ML100670516
| ML100670516 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 12/11/2009 |
| From: | NRC/RGN-II |
| To: | Florida Power & Light Co |
| References | |
| 50-250/09-302, 50-251/09-302, ES-301, ES-301-1 50-250/09-302, 50-251/09-302 | |
| Download: ML100670516 (19) | |
Text
ES-301 Administrative Topics Outline Form ES-301-1 Facility: Turkey Point Units 3 & 4 Date of Examination: 2009 Exam Level: RO Operating Test Number: 2009-301 Administrative Topic Type Code Describe Activity to be performed (See Note)
(See Note)
Perform a Dilution calculation for a Unit Power change from 60-100% (2.1,43 Ability to use procedures to determine the A.1 CR,N effects on reactivity of plant changes, such as reactor coolant Conduct of Operations system temperature, secondary plant, fuel depletion, etc. (CFR:
41.10/43.6/45.6) IMPORTANCE RO 4.1 SRO 4.3 A.2 Perform 3-0SP-059.1O, Perform A QPTR Calculation. (2.2.12 Equipment Control CR,D Knowledge of surveillance procedures. (CFR: 41.10/45.13)
IMPORTANCE RO 3.7 SRO 4.1 Determine Allowable Stay Time & Determine Radiological Requirements for HCV-4-758 Surveillance. (2.3.7 Ability to A.3 CR,N comply with radiation work permit requirements during normal Radiation Control or abnormal conditions. (CFR: 41.12/45.10) IMPORTANCE RO 3.5 SRO 3.6)
IdentifY the correct CSF Priority based on Unit conditions.
A,4 - RO (2,4.22 Knowledge of the bases for prioritizing safety functions Emergency Plan CR,N during abnormal/emergency operations. (CFR: 41.7/41.10/
43.5/45.12) IMPORTANCE RO 3.6 SRO 4,4)
NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.
- Types and Codes (C) Control Room (S) Simulator (CR) Classroom (D)irect from bank (:'S3 for ROs, :'S4 for SROs)
(N)ew or (M)odified from bank (:::1)
(P)revious 2 Exams (:'S1 Randomly selected)
ES-301 Administrative Topics Outline Form ES-301-1 Facility: Turkey Point Units 3 & 4 Date of Examination: 2009 Exam Level: RO Operating Test Number: 2009-301 Administrative Topic Type Code Describe Activity to be performed (See Note)
(See Note)
Perform a Dilution calculation for a Unit Power change from 60-100% (2.1.43 Ability to use procedures to determine the A.I CR,N effects on reactivity of plant changes, such as reactor coolant Conduct of Operations system temperature, secondary plant, fuel depletion, etc. (CFR:
41.10/43.6/45.6) IMPORTANCE RO 4.1 SRO 4.3 1
A.2 Perform 3-0SP-059.1O, Perform A QPTR Calculation. (2.2.12 Equipment Control CR,D Knowledge of surveillance procedures. (CFR: 41.1 0/45.13)
IMPORTANCE RO 3.7 SRO 4.1 Determine Allowable Stay Time & Determine Radiological Requirements for HCV-4-758 Surveillance. (2.3.7 Ability to A.3 CR,N comply with radiation work permit requirements during normal Radiation Control or abnormal conditions. (CFR: 41.12/45.10) IMPORTANCE RO 3.5 SRO 3.6)
Identify the correct CSF Priority based on Unit conditions.
A.4-RO (2.4.22 Knowledge of the bases for prioritizing safety functions Emergency Plan CR,N during abnormal/emergency operations. (CFR: 41.7 /41.10/
43.5/45.12) IMPORTANCE RO 3.6 SRO 4.4)
NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.
- Types and Codes (C) Control Room (S) Simulator (CR) Classroom (D)irect from bank (::;3 for ROs, ::;4 for SROs)
(N)ew or (M)od ified from bank (;:, I )
(P)revious 2 Exams (::;1 Randomly selected)
ES-301 Administrative Topics Outline Form ES-301-1 Facility: Turkey Point Units 3 & 4 Date of Examination: 2009 Exam Level:
SRO (U) & (I)
Operating Test Number: 2009-301 Administrative Topic Type Code Describe Activity to be performed (See Note)
(See Note)
VerifY a Dilution calculation for a Unit Power change from 60-100% (2.1043 Ability to use procedures to determine the effects A.l.a CR,N on reactivity of plant changes, such as reactor coolant system Conduct of Operations temperature, secondary plant, fuel depletion, etc. (CFR: 4l.l0 /
43.6/ 4S.6) IMPORTANCE RO 4.1 SRO 4.3 Perform Review ofO-OSP-20S, Verification of Administratively Controlled Valves, Locks, and Switches (2.1.29 Knowledge of A.l.b CR,N how to conduct system lineups, such as valves, breakers, Conduct of Operations switches, etc. (CFR: 41.10/ 4S.1 / 4S.12) IMPORTANCE RO 4.1 SRO 4.0 Perform 3-0SP-OS9.1 0, Perform A QPTR Calculation. (2.2.12 A.2 CR,D Knowledge of surveillance procedures. (CFR: 41.10 /4S.13)
Equipment Control IMPORTANCE RO 3.7 SRO 4.1 Determine Allowable Stay Time & Determine Radiological Requirements for HCV 7S8 Surveillance. (2.3.7 Ability to A.3 CR,N comply with radiation work permit requirements during normal Radiation Control or abnormal conditions. (CFR: 4l.l2 / 4S.IO) IMPORTANCE RO 3.S SRO 3.6)
ClassifY Plant Event recommend PARS and complete SNF.
AA - SRO 204041 Knowledge of the emergency action level thresholds and Emergency Plan CR,M classifications. (CFR: 4l.l0 / 43.S / 4S.11) IMPORTANCE RO 2.9 SRO 4.6 NOTE: All items (S total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when S are required.
- Types and Codes (C) Control Room (S) Simulator (CR) Classroom (D)irect from bank ( ::;3 for ROs, :s:4 for SROs)
(N)ew or (M)odified from bank (~1)
(P)revious 2 Exams (::;1 Randomly selected)
ES-301 Administrative Topics Outline Form ES-301-1 Facility: Turkey Point Units 3 & 4 Date of Examination: 2009 Exam Level:
SRO (U) & (I)
Operating Test Number: 2009-301 Administrative Topic Type Code Describe Activity to be performed (See Note)
(See Note)
Verify a Dilution calculation for a Unit Power change from 60-100% (2.1,43 Ability to use procedures to determine the effects A.l.a CR,N on reactivity of plant changes, such as reactor coolant system Conduct of Operations temperature, secondary plant, fuel depletion, etc. (CFR: 41.1 0/
43.6/ 4S.6) IMPORTANCE RO 4.1 SRO 4.3 Perform Review ofO-OSP-20S, Verification of Administratively Controlled Valves, Locks, and Switches (2.1.29 Knowledge of A.l.b CR,N how to conduct system lineups, such as valves, breakers, Conduct of Operations switches, etc. (CFR: 41.10/ 4S.1 / 4S.12) IMPORTANCE RO 4.1 SRO 4.0 Perform 3-0SP-OS9.1 0, Perform A QPTR Calculation. (2.2.12
(
A.2 CR, D Knowledge of surveillance procedures. (CFR: 41.10/ 4S.13)
Equipment Control IMPORTANCE RO 3.7 SRO 4.1 Determine Allowable Stay Time & Determine Radiological Requirements for HCV 7S8 Surveillance. (2.3.7 Ability to A.3 CR,N comply with radiation work permit requirements during normal Radiation Control or abnormal conditions. (CFR: 41.12/ 4S.10) IMPORTANCE RO 3.S SRO 3.6)
Classify Plant Event recommend PARS and complete SNF.
A,4 - SRO 2,4,41 Knowledge of the emergency action level thresholds and Emergency Plan CR,M classifications. (CFR: 41.10/ 43.S / 4S.ll) IMPORTANCE RO 2.9 SRO 4.6 NOTE: All items (S total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when S are required.
