ML20014E624

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Draft Written Examination and Operating Test Outlines (Folder 2)
ML20014E624
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 10/01/2019
From: Thomas Setzer
Operations Branch I
To:
Public Service Enterprise Group
Shared Package
ML19007A361 List:
References
EPID L-2019-OLL-0016
Download: ML20014E624 (22)
v • d • e


Text

. ES-301 Adminis_trative Topic_s Outline_

Form ES-301-1 Facility:

Ho~e Creek Generating Station Date of Examination:

8/12/2019 Examination Level: RO

[Z]

SRO D Operating Test Number:

i Administrative Topic (see Note)

Type Describe activity to be performed i

  • 1 Code*

I :

Conduct of Operations S,D Complete The Daily Surveillance Logs I

q '

i]

I Conduct of Operations S,M Perform A Shift Turnover As On-Coming/Off-I

. Going NCO I

I_

i 1,

i 1

I i

t I

1; I

Perform Actions to Achieve Criticality and Raise: '

  • Equipment Control S,D Power to the Point of Adding Heat I

Radiation Control I

R,D Purge The Containment I,

,I'

i.

,I I

i I.

I 1:

Emergency Plan I

I I

I I

NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

  • Type Codes and Criteria:

(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (s 3 for ROs; s 4 for SROs and RO retakes)

(N)ew or (M)odified from bank (;?; 1)

{P)revious 2 exams (s 1, randomly selected)

ES-301 Administr~tive Topics Outline Form ES-301-,1 Facility:

Hoge Creek Generating Station Date of Examination:

8/12/2019 Examination Level: RO D SRO

[gJ Operating Test Number: _____ _

i1l===============9=====;;====a

__===================jl I, Type I

i Administrative Topic (see Note)

Conduct of Operations Conduct of Operations Equipment Control Radiation Control E:mergency Plan Code" i, R,D,P i

I i

I R,M R,D R,M Describe activity to be performed l

Ensure The Operating Shift Is Adequately Manned Review All Operations Logs In Use During A Shift Including Computer Logs Complete an Action Statement Log Sheet Verify Compliance with Gaseous Release Permit Utilize The ECG To Determine The Emergency Classification 1 NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

  • Type Codes and Criteria:

(C}ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (S 3 for ROs; s 4 for SROs and RO retakes)

(N)ew or (M)odified from bank (~ 1)

(P}revious 2 exams (S 1, randomly selected)

_ ES-301 c*ontrol Room/In-Plant System*s Outline Form-ES-301-2 Facility:

Hqpe Cr:ee_(< _Generating, Station Date of Examination: _

8/12/2019 Exam Level: RO

[Z!

SRO-I D SRO-U D Operating Test Number:

Control Room Systems: 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U System/JPM Title Type Code*

Safety Function

~

a.

AC. Electrical Dist. / Respond To A Turbine Generator Malfunction A,D,L,S -

6 I

b.

Reactor Core Isolation Cooling/ Reduce Torus Level Using RCIC D,S 4

System C.

Component Cooling Water I Transfer T ACS To The Standby SACs D,S 8

Loop

d.

Low Pressure Core Spray /Manually Start the Core Spray System A,D,EN,S 2

e.

Control Rod and Drive Mechanism/ Respond To A Control Rod High A,M,S I

1 Temperature

f.

Primary Containment System and Auxiliaries/ Operate The PCIG A,D,EN,S

],

5 System During Post LOCA/lsolation Conditions

g.

Average Power Range Monitor/Local Power Range Monitor/

D,S I

7 Respond To A Recirculation Pump Malfunction i

i h.

Reactorrrurbine Pressure Regulating / Perform a Cooldown Using D,L,P,S 3

Bypass Valves I

I*

In-Plant Systems: 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U

i.

Component Cooling Water/ Respond To A SACS Malfunction D,EN,R

. I B

j.

Uninterruptable Power Supply (A.G. /0.C.} / Remove 120 VAC A,D 1\\l 6

Electrical Distribution System From Service

/1

-*--.c.-.

k.

Primary Containment System and Auxiliaries / Purge the Vent line E,EN,L,N

,I 5

_jl All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions, all five SRO-U systems must serve different safety functions, and in-plant systems and I

functions may overlap those tested in the control room.

(

I.

  • Type Codes I

Criteria for R /SR0-1/SRO-U

I (A)lternate path 4-6/4-6 /2-3 i

(C)ontrol room i

(D)irect from bank S9/S8/S4 (E)mergency or abnormal in-plant

~1,~11~1 (EN)gineered safety feature

1/::: 1/::: 1 (control room system) l (L)ow-Power/Shutdown

~1/:::1/:::1 I

(N)ew or (M)odified from bank including 1 (A)

2/t! 2/:!: 1 (P)revious 2 exams s 3/s 3/s 2 (randomly selected)

(R)CA

!:1/:::1/:::1 (S)imulator

ES-301

  • *- Contr~I Room/In-Plant ~ystems Outline*

Form ES-a*o1.:2 :

Date of Examination:

8/12/2019 Facility:

Hope Creek Generating Station Exam Level: RO O SRO-I

!XI SRO-U 0 Operating Test Number:

Control Room Systems:* 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U System/JPM Title Type Code**

Safety Function

a.

AC. Electrical Dist./ Respond To A Turbine Generator Malfunction

b.

Reactor Core Isolation Cooling/ Reduce Torus Level Using RCIC System

c.

Component Cooling Water/ Transfer TAGS To The Standby SACs Loop

d.

Low Pressure Core Spray /Manually Start the Core Spray System

e.

Control Rod and Drive Mechanism / Respond To A Control Rod High Temperature

f.

Primary Containment System and Auxiliaries/ Operate The PCIG System During Post LOCA/lsolation Conditions

g.

Average Power Range Monitor/Local Power Range Monitor/

Respond To A Recirculation Pump Malfunction

h.

In-Plant Systems:* 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U

i.

Component Cooling Water I Respond To A SACS Malfunction

j.

Uninterruptable Power Supply (A.C. /D.C.) / Remove 120 VAC Electrical Distribution System From Service

k.

