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{{#Wiki_filter:ES-401                                             PWR Examination Outline                                                 Form ES-401-2 Facility: CRYSTAL RIVER 3                                               Date of Exam:       SEPTEMBER 2011 ROK/ACaioyPcnts                                             SRO-Only_Points Tier           Group K   K   K   K     K     KA       A     A   AG                       A2           G*         Total 1   2   3   4     5     6   1   2     3   4         Total
{{#Wiki_filter:ES-401 PWR Examination Outline Form ES-401-2 Facility: CRYSTAL RIVER 3 Date of Exam: SEPTEMBER 2011
: 1.               1           3   3   3                     3   3               3       18           3             3           6 Emergency &
 
Abnormal             2           L +/-                 N/A       2_   j       N/A     1       9           2             2           4 Tier Totals       5   4   5                     5   4               4       27           5             5           10 Evoluhons 1           23332232332                                                 28           3             2           5 2.
ROK/ACaioyPcnts
Plant             2           Ill             11         101             111               10       0     2         1           3 Systems Tier Totals       3   4   4   4     3     3   3   3     4   4   3       38           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 Note:       1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each K/A category shall not be less than two).
SRO-Only_Points Tier Group K
: 2. The point total for each group and tier in the proposed outline must match that specified in the table.
K K
K K
KA A
A AG 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 &
Abnormal 2
L +/-
N/A 2_ j N/A 1
9 2
2 4
Evoluhons Tier Totals 5
4 5
5 4
4 27 5
5 10 1
23332232332 28 3
2 5
2.
Plant 2
Ill 11 101 111 10 0
2 1
3 Systems Tier Totals 3
4 4
4 3
3 3
3 4
4 3
38 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 Note:
1.
Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each K/A 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 point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions.
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.
The final RO exam must total 75 points and the SRO-only exam must total 25 points.
: 3. Systems/evolutions 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/evolutions that are not included on the outline should be added. Refer to Section D.1 .b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.
3.
: 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.
Systems/evolutions 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/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.
: 5. Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected.
4.
Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
5.
Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected.
Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
: 6. Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.
6.
7* The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1 .b of ES-401 for the applicable K/As.
Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.
: 8. On the following pages, enter the K/A 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; if fuel 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.
7*
: 9. For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401 -3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.
The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable K/As.
8.
On the following pages, enter the K/A 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; if fuel 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 from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401 -3. Limit SRO selections to K/As 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 K5 K6 Al A2 A3 A4 G TOPIC:
IRO SRO 007EK3.01 Reactor Trip
- Stabilization
- Recovery 4
4.6 El El El El El El El El El El Actions contained in EOP for reactor trip
/1 008AK3.02 Pressurizer Vapor Space Accident / 3 3.6 4.1 Why PORV or code safety exit temperature is below RCS or PZR temperature OO9EK1.01 Small Break LOCA /3 4.2 4.7 Natural circulation and cooling, including reflux boiling 011 EK2.02 Large Break LOCA / 3 2.6 2.7 El Pumps 015AG2.4.46 RCP Malfunctions / 4 4.2 4.2 Ability to verify that the alarms are consistent with the plant conditions.
025AK1.01 Loss of TRHR System / 4 3.9 4.3 Loss of RHRS during all modes of operation 027AA2.14 Pressurizer Pressure Control System 2.8 2.9 RCP injection flow Malfunction / 3 029EK2.06 ATWS / 1 2.9 3.1 El El El El El El El El El El Breakers, relays, and disconnects.
038EA1.44 Steam Gen. Tube Rupture / 3 3.4 3.4 El El El El El El El El El El Level operating limits for S/Gs 040AG2.4.35 Steam Line Rupture
- Excessive Heat 3.8 4.0 El El El El El El El El El El Knowledge of local auxiliary operator tasks during Transfer / 4 emergency and the resultant operational effects 054AA1.04 Loss of Main Feedwater / 4 4.4 4.5 El El El El El El El El El El HPI, under total feedwater loss conditions Page 1 of 2 9/16/2010 9:49 AM
 
FORM ES-401-2 TOPIC:
Length of time for which battery capacity is designed Definition of saturation conditions implication for the systems Knowledge of EOP entry conditions and immediate action steps.
The cause of possible SWS loss Cause and effect of low-pressure instrument air alarm Voltatge regulator controls 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.
ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE KA NAME I SAFETY FUNCTION:
IA Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G RO SRO 055EK3.0l Station Blackout! 6 2.7 3.4 El 056AK1.04 Loss of Off-site Power! 6 3.1 3.2 058AG2.4.l Loss of DC Power! 6 4.6 4.8 El El El El El El El El El El {l 062AA2.02 Loss of Nuclear Svc Water! 4 2.9 3.6 El El El El El El El El El El 065AA2.0l Loss of Instrument Air! 8 2.9 3.2 El El El El El El El El El El 077AA1.03 Generator Voltage and Electric Grid 3.8 3.7 El El El El El El El El El El Disturbances! 6 BEO4EK2.2 Inadequate Heat Transfer
- Loss of 4.2 4.2 El El El El El El El El El El Secondary Heat Sink ! 4 Page 2 of 2 9!16!2010 9:49AM
 
ES-401, REV 9 T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION:
IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO
 
Reset of demand position counter to zero 2.9 3.8 Bases for power limit for rod misalignment 3.4 3.4 CVCS 2.7 3.1 Power supplies, including proper switch positions 3.8 4.2 Guidance contained in EOP for loss of containment integrity 3.4 3.2 Operating behavior characteristics of the facility.
3.3 3.7 J
Normal, abnormal and emergency operating procedures associated with (Flooding).
3.5 4
Adherence to appropriate procedures and operation within the limitations in the facility s license and amendments.
2.7 4.1 Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.
003AK3.06 Dropped Control Rod / 1 2.7 3
OO5AK1.06 028AA1.02 032AK2.0l 069AK3.01 BAO2AA1.2 BA07AK1.2 BE03EA2.2 Inoperable/Stuck Control Rod /1 Pressurizer Level Malfunction / 2 Loss of Source Range NI / 7 Loss of CTMT Integrity / 5 LossofNNl-X/7 Flooding / 8 Inadequate Subcooling Margin / 4 BEO9EG2.4.30 Natural Circ. /4 Page 1 of 1 9/16/2010 9:49AM


ES-401, REV 9                                           T1G1 PWR EXAMINATION OUTLINE                                                   FORM ES-401-2 KA         NAME / SAFETY FUNCTION:                   IR   K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G   TOPIC:
ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETY FUNCTION:
IRO    SRO 007EK3.01                -
IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
Reactor Trip Stabilization - Recovery  4    4.6                                  Actions contained in EOP for reactor trip El El    El El El El El El El El
            /1 008AK3.02  Pressurizer Vapor Space Accident / 3  3.6  4.1                                  Why PORV or code safety exit temperature is below RCS or PZR temperature OO9EK1 .01  Small Break LOCA /3                    4.2  4.7                                  Natural circulation and cooling, including reflux boiling 011 EK2.02  Large Break LOCA / 3                  2.6  2.7      El                          Pumps 015AG2.4.46 RCP Malfunctions / 4                  4.2  4.2                                  Ability to verify that the alarms are consistent with the plant conditions.
025AK1 .01  Loss of TRHR System / 4                3.9  4.3                                  Loss of RHRS during all modes of operation 027AA2.14  Pressurizer Pressure Control System    2.8  2.9                                  RCP injection flow Malfunction / 3 029EK2.06  ATWS / 1                              2.9  3.1 El    El El El El El El El El El  Breakers, relays, and disconnects.
038EA1 .44  Steam Gen. Tube Rupture / 3            3.4  3.4 El El El El El El    El El El El Level operating limits for S/Gs 040AG2.4.35 Steam Line Rupture  - Excessive Heat  3.8  4.0                                  Knowledge of local auxiliary operator tasks during Transfer / 4 El El El El El El El El El El    emergency and the resultant operational effects 054AA1 .04  Loss of Main Feedwater / 4            4.4  4.5 El El El El El El    El El El El HPI, under total feedwater loss conditions Page 1 of 2                                                  9/16/2010 9:49 AM