- Types and Codes (C) Control Room (S) Simulator (CR) Classroom (D)irect from bank ( ::;3 for ROs, s:4 for SROs)
(N)ew or (M)odified from bank (2: 1)
(P)revious 2 Exams (::;1 Randomly selected)
ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility:
Turkey Point Date of Examination: 2009 Exam Level (circle one): RO Operating Test No.:
2009-Control Room Systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)
System / JPM Title Type Code*
Safety Function a
Respond to a Turbine Runback (Control Rods fail to insert).
A,N,S 1
b Pressurizer Level Transmitter fails Low N,S 2
c Align Safety Injection for Hot Leg Recirculation A, D, L, S 4(P) d Respond to a Source Range Nuclear Instrument Malfunction (MODE 6)
D,E,S 7
e Purging the PRT to Reduce Oxygen or Hydrogen M,S 5
f Initiate Containment Purge D,L,M,S 8
g Fill Accumulator N,S 3
h Perform EDG Normal Start Test.
A,M,S 6
In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U) i Post Accident Hydrogen Monitoring/Place U-4 Post Accident Hydrogen A,D,R,E 5
Monitor in service as an NSO in the Auxiliary Building.
j TRIP and RESET AFW Pump "A" T&T Valve, MOV-6459A N
4(S) k AC Electrical Distribution/Swap from 4B Normal (4Y02) to B SPARE (4Y04)
N 6
Inverter as an NSO.
All control room (and in-plant) systems must be different and 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 (E)mergency or abnormal in-plant
- 1/;
- :1/;::1 (L)ow-Power
- 1/;
- :1/;::1 (N)ew or (M)odified from bank including 1 (A)
- 2/;
- :2/;::1 (P)revious 2 exams
~ 3 / ~ 3/ ~ 2 (randomly selected)
(R)CA
- 1/;
- :1/;::1 (S)imulator
(
ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility:
Turkey Point Date of Examination: 2009 Exam Level (circle one): RO Operating Test No.:
2009-Control Room Systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)
System / JPM Title Type Code*
Safety Function a
Respond to a Turbine Runback (Control Rods fail to insert).
A,N,S 1
b Pressurizer Level Transmitter fails Low N,S 2
c Align Safety Injection for Hot Leg Recirculation A,D,L,S 4(P) d Respond to a Source Range Nuclear Instrument Malfunction (MODE 6)
D,E,S 7
e Purging the PRT to Reduce Oxygen or Hydrogen M,S 5
f Initiate Containment Purge D,L,M,S 8
g Fill Accumulator N,S 3
h Perform EDG Normal Start Test.
A,M,S 6
(
In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U) i Post Accident Hydrogen Monitoring/Place U-4 Post Accident Hydrogen A,D,R,E Monitor in service as an NSO in the Auxiliary Building.
5 j
TRIP and RESET AFW Pump "A" T& T Valve, MOV-6459A N
4(S) k AC Electrical Distribution/Swap from 4B Normal (4Y02) to B SPARE (4Y04)
Inverter as an NSO.
N 6
All control room (and in-plant) systems must be different and 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 (E)mergency or abnormal in-plant
- 1/;
- :1/;::1 (L)ow-Power
- 1/;
- :1/;::1 (N)ew or (M)odified from bank including 1 (A)
- 2/;
- :2/;::1 (P)revious 2 exams
~ 3 / :0; 3 / ~ 2 (randomly selected)
(R)CA
- 1/;
- :1/;::1 (S)imulator
(
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:
Turkey Point Date of Examination:
2009 Exam Level (circle one): SRO-I Operating Test No.:
2009-Control Room Systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)
System / JPM Title Type Code*
Safety Function a
Respond to a Turbine Runback (Control Rods fail to insert).
A,N,S 1
b Pressurizer Level Transmitter fails Low N,S 2
c Align Safety Injection for Hot Leg Recirculation A, D,L,S 4(P) d Respond to a Source Range Nuclear Instrumentation Malfunction (Mode 6)
D,E,S 7
e f
Initiate Containment Purge.
L,M,S 8
g Fill Accumulator N,S 3
h Perform EDG Normal Start Test.
A,M,S 6
In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U) i Post Accident Hydrogen Monitoring/Place U-4 Post Accident Hydrogen A,D,R,E 5
Monitor in service as an NSO in the Auxiliary Building.
j TRIP and RESET AFW Pump "A" T&T Valve, MOV-6459A N
4(S) k AC Electrical Distribution/Swap from 4B Normal (4Y02) to B SPARE (4Y04)
N 6
Inverter as an NSO.
All control room (and in-plant) systems must be different and 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 (E)mergency or abnormal in-plant
~1/~1/~1 (L)ow-Power
~1/~1/~1 (N)ew or (M)odified from bank including 1 (A)
~2/~2/~1 (P)revious 2 exams
=:;; 3 / =:;; 3 / =:;; 2 (randomly selected)
(R)CA
~1/~1/~1 (S)imulator ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility:
Turkel' Point Date of Examination:
2009 Exam Level (circle one): SRO-I Operating Test No.:
2009-Control Room Systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)
System / JPM Title Type Code*
Safety Function a
Respond to a Turbine Runback (Control Rods fail to insert).
A,N,S 1
b Pressurizer Level Transmitter fails Low N,S 2
c Align Safety Injection for Hot Leg Recirculation A, D, L, S 4(P) d Respond to a Source Range Nuclear Instrumentation Malfunction (Mode 6)
D,E,S 7
e f
Initiate Containment Purge.
L,M,S 8
g Fill Accumulator N,S 3
h Perform EDG Normal Start Test.
A,M,S 6
(
In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U) i Post Accident Hydrogen Monitoring/Place U-4 Post Accident Hydrogen A,D,R,E 5
Monitor in service as an NSO in the Auxiliary Building.
j TRIP and RESET AFW Pump "A" T&T Valve, MOV-6459A N
4(S) k AC Electrical Distribution/Swap from 4B Normal (4Y02) to B SPARE (4Y04)
N 6
Inverter as an NSO.
All control room (and in-plant) systems must be different and 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 (E)mergency or abnormal in-plant
~1/~1/~1 (L)ow-Power
~1/~1/~1 (N)ew or (M)odified from bank including 1 (A)
~2/~2/~1 (P)revious 2 exams
- <;; 3 / :<;; 3 / :<;; 2 (randomly selected)
(R)CA
~1/~1/~1 (S)imulator
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:
Turkey Point Date of Examination:
2009 Exam Level (circle one): SRO-U Operating Test No.:
2009-Control Room Systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)
System / JPM Title Type Code*
Safety Function a
Respond to a Turbine Runback (Control Rods fail to insert).
A,N,S 1
b c
Align Safety Injection for Hot Leg Recirculation A,D,L,S 4(P) d e
f Initiate Containment Purge.
L,M,S 8
g h
In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U) i Post Accident Hydrogen Monitoring/Place U-4 Post Accident Hydrogen A,D,R,E 5
Monitor in service as an NSO in the Auxiliary Building.
j TRIP and RESET AFW Pump "A" T&T Valve, MOV-6459A N
4(S) k All control room (and in-plant) systems must be different and 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 (E)mergency or abnormal in-plant
~1/~1/~1 (L)ow-Power
~1/~1/~1 (N)ew or (M)odified from bank including 1 (A)
~2/~2/~1 (P)revious 2 exams
~ 3 / ~ 3 / ~ 2 (randomly selected)
(R)CA
~1/~1/~1 (S)imulator ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2
(
Facility:
Turkey Point Date of Examination:
2009 Exam Level (circle one): SRO-U Operating Test No.:
2009-Control Room Systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)
System 1 JPM Title Type Code*
Safety Function a
Respond to a Turbine Runback (Control Rods fail to insert).
