; CCW SYSTEM ALARMS;. PCPs COOLING WATER FLOW ALARMS" M020 (23) 5. CHOl A "CONTAINMENT ISOL VALVES STATUS" M021 (23) 4 CH02 A "ALARM STATUS ON. PANEL Kl3 - Cl3; CONTAINMENT SPRAY PUMPS STATUS; LOW PRESSURE SI PUMPS STATUS; HIGH PRESSURE SI PUMPS STATUS; CHARGING PUMPS STATUS; BORIC* ACID PUMPS STATUS; SAFETY INJECTION. VALVES STATUS; S/G BLOW DOWN VALVES STATUS; CONTAINMENT AIR COOLER FAN STATUS" M022 (22) 10 CH03 A "CONTAINMENT AIR COOLER STATUS" M023 CH04 DELETED (Failure of Containment Purge Valve CV1806 - This 48" valve no longer exists at Palisades)

M024 (l)b 10 CH05 A "CHARGING PUMP STATUS; BORIC ACID (l)c PUMPS STATUS; HIGH PRESSURE SI PUMPS STATUS; LOW PRESSURE SI PUMPS STATUS; CONTAINMENT SPRAY PUMPS STATUS; SERVICE WATER PUMPS STATUS; CONTAINMENT AIR COOLER FAN STATUS; SI VALVE STATUS; CONTAINMENT SPRAY FLOW INDICATION" M025 (23) 10 CH06 A "CONTROL ROOM HVAC INDICATION" M026 (l)b 10 CH07 25%, 50% & "CONTAINMENT BUILDING HYDROGEN 100% INSTRUMENTATION"

E.49

SIMULATOR TESTS M001 - M221 ABSTRACT ANSI-3.5 OPTIONS

~ 3 .1. 2 ~ ~ TESTED PARAMETERS/SYSTEMS MONITORED M027 (l)b 10 evol. 10%, 50% & 11 evcs INDICATION; CONTAINMENT BLDG (l)c 100% HUMIDITY; RADIATION AND SUMP LEVEL" M028 (l)b 10 evo2 10%, 50% & 11 evcs INDICATION;*RADWASTE BLDG 100% VENTILATION INDICATION; RAD MONITOR LEVEL AND FLOW" M029 (23) 10 evo3 A "CHARGING PUMPS INDICATION AND ALARMS; eves INSTRUMENTATION" M030 (23) 10 CV04 0% & 100% "CHARGING PUMPS INDICATION;, eves.

INSTRUMENTATION" M031 (22) 10 evo5 "INTERMEDIATE PRESSURE CONTROL VALVE INDICATION (evCS)"

M032 (l)b 10 evo6 11 evcs INSTRUMENTATION; QUENCH TANK (22) LEVEL INDICATION" M033 (l)b 10 evo7 20% & 100%. 11 evcs INDICATION; CCW SURGE TANK INDICATION" M034 (22) 10 evos *nevcs INDICATION AND ALARMS" M035 (22) 10 evo9 "CVCS INDICATION; RADWASTE PANEL (C40) ALARMS" M036 (17) 10 ev10 "PRIMARY MAKE-UP SYSTEM TO eves (23) INDICATION; NUCLEAR POWER AND PCS TEMPERATURE INDICATION; CONTROL ROD POSITION INDICATION AND CONTROLS" M037 (17) 20 CVll "CONCENTRATED BORIC SYSTEM TO eves (23) INDICATION; eves INDICATION" M038 (22) 10 CV12 "CVCS AND BORIC ACID PUMPS INDICATION" M039 (22) 10 CV13 10%, 80% & "CVCS INDICATION" 100%

M040 CV14 DELETED (Boronometer failure - The boronometer is not in use at plant)

M041 (22) 10 ev15 5%, 10% & "VOLUME CONTROL TANK INDICATION; 70% RADWASTE AREA VENTILATION; RADIATION LEVEL AND ALARMS" M042 (1) 10 ev16 20%, 40% & 11 evcs INDICATION; PRESSURIZER LEVEL (19) 100% INDICATION; CONTAINMENT BLDG (22) INDICATION AND RADIATION LEVELS"

E.50

SIMVI.ATOR TESTS MOOl - M221 ABS'l'QC'l' ANSI-3.5 OPl'IONS

~ 3 .1. 2 ~ ~ TESTED PARAMETERS/SYSTEMS MONITORED M043 (5) 10 CWOl A "CIRCULATING WATER SYSTEM INDICATION (15) AND ALARMS; MAIN CONDENSER (16) INDICATION AND ALARMS (VACUUM) II (22)

M044 (22) 10 CW02 AA, BB & "COOLING TOWER FAN INDICATION AND BO ALARMS" M045 (3) 10 EDOl "SWITCHYARD INDICATION AND ALARMS; (15) MAIN GENERATOR BREAKERS INDICATION (16):. AND ALARMS; STATION POWER, START-UP (19) POWER AND D/G INDICATION AND ALARMS; SERVICE WATER, CCW, SAFETY INJECTION SYSTEM, AUXILIARY FEEDWATER SYSTEM, CIRCULATING WATER SYSTEM, .CONDENSATE/FEEDWATER, AND VENTILATION SYSTEM INDICATION AND ALARMS" M046 (3) 10 ED02 11 SWITCHYARD INDICATION AND ALARMS; (15) 11 STATION POWER INDICATIONS; COOLING (16) TOWER PUMPS STATUS; CONDENSER (19) VACUUM INDICATION" M047 (3) 10 ED03 A "REACTOR PROTECTION SYSTEM (4) INDICATIONS AND ALARMS; STATION.

POWER INDICATIONS AND ALARMS; PRIMARY COOLANT PUMPS STATUS; CONDENSATE PUMPS STATUS" M048 (3) 10 ED04 A "DIESEL GENERATOR STATUS INCLUDING 2400 VOLT BREAKERS AND ALARMS" M049 (3) 10 ED05 A "STATION POWER INDICATIONS AND ALARMS" M050 . ( 3) 10 ED06* A "MOTOR CONTROL CENTER INDICATIONS AND ALARMS"

M051 (3) 10 EP07 "CHARGING PUMPS STATUS; eves STATUS; (22) & MAIN FEED PUMP STATUS; FEEDWATER (23) VALVES ~TATUS; TURBINE GOVERNOR VALVES STATUS; NUCLEAR INSTRUMENTATION STATUS; CONTROL ROD POSITION INDICATION STATUS; PRESSURIZER PORV AND RELIEF VALVE STATUS AND INSTRUMENTATION; CONTAINMENT BLDG INSTRUMENTATION STATUS; QUENCH TANK INSTRUMENTATION STATUS; CCW SYSTEM INSTRUMENTATION STATUS; MAIN GENERATOR

E.51

SIKtlLATQR TESTS K001 - K221 ABSTBACT ANSI~3.5 OPTIONS

~ 3.1.2 -~ ~ TESTED PABAMETERS/SYSkEMS MONITORED cont. INSTRUMENTATION STATUS; PRIMARY COOLANT PUMPS INDICATION; SERVICE WATER SYSTEM STATUS; INSTRUMENT AIR SYSTEM STATUS; SAFETY INJECTION SYSTEM STATUS; CHEMICAL ADDITION EQUIPMENT STATUS; RADIATION MONITORING SYSTEM STATUS; AUX FEED-WATER SYSTEM STATUS" MOS2 (3) s ED08 A, D "PREFERRED AC BUS CONTROLS INDICAT-(19 }' 10 RCOl ION AND ALARMS; CONTROLS, INDICAT-(22) IONS, STATUS AND ALARMS ASSOCIATED (23) WITH A LOSS OF A PREFERRED AC POWER (l)b SUPPLY, WHICH CONSISTS OF ALL THE (l)c SAFETY SYSTEMS EQUIPMENT" M053 (3) 10 ED09 A. "SWITCHYARD CRITICAL ALARM; SWITCH-(22) YARD NON-CRITICAL ALARM; SWITCHYARD (23) AUX POWER AND STATION POWER TRANS-FORMER 78 (BREAKER STATUS) TRIP ALARM" MOS4 (3) 4 EDlO A, B "VARIOUS ALARMS FOR CONTROL POWER TO AN14 1 PLANT EQUIPMENT;* INDICATING LAMPS AN03 2 FOR DC POWERED EQUIPMENT; ANNUNCIA-TOR POWER SUPPLY; CONTROL POWER TO VARIOUS/NUMEROUS SWITCHES" MOSS (3) 10 EDll A "DIESEL GENERATOR ENGINE STATUS EDOl LIGHTS; BREAKER STATUS LIGHTS; D/G AUTO START CIRCUIT" MOS6 (3) 10 ED12 A "D/G ENGINE STATUS LIGHTS, METERS AND BREAKER STATUS LIGHTS; SAFETY

.INJECTION SYSTEM VALVE STATUS LIGHTS; SAFETY INJECTION SYSTEM PUMP STATUS LIGHTS, INCLUDING SERVICE WATER, AUX FEED PUMPS AND COMPONENT COOLING WATER PUMPS" MOS7 (1) 10 ED13 A "FAILURE OF MANUAL SAFETY INJECTION (6) EDOl SIGNAL" (8)

(11)

(17)

(23)

M057.5 (3) 10 ED02 "C BUS BREAKER INDICATION; D/G 6 ED04 A STATUS LIGHTS, SWITCHYARD BREAKERS ED14 A INDICATIONS" E.52

SIMULATOR TESTS MOOl - M221 ABSTRACT ANSI-:3. 5 OPTIONS

~ 3.1.2 ~ TE STEP PARAMETERS/SYSTEMS MONITORED MOSS (15) 10 EGOl "GENERATOR ALARMS, BREAKERS, BUS (16) BREAKERS FOR A, B, C, D AND E BUS" (19)

M059 (15) 10 EGOJ "GENERATOR VOLTAGE REGULATOR, FIELD (16) SWITCH AND ASSOCIATED ALARMS" (19)

M060 (22) 10 *EG04 "GENERATOR VOLTAGE REGULATOR AND ASSOCIATED ALARMS" M061 ci2> 10 EG.05 "MAIN GENERATOR GAS SYSTEM, TEMPERATURE, PRESSURE AND ALARMS" M062 (15) 10 FTOl A "MAIN FEED PUMP CONTROLS AND ALARMS; (16) STEAM GENERATOR LEVELS" (17)

(19)

(22)

M063 (5) 10 FwOl 50% & 100% "MAIN CONDENSER AND ALARMS (VACUUM);

(9) TURBINE TRIP SETPOINT; TURNING GEAR (15) OPERATION WITH LOSS OF VACUUM; TIME

( 16) TO GO ON T/G.UPON LOSS OF VACUUM COMPARED TO PLANT DATA" M064 FW02 DELETED (Reference SDR~ss-129)

M065 FWOJ DELETED (Reference SDR-88-129)

M066 (9) 10 FW04. A "CONDENSATE PUMP TRIP, FEED PUMP (15) TRIP, AND S/G LEVEL"

( 16).

(19)

M067 FWOS DELETED (Reference SDR-88-129)

M068 * (9) 10' FW06 A@ 1% & "MAIN FEED PUMP SPEED, FLOW, VALVE (19) 100% POSITION AND VARIOUS ALARMS FOR (22) FEEDWATER SYSTEM" M069 (22) 10 FW07 A "HEATER DRAIN PUMPS STATUS AND ALARMS" M070 (22) 7 FWOS A @ 10% & "MAIN FEEDWATER SYSTEM VALVES, 90%

ALARMS AND POSITION INDICATION"

E.53

SIMULATOR TESTS K001 - Ma21 ABS~gci

-* TEST M071 ANSI"".'3. 5 3 .1. 2

{9)

(1_5)

(16)

(17)

~

10

~

FW09 OPTIONS TESTED 10%, 20%,

40% & 100%

PARAMETERS/SYSTEMS MONITORED "MAINFEEDWATER SYSTEM INDICATION ALARMS AND S/G STATUS AND ALARMS"

( 19).

(20)

M072 (9) 10 FWlO 5%, 10% & "MAIN FEEDWATER SYSTEM INDICATION,

{15) 100% ALARMS AND-S/G STATUS AND ALARMS"

{16) c11r

{19)

{20)

M073 {9)_ 10 _FWll 5%, 10% "MAIN FEEDWATER SYSTEM INDICATION, (15) 11 50% & 100% ALARMS AND S/G STATUS AND ALARMS"

{16)

{17)

{19)

{20)

M074 . FW12 DELETED {Reference SDR-89-012) .

