ML13106A183

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Draft - Outlines (Folder 2)
ML13106A183
Person / Time
Site: Vermont Yankee Entergy icon.png
Issue date: 02/22/2013
From: Todd Fish
Operations Branch I
To:
Entergy Nuclear Vermont Yankee
Jackson D
Shared Package
ML13106A183 List:
References
ES-401, ES-401-1, TAC U01898
Download: ML13106A183 (10)
v • d • e


Text

ES-401 BWR Examination Outline Form ES-401-1 II Date of Exam:

RO KIA Category Points S RO*Only Points Tier Group K K K K K K A A A A G A2 G* I Total 1 2 3 4 5 6 1 2 3 4

  • Total
1. 1 5 2 3 3 5 2 20 7 Emergency &

Abnormal Plant 2 3 2 0 N/A 1 1 NlA 0 7 3 Evolutions Tier Totals 8 4 3 4 6 2 27 10 I

1 2 1 2 5 3 3 1 2 3 1 3 26 5 2.

Plant 2 1 1 1 1 1 2 1 2 1 1 0 12 3 Systems Tier Totals 3 2 3 6 4 5 2 4 4 2 3 38 8

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories

!2 3 2 3 Note: 1. Ensure that at least two topics from every applicable KIA category are sam pled within each tier of the AO and SAO-only outlines (i.e.* except for one category in Tier 3 of the SAO-only outline, the "Tier Totals" in each KIA category shall not be less than two).

2. The point total for each group and tief in the proposeld outline must match that specified in the table, The final paint total for each group and tier may deviate by +/- 1 from that specified in the table based on NAC revisions.

The final RO exam must total 75 points and the SRO-only exam must total 25 points.

3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D, 1.b of ES-401 for guidance regarding the elimination of inappropriate KIA statements.
4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
5. Absent a plant-specific priority, only those KlAs having an importance rating (IR) of 2.5 or higher shall be selected.

Use the RO and SRO ratings for the RO and SRO-only portions, respectively_

6. Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories.

7: The generic (G) KlAs in Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be relevant to the applicable evolution or system. Aefer to Section D.1.b of ES-401 for the applicable KlAs.

B. On the following pages, enter the KIA numbers, a brief deSCription of each topic, the topics' importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SAO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.

9. For Tier 3, select topics from Section 2 of the KIA catalog. and enter the KIA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Umit SRO s;elections to KlAs that are linked to 10 CFR 55.43.

ES-401 2 Form ES-401-1 I ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - TIer 1/Group 1 (RO I SRO)

ElAPE # I Name / Safety Function KKKAAG KIA Topic(s) IR #

1 2 3 1**2'>

295001 Partial or Complete Loss of Forced x I I'I " Knowledge of the interrelations between PARTIAL 3.4 Core Flow Circulation 11 & 4 I I OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION and AK2.07 Core flow indication Ability to determine and/or interpret the following as 295003 Partial or Complete Loss of AC / 6 they apply to PARTIAL OR COMPLETE LOSS OF 3.5 2 A.C.POWER:

AA2.04 SyStem lineups Ability to operate and/or monitor the following as 295004 Partial or Total Loss of DC Pwr 16 they apply to PARTIAL OR COMPLETE LOSS OF 3.8 3 D.C. POWER:

k;.. 1<. AA1.02 Systems necessary to assure safe plant w< shutdown

~

II----------------+--i-+-+ Ability to determine and/or interpret the following as

  • 295005 Main Turbine Generator Trip / 3 they apply to MAIN TURBINE GENERATOR TRIP: 3.2 4 I* ... I'; AA2.08 Electrical distribution status.
. i I..' Knowledge of the operational implications of the
  • 295006 SCRAM 11 x t* following concepts as they apply to SCRAM: 3.4 5 AK1.02 Shutdown marain Knowledge of the reasons for the following 295016 Control Room Abandonment 17 x responses as they apply to CONTROL ROOM 3.5 6 ABANDONMENT: AK3.03 Disabling control room controls 295018 Partial or Total Loss of CCW 18 .: 2.4.31 Knowledge of annunciator alarms, 4.2 7 indications, or response procedures.

