ML13214A337

Initial Exam 2013-301 Draft Administrative Documents

ML13214A337
Person / Time
Site:	Browns Ferry
Issue date:	08/01/2013
From:	NRC/RGN-II
To:	Tennessee Valley Authority
References
Download: ML13214A337 (28)

Text

rES-401. Rev. 9 BWR Examination Outikie Form ES-4ó Facility Browns Ferry Date of Exam: 2012 RO KIA Category Points SRO-OnIy Points Tier Group KKKKKKAAAAG A2 G* Total 1 2 3 4 5 8 1 2 3 4

• Total

1. 433 43 320 4 3 7 Emergency& -TrT 21 17 2 1 3 Abnormal Plant NJA NIA EvaitlOllS TierTotals 4 6 4 10 27 1 2333323221226 3 2 5

2. rrT12TTTTT 2 02 1 3 Plant Systems TierTotais34445343323 5 3 8

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

1. Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO aid SROoniy outlines (i.e., except for one category In Tier 3 of the SRO-only outline, the 9ler Totals in each WA category shall not be less than two).

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

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

3. Systomslevolutions 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 that are not Included on the outline should be added. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate WA 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. Absents plant-Specific priority, only those WAs having en importance rating (IR) of 2.5 or higher shall be selected. Use Ui. RO and SRO ratings for the RO and SRO-only portions, respectively.

6. Select SRO topics for Tiers I and 2 from the shaded systems and WA categories.

7. The generic (G) KJAs in Tiers I aid 2 shall be selected from Section 2 of the WA Catalog, but the topics must be relevant to the applicable evolution or system.

8. On the following pages, enter the WA numbers, a brief description of each topic, the topics importance ratings (IRs) for the applicable Ncense level, and the point totals (#) for each system and category. Enter the group and tier totals for each category In the table above; llluel handlIng equipment is sampled In other than Category A2 or G on the SRO-only exam, enter it on the left aide of Column A2 for Tier 2, Group 2 (Note

1. 1 does not apply). Use duplicate pages for RO and SROonly exams.

9. For TierS, select topics from Section 2 of the WA catalog, and enter the WA numbers, descnptions, IRs, aid polnttotsls (#) on Form ES-401-3. Limit SRO selections to WAs that are linked to 10 CFR 55.43.

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

E?APE #1 Name! Safety Function K K K A A G K/A Topic(s) IR #

i---i-R 295001 Partial or Complete Loss of Forced Core Flow Circulation! 1 & 4 (R) AA.0- () AA2. 05 295003 Partial or Complete Loss of AC / 6

£ I. 01 295004 Partial or Total Loss of DC Pwr / 6 295005 Main Turbine Generator Trip 13 295006 SCRAM I 1

R)c2.I.3.

295016 Control Room Abandonment! 7 R - -

295018 Partial or Total Loss of CCW! 8 295019 Partial or Total Loss of Inst. Air? 8 S R (R)Z.2.3 (S)AALo R)M?..OT 295021 Loss of Shutdown Cooling 14 295023 Refueling Acc 18 S (P)AW..0+ ()2.240 g(R)(2.4S cs)C2.

2 4 I 295024 High Drywell Pressure /5 295025 High Reactor Pressure! 3 295026 Suppression Pool High Water i -

- (IAt.0I Temp. IS 295027 High Containment Temperature / 5 CR)Eo4 295028 High Drywell Temperature! 5 295030 Low Suppression Pool Wtr Lvl /5 l2, P)l.oL R QZ)3.o3 295031 Reactor Low Water Level! 2 295037 SCRAM Condition Present (12.) , 03 C5) 2 4 30 and Reactor Power Above APRM Downscale or Unknown? 1 295038 High Off-site Release Rate /9 R

600000 Plant Fire On Site!8

.9 (5) AAZ. (3 700000 Generator Voltage and Electric Grid S

12.) AkI. 01 () 4A . 05 Disturbances /6 K/A Category Totals: 4 i i [3 4 3! Group Point Total: = 20/7 43

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 I SRO)

E/APE # / Name! Safety Function K K K A A G K/A Topic(s) lR #

12312 295002 Loss of Main Condenser Vac /3 295007 High Reactor Pressure /3 295008 High Reactor Water Level! 2 A 14 I 0 a 295009 Low Reactor Water Level /2 295010 High Drywell Pressure /5 295011 High Containment Temp /5 295012 High Drywell Temperature! 5 295013 High Suppression Pool Temp. /5 295014 Inadvertent Reactivity Addition / 1 CE) &A .

