ML18038A322

Forwards NRC Form 474, Simulation Facility Certification & Supporting Documentation

ML18038A322
Person / Time
Site:	Nine Mile Point
Issue date:	08/24/1990
From:	Burkhardt L NIAGARA MOHAWK POWER CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NMP2L-1248, NUDOCS 9009070058
Download: ML18038A322 (121)

Text

ACCELERATED DISTRIBUTION DEMONSTRATION'YSTEM

,. 4. 'EGULATO INFORMATION DISTRIBUTION STEM (RIDS)

ACCESSION NBR:9009070058 DOC.DATE: 90/08/24 NOTARIZED: NO DOCKET FACIL:50-410 Nine Mile Point Nuclear Station, Unit 2, Niagara Moha 05000410 AUTH. NAME AUTHOR AFFILIATION BURKHARDT,L. Niagara Mohawk Power Corp.

RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Forwards NRC Form 474, "Simulation Facility Certification" supporting documentation.

DISTRIBUTION CODE: AOOID TITLE: OR COPIES RECEIVED:LTR Submittal: General'istribution L ENCL L SIZE: Lo NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL' ID CODE/NAME LTTR ENCL PDl-1 LA 1 PD1-1 PD 1 1 MARTIN,R. 2 2 INTERNAL,:-ACRS 6 6 NRR/DET/ECMB 9H 1 1 NRR/DOEA/OTSBll 1 1 NRR/DST 8E2 1 1 NRR/DST/SELB 8D 1 1 NRR/DST/SICB 7E 1 1 NRR/DST/SRXB 8E 1 1 NUDOCS-ABSTRACT 1 1 OC/LFJ4B 1 0 OGC/HDS1 1 0 REG FILE Ol 1 1 RES/DSIR/EIB 1 1 EXTERNAL: NRC PDR 1 1 NSIC 1 1 tVRROLP,@ JLHF6 l NCk ix.8~1 ~a~8 I

'NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WAS'ONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEEDl TOTAL NUMBER OF COPIES REQUIRED: LTTR Q3 ENCL m~V

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V HIIASAIM U APirQHAMK NIAGARAMOHAWKPOWER CORPORATION/301 PI%INFIELD ROAD, SYRACUSE, N.Y. 13212/TELEPHONE (315) 474-1511 August 24, 1990 NMP2L 1248 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Re: Nine Mile Point Unit 2 Docket No. 50-410 NPF-69 Gentlemen:

In accordance with 10CFR55.45 (b)(5), we hereby submit NRC Form 474, Simulation Facility Certification and supporting documentation for initial

~

certification of the Nine Mile Point Nuclear Station Unit 2 plant simulation facility.

Please feel free to contact clarification.

me if you need additional information or U

Very truly yours, NIAGARA MOHAWK POWER CORPORATION L. Burkhardt, III Executive Vice President Nuclear Operations DJW/sek 2508b xc: Regional Administrator, Region I Mr. R. A. Capra, Director Mr. R. E. Martin, Project Manager Mr. W. A. Cook, Senior Resident Inspector (8cPy/z//zN Records Management PRE fAPq//otal i l 9009070058 9008~4 t PDR ADOCK 05000410 P PNV

NRC FORM 474 U.S. NUCLEAR REGULATORY COMMISSION 110 861 ApprOved by OMe 10 CFR g 55 aslb) 55 ~ s<<f555 SIIVlULATION FACILITY CERTIFICATION ~lt001$

INSTRUCTIONS. This form is to be filed for initial certification, recertification fif required), and for any change to 8 simulation facility performance testing plan made after initial submittal of such a plan. Provide the following information, and check the appropriate box to indicate reason for submittal.

F ACIL It'Y DOCKET NUMBER NINE MILE POINT NUCLEAR STATION UNIT 2 EO-4IO LICENSEE \

DATE NIAGARA MOHAWK POWER CORPORATION ttvs is io cemfv that. 1. the above named fsckfy kensee is usino ~ rimv4tvm tetany con<<sting so4iy of ~ 04nt ref<<anted eimusstor that meals the r<<tiiiremems of 10 cFR v 65.46: 2. this sanv41ion fsoely meets Ihe cvvtsrice comsvieo in ANsi/ANs 35, 1985. es <<vtorsee by NRc Reou41ory GivoPeh tea; eno a. oocumenutionis eveteb4 for NRc rev4vv In eccorrfsnce w'nh 10 cFR ~ 5649bf. If ther ~ eie eny

~ vceotvms io Ihe cemhcslen ol item 1 above. check h<<e gg eno describe tvey on edosienst peeve es necess<<y.

NAME (or otheridentifrcationl ANO LOCATION OF SIMULATIONFACILITY ATTACHMENT "SIMULATOR FACILITY CERTIFICATION" SIMULATIONFACILITYPERFORMANCE TEST ABSTRACTS ATTACHED. (For performance tests conductedin the period ending with the dere of this certi%'cation(

DESCRiP T ION OF PERFORMANCE TESTING COMPLETED (Anach additional page(sl as necesM~, endidenrify theirem description being continuedf ATTACHMENT HAH Performance Test Abstract ATTACHMENT "BH Simulator Configuration Management ATTACHMENT "CH Simulator Malfunctions ATTACHMENT HDH Sample Malfunction Cause and Effect and Test (ATP)

ATTACHMENT HEH NMP2 Control Room/Simulator Differences SIMULATIONFACILITYPERFORMANCE TESTING SCHEDULE ATTACHED. (For the conduct of approaimafefy 25B of performance tests per year for the four yatr period commencin with the dare of this certi%'cation.l DESCRIPTION OF PERFORMANCE TESTING To BE CONDUCTEO (Anach additional pageal as necessary, andidentify the item descriPtion beingcontinuedl ATTACHMENT "SIMULATOR FACILITY CERTIFICATION" ATTACHMENT HCH Simulator Malfunctions PF RFOR MANCE TESTING PLAN CHANGE. (For any modificarion to a performance testing plan submi Red on a previous cerrificationl 0 E SC R IPT I ON OF PE R F 0 RMANCE TESTING PLAN CHANG E (A Hach additional page(sf as necessary, andidantify the item description being continuedl No changes to our Simulator performance testing plan are anticipated at this time.

REcERTIF IGATIQN (Detcnbecorrcctiveactions taken, anach results of completed performance teningin accordance with rpcFR g 55 45(b((5(fvl.

Attach additional (sl as nrcrssar and idrnlil thai rem drscri tion bein conlinued.l Not applicable, initial certification Any false llslemenl oi omission in thn document, includine attachments. may be subject to ovil and ciiminsl sanctions, I ceiuly under penally ol perjury that the information in Ibis document and alla enls is true and correct.

SI ATU ~ AU PRESENTATIVE T I 1'L E DATE Exec, Vice .President Nuclear,Operati ns accordance wit 10 6 55.5, Communications, this form shall be submitted to the NRC as follows:

BY MAILADDRESSED TO: Director,'Office of Nuclear Reactor Regulation BY DELIVERY IN PERSON U.S. Nuclear Regulatory Commission TO THE NRC OF FICE AT: 7920 Norfolk Avenue Washington, DC 20555 Bethesda, MD gjf9QQ9Q70058-

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SIMULATION FACILITY CERTIFICATION Docket Number 50-410 II. Licensee Niagara Mohawk Power Corporation Rochester Gas and Electric Corporation Central Hudson Gas E Electric Corporation New York State Electric & Gas Corporation Long Island Lighting Company Name and Location of Simulation Faci lit Niagara Mohawk Power Corporation NMP-2'lant Referenced Simulator Nine Mile Point Nuclear Training Center R.D. ¹1 Box 148 Oswego, New York 13126-9719 IV. Descri tion of Performance Testin Com leted Factory acceptance test - ATP - (October 1984 January 1985)

Customized test procedures written for all simulated and physical fidelity were reviewed by reference plant systems'alfunctions operations personnel, and tests performed at the factory by General Physics Corporation (GP) personnel. The simulator was delivered with numerous open Discrepancies (DR's) all of which were corrected on site.

B. On-site acceptance test (February March 1985)

Re-verification tests conducted by GP following delivery and re-assembly.

l. Initial conditions Cold shutdown re-verified.

2. A reactor and auxiliary systems start up from cold shutdown to 100% and shutdown from 100%.

3. Selected malfunctions were re-verified in accordance with the malfunction cause and effect.

C. Initial ANSI/ANS 3.5 test (July 1989 - January 1990).

1. Test abstracts attached (Attachment 'A'):

a. ANSI/ANS 3.5 section 4.3 Simulator Operating Limits

b. 1989 ANSI/ANS 3.5 Appendix 'A'omputer Real Time Test 1989 ANSI Appendix 'A'ection A3.2 Steady State and Normal Operation (ANSI/ANS 3.5 section 3.1.1)

Simulation Facility Certification Page 1 of 3

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d. 1989 ANSI Appendix 'B'1.2(l ) Manual Scram

e. 1989 ANSI Appendix 'B'1.2(2) Simultaneous Trip of all Feedwater Pumps

f. 1989 ANSI Appendix 'B'1.2(3) Simultaneous Closure of all Main Steam Isolation Valves 1989 ANSI Appendix 'B'1.2(4) Simultaneous Trip of all Recirculation Pumps 1989 ANSI Appendix 'B'1.2(5) Single Recirculation Pump Trip 1989 ANSI Appendix 'B'1.2(6) Main Turbine Trip Transient Test

j. 1989 ANSI Appendix 'B'l.2(7) Maximum Rate Power Ramp (100% 75% 100%)

1989 ANSI Appendix 'B'l.2(8) Maximum Size Reactor Coolant System Rupture (LOCA) combined with Loss of all Off Site Power (LOOP) 1989 ANSI Appendix 'B'1.2(9) Maximum Size Unisolable Main Steam Line Rupture 1989 ANSI Appendix 'B'1.2(10) Simultaneous Closure of all Main Steam Isolation Valves combined with Single Stuck Open Safety Relief Valve

n. ANSI/ANS 3.5 section 3.1.2 Plant Malfunctions Acceptance Test

o. ANSI/ANS 3.5 section 3.2 Simulator Environment

p. Job Performance Measures, Operations Dynamic, and Static Examination Bank Scenarios

2. ANSI/ANS 3.5 sections 5.1, 5.2, and 5.3 Simulator Design, Updating and Modification (Attachment 'B').

a. Nuclear Training Instruction (NTI 4.5.3), Simulator Configuration Management, Attachment B describes the simulator design control process.

V. Simulation Facilit Performance Testin Schedule A. Each year the following tests will be performed:

1. Computer Real Time Test

2. ANSI/ANS 3.5 Appendix 'A'ection A3.2 Steady State and Normal Operation (section 3.1.1,)

Simulation Facility Certification Page 2 of 3

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3 ~ ANSI/ANS 3.5 Appendix 'A'ection A3.3 Transient tests:

a. 1989 ANSI Appendix 'B'1.2(1) Manual Scram

b. 1989 ANSI Appendix 'B'1.2(2) Simultaneous Trip of all Feedwater Pumps

c. 1989 ANSI Appendix 'B'1.2(3) Simultaneous Closure of all Hain Steam Isolation Valves

d. 1989 ANSI Appendix 'B'1.2(4) Simultaneous Trip of all Recirculation Pumps 1989 ANSI Appendix 'B'1.2(5) Single Recirculation Pump Trip 1989 ANSI Appendix 'B' 1.2(6) Main Turbine Trip Transient Test 1989 ANSI Appendix 'B'1.2(7) Maximum Rate Power Ramp 100% 75% 100%)

h. 1989 ANSI Appendix 'B'1.2(8) Maximum Size Reactor Coolant System Rupture (LOCA) combined with Loss of all Off Site Power (LOOP) 1989 ANSI Appendix 'B'1.2(9) Maximum Size Unisolable Main Steam Line Rupture

j. 1989 ANSI Appendix 'B'1.2(10) Simultaneous Closure of all Main Steam Isolation Valves combined with Single Stuck Open Safety Relief Valve

4. ANSI/ANS 3.5 Appendix 'A'ection A3.4 Malfunction tests.

All simulator malfunctions will be tested during the next four years, starting with 1990 as the first year following initial certification, in accordance with the attachment to the Malfunction Tests abstract (Attachment 'C').