I Ability to determine and/or interpret the following as 295019 Partial or Total Loss of Inst. Air 18 they apply to PARTIAL OR COMPLETE LOSS OF 3.5 8 INSTRUMENT AIR: M2.01 Instrument air system l,;, oressure 1l----------------+---jI-+-+-f;~I* ., Ability to operate and/or monitor the following as 295021 Loss of Shutdown Cooling I 4 X l~'< ts~.;. they apply to LOSS OF SHUTDOWN COOLING: 3.4 9

--c'-18~~~ Knowledge of the operational implications of the 295023 Refueling Ace I 8 X 13/ 10 I

following concepts as they apply to REFUELING 3.2 11----------------+-I-+-+-FrR1r=" I>

ACCIDENTS, AK1 m ""';- """""" hawd' Ability to operate and/or monitor the following as 295024 High Drywell Pressure I 5 X they apply to HIGH DRYWELL PRESSURE: EA1.20 3.5 11 Standby Qas treatmentlFRVS: Plant-Specific 295025 High Reactor Pressure / 3 12

. ,..T!. Knowledge of the interrelations between 295026 Suppression Pool High Water X 3" SUPPRESSION POOL HIGH WATER 3.6 13 Temp. 15 < 1</ TEMPERATURE and the following: EK2.02 I' ....*. Suppression pool spray: Plant-Specific i," .'. t!~ .

I 295027 Hiah Containment Temperature 15 i> . * ~, Suppressed, no MK III containment at VY Ie Knowledge of the operational implications of the 295028 High Drywell Temperature /5 X I'. I' ,. following concepts as they apply to HIGH 3.5 14 1;'< DRYWELL TEMPERATURE: EK1.01 Reactor L,< water level measurement H., Knowledge of the interrelations between LOW 295030 Low Suppression Pool Wtr LviI 5 X t'> ;.. . SUPPRESSION POOL WATER LEVEL and the 3.5 15 f(' i1> following: EK2.07 Downcomerl horizontal vent ii'L** submerQence 11----------------+---'1-+-+_ Ability to determine andlor interpret the fOllowi~~ as 1 .

295031 Reactor Low Water Level / 2 they apply to REACTOR LOW WATER LEVEL 40 ltj EA2.02 Reactor power

t:

295037 SCRAM Condition Present X 2.4.18 Knowledge of the specific bases for EOPs. 3.3 17

.,r.

and Reactor Power Above APRM  :.

Downscale or Unknown 11

>.; Knowledge of the reasons for the following 295038 High Off-site Release Rate I 9 X ."

responses as they apply to HIGH OFF-SITE 3.9 18

o.> ,,: RELEASE RATE: EK3.02 System isolations Knowledge of the reasons for the following
> ~~,

600000 Plant Fire On Site 1 8 X responses as they apply to PLANT FIRE ON SITE: 2.8 19 AK3.04 Actions contained in the abnormal

>< : procedure for plant fire on site Ability to operate and/or monitor the following as I 700000 Generator Voltage and Electric Grid Disturbances 1 6 xf"F they apply to GENERATOR VOLTAGE AND 3.6 20

'., I?':

ELECTRIC GRID DISTURBANCES: AA 1.01 Grid frequency and voltage KIA Category Totals: 5 2 3 2 Grou~ Point Total: 20n

3 Form ES-401-1 I ES-401 BWR Examination Outline Form ES-401-1 Emergencv and Abnorma~EVolutions - Tier 1fGroup 2 (RO: SRO)

. ElAPE # I Name I Safety Function KKK 1 2 3 A.,

1 **21****

KIA ToplC(s) IR I #

1:<*, .'

