ML20028H734
| ML20028H734 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 01/17/1991 |
| From: | GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20028H733 | List: |
| References | |
| NUDOCS 9101290282 | |
| Download: ML20028H734 (87) | |
Text
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CG TL E SIMUL R TOR CER TIFICA TION REPORT l99I 4-l I
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'JRC Fon;p 474 U.S. NUCLE AR REQULATOWY COhlMISSION Am.ov E o e v OMS - NO.3160417.J lim 8017.45 SwJo@
k tsTIMAfl0 sunOEN Ff A f;tsPONat TO COMPLY WITH TMis 66 INF OR M ATION COLL E CTION REQUts?' 17o HMS FOMWARD SIMULATION FACILITY CERTIFICATION cra;!,, ?g'itcOt;;;,na;=ty,1,? ;,,'s,";;it
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a COMMastog. n AsMINGTON, Dh US NUCLEAR mtOUL.ATORY 20666, AND TO THE PAPERWOMit REDUCTION PROJECT (3160 os asi OePect Of MANAQtMittT AND SUDOff, WASMiNQtDN, f
DC 20603.
I INSTRUCTIONS. This form is to be filed for init4al certif; cation, recertification Of required). and for any change to a simulation facility performance testing pien made after mitial submitta: of such a plan. Provide the followir1 information, and check the appropriate boa to indicate reason for sutmuttal, F ACILITY lOOutiNUMBER A. W. Vogtle Unit 1 Nuclear Power Plant a 424 LICE NSE E J
Georgia Power Company IDATE 1-4-1991 This is to cert +fy that:
1, The above named facihty licensee is usmo a temulanon fecihty consisting solely of a plant referenced simulator that meets the requirements of to CF R $5.45, 2.
Documentet.on is eveilable for NRC review in accordance with to CF R 55.45(b).
3.
This simulation facility meets the padance contamed in ANSI /ANS 3.5,1985, as endorsed by NRC Reiptatory Guide 1.149.
If there are any suceptions to the certification of this item, cneck here [ { and describe fully on additional pages as necessary. See Attachment 1: Except onf N AME (or other nientifestion) AND LOCATION OF SIMULATION F ACILITY A. W. Vogtle Simp htor, River Rd.
Approx. 5 mi. NE of Hwy 23, Waynesboro, GA 30830 y
SIMULATION F ActLITY PE RFORMANCE TEST ABSTRACTS ATTACHE 0,(Forperformance rests conductod e rhe panod erx/me with the aste orthis certification)
OESCR(PTION OF PE R F0RM ANCE TESTING COMPLETED (Ansch additionelpagets) an neceenery, and nientsty the item oewerption being continued)
See attachment 2:
Performance Tests Completed y
SIMULATlON F ACILil Y PE RFORMANCE TESTING SCHEDULE ATT ACHEO. (/or the conduct of spruommere/y 25% o/ performance tears per yeer for the tour roer pered commencing weh the date of this certification.)
ESCRIPTION OF PERFORMANCE TESTING TO DE CONDUCTEO, 'nech achtstione/ pero (al es neceanery, end ulentity the itsm aeacrrption bemg contsnued)
See Attachment 3: Performance Test Schedule 9E R F0RMANCE TEST lNG PLAN CHANGE. (For eny modifnstion to e pertbomence tentN pian submrtraf on a prewour certification)
DESCRIPTION OF PE R FO RMANCE TESTING PLAN CHANGE (Attach additknetoneefsb an neceenery, and identity the atem dowrtptun beir'e contmuet)
R E CE R T4FICATCON (Descrrbe w rihe actnone taean, attach results of compietedpertunnonce tantag in accorderace wth 10 CFR l 5L43lb)($ilv).
Attach additionalpoorts) en neceanery, stut icientity the iron dee~rrotkn beme continvoi) l Any fates statement or omission in tNs documents suding ettactweents, mey be subsect to civil erus crimmel sanctions, I certify uruser penetty of perjury that the information in this document and attadhments is true and SIGNATURE - AUTHOff! ZED REPRESENTATIVE l TITLE l0 ATE h'h M
General f!anager hl9-$
In
,eence witti 10 CFR g W. Communications, tNo form shall be submrtted to the NRC as fotiows:
BY Mall ADORESSED TOE D6rosese,Omme of Mustese Reneent Am4steen eY DELIVE RY IN PERSON One Whees Filat Merth UA sensamer Regntseeny ceawedessen TO THE NRCOFFICE AT:
11585 Reakvete Pete Waufnemsten,DC 20086 Reekvete, hm NRC f CRM a7e (1404
O EXCEPTIONS 1/4/91 Plant A.W. Vogtle, Unit 1 Docket # 50-424 Georgia Power Company 0
FORM: 00-01 _VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 1 OF 13 i
RM-TITLE: ANSI /ANS 3.5-EXCEPTIONS WORKSHEET REVISION NO O PERFORMED BY: G. Gunn DATE: 9/05/90 REVIEWED BY: M. Gibson DATE: 9/06/90
-APPROVED BY R.
Dorman SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90 ANSI' SPECIFICATION:3.1.1(7)
TITLE:Startuo. Shutdown & Pwr Ooer W/less Than Full Reactor Coolant Flow EXCEPTION:
GPC takes exception to this requirement.
There is no Performance Test which will be performed as part of the Plant Vogtle simulator certification process LO JUSTIFICATION:
Plant Vogtle-is prevented from performing a plant startup or operate t.
at power without full reactor flow by the plant's Technical Specifications O
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FORM: 00-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 2 OF 13 RM TITLE: ANSI /ANS 3.5 EXCEPTIONS WORKSHEET REVISION NO O PERFORMED DY: G. Gunn DATE: 9/05/90 REVIEWED BY: M. Gibson DATE: 9/06/9Q APPROVED BY R.
Dorman SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90 ANSI SPECIFICATION:3.1.1(9)
TITLE: Core Performance T3 sting Usina Permanently Installed Instrumentation EXCEPTION:
GPC takes exception to this requirement only so far as perrnanently installed instrumentation will not be used.
Core performance tests will be conducted as part of the Plant Vogtle simulator certification process using alternate means for monitoring core reactivity.
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~J JUSTIFICATION:
Plant
- Vogtle, by
- design, has no permanently installed instrumentation for core reactivity tests.
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1 r RM: 00-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 3 OF 13 RM TITLE: ANSI /ANS 3.5 EXCEPTIONS WORKSHEET REVISION NO O PERFORMED BY: G. Gunn DATE: 2/05/90 REVIEWED BY: M. Gibson DATE: 9/06/90 APPROVED BY R.
Dorman SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90 ANSI SPECIFICATION:3.1.2(12)
TITLE: Control Rod Failures IDEludina Stuck Rods Uncoupled Rods, Driftina Rods, ani Misalianed Rods EXCEPTION:
GPC takes exception to this requirement only so far as uncoupled rods or drifting rods are not appropriate malfunctions on Plant Vogtle
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'v0STIFICATION:
Malfunctions of this nature are not applicable to the Westinghouse designed control rod drives.
The following malfunctions are presently available:
1.
RCCA Withdrawal Interlock C1, C2, C3 & C4 Fail to Block Rod Movement in Manual or Automatic 2.
Automatic RCCA Speed Signal Fails to Maximum 3.
Uncontrolled Withdrawal of RCCA Bank 4.
Uncontrolled Insertion of RCCA Bank 5.
Uncontrolled Withdrawal of RCCA 6.
Uncontrolled Insertion of RCCA 7.
Control Banks Fall to Move on Auto Demand 8.
Control Banks Fall to Move on Auto or Manual Demand 9.
Control Rod Urgent Failure 10.
Stuck RCCA 11.
RCCA Fails to Move 12.
Dropped RCCA 13.
RCCA Primary Position Indication Fails Low 14.
RCCA Primary Position Indication Fails As Is 15.
RCCA H-8 Ejected (D
t.)
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FORM: 00-01 VOGTLE SIMUIATOR CERTIFICATION PLAN PAGE 4 OF 13
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RM TITLE: ANSI /ANS 3.5 EXCEPTIONS WORKSHEET REVISION NO O
- PERFORMED BY: G. Gunn DATE: 9/05/90 REVIEWED BY: M. Gibson DATE: 9/06/90 APPROVED BY R.
Dorman SUPERVISOR OPERATIONS TRAINING DATE:- 11/15/90
. ANSI SPECIFICATION:3.1.2(25)
TITLE: Reactor Pressure Control System Failure Includina Turbine Bvoass Valve (BWR)
EXCEPTION:~
GPC takes exception to this requirement.
There is no Performance Test which will be performed as part of the Plant Vogtle simulator certification process O
JUSTIFICATION:
Plant Vogtle is a Westinghouse Pressurized Water Reactor (PWR).
This requirement'is not applicable to the Vogtle simulator O
FORM:-00-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 5 OF 13 IM TITLE: ANSI /ANS 3.5 EXCEPTIONS WORKSHEET REVISION NO O__
.PERTORMED BY: G. Gunn DATE: 9/05/90 REVIEWED BY: M. Gibson DATE: 9/06/90 APPROVED BY R.
Dorman SUPEIlVISOR OPERATIONS TRAINING DATE: 11/15/90 ANSI SPECIFICATION:4.1(3) (f)
TITLE: Recirculation Flow EXCEPTION:
.GPC takes exception to this requirement.
This critical parameter will not - be recorded.as part of the Plant Vogtle simulator certification process
-JUSTIFICATION:
Plant Vogtle.is a Westinghouse Pressurized Water Reactor (PWR).
This requirement is not applicable to the Vogtle simulator
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FORM:-00-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 6 OF 13 4
RM TITLE: ANSI /ANS 3.5 EXCEPTIONS WORKSHEET REVISION NO O PERFORMED BY: G. Gunn DATE: 9/05/90 REVIEWED BY: M. Gibson ' DATE: 9/06/90
- APPROVED BY R.'Dorman SUPERVISOR OPERATIONS TRAINING DATE
- 11/15/90 ANSI SPECIFICATION:4.3(5)
TITLE:BWR Sucoression Pool Temo EXCEPTION:
GPC takes exception to this requirement.
This operating limit will not be monitured as part of. alerting the instructor when certain parameters reach model or plant design limits on the Plant Vogtle simulator.
O JUSTIFICATION:
Plant Vogtle is a Westinghouse Pressurized Water Reactor (PWR).
This requirement is not applicable to the Vogtle simulator.
I The - current parameters which are monitored for compliance with Section'4.3 of the ANS 3.5 standard are:
' Containment Pressure RCS Pressure RCS Void Fraction Average Fuel Temperature Average Clad' Temperature A " computer fault" light will illuminate in the instructor's booth when any of the above parameters exceed'their predetermined limit.
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RM: 00-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 7 OF 13 FORM TITLE: ANSI /ANS 3.5-EXCEPTIONS WORKSHEET REVISION NO O PERFORMED BY: G.'Gunn DATE: 9/05/90 REVIEWED BY: M. Gibson DATE: 9/06/90 APPROVED BY R.
Dorman SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90-
- ANSI SPECIFICATION
- B2.1 TITLE: Steady State Performance EXCEPTION:
=GPC will substitute a steady state test at 30% power for the ANSI required 25% steady state test.
Steady state tests at 75% and 100% will be performed as required by the standard.
O JUSTIFICATION:
-Plant data exists-for 30% steady state power.
O
FORM: 00-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 8 OF 13 ORM TITLE: ANSI /ANS'3.5 EXCEPTIONS WORKSHEET 9EVISION NO O PERFORMED BY: G. Gunn DATE: 9/05/90 REVIEWED BY: M. GibFOn DATE: 9/06/90 APPROVED BY R.
Dorman SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90 ANSI SPECIFICATION:B2.2 TITLE: Transient Performance EXCEPTION:
The Standard requires all transient tests listed in Section B2.2 of Appendix B be performed from an initial condition of 100% power, steady. state xenon and decay heat.
GPC takes exception to the requirement to run All tests at 100% power.
GPC-intends on running the following transients at the power level indicated.
All remaining transients will be ran at 100% power.
B2. 2 (5) - Trip of any single reactor coolant pump - 13%
B2.2(6) - Main turbine trip without a reactor trip
-30%
B2.2(9) - Maximum size unisolable main steam line rupture -
The intent of the Standard is still met insofar as the transients will be tested annually but at a power level that will provide more meaningful _ data to GPC.
Specifically, each power level was selected because:
B2. 2 (5) - Highest available initial condition (power level) that GPC could-be certain the reactor would not trip (due to something other than a-low RCS-flow).
It was-felt that not having the reactor trip was preferred since response of the plant to_a complete loss of RCS ' flow would be conducted at 100% power and result in a reactor trip.
B2.2(6) - A turbine trip will not cause a reactor trip at this-power level.
B2.2(9) - Response is more severe at this power level and was close to the power level used in the FSAR analysis of this transient-(the FSAR started with a subcritical core).
FORM:-:00-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 9 OF 13 bRMTITLE:
ANSI /ANS 3.5 EXCEPTIONS WORKSHEET REVISION NO O PERFORMED BY: G. Gunn DATE: 9/05/90 REVIEWED BY: M. Gibson DATE: 9/06/90 APE > ROVED BY R.
Dorman SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90 ANSI SPECIFICATION:B2.2.1/2/3/4 TITLE:Translent Performance EXCEPTION:
This section of Appendix B requires that all Appendix B listed transient tests be recorded with a resolution of.5 second or less.
GPC takes exception to this requirement of recording at
.5 second intervals.
GPC has a record program on the simulator computer which records critical parameter data at
-1 second intervals for transients and at 30 second intervals for normal operation tests.
O JUSTIFICATION:
Current' data recording capabilities meet the requirement of Section 4.4, Monitoring Capability, of the Standard.
With a resolution of 1 second intervals, it is GPC's view that no
. anomalies would be uissed at this rate which could cause negative training.
This is balanced against the amount of data that is stored and plotted.
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FORM: 00-01 VOGTLE: SIMULATOR CERTIFICATION PLAN PAGE 10-OF 13 7
4 RM TITLE: ANSI /ANS-3.5 EXCEPTIONS WORKSHEET REVISION NO O PERFORMED.BY: G. Gunn DATE: 9/05/90 REVIEWED BY: M. Gibson DATE: 9/06/90 APPROVED BY R.
Dorman SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90 ANSI SPECIFICATION:' 4.1 TITLE: Performance Criteria for Steadv State Ooeration EXCEPTION:
. ANSI requirements state that simulator computed values of critical parameters shall agree with +/- 2% of. the reference plant parameters and shall not detract from training. ANSI requirements-also state that the calculated values of noncritical parameters pertinent-to plant operation, that are on the simulator control room. panels,
=shall agree within +/- 10% of the reference plant parameters and shall not detract from training.
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JUSTIFICATION:
-GPC takes exception with this section of the standard only to the extent that since the standard does not define whether the tolerance L
is referenced to plant value or to scale' range, GPC will use the I
scale range. Using a tolerance - based - on plant value can create requirements that are beyond training needs when the value is very small. - (i.e. a meter displaying O. has no tolerance when plant value l
-is.used as criteria)-
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FORM: 00-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 11 OF 13 RM TITLE: ANSI /ANS_3.5 EXCEPTIONS WORKSHEET REVISTON NO O PERFORMED BY: G. Gunn DATE: 9/05/90 REVIEWED BY: M. Gibson DATE: 9/06/90 APPROVED BY R.
Dorman SUPERVISOR OPERATIONS TRAINING DATE: J1/15/90 ANSI SPECIFICATION: 5.3 TITLE: gip 3,lator Modification EXCEPTION:
This requirement specifies that the simulator shall be modified as required within 12 months following the annual establishment of the simulator update design data referenced in Section 5.2 of the ANS 3.5 standard. GPC takes exception to this requirement only so far as the following discrepancy report (DR) has not been resolved within the time period permitted by the ANS standard.
DR 8809012
" Proteus" Computer system simulation is not current JUSTIFICATION:
Plant-Vogtle has critical operational information available to the operator from three separate computer systems. In addition to the Ok
" Proteus" system there is a safety related plasma system ("PSMS")
and a separate " Emergency Response Facility" computer system. These systems monitor many more points than in most plants. The " Emergency Response Facility" computer for example has approximately 1000 analog' inputs The " Proteus" computer system has very little to offer the- ~ operator that is not available to him on the other systems. This is demonstrated by the. fact that the plant initially had a " Proteus" screen on the MCB. This screen is now driven by the
" Emergency Response Facility" computer because it has much more useful information for the operator.
The simulated " Proteus" computer system follows the ~ basic structure of the real system but is a' limited system. The command structure is very similar but has some differences. The screens are different but do accurately represent Vogtle design.
Plant Vogtle is currently developing the specifications to replace the plant " Proteus" computer system. Current plans are to place a stimulated system in the simulator prior to replacing the plant system. The Unit 1 system is expected to be replaced in 1993.
The training value of the simulation is minimal.
The cost of updating the current simulation is significant so GPC has chosen to combine replacement of the plant system and the simulator upgrade.
FORM: 00-01 VOGTLE SINULATOR CERTIFICATION PLAN PAGE 12 OF 13
)RMTITLE:
ANSI /ANS 3.5 EXCEPTIONS WORKSHEET REVISION NO O t
PERFORMED BY: G. Gunn DATE: 9/05/90 REVIEWED BY: M. Gibson DATE: 9/06/90 APPROVED BY R.
Dorman SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90 ANSI SPECIFICATION: 5.3 TITLE: Simulator Modification EXCEPTION:
This requirement specifies that the simulator shall be modified as required within 12 months following the' annual establishment of the-simulator update design data referenced in Section 5.2 of the ANS 3.5 standard._GPC takes exception to this requirement only so far as the following discrepancy report (DR) har not been resolved within the time' period permitted by the ANS standard.
DR 8809011 The MCR lighting is controlled by two relays & dimmer switches.
JUSTIFICATION:
This change will take extensive rewiring of.the lighting fixtures in.the simulator. GPC has been unable to schedule this as yet. The training impact is very insignificant because the lighting does go to backup supplies when power is lost-to lighting busses. The only impact is that all main lighting :is lost on loss of_ power from either of two lighting transformers. In the plant the-lights are split between power supplies some of which are 1E.
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FORM: 00-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 13 OF 13
( \\RM TITLE:
ANSI /ANS 3.5 EXCEPTIONS WORKSHEET REVISION NO O PERFORMED BY: G. Gunn DATE: 9/05/90 REVIEWED BY: M. Gibson DATE: 9/06/90 APPROVED BY F..
Dorman SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90 ANSI SPECIFICATION: 3.1.1 (10)
TITLI: Ooerator Conducted Surveillances EXCEPTION: This requirement specifies that simulators be capable of operator conducted surveillance testing on safety-related equipment or systems. GPC takes exception to this requirement to the extent that many Plant Vogtle surveillances utilize local equipment, process panels, etc. GPC has selected the following surveillances as represenative of the Plant Vogtle-surveillances that can be essentially completed utilizing control board instrumentation:
Voctle Certification Survellance Tests 1) 14980-1 DG operability test 2) 14423-1 Source range NIS channel operability test 3) 14424 Intermediate range NIS analog channel operability test L
4) 14425-1 Power range quarterly analog channel operational test 5
14510-1 Control room emergency filtration system operability test I')))
14490-1 Containment cooling system operability test
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14705-1 Boron injection flow rate verification test 8) 14406-1 Boron injection flow path verification - shutdown 9) 14405-1 Boron injection flow path verification during operation l
10) 14805-1 Residual heat removal pump and check valve IST 11) 14220-1 Main turbine valves weekly stroke test o
12) 14410-1 Control rod operability test 13) 14725-1 Reactor vessel head vent path operational flow test 14) 14842-1 Main steam isolation valves partial stroke inservice test 15) 14505-1 Main feed isolation valves partial stroke inservice test 16) 14230-1 A.
