ML21237A518
ML21237A518 | |
Person / Time | |
---|---|
Site: | Peach Bottom |
Issue date: | 06/01/2021 |
From: | Todd Fish Operations Branch I |
To: | Exelon Generation Co |
Shared Package | |
ML20259A377 | List: |
References | |
EPID L-2021-OLL-0002 | |
Download: ML21237A518 (23) | |
Text
ES-301 Administrative Topics Outline.Form ES-301-1
Facility: Peach Bottom Atomic Power I Station Date of Exami~ation: 06/01/21 Examination Level: RO IXJ SRO D Operating Tesi i Number: 1
I Administrative Topic (see Note) Type Describe acti~ity to be performed Code*
.I I i I G2.1.32 (3.8), Evaluation of High CRD Conduct of Operations RID Temperatures on Control Rod Scram Time I.
- I (PLIOR-348C) I
RIM G2.1.5 (2.9), Appli6ation of Work Hour Rules
Conduct of Operations (PJOR-391C)
I G2.2.6 (3.0), lnitiati~g a Temporary Procedure Equipment Control RID Change (PLOR-245C) I
I I
Not Required I
Radiation Control
G2.4.39 (3.9), Perfo~m State/Local Notifications Emergency Plan S/N for a Declared Emergency (PLOR-41 BC) I I
I NOTE: All items (five total) are required for SROs. RO applicants require bnly four items unless they are retaking only the administrative topics (which would require all !five items).
- Type Codes and Criteria: (C)ontrol room, (S)imulator, or Class(R)o~m (D)irect from bank (s 3 for ROs; s 4 for SROs and RO retakes) 2 (N)ew or (M)odified from bank (;:;: 1) 2 I (P)revious 2 exams (S 1, randomly selected) 0 I
I I
I ES-301 Administrative Topics Outline Form ES-301-1
Facility: Peach Bottom Atomic Power Station Date of Examination: 06/01/21 Examination Level: RO D SRO !ZI Operating Tes!t Number: 1
Administrative Topic (see Note) Type Describe activity I to be performed
Code*,I
G2.1.25 (4.2), jerform SRO Review of I
Conduct of Operations R/D Completed Surveillance (PLOR-393C)
'I G2.1. 7 (4. 7), ReJolution of Thermal Limit
Conduct of Operations R/M Violatiol (PLOR-218C)
G2.2.6 (3.6), Applrove a Partial Procedure
Equipment Control R/N (P OR-416C)
G2.3.14 (3.8), Revi~w and Authorize Issuance
Radiation Control R/N of Thyroid BlockinJ Agent (Kl) (PLOR-41 ?C)
G2.4.41 (4.6), EAL Classification I and
Emergency Plan S/M State/Local Notifilations for SAE - Control
Room EvacJation (PLOR-180C)
I NOTE: All items (five total) are required for SROs. RO applicants require ~nly four items unless they are retaking only the administrative topics (which would require all five items).
I
- Type Codes and Criteria: (C)ontrol room, (S)imulator, or Class(R)oo~
(D)irect from bank (:,; 3 for ROs; :,; 4 for SROs and RO retakes) 1 (N)ew or (M)odified from bank (~ 1) 4 [
(P)revious 2 exams (:,; 1, randomly selecteld) 0 ES-301 Control Room/In-Plant Systems Outline. Form ES-301-2
Facility: PBAPS Date of Examination: 06/01/21 Exam Level: RO ~ SRO-I SRO-U Operating Test Number: 1
Control Room Systems:* 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U
System/JPM Title Type Code* Safety Function
- a. 295037 EA1.01 4.6/4.6, Insert Control Rods using Individual A,N, S 1 Scram Test Switches (PLOR-412CA)
- b. 295001 A4.02 3.9/3.7, Start the "C" Reactor Feedwater I Pump with Vessel Level Control Through AO-8091 (PLOR-M, L, S 2 012C)
- c. 239001 A4.01 4.2/4.0, Perform a Slow Closure and N,S 3 Restoration of a Main Steam Isolation Valve (PLOR-413C)
- d. 202001 A4.04 3.8/3.8, Raise Reactor Power with A, D,S, P 4 Recirculation Flow (Alternate Path) (PLOR-396CA)
- f. 262001 A4.04 3.6, Transfer House Loads to the Unit D,S 6 Auxiliary Transformer (PLOR-039C)
- g. 201005 A2.02 2.8/3.2, Withdraw Control Rod (Alternate Path A, N, S 7
- Loss of Control Rod Position Indication) (PLOR-415CA)
- h. 261000 A2.05 3.0/3.1, Manually Place SBGT on the Equipment Cell Exhaust (Alternate Path - 1 sr Fan Fails to A, EN,D,S 9 Align) (PLOR-265CA)
In-Plant Systems:* 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U
- i. 295029 EA2.01 3.9/3.9, Lowering Torus Level using the ~.E, R 5 Torus Water Filter Pump (PLOR-409P) I
- j. 239002 A2.03 4.1/4.2, Remove Fuses per OT-114 for Stuck M, E, R 3 Open SRV (PLOR-191 P)
- k. 201001 A2.06 2.9/2.9, Loss of CRD Regulating Function ~.E,R 1 (Outside Control Room Actions) (PLOR-073P)
- All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions, all five SRO-U systems must serve different safety functions, and in-plant systems and functions may overlap those tested in the control room. *
- Type Codes I Criteria for R /SRO-1/SRO-U ES-301 Control Room/In-Plant Systems Outline i Form ES-301-2
