ML18038A322
| 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 COPIES RECEIVED:LTR L ENCL L
SIZE: Lo TITLE: OR Submittal: General'istribution NOTES:
RECIPIENT ID CODE/NAME PDl-1 LA MARTIN,R.
COPIES LTTR ENCL' 1
2 2
RECIPIENT COPIES ID CODE/NAME LTTR ENCL PD1-1 PD 1
1 INTERNAL,:-ACRS NRR/DOEA/OTSBll NRR/DST/SELB 8D NRR/DST/SRXB 8E OC/LFJ4B REG FILE Ol EXTERNAL: NRC PDR tVRROLP,@ JLHF6 NCk ix.8~1 ~a~8 6
6 1
1 1
1 1
1 1
0 1
1 1
1 l
I NRR/DET/ECMB 9H NRR/DST 8E2 NRR/DST/SICB 7E NUDOCS-ABSTRACT OGC/HDS1 RES/DSIR/EIB NSIC 1
1 1
1 1
1 1
1 1
0 1
1 1
1
'NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WAS'ONTACTTHE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAMEFROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEEDl TOTAL NUMBER OF COPIES REQUIRED:
LTTR Q3 ENCL m~V
t "g
y~ ~
I
~
L J
1
V HIIASAIM U APirQHAMK NIAGARAMOHAWKPOWER CORPORATION/301 PI%INFIELDROAD, 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 me if you need additional information or clarification.
U Very truly yours, NIAGARA MOHAWK POWER CORPORATION DJW/sek 2508b L. Burkhardt, III Executive Vice President Nuclear Operations xc:
Regional Administrator, Region I Mr. R. A. Capra, Director Mr. R.
E. Martin, Project Manager Mr.
W. A. Cook, Senior Resident Inspector Records Management (8cPy/z//zN PRE fAPq//otal i
l 9009070058 9008~4 t
PDR ADOCK 05000410 P
PNV
NRC FORM 474 110 861 10 CFR g 55 aslb) 55 ~ s<<f555 SIIVlULATION FACILITY CERTIFICATION U.S. NUCLEAR REGULATORY COMMISSION ApprOved by OMe
~lt001$
INSTRUCTIONS. This form is to be filed for initial certification, recertification fifrequired), and for any change to 8 simulation facilityperformance 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 NINE MILE POINT NUCLEAR STATION UNIT 2 LICENSEE
\\
NIAGARA MOHAWK POWER CORPORATION DOCKET NUMBER EO-4IO DATE 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. Ifther ~ 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 LOCATIONOF 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 ofapproaimafefy 25B ofperformance 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 F0 RMANCE TESTING PLAN CHANGE (AHach 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 TI1'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-
~"
J r
k
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
Factory acceptance test - ATP - (October 1984 January 1985)
Customized test procedures written for all simulated systems'alfunctions and physical fidelity were reviewed by reference plant 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.
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
I'A w
'I 1
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
1 5
e g4
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
l A
t
]ry~
's
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.
b.
C.
d.
e.f.
Results:
RPV pressure
> 1250 psig Drywell pressure
> 45 psig or
< 10.0 psia Suppression chamber
> 45 psig or
< 10.0 psia Drywell temperature
> 340'F Suppression pool water temperature
> 212'F Average fuel temperature
> 2200 F
l.
All acceptance criteria were satisfactory.
~Exce tions:
None Attachment A
Page 1 of 20
A tj lt
'g A
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
'Watchdog'rogram is always operational during simulator operation.
If any 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
1 l.
1I4h A
~
"~
'r7)Q
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
Ct'.
ll'\\
t
~
II f
t'
. )CXfp
,J
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
b,<
l
-e~p
Results:
NIAGARA MOHAWK POWER CORPORATION NRC FORM 474 PERFORMANCE TEST ABSTRACT NMP-2 PLANT REFERENCED SIMULATION FACILITY 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.
DR4 Descri tion Scheduled Status
~Com 1etlon 2-941
'2-'942 2-943 2-944 2-945 2-946 2-947 Generator MWE 8 2/ higher than ref. plant
'"APRM read 8 3/. higher than ref. plant Feedwater temp.
low at 25 II 50/. power Drywell temp.
is higher than ref. plant CRD cooling flow is higher than ref. plant Hotwell temp.
does not rise with power level Thermal limit calculations at low power differ from ref. plant P-1 edit.
Closed Closed Working Closed Closed Closed Working 10/90 10/90 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
IIP
'I lb*
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 Initial 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:
0 Reference plant GETARS traces from the following:
1.
LER 89-14, 100% power turbine trip scram.
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 following discrepancies (DR's) were found:
) were met.
The DR¹ Descri tion Status 2-924 2-925 2-926 2-927 2-928 2-929 Total core flow unexplained rise NR vs.
WR RPV level delta reading Mn Gen.
Gas pressure response WR RPV level drop too fast Total steam flow dropped to zero Turbine coast down too fast closed closed ciosed closed closed 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 2-930 Wide range pressure plot did not show MSIV isolation.
Status closed The DR correction testing verifies the ANSI acceptance criteria are still satisfied.
~Exce tions:
None Attachment A
Page 7 of 20
)W k
t
NIAGARA MOHAHK POHER CORPORATION NRC FORM 474 PERFORMANCE TEST ABSTRACT NMP-2 PLANT REFERENCED SIMULATION FACILITY
Title:
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
-'+ ge k
8 $
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
Joi "I
V ~
C>>
~ I
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 Initial 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 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
~4
~t4 Ik~ k1 tw
~t E1
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:
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).
Scheduled
~Com let)on 10/90 The DR correction testing verifies the ANSI acceptance criteria are still satisfied.
~Exce tions:
None Attachment A
Page ll of 20
~
V
~ ~,>~, ~r
. ~
khi
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
'H a
pl
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.
