ML092940703

Initial Exam 2008-301 Draft Administrative Documents

ML092940703
Person / Time
Site:	Catawba
Issue date:	10/20/2009
From:	NRC/RGN-II
To:	Duke Energy Carolinas
References
50-413/08-301, 50-414/08-301
Download: ML092940703 (27)

Text

ES-201 Examination Outline Quality Checklist Facility:

Catawba Date of Examination:

Item 1. W R I T T E N 2. S I M U L A T o R 3. W / T 4. G E N E R A L Task Description

a. Verify that the outline(s) fit(s) the appropriate model, in accordance with ES-401. b. Assess whether the outline was systematically and randomly prepared in accordance with Section 0.1 of ES-401 and whether all KiA categories are appropriately sampled. c. Assess whether the outline over-emphasizes any systems, evolutions, or generic topics. d. Assess whether the justifications for deselected or rejected KiA statements are appropriate.

a. Using Form ES-301-5, verify that the proposed scenario sets cover the required number of normal evolutions, instrument and component failures, technical specifications, and major transients.

b. Assess whether there are enough scenario sets (and spares) to test the projected number and mix of applicants in accordance with the expected crew composition and rotation schedule without compromising exam integrity, and ensure that each applicant can be tested using at least one new or significantly modified scenario, that no scenarios are duplicated from the applicants' audit test(s), and that scenarios will not be repeated on subsequent days. c. To the extent possible, assess whether the outline(s) conform(s) with the qualitative and quantitative criteria specified on Form ES-301-4 and described in Appendix D. a. Verify that the systems walk-through outline meets the criteria specified on Form ES-301-2:

(1) the outline(s) contain(s) the required number of control room and in-plant tasks distributed among the safety functions as specified on the form (2) task repetition from the last two NRC examinations is within the limits specified on the form (3) no tasks are duplicated from the applicants' audit test(s) (4) the number of new or modified tasks meets or exceeds the minimums specified on the form (5) the number of alternate path, low-power, emergency, and RCA tasks meet the criteria on the form. b. Verify that the administrative outline meets the criteria specified on Form ES-301-1:

(1) the tasks are distributed among the topics as specified on the form (2) at least one task is new or significantly modified (3) no more than one task is repeated from the last two NRC licensing examinations

c. Determine if there are enough different outlines to test the projected number and mix of applicants and ensure that no items are duplicated on subsequent days. a. Assess whether plant-specific priorities (including PRA and IPE insights) are covered in the appropriate exam sections.

b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate.

c. Ensure that KiA importance ratings (except for plant-specific priorities) are at least 2.5. d. Check for duplication and overlap among exam sections.

e. Check the entire exam for balance of coverage.

f. Assess whether the exam fits the appropriate job level (RO or SRO). a. Author b. Facility Reviewer n c. NRC Chief Examiner (#) d. NRC Supervisor l I I Form ES-201-2 12/01/2008 Initials a b* ci Date Note: # Independent NRC reviewer initial items in Columil"C";

chief examiner concurrence required.

ES-201 Examination Outline Quality Checklist Facility:

Catawba Date of Examination:

Item 1. W R I T T E N 2. S I M U L A T o R 3. W / T 4. G E N E R A L Task Description

a. Verify that the outline(s) fit(s) the appropriate model, in accordance with ES-401. b. Assess whether the outline was systematically and randomly prepared in accordance with Section 0.1 of ES-401 and whether all KiA categories are appropriately sampled. c. Assess whether the outline over-emphasizes any systems, evolutions, or generic topics. d. Assess whether the justifications for deselected or rejected KiA statements are appropriate.

a. Using Form ES-301-5, verify that the proposed scenario sets cover the required number of normal evolutions, instrument and component failures, technical specifications, and major transients.

b. Assess whether there are enough scenario sets (and spares) to test the projected number and mix of applicants in accordance with the expected crew composition and rotation schedule without compromising exam integrity, and ensure that each applicant can be tested using at least one new or significantly modified scenario, that no scenarios are duplicated from the applicants' audit test(s), and that scenarios will not be repeated on subsequent days. c. To the extent possible, assess whether the outline(s) conform(s) with the qualitative and quantitative criteria specified on Form ES-301-4 and described in Appendix D. a. Verify that the systems walk-through outline meets the criteria specified on Form ES-301-2:

(1) the outline(s) contain(s) the required number of control room and in-plant tasks distributed among the safety functions as specified on the form (2) task repetition from the last two NRC examinations is within the limits specified on the form (3) no tasks are duplicated from the applicants' audit test(s) (4) the number of new or modified tasks meets or exceeds the minimums specified on the form (5) the number of alternate path, low-power, emergency, and RCA tasks meet the criteria on the form. b. Verify that the administrative outline meets the criteria specified on Form ES-301-1:

(1) the tasks are distributed among the topics as specified on the form (2) at least one task is new or significantly modified (3) no more than one task is repeated from the last two NRC licensing examinations

c. Determine if there are enough different outlines to test the projected number and mix of applicants and ensure that no items are duplicated on subsequent days. a. Assess whether plant-specific priorities (including PRA and IPE insights) are covered in the appropriate exam sections.

b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate.

c. Ensure that KiA importance ratings (except for plant-specific priorities) are at least 2.5. d. Check for duplication and overlap among exam sections.

e. Check the entire exam for balance of coverage.

f. Assess whether the exam fits the appropriate job level (RO or SRO). a. Author b. Facility Reviewer (*) c. NRC Chief Examiner (#) -yJ.

d. NRC Supervisor I/;M...,;r IK;K'-l I f Form ES-201-2 12/01/2008 Initials a b* cti 1<:#1 14 Date Note: # Independent NRC reviewer initial items in Columri"d';

chief examiner concurrence required.

ES-401 & Rev. 9 PWR Examination Outline Form ES-401-2 Facility:

CAffllJ/JA Date of Exam: 12/1 / ZI>>f; RO KIA Category Points SRO-Only Points Tier Group K K K K K K A A A A G A2 G* Total 1 2 3 4 5 6 1 2 3 4

• Total 1. 1 3 3 3 3 3 3 18 3 3 6 Emergency

& 2 2 1 2 2 1 1 9 2 2 4 Abnormal Plant N/A N/A Evolutions Tier Totals 5 4 5 5 4 4 27 5 5 10 1 3 3 3 2 2 2 3 3 3 2 2 28 3 2 5 2. 1 1 1 1 1 1 1 0 1 1 1 10 2 1 3 Plant 2 Systems Tier Totals 4 4 4 3 3 3 4 3 4 3 3 38 5 3 8 3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 2 2 3 3 2 2 2 1 1. Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KIA category shall not be less than two). 2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/- 1 from that specified in the table based on NRC revisions.

The final RO exam must total 75 points and the SRO-only exam must total 25 points. 3. Systems/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 the elimination of inappropriate KIA statements.

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

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

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

6. Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories.

7. *The generic (G) KIAs in Tiers 1 and 2 shall be selected from Section 2 ofthe KIA Catalog, but the topics must be relevant to the applicable evolution or system. 8. On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category.

Enter the group and tier totals for each category in the table above; iffuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note # 1 does not apply). Use duplicate pages for RO and SRO-only exams. 9. For Tier 3, select topics from Section 2 of the KIA catalog, and enter the KIA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3.

Limit SRO selections to KIAs that are linked to 10 CFR 55.43. ES-401 & Rev. 9 PWR Examination Outline Form ES-401-2 Facility:

CAffllJ/JA Date of Exam: 12/1/ ZI>>f; RO KIA Category Points SRO-Only Points Tier Group K K K K K K A A A A G A2 G* Total 1 2 3 4 5 6 1 2 3 4

• Total 1. 1 3 3 3 3 3 3 18 3 3 6 Emergency

& 2 2 1 2 2 1 1 9 2 2 4 Abnormal Plant N/A N/A Evolutions Tier Totals 5 4 5 5 4 4 27 5 5 10 1 3 3 3 2 2 2 3 3 3 2 2 28 3 2 5 2. 1 1 1 1 1 1 1 0 1 1 1 10 2 1 3 Plant 2 Systems Tier Totals 4 4 4 3 3 3 4 3 4 3 3 38 5 3 8 3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 2 2 3 3 2 2 2 1 1. Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KIA category shall not be less than two). 2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/- 1 from that specified in the table based on NRC revisions.

The final RO exam must total 75 points and the SRO-only exam must total 25 points. 3. Systems/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 the elimination of inappropriate KIA statements.

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

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

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

6. Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories.

7. *The generic (G) KIAs in Tiers 1 and 2 shall be selected from Section 2 ofthe KIA Catalog, but the topics must be relevant to the applicable evolution or system. 8. On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category.

Enter the group and tier totals for each category in the table above; iffuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note # 1 does not apply). Use duplicate pages for RO and SRO-only exams. 9. For Tier 3, select topics from Section 2 of the KIA catalog, and enter the KIA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3.

Limit SRO selections to KIAs that are linked to 10 CFR 55.43.