A,N,S 1
b c
Align Safety Injection for Hot Leg Recirculation A, D, L, S 4(P) d e
f Initiate Containment Purge.
L,M,S 8
g h
(
In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U) i Post Accident Hydrogen Monitoring/Place U-4 Post Accident Hydrogen A,D,R,E 5
Monitor in service as an NSO in the Auxiliary Building.
j TRIP and RESET AFW Pump "An T&T Valve, MOV-6459A N
4(S) k All control room (and in-plant) systems must be different and serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for RO 1 SRO-II SRO-U (A)lternate path 4-6/4-6/2-3 (C)ontrol room (D)irect from bank s9/s8/s4 (E)mergency or abnormal in-plant 2:1/2:1/2:1 (L)ow-Power 2:1/2:1/2:1 (N)ew or (M)odified from bank including 1 (A) 2:2/2:2/2:1 (P)revious 2 exams s 3 1 s 3 1 s 2 (randomly selected)
(R)CA 2:1/2:1/2:1 (S)imulator
ES-401 1 Rev. 9 PWR examination Outline Form ES-401-2 Facility: Turkey Point Date of Exam: Aug 2009 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 &
2 2
2 2
1 1
1 9
2 2
4 Abnormal Plant N/A N/A Evolutions TIer Totals 5
5 5
4 4
4 27 5
5 10 1
3 3
2 2
2 3
2 2
3 3
3 28 3
2 5
- 2.
2 1
1 1
1 0
1 1
1 1
1 1
10 2
1 3
Plant Systems Tier Totals 4
4 3
3 2
4 3
3 4
4 4
38 5
3 8
- 3. Generic Knowledge and Abilities 1
2 3
4 10 1
2 3
4 7
Categories 2
3 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., except for one category In TIer 3 of the SR().only outline, the "Tier Totals' In each KIA 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.
I
- 3.
Systemslevolutlons 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 I
not Included on the outline should be added. Refer to ES-401, Attachment 2, for guidance regarding I
the elimination of inappropriate KIA statements.
I
- 4.
Select topics from as many systems and evolutions as possible; sample every system or evolution I
In the group before selecting a second topic for any system or evolution.
I i
I
- 5.
Absent a plant-specific priority, only those KIAs having an Importance rating (lR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
I
- 6.
Select SRO topics for 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 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; 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 KIA catalog, and enter the KIA numbers, descriptions, IRs, and pointtotals (#) on Form ES-401-3. Limit SRO selections to KIAs that are linked to 10 CFR 55.43.
ES-401 1 Rev. 9 PWR examination Outline Form ES-401-2 Facility: Turkey Point Date of Exam: Aug 2009 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 &
2 2
2 2
1 1
1 9
2 2
4 Abnormal Plant N/A N/A Evolutions TlerTotals 5
5 5
4 4
4 27 5
5 10 1
3 3
2 2
2 3
2 2
3 3
3 28 3
2 5
- 2.
Plant 2
1 1
1 1
0 1
1 1
1 1
1 10 2
1 3
Systems Tier Totals 4
4 3
3 2
4 3
3 4
4 4
38 5
3 8
- 3. Generic Knowledge and Abilities 1
2 3
4 10 1
2 3
4 7
Categories 2
3 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., except for one category In Tler 3 of the SRQ-only outline, the 'Tier Totals' In each KIA 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/evolutlons within each group are Identified on the associated outline; systems or evolutions that do not apply at the facility should be dele tad 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 In the group before selecting a second topic for any system or evolution.
- 5.
Absenta plant-specific priority, only those KIAs 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 portlons, respectively.
- 6.
Select SRO topiCS for Tlers 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 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 from Section 2 of the KIA catalog, and enter the KIA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. LimltSRO selections to KIAs that are linked to 10 CFR 55.43.
ES-401, REV 9 T1G1 PWR EXAMINATION OUTUNE KA NAME I SAFETY FUNCTION:
IR Kl K2 K3 K4 K5 K6 Ai A2 A3 A4 G RO SRO
," 00BAA2.20 Pressurizer Vapor Space Accident 13 3.4 3.6 0 0 0 0 0 0 0 ~ 0 0 0
'(j
~..,) "".. EGZ:Z:3-Small Break LOCA 13
~ 2.,)'I'fI.{ I~ (22-/1 3.B 3.9 DDDDDDDDDD~
/;"1/ Oil EG2.1.7 01 Large Break LOCA 13 4.4 4.7 0 0 0 0 0 0 0 0 0 0 ~
J 015AK3.04 RCP Malfunctions I 4 3.1 3.2 0 0 ~ 00000000 ft)'22AA2.02 Loss of Rx Coolant Makeup I 2 3.2 3.7 0 0 0 0 0 0 0 ~ 0 0 0 r;:J025AK1.0l Loss of RHRSystem 14 3.9 4.3
~ 0 0 0 0 0 0 0 0 0 0 e
026AA1,07 Loss of Component Cooling Water IB 2.9 3
0 0 0 0 0 0 ~ 0 0 0 0 llJ 027AK1.03 Pressurizer Pressure Control System 2.6 2.9
~ 0 0 0 0 0 0 0 0 0 0 Malfunction 13 03BEA2.0B Steam Gen. Tube Rupture I 3 3.B 4.4 0 0 0 0 0 0 0 ~ 0 0 0 054AK1.01 Loss of Main Feedwater I 4 4.1 4.3
~ 0 0 0 0 0 0 0 0 0 0 G
055EK3.02 Station Blackout 16 4.3 4.6 0 0 ~ 0 0 0 0 0 0 0 0 Page 1 of2 FORM E5-401-2 TOPIC:
~E1iY~~k'i,=~~~~~ code safety, based on.'
Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.
Reduction of power to below the steady state power-to-flow limit pharging pump problerr's Loss of RHRS during aU modes of operation, Row rates to the components and systems that are serviced by the CCWS; interactions among the components Latent heat of vaporization/condensation t, ~i~9~.~,lternatives for placing plant In safe condition
'; when1:otlllehser is not avallabl~
MFW line break depressurizes the S/G (similar to a steam line brea~)
Actions contained in EOP for loss of oftsite and onsite power 212312009 12:56 PM ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G
,r',
OOBAA2.20
'(j (j) 011EG2.1.7
!'1~1 015AK3.04
~
4P"P22AA2.02 G/
c* 025AK1.01 e
026AA1.07
{ti 027AK1.03 03BEA2.0B 054AK1.01
(] 055EK3.02 RO SRO Pressurizer Vapor Space Accident 13 3.4 3.6 0 0 0 0 0 0 0 ~ 0 0 0 3.B 3.9 0 0 0 0 0 0 0 0 0 0 ~
Large BreakLOCA/3 4.4 4.7 0 0 0 0 0 0 0 0 0 0 ~
RCP Malfunctions/4 3.1 3.2 0 0 ~ 0 0 0 0 0 0 0 0 Loss of RxCoolant Makeup/2 3.2 3.7 0 0 0 0 DOD ~ 0 0 0 Loss of RHRSystem 14 3.9 4.3
~ 0 0 0 0 0 0 0 0 0 0 Loss of Component Cooling Water I B 2.9 3
0 0 0 0 0 0 ~ 0 0 0 0 Pressurizer Pressure Control System 2.6 2.9
~ 0 0 0 0 0 0 0 0 0 0 Malfunction I 3 Steam Gen. Tube Rupture 13 3.B 4.4 0 0 0 0 0 0 0 ~ 0 0 0 Loss of Main Feedwater I 4 4.1 4.3
~ 0 0 0 0 0 0 0 0 0 0 Station Blackout I 6 4.3 4.6 0 0 ~ 0 0 0 0 0 0 0 0 Page 1 of 2 FORM ES-401-2 TOPIC:
Th~ ~~~t of an open PORV on code safety. based on Observation of plant parameters Ability to evaluate plant performance and make operational judgments based on operating characteristics. reactor behavior and instrument interpretation.
