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{{#Wiki_filter:BWR Examination Outline Form ES-401-1 ES-401 Facilitv: Peach Bottom Printed: 01/24/2007 Date Of Exam: 02/05/2007 Note: 1. 2. 3. 4. 5. 6. Ensure that at least iwo 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.
{{#Wiki_filter:ES-401                                    BWR Examination Outline                                 Form ES-401-1 Facilitv:   Peach Bottom                                                                   Printed: 01/24/2007 Date Of Exam:     02/05/2007 Note:
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 ES401, 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.
: 1. Ensure that at least iwo 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).
Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
: 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 +from I 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.
Select SRO topics for Tiers 1 and 2 from the shaded systems and WA categories.
: 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 ES401, Attachment 2, for guidance regarding the elimination of inappropriate WA statements.
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
: 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.
(#) for each system and category.
: 5. 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.
Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #I does not apply). Use duplicate pages for RO and SRO-only exams.
: 6. Select SRO topics for Tiers 1 and 2 from the shaded systems and WA categories.
: 9. For Tier 3, select topics from Section 2 of the WA catalog, and enter the WA numbers, descriptions, IRs, and point totals
7.* 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 Form ES401-3. Limit SRO selections to WAS that are linked to 10 CFR 55.43. 1 BWR RO Examination Outline Printed: 0 1 /24/2007 Form ES-401-1 Facility:
: 8. 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; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note # I does not apply). Use duplicate pages for RO and SRO-only exams.
Peach Bottom ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 /Group 1 (RO I SRO) ' "/APE # / Name / Safety Function K1 K2 K3 ,4500 1 Partial or Complete Loss of Forced Core Flow Circulation I 1 & 4 295003 Partial or Complete Loss of AC Pwr 16 295026 Suppression Pool High Water 295028 High Drywell Temperature
: 9. For Tier 3, select topics from Section 2 of the WA catalog, and enter the WA numbers, descriptions, IRs, and point totals (#) on Form ES401-3. Limit SRO selections to WAS that are linked to 10 CFR 55.43.
/ 5 295030 Low Suppression Pool Wtr Lvl 15 Temp. 15 ~~ ~ I lxl 295004 Partial or Complete Loss of DC Pwr I6 X X X 295005 Main Turbine Generator Trip  
1
/ 3 I I 1 29503 1 Reactor Low Water Level I 2 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown I 1 295038 High Off-Site Release Rate 19 295006 SCRAM / 1 I I Ix X 2950 16 Control Room Abandonment I 7 1 I I X 600000 Plant Fire On Site / 8 WA Category Totals: I I Ix 29501 8 Partial or Total Loss of CCW I 8 3 3 4 2950 18 Partial or Total Loss of CCW / 8 2950 19 Partial or Total Loss of Instrument Air 18 I II 295021 Loss of Shutdown Cooling 14 I X I I 5023 Refueling Acc I8 1' 295024 High Drywell Pressure I 5 1x1 I 295025 High Reactor Pressure 13 1 BWR RO Examination Outline Facility:
 
Peach Bottom Printed: 0 1/24/2007 1
BWR RO Examination Outline                       Printed: 0 1/24/2007 Facility:     Peach Bottom ES - 401                   Emergency and Abnormal Plant Evolutions - Tier 1 /Group 1 (RO I SRO)       Form ES-401-1
BWR RO Examination Outline Printed: 0 1 /24/2007 Facility: Peach Bottom 1
' "/APE # / Name / Safety Function
2 BWR RO Examination Outline Printed: 0 1 /24/2007 Facility:
  ,4500 1 Partial or Complete Loss of Forced K1 K2 K3 Core Flow Circulation I 1 & 4 295003 Partial or Complete Loss of AC Pwr 16
Peach Bottom 2.4.3 1 - Knowledge of annunciators alarms and 1
            ~~       ~
Generic Knowledge and Abilities Outline (Tier
295004 Partial or Complete Loss of DC Pwr I6 295005 Main Turbine Generator Trip / 3 II Il x 1l 295006 SCRAM / 1                           I I       I x 2950 16 Control Room Abandonment I 7         1   I   IX 29501 8 Partial or Total Loss of CCW I 8 2950 18 Partial or Total Loss of CCW / 8 I I Ix 2950 19 Partial or Total Loss of Instrument Air 1 8 I I I 295021 Loss of Shutdown Cooling 1 4          IX I I 5023 Refueling Acc I 8 1 '
: 3) BWR RO Examination Outline Printed: 0 1 /24/2007 Facility: Peach Bottom Date of Exam: Form ES-401-3 KA# Topic - IR E L-4' CatePory 2.1.1 2.1.20 Conduct of Operations Knowledge of conduct of operations requirements.
295024 High Drywell Pressure I 5 295025 High Reactor Pressure 1 3 1x1     I 295026 Suppression Pool High Water                X Temp. 1 5 295028 High Drywell Temperature / 5                    X 295030 Low Suppression Pool Wtr Lvl 1 5            X 29503 1 Reactor Low Water Level I 2 295037 SCRAM Condition Present and            X Reactor Power Above APRM Downscale or Unknown I 1 295038 High Off-Site Release Rate 1 9 600000 Plant Fire On Site / 8 WA Category Totals:      3  3  4 1
3.7 1 Ability to execute procedure steps. 4.3 1 Knowledge of the process for determining the internal and external effects on core reactivity.
 
BWR RO Examination Outline Printed: 0 1/24/2007 Facility: Peach Bottom 1
 
BWR RO Examination Outline Printed: 0 1/24/2007 Facility: Peach Bottom 1
 
2 BWR RO Examination Outline                       Printed: 0 1 /24/2007 Facility: Peach Bottom 2.4.3 1 - Knowledge of annunciators alarms and 1
 
Generic Knowledge and Abilities Outline (Tier 3)
BWR RO Examination Outline                                   Printed: 0 1/24/2007 Facility:     Peach Bottom                                   Date of Exam:                               Form ES-401-3 L-4 CatePory                                    KA#                             Topic                             -IR       E Conduct of Operations                2.1.1   Knowledge of conduct of operations requirements.                   3.7       1 2.1.20  Ability to execute procedure steps.                               4.3       1 Subtotal:                                                                                2
  ~      ~    ~    ~~~
Equipment Control                  2.2.24  Ability to analyze the affect of maintenance activities on LCO status.
2.2.28  Knowledge of new and spent fuel movement procedures.          1  2.6  1    1    I 2.2.34  Knowledge of the process for determining the internal and         2.8        1 external effects on core reactivity.
Subtotal:
Subtotal:
2 2.8 1 ~ ~ ~ ~~~
I  Radiation Control                    2.3.2 2.3.4 2.3.1 1 Knowledge of facility ALARA program.
Equipment Control 2.3.2 Knowledge of facility ALARA program. 2.2.24 2.5 1 2.2.28 2.2.34 Subtotal:
Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized.
Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized.
Ability to analyze the affect of maintenance activities on LCO status. 2.5 1 Knowledge of new and spent fuel movement procedures.
Ability to control radiation releases.                         I 2.5 2.5 2.7  I 1
1 2.6 1 1 I 2.4.2 Knowledge of system set points, interlocks and automatic Ability to prioritize and interpret the significance of each actions associated with EOP entry conditions.
1 1
2.4.45 annunciator or alarm. 3.9 1 3.3 1 Radiation Control I Emergency Plan P 2.3.4 2.3.1 1 Ability to control radiation releases.
P  Emergency Plan                      2.4.2 2.4.45 Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.
I 2.7 I 1 Tier 3 Point Total:
Ability to prioritize and interpret the significance of each 3.9 3.3 1
10 1 BWR Examination Outline Form ES-401-1 ES-401 :volu tions 2. Plant Systems Totals 0 0 0 00 00 7 3 10 1 000000000000 3 2 5 2 000000000000 02 1 3 . Totals Tier 0 0 0 0 0 0 0 0 0 0 0 0 5 3 8 1. 2. 3. 4. 5. 6. 7.* 8. 9. 3. Generic Knowledge And Abilities Categories Ensure that at least Wo 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 _+I from that specified in the table based on NRC revisions.
1 annunciator or alarm.
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.
Tier 3 Point Total:                                                                                                            10 1
Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
 