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

IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 007EK2.03 Reactor Trip -Stabilization

-Recovery 3.5 3.6 / 1 009EA2.10 Small Break LOCA / 3 011 EG2.4.30 Large Break LOCA / 3 022AK1.02 Loss of Rx Coolant Makeup / 2 025AG2.4.30 Loss of RHR System /4 Knowledge of the interrelations between (EMERGENCY PLANT EVOLUTION) and the foliowing:(CFR:

41.7/45.7/45.8) 3.1 3.7 0 0 0 0 0 0 0 0 0 0 Ability to determine and interpret the following as they apply to (EMERGENCY PLANT EVOLUTION):(CFR:

41.10/43.5/

45.13) 2.7 4.1 0 0 0 0 0 0 0 0 0 0 This is a Generic, no stem statement is associated.

2.7 3.1 0 0 0 0 0 0 0 0 0 0 Knowledge*

of the operational implications of the following concepts as they apply to the (ABNORMAL PLANT EVOLUTION):(CFR:

41.8 to 41.10/45.3) 2.7 4.1 0 0 0 0 0 0 0 0 0 0 This is a Generic, no stem statement is associated.

026AA2.03 Loss of Component Cooling Water /8 2.6 2.9 0 0 0 0 0 0 0 0 0 0 Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION):(CFR:

41.10/43.5/

45.13) Page 1 of 3 FORM ES-401-2 TOPIC: Reactor trip status panel Airborne activity Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.

Relationship of charging flow to pressure differential between charging and RCS Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.

The valve lineups necessary to restart the CCWS while bypassing the portion of the system causing the abnormal condition 4/1/2008 4:15 PM ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:

IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 007EK2.03 Reactor Trip -Stabilization

-Recovery 3.5 3.6 / 1 009EA2.10 Small Break LOCA / 3 011 EG2.4.30 Large Break LOCA / 3 022AK1.02 Loss of Rx Coolant Makeup / 2 025AG2.4.30 Loss of RHR System /4 Knowledge of the interrelations between (EMERGENCY PLANT EVOLUTION) and the foliowing:(CFR:

41.7/45.7/45.8) 3.1 3.7 0 0 0 0 0 0 0 0 0 0 Ability to determine and interpret the following as they apply to (EMERGENCY PLANT EVOLUTION):(CFR:

41.10/43.5/

45.13) 2.7 4.1 0 0 0 0 0 0 0 0 0 0 This is a Generic, no stem statement is associated.

2.7 3.1 0 0 0 0 0 0 0 0 0 0 Knowledge*

of the operational implications of the following concepts as they apply to the (ABNORMAL PLANT EVOLUTION):(CFR:

41.8 to 41.10/45.3) 2.7 4.1 0 0 0 0 0 0 0 0 0 0 This is a Generic, no stem statement is associated.

026AA2.03 Loss of Component Cooling Water /8 2.6 2.9 0 0 0 0 0 0 0 0 0 0 Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION):(CFR:

41.10/43.5/

45.13) Page 1 of 3 FORM ES-401-2 TOPIC: Reactor trip status panel Airborne activity Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.

Relationship of charging flow to pressure differential between charging and RCS Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.

The valve lineups necessary to restart the CCWS while bypassing the portion of the system causing the abnormal condition 4/1/2008 4:15 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

027AA1.04 Pressurizer Pressure Control System Malfunction 1 3 029EG2.4.34 A TWS 11 03BEK1.02 Steam Gen. Tube Rupture 13 057AA2.13 Loss of Vital AC Inst. Bus 1 6 05BAA1.02 Loss of DC Power 1 6 062AK3.03 Loss of Nuclear Svc Water 1 4 T1G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.9 3.6 0 0 0 0 0 0 0 0 0 0 Ability to operate and 1 or monitor the following as they apply to (ABNORMAL PLANT EVOLUTION):(CFR:

41.7/45.51 45.6) 4.2 4.1 0 0 0 0 0 0 0 0 0 0 This is a Generic, no stem statement is associated. 3.2 3.5 0 0 0 0 0 0 0 0 0 0 3 Knowledge of the operational implications of the following concepts as they apply to the EMERGENCY PLANT EVOLUTION):(CFR:

41.B to 41.10/45.3) 3.4 0 0 0 0 0 0 0 0 0 0 Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION):(CFR:

41.10/43.51 45.13) 3.1 3.1 0 0 0 0 0 0 0 0 0 0 Ability to operate and lor monitor the following as they apply to (ABNORMAL PLANT EVOLUTION):(CFR:

41.7/45.51 45.6) 4 4.2 0 0 0 0 0 0 0 0 0 0 Knowledge of the reasons for the following responses as they apply to (ABNORMAL PLANT EVOLUTION):(CFR:

41.5/41.101 45.6/45.13)

Page 2 of 3 FORM ES-401-2 TOPIC: Pressure recovery, using emergency-only heaters Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects Leak rate vs. pressure drop VCT level and pressure indicators and recorders Static inverter dc input breaker, frequency meter, ac output breaker and ground fault detector Guidance actions contained in EOP for Loss of nuclear service water 4/1/200B 4:15 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

027AA1.04 Pressurizer Pressure Control System Malfunction 1 3 029EG2.4.34 A TWS 11 03BEK1.02 Steam Gen. Tube Rupture 13 057AA2.13 Loss of Vital AC Inst. Bus 1 6 05BAA1.02 Loss of DC Power 1 6 062AK3.03 Loss of Nuclear Svc Water 1 4 T1G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.9 3.6 0 0 0 0 0 0 0 0 0 0 Ability to operate and 1 or monitor the following as they apply to (ABNORMAL PLANT EVOLUTION):(CFR:

41.7/45.51 45.6) 4.2 4.1 0 0 0 0 0 0 0 0 0 0 This is a Generic, no stem statement is associated. 3.2 3.5 0 0 0 0 0 0 0 0 0 0 3 Knowledge of the operational implications of the following concepts as they apply to the EMERGENCY PLANT EVOLUTION):(CFR:

41.B to 41.10/45.3) 3.4 0 0 0 0 0 0 0 0 0 0 Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION):(CFR:

41.10/43.51 45.13) 3.1 3.1 0 0 0 0 0 0 0 0 0 0 Ability to operate and lor monitor the following as they apply to (ABNORMAL PLANT EVOLUTION):(CFR:

41.7/45.51 45.6) 4 4.2 0 0 0 0 0 0 0 0 0 0 Knowledge of the reasons for the following responses as they apply to (ABNORMAL PLANT EVOLUTION):(CFR:

41.5/41.101 45.6/45.13)

Page 2 of 3 FORM ES-401-2 TOPIC: Pressure recovery, using emergency-only heaters Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects Leak rate vs. pressure drop VCT level and pressure indicators and recorders Static inverter dc input breaker, frequency meter, ac output breaker and ground fault detector Guidance actions contained in EOP for Loss of nuclear service water 4/1/200B 4:15 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

065AK3.03 077AA1.01 Loss of Instrument Air / 8 Generator Voltage and Electric Grid Disturbances / 6 WE04EK2.2 LOCA Outside Containment / 3 WE05EK3.1 Inadequate Heat Transfer -Loss of Secondary Heat Sink / 4 T1G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 2.9 3.4 D D D D D D D D D D Knowledge of the reasons for the following responses as they apply to (ABNORMAL PLANT EVOLUTION):(CFR:

41.5/41.10/

45.6 / 45.13) 3.6 3.7 D D D D D D D D D D Ability to operate and / or monitor the following as they apply to (ABNORMAL PLANT EVOLUTION):(CFR:

41.7/45.5/

45.6) 3.8 4.0 D D D D D D D D D D Knowledge of the interrelations between (EMERGENCY PLANT EVOLUTION) and the foliowing:(CFR:

41.7/45.7/45.8) 3.4 3.8 D D D D D D D D D D Knowledge of the reasons for the following responses as they apply to (EMERGENCY PLANT EVOLUTION):(CFR:

41.5/41.10/45.6/

45.13) WE11 EK2.1 Loss of Emergency Coolant Recirc. / 4 3.6 3.9 D D D D D D D D D D WE12EK1.3 Steam Line Rupture -Excessive Heat Transfer / 4 Knowledge of the interrelations between (EMERGENCY PLANT EVOLUTION) and . the foliowing:(CFR:

41.7/45.7/45.8) 3.4 3.7 D D D D D D D D D D Knowledge of the operational implications of the following concepts as they apply to the EMERGENCY PLANT EVOLUTION):(CFR:

41.8 to 41.10/45.3)

Page 3 of 3 FORM ES-401-2 TOPIC: Knowing effects on plant operation of isolating certain equipment from instrument air Grid frequency and voltage Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems and relations between the proper operation of these systems to the operation of the facility.

Facility operating characteristics during transient conditions, including coolant chemistry and the effects of temperature, pressure and reactivity changes and operating limitations and reasons for these operating characteristics.

Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.

Annunciators and conditions indicating signals, and remedial actions associated with the (Uncontrolled Depressurization of all Steam Generators).

