ML20078A135

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Plant Vogtle Training Simulator 4-Yr Certification Update
ML20078A135
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 01/13/1995
From:
GEORGIA POWER CO.
To:
Shared Package
ML20078A121 List:
References
NUDOCS 9501240293
Download: ML20078A135 (115)


Text

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PLANT VOGTLE  !

i TRAINING SIMLLATOR O

4-YEAR CERTIFICATION  !

LPDATE  !

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TABLE OF CONTENTS

.;~m ij ITEM DESCRIPTION Unit 1

1) Form 474
2) Attachment 1 - Exceptions Unit 1 Exceptions
3) Attachment 2 - Performance Tests Completed Form 05 Malfunction Tests Form 06 Normal Operations Tests Form 07 Transient Tests Form 08 Computer Tests Form 05 Malfunction Test Abstracts Form 06 Normal Operations Test Abstracts Form 07 Transient Test Abstracts

/~N Form 08 Computer Test Abstracts

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Form 12-02A - Simulator Performance Test Dates Form 12 Discrepancy Resolution Worksheet Form 17 Certification Review Committee

4) Attachment 3 Form 17 Performance Test ScD 'ule
5) Attachment 4 Form 18 Performance Test Plan Changes Unit 2
1) Form 474
2) Attachment 1 Exceptions Unit i vs Unit 2 Differences

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NRC FORM 474 U.S. NUCLEAR REGULATORY COMMISSION APPROtfED BY OM8: NO. 3150413a g EXPtRES: 10/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTION REQUEST: 120 HOURS. FORWARD 4 SIMULATION FACILITY CERTIFICATION C MMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MANAGEMENT BRANCH (MNBB T714), U.S. NUCLEAR REGULATORY COMMtSSION, WASHINGTON, DC 205554001, AND TO THE PAPERWORK REDUCTION PFOJECT (3150 0138), OFFICE OF MANAGEMENT AND BUDGET, W ASHINGTON, DC 20503 INSTMUCTIONS: This form le to be flied for initial certification, recortshcation (if requered), and for any change to a simulation faculty perfor* nance testing plan made after inmal submmal of such a pian. Provide the following information and check the appropriate box to indicate reason for submlitel FN* DOCKET NUMBER l A. W. Vogtle Unit 1 Nuclear Power Plant 50-424 I UCENSEE DATE Georgia Power Company 1-4-1995 Th.s i to ee,wy that

1. The above named facudy licensee is using a simula: ion facility consisting solely of a plant-referenced simulator that meets the requirements of 10 CFR 55.45.
2. Documentation le ava; table for NRC review in accordance wfth 10 CFR SS.4S(b).
3. This simulation facility meets the gu6 dance contained in ANSI /ANS 3 S,1985, as endorsed by NRC Regulatory Guide 1.140.

E me. any EXCEPTIONS io the c.rtmcation of this ei.m, CHECx NERE K ] and d. scribe fuiiy on additionai page. as n.ce.sa6cc A t tach m ent 1 :Excepti ms NAME (w other Jdene#cepon) ANO LOCATION OF SIMULATION F ACIUTY, 1

A. W. Vogtle Simulator,Iliver Rd., Approx. 5 mi. NE of Ilwy 23, Waynesboro, G A 30830 l l

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X BIMULATION FACluTY PERFORMANCE TEST AB3 TRACTS ATTACHED. (For performance fests conducted M the persod endog with the date of thJs cert #6catfort)

DESCRPTION OF PEF +0HMANCE TESTING COMPLETED. (Attach addettormt pages as necessary and #denery the nem desenpoon bomp conenued)

See Attachment 2: Performance Tests completed.

l 8 l StMULAT10N FACIUTY PERFORMANCE TESTING SCHEDULE ATTACHED. (For the conduct of approstmetely 25* of putbrmance tents per year Ibr me kryear pened commenoong with the dare of thte certt6cattort)

DESCRIPTION OF PERFOHMANCE TESTING TO BE CONDUCTED. (Attech add /conar pages as necessary and sdenWy the nom desenpoort bemg canonued)

See Attachment 3: Performance Test Schedule i

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l eEnFOnuANCE TtSTING etAN CnANae. (Fa a.y modoncanon no e patormaice us,ung pian submated on a m ceancanort) y DESCHFHON OF PERFORMANCE IESTING PLAN CHANGE (Anaon addebonar pages as necessary swf AdenWy the nem desonpoon being canonued)

See Attachment 4: Test Plan Changes RECERTIFICATtON (Describe correcove acDons takert attach results of completed portumoance testing en accordance with f 0 CFR S14S(b)(S)(ity (AMach addeonalpages as recessary and idonely be Nsm descoppeon bemg contmuod)

Any falso statemeni or omionson in thts cocument, includmg anschments, may be eutyect to c#wil and enminas sancteons I r.ortify under penalty of perjury that the Information in this document and attachmente le true and correct.

SiONATUF DM ED HEPHESE NTATIVE TITLE DATE

/2.6 _,/ r General Manager Ca acc6rds e Mm to CJ R SSh, Cor%urucations, thes farm shall be submmed to the NHC as foilows:

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BY M u ADDRESSED TO: DtftECTDR, Orf1CE OF NUCLEAR REACTOR REGULATION BY DELNERY IN PERSON ONE WHITE FLINT NORTH U.S. NUCLEAR REOULATORY COMMIS$40N TO THE NRC OFFICE AT, t1565 ROCKVILLE PIKE WASHINGTON, DC 20555 0001 ROCKVIL12, MD NRC FOHM 474 (1492) PHNTED ON RECYCLED PAPER

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Attachment 1 EXCEPTIONS 01/04/95 Plant A.W. Vogtle, Unit 1 Docket # 50-424 O Georgia Power Company I

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00-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 1 OF 12-RM TITLE: ANSI /ANS 3.5 EXCEPTIONS WORKSHEET REVISION NO 4 PERFORMED BY: T.Petrak DATE: 01/03/95 REVIEWED BY: M.Gibson DATE:01/03/95 i APPROVED BY R. Dorman MANAGER TRAINING & EP DATE: 01/04/95 ,

h ANSI SPECIFICATION:3.1.1(7) TITLE:Startuo. Shutdown & Pwr Oper 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 O ,

JUSTIFICATION: [

Plant Vogtle is prevented from performing a plant startup or operate at' power without full reactor flow by the plant's Technical Specifications 1

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00-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 2 OF 12 RM TITLE: ANSI /ANS 3.5 EXCEPTIONS WORKSHEET REVISION NO 4 PERFORMED BY: T.Petrak DATE: 01/03/95 REVIEWED 'Y: M.Gibson DATE:01/03/95 APPROVED BY R. Dorman MANAGER TRAINING & EP DATE: 01/04/95 ANSI SPECIFICATION:3.1.1(9) TITLE: Core Performance Testina Usina Permanent 1v Installed Instrumentation

. EXCEPTION:

GPC takes exception to this requirement only so far as permanently 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.

O JUSTIFICATION:

Plant Vogtle, by design, has no permanently installed instrumentation for core reactivity tests.

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RM: 00-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 3 OF 12 FORM TITLE: ANSI /ANS 3.5 EXCEPTIONS WORKSHEET REVISION NO 4

~ PERFORMED BY: T.Petrak DATE: 01/03/95 REVIEWED BY: M.Gibson DATE:01/03/95

' APPROVED BY R. Dorman MANAGER TRAINING & EP DATE: 01/04/95 ANSI SPECIFICATION:3.1.2(12) TITLE: Control Rod Failures Includina Stuck Rods. Uncoupled Rods. Driftina Rods, and 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 i

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JUSTIFICATION:

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 Fail to Move on Auto Demand
8. Control Banks Fail 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 H-8 Ejected O

RM: 00-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 4 OF 12 FORM TITLE: ANSI /ANS 3.5 EXCEPTIONS WORKSHEET REVISION NO 4 PERFORMED BY: T.Petrak DATE: 01/03/95 REVIEWED BY: M.Gibson DATE:01/03/95 APPROVED BY R. Dorman MANAGER TRAINING & EP DATE: 01/04/95 ANSI SPECIFICATION: 3.1. 2 (2 5) 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

'RM : 00-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 5 OF 12 FORM TITLE: ANSI /ANS 3.5 EXCEPTIONS WORKSHEET REVISION NO 4 PERFORMED BY: T.Petrak DATE: 01/03/95 REVIEWED BY: M.Gibson DATE:01/03/95 APPROVED BY R. Dorman MANAGER TRAINING & EP DATE: 01/04/95 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

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\m-JUSTIFICATION:

Plant Vcgtle is a Westinghouse Pressurized Water Reactor (PWR) .

This requirement is not applicable to the Vogtle simulator l

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RM: 00-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 6 OF 12 RM TITLE: ANSI /ANS 3.5 EXCEPTIONS WORKSHEET REVISION NO 4 PERFORMED BY: T.Petrak DATE: 01/03/95 REVIEWED BY: M.Gibson DATE:01/03/95 APPROVED BY R. Dorman MANAGER TRAINING & EP DATE: 01/04/95 ANSI SPECIFICATION: 4. 3 (5) TITLE:BWR Sucoression Pool Temo EXCEPTION:

GPC takes exception to this requirement. This operating limit will not be monitored 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.

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 2 01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 7 OF 12 t FORM TITLE: ANSI /ANS 3.5 EXCEPTIONS WORKSHEET REVISION NO 4 PERFORMED BY: T.Petrak DATE: 01/03/95 REVIEWED BY: M.Gibson DATE:01/03/95 APPROVED BY R. Dorman MANAGER TRAINING & EP DATE: 01/04/95 '-

ANSI SPECIFICATION:B2.1 TITLE: Steady State Perform,gnrdt EXCEPTION:

GPC will substitute a steady state test at 35% 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 ESTIFICATION: '

This power level is a more appropriate stopping point for our plant design and procedures.

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h RM: 00-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 8 OF 12 ,

FORM TITLE: ANSI /ANS 3.5 EXCEPTIONS WORKSHEET REVISION NO 4 ,

PERFORMED BY: T.Petrak DATE: 01/03/95 REVIEWED BY: M.Gibson DATE:01/03/95 APPROVED BY R. Dorman MANAGER TRAINING & EP DATE: 01/04/95 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 s level indicated. All remaining transients will be ran at 100%

power.

B2.2(5) - Trip of any single reactor coolant pump - 12%

_p B2. 2 (6) - Main turbine trip without a reactor trip - 35%

B2.2 (9) - Maximum size unisolable main steam line rupture -

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JUSTIFICATION:  ;

I 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. l Specifically, each power level was selected because:

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B2.2 (5) - In previous years this was the 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 havirg 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. For testing consistency we continue to test at this power i level.

B2.2(6) - A turbine trip will not cause a reactor trip at ,

this power level. As above this power level is still used for test consistency.

B2.2(9) - Response is more severe at this power level and Q was close to the power level used in the FSAR analysis of this transient (the FSAR started with a subcritical core).

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RM: 00-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 9 OF 12 ERM TITLE: ANSI /ANS 3.5 EXCEPTIONS WORKSHEET REVISION NO 4 PERFORMED BY: T.Petrak DATE: 01/03/95 REVIEWED BY: M.Gibson DATE:01/03/95 APPROVED BY R. Dorman MANAGER TRAINING & EP DATE: 01/04/95 l

ANSI SPECIFICATION:B2.2.1/2/3/4 TITLE: Transient 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 can meet the requirement. GPC chooses j to record critical parameter data at 1 second l intervals for transient / malfunction testing and at 30 second intervals for normal operation tests due to the massive size of the files.

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1 JUSTIFICATION: )

Current data recording meets the requirement of Section 4.4, Monitoring Capability, of the Standard. ,

With a resolution of I second intervals, it is GPC's view that no anomalies would be missed at this rate i which could cause negative training. This is l balanced against the amount of data that is stored and plotted.

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RM: 00-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 10 OF 12

.. FORM TTTLE: ANSI /ANS 3.5 EXCEPTIONS WORKSHEET REVISION NO 4 L

PERFORMED BY: T.Petrak DATE: 01/03/95 REVIEWED BY: M.Gibson DATE:01/03/95 APPROVED BY R. Dorman MANAGER TRAINING & EP DATE: 01/04/95 ANSI SPECIFICATION: 4.1 TITLE: Performance Criteria for Steady State Operation EXCEPTION:

ANSI requirements state that simulator computed values of l 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 is referenced to plant value or to scale range, GPC will use the 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 is used as criteria) l 0

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RM: 00-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 11 OF 12 FORM TITLE: ANSI /ANS 3.5 EXCEPTIONS WORKSHEET REVISION NO 4 I l

PERFORMED BY: T.Petrak DATE: 01/03/95 REVIEWED BY: M.Gibson DATE:01/03/95 i APPROVED BY R. Dorman MANAGER TRAINING & EP DATE: 01/04/95 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 reports (DR) have not  ;

been resolved within the time period permitted by the ANS '

standard.

i DR 9205015 Get some spray flow with RCP #1 off and it's spray valve open.  ;

STIFICATION: Minor training impact. Expect repair in 1995.

