Text

WCGS Simulator Certificate Data
	ML20126B090
Person / Time
Site:	Wolf Creek
Issue date:	12/14/1992
From:	; WOLF CREEK NUCLEAR OPERATING CORP.
To:	;
Shared Package
ML20126B087	List: ML20126B083; ML20126B090;
References
	NUDOCS 9212210376
	Download: ML20126B090 (178)
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U.S. NVCLE AR REGULA10HY COMMISSIC'N APPHOVtu av OMJ. NO. 3 thoo138 Nnc FORM 4/4 ( APIRES. 9 3092 (1401 10 CFR 68 46M, ESTIMAf tD SURDE N PER RESPON5E TO COMPti WITH THIS l 59 d ond &5 % INS OHM AY lON tdt tECt lON REQUEST : 120 HMS. FORW ARD

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,=nuy",*a',;? ;" Jay,yg SIMULATION FACILITT CERTIFICATION U S. NUCLE AR REGULATORY COMMl1$lON. WASHINGTON DC 7tWb5. AND TO THE P APtHvtORet REDUCT40N PROJECT dire ot Nih OF F ICE OF MAN AGE MENT AND DUDOCT, W A$HtNGf 0N.

DC 20$03 I NSTRUCTIONS. This form es to be fned for trut>a! certificetion. setertification Of requoed), arxi for any change to a simulation facihty peqformente testing plan made after initsal S Jbmittal of such 8 plan. Prov6de the followirq Information, and check the appropriate box to iMeste reason for submettal.

F ACILIT Y lDOO.E I NUMbE H Wolf Creek Generatina Station S 4RP LICENSEE lOATE Wolf Creek Nuclear Operdtina Corporation 12/14/92 This is to certity that:

1. The above named facihty lecenses is us ng a simuistion facil,1y coni.iting solely of a plant refersaced simulator that meets the requirements of 10 CF R % 45.

2. Documentauon is esedsbie for NRC revow in accordance with 10 CF R %.45!bl.

3. This simulanon fecihty moeu the gWdance contened in ANSI /ANS 3.5,1985. as endorsed by NRC Regulatory Cume 1,149.

If thef t Efe $ny e ACoptions to the cettfication of this item, cheCh hete l l snd dmcribe fully on addstional pages as tweeuary, NAME tor other sderWecetroo) AND LOCATION OF SIMULATION F ACILliY Wolf Creek Nuclear Operating Corporation P. O. Box 411 Burlington, KS 66839-0411 SIMULATION F ACtUTY PERFORM ANCE TEST ABST R ACTS ATT ACHED (for performance rests cornfueraf in the pariod ending with the dare o/ ths cortification)

DESCR IPTION OF PE R FORM ANCE T EST 6 NG COMPLE T ED (4ttsch odditionet pegels) as necessary, and Mentify the irem efescription being continued)

See Attachment "A". Wolf Creek Simulator Certification Overview.

e SIMULATION F ACILl TY PE RF ORM ANCE TESTING SCHEDULE AT T ACHED. (For the corduc et approumately 25% of perfurrnance rests per year hu the four year period commencing with the date of this certifocati on.)

DESCRlPT10N OF PERFORMANCE TESTING TO BE CONouCTE D. (Attach additenetpagels)as nn:essary, and identify the irem description beme contonval)

See Attachment "A". Wolf Creek Simulator Certification Overview.

PERF0RMANCE TEST lNG PLAN CHAUGE. (For any modsfocation to a performance testingplan submitted on a previous certification)

DESCRIPTtON OF PER FORMANCE TEST \NG PLAN CHANGE (Attach a1ditionalpagels]ss twcessary andidentify the ttem deactsprion being continued)

No modifications from previous certification. Not applic hic.

R ECERTlF lCATION (Deecnbe corrective actens tak011. attach resutts of compiered performance testmg in accor6ence with 10 CFR 9 55.45(b)(5)fv).

Attach arditionalpeoetsi es necesserv. and esenti/y the item den rioren being continued.

Not applicable.

9212210376 921217 PDR ADOCK 05000482 P PDR Any f also statement or omission in thes document,inctuding attachments, may be subject to civil and crimmal sanctions. I certify under penalty of perjury that the information in this document and attachments is true and correct.

SIGN ATURE . UTHORigip RF# .ESENTATIVE DATE l TITLE

/fffy?/hf/* Yr f t* Y f 31 w d hc Vtt vf] l l In = cordance with 10 CF R $ 56.5, Communications, tfus forrn shall ha submrtted to the NRC as fonows:

tY MAIL ADDRESSED TO: Director, Office of Nuctner Reactor Reguteten BY DELIVE RY IN PERSON One Whrte Fhnt North U.S. Nucteer Reputatory Commissbn TO THE NRCOFFICE AT: 11555 Rockvdle Pike W__ _ ., DC 20E64 Roraville, MD NRC FOJM 474 (1801

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WOLF CitEEK SIMULATOlt CEllTIFICATION OVEltVIEW NTTACIIM ENT 'A' TO NltC FOllM 474 1.0 General Simulator Informati,on 1.1 Hackground The Wolf Creek Simulator was purchased in Febmary 1980, and delivered

. November 1982. The first on-site simulator training commenced in February 1983.

Major post-TMI modi 0 cations were commenced prior to shipment and most of the modifications completed on-site in 1983. Many enhancements have taken place since the delivery date including the addition of support panels simulating the auxiliary shutdown panels and the miscellaneous Balance of Plant (BOP) panel; l/O system changes; and numerous instructor control features.

The Wolf Creek Simulator was initially certified on January 10, 1989 Since initial certification many modeling improvements have been incorporated. The original simulator computers have been upgraded by installing new processors

\ and faster memory. This upgrade allows real-time simulation and some spare capacity for future modifications, Also, the plant computer system is fully stimulated whereas it was approximately 30% simulated at the time of the initial report.

1.1.1 Simulator Information Simulator Type: Reference Plant Simulator Manufacturer: Westinghouse Electric Corgt Owner / Operator: Wolf Creek Nuclear Operating Corp.

Reference Plant: - Wolf Creek Generating Station Plant Location: Burlington, Kansas Plant Type: }y 4-Loop PWR Plant Rating: 1185 MWe -

Date Available for Training: February 1983 Type of Report: Standard Compliance 1.2 Control Room c 1.2.1 The physical arrangement of the Simulator control room is much like the actual control room. The physical layout is illustrated in attachments 1.2.la and 1.2.lb

{v of the initial certification package.

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Differences include the color and locations of the auxiliary shutdown panels, miscellaneous BOP panel (RP068), RM11 panel, and the nuclear instrumentation (NI) panel. These panels are located away from the main control panels and are simulated as being outside the control room. Other major differences include the simulator instructor booth in the proximity of the plant's radiation control and fire protection panels.

-l 1.2.2 The main control pancis are of the same dimensions as the reference plant.

Access cover handles do vary as well as the location of the Gai-tronics handset on panel RL013. The simulator panels do not have maintenance handset jacks or any method to simulate any radio units.

All switches, lights, meters, controllers, etc., match the reference plant in shape, color, size, and scaling with few minor differences. These differences have been identified and dc,cumented per Section 6.1 of KP-891, Simulator Certification.

1.2.3 All systems / equipment operated from the main control panels, auxiliary shut /down panel, Ni panel or RP068 is simulated with exception of the recorders on RP068. These recorders monitor the RCP vibration and the generator core.

Presently there are no immediate plans to incorporate these recorders due to excessive expense. Various plant procedures require local valves, switches, etc.,

to be operated from outside the control room. Many of these local items are modeled and instructor controlled.

1.2.4 The simulator control room and the referenced plant control room are very i similar. The color of carpeting may vary from time to time due to the replacement of the reference plant control room carpeting.

Building safety codes iequire that some lighting remain on at all times. These lights are simulated as the ."DC lights" for the reference plant. All other banks of.

lights are modeled to fail when their simulated power is lost. Exit lights are also installed in the ceiling for safety purposes.

The simulator ceiling is very much like the reference plant except that it does not meet any of the scismic requirements. For this reason the ceiling parabolic grids are made of plastic vice aluminum. The dimensions of the grids are the same The audio level (ventilation noise) is not modeled. Since the simulator is a-teaching / learning environment, there is no need to try to interface / monitor - ,

students over unnecessary noise. The audio of all alarms and annunciators are set as in the plant.

'1J Instructor Interface 2

l .3.1 - The Wolf Creek Simulator has 100 usable initial condition snapshots (ICs). Six-of these are used for automatic (every 5 minutes) hack up ICs, twelve for instmetor and hardware /soflware use, and the remaining 82 for pre-set instructor ICs. The instructor ICs are password protected to prevent inadvertent write-over. Snapshots are controlled by the instruction staff, 1.3.2 The Wolf Creek Simulator can support up to 200 malfunctions. At the presentL time,183 malfunctions are available for the instructor to use. All have the ability.-

for time delayed activation, most have adjustable rates; and many have selectable options. The specifics for each malfunction are described in the Instructor Malfunction Book. Section 1.5 describes all malfunction additions, deletions, and revisions since the last report.

l.3.3 Local operator actions (LOAs) provide simulation of components outside the control room. Most LOAs called for in the operating procedures are simulated if the outcome would be recognized by the control room operator. LOAs are continuously used by the instmetors and are not routinely tested beyond initial ;

installation / acceptance. Problems with LOAs or additional LOAs are addressed via a Simulator Modification Request per KP-880, Simulator Modification-Request. LOAs are listed on Enclosure 1 of the original certification package.

Changes to LOAs are listed in Section 1.5.

The auxiliary shut /down panel is the only physical panel modeled that is located outside the control room. It is a fully functional panel and interfaces directly with the simulation system.

1.3.4 Additional features include freeze, backup, sim speed, and write snap. These standard features allow instructors to stop simulation, backup to a backup IC (up to 30 minutes old), adjust simulator speed from real time, and write ICs. These features and others are described in the Simulator Instructor Book, submitted ,

with initial certification. Changes since the last report are identified in Section 1.5.

Limiters placed in key simulation programs prevent exceeding the bounds-of -

realistic simulation. Two instructors, with an active or previous license, conduct Wolf Creek Simulator training classes. Also, a Limits of Simulation System (LOSS) has been added to assist the instructor. Together, these three methods '

are used to prevent negative simulator training.

l.4 Operational Procedures 1.4.1 All procedures used on the Wolf Creek Simulator are the same as the procedures used in the operation of the reference plant. The License Training. group; p receives al1 revisions, temporary changes, and new procedures for-U implementation mto the procedure manuals.

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.1 1.4.2' All drawings used in the simulator are controlled documents updated and.

maintained by the Wolf Creek Document _ Control Group. These documents include P&lDs, logic, and electrical drawings.

1.5 Changes Since Last Report _

l 1.5.1 Malfunction Additions / Revisions- -

The following malfunctions were added and a copy of the new descriptions enclosed: .

MALF NO. TITLE AFW-2 Turbine-driven Auxiliary FW IN w Failure FWM-17 Feed Reg Valve Positioner Faihm.

PCS-10 Failure of Containment isolation Phase A RCS5 Steam Generator tube leak (0-100gpm)

RIIR-6 RHR Lcw Pressure Letdown header leak RHR-7 RHR injection line break WAT-8 Circ Water Leak upstream of condenser The following Malfunctions were revised and a revised description enclosed:

MALF NO. TITLE RFMSON FOR REVISION AFW-1 Motor driven AFWP trip Removed TD option due to AFW-2 CCW-2 CCW heat exchanger loss of Added note _to plant cooling flow . response CCW-10 CCW heat exchanger temp Expounded on low failure control failure . . description CCW-14 CCW Misc. Radwaste cooling Revised plant response header leak to RW bldg.

CCW-18 Leak in CCW Safety Loop . Revised selected leak size CND Loss of Condenser Vacuum Added note to aid instructor CRF-1 Rods fail to move Revised group option plant

- response --

CRF-4 Dropped rod Revised instructor note as to which rods will result in--

E reactor trip L CVC-7 BTRS-Temp element TE-381 Revised to include TE-382 -

or TE-382 failure element

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DGS-1 Diesel Generator failure Added options ~ to fail both 4 diesels simultaneously if 4

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-[ EPS 2 Main generator voltage regulator _ Changed magnitude of swing- l oscillation to be more realistic and also : I changed title _ _

EPS-4 Service Bus Trip Added options for SL3 and_

SL4 busses -

EPS-8 Loss of 120V AC instrument bus ~ . Changed description for cause to be an inverter failure

- added instructor note FWM-4 Feed water flow transmitter failure Made plant response section -

more descriptive FWM-5 Feed water Pump Turbine speed Added note to ramp time control failure selection .-

FWM-8 Feed line break inside Revised plant response to be containment more descriptive FWM-13 Main Feed pump loss of speed Added options to allow loss ;

signal of signals for both pumps simultaneously MSS-9 Steam Dump control failure Made plant response more

- descriptive j NIS-4 Intermediate range channel Add option to fail both :

gamma compensation failure channels PCS-6 Inadvertent containment isolation- Added notes on significant

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- Phase A'- effects for each train -

PRS-4 Pressurizer PORV Control system Modified to a control system failure. failure vice physical valve PRS-12 PORV stuck open Added selectable position (0-100%) sice full open RCS-1 Fault primary RTD Revised for RTD manifold 1 removal l RCS-2 Steam Generator tube rupture Malf title changed from leak j to rupture. RCS-5 is now a tube leak (0-100 gpm) this -

will allow multiple SG tube leaks RCS-13 Failure of selected thermocouple Removed invalid plant .

computer displays fromylant -

rtsponse description RCS-14 Failure of RCS wide range Removed description of auto pressure-high or low closure ofBB8702A & B since this interlock was removed in plant RHR-4 RHR HX bypass line leak Added more details to plant--

responses concerning Aux. -q N building sump levels - i

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) RMS-1 Radiation monitor process llow failure Added new monitor llF95 RMS-3 Process radiation monita. Added new process monitor actuation HF95 TUR-8 Turbine trip failure Added option to fail trip on SI signal and RA' trip only-all other trips function properly TUR-i l MSR Drain tank drain valve failure Plant response revised to incarporate plant computer alarms WAT-1 Make-up pump trip Added additional annunciators to plant --

response 1.5.2 Local Operator Actions (LOAs) Revisions 1.5.2.1 LOAs allow simulation oflocal operation of equipment by the Nuclear Station Operators. The following LOAs have been added since the initial report.

1OA TJTLE AFW6 AL llV 5 man iso viv MD 'B' to SG 'D' s AFW7 AL HV 6 man iso viv TD to SG 'D' AFW8 AL HV 7 rnan iso viv MD 'B' to SG 'A' AFW9 AL HV 8 man iso viv TD to SG 'A' AFW10 AL HV 9 man iso vlv MD 'A' to SG 'B' AFW11 AL HV 10 man iso viv TD to SG 'B' AFW12 AL HV 11 man iso viv MD 'A' to SG 'C' -

AFW13 AL HV 12 man iso vlv TD to SG 'C' AIR 13 KAV1264 isol valve to serv air header AIR 14 KAV1265 isol valve to inst air header AIR 15 KAV085 KA PV-11 local bypass valve CVC18 PDP speed controller air supply reset DGS11 Sequencer 'A' trouble annun reset DGS12 Sequencer 'B' trouble annun reset DGS13 Diesel auto start reset ECC15 Power to EM llV8924 and lift lead ESF amber light FWM12 (Reserved) (was FWIS jumper for all SGs)

FWM21 SG 'A' FWIS jumper (per EMG FR-HI)

FWM22 SG 'B' FWIS jumper (per EMG FR-HI)

FWM23 SG 'C' FWIS jumper (per EMG FR-Hl)

FWM24 SG 'D' FWIS jumper (per EMG FR-H1)

PCSI AMS AC master bypass logical

,, PCS2 Reset ATI ESFAS bistable counter 6

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_h PCS3 Key bypass GT RT-22 A PCS4 Key bypass GT-RT-31 PCS5 Key bypass GT RT-32 PCS6 Key bypass GT RT-33 PCS7 Key bypass GK RT-04 PCS8 Key bypass GK RT.05 PCS9 Key bypass GK nT-02 PCS10 Key bypa, s GK AT-03 PCSI1 Key bypass GG RT-27 PCS12 Key bypass GG RT-28 PCS13 Key bypass AL PT-37 PCS14 Key bypass AL PT-38 PCSIS Key bypass AL PT-39 -

RCS8 Trd;c A subcooling press input defeat switch RCS9 Train B subcooling press input defeat switch '

RCS10 RCS loop level iso viv BB L1-53 RCS1i RCS loop leveliso viv BB L1-54 SGB15 SG 'A' B/D valve radwaste control SGB16 SG 'B' B/D valve radwaste control SGB17 SG 'C' B/D valve radwaste control SGB18 SG 'D' B/D valve radwaste control TUR7 Turb vibr trip Hilli annun 119A reset j WATI1 Cire water pump manual discharge valve isolation 1.5.3 Instructor Operating System Revisions The simulator computer ungrade and the addition of the plant computer system have lead to changes in the operation of the simulator and some support equipment. The revised sections of Instructor Operating System book are ~

enclosed. liighlights of these changes are discussed belowc Section 1 - Instructor CRT and Keyboard

-Changed method of switching instructor console to simulator floor.

-Removed SPDS key - no longer required with new plant computer stimulation.

-Removed trend key - now accomplished via plant computer simulation.

-Removed team key - feature not used.

-Added LOSS key -lists limits of simulation system key parameters, limits, and acknowledges any alarms;

-Removed TREND key - recorders now set via plant computer stimulation.

O -Removed PENS key - 8 pen instmetor recorders removed -- now -

done via plant computer stimulation.

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-\ Section 10 - 8 Pen Instmetor Recorder

-Section removed - equipment removed.

Section 11 - Systems Index-

-Section removed - now performed via plant computer stimulation.

Section 15 - Computer Information Completely re-written to cover operation of upgraded simulator compuiers.

Section 17 - SPDS Operation

-Completely rewritten and retitled " Stimulated Plant Computer Operation"

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Section 20 - Miscellaneous Information

-Removed references to " TREND CRT" and " TEAM"..

1.5.4 Simulator Test Manual Revisions The Simulator Test Manual has gone through several revisions most of which have been title changes or the additions of malfunctions and monitoring points.

V.Q Copies of the latest revisions are enclosed. Revisions are highlighted below.

SCT Simulator Steady State Testing Rev. 2 - Changed titles and revised to perform separate stability test , ,

Rev. 3 - Allowed data collection via plant computer and organizational restmeturing SCT Simulator Transient Testing ,

Rev. 2 - Changed Titles -

Rev.'3 _ Corrected typographical errors on Attachment 'A' and organizational restructuring _

SCT Simulator Malfunction Testing -

ll Rev._2 - Changed titles and added new malfunctions to schedule i Rev. 3 - Added new malfunctions to schedule Rev. 4 - Added new malfunctions to schedule and organizational restructuring.

SCT Simulator Real-Time Testing L

- Revc2 - Changed titles and added monitoring points to test l

Rev. 3 - Revised stop watch start /stop times and removed alarm CRT 8

g _g e. f- -- os - 4g= , -~ , y

Rev. 4 - Changed to delete SPDS and Rh11I sections due to addition of the simulated plant computer system and organizational restmeturing 1.5.5 Training Division Procedure Revisions Several procedures governing Simulator Certification have been revised to incorporate title changes and to change several of the initial forms. Copies of these revised procedures are enclosed. The highlights of the revisions are discussed below.

KP-880 Simulator hiodification Request Rev. 3 - Changed titles and made form KTF-880.1 triplicate form KP-883 - Simulator hiodification Package Rev. 2 - Changed titles and revised forms KTF-883.1 and KTF 883.2, other forms renumbered KP-884 - Simulator Review of Plant Modification Request Rev.1 - Changed titles and revised form KTF-884.1 KP-891 - Simulator Certification Rev. 3 - Changed titles Rev. 4 - Added additional reference 2.0 Simulator Desien Datn 2.1 Simulator Data Base 2.1.1 The vendor's initial modeling of the Wolf Creek Simulator was based on the three other SNUPPS simulators and other Westinghouse 4-loop simulators.

Information used to develop these models included system descriptions, component design data and controlled drawings consisting of electrical and mechanical schematics, logic diagrams, and piping details. At the time of delivery, neither of the actual SNUPPS plants were operational. The documentation delivered with the simulator by the vendor was generic in nature, and was upgraded to be plant specific by the Wolf Creek Simulator staff.

2.1.2 The best resource of information to correctly update any simulator is the operator. This operator feedback along with use of controlled drawings and procedures initiated many changes to fine-tune the Westinghouse generic software. Applicable LERs are reviewed by the instructional staff and simulator group via the required reading program. LERs may be incorporrted into the simulator via the feedback system. This feedback system is described in procedure KP-880, Simulator Modification Request.

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2.1.3 Plant modification packages (PMRs)' are required to be reviewed by the Training - )

Division and as such by the simulator staff to evaluate plant changes. This review is discussed : in procedure KP-884,- Simulator Review - of Plant Modification Request. All PMRs affecting simulation are incorporated by a Simulator Modification Package per KP-883, Simulator Modification Package.

All modifications are identified and incorporated within the limits of ANS/ ANSI-3.5.

2.1.4 The simulator staff has access to plant technical manuals via the Training Division library or the Plant Document Control library. Copies oflogs, records, completed procedures, etc., may be requested from the Document Control vault.

This information is very useful for incorporating changes into the simulator where actual plant or design data is needed.

2.1.5 In addition to the above simulator data, the simulator staff has created system and handler data files showing the scope of simulator modeling. These files are controlled and updated by the Simulator Modification Package procedure, KP-883, Simulator Modification Package. These files are used in conjunction with the controlled plar.t drawings and procedures maintained in the simulator to aid in determining the effects of plant changes upon the scope of simulation.

2.1.5.1 The system files contain one-line P&ID type drawings that show all valves and major components modeled. The file also contains various data and legend sheets describing points on the drawings. Equipment data for pumps, heat exchangers, tanks, etc., are included in the file. These files are very useful in determining the extent of simulation of a given system and reviewing PMRs for any effects on the simulator.

2.1.5.2 The handler files include one-line electrical and logic drawings of components with similar operating characteristics. For instance, all four RCP breakers have the same interlocks, control features, etc.; therefore the soflware is " grouped" together to form a callable subroutine known as a handler. All handler files have been compared to the equivalent controlled drawing for accuracy.

3.0 Simulator Tests and Normal Operations 3.1 All normal operations listed in ANS/ ANSI-3.5 - 1985 Section 3.1.1 are performed during various Wolf Creek training programs. Any problems found are handled via SMR per KP-880, Simulator Modification Request 3.2 All simulator tests are described in the Simulator Certification Test Manual.

Changes to this manual are discussed in Section 15. Test results are discussed below.

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I 3.2.1 Steady State Tests

- 3.2.1.1 - The results.of the 100% Steady-state tests each year are acceptable and are available on request.- All problems noted in this area on the initial package where corrected in early 1989 3.2.1.2 The 80% Steady-state tests resulted in no additional SMPs. The plant data used for compariso_n was taken during the plant start-up testing ~in 1985. The current plant operating commitments do not include operating for extended periods at 80% power. Therefore, current data collected at this power level is of somewhat of a transient nature and as such results in a few minor discrepencies with simulator data, which is collected at a steady state power level.- The Simulator Fidelity Review Board (SFRB) has reviewed these discrepencies and conclurled they are appropriate for these conditions and therefore bear no negative impact upon training.

3.2.1.3 The results of the 50% Steady-state test parallel the 80% Steady-state test.

3.2.2 Transient Tests ,

No problems were found with any of the required 10 transient tests. There were several questions by the SFRB members reviewing the tests as to the feed flow and steam flow spikes at the time of the reactor trip. Plant data (100% reactor trip) shows these same spikes but of a lesser magnitude._ The SFRB members determined that this spike was due to opening of the steam dumps and has no negative training impact.

The results of the main turbine trip are different from that of the original 1988 and 1989 test. The turbine trip still does not result in an immediate reactor trip (as the test prescribes) but the reactor does trip on 10-10 steam generator level.

The 10-10 level results from a high steam- generator feed water isolation signal (FWIS) and the swell causes the levels to increase. This occurred after Simulator core data was upgraded (decay heat increased) and the feed water system was remodeled and level taps properly set. There is no actual plant data to compare with this response. The SFRB members have seen this response and concur that it has no negative training impact.

3.2.3 Malfunction Tests I _ All_ malfunctions were tested per the test cycle in SCT-3. 'All malfunctions-performed satisfactory. Changes in malfunction additions / deletions are discussed Jin Section 1.5.

/ 3.2.4 - Real-time Test 11

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The results of the_ initial package real-time tests revealed that the simulation system ran slightly slower than real-time. The SFRB determined that this did not impact any of the training programs at that time. Improvement / upgrades to the system were evaluated and the simulation computers were replaced in the fall of 1991. Presently real-time simulation is occurring with spare capacity.

4.0 Simulator Discrepancy Resolution nnd Uncrndine Procram 4.1 All discrepancy resolution and upgrades of the Wolf Creek simulator are .;

discussed in the following procedures. j Training Division Proceslu_rn f KP-880 - Simulator Modification Requests KP-883 - Simulator Modification Package KP-884 - Simulator Review of Plant Modification Request KP-891 - Simulator Certification Simulator Certification Test Manual SCT Simulator Steady State Testing SCT Simulator Transient Testing SCT Simulator Malfunction Testing SCT Simulator Real Time Testing The above procedures have been revised to incorporate title changes; methods involving usage of the plant computer system for data collection and new simulator computers, and addition or deletion of malftmetions. Copies of these procedures are enclosed.

4.2 Simulator Modification Packages greater than 1 year old (as of November -1, 1992):

SMP No. Title SMP91013 Feedwater Preheating Modification Status - Working - PMR #2946 Est. Completion - 12/31/92 To be incorporated in plant during RF6(3-93)

SMP91073 AFW to FW Malfunction Status - Working, may be incorporated with above SMP Est. Completion - 12/31/92 or 3/13/93 if remodel required.

SMP91088 Meter Banding Change Status - Hold, waiting on plant to make change.

Q. Est. Completion - 12/31/92 t2

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r k 5.0 Summnry of Wolf Creek Exceptions to ANS/ ANSI-3.5 5.1 Initially Wolf Creek took exceptions to the ANSI Standard on means to warn the i simulator operator of the " bounds of simulation" and real-time. Since the initial submittal, cornputer replacement corrected the real time problem and the Limits .

of Simulation System (LOSS) was added early this year.

The LOSS monitors key simulator variable: and provides the simulator operator visual and audible indications if any of these limits are approaching or have ,

exceeded pre-determined set points. H 5.2 No exceptions are taken to ANSI - 3.5,1985.

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V WOLF CREEK NUCLEAR OPERATING CORPORATION WCGS SIMULATOR CERTIFICATION TESTING SIMUI.ATOR STEADY STATE TESTING SCT 1 REVISION 3

[ w Supervisor Simulator Maintenance II-3-9 A Date m

A ll~ 10 9 2.

Manager Operations Training - Date

9 h

WOLF CREEK ~ """ '

"'"S '

SIMULATOR -3 1.0 Bimgg 1,1 The purpose of this test procedure O to describe the method used to test steady stat 6 conditions and simulator stability.

1.2 This test procedure also defines actions for test failures.

2.0 Seone 2.1 This test procedure supports the requirements of the parent procedure L -891 "Si nulater Certification" which references the Simulator Test Manual.