295002 Loss of Main Condenser Vac 13 Ie; I 295007 High Reactor Pressure I 3 295008 High Reactor Water level I 2 X t Ii ~ Knowledge of the interrelations between HIGH 3,8 21 I~'} I', REACTOR WATER lEVEL and the following: AK2.05 HPCI: Plant-Specific I~ I. Knowledge of the operational implications of the k

295009 Low Reactor Water Levell 2 X following concepts as they apply to LOW REACTOR 3.0 22 WATER LEVEL: AK1.02 Recirculation pump net positive suction head: Plant- Specific 295010 High Drywell Pressure 15 I I .*.*Y 295011 High Containment Temp 15 Ii' Suppressed. no MK III containment at VY I*, r; 295012 High Drywell Temperature /5

.. I;,,>

295013 High Suppression Pool Temp. I 5 I* * :~

Knowledge of the operational implications of the 295014 Inadvertent Reactivity Addition 11 X ,.

following concepts as they apply to INADVERTENT 3.3 23

~.:

REACTIVITY ADDITION:

AK1.02 Reactivitv anomalv Ability to determine and/or interpret the following as 295015 Incomplete SCRAM / 1 they apply to INCOMPLETE SCRAM: AA2.01 Reactor 4.1 24 I power 1 5< II 295017 Hioh Off-site Release Rate /9 295020 Inadvertent Cont. Isolation / 5 & 7 X I~ Knowledge of the operational implications of the 3.7 25 I~;~

follOwing concepts as they apply to INADVERTENT 1< CONTAINMENT ISOLATION: AK1 ,01 Loss of normal heat sink 295022 loss of CRD Pumps / 1 295029 High Suppression Pool Wtr LviI 5 295032 High Secondary Containment X

,'c;;11<,1 SECONDARY Knowledge of the interrelations between HIGH CONTAINMENT AREA 3.6 26 Area Temperature 15 .¥; In,. TEMPERATURE and the following: EK2.04

. PCIS/NSSSS

\:' i,'

295033 High Secondary Containment ..........

Area Radiation Levels I 9 f*

. I: Ability to operate and/or monitor the following as 295034 Secondary Containment X they apply to SECONDARY CONTAINMENT 3.9 27 Ventilation High Radiation I 9 I> !i VENTILATION HIGH RADiATION: EA1.02 Process radiation monitoring system i*

295035 Secondary Containment High Ii Differential Pressure I 5 I' 295036 Secondary Containment High Iif*'. I;. I w:

Sump/Area Water Level 15 r 500000 Hiah CTMT Hvdroaen Conc. 15 KIA Category Point Totals: Group Point Total: I 7/3 II

ES-401 4 Form ES-401-1 I ES-401 BWR Examination Outline Plant SI stems - Tier 21Group 1 (RO I SRO)

System # / Name KKK KKK AAI AI AI G KIA Topic(s) . IR #

1 2 3 4 5 6 l' 2 3 4.

Knowledge of the physical connections and/or 203000 RHRlLPCI: Injection x 3.9 28 Mode I causeeffect relationships between RHRlLPCI:

INJECTION MODE (PLANT SPECIFIC) and

. ' the following: Kl.06 Automatic depressurization 205000 Shutdown Cooling x I.., Knowledge of electrical power supplies to the 2.5 29 I' followina: K2.02 Motor operated valves Knowledge of HIGH PRESSURE COOLANT 206000 HPCI x INJECTION SYSTEM design feature(s) 4.0 30 and/or interlocks which provide for the following: K4.04 Resetting system isolations:

., BWR-2,3,4 Knowledge of the effect that a loss or 206000 HPCI x malfunction of the following will have on the 3.5 31 HIGH PRESSURE COOLANT INJECTION SYSTEM: K6.05 Suppression pool level:

BWR-23,4 207000 Isolation (Emergency)

I. Suppressed, does not exist at VY Condenser Knowledge of LOW PRESSURE CORE 209001 lPCS x SPRAY SYSTEM design feature(s) and/or 3.B 32 interlocks which provide for the following:

K4.0B Automatic system initiation 209002 HPCS I)ip Suppressed, does not exist at VY 1~~~~~----------~-+-4~r-~+-4-~~-r-+--~;~K~n~OW~I~ed~g~e~O~fS~T~A~N~D~B~Y~L~IQ~U~I=D~C~O~N~T~R~O~l-4----~--~1 211000 SlC X ~~'. 11~,ii~ SYSTEM dedsigfn featufrell(s) .and/0 r ionstesrlocks 4.2 33 which prov! e or the 0 oWing: K 4 . ystem initiation upon operation of SBlC control 1';" 1,i'J; switch 211000 SLC l,\< l:;~ 2.1.32 Ability to explain and apply system 3.8 34 1,\;" Is limits and precautions.