Simulation Facility Certification Page 3 of 3

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NIAGARA MOHAWK POWER CORPORATION NRC FORM 474 PERFORMANCE TEST ABSTRACT NMP-2 PLANT REFERENCED SIMULATION FACILITY

Title:

ANSI/ANS 3.5 section 4.3 Simulator Operating Limits Initial Conditions:

1. Rated power with normal reference plant equipment lineup.

Data Collection Method:

1. Manual.

Com arison

Reference:

1. Reference plant design limits.

Procedure:

1. To avoid negative training, a block of 4 blank annunciators on panel 601 alarm when reference plant design parameters are exceeded to alert the instructor of unrealistic conditions. To test this function a detailed one time only test was performed. The key parameters are:

a. RPV pressure > 1250 psig

b. Drywell pressure > 45 psig or < 10.0 psia C. Suppression chamber > 45 psig or < 10.0 psia

d. Drywell temperature > 340'F

e. Suppression pool water temperature > 212'F

f. Average fuel temperature > 2200 F Results:

l. All acceptance criteria were satisfactory.

~Exce tions: None Attachment A Page 1 of 20

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NIAGARA MOHAWK POWER CORPORATION NRC FORM 474 PERFORMANCE TEST ABSTRACT NMP-2 PLANT REFERENCED SIMULATION FACILITY

Title:

1989 ANSI/ANS 3.5 Appendix 'A'omputer Real Time Test Initial Conditions:

Full power steady state, middle of cycle, with normal reference plant equipment lineup.

Data Collection Method:

1. Computer program 'RTTPRINT'.

2. Manual.

Com arison

Reference:

1. Computer real time clock.

, Procedure:

l. A detailed procedure of computer commands was performed to record the data for acceptance review.

2. Acceptance criteria.

There are 9 executives calculating the engineering models. These executives are divided among 6 processors. The time requirements of each control module and totals for each processor are accessible through a utility supplied by the simulator vendor. If the total module run time is 50 milliseconds or less, the module is running in REAL time.

A 'Watchdog'rogram incorporated into the Master Synchronizing Task (MST) checks that each of the 9 executives completes its assigned

'"calculations on time, during simulator operation. The is always operational during simulator operation. If any

'Watchdog'rogram executive fails to complete its assignment every quarter (1/4) of a second, MST will note the problem, place the simulator in FAIL and type out the offending executive. When MST places the simulator in FAIL, further simulation is halted until the computer is rebooted.

Results:

l. All acceptance criteria were satisfactory.

~fxce Cions: None Attachment A Page 2 of 20

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NIAGARA MOHAWK POWER CORPORATION NRC FORM 474 PERFORMANCE TEST ABSTRACT NMP-2 PLANT REFERENCED SIMULATION FACILITY

Title:

1989 ANSI Appendix 'A'ection A3.2 Steady State and Normal Operation (ANSI/ANS 3.5 section 3.1.1)

Initial Conditions: Cold Shutdown Data Collection Method:

1. Data for the 100% steady state 60 minute run was gathered on the critical parameters using a simulator program called "ANSI SS60".

a. Data is gathered at 30 second intervals, and collected for the 60 minute period.

b. Data is then down loaded to a personal computer (PC) and processed for evaluation.

2."'ata'or 'the'=25%, 50%, 100% steady state operation tests was gathered on the critical parameters using the Process Plant Computer (PPC) on demand BOP log, P-1 and OD-3 edits and procedure check off forms as specified.

3. Reference plant controlled operating procedures were used for recording the ability to operate the simulator.

Com arison

Reference:

1. Reference plant special logs and P-1 edits taken during plant start up April 1989.

2. Reference plant complete value/status of system variables summary report at 100% power taken May 1989.

3. Reference plant controlled operating and selected surveillance procedures.

Attachment A Page 3 of 20

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NIAGARA MOHAWK POWER CORPORATION NRC FORM 474 PERFORMANCE TEST ABSTRACT NMP-2 PLANT REFERENCED SIMULATION FACILITY Procedure:

l. A complete reactor and BOP startup was performed from cold shutdown to rated power, which included reactor startup and heatup, turbine and generator startup, synchronization to the grid, and load changes.

Power was held constant at 25, 50, 75 and 100%. Data was gathered and compared to reference plant data.

2. A complete reactor and BOP shutdown and cool down to cold shutdown from rated power was performed.

3. The simulator was reset to rated power wi th normal reference plant equipment lineup and a manual reactor scram inserted. The reactor was maintained in hot standby. From hot standby a single recirculation loop 'A'eactor startup was conducted to the maximum power for single

'oop. The idle recirculation loop was started and power was raised to

'* "r'ated'c'ondi tions. " The power was'hen reduced to the maximum allowed for single loop operation, and the 'B'ecirc loop was shutdown. The reactor and BOP was then shutdown to hot standby with all rods full-in.

4. The simulator was reset to 100/ power, and the 60 minute steady state test run performed.

5. All surveillance tests selected by the Simulator Configuration Control Board (SCCB) (48 total) were performed.

Attachment A Page 4 of 20

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NIAGARA MOHAWK POWER CORPORATION NRC FORM 474 PERFORMANCE TEST ABSTRACT NMP-2 PLANT REFERENCED SIMULATION FACILITY Results:

l. The performance criteria specified in ANSI/ANS 3.5 section 4.1 steady state operation were satisfactory with one exception listed.

2. The performance criteria specified in ANSI/ANS 3.5 section 4.2.1 were satisfactory for all section 3.F 1 "Normal Plant Evolutions".

3. The following discrepancies (DR's) were identified.

Note: The SCCB determined the identified DR's did not detract from training.

Scheduled DR4 Descri tion Status ~Com 1etlon 2-941 Generator MWE 8 2/ higher than ref. plant Closed

'2-'942 '"APRM read 8 3/. higher than ref. plant Closed 2-943 Feedwater temp. low at 25 II 50/. power Working 10/90 2-944 Drywell temp. is higher than ref. plant Closed 2-945 CRD cooling flow is higher than ref. plant Closed 2-946 Hotwell temp. does not rise with power level Closed 2-947 Thermal limit calculations at low power Working 10/90 differ from ref. plant P-1 edit.

The DR correction testing verifies the ANSI acceptance criteria are still satisfied.

~Exce tlons:

l. ANSI/ANS 3.5 section 4.1 Performance criteria:

Reactor power and recirculation loop flows varied more than

+ 2% from initial values. This was due to recirculation loop flow induced oscillations which are also evident in the reference plant. This variance enhances training.

Attachment A Page 5 of 20

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NIAGARA MOHAWK POWER CORPORATION NRC FORM 474 PERFORMANCE TEST ABSTRACT NMP-2 PLANT REFERENCED SIMULATION FACILITY

Title:

1989 ANSI Appendix '8'1.2(l) Manual Scram Ini ti al Condi tions:

Full power steady state, middle of cycle with normal reference plant equipment lineup.

Data Collection Method:

1. Data was gathered on the critical parameters using a simulator program called "ANSI B121".

a. Data is gathered at 0.5 second intervals, starting 15 seconds before the transient and lasting for 10 minutes into the transient.

b. Data is then down loaded to a personal computer (PC) and graphed for evaluation.

." ""Process "plant computer (PPC) alarm and sequence of events (SOE) printouts were gathered for alarm and automatic action evaluation.

Com arison

Reference:

Reference plant GETARS traces from the following:

1. 89-14, 100% power turbine trip scram.

0 LER

2. LER 89-09, 100% power high flux scram.

3. LER 88-17, 97% power turbine trip scram.

Procedure:

The initial conditions were established and data gathering started.

Malfunction RP01 (Reactor Scram) was inserted. Initial actions of the plant scram procedure were taken to more closely replicate plant comparison 'data conditions. All data was then reviewed by a panel of experts, and the results were reviewed and approved by the Simulat'or Configuration Control Board and Training Management.

Results: All acceptance criteria (ANSI 3.5, Section 4.2.1 ) were met. The following discrepancies (DR's) were found:

DR¹ Descri tion Status 2-924 Total core flow unexplained rise closed 2-925 NR vs. WR RPV level delta reading closed 2-926 Mn Gen. Gas pressure response ciosed 2-927 WR RPV level drop too fast closed 2-928 Total steam flow dropped to zero closed 2-929 Turbine coast down too fast closed The DR correction testing verifies the ANSI acceptance criteria is still satisfied.

~Exec tines: None Attachment A Page 6 of 20

1 NIAGARA MOHAWK POWER CORPORATION NRC FORM 474 PERFORMANCE TEST ABSTRACT NMP-2 PLANT REFERENCED SIMULATION FACILITY

Title:

1989 ANSI Appendix 'B'1.2(2) Simultaneous Trip of all Feedwater Pumps Initial Conditions:

Full power steady state, middle of cycle, with normal reference plant equipment lineup.

Data Collection Method:

1. Data was gathered on the critical parameters using a simulator program called "ANSI B122".

a. Data is gathered at 0.5 second intervals, starting 15 seconds before the transient and lasting for 10 minutes into the transient.

b. Data is then down loaded to a personal computer (PC) and graphed

for'valuation.

2. Process plant computer (PPC) alarm and sequence of events (SOE) printouts were gathered for alarm and automatic action evaluation.

Com arison

Reference:

Reference plant GETARS traces from the following:

1. Start Up Test procedure SUT 27-6, load reject which led to a total loss of normal feedwater LER 88-12.

2. Start Up Test procedure SUT 23-6, FWS P1A Pump Trip.

Procedure:

The initial conditions were established and data gathering started.

Malfunction FW03 (Trip of all Feedwater Pumps) was inserted. The transient was allowed to progress with NO operator actions. All data was then reviewed by a panel of experts, and the results were reviewed and approved by the Simulator Configuration Control Board and Training Management.

Results:

All acceptance criteria (ANSI 3.5, Section 4.2'.1) were met.

DR¹ Status 2-930 Wide range pressure plot did not closed show MSIV isolation.

The DR correction testing verifies the ANSI acceptance criteria are still satisfied.

~Exce tions: None Attachment A Page 7 of 20

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NIAGARA MOHAHK POHER CORPORATION NRC FORM 474 PERFORMANCE TEST ABSTRACT NMP-2 PLANT REFERENCED SIMULATION FACILITY Ti tl e: 1989 ANSI Appendix 'B'1.2(3) Simultaneous Closure of all Main Steam Isolation Valves Initial Conditions:

Full power steady state, middle of cycle, with normal reference plant equipment lineup.

Data Collection Method:

1. Data was gathered on the critical parameters using a simulator program called "ANSI B123".

a. Data is gathered at 0.5 second intervals, starting 15 seconds before the transient and lasting for 10 minutes into the transient.

b.,'."" Data is then down loaded to a personal computer (PC) and graphed for: evaluation.

2. Process plant computer (PPC) alarm and sequence of events (SOE) printouts were gathered for alarm and automatic action evaluation.

Com arison

Reference:

Reference plant GETARS traces from the following:

1. Start Up Test procedure SUT 25-6, MSIV Isolation Procedure:

The initial conditions were, established and data gathering started.

Malfunction .MS12 (Reactor Vessel Isolation) was inserted. The transient was 'allowed'o"progress with NO operator actions. All data was then reviewed by a panel of experts, and the results were reviewed and approved by the Simulator Configuration Control Board and Training Management.

Results: All acceptance criteria (ANSI 3.5, Section 4.2.1) were met.

~Exce tions: None Attachment A Page 8 of 20

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NIAGARA MOHAWK POWER CORPORATION NRC FORM 474 PERFORMANCE TEST ABSTRACT NMP-2 PLANT REFERENCED SIMULATION FACILITY

Title:

1989 ANSI Appendix 'B'1.2(4) Simultaneous Trip of all Recirculation Pumps Initial Conditions:

Full power steady state, middle of cycle, with normal reference plant equipment lineup.

Data Collection Method:

l. Data was gathered on the critical parameters using a simulator program called "ANSI B124".

a. Data is gathered at 0.5 second intervals, starting 15 seconds before the transient and lasting for 10 minutes into the transient.

b. Data is then loaded to a personal computer (PC) and graphed for evaluation.

2. Process plant computer (PPC) alarm and sequence of events (SOE) printouts were gathered for alarm and automatic action evaluation.

Com arison

Reference:

Reference plant GETARS traces from the following:

1. Start Up Test procedure SUT 30-3, Trip of Both Recirc Pumps.

Procedure:

'he'nitial'-"conditions were established and data gathering started.