Select SRO topics for Tiers I and 2 from the shaded systems and WA categories.
ES-401                                    BWR Examination Outline                                Form ES-401-1 Totals  0  0    0                  0    0              0  0            7           3       10
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; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #I does not apply). Use duplicate pages for RO and SRO-only exams.
:volutions 1     0  0    0    0    0  0  0    0  0    0     0   0           3           2       5 2.
For Tier 3, select topics from Section 2 of the WA catalog, and enter the WA numbers, descriptions, IRs, and point totals
2    0  0    0    0    0  0  0    0  0    0    0  0          0      2      1      3 Plant .
(#) on Form ESllOl-3, Limit SRO selections to WAS that are linked to 10 CFR 55.43. 1 2 3 4 1234 0 0 0 0 2212 0- 7 1 BWR SRO Examination Outline Printed: 0 1/24/2007 Facility: Peach Bottom ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 1 (RO I SRO) Form ES-401-1 I SIAPE # I Name I Safety Function ~5003 Partial or Complete Loss of AC Pwr /6 295004 Partial or Complete Loss of DC Pwr /6 29501 8 Partial or Total Loss of CCW / 8 2950 19 Partial or Total Loss of Instrument Air I 8 295023 Refueling Acc 18 29503 1 Reactor Low Water Level / 2 600000 Plant Fire On Site 18 KIA Category Totals: 1 7 BWR SRO Examination Outline Facility:
Systems Tier         0   0   0     0   0   0   0   0   0   0     0   0               5     3       8 Totals 1       2       3         4             1    2      3    4
Peach Bottom Printed: 0 1 12412007 ES - 401 Emergency and Abnormal Pian I II 295036 Secondary Containment High SumpIArea Water Level 15 I WA Category Totals: I 0 I 0 I 0 Evolutions - Tier 1 / Group 2 (RO / SRO) Form ES-401-1 1 Printed: 0 1/24/2007 BWR SRO Examination Outline Facility:
: 3. Generic Knowledge And 0 -                              7 Abilities Categories           0        0        0        0            2    2      1    2
Peach Bottom 1 Printed: 0 1 /24/2007 Form ES-401-1 BWR SRO Examination Outline Facility:
: 1. Ensure that at least Wo 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).
Peach Bottom ES - 401 Plant Systems - Tier 2 / Croup 2 (RO / SRO) . stem limits and c-' I Generic Knowledge and Abilities Outline (Tier 3) BWR SRO Examination Outline Date of Exam: KA # Took - 2.1.4 2.1.6 Facilitv: Peach Bottom
: 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 _+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.
'ii' CatePory Knowledge of shift staffing requirements.
: 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 WA statements.
3.4 1 Ability to supervise and assume a management role 4.3 1 during plant transients and upset conditions.
: 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.
Printed: 0 1 I2412007 Form ES-401 IR !? Equipment Control Conduct of Operations 2.2.18 Knowledge of the process for managing maintenance 3.6 1 2.2.29 Knowledge of SRO fuel handling responsibilities.
: 5. 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.
3.8 1 activities during shutdown operations.
: 6. Select SRO topics for Tiers Iand 2 from the shaded systems and WA categories.
Subtotal:
7.* 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.
2 2.3.1 Knowledge of 10 CFR 20 and related facility radiation 3 .O 1 control requirements.
: 8. 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; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note # I does not apply). Use duplicate pages for RO and SRO-only exams.
Radiation Control 2.4.22 2.4.33 Knowledge of the bases for prioritizing safety functions 4.0 1 Knowledge ofthe process used track inoperable alarms. 2.8 1 during abnormallemergency operations. Emergency Plan
: 9. For Tier 3, select topics from Section 2 of the WA catalog, and enter the WA numbers, descriptions, IRs,and point totals (#) on Form ESllOl-3, Limit SRO selections to WAS that are linked to 10 CFR 55.43.
.~ -- I ~ ~ Tier 3 Point Total: 7 I ES-401 Record of Rejected WAS Form ES-401-4 Tier I Group RO 211 RO 212 SRO 111 SRO 1 12 SRO 211 SRO 111 RO 1 I1 RO 211 SRO 1 I1 Reason for Rejection Peach Bottom uses static inverters for uninterruptable power supplies, not  
1
~ Randomly Selected KIA 262002 AI .02 motor-generators.
 
290003 A3.02 At Peach Bottom, there is no direct association between the Control Room HVAC System and the Fire Protection System.
BWR SRO Examination Outline                           Printed: 0 1/24/2007 Facility:   Peach Bottom ES - 401                   Emergency and Abnormal Plant Evolutions - Tier 1 I Group 1 (RO I SRO)       Form ES-401-1 I SIAPE # I Name I Safety Function
295024 A205 Peach Bottom has no direct indication or procedural guidance for determining suppression chamber air space temperature. 295008 G2.4.49 Unable to construct an SRO question for this KA that meets the requirements of NUREG-1023.
  ~ 5 0 0 Partial 3    or Complete Loss of AC Pwr
259002 G2.1 .I4 Unable to construct an SRO question for this KA that meets the requirements of NUREG-1023. G2.3.2 This KA was already sampled on the RO portion of the exam. Unable to construct an additional question at the SRO level. 295026 EK2.06 Unable to construct an RO question for this KA that meets the requirements of NUREG-1023.
  /6 295004 Partial or Complete Loss of DC Pwr
21 1000 K5.05 Unable to construct an RO question for this KA that meets the requirements of NUREG-1023. 295026 G2.4.30 Unable to construct an SRO level quesiton for this KA that also meets the criteria of 10CFR55.43(b).
  /6 29501 8 Partial or Total Loss of CCW / 8 2950 19 Partial or Total Loss of Instrument Air I 8 295023 Refueling Acc 1 8                                                                                          1 29503 1 Reactor Low Water Level / 2 600000 Plant Fire On Site 1 8 KIA Category Totals:                                                                         7
ES-401, Page 27 of 33 r- ES-301 Administrative Topics Outline Form ES-301-1 acility: Peach Bottom tamination Level: RO [7 SRO Date of Examination: 2/5/2007 Operating Test Number: 2007 NRC Administrative Topic (See Note) Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency Plan TY Pe Code* N, R M. R Describe activity to be performed G2.1.4 - Evaluate Shift Staffing H G2.1.7 - Evaluate A PI Edit And Take Corrective Action For A Thermal Limit Violation [PLOR-218C]
 
G2.2.21 - Determine Post Maintenance Test Requirements For Valve Operability
BWR SRO Examination Outline                         Printed: 0 112412007 Facility: Peach Bottom ES - 401                   Emergency and Abnormal Pian Evolutions - Tier 1 / Group 2 (RO / SRO)       Form ES-401-1 295036 Secondary Containment High SumpIArea Water Level 1 5              II II II I                    WA Category Totals:    0  0    0 1
[NEW] G2.3.9 - Review And Approve Primary Containment PurgeNent Isolation Valve Cumulative Hour Log [NEW] G2.4.38 - Review And Authorize Issuance Of Thyroid Blocking Agent (KI) [PLOR-215C]
 
BWR SRO Examination Outline Printed: 0 1/24/2007 Facility: Peach Bottom 1
 
BWR SRO Examination Outline                      Printed: 0 1/24/2007 Facility: Peach Bottom ES - 401               Plant Systems - Tier 2 / Croup 2 (RO / SRO)                 Form ES-401-1
.
stem limits and c-'
I
 
Generic Knowledge and Abilities Outline (Tier 3)
BWR SRO Examination Outline                               Printed: 0 1 I2412007 Facilitv:  Peach Bottom                                  Date of Exam:                           Form ES-401-3
'  i i '
CatePory                                -
KA #                            Took                          -IR        ?!
Conduct of Operations            2.1.4   Knowledge of shift staffing requirements.                     3.4           1 2.1.6  Ability to supervise and assume a management role             4.3           1 during plant transients and upset conditions.
Equipment Control                2.2.18   Knowledge of the process for managing maintenance             3.6           1 activities during shutdown operations.
2.2.29   Knowledge of SRO fuel handling responsibilities.               3.8           1 Subtotal:                                                                              2 Radiation Control                2.3.1   Knowledge of 10 CFR 20 and related facility radiation         3.O           1 control requirements.
Emergency Plan                  2.4.22   Knowledge of the bases for prioritizing safety functions       4.0           1 during abnormallemergency operations.
.~                                    2.4.33  Knowledge ofthe process used track inoperable alarms.         2.8           1
-- I         ~     ~
Tier 3 Point Total:                                                                                                       7 I
 
