Document Control Desk NND-15-0370training on an important deadband limit on CPS updates parameter....

Document Control DeskNND-15-0370

South Carolina Electric and Gas CompanyVirgil C. Summer Nuclear Station (VCSNS) Units 2 and 3

NND-15-0370

Enclosure 3

Request for a Commission-Approved Simulation Facility

Response to a Request for Additional Information

Redacted Response (Non-Proprietary)

(This enclosure contains 90 pages, including this cover sheet.)

Attachment 5

Westinghouse Non-Proprietary Class 3 VSL-VSG T 000306June 16, 2015

DRAFT RAI Page I of 89

Request for Additional Information pursuant to the VCS request for a Commission ApprovedSimulator

Requirements

10 CFR 55.46(2) - The commission will approve a simulation facility or use of the plant for

administration of operating tests if it finds that the simulation facility and its proposed use, or the

proposed use of the plant, are suitable for the conduct of operating tests for the facilitylicensee's reference plant under 10 CFR 55.45(a).

10 CFR 55.45(a) - The operating tests administered to applicants for operator and senior

operator licenses in accordance with paragraph (b)(1) of this section are generally similar in

scope. The content will be identified, in part, from learning objectives derived from a systematic

analysis of licensed operator or senior operator duties performed by each facility licensee and

contained in its training program and from information in the Final Safety Analysis Report,

system description manuals and operating procedures, facility license and license amendments,

Licensee Event Reports, and other materials requested from the facility licensee by the

Commission. The operating test, to the extent applicable, requires the applicant to demonstrate

an understanding of and the ability to perform the actions necessary to accomplish a

representative sample from among the following 13 items.

The Table below contains simulator deficiency reports that the staff has screened as significant.They are associated with each 10 CFR 55.45 criterion that the staff thought applicable.Consequently some deficiencies are repeated.

Please provide a detailed assessment of the significance of each deficiency as it applies to the

55.45 criterion. The Basis column of each table provides specific areas that the assessmentshould include.

In some cases question marks replace written information. These cases represent deficienciesthat the staff did not understand or deficiencies that were not described sufficiently to draw

conclusions on significance. Please explain these deficiencies in more detail in addition to

assessing the deficiency significance.

May 27, 2015

Westinghouse Non-Proprietary Class 3

DRAFT RAI

10 CFR 55.45(a)(1):

Attachment 5VSLVSG 000306

June 16, 2015Page 2 of 89

Perform vre-startup procedures for the facility, includinq operatinq of those controls associatedI = =

with Wlant equipment that could affect reactivity,

10 CFR 55.45(a)(1): Perform pre-startup Procedures for the facility, including operating of those controls associated with

plant equiDpent that could affect reactivitv.eficiency D eficiency description Significant? Basis Additional Information

No. provided by licensee

VC-TO-55 Creates a false indication The SDR was written beforeassociated with reactivity Westinghouse patches weremanipulations. Potential negative installed which removed thetraining on an important deadband limit on CPS updatesparameter. for increments less than [

ba,, and which improved historianfunctionality. As a result of thesefixes, SR count prompt jump nowdisplays on Ovation trends withno discernible lagThis SDR is not tracking a falseindication, rather a potential

Prompt jump does not occur delay in indication. The SR andimmediately upon rod Yes IR signals that were monitoredwithdrawal/insertion when this SDR was written are

displayed on an Ovation "controlboard" screen. Thoseinstruments, then, were trendedusing the built in trendcapabilities in ovation.

]a,, Using theworse case signal processing

time it was possible to introduce

2May 27, 2015


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Attachment 5VSLVSG_000306


10 CFR 55.45(a)(1): Perform pre-startup procedures for the facility. including operating of those controls associated with

plant equipment that could aftect reactivirtf.Deficiency Deficiency description Significant? Basis provided by licenseea processing delay that can be

as long as 6 to 7 seconds..

As alternate indications, the SRpower level (in cps) and the IRSUR indications can be alsomonitored directly at each PMSdivision monitor. f

]a,c The PMSworkstations do not provide anycustomizable trendingcapabilities like the ovationboard does.This SDR is tracking a requestedaddition of trends for SR and IRpower and SUR to the pre-builttrends available in PMS as anenhancement.

VC-TO-56 Turbine Control valves are Knowledge of CV position is This SDR is tracking a questionnecessary early in E-0 (RNO to determine if a procedure

open [ ]a,c looking at step) to ensure the Main Turbine change is needed to thethe signal diaarams, but is tripped if all the MSVs are not procedure direction to performindicating [ ]ac on Yes closed and for shell and chest shell and chest warming or a

sahoulo b frced io awarming activities, change to the graphic display.should not be forced into a

signal diagram to get a value [a,cneeded for any procedure. Turbine Control Load/Speed

3May 27, 2015

Attachment 5Westinghouse Non-Proprietary Class 3 VSLVSG_000306

June 16, 2015

DRAFT RAI Page 4 of 89

10 CFR 55.45(a)(1): Perform pre-startup procedures for the facility, including operating of those controls associated withplant eauiinment that could affect reactivity. IDeficiency eficiency description Significant? Basis Additional Information

No. provided by licenseeControl Screen. Control Valveposition is displayed to onedecimal point (0.0%). Whenconducting Shell and ChestWarming activities the number 2turbine control valve is open avery small amount to admitsteam to the shell and chestarea. As the valve throttlesclosed during the evolution, itgoes to less than 0.1%, which isthe minimum value that cancurrently be displayed. At thatpoint, the operator can right clickthe point display, to see theminor % valve open position.When the parameter is displayedin this manner, it can also beeasily trended via the normalprocess.

4May 27, 2015


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'n-q of those controls associated with~zg gf those controls associated with

Additional Informationprovided bv licensee

]a,c Theindication discussed in this SDRitem, is the redundant valveposition indication used forturbine control (vs. turbine trip).

.. . . . I

VC-1411-15 Introduces potentialunaccounted for failure modethat operator must respond to inaddition to planned examscenario

Source range counts rise inincrements of [ ]a,c

Yes

A fix has been installed thateliminates the [ ]a,cincrement deadband when lessthan [ ]z,. During startupconditions with SR countsgreater than [ la,c, theresultant increase in countscaused by each successivereactivity addition is greatenough that an incrementaldeadband of [ la cis no

5May 27, 2015


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10 CFR 55.45(a)(1): Perform pre-startup procedures for the facility, including operating of those controls associated with

plant equipment that could affect reactivit,.eficiency Deficiency description Significant? Basis Additional Information

No. provided by licenseelonger noticeable.

VC-1411-09 Could force exam scenario into This SDR has now beenundesired sequence and trigger corrected (5/6/15). The issuecomponent failure was originally identifiedassessment(s) and/or operator 11/12/14. It has been attributedresponses which would add to the Simulator Historian. SIMundesired Historian [ ]a,c has nowcomplexity/distractions to the been installed on both simulators

Inconsistent non-urgent exam scenario. (11/25/14), and retested (5/6/15.failure alarms on loss of ES- Yes The scenario includes a loss of1 power to EK-1, which feeds one

of the two redundant 24 volt rodcontrol cabinets. This results in aloss of one power supply alarm -causing the non-urgent alarm asexpected. After the Historian fixthis alarm now comes in everytime as expected.

VC-1 503-24 Defeats purpose of safety This SDR is now being closed.function alarm (high awareness The item originated from inputand potential necessary taken from ISV activities, whichresponse to safety function were added to the SDR listchallenges) immediately prior to the CAS

Frequent invalid yellow path submittal.

on sub-criticality safety Yes The Westinghouse simulator that

function alarm supported ISV did not have thepatch which removed thedeadband of [ ]ac for SRcounts less than [ ]a,c counts.Prior to installing the patch, thisindication was caused by theSource Range Startup Rate (SR

6May 27, 2015


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plant equipment that could affect reactivit'V.

DeficiencyNo.

Deficiency description Significant? BasisAdditional Informationprovided bv licensee

SUR) input f

]a,c This allows extremelyminor increases in SUR to showas a positive, which causes theindicator to turn "YELLOW".The patch also changed thisinput so that the invalid yellowpath indication is no longerreceived.

VC-1 503-30 Could force exam scenario intoundesired sequence and triggercomponent failureassessment(s) and/or operatorresponses which would addundesiredcomplexity/distractions to theexam scenario.

This indication is caused by theresulting increase in SourceRange (SR) counts when the SRinstruments are automatically re-energized as power level decaysafter a Reactor trip. There is aresulting "spike" when the countsgo from 0 to some value. Thisindication is also seen at existingfleet plants, and is included inoperator training.

I ]a,c post reactortrip, a positive startup ratewas observed, subsequentlyreturning to normal

Yes

The patch which addressed thedeadband of [ ]a,c countincrements for updatina SRindication less than [ ]ac

counts has improved theresponse time and indicationpost trip.

7May 27, 2015


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10 CFR 55.45(a)(1): Perform pre-startup procedures for the facility, including operating of those controls associated withplant equipment that could affect reactivity.Deficiency Deficiency description Significant? Basis provided by licenseeThe SDR is written to track a

determination if potentialimprovements can be realized inthe decay time of this initial spikeafter plant Start Up data isobtained or more plantinstrument data becomesavailable.

VC-1 504-06 ??Description not sufficiently A separate alarm set-point is(Not on complete to assess processed for Rod Insertion Limitdocketed list) significance?? (RIL) for OPDMS OPERABLE or

INOPERABLE.

There is no problem with the RILalarm when OPDMS isOPERABLE.

The alarm set-point discussed inthis SDR is for the case of

Alarm setpoint of the rod OPDMS INOPERABLE. rinsertion limit for bank M2

]a,c Thesimulator, as currentlyconfigured, has the RIL forOPDMS INOPERABLE setcorrectly to allow this

8May 27, 2015


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nl fnt ", nm fn thatm t',n"lW mttw-4 rg•nmt-ti--it II'I

DeficiencyNo.

Deficiency description Significant? BasisAdditional Informationprovided by licensee

I- t * surveillance to be performedwithout entering the RIL LCO.The limit specified in the COLR,however, is the rod full outheight, which is incorrect.

This SDR item is tracking adetermination to either (1) fix theRIL in the COLR, so that analarm set-point change to thesimulator is not required, or (2)change the Alarm setpoint in thesimulator so that the RIL is nowthe full out position. If option 2 ischosen, then the surveillanceprocedure F

]a,c will need toaddress entering LCO 3.1.6 IFthe surveillance is performedwhen OPDMVS is INOPERABLE.

when OPOMS is INOPERABLE.

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June 16, 2015Page 10 of 89

10 CFR 55.45(a)(2):

Manipulate the console controls as required to operate the facility between shutdown and

destgnated nower levels.

10 CFR 55.45(a)(2): Manipulate the console controls as required to operate the facility between shutdown and designated

nower levels.Deficiency Deficiency description Significant? Basis Additional Information

No. IIprovided by licensee

Could force exam scenario intoundesired sequence (manualcalc). Also needed to supportJPM

The two AOPs that addressRCS leakage, AOP-112, RCSLeak, and AOP-1 03, SG Tubeleak both require thecandidate to determine anestimated leak rate r

Ia,c

This is consistent with themethodology used bv existingfleet olants. f

VC-TO-09 dQ" data points]a,c returns "BAD Yes

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June 16, 2015Page 11 of 89


cower levels. T 1-

DeficiencyNo. Deficiency description Significant? Basis

Additional Informationprovided by licensee

Ia,cNo.i

The JPM which would test thiscompetency would not rely onthe candidate simply looking atthe values in the automated"On Demand" leak ratebecause the level of difficultywould be too low. Instead, thecandidate would be required toperform a Manual Leak Ratecalculation, which is notaffected bv this SDR.

