ML063240210: Difference between revisions

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| author name =  
| author name =  
| author affiliation = Exelon Generation Co, LLC
| author affiliation = Exelon Generation Co, LLC
| addressee name = Fish T H
| addressee name = Fish T
| addressee affiliation = NRC/RGN-I/DRS/OB
| addressee affiliation = NRC/RGN-I/DRS/OB
| docket = 05000352, 05000353
| docket = 05000352, 05000353
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{{#Wiki_filter:ES-401 BWR Examination Outline Form ES-401-1 Facility: Limerick Generating Station Printed: 10/30/2006 Date Of Exam: 10/23/2006 Note: 1. 2. 3. 4. 5. 6. 7.* 8. 9. Ensure that at least two topics from every WA 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 WA category shall not be less than two). 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 k1 from that specified in the table based on NRC revisions.
{{#Wiki_filter:ES-401 BWR Examination Outline Form ES-401-1 Facility: Limerick Generating Station Printed: 10/30/2006 Date Of Exam: 10/23/2006 Note: 1. 2. 3. 4. 5. 6. 7.* 8. 9. Ensure that at least two topics from every WA 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 WA category shall not be less than two). 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 k1 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. 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 WA statements. 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. Absent a plant-specific priority, only those WAS having an importance rating (IR) of 2.5 or higher shall be selected.
The final RO exam must total 75 points and the SRO-only exam must total 25 points. 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 WA statements. 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. Absent a plant-specific priority, only those WAS 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. Select SRO topics for Tiers 1 and 2 from the shaded systems and WA categories. The generic (G) WAS in Tiers 1 and 2 shall be selected from Section 2 of the WA Catalog, but the topics must be relevant to the applicable evolution or system. On the following pages, enter the WA numbers, a brief description of each topic, the topics' importance ratings (IRs) for the applicable license level, and the point totals  
Use the RO and SRO ratings for the RO and SRO-only portions, respectively. Select SRO topics for Tiers 1 and 2 from the shaded systems and WA categories. The generic (G) WAS in Tiers 1 and 2 shall be selected from Section 2 of the WA Catalog, but the topics must be relevant to the applicable evolution or system. On the following pages, enter the WA 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.
(#) for each system and category.
Enter the group and tier totals for each category in the table above. Use duplicate pages for RO and SRO-only exams.
Enter the group and tier totals for each category in the table above. Use duplicate pages for RO and SRO-only exams.
Line 25: Line 25:
/ 5 & 7 Secondary Containment Area Radiation Levels 19 # I 1 1 7 1 BWR RO Examination Outline Facility: Limerick Generating Station Plant Systems - Tier 2 I Group 1 (RO I SRO) ES - 401 1 SysIEvol # I Name IK1 IK21K3 203000 RHWLPCI: Injection Mode 205000 Shutdown Cooling 206000 HPCI 209001 LPCS X 209001 LPCS I/ 2 12000 RPS I212000RPs I I 215003 IRM I IxI Ill I 2 15004 Source Range Monitor IxI I I 2 15005 APWLPRM I I I 2 17000 RCIC 2 17000 RCIC 2 18000 ADS 223002 PCIS/Nuclear Steam Sur& Shutoff K 239002 SRVs 259002 Reactor Water Level Control I 261000 sGTs Ill I 262001 AC Electrical Distribution I I 1 I 262002 UPS (ACDC) I Ix X X Printed: 10/30/2006 Form ES-401-1 1 2
/ 5 & 7 Secondary Containment Area Radiation Levels 19 # I 1 1 7 1 BWR RO Examination Outline Facility: Limerick Generating Station Plant Systems - Tier 2 I Group 1 (RO I SRO) ES - 401 1 SysIEvol # I Name IK1 IK21K3 203000 RHWLPCI: Injection Mode 205000 Shutdown Cooling 206000 HPCI 209001 LPCS X 209001 LPCS I/ 2 12000 RPS I212000RPs I I 215003 IRM I IxI Ill I 2 15004 Source Range Monitor IxI I I 2 15005 APWLPRM I I I 2 17000 RCIC 2 17000 RCIC 2 18000 ADS 223002 PCIS/Nuclear Steam Sur& Shutoff K 239002 SRVs 259002 Reactor Water Level Control I 261000 sGTs Ill I 262001 AC Electrical Distribution I I 1 I 262002 UPS (ACDC) I Ix X X Printed: 10/30/2006 Form ES-401-1 1 2
BWR RO Examination Outline Facility: Limerick Generating Station Plant Systems - Tier 2 / Group 2 (RO / SRO) ES - 401 Printed: 10/30/2006 Form ES-401-1 I SyslEvol # I Name IK1 lK2lK31 K4 230000 RHWLPCI: Torus/Pool Spray Mode 245000 Main Turbine GeneratodAux 256000 Reactor Condensate X 259001 Reactor Feedwater  
BWR RO Examination Outline Facility: Limerick Generating Station Plant Systems - Tier 2 / Group 2 (RO / SRO) ES - 401 Printed: 10/30/2006 Form ES-401-1 I SyslEvol # I Name IK1 lK2lK31 K4 230000 RHWLPCI: Torus/Pool Spray Mode 245000 Main Turbine GeneratodAux 256000 Reactor Condensate X 259001 Reactor Feedwater  
///Ix 290003 Control Room HVAC WACategory Totals: 1 1 1 2 1 Generic Knowledge and Abilities Outline (Tier  
///Ix 290003 Control Room HVAC WACategory Totals: 1 1 1 2 1 Generic Knowledge and Abilities Outline (Tier
: 3) BWR RO Examination Outline Printed: 10/30/2006 2.1.28 Facilitv: Limerick Generating Station Form ES-401-3 Knowledge of the purpose and function of major 3.2 1 system components and controls.
: 3) BWR RO Examination Outline Printed: 10/30/2006 2.1.28 Facilitv: Limerick Generating Station Form ES-401-3 Knowledge of the purpose and function of major 3.2 1 system components and controls.
IR - # Catepory - KA# Topic - I I I I 2.5 Conduct of Operations 1 2.1.3 1 Knowledge of shift turnover practices.
IR - # Catepory - KA# Topic - I I I I 2.5 Conduct of Operations 1 2.1.3 1 Knowledge of shift turnover practices.
I 3.0 I 1 2.1.19 Ability to use plant computer to obtain and evaluate parametric information on system or comoonent status.
I 3.0 I 1 2.1.19 Ability to use plant computer to obtain and evaluate parametric information on system or comoonent status.
3*0 I 2.2.1 Ability to perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivitv. 2.2.1 1 Knowledge of the process for controlling temDorarv changes. 2.2.13 Knowledge of tagging and clearance procedures. Category Total:  
3*0 I 2.2.1 Ability to perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivitv. 2.2.1 1 Knowledge of the process for controlling temDorarv changes. 2.2.13 Knowledge of tagging and clearance procedures. Category Total:  
; 3.6 3 Radiation Control  
; 3.6 3 Radiation Control 2.3.4 Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized.  
 