Reduction of power to below the steady state power-to-flowlimil Charging pump problems Loss of RHRS during all modes of operation.
Flow rates to the components and systems that are serviced by the CCWS; interactions among the components Latent heat of vaporization/condensation
.' Yiable aHernatives for placing plant in safe condition
'. wnerfcondehser is not available MFW line break depressurizes the S/G (similar to a steam line break)
Actions contained in EOP for loss of offsite and onsile power 212312009 12:56 PM
ES-401, REV 9 KA NAME I SAFETY FUNCTION:
/'~
r;v rf~)
0' 056AG2.4.41 057AA1.04 r"1065AA1.01
~
/>**.WE04EK2.1
.'7
\\
V:;)WE05EK2.2
~
Loss of Off-site Power I 6 Loss of Vital AC Inst. Bus 16 Loss of Instrument Air I 8 LOCA Outside Containment 13 Inadequate Heat Transfer - Loss of Secondary Heat Sink I 4 T1G1 PWR EXAMINATION OUTLINE IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G RO SRO 2.9 4.6 0 0 0 0 0 0 0 0 0 0 ~
3.5 3.6 0 0 0 0 0 0 ~ 0 0 [J 0 2.7 2.5 0 0 0 0 0 0 ~ 0 0 0 0 3.5 3.9 0 ~ 0 0 0 0 0 0 0 0 0 3.9 4.2 0 ~ 0 ODD 0 0 0 0 0
,/~) WE11EK3.1 Loss of Emergency Coolant Recirc. 14 3.3 3.9 0 0 ~ 0 0 0 0 0 0 0 0 0'
(j) WE12EK2.2 Steam Une Rupture - Excessive Heat Transfer 14 3.6 3.9 0 ~ 0 0 0 0 0 0 0 0 0 Page 2 of 2 FORM ES-401-2 TOPIC:
. Knowledge of the emergency action level thresholds and classifications.
, Remote manual loaders Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.
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.
Facility operating characteristics during transient conditions, including coolant chemistry and the effects of temperature, pressure and reactivity changes and operating limitations and reasons for these operating characteristics.
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.
212312009 12:56 PM ES-401, REV 9 KA NAME I SAFETY FUNCTION:
056AG2.4.41 OS7AA1.04 r,' i 065AA 1.01
~
/~ *.WE04EK2.1
.'7
\\
f':jWEOSEK2.2
~
Loss of Off-site Power / 6 Loss of Vital AC Ins!. Bus / 6 Loss of Instrument Air / 8 LOCA Outside Containment / 3 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 T1G1 PWR EXAMINATION OUTLINE IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G RO SRO 2.9 4.6 0 0 0 0 0 0 0 0 0 0 ~
3.S 3.6 0 0 0 0 0 0 ~ 0 0 [J 0 2.7 2.5 0 0 0 0 0 0 ~ 0 0 0 0 3.S 3.9 0 ~ 0 0 0 0 0 0 0 0 0 3.9 4.2 0 ~ 0 0 0 0 0 0 0 0 0 WE11EK3.1 Loss of Emergency Coolant Recirc. / 4 3.3 3.9 DD~DDDDDDDD FORM ES-401-2 TOPIC:
. Knowledge of the emergency action level thresholds and classifications.
RWST and VCT valves Remote manual loaders Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.
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.
Facility operating characteristics during transient conditions, including coolant chemistry and the effects of temperature, pressure and reactivity changes and operating limitations and reasons for these operating characteristics.
(\\))
~W-E-1-2~E:-:K2-.-2--=S-te-a-m:-:U:-:'n-e-:::CR-up-Ct-ur-e---=Ex:-c-e-s-si:-ve--:-:H-ea-Ct--=3C":.6::---=3-=.9-=D=-:~~-=D=-=D=-:D~-=D=-=D=-:D~-=D=-:b-D---F-ac::iIi:-ty-:-'s-=h-e-at:--r-e-m-o-va-=l-s-ys-Cte-m-s-,-cin-c-:-lu-cd:-in-g-pC":ri-cm-a-ry---
(::f)'
Transfer / 4 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 of2 212312009 12:S6 PM
ES-401, REV 9 T1~2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
.,. -oGaAKe:tl:r-Dropped Contro, Rod 11 3.4 3.7 0 0 ~ 0 0 0 0 0 0 0 0 Turbine automatic runback with reactor in order to
~,4(j<o1' 11../-
~/,?/~
"'--:7ba::-la_nc_e_po_w_er_o_utp:-ut---,-:-~_-:--,---___
,*04AK3.01EmergencYBoration/14.14.4 0 0 ~ 0 0 0 0 0 0 0 0 When emergency boration is required o
- V
!':"7j028AG2.2.12
~
<@36AK1.03 h:0/59AA2.03 liY
@068AK2.02
<<l074EK1.0l t2/
Pressurizer Level Malfunction I 2 3.7 4.1 000000000 0 ~
Fuel Handling Accident I 8 4
4.3
~ 0 0 0 0 0 0 0 0 0 0 Accidental Uquid RadWaste ReI. 19 3.1 3.6 0 0 0 0 0 0 0 ~ 0 0 0 Control Room Evac. I 8 3.7 3.9 0 ~ 0 0 0 0 0 0 0 0 0 Inad. Core Cooling I 4 4.3 4.7
~ 0 0 0 0 0 0 0 0 0 0
~
',WE02EK2.1 SI Termination 13 3.4 3.9 0 ~ 0 0 0 0 0 0 0 0 0
~
. 1 \\ WE16EA 1.1 High Containment Radiation 19 3.1 3.2 0 0 0 0 0 0 ~ 0 0 0 0
}
Page 1 of 1 Knowledge of surveillance procedures.
Indications of approaching criticality t.Efiilijremodes;*~helrsvmntom~.~nrl.n1~~~Q~"Qf!:~"
lii\\1fil"aar*'*~nar*'*t**'*'**'**~J.i;*~*'t''al!~*'~llv**'*li%'fa"i#linit&r
!l ea ng. ca Icms.Q/lJUiL.Qll!\\i!.ye\\'Jqu Reactor trip system Methods of calculating subcooling margin Components and functions of control and safety systems, including instrumentation, Signals, interlocks, failure modes and automatic and manual features.
Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.
212312009 12:56 PM ES-401, REV 9 KA NAME I SAFETY FUNCTION:
-GOaAKS:tl3 Dropped Control Rod 11 I/)../-
¥/Zc/1 T1~2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.4 3.7 DD~DDDDDDDD FORM ES-401-2 TOPIC:
Turbine automatic runback with reactor in order to balance'power output ','
~n::j'D1'
'O 4-A-K-3-.0-1--~E-m-e~~-en-c-y~B~0-m~ti-on-/~1~--------~4.~1--4~.4--~-=~=-~~-=~=-~ ----'---,-,:-::---------:--~~--~-------------
o 0 ~ 0 0 0 0 0 0 0 0 When emergency boration is required o
'1/
~¥9AA2.03
<iY
@068AK2.02 074EK1.01
-'1,;
Pressurizer Level Malfunction 1 2 Fuel Handling Accident 1 8 Accidental Uquid RadWaste Rei. 19 Control Room Evac. 1 8 Inad. Core Cooling 1 4 3.7 4.1 DDDDDDDDDD~
4 4.3
~DDDDDDDDDD 3.1 3.6 DDDDDDD~DDD 3.7 3.9 D~DDDDDDDDD 4.3 4.7
~DDDDDDDDDD
-:-:-::::-:-:-=-----::-:-=--:--~-:-::-----------.------..
~
r;,.,"WEll2EK2" 1 SlTe~;MIiM 13 a4 3J! D Oil D D D D D D D D D A 'WE16EA 1.1 High Containment Radiation J 9 3.1 3.2 0 0 0 0 0 0 ~ 0 0 0 0
}'
Page 1 of 1 Knowledge of surveillance procedures.