During plant C/D and H/U the Creates a false indication Additional investigation of this

VC-TO-40 sub-criticality CSF title block is Yes associated with reactivity item is in progress.

turning magenta (bad input) manipulations.

intermittentlyRods are rejecting to MANUAL Could force exam scenario into Two Westinghouse patches

-25% of the time when there is a undesired sequence and trigger have been installed since this

power loss to Incore component failure SDR was initiated: I

instrumentation PROCESSING assessment(s) and/or operator

CABINET I or 2. From a [ responses which would add

]ac power condition, after power undesired ]a~c It has

VC-TO-45 loss to either cabinet, corrected Yes complexity/distractions to the also been identified that minor

Rx Power points (PC-PRPP- exam scenario. The rapid rod changes in plant conditions at

COMP-A [ B.CD ]) are driven movement specified is more the test starting point can be

down to [ ]a,c before significant than shifting to caused by running multiple

returning to normal. Rods move manual. iterations of a testing scenario

rapidly OUT then IN in response in an automated "chain"

to this event when they don't overnight. These, in turn, also

reject to manual. affect plant performance - in

11May 27, 2015

I

I


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June 16, 2015Page 12 of 89


power levels.Deficiency Deficiency description Significant? Basis Additional Information

No. provided by licenseeparticular causinQ minordeviations in F

]a,c Overall changes tosimulator operating practiceswhich include much more

frequent simulator rebootinghave been implemented alongwith changes to "chained"testing.

The results have been a

significant reduction ofinstances of rods rejecting tomanual over several months oftraining and examinations. The

item is being left open tocontinue monitoring for issues,and to track any future designhardening improvements.

I his •SL)R expands uponpreviously identified oroblemswith r

VC-TO-54VC-TO-58VC-TO-88

VC-1502-11

],,c issues.Previous feedwater SDRs haveFW control problems during RXStartup and also at low powerconditions affecting MFW/SFWtransfer durina startun. PreviousSDRs on i 1

Multiple problems could triggercomponent failureassessment(s) and/or operatorresponses which would addundesiredcomplexity/distractions to theexam scenario. They would alsoplace unplanned and probablyunreasonable workload on theoperators.

Yes

This SDR is expanding thepreviously cited SDRs (VC-TO-45, VCS-TO-54, VCS-TO-58, VC-TO-1 01, and VC-1 502-9) to note that the interactionsbetween the secondary plantand the primary plant duringcomplex plant power changesare impacting SimulatorSAT/ANS/ANSI 3.5 testresults. Those results, thenneed to discuss this imnact.

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June 16, 2015Page 13 of 89

10 CFR 55.45(a)(2): Manipulate the console controls as required to operate the facility between shutdown and designatedpower levels.Doeficiencys Additional InformationDeficiency Deficiency description Significant? Basis provided by licenseeN o . p o i e y l c n e

/Rod performance after IncoreInstrumentation System (IIS) The aggregate impact of

server power losses and events which cause

corrected RX power at >100% perturbations to steady state

steam flow conditions. This SDR conditions in the secondary

expands these issues to include: plant affect the primary plant,

1. Variations in the timing for the as expected. For cases where

transfer from MFW to SFW plant response produces

control valves during re-runs of process parameters that are

tests where a Rapid Power within the deadband of

Reduction actuation occurs controller responses, the

without operator action. system responses can vary -

2. While software modifications as expected.

have significantly reduced thefrequency of Rods Rejecting to In all cases, training scenarios

Manual, inconsistencies in rod and exam scenarios which are

response (documented on other used by the students are

SDRs) persist, including cases validated lAW training

where AO Rod movement and processes. The variances that

Urgent Failures occur. are potentially seen are not

3. SGWLCS control degrades impacting the ability to

significantly as reactor power is successfully train the learning

lowered. This results in control objectives of scenarios or

system induced oscillations in accomplish the expected

many transients where reduction procedural flowpath through

in reactor power or a reactor trip exam scenarios. The impact is

occurs. The timing and in line with the differences

characteristics of these between different license class

oscillations may be very sensitive crews performing the same

to minute differences in initial exam scenario.

conditions. These effects can The SDR is written to track the

propagate back to the primary eventual re-run of these cited

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June 16, 2015Page 14 of 89

10 CFR 55.45(a)(2): Manipulate the console controls as required to operate the facility between shutdown and dpesi~nat~d


power levels.eficiency Deficiency description Significant? Basis Additional Information


side and may cause differences in simulator engineering

test results directly or indirectly by evolutions when secondary

influencing Control Rod response. plant tuning data becomesavailable.

Creates a false indication See previous response to VC-

Prompt jump does not occur associated with reactivity TO-55 above.

VC-TO-55 immediately upon rod Yes manipulations. Potentialwithdrawal/insertion negative training on an

important parameter.Could force exam scenario into This event occurred onceundesired sequence and trigger during Site Acceptance

A rx trip recovery startup to component failure Testing. Additional

VC-TO-89 100%, a hotwell level low alarm Yes assessment(s) and/or operator investigation of this item is in

came in during the ramp up responses which would add progress.

without apparent cause. undesiredcomplexity/distractions to theexam scenario.Common job performance Tmeasure

Time to Boil values in Mode 5 at190F were BAD Q but seemedreasonable values. During a Loss

VC-TO093 of RNS, as temperatures laxincreased the TTB values went Yes

Good Quality, but the value went Currently, there is insufficientto 1.00 E7. This happened as dataentout ther e fu elTcold exceeded 202F data about the expected fuel

conditions for the first fuelcycle at this time. This data isexpected to become availablewhen BEACON data for the

14May 27, 2015

Attachment 5

Westinghouse Non-Proprietary Class 3 VSL.VSG_000306June 16, 2015


10 CFR 55.45(a)(2): Manipulate the console controls as required to operate the facility between shutdown and designatedDower levels. IDeficiency eficiency description Significant? Basis Additional Information

No. provided by licenseefirst fuel cycle becomesavailable. There is also a needto identify the proceduralguidance that will benecessary to input this data,so that the calculations willoccur correctly.

Even when both of these areresolved, an Admin orSimulator JPM to simply lookat the displayed values wouldlack the level of difficultyrequired to allow it to be usedas a valid measure of studentknowledge or abilities. A morecommon admin JPM would beto provide reference materialand have the applicantdetermine their own Time toBoil limit, then apply that togiven plant parameters anddetermine if the limit isexceeded

Malfunction TOS02, Turbine Trip Potentially disrupts operational This SDR documents incorrectFailure, has "future" information in analysis, decision making and information in the "Cause andthe Cause and Effect info. "In action Effect" information of the

VC-TO-96 More Current Baselines"...the Yes malfunction, not anythingPLS will r incorrect in the malfunction as

currently configured in this]a,c That baseline, or in the plant

feature is not functional in BL7 response to the malfunction.

15

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June 16, 2015Page 16 of 89


power levels.eficiency D eficiency description Significant? Basis Additional Information

No. Dfcecdecitog .provided by licenseeand should be removed from the Use of the malfunctionTOSo2 C&E document for this produces the effects that arebaseline.

currently designed to actuate.This does not impact

operational analysis, ordecision making or actions,because the instructor, the

students, and the simulatorare all doing/seeing the planteffects as they currently areconfigured.

Could force exam scenario into Both of these SDRs captureundesired sequence and trigger information noted bycomponent failure Westinghouse before theassessment(s) and/or operator current simulator (design BL7)responses which would add was turned over to the station.

It has been noted that sometimes undesired These items are also

the control rods reject to manual complexity/distractions to the discussed SDR item, VC-TO-

for no known reason. This past exam scenario. 45, in this same section.

weekend the simulator was left in

VC-TO101 run at 100% power (rods in auto) Two Westinghouse patches

VC-TO-104 and ran for the entire weekend. Yes have been installed since thisVC-T0-104 SRwsiiitdOn Monday morning the rods SDR was initiated: Fwere noted to be in manual. Thishas been noted before but it doesnot appear to be connected to ]a,c

any specific operation." It was also discovered thatminor changes in plantconditions at starting pointwhich can be caused byrunning multiple iterations of atesting scenario in an

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Attachment 5VSLVSG-000306

June 16, 2015Page 17 of 89

10 CFR 55.45(a)(2): Manipulate the console controls as required to operate the facility between shutdown and desiqnated

power levels.Deficiencyve. Basis Additional InformationNo. Significant? provided by licenseeautomated "chain" overnightalso affect plant performance- in particular causing minordeviations in r

la,C

Overall changes to simulatoroperating practices whichinclude much more frequentsimulator rebooting has alsobeen implemented along withchanges to "chained" testing.The results have beensignificantly reduced instancesof Rods rejecting to manual atthe station over severalmonths of training andexaminations. The item isbeing let open to continuemonitoring for issues, and totrack any future designhardening improvements.

Potentially disrupts operational See previous response to VC-

VC-T120 Identified and unidentified leak Yes analysis, decision making and TO-9 above.rate always indicates bad quality action

Could force exam scenario into This SDR item is not trackingMSR valve response during undesired sequence and trigger a simulator issue, rather a

VCTO-128shutdown is incorrect and causesVC-TO-128an undesired RS temperature Yes component failure current plant configuration

ranuesiren assessment(s) and/or operator issue which will occur unlesstransient. responses which would add the deadbands, and control

17May 27, 2015

Attachment 5

ouse Non-Proprietary Class 3 VSLVSG_000306Westingh

DRAFT RAIJune 16, 2015Page 18 of 89

10 CFR 55.45(a)(2): Manipulate the console controls as required to operate the facility between shutdown and desimnated

Power levels.II

Deficiency Deficiency descriptionNo.

Significant? BasisT T t

undesiredcomplexity/distractions to theexam scenario.


gains on these controllers arechanged. A procedure changeimplemented in BL7 has stepswhich eliminate the potentialfor this to occur. Updatedcontroller setpoints will alsoeliminate it from beingpossible, even if the procedurewas not followed.

It is highly unlikely that anNRC exam scenario would bewritten which would requirecrews to perform the entireevolution of shutting down theturbine completely, includingthe automatic unloading of theMSRs as a normal or reactivityevolution. This would be anoverly complex "Normal" plantevolution in an NRC examscenario.The unexpected Main TurbineSystem alarm is "LP TurbineDifferential Expansion low 1".The alarm is repeatable.Receiving this alarm is not asimulator modeling issue, or aplant design issue.Currently, the setpoint is lowenough that the alarm value isreached when performing a

Could force exam scenario intoundesired sequence

VC-1411-03Unexpected Main Turbine Systemalarm at [ ]a,c power

Yes

L ______________________________ .1

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June 16, 2015Page 19 of 89

10 CFR 55.45(a)(2): Manipulate the console controls as required to operate the facilitZ between shutdown and designated

nower levels.Deficiency Deficiency description Significant? Basis Additional Information

No. provided by licenseesteady downpower from 100%to [ ]a,c. The alarm valueneeds to be adjusted based onplant data.

SCE&G training is currentlydefeating the alarm so that itdoes not impact operator

training or examinations duringnormal anticipated turbine loadchanges.

Could force exam scenario into Additional investigation of thisundesired sequence and trigger item is in progress.

Rod control urgent failure on loss component failure

VC-1501-08 of EK-12. Appears inconsistently Yes assessment(s) and/or operatorwithout loss of power responses which would addundesired

complexity/distractions to theexam scenario.Could force exam scenario into This SDR was written duringundesired sequence and trigger the performance of thecomponent failure ANS/ANSI 3.5 test to performassessment(s) and/or operator a maximum possible upwardresponses which would add plant ramp rate of 60mw/min.

AO rods move inconsistently undesired This maneuver is neverVC-1 502-10 between tests. Yes complexity/distractions to the expected to be performed in

exam scenario, actual plant operation or intraining settings. The normalplant power increases will belimited [ la,c.

The items are related to the

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June 16, 2015Page 20 of 89

10 CFR 55.45(a)(2): Manipulate the console controls as required to operate the facility between shutdown and designatednower levels.

Defiiec SAdditional InformationNo. Defiienc description provided by licenseeprevious items discussed in

aggregate in this section (VC-TO-54, VC-TO-58, VC-TO-88,and VC-1502-11). Asdiscussed there, the resultinginteractions between thesecondary plant and theprimary plant during complexplant power changes areimpacting test results. In otherwords, the aggregate impactof events which perturbatesteady state conditions in thesecondary plant affect theprimary plant, as expected.This impact is in line with thedifferences between differentlicense class crews performingthe same exam scenario.

The plant is desicined

]a,c. Ifan exam scenario desired toadd a malfunction to rodcontrol so that motion was inthe incorrect direction, or

20

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June 16, 2015Page 21 of 89

10 CFR 55.45(a)(2): Manipulate the console controls as required to operate the facility between shutdown and designatednnwnr lees

Deficiency Deficiency description Significant? Basis Additional InformationNo. D provided by licensee

halted, or a rod was dropped,this can easily beaccomplished by ensuring thata trigger for either AO rods orM bank rods would be met.Either case would exercise thesame abnormal, and considerthe same technicalspecifications.