ES-401, REV 9                                        T1G1 PWR EXAMINATION OUTLINE                                                    FORM ES-401-2 KA        NAME I SAFETY FUNCTION:                IA    Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G  TOPIC:
Seal injection flow Understanding of interface with LRS Relationship (dependence) of time available to perform system isolation surveillance test to time for decay heat to reach high limit Position of RWST recirculation valve (locked when not in use, continuously monitored when in use).
RO    SRO 055EK3.0l  Station Blackout! 6                2.7  3.4                                El Length of time for which battery capacity is designed 056AK1 .04 Loss of Off-site Power! 6          3.1  3.2                                  Definition of saturation conditions implication for the systems 058AG2.4.l Loss of DC Power! 6                4.6  4.8 El El El El El El El El El El {l  Knowledge of EOP entry conditions and immediate action steps.
Valves normally isolated from their control power Monitoring quench tank temperature Method of forming a steam bubble in the PZR CCW pump, including emergency backup Loads cooled by CCWS RCS pressure Bypass-block circuits RO SRO
062AA2.02  Loss of Nuclear Svc Water! 4        2.9  3.6 El El El El El El El    El El El The cause of possible SWS loss 065AA2.0l  Loss of Instrument Air! 8          2.9  3.2 El El El El El El El    El El El Cause and effect of low-pressure instrument air alarm 077AA1 .03 Generator Voltage and Electric Grid 3.8  3.7 El El El El El El    El El El El Voltatge regulator controls Disturbances! 6 BEO4EK2.2                            -
Inadequate Heat Transfer Loss of    4.2  4.2                                  Facility s heat removal systems, including primary Secondary Heat Sink ! 4 El    El El El El El El El El El  coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.
Page 2 of 2                                                  9!16!2010 9:49AM


ES-401, REV 9                                        T1G2 PWR EXAMINATION OUTLINE                                                      FORM ES-401-2 KA          NAME / SAFETY FUNCTION:                IR    Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G  TOPIC:
003A3.0l Reactor Coolant Pump 3.3 3.2 004K1.35 Chemical and Volume Control 2.5 2.8 El El El El 005A1.06 Residual Heat Removal 2.7 3.1 El El El El El El l El El El El 005A4.05 Residual Heat Removal 2.8 2.8 El El El El El El El El El El 006K4.18 Emergency Core Cooling 3.6 3.7 El El El l El El El El El El El 007A1.03 Pressurizer Relief/Quench Tank 2.6 2.7 El El El El El El El El El El 007K5.02 Pressurizer Relief/Quench Tank 3.1 3.4 El El El El El El El El El El 008K2.02 Component Cooling Water 3.0 3.2 El El El El El El El El El El 008K3.Ol Component Cooling Water 3.4 3.5 El El ] El El El El El El El El 010A1.07 Pressurizer Pressure Control 3.7 3.7 El El El El El El El El El El 012K6.04 Reactor Protection 3.3 3.6 El El El El El El El El El El Page 1 of 3 9/16/2010 9:49AM
RO    SRO 003AK3.06   Dropped Control Rod / 1            2.7   3                                     Reset of demand position counter to zero OO5AK1 .06  Inoperable/Stuck Control Rod /1   2.9    3.8                                   Bases for power limit for rod misalignment 028AA1 .02  Pressurizer Level Malfunction / 2 3.4    3.4                                  CVCS 032AK2.0l    Loss of Source Range NI / 7      2.7   3.1                                   Power supplies, including proper switch positions 069AK3.01    Loss of CTMT Integrity / 5        3.8    4.2                                  Guidance contained in EOP for loss of containment integrity BAO2AA1 .2  LossofNNl-X/7                    3.4    3.2                                   Operating behavior characteristics of the facility.
BA07AK1 .2  Flooding / 8                      3.3   3.7                                J Normal, abnormal and emergency operating procedures associated with (Flooding).
BE03EA2.2    Inadequate Subcooling Margin / 4 3.5   4                                    Adherence to appropriate procedures and operation within the limitations in the facility s license and amendments.
BEO9EG2.4.30 Natural Circ. /4                  2.7    4.1                                  Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.
Page 1 of 1                                                      9/16/2010 9:49AM


ES-401, REV 9                                   T2G1 PWR EXAMINATION OUTLINE                                                     FORM ES-401-2 KA         NAME/SAFETY FUNCTION:               IR   Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G     TOPIC:
ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETY FUNCTION:
RO     SRO 003A3.0l   Reactor Coolant Pump            3.3  3.2                                      Seal injection flow 004K1.35  Chemical and Volume Control    2.5  2.8                          El El El El Understanding of interface with LRS 005A1.06  Residual Heat Removal          2.7  3.1 El El El El El El l El El El El      Relationship (dependence) of time available to perform system isolation surveillance test to time for decay heat to reach high limit 005A4.05  Residual Heat Removal          2.8  2.8 El El El El El El El El El        El Position of RWST recirculation valve (locked when not in use, continuously monitored when in use).
IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
006K4.18  Emergency Core Cooling          3.6  3.7 El El El l El El El El El El El      Valves normally isolated from their control power 007A1 .03 Pressurizer Relief/Quench Tank 2.6    2.7 El El El El El El        El El El El Monitoring quench tank temperature 007K5.02  Pressurizer Relief/Quench Tank 3.1    3.4 El El El El      El El El El El El  Method of forming a steam bubble in the PZR 008K2.02  Component Cooling Water        3.0    3.2 El    El El El El El El El El El    CCW pump, including emergency backup 008K3.Ol  Component Cooling Water        3.4    3.5 El El ] El El El El El El El El      Loads cooled by CCWS 010A1.07  Pressurizer Pressure Control  3.7   3.7 El El El El El El        El El El El RCS pressure 012K6.04  Reactor Protection            3.3    3.6 El El El El El        El El El El El Bypass-block circuits Page 1 of 3                                                     9/16/2010 9:49AM
RO SRO 013K5.02 Engineered Safety Features Actuation 2.9 3.3 Safety system logic and reliability 022K2.0l Containment Cooling 3.0 3.1 Containment cooling fans 026K1.01 Containment Spray 4.2 4.2 fl j ECCS 026K4.02 Containment Spray 3.1 3.6 Neutralized boric acid to reduce corrosion and remove inorganic fission product iodine from steam (NAOH) in containment spray 039A2.03 Main and Reheat Steam 3.4 3.7 Indications and alarms for main steam and area radiation monitors (during SGTR) 059A3.03 Main Feedwater 2.5 2.6 Feedwater pump suction flow pressure 061 K2.0l Auxiliary/Emergency Feedwater 3.2 3.3 AFW system MOVs 062K3.03 AC Electrical Distribution 3.7 3.9 DC system 063K3.02 DC Electrical Distribution 3.5 3.7 Components using DC control power 063K4.01 DC Electrical Distribution 2.7 3.0 Manual/automatic transfers of control 064A3.02 Emergency Diesel Generator 3.4 3.7 Minimum time for load pickup Page2of 3 9/16/2010 9:49AM


ES-401, REV 9                                          T2G1 PWR EXAMINATION OUTLINE                                                 FORM ES-401-2 KA        NAME/SAFETY FUNCTION:                    IR   Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
T2G1 PWR EXAMINATION OUTLINE IR Ki K2 K3 K4 K5 k6 Al A2 A3 A4 G RO SAC 3.2 3.3 ES-401, REV 9 KA NAME / SAFETY FUNCTION:
RO     SRO 013K5.02  Engineered Safety Features Actuation 2.9    3.3                                Safety system logic and reliability 022K2.0l  Containment Cooling                  3.0  3.1                                Containment cooling fans 026K1.01  Containment Spray                    4.2    4.2                     fl j      ECCS 026K4.02  Containment Spray                    3.1  3.6                                Neutralized boric acid to reduce corrosion and remove inorganic fission product iodine from steam (NAOH) in containment spray 039A2.03  Main and Reheat Steam                3.4  3.7                                Indications and alarms for main steam and area radiation monitors (during SGTR) 059A3.03  Main Feedwater                      2.5    2.6                                Feedwater pump suction flow pressure 061 K2.0l  Auxiliary/Emergency Feedwater        3.2    3.3                                AFW system MOVs 062K3.03  AC Electrical Distribution            3.7  3.9                                 DC system 063K3.02  DC Electrical Distribution            3.5  3.7                                Components using DC control power 063K4.01  DC Electrical Distribution          2.7    3.0                                Manual/automatic transfers of control 064A3.02  Emergency Diesel Generator           3.4  3.7                                Minimum time for load pickup Page2of 3                                                  9/16/2010 9:49AM
064K6.08 Emergency Diesel Generator 073A4.03 Process Radiation Monitoring 3.1