I (A)lternate path 4-6/4-6 /2-~ 4 (C)ontrol room I (D)irect from bank ::;; 9/:5 8/:5 4 l 4 (E)mergency or abnormal in-plant.: 11.: 11.: 1 I 3 (EN)gineered safety feature.: 1/.: 1/.: 1 (control room system) 2 (L)ow-Power/Shutdown.: 1/.: 1/.: 1 I 1 (N)ew or (M)odified from bank including 1 (A).: 2/.: 2/.: 1 i 7(3)
(P)revious 2 exams :5 3/:5 3/:5 2 (randomly selected) 1 1 3 (R)CA.: 1/.: 1/.: 1 (S)imulator
. I
ES-301 Control Room/In-Plant Systems Outline I Form ES-301-2
Facility: PBAPS Date of Examitation: 06/01/21 Exam Level: RO SRO-I [Zl SRO-U Operating Test Number: 1 r
Control Room Systems:. 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U _,I I
System/ J PM-Title Ty~e Code* Safety
-- I Function
- 1
- a. 295037 EA 1.01 4.6/4.6, Insert Control Rods using Individual Scram Test Switches (PLOR-412CA) t,N, S 1
- b. 295001 A4.02 3.9/3.7, Start the "C" Reactor Feedwater I Pump with Vessel Level Control Through AO-8091 (PLOR-M, L, S 2 012C) 'I *-
C. 239001 A4.01 4.2/4.0, Perform a Slow Closure and.,IN, s 3 Restoration of a Main Steam Isolation Valve (PLOR-413C)
- d. 202001 A4.04 3.8/3.8, Raise Reactor Power with A, D,S, P 4 Recirculation Flow (Alternate Path) (PLOR-396CA)
- f. Not Required I
I
- g. 201005 A2.02 2.8/3.2, Withdraw Control Rod (Alternate Path 7 'I
- Loss of Control Rod Position Indication) (PLOR-41 SCA) j,N,S
- h. 261000 A2.05 3.0/3.1, Manually Place SBGT on the I
- Equipment Cell Exhaust (Alternate Path - 1 ST Fan Fails to A,i::N,D,S 9 Align) (PLOR-265CA) I
.J n-Plant Systems:. 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U I
- i. 295029 EA2.01 3.9/3.9, Lowering Torus Level using the I N,E,R 5 Torus Water Filter Pump (PLOR-409P) I
I '
- j. 239002 A2. 03 4.1 /4.2, Remove Fuses per OT-114 for Stuck I Open SRV (PLOR-191P) 1,E,R 3
- k. 201001 A2.06 2.9/2.9, Loss of CRD Regulating Function I I (Outside Control Room Actions) (PLOR-073P) ~,E,R 1
- All RO and SRO-I control room (and,in-plant) systems must be different a~d serve different safety functions, all five SRO-U systems must serve different safety functions, at in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for R /SR0-1/SRO-U I I I i
I I
I I
ES-301 Control Room/In-Plant Systems Outline I Form ES-301-2
(A)lternate path 4-6/4-6 /2-3 I 4
(C)ontrol room (D)irect from bank S 9/S 8/S 4 3 (E)mergency or abnormal in-plant ~1,~1,~1 3 (EN)gineered safety feature ~ 1/~ 1/~ 1 tcontrol room system) 2 (L)ow-Power/Shutdown ~ 1/~ 1/~ 1 j 1 (N)ew or (M)odified from bank including 1 (A) ~ 2/~ 2/~ 1 7(3)
(P)revious 2 exams s 3/S 3/S 2 irandomly selected) 1 (R)CA ~ 1,~ 1,~ 1 I 3 (S)imulator Appendix D Scenario Outline ES-D-1 :
Simulation Facility Peach Bottom. Scenario No. #1 Op Test I No. 2021 NRC
Examiners Operators CRS (SRO) ' I URO (ATC)
I PRO (BOP)
Initial IC-71 Approximately 3-4% power Conditions
Turnover
- Unit 2 startup is in progress.
- Reactor Power is approximately 3-4% with direction to continue to raise Reactor power with control rod withdrawal usihg GP-2-2.
- Nitrogen inerting of the Primary Containment i's to be commenced. The, :
PRO will begin inerting the Primary Containm~nt following shift turnover.
I. !
I Critical Critical Task 1: Prior to reaching 450 psig, close t~e Inboard and/or Tasks Outboard MSIVs to stop Reactor Depr~ssurization.
Critical Task 2: Inhibit ADS before an automatic dlpressurization occurs.
Critical Task 3: Perform an Emergency Slowdown Lhen RPV water level.
cannot be restored and maintained: above -172", or within 10 minutes of dropping below -17l _
Event Malfunction Event [ Event
No. No. Type* 0escription I., I I
1 See Scenario N I. PRO Secure the Mechanical Vacuum Pump Guide CRS I I
2 See' Scenario R I URO Raise reactor power by withdrawing control rods.*
Guide CRS I
3 See Scenario T;C ~:~ Control Rod Drtft/URO insrrts rod Guide
I 4 See Scenario TS CRS OW Pressure Instrument I I ailure Guide
. ! I 5 See Scenario PRO "A" Core Spray loop spuriously starts/ PRO secures PU!'TlPS Guide C CITS CRS and CRS enters Tech Specs. 1
1:
I I
2021 NRC Scenario #1 D-1 Rev 0. I I
- I
I I
Appendix D Scenario Outline ES-D-1 I
I 6 See Scenario C ALL Pressure Regulator Failuro/Scram/T-101 Entry Guide I
7 See Scenario M ALL Recirc Water Leak in PC I Guide
8 See Scenario C URO HPCI Fails to Start Guide CRS
9 See Scenario C URO HPCI/RCIC Trip Guide CRS
10 See Scenario C URO CRD Pump Trip Guide CRS
- (N)ormal, (R)eactivity, {l)nstrument, (C)omponent, (M)ajor, (TS) TeL Spec
2021 NRC Scenario #1 D-1 Rev 0
I Appendix D Scenario Outline ES-D-1
Simulation Facility Peach Bottom Scenario No. #2 Op Test No. 2021 NRC
URO (ATC)
PRO (BOP)
Initial IC-14, 100% power Conditions.
Turnover
- Reactor power is 100% power.