3.0 References 3.1- KP-880, " Simulator Modification Requests". .

3.2 KP-883, " Simulator Modification Packages".

3.3 KP 884, " Simulator Review of PMR's".

3.4 KP-891, " Simulator Certification".

3.5 ANSI /ANS-3.5 - 1985, " Nuclear Power Plant Simulators For Use In Operator Training",

4.0 Definitions 4.1 Empirical Data Data used when a best estimate is needed for simulator response. This data may include US AR, LER's, SOER's, OAR's, etc. or data based on engineering evaluation or operational assessments.

4.2 Factory Data Generic SNUPPS data in the simulator that is not nassarily plant specific.

4.3 Malfunction Simulated fsilure er degradation situations that are used in simulator training. ,

4.4 Malfunction Description - Cause and ef1ect situations that are used in simulator trai iing.

4.5 Plant Operational Data - Data used to verify simulator response as compared to plant operations / transients which may include:

- a. Start up test procedures.

b. Plant trip reports.-

c. Operationallogs.

d. Nuclear Plant Information System (NPIS).

I Page 1 of 5 2-7 e 4 - e,- - e-e- . m-p ; ,, a-- q -e w

WC' F CR sEK O SIMULATOR RtwSiom 4.6 Rea: Time - Simulation of dynamic performance in the same time based relationships, sequence duration's, rates, and accelerations as the dynamic performance of the referenced plant.

4.7 Reference Plant - The specific nuclear power plant from which the simulator control room configuration, systems control arrangement, and simulator design data is derived, i.e., Wolf Creek Nuclear Generatmg Station.

4.8 Simulator Fidelity Review Board (SFRB) - A panel consisting of the Manager Operations Training Supenisor Simulator Maintenance, License Supenising Instructor (Simulator), and a Plant Shift Supenisor with an active SRO License. The board will resiew timulator and plant differences for their impact on training.

43 Other terms and abbreviations used in this pwcedure tr.ay be found in the Training Division Procedure Manual Glossary.

5.0 itemonsibilitin 5.1 The Supenisor Sinvilator Maintenance has overall responsibility for the Steady State Testing program including:

a. Scheduling Steady State Testing.

b. Review of Tests.

( c. Issuing of Simulator Modification Packages (SMP's).

d. Maintaining Steady State Test Results.

5.2 The Manager Operations Training is responsible for providing instructional stalito assist with Steady State Testing.

5.3 Simulator Specialists are responsible for correcting discrepancies generated by SMP's.

5.4 The SFRB is responsible for reviewing all tests and providing resolutions for any discrepancies.

6.0 Procedure 6.1 Steady State.

6.i.1 Data used for steady state testing will be taken from actual plant indicators using Attachment A.

An alternative data collection method will allow the use of the NPIS using Atancnrnent D. The plant equipment lineup will be recorded on Attachment B.

6.1.2 The data is categorized into two types:

a. Critical - data listed in ANSI /ANS-3.5 as critical data or determined by the SFRB in w hich the simulator value and the plant value should be within 12 percent.

b. Non-Critical - data recorded that is not critical and v hich the plant value should be within 110 percent.

s

/,

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WOLF CREEK -

O SIMULATOR "'"S ' "

3 6.1.3 The Steady State tests are performed at three steady state po ver levels, preferably at the same pcw v incts as heat balance calculations are performed. Heat balances required only a few parar.reters to be stable while ethers are changing (i c., x:non, etc.). Therefore, all parameters may not match within the required tolerance These items should be noted and differences explained.

6.1.4 - Data will be used that best reflects total plant stability such as start up testing or equilibrium xenon conditions.

6.2 Test Description - Steady State.

6.2.1 The Simulator is placed at the proper initial steady state equilibrium conditions for the approximate core age at which the plant data was collected and operating equipment lined up per Attachment B.

6.2.2 The simulator data is then recorded, using the same meter (Attachment D) and/ci r Anputer point (Attachment A) that was used for Plant Data.

6.2.3 After the data collection is completed, simulator deviation shall be calculated and recorded.

6.3 Stability 6.3.1 Data points used for stability testing will be those points used for steady state testing referenced on Attachment A.

6.3.2 The stability test will be conducted at steady state full power lineup.

6.4 Test Description - Stability 6.4.1 The simulator is placed in full power, steady state, equilibrium xenon condition and run with no .

operator actions.

6.4.2 The test program is started and the initial simulator data is read into the initial data array.

6A3 The test will automatically stop after one hour of data collection, then compare the initial data calculated high and low limits for each parameter.

6.4.4 A per:ent deviation is calculated and a printed report with this information and other useful descriptions is generated (See Attachment C).

6.4.5 The data is also placed on magnetic tape and archived for a two year period.

6.5 Test Review LO Page 3 of 5

~._ _ _ . _ , _ _ _ _ - - _ _ . _ _ . . _ _ -.,_ . . .- . .. _ _ _ -

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WOLF CREEK -

U SIMULATOR ""S ' "

3 6.5.1 The tests are resiewed by the Supenisor Simulator Maintenance or his designee to ensure that the simulator generated data is within the allowable tolerance for the test that was performed:

a. Steady State Test

1. CriticalData12%

2. Non-Critical Data 110%

b. Stability Test 12%

6.5.2 All differences will be footnoted and explained or be assigned a Simulator Modification Package (SMP) number showing that a work package has been assigned to correct the discrepancy.

6.5.3 The resiewer will attach an SFRB Review Sheet to the test package and sign for the review:

a, SFRB Steady State Test Review" form SCT 1.1

b. "SFRB Stability Test Resiew" form SCT 1.2 6.5.4 The package will be routed to the SFRB members for their concurrence on footnoted items. The SFRB members will sig,n for their review of the package if they agree with the footnoted items.

6.5.5 Test discrepancies will be forwarded to the SFRB for resolution. Resolutions may include SMP's, acceptance, data correction, etc..

gm 6 5.6 Completed Steady State Tests will be maintained by the Supenisor Simulator Maintenance. ,

7.0 Attachments 7.1 Attachment A, " Data Collection Sheet".

7.2 Attachment B, " Equipment Line Up Sheets".

7.3 Attachment C, " Sample Stability Test Format".

7.4 Attachment D, "NPIS Data Collection Sheets".

8.0 f.9 Ens 8.1 SCT-1.1. "SFRB Steady State Test Resiew" 8.2 SCT-1.2, "SFRB C:. ability Test Review" 9.0 Bnoids 9.1 There are no QA records generated as a result of this procedure.

O Page 4 of 5 l

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WOLF CREEK '"

O SIMULATOR esiost 9.2 ' The Steady State Test Packages shall te maintained by the Supenisor Sirnulator Maintenance and be retained for four years.

O O Page5of5 _

STEADY STATE TEST Sim. Data Collected / /

Power % Plant Data Coll &ted / /

TAB. LOG 5IANT SIM. DEV. TYPE COMMENTS DESCRIPTION COMPUTER POINT NAME SMDAT4 C RCP Tot SealInj A Flow 13GF0215A BGF0215B SMDAT4 C RCP Tot Seallnj B Flow BBMM03 SMDAT4 C l RC Svs WR LP Ch4 Press BBNM05 SMDAT4 C RC Svs WR LP Chi Press BGF0132A SMDAT4 C Letdon !!x Ltdn Out Flow BGF0121 SMDAT4 C Chg Pmp Disch Ildr Flow BBPN55 SMDAT4 C l Pzr Chi Press BBPO456 SMDAT4 C Pzr Ch2 Press BBIN57 SMDAT4 C Pzr Ch3 Press BBPM58 SMDAT4 C Pzr Ch4 Press BBIA459 SMDAT4 C Pzr Chi Level BBLN60 SMDAT4 C Pzr Ch2 level BBLO461 SMDAT4 C Pzr Ch3 Level SEUI167

SMDATS C Power Rance Flux Diff 4i SEUI165

SMDATS C Power Rance Flux DifT42 SEUI164

SMDATS C Pourr Ranee Flux DifT43 SEUll66

l SMDATS C Power Rance Flux Diff 44

Calculated by Plant Computer.

1. Computer point not available - use instrument TYPE: C-Critical parameter 12%

N-Non-Critical parameter 110%

Page I of 8 L . -- - . . --

. _ . _ __ .__ i

(y (3 scr u =:*, =

\ s, C)

STEADY STATE TEST Sim. Data Collected / /

Power % Plant Data Collected / /

PLANT SISL DEV. TYPE COMMENTS DESCRIPTION COMPUTER POINT TAB. LOG NAME SMDAT5 C RC Lt DT BBTNO3A SNU)AT5 C RC L2 DT fiBTN23 ShH)AT5 C RC L3 DT BBTN43C SMDAT5 C RC L4 DT 13BTN63A SMDAT5 C PR Chi QIM Q SENON9A SMDAT5 C l PR Ch2 QD2 Q SEN0050A SMDAT5 C PR Ch3 QDI Q SEN0051A SMDAT5 C PR Ch4 QD3 Q SEN0052D SMDATS C RCL Ilighest T Avg (Aucticrm) BBT0499A SMDAT6 C RC LI T Avg BBTN00A SMDAT6 C RC L2 T Avg BBT0420A SMDAT6 C RC L3 T Avg BBTGS40A SMDAT6 C RC L4 T Avg BUTN60A 05/IS C ,

MN FW lleader Press AE PI-50R ##

05/167 C Main Steam IIcader Press AB PI-507 ##

SMDAT6 C Main Generator Power MAP 000i SMDAT6 C RC Svs WR LP Chi Press (Repeat) BBPO405

' Calculated by plant computer.

fComputer point not available - use instrument TYPE: C-Critical parameter 12%

N-Non-Critical parameter 110%

Page 2 of 8

j_

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N scT Anute=mi (f STEADY STATE TEST Penrr % Plant Data Collected / / Sim. Data Collected / /

DESCRIPTION COMPUTER POINT TAB. LOG PLANT SISL DEV. TYPE COMMENTS NAME RC Svs WR LP Ch4 PresMRepeat) BBPO403 SMDAT6 C RC L1 WR Cold Leg Temp BBT0413B SMDAT6 C RC L2 %7 Cold Leg Temp BBTN23B SMDAT6 C '!

RC L3 WR Cold Leg Temp BBT0433B SMDAT6 C RC L4 WR Cold leg Temp BBTM43B SMDAT6 C RC L1 WR llot Leg Temp BBT0413A SMDAT6 C RC L2 WR Ilot Leg Temp BUTN23C SMDAT6 C RC L3 Ilot Lee Temp BBTN33A SMDAT7 C RC IA flot leg Temp BBTN43 SMDAT7 C RCP A Ili Rng #1 Seal L BGF0157 SMDAT7 C RCP A Im Rng #1 Seal L BGF0161B SMDAT7 C RCP B Ili Rng #I Seal L BGF0156 SMDAT7 C RCP B Lo Rng #I Sea! L BGF0160 SMDAT7 C _

RCP C Ili Rng #1 Seal L BGF0155 SMDAT7 C ,

RCP C le Rng #1 Seal L BGF0159 SMDAT7 C RCP Dlli Rng #1 Seal L BGF0154 SMDAT7 C RCP D Lo Rng #1 Seal L BGF0158 SMDAT7 C

Calculated by Plant Computer.

f! Computer point not available - use instrument TYPE: C-Critical parameter 12%

N-Non-Critical parameter 110%

Page 3 of 8

,x ,--

s ,/

SCT-* * .

STEADY STATE TEST Sim. Data Collected / /

Power *6 Plant Data CoIIected / /

PLANT SIM. DEV. TYPE COMMENTS DESCRIPTION COMPUTER POINT TAB. LOG NAME SMDAT7 C SG A FWIn Temp AET0065 SMDAT7 C SG H FW In Temp AET0066 AET0067 SMDAT7 C _

SG C FW In Temp C

)

SG D FW In Temp AET006S SMDATE SMDAT8 C SG A NR CM Level AELO551 AELO552 SMDAT8 C SG B NR CM Level SMDATE C SG C NR CM Level AELO553 AELO554 SMDAT8 C SG D NR CM Level SMDATB C SG A FWIn Chi Flow AEFOSIO SMDAT8 C SG A FW In Ch2 Flow AEF051i SMDAT8 C SG A Stm Out Chi Flow ABF0512 SMDAT3 C SG A Stm Out Ch2 Flow Af3F0513 SMDAT8 C SG B FW in Chi Flow AEF0520 SMDAT8 C SG B FW In Ch2 Flow AEF052i SMDAT8 C SG B Stm Out Ch1 Flow A"F0522 SMDATE C SG B Stm Out Ch2 Flow ABF0523 AEF0530 SMDAT9 C SG C FW In Ch1 Flow

' Calculated by Plant Computer.

CCComputer point not available - use instrument TYPE: C-Criticalparameter12%

N-Non-Critical parameter 110*4 Page 4 of 8

s ~

N SCT4 Attachment g STEADY STATE TEST Power % Plant Data Collected / / Sim. Data Collected / /

DESCRIPTION COMPUTER POINT TAB. LOG PLANT SIM. DEV. TYPE COMMENTS NAME SG C FW In Ch2 Flow AEF0531 SMDAT9 C SG C Stm Out Chi Flow ABF0532 SMDAT9 C SG C Stm Out Ch2 Flow- ABF0533 SMDAT9 C SG D FW In Chi Flow AEF0540 SMDAT9 C SG D FW In Ch2 Flow AEF0541 SMDAT9 C SG D Stm Out Chi Flow ABF0542 SMDAT9 C SG D Stm Out Ch2 Flow ABF0543 SMDAT9 C SG A Stm Out Chi Press ABP0514 SMDAT9 C SG A Stm Out Ch2 Press ABP0515 SMDAT9 C SG A Stm Out Ch3 Press APB0516 SMDAT9 C SG B Stm Out Chi Press ABP0524 SMDAT9 C SG B Stm Out Ch2 Press ABP0525 SMDAT9 C SG B Stm Out Ch3 Press ABP0526 SMDATIO C SG C Stm Out Chl Press ABP0534 SMDAil0 C ,

SG C Stm Out Ch2 Press ABP0535 SMDATIO C SG C' Stm Out Ch3 Press ABP0536 SMDATIO C SG D Stm Out Chi Press - ABP0544 SMDATIO C

Calculated by Plant Computer.

fi# Computer point not available - use instrument TYPE: C-Criticalparameter12%

N-Non-Critical param-ter 110% -

Page 5 of 8

scr u m i -

-3 4 STEADY STATE TEST Power % Plant Data Collected / / Sim. Data CoIIccted / /

DESCRIPTION COMPUTER POINT TAB. LOG PLANT SIM. DEV. TYPE COMMENTS NAME SG D Sim Out Ch2 Press ABP0545 SMDATIO C SG D Stm Out Ch3 Press ABP0546 SMDATIO C SG A NR Chi Imel AELO517 SMDAT10 C i c

SG A NP. Ch2 level A?t0518 SMDATIO C SG A NR Ch3 lesel AELD519 SMDATIO C SG B NR Chi level AELO527 SMDATIO C SG B NR Ch2 level AEIA528 SMDATIO C SG B NR Ch3 Level AELOS29 SMDATIO C SG C NR Chi Irret AELO537 SMDATII C SG C NR Ch2 Lent AEIA538 SMDATI1 ,

C

, SG C NR Ch3 Level AELD539 - SMDAT!1 C SG D NR CM Level AELO547 SMDATII C SG D NR Ch2 Level AELG548 SMDATII C SG D NR Ch3 Level AELD549 SMDATII C Mn Steam Line larp i Temp ABT0026 M.DATI1 C Mn Stm Line Loop 2 Temp _

, AUT0028 ShmK 1I C Mn Stm Line loop 3 Temp l ABT0030 l SMDATII C i

' Calculated by Plant Comp- ter.

Comp-ter point nc; availa$ - use instrument TYPE: C-Criticalparameter 2% ,

N-Non-Critical parranc;er110% l Page 6 of 8 e a - - - - _ - - - _ _ _ _ _

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STEADY STATE TEST Power % Plant Data Collected / / Sim. Data Collected I /

DESCRIPTION COMPUTER POINT TAIL LOG PIANT STSL DEV. TYPE COMMENTS NAME MSR D 2nd Stage Steam Row ACUn?OR SMDAI3 N '

Conds Pump Disch Press ADP0025 SMDATI3 N MSR A ist Stage Steam Row ACUO701 SMDA13 N MSR A 2nd Stage Steam Row ACUO702 Sh0A13 N MSR B 1st State Steam Mow ACUO703 - SMDA13 - N MSR B 2nd Stare Steam Row ACUO704 SMDA13 N MSR C ist Stare Steam Row ACUO705 SMDA13 N MSR C 2nd Stace Steam Flow ACUO706 SMDA13 N

' Calculated by PLnt Computer.

C# Computer point not anilable - use iisu msnt TYPE: C-Criticalparameter12%

N-Non{ritical parameter 110%

l i

i Page 8 of 8

.,_ - -_ ~_ _

.au mm .

STEADY STATE TEST Power % Plant Data Collected / /

O Equipment ID ON OFF AUTO Comments CIRC %TR PMP I A UP it-CWT 1002 CIRC WTR PMP 1Il UP B-CWT 1006 CIRC %TR PMP 1C UP 114%T1010 PMP 1 A MTR UP llRG 1E WST1007 PMP 111 hf!R UP DRG TE-WST1010 PMP 1C MTR IIP BRG TE WSTl013 1.0110 PUMP MTR UP ll-WSTl016 ESW PMP A EFE0001 ESW PMP B-EFE0002 CCW PMP A EGE0021 CCW PMP B EGE0022 CCW PMP C-EGE0023 CCW PMP D-FGE0024 IITR DRN PUMP A AFE0001 111R DRN PUMP B-AFE0002 CNDS PUMP A-ADE000)

CNDS PlIMP 11-ADE0002 CNDS PUMP C.ADE0003 VACIIITM P11MPS: A B

C _ _ .

EllC PUMPS A B

FEED PUMPS: A 11 PRESSIIRIZER IIEATERS GRP A GRP B GRPC CCPA-BGE0001 i- CCP5A IlG10007 v _CCPB-BGE0002 CCP51kBG10017 l

Pageiof2 l

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STEADY STATE TEST Power % Plant Data Collected / /

Equipment ID ON OIT AUTO Comments PDP-BGE000)

CINIRAL Clil!1ER PUMP-GBIXX101 CENT Cifl, PUMP 1 A AMP-GB10002 CEVTRAL CIII!1FR PUMP-GBTXX102 CINT Citt PUMP lB AMP-GB10014 O

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STEADY STATE TEST Power % Plant Data CcIlectid /_/ Sim. Data Collected /_

PANEL PLANT SI5L D EV. TYPE COM31ENTS DESCRIPTION LNSTRUMENT ITE5ts BG FT-21 SA 0I/173 C Charge Pump to Seal Flow Charre Pump to Seal Ilow IG FT-215B 01/174 C BB PI406 02/78 C RCS Wide Rance Press BG F1-137 02/J6A C LTUN liX Outlet Flow BG FI-121 A - 02/53B C CHRG IIcader Flow BB Pf455A 02/I3A C Pressurizer Pressure 455 BB PI456 02/13B C Pressurizer Pressure 456 BB Pf457 02/13C C Pressuriier Pressure 457 BB PI458 02/13D C Pressuriier Pressure 458 BB LI459A 02/14A C Pressuriier Irvel 459 BB LI460A 02/14B C Pressurizer le el 460 BB LT 461 02/14C C l Pressunzer to en 461 SE N141C 04/16A C Power Rance Flux Difr41 SE NT42C 04/16B C Power Rance Flux IhfT42 SE N143C (M/16C C Power Range Flux Difr43 SE NT44C G1/16D C Power Range Flux DitT44 BB TT4II A Gt/1A C DT Loop I Page 1 of 7 i

' i

,x o sa., s. ,

\v v STEADY STATE TEST Power *4 Plant Data Collected / / Sint Data Collected _ /

DESCRIPTION INSTRUMENT PANEL PLANT SIAL DEV. TYPE COMMENTS ITEM #

DT lay 2 BB T142] A NI4A C DT Int 3 BB T1431A 04/5A C DT Loop 4 BG 11441 A N/6A C PWR Range 41% Pouer SE NT4iB N/17A C PWR Range 42% Pouw SE N142B N/17B C PWR Range 43% Power SE N143B Gt/I?C C PWR Range 44% Pown SE N144B Gt/17D C RCS Averare Temperature DB TR412 St/19 C

'tC LPI AVG BB T1412 G4'3D C RC LP2 AVG BB T1-422 G1/4D C RC LP3 AVG BB T1432 04/5D C RC LP4 AVG BB T7442 Gs/6D C MN FW IIcader Press AE PI-503 05/150 C Main Steam IIcader Press AB PI-507 05n67 C Main Gen Megswatt MA Ji-1 Or/12 C Wide Rage Loop I hess BB PI405 22/25A C

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- Range Loop 4 Press BB PI 403 22/25B C

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STEADY STATE TEST Power % Plant Data Collected / / Sim. Data CcI!ccred / /

DESCRIPTION LNSTR131ENT PANEL PLANT SIht DEV. TYPE CO313 TENTS ITEh18 Ixop 1 Cold Lee Temper. BB TR413 22n C Leop 2 Cold Leg Temper BB TR-423 22/3 C Loop 3 Cold Lee Temp::r BB TR433 22/14 C leop 4 Cold Lee Temper. BB TR443 22/I5 C Loop I flot Lee Temper BB TR413 22n C Ecop 2 Ilot tre Temper. BB TR423 22/8 C Imep 3 Ilot Ire Temper. BB TR413 22/14 C 1 cop 4 Ilot 1er Temper. BB TR443 22/I5 C RCP A Seal LeakofTA Inj BG FR-157 22/5 C RCP B Seal LeakotT A Inj ' BG FR-156 22/6 C RCP C Seal LeakofT A Inj BG FR-155 22/12 C RCP D SeallealofiA lnj P3 FR-154 22/13 C Feedwater Temp AE TI-37 24/14 C Steam Generator'A'Irvel AE U-551 25/148 C Steam Ger.crator TT level AE U-552 25/149 C

~

Steam Generator t'Ixvel AE U-553 25/150 C Steam Generator TJ Level AE U-554 25/151 C Page 3 of 7 U

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STEADY STATE TEST Power % Plant Data Collected / / Sim. Data Co!!ccted / /

DESCRIPTION INSTRUMENT PANEL PIANT S131. DEV. TYPE COM3 TENTS ITEM 8 Feedw3ter Flow S/G 'N AE R510A 26/5A C Feedater Flow S/G 'A' AE R$11 A 26/5B C Steam Flow S/G 'N AB FI-5I2A 26/5C C 4

Steam Flow S/G 'A' AB R513A 26/5D C Feedwater Flow S/G 'Ir AE R$20A 26/6A C Feedwater Flow S/G Tr AE RS21A 26/6B C Steam Flow S/G 1r AB RS22A 26/6C C Steam How S/G IP AB F1-523A 26/6D C Feedwater Flow S/G C ' AE R530A 2tWA C Feedwater Flow S/G C AE RS31 A 26CB C Steam Flow S/G C AB R532A 26CC C Steam Flcw S/G C AB FI-533A 26CD C Feeduter Flow S/G U AE FI-540A 26/SA C Feedwater Flow S/G V AE FI-541 A 26/SB C Steam Flow S/G U AE FI-542A 26htC C Steam Flow S/G U AE F1-543A 26/RD C Steam Generator'N Press AB PI-514A 26/9A C Steam Generator 'N Press AB PI-51SA 26/9B C Page 4 of 7

m .

STEADY STATE TEST Sim. Data Co!!ccred / /

Power % Plant Data Collected / /

PLANT SISL DEV. TYPE COM31ENTS DESCRIPTION INSTRUMENT PANEL ITEM #

AB PI-516A 26/9C C Steam Generator 'A' Press AB PI-524A 26/10A C Steam Generator W Press AB PI-525A 26/10B C Steam Generator U Press AB PI-526A 26/10C C Steam Generator W Press AB 11-534A 26/lI A C Steam Generator C Press AB P!-535A 26/ IIB C Steam Generator C Press AB P!-536A 26/I!C C Steam Generator C Press AB PI-544A 26/12A C Steam Generator U Press AB Pi-545A 26/12B C Steam Generator U Press AB PI-546A 26/12C C Steam Generator TP Press AE U-517 26/13A C Steam Generator'N evel AE U-518 26/13B C Steam Generator 'A' level AE U-519 26/l3C C Steam Generator 'A' level AE U-527 26/14A C Steam Ge wrator Uleve!

AE U-528 26/14B C Steam Generator vlevel AE U-529 26/14C C Steam Generator W level AE U-537 26/15A C Steam Generator C Level l

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scr.: A STEADY STATE TEST Sim. Data Collected / /

Power % Plant Data CoIIected / /

PLANT SISL DEV. TYPE COMMENTS DESCRIPTION INSTRUMEN PANEL ITEM #

I AE LI-538 26/15B C Steam Generator C Level i

2M15C C Steam Generator C Level AE LI-539 26/16A C Steam Generator T7 tevel AE LI-547 26/16B C Steam Generator Ty Level AE LI-548 AE LI-549 26/16C C Steam Generator 17 Irvel CMPTR C Mn Stm Line Loop i Temp ABTCO26 CMPIR C Mn Stm Line Loop 2 Temp ABT0028 CMPTR C Mn Stm Line Loop 3 Temp ABT0030 ABT0024 CAFTR C Mn Stm Line Loop 4 Ternp FC SI-33 05/125 N MFW Fwnp A Speed l

FC 51-133 05/133 N MFW rwup B Speed IPI-WS009A 14/97 N Serv Wtr Pumas Disch 1PICWO12A I4/IO3 N Cire Wtr Pwnis Disch 15/124 N XNB01 to 4.16 KV Bus NB01 NBU-I 15/127 N XNB02 to 4.16 KV Bus NB02 NB II4

. PA U-2 lu!4 N Unit Aux XRMR 13.8 KV io PAU-7 16/15 N Unit Aux XRMR 13.8 KV to Page 6 of 7

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STEADY STATE TEST Power % Ping Ere Collected / / Sim. Data Collected / /

DESCRIPTION LNSTRUMENT PANEL PLANT SDL DEV. TYPE COMMENTS ITEM 8 RCS Degrees Subcool BB T1-1390A 22/32 N RCS Decrees Subcool BB T1-1190B 22i33 N ,

MSR A 1st Stage Steam Flow AC F1-187 24n N MSR A 2nd Stage Steam Flow AC F1-IS4 24/8 N MSR B 1st Stage Steam Flow AC F1-178 24/9 N 9

MSR B 2nd Stsge Steam Flow AC F1-175 24/10 N MSR C lst Stare Steam Flow AC F144 24/115 N MSR C 2nd Stage Steam Flow AC FI-82 24/116 N MSR D 1st Stage Steam Flow AC F1-91 a 24/117 N MSR D 2nd Stage Steam Flow AC F1-87 24/118 N IIP Turbine Ist Stage Press AC PI-506 24/2 N IIP Turbme 1st Stage Press AC PI-505 24/3 N Conds Pump Disch Press AD PI-25 25/58 N Cire Water inlet Temp TLAKE MODF1 S/G Blowdown Flow WSGNBT MODEL Page 7 of 7 1

Form SCT 3.1 Rev. I WOLF CREEK SIMULATOR SFRB STEADY STATE TEST REVIEW O Power Level Date Initial Resiewer Date of Plant Data _

. =-

I have reviewed the attached Steady State Test and agree with all items noted and that there is no negative impact on any WCGS Simulator Training programs.

1) Manager-Operation. Training /

2) License Supervising Instructor Simulator /

3) I'lant Shift Supervisor /

4) Supenisor Simulator Maintenance /

Comments for discussion:

O\

V Corr.ments Resolved (if required):

SFRB Chairman /

b v

l Form SCT 1.2 Rev. O WOLF CREEK SIMULATOR n SFRB STABILITY TEST REVIEW v Power Level Date initial Reviewer Date of Plant Data I have rniewed the attached Steady State Test and agree with all items noted and that there is no ,

negative impact on any WCGS Simulator Training programs.

