ML061560137: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
 
Line 15: Line 15:


=Text=
=Text=
{{#Wiki_filter:ES-301 Administrative Topics Outline Form ES-30 1-1 Facility:
{{#Wiki_filter:ES-301                               Administrative Topics Outline                     Form ES-301-1 Facility:     Callaway                                 Date of Examination:         8/22/2005 Examination Level (circle one):       RO               Operating Test Number:       NRC Administrative Topic             Type                  Describe activity to be performed (see Note)               Code*
Callaway Date of Exa m ination: 8/22/2005 Exa m ination Level (circle one):
JPM: Perform a QPTR Calculation.
RO Operating Test Number:
Conduct of Operations             D,R K/A: 2.1.32 (3.4)
NRC Administrative Topic (see Note)
Ability to explain and apply all system limits and precautions JPM: Calculate blended makeup volume and flow to Conduct of Operations             N,R             the RWST.
Type Code* Describe act i vity to be performed JPM: Perform a QPTR Calculation.
K/A: 2.1.25 (2.8)
Conduct of Operations D,R K/A: 2.1.32 (3.4)
Ability to obtain and interpret station reference materials such as graphs, nomographs, and tables which contain performance data.
Ability to explain and ap ply all system limits and precautions JPM: Calculate blended makeup volume a nd flow to the RWST. Conduct of Operations N,R K/A: 2.1.25 (2.8)
JPM: Determine Tagging Boundaries for Equipment Control                 N, R             Containment Spray Pump.
Ability to obtain and inter p ret station r e ference  materials su ch as graph s, nomographs, and tables which contain perf o rmance data.
K/A: 2.2.13 (3.6)
JPM: Determine T agging Boundaries for Containmen t Spray Pu mp. Equipment Control N, R K/A: 2.2.13 (3.6)
Knowledge of tagging and clearance procedures JPM: Determine Stay Time.
Knowledge of tagging a nd clearance procedures JPM: Determine Stay Time.
Radiation Control                 M, R K/A: 2.3.2 (2.5)
Radiation Control M, R K/A: 2.3.2 (2.5)
Knowledge of facility ALARA program Emergency Plan 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.
Knowledge of facility AL ARA progra m  Emergency Plan NOTE: All items (5 t o tal are req u ired for SROs. RO app licants req u ire only 4 items unless they are retaking only t he administrative topics, when 5 are required.  
*Type Codes & Criteria:         (C)ontrol room (D)irect from bank ( 3 for ROs;  for SROs & RO retakes)
*Type Code s & Criteria: (C)ontrol room (D)irect from bank ( 3 for ROs;  for SROs & RO retakes)
(N)ew or (M)odified from bank (> 1)
(N)ew or (M)odified from bank (> 1)
(P)revious 2 exams ( 1; randomly s e lected) (S)imulator Class(R)oom NURE G-10 21, Revision 9 ES-301 Administrative Topics Outline Form ES-301-1 NUREG-1021, Revision 9 TASK  
(P)revious 2 exams ( 1; randomly selected)
(S)imulator Class(R)oom NUREG-1021, Revision 9
 
ES-301                           Administrative Topics Outline                   Form ES-301-1 TASK  


==SUMMARY==
==SUMMARY==


A1a: Conduct of Operations:
A1a:   Conduct of Operations:
Perform a QPTR Calculation. The task will require the RO and SRO applicants to perform a QPTR Calculation for Mode 1 conditions. The JPM will be a bank JPM A1b: Conduct of Operations:
Perform a QPTR Calculation. The task will require the RO and SRO applicants to perform a QPTR Calculation for Mode 1 conditions. The JPM will be a bank JPM A1b:   Conduct of Operations:
Calculate blended makeup volume and flow for a makeup to the RWST. The task will require the applicant to determine volume of boric acid required based upon boric acid storage tank concentration, and makeup flow controller settings based upon desired makeup flow. This is a new JPM. A2: Equipment Control:
Calculate blended makeup volume and flow for a makeup to the RWST. The task will require the applicant to determine volume of boric acid required based upon boric acid storage tank concentration, and makeup flow controller settings based upon desired makeup flow. This is a new JPM.
Determine Boundaries for Containment Spray Pump. The RO applicants will be required to determine the isolation boundaries for a Containment Spray Pump that will be removed from  
A2:     Equipment Control:
Determine Boundaries for Containment Spray Pump. The RO applicants will be required to determine the isolation boundaries for a Containment Spray Pump that will be removed from service. This is a new JPM.
A3      Radiation Control:
Determine Stay Time. Given several Radiation Work Permits to choose from, survey maps of an area where work is required, and alarming dosimetry, the RO and SRO applicants will be required to determine their allowed stay time prior to reaching the dosimetry alarm setpoint.
This task is modified from a task performed on the 2003 NRC examination NUREG-1021, Revision 9


service. This is a new JPM.
ES-301                               Administrative Topics Outline                     Form ES-301-1 Facility:     Callaway                                 Date of Examination:         8/22/2005 Examination Level (circle one):       SRO               Operating Test Number:       NRC Administrative Topic             Type                  Describe activity to be performed (see Note)               Code*
A3 Radiation Control:
JPM: Perform A QPTR Calculation.
Determine Stay Time. Given several Radiation Work Permits to choose from, survey maps of an area where work is required, and alarming dosimetry, the RO and SRO applicants will be required to determine their allowed stay time prior to reaching the dosimetry alarm setpoint.
Conduct of Operations             D,R K/A: 2.1.32 (3.8)
This task is modified from a task performed on the 2003 NRC examination ES-301 Administrative Topics Outline Form ES-30 1-1 Facility:
Ability to explain and apply all system limits and precautions JPM: Calculate blended makeup volume and flow to Conduct of Operations             N,R             the RWST.
Callaway Date of Exa m ination: 8/22/2005 Exa m ination Level (circle one):
K/A: 2.1.25 (3.1)
SRO Operating Test Number:
Ability to obtain and interpret station reference materials such as graphs, nomographs, and tables which contain performance data.
NRC Administrative Topic (see Note)
JPM: Review a Tagging Order for approval.
Type Code* Describe act i vity to be performed JPM: Perform A QPTR Calculation.
Equipment Control                 N,R K/A: 2.2.13 (3.8)
Conduct of Operations D,R K/A: 2.1.32 (3.8)
Knowledge of tagging and clearance procedures JPM: Determine Stay Time.
Ability to explain and ap ply all system limits and precautions JPM: Calculate blended makeup volume a nd flow to the RWST. Conduct of Operations N,R K/A: 2.1.25 (3.1)
Radiation Control                 M,R K/A: 2.3.2 (2.9)
Ability to obtain and inter p ret station r e ference  materials su ch as graph s, nomographs, and tables which contain perf o rmance data.
Knowledge of facility ALARA program JPM: Upgrade Emergency Classification and make Emergency Plan                   N,R,S             initial Protective Action Recommendation K/A: 2.4.44 (4.0)
JPM: Review a Ta gging Order for approval.
Knowledge of emergency plan protective action recommendations 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.
Equipment Control N,R K/A: 2.2.13 (3.8)
*Type Codes & Criteria:         (C)ontrol room (D)irect from bank ( 3 for ROs;  for SROs & RO retakes)
Knowledge of tagging a nd clearance procedures JPM: Determine Stay Time.
Radiation Control M,R K/A: 2.3.2 (2.9)
Knowledge of facility AL ARA progra m JPM: Upgrade Emergency Classif i cation and make initial Protective Action Recommen dation Emergency Plan N,R,S K/A: 2.4.44 (4.0) Knowledge of emergency plan protective action recommend ations  NOTE: All items (5 t o tal are req u ired for SROs. RO app licants req u ire only 4 items unless they are retaking only t he administrative topics, when 5 are required.  
*Type Code s & Criteria: (C)ontrol room (D)irect from bank ( 3 for ROs;  for SROs & RO retakes)
(N)ew or (M)odified from bank (> 1)
(N)ew or (M)odified from bank (> 1)
(P)revious 2 exams ( 1; randomly s e lected) (S)imulator Class(R)oom NURE G-10 21, Revision 9 ES-301 Administrative Topics Outline Form ES-301-1 NUREG-1021, Revision 9 TASK  
(P)revious 2 exams ( 1; randomly selected)
(S)imulator Class(R)oom NUREG-1021, Revision 9
 
ES-301                             Administrative Topics Outline                   Form ES-301-1 TASK  


==SUMMARY==
==SUMMARY==


A1a: Conduct of Operations:
A1a:   Conduct of Operations:
Perform a QPTR Calculation. The task will require the RO and SRO applicants to perform a QPTR Calculation for Mode 1 conditions with a dropped control rod. The JPM will be a bank JPM   A1b: Conduct of Operations:
Perform a QPTR Calculation. The task will require the RO and SRO applicants to perform a QPTR Calculation for Mode 1 conditions with a dropped control rod. The JPM will be a bank JPM A1b:   Conduct of Operations:
Calculate blended makeup volume and flow for a makeup to the RWST. The task will require the applicant to determine volume of boric acid required based upon boric acid storage tank concentration, and makeup flow controller settings based upon desired makeup flow. This is a new JPM. A2: Equipment Control:
Calculate blended makeup volume and flow for a makeup to the RWST. The task will require the applicant to determine volume of boric acid required based upon boric acid storage tank concentration, and makeup flow controller settings based upon desired makeup flow. This is a new JPM.
A2:     Equipment Control:
Review a Tagging Order for approval. The SRO applicants will review a tagging order that contains critical errors. The applicants will be required to determine the errors that exist and recommend correction prior to tagging order approval. This is a new JPM.
Review a Tagging Order for approval. The SRO applicants will review a tagging order that contains critical errors. The applicants will be required to determine the errors that exist and recommend correction prior to tagging order approval. This is a new JPM.
A3 Radiation Control:
A3     Radiation Control:
Determine Stay Time. Given several Radiation Work Permits to choose from, survey maps of an area where work is required, and alarming dosimetry, the RO and SRO applicants will be required to determine their allowed stay time prior to reaching the dosimetry alarm setpoint. This task is modified from a task performed on the 2003 NRC examination A4: Emergency Plan:
Determine Stay Time. Given several Radiation Work Permits to choose from, survey maps of an area where work is required, and alarming dosimetry, the RO and SRO applicants will be required to determine their allowed stay time prior to reaching the dosimetry alarm setpoint.
This task is modified from a task performed on the 2003 NRC examination A4:     Emergency Plan:
Upgrade Emergency Classification and make initial PAR. The SRO applicants will be given plant conditions requiring escalation of an emergency classification to a General Area Emergency. The applicants will then make an initial Protective Action Recommendation based upon the existing conditions. This is a new JPM.
Upgrade Emergency Classification and make initial PAR. The SRO applicants will be given plant conditions requiring escalation of an emergency classification to a General Area Emergency. The applicants will then make an initial Protective Action Recommendation based upon the existing conditions. This is a new JPM.
ES-401 PWR Exami nation Outline Form ES-40 1-2 Facility:
NUREG-1021, Revision 9
Callaway Date of Exam:
 