Critical Critical Task #1: Scram the reactor or restore char1~ing header pressure Tasks above 940 psig within 20 minutesf of charging header pressure lowering below 940 psig and 2 or more accumulator alarms in.
Critical Task #2: Perform an RPV Slowdown within 10 minutes of the second '
Reactor Building area temperature exceeding an Action Level.
- I.
Event Malfunction Event *1 Event
No. No. Type* Description I.
1 See Scenario Guide N PRO Perform SO 28B.1.A to staA a cooling tower CRS
2 See Scenario Guide C URO CRD Pump Trip CRS 3 See Scenario Guide R URO Main turbine high vibrations! require lowering power to address I
C CRS the vibr~tions * ; I
I 4 See Scenario Guide C ALL ADS Valve Fails Open. CRS enters Tech Specs.
TS CRS. I -
5 See Scenario Guide C PRO Shutdown E-4 diesel gener~tor following inadvertent start. CRS TS/C CRS enters Tech Specs.. I :
6 See Scenario Guide C ALL Loss of TBCCW I ',., : I
7 See Scenario Guide C ALL
- Loss of #2 Bus/T-1 O 1 Entry[ I
. I 8 See Scenario Guide M ALL RWCU Steam Leak/T-103 fntry
- (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor, (TS) Tebh Spec
2021 NRC Scenario #2 D-1 Rev 0
I Appendix D Scenario Outline ES-D-1 1
Simulation Facility Peach Bottom Scenario No. #4 Op Test No. 2021 NRC
URO (ATC)
PRO (BOP)
Initial IC-14, 100% power (Reactor power is lowered to 97%,Power)
Conditions
Turnover
- Reactor power is approximately 97% for rod coupling checks.
Critical Critical Task #1: Attempt to shutdown the reactor by performing one or Tasks more of the following: I
- a. T-2113, Scram Solenoid Deenergization
- c. T-220, Driving Control Rods during a Failure to Scram
- d. Injecting Standby Liquid befofe Torus Temperature exceeds 110°F
Critical Task #2: Perform T-240, Termination and P'revention of Injection into 1 the RPV to minimize thermal-hyd~aulic instabilities (THI) until RPV water level is below -60r.
Event Malfunction Event [Event
No. No. Type* Description I
1 See Scenario Guide N PRO Swap RBCCW Pumpsl I CRS 2 See Scenario Guide C URO Control rod becomes uncoupled / attempt to recouple I
TS/C CRS using ON-105 I
3 See Scenario Guide R URO Raise reactor power with ecirculation flow.
I 4 C PRO Loss of power to RPS bre i 1aker and transfer of RPS to.
See Scenario Guide TS/C CRS alternate power supply. CRS enter/apply Technical ' '
Specifications. I I 5 C ALL Loss of RBCCW See Scenario Guide
2021 NRC Scenario #4 (Spare) D-1 Rev 1 I
Appendix D Scenario Outline ES-f>-1 I I I
I I
I 6 C URO Both Recirc Pumps Trip I See Scenario Guide I CRS I I 7 See Scenario Guide M ALL ATWS I I I I I I
I I 8 See Scenario Guide C URO SBLC Pump Trip CRS
- (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor, (TS) Te~h Spec
I 2021 NRC Scenario #4 (Spare) D-1 Rev 1 I I
I I
i
~-------------ES-401 BWR Examination Outline FORM ES.-401-1 Facility Name: Date of Exam: :
RO KIA Category Points i SRO-Only Points I Tier Group K K K K K K A A A A G I 1 2 3 4 5 6 1 2 3 4
- I Total A2 G* Tc)tal
I '
- 1. 1 4 3 4 3 3 3 20 4 3 17 Emergency & I Abnormal 2 1 2 0 N/A 2 1 N/A 1 7, 2 1 '3 I
Plant Evolutions Tier Totals 5 5 4 5 4 4 27; 6 4 '10
I
- 2. 1 3 2 3 2 2 2 3 3 3 1 2 26' 3 2 15
Plant 2 1 1 1 1 2 1 2 1 0 1 1 12* 0 2 1 !3 I I Systems 3 's Tier Totals 4 3 4 3 4 3 5 4 3 2 3 38, 5
- 3. Generic Knowledge and Abilities I 1 2 3 4 1 2 3 4 :
Categories 10: :7 3 3 2 2 ' 2 2 1 2 :
Note: 1. Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO only outlines (i.e., except for one category in Tier 3 of the SRO-only ou~line, the "Tier Totals" in each KIA ca*gory shall not be less than two). (One Tier 3 Radiation Control KIA is allowed if the KIA is replaced by a KIA from I
another Tier 3 Category). I
- 2. The point total for each group and tier in the proposed outline must match that I specified in the table. The final point total for each group and tier may deviate by +/-1 from that specifieq in the table based on NRC revision~. The final RO exam must total 75 points and the SRO-only exam must total 25 points. I
- 3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do' not
' I apply at the facility should be deleted and justified; operationally imporfant, site-specific systems that are not included on the outline should be added. Refer to Section D.1.b of ES"401 for guidance regarding the elimir of inappropriate KIA statements., 1iation
- 4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the grqup before selecting a second topic for any system or evolution. ' I
- 5. Absent a plant-specific priority, only those KIAs having an importance r,ating (IR) of 2.5 or higher shall be selected.
Use the RO and SRO ratings for the RO and SRO-only portions, respectively. !
I
- 6. Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA pategories. I 7.* The generic (G) Kl As in Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics mu:st be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable KIAs. I I
- 8. On the following pages, enter the KIA numbers, a brief description of e~ch topic, the topics' importance ratings
- I (I Rs) for the applicable license level, and the point totals(#) for each system and category. Enter the groupIand tier totals for each category in the table above; if fuel handling equipm~nt is sampled in other than CategoryiA2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply~. Use duplicate pages for RO and SRO-only exams.