M075 (9) 10 Flo713* A @ 50% & "MAIN FEEDWATER SYSTEM INDICATION,

{19) 100% ALARMS AND S/G STATUS AND ALARMS" M076 {23) 10 FW14 "AUX FEEDPUMP CONTROL.9, INDICATION AND ALARMS; FIRE PuMP CONTROL.9, INDICATION AND ALARMS" M077 {23) 5 FW15 *30%, 50%, "AUX FEEDWATER*SY'STEM*coNTROL.9, 70% & 75% INDICATION AND ALARMS; S/G INDICATION, *coNTROL.9 AND ALARMS" M078 {23) 10 FW16 A "AUX FEEDWATER SYSTEM CONTROL.9, INDICATION AND ALARMS"

.M079 (23) 10 FW17 10%, 15%, "AUX FEEDWATER SYSTEM CONTROL.9, 25% & 50% INDICATION AND AIARMS" -

M080 {23) 5 FW18 c "AUX FEEDWATER SYSTEM CONTROL.9, INDICATION AND AIARMS" M081 {23) 5 FW19 A &B @ "AUX FEEDWATER SYSTEM CONTRO~,

33%, 67% & INDICATION AND A~"

100%

M082 (2) 10 IAOl 40%, 70% .& "PLANT AIR SYSTEM CONTROL.9.,

(6) 100% INDICATION AND AIARMS; COMPRESSED

{19) AIR OPE~TED VALVES STATUS"

E.54

SIMULATOR TESTS M001 - M221 ABSTRACT ANSI-3.5 OPTIONS

~*

~ 3.1.2 ~ ~ TESTED PARAMETERS/SYSTEMS MONITORED

. MOS3 (23) 5 IAOl 100% "PIANT AIR SYSTEM CONTROLS, IA02 INDICATION AND ALARMS AND NITROGEN BACKUP TO AIR OPERATED VALVES; AUX FEEDWATER SYSTEM INDICATION, CONTROLS AND ALARMS" MOS4 (23) 5 IA-01 100%. "PLANT AIR SYSTEM CONTROLS, IA03 INDICATION AND ALARMS AND NITROGEN BACKUP TO AIR OPERATED VALVES; AUX FEEDWATER SYSTEM INDICATION, CONTROLS AND ALARMS" MOSS (17) 6 MSOl A "MAIN STEAM SYSTEM INDICATION AND

( 20) MS03 A @ 100% CONTROLS; MAIN FEEDWATER SYSTEM CONTROLS AND INDICATION" MOS6 (19) 10 MS02 A * "MAIN STEAM SYSTEM INDICATION AND (22) CONTROLS" TOOS* (15) 20 MS03 A @ 100% Reference Transient Test TOOS (16) Abstract, pages E.40 - E.41 (19)

(20)

MOSS M089 (19)

(20)

(20) 20 8

. MS04

MSOS "MAIN STEAM SYSTEM AND S/G INDICATION, CONTROLS AND.ALARMS" 10%, 50% & "MAIN STEAM SYSTEM AND S/G 100% INDICATION, CONTROLS AND ALARMS" M090 (20) 8 MS06 A @ 50% & "MAIN STEAM SYSTEM. INDICATION AND 100% CONTROLS; FEEDWATER SYSTEM INDICATION AND CONTROLS" M091 (22) 5 MS07 "MAIN STEAM SYSTEM INDICATION AND CONTROLS; ATMOSPHERIC STEAM DUMPS INDICATION AND CONTROLS; TURBINE BYPASS VALVE INDICATION AND CONTROLS" M092 (15) 20 MSOS "MAIN STEAM SYSTEM INDICATION AND (22) CONTROLS; ATMOSPHERIC STEAM DUMPS INDICATION AND CONTROLS" M093 (22) 6 MS09 "MAIN STEAM SYSTEM INDICATION AND CONTROLS; ATMOSPHERIC STEAM DUMPS INDICATION AND CONTROLS; TURBINE BYPASS VALVE INDICATION AND CONTROLS"

TOOS replaced M087. Test number M087 is not used *

E.55

SIMUL1\'l'OR TESTS MOOl - M221 ABSTRACT

- ~

M094 ANSI-3.5 3.1.2 (19)

(22)

~ _

10 MSlO OPTIONS TESTED PARAMETERS/SYSTEMS MONITORED "MAIN STEAM SYSTEM INDICATION AND CONTROLS;.ATMOSPHERIC STEAM DUMPS INDICATION AND CONTROLS; TURBINE BYPASS VALVE INDICATION AND CONTROLS; S/G INDICATION AND CONTROLS; PRESSURIZER INDICATION AND CONTROLSH M095 (22) 6 MSll "MAIN STEAM SYSTEM INCLUDING TURBINE BYPASS VALVE" M096 (22 ):. 6 MS13 "MAIN TURBINE GLAND SEAL STEAM EQUIPMENT CONTROLS, INDICATION AND ALARMS; MAIN CONDENSER CONTROLS, INDICATION AND ALARMS" M097 (22) 10 MS14 "MAIN TURBINE-GLAND SEAL EQUIPMENT INDICATION AND CONTROLS" M098 (22) 10 PCOl A &C "PRIMARY AND SECONDARY DATA LOGGERS INDICATION AND ALARMS; CRITICAL FUNCTION MONITOR EQUIPMENT; eves INDICATION AND CONTROLS" T009* (l)b,c 10 RCOl Reference Transient Test T009 (3) Abstract, pages E.42 - E.43 (15)

(16)

(19)

MlOO (l)b 10 - RC02 --- "MAIN.FEEDPUMP CONTROLS AND INDICATION1 PRIMARY COOLANT PUMP CONTROLS AND INDICATION1 CONTAINMENT BUILDING INDICATION; SAFETY INJECTION SYSTEM INDICATION AND CONTROLS1 eves INDICATION AND CONTROLS" MlOl (l)c 10 RC03 8%, 60% & "CHEMICAL AND VOLUME CONTROL SYSTEM 100% INDICATIONS1 PRESSURIZER LEVEL INSTRUMENTATION1 CONTAINMENT PRESSURE/TEMPERATURE, HUMIDITY AND RADIATION INSTRUMENTATION" Ml02 (l)c 10 RC04 Sgpm & "PRESSURIZER LEVEL1 CONDENSER OFF (19) lOOgpm GAS; CONTAINMENT BUILDING RADIATION AND HUMIDITY" Ml03 (23) 10 RC05 "PCS FLOW1 PCP AMPERES1 NUCLEAR POWER LEVEL1 REACTOR VESSEL DELT1' P"

T009 replaced M099. Test number M099 is not used *

E.56

SIMULATOR TESTS MOOl - M221 ABSTRACT

~

M104 M105 ANSI-3.5 3 .1. 2 (4)

(19)

(4)

~

10 10 MALE RC06 RC07 OPTIONS TESTED A

PABAMETERS/SYSTEMS MONITORED "PRIMARY COOLANT PUMP TRIP; REACTOR TRIP" "PRIMARY COOLANT PUMP STATUS, AMPS, .

TRIP AND VIBRATION; REACTOR VESSEL DELTA pn M106 (4) 10 RCOS "PRIMARY COOLANT PUMP ALARMS; PCS (19) LOOP FLOW AND CORE FLOW; PRIMARY COOLANT PUMP STATUS, AMPS AND TRIP" M107 (4) 10 RC09 A "PRIMARY COOLANT PUMP ALARMS; REACTOR TRIP" M108 (22) 10 RC09 A "PRIMARY COOLANT PUMP ALARMS; REACTOR TRIP" M109 (4) 10 RCll "PRIMARY COOLANT PUMPS INSTRUMEN-(8) TATION AND STATUS; CCW TANK .

INSTRUMENTATION; REACTOR TRIP" MllO (23) . 10 RC12 A "PRIMARY COOLANT PUMP SEAL INDICATION"

Mlll M112 Mll3 (23)

(23)

(23) 10 10 10 RC13 RC14 RC15 A

A A

"PRIMARY COOLANT PUMP SEAL INDICATION" "PRIMARY COOLANT PUMP SEAL INDICATION" "PRIMARY COOLANT PUMP SEAL

' INDICATION;*cvcs INDICATIONS" Mll4 (4) 10 RC16 A "PRIMARY COOIANT PUMP INDICATIONS (23) (VIBRATION)"

MllS (22) 10 RC17 100% "PCS/PRESSURIZER INDICATION AND ALARMS"

.M116 (22) 10 RC18 100% "PCS/PRESSURIZER INDICATION AND ALARMS" Mll7 (l)d 10 RC19 0% & 100% "POWER OPERATED RELIEF VALVE (PORV)

INDICATIONS AND ALARMS; QUENCH TANK INDICATION; Mll8 (l)d 10 RC20 0% & 100% "POWER OPERATED RELIEF VALVE (PORV)

INDICATIONS AND ALARMS; QUENCH TANK I.NDICATION"

E.57

SIMULATOR TESTS MOOl - M221 ABSTRACZ ANSI-3.5 OPTIONS

~ 3.1.2 IC ~ TESTED PARAMETERS/SYSTEMS MONITORED TOlO* (10) 10 RC21 100% Reference Transient Test TOlO Abstract, pages E.44 - E.45 Ml20 * (l)b 2o' RC22 10% & 100% "FAILED FUEL MONITOR (14) INSTRUMENTATION; CONTAINMENT BLDG RADIATION INSTRUMENTATION; eves INDICATION AND ALARMS (RADIATION)"

M121 RDOl DELETED (Failure of Auto Withdrawal Prohibit to initiate - Using auto rod control is not permitted)

M122 (17) 10 RD02 "CONTROL ROD POSITION INDICATION ALARMS AND DATA LOGGER" M123 (17) 4 RD03 "CONTROL ROD POSITION INDICATION" M124 (12) 6 RD04 F "CONTROL ROD POSITION INDICATION; (17) REACTOR POWER INDICATION" Ml25 (12) 6 ROOS F "CONTROL ROD POSITION INDICATION; (17) REACTOR POWER LEVEL INDICATION" M126 (12) 6 RD06 .. 38 "CONTROL ROD POSITION INDICATION AND*

(17) .. ALARMS; REACTOR POWER LEVEL (19) INDICATION" M127 (12) 6 RD07 38 "CONTROL ROD POSITION INDICATION AND ALARMS; REACTOR POWER LEVEL INDICATION" Ml28 (12) 6 ROOS "CONTROL ROD POSITION INDICATION" (13)

Ml29 (12) ' 4 RD09 23 "CONTROL ROD POSITION INDICATION AND ALARMS" Ml30 (12) 6 . RDlO 40 "CONTROL ROD POSITION INDICATION AND (13) . ALARMs : REACTOR TRIP" M131 (12) 6 RDll 41 "CONTROL ROD POSITION INDICATION AND (13) ALARMS: . REACTOR TRIP" M132 (12) 10 RD12 34 "CONTROL ROD POSITION INDICATION AND ALARMS; REACTOR POWER AND TURBINE LOAD" Ml33 (12) 10 RD13 1, 21, 42 "CONTROL ROD POSITION INDICATION AND ALARMS; REACTOR POWER" TOlO replaced Mll9. Test number Mll9 is not used

E.58

SIMULATOR TESTS M001 - M221 ABSTBACT ANSI-3.5 OPTIONS

~ 3 .1. 2 IC ~ TESTED PARAHETERS/SXSTEMS MONITORED Ml34 (l)c 4 RD14 21 "CONTROL ROD POSITION INDICATION; (12) CONTAINMENT RADIATION AND HUMIDITY INDICATION" M135 (23) 10 RM04 100% "AUX BLDG RADIATION AND ALARMs; AUX BLPG VENTILATION INDICATION" M136 (22) 10 RM05 A, c "CONTAINMENT BLDG RADIATION INDICATION AND ALARMS" Ml37 (22} 10 RM06 v, w "AUX BLDG AREA RADIATION MONITOR INDICATION AND ALARMS; AUX BLDG.

VENTILATION INDICATION AND ALARMS" Ml38 (22) 10 RM07 F @ 100% "PROCESS RADIATION MONITOR H @ 50% INDICATION AND ALARMS; PROCESS A @ 5% CONTROL EQUIPMENT INDICATION AND I @ 10% ALARMS" Ml39 (22) 10 RM08 E, J "PROCESS RADIATION MONITOR INDICATION AND ALARMS" Ml40 (21) 4 RPOl A NUCLEAR INSTRUMENT INDICATION AND ALARMS"

M141 M142 Ml43 (21)

( 21) .

(21) 4 4

4 RP02 RP03 RP04 A

A A

NUCLEAR INSTRUMENT INDICATION AND ALARMS"

NUCLEAR INSTRUMENT INDICATION"

NUCLEAR INSTRUMENT INDICATION AND ALARMS" Ml44 (21) 4 RP05 A NUCLEAR INSTRUMENT INDICATION AND ALARMS" Ml45 (21) 5 RP06 A "NUCLEAR INSTRUMENT ALARMS AND CONTROLS" M146 (21) 8 RP07 A NUCLEAR INSTRUMENT INDICATION" M147 (21) 5 RP08 A NUCLEAR INSTRUMENT INDICATION AND ALARMS" M148 (21) 14 RP09 A NUCLEAR INSTRUMENT INDICATION AND

. ALARMS" M149 (21) 6 RPlO A "NUCLEAR INSTRUMENT INDICATION AND ALARMS"

E.59

SIMULATOR TESTS MOOl - M221 ABSTRACT ANSI-3.5 OPTIONS

~ 3.1.2 ~ ~ TESTED PARAMETERS/SYSTEMS MONITORED Ml50 (21) 8 RPll A "NUCLEAR INSTRUMENT INDICATION AND ALARMS" M151 ( 21) 8 RP12 A "NUCLEAR INSTRUMENT INDICATION AND ALARMS" M152 (21) 8 RP13 A "NUCLEAR INSTRUMENT INDICATION AND ALARMS" M153 (21). 8 RP14 A "NUCLEAR INSTRUMENT INDICATION AND ALARMS" M154 (21) 10 RP15 "NUCLEAR INSTRUMENT INDICATION AND ALARMS" M155 (21) 10 RP16 "NUCLEAR INSTRUMENT INDICATION AND ALARMS" M156 (21) 8 RP17 A "-NUCLEAR INSTRUMENTATION" M157 (21) 8 RP18 A "NUCLEAR INSTRUMENTATION" M158 (15) 6 RP19 * "FAILURE OF AUTOMATIC REACTOR TRIP; (24) 7 PLANT INSTRUMENTATION AND ALARMS; 10 RPS INDICATIONS" 14 M159 (22) 10 RP20 "FAILURE OF MANUAL REACTOR TRIP;

.PLANT INSTRUMENTATION AND ALARMS; .