====2.3.4 Knowledge====
of radiation exposure limits and contamination control, including permissible levels in excess of those authorized.  
~ I Ability to control radiation releases.
~ I Ability to control radiation releases.
7- ~ Category Total:
7- ~ Category Total:
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Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
Select SRO topics for Tiers 1 and 2 from the shaded systems and WA categories.
Select SRO topics for Tiers 1 and 2 from the shaded systems and WA categories.
7.* The generic (G) WAS in Tiers 1 and 2 shall be selected from Section 2 of the WA Catalog, but the 8. topics must be relevant to the applicable evolution or system. On the following pages, enter the WA numbers, a brief description of each topic, the topics' importance ratings (IRs) for the applicable license level, and the point totals  
7.* The generic (G) WAS in Tiers 1 and 2 shall be selected from Section 2 of the WA Catalog, but the 8. topics must be relevant to the applicable evolution or system. On the following pages, enter the WA 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.
(#) for each system and category.
Enter the group and tier totals for each category in the table above.
Enter the group and tier totals for each category in the table above.
Use duplicate pages for RO and SRO-only exams.  
Use duplicate pages for RO and SRO-only exams.
: 9. For Tier 3, select topics from Section 2 of the WA catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3.
: 9. For Tier 3, select topics from Section 2 of the WA catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3.
Limit SRO selections to WAS that are linked to 10 CFR 55.43. Note: This form deviates from theNUREG-1021 Form ES-401-1 by the addition oftheK and A column under the SROOnly Points. This allows sampling all Fuel Handling System KAs as required by ES-401. 1 BWR SRO Examination Outline Facility: Limerick Generating Station Printed: 10/30/2006 ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 1 (RO I SRO) Form ES-401-1 EIAPE # I Name I Safety Function 295001 Partial or Complete Loss of Forced Core Flow Circulation I 1 & 4 295003 Partial or Complete Loss of AC Pwr /6 295016 Control Room Abandonment  
Limit SRO selections to WAS that are linked to 10 CFR 55.43. Note: This form deviates from theNUREG-1021 Form ES-401-1 by the addition oftheK and A column under the SROOnly Points. This allows sampling all Fuel Handling System KAs as required by ES-401. 1 BWR SRO Examination Outline Facility: Limerick Generating Station Printed: 10/30/2006 ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 1 (RO I SRO) Form ES-401-1 EIAPE # I Name I Safety Function 295001 Partial or Complete Loss of Forced Core Flow Circulation I 1 & 4 295003 Partial or Complete Loss of AC Pwr /6 295016 Control Room Abandonment  
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# 1 1 1 1 7 - 1 BWR SRO Examination Outline Printed: 10/30/2006 Facility: Limerick Generating Station ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 (RO / SRO) Form ES-401-1 tions for operations and safety 1 BWR SRO Examination Outline Facility:
# 1 1 1 1 7 - 1 BWR SRO Examination Outline Printed: 10/30/2006 Facility: Limerick Generating Station ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 (RO / SRO) Form ES-401-1 tions for operations and safety 1 BWR SRO Examination Outline Facility:
Limerick Generating Station Plant Systems - Tier ES - 401 21 Group 1 (ROI SRO) Printed: 10/30/2006 Form ES-401-1 1 1
Limerick Generating Station Plant Systems - Tier ES - 401 21 Group 1 (ROI SRO) Printed: 10/30/2006 Form ES-401-1 1 1
Generic Knowledge and Abilities Outline (Tier  
Generic Knowledge and Abilities Outline (Tier
: 3) BWR SRO Examination Outline Printed: 10/30/2006 Facility:
: 3) BWR SRO Examination Outline Printed: 10/30/2006 Facility:
Limerick Generating Station Form ES-401-3 2.1.34 Category Ability to maintain primary and secondary plant 2.9 1 chemistry within allowable limits. Conduct of Operations Knowledge of the process for making changes in procedures as described in the safety analysis report. Knowledge of new and spent fuel movement procedures.
Limerick Generating Station Form ES-401-3 2.1.34 Category Ability to maintain primary and secondary plant 2.9 1 chemistry within allowable limits. Conduct of Operations Knowledge of the process for making changes in procedures as described in the safety analysis report. Knowledge of new and spent fuel movement procedures.
Line 90: Line 87:
Limerick Exam Level: RO [XI SRO-I SRO-U 0 Date of Examination:
Limerick Exam Level: RO [XI SRO-I SRO-U 0 Date of Examination:
10/23/06 Operating Test Number:
10/23/06 Operating Test Number:
ILT05-1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF) Safety Type 'Ode* Function System / JPM Title  
ILT05-1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF) Safety Type 'Ode* Function System / JPM Title
: a. Reactor RecirciStart MG Set - High Vibration b. Shutdown "1 C" Reactor Feed Pump From Standby Condition A, L, P, S 1 A, N, S 2 c. Manually Initiate a Control Room Ventilation Radiation Isolation 1 p,s I 9 d. Manually Initiate Core Spray  
: a. Reactor RecirciStart MG Set - High Vibration b. Shutdown "1 C" Reactor Feed Pump From Standby Condition A, L, P, S 1 A, N, S 2 c. Manually Initiate a Control Room Ventilation Radiation Isolation 1 p,s I 9 d. Manually Initiate Core Spray
("D" Core Spray Pump fails to start)
("D" Core Spray Pump fails to start)
A, N, S 4 e. Restore RECW, DWCW, PClG D, s 5 f. DG Fast Start From Control Room (Jacket Water High Temp) A, N, S 6 g. Scram Reset A, D, S 7 h. Placing Alternate RECW Pump in Service in-Plant Systems@  
A, N, S 4 e. Restore RECW, DWCW, PClG D, s 5 f. DG Fast Start From Control Room (Jacket Water High Temp) A, N, S 6 g. Scram Reset A, D, S 7 h. Placing Alternate RECW Pump in Service in-Plant Systems@
(3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) A, N, S 8 i. Start "OB" ESW Pump From D12 SG (SE-6) j. Place Alternate CRD Flow Control Valve In Service k. MSlV -129" Bypass (T-221)
(3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) A, N, S 8 i. Start "OB" ESW Pump From D12 SG (SE-6) j. Place Alternate CRD Flow Control Valve In Service k. MSlV -129" Bypass (T-221)
ID,E,RI 4 @ 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:
ID,E,RI 4 @ 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:
Line 100: Line 97:
/ SRO-I I SRO-U 4-6 / 4-6 / 2 <9/ (8 /(4 - >I/ 21 />I - >I/ 21 />I - >2/ 22 /,I - >I/ 21 /?I - 3 3 / 5 2 (randomly selected)
/ SRO-I I SRO-U 4-6 / 4-6 / 2 <9/ (8 /(4 - >I/ 21 />I - >I/ 21 />I - >2/ 22 /,I - >I/ 21 /?I - 3 3 / 5 2 (randomly selected)
ES-301, Page 23 of 27 ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 -acility: Limerick Exam Level: RO 0 SRO-I SRO-U 0 Date of Examination:
ES-301, Page 23 of 27 ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 -acility: Limerick Exam Level: RO 0 SRO-I SRO-U 0 Date of Examination:
10123/06 Operating Test Number: ILT05-1 Zontrol Room Systems@ (8 for RO); (7 for SRO-I);  
10123/06 Operating Test Number: ILT05-1 Zontrol Room Systems@ (8 for RO); (7 for SRO-I);
(2 or 3 for SRO-U, including 1 ESF) Safety Type 'Ode* Function System I JPM Title  
(2 or 3 for SRO-U, including 1 ESF) Safety Type 'Ode* Function System I JPM Title
: 3. Reactor Recirc/Start MG Set - High Vibration  
: 3. Reactor Recirc/Start MG Set - High Vibration
: 3. Shutdown "1 C" Reactor Feed Pump From Standby Condition A, L, P, S 1 2 c. Manually Initiate a Control Room Ventilation Radiation Isolation  