C.
source verification JUSTIFICATION:
l Simulation of local panels, process panels, etc. is beyond the scope of the Vogtle simulator and most other simulators, i
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PERFORMANCE TESTS COMPIETED 1/4/91' Plant-A.W. Vogtle, Unit 1 Docket # 50-424-i Georgia Powtr Company 0
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Form No.
Description 05-01 Malfunction Tests - This section contains a list of the malfunctions that were tested. The list includes the required malfunctions from section 3.1.2 of the standard plus those selected from a review of the Control Room Tasks derived from a systematic approach to training.
06 Normal Operations Tests - This section contains a list of the normal operations tests that were performed. This list includes the tests that are required by section 3.1.1 of the standard.
07-01 Transient Tests - This section contains a list of the transient tests that were performed.
This list includes the required transients from Appendix B of the standard.
08-01 Computer System Tests - This section contains
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the real time tests and the simulator out of limits testing.
1 05-02 Test Abstracts for the malfunction testing identified on Form 05-01
'- 02 Test Abstracts for the normal operations testing-identified on-Form 06-01 07-02 Test Abstracts for the transient testing identified on Form 07-01 08-02 Test Abstracts for the computer system testing identified on Form 08-01.
12-01 Discrepancy Resolution Worksheet - Describes the discrepancies identified during the testing and includes the current status of-the discrepancies.
17-03 Certification Review Committee - Describes the qualifications of the committee members, the methodology of their review and includes any differing opinions.
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FORM:.05-01~
EVOGTLE SIMULATOR CERTIFICATION PLAN PAGE 1 OF 4 bU4 TITLE: MALFUNCTION' PERFORMANCE ~ TEST LIST REVISION 0-
' PREPARED BY: M.Pellechi DATE: 4/06/88 REVIEWED BY: M.Gibson DATE: 9/26/90 APPROVED lBY: R.
Dorman SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90 7
MALFUNCTION MALFUNCTION TEST
-TEST NUMBER
. TITLE
'05-01 Loss of coolant, significant PWR steam-generator leaks 05 Loss of coolant, Inside primary containmen':
05 Loss _ of coolant, Outside primary containment 05-04 Loss of coolant, Large reactor coolant breaks including demonstration of saturation conditions t
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~ 05-05 Loss of coolant, Small reactor coolant breaks
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including demonstration of saturation conditions 05-06'
' Failure of safety and relief valves 05-07
' Loss of instrument air to the extent-that the
~
whole~ system or-individual headers can lose-pressure and affect.the plant's static or dynamic performance 05-08 Loss or degraded-electrical power to the station, loss of offsite power 05-09 Loss or-degraded electrical' power to the station,' loss of emergency power 05-10 Loss or. degraded electrical power to the station, loss-of emergency generators 05 Loss or degraded electrical power to the station,-loss of power to the plant's electrical distribution busses O
- FORM: 05-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 2 OF 4
()RMTITLE:
MALFUNCTION PERFORMANCE TEST LIST REVISION O
--PREPARED BY:' M. Pellechi DATE: 4/06/88 REVIEWED BY: M.Gibson DATE: 9/26/90
-APPROVED BY:
R.
Dorman SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90 MALFUNCTION MALFUNCTION TEST TEST NUMBER TITLE 05-12 Loss or degraded electrical power to the station, loss of power to the individual instrumentation busses (AC) that provide power to the control room indication or plant control functions affecting the plant's response 05-13 Loss or degraded electrical power to the station, loss of power to the individual instrumentation busses-(DC) that provide power to the control room indication or
-(T.
plant control functions affecting the plant's M/
response Loss of forced core coolant flow due to single or multiple pump failure (This test is a duplicate of_ Tests 07-04 & 07-05) 05-14 Loss of condenser vacuum including loss of
-condenser level control 05-15 Loss of. service water or cooling to individual components 05-16 Loss of shutdown cooling 05-17 Loss of component cooling system or cooling to individual components Loss of normal feedwater or normal feedwater system failure (This is a duplicate of test 07-02) 05-18 Loss of all feedwater (normal and emergency)
Loss of protective system channel (This test
-is covered in Test 05-12)
i FORM:'05 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 3 OF 4
!h X fkM TITLE: MALFUNCTION PERFORMANCE TEST LIST REVISION O
PREPARED BY: M.Pellechi DATE:, 4/06/88 REVTEWED BY: M. Gibson DATE: 9/26/90
~ APPROVED BY: R.
DorMan_ SUPERVISOR OPERATIONS TRAINING DATE:-11/15/90 MALFUNCTION MALFUNCTION TEST
-TEST NUMBER-TITLE 05-19 Control'_ rod failure including stuck rods, rod drops, and misaligned rods 05-20 Inability to drive control rods-05-21 Fuel cladding failure resulting in high activity:in reactor coolant or off gas and the associated-high radiation alarms Turbine trip (This test is a duplicate of Test 07-06) 05-22 Generator trip 05-23 Failure in automatic control system (s) that affect reactivity and core heat removal t
05-24' Failure of reactor coolant pressure and volume
. control systems (PWR)
ReactorEtrip (This test is a duplicate of Test 07-01) l
' Main steam line break inside containment (This test'is a duplicate of Test 07-09) 05 'Mainisteam line break outside. containment 05-26 MainLfeed line break inside containment 05-27:
Main feed line break outside containment 05-28'
' Nuclear instrumentation failure (s) 05-29 Process instrumentation, alarms, and control system failures O
FORM: 05-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 4 OF 4
( J TITLE:
MALFUNCTION PERFORMANCE TEST LIST REVISION O
PREPARED BY: M.Pellechi DATE: 4/06/88 REVIEWED BY: M.Gibson DATE: 9/26/90 APPROVED BY:
R.
Dorman SUPERVISOR OPERATIONS TRAINING DATE: 31/15/90 MALFUNCTION MALFUNCTION TEST TEST NUMBER TITLE 05-30 Passive malfunctions in systems, such as engineered safety features, emergency feedwater system 05-31 Failure of the automatic reactor trip system c) i l'
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. FORM: 06-01 VoGTLE SIMULATOR CERTIFICATION PLAN PAGE 1 oF 2 O
'k lRM TITLE: NORMAL AND STEADY STATE TEST LIST PEVISIoN O PREPARED BY: P. Rubin DATE: 9/27/90 REVIEWED BY: M.Gibson DATE: 9/28/90 APPROVED BY:
R. Dorman SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90 1
NORMAL AND STEADY STATE TEST NUMBER TEST TITLE 06-01 Plant startup - cold to hot standby. The starting conditions shall be cold shutdown conditions of
-temperature and pressure.
Operations at hot standby-(This test is redundant with portions of Test 06-01) 06-02 Nuclear startup from hot standby to rated po;.r Turbine startup and generator synchronization (This test is redundant with portions of Test 06-02) 06-03 Load changes
_f-)
- 04 Plant shutdown from rated power to hot standby 06-05 Cooldown to cold shutdown conditions 06-06 Reactor trip followed by recovery to rated power Core performance testing, Heat balance (This test as part of Tests 06-09, 06-10 and 06-11)
Core performance testing, Shutdown Margin Demonstration (This test is performed as part of Tests 06-01 and 06-05) 05-07 Core performance testing, Reactivicy Coefficient Measurements Core performance testing, Control Rod Worth using permanently installed instrumentation (This test is performed las part of Test 06-07) 06-08 Operator conducted surveillance testing on safety-related eqttipment or systems O
FORM 06-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 2 OF 2 f
\\ :RM TITLE: NORMAL AND STEADY STATE TEST LIST RWVISION O PREPARED BY P. Rubin DATE: 9/27/90 REVIEWED BY M.Gibson DATE 9/28/90 APPROVED BY:
R.
Dorman SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90 i
NORMAL AND STEADY STATE TEST NUMBER TEST TITLE 06-09 Steady State Performance at 30% power 06-10 Steady State Performance at 75% power 06-11 Steady State Performance at 100% power for 60 minutes (3) m l
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~ FORM 07-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 1 OF 1 ORM TITLEt TRANSlENT PERFORMANCE TEST LIST REVISION O
PREPARED BY: P. Rubin _ DATE: 9/15/90 REVIEWED BY: Mii.lbson DATE: 9/16/90 APPROVED BY:
R.
Dormari SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90 TRANSIENT TRANSIENT 'PERATIONS TEST NUMBER TEST TITLE 07-01 Transient Performanco, Manual reactor trip 07-02 Transient Performanco, Simultaneous trip of all foodwater pumps 07-03 Transient Performance, Simultaneous closure of all Main Steam Isolation Valves 07-04 Transient Performanco, Simultaneous trip uf all reactor ecolant pumps 07-05 Transient Performance, Single reactor coolant pump trip 07-06 Transient Performanco, Main turbino trip (from the O-maximum power level which will not result in an immediate reactor trip) 07-07 Transient Performance, Maximum rate power ramp (100%
down to approximately 75% and back to 100%)
07 08 Transient Performanco, Maximum sizo reactor coolant system rupture combined with a loss of offsito power 07-09 Transient Performanco, Maximum size unisolabic main steam lino rupture 07-10 Transient Perforcance, Slow primary system depressurization to saturatoa condition using pressurizer rollof or safety valve stuck open (Inhibit activation of the high pressuro Emergency Core Cooling Systems) i O
FORM 08-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 1 OF 1
)RM TITLFJ COMPUTER SYSTEMS TEST REVISION O
PREPARED BY:
P. Rubin DATE: 9/15/90 REVIEWED BY:
M., Gibson DATE: 9/16/90 APPROVED BY: R.Dorman SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90 COMPUTER SYSTEM TESTS TEST NUMBER TEST TITLE 08-01 Computer Real Time Test l
08-02 Simulator Limits Exceeded Test
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l FORM 05-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 1 OF 33 i
FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O l
PREPARED BY P. Rubin DATE 9/27/90 REVIEWED BY:M.Gibson DATE:9/28/90 APPROVED BY:R. Dorman SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90 a
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J SIMULATOR PERFORMANCE TEST ABSTRACT TITLE: IDCA: Sianificant SG Leaks (05-01)
The Vogtle simulator is initialized to 100% power, EOL, Equilibrium Xe.
A SG 1 tube rupture (malf #84) is inserted one minute after the simulator is placed in_run 6 10% severity.
The leak is increased to 50% severity after 6 minutes. At 11 minutes from the beginning of the l
session, the malfunction severity is increased to 100%.
The exercise is - terminated once the pressurizer level is stable or blowly increasing above 20%.
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The simulator response is evaluated against best estimate judgement where Vogtle plant data is not available.
This testing was satisfactorily completed. Any discrepancies are identified on Form 12-01.
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FORM 05-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 2 OF 33 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY:P. Rubin DATE 9/27/9Q REVIEWED BY:M.Gibson DATE:9/28/90 APPROVED BY R. Dorman SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE: 14CA: Ing11;1e Containment (05-02)
O The Vogtle simulator is initialized to 100% power, EOL, Equilibrium Xe.
A Hot Leg #2 rupture (malf #37) is inserted 9 100% severity one minute after the simulator is placed in run.
The exercise is terminated 3 minutes after. safety injection actuates.
The simulator response is evaluated against best estimate judgement where Vogtle plant data is not available.
'This testing was satisfactorily completed. Any discrepancies are identified on Form 12-01.
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FORM 05-02 VOGTLE SIMULATOR CERTIFICMrION PLAN PAGE 3 OF 33 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY P. Rubin DATE 9/27/90 REVIEWED BY M.Gibson DATE 9/28/90 APPROVED BY:R. Dorman SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE: IDCA: Outside containment (05-03)
The Vogtle simulator is initialized to 0% power, DOL, Hot Standby, positive displacement charging pump is in service.
A letdown line leak in the auxiliary building (malf #76) is inserted 0 10% severity one minute after the simulator is placed in run.
The exercise is terminated after the leak has been automatically isolated and the pressurizer level is increasing.
The simulator response is evaluated against best estimate :tudgement where Vogtle plant data is not available.
This testing was satisfactorily completed. Any discrepancies are identified on Form 12-01.
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FORM 05-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 4 OF 33 FORM TITLE: PERFORMANCE TFST ABSTRACT REVISION O PREPARED BY:P. Rubin DATE:9/27/90 REVIEWED BY M.Gibson DATE 9/28/90 APPROVED BY R. Dorman SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE: LOCA Larae Break (05-04)
The Vogtle simulator is initialized to 100% power, EOL, Equilibrium Xe.
A RCS Loop 3 cold leg rupture (malf #35) is inserted one minute after the simulator is placed in run.
The exercise is terminated 11 minutes after the simulator has been placed in run.
The simulator response is evaluated against best estimate judgement
.Q where Vogtle plant. data is not available.
This testing was satisfactorily completed. Any discrepancies are identified on Form 12-01.
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j FORM 05-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 5 OF 33
- FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O
- PREPARED BY P. Rubin DATE 9/27/90 REVIEWED BY M.Gibson DATE 9/28/90 APPROVED BY R. Dorman SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90 1
SIMULATOR PERFORMANCE TEST ABSTRACT t
TITLE: ICCA: Small break (05-05) i i
The Vogt e s mu ator is initia11 zed to 100% power EOL, Equilibrium t
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Xe.
A hot leg' leak at SG #2 inlet (malf #37) is inserted 0-20%
severity one minute after the simulator is placed in run.
The exercise is terminated 3 minutes after safety injection actuates.
The simulator response is evaluated against best estimate-judgement O
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This testing-was satisfactorily completed. Any discrepancies are-identified on Form 12-01.
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FORM 05-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 6 OF 33 O
rORM T1TtE: PERro - NCE TEST ABS = cT REVISION O PREPARED BY:P_,. Rubin DATE:9/27/90 REVIEWED BY:M.Gibson DATE:9/28/90 APPROVED BY:R. Dorman SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE: Failure of Pzr SVs and PORVs (05-06)
The Vogtle simulator is initialized to 100% power, EOL, Equilibrium Xe.
A pressurizer safety valve PSV-8010c leakage (malf #58) is inserted 0 10% severity one minute after the simulator is placed in run.
At 6 minutes from the beginning of the simulator run, the malfunction severity is increased to 100%. The exercise is terminated 3 minutes after safety injection actuates.
O The Vogtle simulator is reinitialized to 100% power, EOL, Equilibrium Xe, PORV block HV-8000A open with I/O override.
A pressurizer relief valve PV-455a leakage (malf f63) is inserted 9 100% severity one minute after the simulator is placed in run.
The exercise is terminated 3 minutes after safety injection actuates.
The simulator response is evaluated against best estimate judgement where Vogtle plant data is not available.
This testing was satisfactorily completed. Any discrepancies are identified on Form 17-01.
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FORM 05-02 VOGTLE SIMUIATOR CERTIFICATION PLAN PAGE 7 OF-33 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY P. Rubin DATE 9/27/90 REVIEWED BY M.Gibson DATE 2/20/90 APPROVED BY:R. Dorman SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90
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SIMULATOR PERFORMANCE TEST ABSTRACT TITLE: Loss of Instrument Air (05-07)
The Vogtle simulator is initialized-to 100% power, EOL,-Equilibrium Xe. - A loss of instrument air (malf fl98) is inserted.0 70% severity one minute after the simulator is placed in run.
The main turbine is tripped at 70 psig.
When the instrument air pressure decreases to 10 the malfunction is removed.
The exercise is terminated 3 O
- psig, taut et r en ia tru at ir vr ura retura to aor= t-The simulator response is evaluated against best estimate judgement.
This ~ testing was satisfactorily completed. Any discrepancies are identified on Form 12-01.
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FORM 05-02 VOGTLE SIMULATOR CERTIFICATION PIAN PAGE 8 OF 33 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY P_i_ Rubin DATE 9 r2 7/90 REVIEWED BY:M.Gibson DATE 9/23/90 APPROVED BY:R. Dorman SUFF.' VISOR OPERATIONS TRAINING DATE: 11/15/90 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE: Loss of offsite Power (05-08)
The Vogtle simulator is initialized to 100% power, EOL, Equilibrium Xe. A loss of reserve auxiliary transformers 1NXRA/B (malf 126 & 127) and loss of unit auxiliary transformers 1NXAA/B (malf 128 & 129) is inserted one minute after the simulator is placed in run.
The malfunctions arc removed after specified LORs are verified not able O
to ne re et-rne ton = are re ee arter airunotion re=ovat aaa the 4160 SWGR transferred from the Emergency Diesels to the RATS.
The exercise is terminated after the Emergency Diosols are unloaded.
The simulator response is evaluated against best estimate judgement where Vogtle plant data is not available.
This testing was satisfactorily completed. Any discrepancies are identified on Form 12-01.
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FORM 05-02 VOGTLE SIMUIATOR CERTIFICATION PLAN PAGE 9 OF 33 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY: P. Rubin DATE 9/27/90 REVIEWED BYtM.Gibson DATE:9/28/90 APPROVED BY:L._Dorman SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE: Loss of Emeroency Power (05-09)
The Vogtle simulator is initialized to 100% power, EOL, Equilibrium Xe.
A. loss of control building 4.16 KV swgr 1AA02 (malf #132) is inserted ' one minute after the simulator is placed in run.
The malfunction is removed after the proper loads have been verified deenergized.
The exercise is terminated after the appropriate loads have been restarted.
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The: simulator response is evaluated against best estimate judgement where Vogtle plant data is not available.
This testing was satisfactorily completed. Any discrepancies are identified on Form 12-01.
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FORM 05 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 10 OF 33 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY!P. Rubin DATE:9/27/90 REVIEWED BY:M.Gibson DATE:9/28/90 APPROVED BY:R. Dorman SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90 SIMULA' TOR PERFORMANCE TEST ABSTRACT TITLE: Loss of Emeraency Generators (05-10)
The Vogtle simulator is initialized to 100% power, EOL, Equilibrium Xe..
An emergency diesel DG 1A fails to start (malf $139A) is inserted one minute after the simulator is placed in run.
The DG is verified not to manually start and then placed in standby.
A loss of reserve auxiliary transformer 1NXRA (malf f 126) is inserted.- The DG 1A is verified that it starts and loads properly.
The exercise is l
terminated after the appropriate equipment has started.
O rue i=ut tor re von e i ev 1u tea sein e de t e timate sua ement v
where Vogtle plant data is not available.
This testing was satisfactorily ccmpleted. Any discrepancies are identified on Form 12-01.
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FORM 05-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 11 OF 33 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY:P. Rubin DATE:9/27/90 REVIEWED BY:M.Gibson DATE:9/28/90 APPROVED BY:R. Dorman SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE: Loss of Elec. Dist. Busses (05-11)
MI The Vogtle simulator is initialized to 100% power, EOL, Equilibrium Xe.
A loss of turbine building 13.8 KV swgr 1NAA (malf #130A) is inserted one minute after the simulator is placed in run.
The malfunction is removed after the proper loads have been verified deenergized.
The malfunction is then removed.
The exercise is terminated after the appropriate loads have been restarted.
Tho Vogtle simulator is initialized to 100% power, EOL, Equilibrium Xe.
A loss of control building 4.16 KV swgr 1BA03 (malf $132B) is
' h inserted one minute after the simulator is placed in run.
The malfunction is removed after the proper loads have been verified deenergized.
The malfunction is then removed.
The exercise is terminated after the appropriate loads have been restarted.
The Vogtle simulator is initialized to 100% power, EOL, Equilibrium Xe.
A loss of 480 V swgr 1NB03.(malf #134A) is inserted one minute after the simulator is placed in run.
The-malfunction is removed after-the proper loads have been verified deenergized.
The malfunction is then removed.
The exercise is terminated after the appropriate loads have been restarted.
The Vogtle simulator is initialized to 100% power, EOL, Equilibrium Xe.
A loss of 480 V swgr 1NB02 (malf #134D) is inserted one minute after the simulator is placed in run.
The malfunction is removed after the proper loads -have been verified deenergized.
The malfunction is then removed.
The exercise is terminated after the appropriate loads have been restarted.
The Vogtle simulator is initialized to 100% power, EOL, Equilibrium Xe.
