ML13032A151

Initial Exam 2012-301 Draft Administrative Documents

ML13032A151
Person / Time
Site:	Brunswick
Issue date:	01/29/2013
From:	NRC/RGN-II
To:	Duke Energy Corp
References
50-324/12-301, 50-325/12-301
Download: ML13032A151 (26)

Text

ES-401, Rev. 9 BWR Examination Outline Form ES-401-1 FaciIyBRw4St)tl(_- DateofExam:

2012, PECEWP.

RO K1A Category Points

$RO.Only Points Tier Group 11K K

K A

AAAGF A2 G*

Total 1

21314 5

6 1

2 3

4

• lTotaI i

343 7

Emergency&

ITT 1

17 2

1 3

Abnormal Plant

NIA

NIA

,el-Totals 6

5 4

27 8

4 10

=

= =

=

1 23232223223 26 3

2 5

2.

2 12111111111 12 0

2 1

3 Plant Systems Tier Totals 3

4 3

3. GenerIc Knowledge and Abilities 1

2 3

4 10 1

2 3

4 7

CategorIes 3

3 2

2 1

2 2

2 1.

Ensure that at least two topics from every applicable KIA category are sampled within each tier ofthe RO and SRO-OI1IY outlines (I.e., except for one category in Tier 3 ofthe SRO-only outline, the tter Totals in each KIA category shall not be less than two).

2.

The pointtotal for each group and tier in the proposed outline must match that specified in the table.

The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO.only exam must total 25 points.

3.

Systemsievolutloas within each group are Identified on the associated outline; systems or evolutions that do not apply at the facliity should be deleted andjustified; operationally Important, site-specific systems that are not included on the outline should be added. Refer to ES-401, Attachment2, 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 KAs 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 I and 2from the shaded systems and KIA categories.

7.

The generic (G) KlAs In Tiers I and 2 shall be selected froni SectIon 2 of the t(IA Catalog, but the topics must be relevant to the applicable evolution or system.

8.

On the following pages, enter the KIA numbers, a brief description ofeach 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; Iffuel handling equipment Is sampled In other than Category P2 or G* on the SRO.only exam, enter It on the left side of Column P2 for Tier 2, Group 2 (Note

1. 1 does not apply). Use duplicate pages for RO and SRO-anly exams.

9.

For TierS, select topics from Section 2 of the KJA catalog, and enter the IVA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Um1tSRO selections to KIAs that are linked to 10 CFR 55.43.

ES4OI 2

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

E/APE #1 Name! Safety Function K

K K

A A

G K/A Topic(s)

IR 12312 295001 Partial or Complete Loss of Forced

z. za Core Flow Circulation /1 & 4 295003 Partial or Complete Loss of AC /6

AA.01 295004 Partial or Total Loss of DC Pwr /6

t (R) A 4 I. o3

(çL),,

295005 Main Turbine Generator Thp /3

(j) A kg.

295006 SCRAM/I ft

() 4 I.

(z)

2. 1. 2.S

295016 Control Room Abandonment /7

A R 3.o I 295018 Partial orTotal Loss of CCWI8 g

(P.) AA 1 0 1 295019 Partial or Total Loss of Inst. Air! 8

g (13)c 2.

3 a

2 () ft A. i 2-

29502 1 Loss of Shutdown Cooling! 4

R (s.) A-A. #

295023 RefuelingAcc/8 g.

(F) Ai&3,o2

295024 High Drywell Pressure /5

(R)

E I. 04-

295025 High Reactor Pressure /3

R $

([i).tA I OS,, ()

2. o3 295026 Suppression Pool High Water r 1j Temp./5 tS? f.O(D 295027 High Containment Temperature 15 295028 High Drywell Temperature /5 t.

(R.. R I 02.

295030 Low Suppression Pool Wtr Lvi! 5

R

A 2.

295031 Reactor Low Water Level/2 R.

(s.) EI. 0

295037 SCRAM Condition Present and Reactor Power Above APRM 1

1/)) £I I. ()

2 Downscale or Unknown / I 295038 High Off-site Release Rate / 9

P) E-i 2. 0(0 600000PlantFireOnSite/8

(Li) PrA.I 0

() iS

Voltage and Electric Grid

C) 2 4.30, (0).. -z

K/A CategoryTotais:

4 3 3 3

Group PointTotal:

2on 4

TIGI BWR EXAMINATION Cause of partial or complete loss of A.C. power A.C. electrical distribution.