ES-401                           Record of Rejected WAS                               Form ES-401-4 Tier I     Randomly Reason for Rejection
          ~
Group      Selected KIA RO       262002 A I .02 Peach Bottom uses static inverters for uninterruptable power supplies, not 211                      motor-generators.
RO      290003 A3.02   At Peach Bottom, there is no direct association between the Control Room 212                      HVAC System and the Fire Protection System.
SRO      295024 A 2 0 5 Peach Bottom has no direct indication or procedural guidance for 111                      determining suppression chamber air space temperature.
SRO    295008 G2.4.49   Unable to construct an SRO question for this KA that meets the 1 12                    requirements of NUREG-1023.
SRO    259002 G2.1 . I 4 Unable to construct an SRO question for this KA that meets the 211                      requirements of NUREG-1023.
SRO          G2.3.2     This KA was already sampled on the RO portion of the exam. Unable to 111                      construct an additional question at the SRO level.
RO    295026 EK2.06     Unable to construct an RO question for this KA that meets the 1I 1                    requirements of NUREG-1023.
RO      21 1000 K5.05 Unable to construct an RO question for this KA that meets the 211                      requirements of NUREG-1023.
SRO    295026 G2.4.30   Unable to construct an SRO level quesiton for this KA that also meets the 1I 1                    criteria of 10CFR55.43(b).
ES-401, Page 27 of 33
 
r - ES-301                           Administrative Topics Outline                           Form ES-301-1 acility: Peach Bottom                                             Date of Examination: 2/5/2007 tamination Level: RO [7 SRO                                      Operating Test Number: 2007 NRC AdministrativeTopic              TYPe                    Describe activity to be performed (See Note)             Code*
Conduct of Operations                         G2.1.4 - Evaluate Shift Staffing H
G2.1.7 - EvaluateA PI Edit And Take Corrective Action Conduct of Operations For A Thermal Limit Violation [PLOR-218C]
G2.2.21 - Determine Post MaintenanceTest Equipment Control                  N, R        Requirements For Valve Operability [NEW]
G2.3.9 - Review And Approve Primary Containment Radiation Control PurgeNent Isolation Valve Cumulative Hour Log [NEW]
G2.4.38 - Review And Authorize Issuance Of Thyroid Emergency Plan                    M. R        Blocking Agent (KI)[PLOR-215C]
OTE: 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.
OTE: 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)
Type Codes & Criteria:             (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (53 for ROs; 5 4 for SROs & RO retakes)
ES 301, Page 22 of 27
(N)ew or (M)odified from bank (2 1)
, ES-301 Administrative Topics Outline Form ES-301-1 3cility: Peach Bottom xamination Level: RO [XI SRO 0 Date of Examination: 2/5/2007 Operating Test Number: 2007 NRC Administrative Topic (See Note) Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency Plan TY Pe Code* Describe activity to be performed G2.1.7 - Calculate Drywell Bulk Average Temperature
(P)revious 2 exams (5 1; randomly selected)
[2005 NRC] G2.1.25 - Perform Reactor Coolant Leakage Surveillance
ES 301,Page 22 of 27
[NEW G2.2.11 - Prepare A Partial Procedure [PLOR-205C]
 
G2.4.43 - Perform Personnel Notifications During A Security Threat [PLOR-217C]
, ES-301                           Administrative Topics Outline                           Form ES-301-1 3cility: Peach Bottom                                             Date of Examination: 2/5/2007 xamination Level: RO [XI SRO      0                              Operating Test Number: 2007 NRC Administrative Topic           TYPe                      Describe activity to be performed (See Note)               Code*
G2.1.7 - Calculate Drywell Bulk Average Temperature Conduct of Operations
[2005 NRC]
G2.1.25 - Perform Reactor Coolant Leakage Surveillance Conduct of Operations
[NEW Equipment Control                              G2.2.11 - Prepare A Partial Procedure [PLOR-205C]
Radiation Control G2.4.43 - Perform Personnel Notifications During A Emergency Plan Security Threat [PLOR-217C]
OTE: 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.
OTE: 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)
Type Codes & Criteria:             (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (53 for ROs; 5 4 for SROs & RO retakes)
ES 301, Page 22 of 27 4,' a. 295037 EA1.04 - Inject Boron Into RPV (Alternate Path - RWCU Fails To Isolate) [PLOR-301 CAI - SET 1 ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: Peach Bottom Exam Level: RO SRO-I 0 SRO-U 0 Date of Examination: 2/5/2007 Operating Test Number:
(N)ew or (M)odified from bank (2 1)
2007 NRC A, D, S Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF) d. 209001 A4.04 - Perform Core Spray B Pump Capacity Test For IST
(P)revious 2 exams (5 1; randomly selected)
: e. 219000 A4.13 - HPSW Injection Into The Torus [PLOR-O81C] - SET 1 [NEW] - SET 4 System / JPM Title N, s D, s Type Code*
ES 301,Page 22 of 27
: f. 262001 A4.04 - Synchronize Turbine Generator Output With Grid At g. 295018 AA1.01 - Emergency Cooling Water System Startup [PLOR-
 