1) Manager Operations Training /

2) Lic. Supervising Instr. Simulator /

3) Plant Shin Supenisor /

4) Supervisor Simulator Maintenance /

Comments for discussion:

O I

Comments Resolved (if required):

SFRil Chairman /

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WOLF CREEK NUCLEAR OPERATING CORPORATION WCGS SIM ULATOR CERTIFICATION TESTING ,

SIMULATOR TRANSIENT TESTING SCT-2 REVISION 3

f. Y Sipenisor Simulator Maintenance Il-S -3 2 Date

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l.0 ht!WR 1.1 The purpose of this test procedure is to describe the actual method used to test ANS/ ANSI- 15 required transients.

1.2 This test procedure further defines actions for test failures 2.0 Sgpps 2.1 This test procedure supports the requirernents of the par nt procedure KP 891 " Simulator Certification" which re' rences the Siinulator Test Manual.

3.0 Br.franccs 3.1 KP-880, " Simulator hkxlification Requests" 3.2 KP-883, " Simulator Modification Packages" 3.3 KP 884, " Simulator Review of PMR's" C\

Q 3.4 KP 891, " Simulator Certification" 3.5 ANSI /ANS 3.5 - 1985, "Nuc! car Power Plant Simulators For Use In Operator Training" 4.0 Definitione 4.1 Best estimate Referenced plant response data based on engineering evaiuation or operational assessments.

4.2 Empirical Data Data used when a tat estimate is needed for simulator response. This data may include USAR, LER's, SOER's, OAR's, etc.

4.3 Factory Data Generic SNUPPS data in the sier alator that is not necessarily plant specific.

4.4 Malfunction Simulated failure or degradation in performance of plant equipment.

4.5 Malfunction Description - Cause and efl~ect situations that are used in simulator training.

4.6 Plant Operational Data Data used to verify simulator response as compared to plant operations / transients u hich may include:

a. Start up test procedures,

b. Plant trip reports.

c. Operationallogs.

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3 4' Real Time - Simulation of dynamic performance in the same time based relationships, sequences duration's, rates, and accelerations as the dynamic performance of the referenced plant.

4.8 Reference Plant - The specific nuclear power plant from which the simulator control room configuration, s) stem control arrangement, and simulator design data is derived, i.e., Wolf Creek Nuclear Generating Station.

4.9 Simulator Fidelity Resiew Iloard (SFRB) . A panel consisting of the hianager Operations Training Supc visor Simulator hiaintenance, Licensed Supenising Instructor . Simulator, and an act)~e SRO. The board will review simulator and plant differences for their impact on training.

4.10 Other terms and abbreviations used in this procedure may be feund in the Training Division Procedure hianuel Glossary.

50 Ersmtllibililits 5.1 The Supenisor Simulatoi hiaintenance has overall responsibility for the Transient Testing program including:

,o a. Scheduling Transient test.

b. Review of Transient tests.

c. Issuing of Simulator hiodification Packages (ShlP's).

d. hiaintaining Transient Test Results.

5.2 The hianager Operations Training is responsible for providing instrv:tional staff to asaist with Transient testing.

5.3 Simulator Specialists are responsib!c for correcting discrepancies generated by Ship's.

5.4 The SFRD is responsible for reviewing all tests and providing resolution fe,r any discrepancies.

6.0 Etattd.uts 6.1 Types of Transient Tests and Required Data 6.1.1 The following are the ANS/ ANSI 3.5 required transients:

1. hianual reactor trip.

2. Simultaneous trip of all feed water pumps,

3. Simultaneous closure of all htSIV's.

4. Simultaneous trip of all RCP's.

5. Trip of any single RCP.

6. hiain turbine trip (maximum power without reactor trip 50%).

7. hiaximum rate power ramp (100% - 75% - 100% at 5%' minute).

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8. Masimum sir.e LOCA (10,000 gpm) with loss of PA01/02.

9. Masimum sir.c unisolable main steam line rupture.

10. Slow primary system depressurization to saturated condition using PORV or safety valve stuck open.

6.1.2 Required data points are shown on Attachment A.

6.2 Test Cherviews 6.2.1 Each test will record data eve y .5 seconds over the entire 20 minute test.

6.2.2 Each test will have 60 seconds of steady state operation prios to event initialization.

6.2.3 Test data will be recorded on magnetle tape and archived for two years.

6.2.4 Each transient test will be complete prior to NRC Form 474 submission annually.

6.2.5 Transient data points will be plotted vs. time for each test.

6.2.6 Copies of transient data plots will be maintained for four years.

6.2.7 Tests will be performed without operator interface and usually initiated by malfunction unless O_ otherwise noted.

6.3 Specific Test Guidelines 6.3.1 Manual Reactor Trip initiated by inadvertent reactor trip malfunction with a 60 second time delay conditional on the test logical.

6.3.2 Simultaneous trip of all feed water pumps -initiated by feed pump trip malfunction with option set to trip both MFP's. 60-second time delay conditional on test logical.

6.3.3 Simultaneous closure of all MSIVs initiated by malfunction with *all" options and 60-second time delay conditional on test logical.

6.3.4 Simultanctus trip of all RCP's initiated manually afler 60 seconds of steady state data.

6.3.5 Trip on any single RCP usually pump 'D' selected by malfunction with 60 second time delay conditional on test logical.

6.3.6 Main turbine trip - initialized at approximately 50% steady state by malfunction with 60-second time delay conditional on test logical.

6.3.7 Maximum rate power ramp . initiated at 100% stead state by placing load dec case "ON" at -

$Wminute and decreasing MW load to approximately 881, When stable, increase MW load to approximately 1185 at SWminute. (Note place rod controlin " Auto" prior to test.)

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i 63.8 Masimum size LOCA with loss of PA01/PA02 initiated by RCS leak malfunction set at i maximum size (10,000 gpm) with 60 second time delay conditional on test logical, and loss of site power malfunction conditional on the RCS leak nulfunction. The time delays for the site power malfunction should be minimal (1 = 1 sec.,2 = 1 sec).

63.9 Masimum size unisolable main steam rupture inillated by malfunction set at maximum size (5.4 E6 Lbnvllt) on 'D' S/G. Sisty second time delay conditional on test logical.

63.10 Slow primary systern depressurization to saturated conditions using PORV or Safety Valve stuck open - initiated with charging pump nulfunction selected to lose both CCP's conditional on SI signal. PORVs auto close option,60-second tirne delay, and conditional on the test logical. The salve should be failed to the 100% value.

64 Test Plotting 64.1 As the ir ividual transient tests are run, the data points are collected on magnetic tape for archival purposes.

6.4.2 The data points are transferred to a micro computer and plotted using a plotting program. A sample plot is shown on Attachment D.

6.5 Transient Test Review 6.5 1 The test plots shall be resiewed by the Supenio Simulator Maintenance or his designee to ensure that th: plots contain the general characteristics of the transient.

6.5.2 Where asailable, actual plant data (for that particular transient) will be plotted so that the simulator data may be compared to real event data. Actual plant data may be data from similar plants or from the WCGS plant. Since actual plant data would include operator response, only the general characteristics of the parame:er should be reviewed.

6.33 The test reviewer will attach an 'SFRD Transient Test Review Sheet" (Form SCT 2.1) to the test

ickage along with any actual plant d ta plots and sign for the review.

6.5.4 The package will be routed to the SFRB for their review of the plotted parameters, numbers, and any plant data. The SFRB members will s:gn for their review of the package if they agree with the plots.

6.5.5 Test discrep.meks will be forwarded to the SFRB chainnan for resolution by the SFRD.

6.5.5.1 Resolutions may include SMP's, acceptance, data correction, etc.

6.5.6 Complete transient tests will be maintained by the Supenisor Simulator Maintenance.

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.y 7.0 Attachments

7.1 Attahment A,' Required Data Points" L2 Attachmen: D, %mple Transient Plot

I 8.0 EpJny 8.1 SCT 4.5, *SFRD Transient Test Rniew Sht#

t 9.0 Records 9.1 There are no QA records generated as a result of tids procedule.

9.2 The Transient Test Packages shall be maintained by the Supenisor Simulator Maintenance and -

be retained for four years.

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WOLF CREEK SIMULATOR ,

g REQUIRED DATA POINTS Test Number Parameler 1.2,3 5 8,9- 10 4,5,6 Power Range Power X X Intermediate Range Power X X' Source Range Power X X X Tavs X ,

Pressurizer Pressure X X Wide Range Pressurc X X ,

Pressurizer Level X X Pressurizer Temperature X X Feed Flow Loop i X 'X Feed Flow Loop 2 X X Feed Flow Loop 3 X X Feed Flow Loop 4 X X Steam Flow Loop i X X Steam Flow Loop 2 X X Steam Flow Loop 3 X X Steam Flow Loop 4 X X Steam Pressure S/O A X Steam Pressure S/O B X Steam Pressure S/O C X Steam Pressure S/O D X X S/O Level A X S/O Level B X O S/O Level C S/O Level D X X

X 1101 Leg Temp. Loop 1 X llot Leg Temp. Loop 2 X 1101 Leg Temp. Loop 3 X llot Leg Temp Loop 4 X X X Cold Leg Temp. Loop 1 X Cold Leg Temp. Loop 2 X Cold Leg Temp. Loop 3 X Cold Leg Temp. Loop 4 X X Containment Pressure X X Containment Temperature X X RCS Loop i Flow X RCS Loop 2 Flow X RCS Loop 3 Flow X-RCS Loop 4 Flow X RCS Degrees Subcooled X Relief Valve Flow X RVLIS - -X Surge Line Temperature X ATTACitMENT A l

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Form SCT . 2.1 WOLF CREEK SIMULATOR O SFRB TRANSIENT TEST REVIEW Transient initial Resiewer Date I have reviewed the attached Transient Test Plots and agree with the general characteristics of the plots and that there is no negative impact on any WCGS Simulator Training programs.

1) Manager . Operations Training /

2) Lic. Supenising lastr.. Simulator /

3) Plant Shift Supenisor /

4) Supenisor - Simulator Maintenance /

Comments for discussion:

Comments Remlved (if required):

SFRB Chairman - /

by/

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WOLF CREEK NUCLEAR OPERATING CORPORATION i

t WCGS SIMULATOR CERTIFICATION TESTING ,

i SIMULATOR MA1 JUNCTION TESTING f SCT 3 .

REVISION 4 i

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- ll .3-31 Supenisor Simulator Maintenance Date ,

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4 1.0 httpsg 1.1 The purpose of this test procedure is to descritie the actual method used to test all nulfunctions.

1.2 This test procedure further defines actions for test failures and will provide a test schedule for malfur_ctions.

2.0 Sprps 21 This test procedure suppens the requirements of the parent procedure KP-891

Simulator Certification

which references the Simulator Test Manual.

3.0 Bsicrgpsg 3.1 KP 880,

Simulator Mcdification Requests",

3.2 KP-883.

Simulator Modification Packages".

p 33 KP-884, ' Simulator Review of PMR's".

3.4 KP 891," Simulator Certification".

3.5 ANSI /ANS 3.5 1985, ' Nuclear Power Plant Simulators For Use in Operator Training

4.0 DSfmiliQM 4.1 Best Estimate . Refer nced plant response data based on engineering evaluation or operational assessments.

4.2 Empirical Data Data used when a best estimate is needed for simulator response. This dats may include USAR,.LER's, SOER's, OAR's,etc.

4.3 Factory Data Generic SNUPPs data in the simulator that is not necessarily plant specific.

4.4 Malfunction Simulated failure or degradation in performance of plant equipment.

4.5 Malftmetion Description - Cause and effcet situations that are used in simulator training.

4.6 Plant Operational Data - Data used to verify simulator response as compared to plant operations / transients which may include:

a Start up test procedures.

b. Plant trip reports.

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c. Operationallogs.

4.7 Real Time Simulation of dynamic performance in the same time based relationships, sequences duration's, rates and accelerations as the dynamic performance of the referenced plant.

48 Reference Plant The specific nuclear power plant from which the simulator control room configuration, sy stem control arrangement, and simulator design data is derived, i.e. Wolf Creek Nuclear Generating Station.

4.9 Simulator Fidelity Review Board (SFRB) A panel consisting of the hianager Operations Training, Licensed Supenising Instructor Simulator Training, Licensed Supenising Instructor (Simulator), and an active SRO. The board will review simulator and plant differences for their impact on training.

4.10 Other terms and abbreviations used in this procedure may be found in the Training Division Procedure hianual Glossary.

5.0 J1eng.nnihilifig.3 51 The Supervisor Simulator hiaintenance has overall responsibility for the hialfunction Testing program including:

'O a hialfunction test schedule.

b. Periodic review of hialfunction Descriptions.

c. Review of hialfunction Tests.

d. Issuing of Simulator hiodification Packages (Ship's).

c. hiaintaining hialfunction Test Results.

5.2 The hianager Operations Training is responsible for providing instructional staff to assist with hialfunction testing.

5.3 The I.icensed Supervising Instructor (Simulator) is responsible for maintaining the hialfunction Description Book cunent.

5.4 Simulator Specialists are responsible for correcting malfunction discrepancies generated by ShtP's.

6.0 hggt dagg 6.1 Initial Review of hialfunctions 6.1.1 All hialfunctions were initially reviewed by the SFRB to detennine ANSI /ANS 3.5 category and to ensure that the brief plant response description matched the actual plant response or best estimate.

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6.1.2 The SFRB determined that any given malfunction rnay cover more than one ANSI /ANS . 3.5 category.

6.2 Test Procedure 6.2.1 The Supenisor Simulator Maintenance will compile a malfunction test package consisting of a '

Malfunction Test Form (form SCT. 3.1) and the appropriate Malfunction Description (Attachment D).

6.2.2 The Supervisor Simulator Maintenance will complete the blocks on the malfunction test form for Malfunction Title, Malfunction Number, and ANSI 3.5 Categories then give the package to the testers.

6.2.3 The testers, one of which must be a qualified simulator instructor and holds or has held a license or certification on a PWR type plant, will evaluate the IC and malfunction options that will best test the malfunctions.

6.2.4 The testers will complete the following on the malfunction test form:

a. Date of the test.

b. IC#.

c Brief description ofIC.

d. Malfunction options (if applicable).

O. c. Malfunction size (if applicable).

6.2.5 Variable Monitored / Recorded as well as any other useful information may be recorded in the appropriate section of the forms. This information may be useful for future tests.

6.2.6 The testers will test the malfunction using the least two different options and sizes (if applicable).-

6.2.7 If the simulator response to the malfunction matches the plant response as determined by the two testers, the appropriate block is checked and the testers will sign /date the test sheet. The testers may list any plant procedures used for future reference.

6.2.8 If the simulator response is not as stated in the malfunction plant response description, the appropriate block is checked and a Simulator Modification Request (SMR) is completed per KP-880. The SMR should be attached to the package and submitted to the Supenisor Simulator Maintenance.

6.2.9 The Supenisor Simulator Maintenance shall review the Malfunction Test Form and sign /date for the review. If an SMR was submitted, it will be processed per KP-880, and an SMP will be -

issued per KP 883, and the SMP number.will be placed on the Malfunction Test Fonn. -

Notification of an unsatisfactory test shall be IAW KP 891 step 6.3.3.

6.3 Test Archiving t

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6.3.1 All Malfunction Test Forms will te retained by the Supenisor Simulator Maintenance for a a

periad of at least eight years. This will pro ide test history for the most recent test and the previous test.

6.4 Re-testing Failed Malfunctions 6.4.1 After all work has been completed by the applicable SMP, the Malfunction shall be retested as described in section 6.2 above.

6.4.2 Notification of satisfactory completion shall be IAW KP 891 step 6.3.3 6.5 Schedule 65.1 All tr.alfunctions shall be tested initially prior to NRC Form-474 mbmittal.

6.5.2 Approximately 25 percer.1 erall matfunctions shall tw tested each calendar year commencing the calendar year after NRC Form 474 submittal.

6.5.3 The Malfunction Test Schedule shown on Attachment A is a general guidelir.e to aid in testing approximately 25 percent per year and may be altered as necessary as long as all malfunctions are tested every four calendar years.

6.5,4 Any new malfunctions will be initially tested prior to unice and then pbced on the Malftaction Test Schedule to tw tested every four er'endar years thereafter.

6.5.5 A Malfunction Test may be tested early if work was performed on that malfunction. If greater than one year early, the Malfunction Test Schedule should be adjusted back to every four calendar years.

L5.6 Any malfunction test that cannot be performed within four calendar years shall be reported in writing to the NRC Regional office stating w hy it can not be perfoemed and when the test is rescheduled.

7.0 Altshg1mts 7.1 Attachment A,' Simulator Malfunction Test Schedule" 7.2 Attachment B," Sample Malfunction Description".

8.0 Forms 8.1 SCT 3.1, " Simulator Malfunction Test Cover Sheet".

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______ _ ____ _ ____________ _________________ _____ _ __________________ __________j

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SIMULATOR 4 9.0 Eggplsl.1 9.1 There are ao QA records generated as a result of this procedure.

9.2 The Malfunction Test Packa 5 shall be maintained by the Supervisor Simulator Maintenance and be retained for eight yeare (two test cycles).

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SCT 3 Attachment A WOLF CREEK SIMULATOR: :

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Malfunction Test Schedule 1 CYCLE A* CYCLEB* CYCLE C* CYCLE D*

AFW1 AFW 3 AIR 1. AFW 2 CCW1 CCW 2 CCW 3 AIR 2 CCW 5 CCW 6 CCW 7 - CCW-4 CCW-9 CCW 10 CCWll CCW 8 CCW-13 CCW 14 _CCW 16 CCW 12 -

CCW 18 CCW 19 'CCW 20 CCW 17 CND-2 CND 3 CND5 CND1-CRF1 CRF 2 CRF 3 CND 6 CRF 5 - CRF-6 CRF-7 CRF-4 _

CRF-9 CRF-10 CRF 11 CRF-8 CVC CVC-2 CVC-3 CRF 12 CVC-5 CVC-6 CVC 7 CVC-4 CVC-9 CVC-14 CVC-Il - CVC-8 CVC-13 CVC-18 CVC-15 CVC-12 CVC 17 CVL-4 CVL CVC-16 .

CVL-3 CVM-4 CVM1 CVL 2 1 CVM 3 ECC-3 DGS-1 CVM 2-ECC 2 EPS-4 EPS1 ECC EPS 3 EPS EPS 5 EPS 2 EPS 7 FWM-3 f

s FWM 2 FWM 7 EPS-9 FWM-4 EPS-6 FWM1 FWM 6 FWM!! FWM 8 FWM5 FWM 10 FWM-15 FWM-12 FWM 9 FWM 14 FWM 17 FWM 16 FWM 13 MSS 2 MSS 3 MSS-4 = MSS-1 MSS-6 MSS-7 MSS 8 MSS 5 MSS 10 MSS-Il MSS-12 MSS 9 NIS-1 NIS 2 - NIS 3 - MSS 13 NIS 5 NIS 6 NIS-7 NIS 4 7 NIS 9 NIS 10_ PCS1 NIS-8 .

PCS 3 PCS 4 ' PCS-5 PCS-2 PCS-7 PCS-8 PCS-9 PCS-6 PCS 10 PRS-3 PRS-4 PRS 1-

. 1 L

u I 1 .

~

- SCT 3 Attachment A'

-WOLF: CREEK SIMULATOR Malfunction Test Schedule CYCLE A* CYCLE B* CYCLE C* CYCLE D*

PRS-2 PRS-7 PRS-8 PRS-5 PRS!!

PRS-6 PRS 12 PRS-9 PRS 10 RCS 3 RCS-4 RCS1-RCS 2 - RCS-8 RCS-9 RCS-5 RCS 7 RCS-13 RCS 14 RCS-6.

RCS 12 RHR 3 RHR-4 Rihl RHR 2 RMS-2 RMS-3 RHR5 RMS-1 TUR 3 TUR-4 TUR1 TUR 2 TUR-7 TUR-8 TUR-5 TUR 10 TUR11 TUR 12 TUR9 WAT4 WAT-3 WAT-4 WAT-1 WA14 WAT-7 DSP1 WAT 5 WAT-8

CYCLE A - 1989,1993,1997,. 2001,2005,2009,2013,2017,2021,2025

CYCLE B - 1990,1994,1998,2002,2006,2010,2014,2018,2022,2026

-

CYCLE C_- 1991,1995,1999,2003,2007,2011,2015,2019,2023,2027

'V

CYCLE D - 1992,1996,2000,2004,2008,2012,2016,2020,2024,2028 F

n 2

e- m + x w .vn' ,1- n

WCCS SDGNKR MALFUICTION X' .

TITLE: RCS leak ID: RCS-6

, DESCRIPTION: LOCA frcra loop cold leg located between RCP and

.' Rx vessel, dcststream of cold leg RTD inlet line, sized up to a 5" break. .

DME: 12/04/86

,~ ,

SELECIABIE 3

STEPS DHVIS CONENIS 1 Select loop 1,2,3, or 4 Select leak rate 2 0-10000 gpn

/' ; 3 Seleet' ramp time 0-99999'Sec.

L} ~

~

BRIEF PIA!TT RESPOtGE: D? crease in PZR pressure and level, Rx trip /SI if leak size is greater than naximum charging capacity. LOCA indications for the RCS and Cnft.

EXYh;na S7UDD7T RESPCrEE: Students should respond to alarms IAW appropriate ALRs. If leak is within the' capacity of charging, actions should be IAW OFN-007 (RCS LEAKAGE HIGH) . If not, E-0 should be entered upon receipt of Rx trip /SI. SS should be notified, T.S. consulted for limitations, and i appropriate group contacted to investigate / repair. E-Plan entry may be discussed.

s cT - 3 n e.LJ B 1

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h @ 4

Form SCT ll I i

WOLF CIGEK SIMULATOR !

l F MALFUNCTION TEST FORM.

V .

Malfunction Title Malf #

Date of Test ANSI 3.5 Categories initial Plant Conditions / Options Selection:

l IC #

Brief Description ofIC Malfunction Option #1 Malfunction Option #2 Malfunction Size #1 Malfunction Size #2 Variables Monitored / Recorded Olst);

Malfunction Response:

O The atxwe malfunction responds as described in the Plant Response section of the attached k malfunction description for the options and sizes selected.

Ist Tester /

Date 2nd Tester /

Date -

Plant Procedure (s) Referenced:

O The above malfunction does not respond as described and problems are noted on the attached SMR form.

Review Section:.

SMP# (if correction required)

Reviewed /

Supenisor Simulator Maintenance Date O

l O

WOLF CREEK NUCLEAR OPERATING CORPORATION WCGS SIMULATOR CERTIFICATION TESTING SIMULATOR REAL TIME TESTING SCT-4 REVISION 4 0

. a u I } _S *N Supervisor Simulator Maintenance Date

, //- /O- 92 Mimager Operations Training Date O

. . . ~ ..m., - ._ . _ - . . . . . . . - - ~ m._ .. . -. .-- . . _ _ _

Y WOLF CREEK -

O SIMULATOR- RmSiost 1.0 hyppig The purpose of this lett procedure is to describe the actual method used to collect and evaluate .

simulator real time data to meet the requirements of ANSI /ANS - 3.5.

1.2 This test procedure further defines actions for tests that exceed real time.

2.0 Sppas 2.1 This test procedure supports the requirements of the parent procedure KP-891 " Simulator Cenification" which references the Simulator Test Manual.

3.0 References 3.1 KP-880, " Simulator Modification Requests".

3.2 KP-883. " Simulator Modification Packages".

3.3 KP-884, " Simulator Review of PMR's".

3.4 KP-891, " Simulator Certification".

3.5 ANSI /ANS 3.5 - 1985, " Nuclear Power Plant Simulators For Use In Operator Training",

4.0 Definitions 4.1 Best Estimate - Referenced plant response data based on engineering evaluation or operational assessments.

.o.

4.2 Empirical Data - Data used when a best estimate is need d for simulator response. This data may include US AR, LER's, SOER's, OAR's, etc..

4.3 Factory Data - Generic SNUPPS data in tLt. simulator that is not n ,cessarily plant ' specific.

4.4 Malfunction - Simulated failure or degradation in performance of plant equipment.

4.5 Malfunction Description - Cause and effect situations that are used in simulator training.

l 4.6 Plant Operational Data - Data used to verify simulator response as compared to plant -

operations / transients uhich may include:

a. Start up test procedures.

b. Plant trip reports. '

l. c. Operationallogs.

Page 1 of 4

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NUMBER: I WOLF CREEK - "

O SIMULATOR - "'"S '

4 4.7 Real Time Simulation of dynamic performance in the same time based relationships, sequences duration's, rates, and accelerations as the dpamic performance of the referenced plant.

4.8 Reference Plant - The specific nuclear power plant from which the simulator control room ,

configuration, system control arrangement, and simulator design data is derived, i.e., Wolf Creek Nuclear Generating Station.

4.9 Simulator Fidelity Resiew Boa ti (SFRB) A panel consisting of the Manager Operations Training, Supenisor Simulatoi Maintenance, License Supenising Instructor (Simulator), and an active SRO. The board will resiew simulator and plant differences for their impact on training.

i 4.10 Other items and abbreviations used in this procedure may be found in the Training Disision Procedure Manua' Glossary.

5.0 Responsibililjg 5.1 The Supervisor Simulator Maintenance has overall responsibility for Real Time Testing including:

a. Scheduling Real Time tests.

b. Review of Real Time tests.

c. Issuing of Simulator Modification Packages (SMP's).

. d. Maintaining Real Time test results.

5.2 The Manager Operations Training is responsible for providing instructional stafito assist with Real Time testing.

5.3 Simulator Specialists are responsible for correcting discrepancies generated by SMPs.

5.4 The SFRB it responsible for reviewing all tests and providing resolution for any discrepancies.

6.0 Procedure i~ 6.1 Test Requirements 6.1.1 Real Time testing will be performed prior to initial cenification and on each new training system when it is placed in senice.

6.1.2 Partial or complete Real Time testing may be completed at any time as directed by the Supersisor

, Simulator Maintenance. Changes in computer equipment or operating system may prompt i

partial or complete testing.

6.2 Test Oveniew 6.2.1 Times will be recorded for various simulator support equipment line-ups at Steady State and Transient conditions.

Par:2 of 4 l

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NUMBER:

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WOLF CREEK O SIMULATOR RowSiost

a. Steady State Condition

1. Simulator Only - No monitoring points.

2. _ Simulator with all support equipment Simulator with 24 monitor points, RMll and NPISSIM.

b. Transient Conditions

1. Initial conditions set up the same as in Steady State Conditions steps one and two.

6.2.2 The simulator will be ran 300 " Simulator" seconds and compared to a stop watch. The stop watch reading will be recorded in seconds.

6.2.3 The tester will perform each test three times and calculate and record the average value of the three.

6.2.4 The average values will be used for all evaluations concerning simulator real time.

6.2.5 All times will be recorded on form SCT-4.1.

6.3 Performing Tests 6.3.1 The tester shral initialize the simulator at 100%. Steady-state conditions with the appropriate simulator support equipment on.

6.3.2 The tester shall type in "RUN 305" at the instructor's console.

6.3.3 The tester shall press the run button on the instructor's console and start the stap watch at plus

' five seconds.

6.3.4 For transient condition testing, the tester shauld initiate a manual safety injection at approximately 20 seconds into the 305 second run period.

6.3.5 When the "FRZ" command appears on the console, the tester shall stop the stop watch.

6.3.6 The tester shall record the time (in seconds) from the stop watch on form SCT-4.1.

6.3.7 The tester shall repeat steps 6.3.1 through 6.3.6 until three sets of data for each simulator support equipment line up.