295015 Incomplete SCRAM/i Ae&3.oI 295017 High Off-site Release Rate! 9 2 ,O 0

AA 295020 Inadvertent Cont. Isolation /5 & 7 295022 Loss of CR0 Pumps /1 295029 High S CS) EAZ. 03 Suppression Pool Wtr Lvi! 5 295032 High Secondary Containment R) ) eK2.og Area Temperature /5 295033 High Secondary Containment Area Radiation Levels /9 295034 Secondary Containment Ventilation High Radiation I9 295035 Secondary Containment High Differential Pressure /5 295036 Secondary Containment High Sump/Area Water Level /5 500000 High CTMT Hydrogen Conc. /5 G. 2.2.44 K/A Category Point Totals: 1 I j I Group Point Total:

=

ES-401 4 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems Tier 2/Group 1 (RO I SRO)

System#IName K K K K K K A A A A G KIATopic(s) IR #

1 2 3 4 5 6 1 234 203000 RHRJLPCI: Injection (R) A2 I Mode 2O5000ShutdownCooling A4V7 206000 HPCI - - -

P) 2. 2.31 207000 Isolation (Emergency)

Condenser -

//

cCJ)A3.O3()P.l3I 2O9001LPCS 209002 HPCS 21I000SLC 212000 RPS K4.°I 2150031RM

$)A.°J CR) I.(I 215004 Source Range Monitor 215005APRMILPRM 217000RCIC 218000 ADS P.) K4.o (Si Ao2 .

223002 PClSlNuclear Steam R) /2 .06 Supply Shutoff P*.) v.4.04 239002SRVs 259002 Reactor Water Level P) KS.03 Control 261000SGTS (R)Ai.07 262001 AC Electrical

) 142.0 I Distribution

( a 262002 UPS (AC/DC)

(R) I(. i7 263000 DC Electrical P S q.) Al. 01 Distribution F) 146.01 264000 EDGs (P.) 143.03 300000 Instrument Air (f) G .4.3 400000 Component Cooling Ps P.) I.I 0 I Water K/A Category PointTotals: 3 1

-j Group PointTotal: 2615 3

ES-401 5 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems- Thr Gmu 2 O I SRO)

System #1 Name K K K K K K A A A A G K/A Topic(s) IR #

12345612 34 201001 CR0 Hydraulic 201002 RMCS q) 34,O4 201 003 Control Rod and Drive S CS) Gq 2 .4. 18 Mechanism 201004 RSCS 201005 RCIS 2O1006RWM 202001 Recirculation 202002 Recirculation Flow Control 204000 RWCU 214000 RPIS

<(peOf 215001 Traversing In-core Probe 215002 RBM 216000 Nuclear Boiler Inst. ft) 1 Do..

A4-219000 RHRILPCI: Tows/Pool Cooling Mode 223001 Primary CThff and Aux.

226001 RHRILPCI: CTMT Spray Mode 230000 RHRILPCI: Torus/Pool Spray P. A I JO Mode 233000 Fuel Pool Cooling/Cleanup 234000 Fuel Handling Equipment (p.) J 5. O 239001 Main and Reheat Steam C5) A ?. I I 239003 MSIV Leakage Control 241000 Reactor/Turbine Pressure Regulator 245000 Main Turbine Gen. I Aux.

256000 Reactor Condensate 259001 Reactor Feedwater )

268000 Radwaste s c) A,2 .0 I 271000 Offgas 272000 Radiation Monitoring I4 .03 286000 Fire Protection 268000 Plant Ventilation () i43.oS 290001 Secondary CTMT 290003 Control Room HVAC 1P..) A 3.o 290002 Reactor Vessel Internals P.. (A) K . 4 K/A Category Point Totals:

iii LI .L2 .L L I  ! . II Group Point Total: 12/3 2.. I

fl m

0 C) 0 0

0 1

0 3

m C,

0 3

t

ES-401, REV 9 T1G1 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR 1(1 K2 K3 1(4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 295001A1<l.03 Partial or Complete Loss of Forced 3.6 4.1 El El El LI El El LI El Thermal limits Core Flow Circulation / 1 & 4 295003A42.02 Partial or Complete Loss of AC /6 4.2 4.3 [] c] El LI LI El [I LI El LI Reactor power! pressure / and level 295004AA1.O1 Partial or Total Loss of DC Pwr /6 3.334 [] El Li C] LI CI ll LI LI LI [1 D.C. electrical distribution systems 295005AA1.O1 Main Turbine Generator Trip! 3 3.1 3.3 El El El El El El Recirculation system: Plant-Specific 295006AK1.02 SCRAM Il 3.43.7 LI C Li Li [J LI U LI LI U Shutdown margin 295016G2.1 .32 Control Room Abandonment /7 3.8 4.0 El El El LI El El El El El El ] Ability to explain and apply all system limits and precautions.

295018A41.02 Partial or Total Loss of CCW / 8 3.3 3.4 El El El El El El II El El El El System loads 295019G2.2.39 Partial or Total Loss of Inst. Air / 8 3.9 LI El El El El El El El LI El Knowledge of less than one hour technical specification action statements for systems.