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DR 9206006 With a loss of 1BY1B our Plasma Display remains in Service.

JUSTIFICATION: With our current computer system, the display can not be put back in service after a loss of power without rebooting the computer system. We are replacing this computer system in 1995/1996 and will be able to remove power with the new l system.

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RM: 00-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 12 OF 12 RM TITLE: ANSI /ANS 3.5 EXCEPTIONS WORKSHEET REVISION NO 4 PERFORMED BY: T.Petrak DATE: 01/03/95 REVIEWED BY: M.Gibson DATE:01/03/95 APPROVEL S/ R. Dorman MANAGER TRAINING & EP DATE: 01/04/95 ANSI SPECIFICATION: 3.1.1 (10) TITLE: Operator Conducted Surveillances EXCEPTION: This requirem2nt 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 representative of the Plant Vogtle surveillances that can be essentially completed utilizing control board instrumentation:

Voatle Certification Surveillance Tests

1) 14930-1 DG operability test
2) 14423-1 Source range NIS channel operability test r' 3) 14424-1 Intermediate range NIS analog channel operability test

()) 4) 14425-1 Power range quarterly analog channel operational test

5) 14510-1 Control room emergency filtration system operability test
6) 14490-1 Containment cooling system operability test
7) 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
10) 14805-1 Residual heat removal pump and check valve 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 JUSTIFICATION:

Simulation of local panels, process panels, etc. is beyond the scope of the Vogtle simulator and most other simulators.

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Attachment o PERFORMANCE TESTS COMPLETED 01/04/95 Plant A.W. Vogtle, Unit 1 Docket # 50-424

'O Georgia Power Company O

. l INDEX OF PERFORMANCE TESTING Form No. Description I I

05-01 Malfunction Tests -

This section contains a i list of the malfunctions that were tested. The list includes the required malfunctions from section 3.1.2 of the standard plus those

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selected from a review of the Control Room Tasks derived from a systematic approach to training.

06-01 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 the real time tests and the simulator out of i limits testing.

(V~3-05-02 Test Abstracts for the malfunction testing identified on Form 05-01 J'

06-02 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. ,12-02A Simulator Performance Test Dates 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 i qualifications of the committee members, the methodology of their review and includes any differing opinions.

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FORM: 05-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 1 OF 4

,M TITLE: MALFUNCTION PERFORMANCE TEST LIST REVISION O PREPARED BY:M.Pellechi DATE:4/06/88 REVIEWED BY: M.Gibson DATE:12/16/94 APPROVED BY: R. Dorman SUPERVISOR OPERATIONS TRAINING DATE: 01/04/95 j i

MALFUNCTION MALFUNCTION TEST ,

TEST NUMBER TITLE I l

05-01 Loss of coolant, significant PWR steam I generator leaks  !

1 05-02 Loss of coolant, Inside primary containment 05-03 Loss of coolant, Outside primary containment j i

05-04 Loss of coolant, Large reactor coolant breaks )

including demonstration of saturation  !

conditions 05-05 Loss of coolant, Small reactor coolant breaks including demonstration of saturation j 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 05-11 Loss or degraded electrical power to the station, loss of power to the plant's electrical distribution busses l I

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l FQRM: 05-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 2 OF 4 '

llhU4 TITLE: MALFUNCTION PERFORMANCE TEST LIST REVISION O PREPARED BY:M.Pe11echi DATE:4/06/88 REVIEWED BY: M.Gibson DATE:12/16/94 APPROVED BY: R. Dorman SUPERVISOR OPERATIONS TRAINING DATE: 01/04/95 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 plant control functions affecting the plant's g g 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 Lors 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)

FQRM: 05-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 3 OF 4 lItMTITLE: MALFUNCTION PERFORMANCE TEST LIST REVISION O PREPtRED BY:H.Pellechi DATE:4/06/88 REVIEWED BY: M.Gibson DATE:12/16/94 APPROVED BY: R. Dorman SUPERVISOR OPERATIONS TRAINING DATE: 01/04/95 MALFUNCTION MAL 1' UNCTION 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 q g 05-23 Failure in automatic control system (s) that affect reactivity and core heat removal 05-24 Failure of reactor coolant pressure and volume control systems (PWR)

Reactor trip (This test is a duplicate of Test 07-01)

Main steam line break inside containment (This test is a duplicate of Test 07-09) 05-25 Main steam line break outside containment 05-26 Main feed 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]

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' FORM: 05-01 VOGTLE SIMULATOR CERTIFICATION PLAN 'PAGE 4 OF 4 mm r

' _,JE TITLE: MALFUNCTION PERFORMANCE TEST LIST REVISION O i PREPARED BY:M.Pellechi DATE:4/06/88 REVIEWED BY: H,Gibson DATE:12/16/94 I

APPROVED BY: R. Dorman SUPERVISOR OPERATIONS TRAINING DATE: 01/04/95

. 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 l

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RM: 06-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 1 OF 2 FORM TITLE: NORMAL AND STEADY STATE TEST LIST REVISION O PREPARED BY: P. Rubin DATE: 9/27/90 REVIEWED BY: M.Gibson DATE:22/16/94 APPROVED BY: R. Dorman SUPERVISOR OPERATIONS TRAINING DATE: 01/04/95 NORMAL AND STEADY STATE l TEST NUMBER TEST TITLE 06-01 Plant startup - cold to hot standby. The starting j 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 power Turbine startup and generator synchronization (This test is redundant with portions of Test 06-02) 06-03 Load changes 06-04 Plant shutdown from rated power to hot standby l 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, Shutdcwn Margin Demonstration (This test is performed as part of Tests 06-01 and 06-05) 06-07 Core performance testing, Reactivity Coefficient Measurements Core performance testing, Control Rod Worth using permanently installed instrumentation (This test is performed as part of Test 06-07) 06-08 Operator conducted surveillance testing on safety-related equipment or systems O

06-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 2 OF 2 4RM:

FORM TITLE: NORMAL AND STEADY STATE TEST LIST REVISION O PREPARED BY: P. Rubin DATE: 9/27/90 REVIEWED BY: M.Gibson DATE:12/16/94 APPROVED BY: R. Dorman SUPERVISOR OPERATIONS TRAINING DATE: 01/04/95 NORMAL AND STEADY STATE TEST NUMBER TEST TITLE i

06-09 Steady State Performanc' at 35% power 06-10 Steady State Performance at 75% power 06-11 Steady State Performance at 100% power for 60 minutes 5

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1 FORM: _07-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 1 OF 1

-RM TITLE: TRANSIENT PERFORMANCE TEST LIST REVISION O +

'7REPARED BY: P. Rubin DATE: 9/15/90 REVIEWED BY: M.Gibson DATE:12/16/94 APPROVED BY: R. Dorman SUPERVISOR OPERATIONS TRAINING DATE: 01/04/95 1

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' TRANSIENT TRANSIENT OPERATIONS TEST NUMBER TEST TITLE 07-01 Transient Performance, Manual reactor trip {

07-02 Transient Performance, Simultaneous trip of all feedwater pumps 07-03 Transient Performance, Simultaneous closure of all Main Steam Isolation Valves  !

07-04 Transient Performance, Simultaneous trip of all reactor coolant pumps 07-05 Transient Performance, Single reactor coolant pump trip ,

07-06 Transient Performance, dain turbine trip (from the 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 Performance, Maximum size reactor coolant r system rupture combined with a loss of offsite power  !

I 07-09 Transient Performance, Maximum size unisolable main steam line rupture

, 07-10 Transient Performance, Slow primary system depressurization to saturated condition using .

pressurizer relief or safety valve. stuck open .

(Inhibit activation of the high pressure Emergency Core Cooling Systems) l

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F,ORM: 08-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 1 OF 1 ,

-M TITLE: COMPUTER SYSTEMS TEST REVISION O .

' PREPARED BY: P. Rubin DATE: 9/15/90 REVIEWED BY: M. GibEgD DATE: 12/16/94 APPROVED BY: R.Dorman SUPERVISOR OPERATIONS TRAINING' DATE: 01/04/95  !

COMPUTER SYSTEM TESTS TEST NUMBER TEST TITLE 08-01 Computer Real Time Test 08-02 Simulator Limits Exceeded Test .

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' FORM 05-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 1 OF 33 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION 4 PREPARED BY:T.PETRAK DATE:11/4 /94 REVIEWED BY:M.GIBSON DATE:11/4 /94 APPROVED BY:R. DORMAN MANAGER TRAINING & EP DATE: 01/13/92 1

SIMULATOR PERFORMANCE TEST ABSTRACT TITLE: LOCA: Sionificant 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 @ 10% severity. The leak is increased to 50% severity after 6 minutes. At 11 minutes from the beginning of the session, the malfunction severity is increased to 100%. The exercise is terminated once the pressurizer level is stable or slowly

{T increasing above 20%. 9 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 n

V FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION 4 PREPARED BY:T.PETRAK DATE:11/4 /94 REVIEWED BY:M.GIBSON DATE:11/4 /94 APPROVED BY:R. DORMAN MANAGER TRAINING & EP DATE: 01/13/92 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE: LOCA: Inside Containment (05-02)

The Vogtle simulator is initialized to 100% power, EOL, Equilibrium Xe. A Hot Leg #2 rupture (malf #36) is inserted 0100% 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.

,0 This testing was satisfactorily completed. Any discrepancies are identified on Form 12-01. g f

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.' FORM 05-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 3 OF 33 .

FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION 4 l

PREPARED BY:T.PETRAK DATE:11/4 /94 REVIEWED BY:M.GIBSON DATE:11/4 /94 APPROVED BY:R. DORMAN MANAGER TRAINING & EP DATE: 01/13/92 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE: LOCA: Outside Containment (05-031 The Vogtle simulator is initialized to 0% power, BOL, Hot Standby. 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.

The simulator response is evaluated against best estimate judgement 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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. FORM 05-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 4 OF 33 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION 4 )

PREPARED BY:T.PETRAK DATE:11/4 /94 REVIEWED BY:M.GIBSON DATE:11/4 /94 j APPROVED BY:R. DORMAN MANAGER TRAINING & EP DATE: 01/13/92 i SIMULATOR PERFORMANCE TEST ABSTRACT TITLE: LOCA: Larae Break (05-04)

The Vogtle simulator is initialized to 100% power, EOL, ,quilibrium Xe. A RCS Loop 3 cold leg rupture (malf RC03C) is inserte one minute after the simulator is placed in run. The exercise is tt minated 11 minutes.after the simulator has been placed in run.

The simulator response is evaluated against best estimate judgement where Vogtle plant data is not available.

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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 5 OF 33

( FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION 4 PREPARED BY:T.PETRAK DATE:11/4 /94 REVIEWED BY:M.GIBSON DATE:11/4 /94 APPROVED BY:R. DORMAN MANAGER TRAINING & EP DATE: 01/13/92 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE: LOCA: Small Break (05-05)

The Vogtle simulator is initialized to 100% power, EOL, Equilibrium Xe. A hot leg leak at SG #2 inlet (malf #37) is inserted 0 8%

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 Q

V where Vogtle plant data is not available.