A loss of'480 V swgr 1NB09 (malf #135A) is inserted one minute
-after the simulator is placed in run.
The malfunction is removed i
after the proper loads have been verified deenergized.
The malfunction is then removed.
The exercise is terminated after the appropriate loads have been restarted.
This testing was satisfactorily completed. Any. discrepancies are j
identified on Form 12-01.
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FORM 05-02 VOGTLE SIMULATOR CERTIFICATICI4 PIAN PAGE 12 OF 33 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY:P. Rubin DATE:9/27/90 REVIEWED BYtM.GihSQD DATE:9/28/90 APPROVED BY:R. Dorman SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90 SIMUIATOR PERFORMANCE TEST ABSTRACT TITLE: Loss of Elec. Dist. Busses (05-11)
The Vogtle simulator is initialized to 100% power, EOL, Equilibrium Xe.
A loss of 480 V swgr 1BB06 (malf $13511) is inserted one minute after the simulator is placed in run.
The malfunction is removed after the proper loads have been verified doenergized.
The malfunction is then removed.
The exercise is terminated after the appropriate loads have been restarted.
O The i=utator re con =e i= eva1uatea #9ain=t de=t eatiaate suase eat where Vogtle plant data is not available.
This testing was satisfactorily completed. Any discrepancies are identified on Form 12-01.
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FORM 05-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 13 O? 33' FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY:P. Rubin DATE:9/27/90 REVIEWED BY:M. Gibs 2D DATE:9/28/90 APPROVED BY: R. Dorman SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE: Loss of Instrument AC Busses (05-12)
The Vogtle simulator is initialized to 100% power, EOL, Equilibrium Xe, - unaffected SG control channel selected for input to SGWLC.
A vital instrument panel 1AY1A failure (malf #138A) is inserted one minute'after the simulator is placed in run.
- The malfunction is 0
re oved after the proper loads have been verified deenergi rem The x roi -
1-t r to t a reer the varopri te 1oea-n ve been started.
The Vogtle simulator is initialized to 100% power, EOL, Equilibrium Xe, unaffected SG control channel selected for input to SGWLC.
A vital instrument panel 1CY1A failure (malf #138C) is inserted one minute after the simulator is placed in run.
The malfunction is removed after the proper loads have been verified deenergized.
The exercise is terminated after the appropriate loads have been restarted.
The simulator response is evaluated against best estimate judgement where Vogtle plant data is not available.
This testing was satisfactorily completed. Any discrepancies are identified on Form 12-01.
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FORM 05-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 14 OF 33 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY:P. Rubin DATE:9/27/90 REVIEWED BY:M.GibsoD DATE 9/28/90 APPROVED BY:R. Dorman SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE: Loss of Instrument DC Busses (05-13)
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The Vogtle simulator is initialized to 100% power, EOL, Equilibrium Xe.
An ESF 125 V DC swgr 1AD1 fault (malf #136A) is inserted one minute af ter the simulator is placed in run.
The malfunction is removed after the proper loads have been verified deenergized.
The exercise is terminated after the appropriate loads have been restarted.
1 The Vogtle simulator is initialized to 100% power, EOL, Equilibrium
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minute Xe.
An ESF 125 V DC svgr 1DD1 fault (malf #136D) is inserted one after the simulator is placed in run.
The malfunction is removed after the proper loads have been verified deenergized.
The exercise is terminated after the appropriate loads have been restarted.
The Vogtle simulator is initialized to 100% power, EOL, Equilibrium Xe.
An non-ESP 125 V DC swgr 1ND1 fault (,nalf #137A) is inserted one minute after the simulator is placed in run.
The malfunction is removed after the proper loads have been verified deenergized.
The exercise is terminated after the appropriate loads have been restarted.
The Vogtle simulator is initialized to 100% power, EOL, Equilibrium Xe.
An non-ESP 125 V DC swgr 1ND3 fault (malf #137C) is inserted one minute after the simulator is placed in run.
The malfunction is removed after 1)the proper loads have been verified deenergized and 2) the 480 V ESS instrument panel power auto transfers to the alternate supply.
The exercise is terminated after the appropriate loads have been restarted.-
The simulator response is evaluated against best estimate judgement where Vogtle plant data is not available.
This testing was satisfactorily completed. Any discrepancies are identified on Form 12-01.
FORM 05-02 VOGTLE SIMULATOR CEliTIFICATION PLAN PAGE 15 OF 33 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY P. Rubin DATEt 9/27/90 REVIEWED BY M.Gibson DATE:9/28/90 APPROVED BY R. Dorman SUPERVISOR OPERATIONS TRAINING DATE: 21/15/90 7
SIMULATOR PERFOR&aNE TEST ABSTRACT TITLE: Loss of cond Vacuum /Lvl control (05-14)
The Vogtle simulator is initialized to 100% power, BOL, Equilibrium Xe.
A -loss of _ condenser vacuum (malf $141) is _ inserted 9 100%
severity one minute. after.the simulator is placed in run.
The malfunction is removed when condenser vacuum reaches 7 psia.
'The exercise is~ terminated after condenser vacuum reaches 5-psia.
O The vostte ei utator ie tattiatizea to 1oo* Power, sot, raut11erium
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A hotwell level transmitter LT-4415 failure (malf f 14 2 ). is.
inserted 9 10% severity one minute after the simulator.is placed in run.
The malfunction is removed 8 minutes after_the simulator has been placed in run.
The exercise is terminated after condenser _ level returns to normal.
The simulator response is evaluated against best estimate judgement where Vogtle'planc data is not available.
-This testing was satisfactorily completed. Any discrepancies are identified on Form 12-01.
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FORM 05-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 16 OF 33 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY:P. Rubin DATE:9/27/90 REVIEWED BY:M.Gibson DATE 9/28/90 APPROVED BY: R. Dorman SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE: Loss of Service Water (05-15) i
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The Vogtle simulator is initialized to 100% power, BOL, Equilibrium Xe, standby NSCW pump in auto. -An NSCW train B pump P-2 shaft break (malf $191A) is inserted one minute after the simulator is placed in run. The NSCW. pump P-2 handswitch is placed to STOP and then START.
Both NSCW pumps P-2 & 4 handswitches are placed in the " Pull to Lock" 0
. position.
malfunction is removed. Pump P-2 is then manually The -
t rt a-Ta x roi - 1 ter in tea arter "SCw riow return-to normal.
The Vogtle simulator is initialized to 100% power, BOL, Equilibrium Xe, standby NSCW pump in auto.
An NSCW train A pipe break to CCW Hx
- 1 (malf #192) is inserted one minute after the simulator is placed in run.- The malfunction is removed after 5 additional minutes.
The exercise is terminated after NSCW pressure returns to normal.
The Vogtle simulator is initialized to 100% power, BOL, Equilibrium Xe, standby NSCW pump in auto.
An NSCW train B pipe break to ACCW Hx
- 2 (malf #193) is inserted one minute after the simulator is placed in run.
The malfunction is removed after 5 additional minutes.
The exercise is terminated after NSCW pressure returns to normal.
The simulator response is evaluated against best estimate judgement.
This testing was satisfactorily completed. Any -discrepancies are
' identified on Form 12-01.
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FORM 05-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 17 OF 33 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY:P. Rubin DATE:9/27/90 REVIEWED BY:M.Gibson DATE:9/28/90 APPROVED BY:R. Dorman SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90 4
SIMULATOR PERFORMANCE TEST ABSTRACT TITLE: Loss of Shutdown Coolina (05-16)
The Vogtle simulator is initialized to 0% power, BOL,197 Deg F, Mode 1
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A RHR pump P-1 trip (malf #45A)~is inserted one minute after the simulator is placed in run.
The RHR pump P-1 handswitch is placed to STOP and then START.
RHR pump P-1 is verified not started.
RHR pump P-1 handswitch is placed to STOP and the malfunction removed.
Pump The exercise is terminated after RHR O
P-1 is then manually started.
riov returns to norma 1.
The simulator-response is evaluated against best estimate judgement.
This testing was satisfactorily completed. Any discrepancies are identified on Form 12-01.
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FORM 05-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 18 OF 33 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY:P. Rubin DATE:9/27/90 REVIEWED BY L_GihDJ2D DATE 9/28/90 APPROVED BY:R. Dorman SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE: Loss of Comoonent Coolina (05-17)
The Vogtle simulator is initialized to 50% power, BOL, Equilibrium Xe, standby CCW pump in AUTO.
A CCW pump P-3 trip (malf #194B) is inserted one minute after the simulator is placed in run.
The CCW pump P-3 handswitch is placed to STOP and then START.
CCW pump P-3 is verified not started.
CCW pump P-3 handswitch is placed to STOP and the malfunction removed.
Pump P-3 is then manually started.
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exerci e 1 ter ta tea reer ccW r1ew t 8111=e -
The Vogtle simulator is initialized to 0% power, BOL, Hot Shutdown, standby CCW pump in AUTO.
A CCW train B pipe break to RHR HX #2 (malf #196) is inserted one minute after the simulator is placed in run.
The malfunction is removed after the CCW pumps have tripped.
Two CCW pumps on train B are then manually started.
The exercise is terminated after CCW train B pressure returns to normal.
The Vogtle simulator is initialized to 50% power, BOL, Equilibrium Xo, standby ACCW pump in AUTO.
An ACCW pump P-1 locked rotor (malf #197A) is inserted one minute after the simulator is placed in run.
The ACCW pump P-1 handswitch is placed to STOP and then START.
ACCW pump P-1 is verified not started.
ACCW pump P-1 handswitch is placed to STOP and the malfunction removed.
Pump P-1 is then manually started.
The exercise is terminated after ACCW flow stabilizes.
The simulator response is evaluated against best estimate judgement.
This testing - was satisfactorily completed.- Any discrepancies are identified on Form 12-01.
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R TORM 05-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 19 OF 33 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY P. Rubin DATE:9/27/90 REVIEWED BY:M.Gibson DATE 9/28/90 APPROVED BY:R. DormAD SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90 L
!o SIMULATOR PERFORMANCE TEST ABSTRACT
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TITLE: Loss of All Feedwater (05-18) p i-Ln f
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.The Vogtle simulator is initialized to 100% power, EOL, Equil!,
Xe. A complete loss of all feedwater is initiated by insorting a trip of both main feedwater pumps (malf 146A & B) and a trip of all j.
emergency feedwater pumps (malf 160A & B and 161) one minute after tl A simulator is placed in run.
Malfunctions 160A & B are removed af' h
the pressurizer PORVs have opened and Qen all SGs are emptied.
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P-2 & 3 are then manually started.
The exercise is terminated after j
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the pressurizer safety. relief valves _close.
4 The simulator response is evaluated against best estimate jud, Paaent where Vogtle plant data is not available.
This ' testing was satisfactorily completed. Any discrepancies are o
identified on Form 12-01.
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l FORM 05-02 VOGTLE SIMULATOR CERTIFICATION PIAN PAGE 20 OF 33 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY P. Rubin DATE:9/27/90 REVIEWED BY:M.Gibson DATE:9/28/90 APPROVED BY:R. Dorman SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90 1
SIMULATOR PERFORMANCE TEST ABSTRACT TITLE: Control Rod Failures (05-19)
The Vogtle simulator is initialized to 50% power, EOL, Equilibrium Xe.
A dropped RCCA H8 (malf #28I) is inserted one minute after the simulator is placed in run.
The rod is verified unmovable in all rod control modes.
The malfunction is removed and the dropped roc retrieved using the appropriate plant procedure.
The exercise is terminated after the rod is within 2 steps of its group.
O The Vogtle simulator is initialized to 1E-8% power, BOL, 557 Dog F, RCCA bank D not fully inserted or withdrawn.
A stuck RCCA H8 (malf
- 241) is inserted one minute after the simulator is placed in run.
RCCA bank CD is_ withdrawn and then inserted 10 steps.
The rod is 4
verified to remain stationary.
The lift coils for all rods except 118 in bank CD are opened.
Again an attempt to withdraw / insert 118 is made.
This is followed by a manual reactor trip.
The exercise is terminated after the rod is verified stuck following a reactor trip.
The simulator response is evaluated against best estimate judgement where Vogtle plant data is not available.
This testing was satisfactorily completed. Any discrepancies are identified on Form 12-01.
l
j" FORM 05-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 21 OF 33 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY P. Rubin DATE:9/27/90 REVIEWED BY M.GibsGD DATE:9/28/90 i
APPROVED BY:R. Dorman SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90 FIMULATOR PERFORMANCE TEST ABSTRACT T!fLE: Inability to Drive Control Rods (05-20) l I
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.The Vogtle simulator is initialized to 50% power, BOL, Equilibrium Xe, 1
rod control in Manual.
A control banks fail to move on auto or manual-demand (malf #22) is inserted.
The rods are verified unmovable in Manual.:
Rod control is shifted to Auto.
This is followed by adjusting turbine ' load by i 10%.
After the rods are verified The exercise is terminated after O
stationary, the reactor is tripped.
all the rods are verified on the bottom.
Tlie simul'ator response is evalu'ated against best estimate judgement where Vogtle plant data is not available.
This testing was satisfactorily completed. Any discrepancies are identified on Form 12-01.
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FORM 05-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 22 OF 3 3 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY:P. Rubin DATE:9/27/90 REVIEWED BY:M.Gibson DATEt 9/28/9,Q APPROVED BY:R. Dorman SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE: Fuel Claddina Failure (05-21)
The Vogtle simulator is initialized to 50% power, BOL, Equilibrium Xe.
A failed fuel (malf #60B) is inserted @ 10% severity one minute after the simulator is placed in run.
This is followed by inserting a SG
- 2 tube rupture (malf 86) 010% severity 6 minutes af ter the simulator is placed in run.
The exercise is terminated after 11 minutes after the simulator is placed in run.
O The simulator response is evaluated against best estimate judgement where Vogtle plant data is not available.
l This testing was satisfactorily completed. Any discrepancies are identified on Form 12-01.
O
FORM 05-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 2 3 Ef'~E
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FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY:P. Rubin DATE:9/27/90 REVIEWED BY:M.Gibson DATE:2/_20/90 APPROVED BY:R. Dorman SUPERVISOR OPERATIONS TRAINING DATE: 12/15/90 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE: Generator Trio (05-22)
I I
The Vogtle simulator is initialized to 100% power, BOL, Equilibrium Xe.
A main generator trip (malf #116) is inserted one minute after the simulator is placed in run.
The malfunction is removed after it is verified that LOR 386-G9 will not reset.
The exercise is terminated after i.sa 386-G9 is reset.
O rue simu1 tor reevonee te evatu tea 9ainet deet eetimate suasement where Vogtle plant data is not available.
This testing was satisfactorily completed. Any discrepancies are identified on Form 12-01.
l l
FORM 05-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 24 OF 3 3 qb FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY:P. Rubin DATE:9/27/90 REVIEWED BY:M.Gibson DATE:9/28/9.Q APPROVED BY:R. Dorman SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE: Failure in Auto Control Svs That Affect Reactivity & Core _ Heat Removal (05-231 The Vogtle simulator is initialized to 100% power, BOL, Equilibrium Xe.
A spurious train B safety injection signal (malf #168) is inserted one minute after the simulator is placed in run.
This is followed by verifying selected SI signale can be reset after the block / reset time delay has timed out.
The exercise is terminated after the SI signals are rest.
O The Vogtle simulator is initialized to 100% power, BOL, Equilibrium Xe, control rods in AUTO, one BATP running.
A RCS boration (malf #82) is inserted 0 100% severity one minute after the simulator is placed
~
in run.
The malfunction is removed 11 minutes after the simulator is placed in run.
This is followed by manually closing valve HV-8104.
The exercise is terminated 5 minutes after valve HV-8104 is closed.
The simulator response is evaluated against best estimate judgement where Vogtle plant data is not available.
This testing was satisfactorily completed. Any discrepancies are identified on Form 12-01.
i J
_ _ _ = _ _ _ _. -
FORM 05-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 25 OF 33 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY:P. Rubin DATE:9/27/90 REVIEWEL' BY:M.Gibson DATE:2/_2pf1Q APPROVED BY:R. Dorman SUPERVISOR OPERATIONS TkAINING DATE: 11/15/90 i
SIhtJLATOR PERFORMANCE TEST ABSTRACT TITLE: Failure in Reactor Coolant Pressure tur15L,.
Volume Control SYrgem ( 0 5-2_41._
WI The Vogtle simulator is initiclized to 100% power, BOL, Equilibrium i
Xe.. A pressurizer pressure transmitter PT-455 failure (malf #59A) is inserted 0100% severity one minute after the simulator is placed in run.
The malfunction is removed after 5 additional minutes.
The exercise is terminated after the actual pressurizer level increases to 30%.
O I
The Vogtle simulator is initialized to 100% power, BOL, Equilibriut; I
Xe.
A pressurizer pressure transmitter PT-459 failure (malf #61A) is' inserted 9 00 severity one minute after the simulator is placed in run.-
The maFunction is removed after 5 additional minutes.
The exercise is cerminated after 10 ininutes.
The:simulat7r response is evaluated against best estimate judgement where Vogtle plant data is not available.
This testing was satisfactorily completed. Any discrepancies are identified on Form 12-01.
9
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FORM 05-02 VOGTLE SIMULATOR CERTIFICATION PIAN PAGE 26 OF 33
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FORM TITLE: PERFORMANCE TEST AB'3 TRACT REVISION O PREPARED BY: P. Rubin DATE:9/27/90 fEVIEWED BY:M.Gibson DATE:9/28/90 APPROVED BY:R. Dorman SUPERVISOR OF'/P.ATIONS TRAINING DATE: 11/15/90 4
. i __
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SIMULATOR PERFORMANCE TEST ABSTRACT TIF',E: Main Steam Line Break OutsidqL, Containment (05-25)
{
Ti itle sind ator is initialized to 49% power, EOL, Equilibrium Xe.
~
l:
' team sr tety valve PSV-3001 leak (malf #947; is inserted 0100%
< *foricy c:ie minute - af ter the simulator is pleimd in run.
The exercise is terminated 6 minutes after the simulato; L > 71 aced in run.
"he Equilibrium O
xe Vogtle simulator is initialized to 100% power, Eot.,
^ = in '*
dro v tve ne aer rupture (= te asz) 1 in ertea 9100% se'4r14(i one minute after the simulator is placed in run.
The exerc).se 1i ter7r.%ated 11 minutes after the simulator is J, laced in run.
The cimulator rasp use is evaluated against best estimate N gament where 'fogtle plant data is not available.
This t e s t i n g w a r, satisfactorily completed. Any discrepancies are identified on Form 12-01.
O L
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FORM 05-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 27 OF 33 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPlaED BY:P. Rubin DATE:9/27/90 REVIEWED BY:M.Gibson DATE:9/28/90 APPROVED BY:R. Dorman SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90 SIMULATOR PERFORMAN' E TEST ABSTRACT TITLE: Main Steam Line Break Inside Containmgnt
_(05-26)
The Vogtle simulator is initialized to 100% pover, EOL, Equilibrium Xa.
A foodwater line #2 rupture - inside containment (malf #153) is inserted 0 50% neverity one minuto after the simulator is placed in run.
The exercise is terminated 11 minutes after the simulator is placed in run.
O The simutator reePonse is eve 1uated e9einst dest estimate 9udeement where Vogtle plant data is not available.
This testing was satisfactorily completed. Any discrepancies are identified on Form 12-01.
O
l FORM 05-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 28 OF 33 FOPJi TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY:P_ dubin DATE:9/27/90 LEVIEWED BY:M.Gibson DATE:9/28/90 APPROVED BY:B. Dorman SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE: Main Feed Line Break Inside Containrent (05-27)
The Vogtle simulator is initialized to 100% power, EOL, Equilibrium Xe.
A feedwater line #1 rupture outside containment (malf #154) is inserted 0 100% severity one minute after the simulator is placed in run.
The exercise is terminated 11 minutes after the simulator is placed in run.