Primary Containment System and Auxiliaries / Purge the Vent line I

A,D,L,S - '

D,S I

i '"

D,S I

A,D,EN,S I

A,M,S A,D,EN,S D,S D,EN,R i

I A,D I

i I

1; E,EN,L,N II I

All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions, all five SRO-U systems must serve different safety functions, and in-plant systems and functions may overlap those tested in the control room.

  • Type Codes (A)ltemate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power/Shutdown (N)ew or (M)odified from bank including 1 (A)

(P)revious 2 exams (R)CA (S)imulator Criteria for R /SR0-1/SRO-U 4-6/4-6 /2-3

9/$ 8/$ 4 2
1/.: 1/.: 1 2: 1/2: 1/2: 1 (control room system) 2: 1/2: 1/2: 1 2: 2/~ 2/~ 1
3/
::i 3/~ 2 (randomly selected)

.: 1/2: 1/.: 1 6

4 8

2 1

5 7

8 6

5

Contro! Room/h1:Plant_Syst~ms Outline_.

Form ES-301-2 Facility:

Hope Creek Generating Station _

Date of Examination:

8/12/2019 ---

Exam Level: RO D SRO-I D SRO-U IX]

Operating Test Number:

Control Room Systems: 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U System/JPM Title Type Code*

Safety Function

-*-~*

a. AC. Electrical* Dist. / Respond To A Turbine Generator Malfunction A,D,L,S 6
b.
c.
d.

BE005; Manually Start the Core Spray System A,D,EN,S 2

e.

Control Rod and Drive Mechanism / Respond To A Control Rod High A,M,S 1

Temperature

' i

f.
g.

i

h.

In-Plant Systems: 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U

i.

Component Cooling Water/ Respond To A SACS Malfunction D,EN,R 8

j.
k.

Primary Containment System and Auxiliaries/ Purge the Vent line E,EN,L,N 5

All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions, all five SRO-LI systems must serve different safety functions, and in-plant systems and functions may overlap those tested in the control room.

  • Type Codes Criteria for R /SR0-1/SRO-U (A)lternate path 4-6/4-6 /2-3 (C)ontrol room (D)irect from bank S 9/S 8/S 4 (E)mergency or abnormal in-plant

~ 1k 1k 1 (EN)gineered safety feature

~ 1P-1P-1 (control room system)

(L)ow-Power/Shutdown

~ 1P-1P-1 (N)ew or (M)odified from bank including 1 (A)

'ii!. 2/'i!. 2/t?. 1 (P)revious 2 exams s 3/S 3/s 2 (randomly selected)

(R)CA

~ 1P-1/~ 1 (S)imulator

  • Appendix D Scenario OutUne Form E$-D-1

',.r.==================::;;====;=.,============:::::::::========

1 Facility:

I Hope~Cr.ee!< _.

Scenario No.: -----,-'"~

.. -~

1 Op-Test No.:..,,.----~

. ' J Examiners:

Operators: -.. -.. --'---_.--'--.. -.. --=--~-.-

Initial Conditions:

Plant is operatin~geroximately]5%.__po_w_er_. __________ _

Turnover:

.. ** Lqwer_f Pwer to ~pproximate.ly]0%.. Remove _a RFJ~ ~om sexvice...

Critical Tasks:

1. Manually initiate 1.1-RI to shut down the reactor. 2. Place HPCI in service to restore and maintain Reactor water level.

Event Malf.

r Event Event No.

I.

No.

j Type*

Description I

-*"~

1 I

R Lower Reactor Power with Recirculation System 2

N

' Remove RFP In Service 3

RM9635 I

Radiation Monitor Failure 4

, CU07 C

RWCU Leak Into RACS 5

ED09D2 C

Loss of 100482 6

RR31 M

LOCA 7

RP04 C

RPS Failure-ATWS/ARI Scram Successful i,!!-----+--------.--.+---.-.. ----------------------.. -. --------

8 i FW30/

,I HP14/5 C

Loss of Condensate-HPCI Injection Valves' Failure

- ~*,.---

I

/!

I I I I

i; I'

  • 1 (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor
  • . Appendix D Scenario Outline.

Form ES-D-1

-~- -..- ' -

Facility:

Ho~e Creek Scenario No.:

2 Op-Test No.:

Examiners:

Operators:..

I Initial Conditions:

AQeroximatel}{,95% Reactor:~ower with a startup::in [!roaress. SSW Pumg:c ta~j3ed out for maintenance.

Turnover:

Secure OrtWell makeu*e. Raise Reactor Power to 100% Power.

I I

I

Critical Tasks:

1. Start the A EOG. 2. Isolate HPCI steam leak. 3. Initiate actions to Emergenct Oeeressurize the reactor/Restore RPV Level..

Event Malf.

Event Event No.

No.

Type*

Description I

1 i

N Secure containment makeup I

2 R

Raise power with Recirculation Pumps I

I 3

SL03 I

Inadvertent SBLC Initiation

- -s-4 ED11B C

Loss of 100420 125 voe Bus I

I

. - -~

5A127 C

Secondary Condensate Pump Malfunction I

5 I

6 I

EG12 M

Loss of Offsite Power 7

i DG07A C

Auto Start Failure of EDG/LOP Sequencer Failure I

I 8

HP09 C

Steam Leak in H PCI Room with Auto Isolation Failure i

'I I

I

  • 1 I

I, I

(N)ormal, (R)eactivity, (I) nstrument, (C)omponent, (M)ajor

, Appendix D Scenario Outline Form E_S-D-1..

Facility:

~. --

Hoee Creek Scenario No.:

3 Op-Test No.:

Examiners:

Operators:,

- -~* -

Initial Conditions:

100% Qower.

Turnover:

Critical Tasks:

1. TriB and isolates RR pumB before DRWL ~ressure reaches 1.68 esiS:
2. OQen five SRVs after determining :SC ~ress_ure cannot be maintained below PSP curve.

Event Malf.

Event Event No.

No.

Type*

I Description 1

N

, Swap In-feeds to Non-1 E bus 2

RR19 I

Recirculation flow transmitter failure 3

I RCOB C

RCIC Suppression Pool Suction Valve Failure I

I 1

4 I

RR26 C

Reactor Recirculation Pump Seal Failures

. - i 5

_ I CR02 R

Core Instabilities I

6 I

MS15 I

Spurious Group 1 MSIV Isolation 7

  • 1 RR31 M
LOCA I

I I,.