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 2-935 2-936 CSH pump breaker response and EDG readings closed Unexplained supp chamber air temp.
peak closed 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
'a I
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:
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
~
f J
e'j P
4 er 1
g5~) 4
~
k'
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:
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
~ <<$f
'k - y A,
~ y,'i
~ '.8 A\\+
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
l ~
I gC
'C lp AVpAl 4
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 2-969
'-970 2-971 2-1004 2-1005 2-1008 2-1170 Description Panel 824 cosmetic DR's Panel 842 cosmetic DR's Panel 849 cosmetic DR's Panel
- 614, 606,
- 663, 882 and 898 cosmetic DR's Panel 632 cosmetic DR's Panel 870 cosmetic DR's Cosmetic DR's left over from DR ¹ 2-972 and 2-1006 Status Working Working Working Working Working Working Working Attachment A
Page 17 of 20
~"
el
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 k.
P623 Outboard valve relay panel 1.
P625 HPCS relay panel m.
" P629
.Division 1
P642 Division 2 leak detection panel o.
P659 RSCS panel 4.
5.
Electrical termination cabinets have been visually simulated with storage cabinets.
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
t I>
V
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
t l~
NINE MILE'OINT NUCLEAR STATION NUCLEAR TRAINING INSTRUCTION NTI-4.5.3 SIMULATOR CONFIGURATION MANAGEMENT DATE AND INITIALS REVISION 3 REVISION 4 REVISION 5 APPROVALS Superintendent Training-Nuclear A. D. Rivers 7/p Pa es 7
20 89 SIGNATURE@
r,ee e
'f
'a C
g'a,~
~Sf
~~ Revision 3 (Effective
(~
~Pa es i,h-6,8"21 4'7 Date June 1989 August 1989 (Publication.'hange)
P. '
~
T'IAGARA MOHANK PONER CORPORATION
, V'ef THIS PROCEDURE NOT BE USED AFTER July
)993, SUBJECT TO PERIODIC NEVIEH.
e 1-ATTACHMENT B
page 1 of 23
k%,
I
.;, ttTI-4. 5. 3
(~Cat(
~
S ItlU'TQR CONFIGURATION MAIVAGEMENT
~ v ~ JTi SECTION 1.0 2.0 3.0 TITLE PURPOSE REFERENCES DE FI HITIOHS TABLE OF CONTENTS PAGE 4.0 4.1 4.2 4.3 4.4 4
4.6 5.0 6.0 7.0 8.0 9.0 10.0 FIGURE 1
FIGURE 2
FIGURE 3
FIGURE 4 FIGURE 5
FIGURE 6
FIGURE 7
FIGURE 8
FIGURE 9
FIGURE 10 FIGURE 1
1 RESPONSIBILITIES Supervisor Simulator Technology Simulator Operator Simulator Software Engineer Simulator Hardware Specialists Simulator Clerk Lead Software Engineer COMPUTER TRACKING MODIFICATION PROCESS ENHANCEMENT PROCESS DISCREPANCY REPORT (DR)
PROCESS COST ACCOUNTING REFERENCE PLANT OPERATING PROCEDURE SIMUL'ATOR.-
EXCEP TIONS MODIFICATION REVIE'N FORM MODIFICATION CLOSEOUT FORti ENHANCEMENT REQUEST FORti SOFTHARE CHANGE REPORT SIMULATOR HARDHARE CHANGE REPORT DATA BASE t""". ~(-ICATION REPORT DISCREPAN'.
REPORT EXCEPTION SHEET SIMULATOR MOD IF ICA (.'OH PROCESS ENHANCEMENT PROC SS REFERENCE PLANT OPERATING PROCEDURE SIMULATOR EXC
. TIOtt FORM t<TI--".:.3 -i June 1989 8
~~I
~
9" 10 12
'13 14
,15 17 18 19
() %
H Tt I3 wt tO Lp I
ATTACHNENT B
page 2 of 23
"I
NTI-4.5.3 SIMULATOR CONFIGURATION MANAGEMENT 1.0 PURPOSE 1.2 Derine simulator personnel responsibilities.
,w ~
~ "
Detail instructions for:
Computer tracking Modification Process Enhancement Process Discrepancy Correct'.on Cost Accounting
2.0 REFERENCES
2.1 2.2 2.3 2.4 ANS/ANSI 3.5 -
1985 "Nuclear Power Plant Simulators For Use In Operator Training" TQ-504, "Simulator Configuration Management"
\\
Regulatory Guide 1.149, "Nuclear Power Plant Simulators For Use In Operator Training" NUREG
- 1258, "Evaluation Procedures for Simulators Certified Under 10CFR55" 2.5 2.6 2.7 AP-6.0, "Procedure for Modification" ND-100, "Plant Modifications"
" AP-6.0, AP-6.1, and AP-6.2 3.0 DE F INITIONS 3.1 3.2 3
3 3.4 Simulator Modification A referenced plant modification that has been identified as having an impact on the simulator.
Enhancement An instructional improvement on the simulator.
Software Discrepancy A conflict between actual simulation and that predicted or prescribed by the current database.
Hardware Discrepancy A physical defect (i.e.
broken switch).
N: -4.5.3
-1 June 1989
'TTACHMENT B
page 3 of 23
3.5 3.6 3.6.1 n
Simulator Configuration Con:rol Board (SCCB)
A committee of'lan".
and training department personnel that review reference plant modifications that imoac'.
the simulator and set priorities for implementation.
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.
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 3.7 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.
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
4 t+e I
4.1 4.1.1 4.1.2 RESPONS I8 I LITIES Supervisor Simulator Technoloa (SST)
Responsible to the
- Assistant Training Superintendent
'for
'implementation of this pr'ocedure.
Directs the activities of all personnel assigned to simulator support.
(3 4.1.3 Oversees all expenditures.
4.1.4 Maintains simulator usage schedule.
4.1.5 4.1.6 4.1.7 4.2 Documents ANS/ANSI 3.5 compliance.
