ML100830061

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Initial Exam 2009-302 Draft Administrative Documents
ML100830061
Person / Time
Site: Watts Bar Tennessee Valley Authority icon.png
Issue date: 02/11/2010
From:
NRC/RGN-II
To:
Tennessee Valley Authority
References
50-390/09-302
Download: ML100830061 (19)
v • d • e


Text

FACILITY FACI NAME:

LlTY NAM E: _ _....;;..;W;...;;;;a;.;;.;;tt;.;;.s...;;;;B;...;;;;a~r

.:..:W:..:::a:.:.:tt:.:.s-=B=a~r_ _ Section 1 REPORTNUMBER: __~2~OO~9~-3~O~2~

REPORTNUMBER:_~20~O~9~-3~O~2 ________________

DRAFT ADMINISTRATIVE DOCUMENTS CONTENTS:

~Oraft Written Exam sample plan (ES-401-1/2/3)

IB"'Oraft C!Y6raft Administrative Topics Outline (ES-301-1)

CB1)raft g/Oraft Control Room Systems & Facility Walk-Through Test Outline (ES-301-2)

Location of Electronic Files:

Submitted By: P~~0veri1iOOBy:1J1J Submit ooBy: p~ ~tbverified

, By 1nJifd1.1(A,

1. 2Jk

( ES-401 11 Rev. 9 PWR examination Examination Outline ES-401-2 Form ES-4D1-2 I Facility: Watts Bar Date of Exam: Nov 2009 I

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

  • Total
1. 1 3 3 3 3 3 3 18 3 3 6 Emergency & 4 2 1 1 2 2 1 2 9 2 2 Abnormal Plant N/A N/A Evolutions Tier Totals 4 4 5 5 4 5 27 5 5 10 1 3 2 3 3 2 2 2 3 2 3 3 28 3 2 5 2.

2 1 0 1 1 1 1 1 1 1 1 1 10 2 1 3 Plant Systems Tier Totals 4 2 4 4 3 3 3 4 3 4 4 38 5 3 8

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 3 2 2 3 1 2 2 2
1. Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (i.e.,

(Le., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KIA category shall not nolbe 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 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. Systems/evolutions Systemslevolutions 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 KIA statements.
4. Select topics from as many systems and evolutions as possible; sample every system or evolution evolution*

in the group before selecting a second topic for any system or evolution.

5. Absent a plant-specific priority, only those KIAs having an importance rating (IR) of 2.5 or.

or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

6. Select SROtopicsJor Tiers 1 and 2 from the shaded systems and KIA categories.
7. *The generic (G) KIAs in Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics topiCS must be relevant to the applicable evolution or system.
8. On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; iffuel handling equipment is sampled in 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. 1 does not apply). Use duplicate pages for RO and SRO-only exams.
9. For Tier 3, select topiCS topics from Section 2 of the KIA catalog, and enter the KIA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. LimitSRO selections to KIAs that are linked to 10 CFR 55.43.

~/-- ~"

ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 KS K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO 007EG2.4.21 Reactor Trip - Stabilization - Recovery 4.0 4.6 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of the parameters and logic used to assess 11 the status of safety functions 009EA2.20 Small Break LOCA 13 2.6 2.9 0 0 0 0 0 0 0 ~ 0 0 0 Containment vent damper position indicator 011 EK1.01 Large Break LOCA 1 I3 4.1 4.1 4.4 4.4 0 0 0 0 0 0 0 0 0

~DDDDDDDDD

~ 0 Natural circulation and cooling, including reflux boiling.

015AK1.03 RCP Malfunctions 14 3 4 4 ~DDDDDDDDDD The basis for operating at a reduced power level when one RCP is out of service 022AA1.02 Loss of Rx Coolant Makeup 1 I2 3 2.9 2.9 DODD DDDDDD~DDDD 0 0 ~ 0 0 0 0 CVCS charging low flow alarm, sensor and indicator 02SAK2.0S 025AK2.05 Loss of RHR System 14 2.6 2.6 o0 ~ 0 0 0 0 0 0 0 0 0 Reactor building sump 026AK3.02 Loss of Component Cooling Water 18 I8 3.6 3.9 DD~DDDDDDDD The automatic actions (alignments) within the CCWS resulting from the actuation of the ESFAS 027AK2.03 Pressurizer Pressure Control System 2.6 2.8 D~DDDDDDDDD Controllers and positioners Malfunction I1 3 029EK1.0S 029EK1.05 ATWS/1 2.8 3.2 ~D 00000'000