Malfunction RR10 (Reactor Recirculation Pump Breaker Trip) was inserted.

The transient was allowed to progress with NO operator actions. All data was then reviewed by a panel of experts, and the results were reviewed and approved by the Simulator Configuration Control Board and Training Management.

Results:

All acceptance criteria (ANSI 3.5, Section 4.2.1) were met.

~Exce tines: None Attachment A Page 9 of 20

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NIAGARA MOHAWK POWER CORPORATION NRC FORM 474 PERFORMANCE TEST ABSTRACT NMP-2 PLANT REFERENCED SIMULATION FACILITY

Title:

1989 ANSI Appendix 'B'1.2(5) Single Recirculation Pump Trip Ini ti al Condi ti ons:

Full power steady state, middle of cycle, with normal reference plant equipment lineup.

Data Collection Method:

1. Data was gathered on the critical parameters using a simulator program called "ANSI B125".

a. Data is gathered at 0.5 second intervals, starting 15 seconds before the transient and lasting for 10 minutes into the transient.

b. Data is then down loaded to a personal computer (PC) and graphed for evaluation.

2. Process plant computer (PPC) alarm and sequence of events (SOE) printouts were gathered for alarm and automatic action evaluation.

Com arison

Reference:

Reference plant GETARS traces from the following:

1. Start Up Test procedure SUT 30-6, B Recirc Pump Trip from 100% Power.

Procedure:

The initial conditions were established and data gathering started.

Malfunction RR10A (Reactor Recirculation Pump 'A'reaker Trip) was inserted.'The'ransient was allowed to progress with NO operator actions. All data was then reviewed by a panel of experts, and the results were reviewed and approved by the Simulator Configuration Control Board and Training Management.

Results:

All acceptance criteria (ANSI 3.5, Section 4.2.1) were met.

~Ence tione: None Attachment A Page 10 of 20

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NIAGARA MOHAWK POWER CORPORATION NRC FORM 474 PERFORMANCE TEST ABSTRACT NMP-2 PLANT REFERENCED SIMULATION FACILITY

Title:

1989 ANSI Appendix 'B'1.2(6) Main Turbine Trip Transient Test Initial Conditions:

Maximum Power level which did not result in immediate reactor scram, and normal reference plant equipment lineup.

Data Collection Method:

l. Data is gathered on the critical parameters using a simulator program called "ANSI 8126".

a. Data is gathered at 0.5 second intervals, starting 15 seconds before the transient and lasting for 10 minutes into the transient.

-"b. Data is then down loaded to a personal computer (PC) and graphed for evaluation.

Process plant computer (PPC) alarm and sequence of events (SOE) printouts were gathered for alarm and automatic action evaluation.

Com arison

Reference:

Reference plant GETARS traces from the following:

1. Start Up Test procedure SUT 27-2, Turbine Trip within Bypass Valve Capability.

Procedure:

The initial conditions were established and data gathering started.

Malfunction TU07 (Turbine Trip) was inserted. The transient was allowed to progress with NO operator actions. All data was then reviewed by a panel of experts, and the results were reviewed and approved by the Simulator Configuration Control Board and Training Management.

Results: Scheduled

~Com let)on All acceptance criteria (ANSI 3.5, Section 4.2.1) were met.

Discrepancy ¹2-933 (APRM power rise following trip was 8 71.,

should have been 4-5% above initial power level). 10/90 The DR correction testing verifies the ANSI acceptance criteria are still satisfied.

~Exce tions: None Attachment A Page ll of 20

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NIAGARA MOHAWK POWER CORPORATION NRC FORM 474 PERFORMANCE TEST ABSTRACT NMP-2 PLANT REFERENCED SIMULATION FACILITY

Title:

1989 ANSI Appendix '8'1.2(7) Maximum Rate Power Ramp (100% 75% 100%)

Initial Conditions:

Full power steady state, middle of cycle, with normal reference plant equipment lineup.

Data Collection Method:

1. Data was gathered on the critical parameters using a simulator program called "ANSI 8127".

a. Data is gathered at 0.5 second intervals, starting 15 seconds before the transient and lasting for 10 minutes into the transient.

b. 'a'ta is then down loaded to a personal computer (PC) and graphed for evaluation.

2. Process plant computer (PPC) alarm and sequence of events (SOE) printouts were gathered for alarm and automatic action evaluation.

Com arison

Reference:

Reference plant GETARS traces from the following:

1. Start Up Test procedure SUT 29-6, Recirc System Step Changes Procedure:

The initial conditions were established and data gathering started.

'ith recirc flow control in flux auto, using the master controller, power was ramped to 75% and allowed to stabilize then ramped backed to 100% power. All data was then reviewed by a panel of experts, and the results were reviewed and approved by the Simulator Configuration Control Board and Training Management.

Results:

All acceptance criteria (ANSI 3.5, Section 4.2.1) were met.

~Exce tions: None Attachment A Page 12 of 20

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NIAGARA MOHAWK POWER CORPORATION NRC FORM 474 PERFORMANCE TEST ABSTRACT NMP-2 PLANT REFERENCED SIMULATION FACILITY

Title:

1989 ANSI Appendix 'B'1.2(8) Maximum Size Reactor Coolant System Rupture (LOCA) combined wi th Loss of all Off Site Power (LOOP)

Initial Conditions: Full power steady state, middle of cycle, with normal reference plant equipment lineup.

Data Collection Method:

1. Data was gathered on the critical parameters using a simulator program called "ANSI B128"

a. Data is gathered at 0.5 second intervals, starting 15 seconds before the transient and lasting for 10 minutes into the transient.

b. Data is then down loaded to a personal computer (PC) and graphed

'or evaluation.

2. Process plant computer (PPC) alarm and sequence of events (SOE) printouts were gathered for alarm and automatic action evaluation.

Com arison

Reference:

1. General Electric Company analytical Model for Loss of Coolant analysis NED0-20566.

2. Reference plant FSAR transient analysis.

Procedure The initial conditions were established and data gathering started.

Malfunctions RR20 (RCS Loop Rupture) and ED02 (Loss of Offsite 115KV Power) were inserted. The transient was allowed to progress with NO operator actions. All data was then reviewed by a panei of experts, and the results were reviewed and approved by the Simulator Configuration Control Board and Training Managements Results: All acceptance criteria;(ANSI 3.5, Section 4.2.1) were met. The following discrepancies (DR's) were found:

OR¹ Descri tion Status 2-934 CSH pump breaker response and EDG readings closed 2-935 Unexplained supp chamber air temp. peak closed 2-936 Drywell pressure vs. temperature response closed The DR correction testing verifies the ANSI acceptance criteria are still satisfied.

~Exce tious:

ANSI A3 ~ 3(2) The FSAR is currently the best available data f'r this transient. The panel of experts reviewing the data took into account that FSAR data is "WORST CASE".

Attachment A Page 13 of 20

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NIAGARA MOHAWK POWER CORPORATION NRC FORM 474 PERFORMANCE TEST ABSTRACT NMP-2 PLANT REFERENCED SIMULATION FACILITY

Title:

1989 ANSI Appendix '8'1.2(9) Maximum Size Unisolable Main Steam Line Rupture.

Initial Conditions:

Full power steady state, middle of cycle, with normal reference plant equipment lineup.

Data Collection Method:

1. Data was gathered on the critical parameters using a simulator program called "ANSI 8129".

a. Data is gathered at 0.5 second intervals, starting 15 seconds before the transient and lasting for 10 minutes into the transient.

b. Data is then down loaded to a personal computer (PC) and graphed

"'or"evaluation.

2. Process plant computer (PPC) alarm and sequence of events (SOE) printouts were gathered for alarm and automatic action evaluation.

Com arison

Reference:

1. Reference plant FSAR transient analysis.

Procedure The initial conditions were established and data gathering started.

Malfunctions MS04 (Steam Line Rupture Inside Primary Containment) was inserted. The transient was allowed to progress with NO operator actions. All data was then reviewed by a panel of experts, and the

'results were reviewed and approved by the Simulator Configuration Control Board and Training Management.

Results: All acceptance criteria (ANSI 3.5, Section 4.2.1) were met. The following discrepancies (DR's) were found:

OR¹ Descri tion Status 2-937 Total feedwater flow response at time +50 closed The DR correction testing verifies the ANSI acceptance criteria are still satisfied.

~Exce tioes:

ANSI A3.3(2) The FSAR is currently the best available data for this transient. The panel of experts reviewing the data took into account that FSAR data is "WORST CASE".

'NSI B1.2:3 Deleted fuel:zone water level -critical parameter. There is no change in fuel zone water level during this transient.

Attachment A Page 14 of 20

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NIAGARA MOHANK POHER CORPORATION NRC FORM 474 PERFORMANCE TEST ABSTRACT NMP-2 PLANT REFERENCED SIMULATION FACILITY

Title:

1989 ANSI Appendix 'B'1.2(10) Simultaneous Closure of all Main Steam Isolation Valves combined with Single Stuck Open Safety Relief Valve Initial conditions:

Full power steady state, middle of cycle, with normal reference plant equipment lineup.

Data Collection Method:

1. Data was gathered on the critical parameters using a simulator program called "ANSI 812A".

a. Data is gathered at 0.5 second intervals, starting 15 seconds before the transient and lasting for 10 minutes into the transient.

b. Data is then down loaded to a personal computer (PC) and graphed for evaluation.

2. Process plant computer (PPC) alarm and sequence of events (SOE) printouts were gathered for alarm and automatic action evaluation.

Com arison

Reference:

Reference plant GETARS traces from the following:

1. Start Up Test procedure SUT 25-6, MSIV Isolation.

Procedure

'The "initial- conditions were established and data gathering started.

Malfunctions MS12 (Vessel Isolation)and AD03B (SRV*PSV128 sticks open) were inserted. The transient was allowed to progress with NO operator actions. All data was then reviewed by a panel of experts, and the results were reviewed and approved by the Simulator Configuration

'ontrol Board and Training Management.

Results: All acceptance criteria (ANSI 3.5, Section 4.2.1) were met.

~Exec tions: ~

ANSI 81.2.3 Deleted fuel zone water level critical parameter. There is no change in fuel zone water level during this transient.

Deleted ECCS flow from critical parameters. There is no ECCS injection during this transient.

Attachment A Page 15 of 20

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NIAGARA MOHAWK POWER CORPORATION NRC FORM 474 PERFORMANCE TEST ABSTRACT NMP-2 PLANT REFERENCED SIMULATION FACILITY

Title:

ANSI/ANS 3.5 section 3.1.2 Plant Malfunctions Acceptance Test Initial Conditions: In accordance with the individual malfunction acceptance test procedure.

Data Collection Method: Manual.

Com arison

Reference:

1. Controlled reference plant elementary drawings.

2. Reference plant GEK manuals.

Procedure:

l. Each malfunction listed on attachment 'C'as tested using a customized malfunction acceptance. test procedure. A sample

""'malfunc'tion"cause and "effect and 'acceptance test procedure, CWOl Service Water Pump Trip, is included as attachment 'D'.

Results:

l. All malfunctions released for training use were tested with satisfactory acceptance criteria (ANSI 3.5, Section 4.2.1).

~Exce tionx:

l. ANSI/ANS 3.5 section 3.1.2 (10) Loss of all feedwater (normal and emergency).

a. No individual malfunction exists for this effect. However, the same effect may be accomplished by utilizing several

"'malfunctions in conjunction with each other.

2. ANSI/ANS 3.5 section 3.1.2(18) Failure of reactor coolant pressure and volume control system (PWR).

a. NMP-2 is BWR-5 type.

Attachment A Page 16 of 20

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NIAGARA MOHAWK POWER CORPORATION NRC FORM 474 PERFORMANCE TEST ABSTRACT NMP-2 PLANT REFERENCED SIMULATION FACILITY

Title:

ANSI/ANS 3.5 section 3.2 Simulator Environment Initial Conditions: NONE Data Collection Method:

1. Manual.

Com arison

Reference:

1. Reference plant photographs dated July 1989.

Procedure:

1. Photographs were taken of the reference plant control room panels and llxl5" prints were generated. The simulator control panels were compared to the reference plant photographs.

Results:

l. All requirements of ANSI/ANS 3.5 section 3.2, are satisfied.

2. For each panel simulated hardware discrepancies (DR's) listed below were identified in the simulator configuration management system.