ES-401, REV 9                                T2G1 PWR EXAMINATION OUTLINE                                                  FORM ES-401-2 KA        NAME / SAFETY FUNCTION:          IR    Ki K2 K3 K4 K5 k6 Al A2 A3 A4 G TOPIC:
===3.2 TOPIC===
RO    SAC 064K6.08  Emergency Diesel Generator  3.2  3.3                                Fuel oil storage tanks 073A4.03  Process Radiation Monitoring 3.1  3.2                                 Check source for operability demonstration 073G2.4.3 Process Radiation Monitoring 3.7   3.9                                 Ability to identify post-accident instrumentation.
Fuel oil storage tanks FORM ES-401-2 073G2.4.3 Process Radiation Monitoring 3.7 3.9 076G2.l.28 Service Water 4.1 4.1 Check source for operability demonstration 078A4.Ol Instrument Air 3.1 3.1 Ability to identify post-accident instrumentation.
076G2.l.28 Service Water               4.1   4.1                                 Knowledge of the purpose and function of major system components and controls.
103A2.05 Containment 2.9 3.9 Knowledge of the purpose and function of major system components and controls.
078A4.Ol   Instrument Air               3.1   3.1                                 Pressure gauges 103A2.05   Containment                 2.9   3.9                                 Emergency containment entry Page 3 of 3                                                 9/16/2010 9:49AM
Pressure gauges Emergency containment entry Page 3 of 3 9/16/2010 9:49AM


ES-401, REV 9                                       T2G2 PWR EXAMINATION OUTLINE                                               FORM ES-401-2 KA         NAME / SAFETY FUNCTION:               IR   Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
ES-401, REV 9 T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION:
RO     SRO 001 K5.88 Control Rod Drive                 2.9   3.4                                 Effects of boron on temperature coefficient 011 K3.03 Pressurizer Level Control         3.2   3.7                                 PZR PCS 014K4.06   Rod Position Indication           3.4   3.7                                 Individual and group misalignment 01 7A4.01 In-core Temperature Monitor       3.8   4.1                                 Actual in-core temperatures 027G2.4.6 Containment Iodine Removal         3.7   4.7                       Lj     j Knowledge symptom based EOP mitigation strategies.
IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
029K1.04   Containment Purge                 3.0   3.1                                 Purge system 034A2.03   Fuel Handling Equipment           3.3   4.0                                 Mispositioned fuel element 041 A3.05 Steam Dump/Turbine Bypass Control 2.9   2.9                                 Main steam pressure 068K6.l0   Liquid Radwaste                   2.5   2.9                                 Radiation monitors 075K2.03   Circulating Water                 2.6   2.7                                 Emergency/essential SWS pumps Page 1 of 1                                             9/16/2010 9:49 AM
RO SRO 001 K5.88 Control Rod Drive 2.9 3.4 Effects of boron on temperature coefficient 011 K3.03 Pressurizer Level Control 3.2 3.7 PZR PCS 014K4.06 Rod Position Indication 3.4 3.7 Individual and group misalignment 01 7A4.01 In-core Temperature Monitor 3.8 4.1 Actual in-core temperatures 027G2.4.6 Containment Iodine Removal 3.7 4.7 Lj j
Knowledge symptom based EOP mitigation strategies.
029K1.04 Containment Purge 3.0 3.1 Purge system 034A2.03 Fuel Handling Equipment 3.3 4.0 Mispositioned fuel element 041 A3.05 Steam Dump/Turbine Bypass Control 2.9 2.9 Main steam pressure 068K6.l0 Liquid Radwaste 2.5 2.9 Radiation monitors 075K2.03 Circulating Water 2.6 2.7 Emergency/essential SWS pumps Page 1 of 1 9/16/2010 9:49 AM


ES-401, REV 9                                  T3 PWR EXAMINATION OUTLINE                                                    FORM ES-401-2 KA        NAME / SAFETY FUNCTION:        IR      Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
LI LI LI LI LI LI LI LI AbUity to use plant computer to evaluate system or component status.
RO    SAC G2.1.19    Conductof operations      3.9    3.8        LI LI LI LI LI LI LI LI   AbUity to use plant computer to evaluate system or component status.
4.3 4.4 Ability to perform specific system and integrated plant procedures during all modes of plant operation.
G2.1 .23  Conduct of operations      4.3   4.4                                   Ability to perform specific system and integrated plant procedures during all modes of plant operation.
3.8 4.8 Ability to manage the control room crew during plant transients.
G2.l.6    Conduct of operations      3.8   4.8                                   Ability to manage the control room crew during plant transients.
2.6 3.8 Knowledge of the process for managing maintenance activities during power operations.
G2.2.17    Equipment Control          2.6   3.8                                   Knowledge of the process for managing maintenance activities during power operations.
4.6 4.1 Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels.
G2.2.2    Equipment Control          4.6   4.1                                   Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels.
2.9 4.1 Knowledge of pre-and post-maintenance operability requirements.
G2.2.21    Equipment Control          2.9   4.1                                   Knowledge of pre- and post-maintenance operability requirements.
3.8 4.3 Ability to control radiation releases.
G2.3.1 1  Radiation Control          3.8   4.3                                   Ability to control radiation releases.
3.5 3.6 Ability to comply with radiation work permit requirements during normal or abnormal conditions 4.5 4.7 Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.
G2.3.7    Radiation Control          3.5   3.6                                   Ability to comply with radiation work permit requirements during normal or abnormal conditions G2.4.4    Emergency Procedures/Plans 4.5   4.7                                   Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.
4.2 4.2 Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.
G2.4.47    Emergency Procedures/Plans 4.2   4.2                                   Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.
ES-401, REV 9 RO SAC KA NAME / SAFETY FUNCTION:
Page 1 of 1                                                 9/16/2010 9:49AM
IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
G2.1.19 Conductof operations 3.9 3.8 T3 PWR EXAMINATION OUTLINE FORM ES-401-2 G2.1.23 G2.l.6 G2.2.17 G2.2.2 G2.2.21 G2.3.1 1 G2.3.7 G2.4.4 G2.4.47 Conduct of operations Conduct of operations Equipment Control Equipment Control Equipment Control Radiation Control Radiation Control Emergency Procedures/Plans Emergency Procedures/Plans Page 1 of 1 9/16/2010 9:49AM