O
- where Vogtle plant data is not available.
ue ei u1 tor reePoase se evetuetea eeetaet deet eeti ete sua e eat e
This testing was satisfactorily completed. Any discrepancies are identified on Form 12-01.
O i
1
)RM 05-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 29 OF 33 FORM TITLE:. PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY:P. Rubin DATE:9/27/90 REVIEWED BY:M.Gibson DATE:9/28/90
- APPROVED BY:R. Dorman SUPERVISOR OPERATIONS TRAINING DATF: 11/15/90 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE: Nuclear InstrumerLhilures (05-28)
The Vogtle simulator is initialized to 100% power, BOL, Equilibrium Xe.
A power range chan 42 upper detector failure (malf #7B) is inserted 0 50%. severity one minute after the simulator is placed in run. -.
Three minutes after the simulator is placed in
- run, reactor / turbine load is reduced 10%. The malfunction is then removed.
The exercise is terminated 1 minute after malfunction removal.
The Vogtle simulator is initialized to 100% power, BOL, Equilibrium Xe. - A power range chan 44 high voltage failure (malf #8D) is inserted 0 30% severity one minute after the simulator is placed in run.
Three minutes after the simulator is placed in run, reactor / turbine load. is
- reduced 10%.
The malfunction is then removed.
The exercise is terminated 1 minute after malfunction removal.
The Vogtle simulator is initialized to 50% power, BOL, Equilibrium Xe.
A power range output oscillation (malf #11A) is inserted 0 30%
severity one _ minute after the simulator is placed in run.
Three minutes after _the simulator is placed in run, reactor / turbine load 'is increased 10%.
The malfunction is-then removed.
-The exercise is terminated 1 minute after malfunction removal.
The simulator response is evaluated against best estimate judgement.
This testing was satisfactorily completed. Any discrepancies are identified on Form 12-01.
- O
FORM 05-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 30 OF 33 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY:P. Rubin DATE:9/27/90 REVIEWED BY:M.Gibson DATE:9/28/90 APPROVED BY:R. Dorman SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE: Process Instrument Failures (05-29)
The Vogtle simulator is i..itialized to 0% power, BOL, cold shutdown, i
solid pressurizer, RHR train A in operation.
A loop pressure transmitter-PT-438 failing high (malf #38A) is inserted one minute after.the simulator is placed in run.
The RHR pump for loop 1 is secured and an attempt to open RHR valve HV-8701A is made.
The malfunction is removed after 5 minutes after the simulator is placed in run.
The exercise is terminated 7 minutes after malfunction removal.
O
'*Xe.
ne voet1e ei utetor te taitietizea to 1oo= Power, not, seui11drium A hot leg RTD ' TE-411A failure (malf #40A) is inserted 0 0%
. severity one minute after the simulator la placed in run.
After-5 additional minutes, the malfunction is removed.
The exercise is terminated 1 minute after malfunction removal.
The Vogtle simulator is initialized to 100% power, BOL, Equilibrium Xe.
A cold leg RTD TE-413B failure (malf #41A) is inserted 0 90%
severity one minute after the simulator-is placed in run.
After 2 additional minutes, the malfunction is removed.
The exercise is-terminated--I minute after malfunction removal.
The Vogt.le simulator is initialized to 30% power, BOL, Equilibrium Xe.
A-channel 1 RCS flow elements failure (malf #44C) is inserted 0 50%
severity one minute after the simulator is placed in run.
After 2 additional minutes, the malfunction severity-is reduced to 0%.-
The malfunction is removed 6 minutes after the simulator is placed in run.
The exercise is term nated 1 minute after malfunction removal.
'The Vogtle simulator is initialized to 100% power, BOL, Equilibrium Xe, LT 459 selected for control.
A pressurizer level transmitter LT-459 failure (malf #61A) is inserted 0 100% severity one minute after the simulator is placed 'in run.
After 2 additional minutes, the calfunction is removed.
The exercise is terminated 1 minute after malfunction removal.
This testing was satisfactorily completed. Any discrepancies are identified on Form 12-01.
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FORM 05-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 31 OF 33 -
FORM TITLE:-PERFORMANCE TEST ABSTRACT REVISION 0 1
PREPARED BY P. Rubin DATE:9/27/90 REVIEWED BY:M.Gibson DATE:9/28/90 -
1 APPROVED BY:R. Dorman SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90 SIMULATOR-PERFORMANCE TEST ABSTRACT 1
TITLE: Process Instrument Failures (05-29)
The Vogtle simulator-is initialized to 100% power, BOL, Equilibrium Xe.
A steam generator-level transmitter-'LT-519_ failure _(malf #88A)_
-is. inserted;9-90% severity'one minute after the simulator is placed in-run.
' Eleven minutes -after the simulator is placed in run, the
-malfunction is removed.
The exercise is terminated 1 minute after-i malfunction removal..
h.TheVogtle--simulatorisinitializedto100%-power,BOL, Equilibrium
- Xe, -control rods _ in AUTO. A main turbine impulse pressure transmitter PT-505 failure' (malf #62A) is inserted 910% severity one minute after
-j the. simulator is placed in run. The malfunction' severity is increased' to 85% afterL 2 additional minutes.
Five minutes after the simulator
-ic placed-in run, the malfunction -is removed.
The ixercise is
-terminated 1 minute after malfunction removal.
.The simulator response-is evaluated against best-estimate judgement where Vogtle plant data-is_not available.
l>
This testing was' satisfactorily completed. Any discrepancies ~are 11dentified-on Form 12-01.
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FORM 05-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 32 OF 33 O
v FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY:P. Rubin DATE:9/27/90 REVIEWED BY:M.Gibson DATE:,2D 8/90 APPROVED BY:R. Dorman SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE: Passive Malfunctions in ESF (05-30)
The Vogtle simulator is initialized to 100% power, EOL, Equilibrium Xe.
A train A main steam line isolation automatic actuation failure (malf #164) it, inserted.
A main steam line #3 rupture insido containment (malf #91) is inserted at 100% severity one minute after the simulator is placed in run.
Af ter 2 additional minutes the train A MSIV handswitch is placed to close.
The exercise is terminated 6 O
minutes after the simulator is placed in run.
w/
The Vogtle simulator is initialized to 100% power, EOL, Equilibrium Xe.
A train A containment spray automatic actuation failure (malf
- 164) is inserted.
A RCS loop 3 cold leg rupture (malf #35) is inserted one minute after the simulator is placed in run.
After 2 additional minutes the containment spray pump #1 handswitch is placed to start.
Four minutes after the simulator is placed in run valves HV-9001A & HV-8994A handswitches are placed to open.
The exercise is terminated 6 minutes after the simulator is placed in run.
The Vogtle simulator is initialized to 100% power, EOL, Equilibrium Xe.
A train B safety injection manual actuation failure (malf #170) is inserted.
Three minutes after the simulator is placed in run an attempt to manually initiate safety injection on both channels is made.
The exercise is terminated 6 minutes after the simulator is placed in run.
The simulator response is evaluated against best estimate judgement.
This testing was satisfactorily completed. Any discrepancies are identified on Form 12-01.
o
FORM 05-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 33 OF 33 i
FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION O PREPARED BY:P. Rubin DATE:9/27/90 REVIEWED EY:M.Gibson DATE:9/28/90 APPROVED BY:R. Dorman SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE: Failure in Auto Reactor Trio (05-31)
The Vogtle simulator is initialized to 100% power, EOL, Equilibrium Xe, control rods in manual.
A failure of automatic reactor trip (malf
- 12) is inserted.
A main turbine trip (malf # 98) is inserted one minute after the simulator is placed in run.
After 10 additional minutes, the reactor-is manually tripped.
The exercise is terminated 16 minutes after the simulator is placed in run~.
The simulator response is evaluated against best estimate judgement O
where Vogtie-plant data is not available.
This testing was satisfactorily completed. Any discrepancies. are identified on Form 12-01.
i O
1 FORM:.06-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 1 OF 12 A
\\.
RM TITLE: PERFORMANCE TEST-ABSTRACT REVISION O
PREPARED BY: P. Rubin DATE: 9/27/90 REVIEWED BY: L_Gibson DATE: 9/28/90 APPROVED BY:
R.
Dorman SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE : Plant Startuo to Hot Standby (06-01)
The Vogtle simulator is initialized to 0% power, BOL, < 160 Deg F, Mode 5.
A plant startup is performed from cold shutdown to Hot Standby.
The exercise is conducted using controlled copies of the Vogtle plant procedures.
If a step is performed and the response of the simulator does not meet the startup test criteria, or if a step can not be performed, or if an alarm annunciates but shouldn't or doesn't annunciate but should, then a discrepancy report is written.
This scenario includes coming off Shutdown Cooling (i.e.,
RHR),
O tor tas e dudete ia the pre
- urizer, tertia 9 ene reeotor oooteat pumps, warmup of the secondary side, forming a condenser vacuum, maintaining steam generator levels with auxiliary feedwater, and performing boron dilution.
The exercise is terminated when the plant is stable at 557 Deg F.
The simulator response is evaluated against best estimate judgement where Vogtle plant data is not available.
This testing was satisfactorily completed. Any discrepancies are identified on Form 12-01.
O i
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FORM: 06-02 VOGTLE SIMULATOECERTIFICATION PLAN PAGE 2 OF 12 (h
\\_!RM TITLE: PERFORMANCE TEST ABSTRACT REVISION O
PREPARED BY: P. Rubin DATE: 9/27/90 REVIEWED BY: M. Gibson DATE: 9/28/90 APPROVED BY:
R.
Dorman SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE : Nuclear Startuo from Hot Standby to Rated Power (06-02)
The Vogtle simulator is initialized to 0% power, BOL, 557 Dog F.
A nuclear startup is performed from Hot Standby to rated power.
The exercise is conducted using controlled copies of the Vogtle plant procedures.
If a step is performed and the response of the simulator does not meet the startup test criteria, or if a step can not be performed, or if an alarm annunciates but shouldn't or doesn't annunciate but should, then a discrepancy report is written.
This scenario includes conducting a 1/M plot during rod withdrawal, O
treneferrine steem seneretor 1evet contro1 from the eux111ery feedwater system to the main feedwater system, rolling the turbine up to speed, synchronizir.g the main generator to the grid, and performing boron dilution to 100% power.
The exercise is terminated when the plant is stable at 100% power.
The simulator response is evaluated against best estimate judgement where Vogtle plant data is net available.
This testing was satisfactorily completed. Any discrepancies are identified on Form 12-01.
FORM:-06-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 3 OF 12 A
( JRM TITLE: PERFORMANCE TEST ABSTRACT REVISION O
PREPARED BY: P. Rubin DATE: 9/27/90 REVIEWED BY: M. Gibson DATE: 9/28/90 APPROVED BY: R.
Dorman SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE : Load Chances (06-03)
The Vogtle simulator is initialized to 100% power, BOL.
A plant load change is performed from 100%
to 80% and back to 90%.
The exercise is conducted using controlled copies of-the vogtle plant procedures.
If a step is performed and the response of the simulator does not meet the startup test criteria, or if a step can not be performed, or if an alarm annunciates but shouldn't or doesn't annunciate but should, then a discrepancy report is written.
This scenario includes a load reduction of 20% at a rate of 1% per O
followed by a load increase of 10% at a rate of rae 9 eat te 11 owed to eted111=e ror s taute -
rate is taute-1 8% per hour.
The exercise is terminated when the plant is stable at-90% power.
.The simulator response is evaluated against best estimate judgement where Vogtle. plant data is not available.
This testing was satisfactorily completed. Any discrepancies are identified on Form 12-01.
l O
FORM: 06-02 VOGTLE SIMULATOR-CERTIFICATION PLAN PAGE 4 OF 12 O
N JRM TITLE: PERFORMANCE TEST ABSTRACT REVISION O
PREPARED BY: P. Rubin DATE: 9/27/90 REVIEWED BY: M. Gibson DATE: 9/28/90 APPROVED BY:
R.
Dorman SUPERVISOR OPERATIONS TRAINING DATE: 11/_15/90 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE : Plant Shutdown from Rated Power to-Hot Standby (06-04)
The ' Vogtle simulator is initialized to 100% power, BOL.
A plant shutdown is performed from rated power to Hot Standby.
The exercise is conducted using controlled copies of the Vogtle plant procedures.
If a step is. performed and the resp 5nse of the_ simulator does not meet the startup test criteria, or if a step can not be performed, or if an alarm annunciates but shouldn't or doesn't annunciate but should, then a discrepancy report is written.
This scenario includes commencing a power descent to 5% at a rate of
_1%.per minute, inserting all control
- rods, transferring steam generator level control from the main feedwater system to the auxiliary feedwater system, and tripping the main turbine.
The exercise is-terminated when the plant is stable at Hot Standby.
The simulator response is evaluated against best estimate judgement where Vogtle plant data is not available.
This testing was satisfactorily completed. Any discrepancies are identified on Form 12-01.
O 1
m FORM:- 06 VOGTLE SIMULATOR CERTIFICATION PLAN PAdE 5 OF 12 p
RM TITLE: PERFORMANCE TEST ABSTRACT REVISION O
PREPARED BY: P. Rubin DATE: 9/27/90 REVIEWED BY: M. Gibson DATE: 9/28/90 APPROVED BY:
R.
Dorman' SUPERVISOR OPERATIONS TRAINING DA7E: 11/15/90
~
SIMULATOR PERFORMANCE TEST ABSTRACT TITLE : Cooldown to Cold Shutdown Condit19_DE (06-05)
'The Vogtle simulator is initialized to 0% power, BOL, Hot Standby.
A plant shutdown is - performed from Hot Standby to cold shutdown conditions.
The exercise is conducted using controlled copies of the Vogtle plant procedures.
If a step is performed and the response of the simulator does not meet the startup test criteria,_or if a step can not be performed, or if-an~ alarm annunciates but shouldn't or doesn't annunciate but should, then a discrepancy report is written.
This scenario includes commencing a plant shutdown to < 200 Deg F, verifying an adequate-shutdown margin exists, borating the. RCS,
10 -
ourias ene re ctor coot at vu 9, sota9 oa suutaowa coo 11a9, eaa collapsing the pressurizer-bubble.
The exercise is terminated when the plant is stable at < 140 Deg F.
The simulator response is evaluated against best estimate judgement
-where Vogtle plant data is-not available.
This testing was satisfactorily completed. Any discrepancies are identified on Form 12-01.
4 O
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- ~ _ - -
FORM: _06-02 VOGTLE SIMULATOR CERTIFICATION PLAN
.PAGE 6 OF 12 RM TITLE: PERFORMANCE TEST ABSTRACT REVISION O
PREPARED _BY: P. Rubin DATE: 9/27/90 REVIEWED BY: M. Gibson DATE: 2/_28/90 1
l APPROVED BY:
R.
Dorman SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE : Reactor Trio With Recovery to Rated Power (06-06)
The Vogtle simulator is initialized to 100% power, BOL, Equilibrium Xe.
A' reactor trip is performed with a recovery to rated power.
The exercise is conducted using controlled copies of the Vogtle plant procedures.
If a step is performed and.the response of the simulator does not meet the startup test criteria, or if a step can not be or if an alarm annunciates but shouldn't or doesn't performed, annunciate but should, then a discrepancy report is written.
This scenario includes initiating a reactor. trip 1 minute after the simulator _is placed in run, stabilizing the plant at Hot Standby, b
utilizing "Fest Time" to accelerate the Xe concentration at 60Xs
. normal for 20 minutes (equates to 20 Hrs real time), and commencing a power ascension to 100%.. The exercise is terminated when the plant is stablo.at 100%_ power.
The simulator response is evaluated against best estimate judgement where Vogtle plant data is not available.
This testing was satisfactorily completed. Any discrepancies are identified on Form 12-01.
i O
FORM: 06-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 7 OF 12
( /RM TITLE: PERFORMANCE _ TEST ABSTRACT REVISION O
PREPARED BY: P. Rubin DATE: 9/27/90 REVIEWED BY: M. Gibson DATE: 9/28/90 APPROVED BY:
R.
Dorman SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE : Core Performance Tests (06-07) __
The Vogtle simulator is utilized to perform core physics testing to determine rod worth for BOL & EOL, Rod Worth with overlap, Power Defect, Doron Worth and ITC. " Coretest", an internal program supplied by Westinghouse is used to determine most of this data. " Coretest" was sucessfully validated during the acceptance testing of the core model.
For certification, the test results are compared to the acceptance criteria outlined in the procedure. The criteria is based on the Unit 1, Cycle 2 NDR. In addition, the results are compared to the current cycle NDR to ensure that no training impact exists. If the simulator response does not meet the acceptance
- criteria, a
O aiecrevency report te writtea e,a aotea witnin ene proceaure-This testing was satisfactorily completed. Any discrepancies are identified on Form 12-01.
O
-J FORM: 06-02 VOGTLE SIMUIATOR CERTIFICATION-PLAN PAGE 8 OF 12 RM TITLE: PERFORMANCE TEST' ABSTRACT REVISION O
-PREPARED BY: P. Rubin DATE: 9/27/90 REVIEWED BY: M. Gibson DATE: 9/28/90 APPROVED BY:
R.
Dorman SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90 SIMULATOR PERFORMANCE TEST ABSTRACT-TITLE : Surveillance Testina on Safety Eauinment-or Systems (06-08)
The.Vogtle simulator is initialized to conditions required by the diesel generator operability test procedure.
A diesel-generator surveillance test is performed to determine the availability of the
- 1-diesel-generator.
The exercise is conducted using controlled copies of the Vogtle plant procedures.
If a step is performed and the
-response of the simulator does not meet the test criteria, or-if a step can not be performed, or if an alarm annunciates but shouldn't or doesn't. annunciate but should, then a discrepancy report is written.
- O The voet1e simu1ator is inteiatized to conditions required to perform
.each of the following surveillance tests:
1) 14980 DG operability. test 2) 14423-1 Source range NIS channel operability test 3) 14424-1 Intermediate range'NIS analog channel operability test 4) 14425-1 Power range quarterly analog channel operational test
-5) 14510 Control room emergency filtration system operability test
.7) _
14490 -Containment cooling system operability test 6) 14705-1 Boron injection flow rate verification-test
'8)-
-14406-1 Boron injection flow path verification - shutdown 9) 14405-1 Boron injection flow path verification during operation 0
i l
1 FORM: 06-02
.VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 9 OF 12 RM TITLE: PERFORMANCE TEST ABSTRACT REVISION O
PREPARED BY: P. Rubin DATE: 9/27/90 REVIEWED BY: M. Gibson DATE: 9/28/90 APPROVED BY: R.
Dorman SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90 f
\\
t SIMULATOR PERFORMANCE TEST ABSTRACT TITLE : Surveillance Testino on Safety Eauioment or Systems (06-08) 10) 14805-1
-Residual heat removal pump and check va.1ve IST 11) 14220-1 Main turbine valves weekly stroke test 12) 14410-1 Control rod operability test 13) 14725-1 Reactor vessel head vent path operational flow test 14) 14842-1 Main steam isolation valves partial stroke inservice test 15).
14505-1 Main feed isolation valves partial stroke inservice test 16) 14230-1
-A.
C.
source verification
.( )
This testing was satisfactorily completed. Any discrepancies are identified-on Form 12-01.
O
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FORM: 06-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 10 OF 12 RM TITLE: PERFORMANCE TEST ABSTRACT REVISION O
i PREPARED BY: P. Rubin DATE: 9/27/90 REVIEWED BY1 M. Gioson DATE:-9/28/90
{
APPROVED BY:
R.
Dorman SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90 i
SIMULATOR PERFORMANCE TEST ABSTRACT TITLE : Steady State Test 0 30% Power (06-09)
The Vogtle simulator is initialized to 30% power, BOL, Equilibrium Xe.
The simulator is placed in run and allowed to operate for 60 minutes.
A heat balance calculation is performed 10 minutes after the simulator is placed in run.