Determines applicability of configuration management process steps Pre'paration and submittal of NRC Form 474 for Simulator Certification and Recertificaiion.
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 4.3.2 Responsible to the Supervisor Simulator Technology for simulator i3 software changes and maintenance in accordance with this procedures Document changes using embedded comments in model source code.
4.3.3 Maintains computer load balancing.
4.4 Simulator Hardware Specialist 4.4.2 4.4.3 4.4.4 Responsible to the Supervfsor Simulator Technology for Hardware i3 changes and maintenance in accordance with this procedure.
Maintain simulator spare par:: inve".tory.
Maintain simulator consumable stock inventory.
Perform preventive maintenance.
NTI-4.5.3
-3 June 1989 ATTACHltENT l3 page 5 of 23
M 0
1
4.5 4.5.1 4.6 Simulator Clerk Maintain controlled documents Maintain simulator hard copy database Maintain simulator change database Computer data entry in support of'this procedure Lead Software En ineer Responsible to the Supervisor Simulator Technology for:
a.
b.
C.
d.
[3
/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:
5.1.2 Unit 1 controlled document" distribution CDD.NEH Unit 2 document control information system DCIS 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.
5.2.2 Simulator operating and maintenance cost accounting.
5.2.3 Discrepancy Reports (DR's) 5.2.4 Enhancement implementation and cost accounti'ng.
/3 t3 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) 6.2 6.2.1 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.
Modifications wi th no simulator impact shall be processed in 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.
No impact mods refer to flow chart Figure 9
/3 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 6.2.1.3 6.2.1.4 SCCB Representative signs concurrence Figure 1, if he does not
- concur, the SCCB Board shall resolve.
Update the Reference Plant Computer Modification Tracking System.
File the Modification Reference Drawings impacting the Simulator Dynamic Database in the Simulator Dynamic Database.
J3 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 6.2.2.1 Reference Plant Modifications impacting the simulator (refer to Flow
- Chart, Figure 9).
Prepare a simulator modification package for presentation to the SCCB which includes:
a.
b.
C.
Modification Review
- Form, Figure 1,
processed through the Supervisor Simulator Technology Signature.
Modification implementation cost estimate.
Modifications safety evaluation and source.
documents as applicable.
/3 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
a ii
< ~
6.2.2.2 (Cont'd)
If 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.
b.
C.
d.
e.f.
Generate Simulator Exceptions
- Sheet, Figure 8
and file in the ANS/ANSI 3.5 Reports, file.
Brief simulator instructors on the Exception.
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.
File the Modification Reference Drawings impacting the Simulator Dynamic Database in the Simulator Dynamic Database.
Update the Reference Plant Computer Modification Tracking.
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 6.2.2.9 6.2.2.10 Nhen applicable sofiwar and hardware changes are implemented, test the modification in accordance with a Modification Test Procedure.
Correct and retest any priority 1
DR's generated against the
. )3 modification.
3 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
"t II C a ri
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 6.2.2.14 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.
Update the Reference Plant Computer Modification Tracking Simulator close date.
6.2.2.15 File the Modification Reference as-bui 1 t drawings impacting the Simulator Dynamic Database in the Simulator Dynamic Database.
6.2.2.16 Process a Modification Closeout Form, Figure 2.
7.0 7.1 7.2 7.3 7.3.1 7.3.2 ENHANCEMENT PROCESS (Figure 10)
Simulator enhancements are generated by the originator submitting an Enhancement Request
- Form, Figure 3,
to the Supervisor Simulator Technology.
The Supervisor Simulator Technology assigns an internal tracking number and submits Enhancement Requests with implementation cost estimate to the SCCB.
Enhancement Requests are reviewed by the SCCB.
If SCCB does not recommend implementation, the request is closed out with remarks by the Simulator Supervisor and a
copy returned to the originator.
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 funding
7.4 7.5 7.6 7.7 Recommended Enhancements are scheduled for implementation by the Supervisor Simulator Technology.
The Assistant Superintendent Training verifies funding and grants approval to commence work.
The Supervisor Simulator Technology schedules and assigns work to implement enhancement.
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 7.9 7.10 7.11 7.12 7.13 Hardware Enhancement changes implemented and Hardware Change
- Report, Figure 5, is generated if applicable to enhancement.
Generate an Enhancement Test Procedure and test Enhancement 'f applicable to enhancement.
Correct and retest any priority 1
OR's generated against the (3
enhancement.
'3 Turn, over to Training by performing a disc turnover to Training.
Update the ANS/ANSI 3.5 Reports File with the Enhancement
- Number, description, and Database Modification
- Report, Figure 6,
as applicable.
Update the Reference Plant Computer (COD.)EN or OCIS) simulator revision field for Simulator Dynamic Database documents impacted by enhancement.
7.14 7.15 File enhancement source documents in the Simulator Dynamic Database as applicable.
Closeout enhancement tracking.
8.0 8.1 8.2 8.3 DISCREPANCY REPORT (DR)
PROCESS (FIGURE 7)
DR's are generated to identify simulator modeling or hardware problems between the reference plant and the simulator.
The originator fills out the DR Form describing the problem, expected performance, and data reference, 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:
2.'.
Discrepancy prevents the performance of a
critical step or completion of a objective in a Simulator lesson plan currently being taught.
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 8.4 8.5 8.6 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 1 i ty The DR is assigned a
tracking
- number, verified and validity checked against the current simulator database by the Simulator Support Groups 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.
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 9.3
~
Operating time costs when operated by General Physics Corporation Instructors in approved Niagara Mohawk Training Programs 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 10.2
- 10. 3 10.3.1 10.3.2 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.
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.
The SCCB chairman should approve or disapprove the exception.
,/3 If approved the exception should be filed in the "instructor Station (3
Procedure Exceptions Book: which is located at the instructor console.
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.