DR's still open are cosmetic in nature and DO-NOT detract from training as determined by the Simulator Configuration Control Board. Scheduled completion 12/90.

DR¹ Description Status 2-969 Panel 824 cosmetic DR's Working

'-970 Panel 842 cosmetic DR's Working 2-971 Panel 849 cosmetic DR's Working 2-1004 Panel 614, 606, 663, 882 and 898 Working cosmetic DR's 2-1005 Panel 632 cosmetic DR's Working 2-1008 Panel 870 cosmetic DR's Working 2-1170 Cosmetic DR's left over from Working DR ¹ 2-972 and 2-1006 Attachment A Page 17 of 20

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NIAGARA MOHAWK POWER CORPORATION NRC FORM 474 PERFORMANCE TEST ABSTRACT NMP-2 PLANT REFERENCED SIMULATION FACILITY

Title:

ANSI/ANS 3.5 section 3.2 Simulator Environment (Cont'd)

~Exce tions: ANSI/ANS 3.5 section 3.2 physical fidelity exceptions listed below do not detract from training:

Refer to attachment "E" control room lay out.

The simulator shift supervisors office contains the instructor console, and the office reference material is located in a book case next to the room.

The reference plant control room training and documentation room is used as a simulator class room.

Control Room panels not simulated:

During .simulator procurement NMPC determined the following back

-"'-" pane"ls-were" not required for'operator training or'esting, due to their limited training valve.

a. P200 Wells Fargo Fire System computer

b. P609 Trip system "A" RPS Vertical Board

c. P611 Trip system "B" RPS Vertical Board

d. P612 Feedwater and Recirc Instrumentation panel

e. P613 Process instrumentation panel

f. P615 Control rod position information panel

g. P616 CRD select relay instrument panel

h. P618 Division 2 RHR BEC relay panel

i. P621 RCIC relay panel

j. P622 Inboard valve relay panel Outboard valve relay panel

k. P623

1. P625 HPCS relay panel

m. " P629 .Division 1 LPCS 5 RHR A relay panel

n. P642 Division 2 leak detection panel

o. P659 RSCS panel

4. Electrical termination cabinets have been visually simulated with storage cabinets.

5. The simulated north end of the reference plant control room has been partitioned off at the last row of simulated panels to provide working space.

6. Wall mounted equipment such as electrical boxes, pipes, and hangers are not simulated.

Emergency lighting for station blackout simulation is not simulated.

Simulator room lighting is not controlled by simulator software.

Attachment A Page 18 of 20

T

Title:

ANSI/ANS 3.5 section 3.2 Simulator Environment (Cont'd)

8. Meteorological tower recorders on back panel P882 are not the same model as reference plant.

a. The SCCB determined that the cost to training value comparison did not warrant up-grading the model type. All required information is displayed on the installed model.

9. The GETAR computer is not simulated.

10. Control room sound powered phone system is not simulated.

ll. The core engineering computer, 3D Monicore, is not simulated.

12. Simulator control push buttons are located at the end of control panels 601 and 800C.

13. Control room back panels partially simulated.

a. P606 and P633 contains only one SRM and two IRM drawers in each cabinet vice the six in the Control Room.

b. P607 contains one complete TIP system vice the five located in the Control Room.

c. P608 contains "C" APRM and "A" RBM, the others are not visually simulated.

d. P852 rear instrumentation does not include Battery Grounding System.

e. PBOOA houses three RGB monitors for the process plant computer.

Two of the three are functional with the third visually simulated only.

f. PBOOB contains a process plant computer monitor that is visually

'imulated only.

g. P880 is a four bay electronics rack with no DRMS monitors installed. DRMS is simulated with operator interface on P800B.

Attachment A Page 19 of 20

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NIAGARA MOHANK PONER CORPORATION NRC FORM 474 PERFORMANCE TEST ABSTRACT NMP-2 PLANT REFERENCED SIMULATION FACILITY

Title:

Job Performance Measures, Operations Dynamic, and Static Examination Bank Scenarios Initial Conditions: Various in accordance with Scenario.

Data Collection Method: Manual.

Com arison

Reference:

1. Controlled operating procedures.

2. Controlled emergency operating procedures.

3. Controlled surveillance test procedures.

4. Controlled reference plant elementary drawings.

""Procedure:

l. In accordance with NUREG 1021 ES601 job performance measures (JPM's),

dynamic (simulator scenarios) and static (section 'A'pen reference written exam) operations re-qualification examination questions are written by the training department and tested for accuracy using the simulator and comparison reference documents.

2. A training department instructor, using a NRC licensed operating crew, validates the dynamic simulator scenario using the simulator and comparison reference documents.

3. A training department instructor, using a,NRC licensed control room operator, validates the JPM's and the static exam scenarios using the simulator.and comparison reference documents.

Results:

l. All scenarios and questions entered into the exam bank were tested satisfactorily.

~Exce tions: NONE Attachment A Page 20 of 20

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NINE MILE'OINT NUCLEAR STATION NUCLEAR TRAINING INSTRUCTION NTI-4.5.3 SIMULATOR CONFIGURATION MANAGEMENT DATE AND INITIALS APPROVALS SIGNATURE@ REVISION 3 REVISION 4 REVISION 5 Superintendent Training-Nuclear r,ee A. D. Rivers

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~Pa es Date i,h-6,8"21 June 1989 4'7 August 1989 (Publication.'hange)

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T'IAGARA MOHANK PONER CORPORATION V'ef THIS PROCEDURE NOT BE USED AFTER July )993, SUBJECT TO PERIODIC NEVI EH.

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S ItlU'TQR CONFIGURATION MAIVAGEMENT TABLE OF CONTENTS SECTION TITLE PAGE 1.0 PURPOSE

2.0 REFERENCES

3.0 DE F I H I TIOHS 4.0 RESPONSIBILITIES 4.1 Supervisor Simulator Technology 4.2 Simulator Operator 4.3 Simulator Software Engineer 4.4 Simulator Hardware Specialists 4 Simulator Clerk 4.6 Lead Software Engineer I3 5.0 COMPUTER TRACKING 6.0 MODIFICATION PROCESS 7.0 ENHANCEMENT PROCESS 8.0 DISCREPANCY REPORT (DR) PROCESS 9.0 COST ACCOUNTING 10.0 REFERENCE PLANT OPERATING PROCEDURE SIMUL'ATOR.- () %

EXCEP TIONS ';-,, 8 H

~~I ~ Tt FIGURE 1 MODIFICATION REVIE'N FORM 9" wt tO Lp I

FIGURE 2 MODIFICATION CLOSEOUT FORti 10 FIGURE 3 ENHANCEMENT REQUEST FORti FIGURE 4 SOFTHARE CHANGE REPORT 12 FIGURE 5 SIMULATOR HARDHARE CHANGE REPORT '13 FIGURE 6 DATA BASE t""". ~(-ICATION REPORT 14 FIGURE 7 DISCREPAN'. REPORT ,15 FIGURE 8 EXCEPTION SHEET FIGURE 9 SIMULATOR MOD IF I CA ( .'OH PROCESS 17 FIGURE 10 ENHANCEMENT PROC SS 18

• FIGURE 1 1 REFERENCE PLANT OPERATING PROCEDURE SIMULATOR EXC . TIOtt FORM 19 t<TI--".:.3 -i June 1989 ATTACHNENT B page 2 of 23

"I NTI-4.5.3 SIMULATOR CONFIGURATION MANAGEMENT 1.0 PURPOSE Derine simulator personnel responsibilities. ,w ~ ~ "

1.2 Detail instructions for:

Computer tracking Modification Process Enhancement Process Discrepancy Correct'.on Cost Accounting

2.0 REFERENCES

2.1 ANS/ANSI 3.5 - 1985 "Nuclear Power Plant Simulators For Use In Operator Training" 2.2 TQ-504, "Simulator Configuration Management"

\

2.3 Regulatory Guide 1.149, "Nuclear Power Plant Simulators For Use In Operator Training" 2.4 NUREG 1258, "Evaluation Procedures for Simulators Certified Under 10CFR55" 2.5 AP-6.0, "Procedure for Modification" 2.6 ND-100, "Plant Modifications" 2.7 AP-6.0, AP-6.1, and AP-6.2 3.0 DE F I NI T I ONS 3.1 Simulator Modification A referenced plant modification that has been identified as having an impact on the simulator.

3.2 Enhancement An instructional improvement on the simulator.

3 3 Software Discrepancy A conflict between actual simulation and that predicted or prescribed by the current database.

3.4 Hardware Discrepancy A physical defect (i.e. broken switch).

N: -4.5.3 -1 June 1989 of

'TTACHMENT B page 3 23

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n 3.5 Simulator Configuration Con:rol Board (SCCB) A committee and training department personnel that review reference plant modifications that imoac'. the simulator and set priorities for implementation.

3.6 S'imulator Database - The simulator database consists of the reference drawings, prints, procedures, texts, and photographs that were used to initially build and later update 'the respective simulator. The simulator database may be divided into two categories of references:

static references and dynamic references.

3.6.1 Static Database References This simulator database subsection includes the FSAR, Operating and other procedures, photographs, vendor manuals and other non-controlled information. The information contained in these references was used to initially build the simulator. Changes to these references are not evaluated for simulator impact or modification.

3.6.2 Dynamic Database References - This simulator database subsection is made up of the reference drawings actually used to define the simulator configuration. These drawings are controlled or tracked using the computer based configuration management system.

3.7 Simulator Change Database The change database represents data collected for integration at a future date. As a simulator modification is completed, the data located here is moved to the simulator database.

3.8 Disc Turnover to Trainin There are three (3) sets of disc packs for each simulator as follows:

~Trainin -'he disc packs designated for training use Simulator Support - the disc packs use for making simulator modifications, enhancements, and DR corrections.

~Back U the disc packs held in reserve since the last disc turnover Nhen significant changes have been made to the Simulator Support Discs and tested satisfactorily, they are then designated the .

Training Discs, the Training Discs become the back up discs, and the back up discs are cold started from the Simulator Suoport disc tape save and designated the Simulator Support Discs. The simulator instructors are then briefed on the changes to the Training Discs since the last turnover.

NTl-'.5." -2 June 1989 ATTACHMENT B page 4 of 23

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RESPONS I 8 I L I TIES 4.1 Supervisor Simulator Technoloa (SST) (3 4.1.1 Responsible to the  : Assistant Training Superintendent 'for

'implementation of this pr'ocedure.

4.1.2 Directs the activities of all personnel assigned to simulator support.

4.1.3 Oversees all expenditures.

4.1.4 Maintains simulator usage schedule.

4.1.5 Documents ANS/ANSI 3.5 compliance.

4.1.6 Determines applicability of configuration management process steps 4.1.7 Pre'paration and submittal of NRC Form 474 for Simulator Certification and Recertificaiion.

4.2 Simulator 0 erator i3 4.2.1 Responsible to the Supervisor Simulator Technology for simulator

. i3 testing in accordance with this procedure.

4.2.2 Maintains simulator initial condition (IC) sets 1 through 20.

4.2.3 Prepares simulator test procedures as directed.

4.3 Simulator Software Engineer (3 4.3.1 Responsible to the Supervisor Simulator Technology for simulator i3 software changes and maintenance in accordance with this procedures 4.3.2 Document changes using embedded comments in model source code.

4.3.3 Maintains computer load balancing.

4.4 Simulator Hardware Specialist Responsible to the Supervfsor Simulator Technology for Hardware i3 changes and maintenance in accordance with this procedure.

4.4.2 Maintain simulator spare par:: inve".tory.

4.4.3 Maintain simulator consumable stock inventory.

4.4.4 Perform preventive maintenance.

NTI-4.5.3 -3 June 1989 ATTACHltENT l3 page 5 of 23

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4.5 Simulator Clerk 4.5.1 Responsible to the Supervisor Simulator Technology for: [3

a. Maintain controlled documents

b. Maintain simulator hard copy database C. Maintain simulator change database

d. Computer data entry in support of'this procedure 4.6 Lead Software En ineer /3 4.6.1 Responsible -;o the Supervisor Simulator Technology for. overall task /3 coordination on projects as assigned.

5.0 COMPUTER TRACKING 5.1 The Reference Plant dedicated computer should be used to track the following:

5.1.1 The Document Revision Difference between the Simulator Dynamic Database and the Reference Plant as-built database using the following programs:

Unit 1 controlled document" distribution CDD.NEH Unit 2 document control information system DCIS 5.1.2 Reference Plant Modifications as to simulator impact and integration using computer Databases.