: h. 261 000 A2.10 - PRO Scram Actions (Alternate Path - SBGT Fails To Minimum Load
ES-301                           Control Roomlln-Plant Systems Outline                             Form ES-301-2 Facility: Peach Bottom                                                   Date of Examination: 2/5/2007 Exam Level: RO             SRO-I 0 SRO-U 0                               Operating Test Number: 2007 NRC Control Room Systems@(8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
[PLOR-O17C] - SET 4 028Cl- SET 3 Automatically Initiate)
Safety System / JPM Title                                      Type Code*
[NEW] - SET 2 D, s M, s A, L, N, s b. 295031 EA1.02 - Manually Initiate HPCl (Alternate Path - Manual Initiation Pushbutton Fails To Operate) [PLOR300CA] - SET 2 c. 218000 A4.03 - ADS Reset Following Blowdown
Function
[PLOR-O23C
: a. 295037 EA1.04 - Inject Boron Into RPV (Alternate Path - RWCU Fails To                    A, D, S          1 Isolate) [PLOR-301CAI - SET 1
/ 2005 NRC] - SET 3 i. 201001 A2.09 - Low CRD Scram Air Header Pressure - Unit 3 (Alternate
: b. 295031 EA1.02 - Manually Initiate HPCl (Alternate Path - Manual                                            2 Initiation Pushbutton Fails To Operate) [PLOR300CA] - SET 2
: i. 295031 EA1.05 - Defeat RClC Low Pressure Isolation - Unit 2 k. 264000 A2.10 - Diesel Generator Air Start Solenoid Override Path - Place Standby Regulator In Service) [PLOR-316PA
: c. 218000 A4.03 - ADS Reset Following Blowdown [PLOR-O23C / 2005                                              3 NRC] - SET 3
/ 2002 NRC]
: d. 209001 A4.04 - Perform Core Spray B Pump Capacity Test For IST                             N, s            4
[NEW] - SET 4
: e. 219000 A4.13 - HPSW Injection Into The Torus [PLOR-O81C] - SET 1                           D, s             5
: f. 262001 A4.04 - Synchronize Turbine Generator Output With Grid At                           D, s            6 Minimum Load [PLOR-O17C] - SET 4
: g. 295018 AA1.01 - Emergency Cooling Water System Startup [PLOR-                             M, s            8 028Cl- SET 3
: h. 261000 A2.10 - PRO Scram Actions (Alternate Path - SBGT Fails To                       A, L, N, s         9 4,'
Automatically Initiate) [NEW]- SET 2
: i. 201001 A2.09 - Low CRD Scram Air Header Pressure - Unit 3 (Alternate                     A, D, E,          1 Path - Place Standby Regulator In Service) [PLOR-316PA / 2002 NRC]                        p, R
: i. 295031 EA1.05 - Defeat RClC Low Pressure Isolation - Unit 2                               D, E, R          2
[PLOR-O86P]
[PLOR-O86P]
: k. 264000 A2.10 - Diesel Generator Air Start Solenoid Override                                D, E            6
[PLOR-O49P]
      @        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.
I
                        *Type Codes                                    Criteria for RO / SRO-I / SRO-U I
(A)lternate path                                            4-6 I 4-6 I 2-3 (C)ontrol room 4 (D)irect from bank (E)mergency or abnormal in-plant (L)ow-Power I Shutdown (N)ew or (M)odified from bank including 1(A)
(P)revious 2 exams (WA (S)imulator ES-301, Page 23 of 27
ES-301                        Control Roomlln-Plant Systems Outline                    Form ES-301-2 Facility: Peach Bottom                                          Date of Examination: 21512007 Exam Level: RO 0 SRO-I          SRO-U [7                        Operating Test Number: 2007 NRC Control Room Systems* (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System I JPM Title                              I            1  Safety Function
: a. 295037 EA1.04 - Inject Boron Into RPV (Alternate Path - RWCU Fails To        A, D, S        1 Isolate) [PLORdOl CAI - SET I
: b. 295031 EA1.02 - Manually Initiate HPCl (Alternate Path - Manual              A, D, L, s      2 Initiation Pushbutton Fails To Operate) [PLOR300CA] - SET 2
: c. 218000 A4.03 -ADS Reset Following Blowdown [PLOR-O23C I2005                  D, L, P, s      3 NRCl - SET 3
: d. 209001 A4.04 - Perform Core Spray 6 Pump Capacity Test For IST                  N,s          4
[NEW] - SET 4
: e. 219000 A4.13 - HPSW Injection Into The Torus [PLOR-O81C] - SET 1                D, s          5
: g. 295018 AA1.01 - Emergency Cooling Water System Startup [PLOR-                  M, s          8 028Cl- SET 3
: h. 261000 A2.10 - PRO Scram Actions (Alternate Path - SBGT Fails To            A, L, N, s      9 Automatically Initiate) [NEW] - SET 2
: i. 201001 A2.09 - Low CRD Scram Air Header Pressure - Unit 3 (Alternate          A, D, E,      1 Path - Place Standby Regulator In Service) [PLOR-316PA 12002 NRC]              p, R
: j. 295031 EA1.05 - Defeat RClC Low Pressure Isolation - Unit 2                  D, E, R        2
[PLOR-086Pl
: k. 264000 A2.10- Diesel Generator Air Start Solenoid Override                      D,E          6
                  *Type Codes                              Criteria for RO I SRO-I I SRO-U (A)lternate path                                                  4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank                                                -
                                                                    < 9 / (8 1 5 4 (Epergency or abnormal in-plant                                    -
                                                                    > I / 21 1 2 1 (L)ow-Power / Shutdown (N)ew or (M)odified from bank including I(A)
(P)revious 2 exams                                    -
                                                      < 3 11 3 I  (2  (randomly selected)
(R)CA                                                              -
                                                                    > I 1 >I/ > I (S)imulator
ES-301                            Control Roomlln-Plant Systems Outline                            Form ES-301-2 Facility: Peach Bottom                                                  Date of Examination: 2/5/2007 Exam Level: RO 0 SRO-I 0 SRO-U [XI                                      Operating Test Number: 2007 NRC Control Room Systems@(8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System I JPM Title                                    I Type Code*        Safety Function a.
: b. 295031 EA1.02 - Manually Initiate HPCl (Alternate Path - Manual                        A, D, L, S        2 Initiation Pushbutton Fails To Operate) [PLOR-300CA] - SET 2                              ESF
: c. 218000 A4.03 - ADS Reset Following Blowdown [PLOR-O23C / 2005                          D, L, p, s        3 NRC] - SET 3                                                                              ESF
: d. 209001 A4.04 - Perform Core Spray B Pump Capacity Test For IST                            N, s            4
[NEW] - SET 4                                                                              ESF e.
f.
h.
In-Plant Systems@(3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
: i. 201001 A2.09 - Low CRD Scram Air Header Pressure - Unit 3 (Alternate                    A, D, E, Path - Place Standby Regulator In Service) [PLOR316PA 12002 NRC]
i.
: k. 264000 A2.10 - Diesel Generator Air Start Solenoid Override
[PLOR-O49P]
[PLOR-O49P]
A, D, E, p, R D, E, R D, E Safety Function 1 2 3 4 5 6 8 9 1 2 6 @ 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.
  @       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.
I *Type Codes Criteria for RO / SRO-I / SRO-U I 
                    *Type Codes                                     Criteria for RO I SRO-I / SRO-U (A)lternate path                                                           4-6 I 4-6 I 2-3 (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 I(A)
'4 (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 1(A) (P)revious 2 exams (WA (S)imulator 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 a. 295037 EA1.04 - Inject Boron Into RPV (Alternate Path - RWCU Fails To b. 295031 EA1.02 - Manually Initiate HPCl (Alternate Path - Manual c. 218000 A4.03 -ADS Reset Following Blowdown
(P)revious 2 exams (WA (S)imulator ES-301, Page 23 of 27
[PLOR-O23C I2005 Isolate) [PLORdOl CAI - SET I Initiation Pushbutton Fails To Operate) [PLOR300CA] - SET 2 NRCl - SET 3 Facility: Peach Bottom Exam Level: RO 0 SRO-I SRO-U [7 A, D, S 1 A, D, L, s 2 D, L, P, s 3 Date of Examination:
 
21512007 Operating Test Number: 2007 NRC d. 209001 A4.04 - Perform Core Spray 6 Pump Capacity Test For IST e. 219000 A4.13 - HPSW Injection Into The Torus
Scenario Outline                                       ES-D-1 1
[PLOR-O81C] - SET 1 [NEW] - SET 4 Control Room Systems*
Simulation Facility Peach Bottom              Scenario No.               -
(8 for RO); (7 for SRO-I);
                                                                            #1        Op Test No. 2007 NRC Examiners                                                        Operators                              CRS (SRO)
(2 or 3 for SRO-U, including 1 ESF) N, s 4 D, s 5 System I JPM Title g. 295018 AA1.01 - Emergency Cooling Water System Startup [PLOR- 028Cl- SET 3 h. 261000 A2.10 - PRO Scram Actions (Alternate Path - SBGT Fails To Automatically Initiate)
URO (ATC)
[NEW] - SET 2 Safety I 1 Function M, s 8 A, L, N, s 9 i. 201001 A2.09 - Low CRD Scram Air Header Pressure - Unit 3 (Alternate Path - Place Standby Regulator In Service) [PLOR-316PA 12002 NRC]
PRO (BOP)
: j. 295031 EA1.05 - Defeat RClC Low Pressure Isolation - Unit 2 [ PLOR-086Pl k. 264000 A2.10 - Diesel Generator Air Start Solenoid Override A, D, E, 1 D, E, R 2 p, R D, E 6 *Type Codes (A)lternate path (C)ontrol room (D)irect from bank (Epergency or abnormal in-plant Criteria for RO I SRO-I I SRO-U 4-6 I 4-6 I 2 <9/ (8 154 - >I/ 21 121 (L)ow-Power
Scenario    The scenario begins with the reactor at approximately 5% power during a reactor startup. Following Summary      shift turnover, the crew should continue with the reactor startup, pulling control rods in accordance with the approved startup sequence. A control rod will drift out, requiring the crew to execute ON-I21 Drifting Control Rod and declare the affected control rod inoperable.
/ Shutdown (N)ew or (M)odified from bank including I(A) (P)revious 2 exams (S)imulator (R)CA - < 3 11 3 I ( 2 (randomly selected) - >I1 >I />I ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 a. b. 295031 EA1.02 - Manually Initiate HPCl (Alternate Path - Manual Initiation Pushbutton Fails To Operate) [PLOR-300CA] - SET 2 c. 218000 A4.03 - ADS Reset Following Blowdown
Following the control rod drift, the crew should secure drywell purge in preparation for inerting the drywell. Once drywell purge is secured, an inadvertent RClC initiation will occur, requiring the crew to perform a RClC shutdown and declare it inoperable. This event will be followed by a failure of the in-service CRD flow control valve, which will require the crew to enter ON-1 07 Loss of CRD Regulating Function and shift to the alternate flow control valve.
[PLOR-O23C
Next, a Recirc system leak will develop in the drywell requiring entry into OT-101 High Drywell Pressure. The crew should take actions for the rising drywell pressure and should manually scram the reactor and enter T-100 Scram. During the scram, seven rods will fail to insert resulting in an ATWS. When drywell pressure reaches 2 psig, the crew should enter T-101 RPV Control and T-102 Primary Containment Control. Multiple failures of drywell spray valves will prevent spraying the drywell, requiring the crew to perform T-I12 Emergency Blowdown when drywell temperature cannot be restored and maintained below 281 degrees F. With several rods stuck out, the crew should terminate and prevent injection in accordance with T-240 prior to the emergency depressurization.
/ 2005 NRC] - SET 3 d. 209001 A4.04 - Perform Core Spray B Pump Capacity Test For IST
Initial        IC-70, 5% power Conditions Turnover      See Attached Shift Turnover Sheet Event    Malfunction            Event                                          Event No.          No.              Type*                                        Description I                          R     URO        Power ascension with control rods CRS
[NEW] - SET 4 e. f. Facility: Peach Bottom Exam Level: RO 0 SRO-I 0 SRO-U [XI A, D, L, S ESF D, L, p, s ESF N, s ESF Date of Examination: 2/5/2007 Operating Test Number: 2007 NRC Control Room Systems@
                                              -    ~    ~~            ~~
(8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF) System I JPM Title I Type Code* h. In-Plant Systems@
2                          C     ALL        Control rod drifts out TS      .
(3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) i. 201001 A2.09 - Low CRD Scram Air Header Pressure - Unit 3 (Alternate Path - Place Standby Regulator In Service) [PLOR316PA 12002 NRC] i. k. 264000 A2.10 - Diesel Generator Air Start Solenoid Override Safety Function 2 3 4 A, D, E, [PLOR-O49P]
Secure drywell purge
@ 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 I Shutdown (N)ew or (M)odified from bank including I(A) (P)revious 2 exams (S)imulator (WA Criteria for RO I SRO-I / SRO-U 4-6 I 4-6 I 2-3 ES-301, Page 23 of 27 Scenario Outline ES-D-1 1 Event No. I 2 Simulation Facility Peach Bottom Scenario No. - #1 Op Test No. 2007 NRC Examiners Operators CRS (SRO) Malfunction Event No. Type* R URO CRS C ALL TS . URO (ATC) PRO (BOP) ~~ - ~ ~~ Control rod drifts out Scenario Summary The scenario begins with the reactor at approximately 5% power during a reactor startup. Following shift turnover, the crew should continue with the reactor startup, pulling control rods in accordance with the approved startup sequence.
                                              ~~                ~        ~~
A control rod will drift out, requiring the crew to execute ON-I21 "Drifting Control Rod" and declare the affected control rod inoperable.
Inadvertent RClC initiation 5                          C    URO        CRD flow control valve failure CRS 1    6                           M    ALL        Recirculation system leak in the drywell C    URO      Seven rods stick full out during the scram l 7                                    CRS 8                          C    PRO        Drywell spray valve failures - prevents drywell spray CRS
~~ ~~ ~ Inadvertent RClC initiation Following the control rod drift, the crew should secure drywell purge in preparation for inerting the drywell. Once drywell purge is secured, an inadvertent RClC initiation will occur, requiring the crew to perform a RClC shutdown and declare it inoperable.
 