8/22/2005 RO K/A Category Points SRO-Only Po ints T i e r G r o u p K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 G* Total A 2 G* T o t a l 1 1 1 3    7 4   2 1 8 3 3 6 2 1 2 2    2 2  0 9 2 2 4 1. Emerge ncy &  Abnorm a l Plant Evolutions Tier Totals 2 3 5    9 6   2 2 7 5 5 10 1 4 2 2 4 2 2 3 3 2 3 1 2 8 3 2 5 2 1 2 1 0 0 1 0 0 2 1 2 1 0  1 2 3 2.          Plant S y st ems Tier Totals 5 4 3 4 2 3 3 3 4 4 3 3 8 4 4 8 1 2 3 4 1 2 3 4 3. Generi c Knowl edge a n d Abilities C a te go r i es 2 2 2 4 10 1 2 2 2 7 Note: 1. Ensu re that a t least two topics from eve r y applicable K/A category are sampl ed within ea ch ti er of the RO an d SRO-only outli nes (i.e., except for one ca tegory in Tier 3 of the SRO-only outline, the "Tier T o tals" i n each K/A category shall not be less th an two).
ES-401                                     PWR Examination Outline                                   Form ES-401-2 Facility:     Callaway                                       Date of Exam:     8/22/2005 RO K/A Category Points                             SRO-Only Points Tier        Group      K   K   K   K   K   K   A   A   A   A   G Total         A2      G*     Total 1   2  3  4    5    6  1    2  3    4  *
: 2. The point tota l for each g r o up and tier in the prop osed outline mu st match that sp ecified in the table. The final point total for each gro up and tier m a y deviate by 1 from that spe c ified in th e table ba sed o n NRC revi si ons. The fina l RO ex am m u st total 75 p o ints an d the SRO-only exam must total 25 points. 3. Systems/evol utions within each gro up a r e identified o n t he asso cia t ed outline; systems o r evolution s that do not appl y at the facility should b e d e leted an d ju stified; operationally import ant, site-spe cific systems that a r e not incl ude d on the outli ne sh ould b e adde d. Refer to ES-401, Attachment 2
: 1.                  1        1   1   3                 7   4           2     18            3       3         6 Emergency &
, for guidan ce rega rdin g elim ination of in approp riate K/A statements.
Abnormal            2       1   2    2                 2    2           0       9           2       2         4 Plant Evolutions         Tier     2   3   5                 9   6           2     27            5       5         10 Totals 1       4   2   2   4   2   2   3   3   2   3   1     28            3       2         5 2.
: 4. Select topics from as m any system s and evolutions a s possible; sa mple every system or evolution in the gro up bef ore sele cting a se con d topi c for any sy stem or evoluti on. 5. Absent a pla n t specifi c prio rity, only those KAs having an importa nce rating (I R) o f 2.5 or highe r shall b e sel e cted. Use the RO an d SRO ratings fo r the RO an d SRO-only po rtio ns, re spe c tively. 6. Select SRO t opics for Tie r s 1 and 2 fr o m the shad ed system s and K/A categori e s. 7.* The gen eri c (G) K/As in Tiers 1 a nd 2 shall be sele cted from Se ction 2 of the K/A Catalog, bu t the topics must b e relevant to the appli c abl e evolution or system.
2        1   2   1   0   0   1   0   0   2   1   2     10              1     2         3 Plant Tier     5   4   3   4   2   3   3   3   4   4   3     38 Systems                                                                                        4       4         8 Totals
: 8. On the followi ng pag es, ent er the K/A numbers, a brief descriptio n o f each topi c, the topics' importa nce ra tings (I R) for t he appli c abl e licen se level, and the point totals (#) fo r each system and catego ry. Enter the group an d tier totals for ea ch catego ry in the table ab ove: if fuel handling equipm ent is sampl ed in ot her than Cate gory A2 or G* on the SRO-Only exam, enter it on the left side of colum n A2 for Tier 2, Grou p 2. Use du plicate page s for RO and SRO-onl y exams. 9. For Tie r 3, se lect topics fro m Section 2 o f the K/A Catalog, and e n ter the K/A numbers, descri p tion s, IRs, and p o in t totals (#) on Form ES-4 0 1-3. Limit SRO sele ction s to K/As that are linke d to 10CFR55.4 3  NURE G-10 21 1 ES-401 Callaway PWR BOTH Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 Form ES-40 1-2    E/APE # / Name Safety Function G K1 K2 K3 A1 A2 Number K/A Topic(s)
: 3. Generic Knowledge and Abilities        1       2       3       4                   1   2   3   4 10                              7 Categories 2       2       2       4                   1   2   2   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).
Imp. Q# 008 / Pressurizer Vapor Space Ac cident / 3 X AA2.30 Ability to dete r mi ne and interp ret t he follow i ng as t h e y appl y to the P r e ssurizer Vapor S pace Accident:
: 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.
Inadequate Core Cooling 4.7  7 6 011 / Larg e Brea k LOCA / 3 X           2.2.25 Equipment Contr o l Know ledg e of bases in technical specificat ions for limiting co ndit ions for operations and safety limits. 3.7  7 7 022 / Loss of Rx Coolant Makeup  
: 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 that are not included on the outline should be added. Refer to ES-401, Attachment 2, for guidance regarding elimination of inappropriate K/A statements.
/ 2           X AA2.03 Ability to dete r mi ne and interp ret t he follow i ng as t h e y appl y to the Loss of Reactor Coo l ant Makeup: Failures of flow cont rol valve or controller 3.6  7 8 038 / Steam Gen. Tube Ru pture / 3 X           2.1.32 Conduct of O perations: Ability to ex plain and appl y all sy stem limits and precautions.
: 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.
3.8  7 9 054 / Loss of Main Feed water / 4 X           2.4.49 Emergenc y P r oc edures / Plan Ability to p e rfo r m w i t hout reference to proc edures t hose actions that require immediate opera t ion of s y stem components and co ntrols. 4.0  8 0 E04 / LOCA Out s ide Containmen t / 3           X EA2.1 Ability to dete r mi ne and interp ret t he follow i ng as t h e y appl y to the (L OCA O u tside Cont ainment) Facilit y conditions and selection of appro p riate procedu re s during abnormal and e m ergenc y operat i ons. 4.3  8 1 007 / Reactor Tri p - Stabilization - Recovery
: 5. Absent a plant specific priority, only those KAs 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.
/ 1         X   EA1.02 Ability to ope rate and monitor th e follow i ng as the y appl y to a reactor t r ip: MFW S y stem 3.8  3 9 008 / Pressurizer Vapor Space Ac cident / 3 X       AK2.03 Kno w ledge of th e interrelations b e tween the P r es surizer Vapor Space Ac cident and the fol l ow ing: C ontrolle rs and positioners 2.5 4 0 009 / Small Brea k LOCA / 3 X     EK3.12 Kno w ledge of th e reasons for th e follow i ng respo n s es as the y ap pl y to the small break LOCA: Letdo w n isolation 3.4  4 1 011 / Larg e Brea k LOCA / 3 X           2.1.23 Conduct of O perations: Ability to perform specific sy stem and integrate d plant procedu res d u ring all modes of plant operation.
: 6. Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.
3.9 4 2 025 / Loss of RH R S y stem / 4 X           2.1.30 Conduct of O perations: Ability to locate and ope rat e components, including local controls.
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.
3.9  4 3 026 / Loss of Co mponent Cooling Water / 8 X AA2.06 Ability to dete r mi ne and interp ret t he follow i ng as t h e y appl y to  the Loss of Component Cooling Water: T he length of time aft e r the loss of CC W flow to a comp onent  before that comp onent ma y be da maged 2.8  4 4 027 / Pressurizer Pressure Cont ro l Sy stem Malfunc tion / 3          X AA2.10 Ability to dete r mi ne and interp ret t he follow i ng as t h e y appl y to  the P r e ssurizer Pressure Control Malfun ctions: Heater e nergized/de-ene rgized condition 3.3  4 5 029 / ATWS / 1 X   EA1.10 Ability to ope rate and monitor th e follow i ng as the y appl y to a ATWS: Rod control function sw itch 3.6  4 6 NURE G-10 21 2 ES-401 Callaway PWR BOTH Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 Form ES-40 1-2    E/APE # / Name Safety Function G K1 K2 K3 A1 A2 Number K/A Topic(s)
: 8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics importance ratings (IR) 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. Use duplicate pages for RO and SRO-only exams.
Imp. Q# 038 / Steam Gen. Tube Ru pture / 3         X   EA1.35 Ability to ope rate and monitor th e follow i ng as the y appl y to a  SGTR: Stea m dump condens er 3.5  4 7 040 / Steam Line Rupture - Exces s ive Heat Transf e r / 4         X   AA1.05 Ability to ope rate and / or mo nitor the follow i ng as t h e y appl y to  the St e a m Line Ruptu r e: Manual and aut omatic RPS tr ip initiation 4.5 4 8 054 / Loss of Main Feed water / 4 X AA2.02 Ability to dete r mi ne and interp ret t he follow i ng as t h e y appl y to the Loss of Main Feed water (M FW): Differentiation be tw e en loss of all MFW and trip of one MFW pump 4.1  4 9 056 / Loss of Off
: 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 10CFR55.43 NUREG-1021                                                1
-site Pow e r / 6   X         AK1.01 Kno w ledge of th e operational imp lications of the follow i ng concepts as the y  appl y to Loss of Offsite Po w e r: P r inciple of cooling b y nat ural convection 3.7  5 0 057 / Loss of Vital AC Inst. Bus / 6 X   AA1.04 Ability to ope rate and / or mo nitor the follow i ng as t h e y appl y to the Loss of Vital AC Instrument Bus: RW ST and VCT valves 3.5 5 1 058 / Loss of DC Power / 6 X AA2.01 Ability to dete r mi ne and interp ret t he follow i ng as t h e y appl y to the Loss of DC Po w e r: T hat a loss of dc power has occurred; ve rification that substitute pow e r sou r ces have come on line 3.7  5 2 062 / Loss of Nu clear Svc. Water / 4 X   AA1.07 Ability to ope rate and / or mo nitor the follow i ng as t h e y appl y to  the Loss of Nuclear Serv ice Water: Flo w r a tes to the components and s y stems that are serviced b y t he CCWS; interactions among the co mponents 2.9  5 3 E04 / LOCA Out s ide Containmen t / 3      X    EK3.2 Kno w ledge of th e reasons for th e follow i ng respo n s es as the y ap pl y to the (LOCA Outside Containment)
 