(circle one)
Remarks:
Supervisor Simulator Technology Dare Does not impact concurrence SCCB Representative Date Simulator Configuration Control Board This modification is/is not recommended
, for implementation into the simulator.
Remarks SCCB Chairman Date Priority Sci'vied Implementation Date Supervisor Simulator Technology Date Permission granted to commence work.
Assistant Training Superintendent Da.e I3 NTI-4.5.3 -ll June 1989 ATTACHMENT page 13 of 23
~ 4 4
l~
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
~a D
FIGURE 3
ENHANCEMENT RE UEST FORM Tracking
~
Name
.Originator Date Description of Enhancement:
Reason Enhancement is Heeded:
Simulator Configuration Control Boarc This enhancement is/is not recommended for implementation into the simulator.
Priority Assigned SCCB Chairman Date 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
I
~ J fi 5 4
FIGURE 4
SOFTHARE CHANGE REPORT HORY PACKAG.
NUMBER AFFECTED SYSTEM MODULE USER REMARKS/NOTES 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 Initial Date Simulator Sor tware Engineer NTI-4.5.3
-14 June 1969 Date ATTACilliENT 3
page 16 of 23
t 4W~
L I
V 1
a, f 4A
~ I
~
~
~ ~
~ g
~
I g
~
g ~
~
~
~
I
~WMM
~WMM
~&MM
~&MM
~WMM
~WMM
~WMM
~WMM
~&MM
~
~
~
I I
~
e y
I
~
y
~
~
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
I C
~
C I
FIGURE 7
DISCREPANCY REPORT PRI ORIGINATOR PLANT CONDITION NATURE OF PROBLEM OBSFRVED:
SYSTEM TRACKING NUMBER DATE EXPECTED:
DATA REFERENCE (print¹, OP¹, plant" )
("Plant" must be supported by a site contact)
PROBLEM VERIFIED INITIAL YES DATE Problem valid for current Simulator data base YES NO CORRECTIVE ACTION/REMARKS RECHECK ACTION Rejected By (Reason)
NAME DATE 0 0 0 0
- Jr 0 k 0 w m
- k k 0 *k 0 **x 0 0 *i 0 0 ++*****4 k 0
- 0 k
- 0 0 *i'*0' r w ****k 0 0 k 0 0 0 4' **k 0 g *
- 0 **i0* 4 0 Accepted By NAtl=
DATE Update DR Tracking INITIALS NTI-4.5..
-l7 June
!989 DATc 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
~ "q
,FIGURE 9 S IvIULATOR k)OD F CA, ON PROCESS REF PLANT MOD g ASSIGNED GENERATE EXCEPTION REPORT INSTRUCTOR BRIEF TURN OVER TO TRAINING PRELIM IMPACT REVIEW OM ACIUAL REF PUNT MOD CLOSEOUT APPROVAL TO tP/ORK UPDATE ANS/ANSI 3.5 FILE PRELIM COST ESTIMATE TO MOD ENG zs APPROVAL
?
SCHEDULE 8c ASSIGN III/ORK UPDATE COMPUTER SIM REV UPDATE COMPUTER MOD TRACKING ACtUAL iKF PLAhV ILIPLE NO S!IIIAIOR IMPACT
?
UPDATE DYNAMIC DATA BASE NO ovum 2
Y"-S ARCHNES NO TEST SAT
?
YES DR MOD CLOSEOUT FORM CQ.'!. LE!.0 HT:--':.5.3
-19 June 1989 ATTACHMENT B
page 21 of 23
P I ssoe 0
4 FIGURE 10 I
~
I ENHANCEMENT REQUCST APPROVAL TO Itj/ORK II INSTRUCTOR BRIEF TURN OVER TO TRAINING TRACKING g ASSIGNED
'IMPL'EMENTATION COST ESTIMATE SCHEDULE Ec ASSIGN Y/ORK UPDATE ANS/eSI S.5
(
t scca APPROV~
'?
UPDATE COMPUTER SIM REV NO I
I I
I I
I I
I I
I I
I I
IL~~~~
ARCHIYES TEST NO SAT OR UPOATE DYNAMIC DATA BASE MOD CLOSEOUT FORM 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 MALFUNCTION NUMBER NHP UNXT-2 SXHULATOR MALFUNCTXOHB TEST YEAR 2990 AD02 AD03 CS02 CB03 CS06 CU05 CU07 CM03 ED01 ED02 ED06 EDll EG13 EG14 FP02 FP16 FM01 FM06 FM23 FM27 FM31 HC02 MS03 HB05 MB07 HB10 MB13 NM01 NH05 NM09 NH24 HM16 HH22 RC01 RC05 RC09 RD02 ADS FAILS TO INITIATE ADB/RELIEF UALVE FAILURE-STUCK tl-18 QR AHY OR ALL)
HIGH PRESSURE CORE SPRAY tCBH) FAZLS TO AUTO START HIGH PRESSURE CORE SPRAY tCSH)
DIESEL EHGXNE FAILURE LOM PREBBURE CORE SPRAY tCSL)
PUHP TRIP REACTOR MATER CLEANUP tMCB) FILTER DEHXHERALIZER RESIN DEPLETXON COOLANT LEAK OUTSIDE PRIHARY COHTAIHHEHT TURBINE BUXLDING CLOSED LOOF COOLING MATER tCCB)
PUMP TRIP HAXH TRANSFORHER LOSS OF COOLING LOSS OF OFFSITE 125KV FOMER SOURCEtB) tLXHE 5/6) 600 U NORHAl BUB tHJS)
FAULT t2HJB-UB1 --> US10) 24 VDC NORHAL BATTERY BUS FAULT t3A or 3B)
MAXN GENERATOR LOSS QF LQAD HAIN GENERATOR AVR FAILURE OSCZLLATEONB CONTROL ROOH FIRE DETECTOR FAILURE FIRE AT TURBINE BEARING 4 8 COHDEHBATE PUHP TRXP tA, BiC or AHY)
FEEDMATER PUHP TREF thi B,C, OR AHY)
FEEDMATER LOM PRESSURE LOM FLOM Uhl UE t LV137) FAXLURE AB ES COHDEHBATE DEMIHERALEZER HIGH DXFFERENTZAL PRESSURE FEEDWATER HEATER DRAXH PUHP TRIP FEEDMATER LIHE BREAK INSIDE DRYMELL HAXN CONDENSER AXR EHLEAKAGE STEAH LEAKAGE INSIDE THE PRXHARY CONTAINMENT HAXN BTEAH LINE IBOLATIOH VALUE FAILURE OPEN TURBINE BTEAH SEAL REGULATOR FAILS CLOSED LOSB OF EXTRACTION BTEAH TO FEEDMATER HEATER MBXV ISOLATIOH FAXLURE SOURCE RANGE MONITOR CHANNEL FAXLURE UPSCALE SOURCE RANGE HOHXTOR CHANNEL DETECTOR STUCK XHTERMEDIATE RANGE MONITOR CHANNEL FAILURE INOPERATIVE LOCAL PQMER RANGE HQNXTOR FAILURE tX-Y-J) - UPSCALE ROD BLQCK HONZTOR CHANNEL FAILURE UPSCALE LPRM FAELURE DRIFT
~
OR 25K REACTOR CORE ISOLATEOH COQLIHG AUTQ START FAXLURE REACTQR CORE IBQLATXON COOLING SYSTEM TURBINE SPEED COHTRQLLER FAXLURE AB XS REACTQR CORE ISOLATZOH COOLING FLOM TRAHBHXTTER FAILURE AS XB RQD DRXVE CONTRQL SYSTEM FAILURE TXHER HALFUHCTIOH ATTACE1ENT C Page 1 of 8
e Page Ha.