4/1/2008 4:15 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

065AK3.03 077AA1.01 Loss of Instrument Air / 8 Generator Voltage and Electric Grid Disturbances / 6 WE04EK2.2 LOCA Outside Containment / 3 WE05EK3.1 Inadequate Heat Transfer -Loss of Secondary Heat Sink / 4 T1G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 2.9 3.4 D D D D D D D D D D Knowledge of the reasons for the following responses as they apply to (ABNORMAL PLANT EVOLUTION):(CFR:

41.5/41.10/

45.6 / 45.13) 3.6 3.7 D D D D D D D D D D Ability to operate and / or monitor the following as they apply to (ABNORMAL PLANT EVOLUTION):(CFR:

41.7/45.5/

45.6) 3.8 4.0 D D D D D D D D D D Knowledge of the interrelations between (EMERGENCY PLANT EVOLUTION) and the foliowing:(CFR:

41.7/45.7/45.8) 3.4 3.8 D D D D D D D D D D Knowledge of the reasons for the following responses as they apply to (EMERGENCY PLANT EVOLUTION):(CFR:

41.5/41.10/45.6/

45.13) WE11 EK2.1 Loss of Emergency Coolant Recirc. / 4 3.6 3.9 D D D D D D D D D D WE12EK1.3 Steam Line Rupture -Excessive Heat Transfer / 4 Knowledge of the interrelations between (EMERGENCY PLANT EVOLUTION) and . the foliowing:(CFR:

41.7/45.7/45.8) 3.4 3.7 D D D D D D D D D D Knowledge of the operational implications of the following concepts as they apply to the EMERGENCY PLANT EVOLUTION):(CFR:

41.8 to 41.10/45.3)

Page 3 of 3 FORM ES-401-2 TOPIC: Knowing effects on plant operation of isolating certain equipment from instrument air Grid frequency and voltage Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems and relations between the proper operation of these systems to the operation of the facility.

Facility operating characteristics during transient conditions, including coolant chemistry and the effects of temperature, pressure and reactivity changes and operating limitations and reasons for these operating characteristics.

Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.

Annunciators and conditions indicating signals, and remedial actions associated with the (Uncontrolled Depressurization of all Steam Generators).

4/1/2008 4:15 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

001AA1.06 Continuous Rod Withdrawal / 1 005AG2.4.6 Inoperable/Stuck Control Rod / 1 024AK1.04 Emergency Boration / 1 .01 Loss of Intermediate Range NI / 7 037AA2.03 Steam Generator Tube Leak / 3 074EA1.01 Inad. Core Cooling / 4 T1G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3 2.9 0 0 0 0 0 0 0 0 0 0 Ability to operate and / or monitor the following as they apply to (ABNORMAL PLANT EVOLUTION):(CFR:

41.7/45.5/

45.6) 3.7 4.7 0 0 0 0 0 0 0 0 0 0 This is a Generic, no stem statement is associated.

2.8 3.6 0 0 0 0 0 0 0 0 0 0 2.7 3 Knowledge of the operational implications of the following concepts as they apply to the (ABNORMAL PLANT EVOLUTION):(CFR:

41.8 to 41.10 / 45.3)

Knowledge of the operational implications of the following concepts as they apply to the (ABNORMAL PLANT EVOLUTION):(CFR:

41.8 to 41.10/45.3) 3.4 3.9 0 0 0 0 0 0 0 0 0 0 Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION):(CFR:

41.10/43.5/

45.13) 4.2 4.4 0 0 0 0 0 0 0 0 0 0 Ability to operate and / or monitor the following as they apply to (EMERGENCY PLANT EVOLUTION):(CFR:

41.7/45.5/

45.6) Page 1 of 2 FORM ES-401-2 TOPIC: Rod transfer switches Knowledge symptom based EOP mitigation strategies.

Low temperature limits for boron concentration Effects of voltage changes on performance That the expected indication on main steam lines from the S/Gs should show increasing radiation levels RCS water inventory 4/1/2008 4:15 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

001AA1.06 Continuous Rod Withdrawal / 1 005AG2.4.6 Inoperable/Stuck Control Rod / 1 024AK1.04 Emergency Boration / 1 033AK1.01 Loss of Intermediate Range NI / 7 037AA2.03 Steam Generator Tube Leak / 3 074EA1.01 Inad. Core Cooling / 4 T1G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3 2.9 0 0 0 0 0 0 0 0 0 0 Ability to operate and / or monitor the following as they apply to (ABNORMAL PLANT EVOLUTION):(CFR:

41.7/45.5/

45.6) 3.7 4.7 0 0 0 0 0 0 0 0 0 0 This is a Generic, no stem statement is associated.

2.8 3.6 0 0 0 0 0 0 0 0 0 0 2.7 3 Knowledge of the operational implications of the following concepts as they apply to the (ABNORMAL PLANT EVOLUTION):(CFR:

41.8 to 41.10 / 45.3)

Knowledge of the operational implications of the following concepts as they apply to the (ABNORMAL PLANT EVOLUTION):(CFR:

41.8 to 41.10/45.3) 3.4 3.9 0 0 0 0 0 0 0 0 0 0 Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION):(CFR:

41.10/43.5/

45.13) 4.2 4.4 0 0 0 0 0 0 0 0 0 0 Ability to operate and / or monitor the following as they apply to (EMERGENCY PLANT EVOLUTION):(CFR:

41.7/45.5/

45.6) Page 1 of 2 FORM ES-401-2 TOPIC: Rod transfer switches Knowledge symptom based EOP mitigation strategies.

Low temperature limits for boron concentration Effects of voltage changes on performance That the expected indication on main steam lines from the S/Gs should show increasing radiation levels RCS water inventory 4/1/2008 4:15 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

076AK3.06 High Reactor Coolant Activity 1 9 WE03EK2.1 LOCA Cooldown -Depress. 1 4 WE09EK3.3 Natural 4 T1 G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.2 3.8 0 0 0 0 0 0 0 0 0 0 Knowledge of the reasons for the following responses as they apply to (ABNORMAL PLANT EVOLUTION):(CFR:

41.5/41.101 45.6/45.13) 3.6 4.0 0 0 0 0 0 0 0 0 0 0 Knowledge of the interrelations between (EMERGENCY PLANT EVOLUTION) and the foliowing:(CFR:

41.7/45.7/45.8) 3.5 3.6 0 0 0 0 0 0 0 0 0 0 Knowledge of the reasons for the following responses as they apply to (EMERGENCY PLANT EVOLUTION):(CFR:

41.5/41.10/45.61 45.13) Page 2 of 2 FORM ES-401-2 TOPIC: Actions contained in EOP for high reactor coolant activity Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.

Manipulation of controls required to obtain desired operating results during abnormal and emergency situations.

4/1/2008 4:15 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

076AK3.06 High Reactor Coolant Activity 1 9 WE03EK2.1 LOCA Cooldown -Depress. 1 4 WE09EK3.3 Natural Circ. 1 4 T1 G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.2 3.8 0 0 0 0 0 0 0 0 0 0 Knowledge of the reasons for the following responses as they apply to (ABNORMAL PLANT EVOLUTION):(CFR:

41.5/41.101 45.6/45.13) 3.6 4.0 0 0 0 0 0 0 0 0 0 0 Knowledge of the interrelations between (EMERGENCY PLANT EVOLUTION) and the foliowing:(CFR:

41.7/45.7/45.8) 3.5 3.6 0 0 0 0 0 0 0 0 0 0 Knowledge of the reasons for the following responses as they apply to (EMERGENCY PLANT EVOLUTION):(CFR:

41.5/41.10/45.61 45.13) Page 2 of 2 FORM ES-401-2 TOPIC: Actions contained in EOP for high reactor coolant activity Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.

Manipulation of controls required to obtain desired operating results during abnormal and emergency situations.

4/1/2008 4:15 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

003A2.02 Reactor Coolant Pump 004A1.01 Chemical and Volume Control .34 Chemical Volume Control 005K4.11 Residual Heat Removal 006A1.05 Emergency Core Cooling 007G2.4.6 Pressurizer Relief/Quench Tank T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.7 3.9 0 0 0 0 0 0 0 0 0 0 Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR:

41.5/43.5/45.3/45.13) 2.9 3.8 0 0 0 0 0 0 0 0 0 0 Ability to predict and/or monitor changes in parameters associated with operating the (SYSTEM) controls including:(CFR:

41.5/ 45.5) 2.7 2.9 0 0 0 0 0 0 0 0 0 0 Knowledge of the physical connections and/or cause-effect relationships between (SYSTEM) and the foliowing:(CFR:

41.2 to 41.9/45.7 to 45.8) 3.5 3.9 0 0 0 0 0 0 0 0 0 0 Knowledge of (SYSTEM) design feature(s) and or interlock(s) which provide for the foliowing:(CFR:

41.7) 2.9 3.3 0 0 0 0 0 0 0 0 0 0 Ability to predict and/or monitor changes in parameters associated with operating the (SYSTEM) controls including:(CFR:

41.5/ 45.5) 3.7 4.7 0 0 0 0 0 0 0 0 0 0 This is a Generic, no stem statement is associated.