8 i

QQ21 C

i RHR Pump Failure I

_J.

I 9

RH20 C

i Drywell Spray Valve Failure/Downcomer Failure i

I,

I I

i (N)ormal, (R)eactivlty, (l)nstrument, (C)omponent, (M)ajor

  • .*1*

.*. Form ES-401-1 Facility: Hope Creek.*

Date of Exam: 2Q19

  • Tier:

Group

, ROK/A Category Points,

SRO-Only Points.*

K1 K2. K3 K4 K5 K6 A1 A2. A3 A4 G*. Total A2.

G*

Total t

, 1

3.

3 3

3 4

  • 4 20

, 3.<*

.4

7.

Emergency and N/A N/A*.*

2 1

1 1

1.

2 1

, 7

2.

.1 3

Abnormal Plant Evolutions :

TierTptals 4.4:

4.

. 4 6.

.5

27. *

.5 5

lO *

2.

1 3

2

3. 3 1

,2

3.

2

.2

2.

.3 26 3:

2.

5

  • Plant 2

. 2 0

2.

1,,

1 1

1

1.

1 1 1

12 0

, 1,.*

, 2,,

.3 Systems Tier Totals 5

2 5

4 2

3* A

3. 3 3.4 38

,, 4 4*

.8

3. Generic Knowledge and Abilities Categories.

1

.2 3:

4 10

1

.*2*.

3 4

l 7

. 3

, 2:.

2 3.

~.

~.

1 2.,

Note: '.L :Ensure that at least tviio topics from every applicable KIA category are sampled within each tier of the RO ahd.. *

  • SRO-only outline sections (i.e:; except for one category in Tier 3 of the: SRO-ohly section, the 'Tier.Totals" ih.

each KIA category shall not be less than tviio). (One.Tier 3 radiation control KIA is allowed if it is replaced by a KIA from another Tier3 category.)

2.. The point total for each group and tier iri the proposed outline niust match that specified in the table.

  • The final
  • . point total 'for each group arid tier may deviate by +/-1 frorri that specified iri the table based on NRC revisions.

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

3. Systems/evolutions within each groupare identified oh tt,e outline. : Systems or.evolutions that do not apply at
  • the facility should be deleted with justification. Operationally important, site-specific systems/evqlutions that are not included on the outline should b.e added. Refer to Section D.1.b of ES~401 for guidan'ce regarding the.

. * ~liminatiori of inappropriate KIA statements.

4. Select topics from as many systems and evoiutions as possible. Sample every system or. evolution in thf3.

gmup before selecting a second topic for ariy*system Cl~ evo.lution. *.,

5.

Absent a plant-specific priority, only those Kl As having ari importance rating (IR.) of 2.5 or.nigher: Use the RO and SRO ratings for the RO c!nd SRO-only portions; respectively.. *..

6. Sel.ect SRO topics for Tiers. 1 an.d 2 from the. shaded systems.and KIA categories.
7. The generic (G) l</As in Tiers 1 and 2 shall be selecte.d from Section 2 of the KIA catalog, butthe topics m.ust..
*. ~e :re.levant to the.applicable evolution or system: Refer to Sectie>h D.1'.b. of E~-401 for tt,e applicable K/As..
8. *.on the following pages; enterthe KIA numbers; a brief description of.each topic, the topics'.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 equipf'Tlent is sampled in a category other than

.* Category A2 or G* on the SRO-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, I Rs, ~nd
  • point totals (#):on Form. ES-401~3. *Limit SRO selections to KIM, that are linked to 10 CFR 55.43.

. G* Generic K/As *

)

These systems/evolutions must be included as part ofthe sample (as applicable to the facility) when Revision 3*

of the KIA catalog is used to develop the sample plan: They are not required to be included when Lising earlier revisions of the KIA catalog.

These systems/evoiutions may be eliminated fmm the :sample ( as applic,able to the facility) when Revision 3 of the KIA.catalog is used to develop the sample plan;

Form ES-401-1 ES-401

  • BWR Examination Outline.

Emeraencv and Abnormal Plar,t. Evoiutions Tier 1/Grouo

  • 1./RO/SRO\\.*

Form ES040H.

E/APE. # / Name/ Safetv Function K1 K2 K3.. A1 A2

  • G*

K/ATooic(s). *.*

  • IR
  • ..
  • i9sb1 s.(APE 1.6) CPntro1 Rooni Al;iari~onmerit...
  • . tf *.... : :.,.. *.*.... *: *... **. '.

295019 (APE 19) Partiai *o~ Complete Loss.of Jnstrument Air t.~ *

  • 295021 (APE 21) Leiss qf Shutdown ~ooling' /
4.

. ;295023.(APE ~3)Retueling*AccidentsJ a.

295025 (EPE 2) High Reacitor'P~essure / 3 29,5031 (~PE 8) Reactqr Lo~ Water Levei f 2.

295001.(~PE 1) P~rtial or:Complet~ L~~s cit.

Forced Core Flow. C1rci.rlation / 1 & 4...

r*

295003 (APE 3) Partiai orComplete L~~s of AC Power/6.

295004 (APE 4) Partial or Total L~ss of DC.. X

X.

. 3 295006 (APE 6) Scram/1..

X 295016 (APE 16) <;:ontrol ~oom Ab~ndonrrient

. {7..

295018 (APE18) Parti~I cir c~*mplete Loss ~f

  • CCW/8*

295019 (APE 19) Partial or Complete Los~ of Instrument Ai.r / 8

  • 295021 (APE 21) Loss of Shutdown Cooling/. X 4

X..

G 2:4:35 !<riowledge oflocal !,iuxiliary...

  • . X ** ope_ratorta~ks i:lurin_g an Elmergen.cyarid the _4,0 76 -*

..*. resi.rltant ooerational effects:..

  • . x.*

AA2i01 Ability tcfdeterrnihe ar,d/or.iriterpreL tl'.le following as they:apply' to-PARTIA~ OR* 3.6

  • 11.*

COMPLETELO$$ OFiNSTRUMENTAIR:.

Instrument air svstem* oressure.

x.

G_ *2.4.47 Ability to di~gnose and recogriite *

  • X *.
  • trnds ln i;in accurate arid tim~ly manrier-
  • 4.2 78 * *.