: 3. Shutdown "1 C" Reactor Feed Pump From Standby Condition A, L, P, S 1 2 c. Manually Initiate a Control Room Ventilation Radiation Isolation
: d. Manually Initiate Core Spray ("D" Core Spray Pump fails to start) P, s 9 A, N, S 4 A, N, S 6 e. DG Fast Start From Control Room (Jacket Water High Temp)  
: d. Manually Initiate Core Spray ("D" Core Spray Pump fails to start) P, s 9 A, N, S 4 A, N, S 6 e. DG Fast Start From Control Room (Jacket Water High Temp)
: f. Scram Reset A, D, S 7 g. Placing Alternate RECW Pump in Service A, N, S 8 h. In-Plant Systems@ (3 for RO); (3 for SRO-I);  
: f. Scram Reset A, D, S 7 g. Placing Alternate RECW Pump in Service A, N, S 8 h. In-Plant Systems@ (3 for RO); (3 for SRO-I);
(3 or 2 for SRO-U) i. Start"0B" ESW Pump From D12 SG (SE-6) D, E, R 8 j. Place Alternate CRD Flow Control Valve In Service D, L, R 1 k. MSlV -129" Bypass (T-221) ID,E,R/ 4 @ 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 (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (L)ow-Power  
(3 or 2 for SRO-U) i. Start"0B" ESW Pump From D12 SG (SE-6) D, E, R 8 j. Place Alternate CRD Flow Control Valve In Service D, L, R 1 k. MSlV -129" Bypass (T-221) ID,E,R/ 4 @ 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 (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (L)ow-Power  
/ Shutdown (N)ew or (M)odified from bank including (P)revious 2 exams (S)imulator Criteria for RO / SRO-l I SRO-U 4-6 I 4-6 I 2-3 ES-301, Page 23 of 27 ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 b. DG Fast Start From Control Room (Jacket Water High Temp) A, N, S . 6 (ESF) 1 Facility: Limerick Exam Level: RO 0 SRO-I 0 SRO-U c. Restore RECW, DWCW, PClG d. Date of Examination: 10/23/06 Operating Test Number: ILT05-1 D, S 5 a. Reactor RecircIStart MG Set - High Vibration  
/ Shutdown (N)ew or (M)odified from bank including (P)revious 2 exams (S)imulator Criteria for RO / SRO-l I SRO-U 4-6 I 4-6 I 2-3 ES-301, Page 23 of 27 ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 b. DG Fast Start From Control Room (Jacket Water High Temp) A, N, S . 6 (ESF) 1 Facility: Limerick Exam Level: RO 0 SRO-I 0 SRO-U c. Restore RECW, DWCW, PClG d. Date of Examination: 10/23/06 Operating Test Number: ILT05-1 D, S 5 a. Reactor RecircIStart MG Set - High Vibration
: e. II ~~ I I u f. 9. h. 11 Implant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) ' i. Start "OB" ESW Pump From Dl2 SG (SE-6) D, E, R 8 j. MSlV -129" Bypass (T-221) D, E, R 4 k. @ 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-I I SRO-U (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (L)ow-Power I Shutdown (N)ew or (M)odified from bank including l(A) (P)revious 2 exams (S)imulator (R)CA 4-6 I 4-6 / 2-3 ES-301, Page 23 of 27 Appendix D Scenario Outline Form ES-D-1 4 Facility: Limerick Scenario No.: 1 Op-Test No.: ILT05-1 MED263D Examiners: Operators:
: e. II ~~ I I u f. 9. h. 11 Implant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) ' i. Start "OB" ESW Pump From Dl2 SG (SE-6) D, E, R 8 j. MSlV -129" Bypass (T-221) D, E, R 4 k. @ 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-I I SRO-U (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (L)ow-Power I Shutdown (N)ew or (M)odified from bank including l(A) (P)revious 2 exams (S)imulator (R)CA 4-6 I 4-6 / 2-3 ES-301, Page 23 of 27 Appendix D Scenario Outline Form ES-D-1 4 Facility: Limerick Scenario No.: 1 Op-Test No.: ILT05-1 MED263D Examiners: Operators:
6 Initial Conditions: 100% power. RCIC is out of service for bearing replacement. Regulatory actions log entry has been made. Estimated time of repair is 24 hours.
6 Initial Conditions: 100% power. RCIC is out of service for bearing replacement. Regulatory actions log entry has been made. Estimated time of repair is 24 hours.