The calorimetric is conducted using controlled copies of the Vogtle plant procedures.
If a step is performed and the response of the simulator does not meet the startup test criteria, or if a step can not be performed, or if an alarm annunciates but shouldn't or doesn't annunciate but should, then a discrepancy report is written.
The exercise is terminated after 30 minutes.
O The simulator response is evaluated against the acceptance criteria specified in-the plant procedures and in Section 4.1, Steady State Operation, of-ANSI /ANS-3.5-1985.
This testing was satisfactorily completed. Any discrepancies are identified on Form 12-01.
O
. ~. _
FORM: 06-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 11 OF 12 RM TITLE: PERFORMANCE TEST ABSTRACT REVISION O
PREPARED BY: P. Rubin. DATE: 9/27/90 REVIEWED BY: M. Gibson DATE: 9/28/90 APPROVED BY:.R. Dorman SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE : Steady State Test 0 75% Power (06-10)
The Vogtle simulator is initialized to 75% power, BOL, Equilibrium Xe.
The simulator. is placed in run-and allowed to operate for 60 minutes.
A heat balance calculation _is performed 10 minutes af ter the simulator is'placed in run.
The calorimetric is conducted using controlled copies of the Vogtle plant procedures.
If a step is performed and the response of the simulator does not meet the startup test criteria, or if a step can not be performed, or if an alarm annunciates but shouldn't or doesn't annunciate but should, then a discrepancy report is written.
The exercise is terminated after 30 minutes, h
The simulator response is evaluated against the acceptance criteria specified-in the plant procedures and in Section 4.1, Steady State Operation, of ANSI /ANS-3.5-1985.
This testing was satisfactorily completed. Any discrepancies are identified on Form 12-01.-
i-O
. - _. -.. _ _ - - - - ~.. - ~.
l FORM.06-02 VOGTLE SIMTJLATOR CERTIFICATION PLAN PAGE 12 OF 12 RM TITLE: PERFORMANCE TEST ABSTRACT REVISION
-O PREPARED BY :P. Rubin DATE: 2/_2.7/9A REVIEWED BY: M. Gibson DATE: 9/28/90 1
APPROVED BY: R.
Dorman SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90 SIMULATOR PERFORMANCE TEST ABSTRAOT
-TITLE': Steady State Test 0 100% Power (06-11)
The Vogtle simulator is initialized to 100% power, BOL, Equilibrium
.Xe.
The simulator is placed in run and allowed to--operate for 60 minutes., - A heat balance calculation is performed 10 minutes after the simulator is placed in run.
.The calorimetric-is conducted using controlled copies of the Vogtle plant procedures.
If a step is performed and the response of the simulator does not meet the'startup
. test criteria, -or if - a step can not be performed, or if an alarm annunciates but shouldn't or doesn't annunciate but should, then a-discrepancy report is-written.
The exercise is terminated after 60 minutes.
The-simulator response is evaluated against the acceptance criteria specified in the plant procedures.and in Section 4.1, Steady State Operation, of ANSI /ANS-3.5-1985.
ThisL testing was satisfactorily completed. Any discrepancies are identified on Form 12-01..
s O
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FORM: 07-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 1 OF 10 RM TITLE: PERFORMANCE TEST ABSTRACT REVISION 1
PREPARED BY: P. Rubin DATE: 9/27/90 REVIEWED BY: M. GIBSON DATE: 9/28/90
' APPROVED BY:
R.
Dorman SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE : linnual Reactor Trio '(07-01)
'i The Vogtle simulator is initialized to 100% power,BOL, Equilibrium Xe.
A manual reactor trip is performed one minute after the simulator is
.placed in run.
The simulator is ellowed-to run with no operator actions except modulating Auxiliary Feedwater flow.
The operator should control feedwater flow as necessary to stabilize SG levels above 5%.
The exercise
~is_ terminated 16 minutes after the simulator is place in run.
The simulator response is evaluated against best estimate judgement where Vogtle plant data is not available.
was satisfactorily completed.
Any discrepancies are (This. testing dentified on Form 12-01.
O
FORM: 07-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 2 OF 10 R
( )RM-TITLE: PERFORMANCE TEST ABSTRACT REVISION 1
PREPARED BY:- P. Rubin. DATE: 9/27/90 REVIEWED BY: M. GIBSON DATE: 9/28/90 APPROVED BY:
R.
Dorman SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90-SIMULATOR PERFORMANCE TEST ABSTRACT TITLE : Simultaneous Trio of All Feedwater Pumos (07-02)
The Vogtle simulator is initialized to 100% power,BOL, Equilibrium Xe.
A trip of both turbine driven Main Feedwater pumps (malfunctions 146A~ and 146B) is inserted one: minute after the simulator is placed in run.
The operator shall only perform the following actions:
o Reduce TDAFW flow to minimum after AFW punps start f~o Modulate the motor driven auxiliary feedwater pump throttle valves
(_)
to stabilize SG levels abova 5%
The exercise is terminated 11 minutes after the simulator is place in run.
The simulator response is evaluated against best estimate judgement where
~Vogtle plant data is not available.
This testing was satisfactorily completed.- Any discrepancies are identified on Form 12-01.
O l
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-FORM: 07-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 3 OF 10 RM TITLE: PERFORMANCE TEST ABSTRACT REVISION 1
PREPARED BY: P. Rubin DATE: 9/27/90 REVIEWED BY: M. GIBSON. DATE: 9/28/90 APPROVED BY:
R.
Dorman SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90
==:.
SIMULATOR PERFORMANCE TEST ABSTRACT TITLE-: Simultaneous Closure of All Main Stm Isol Valves (07-03)
The Vogtle simulator is initialized to 100% power,BOL, Equilibrium Xe.
A simultaneous ' closure of all main steam isolation valves malfunction
'(malfunctions ' 179A, B,
C, and D) is inserted one minute after the simulator -is placed in run.
The operator'shall perform only the following actions:
o Reduce TDAFW flow to minimum after AFW starts g.o Modulate the motor driven auxiliary feedwater pump throttle valves-d to stabilize SG levels above 5%
The exercise is-terminated 11 minutes after the' simulator is placed in run.
The simulator response is evaluatqd against best estimate judgement where
- Vogtle plant data is not available.
This testing was satisfactorily completed.
Any discrepancies are identified on Form 12-01.
O
l FORM: 07-02 VOGTLE SIMULATOR-CERTIFICATION PLAN PAGE 4 OF 10 RM TITLE: PERFORMANCE TEST ABSTRACT REVISION 1
PREPARED BY: P. Rubin DATE: 9/27/90 REVIEWED BY: M. GIBSON DATE: 9/28/90 f
APPROVED BY:
R.
Dorman SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE : Simultaneous Trio of All Reactor Coolant Pumos (07-04)
The Vogtle simulator is initialized to 100% power,EOL, Equilibrium Xe.
A simultaneous trip of all reactor coolant pumps malfunction (malfunctions 4 6A, B, C, and D) is inserted one minute after the simulator is placed in run.
The operator shall_ perform only the following actions:
o Reduce TDAFW flow to minimum after AFW starts o-Modulate the motor driven-auxiliary-feedwater pump throttle valves to stabilize SG levels above 5%
The exercise is terminated 16 minutes after-the simulator is placed in run.
The simulator response is evaluated aga' inst best estimate judgement where Vogtle plant data is not available.
This testing was satisfactorily completed.
Any discrepancies are identified on Form 12-01.
i --
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.=.
FORM: 07-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 5 OF 10 RM TITLE: PERFORMANCE TEST ABSTRACT REVISION 1
PREPARED BY: P. Rubin DATE: 9/27/90 REVIEWED BY: M. GIBSON DATE: 9/28/90 APPROVED BY:
R.
Dorman SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE : Sincle Reactor Coolant Pumu Trio (07-05)
The Vogtle simulator is initialized to 13% power,BOL, Equilibrium Xe.
Place the simulator in run and shift the rod control system to manual.
A trip of a single reactor coolant pump malfunction (malfunction 46A) is inserted one minute after the simulator is placed in run.
The simulator is allowed to run with NO OPERATOR ACTION for the remainder of the exercise.
The exercise is terminated 16 minutes after the simulator is placed in un.
The simulator response is evaluated against best estimate judgement where Vogtle= plant data is not available.
'This testing was satisfactorily completed.
Any discrepancies are identified on Form 12-01.
l O
I
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.-FORM: 07-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 6 OF 10 RM TITLE: PERFORMANCE TEST ABSTRACT REVISION 1
PREPARED BY: P. Rubin DATE: 9/27/90 REVIEWED BY: M. GIBSON DATE: 9/28/90 APPROVED BY: R.
Oorman SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE : Main Turbine Trio w/o a Reactor Trio (07-06)
The Vogtle-simulator is initialized to 30% power,MOL, Equilibrium Xe.
A main turbine. trip w/o a reactor trip malfunction (malfunction 98) is inserted one minute after the simulator is placed in run.
Once the simulator is placed in run, the rod control system is switched to manual.
The simulator is allowed to run with NO OPERATOR ACTION for the remainder of the exercise.
The exercise is terminated 11 minutes after the simulator is placed in run.
-- The simulator response is evaluated against best estimate judgement where
()gtleplantdataisnotavailable.
This testing was satisfactorily completed.
Any discrepancies are identifled on Form-12-01.
-.O I
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-1 i
RM: 07-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 7-OF 10
?
1 1RM' TITLE: PERFORMANCE TEST ABSTRACT REVISION' 1 m
PREPARED BY: P. Rubin _DATE: 9/27/90 REVIEWED BY: M. GIBSON DATE: 9/28/90 APPROVED BY:
R.
Dorman SUPERVISOR OPERATIONS TRAINING DATE: 11/15/9Q SIMULATOR PERFORMANCE TEST ABSTRACT o
TITLE : Maximu.5_ Rate Power Ramo (100% to 7S%.
Back to'i00%) (07-07)
- The Vogtle simulator-is initialized to 100% power, EOL', Equilibrium,Xe.
The rod-control'. system is placed(verified) in automatic operation after the simulator. is placed in run.-
After a one minute time delay, the-operator shall manually. reduce turbine load -to approxiraately 75% (860 MW)
'over a.5 minute period.
Eleven minutes after the load reduction., the operator shall raise. turbine load to - 100% (1150 MW) over a.5 ' minuto period.
l he exercise is terminated 5 minutes after reaching 100% power.
i he simulator response is evaluated against best estimate judgement where Vogtle plant data is'not available.
i This testing =.was satisfactorily complaced.
Any discrepancios are
. identified on-Form 12-01.
4 I
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iFORM: 07-02
.VOGTLE SIMULATOR CERTIFICATION-PLAN PAGE 8 07 10
'x 4RM TITLE! PERFORMANCE TEST ABSTRACT REVISION l,__
PREPARED BY: P. Rubin
'DATE: 2/2.7/90 REVIEWED BY: L_QIBSON. Dr.TE: 2/_2"i/_2p APPROVED BY:
R.
DorMA.D SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90
- q SIMULATOR. PERF00MANCE TEST ABSTRACT TITLE :~LOCA with Loss of Offsite_ Power (07-091 L
=__
l
=
~The Vogtle simulator is initialized to 100% power, EOL, Equilibrium Xe.
A LOCA with a loss of offsite power is initiated by insortion-of the following-malfunctions:-
~ o 35 (RCS Loop 3 Cold Leg Rupturce) o 126 and 127 (loss. of reeerve auxiliary transformers 1NXRA/B) o si'28 and 129 ' (loss of unit auxiliary transformers 1NXAA/B) ne simulator is placed in run and allowed to operate with NO QPERATOR-LQR for - ~20 minutes.
The operator then places - the ECCS in the recirculation mode.
The: exercise is tarminated 25 ninutes af ter the simulator is placed in run or 2 minutes after recirc f1cw is established.
(whichever is later).
- The simulator response is evaluated against best estiraate judgement where Vogtle plant data-is not available.
This
. testing was-satisfactorily completed.
Any discrepancies are-
' identified-on. Form 12-01.
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FORM: 07-02
- VOCTLE SIMULATOR CERTITTcKrTO IPl PAGE 9.OF 10
~
,TITIM' ?M,';QJ&lNCE TEST ' ABSTRACT REVISION 1
PREi%5tED M i F.,.31.h.irl DATE: 9/27/90 REVIEHED BY: M. GIBSON DATE: 9/28/90
.A%^4&YRO BY: R.
Doggn SUPERVISOR OPERATIONS TRAININC DATE: 11/15/90 SIMULNTOR PERFORMANCE TEST ABS'fMCT i
T1TLE : 'M.D.ipolaM e Main Steam Line Ruoture Inside Containment (07-09)
The Vogtle simulator is initialized to 0% power, EOL, Hot zero power.
n y
. steam line rupture -insido containment (malfunction 91) is insertad at 1004 severity one minute after the simulator ic placed in run.
Ttto ticulator c
is allowed to run with NO OPERATOR ACTION (nther tnan isol W.;a the faulted SG) for the reMrinder of the exercise. The e' erciB6 is torifial.'ted i
.10 minutes after the ui nulator is placed in run.
- Thc simulator response is evaluated againct best osilmste jydgemo}t where J
9tle plant data is not available.
1 is testing was satisfactorily completed.
Any discrepancies are ~
identified-on Form 12-01.
P f
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FORM 07-02 VOGTLL SIMULATOR CERTIFICATION PLAN PAGE 10 OF 10 O
'CRM TITLE: PERFORMANCE TEST ABSTRACT REVISION 1
PREPARED BY: P.RublD DATE: 9/27/90 REVIENED BY: 11. GIDSON DATE: 9/28/90
)
APPROVED BY: R.
Dorman SUPERVISOR OPERATIONS TRAINING DAl'Er 11/15/90 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE : ElpL Primary Svs Doorossurization to Sat Cond
'/_Etpck SV (07-10) d u
The Vogtle simulator is initialized to 100% power, EOL, Equilibrium Xo.
A Slow primary system depressurization malfunction (malfunction 58) is inserted at 20% one minuto after tne simulator is placed in run.
The operator will manually throttle APW flow and steam drains. The cimulation will run with no other operator actions.
The exerciso is terminated 40 minutos after the simulator is placed in run.
ino simulator responso is ovaluated against best estimato judgement where ogtlo plant data is not available.
ihis testing was satisfactorily comploted.
Any discrepancies are identified on Form 12-01.
O
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I PORMt 08-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 1 OF 3 TLEt PERFORMANCE TEST ABSTIBCT REVISION 1~
PERPARED BY: P. Rubin DATE: 9/20/90 REVIEWED BY: M. Gibson DATE: 9/23/90 APPROVED BYt R2 Dorman SUPERVISOR OPERATIONS TRAINING DATEt 11/15/90 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE 1 ConDuter Real Time Test (08-01)
The Computer Real Time Test consists of 3 tests.
In the first test the simulator lo initialized to any fuA. pawor initial condition (IC) and placed in run.
The simulator is allowed ':o ru.i for 30 minutes at steady state conditions.
During the 30 minutes, the minimum apare time of the CPU and the IPU are recorded.
If eithr.r of the spare times show less than adequate spare time a discrepancy report-is ganerated.
In the second test three malfunctions are selected which will exerciso the jor models of the simulator (i.e., LOCA, Reactor Trip and MSIV Closure).
r gash malfunction, the simulator is initialized to the IC used in the
(-
rat test and placed in run.
The simulator is allowed to run for 10 minutos with the malfun tion active.
During the 10 minutes, the minimum apare time of.the CPU and the IPU are recorded.
If either of the spare timos show less than adequate spare time, a discrepancy report is generated.
In the third test 5 valves are selected for valve stroking.
The valves selected are from different systems and have a minimum of 15 second stroke time.
The valves are stroked on the simulator and the times recorded.
If any actual valve stroke time exceeds its calculated value by more than 1 2%, a discrepancy report is generated.
This testing was satisfactorily completed.
Any discrepancies are identified on Form 12-01.
O 1
FORM: 08-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 2 OF 3 TLE: PERFORMANCE TEST ABSTRACT REVISION 1 PERPARED BY: P. Rubin DATE: 9/20/90 REVIEWED BY: M. Gibsan_ DATE: 9/23/90 APPROVED BY:
R.
Dorman SUPERVISOR OPERATIONS TRAINING DATE: 11/15/90 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE : Simulator L}mits Exceeded (08-02)
Tho " Simulator Limits Exceeded" light in the Instructor's Booth will be illuminated when certain model limits are exceeded. These limits were chosen to cover instances in which either:
1)
The simulated conditions are outside the bounds imposed by modeling cocumptions. (for example, gross voiding of the RCS) 2)
The simulated conditions are outside the design limits of plant equipment (for example, the containment pressure exceeds the design
$imit).
Jimulator instructors monitor the " Simulator Limits Exceeded" light to see if their scenario has exceeded these limits. If the light is illuminated, tho instructor addresses whether the training is being impacted by the cimulation and, if so, steps are taken to correct any negative training that might occur.
The parameters which are monitored for the " Simulator Limits Exceeded" light are:
Parameter Setpoint Containment Pressure
> 66.7 psia 1
l BCa Pressure
> 2700 psia l
Core Voiding
> 100%
Fuel Temperature
> 4000 Degf l
To simulation can not normally achieve.
n
FORM: 08-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 3 OF 3 TLE: PERFORMANCE TEST ABSTRACT REVISION 1 PERPARED BY: P. Rubin DATE: 9/20/90 REVIEWED BY: M. Gibson DATE: 9/23/90 APPROVED BY:
R.
Dorman GUPERVISOR OPERATIONS TRAINING DATE: 11/15/90 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE : Simulator L(mits Exceeded (09-02) m To test the operation of the light, all models are frozen except the operating limits program. Each of the inputs to the program are set to croato an out of limits input and then set to clear the alarm.
Tho " Simulator Limits Exceeded" light performed as required.
(
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l FORM: 12-01 VOGTLE SIKULATOR CERTIFICATION PLAN PAGE 1 OF 34 kRMTITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION 1 PERFORMED BY: P. Rubin DATE: 12/10/90 REVIEWED BY: M.
Gibson DATE: 12/10/90 APPROVED BY:
R.
Dorman SUPERVISOR OPERATIONS TRAINING DATE: 12/10/90 Porformance Test Procedures:05-01; 05-04; 05-05;05-06A; 05-06B Interval: Malfunction to Rx Trin DR Number:1 (9008032)
Comparison Comparison Parameter Measure Value FI 112 Charging Flow NA TABLE TOP roblem
Description:
Cause:
4hargingflowinitiallydecreases Model is not correctly calculating to zero on SI actuation, but then delta P's throughout the CVCS.
returns on scale.
A negative delta P is generated immediately following the SI causing the flow to go to zero.
Corrective Action:
Impact if not Corrected:
Correct delta P calculations.
Mirior impact, flow is zero for a very short period of time.
Flow magnitude when returned en scale appears to be correct.
Resolution:
Results:
DR 9008032 was written.
DR is open.
O
___.___________._____.._._____._m.
i
- l FORM: 12-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 2 OF 37 RM TITLE DISCREPANCY RESOLUTION WORKSHEET REVISION.1,,,
4 PERFORMED BY: P. Rubin DATE: 12/10/90 REVIEWED BY: M. Gibson DATE: 12/10/90 a
APPROVED BY:
R.
Dorman SUPERVISOR OPERATIONS TRAINING DATE: 12/10/90 Performance Test Procedures:05-01; 05-02; 05-05;05-06A; 05-06B; 05-23At 05-24Af 05-25Br 05-26: 05-30Ar 05-30C-Interval:Rx Trio to Termination DR Number:2 (9008033)
Comparison Comparison Paramet'r Measure-Value p
.FI 917~ BIT Flow NA TABLE TOP Iroblem
Description:
Causes v
TIT flow -initially overshoots Method of flow calculation by model
-before tracking RCS pressure, results in overshoot.
l Corrective Action:
Impact if not Corrected:
None No impact. The overshoot is small and could be explained away as meter inertia if it was noticed by the operator. It would not likely be noticed by the operator.