. utilizing the appropriate control r.ooin..

  • reference.material.

~.04 Ability to 9eten:nine al:id/or i.nterpret

  • tl'lefoll.owing as they:apply to REl=UEL1t'1G.
  • 4,1 79 *.

A~CIDENTS: * :.. :

I +Occurrence of fuel-handliria accident

  • G 2.2.40 Abifity to apply Tec;hni~I X. Soecifications-for a svstem:..

.u. so

  • EA2.0.1.Abjlity to dete'rniine arid/or interpret.

the following as they apply to:HIGH: * *... *

  • 4.3 ** 81 :*

REACTOR PRESSURE:. Reactor oressure.*

G.2~ 1 :32 A!Jilify to. explain and 13pply $ystem X:. Umits*and ore'cautions.*

4.0. *.* 82..

... AA2.06Ability to detemiine arid/or interpret.

. X.

  • . *
  • the following as they apply to PARTIAL OR
  • 3.2
  • 1.

... COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION: Nuclec1r boiler *.

instrumentation..

G 2.2.39. Knowledgeofless*than or equal to

  • X one hour TedinicalSpecification acUon.
  • 3.9 2

statements for svstenis...

..

  • AKf 05 Knowledge of the operational.

implications of the following concepts as 3:3 *

  • 3

.. they apply to PARTIAL OR COMPLETE *

. LOSS OF D.C:POWER: Loss of breaker*..

  • I nrotection
  • AK2.05 Knowledge of the interrelations between MAIN TURBINE GENERATOR.

2.6 4

. TRIP andthefollowing: Extraction steam

.. svstem.

  • AK3.04 KnoWledge of the reasons for the' * *

.*.. followjng responses as they apply to

.. 3.1:. 5

  • .*. SCRAM: Reactor water. level setpoint setdown: -Plant~Sdecific. *.

AA 1.05 Ability*tci operate and/or monitor the following as they apply to CONTROL _*.

  • 2.8
  • 6 *
  • ROOM ABANDONMENT: D.C. electrical

... distribution*..

AA2,03Ability*to'.determjrie* and/or.interpret *

  • X.

the follOw1ng as they apply to PARTIAL OR 3.2... 7.

COMPLETE LOSS OF.COMPONENT.

  • COOLING WATER: Cause for par:tial or comblete loss.

G 2.2.36 Ability to analyze the effect Of 3

1 X.

  • maintenance activities, Sl!Ch as degraded.

8.

. poWer SOl,lrCeS, On the status.of limiting conditions for ooerations....

. *

  • AK1.02 Knowledge of the operational *
  • .*. implications oftheJ6ilowing concepts as 3.3. 9.

they apply to LOSS OF SHUTDOWN

  • *.. COOLING: ThemJal stratification
  • AK2.03 Knowledge of the interrelatio'ris
  • between REFUELING ACCIDENTS anc:I the 3.4
10.

followina: Radiatlon mOnitoririq eouibnient..

. I...

Form ES-4014*

EK3.02 Knowledge of thereasons for the *.

295024 High Drywall Pr_essure / 5

  • X

. following responses as they apply to HIGH ' 3.5 11 DRYWELL PRESSURE: Suppression pool sorav-ooeration: Plarit-Sriecific. :.

295025 (EPE 2) High Reactor' Pressure/ 3 X

EA1_;04 Abjjity"to operate arid/or nion_itor the*

3.8* 12 following as they apply to HIGH REACTOR PRESSURE: HPCI: :Plaht-Soecific *..

  • EA1.0.1 Ability to operate and/or"nionitor the.

295026 (EPE 3)Suppression Pool High Water X.

following as they apply to. SUPPRESSION 4.1.. 13 Temperature/ 5 POOL HIGH WATER TEMPERATURE:

Surmression cool cciolino.

295028. (EPE 5) High bryweli Temperature G 2.4.49*Ability to perform without refer.ence 4.6 14 X

to procedures those acUon.s that I require.. *.

(Mark I and Mark II only)/5 **

. ' immediate operation of system components and.controls..

295030 (EPE 7) Low Suppression Pool Water EK1,03 :Knowledge of the o*peraticinal.

  • 3.8.

15 X.

. implications of the following concepts as *..

Level/ 5

  • they apply to LOW SUPPRESSiON POOL..

WATER LEVEL: Heat caoacitv.. *. *

  • \\.*

2950_31 (EPE 8) ~eactor LowWater Level (2.

EK2:05 Knowledge of the*i.nterrela_tions *.

4.2 16 X

between.REACTOR LOW WATER LEVEL.

and the following: Low pressure coolant. :

)

iniection (RHR) *.*.....**

. EK3,01 Knowledge of the*reasons for the..

295037 (EPE 14) Scram Condition Presa"nt..

.X

.. following resporises as* they apply to

.. 4.1 17 and Reactor PowerAbove APRM Downscale.

SCRAM CONDITIONPRESENT AND or Unknown 11 :.

REACTOR POWER ABOVE APRM DOWNSCALE OR. UNKNOWN:

Recin,:ulatiori pump ti"ip/runback: Plant~:

.*. Saecific

  • 295038 (EPE 15) High Off~ite Radioactivity EA1 :05 Ability to operate and/or monitor the.

3.0.

18.

x:

..

  • following as they apply to HIGH OFF-SITE.

Release Rate/ 9 RELEASE.RATE: Post accident sample svsteni (PASS): Plant-Soecific.

AA2.10:Ability to dete"rmine and interpret the 2.9 600.0.00 (APE 24) Plant Fire On Site /8:

X following as they apply:to PL.ANT FIRE.ON 19

. SITE: TimeUmit of IOhQ~teim-breafhing air svstem for control room. *

  • G 2.2:22 Knowledge oflimiting conditions 700000 (APE 25} Generator Voltage and
x. for c:>peratioris and safety Um its..

4,0* 20 Electric Grid Disturbances 16...

KIA Cateaorv Totals:

3

3. 3 3

4i3* 4[4. Grouo PoiritTotal:

  • 20'~.. II*

\\.

\\

. G

4

. *. For:in ES-401-1 *.

ES-401

. BWR Examination Outline..