The SDR is written to track theeventual re-run of these testswhen secondary plant tuningdata becomes available whichis expected to improve thiscondition.

Could force exam scenario into Additional investigation of thisundesired sequence and trigger item is in progress.

RCS wide range pressure component failureVC-1503-03 dropped from 1400 to 700 psig Yes assessment(s) and/or operatorVC-1 503-04 then stabilized. No action taken responses which would add

for 13 min prior to pressure drop undesiredcomplexity/distractions to theexam scenario.?? Are control manipulations This SDR was initiated toand/or verifications done from document and track to closurethis panel or is it indication the delta between fidelity of

The MCR fire control panel is not only?? simulator layout to controlmodeled on the simulator room layout. No control

manipulations or verificationsare required to be done on thispanel.

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June 16, 2015Page 22 of 89


nower levels.Deficiency DAdditional InformationNo. D Significant? Basis provided by licenseeThe next iteration of plant

design is expected to removethe Fire Panel from the controlroom entirely, to the roombehind the rear wall of thecontrol room.

Defeats purpose of safety See previous response to VC-V1503-24 Frequent invalid yellow path on Yes function alarm (high awareness 1503-24 above.

-- subcriticality function. and possible response to safetyfunction challenges)

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June 16, 2015Page 23 of 89

10 CFR 55.45(a)(3):

Identify annunciators and condition-indicating signals and perform appropriate remedial actionsm

where appropriate.

10 CFR 55.45(a)(3): Identify annunciators and condition-indicating siqnals and perform appropriate remedial actions whereapprop~riate.DeficiencyDef Additional Information

No. Deficiency description Significant? Basis provided by licenseeUser Defined Alarm Limits do not Possible challenge to exam Although any user defined

clear on RESET of an IC. They security as well as potentially alarm limits do not

stay at whatever value an disrupting operational analysis, automatically reset when an

operator has placed them in a decision making and action Initial Condition (IC) is

previous training session. The "RESET", there is a search

event is not captured in any capability currently being used"action" log so it will be very in Ovation, which allows the

VC-TO97 difficult for an instructor to keep Yes instructors to search for eachtrack of which limits are changed user alarm limit which was

and restore them to default. (and changed during a training

limiting on students if it is not session, and return them all to

allowed), default values.

The result is no challenge toexam security, operationalanalysis or decision making

The current high Alarm function supports event As currently modeled, the

setpoint/deadband combinations diagnostics alarms will actuate when

for containment radiation alarms appropriate, which provide the

do not allow for the high-1 and primary indications for

high-2 alarms to clear. The alarm responding to degrading

VC-TO-1 17 reset values are above the alarm Yes conditions. For the relatively

setpoint values and will not work short time frame (2-4 hrs) of

correctly training and examinationscenarios, and considering thetypes of events which wouldcause these alarms (e.g.: fuel

23May 27, 2015


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June 16, 2015Page 24 of 89

10 CFR 55.45(a)(3): Identify annunciators and condition-indicating stgnals and perform appropriate remedial actions where

anorooriate.eficiency D eficiency description Significant? Basis Additional Information

No. provided by licenseefailures, RCS leak, LOCA),and the relatively low setpointof these alarms, conditionswhich actuate the alarms

would not be expected to clear

during the scenario.

Additionally, the radiationvalue is also provided to theoperator in APS with thealarm. This can be used toquickly start a trend of thevalue to use for diagnosticpurposes.

When the Map and Migration ?? This SDR item does notTools are set up so that each impact operator training orindividual datalink has a unique examination.entry in the configuration, thedigital alarm points respond VCS is currently using APPincorrectly when datalink failures files to perform mostare inserted. malfunctions/overrides, which

VC-TO-1 34 If a failure is inserted on the last is an alternative way to get to

Orig. list datalink listed in the ?? the same results as usingduplicates this AsvDataLinks.xml file from the scripted malfunctions in the j-

deficiency# datalink package, all of digital station.

alarm points will go into alarm. Ifa failure is inserted on any other This is not impacted by thisdatalink in that AsvDataLinks.xml problem statement. This onlyfile, none of the digital alarm impacts the ability of thepoints will go into alarm. The simulator engineeringexpected response is that only organization to create andthe digital alarm point associated move new alarm points

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June 16, 2015Page 25 of 89

10 CFR 55.45(a)(3): Identify annunciators and condition-indicating signals and perform appropriate remedial actions whereal ro riate.Deficiency.

Additional Information

No. Deficiency description provided by licensee

with that datalink will go intoalarm when a datalink failure isinserted.Unexpected Main Turbine Could force exam scenario into See previous response to VC-

VC-1411-03 System alarm at [ ]a,C power Yes undesired sequence 1411-03 above.

Can't open Signal Diagrams from ?? Is this needed for Use of this functionality in APS

an alarm history in APS. The diagnostics?? is not required to diagnose

cbViewer opens but nothing is plant events and to perform

there the cause and effect level oftriage that is required toprosecute the ARP, AOP. andEOP Drocedures. r

VC-1411-08 ]a,C

If additional diagnosis iswanted by an operator, anysignal diagram needed is alsoimmediately available from theOvation control screens, and

are accessed at the other 3workstations at each operatorsdesk.

Inconsistent non-urgent failure Could force exam scenario into See previous response to VC-

VC-1411-09 alarms on loss of ES-1 Yes undesired sequence and trigger 1411-09 above.component failureassessment(s) and/or operator

25May 27, 2015


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June 16, 2015Page 26 of 89

.4f~ f~D rr ~ ~ ,rn1ma,.i~a#r~rc ~nrl rnndifinn~indiP.Qfintl ~inn~Iirc Rnd n~dnrm .nnrnnrisaf~ mmc.rliAI ~finn~ wh.~irca I U '.jrr~ ~ IL5~IIL55 V ~.................................

approDriate.Deficiency Deficiency description Significant? Basis Additional Information


responses which would addundesiredcomplexity/distractions to theexam scenario.

+ t ISeveral tests have resulted inPMS division fault alarms. Noway to tell if alarms are valid or ifthe correct input caused it.

The simulator exhibitsinexplicable panel indicationsduring the evolution execution.Could force exam scenario intoundesired sequence and triggercomponent failureassessment(s) and/or operatorresponses which would addundesiredcomplexity/distractions to theexam scenario.

I

VC-1411-11 Yes

The "PMS [ ]a,calarms" that were generatedduring these tests arefunctionina correctly. r

]a,c

One key sentence was omittedwhen the Deficiencydescription was added to thislist from the original SDR list.That was: "The AlarmResponse Procedure for thisalarm states F

]a,c. The orocedurewhich is cited. [

]a,o, has not yet been releasedto the site. This SDR istracking a [

]a.c when the procedure

26May 27, 2015


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June 16, 2015Page 27 of 89

10 CFR 55.45(a)(3): Identify annunciators and condition-indicating signals and perform appropriate remedial actions whereappiropri ate.DeficiencyD

Additional InformationNo. Deficiency description Significant? Basis provided by licenseeis obtained.

There are no erroneous panelindications, or impacts tooperator response caused bythese expected alarms.

WPIS-4 (APS Secondary ??How bad is the shaking? This monitor display hasDisplay) - is "shaking", not totally Does it interfere with the ability stopped shaking, and has

VC-1411-13 cutting out but it does have a ?? to reliably read indications?? been trouble free for > 2distracting connection. months. The SDR is open to

monitor for repeat problems.

Rod control urgent failure on loss Could force exam scenario into Additional investigation of thisof EK-12. Appears inconsistently undesired sequence and trigger item is in progress.without loss of power component failure

VC-1 501-08 Yes assessment(s) and/or operatorresponses which would addundesiredcomplexity/distractions to theexam scenario.

Alarm response after certain Alarms place unplanned and While over 2,000 alarms areevents is difficult due to the probably unreasonable workload reached in some scenarios,number of alarms that are on the operators. Could force not all of these alarms are ofreceived, over 2 thousand in exam scenario into undesired the same priority. In mostsome scenarios. sequence and trigger cases, the number of

VC-1503-16 component failure significant priority 1 red alarms

VC-TO-129 Yes assessment(s) and/or operator are equal to or less than thatresponses which would add typically received in the controlundesired room of an existing fleet unit.complexity/distractions to theexam scenario. Furthermore, the APS system

provides much more readyinformation about any alarm

27May 27, 2015

Attachment 5


DRAFT RAI

VSLVSG_000306June 16, 2015Page 28 of 89

10 CFR 55.45(a)(3): Identify annunciators and condition-indicating signals and perform appropriate remedial actions where

annropriate.eficiency D eficiency description Significant? Basis Additional Information

No. provided by licenseethan the standard existina fleetolant. f

]a,c Noneof these features are availableat any existing fleet plant.

Currently operators are trainedand examined to r

]a,c Inaddition, Operations rules ofusage are established that set

28May 27, 2015


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June 16, 2015Page 29 of 89


annranriate.

Deficiency Deficiency description Significant? Basis Additional Information

No. I I I provided by licenseeexpectations for addressingalarms in order of p)riority:

la~c

There are multiple indicationswhich are received when a [

]a,c SO

ample indication and time areavailable for operatordiaanosis.

lac, butit lacks clarity - which this SDRhas identified. r

-+ -4 -4

No alarm is received for r

]ac

Could force exam scenario intoundesired sequence and triggercomponent failureassessment(s) and/or operatorresponses which would add

undesiredcomplexity/distractions to the

exam scenario.

VC-1 503-31 Yes

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10 CFR 55.45(a)(3): Identify annunciators and condition-indicating siqnals and perform appropriate remedial actions wheren nnrnnrintf__

approriat

DeficiencyNo. Deficiency description Significant? Basis Additional Information

provided bv licenseeNo.

I-

1~~"ac" light on

Mode 5/6 Critical Safety FunctionStatus Tree" for Mode 5/6 doesnot update to green when RCSTemoerature is stable for

]ac

-+ i

Potentially disrupts operationalanalysis, decision making andaction

This SDR is tracking adecision to either (1) make aprocedure change to provideoperator prompts to inputrequired information in orderfor the current calculation towork, or to change the CSFtree logic and display. Thesimulator is operating as therplant is currentlv desianed. fVC-1504-03

(Not ondocketed list)

Yes

30May 27, 2015

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DRAFT RAI

VSL_VSG 000306June 16, 2015Page 31 of 89


appropriate.Deficiency Deficiency description Significant? Basis Additional Information

No. Provided bv licensee

]a,c There is currentlyno procedure direction toprovide this input at this time.

31May 27, 2015


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10 CFR 55.45(a)(4):


June 16, 2015Page 32 of 89

Identify the instrumentation systems and the siqnificance of facility instrument readings.

10 CFR 55.45(a)(4•: Identify the instrumentation systems and the sicmnificance of facility instrument rPardinnz•_10 CFR 55.45(a)(4): Identifv the instrumentation svstems and the sianificance of facilitv instrument readin-

eficiency De Significant? Basis Additional InformationNo. Deficiency description Snit provided by licensee

Setpoint for the WLS Degassifierair pumps (WLS-V028A andV028B) are set to [ ]a,c inturnover IC. This value was notenough to maintain constantletdown flow of [ ]a,c gpm.Degassifier level was cvcling atHigh-1 Setpoint of [ ]a.•causing LTDN valves to closeuntil level alarm cleared.


VC-TO-1 6 Yes

The controller setpoint set inthis simulator IC can always beadjusted by the crew asdesired when initiating letdownflow - which is not normally inservice in the AP1 000 plantdesign. An SDR item has beeninitiated to track a potentialchange to the plant SystemOperating Procedure whichwould increase the initialsetting on this controller sothat a greater initial letdownflowrate could be establishedbefore manipulations to thecontroller are performed. If thisis changed, then theassociated ICs would, then,also need to reflect thischange when it is issued.

[] do not reflect what is shownon PMS Node Boxes.

VC-TO-28 Yes

Could force exam scenario intoundesired sequence and triggercomponent failureassessment(s) and/or operatorresponses which would addundesiredcomplexity/distractions to theexam scenario.

-t The primary operator interfacebetween PMS status and thecrew is the r

32May 27, 2015


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10 CFR 55.45(a)(4): Identify the instrumentation systems and the significance of facility instrument readings.

DeficiencyNo.