~DDDDDDDDDD definition of negative temperature coefficient as applied to large PWR coolant systems 038EA2.11 Steam Gen. Tube Rupture I13 3 3.7 3.9 DDDDDDD~DDD Local radiation reading on main steam lines 040AA1.23 Steam Line Rupture - Excessive Heat 3,6 3.6 3.S 3.5 DDDDDD~DDDD All pressure gauges per steam generator (for pressure Transfer 14 drop)

Page 1 of 2 2111/20097:17AM 2111/2009 7:17 AM

ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO 054AK3.03 Loss of Main Feedwater / 4 3.8 4.1 ~ 0 0 0 0 0 0 0 0 0 0 Ii'l Manual control of AFW flow control valves 055EA2.06 Station Blackout / 6 3.7 4.1 0 0 0 0 0 0 0 Ii'l ~ 0 0 0 Faults and lockouts that must be cleared prior to re-energizing buses 057 AG2.1.23 Loss of Vital AC Inst.

Ins!. Bus / 6 4.3 4.4 0 0 0 0 0 DOD 0 0 0 0 0 Ii'l~ Ability to perform specific system and integrated plant procedures during all modes of plant operation.

058AG2.4.34 Loss of DC Power / 6 4.2 4.1 0 0 0 0 0 0 0 DDDIi'l 0 0 0 ~ Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects 065AK3.04 Loss of Instrument Air / 8 3 3.2 ~ 0 0 0 0 0 0 0 0 0 0 Ii'l Cross-over to backup air supplies 077AK2.03 Generator Voltage and Electric Grid 3.0 3.1 ~ 0 0 0 0 0 0 0 0 Ii'l 0.0 0 0 Sensors, detectors, indicators Disturbances / 6 WE04EA 1.3 LOCA Outside Containment //3 3 3.8 4.0 0 0 0 0 0 0 Ii'l ~ 0 0 0 0 Desired operating results during abnormal and emergency situations.

Page 2 of 2 2/11/2009 7:17 AM 2111/2009

ES-401, REV 9 T1G2 T1 G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2K3 K2 K3 K4 KS K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO 024AA2.02 Emergency Boration 11 /1 3.9 4.4 0 0 0 0 0 0 0 ~ 0 0 0 When use of manual boration valve is needed 028AK3.05 028AK3.0S Pressurizer Level Malfunction I/ 2 3.7 4.1 0 0 ~ 0 0 0 0 0 0 0 0 Actions contained in EOP for PZR level malfunction 036AG2.4.2 Fuel Handling Accident I 8 4.S 4.5 4.6 0 0 0 0 0 0 0 0 0 0 ~ pOints, interlocks and Knowledge of system set points, and automatic actions associated with EOP entry conditions.

OS9AK3.01 059AK3.01 Accidental Liquid RadWaste ReI. 19 /9 3.5 3.S 3.9 0 0 ~ 0 0 0 00 0 0 0 0 Termination of a release of radioactive liquid 067 AK1.01 067AK1.01 Plant Fire On-site 19

/ 98 2.9 3.9 ~ 0 0 0 0 00 0 0 0 0 0 Fire classifications by type 069AA 1.01 Loss of CTMT Integrity I/ S 5 3.S 3.5 3.7 000 0 0 0 0 0 0 ~ 000 0 0 0 0 Isolation valves, dampers and electropneumatic devices.

WE01 EA 1.3 Rediagnosis I/ 3 3.4 3.8 0 0 0 0 0 0 ~ DOD 0 0 0 0 Desired operating results during abnormal and emergency situations.

Over-pressure I/ 4 we13EG2.1.31 Steam Generator OverCpressure 4.6 4.3 0 0 0 0 0 0 0 0 0 0 ~ Ability to locate control room switches, controls and, and indications and to determine that they are correctly reflecting the desired plant lineup.

WE1SEK2.2 WE15EK2.2 Containment Flooding 15IS 2.7 2.9 0 ~ 0 0 0 0 0 0 0 0 0 Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems and relations between the proper operation of these systems to the operation of the facility.