Main generator protection Shutdown margin Reactor SCRAM Backup systems Ability to explain and apply all system limits and precautions.

Reactor water temperature Interlocks associated with fuel handling equipment....

Emergency depressurization RCIC: Plant-Specific RO SRO ES-401, REV 9 OUTLINE FORM ES-401-1 KA NAME I SAFETY FUNCTION:

IR 1(1 K2 K3 1(4 1(5 K6 Al A2 A3 A4 G TOPIC:

295003AA2.01 Partial or Complete Loss of AC! 6 3.4 3.7

[] LI LI LI C I

LILILILI 295004AA1.03 Partial or Total Loss of DC Pwr/ 6 3.4 3.6 LI LI LI LI L LI II LI LI El El 295005AK2.04 Main Turbine Generator Trip! 3 3.3 3.3 LI LI El C El LI LI LI LI El 295006AK1.02 SCRAM!

3.4 i LI LI LI L LI Li LI LI LI El 295016AK3.Q1 Control Room Abandonment! 7 4.1 4.2 LI LI l] LI LI LI LI LI LI LI 29501 8AP1.01 Partial or Total Loss of CCW 18 3.3 3.4 LI LI LI El L LI LI LI LI El 295019G2.1.32 PartialorTotal Loss of Inst. Air/B 3.8 4.0 LI LI LI LI L LI LI LI LI LI 295021AA2.04 Loss of Shutdown Cooling /4 3.6 3.6 LI LI LI LI E LI LI (l LI LI El 295023AK3.02 Refueling Acc CeeL M..4s 18 3.4 3.8 LI LI L1 LI L LI LI LI LI LI E]

295024Ek3.04 High Drywell Pressure/S 3.7 4.1 El LI I1 LI C LI LI LI LI LI El 295025EA1.05 High Reactor Pressure /3 3.7 3.7 LI El LI LI L LI ll LI LI LI El Page 1 of 2 211512012 5:58AM

NAME I SAFETY FUNCTION:

Suppression Pool High Water Temp. /

5 High Dryweli Temperature /5 Low Suppression Pool Wtr Lvi! 5 Reactor Low Water Level /2 SCRAM Condition Present and Power Above APRM Downscaie or Unknown Il High Off-site Release Rate /9 Plant Fire On Site / 8 Generator Voltage and Electric Grid Distwrbancecs Partial or Complete Loss of Forced Core Flow Circulation/i & 4 FORM ES-401-1 TOPIC:

Suppression pool cooling Equipment environmenlal quaflcation Suppression pool temperature Natural circulation: Plant-Specific Reactor pressure effects on reactor power Process liquid radiation monitoring system Time limit of long-term-breathing air system for control room Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.

Knowledge of limiting conditions for operations and safety limits.

ES-401, REV9 KA 295026EK2.O1 295028EK1.02 295030EA2.02 295031 EK1.02 295037EK1.01 295038EK2.06 600000M2.10 700000G24.30 295001022.22

()

TIGI BWR EXAMINATION OUTLINE IR KIK2K3K4K5K6A1A2A3A4G RO SRO 3.9 4.0 2.9 3.1 3.939 LEL1IEJiiE 3.8 4.1 4.1 4.3 3.4 3.7 DEEEOLE 29 3.1 LEEE1L1 2.7 4.1 EÜEL1DEJL1 4.0 4,7 Page 2 of 2 2/15/2012 6:04 AM

SRO TIGI BWR EXAMINATION OUTLINE IR K1K2K3K4K5K6AIA2A3A4G RO SRO

• DDDDODDDD1 3.9 4.2 flJflEJD 3.6 3.7 3.9 4.1 flOJOL1flfl 4.2 4.3 EJEDüOOL1Uü 2.3 3.5 EDODDUDUI1 3.9 4.6 ELOÜOL1DDLI Contrd rod position Requirements for establishing a fire watch Abllity to ecagnize system parameters that are entry-level conditions for Technical Specifications FORM ES-401-1 ES-401 1 REV 9 KA NAME I SAFETY FUNCTION:

295004G2.l.23 Partial or Total Loss of DC Pwr/ 6 295006G2.1.25 SCRAM! 1 29501 9AR2.02 Partial or Total Loss of Inst. Air /8 295025EA2.03 High Reactor Pressure /3 295037EA2.05 SCRAM Condition Present and Pa.ver Above APRM Downscale or Unkncmn I 600000AA2.15 PlantFireOnSite!8 700000G2.2.42 Generator Vcdtage and Electric Grid Distrurbanoecs TOPIC:

Ability to perform specific system and integrated plant procedures during all mcxles of plant operation.

Ability to interpret reference mat&als such as graphs, monographs and tables which contain performance data.

Status of safety-related instrument air system loads (see AK2.1 -AK2.19)

Suppression pool temperature Page 1 of 1 2/1512012 6:08AM

ES-401 3

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

=

EIAPE #/ Name I Safety Function K

K K

A A

G K/A Topic(s)

IR 12312 295002 Loss of Main Condenser Vac /3

R 2 +

295007 High Reactor Pressure /3

295008 High Reactor Water Level! 2 295009 Low Reactor Water Level/2

(R) A.A 2..02.

295010 High Drywell Pressure 15 R

{L.) A 1< I 03 ()

2. I. 20

295011 High Containment Temp 15

295012 High Drywell Temperature! 5

295013 High Suppression Pool Temp. /5

295014 Inadvertent Reactivity Addition 11 295015 Incomplete SCRAM! I 295017 High Off-site Release Rate I 9

I)

A I.,OS 295020 Inadvertent Cont. Isolation/S & 7 295022 Loss of CRD Pumps! 1 (P.)

A K?. 3

295029 High Suppression Pool Wtr LVI /5 f)

EA 295032 High Secondary Containment r

n Area Temperature! 5 is) 0 295033 High Secondary Containment c A -

Area Radiation Levels /9

La?) 1t c(

I

295034 Secondary Containment Ventilation High Radiation / 9 295035 Secondary Containment High Differential Pressure /5 295036 Secondary Containment High Sump!Area Water Level! 5 500000 High CTMT Hydrogen Cone. / 5

(#) 4 2. ci

K/A Category Point Totals:

R.0 lz L I Lb.

Group Point Total:

S P.O

295009AA2.02 Low Reactor Water Level /2 3.6 3.7 295010AX1.03 High Drywell Pressure /5 3.2 3.4 ES-401, REV 9

(>

TIG2 BWR EXAMINATION OUTLINE KA NAME I SAFETY FUNCTION:

IR K1 1(2 K3 1(4 K5 K6 Al A2 A3 A4 G RO SRO 295002G2.4.45 Loss of Main Condenser Vac /3 4.1 4.3 LI LI [I LI C El LI El El El DLI LIE LI L1LID El LI LID C El LI DL] Eli LIDC LID DLI [1 El DLI LIE DDDDLI El LI]CLIDD DDIDEDLIDD 29501 7AK2.08 High Off-site Release Rate 19 2.8 3.3 El 295022AK1.02 Loss of CRD Pumps/i 3.6 3.7 295029EA1.04 High Suppression Pool Wtr Lvi / 5 3.4 3.5 295032EK3.01 3.5 3.8 High Secondary Containment Area Temperature /5 FORM ES-401-1 TOPIC:

Ability to prioritize and interpret the significance of each annunciator or alarm.

Steam flow/feed flow mismatch Tomperalure increases SPDSIERIS/CRIDS/GDS Reactivity control LI El RCIC: Plant-Specific LI El Emergency/normal depressurization Page 1 of 1 2)15/2012 6:06AM

ES-401, REV9 KA NAME I SAFETY FUNCTION:

295010G2.1.20 High Drywell Pressure/5 296033EA2.03 High Secondary Containment Area Radiation Levels I 9 500000EA2.O1 High CTMT Hydrogen Conc. 15 SRO TIG2 BWR EXAMINATION OUTLINE IR K1K2K3K4K5K6A1A2A3A4G RO SRO 4.6 4.6 3.7 4.2 L1LLJUEÜL11E1E1Z 3.1

ÜEÜELL1LLJLli1 TOPIC:

Ability to execute procedure steps.