07)09)90 MALFUNCTION TXTLE NUMBER HMP UNIT-2 BIHULATOR HALFUNCTIONB TEST YEAR 2990 RD03 RD04 RD08 RD23 RD26 RH02 RH03 RP02 RP02 RPQS RP21 RR02 RR06 RR07 RR20 RR2S RR22 RR26 TC03 TCQS TU04 TUQS ROD DRIVE CONTROL SYSTEH FAILS TO ZHBERT CONTROL ROD FAZLURE fXX-YY) DRIFT XH CONTROL RQD <XX-YY) FAXLURE UNCOUPLED CONTROL ROD DRIVE FLOM CONTROL VALVE FAILURE OPENED SCRAM DXSCHARGE VOLUME RUPTURE REBXDUAL HEAT REHOVAL PUMP TRIP tA, B,C, OR AHY)
RESIDUAL HEAT REMOVAL STEAM DUMP VALVE FAXLURE CLOBED BPURIOUB REACTOR BCRAH REACTOR PROTECTZQH SYBTEH FAILURE TO SCRAH AUTOMATXC LQBS OF NORHAL POMER TO RPB CHANNEL RRCB FAILURE QF RECIRC PUMP TRIP/DOMNBHZFT REACTOR RECIRCULATION HASTER FLOW COHTRQLLER FAILURE-LQM REACTOR RECIRCULATION LOOP FLOM CONTROLLER FAILURE AB IB REACTOR RECIRCULATION FLOM UNIT FAXLURE UPSCALE REACTOR RECIRCULATION PUMP BKR TRXP FAILURE OF REACTOR RECIRC PUHP INNER BEAL REACTOR VESSEL PREBBURE RECORDER FAXLURE DOMHBCALE REACTOR VESSEL PRESSURE IHDXCATOR FAXLURE AB IB ROD MORTH MINIMIZER FAILURE FUEL CLADDING FAXLURE INCREASED ROD MORTH FOR AHY CONTROL ROD IXX-YY)
EHC SYSTEH STEAH PRESSURE REGULATQR FAILURE OBCZLLATXON HAIN TURBIHE BYPASS VALVE FAILURE - CLOSED EXHAUST HQQD SPRAY VALVE FAILURE CLQSED MAZH TURBXHE BEARXHG OXL PRESSURE LOW.
ATTACEfENT C Page 2 of 8
4 Page No.
07/09/90 MALFUNCTION NUMBER TXTLE HMP UNIT-2 SEMULATOR MALFUNCTIONS TEST YEAR 2991 AD04 CS04 CB07 CU02 CU02 CMQL CM04 DG01 ED03 ED07 EGOL EG02 EGOB FP03 FP07 FP15 FP17 FP19 PM02 FM20 FM14 FM15 FM24 PM'M32 FM33 MC03 MS04 MS11 HM02 HM06 HMLO HM15 HM17 HM23 OGOL PC02 PC03 ADS/RELIEF VALVE FAXLURE-LEAKS tL-28 QR AHY QR ALL)
HIGX PRESBURE CORE SPRAY tCSH)
INJECTXQN VALVE FAXLS TQ OPEH LQM PRESSURE CORE BPRAY tCSL)
XHJECTXGN VALVE PAILS TO OPEN REACTOR MATER CLEAN-UP PUMP TRIP REACTOR MATER CLEANUP DRAXH FLOM COHTROL VALUE FAXL-OPEN SERUICE MATER PUMP TRXP tAHY OR ALL)
CXRCULATZHG MATER fCMS)
PUMP TRIP DIESEL GENERATOR FAXL TO BTART 13 8 KV BUB fNPB) FAULT fSMGR 001,
- 002, 003) 600 U EMERGENCY BUB tEJB)
FAULT t USL AHD/OR US3)
MAXN GENERATOR TRIP MAXN GENERATOR AUTO UGLTAGE REGULATOR FAXLURE INCREASE HATH GENERATOR AHD EMERGENCY HYDROGEN SEAL OXL PUMP FAILURE TURBXHE BUELDXNG FXRE DETECTOR FAXLURE EHGIHE DRIVEN FXRE PUMP FAXLURE FIRE XN NORMAL STATXOH BERUICE TRANSFORMER t2BTX-XHBL)
FXRE ZN DXVXBXON ZZ DIEBEL ROOM FXRE XH RELAY ROOM CONDENSATE BOOSTER PUMP TRIP tA, B C or AHY)
FEEDMATER HIGH PRESSURE LOM FLQM VALVE tLU55A or B)
FAXLURE OPEN FEEDMATER HIGH PRESBURE HEGH FLOM VALVE FAILURE OPEN t Ap Bp C or ANY)
FEEDMATER MASTER CONTROLLER FAELURE LOM FEEDMATER MASTER CONTROLLER FAELURE AS EB CONDENSATE RECIRCULATION VALVE FAELURE OPEN REACTOR VESSEL LEUEL HARRQM RANGE TRAHBMXTTER FAILURE UPSCALE FEEDMATER LINE BREAK IHBXDE STEAM TUNNEL FEEMATER CHECK VALVES PAXL OPEN HOTMELL LEVEL CONTROLLER FAXLURE HIGH STEAM LXHE RUPTURE XHSXDE PRXMARY CQHTAXNMENT LOSB OF STEAM TQ MOZSTURE SEPERATOR REHEATER tA, B, OR BOTH)
SOURCE RANGE MOHXTER CHANNEL FAXLURE DOMHSCALE INTERMEDIATE RAHGE MONITOR CHANNEL PAXLURE UPSCALE ZHTERMEDXATE RANGE MOHETOR CHANNEL DETECTOR STUCK LOCAL PQMER MONITOR FAILURE DOMNBCALE tX-Y-J)