Tec..h Y.83 ,4cevi 1) 295021AA2.07 Loss of Shutdown CoolIng 14 2.9 3.1 El El LI El El El El El El El Reactor recirculation flow 295023AK3.04 Refueling Acc Cooling Mode /8 3.0 3.5 El C] El El El El El El El El Non-coincident SCRAM function 296024G2.4.8 High Drywell Pressure / 5 3.8 4.5 El El El El LI El El El El El El Knowledge of how abnormal operating procedures are used in conjunction with EOP5.

Page 1 of 2 8/2/2012 10:25AM

ES-401, REV 9 T1G1 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 296025EA2.O1 High Reactor Pressure! 3 4.3 4.3 Li LI [1 Li LI Li Li Li Li LI Reactor pressure 295026EA1.O1 Suppression Pool High Water Temp. / 4.1 4.1 Li Li L] LI Li LI fi Li Li LI LI Suppression pool cooling 5

295028EK3.04 High Drywell Temperature! 5 3.6 3.8 EJ Increased drywell cooling Li LI Li Li Li Li [1 LI LI 295030EK2.O1 Low Suppression Pool Wtr Lvi / 5 3.8 3.9 LI Li Li Li Li Li Li Li Li H HPCI: Plant-Specific ........

295031 EK3.03 Reactor Low Water Level! 2 4.1 4.4 Li LI I Li Li LI Li Li Li Li Li Spray cooling 295037EK1.03 SCRAM Condition Present and Power 4.2 4.4 J LI LI LI Li Li U Boron effects on reactor power (SBLC)

Above APAM Downscale or Unknown LI Li Li LI

/1 295038EK2.02 High Off-site Release Rate! 9 3.6 3.8 Offgas system Li Li Li LI Li Li LI Li Li Li 600000AK2.O1 Plant Fire On Site! 8 2.6 2.7 Sensors / detectors and valves Li Li [1 Li Li Li Li LI Li Li 700000AK1.O1 Generator Voltage and Electric Grid 3.3 3.5 i Li Li LI LI LI Li LI Li Li LI Definition of the terms: volts, watts, amps, VARS, power Distrurbancecs factor

r. ifS Page 2 of 2 8/212012 10:25AM

ES-401, REV 9 T1G2 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR K1K2K3K4K5K6A1A2A3A4G TOPIC:

RO SRO 295008AK1 .02 High Reactor Water Level / 2 2.8 2.8 Component erosion/damage 295O14AP2.O3 Inadvertent Reactivity Addition / 1 4.043 Cause of reactivity addition 295015AK3.O1 Incomplete SCRAM! 1 LILIEÜLILJLIE Bypassing rod insertion blocks 295020G2.4.4 Inadvertent Cont. Isolation / 5 & 7 LHZE1L1DL1L1LJL1L1 Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

295032EK2.08 High Secondary Containment Area 3.8 3.9 Systems required for safe shut-down Temperature / 5 295033EA1 .05 High Secondary Containment Area 3.9 4.0 EFLEJ Affected systems so as to isolate damaged portions....

Radiation Levels /9 295035EA1 .01 Secondaly Containment High 3.6 3.6 Secondary containment ventilation system Differential Pressure / 5 Page 1 of 1 8/2/2012 10:25AM

ES-401, REV 9 T2G1 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR 1(1 K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 203000A2.16 RHR/LPCI:Injection Mode 44 45 [J LI H H H H F] fl F] fl Loss of coolant accident 205000A4.07 Shutdown Cooling 3.7 3 F] F] LI LI LI LI LI F] F] Reactor temperatures (moderator, vessel, flange) 206000G2.2.38 HPCI 3.6 4.5 F] F] F] F] LI F] [] F] F] F] fJ Knowledge of conditions and limitations in the facility license.

209001A3.03 LPCS 3.5 3.5 F] F] [] F] F] [] F] [] [J F] F] System pressure 2110001(1.01 SLC 3.0 3.3 F] F] F] F] F] [ F] F] F] F] Gore spray line break detection: Plant-Specific 2110001(3.01 SLC 4.3 4.4 F] F] F] F] F] LI F] F] F] F] Ability to shutdown the reactor in certain conditions 2120001(4.01 RPS 3.4 3.6 F] F] F] LI LI LI LI F] LI LI System redundancy and reliability 215003A3.03 IRM 3.7 3.6 F] F] F] F] F] [F] F] F] [] F] F] RPS status 2150041(2.01 Source Range Monitor 2.6 2.8 F] [i F] LI LI LI LI LI LI LI F] SRM channels/detectors 215005K2.02 APRM I LPRM 2.6 2.8 F]F]LILILILILILILILI APRM channels 217000A1.02 RCIC 3.3 3.3 LILILIF]F]LILILIF]LI RCIC pressure Page 1 of 3 8/2/2012 10:25AM