This event will be followed by a failure of the in-service CRD flow control valve, which will require the crew to enter ON-1 07 "Loss of CRD Regulating Function" and shift to the alternate flow control valve.
Scenario Outline                                          ES-D-1.
5 C URO CRD flow control valve failure CRS 16 M ALL Recirculation system leak in the drywell C URO Seven rods stick full out during the scram CRS l7 8 C PRO Drywell spray valve failures - prevents drywell spray C RS Next, a Recirc system leak will develop in the drywell requiring entry into OT-101 "High Drywell Pressure".
Simulation Facility Peach Bottom            Scenario No.              #2              Op Test No. 2007 NRC 1 Examiners                                                        Operators                                  CRS (SRO)
The crew should take actions for the rising drywell pressure and should manually scram the reactor and enter T-100 "Scram". During the scram, seven rods will fail to insert resulting in an ATWS. When drywell pressure reaches 2 psig, the crew should enter T-101 "RPV Control" and T- 102 "Primary Containment Control". Multiple failures of drywell spray valves will prevent spraying the drywell, requiring the crew to perform T-I12 "Emergency Blowdown" when drywell temperature cannot be restored and maintained below 281 degrees F. With several rods stuck out, the crew should terminate and prevent injection in accordance with T-240 prior to the emergency depressurization.
URO (ATC)
Initial IC-70, 5% power Conditions Turnover See Attached "Shift Turnover" Sheet Event Description Power ascension with control rods Secure drywell purge Scenario Outline ES-D-1. Simulation Facility Peach Bottom Scenario No. #2 Op Test No. 2007 NRC Event Malfunction No. No. 11 Examiners Operators CRS (SRO) Event Type* URO (ATC) 2 3 4 5 6 PRO (BOP) TS CRS C URO CRS I URO TS CRS M ALL I URO CRS Scenario Summary _. The scenario begins with the plant at 76% power and the 'B' RHR pump blocked for motor replacement. Following turnover the crew will perform a main turbine master trip solenoid valves routine test. Following this test, the SBO line will fail, requiring a Tech Spec (TRM) entry. A loss of feedwater heaters will require the crew to respond to a positive reactivity addition and reduce reactor power to ensure thermal limits are not exceeded.
PRO (BOP)
The crew will then receive an RPS half scram due to a failed low vacuum pressure transmitter (blown fuse). This will require a Tech Spec entry. Troubleshooting and repairs will be time-compressed, allowing the crew to reset the half scram.
Scenario    The scenario begins with the plant at 76% power and the BRHR pump blocked for motor Summary      replacement. Following turnover the crew will perform a main turbine master trip solenoid valves
8 7 8 After RPS is reset, a steam leak will develop in the Turbine Building. As the steam leak grows in magnitude, the crew should recognize the need to shutdown the plant. During the manual scram, a reactor mode switch failure will require the crew to use the manual pushbuttons or Alternate Rod Insertion (ARI) to terminate the ATWS. C PRO CRS isolate PRO CRS pressure control I depressurization Group I failure to auto isolate
_.           routine test. Following this test, the SBO line will fail, requiring a Tech Spec (TRM) entry. A loss of feedwater heaters will require the crew to respond to a positive reactivity addition and reduce reactor power to ensure thermal limits are not exceeded. The crew will then receive an RPS half scram due to a failed low vacuum pressure transmitter (blown fuse). This will require a Tech Spec entry.
/failure of the 'D' MSL to manually C Unable to restore drywell nitrogen I only ADS SRVs available for A failure of the Group I isolation will require a manual isolation but the 'D' MSL will fail to isolate. The crew should enter T-104 "Radioactive Release" to evaluate and control the release.
Troubleshooting and repairs will be time-compressed, allowing the crew to reset the half scram.
The inability to restore instrument nitrogen to the SRVs wi!l result in a loss of all non-ADS SRVs. When the release exceeds the General Emergency level, the crew should perform an Emergency Blowdown in accordance with T-112 "Emergency Blowdown."
After RPS is reset, a steam leak will develop in the Turbine Building. As the steam leak grows in magnitude, the crew should recognize the need to shutdown the plant. During the manual scram, a reactor mode switch failure will require the crew to use the manual pushbuttons or Alternate Rod Insertion (ARI) to terminate the ATWS.
I I I I N PRO 1 CRS Event Descrintion Perform the main turbine master trip solenoid valves routine test SI30 line failure (TRM)
A failure of the Group I isolation will require a manual isolation but the D MSL will fail to isolate. The crew should enter T-104 Radioactive Release to evaluate and control the release. The inability to restore instrument nitrogen to the SRVs wi!l result in a loss of all non-ADS SRVs.
Loss of extraction steam to feedwater heaters I power reduction
When the release exceeds the General Emergency level, the crew should perform an Emergency Blowdown in accordance with T-112 Emergency Blowdown.
~~ Failure of a vacuum transmitter I RPS half scram
Event    Malfunction            Event                                            Event No.          No.               Type*                                         Descrintion I    I  I                    I  N    PRO        Perform the main turbine master trip solenoid valves routine test 1    2                        TS CRS CRS        SI30 line failure (TRM) 3                          C     URO        Loss of extraction steam to feedwater heaters I power reduction CRS
& reset Steam leak in the turbine building ~~ ~~~~~~ Reactor mode switch failure (manual scram I ARI work)
                                              ~~
Scenario Outline ES-D-1 Simulation Facility Peach Bottom Scenario No. #3 Op Test No. 2007 NRC Exam i ners Operators CRS (SRO) URO (ATC) PRO (SOP) Event No. 1 2 3 Scenario Summary The scenario begins with the reactor at 100% power. The 25 EHC Pump is blocked out of service for filter replacement. Following shift turnover, the crew should transfer RPS bus 'B' to the alternate supply to facilitate repairs for a failed trip coil on the 'B' RPS bus feeder breaker.
4                          I    URO        Failure of a vacuum transmitter I RPS half scram & reset TS    CRS 5                          M     ALL        Steam leak in the turbine building
The failed 'B' RPS feeder breaker will already be inoperable when the crew takes the shift. Malfunction Event Event No. Type* Description N TS breaker) TS CRS RClC 250 VDC bus failure C URO Lossof RBCCW ALL Transfer RPS bus to alternate supply (failed trip coil on 'B' RPS feeder CRS Following the RPS bus transfer, the RCIC 250 VDC bus will de-energize, rendering RClC inoperable and requiring a Tech Spec entry. Next, the running RBCCW pump will trip and the standby pump will fail to start, resulting in a complete loss of RBCCW. The crew should reduce RBCCW loads (e.9. RWCU) and reactor power as directed by ON-113 "Loss of RBCCW." 4 5 The crew should perform a GP-4 manual scram due to the inability to restore RBCCW to the recirculation pump motors.
                                                  ~~                  ~~~~~~
An ATWS will occur requiring the crew to execute T-101 "RPV Control" and T-I 17 "LeveVPower Control."
6                          I    URO        Reactor mode switch failure (manual scram I ARI work)
Shortly after SLC is initiated the SLC pump will trip, requiring the URO to place the alternate SLC pump in service. A drywell vent valve will fail to isolate on low RPV level and the PRO should manually isolate the valve. I I M ALL ATWS (hydraulic)
CRS 8
A failure of the only available EHC pump will cause the turbine to trip and the turbine bypass valves to close, requiring the crew to utilize SRVs for reactor pressure control. The crew should perform T- 216 "Control Rod Insertion By Manual Scram or Individual Scram Test Switches" to bypass ARI and RPS, drain the scram discharge volume and initiate another scram.
7                          C    PRO        Group I failure to auto isolate /failure of the D MSL to manually CRS        isolate 8                          C    PRO        Unable to restore drywell nitrogen I only ADS SRVs available for CRS        pressure control I depressurization
C URO Standby liquid control pump trips URO Reduce reactor power 1 CRS 1 7 I PRO Drywell vent valve (AO-2509) fails to isolate CRS I' *I PRO 'A' EHC pump trips / loss of turbine bypass valves 1 CRS 1 (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS) Tech Spec}}
 