ROD BLOCK MOHETQR CHAHHEL FAILURE DOMHSCALE APRM UPSCALE HEUTRGN TRXP EXPLOBIOH XH AIR EJECTOR DISCHARGE PIPING PRIMARY COHTAXNMENT LEAKAGE 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 RC06 RC22 RD05 RD09 RD11 RHQS RP03 RP07 RP09 RP12 RR03 RR08 RR12 TC05 TC09 TU02 TU06 REACTOR CORE ZSOLATION COOLING FAILURE ISOLATION QF RCEC BYBTEH REACTOR CORE ISOLATIOH COOLZNG TURBXHE TREP RCIC STEAH LEAR IN REACTOR BUILDEHG ELEVATIQN 215 CONTROL RQD FAILURE (XX-YY) DRIFT OUT CONTROL ROD FAILURE tXX-YY) SCRAMHED CONTROL ROD XX-YY FAXLURE RPZB REBEDUAL HEAT REMOVAL HEAT EXCHANGER LEVEL CONTROLLER FAXLURE UPSCALE REACTOR PROTECTXON SYSTEH FAXLURE TO SCRAM RRCB 25 BECOND TIMER FAXLURE RRCS SPURXOUS XHXTXATXQH RRCB DXVZSIOHAL FAXLURE REACTOR RECZRCULATZOH HASTER FLOM CONTROLLER FAILURE AS ZS REACTOR RECIRCULATXON FLQM UNIT FAILURE - DO'l4HSCALE 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 ALL TURBINE BYPASS VALVEB FAXL OPEN NUMBER QNE TURBINE BYPASB VALVE FAILURE STICKS OPEN MAIN TURBINE BEARZHG HIGH TEMPERATURE HAIN TURBXNE THRUST BEARENG NEAR.
ATTACHMENT C Page 4 of 8
Page Ho.
07/'09/'90 MALFUHCTXON NUMBER NMP UNIT-2 SIMULATOR MALFUNCTIONS TEBT YEAR 1992 AD02 AD05 CS05 CU03 CU06 CU08 CM05 DQ02 ED04 ED08 EG03 EG04 EQ06 EG09 EG12 FP04 FP08 FM04 FW08 FM11 FM16 FM20 FM25 FM29 MC04 MB01 MB09 MB12 HM03
, HM07 HM22 NM19 NM20 OG02 PC04 RELXEF VALVE FAILURE t2-28 QR AHY OR ALL)
ADS/RELIEF VALVE FAILURE-OPEN i2-28 QR AHY OR ALL)
HIGH PRESSURE CORE BPRAY
<CSH)
PUMP TRIP REACTOR MATER CLEANUP DRAXH FLOW CONTROL VALVE FAXL-CLOSED REACTOR MATER CLEANUP NOH-REGENERATIUE HEAT EXCHANGE TUBE LEAK REACTOR MATER CLEAHUP (MCS)
ISOLATZOH FAXLURE CXRCULATING MATER EXPAHBION JOINT LEAKAGE DIESEL GENERATOR TRIP 4.16 KV NORMAL BUS iNHB) FAULT (
SMGR 11 --x 28
)
125 UDC NORMAL BUS (BYB) FAULT t SMQR 00lh, B,C
)
MAIN GENERATOR AUTQ VOLTAGE REGULATOR FAILURE DECREASE MAIN GENERATOR CQRE INTERNAL HEATIHG
~
MAIN GENERATOR STATOR COQLXNG PUMP TREP <A/B)
TURNING GEAR OEL PUMP FAELURE POMER GRID HETMORK LQAD TRANSIENT DECREASE DIESEL ROOM FIRE DETECTOR FAILURE 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 FEEDMATER LOM PRESSURE LOM FLOM UALUE iLU237) FAXLURE QPEN FEEDWATER HIGH PRESSURE LOM FLOM UALUE <LV55A and/or B)
FAXLURE CLOSED FEEDMATER HXGH PRESBURE HIGH FLOM UALVE FAXLURE CLOSED ih, B C or AHY)
FEEDMATER PUMP RECIRCULATION Vhl VE FAELURE OPEN COHDENBATE DEMXHERALXZER RESIN DEPLETZQN CONDENSATE RECIRCULATION VALVE PAXLURE CLOSED REACTOR VESSEL HARROW RANGE TRAHSMZTTER FAILURE - DOMHSCALE HOTMELL LEVEL CQHTROLLER FAILURE LQM STEAM LEAKAGE OUTBIDE PRIMARY COHTAINMEHT MOISTURE SEPARATOR REHEATER HXGH LEVEL (A, B, OR BOTH)
REACTOR VESSEL ISOLATXON BRM RECORDER FAXLURE INTERMEDIATE RANGE MONITOR CHANNEL FAILURE - DQMNBCALE AVERAGE POMER RANGE MONITOR CHANNEL FAXLURE UPSCALE ROD BLOCK MONITOR FAELURE AVERAGE POMER RANGE MONITOR CHANNEL FAILURE OFFQAS RECOMBZHER PREHEATER STEAM SUPPLY VALUE FAXLURE CLOBED STANDBY GAB TREATMENT TRAXN EXHAUST FAN TRIP ATTACHMENT C Page 5 of 8
Page Nu.