  • Emeraencv and Abnormal Plant Evoiutioris Tier'1/Grouo 2 (RO/SRO). *
  • For~ *ESc401~1 E/APE # / Name I Safetv Function.*.

K1 K2-.K3 A1 A2 G*

KIA Tooic(s) -*

IR i95007. (APE 7) H.igh. R~a~tcir Pressure,* 3 295009 (AP:E 9) Low Reactor Water Level / 2 :

(

  • 295.0.34 (E;PE 11).Secon~aryCOntainmer:it.

Ventilation. High Raaiation/9. * *.

295002 (APE 2) Loss of Main Condenser.*

Vacuum 13* *

. 29§orn (APE 10) High DryWell P~essure (5...

295014 (APE 14) ln~dvertent Reactivity Addition / 1 **

X 295015 (APE 15) Incomplete Scram/ 1

. X 2~§011 (APE 1n Abnormai bff~it~ Relea~e:....

  • X.

Ratei9 295029 (EPE 6) High Suppr~ssion Pool Water.

X Leve115

  • 295036 (EPE 13) Sebondary Containment High Sump/Area Water Level /5 X

AA'L02 Ability.to determine arid/odoterpret * * ***.

the following as*~h~y ~pply to ftiGH_* * * *

  • 4,1 83..

REACTOR-PRESSURE: Reactor power :

  • G 2A.34.Kriowledge of RO tasks X. iierfolTl)ed :outsi~ei the -~ain ~oritrol rO:otri 4.1 84 during -~n.emergency and the resultant

\\. *

. 6oeration*a1 effects.. *.

EA2.0~ Abil_ity to i;!Elfermin*e anq/or inte~pret. * *

  • the.fo*nowirig as.they appiyto : * *..

. 4.2*

  • VENTllATIONtllGH.RADIATION:.
  • . vent,latio*n.radiation levels

. *: AA2.02 Ability to determine and/or interpret.. *.

~:.... the following as they apply to LQSS OF :

3.2 21.

.. I DO;..,,er: Plant-Soecific.

G:2.4.31 Knowledge bf annunciator. *

. : X alarms, inqications, or respons~

4.2 22

  • X

. *1...*

  • I nrocedures.
  • .. AK1.03 Knowledge of the operational implications of the following concepts as **.

3:7 *

  • 23
  • they apply to-INADVERTENT.

REACTIVITY ADDITION: Shutdown.

marain*.*

. AK2, 11 Knowledge of the iriterrelations..

. between INCOMPLETE SCRAM and the *.

  • followina: Instrument air *
  • AK3.02 Knowledge ofttie re*asons for the.

following respons_es as ttiey apply to.t-:UGH OFF-SITE RELEASE RATE: Plant*

... ventilation...

EA 1 ;03 Ability to operate.and/or monitor **

..

  • the following as.th~y apply tci HIGH.....

. SUPPRESSION POOL WATER LEVEL:.*

.

  • RHR/LPC1*

EA2, Ability to determine*arid/or interpret.

.. the following as they apply to

..

. SUMP/AREA WATER LEVEL: Water level.

in the affected area.. *

  • 3.5 24 3.3 25 2.9 26 3.1 27
  • . 1 1

1 2/2 1/1 Grouo PointTotal:.

7i3

.*ES-401.

5 Form ES-401-1 ES-401

BWR Examination Outline Form ES-401-1
  • . Plant Svstems--':-Tier 2/Grouo 1 RO/SRO\\*

System#! Name.

1<1 K2 K3 1<4 K5 K6 A1 A2 A3 A4 G~

. K/J\\Tcipic(s)

. iR * : #

203000 (SF2, SF4 RHR/LPCI).

RHR/LPCI: Injection rvtode 215.004 (SF-7 SRMS) sciurce~Range Monitor 215.005 (!:3Fi PRMS) Avetage Po~er*:

Ra11ge MonitciriLo.cal Power Range Monito(.

2.62002 (SF6 UPS) uriinterr'uptable Pi;iwe~ supp1yyi.c1Dc) *

  • 206000 (SF2,SF4 HPCIS)

High-Pressure Coolant Injection.

203000 (SF2, SF4 RHR/LPCI).

RHR/LPCI.:_ Injection Mode 205000 (SF4 SCS) Shutdown Cooling 205000 (SF4 scsj Shutdown Cooling X

  • 206000: (SF2, SF4 HPCIS)
  • High~Pressure Coolant Injection 209001 (SF2, SF4 L.PCS)

Low-Pressure Core Spray 209001 (SF2, SF4 LPCS)

Low-Pressu*re* Core Spray 211 ooo (SF1 SLCS) Standby Liquid Control 212000 (SF? RPS) R~actorProtectlon X X

X X

X

  • x A2:01 Abllity tp (a) predict the impacts of the** 3;4 86 following Ori the RHR/L.PCI: INJECTION...

MODE (PLANTSPECIFIC); and.(b) based on

. those predictio,:ii;;.use procedures to. correct, coritroi, or mitigate the consequences bf..

those abhorrnal con_diticins. or bpercition~:

lnadeauate net oositive suction head :

. X G 2A9 *Knov;,ledge of lov{power/shutdown implications in accident (e:g:, loss of coolant

  • accid.erit.*or loss of residual heatreniovalj n:iitioation* strateaies;. :.

A2:0~Apility to (a) precli~ttt)e impc!cts ofthe.

.following on the AVERAGE POWER RANGE MONITOR/LOCALPOVVER.RANGE *

. MONITOR SYSTEM; and (b ). based on tho~e.

preciicticiris; use procedures to correct;.*....

control, qr:mitigate the.consequences of

. those abnon'rial-.conditions* or: operations:

. f\\2;08 F~ulty *o.i: erratic operaticin *qf detectors/svstems :

X. G 2.1.20 Abilfty to interpretand :execute :

procedure steps..

4.2.

87 3A*.BB 4.6 89.*:

i;;:gb~~t~oe (H~~~~~~~~ttrts *of the* 4:o 90 COOLANT.INJ.ECTIO.N SYSTEM; arid (b).

based.on _those predictions,.use procedures to ~drrect, control, or mitigate the.....

consequences cif those abriorrnal conditions ot:ooeraticins: Turbine fries:. BWR-2,3,4 x

  • G*2;1.2~ Ability to interpret reference 3.9 28 materials, such as graphs.curves, tables_, etc.

x G 2:4.30 Knowledge of events related tc, : :

  • 2;7 29 system operation/status that m.ust be reported to. internal organizations or external agencies, such as the State; the NRC, or the transmission* svstem. onerator.