This testing was satisfactorily completed. Any discrepancies are identified on Form 12-01, O

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[ ' FORM:05 .VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 6 OF 33 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION 4 l

PREPARED BY:T.PETRAK DATE:11/4 /94 REVIEWED BY:M.GIBSON DATE:11/4 /94 -

. APPROVED BY:R. DORMAN MANAGER TRAINING.& EP DATE: 01/13/92 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE: Failure of Pzr SVs and PORVs (05-06) t The Vogtle simulator is initialized to 100% power, EOL, Equilibrium Xe. A pressurizer safety valve PSV-8010a 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 20 minutes after the start of the simulator run. >

i The Vogtle simulator is reinitialized to 100% power, EOL, Equilibrium O Xe, PORV block HV-8000A open with I/O override. A pressurizer relief valve PV-455a leakage (malf #63) is insertad 0 100% severity one minute after the simulator is placed in run. The exercise is ,

terminated 15 minutes after the start of the simulator run.  ;

The simulator response is evaluated against best estimate judgement '!

where Vogtle plant data is not available, j

.i This testing was satisfactorily completed. Any discrepancies are identified on Form 12-01. l l

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. FORM 05-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 7 OF 33 7 r FORM TITLE: PERFORMANCE TEST ABSTRACT' REVISION 4 PREPARED BY:T.PETRAK DATE:11/4 /94 REVIEWED BY:M.GIBSON DATE:11/4 /94  ;

APPROVED BY:R. DORMAN MANAGER TRAINING & EP DATE: 01/13/92 ,

SIMULATOR PERFORMANCE TEST ABSTRACT ,

TITLE: Loss of Instrument Air (05-07) ,

The Vogtle simulator is initialized to 100% power, EOL, Equilibrium f Xe. A loss of instrument air (malf #198) is inserted 0 70% severity' f 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 psig, the malfunction is removed. The exercise is terminated 3 minutes after the instrument air pressure returns to normal. ,

The simulator response is evaluate 4 against best estimate judgement.  ;

O 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 8 OF 33 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION 4 - 1 PREPARED BY:T.PETRAK DATE:11/4/94 REVIEWED BY:M.GIBSON DATE:11/4 /94 l APPROVED BY:R. DORMAN MANAGER TRAINING & EP DATE: 01/13/92 i SIMULATOR PERFORMANCE TEST ABSTRACT I

TITLE: Loss of Offsite Power (05-081 i The Vogtle simulator is initialized to 100% power, EOL, Equilibrium Xe. A loss of reserve auxiliary transformers 1NXRA/B '(malf ELO2 &- ,

ELO3) and loss of unit auxiliary transformers 1NXAA/B (malf ELO4 & i ELOS) is inserted one minute after the simulator is placed in run. {

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The malfunctions are removed after a sample of loads are checked for proper load shedding and reloading. Following malfunction removal, l the RAT's and the Non 1-E buses are re-energized and the 4160V 1E  !

p buses are transferred from the DG's to the RAT's. The exercise is i V terminated after the Diesels are unloaded. ,

I The simulator response is evaluated against best estimate judgement >

where Vogtle plant data is not available. i This testing was satisfactorily completed. Any discrepancies are ,

identified on Form 12-01. l 1

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. FORM 05-02' VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 9 OF 33 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION 4 PREPARED BY:T.PETRAK DATE:11/4 /94 REVIEWED BY:M.GIBSON DATE:11/4 /94 APPROVED BY:R. DORMAN MANAGER TRAINING & EP DATE: 01/13/92 ,

t SIMULATOR PERFORMANCE TEST ABSTRACT i

TITLE: Loss of Emeraency 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. A Train equipment that was running prior to the loss of the bus is verified to have tripped and attempts are made to restart bus loads. The exercise is terminated after attempts to restart loads.

O The Vogtle simulator is reinitialized to 100% power, EOL, Equilibrium Xe. A loss of reserve auxiliary transformer, 1NXRA (malf 126) is inserted one minute after the simulator is placed in run. The exercise is terminated after the appropriate bus loads have verified to have been properly sequenced onto the bus.

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 10 OF 33

( FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION 4 PREPARED BY:T.PETRAK DATE:11/4 /94 REVIEWED BY:M.GIBSON DATE:11/4 /94  ;

APPROVED BY:R. DORMAN MANAGER TRAINING & EP- DATE: 01/13/92 ?

l SIMULATOR PERFORMANCE TEST ABSTRACT i

TITLE: Loss of Emeraency Generators (05-10)

The Vogtle simulator is initialized to 100% power, EOL, Equilibrium Xe. An emergency diesel DG 1A f ails 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 1 auxiliary transformer 1NXRA (malf #126) is inserted. Following verification that DG 1A did not start, malf #139A is removed and DG 1A is verified that it starts and loads properly. The exercise is terminated after the appropriate equipment has started.

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 11 OF 33 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION 4 PREPARED BY:T.PETRAK DATE:11/4 /94 REVIEWED BY:M.GIBSON DATE:11/4 /94 APPROVED BY:R. DORMAN MANAGER TRAINING & EP DATE: 01/13/92 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE: Loss of Elec. Dist. Busses (05-11)

The Vogtle simulator is initialized to 100% power, BOL, 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.

The Vogtle simulator is initialized to 100% power, EOL, Equilibrium

] Xe. A loss of control building 4.16 KV swgr 1BA03 (malf #132B) is inserted one minute after the simulator is placed in run. B train equipment that was running / energized prior to the loss of the bus are verified to have tripped and attempts are made to restart / .

energize bus loads. The exercise is terminated after attempts to restart / energize loads.  !

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. l The Vogtle simulator is initialized to 100% power, EOL, Equilibrium Xe. A loss of 480 V swgr 1NB02 (malf #134D) is inserted one minute l 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 after the proper leads have been verified deenergized. The s malfunction is then removed. The exercise is terminated after the

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... l s' ' FORM 05-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 12 OF 33 FORM TITLE: PERFORMANCE' TEST ABSTRACT REVISION 4 PREPARED BY:T.PETRAK DATE:11/4 /94 REVIEWED BY:M.GIBSON DATE:11/4 /94 APPROVED BY:R. DORMAN MANAGER TRAINING & EP DATE: 01/13/92 i

SIMULATOR PERFORMANCE TEST ABSTRACT TITLE: Loss of Elec. Dist. Busses s (05-11) appropriace loads have been restarted.

The Vogtle simulator is initialized to 100% power, EOL, Equilibrium Xe. A loss of 480 V swgr 1BB06 (malf #135H) 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 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 13 OF 33 h FORM TITLE
  • PERFORMANCE TEST ABSTRACT REVISION 4 PREPARED BY:T.PETRAK DATE:11/4 /94 REVIEWED BY:M.GIBSON DATE:11/4 /94 APPROVED BY: R. DORMAN MANAGER TRAINING & EP DATE: 01/13/92 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 EL13A) 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

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) Xe, unaffected SG control channel selected for input to SGWLC. A vital instrument panel 1CY1A failure (malf EL13C) 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 V FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION 4 PREPARED BY:T.PETRAK DATE:11/4 /94 REVIEWED BY:M.GIBSON DATE:11/4 /94 APPROVED BY:R. DORMAN MANAGER TRAINING & EP DATE: 01/13/92 SIMULATOR PERFORMANCE TEST ABSTRACT ,

TITLE: Loss of Instrument DC Busses (05-13)

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 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 ESF 125 V DC swgr 1DD1 fault (malf #136D) 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-ESF 125 V DC swgr 1ND1 fault (malf #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-ESF 125 V DC swgr 1ND3A 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) it is verified that the input power to the inverters normally feed from 1ND3A auto transfer to the alternate input power supply (no loss of essential 120 VAC power). 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.

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C 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 15 OF 33

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FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION 4

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PREPARED BY:T.PETRAK DATE:11/4 /94 Ri:NIEWED BY:M.GIBSON DATE:11/4 /94 APPROVED BY:R. DORMAN MANAGER TRAINING & EP DATE: 01/13/92 SIMULATOR PERFORMANCE 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 0 100%

severity one minute after the simulator is placed in run. The malfunction is removed when condenser vacuum reaches loin Hg Vac. The exercise is terminated after condenser vacuum reaches 20in Hg Vac.

fs The Vogtle simulator is initialized to 100% power, BOL, Equilibrium d Xe. A hotwell level transmitter LT-4415 failure (malf #142) inserted 0 10% severity one minute after the simulator is placed in is run. The malfunction is removed 9 minutes after the simulator has been placed in run. Condenser level is then verified to be returning to normal. The exercise is terminated 25 minutes after the simulator is placed 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.

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. FORM 05-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 16 OF 33 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION 4 l

PREPARED BY:T.PFTRAK DATE:11/4 /94 REVIEWED BY:M.GIBSON DATE:11/4 /94 APPROVED BY:R. DORMAN MANAGER TRAINING & EP DATE: 01/13/92 SIMULATOR PERFORMANCE TEST ABSTRACT 1

TITLE: Loss of Service Water (05-15) l The Vogtle simulator is initialized to 100% power, BOL, Equilibrium l Xe, standby NSCW pump in auto. An NSCW train B pump P-2 shaft break '

I (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" l position. The malfunction is removed. Pump P-2 is then manually i started. The exercise is teerminated after NSCW flow returns to

normal.

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O The Vogtle simulator is initialized to 100% power, BOL, Equilibrium l Xe, standby NSCW pump in auto. An NSCW train A pipe break to CCW Hx

  1. 1 (malf #192) is inserted one minute after the simulator is placed in run. The malfunction is removed after 6 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 ,

  1. 2 (malf #193) is inserted one minute after the simulator is placed I in run. The malfunction is removed after 6 additional minutes. The l exercise is terminated after NSCW pressure returns to normal. I i The simulator response is evaluated against best estimate judgement.

This testing was satisfactorily completed. Any discrepancies are ,

identified on Form 12-01, 1

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. FORM 05-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGF 17 OF 33 FORM' TITLE: PERFORMANCE TEST ABSTRACT REVISION 4 PREPARED BY:T.PETRAK DATE:11/4 /94 REVIEWED BY:M.GIBSON DATE:11/4/94 APPROVED BY:R. DORMAN MANAGER TRAINING & EP DATE: 01/13/92 l I

SIMULATOR PERFORMANCE TEST ABSTRACT  !

TITLE: Loss of Shutdown Coolinct (05-16) ,

The Vogtle simulator is initialized to 0% power, BOL, 330 Deg F, Mode

4. A RHR pump P-1 trip (malf RH01A) 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 P-1 is then manually started. The exercise is terminated after RHR '

flow returns to normal.

The simulator response is evaluated against best estimate judgement.

6 This testing was satisfactorily completed. Any discrepancies are identified on Form 12-01.  ;

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. IFORM 05-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 18 OF 33 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION 4 PREPARED BY:T.PETRAK DATE:11/4 /94 REVIEWED BY:M.GIBSON DATE:J1/4/94

' APPROVED BY:R. DORMAN MANAGER TRAINING & EP DATE: 01/13/92 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE: Loss of Component 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. The exercise is terminated after CCW flow stabilizes.

The Vogtle simulator is initialized to 0% power, BOL, Hot Shutdown, standby CCW pump in AUTO. A CCW train B discharge header pipe break (JMCCW1B) 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 Xe, 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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- FORM 05-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 19 OF 33 FC w ' TITLE: PERFORMANCE TEST ABSTRACT REVISION 4 PREPARED BY:T.PETRAK DATE:11/4 /94 REVIEWED BY:M.GIBSON DATE:11/4 /94 APPROVED BY:R. DORMAN MANAGER TRAINING & EP DATE: 01/13/92 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE: Loss of All Feedwater (05-18)

The Vogtle simulator is initialized to 100% power, EOL, Equilibrium Xe. A complete loss of all feedwater is initiated by inserting a trip of both main feedwater pumps (malf 146A & B) and a trip of all auxiliary feedwater pumps (malf 160A & B and 161) one minute after the simulator is placed in run. Malfunctions 160A & B are removed 35 minutes after the start of the run which is after the pressurizer PORVs have opened and when all SGs are emptied. AFWPs P-2 & 3 are p)

  • y, then started.

Close.

The exercise is terminated after the pressurizer PORVs 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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l FORM 05-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 20 OF 33

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U FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION 4 i

PREPARED BY:T.PETRAK DATE:11/4 /94 REVIEWED BY:M.GIBSON DATE:11/4 /94 i APPROVED BY:R. DORMAN , MANAGER TRAINING & EP DATE: 01/13/92 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE: Control Rod Failures (05-19)

The Vogtle simulator is initialized to 100% 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 rod retrieved using the appropriate plant procedure. The exercise is terminated after the rod is within 2 steps of its group.

The Vogtle simulator is initialized to 1E-8% power, BOL, 557 Deg F, RCcA bank D not fully inserted or withdrawn. A stuck RCCA H8 (malf

  1. 241) is inserted one minute after the simulator is placed in run.

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RCCA bank CD is withdrawn and then inserted 10 steps. The rod is verified to remain stationary. The lift coils for all rods except H8 in bank CD are opened. Again an attempt to withdraw / insert H8 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.

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FORM 05-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 21 OF 33 I FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION 4 PREPARED BY:T.PETRAK DATE:11/4 /94 REVIEWED BY:M.GIBSON DATE:11/4 /94 f DATE: 01/13/92 APPROVED BY:R. DORMAN MANAGER TRAINING & EP i

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SIMULATOR PERFORMANCE TEST ABSTRACT [

t TITLE: Inability to Drive Control Rods ,

(05-20)  !

i The Vogtle simulator is initialized to 50% power, BOL, Equilibrium Xe, rod control in Manual. A control banks fail to move on auto or manual  ;

demand (malf RD08) is inserted. The rods are verified unmovable in Manual. Rod control is shifted to Auto. This is followed by  ;

adjusting turbine load 110%. Af ter the rods are verified stationary, ,

the reactor is tripped. The exercise is terminated after all the rods  !

are verified on the bottom.  !

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

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. FORM 05-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 22 OF 33 ,

d,. FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION 4 PREPARED BY:T.PETRAK DATE:11/4 /94 REVIEWED BY:M.GIBSON DATE:11/4 /94 ;

APPROVED BY:R. DORMAN MANAGER TRAINING & EP DATE: 01/13/92 i SIMULATOR PERFORMANCE TEST ABSTRACT i TITLE: Fuel Claddino Failure (05-21)

The Vogtle simulator is initialized to 50% power, BOL, Equilibrium Xe.

