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{{#Wiki_filter:FACI LlTY NAM E: | {{#Wiki_filter: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 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 KA NAME / SAFETY FUNCTION: | ~/-- ~" | ||
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. | |||
Knowledge of the parameters and logic used to assess the status of safety functions | 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 | |||
2 | |||
2111/2009 7:17 AM | |||
ES-401, REV 9 | 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: | ||
IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO | 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 | |||
Page | .-----~.-. | ||
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 | |||
,J'(.'-..."" | |||
\ | |||
Temperature control valves | 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. | |||
3. | 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. | |||
3. | 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 | |||
3.7 | . - - - . - . -.... --.-=----,,-~~~~~~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~ | |||
3. | 0 0 0 0 0 0 0 0 0 ~ Ability to locate and operate components, including local controls. | ||
3. | 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 | |||
2 | ~--- | ||
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. | |||
3. | 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 | |||
"'"~" /'~'" -", | |||
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 | |||
/ | |||
( | |||
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 | |||
( | |||
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}} |
Latest revision as of 03:06, 12 March 2020
ML100830061 | |
Person / Time | |
---|---|
Site: | Watts Bar |
Issue date: | 02/11/2010 |
From: | NRC/RGN-II |
To: | Tennessee Valley Authority |
References | |
50-390/09-302 | |
Download: ML100830061 (19) | |
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 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
,J'(.'-...""
\
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
"'"~" /'~'" -",
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
/
(
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
(
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
- 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
( 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.
- 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