Unit 1: Mods Unit 2: Modification Tracking J3 5.2 A computer tracking system should be used for the following:

5.2.1 Simulator implementation and cost accounting for Reference Plant Modirication and changes arfecting the simulator. /3 5.2.2 Simulator operating and maintenance cost accounting.

5.2.3 Discrepancy Reports (DR's) t3 5.2.4 Enhancement implementation and cost accounti'ng.

6.0 MODIFICATION PROCESS FIGURE 9 6.1 All Reference Plant Modifications assigned a Modification Number (MODNO) should have a preliminary review by the Supervisor Simulator Technology for simulator impact in accordance with Reference 2.5 and 2.6, within 3 months of issue Date ( ISSUEDATE) for Unit-1 and Assigned to MOD ENG Date (ASMODENG) for Unit-2, and shall be reviewed no later than 6 mon".hs following actual operations acceptance (AOPACCEPT).

NTI--".5.3 -4 June 1989 ATTACHMENT B page 6 of 23

A 6.1 (Cont'd)

If the modification impacts the simulator, a preliminary simulator implementation cost estimate should be supplied to the Mod. Fnginee" in accordance with Reference 2.5 and 2.6.

6.2 Modifications wi th no simulator impact shall be processed in /3 accordance with 6.2.1 no impact mods. Modifications with simulator impact shall be processed in accordance with 6.2.2, Rererence Plan".

Modifications impacting the simulator.

6.2.1 No impact mods refer to flow chart Figure 9 6.2.1.1 Supervisor Simulator Technology provides a brief modifi'cation )3 description, and reason for no impact under Remarks and Signature, Figure l.

6.2.1.2 SCCB Representative signs concurrence Figure 1, if he does not concur, the SCCB Board shall resolve.

J3 6.2.1.3 Update the Reference Plant Computer Modification Tracking System.

6.2.1.4 File the Modification Reference Drawings impacting the Simulator Dynamic Database in the Simulator Dynamic Database.

6.2.1.5 Update the Reference Plant Computer (COD.NEH or DCIS) simulator revision field to the modification reference drawing revision for drawings in the Simulator Dynamic Database.

6.2.1.6 File the Modification Review Form, Figure l.

6 ~ 2.2 Reference Plant Modifications impacting the simulator (refer to Flow Chart, Figure 9).

6.2.2.1 Prepare a simulator modification package for presentation to the SCCB which includes:

a. Modification Review Form, Figure 1, processed through the Supervisor Simulator Technology Signature. /3

b. Modification implementation cost estimate.

C. Modifications safety evaluation and source. documents as applicable.

6.2.2.2 If the SCCB recommends approval, the SCCB Chairman shall sign and set an implementation priority as follows:

7 Indicates SCCB order of preference for implementation. Mods wi th a priori ty = I should be implemented first, as simulator time is ava i 1 ab1 e, and shal 1 be imple...ented wi thin 12 months of the actual opera:ions acceptance date.

I NT -4.5.3 -5 June 1989 ATTACHMENT 8 page 7 of 23

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If 6.2.2.2 (Cont'd) a priority 1 mod has a significant impact on the completion or a Simulator Lesson Plan objective or critical step, the SCCB should assign a required Simulator implementation date along with the priority. The Supervisor Simulator Technology should then schedule work and simulator time to meet the required implementation date.

Indicates SCCB order of preference for implementation as simulator time is available, and shall be implemented within 12 months of the actual operations acceptance date.

Indicates SCCB order of preference ror implementation as simulator time is avai 1 able, and shal 1 be implemented within 12 months of the actual operations acceptance date.

6.2.2.3 If the SCCB does not recommend implementation, the SCCB Chairman shall sign and make a justification statement under remarks.

Administratively document as follows:

a. Generate Simulator Exceptions Sheet, Figure 8 and file in the ANS/ANSI 3.5 Reports, file.

b. Brief simulator instructors on the Exception.

C. Update the Reference Plant Computer (CDD.NEH or DCIS) simulator revision field to the modification reference drawings revision for drawings in the Simulator Dynamic Database.

d. File the Modification Reference Drawings impacting the Simulator Dynamic Database in the Simulator Dynamic Database.

e. Update the Reference Plant Computer Modification Tracking.

f. Process a Modification Closeout Form, Figure 2.

6.2.2.4 The Assistant Training Superintendent grants permission to commence work.

6.2 '.5 Supervisor -

Simulator Technology schedules and assigns work to 3

, implemen.t .modification.

6.2.2.6 Software modifications implemented on the Simulator Support Computer load and Software Change Report, Figure 4, generated if applicable.

6.2.2.7 Hardware modification implemented and Hardware Change Report, Figure 5, generated if applicable.

6.2.2.8 Nhen applicable sofiwar and hardware changes are implemented, test the modification in accordance with a Modification Test Procedure.

6.2.2.9 Correct and retest any priority 1 DR's generated against the . )3 modification.

3 6.2.2.10 Turnover modification to Training by performing a disc turnover to Training and update the rererence plant computer modification tracking implementation date.

NTI-4.5.3 -6 June 1989 ATTACHMENT B page 8 of 23

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6.2.2.11 Update the ANS/ANSI 3.5 Reports File with the modification number, description, generated exceptions, and simulator database Modifications Report, Figure 6.

6.2.2.12 When final reference plant close out documentation is received, review the as built data for simulator impact.

6.2.2.13 Update the Reference Plant Computer (CDD.NEW or DCIS) simulator revision field to the Modification Reference Drawing Revision for drawings in the Simulator Dynamic Database.

6.2.2.14 Update the Reference Plant Computer Modification Tracking Simulator close date.

6.2.2.15 File the Modi fi cation Reference as-bui t drawings impacting 1 the Simulator Dynamic Database in the Simulator Dynamic Database.

6.2.2.16 Process a Modification Closeout Form, Figure 2.

7.0 ENHANCEMENT PROCESS (Figure 10) 7.1 Simulator enhancements are generated by the originator submitting an Enhancement Request Form, Figure 3, to the Supervisor Simulator Technology.

7.2 The Supervisor Simulator Technology assigns an internal tracking number and submits Enhancement Requests wi th implementation cost estimate to the SCCB.

7.3 Enhancement Requests are reviewed by the SCCB.

7.3.1 If SCCB does not recommend implementation, the request is closed out with remarks by the Simulator Supervisor and a copy returned to the originator.

funding 7.3.2 If SCCB recommends implementation the SCCB Chairman signs and assigns an implementation priority.

'NOTE: Priorities falling within fiscal year without sufficient funding for the Enhancement wi 1 1 require special .

7.4 Recommended Enhancements are scheduled for implementation by the Supervisor Simulator Technology.

7.5 The Assistant Superintendent Training verifies funding and grants approval to commence work.

7.6 The Supervisor Simulator Technology schedules and assigns work to implement enhancement.

7.7 Software changes are made on the Simulator Support discs, and a Software Change Report, Figure 4, is generated if applicable to enhancement.

NTI-4.5.3 -7 August 1989 ATTACHMENT B page 9 of 23

1 7.8 Hardware Enhancement changes implemented and Hardware Change Report, Figure 5, is generated if applicable to enhancement.

7.9 Generate an Enhancement applicable to enhancement.

Test Procedure and test Enhancement 'f 7.10 Correct and retest any priority 1 OR's generated against the (3 enhancement.

'3 7.11 Turn, over to Training by performing a disc turnover to Training.

7.12 Update the ANS/ANSI 3.5 Reports File with the Enhancement Number, description, and Database Modification Report, Figure 6, as applicable.

7.13 Update the Reference Plant Computer (COD.)EN or OCIS) simulator revision field for Simulator Dynamic Database documents impacted by enhancement.

7.14 File enhancement source documents in the Simulator Dynamic Database as applicable.

7.15 Closeout enhancement tracking.

8.0 DISCREPANCY REPORT (DR) PROCESS (FIGURE 7) 8.1 DR's are generated to identify simulator modeling or hardware problems between the reference plant and the simulator.

8.2 The originator fills out the DR Form describing the problem, expected performance, and data reference, 8.3 The simulator instructor assigns a priority and processes as follows:

CAUTION:

HORKING ON THE TRAINING DISCS INVOLVES A RISK THAT AN ERROR BY THE SOFTHARE.. ENGINEER COULD CAUSE PROBLEMS SEVERELY'MPACTING TRAINING AND SIMULATOR AVAILABILITY.

~Priori t . i Indicates a requirement to make a change on the training discs. Hork should begin within 2 working "

days of DR verification. Assigning priority 1 should meet the following requirements:

Discrepancy prevents the performance of a critical step or completion of a objective in a Simulator lesson plan currently being taught.

2.'.

Must not be a reference plant modification scheduled for simulator implementation Must not be existing Priority 2 or 3 NTI-4.5.3 -8 June 1989 ATTACHMENT page 10 of 23

1 ~

4. Should be hand delivered to the SST or his designee by the originator on the date written S. Should be entered into DR tracking sys tem anc ve: sfied'it>> n "

working days of delivery to the SST

~Priorit 2 indicates the order of preferenc for work. Priority 2 DRs should be corrected wi thin 6 months o, origination date, depending on simulator availability If a priority 2 DR has a significant impac". cn the completion of a simulator lesson plan or object'"e or critical step scheduled to be taught within the next 3 months, the first date the lesson plan is t be taught should be identified on the DR and brought to the attention of the Supervisor Simulator Technology

~Priorit 3 Indicates the order or preference for work. Priority-3 DRs should be corrected within 12 months of origination date, depending. on "simulator avai labi i ty 1 8.4 The DR is assigned a tracking number, verified and validity checked against the current simulator database by the Simulator Support Groups 8.5 The DR corrective work is performed on the Training Disc Packs for

'priori ty 1 DRs, and on the Simulator Support Di sc Packs for priority - 2 and 3 DRs. Corrective action comments are'ade on the DR Form, and the DR is submitted f'r recheck.

8.6 Independent DR correction recheck is performed. Accepted priority 1 DRs are closed and filled in archives, accepted priority 2 or 3 DRs are placed on hold until the next disc turnover then closed and filled in archives.

8.7 Simulator instructors are briefed on DR correction at disc turnowver, to training.

9.0 COST ACCOUNTING 9.1 'Reference Plant Modification

~

, Simulator modification and testing should be changed to the.

major order number of the reference plant modification.

~ The modification engineer is responsible for including the simulator modification cost into the overall modification cost estimate in accordance with Reference 2.S and 2.6.

NTI-4.S.3 -9 June 1989 ATTACHMENT B page 11 of 23

9.2 Simulator operating and lease agreement major order. Fund -..ne following:

~ Preventive and corrective maintenance costs

~ Consumable material

~ Operating time costs when operated by General Physics Corporation Instructors in approved Niagara Mohawk Training Programs 9.3 The annual simulator budget funds the following:

~ Discrepancy Report (DR) correction

~ Enhancements

~ Reference plant modifications not funded by reference plant Mod Major Order number, i.e., Major Order Account already closed f3 10.0 REFERENCE PLANT OPERATING PROCEDURE SIMULATOR EXCEPTIONS 10.1 The simulator should be capable of operation in accordance with reference plant operating procedures. The followi'ng describes the process to keep simulator instructors informed of differences.

10.2 If a Control Room manipulation cannot be performed in the simulai:or in accordance with the reference plant operating procedure, a simulator exception form (Figure 11) should be initiated.

10. 3 The SCCB chairman should approve or disapprove the exception. ,/3 10.3.1 If approved the exception should be filed in the "instructor Station (3 Procedure Exceptions Book: which is located at the instructor console.

10.3.2 If disapproved, the Supervisor Simulator Technology shall generate an (3 enhancement request in accordance with Section 7.0, and file exception form in the "Instructor Station Procedure Exceptions Book" until the enhancement is incorporated into the Simulator Computer Training Load.

NT:-4.5.3 -10 June 1989 ATTACHtlENT page 12 of 23

FIGURE 1 MODIFICATION REVIEN FORM Reference Plant Modification Control/internal Tracking Number Brief Description of Modification:

This modification does/does not impact on the configuration of the simulator. Supervisor Simulator Dare (circle one) Technology Remarks:

Does not impact concurrence SCCB Representative Date Simulator Configuration Control Board This modification is/is not recommended

, for implementation into the simulator. SCCB Chairman Date Remarks Priority Sci'vied Implementation Date Supervisor Simulator Date Technology Permission granted to commence work.