6.3.8 Once all tests have been complated, the tester will average the times and record the averages on -

form SCT-4.1.

6.3.9 The tester will sign and date the test form and forward the completed form to the Supervisor Simulator Maintenance.

6.4 Test Resiew-6.4.1 The Supenisor Simulator Maintenance will review the form for completeness and evaluate the results. '

Page 3 of 4

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WOLF CREEK '~

O SIMULATOR nmSiom 6.4.2 If the average values for all of the tests are less than or equal to 300 seconds, the Supenisor Simulator Maintenance will check the " meets Real Time requirements" block, sign /date the form, -

and then file the form appropriately.

6.4.3 If the average values for any of the tests are greater than 300 seconds, the Supenisor Simulator Maintenance will check the " Requires SFRB resiew/ resolution" block, sign /date the form, and continue on the system unless the Supenisor Simulator Maintenance determines that the differences will greatly impact any training programs.

6.4.4 At the next SFRB meeting the tests will be discussed by the SFRB members to determine if the system should be:

a. Reworked to try to reduce the times in which case the old system should be restarted.

b. Continue to use the system but investigate reasons for difTerences.

c. Use the system as is - no impact on training.

d. Other resolutions (such as hardware / software upgrades) 6.4.5 The SFRB resolution will be noted on the back of the form by the SFRB chairman and the form returned to the Supenisor Simulator Maintenance for filing.

7.0 Attachments 7.1 Attachment A, "Simtest".

8.0 Fonns 8.1 SCT - 4.1, "Real Time Test Collection Sheet".

9.0 Records 9.1 There are no QA records generated as a result of this procedure.

9.2 The Real Time Test Packages shall be maintained by the Supenisor Simulator Maintenance and be retained for four years.

4 Page 4 of 4 4 --

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Attachment A. SCT-4 WOLF CREEK SIMULATOR n SIMTEST FILE V

FILE NAhE = SlhfTEST

SIMCERT TEST FILE REAL TlhE TEST SW NMPTS4 MONV TPCSAV,TRCSHL,BSGNWL PSGNS.PPRSVS.BPRSVS.TPCSAUCT XFILE U

Attachment A fs

'V

, .- . = . -

Form SCT-4.1 -

WOLF CREEK SIMULATOR

. ,o REAL TIME TEST

():

Note: File SIMTEST prior to Simulator with all support.-

DATE I

Steady State Conditions (100% Steady State) !

Time 1 (sx) Time 2 (sec) Time 3 (sec) Average Simulator Only Simulator with all support equipment Transient Conditions (Manual SI from 100% Steady State)

Time 1 (sec) Time 2 (sec) Time 3 (sec) Average

~O V- Simulator Only Simulator with all support equipment Tester Date O Meets Real Time requirements O Requires SFRB review / resolution Reviewed Supervisor Simulator Maintenance Date

e

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06/11/92 NCES 'IRAllmG SIMEA'KR MAIMRCf1CN DESCRTPf1CN AUXILIARY PEEE%fATER SYSTEM (AEW) f,' rNr Title AEW-1 Auxiliary F.W. pa:q) trip AEW-2 Turbine-driven Auxiliary Feedwater Ptap Failure AIW-3 Aux. feedwater valve failure

/~N O

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n MES SIMOLA'ICR MALFUETICN TrIIEs. Turbin(Hiriven Auxiliary Feedwater Pump Failure: ID: . ATW 2 ;

4-DESCRIPTION: Turbine-driven Auxiliary Feedwater Punp fails to start or, if '

running, trips. Start failure 11s due to AFAS-T. master relay . l failure to open AB IN-5, AB IW-6 and FC IW-312. Pump trip is due to pump failure (e.g. seize:1 punp bearings). .

ENABLDG CRTICEIVE: Rocognize failure and use svc.siures to respond to AEW pump trip.

DA'IE 06/22/92 SIEPS OPTIONS C WMENIS Select failure node 1,2 1 - Pump fails to autcznatically start but may be started -

1 fran NCB 2 - Pump trips and cannot be

' started 2 lbne 3 lbne M

O BRIEP PIAMP RESPCNSE: (Based on plant being in a condition that requires,- or will require, AEW flow to the SGs to naintain a heat sink for the RCS, i.e. SI, Rx trip on SG Io-Io level, etc.)

Auxiliary feeteater flow capability will be reduced or lost to all four SGs. .

EKPICIED SITENP RESEGEE: Students should respond to alarms IAW ayg v g iate ALRs. Pump nalfunction should be recognized. 'Ihe appropriate plant groups should be contacted to investigate / repair. T. S. should be consulted for

- limitations. If SI/Rx trip has occurred, Ref. A/B should be entered.

<- l l

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.( 11/26/90 WCIE 1RAINDG SDe[JtTOR MAIJUcrIG8 TE!ULIP!]Gl FEEDRATER SYSTEM f.M Ruter 21 tin F%1 Main feedwater pep trip FW2 Steam generator level channel failure FHM-3 Steam generator feedwater ocntrol valve failure M -4 Feedwater flow transmitter failure FNM-5 Feedwater.pmp speed: control. failure FHM Heater drain pe p trip

-FNM-7 H.P. feedwater heater bypass valve failure 3 M -8 Feedwater line break inside containment-FHM-9 Feedwater line break outside contalment FHM10 Feedwater punp speed control oscillates FHM11 Feedwater heater-tube break FHM12 Failure of a FWIV to close FNM13 Main feed punp loss of speed signal PWG4 Motor driven feed pung trip INM15 Unstable steam generator level controller.

FHM16 Feed header pressure transmitter failure INM17 PR7 Valve Positicmar Failure g

NEE SDRA'KR MAIMMTICN O TrlLE: FRV Valve Positioner Fallure ID D N-17 DESCIUPrICH: Selected feedwater control valve fails to select positicn due to a disconnected feedback arm on the valve positioner.

INABLDG CHIKTIVE: WDG control board indications, RMTYWIZE failure and PmFCIM actions to attanpt to regain control of SG feed flw.

DME: 12/11/90-Smes CerIous (neems 510 FRV 510

, 1 Select FRV 520 FRV 520 530 FRV 530 540 FRV 540 2 Select Failed Position 0-100%

3 Select ramp time 0-99999 Sec BRIEP PIMP RESENGE: (Based on plant being at full power)

FULL OPEN FAIwRE - Feed flw to affected SG increases, causing its level to -

increase to the Hi-Hi turbine trip setpoint. Controller shws svg controller output, but level continues to increase.- Turbine /Rx trip _ ,

should occur and P-14 causes NIS. (Assumes no operator action)

FULL CLOSED FAIw RE - Feed fl w to the affected SG decreases to zero, causing its level to increase to the Io-Lo level Rx trip setpoint. Controller <

shows proper output, but level continues to decrease.. (Operator action will have no effect)

EKPICITD S1IDNP RESKNIE: Students should respond to ala = IAW app ur iate ALRs and attempt to regain control of feed fl w. 'lhe FRV controller is working properly in autanatic. (i.e. if the positioner is failing valve open, the cuhuller will have decreasing output), but students may attempt manual control anyway. Eventually, the students should enter.REF. A/S Upon Rx trip.

SS should be infonned and the appvglate group contacted to investigate / repair.

O i d l

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t

NWS SIMEA'ITR MMEtDCPION V

TrliE Failum of Containnent Isolation Phase A ID: PCS-10 DESCRIFf1CM Failure of phase A on selected train caused by a loose or broken wim.

FJmBLDG ORTECTIVE: Recognize and use svwdares to respord to failum of CISA.

oms: 08/22/90-SIEPS CFfl0NS COWGMPS Auto Only Auto & Manual 1 Select failum node. 1-6 Tr A 1 4-Tr B 2 5 BCTIM 3 6 2 None 3 None O

IRIEP PU WF RPR O EE:

AULD (ET:

Upon an automatic Phase A actuation, selected train (s)_will not operate equip-nunt. For selocted train (s), no autmatic CRVIS or CPIS will occur. Manual Phase A actuation will still work properly and actuate all equiptent as well as achv** CRVIG m.1 CPIS.

AUID NO MAN [RL:

Upon a Phase A actuation, either manual or autmatic, selected Trains will not operate equiprent. For selected train (s)_no automatic CRVIS or CPIS'will occur.

EKPFfMD S'IUMNT RESEOGE: Use Appendix A to E-0 to Manually align equipnent-as requirad. Manually initiate CRVIS and CPIS on affected Train (s). If option- -

is for "AUIO CELY," nanual Phase A actuation .90uld'be used to actuate iso-'

lation.

d

8/04/92 WIS 'mAINDG SIMUIA101 MAI2UCPIO{ DWCIUPfIO{

RFJCIOR C00fMP SYSTEM (RCS)

Lkunber Ti.tle RCS-1 Faulty primu y RID RCS-2 Steam generator tube rupture RCS-3 RCP trip RCS-4 RCP locked rotor RCS-5 Steam generator tube leak RCS-6 RCS leak RCS-7 Variable RCS boron concentration RCS-8 RCS loop flow transmi.tter failure RCS-9 Reactor vessel flange leak Reserved Reserved RCS12 RID wide range cold and hot leg failure RCS13 Failure of selected thernocouple RCS14 Failure of RCS NR press transmitter Reserved 1

(pv

)

NOGS SIMLRMUt MAIFLNCTICN TnIE: Steam generator tube leak 10: RCS-5 MSCRIPTICE: Primary to secondary tube leak.

DWL1}G CIMICPIVE: Recognize symptoms ard use procoAuns to respond to M tubo failure.

CNIE: 9/22/92 STEPS GTIOE COtthf5 1 Select SG A, B, C, or D 2 Select leak rate 0-100 GPM Rate based on RCS at 2235 peig 3 Select ranp tlne 0-99999 Sec.

IRIIT FIANr RESIOGE: Det. Ming on the selectal leak rate value, the following response nay occur with differing rapidity:

RCS pressure decrease, PZR level decrease, SG activity increase, and possible

,m Rx trip /SI; radiation alarms occur on the bloadown nanitor, the condenser air

/ \ discharge nonitor, and the sanple nonitor. Possible steam flow / feed flow

(,) deviation, ard a level increase in the affected SG.

} OPE: Estinated flowrate thru a double-ended shear of one tube at NOGS is ~432 gpn at IOP.

EKPirfED SIUXNf RESIONSE: Response will vary depending on the size of the leak. REF. 7 should be initiated. Camence an Cypoditious Plant Shutdown.

If large enough, SI/Rx trip should be initi4 ct=d, and REF. A/B should be en-tered. REF. H should follow. SS should be notified. Students should 'denon-strate concern for limiting possible release to environment. As familiarity with procedures increases, students should denenstrate ability to isolate affected SG in less and less time.

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8/05/92

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am mutaato mMuuuat MMIMYRE DES GFIEN JMSJDUAL HCAT RDWAL (MR)

Number Title mm-1 M R pwp trip mm-2 mm hmt exchanger flcw cmtrol valve failum M R-3 mm het exchanger bypass valve control failure mm-4 mm hmt exchanger bypass line leak MR-5 INST level channels failure MR-6 mm low pressure letdown heder leak FHR-7 MR injection line break gm, s 4

\.s/

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i

WWS SDERATTR MAIMCTIQt

- ITHE: MR Iow Pressure Intdown Header Imak ID: MR-6 DESCRIPTICM: Selectable size leak in RHR to CVCS letdown }wriar.

DRBGDU O1HCPIVE: Recognize symptcms and parfoIm action to control loss of coolant and restore RCS inventory.

DATE: B/5/92 '

S*H:PS G'rIOE CINGW5S 1

2 Select leak rate 0-3500 gpn Isak rate based on RCS aligned to RHR/CVCS letdown at normal operating pressures.

3 Select ranp tima 0-99999 sec.

IRIEP PIANP RESPOEE: (Based on fault occurring while plant is on MR) tore he rate of plant parameter changes is dependent upon the leak rate selected.

We following plant paramters are generally listed in order of significance:

EIANP PARA?ETER RESPONSE REEATED ANNUNCIA3GS PZR level decreases 032C PZR ID LEV DEV 032B PZR 17% HIRS CFF L'IDN ISO VCr level decreases 042B VCT LEV HILO Auxiliary Bldg. sump level increases 094F MISC SIMP LEVEL HI RCS pressure decreases 071A RCP #1 SEAL dP ID CVCS letdown flow decreases Total MR flow decreases

%e RHR leak may be 1solated by locally closing MR to CVCS letdown valves -

EJV001 and EJV002. (Simulator variables REJV001 and REJV002).

EXPICITD STUDDTP RESPOEE: Students should respond to alanns IAW agu.cydate ALRs. he appu.vgiate plant groups should'be contacted to investigate / repair the system. T.S. should be consulted for limitaticns.-

NCIE SIMIRATUI MMRRCTIOi

<O iTIIR: RHR Injection Line Break ID: RER-7 DESCRIITIOM: Selectable size leak in selectable MR injection line.

DRBGDG ORIDCTIVE: Recognize synptar.3 and perfom action to ocntrol loss of ecolant and restore RCS inventory.

DME: 8/5/92 SIEPS OFfl06 CORENIS 1 Select leak location A,B,C A 'A' RIR injection line up-stream of valve FJ HV-8809A B 'B' RHR injection line up-stream of valve FJ HV-8809B C - M R cross-tie line between valves FJ HV-8716A and B.

2 Select leak rate 0-4000 gpn Isak rate based on RCS aligned to MR at norml operating pressures.

r) 3 Select ramp tim 0-99999 sec.

IRIEF PIR?P RESMDEE: (based on fault CmMg While plant 18 on MR)

IDrE: We rate of plant paramter changes is degndent upon the leak rate selected. We following plant parameters are generally listed in order of significance:

PIRTT PARAMETER RESPONSE RELATED ANNUtCIA'IORS PZR level decreases 032C PZR IO LEV DEV 032B PZR 17% IfIRS OFF IIIDN ISO VCr level decreases 042B VCr LEV HIID Auxiliary Bldg. sump level increases 094F MISC SUMP LEVEL HI RCS pressure decreases 071A RCP #1 SFAL dP ID Total RHR flow increases (Option A/B)

Total RHR floa decreases (Option C)

Option A/B - Ieak may be isolated by closing EJ HCV-606/607, FJ ICV-618/619, FJ HV-8716 A/B and FJ HV-8809 A/B.

Option C -- Isak Iray be isolated by closing RHR cross-tie isolation valves FJ HV-8716A and FJ HV-8716B.

, (O k

EKPirTED STUDDTT RESPOtGE: Students should respond to alarms IAW ayg og iate ALRs. % e appropriate plant groups should be contacted to investigate / repair l

the systen. T.S. should be consulted for limitations.

i

09/30/92

,c 3 I

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tj WCCS '111AINIM; SIMEA'IUt MAIEtNCTICN DESOLIITICM COOLI!C WATFR SYS'ITRS (WAT) thimber Title WAT-1 Make-up m ter pump trip WAT-2 Service water pump trip WAT-3 Loss of ESW punp WAT-4 Ioss of service water to various cmponents NAT-5 loss of ESW to various camponents WAT-6 Circulating water punp trip WAT-7 ES9 leak inside containment WAT-8 Circulating water pipe leak

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,A Nms SIMIA' Int MAtlucrION V)

Trtiz: Circulating Water Pipe Imk ID: WAT-8 DCSCRIPTICN: Circulating Water Pip 3 Break Upstream of Condenser INAELDG GUICTIVE: Recognize failure and use procedures to respmd to loss of circulating water.-

[WIE: 09/30/92 SIEPS GTIO6 0090RIS 1 - Irak into Cordenser Pit 1 Select leak location 1, 2 2 = Inak between CWSH and plant 2 Select leak size 0 - 2.5ES gpn Ibrmal CW ficw = SES gpn 3 lbne EYlIEF FUMP RESmNSE: Generator Imd Decreases, C9 Pemissives clear Standby Condenser Air Renoval Pump (s) will start. Icw condenser vacuum alarms will actuate. If leak is into Condenser Pit, Condenser Pit Sump level Hi and Condenser Pit level Hi alarms will actuate. All but one Circulating Water

! Pump will trip when Condenser Pit Invel Hi alarm omes in.

l l

l l tuu.am S11 DENT RESPOSE: Students should respond to alams IAW appropriate l AIRS . 'Ihe appropriate plant groups should be contacted to investigate / repair' the control systen. T.S. should be consulted for limitations. If SI/Rx trip occurs, Ref. A/B should be entered.

(m)

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l

NOGS SIMmA'101 MMEUCTIm O)

(~ TITLE: Motor-driven Auxiliary Feedwater Pump Trip ID: AW-1 l- DI:SCRIITims Selected pump fails to start or trips, if running. 1G01/1802 breaker supplying pcuer trips due to a lock-out condition (e.g. overcurrent relay energized).

DalLUG GUIC1'1VE: Recognize failure and use s v;elures to respond to MV pump (s) trip.

DMEs 06/11/92 STEPS crrIOE CI:HMDUS Select pump A, B, or BCTIH A 'A' MD AIM Pump 1 B 'B' 10 AN Pump IDIH - Doth MD AW Pumps 2 lbne 3 None BRIEF PIRTP RESPOEE: (Based on plant being in a condition that Itquires, or will require, AW flw to the SGs to maintain a heat sink for the RCS, i.e.

. SI, Rx trip on SG Lo-Lo level, etc.)

A - Auxiliary feedwater flow capability will be Induced or lost to SGs B and C.

B - Auxiliary feedwater flow capability will be reduced or lost to SGs A and D.

IDIH - Auxiliary feodwater flow capability will be reduced or lost to all four SGs.

/

run;nu snDDir RESPOSE: Students should respond to alants IAW apre giate ALRs. Pump Italfunctions should be recognized. The appropriate plant groups should be contacted to investigate / repair. T. S. should be consulted for limitations. If SI/Rx trip has occurred, Ref. A/B should be entered.

A V

NOGS SINKA'IIR MMEufCFICM TIT 2: OCW heat exchanger loss of ocoling flow ID: -OCW-2 DESQUFf1CN Selected CCR heat exchanger's ESW inlet or outlet isolation valve closes due to an electrical malfuncticn.

> DDELDG OEUBCTIVE: Recognize loss of CCR E cooling flow.

Perfom actions to mstore cooling flow.

IRTE: 06/21/89 S'5PS OPPIONS (D MENIS Select faulty heat 1 = E A inlet (IN-51) 1 exchanger and valve 1,2,3, or 4 2 = E A outlet (IN-59) failure 3 = E B inlet (IN-52) 4 = E B outlet (IN-60) 2 None 3 None IRIEP PIRif RESPOEE:

OPPICN 1 & 3 - When the selected inlet valve closes, ESW flow thru the O E drops to zero. LCW E outlet taiperature increases causing various tsoperature alams on the cmponents cooled by that train of CCW.

2 & 4 - When the selected outlet valve closes, ESW flow thru the E drops fran ~12,500 9Fn to ~7,350 gpn. Tanperature out of the affected CCW E starts increasing slowly, causing tauperatures of all cmponents cooled by that i

train of CCW to increase also.

IUTE: 'Ihe CCW loop with SFP Hx and pump will actually maintain CCW System cool due to the fact that the SFP is a heat sink. .If you want alams/ indications use the other train.

EEPECED S10DEfff RESPCNSE:' Students should respond to various alams IAW aa w s;iate AIRS. Should also dananstrate ability to diagnose underlying causes of alams and initiate necessary actions to locate and correct cause of high teuperatures. Students may refer to REF. 4, and should notify.SS.

l LO i-

NTS SIMERIm MAIEUN: TION i

(VD TIYiE CCW heat exchanger tmperature control failure ID: CCN10-DESCRIFFION: Selected OCW heat exchanger outlet t m perature controller fails to selected value.

INAILI!G C111InfIVE: Recognize failure and act IAW procedures to restore CCW HX outlet t m perature control.

ImTE: 06/21/89 snTS OFf1CNS CO EENTS A = TIC 29 1 Select CCW hm t A or B exchanger B = TIC 30 I s t mp. - HX Byp. opens 2 Select fail value 50 to 150cy High tmp. HK Byp. closes 3 Select ramp time 0-99999 Sec.

mIEP PIAh"f RESPONSE

p. Righ Failure 'Ihe cooling water bypass around the CCW heat exchanger will

() close, causing the CCW outlet tmperature to decrease to its minimum value, thus causing the temperature to decrease on those cmponents supplied by _

affected train of TW cooling.

Im Failure 'Ihis condition has little noticable effect during normal power operations. During conditions of high heat load on the CCW system (i.e.

shutdown conditions with RHR inservice on the affect train). Im failure causes the ccoling water bypass valve around the affected trains heat exchanger to open. CCW heat exchanger outlet tmp will increase and may be accmpanied by high tmperature alarms frm affected cmponents (this depends on the CCW heat load).

NOIE: Due to large changes in systs flow due to bypass valve stroking, ANN 74A may alarm. 'Ihis is expected and is consistant with reference plant behavior. 'Ihis is not a fast responding malfunction.

tau'n;nD SITENP RESIOEE: Students should respond to alarms IAW apewgriate AIRS. May send A.B. watch to investigate. SS should be notified and appropriate group contacted to investigate / repair.

G 1

1<ES SIMrRA'IGt MAI2DCIIQI f,, fi

'v' TrIIR: CCN misc. radwaste cooling header leak to RW bldg. ID: CCW14 DESCRIITIQi Imk in piping downstream of DQW70A DWLDG QUECTIVE: Recognize failure and use pwculares to locate and isolate CCW leak to Rad. Waste header.

DA'IE: 12/11/90 SIEPS CPrICNS OFM2HS 1 Select leak size 0 - 100% 100% ~ 2000 gpn 2 Select ramp tine 0-99999 Sec.

3 lbne HJIT PIRE RESPQGE: Radwaste header should isolate on high flow, stopping the leak. Various Radwaste alanus should actuate.

t i U

Ewnmi S'1TDDR RESPCrEE: Students should respond to alanns IAW anu.O p iate ALRs. REF. 4 should be used. SS should be notified and students denenstrate conceIn for loss of water processing cap hi1it.,f when leak location is dis-covered. Appropriate groups should be contacted for repairs.

(~'\

U

_ _ - _______ _________ _ _ _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___~

MIE SIMINIm MAIMMTICM l O TI'liEt lemk in OCW safety loop ID: C0110 INSCILIFI'IGi: Leak in soloctcd safety loop piping in A,D.

DWLIfG QUICI'1VE: Rocognize faili.ru and uso gOcujures to locato, isolato, and respond to leak in CCW safety icop.

tw1E: 10/26/89 RIEPS GTIOC GMGNIS 1 Select train A,B

'IRAD4 A 200 GH 2 Select Icek sizo 0 - 100% 100% ~

'IFAIN B: 270 Gni 3 Select ranp tinn 0-99999 Soc.

O litDT FIRif IUSIDEE: Surge tank level decreases, causing auto unkeup, low lovel alanm, and radesto header isolation if loak is on train supplying service loop. RIIR sump level for selectcd train should increaso.

EKIYUITD SIUXWP RESIDEE: Students should respond IAW agweinte AIRS.

RSF. 4 rey be used. When leak location is discovered, students should be amre of restrictions placed on plant due to 'Ibch Specs, regarding operable ECCS subsystems. SS should be notified, Systtxn Ops advised of plant status, ard appropriate group (s) contacted for assistanco in repair.

O

_- _ _ _ _. ____....._-__._____.__...__.___m _.. _ .. m . - _ _ _ _

r 4

WEIE SIMEAlut MMFiscr131 i i

TI'ITE: Irass of condenser vacuum ID: 00-1 UtGCRIPHON: large anount of air inloakage due to faulty vacuum breaker.

I ledMLI)G GUICf1VE: Rocognizo failuto and use procodures to respond to loss of condensar vacuum. l DME: 09/22/92 '

ams wncus atmenetts 1 Select fall position 0 - 100%

f 2 Select ramp tinn 0-99999 Soc.

3 tbne 1RIEF MAlff RIGIOEE Plant will respond to increased air inleakage by start-ing standby vacutun punp and actuating low vacuum alanns. Turbine should trip ,

on low vacuum, and steam dumps should be blocked. '!

MnE: At 100% pomr and 100% fall position, nnin turbine will trip in ;

~10 minutes.

MnE: If trip is desired sooner or studant actions delay Trip and want ,

a trip anyway, use ccmrand "SETP SMICND1 = 1.1" or higher to :

facilitate Trip. ,

EKPICIED S'IUuteff RESIDEE: Students should respond IAW appropriate AIRS.

SS should be notified and'Systan Ops advised that unit may have to cane off line. Students should send T.B. watch to investigate ard contact appropriate .

group for support. If SI/Rx trip occurs, REF.'A/B should be entered.

1 e4 a

. . - , . - < . . , - . , - . . . . , , , , , , , - - , , , , , , . . . . , , - . . . , - , ~ . , . . . , , . . - , .

i r

Mal SIML4A'ItR MMEIRCrION ;

O TrnE Rods fall to novo ID: CRF-1 DH9CRUTION: Selected type ct failum prevents various tanks or ,,Ioups of rods fran noving. j i

IMMLIPC QUICf1VE: Recognize malfunction and use iu.u.udures to respond to the failure of rods i to nave. l IRTE: 05/10/91 S'IEPS GTIG6 OMENfS r A = Auto only !

H = Affects all rods in auto &

1 Select type of failure A,H, or G manual except S/D bank ,

C, D, and E G = Group -

SA 1 CA 1 SB 1 S = Shutdown bank -'

Select group SA 2 CA 2 SB 2 2 (Use only when input of SD 1 CB 1 SC 1 C = Control bank "G" used in step 1) SE 1 CB 2 CD 1 CD 2 CC 1 CC 2 Enter NA if rot using Group O 3 None if M F PIWif RESPOER: (Based on fault occurring to the controlling bank during power reduction with no operator action.)

Autn & Man - h1 hen the ocntrol rods do not nove following the start of the load reduction, Tavg will increase, causing Tavg-Tref deviation and high Tavg ,

alarms. Se inemased Tavg will help decrease nuclear pur, but tfill cum PZR Jml .end pmerurc aid hu pmssure to increase. Charging flow, steam floa and feed flow should all increase. We variable heaters should turn off and later the backup heaters will turn on due to a 5% PZR level deviation.-

As PZR pressure increases, PZR spray valves should cycle to control pmssure.

An OIttr runteck nay occur, .along with a rod stop. Olttr Rx trip nay occur.

Grue - As turbine load decmases, only one group of the controlling bank will insert. Rod deviation, rod insertion limit, and flux tilt alarms may occur.

No rod control failure alanns occur due to the specific natum of this mal-function (i.e. isolation anplifier failure).

l l

EKPICITD S'mDDff REFONSE Students should respond to the rod a ntrol failure '

IAW REF. 12. SS should be notified and the app upciate group contacted to.

investigate / repair. Students should consult T.S. for.any limitations. If.Rx trip occurs, REF. A/B 'should be entered.

0

W.TE SIHLHA'IW MAIJUCf1(N TI'IYE Dropped rod ID: CRF-4 6

Dit10GITICN: F 4ure of either the novable or the stationary gripper ciautit, causing the selected rod to fall into the core.

17mILUG GUICI'IVII: Recognize failure and uso procedures to respord to a droppad rod.

IWIE: 10/13/89 811TS GT106 02fGNIS 10 = Movable gripper 1 Select faulty gripper 1G or SG SG = Stationary gripper H6,lu2 See attached core nep for rod 2 Select zori F2, etc. locations.

3 lbne I n IIT FI n tr In sI O E n: (Based on plant being at 3% power when rod drops, no operator action.)