Indications of approaching criticality Reactor trip system Methods of calculating subcooling margin Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.
Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.
212312009 12:56 PM
ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
RO SRO 2.6 2.5 DDDDDDDD~DD Motor current I~ Reactor Coolant Pump
<bf;J5.4 $,'-"3
. I
/1",.-. :;-/If/o4 Q
003A4.0S 0 r Reactor Coolant Pump 3.1 3.0 0 0 0 0 0 0 0 0 0 ~ 0 RCP seal leakage detection Instrumentation Chemical and Volume Control 3.1 3.S 0 0 0 0 0 ~ 0 Q 0 0 0 4K6.31
-*,0 Seal injection system and limits on flow range 00SA4.0S Residual Heat Removal 2.B 2.8 0 0 0 0 0 0 0 0 0 ~ 0 Position -ofRWSTrecirculation valve (locked when not in D..
use, continuously monitored when in use).
cJt
.~---~-.-&----E-m-e-~-e-nc-y~Co-r-e~C-oo~lin-g---------4-.2---4.-3~D=-D=-D~~D~D=-D=-D=-~D~~=-D=-D=---~-~o'~c~
.. ~
... ~'~~-R"~
- =*,'~**~**=***=".=c~~.~.~.. ~.=~~=*k=g~.--------
Q ('{itA 7. 0 $'" /lvt..,It c 11
/"07'.)
~ 006K6.02 Emergency Core Cooling 3.4 3.9 0 0 0 0 0 ~ 0 0 0 0 0 Core flood tanks (accumulators) o
~."'"
~007G2.2.40
/~)
0Y 00BK4.07
~-., 010K2.04 Pressurizer Relief/Quench Tank Component Cooling Water Pressurizer Pressure Control 3.4 4.7 0 0 0 0 0 0 0 0 0 0 ~
2.6 2.7 0 0 0 ~ 0 0 0 0 0 0 0 2.7 2.9 0 ~ 0 0 0 0 0 0 0 0 0 Ability to apply technical specifications for a system.
Operation of the CCW swing-bus power supply and its associated breakers. and controls Indicator for code safety position
--~----~~--~~----~~~----~~~~~-=~~~~~~~=-~~-=~--~--~~----~~~--------------~
~)
010K4.02 Pressurizer Pressure Control 3.0 3.4 0 0 0 ~ 0 0 0 00 0 0 Prevention of uncovering PZR heaters 0/
()} 012Kl.ll2 Reactor Protection 3.4 3.7
~ 0 0 0 0 0 0 0 0 0 0 12SV dc system Page 1 ot3 212312009 12:56 PM ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION:
IR K1 K2 K3 K4 KS K6 A 1 A2 A3 A4 G TOPIC:
-3A~ Reactor Coolant Pump 2.6 2.S 0 0 0 0 0 0 0 0 ~ 0 0 Motor current
<t£7~4s,o"3.
1/v0- Shf/t!1
~------~~~~------------~--~-=~~~~~-=~--=-~-=----~~-------------------------------
Reactor Coolant Pump 3.1 3.0 0 0 0 0 0 0 0 0 0 ~ 0 RCP seal leakage detection Instrumentation c' 003A4.0S 7-, oi 0'
1":~'Oq4K6.31
~}
Chemical and Volume Control 3.1 3.S 0 0 0 0 0 ~ 0 [J 0 0 0 Seal injection system and limits on flow range
---=--=:=--------_._--_._------
005A4.0S Residual Heat Removal 2.8 2.8 0 0 0 0 0 0 0 0 0 ~ 0 Position of RWST recirculation valve (locked when not in
@ ________________________________________ -::::-_=:-:-=-=--=-==-==-==--=-==-==---.".u,.,.,s,...e-. co n,...tin..."UO.""..,USI Y
monitored when in use). ".,-______ __
- --OO6A3:O&
Emergency Core Cooling 4.2 4.3 0 0 0 0 0 0 0 0 ~ 0 0
() cr:(-.,.....,.!J.....,..,7..,...,.C_S_--=-Ih_--_L _¥-:=-/_l-:=-c--:fi:--'l ___
-::-:---=-=--=-=-==-=:-=--=-==-==-=--=-:=----::---::--:-:---:--:-_-:----:--____
@006K6.02 Emergency Core Cooling 3.4 3.9 0 0 0 0 0 ~ 0 0 0 0 0 Core flood tanks (accumulators)
~007G2.2.40 Pressurizer Relief/Quench Tank 00BK4.07 Component Cooling Water
~_' 010K2.04 Pressurizer Pressure Control
/~') 010K4.02 (2)
Pressurizer Pressure Control
(];J 012Kl.02 Reactor Protection 3.4 4.7 0 0 0 0 0 0 0 0 0 0 ~
2.6 2.7 DDD~DDDDDDD 2.7 2.9 0 ~ 0 0 0 0 0 0 0 0 0 3.0 3.4 0 0 0 ~ 0 0 0 0 0 0 0 3.4 3.7
~ 0 0 0 0 0 0 0 0 0 0 Page 1 of 3 Ability to apply technical specifications for a system.
Operation of the CCW swing-bus power supply and its associated breakers. and controls Indicator for code safety poSition Prevention of uncovering PZR heaters 125V dc system 2123/2009 12:56 PM
ES-401, REV 9 T2Gl PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION:
IH Kl K2 K3 K4 K5 K6 A 1 A2 A3 A4 G TOPIC:
RO SRO ffij012K2.01 Reactor Protection' 3.3 3.7 0 ~ 0 0 0 0 0 0 0 0 0 RPS channels, components and interconnections
~
013A2.01 E"",,,,,,red Sa1e~ Fee"'" _.000 4.6 4.8 0 0 0 0 0 0 0 Ii1I 0 0 0 LOCA Q022K1.04 Containment Cooling C)022K3.02
\\&1 Containment Cooling
@26A3.01 Containment Spray
- -~~9Al.05
~
Main and Reheat Steam 1/,') 039G2.4.45 W'
Main and Reheat Steam 059K3.03 Main Feedwater
@61IG.02 Auxiliary/Emergency Feedwater
{!l/62Kl.02 AC Electrical Distribution
~;063A4.02 DC Electrical Distribution 2.9 2.9
~ 0 0 0 0 0 0 0 0 0 0 3.0 3.3 0 0 ~ 0 0 0 0 0 0 0 0 4.3 4.5 0 0 0 0 0 0 0 0 ~ 0 0 3.2 3.3 0 0 0 0 0 0 ~ 0 0 0 0 4.1 4.3 0 0 0 0 0 0 0 0 0 0 ~
3.5 3.7. 0 0 ~ 0 0 0 0 0 0 0 0 3.2 3.6 0 0 0 0 ~ 0 0 0 0 0 0 4.1 4.4
~ 0 0 0 0 0 0 0 0 0 0 2.8 2.9 0 0 0 0 0 0 0 0 0 ~ 0 Page 2 of3 Chilled water Containment instrumentation readings Pump starts and correct MOV positioning RCS T-ave Ability to prioritize and interpret the significance of each annunciator or alarm.
SlGS Decay heat sources and magnitude ED/G Battery voltage indicator 212312009 12:56 PM ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION:
IH K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
/~012K2.01
\\2:/
Reactor Protection' 3.3 3.7 D ~ D D D D D D D D D RPS channels, components and interconnections
~~~--~~~~~~--~~--~~~~~~~~~~~~~~=-~~~--------------------.------
~
013A2.01 Engineered Safety Features Actuation 4.6 4.8 DOD D D D D ~ D D D LOCA
~022K1.04 Ci022K3.02
~
(~26A3.01 2;
f*~19A1.05
~
!/)
039G2.4.45 (J;Y 059K3.03 Containment Cooling Containment Cooling Containment Spray Main and Reheat Steam Main and Reheat Steam Main Feedwater Auxiliary/Emergency Feedwater AC Electrical Distribution DC Electrical Distribution 2.9 2.9
~ D D D D D D D D D D 3.0 3.3 D D ~ D D D D D D D D 4.3 4.5 D D D D D DOD ~ D D 3.2 3.3 D D D D D D ~ D D D D 4.1 4.3 D D D D D D D D D 0 ~
3.5 3.7. D D ~ D D D D D D D D 3.2 3.6 D D D 0 ~ D DOD D D 4.1 4.4
~ D D D D D D D D D D 2.8 2.9 D D D D D D D D D ~ D Page 2 of3 Chilled water Containment instrumentation readings Pump starts and correct MOV positioning RCS T-ave Ability to prioritize and interpret the significance of each annunciator or alarm.