- 9. For Tier 3, select topics from Section 2 of the KIA catalog, and enter the KIA numbers, descriptions, !Rs, and point totals(#) on Form ES-401-3. Limit SRO selections to KIAs that are linked to 10 CFR 55.43.
G* Generic KIAs I
- 1
ES-401 2 Form ES-~01-1 I I 'I ES-401 BWR Examination Outline I Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (Ren E/APE # / Name I Safety Function 1 2 3 1 K/,f-. K K K A I Topic(s) IR #
I 295001 Partial or Complete Loss of Forced 0 I Ability to operate and/or monitor the following as they apply to Partial or Complete 3.3 Core Flow Circulation / 1 & 4 2 Loss of Forced Core Flow Circulation: RPS I I 0 Knowledge of the operational implicatibns of the following concepts as they apply to I 295003 Partial or Complete Loss of AC / 6 3 Partial or Complete Loss of AC: Unde1 voltage/degraded voltage effects on electrical 2.9 loads I
295004 Partial or Total Loss of DC Pwr / 6 0 Knowledge of the interrelations betweJn Partial or Total Loss of DC Pwr and the 3.1 I 1 following: Battery charger I
295005 Main Turbine Generator Trip/ 3 0 Knowledge of the reasons for the follo}ing responses as they apply to Main Turbine 2.8: I 3 Generator Trip: Feedwater temperaturr decrease
295006 SCRAM / 1 Ability to use plant computers to evalulie system or component status. 3.91 I
295016 Control Room Abandonment/ 7 Ability 0 I to operate and/or monitor the lo/lowing as they apply to Control Room 4 *z: I 7 Abandonment: Control roomnocal control transfer I mechanisms
295018 Partial or Total Loss of CCW / 8 0 Knowledge of the interrelations betweJn Partial or Total Loss of CCW and the 3.3 I 1 following: System loads I
295019 Partial or Total Loss of Inst. Air/ 8 3 Loss of Inst. Air: 0 Knowledge of the reasons for the folloking responses as they apply to Partial or Total I Service air isolations{Ptant-Specific 3.2 I
295021 Loss of Shutdown Cooling/ 4 0 Knowledge of the reasons for the follo~ing responses as they apply to Loss of 3.3 1 Shutdown Cooling: Raising reactor wa ter level
1 295023 Refueling Ace / 8 0 Knowledge of the interrelations betwe~n Refueling Accidents and the following: 3.4 6 Containment ventilation: Mark-Ill 1*
295024 High Drywell Pressure / 5 Ability to operate and/or monitor the 1J11owing as they apply to High Drywell Pressure: 3.4 4 Drywell ventilation system I
295025 High Reactor Pressure/ 3 Ability to determine and/or interpret thi following as they apply to High Reactor Pressure: Reactor pressure r 4.3
295026 Suppression Pool High Water 0 Knowledge of the operational implicati~ns of the following concepts as they apply to 3.5 Temp./ 5 2 Suppression Pool High Water Temp.: fteam condensation
295027 High Containment Temperature I 5 I 0
295028 High Drywell Temperature I 5 Ability to determine and/or interpret th~ following as they apply to High Drywell Temperature: Reactor water level I 3.7
295030 Low Suppression Pool Wtr Lvl / 5 I 3.8 Knowledge of the operational implications of EOP warnings, cautions, and notes.
I 295031 Reactor Low Water Level/ 2 Knowledge of the 0 I reasons for the following responses as they apply to Reactor Low 4.4 2 Water Level: Core coverage I,
295037 SCRAM Condition Present and I operational implications of the following concepts as they apply to Reactor Power Above APRM Downscale or 0 Knowledge of the 5 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown: 3.4 Unknown/ 1 Cold shutdown boron weight: Plant-Sp'ecific I
295038 High Off-site Release Rate I 9 0 Knowledge of the operational implicaJons of the following concepts as they apply to 4.2 2 High Off-site Release Rate: Protectior\\ I of the general public
600000 Plant Fire On Site / 8 Ability to determine and/or interpret the following as they apply to Plant Fire On Site:
Damper position I 2.8
700000 Generator Voltage and Electric Grid Ability to analyze the effect of mainte~,ance activities, such as degraded power 3.1 Disturbances / 6 sources, on the status of limiting conditions for operations.
KIA Category Totals: 4 3 4 3 Group Point Total: 20
ES-401, Page 34 of 50
.-ES-401 3 Form ES-401-1
ES-401 BWR Examination Outline Form ES-401-1
11------------------r--.--,----,,--- ------------,--------------.---,"""T---t Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (Rq>)
E/APE # / Name / Safety Function K K K A 2 3 1 KIA Topic(s) IR #
295002 Loss of Main Condenser Vac / 3 0
295007 High Reactor Pressure / 3 0
I 295008 High Reactor Water Level / 2 0 Ability to operate and/or monitor the following as they apply to High Reactor Water 3.5 8 Level: Feedwater system '
295009 Low Reactor Water Level / 2 0
29501 O High Drywell Pressure / 5 0
295011 High Containment Temp I 5 0
295012 High Drywell Temperature/ 5 0
0 Ability to operate and/or monitor the following as they apply to High Suppression Pool I 295013 High Suppression Pool Temp./ 5 Temp.: Suppression pool cooling I 3.9 I
295014 Inadvertent Reactivity Addition/ 1 0
295015 Incomplete SCRAM/ 1 0 Knowledge of the interrelations betwe~n Incomplete SCRAM and the following: RPS l 4.0 4
I
295017 High Off-site Release Rate/ 9 0
295020 Inadvertent Cont. Isolation / 5 & 7 0
Ab1l1ty to deterrrnne and/or interpret.... I, the following as they apply to Loss of CRD Pumps:
295022 Loss of CRD Pumps / 1 CRD system status ' 3.3
295029 High Suppression Pool Wtr Lvl / 5 0
295032 High Secondary Containment Area 0 Temperature/ 5
295033 High Secondary Containment Area 0 Radiation Levels / 9
295034 Secondary Containment Ventilation o Knowledge of the interrelations betwekn Secondary Containment Ventilation High 4.3, High Radiation / 9 3 Radiation and the following: SBGT/FRVS: Plant-Specific I
295035 Secondary Containment High 0 Knowledge of the operational implicati,ons I of the following concepts as they apply to Differential Pressure / 5 2 Secondary Containment High Differe~tial Pressure: Radiation release 3.7
295036 Secondary Containment High 0 Sump/Area Water Level / 5
500000 High CTMT Hydrogen Cone. / 5 Knowledge of EOP entry conditions and immediate action steps. 4.6' I
KIA Category Totals: 2 0 2 Group Point Total: 7
ES-401, Page 35 of 50 I
ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 1 (RO)
System # I Name K K K K K K A A A KIA Topic(s) IR # 2 3 4 5 6 4 '
203000 RHR/LPCI: Injection Mode 0 Knowledge of the operational implications of the following concepts as they 1 apply to RHR/LPCI: Injection MOde: Testable check valve operation 2.7
Knowledge of the effect that a loss or malfunction of the Shutdown Cooling 205000 Shutdown Cooling 0 0 will have on following: Reactor water level: Plant-Specific; Knowledge of the 3.2; 2 2 8 effect that a loss or malfunction of the following will have on the Shutdown 3.5 !