K1 ;QB Knowledge of the physical corinections 3.9

. SHUTDOWN COOLING MODE) and the followinq: LPCI

  • K2.04 Knowledge of electrical power supplies. 2.5 31.
  • to the following: Turbine control circuits:
  • BWR-2,3,4 K3.01 Knowledge of the.effect that a loss. or *
  • 3.8
  • 32 malfunction of the LOW PRESSURE CORE SPRAY SYSTEM will have on following:

Reactor water level K4.07 Knowledge cif LOW PRESSURE CORE SPRAY SYSTEM designfeature(s) and/or interlocks which provide for the followina: Pumo oo:erabilitv testina

  • 2.8 33 K4,03 Kriowledge.ofSTANDBYUQUIO 3.8
34.
  • CONTROL SYSTEM design feature(s) and/or
  • interlocks which provide for the following:

Ke.eoina.sodium oentaborate in solution K1.10 Knowledge of the physical connectibris 3._2

~5 and/or cause/effect relationships between REACTOR PROTECTION SYSTEM and the followinq: Main turbine

ES-401 6

Form ES-401-1 212000 (SF7 RPS) Reactor Protection X

K5.01 Knowledge of the operational 2.7

  • 36 implications of the following concepts as they apply to REACTOR PROTECTION SYSTEM:

Fuel thermal time constant

  • 215003 (SF7 IRM)

X K6.03 Knowledge of the effect that a loss or 2.8 37 Intermediate-Range Monitor malfunction of the following will have on the INTERMEDIATE RANGE MONITOR (IRM)

SYSTEM: Detector drive motor 215004 (SF7 SRMS) Source-Range X

A 1.06 Ability to predict and/or monitor 3.1 38 Monitor changes in parameters associated with operating the SOURCE RANGE MONITOR (SRM) SYSTEM controls including: Lights

. and alarms 215005 (SF7 PRMS) Average Power x*

A2.10 Ability to (a) 'predict the impacts of the 2.8 39 Range Monitor/Local Power.Range following on the AVERAGE POWER RANGE Monitor

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

Chanaes in void concentration*

217000 (SF2, SF4 RCIC) Reactor X

A3.02 Ability to monitor automatic operations 3.6 40 Core Isolation Cooling of the REACTOR CORE ISOLATION

  • COOLING SYSTEM (RCIC) including:

. Turbine startuo 218000 (SF3 ADS) Automatic X

A4.07 Ability to manually operate and/or 3.5 41 Depressurizatiori monitor iri the control room: ADS valve acoustical monitor noise: Plant-Soecific 223002 (SF5 PCIS) Primary X

G_2.4.50 Ability to verify system alarm 4.2 42 Containment Isolation/Nuclear Steam setpoints and operate controls identified in Supply Shutoff the alarm response manual.

239002 (SF3 SRV) Safety Relief X

K1.04 Knowledge of the physical connections 3.6 43 Valves and/or cause/effect relationships between RELIEF/SAFETY VALVES and the following:

Main steam 259002 (SF2 RWLCS) Reactor Water X

K2.02 Knowledge of electrical power supplies 3.5 44 Level Control to the following:. Feedwater coolant injection

, (FWCI) initiation loaic: FWCI/HPCI 261000 (SF9 SGTS) Standby Gas X

A4.08 Ability to manually operate and/or 2.6 45 Treatment monitor in the control room: System temperature 261000 (SF9 SGTS) Standby Gas x

K3.01 Knowledge of the effect that a loss or

K4.06 Knowledge of A.C. ELECTRICAL 3.6 47 Distribution DISTRIBUTION design feature(s) and/or interlocks which provide for the following:

Redundant cower sources lb vital buses.

262002 (SF6 UPS) Uninterruptable X

A 1.02 Ability to predict and/or monitor 2.5 48 Power Supply (AC/DC) changes in parameters associated with operating the UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) controls including: Motor aenerator outouts 263000 (SF6 DC) DC Electrical

  • X K6.01 Knowledge of the effect that a loss or 3.2 49 Distribution malfunction of the following will have on the D.C. ELECTRICAL DISTRIBUTION: A.C.

electrical distribution 264000 (SF6 EGE) Emergency X

A1.03 Ability to predict and/or monitor 2.8 50 Generators (Diesel/Jet) EOG changes in parameters associated with operating the EMERGENCY GENERATORS (DIESEUJET) controls including: Operating voltaaes, currents, and temoeratures 300000 (SF8 IA) Instrument Air X

K3.02 Knowledge of the effect that a loss or 3.3 51 malfunction of the INSTRUMENT AIR

?YSTEM will have on the following: Systems havinq pneumatic valves and controls

ES~401 7

. *. Forrri ES-401-1'.

300000 (SFB IA) lnsfrurnenfAir.

X A2.01 Ability to (a).predict the impacts *of the. 2;9 52 following.on the INSTR.UM ENT AIR SYSTEM*

and (b) based on those pred.it:tioris, use I

procedures to com,:ict; control, or mitigate the.

consequences ofthose abnoiinal operation:.

  • Air:drver and filter malfunctions.

400000 (SFB CCS) Component X

A3.01

  • Ability tb moriitor a.utomat.ic operations*
  • 3.0*. 53 Cooling Water of the CCWS* including*: Setpoints o.n
  • iristrumerit sigrial levels for norrnal operatioris:.warnirigs, ahdtrips that are aoolicable to the ccws.

KIA CategoryPoinfTotals:

3 2 3 3 1.2 3 2/ z> 2 3i C31'oup Poli1ffotai:

26i5 3

2

).

I*

  • Es.:401*

Form ES-401~1-.*

ES401

  • BWR Examination Outline.

"Form ES-40H

  • Plant Svstem5-'-Tier 2!Grouo* 2 (RO/SRO\\

Svstem # I Jilame..

K~ K2 K3 K4 K5 K6 A1 A2 A3 A4. i3*.

K/ATo~i~/s\\

  • IR

~o.1061. (Sl',1. CROH) CR,D Hydrauiic

.* X.