Page 1 of 1 7:17 AM 2I11/20097:17AM 2111/2009

ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO 003A1.09 Reactor Coolant Pump 2.B 2.8 2.B 2.8 DDDDDD~DDDD Seal flow and D/P 004K5.36 Chemical and Volume Control 2.5 2.B DD[JD~DDDDDD Solubility of boron in water; tem temperature perature effect 005G2.1.23 Residual Heat Removal 4.3 4.4 DDDDDDDDDD~ Ability to perform specific system and integrated plant procedures during all modes of plant operation.

005K6.03 Residual Heat Removal 2.5 2.6 DDDDD~DDDDD RHR heat exchanger 006K5.09 Emergency Core Cooling 3.3 3.6 DDDD~DDDDDD Thermodynamics of water and steam, including subcooled margin, superheat and saturation 007A4.01 Pressurizer Relief/Quench Tank 2.7 2.7 DDDDDDDDD~D PRT spray supply valve

.-----~.-.

007A4.09 Pressurizer Relief/Quench Tank 2.5 2.7 DDDDDDDDD~D Relationships between PZR level and changing levels of the PRT and bleed holdup tank 00BK1.05 Component Cooling Water 3.0 3.1 ~DDDDDDDDDD Sources of makeup water 010A4.03 Pressurizer Pressure Control 4.0 3.B DDDDDDDDD~D PORV and block valves 012A3.03 Reactor Protection 3.4 3.5 DDDDDDDD~DD Power supply 012G2.1.30 Reactor Protection 4.4 4.0 DDDDDDDDDD~ Ability to locate and operate components, including local controls.

Page 1 of 3 2111/2009 7:17 AM 2I11/20097:17AM

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ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I/ SAFETY FUNCTION: IR K1 K2 K3 K4 K5 KS K6 A1 A2 A3 A4 G TOPIC:

RO SRO 013K6.01 Engineered Safety Features Actuation 2.7 3.1 0 0 0 0 0 ~ 0 0 0 0 0 Sensors and detectors 022K2.02 Containment Cooling 2.5 2.S 2.4 0 ~ 0 0 0 0 0 0 0 0 0 Chillers 026K4.0B Containment Spray 4.1 4.3 0 0 0 ~ 0 0 0 0 000 0 0 0 Automatic swapover to containment sump suction for recirculation phase after LOCA (RWST low-low level alarm) 039K1.02 Main and Reheat Steam 3.3 3.3 ~ 0 0 0 0 0 0 0 0 0 0 Atmospheric relief dump valves 059K3.04 OS9K3.04 Main Feedwater 3.6 3.B 0 0 ~ 0 0 0 0 0 0 0 0 RCS 059K4.02 OS9K4.02 Main Feedwater 3.3 3.5 0 0 0 ~ 0 0 0 0 0 0 0 Automatic turbine/reactor trip runback 061A2.0B Auxiliary/Emergency Feedwater 2.7 2.9 0 0 0 0 0 0 0 ~ 0 0 0 Flow rates expected from various combinations of AFW pump discharge valves 062A2.09 AC Electrical Distribution 2.7 3.0 0 0 0 0 0 0 0 ~ 0 0 0 Consequences of exceeding current limitations 062A2.10 AC Electrical Distribution 3.0 3.3 DOD LJ 0 DOD 0 0 0 0 ~ 0 0 0 Effects of switching power supplies on instruments and controls 063K3.01 DC Electrical Distribution 3.7 4.1 0 0 ~ 0 0 0 0 00 0 0 0 0 0 0 0 0 ED/G 063K4.01 DC Electrical Distribution 2.7 3.0 0 0 0 ~ 0 0 0 0 0 0 0

~DDDDDDD Manual/automatic transfers of control Page 2 of 3 7: 17 AM 2/1112009 7:17 211112009

ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO 064A1.04 Emergency Diesel Generator 2.8 2.9 0D 0D 0D 0D 0D 0D 21 ~ 0D 0D 0D 0D" Crankcase temperature and pressure 064K1.03 Emergency Diesel Generator 3.6 4.0 21

~ 0D 0D 0D 0D 0D 0D 0D D 0 0D 0D Diesel fuel oil supply system 073K3.01 Process Radiation Monitoring 3.6 4.2 0D 0D 21~ 0D 0D 0D 0D D 0 0D 0D 0D Radioactive effluent releases

--=-==----::---,----------------

076K2.01 Service Water 2.7 2.7 0D 21~ 0 0 D 0D D 0 0D D 0 0D D0 0D Service water 078A3.01 Instrument Air 3.1 3.2 D 0 D 0 0D 0D 0D 0D 0D 0D 21 ~ D0 0D Air pressure 103G2.4.30 Containment 2.7 4.1 D 0 0D 0D D 0 0D 0D D 0 0D D 0 D0 21

~ Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.