RPS INDICATIONS" M160 (19) 5 RP21 A "RP,S INDICATIONS" (22)

M161 (22) 10 RP22 A @. 0% & "PCS TEMPERATURE INDICATION AND 100% POWER LEVEL" M162 (22) 10 RP23 A @ 0% & "PCS TEMPERATURE INDICATION AND 100% POWER LEVEL" M163 (22) 10 RP24 A @ 0% & "PCS TEMPERATURE AND ALARMS 100% INDICATION AND POWER LEVEL" M164 (22) 10 RP25 A @ 0%. & "PCS TEMPERATURE INDICATION, ALARMS 100% AND POWER LEVEL" M165 (22) 10 RP26 A "PCS PRESSURE INDICATION AND ALARMS" M166 (22) 10 RP27 A @ 1% & "STEAM GENERATOR LEVEL INDICATION 100% AND -ALARMS"

E.60

SIMULATOR TESTS M001 - M221 ABSTRACT ANSI-3.5 OPTIONS

~ 3.1.2 ~ MAL[ TESTED PARAMETERS/SYSTEMS MONITORED Ml67 (22) 10 RP28 A @ 1% & "STEAM GENERATOR INDICATION AND 100% ALARMS" Ml68 (22) 10 RP29 AA 11 S.TEAM GENERATOR PRESSURE INDICATION" Ml69 (22) . 10 RP30 AA "STEAM GENERATOR PRESSURE INDICATION AND ALARMS; RPS ALARMS" Ml70 (22) 8 RXQl 0% & 100% "PCS TEMPERATURE INDICATION" Ml71 (22) 8 RX02 0% & 100% "PCS TEMPERATURE INDICATION" Ml72 (22) 8 RX03 A @ 0% & "PCS TEMPERATURE INDICATION'*

100%

Ml73 (22) 8 RX04 A @ 0% & "PCS TEMPERATURE INDICATION AND 100%. CONTROLS" Ml74 (22) 8 RXOS A "PCS PRESSURE INDICATION AND (18) *CONTROLS" Ml75 (22) 10 RX06 A "PCS PRESSURE INDICATION AND (18) CONTROLS"

Ml76 (22) 8 RX07 A "PCS LEVEL INDICATION AND CONTROLS" (18)

Ml77 (22) 8 RX08 A "PCS LEVEL INDICATION AND CONTROLS" (18)*

Ml78 (22) 8 RX09 "PCS LEVEL INDICATION AND CONTROLS" (18)

Ml79 (22). 10 RXlO B @ 10% & "STEAM GENERATOR LEVEL INDICATION.

90% AND CONTROLS"

Ml80 (22) 10 RXll A "STEAM GENERATOR LEVEL INDICATION AND CONTROLS" Ml81 (22) 10: RX12 B, C, D, "PCS *PRESSURE INDICATION AND (18) E &F CONTROLS".

Ml82 (22) 10 RX13 "PRESSURIZER HEATER CAPACITY

. (18) INDICATION" Ml83 (22) 10 RX14 A @ 1% & "STEAM GENERATOR LEVEL INDICATION 25% AND CONTROLS" Ml84 (22) 10 RX15 A @ 100% "STEAM GENERATOR LEVEL INDICATION AND CONTROLS"

E.61

SIMULATOR TESTS MOOl - M221 ABSTRACT

~

Ml85 ANSI-3.5 3.1.2 (l)a

.(19)

~

10

~

SGOl OPTIONS TESTED A @ 14%,

PARAMETERS/SYSTEMS MONITORED "PCS LEVEL INDICATION AND ALARMS; 27%, 52% & C9NTAINMENT BLDG RADIATION 100% INDICATION AND ALARMS; eves INDICATION, CONTROL AND ALARMS; RPS INDICATIONS (RX. TRIP)"

Ml86 (23) 10 SIOl A "SAFETY INJECTION SYSTEM STATUS, PUMP INDICATION, CONTROLS" Ml87 (23L 10 SI02 A "SAFETY INJECTION SYSTEM STATUS, PUMP INDICATION, CONTROLS" Ml88 (23) 10 SI03 A "CONTAINMENT SPRAY SYSTEM STATUS, PUMP INDICATION, CONTROLS AND ALARMS" Ml89 (23) 10 SI04 A "SAFETY INJECTION SYSTEM STATUS, CONTROLS AND ALARMS" Ml90 (23) 10 SIOS A "SAFETY INJECTION SYSTEM STATUS, PUMP INDICATION, CONTROLS AND ALARMS" Ml91 ( l. 7) 10 SI07 A "SAFETY INJECTION SYSTEM STATUS,

Ml92 Ml93 (22)

(17)

(22)

(17) 10 10 SIOS SilO RCOl A

A @ 100%

CONTROLS AND ALARMS" "SAFETY INJECTION SYSTEM STATUS, CONTROLS AND ALARMS"

"(RAS) SAFETY INJECTION SYSTEM STATUS, CONTROLS AND ALARMS" (22)

Ml94 (23) 2 Sill ~A @ 20% & "SHUTDOWN COOLING SYSTEM STATUS, 50% *CONTROLS AND ALARMS; INCLUDING RADIATION MONITORS" Ml95 (23) 10 SI12 A "SAFETY INJECTION SYSTEM STATUS AND ALARMS" Ml96 (23) 2 SilJ "PCS AND SHUTDOWN COOLING SYSTEMS (7) STATUS, CONTROLS AND ALARMS" Ml97 (6) 10 SWOl "MAIN TURBINE GENERATOR STATUS AND ALARMS" Ml98 (6) 10 SW02 "MAIN TURBINE GENERATOR STATUS AND ALARMS" Ml99 SWOJ DELETED (Failure of pump P-44; Pump status requires local inspection)

E.62

SIMULATOR TESTS M001 - M221 ABSTRACT ANSI-3.5 OPTIONS

~ 3.1.2 ~ ~ TESTED PARAMETERS/SYSTEMS MONITORED M200 (6) 10 SW04 A "SERVICE WATER SYSTEM STATUS AND ALARMS" M201 (2) 10 SW05 A &B "COMPONENT COOLING WATER STATUS AND (6) ALARMs" (8)

M202 (6) 2 SW06 10%, 50% & "SECONDARY PLANT STATUS AND ALARMS; 100% SERVICE WATER SYSTEM STATUS AND ALARMS" M203 (6) 10 SW07 10%, 50% & "SERVICE WATER SYSTEM STATUS AND 100% ALARMS" (l5) 10 TCOl "MAIN TURBINE/GENERATOR STATUS AND (16) ALARMS; SECONDARY PLANT STATUS AND (19) ALARMS; STATION POWER/STANDBY POWER STATUS AND ALARMS" M205 (15) 1* TC02 "MAIN TURBINE/GENERATOR STATUS AND (22) ALARMS" .

r;,

M206 (22) 6 TC03 A "MAIN TURBINE/GENERATOR STATUS" M207 10 TC04 "MAIN TURBINE/GENERATOR STATUS; (19) A (22) REACTOR STATUS AND ALARMS"

. M208 (22) 10 TC05 A &D MAIN TURBINE/GENERATOR STATUS" (23) TCOl M209 TC06 DELETED (Turbine runback circuitry no longer exists at Palisades)

M210 TC07 DELETED * (Turbine runback circuitry .

no longer exists at Palisades)

M211 (22) 6 '::'J TCOS 3%; 20% & "MAI~ TURBINE/GENERATOR STATUS" 100%

M212 (22) 10 TC09 "MAIN TURBINE/GENERATOR STATUS" M213 (22) 10 TClO "MAIN TURBINE/GENERATOR STATUS" M214 TCll DELETED (Load-Power Mismatch -

Malfunction Disabled)

M215 (19) 10 TC12 A & B "MAIN TURBINE/GENERATOR STATUS AND (23) ALARMS; REACTOR.STATUS AND ALARMS" E.63

SIMULATOR TESTS M001 - M221 ABSTRACT ANSI-3.5 OPTIONS

~ 3 .1. 2 ~ Du: TESTED PARAMETERS/SYSTEMS MQNITOBEO M216 (22) 10 TC13 10%, 50% & "MAIN TURBINE/GENERATOR STATUS AND 100% ALARMS: PRIMARY COOLANT SYSTEM STATUS" M217 (23) 9 TUOl 20%, 60% & "MAIN TURBINE/GENERATOR STATUS AND 100% ALARMS" M218 (23) 7 TU02 "MAIN TURBINE/GENERATOR STATUS AND ALARMS" M219 c1sr* 9 TU03 50% "MAIN TURBINE/GENERATOR STATUS AND (23) ALARMS".

M220 (23) 10 TU04 "MAIN TURBINE/GENERATOR STATUS AND ALARMS" M221 (23) 10 TU05 "MAIN TURBINE/GENERATOR STATUS AND ALARMS"

6. FINAL CONDITIONS/DURATION OP TEST The simulator was set up in the initial condition as identified above and then the malfunction(s) was entered. Test steps were then followed that would verify if the component did indeed malfunction. After this was achieved the test would be terminated.

It is estimated that the average time to conduct each malfunction test was 20.to 30 minutes.

7. BASBLINB DATA The baseline data was actual plant data or data utilized by the plant such as prints, charts, schematics, plant procedures, and subject matter experts.

8. DEFICIENCIES The following simulator deficiencies were noted during*

performance of these tests.

A. CC MAKEUP FLOWS ARE INCORRECT SDR-88-127 OP B. CONTROL.VALVES ON WRONG POWER SUPPLY AND RELAY SDR-86-144 OP C*. FAN TRIP EXTINGUISHES BOTH BREAKER LIGHTS SDR-89-016 OP D. NO CONTAINMENT AFFECTS WITH PCS LEAK SDR-84-027 OP E. RIAs DON'T RESPOND TO AUX BLDG LEAK SDR-87-092 OP F. HOT LETDOWN FLOW DOESN'T FLASH TO STEAM SDR-89-041 CL G. CONTROLLERS DON'T OPERATE IN AUTO SOR-87-010 OP H. PCS RESPONDS TOO FAST TO eves BORON CHANGE SOR-88-157 CL

. I. CALCULATION OF PCS BORON IS INCORRECT SDR-89-017 CL J. CONTROL VALVES AUTO .CLOSE WHEN P39A IS TRIPPED SOR-88-158 OP

E.64

SIMYLATQR TESTS M001 - M221 ABSTftACT

8. DEFICIENCIES (cont.)

K. ANNUNCIATORS DON'T OPERATE CORRECTLY SDR-88-030 OP L. BUS lF & lG LOAD SHED INCONSISTENT SDR-88-159 CL M. BUS lA VOLTMETER SHOWS VOLTAGE WITH NO POWER SDR-88-160 CL N. 1-1 D/G DIDN'T SHUT DOWN WHEN BREAKER OPENED SDR-88-161 CL O. TI-0101/02 SHOULD FAIL "AS IS" SDR-86-142 CL P. LIGHT STAYS ON WHEN POWER IS LOST TO PI-1419 SDR-89-015 OP Q. CONTROL VALVES DON'T CLOSE ON LOSS OF PREF A-C SDR-89-018 CL R. LIA-0365 SHOULD FAIL "AS IS" SDR-89-019 OP S. RIAs POWERED FROM WRONG BUS SDR-89-020 CL T. IMPROPER RESPONSES TO LOSS OF Y-10 SDR-89-021 CL U. IMPROPER RESPONSES TO LOSS OF Y-40 SDR-89-022 CL V. "D" CHANNEL OF TMD DOESN'T OPERATE PROPERLY SDR-89-026 OP W. BREAKER LTS DON'T WORK PROPERLY ON LOSS OF 010 SDR-89-024 CL X. D/G LIGHTS RESPOND INCORRECTLY. DURING STARTS SDR-89-007 CL Y. MALF FW08A SHOWS 10% BUT PRODUCES 5% VLV POS SDR-89-025 OP

z. ELECTRIC FIRE PUMP P9A FAILED TO START SDR-88-162 OP AA. PCP AMPS TOO HIGH DURING HEATUP FROM COLD S/D SDR-84-069 OP AB. SOME AIR OPERATED VALVES ON WRONG AIR SUPPLY SDR-87-151 OP AC. MALF MS05 SHOWS 10% BUT PRODUCES 50% STM FLOW SDR-89-027 OP AD. TURBINE BYPASS VALVE.TOO SLUGGISH SDR-87-107 CL AE. SPI RESPONSE TO PIP MALFUNCTION INCORRECT SDR-88-039 OP AF. PC FLOW DOESN'T INCREASE ON CORE BARREL FAILURE SDR-89-028 OP AG. NO VIBRATION ALARM ON PCP COUPLING FAILURE SDR-88-163 OP

.1Uf. REACTOR DP, PC FLOW & AMPS, CHANGE IN WRONG DIR SDR-88-164 OP AI. PCP CONT B.O. FLOW HAS NO INCREASE ON FAILURE SDR-88-165 OP AJ. PCP HI VIBRATION SHOULD STOP @ 30 SECONDS SDR-89-029 OP AK. IMPROPER RADIATION MONITOR RESPONSES SDR-89-030 OP AL. CORE 8 RELOAD (REACTIVITY LEVELS INCORRECT) FC-814 OP AM. IMPROPER EQUIPMENT RESPONSES TO HI RADIATION SDR-89-031 OP AN. MALFUNCTION RPOlA DOES NOT WORK PROPERLY SDR-88-124 op*

AO. DRAWER TRIP TEST SWITCH DOESN'T WORK PROPERLY SDR-89-032 OP AP. CONTROL PANEL SHOULD BE AT 125 WITH +lOV ACTIVE SDR-87-116 OP AQ. Ml V-METER RETURNS* TO NORMAL AFTER TRIP SDR-89-033 OP AR. MALF RX09 DOESN'T DISABLE "BACKUP VOL CONT" SGNL SDR..;89*034 OP AS*. MALF RXlOA DOESN'T AFFECT LI-0702 SDR-89-035 OP AT. OFFGAS & S/G BLOWTANK MONITORS RESPOND INCORRECT SDR-87-141 CL AU. SIT LEVEL & PRESSURE ALARMS DON'T WORK PROPERLY SDR-87-124 OP AV. OIL TEMPS DON'T RESPOND TO TEMP INCREASES SDR-89-036 OP AW. LOSS OF SW FLOW DOESN'T CAUSE HI TEMP ALARM SDR-87-013 OP AX. MALF TC02 DESCRIPTION DOESN'T MATCH AFFECT SDR-88-024 OP AY. MALF TC08 DOESN'T CAUSE SHIFT FROM AUTO TO MAN SDR-89-037 OP AZ. TURBINE INDICATORS WORK IMPROPERLY AFTER TRIP SDR-89-038 OP BA. ALARM KOl-3 DIDN'T TRIP WHEN SET POINT EXCEEDED SDR-89-039 OP These simulator deficiency reports (SOR) and facility change (FC) have been corrected as indicated by a "CL" beside the number, or

are open as indicated by an "OP" and are scheduled to be resolved by 12/30/91 (reference the enclosed "Paltrack" report listing). ,

E.65

SIMULATOR* TESTS MOOl - M221 ABSTRl\CT

9. EXCBP'l'XONS TO ANSX/ANS~3.5-1985 The simulator does not have specific malfunctions for "uncoupled rods" or "drifting rods" (Ref section 3 .1. 2 ( 12)) *

However, our present capabilities in the area of rod malfunctions are adequate to provide the operators with the necessary training related to rod operation *

E.66

SECl'ION F CONFIGURATION

.CONTROL

~ .. ..