No rmal, abnormal and e m ergenc y operat i ng procedures associated w i th (L OCA Outside C ontainment).
ES-401                                                                       Callaway                                                                     Form ES-401-2 PWR BOTH Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 E/APE # / Name Safety Function                     G   K1   K2   K3 A1   A2     Number                           K/A Topic(s)                           Imp. Q#
3.4 5 4 E11 / Loss of Emergenc y Coolant Recirc. / 4 X    EK3.4 Kno w ledge of th e reasons for th e follow i ng respo n s es as the y ap pl y to the (Loss of Emerg enc y Coolant Recirculation) RO or S R O fu nction as a w i thin the control room team as ap propriate to the assigned positio n, in such a w a y that procedures a r e a dhered to and th e  limitations in the facilit ies l i cense and amendme n t s are not violated.
Ability to determine and interpret the following as they 008 / Pressurizer Vapor Space Accident / 3                                       X     AA2.30   apply to the Pressurizer Vapor Space Accident:                 4.7  76 Inadequate Core Cooling Equipment Control Knowledge of bases in technical 011 / Large Break LOCA / 3                               X                             2.2.25   specifications for limiting conditions for operations and     3.7  77 safety limits.
3.6  5 5 E12 / Steam Line Rupture - Exces s ive Heat Transf e r / 4         X   EA1.3 Ability to ope rate and / or mo nitor the follow i ng as t h e y appl y to the (Unc ontrolled Depr essurization of all S t eam Gene rators) Desired ope rating res u lts during abnor mal and emerg enc y s i tuations.
Ability to determine and interpret the following as they 022 / Loss of Rx Coolant Makeup / 2                                               X     AA2.03   apply to the Loss of Reactor Coolant Makeup: Failures of       3.6  78 flow control valve or controller Conduct of Operations: Ability to explain and apply all 038 / Steam Gen. Tube Rupture / 3                         X                             2.1.32                                                                   3.8  79 system limits and precautions.
3.4  5 6 K/A Categor y Poi n t Totals:
Emergency Procedures / Plan Ability to perform without 054 / Loss of Main Feedwater / 4                         X                             2.4.49   reference to procedures those actions that require             4.0  80 immediate operation of system components and controls.
2/3     1 1 3 7 4/3 Grou p Point Tota l: 18/6 NURE G-10 21 3 ES-401 Callaway PWR BOTH Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 Form ES-40 1-2    E/APE # / Name Safety Function G K1 K2 K3 A1 A2 Number K/A Topic(s)
Ability to determine and interpret the following as they apply to the (LOCA Outside Containment) Facility E04 / LOCA Outside Containment / 3                                               X     EA2.1                                                                   4.3  81 conditions and selection of appropriate procedures during abnormal and emergency operations.
Imp. Q# 001 / Continuous Rod Withdra w al / 1           X AA2.02 Ability to deter mi ne and inter p r e t the follow i ng as they appl y to the Co ntinuous Rod Withdra w al: Pro per actions to be taken if aut omatic safety fun c tions have not taken place 4.5  8 2 037 / Steam Gen e rator Tube L eak / 3 X           2.2.22 Equipment Contr o l Know ledg e of limiting conditions for operations and s a fet y limits. 4.1  8 3 060 / Accidental Gaseous RadWa s te Rel. / 9 X AA2.06 Ability to deter mi ne and inter p r e t the follow i ng as they appl y to the Accidental Gaseous Rad w aste: Valve lineup for release of rad i oactive gases 3.6  8 4 E14 / Loss of CT MT Integrit y / 5 X           2.4.6 Emergenc y P r oc edures / Plan Kn ow led ge s y mpto m based EOP mitigation strategies.
Ability to operate and monitor the following as they apply 007 / Reactor Trip - Stabilization - Recovery / 1                           X           EA1.02                                                                   3.8  39 to a reactor trip: MFW System Knowledge of the interrelations between the Pressurizer 008 / Pressurizer Vapor Space Accident / 3                         X                   AK2.03   Vapor Space Accident and the following: Controllers and       2.5   40 positioners Knowledge of the reasons for the following responses as 009 / Small Break LOCA / 3                                             X               EK3.12                                                                   3.4  41 they apply to the small break LOCA: Letdown isolation Conduct of Operations: Ability to perform specific system 011 / Large Break LOCA / 3                               X                             2.1.23   and integrated plant procedures during all modes of plant     3.9   42 operation.
4.0  8 5 036 / Fuel Ha ndling Accident / 8 X   AA1.02 Ability to ope rate and / or mo nitor the follow i ng as t h e y appl y to  the Fuel Handling Incidents: ARM s y stem 3.1  5 7 037 / Steam Gen e rator Tube L eak / 3         X   AA1.06 Ability to ope rate and / or mo nitor the follow i ng as t h e y appl y to  the St e a m Gene rato r Tu be Leak: Main steam line rad monitor meters 3.8  5 8 074 / Inadeq uate Core C ooling / 4 X         EK1.01 Kno w ledge of th e operational imp lications of the follow i ng concepts as they appl y to Inade quate Co re Cooli ng: Methods of calculating subcooling margin 4.3  5 9 E01 & E02 Redia gnosis and SI Te rmination / 3 X     EK3.2 Kno w ledge of th e reasons for th e follow i ng respo n s es as the y ap pl y to  the  (Reactor Trip o r Safet y Injection/Rediagnosis) Normal, a b normal, and em ergenc y procedures asso ciated w i th Re actor Trip o r Safet y Injection/Rediagnosis.
Conduct of Operations: Ability to locate and operate 025 / Loss of RHR System / 4                             X                             2.1.30                                                                   3.9  43 components, including local controls.
3.0  6 0 E03 / LOCA Cool do w n - Depress. / 4       X     EK3.2 Kno w ledge of th e reasons for th e follow i ng respo n s es as the y ap pl y to the (LOCA Cooldo wn and Dep r essurization)
Ability to determine and interpret the following as they apply to the Loss of Component Cooling Water: The 026 / Loss of Component Cooling Water / 8                                         X     AA2.06                                                                   2.8  44 length of time after the loss of CCW flow to a component before that component may be damaged Ability to determine and interpret the following as they 027 / Pressurizer Pressure Control System Malfunction /
Normal, abno rm al and emerge ncy ope rating proc edures associated w i th (L OCA C ooldo w n and Dep r essurization).
X     AA2.10   apply to the Pressurizer Pressure Control Malfunctions:       3.3  45 3
3.4  6 1 E07 / Inad. Co re Cooling / 4 X EA2.2 Ability to deter mi ne and inter p r e t the follow i ng as they appl y to the (Sat urated C o re C ooling) Adherence t o approp riate proc edures and o per ation w i thin the limitations in the facility
Heater energized/de-energized condition Ability to operate and monitor the following as they apply 029 / ATWS / 1                                                             X           EA1.10                                                                   3.6  46 to a ATWS: Rod control function switch NUREG-1021                                                                      2
's license and amendme n t s. 3.3  6 2 E08 / RCS Overcooling - PTS / 4 X       EK2.1 Kno w ledge of th e interrelations b e tween the (Pres s urized Thermal Shock) and the follo w i ng: Components, a n d functions of control and safet y s y s t ems, including instrumentation, signals, in terlocks, failure modes, and automatic and m anual features.
 
3.4  6 3 NURE G-10 21 4 ES-401 Callaway PWR BOTH Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 Form ES-40 1-2    E/APE # / Name Safety Function G K1 K2 K3 A1 A2 Number K/A Topic(s)
ES-401                                                                       Callaway                                                                         Form ES-401-2 PWR BOTH Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 E/APE # / Name Safety Function                   G   K1   K2   K3 A1   A2     Number                               K/A Topic(s)                           Imp. Q#
Imp. Q# E09 / Natural Circ. / 4 X EA2.2 Ability to deter mi ne and inter p r e t the follow i ng as they appl y to the (Nat ural Circul ation Oper ations) Adh e rence to approp riate pr ocedures and op eration w i thin the limitations in the facility
Ability to operate and monitor the following as they apply 038 / Steam Gen. Tube Rupture / 3                                         X           EA1.35                                                                     3.5  47 to a SGTR: Steam dump condenser Ability to operate and / or monitor the following as they 040 / Steam Line Rupture - Excessive Heat Transfer / 4                     X           AA1.05       apply to the Steam Line Rupture: Manual and automatic          4.5   48 RPS trip initiation Ability to determine and interpret the following as they apply to the Loss of Main Feedwater (MFW):
's license and amendme n t s. 3.4  6 4 E14 / Loss of CT MT Integrit y / 5     X       EK2.1 Kno w ledge of th e interrelations b e tween the (High Containment Pre ssure) and the f o llow i ng: Compo n e nts, and functions of control and safet y s y stems, including instrumentation, signals, in terlocks, failure modes, and automatic and m anual features.
054 / Loss of Main Feedwater / 4                                                X    AA2.02                                                                      4.1  49 Differentiation between loss of all MFW and trip of one MFW pump Knowledge of the operational implications of the following 056 / Loss of Off-site Power / 6                             X                         AK1.01       concepts as they apply to Loss of Offsite Power: Principle    3.7  50 of cooling by natural convection Ability to operate and / or monitor the following as they 057 / Loss of Vital AC Inst. Bus / 6                                       X           AA1.04       apply to the Loss of Vital AC Instrument Bus: RWST and         3.5   51 VCT valves Ability to determine and interpret the following as they apply to the Loss of DC Power: That a loss of dc power 058 / Loss of DC Power / 6                                                      X    AA2.01                                                                      3.7  52 has occurred; verification that substitute power sources have come on line Ability to operate and / or monitor the following as they apply to the Loss of Nuclear Service Water: Flow rates to 062 / Loss of Nuclear Svc. Water / 4                                       X           AA1.07                                                                     2.9  53 the components and systems that are serviced by the CCWS; interactions among the components Knowledge of the reasons for the following responses as they apply to the (LOCA Outside Containment) Normal, E04 / LOCA Outside Containment / 3                                    X                EK3.2                                                                      3.4   54 abnormal and emergency operating procedures associated with (LOCA Outside Containment).
3.4  6 5 K/A Categor y Poi n t Total: 0/2     1 2 2 2 2/2 Grou p Point Tota l: 9/4 NURE G-10 21 5 ES-401 Callaway PWR BOTH Written Examination Outline Plant Systems - Tier 2 Group 1 Form ES-40 1-2  S y stem #/Nam e G K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 Number K/A T opics Imp. Q# 006 Emergenc y Core Co oling                X    A2.12 Ability to (a) predict the impacts of the follow i ng malfunctions or operations on the ECCS; and (b) based on those p r edictions , use procedures to correct, control, or mitigate the co nsequences of those malfunctions or operations:
Knowledge of the reasons for the following responses as they apply to the (Loss of Emergency Coolant Recirculation) RO or SRO function as a within the control E11 / Loss of Emergency Coolant Recirc. / 4                            X                EK3.4      room team as appropriate to the assigned position, in         3.6  55 such a way that procedures are adhered to and the limitations in the facilities license and amendments are not violated.
Conditions requiring actuatio n of ECCS 4.8  8 6 010 Pressurizer Pressure Cont rol                X    A2.03 Ability to (a) predict the impacts of the follow i ng malfunctions or operations on the PZR PCS; and (b) based on those p r edictions, use procedures to correct, control, or mitigate the co nsequences of those malfunctions or operations:
Ability to operate and / or monitor the following as they apply to the (Uncontrolled Depressurization of all Steam E12 / Steam Line Rupture - Excessive Heat Transfer / 4                     X           EA1.3                                                                     3.4  56 Generators) Desired operating results during abnormal and emergency situations.
PORV failures 4.2  8 7 064 Emergenc y Diesel Generato r X                     2.4.30 Emergenc y P r oc edures / Plan Kn ow led ge of w h ich events related to sy stem o peration s/status should be reporte d to outsi de agencies.
K/A Category Point Totals:                             2/3 1   1   3   7   4/3 Group Point Total:                                                                 18/6 NUREG-1021                                                                    3
3.6  8 8 076 Service Water X    A2.02 Ability to (a) predict the impacts of the follow i ng malfunctions or operations on the SWS; and (b) based on those p r edictions, use procedures to correct, control, or mitigate the co nsequences of those malfunctions or oper ations: Service w a te r header p r essure 3.1  8 9 103 Containment X                     2.1.14 Conduct of Oper ations: Know ledg e of s y stem statu s criteria which req u ire the notification of plant personnel.
 