Page 3 of 3 2I11/20097:17AM 2111/2009 7:17 AM

ES~401, REV.9 ES-401, REV 9 T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO 001A1.13 Control Rod Drive 4.0 4.2 D D D D D D ~ D D D D 'Prepower "Prepower dependent insertion limit' limit" and pbwer power dependent insertion limit, determined with metroscope 002A4.05 Reactor Coolant 2.8 2.7 D D D D D D D D D ~ D The HPI system when it is used to refill the refueling cavity

- - - - - _ . _ . _. .---------~-----------------------

016G2.2.38 Non-nuclear Instrumentation 3.6 4.5 D D D D D D D D D D ~

~ Knowledge of conditions and limitations in the facility license.

027K1.01 Containment Iodine Removal 3.4 3.4 3.7 3.7 ~ D D D D D D D D D D

~DDDDDDDDDD CSS

. - - - . - . -.... --.-=----,,-~~~~~~c:__~::_::_~~~~____:=__=~____:=__=~____:=_~~~=_~~~~~~~~~~~~~~~~~-

033A3.01 Spent Fuel Pool Cooling 2.5 2.7 D D D D D D D D ~ D D DDDDDDDD~DD Temperature control valves 035K6.01 Steam Generator 3.2 3.2 3.6 3.6 D D D D D ~ D D D D D DDDDD~DDDDD MSIVs 045K4.46 Main Turbine Generator 2.5 2.5 2.8 2.8 D D D ~ D D D D D D D DDD~DDDDDDD overspeed Defeat of reactor trip by overs peed trip test lever 055K3.01 Condenser Air Removal 2.5 2.5 2.7 2.7 D DD.~~ D D D D D D D D Main condenser 071A2.02 Waste Gas Disposal 3.3 3.6 D D D D D D D ~ D D D Use of waste gas release monitors, radiation, gas flow rate and totalizer 086K5.04 Fire Protection 2.9 3.5 D D D D ~ D D D D D D Hazards to personnel as a result cifof fire type and methods of protection Page 1 of 1 2111/2009 7:17 AM

"r",....--~, ~

3 ES-401, REV 9 T3 PWR EXAMINATION OUTLINE FORM ES-401~ ~

KA NAME / SAFETY FUNCTION: IR KS K6 A1 A2 A3 A4 G K1 K2 K3 K4 K5 TOPIC:

RO SRO G2.1.29 Conduct of operations 4.1 4.1 4.0 4.0 0DDDDDDDDDD~

0 0 0 0 0 0 0 0 0 ~ Knowledge of how to conduct system lineups, such as valves, breakers, switches, etc.

G2.1.30 Conduct of operations 4.4 4.4 4.0 4.0 0DDDDDDDDDD~

0 0 0 0 0 0 0 0 0 ~ Ability to locate and operate components, including local controls.

G2.1.6 Conduct of operations 3.8 4.8 DDDDDDDDDD~ Ability to manage the control room crew during plant transients.

G2.2.41 G2.2,41 Equipment Control 3.5 3.S 3.9 0DDDDDDDDDD~

00000000 ~ Ability to obtain and interpret station electrical and mechanical drawings

~---

G2.2.42 Equipment Control 3.9 4.6 DDDDDDDDDD~ Ability to recognize system parameters that are entry-level conditions for Technical Specifications

--~.-~-

G2.3.13 Radiation Control 3.4 3.8 DDDDDDDDDD~ Knowledge of radiological safety procedures pertaining to licensed operator duties G2.3.6 Radiation Control 2.0 3.8 DDDDDDDDDD~ Ability to aprove release permits G2.4.12 Emergency Procedures/Plans 4.0 4.3 DDDDDDDDDD~ Knowledge of general operating crew responsibilities operations..

during emergency operations G2.4.21 Emergency Procedures/Plans 4.0 4.6 DDDDDDDDDD~ Knowledge of the parameters and logic used to assess the status of safety functions G2.4.39 Emergency Procedures/Plans 3.9 3.8 DDDDDDDDDD~ Knowledge of the RO's responsibilities in emergency plan implementation.