Scenario Outline                                        ES-D-1 Simulation Facility Peach Bottom                 Scenario No.           #3            Op Test No. 2007 NRC Examiners                                                         Operators                                 CRS (SRO)
URO (ATC)
PRO (SOP)
Scenario     The scenario begins with the reactor at 100% power. The 25 EHC Pump is blocked out of service for Summary      filter replacement. Following shift turnover, the crew should transfer RPS bus B to the alternate supply to facilitate repairs for a failed trip coil on the B RPS bus feeder breaker. The failed B RPS feeder breaker will already be inoperable when the crew takes the shift.
Following the RPS bus transfer, the RCIC 250 VDC bus will de-energize, rendering RClC inoperable and requiring a Tech Spec entry. Next, the running RBCCW pump will trip and the standby pump will fail to start, resulting in a complete loss of RBCCW. The crew should reduce RBCCW loads (e.9.
RWCU) and reactor power as directed by ON-113Loss of RBCCW.
The crew should perform a GP-4 manual scram due to the inability to restore RBCCW to the recirculation pump motors. An ATWS will occur requiring the crew to execute T-101 RPV Control and T-I 17 LeveVPower Control. Shortly after SLC is initiated the SLC pump will trip, requiring the URO to place the alternate SLC pump in service. A drywell vent valve will fail to isolate on low RPV level and the PRO should manually isolate the valve.
A failure of the only available EHC pump will cause the turbine to trip and the turbine bypass valves to close, requiring the crew to utilize SRVs for reactor pressure control. The crew should perform T-216 Control Rod Insertion By Manual Scram or Individual Scram Test Switches to bypass ARI and RPS,drain the scram discharge volume and initiate another scram.
Event     Malfunction              Event                                          Event No.              No.              Type*                                      Description 1                              N      ALL    Transfer RPS bus to alternate supply (failed trip coil on BRPS feeder TS              breaker) 2                             TS      CRS     RClC 250 VDC bus failure 3                               C     URO     Lossof RBCCW CRS 4
1 I
URO CRS   1 I
Reduce reactor power 5                              M      ALL    ATWS (hydraulic)
I                        C      URO     Standby liquid control pump trips 7                              I      PRO    Drywell vent valve (AO-2509) fails to isolate CRS
  *I                          1          PRO CRS   1 A EHC pump trips / loss of turbine bypass valves (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS) Tech Spec}}

Revision as of 08:57, 23 November 2019

Final Outlines (Folder 3)
ML070610478
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 01/29/2007
From: Vanwyen T
Exelon Generation Co
To: Todd Fish
Operations Branch I
Sykes, Marvin D.
Shared Package
ML060800089 List:
References
ES-401, ES-401-1
Download: ML070610478 (23)
v • d • e


Text

ES-401 BWR Examination Outline Form ES-401-1 Facilitv: Peach Bottom Printed: 01/24/2007 Date Of Exam: 02/05/2007 Note:

1. Ensure that at least iwo 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).
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 +from I 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 ES401, Attachment 2, for guidance regarding the elimination of inappropriate WA 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 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.
6. 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 topics must be relevant to the applicable evolution or system.

8. 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; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note # I does not apply). 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 WA numbers, descriptions, IRs, and point totals (#) on Form ES401-3. Limit SRO selections to WAS that are linked to 10 CFR 55.43.

1

BWR RO Examination Outline Printed: 0 1/24/2007 Facility: Peach Bottom ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 /Group 1 (RO I SRO) Form ES-401-1

' "/APE # / Name / Safety Function

,4500 1 Partial or Complete Loss of Forced K1 K2 K3 Core Flow Circulation I 1 & 4 295003 Partial or Complete Loss of AC Pwr 16

~~ ~

295004 Partial or Complete Loss of DC Pwr I6 295005 Main Turbine Generator Trip / 3 II Il x 1l 295006 SCRAM / 1 I I I x 2950 16 Control Room Abandonment I 7 1 I IX 29501 8 Partial or Total Loss of CCW I 8 2950 18 Partial or Total Loss of CCW / 8 I I Ix 2950 19 Partial or Total Loss of Instrument Air 1 8 I I I 295021 Loss of Shutdown Cooling 1 4 IX I I 5023 Refueling Acc I 8 1 '

295024 High Drywell Pressure I 5 295025 High Reactor Pressure 1 3 1x1 I 295026 Suppression Pool High Water X Temp. 1 5 295028 High Drywell Temperature / 5 X 295030 Low Suppression Pool Wtr Lvl 1 5 X 29503 1 Reactor Low Water Level I 2 295037 SCRAM Condition Present and X Reactor Power Above APRM Downscale or Unknown I 1 295038 High Off-Site Release Rate 1 9 600000 Plant Fire On Site / 8 WA Category Totals: 3 3 4 1

BWR RO Examination Outline Printed: 0 1/24/2007 Facility: Peach Bottom 1

BWR RO Examination Outline Printed: 0 1/24/2007 Facility: Peach Bottom 1

2 BWR RO Examination Outline Printed: 0 1 /24/2007 Facility: Peach Bottom 2.4.3 1 - Knowledge of annunciators alarms and 1

Generic Knowledge and Abilities Outline (Tier 3)

BWR RO Examination Outline Printed: 0 1/24/2007 Facility: Peach Bottom Date of Exam: Form ES-401-3 L-4 CatePory KA# Topic -IR E Conduct of Operations 2.1.1 Knowledge of conduct of operations requirements. 3.7 1 2.1.20 Ability to execute procedure steps. 4.3 1 Subtotal: 2

~ ~ ~ ~~~

Equipment Control 2.2.24 Ability to analyze the affect of maintenance activities on LCO status.

2.2.28 Knowledge of new and spent fuel movement procedures. 1 2.6 1 1 I 2.2.34 Knowledge of the process for determining the internal and 2.8 1 external effects on core reactivity.

Subtotal:

I Radiation Control 2.3.2 2.3.4 2.3.1 1 Knowledge of facility ALARA program.

Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized.

Ability to control radiation releases. I 2.5 2.5 2.7 I 1

1 1

P Emergency Plan 2.4.2 2.4.45 Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.

Ability to prioritize and interpret the significance of each 3.9 3.3 1

1 annunciator or alarm.

Tier 3 Point Total: 10 1

ES-401 BWR Examination Outline Form ES-401-1 Totals 0 0 0 0 0 0 0 7 3 10

volutions 1 0 0 0 0 0 0 0 0 0 0 0 0 3 2 5 2.

2 0 0 0 0 0 0 0 0 0 0 0 0 0 2 1 3 Plant .

Systems Tier 0 0 0 0 0 0 0 0 0 0 0 0 5 3 8 Totals 1 2 3 4 1 2 3 4

3. Generic Knowledge And 0 - 7 Abilities Categories 0 0 0 0 2 2 1 2
1. Ensure that at least Wo 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).
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 _+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.
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 WA 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 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.
6. Select SRO topics for Tiers Iand 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 topics must be relevant to the applicable evolution or system.

8. 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; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note # I does not apply). 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 WA numbers, descriptions, IRs,and point totals (#) on Form ESllOl-3, Limit SRO selections to WAS that are linked to 10 CFR 55.43.