3.3  9 0 003 Reactor Coo l ant Pump   X                   K1.01 Kno w ledge of th e ph y s ical connections and/or cause-effect relat i onships betw e e n the RCPS an d the follow i ng s y st ems: RCP lube o il 2.6  1 003 Reactor Coo l ant Pump              X      A1.01 Ability to predict and/or monito r changes in paramete r s (to p r event exceeding design limits) associated w i th o perating the RCP S controls including: RCP vibration 2.9  2 004 Chemical an d Volume Control      X              K3.06 Kno w ledge of th e effect that a loss or malfunction of the CVCS w ill have on the follow i ng: RCS temperatu r e and pressure 3.4 3 004 Chemical an d Volume Control       X            K4.15 Kno w ledge of C V CS design feat ure(s) a nd/or inter l ock(s) w h ic h pr ovide for the follow i ng: Inter l ocks associated w i th o peration of o r ifice isolation valves 3.0  1 6 005 Residual He at Removal X           K5.03 Kno w ledge of th e operational imp lications of the follow i ng concept s as the y appl y t he RHRS: Reactivity effects of RHR fill water 2.9  4 006 Emergenc y Core Co oling        X            K4.10 Kno w ledge of E CCS design feat ure(s) a nd/or interlock(s) w h ic h provide for th e follow i ng: Redundant pressure mete rs 2.9 5 NURE G-10 21 6 ES-401 Callaway PWR BOTH Written Examination Outline Plant Systems - Tier 2 Group 1 Form ES-40 1-2  S y stem #/Nam e G K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 Number K/A T opics Imp. Q# 007 Pressurizer Relief/Quench Tank                X    A2.02 Ability to (a) predict the impacts of the follow i ng malfunctions or operations on the PRTS; and (b) based on those p r edictions, use procedures to correct, control, or mitigate the co nsequences of those malfunctions or operat ions: Abnormal press u re in the PRT 2.6  6 008 Compon ent Cooling Water X  A3.08 Ability to monito r automatic operati on of the C C WS, including: Automatic actions associated w i th the CCWS that occur as a result of a safet y injection signal 3.6  7 008 Compon ent Cooling Water X                 K2.02 Kno w ledge of bu s pow e r supplies to the follo w i ng: CCW pump, including emergenc y backup 3.0  8 010 Pressurizer Pressure Cont rol              X      A1.08 Ability to predict and/or monito r changes in paramete r s (to p r event  exceeding design limits) associated w i th o perating the P Z R PCS controls including: Spra y nozzle DT 3.2  9 010 Pressurizer Pressure Cont rol   X                   K1.01 Kno w ledge of th e ph y s ical connections and/or cause-effect rela tionships betw e e n the PZR PCS and the follo w i ng sy stems: RPS 3.9  1 0 012 Reactor P r ot ection    X                 K2.01 Kno w ledge of bu s pow e r supplies to the follo w i ng: RPS channels, components, and i n terconnections 3.3  1 1 012 Reactor P r ot ection                  X  A3.06 Ability to monito r automatic operati on of the RPS, including: Trip logic 3.7  1 2 013 Engineered Safet y F eatur es Actuation X                   K1.14 Kno w ledge of th e ph y s ical connections and/or cause effect relationships between the ESFAS and the follow i ng s y stem s: IAS 3.1 1 3 013 Engineered Safet y F eatur es Actuation X           K5.01 Kno w ledge of th e operational imp lications of the follow i ng concept s as the y appl y t o the ESFAS:
ES-401                                                             Callaway                                                                     Form ES-401-2 PWR BOTH Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 E/APE # / Name Safety Function         G   K1   K2   K3 A1   A2     Number                           K/A Topic(s)                           Imp. Q#
Definitions of safet y train a nd ES F channel 2.8  1 4 022 Containment Cooling                X    A2.04 Ability to (a) predict the impacts of the follow i ng malfunctions or operations on th e CCS; and (b) based on those p r edictions, use procedures to correct, control, or mitigate the co nsequences of those malfunctions or oper ations: Loss of service wa t e r 2.9  1 5 026 Containment Spra y X                     2.1.2 Conduct of Oper ations: Know ledg e of operat or responsibilitie s during all modes of plant operation.
Ability to determine and interpret the following as they apply to the Continuous Rod Withdrawal: Proper actions 001 / Continuous Rod Withdrawal / 1                                   X     AA2.02                                                                   4.5 82 to be taken if automatic safety functions have not taken place Equipment Control Knowledge of limiting conditions for 037 / Steam Generator Tube Leak / 3           X                             2.2.22                                                                   4.1  83 operations and safety limits.
3.0  1 7 039 Main and Re heat Steam X               K3.05 Kno w ledge of th e effect that a loss or malfunction of the MRSS w ill have on the follow i ng: RCS 3.6  1 8 NURE G-10 21 7 ES-401 Callaway PWR BOTH Written Examination Outline Plant Systems - Tier 2 Group 1 Form ES-40 1-2  S y stem #/Nam e G K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 Number K/A T opics Imp. Q# 059 Main Feed w a ter                X    A2.07 Ability to (a) predict the impacts of the follow i ng malfunctions or operations on th e MFW; and (b) based on those p r edictions , use procedures to correct, control, or mitigate the co nsequences of those malfunctions or oper ations: Tripping of M F W pump turbine 3.0  1 9 061 Aux illary/Em e rgenc y Feed w a t e r            X        K6.02 Kno w ledge of th e effect of a loss or malfunction of the follow i ng w ill have on the AFW components:
Ability to determine and interpret the following as they 060 / Accidental Gaseous RadWaste Rel. / 9                             X     AA2.06   apply to the Accidental Gaseous Radwaste: Valve lineup         3.6  84 for release of radioactive gases Emergency Procedures / Plan Knowledge symptom E14 / Loss of CTMT Integrity / 5               X                             2.4.6                                                                   4.0  85 based EOP mitigation strategies.
Pumps 2.6 2 0 062 AC Electrical Distribution X      A1.01 Ability to predict and/or monito r changes in paramete r s (to p r event  exceeding design limits) associated w i th o perating the ac di stribution sy stem controls includin g: Signi ficance of D/G load limits 3.4  2 1 063 DC Electrical Distribution X            K4.02 Kno w ledge of dc electrical sy stem design feature(s) and/or interlock(s
Ability to operate and / or monitor the following as they 036 / Fuel Handling Accident / 8                                 X           AA1.02                                                                   3.1  57 apply to the Fuel Handling Incidents: ARM system Ability to operate and / or monitor the following as they 037 / Steam Generator Tube Leak / 3                             X           AA1.06   apply to the Steam Generator Tube Leak: Main steam             3.8  58 line rad monitor meters Knowledge of the operational implications of the following 074 / Inadequate Core Cooling / 4                 X                         EK1.01   concepts as they apply to Inadequate Core Cooling:             4.3  59 Methods of calculating subcooling margin Knowledge of the reasons for the following responses as they apply to the (Reactor Trip or Safety E01 & E02 Rediagnosis and SI Termination / 3                 X               EK3.2     Injection/Rediagnosis) Normal, abnormal, and emergency        3.0  60 procedures associated with Reactor Trip or Safety Injection/Rediagnosis.
) w h ich provide f o r the follo w i ng: Breaker interlocks, permissives, b y passes and cr oss-ties. 2.9 2 2 063 DC Electrical Distribution X A4.01 Ability to manu ally ope rate and/or monitor in the control room: Ma jor breakers and control po w e r fuses 2.8 2 3 064 Emergenc y Diesel Generato r            X        K6.07 Kno w ledge of th e effect of a loss or malfunction of the follow i ng  w ill have on the ED/G s y stem: Air Receiver s 2.7 2 4 073 Process Rad i ation Monitoring X A4.01 Ability to manu ally ope rate and/or monitor in the control room: Effl uent release 3.9 2 5 076 Service Water X                   K1.19 Kno w ledge of th e ph y s ical connections and/or cause- effect rela tionships betw e e n the SWS and t h e follow i ng s y stem s: SWS emergen cy heat loads 3.6  2 6 078 Instrument A i r        X            K4.01 Kno w ledge of IA S design feature(s) and/or interlock(s) w h ic h provide for th e follow i ng: Manual/automati c transfers of con t rol 2.7  2 7 103 Containment X A4 04 Ability to manu ally ope rate and/or monitor in the control room: Ph ase A and phase B resets 3.5  2 8 K/A Categor y Poi n t Totals:
Knowledge of the reasons for the following responses as they apply to the (LOCA Cooldown and Depressurization)
1/2       4 2 2 4 2 2 3 3/3 2 3 Grou p Point Tota l: 28/5 NURE G-10 21 8 ES-401 Callaway PWR BOTH Written Examination Outline Plant Systems - Tier 2 Group 2 Form ES-40 1-2  S y stem #/Nam e G K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 Number K/A T opics Imp. Q# 001 Cont rol Rod Drive X                   2.4.4 Emergenc y P r oc edures / Plan Ability to recognize abnormal indications for s y stem o perating paramete r s w h ich are ent r y-level conditions for emergenc y and abnormal ope rati ng procedu res. 4.3  9 1 002 Reactor Coo l ant X                     2.1.28 Conduct of Oper ations: Know ledg e of the pu rpose and function of m a jor s y stem com ponents and controls.
E03 / LOCA Cooldown - Depress. / 4                           X               EK3.2                                                                   3.4  61 Normal, abnormal and emergency operating procedures associated with (LOCA Cooldown and Depressurization).
3.3  9 2 011 Pressurizer Level Control X    A2.03 Ability to (a) predict the impacts of the follow i ng malfunctions or operations on the PZR LCS; an d (b) based on those p r edictions , use procedures to correct, control, or mitigate the co nsequences of those malfunctions or operations:
Ability to determine and interpret the following as they apply to the (Saturated Core Cooling) Adherence to E07 / Inad. Core Cooling / 4                                           X     EA2.2                                                                   3.3  62 appropriate procedures and operation within the limitations in the facility's license and amendments.
Loss of PZR level 3.9  9 3 001 Cont rol Rod Drive     X                 K2.02 Kno w ledge of bu s pow e r supplies to the follo w i ng: One-line diagr a m of po w e r sup p l y to trip breake r s 3.6  2 9 011 Pressurizer Level Control X         K6.04 Kno w ledge of th e effect of a loss or malfunction on the follow i ng w ill have on the PZR LCS: O p er ation of PZ R level contr o ller s 3.1 3 0 014 Rod Position Indication X                     2.1.27 Conduct of Oper ations: Know ledg e of s y stem purpose and or f unction. 2.8  3 1 015 Nuclear Instr u mentation X                 K2.01 Kno w ledge of bu s pow e r supplies to the follo w i ng: NIS channels, components, and in terconnections 3.3  3 2 017 In-core Tem peratur e Monitor X                     2.1.28 Conduct of Oper ations: Know ledg e of the pu rpose and function of m a jor s y stem com p onents and controls.
Knowledge of the interrelations between the (Pressurized Thermal Shock) and the following: Components, and E08 / RCS Overcooling - PTS / 4                         X                   EK2.1     functions of control and safety systems, including             3.4  63 instrumentation, signals, interlocks, failure modes, and automatic and manual features.
3.1 3 3 029 Containment Purge                  X   A3.01 Ability to monito r automatic operati on of the Containment Pur ge S y stem including: CPS isolatio n 3.8  3 4 041 Steam Dum p/Turbine B y pas s Control                  X    A3.05 Ability to monito r automatic operati on of the SDS, including: Main steam pressure 2.9 3 5 045 Main Tu rbine Gene rator   X                  K1.19 Kno w ledge of th e ph y s ical connections and/or cause-effect relat i onships betw e e n the MT/G s y ste m and the follo w i ng sy stems: ESFA S 3.4  3 6 071 Waste Gas Disposal      X              K3.05 Kno w ledge of th e effect that a loss or malfunction of the Waste G a s Disposal Sy stem w ill have on the follow i ng: ARM a nd PRM s y stems 3.2  3 7 079 Station Air X A4.01 Ability to manu ally ope rate and/or monitor in the control room: C r oss-tie valves w i th IAS 2.7  3 8 K/A Categor y Poi n t Totals:
NUREG-1021                                                          4
2/2       1 2 1 0 0 1 0 0/1 2 1 Grou p Point Tota l: 10/3 NURE G-10 21 9 ES-401 Generic Knowledge and Abilities Outl ine (Tier3)
 