07/09'0 HALFUNCTION TZT1 E NUHBER NHP UNXT-2 SIMULATOR MALFUNCTZONB TEST YEAR 1992 PC06 RC03 RC07 RD06 RD10 RD12 RD15 RH06 RP04 RPOS RP13 RR04 RR09 RR12 RR1B RR19 RR24 RX04 TC01 TC06 TC10 TC12 TU02 TUO'7 SECONDARY CONTAINHENT ISOLATION FAILURE REACTOR CORE ISOLATION CQOLXNG TURBXNE SPEED CONTROLLER FAXLURE HIGH REACTQR CORE ISOLATEON COOLENG FLOM TRANSMITTER FAXLURE HIGH CONTROL ROD FAXLURE tXX-YY) ACCUHULATQR TROUBLE CQNTRQL ROD FAXLURE tXX-YY) GLOM BCRAH TIME CRD FEED PUHP TRXP LQBB OF INSTRUHENT AXR PREBSURE REBXDUAL HEAT REMQVAL HEAT EXCHANGER LEVEL CONTROLLER FAILURE DOMNSCALE ANTICIPATED TRANBXENT MITHOUT SCRAH RRCS 98 SECOND TXHER FAILURE RRCB INADVERTENT ALTERNATE ROD XNSERTXON REACTOR RECIRCULATXQN LOOP FLOM CONTROLLER FAXLURE HIGH REACTOR RECIRCULATION FLQM UNET FAILURE AB ZB REACTOR RECXRCULATZON LQM FREQUENCY HOTOR GENERATOR SET DRIVE HOTOR BKR TRIP REACTOR RECIRCULATION LQM FREQUENCY HG SET VOLTAGE REGULATOR FAILS LQM JET PUHP FAILURE COOLANT LEAKAGE INSIDE PRIMARY CONTAINHENT VEBSEL PREBSURE ZNDXCATOR FAILURE UPSCALE CORE PO'MER INBTABXLXTYMHEN OPERATZNG IN THE RESTRICTED 2QNE EHC SYSTEM PRESSURE REGULATOR FAELURE HIGH ALL TURBXNE BYPASS VALVES FAIL CLOSED HAIN TURBXNE GOVERNOR FAXLURE HIGH HAIN TURBINE CONTROL VALVE FAXLURE - CLOSED HAXN TURBINE BEARXNG HXGH VZBRATEON 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 CB01 CU04 CM02 DG03 EDOS ED09 EGOS EG07 EG10 EG12 FP01 FPQS FP06 FP09 FP12 FP14 FM09 FW12 FM13 FM22 FW26 FM30 EA02 MC02 HCOS HB02 HS06 M Oe HH04 NHOe HH12 NH21 QG03 PC01 PCQS TMI ACCIDENT BMR EQUIVALENT HIGH PRESSURE CORE SPRAY tCBH)
INADVERTENT INITZATEQN REACTOR MATER CLEANUP DRAIN FLOM CONTROL VALUE FAIL-AS XS REACTOR BUILDING CLOSED LOOP COQLZHG MATER tCCP)
PUMP TRIP DIEBEL GENERATOR LOAD SEQUENCE TXHER FAXLURE tDEV I / XE) 4 16 KU EMERGENCY BUB f EHB) FAULT f 201 f 202g 1Q3) 125 VDC EHERGENCY BUB FAULT t2BYS~SWG002A, B or C)
HAXH GENERATOR HYDROGEN COOLXHG SYBTEH LEAKAGE HAIN GENERATOR STATOR CQOLIHG DEHXHERALXZER RESIN DEPLETION POMER GRXD HETMQRN LOAD TRANSIENT-INCREASE HAXH GENERATOR ZBOPHABE BUS DUCT FAH TRIP fA/B)
TURBXHE IBLAND FIRE DETECTOR FAILURE CABLE SPREADING ROOH FXRE DETECTOR FAXLURE REACTOR BUILDING FXRE DETECTOR FAXLURE AUXILIARYFXRE PUHP FAXLURE fA, B,
BOTH)
FIXED BYSTEM FOAH CONCENTRATE PUMP FAXLURE flA, 1B, BOTH)
HALON BANN FAILURE FEEDMATER LOW PRESSURE LQM FLOM UALVE tLV137) FAXLURE CLOBED FEEDMATER HIGH PREBBURE LOM FLOW CONTROL UALVE tLUSSA and/or B) FAILURE AB EB FEEDMATER HIGH PRESSURE HIGH FLOM VALVE FAILURE AB IS fA, B C or ANY)
FEEDWATER HASTER CONTROLLER FAXLURE HIGH FEEDMATER HEATER TUBE LEAN-FEEDMATER HEATER fA2, Bl,C2)
CONDENSATE RECIRCULATION VALVE FAILURE AB XS REACTOR VESSEL NARROW RANGE TRAHBHXTTER FAELURE - AB IS LOBB OF XNBTRUMEHT AIR HAIN CONDENSER TUBE LEAR HQTMELL REFLOOD VALVE FAIL-OPEN STEAH LINE RUPTURE OUTBXDE PRIMARY COHTAINMEHT fDBA)
HAIN STEAH LINE ISOLATION VALVE FAELURE CLOSED STEAH JET AXR EJECTOR STEAH SUPPLY UALUE FAILURE CLOSED SRH CHANNEL INOPERATIUE XHTERHEDXATE RANGE RECORDER/APRH RECORDER CHANHEL FAELURE INOPERATXVE AVERAGE POWER RANGE HONZTOR CHANNEL FAXLURE DQMNBCALE TRAVERSXNG IH-CORE PRQBE FAILURE STUCK IH CORE QFFGAB DISCHARGE ISOLATZQN VALVE FAELURE CLOSED LOSB OF DRYMELL CQOLING DBA HYDROGEN RECOHBIHER BLOMER FAILURE ATTACHMENT C Page 7 of 8
E*
~ ~
4 0
Page Ho.