O V to1E: In this nelfunction, the indication and alams received will differ frm case to case, depending on which rod was dropped and its proximity to the excore neutron detectors. Basically, it should be as follow:

When the rod drops, the digital rod position for the af fectrd mri vill f.ry!.icMn a red b ttera LD. hunciators for roc! at bottcm, RPI deviation, RPI rod deviation, and various other alarms nay actuate. %e power range noters should exhibit a flux tilt. Delta flux indication should be affected. Tavg will decrease and cause the PZR level and pressure to decrease. We B/U heaters should cuae on. % e decreasing Tavg should cause the Tavg-Truf deviation alarm to actuate. C-16 interlock nay be actuated.

UUntLCIm ic1E: W e fol3cwing rods will not cause a Rx trip when dropped: M2, D2, P4, B4, H6, K8, HB, F8,1n0, P12, B12, M14, D14. Any other dropped rod will cause Rx trip unless file RODDROP is run first.

IMPICIID SIUDEWr RFSIDEE: St&lents should Inspond IAW REP. 11. SS should be notified. System Ops should be advised of actions required to recover a dropped rod that nay affect turbine load. Students should be aware of any T.S.

limitations on control rods that nay be applicable. If a Rx trip occurs, REF. A/B should bo entered.

Q LJ j

R P W M L K J H G F E D C B A 18(P 12/12/88 1 '

2 S B C B Sg 3

3 4 S D S -

D S

~

I 3 E 3 5 S 8 C -D >

G B C A C B 7 8 88 8

8 C Sg A D A S C E pp 8 8 88 8 -

10 B C A C R U % # 8 C

- n 8 x D S E

D S 3 '

O 1' 14

'C - - %

S B C B S 3 3 i

I i 1 l CD ccren mMarR -

SHt2DONN E MBER .

IWE & RODS ._ BME & IGS A 4 Sg 8 B 8

% 8

'C .8 S 4 C

D 5 g 4

'IDIAL: 25 Sg 4

'IOTAL: 28 1

, CCNDIOL NO SEHDODN RE ILCNFIG6

J MIE SIMLERIUt MMJUCTICM l TflIE: BIRS 'naiperature elaient TE-381 or TE-382 failure ID: CVC-7 DefDt1Ff10N: TE-381 or TE-382 fails to selected value.

ENMLING 01UECTIVE: Recognize malfunctim of taiparature controller, and perfom acticns to rutove Unts frm service and repair.

i

, tWIE: 03/20/89 ,

1 SmW OFfl0DE COMMDfIS 1 Select failed elatent Opt. 1=TE-381 ;

Opt. 2=TE-382 2 Select fall value 0-300 F. '

i 3 Select vanp 0-99999 Sec. -

HIIW IYANP RISIDGE:

Optim 1 - (Note: Falling TE-381 could affect RH in out tarp which may cause a letdcun divert around CYCS mixed bed danins on high tarp. this is an +md respanse.) ,

If diluting -

1. TE-381 failing high will cause ' ICV-386 to open, chilling (if possible) );

the letdcun even further. ..

2. TE-381 falling J_gf will cause ' ICV-386 -to close, not cooling the letdown, causing the dilution effect of the danineralizers to decrease.

If barating -

1. TE-381 failing high will cause ' ICV-381A to close and ' ICV-381D to open.

'Ihis prevents the reheat in fran heating the letdown. Ihis, in turn, will decrease or stop the boration effect. 'i

- 2. TE-381 failing low will cause ' ICV-381v to open and ' ICV-381B to close.

'Ihis will heat the letdown, causing a high tarporature alam and diversion ;

of flow around both the BIES danins and the CVCS danins. (Direct caused by TE-382)

(PflON 2-Failing TE-382 high will cause a divert around the mixed bed danins arxi an .

F - alam (A 040) en ICB..

EKPECTED S'ItEENP RESEOGE: Students should respond to alarms IAW ap[ui p iate AUts. Students should recognize malfunction of systan and denonstrate systen i

knowledge sufficient to diagnose failure and contact aa uuriate group to investigate / repair. SS should be notified.

+

, ,.~[ .- ..,m, n . . . . , o-,_,y-.,.yp ,,,4- - , , . . ..#w.- y,, ..-w_,.,,,.,,m..W, -...%,'-.U..,,

. .b.'.... d. ,,E -.m-m.

. .,,-,.m'>-..*r-- - ,e---4.,=,E-

M3GS SIMERIUt MMElfCTICH v TPIIE: Diesel generator failure ID: DGS-1 DEDClu1TICE: Selected D/G trips or fails to start due to a nochanical failurn of the fuel rack's control nochanism. (Options 1, 2 or 3).

Options 4, 5 or 6 sinulates failuro of auto start circuitry.

FNAILIfG GULUTIVE: Rocognize nelfunct. ion and use procMures to respond to D/G failuru.

i DN1'E: 10/26/89 S'11TS G TICM3 E M4ENIS 1 = IE01 Fails auto 1 Select faulty diesel 1,2, or 3 2 = IE02 arxl nanual 3 = NE01 and !!E02 start.

4 = IE01 5 = IE02 Fails auto 6 = IE01 and NE02 start.

2 lbne -

3 awxe

]

IRIIT PINff RESOEE: If the diesel were running, it would trip, (if options 1, 2, or 3) causing a loss of power to its' ESF bus (unless in parallel node).

If the diesel were S/D when the nn1 function was activato:1, nothing would occur until the diesel was required to start (annually or auto start).

meluru S'IUXWP RFSOEE: Students should respond to trip of D/G (or failure to start) IAW appropriate AIRS /DG steps. SS should be notified. T.S. should be consulted and the app w iate group contacted to investigate / repair.

Students should recognize neod to prove operability of othar D/G, electrical

(^ pomr sources, and other amvgiate requirunents of T.S.

MIE EDKKJmR MALIgsviral Tr!12: Msin gmarator voltage regulator cet11ation ids EPS-2 DES 0tIPTICN Failure of the AC (autmatic) regulator, causing a change in the ger:rator's voltage output. Manual control posuible in DC regulaticn (manual) sode, t

INmtiDG OnHCEIVE: Recognize nalfuncthn and use pwc.alures to respond to failure of voltage regulator.

DME: 11/19/90 MEPS OPTICEE (DGEECS 1 Select anplitude of 0 - 25% % of current value voltage output change 2 Select period 0-99999 Sec.

s 3 Ncne IRIEF PLANT RESEUEE: %m tM oscillatim occurs,' the auto regulator will

' cause the excitar field current and output voltage to &e.ge,. effecting the generator output voltage. 'Ihe generator's MVAR load will chany) in p.vru. cit.at 1 to the anount of under or over excitation. Various ala= and protection circuits can be actuated, possibly tripping the regulator to manual, triming the generator output breakers and/or exciter field breaker.

EKPretyn Mt] DENT RESEUEE: Students should respcrd to ala- IAW app.vp. late If a t,mhine/Rx trip occurs, REP. A/B should be entered. SS abould be l AIRS.

i notified of regulator problems, and the a g.vg. e late group should be contacted l to investigate / repair.

O

.~ . _ _ = _ _ _ _

NOCs SImricot MtJJuccInt d Tim: Service bus trip ID: EPS-4 DESCRIFIION: Selectal service bus feeder beaker (s) trip (s causing a loss of that bus's power.

Trip is),due to failure in the breaker's nochanical latching nochanism.

DFETIG CBJR;nVE8 Recogn1Z0 failure and us0 PIOCodures to respond to servico bus trip.

IEE: 02/25/92 snTs crricus cannas 1 Select bus with faulty See list feeder brosker I

2 lbne 3 lbne IRIT FIIJE RESIQEE: Khen the fault occurs, all loads being powend by that bus will de-energize, affecting their appuplate systans.

WS PA01 IG14 IG20 PA02 m15 IG21 PB03 IG16 PG22 PB04 IG17 IG24 '

IG11 IG18 IG25 IG12 IG19 PG26 IG13 SL3 SIA e

IXPICIID SHDDR RESIQEE: Students should Inspond to alarms IAW anu.vplate AIRS . If Rx trip occurs, R E. A/B should be entered. Recovery of selected bus (es) should be IAW appus iate SYSs. SS should be notified. Systen Ops should be advised of plant status. T.S. should 1:e consulted for limitations.

t

. . - ._-_ =_ .

O N018 S3MRA'lut mat &UCHOi

(

U) TITIE: Icss of a 120 V/C Instrunent Bus ID: ITS-8 DIECIIIFf10N: limakers feuilng bus trip due to inverter failum (for loss of M1) or internal bus fault (for loss of PN).

FNAILIN3 GUICf1VE: Recognize failure and use procedures to respond to a loss of a 120 V/C instrununt bus.

IWIE: 09/23/92 mErs avrIONG 03euwls 1 = NN01 5 = PN07 1 Select bus 1-8 2 = INO2 6 = PN08 3 = IN03 7 = PN09 4 = IN04 8 = PN10 2 lbrua 3 lbne I R II T PIJ N f itf S T N S E : Plant response will vary, depending on which bus is lost. Ibr a compmhansive list of indication that is affected when an NN bus is lost, refer to REF. 21.

t

( 2W: Pcr : lecc en 15! h. , the EOIA t3m femr T/V cen M nard to re-energize the bus. If the instructor desires to treat the Im failure as a bus fault, than do not attmpt SmA transforner re-energization and then infom the students that the bus cannot be Ir+-energized due to a fault.

EXPFCIYD SIU1NP ll1SOEE: Students should respond to alams IAW alpropriate AIRS . Ioss of an instrument bus should be diagnosed, and proper OFN entemd.

'lhe appropriate plant groups should be contacted to investigate / repair the probim.

O

\

v

I N[IE SDIU[A'IER MAIEUNCTIGE TI'!1Es Feedwater flw transmLtter failure ids M -4 !

DESCRIPTIOff Selected feed flw transmitter fails to selected value. ;

INEING OLTICTIVE: Recognize e lfunction and perfo m actions to regain control of S/G level. Use procedures to respond to failed channel.

DME: 10/1'5/91 STEPS (PflO6 COMENIS 510 511 SG "A" = 510, 511 1 Select faulty 520 521 SG "B" = 520,-521 transmitter 530 531 SG "C" = 530, 531 540 541 SG "D" = 540, 541 6

2 Select fail value 0 to 4.8x10 lbm/hr.

3 Select ramp tine 0-99999 Sec.

IRIEP PIJMP RESFOEE: Plant response will depend on which f1w transmitter is :

usea for Mwir and widen one is failed.

T Transmitter not used for SGN[C - indication on that channel will go to selected value. -

Transmitter used for SGN[C - indication cn that channel will go to the selected value.

Palled IDi - the affected SG's feed reg. valve (11N) will initially open, Weh will cause the SG level to increase. Since the FRV controller is " level . dam-inant," SG 1evel my autanatically recover prior to reaching 78%, the P-14 tur-bine trip setpoint (Rx trip if above P-9).

Palled IIIGI - the affected SG's feed reg. valve (FRV) will' initially _ close, _

witich will cause the SG level to decrease. Since the FRV ccntroller is

" level - dczninant," SG level my autmatically recover prior to reaching 23.5%, the lw .1w SG level Rx trip setpoint.

10!E Plant' response description assumes no operator action.

EKPICITD SIUDENT RESIDEE: Students should respond to alams IAW aa w giate AIRS and attmpt to' regain control of feed fl w. SS should be notified and T.S. consulted for limitations. Students my refer to REF. 8. If Rx trip-

l. occurs, REF. A/B should be entered.

l-o

.-. . .....___,.. _ ,- _ _ , , _ , , ~ . _ , _ . . . - . . . _ ~ , . _ . . _ , . . . _ _ . . _ . . . , _ . - _ - _ . , , . . . . , _ . _ . - _ - . . _ . _ _ . . _ _ , . , _ , . , . _ . . . . . _ . -

g WIE SIMLEXIUt MAIEUNLYICH TISYJss Foodwater pmp turbine specxl contml failuro ID: FW5 IESCRUYIO4: Food punp speed control fails to specified value. K-SK509A affecting both pumps, failure of K-SK509B or PC-SK509C for individual punps. Manual control availablo in all cases.

194AIRJ)G QUICTIVE: Rocognito failure and perfonn actions to regain control of MFW spood.

DME: 09/28/92 S'IEPS G'rIOiS cohMietIs ,

A = FC-SK509B, punp A Select pump with faulty A,B, or Both 1 B = K-SK509C, punp B '

specxi control Both = K-SK509A, A & B punps 2 Select fallod speed 3650-5712 RPM 3 Select ranp time 0-99999 Soc. (Controller ramp, IWP follows) 1RIEF PIMff RESFOEE: (Based on plant at full load when a feed pmp speed controller iails.)

FAIIS IIIGI - Affected punp's spood increases to specified value. The other punp decreases its' speed in an attenpt to maintain the proper feed header pressuru. Food ficw increases to all SGs,' causing -

their levels to increase s ughtly and their feed control valves to close down.

FAIIS IIM - Affected punp's speed decreases to specified value. The other punp increases spood in an attspt to naintain proper food header pressure. Feed flow decreases to all SGs, causing their levels to decrease slightly and their feed control valves to open. Rx trip on In-In SG level nay- occur.

EKPICDU S'IUEfff RFS00EE: Students should respond to alarms IAW app.vg iate AIRS arxi attspt to regain control of food punp speed.in manual. 'SS should -

be infonnad and Systczn Ops advised of-possiblo need to reduce load. Appro- ,'

priate group should be contacted to investigate / repair. If-Rx trip occurs, REF. A/B should'be entered.

O ,

- --m_._.____._-___ _ . - - _ . . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ .

1 WCGs SIMIKA'Im MAIEmerim TrIn: Feed 11ne bruak inside contaimmt ID: I%8 DHSCPlPTIW: Bmak in the selected feodwater line down-stznam of check valve inside containment.

ENAHGDG G1782f1VE: Recognize syrrptczns and use prooec. ares to respond to feed break inside CDc.

DME: 04/23/90 swss wfIms caMm w2s

)

1 Select SG with break A,B,C, or D 2 Select leak rate 0 to 5 x 10 6 1hu/hr. .

3 Select ramp time 0-99999 Sec. l HRIEP FIANf RESPOEE: The affected SG will indicate a higher feed flow while .

the other three SGs feed flow decreases. Ievel in the affected SG decreases.

The fc<xi control valve for the affected SG opens to maintain SG level. Con-tainment hunidity, pressure, and tauparature increase. Rx trip should occur on .

Io-Io SG level or SI on CDR pressure 111-1.

+

t EKPRrmn S1U]ENT RES10EE: Students should enter REF. A/B upon SI/Rx trip.

Students should enter REF. G when it is detennined that a secondary side fault exists. SS should be notified.

%4 O

NCI18 SLN MAUTtCf10N O TrIIR: Ftin feal pnp loss of speed signal Et DM13 r- IESCRIPTICH: 7.oss of the feed punp speed control signal.

DWLIPG CEiTICTIVE: Recognize failure and perfomaa u.vgiate acticns to investigate and/or reduce load to maintain S/G 1evels.

DME: 01/24/90 SIEPS OPTIGE CORENIS 1 Select affected puap A1, A2, B1, B2 OPTICtf MFP # OF SIGW.S IDST Al A 1 A2 A- BOIH B1 B 1 . .

B2 B BOIH 2 lbne 3 lbne O IRIEP PIANf RESPQEE: If only one speed signal is lost, the caly plant response is for the "Inss of SPD Signal" annunciator for the selected'feedwtiter puap te als.un.

If both speed signals are lost, the "Ioss of SPD Signal" annunciator will alarm and the nain fecdwater punp turbino control valves will close without a trip signal. J.12 manual or autcastic control is available to the cperator.

EXPICITD SITENT RESKNSE: Students should respond-to alarms IAW apiu.vpriate

. AIRS. If only one spaed signal is lost, students should send T.B.-watch to. >

investigate locally. 'Ihe appropriate groupe should be contacted to investigate / repair. If both speed signals are lost, students should initiate. >

a load reduction as necessary to maintain S/G levels. If Rx trip occurt, REF.

O A/B should be entered.

- _ __ _ _ _ _ _... __.. _ . __ . __ ._ , _ , _ _- u -.._..__ _ _ _ . _ -

NG23 SIMHA*IUt MAI1UCTIO4

'1 T H E : Stmm dump ccutrol failuro 3D: MSS-9 IRDCICIITIO1: Failtiro of eny ano of the four stnam dump valvo sequencers.

12JAIUJtG OUIUTIVE: Rrcognito nalfunction and perfonn actions to roostablish control of steam dunps or to mitigato the conseguoncos of the falluru.

IWit: 10/13/09 mus GTIOG 00MMINIS 1 = Cooldcun valves (34,41,45) 1 Select faulty group 1,2,3, or 4 2 = Group 2 (37,38,43) 3 = Group 3 (39,40,42) 4 = Group 4 (35,36,44) 2 Select fail position 0 - 100% 100% = Full open 3 Soloct ramp tino 0-99929 Soc.

11111 7 PI Nff IllEIO UE:

IUIE: All steam dump interlocks are functional during title nnlfunction.

\

(i.e. - Steam dumps nust have an anning signal for

- lfm rtion to W rk1)

If failed to zoro, solocted group will not open when Irquired. RCS tm p-oratum will inemaso, causing steam pressum to increase and possibly acutato the SG relief valvos. If tmperaturo is greator than or equal to liigh 1 or litgh 2 affected valvos will fully open.

If failed open, steam ficw increases, causing Tavg to decrease, pressurizer pressuru and levol to decrease, and SG 1evels to swoll. Nhan tm poraturo drops below penntsoivo P-12, the steam dump valvos closo, tenninating the ecoldown. As RCS taperaturu increases, P-12 clears, and the steam dumps again open, starting the cycle all over again.

12P1mn S!7.a212 ItESIDEE: Students should respond to alarms IAW ai g vi41ato ALRs. Students should diagnoso nnlfunction in steam dump control systczn. SS should be notified and appropriato group cantacted to investigato/ repair.

O v

l

/

rN \ W.IE sit 1HRIUt WJ1UCTIOi k

THLE: Intentrdiate range channel ganen cmpensatica failuro ID: NIS-4 112Dt11'f104: Variation of ccupansation to either intenwriiate range channel.

12mlLilU Gull'f1VE: Recognize failure and use procedures to respond to incorrect ccuperisating voltage probim.

DNIE: 09/22/92 S'IMS GFfl06 Q M ENIS 1 = 35 1 Select channel 2 = 36 3 = Ebth Positive = underwipwisation 1 (10~11 to ikgative g overwigxsisation 2 Select current value If +5x10~ or gruater is used, 10-5) amps low cmp. voltage alarm will actuate.

3 Select ramp tinn 0-99999 Sec.

(,,/ 11111 7 MANP RIELUEE: PUIE: 1.R. meter will respond according to the

, following formula I

gy g=Iahl + step 2 value

1. When undet wigxasated, the I.R. channel will indicate both nou p and ganun flux, causing it to level off at a high value (above 10~ amps) during a Rx snutdown. If the failure is high enough, it can prevent auto re-energization of the source range high voltage. P-6 will not clear.

2. When overempensated, the I.R. channel will indicato lower than actual because part of the neutron flux is also being cancelled with the gannu flux. During a plant shutdown, the affected channel will decrease faster than the unaffected channel. If,both channels are overempansated, a reactor trip on SR high flux (10" cps) nny occur during nornal plant start-un and shutdown.

IXITURD SIUINP RFSIONSE: Students should recognize misantch between I.R.

channels, or that source range has not re-energized as it should on Rx shut-down. SS should be infonrad and the appmpriate group contacted to investi-gate / repair. Any alarms should be responded to IAW appropriate ALRs. T.S.

should be consulted for any limitations.

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MIE SIMIMM MAIJUCI'IO4 TrlfRt Inadvertent contairuaant isolation ' Phase A' In: PCS-6 IESCR11 TION: Spurious sicym1 fmn cxmtainnmt isolation pushbutta).

194MEJM3 GUTCf1VE: Recognize unlfunction end take actions to woover fmn Phase A isolation.

IWIE: 09/22/92 STEPS GTIOG QDOMf15 1 Select train X or Y 2 lbne 3 lbne 15tIEF MJeff RESIOGE: lbutal containmnt ' Phase A' isolation and containment ventilation isolation will occur to solc h train.

SIGNIFICMfr EITICIS:

FOR OFIIO4 X - KA IN-29 will close, causing loss of letdown and loss of nontal pressurizer spray. Pmr.Titcr lawsl arn pressum will- l i m_r.co. Ideo 11; W-8112 will close, causing RCP seal return to go to the IWP. Plc level and pressure will increase.

Im OITIQi Y - IU IW-8152 will close, isolating the nontal letdown path.

'Ihis causes Iulief valve EU V-8117 to send Int 4cwn to the PFt. Also IG IN-8100 will close, causing RCP seal return to go to the IRP. PRP level and pressure will increase.

EKPICITD S'IUDE9fr RESIDEE: Students should recognize nelfuncticm fmn-L available indication. Students nny refer to a a u.qu. late sectionc of REP. 24, AIRS, arxl appropriate SYSs to recover fran inadvertant actuation and _ restore to noural operating configuration. SS should be notified and app.q;riate group contacted to investigate / repair 4 i

- - ~ . .

, , . _ . . _ . . ~ ~ -- . _ . _ - _

NGE SIMTWInt MAlluCTIO(

U TI'IIE: Pressurizer IGN Contml Systen Failure ID: PRS-4 DIIDlIPTIO1 _ Due to a ceritrol systen malfunction, the PER PGN sparlously opens or fails to close khon op3ned nornnlly. %e TGN 104 pressure interlock to close ,

the PZR FGW and its block valve will or will not work (depending on the option selected).

12WLI!G GUICTIVE: Recognize PZR ION failure and parform actions to regain pressure contml.

rWIT 09/25/92 SnTS OPTIos cuenwrS 1 = PORV 455A 1 Select IOiV 1, 2, 3 2 = PORV 456A 3 = IDIH 1 = Spuriously opens w/LP interlock 2 = Spuriously opens w/o LP 2 Select failure typa 1,2,3,4 interlock

3 = Falls to close w/LP interlock k 4 = Falls to close w/o LP interlock 3

1RUF 14H(r RESIOsEt Plant response will depend on type of failure. In all cases, a plant depressurization will occur. With the LP interlock available, the POIN and associated block valve will close khon PZR pInssure decreases to 2185 psig. Without the interlock available, the PorW and associated block valve will rutnin open until closed by the operator.

EKFICnD S'IUDE2(r IUSIDEE: Students should respond to alanns I1M appmpriate ALRs. Valve malfunction should be recognized. %e appmpriate plant groups shoold be contacted to investigate /repsir the control systan. T.S. should be consulted for limitations. If SI/Rx trip occurs, Ref. A/B should be entemd.

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Mrs SIMLHW10( MAIJucrIO4

'IT1IP.: IGN stuck open ID: ISS12 FAEGIFFION: SelNtod TGN will stick after opaning due to m>ianical failure, with in:11 cation, unless stuck at 0%.

12MILUG CLUICTIVE: Recognite that P'J R IGN is stuck gen and perfonn actions IAW procedures to isolate leak.

nut: 09/25/92

'~

UIU'S OPfl00 COMlWIS l = IGN 455A 1 Select IGN 1,2,3 2 = ION 456A 3 = Ibth 2 Select failed position 0 - 100% % open a

IRIIT FIRfP RIS10GB: h' hen selected PORV opens, it should rcnnin gun. The plant should contdnue to dopmssurize until the block valve is shut at l 2185 psig if Cold Overpro.3 sum Protection is not anned, or until the operator rianually closes the block valve if Cold %rpressuru Protoction is anted.

IZPIURD SIUXNP RESIDGE: Students should respond to alanns IAW appropriate AIRS . Students should recognize decrmsing RCS pressure and take action to locate and isolate leak. T.S. should be consulted for limitations. If SI/Rx trip occurs, Ref. A/B should be entered.

WEIE SINKKlut MAIJisCfl04 TITIR: Faulty primry IUD ID: ItCS-1 IMDti1TIOft Failum of narrw rango IUD i IMillC 0111Cf1VE: !ATgnize mlfunction and use procedurna to resp:md to faulty primry ICD. i Iwlt: 11/03/92 Im2'S GTIGE CDecef!S I t

SelectIppand 411A, 411B, 411C 411 = Imp 1 ,

1 have 421A, 421B, 421C 421 = Imp 2 A=fhave j

,p 431A, 431B, 431C 431 = Imp 3 ,

cold 441A, 441B, 441C 441 = Imp 4 D=pcold T

hot C=Thot 2 SelAt final value 5300F-6300F 3 Select ranp tino 0-99999 seconds IRIF# IMff RIELONSE: Failure indications on E B

[

\ T r Thave +:P'# avg i delta T p Tczid @ :) Tavg i delta T M h l T T r have + 9T avg & delta T. p Tcold A Tavg4/deltaTf h

Any falluro which causes T to increase (f) will cause auctioneered high ,

T to increaev. Depardiffon plant conditions, an increasing T ,

aiYSct autcznatic rod control-(rods drive in), steam dunp control--iE1,HI-2), muld '

PZR level control (progranmed level setpoint increase), and rod insertion limit calculation.

Any failure which causes T co decrease (4) will cause aucticnecred low-T to decrease. 'Ihis witFeause a low tmperature error alarm (C-1s) to o E and the rod control ("/RCS /Tg) tanperature error meter will indicate erroneously Icu.

AnyfailurewhichcausesdeltaTtoincrease(4)willaffeetthatloop's or/ delta T circuits; causing deviation alarms and my actuate protection ,

histables.

Any failure which causes delta T to decrease -(M will have no effect cm. r plant rusponse.

EKPHCnD SMHeff RESEOGE: Students should respord to alanne IAW anAvslate AIRS and OFNs. Control mlfunctions should be recognized. 'Ihe. appropriate

- plant groups should be contacted to investigate / repair the. control systan.

T.S. should be consulted for limitations. If SI/Rx trip occurs, Ref. A/B ;

should be entered.

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MIE SIMIH A'IUt MAI1UUTICN T1'11F.: Steam generator tute rupturo ID: RCS-2 D11X3tIPfl(N Prinary to secondary tube mptum (up to design lusis mpture).

IMLUG GulcrIVE: Recog tize eymptcus and use proecxlures to mqund to SG tube failure.

LEIE: 8/4/92 UIM'S OPfl06 Q7HINiti 1 Select SG A,B,C, or D 2 Select leak rate 0-3500 GIH Rate 1.usod on RCS at 2235 psig.

3 Select ranp tinu 0-99999 Sec.

lHIIT PIRif RIG U EE: Depending on the selected Icek rate value, the follcwing meponee m y ~~ car with differing rapidity:

RCS prussura docrease, PZR level docmase, SG activity increase, and possible Itx trip /SI; radiation alarns occur on the blowdcwa nonitor, the condensor air discharxje nonitor, and the sanple nonitor. Possible steam ficw/fecxl ficw deviation, and a level increase in the affectrri SG.

toIE: Estimted fIcwrato thru a double-endcxi shoar of one tube at NCGS is

~432 gpn at IDP.

IMPICIM) SIUDIWP 111G06E: Response will vary depending on the size of the leak. If smil, a fairly rapid power decrmse should be initiated. If lanje enough, SI/Rx trip should be initiated, and REF. A/B should be entemd. REF. 11 should follcw. SS should be notified. Students should danonstrate concern for limiting possible release to envimnnent. As familiarity with proceduros incrmses, students should dcznonstrate ability to isolate affected SG in less and less tino.

i

MIE SDEutKR Mh1FfEFFtfEI

.i O ids RCS13 TI51JE - Failure of selected ti- --x-mia IESCRIPHIN: Selected tA -r-gle will reacti selectai fail positics within desized rang time.