Form ES-40 1-3 Facility:
ES-401                                                     Callaway                                                                       Form ES-401-2 PWR BOTH Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 E/APE # / Name Safety Function G   K1   K2   K3 A1   A2     Number                               K/A Topic(s)                         Imp. Q#
Callaway Date of Exam:
Ability to determine and interpret the following as they apply to the (Natural Circulation Operations) Adherence E09 / Natural Circ. / 4                                       X     EA2.2                                                                     3.4  64 to appropriate procedures and operation within the limitations in the facility's license and amendments.
8/22/2005 RO S R O-Onl y Categor y K/A # T o p i c I R Q# I R Q# 2.1.33 Ability to r e cognize indicati ons for sy stem oper ating paramete r s w h ich are ent r y-level conditions for technical specif ications.
Knowledge of the interrelations between the (High Containment Pressure) and the following: Components, E14 / Loss of CTMT Integrity / 5               X                     EK2.1       and functions of control and safety systems, including       3.4  65 instrumentation, signals, interlocks, failure modes, and automatic and manual features.
4.0 9 4 2.1.18 Ability to make accur a te, clear and concise logs, records, status b oards, and r eport s. 2.9 6 6  2.1.16 Ability to ope rate plant phone, pa ging sy stem, and tw o-w a y r adio. 2.9 6 7  1. Conduct of Oper ations S u b t o t a l  2 1 2.2.33 Kno w ledge of co ntrol rod p r ogr am ming. 2.9 9 5 2.2.10 Kno w ledge of th e process for det ermining if the m a rgin of safet y , as defi ned in the basis of an y technical specificat ion is reduced b y a prop osed change, tes t or expe riment. 3.3 9 6 2.2.25 Kno w ledge of ba ses in technical specifications for limiting condit i ons for operations and safet y limits. 2.5 6 8  2.2.2 Ability to manipul ate the cons ole controls as required to operate the fa cility bet w een sh utdo w n and designated po w e r levels.
K/A Category Point Total:             0/2 1   2   2   2   2/2 Group Point Total:                                                               9/4 NUREG-1021                                                  5
4.0 6 9  2. Equipment Contr o l S u b t o t a l  2  2 2.3.8 Kno w ledge of th e process for per forming a planne d gaseous radioactive release.
 
3.2 9 7 2.3.10 Ability to pe rform procedures to re duce ex cessive levels of radiatio n and gua rd agai nst personnel exposure. 3.3 9 8 2.3.9 Kno w ledge of th e process for per forming a containment pur ge. 2.5 7 0  2.3.11 Ability to contr o l radiation r e leases. 2.7 71   3. Radiation Contr o l S u b t o t a l  2 2 2.4.4 Ability to recog n ize abnormal indications for sy ste m operating pa ram e ters w h ich are e n tr y-level conditions for emer genc y a nd abnorm a l ope rating procedu re s. 4.3 9 9 2.4.38 Ability to take actions called for in the facility emergenc y plan, including (if required) suppo rting o r acting as emerge ncy coordinato
ES-401                                                       Callaway                                                                     Form ES-401-2 PWR BOTH Written Examination Outline Plant Systems - Tier 2 Group 1 System #/Name                    G K1 K2 K3 K4 K5 K6 A1   A2 A3   A4   Number                         K/A Topics                          Imp. Q#
: r. 4.0 1 0 0 2.4.31 Kno w ledge of an nunciators, alarm s and indications, and use of the re sponse instructio ns. 3.3 7 2  2.4.3 Ability to identif y post-accident ins t rumentation.
Ability to (a) predict the impacts of the following malfunctions or operations on the ECCS; and (b) based on those predictions, use procedures to 006 Emergency Core Cooling                                X              A2.12                                                              4.8  86 correct, control, or mitigate the consequences of those malfunctions or operations: Conditions requiring actuation of ECCS Ability to (a) predict the impacts of the following malfunctions or operations on the PZR PCS; and (b) 010 Pressurizer Pressure Control                          X              A2.03  based on those predictions, use procedures to               4.2  87 correct, control, or mitigate the consequences of those malfunctions or operations: PORV failures Emergency Procedures / Plan Knowledge of which 064 Emergency Diesel Generator  X                                       2.4.30 events related to system operations/status should be         3.6  88 reported to outside agencies.
3.5 73   2.4.12 Kno w ledge of ge neral operating cre w respo n sibiliti e s during emer genc y ope rations. 3.4 7 4  2.4.29 Kno w ledge of th e emergenc y pla n. 2.6 75   4. Emergenc y P r oc edures /  Plan S u b t o t a l  4  2 Tier 3 Point Tot a l  10 7 NURE G-10 21 10 ES-401 Record of Rejected K/As Form ES-40 1-4 Tier / Group Randomly Selected K/A Reason for Rejection 2 / 1 008 / A2.07 The subject K/A isn't rele vant at the subject facilit
Ability to (a) predict the impacts of the following malfunctions or operations on the SWS; and (b) based on those predictions, use procedures to 076 Service Water                                          X              A2.02                                                              3.1  89 correct, control, or mitigate the consequences of those malfunctions or operations: Service water header pressure Conduct of Operations: Knowledge of system status 103 Containment                 X                                       2.1.14 criteria which require the notification of plant             3.3  90 personnel.
: y. No pump auto start o n flow rate 2 / 1 008 / A3.02 The subject K/A isn't rele vant at the subject facilit
Knowledge of the physical connections and/or 003 Reactor Coolant Pump           X                                     K1.01 cause-effect relationships between the RCPS and              2.6    1 the following systems: RCP lube oil Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) 003 Reactor Coolant Pump                              X                  A1.01                                                              2.9    2 associated with operating the RCPS controls including: RCP vibration Knowledge of the effect that a loss or malfunction of 004 Chemical and Volume                  X                                K3.06  the CVCS will have on the following: RCS                     3.4   3 Control                                                                         temperature and pressure Knowledge of CVCS design feature(s) and/or 004 Chemical and Volume                    X                            K4.15  interlock(s) which provide for the following: Interlocks    3.0  16 Control                                                                          associated with operation of orifice isolation valves Knowledge of the operational implications of the 005 Residual Heat Removal                     X                         K5.03 following concepts as they apply the RHRS:                   2.9    4 Reactivity effects of RHR fill water Knowledge of ECCS design feature(s) and/or 006 Emergency Core Cooling                  X                            K4.10  interlock(s) which provide for the following:               2.9   5 Redundant pressure meters NUREG-1021                                                    6
: y. Facility does not have booster pumps.
 
2 / 1 012 / A1.01 It isn't possible to prepa re a psychometrically sound questio n related to t he subject K/A.
ES-401                                                       Callaway                                                                 Form ES-401-2 PWR BOTH Written Examination Outline Plant Systems - Tier 2 Group 1 System #/Name                    G K1 K2 K3 K4 K5 K6 A1   A2 A3   A4   Number                         K/A Topics                      Imp. Q#
Not a task performed by operations 2 / 1 061 / A1.03 The subject K/A isn't rele vant at the subject facilit
Ability to (a) predict the impacts of the following malfunctions or operations on the PRTS; and (b) 007 Pressurizer Relief/Quench                                                    based on those predictions, use procedures to X              A2.02                                                            2.6    6 Tank                                                                            correct, control, or mitigate the consequences of those malfunctions or operations: Abnormal pressure in the PRT Ability to monitor automatic operation of the CCWS, including: Automatic actions associated with the 008 Component Cooling Water                                    X        A3.08                                                            3.6    7 CCWS that occur as a result of a safety injection signal Knowledge of bus power supplies to the following:
: y. Not multi
008 Component Cooling Water           X                                   K2.02                                                           3.0    8 CCW pump, including emergency backup Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) 010 Pressurizer Pressure Control                      X                  A1.08                                                            3.2    9 associated with operating the PZR PCS controls including: Spray nozzle DT Knowledge of the physical connections and/or 010 Pressurizer Pressure Control   X                                     K1.01 cause-effect relationships between the PZR PCS           3.9  10 and the following systems: RPS Knowledge of bus power supplies to the following:
-unit. 2 / 1 103 / A4.06 The subject K/A isn't rele vant at the subject facilit
012 Reactor Protection                X                                   K2.01                                                           3.3  11 RPS channels, components, and interconnections Ability to monitor automatic operation of the RPS, 012 Reactor Protection                                          X        A3.06                                                            3.7  12 including: Trip logic Knowledge of the physical connections and/or cause 013 Engineered Safety Features    X                                     K1.14 effect relationships between the ESFAS and the           3.1   13 Actuation                                                                        following systems: IAS Knowledge of the operational implications of the 013 Engineered Safety Features                X                         K5.01 following concepts as they apply to the ESFAS:           2.8  14 Actuation                                                                        Definitions of safety train and ESF channel Ability to (a) predict the impacts of the following malfunctions or operations on the CCS; and (b) based on those predictions, use procedures to 022 Containment Cooling                                    X              A2.04                                                            2.9  15 correct, control, or mitigate the consequences of those malfunctions or operations: Loss of service water Conduct of Operations: Knowledge of operator 026 Containment Spray            X                                       2.1.2                                                           3.0  17 responsibilities during all modes of plant operation.
: y. No ability to monitor this system and component from the control room.
Knowledge of the effect that a loss or malfunction of 039 Main and Reheat Steam               X                               K3.05                                                           3.6  18 the MRSS will have on the following: RCS NUREG-1021                                                    7
2 / 2 027 / 2.1.27 The subject K/A isn't rele vant at the subject facilit
 
: y. Syste m is retired in p l ace. 2 / 2 017 / A2.01 It isn't possible to prepa re a psychometrically sound questio n related to t he subject K/A.
ES-401                                                         Callaway                                                                 Form ES-401-2 PWR BOTH Written Examination Outline Plant Systems - Tier 2 Group 1 System #/Name                    G   K1 K2 K3 K4 K5 K6 A1   A2   A3   A4 Number                           K/A Topics                      Imp. Q#
Operating the system controls would not result in the effects stated. 2 / 1 006 / A2.07 The subject K/A isn't rele vant at the subject facilit
Ability to (a) predict the impacts of the following malfunctions or operations on the MFW; and (b) based on those predictions, use procedures to 059 Main Feedwater                                            X            A2.07                                                            3.0  19 correct, control, or mitigate the consequences of those malfunctions or operations: Tripping of MFW pump turbine Knowledge of the effect of a loss or malfunction of 061 Auxillary/Emergency X                      K6.02   the following will have on the AFW components:           2.6   20 Feedwater Pumps Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) 062 AC Electrical Distribution                          X                  A1.01                                                            3.4  21 associated with operating the ac distribution system controls including: Significance of D/G load limits Knowledge of dc electrical system design feature(s) and/or interlock(s) which provide for the following:
: y. No heat tracing on thi s sy stem. 2 / 1 022 K4.03 The function required by the topic do es not exist at this facilit y 1 / 2 001 AA2.02 There is no relationship between these components for this e v ent at this f a cility 1 / 2 060 AA2.04 Could not develop a psychometrically sound SRO level test item for this topic 1 / 1 008 AA2.10 Could not develop a psychometrically sound SRO level test item for this topic 1 / 1 027 AA2.04 Could not develop a psychometrically sound ite m for the subject KA.
063 DC Electrical Distribution                X                            K4.02                                                            2.9   22 Breaker interlocks, permissives, bypasses and cross-ties.
Replaced with 027 AA2.10 1 / 2 059 AK1.02 Could not develop a psychometrically sound ite m for the subject KA.
Ability to manually operate and/or monitor in the 063 DC Electrical Distribution                                        X    A4.01    control room: Major breakers and control power          2.8   23 fuses Knowledge of the effect of a loss or malfunction of 064 Emergency Diesel Generator                      X                      K6.07    the following will have on the ED/G system: Air         2.7   24 Receivers Ability to manually operate and/or monitor in the 073 Process Radiation Monitoring                                      X    A4.01                                                            3.9   25 control room: Effluent release Knowledge of the physical connections and/or 076 Service Water                   X                                     K1.19   cause- effect relationships between the SWS and the      3.6  26 following systems: SWS emergency heat loads Knowledge of IAS design feature(s) and/or 078 Instrument Air                            X                            K4.01    interlock(s) which provide for the following:           2.7  27 Manual/automatic transfers of control Ability to manually operate and/or monitor in the 103 Containment                                                        X    A4 04                                                            3.5  28 control room: Phase A and phase B resets K/A Category Point Totals:       1/2 4 2 2 4 2 2   3   3/3   2   3   Group Point Total:                                                   28/5 NUREG-1021                                                        8
Replaced with 074 EK1.01 2 / 1 064 K6.08 Event would have no effect on the fa cility. Repla c ed with 06 4 K6.07 1 / 2 E01 EK3.1 Could not develop a psychometrically sound ite m for the subject KA.
 