> **~ 2.4.34 Knowledge of RO tasks performed 212000 RPS <., outside the main control room during an 4.2 35

./ .... emergency and the resultant operational

~ effects.

7 : " ) Ability to monitor automatic operations of the 2150031RM . ". X.;. INTERMEDIATE RANGE MONITOR (IRM) 3.5 36 i< SYSTEM including: A3.04 Control rod block I'i 215004 Source Range Monitor x I.'

Ii

. ." status Knowledge of the operational implications of the following concepts as they apply to 2.8 37 I, SOURCE RANGE MONITOR (SRM)

I' . k SYSTEM: K5.03 Changing detector position 215004 Source Range Monitor If I".> Ability to monitor automatic operations of the 3.6 38 X 1\ SOURCE RANGE MONITOR (SRM)

.." kL SYSTEM including: A3.04 control rod block 11-----------+-+--1I-+-+-+-1--!-I.....; '~i-t-D ~t~~~; to (a) predict the impacts of the 215005 APRM / LPRM i,X following on the AVERAGE POWER RANGE 3.5 39

'i~ MONITORllOCAl POWER RANGE I .-'.i

~~;

I,r* MONITOR SYSTEM; and (b) based on those predictions, use procedures to correct, V. . control, or mitigate the consequences of

' I,> ~~~~ ~=rmal conditions or operations:

215005 APRM I LPRM ,

x I'

Ability to monitor automatic operations of the AVERAGE POWER RANGE MONITOR 3.3 40

. ILOCAL POWER RANGE MONITOR SYSTEM including: A3.03 Meters and

                • recorders Knowledge of the operational implications of 217000 RCIC X l' 2.6 41

.i.**. the following concepts as they apply to REACTOR CORE ISOLATION COOLING I* SYSTEM (RCIC) : K5.01 Indications of pump I>. I'e)< cavitation I' Knowledge of the effect that a loss or 218000 ADS X I****** malfunction of the following will have on the 3.8 42 AUTOMATIC DEPRESSURIZATION SYSTEM: K6.03 Nuclear boiler instrument

i. system (level indication)

I.**.** Knowledge of the effect that a loss or 223002 PCIs/Nuclear Steam X l' 3.7 43 I.~l~'

malfunction of the PRIMARY CONTAINMENT Supply Shutoff I;}> ISOLATION SYSTEM/NUCLEAR STEAM I* SUPPLY SHUT-OFF will have on following:

} K3.07 Reactor pressure Knowledge of the operational implications of 239002 SRVs X . .t> the following concepts as they apply to 2.7 44

',r RELIEF/SAFETY VALVES: K5.06 Vacuum

.*~. ',,' breaker ooeration Xiii Ability to manually operate andlor monitor in 259002 Reactor Water Level Control ~~}~ I,*

the control room: A4.04 FWRV lockup reset controls 3.7 45

" i. Knowledge of the effect that a loss or 261000SGTS X X malfunction of the STANDBY GAS 3.1 46 I( l,e TREATMENT SYSTEM will have on It li~;; following: K3.04 High pressure coolant iniection svstem: Plant- Soecific

~

Knowledge of STANDBY GAS TREATMENT 261000 SGTS X l*\ti SYSTEM design feature(s) andlor interlocks which provide for the following: K4.05 Fission 2.6 47 product !las removal 262001 AC Electrical Distribution tr 2.4.11 Knowledge of abnormal condition procedures.