TECHNICAL SUPPORT GROUP (TSG)

I* Mission:

To efficiently and opportunely modify and maintain the Palisades Nuclear Plant simulation facility to the level of fidelity and availability determined by our clients, management and regulators to support the training and evaluation of Palisades plant personnel.

II. Organizati9n TECHNICAL SUPPORT GROUP (TSG)

TSG SUPERUISOR Engineering I> Hanlwara Group Senior Senior Nucleer Engineer Analyst Technicians

- - Senior Slmulatlousystem Software Group Technologist Senior Nuclear Analyst Slmulator Analyst*

III. TSG Responsibilities A. TSG Supervisor Responsibilities

l. Direct the technical and administrative activities of the. TSG staff.

2. Direct the activities required to achieve and maintain simulator certification (Reg Guide 1-149).

3. Represent the TSG'as a member of the Operations Curriculum Committee.

4. Establish the scope and schedule for simulator modifications and assure completion of the objectives.

S. Direct the activities required.to assure the availability of the

~*

6.

Palis.ades simulator and Midland Training Center (HTC) laboratories

Provide required TSG resources (budget, personnel, etc).

F.l HI0290-0004A-HC01

B. Engineering and Hardware Group Responsibilities

1. Complete the activities required to achieve and maintain simulator certification, (ie. planning, scheduling, testing, documentation, reports, procedures, etc).

2. Maintain the simulator configuration control program "PALTRACK".

3. Completion of simulator modifications.

a. Evaluate plant modifications for simulator impact.

b. Evaluate simulator discrepancies.

c. Prepare simulator modification specifications.

d. Design simulator hardware.

e~ Purchase/fabricate simulator hardware.

f. Install simulator hardware.

g. *Maintain simulator hardware documentation *

4.

h.

i.

Prepare and conduct simulator modification acceptapce tests.

Provide plant technical support to other TSG groups.

Maintain simulator availability (Palisades and Midland)

a. Complete preventative maintenance.

b~ Complete corrective maintenance.

5. Maintain Midland Training Center (HTC) laboratories

a. Complete modifications.

b. Complete preventative maintenance.

c. Comp~ete corrective maintenance.

6. Provide supervision for HTC facilities personnel.

C. Software Group Responsibilities

1. Completion of simulator modifications

a. Develop simulation software *

b. Document simulation software modifications.

F.2 HI0290-0004A-HC01

2.

3.

Coordinate implementation of simulator modifications into training (Training Load Saves}.

Maintain simulator computer system software

a. Control/modify system software and configuration.

b. Provide operating system support.

4. Develop and maintain simulator.software quality assurance programs.

5. Provide personal computer support for HTC personnel (software and maintenance}.

6. Provide software support for University of Michigan Diagnostic and Controls Project.

IV *. Simulator Configuration Control Process (Surmnary only-for details refer to Local Instructions HTC 6.0 and HTC

.9.0).

A. Simulator Discrepancies (SOR}:

1. Can be identified by anyone.

2. Must be documented once identified.

3. Are evaluated by simulator instructors (SI} and TSG engineering for validity.

4. Are tracked on the computerized database called "Paltrack".

5. Are assigned a training priority by the Operations Curriculum Committee (OCC}.

NOTE: The OCC is responsible for determining the curricuia for the Palisades plant operator training program. Individuals from

. the Operations Department, Simulator Training and Technical Support Group attend OCC meetings.

6. Are scheduled for implementation into .the simulator by the TSG supervisor with OCC input.

8. Plant Modifications (Simulator Update Design Data}

1. Are identified from the Palisades Plant's computerized modification tracking system through direct transfer of data to the simulator's computerized modification tracking system, "Pal track".

F.3 HI0290-0004A-MC01

- - 2.

3.

Are tracked on the computerized database called "Paltrack" Are initially evaluated by TSG engineering for simulator impact.

Decision on impact is made by the OCC.

4 Are assigned a training priority by the OCC.

5. Are scheduled for implementation into the simulator by the TSG supervisor with OCC input.

C. Simulator Modifications

1. TSG Engineering group assembles one or more SOR/Plant modification into a Sim~lator Hodific~tion Package (SHP). (TSG supervisor approves).

2. TSG Engineering group develops specification for SHP (engineer supervisor reviews). (Simulator supervisory instructor approves)

3. TSG Hardware group designs/installs hardware per specification.

4. TSG Software group develop software for the SHP. The software designer is not the same person that developed the specification or test.. (Software supervisor reviews software design)

5 The software designer also identifies the root cause of any SDR's in the SHP *.

6. TSG Engineering group develops SHP Acceptance Test Procedure (ATP) based on specification (review by engineering supervisor)

(approved by simulator sup~rvisory instructor).

7. TSG engineering and a simulator supervisory instructor conduct test and issue Test Analysis report 8 Simulator supervisory.instructor accepts or rejects SHP, SDR's issued if needed.

9 Accepted SHPs are grouped together into a Training Load Save*

(TLS).

10. TLS are periodically (3 or 4 times per year) tested and incorporated into simulator training.

11. Resoived SDR's are closed by the TSG supervisor, copied to the

_originator and filed.

12. Documentation is updated and the SHPs are closed by the TSG Supervisor and filed *

F.4.

HI0290-0004A-HC01

- V. SIMULATOR CERTIFICATION CONTROL PROCESS (Sunvnary only - for details refer to Local Instruction HTC 17.0.

A. Plant Modifications (Simulator Update Design Data)

1. Are reviewed each year to determine those that impact the simulator and are completed at the plant. (Based on student feedback, engineering and training value assessment).

2. Impacting the simulator and completed at the plant are scheduled and incorporated on the simulator within 12 months of the review date. (TSG Supervisor).

3. Are tracked on the simulator's computerized modification tracking system, "Paltrack".

4. Documentation is updated.

B. Physical Differences

1. Are identified by comparing pictures of the Plant's control room to the simulator.

2.

4.

Are initially evaluated by TSG engineering for simulator impact

Decision on impact is made by the OCC.

3. *Are corrected by the TSG hardware group.

Documentation is updated.

c. Annual Performance Testing

1. Is identified in the "Palisades Simulator Certification Submittal".

2. Is updated with the most recent plant response data.

3. Is scheduled and conducted prior to the certification anniversary date.

4. Is documented and evaluated prior to the certification anniversary date.

5. Has SDR's written, if identified, to .document discrepancies.

6. Is filed.

D. Significant Simulator Design Change Performance Testing

1. Is scheduled when simulator design changes result in significant simulator configuration or performance variations, as determined by the TSG supervisor.

F.5 MI0290-0004A-MC01

NOTE: Design changes, that result in significant simulator configuration or performance variations, are defined as follows:

These design changes that use* a new or different design methodology, from existing sys-tems, to accomplish simulation.

Following are examples:

a. Configuration - Installation of a new computer system (ex.

Encore 32/77 to 32/2000), a new I/O system or a new trainer.

b. Performance Variation - A logic to dynamic model rewrite or a major model replacemen.t (ex. core, pressurizer, steam generator, safety injection, et~).

2. Is updated with the most recent plant response data.

3. Is conducted, documented and evaluated by the TSG engineering group.

4. Has SDR's written, if identified, to do.cument discrepancies.

5. Is filed.

E. Reporting 1.

2.

Is prepared for the NRC if simulator design changes result in significant simulator configuration or performance variations.

Is prepared for the NRC every fourth anniversary of the initial certification submittal.

3. Is prepared for the NRC for any change to the performance testing plan made after initial submittal of such a plan.

4. Shall include NRC Form 474, a description of the Performance Testing completed, and an schedul~ for the conduct of approximately 25% of the Performance Test per year for the subsequent 4 years. *

5. For the fourth anniversary reports only, shall include a list of any SDR's identified during initial performance testing not yet resolved and a schedule for resolution of the SDR's identified.

6. Is filed *

MI0290-0004A-MC01 F.6

SIMULATOR OPEN ITEMS REPORT (PALTRACK LISTING)

PALTRACK REPORT EXPLANATION

The following computerized report (PALTRACK) identifies the current list of open plant modifications (Facility Changes (FC), Specification Changes (SC) and Set Point Changes (SPC)) impacting ~he simulator and the open Simulator Deficiency Reports (SOR) identified while conducting the simulator Performance Test. The report also identifies when these "Source Documents" are scheduled to be incorporated on the simulator.

Following is a brief explanation of each heading shown on the "PALTRACK" report.

HEADING SOURCE DOC - (SOURCE DOCUMENT)

The unique identifier of the document that forms the basis for a simulator modification. These documents include Plant Modifications (Fa~ility Changes (FC), Specification Changes (SC) and Set Point Changes (SPC)) and Simulator Deficiency Reports (SOR)

PLT STATUS-DATE - (PLANT STATUS - PLANT STATUS DATE)

The "plant status" is a code ranging from 1 to 6 and X,

- designating the status of a plant modification currently being worked on at the Palisades plant.

1 = Control Number Assigned 2 = Review Completed / Ready To Install 3 = Installed But Operability Not Authorized 4 = Operability Authorized 5 = Closed out 6 = Number Not Used / Cancelled X = Inactive - Expected Completion 2 Years Or Greater The "plant status date" is the date associated with the "plant status" number, indicating when the status of the plant modification occurred.

PLT SCHDLE DATE - (PLANT SCHEDULE DATE)

The date or time when the plant modification 1s scheduled to be completed.

WBS NUMBER - (WORK BREAKDOWN STRUCTURE NUMBER)

A number utilized by the Palisades plant for budgeting and scheduling purposes. This number may be cross-referenced to Plant Modification numbers.

Note: One WBS Number may cover several Plant Modification Numbers .

F.7

PALTRACK REPORT EXPLANATION SIM STS-DATE - (SIMULATOR STATUS - SIMULATOR STATUS DATE)

The "simulator status" indicates the status of the "source document" at the simulator.

OP= OPEN= The "source document" has not.been resolved.

CL = CLOSED = The "source document" has been resolved.

DF = DEFERRED = The "source document" will not be resolved until a future event or date occurs.

RJ = REJECTED = Based on Operations and Training* Evaluation, this "source document" is not scheduled to be resolved.

The "simulator status-date" is the date associated with the "simulator status", indicating when the "simulator status" occurred.

SIM SCH DATE - (SIMuLATOR SCHEDULE DATE)

The date when the "source document" is scheduled to be completed at the simulator.

PRIORITY A numerical value assigned to the "source do_cument" based on training impact.* The lower the number, the higher the impact ori training.

The format for this number is XXX.X, and the current range utilized is from 0.1 to 500. The values on this report are rounded to the nearest whole number.

DESCRIPTION A brief statement explaining the topic of the "~ource document".

SYSTEM CODE 1/2 - (SYSTEM CODE 1 / SYSTEM CODE 2)

A two or three letter abbreviation that designates the primary and/or secondary plant system the "source document" affects.

ANN = ANNUNCIATOR . PCP = PRIMARY COOLANT PUMP CC = COMPONENT COOLING PPC = PLANT PROCESS COMPUTER CFM = CRITICAL FUNCTION MONITOR PZR = PRESSURIZER CH = CONTAINMENT AND HVAC RC = PRIMARY COOLANT CR = CORE PHYSICS RD = CONTROL ROD DRIVE CV = CHEMICAL AND VOLUME RMD = RADIATION MONITORING CW = CIRCULATING WATER RP = REACTOR PROTECTION ED = ELECTRICAL DISTRIBUTION RX = REACTOR REGULATING EG = ELECTRICAL GENERATION SG = STEAM GENERATOR FT = FEEDWATER PUMP TURBINE SI = SAFETY INJECTION FW = FEEDWATER SS = SYSTEM SOFTWARE (SIM)

IA = INSTRUMENT AIR SW = SERVICE WATER I/O = INPUT/OUTPUT OVERRIDE TC = TURBINE CONTROL MS = MAIN STEAM TMM = THERMAL MARGIN MONITOR NI = NuCLEAR INSTRUMENTATION TU = TURBINE PCM = PROGRAM CONTROL MONITOR WP = WASTE PROCESSING F.8

PALTRACK REPORT EXPLANATION

HARDWARE Indicates whether or not hardware needs to be installed to resolve the "source document", or indicates the initials of the person responsible for completing the hardware installation.