Replaced with E01 EK3.2 NURE G-10 21 11}}
ES-401                                                         Callaway                                                                     Form ES-401-2 PWR BOTH Written Examination Outline Plant Systems - Tier 2 Group 2 System #/Name                  G   K1 K2 K3 K4 K5 K6 A1   A2   A3   A4 Number                             K/A Topics                      Imp. Q#
Emergency Procedures / Plan Ability to recognize abnormal indications for system operating 001 Control Rod Drive           X                                         2.4.4                                                               4.3  91 parameters which are entry-level conditions for emergency and abnormal operating procedures.
Conduct of Operations: Knowledge of the purpose 002 Reactor Coolant              X                                         2.1.28     and function of major system components and               3.3  92 controls.
Ability to (a) predict the impacts of the following malfunctions or operations on the PZR LCS; and (b) 011 Pressurizer Level Control                                X            A2.03      based on those predictions, use procedures to             3.9  93 correct, control, or mitigate the consequences of those malfunctions or operations: Loss of PZR level Knowledge of bus power supplies to the following:
001 Control Rod Drive                 X                                   K2.02                                                               3.6  29 One-line diagram of power supply to trip breakers Knowledge of the effect of a loss or malfunction on 011 Pressurizer Level Control                     X                       K6.04     the following will have on the PZR LCS: Operation of     3.1   30 PZR level controllers Conduct of Operations: Knowledge of system 014 Rod Position Indication     X                                         2.1.27                                                               2.8  31 purpose and or function.
Knowledge of bus power supplies to the following:
015 Nuclear Instrumentation            X                                   K2.01                                                               3.3  32 NIS channels, components, and interconnections Conduct of Operations: Knowledge of the purpose 017 In-core Temperature Monitor X                                         2.1.28     and function of major system components and               3.1  33 controls.
Ability to monitor automatic operation of the 029 Containment Purge                                            X        A3.01                                                                3.8  34 Containment Purge System including: CPS isolation 041 Steam Dump/Turbine Bypass                                                        Ability to monitor automatic operation of the SDS, X        A3.05      including: Main steam pressure                           2.9  35 Control Knowledge of the physical connections and/or 045 Main Turbine Generator          X                                      K1.19      cause-effect relationships between the MT/G system        3.4  36 and the following systems: ESFAS Knowledge of the effect that a loss or malfunction of 071 Waste Gas Disposal                    X                                K3.05      the Waste Gas Disposal System will have on the           3.2  37 following: ARM and PRM systems Ability to manually operate and/or monitor in the 079 Station Air                                                      X    A4.01                                                                2.7  38 control room: Cross-tie valves with IAS K/A Category Point Totals:     2/2 1 2 1 0 0 1   0   0/1   2   1 Group Point Total:                                                         10/3 NUREG-1021                                                      9
 
ES-401                           Generic Knowledge and Abilities Outline (Tier3)                   Form ES-401-3 Facility:             Callaway                     Date of Exam:                       8/22/2005 RO     SRO-Only Category        K/A #                               Topic IR    Q# IR    Q#
Ability to recognize indications for system operating 2.1.33   parameters which are entry-level conditions for                 4.0     94 technical specifications.
: 1.                             Ability to make accurate, clear and concise logs, 2.1.18                                                          2.9   66 Conduct of Operations          records, status boards, and reports.
Ability to operate plant phone, paging system, and 2.1.16                                                          2.9   67 two-way radio.
Subtotal                                                                2         1 2.2.33   Knowledge of control rod programming.                           2.9     95 Knowledge of the process for determining if the margin of safety, as defined in the basis of any technical 2.2.10                                                                    3.3    96 specification is reduced by a proposed change, test or experiment.
2.
Knowledge of bases in technical specifications for Equipment Control      2.2.25                                                          2.5    68 limiting conditions for operations and safety limits.
Ability to manipulate the console controls as required 2.2.2    to operate the facility between shutdown and           4.0    69 designated power levels.
Subtotal                                                                2          2 Knowledge of the process for performing a planned 2.3.8                                                                     3.2    97 gaseous radioactive release.
Ability to perform procedures to reduce excessive 2.3.10   levels of radiation and guard against personnel                 3.3     98
: 3.                             exposure.
Radiation Control              Knowledge of the process for performing a 2.3.9                                                          2.5   70 containment purge.
2.3.11   Ability to control radiation releases.                 2.7   71 Subtotal                                                                2         2 Ability to recognize abnormal indications for system 2.4.4   operating parameters which are entry-level conditions           4.3     99 for emergency and abnormal operating procedures.
Ability to take actions called for in the facility 2.4.38  emergency plan, including (if required) supporting or            4.0    100 acting as emergency coordinator.
: 4.                             Knowledge of annunciators, alarms and indications, 2.4.31                                                         3.3    72 Emergency Procedures            and use of the response instructions.
    / Plan                2.4.3   Ability to identify post-accident instrumentation. 3.5   73 Knowledge of general operating crew responsibilities 2.4.12                                                         3.4   74 during emergency operations.
2.4.29   Knowledge of the emergency plan.                       2.6   75 Subtotal                                                                4         2 Tier 3 Point Total                                                                            10         7 NUREG-1021                                                      10
 
ES-401                               Record of Rejected K/As                             Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A The subject K/A isn't relevant at the subject facility. No pump auto start on 2/1   008 / A2.07 flow rate The subject K/A isn't relevant at the subject facility. Facility does not have 2/1   008 / A3.02 booster pumps.
It isn't possible to prepare a psychometrically sound question related to the 2/1  012 / A1.01 subject K/A. Not a task performed by operations 2/1   061 / A1.03 The subject K/A isn't relevant at the subject facility. Not multi-unit.
The subject K/A isn't relevant at the subject facility. No ability to monitor this 2/1  103 / A4.06 system and component from the control room.
2/2   027 / 2.1.27 The subject K/A isn't relevant at the subject facility. System is retired in place.
It isn't possible to prepare a psychometrically sound question related to the 2/2  017 / A2.01  subject K/A. Operating the system controls would not result in the effects stated.
The subject K/A isn't relevant at the subject facility. No heat tracing on this 2/1  006 / A2.07 system.
2/1   022 K4.03   The function required by the topic does not exist at this facility 1/2   001 AA2.02   There is no relationship between these components for this event at this facility 1/2   060 AA2.04   Could not develop a psychometrically sound SRO level test item for this topic 1/1   008 AA2.10   Could not develop a psychometrically sound SRO level test item for this topic Could not develop a psychometrically sound item for the subject KA.
1/1  027 AA2.04 Replaced with 027 AA2.10 Could not develop a psychometrically sound item for the subject KA.
1/2  059 AK1.02 Replaced with 074 EK1.01 2/1   064 K6.08   Event would have no effect on the facility. Replaced with 064 K6.07 Could not develop a psychometrically sound item for the subject KA.
1/2  E01 EK3.1 Replaced with E01 EK3.2 NUREG-1021                                      11}}

Latest revision as of 17:50, 23 November 2019

CW-08-2005-Final Outline
ML061560137
Person / Time
Site: Callaway Ameren icon.png
Issue date: 08/22/2005
From:
NRC Region 4
To:
References
Download: ML061560137 (15)
v • d • e


Text

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Callaway Date of Examination: 8/22/2005 Examination Level (circle one): RO Operating Test Number: NRC Administrative Topic Type Describe activity to be performed (see Note) Code*

JPM: Perform a QPTR Calculation.

Conduct of Operations D,R K/A: 2.1.32 (3.4)

Ability to explain and apply all system limits and precautions JPM: Calculate blended makeup volume and flow to Conduct of Operations N,R the RWST.

K/A: 2.1.25 (2.8)

Ability to obtain and interpret station reference materials such as graphs, nomographs, and tables which contain performance data.

JPM: Determine Tagging Boundaries for Equipment Control N, R Containment Spray Pump.

K/A: 2.2.13 (3.6)

Knowledge of tagging and clearance procedures JPM: Determine Stay Time.

Radiation Control M, R K/A: 2.3.2 (2.5)

Knowledge of facility ALARA program Emergency Plan 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.

  • Type Codes & Criteria: (C)ontrol room (D)irect from bank ( 3 for ROs; for SROs & RO retakes)

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

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

(S)imulator Class(R)oom NUREG-1021, Revision 9

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

SUMMARY

A1a: Conduct of Operations:

Perform a QPTR Calculation. The task will require the RO and SRO applicants to perform a QPTR Calculation for Mode 1 conditions. The JPM will be a bank JPM A1b: Conduct of Operations:

Calculate blended makeup volume and flow for a makeup to the RWST. The task will require the applicant to determine volume of boric acid required based upon boric acid storage tank concentration, and makeup flow controller settings based upon desired makeup flow. This is a new JPM.

A2: Equipment Control:

Determine Boundaries for Containment Spray Pump. The RO applicants will be required to determine the isolation boundaries for a Containment Spray Pump that will be removed from service. This is a new JPM.

A3 Radiation Control:

Determine Stay Time. Given several Radiation Work Permits to choose from, survey maps of an area where work is required, and alarming dosimetry, the RO and SRO applicants will be required to determine their allowed stay time prior to reaching the dosimetry alarm setpoint.

This task is modified from a task performed on the 2003 NRC examination NUREG-1021, Revision 9

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Callaway Date of Examination: 8/22/2005 Examination Level (circle one): SRO Operating Test Number: NRC Administrative Topic Type Describe activity to be performed (see Note) Code*

JPM: Perform A QPTR Calculation.

Conduct of Operations D,R K/A: 2.1.32 (3.8)

Ability to explain and apply all system limits and precautions JPM: Calculate blended makeup volume and flow to Conduct of Operations N,R the RWST.

K/A: 2.1.25 (3.1)

Ability to obtain and interpret station reference materials such as graphs, nomographs, and tables which contain performance data.

JPM: Review a Tagging Order for approval.

Equipment Control N,R K/A: 2.2.13 (3.8)

Knowledge of tagging and clearance procedures JPM: Determine Stay Time.

Radiation Control M,R K/A: 2.3.2 (2.9)

Knowledge of facility ALARA program JPM: Upgrade Emergency Classification and make Emergency Plan N,R,S initial Protective Action Recommendation K/A: 2.4.44 (4.0)

Knowledge of emergency plan protective action recommendations 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.

  • Type Codes & Criteria: (C)ontrol room (D)irect from bank ( 3 for ROs; for SROs & RO retakes)

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

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

(S)imulator Class(R)oom NUREG-1021, Revision 9

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

SUMMARY

A1a: Conduct of Operations:

Perform a QPTR Calculation. The task will require the RO and SRO applicants to perform a QPTR Calculation for Mode 1 conditions with a dropped control rod. The JPM will be a bank JPM A1b: Conduct of Operations:

Calculate blended makeup volume and flow for a makeup to the RWST. The task will require the applicant to determine volume of boric acid required based upon boric acid storage tank concentration, and makeup flow controller settings based upon desired makeup flow. This is a new JPM.