Assistant Training Superintendent Da.e I3 NTI-4.5.3 -ll June 1989 ATTACHMENT page 13 of 23

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FIGURE 2 SIMULATOR MODIFICATION CLOSEOUT FORM Modification/Internal Tracking 0 Initial Date

1. Software Change Report

2. Hardware Change Report

3. Acceptance Test Procedure complete Im DR's corrected.

4. Simulator Instructor's Briefed.

5. Turned over to Training.

6. Remove, applicable simulator procedure exception forms.

7. ANS/ANSI 3.5 File updated.

8. Dynamic Database updated Hard copy Reference Plant Computer

9. Reference Plant computer Mod Tracking updated

10. Modification Package and Applicable Source Documents filed in archives.

Modification Closed Out Supervisor Simulator/ Date Technology NTI-4.5.3 -12 June 1989 ATTACHMENT B page 14 of 23

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FIGURE 3 ENHANCEMENT RE UEST FORM Tracking ~

Name Date

.Originator Description of Enhancement:

Reason Enhancement is Heeded:

Simulator Configuration Control Boarc This enhancement is/is not recommended for implementation into the simulator. SCCB Chairman Date Priority Assigned Scheduled for implementation on Date Supervisor Simulator Date Technology Approval to commence work.

Assistant Superintendent Training Da=<

NTI-4.5.3 -13 June l989 ATTAC11MENT B page 15 of 23

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FIGURE 4 SOFTHARE CHANGE REPORT HORY PACKAG. NUMBER AFFECTED SYSTEM MODULE USER REMARKS/NOTES Ini tial Date Final Design Specification Update modification summary in header of each source file changed.

Move all sources to ODS/System level, delete user and superceded source files.

Place drawing, sketches, or engineer's notes in three ring binder for future reference.

Update Source Code Hanging File Folders Chances Documented Using embedded Source Code Comments in the Manual Simulator Sor tware Date Engineer NTI-4.5.3 -14 June 1969 ATTACilliENT 3 page 16 of 23

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tl FIGURE 6 DATA BASE MODIFICATION REPORT Data Base Modification is the result of:

( (

Plant Modification

( Discrepancy Report ¹

(

Enhancement Request ¹ Data Base Changes Document Section Revision

'NTI-4.:".3 -16 June 1989 ATTACHMENT 'B page 18 of 23

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FIGURE 7 DISCREPANCY REPORT PRI ORIGINATOR TRACKING NUMBER PLANT CONDITION SYSTEM DATE NATURE OF PROBLEM OBSFRVED:

EXPECTED:

DATA REFERENCE (print¹, OP¹, plant" )

(" Plant" must be supported by a site contact)

PROBLEM VERIFIED Problem valid for current YES Simulator data base YES NO INITIAL DATE CORRECTIVE ACTION/REMARKS RECHECK ACTION Rejected By NAME DATE (Reason) 0 0 0 0

• Jr 0 k0 w m

• k k 0

• k 0 **x 0 0

• i 0 0 ++ *****4k 0

• 0 k

• 0 0

• i'*0' r w ****k 0 0 k 0 0 0 4' **k 0 g *

• 0 **i 0* 4 0 Accepted By NAtl= DATE Update DR Tracking INITIALS DATc NTI-4.5.. -l7 June !989 ATTACHHENT B page 19 of 23

FIGURE 8 Nine Mile Point Unit Simulator Exceptions Sheet Mod Control No:

Date:

DESCRIPTION OF SIMULATOR AND PLANT DIFFERENCES:

JUSTIFICATION/RATIONALE FOR DIFFERENCES:

III. SIMULATOR DATABASE REFERENCES IMPACTED AS A RESULT OF EXCEPTION:

NTI-4.5.3 -18 June 1989 ATTACHMENT B page 20 of 23

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,FIGURE 9 S IvIULATOR k)OD F CA, ON PROCESS REF PLANT GENERATE TURN INSTRUCTOR MOD g EXCEPTION OVER TO BRIEF ASSIGNED REPORT TRAINING UPDATE APPROVAL ANS/ANSI 3.5 PRELIM REVIEW OM ACIUAL FILE IMPACT TO tP/ORK REF PUNT MOD CLOSEOUT UPDATE SCHEDULE COMPUTER PRELIM COST 8c ASSIGN SIM REV ESTIMATE TO MOD ENG zs III/ORK APPROVAL

?

UPDATE COMPUTER MOD TRACKING ACtUAL iKF PLAhV ILIPLE S!IIIAIOR UPDATE IMPACT DYNAMIC NO  ? DATA BASE TEST SAT NO ovum NO  ?

DR 2

YES MOD CLOSEOUT Y"-S FORM CQ.'!. LE!. 0 ARCHNES HT:--':.5.3 -19 June 1989 ATTACHMENT B page 21 of 23

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4 FIGURE 10

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I I II TURN ENHANCEMENT INSTRUCTOR APPROVAL OVER TO REQUCST BRIEF TO Itj/ORK TRAINING TRACKING g ASSIGNED UPDATE

'IMPL'EMENTATION ANS/eSI S.5 COST ESTIMATE SCHEDULE Ec ASSIGN Y/ORK

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t UPDATE scca COMPUTER APPROV~

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I UPOATE I

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I TEST NO DATA BASE I SAT OR I

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I I MOD CLOSEOUT I

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L~~~~ ARCHIYES COMPLilEI'ITI-4.5.3

-20 June 1989 ATTACHMENT 'B page 22 of 23

I FIGUR I )

REFERENCE PLANT OPERATING PROCEDURES SIMULATOR EXCEPTION FORM PROCEDURE NUMBER:

EXCEPTION DESCRIPTION:

EXCEPTION HRITTEN BY: DATE:

SCCB Exception Approval SCCB Chairman Date SCCB Exception Disapproval SCCB Chairman Date Enhancement Request 4 or disapproved exceptions Supervisor Simulator Technology Date /3 NTI-4.5.3 -21 June 1989 r 0 ATTACHMENT B page 23 of 23

Page No.

07/09i90 NHP UNXT-2 SXHULATOR MALFUNCTXOHB TEST YEAR 2990 MALFUNCTION NUMBER AD02 ADS FAILS TO INITIATE AD03 ADB/RELIEF UALVE FAILURE- STUCK tl-18 QR AHY OR ALL)

CS02 HIGH PRESSURE CORE SPRAY tCBH) FAZLS TO AUTO START CB03 HIGH PRESSURE CORE SPRAY tCSH) DIESEL EHGXNE FAILURE CS06 LOM PREBBURE CORE SPRAY tCSL) PUHP TRIP CU05 REACTOR MATER CLEANUP tMCB) FILTER DEHXHERALIZER RESIN DEPLETXON CU07 COOLANT LEAK OUTSIDE PRIHARY COHTAIHHEHT CM03 TURBINE BUXLDING CLOSED LOOF COOLING MATER tCCB) PUMP TRIP ED01 HAXH TRANSFORHER LOSS OF COOLING ED02 LOSS OF OFFSITE 125KV FOMER SOURCEtB) tLXHE 5/6)

ED06 600 U NORHAl BUB tHJS) FAULT t2HJB-UB1 --> US10)

EDll 24 VDC NORHAL BATTERY BUS FAULT t3A or 3B)

EG13 MAXN GENERATOR LOSS QF LQAD EG14 HAIN GENERATOR AVR FAILURE OSCZLLATEONB FP02 CONTROL ROOH FIRE DETECTOR FAILURE FP16 FIRE AT TURBINE BEARING 4 8 FM01 COHDEHBATE PUHP TRXP tA, BiC or AHY)

FEEDMATER PUHP TREF thi B,C, OR AHY)

FM06 FEEDMATER LOM PRESSURE LOM FLOM Uhl UE t LV137) FAXLURE AB ES FM23 COHDEHBATE DEMIHERALEZER HIGH DXFFERENTZAL PRESSURE FM27 FEEDWATER HEATER DRAXH PUHP TRIP FM31 FEEDMATER LIHE BREAK INSIDE DRYMELL HC02 HAXN CONDENSER AXR EHLEAKAGE MS03 STEAH LEAKAGE INSIDE THE PRXHARY CONTAINMENT HB05 HAXN BTEAH LINE IBOLATIOH VALUE FAILURE OPEN MB07 TURBINE BTEAH SEAL REGULATOR FAILS CLOSED HB10 LOSB OF EXTRACTION BTEAH TO FEEDMATER HEATER MB13 MBXV ISOLATIOH FAXLURE NM01 SOURCE RANGE MONITOR CHANNEL FAXLURE UPSCALE NH05 SOURCE RANGE HOHXTOR CHANNEL DETECTOR STUCK NM09 XHTERMEDIATE RANGE MONITOR CHANNEL FAILURE INOPERATIVE NH24 LOCAL PQMER RANGE HQNXTOR FAILURE tX-Y-J) - UPSCALE HM16 ROD BLQCK HONZTOR CHANNEL FAILURE UPSCALE HH22 LPRM FAELURE DRIFT ~ OR 25K RC01 REACTOR CORE ISOLATEOH COQLIHG AUTQ START FAXLURE RC05 REACTQR CORE IBQLATXON COOLING SYSTEM TURBINE SPEED COHTRQLLER FAXLURE AB XS RC09 REACTQR CORE ISOLATZOH COOLING FLOM TRAHBHXTTER FAILURE AS XB RD02 RQD DRXVE CONTRQL SYSTEM FAILURE TXHER HALFUHCTIOH ATTACE1ENT C Page 1 of 8

Page Ha.

07)09)90 HMP UNIT-2 BIHULATOR HALFUNCTIONB e MALFUNCTION TXTLE NUMBER TEST YEAR 2990 RD03 ROD DRIVE CONTROL SYSTEH FAILS TO ZHBERT RD04 CONTROL ROD FAZLURE fXX-YY) DRIFT XH RD08 CONTROL RQD <XX-YY) FAXLURE UNCOUPLED RD23 CONTROL ROD DRIVE FLOM CONTROL VALVE FAILURE OPENED RD26 SCRAM DXSCHARGE VOLUME RUPTURE RH02 REBXDUAL HEAT REHOVAL PUMP TRIP tA, B,C, OR AHY)

RH03 RESIDUAL HEAT REMOVAL STEAM DUMP VALVE FAXLURE CLOBED RP02 BPURIOUB REACTOR BCRAH RP02 REACTOR PROTECTZQH SYBTEH FAILURE TO SCRAH AUTOMATXC RPQS LQBS OF NORHAL POMER TO RPB CHANNEL RP21 RRCB FAILURE QF RECIRC PUMP TRIP/DOMNBHZFT RR02 REACTOR RECIRCULATION HASTER FLOW COHTRQLLER FAILURE-LQM RR06 REACTOR RECIRCULATION LOOP FLOM CONTROLLER FAILURE AB IB RR07 REACTOR RECIRCULATION FLOM UNIT FAXLURE UPSCALE RR20 REACTOR RECIRCULATION PUMP BKR TRXP RR2S FAILURE OF REACTOR RECIRC PUHP INNER BEAL RR22 REACTOR VESSEL PREBBURE RECORDER FAXLURE DOMHBCALE RR26 REACTOR VESSEL PRESSURE IHDXCATOR FAXLURE AB IB ROD MORTH MINIMIZER FAILURE FUEL CLADDING FAXLURE INCREASED ROD MORTH FOR AHY CONTROL ROD IXX-YY)

TC03 EHC SYSTEH STEAH PRESSURE REGULATQR FAILURE OBCZLLATXON TCQS HAIN TURBIHE BYPASS VALVE FAILURE - CLOSED TU04 EXHAUST HQQD SPRAY VALVE FAILURE CLQSED TUQS MAZH TURBXHE BEARXHG OXL PRESSURE LOW.

ATTACEfENT C Page 2 of 8

Page No.