Page 1 of 1 2111/2009 7:17 AM

ES-401, REV 9 SRO T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2K3 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO 022AA2.03 Loss ot'Rx o(Rx Coolant Makeup /2/2 3.1 3.6 0 0 D D D0 D0 0D DOli']

D D ~J 0 0 D D D 0 Failures of flow control valve or controller 029EG2.2.22 ATWS/1 ATWS / 1 4.0 4.7 0 0 D 0 0 0 0 D DOD D D 0 D 0 DOli']

D D ~ Knowledge of limiting conditions for operations and safety limits.

038EG2.2.4 Steam Gen. Tube Rupture 13/3 3.6 3.6 0 0 D D D0 0D 0D 0 D 0 D 0 D DOli']

D D ~ (multi-unit) Ability to explain the variations in control board layouts, systems, instrumentation and procedural actions between units at a facility.

058AA2.02 Loss of DC Power 16

/6 3.3 3.6 0 0 D D D0 0D 0D DOli']

D D ~ 0 D D 0 0D 125V dc bus voltage, lowlcriticallow, low/critical low, alarm 077AA2.07 Generator Voltage and Electric Grid 3.6 4.0 0 D D 0 D0 0D 0D DOli']

D D ~ 0 D D 0 D0 Operational status of engineered safety features Disturbances I/ 6 we05EG2.4.3 Inadequate Heat Transfer - Loss of 3.7 3.9 D D 0 0 D0 D0 D D D D DOli']

0 DOD D D ~ Ability to identify post-accident instrumentation.

Secondary Heat Sink I/ 4 Page 1 of 1 2111/2009 7:17 AM 2/11/2009

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ES-401, REV 9 SRO T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO 033AG2.2.40 Loss of Intermediate Range NI/7 3.4 4.7 0 0 0 0 0 0 0 0 0 0 ~ Ability to apply technical specifications for a system.

067AA2.12 Plant Fire On-site 1 9 8 2.9 3.9 ° 0 0 0 0 0 0 0 ~ 0 0 0 Location of vital equipment within fire zone we06EG2.1.23 Degraded Core Cooling 1 14 4 4.3 4.4 0 0 0 0 DOD 0 0 DO 0 0 0 ~ Ability to perform specific system and integrated plant procedures during all modes of plant operation.

WE09EA2.1 14 Natural Circ. 14 3.1 3.8 0 0 0 0 0 0 0 ~ 0 0 0 Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

Page 1 of 1 2I11/20097:17AM 2111/2009 7:17 AM

ES-401, REV 9 SRO T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO 008G2.2.25 Component Cooling Water 3.2 4.2 D nD nD nD nD D D D D D n ~ Knowledge of the bases in Technical Specifications for lim iting conditions for operations and safety limits.

limiting lim its.

010A2.02 Pressurizer Pressure Control 3.9 3.9 D D D D D D D ~ D D D DOD Spray valve failures 026A2.03 Containment Spray 4.1 4.1 4.4 4.4 D DDDDDD~

D D D D D D ~ D D D Failure of ESF 063G2.4.20 DC Electrical Distribution 3.8 4.3 D D D 0D D D D D D D DOD ~ Knowledge of operational implications of EOP warnings, cautions and notes.

103A203 Containment 3.5 3.5 3.8 D D D D D D D ~ D D D DDDDD~DDD Phase A and B isolation Page 1 of 1 2I11/20097:17AM 2111/2009 7:17 AM

ES-401, REV 9 SRO T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO 028A2.01 Recombiner and Purge Hydrogen f!ecombiner 3.4 3.6 0 0 0 0 0 0 0 lilI ~ 0 0 0 setting, determined by using Hydrogen recombiner power setting.

Control plant data book 068A2.03 Liquid Radwaste 2.5 2.6 0 0 0 0 0 0 0 lilI ~ 0 0 0 Insufficient sampling frequency of the boric acid in the evaporator bottoms 071G2.4.9 DispOl~al Waste Gas Disposal 3.8 4.2 0 D0 0 [j0 0 0 0 0 0 0 lilI ~ Knowledge of low power 1 shutdown implications in accident (e.g. LOCA or loss of RHR) mitigation strategies.