Deficiency description Significant? Basis Additional InformationProvided bv licensee

]a,c Not all of theinformation for changes tostatus is provided on themimics. This is not a simulatormodeling limitation, it is thecurrent plant design.

All necessary information tooperate and evaluate the plantstatus is available on PMS,and this indication is expectedto be used as the primaryindication by the crew.

This SDR is tracking anenhancement to include therest of the specific channelinformation on Ovation.

RCS-101 calls for checkingVariable Frequency Drivetransformer temperatures prior toclosing CCS-V500. Points don'tappear to be available.

Cannot complete proceduraldirection due to missingindication.

The current RCS SOP [

VC-TO-51 Yes]a,c It does not

specify a point to use, or avalue to check it less than. Italso does not specify if theinformation should beperformed via local readings orusing the limited information

33May 27, 2015


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10 CFR 55.45(a)(4): Identify the instrumentation systems and the sicmnificance of facility instrument readincs.I

eficiency Deficiency description Significant? Basis Additional Information

No. provided by licenseewhich appears to be availablein Ovation, but is currently not

displayed on any graphic.

Currently, this information isprovided to the candidate by

an instructor prompt acting asa field operator.

This SDR is tracking a

potential required update tothe simulator/plant if a point ischosen to evaluate which canbe added to an Ovation screen

Turbine Control valves are open [ Knowledge of CV position is See previous response to VC-

]a,, looking at the sianal necessary early in E-0 (RNO TO-56 above.

diagrams, but indicating [ step) to ensure the Main Turbine

VC-TO-56 ]a,, on graphic 50211. OPS Yes is tripped if all the MSVs are not

should not be forced into a signal closed.diagram to get a value neededfor any procedure.VRS monitor and VHS monitorgo up by [ ]a,c decades in[],, minutes on a loss of processflow. This gives a pri 1 alarm andleads to an unnecessary entryinto AOP.


This event occurs during aprolonged loss of power to theassociated power supplies forthese HVAC systems. Duringany electric plant malfunctionthere are also numerous othersvstem alarms which actuate,

VC-TO-75VC-TO-76

Yes

]akc Crews are required

34May 27, 2015


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Attachment 5VSL.VSG_000306

June 16, 2015Page 35 of 89



No. provided by licenseeto use the same skill setemployed at existing fleet plantto diagnose the aggregate of

these alarms, and diagnosethe loss of power supply.Once that is accomplished, thecrew will then prioritize their

response by deciding whichAOPs will be used, as well asthe order they will beaddresses.As currently configured, thereis not enough data to conclude

that the rad monitors responseis incorrect. Given this, thecrews are expected to respondas described: treat this as areal indication and prioritizethe crew response accordingly,while continuing to address toloss or power supply.

The purpose of this RITS is to Could force exam scenario into This SDR tracks a question

evaluate the calculation of the undesired sequence and trigger originating from Westinghouse

BEACON operability Ovation component failure staff members while preparing

points within the reactor core assessment(s) and/or operator for ISV to evaluate adding

model. There is concern that the responses which would add additional functionality in the

VC-TO-1 02 fidelity of the current calculation Yes undesired simulator to the "calculated"is sufficient for training purposes. complexity/distractions to the plant comouter ooint which IDuring failure testing of the BDP exam scenario.application a potential situationwas noted relative to the ]na,coperability status points and how The Westinghouse staff was

35May 27, 2015


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No. provided by licenseeit is calculated. Failure of the concerned that they did notBDP application causes the have enough ways tomanual override signal originated manipulate this point to make itby BDP to have BAD quality. The show bad quality,BAD indication is passed through INOPERABLE, etc. In otherthe BEACON operability words, adding additionalcalculations in the PST malfunctions or overrides thatapplication and appears impact this point - or theon the OPDMS displays as datalinks points that feed this""operable"" but with BAD quality, point.Failure of the BDP application Currently, for any point whichshould cause BEACON to be is within the scope of theinoperable via the logic in simulator, e.g. these NAPsBEACON input processing. points inputting to OPDMS, aAs part of the investigation of this change to the status of thoseissue a concern was raised as to points will correctly changehow the reactor core model OPDMS Operability. VCS cancalculates the BEACON cause OPDMS to becomeoperability points. The reactor INOPERABLE whenever thatcore model currently simulates all is required for training orBEACON / BEACON datalink evaluation.outputs. The real BEACONexecutables have logic that isused to determine operability thatis based on tech specrequirements.Wall Panel Indication System Potentially disrupts operational This SDR documents a one-trends went blank analysis, decision making and time event that occurred in

VC-1 409-1 Yes action Sept of 2014. Since that eventa change has beenimplemented to SimulatorOperation at the station which

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10 CFR 55.45(a)(4): Identify the instrumentation systems and the sianificance of facility instrument rendinaz_

10 CFR 55.45(a)(4): Identify the instrumentation systems and the significance of facilitv instrument readinri-c

eficiency Deficiency description Significant? Basis Additional InformationNo. provided by licensee

includes a scheduled regimentof simulator reboots andresets. No repeat of this eventhas been noted, so it is beingevaluated for closure.

Random DAS indications showed Potentially disrupts operational Two instances of this wereFAULT and then returned to analysis, decision making and observed on 2/10/15 on the 2Anormal within a few seconds. action simulator. The problem wasOPS crews have reported a few corrected by re-booting theinstances of the same thing Trainer (Instructor interface).

Two Westinghouse patches

VC-1410-11 Yes have been installed since thisevent was observed: r

]a,c The SDR remainsopen while investigating thecause, and monitoring that thecorrection has fixed theproblem.

Calorimetric power data points do Common job performance This SDR documented a GOPnot have required precision. measure procedure step which requires

]a,c TheVC-1411-06 Yes point as currently displayed onthe DDS control screen only

displays whole numbers, sothe operator is required to pullup the point information byright clicking the point, in orderto see more significant digits.

37May 27, 2015


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Dficiency EDeficiency description Significant? Basis Additional Information

No. D i provided by licenseeThe SDR is tracking animprovement to the DDSdisplay to include one moresignificant digit.

There is no impact to theability to perform a manualCalorimetric, which would be acommon JPM associated withthis item

WPIS 9 developed an orange tint ?? Does the orange tint affect This item is now closed. WPIS

VC-1411-10 on the entire screen. ?? readability? panel 9 has been replaced on5/8/15.

Steady state testing indicated SG The simulator exhibits a No mass/energy imbalances

press, TB 1 st stg press, and RCS mass/energy imbalance in were identified in this SDR.

loop flows were out of tolerance. violation of ES-302 This SDR item documented

Cause is believed to be RCS that the initial Site AcceptanceFlow in the simulator below what test for Steady State startedis assumed in the design. and ended with the identified

items out of bounds. This wasdone to obtain comparisoninformation for a similar

VC-1501-10 Yes Factory Acceptance test doneat westinghouse. The test hasbeen re-run with theseparameters adjusted to bewithin bounds at the start ofthe test. In the retest all RCSDNB parameters; PzrPressure, RCS Tavg, RCSflow rate, matched the design

as stated in COLR item 2.12.1,

38May 27, 2015


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F10 CFR 55.45(a)(4): Identify the instrumentation systems and the siqnificance of facility instrument readinas.

Basis Additional Informationprovided by licensee

which has been inspected inthe NRC 41502 inspectionactivity conducted on site. Thisitem is open to track aremaining question to thevendor to understand if RCSflow is low in the band.

MB and MC rods are reversed onGraphic 1805

Potential to confuse rod dropdiagnosis particularly if this isprimary indication

The primary indication fordiagnosing Rod drops, orpotential Rod Positionindication problems is theWPIS araDhic r

]a,c The depiction ofwhich rods are assigned towhat bank is correct on thisscreen. The graphicreferenced in this SDR, 1805,is only used by the operatorwhen lookina for DRPI alarms

VC-1 501-05 Yes

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10 CFR 55.45(a)(4): Identify the instrumentation systems and the significance of facility instrument readinqs.

I IDeficiency

Nn. Deficiency description Significant? BasisAdditional Informationprovided by licensee

1ArNo -

L _______________________________________________________ I- + -I-

VC-1502-16

The MWt point provided by WECto be used in all Steady Statetests is DDS-PPP11-AVO.Ovation Point Information is ableto display this point with a value,and the point is able to bequeried and added using bothJRTT and MP tools on JStationbut no value is displayed, rathera-.

Parameter designated for use intests. It is unclear how testswere completed sat without theindication.

I

Yes]acThis SDR

is tracking a fix to the ability toalso be able to see thisinformation directly at theJStation.

I IManually tripped the reactorfollowing indication that shutdownbank 3 indicated 265 steps.


VC-1 503-17 Yes

This SDR item captures acondition encountered by onecrew during ISV testing. Theypulled a shutdown bank ofrods out 1 step past thedirected position during areactor start-up evolution. Atthat time, there was noprocedure guidance for what todo, therefore the crewconservatively chose to trip thereactor and start the evolutionagain. VCS has now updatedthe GOP to provide direction inthis event. The SDR is writtento track the long termdisposition of this item in BL8rprocedures.

___________ .1 ______________________________ -,

40

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10 CFR 55.45(a)(5):

Observe and safely control the operating behavior characteristics of the facility.

10 CFR 55.45(a)(5): Observe and safely control the operating behavior characteristics of the facility.

eficiency D eficiency description Significant? Basis Additional Information


Jstation Monitored Parameter ??is this simulator feature used This function is not required to

display does not update at times. to support exams?? support examinations orDuring a RCS Boration we were There are a number of deficiencies that training.

follow that we think are support functions formonitoring RCS boron and it the simulator operator. It is not clear which

showed no change after a 500 are needed to ensure scenarios run as Any plant parameter can begallon boration. designed and which are informational. We trended in the simulator boothhave personnel with simulator expertise

evaluating these deficiencies but will not work stations, just like in thehave their results within the time we plant or simulator. This

VC-TO-1 5 ?? committed to issue this RAI. additional functionality is

helpful to the simulatorengineering staff, duringtroubleshooting, but is notnecessary for the reason citedabove. Additionally, it is notused by instructors duringtraining or examinations.

Jstation JRTT function is very ??Is this visible to the This function is not required to

sluggish at times, both when operators? support examinations or

accessing a previously built training.

TREND or adding points to anopen TREND file. This condition Any plant parameter can be

VC-T0-27 seems to get worse each day the ?? trended in the simulator boothsimulator is running. work stations, just like in the

plant or simulator. Thisadditional functionality ishelpful to the simulatorengineering staff, duringtroubleshooting, but is not

41May 27, 2015


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10 CFR 55.45(a)(5): Observe and safely control the operatingq behavior characteristics of the facility.

Deficiency eficiency description Significant? Basis Additional Information


necessary Tor me reason citedabove. The functionality is notused by instructors duringtraining or examinations.

Additionally, a schedule ofdaily and weekly resets of keysimulator hardware has beenimplemented since thisproblem was noted, whichappears to have mitigated thisissue. It is currently beingmonitored for closure.

When SLIDING from 100 to 0%on Jstation LOA for valveoperation popups, the Slide LeftValue is not "0" in severalinstances. On several LOAs thevalue goes to an exponentialvalue (2.75855e-12 for example)and shows that value onfeedback

??Is this simulator feature usedto support exams??

I

VC-TO-31 7?

This feature is not used tosupport exams. If utilized, thefeature would be mostcommonly used to build appfiles.The booth operators also canchoose between two methodsto change valve position: 1)use the slide feature or 2) typethe required valve position indirectly (e.g. "0").In either case, any of thoseapp files built would bevalidated in all cased, andvalidated + SBT for anyrequlatorv exam.

[

lax

1- hour heatup rate not on This indication is operationallyVC-TO-41 graphic Yes significant in that operators

could potentially violate Tech

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No. provided by licenseeSpec Heat Up Rate limits.

This SDR item is tracking anoperator preference request toadd the 1 hr heatup rate to thedisplay. Additionally, the 1hour heat up rate can betrended by the operator, usingthe existing Ovation trendingcapabilities.

SGWLC at 90% Power not Affects job performance The SDR is documenting a

Stable. Heat balance at 90% measure. Simulator exhibits a swing in FW flow at 90%

could not be performed. SG total mass/energy imbalance. power that is interfering withFW flow was BAD Q due to FRV the plant obtaining anoscillations extremely constant value with

less than a 0.015 Mlbm/hrswing which will allow the HeatBalance to be performed. Theminor swing is caused by asmall amount of hunting of theFeed Regulating Valves.