Revision as of 09:42, 13 July 2019

Final Outlines (Folder 3)
ML063240210
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 10/10/2006
From:
Exelon Generation Co
To: Todd Fish
Operations Branch I
Sykes, Marvin D.
References
Download: ML063240210 (23)


Text

ES-401 BWR Examination Outline Form ES-401-1 Facility: Limerick Generating Station Printed: 10/30/2006 Date Of Exam: 10/23/2006 Note: 1. 2. 3. 4. 5. 6. 7.* 8. 9. Ensure that at least two topics from every WA 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 WA category shall not be less than two). 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 k1 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. 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 WA statements. 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. Absent a plant-specific priority, only those WAS 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. Select SRO topics for Tiers 1 and 2 from the shaded systems and WA categories. The generic (G) WAS in Tiers 1 and 2 shall be selected from Section 2 of the WA Catalog, but the topics must be relevant to the applicable evolution or system. On the following pages, enter the WA 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. Use duplicate pages for RO and SRO-only exams.

For Tier 3, select topics from Section 2 of the WA catalog, and enter the WA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3.

Limit SRO selections to WAS that are linked to 10 CFR 55.43. Note: This form deviates from theNUREG-1021 Form ES-401-1 by the addition oftheK and A column under the SROOnly Points. This allows sampling all Fuel Handling System KAs as required by ES-401. 1 BWR RO Examination Outline Facility: Limerick Generating Station K1 X X X Printed: 10/30/2006 K2 X X X X ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 1 (RO I SRO) Form ES-401-1 IR # EIAPE # I Name I Safety Function 3.5 1 295001 Partial or Complete Loss of Forced Core Flow Circulation I 1 & 4 3.5 295003 Partial or Complete Loss of AC Pwr 16 295004 Partial or Complete Loss of DC Pwr /6 295005 Main Turbine Generator Trip I 3 3.8 3.8 4.3* 2.8 4.4* ~~~ 295006 SCRAM I 1 295016 Control Room Abandonment 17 295016 Control Room Abandonment 17 3.3 3.3 - - 3.7 295018 Partial or Total Loss of CCW I 8 295019 Partial or Total Loss of Instrument Air I 8 295021 Loss of Shutdown Cooling I 4 2.6 4.1 4.4* 3.9 295023 Refueling Acc I 8 295024 High Drywell Pressure I 5 295025 High Reactor Pressure I 3 1 295026 Suppression Pool High Water Temp. I 5 295028 High Drywell Temperature I 5 3.6 295030 Low Suppression Pool Wtr Lvl 15 3.5 4.6* 1 29503 1 Reactor Low Water Level I 2 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown I 1 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown I 1 1 4.0 4.2* 3.6 1 1 295038 High Off-Site Release Rate I 9 I I WACategory Totals: I 3 I 4 tTotal: 20 1 BWR RO Examination Outline Facility: Limerick Generating Station 500000 High CTMT Hydrogen Conc.

I 5 WACategory Totals: Printed: 1013012006 1 1 1 ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 (RO / SRO) Form ES-401-1 295007 High Reactor Pressure 13 I T I 295010 High Drywell Pressure I 5 I I Ix I 295015 Incomplete SCRAM I I II lxl 295020 Inadvertent Cont. Isolation

/ 5 & 7 Secondary Containment Area Radiation Levels 19 # I 1 1 7 1 BWR RO Examination Outline Facility: Limerick Generating Station Plant Systems - Tier 2 I Group 1 (RO I SRO) ES - 401 1 SysIEvol # I Name IK1 IK21K3 203000 RHWLPCI: Injection Mode 205000 Shutdown Cooling 206000 HPCI 209001 LPCS X 209001 LPCS I/ 2 12000 RPS I212000RPs I I 215003 IRM I IxI Ill I 2 15004 Source Range Monitor IxI I I 2 15005 APWLPRM I I I 2 17000 RCIC 2 17000 RCIC 2 18000 ADS 223002 PCIS/Nuclear Steam Sur& Shutoff K 239002 SRVs 259002 Reactor Water Level Control I 261000 sGTs Ill I 262001 AC Electrical Distribution I I 1 I 262002 UPS (ACDC) I Ix X X Printed: 10/30/2006 Form ES-401-1 1 2

BWR RO Examination Outline Facility: Limerick Generating Station Plant Systems - Tier 2 / Group 2 (RO / SRO) ES - 401 Printed: 10/30/2006 Form ES-401-1 I SyslEvol # I Name IK1 lK2lK31 K4 230000 RHWLPCI: Torus/Pool Spray Mode 245000 Main Turbine GeneratodAux 256000 Reactor Condensate X 259001 Reactor Feedwater

///Ix 290003 Control Room HVAC WACategory Totals: 1 1 1 2 1 Generic Knowledge and Abilities Outline (Tier

3) BWR RO Examination Outline Printed: 10/30/2006 2.1.28 Facilitv: Limerick Generating Station Form ES-401-3 Knowledge of the purpose and function of major 3.2 1 system components and controls.

IR - # Catepory - KA# Topic - I I I I 2.5 Conduct of Operations 1 2.1.3 1 Knowledge of shift turnover practices.

I 3.0 I 1 2.1.19 Ability to use plant computer to obtain and evaluate parametric information on system or comoonent status.

3*0 I 2.2.1 Ability to perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivitv. 2.2.1 1 Knowledge of the process for controlling temDorarv changes. 2.2.13 Knowledge of tagging and clearance procedures. Category Total:

3.6 3 Radiation Control 2.3.4 Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized.

~ I Ability to control radiation releases.

7- ~ Category Total:

I Emergency Plan 2.4.21 2.4.46 Knowledge of the parameters and logic used to assess the status of safety functions including: 1 .Reactivity control 2.Core cooling and heat removal 3.Reactor coolant system integrity 4.Containment conditions 5.Radioactivity release control.

Ability to verify that the alarms are consistent with the olant conditions.

I 3.5 I 1 Category Total: 2 Generic Total:

10 1 ES-401 BWR Examination Outline Form ES-401-1 Facilitv: Limerick Generating Station Printed: 10/30/2006 Date Of Exam: 10/23/2006 RO WA Category Points I SRO-Only Points Note: 1. 2. 3. 4. 5. 6. Ensure that at least two topics from every WA category are sampled within each tier of the RO and SRO-only outlines (Le., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each WA category shall not be less than two). 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 +I 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. 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 WA statements. 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. Absent a plant-specific priority, only those WAS 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.