Page 1 of 1 2111/2009 7:17 AM

3 ES-401, REV 9 SRO T3 PWR EXAMINATION OUTLINE ES-401~

FORM ES-401'\ ~

KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO G2.1.41 Conduct of operations 2.8 3.7 0D 0D 0D 0D 0D 0D DO D D 0D 0D ~ Knowledge of the refueling processes G2.222 G2.2.22 Equipment Control 4.0 4.7 0D 0D 0D 0D 0D 0D 0D 0D 0D 0D ~ Knowledge of lim iting conditions for operations and safety limiting limits.

~----

G2.2.37 Equipment Control 3,6 3.6 4.6 0D 0D 0D 0D 0D 0D 0D 0D 0D 0D ~

~ Ability to determine operability and/or availability of safety related equipment G2.3.6 Radiation Control 2.0 3.8 0D 0D 0D 0D 0D 0D 0D 0D 0D 0D ~ Ability to aprove release permits G2.3.7 Radiation Control 3.5 3.6 0D 0D 0D 0D 0D 0D 0D 0D 0D 0D ~ Ability to comply with radiation work permit requirements during normal or abnormal conditions

-=-=-:-:-::------=-------=---~__cc=_------ ----------------------------------~--------------_:__----__:_c----_,_--~

~~----~~----~--~~~------~~~~~~~=-~~-=~~=-~~~~--~~~~~--~~--~~~-----------

G2.4.18 Emergency Procedures/Plans 3.3 4.0 0D 0D 0D 0D 0D 0D 0D 0D 0D 0D ~ Knowledge of the specific bases for EOPs.

G2.4.3 Emergency Procedures/Plans 3.7 3.9 0D 0D 0D 0D 0D 0D 0D 0D 0D 0D ~ Ability to identify post-accident instrumentation.

Page 1 of 1 2111/20097:17AM 2111/2009 7:17 AM

ES-401 Record of Rejected KI KlAs As Form ES-401-4 Watts Bar Nov. 2009 RO exam

(

Tierl Tier/ Randomly Reason for Rejection Group Selected KIA Reactor Coolant Pump (RCP) Malfunctions 1/1 015 AK1.03 Knowledge of the operational implications of the following concepts as they apply to Reactor Coolant Pump Malfunctions (Loss of RC Flow):

AK1.03 The basis for operating at a reduced power level when one RCP is out of service.

Replaced because Watts Bar procedures do not allow this operating configuration.

Replaced by Chief Examiner on 08/04/09 with KA AK1.02 Containment Iodine Removal System (CIRS) 2/2 027 K1.01 Knowledge of the physical connections andlor and/or cause effect relationships between the CIRS and the following systems: CSS Replaced - Watts Bar CSS has no interface with the iodine removal function.

Replaced by Chief Examiner on 08/04/09 with KA K5.01 Spent Fuel Pool Cooling System (SFPCS) 2/2 033 A3.01

( Ability to monitor automatic operation of the Spent Fuel Pool Cooling System including:

Temperature control valves Replaced because Watts Bar design is using manual valves only; there are no automatic temperature control valves for SFP cooling. .

Replaced by Chief Examiner on 08/04/09 with KA A2.03 Ability to approve release permits.

3 G 2.3.6 Replaced - per alignment with Chief Examiner, it is not feasible to write an operationally valid question for an RO to approve .

release permits.

Replaced by Chief Examiner on 08/04/09 with KA G2.3.4

/

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

(

Facility: Watts Bar Date of Examination: 11/30/2009 Examination Level: RO 181 J:8J SRO D 0 Operating Test Number: 1 Administrative Topic Type Describe activity to be performed (See Note) Code*

G 2.1.1 Knowledge of conduct of operations Conduct of Operations M,R . requirements. 3.8 / 4.2 3.8/4.2 JPM: Determine License Status.

G 2.1.25 Ability to interpret reference materials, such as G2.1.25 Conduct of Operations N,R graphs, curves, tables, etc. 3.9/4.2 3.9 1 4.2 JPM: Perform RCS Deboration Calculation.

G 2.2.12 Knowledge of surveillance procedures. 3.7/4.1 Equipment Control N,R JPM: Perform 1-SI-0-2A-03, "1900-0700 Shift and Daily Surveillance Log Mode Three.

(

G 2.3.4 Knowledge of radiation exposure limits under Radiation Control D,R normal or emergency conditions. 3.2/3.7 3.21 3.7 JPM: Determine Potential Dose for Valve Alignment.