07/09/90 HALFUNCTXON NUHBER HMP UNIT-2 SXHULATOR HALFUHCTXONB TEST YEAR 1993 RC04 RC08 RC10 RCll RD01 RD07 RD14 RD17 RH02 RH04 RP06 RP10 RP14 RR01 RR05 RR17 RR20 RR21 RR25 RM02 BL01 BL02 TC02 TC07 TC11 TU03 REACTOR CORE ISOLATIQH CQOLIHG TURBXNE SPEED CONTROLLER FAILURE LOM REACTOR CORE ISOLATION COOLING FLOM TRANSHXTTER FAILURE LOW REACTOR CORE ISOLATEOH COOLING SYSTEH SPURIOUB IHETXATZOH RCIC ZSOLATIOH FAXLURE ROD POBITION INFORHATIOH BYSTEH FAXLURE IHQP CONTROL ROD FAILURE <XX-YY) STUCR CRD FLOM CONTROL VALVE FAXLURE CLOBED PARTIAL XNBERTZQH OF QNE BANK OF CONTROL RODS UNDER SCRAH CQNDITIONB REBZDUAL HEAT REHOVAL LQM PRESSURE COOLANT INJECTION VALVES FAILS TO QPEH RESIDUAL HEAT REHOUAL HEAT EXCHANGER TUBE LEAR LOSB OF HQTOR GEHERATOR RRCS FAELURE OF FMC RUNBACK RRCB ARX FAILUREjDEFEATED REACTOR RECIRCULATXOH HASTER FLOM CONTROLLER FAXLURE-HEGH REACTOR RECIRCULATION LOOP FLOM CONTROLLER FAXLURE LQM REACTOR RECZRCULATZQH PUHP HXGH BPEED TO LQW SPEED AUTO TRANSFER INCOMPLETE REACTOR RECZRCULATEOH PUHP DEBCHARGE VALUE FAXLURE REACTOR RECXRCULATEOH LOOP RUPTURE DBA LQCA REACTOR VESSEL PREBSURE RECORDER FAILURE -UPSCALE REACTOR VESSEL PRESSURE INDXCATOR FAILURE - DOMNBCALE ROD SEQUENCE COHTROL SYSTEM FAILURE DOEB HOT ENFORCE NOTCH LOGXC STANDBY LIQUXD CONTROL PUHP TRIP 2BLB-VEX3A, 2SLS-VEX3B QR BOTH FAIL TO FXRE MHEH SLC PUHP ZS TURHED OH EHC SYSTEH PRESSURE REGULATOR FAXLURE LOM HAZH TURBXNE BYPASS UALVE FAILURE - OPEN HAXN TURBXHE GQUERHOR FAXLURE-LOM HAIN TURBINE HIGH ECCEHTRXCXTY ATTACHMENT C Page 8 of 8
~'y At A.
q 'l<%"
P
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)
TYPE'AUSE:
DiSCRETE INSTANTANEOUS CURRENT OVERLOAD ON MOTOR PLT STA:
ANY WITH SERVICE WATER SYSTEM OPERATiNG
'FFECTS'UMP MOTOR CURRENT WILL SPIKE UPSCALE, THEN FALL TO ZERO AS 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
t4
~ <<4-e I~
~
,~, k~
0
NINE MILE POINT UNIT 2 SIMULATOR TEST (ATP)
COOLING WATER SYSTEM SERVICE WATER PUMP TRIP DATE:
11/15/89 PAGE:
1 REV:
2 MALFUNCTION CH01 SERVICE HATER PUMP TRIP (AgB g Cg D ~ Eg F OR ANY) 01 INITIALIZETHE SIMULATOR TO A FULL POWER IC (PCM)
AND NOTE THAT THREE SERVICE WATER PUMPS ARE OPERATING IN DIVISION I AND TWO XN DIVISION IX (P601)
INITIAL DATE 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).
AT THE PCM, ACTIVATE MALFUNCTION CW01B AND VERIFY THE FOLLOWING RESPONSES:
INITXAL DATE 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
g~
I <
. et<
0
C I NINE MILE POXNT UNIT 2 SIMULATOR TEST (ATP)
COOLING WATER SYSTEM SERVICE WATER PUMP TRIP DATE:
11/15/89 PAGE:
2 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 SIMXLAR TO THAT FOR PUMP 1B.
INITIAL DATE 08 ACTIVATE MALFUNCTION CW01 AND NOTE THAT ALL SERVICE WATER PUMPS RECEIVE TRIP SIGNAIS.
INITIAL DATE 09 SXMULATE A LOSS OF OFF-SITE POWER BY TRIPPING P852 BREAKER 16-2 AND 17-2.
VERIFY THE FOLLOWING:
INITIAL DATE "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
au
I 1%5fl8851 IHRRESSRR
~~SIR%
5RW 55855@%5 RS A
+g>>"
i+~+
+~.
6 i< ~~6
~5])
~9
~
~
c
~ f)"i
~'