07/09/90 HMP UNIT-2 SEMULATOR MALFUNCTIONS 4 MALFUNCTION TXTLE NUMBER TEST YEAR 2991 AD04 ADS/RELIEF VALVE FAXLURE- LEAKS tL-28 QR AHY QR ALL)

CS04 HIGX PRESBURE CORE SPRAY tCSH) INJECTXQN VALVE FAXLS TQ OPEH CB07 LQM PRESSURE CORE BPRAY tCSL) XHJECTXGN VALVE PAILS TO OPEN CU02 REACTOR MATER CLEAN-UP PUMP TRIP CU02 REACTOR MATER CLEANUP DRAXH FLOM COHTROL VALUE FAXL-OPEN CMQL SERUICE MATER PUMP TRXP tAHY OR ALL)

CM04 CXRCULATZHG MATER fCMS) PUMP TRIP DG01 DIESEL GENERATOR FAXL TO BTART ED03 13 8 KV BUB fNPB) FAULT fSMGR 001, 002, 003)

ED07 600 U EMERGENCY BUB tEJB) FAULT t USL AHD/OR US3)

EGOL MAXN GENERATOR TRIP EG02 MAXN GENERATOR AUTO UGLTAGE REGULATOR FAXLURE INCREASE EGOB HATH GENERATOR AHD EMERGENCY HYDROGEN SEAL OXL PUMP FAILURE FP03 TURBXHE BUELDXNG FXRE DETECTOR FAXLURE FP07 EHGIHE DRIVEN FXRE PUMP FAXLURE FP15 FIRE XN NORMAL STATXOH BERUICE TRANSFORMER t2BTX-XHBL)

FP17 FXRE ZN DXVXBXON ZZ DIEBEL ROOM FP19 FXRE XH RELAY ROOM PM02 CONDENSATE BOOSTER PUMP TRIP tA, B C or AHY)

FEEDMATER HIGH PRESSURE LOM FLQM VALVE tLU55A or B) FAXLURE OPEN FM20 FEEDMATER HIGH PRESBURE HEGH FLOM VALVE FAILURE OPEN t Ap Bp C or ANY)

FM14 FEEDMATER MASTER CONTROLLER FAELURE LOM FM15 FEEDMATER MASTER CONTROLLER FAELURE AS EB FM24 CONDENSATE RECIRCULATION VALVE FAELURE OPEN REACTOR VESSEL LEUEL HARRQM RANGE TRAHBMXTTER FAILURE PM'M32 UPSCALE FEEDMATER LINE BREAK IHBXDE STEAM TUNNEL FM33 FEEMATER CHECK VALVES PAXL OPEN MC03 HOTMELL LEVEL CONTROLLER FAXLURE HIGH MS04 STEAM LXHE RUPTURE XHSXDE PRXMARY CQHTAXNMENT MS11 LOSB OF STEAM TQ MOZSTURE SEPERATOR REHEATER tA, B, OR BOTH)

HM02 SOURCE RANGE MOHXTER CHANNEL FAXLURE DOMHSCALE HM06 INTERMEDIATE RAHGE MONITOR CHANNEL PAXLURE UPSCALE HMLO ZHTERMEDXATE RANGE MOHETOR CHANNEL DETECTOR STUCK HM15 LOCAL PQMER MONITOR FAILURE DOMNBCALE tX-Y-J)

HM17 ROD BLOCK MOHETQR CHAHHEL FAILURE DOMHSCALE HM23 APRM UPSCALE HEUTRGN TRXP OGOL EXPLOBIOH XH AIR EJECTOR DISCHARGE PIPING PC02 PRIMARY COHTAXNMENT LEAKAGE PC03 PRIMARY COHTAIHMEHT EBOLATIQN ATTACHMENT C Page 3 of 8

Page No.

07 /09I'90 HHP UNIT-2 BXHULATQR HALFUNCTXOHB TEST YEAR 2991 HALFUNCTXOH TITLE NUHBER RC02 REACTOR CORE ZSOLATION COOLING FAILURE ISOLATION QF RCEC BYBTEH RC06 REACTOR CORE ISOLATIOH COOLZNG TURBXHE TREP RC22 RCIC STEAH LEAR IN REACTOR BUILDEHG ELEVATIQN 215 RD05 CONTROL RQD FAILURE (XX-YY) DRIFT OUT RD09 CONTROL ROD FAILURE tXX-YY) SCRAMHED RD11 CONTROL ROD XX-YY FAXLURE RPZB RHQS REBEDUAL HEAT REMOVAL HEAT EXCHANGER LEVEL CONTROLLER FAXLURE UPSCALE RP03 REACTOR PROTECTXON SYSTEH FAXLURE TO SCRAM RP07 RRCB 25 BECOND TIMER FAXLURE RP09 RRCS SPURXOUS XHXTXATXQH RP12 RRCB DXVZSIOHAL FAXLURE RR03 REACTOR RECZRCULATZOH HASTER FLOM CONTROLLER FAILURE AS ZS RR08 REACTOR RECIRCULATXON FLQM UNIT FAILURE - DO'l4HSCALE RR12 REACTOR RECIRCULATION PUMP SEIZURE RECXRCULATIOH PUHP UPPER BEAL FAILURE REACTOR VEBBEL PRESSURE RECORDER FAXLURE- AS IS ROD SEQUENCE CONTROL SYBTEH TOTAL FAILURE CHANGE EH CORE REACTEVZTY BLC PUMP SUCTION VALVE FAXLS TO OPEN HAIN TURBINE ACCELERATZON COHTROL FAILURE TC05 ALL TURBINE BYPASS VALVEB FAXL OPEN TC09 NUMBER QNE TURBINE BYPASB VALVE FAILURE STICKS OPEN TU02 MAIN TURBINE BEARZHG HIGH TEMPERATURE TU06 HAIN TURBXNE THRUST BEARENG NEAR.

ATTACHMENT C Page 4 of 8

Page Ho.

07/'09/'90 NMP UNIT-2 SIMULATOR MALFUNCTIONS TEBT YEAR 1992 MALFUHCTXON NUMBER AD02 RELXEF VALVE FAILURE t2-28 QR AHY OR ALL)

AD05 ADS/RELIEF VALVE FAILURE- OPEN i2-28 QR AHY OR ALL)

CS05 HIGH PRESSURE CORE BPRAY <CSH) PUMP TRIP CU03 REACTOR MATER CLEANUP DRAXH FLOW CONTROL VALVE FAXL-CLOSED CU06 REACTOR MATER CLEANUP NOH-REGENERATIUE HEAT EXCHANGE TUBE LEAK CU08 REACTOR MATER CLEAHUP (MCS) ISOLATZOH FAXLURE CM05 CXRCULATING MATER EXPAHBION JOINT LEAKAGE DQ02 DIESEL GENERATOR TRIP ED04 4.16 KV NORMAL BUS iNHB) FAULT ( SMGR 11 --x 28 )

ED08 125 UDC NORMAL BUS (BYB) FAULT t SMQR 00lh, B,C )

EG03 MAIN GENERATOR AUTQ VOLTAGE REGULATOR FAILURE DECREASE EG04 MAIN GENERATOR CQRE INTERNAL HEATIHG EQ06 ~

MAIN GENERATOR STATOR COQLXNG PUMP TREP <A/B)

EG09 TURNING GEAR OEL PUMP FAELURE EG12 POMER GRID HETMORK LQAD TRANSIENT DECREASE FP04 DIESEL ROOM FIRE DETECTOR FAILURE FP08 ELECTRIC FIRE PUMP FAILURE LOBB OF C02 FROM BTORAGE TANK (TK1, TK2, BOTH)

HOSE REEL FOAM COHCEHTRATE PUMP FAILURE llh, 1B, BOTH)

FXRE ZN DIVISZOH E BATTERY RQOM FM04 FEEDMATER LOM PRESSURE LOM FLOM UALUE iLU237) FAXLURE QPEN FW08 FEEDWATER HIGH PRESSURE LOM FLOM UALUE <LV55A and/or B)

FAXLURE CLOSED FM11 FEEDMATER HXGH PRESBURE HIGH FLOM UALVE FAXLURE CLOSED ih, B C or AHY)

FM16 FEEDMATER PUMP RECIRCULATION Vhl VE FAELURE OPEN FM20 COHDENBATE DEMXHERALXZER RESIN DEPLETZQN FM25 CONDENSATE RECIRCULATION VALVE PAXLURE CLOSED FM29 REACTOR VESSEL HARROW RANGE TRAHSMZTTER FAILURE - DOMHSCALE MC04 HOTMELL LEVEL CQHTROLLER FAILURE LQM MB01 STEAM LEAKAGE OUTBIDE PRIMARY COHTAINMEHT MB09 MOISTURE SEPARATOR REHEATER HXGH LEVEL (A, B, OR BOTH)

MB12 REACTOR VESSEL ISOLATXON HM03 BRM RECORDER FAXLURE HM07 INTERMEDIATE RANGE MONITOR CHANNEL FAILURE - DQMNBCALE HM22 AVERAGE POMER RANGE MONITOR CHANNEL FAXLURE UPSCALE NM19 ROD BLOCK MONITOR FAELURE NM20 AVERAGE POMER RANGE MONITOR CHANNEL FAILURE OG02 OFFQAS RECOMBZHER PREHEATER STEAM SUPPLY VALUE FAXLURE CLOBED PC04 STANDBY GAB TREATMENT TRAXN EXHAUST FAN TRIP ATTACHMENT C Page 5 of 8

Page Nu.

07/09'0 NHP UNXT-2 SIMULATOR MALFUNCTZONB TEST YEAR 1992 HALFUNCTION TZT1 E NUHBER PC06 SECONDARY CONTAINHENT ISOLATION FAILURE RC03 REACTOR CORE ISOLATION CQOLXNG TURBXNE SPEED CONTROLLER FAXLURE HIGH RC07 REACTQR CORE ISOLATEON COOLENG FLOM TRANSMITTER FAXLURE HIGH RD06 CONTROL ROD FAXLURE tXX-YY) ACCUHULATQR TROUBLE RD10 CQNTRQL ROD FAXLURE tXX-YY) GLOM BCRAH TIME RD12 CRD FEED PUHP TRXP RD15 LQBB OF INSTRUHENT AXR PREBSURE RH06 REBXDUAL HEAT REMQVAL HEAT EXCHANGER LEVEL CONTROLLER FAILURE DOMNSCALE RP04 ANTICIPATED TRANBXENT MITHOUT SCRAH RPOS RRCS 98 SECOND TXHER FAILURE RP13 RRCB INADVERTENT ALTERNATE ROD XNSERTXON RR04 REACTOR RECIRCULATXQN LOOP FLOM CONTROLLER FAXLURE HIGH RR09 REACTOR RECIRCULATION FLQM UNET FAILURE AB ZB RR12 REACTOR RECXRCULATZON LQM FREQUENCY HOTOR GENERATOR SET DRIVE HOTOR BKR TRIP REACTOR RECIRCULATION LQM FREQUENCY HG SET VOLTAGE REGULATOR FAILS LQM RR1B JET PUHP FAILURE RR19 COOLANT LEAKAGE INSIDE PRIMARY CONTAINHENT RR24 VEBSEL PREBSURE ZNDXCATOR FAILURE UPSCALE RX04 CORE PO'MER INBTABXLXTY MHEN OPERATZNG IN THE RESTRICTED 2QNE TC01 EHC SYSTEM PRESSURE REGULATOR FAELURE HIGH TC06 ALL TURBXNE BYPASS VALVES FAIL CLOSED TC10 HAIN TURBXNE GOVERNOR FAXLURE HIGH TC12 HAIN TURBINE CONTROL VALVE FAXLURE - CLOSED TU02 HAXN TURBINE BEARXNG HXGH VZBRATEON TUO'7 SPURXQUB HAIN TURBINE TREP ATTACHMENT C Page 6 of 8

Page Ho.