. Emergency Procedures 1 /

Plan

-- N/A NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics; topics, when all 5 are required.

  • Type Codes & & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom

(~3 (D)irect from bank (.::5. ~ 4 for SROs &

3 for ROs; .::5. & RO retakes)

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

(~ 1; randomly selected)

(P)revious 2 exams (.::5.

Page 22 of 27 ES 301, Page

ES-301 ES*301 Administrative Topics Outline Form ES-301-1 ES*301*1

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Facility: Watts Bar Date of Examination: 11/30/2009 Examination Level: ROO SRO (gj ~ Operating Test Number: 1 Administrative Topic Type Describe activity to be performed (See Note) Code*

G 2.1.1 Knowledge of conduct of operations Conduct of Operations M,R requirements. 3.8 1/ 4.2 JPM: Determine License Status.

G 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc. 3.9 3.9/4.2 1 4.2 Conduct of Operations D,R JPM: Review of Estimated Critical Position Calculation.

G 2.2.12 Knowledge of surveillance procedures. 3.71 3.7/

4.1 Equipment Control N,R JPM: Review 1-SI-0-2A-03, "1900-0700 Shift and Daily Surveillance Log Mode Three."

(,

G 2.3.4 Knowledge of radiation exposure limits under Radiation Control D,R normal or emergency conditions. 3.2 3.2/3.7 1 3.7 JPM: Determine Potential Dose for Valve Alignment.

G 2.4.40 Knowledge of SRO responsibilities in emergency plan implementation. 2.5/3.3 Emergency Procedures 1/

M,R G 2.4.41 Knowledge of the emergency action level Plan thresholds and classifications. 2.9 14.6 /4.6 JPM: Classify the Event and Determine PAR.

for SROs. RO applicants require only 4 items unless they are NOTE: All items (5 total) are required forSROs.

required.

retaking only the administrative topics, when all 5 are required.

  • Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom

(~3 (D)irect from bank (:::. ~ 4 for SROs &RO 3 for ROs; :::. & RO retakes) .

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

(P)revious 2 exams (~ (:::. 1; randomly selected)

( ES 301, Page 220f22 of 27

\

.ES-301 ~ Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Watts Bar Date of Examination: Nov-Dec 2009

(

Exam Level: RO ~ SRO-I ~ SRO-U ~ Operating Test Number: 1 (Bolded JPMs are SRO-U.)

(Bo/ded (Italicized JPM is RO only.)

Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Safety System / JPM Title Type Code*

Function

a. Exercise Control Rods per 1-SI-85-2. N 1
b. Perform FR-1.1,"High Pressurizer Level." A,M,L 2
c. Align RHR for Hot Leg Recirculation. A,D,EN 3
d. Place Standby Main Feedwater Pump in service for Periodic Operation N 4S with Main Feedwater Pumps.

CROM Coolers.

e. Align CRDM N 5
f. Reinstate Source Range following a Reactor Trip. A,M 7 Board 1
g. Transfer 6.9 KV RCP Board 10D from Alternate to Normal per SOI-202.01. A,M 6
h. Swap CCS Pumps (place 18 in service, remove 1A from service).(RO Only) A,N 8

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

i. Isolate The RCP Seal Injection And Thermal Barrier Per ECA-O.O. D,E,L,R 2
j. Align High Pressure Fire Protection (HPFP) to Centrifugal Charging Pump D,EN,R 8 1A-A Lube Oil Coolers.

1A-A

k. Align the Upper Containment Monitor to Lower Containment Locally. O,R D,R 7

@ 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 / SRO-I / SRO-U (A)lternate path 4-6/ 4-6 / 2-3 (C)ontrol room (D)irect from bank ~9/ ~8 / ~4

~4 (E)mergency or abnormal in-plant ~1 /

.=:: ~1

,=::1 / ~

.=:: 1 (EN)gineered safety feature (EN)gineeredsafety - / - / ~

>1 (L)ow-Power / Shutdown ~ 1 /

.=:: ~1

.=::1 ~1

/ .=::1 (N)ew or (M)odified from bank including 1(A) ~2/

.=::2/ ~2 / .=::

.=::2 ~1 (P)revious 2 exams ~3 ~3 / ~ 2 (randomly selected)

(R)CA ~1 /

.=:: ~1

.=::1 ~ 1

/ .=::

(S)imulator ES-301, Page 23 of 27

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