Page 1 of 5 FORM ES-401-2 TOPIC: Conditions which exist for an abnormal shutdown of an RCP in comparison to a normal shutdown of an RCP Activity levels in primary system Interface between CVCS and reactor coolant drain tank; and PZR PCS Lineup for low head recirculation mode (external and internal)

CCW flow (establish flow to RHR heat exchanger prior to placing in service Knowledge symptom based EOP mitigation strategies.

4/1/2008 4:22 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

003A2.02 Reactor Coolant Pump 004A1.01 Chemical and Volume Control 004K1.34 Chemical and Volume Control 005K4.11 Residual Heat Removal 006A1.05 Emergency Core Cooling 007G2.4.6 Pressurizer Relief/Quench Tank T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.7 3.9 0 0 0 0 0 0 0 0 0 0 Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR:

41.5/43.5/45.3/45.13) 2.9 3.8 0 0 0 0 0 0 0 0 0 0 Ability to predict and/or monitor changes in parameters associated with operating the (SYSTEM) controls including:(CFR:

41.5/ 45.5) 2.7 2.9 0 0 0 0 0 0 0 0 0 0 Knowledge of the physical connections and/or cause-effect relationships between (SYSTEM) and the foliowing:(CFR:

41.2 to 41.9/45.7 to 45.8) 3.5 3.9 0 0 0 0 0 0 0 0 0 0 Knowledge of (SYSTEM) design feature(s) and or interlock(s) which provide for the foliowing:(CFR:

41.7) 2.9 3.3 0 0 0 0 0 0 0 0 0 0 Ability to predict and/or monitor changes in parameters associated with operating the (SYSTEM) controls including:(CFR:

41.5/ 45.5) 3.7 4.7 0 0 0 0 0 0 0 0 0 0 This is a Generic, no stem statement is associated.

Page 1 of 5 FORM ES-401-2 TOPIC: Conditions which exist for an abnormal shutdown of an RCP in comparison to a normal shutdown of an RCP Activity levels in primary system Interface between CVCS and reactor coolant drain tank; and PZR PCS Lineup for low head recirculation mode (external and internal)

CCW flow (establish flow to RHR heat exchanger prior to placing in service Knowledge symptom based EOP mitigation strategies.

4/1/2008 4:22 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

00BK3.03 Component Cooling Water 00BK4.07 Component Cooling Water 010G2.1.25 Pressurizer Pressure Control 012A2.02 Reactor Protection 012K5.01 Reactor Protection T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 4.1 4.2 D D D D D D D D D D Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the foliowing:(CFR:

41.7/45.6) 2.6 2.7 D D D D D D D D D D Knowledge of (SYSTEM) design feature(s) and or interlock(s) which provide for the foliowing:(CFR:

41.7) 3.9 4.2 D D D D D D D D D D This is a Generic, no stem statement is associated. 3.6 3.9 D D D D D D D D D D Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR:

41.5/43.5/45.3/45.13) 3.3 3.B D D D D D D D D D D Knowledge of the operational implications of the following concepts as they apply to the (SYSTEM):(CFR:

41.5/45.7) 013K6.01 Engineered Safety Features Actuation 2.7 3.1 D D D D D D D D D D 022K2.02 Containment Cooling Knowledge of the effect that a loss or malfunction of the following will have on the (SYSTEM):(CFR:

41.7/45.7) 2.5 2.4 D D D D D D D D D D Knowledge of electrical power supplies to the foliowing:(CFR:

41.7) Page 2 of 5 FORM ES-401-2 TOPIC: RCP Operation of the CCW swing-bus power supply and its associated breakers and controls Ability to interpret reference materials such as graphs, monographs and tables which contain performance data. Loss of instrument power DNB Sensors and detectors Chillers 4/1/200B 4:22 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

00BK3.03 Component Cooling Water 00BK4.07 Component Cooling Water 010G2.1.25 Pressurizer Pressure Control 012A2.02 Reactor Protection 012K5.01 Reactor Protection T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 4.1 4.2 D D D D D D D D D D Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the foliowing:(CFR:

41.7/45.6) 2.6 2.7 D D D D D D D D D D Knowledge of (SYSTEM) design feature(s) and or interlock(s) which provide for the foliowing:(CFR:

41.7) 3.9 4.2 D D D D D D D D D D This is a Generic, no stem statement is associated. 3.6 3.9 D D D D D D D D D D Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR:

41.5/43.5/45.3/45.13) 3.3 3.B D D D D D D D D D D Knowledge of the operational implications of the following concepts as they apply to the (SYSTEM):(CFR:

41.5/45.7) 013K6.01 Engineered Safety Features Actuation 2.7 3.1 D D D D D D D D D D 022K2.02 Containment Cooling Knowledge of the effect that a loss or malfunction of the following will have on the (SYSTEM):(CFR:

41.7/45.7) 2.5 2.4 D D D D D D D D D D Knowledge of electrical power supplies to the foliowing:(CFR:

41.7) Page 2 of 5 FORM ES-401-2 TOPIC: RCP Operation of the CCW swing-bus power supply and its associated breakers and controls Ability to interpret reference materials such as graphs, monographs and tables which contain performance data. Loss of instrument power DNB Sensors and detectors Chillers 4/1/200B 4:22 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

025A4.01 Ice Condenser 026A1.03 Containment Spray 026K1.01 Containment Spray 039K5.01 Main and Reheat Steam 059A4.11 Main Feedwater 061A3.04 Auxiliary/Emergency Feedwater 062A3.01 AC Electrical Distribution T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.0 2.7 D D D D D D D D D D Ability to manually operate and/or monitor in the control room:(CFR:

41.7/45.5 to 45.8) 3.5 3.5 D D D D D D D D D D Ability to predict and/or monitor changes in parameters associated with operating the (SYSTEM) controls including:(CFR:

41.5/ 45.5) 4.2 4.2 D D D D D D D D D D Knowledge of the physical connections and/or cause-effect relationships between (SYSTEM) and the foliowing:(CFR:

41.2 to 41.9/45.7 to 45.8) 2.9 3.1 D D D D D D D D D D Knowledge of the operational implications of the following concepts as they apply to the (SYSTEM):(CFR:

41.5/45.7) 3.1 3.3 D D D D D D D D D D Ability to manually operate and/or monitor in the control room:(CFR:

41.7/45.5 to 45.8) 3.9 3.9 D D D D D D D D D D Ability to monitor automatic operations of the (SYSTEM) including:(CFR:

41.7/45.5) 3.0 3.1 D D D D D D D D D D Ability to monitor automatic operations of the (SYSTEM) including:(CFR:

41.7/45.5)

Page 3 of 5 FORM ES-401-2 TOPIC: Ice condenser isolation valves Containment sump level ECCS Definition and causes of steam/water hammer Recovery from automatic feedwater isolation AFW S/G level control on automatic start Vital ac bus amperage 4/1/2008 4:22 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

025A4.01 Ice Condenser 026A1.03 Containment Spray 026K1.01 Containment Spray 039K5.01 Main and Reheat Steam 059A4.11 Main Feedwater 061A3.04 Auxiliary/Emergency Feedwater 062A3.01 AC Electrical Distribution T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.0 2.7 D D D D D D D D D D Ability to manually operate and/or monitor in the control room:(CFR:

41.7/45.5 to 45.8) 3.5 3.5 D D D D D D D D D D Ability to predict and/or monitor changes in parameters associated with operating the (SYSTEM) controls including:(CFR:

41.5/ 45.5) 4.2 4.2 D D D D D D D D D D Knowledge of the physical connections and/or cause-effect relationships between (SYSTEM) and the foliowing:(CFR:

41.2 to 41.9/45.7 to 45.8) 2.9 3.1 D D D D D D D D D D Knowledge of the operational implications of the following concepts as they apply to the (SYSTEM):(CFR:

41.5/45.7) 3.1 3.3 D D D D D D D D D D Ability to manually operate and/or monitor in the control room:(CFR:

41.7/45.5 to 45.8) 3.9 3.9 D D D D D D D D D D Ability to monitor automatic operations of the (SYSTEM) including:(CFR:

41.7/45.5) 3.0 3.1 D D D D D D D D D D Ability to monitor automatic operations of the (SYSTEM) including:(CFR:

41.7/45.5)

Page 3 of 5 FORM ES-401-2 TOPIC: Ice condenser isolation valves Containment sump level ECCS Definition and causes of steam/water hammer Recovery from automatic feedwater isolation AFW S/G level control on automatic start Vital ac bus amperage 4/1/2008 4:22 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

063K2.01 DC Electrical Distribution 063K3.01 DC Electrical Distribution 064A3.07 Emergency Diesel Generator 064K6.07 Emergency Diesel Generator 073A2.02 Process Radiation Monitoring 076K2.01 Service Water 078K3.02 Instrument Air T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 2.9 3.1 D D D D D D D D D D 3.7 4.1 3.6 3.7 2.7 2.9 2.7 3.2 2.7 2.7 3.4 3.6 Knowledge of electrical power supplies to the foliowing:(CFR:

41.7)

Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the foliowing:(CFR:

41.7/45.6)

Ability to monitor automatic operations of the (SYSTEM) including:(CFR:

41.7/45.5)