VC-TO-63 YesThis SDR does not documenta mass/energy balance issue.

The ability to watch the plantautomatically perform a heatbalance would not be ofsufficient difficulty to be usedas a JPM. Manuallyperforming a Heat balance,given plant data, is a commonJPM which is often performed

43May 27, 2015


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Additional InformationDefiDeficieneficiency description Significant? Basis provided by licenseeN o . p o i e y l c n eas an Admin JPM. This activity

can be accomplished with noimpact from this SDR.

During investigation of VC-TO-67, ??Is this simulator feature used This is a diagnostic tool usedRod movement issues, we to support exams?? for the simulator engineeringbacktracked and attempted to group which is not used foruse Replay. When Replay was training or examination.chosen, the "Pause, Start,Terminate" buttons would This function is different thatilluminate for a second then go "Backtrack", which is useddark. We stopped and started

during training. The use ofthe trainer and tried again with "Backtrack" is specifically notsame results. allowed during the conduct ofNRC Exams (NUREG 1021,ES-302, 3.q. -page 12).Replay would allow aninstructor to return the

VC-TO-68 ?? simulator to some previouspoint (using backtrack), thenreplay the crews' activitiesduring the event.

The closest parallel to this ascompared to exam or trainingactivity would be the use ofSBT to record crewperformance - along with theuse of video taping of ascenario. While neither one ofthose are required either, theyboth can be accomplishedindependent of this SDR item

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Deficiency [Deficiency description Significant? Basis Additional Information

No. I I provided by licenseeOvation control cabinets are tohave independent primary andsecondary power supplies asspecified in APP-PLS-J4-007,Rev 4. (AP1000 Plant ControlSystem and Data Display System- System Design Specification) -See Table 10.1-1. NSSS CabinetPower Assignment. PRS testinguncovered multiple instanceswhere Ovation controllersexperienced complete loss ofpower upon loss of a SINGLEEDS division. Each total loss ofan EDS division failure results inan unanticipated plant transient,accompanied by hundreds of lostindications and an alarm flood.(noted as a plant design issue)


This SDR was written toinvestigate the currentdifference between how theprimary and alternate powersources for the Turbine Islandovation control cabinets werechosen, as compared to theNSSS ovation controlcabinets. r

]a,c

NSSS cabinets are notaffected by this SDR. In ALLCASES for the Turbine Islandcabinets affected, for the endstatement concerningunanticipated plant transients,etc. to be true, r

VC-TO-71 Yes

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Significant? BasisAdditional Informationprovided by licensee

]a,c

Part of this SDR statementwas truncated when it wasadded to this list. The originalSDR statement also includesthe following statement whichprovided an example of thisconfiauration:r

1a,C

I

1a,c

r

]a,c

I

46May 27, 2015


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I I IDeficiency Deficiency description

No.Significant? Basis

F t t

Additional InformationProvided bv licensee

]a,c

This is not a simulator issue.The simulator is wired asstated in the design, and thedesign is allowed. Thequestion being tracked is aconcern about in the impact ofthis plant design to outageflexibility and ultimatesecondary plant hardiness thatwas identified during simulatorperformance observation.

As currently configured thereare some combinations ofmultiple power supply losses(both AC and DC sources)that will make the plantrespond as described above.Any training exercise orsimulator demo exam thatincluded that complexcombination will have to bevalidated and/or undergo SBTto validate the expectedplant/crew response.

VC-TO-72

i. 4??Is this simulator feature usedto support exams??

r??

47May 27, 2015


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Attachment 5VSL VSG 000306

June 16, 2015Page 48 of 89

10 CFR 55.45(a)(5): Observe and safely control the oneratina behavior characteristics of the farcility.10 CFR 554(a() Obev an sael control.

........ th prtn¥eaircaaceitc.ftefcft

Adiioa InomtoDeficiency Deficiency description

No. ISignificant? Basis

-t 4


]a,c

This is not a simulator featureused during exams or training.

]a,c- A loss of EDS 1 (for example)results in all shared sensor inputsfor PMS A and C that arehardwired inputs to PLS to goBAD. Any previous or subsequentfailure on any instrumentation orcomponents used in the non-affected PMS divisions wouldforce associated PLS controlsystems into MANUAL. (noted asa plant desiqn issue)Jstation sometimes remains ??Is this simulator feature used This feature is not used duringOPEN when Stop Trainer is to support exams?? Exams, only during start-upperformed from the ISS. Trainer and shutdown of simulator. Itdoes stop (based on Ovation and is easily addressed as noted inPMS indications). Jstation the deficiency description, and

VC-TO-100 windows do not close. The ISS ?? does not impact the students.was rebooted and a Start Trainercommand was issued. It flashedup a command window whichimmediately closed and trainerdid not start. The P drive had ared X on it when viewed.. .once

48

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10 CFR 55.45(a)(5): Observe and safely control the operatincq behavior characteristics of the facility.

Deficiency Deficiency description Significant? Basis Additional Information


you clicked on it the red X wentaway. Start trainer was thendone successfullyThe purpose of this RITS is to Could force exam scenario into See response to VC-TO-1 02

evaluate the calculation of the undesired sequence and trigger above.

BEACON operability Ovation component failurepoints within the reactor core assessment(s) and/or operatormodel. There is concern that the responses which would add

fidelity of the current calculation is undesiredsufficient for training purposes. complexity/distractions to theDuring failure testing of the BDP exam scenario.

application a potential situationwas noted relative to theoperability status points and howit is calculated. Failure of the BDPapplication causes the manualoverride signal originated by BDP

VC-TO-102 to have BAD quality. The BAD Yesindication is passed through theBEACON operability calculationsin the PST application andappearson the OPDMS displays as""operable'" but with BAD quality.Failure of the BDP applicationshould cause BEACON to beinoperable via the logic inBEACON input processing.As part of the investigation of thisissue a concern was raised as tohow the reactor core modelcalculates the BEACON

49May 27, 2015


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Deficien Significant? Basis Additional InformationNo. Deficiency description provided by licensee

operability points. The reactorcore model currently simulates allBEACON / BEACON datalinkoutputs. The real BEACONexecutables have logic that isused to determine operability thatis based on tech specrequirements.DDSOIA/B currently do not ?? This SDR documented a

function malfunction to fail the VX80,which provides an interfacebetween the plant computersand the control room. It onlyaffected the Westinghousesimulators, because thosesimulators do not have theVX80 switch installed (likeVCS).

VC-TO-108 ?? The VCS simulators can fail

the VX80, but can't recoverthem at the instructor J-stationwithout using APP files, orresetting them locally in thesimulator computer room.

This SDR item is being trackedas an eventual fix and retest at

the Westinghouse facility,which will then beimplemented at VCS.

VC-TO-109 WPNS and ROPCS Configuration ?? ?? These components are

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10 CFR 55.45(a)(5): Observe and safely control the oneratincg behavior characteristics of the facility.

Deficiency Additional InformationNo. Deficiency description Significant? Basis provided by licensee

files incorrect configured correctly at VCS. Itis tracking an eventual fix andretest at the Westinghousesimulator facility.

The Monitor Parameters (MP) ??Is this simulator feature used This feature is not being useddisplay on the JADE Instructor to support exams?? to support exams or training.Station stops updating on The feature is only used as anunselected tabs after about 2 ancillary way to monitorminutes. scenario activities in the

VC-TO-1 10 ?? simulator booth. 100%monitoring and trendingcapabilities are also availableusing the ovation work stationsavailable in the simulatorbooth.

Ovation CLF names on the ISS ??Is this simulator feature used This SDR item does notdo not match the cause and to support exams?? impact operator training oreffect names examination.

VCS is currently using APPfiles to perform mostmalfunctions/overrides, whichis an alternative way to get to

VC-TO-1 14 ?? the same results as usingscripted malfunctions in the j-station. This is not impacted bythe SDR problem statement.

Additionally, this SDR waswritten to identify thetypographical errors betweenthese two documents, not

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Additional InformationDeficiency Deficiency description Significant? Basis provided by licensee

about problems with thefunctions themselves.

The following component level ?? This SDR item does notfailures as defined by APP-STS- impact operator training orJ4-025 could not be found on the examination.simulator to verify the C&E hadbeen correctly loaded and VfS is currently using APPavailable at the instructor station. files to perform most1" malfunctions/overrides, which

VCTO-1 15 ?? is an alternative way to get tothe same results as usingscripted malfunctions in the j-station.

It seems that it is possible for the ?? This is a diagnostic tool usedtcpip command memory mapper for the simulator engineeringprogram to stop working, but the group. It is not used forexecutable still shows up in task training or examination. Themanager. There appears to be no ability to conduct training orlog files generated from it and examination is not impacted bythere is no way to tell that it this-SDR item.

VC-TO-121 stopped functioning other than ??points-assigned to controllers donot time out when the controllersare failed. It was also noted thatthere was not a TCP CommandMemory Mapper option in theTRAC system to create a TRACissue-for this.

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Deficiency Significant? Basis Additional InformationNo. Deficiency description provided by licensee

On PMS displays, divisions C and The deficiency states it can lead The display configuration wasD the circled box does not ever to an error likely situation changed between Simulatoraet an X in it. [ Factory Acceptance Testing,

when this item wasdocumented, and installationat the site. These items

la,c). As noted by the currently have an "N/A" incustomer on the simulator, having those fields which will not

VC-TO-122 this box on these divisions when Yes change state in that division.it is not driven does not makesense and could lead to an error This potential error likelylikely situation. situation does not exist at

VCS. This SDR item is beingheld open because a furtherchange to this graphic andconfiguration is beingconsidered for design BL8.

When attempting to view an SBT ??Is this simulator feature used This is a diagnostic tool used"history" report on the PMC to support exams?? for the simulator engineeringstation, it is observed that all group, not something used for

VC-TO-123 open JADE windows close (Jade ?? training or examination. Thecrashes) and JStation needs to ability to conduct training orbe restarted on the PMC. This examination is not impacted bydoes not occur when viewing this SDR item.SBT history reports on the ISS."HART modem" CLFs can befound on the simulator when theyshould not be there. f

VC-TO-124

This is a diagnostic tool usedfor the simulator engineeringgroup, not something used fortraining or examination. Theability to conduct training orexamination is not impacted bythis SDR item.

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10 CFR 55.45(a)(5): Observe and safelv control the operatinq behavior characteristics of the facility.


"Profibus port failure" CLFs can ?? This SDR item does notbe found on the simulator that impact operator training orshould not be there. r examination. VCS is currently

using APP files to performmost malfunctions/overrides,

VC-TO-1 25 ?? which is an alternative way to

la,c get to the same results asusing scripted malfunctions inthe j-station. This is notimpacted by this problem

statement.The power-on-connections file for ?? Is this simulator feature used This SDR documents aVX80B has the wrong destination to support exams?? labeling issue for simulator

port for the WPIS Repeater, it hardware noted during0should be 50, not 59. ?? installation, which was noted

VC•TO 30 s by simulator engineers when

installing/re-configuring thesimulator. It does not impactsimulator functionality.

On SDS-4 on 6/25/2014 after ?? This SDR item occurred oncehaving placed the simulator in at the vendor facility prior toFREEZE at 23:54 real time (as simulator delivery at VCS. Itindicated on the ISS) a backtrack has not been observed here,was performed. The backtrack IC and is being being trackedreset into had a real time of 22:07 until final closeout by the

VC-TO-132 as indicated on the ISS. Once the ?? vendor.simulator was reset into thebacktrack IC and placed in RUN,it was observed that the timedisplayed on Ovation indicated04:03 6/26/2014. This wasunexpected. It is noted that the

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eficiency Deficiency description Significant? Basis Additional InformationNo. DfcecdecitoSinfcnprovided by licensee

simulator was continuously

running the duration of the shiftand that the only simulator resetperformed prior to backtrackingwas at the start of the shift (at15:00).Upon rebooting drop160 to clear ?? This SDR item occurred at the

out and restart the historian, a vendor facility prior to

number of pointnames of the type simulator delivery at VCS. It

DROP* show up as Invalid. has not been observed here,

These drop points should not and is being being tracked

exist on the simulator since they until final closeout by the

are for drops that we do not have vendor.