A #2 SG tube rupture (malf #86) is inserted @ 1% severity one minute after the simulator is placed in run. This is followed by inserting a fuel failure (malf 60B) @ 50% severity 4 minutes after the simulator is placed in run. The exercise is terminated after radiation levels are verified.

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 23 OF 33

.( FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION 4 PREPARED BY:T.PETRAK DATE:11/4 /94 REVIEWED BY:M.GIBSON DATE:11/4 /94 APPROVED BY:R. DORMAN MANAGER TRAINING & EP DATE: 01/13/92 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE: Generator Trio (05-22)

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 at 6 minutes after the start of the run which is after. LOR 386-G9 is reset.

The simulator response is evaluated against best estimate judgement O 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 24 OF 33

! FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION 4 PREPARED BY:T.PETRAK DATE:11/4 /94 REVIEWED BY:M.GIBSON DATE:11/4 /94 APPROVED BY:R. DORMAN MANAGER TRAINING & EP DATE: 01/13/92 SIMULATOR PERFORMANCE TEST PSTRACT TITLE: Failure in Auto Control Svs That Affect Reactivity & Core Heat Removal (05-23)

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 signals can be resat after the block / reset time delay has timed out. The exercise is terminated after the SI signals are rest.

The Vogtle simulator is initialized to 100% power, MOL, Equilibrium N Xe, control rods in AUTO, one BATP running. A RCS boration (malf #82)

(d 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.

.' ' FORM 05-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 25 OF 33 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION 4 i

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PREPARED BY:T.PETRAK DATE:11/4 /94 REVIEWED BY:M.GIBSON DATE:11/4 /94 APPROVED BY:R. DORMAN MANAGER TRAINING & EP DATE: 01/13/92 ,

SIMULATOR PERFORMANCE TEST ABSTRACT TITLE: Failure in Reactor Coolant Pressure and, Volume Control System (05-24)

The Vogtle simulator is initialized to 100% power, BOL, Equilibrium Xe. A pressurizer pressure transmitter PT-455 failure (malf PR02A) .

is inserted 0 100% severity one minute after the simulator is placed l in run. The malfunction is removed after 6 additional minutes. The '

exercise is terminated after 10 minutes.

i The Vogtle simulator is initialized to 100% power, BOL, Equilibrium O Xe. A pressurizer pressure transmitter PT-459 failure (malf PR03A) is inserted 0 0% severity one minute after the simulator is placed in run. The malfunction is removed after 6 additional minutes. The exercise is terminated after 10 minutes.

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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i I' FORM 05-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGF N OF 33 l FORM TITLE: PERFORMANCE TEST ABSTRACT REV.. J.4-PREPARED BY:T.PETRAK DATE:11/4 /94 REVIEWED BY:M.GIBSON DATE:11/4 /94 '

APPROVED BY:R. DORMAN MANAGER TRAINING & EP DATE: 91/13/92 SIMULATOR PERFORMANCE TEST ABSTRACT '

i TITLE: Main Steam Line Break Outside Containment (05-25) l The Vogtle simulator is initializesd to 48% power, BOL, Equilibrium Xe. l A main steam safety valve PSV-300A leak (malf #94A) is inserted 0100%

severity one minute after the simulator is placed in run. The exercise is terminated 6 minutes after the simulator is placed in run. ,

The Vogtle simulator is initialized to 48% power, BOL, Equilibrium Xe.

A main steam bypass valve header rupture (malf #92) is inserted @ 100%

  • O severity one minute after the simulator is placed in - run.

exercise is terminated 11 minutes after the simulator is placed in The run.

i 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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. I FORM 05-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 27 OF 33 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION 4 l PREPARED BY:T.PETRAK DATE:11/4 /94 REVIEWED BY:M.GIBSON DATE:,11/4 /94 APPROVED BY:R. DORMAN MANAGER TRAINING & EP DATE: 01/13/92 l

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SIMULATOR PERFORMANCE TEST ABSTRACT TITLE: Main Feedwater Line Break Inside Containment (05-26)

The Vogtle simulator is initialized to 100% power, EOL, Equilibrium Xe. A feedwater line #2 rupture inside containment (malf #153) is inserted 0 50% severity one minute after the simulator is placed in run. The exercise is terminated 10 minutes after the simulator is placed 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.

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  • -FORM 05-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 28 OF 33 FORM TITLE:' PERFORMANCE TEST ABSTRACT REVISION 4 PREPARED BY;T.PETRAE DATE:11/4 /94 REVIEWED BY:M.GIBSON DATE:11/4 /94 APPROVED BY:R. DORMAN MANAGER TRAINING & EP DATE: 01/13/92 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE: Main Feed Line Break Outside Containment (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 10 minutes after the simulator is placed 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.

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. FORM 05-02 VOGTLE SIMULATOR CERTIFICATlON PLAN PAGE 29 OF 33

() FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION 4 PREPARED BY:T.PETRAK DATE:11/4 /94 REVIEWED BY:M.GIBSON DATE:11/4 /94 APPROVED BY:R. DORMAN MANAGER TRAINING & EP DATE: 01/13/92 i

SIMULATOR PERFORMANCE TEST ABSTRACT TITLE: Nuclear Instrument Failures (05-28)

The Vogtle simulator is initialized to 100% power, BOL, Equilibrium '

Xe. Power range chan 42 upper detector failure (malf NIO7B) is inserted 0 50% severity one minute after the simulator is placed in run. Four 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.

O V The Vogtle simulator is initialized to 100% powcr, BOL, Equilibrium Xe. Power range chan 44 high voltage failure (malf NIO8D) is inserted

@ 30% severity one minute after the simulator is placed in run. Four 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 NIllA) is inserted @ 25%

severity one minute after the simulator is placed in run. Four 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.

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' FORM 05-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 30 OF 33 arv1S10N4

_O roaa 11rtz: rzaroaxiuct rest ^8sra^ce PREPARED BY:T.PETRAK DATE:11/4 /94 REVIEWED BY:M.GIBSON DATE:11/4 /94 APPROVED BY:R. DORMAN MANAGER TRAINING & EP DATE: 01/13/92 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE: Process Instrument Failures (05-29)

The Vogtle simulator is initialized to 0% power, BOL, cold shutdown, 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 5 minutes after the simulator is placed in run.

The exercise is terminated 5 minutes after malfunction removal.

The Vogtle simulator is initialized to 100% power, BOL, Equilibrium

.O' Xe. A hot leg RTD TE-411A failure (malf #40A) is inserted 0 0%

severity one minute after the simulator is 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 @ 90%

severity one minute after the simulator is placed in run. After 2 additional minutes, the malfunction is removed. The exercise is terminated 1 minute after malfunction removal.

The Vogtle 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 terminated 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 malfunction is removed. The exercise is terminated 1 minute after malfunction removal.

  • FORM 05-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 31 OF 33 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION 4 PREPARED BY:T.PETRAK DATE:11/4 /94 REVIEWED BY:M.GIBSON DATE:11/4 /94 APPROVED BY:R. DORMAN MANAGER TRAINING & EP DATE: 01/13/92 SIMULATOR PERFORMANCE TEST ABSTRACT 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 0 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 malfunction removal.

The Vogtle simulator is initialized to 100% power, BOL, Equilibrium Xe, control rods in AUTO. A main turbine impulse pressure transmitter p PT-505 failure (malf #62A) is inserted 010% severity one minute after

\_/ the simulator is placed in run. The malfunction severity is increased to 85% after 2 additional minutes. Five minutes after the simulator is placed in run, the malfunction is removed. The exercise is terminated 1 minute after malfunction removal.

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 32 OF 33 FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION 4 PREPARED BY:T.PETRAK DATE:11/4 /94 REVIEWED BY:M.GIBSON DATE:11/4 /94 APPROVED BY:R. DORMAN MANAGER TRAINING & EP DATE: 01/13/92 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) is inserted. A main steam line #3 rupture inside containment (malf #91) is inserted at 100% severity one minute after the simulator is placed in run. After 3 additional minutes the train A MSIV handswitch is placed to close. The exercise is terminated 6 minutes after the simulator is placed in run.

V The Vogtle simulatc)r is initialized to 100% power, EOL, Equilibrium Xe. A train A cocrtainment spray automatic actuation failure (malf

  1. 166) is inserted. A RCS loop 3 cold leg rupture (naalf #35) is inserted one minute after the simulator is placed in run. After 3 additional minutes the containment spray pump #1 handswitch is placed to start. Five 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. 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.

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FORM 05-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 33 OF 33 h FORM TITLE: PERFORMANCE TEST ABSTRACT REVISION 4 PREPARED BY:T.PETRAK DATE:11/4 /94 REVIEWED BY:M.GIBSON DATE:11/4 /94 APPROVED BY:R. DORMAN MANAGER TRAINING & EP DATE: 91/13/92 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

  1. 12) is inserted. A main turbine trip (malf #98) is inserted one minute after the simulator is placed in run. After 11 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 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: 06-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 1 OF 11 hMTITLE: PERFORMANCE TEST ABSTRACT REVISION 4 PREPARED BY:T.Petrak DATE: 11/04/94 REVIEWED BY:M. Gibson DATE:11/04/94 APPROVED BY: R. Dorman MANAGER TRAINING & EP DATE:01/04/95 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE : Plant Startuo to Hot Standby (06-01)

The Vogtle simulator is initialized to 0% power, BOL, < 140 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),

starting the reactor coolant pumps, forming a bubble in the pressurizer, warmup of the secondary side, forming a condenser vacuum, maintaining steam generator levels with auxiliary feedwater, and A performing boron dilution. The exercise is terminated when the plant U 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.

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  • FORM: 06-02 VOGTLE: SIMULATOR CERTIFICATION PLAN PAGE 2 OF 11 J4 TITLE: PERFORMANCE TEST ABSTRACT REVISION 4 PREPARED BY:T.Petrak DATE: 11/04/94 REVIEWED BY:M. Gibson DATE:11/04/94 APPROVED BY: R. Dorman MANAGER TRAINING & EP DATE:01/04/95 ,

SIMULATOR PERFORMANCE TEST ABSTRACT j j

TITLE : Nuclear Startuo from Hot Standby to Rated Power (06-02) l j

The Vogtle simulator is initialized to 0% power, BOL, 557 Deg F. A nuclear startup is performed from Hot Standby to rated power. The exercise is conducted using controlled copies of the Vogtle plant j procedures. If a step is performed and the response of the simulator does not meet the startup tost criteria, or if a step can not be performed, or if an alarm annunciates but shouldn't or doesn't i annunciate but should, then a discrepancy report is written. J This scenario includes conducting a 1/M plot during rod withdrawal, l transferring steam generator level control from the auxiliary-feedwater system to the main feedwater system, rolling the_ turbine up to speed, synchronizing the main generator to the grid, and performing O 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 not available.

This testing was satisfactorily completed. Any discrepancies are identified on Form 12-01.

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  • 5'ORM: 06-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 3 OF 11

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<M TITLE: PERFORMANCE TEST ABSTRACT REVISION 4 PREPARED BY:T.Petrak DATE: 11/04/94 REVIEWED BY:M. Gibson DATE:11/04/94 APPROVED BY: R. Dorman MANAGER TRAINING & EP DATE:01/04/95 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 minute. The plant is allowed to stabilize for 5 minutes. This is 7s followed by a load increase of 10% at a rate of 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.

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' FORM: 06-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 4 OF 11 di TITLE: PERFORMANCE TEST ABSTRACT REVISION 4 PREPARED BY:T.Petrak DATE: 11/04/94 REVIEWED BY:M. Gibson DATE:11/04/94 APPROVED BY: R. Dorman MANAGER TRAINING & EP DATE:OlfC4/95 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 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 power descent to 1-3% 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 n exercise is terminated when the plant is stable at Hot Standby. )

U 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: 06-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 5 OF 11 I but TITLE: PERFORMANCE TEST ABSTRACT REVISION 4 PREPARED BY:T.Petrak DATE: 11/04/94 REVIEWED BY:M. Gibson DATE:11/04/94 APPROVED BY: R. Dorman MANAGER TRAINING & EP DATE:01/04/95 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE : Cooldown to Cold Shutdown Conditions (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 commencino a plant shutdown to < 140 Deg F, verifying an adequate shutdown margin exists, boraLing the RCS, l securing the reactor coolant pumps, going on shutdown cooling, and .

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.