Knowledge of the effect that a loss or malfunction of the following will have on the (SYSTEM):(CFR:

41.7/45.7)

Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR:

41.5/43.5/45.3/45.13)

Knowledge of electrical power supplies to the foliowing:(CFR:

41.7)

Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the foliowing:(CFR:

41.7/45.6)

Page 4 of 5 FORM ES-401-2 TOPIC: Major DC loads ED/G Load sequencing Air receivers Detector failure Service water Systems having pneumatic valves and controls 4/1/2008 4:22 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

063K2.01 DC Electrical Distribution 063K3.01 DC Electrical Distribution 064A3.07 Emergency Diesel Generator 064K6.07 Emergency Diesel Generator 073A2.02 Process Radiation Monitoring 076K2.01 Service Water 078K3.02 Instrument Air T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 2.9 3.1 D D D D D D D D D D 3.7 4.1 3.6 3.7 2.7 2.9 2.7 3.2 2.7 2.7 3.4 3.6 Knowledge of electrical power supplies to the foliowing:(CFR:

41.7)

Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the foliowing:(CFR:

41.7/45.6)

Ability to monitor automatic operations of the (SYSTEM) including:(CFR:

41.7/45.5)

Knowledge of the effect that a loss or malfunction of the following will have on the (SYSTEM):(CFR:

41.7/45.7)

Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR:

41.5/43.5/45.3/45.13)

Knowledge of electrical power supplies to the foliowing:(CFR:

41.7)

Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the foliowing:(CFR:

41.7/45.6)

Page 4 of 5 FORM ES-401-2 TOPIC: Major DC loads ED/G Load sequencing Air receivers Detector failure Service water Systems having pneumatic valves and controls 4/1/2008 4:22 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

103K1.07 Containment T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.5 3.7 0 0 0 0 0 0 0 0 0 0 Knowledge of the physical connections and/or cause-effect relationships between (SYSTEM) and the foliowing:(CFR:

41.2 to 41.9/45.7 to 45.8) Page 5 of 5 FORM ES-401-2 TOPIC: Containment vacuum system 4/1/2008 4:22 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

103K1.07 Containment T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.5 3.7 0 0 0 0 0 0 0 0 0 0 Knowledge of the physical connections and/or cause-effect relationships between (SYSTEM) and the foliowing:(CFR:

41.2 to 41.9/45.7 to 45.8) Page 5 of 5 FORM ES-401-2 TOPIC: Containment vacuum system 4/1/2008 4:22 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

001K2.02 Control Rod Drive 011A1.02 Pressurizer Level Control .12 Non-nuclear Instrumentation 017K3.01 In-core Temperature Monitor 027K5.01 Containment Iodine Removal 035G2.2.40 Steam Generator 045A3.05 Main Turbine Generator T2G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.6 3.7 D D D D D D D D D D Knowledge of electrical power supplies to the foliowing:(CFR:

41.7) 3.3 3.5 D D D D D D D D D D Ability to predict and/or monitor changes in parameters associated with operating the (SYSTEM) controls including:(CFR:

41.51 45.5) 3.5 3.5 D D D D D D D D D D Knowledge of the physical connections and/or cause-effect relationships between (SYSTEM) and the foliowing:(CFR:

41.2 to 41.9/45.7 to 45.8) 3.5 3.7 D D D D D D D D D D Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the foliowing:(CFR:

41.7/45.6) 3.1 3.4 D D D D D D D D D D Knowledge of the operational implications of the following concepts as they apply to the (SYSTEM):(CFR:

41.5/45.7) 3.4 4.7 D D D D D D D D D D This is a Generic, no stem statement is associated.

2.6 2.9 D D D D D D D D D D Ability to monitor automatic operations of the (SYSTEM) including:(CFR:

41.7/45.5)

Page 1 of 2 FORM ES-401-2 TOPIC: One-line diagram of power supply to trip breakers Charging and letdown flows S/G Natural circulation indications Purpose of charcoal filters Ability to apply technical specifications for a system. Electrohydraulic control 4/1/2008 4:15 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

001K2.02 Control Rod Drive 011A1.02 Pressurizer Level Control 016K1.12 Non-nuclear Instrumentation 017K3.01 In-core Temperature Monitor 027K5.01 Containment Iodine Removal 035G2.2.40 Steam Generator 045A3.05 Main Turbine Generator T2G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.6 3.7 D D D D D D D D D D Knowledge of electrical power supplies to the foliowing:(CFR:

41.7) 3.3 3.5 D D D D D D D D D D Ability to predict and/or monitor changes in parameters associated with operating the (SYSTEM) controls including:(CFR:

41.51 45.5) 3.5 3.5 D D D D D D D D D D Knowledge of the physical connections and/or cause-effect relationships between (SYSTEM) and the foliowing:(CFR:

41.2 to 41.9/45.7 to 45.8) 3.5 3.7 D D D D D D D D D D Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the foliowing:(CFR:

41.7/45.6) 3.1 3.4 D D D D D D D D D D Knowledge of the operational implications of the following concepts as they apply to the (SYSTEM):(CFR:

41.5/45.7) 3.4 4.7 D D D D D D D D D D This is a Generic, no stem statement is associated.

2.6 2.9 D D D D D D D D D D Ability to monitor automatic operations of the (SYSTEM) including:(CFR:

41.7/45.5)

Page 1 of 2 FORM ES-401-2 TOPIC: One-line diagram of power supply to trip breakers Charging and letdown flows S/G Natural circulation indications Purpose of charcoal filters Ability to apply technical specifications for a system. Electrohydraulic control 4/1/2008 4:15 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

071K4.01 Waste Gas Disposal Station Air 086K6.04 Fire Protection T2G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 2.6 3.0 0 0 0 0 0 0 0 0 0 0 Knowledge of (SYSTEM) design feature(s) and or interlock(s) which provide for the foliowing:(CFR:

41.7) 2.7 2.7 0 0 0 0 0 0 0 0 0 0 Ability to manually operate andlor monitor in the control room:(CFR:

41.7/45.5 to 45.8) 2.6 2.9 0 0 0 0 0 0 0 0 0 0 Knowledge of the effect that a loss or malfunction of the following will have on the (SYSTEM):(CFR:

41.7/45.7)

Page 2 of 2 FORM ES-401-2 TOPIC: Pressure capability of the waste gas decay tank Cross-tie valves with lAS Fire, smoke and heat 4/1/2008 4:15 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

071K4.01 Waste Gas Disposal 079A4.01 Station Air 086K6.04 Fire Protection T2G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 2.6 3.0 0 0 0 0 0 0 0 0 0 0 Knowledge of (SYSTEM) design feature(s) and or interlock(s) which provide for the foliowing:(CFR:

41.7) 2.7 2.7 0 0 0 0 0 0 0 0 0 0 Ability to manually operate andlor monitor in the control room:(CFR:

41.7/45.5 to 45.8) 2.6 2.9 0 0 0 0 0 0 0 0 0 0 Knowledge of the effect that a loss or malfunction of the following will have on the (SYSTEM):(CFR:

41.7/45.7)

Page 2 of 2 FORM ES-401-2 TOPIC: Pressure capability of the waste gas decay tank Cross-tie valves with lAS Fire, smoke and heat detectors 4/1/2008 4:15 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

G2.1.45 Conduct of operations G2.1.B Conduct of operations G2.2.2 Equipment Control G2.2.39 Equipment Control G2.3.11 Radiation Control G2.3.4 Radiation Control G2.3.7 Radiation Control T3 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 4.3 4.3 0 0 0 0 0 0 0 0 0 0 3.4 4.1 0 0 0 0 0 0 0 0 0 0 4.6 4.1 0 0 0 0 0 0 0 0 0 0 3.9 4.5 0 0 0 0 0 0 0 0 0 0 3.B 4.3 0 0 0 0 0 0 0 0 0 0 3.2 3.7 0 0 0 0 0 0 0 0 0 0 3.5 3.6 0 0 0 0 0 0 0 0 0 0 Page 1 of 2 FORM ES-401-2 TOPIC: Ability to identify and interpret diverse indications to validate the response of another indication Ability to coordinate personnel activities outside the control room. Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels. Knowledge of less than one hour technical specification action statements for systems. Ability to control radiation releases.

Knowledge of radiation exposure limits under normal and emergency conditions Ability to comply with radiation work permit requirements during normal or abnormal conditions 4/1/200B 4:15 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

G2.1.45 Conduct of operations G2.1.B Conduct of operations G2.2.2 Equipment Control G2.2.39 Equipment Control G2.3.11 Radiation Control G2.3.4 Radiation Control G2.3.7 Radiation Control T3 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 4.3 4.3 0 0 0 0 0 0 0 0 0 0 3.4 4.1 0 0 0 0 0 0 0 0 0 0 4.6 4.1 0 0 0 0 0 0 0 0 0 0 3.9 4.5 0 0 0 0 0 0 0 0 0 0 3.B 4.3 0 0 0 0 0 0 0 0 0 0 3.2 3.7 0 0 0 0 0 0 0 0 0 0 3.5 3.6 0 0 0 0 0 0 0 0 0 0 Page 1 of 2 FORM ES-401-2 TOPIC: Ability to identify and interpret diverse indications to validate the response of another indication Ability to coordinate personnel activities outside the control room. Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels. Knowledge of less than one hour technical specification action statements for systems. Ability to control radiation releases.