Coolin : RHR service water: Plant-S ecific
206000 HPCI Knowledge of annunciator alarms, indications, or response procedures. 4,2 1 i
207000 Isolation (Emergency) I ()
Condenser '
209001 LPCS Ability to monitor automatic operB.tions of the LPCS including: System 3.5
209002 HPCS 0 I
\\
211000 SLC determine that they correctly refl~ct bility to locate control room switches, controls, and indications, and to I the desired plant lineup. 4,6 1 I
212000 RPS 2 between RPS and the following: Reactor/turbine pressure control system: 3.4 1 1 Knowledge of the physical connections and/or cause-effect relationships
Plant-Specific 215003 IRM 0 Knowledge of electrical power supplies to the following: IRM ' 2.5 1
215004 Source Range Monitor 0 Knowledge of the effect that a loss or malfunction of the Source Range 3,7 4 Monitor will have on following: Reactor power and indication
215005 APRM I LPRM 0 Knowledge of the physical connections and/or cause-effect relationships 3.4 3 between APRM / LPRM and the following: RBM: Plant-Specific
217000 RCIC 0 Knowledge of the effect that a loss or malfunction of the following will have on 3.5 1:
3 the RCIC: Suppression pool water supply Ability to (a) predict the impacts ?f the following on the ADS; and (b) based on those predictions, use procedures to correct, control, or mitigate the 4.2; 218000 ADS consequences of those abnormal conditions or operations: ADS initiation 2 signals present; Ability to monitor automatic operations of the ADS including: 3,7 OS valve acoustical monitor noise: Plant-S ecific bility to predict and/or monitor changes in parameters associated with !
223002 PCIS/Nuclear Steam Supply 0 operating the PCJS/Nuclear Steam Supply Shutoff controls including: System 3.5; Shutoff 1 indicating lights and alarms; Abili~ to manually operate and/or monitor in the 3,6 2 control room: Valve closures Ability to (a) predict the impacts 6f the following on the SRVs; and (b) based 239002 SRVs on those predictions, use proced~res to correct, control, or mitigate the 3.0 1 consequences of those abnorma! conditions or operations: Stuck open '
vacuum breakers
259002 Reactor Water Level Control 0 Knowledge of Reactor Water Level Control design feature(s) and/or interlocks 3.1 6 which provide for the following: qontrol signal failure
261000 SGTS bility to monitor automatic operations of the SGTS including: System flow 3.2 1!
262001 AC Electrical Distribution Ability 0 I to predict and/or monitor changes in parameters associated with 2.7 1 4 operating the AC Electrical Distribution controls including: Load currents
Knowledge of the effect that a lo~s or malfunction of the UPS (AC/DC) will 2,9; 262002 UPS (AC/DC) 0 have on following: Process monitoring: Plant-Specific; Knowledge of UPS 2 7 1 (AC/DC) design feature(s) and/or; interlocks which provide for the following: 3,1
Transfer from preferred power to:alternate power supplies
and/or monitor ~anges in parameters associated with 263000 DC Electrical Distribution 0 to predict ctrical Distribution controls including: Battery 2.5 1 rate I
Knowledge of the physical conne'ctions and/or cause-effect relationships 264000 EDGs 4 5 Knowledge of the operational imPlications of the following concepts as they 3.4 ~ 0 0 between EDGs and the following: Emergency generator cooling water system; 3.2; I
apply to EDGs: Paralleling A.C. ~ower sources I
300000 Instrument Air 0 Knowledge of electrical power supplies to the following: Instrument air 2.8 1
Ability to (a) predict the impacts Of the following on the Component Cooling :
400000 Component Cooling Water or mitigate Water; and (b) based on those pfedictions, use procedures to correct, control, the consequences of those abnormal conditions or operations: 3.3 1 Loss ofCCW um
KIA Category Totals: 3 2 3 2 2 2 3 26 I
ES-401, Page 36 of 50 I
ES-401 BWR Examination Outline Form ES,401-1 Pian! Systems - Tier 2/Group 2 (RO)
System # I Name K K K K K K IK/A Topic(s) IR # 2 3 4,*5 6
0 Knowledge of the physical connections and/or cause-effect relationships I 1 I 201001 CRD Hydraulic between CRD Hydraulic Systen\\ and the 3 I following: Recirculation pumps (seal 3.1 purge): Plant-Specific I I 201002 RMCS 0 Knowledge of the effect that a loss or malfunction of the following will have on I 2.5 :
1 the RMCS: Select matrix powe~ I 201003 Control Rod and Drive Mechanism operating the Control Rod and frive I 2.8 I Mechanism controls including: CRD drive
201004 RSCS I I 0
201005 RCIS I I 0