ES-401, REV 9                                         SRO T1G1 PWR EXAMINATION OUTLINE                                                 FORM ES-401-2 KA         NAME / SAFETY FUNCTION:                     IR   Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
ES-401, REV 9 SRO T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION:
RO     SRO 007EA2.04   Reactor Trip Stabilization   Recovery 4.6   4.4                                 If reactor should have tripped but has not done so, I1                                                                                manually trip the reactor and carry out actions in ATWS EOP 038EG2.4.20 Steam Gen. Tube Rupture / 3             3.8   4.3                                 Knowledge of operational implications of EOP warnings, cautions and notes.
IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
057AA2.06   Loss of Vital AC Inst. Bus! 6           3.2   3.7                                 AC instrument bus alarms for the inverter and alternate power source 062AG2.2.36 Loss of Nuclear Svc Water / 4           3.1   4.2             E D LI LI LI       Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions of operations 077AG2.2.37 Generator Voltage and Electric Grid     3.6   4.6                                 Ability to determine operability and/or availability of safety Disturbances / 6                                                                 related equipment BEO5EA2.l  Steam Line Rupture    - Excessive Heat  3    4.2                                Facility conditions and selection of appropriate Transfer / 4                                                                      procedures during abnormal and emergency operations.
RO SRO 007EA2.04 Reactor Trip
Page 1 of 1                                               9/16/2010 9:49 AM
- Stabilization
- Recovery 4.6 4.4 If reactor should have tripped but has not done so, I 1 manually trip the reactor and carry out actions in ATWS EOP 038EG2.4.20 Steam Gen. Tube Rupture / 3 3.8 4.3 Knowledge of operational implications of EOP warnings, cautions and notes.
057AA2.06 Loss of Vital AC Inst. Bus! 6 3.2 3.7 AC instrument bus alarms for the inverter and alternate power source 062AG2.2.36 Loss of Nuclear Svc Water / 4 3.1 4.2 E D LI LI LI Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions of operations 077AG2.2.37 Generator Voltage and Electric Grid 3.6 4.6 Ability to determine operability and/or availability of safety Disturbances / 6 related equipment Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
BEO5EA2.l Steam Line Rupture
- Excessive Heat Transfer / 4 3
4.2 Page 1 of 1 9/16/2010 9:49 AM


ES-401, REV 9                                   SRO T1G2 PWR EXAMINATION OUTLINE                                               FORM ES-401-2 KA          NAME / SAFETY FUNCTION:              IR   K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
ES-401, REV 9 KA 003AA2.05 SRO T1G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G RD SRO 2.5 3.2 3.3 4.0 3.9 4.1 BAO5AG2.2.12 Emergency Diesel Actuation! 6 3.7 4.1 Knowledge of surveillance procedures.
RD   SRO 003AA2.05    Dropped Control Rod / 1          2.5   3.2                                 Interpretation of computer in-core TC map for dropped rod location 005AG2.4.18  Inoperable/Stuck Control Rod / 1 3.3   4.0                                 Knowledge of the specific bases for EOPs.
NAME / SAFETY FUNCTION:
051AA2.02    Loss of Condenser Vacuum / 4    3.9   4.1                                 Conditions requiring reactor and/or turbine trip BAO5AG2.2.12 Emergency Diesel Actuation! 6   3.7   4.1                                 Knowledge of surveillance procedures.
Dropped Control Rod / 1 TOPIC:
Page 1 of 1                                               9/16/2010 9:49AM
005AG2.4.18 Inoperable/Stuck Control Rod / 1 051AA2.02 Loss of Condenser Vacuum / 4 FORM ES-401-2 Interpretation of computer in-core TC map for dropped rod location Knowledge of the specific bases for EOPs.
Conditions requiring reactor and/or turbine trip Page 1 of 1 9/16/2010 9:49AM


ES-401, REV 9                            SRO T2G1 PWR EXAMINATION OUTLINE                                                 FORM ES-401-2 KA        NAME / SAFETY FUNCTION:          IR   Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
FORM ES-401-2 SRO T2G1 PWR EXAMINATION OUTLINE IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G RO SRO 2.9 4.6 ED DDE DDDDDDDDL1 D
RO   SRO 008G2.4.41 Component Cooling Water      2.9   4.6                                 Knowledge of the emergency action level thresholds and classifications.
TOPIC:
010A2.Ol   Pressurizer Pressure Control 3.3   3.6                                 Heater failures 022A2.02   Containment Cooling         2.3   2.6                                 Fan motor vibration 026A2.09   Containment Spray           2.5   2.9 D ED                    DDE    Radiation hazard potential of BWST 059G2.l.25 Main Feedwater               3.9   4.2   DDDDDDDDL1                  Ability to interpret reference materials such as graphs, monographs and tables which contain performance data.
Knowledge of the emergency action level thresholds and classifications.
Page 1 of 1                                               9/16/2010 9:49AM
Heater failures ES-401, REV 9 KA NAME / SAFETY FUNCTION:
008G2.4.41 Component Cooling Water 010A2.Ol Pressurizer Pressure Control 3.3 3.6 022A2.02 Containment Cooling 2.3 2.6 026A2.09 Containment Spray 2.5 2.9 059G2.l.25 Main Feedwater 3.9 4.2 Fan motor vibration Radiation hazard potential of BWST Ability to interpret reference materials such as graphs, monographs and tables which contain performance data.
Page 1 of 1 9/16/2010 9:49AM


ES-401, REV 9                         SRO T2G2 PWR EXAMINATION OUTLINE                                               FORM ES-401-2 KA         NAME/SAFETY FUNCTION:       IA   Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
ES-401, REV 9 SRO T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETY FUNCTION:
RO   SRO 015A2.05   Nuclear Instrumentation 3.3   3.8                                 Core void formation 029A2.Ol   Containment Purge       2.9   3.6                                 Maintenance or other activity taking place inside containment 071 G2.2.38 Waste Gas Disposal     3.6   4.5                                 Knowledge of conditions and limitations in the facility license.
IA Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
Page 1 of 1                                               9/16/2010 9:49 AM
RO SRO 015A2.05 Nuclear Instrumentation 3.3 3.8 Core void formation 029A2.Ol Containment Purge 2.9 3.6 Maintenance or other activity taking place inside containment 071 G2.2.38 Waste Gas Disposal 3.6 4.5 Knowledge of conditions and limitations in the facility license.
Page 1 of 1 9/16/2010 9:49 AM


ES-401, REV 9                             SRO T3 PWR EXAMINATION OUTLINE                                                FORM ES-401-2 KA         NAME I SAFETY FUNCTION:        IR    Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
ES-401, REV 9 KA NAME I SAFETY FUNCTION:
RO    SRO G2.1.15   Conduct of operations     2.7  3.4                                Knowledge of administrative requirements for temporary management directives such as standing orders, night orders, Operations memos, etc.
G2.1.15 Conduct of operations G2.1.31 Conduct of operations G2.2.19 Equipment Control G2.2.7 Equipment Control G2.3.4 Radiation Control G2.4.34 Emergency Procedures/Plans G2.4.8 Emergency Procedures/Plans SRO T3 PWR EXAMINATION OUTLINE IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G SRO 3.4 3.6 3.7 4.1 4.5 FORM ES-401-2 RO
G2.1 .31   Conduct of operations     4.6                                      Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup.
G2.2.19   Equipment Control         2.3                                      Knowledge of maintenance work order requirements.
G2.2.7     Equipment Control         2.9  3.6                                Knowledge of the process for conducting special or infrequent tests G2.3.4     Radiation Control         3.2  3.7                                Knowledge of radiation exposure limits under normal and emergency conditions G2.4.34   Emergency Procedures/Plans 4.2  4.1                                Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects G2.4.8     Emergency Procedures/Plans 3.8  4.5                                Knowledge of how abnormal operating procedures are used in conjunction with EOPs.
Page 1 of 1                                                9/16/2010 9:49AM


ES-301, Rev. 9, Supp. 1             Administrative Topics Outline                               Form ES-301-1 Facility:         Crystal River Unit #3                       Date of Exam:                 09/12/11 thru 09/29/11 Examination Level:       RO               SRO                 Operating Test Number:                 1 (NRC)
2.7 4.6 2.3 2.9 3.2 4.2
Administrative Topic           Type Describe activity to be performed (See Note)             Code*
 
RO & SRO - (CO1) - Perform an RCS boron change calculation.
===3.8 TOPIC===
Conduct of Operations            M, R K/A - G2.1.37 RO 4.3 SRO 4.6 OP-304 RO & SRO - (CO2) - Calculate SDM with a misaligned rod.
Knowledge of administrative requirements for temporary management directives such as standing orders, night orders, Operations memos, etc.
K/A - G2.1.7 RO 4.4 SRO 4.7 Conduct of Operations            D, R        SRO Only - After completing the SDM calculation determine required ITS actions, if any.
Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup.
K/A - G2.2.40 SRO 4.7 SP-421 RO & SRO - (EC1) - Perform a QPTR calculation.
Knowledge of maintenance work order requirements.
K/A - G2.2.12 RO 3.7 SRO 4.1 SRO Only - After completing the QPTR calculation Equipment Control                M, R determine required ITS actions, if any.
Knowledge of the process for conducting special or infrequent tests Knowledge of radiation exposure limits under normal and emergency conditions Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects Knowledge of how abnormal operating procedures are used in conjunction with EOPs.
K/A - G2.2.40 SRO 4.7 SP-303 RO & SRO - (RC1) - Determine stay times using survey maps.
Page 1 of 1 9/16/2010 9:49AM
Radiation Control                D, R K/A - G2.3.4 RO 3.2 SRO 3.7 DOS-NGGC-0004 SRO Only - (EP1) - Determine Emergency Action Level and Protective Action Recommendations.
 