VC-TO-133 on the simulator due to the ??simulation of their logic. However,it does not seem appropriate forthem to show up as "InvalidPointname DROP*" in theOvation Error Log on drop160,since they shouldn't be there inthe first place.The instructions in APP-STS- ?? This SDR documents a

GEY-013 Rev 1 need to be simulator firmware installation

modified to reflect the following procedure error was noted

change: during installation by simulator

Section 4.7.3, Step 7 (E0 and El engineers when installing/re-

VC-TO-138 Attribute Update Script) should be ?? configuring the simulator to

performed after Section 4.7.4, BL7. It does not impact

Step 7 (Load all drops - First simulator functionality. It is

Time). being tracked until final

In addition, another step should closeout by the vendor.

be added to Section 4.7.3 after

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Step 7.e (Searching for Errors inthe log file). The new step shouldbe "Confirm all of the intendedpoint fields were updated bysearching the file for the line "0rows updated". Step 7.f should beupdated to say "If there are errorsor rows that were not updated..."JRTT points did not collect if they ?? This is a diagnostic tool usedwere not model variables. Any for the simulator engineeringpoint using OVA or DAI/DDI, etc group, not something used forinputs did not have good data. training or examination. The(Instead they read ability to conduct training or3.4028235E+38) The same examination is not impacted by

VC-1409-2 tests were run the previous day ?? this SDR item.and worked ok. Any test that hadNO model variable in the .tvl filehad NO data collected. If the filehad ONE model variable it wascollected correctly and the otherswere 3.4028235E+38During overnight testing an EXEC A freeze state occurs during a This SDR documents a one-FAILURE occurred. MALF-3-7, scenario, or a "Beyond time event that occurred inLoss of ES-2, was in progress, simulated limits" alarm is Sept of 2014. Since that eventFAIL occurred at 6:04 point, received on the instructor's a change has been

station implemented to SimulatorVC-1 409-6 Yes Operation at the station which

includes a scheduled regimentof simulator reboots andresets. No repeat of this eventhas been noted, so it is beingevaluated for closure.

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Simulator out of bounds: trigger A freeze state occurs during a This SDR documents a one-

13 caused event scenario, or a "Beyond time event that occurred insimulated limits" alarm is Sept of 2014. Since that eventreceived on the instructor's a change has beenstation implemented to Simulator

VC-1412-02 Yes Operation at the station whichincludes a scheduled regimentof simulator reboots andresets. No repeat of this event

has been noted, so it is beingevaluated for closure.

During performance of AP-MALF-03-6, Loss of ES-1, VCS Fan Cdoes not start. [


This SDR was written toinvestigate if system responseduring this malfunction testwas in accordance withdesign. The vendor has nowprovided a response, whichconcluded that the fans didrespond lAW design. Theconfusion resulted from aconflict between the SSD andthe M3C document, which isbeing fixed.

Considering the question ofexam scenario sequence; TheVCS system iis a non-safetyrelated system. It's svstemdesian is such that [

VC-1501-03 Yes

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10 CFR 55.45(a)(5): Observe and safely control the operatingq behavior characteristics of the facility.

I I


Significant? Basis Additional InformationProvided bv licensee

-1 I 4 4-

lao

I

la,c

r

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1I CFR 55.45(a)(5): Observe and safely control the operatingi behavior characteristics of the facility.

1 *~~I - - -

Deficiency Deficiency descriptionNo. Significant? Basis Additional Information

vrovided by licenseeNo.

]a.c

Middle of life and end of life InitialConditions have decay heatreflective of BOL. Core testinglimited to BOL until complete rxphysics data provided

Creates a false indicationassociated with heat removal.Potential negative training oncritical task.

I

VC-1 501-09 Yes

The simulator is currently onlyused for training andevaluation in BOL conditions.The SDR is tracking a requestto the vendor to provide moredecay heat data for MOL andEOL core conditions to supportfurther physics testing. Allrequired ANS/ANSI 3.5 testinghas been successfullycompleted.

Although the simulator can beadvanced to MOL and EOL,the decay heat loads at thosetimes are best estimates untilmore data is obtained..

Simulator out of bounds: S-115 in A freeze state occurs during a This SDR documents a one-

VC-1 502-02 progress, activated trigger 2 Yes scenario, or a "Beyond time event that occurred in oneC when Out of Bounds occurred. simulated limits" alarm is simulator once simulator

received on the instructor's training began around the

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Deficiency DAdditional InformationNo. Significant? Basis provided by licenseestation

clock. To date, it has notrepeated and no apparentreason for the condition has

been discovered. This SDR isbeing held open to tracktrending and furtherinvestigation of the event.

During run of AP-MALF-1 0-1 (71 ??Is this simulator feature used This malfunction is not used tomi version) retest, an EXEC to support exams?? support exams or training. ThisFailure occurred. SIM was reset Malfunction was used duringand same test ran without a

SAT testing. The EXECproblem. The same test has Failure that occurred isbeen run on both simulators believed to have been causedVC150204 without issue, this test was only ?? by the previous practice ofbeing run to look at additional running multiple iterations ofdatapoints. the same malfunction using"chained" computer

commands. This practice hasbeen stopped and no repeat ofthis issue has occurred. ThisSDR is now being closed.

During run of AP-OPS-T-010, a ?? This SDR was observedMAXPP sime STOP occurred. during SAT testing. The STOPSIM was reset and same test ran that occurred is believed towithout a problem. The same have been caused by thetest has been run on both previous practice of running

VC-1502-05 simulators without issue, this test ?? multiple iterations of the samewas only being run to look at malfunction using "chained"additional datapoints. computer commands. This

practice has been stopped andno repeat of this issue hasoccurred. This SDR is now

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DeDeficiency description Significant? Basis Additional Information

No. provided by licenseebeing closed.

While training using IS-1 09, PZR This indication would be This SDR was written toLevel went down in 2 of 3 training contrary to expected physical investigate a one-time eventscenarios with the leak through principles. Could force exam which was observed during athe PZR safety. Actions prior to scenario into undesired training scenario that featuredFailure - They had iust started sequence and trigger a Steam Space Pressurizerramping down at [ ]a,c mw/min. component failure leak.

assessment(s) and/or operatorresponses which would add For the one crew who hadundesired different response, theycomplexity/distractions to the starting their downpower at aexam scenario, significantly different time than

the other crews. For thisVC-1 502-08 Yes scenario, the leak size starts

small enough that the initialpzr level decrease due to RCStemperature decrease causeslevel to drop. As the steamleak size progresses in size,the surge line floodingphenomena becomes thelarger affect, causing Pzr levelto rise.

This SDR is now being closed.

While doing a demo, a steam Could force exam scenario into Additional investigation of thisleak was placed in by lifting undesired sequence and trigger item is in progress.several SG Safety valves and no component failure

VC-1502-09 operator action taken. Over Yes assessment(s) and/or operatorpower control permissives did not responses which would add AOrespond as designed. WEC was undesiredable to reproduce this event and complexity/distractions to the

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according to the CR has no exam scenario.response at this time.AO rods move inconsistently Could force exam scenario into See previous response to VC-between tests. undesired sequence and trigger 1502-10 above.

component failure1Yes assessment(s) and/or operator

VC-1502-10 es responses which would addundesiredcomplexity/distractions to theexam scenario.

Pressurizer Water Level Could force exam scenario into This SDR was written duringresponse during Safety valve undesired sequence and trigger SAT test VCS2-IST-0002, AP-malfunctions has variations in component failure MALF-01-5. This test checkstests where a PZR Safety valve is assessment(s) and/or operator plant response to a pressurizeropened, PZR Water level responses which would add safety failing open. During theresponse is correct in direction undesired performance of the test thereand magnitude, but show complexity/distractions to the are some variances ininconsistencies in timing of exam scenario, compensated Pzr level at themaxima and minima. point in the event where the

passive CMT injectionovercomes the leak size so

VC-1 502-12 Yes that pressurizer level recovers.There is a variance of - 60seconds between the initiationof the full recovery ofinventory, and there is avariance of- 5% between thehighest observed Pzr levelprior to level stabilizing.

The minor differences in thetiming of the inventory

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10 CFR 55.451a)15): Observe and safely control the oDeratina behavior characteristics of the facility.

Deficiency DSignificant? Basis Additional InformationNo. Deficiency dsrpi provided by licenseerecovery and the highest

observed Pzr level do notaffect operator decision pointsduring this accident sequence.

All training scenarios andexam scenarios are validatedto ensure that a consistentprocedure flowpath is followed.

During Load Rejection events, Could force exam scenario into Additional investigation of thisLoad Unbalance response is undesired sequence and trigger item is in progress.inconsistent causing noticeable component failuredeltas in several key parameters. assessment(s) and/or operatorThese test deltas were previously responses which would addattributed to the Rods to Manual undesired

VC-1502-13 issue (VC-TO-101). After Yes complexity/distractions to themultiple test runs where initial rod exam scenario.response was correct, somedeltas were still occurring andfurther testing revealed thatIntercept Valve response isinconsistent.RCS wide range pressure Could force exam scenario into Additional investigation of thisdropped from 1400 to 700 psig undesired sequence and trigger item is in progress.then stabilized. No action taken component failure

VC-1 503-03 for 13 min prior to pressure drop Yes assessment(s) and/or operatorVC-1 503-04 responses which would add

undesiredcomplexity/distractions to theexam scenario.

VC-1503-16 Alarm response after certain Yes Alarms place unplanned and See previous response to VC-events is difficult due to the probably unreasonable workload 1503-16 above.

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Deficien Significant? Basis Additional Information

No. Deficiency description provided by licensee

number of alarms that are on the operators. Could force

received, over 2 thousand in exam scenario into undesired

some scenarios. sequence and triggercomponent failureassessment(s) and/or operatorresponses which would addundesiredcomplexity/distractions to theexam scenario.

An Axial Flux Difference spike Could force exam scenario into This SDR captured an issue

periodically will cause rod control undesired sequence and trigger observed at the Westinghouse

for the M and AO rods to shift to component failure simulator during ISV workup

manual. The issue has repeated assessment(s) and/or operator activities.

itself during simulated responses which would add

surveillance activities undesired Two Westinghouse patchescomplexity/distractions to the have been installed at the VCSexam scenario, simulator since this SDR was

initiated: r

VC-1503-18 Yes ]a,, The VCS

simulator has alsoimplemented overall changesto simulator operating

practices which include muchmore frequent simulatorrebooting.

This problem has not been

observed at VCS duringtesting of availablesurveillance activities. This

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DeDeficiency description Significant? Basis Additional InformationNo. provided by licensee

SDR is now being closed.E-1 Fold Out Page logical ties are Potentially disrupts operational This item has been correctednot made in Computerized analysis, decision making and as of 5/4/15

VC-1 503-19 Procedure System. So when in E- Yes action1 and criteria are met per theFOP they never actuate.

VC-1 503-33

TCS heat transfer characteristicsthrough the H2 coolers areunrealistic. At 50% turbine powerthe H2 cooler TCV was fullyclosed, in automatic. Also, theEHC coolers had zero flowdemanded, causing TCS highdischarge pressure and low flowalarms.


Yes

Additional investigation of thisitem is in progress.

APS "InstrumentAir" tile has no points assigned toit


r

VC-1 504-01(Not on

docketed list)Yes

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r I F I

DeficiencyNo. Deficiency description Significant? Basis

NoI-I


]a,c

The SDR was written to trackreassignment of some alarmsto this tile.

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10 CFR 55.45(a)(6):

Perform control manipulations required to obtain desired operating results durinq normal,

abnormal, and emerqencv situations.

10 CFR 55.45(a)(6): Perform control manipulations required to obtain desired operatinq results durinq normal, abnormal.

and emergency situations.

DDeficiency efce c e ci to i nfc n ?B ssAdditional Inform ation

No. Significant? Basis provided by licenseeDuring MCR/RSR transfer testing Supports Job Performance This is transparent to the

it was noted that PMS screens Measures student and easily fixed by the

were not all following actions instructor by refreshing the

correctly. In each case, once the display while moving the

VC-TO-06 screen was refreshed it displayed Yes students from the Simulator tocorrecting, the Remote Shutdown Room.This does not impact the ability

to use the Remote ShutdownRoom for Job PerformanceMeasures.