ES-401, REV 9 T2G1 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME! SAFETY FUNCTION: IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 2170001(5.06 RCIC 2.7 2.7 H [] [] [] [J [] H [] [] [] [] Turbine operation 218000K4.O1 ADS 3.7 3.9 fl H H LI Li H Prevent inadvertent initiatior of ADS logic 223002P.2.06 PCIS/Nuclear Steam Supply Shutoff 3.0 3.2 fl H H H H H H H Containment instrumentation failures 223002K4.04 PCI S/Nuclear Steam Supply Shutoff 3.2 3.6 H H H H H H H H H Automatic bypassing of selected isolations during specified plant conditions 2390021(6.02 SRVs 3.4 3.5 [1 [1 H J J H Air (Nitrogen) supply: Plant-Specific 2590021(5.03 Reactor Water Level Control 3.1 32 H [] H H H H Water level measurement H H H H 261000A1.07 SGTS 2.8 2.9 SBGTS train temperature 2620011(2.01 AC Electrical Distribution 3.3 3.6 [] [] H H [] [] H [] [] [] Off-site sources of power 262001K5.02 AC Electrical Distribution 2.6 2.9 El H [] [] [] H H H [] H Breaker control 262002K3.17 UPS (AC/DC) 2.9 3.1 H H fJ H H H H H H H Process monitoring: Plant-Specific 263000A1.01 DC Electrical Distribution 2.5 2.8 H H [1 L] H H l H El H H Battery charging/discharging rate Page 2013 8/2/2012 10:25AM

ES-401, REV 9 T2G1 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR Kl K2 K3 K4 K5 1(6 Al A2 A3 A4 G TOPIC:

RO SF10 2630001(6.01 DC Electrical Distribution 3.2 L1L1E1LIEE1E1LE1L A.C. electrical distribution 2640001(3.03 EDGs 4.1 4.2 LL1E1E1L1L1DDL1U Major loads powered from electrical buses fed by the emergency generator(s) 30000002.4.3 Instrument Air 3.7 3.9 L1ULJL1E1LDE1ÜL1 Ability to identity post-accident instrumentation.

4000001(1.01 Component Cooling Water 3.2 3.3 DLH1L1LL1LL1L1L Service water system Page 3 oF 3 8/2/2012 10:25AM

ES-401, REV 9 T2G2 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 201002K4.04 RMCS 3.3 3.3 El [] El [] [] [] [] [] [] [] [J Single notch rod withdrawal and insertion 201006P2.05 RWM 3.1 3.5 [] [] [] [j Out of sequence rod movement; P-Spec(Not-BWR6) 2140001(6.01 RPIS 2.5 2.6 [] { [] [] [] ] {] LI El El El A.C. electrical power 216000A4.02 Nuclear Boiler Inst 3.3 3.1 El El El El El El El El El Channel select controls 230000A1.1O RHR/LPCI: Torus/Pool Spray Mode 3.7 3.7 [ fl El El ( [] } [] [] [] [] System lineup 2340001(5.02 Fuel Handling Equipment 3.1 3.7 El LI El El [} El El El El El El Fuel handling equipment interlocks 259001G2.4.6 Reactor Feedwater 3.7 4.7 El El El El El El El El El El () Knowledge symptom based EOP mitigation strategies.

271000K5.1 1 Offgas 2.6 2.8 El El [] El El El [] [] El El Explain the necessity of reducing relative humidity for carbon bed filters.

2720001(2.03 Radiation Monitoring 2.5 2.8 El El El El El El El El El El Stack gas radiation monitoring system 2880001(3.05 Plant Ventilation 3.1 3.3 El El El El El LI LI El El LI Reactor building pressure: Plant-Specific 2900021(1.14 Reactor Vessel Internals 2.9 3.1 1 El El El El El El El El El El RWCU Page 1 of 2 8/2/2012 10:25AM

ES-401, REV 9 T2G2 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR Kl 1(2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 290003A3.02 Control Room HVAC 3.0 L1 El LI LI LI LI LI Li } [1 LI Initiation/failure of fire protection system Page 2of 2 8/2/2012 10:25AM

ES-40I, REV 9 T3 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME I SAFETY FUNCTiON: IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SF10 G2.1 .27 Conduct of operations 39 4 LI LI El LI LI LI LI [1 LI LI 1] Knowledge of system purpose and or function.

02.1.31 Conduct of operations 4.6 4.3 fl Li LI LI LI LI LI LI LI LI lI Abitity to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup.

02.1 .36 Conduct of operations 3.0 4.1 LI LI LI LI LI LI LID LI LI l Knowledge of procedures and limitations involved in core alterations G2.2.15 Equipment Control 3.9 4.3 LI LI LI LI LI LI LI LI LI LI Ability to determine the expected plant configuration using design and configuration control documentalon G22.25 Equipment Control 3.2 4.2 LI LI El LI LI LI LI LI LI LI l1 Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.