4 ENMLDG (ERCTIVE: Recognize and mpd to failed tJuunoccuple. ,

i tant 11/21/90 i i

82EPS OPerrist nrnessem See attached sheet fcr subcool- l 1 Select th -x-gle 1 - 50 ing train assigreent ard T/C location.

2 Select final value 0-50000F Aucticomered high T/C used in ~~

subcooling nonitor.

, 3 Salect rtinp t.ina 0-i&M 9 Sec.

IRUF PIANT RESKEER: If failed high, selected T/C will be the Auct. high T/C and will affect the amylate train's subccoling acmitcr. RCS less than 500F subcoolcd and RCS Saturate alarms may activate. Other indications would .

O be on CFC display 5 MAP.

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S 3

N imIENP RESEOEE ._ Students should mp-d to alama IAW &au.vga. late AIRS. SS should be notified and T.S. consulted fcr limitations. Aau.v3 late group shoald be ecntacted to investigate / repair.

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8 25 47 19 40 11 32- 4 26 900 27 @ l 9

10 50 23 44 16 36 9- 29 2 12 48- 20 41 12 33 5 ,

O n 14 24 45 17 37 9- 30 15- 38

'IRAIN A '5ULIN B 1,4,5,7,13,15,20,27, - 2,3,6,8,9,10,11,12, 29,30,31,32,33,35,38,- 14,16,17,18,19,21,22, 39,41,42,43,44,45,46, -23,24,25,26,28,34,36, i 47,48,49 37,40,50 LO ,

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m WCGS SINULATOR MALEUNCTION i

TITLE: Failure of RCS wide range pressure-high or low. 10: RCS14 DESCRIPTION: fails selected transmitter output to desi;ed value.

ENABLING OBJECTIVE: Recognize malfunction and respond to failed wide range pressure transmitter.

DATE: 10/15/91 STEPS OPTIONS CONMENTS A = BB PT-403 1 Select transmitter A,B, Both B = BB PT-405 Both = BB PT-403 and BB PT-405 2 Select fail value 0-3000 psig 3 Select ramp time 0-99999 Sec.

BRIEF PLANT RESPONSE:

A A - BB PT-403 feeds: RHRinterlock(<383psigopenpermissive),forBBHV-8702

() A&B Yellow train subcooling (fail low possible subcooling alarm if Rx trip breakersopen)

Yellow train cold o/p (fails high possible overpress, alarms and PORV 456 may open)

B - BB PT-405 feeds: RHR interlock (<383 psig open permissive), for EJ HV-8701 A&B Red train subcooling (fail low possible subcooling alarms if Rx trip breakersopen)

Redtraincoldo/p(failhighpossibleoverpress,alarmandPORY455open)

Both - Affects both trains as above.

EXPECTED STUDENT RESPONSE: Response will vary depending on plant conditions.

Students should respond to alarms IAW appropriate ALRs. T.S. should be con-sulted for limitations, and appropriate group contacted to investigate / repair.

m

MIE SIMIRIOR MhIEUCTIN i O TTHE: RHR HX bypass line leak 1D: RHR-4 IETRIPTION: Selectable size leak upstream of the colected RHR HX bypass valvo.

nWLDG ODIcrIVE: Reccgnize synptcrns and perfom acticns to ocntrol loss of coolant and systan f1wrata and cooldcwn rate change.

IRIE: 12/22/89 SHTS OETIQ6 009ENIS 1 Select RHR train A, B 2 Select leak rate 0-3500 GPM Isak rats based cm) an RHR purp discharge pressure of ~550 psig.

3 Select ranp tine 0-99999 Sec. ,

IRIIT PI/Nr RISIDEE: (Bastd cn fault occurring during a plant cooldcun cn RHR.)

he affected RHR trains flw will decrease, causing the bypass valve to open.

O- As the bypass valve opens to naintain system flow, less flow will pass thru the HX, causing an increase in its discharge tmperature and a decrease in cooldown rate. PZR level will decrease, and if solid, PZR pressure will also drop (negnitude depends en size of leak). WI level should decrease and actuate auto nako-up. We Aux building (DW) sung level should increase as indicated cn IE LI-103 and 104 until the stmps overficw (at approxinately 66").

~

EXIvrMm STUDENT RESPONSE: Students should recognize ficM/cooldown transient in systan ard respord to any alarms IAW appropriate AIRS. Students my send A.B. watch to investigate problan. SS should be notified and appwp., Lte -

group contacted to investigate / repair. Students ney ocasider switchij $ to other RHR train. T.S. should be ocnsulted for 132nitations. Students may refer to REF.15.

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Wats SIMLIIAlat MAIRicfIm THIE: Radiation nonitor2 process f1w failure ID: RMS-1 DESCRII'f1CH: Selected process nonitor experiences loss of process flow.

DWLIIG Q.tTIUf1VE: Recognizo failure of rad nonitor and perform actions to restore flw through nonitor.

IEIE: 04/23/90 MEPS OPrIors aneNfS 1 Select nonitor 1 - 32, 40 See attached list 2 Select % of failure 0 - 100%

3 lbne HuBP Iurir ItESIOEE: (Plant response will vary depending on nonitor selected.)

NJIE: With present nodel, % failuru selected should be 100.

O EKPIE110 muXNT RESIDEE: Student response should be IAW appropriata ALRs.

When it is detennined that nonitor failure is due to lcw flw, chcmistry should be contacted. SS should be notified of failure and T.S. consulted for 1. imitations.

O

MAutNCTION 106-1 (AT1?OMENT)

J OPrim i KNI'Itll ID I DPSCRTPI7m 04/23/90 1 SJ01 CVCS IIIDCEN 2 SJ02 SG LICUID 3 EF35 ESSDTIIAL SERVICE h%TER 4 EF36 ESSDEIAL SDNICE h1TER 5 H309 CCW 'nMIN "A" 6 LE59 'IURBD{E BIDG DRAIN 7 8425 SG BwWDCHit PROCESS 8 EA4A SDNICE h%TER REIURN 9 EA4B SERVICE WATER RUIUR11 10 m10 CCW 'HtAIN *B" 11 FB50 AUX S'H4 00tO RECOERY TATE 12 R{52 SG BIGOOhH DISC 1NGE 13 HB18 LICUID WASTE DISCIWGE 14 HF45 SEC LICUID WASTE DISCHARGE 15 HE16 DORati RECYCLE DISTILIATE 16 GH23 GAS DECAY TANK VDE EXH 17 GE92 CatOEt1SER AIR DISCHARGE 18 GT21 PLAllr UET VDE (Gasocus/ Effluent) 19 GIl0 RAGASTE BLDG E01AUST (Gaseous / Effluent) 20 GK04 00tuROL R004 SUPPLY 21 GK05 COtEROL R004 SUPPLY 22 GG27 FUEL BLDG VDTI EXHAUST 23 GG28 FUEL EIDG VDff DOIAUST 24 GT33 00tfrADEDTI PURGE EXHAUST 25 GT31 00t7tADMDE A'DOSPHERE 26 GT32 CITIADNDE A'DOSPHERE 27 GT22 CatEADEDir PURGE DOIAUST 28 GH10 RADWASTE BIDG EXHAUST (Part./ Iodine) 29 GT21 PIAlfr UGT VDTI (Part./Icdine)

-30 GI22 RAURSTE HIDG VDfr

. 31 GL60 AUX BLDG VDTI EKHAUST 32 GK41 ACCESS 00tuROL VD7tIIATIOti 40 HF95 SW DISQWGE 'IO hWI i

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1 NOCS SIMHA'101 MMEUCTICM i Trna: Process radiaticovicnitor actuation ids RMS-3 mntIPI'ICM Selected process acnitor indication increases !

FNMEJPG GUICFIVE: Recognize and respond to alarms /- ,

actuations IAN a3;pvgiate procalures, scE: 04/23/90 e1EPS TrIGE COMMENPJ l Select channel 1 - 64 See attached list 2 Select indication 0 - 1000 pc 3 Select ranp time 0-99999 Sec.

U tIEP I W W F Rl!SI D E E: Plant response will vary depending on ntnitor selected and selected indication.-

Kite Nonitors denoted with an asterisk (*) represent an autmatic action if Indication is greater than channels alam setpoint.

See list.

ICIE: When mlfunction is cleared, Rad level my be returned to norml quickly by ramping ZO9WAL(X) to the a3;gvgiate reading where X =

the option number of m 1f RMS-3.

i.e. PAT ZORWAL(3),2.3E-6,120,0 EXPICED SIUDENP RESNNSE: Response will vary depending on nonitor selected and final indication. Students should respond to alams and/or_ increasing indication IAW aissvgiate AIRS. . Students my display process nonitor list on CRT to locate alaming monitor, or they my use the RM-ll (if. functional).

SS should be notified and ch mistry contacted for back-up samples. .If_a failed nonitor is the cause, the am vg iate group should be contacted to

- investigate /rerair. T.S. should be consulted for limitations.-

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MALFUNCnm 10G-3 (NIT /CIMENP) 04/23/90 orn(_N 1 rum a m Ixmmmm gne mvr Arann mvr 1 &701 CVCS IA N I 5.0 E-01 1.0 E-00 2* SJ02 S'IM GEN SAMPLE LINE 1.r b05 1.0 E-04 3 EF35 ESW ' MAIN A (RED) 1.0 E-05 1.0 E-04 4 EF36 ESW 'UtAIN D (YELIIM) 1.0 E-05 1.0 E-04 5* EG09 CCW 'IRADI A (RED) 1.0 E-06 1.0 E-05 6* GK04 CIE IN AIR nm (GAS) 1.0 E-05 1.1 E-03 7 GK04 CIE IM AIR nm (PART) 1.0 E-08 1.0 E-07 8 GK04 CIE IM AIR nm (IOD) 9.0 E-09 9.0 E-08 9* GK05 CIE IM AIR nm (GAS) 1.0 E-05 1.1 E-03 10 GK05 CIE RM AIR nm (PART) 1.0 E ,)8 1.0 E-07 11 GK05 CIE IM AIR Um (IOD) 9.0 E-09 9.0 E-08 12 GK41 ACCESS GIE AREA (PART) 5.8 E-07 5.8 E-06 13* LES9 'IURBINE ELOG DRAINS 2.0 E-04 2.0 E-03 14* GE92 CONDENSER AL DISOIARGE 2.0 E-06 2.0 E-05 15* EH25 S'IM GEN BWWDOWN PROCESS 1.0 E-06 1.0 E-05 16 EA41 SERVICE WATER 'IRAIN A 1.0 E-06 1.0 E-05 17 EA42 2ERVICE WATER 'IRAIN B 1.0 E-06 1.0 E-05 18* G327 FUEL BLDG VDE EKH (GAS) 1.0 E-05 2.2 E-03 19 GG27 FUEL BLDG VDE EXH (PART) 1.0 E-08 1.0 E-07 _

20 G327 FUEL BLOG VDE EXH (IOD) 9.0 E-09 9.0 E-08 21* GG28 FUEL BLDG VDE EDI (GAS) 8.1 E-06 1.8 E-03 22 GD FUEL BIDG VDE EXH (PART) 1.0 E-08 1.0 E-07 23 T;.28 FUEL BLDG VDE EXH (IOD) 9.0 E-09 9.0 E-08 24 GL60 AUX BII:G VDC EXII (PART) 5.8 E-07 5.8 E-06 25* Gr33 CDC PURGE EXH (GAS) 8.81 E-05 3.5 E-04 26 GT33 CDC PURGE EXH (PART) 5.8 E-07 5.8 E-06 27 GT33 CDE PURGE EXH (IOD) 7.8 E-09 7.8 E-08 28* GT31 CDC ADOS (GAS) 3.9 E-04 3.9 E-03 29 G. CDC A'1NOS (PART) 5.8 E-07 5.8 E-06 30 G1 CnC RnOS (ICD) 7.8 E-09 7.8 E-C8 31 Gh. UNIT VDE EFF (PNIT) 5.8 E-07 5.8 E-06 32 Gr21 , UNIT VDE EFF (IOD) 7.8 E-09 7.8 E-08 I

MMEWCTIm RMS-3 L(ATim m ) 04/23/90 hf

< v s Paae 2 l EE. $ EE AIM M ;

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33* GT32 One ADOS (GAS) 3.9 E-04 3.9 E-03 34 Gr32 CDC A' DOS (PART) 5.8 E-07 5.8 E-06 35 Gr32 CHE A' DOS (IOD) 7.8 E-09 7.8 E-08 36* Gr22 CDC PUfGE EXH (GAS) 8.81 E-05 3.5 E-04 37 Gr22 CDC PURGE EXH (PART) 5.8 E-07 5.8 E-06.

38 UP22 CDU PURGE EXH (IOD) 7.8 E-09 7.8 E .

39* m10 OCN TRAIN B -(TELIN) 1.0 E-06 1.0 E 40 GH23 NASTE GAS VEtc 1.0 E-05 1.0 E-04 41* FB50 AUX SDI OND 'IK DISCH 1.0,E-05 1.0 E-04 42* BH52 S1M GEN BwN EET 2.0 E-05 5.0 E-03 43* HB18 LIQUID RW DISCH 2.22 E 2.22 E-02 44* HF45 SEC LIQ NASTE DISCH 2.62 E-05 2.62 E-04 45* GH10 RW BEDG EFF (PART) 5.8 E-07 5.8 E-06

'3 qp 46 GH10 7.8 E-09 7.8 E-08

, RN BEDG EFF (ICD) 4~* HE16 BORON RECYCLE L% P DISTL 1.0 E-06 1.0 E-05 K GH22 RN HwG EXH (PART) 5.8 E-07 5.8 E-06 43 GH10 RN BEDG VENT (ID RAIGE) 4.98 E+02 5.66 E+04 50 GH10 RN BLDG VENT (HID RANGE) 0.0 E 00- 0.0 E 00 51 GH10 RW EDG VENP (HI PANGE)- 'O.0 E 00 0.0 E 00~

52 GOO RW BLDG VEtE (EFF RLS RATE) 1.33 M03 5.66 E+04'

< 53 - Gr21 PIANT UNIT VENT (ID RANGE) 1.0 E-04 1.0 E-03 54 Gr21 PIANI UNIT VENT (MID RANGE) -0.0 E 00 0.0 E 00-55 GT21 PLANT UNIT VENT (HI RANGE) 0.0 E 00 0.0 E 00 56 Gr21 PLANI UNIT VENT (EFF RIS RATE) 5.85 E+03 2.92 E+05 57 AB111 SDI LINE D PORV DISCH 1.5 E+01 1.5 E+02 58 AB112 SIM LINE C PORV DISCH 1.5 E+01- 1.5 E+02~

59 AB113 SDI LINE B PORV DISCH ~ 1.5 E+01 1.5 E+02:

60 AB114 SIM LINE A PCRV DIFCH 1.5 E+01 1.5-E+02 0 61 -FC38 AUX IW 'IURB DISCH 1.5 E+01 1.5 E+02 l

l 62 GT59 CDC HI RANGE AREA ION 1.0 E+02

[ 63- GT60 Cnc m RAIGE AREA ION 1.0 E+02 64 HF95 SIN DISCHARGE 'IO WNP 3.0 E-07 3.0 E ,

l: '

L i

i NrES SDEA'IIR MAIRICTION f

la ID: 'HR-8 TflYE Turbine trip failure DESCRIFfli.N Defeats auto end/or unual turbine trip functions.

DWLI!G GUICTIVE: Recognize that turbine has fai'.ed to trip and respond IAW appropriate procedures.

IvaE: 06/21/89 snTS OPrIOs acr*ENIS 1 = nanual 1 Select type of failure 1,2,3 2 = auto + nanual 3 = no auto trip w/RX trip /SI 2 lbne 3 lbne IRIEP FIANP RESPOEE:

MANUAL - Operator is unable to trip turbine sten he desires to. Rx and

(- turbine protection systems will trip turbine.

U AITIO &

MANGAL - Turbine will not trip unless DC pumps are put in PIL. If Rx has tripped, plant will cooldown until the MSIVs are closed.

Possible SI on stmmline pressure follcwing Rx trip.

Ib Auto w/Rx Trip /SI - Turbine will not trip on Reactor or Safety Injection. Turbine will still trip fram other trip signals including manual. If Rx has tripped, plant will cooldcan until MSIV's are closed.

Possible SI on stu mline pressure follow Rx trip.

EXPICIED S'IUDENT RESPOtEE: Students should respond to inability to trip turbine by sending T.B. watch to locally trip at front stane d or by seu W DC punps. If turbine will not trip, students should consider closing MSIVs.

l SS should be notified and aps vg iate group contacted to investigate / repair.

Students should respond to alarms IAW aps vgiate ALRs. If Rx trip occurs, REF. A/B should be entered.

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.. . - -- .. . _~

p) s MIE SIMIMOR MhTEarvrrw er'rrR MSR drain tank drain valve fatlure ID: 'ItRll DESCRIPflIN: Selected MSR drain tank level control valve fails to specified positicn due to a faulty positicmar.

BWLIIC GUIIMVE: Recognize fallure and Isoycid IAW mauvgiate s vidares.

DME: 11/21/90 sues m fraus cneenes A = LV 28 1 Selact tank with A,B,C, or D B = LV 33 faulty valve C = LV 219 D = LV 223 2 Select fail positicn 0 - 100% % open 3 Select ranp time 0-99999 Sec.

IRIEP EJMP RESPOEE: (If the local valve in series with the NSR drain tank dunp valve (IIA) is closed, this elfunctico could lead to a turbine trip cn O MSR drain tank high level.)

If failed open, low level alama will be actuated via tim plant cxmputer.

If failed closed, level in the drain tank will increase, actuating a high level alam. 'Ihe dump valve will open, sending the excess water directly to the condenser. Imvel will be ccntrolled at the dung valve setpoint.

pyn sImENP RESEGEE: Students should respond to alanm IAW dauvplate AIRS. If turbine trip without Rx trip occurs (belcw P-9), students my re=rmd IAW REF. 1. If Rx trip occurs, REP. A/B should be entered. SS should be notified, Systm Ops advised of any plant limitations, and the anacilate group contacted to investigate /rapair.

O

. _ _-- . _ m -- . _ . .. __ _ _ . _ _ _ _ . -_ _ _ _ .

KIE SINKA' Int MAIJUCTIOi TITMs - Make-up pump trip ID: HAT-1 IM Dtn'rION: Golected MUP trips, due to bearing fallure.

ENMLTIG OUICPIVE: Rewgnize failure and respord to trip IAW appropriate procadures.

DPOE: 09/22/92 S1YPS G7f106 (IMENIS 1 Select faulty MUP A,B, or C 2 None 3 tbne IRUT FI#ff RES106Es M/U PUMP 'IRIP AND MUSS SCREEN EMERG annunciators alams.

If no aux raw mter pump running,= M/U !!DR ICT FULL alam should activiate if no other MUP running. If action not taken to restore flow, MUDS WIR LEVEL ID annunciator should activate after appropriate tine delay, followed by WIR TREAT 'IROUBLE annunciator.

INSTHUC'lut IDIE: All alams except M/U pump trip will need to be instructor actuated after an aps w inte time delay.~ -

M/U HDR NC7P Eu L - 001E MUDS WrR LEVEL'ID - 003B WIR 'IREAT 'IROUBLE - 006E EXPICPFD SIU]ENP RESEOEE: Students should respmd IAW appupinte ALRs and.

Initiate actions to identify and correct cause of MUP. trip,' (i.e., contact site e tch, E-maint. etc.). SS-should be notified.

FORM KGF.1 REV 4/89 o W$1.F CREEK NUCLEAR OPERATING CORPORATION PROCEDURE NO.: lON:

KP-880 3 l TITLE:

SIMULATOR MODIFICATION RAQUEST 0 " '" N REVISION

SUMMARY

0 o ff@

Titles changed to correspond to Division organization chaEt after recent reorganization.

Form KTF-880.1 has been reviewed and revised.

O men eu uRu 019 l

, APPROVALS - . DATE APPROVALS DATE lA$iff b k Y /- 7-97 ==e-- W hd 9006f2.

karakhn Mw v%#Ad ' un

' LO W}! c.e-9e hp -

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-[ AUTHORIZATION: DATE:

'- 'U 7 [ /d 7O D d[d!fC RELEASE!):

PAGE 1 OF 4

FORM KGF:2 REV,1/87 -

NUMBER; Wei.F CREEK

' NUCLEAR OPERATING CORPORATION REVISION:

1.0 PURPOSE This procedure establishes the methods and-responsibilities for the initiation and approval of simulator modification requests.

2.0 SCOPE 2.1 This procedure applies to all proposed modifications to the Wolf Creek Generating Station simulator facility.

2.2 This procedure is limited to recommended changes to hardware simulator configurations and software programs.

3.0 REFERENCES

Training Division Procedures Manual Glossary 4.0 DEFINITIONS Terms and abbreviations used in this procedure may be found in the Training Division Procedures Manual Glossary.

5.0 RESPONSIBILITIES 5.1 The Maneger Operations. Training shall approve all modifications to the simulator facility. '

5.2 The Supervisor Simulator Maintenance has responsibility and authority for implementation and administration of this procedure.

5.3 An originator is responsible for the preparation of the simulator Modification Request form, providing a clear description of the proposed modification, 5 and supplying supporting documents or information.

1 i

PAGE 2 F4

FORM KGF-2 REV.1/87 NUMBER:

o(/ W81.F CREEK

' NUCLEAR OPERATING CORPORATION REVISION:

6.0 PROCEDURE 6.1 The simulator Modification Request (SMR) may be initiated by any WCNOC individual. Items may include, but are not limited to:

a. Observed differences in the response of simulator facility controls or indicators from actual plant controls or indicators.

b. Modifications to simulator facility hardware or software systems necessitated by an approved plant modification package,

c. Suggested additions or enhancements intended to increase simulator facility capabilities.

6.2 An originator shall complete an SMR form (Form KTF-880.1) and forward it to the Supervisor Simulator Maintenance.

6.2.1 If the SMR documents a response difference between

('_T the plant and the simulator, the originator should i,/ include in the description such items as plant operating conditions, related system equipment lineups and parameter trends, if availtble.

6.3 The Supervisor Simulator Maintenance shall assign an index number to the SMR for tracking.

6.4 .The Supervisor Simulator Maintenance may assign the SMR to other members of the simulator staff for a preliminary review or feasibility study.

6.5 Basad upon staff recommendations and personal i review, the Supervisor Simulator Maintenance may. l either recommend approval or disapproval of the SMR by the Manager Operations Training.

l 6.5.1 If the SMR is disapproved, or only approved for l partial implementation, the Supervisor Simulator l Maintenance shall include the reasons for this disposition in the comments section of the form.

6.6 The Supervisor Simulator Maintenance shall forward a copy of the SMR to the originator. The original shall be maintained in accordance with simulator section policies.

I PAGE 3OF4

un,. nur -4 n u . i,..

NUMBER 2 WfdiF CREEK

' NUCLEAR OPERATING CORPORATION REVISION:

7.0 FORMS Form KTF-880.1, " Wolf Creek Simulator Modification Request" 8.0 ATTACHMENTS Nono 9.0 RECORDS 9.1 Form KTF 880.1 is not a Quality Assurance Record.

9.2 Simulator Modification Request forms shall be maintained by the Simulator Section for a period of two years.

O

FORM KGF.1 REV. 4/89 o

V Wei.F CREEK

' NUCLEAR OPERATING CORPORATION PROCEDURE NO.: REVISION:

KP-882 2 l TITLE:

REQUEST FOR SIMULATOR USE REVISION

SUMMARY

O *" ' 'V

o a fYcb\Sa This procedure has been revised to reflect current titles End terminology Form KTF-882.1 has been reviewed, and changed.

iMF0DMLY

,, APPROVALS . , DATE APPROVALS DATE

?

Ei / t' l 7-97 L 2:==e W V00dfE

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' AUTHORIZATION:

en w DATE:

RELEASED: 004 hfb b PAGE 1 OF 4

- FORM KGF-2 REY.1/87 NUMBER:

Wei.F CREEK

' NUCLEAR OPERATING CORPORATION REVISION:

1.0 PURPOSE This procedure establishes the process by which Wolf Creek Nuclear Operating Corporation (WCNOC) individuals or groups outside of the Training Division request use of the Wolf Creek Generating Station (WCGS) Simulator.

2.0 SCOPE This procedure applies to personnel outside Training Division for the use of the WCGS Simulator for training, demonstration, operating procedure review or other approved purposes.

3.0 REFERENCES

KP-803, " Manager Operations Training Qualifications, Training and Responsibilities."

4.0 DEFINITIONS Terms and definitions used in this procedure may be found in the Training Division Procedure Manual Glossary.

5.0 RESPONSIBILITIES 5.1 Individuals or groups requiring use of the WCGS Simulator are responsible for submitting-a request-to the Training Division in accordance_ with this procedure.

5.2 The Manager Training is responsible -for the implementation of this procedure.

5.3 The Manager Operatio'ns Training has the responsibility for scheduling simulator time, including time for activities not related to established training programs.

O PAGE 2OF4

FORM KGF 2 REV.1/87 NUMBER:

'\_/-

(s )

W81F CREEK

' NUCLEAR OPERATING CORPORATION REVISION:

2 5.4 The Supervisor Simulator Maintenance is responsible for scheduling simulator time for hardware- and software maintenance work, simulator certification and acceptance test programs.

5.5 The Licensed Supervising Instructor (Simulator) is responsible for scheduling simulatorftime for.all training programs conducted, in whole or in part on the simulator, by Training Division personnel.

6.0 PROCEDURE 6.1 The requestor should complete Form KTF-882.1

" Simulator Use Request", providing as much detail as possible, including:

a. amount of time required

b. time frame and variation parameters

c. types of support personnel, simulator instructors or operators required.

O

's~ I Forward completed Form KTF-882.1 to the Manager 6.1.1 Operations Training for review and approval.

6.2 The Manager Operations Training will review the "Gimulator Use Request," Form KTF-882.1 and assign-

. a request number.

6.2.1 If the request is approved, the Manager Operations Training should forward a copy of Form KTF-882.1 to the requester and contact the requester to confirm details of the simulator use.

6.2.2 If disapproved, the Manager Operations Training _

should notify the requester and provide the reason for the disapproval.

6.3 In all cases,'the simulator.shall be operated under the direction of a member of the Operations Training Section.

i o

\m /

PAGE 3OF4 l

FORM KOF 2 REY.1/87 NUMBER:

W81F CREEK

' NUCLEAR OPERATING CORPORATION REYlS!ON:

O 6.3.1 Non-simulator personnel may-be permitted to serve as instructors or to occupy operating positions on the nimulator.

7.0 FORMS KTF-882.1 " Simulator Use Request Form" 8.O ATTACHMENTS None 9.0 RECORDS 9.1 Fom KTF-882.1 is a non QA Record.

9.2 Completed Simulator Use Requests (approved or disapproved) should be maintained by the Manager Operations Training.

O O

PAGE 4 OF 4

FORM KTF-882.1, REY. 6/90 oO Do e

.C); :gqcL01 %-

W 3 SIMULATOR USE REQUEST FORM ,

Request-No._ _ (to be completed by Simulator Section)

REQUESTOR Dates Name:

Position:-

Organization:.

i Phone: i,.

Amount of sin ,lator time requested:

Desired date(s) of simulator time:

Desired time of day of use: ,

Natur'e of requested use: Demonstration Training-Procedure-Verification /Walkthrough Other-(Specify - -)

Willsimulatorinstructors/operatorsberequired(otherth'antooperatetne

~

simulator? Yes- No If so, how many?-

Is this use intended:to satisfy any commitments? Yes _ _ No If so, list requirements:

'Is-documentation of the use necessary7 tes No If so, list extent:

FORM KGF 1 REV. 4/89 ,

O W6LF CREEK ' NUCLEAR OPERATING CORPORATION PROCEDURE NO.: RNSION: 2 l KP-883 mu:

SIMULATOR MODIFICATION PACKAGE

..sar. ,,

REVISION

SUMMARY

0" O g pds\ *3 Titles changed to correspond to Division o ganization ch[rt after recent reorganization.