SlGS Decay heat sources and magnitude ED/G Battery voltage indicator 212312009 12:56 PM
ES-401, REV 9 KA NAME I SAFETY FUNCTION:
t;;,;)064G2.2.42 ti9
/~064K6.08
~
@)
.~ 073KS.01
,.-l..
~
r&'00A,.0'
/)
Emergency Diesel Generator Emergency Diesel Generator Process Radiation Monitoring Service Water Instrument Air Containment T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 KS K6 A1 A2 A3*A4 G RO SRO 3.9 4.6 0 0 0 0 0 0 0 0 0 0 ~
3.2 3.. 3 DDDDD~DDDDD 2.S 3.0 DDDD~DDDDDD 3.S 3.7 0 0 0 0 0 0 0 ~ 0 0 0 3.3 3.S D~DDDDDDDDD 3.7 4.1 0 0 0 0 0 0 ~ 0 0 0 0 Page 30'3 FORM E8-401-2 TOPIC:
Ability to recognize system parameters that are entry-level conditions for Technical Specifications Fuel oil storage tanks Radiation theory, including sources, types, units and effects LossofSWS Emergency air compressor Containment pressure, temperature and humidity 212312009 12:S6 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:
./Iv @
064G2.2.42
.j-,
')
(J
~
064K6.08
,-\\
,s.
"---',073K5.01 (0) 0.. ' 076A2.01 --
Emergency Diesel Generator Emergency Diesel Generator Process Radiation Monitoring Service Water T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3* A4 G RO SRO 3.9 4.6 DDDDDDDDDD~
3.2 3.3 DDDDD~DDDDD 2.5 3.0 DDDD~DDDDDD 3.5 3.7 DDDDDOD~DDD FORM ES-401-2 TOPIC:
Ability to recognize system parameters that are entry-level conditions for Technical Specifications Fuel oil storage tanks Radiation theory, including sources, types, units and effects Loss of SWS
~-
~
~07~8~K2~.0~2--~I~n~st-ru-m-e-nt-A~i-r----------------3~.3~~3~.5~~D~~~~D~D~[]-D--tJ=-~D~D=-~D~D=----=Ern--er-g-en-c-y-a~ir-co-m-p-r-es-s-or--------------------
"'~ ~
'7 0.;) 103A1.01 o
Containment 3.7 4.1 DDDDDD~DDDD Containment pressure, temperature and humidity Page 3 of 3 212312009 12:56 PM
ES-401, REV 9 T2G2 PWR EXAMINATION OUTLINE KA NAME I SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO Pressurizer Level Control 2.5 2.8 0 0 0 0 0 ~ 0 0 DO 0 FORM ES-401-2 TOPIC:
Correlation of demand signal indication on charging pump flow valve controller to the valve position (j) 01106.06
~?16G2.4.3
.. ---.---.---::--------::-::----:--=---=:-=::c-::=_=_-=-==-=~=_=__==_=::__-_:_:_::c____:__,___:_::_--_:_----__,_----
Non-nuclear Instrumentation 3.7 3.9 0 0 0 0 0 0 0 0 0 0 ~
Ability to identify post-accident instrumentation.
~
/i'j.
029A2.03
~
/!' 033A 1.01
/(tt)
(:/
Containment Purge 2.7 3.1 000000 0 ~ ODD Spent Fuel Pool Cooling 2.7 3.3 0 0 0 0 0 0 ~ 0 0 0 0 Startup operations and the associated required valve lineup~
Spent fuel pool water level
~--------------------~~~=-=-~~~-
Steam Generator 2.7 2.8 0 0 0 0 0 0 0 0 0 ~ 0 Fill of dry S/G 035A4.02 (9
Main Turbine Generator 2.5 2.8 0 0 0 ~ 0 0 0 0 0 0 0 Impulse pressure mode control of steam dumps r" 045K4.44
,,-'-': " 055K3.01-Condenser Air Removal
/ ty"7,r lif. '.~. ~ Liquid Radwaste Ii'
'OL?~ A '?t2 I~ ¥/ttl?
2.5 2.7 0 0 ~ 0 0 0 0 0 DOD Main condenser 2.5 2.4 0 0 0 0 0 0 0 0 ~ 0 0
~~~~!~;~Q!fq'ii~l (J
~) 072K1.04 Area Radiation Monitoring 3.3 3.5
~ 0 0 0 0 0 0 0 0 0 0 Control room ventilation
!,\\;
-.l
?1l75K2.03 If'
~
/,/
Circulating Water 2.6 2.7 0 ~ 0 0 0 0 0 0 0 0 0 Emergency/essential SWS pumps Page 1 of 1 212312009 12:56 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:
Pressurizer Level Control T2G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 2.5 2.8 0 0 0 0 0 ~ 0 0 DO 0 FORM ES-401-2 TOPIC:
Correlation of demand signal indication on charging pump flow valve controller to the valve position
.--------.--:-:-:--------=:-=--=-:::--=:-=~=_=__=__==_=~=_=__==_==__-_:_:_:c::c__,__:_:__:_::_--_:_:_-:__--__:_----
Non-nuclear Instrumentation 3.7 3.9 0 0 0 0 0 0 0 0 0 0 ~
Ability to identify post-accident instrumentation.
@)
_._029A2.03
/"6
'7 Containment Purge 2.7 3.1 0 0 0 0 0 0 0 ~ 0 0 0 Spent Fuel Pool Cooling 2.7 3.3 0 0 0 0 0 0 ~ 0 0 0 0
/;'4 033A1.01 0j)
,{,
~.. ; 5-A-4.-02---=-St-e-am--::"G-en-e-ra-to-r--------=-2.-=-7---=2-::.8-O=--=O~O=-O=--=O=-:O= 0 0 0 ~ 0 Main Turbine Generator 2.5 2.8 0 0 0 ~ 0 0 0 0 0 0 0 Area Radiation Monitoring 3.3 3.5
~ 0 0 0 0 0 0 0 0 0 0 Circulating Water 2.6 2.7 0 ~ 0 0 DO 0 0 0 0 0 Page 1 of 1 Startup operations and the associated required valve Iineup$
Spent fuel pool water level Fill of dry S/G Impulse pressure mode control of steam dumps Main condenser Control room ventilation Emergency/essential SWS pumps 212312009 12:56 PM
ES-401, REV 9 T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
HO SRO G
"G2.1.21 I
,I
- .r
- 1 Conduct of operations 3.5 3.6 0 0 0 0 0 0 0 0 0 0 ~
Ability verify the control/ed procedure copy.
Conduct of operations 2.5 3.4 0 0 0 0 0 0 0 0 0 0 ~
Knowledge of new and spent fuel movement procedures
((01
~
G2.1.42
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~=-~~-=~~~~~~~~~~~~~--~~~~---
-.J.
G2.2.11 Equipment Control 2.3 3.3 0 0 0 0 0 0 0 0 0 0 ~
Knowledge of the process for controlling temporary L
Q 0 design changes.
Equipment Control 3.6 3.6 0 0 0 0 0 0 0 0 0 0 ~
(multi-unit) Ability to explain the vanations in control board layouts, systems, instrumentation and procedural actions between units at a facility.