Knowledge of radiation exposure limits under normal and emergency conditions Ability to comply with radiation work permit requirements during normal or abnormal conditions 4/1/200B 4:15 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

G2.4.13 Emergency Procedures/Plans G2.4.22 Emergency Procedures/Plans G2.4.42 Emergency Procedures/Plans T3 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 4.0 4.6 0 0 0 0 0 0 0 0 0 0 3.6 4.4 0 0 0 0 0 0 0 0 0 0 2.6 3.8 0 0 0 0 0 0 0 0 0 0 Page 2 of 2 FORM ES-401-2 TOPIC: Knowledge of crew roles and responsibilities during EOP usage. Knowledge of the bases for prioritizing safety functions during abnormal/emergency operations.

Knowledge of emergency response facilities.

4/1/2008 4:15 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

G2.4.13 Emergency Procedures/Plans G2.4.22 Emergency Procedures/Plans G2.4.42 Emergency Procedures/Plans T3 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 4.0 4.6 0 0 0 0 0 0 0 0 0 0 3.6 4.4 0 0 0 0 0 0 0 0 0 0 2.6 3.8 0 0 0 0 0 0 0 0 0 0 Page 2 of 2 FORM ES-401-2 TOPIC: Knowledge of crew roles and responsibilities during EOP usage. Knowledge of the bases for prioritizing safety functions during abnormal/emergency operations.

Knowledge of emergency response facilities.

4/1/2008 4:15 PM ES-401, REV 9 KA NAME I SAFETY FUNCTION:

009EG2.2.25 Small Break LOCA / 3 011 EG2.2.36 Large Break LOCA /3 SRO T1G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.2 4.2 0 0 0 0 0 0 0 0 0 0 This is a Generic, no stem statement is associated.

3.1 4.2 0 0 0 0 0 0 0 0 0 0 This is a Generic, no stem statement is associated.

026AA2.05 Loss of Component Cooling Water /8 2.4 2.5 0 0 0 0 0 0 0 0 0 0 Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION):(CFR:

41.10/43.5/

45.13) 057AG2.4.21 Loss of Vital AC Inst. Bus / 6 4.0 4.6 0 0 0 0 0 0 0 0 0 0 This is a Generic, no stem statement is associated.

058AA2.03 Loss of DC Power / 6 3.5 3.9 0 0 0 0 0 0 0 0 0 0 Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION):(CFR:

41.10/43.5/

45.13) 077AA2.04 Generator Voltage and Electric Grid 3.6 3.6 0 0 0 0 0 0 0 0 0 0 Disturbances / 6 Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION):(CFR:

41.10/43.5/

45.13) Page 1 of 1 FORM ES-401-2 TOPIC: Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits. Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions of operations The normal values for CCW-header flow rate and the flow rates to the components cooled by the CCWS Knowledge of the parameters and logic used to assess the status of safety functions DC loads lost; impact on ability to operate and monitor plant systems VARs outside the capability curve 4/1/2008 4:15 PM ES-401, REV 9 KA NAME I SAFETY FUNCTION:

009EG2.2.25 Small Break LOCA / 3 011 EG2.2.36 Large Break LOCA /3 SRO T1G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.2 4.2 0 0 0 0 0 0 0 0 0 0 This is a Generic, no stem statement is associated.

3.1 4.2 0 0 0 0 0 0 0 0 0 0 This is a Generic, no stem statement is associated.

026AA2.05 Loss of Component Cooling Water /8 2.4 2.5 0 0 0 0 0 0 0 0 0 0 Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION):(CFR:

41.10/43.5/

45.13) 057AG2.4.21 Loss of Vital AC Inst. Bus / 6 4.0 4.6 0 0 0 0 0 0 0 0 0 0 This is a Generic, no stem statement is associated.

058AA2.03 Loss of DC Power / 6 3.5 3.9 0 0 0 0 0 0 0 0 0 0 Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION):(CFR:

41.10/43.5/

45.13) 077AA2.04 Generator Voltage and Electric Grid 3.6 3.6 0 0 0 0 0 0 0 0 0 0 Disturbances / 6 Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION):(CFR:

41.10/43.5/

45.13) Page 1 of 1 FORM ES-401-2 TOPIC: Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits. Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions of operations The normal values for CCW-header flow rate and the flow rates to the components cooled by the CCWS Knowledge of the parameters and logic used to assess the status of safety functions DC loads lost; impact on ability to operate and monitor plant systems VARs outside the capability curve 4/1/2008 4:15 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

024AG2.2.39 Emergency Boration 1 1 068AG2.4.21 Control Room Evac. 18 069AA2.02 Loss of CTMT Integrity 1 5 WE16EA2.1 High Containment Radiation 1 9 SRO T1G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.9 4.5 0 0 0 0 0 0 0 0 0 0 This is a Generic, no stem statement is associated.

4.0 4.6 0 0 0 0 0 0 0 0 0 0 This is a Generic, no stem statement is associated.

3.9 4.4 0 0 0 0 0 0 0 0 0 0 Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION):(CFR:

41.10/43.51 45.13) 2.9 3.3 0 0 0 0 0 0 0 0 0 0 Ability to determine and interpret the following as they apply to (EMERGENCY PLANT EVOLUTION):(CFR:

41.10/43.51 45.13) Page 1 of 1 FORM ES-401-2 TOPIC: Knowledge of less than one hour technical specification action statements for systems. Knowledge of the parameters and logic used to assess the status of safety functions Verification of automatic and manual means of restoring integrity Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

4/1/2008 4:15 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

024AG2.2.39 Emergency Boration 1 1 068AG2.4.21 Control Room Evac. 18 069AA2.02 Loss of CTMT Integrity 1 5 WE16EA2.1 High Containment Radiation 1 9 SRO T1G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.9 4.5 0 0 0 0 0 0 0 0 0 0 This is a Generic, no stem statement is associated.

4.0 4.6 0 0 0 0 0 0 0 0 0 0 This is a Generic, no stem statement is associated.

3.9 4.4 0 0 0 0 0 0 0 0 0 0 Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION):(CFR:

41.10/43.51 45.13) 2.9 3.3 0 0 0 0 0 0 0 0 0 0 Ability to determine and interpret the following as they apply to (EMERGENCY PLANT EVOLUTION):(CFR:

41.10/43.51 45.13) Page 1 of 1 FORM ES-401-2 TOPIC: Knowledge of less than one hour technical specification action statements for systems. Knowledge of the parameters and logic used to assess the status of safety functions Verification of automatic and manual means of restoring integrity Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

4/1/2008 4:15 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

003A2.01 Reactor Coolant Pump 026G2.4.47 Containment Spray 039A2.02 Main and Reheat Steam .20 AC Electrical Distribution 076A2.02 Service Water SRO T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.5 3.9 0 0 0 0 0 0 0 0 0 0 Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR:

41.5/43.5/45.3/45.13) 4.2 4.2 0 0 0 0 0 0 0 0 0 0 This is a Generic, no stem statement is associated. 2.4 2.7 0 0 0 0 0 0 0 0 0 0 Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR:

41.5/43.5/45.3/45.13) 4.6 4.6 0 0 0 0 0 0 0 0 0 0 This is a Generic, no stem statement is associated.

2.7 3.1 0 0 0 0 0 0 0 0 0 0 Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR:

41.5/43.5/45.3/45.13)

Page 1 of 1 FORM ES-401-2 TOPIC: Problems with RCP seals, especially rates of seal leak-off Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

Decrease in turbine load as it relates to steam escaping from relief valves Ability to execute procedure steps. Service water header pressure 4/1/2008 4:15 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

003A2.01 Reactor Coolant Pump 026G2.4.47 Containment Spray 039A2.02 Main and Reheat Steam 062G2.1.20 AC Electrical Distribution 076A2.02 Service Water SRO T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.5 3.9 0 0 0 0 0 0 0 0 0 0 Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR:

41.5/43.5/45.3/45.13) 4.2 4.2 0 0 0 0 0 0 0 0 0 0 This is a Generic, no stem statement is associated. 2.4 2.7 0 0 0 0 0 0 0 0 0 0 Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR:

41.5/43.5/45.3/45.13) 4.6 4.6 0 0 0 0 0 0 0 0 0 0 This is a Generic, no stem statement is associated.