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  • FORM: 06-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 6 OF 11 34 TITLE: PERFORMANCE TEST ABSTRACT REVISION 4 .;

PREPARED BY:T.Petrak DATE: 11/04/94- REVIEWED BY:M. Gibson DATE:11/04/94 *

' APPROVED BY: R. Dorman MANAGER TRAINING & EP DATE:01/04/95 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE : Reactor Trio With Recovery to Rated Power (06-06)  ;

i 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 performed, or if an alarm ar.nunciates but shouldn't or doesn't 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, utilizing " Fast Time" to accelerate the Xe concentration at 60Xs normal for 20 minutes (equates to 20 Hrs real time), and commencing O a power ascension to 100%. The exercise is terninated when the plant is stable at 100% power.

l 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: 06-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 7 OF 11

,R TITLE: PERFORMANCE TEST ABSTRACT REVISION 4 PREPARED BY:T.Petrak DATE: 11/04/94 REVIEWED BY:M. Gibson DATE:11/04/94 APPROVED BY: R. Dorman MANAGER TRAINING & EP DATE:01/04/95 i

SIMULATOR PERFORMANCE TEST ABSTRACT TITLE : Core Performance Tests (06-07)

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The following tests makeup the Core Performance Test: '

Critical Boron Concentration & 100% Power Delta I Rod Worth Measurement  !

Shutdown Bank B Worth Measurement /Most Reactive Rod Overlap Rod Worth Measurement ,

ITC Measurement Differential Boron Worth Measurement HFP EQ Xenon Worth Measurement  !

HFP EQ Samarium Measurement .

Transient Xe and Sm Following Rx Trip from 100% Power 50% EQ Xe Worth Measurement '

50% EQ Sm Worth Measurement O Transient Xe and Sm Following Rx Trip form 50% Power Reactor Kinetic Response Power Defect Measurement For certification, tr.e test results are compared to the acceptance criteria outlined f.n the procedure. The criteria is based on the Unit 1, Cycle 5 NDR. If th'a simulator response does not meet the acceptance criteria, a discrepancy report is written.

This testing was satisfactorily completed. Any discrepancies are identified on Form 12-01.

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FORM: 06-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 8 OF 11

M: TITLE: PERFORMANCE TEST ABSTRACT REVISION 4 PREPARED BY:T.Petrak DATE: 11/04/94 REVIEWED BY:M. Gibson DATE:11/04/94 APPROVED BY: R. Dorman MANAGER TRAINING & EP DATE:01/04/95 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE : Surveillance Testina on Safety Eauioment or Systems (06-08)

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.

The Vogtle simulator is initialized to conditions required to perform each of the following surveillance tests:

1) 14980-1 DG operability test
2) 14423-1 Source range NIS channel operability test
3) 14424-1 Intermediate range NIS analog channel operability hd; rw 4) 14425-1 Power range quarterly analog channel operational test

(,,) 5) 14510-1 Control room emergency filtration system operability test

6) 14490-1 Containment cooling system operability test
7) 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
10) 14805-1 Residual heat removal pump and check valve 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.

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  • h'ORM: 06-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 9 OF 11 h TITLE: PERFORMANCE TEST ABSTRACT REVISION 4 PREPARED BY:T.Petrak DATE: 11/04/94 REVIEWED BY:M. Gibson DATE:11/04/94 APPROVED BY: R. Dorman MANAGER TRAINING & EP DATE:01/04/95 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE : Steady State Test 0 35% Power ,

(06-09)

The Vogtle simulator is initialized to 35% 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 precedures. If a step is performed and the '

response of the simulator does net 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. i 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.

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  • FORM: 06-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 10 OF 11

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l M TITLE: PERFORMANCE TEST ABSTRACT REVISION 4 PREPARED BY:T.Petrak DATE: 11/04/94 REVIEWED BY:M. Gibson DATE:11/04/94 APPROVED BY: R. Dormam MANAGER TRAINING & EP DATE:01/04/95 SIMULATOR PERFORMANCE TEST ABSTRACT l

TITLE : Steady State Test 0 75% Power l (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 after the simulator i 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.

This testing was satisfactorily completed. Any discrepancies are identified on Form 12-01.

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  • h'ORM: 06-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 11 OF 11

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34 TITLE: PERFORMANCE TEST ABSTRACT REVISION 4 PREPARED BY:T.Petrak DATE: 11/04/94 kEVIEWED BY:M. Gibson DATE:11/04/94 APPROVED BY: R. Dorman MANAGER TRAINING & EP DATE:01/04/95 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE : Steady State Test 9 100% Power (06-11) 1 The Vogtle simulator is initialized to 100% power, BOL, Equilibrium Xe. The siculator is placed in run and allowed to operate for 60 minutes. A h, at balance calculation is performed 10 minutes after the

. i simulator is placed in run. The calorimetric is conducted using l controlled copies of the Vogtle plant procedures. If a step is l 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 cluated against the acceptance criteria specified in the plant pro; :tres and in Section 4.1, Steady State O

Operation, of ANSI /ANS-3.5-1985.

This testing was satisfactorily completed. Any discrepancies are identified on Form 12-01.

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  • FORM: 07-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 1 OF 10 m

_ 2 TITLE: PERFORMANCE TEST ABSTRACT REVISION 5 PREPARED BY: T.Petrak DATE: 11/04/11 REVIEWED BY: M. GIBSON DATE:11/04 /94 APPROVED BY: R. Dorman MANAGER TRAINING & EP DATE: 01/04/95 ,

i SIMULATOR PERFORMANCE TEST ABSTRACT TITLE : Manual Reactor Trio (07-01)

The Vogtle simulator is initialized to 100% power,BOL, Equilibrium Xe. 1 A manual reactor trip is performed one minute after the simulator is placed in run. The simulator is allowed to run with no operator actions except to control RCS temperature at no-load Tavg by throttling Auxiliary Fecdwater Flow and by tripping both Main Feedwater Pumps. The exercise in 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. t This testing was satisfactorily completed. Any discrepancies are idsntified on Form 12-01.

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l FORM: 07-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 2 OF id M TITLE: PERFORMANCE TEST ABSTRACT REVISION 5 1 l

l PREPARED BY: T.Petrak DATE: 11/04/94 REVIEWED BY: M. GIBSON DATE:11/04 /94 l APPROVED BY: R. Dorman MANAGER TRAINING & EP DATE: 01/04/95 l SIMULATOR PERFORMANCE TEST ABSTRACT l'

TITLE : Simultaneous Trio of All Feedwater Pumos (07-02)

Th3 Vogtle simulator is initialized to 100% power,BOL, Equilibrium Xe.

A trip of both turbine driven Main Feedwater pumps (malfunctions FWO1A and FWO1B) is inserted one minute after the simulator is placed in run. The opsrator shall only perform the following actions:

o Reduce TDAFW flow to minimum after AFW pumps start o Modulate the motor driven auxiliary feedwater pump throttle ,

valves to establish 200 gpm per SG The exercise is terminated 11 minutes after the simulator is place in run.

The simulatur response is evaluated against best estimate judgement where

~}gtleplantdataisnotavailable.

i This testing was satisfactorily completed. Any discrepancies are identified on Form 12-01.

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  • FORM: 07-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 3 OF 10

_, M TITLE: PERFORMANCE TEST ABSTRACT REVISION 5 PREPARED BY: T.Petrak JATE: 11/04/94 REVIEWED BY: M. GIBSON DATE:11/04 /94 APPROVED BY: R. Dorman MANAGER TRAINING & EP DATE: 01/04/95 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 MS10A, B, C & D) is inserted one minute after the simulator lo 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 establish 200 gpm per SG The exercise is terminated 11 minutes after the simulator is placed in run.

('}e simulator response is evaluated against best estimate judgement where Lagtle plant data is not available.

This testing was satisfactorily completed. Any discrepancies are idantified on Form 12-01.

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' FORM: 07-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 4 OF 10 1

_ M TITLE: PERFORMANCE TEST ABSTRACT REVISION 5 PREPARED BY: T.Petrak DATE: 11/04/94 REVIEWED BY: M. GIBSON DATE:11/04 /94 APPROVED BY: R. Dorman MANAGER TRAINING & EP DATE: 01/04/95 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE : Simultaneous Trio of All Reactor Coolant Pumos (07-04)

Tha Vogtle simulator is initialized to 100% power,EOL, Equilibrium Xe.

A simultaneous trip of all reactor coolant pumps malfunction (malfunctions ELO6A & ELO6B, Loss of NAA and NAB) 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 establish 200 gpm per SG The exercise is terminated 16 minutes after the simulator is placed in run.

o 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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'h'ORM: 07-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 5 OF 10 h8MTITLE: PERFORMANCE TEST ABSTRACT REVISION 5 PREPARED BY: T.Petrak DATE: 11/04/94 REVIEWED BY: M. GIBSON DATE:ll /04 /94 APPROVED BY: R. Dorman MANAGER TRAINING & EP DATE: 01/04/95 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE : Sinale Reactor Coolant Pumn Trio (07-05)

Tha 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 RP01) is incerted one minute after the simulator is placed in run. The simulator 10 allowen to run with NO OPERATOR ACTION for the remainder of the exercise.

The exercise is terminated 6 minutes after the simulator is placed in run.

Tha simulator response is evaluated against best estimate judgement where Vogtle plant data is not available.

This testing was satisfactorily completed. Any discrepancies are r^',cntified on Form 12-01.

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  • FORM: 07-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 6 OF 10 JI TITLE: PERFORMANCE TEST ABSTMACT REVISION 5 PREPARED BY: T.Petrak DATE: 11/04/94 REVIEWED BY: M. GIBSON DATE:11/04 /94 i APPROVED BY: R. Dorman MANAGER TRAINING & EP DATE: 01/04/95 I

SIMULATOR PERFORMANCE TEST ABSTRACT 1

TITLE : Main Turbine Trio w/o a Reactor Trio (07-06) i The Vogtle simulator is initialized to 30% power,MOL, Equilibrium Xe. A l main turbine trip w/o a reactor trip malfunction- (malfunction TUO1)- 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.

i Tha 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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  • h'ORM: 07-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 7 OF 10
M TITLE
PERFORMANCE TEST ABSTRACT REVISION 5 PREPARED BY: T.Petrak DATE: 11/04/94 REVIEWED BY: M. GIBSON DATE:11/04 /94 LAPPROVED BY: R. Dorman MANAGER TRAINING & EP DATE: 01/04/95 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE : Maximum Rate Power Ramo (100% to 75%.

Back to 100%) (07-07)

Th3 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 oparator shall manually reduce turbine load to approximately 75% (900 MW) over a 5 minute period. Five minutes after the load reduction, the operator shall raise turbine load to 100% (1200 MW) over a 5 minute period. ,

i The exercise is terminated 5 minutes after reaching 100% power.

The simulator response is evaluated against best estimate judgement where Vogtle plant data is not available.

is testing was satisfactorily completed. Any discrepancies are OentifiedonForm12-01.

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  • h0RM: 07-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 8 OF 10 hRMTITLE: PERFORMANCE TEST ABSTRACT REVISION 5 PREPARED BY: T.Petrak DATE: 11/04/94 REVIEWED BY: M. GIBSON DATE:11/04 /94 APPROVED BY: R. Dorman MANAGER TRAINING & EP DATE: 01/04L155 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE : LOCA with Loss of Offsite Power (07-08)

Ths Vogtle simulator is initialized to 100% power, EOL, Equilibrium Xe.

A LOCA with a loss of offsite power is initiated by insertion of the following malfunctions:

o RCO3C (RCS Loop 3 Cold Leg Rupture) o ELO2 & ELO3 (loss of reserve auxiliary transformers 1NXRA/B) o ELO4 & ELO5 (loss of unit auxiliary transformers 1NXAA/B)

Tha simulator is placed in run and allowed to operate with NO OPERATOR ACTION for 20 minutes. The operator then places the ECCS in the recirculation mode. The exercise is terminated 25 minutes after the simulator is placed in run or 2 minutes after recirc flow is established (whichever is later).

Il Cao simulator response is evaluated against best estimate judgement where Vogtle plant data is not available.

This testing was satisfactorily completed. Any discrepancies are idantified on Form 12-01.

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FORM: 07-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 9 OF 10

7M TITLE: PERFORMANCE TEST ABSTRACT REVISION 5 PREPARED BY: T.Petrak DATE: 11/04/94 REVIEWED BY: M. GIBSON DATE:11/04 /94 APPROVED BY: R. Dorman MANAGER TRAINING & EP DATE: 01/04/95 SIMbuATOR PERFORMANCE TEST ABSTRACT TITLE : Unisolable Main Steam Line Ruoture Inside Containment (07-09)

Tha Vogtle simulater is initialized to 10E-8 amps, EOL, Hot Zero Power.

A cteam line rupture inside containment (malfunction MSO4C) is inserted ct 100% severity one minute after the simulator is placed in run. The simulator is allowed to run with no operator action other than to isolate the faulted SG and to isolate all Auxiliary Feedwater to the intact SG's efter the ruptured SG drys out. The exercise is terminated 10 minutes after the simulator is placed 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.

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' FORM: 07-02 VOGTLE SIMULATOR CERTIFICATION PLAN I PAGE 10 OF 10 1 1

dM TITLE: PERFORMANCE TEST ABSTRACT REVISION 5 l

PREPARED BY: T.Petrak DATE: 11/04/94 REVIEWED BY: M. GIBSON DATE:11/04/94 APPROVED BY: R. Dorman MANAGER TRAINING & EP DATE: 01/04/95 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE : Slow Primary Svs Depressurization to Sat Cond w/ Stuck SV (07-10)

The Vogtle simulator is initialized to 100% power, EOL, Equilibrium Xe.