Emergency Procedures D, P, R        K/A - 2.4.41 SRO 4.6
ES-301, Rev. 9, Supp. 1 Administrative Topics Outline Form ES-301-1 Page 1 of 1K:\\scandocs\\Operator Licensing\\Capehart\\Crystal River 2011-301\\Draft Exam\\Form ES-301-1 (JPM Admin Outline)
/ Plan K/A - 2.4.44 SRO 4.4 EM-202 All items (5 total) are required for SROs. RO applicants require only 4 items unless Note:
NRC 2011 Rev 0.docx ES-301 Facility:
they are retaking only the administrative topics, when all 5 are required.
Crystal River Unit #3 Date of Exam:
09/12/11 thru 09/29/11 Examination Level:
RO SRO Operating Test Number:
1 (NRC)
Administrative Topic (See Note)
Type Code*
Describe activity to be performed Conduct of Operations M, R RO & SRO - (CO1) - Perform an RCS boron change calculation.
K/A - G2.1.37 RO 4.3 SRO 4.6 OP-304 Conduct of Operations D, R RO & SRO - (CO2) - Calculate SDM with a misaligned rod.
K/A - G2.1.7 RO 4.4 SRO 4.7 SRO Only - After completing the SDM calculation determine required ITS actions, if any.
K/A - G2.2.40 SRO 4.7 SP-421 Equipment Control M, R RO & SRO - (EC1) - Perform a QPTR calculation.
K/A - G2.2.12 RO 3.7 SRO 4.1 SRO Only - After completing the QPTR calculation determine required ITS actions, if any.
K/A - G2.2.40 SRO 4.7 SP-303 Radiation Control D, R RO & SRO - (RC1) - Determine stay times using survey maps.
K/A - G2.3.4 RO 3.2 SRO 3.7 DOS-NGGC-0004 Emergency Procedures
/ Plan D, P, R SRO Only - (EP1) - Determine Emergency Action Level and Protective Action Recommendations.
K/A - 2.4.41 SRO 4.6 K/A - 2.4.44 SRO 4.4 EM-202 Note:
All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
* Type Codes & Criteria:
(C)ontrol room, (S)imulator or Class(R)oom (D)irect from bank ( < 3 for ROs; < 4 for SROs & RO retakes)
(C)ontrol room, (S)imulator or Class(R)oom (D)irect from bank ( < 3 for ROs; < 4 for SROs & RO retakes)
* Type Codes & Criteria:
(N)ew or (M)odified from bank ( > 1)
(N)ew or (M)odified from bank ( > 1)
(P)revious 2 exams ( <1; randomly selected)
(P)revious 2 exams ( <1; randomly selected)  
Page 1 of 1K:\scandocs\Operator Licensing\Capehart\Crystal River 2011-301\Draft Exam\Form ES-301-1 (JPM Admin Outline)
NRC 2011 Rev 0.docx                                  ES-301


ES-301, Rev. 9, Supp. 1           Control Room / In-Plant Systems Outline                       Form ES-301-2 Facility:         Crystal River Unit #3                             Date of Exam: 09/12/11 thru 09/23/11 Exam Level: RO               SRO-I         SRO-U                   Operating Test Number:                 1 (NRC)
ES-301, Rev. 9, Supp. 1 Control Room / In-Plant Systems Outline Form ES-301-2 Page 1 of 1K:\\scandocs\\Operator Licensing\\Capehart\\Crystal River 2011-301\\Draft Exam\\Form ES-301-2 (JPM MCR-Plant Outline) NRC 2011 Rev 3.docx ES-301 Facility:
Crystal River Unit #3 Date of Exam: 09/12/11 thru 09/23/11 Exam Level: RO SRO-I SRO-U Operating Test Number:
1 (NRC)
Control Room systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U, including 1 ESF)
Control Room systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U, including 1 ESF)
Type          Safety System / JPM Title Code*         Function
System / JPM Title Type Code*
: a.       CRDS - Perform actions of AP-504 D, S            1 K/A - 001A4.15 RO 3.1 SRO 3.1 (AP-504)                             [RO]
Safety Function
: b.       ESFAS - Respond to an ES Actuation                                 [SRO-U]
: a.
CRDS - Perform actions of AP-504 K/A - 001A4.15 RO 3.1 SRO 3.1 (AP-504)
[RO]
D, S 1
: b.
ESFAS - Respond to an ES Actuation
[SRO-U]
K/A - BW/E03EA1.1 RO 4.1 SRO 3.8 (EOP-3)
[RO, SRO-I]
A, EN, N, S 4
A, EN, N, S 4
K/A - BW/E03EA1.1 RO 4.1 SRO 3.8 (EOP-3)                            [RO, SRO-I]                            Primary
Primary
: c.       PPCS - Respond to a stuck open PZR spray valve                                           A, D, L, P, 3
: c.
K/A - 010A4.01 RO 3.7 SRO 3.5 (AP-520)                             [RO, SRO-I]               S
PPCS - Respond to a stuck open PZR spray valve K/A - 010A4.01 RO 3.7 SRO 3.5 (AP-520)
: d.       EFW - Establish Auxiliary Feedwater flow N, S 4
[RO, SRO-I]
K/A - 061G2.1.20 RO 4.6 SRO 4.6 (EOP-04)                           [RO, SRO-I]                         Secondary
A, D, L, P, S
: e.       CSS - Initiate Reactor Building Spray                               [SRO-U]
3
A, L, M, S            5 K/A - 026A3.01 RO 4.3 SRO 4.5 (EM-225C)                             [RO, SRO-I]
: d.
: f.       EDG - Synchronize Off-Site Power with EDG-1A D, S            6 K/A - 064A4.09 RO 3.2 SRO 3.3 (AP-770)                             [RO, SRO-I]
EFW - Establish Auxiliary Feedwater flow K/A - 061G2.1.20 RO 4.6 SRO 4.6 (EOP-04)
: g.       CWS - Start CWP-1C While at Power                                   [SRO-U A, D, P, S          8 K/A - 075G2.1.31 RO 4.2 SRO 3.9 (OP-604)                           [RO, SRO-I]
[RO, SRO-I]
: h.       WGS - Respond to a Waste Gas Header leak A, D, S            9 K/A - 060AA2.05 RO 3.7 SRO 4.2 (AP-250)                             [RO, SRO-I]
N, S 4
SPARE             MU - Restart a MUP following an RCS leak isolation D, S            2 K/A - 002A2.01 RO 4.3 SRO 4.4 (AP-520)
Secondary
: e.
CSS - Initiate Reactor Building Spray
[SRO-U]
K/A - 026A3.01 RO 4.3 SRO 4.5 (EM-225C)
[RO, SRO-I]
A, L, M, S 5
: f.
EDG - Synchronize Off-Site Power with EDG-1A K/A - 064A4.09 RO 3.2 SRO 3.3 (AP-770)
[RO, SRO-I]
D, S 6
: g.
CWS - Start CWP-1C While at Power
[SRO-U K/A - 075G2.1.31 RO 4.2 SRO 3.9 (OP-604)
[RO, SRO-I]
A, D, P, S 8
: h.
WGS - Respond to a Waste Gas Header leak K/A - 060AA2.05 RO 3.7 SRO 4.2 (AP-250)
[RO, SRO-I]
A, D, S 9
SPARE MU - Restart a MUP following an RCS leak isolation K/A - 002A2.01 RO 4.3 SRO 4.4 (AP-520)
D, S 2
In-Plant Systems* (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)
In-Plant Systems* (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)
: i.       ECCS - Respond to a CFT Low Pressure condition                     [SRO-U]
: i.
D, E, L, R          3 K/A - 006A1.13 RO 3.5 SRO 3.7 (AP-404)                             [RO, SRO-I]
ECCS - Respond to a CFT Low Pressure condition
: j.       HRPS - Place a Hydrogen Analyzer in Service A, D, E, L          5 K/A - 028A4.03 RO 3.1 SRO 3.3 (EOP-14)                             [RO, SRO-I]
[SRO-U]
: k.       WGDS - Perform a Waste Gas Release to the RB                       [SRO-U]
K/A - 006A1.13 RO 3.5 SRO 3.7 (AP-404)
D, R              9 K/A - 071G2.3.11 RO 3.8 SRO 4.3 (OP-412A)                           [RO, SRO-I]
[RO, SRO-I]
SPARE             FS/OTSG - Transfer excess secondary inventory to FST D, E            8 K/A - 038EK3.06 RO 4.2 SRO 4.5 (EOP-14, Enc. 9)
D, E, L, R 3
All RO and SRO-I control room (and in-plant) systems must be different and serve different safety
: j.
* functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
HRPS - Place a Hydrogen Analyzer in Service K/A - 028A4.03 RO 3.1 SRO 3.3 (EOP-14)
* 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 (E)mergency or abnormal in-plant                                                               >1/>1/>1 (EN)gineered safety feature                                       (control room system)        - / - />1 (L)ow Power / Shutdown                                                                         >1/>1/>1 (N)ew or (M)odified from bank including 1 (A)                                                 >2/>2/>1 (P)revious 2 exams                                                (randomly selected)         <3/<3/<2 (R)CA                                                                                          >1/>1/>1 (S)imulator Page 1 of 1K:\scandocs\Operator Licensing\Capehart\Crystal River 2011-301\Draft Exam\Form ES-301-2 (JPM MCR-Plant Outline) NRC 2011 Rev 3.docx ES-301
[RO, SRO-I]
A, D, E, L 5
: k.
WGDS - Perform a Waste Gas Release to the RB
[SRO-U]
K/A - 071G2.3.11 RO 3.8 SRO 4.3 (OP-412A)
[RO, SRO-I]
D, R 9
SPARE FS/OTSG - Transfer excess secondary inventory to FST K/A - 038EK3.06 RO 4.2 SRO 4.5 (EOP-14, Enc. 9)
D, E 8
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 (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow Power / Shutdown (N)ew or (M)odified from bank including 1 (A)
(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3
< 9 / < 8 / < 4
> 1 / > 1 / > 1 (control room system)  
- / - / > 1
> 1 / > 1 / > 1
> 2 / > 2 / > 1 (randomly selected)  
< 3 / < 3 / < 2  
> 1 / > 1 / > 1  