201006 RWM
- 1 0
202001 Recirculation I 0
202002 Recirculation Flow Control I 0
204000RWCU 0 Knowledge of the effect that a loss or malfunction of the RWCU will have on 2.6 6 following: Area radiation levels I
- 214000 RPIS 0
215001 Traversing In-core Probe I 0
215002 RBM I 0
216000 Nuclear Boiler Inst. 0 Knowledge of the operational implications of the following concepts as they 3.1 8 apply to Nuclear Boiler Inst.: St~am fiow effect on reactor water level 219~00 RHR/LPCI: Torus/Pool Cooling Mode 0 1 Knowledge of the operational implications of the following concepts as they 223001 Primary CTMT and Aux. apply to Primary CTMT and Au~.: Oxygen concentration measurement: Plant-2.7 3 Specific I
226001 RHR/LPCI: CTMT Spray Mode 0
230000 RHR/LPCI: Torus/Pool Spray Mode 0
233000 Fuel Pool Cooling/Cleanup Knowledge of Fuel Pool Cooling/Cleanup design feature(s) and/or inte~ocks 2.8 1, which provide for the following: (vlaintenance of adequate pool temperature 234000 Fuel Handling Equipment Knowledge of less than or equal to one hour Technical Specification action statements for systems. *1 3.9
239001 Main and Reheat Steam I I I
I I 0 239003 MSIV Leakage Control I 'I 0 Ability to (a) predict the impacts*1of the following on the Reactor/Turbine
41000 Reactor/Turbine Pressure Regulator Pressure Regulator; and (b) baJed on those predictions, use procedures to 3.3 correct, control, or mitigate the donsequences of those abnormal conditions or
operations: Main turbine overspped
245000 Main Turbine Gen. / Aux. I I 0
256000 Reactor Condensate : 0 I
59001 Reactor Feedwater Ability to manually operate and/6r monitor in the control room: System valves 3.1 I I I 268000 Radwaste : 0 I
271000 Offgas. I 0
Ability to predict and/or monitor changes in parameters associated with 272000 Radiation Monitoring operating the Radiation Monitorirg controls including: Lights, alarms, and 2.9 indications associated with surveillance testing 286000 Fire Protection 0 Knowledge of electrical 2 I power s~pplies to the following: Pumps 2.9
288000 Plant Ventilation I 0
290001 Secondary CTMT- 0
290003 Control Room HVAC I 0
290002 Reactor Vessel Internals 0 I
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KIA Category Totals: 2 I 12
ES-401, Page 37 of 50 ES-401 2 Form ES-~J01-1
'-I
ES-401 BWR Examination Outline Form E_S-401-1 11-----------------.=---i--.-----.--,-----------...;_---'..;_-----------~---'r------11 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (SRO)
E/APE # / Name I Safety Function K K K A KIA Topic(s) IR #
2 3
295001 Partial or Complete Loss ofForced 0 Core Flow Circulation / 1 & 4
Ability to determine and/or interpret the following as they apply to Partial 295003 Partial or Complete Loss of AC / 6 or Complete Loss of AC: Whether a partial or complete loss of AC. power 4.2 has occurred 295004 Partial or Total Loss of DC Pwr / 6 Ability to determine and/or interpret the following as they apply to Partial 2.9 or Total Loss of DC Pwr: Battery voltage
I 295005 Main Turbine Generator Trip / 3 Ability to determine and/or interp~et the following as they apply to Main 3.9 Turbine Generator Trip: Reactor power
295006 SCRAM / 1 0
295016 Control Room Abandonment 17 0
295018 Partial or Total Loss of CCW / 8 0
Ability to determine and/or interp(et the following as they apply to Partial 295019 Partial or Total Loss of Inst. Air/ 8 or Total Loss of Inst. Air: Status bf safety-related instrument air system 3.7 loads (see AK2.1-AK2.19) '
295021 Loss of Shutdown Cooling/ 4 0
295023 Refueling Ace / 8 0
295024 High Drywell Pressure / 5 0
295025 High Reactor Pressure / 3 0
295026 Suppression Pool High Water 0 Temp./ 5
295027 High Containment Temperature/ 5 0
295028 High Drywell Temperature/ 5 0
295030 Low Suppression Pool Wtr Lvl / 5 Knowledge of EOP mitigation strategies. 4.7
295031 Reactor Low Water Level/ 2 Knowledge of the specific bases for EOPs. 4.0 I
295037 SCRAM Condition Present and Reactor Power Above APRM 0 Downscale or Unknown / 1
295038 High Off-site Release Rate I 9 0
600000 Plant Fire On Site I 8 0
700000 Generator Voltage and Electric Grid Knowledge of the emergency action level thresholds and classifications. 4.6 Disturbances / 6
KIA Category Totals: 0 0 0 0 Group Point Total: 7
ES-401, Page 34 of 50 I I
ES-401 BWR Examination Outline Form ES-401-1 I I I
Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (SRI))
lt----------------.-K--r--K---,--K--,-A- -------------,-1--. ---------...-------,----1!