A pressurizer safety valve, PSV-8010A leakage (PR01A) is inserted at 20%

esverity along with SI Channel A&B failures (malf's ES08 and ES16) one minute after the simulator is placed in run. These malfunctions establish c elow depressurization of the RCS to saturation. The operator shall only parform the following actions:

o Throttle AFW flow to 200 gpm per SG o Trip both Main Feedwater Pumps The exercise is terminated 40 minutes after the simulator is placed in run.

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C3o 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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RM: 08-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 1 OF 3 TITLE: PERFORMANCE TEST ABSTRACT REVISION 1 PREPARED BY: P. Rubin DATE: 9/20/90 REVIEWED BY: M. Gibson DATE: 11/04/94 APPROVED BY: R. Dorman MANAGER TRAINING & EP DATE: 01/04/95 SIMULATOR PERFORMANCE TEST ABSTRACT TITLE : Computer Real Time Test (08-01)

The Computer Real Time Test consists of 3 tests.

In the first test the simulator is initialized to any full power initial condition (IC) and placed in run. The simulator is allowed to run for 30 minutes at steady state conditions. During the 30 minutes, the minimum epare time of the CPU and the IPU are recorded. If either of the spare times show 12ss than adequate spare time a discrepancy report is ganerated.

In the second test three malfunctions are selected which will exercise the mejor models of the simulator (i.e. , LOCA, Reactor Trip and MSIV Closure) .

(~7r each malfunction, the simulator is initialized to the IC used in the (2rst test and placed in run. The simulator is allowed to run for 10 minutes with the malfunction active. During the 10 minutes, the minimum spare time of the CPU and the IPU are recorded. If either of the spare times show less than adequate spare time, a discrepancy report is generated.

In the third tect 5 valves are selected for valve stroking. The valves selected are from dif ferent 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 t 2%, a discrepancy report is generated.

This testing was satisfactorily completed. Any discrepancies are identified on Form 12-01.

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F RM: 08-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 2 OF 3 TITLE: PERFORMANCE TEST ABSTRACT RENISION 1 PREPARED BY: P. Rubin DATE: 9/20/90 REVIEWED BY: M. Gibson DATE: 11/04/94 APPROVED BY: R. Dorman MANAGER TRAINING & EP OATE: 01/04/95

==

SIMULATOR PERFORMANCE TEST ABSTRACT TITLE : Simulator Limits Exceeded (08-02)

Th3 " 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 simulaued conditions are outside the bounds imposed by modeling assumptions. (for example, gross voiding of the RCS)
2) The simulated conditions are outside the design limits of plant equipment (for exa.nple , the containment pressure exceeds the design limit).

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( ;mulator instructors monitor the " Simulator Limits Exceeded" light to see if their scenario has exceeded these limits. If the light is illuminated, the instructor addresses whether the training is being impacted by the simulation 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 Preasure > 66.7 psia RCS Pressure > 2700 psia Core Voiding > 100%

Fuel Temperature > 4000 Degf l

l To test the limits requires the simulator models to be frozen because the I limits are intentionally set at values that the simulation can not normally achieve.

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RM: 08-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 3 OF 3 MTLE: PERFORMANCE TEST ABSTRACT REVISION 1 PREPARED BY: P. Rubin DATE: 9/20/90 REVIEWED BY: M. Gibson DATE: 11/04/94 APPROVED BY: R. Dorman MANAGER TRAINING & EP DATE: 01/04/95 SIMULATOR PERFORMANCE TEST AB TXACT TITLE : Simulator Limits Exceeded (08-02)

.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 create an out of limits input and then set to clear the alarm.

The " Simulator Limits Exceeded" light performed as required.

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' FORM: 12-02A VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 1 OF 4 lhhMTITLE: SIMULATOR PERFORMANCE TEST DATES REVISION 1 PERFORMED BY: T.Petrak DATE: 01/03/94 REVIEWED BY: M.Gibson DATE: 01/03/94 APPROVED BY: R. Dorman MANAGER TRAINING & EP DEE: 01/04/95 The first year's tests were completed on the following dates:

Certification Test Procedure Tested Date 5-01 5/19/91 5-05 3/24/91 5-09A 6/06/91 5-09B 6/06/91 5-13A 11/13/91 5-13B 11/13/91 5-13C 11/13/91 5-13D 11/13/91 5-17A 8/17/91 5-17B 8/17/91 5-17C 8/17/91 (N 5-21 5/19/91

(-) 5-25A 5/19/91 5-25B 5/19/91 5-29A 3/24/91 5-29B 3/24/91 5-29C 3/24/91 j 5-29D 3/24/91 5-29E 3/24/91 5-29F 5/19/91 5-29G 3/24/91 6-01 7/12/91 6-05 6/09/91 6-09 5/19/91 6-10 5/31/91 6-11 5/19/91 7-01 5/19/91 7-02 5/19/91 7-03 5/31/91 1 7-04 5/31/91 l 7-05 5/31/91 7-06 5/31/91 7-07 5/31/91 7-08 5/31/91 7-09 5/31/91 7-10 5/31/91 8-2 8/17/91 LJ l

' FORM: 12-02A VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 2 OF 4

i4 TITLE
SIMULATOR PERFORMANCE TEST DATES REVISION 1 PERFORMED BY: T.Petrak DATE: R1193/94 REVIEWED BY: M.Gibson DATE: 01/03/91 APPROVED BY: R. Dorman MANAGER TRAINING & EP DEm: OJ/04/95 The second year's tests were completed on the following dates:

Certification Test Procedure Tested Date 5-02 03/12/92 5-06A 03/12/92 5-06B 03/12/92 5-10 03/12/92 5-14A 03/12/92 5-14B 03/12/92' 5-18 12/01/92 5-22 03/16/92 5-26 03/16/92 5-30A 11/29/92 5-30B 03/16/92 5-30C 03/16/92

( 6-02 02/26/92

  • 6-06 02/27/92 6-09 03/19/92 6-10 08/29/92 6-11 03/31/92 '

7-01 03/03/92 7-02 03/03/92 7-03 03/03/92 7-04 03/03/92 7-05 03/06/92 7-06 03/16/92 7-07 03/03/92 7-08 03/16/92 7-09 03/16/92 7-10 03/16/92 8-2 04/10/92 O

' FORM: 12-02A VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 3 OF 4 M TITLE: SIMULATOR PERFORMANCE TEST DATES REVISION 1 PERFORMED' BY : T.Petrak DATE: 01/03/94 REVIEWED BY: M.Gibson DATE: 01/03/94 APPROVED BY: R. Dorman MANAGER TRAINING & EP DATE: 01/04/95 The third year's tests were completed on the following dates:

Certification Test Procedure Tested Date 5-03 03/18/93 5-07 03/18/93 5-11A 03/19/93 5-11B 03/19/93 5-11C 03/19/93 5-11D 03/19/93 5-11E- 03/19/93 5-11F 03/19/93 5-15A 03/18/93 5-15B 03/18/93 5-15C 03/18/93 5-19A 03/18/93

/~N 5-19B 03/18/93 5

5-23A 03/18/93 5-23B 03/19/93 5-27 03/19/93 5-31 03/19/93 6-03 03/15/93 6-07 08/09/93 6-09 03/15/93 6-10 04/10/93 6-11 04/01/93 7-01 04/10/93 7-02 03/16/93 7-03 03/16/93 7-04 03/18/93 7-05 03/19/93 7-06 03/16/93 7-07 03/19/93 7-08 03/19/93 7-09 03/19/93 7-10 03/19/93 8-2 12/15/93 O

' FORM: 12-02A VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 4 OF 4 m

_ di TITLE: SIMULATOR PERFORMANCE TEST DATES REVISION 1 PERFORMED BY: I.Petrak DATE: 01/03/94 REVIEWED BY: M.Gibson DATE: 01/03/94 APPROVED BY: R. Dorman MANAGER TRAINING & EP DATE: 01/04/95 The fourth year's tests were completed on the following dates:

Certification Test Procedure Tested Date 5-04 11/03/94 5-08 11/03/94 5-12A 09/22/94 5-12B 09/26/94 5-16 09/23/94 5-20 09/23/94 5-24 09/23/94 5-28 09/23/94 6-04 09/23/94 6-09 11/03/94 6-10 12/05/94 6-11 12/05/94

("N 7-01 09/02/94

( ># 7-02 09/20/94 7-03 09/20/94 7-04 09/20/94 7-05 09/20/94 7-06 01/02/95 7-07 09/20/94 7-08 09/21/94 7-09 09/20/94 7-10 09/20/94 8-2 11/04/94

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' FORM: 12-01 VOLE SIMULATOR CERTIFICATION PLAN PAGE 1 OF 10 m

M TITLE: DISCREPANC:, RESOLUTION WORKSHEET REVISION 4 PERFORMED BY:T. PETRAK DATE: 01/03/94 REVIEWED BY:M. GIBSON DATE: 01/03/94 APPROVED BY: R. DORMAN MANAGER TRAINING & EP DATE: 01/04/95 Form 12-01's are available for each individual year's testing at the time of the tests. A review of these forms shows that there are no discrepancies that remain open that would impact the training or examination process. The open discrepancies are minor in nature such that the student would not see them or they would not impact his actions. Enclosed is a  ;

consolidatation of the discrepancies that are still open.

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i FORM: 12-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 2 OF 10 m

34 TITLE: DISCREPANCY RESOLUTION'WORKSHEET REVISION 4 PERFORMED BY:T. PETRAK DATE: 01/03/94 REVIEWED BY:M. GIBSON DATE: 01/03/94 i

APPROVED BY: R. DORMAN MANAGER TRAINING & EP DATE: 01/04/95 ,

.Parformance Test Procedures: 05-04,05-08.05-23A,05-24A Interval: Malfunction to Trarmination DR Number: 1 (9304013) o comparison Comparison Parameter Measure Value SG NR & WR LVL NA Table Top .

Problem

Description:

Cause:

dare is an oscillation in the SG Model problem.

NR & WR level immediately following a reactor trip.

Corrective Action: Impact if not Corrected:

Correct model. Minor impact. Overall trend is correct and the oscillations are damped. They only last for a few seconds and probably would not be seen by the student.

1 RanolutIO':n Results:

l DR 9304013 was written. DR is open. j O

FORM: 12-01 VOGTLE SIMULATOR CERTIFItt, TION PLAN PAGE 3 OF 10

_ -;M TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION 4 PERFORMED BY:T2_2fTRAK DATE: 01/03/94 REVIEWED BY:M. GIBSON DATE: 01/03/94 APPROVED BY: R. DOR'iAN. MANAGER TRAINING & EP DATE: 01/04/95 l

-Performance Test Procedures: 05-04 Interval: Malfunction to Termination DR Number: 2 (9501001)

Comparison Comparison

  • Parameter Measure Value SG Pressure NA Table Top Problem

Description:

Cause:

( cd to evaluate SG2 vs SG3 Model problem.

pressure response looking at steam flows Corrective Action: Impact if not Corrected:

Correct model. Minor impact. Overall trend is correct but the values were questioned during the analysis.

Will review to determine if there is a problem.

Rscolution: Results:

DR 9501001 was opened. DR is open. l O

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4 FORM: 12-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 4 OF 10 I IRM TITLE: DISCREPANC't RESOLUTION WORKSHEET REVISION 4 PERFORMED BY:T. PETRAK DATE: 01/03/94 REVIEWED BY:M, GIPSON DATE: 01/03/94 APPROVED BY: R. DORMAN MANAGER TRAININC & EP DATE: 01/04/95 Parformance Test Procedures: 05-04 Interval: Malfunction to Termination DR Number: 4 (9501002)

Comparison Comparison Parameter Measure Value Containment Pressure NA Table Top Problem

Description:

Cause:

,nao response of containment Model problem.

pressure vs containment spray actuation was questioned during the testing analysis.

Corrective Action: Impact if not Corrected:

Correct model. Minor impact. The response is in the correct direction. Will review response to determine if there is a problem.

R:colution: Results:

DR 9501002 was written. DR is open. l

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FORM: 12-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 5 OF 10

.m

_,xM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION 4 PERFORMED BY:T. PETRAK DATE: 01/03/94 REVIEWED BY:M. GIBSON DATE: 01/03/94

' APPROVED BY: R. DORMAN MANAGER TRAINING & EP DATE: 01/04/95 Parformance Test Procedures: 05-24A Interval: Rx Trio to Termination DR Number:_7 (9501004)

Comparison Comparison Parameter Measure Value TDAFW Pressure NA Table Top Problem

Description:

Cause:

20 response of the TDAFW pressure Model problem.

r~3 the ramp circuit was questioned

\_

during the test analysis.

Corrective Action: Impact if not Corrected:

Correct model. Minor impact. Will verify response. f Response is in the proper direction and reasonable for training.