Knowledge of UNINTERRUPTABLE POWER 4.0 48 262002 UPS (AC/DC) X fflf SUPPLY (A.C.!D.C.)

design feature(s) andlor interlocks which 3.1 49

~;; provide for the following: Transfer from preferred DOwer to altemate power supplies l~r k Knowledge of the effect that a loss or l~i~'

, 263000 DC Electrical X malfunction of the following will have on the 3.2 50 Distribution D.C. ELECTRICAL DISTRIBUTION: K6.01

./.

A.C. electrical distribution 264000 EDGs X !;,z 4', Ability to predict andlor monitor changes in 2.8 51 I'

,'. i parameters associated with operating the EMERGENCY GENERATORS (DIESEUJED controls including: A 1.03 Operating voltages, currents, and tem peratures

......... .;. Knowledge of the connections and I or cause 300000 Instrument Air X effect relationships between INSTRUMENT 2.8 52 I;,," AIR SYSTEM and the following: K1.03

. Containment air f<r,:: Ability to (a) predict the impacts of the 400000 Component Cooling X following on the CCWS and (b) based on 53 Water those predictions, use procedures to correct, r, I*****~. control, or mitigate the consequences of those abnormal operation: A2.03 High/low I:: IT.'

It.

CCW temperature is -BE3. Group Point Total:

I 2615 I

ES-401 5 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Svstems Tier 2fGrouD 2 IRO I SROI System # I Name K 1 5 K K 6

A 1 I:'~ J AG 4

KIA Topic(s) fR I #

201001 CRD Hvdraulic ' . ,

201002 RMCS I Ability to (a) predict the impacts of the 201003 Control Rod and Drive Mechanism lit. 1;,',

'. following on the CONTROL ROD AND DRIVE MECHANISM; and (b) based on those predictions, use procedures to 3.1 54 correct, control, or mitigate the consequences of those abnormal conditions or operations: A2.07 Loss of i,,".' CRD drive water flow 201004 RSCS I'.**** 1** Suooressed, does not exist at VY 201005 RCfS 1<,

201oo6RWM I I I

" ~

Suppressed, does not exist at VY

,,< Ability to (a) predict the impacts of the 202001 ReCirculation I;'x following on the RECIRCULATION 3.1 55 it; I~,

SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

I,;; A2.22 Loss of comoonent cooling water 1,:;;(' Knowledge of RECIRCULATION FLOW I~~

202002 Recirculation Flow Control X 3.1 56 l~~ CONTROL SYSTEM design feature(s)

~ ,"",0"",,00Cks wh<h p,,,,,;d, 10' the

, following: K4.02 Recirculation pump speed control: Plant* Specific 204000 RWCU ij(i 214000 RPfS ;k\'> ~c I~:r~

I;!i~:

Knowledge of the physical connections 215001 Traversing In-core Probe X 3,3 57 and/or cause effect relationships t~

between TRAVERSING IN-CORE PROBE and the following: K1.05 Primary r,~;, containment isolation system: (Not BWR1) 1."<;: I~;

215OO2RBM

,,: 1 n

216000 Nuclear Boiler Inst.

219000 RHRlLPCI: TorusIPool Cooling Ii"~. .' Ability to manually operate and/or 4.1 58 XI; Mode I, monitor in the control room: A4.12 Suppression pool temperature

~

,i Ability to monitor automatic operations of 223001 Primary CTMT and Aux. X 3.4 59 the PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES including:

AS.03 System indicating light and alarms Knowiedge of the operational 226001 RHRlLPCI: CTMT Spray Mode X

. I.

implications of the following concepts as they apply to RHA/LPCI:

2.6 60 I,'

I,>'"

CONTAINMENT SPRAY SYSTEM 1"\ L' MODE: K5.06 Vacuum breaker ooeration o RHRlLPCf: Torus/Pool Spray I~::j;; m:f I I

I':." Ability to predict and/or monitor changes 233000 Fuel Pool Cooling/Cleanup x I,> I" .. in parameters associated with operating 3.1 61 the FUEL POOL COOLING AND 1

CLEAN-UP controls including: AL03 Pool b i temoerature 234000 Fuel Handline Equipment I..**.. I.,". ". I', 1< Ii.;*.. I* '.