(j}G2 24 G9
~'\\-G-2.-2-.44-------E-qU-i-pm--en-t~C-o-n-tro-I--------------~4~.2~4~.~4--=D~D=-~D=-D=-~D=-~D=-D=-~D=-~D=-D=-~~=---~Ab~i=lity--ro-i~n-te-~-re-t-co--nt-ro~l-roo--m-i~n~di-~-t~io-ns--to-v-e~nfy~th~e----
(/Ij);;' )
status and operation of a system, and understand how operator actions and directives affect plant and system conditions Radiation Control 3.8 4.3 DDDDDDDDDD~
Ability to control radiation releases.
/~G2.3.11 Cj,Y Radiation Control 3.4 3.8 nnnnnDDDDD~
~~~~~~~~~~--~~~----~~~~~-=~~=-~~
"'---', G2.3.13 Radiation Control 3.4 3.8 0 0 0 0 Don n n
n
~
Knowledge of radiological safety procedures pertainina to W
Emergency Procedures/Plans 4.5 4.6 2.4.45 Emergency Procedures/Plans 4.1 4.3
'2.4.6 Emergency Procedures/Plans 3.7 4.7 DDDDDDDDDD~
DDDDDDDDDD~
DDDDDDDDDD~
Page 1 of 1 Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.
Ability to prioritize and interpret the signifi~nce of each annunciator or alarm.
Knowledge symptom based EOP mitigation strategies.
212312009 12:56 PM ES-401, REV 9 KA NAME I SAFETY FUNCTION:
G G2.1.21 1
i r '
Conduct of operations G2.1.42 Conduct of operations G2.2.11 Equipment Control T3 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G R,O SRO 3.5 3.6 0 0 0 0 0 0 0 0 0 0 ~
2.5 3.4 DDDDDDDDDD~
2.3 3.3 0 0 0 0 0 0 0 0 0 0 ~
FORM ES-401-2 TOPIC:
Ability verify the controlled procedure copy.
Knowledge of new and spent fuel movement procedures Knowledge of the process for controlling temporary design changes.
@\\1'I
',\\-
_G_2_.2_.4 _______
E_q_ui_pm __
en_t_C_o_n_tro_ _______________
3_.6 ___
3._6 __ ~D~D--~D=_=D
__ D~~D=_~D
__ D=_~D=_D=-~~=_--~(m~u~lt-i--un-i~tl-A_b_ili_ty_to __
ex_p~la-in--th-e~v~an-a-ti-o-nS-i-n-c-on-tr-o_1 ____ _
v board layouts, systems, instrumentation and procedural actions between units at a facility.
?f[)\\G2.2.44EquiPmentControI4.24.4 D 0 0 0 0 0 0 0 0 0 ~
Ability to interpret control room indications to verify the fI: In )
status and operation of a system, and understand how operator actions and directives affect plant and system conditions Radiation Control 3.8 4.3 0 0 0 0 0 0 0 0 0 0 ~
Ability to control radiation releases.
nG2.3.11 elY
- -;-)
-=G,.-::2~.3~.1:-:3,-----=R~a--:di,----a-::-tio-n-C=-0-n-:-tr-o:-1 ---------------:3:-.4:---::3-=.8,--;:::D~D=---;:D::::--;:::D~D=---;:D::::--;:::D~D=---;:D::::-:=D:::---;~=---~K;--no-w~l:-ed-:-g-e-o-;-f-ra-d;:-io--;-lo-g-:-ic-a-:-1 s-a-;-fe--:ty--p~-o-ce-d-:-u-re-s-p-e-:rt-ai;--n:-in-g--;-to--
licensed operator duties Emergency Procedures/Plans 4.5 4.6 0 0 0 0 0 0 0 0 0 0 ~
Emergency Procedures/Plans 4.1 4.3 0 0 0 0 0 0 0 0 0 0 ~
Emergency Procedures/Plans 3.7 4.7 0 0 0 0 0 0 0 0 0 0 ~
Page 1 of 1 Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.
Ability to prioritize and interpret the significance of each annunciator or alarm.
Knowledge symptom based EOP mitigation strategies.
212312009 12:56 PM
ES-401, REV 9 SRO T1G1 PWR EXAMINATION OUTLINE KA NAME I SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 69 007EG2.4A1
~)009EA2.20 Reactor Trip - Stabilization - Recovery 2.9 4.6 0 0 0 0 0 0 0 0 0 0 ~
11 Small Break LOCA 1 3 2.6 2.9 0 0 0 0 0 0 0 ~ 0 0 0 C!/
~).22AA2.01
~)
Loss of Ax Coolant Makeup 1 2 3.2 3.8 0 0 0 0 0 0 0 ~ 0 0 0 Loss of Vital AC Inst. Bus 1 6 3.3 3.5 ooooooo~ooo
~.
'c,.
057AA2.",
W Loss of Emergency Coolant Recirc. 14 4.2 4.4 oooooooooo~
a we12EG2.4.5 Steam Une Rupture - Excessive Heat o
Transfer 14 4.2 4.0 0 0 0 0 0 0 0 0 0 0 ~
Page 1 of 1 FORM ES-401-2 TOPIC:
Knowledge of the emergency action level thresholds and classifications.
Containment vent damper position indicator Whether charging line leak exists Valve indicator 01 charging pump suction valve from RWST Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.
212312009 12:56 PM ES-401, AEV 9 KA NAME! SAFETY FUNCTION:
@ 007EG2.4.41
~.)009EA2.20 C!/
Cv"""~22AA2.01 CV' Reactor Trip - Stabilization - Recovery
/1 Small Break LOCA / 3 Loss of Ax Coolant Makeup / 2 Loss of Vital AC Ins!. Bus / 6 SAO T1G1 PWA EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 2.9 4.6 DDDDDDDDDD~
2.6 2.9 DDDDDDD~DDD 3.2 3.8 DDDDDDD~DDD 3.3 3.5 DDDDDDD~DDD FOAM ES-401-2 TOPIC:
Knowledge of the emergency action level thresholds and classifications.
Containment vent damper position indicator Whether charging line leak exists Valve indicator of charging pump suction valve from RWST 1Lo we11EG2.2.4
~
057AA2.07 Loss of Emergency Coolant Recirc. / 4 4.2 4.4
-.--.-----=-=----:-~--:--:-:-----:----:----:--::---:-----:---:---
o 0 0 0 0 0 0 0 0 0 ~
Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions "10 a
we12EG2.4.5 Steam Une Rupture - Excessive Heat o
Transfer /4 4.2 4.0 0 0 0 0 0 0 0 0 0 0 ~
Page 1 of 1 Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.
212312009 12:56 PM
ES-401, REV 9 KA NAME I SAFETY FUNCTION:
/':') 003AG2.4.47 Dropped Control Rod/1 W @
028AA2.01
~
"' 036AA2.02
'~.
,,~~ 068AG2.4.20 Pressurizer Level Malfunction / 2 Fuel Handling Accidentl 8 Control Room Evac. / 8 SRO T1G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 42'4.2 DDDDDDDDDD~
3.4 3.6 0 0 0 0 0 0 0 ~ 0 0 0 3.4 4.1 0 0 0 0 0 0 0 ~ 0 0 0 3.8 4.3 0 0 0 0.0 0 0 0 0 0 ~
Page 1 of 1 FORM ES-401-2 TOPIC:
Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material *
- PZR level indicators and alarms Occurrence of a fuel handling incident Knowledge of operational implications of EOP warnings, cautions and notes.
212312009 12:56 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:
6Y 003AG2.4.47 Dropped Control Aodl1 r::iJ 028AA2.01 Pressurizer Level Malfunction 12 SRO T1 G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G AO SAO 4.2 *4.2 DDDDDDDDDD~
3.4 3.6 DDDDDDD~DDD FORM ES-401-2 TOPIC:
Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.