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

7.* The generic (G) WAS in Tiers 1 and 2 shall be selected from Section 2 of the WA Catalog, but the 8. topics must be relevant to the applicable evolution or system. On the following pages, enter the WA 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.

Use duplicate pages for RO and SRO-only exams.

9. For Tier 3, select topics from Section 2 of the WA catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3.

Limit SRO selections to WAS that are linked to 10 CFR 55.43. Note: This form deviates from theNUREG-1021 Form ES-401-1 by the addition oftheK and A column under the SROOnly Points. This allows sampling all Fuel Handling System KAs as required by ES-401. 1 BWR SRO Examination Outline Facility: Limerick Generating Station Printed: 10/30/2006 ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 1 (RO I SRO) Form ES-401-1 EIAPE # I Name I Safety Function 295001 Partial or Complete Loss of Forced Core Flow Circulation I 1 & 4 295003 Partial or Complete Loss of AC Pwr /6 295016 Control Room Abandonment

/ 7 29502 1 Loss of Shutdown Cooling

/ 4 295024 High Drywell Pressure

/ 5 29503 1 Reactor Low Water Level

/ 2 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown / 1 KIA Category Totals:

  1. 1 1 1 1 7 - 1 BWR SRO Examination Outline Printed: 10/30/2006 Facility: Limerick Generating Station ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 (RO / SRO) Form ES-401-1 tions for operations and safety 1 BWR SRO Examination Outline Facility:

Limerick Generating Station Plant Systems - Tier ES - 401 21 Group 1 (ROI SRO) Printed: 10/30/2006 Form ES-401-1 1 1

Generic Knowledge and Abilities Outline (Tier

3) BWR SRO Examination Outline Printed: 10/30/2006 Facility:

Limerick Generating Station Form ES-401-3 2.1.34 Category Ability to maintain primary and secondary plant 2.9 1 chemistry within allowable limits. Conduct of Operations Knowledge of the process for making changes in procedures as described in the safety analysis report. Knowledge of new and spent fuel movement procedures.

Topic IR - # I I I 3.3 1 3.5 1 2.1.4 Radiation Control 2.3.9 Knowledge of the process for performing a containment purge. Knowledge of shift staffing requirements.

I 3.4 I 1 3.4 1 Emergency Plan Equipment Control Category Total:

1 2.4.1 Knowledge of EOP entry conditions and 4.6 1 2.4.6 Knowledge symptom based EOP mitigation 4.0 1 Category Total:

2 immediate action steps. strategies.

2.2.6 2.2.28 Generic Total: 7 1 Limerick lLTO5-1 ES-401 Record of Rejected WAS Form ES-401-4 Tier I Randomly Reason for Rejection Group Selected WA 295016 2.2.25 295023 2.1.27 295031 EA2.01 295038 EKl.03 600000 2.4.6 295007 AAI .04 295033 2.1.23 203000 K6.08 212000 A4.14 261000 K6.01 262002 K3.07 234000 A3.02 2.1.28 RO EXAM Redrawn with the approval of the lead examiner due the lack of concepts that would meet the WA and still distinguish between a competent and non-competent operator.

Redrawn with the approval of the lead examiner due the lack of concepts that would meet the WA and still distinguish between a competent and non-competent operator.

Redrawn with the approval of the lead examiner due the lack of concepts that would meet the WA and still distinguish between a competent and non-competent operator.

Redrawn with the approval of the lead examiner due the lack of concepts that would meet the WA and still distinguish between a competent and non-competent operator and WA corresponds to a task that is NIA for RO's. Redrawn with the approval of the lead examiner due the lack of concepts that would meet the WA and still distinguish between a competent and non-competent operator and generic WA refers to EOP mitigation strategy, while the category is an AOP. Redrawn with the approval of the lead examiner due to WA overlap with another WA already included on this portion of the exam.

Redrawn with the approval of the lead examiner due the lack of concepts that would meet the WA and still distinguish between a competent and non-competent operator.

Redrawn with the approval of the lead examiner due the lack of concepts that would meet the WA and still distinguish between a competent and non-competent operator.

Also a loss of ECS room cooling has no effect on LPCl because LGS is analyzed for loss of room cooling.

Redrawn with the approval of the lead examiner due to WA overlap with a JPM. Redrawn with the approval of the lead examiner due this WA is a duplicate from 2005 ILT Exam (Q375215). Substituted another K6 in its place. Redrawn with the approval of the lead examiner due to this WA is essentially the same as another already on the exam.(215002 K2.03 RBM, electrical power supplies to APRM channels). Substituted another K3 in its Redrawn with the approval of the lead examiner due to A3 not applicable to SRO exam, deselected due to a known deficiency in the software. Redrawn with the approval of the lead examiner due the lack of concepts that would meet the WA and still distinguish between a competent and non-competent operator. ES-401, Page 27 of 33 Limerick ILT05-I ES-401 Record of Reiected WAS Form ES-401-4 ';;I.IvyLyyI 295031 2.1.6 1/2 295007 2.2.25 2/1 21 8000 A2.05 2/1 223002 A2.05 2/1 295002 A2.02 2.4.32 SRO EXAM Redrawn with the approval of the lead examiner due to WA overlap with questions on the RO portion of the exam. Redrawn with the approval of the lead examiner due the lack of concepts that would meet the WA and still distinguish between a competent and non-competent operator.