A2: Equipment Control:

Review a Tagging Order for approval. The SRO applicants will review a tagging order that contains critical errors. The applicants will be required to determine the errors that exist and recommend correction prior to tagging order approval. This is a new JPM.

A3 Radiation Control:

Determine Stay Time. Given several Radiation Work Permits to choose from, survey maps of an area where work is required, and alarming dosimetry, the RO and SRO applicants will be required to determine their allowed stay time prior to reaching the dosimetry alarm setpoint.

This task is modified from a task performed on the 2003 NRC examination A4: Emergency Plan:

Upgrade Emergency Classification and make initial PAR. The SRO applicants will be given plant conditions requiring escalation of an emergency classification to a General Area Emergency. The applicants will then make an initial Protective Action Recommendation based upon the existing conditions. This is a new JPM.

NUREG-1021, Revision 9

ES-401 PWR Examination Outline Form ES-401-2 Facility: Callaway Date of Exam: 8/22/2005 RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G Total A2 G* Total 1 2 3 4 5 6 1 2 3 4 *

1. 1 1 1 3 7 4 2 18 3 3 6 Emergency &

Abnormal 2 1 2 2 2 2 0 9 2 2 4 Plant Evolutions Tier 2 3 5 9 6 2 27 5 5 10 Totals 1 4 2 2 4 2 2 3 3 2 3 1 28 3 2 5 2.

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

3. Generic Knowledge and Abilities 1 2 3 4 1 2 3 4 10 7 Categories 2 2 2 4 1 2 2 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 that are not included on the outline should be added. Refer to ES-401, Attachment 2, for guidance regarding 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 KAs 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.

8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics importance ratings (IR) 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. 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 10CFR55.43 NUREG-1021 1

ES-401 Callaway Form ES-401-2 PWR BOTH Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 E/APE # / Name Safety Function G K1 K2 K3 A1 A2 Number K/A Topic(s) Imp. Q#

Ability to determine and interpret the following as they 008 / Pressurizer Vapor Space Accident / 3 X AA2.30 apply to the Pressurizer Vapor Space Accident: 4.7 76 Inadequate Core Cooling Equipment Control Knowledge of bases in technical 011 / Large Break LOCA / 3 X 2.2.25 specifications for limiting conditions for operations and 3.7 77 safety limits.

Ability to determine and interpret the following as they 022 / Loss of Rx Coolant Makeup / 2 X AA2.03 apply to the Loss of Reactor Coolant Makeup: Failures of 3.6 78 flow control valve or controller Conduct of Operations: Ability to explain and apply all 038 / Steam Gen. Tube Rupture / 3 X 2.1.32 3.8 79 system limits and precautions.

Emergency Procedures / Plan Ability to perform without 054 / Loss of Main Feedwater / 4 X 2.4.49 reference to procedures those actions that require 4.0 80 immediate operation of system components and controls.

Ability to determine and interpret the following as they apply to the (LOCA Outside Containment) Facility E04 / LOCA Outside Containment / 3 X EA2.1 4.3 81 conditions and selection of appropriate procedures during abnormal and emergency operations.

Ability to operate and monitor the following as they apply 007 / Reactor Trip - Stabilization - Recovery / 1 X EA1.02 3.8 39 to a reactor trip: MFW System Knowledge of the interrelations between the Pressurizer 008 / Pressurizer Vapor Space Accident / 3 X AK2.03 Vapor Space Accident and the following: Controllers and 2.5 40 positioners Knowledge of the reasons for the following responses as 009 / Small Break LOCA / 3 X EK3.12 3.4 41 they apply to the small break LOCA: Letdown isolation Conduct of Operations: Ability to perform specific system 011 / Large Break LOCA / 3 X 2.1.23 and integrated plant procedures during all modes of plant 3.9 42 operation.

Conduct of Operations: Ability to locate and operate 025 / Loss of RHR System / 4 X 2.1.30 3.9 43 components, including local controls.

Ability to determine and interpret the following as they apply to the Loss of Component Cooling Water: The 026 / Loss of Component Cooling Water / 8 X AA2.06 2.8 44 length of time after the loss of CCW flow to a component before that component may be damaged Ability to determine and interpret the following as they 027 / Pressurizer Pressure Control System Malfunction /

X AA2.10 apply to the Pressurizer Pressure Control Malfunctions: 3.3 45 3

Heater energized/de-energized condition Ability to operate and monitor the following as they apply 029 / ATWS / 1 X EA1.10 3.6 46 to a ATWS: Rod control function switch NUREG-1021 2

ES-401 Callaway Form ES-401-2 PWR BOTH Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 E/APE # / Name Safety Function G K1 K2 K3 A1 A2 Number K/A Topic(s) Imp. Q#

Ability to operate and monitor the following as they apply 038 / Steam Gen. Tube Rupture / 3 X EA1.35 3.5 47 to a SGTR: Steam dump condenser Ability to operate and / or monitor the following as they 040 / Steam Line Rupture - Excessive Heat Transfer / 4 X AA1.05 apply to the Steam Line Rupture: Manual and automatic 4.5 48 RPS trip initiation Ability to determine and interpret the following as they apply to the Loss of Main Feedwater (MFW):

054 / Loss of Main Feedwater / 4 X AA2.02 4.1 49 Differentiation between loss of all MFW and trip of one MFW pump Knowledge of the operational implications of the following 056 / Loss of Off-site Power / 6 X AK1.01 concepts as they apply to Loss of Offsite Power: Principle 3.7 50 of cooling by natural convection Ability to operate and / or monitor the following as they 057 / Loss of Vital AC Inst. Bus / 6 X AA1.04 apply to the Loss of Vital AC Instrument Bus: RWST and 3.5 51 VCT valves Ability to determine and interpret the following as they apply to the Loss of DC Power: That a loss of dc power 058 / Loss of DC Power / 6 X AA2.01 3.7 52 has occurred; verification that substitute power sources have come on line Ability to operate and / or monitor the following as they apply to the Loss of Nuclear Service Water: Flow rates to 062 / Loss of Nuclear Svc. Water / 4 X AA1.07 2.9 53 the components and systems that are serviced by the CCWS; interactions among the components Knowledge of the reasons for the following responses as they apply to the (LOCA Outside Containment) Normal, E04 / LOCA Outside Containment / 3 X EK3.2 3.4 54 abnormal and emergency operating procedures associated with (LOCA Outside Containment).

Knowledge of the reasons for the following responses as they apply to the (Loss of Emergency Coolant Recirculation) RO or SRO function as a within the control E11 / Loss of Emergency Coolant Recirc. / 4 X EK3.4 room team as appropriate to the assigned position, in 3.6 55 such a way that procedures are adhered to and the limitations in the facilities license and amendments are not violated.

Ability to operate and / or monitor the following as they apply to the (Uncontrolled Depressurization of all Steam E12 / Steam Line Rupture - Excessive Heat Transfer / 4 X EA1.3 3.4 56 Generators) Desired operating results during abnormal and emergency situations.

K/A Category Point Totals: 2/3 1 1 3 7 4/3 Group Point Total: 18/6 NUREG-1021 3

ES-401 Callaway Form ES-401-2 PWR BOTH Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 E/APE # / Name Safety Function G K1 K2 K3 A1 A2 Number K/A Topic(s) Imp. Q#

Ability to determine and interpret the following as they apply to the Continuous Rod Withdrawal: Proper actions 001 / Continuous Rod Withdrawal / 1 X AA2.02 4.5 82 to be taken if automatic safety functions have not taken place Equipment Control Knowledge of limiting conditions for 037 / Steam Generator Tube Leak / 3 X 2.2.22 4.1 83 operations and safety limits.

Ability to determine and interpret the following as they 060 / Accidental Gaseous RadWaste Rel. / 9 X AA2.06 apply to the Accidental Gaseous Radwaste: Valve lineup 3.6 84 for release of radioactive gases Emergency Procedures / Plan Knowledge symptom E14 / Loss of CTMT Integrity / 5 X 2.4.6 4.0 85 based EOP mitigation strategies.

Ability to operate and / or monitor the following as they 036 / Fuel Handling Accident / 8 X AA1.02 3.1 57 apply to the Fuel Handling Incidents: ARM system Ability to operate and / or monitor the following as they 037 / Steam Generator Tube Leak / 3 X AA1.06 apply to the Steam Generator Tube Leak: Main steam 3.8 58 line rad monitor meters Knowledge of the operational implications of the following 074 / Inadequate Core Cooling / 4 X EK1.01 concepts as they apply to Inadequate Core Cooling: 4.3 59 Methods of calculating subcooling margin Knowledge of the reasons for the following responses as they apply to the (Reactor Trip or Safety E01 & E02 Rediagnosis and SI Termination / 3 X EK3.2 Injection/Rediagnosis) Normal, abnormal, and emergency 3.0 60 procedures associated with Reactor Trip or Safety Injection/Rediagnosis.

Knowledge of the reasons for the following responses as they apply to the (LOCA Cooldown and Depressurization)

E03 / LOCA Cooldown - Depress. / 4 X EK3.2 3.4 61 Normal, abnormal and emergency operating procedures associated with (LOCA Cooldown and Depressurization).

Ability to determine and interpret the following as they apply to the (Saturated Core Cooling) Adherence to E07 / Inad. Core Cooling / 4 X EA2.2 3.3 62 appropriate procedures and operation within the limitations in the facility's license and amendments.

Knowledge of the interrelations between the (Pressurized Thermal Shock) and the following: Components, and E08 / RCS Overcooling - PTS / 4 X EK2.1 functions of control and safety systems, including 3.4 63 instrumentation, signals, interlocks, failure modes, and automatic and manual features.

NUREG-1021 4

ES-401 Callaway Form ES-401-2 PWR BOTH Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 E/APE # / Name Safety Function G K1 K2 K3 A1 A2 Number K/A Topic(s) Imp. Q#

Ability to determine and interpret the following as they apply to the (Natural Circulation Operations) Adherence E09 / Natural Circ. / 4 X EA2.2 3.4 64 to appropriate procedures and operation within the limitations in the facility's license and amendments.

Knowledge of the interrelations between the (High Containment Pressure) and the following: Components, E14 / Loss of CTMT Integrity / 5 X EK2.1 and functions of control and safety systems, including 3.4 65 instrumentation, signals, interlocks, failure modes, and automatic and manual features.

K/A Category Point Total: 0/2 1 2 2 2 2/2 Group Point Total: 9/4 NUREG-1021 5

ES-401 Callaway Form ES-401-2 PWR BOTH Written Examination Outline Plant Systems - Tier 2 Group 1 System #/Name G K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 Number K/A Topics Imp. Q#

Ability to (a) predict the impacts of the following malfunctions or operations on the ECCS; and (b) based on those predictions, use procedures to 006 Emergency Core Cooling X A2.12 4.8 86 correct, control, or mitigate the consequences of those malfunctions or operations: Conditions requiring actuation of ECCS Ability to (a) predict the impacts of the following malfunctions or operations on the PZR PCS; and (b) 010 Pressurizer Pressure Control X A2.03 based on those predictions, use procedures to 4.2 87 correct, control, or mitigate the consequences of those malfunctions or operations: PORV failures Emergency Procedures / Plan Knowledge of which 064 Emergency Diesel Generator X 2.4.30 events related to system operations/status should be 3.6 88 reported to outside agencies.

Ability to (a) predict the impacts of the following malfunctions or operations on the SWS; and (b) based on those predictions, use procedures to 076 Service Water X A2.02 3.1 89 correct, control, or mitigate the consequences of those malfunctions or operations: Service water header pressure Conduct of Operations: Knowledge of system status 103 Containment X 2.1.14 criteria which require the notification of plant 3.3 90 personnel.