07/09/90 NMP UNIT-2 BXHULATQR HALFUHCTEQHS TEST YEAR 1993 HALFUNCTXON NUMBER AD06 TMI ACCIDENT BMR EQUIVALENT CB01 HIGH PRESSURE CORE SPRAY tCBH) INADVERTENT INITZATEQN CU04 REACTOR MATER CLEANUP DRAIN FLOM CONTROL VALUE FAIL-AS XS CM02 REACTOR BUILDING CLOSED LOOP COQLZHG MATER tCCP) PUMP TRIP DG03 DIEBEL GENERATOR LOAD SEQUENCE TXHER FAXLURE tDEV I / XE)

EDOS 4 16 KU EMERGENCY BUB f EHB) FAULT f 201 f 202g 1Q3)

ED09 125 VDC EHERGENCY BUB FAULT t2BYS~SWG002A, B or C)

EGOS HAXH GENERATOR HYDROGEN COOLXHG SYBTEH LEAKAGE EG07 HAIN GENERATOR STATOR CQOLIHG DEHXHERALXZER RESIN DEPLETION EG10 POMER GRXD HETMQRN LOAD TRANSIENT- INCREASE EG12 HAXH GENERATOR ZBOPHABE BUS DUCT FAH TRIP fA/B)

FP01 TURBXHE IBLAND FIRE DETECTOR FAILURE FPQS CABLE SPREADING ROOH FXRE DETECTOR FAXLURE FP06 REACTOR BUILDING FXRE DETECTOR FAXLURE FP09 AUXILIARY FXRE PUHP FAXLURE fA, B, BOTH)

FP12 FIXED BYSTEM FOAH CONCENTRATE PUMP FAXLURE flA, 1B, BOTH)

FP14 HALON BANN FAILURE FEEDMATER LOW PRESSURE LQM FLOM UALVE tLV137) FAXLURE CLOBED FM09 FEEDMATER HIGH PREBBURE LOM FLOW CONTROL UALVE tLUSSA and/or B) FAILURE AB EB FW12 FEEDMATER HIGH PRESSURE HIGH FLOM VALVE FAILURE AB IS fA, B C or ANY)

FM13 FEEDWATER HASTER CONTROLLER FAXLURE HIGH FM22 FEEDMATER HEATER TUBE LEAN-FEEDMATER HEATER fA2, Bl,C2)

FW26 CONDENSATE RECIRCULATION VALVE FAILURE AB XS FM30 REACTOR VESSEL NARROW RANGE TRAHBHXTTER FAELURE - AB IS EA02 LOBB OF XNBTRUMEHT AIR MC02 HAIN CONDENSER TUBE LEAR HCOS HQTMELL REFLOOD VALVE FAIL-OPEN HB02 STEAH LINE RUPTURE OUTBXDE PRIMARY COHTAINMEHT fDBA)

HS06 HAIN STEAH LINE ISOLATION VALVE FAELURE CLOSED M Oe STEAH JET AXR EJECTOR STEAH SUPPLY UALUE FAILURE CLOSED HH04 SRH CHANNEL INOPERATIUE NHOe XHTERHEDXATE RANGE RECORDER/APRH RECORDER CHANHEL FAELURE INOPERATXVE HH12 AVERAGE POWER RANGE HONZTOR CHANNEL FAXLURE DQMNBCALE NH21 TRAVERSXNG IH-CORE PRQBE FAILURE STUCK IH CORE QG03 QFFGAB DISCHARGE ISOLATZQN VALVE FAELURE CLOSED PC01 LOSB OF DRYMELL CQOLING PCQS DBA HYDROGEN RECOHBIHER BLOMER FAILURE ATTACHMENT C Page 7 of 8

E* ~ ~ 4 Page Ho.

07/09/90 HMP UNIT-2 SXHULATOR HALFUHCTXONB 0 HALFUNCTXON NUHBER TEST YEAR 1993 RC04 REACTOR CORE ISOLATIQH CQOLIHG TURBXNE SPEED CONTROLLER FAILURE LOM RC08 REACTOR CORE ISOLATION COOLING FLOM TRANSHXTTER FAILURE LOW RC10 REACTOR CORE ISOLATEOH COOLING SYSTEH SPURIOUB IHETXATZOH RCll RCIC ZSOLATIOH FAXLURE RD01 ROD POBITION INFORHATIOH BYSTEH FAXLURE IHQP RD07 CONTROL ROD FAILURE <XX-YY) STUCR RD14 CRD FLOM CONTROL VALVE FAXLURE CLOBED RD17 PARTIAL XNBERTZQH OF QNE BANK OF CONTROL RODS UNDER SCRAH CQNDITIONB RH02 REBZDUAL HEAT REHOVAL LQM PRESSURE COOLANT INJECTION VALVES FAILS TO QPEH RH04 RESIDUAL HEAT REHOUAL HEAT EXCHANGER TUBE LEAR RP06 LOSB OF HQTOR GEHERATOR RP10 RRCS FAELURE OF FMC RUNBACK RP14 RRCB ARX FAILUREjDEFEATED RR01 REACTOR RECIRCULATXOH HASTER FLOM CONTROLLER FAXLURE-HEGH RR05 REACTOR RECIRCULATION LOOP FLOM CONTROLLER FAXLURE LQM REACTOR RECZRCULATZQH PUHP HXGH BPEED TO LQW SPEED AUTO TRANSFER INCOMPLETE RR17 REACTOR RECZRCULATEOH PUHP DEBCHARGE VALUE FAXLURE RR20 REACTOR RECXRCULATEOH LOOP RUPTURE DBA LQCA RR21 REACTOR VESSEL PREBSURE RECORDER FAILURE -UPSCALE RR25 REACTOR VESSEL PRESSURE INDXCATOR FAILURE - DOMNBCALE RM02 ROD SEQUENCE COHTROL SYSTEM FAILURE DOEB HOT ENFORCE NOTCH LOGXC BL01 STANDBY LIQUXD CONTROL PUHP TRIP BL02 2BLB-VEX3A, 2SLS-VEX3B QR BOTH FAIL TO FXRE MHEH SLC PUHP ZS TURHED OH TC02 EHC SYSTEH PRESSURE REGULATOR FAXLURE LOM TC07 HAZH TURBXNE BYPASS UALVE FAILURE - OPEN TC11 HAXN TURBXHE GQUERHOR FAXLURE- LOM TU03 HAIN TURBINE HIGH ECCEHTRXCXTY ATTACHMENT C Page 8 of 8

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N1NE MILE POINT UNIT 2 MALFUNCTION CAUSE AND EFFECTS MALFUNCTION TITLE/RANGE/CAUSE AND EFFECT CW01 SERVICE WATER PUMP TRIP (Ag Bg C/ Dg Ef F OR ANY)

DiSCRETE TYPE'AUSE:

INSTANTANEOUS CURRENT OVERLOAD ON MOTOR PLT STA: ANY WITH SERVICE WATER SYSTEM OPERATiNG MOTOR CURRENT WILL SPIKE UPSCALE, THEN FALL TO ZERO AS

'FFECTS'UMP THE AFFECTED PUMP BREAKER TRIPS AS SHOWN ON AM-2SWPA51 ON P601. IF THE OPERATOR MANUALLY STARTS A STANDBY SERVICE WATER PUMP, SYSTFM PRESSURE AND FLOWS WILL RETURN TO NORMAL.

DISCHARGE FLOW FROM THE AFFECTED PUMP FALLS TO ZERO AS INDICATED ON 2SWP*FI96A LOCATED ON P601, SERVICE WATER DISCHARGE HEADER PRESSURE WILL DECREASE IF A SIGNIFICANT

'SERVICE'ATER DEMAND EXISTS 'HIS'ZLL BE INDICATED ON 2SWP*PI2A(B) ON P601. THE AFFECTED SERViCE WATER PUMP SUCTION PRESSURE INDICATOR 2SWP*PI4A (B,C,D,E,F) WILL RETURN TO A STATIC CONDITION. THE AFFECTED SERViCE WATER PUMP DISCHARGE PRESSURE INDICATOR FALLS AS SHOWN ON 2SWP*PI6A(B).

THE FOLLOWING ANNUNCIATORS ARE EXPECTED AS A DIRECT RESULT OF THIS MALFUNCTION:

601114 SER WTR PUMP lA/1C/1E MOT/FEEDER ELEC FAULT 601116 SER WTR PUMP lA/1C/1E DISCHARGE FLOW LOW 601217 SER WTR PUMP 1B/1D/1F MOT/FEEDER ELEC FAULT 601219 SER WTR PUMP 1B/1D/1F DISCHARGE FLOW LOW OTHER ANNUNCIATORS WILL BE A FUNCTION OF PLANT STATUS AND SYSTEM LINE-UP AT THE TIME'HE MALFUNCTiON IS ENTERED.

REMOVAL OF THIS MALFUNCTION WILL RETURN THE AFFECTED PUMP(S)

TO NORMAL.

REFERENCES:

2IHC-3, ESK-SSWP01,03,07, LSK-9-10, LSK-24-9.4C, 2SWP-2 Attachment D page 1 of 3

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NINE MILE POINT UNIT 2 SIMULATOR TEST (ATP) DATE: 11/15/89 COOLING WATER SYSTEM PAGE: 1 SERVICE WATER PUMP TRIP REV: 2 MALFUNCTION CH01 SERVICE HATER PUMP TRIP (Ag B g Cg D ~ Eg F OR ANY) 01 INITIALIZE THE SIMULATOR TO A FULL POWER IC (PCM) AND NOTE THAT THREE INITIAL DATE SERVICE WATER PUMPS ARE OPERATING IN I

DIVISION AND TWO XN DIVISION IX (P601) 02 ACTIVATE MALFUNCTION CWOlA (PCM) AND VERIFY THE FOLLOWING RESPONSES ON P601: INITIAL DATE DISCHARGE FLOW ON 2SWP*FI96A FALLS TO ZERO HEADER DISCHARGE PRESSURE 2SWP*PI2A MAY

- ~':DECREASE..(DEPENDING ON LOAD)

SUCTION PRESSURE 2SWP*PX4A GOES TO STATIC PUMP DISCHARGE PRESSURE 2SWP*PI6A GOES TO ZERO SERVICE WATER PUMP 1A/1C/1E DISCH FLOW LOW ANNUNCIATOR (601116)

PUMP MOTOR CURRENT AM-2SWPA51 SPIKES, THEN FALLS TO ZERO SERVICE WATER PUMP 1A/1C/1E. MOTOR/FEEDER ELEC FAULT ANNUNCIATOR (601114) 03 REMOVE MALFUNCTION CW01A (PCM) AND RETURN THE SYSTEM TO STEP 01 LINEUP. INITIAL DATE 04 REPEAT STEPS 02 AND 03 FOR PUMPS 1C AND 1E. VERIFY THAT THE RESPONSE IS SIMILAR. INITIAL DATE 05 START THREE SERVICE WATER PUMPS IN DIV II AND SECURE ONE OF THE DIV I PUMPS (P601). INITXAL DATE AT THE PCM, ACTIVATE MALFUNCTION CW01B AND VERIFY THE FOLLOWING RESPONSES:

DISCHARGE FLOW ON 2SWP*FX96B FALLS TO ZERO HEADER DISCHARGE PRESSURE 2SWP*PI2B MAY DECREASE (DEPENDING ON LOAD)

SUCTION PRESSURE 2SWP*PI4A GOES TO. STATXC Attachment D page 2 of 3

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C I NINE MILE POXNT UNIT 2 SIMULATOR TEST (ATP) DATE: 11/15/89 COOLING WATER SYSTEM PAGE: 2 SERVICE WATER PUMP TRIP REV: 2 PUMP DISCHARGE PRESSURE 2SWP*PI6A GOES TO ZERO SERVICE WATER PUMP 1B/1D/1F DISCH FLOW LOW ANNUNCIATOR (601219)

A PUMP MOTOR CURRENT AM-2SWPB51 SPIKES, THEN FALLS TO ZERO 4

SERVICE WATER PUMP 1B/1D/1F MOTOR/FEEDER ELEC FAULT ANNUNCIATOR (601217) 06 REMOVE MALFUNCTION CW01B AND RETURN THE SYSTEM TO NORMAL. INITXAL DATE 07 REPEAT STEPS 05 AND 06 FOR PUMPS 1D AND. 1F. VERIFY THAT THE RESPONSE IS INITIAL DATE SIMXLAR TO THAT FOR PUMP 1B.

08 ACTIVATE MALFUNCTION CW01 AND NOTE THAT ALL SERVICE WATER PUMPS RECEIVE TRIP INITIAL DATE SIGNAI S.

09 SXMULATE A LOSS OF OFF-SITE POWER BY TRIPPING P852 BREAKER 16-2 AND 17-2. INITIAL DATE VERIFY THE FOLLOWING:

"SERVICE WATER PUMP 1A/1C/1E AUTO TRIP/

FAIL TO START ANNUN AFTER TD (601113)

SERVXCE WATER PUMP 1B/1D/1F AUTO TRIP/

FAIL TO START ANNUN AFTER TD (601216)

END OF MALFUNCTION TEST

REFERENCES:

LSK 24-9.4, LSK 9-10, ESK-5SWP1-12 Attachment D page 3 of 3

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