Redrawn with the approval of the lead examiner due the lack of concepts that would meet the WA and still distinguish between a competent and non-competent operator.

Redrawn with the amroval of the lead examiner due the lack of concepts that would meet the k/A and still distinguish between a competent and non-competent operator.

Redrawn with the approval of the lead examiner due to WA overlap with questions on the RO portion of the exam.

Redrawn with the approval of the lead examiner due to WA overlap with questions on the RO portion of the exam. Redrawn with the approval of the lead examiner due to WA overlap with questions on the Rb'portion of the exam. Redrawn with the amroval of the lead examiner due the lack of conceDts that would meet the k/A and still distinguish between a competent and non-competent operator.

Redrawn with the approval of the lead examiner due to WA overlap with questions on the RO portion of the exam. Redrawn with the approval of the lead examiner due the lack of concepts that would meet the WA and still distinguish between a competent and non-competent operator.

Redrawn with the approval of the lead examiner due the lack of concepts that would meet the WA and still distinguish between a competent and non-competent operator.

Redrawn with the approval of the lead examiner due the lack of concepts that would meet the WA and still distinguish between a competent and non-competent operator.

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Limerick Examination Level:

RO SRO 0 Administrative Topic (See Note) I Radiation Control Emergency Plan Type Code* N. R Date of Examination: 10/23/06 Operating Test Number: ILT05-1 Describe activity to be performed Determination of Adequate Shift Staffing Review Main Turbine Bypass Valve Exercising ST Calculate Stay Time 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.

Fire Alarm in Invertor Room (CE 254')

  • Type Codes

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

ES 301, Page 22 of 27 ES-301 Ad m i n is t rat ive Toei cs 0 ut I i ne Form ES-301-1 Facility: Limerick Examination Level: RO 0 SRO [XI Administrative Topic (See Note) Conduct of Operations Conduct of Operations Equipment Control Radiation Control I I Emergency Plan Type Code* N. R N, R D. S Date of Examination:

10/23/06 Operating Test Number: ILT05-1 Describe activity to be performed Determination of Adequate Shift Staffing Administrative Actions on a Thermal Limit Violation Review Main Turbine Bypass Valve Exercising S.T. Calculate Stay Time ERP Classification and Reporting (LOCA) 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, (S)imulator, or Class(R)oom (D)irect from bank (5 3 for ROs; 5 4 for SROs & RO retakes) (N)ew or (M)odified from bank (2 1) (P)revious 2 exams (5 1; randomly selected)

ES 301, Page 22 of 27 ES-301 Control Roomhn-Plant Systems Outline Form ES-301-2 Facility:

Limerick Exam Level: RO [XI SRO-I SRO-U 0 Date of Examination:

10/23/06 Operating Test Number:

ILT05-1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF) Safety Type 'Ode* Function System / JPM Title

a. Reactor RecirciStart MG Set - High Vibration b. Shutdown "1 C" Reactor Feed Pump From Standby Condition A, L, P, S 1 A, N, S 2 c. Manually Initiate a Control Room Ventilation Radiation Isolation 1 p,s I 9 d. Manually Initiate Core Spray

("D" Core Spray Pump fails to start)

A, N, S 4 e. Restore RECW, DWCW, PClG D, s 5 f. DG Fast Start From Control Room (Jacket Water High Temp) A, N, S 6 g. Scram Reset A, D, S 7 h. Placing Alternate RECW Pump in Service in-Plant Systems@

(3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) A, N, S 8 i. Start "OB" ESW Pump From D12 SG (SE-6) j. Place Alternate CRD Flow Control Valve In Service k. MSlV -129" Bypass (T-221)

ID,E,RI 4 @ 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 (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (L)ow-Power

/ Shutdown (N)ew or (M)odified from bank including (P)revious 2 exams (WCA (S)imulator Criteria for RO

/ SRO-I I SRO-U 4-6 / 4-6 / 2 <9/ (8 /(4 - >I/ 21 />I - >I/ 21 />I - >2/ 22 /,I - >I/ 21 /?I - 3 3 / 5 2 (randomly selected)

ES-301, Page 23 of 27 ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 -acility: Limerick Exam Level: RO 0 SRO-I SRO-U 0 Date of Examination:

10123/06 Operating Test Number: ILT05-1 Zontrol Room Systems@ (8 for RO); (7 for SRO-I);

(2 or 3 for SRO-U, including 1 ESF) Safety Type 'Ode* Function System I JPM Title

3. Reactor Recirc/Start MG Set - High Vibration
3. Shutdown "1 C" Reactor Feed Pump From Standby Condition A, L, P, S 1 2 c. Manually Initiate a Control Room Ventilation Radiation Isolation
d. Manually Initiate Core Spray ("D" Core Spray Pump fails to start) P, s 9 A, N, S 4 A, N, S 6 e. DG Fast Start From Control Room (Jacket Water High Temp)
f. Scram Reset A, D, S 7 g. Placing Alternate RECW Pump in Service A, N, S 8 h. In-Plant Systems@ (3 for RO); (3 for SRO-I);