32239 Equipment Control 3.9 4.5 LI LI Li LI LI LI LI LI LI LI Knowledge of less than one hour technical specification action statements for systems.

02.3.13 Radiation Control 3.4 3.8 LI LI El LI LI LI LI LI LI El I] Knowledge of radiological safety procedures pertaining to licensed operator duties 02.3.14 Radiation Control 3.4 3.8 LI LI El LI LI LI LI LI LI El ] Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities 02.4.1 Emergency Procedures/Plans 4.6 4.8 [] LI LI El LI LI LI LI LI LI I] Knowledge of EOP entry conditions and immediate action steps.

G2.4.9 Emergency Procedures/Plans 3.8 4.2 LILILILILILILILILILI Knowledge of low power I shutdown implications in accident (e.g. LOCA or loss of RHR) mitigation strategies.

Page 1 of 1 8/2/2012 10:25AM

(JT1G1 BWR EXAMINATION OUTLINE FORM ES-401-1 ES-401,REV9 NAME / SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

KA RO SRO 295003AA2.05 Partial or Complete Loss of AC! 6 3.9 4.2 j J Whether a partial or complete loss of A.C. power has occurred 295019AA2.02 Partial or Total Loss of Inst. Air / 8 3.6 3.7 j cJ D El El LI El LI [] Status of safety-related instrument air system loads (see AK2.l -AK2.19) 295023G2.2.40 Refueling Acc Cooling Mode / 8 3.4 4.7 LI LI [1 LI LI LI [] Ability to apply technical specifications for a system.

Knowledge of the parameters and logic used to assess 29502462.4.21 High Drywell Pressure / 5 4.04.6 LI LI LI LI LI LI LI LI [ [} -

the status of safety functions 4.1 [] [] Knowledge of events related to system operations/status 29503762.4.30 SCRAM Condition Present and Power 2.7 LI LI LI fl that must be reported to internal orginizations or outside Above APRM Downscale or Unknown I1 agencies.

Need for emergency plant shutdown 600000AA2.13 Plant Fire On Site / 8 3.2 3.8 [ILI LI LI LI LI LI ] LI LI LI

[] LI fl Operational status of offsite circuit 700000AA2.05 Generator Voltage and Electric Grid - 3.2 3.8 [] [J []

Distrurbancecs Page 1 of 1 8/212012 10:26AM

ES-401, REV 9 4T1G2 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME! SAFETY FUNCTION: IR K1K2K3K4K5K6A1A2A3A4G TOPIC:

RO SRO 29501 7AA2.01 High Off-site Release Rate /9 2.9 4.2 Off-site release rate: Plant-Specific 295029EA2.03 High Suppression Pool Wtr Lvi / 5 L1[1H L1DDDI[iDD Drywell/containment water level 500000G2.2.44 High CTMT Hydrogen Conc. / 5 4.2 4.4 Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions Page 1 of 1 8/2/2012 10:26AM

YT2G1 BWR EXAMINATION OUTLINE FORM ES-401-1 ES-401, REV 9 KA NAME / SAFETY FUNCTION: IR Ki 1(2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

HO SRO Ability to locate control room switches, controls and 209001 G2.1.31 LPCS 4.6 4.3 fl J El [] [] [] [] [] [] indications and to determine that they are correctly reflecting the desired plant lineup.

Loss of SBLC tank heaters 21 1000A2.05 SLC 3.1 3.4 El El El LI LI El LI [I El C] LI El C] El Power supply degraded 215003A201 IRM 2.8 3.2 [] C]. C] C] El El El Loss of AC. or D.C. power to ADS valves 218000A2.05 ADS 3.4 3.6 C] C] C] El El Li El fl El [i C]

Knowledge of surveillance procedures.

239002Ga2.12 SRVs 3.7 4.1 C] El El El El El El El El El Page 1 of 1 8/2/2012 10:26AM

ES-401, REV 9 2G2 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME I SAFETY FUNCTION: IR 1(1 K2 1(3 K4 1(5 1(6 Al A2 A3 A4 (3 TOPIC:

RO SRO 201003G2.4.18 Control Rod and Drive Mechanism 3.3 4.0 [ [] [] [] [] [] [1 [] [] Knowledge of the specific bases for EOPs.

239001A2.11 Main and Reheat Steam 4.1 4.3 Li Li Li LI LI El [1 l Li LI [] Steam line break 268000A2.O1 Radwaste 2.9 3.5 Li J System rupture Page 1 of 1 8/2/2012 10:26 AM

ES-401, REV 9 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO G2.1.35 Conduct of operations 2.2 3.9 Knowledge of the fuel handling responsibilities of SROs G2.1.43 Conduct of operations 4.1 4.3 Ability to use procedures to determine the effects on

[][J reactivity of plant changes G2.2.18 Equipment Control 2.6 3.8 El LI LI LI El Knowledge of the process for managing maintenance activities during shutdown operations G2.2.3 Equipment Control 3.8 3.9 (multi-unit license) Knowledge of the design, procedural LI LI LI LI L] [1 LI [] LI and operational differences between units.