SOFTWARE Indicates whether or not software needs to be developed to resolve the "source document", or indicates the initials of the person responsible for completing the software development.

SIMULATOR IMPACT DESCRIPTION A field used primarily by the simulator's Technical Support Group (TSG) for documenting notes and comments.

SIM ENGINEER - (SIMULATOR ENGINEER)

Initials of the Technical Support Group member responsible for resolving the "source document".

~ SIM MOD NUMBER ~ (SIMUL]\TOR MODIFICATION NUMBER)

Designates.the "simulator modification package number" in which

the "source document" resides. Example: P-87-15 .where P - is for the Palisades plant~

87 - is the year the package was opened, 15 - is the sequential package number for.the specified year.

Note: Simulator Modification Packages may contain more than one "source document".

COGNIZANT INDV - (COGNIZANT INDIVIDUAL)

The person originating or knowledgeable with the "source document" .

F.9

.F.10 PLT STATUS-DATE PALTRACK REPORT #21 SIM STS-DATE 05/15/90

SYS HARD/

CERTIFICATION REPORT OPEN ITEMS SIM ENGINEER/

PLT SCHDLE DATE SIM SCH DATE *CODE SOFT SIMULATOR IMPACT. *SIM MOO NUMBER/

SOURCE DOC WBS NUMBER PRIORITY DESCRIPTION 1/2 WARE DESCRIPTION COGNIZANT !NOV

::============== ============ =================================== ---- ----- =================================== ===============

FC-494-03 5 - 08/24/83 OP-08/24/83 RADIOACTIVE GASEOUS EFFLUENT RMD RLT HARDWARE COMPLETE AJH 07/15/90 MONITOR SYSTEM - PROJ 703 YES P-85-04 17 LEVA TE FC-685 1 - 06/04/87 OP-07/25/89 ADD DIVERSE SCRAM TO RPS (REQUIRED

RX RLT 90 REFOUT 12/30/91 FOR 90 REfOUT). YES P-86-38 98 PROJ ENGR: AGNELLO D - AGNELLO D FINAL ACCEPTANCE FC-706 x- 06/04/87 OP-07/25/89 INSTALL PRESSURE ALARM ON T-9C IA 01/01/92 06/01/93 TURBINE BUILDING HIGH PRESSURE AIR. P- .

266 FERENS MA FC-737 5 - 02/04/89 OP-02/04/89 REPLACE DBA/NSD SEQUENCERS. SI YES 2 ANNUNCIATOR WINDOWS "SEQUENCER WAS 88 REFOUT 10/05/90 TROUBLE" & "BATTERY LOW" P-90-08 500 CORBETT RJ FC-740-01 5 - 01/26/88 OP-12/12/88 INSTALLATION OF GENERATOR RADIO EG RLT HARDWARE NOT TO BE INSTALLED ON AJH 07/15/90 FREQUENCY MONITOR. YES SIMULATOR P-88-28 110 CORBETT RJ FC-740-02 5 - 04/11/88 OP-04/11/88 INSTALL GENERATOR RTD MONITORING TU RLT AJH 07/15/90 SYSTEM. YES P-88-28 120 MEREDITH BO FC-740-03 5 - 04/13/88 OP-12/12/88 INSTALL GENERATOR.END TURN EG RL'r HARDWARE NOT TO BE INSTALLED ON AJH 07/15/90 VIBRATION MONITORING SYSTEM. YES SIMULATOR P-88-28 111 MEREDITH BO FC-766 5 - 08/16/88 OP-08/16/88 COMPUTER MODIFICATION TO SUPPORT CFM NO DO IN CONJUNCTION WITH SPR-88-076 WED 12/21/90 ROD DROP TIMING. RD YES P-90-14 WBS-21510 400 HAMM RM FC-768 5 - 03/21/88 OP-03/21/88 REPLACE RE-0631 AND RIA-0631. RMD RLT (PER WAS 12/87) WED 10/05/90 FW YES P-87-48 19 RADZWION DJ FC-769 5 -. 04/08/88 OP-04/08/88 REPLACE RE-5711, RIA-5711, RE-5712 RMD RLT WED 10/05/90 AND RIA-5712. YES P-87-48 400 RADZWION DJ FC-797 2 - 08/07/89 OP"07/25/89 PERMANENT REMOVAL.OF RCP MOTOR RC RLT REMOVE PCP ROTATION LIGHTS ON HOLD 12/30/92 SHAFT PROXIMITY .PROBES (PERM. YES P- -

WBS-43050 78 INCORPORATION OF JLB-87-009). AGNELLO D FC-798 5 - 12/05/88 OP-12/05/88 INSTALL LOCAL CALIBRATED ANN RLT ALARM WINDOW 32 ON C106 - PER WAS WAS 12/21/90 TEMPERATURE INDICATORS IN BATTERY NO 8/5/88 P-90-12 206 *ROOMS (ED-01/02). MEREDITH BO FC-800 2 - 01/24/90 OP-01/15/90 ADDITION OF 2400V OFFSITE POWER. ED YES C07 ADDITIONS FOR NEW 2400 V SUPPLY 90 MAOUT 12/30/91 PROJ ENGR: FOSTER GW - FINAL YES P- -

F.11 PALTRACK REPORT #21 . CERTIFICATION REPORT 05/15/90 OPEN ITEMS PLT STATUS*DATE SIM STS*DATE SYS HARD/ SIM ENGINEER/

PLT SCHDLE DATE SIM SCH DATE CODE SOFT SIMULATOR IMPACT SIM MOD NUMBER/

SOURCE DOC WBS NUMBER PRIORITY DESCRIPTION 1/2 WARE DESCR I PT! ON COGNIZANT INDV

============ ---------------

WBS*64380

====== =============================

ACCEPTANCEDATE:

----- =================================== ===============

HAMM RM 15 FC-803 5 - 12/22/88 OP-12/22/88 CRITICAL PUMP INSERVICE INSPECTION SI PER WAS 4/19/88 WAS 07/15/90 BYPASS FLOW FE/FT/FI-0404. YES P-90-04 WBS-35015 100 MURPHY HK FC-808 5 - 12/21/88 OP-12/21/88 TURBINE TURNING GEAR MOD. TU RLT 12/30/91 YES P- -

WBS-64785 218 MEREDITH BO FC-812 5 - 12/01/88 OP-12/01/88 MODIFY SIS TEST CIRCUITRY FOR SW CV WILL ANNUNCIATE ON SIS PANEL AND 12/30/91 CV-1359. SI YES WILL NOT STROKE ON SIS TEST. SEE P- -

WBS-44580 80 FC 816 SLEEPER GW FC-814 5 - 07/13/89 OP-01/24/89* CORE 8 RELOAD. CR NO REOPENED BECUASE P-87-36 CODE WAS ERQ 88 REFOUT 07/15/90 RC ERQ REMOVED IN TLS 26 (SEE P89-32). P-90-16 5 FC-814 WAS ORIGINALLY IN P-87-36 PIERCE SF FC-816 1 - 05/09/88 OP-07/25/89 MODIFY CV-1359 CONTROL SCHEME. SW NO CLOSE CV ON RIGHT OR LEFT CHANNEL 90 REFOUT 12/30/91 SI YES SIS. SEE FC-812 P- -

WBS-44540 81 ANDREWS KH FC-817 5 - 02/26/90 OP-07/25/89 REPLACE PIC-0202 AND HIC-2122. CV YES WAS 89 MAOUT 12/30/91 YES P*90*08 WBS-62625 84 RADZWION DJ FC-818 1 - 05/26/88 OP-07/25/89 AIR SUPPLY MOD TO CV-0522A/B. FW CHANGE OPENING TIME 90 REFOUT 12/30/91 YES P- -

WBS-42111 99 CORBETT RJ FC-829 1 - 10/04/88 OP-07125/89 ELECTRICAL PENETRATION INSTALLATION NI YES 90 REFOUT 12/30/91 CRG 1.97 NUCLEAR INSTRUMENTATION RP YES P- -

WBS-62926 40 UPGRADE - PHASE II). CRIPPS JL FC-839 5 - 02/01/90 OP-07/25/89. MODIFY 480V POWER SOURCES TO CV 89 MAOUT 12/30/91 PROVIDE FEED TO P-55B FROM EITHER YES WBS-41210 39 1C OR 10 BUS. AGNELLO D FC-842 x - 02/28/89 OP-04/06/89 UPGRADE AUX FEEDWATER INSTRUMENT FW YES ANN CHANGES AND NEW PS 92 REFOUT 12/30/93 POWER SUPPLY. YES P- -

WBS-40250 39 CORBETT RJ FC-843 1 - 02/28/89 OP-04/06/89 REPOWER CERTAIN CONTROL ROOM 7 90 REFOUT 12/30/91 INSTRUMENTS. ED YES P- -

WBS-44820 39 ROSS VL FC-844 2 - 11/14/89 OP-04/06/89 INSTALL WESTINGHOUSE DIGITAL TC YES WAS 90 REFOUT 10/05/90 ELECTRO-HYDRAULIC (DEH) CONTROL YES P-89-38 WBS-64740 0 SYSTEM FOR TURBINE GENERATOR. GRIFFIN BR

.F.12 PLT STATUS-DATE PALTRACK REPORT #21 05/15/90 SIM STS-DATE

SYS HARD/

CERTIFICATION REPORT OPEN ITEMS SIM ENGINEER/

PLT SCHDLE DATE SIM SCH DATE CODE SOFT SIMULATOR IMPACT SIM MOO NUMBER/

SOURCE DOC was NUMBER PRIORITY . DESCRIPTION 1/2 WARE DESCRIPTION COGNIZANT INDV

====== =============== ============ =================================== ==== ===== =================================== =========

FC-848 1 - 03/29/89 OP-05/02/89 FUEL RELOAD M, CORE CYCLE 9, 90 CR NO 90 REFOUT. 12/30/91 REFOUT. YES P- -

WBS-94112 80 KNEELAND JR FC-849 1 - 03/29/89 OP-05/02/89 REMOVE LR-0612, PTR-0115, PTR-0125, FW YES 90 REFOUT 06/01/92 PTR-8612, LT-0612, LT-0614, YES P- -

WBS-62615 75 LT-0617, LT-0618, LT-0620, LT-0623, KENNEDY OM LT-0626 AND LT-0629.

FC-852 1 - 04/13/89 OP-05/02/89 ADDITION OF REDUNDANT RCS LEVEL RC YES 90 REF OUT 90 REFOUT 12/30/91 INDICATING LOOP AND ALARM. YES P- -

WBS-63070 80 CORBETT RJ FC-854 1 - 04/17189 OP-05/02/89 1) MODIFY PREFERRED AC INVERTER ED 90 REFOUT 12/30/91 BYPASS CIRCUITS AND 2) MODIFY YES P- -

WBS-64381 20 DIESEL GENERATOR BREAKER CONTROL SONNENBERG DJ SCHEMES.

FC-855 2 - 10/09/89 OP-05/02/89 INSTALLATION OF TURBINE TU YES 90 REFOUT 12/30/91 SUPERVISORIES. YES P- -

WBS-64700B 9 DAY DR FC-857 x - 05/05/89 OP-06/06/89 REACTOR PROTECTIVE SYSTEM RP 92 REFOUT 12/30/93

.1 ENHANCEMENTS. NI YES P- -

WBS-90015 ROSS VL FC-861 1 - 05/16/89 OP-06/05/89 ELIMINATE REACTOR REG SYSTEM AND CR YES 90 REFOUT 12/30/91 UPGRADE PCS AVG/DELTA TEMPERATURE RD YES P- -

WBS-43030 2 INSTRUMENTS. SWIECICKI TJ FC-862 5 - 02/26/90 OP-07/17/89 REPLACE PT/PIA-0116. RC YES CHANGE QUENCH TANK TO DUAL RANGE WED 89 MAOUT 07/15/90 YES *WITH SWITCH P-90c06 WBS-62645 1 BISCHOFF RA FC-863 x - 06/06/89 OP-07/11/89 INSTALL ADDlrlONAL VIBRATION RC YES 92 REFOUT 12/30/93 INDICATION *FOR PCP MOTORS AND YES P- -

WBS-43076 50 PUMPS. FERENS MA FC-869 5 - 12/01/89 OP-07/14/89 REPLACE HS-0944A. cc YES CHANGE TO 3 POSITION SWITCH WED 89 MAOUT 07/15/90 YES P-90-02 1 SONDGERATH PJ FC-878 x - 09/14/89 OP-09/26/89 REPOWER P-56B .BORIC ACID PUMP FROM CV WAS 92 REFOUT 12/30/93 POWER SUPPLY FED FROM BUS 10 YES P-90-10 WBS-61230 39 (MCC-26). AGNELLO D FC-881 1 - 09/28/89 OP-12/12/89 RETIRE STACK GAS MONITORING SYSTEM. RMD REMOVE RIA's 2318, 2319 FROM RAD 01/31/90 12/30/91 RECORDER P- -