1

BWR SRO Examination Outline Printed: 0 1/24/2007 Facility: Peach Bottom ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 1 (RO I SRO) Form ES-401-1 I SIAPE # I Name I Safety Function

~ 5 0 0 Partial 3 or Complete Loss of AC Pwr

/6 295004 Partial or Complete Loss of DC Pwr

/6 29501 8 Partial or Total Loss of CCW / 8 2950 19 Partial or Total Loss of Instrument Air I 8 295023 Refueling Acc 1 8 1 29503 1 Reactor Low Water Level / 2 600000 Plant Fire On Site 1 8 KIA Category Totals: 7

BWR SRO Examination Outline Printed: 0 112412007 Facility: Peach Bottom ES - 401 Emergency and Abnormal Pian Evolutions - Tier 1 / Group 2 (RO / SRO) Form ES-401-1 295036 Secondary Containment High SumpIArea Water Level 1 5 II II II I WA Category Totals: 0 0 0 1

BWR SRO Examination Outline Printed: 0 1/24/2007 Facility: Peach Bottom 1

BWR SRO Examination Outline Printed: 0 1/24/2007 Facility: Peach Bottom ES - 401 Plant Systems - Tier 2 / Croup 2 (RO / SRO) Form ES-401-1

.

stem limits and c-'

I

Generic Knowledge and Abilities Outline (Tier 3)

BWR SRO Examination Outline Printed: 0 1 I2412007 Facilitv: Peach Bottom Date of Exam: Form ES-401-3

' i i '

CatePory -

KA # Took -IR  ?!

Conduct of Operations 2.1.4 Knowledge of shift staffing requirements. 3.4 1 2.1.6 Ability to supervise and assume a management role 4.3 1 during plant transients and upset conditions.

Equipment Control 2.2.18 Knowledge of the process for managing maintenance 3.6 1 activities during shutdown operations.

2.2.29 Knowledge of SRO fuel handling responsibilities. 3.8 1 Subtotal: 2 Radiation Control 2.3.1 Knowledge of 10 CFR 20 and related facility radiation 3.O 1 control requirements.

Emergency Plan 2.4.22 Knowledge of the bases for prioritizing safety functions 4.0 1 during abnormallemergency operations.

.~ 2.4.33 Knowledge ofthe process used track inoperable alarms. 2.8 1

-- I ~ ~

Tier 3 Point Total: 7 I

ES-401 Record of Rejected WAS Form ES-401-4 Tier I Randomly Reason for Rejection

~

Group Selected KIA RO 262002 A I .02 Peach Bottom uses static inverters for uninterruptable power supplies, not 211 motor-generators.

RO 290003 A3.02 At Peach Bottom, there is no direct association between the Control Room 212 HVAC System and the Fire Protection System.

SRO 295024 A 2 0 5 Peach Bottom has no direct indication or procedural guidance for 111 determining suppression chamber air space temperature.

SRO 295008 G2.4.49 Unable to construct an SRO question for this KA that meets the 1 12 requirements of NUREG-1023.

SRO 259002 G2.1 . I 4 Unable to construct an SRO question for this KA that meets the 211 requirements of NUREG-1023.

SRO G2.3.2 This KA was already sampled on the RO portion of the exam. Unable to 111 construct an additional question at the SRO level.

RO 295026 EK2.06 Unable to construct an RO question for this KA that meets the 1I 1 requirements of NUREG-1023.

RO 21 1000 K5.05 Unable to construct an RO question for this KA that meets the 211 requirements of NUREG-1023.

SRO 295026 G2.4.30 Unable to construct an SRO level quesiton for this KA that also meets the 1I 1 criteria of 10CFR55.43(b).

ES-401, Page 27 of 33

r - ES-301 Administrative Topics Outline Form ES-301-1 acility: Peach Bottom Date of Examination: 2/5/2007 tamination Level: RO [7 SRO Operating Test Number: 2007 NRC AdministrativeTopic TYPe Describe activity to be performed (See Note) Code*

Conduct of Operations G2.1.4 - Evaluate Shift Staffing H

G2.1.7 - EvaluateA PI Edit And Take Corrective Action Conduct of Operations For A Thermal Limit Violation [PLOR-218C]

G2.2.21 - Determine Post MaintenanceTest Equipment Control N, R Requirements For Valve Operability [NEW]

G2.3.9 - Review And Approve Primary Containment Radiation Control PurgeNent Isolation Valve Cumulative Hour Log [NEW]

G2.4.38 - Review And Authorize Issuance Of Thyroid Emergency Plan M. R Blocking Agent (KI)[PLOR-215C]

OTE: 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 (53 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 Administrative Topics Outline Form ES-301-1 3cility: Peach Bottom Date of Examination: 2/5/2007 xamination Level: RO [XI SRO 0 Operating Test Number: 2007 NRC Administrative Topic TYPe Describe activity to be performed (See Note) Code*

G2.1.7 - Calculate Drywell Bulk Average Temperature Conduct of Operations

[2005 NRC]

G2.1.25 - Perform Reactor Coolant Leakage Surveillance Conduct of Operations

[NEW Equipment Control G2.2.11 - Prepare A Partial Procedure [PLOR-205C]

Radiation Control G2.4.43 - Perform Personnel Notifications During A Emergency Plan Security Threat [PLOR-217C]

OTE: 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 (53 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 Roomlln-Plant Systems Outline Form ES-301-2 Facility: Peach Bottom Date of Examination: 2/5/2007 Exam Level: RO SRO-I 0 SRO-U 0 Operating Test Number: 2007 NRC Control Room Systems@(8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Safety System / JPM Title Type Code*

Function

a. 295037 EA1.04 - Inject Boron Into RPV (Alternate Path - RWCU Fails To A, D, S 1 Isolate) [PLOR-301CAI - SET 1
b. 295031 EA1.02 - Manually Initiate HPCl (Alternate Path - Manual 2 Initiation Pushbutton Fails To Operate) [PLOR300CA] - SET 2
c. 218000 A4.03 - ADS Reset Following Blowdown [PLOR-O23C / 2005 3 NRC] - SET 3
d. 209001 A4.04 - Perform Core Spray B Pump Capacity Test For IST N, s 4

[NEW] - SET 4

e. 219000 A4.13 - HPSW Injection Into The Torus [PLOR-O81C] - SET 1 D, s 5
f. 262001 A4.04 - Synchronize Turbine Generator Output With Grid At D, s 6 Minimum Load [PLOR-O17C] - SET 4
g. 295018 AA1.01 - Emergency Cooling Water System Startup [PLOR- M, s 8 028Cl- SET 3
h. 261000 A2.10 - PRO Scram Actions (Alternate Path - SBGT Fails To A, L, N, s 9 4,'

Automatically Initiate) [NEW]- SET 2

i. 201001 A2.09 - Low CRD Scram Air Header Pressure - Unit 3 (Alternate A, D, E, 1 Path - Place Standby Regulator In Service) [PLOR-316PA / 2002 NRC] p, R
i. 295031 EA1.05 - Defeat RClC Low Pressure Isolation - Unit 2 D, E, R 2

[PLOR-O86P]

k. 264000 A2.10 - Diesel Generator Air Start Solenoid Override D, E 6

[PLOR-O49P]

@ 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.

I

  • Type Codes Criteria for RO / SRO-I / SRO-U I

(A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room 4 (D)irect from bank (E)mergency or abnormal in-plant (L)ow-Power I Shutdown (N)ew or (M)odified from bank including 1(A)

(P)revious 2 exams (WA (S)imulator ES-301, Page 23 of 27

ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: Peach Bottom Date of Examination: 21512007 Exam Level: RO 0 SRO-I SRO-U [7 Operating Test Number: 2007 NRC Control Room Systems* (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System I JPM Title I 1 Safety Function

a. 295037 EA1.04 - Inject Boron Into RPV (Alternate Path - RWCU Fails To A, D, S 1 Isolate) [PLORdOl CAI - SET I
b. 295031 EA1.02 - Manually Initiate HPCl (Alternate Path - Manual A, D, L, s 2 Initiation Pushbutton Fails To Operate) [PLOR300CA] - SET 2
c. 218000 A4.03 -ADS Reset Following Blowdown [PLOR-O23C I2005 D, L, P, s 3 NRCl - SET 3
d. 209001 A4.04 - Perform Core Spray 6 Pump Capacity Test For IST N,s 4

[NEW] - SET 4

e. 219000 A4.13 - HPSW Injection Into The Torus [PLOR-O81C] - SET 1 D, s 5
g. 295018 AA1.01 - Emergency Cooling Water System Startup [PLOR- M, s 8 028Cl- SET 3
h. 261000 A2.10 - PRO Scram Actions (Alternate Path - SBGT Fails To A, L, N, s 9 Automatically Initiate) [NEW] - SET 2
i. 201001 A2.09 - Low CRD Scram Air Header Pressure - Unit 3 (Alternate A, D, E, 1 Path - Place Standby Regulator In Service) [PLOR-316PA 12002 NRC] p, R
j. 295031 EA1.05 - Defeat RClC Low Pressure Isolation - Unit 2 D, E, R 2