G2.3.4 Radiation Control 3.2 3.7 LI LI LI LILI LI LI LI LI LI Knowledge of radiation exposure limits under normal and emergency conditions G2.418 Emergency Procedures/Plans 3.3 4.0 Knowledge of the specific bases for EOPs.

LI LI fl LI [] LI LI LI ]

G2.4.19 Emergency Procedures/Plans 3.4 4.1 LI LI LI LI LI LI LI LI LI LI Knowledge of EOP layout, symbols and icons.

Page 1 of 1 8/212012 10:26 AM

ILT 1306 Administrative Topics Outline Form ES-301-1 Facility: Browns Ferry NPP Date of Examination: 6/3/20 13 Examination Level: RO/SRO Operating Test Number: 1306 Administrative Topic Type Describe activity to be performed Code (see Note)

Conduct of Operations D 2.1.7: 1-SR-3.4.2.l Jet Pump Mismatch and Operability, need to modify after SR updated following unit 1 outage SRO/RO Ala Conduct of Operations RO Aib N 2.1.18: 2/3-SR-2 Operator Logs MODE 5 Table 4.1 through 4.7 part 2 2.1.18: 2-SR-2 Review a completed set of MODE 5 Operator Logs SROA1b N Equipment Control N 2.2.41: Determine PSC Pump 2B or 3B isolation boundary ROA2 SRO A2 N 2.2.23: LCO Tracking Log entry for PCIS Valve failed.

Radiation Control SRO/RO A3 M 2.3.11: Calculate Airborne Effluent Release Rate JAW 0-SI-4.8.b. l.a. 1 Emergency Plan N 2.4.44: Follow up Notification and PAR Change SRO A4 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 (D)irect from bank ( 3 for ROs; <4 for SROs and RO retakes)

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

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

(S)imulator

ILT 1306 Administrative Topics Outline Form ES-3d-I Reactor Operator

1. 1 -SR-3 .4.2.1 Jet Pump Mismatch and Operability

• Direct from Banic o i-SR-3.4.2.1

• Complete a surveillance requirement on Reactor Recirculation Syem Jet Pump Mismatch and Operability, determines that an Engineering review is required and determines that the Acceptance Criteria is met even though some parts fail to meet the initial requirements.

• 2.1.7 Ability to evaluate plant performance and make operatioial judgments based on operating characteristics, reactor behavior, and instrument interpretation. Importance RO 4.4 SRO 4.7

2. [CS Logs o New

• 2-SR-2 or 3-SR-2

• Perform Operator logs in accordance with 2-SR-2 Instrument Checks and Observations for log tables 4.1 through 4.7. Verify acceptance criteria are satisfied in accordance with notes. If acceptance criteria is NOT_satisfied correct if possible.

• 2.1.18 Ability to make accurate, clear, and concise logs, records, status boards, and reports.

RO3.6 SRO3.8

3. Determination of Isolation Boundary for PSC Pump 2B or 3B 1f

. New

• Drawings 2/3 -47E8 14-1, 2/3-45E779- 19, 2/3-47E6 1 0-75-1, and 2/3-45E75 1-3

• Determine the components that shall be identified to isolate PSC Pump 2B or 3B

• 2.2.4 1 Ability to obtain and interpret station electrical and mechanical drawings. Importance RO 3.5

4. Calculate Airborne Effluent Release Rate in accordance with 0-SI-4.8.b. l.a. 1

• Modified

• 0-SI-4.8.B.1.a.l

• Calculate Building Ventilation Release Fraction and determine acceptance cxilria met.

Calculate Stack Release Fraction and determine that acceptance criteria NOT met. Calculate Total Site Release Fraction and determine acceptance criteria met.

• 2.3.11 Ability to control radiation releases RO 3.8 SRO 4.3 A.:,

ILT 1306 Administrative Topics Outline Form ES-301-1 Senior Reactor Operator

1. 1-SR-3.4.2.1 Jet Pump Mismatch and Operability

• Direct from Bank

• 1-SR-3.4.2.1

.. Complete a surveillance requirement on Reactor Recirculation System Jet Pump Mismatch and Operability, determines that an Engineering review is required and determines that the Acceptance Criteria is met even though some parts fail to meet the initial requirements.

• 2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instruhient interpretation. Importance SRO 4.7

2. ICS Logs

• New

• 2-SR-2

• Review a completed set of Mode 5 Operator logs in accordance with 2-SR-2 Instrument Checks and Observations. Verif acceptance criteria are satisfied in accordance with notes. If acceptance criteria is NOT satisfied correct if possible.

• 2.1 .18 Ability to make accurate, clear, and concise logs, records, status boards, and reports.