Cause of high area radiation Hydrogen monitoring system availability FORM ES-401-1 Page 1 of I 211512012 6:09AM

ES-401 4

Form ES4OI-1 ES-401 BWR Examination Outline Form ES-401-1 PIantms-Tier2IGrou1(RO!SRO)

=

System #1 Name K

K K

K K

K A

A A

A G

KIA Topic(s)

IR 1234561234 203000 RHRILPCI: Injection LR) IQ. D Mode 205000 Shutdown Cooling LR)

At ID

() AZ Ia

206000 HPCI 1.

) IØ 207000 Isolation (Emprgency)

Condenser C J/A) 209001 LPCS

( R4.o, (J)Gi 2,

209002 HPCS (J/A

2I1000SLC (g) R5,D 21 2000 RPS

()

A 4; 04-215003 IRM

- - c 4. c-, ()

215004 Source Range Monitor

() A 4- 03

215005 APRM I LPRM

VL f\\3, 1)4

217000 RCIC

() 1 4

3.oi

218000 ADS PS ()

2.4.20, (i) A.

223002 PClSINuclear Steam SupplyShutoff 1.0

239002 SRVs

jZ (s) G1 2 +.2- () 3. D

259002 Reactor Water Level j2_

Control is.

(c.),3.)O 261000 SGTS g

() kI. 03, g,

()A 2,Q3 262001 AC Electrical PS u -,

Distribution U) °(

262002 UPS (AC/DC)

(es) A ;;t op..

26300000 Electrical i, o I, ()

. 4-. 4s 264000EDGs CRA2.06,. iR)l5.05 300000 Instrument Air

cR) G z, a. 3

400000 ComponentCooling (Z

ft

() y-Z.0L, R) R(o7 K/A Category PointTotals: Rt 12312 jJ2 2 L3 3

Group PointTotal:

26/5 3

C U)

Lii C.)

CI) cl o

a)

LI 0)

C

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E E

z C

0

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C E

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C C

S z

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a-C.)

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C El El El El El El El El El El El z<

El El El El El El El El El El El El El El El El El El El El El l

El El El El El El El El El El El El El El El El El El El El El El El El El El El El El El El El El

[1 El El El El El El El El El El El El El El El El El El El El El El El El El El El El El El El El El El El El El El El El El El El El El C,

0 0) 0 0

0 0) 0)

N N

c) 1 CI)

CI)

(N (N

CI)

CI) o 0

U 0

0) 0)

(4 CI)

CI)

(N CI)

()

(4 CI)

(4 (4

CI)

CI) 0 0zD a

U-E I

5 W

0) 0)

5 Li.

C

5 W

0

° a-

-J D_

a-C.)

Z U)

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Cl) w 0

0 CI) c 0

0 0

0 U)

CI)

§ W

N N

N N

N N

N

I I

2 Ti m

x Co ci,

-o 0

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>e G) m CO C!!

-o C)

G) co D

0 C)

I ci)>

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Ci) c c

0z C.)

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I%3 C.)

C.)

Co C.)

Co (31 (31 Ci)

Co F)

Co C.)

3Col Co b)

CD 0

01 b) 0)

El El El El El H

L El

[]

El El El El C]

El C]

El El El El El C]

El El El El El El El El El El El El Eli El El El CD El El El El El El El El El El El C..)

El El El El El El Elj El El El El El El El El El Eli Eli El El El El El El El El Eli El El El

>0 C

El El El El El El Eli El El El El El El El El El Eli Eli El El El

>Z El El El El El El El Eli

{i El o

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C,

T2GI BWR EXAMINATION OUTLINE FORM ES-401-1 ES-401, REV 9 KA NAME / SAFETY FUNCTION:

IR Ki K2 KS K4 K5 K6 Al A2 AS A4 (3

TOPIC:

RO SRO 264OOOK5O5 EDGs 3.4 3.4 Li Li Li Li I1 Li Li Li Li Li Li Paralleling A.C. power sources 300000G2.2.39 Instrument Air 3.9 Li Li Li Li Li LI Li Li LI Li I1 Knowledge of less than one hour technical specification action statements for systems.