Knowledge of the physical connections and/or 003 Reactor Coolant Pump X K1.01 cause-effect relationships between the RCPS and 2.6 1 the following systems: RCP lube oil Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) 003 Reactor Coolant Pump X A1.01 2.9 2 associated with operating the RCPS controls including: RCP vibration Knowledge of the effect that a loss or malfunction of 004 Chemical and Volume X K3.06 the CVCS will have on the following: RCS 3.4 3 Control temperature and pressure Knowledge of CVCS design feature(s) and/or 004 Chemical and Volume X K4.15 interlock(s) which provide for the following: Interlocks 3.0 16 Control associated with operation of orifice isolation valves Knowledge of the operational implications of the 005 Residual Heat Removal X K5.03 following concepts as they apply the RHRS: 2.9 4 Reactivity effects of RHR fill water Knowledge of ECCS design feature(s) and/or 006 Emergency Core Cooling X K4.10 interlock(s) which provide for the following: 2.9 5 Redundant pressure meters NUREG-1021 6

ES-401 Callaway Form ES-401-2 PWR BOTH Written Examination Outline Plant Systems - Tier 2 Group 1 System #/Name G K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 Number K/A Topics Imp. Q#

Ability to (a) predict the impacts of the following malfunctions or operations on the PRTS; and (b) 007 Pressurizer Relief/Quench based on those predictions, use procedures to X A2.02 2.6 6 Tank correct, control, or mitigate the consequences of those malfunctions or operations: Abnormal pressure in the PRT Ability to monitor automatic operation of the CCWS, including: Automatic actions associated with the 008 Component Cooling Water X A3.08 3.6 7 CCWS that occur as a result of a safety injection signal Knowledge of bus power supplies to the following:

008 Component Cooling Water X K2.02 3.0 8 CCW pump, including emergency backup Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) 010 Pressurizer Pressure Control X A1.08 3.2 9 associated with operating the PZR PCS controls including: Spray nozzle DT Knowledge of the physical connections and/or 010 Pressurizer Pressure Control X K1.01 cause-effect relationships between the PZR PCS 3.9 10 and the following systems: RPS Knowledge of bus power supplies to the following:

012 Reactor Protection X K2.01 3.3 11 RPS channels, components, and interconnections Ability to monitor automatic operation of the RPS, 012 Reactor Protection X A3.06 3.7 12 including: Trip logic Knowledge of the physical connections and/or cause 013 Engineered Safety Features X K1.14 effect relationships between the ESFAS and the 3.1 13 Actuation following systems: IAS Knowledge of the operational implications of the 013 Engineered Safety Features X K5.01 following concepts as they apply to the ESFAS: 2.8 14 Actuation Definitions of safety train and ESF channel Ability to (a) predict the impacts of the following malfunctions or operations on the CCS; and (b) based on those predictions, use procedures to 022 Containment Cooling X A2.04 2.9 15 correct, control, or mitigate the consequences of those malfunctions or operations: Loss of service water Conduct of Operations: Knowledge of operator 026 Containment Spray X 2.1.2 3.0 17 responsibilities during all modes of plant operation.

Knowledge of the effect that a loss or malfunction of 039 Main and Reheat Steam X K3.05 3.6 18 the MRSS will have on the following: RCS NUREG-1021 7

ES-401 Callaway Form ES-401-2 PWR BOTH Written Examination Outline Plant Systems - Tier 2 Group 1 System #/Name G K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 Number K/A Topics Imp. Q#

Ability to (a) predict the impacts of the following malfunctions or operations on the MFW; and (b) based on those predictions, use procedures to 059 Main Feedwater X A2.07 3.0 19 correct, control, or mitigate the consequences of those malfunctions or operations: Tripping of MFW pump turbine Knowledge of the effect of a loss or malfunction of 061 Auxillary/Emergency X K6.02 the following will have on the AFW components: 2.6 20 Feedwater Pumps Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) 062 AC Electrical Distribution X A1.01 3.4 21 associated with operating the ac distribution system controls including: Significance of D/G load limits Knowledge of dc electrical system design feature(s) and/or interlock(s) which provide for the following:

063 DC Electrical Distribution X K4.02 2.9 22 Breaker interlocks, permissives, bypasses and cross-ties.

Ability to manually operate and/or monitor in the 063 DC Electrical Distribution X A4.01 control room: Major breakers and control power 2.8 23 fuses Knowledge of the effect of a loss or malfunction of 064 Emergency Diesel Generator X K6.07 the following will have on the ED/G system: Air 2.7 24 Receivers Ability to manually operate and/or monitor in the 073 Process Radiation Monitoring X A4.01 3.9 25 control room: Effluent release Knowledge of the physical connections and/or 076 Service Water X K1.19 cause- effect relationships between the SWS and the 3.6 26 following systems: SWS emergency heat loads Knowledge of IAS design feature(s) and/or 078 Instrument Air X K4.01 interlock(s) which provide for the following: 2.7 27 Manual/automatic transfers of control Ability to manually operate and/or monitor in the 103 Containment X A4 04 3.5 28 control room: Phase A and phase B resets K/A Category Point Totals: 1/2 4 2 2 4 2 2 3 3/3 2 3 Group Point Total: 28/5 NUREG-1021 8

ES-401 Callaway Form ES-401-2 PWR BOTH Written Examination Outline Plant Systems - Tier 2 Group 2 System #/Name G K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 Number K/A Topics Imp. Q#

Emergency Procedures / Plan Ability to recognize abnormal indications for system operating 001 Control Rod Drive X 2.4.4 4.3 91 parameters which are entry-level conditions for emergency and abnormal operating procedures.

Conduct of Operations: Knowledge of the purpose 002 Reactor Coolant X 2.1.28 and function of major system components and 3.3 92 controls.

Ability to (a) predict the impacts of the following malfunctions or operations on the PZR LCS; and (b) 011 Pressurizer Level Control X A2.03 based on those predictions, use procedures to 3.9 93 correct, control, or mitigate the consequences of those malfunctions or operations: Loss of PZR level Knowledge of bus power supplies to the following:

001 Control Rod Drive X K2.02 3.6 29 One-line diagram of power supply to trip breakers Knowledge of the effect of a loss or malfunction on 011 Pressurizer Level Control X K6.04 the following will have on the PZR LCS: Operation of 3.1 30 PZR level controllers Conduct of Operations: Knowledge of system 014 Rod Position Indication X 2.1.27 2.8 31 purpose and or function.

Knowledge of bus power supplies to the following:

015 Nuclear Instrumentation X K2.01 3.3 32 NIS channels, components, and interconnections Conduct of Operations: Knowledge of the purpose 017 In-core Temperature Monitor X 2.1.28 and function of major system components and 3.1 33 controls.

Ability to monitor automatic operation of the 029 Containment Purge X A3.01 3.8 34 Containment Purge System including: CPS isolation 041 Steam Dump/Turbine Bypass Ability to monitor automatic operation of the SDS, X A3.05 including: Main steam pressure 2.9 35 Control Knowledge of the physical connections and/or 045 Main Turbine Generator X K1.19 cause-effect relationships between the MT/G system 3.4 36 and the following systems: ESFAS Knowledge of the effect that a loss or malfunction of 071 Waste Gas Disposal X K3.05 the Waste Gas Disposal System will have on the 3.2 37 following: ARM and PRM systems Ability to manually operate and/or monitor in the 079 Station Air X A4.01 2.7 38 control room: Cross-tie valves with IAS K/A Category Point Totals: 2/2 1 2 1 0 0 1 0 0/1 2 1 Group Point Total: 10/3 NUREG-1021 9

ES-401 Generic Knowledge and Abilities Outline (Tier3) Form ES-401-3 Facility: Callaway Date of Exam: 8/22/2005 RO SRO-Only Category K/A # Topic IR Q# IR Q#

Ability to recognize indications for system operating 2.1.33 parameters which are entry-level conditions for 4.0 94 technical specifications.

1. Ability to make accurate, clear and concise logs, 2.1.18 2.9 66 Conduct of Operations records, status boards, and reports.

Ability to operate plant phone, paging system, and 2.1.16 2.9 67 two-way radio.

Subtotal 2 1 2.2.33 Knowledge of control rod programming. 2.9 95 Knowledge of the process for determining if the margin of safety, as defined in the basis of any technical 2.2.10 3.3 96 specification is reduced by a proposed change, test or experiment.

2.

Knowledge of bases in technical specifications for Equipment Control 2.2.25 2.5 68 limiting conditions for operations and safety limits.

Ability to manipulate the console controls as required 2.2.2 to operate the facility between shutdown and 4.0 69 designated power levels.

Subtotal 2 2 Knowledge of the process for performing a planned 2.3.8 3.2 97 gaseous radioactive release.

Ability to perform procedures to reduce excessive 2.3.10 levels of radiation and guard against personnel 3.3 98

3. exposure.

Radiation Control Knowledge of the process for performing a 2.3.9 2.5 70 containment purge.

2.3.11 Ability to control radiation releases. 2.7 71 Subtotal 2 2 Ability to recognize abnormal indications for system 2.4.4 operating parameters which are entry-level conditions 4.3 99 for emergency and abnormal operating procedures.

Ability to take actions called for in the facility 2.4.38 emergency plan, including (if required) supporting or 4.0 100 acting as emergency coordinator.

4. Knowledge of annunciators, alarms and indications, 2.4.31 3.3 72 Emergency Procedures and use of the response instructions.

/ Plan 2.4.3 Ability to identify post-accident instrumentation. 3.5 73 Knowledge of general operating crew responsibilities 2.4.12 3.4 74 during emergency operations.

2.4.29 Knowledge of the emergency plan. 2.6 75 Subtotal 4 2 Tier 3 Point Total 10 7 NUREG-1021 10

ES-401 Record of Rejected K/As Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A The subject K/A isn't relevant at the subject facility. No pump auto start on 2/1 008 / A2.07 flow rate The subject K/A isn't relevant at the subject facility. Facility does not have 2/1 008 / A3.02 booster pumps.

It isn't possible to prepare a psychometrically sound question related to the 2/1 012 / A1.01 subject K/A. Not a task performed by operations 2/1 061 / A1.03 The subject K/A isn't relevant at the subject facility. Not multi-unit.

The subject K/A isn't relevant at the subject facility. No ability to monitor this 2/1 103 / A4.06 system and component from the control room.

2/2 027 / 2.1.27 The subject K/A isn't relevant at the subject facility. System is retired in place.

It isn't possible to prepare a psychometrically sound question related to the 2/2 017 / A2.01 subject K/A. Operating the system controls would not result in the effects stated.

The subject K/A isn't relevant at the subject facility. No heat tracing on this 2/1 006 / A2.07 system.

2/1 022 K4.03 The function required by the topic does not exist at this facility 1/2 001 AA2.02 There is no relationship between these components for this event at this facility 1/2 060 AA2.04 Could not develop a psychometrically sound SRO level test item for this topic 1/1 008 AA2.10 Could not develop a psychometrically sound SRO level test item for this topic Could not develop a psychometrically sound item for the subject KA.

1/1 027 AA2.04 Replaced with 027 AA2.10 Could not develop a psychometrically sound item for the subject KA.

1/2 059 AK1.02 Replaced with 074 EK1.01 2/1 064 K6.08 Event would have no effect on the facility. Replaced with 064 K6.07 Could not develop a psychometrically sound item for the subject KA.

1/2 E01 EK3.1 Replaced with E01 EK3.2 NUREG-1021 11

Retrieved from "https://kanterella.com/w/index.php?title=ML061560137&oldid=2190859"