Response has not.been evaluated. It-may be correct.

Rs=olution: Results:

DR 9501004 was written. DR is open. i l

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FORM: 12-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 6 OF 10 DISCREPANCY RESOLUTION WORKSHEET REVISION 4 lllRMTITLE:

PERFORMED BY:T. PETRAK DATE: 01/03/94 REVIEWED BY:M. GIBSON DATE: 01/03/94 APPROVED BY: R. DORMAN MANAGER TRAINING & EP DATE: 01/04/95 Parformance Test Procedures: 06-08 Interval: Surveillance Test DR Number: 9 (9501007)

Comparison Comparison Parameter Measure Value Source Range Hi Flux at NA Table Top Shutdown Problem

Description:

Cause:

c Hi Flux at Shutdown setpoint IC's snapped with wrong setpoint.

/"j;d

(, not meet the acceptance criteria of Procedure 14432-1.

Corrective Action: Impact if not Corrected:

R: snap IC's with proper setpoint. Minor impact. Surveillance can be performed.

Recolution: Results:

DR 9501007 was written. DR is open.

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PORM: 12-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 7 OF 10

.llhRMTITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION 4 PERFORMED BY:T. PETRAK DATE: 01/03/94 REVIEWED BY:M. GIBSON DATE: 01/03/94 APPROVED BY: R. DORMAN MANAGER TRAINING & EP DATE: 01/04/95 Parformance Test Procedures: 07-01.05-11A.05-23A.05-27 Interval: Malfunction to Termination DR Number: 10 (9304007)

Comparison Comparison Pcrameter Measure Value SG PRESS NA TABLE TOP

("'loblem

Description:

Cause:

gr SG Pressure response following a Model problem R actor Trip does not match plant data. Response is too slow.

Corrective Action: Impact if not Corrected:

Tune steamline model to match plant Minor training impact. The pre and trip data. post trip SG pressures are correct.

It is unlikely that the operator would notice that the pressure response is a little slow following a trip.

R::olution: Results:

DR 9304007 was written DR is open v

4 FORM: 12-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 8 OF 10 ,

,,xM TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION 4

? PERFORMED BY:T. PETRAK DATE: 01/03/94 REVIEWED BY:M. GIBSON DATE: 01/03/94 APPROVED BY: R. DORMAN MANAGER TRAINING & EP DATE: 01/04/95 !

Psrformance Test. Procedures: 07-09 Interval: Malfunction to Termination DR Number: 12 (9501005)

Comparison Comparison Parameter Measure Value Fssd Flow NA Table Top Problem

Description:

Cause: i

.~sd Flow goes to a very small Model problem. [

value after the event.

Corrective Action: Impact if not Corrected:

Correct model. Minor impact. Overall trend is correct. The value is very small and would probably not be noticed by the operator.

Racolution: Results:  ;

DR'9501005 was written. DR is open.

t FORM: 12-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 9 OF 10

- i TITLE: DISCREPANCY RESOLUTION WORKSHEET J REVISION 4 PERFORMED BY:T. PETRAK DATE: 01/03/94 REVIEWED BY:M. GIBSON DATE: 01/03/94

-AP' PROVED BY: R. DORMAN MANAGER TRAINING & EP DATE: 01/04/95

)

Psrformance Test Procedures: 05-12A Interval: Malfunction to Termination DR Number: 14 (9501006) 4 Comparison Comparison i Parameter Measure Value l

Pressurizer. Pressure NA Table Top f

Problem

Description:

Cause: .

f

,._essurizer Pressure has a slight - Model. problem. {'

ovarshoot after power is restored.

lt Corrective Action: Impact if not Corrected: i.

Correct model. Minor impact. Student is very unlikely to notice-the small change in pressure. It has not'been analyzed. It may be correct.  ;

R3colution: Results:

DR 9501006 was opened. DR is open.

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4 JF'O RM: 12 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 10 OF 10

~

di TITLE: DISCREPANCY RESOLUTION WORKSHEET REVISION 4 PERFORMED BY:T, PETRAK DATE: 01/03/94 REVIEWED BY:M. GIBSON DATE: 01/03/94

APPROVED BY
R. DORMAN MANAGER TRAINING & EP DATE: 01/04/95 Parformance Test Procedure,s: 05-31

-Interval: Malfunction to SI DR Number: 8 (9304015)

Comparison Comparison ,

Parameter Measure- Value PR FLUX, PRZR LVL, PRZR NA Table Top PRESS, WR PRESS, SG NR & WR LVL, SG PRESS, FEED FLOW &

STEAM FLOW ,

d Problem

Description:

Cause:

Model problem.

Q*areisanoscillationinallthe ove parameters from just after the turbine trip and continues  ;

until the feed pumps trip.  ;

5 Corrective Action: Impact if not Corrected:

Correct models to remove the Minor impact. -The overall trends oscillation. are correct.

8 Razolution: Results:

DR 9304015 was written. DR is open.

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1I NJ FORM: 17-03 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 1 OF 3 i'

FORM TITLE: CERTIFICATION REVIEW COMMITTEE REVISION 4 The "1994 Simulator Certification Committee was set up to review the steady state, normal operations and tr .ient testing of the Vogtle simulator.

The " Committee" met on 12/20/94. It consisted of four individuals with the following credentials:

Steve Dyer:

RO and SRO licenses at Plant Vogtle. One year education at Floyd Junior College and two years at Coosa Vocational Technical School.

Plant Vogtle: 7 years operational experience as a Plant Equipment Operator, Assistant Plant Operator, and Plant Operator (RO licensed) . Duties included Preop Testing, Startup and Commercial Operation l Plant Vogtle: Attended SRO License Upgrade school. Has taught Requal and Initial Operator Training classes since February .

1992.

Plant Hatch: 2 years BWR Preop Testing, Startup and Commercial Operation.

George Gunn:

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. l Plant Vogtle: 4 years Operations Instructor experience.

Duties have included hot license class instruction, requal instruction and simulstor certification.

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FORM: 17-03 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 2 OF 3 FORM TITLE: CERTIFICATION REVIEW COMMITTEE REVISION 4 Thad Thompson:

SRO license at Plant Vogtle (# SOP-20865): RO license at Plant Vogtle Plant Vogtle: 6.5 years operational experience as a Reactor Operator. Duties included the operation of various plant equipment, refueling operations, initial energization, hot functional testing, power ascension testing, and commercial operation of Units 1 and 2 in the control room.

Plant Vogtle: 4 years Operations Instructor experience. Duties have included 3 hot license classes instruction in classroom, plant, and simulator. Other duties related to training include simulator certification and Shift Superintendent course developent.

O'v Plant Hatch: 2 years as a Plant Equipment Operator and as Radwaste Operator. Duties included mostly various plant equipment operation as a Plant Equipment Operator. As a Radwaste Operator performed mostly plant equipment operation and Radwaste Control Room operations of various equipment.

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.

Plant Vogtle: 5.5 years Senior Nuclear Instructor experience.

Duties have been requal instruction, maintenance and testing of simulator software, simulator acceptance testing and simulator certification.

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HO FORM: 17-03 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 3 OF 3 FORM TITLE: CERTIFICATION REVIEW COMMITTEE REVISION 4 The committee used plant data, FSAR data, and owner's group guidelines ac available and needed. If no data was available, then the best Ludgement of the committee based on their various backgrounds and plant experiences was used.

All tests were determined to be satisfactory with 'the exception of those items identified on Form 1201 of the report.

The committee was in full agreement for all tests.

Test analysis was completed in the same manner utilizing individuals with similar backgrounds for each of the previous years.

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O Attachment 4 PERFORMANCE TEST PLAN CHANGES 01/04/95 '

Plant A.W. Vogtle, Unit 1 f3 Docket #50-424 U Georgia Power Company

FORM: 18-01 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 1 OF 1 R TITLE: PERFORMANCE TEST FLAN CHANGES REVISION 1 i PERFORMED BY:T. Petrak DATE: 01/02/94 REVIEWED BY:M. Gibson DATE: 01/02/94 APPROVED BY: R. Dorman MANAGER TRAINING & EP DATE: 01/04/95 -

Changes have been made to the test plan to cover plant changes, plant procedure changes, and minor errors in the test guides, testing procedures and abstracts. The testing procedures were also changed to better define tha testing and thereby improve test consistency from year to year. Many minor changes were made to cover the above situations. Other test changes that were made are:

1) A new instructor station was added to the simulator. It uses an improved naming scheme for malfunctions and remote functions.

The test procedures and abstracts are being changed to reflect ,

the new scheme as the tests are run each year.

2) A new CCW model was written. The location of the CCW system leak '

(test 05-17) was moved to the pump discharge vs being somewhere down the CCW system piping. This change made no difference in operator action but made more sense for model development.

3) The IC used for Test 05-19A (dropped rod) was changed to 100%

power since Plant Vogtle no longer has a negative rate trip circuit.

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4) Test 05-21B (RCS Boration) was changed to be run from an MOL ,

core vs a BOL. Core reloads now yield a greater cooldown at BOL.

Utilizing MOL makes the test more consistent with previous tests.

5) Test 05-25 (MSLB ORC) is changed to utilize a 48% BOL IC. We no longer maintain a 49% EOL IC.
6) A new form was added (Form 12-03) to track testing problems.

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I NRC FORM 474 U.S, NUCLEAR REGULATORY COMMISSION APPROVED LV OMB; NO. 3tS0 4134  ;

p EXPIRES: 19/3t/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS ,

INFORMATION COLLECTION REQUEST: 120 HOURS. FORWARD j SIMULATION FACILITY CERTIFICATION C WMENTS REGARDING BURDEN EST1 MATE TO THE INFORMATION AND RECORDS MANAGEMENT BRANCH (MNBB T714L U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 205554001,AND TO THE PAPEFIWOFIK RETIUCTION PRCUECT (31504138), OFFICE OF MANAGEMENT ,

AND BUDGET, WASHINGTON. DC 20503 I INSTRUCTIONS: The form le to be fhed for initial certification, recemfication (if required), and for any charge to a simulaim facilNy performance testmg plan made after inmal sut,mntal of such a plan. Pros 6de the following mformahon and checle the appropnate bon to mdicate reason for submtttal.

FACiUTY - DOCKET NUMBER A. W. Vogtic Unit 2 Nuclear Power Plant S425 UCENSEE DATE Georgia Power Company 1-4-1995

' ne is to certify that:

1. The above named facilNy lleensee le uomg a simulat6on faciuty consenting soley of a planl-roterenced esmulator that meets the requirements of 10 CFR 55.45.

p 2. Documentation is availabia for NRC revow in accordance with to CFR SS 4S(h).

3. The esmulation facilNy meets the guidance contamed in ANSI /ANS 3 S,1985, as endorsed by NRC Reg.ilatory Guide 1.140.

n me,e ar. any EXCEPTIONS to me cemhcpan of his Nem, CHECK HERE [X] and descitbe fuly on additional paces as recessarEcc Attachment 1:Except ons i NAuE (or ome, we,.nce,,on) ANo LOCAriON OF siuutATiON F ACii;TY.

A. W. Vogtle Simulator, River Rd., Approx. 5 mi. NE, Hwy. 23, Waynesboro, GA 30830 i SIMULATION F ACluTY PERFORMANCE TEST ABSTRACTS ATTACHED. (For perbrmance tests conductedin the penod endtng with me defe of rus cer0#caeort)

(1f. CFuPTION OF PERFORMANCE TESTING COMPLETED. (Attach adeconar pages es necessary and sdenefy me nem desenpoon bomp canonued)

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 I to this form.

e SIMULATION F ACIUTY PERF0Fe **NCE TESTING BCHEDULE ATTACHED. (For the conduct of apprommately 25" of performance loses per year br me bur-year penod cominenomp wim X she date ar ea ce*caaorts DESCHIPTION OF PERFORMANCE TE STING TO BE CONDUCTED. (Atrech adeconat pages as necessary and Adentify the nem desenpoon bemg canonued.)

Plant A. W. Vogtle, Unit 2 Simulator Training will be performed using the Unit 1 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.

X *""'***"^"'""#'"*"'""****'*""'"**"""'""'"*'""#"'""*"""*'*"'

DESCRIPTION OF PLHFORMANCE YESTING PLAre CHANGE (Attach addroonalpages as necessary and #dencry the som desenpoon bomp contraved)

Unit 2 test plan changes are the same as thit 1.

RECERTIFICATION (Desortbe correctrue acem tenert attech results or comptered performance toseng m eccordance with to CFR Skt5(b)($)(4 (Attach eddeonal pages as necessary and odency the Mem descnpban bemg conenued)

Any feine statement or omiseen m the document, mciudmg attachments, may to subtect to cui and snmmel sanctiore. I ce<ttey under penalty at pequry that tre mtormation en the document and attachments is true and correct.

$1 GNAT UT ' 'ED R PHL NTATNE flTLE 3 UATE t.s .