ES-301, Rev. 9, Supp. 1           Control Room / In-Plant Systems Outline                       Form ES-301-2 Page 2 of 2K:\scandocs\Operator Licensing\Capehart\Crystal River 2011-301\Draft Exam\Form ES-301-2 (JPM MCR-Plant Outline) NRC 2011 Rev 3.docx ES-301}}
ES-301, Rev. 9, Supp. 1 Control Room / In-Plant Systems Outline Form ES-301-2 Page 2 of 2K:\\scandocs\\Operator Licensing\\Capehart\\Crystal River 2011-301\\Draft Exam\\Form ES-301-2 (JPM MCR-Plant Outline) NRC 2011 Rev 3.docx ES-301}}

Latest revision as of 21:47, 12 January 2025

Initial Exam 2011-301 Draft Administrative Documents
ML113340410
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 11/28/2011
From:
NRC/RGN-II/DRS/OLB
To:
Progress Energy Florida
References
50-302/11-301
Download: ML113340410 (17)
v • d • e


Text

ES-401 PWR Examination Outline Form ES-401-2 Facility: CRYSTAL RIVER 3 Date of Exam: SEPTEMBER 2011

ROK/ACaioyPcnts

SRO-Only_Points Tier Group K

K K

K K

KA A

A AG 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 &

Abnormal 2

L +/-

N/A 2_ j N/A 1

9 2

2 4

Evoluhons Tier Totals 5

4 5

5 4

4 27 5

5 10 1

23332232332 28 3

2 5

2.

Plant 2

Ill 11 101 111 10 0

2 1

3 Systems Tier Totals 3

4 4

4 3

3 3

3 4

4 3

38 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 Note:

1.

Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each K/A 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 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 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/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.

4.

Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.

5.

Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected.

Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

6.

Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.

7*

The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable K/As.

8.

On the following pages, enter the K/A 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; if fuel 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 from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401 -3. Limit SRO selections to K/As 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 K5 K6 Al A2 A3 A4 G TOPIC:

IRO SRO 007EK3.01 Reactor Trip

- Stabilization

- Recovery 4

4.6 El El El El El El El El El El Actions contained in EOP for reactor trip

/1 008AK3.02 Pressurizer Vapor Space Accident / 3 3.6 4.1 Why PORV or code safety exit temperature is below RCS or PZR temperature OO9EK1.01 Small Break LOCA /3 4.2 4.7 Natural circulation and cooling, including reflux boiling 011 EK2.02 Large Break LOCA / 3 2.6 2.7 El Pumps 015AG2.4.46 RCP Malfunctions / 4 4.2 4.2 Ability to verify that the alarms are consistent with the plant conditions.

025AK1.01 Loss of TRHR System / 4 3.9 4.3 Loss of RHRS during all modes of operation 027AA2.14 Pressurizer Pressure Control System 2.8 2.9 RCP injection flow Malfunction / 3 029EK2.06 ATWS / 1 2.9 3.1 El El El El El El El El El El Breakers, relays, and disconnects.

038EA1.44 Steam Gen. Tube Rupture / 3 3.4 3.4 El El El El El El El El El El Level operating limits for S/Gs 040AG2.4.35 Steam Line Rupture

- Excessive Heat 3.8 4.0 El El El El El El El El El El Knowledge of local auxiliary operator tasks during Transfer / 4 emergency and the resultant operational effects 054AA1.04 Loss of Main Feedwater / 4 4.4 4.5 El El El El El El El El El El HPI, under total feedwater loss conditions Page 1 of 2 9/16/2010 9:49 AM

FORM ES-401-2 TOPIC:

Length of time for which battery capacity is designed Definition of saturation conditions implication for the systems Knowledge of EOP entry conditions and immediate action steps.

The cause of possible SWS loss Cause and effect of low-pressure instrument air alarm Voltatge regulator controls 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.

ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE KA NAME I SAFETY FUNCTION:

IA Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G RO SRO 055EK3.0l Station Blackout! 6 2.7 3.4 El 056AK1.04 Loss of Off-site Power! 6 3.1 3.2 058AG2.4.l Loss of DC Power! 6 4.6 4.8 El El El El El El El El El El {l 062AA2.02 Loss of Nuclear Svc Water! 4 2.9 3.6 El El El El El El El El El El 065AA2.0l Loss of Instrument Air! 8 2.9 3.2 El El El El El El El El El El 077AA1.03 Generator Voltage and Electric Grid 3.8 3.7 El El El El El El El El El El Disturbances! 6 BEO4EK2.2 Inadequate Heat Transfer

- Loss of 4.2 4.2 El El El El El El El El El El Secondary Heat Sink ! 4 Page 2 of 2 9!16!2010 9:49AM

ES-401, REV 9 T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION:

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

RO SRO

Reset of demand position counter to zero 2.9 3.8 Bases for power limit for rod misalignment 3.4 3.4 CVCS 2.7 3.1 Power supplies, including proper switch positions 3.8 4.2 Guidance contained in EOP for loss of containment integrity 3.4 3.2 Operating behavior characteristics of the facility.