Forms KTF-883.1 and 883.2, and been revised.

Forms KTF-883.3a, 883.3b, 883.3c, 883.3d and 883.e are deleted and replaced with Forms KTF-883.3, 883.4, 883.5, 883.6 and 883.7 respectively.

O-WF3 OWLY APPROVALS .

,- DATE APPROVALS DATE

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FORM KGF-2 REV.1/87 NUMBER:

W81sF CREEK ' NUCLEAR OPERATING CORPORATION REVISION:

1.0 PURPOSE 1.1 The purpose of the procedure is to establish a method of accurate and consistent flow of information to the Simulator Group to modify the WCGS Simulator because of plant upgrades, simulation modifications, and major hardware outages. --

1.2 This procedure also will provide documentation of simulator changes and major hardware corrective -

maintenance.

2.0 SCOPE 2.1 As changes occur in the plant, modifications to the WCGS Simulator may be required to maintain the simulator to model the plant.

2.2 Simulator Modification Requests (SMRs) are generated per procedure KP-880. A Shulator Modification Package (SMP) may be generated per SMR.

' 2.3 Plant Modification Requests (PMR) are processed per ADM 01-042 and reviewed per KP-884. PMRs, affecting the Simulator, generate a Simulator Modification Package.

2.4 The Simulator group receives PMRs through the Training IMPACT System, KP-844.

2.5 Minor hardware problems that require no "down-time"

.1 (such as, light bulbs, tightening of screws, etc.)

will be noted in the Simulator Minor Trouble Report (MTR) Log, covered in SPM-313.

3.0 REFERENCES

3.1 ADM 01-042, " Plant Modification Package" s.

O PAGE 2OF8 _

l

.m -__._.__._m..______ .-

FORM KGF<2 REY.1/87 NUMBER:

- wei.F CREEK

' NUCLEAR OPERATING CORPORATION REVISION:

3.2 KP-844, " Training IMPACT System" 3.3 KP-880, " Simulator Modification Request" 3.4 KP-884, "Staulator Review of Plant Modification Requests" 3.5 SPM-313, " Simulator Minor Trouble Report Log" 4.0 DEFINITIONS Terms and definitions used in this procedure may be found in the Training Division Procedura Manual Glossary.

5.0 RESPONSIBILITY 5.1 The Manager Operations Training has the overall responsibility for any change or modification to the WCGS Simulator.

n I i 5.2 The Supervisor Simulator Maintenance is responsible for the following

a. Maintaining the Simulator Modification Request Index

b. Determining the validity of Simulator Modification Requests

c. Providing feedback to the originator

d. Issuing the -SMP and assigning personnel -to perform the-work

e. Outlining the steps for testing of the completed modification

f. Closing out the SMP and notifying- applicable groups of the completion

g. Maintaining completed. SMPs on file and j accumulating any desired trend data

h. Reviewing Training IMPAC.T items for possible affect on the simulator

()

\_/

5.3 Hardware and software personnel are responsible for completion of SMPs as assigned and documenting the recuired information on the SMP.

FORM KGF-2 RO/.1/87 NUMBER 1 W$1.F CREEK NUCLEAR OPERATING CORPORATION REVISION:

5.4 Members of the simulator instructional group, assigned by the Supervisor Operations Training, are responsible for assisting in the testing of the completed modification.

6.0 PROCEDURE 6.1 REQUESTING MODIFICATION 6.1.1 Upon receipt of an SMR, the Supervisor Simulator Maintenance should assign the next number in the SMR index to the request and fill in the following information on the index sheet (form KTF-883.1):

a. Date

b. Originator (name and group or training impact number)

c. Valid request (yes or no)

d. SMP or MTR # issued (valid requests only) 6.1.2 The Supervisor Sinulator Maintenance should evaluate the request considering the following criteria

a. Do actual plant references (i.e. drawings, technical manuals, etc.) exist to support the request?

b. Is the request needed to upgrade the simulation system or is it a " nice to have" item?

c. Will the request be cost effective as far as effort expended versus training benefit realized?

d. Is the requested change within the scope of simulation?

6.1.3 A copy of the request, whether approved or disapproved, should be returned to the originator, if not a member of the simulator group. For approved requests, an SMP or MTR number should be referenced. For disapproved requests, reasons for disapproval should be stated.

PAGE 4OF8

FORM KGF 2 REV.1/87 NUMBER:

W$LF CREEKNUCLEAR OPERATING CORPORATION REVISION:

6.1.4 Responses to the Training IMPACT System shall be done by completing section II of the Training IMPACT Cover Sheet, form KTF-884.1.

6.2 SIMULATOR MODIFICATION PACKAGE ISSUE 6.2.1 Once the request has been validated, the Supervisor Simulator Maintenance should issue the SMP, 6.2.2 On the Simulator Modification Package Index (form KTF-883.2) the following information should be filled int

a. SMP number (next sequential number for the year, i.e.,88-001, etc.) ;

b. SMR number (Simulator Modification Ri1quiest that l ,

generated the SMP)

{

c. Originator of the SMR

d. Date issued (date of SMP issue)

O e. Title V 4 6.2.3 On the SMP cover page (form KTF-883.3) the Supervisor Simulator Maintee.nce will fill in the following informations

a. Title, SMP number, and date issued (from SMP index)

b. Reason for modification (for Plant Modification Package fill in number)

c. Type of modification and assignment (may be both types)

d. Brief description of modification 6.2.4 The Supervisor Simulator Maintenance will fill in the following information on page one (form KTF-883.4) of the SMPs

a. Description of problem and panel information-(if applicable)

b. References including the simulator modification request number PAGE S OF R !

FORM KGF.2 REY.1/87 NUMBER 3 Wdj) NUCLEAR OPERATING CORP REYlSION: _

6.2.5 If the modification is to hardware, the Supervisor Simulator Maintenance will issue form KTF-883.5.

6.2.6 If the modification is to software, the-Supervisor Simulator Maintenance will issue form KTF-883.6.

6.2.7 Modification testing requirements will be outlined on form KTF-883.7 of the package. The Supervisor Simulator Maintenance will approve testing. The purpose of modification testing is to ensure that the modification performs the purpose intended and to ensure that the modification does not adversely affect other areas of simulation.

6.2.8 The package is next routed for completion to the person assigned on the cover sheet.

6.3 WORKING THE SMP 6.3.1 For hardware packages, the Simulator Technician should describe the corrective actions taken, list any spare parts information, and sign for the completion of form KTF-883.6 of the SMP 6.3.2 For packages involving software changes, the Simulator Specialist should attach a sheet showing the old configuration and the new configuration with areas of change highlighted. Programs / files affected by the modification should also be listed and the Simulator Specialist should sign for making the change and for integrating the change into the system.

6.3.3 The assigned Simulator Specialist should. review any simulator data base files that may be affected by the software changes and attach any required change to the files to the SMP. The Simulator Specialist should list any file that requires revision on form KTF-883.6.

6.4 . TESTING 6.4.1 Once the work has been completed, the Supervisor

-Operator Training , should coordinate assignment of Instructional / Simulator personnel to perform testing in accordance with the acceptance criteria set forth on form KTF-883.7 of the SMP.

6.4.2 If the test is successful, the tester should sign for the test completion and return the package to the Supervisor Simulator Maintenance.

PAGE 6OF8

FORM KGF-2 REW 1/IW NUMBER;

. W81F CREEK

' NUCLEAR OPERATING CORPORATION REVISION:

6.4.3 If the test is unsuccessful, the tester will comment in the comment section why the test failed and return the package to the hardware / software person for rework.

6.4.4 If rework is required then KTF-883.5 and/or KTF-883.6 should., be renewed and the worker should complete the new page(s) as stated in sections above.

6.4.5 After rework the test section should then be performed again.

6.5 PACKAGE CLOSEOUT 6.5.1 Once the package has been completed, tested, and returned to the Supervisor Simulator Maintenance; the Supervisor Simulator Maintenance should closecut the SMP.

6.5.2 The Supervisor Simulator Maintenance should record all trend data in the appropriate section on the f- SPM cover sheet KTF-S83.3. This data is collected

(' g '

for future use such as reports, inventory control, etc.

6.5.3 Frior to close-out, the Supervisor Simulator Maintenance shall ensure that simulator data base files are updated.

6.5.4 The Supervisor Simulator Maintenance should check all pages of the SMP for completeness and check-off that item in the completion section of the cover page (KTF-883.3).

6.5.5 In the ccse of Plant Modification Packages, .the Supervisor Simulator Maintenance should notify the Results Engineering Group per ADM 01-042 of completion and check this action off on the cover sheet (if this action is not required then N/A should be entered).

6.5.6 The next step of the completion block is to update the SMP index (KTF-883.2). This is accomplished by completing the System IMPACT and Date Cleared columns as follows:

a. System IMPACT - This column will be filled in-only when computer system down-time, simulator:

()

N_/

system down-time, or training time is lost as indicated in the trend section. An example 7OF8 il,ti@U Oyl PAGE !thl L)ft!_

FORM KOF 2 REV.1/ft7 NUMBER; Ud>LF CREEK

' NUCLEAR OPERATING CORPORATlON REVISION:

would be that the computer system was down for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />; the entry would be C-3. (Use S for simulator system, and T for training time followed by the number of hours).

b. Date Cleared - Enter the date that the SMP was completed.

6.5.7 After the above-has been completed, the Supervisor Simulator Maintenance should sign for the completion of the SMP in the completion block and fill the computer SMP in sequential order.

6.5.8 After closing out an SMP generated from a Training IMPACT Item, the Supervisor Simulator Maintenance should complete section III of the Training IMPACT Cover Sheet, from KTF-844.1.

7.0 FORMS 7.1 Form KTF-883.1, Simulator Modification Request Index 7.2 Form KTF-883.2, Simulator Modification Package Index 7.3 Form KTF-883.3, simulator Modification Package (Cover Sheet) 7.4 Forp KTF-883.4, Simulator Modification Package 7.5 Form KTF-883.5, Simulator Modification Package 7.6 Form KTF-883.6, Simulator Modification Package 7.7 Form KTF-883.7 Jimulator Modification Package 8.0 ATTACHMENTS None-9.0 RECORDS 9.1 There are no QA records generated by this procedure.

9.2 Completed Simulator Modification Packages and Indices should be maintained by the Supervisor Simulator Maintenance for a minimum of four years.

PAGE 8OF8

FORM KTF-883.1, REV. 6/90 OMENP O .

(Cpd 3;

q

-YEAR 9 i#

PAGE SIMULATOR MODIFICATION REQUEST INDEX SMR f DATE ORIGINATOR - GROUP R T S o

o INFO ONLY .

FORM KTF-883.2, REY. 6/90 GMENP o o O a *%

G< _#

g 4qCU \

g YEAR

' PAGE SIMULATOR MODIFICATION PACKAGE INDEX SMR/ DATE SYSTEM DATE SMP i PMR # ORIGINATOR ISSUED TITLE IMPACT CLEARED O

lWF0 GWi_Y 1

FORM KTF-883.3 , REY. 6/90 oU*Htvy

- l-SIMULATOR MODIFICATION PACKAGE g o TITLE SMP i DATE ISSUED REASON FOR MODIFICATION:

1 I I I PMR ,

INSTRUCTIONAL ENHANCEMENT SIMULATION UPGRADE SOFTWARE ENHANCEMENT U HARDWARE CORRECTIVE MAINTENANCE OTHER(Specify)

TYPE OF MODIFICATION:

I I HARDWARE SOFTWARE ASSIGNED TO ASSIGNED TO BRIEF DESCRIPTION:

TREND DATA:

WORKER / HOURS USED HARDWARE DATA ONLY:

I I I I I I PARTS ON HAND YES NO PARTIAL COMPUTER SYSTEM DOWN TIME SIMULATOR SYSTEM DOWN TIME TRAINING TIME LOST COMPLETION: (To be completed by Supervisor Simulator Maintenance)

Page 2A completed Page 2B completed RESULTS ENGINEERING NOTIFIED SMP COMPLETED:

TESTINGCOMPLETED(Page3)

/

INDEX UPDATED Supervisor Simulator Maintenance B!F0 DNLY

-FORM KTF-883.4,- REY. 6/90 oO fo D ADb\ * .

SIMULATOR MODIFICATION PACKAGE i Page 1.

DESCRIPTION OF PR'0BLEM:

PANEL ITEM f

^

DEVICE TAG NAME O

REFERENCES:

,,R ,

IEF] :1Y o

FORM KTF-883.5, REV. G/90 0 e,OLA EN pO 9

n g gfoh\g+g o g f SIMULATOR MODIFICATION PACKAGE #

s Page 2A (Hardware)

DESCRIPTION OF PROBLEM / CORRECTIVE ACTIONS TAKEN:

MFD TILY r

b)

DOCUMENTATIONAFFECTED(attachproposedchanges):

ANNUNCIATOR SWITCHES CONTROLLERS METERS LIGHTS OTHER PARTS LIST:

PART MANUFACTURE'S PART i ON HAND MRf (if no)

YES NO COMPLETION:

('S DOCUMENTATION / WORKED /

(,/ Technician Date Technician Date i

FORM KTF-883.6, REV. 6/90 G#NP p o4 SIMUL.ATOR MODIFICATION PACKAGE i ppcW

}

Page 28 (Software).

CHANGES MADE TO SOFTWARE:

Attach sheet showing old configuration and .new configuration.

PROGRAMS / FILES EFFECTED:

DOCUMENTATION EFFECTED (Attach. proposed changes):

System File Handler File-Malfunction Description Test Procedure Other COMPLETION:

CHANGES.MADE /

Software Specialist Date.

CHANGES INTEGRATED ./

Software Specialist- Date DOCUMENTATION UPDATED: /

Software Specialist Date O

W 'YP o FORM KTF-883.7, REY. 6/90 90 0, 0

[3 a e S!HULATOR MODIFICATION PACKAGE i Page3(Test) <

ACCEPTANCE CRITERIA:

I l o

APPROVAL /

Supervisor Simulator Maintenance Date COMMENT:

q TEST COMPLETED /

g Tester Date

FORM K"F.1 REV. 4/89 LEA CP Tit CO PORATI PROCEDURE NO.: REVISION: y KP-084 l TITLE:

SIMULATOR REVIIN OF PLANT MODIFICATION REQUEST

_a*AEns REVISION

SUMMARY

0*~ 'O 9

e t 8

5

@th \ sr Titles changed to correspond to Division organization chart after recent reorganization.

Form KTF 884.1 has boon reviewed and revised.

o gEt BID .

APfROVALS . .DATE APPROVALS DATE

.*'L NI 0 A?/b $O4 a , f il - YC YA E//$ iY /.2 h0Si Adin A / V00$fE-ht!// a d,~G~To dTHORIZATION: # DATE:

O W 0.

f/ a/aleo RELEASED: OCA e,//388 V

PAGE 1 OF 4 )

L

FORM KOF.2 RO/.1/87 NUMBER 3 W$LF CREEK NUCLEAR OPERATING CORPORATION REVISION:

1.0 PURPOSE The purpose of the procedure is to establish the process of reviewing Plant Modification Requests (PMRs) for IMPACT on the WCGS Simulator.

2.0 SCOPE This procedure applies to improvements made to the site, plant, and plant systems to Adentify the changes that effect the simulator panels and simulation scope in order to maintain simulation as close as practical to plant operation.

3.0 REFERENCES

3.1 ADM 01-042, " Plant Modification Request Implementation" 3.2 KP-844, " Training IMPACT System" 3.3 KP-883, " Simulator Modification Package" 4.0 QEFINITIONE Terms and abbreviations used in this procedure may be found in the Training Division Procedure Manual Glossary.

5.0 RESPONSIBILITY 5.1 The Supervisor Simulator Maintenance is responsible for maintaining the PMR Review sheets; assigning a Simulator Modification Package (SMP) if work on Simulator Hardware / Software is required; and final review of the PMR Review sheets.

5.2 The Simulator Technicians / Specialists personnel, as directed by the Supervisor Simulator Maintenance, are responsible for the initial review of PMRs.

O PAGE 2OF4

FORM KOF-2 REV.1/87 NUMBER:

T W@&LF CREEK

' NUCLEAR OPERATING CORPORATION REVISION:

(d . ..

6.0 PROCEDURE 6.1 Upon receipt of PMRs by the Simulator group, and in accordance with KP-844, Training IMPACT system, the PMR will be reviewed for any effect on the simulator panels /models.

6.2 The reviewer shall use the PMR Review form (KTF-884.1) and record the following information in the spaces provided.

6.2.1 PMR Title - title from PMR cover sheet 6.2.2 PMR Number - the number assigned on the PMR cover sheet 6.2.3 Date Issued - the date the PMR was issued from the PMR cover sheet -

6.2.4 Revision Date - the date of the latest revision to the PMR found on the PMR cover sheet 6.2.5 Revision Number - the current revision of the PMR from the PMR cover sheet 6.2.6 Data Received - the date received for review, normally the date of review.

6.2.7 Modification Description - this section should be completed after the PMR has been reviewed. It should include a basic description stating the goal of the PMR and what system / components it will effect.

6.2.8 Simult. tor Ef f ected - Based 'on *;he knowledge of the rrviewer; correspondence with other members of the group, and review of existing simulator documentation, the reviewer will make a determination whether the simulator is/is not effected. An explanation should be written explaining why the simulation system is/is not affected.

t 6 *>.9 Reviewer /Date - the reviewer should sign and date the review of the PMR. At this time the reviewer should also sign for any review of the PMR covered by other tracking systems whether departmental or site related. If the PMR does effect the Simulation System, the reviewer should request a copy of the PMR fL r the Training Library.

- S O, 4 gg \iA'i

.______.-----m_____._ _ , . _ . . _ _ _ _ _ _ . m.. _ . . .

- i - - - -- ' I

FORM KOF.2 REY.1/87 .

NUMBER:

W$1F CREEK NUCLEAR OPERATING CORPORATION REVISION: I 6.2.10 Supervisor Review /Date - The Supervisor Simulator Maintenance should review and sign the PMR review sheet. If the simulator is affected he should issue a simulator Modification Package per KP-883, and record the SMP number in the space provided. A copy of the PMR should be attached to the Simulator Modification Package.

6 2.10.1 The Supervisor Simulator Maintenance or his designee (usually the reviewer), should complete Section II of the Training IMPACT Cover Sheet, form KTF-844.1, and return it to the designated clerk per KP-844.

6.2.11 Upon completion and incorporation of the SMP, the Supervisor Simulator Maintenance should complete Section III of the Training IMPACT Cover Sheet.

6.3 The PMR review sheets will be maintained by PMR number /Rev number in a PMR notebook by the Supervisor Simulator Maintenance or his designee.

7.0 FORMS KTF-884.1 - ' Wolf Creek Simulator Plant Modification Package Review for Simulator IMPACT" 8.0 ATTACHMENT None 9.0 EECORDS 9.1 There are no CA records generated by this procedure. ,

9.2 Completed PMR review sheets should be maintained by the Supervisor Simulator Maintenance for a minimum of four years.

O PAGE 4 OF 4

FORM KTF-864.1, REY. 6/90 0 ,j.v Enf,0

.O I

MOW ! i:: l s 1 WOLF CREEK SIMULATOR -

PLANT MODIFICATION PACKAGE REVIEW FOR SIMULATOR IWACT !

PMR

Title:

PMR f

Date Issued: Rev. Date Rev.

Date Received: ,

Modificatlon Deb eipt M >

r O

Simulator Effected? Yes No If Simulator Affected--

SMP f Assigned h

/ /

Reviewer Date Supervisor Simulator Date Maintenance 5

L...+. ,....~.c...--,-....w,b,.ww,,,,,.-L.w-~-4 'we..w. -----i.-*--.#rw.-,~..p-'.e._,m'i' a-W r 7 -va--ch -5< e w. w-r r en-- y------

FORM KOF.1 REV. 4/39 W4$1.F CREEK NUCLEAR OPERATING CORPORATION PROCEDURE NO. REVISIOW KP-891 4 l TITLE:

SIMULATOR CERTIFICATION REYlSION

SUMMARY

guMl!N7 O O O TF1 Die I ^

E r-Forms KTF-891.1, KTF-891.2, KTF-891.3, KTF-091.4, KTF-891.5.

KTF-891.6 and KTF-091.7 have been reviewed and no changes are necessary.

O Commitment Paragraph 3.11 15( M* d L4 l APPROVALS DATE APPROVALS DATE

~

babb. Y IC r7 90 ~7&[ W/ r/fo

D ~ ... d r M sw i, k w??rff h d+ neo

<M

/ /~7 9

$THORIZATION: DATE:

O M"# X# '" # @ ""'e>s"o ' ~~'o s PAGE 3 0F 10

FORM KOF.2__E2V.1/87 NUMBER:

W$LF CREEK NUCLEAR OPERATING CORPORATION RENISION:

4 1.0 Pu rposo 1.1 This proceduro establishes the methods used to cortify and maintain the WCGS Simulator as a certified NRC Examination Facility.

1.2 Additionally, this proceduro establishest

a. required simulator tests

b. periodicity of required testing

c. maintenance of test results

d. maintonanco of simulator data base 2.0 SCOPE 2.1 This proceduro supports the requirements established for the operating portion of the NRC License Operator examination which must be given on a cortiflod, plant-referenced simulator (WCGS Simulator) por 10 CFR 55.45(b).

2.2 This proceduro also applion to auditing of simulator facilities por NUREG-1250.

O

3.0 REFERENCES

3.1 10 CFR 55, " Operators License" 3.2 NUREG-1258, " Evaluation Proceduro for Simulator Facilition Certified Under 10CFR55" 3.3 Rogulator) .de 1.149, April, 87, "Nuclonr Powor Plant Simulation Facilition For Uso In Operator License Examinotion" 3.4 ANSI /ANS-3.5-1905, " Nuclear Power Plant Simulators For Use In Operator Training" 3.5 Form NRC-474, ' Simulator Cortification" O

PAGE 2 OF 10

FORM KOF.2 REV.1/87 NUMBER:

[

v W41) NUCLEAR OPERATING C REVISION:

3.6 KGP-1261,

Transmittals to the NRC and KDHE"

, 3.7 KP-844,

Training IMPACT System" 3.8 KP-880, " Simulator Modification Requests" 3.9 KP-883, " Simulator Modification Packages" 3.10 KP-884, " Simulator Review of PMRs" 3.11 WM 90-0091, dated April 27, 1990 from B. D. Withers, WCNOC to NRC, Simulator Certification Request for Additional Information.

4.0 plFINITIONE 4.1 Best Estimate - Referenced plant response data based on engineering evaluation or operational assessments.

4.2 Empirical Data - Data used when a best estimate is needed for simulator response. This data may include USAR, LERs, SOERs, OARS etc.

4.3 Factory Data - Generic SNUPPs data in the simulator that is not necessarily plant specific.

4.4 llandler Files - Software programs that operate similar types of components and includes

a. on-line simplified electrical diagrams

b. logic diagrams

c. list of handler operated components

d. list of calls (triggers that call the handler) 4.5 Malfunction - Simulated failure or degradation in perfomance of plant equipment.

4.6 Malfunction Description - Cause and effect situations that are used in simulator training.

4.7 Plant Operational Data - Data .used to verify simulator response as compared to plant operations / transients which may include

a. start up test procedures d

PAGE 3 OF 10 h

(

FORM KGF12 REV.1/87 NUMBER:

~

W$LF CREEKNUCLEAR OPERATING CORPORATION REVISION:

b. plant trip reports

c. operational logs.

4.8 Real Time - Simulation of dynamic performance in the same time based relationehips, sequences, durations, rates and accelerations as the dynamic performance of the referenced plant, 4.9 Reference Plant - The specific nuclear power plant from which the simulator control room configuration, system control arrangement, and simulator design data in derived, i.e., Wolf Creek Nuclear Generating Station.

l (3.11) 4.10 Simulator Fidelity Review Board (SFRB) - A panel consisting of the Manager Operations Training, Supervisor Simulator Maintenance, Supervisor Operator Training , Licensed Supervising Instructor (Simulator), and an active SRO. The board will review simulator and plant differences for their impact on training, as well as related simulator concerns.

4.11 Simulator Data Base - A compilation of various data used to accurately model the simulator. The data base includes controlled plant information as well as simulator specific documents that show what is actually modeled. The data base may be used to determine if plant changes (via PMR) affect the simulator system.

4.12 System Files - A gathering point for information about a particular system, and may includes

a. a simplified diagram of the system

b. "information'only" copy of the system description

c. system legend sheets

d. valve collection data sheets

e. equipment data such as pumps, heat exchangers, tanks, etc.

f. usage sheet to document changes to the system file i 9 PAGE 4 OF 10

FORM K"F.2 REV.1/87 NUMBER: .

L (

W4$1.F CREEK NUCLEAR OPERATING CORPORATION HEVISION:

4.13 Other terms and abbreviations used in this procedure may be found in the Training Division Procedure Manual Glossary.

5.0 RESPONSIBILITIES 5.1 The Manager Training is responsible for implementation of this procedure and approval of all applicable forms.

5.2 The Manager Operations Training is responsible for

implomontation of this proceduro and approval of all applicable forms.

5.3 The Supervisor Simulator Maintenance is responsible for scheduling of simulator certification testing, and for maintaining all simulator certification data and test results.

5.3.1 The Supervisor Simulator Maintenance is responsible for ensuring that appropriate data from the Training IMPACT System, KP-844, is incorporated into the Simulator Data Base.

5.3.2 The Supervisor Simulator Maintenance will chair the Siraulator Fidelity Review Board and is responsible for determining when the SPRB meets and the scheduling of the SFRB meetings.

5.3.3 The Simulator Fidolity Review Board is responsible for final revicw and acceptance of all certification testing results.

5.3.4 The Supervisor Simulator Maintenance, is assisted by the WCNOC Simulator Group in gathering data for use in simulator certification.

5.4 Supervisor Operator Training is responsible for promoting feedback from the Simulator Instructional staff and other users of the Simulator. The feedback method is described in KP-880, " Simulator Modification Roquest."

5.4.1 The Supervisor Operator Training is also responsible for having his instructional staff assist with Certification testing.

5 PAGE 5 OF 10

_am

FORM KGF.2 MEV.1/87 NUMBER:

W$1.F CREEKNUCLEAR OPERATING CORPORATION REVISION:

5.5 The simulator group, which includes software and hardware personnel, is responsible for maintaining the simulator hardware and software and may include incorporating:

a. Approved modifications from feedback

b. plant modifications which affect simulator systems

c. results of simulator testing 5.5.1 The Simulator group will also be responsible l'or maintaining:

a. periodic pictures

b. simulator data collection forms

c. simulator tests [ performed with assistance from the Operator TrainLng Group).

l (3.11) 6.0 PROCEDURE j 6.1 SIMULATOR HARDWARE FIDELITY 6.1.1 Simulator hardware fidelity checks shall be conducted to ensure that the Simulator control board panels match the plant main control board panels.

6.1.2 Hardwaro fidelity shall be maintained by using, as appropriates a, periodic pictures

b. simulator item to Main Control Board (MCB) item comparison

c. simulator item to controlled plant drawing / document item comparison

d. plant modification request (PMR) review

o. user feedback O

PAGE 6 OF 10

FORM KGF 2 REY. Its?

NUMBER:

W$LF CREEK NUCLEAR OPERATING CORPORATION REVISION:

6.1.2.1 Periodic pictures are taken annually, at a minimum, of the simulator and/or MCD. The pictures are used for resolving applicable hardware fidelity concerns.