17 ROBERTS WL

F.13 PALTRACK REPORT #21 CERTIFICATION REPORT 05/15/90 OPEN ITEMS PLT STATUS-DATE SIM STS-DATE SYS HARD/ SIM ENGINEER/

PLT SCHDLE DATE SIM SCH DATE CODE SOFT SIMULATOR IMPACT SIM MOD NUMBER/

SOURCE DOC WBS NUMBER PRIORITY DESCRIPTION 1/2 WARE DESCRIPTION COGNIZANT INDY

==

FC-883

===

1 - 10/19/89

==

OP-12/12/89

=======================

INSTALL MINIMUM FLOW ORIFICE ON FW YES

=======================

HS IN C-01 AND POSITION LIGHTS

===

90 REFOUT 12/30/91

/

P-8C. YES P- -

1 MEIGH KP

. FC-885 1 - 11/10/89 OP-11/30/89 EC-33 HUMAN FACTORS MODIFICATIONS. SI YES 90 REFOUT 12/30/91 YES P- -

207 WADE MR FC-887 2 - 04/02/90 OP-01/31/90 REVISE LTOP CURVE. RC NO 06/01/90 12/30/91

' 2 YES P- -

SONNENBERG DJ FC-888 x - 01/03/90 . OP-01/31/90 UPGRADE REACTOR PROTECTION SYSTEM NI . YES 92 REFOUT 12/30/93 BISTABLE TRIP UNITS AND POWER RP YES P- -

WBS-43310 12 SUPPLIES. FERENS MA FC-892-01 1 - 02/11/90 OP-03/16/90 IMPROVE STEAM GENERATOR BLOWDOWN SG 90 REFOUT 12/30/91 SYSTEM - PHASE I. YES P- -

WBS-44264 0 MULLHOLAND AD FC-892-02 x - 01i22/90 OP-03/16/90 IMPROVE STEAM GENERATOR BLOWDOWN SG 92 REFOUT 12/30/93 SYSTEM - PHASE 11. YES P" -

WBS-44264 0 MULLHOLAND AD FC-900 x - 02/13/90 OP-03/16/90 UPGRADE BORIC ACID MAKEUP WATER AND CV YES 92 REF OUT 92 REFOUT 12/30/93 BORATION FLOW SYSTEM CONTROLLERS YES P- -

0 AND FLOW TRANSMITTERS. MEYERS DR SC-84-091 5 - 01/28/85 OP-11/08/89 REPLACEMENT METERS FOR RIA-2323, RMD RLT 2326 & 2327 ONLY AJH 07/15/90 2324, 2326, & 2327. YES P-85-04 400 LEVA TE SC-85-166 5 - 11/30/88 OP-11/30/88 REPLACE RIA-1049 AND RE-1049. RMD RLT PER LAS, 9/87 WED 10/05/90 WP YES P-87-48 242 RADZWION DJ SC-87-117 2 - 06/05/87 OP-07/25/89 CHANGEOUT OF SV-2003, SV-2004 AND CV (PER WAS, 8/87) 90 REFOUT 12/30/91 SV-2005. P- -

400 CEDARQUIST SC SC-87-228 5 - 04/12/88 OP-04/12/88 REPLACE RE-1815, RIA-2318 AND RMD RLT (PER WAS 12/87) WED 10/05/90 RIA-2319. YES P-87-48 242 RADZWION DJ SC-87-352 5 - 01/25/88 OP-01/25/88 ADD REFLASH CAPABILITY TO EK-0231. RMD NO CODE TO BE ADDED WITH MODEL AJH 07/15/90 ANN YES P-85-04 57 WESTERHOF RS .

SC-88-088 2 - 04/14/89 OP-07/25/89 REPLACE *iA-2327. RMD

RLT CHANGE TO DIGITAL WED 90 REFOUT 10/05/90 YES P-87-48 450 RADZWION DJ

.F.14

PLT STATUS-DATE PALTRACK REPORT #21 SIM STS-DATE 05/18/90

SYS HARD/

CERTIFICATION REPORT OPEN ITEMS SIM ENGINEER/

PLT SCHDLE DATE SIM SCH DATE CODE SOFT SIMULATOR IMPACT SIM MOD NUMBER/

SOJRCE DOC WBS NUMBER PRIORITY DESCRIPTION . 1/2 WARE DESCRIPTION COGNIZANT !NOV

=============== ============ =================================== ==== ----- =================================== ---------------

SC-88-180 5 - 04/28/89 OP-11/18/88 ADD MANUAL OVERRIDE TO VOP-3025 AND CV WAS 88 REFOUT 12/21/90 VOP-3055. YES P-90-10 228 LITWINSKI CA SC-88-185 5 - 12/07188 OP-12/07188 CHANGE STROKE TIMES FOR CV-3029, CV WAS 12/21/90 CV-3030,. CV-3031 AND CV-3057. SI YES P-90-10 243 SAARELA TC SC-88-288 5 - 01/24/89 OP-12/05/88

LS-5305/5306 - INSTALL JUMPER ON cw NO LEVEL SWITCHES DISABLED UNTIL WED 02/28/89 07/15/90 C/T PUMP START PERMISSIVE FOR YES VACUUM SYSTEM IS FIXED P-90-02 104 DISCHARGE PIPE LEVEL. TIFFANY ER SC-88-298 5 - 01/03/90 OP-07/25/89 REPLACE PB-34L AND PB-34R WITH KEY SI YES WAS 89 MAOUT 07/15/90 LOCK SWITCH. NO P-90-04 1 CORBETT RJ SC-89-026 .. 5 - 02/19/90 OP-07/25/89 REPLACE HIC/POC-3003, HIC/POC-3004, SI YES WAS 89 MAOUT 10/05/90 HIC/POC-3039 ANO HIC/POC-3043. YES P-90-08 39 RADZWION DJ SC-89-032 5 - 02/19/90 OP-07/25/89 REPLACE PIC-0338, PT-0338, SI YES WAS 89 MAOUT 10/05/90 PIC-0342, PT-0342, PIC-0346, YES P-90-08 39 PT-0346, PIC-0347, AND PT-0347. RADZWION DJ SC-89-048 5 - 10/30/89 OP-W/25/89 REPLACE TI-0101 AND Tl-0102. RC FAIL DOWNSCALE ON LOSS OF AC.

89 MAOUT 12/30/91 YES P- -

51 KENNEDY OM SC-89-050 2 - 08/07/89 OP-07/25/89 REPLACE PT-0751A-D AND PT-0752A-D SG YES CHANGE RANGE TO 0-1200.

90 REFOUT 12/30/91 FOR RG 1.97. YES P- -

51 ANDREWS KH SC-89-051 5 - 10/30/89 OP-07/25/89 UPGRADE QUENCH TANK TEMPERATURE RC YES CHANGE RANGE TO 0-350.

89 MAOUT 12/30/91 LOOP TIA-0116 TO COMPLY WITH RG YES P- -

84 1.97. SEAMANS LO SC-89-061 5 - 10/25/89 OP-07/25/89 CHANGE TI-0328 FROM SIGMA TO SI FAIL DOWNSCALE ON LOSS OF AC. WAS 89 MAOUT 10/05/90 VERSATILE. YES P-90-08 39 KENNEDY OM SC-89-075 5 - 10/25/89 OP-04/06/89 REPLACE LIA-2021 AND LIA-2022 ON FW NO FAIL DOWNSCALE ON LOSS OF AC 12/30/91 T-2. YES P- -

39 KENNEDY OM SC-89-082 5 - 07/14/89 OP-04/06/89 ADD REFLASH.CAPABILITY TO EK-0207 RMD RGEM ON C11A AJH

. 07/01/89 07/15/90 AND EK-0219. P-85-04 39 WESTERHOF RS SC-89-083 5 - 11/13/89 OP-04/06/89 HIGH PRESSURE SAFETY INJECTION HOT SI NO FAIL DOWNSCALE ON LOSS OF AC WAS 89 MAOUT 10/05/90 LEG PRESSURE AND FLOW. YES P-90-08

.F.15 PLT STATUS-DATE PAL TRACK REPORT #2.1 SIM STS-DATE 05/18/90

SYS HARD/

CERTIFICATION REPORT OPEN ITEMS SIM ENGINEER/

PLT SCHOLE DATE SIM SCH DATE CODE SOFT SIMULATOR IMPACT SIM MOO NUMBER/

SOURCE DOC WBS NUMBER PRIORITY DESCRIPTION 1/2 WARE DESCRIPTION COGNIZANT !NOV

====== =============== ======

39

=================================== ---- ===== =================================== ---------------

KENNEDY OM SC-89-099 5 - 12/29/89 OP-04/06/89 PLUG TUBES IN E-50B. SG NO 89 MAOUT 12/30/91 YES P- -

CEDARQUIST SC 39 SC-89-107 5 - 12/29/89 OP-04/06/89 PLUG TUBES IN E-50A. SG NO 89 MAOUT 12/30/91 YES P- -

39. CEDARQUIST SC SC-89-109 5 - 11/13/89 OP-05/02/89 REPLACE FI-0727A, FI-0736A, FI-0737 FW FAILURE MODE 89 MAOUT 12/30/91 . AND FI -0749A". YES P- -

75 KENNEDY OM SC-89-114 5 - 03/20/90 OP-05/02/89 REPLACE RE/RIA-0707. RMD WED 12/30/89 10/05/90 P-87-48 36 RADZWION DJ SC-89-116 5 - 11/13/89 OP-05/04/89 REPLACE TI-1815. CH NO FAIL DOwNSCALE ON LOSS OF .AC 89 MAOUT 12/30/91 YES P- -

75 KENNEDY OM SC-89-117 5 - 11/09/89 OP-05/04/89 REPLACE TI-0303. CV NO FAIL DOWNSCALE ON LOSS OF AC 12/30/91 YES P- -

75 KENNEDY OM SC-89-123 5 ~ 10/25/89 OP-05/02/89 REPLACE LIA-0920. cc FAILURE MODE 12/30/91 P- -

75 KENNEDY OM SC-89-132 5 - 11/13/89 OP-05/02/89 REPLACE TIC-0201. CV FAILURE MODE 89 MAOUT 12/30/91 YES P- -

75 KENNEDY OM SC-89-133 5 - 11/13/89 OP-05/04/89 REPLACE TIA-0205. CV NO FAIL DOWNSCALE ON LOSS OF AC 89 MAOUT 12/30/91 YES P- -

75 KENNEDY OM SC-89-179 5 - 11/03/89 OP-07/11/89 REPLACE P-40A/B AMMETERS CEAI-1102 cw YES CHANGE SCALE TO 0-150 WED 12/30/89 07/15/90 AND EAI-1309). YES P-90-02 41 HAUMERSEN J SC-89-213 5 - 09/22/89 OP-07/12/89 CHANGE SET POINT FOR TIA-0107, RC YES SHOULD ONLY BE A HARDWARE CHANGE WED 07/03/89 07/15/90 TIA-0108 AND TIA-0109. P-90-06 1 GRIEVES TS SC-89-242 1 - 08/04/89 OP-09/28/89 REPLACE FQIS-0210A. CV YES CHANGE TO DIGITAL 90 REFOUT 12/30/91 YES P- -

45 KENNEDY DM I.

PALTRACK REPORT #21 05/18/90

- CERTIFICATION REPORT OPEN ITEMS

. 16 PLT STATUS-DATE SIM STS-DATE SYS HARD/ SIM ENGINEER/

, PL T SCHDLE DATE SIM SCH DATE COOE SOFT SIMULATOR IMPACT SIM MOD NUMBER/

SOURCE DOC was NUMBER PRIORITY DESCRIPTION 1/2 WARE DESCRIPTION COGNIZANT INDV

==

SC-89-290

===

5 - 03/20/90

==

OP-12/01/89

=======================

CHANGE EK-0200 ALARM ACTUATION.