3.3 3.7 J

Normal, abnormal and emergency operating procedures associated with (Flooding).

3.5 4

Adherence to appropriate procedures and operation within the limitations in the facility s license and amendments.

2.7 4.1 Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.

003AK3.06 Dropped Control Rod / 1 2.7 3

OO5AK1.06 028AA1.02 032AK2.0l 069AK3.01 BAO2AA1.2 BA07AK1.2 BE03EA2.2 Inoperable/Stuck Control Rod /1 Pressurizer Level Malfunction / 2 Loss of Source Range NI / 7 Loss of CTMT Integrity / 5 LossofNNl-X/7 Flooding / 8 Inadequate Subcooling Margin / 4 BEO9EG2.4.30 Natural Circ. /4 Page 1 of 1 9/16/2010 9:49AM

ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETY FUNCTION:

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

Seal injection flow Understanding of interface with LRS Relationship (dependence) of time available to perform system isolation surveillance test to time for decay heat to reach high limit Position of RWST recirculation valve (locked when not in use, continuously monitored when in use).

Valves normally isolated from their control power Monitoring quench tank temperature Method of forming a steam bubble in the PZR CCW pump, including emergency backup Loads cooled by CCWS RCS pressure Bypass-block circuits RO SRO

003A3.0l Reactor Coolant Pump 3.3 3.2 004K1.35 Chemical and Volume Control 2.5 2.8 El El El El 005A1.06 Residual Heat Removal 2.7 3.1 El El El El El El l El El El El 005A4.05 Residual Heat Removal 2.8 2.8 El El El El El El El El El El 006K4.18 Emergency Core Cooling 3.6 3.7 El El El l El El El El El El El 007A1.03 Pressurizer Relief/Quench Tank 2.6 2.7 El El El El El El El El El El 007K5.02 Pressurizer Relief/Quench Tank 3.1 3.4 El El El El El El El El El El 008K2.02 Component Cooling Water 3.0 3.2 El El El El El El El El El El 008K3.Ol Component Cooling Water 3.4 3.5 El El ] El El El El El El El El 010A1.07 Pressurizer Pressure Control 3.7 3.7 El El El El El El El El El El 012K6.04 Reactor Protection 3.3 3.6 El El El El El El El El El El Page 1 of 3 9/16/2010 9:49AM

ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETY FUNCTION:

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

RO SRO 013K5.02 Engineered Safety Features Actuation 2.9 3.3 Safety system logic and reliability 022K2.0l Containment Cooling 3.0 3.1 Containment cooling fans 026K1.01 Containment Spray 4.2 4.2 fl j ECCS 026K4.02 Containment Spray 3.1 3.6 Neutralized boric acid to reduce corrosion and remove inorganic fission product iodine from steam (NAOH) in containment spray 039A2.03 Main and Reheat Steam 3.4 3.7 Indications and alarms for main steam and area radiation monitors (during SGTR) 059A3.03 Main Feedwater 2.5 2.6 Feedwater pump suction flow pressure 061 K2.0l Auxiliary/Emergency Feedwater 3.2 3.3 AFW system MOVs 062K3.03 AC Electrical Distribution 3.7 3.9 DC system 063K3.02 DC Electrical Distribution 3.5 3.7 Components using DC control power 063K4.01 DC Electrical Distribution 2.7 3.0 Manual/automatic transfers of control 064A3.02 Emergency Diesel Generator 3.4 3.7 Minimum time for load pickup Page2of 3 9/16/2010 9:49AM

T2G1 PWR EXAMINATION OUTLINE IR Ki K2 K3 K4 K5 k6 Al A2 A3 A4 G RO SAC 3.2 3.3 ES-401, REV 9 KA NAME / SAFETY FUNCTION:

064K6.08 Emergency Diesel Generator 073A4.03 Process Radiation Monitoring 3.1

3.2 TOPIC

Fuel oil storage tanks FORM ES-401-2 073G2.4.3 Process Radiation Monitoring 3.7 3.9 076G2.l.28 Service Water 4.1 4.1 Check source for operability demonstration 078A4.Ol Instrument Air 3.1 3.1 Ability to identify post-accident instrumentation.

103A2.05 Containment 2.9 3.9 Knowledge of the purpose and function of major system components and controls.

Pressure gauges Emergency containment entry Page 3 of 3 9/16/2010 9:49AM

ES-401, REV 9 T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION:

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

RO SRO 001 K5.88 Control Rod Drive 2.9 3.4 Effects of boron on temperature coefficient 011 K3.03 Pressurizer Level Control 3.2 3.7 PZR PCS 014K4.06 Rod Position Indication 3.4 3.7 Individual and group misalignment 01 7A4.01 In-core Temperature Monitor 3.8 4.1 Actual in-core temperatures 027G2.4.6 Containment Iodine Removal 3.7 4.7 Lj j

Knowledge symptom based EOP mitigation strategies.

029K1.04 Containment Purge 3.0 3.1 Purge system 034A2.03 Fuel Handling Equipment 3.3 4.0 Mispositioned fuel element 041 A3.05 Steam Dump/Turbine Bypass Control 2.9 2.9 Main steam pressure 068K6.l0 Liquid Radwaste 2.5 2.9 Radiation monitors 075K2.03 Circulating Water 2.6 2.7 Emergency/essential SWS pumps Page 1 of 1 9/16/2010 9:49 AM

LI LI LI LI LI LI LI LI AbUity to use plant computer to evaluate system or component status.

4.3 4.4 Ability to perform specific system and integrated plant procedures during all modes of plant operation.

3.8 4.8 Ability to manage the control room crew during plant transients.

2.6 3.8 Knowledge of the process for managing maintenance activities during power operations.

4.6 4.1 Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels.

2.9 4.1 Knowledge of pre-and post-maintenance operability requirements.

3.8 4.3 Ability to control radiation releases.

3.5 3.6 Ability to comply with radiation work permit requirements during normal or abnormal conditions 4.5 4.7 Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

4.2 4.2 Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

ES-401, REV 9 RO SAC KA NAME / SAFETY FUNCTION:

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

G2.1.19 Conductof operations 3.9 3.8 T3 PWR EXAMINATION OUTLINE FORM ES-401-2 G2.1.23 G2.l.6 G2.2.17 G2.2.2 G2.2.21 G2.3.1 1 G2.3.7 G2.4.4 G2.4.47 Conduct of operations Conduct of operations Equipment Control Equipment Control Equipment Control Radiation Control Radiation Control Emergency Procedures/Plans Emergency Procedures/Plans Page 1 of 1 9/16/2010 9:49AM

ES-401, REV 9 SRO T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION:

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

RO SRO 007EA2.04 Reactor Trip

- Stabilization

- Recovery 4.6 4.4 If reactor should have tripped but has not done so, I 1 manually trip the reactor and carry out actions in ATWS EOP 038EG2.4.20 Steam Gen. Tube Rupture / 3 3.8 4.3 Knowledge of operational implications of EOP warnings, cautions and notes.

057AA2.06 Loss of Vital AC Inst. Bus! 6 3.2 3.7 AC instrument bus alarms for the inverter and alternate power source 062AG2.2.36 Loss of Nuclear Svc Water / 4 3.1 4.2 E D LI LI LI Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions of operations 077AG2.2.37 Generator Voltage and Electric Grid 3.6 4.6 Ability to determine operability and/or availability of safety Disturbances / 6 related equipment Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

BEO5EA2.l Steam Line Rupture

- Excessive Heat Transfer / 4 3

4.2 Page 1 of 1 9/16/2010 9:49 AM

ES-401, REV 9 KA 003AA2.05 SRO T1G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G RD SRO 2.5 3.2 3.3 4.0 3.9 4.1 BAO5AG2.2.12 Emergency Diesel Actuation! 6 3.7 4.1 Knowledge of surveillance procedures.

NAME / SAFETY FUNCTION:

Dropped Control Rod / 1 TOPIC:

005AG2.4.18 Inoperable/Stuck Control Rod / 1 051AA2.02 Loss of Condenser Vacuum / 4 FORM ES-401-2 Interpretation of computer in-core TC map for dropped rod location Knowledge of the specific bases for EOPs.