Malfunction ATWS with Turbine Any repeatability issue is a This SDR originated at

Trip - non-repeatability. Rods cause for concern in an exam Westinghouse during Factory

were noted during several tests Accepance Testing and ISV

rejecting to MAN on Hi Auct Tavg scenario validation activities.MERE signal. Two Westinghouse patches

have been installed since thisSDR was initiated: I

VC-TO-47 Yes

]a,c It was also

discovered that minor changesin plant conditions at startingpoint which can be caused byrunning multiple iterations of atesting scenario in an

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10 CFR 55.45(a)(6): Perform control manipulations required to obtain desired operating results during normal, abnormal,


Deficien Significant? Basis Additional Information

No. Deficiency description provided by licenseeautomated "chain" overnightalso affect plant performance -in particular causina minordeviations I

]a,c

Overall changes to simulatoroperating practices whichinclude much more frequentsimulator rebooting has alsobeen implemented along withchanges to "chained" testing.The results have been asignificant reduction ininstances of Rods rejecting tomanual over several months oftraining and examinations.

The item is being let open tocontinue monitoring for issues,and to track any future designhardening improvements.

Malfunction RCP Shaft Break - Inconsistent response could This SDR originated at VNP

non-repeatability. An ESF force exam scenario into during their Site Acceptance

actuation on Low Steamline undesired sequence and trigger testing/ANS testing. The last

VC-TO-48 Pressure occurs over 30% of our Yes component failure sentence states that VCS did

tests. In over 40 tests we have assessment(s) and/or operator not see this response in overnot received a ESF actuation on responses which would add 40 tests at our site. In all casesLocked Rotor undesired and at all sites it was noted

complexity/distractions to the that the plant event causes

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10 CFR 55.45(a)(6): Perform control manipulations required to obtain desired operating results during normal, abnormal,and emergency situations.

Deficiency DSignificant? Basis Additional InformationNo. Defiienc description provided by licenseeexam scenario, conditions which all initially

stabilize extremely near theactuation setpoint.

The delta in performance atother stations has beenconcluded to be attributable tominor differences in thestarting conditions at eachfacility which allow the setpointto be met in some cases, andnot met in other cases,

When this testing wasrepeated at all stations using astandardized IC that exactlymatched the primary plant sidestarting parameters, the resultsrepeat each time and at allstations.

MSR valve response during Could force exam scenario into See previous response to VC-shutdown is incorrect and causes undesired sequence and trigger TO-128 above.an undesired RCS temperature component failure

VC-TO-128transient. Yes assessment(s) and/or operatorresponses which would addundesiredcomplexity/distractions to theexam scenario.

Steam dumps capacity appears Potentially disrupts operational Additional investigation of thisVC-1410-7 to be larger than expected based Yes analysis, decision making and item is in progress.

on the following observations: action. Could force exam

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10 CFR 55.45(a)(6): Perform control manipulations required to obtain desired operating results during normal ahnnrmal


1 T 7

UeficiercyNo.

Deficiency description Significant? Basis Additional Informationprovided by licensee

- On a turbine trip within F

lax

- If Rapid Power Reductionblocked, steam dumps will allowplant shutdown. Initial postturbine trip steam flow is [

]ac. As Auto rods reducepower, [ ],,, steam dumps.are closed as steam flow reaches[ 11'c-If [ 4a. steam dumps areisolated before a Turbine Trip,the plant response is nearlyidentical to havina none-isolated.

scenario into undesiredsequence and triggercomponent failureassessment(s) and/or operatorresponses which would addundesiredcomplexity/distractions to theexam scenario.

I

-II

VC-1 501-02

During performance of AP-MALF-01-2, LOCA OutsideContainment, a decrease inCTMT pressure was noted. WRoressure went r

]axc. At thetime this pressure decreasestarted, CTMT exhaust fans hadstarted but had not aligned toVAS and VRS. During aRETEST it was noted that ifradiation never gets high enoughto align VAS/VRS to VFS butVAS flowslower enough to tripthe fans. The-situation with VASventilation continues to degrade

I Could force exam scenario intoundesired sequence and triggercomponent failureassessment(s) and/or operatorresponses which would addundesiredcomplexity/distractions to theexam scenario.

This is being tracked todetermine if it is the correctplant system response if nooperator intervention is taken.Currently, the-simulator isresponding as the plant isdesigned. If this condition wereencountered in an examscenario, then the crew will beexpected to respond to theseconditions. The examvalidation. process is used to

Yes

I _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

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10 CFR 55.45(a)(6): Perform control manipulations required to obtain desired operating results during normal, abnormal.and emergency situations.

Deficiency DAdditional InformationNo. Significant? Basis provided by licenseeultimately leading to a start ofVFS exhaust system aligned toCTMT. More investigation isneeded to determine if this is

__________proper system response.During performance of AP- Could force exam scenario into See previous response to VC-MALF-03-6, Loss of ES-i. VOS undesired sequence and trigger 1501-03 above.Fan C does not start. [ component failureassessment(s) and/or operator

responses which would addundesired

0Yes complexity/distractions to theVC-1501-03 es exam scenario.

After CETC exceed [ Potentially disrupts operational Currently, VCS has made aanalysis, decision making and procedure change to the FRPs]a,c This causes the CSF action. Confuses operator about so that the crew now will enter

for Core Cooling to go yellow, core cooling status and whether FR-C.1 as soon as the CETCorange, and red several times or not to implement the FRP.

VC1502-07 without locking in. YesVC-1 52-07

a,o

Further investigation has beenconducted on the VCSsimulator, which isolated more

71May 27, 2015

Attachment 5

Westinghouse Non-Proprietary Class 3 VSLVSG 000306June 16, 2015




Deficiency Deficiency description Significant? Basis Additional InformationNo. provided by licensee

of the potential coolingmechanisms that could providecooling to the core during theconditions set up in the event.Originally, the Accumulators,CMT, and IRWST injectionpaths were blocked. VCS nowalso blocked the containmentsump gravity injection path,and breached containment, inorder to eliminate potentialbackfeeding of the corethrough the RCS pipe shear.

When these items were added,it was noted that the CETCtemperatures swing coincideswith a pressure swinei in thereactor vessel. f

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Attachment 5VSL VSG_000306

June 16, 2015Page 73 of 89

10 CFR 55.45(a)(6): Perform control manipulations required to obtain desired operating results durinq normal, abnormal.

and emeraencv situations...... .. • E

- -- - T r rDeficiency

No.Deficiency description Significant? Basis

f 1- t -~

Additional InformationDrovided bv licensee

]a,c

This response, once all ofthese malfunctions are added,can be consistently repeatedon the simulator. Until moreinformation becomes available,the crews will be trained andexamined to enter FR-C.1 asdescribed above.

i i i

VC-1 502-13

During Load Rejection events,Load Unbalance response isinconsistent causing noticeabledeltas in several key parameters.These test deltas were previouslyattributed to the Rods to Manualissue (VC-TO-101). Aftermultiple test runs where initial rodresponse was correct, somedeltas were still occurring andfurther testing revealed thatIntercept Valve response isinconsistent.


Additional investigation of thisitem is in progress.

Yes

Following SG dryout, SG Wide Potentially disrupts operational Further analysis has been

VC-1502-14 Range level does not stay at Yes analysis, decision making and conducted on this SDR. Duringzero. Level will oscillate between action a Faulted SG condition, it was

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10 CFR 55.45(a)(6): Perform control manipulations required to obtain desired ooeratin, results durina normaL abnormal


-- - 1 I T r

DeficiencyNo.

Deficiency description

r] This is unexpected as

there is no mass being added tothe SG. (NOTE -This [ ]acvalue is below the Normal CTMTconditions [ ]a,c usedto state SG Wide Range level is"just on span").

Significant? Basis Additional Informationprovided by licensee

-i inoted that SG levels initiallydecrease to between [

Ia,c were they oscillate in-11 minutes. This level isbelow the lowest level that isused as any minimum leveldecision point in any EOP. At-25 minutes, then levels thendrop to 0% and remain steady.The SDR is tracking this itemwhile checking with the vendorthat this is expected.As noted in the deficiencydescription: The [

]a,c, so does notprevent execution of any EOPrfinni~inn nnint

During ISV the crew had trouble Potentially disrupts operational When a CMT is operating indetermining CMTs Operating in analysis, decision making and the recirculation mode, andboth Recirc and Injection modes action. Could force exam during the earliest staae of thedue to indications observed, scenario into undesired iniection mode, r

VC-1503-08 Manual DAS ADS Stage 1-3 & 4 sequence and trigger

VC-1503-09 actuation was not oerformed w/in Yes component failureI I assessment(s) and/or operator ]a,c

]ac) during a LBLOCA scenario responses which would addwhere CMTs failed to actuate. undesired When this SDR was recorded

complexity/distractions to the there was no clear guidanceexam scenario, for the crews to use to

74May 27, 2015

Attachment 5

Westinghouse Non-Proprietary Class 3 VSLVSG_000306June 16, 2015


10 CFR 55.45(a)(6): Perform control manipulations required to obtain desired operating results during normal, abnormal.


Deficiency Deficiency description Significant? Basis ] dditional InformationNo. provided by licensee

consistently differentiatebetween changes to CMTtemperature instrumentationcaused by changingContainment ambientconditions (such as during aLOCA environment), and thebeginning of CMT operation.VCS has added an additionaldiscussion to the backgrounddocument for the EOP whichevaluates this condition; E-0.

Additionally, when the SDRitem was written r

]ac

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]ac The VCSEOP/AOP users guide nowdirects that this task only bedone using the FOP directionto ensure enabling the panel isnot missed.

Based on observed indications,the crew misdiagnosed theFaulted Steam generator asbeing both Faulted and Rupturedand actuated ADS based on FoldOut Page criteria in E-3. Thismay be related to the ANSItesting SDR for Dryoutindications.


This SDR item captures anISV preliminary HED condition.During the ISV, one crewobserved the SG Wide Rangelevel response as the SG wasblowing down, and determinedthat the SG was both faultedand ruptured.

This is a onetime incidentwhich will be closed withtraining.VC-1 503-12 Yes

____________________________________ I

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10 CFR 55.45(a)(6): Perform control manipulations required to obtain desired operating results during normal, abnormal,and emeraencv situations.

I IDeficiency

Mn Deficiency description Significant? BasisNo I


]a~c

See previous response to VC-1503-16 above.

-I- t 1Alarm response after certainevents is difficult due to thenumber of alarms that arereceived, over 2 thousand insome scenarios.

VC-1 503-16 Yes

Alarms cause unplanned andprobably unreasonable workloadon the operators. Could forceexam scenario into undesiredsequence and triggercomponent failureassessment(s) and/or operatorresponses which would addundesiredcomplexity/distractions to theexam scenario.

When transferring to the RSR the Supports Job Performance This SDR is written to evaluateleft hand screen of the right Measures an item identified duringstation didn't work. This was a Westinghouse ISV activities.

VC-1503-21 Westinghouse simulator issue. Yes Transferring to the panel wasThough on simulator 2A it was not configured the same as thenoted that the Right hand station simulator. This item has beendid not work when transferring to confirmed to not be occurringthe RSR. here and will be closed.

The MCR fire control panel is not ?? are control manipulations See previous response to VC-VC-1503-22 modeled on the simulator ? done from this panel or is it 1503-22 above.

indication only??

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10 CFR 55.45(a)(7):

Safely operate the facility's heat removal systems, including primary coolant, emergencycoolant, and decay heat removal systems, and identify the relations of the proper operation of

these systems to the operation of the facility.

10 CFR 55.45(a)(7): Safely operate the facility's heat removal systems, including primary coolant, emergency coolant, anddecay heat removal systems, and identify the relations of the proper operation of these systems to the operation of thefacility.eficiency D eficiency description Significant? Basis Additional Information

No. provided by licenseeAfter CETC exceed F Potentially disrupts operational See previous response to VC-

analysis, decision making and 1502-07 above.

VC-1 502-07 ]a,c. This causes the CSF Yes actionfor Core Cooling to go yellow,orange, and red several timeswithout locking in.Placing RNS in service with RCSpressure greater than RNSdesign pressure. No interlockexists on RNS-V061 to preventover pressurizing RNS and thatPressure and Temperaturerequirements shall be met priorto opening RNS-V061.

Listed as priority 1 HED whichindicates WEC believes this issafety issue

This item was identified duringWestinghouse ISV activities.The valve identified, RNS-V061, is the CVS PurificationReturn Line Isolation. Thesimulator is currentlyconfigured as the BL7 Plant isdesigned. No final HEDpriorities have been assigned,however all potential priority 1HEDs have been assessed fortraining needs analysis.