4000001(2.02 Component Coding Water 2.9 2.9 Li l Li Li Li Li Li LI Li Li Li CCW valves 4000001(6.07 Component Coohng Water 2.7 2.8 Li Li Li Li Li Li Li Breakers, relays, and disconnects Pages of 3 211512012 6:07 AM

ES-401, REV 9 SRO T2GI BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION:

IR KI K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 209001G2.1.27 LPCS 3.9 4

[] Li Li Li L []

[fl fl El fl j Knowledge of system purpose and orfunction.

215003A2.01 IRM 2.8 3.2 fl fl fl fl []

Li []

]

Powersupplydegraded 218000A2.05 ADS 3.4 3.6 El Li F El El [I Li Li Li Loss of AC. or D.C. power to ADS valves 261000A2.03 SGTS 2.9 3.2 Li Li Li f]

f [

}

High train temperature 263000G2.4.45 DC Electrical Distribution 4.1 4.3 Li 1 [] fl El Li Li Li Li LI Ability to prioritize and interpret the significance of each annunciator or alarm.

Page 1 of 1 211512012 6:09AM

a Cl)

LU 0

g) 0 1*

Cl)uJ

R T2G2 BWR EXAMINATION OUTLINE ES-401 REV9 KA NAME! SAFETY FUNCTION:

IR K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO El E Li LI LID LI FORM ES-401-1 201 003G2.4.50 Control Rod and Drive Mechanism 4.2 4.0 fl fl fl j

Ability to verify system alarm selpoints and operate controls identified in the alarm response manual.

215001A1.O1 Traversing In-core Probe 18 29

[] Li Li Li C Li f]

[] []

]

Radiation levels: (Not.8WR1) 21900044.12 RHR!LPCI: Tows/Pool Cooling Mode 4.1 4.1

[] [] [] Li C []

] fl fl J Suppression pool temperature 226001K4.01 RHR!L PCI: CTMT Spray Mode 2.6 2.8 fl LI LI iI C [] [1 []

[]

Testability of all operable components 2300001(3.04 RHRfl.PC1: ToruslPooi Spray Mode 3.7 3.8

[j []

El C [] [] [1

[]

]

Suppression chamber air temperature 239001 1<2.01 Main and Reheat Steam 3.2 3.3

[]

[] LI C Li Li LI LI [] Li Main steam isolation valve solenoids 24500042.09 Main Turbine Gen. I Aux 2.5 2.8 Li El LI LI C Li Li Li Li Li Turbine vibration 256000K6.09 Reactor Condensate 2.6 2.6 Li Li Li LI C I] Li Li Li Li Li Offgas system 2710001<1.11 Offgas 3.1 3.6 J LI LI LI C Li LI LI LI Li

]

Station radioactive release rate 272000K2.03 Radiation Monitoring 2.5 2.8 Li LI LI Li LI LI Stack gas radiation monitoring system 288000K5.01 Plant Ventilation 3.1 3.2 Li Li Li Li Li Li Li Li Airborne contamination control Page 1 of 2 2115/2012 6:07 AM

ES-401, REV 9

(!

T2G2 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME I SAFETY FUNCTION:

IR Ki K2 K3 K4 K5 KG Al A2 A3 A4 G TOPIC:

RO SRO 290001A3.02 Secondary CTMT 3.5 3.5 fl fl fl L E [] fl fl

[]

]

Normal building differential pressure; Plant-Specific Page 2 of 2 2/15/2012 6:07 AM

ES-401, REV 9 SRO T2G2 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNC11ON:

IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 C TOPIC:

RO SRO 215002A201 RBM 3.3 35 Li LI I

r9 Fj fl Withdrawal of control rod in high power region of core:

BWR-3,4,5 241000G2.4.9 Reactor/Turbine Pressure Regulator 3.8 4.2

[fl El fl El El fl E fl j Knowledge of low power! shutdown implications in accident (e.g. LOCA or toss of RHR) mitigation strategies.