TC NO

============================.= =========

03/26/90 12/30/91 YES P- -

2 PALMISANO GG SC-89-291 2 - 04/10/90 OP-12/12/89 REPLACE RADIATION RECORDERS. RHO YES CHANGE 2300, 01, 02 TO 90 REFWT 12/30/91 YES ESTERLINE-ANGUS P- -

1 KENNEDY DM SC-89-293 2 - 03/26/90 OP-12/12/89 REPLACE FEEDWATER AND LEVEL FW YES CHANGE LR .AND FR"S 0701/0703 TO 90 MAOUT 12/30/91 RECORDERS. YES CHESSELL P- -

1 KENNEDY DM SC-89-328 5 - 01/23/90 OP-01/10/90 REDUCE TIME SETTING FOR CONTROL CH NO CH MODULE EQ 541 CHANGE TIMER FROM 03/01/90 12/30/91 ROOM HVAC TIMING RELAYS 62-3 AND YES TWO MIN TO ONE MIN P- -

212 62-4. PHILLIPS LT SC-89-334 5 - 01/30/90 OP-12/12/89 REPLACE PT-0208 AND PIC-0208. CV YES CHANGE PIC-0206 AND 0208 TO WAS 89 MAOUT 12/30/91 YES YOKOGAWA P-90-08 54 KENNEDY DH SC-89-335 5 - 12/28/89 OP-01/10/90 UPGRADE TI-0530 AND TI-0533 TO A TU YES REHEATER CONTROL POWER 03/16/90 12/30/91 32-600 DEGREE RANGE, MS YES P- -

122 O'CONNELL WT SC-89-339 5 - 12/13/89 OP-12/01/89 CHANGE MINIMUM CLOSURE STROKE TIME CV NO 03/01/90 12/30/91 FOR CV-3029 AND CV-3030. YES P- -

403 SAARELA TC SC-89-348 5 - 01/05/90 OP-12/13/89 REPLACE PENS ON PTR-0112 AND RC YES CHANGE PEN COLORS 06/01/90 12/30/91 PTR-0122. NO P- -

1 SONNENBERG DJ SC-89-354 3 - 04/12/90 OP-01/31/90 CHANGE LOW LEVEL SET POINT FOR ED2 YES 04/16/90 12/30/91 LIA-1400. YES P- -

114 SWIECICKI TJ SC-89-363 2 - 02/12/90 OP-01/31/90 REVERSE TURBINE NO-LOAD PRETRIP TU NO 452X TO NC CONTACT ON E-287, SH 1, 90 MAOUT 12/30/91 ALARM LOGIC. TC YES K-01(7) P- -

2 HAUMERSEN J SC-90-003 1 - 01/08/90 OP-01/31/90 REPLACE TR-0351. SI YES S/D COOLING RECORDER REPLACEMENT 90 REFOUT 12/30/91 YES P- -

12 MEYERS DR SC-90-005 2 - 02/12/90 OP-01/31/90 CHANGE PC-0521 CONTROLLER SET'POINT .MS NO 90 MAOUT 12/30/91 . AND ANTI-RESET WIND-UP ORIENTATION. YES P* -

52 BIXEL DA SDR-84-027 I I OP-08/14/84 PSC LEAK INTO CNTMT HUMIDITY, TEMP, CH NO REMOVED FROM P85-17 12/30/91 RAD LEVELS YES P- -

223

.F.17 PLT STATUS-DATE PALTRACK REPORT #21 SIM STS-DATE 05/18/90

SYS HARD/

CERTIFICATION REPORT OPEN ITEMS SIM ENGINEER/

PLT SCHDLE DATE SIM SCH DATE . CODE SOFT SIMULATOR IMPACT SIM MOD NUMBER/

SOURCE DOC WS NUMBER PRIORITY DESCRIPTION 1/2 WARE DESCRIPTION COGNIZANT !NOV

=============== ============ =================================== ==== ----- =================================== ===============

SDR-84-069 I I OP-10/23/84 CONTAINMENT SUMP LEVEL WHEN QUENCH CH NO 12/30/91 TANK DISC RUPTURES YES P-86-09 30 SDR-86-017 I I OP-01/28/86 SIG PRESS DOES NOT RESPOND SG 12/30/91 CORRECTLY ON SGTR P- -

227 SDR-86-144 I I OP-12/10/86 CV 2083 *& CV 2099 MODELED ON WRONG CH NO 12/30/91 POWER SUPPLIE~ & WRONG ISOCATION CV YES P- -

123 RELAYS SDR-87-010 I I OP-01/08/87 CONTROLLERS FIC-0306 AND TIC-0203 SI NO 12/30/91 DON'T OPERATE IN AUTO CV YES P-87-31 109 SDR-87-013 I I OP-01/08/87 TURB GEN COLD GAS OUTLET TEMP, EG NO 12/30/91 TR-0505, SHOULD BE 45 DEG. C., NOT TU YES P-87-25 259 31 DEG. C, LOSS OF SW FLOW DOESN'T CAUSE HI TEMP ALARM SDR-87-092 I I OP-09/01/87 RIA 1809, 2319, AND 2319 DON'T RMD NO 12/30/91 RESPOND TO AUX BLDG LEAK YES P- -

125 SDR-87-093 I I OP-09/01/87 PRESSURIZER HEATER AMP METER IS NOT PZR 12/30/91 LINEAR, BUT INPUT TO IT.IS YES P- -

255 SDR-87-116 I I OP-09/30/87 CONTROL PANEL C-27 DOES NOT WORK NI Nq 12/30/91 CORRECTLY. IT SHOULD GO TO 125 YES 79 WHEN +10V IS DEPRESSED, BUT GOES TO 120 INSTEAD c

SDR-87-120 I I OP-10/07/87 FILLING SI TANKS WITH CTMT SPRAY SI NO 12/30/91 PUMPS CAUSES PCS PRESSURE TO YES 83 INCREASE SDR-87-124 I I OP-10/21/87 SIT LEVEL AND PRESSURE ALARMS DO SI NO 12/30/91 NOT WORK PROPERLY. YES 54 SDR-87-151 I I OP-12/23/87 SOME AIR OPERATED VALVES LIN~D UP IA NO 12/30/91 TO INCORRECT AIR SUPPLY. YES 230 SDR-88-024 I I OP-02/10/88 MALF TC02 DESCRIPTION DOESN'T AGREE TC NO INSTRS DO NOT GET SCENARIO EXPECTED 12/30/91 WITH ACT.EFFECT: SAYS BLOCKS 20/AST RP YES OPPORTUNITY FOR DIAGNOSTIC EXERCISE 119 AS MODELED, BLOCKS 20/AST, 20/ET, IS LOST 305L, 305R

F .18 PALTRACK REPORT #21 CERTIFICATION REPORT 05/18/90 OPEN ITEMS PLT STATUS-DATE SIM STS-DATE SYS HARD/ SIM ENGINEER/

PLT SCHDLE DATE SIM SCH DATE CODE SOFT SIMULATOR IMPACT SIM MOO NUMBER/

SOURCE DOC WS NUMBER PRIORITY DESCRIPTION 1/2 llARE DESCRIPTION COGNIZANT INDV

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

SDR-88*030 I I OP-09/25/86 ANNUNCIATORS FAILED P*86*25 TEST ANN SIM MOO P*86*39 llAS ORIGINALLY 12/30/91 PROCEDURE YES OPENED lllTHOUT ASPR P*86*39 96 SDR*88*039 I I OP-03/16/88 SPI RESPONSE TO PIP MALFUNCTION RD NO NEGATIVE TRAINING 12/30/91 INCORRECT PPC YES 69 SDR*88*124 I I OP-09/02/88 RP01A DOES NOT llORK RIGHT: SHOULD RP NO REDUCES INSTR. CHOICES IN SETTING 12/30/91 BE SAME AS RP01B. PCM YES UP SCENARIO.

27 RLDICKS SDR*88*127 I I OP-09/02/88 CC\I MALFUNCTION CC03, AND CC MAKEUP cc NO PLANT CAN'T SURVIVE A LEAK OF

.12/30/91 FLOllS ARE llRONG. CV YES MAGNITUDE CURRENT MODEL SHOllS AS 265 TOLERABLE. BL SCHANER SDR*88*129 I I OP-09/02/88 DELETE MALF. F1102, Fll03, AND Fll05. Fii NO REDUNDANT, OBSOLETE MALF. CLUTTERS 12/30/91 NO LONGER NEEDED. PCM YES PCM SCREEN. ADDS UNNECESSARY EFFORT 461 TO CERT. BL SCHANER SDR*88*158 I I OP-11/29/88 CV5301 & 5305 AUTO-CLOSE llHEN P39A Cll NO MISLEADING TO TRAINEES 12/30/91 TRIPPED BY uv .** THEY SHOULD NOT ED YES P-88*39 20 BL SCHANER SDR*88*162 I I OP-05/08/89 ELECTRIC FIRE P9A FAILED TO START Sii NO MISLEADING TO TRAINEES 12/30/91 llHEN AUX Fii P8A DEMANDED GREATER YES 113 THAN 300 GPM FROM FIRE llATER SYSTEM BLSCHANER SDR*88*163 I I OP-11/29/88 NO VIBRATION ALARM RECEIVED UPON RC NO MISLEADING TO TRAINEES 12/30/91 PCP COUPLING FAILURE: MALF RC07 YES 66 BL SCHANER SDR*88*164 I I OP-11/29/88 REACTOR DP, PC FLOll, AND PCP AMPS RC NO NEGATIVE TRAINING 12/30/91 ALL CHANGE IN llRONG DIRECTION FOR YES 66 MALF RC07 BL SCHANER

soR-88*165 I I OP-11/29/88 PCP CONT B.O. FLOll DOES NOT RC NO MISLEADING TO TRAINEES 12/30/91 INCREASE UPON FAILURE OR MIDDLE CV YES 66 SQAL: MALF RC13 BL SCHANER SDR*89*012 I I OP-02/01/89 DELETE MALFUNCTION F1112: NO FW NO USE LESS MALFUNCTION ADDS CLUTTER 12/30/91 TRAINING VALUE PCM YES TO PCM 226 BLS/DRA SDR*89*015 I I OP-02/21/89 "POllER ON" INDICATING LIGHT ON EG SIMULATOR CERTIFICATION (TEST 12/30/91 Pl-1419 DOES NOT GO OFF WHEN POllER YES M051), P-89*16 205 IS LOST TO INSTRUMENT (ED07). GJASHWORTH SDR*89*016 I I OP*02/21/89 TRIPPING OF "B" CAC FANS ON CHP CH SIMULATOR CERTIFICATION (TEST 12/30/91 EXTINGUISHES BOTH BREAKER LIGHTS

SI YES M021).

PLT STATUS-DATE PALTRACK REPORT #21 SIM STS-DATE 05/18/90

SYS HARD/

CERTIFICATION REPORT OPEN ITEMS

. 19 SIM ENGINEER/

PLT SCHDLE DATE SIM.SCH DATE CODE SOFT SIMULATOR IMPACT SIM MOO NUMBER/

SOURCE DOC WBS NUMBER PRIORITY DESCRIPTION 1/2 WARE DESCRIPTION COGNIZANT INDY

====== =============== ======

82

=======================

SHOULD TURN OFF RED AND TURN ON

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

GJASHWORTH GREEN. SEE E218.

SDR-89-019 - . I I OP-05/09/89 LIA-0365 LOSS OF POWER FAILURE MOOE SI SIMULATOR CERTIFICATION (TEST 12/30/91 IS INCORRECT. SHOULD FAIL AS IS, YES M052).

92 CURRENTLY FAILS DOWNSCALE. GJASHWORTH SDR-89-025 I I OP-02/21/89 VARIABLE MALF FWOBA DOESN'T YIELD FW SIMULATOR CERTIFICATION (TEST 12/30/91 EXPECTED RESULT - ie 10% DOESN'T YES M070). P-89-25 72 PRODUCE 10% VALVE .POSITION, ONLY 5% GJASHWORTH OPENING.

SDR-89-026 I I OP-02/21/89 "D" CHANNEL OF TMD DOESN'T GO BLANK ED SIMULATOR CERTIFICATION (TEST

. 12/30/91 UPON LOSS OF Y40 CEDoaD) IF CH A&B TMD YES M052). P*89-16 62 ARE SELECTED FOR DISPLAY. GJASHWORTH SDR-89-027 I I OP-02/22/89 MALF MSOS CMS LINE LEAK-OUTSIDE) PCM SIMULATOR CERTIFICATION (TEST 12/30/91 PRODUCES > SOX STEAM FLOW - ITS MS YES M089).

72 DESCRIPTION SAYS n SHOULD ADD 10% GJASHWORTH STEAM FLOW.

SDR-89-028 I I OP-02/22/89 PRIMARY COOLANT FLOW AS SHOWN ON RC SIMULATOR C.ERTIFICATION (TEST 12/30/91. FI0102A,B,C,D HAS NO INCREASE WHEN YES M103).

247 MALF RCOS (CORE BARREL FAIL) IS GJASHWORTH ACTIVATED.

SDR-89-029 I I OP-02/22/89 HI VIBRATION INDICATION CMALF RC16) RC SIMULATOR CERTIFICATION (TEST 12/30/91 ON TRIPPED PCP DOESN'T D.IMINISH YES M114).

66 UNTIL Cil 50 SEC - PUMP SHOULD STOP Iii GJASHWORTH 30 SECONDS.

SDR-89-030 I I OP-02/22/89 IMPROPER RADIATION MONITOR RMD SIMULATOR CERTIFICATION (TESTS M120 12/30/91 RESPONSES - MALF RC22 DOESN'T RAMP, PCM YES &M138).

63 SEVERITY vs METER SCALE DIFF, MALF GJASHWORTH RM07 DOESN'T RAMP.

SDR-89-031 I I OP-02/22/89 IMPROPER EQUIPMENf RESPONSES TO HI RMD SIMULATOR CERTIFICATION.

12/30/91 RADIATION - V14A/B, P01809, CH YES 64 cvono1on1. GJASHWORTH SDR-89-032 I I OP-02/22/89 WITH MALF RP02A ACTIVE CSU HV NI SIMULATOR CERTIFICATION (TEST 12/30/91 FAIL), DRAWER TRIP TEST SW GAVE NO YES M141).

79 AUDIBLE CR, BUT TRIPPED FLUX TILT GJASHWORTH ALARMS ON ALL 4 CHNLS SDR-89-033 I I OP-02/22/89 MALF RP21A IN & RPS IS RESET AFTER RP SIMULATOR CERTIFICATION (TEST 12/30/91 TRIP - M1 STAYS TRIPPED AS IT YES M160). P- -

79 SHOULD BUT M1 V-METER RETURNS TO GJASHWORTH NORMAL FROM ZERO.

.F.20 PLT STATUS-DATE PALTRACK REPORT #21 SIM STS-DATE 05/18/90

SYS HARD/

CERTIFICATION REPORT OPEN ITEMS SIM ENGINEER/

PLT SCHDLE DATE SIM SCH DATE CODE SOFT SIMULATOR IMPACT SIM MOD NUMBER/

SOJRCE DOC WBS NUMBER PRIORITY DESCRIPTION 1/2 \IARE DESCRIPTION COGNIZANT INDV

====== =============== ============ =================================== ==== ===== =================================== ?========

SDR-89-034 I I OP-02/22/89 MALF RX09 DOESN'T DISABLE "BACKUP RX SIMULATOR CERTIFICATION (TEST 12/30/91 VOLUME CONTROL" SIGNAL AS CV YES M178). P- -

66 ADVERTISED. GJASH\IORTH SDR-89-035 I I OP-02/22/89 MALF RX10A DOESN'T AFFECT Ll0702 ON SG SIMULATOR CERTIFICATION (TEST 12/30/91 C33 PANEL*, AS IT SHOULD - ONLY RX YES M179).