I 239001 Main and Reheat Steam I 239003 MSIV Leakage Control r"*/ Knowledge of the effect that a loss or 241000 ReactorlTurbine Pressure Regulator I> malfunction of the following will have on the REACTORITURBINE PRESSURE 3.8 62 REGULATING SYSTEM: K6.06 Reactor

~.c pressure 245000 Main Turbine Gen. fAux. I', . ,.

00 Reactor Condensate h

Knowledge of electrical power supplies 259001 Reactor Feedwater X I, to the following: K2.01 Reactor 3.3 63 I'rr feedwater pump{s): Motor-Driven-Only 268000 Radwaste 271000 Offgas tl X Ii

. Knowledge of the effect that a loss or 64 s;~i' 3.2 maHunction of the following will have on I~ the OFFGAS SYSTEM; KS.11 Condenser vacuum 272000 Radialion Monitoring X

[1 . . . . I' Knowledge of the effect that a loss or 3.5 65

.. ,; maHunction of the RADIATION I.Ri~ .

MONITORING System will have on 1: .* ,. following: K3.05 Offaas system I~~'"

if.

266000 Fire Protection 268000 Plant Ventilation 1 ~) I; 290001 Secondarv CTMT n' 1%1;';

~1 290003 Control Room HVAC I~ft;;

290002 Reactor Vessel Internals I'i:ir I. . I 1

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facil Category KIA # Topic RO IR # IR #

2.1.23 Ability to perform specific system and integrated 4.3 66 plant procedures during I 1.

Conduct 2.1.25 such as 3.9 67 of Operations etc.

Subtotal 2.2.12 surveil 3.7 68 2.2.42 to recognize systE~m parameters that are 3.9 69 entry-level conditions for I 2.

Equipment Technical Control Knowledge of the bases in Technical Specifications 2.2.25 3.2 70 for limiting conditions limits.

Subtotal 2.3.4 Knowledge of radiation exposure limits under 3.2 71 normal or emergency I

3. of radiation or contamination h Radiation 2.3.14 3.4 72 Control that may arise during I normal, abnormal, or emergency conditions or activities.

Subtotal 2.4.1 Knowledge of EOP entry conditions and immediate 4.6 73 action

4. Knowledge how abnormal operating procedures Emergency 2.4.8 3.8 74 are used in I Procedures I Plan with EOPs.

of the bases for EOPs. 3.3 75

ES-401 Record of Rejected KIAs Form ES-401-4 Tier I Randomly Reason for Rejection Group Selected KIA Tier 1/ 295023/AK1.02 This K& A selection resulted in exam overlap with question #5 for Group 1 replaced with the K&A statement about Shutdown margin. Although different topic AK1.01 names/areas the concept is of limited use in operator knowledge discrimination. liandomly selected AK1.0l. Radiation exposure hazards.

Tier 21 2003000/K 1.18 This K&A statement ask what the physical relationship between Group 1 replaced with Kl.06 RHR/LPCI and the Reactor vessel is. It would be difficult to write an adequate question beyond what the RHR to vessel flowpath is.

Randomly selected Kl.06 for the ADS relationship to RHR.

Tier 21 215004/A3.03 This K&A for monitoring SRM operation and RPS status would not, Group 1 replaced with A3.04 have resulted in a valid question. The only connection would be using the concept of RPS shorting links removed which VY has not done in many years and has no operational intention or need of doing to make the logic system non-coincidence. A question about control rod block status is more operationally relevant.

Tier 21 202002lK4.05 This K&A statement was for design features of recirculation flow Group 2 replaced with K4.02 control that limited recirc pump speed mismatch. There are no design features at VY that do this. Another statement was randomly chosen resulting in a much broader area of knowledge in this topiC.

Tier 21 241000/K6.14 This K&A statement on the bearing oil malfunction to reactor/turbine Group 2 replaced with KG.06 pressure control was a low value (2.7) and would result in limited topics for a valid RO question. Randomly chose K6.06 for a better higher cognitive question result.

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