271000A2.04 Offgas 3.7 4.1

[J LI LI Li [I Li LI

[J} [1 fi Offgas system high radiation Pagelofi 2/15/2012 610AM

ES-401 Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401 -3 Facility: BRLAN6L4JltI(

Date of Exam:

[)ECEMF ZOIZ Category K/A #

Topic SRO-Only IR IR 2.1.

(ia) 62.1ST 2.1.32 )

2.1.32 1.

Conduct 2.1.44 (ft.) C 1

2,i.44-of Operations 2.1.

2.1.4a 2.1.

Subtotal 23 2.2.

f?

2.2. 20 2.2.35

(/a)cZ2.3S 2.

2.2.42

(/)

2, 2.4-2 Equipment Control 2.2.

2.2.19 ()c2,z.I9 2.2.3Z 1

)c.2.2.3 Subtotal 3

2 2.3.1? ) 2..3.Ii 2.3. 13 fI?) c,,

3.

2.3.

Radiation Control 2.3.

2,3.

2.3.

2.3.

Subtotal a

2.4.l () C2.4.I 2.4. 25

() c 2,4. tS 4.

Emergency 2.4.

Procedures /

Plan 2.4. 3 )

a. 43 2.4.40 ($) 2. 4. 40 2.4.

Subtotal 3.

Tier 3 Point Total 1D lo 7

7

El fl ]

Ability to explain and apply afi system limits and precautions.

El C] C] J Knowledge of RO duties in the control room during fuel handling.

[] C] C] j Ability to locate and use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.

El C] C] ]

Knowledge of the process for managing troubleshooting activities.

El El C]

Ability to determine Technical Specification Mode of Operation

[1 [] El ]

Ability to recognize system parameters that are entry-level conditions for Technical Specifications

[1 El []

Ability to control radiation releases.

C] C] E] ]

Knowledge of radiological safety procedures pertaining to licensed operator duties C] C] [] ]

Knowledge of LOP layout, symbols and icons.

RO SRO ES-401, REV 9 T3 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME! SAFETY FUNCTION:

IR 1<1 1<2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

G2.1.32 Conduct of operations 3.8 4.0 El C] El El C El LI El G1A4 Conduct of operations 3.9 3.8 C] [1 C] El C Cl [1 G2.1.5 Conduct of operations 2.9 3.9

[] C] [1 Cl LI El El G2.220 Equipment Control 2.6 3.8 C] [1 C] El C C] El G2.2.35 Equipment Control 3.6 4,5 U

C] LI C] C El El (32.2.42 Equipment Control 3.9 4.6 (C] C] C] (C] C El C]

G2.3.1 I Radiation Control 3.8 4.3

[] C] El C] C El El G2.3.13 Radiation Control 3.4 3.8 El El El C] C El C]

(32.4.19 Emergency Procedures/Plans 3.4 4.1 El El El El C C] El G2.4.25 Emergency Procedures/Plans 3.3 3.7 El El El C] C El El El El El Knowledge of fire protection procedures.

Page 1 of 1 2/15/2012 6:08 AM

ES-401, REV 9 SRO T3 BWR EXAMINATiON OUTLINE KA NAME I SAFETY FUNCTION:

IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G RO SRO 02.1.42 Conduct of operations 2.5 3.4 LI fl..i fl 02.2.19 Equipment Control 2.3 3.4

[1 Li Li Li.

LI 02.2.38 Equipment Control 3.6 4.5 LI LI Li Li: IL LI [Li LI LI Li 02.3.5 Radiation Control 2.9 2.9 LI LI LI LI LI LI LI LI LI LI] }

02.3.6 RadiationControl 2.0 3.8 LILILILILILILIL]LILI G243 Emergency Procedures/Plans 3.7 3.9 LI LI LI LI LI LI LI LI] LI LI ]

02.4.40 Emergency Procedures/Plans 2.7 4.5 LI LI LI LI LI El LI LI LI Li i FORM ES-401-1 TOPIC:

Knowledge of new and spent fuel movement procedures Knowledge of maintenance work order requirements.