6.1.2.2 Simulator item to MCB item comparison shall be completed if a hardware item has been changed because of a PMR or a simulator item has been upgraded to meet an MCB item. The information from the comparison of the simulator item to the MCB item shall be recorded on a data collection form.

6.1.2.3 Simulator item to controlled plant drawing shall be accomplished by comparing simulator items against the applicable drawing. Differences shall be noted on the data collection form.

6.1.2.4 PMRs shall be reviewed for their effect on the Simulator per KP-884, " Simulator Review of PHRs." If the PMR review requires the simulator hardware or software to be changed, a simulator modification package is initiated per KP-883, " Simulator Modification Packages (SMP)." Upon completion of the SMP, a data collection form, approved by the Manager g Training, shall be completed to show that no differences exist between the simulator and MCB.

6.1.2.5 User feedback, per KP-880, " Simulator Modification Request," may identify hardware fidelity problems.

One or more of the methods listed in 6.1.2.1 through 6.1.2.4 may be used to verify the fidelity problem.

6.1.3 Hardware fidelity differences may be permitted when they have no detrimental impact on training.

6.1.3.1 Simulator hardware fidelity differences shall be reviewed by the SFRB. The SFRB will determine if the difference has any direct impact on training. If the difference has no direct impact on training, the item will be categorized as " Compares with minor differences -- no impact on trainings on the appropriate data collection form. If the SFRB determines that the item shall be corrected, and SMP will be issued and the " Requires simulator modification: block will be checked on the applicable data collection form. Once the -item has been corrected a new data collection form will be completed replacing the old form.

_w PAGE 7 OF 10

FORM KOF 2 HEV.1/87 NUMSER:

F CREEK NUCLEAR OPERATING CORPORATION REVISION: .

6.2 SIMULATOR SOFTWARE FIDELITY 6.2.1 Major plant modifications are reviewed per KP-884

" Simulator Review of Plant Modification Request." If the plant change is minimal and the change may have little effect on the operation of the simulator, the proposed change should be presented to the SFRB for recommendation. The SFRB should be briefed at all SFRB meetings on the current changes being made to the Simulator that are prompted by plant changes.

6.2.2 It may be desirable to incorporate plant / industry events into the simulator. The Licensed Supervising Instructor (Simulator) and the Supervisor Operator Training should review these events via KP-044

" Training IMPACT System" and submit a simulator nodification request per KP-880.

6.2.3 The SFRB should discuss any model enhancement considerations that may be required to support future training needs.

6.2.4 The SFRB should be made aware of any changes in the operating parameters of the simulation computer.

These parameters include but are not limited to:

Simulator Real-Time, Spare Duty Cycle Time, and Model Run Frequencies. They should make recommendations to management if any of these parameters are approaching limits or are excooded.

6.3 SIMULATOR TESTING 6.3.1 Simulator testing is required per Reg Guide 1.149 to ensure the simulator responds based on operational experience, actual plant data, or best estimate empirical data. Actual plant data should be used whenever p(saible. Data from other plants may be used if the plant has similar operating characteristics, 6.3.2 In instances where real data does not exist, empirical data or data from other simulators may be used for best estimate simulation response.

PAGE 8 OF 10

FORM KGF 2 REY.1/87

. NUMBER:

O W4lM.F CREEK NUCLEAR OPERATING CORPORATION REVISION:

0

6.3.3 TYPES OF TESTS 6.3.3.1 The four types of certification tests ares

a. steady state tests performed at power levels that correspond to the plants calorimetric heat balances

b. transient tests performed at conditions stated in ANSI 3.5, 1985

c. Selected malfunction tests stated in ANSI 3.5, 1985

d. Simulator Real-Time testing 6.4 TEST SCHEDULING 6.4.1 Simulator tests shall be performed prior to simulator certification (Forn NRC-474). After certification is complete, approximately 25% of the tests will be performed each year so that all tests are completed in a four year cycle; all other tests'will be performed annually.

i

\ G.4.2 Testa may be performed earlier than scheduled in conjunction with work done on a component or system.

In this case, the SMP should state that the teet requirements are that the Simulator certification Test (SCT) be performed.

6.4.3 Every four years, on the anniversary of certification a written report should be submitted to'the NRC, that identifies any uncorrected tent failures, a plan to correct failures, a test schedule for the next four-year cycle, and a summary of any major modifications since the last report.

6.5 SIMULATOR DATA BASE 6.5.1 The Simulator Data Base is controlled by the Supervisor Simulator Maintenance and may includes

a. factory data

b. controlled drawings and documents c., system fL.es t '

( k .

PAGE 9 OF 10 \\o "

FORM KOF 2 REV.1/87 NUMBER: '

~

W$LF CREEK NUCLEAR OPERATING CORPORATION REVISION:

d. handler files

o. malfunction descriptions

f. plant oporational data

g. ompirical data 7.0 ATTACHMENTS None 8.0 FORMS 8.1 Forms KTF-891.1, " Indicating Light Data Collection Form" 8.2 KTF-891.2, " Meter and Digital Data Collection Form" 8.3 KTF-891.3, " Control Switch Data Collection Form" 8.4 KTF-891.4, " Recorder Data Collection Form" 8.5 KTF-891.5, " Annunciator Data Collection Form" 8.6 KTF-891.6, " Controller Data Collection Form" 8.7 KTF-891.7, " Status Panel Discrepancy Sheet" 9.0 RECORDS 9.1 There are no QA rscorde generated as a result of this procedure.

9.2 The Simulator Data Base and other recorde generated by this procedure shall be maintained under direct control by Supervisor Simulator Maintenance or his designeo.

O PAGE 10 OF 10 l

l

KTF-COi.i Rov. 3/CQ OLF CREEK SIMULATOR (7 Indicating Light Data O O V Collection Form ,0 O

gj O Plant Simuiston O e

Tag Name _.

Item #

T y r.s e SPECIAL FEATURES O

SKETCH ,

NOTES

)

a '- "" a~a-

, ; 3c.m..r.. -itm ,1.nt 0 Eri;;:ct*:" tA"in,R&"" ""- comoi s.d w o. .

m simusator modification

]Amavires ,

Supv, Simulator date

KTF-ODS.D Rov. 3/C0 j W O L. F CREE < S :: M U __ A T O R

/~'I Meter G Digital Data IV Collection Form gOME/v7 no upt,I C o_

Plant (f O

m( tor n

F r Tag b'" m e i

Item #

Type Parameter Units

/ Range ,

Divisions Zone Bending Legends .

3

} ] Compares with plant n%\\ ,

] R**i"E*ot *i" U"f"iES " *"*" * * .hoMi'We'uy eat.

] Requires simuistor modification V Supv. Simulator date

KTF-COS.3 A3v. 3/CD W O __F CREEK SIMU._ATOR s Control Switch Data OOMNPo Collection Form O g0 4 Plant Simulator O t

Tag Name Item #

Type Function / ,

Special Features O

Sketch

(

i

~

) ]Compar'em with plant.

l O E 8** *""* e t *!" #"?"in s """""* *

Compiled by date

.. Requires simulator moclification

__ SMP#. /

/ Supv. Simulator date l

l

75tW""CPEEK SIMULATOP '

v. '?Ny

U Recorder Data e, f S, i Collection Form

///[v Plant Simuistor Tag Name Item #

Type Pen Assign-ment Label Units Range Divisions Zone -

Bending Compares with plant m!!ct o $ni Compiled by date Ascuires simuistor modification ,g,g ,

gQ$b knt. dos.

w.

1 ,

KTF-CD1.5 nov. 3/00 WO_ CREE < SIMU_ATOR Annunciator Oata CMNNI Collection Form O 0 j 4 Plant $'simuistor h i Window #

g dngraving Color Demarcation O

gyg BTM a ' r ac- =~a-

> itm 1.m.

o como. .. .

] E *a;;;;:ot*:" mmR&" " "=" comni1.. ox ..t.

simulator modific. tion

]ReQuiren ,

O -

em, . e,mm1.to- .. ..

e KTF-031.O Asv. 3/C0

. WOLF CPEEK Controller SIMULAT,OR CMME4 f) Data o0 Co3lection Form O {[g 9 Plant 3 Simulator p t l Tag Name i

Item #

T Ype Meter Range

\

Input Range Indicating Light Information I

Compares with plant n $mpact on $ni Compiled by cate g- s, Requires simulator modification SMP*

Supv. Simulator ste

. A E$ k i.

0Y**

KTF-COi.7 rov 3/CD W O __F CREEK S :: lv U _. A T O R f[ Status Panel Discrepancy Sh e $ MEN Item # Panel Name f dI/

i ) Reference Dwg# She[t of All lettering, demarcation, Coloring. and general appearance of this item are the same for the simulator. Plant, and applicable goCumentation with the exception of the following windows:

}

Window Plant Simulator Deaument -

O I

l Compares with plant *

/

$ni n $ ac Compiled by date

] Requires simulator % ,

U ""a*

modification t.@,g bp .

gQ simuistor d.t.

/ WCGS INSTRUCTOR OPERATING SYSTEM

(

INDEX SECTION DESCRIPTION 1 Instructor CRT and Keyboard 2 initialization Process and Features 3 Back-up Features 4 Malfunctions 5 Local Operator Actions 6 Annunciator / Override 7 Plant Parameters 8 System Monitoring 9 Main Control Board Trend Recorders 10 (Reserved) 11 (Reserved) 12 Digital Displays 13 Writing Snapshots 14 Simulation Speed 15 Computer Information 16 Remote Control Operation 17 Stimulated Plant Computer Operation 18 Display Features 19 Diagnostics V 20 Miscellaneous Information

O WCGS SIMULATOR G

SECTION 1 INSTRUCTOR CRT AND KEYBOARD INSTitUCTOR CRT AND KEYi10ARD The instructor system is controlled through a standard keyboard, and also through a special set of 89 functic ' 4cys. These keys are defined as follows:

SYSTEM KEYS dedicated keys used to list options associated within broad systems uhile operating with certain MODE keys active.

MODE KEYS there are five modes in which the SYSTEM keys have dedicated input. These modes are:

1. MALF Malfunction section.

2. LOA Local Operation Action.

3. PLANT PARAM Plant Parameter manipulation.

4. ANNUN - Alarm failures

5. OVERRIDE - Control board failures.

(' MALFUNCTION SET KEYS - there are four keys used in conjunction with malfunctions, local operator actions (LOA), plant parameters and control board failures to set up function conditions,

l. ACTIVATE - when the conditions have been estab!!shed within MODE, the activate key transmit the information to the program start a malfunction; LOA, ANNUN, or OVERRIDE - when pressed from a " COMMAND 7" line without being inside a specific malfunction or ANNUN, or OVERRIDE, the activate key will produce a list of malfunctions, ANNUN's, or OVERRIDE that are "acth c", ' time delay", or

' conditional".

2. CLEAR - used only with an "actht", 'in time delay" or ' conditional" malfunction to remove the malfunction input from the computer.

3. SET used only with ' clear" malfunctions to allow input of data parameters to the malfunction controls.

4. COFTTINUE used in any MODE to exi! frova a specific malfunction, LOA, ANNUN or OVE'lRIDE without changing the stated of the LOA, ANNUN, OVERRIDE or malfunction.

FUNCTION KEYS SIMSPEED - The systetn allows the capability of changing the simulation speed through changing the value of the variable SIMSPEED.

SWITCH INSTRUCTOR CONSOLE This key toggles the instructor console control betwren the instructor booth CRT and the portable instructor console on the simulator floor. File fx

'CONSWAP' needs to be filed to activate this key and allow switching to the portable instructor

. console.

MQlifP ON/OFF (MONITOR CONTROL PANEL $b De instructor system contains a feature to monitor the control panels. His monitoring acts on all digital inputs. This feature can be useful for testing the 1/0 system and also for the instructors to casily see what actions the student is taking. This key monitoring of control panels to be disabled STOPMON.

hiQNfE Can be in effect whethr the system is running or frozen. When using MONCP normal monitoring is halted. To stop MONCP and resume normal monitoring depress tie MONSIM key.

DI AO This key puts the instructor system in the diagnostic mode. It cannot be entered unless the simulator is frozen.

SHAP_ID DISPLAY To find out w hich snaps are currently on disc, the SNAP ID DISPLAY special function key will display the current snaps along with a brief description.

INIT -Initialization conditions have been established to allow the user to start a run from a variety of core-ages and plant conditions. To select an initialization condition the INIT key is used, which causes basicallyjust a read of a specific snapshot, constant, and cere-age area.

IIACKUE - ne simulator system automatically takes snapshots every 5 minutes and 6 of these backup snapshots are retained (i.e., a snap is retained for 30 minutes). This allows the user to

back up" the simulator at 5 minute intervals up to a maximum of 30 minutes. When the backup key is depressed, the CRT displays a list of the 13ACKP snaps and how old they are.

ANNUN llORN ON/OFF This key toggles a!! control room audible alarms off or on.

ANNUN ACK This key acknowledges any existing alarm on the control board.

l?T ON/OFF (MON) This special function key is also a toggle on/off switch. Using this option will cause monitoring to also occur on the line printer, at the same frequency that is uppears on the CRT. When disab!!ng this key, PRTOFF will appear on the CRT.

MONITOR ON/OFF (MQNSIM) This special function key also toggles. Using this option will cause all commands input to the CRT to be output on the line printer. When disabling, PRT OFF will appear on the CRT.

MONITOR ON/OFF (MONSIM) The MONSIM special function key is a dual purpose button.

Depressing it once activates the monitoring, depressing it again disables monitoring.

DISPLAY (DIS) - This key is used to show the value/ status of variables, hiQNY - His key is used to insert variables into a monitoring circuit which displays the updated value of the variable continuously on the upper portion of the instructor CRT. A maximum of 63 variables can be rnonitored at one time.

RUN - RUN causes the simulation to run.

ERZ FRZ causes a simulation freeze (i.e., the system stops). Note that freeze does not cancel variable or control panel monitoring (i.e., a subsequent RUN command will cause monitoring to resume, and control panel monitoring can occur during the freeze).

(m REPEAT . The REPEAT key repeats the last command entered.

DifER All commands (ucept for some of the above special function key commands) are executed by the DilT.R key.

EM11. Dual purpose key: Press once sets logical true to enabic programs to send thformation to RM11 panel. Depress key a second time sets logical false.

SET DIAG . Used in cordunction with diagnostic key, will set all panels to any one of the diagnostic tests.

DZADD Displays the absolute llex address of a name or program relative address.

DIS ASM Use for testing of software, to disassemble programs, DZW/ DAW.DZW.Displaylicx word.

DAW. Display Alpha word.

DIJI/DAll DZil Display Hex half word.

DAll . Display Alpha half word.

DIJ)!QAll.DZB .Displayllex byte. ,

DAD . Display Alpha byte.

CRW/CIW . CRW . Compute real word.

CIW . Compute integer word.

REMOTE . Allows operator to set up the twelve (12) function on the remote control device.

MCRT/MPRT . MCRT allows operator to change monitoring frequency, e.g. MCRT 5 (monitor updates every 5 seconds).

MPRT allows operator to select monitoring frequency of the printer. e g. MPRT 1(printer will print every scoond).

KEY TEST Mode which will reassign the function of(lower middle row of keys) to a toggic function for up to 15 assigned logicals, LQQ Menu to assign and/or display what is assigned to the various key test keys.

USEM/S AVEM USEM (filename) calls a previously save monitoring file.

SAVEM (filename) will cause the monitoring points in use to be saved into a file that has been created by software. SAVEM will replace whatever is in the file with the latest information.

BLINKINIT . This key is a dual purpose key. Depressing it once enables BLINKINIT (in INIT section), depressing it second time turns DLINKINIT oft.

l WRSNAP . (SNAP /WR ID) Depressing this key will call a subroutine that will allow)cu to l:

E change the description of the 'IC" when you write a snap.

IJII . Allows a file to be displayed without activating it.

l

ElLE- Calls a file and activates it.

O~ JMME Allows operator to 5ter a ramp command.

QlSRP Will display value and description of all elements of an array.

DELM Used to delete monitoritig points.

SW NMI'TS Used to limit numter of monitoring points.

BEPLAY This key will cause the replay menu to be displayed.

LQS.S Displays Limits of Simulation System parameters, limits, and acknowledge loss alarms.

~a A

U O

WCGS SIMULATOR SECTION 10 8-PEN INSTRUCTOR RECORDERS This section is covered under the E0P Operation procedure.

O O

WCGS SIMULATOR SECTION 11 SYSTEM INDEX DISPLAYS Section covered under new BOP Operation rocedure.

O o

V

4 O wccs sluut^ron SECTION 15 COMPUTER INFORMATION NOTE: Do not clear memory or reboot either computer without checking with users on both computers.

PEBOOT PROCEDURE 'A' or 'B' Computer

1. If you have anything othcr than back slashes on screen enter "@%P", and RETURN.

2. At double back slashes enter "IIALT", and RETURN, to halt the computer.

3. At double back slashes enter "CLE", and RETURN, to clear memory.

4. At doub!c back slashes enter "RST", and RETURN, to clear memory,

5. Enter "lPL=802", for Simulator, or "lP17800", for Development, and RETURN.'

6 A prompt will respond with 'Do you wish to use 'MPX-SIM* default image (Y/N)?'

Enter "Y", for Computer 'A', enter 'N'. for Computer 'B', and RETURN.

7. Enter date and military time. Fonnat is Mit/DD/)7 0000.

8. Enter "@l@A",77 will appear on the screen. Enter "ACTI RMEMINT", and RETURN, to activate reflective memory.

9. Enter "@@A",77 will appear on screen. Enter "ACTI SIM", and RETURN, to activate .('A Computer Only)

> NOTE: After ensuring that the Stimulated plant computer system is running on the VAX Computer (See Sectino 17) continue to step 10.

- 10. Enter "@gA", ?? will appear on screen. Enter "ACTI NPISSIM" , and RETURN, to activate.

('B' Computer Only),

o

POWERING UP SYSTEM IMlY)RTANTNOTES NOTE 1: If in doubt as to what breakers on Panel P-7 should be closed, close all of them. It will not hurt to have the spare breakers closed.

NOTE 2: When Closing breakers do so one at a time, not all at once. This will keep the power surEe down to a minimum.

NOTE 3: When activating the simulator for the first time after powering up, it is important to know the EFSAS status panel and the partial trip status panel will not light in diag until after you have initiated the first time.

A. MECH ANICAL EOUJPMENT ROOM

1. Make sure T 2 is completely open.

2. Close T-2.

B. BRE AKER PANEL P-7 O 1. Close main breaker.

2. Close every individual breaker. " NOTE 1 & 2 "

C. COMPUTER ROOM

1. Go to Procedure " Purge the Disk Drives - When Powering Up" _

2. Close computer breakers. " NOTE 2"

3. Close tape drise breakers. " NOTE 2"

4. Power front of computers up.

5. Turn on line printer.

6. Turn on terminals.

7. Turn on CRT's on simulator floor & instructor's booth.

When purge mode is completed.

8. Boot computers.

9. Activate simulator. " NOTE 3" O

.w

(~' POWER UP AND POWER DOWN PROCESS POWERING DOWN SYSTEM NOTE 1: When powering up or down the disk drives it is very important to push the start switch with a dehberate move. If this is down with a stutter or more than one push, allow the disk drives to power all the way down or up, but do not attempt to push the start button again until the drives have completed their nornul course. Then you may try pushing the start button again if you need to do so.

NOTE 2: Disk Drive Breakers are located on the back of the drives.

A. COMPUTER ROOM

1. Halt both computers.

2. Turn off disk drives from front panel. " NOTE 1"

3. Turn oft tape drives from front panel.s.

4. Turn off the computers from front panels.

5. Open computer breakers.

gO' 6. Open tape drives breakers.

7. Open disk drives breakers. " NOTE 2"

8. Turn o!Tline printers.

9. Turn off terminals.

10. Turn oft CRT's on simulator floor and instructors booth.

B. BREAKER PANEL P-7

1. Open every individual breaker in P-7.

2. Open main breaker in P-7.

C. MECHANICAL EOUIPMENT ROOM

1. Open breaker T 2.

,r

> )d

q WCGS SIMULATOR SECTION 17 STIMULATED PLANT COMPUTER OPER ATION POWERING-UP AND BOOTTNG TIIE VAX 3800

1. Turn the orange power switch on the front of the system cabinet to the 'l' position.

The rocker switch should light. If not turn the switch back'to the 'O' position and check the breaker panel 'P-7' to ensure all breakers are closed, then begin again.

2. When the green ready lights are on, the system is ready to boot. If the computer does -

not begin an autostart sequence, a 'B'should be entered at the '>>>' prompt. If no prompt is visible, ensure the monitor is on, then push the ' RESET /RUN' button.' This

should start the system start-up routines. The start-up may last 10 minutes or more.

Turn on VAX tenninals.

NOTE: If possible, do not use the system console to sign on to the VAX for SIMULATOR operation.

3. Strike the ' RETURN' key until the system prompts you for a user name. Enter

' SIMULATOR' and then the password 'SIM'. A menu will come up with the-following choices:

1] Start SMS 2] Stop SMS 3] Halt Simulator CPU (WCSI A) 4] TTEST 5] Print TTEST. LOG 6] Restart SMFEPZ (Front End Processor)-

7] Check to see in SMFEPZis running S] STOP/ START ALARM TYPER 9] Exit without taking any action

4. . To start the Simulator Monitoring System select choice 'I'. At this point the SMS begins initiation. It may be 10 minutes to completely finish.

5. After SMFEPZ is running, NPISSIM may be activated on the Simulator Computer.

Use Option #7 to check for the SMFEPZ process.-

6. The ' Simulator' user will normally remain signed on.

A

^\ ) POWERING-DOWN TIIE VAX 3800

1) Press the shift key to reactivate display. If the menu is displayed go to step 3, otherwise sign on per Step 2.

2) Stike the ' RETURN' key until the system prompts you for a user name. Enter

' SIMULATOR' and then the password 'SIM'. A menu will come up with the following choices:

1] Start SMS 2] Stop SMS 3] Halt Simulator CPU (WCSI A) 4] TTEST 5] Print TTEST. LOG 6] Restart SMFEP7,(Front End Processor) 7] Check to see in SMFEPZ is mnning 8] STOP/ START ALARM TYPER 9] Exit without taking any action NOTE: SMS stands for Simulator Monitoring System and PMS stands for Plant (n) Monitoring System. For the purpose of this document they may be used interchangeably.

3) To shut down the Simulator Monitoring System select choice '2'. The next question up is 'Are you sure you want to stop PMS?' Answer 'YES' to this question. At this point the system begins to shut down SMS. It may take five minutes to completely finish.

4) The next question the system will ask is 'Do you want to stop VAXNMS?' This -

should only be done if the computer needs shutdown completely or if severe problems are encountered with SMS. During normal hours call I&C Computers at extension 4707 to ensure no other work is being done on the simulator node. Off normal hours the system can be rebooted or shutdown as required. This can also be done directly from the menu.

2

O 5) If you elect to completely shut down the VAX, the following questions should be answered as indicated:

How may minutes to shutdown [0]? <CR>

Reason for shutdown [ stand-alone)? <CR>

Do you want to spin down disk volumes [no)? Y<CR> (to power down)

Invoke site-specific shutdown procedure [yes)? <CR>

Should an automatic reboot be performed [yes)? 'N'<CR> (to power dowm)

When will the system be rebooted [later)? <CR>

Shutdowm options [none)? <CR>

6) Turn the orange power switch on the front of the system cabinet to the 'O' postion.

The rocker switch light should go out.

O O

3

l O "' S S ' " "'^' "

SECTION 20 MISCELLANEOUS INFORMATION COMMANDS Many times you will want to varf a parameter to enhance training. There are two ways of changing variables, the SET command and the RAMP command.

SET /SW -

Each variable is defined within the computer as a word or byte /real or integer. A specific command such as SW will only work on a single word variable. Since it may be difIlcult to tell in what form a variable has been defined, the SET command is used most often.

The SET command has the advantage of working on any type of variable. One disadvantage is its ability to change every word in an array if used carelessly.

Examples:

SW INSRADD(1) = TPCSAUCT will work and cause the address for digital display #1 to be TPCSAUCT r.

SET INSRADD(1) = TPCSAUCT .

will also work SE T INSRADD = TPCSAUCT will cause the address for both digital displays to change to TPCSAUCT. ,

SET JCRFDIS = 1 h will work causing the rod control system to think all the lift coil disconnect switches are open SW JCRFDIS = 1 won't work because JCRFDIS is a BYTE array not a word array RAMP -

Sometimes you may want to change a variable slowly. For example you might want to decrease the gas purity of the main generator H2 system.

O-V The RAMP command has tl'e following form:

RAMP name, final value, ramp time, time delay All the spaces must be filled in and all times must be in seconds.

Examples:

COMMAND 7 RAMP DCCH, 0.20, 1200, 60 DCCH will change from its present value to 0.20 during a 1200 second time interval 60 seconds after you pressed enter.

Up to 20 ramps may be active at any one time. Issuing a ramp command for a variable in the process of being ramped (ramp not yet complete) is acceptable._ This will reset the ramp to ramp from where it is to where you tell it, over the new time period.

DISC FILES p The simulation system is stored on disc drive units, but many other files reside on the discs

() also. The fdes associated with the SAVEM/USEM commands is disc resident.

Commands can be stored in a disc file for use later during simulation.

Files exist for setup of the 8-pen recorders, the trend recorders and other uses.

When a disc file is called, the file data is read into the computer. Each line ofinstruction is displayed on the instructor CRT and can be printed on the line printer.

To activate a fde, do the following:

1. Type or press ' FILE' key: FILE file name

2. Press: ' ENTER' When the file activation is complete the CRT will display a ' COMMAND 7'.

To view a disc file without activating it:

1. Type or press ' LIB' key: LIB file name

2. Press: ' ENTER' When the file is displayed the CRT, press ' CONTINUE' to exit, or enter a new file name.

V 2

O FUNCTION KEYS Keytest & Log - these two keys are used together to set up the middle row of keys (those keys on the same row as the ' log' key) as toggles for any assigned logical.

To use this feature perform the following:

1. Depress the ' LOG' key.

- CRT displays: KEYTEST 1 = through .

KEYTEST 15 =

2. Depress ' SET key to set all 15 keys or type in a number 1-15 and depress ' SET key to set only that key. The cursor will appear at the equals sign of the keytest to be set.

3. Type in the logical name. Depress the ' ENTER' key,

4. Repeat step 3 for remaining keys.

NOTE: To exit the set mode at any time depress the ' CONTINUE' key.

O 5. Depress the 'KEYTEST key.

6. When you depress any assigned key on the middle row you will change the state of the assigned logical. The keys are numbered 1-15 from len to right. Depress the key again and the logical is changed again.

7. To return keys to their normal functions, depress the 'KEYTEST key a second time.

Assignments remain until changed or until re-initializing.

NOTE: An alternate method of setting one key is to type in the following:

KEYTEST X = Logical name Then depress the ' ENTER' key.

X = any number 1-15 A

-U 3

L

()

p REPLAY While the simulator is running, the control panel output buffers will be stored in a circular file once per second over the previous 20 minutes. When the REPLAY feature is initiated, the simulator will replay the simulation staning at the instructor selected point up to 20 minutes in the past. Since the simulator is frozen during REPLAY, all control board input signals will be ignored until simulation is restarted. The taking of back-up snapshots is also suspended while the simulator is frozen. The REPLAY function does not include the storing of the control board input buffers since these can serve no purpose for a frozen simulator. The replay storage area will be erased each time the simulator is re-initialized. If the instructor desires to return to the same point after doing a replay, simply take a snapshot prior to beginning the replay.

4

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