2.7 3.1 0 0 0 0 0 0 0 0 0 0 Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR:

41.5/43.5/45.3/45.13)

Page 1 of 1 FORM ES-401-2 TOPIC: Problems with RCP seals, especially rates of seal leak-off Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

Decrease in turbine load as it relates to steam escaping from relief valves Ability to execute procedure steps. Service water header pressure 4/1/2008 4:15 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

033G2.2.22 Spent Fuel Pool Cooling 072A2.02 Area Radiation Monitoring 086A2.01 Fire Protection SRO T2G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 4.0 4.7 D D D D D D D D D D This is a Generic, no stem statement is associated. 2.8 2.9 D D D D D D D D D D Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR:

41.5/43.5/45.3/45.13) 2.9 3.1 D D D D D D D D D D Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR:

41.5/43.5/45.3/45.13)

Page 1 of 1 FORM ES-401-2 TOPIC: Knowledge of limiting conditions for operations and safety limits. Detector failure Manual shu1down of the FPS 4/1/2008 4:15 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

033G2.2.22 Spent Fuel Pool Cooling 072A2.02 Area Radiation Monitoring 086A2.01 Fire Protection SRO T2G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 4.0 4.7 D D D D D D D D D D This is a Generic, no stem statement is associated. 2.8 2.9 D D D D D D D D D D Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR:

41.5/43.5/45.3/45.13) 2.9 3.1 D D D D D D D D D D Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR:

41.5/43.5/45.3/45.13)

Page 1 of 1 FORM ES-401-2 TOPIC: Knowledge of limiting conditions for operations and safety limits. Detector failure Manual shu1down of the FPS 4/1/2008 4:15 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

G2.1.14 Conduct of operations G2.1.36 Conduct of operations G2.2.15 Equipment Control G2.2.3 Equipment Control G2.3.13 Radiation Control G2.3.14 Radiation Control G2.4.3 Emergency Procedures/Plans SRO T3 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.1 3.1 0 0 0 0 0 0 0 0 0 0 3.0 4.1 0 0 0 0 0 0 0 0 0 0 3.9 4.3 0 0 0 0 0 0 0 0 0 0 3.8 3.9 0 0 0 0 0 0 0 0 0 0 3.4 3.8 0 0 0 0 0 0 0 0 0 0 3.4 3.8 0 0 0 0 0 0 0 0 0 0 3.7 3.9 0 0 0 0 0 0 0 0 0 0 Page 1 of 1 FORM ES-401-2 TOPIC: Knowledge of criteria or conditions that require plant-wide announcements, such as pump starts, reactor trip, mode changes, etc. Knowledge of procedures and limitations alterations core Ability to determine the expected plant configuration using design and configuration control documentaion (multi-unit license) Knowledge of the design, procedural and operational differences between units. Knowledge of radiological safety procedures pertaining to licensed operator duties Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities Ability to identify post-accident instrumentation.

4/1/2008 4:15 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:

G2.1.14 Conduct of operations G2.1.36 Conduct of operations G2.2.15 Equipment Control G2.2.3 Equipment Control G2.3.13 Radiation Control G2.3.14 Radiation Control G2.4.3 Emergency Procedures/Plans SRO T3 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.1 3.1 0 0 0 0 0 0 0 0 0 0 3.0 4.1 0 0 0 0 0 0 0 0 0 0 3.9 4.3 0 0 0 0 0 0 0 0 0 0 3.8 3.9 0 0 0 0 0 0 0 0 0 0 3.4 3.8 0 0 0 0 0 0 0 0 0 0 3.4 3.8 0 0 0 0 0 0 0 0 0 0 3.7 3.9 0 0 0 0 0 0 0 0 0 0 Page 1 of 1 FORM ES-401-2 TOPIC: Knowledge of criteria or conditions that require plant-wide announcements, such as pump starts, reactor trip, mode changes, etc. Knowledge of procedures and limitations involved in core alterations Ability to determine the expected plant configuration using design and configuration control documentaion (multi-unit license) Knowledge of the design, procedural and operational differences between units. Knowledge of radiological safety procedures pertaining to licensed operator duties Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities Ability to identify post-accident instrumentation.

4/1/2008 4:15 PM ES-401, Rev. 9 Form ES-401-4 Tier I Randomly Reason for Rejection Group Selected KA 1/2 APE076 AK3.06 (Q25) There is a question that was used on the 2006R (exam bank #148) which would meet this but within 2 years. It deals with demineralizers which is the only real action in AP/18. Replaced with KIA APE036 AK3.03 2/1 SYS008 K4.07 Q(35) No such component at eNS. KIA replacements originally provided 4.04 and 4.08 are not high enough value (2.1 and 2.3) Replaced with KIA SYS008 K4.09 1/0 APE077 AA2.04 Q(81) Duplicate KA of RO exam #14. Replaced with KIA APE077 AA2.09 1/2 APE069 AA2.02 Q(84) Cannot write an SRO question.

Replaced with KIA APE069 AA2.01 ES-401, Rev. 9 Form ES-401-4 Tier I Randomly Reason for Rejection Group Selected KA 1/2 APE076 AK3.06 (Q25) There is a question that was used on the 2006R (exam bank #148) which would meet this but within 2 years. It deals with demineralizers which is the only real action in AP/18. Replaced with KIA APE036 AK3.03 2/1 SYS008 K4.07 Q(35) No such component at eNS. KIA replacements originally provided 4.04 and 4.08 are not high enough value (2.1 and 2.3) Replaced with KIA SYS008 K4.09 1/0 APE077 AA2.04 Q(81) Duplicate KA of RO exam #14. Replaced with KIA APE077 AA2.09 1/2 APE069 AA2.02 Q(84) Cannot write an SRO question.

Replaced with KIA APE069 AA2.01 ES-301, Rev. 9 Administrative Topics Outline Form ES-301-1 Facility:

Catawba Nuclear Station Date of Examination 12/1/2008 Exam Level DSRO Operating Test No.: Administrative Topic Type Describe activity to be performed (see Note) Code* Conduct of Operations R N Using Data Book Figure 9 (Permissible Successive Attempts to Start Motors) determine the allowed starting time for NCP. Conduct of Operations R M Perform a manual shutdown margin calculation (Unit at Power) per OPjOjAj6100j006 (Reactivity Balance Calculation) with untrippable rods Equipment Control S M Calculate Unit Vent flow manually per PTjljAj44S0j017 (Unit Vent Flow Manual Calculation).

Radiation Protection R M Calculate the Maximum Permissible Stay Time Within Duke Power ALERT Administrative Dose Limits 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 all 5 are required.

• Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank 3 for ROs;.:5. 4 for SROs & RO retakes) (N)ew or (M)odified from bank 1) (P)revious 2 exams (.:5. 1; randomly selected)

ES-301, Rev. 9 Administrative Topics Outline Form ES-301-1 Facility:

Catawba Nuclear Station Date of Examination 12/1/2008 Exam Level DSRO Operating Test No.: Administrative Topic Type Describe activity to be performed (see Note) Code* Conduct of Operations R N Using Data Book Figure 9 (Permissible Successive Attempts to Start Motors) determine the allowed starting time for NCP. Conduct of Operations R M Perform a manual shutdown margin calculation (Unit at Power) per OPjOjAj6100j006 (Reactivity Balance Calculation) with untrippable rods Equipment Control S M Calculate Unit Vent flow manually per PTjljAj44S0j017 (Unit Vent Flow Manual Calculation).

Radiation Protection R M Calculate the Maximum Permissible Stay Time Within Duke Power ALERT Administrative Dose Limits 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 all 5 are required.

• Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank 3 for ROs;.:5. 4 for SROs & RO retakes) (N)ew or (M)odified from bank 1) (P)revious 2 exams (.:5. 1; randomly selected)

ES-301, Rev. 9 Administrative Topics Outline Form ES-301-1 Facility:

Catawba Nuclear Station Date of Examination 12/1/2008 Exam Level ORO Operating Test No.: Administrative Topic Type Describe activity to be performed (see Note) Code* Conduct of Operations R M Determine if a work hours extension is required and if so, which limits are exceeded.

Conduct of Operations R M Perform a manual shutdown margin calculation (Unit at Power) per OPjOjAj6100j006 (Reactivity Balance Calculation) with untrippable rods . Equipment Control S M Determine SLC requirements and complete a Unit Vent Flow Manual Calculation per PTjljAj4450j017 Radiation Protection R M Calculate the Maximum Permissible Stay Time Within Duke Power ALERT Administrative Dose Limits Emergency Plan R D Upgrade an Emergency Classification and Complete an Emergency Notification Form NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

• Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (::: 3 for ROs; ::: 4 for SROs & RO retakes) (N)ew or (M)odified from bank (::: 1) (P)revious 2 exams (::: 1; randomly selected)

ES-301, Rev. 9 Administrative Topics Outline Form ES-301-1 Facility:

Catawba Nuclear Station Date of Examination 12/1/2008 Exam Level ORO Operating Test No.: Administrative Topic Type Describe activity to be performed (see Note) Code* Conduct of Operations R M Determine if a work hours extension is required and if so, which limits are exceeded.