Knowledge of conditions and limitations in the facility license.

Ability to use radiation monitoring systems Ability to aprove release permits Ability to identify post-accident instrumentation.

Knowledge of the SROs responsibilities in emergency plan implementation.

Page 1 of 2/15/2012 612AM

ES-301 Administrative Topics Outline Form ES-301-1 Facility:

Brunswick Date of Examination: December 2012 Examination Level: RO SRO Operating Test Number:

DRAFT Administrative Topic Type Describe activity to be performed (see Note)

Code*

R, N Evaluate Status of Operator Licenses Conduct of Operations 2.1.4 Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, no-solo operation, maintenance of active license status, 10CFR55, etc.

R, D Evaluate Reactor Water Level Instruments using Caution I Conduct of Operations 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc.

R, D Develop a Clearance Boundaty - RBCCW Pump 2C Equipment Control 2.2.13 Knowledge of tagging and clearance procedures R, D Determine Total Dose for ALARA Radiation Control 2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions (SRO Only) Determine Offsite Release Rate Per R D OPEP-03.4. 7 Emergency Procedures/Plan 2.4.40 Knowledge of SRO responsibilities in Emergency Plan implementation NOTE:

All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

• Type Codes & Criteria:

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

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

(P)revious 2 exams ( 1; randomly selected)

Conduct of Operations Evaluate Status of Operator Licenses R, N K/A 2.1.4 Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, no-solo operation, maintenance of active license status, 10CFR55, etc.

This is a new JPM that requires the examinee to determine the active/inactive status of licensed operators under different conditions.

Conduct of Operations Evaluate Reactor Water Level Instruments using Caution 1 R, D K/A 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc.

This is a bank JPM that requires the examinee to determine operability of reactor water level instruments using Caution 1 of the EOPs.

Equipment Control Develop a Clearance Boundary

- RBCCW Pump 2C R, D K/A 2.2.13 Knowledge of tagging and clearance procedures.

This is a bank JPM that will require the examinee to develop an equipment clearance manually.

Radiation Control Determine Total Dose for ALARA R, D K/A 2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions.

This is a bank JPM that will require the examinee to determine the lowest dose path to a work activity.

Emergency ProcedureslPlan (SRO Only) Determine Offsite Release Rate Per OPEP-03.4.7 R, D K/A 2.4.40 Knowledge of SRO responsibilities in Emergency Plan implementation.

This is a bank JPM that requires the examinee to determine offsite release rates during accident conditions.

ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: Brunswick Date of Examination:

Dec-12 Exam Level: ROj SRO-l SRO-U Operating Test No.:

Draft Control Room Systems@ (8 for RO); (7 for SRO-l); (2 or 3 for SRO-U, including I ESF)

System / JPM Title Type Code*

Safety Function

a. Secure Main Turbine with failure of PCB to open

, A, P 4

b.

Resetting O-Fl-49 5

P 8

c.

ManualStartofCREv 5, D, EN 9

d.

Diesel Generator to normal feeder 5

D 6

e.

HPCI in Pressure Control I Exhaust Diaphragm failure s, A, D, L, EN 3

f*

RCIC with flow controller failure 5, A, L, D 2

g. Startup second Reactor Recirc Pump s

M A 1

h.

(RO Only) Bypass control rod from RWM 5

D 7

In-Plant Systems (3 for RO); (3 for SRO-l); (3 or 2 for SRO-U)

SLC with Demin Water R, D, L, E 2

j.

HCU Accumulator charging

- scram occurs R D A 1

k. Alignment of RCC Pump from RCC to ADHR Mode R, N, L 9

All RO and SRO-l control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

Type Codes Criteria for RO I SRO-l I SRO-U (A)Iternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank 9 /

8 /

4 (E)mergency or abnormal in-plant I /

1 I 1

(EN)gineered safety feature

- /

I 1 (control room system)

(L)ow-PowerlShutdown 1 I 1 I 1

(N)ew or (M)odified from bank including 1 (A) 2 I 2 I 1

(P)revious 2 exams 3 I 3 I 2 (randomly selected)

(R)CA 1I1/1 (S)im ulator ES-301, Page 23 of 27

Simulator JPMs

a. Secure Main Turbine with failure of PCB to open (4) 245000 A2.01 Ability to predict impacts of a turbine trip on the Main Turbine Generator and Auxiliary Systems; and based on those predictions, use procedures to correct, control or mitigate consequences of those abnormal conditions.