Grcral Monger in act canc3 men to Cf 6 65 S, dbmmunecatens, the 6xm shall be submmed to the NHC as 8anown

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9 Mall ADORF5 SED TO. OtRECTOR, OFFICE OF NUCLLAR REACTOR Rt0ULATION BY DELNERY IN PERSON ONE WHITE FUpfT NORTH UA NUCLEAR REQULATORY COMMISSION TO THE NRC OFFICE AT: 11655 ROCKVILLE P6KE WASHINGTON, DC 305S64001 ROCKYlLLE, MD NHC FOfaA 474 {10-92) PRINTED ON RECYCLED PAPER

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Attachment 1 EXCEPTIONS 01/04/95 Plant A.W. Vogtle, Unit 2 Docket # 50-425 O Georgia Power Company i

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4-A.W.' PLANT VOGTLE, UNIT 2 #50-425

  • - ATTACHMENT 1 01/04/95 i EO  :

i 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. The differences between the two units are very minor. Georgia Power Company feels that the Unit 1 simulator is acceptable for training of Unit 2 operators. This report is made a part of the attachment and serves to document compliance with Regulatory Guide 1.149.

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() 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 contrals on the Main Control boards except for one small panel (section D). Section D is on the left 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 tsolation 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 pattem 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 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 (q/ extent that the Vogtle simulator can be used for Unit 2 operators with basically no training impact.

1. Boron injection Tank Unit i BIT inlet valves are installed with power removed and locked open Unit 2 BIT is not piped into the system flowpath and the BIT inlet valves were never installed.
2. Diesel Generator Unit 2 Train B Fuel Oil Transfer system has local / remote handswitch located on 2BBF-27 Unit 2 DG Day Tanks can be drained back to the Fuel Oil Storage Tank.

Unit 2 DG Sync Mode Selector Switch turns in the opposite diraction of Unit 1's.

1) nit 1 DG has added a Jacket Water Chem Add system.

Unit 1 DG has a digital governor which allows both " slow" and " fast" starts.

Unit 1 DG has generator loading control (GLC) which is used whenever the diesel is paralleled to the grid.

A ten tum pot is used to control generator load during parallel operation.

Unit 1 DG has removed the manual backup voltage regulator and has added a second automatic voltage regulator.

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3. QMCB Annunciator Power Supplies If the normal power supply (AC) is lost to the CMCB annunciators, the backup supply (DC) will keep the annunciators powered on each Unit. When AC power is restored on Unit 1. the annunciato_rii must be manually transferred / reset to retum to the normal supply. (Auto transter on Unit 2).

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4. NSCW Unit 2 Aux Containment Cooler isolation valves are interlocked so that the outlet valves must be opened first When opening the outlet valves, they will stroke open for 3 seconds, and then stop for 60 seconds before stroking full open.

Unit 2 also has hiah point vacuum breakers located at the ESF chil!srs and the CCW heat exchangers.

5. Aux Feedwater I

Unit 1 has installed handswitches to allow blocking of the AFW actuation circuitry when needed.

Unit 1 has replaced the AFW pump shaft seals with mechanical seals.

6. HVAC & Freeze Protection

\ Unit 1 SGBD Hx room now has a room cooler supplied with normal chilled water. This lessens the chances of an inadvertent actuation of the HELBA system on high room temperature during normal operation.

Unit 1 MSIV HVAC routs air directly onto the MSIV valve bodies to keep them relatively cool. This reduces the chances of temperature-related equipment failures.

Unit i utilizes heat tracina for freeze protection in outside areas. Unit 2 uses area heaters.

7. Nuclear Sampling Unit 1 sande systen, has oressure reduction and relief valves.

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8. Waste Systems Unit 2 Waste Evaporator Packaae not completed.

Unit 2 has two additional Waste Monitor Tanks (designaied as common). Each tank has a 20,000 gallon capacity.

9. Main Feed Pumps i Unit 2 MFP segliniection filters have DP aauaes.  !

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10. Tech Specs 1 l

Any d%rences in Tech Spec requirements between the units are designated by the use of parentheses, '

sepaiate listings and/or diagrams, etc.

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11. Spent Fuel Pool storage capacity Unit 1(East)- 288 storage locations Unit 2(West) 2098 storage locations l
12. RHR Venting Unit 2 RHR hiah-ooint vents (10465 & 10466) have drain lines routed outside the cubicles.
13. Human Factors Floor colors Unit 1 and common areas have cream / tan colored floors. Unit 2 has powder blue floors.

_C_2moonent labelina Unit 1 and common equipment have white sectangular labels. Unit 2 has round blue labels.

14. Plant Computer Unit 1 has been replaced the Proteus /ERF/ATSI computers with the Integrated Plant Computer (IPC).
15. EHC Pressure Turbine Trip Unill has added a 3 second delay to the Low EHC pressure turbine trip.
16. EHC Filters Unit 1 EHC Filters has been modifed as follows:
a. Addition of a second parallel EHC filter.
b. Fines filter changed to a one micron filter,
c. High filter delta P Indicating light remains on when delta P is normal.
17. Turbine Control Unit 1 has added a speed error signal filter card.

Unit 1 has updated the Load Set and Load meter scales.

18. Pressurizer Pressure Control Loop Unit 1 has removed the setpoint potentionmeters for controllers 455A,455B,455C,455D and 455E.
19. Standby Auxiliary Transformer
1) nit 1 has added the Standby Auxiliary Transformer.

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1' Attachment 3  :

i PERFORMANCE TEST SCHEDULE 01/04/95  :

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i Plant A.W. Vogtle', Unit 1  !

n- Docket #50-424 V Georgia Power Company {

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FORM: 13-04 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 1 OF 1

'M TITLE: UNIT 1/ UNIT 2 PROCEDURE DIFFERENCES

. REVISION 1 PERFORMED BY: T.Petrak DATE: 1216/94 REVIEWED BY: M.Gibson DATE: 12/16/94 UNIT 1 UNIT 2 TRAINING IMPACT REQUIRED PROCEDURE PROCEDURE DESCRIPTION ACTION NOTE:

The Vogtle EOPs, AOPs, and UOPs exist in procedures common to both units. Any differences in steps will be identified in a two column (Unit 1 - Unit 2) format. These differences will generally only exist from onn outage to the next. Plant Vogtle has made a major effort to make the units identical.

1. The unit designator is not used in the procedures for mechanical components such as valves, pumps, tanks, fans, etc. when they are the same for both units.
2. If mechanical equipment does not have the same number on both units than the procedure gives the entire component description including the it designator and the equipment number. -
3. If electrical equipment is referred to in common procedures, then the entire component description including the unit designator and equipment number is given. .
4. When referencing unit particular operation procedures in common procedures, the unit designator is not mentioned. The unit designator will be left off and the user should refer to the applicable unit procedure.
5. When referencing common procedures in unit procedures the designator "C" will be used.

With a limited review no difference in component numbers have been identified when comparing the two units. No operational differences, except for setpoints normally, exist in the EOPs and AOPs.

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t FORM: 17-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 1 OF 5 NM TITLE: PERFORMANCE TEST SCHEDULE REVISION 1 PERFORMED BY:T. Petrak DATE: 11/02/94 REVIEWED BY:M. Gibson DATE: 11/02/94 APPROVED BY: R. Dorman MANAGER TRAINING & EP DATE: 01/04/95 Annual operability Test The following operability tests will be conducted annually (Computer Tasting and Appendix B - Steady State and Transient Performance Tests):

l o COMPUTER REAL TIME TEST (08-01) o SIMULATOR LIMITS EXCEEDED TEST (03-02) o STEADY STATE PERFORMANCE AT 35% 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 SIMULTANEOUS TRIP OF ALL FEEDWATER PUMPS (07-02)

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'/ o SIMULTANEOUS CLOSURE OF ALL MAIN STEAM ISOL VALVES (07-03) o SIMULTANEOUS TRIP OF ALL REACTOR COOLANT PUMPS (07-04) o SINGLE REACTOR COOLANT PUMP TRIP (07-05) o MAIN TURBINE TRIP W/O REACTOR TRIP (07-06) o MAXIMUM RATE POWER RAMP (07-07) j o MAXIMUM SIZE RCS RUPTURE W/ LOSS OF OFFSITE POWER (07-08)  !

o MAXIMUM SIZE UNISOLABLE MAIN STEAM LINE RUPTURE (07-09) o SLOW PRIMARY SYS DEPRESSURIZATION TO SATURATED CONDITION (07-10)

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1 FORM: 17-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 2 OF 5 A i di TITLE: PERFORMANCE TEST SCHEDULE REVISION L_ i P"ERFORMED BY:T. Petrak DATE: 11/02/94 REVIEWED BY:M. Gibson DATE: 11/02/94 l APPROVED BY: R. Dorman MANAGER TRAINING & EP DATE: 01/04/95 l

P rformance Tests Tha 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 cs Annual Operability Tests):

o LOSS OF COOLANT- SIGNIFICANT PWR STEAM GENERATOR LEAKS (05-01) o LOSS OF COOLANT- SMALL RCS BREAKS (05-05) o LOSS OF EMERGENCY POWER (05-09) o LOSS OF POWER TO INDIVIDUAL INSTRUMENT DC BUSES (05-13) o LOSS OF COMPONENT COOLING SYS OR COOLING TO INDIVIDUAL COMPONENTS (05-17) n o FUEL CLADDING FAILURE (05-21)

U o MAIN STEAM LINE BREAK OUTSIDE CONTAINMENT (05-25) o PROCESS INSTRUMENT, ALARMS. AND CONTROL SYSTEM FAILURES (05-29) o PLANT STARTUP FROM COLD TO HOT STANDBY (06-01) o COOLDOWN FROM HOT STANDBY TO COLD SHUTDOWN CONDITIONS (06-05)

FORM: 17-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 3 OF 5 2 TITLE: PERFORMANCE TEST SCHEDULE ' REVISION 1 PERFORMED BY:T. Petrak DATE: 11/02 /94 ' REVIEWED BY:li. Gibson DATE: 11/02/94 APPROVED BY: R. Dorman MANAGER TRAINING & EP DATE: 01/04/95 PCrformance 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 COOLANT- INSIDE PRIMARY CONTAINMENT (05-02) o FAILURE OF SAFETY AND RELIEF VALVES (05-06) o LOSS OF EMERGENCY GENERATORS (05-10) o LOSS OF CONDENSER VACUUM INCLUDING LOSS OF CONDENSER LEVE_L CONTROL (05-14) o LOSS OF ALL FEEDWATER- NORMAL AND EMERGENCY (05-18) o GENERATOR TRIP (05-22) o 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 REACTOR TRIP FOLLOWED BY RECOVERY TO RATED POWER (06-06) l 1

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.10RM: 17-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 4 OF 5

-M TITLE: PERFORMANCE TEST SCHEDULE REVISION 1 PERFORMED BY:T. Petrak DATE: 11/02/94 REVIEWED BY:M. Gibson DATE: 11/02/94 APPROVED BY: R. Dorman MANAGER TRAINING & EP DATE: 01/04/95 P rformance Tests Tha following performance tests will be conducted (in addition to the annual operability tests) in the third year following certification (Normal Or sration Tests, Malfunction Tests, and Transient Tests not tested cc Annual Operability Tests):

o LOSS OF COOLANT- OUTSIDE PRIMARY CONTAINMENT (05-03) o LOSS OF INSTRUMENT AIR (05-07) o LOSS OF POWER TO THE PLANT'S ELECTRICAL BUSES (05-11) o LOSS OF SERVICE WATER OR COOLING TO INDIVIDUAL COMPONENTS (05-1E.1.

o CONTROL ROD FAILURES (05-19) p v

o FAILURE IN AUTOMATIC CONTROL SYSTEMS (05-23) o 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 l

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PORM: 17-02 VOGTLE SIMULATOR CERTIFICATION PLAN PAGE 5 OF 5 W TITLE: PERFORMANCE TEST SCHEDULE REVISION 1 PERFORMED BY:T. Petrak DATE: 11/02/94 REVIEWED BY:M. Gibson DATE: 11/02/94

-APPROVED BY: R. Dorman MANAGER TRAINING & EP DATE: 01/04/95 l

POrformance Tests i l

-Tha following performance tests will be conducted (in addition to the ,

annual operability tests) in the fourth year following certification l (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)  !

t o LOSS OF POWER TO INSTRUMENT AC BUSES (05-12) o LOSS OF SHUTDOWN COOLING (05-16) ,

o INABILITY TO DRIVE CONTROL RODS (05-20) ,

o FAILURE OF RCS PRESSURE & VOLUME CONTROL SYSTEMS (05-24)  :

o NUCLEAR INSTRUMENTATION FAILURES (05-28L o PLANT SHUTDOWN FROM RATED POWER TO HOT STANDBY (06-04.1 o OPERATOR CONDUCTED SURVEILLANCE TESTING ON SAFETY RELATED ,

SYSTEMS (06-08) l e

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