51 AFFECTS LIA0702 ON C12. GJASH\IORTH SDR-89-036 I I OP-02/23/89 MAIN TURB & GEN BRGS.OIL OUTLET TU NO SIMULATOR CERTIFICATION (TEST ERQ 12/30/91 TEMPS DON'T RESPOND TO INCREASE IN S\I YES M197). P-90,09 121 OIL SUPPLY TEMP. GJASH\IORTH SDR-89-037 I I OP-02/23/89 MALF TC08 (TURB SPEED CNTRL_ ERR) TC SIMULATOR CERTIFICATION (TEST 12/30/91 DOESN'T CAUSE SHIFT FROM OPER AUTO YES M211).

89 TO MAN \IHEN SPEED ERR EXCEEDS 600 GJASH\IORTH r/min AS IT SHOULD SDR-89-038 I I OP-02/23/89 MALF TU01 (TURB HI VIB) PROBLEMS - TU SIMULATOR CERTIFICATION (TEST 12/30/91 VIB DROPS INSTANTLY ON TRIP, 'OIL YES M217).

121 TEMPS DROP TOO FAST, NO HI TEMP GJASH\IORTH ALARM.

SDR-89-039 I I OP-02/23/89 ALARM K01-3 FOR TURB ECCENTRICITY TU SIMULATOR CERTIFICATION (TEST 12/30/91 DIDN'T TRIP \IHEN ECCENTRICITY* YES M221).

121 EXCEEDED SETPOINT. GJASH\IORTH SDR-89-047 I I OP-03/27/89 _PZR PRESS FELL TOO LO\I ON AN . RC NO COMPLICATES TRAINEES' DIAGNOSES OF 12/30/91 UNCOMPLICATED RX TRIP \I/NORMAL. TAV YES TRANSIENTS 56 & PZR LEVEL RESPONSE. SEE CERT TEST EHKOEPKE T002 SDR-89-049 I I OP-03/27/89 PCP/PC FLO\I COASTDO\IN TOO SLO\I ON RC NO COMPLICATES TRAINEES' DIAGNOSES OF 12/30/91 SINGLE PUMP TRIP FROM 4 PUMP YES TRANSIENTS 66 OPERATION - SEE CERT TEST T005 'EHKOEPKE SDR-89-050 I I OP-03/27/89 SG LEVEL RESPONSES TO SINGLE PCP SG NO COMPLICATES TRAINEES' DIAGNOSES OF 12/30/91 TRIP ARE* REVERSE OF \IHAT THEY RC YES TRANSIENTS 112 SHOULD BE EH KOEPKE IE, \IRONG ONE HAS GRTR DROP-SEE CERT TEST T005 SDR-89-051 I I OP-03/29/89 REAL TIME TEST REVEALED DISCREPANCY TC NO FAILS TEST OF REAL TIME SIMULATION 12/30/91 ON TURB LOAD C~ANGE RATE-SEE CERT YES 500 TEST RT04 EHKOEPKE SDR-89-055 I I OP-03/29/89 VCT DRA\IDO\IN DOES NOT AGREE \llTH CV NO COMPL.ICATES TRAINEES' DIAGNOSES OF 12/30/91 NET CHARGING \llTHDRA\IAL: \llTH NET YES SOME MALFUNCTIONS 94 409PM, LEVEL CHANGE = 60 GPM-SEE EH KOEPKE CERT TEST RT03 I

I

.F.21

(

PALTRACK REPORT #21 CERTIFICATION REPORT 05/18/90 OPEN ITEMS PLT STATUS-DATE. SIM. STS*DATE SYS HARD/ SIM ENGINEER/

PLT SCHDLE DATE SIM SCH DATE CODE SOFT SIMULATOR IMPACT SIM MOD NUMBER/

SCXJRCE DOC WS NUMBER PRIORITY DESCRIPTION 1/2 WARE DESCRIPTION COGNIZANT INDV

==

SDR-89*056

========= ======

OP-03/29/89

=======================

VCT AUTO MAKEUP DOES NOT STOP WHEN

==

CV NO

=======================

COMPLICATES TRAINEES' DIAGNOSES OF

===

WAS I I 12/21/90 ITS SUPPOSED TO YES TRANSIENTS P-90-10 17 CONTINUES UP TO 94X VS SETPOINT OF EHKOEPICE 78.5X*SEE CERT TEST N001 SDR-89-057 I I OP~03/29/89 PCP FLOW RATES AT REDUCED RC NO COMPLICATES TRAINEES' DIAGNOSES OF 12/30/91 TEMPERATURE NOT CALCULATED YES . TRANSIENTS 247 CORRECTLY~SEE CERT TEST N001 EHKOEPICE SDR-89-058 I I OP-03/02/89 CONDENSATE PUMP AMPS.TOD LOW ON FW NO COMPLICATES TRAINEES' DIAGNOSES OF 12/30/91

INITIAL PUMP START AND WHEN RUNNING YES SOME MALFUNCTIONS 226 ON RECIRC*SEE CERT TEST N001 EHKOEPKE SDR-89-059 I I OP-03/29/89 PZR PRESS DOES NOT RESPOND TO RC NO COMPLICATES TRAINEES' DIAGNOSES OF 12/30/91* PRC0101 75X SIGNAL DURING BUBBLE YES SOME MALFUNCTIONS 43 VERIFICATION STEP IAW SOP1, EHKOEPKE 7.1.4N*SEE CERT TEST N001 SDR-89-062 I I OP-03/30/89 SG LEVELS DO NOT ALWAYS FALL TO SG NO COMPLICATES TRAINEES' DIAGNOSES OF 12/30/91 APPROPRIATE MINIMUM UPON RX YES TRANSIENTS 112 TRIP-SEE CERT TEST N003 EHKOEPKE SDR-89-063 I I OP-03/30/89 10X REDUCTION IN TURB CONTROL TC NO COMPLICATES TRAINEES' DIAGNOSES OF WAS 12/21/90 REFERENCE DOES NOT CAUSE 10X YES TRANSIENTS P-90-10 89 REDUCTION IN GENERATOR LOAD EHKOEPKE (IMPULSE IN)*SEE CERT TEST N005 SDR-89-064 I I OP-03/30/89 ASDV CLOSING STROKE TIME TOO' LONG MS NO COMPLICATES TRAINEES DIAGNOSES OF 12/30/91 48 SEC VS 9 SEC-SEE CERT TEST N006 RX YES TRANSIENTS 9 EHKOEPKE SDR-89*065 I I OP-04/04/89 RPS TESTING SYSTEM DOES NOT OPERATE RP NO COMPLICATES:TRAINEES' UNDERSTANDING 12/30/91 CORRECTLY. AC AND DC LIGHTS GO OFF YES OF THE RPS TESTING SYSTEM 27 WHEN THEY SHCXJLD NOT. SIMULATOR EHKOEPKE CERT TEST N008 SDR-89*085 I I OP-05/04/89 FEEDWATER FLOW DOES NOT MATCH THE FW NO SIMULATOR CERTIFICATION TEST N007 12/30/91 PLANTS WITHIN THE 2X TOLERENCE AT SG YES 39 THE 75X & 100X POWER LEVELS-CERT EHKOEPKE TEST N007 SDR-90-030 I I OP-04/10/90 GROSS/NET GEN CXJTPUT AS INDICATED EG DOES NOT MEET CERT TEST 12/30/91 ON PRI DATA LOGGER CPIP) ARE NOT REQUIREMENTS P- -

0 ACCURATE TO 2X VALUES PER ANSI N007 WE DRUMMOND CERT TEST.

SDR-90-035 I I OP-05/11/90 PRESSURIZER LEVEL OSCILLATES ABCXJT PZR NO 12/30/91 2X ARCXJND SET POINT. REF STEADY RC YES 27 STATE TEST NOOl. WEDRUMMOND

PLT STATUS-DATE PALTRACK REPORT #21

.SIM STS-DATE 05/18/90 ** SYS . HARD/

CERTIFICATION REPORT OPEN ITEMS SIM ENGINEER/

PLT SCHDLE DATE SIM SCH DATE CODE SOFT SIMULATOR IMPACT . SIM MOO NUMBER/

SOURCE DOC WBS NUMBER PRIORITY DESCRIPTION 1/2 WARE DESCRIPTION COGNIZANT INDV

====== =============== . ============ =================================== ==== ----- =================================== =========

SDR-90-049 I I OP-05/18/90 PPDIL/PDIL HORNS IN C12 DO NOT RD INADEQUATE TRAINING WED 12/30/91 ALARM WHEN REQUIRED 120 WE DRUMMOND SPC-85-025 5 - 11/17/87 OP-04/27/89 RIA-2326 ALERT/ALARM SET POINT RMD RLT. AJH 07/15/90 REVISED. YES P-85-04 243 .

SPC-85~026 5 - 11/17/87 OP-04/27/89 RIA-2327 ALERT/ALARM SET POINT RMD RLT AJH 07/15/90 REVISED. . YES P-85-04 244 SPC-85-027 5 - 11/17/87 OP-04/27/89 RIA-2318 ALERT/ALARM SET POINT RMD RLT AJH 07/15/90 .. REVISED. YES P-85-04 245

SECl'ION G

PERFORMANCE TESTING

SCHEDULE

PERFORMANCE TESTING SCHEDULE Tests to be conducted the first year following certification (1991):

The Palisades simulator is scheduled to be moved from its existing location i~ Midland, Michigan to the Palisades plant site in Covert, Michigan in April, 1991.

Although this move is significant to the hardware portion of the simulator, no software changes ~ill occur to t~e code utilized for training during the move. After the move, significant hardware diagnostic testing is planned and the

software~testing Scheduled is as follows:

1. Operability Test

a. One Steady State Test (N007).

b. Ten Trartsient Tests (TOOl through TOlO).

2. Performance Test

a. Approximately25% of.the Malfunction Tests (Note: This testing includes complete coverage of the_

ANSI Standard requirements listed in section*3.1~2)

MOOl M046 MOSS M130 M17S MOOS M050 M,092 M137 M185 M009 M054 Ml02 Ml41 M186 M013 M057 Ml03 M145 M190 M020

M063 Ml07 M149 M196 M024 M066 M109

M158 M198 M029* M071 Mll7 M162 M203 M033 M076 Ml20 *. Ml66 M207 M037* MOS2 M125 . M170 M213 M042 M084 M129 M174* M218

b. Approximately 25% of the Normal Operation Tests (N004,-

N005 and .N006).

c. Approximately 25% of the Real Time Tests (RTOl and RT05) .

B. Tests to be conducted the second year following certification

( 1992) :

The entire Performance Test is scheduled to be conducted due to

planned module upgrades of the core, pressurizer, reactor coolant system, containment .and radiation monitoring system~

l*

G.1

P.ERFORMANCE TESTING SCHEDULE

. * -c. Tests to be conducted the third year following certification (1993):

1. Operability Test

a. One Steady State Test (N007).

b. Ten Transient Tests (TOOl through TOlO).

2 . Performance Test

a. Approximately 25% of the Malfunction Tests MOOl M046 MOSS M133 Ml7S M005 M050 M092 M137 MlS2 M009 M054 M096 M141 M1S6 M013 M057.5 Ml03 M145 Ml90 M020 M060 M107

Ml49 Ml94*

M025 M066 Mlll Ml53 M19S*

M029 M071 MllS M162 M203 M033 M076 Ml2_0 M166 M207 M037 MOSO M125 Ml70 M213 M042 MOS4 M129 M174 M21S

b. Approxi~ately 25% *of the Normal Operation Tests (NOOl)

c. Approximately 25% of the Real* Time Tests (RTOl and RT05)

D. Tests to be.condubted the fourth ye~r tollowing certification (1994):

1. Operability Test

a. One Steady state Test _(N007) *

b. Ten Transient Tests (Tooi through TOlO).

2. Perf orman~e ~est :

a. Approximately 25% of th~ Malfunction Tests M003 M044 M090 M135 Ml76 M220 M007 M04S M094 M139 Ml SO MOll 'M052 M09S M143 M1S4 M015 M056 M105 M147 Ml SS MOlS M062 . M109 *

M151 Ml92 M022 M069 Ml13 Ml54 - Ml96 M027 M073 M117 Ml60 M201 M031 . M07S M123 Ml64 M205 M035 MOS2* M127 M16S M211 M039 MOS6 M131* M172 M216

b. Approximately 25% of the Normal Operation Tests (N004, N005, N006)

c. Approximately 25% of the Real Time_ Tests (RT03 and RT05)

- - - G. 2

ML18057A261

Text

SUMMARY

RESPONSE

RESPONSE

RESPONSE

RESPONSE

RESPONSE

===================== ========= ======== ==============

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

=

==

========

_::;:::_===================== ========= ======== ===============

====================================================

====================================================

====================================================

====================================================

====================================================

===========================================================?

~=========================================================

~==~==================================================

====== =============================

====== =============== ============ =================================== ==== ===== =================================== =========

==

===

==

=======================

=======================

===

====== =============== ======

==

===

==

=======================

============================.= =========

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

====== =============== ======

=======================

====== =============== ============ =================================== ==== ===== =================================== ?========

==

========= ======

=======================

==

=======================

===

====== =============== . ============ =================================== ==== ----- =================================== =========

Navigation menu

Search