[PLOR-086Pl

k. 264000 A2.10- Diesel Generator Air Start Solenoid Override D,E 6
  • Type Codes Criteria for RO I SRO-I I SRO-U (A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank -

< 9 / (8 1 5 4 (Epergency or abnormal in-plant -

> I / 21 1 2 1 (L)ow-Power / Shutdown (N)ew or (M)odified from bank including I(A)

(P)revious 2 exams -

< 3 11 3 I (2 (randomly selected)

(R)CA -

> I 1 >I/ > I (S)imulator

ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: Peach Bottom Date of Examination: 2/5/2007 Exam Level: RO 0 SRO-I 0 SRO-U [XI Operating Test Number: 2007 NRC Control Room Systems@(8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System I JPM Title I Type Code* Safety Function a.

b. 295031 EA1.02 - Manually Initiate HPCl (Alternate Path - Manual A, D, L, S 2 Initiation Pushbutton Fails To Operate) [PLOR-300CA] - SET 2 ESF
c. 218000 A4.03 - ADS Reset Following Blowdown [PLOR-O23C / 2005 D, L, p, s 3 NRC] - SET 3 ESF
d. 209001 A4.04 - Perform Core Spray B Pump Capacity Test For IST N, s 4

[NEW] - SET 4 ESF e.

f.

h.

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

i. 201001 A2.09 - Low CRD Scram Air Header Pressure - Unit 3 (Alternate A, D, E, Path - Place Standby Regulator In Service) [PLOR316PA 12002 NRC]

i.

k. 264000 A2.10 - Diesel Generator Air Start Solenoid Override

[PLOR-O49P]

@ 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 / SRO-U (A)lternate path 4-6 I 4-6 I 2-3 (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 I(A)

(P)revious 2 exams (WA (S)imulator ES-301, Page 23 of 27

Scenario Outline ES-D-1 1

Simulation Facility Peach Bottom Scenario No. -

  1. 1 Op Test No. 2007 NRC Examiners Operators CRS (SRO)

URO (ATC)

PRO (BOP)

Scenario The scenario begins with the reactor at approximately 5% power during a reactor startup. Following Summary shift turnover, the crew should continue with the reactor startup, pulling control rods in accordance with the approved startup sequence. A control rod will drift out, requiring the crew to execute ON-I21 Drifting Control Rod and declare the affected control rod inoperable.

Following the control rod drift, the crew should secure drywell purge in preparation for inerting the drywell. Once drywell purge is secured, an inadvertent RClC initiation will occur, requiring the crew to perform a RClC shutdown and declare it inoperable. This event will be followed by a failure of the in-service CRD flow control valve, which will require the crew to enter ON-1 07 Loss of CRD Regulating Function and shift to the alternate flow control valve.

Next, a Recirc system leak will develop in the drywell requiring entry into OT-101 High Drywell Pressure. The crew should take actions for the rising drywell pressure and should manually scram the reactor and enter T-100 Scram. During the scram, seven rods will fail to insert resulting in an ATWS. When drywell pressure reaches 2 psig, the crew should enter T-101 RPV Control and T-102 Primary Containment Control. Multiple failures of drywell spray valves will prevent spraying the drywell, requiring the crew to perform T-I12 Emergency Blowdown when drywell temperature cannot be restored and maintained below 281 degrees F. With several rods stuck out, the crew should terminate and prevent injection in accordance with T-240 prior to the emergency depressurization.

Initial IC-70, 5% power Conditions Turnover See Attached Shift Turnover Sheet Event Malfunction Event Event No. No. Type* Description I R URO Power ascension with control rods CRS

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2 C ALL Control rod drifts out TS .

Secure drywell purge

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Inadvertent RClC initiation 5 C URO CRD flow control valve failure CRS 1 6 M ALL Recirculation system leak in the drywell C URO Seven rods stick full out during the scram l 7 CRS 8 C PRO Drywell spray valve failures - prevents drywell spray CRS

Scenario Outline ES-D-1.

Simulation Facility Peach Bottom Scenario No. #2 Op Test No. 2007 NRC 1 Examiners Operators CRS (SRO)

URO (ATC)

PRO (BOP)

Scenario The scenario begins with the plant at 76% power and the BRHR pump blocked for motor Summary replacement. Following turnover the crew will perform a main turbine master trip solenoid valves

_. routine test. Following this test, the SBO line will fail, requiring a Tech Spec (TRM) entry. A loss of feedwater heaters will require the crew to respond to a positive reactivity addition and reduce reactor power to ensure thermal limits are not exceeded. The crew will then receive an RPS half scram due to a failed low vacuum pressure transmitter (blown fuse). This will require a Tech Spec entry.

Troubleshooting and repairs will be time-compressed, allowing the crew to reset the half scram.

After RPS is reset, a steam leak will develop in the Turbine Building. As the steam leak grows in magnitude, the crew should recognize the need to shutdown the plant. During the manual scram, a reactor mode switch failure will require the crew to use the manual pushbuttons or Alternate Rod Insertion (ARI) to terminate the ATWS.

A failure of the Group I isolation will require a manual isolation but the D MSL will fail to isolate. The crew should enter T-104 Radioactive Release to evaluate and control the release. The inability to restore instrument nitrogen to the SRVs wi!l result in a loss of all non-ADS SRVs.

When the release exceeds the General Emergency level, the crew should perform an Emergency Blowdown in accordance with T-112 Emergency Blowdown.

Event Malfunction Event Event No. No. Type* Descrintion I I I I N PRO Perform the main turbine master trip solenoid valves routine test 1 2 TS CRS CRS SI30 line failure (TRM) 3 C URO Loss of extraction steam to feedwater heaters I power reduction CRS

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4 I URO Failure of a vacuum transmitter I RPS half scram & reset TS CRS 5 M ALL Steam leak in the turbine building

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6 I URO Reactor mode switch failure (manual scram I ARI work)

CRS 8

7 C PRO Group I failure to auto isolate /failure of the D MSL to manually CRS isolate 8 C PRO Unable to restore drywell nitrogen I only ADS SRVs available for CRS pressure control I depressurization

Scenario Outline ES-D-1 Simulation Facility Peach Bottom Scenario No. #3 Op Test No. 2007 NRC Examiners Operators CRS (SRO)

URO (ATC)

PRO (SOP)

Scenario The scenario begins with the reactor at 100% power. The 25 EHC Pump is blocked out of service for Summary filter replacement. Following shift turnover, the crew should transfer RPS bus B to the alternate supply to facilitate repairs for a failed trip coil on the B RPS bus feeder breaker. The failed B RPS feeder breaker will already be inoperable when the crew takes the shift.

Following the RPS bus transfer, the RCIC 250 VDC bus will de-energize, rendering RClC inoperable and requiring a Tech Spec entry. Next, the running RBCCW pump will trip and the standby pump will fail to start, resulting in a complete loss of RBCCW. The crew should reduce RBCCW loads (e.9.

RWCU) and reactor power as directed by ON-113Loss of RBCCW.

The crew should perform a GP-4 manual scram due to the inability to restore RBCCW to the recirculation pump motors. An ATWS will occur requiring the crew to execute T-101 RPV Control and T-I 17 LeveVPower Control. Shortly after SLC is initiated the SLC pump will trip, requiring the URO to place the alternate SLC pump in service. A drywell vent valve will fail to isolate on low RPV level and the PRO should manually isolate the valve.

A failure of the only available EHC pump will cause the turbine to trip and the turbine bypass valves to close, requiring the crew to utilize SRVs for reactor pressure control. The crew should perform T-216 Control Rod Insertion By Manual Scram or Individual Scram Test Switches to bypass ARI and RPS,drain the scram discharge volume and initiate another scram.

Event Malfunction Event Event No. No. Type* Description 1 N ALL Transfer RPS bus to alternate supply (failed trip coil on BRPS feeder TS breaker) 2 TS CRS RClC 250 VDC bus failure 3 C URO Lossof RBCCW CRS 4

1 I

URO CRS 1 I

Reduce reactor power 5 M ALL ATWS (hydraulic)

I C URO Standby liquid control pump trips 7 I PRO Drywell vent valve (AO-2509) fails to isolate CRS

  • I 1 PRO CRS 1 A EHC pump trips / loss of turbine bypass valves (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS) Tech Spec
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