ML21237A518

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Final Written Examination and Operating Test Outlines (Folder 3)
ML21237A518
Person / Time
Site: Peach Bottom  Constellation icon.png
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)
e. 295024 EA 1.11 4.2/4.2, Spray the Containment using HPSW M, EN, S 5 per T-205 (PLOR-079C)
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)
e. 295024 EA 1.11 4.2/4.2" Spray the Containment using HPSW M EN,S 5 per T-205 (PLOR-079C)
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.

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

Examiners Operators CRS (SRO)

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

Examiners Operators CRS (SRO)

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
b. T-214, Isolating and Venting t1e Scram Air Header
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.

CRS

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 4 Form ES-401.-

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

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

I ES-401 3 Form ES-ii01-1

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

215005 APRM / LPRM 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.

j

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