4.
Resolution:
Results:
1 DR 9008033-was written.
DR was closed with no action taken due to no impact on training.
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FORM: 12-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 3 OF 34
(
RM TITLE:
DISCREPANCY RESOLUTION WORKSHEET REVISION 1_
PERFORMED BY: P. Rubin DATE: 12/10/90 REVIEWED BY: M. Gibson DATE: 12/10/90 l
APPROVED BY: B. Dorman SUPERVISOR OPERATIONS TRAINING DATE: 12/10/90 Performance Test Procedures:05-02; 05-04; 05-05;05-06A; 05-06B; 05-20; 05-24Af 05-27; 05-29Ff 07-01r 07-02; 07-08 Interval:Rx Trio to SI Actuation DR Number:3 (9008010)
Comparison Comparison
' Parameter Measure Value FI 522 Loop 2 Stm Flow NA TABLE TOP FI 532 Loop 3 Stm Flow NA TABLE TOP l-
.M'
()oblemDescription:
Cause:
Steam flow spikes high at time of Time. delay on turbine trip is Rx trip.
causing the steam dumps to open on the reactor trip controller before the steam flow to the turbine is-isolated.
Corrective Action:
Impact if not Corrected:
Reduce turbine trip time delay.
Minor impact, it is unlikely that this momentary spike would be noticed on the MCB indicators.
(-
' Resolution:
Results:
DR 9008010 was written..
The time delay was removed from the coding. The DR was satisfactorily tested and closed.
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I i
FORM: 12-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 4 OF 34 (h
(_ 'IU4 TITLE : DISCREPANCY RESOLUTION WORKSHEET REVISION 1 PERFORMED BY:
P. Rubin DATE: 12/10/90 REVIEWED BY: M. GibEqn_ DATE: 12/10/90 APPROVED BY:
R.
Dorman SUPERVISOR OPERATIONS TRAINING DATE: 12/10/90 Performance Test Procedures:05-02; 05-04; 05-05; 05-26;05-06A; 05-06B i
Interval:SI Actuation to _ Termination DR Number:4 (9008034) i l
Comparison Comparison Parameter Measure Value UT 7501 Containment Temp NA TABLE TOP
,Eroblem
Description:
Cause:
I'tep change increase in containment Model problem.
at time malfunction initiation.
Corrective Action:
Impact if not Corrected:
Correct model to reflect a gradual Minor impact, temperature does increase in temperature rather than increase and it is unlikely that a step change.
the step change would be noticed on the MCB indications.
Resolution:
Results:
DR 9008034 was written.
The coding was corrected. The DR was satisfactorily tested and closed.
(9 v
FORM: 12-01 VOGTLE SIKULATOR CERTIFICATION PLAN PAGE 5 OF 34
(~%
( !RM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION 1 PERFORMED BY:
P. Rubin DATE: 12/10/90 REVIEWED BY: M. Gibson DATE: 12/10/.22 APPROVED BY:
R.
Dorman SUPERVISOR OPERATIONS TRAINING DATE: 12/10/90 Performance Test Procedures:05-03; 05-05; C5-06A;05-06B Interval: Letdown Isolation to Termination DR Number:5 (9008009)
Comparison Comparison Porameter Measure Value FI 132 Letdown Flow NA TABLE TOP roblem
Description:
Cause:
followingletdownisolation, Flow calculation problem in model.
letdown flow initially increases, and then takes over a minute to reach zero.
Corrective Action:
Impact if not Corrected:
Correct model such that letdown Minor impact, initial increase and flow begins to decrease at time of length of time to reach zero are letdown isolation and reaches zero not extremely noticeable on MCB quickly.
indications.
If detected, monitoring of the parameter will show it changing in the correct direction and eventually reaching zero.
Resolution:
Results:
DR 9008009 was written.
The coding was corrected. The DR was satisfactorily tested and closed.
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l
i FORM: 12-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 6 OF 34 RM TITLEt DISCREPANCY RESOLUTION WORKSHEET REVISION 1 1
PERFORMED BY: P. Rubin DATE: 12/10/90 REVIEWED BY:.M. Gibson DATE: 12/10/90 J
APPROVED BY:
R.
Dorman SUPERVISOR OPERATIONS TRAINING DATE: 12/10/90 t
Performance Test Procedures 05-04; 07-08 l
Interval: Malfunction to Termination DR Number:6 (9008035)
)
i comparison comparison Parameter Measure Value TI 422 Loop 2 Tave NA TABLE TOP TI 432 Loop 3 Tave NA TABLE TOP
-,2roblem
Description:
Cause:
'Tave initially increases at
.Model problem.
malfunction insertion (Large Break Loca), then decreasaw offscale low
'(<540 degf).
Unaffected loop Tave comes back onscale for a short pariod of time.
Corrective Action:
Impact if not corrected:
Correct Tave calculation such that Minor impact, the initial increase all' loops decrease from malfunction and the return onscale are small in to offscale low with no return-uagnitude. They would not cause the onscale.
operator to misdiagnose an-event or cause any training impact. It~would be difficult to see on the MCB indications.
Resolution:
Recults:
DR 9008035 was written.
DR is still an open item with Westinghouse for warranty repair O
They have made some improvement in the response.
FORM: 12-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 7 OF 34
("(T11Mi_ TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION 1 PERFORMED BY:
P. Rubin DATE: 12/10/90 REVIEWED BY: M. Gibson DATE: 12/10/90 APPROVED BY:
R.
Dorman SUPERVISOR OPERATIONS TRAINING DATE: 12/10/90 Performance Test Procedures:05-04 Interval:SI Actuation to Termination DR Number:7 (9009036)
Comparison Comparison P0rameter Measure Value FI 610 RHR Pp Flow NA TABLE TOP PI 614 RHR Pp Disch Press NA TABLE TOP
,Eroblem
Description:
Cause:
1BIR pressure and flow spike at time Model problem.
of SI accumulator discharge.
Corrective Action:
Impact if not Corrected:
Correct model to reflect that Minor impact, the spike is small accumulator discharge should be and it is unlikely that the spike complete prior to RHR injection, in RHR pressure and flow would be (200 psig), such that no effect noticed on MCB indications.
should be seen on the RHR sistem.
i Resolution:
Results:
DR 9008036 was written.
Several RHR model repairs were made betwoon the time of the testing and the analysis of the data. This DR l
/'N was corrected as a part of these
(~)
repairs and could not be reproduced. The DR was closed.
1 l
FORM: 12-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 8 OF 34 Im4 TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION 1 PERFORMED BY:
P. Rubin DATE: 12/10/90 REVIEWED BY: M. Gibson DATE: 12/10/90 APPROVED BY:
R.
Dorman SUPERVISOR OPERATIONS TRAINING DATE: 12/10/90 Performance Test Procedures:05-06A, 05-6B Interval: Malfunction to Rx Trio DR Number:8 (9008037)
Comparison Comparison Parameter Measure Value UT 7501 Containment Temp NA TABLE TOP roblem
Description:
Cause:
fontainmenttemperatureincrease Containment temperature does not dons not_ correspond with time of begin to increase until water PRT rupture.
starts flowing out of the PRT rupture disk.
The model does not see the hot steam / gas that is escaping prior to the water.
Corrective Action:
Impact.if not Corrected:
Correct modeL to reflect increase Minor impact, it is unlikely that in Containme nt temperature prior to the delay in containment water escaping from rupture disk.
temperature increase will be noticed on MCB indications.
1 L
Resolution:
Results:
DR 9008037 was written.
DR is still an open item with Westinghouse for warranty repair.
They have attempted to repair it but the repair was not totally successful.
[)
FORM: 12-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 9 OF 34 bRM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION 1 PERFORMED BY:
P. Rubin DATE: 12/10/90 REVIEWED BY: M. Gibson DATE: 12/10/90 APPROVED BY: R._Dorman SUPERVISOR OPERATIONS TRAINING DATE: 12/10/90 Parformance Test Procedures 205-16 i
Interval: Malfunction to Pumo Restart _
DR Number:9 (9008038)
Comparison Comparison Parameter Measure value PI 614 RHR Pp Disch Press NA TABLE TOP e
,Eroblem
Description:
Cause:
l
' Pressure spikes following stop of Model problem.
RHR pump.
1 i
.Cor ective Action:
Impact if not Corrected:
None.
No impact, spike is very small and it is unlikely that it would be seen on MCB indications.
Resolution:
Results:
DR 9008038 was written and closed Several RHR model repairs were'made with no action taken.
between the time of the. testing and the analysis of the-data. This DR was corrected as a part of these repairs and could not be reproduced. The DR was closed.
O l
FORMS 12-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 10 OF 34 m
_ RM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION 1 PERFORMED BY:
P. Rubin DATE: 12/10/90 REVIEWED BY: M.
Gibson DATE: 12/10/90 APPROVED BY: R.
Dorman SUPERVISOR OPERATIONS TRAINING DATE: 12/10/90 i
Performance Test Procedures:05-16 Interval:Pumn Start to Flow Stabilize DR Number:10 (9008039)
Comparison Comparison Parameter Measure Value FI 618 RHR Pp Flow NA TABLE TOP
, Problem
Description:
Cause:
' Flow does not overshoot due to FV Model problem.
618 being full open, and then dscrease to 3000 gpm as the valve throttles.. Instead flow comes up below 3000 gpm and then gradually increases.
i corrective Action:
Impact if not Corrected:-
Correct model to show proper flow Minor impact, operators would response with-FV 618 in automatic.
generally * + controlling flow it is not likely that
- manually, this wouls.- noticed on MCB indications l Resolution:
Results:
DR 9008039 was written.
Several RHR model repairs were made-between the time of the testing and the analysis of the data. This DR was corrected as a part of these repairs and could not be reproduced. The DR was closed.
s FORMS 12-01 VOGTLE SIMULATOR CERTIFI5ATION PLAN PAGE 11 OF 34 i
RM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION 1 PERFORMED BY:
P. Rubin DATE: 12/10/90 REVIEWED BY: M. Gibson DATE: 12/10/90 s
A APPROVED BY: R. Dorman SUPERVISOR OPERATIONS TRAINING DATE: 12/10/90 Performance Test Procedure:05-18 Interval: Malfunction to Rx Trio DR Number: 11 (9008040)
Comparison-
-Comparison Parameter Measure Value TI 412 Loop 1 Tave NA TABLE TOP LI 459 PZR Level NA TABLE TOP
NA TABLE TOP
.FI 512A Loop 1 Stm Flow NA TABLE TOP FI 542A Loop 4 Stm' Flow NA TABLE TOP l
fjoblemDescription:
Cause At point of SG dryout, a spike Model problem at SG dryout.
occurs in all of the above listed parameters.
Corrective Action:
Impact if not Corrected:
Correct model such that the Minor impact, it_is unlikely that unexplained spike does not occur.
the spike woula he noticed on MCB-indications.
4 i
Resolution:
Results:
DR 9008040 was written.
Modified coding for SG dryout situation. Satisfactorily tested the changes and closed the DR.
O i
l.
~ - -
j FORM: 12-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 12 OF 34 hAMTITLE:
DISCREPANCY RESOLUTION WORKSHEET REVISION 1 i
PERFORMED BY: P. Rubin _ DATE: 12/10/90 REVIEWED BY: L_11bson DATE: 12/10/90 I
APPROVED BY:
R.
Dorman SUPERVISOR OPERATIONS TRAINING DATE: 12/10/90
)
t Parformance Test Procedure:05-20 Interval: Malfunction to Verification DR Number:12 (9001001)
Comparison Comparison Parameter Measure Value ROD-CONTROL URGENT FAILURE ON ON Alarm 1
froblem
Description:
Cause:
Tlarm comes in immediately upon Logic problem in model.
malfunction insertion.- Should not come in.until rod movement is demanded.
s Corrective Action:
Impact if not Corrected:
Correct model logic.
Moderate impact, training value of malfunction is lost if alarm comes in at malfunction insertion.
Resolution:
Results:
Dh 9001001 was written.
The coding was changed. The DR was satisfactorily tested and closed.
O
i FORM: 12-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 13 OF 34
(\\RM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION 1 PERFORMED BY:
P. Rubin DATE: 12/10/90 REVIEWED BY: M. Gibson DATE: 12/10/90 APPROVED BY:
R.
Dorman SUPERVISOR OPERATIONS TRAINING DATE: 12/10/90 Performance Test Procedures:05-25B Interval: Malfunction to Termination DR Number:13 (9008041)
Comparison Comparison Parameter Measure Value LI 517 SG 1 NR Level NA TABLE TOP LI 547 SG 4 NR I4 vel NA TABLE TOP Problem
Description:
Cause:
(x devel spikes back on scale post Swell transient.
trip.
Corrective Action:
Impact if not Corrected:
None.
No impact.
Resolution:
Results:
DR 9008041 was written and closed No action necessary, level I
with no action taken.
After response satisfactory.
further review it was determined that the level spike was due to a rmhrink and swell transient post
]
(_) rip.
l i
1 i
1
-PORM: 12-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 14 OF 34
' 'N -
i
/
i
( 1RM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION 1 PERFORMED BY P. Rubin DATE: 12/10/90 REVIEWED BY: M. GihEOD_ DATE: 12/10/90 APPROVED BY: R.
Dorman SUPERVISOR OPERATIONS TRAINING DATE: 12/10/90 3
I Performance Test Procedures:05-26
-Interval:SI to Termination DR Number:14 (9000042) t i
Comparison Comparison Parameter Measure Value LI 537 SG=3 NR Level NA TABLE TOP LI 502 SG 2 WR Level NA TABLE TOP LI 503 SG ll WR Level NA TABLE TOP Problem Description Causes st trip level response exhibits Model problem.
nexplained recovery and then decrease.
Corrective Action:
Impact if not Corrected:
Correct model such that level Minor impact, the magnitude of the spikes do not occur.
swings are not large. The overall trend is in the correct direction.
i The MCB instrumentation Will dampen the swings. Training of the operator will not be impacted by these small swingc. Le probable-won't notice them.
Resolution:
Results
'DR 9008042 was written.
DR is an open item with Westinghouse for warranty O.
repair.
~
FORM: 12-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 15 OF 34
()RMTITLE:
DISCREPANCY RESOLUTION WORKSHEET REVISION 1_
PERFORMED BY:
P. Rubin DATE: 12/10/9_2 REVIEWED BY: M.
Gibson. DATE: 12/10/90 APPROVED BY: R....Dpraan SUPERVISOR OPERATIONS TRAINING DATE: 12/10/2p Performance Test Procedures:05-27 Interval: Malfunction to Rx Trio DR Number:15 (9009011)
Comparison Comparison Parameter Measure Value TI 413B Loop 1 Tcold NA TABLE TOP Problem
Description:
Cause:
(r
\\'tcold decreases at time of Misinterpretation of data.
foodwater line break outside containment.
Corrective Action:
Impact if not Corrected:
None.
The change in Tcold noted No impact, response is correct.
actually occurs at time of Rx trip and is normal post trip response.
Tcold remains relatively constant at time of foodwater line break.
Resolution:
Results:
DR 9009011 was written and closed Tcold response is satisfactory, with no action taken.
no action required.
O
FORM: 12-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 16 OF 34 RM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION 1 3
PERFORMED BY:
P. Rubin DATE:-12/10/92 REVIEWED BY: d6 Gibson DATE: 12/10/90 APPROVED BY: R.
Dorman SUPERVISOR OPERATIONS, TRAINING DATE: 12/10/90 Performance Test Procedures:05-30A Interval:Rx Trio to SI DR Nutr.b er Q0,,,_(1008 04 3 )
Comparison Comparison Parameter Measure Value FI S22A SG 2 Stm Flow NA TABLE TOP FI S32A SG 3 Stm Flow NA TABLE TOP
,Eroblem
Description:
Cause:
'Ftoam ' flow on unaffected SG spikes Model problem.
twice following isolation.
Corrective Action:
Impact if not Corrected:
-Correct model'such that steam Minor impact, it is unlikely that.
pressure does not increase to the the steam flow spikes would be point of-causing the SG safeties noticed on MCB indications, and l
and ARVs to open.
steam flow and pressure respond properly for the remainder of the transient.
-Resolution:
Results:
l l
DR 9008043 was written.
The'first spike is when the dumps.
open before the MSIV's are closed.
The second occurs when the ARV's open after the MSIV's are closed.
This is expected. The DR was closed.
O
FORM: 12-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 17 OF 34
()RMTITLE:
DISCREPANCY RESOLUTION WORKSHEET REVISION 1 PERFORMED BY:
P. Rubin DATE: _12/10/90 REVIEWED BY: M. Gibson DATE: 12/10/90 APPROVED BY: R.
Dorman SUPERVISOR OPERATIONS TRAINING DATE: 12/10/90 Performance Test Procedures:05-30C Interval: Malfunction to Termination DR Number:17 (9008044)
Ecomparison comparison Parameter Measure Value FI 5150 SG 1 AFW Flow NA TABLE TOP FI.5153 SG 3 AFW Flow NA TABLE TOP PI 5107-TDAFW Pump Disch NA TABLE TOP Press roblem
Description:
Cause:
/lowisbeingdeliveredtotheSGs Model. problem.
from-the TDAFW pump before its discharge pressure is greater than SG pressure.
Corrective Action:
Impact if not Corrected:
Correct model such-that there will Minor impact, it is unlikely that-be no flow from the TDAFW pump the flow being delivered prior to unti1 Lits' discharge pressure is adequate discharge would be noticed
. greater than its discharge source.
on the MCB indications.
4 Resolution:
Results:
DR 9008044 was written.
The feedwater model was repaired and satisfactorily tested. The DR was closed.
O I
1
FORM 12-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 18 OF 34 l
(
BM TITLE:
DISCREPANCY RESOLUTION WORKSHEET REVISION 1.
PERFORMED BY:
P. Rubin DATE: 12/10/90 REVIEWED BY: M. Gibson DATE: 12/1022p APPROVED BY:
R.
Dorman SUPERVISOR OPERATIONS TRAINING DATE: 12/10/90 Parformance Test Procedures:05-31 1
Interval: Malfunction to SI DR Number:18 (9008045)
Comparison.
Comparison Parameter Measure Value NI 41-PR Flux NA TABLE TOP NI 35B IR Flux NA TABLE TOP NI 35D IR SUR NA TABLE TOP
,Eroblem
Description:
Cause:
' Nuclear instrumentation oscillates Model problem.
with RCS pressure.
Corrective Action:
Impact if not Corrected:
Correct model such that nuclear Minor. impact, the oscillations instrumentation. indications are not-would not detract from training affected by RCS pressure spikes.
significantly, and the overall trend of-the indications is in the correct direction.
i l
' Resolution:
Results:
- DR 9008045 was written.
Westinghouse did further tuning of l-the models after the certification testing was completed._Some of this tuning has repaired the problem. We O
could not reproduce the problem.
The DR was closed.
- - - - - ~
FORM: 12-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 19 OF 34 hhRMTITLE:
DISCREPANCY RESOLUTION WORKSHEET REVISION 1 PERFORMED BY:
P. Rubin DATE: 12/10/90 REVIEWED BY: M. Gibson DATE: 12/10/90 APPROVED BY: R. Dorman SUPERVISOR OPERATIONS TRAINING DATE: 12/10/90 Performance Test Procedure:05-18 06-06 07-09: 07-10 Interval:MalfuDetion to Rx Trio DR Number:19 (900804_6)
Comparison Comparison Parameter Measure Value NI 35D IR SUR NA TABLE TOP Problem
Description:
Cause:
R SUR goes offscale low after Record program problem.
stabilizing at 0 dpm post-trip.
Corrective Action:
Impact if not Corrected:
Will attempt to plot different No impact.
point in the future that is scaled for more definition.
Resolution:
Results:
DR 9008046 was written.
IR SUR responds properly. The plotting program was changed to look at a linear variable in the i
l future. The DR was satisfactorily l
tested and closed. Future plotting will utilize the new point.
i l
_ ~ _. _ - - -.. _ _..