(3 or 2 for SRO-U) i. Start"0B" ESW Pump From D12 SG (SE-6) D, E, R 8 j. Place Alternate CRD Flow Control Valve In Service D, L, R 1 k. MSlV -129" Bypass (T-221) ID,E,R/ 4 @ 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 (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (L)ow-Power

/ Shutdown (N)ew or (M)odified from bank including (P)revious 2 exams (S)imulator Criteria for RO / SRO-l I SRO-U 4-6 I 4-6 I 2-3 ES-301, Page 23 of 27 ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 b. DG Fast Start From Control Room (Jacket Water High Temp) A, N, S . 6 (ESF) 1 Facility: Limerick Exam Level: RO 0 SRO-I 0 SRO-U c. Restore RECW, DWCW, PClG d. Date of Examination: 10/23/06 Operating Test Number: ILT05-1 D, S 5 a. Reactor RecircIStart MG Set - High Vibration

e. II ~~ I I u f. 9. h. 11 Implant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) ' i. Start "OB" ESW Pump From Dl2 SG (SE-6) D, E, R 8 j. MSlV -129" Bypass (T-221) D, E, R 4 k. @ 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-I I SRO-U (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (L)ow-Power I Shutdown (N)ew or (M)odified from bank including l(A) (P)revious 2 exams (S)imulator (R)CA 4-6 I 4-6 / 2-3 ES-301, Page 23 of 27 Appendix D Scenario Outline Form ES-D-1 4 Facility: Limerick Scenario No.: 1 Op-Test No.: ILT05-1 MED263D Examiners: Operators:

6 Initial Conditions: 100% power. RCIC is out of service for bearing replacement. Regulatory actions log entry has been made. Estimated time of repair is 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

MRR441 Turnover: Maintain 100%

power. Continue repairs on RCIC. The crew is to perform ST-6-047-200-1, SDV Valve Exercise Test. Event J-7F I MFW245C I MH P448B Event Type* N (ALL) I (PRO/CRS)

C (ROKRS) R (PRO) C (ALL) Event Description Perform ST-6-047-200-1, SDV Valve Exercise Test Inadvertent isolation of PClG (TS)

RFP "B" high vibration, power reduction, remove "B" RFP from service. D14 bus overcurrenffloss of D14 bus (TS), loss of "B" CRD pump and "B" drywell chiller.

C (ALL) SRV "L" fails open mechanically Coolant leakage / "B" Feedwater line rupture inside Primary Containment C (PRO/CRS)

HPCl speed/flow controller fails low in AUTO with subsequent HPCl turbine trip * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor APPENDIX D, Page 38 of 39 Appendix D Scenario Outline Form ES-D-1 Event Type*

R (PRO) I (RO/CRS) C (PRO/CRS)

Facility:

Limerick Scenario No.: 2 Op-Test No.: ILT05-1 Event Description Raise power to 100% with recirc. "A RPV Pressure Transmitter (RPS) fails high (TS). RECW valve to RWCU non-regen heat exchanger closes. RWCU outboard isolation valve does not automatically isolate on high demin. inlet temp. Exami ne rs : 0 pera to rs : C (PRO/ CRS)

R (RO) M (ALL) Initial Conditions: 95% power recovering from a planned down power to perform a minor rod pattern adjustment.

"IB" Recirc Pump trips (TS) Insert control rods to exit Restricted Region "1A Recirc Pump trips / ATWS - "B" RPS fails to trip, both RRCS channels fail to initiate ARI Turnover: 95%

power. The minor rod pattern adjustment is complete. Raise power to 100% using GP-5, Appendix 2, and OP-AB-300-1003 without RE presence in the MCR. 5 Event Malf. N/A MRR435A MRP029D MRP407C RCW219 MCU002B C (RO/CRS) C (PRO/CRS)

I MRR435B SLC pipe rupture in drywell Main turbine bypass valves fail closed EHC load set runs back to minimum MEH 108 MEHl04B * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor APPENDIX D, Page 38 of 39 Appendix D Scenario Outline Form ES-D-I Event No. 1 2 3 4 5 6 Facility:

Limerick Scenario No.: 3 Op-Test No.: ILT05-1 Examiners: Operators:

Malf. Event Type*

Event No. Description N/A N (PRO) Start the "IC condensate pump for PMT N/A R (RO)

Continue to withdraw control rods MSR214F I (RO/CRS) IRM channel "F" fails upscale (TS) E51 -S37-PB C (CRS) VlCl14A C (RO/CRS)

"1A CRD Pump high vibration MRR441 M (ALL) MMS067 in the drywell RClC inadvertent start and RPV injection (TS) Small coolant leak followed by a large steam leak 7 8 9 MRP029C C (RO/CRS) "A RPS failure to scram MRH171A C (PRO/CRS)

"A RHR pump trips on start signal MRH574A MRH171B HV51-1 F024B fails due to thermal overload "B" RHR pump trips when attempting to spray the drywell / must spray drywell with RHRSW. C (ALL) * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor APPENDIX D, Page 38 of 39