Importance SRO 3.8

3. LCO Tracking Log entry for failed PCIS Valve

. New e OPDP-8

• Complete an LCO Tracking Log Entry computer or hard copy from the results of 2/3-SR-3.6.1.3.5 Primary Containment Isolation Valve Operability Section 7.16 RWCU Testing

• 2.2.23 Ability to track Technical Specifications limiting conditions for Operations.

Importance SRO 4.6

4. Calculate Airborne Effluent Release Rate iaw O-SI-4.8.b.1.a.1

• Modified

• O-SI-4.8.B.1.a.1

• Calculate Building Ventilation Release Fraction and determine acceptance criteria met.

Calculate Stack Release Fraction and determine that acceptance criteria NOT met. Calculate Total Site Release Fraction and determine acceptance criteria met.

• 2.3.11 Ability to control radiation releases. Importance SRO 4.3

ILT 1306 Administrative Topics Outline Form ES-301-1

5. Protective Action Recommendation Evaluation New

• EPIP-l and 5 Emergency Classification Procedure and General Emergency

• Completed Notification Handouts Appendix F General Emergency Follow-Up hiiormation Form and J Upgrade Protective Action Recommendation e 2.4.44 Knowledge of emergency pian protective action recommendations. Importance SRO 4.4

ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: Browns Ferry NPP Date of Examination: 6/3/20 13 Exam Level: RO/SROIISROU Operating Test No.: 1306 Control Room Systems (8 for RO); (7 for SRO-l); (2 or 3 for SRO-U, including I ESF)

Safety System I JPM Title Type Code*

Function

a. Recirc Pump Shutdown Plant in Mode 2, 2/3-01-68 A, N, 5, L 1

b. Alternate RPV Injection Standby Coolant, 2/3-EOI Appendix-7D D, S 2

c. Alternate RPV Pressure Control RFPT, 2/3-EOI Appendix-i iF D, S 3

d. Restore Shutdown Cooling, 2/3-AOI-74-i M, 5, L 4

e. Stroke Time PCIS Valve 3-SR-3.6.1.3.5 (CSII) N, A, 5, EN 5

f. Alternate Method of Determining Control Rod Position of a N A 5 7 Single Control Rod, 3-AOI-85-4

g. Containment Venting, High Pressure 2/3-E0I Appendix-12 M, 5, A 9

h. 0-SSI-2-1 Steps 10 thru 24 (U2 Only) N, 5, L 8 (RO only)

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

i. 263000 A3.Oi: Transfer of AC Alternate Source to Battery N A 6 Charger SB-C ONLY, 0-OI-57D section 8.6

j. 600000 AA2J7: 0-SSI-21 Attachment 7 N, E 8

k. 295031 EA1.08: 1-E0I Appendix-7B SLC Alternate Injection N, R, E 2 All RO and SRO-I 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)lternate path 4-6/2-3 (C)ontrol room (D)irect from bank <91<81<4 (E)mergency or abnormal in-plant > 1I 11>1 (EN)gineered safety feature - I 1>1 (control room system)

(L)ow-Power I Shutdown ?i1I1I?1 (N)ew or (M)odified from bank including 1 (A) > 2/> 2/>1 (P)revious 2 exams 3I 3I 2 (randomly selected)

(R)CA >1/1/?1 (S)imulator

ILT 1306 Control Roomlln-Plant Systems JPM Narrative Control Room Systems:

a. Recire Pump Shutdown with plant in Mode 2 (Unit 2 or 3)

• Altemate path / New / Simulator / Low power

• 2/3-01-68 Reactor Recirculation System

• 295001 Partial or Complete loss of forced core flow circulation AA1.Oi Ability to operate and/or monitor the following as they apply to Partial or Complete loss of bçece flow circulation: Recirculation system IMPORTANCE: RO 3.5 SRO 3.6

• Operator directed to shutdown Recirculation Pump B and maintain temperature in the idle loop in MODE 2 in accordance with 2/3-01-68 section 7.1, when the operator opens the discharge valve to maintain temperature the idle Reactor Recirculation pump will rotate requiring the operator to close the discharge valve.

b. Alternate RPV Injection Standby Coolant (Unit 2 or 3)

• Direct from Bank / Simulator

• 2/3-EOI Appendix-7D Alternate RPV Injection System Lineup Standby Coolant

• 29503 iReactor Low Water Level EA1 .08 Ability to operate and/or monitor the following as they apply to Reactor Low Water Level: Alternate Injection systems: Plant-specific IMPORTANCE: RO 3.8 SRO 3.9

• Inject with Standby Coolant JAW 2/3-EOI Appendix-7D to restore RPV Level.

c. Alternate RPV Pressure Control RFPT (Unit 2 or 3)

• Direct from Bank / Simulator

• 2/3-EOI Appendix-i iF Alternate RPV Pressure Control Systems RFPT On Minimum Flow