E/APE #/Name I Safety Function 2 3 Kit TopIc(s) IR #
,-1-------------+---+-----tl 295002 Loss of Main Condenser Vac / 3 Knowledge of abnormal condition prodedures. 4.2
295007 High Reactor Pressure / 3 0
295008 High Reactor Water Level / 2 0
295009 Low Reactor Water Level / 2 0
295010 High Drywell Pressure/ 5 0
295011 High Containment Temp/ 5 0
295012 High Drywell Temperature/ 5 0
295013 High Suppression Pool Temp./ 5 0
295014 Inadvertent Reactivity Addition/ 1 0
295015 Incomplete SCRAM/ 1 0
295017 High Off-site Release Rate/ 9 0
295020 Inadvertent Cont. Isolation I 5 & 7 0
295022 Loss of CRD Pumps / 1 0
295029 High Suppression Pool Wtr Lvl / 5 0
295032 High Secondary Containment Area 0 Temperature/ 5 I
295033 High Secondary Containment Area bility to determine and/or interpret th~ following as they apply to High Secondary 4.2 Radiation Levels / 9 Containment Area Radiation Levels: qause of high area radiation
295034 Secondary Containment Ventilation 0 High Radiation / 9
295035 Secondary Containment High 0 Differential Pressure / 5 295036 Secondary Containment High Ability to determine and/or interpret th~ following as they apply to Secondary Containment High Sump/ Area Wate( Level: Operability of components within the 3.2 Sump/Area Water Level / 5 affected area [
500000 High CTMT Hydrogen Cone. I 5 0
KIA Category Totals: 0 0 0 0 Group Point Total: 3
ES-401, Page 35 of 50
"""'----------------.-ES-401 4 Form ES-~io1-1 ES-401 BWR Examination Outline Form ES-401-1 I 11---------------.,.....-,---,-.,.....-,---,_.,....._ ----------'--------------~-----'II Plant Systems - Tier 2/Group 1 (SRO)
System # I Name K K K K K K A A A I IR #
2 3 4 5 6 1 3 KIA Topic(s) I
203000 RHR/LPCI: Injection 0
205000 Shutdown Cooling Mode 0
206000 HPCI 0
207000 Isolation (Emergency) 0 Condenser ru,
209001 LPCS Ability to recognize system paralneters that are entry-level conditions for 4.6 Technical Specifications. I
209002 HPCS 0
211000 SLC 0
I 212000 RPS Ability to detenmine operability ahd/or availability of safety related equipment. 4.6 I
215003 !RM 0
215004 Source Range Monitor 0
Ability to (a) predict the impacts of the following on the RCIC; and (b) based on 217000 RCIC those predictions, use procedures to correct, control, or mitigate the 3.0 consequences of those abnonmal conditions or operations: Loss of vacuum um I
218000 ADS 0
223002 PCIS/Nuclear Steam Supply 0 Shutoff Ability to (a) predict the impacts of the following on the SRVs; and (b) based on 239002 SRVs those predictions, use procedur~s to correct, control, or mitigate the 4.3 consequences of those abnonmal conditions or operations: Reactor high ressure !
259002 Reactor Water Level Control 0
Ability to (a) predict the impacts of the following on the SGTS; and (b) based on 261000 SGTS those predictions, use procedures to correct, control, or mitigate the 2.8 consequences of those abnonmal conditions or operations: A.C. electrical failure
262001 AC Electrical Distribution 0
262002 UPS (AC/DC) 0
263000 DC Electrical Distribution 0
264000 EDGs 0
300000 Instrument Air 0
00000 Component Cooling Water 0
KIA Category Totals: 0 0 0 0 0 0 0 Group Point Total: 5
ES-401, Page 36 of 50 i
ES-401 5 Form ES-40~ -1 I
ES-401 BWR Examination Outline Form ES-4;01-1 Plant Systems - Tier 2/Group 2 (SRO) I I System # I Name K K K K K K I. ) IR I# 2 3 4 5 6 fA Top1c(s
201001 CRD Hydraulic 10 I 1* I
201002RMCS I I a
201003 Control Rod and Drive Mechanism I la I
201004 RSCS I 1
201005 RCIS 10
201006 RWM 1
202001 Recirculation Ability to apply Technical Specifi6ations for a system.
I 4.7 11
202002 Recirculation Flow Control I 1
204000 RWCU I 1
214000 RPIS 1
215001 Traversing In-core Probe 1
I 215002 RBM Jo
216000 Nuclear Boiler Inst., la I
Ability to (a} predict the impacts bf the following on the RHR/LPCI: Torus/Pool I 219000 RHR/LPCI: Torus/Pool Cooling Cooling Mode; and (b} based onlthose predictions, use procedures to correct, 3.2 ;1 Mode control, or mitigate the consequences of those abnormal conditions or o erations: Valve a enin s I I
223001 Primary CTMT and Aux. I I
226001 RHR/LPCI: CTMT Spray Mode 1
230000 RHR/LPCI: Torus/Pool Spray Mode I
233000 Fuel Pool Cooling/Cleanup lo I
234000 Fuel Handling Equipment. [a
Ability to (a} predict the impacts bf the following on the Main and Reheat 239001 Main and Reheat Steam Steam; and (b} based on those predictions, use procedures to correct, control, 3.9 11 or mitigate the consequences off those abnormal conditions or operations: I Malfunction of reactor turbine prfssure regulating system I
239003 MSIV Leakage Control I 1
241000 Reactor/Turbine Pressure Regulator I 1
245000 Main Turbine Gen. / Aux. I la. !
256000 Reactor Condensate : la
259001 Reactor Feedwater la I
, I 268000 Radwaste a
271000 Off gas a
272000 Radiation Monitoring a
286000 Fire Protection a
<' 288000 Plant Ventilation a
290001 Secondary CTMT a
290003 Control Room HVAC !
290002 Reactor Vessel Internals la I
I I
KIA Category Totals: a a a a a a 13
ES-401, Page 37 of 50 ES-401 Generic Knowledge and Abilities Outline (Tier
- 13) Form ES-401-3
!Facility Name: Date of Exam: I I
Category KIA# Topic I RO SRO-Only
I IR # IR #
2.1. 20 Ability to interpret and execute procedure steps. 4.6 1 4.6
2.1. 30 Ability to locate and operate components, including local controls. 4.4 1 4.0 I
Knowledge of RO duties in the control room during fuel handling such as responding' to
- 1. operated from the control room in support of fueling operations, and supporting 2.1. 44 alarms from the fuel handling area, communication with the fuel storage facility, systems 3.9 1 3.8
instrumentation. '
Conduct of to use procedures related to shift staffing, such as minimum crew complement, 2.9 3.9 1 Operations 2.1. 05 Ability overtime limitations, etc.