G 2.* 4.45 Ability tq priori~ize and *.

4,3 9.1 interpret the_*significance ofea~li.

annunciator or alarm,... *

  • 214000 (SF7RP1S) Rod Position iriform~iion.

X

.*. A2.92 Ability to (a) predict.the*..

3.1 92

\\mpacts. of the foll01.ying *ol:i° the ROD

  • POS1Tlot{INFQRMATIC>N... *.

.. *sYSTEM; and.(b).based _ori those.

  • predictions, use procedures-_to..
  • correct, coiitroi, ormitigate the.. * :
  • ri9nseqllences.ofth6¢e abn*orma.1
  • . con.dition$ or operation$: Reactor SCRAM*.

2i2ocio" (SF7; SF9 _RMSi RadiatiO!l Monitoring G *2.1.31 Ability to locate control rciom

}(. switches, ccintrols,."and iridicaticins;°.. 4.3

!1~*

. *and to.detert'riirie that t~ey correctly reflect the desired olant lineup,.

  • 201002 (SF1 RMCS)Reactor Manu*a1 Coritrol X

K1 :03 Knowledge cif the physical*

coimeictic;>ns arid/or ca*use/effect..

3.4

54.

relatlonships between REACTOR*

  • MANUAL CONTROL SYSTEM and the following: Control rod block *.

.. interlocks/power operation"& *.

refuelina..

20*100-3:(si=1 CRDM)"Co"ntrol Rod and Drive

.x K3.02 Knowledge of the effect that a 2.8 55 Mechanism.

loss or malfunction* of the CONTROL

.. ROb AND DRIVE MECHANISM wili

  • have on followina:.tFlux shapini::I
  • 20200f (SF1: SF4 RS) Recircula!iori

. X K4,01 Knowledge of RECIRCULATION System design

. feature(s}arid/or interlocks whi_ch

  • 3.. 9.

56 provide for the following: 2/3.core

  • coveraae:: Plant-Soecific.
  • 204000 (SF2 RWCU) Reactor Wate_r Cleanup
  • X

.. K5.05 Knowledge of the operational

  • 2.6.

57 implicatibns*ofthe following*

concepts as they"applyto-REACTOR WATER CLEANUP*

  • SYSTEM:* Flow controllers.

216000 (SF?. NBI) Nuclear Boiler lnsirun'ieritati6n X

K6.02: Knowledge of the effectthat a. 2.8

58.

loss 0~ rnalfuriction of th_e following.

  • will.have cin the NUCLEAR BOILER INSTRUMENTATION: D.C. electrical distribution

X Al:09.Ability.to predict and/or nioriitor 3.5 59 Auxiliaries

changes in parameters associated..

with operating the PRIMARY.

CONTAINMENT.SYSTEM AND

.A.UXiLIARIES controls including:

Sunrire*ssion oool temo*erature.

  • 25600() (S F2. CDS) Condensate
  • X.

A2.0t Abilizy to (a) predictthe. *:

3.3 60 impacts of the following on the REACTOR CONDENSATE SYSTEM; and (b) based o.n those predictions;. use procedures to.

correct,.control, or mitigate the consequences*ot those abnormal.

  • conditions or ooerations: Pump.trips
  • 259001 (SF2* FWS) Feedwat~r A3.09 Abilitytci monitor automatic x

operaticms of tt:,e REACTOR * * *.

Liahts arid alarms 26800"0" (SF9 RW) Radwaste A4.0.1 Ability to manually operate:

X and/or monitor in the control room:

3.4 62

  • A4.01 Sumo intearators* *
  • Es.:401*

Form ES-401~1' 271000 (SF9 OGJ°Offgas G 2.4.4 Ability to. recognize abnormal..

X indications fcir system operating. *

  • 4.5 63

!parameters that are entry-level

. conditions fcir emergency and abnormal ooeratinci orocedures:

2s*socio (SF9 PVS) Plant Veniilation X

K1.04 Knowledge of the physical**

2.6 64*

conriection*s.and/br.cause/effect relatioriships b.etween PLANT VENTILATION S'i'STEMSandthe following: Applicable component *.

coolina*water svstem: P.lant Specific 290001 (SF5 SC) Second~ry Coniainment X

.. K3.01. Knowledg~ of th~ effectthat c1. 4.0 65 loss or malfunction ofthe

have on following: tOff-site radioactive release rates K/A Cateaorv Point Totals:-.

  • 2 0

2

1.. 1 1. 1 i/1 1. 1 1/2 Grouo Point Total:..

12/3.

  • . * *..* Generic Knowledge. arid "bilities. Outnne (Tiet 3) :.*

.*. Form ES-401~3

. Facmty:. Hope Creek D~te of Exam: 201 ~

Category t conduttot Operations *..

  • 2. Equipment* *.
  • Control*
  • 3;Radiatiori.

. Control. *.. : *

  • 4. Emergency'.

Procedures/Plan Tier 3 Point Total.*

KIA#

Topic.

  • . RO*..

. SRO~oniv.

IR IR 2.1.4

. Knowledge of individual licensed*op*erator responsibilities

  • related to shift staffing, Stich as medical' requirements; "no~..

solo;'. operation, maintenance of active license status.,..

. 1 OCFR55, etc. *

  • Ability.tci direct perscinne1*activitiElS inside the:controlroom.*.
  • 3.3.

66

67.

2,1.34

Knowledge of primary *and secondary. plarit chemistry.limits.. : * *

. 68

. 2,7 2.12

. l<rio:Wledgeof operator. responsibilities during.au.m*odes.of plant*

ooeration: * *
Knowledge qf how to conduct system lineups,. such :as val\\ies;

. breakers,'.switches, etc:...

. Subtotal.*

Knowledge of the process for making changes* to procedures.*

.2.2.6 *.*

. 2,2 _13: : *. Knowledge of tagging and clearance procedures...

  • Kn*owleqge of the p~oriess fcir making. design qr oper;:iting *
  • 2.2.9.

. chances to the f1:1cilitv; * *

  • * *. Know!edge ¢f the process'for managing *mainfenanpe.activifies 2;2;18, *
  • during shutdown :operations; such as risk assessriients, :Work..
  • orioritiiation; etc.. :*.
  • Subtotal.*

4.1

. 2.3~5.