/. 295007 High Reactor Pressure AA2.0i Ability to determine and/or interpret the following as they apply to High Reactor Pressure: Reactor Pressure IMPORTANCE: RO 4.1 SRO 4.1

• Places RFPT A and B in pressure control in accordance with 2/3-EOI Appendix-i iF

ILT 1306 Control Roomiln-Plant Systems JPM Narrative

d. Restore Shutdown Cooling (Unit 2 or 3)

• Modified from Bank / Low Power / Simulator

• 213-AOI-74-1 Loss of Shutdown Cooling

• 295021 Loss of Shutdown Cooling AA1 .02 Ability to operate andlor monitor the following as they apply to Loss of Shutdown Cooling: RHRlshutdown cooling IMPORTANCE: RO 3.5 SRO 3.5

• Operator is directed to restore shutdown cooling following an inadvertent RPS actuation, will restore shutdown cooling with RHR Pump B and establish a cooldown JAW with the AOl for loss of Shutdown Cooling.

e. Perform Surveillance 3-SR-3.6.1.3.5(CSII) (Unit 3 Only)

• New / Alternate Path / Simulator / Engineered Safety Feature

• 3-SR-3.6.1.3.5(CSII)

• 223002 Primary Containment Isolation System/Nuclear Steam Supply Shut-Off A4.01 Ability to manually operate and/or monitor in the control room: Valve closures IMPORTANCE: RO 3.6 SRO 3.5

• Operator properly strokes and times Core Spray PCIS valve and restrokes valve for having a time above high alert but below limiting value when valve is stroked closed.

f. Alternate Method of Determining Control Rod Position of a Single Control Rod

• New I Alternate Path I Simulator

• 3-AOI-85-4

• 214000 Rod Position Information System A4.02 Ability to manually operate and/or monitor in the control room: Control Rod Position IMPORTANCE: RO 3.8 SRO 3.8

• Operator uses alternate methods of determining Control Rod position of a signal Control Rod in accordance with 3-AOI-85-4. When inserting the control rod one notch fails to restore position indication the operator fully inserts the control rod.

g. Containment Venting High (Unit 2 and 3)

• Modified / Simulator / Alternate Path

• 2/3-EOI Appendix-12 Primary Containment Venting

• 261000 Standby Gas Treatment System A2.14 Ability to (a) predict the impacts of the following on the Standby Gas Treatment System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: High System Pressure IMPORTANCE: RO 3.0 SRO 3.2

• Vent Primary Containment JAW 2/3-EOI Appendix-12, due to high system pressure vent valve will cycle open and close until the operator adjusts flow to lower the system pressure.

ILT 1306 Control Roomlln-Plant Systems JPM Narrative

h. Unit 2 Control Room actions for a major fire in Unit 2 Reactor BLDG (Unit 2 Only)

• New / Simulator / Low Power

• 0-SSI-2-1, Unit 2 Reactor Building Fire EL 519 through 565 West of Column Line Ru

• 600000 Plant Fire on Site AA2.16 Ability to determine and interpret the following as they c apply to Plant Fire on Site: Vital equipment and control systems to be maintained and operated during a fire IMPORTANCE: RO 3.0 SRO 3.5

• Perform Time Critical steps 10 through 24 of 0-SSI-2-1, prevent HPCI operation, aligns diesel generators, and commences rapid depressurization.

In-Plant Systems:

i. Transfer of AC Alternate Source to Battery Charger Shutdown Board C ONLY -

• New / Alternate Path

• 0-OI-57D, DC Electrical System

• 263000 A3.01 Ability to monitor automatic operations of the DC ELECTRICAL DISTRIBUTION including meters, dials, recorders, alarms, and indicating lights.

IMPORTANCE: RO 3.2 SRO 3.3

• Simulate Transfer of AC Alternate Source to Battery Charger Shutdown Board C ONLY and when charger malfunctions AC and DC power breakers will be placed in OFF.

j. Align Common Accident Signal Logic Inhibit Switches

• New / Emergency in Plant

• 0-SSI-2 1, Unit 3 Diesel Generator Building

• 600000 Plant Fire on Site AA2. 17 Ability to determine and interpret the following as they apply to Plant Fire on Site: Systems that may be affected by the fire IMPORTANCE: RO 3.1 SRO3.6

• Align Common Accident Signal Logic Inhibit Switches for all three Units.

k. Alternate RPV Injection Standby Liquid Control System

• New / Emergency in Plant / RCA

• 1-EOI Appendix-7B Alternate RPV Injection System Lineup SLC System

• 29503 lReactor Low Water Level EA1 .08 Ability to operate andlor monitor the following as they apply to Reactor Low Water Level: Alternate Injection systems: Plant-specific IMPORTANCE: RO3.8 SRO3.9

• Perform field actions to Line Up for Injection with SLC L&W 1-EOI Appendix-7B.