VC-1 503-13 Yes

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10 CFR 55.45(a)(7): Safely operate the facility's heat removal systems, including primary coolant, emergency coolant, anddecay heat removal systems, and identify the relations of the proper operation of these systems to the operation of thefacility.

]a,, Addition of aninterlock here is a future plantenhancement which is underconsideration.

I + F

VC-1 503-14

Failed to perform AOP-702 stepto secure CVS and RNS pumpswith inadequate CCS cooling.

Failed to identify [ ]a,cwhich resulted in the CCS pumpsrunning while cavitating due tolow CCS surge tank level,resulting in frequent pumpcycling, which would likely resultin damaae to the pumos.

Yes

Listed as priority 1 HED whichindicates WEC believes this issafety issue. Not clear ifnecessary indications areavailable.

This SDR was caused by aprocedure usage conflict,rather than a lack of indication.[

]a,c

VCS has added a procedurestep in the loss of SWprocedure to direct theoperators to perform loss ofCCS procedure whilecontinuing in the loss of SWprocedure.

-I- I- -I

VC-1503-15 Yes

Could force exam scenario intoundesired sequence and triggercomponent failureassessment(s) and/or operatorresponses which would addundesiredcomrlexitv/distractions to the

This SDR is written todocument 1 ISV crew whomissed the alarm during a postreactor trip event. The otherISV crews successfullydiagnosed and responded tothe condition.

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10 CFR 55.45(a)(7): Safely operate the facility's heat removal systems, including primary coolant, emergency coolant, anddecay heat removal systems, and identify the relations of the proper operation of these systems to the operation of thefacility.

exam scenario.The CCS low surge tank levelalarm is currently a priority 3alarm. This alarm priority isbeing increased to increasethe visibility to the operators.

RNS pump does not restart on Potentially disrupts operational The SDR item is transparent toDG Sequencer analysis, decision making and the students. This issue is

VC-1410-09 Yes action currently being compensatedby use of an APP file to startthe RNS pump at the propermoment.

Time to Boil values in Mode 5 at Common job performance See previous response to VC-190F were BAD Q but seemed measure TO-93 above.reasonable values. During a

VC-TO-93 Loss of RNS, as temperatures Yesincreased the TTB values wentGood Quality, but the value wentto 1. 00 E7. This happened asTcold exceeded 202F

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10 CFR 55.45(a)(8):

Safely operate the facility's auxiliary and emergency systems, including operation of thosecontrols associated with plant equipment that could affect reactivity or the release of radioactive

materials to the environment.

10 CFR 55.45(a)(8): Safely operate the facility's auxiliary and emergency systems, including operation of those controlsassociated with Dlant equipment that could affect reactivity or the release of radioactive materials to the environment.

r 1 rDeficiency

No.Deficiency description

EDS batteries last []a,c hours and when they

go low enough to drop loads;voltage swings cause allpowered components to cycle.This includes Ovationcontrollers and hardwarerelays.

Significant? BasisAdditional Informationprovided by licensee

i -f i

VC-TO-04

This SDR has minimal impacton training and almost noimpact on examination. F

]a,c LicenseOperator exam scenarios donot typically last past the 4 hourpoint, which would still bebefore this is expected tooccur.

Any training, exam scenario orJPM which would need toexercise this feature wouldthen have to use timecompression and jump to an ICwith this occurring. A muchmore likely training and examactivity would be theperformance of the loadshedding, which is unaffectedby this SDR.

VC-TO-1 0 MS rad monitors do not Yes Critical parameter for Additional investigation of this

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10 CFR 55.45(a)(8): Safely operate the facility's auxiliary and emergency systems, including operation of those controlsi with nltnf 'ntiinmenf that could affect reactivity or the release of radinoactive Mrnarinla t fhna n

Deficiency Additional InformationNo. Deficiency description Significant? Basis provided by licensee

respond during SGTR diagnosing SGTR item is in progress.

IascMalfunction ATWS with Any repeatability issue of this See previous response to VC-Turbine Trip - non- significance is a concern for TO-47

VC-TO-47 repeatability. Rods were noted Yes exams.during several tests rejecting toMAN on Hi Auct Tavg MEREsignal.RNS pump does not restart on Potentially disrupts operational See previous response to VC-

VC-1410-09 DG Sequencer Yes analysis, decision making and 1410-09.action

During performance of AP- Software module has halted or This SDR documents aMALF-01-2, LOCA Outside kicked out problem that occurred when

VC-1411-12 Containment, a maxPPsteam the simulators first arrived atSTOP occurred. Intermittent the station and SAT/ANSrecurrence on retest. testing was just starting. It was

later discovered that running

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10 CFR 55.45(a)(8): Safely operate the facility's auxiliary and emergency systems, including operation of those controls-...:__a ,...:=kzt.÷ ... ;,II,• ÷ , uIrI •-ff,-f ro#w-fivift, nr the. releas~e of radioactive materials to the environment.

a,5• oUILa~u WIUI I JIdIIL t~4L.Jt~jlIlIl'II.L L55CL ,, u~ r.H.. • -u.. . ...... .. .. ... .. ....... .. .. .. ... .. .........

Deficiency Deficiency description Significant? Basis Additional InformationNo. provided by licensee

multiple iterations of a testingscenario in an automated"chain" overnight can affectplant performance - inparticular causina minordeviations in [

. Overallchanges to simulator operatingpractices which include muchmore frequent simulatorrebooting has also beenimplemented along withchanges to how "chained"testing is used. Once thesechanges were implemented,this test was run withoutissues. The item is being letopen to continue monitoring forissues, and to track any futuredesign hardeningimprovements.

During performance of AP- Could force exam scenario into Additional investigation of thisMALF-01-2, LOCA Outside undesired sequence and item is in progress.Containment, a decrease in trigger component failureCTMT pressure was noted. assessment(s) and/or operatorWR pressure went F responses which would add

VC-1501-02 ]a,c. At Yes undesiredthe time this pressure complexity/distractions to thedecrease started, CTMT exam scenario.exhaust fans had started buthad not aligned to VAS andVRS. During a RETEST it was

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Attachment 5VSL.VSG 000306

June 16, 2015Page 84 of 89

10 CFR 55.45(a)(8): Safely operate the facility's auxiliary and emergency systems, including operation of those controlsassociated with nlant eciuinment that could affect reactivitv or the release of radioactive materials tn the envirnnmcanf

eficiency Deficiency description Significant Basis Additional Information


noted that if radiation nevergets high enough to alignVAS/VRS to VFS but VASflows lower enough to trip thefans. The situation with VASventilation continues todegrade ultimately leading to astart of VFS exhaust systemaligned to CTMT. Moreinvestigation is needed todetermine if this is propersystem response.During ISV the crew had Potentially disrupts operational When a CMT is operating in

trouble determining CMTs analysis, decision making and the recirculation mode, and

Operating in both Recirc and action. Could force exam during the earliest staoe of the

Injection modes due to scenario into undesired iniection mode, r

indications observed. Manual sequence and triggerDAS ADS Stage 1-3 & 4 component failure

actuation was not i)erformed assessment(s) and/or operator ]a,c

w/in [ responses which would add When this SDR was recorded

VC-1503-08 ]a,, during a LBLOCA undesired there was no clear guidance for

VC-1 503-09 scenario where CMTs failed to Yes complexity/distractions to the the crews to use to consistently

VC-1503-28 actuate. exam scenario, differentiate between changesto CMT temperatureinstrumentation caused bychanging Containment ambientconditions (such as during aLOCA environment), and the

beginning of CMT operation.VCS has added an additionaldiscussion to the backgrounddocument for the EOP which

84May 27, 2015

Attachment 5


DRAFT RAI

VSLVSG_000306June 16, 2015Page 85 of 89

10 CFR 55.45(a)(8): Safely operate the facility's auxiliary and emergency systems, including operation of those controlsc¢nr~i:fcd wvifh ni~nt i_'nliinmpnt that coiild affect reactivity or the release of radioactfive r~tnt.riAlR tn thvp nnvirnnmonf


No. provided by licenseeevaluates this condition; E-0.Additionally, when the SDRitem was written f

]a,c The VCS EOP/AOPusers guide now directs thatthis task only be done using

the FOP direction to ensureenabling the panel is notmissed.

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10 CFR 55.45(a)(9):

Demonstrate or describe the use and function of the facility's radiation monitoring systems,including fixed radiation monitors and alarms, portable survey instruments, and personnel

monitoring equipment.

10 CFR 55.45(a)(9): Demonstrate or describe the use and function of the facility's radiation monitoring systems, includingfixed radiation monitors and alarms, Portable survey instruments, and personnel monitorinq equipment.

Deficiency Deficiency description Significant? Basis Additional InformationNo. I provided by licensee

MS rad monitors do not respondduring SGTR

Critical parameter for diagnosingSGTR

See previous response to VC-TO-10 above.

VC-TO-1 0 Yes

VC-TO-75

VRS-JE-RE023 goes up by [ ]a,c

decades in [ ]a,, minutes on aloss of process flow. This gives aPriority 1 alarm on VRS andRADIATION MONITORING. Thiswill lead to an unnecessary entryinto AOP-315 (HIGHRADIOACTIVITY).

Yes


See previous response to VC-TO-75.

t

VC-TO-76

VHS-JE-RE001 goes up by [ ]acdecades in[ ]a,c minutes on aloss of process flow. This gives aPriority I alarm on VHS andRADIATION MONITORING. Thiswill lead to an unnecessary entryinto AOP-315 (HIGHRADIOACTIVITY)The current [ ]a,csetpoint/deadband combinationsfor containment radiation alarmsdo not allow for the [

]aL , alarms to clear. The

Yes


See previous response to VC-TO-76.

-I- + -IAlarm function supports eventdiagnostics


VC-TO-1 17 Yes

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10 CFR 55.45(a)(9): Demonstrate or describe the use and function of the facility's radiation monitoring systems, includingfixed radiation monitors and alarms, portable survey instruments, and personnel monitoring equipment.

alarm reset values are above thealarm setpoint values and will notwork correctly

When Containment Air Filtration Could force exam scenario into Additional investigation of thisSystem had no flow, VFS-RY102 undesired sequence and trigger item is in progress.alarmed for high iodine. The component failure

VC-1503-25 scenario where this occurred was Yes assessment(s) and/or operatorduring a cooldown with an responses which would addaccumulator leak in progress. undesired

complexity/distractions to theexam scenario.

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10 CFR 55.45(a)(1 0): Demonstrate knowledge of significant radiation hazards, including permissible levels in excess of

those authorized, and ability to perform other procedures to reduce excessive levels of radiation and to guard against

personnel exposure.

No questions were identified in this area.

10 CFR 55.45(a)(11):

Demonstrate knowledge of the emergency plan for the facility, including, as appropriate, theoperator's or senior operator's responsibility to decide whether the plan should be executed and

the duties under the plan assigned.

10 CFR 55.45(a)(11): Demonstrate knowledge of the emergency plan for the facility, including, as appropriate, the

operator's or senior operator's responsibility to decide whether the plan should be executed and the duties under the plan

assianed.eficiency D eficiency description Significant? Basis Additional Information

No. provided by licenseeVC-TO-40 During plant C/D and H/U the Yes Creates a false indication Additional investigation of this

subcriticality CSF title block is associated with reactivity item is in progress.turning magenta (bad input) manipulations.intermittently

VL;I U-1i3 Time to BOll values in Mode 5 at190F were BAD Q but seemedreasonable values. During aLoss of RNS, as temperaturesincreased the TTB values wentGood Quality, but the value wentto 1.00 E7. This happened asTcold exceeded 202F"[ I]ac" light onMode 5/6 Critical Safety FunctionStatus Tree" for Mode 5/6 doesnot update to green when RCSTemperature is stable for [

Yes Common job performancemeasure


VC-1 504-03(Not ondocketed list)

I Yes Potentially disrupts operationalanalysis, decision making andaction

See previous response to VC-1504-03 above.

I. _____________________________________________________ I ___________________________________________________

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10 CFR 55.45(a)(12): Demonstrate the knowledge and ability as appropriate to the assigned position to assume the

responsibilities associated with the safe operation of the facility.


10 CFR 55.45(a)(13): Demonstrate the applicant's ability to function within the control room team as appropriate to the

assigned position, in such a way that the facility licensee's procedures are adhered to and that the limitations in its license

and amendments are not violated.


89May 27, 2015

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