FORM: 12-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 20 OF 34
()RMTITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION 1 PERFORMED BY:
P. Rubin DATE: 12/10/90 REVIEWED BY:
M. Gibson DATE: 12/10/90 APPROVED BY: R.
Dorman SUPERVISOR OPERATIONS TRAININC DATE: 12/10/90 Performance Test Procedures:05-08 Interval: Malfunction to Termination DR Number:20 (9009012)
Comparison Comparison Parameter Measure Value TI 412 Loop 1 Tave NA TABLE TOP roblem
Description:
Cause:
Tave stabilizes post trip rather Tave appears to-be following wide than cooling off to ambient due to range Th and Tc rather than narrow loss of forced circulation.
range RTD's.
Corrective Action:
Impact if not Corrected:
Correct Tave indication to be based Minor impact, operators are trained on narrow range RTD's, which would not to rely on narrow range gradually cool to ambient temperatures in loops with no RCP's conditions with no forced running.
circulation.
i Resolution:
Results:
DR 9009012-was written.
Westinghouse did further tuning of the models after the certification i
testing was completed. Some of this tuning has repaired the problem. We could not reproduce the problem.
The DR was closed.
O
\\_/ -
l l
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FORM: 12-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 21 OF 34
('7RM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION 1 V
PERFORMED BY:
P. Rubin DATE: 12/10/90 REVIEWED BY: M. Gibson. DATE: 12/10/90 APPROVED BY:
R.
Dorman.
SUPERVISOR OPERA'tIONS TRAINING DATE: 12/10/9Q Performance Test Procedures:05-08 Interval: Malfunction to Termination DR Number:21 (9009013) comparison comparison Parameter Measure Value I
TR 413A Loop 1 WR Thot NA TABLE TOP TR 443A Loop 4 WR Thot NA TABLE TOP
-3roblem
Description:
Cause:
v Thot decreases and then remains Model problem.
stable following malfunction insertion.
Corrective Action:
Impact if not Corrected:
Correct model to show an increase Moderate impact, model should show in Thot until natura) circulation expected dynamic RCS response as is established.
natural circulation is established for training effectiveness.
Resolution:
Results:
DR 9009013 was written.
Westinghouse did further tuning of the models after the certification testing was completed. Some of this tuning has repaired the problem. We could not reproduce the problem.
The DR was closed.
O
~
FORM: 12-01 VOGTLE SIMULATOR CERTIFICATION PLhN PAGE 22 OF 34 RM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION 1 PERFORMED BY:
P. Rubin DATE: 12/10/90 REVIEWED BY: L_ qibson. DATE: 12/10/90
~ APPROVED BY:
R.
Dorman SUPERVISOR OPERhTIONS TRAINING DATE: 12/10/90 Performance Test Procedures:05-14B Znterval: Malfunction to Termination DR Number:22 (9009025)
Comparison Comparison Parameter Measure Value LZ-5111A CST Level NA TABLE TOP
.LR 5101 C5T Level Recorder
.NA TABLE TOP LI 4415 Hotwell' Level NA TABLE TOP troblem'
Description:
Cause:
l
?
Hotwell level and CST. level show Model problem, partially due to very little if any response to the improper sizing of hotwell.
level' controller malfunction.
Corrective Action:
Impact if not Corrected:
-Correct model to show proper Minor impact, non-safety related response.
system malfenction.
-Resolution:
Results:
l' DR 9009025 was written.
Corrections to coding were made and natisfactorily tested. The DR was closed.
i
-9
.. ~. _...
~
FORMS 12-01 YOGTLE SIMULATOR CERTIFICATION PIAN PAGE 33 OF 34 C ORM TITL(t DISCREPANCY REEQLUTION WORKSHEET FJYlHLQJJ{_L U
PERFORMED BY Ex_ Rubin DATE: 12/10/90 REVIFhT9 BY: M.
Gibson DATE: 12/10/90 APPROVED BY:
R.
Do rman SUPERVISOR OPERAT9ONS TRAINING DATE: 12/10/90 Performance Test Procedure:05-18 Interval:Rx Trio to Termination DR Number:23 (09008042)__
Comparison Comparison Parameter Measure Value FI 3151 AFW Flow to SG 1 NA TABLE TOP FI 5154 AFW Flow to SG 4 NA TABLE TOP Problem
Description:
Cause:
rs
(,JW flow overshoots and then Model AFW flow calculation problem.
returns to stable value.
Corrective Action:
Impact if not Corrected:
Correct overshoot.
No impact, unlikely that overshoot would be seen on MCB indications, flow stabilizes at appropriate value and responds as expected.
l Resolution:
Results:
t DR 9008047 was written and closed.
The coding for the pumps was changed to correct the problem and satisfactorily tested.
- ()
1 i
M d
" FORM: 12-01 VOGTLE SIMULATOR CERPIFlCATEGI PLAH PAGE 24 OF 34 2M TITLE: DIECREPANCY RESOLUTION WORKSHEET REVISION'1 PERFORMED BY:
P. Rubin DATE: 12/10/90 REVIEWED BY: f. Gibson. DATE: J2/10/90
-APPROVED BY: }3. Dorman SUPERVISOR OPERATIti!!S '1RAINIllG DATE: 12/10/90
- ~
Performance Test Procedures:05-21 1
Istterval: Malfunction to Verification DR Number:24 (9009014)
)
Comparison Comparison Parameter Measure Value GROSS FAILED FUEL DETECTOR ON ON Alarm l
Problem Desdription:
Cause:
Odd not receive alarm with failed Model problem.
.N uel malfunction inserted.
t i
corrective ;,ction:
Impact if not corrected:
Correct model such that' alarm is Minor impact, the alarm can be received with failed fuel present.
overridden on by the instructor if needed for training' purposes.
Resolution:
Results:
DR'9009014 was written.
The coding was modified and satisfactorily tested. The
~
DR was closed.
O.
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FORM: 12-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 25 OF 35
( ORM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISIO11_L V
PERFORMED BY:
P. Pubin DATE: 12/10/90 REVIEWED Bf: M. Gibson DATE: 12/10/90 APPROVED BY: R. Dorman SUPERVISOR OPERATIONS TRAININC DATE: 12210/90 Performance Test Procedures:05-29A Interval: Malfunction to Termination __
DR Number:25 (9009016)
Cvmparison Comparison Parametcr Measure Value PI 614 RHR Pp Disch Press NA TABLE TOP e
Problem Doscription:
Cause:
(pikpumpcavitateswhensuction Model problem.
valve fails closed, but mini-flow valve is open.
Correctiva A tion:
Impact if not Corrected:
Correct model to reflect a dr.rease Mir, r impact, operators would in discharge pressure, but no-nortually take action to trip the cavitation as long as the mini-flow RHR pump if the suction valve went is open.
closed, and thus would not see the indications of cavitation and automatic pump trip.
], solution:
Results:
DR 9009016 was written.
Further review by the committee determined that while cailtation would not necessarily occur in this condition, it is feasible due to system leakages. The DR was closed.
O i
t I
m FORM: 12-01 VOGTLE SIMULATOR CERTIFICATIOri PLAN PAGE 26 OF 34
+-
RM TITLE: DISCREPANCLREFDLUTION WORKSHEET REVISIOR_1._
' PERFORMED BY:
P. Rubin. DATE: 12/10/90 REVIEWED BY:
M.
Gibson DATE: 12/10/90 APPROVED BY:
R.
Dorman SUPERVISOR OPERATIONS TRAINING DATE: 12/10/90 Performance Test Procedures:06-01 Interval: Plant Heatuo to Hot Shutdown DR Number:26 (9009017)
Comparison Comparison Parameter Measure Value PI 403 RCS WR Press NA TABLE TOP 4
Problem
Description:
Cause:
CbSpreeeuretaxes1aree/ rapid Mode 1 prod 1em.
decrease when RHR pump stopped.
Corrective Action:
Impact if not Corrected:
LCorrect model such that RHR Moderate-impact, makes training configuration changes have only evolutions difficult while small etfects on RCS pressure.
performing RHR operations.
-Resolution:
Results:
DR 9009017 was written.
Several RHR model repairs were made between the time of the testing and the' analysis of the data. This DR was corrected as a part of these repairs and could not be reproduced. The DR was closed.
0 l
l l
1 FORM 12-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 27 OF 34
{}RMTITLE:
DISCREPANCY RESOLUTION WORKSHEET REVISION 1 PERFORMED-BY:
P. Rubin DATE: 12/10/90 REVIEWED BY: M. Gibson DATE: 12/10/90 APPROVED BY: R. Dorman SUPERVISOR OPERATIONS TR*.INING DATE: 12/10/90 Performance Test Procedures:06-01 Interval:Elant Heatuo to NOP/NOT DR Number:27 (9009018)
Comparison Parameter Comparison Value Measure FI 416 Loop 1 RCS Flow NA TABLE TOP FI 426 Loop 2 RCS Flow NA TABLE TOP FI' 435 Loop 3 RCS Flow NA TABLE TOP
'FI 445 Loop 4 RCS Flow NA TABLE TOP l
r"yoblem.
Description:
Cause:
V Loop flows indicate a small amount Model problem.
of flow with no RCP's running.
Corrective Action:
Impact if not Corrected:
Correct-model such that.RCS flow No impact, this.small amount of indicates zero with no RCP's flow is not discernable on the MC8 running.
indications.
Resolution:
Results:
DR 9009018 was written and closed-No action taken, no impact on with nolaction taken since there training.
would be: no adverse effects on training.
.O 1y**-/M t-t(-t Nt w
e 9
qr-n
,,,3 g
f
' FORM: 12-01
- VOGTLE SIMULATO'd CERTIFICATION PLAN PAGE 28 OF 34
![1RMTITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION 1 u.r
+
PERFORMED B,Y:
P. Rubin DATE: 12/10/90 REVIEWED BY: M. Gibson DATE: 12/10/90
' APPROVED BY: R.
Dorman 1 SUPERVISOR OPERATIONS TRAINING.
DATE: 12/10/90 Parformance Test Procedures:06-01 Interval: Plant Heatuo to Hot Shutdown __
'DR Number:28 (9009019)
Comparison Comparison l Parameter Measure Value
! Problem-Description:
Cause:
k(cold. swings.
Model problem..
Corrective Action:
Impact =if not Corrected:
- Correct model-such that temperature Minor impact, temperature. returns.
swings do not occur.
to: correct _value after swing,.and overall trend is in the-correct-
' direction.
L Resolution:
Results:
l:
IHL9009019 was written.
Westinghouse did further tuning of:
-t the models after the certification-l=
testing was completed. Some of.this-tuning has repaired the problem.-We-could not reproduce the problem.
The DR was closed.
O
FORM: 12-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 29 OF 34 M4 TITLE: DISCREPANCY RESOLUTION WORKSHERT REVISION 1
-PERFORMED BY:
P.-- Rubin.DATE: 12/10/90 REVIEWED BY: M. Gibson DATE: 12/10/90 APPROVED BY: R.
Dorman SUPERVISOR OPERATIONS TRAINING DATE: 12/10/90 Performance Test Procedures:07-08; 07-09 Interval: Malfunction to Termination DR Number:29 (9008048)
Comparison Comparison Parameter Measure Value TR 413B Loop 1 WR Tcold NA TABLE TOP Problem
Description:
Cause:
'old spikes low before stabilizing Model problem.
saturation following malfunction insertion.
-Corrective Action:
ImpactLif not Corrected:
Correct model.such that Tcold Minor impact, overall trend is decreases to saturation without proper and it is not very likely
- spiking, that-the spikes would be noticed on MCB indications.
Resolution:
Results:
1DR-9008048 was written.
Westinghouse did further tuning of the models after the certification testing was completed. Some of this tuning has repaired the problem. We could not reproduce the problem.
The DR was closed.
O 1
.- ~
FORM: 12-01 VOGTLE SIMULATOR CERTIFICATION PLAN
.PAGE 30 OF 34
(]RMTITLE:
DISCREPANCY RESOLUTION WORKSHEET REVISION-1 PERFORMED BY:
P. Rubin DATE: 12/10/90 REVIEWED BY: M. Gibson DATE: 12/10/90 APPROVED BY: R.
Dorman SUPERVISOR OPERATIONS TRAINING DATE: 12/10/90 Performance Test Procedures:07-09 Interval: Malfunction to Termination DR Number:30 (9008049)
Comparison Comparison Parameter Measure Value TI 2563 Containment Temp NA TABLE TOP Problem
Description:
Cause:
-(smperaturedecreasedatsteamline Model' problem.
break initiation.
Corrective Action:
Impact if not corrected:
(Correct model such that temperature Moderate impact, temperature does increases on a high energy line trend in the proper-direction after
. secondary system break, initial decrease, however the magnitude of this increase should be larger.
i Resolution:
Results:
DRl9008049 was written.
The temperature calculation was corrected and satisfactorily tested. The DR was closed.
.O
I FORM: 12-01 VOGTLE SIMULATOR CERTIFICATION-PLAN PAGE 31 OF 34 JcnRM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION 1
' EERFORMED BY: P. Rubin DATE: 12/10/90 REVIEWED BY: M. Gibson DATE: 12/),0/90 APPROVED BY: R. Dorman SUPERVISOR OPERATIONS TRAINING DATE: 12/10/90:
Performance Test Procedures:07-10 Interval: MDlfunction to Termination DR Number: 31-(9009020)
Comparison-Comparison Parameter Measure Value LR 1310 RVLIS Dynamic Range NA TABLE TOP Problem
Description:
Cause:
-RVLIS initially increases at: time Model does not automatically of trip and appears to be directly compensate RVLIS indication for j
(pilowingRCSflow.
temperature and pressure, and does not-appear-to be presenting a direct indication of void fraction.
Corrective. Action:
Impact if-not corrected:
Correct model such that it reflects No impact. The increase is small the temperature and pressure and occurs at a time that RVLIS is compensation, and provides not important to the operator. The indication on core void fraction.
operatorLwould only notice it on a computer trend. It would not_cause-a misdiagnosis of,an event and will not' impact training effectiveness.
Resolution:
Results:
DR 9009020 was written.
-The DR is an open_ item to Westinghouse for warranty repair, although we feel that
+
there is little or no training l
impact.
FORM: 12-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 32 OF 34 gIQITITLE:
DISCREPANCY RESOLUTION WORKSHEET REVISION 1
-PERFORMED-BY:
P. Rubin DATE: 12/10/90_ REVIEWED BY:
M. Gibson DATE: 12/10/90 APPROVED BY:
R.
Dorman SUPERVISOR OPERATIONS TRAINING DATE: 12/10/90
-Perf3rmance Test Procedures:07-10 Interval: Malfunction to Termination DR Number:32 (9009021)
Comparison Comparison Parameter Measure Value-
-FI 416 Loop 1 RCS Flow NA TABLE TOP FI 426 Loop'2 RCS Flow NA TABLE TOP FI 435 Loop 3 RCS Flow NA TABLE TOP FI 445 Loop 4 RCS Flow NA TABLE TOP Problem
Description:
Cause:
fn (Io.w spikes prior to and during Model problem.
saturation conditions.
Also has a
' sharp' decline prior to reaching saturation.
Corrective-Action:
Impact if not Corrected:
Correct model{to reflect gradual Minor impact, overall trend is decrease as pressure decreases, proper and it is unlikely that the without: spiking.-
spikes would be. noticed on the MCB indications.
Resolution:
Results:
'DR 9009021 was' written.
Corrected the calculation of P-sat. The DR was satisfactorily tested and closed.
LOL
l FORM: 12-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 33 OF 34
('9RM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION 1 v
PERFORMED BY:
P. Rubin DATE: 12/10/90 REVIEWED BY: M a ibson DATE: 12/10/90 APPROVED BY:
R.
Dorman SUPERVISOR OPERATIONS TRAINING DATE: 12/10/90 Performance Test Procedures:.Q6-08 Interval:S_urveillance Procedure Performance DR Number:33 (9009022)
Comparison Comparison Parameter Measure Value NA NA NA Problem
Description:
Cause:
hip-14220-1 can not be performed Model problem on steam admission due to excessive secondary plant through stop valves.
trannient.
Corrective Action:
Impact if not Corrected:
Correct model such that load swings Minor impact, only affects the while stroke testing valves are performance of this one limited to 2 to 3%.
surveillance. The surveillance can be performed but the load swing is excessive.
Resolution:
Results:
DR 9009022 was written.
DR is open.
O 1
~-
FORM:-12-01' VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 34 OF 34
'*Id4 TITLE:- DISCREPANCY RESOLUTION WORKSHEET REVISION 1 PERFORMED BY:
P. Rubin DATE: 12/10/90 REVIEWED BY: M. Gibson DATE: 12/10/9.9 APPROVED BY: EL, Dorman SUPERVISOR OPERATIONS TRAINING DATE: 12/10/92 Performance Test Procedures:06-05 Interval: Plant Cooldown to Cold Shutdown DR Number:23 (9009024)
Comparison Comparison Parameter Measure Value PI 614 RHR Pp Disch Press NA TABLE TOP roblem
Description:
Cause:
Abnormal pressure fluctuations when Model problem.
pump started on mini-flow.:
4 l Corrective Action:
Impact if not Corrected:
Correct model such that discharge Minor impact, fluctuations are only.
pressure responds properly, seen at-time of pump start, pressure responds properly the remainder of the time.
Resolution:
Results:
DR 9009024 was written.
Several RHR model repairs were;made between the time of the testing.and-the analysis of the data. This DR was corrected as a part of these repairs and could not be reproduced. The DR was closed.
O I
e
._...___._.___..m FORM: 17-03 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 1 OF 3 FORM TITLE: CERTIFICATION REVIEW COMMITTEE REVISION 0-
.The " Simulator certification committee" was set up;to review the steady. state, normal operations and transient-testing of the Vogtle simulator.
The " Committee" iirst met on 8/22/90. It consisted of four individuals with the following credentials:
Dan Cooper:
SRO. certified / licensed at Byron Unit 1 and the Westinghouse Nuclear Training.Conter - Zion. ( # SOP-30218).
Byron /Braidwood - 3.5 years operational experience as a plant
~
equipment operator, work planner, and operating engineer assistant. Duties included various plant _ equipment operation, coordinating work activities of maintenance-departments,
.i outage pre-planning. and problem _ solving, writing / revising abnormal operating procedures and surveillance testing review.
Plants Vogtle, Sheron Harris,, Braidwood, Beaver -. Valley, Byron -7 years Operations Instructor; experience.. Duties have O
included instruction 'of cold
- license, hot
- license, and operations requalification classes. Also administered plant requalification exams, did program development, EOP review /
revisions, and simulator acceptance testing George Gun'n:
RO and 'SRO licenses at Plant Vogtle (#0P-20475 and # SOP-20863).
Bachelor of Science degree from Clemson University majoring in Wood Science.
Plant - Vogtle:
- 5. 5 _ years operational experience as a Plant-Equipment Operator and Reactor. Operator. Duties included the operation. of Various plant equipment, fuel loading, power.
ascension testing and commercial operation of Units 1 & 2 in the control room..
Plant Vetle:
4 months Operations Instructor experience.
Duties ve included-hot license class
-instaction and=
simulator certification.
O
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i 5
_ FORM: 17 VOGTLE-SIMULATOR CERTI 'ICATION PLAN PAGE 2 OF 3
-FORM TITLE: CERTIFICATION REVIEW COMMITTEE REVISION O Thomas G.
Petrak:
SRO license - at Plant Vogtle. (# SOP-20765)
M.S.
degree from Ohio State University in Mechanical Engineering.
B.S..
from University of Cincinnati in Nuclear. Engineering.
-Zion,.-
Plant _ Vogtle = -
4.5 years Operational Engineering experience._ _ Duties included reactivity management, reactor--
trip reviews, Systems Engineer, start-up testing and _ re-fueling.
i
- Plant Vogtle
1 year 3 months Senior Nuclear Instructor experience. Duties have been.the maintenance and testing of simulator software, simulator acceptance testing and simulator 1
. certification.