Conduct of Operations R M Perform a manual shutdown margin calculation (Unit at Power) per OPjOjAj6100j006 (Reactivity Balance Calculation) with untrippable rods . Equipment Control S M Determine SLC requirements and complete a Unit Vent Flow Manual Calculation per PTjljAj4450j017 Radiation Protection R M Calculate the Maximum Permissible Stay Time Within Duke Power ALERT Administrative Dose Limits Emergency Plan R D Upgrade an Emergency Classification and Complete an Emergency Notification Form NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

• Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (::: 3 for ROs; ::: 4 for SROs & RO retakes) (N)ew or (M)odified from bank (::: 1) (P)revious 2 exams (::: 1; randomly selected)

ES-301, Rev. 9 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:

Catawba Nuclear Station Date of Examination 12/1/2008 Exam Level o SRO-I o SRO-U Operating Test No.: Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 E System / JPM Title Type Code* Safety Function a. Perform a Manual Makeup to the vcr D S 1 b. Respond to NC System Leakage A D S 2 c. Depressurize the NC System to Minimize Primary to Secondary Leakage during A D S 3 a SGTR d. Cooldown the PRT Using NCDT Heat Exchanger D S 5 e. Restore Offsite Power to 6.9 kV Busses per AP/O? (Loss of Normal Power) A N S 6 Enclosure 21 (Black Restart Procedure)

f. Perform the Immediate Actions of AP/1/A/5500/16, (Malfunction of Nuclear D S ? Instrumentation System), Case 4, (P/R Malfunction)

g. Manually Operate the Steam Dump Valves from the Control Room D L S 4S h. Perform the Immediate Actions of AP/1/A/5500/004, (Loss of Reactor Coolant A EN M S 4P Pump) for Loss of One NC Pump) In-Plant Systems@(3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) i. Locally Break Vacuum on a Loss of Feedwater D E 4S j. Align Seal Injection to the Unit 2 NC Pumps D E 2 k. Alternate Cooling to 1A NV Pump D E R 8 @ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room

• Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 1 4-6 1 2-3 (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant .=::1 I.=::1 I.=::1 (EN)gineered safety feature I.=:: 1 (control room system) (L)ow-Power 1 Shutdown .=::1 I.=::1 I.=::1 (N)ew or (M)odified from bank including 1 (A) .=::2 I.=::2 I.=::1 (P)revious 2 exams 3 1 3 1 2 (randomly selected) (R)CA .=::1 I.=::1 I.=::1 (S)imulator ES-301, Rev. 9 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:

Catawba Nuclear Station Date of Examination 12/1/2008 Exam Level o SRO-I o SRO-U Operating Test No.: Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 E System / JPM Title Type Code* Safety Function a. Perform a Manual Makeup to the vcr D S 1 b. Respond to NC System Leakage A D S 2 c. Depressurize the NC System to Minimize Primary to Secondary Leakage during A D S 3 a SGTR d. Cooldown the PRT Using NCDT Heat Exchanger D S 5 e. Restore Offsite Power to 6.9 kV Busses per AP/O? (Loss of Normal Power) A N S 6 Enclosure 21 (Black Restart Procedure)

f. Perform the Immediate Actions of AP/1/A/5500/16, (Malfunction of Nuclear D S ? Instrumentation System), Case 4, (P/R Malfunction)

g. Manually Operate the Steam Dump Valves from the Control Room D L S 4S h. Perform the Immediate Actions of AP/1/A/5500/004, (Loss of Reactor Coolant A EN M S 4P Pump) for Loss of One NC Pump) In-Plant Systems@(3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) i. Locally Break Vacuum on a Loss of Feedwater D E 4S j. Align Seal Injection to the Unit 2 NC Pumps D E 2 k. Alternate Cooling to 1A NV Pump D E R 8 @ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room

• Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 1 4-6 1 2-3 (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant .=::1 I.=::1 I.=::1 (EN)gineered safety feature I.=:: 1 (control room system) (L)ow-Power 1 Shutdown .=::1 I.=::1 I.=::1 (N)ew or (M)odified from bank including 1 (A) .=::2 I.=::2 I.=::1 (P)revious 2 exams 3 1 3 1 2 (randomly selected) (R)CA .=::1 I.=::1 I.=::1 (S)imulator DRAFT ES-301, Rev. 9 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:

Catawba Nuclear Station Date of Examination 12/1/2008 Exam Level ORO SRO-I o SRO-U Operating Test No.: Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 E System / JPM Title Type Code* Safety Function a. b. Respond to NC System Leakage A D 5 2 c. Depressurize the NC System to Minimize Primary to Secondary Leakage during A D 5 3 a SGTR d. Cooldown the PRT Using NCDT Heat Exchanger D 5 5 e. Restore Offsite Power to 6.9 kV Busses per AP/O? (Loss of Normal Power) A N 5 6 Enclosure 21 (Black Restart Procedure)

f. Perform the Immediate Actions of AP/1/A/5500/16, (Malfunction of Nuclear D 5 ? Instrumentation System), Case 4, (P/R Malfunction)

g. Manually Operate the Steam Dump Valves from the Control Room D L 5 45 h. Perform the Immediate Actions of AP/1jA/5500/004, (Loss of Reactor Coolant A EN M 5 4P Pump) for Loss of One NC Pump) In-Plant Systems@(3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) i. Locally Break Vacuum on a Loss of Feedwater D E 45 j. Align Seal Injection to the Unit 2 NC Pumps D E 2 k. Alternate Cooling to 1A NV Pump D E R 8 @ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room

• Type Codes Criteria for RO I SRO-II SRO-U (A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank (E)mergency or abnonmal in-plant (EN)gineered safety feature -I -I 1 (control room system) (L)ow-Power I Shutdown :=:1 I:=:1 I:=:1 (N)ew or (M)odified from bank including 1 (A) (P)revious 2 exams 3 I 3 I 2 (randomly selected) (R)CA (S)imulator DRAFT ES-301, Rev. 9 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:

Catawba Nuclear Station Date of Examination 12/1/2008 Exam Level ORO SRO-I o SRO-U Operating Test No.: Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 E System / JPM Title Type Code* Safety Function a. b. Respond to NC System Leakage A D 5 2 c. Depressurize the NC System to Minimize Primary to Secondary Leakage during A D 5 3 a SGTR d. Cooldown the PRT Using NCDT Heat Exchanger D 5 5 e. Restore Offsite Power to 6.9 kV Busses per AP/O? (Loss of Normal Power) A N 5 6 Enclosure 21 (Black Restart Procedure)

f. Perform the Immediate Actions of AP/1/A/5500/16, (Malfunction of Nuclear D 5 ? Instrumentation System), Case 4, (P/R Malfunction)

g. Manually Operate the Steam Dump Valves from the Control Room D L 5 45 h. Perform the Immediate Actions of AP/1jA/5500/004, (Loss of Reactor Coolant A EN M 5 4P Pump) for Loss of One NC Pump) In-Plant Systems@(3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) i. Locally Break Vacuum on a Loss of Feedwater D E 45 j. Align Seal Injection to the Unit 2 NC Pumps D E 2 k. Alternate Cooling to 1A NV Pump D E R 8 @ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room

• Type Codes Criteria for RO I SRO-II SRO-U (A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank (E)mergency or abnonmal in-plant (EN)gineered safety feature -I -I 1 (control room system) (L)ow-Power I Shutdown :=:1 I:=:1 I:=:1 (N)ew or (M)odified from bank including 1 (A) (P)revious 2 exams 3 I 3 I 2 (randomly selected) (R)CA (S)imulator ES-301, Rev. 9 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:

Catawba Nuclear Station Date of Examination 12/1/2008 Exam Level ORO o SRO-I SRO-U Operating Test No.: Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 E System / JPM Title Type Code* Safety Function a. b. c. d. e. Restore Offsite Power to 6.9 kV Busses per APjO? (Loss of Normal Power) A N S 6 Enclosure 21 (Black Restart Procedure)

f. g. Manually Operate the Steam Dump Valves from the Control Room D L S 4S h. Perform the Immediate Actions of APj1jAj5500j004, (Loss of Reactor Coolant A EN M S 4P Pump) for Loss of One NC Pump) In-Plant Systems@(3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) i. j. Align Seal Injection to the Unit 2 NC Pumps D E 2 k. Alternate Cooling to 1A NV Pump D E R 8 @ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room

• Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature -/ -/ 1 (control room system) (L)ow-Power

/ Shutdown (N)ew or (M)odifjed from bank including 1 (A) (P)revious 2 exams 3 / 3 / 2 (randomly selected) (R)CA (S)imulator ES-301, Rev. 9 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:

Catawba Nuclear Station Date of Examination 12/1/2008 Exam Level ORO o SRO-I SRO-U Operating Test No.: Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 E System / JPM Title Type Code* Safety Function a. b. c. d. e. Restore Offsite Power to 6.9 kV Busses per APjO? (Loss of Normal Power) A N S 6 Enclosure 21 (Black Restart Procedure)

f. g. Manually Operate the Steam Dump Valves from the Control Room D L S 4S h. Perform the Immediate Actions of APj1jAj5500j004, (Loss of Reactor Coolant A EN M S 4P Pump) for Loss of One NC Pump) In-Plant Systems@(3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) i. j. Align Seal Injection to the Unit 2 NC Pumps D E 2 k. Alternate Cooling to 1A NV Pump D E R 8 @ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room

• Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature -/ -/ 1 (control room system) (L)ow-Power

/ Shutdown (N)ew or (M)odifjed from bank including 1 (A) (P)revious 2 exams 3 / 3 / 2 (randomly selected) (R)CA (S)imulator