This is a previously used (NRC Exam in April. 2010) JPM that will require the examinee to shutdown the turbine. As an alternate path one of the PCBs will fail to auto open and the examinee will have to open the PCB manually.

b. Resetting CO-FIC-49 (8) 291003 KI.03 Operation of a valve controller, including seal-in features 400000 A4.01 Ability to manually operate and/or monitor in the control room CCW indications and control This is a previously used (NRC Exam in Dec. 2010) simulator JPM that will require the examinee to place the CO-FIC-49 controller (which establishes cooling water flow to the SJAE Condensers) back in service after power was lost to the controller.

c. Manual Start of CREV (9) 290003 A4.01 Ability to manually operate and/or monitor in the control room: Intiate /

reset system This is a banked JPM that will require the examinee to manually start CREV in the high radiation mode for an inspection test.

d. Diesel Generator to normal feeder (6) (U-SRO) 264000 A4.05 Ability to manually operate and/or monitor in the control room: Transfer of emergency generator (with load) to grid This is a banked JPM. DG3 is loaded and supplying power to E3. The student must unload the DG to place E3 back onto its normal power supply of D bus.

e. HPCI in Pressure Control I Exhaust Diaphragm failure (3) (U-SRO) 295025 EA1.04 Ability to operate and/or monitor the following as they apply to High Reactor Pressure: HPCI (plant specific)

This is a modified alternate path JPM. The modification was to make this an alternate path JPM. The unit has scrammed and the MSIVs are closed. The student is to place HPCI in reactor pressure control mode. After placed in service the exhaust diaphragm breaks and HPCI must be shutdown.

f.

RCIC with flow controller failure (2) 295031 EA1.05 Ability to operate and/or monitor the following as they apply to Reactor Low Water Level: Reactor Core Isolation System (plant specific)

This is a banked JPM. Unit has scrammed due to a loss of feedwater; level is below LL2 with HPCI under clearance. RCIC has failed to start.

g. Startup second Reactor Recirc Pump w/ trip of pump(1) (U-SRO) 202001 A4.01 Ability to manually operate and/or monitor in the control room:

Recirculation Pumps This is a modified Alternate path JPM (no longer have MG Sets) that have the examinees preparing to start the second recirc pump. When the pump flow of the running pump is reduced to within limits the only running pump will trip requiring a scram to be inserted and immediate scram actions taken.

h. Bypass control rod from RWM (RO Only) (7) 201006 A2.05 Ability to use procedures to correct or control out of sequence rod movement This is a banked JPM. A control rod has been inserted to suppress a fuel leak. The student is to bypass the control rod in the RWM sequence.

\\\\j)1 Li

In-Plant JPMs i.

SLC with Demin Water (2) (U-SRO) 295031 EAI.08 Ability to operate and/or monitor the following as they apply to Reactor Low Water Level: Alternate Injection Systems This is a banked JPM that is performed in the RCA. The control room has directed alternate coolant injection with demin water using the SLC pumps per EOP-01-LEP-01.

j.

HCU Accumulator charging

- scram occurs (1) (U-SRO) 201001 A2. 10 Ability to (a) predict the impacts of the following on the CR D Hydraulic System

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

tLow HCU accumulator pressure/high level This is a banked JPM that is performed in the RCA. The student will determine that the cause of a control room alarm is low pressure on an HCU and take actions to re-charge the accumulator. While re-charging the accumulator a reactor scram will occur requiring actions to isolate the drain valve on the HCU.

k. Alignment of RCC Pump from RCC to ADHR Mode (9) 233000 K4.07 Knowledge of Fuel Pool Cooling and Cleanup design features which provide for Supplemental heat removal capability.

This is a new JPM for a new system (ADHR) that was installed in the plant in the last refueling outage. This JPM is performed in the RCA aligning a RCC pump for ADHR operation during a refueling outage (low power).

1