, PZA level indicators and alarms
~
~------~~~~--~~~--------~~~~~-=~=-~~~~~=-~~-=~--~----~------~---------
036AA2.02 Fuel Handling Accident j 8 3.4 4.1 0 0 0 0 0 0 0 ~ 0 0 0 Occurrence of a fuel handling incident
~.'~ 068A02.4.20 09 Control Aoom Evac. I 8 3.8 4.3 DDDD*DDDDDD~
Knowledge of operational implications of EOP warnings, cautions and notes.
Page 1 of 1 212312009 12:56 PM
ES-401, REV 9 KA NAME I SAFETY FUNCTION:
~005A2~
Residual Heat Removal Component Cooling Water "012G2.1.27 Reactor Protection t:A\\ 039A2.03
~
Main and Reheat Steam
@ 002AZ15 AC Electrical Distribution SRO T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 2.9 2.9 0 tJ 0 0 0 0 0 ~ 0 0 0 3.8 4.0 0 0 0 0 0 0 0 0 0 0 ~
3.9 4
0 0 0 0 0 0 0 0 0 0 ~
3.. 4 3.7 0 0 0 0 0 0 0 ~ 0 0 0 2.8 3.2 DDDDDDD~DDD Page 1 of 1 FORM ES-401-2 TOPIC:
RHR valve malfunction Knowledge of local auxiliary operator tasks during emergency and the resultant operational effects Knowledge of system purpose and or function.
Indications and alarms for main steam and area radiation monitors (during SGTR)
Consequence of paralleling out-of-phaselmismatch in volts 212312009 12:56 PM ES-401, REV 9 SRO T2Gl 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 G9~M Residual Heat Removal 2.9 2.9 0 tJ 0 0 0 0 0 ~ 0 0 0 RHR valve malfunction 00BG2.4.35 Component Cooling Water 3.B 4.0 0 0 0 0 0 0 0 0 0 0 ~
Knowledge of local auxiliary operator tasks during
~
______________ ~ __ ~ ______________ ~~~ __ ~~~~~~~~~~~-=~=-__ ~e~m_e_rg~e~~_y_a~n_d_fu~e_re su_I~_n_t_o_pe_r7m_io~n~al_e~ff_ec_t_s ____ ___
n)12G2.1.27 Reactor Protection 3.9 4
0 0 0 0 0 0 0 0 0 0 ~
Knowledge of system purpose and or function.
t:A\\ 039A2.03
~
Main and Reheat Steam
@O_15 AC Electrical Distribution 3.4 3.7 0 0 0 0 0 0 0 ~ 0 0 0 2.B 3.2 0 0 0 0 0 0 0 ~ 0 0 0 Page 1 of 1 Indications and alarms for main steam and area radiation monitors (during SGTR)
Consequence of paralleling out-of-phaselmismatch in volts 212312009 12:56 PM
(§~H~
~'A2.06
~79A201
~.
NAME I SAFETY FUNCTION:
Liquid Radwaste Waste Gas Disposal Station Air SRO T2G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G RO SRO 3.8 4.0 0 0 0 0 0 0 0 0 [j 0 ~
2.4 2.S 0 0 0 0 0 0 0 ~ 0 0 0 2.9 3.2 0 0 0 0 0 0 0 ~ 0 0 0 Page 1 of 1 FORM ES-401-2 TOPIC:
Ability to explain and apply all system limits and precautions.
Supply failure to the isolation valve
~~~~~"o.oVt/ith
.. IAS:t,'it~l~i 212312009 12:S6 PM ES-401, REV 9 SRO T2G2 PWR EXAMINATION OUTLINE KA NAME I SAFETY FUNCTION:
IR K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G RO SRO Liquid Radwaste 3.8 4.0 0 0 0 0 0 0 0 0 [j 0 ~
Waste Gas Disposal 2.4 2.S 0 0 0 0 0 0 0 ~ 0 0 0 Station Air Page 1 of 1 FORM ES-401-2 TOPIC:
Ability to explain and apply all system limits and precautions.
Supply failure to the isolation valve 212312009 12:S6 PM
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
Conduct of operations
.( L1 SRO T3 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 4.3 4.3 0 0 0 0 0 0 0 0 0 0 ~
FORM ES-401-2 TOPIC:
Ability to identify and interpret diverse indications to validate the response of another indication (82-2.1.45
~----~--~---------------------------------------------------------
Q'"') G2.2.39 Equipment Control 3.9 4.5 0 0 0 0 0 0 0 0 0 0 ~
0/'
KnOwledge of less than one hour technical specification action statements for systems.
G2.2.5 Equipment Control 2.2 3.2 0 0 0 0 0 0 0 0 0 0 ~
Knowledge of the process for making design or operating changes to the facility
~~~--~~~~~~------------~~~~~~~~~~~~~~~~~~--~~~~~~----~~--~-----------
G2.3.15 Radiation Control 2.9 3.1 0 0 0 0 0 0 0 0 0 0 ~
Knowledge of radiation monitoring systems
~----~----~~~~~~~~~----
~2.3.5 R,dl,lIon Coowl Z9 2.9 0 0 0 0 0 0 0 0 0 0.,
A'uty..... m""'lIon moo"",", ',..,m'
~ G2.4.14 Emergency Procedures/Plans 3.8 4.5 0 0 0 0 0 0 0 0 0 0 ~
Knowledge of general guidelines for EOP usage.
~
~G2.4.27 Emergency Procedures/Plans 3.4 3.9 0 0 0 0 0 0 0 0 0 0 ~
Knowledge of 'fire in the plant' procedures.
Page 1 of 1 212312009 12:56 PM ES-401, REV 9 SRO T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
~.
"(. ~.
2_.'-,-1...".45,,---_---::C:-o_n:-du_c_t O_f-:o:-
p
_er_at-,io_n_s _____
---::4:-:.3:----:-4.-::-3_
0
=--=O=-O::::--::O=-=O:--::O=-=O:--::O=--=O=--O=-_~ __
--,Ac-b_ili_ty_tO_id_en-:-tify and interpret diverse indications to
~
validate the response of another indication Q,
'1,-.;"",
"'J' G2.2.39 Equipment Control 3.9 4.5 0 0 0 0 0 0 0 0 0 0 ~
Knowledge of less than one hour technical specification l5J action statements for systems.
G2.2.5:----E=q-u-=-ip-m-e-n-t C=0-n-tr-ol:--------2=-.2-=---=3:-:.2:---=O=--=O=--=O=--=O=--=O=-O=--=O=-O=--=O=-=O:--::~::::---K:c:n-o-w-Ied--:-ge-o---,f:-th:-e-p-roc-e-ss-f:-o-r m-ak""'in-g-dC-e-s-ig-n -or-o-p-e-ra-tin-g-
~
________ ~
__________,..,---,_-==-=~=--::::-~-=:--::=-::::--==-=:--::=-__
c:c:h_a_ng_e_s_to_th_e_fa~c_ility:--__________ _
G2.3.15 Radiation Control 2.9 3.1 0 0 0 0 0 0 0 0 0 0 ~
Knowledge of radiation monitoring systems
~~~~~--~~~~~~~~~----
~-::-2'_3-c'5~_---::R~a_d_ia_tio_n_c_o=n_tr_0_1 :---=~ ___ ---::2:-'9:---:2-='9:--[]_O O_O O_O_-::O=-O
__ O=--=O_~
A_b_il_ity_t_o_u_se_m_d_ia_tio_n_m_o_n_ito_r_in_g_s_ys_te_m_s _____ _
G24 14 Emergency Procedures/Plans 3.8 4.5 0 0 0 0 0 0 0 0 0 0 ~
Knowledge of general guidelines for EOP usage.
~
~~:----=-----=-~--~------~~~~~~~~~~~~~~~--~~~~~~~~--~.--------
~
G2.4.27 Emergency Procedures/Plans 3.4 3.9 0 0 [] 0 0 0 0 0 0 0 ~
Knowledge of 'fire in the plant' procedures.
Page 1 of 1 212312009 12:56 PM