Ability to use radiation.monitoring systems, such as fixe.d *.

. *. 2_9. *

. radiation monitors and 'alarms; portable survey instruments,..

personnel 'monitorinq eauioment; etc.

  • 2'.3.7. i Ability to comply with. radiation work permitrequiremeirits during *
normalor abnormal conditions.. *
  • 3.5

. 2'.3.11*

Subtotal.

.*.2.4.2 :*

2.4.26:

. 2A.29

. 2.4.38

.* Ability to control. ra.diation. releas:es. *....

  • Knowledge of system* set points; interlocRs.and automatic**

actions associated with EOP entrv conditions..

  • Knowledge*offacility protection requiremeilts;iricludirig fire.. *
  • briaade and ocirfable firefiahtinci eciuiomentusaae. * * *

'l<nowledge6f the e1T1ergency plan;. * *

Ability to tak'e actions called for.iii ~e facility emergency* plan,

)ncludi!]g supporting or act.ing as.emergericy qqordina~or if..

  • .* reauited: :- *

. 2A:39: Knowl.edge ¢f RO {esponi,'ibilities. in en:iergency. plan'. *

. im olemeritation.

  • Subtotal.*

..... I 4:5.:

3.1 71 72..

73 * *

  • .. 74.

.75.

10

.4A

. 94:

4.o*

.96.*

3.9

.97'

.. 4.3 :. *gs:

4.4*.*

99 3.8

100

ES-401 Record of Rejected K/As Form ES-401-4 Tier/ Group Randomly Selected Reason for Rejection KIA Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations.

1/1 (#8) 295019 / G 2.2.36 Cannot write a TS question for instrument air.

Randomly re-selected G 2.4.50 Ability to perform without reference to procedures those actions that I require immediate operation of system components and controls-High Drywall Temperature 1/1 (#14) 295028 / G 2.4.49 No Immediate Operator Actions for Hi Drywall Temperature condition.

Randomly re-selected G 2.1.23 Ability to operate and/or monitor the following as they apply to HIGH OFF-SITE RELEASE RATE: Post accident sample system (PASS): Plant-Specific 1/1 (#18) 295038 / EA 1.05 The PASS system is no longer used at Hope Creek. There are other means used for sampling post-accident.

Randomly re-selected EA1.04 Ability to determine and interpret the following as they apply to PLANT FIRE ON SITE: Time limit of long-term-breathing air system for control room.

1/1 (#19) 600000 I AA2.10 There is no long-term breathing air system at Hope Creek.

OBAs are used for this purpose.

Randomly re-selected AA2.17 Knowledge of limiting conditions for operations and safety limits.

There are no technical specification associated safety limits for 1/1 (#20) 700000 I G 2.2.22 Generator voltage and Electric Grid Disturbances.

Randomly re-selected G 2.4.47

ES-401 Record of Rejected K/As Form ES-401-4 Tier/ Group Randomly Selected Reason for Rejection KIA Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator.

2/1 (#29) 205000 I G 2.4.30.

Reportable (ECG) is at the SRO. level.

Randomly re-selected G 2.4.47 Knowledge of the operational implications of the following concepts as they apply to REACTOR PROTECTION SYSTEM:

Fuel thermal time constant.

2/1 (#36) 212000 I K5.01 Cannot write an operationally valid question for fuel thermal time constant.

Randomly selected K5.02 Ability to (a) predict the impacts of the following on the AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Changes in void concentration 2/1 (#39) 215005 / A2.10 GFES-Thermodynamics. There are no mitigating strategies (procedures) for changes in void concentration specifically.

Randomly selected A2.01 Knowledge of the effect that a loss or malfunction of the CONTROL ROD AND DRIVE MECHANISM will have on following: tFlux shaping 2/2 (#55) 201003 / K3.02 Cannot write an operationally valid question.

Randomly selected K3.01 Ability to direct personnel activities inside the control room.

KIA is not an RO level question.

3/1 (#67)

G 2.1.9 Randomly selected G 2.1.31

ES".'401 Record of Rejected K/As Form ES-401-4 Tier/ Group Randomly Selected

~

Reason for Rejection KIA Knowledge of primary and secondary plant chemistry limits. KIA is likely to require a reference, such as an entire procedure (DLU).

Cannot write a discriminating question.

3/1 (#68) 2.1.34 Randomly reselected 2.1.1 Ability to use radiation monitoring systems, such as fixed

/

radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

3/3 (#71) 2.3.5 Cannot write a discriminating question.

Randomly reselected 2.3.12

. Knowledge of facility protection requirements, including fire brigade and portable firefighting equipment usage.

3/4 (#74) 2.4.26 Cannot write a discriminating question.

Randomly selected 2.4.39 Cannot write a discriminating question.

1/1 (#82) 2.1.32 Random Iv selected 2.1.20 Cannot write an SRO level discriminating question for this APE.

Added in EPE 295031 to Tier 1 Group 2 IAW ES-401, as a site specific KIA that is operationally important 1/2 (#83) 295007 I A2.02 pertaining to this facility but was not originally included on the generic Tier 1 Group 2 list.

Randomly selected 295031 / A2.02 Cannot write a discriminating question.

2/1 (#86)

A2.01 Randomly selected A2.04

\\

Cannot write a discriminating question.

3/4 (#100) 2.4.39 Randomly selected 2.4.25 HC does not monitor system temperature from the control room 2/1 (#45)

A4.08 for standby gas.

(

Randomly reselected A4.07 Cannot write an operationally valid question regarding DC for 2/2 (#58)

K6.02 nuclear boiler.

ES-401 Record of Rejected K/As Form ES-401-4 Randomly reselected K6.01 Cannot write a discriminating question of appropriate level of 2/2 (#65)

K3.01 difficulty.

Randomly reselected K6.01 KIA is more suited for RO level knowledge.

1/2 (#84) 2.1.28

  • Randomly reselected 2.1.20 KIA is more suited for RO level knowledge.

2/1 (#87) 2.4.9 Randomly reselected 2.2.40 This KIA overlaps substantially with question #44.

2/1 (#31) 206000 I K2.04 Randomly reselected K2.01 Cannot write a discriminating question.

2/1 (#46) 261000 / K3.01 Randomly reselected K3.04

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