Conditions requiring reactor and/or turbine trip Page 1 of 1 9/16/2010 9:49AM

FORM ES-401-2 SRO T2G1 PWR EXAMINATION OUTLINE IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G RO SRO 2.9 4.6 ED DDE DDDDDDDDL1 D

TOPIC:

Knowledge of the emergency action level thresholds and classifications.

Heater failures ES-401, REV 9 KA NAME / SAFETY FUNCTION:

008G2.4.41 Component Cooling Water 010A2.Ol Pressurizer Pressure Control 3.3 3.6 022A2.02 Containment Cooling 2.3 2.6 026A2.09 Containment Spray 2.5 2.9 059G2.l.25 Main Feedwater 3.9 4.2 Fan motor vibration Radiation hazard potential of BWST Ability to interpret reference materials such as graphs, monographs and tables which contain performance data.

Page 1 of 1 9/16/2010 9:49AM

ES-401, REV 9 SRO T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETY FUNCTION:

IA Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 015A2.05 Nuclear Instrumentation 3.3 3.8 Core void formation 029A2.Ol Containment Purge 2.9 3.6 Maintenance or other activity taking place inside containment 071 G2.2.38 Waste Gas Disposal 3.6 4.5 Knowledge of conditions and limitations in the facility license.

Page 1 of 1 9/16/2010 9:49 AM

ES-401, REV 9 KA NAME I SAFETY FUNCTION:

G2.1.15 Conduct of operations G2.1.31 Conduct of operations G2.2.19 Equipment Control G2.2.7 Equipment Control G2.3.4 Radiation Control G2.4.34 Emergency Procedures/Plans G2.4.8 Emergency Procedures/Plans SRO T3 PWR EXAMINATION OUTLINE IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G SRO 3.4 3.6 3.7 4.1 4.5 FORM ES-401-2 RO

2.7 4.6 2.3 2.9 3.2 4.2

3.8 TOPIC

Knowledge of administrative requirements for temporary management directives such as standing orders, night orders, Operations memos, etc.

Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup.

Knowledge of maintenance work order requirements.

Knowledge of the process for conducting special or infrequent tests Knowledge of radiation exposure limits under normal and emergency conditions Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects Knowledge of how abnormal operating procedures are used in conjunction with EOPs.

Page 1 of 1 9/16/2010 9:49AM

ES-301, Rev. 9, Supp. 1 Administrative Topics Outline Form ES-301-1 Page 1 of 1K:\\scandocs\\Operator Licensing\\Capehart\\Crystal River 2011-301\\Draft Exam\\Form ES-301-1 (JPM Admin Outline)

NRC 2011 Rev 0.docx ES-301 Facility:

Crystal River Unit #3 Date of Exam:

09/12/11 thru 09/29/11 Examination Level:

RO SRO Operating Test Number:

1 (NRC)

Administrative Topic (See Note)

Type Code*

Describe activity to be performed Conduct of Operations M, R RO & SRO - (CO1) - Perform an RCS boron change calculation.

K/A - G2.1.37 RO 4.3 SRO 4.6 OP-304 Conduct of Operations D, R RO & SRO - (CO2) - Calculate SDM with a misaligned rod.

K/A - G2.1.7 RO 4.4 SRO 4.7 SRO Only - After completing the SDM calculation determine required ITS actions, if any.

K/A - G2.2.40 SRO 4.7 SP-421 Equipment Control M, R RO & SRO - (EC1) - Perform a QPTR calculation.

K/A - G2.2.12 RO 3.7 SRO 4.1 SRO Only - After completing the QPTR calculation determine required ITS actions, if any.

K/A - G2.2.40 SRO 4.7 SP-303 Radiation Control D, R RO & SRO - (RC1) - Determine stay times using survey maps.

K/A - G2.3.4 RO 3.2 SRO 3.7 DOS-NGGC-0004 Emergency Procedures

/ Plan D, P, R SRO Only - (EP1) - Determine Emergency Action Level and Protective Action Recommendations.

K/A - 2.4.41 SRO 4.6 K/A - 2.4.44 SRO 4.4 EM-202 Note:

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

  • Type Codes & Criteria:

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

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

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

ES-301, Rev. 9, Supp. 1 Control Room / In-Plant Systems Outline Form ES-301-2 Page 1 of 1K:\\scandocs\\Operator Licensing\\Capehart\\Crystal River 2011-301\\Draft Exam\\Form ES-301-2 (JPM MCR-Plant Outline) NRC 2011 Rev 3.docx ES-301 Facility:

Crystal River Unit #3 Date of Exam: 09/12/11 thru 09/23/11 Exam Level: RO SRO-I SRO-U Operating Test Number:

1 (NRC)

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

System / JPM Title Type Code*

Safety Function

a.

CRDS - Perform actions of AP-504 K/A - 001A4.15 RO 3.1 SRO 3.1 (AP-504)

[RO]

D, S 1

b.

ESFAS - Respond to an ES Actuation

[SRO-U]

K/A - BW/E03EA1.1 RO 4.1 SRO 3.8 (EOP-3)

[RO, SRO-I]

A, EN, N, S 4

Primary

c.

PPCS - Respond to a stuck open PZR spray valve K/A - 010A4.01 RO 3.7 SRO 3.5 (AP-520)

[RO, SRO-I]

A, D, L, P, S

3

d.

EFW - Establish Auxiliary Feedwater flow K/A - 061G2.1.20 RO 4.6 SRO 4.6 (EOP-04)

[RO, SRO-I]

N, S 4

Secondary

e.

CSS - Initiate Reactor Building Spray

[SRO-U]

K/A - 026A3.01 RO 4.3 SRO 4.5 (EM-225C)

[RO, SRO-I]

A, L, M, S 5

f.

EDG - Synchronize Off-Site Power with EDG-1A K/A - 064A4.09 RO 3.2 SRO 3.3 (AP-770)

[RO, SRO-I]

D, S 6

g.

CWS - Start CWP-1C While at Power

[SRO-U K/A - 075G2.1.31 RO 4.2 SRO 3.9 (OP-604)

[RO, SRO-I]

A, D, P, S 8

h.

WGS - Respond to a Waste Gas Header leak K/A - 060AA2.05 RO 3.7 SRO 4.2 (AP-250)

[RO, SRO-I]

A, D, S 9

SPARE MU - Restart a MUP following an RCS leak isolation K/A - 002A2.01 RO 4.3 SRO 4.4 (AP-520)

D, S 2

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

i.

ECCS - Respond to a CFT Low Pressure condition

[SRO-U]

K/A - 006A1.13 RO 3.5 SRO 3.7 (AP-404)

[RO, SRO-I]

D, E, L, R 3

j.

HRPS - Place a Hydrogen Analyzer in Service K/A - 028A4.03 RO 3.1 SRO 3.3 (EOP-14)

[RO, SRO-I]

A, D, E, L 5

k.

WGDS - Perform a Waste Gas Release to the RB

[SRO-U]

K/A - 071G2.3.11 RO 3.8 SRO 4.3 (OP-412A)

[RO, SRO-I]

D, R 9

SPARE FS/OTSG - Transfer excess secondary inventory to FST K/A - 038EK3.06 RO 4.2 SRO 4.5 (EOP-14, Enc. 9)

D, E 8

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

(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3

< 9 / < 8 / < 4

> 1 / > 1 / > 1 (control room system)

- / - / > 1

> 1 / > 1 / > 1

> 2 / > 2 / > 1 (randomly selected)

< 3 / < 3 / < 2

> 1 / > 1 / > 1

ES-301, Rev. 9, Supp. 1 Control Room / In-Plant Systems Outline Form ES-301-2 Page 2 of 2K:\\scandocs\\Operator Licensing\\Capehart\\Crystal River 2011-301\\Draft Exam\\Form ES-301-2 (JPM MCR-Plant Outline) NRC 2011 Rev 3.docx ES-301

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