2.1. 41 Knowledge of the refueling process. I 2.8 3.7 1
2.1.
Subtotal I 3 2 2.2. 01 Ability to perform pre-startup procedures for the facility, including operating those co~trols associated with plant equipment that could affect reactivity. 4.5 1 4.4
2.2. 03 Knowledge of the design, procedural, and operational differences between units. 3.8 1 3.9 2.2. 44 Ability to interpret control room indications to verify the status and operation of a system, 4.2 1 4.4
- 2. and understand how operator actions and directives affect plant and system conditiohs.
Equipment 2.2. 25 Knowledge of the bases in Technical Specifications for limiting conditions for operations 3.2 4.2 1 Control and safety limits. I 2.2. 18 Knowledge of the process for managing maintenance activities during shutdown 2.6 3.9 1 operations, such as risk assessments, work prioritization, etc.
2.2. I Subtotal I ~
2.3. 15 Knowledge of radiation monitoring systems, such as fixed radiation monitors and ala/ms, 2.9 1 3.1 portable survey instruments, personnel monitoring equipment, etc. '
2.3. 11 Ability to control radiation releases. 3.8 1 4.3 2.3. 05 Ability to use radiation monitoring systems, such as fixed radiation monitors and alarrTls, 2.9 2.9 1
- 3. portable survey instruments, personnel monitoring equipment, etc.
Radiation 2.3.-
Control 2.3.
2.3.
0 2 1 Subtotal !
Knowledge of the parameters and logic used to assess the status of safety functions, such 2.4. 21 as reactivity control, core cooling and heat removal, reactor coolant system integrity, I 4.0 1 4.6 containment conditions radioactivitv release control etc.
2.4. 49 Ability to perform without reference to procedures those actions that require immediate 4.6 1 4.4 operation of system components and controls.
- 4. 2.4. 43 Knowledge of emergency communications systems and techniques. 3.2 3.8 1 Emergency Knowledge of the organization of the operating procedures network for normal, abnormal, Procedures 2.4. 05 and emergency evolutions. 3.7 4.3 1
/ Plan )
2.4.
2.4.
Subtotal I EE Tier 3 Point Total 7
ES-401, Page 43 of 50 ES-401 Record of Rejected K/As Form ES-401-4
Tier/ Randomly Reason for RejJction Group Selected KIA I
SRO 1/1 295031 G2.4.02 Supports testing the RO level, but not the sJo level. Replaced with (79) 295031 G2.4.18 I SRO 1/2 295002 G2.4.04 Overlap with NRC item 295031 G2.4.04. Rbplaced with 295002 G2.4.l 1 (85) I
RO 1/2 295033EKI.03 Overlap with NRC item 295033 A2.03. ReJlaced with 295034 K2.03 (56) I
RO 2/2 (1) 239003 K4.02 System not at Peach Bottom. Replaced with b33000 K4.03
RO 1/1 295037 EKI.07 Unable to write adequate question. Replaceh with 295037 EKl.05 (40) I
ROI/I 295016 AAI.03 Unable to develop adequate question. Repla!ed with 295016 AAI.07 (53) I SRO 1/1 295005 AA2.03 Unable to develop adequate question. Repl,ced with 295006 AA2.05 (82)
SRO 1/2 295036 AA2.03 Unable to develop SRO level question. Replaced with 295036 AA2.01 I (86)
SRO2/2 233000 G2.42 Oversample issue. Replaced with 202001 f.40 (94)
SRO 2/2 I, 234000 K4.02 Oversample issue. Replaced with 239001 AQ.05 (88) I 3 (22) G2.3.7 Unable to develop adequate question. Repl~ced with G2.3.11 SRO 2/1 209001 G2.4.50 Unable to develop adequate question. ReplJced with G2.2.42 (91) I 3 (92) G2.2.4 Unable to develop SRO level question. Replaced with G2.2.25 I
RO 1/2 (43) 500000 G2.4.03 Unable to develop adequate question. Repl~ced with G2.4.01 RO2/1 218000 A3.09 Unable to develop adequate question. Repl,ced with 218000 A3.03 (26)
RO 1/1 295030 G2.4.30 Unable to develop adequate question due to hverlap. Replaced with (13) G2.4.20 I
RO2/2 201003 A3.0l Unable to develop adequate question. Replabed with 201003 Al.02 (65) I
RO 1/2 295035 EK2.03 Unable to develop adequate question. Replared with 295035 Kl.02 (30)
SRO 2/1 239002 A2.04 Overlap issue. Replaced with 239002 A2.0, (99)
3 (6) G2.l.19 Unable to develop adequate question. Replabed with 2.1.20 3 (97) G2.l.39 Unable to develop adequate question. Replabed with 2.1.41
3 (48) G2.2.4 Unable to develop adequate question. Replabed with 2.2.3 3 (89) G2.3.7 Too many G2.3 topic questions. Replaced Jith 2.2.18 ES-401 Record of Rejected K/As Form ES-401-4
RO 1/2 (47) 295015 AK.3.01 Overlap with question 71. Replaced with 2~5015 AK2.04
3 (57) G2.4.35 Unable to develop adequate question. Repl~ced with G2.4.49 RO 2/1 (61) 261000 A4.02 Unable to develop adequate question. ReplJced with 261000 A3.0l
SRO 2/1 261000 A2.05 Unable to develop adequate question. ReplJced with 261000 A2.07 (76) I SRO 2/2 239001 A2.05 Unable to develop adequate question. ReplJced with 239001 A2.01 (88) - I 3 (96) G2.l.13 Unable to develop adequate question. Repl~ced with G2. l.5.
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