Paul W. Rubin i
.RO and/or..SRO certified / licensed at Crystal River Plant,-San A
On'ofre Generating Station, Shearon' Harris Plant and Plant
(> ;.
Vogtle.LU.S. Navy Nuclear Machinist Mate Qualified (# OP-5882)
(Dock # 55.08234)
Calvert Clif fs, Crystal River - 3 years operational experience as-a Plant Equipment Operator and Reactor Operator.; Duties'
-included - operation'_ of - various plant. _ equipment, procedure writing'and review, refueling and plant commcrcial operation in the: main-control room.
~
WPPSS, San _Onofre. Station, Shearon. Harris, Plant Vogtle - 8 years -Operations Instruction experience.
Duties included training' program development, operations procedure review and
-writing, cold license instruction, hot license instruction,_
requalification instruction, writing and administering annual requal exams and initial license audits at various plants, simulator acceptance testing and certification.
4
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FORM: 17-03 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 3 0F 3 FORM. TITLE: CERTIFICATION REVIEW COMMITTEE REVISION-0
~
1.
a i,
The committee first'~ reviewed the data against actual ' plant data as available. Ifl plant data was not available, then FSAR data was used, when available. If-no data was available, then best judgement of the committee based on their various backgrounds and t
'l plant _ experiences was used.
l' All' tests were determined 'to be satisfactory with' the-exception of those items identified on--Form 1201 of the report.
The committ'ee-was in full agreement for all tests with:the-exception of Test 07-03. We had an unexpected safety -injection due to _ pressurizer pressure.
Review of FSAR data showed that pressurizer _ pressure should be very cloce to the SI setpoint. Three -
-of the - four members agreed that - the SI was acceptable but.the.
fourth member was -not-convinced.- The test was considered satisfactory.-
I s
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PERFORMANCE TEST SCHEDULE 1/4/91 Plant A.W. Vogtle, Unit 1 Docket #50-424 Georgia Power Company O
9
-FORM: 17-02 VOGTLE SIMULATOR CERTIFICATION PLAN-PAGE 1 OF 5 RM' TITLE: PERFORMANCE TEST SCHEDULE REVISION O TERFORMED BY: P. Rubin DATE: 9/25/90 REVIEWED BY: M. Gibson DATE: 9/25/90
- APPROVED BY:
R.
Dorman SUPERVISOR OPERATIONS TRAINING DATE:
11/15/90 Annual Operability Test The following operability tests will be conducted annually (Computer Tasting and Appendix B - Steady Gtate and Transient Performance Tests):
o:
COMPUTER REAL TIME TEST o.
SIMULATOR LIMITS EXCEEDED TEST o
STEADY STATE PERFORMANCE AT-30% POWER FOR 60 MINUTES (06-09) o STEADY = STATE PERFORMANCE AT 75% FOR 60 MINUTES (06-10) o STEADY STATE PERFORMANCE AT 100% POWER FOR 60 MINUTES (06-11)
'o
. MANUAL = REACTOR TRIP (07-01)-
o ~
SIMULTANOEUS TRIP OF ALL FEEDWATER PUMPS (07-02)
O
%A-SIMULTANEOUS CLOSURE OF ALL MAIN STEAM ISOL VALVES (07-03) o-SIMULTANEOUS TRIP OF ALL REACTOR COOLANT PUMPS (07-04L o
SINGLE REACTOR COLLANT PUMP TRIP (07-05) o MAIN TURBINE TRIP W/O REACTOR TRIP (07-06)
.o.
. MAXIMUM RATE POWER RAMP (07-07) s
'o MAXIMUM SIZE RCS RUPTURE W/ LOSS OF OFFSITE POWER (07-08)
.o MAXIMUM SIZE UNISOLABLE MAIN STEAM LINE RUPTURE (07-09)
(
ol SLOW PRIMARY'SYS DEPRESSURIZATION TO-SATURATED CONDITION (07-10) l' t
L lr pa 9
r
FORM: 17-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 2 OF 5 5
DRM TITLE: PERFORMANCE TEST SCHEDULE REVISION O PERFORMED BY: P. Rubin DATE: 9/25/90 REVIEWED BY: M. Gibson DATE: 9/25/90 APPROVED BY:
R.
Dorman SUPERVISOR OPERATIONS TRAINING DATE:
11/15/90 Porformance Tests The following performance tests will be conducted (in addition to the annual operability tests) in the first year following certification (Normal Operation Tests, Malfunction Tests, and Transient Tests not tested as Annual Operability Tests):
o LOSS OF COOLANT-SIGNIFICANT PWR STEAM GENERATOR LEAKS (05-01) o LQSS OF COOLANT-SMALL RCS BREAKS (05-05) o LOSS OF EMERGENCY POWER (05-09) o IDSS OF POWER TO INDIVIDUAL INSTRUMENT DC BUSES (05-13) o LOSS OF COMPONENT COOLING SYS OR COOLING TO INDIVIUAL COMPONENTS (05-17) l (19 FUEL CIADDING FAILURE (05-21)
(/
o MAIN STEAM LINE BREAK OUTSIDE CONTAINMENT (05-25) o PROCESS INSTRUMENT. ALARMS. AND CONTROL SYSTEM FAILURES (05-29).
l o
PLANT STARTUP FROM COLD TO HOT STANDBY (06-01) o
-COOLDOWN FROM HOT STANDBY TO COLD SHUTDOWN CONDITIONS (06-05) l l
I l
l l'
()
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FORM: 17-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 3 OF 5 (PERFORMEDBY:
ORM TITLE: PERFORMANCE TEST SCHEDULE REVISION O P. Rubin DATE: 9/25/90 REVIEWED BY: M. Gibson DATE: 9/25/90 APPROVED BY:
R.
Dorman SUPERVISOR OPERATIONS TRAINING DATE:
11/15/90 Performance Tests The following performance tests will be conducted (in addition to the annual operability tests) in the second year following certification (Normal Operation Tests, Malfunction Tests, and Transient Tests not tested
-as' Annual Operability Tests):
o LOSS OF COOIANT-INSIDE PRIMARY CONTAINMENT (05-02) o FAILURE OF SAFETY AND RELIEF VALVES (05-06) o LOSS OF EMERGENCY GENERATORS (05-10) o LQSS OF CONDENSER VACUUM INCLUDING LOSS OF CONDENSER LEVEL CONTROL (05-14) o LOSS OF ALL FEEDWATER-NORMAL AND EMERGENCY (05-18)
GENERATOR TRIP (05-22) b-oo MAIN FEED LINE BREAK INSIDE CONTAINMENT (05-26) o PASSIVE MALFUNCTIONS IN SYSTEMS (05-30) o NUCLEAR STARTUP FROM HOT STANDBY TO RATED POWER (06-02) o BEACTOR TRIP FOLLOWED BY RECQVERY TO RATED POWER (06-06)
O
l FORM: 17-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 4 OF 5 N
, ORM TITLE: PERFORMANCE TEST SCHEDULE REVISION 0
' PERFORMED BY: P. Rubin DATE: 9/25/90 REVIEWED BY: M. Gibson DATE: 9/25/90 APPROVED BY:
R.
Dorman SUPERVISOR OPERATIONS TRAINING DATE:
11/15/90 Parformance Tests The following performance tests will be conducted (in addition to the annual operability tests) in the third year following certification (Normal Operation Tests, Malfunction Tests, and Transient Tests not tested as Annual Operability Tests):
o LOSS OF COOLANT-OUTSIDE PRIMARY CONTAINMENT (05-03) o LOSS OF INSTRUMENT AIR (05-071 o
LOSS OF POWER TO THE PLANT'S ELECTRICAL BUSES (05-11) o LOSS OF SERVICE WATER OR COOLING TO INDIVIDUAL COMPONENTS (05-15) o CONTROL ROD FAILURES (05-19) o FAILURE IN AUTOMATIC CONTROL SYSTEMS (05-231 b
MAIN FEED LINE BREAK OUTSIDE CONTAINMENT (05-27) o FAILURE OF AUTOMATIC REACTOR TRIP SYSTEM (05-31) o LOAD CHANGES (06-03) o CORE PERFORMANCE TESTING (06-07) l D
i
l FORM: 17-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 5 OF 5
)
l
,DRM TITLE: PERFORMANCE TEST SCHEDULE REVISION O PERFORMED BY: P. Rubin DATE: 9/25/90 REVIEWED BY: M. Gibson DATE: 9/25/90 APPROVED BY:
R.
Dorman SUPERVISOR OPERATIONS TRAINING DATE:
11/15/90 JPorformance Tests The following performance tests will be conducted (in addition to the annual operability tests) in the fourth year following certification (Normal Operation Tests, Malfunction Tests, and Transient Tests not tested as Annual Operability Tests):
o LOSS OF COOLANT-LARGE RCS BREAKS (05-04) o LOSS OF OFFSITE POWER (05-08) o LOSS OF POWER TO INSTRUMENT AC BUSES (05-12) o LOSS OF SHUTDOWN Ci n NG (05-16) o INABILITY TO DRIVE CONTROL RODS (05-20) o FAILURE OF RCS PRESSURE & VOLUME CONTROL SYSTEMS (05-24) b NUCLEAR INSTRUMENTATION FAILURES (05-28) o PIANT SHUTDOWN FROM RATED POWER TO HOT STANDBY (06-04) o' OPERATOR CONDUCTED SURVEILLANCE TESTING ON SAFETY RELATED SYSTEMS (06-08)
O
U S. NUCLEAR Af 0VLATOdy COh4Mi&S10N APPnovt0SvOM8 No. Jimc1M RC, FOAM 474 (1J0 8 012E5 $40C 66 ttfiMATED BVADf h FEA RiSPONat TO COMPLY RtTH THl$
tN 807,M A T ION COL LICTIJ N R80VitT; 120 MAS 708 mat;D SIMULATION FACIUTY CERTIFICATION l?a**o',"yJT,^tt,=,=E,~,^4'g,? m,'a;;;
64 AN TO THE A O
E T I'O R ECT si 0138# OeFICE OF WAN AGEMENT AND WDOET, vt ASHiNGTON, oc ras INSTRUCTIONS. This form is to be faaJ for inst.si cert.fication, rece'tification (if requiredL sad for any change to e simulation facihty performance testing plan made a'ter initial e;#bmittal of such a plan Provide the following mformation, and check the appropriate bon to mdicate reason for submittal.
lOOGKET NUMBEFt F ACILITY A. W. Vogtle dnit 2 Huclear Power Plant so. 425 LICE NSE E l0 ATE deorgia Power Company 1-4-1991 This is to certify that:
1.
The above named facility licensee is usirig a stmutation facility consisting solely of a plant referenced simulator that meets the recurrements of to CF R 55.45.
2.
Documentation is eve 11eone for NRC review in accoroance with 10 CF R 66.45(bL 3.
This simulation facihty meets the guidance contamed m ANSI /ANS 3.6,1985, as endorsed by N RC Reguistory Guce !.140.
If there are any exceptions to the certification of tNs item, check here l X l and describe fully en additions: pages as necessary.See At ta c hmen t 1: Excep ti o1s N AME (or other #denri/sretion) AND LOCATION OF SIMULATION F ACILITY A.11. Vogtle Simulator, River Rd., Approx. 5 mi. NE, Hwy. 23, Waynesboro, GA 30830 SIMULATION F ACILITY PE RFORM Arc TEST ABSTR ACTS ATTACHED, (for performence tests conducted /n the per/od ending with the dare of this certificaten/
y DESCRIPTION OF PE R FOR M ANCE T ESTING COar PLET ED (Artsch a Idttrons/ page/s/ es necessery, and klent/N tne trem descr, pron be,ng continued)
Plant A. W. Vogtle, Unit 2 Simulator Training will be performed using the Unit 1 Training simulator. The performance tests were run per the Unit I certification.
Operational characteristics of Unit 2 were considered and difference which may result in negative training are identified as exceptions in Attachment 1 to this form.
SiMULATlON F ACILliY PE RF0RMANCE TEniTlNG SCHEDULE ATT ACHED. Ifor the conduct et sporosomecely 25% of performance tests per yeer Mr the tour year X
period commencing with the date of this certificatoon.)
- SCRIPTION OF PERFORMANCE TESTINO TO DE CONDUCTED. (Attach additionnipagettina rseceentry en# xtentiN the item unectroten bemg continued)
I blant A. W. Vogtles Unit 2 Simulator Training will be performed using the Unit 1 l
Training simulator.
The performance tests will be run per the Unit 1 certification.
The operational characteristics of Unit 2 have been considered and differences which result in negative training identified and resolved as described in Attachment 1.
Ft' DANCE TESTIHG PLAN CHANGE, Ifor any modification to e performance testing pian submitted on a omicus certifmetton)
DESCRIPTloN OF PE RFORMANCE TESTING PLAN CHANGE (Attach addtreesipege(sl an necessery, and ioenttN the ttom description being continued)
R ECE R TIFlCA TION (Deacnbe correctin actone tsk en, et5tronufts of completed performance testmg in accordance with 10 CFR l 55,45(b)(5)/v),
Artsch odditions/ papels) es nece.sery, ed Mont/N the itn deactretion borne contmuodJ Any false statement or omiesson en this do mentc!Miudmg attachments, may be subject to civil and criminal sanctions. I certify under ponetty of perjury that the information m this document and attachments es true end conoc(
l TITLE l0 ATE SIGNATURE - AUTHORIZED REPRESENTATIVE
[
T Ceneral ManaGOr n accon$ance with 10 CF R $ 66A pmunicatens, thee form shall be submitted to the NRC as tollows:
i BY Mall ADDRESSED TO: derector, Offtco of Nucesor Reector Requietton BY DE LIVE R Y IN Pf RSON one ythete Funt North U,8. Nesteer Regutomovy Commese6en TO THE NRC OFFlCE AT:
11666 Rockville Pthe Washengsen, DC 20606 Roadsvalle, le NMC FORM 474 (l 005
O EXCEPTIONS 1/4/91 Plant A.W. Vogtle, Unit 2 Docket # 50-425 Georgia Power Company O
l 0
l
A.W.
PLANT VOGTLE, UNIT 2
- 50-425 ATTACHMENT 1 1/4/91 l
ll0 Exceptions to ANSI /ANS3.5-1985 for Unit 2 are the same as those specified for Unit 1.
Georgia Power Company has researched the differences between Unit 1 and Unit 2. This report is made a part of the attachment and serves to document compliance with Regulatory Guide 1.149.
O O
I 1
O UNIT 1 VS UNIT 2 DIFFERENCES Plant Vogtle has made a concerted effort to make Unit 1 and Unit 2 as identical as possible. The controls in both units are-essentially identical with minor differences as described below.
The Unit 2 Main Control Board is a rotated image of the Unit 1 Main Control Board. A left-right relationship exists for all controls on the Main Control boards except for one small panel (section D). Section D is on the lef t side of the Unit 1 panels and on the_right side of Unit 2 panels. This panel contains RVLIS, PSMS, and the Main Steam Bypass Isolation valves on each unit. This difference has no noticable impact on operation of the units.
The rest of the Unit 2 control boards appear as if the Unit 1 boards were. moved west..Their appearance on Unit 2 will be the same on either unit. This requires a slightly different scanning pattern but has no noticable impact on unit operation.
All common or shared equipment is located on Unit 1 so some of the Unit 2 panels have slightly less equipment. The Unit 2 plant computer systems have no common equipment inputs.
The differences-listed below are identified based on the May 11, 1988 letter to the NRC requesting dual unit licenses for Vogtle operators, a review of the Design Change Packages for each unit, and_ operator experience.
There are very few differences that will affect operation of h'
the units and these are very minor. Vogtle operators receive classroom training on plant differences that may affect operation.
The intent is not to identify every minor difference in the units but to show that they are alike to the extent that the Vogtle simulator can be used for Unit 2 operators with basically no training impact.
From the dual unit license letter the following differences still exist:
1)
-Boron Injection T=nv (3IT) and the BIT Recirc System Differences: The BIT and BIT recirc system were. not installed on Unit 2 while Unit 1 has the components disabled in place. The reactor operator does not see any difference in system response due to this and therefore it has no training impact. This difference is covered as part of the licensed operator training program.
2)
Waste Evaporator Differences: 'The Unit 2
Waste Evaporator was not completed. This is not simulated and therefore has no training impact. This difference is covered as part of the licensed operator training program.
O
3)_
Waste Monitor Tank Capacity
~
Differences: Unit 2 has 2 additional 20,000 gallon tanks designated as common tanks.
This is not simulated and therefore has no training impact.
This difference is covered as part of the licensed operator training program.
4)
'NSCW Aux Containment Cooler Isolation-Valves Differences: Unit 2 valves are' interlocked so that the outlet valves-must be opened first. This minor system-variation is covered as part of the licensed operator training program and does not have any significant impact
-on. operator simulator training.
5)
NSCW high point. vacuum breakers Differences: -Only unit 2 has these breakers. The reactor operator does not see any difference in system response due to this andLtherefore it has no training impact. This difference is covered as part of the' licensed operator training program.
6)-
Diesel Generator System Differences:.The Unit 2-DG fuel oil transfer pumps have a local / remote transfer switch - so that they can be
- operated locally. -This minor s'ystem variation is covered-as-part of-the= licensed operator -training program and does.not - have. any significant intoact on operator simulator training.
The Unit 2 DG'has a drain linecinstalled on the day tank so;that the day tank can be drained back to the fuel oil storage-tank. This is not simulated:and therefore has no-training impact. This difference is_ covered as part of the licensed operator. training program.
- The." Sync Mode-Selecter" switch turns in the opposite direction. This minor system variation is covered as part.
-of~the licensed-operator training program and does not
. have-any significant impact on operator simulator training.
7)-
CRDM Low Flow Alarm
~
Differences: Only Unit 2 has this alarm. This minor system variation is covered as part of the annual operator requalification program and does not have any significant impact on operator simulator training.
,,---w-,
-nv--
8)
Control Buildi.?q Electrical Penetration Filter Units Differences: Only Unit 1 has these units. This minor system variation ic covered as part of the licensed operator training 7rogram and does not have any significant impact on operator simulator training.
9)
Main Food Pump Seal Injection Differences: Unit 2 MFP seal injection filters have filter D/P indication that Unit 1 doesn't. This is not simulated and therefore has no training impact. This difference is covered as part of the licensed operator training pEogram.
10)
RHR Injection Orfices Differences:
Unit 2 i's sized smaller.
The reactor operator does not see any difference in system response due to this and therefore it has no training impact. This difference is covered as part of the licensed operator training program.
11)
Annunciator Power Supplies Differences: Unit 2 supplies w4,ll auto-swap from primary
]
to secondary or secondary to primary. This minor system variation is covered as part of the licensed operator training prcgram and does not have any significant impact on operator simulator training.
From the tech spec differences section:
1)
RTNDT Limits and Copper Content Limits e.re slightly different resulting in variations in the Units 1 and 2 operating heatup and cooldown limitation curves. This minor system variation is covered as part of the licensed operator training program and does not have any significant impact on operator simulator training.
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p
.lV Other differences identified from review of the " Design Change
. Packager" are:
1)
Unit 2 Steam Generators have been modified with expanded narrow range level taps and indication. This has resulted th a different normal operating level setpoint as well as different setpoints for Reactor trip and ESFeS actuations.
This same change will be made to Unit 1 Steam Generators during the next refueling outage.
The simulhtor will be updated with this change once it is installed on Unit 1.
This difference will be covered as a part of the 1991 licensrd operator requalification program.
- 2) Unit 2 has.nstalled a separate firAt out reset pushbutton for the Reactor trip first out annunciator panel. This same change will be made to Unit I during the next refueling outage.
The simulator will be updated witt, this chane once it is installed on Unit 1.
The difference will be covered c.s a part of the 1991 licensed operator requalification program.
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