ML17013A460

Draft - Outlines (Folder 2)

ML17013A460
Person / Time
Site:	Susquehanna
Issue date:	11/14/2016
From:	Operations Branch I
To:	Susquehanna
Shared Package
ML16076A438	List: IR 05000387/2016301 ML16155A069 ML16315A244 ML17013A454 ML17013A455 ML17013A457 ML17013A458 ML17013A459 ML17013A460 ML17013A461 ML17013A462 ML17102A838 ML17102A839
References
U01931
Download: ML17013A460 (28)

Text

Appendix D Scenario Outline Form ES-D-1 Facility: SSES Unit 1 And 2 Scenario No.: 1 Op-Test No.: LOC28 Examiners: Operators:

Initial Conditions: Unit 1 is at 95 % gower for a rod control gattern adjustment at EOL. HPCI is out of service. The 'E' EOG is substituted for 'A' EOG.

Turnover: Swag 'A' RFP main lube oil gumgs . RFP lube oil conditioner swagged from 'A' to 'B' last shift. Severe thunderstorm watch is in effect for Luzerne County.

Event Malf. Event Event No. No. Type* Description N Swap 'A' RFP main lube oil pumps 1 N/A SRO,BOP (OP-145-003)

R Withdraw control rods to raise reactor power 3 percent.

2 N/A SRO, ATC (OP-A0-338, G0-100-012)

'B' RFPT trips on high vibration, Recirc LIM2 runback, Setup for mfFW145 3 0078 N/A event4 (AR-101-A16, ON-164-002) cmfTR03_ APRM 2 and 3 'A' Recirc Loop drive flow fails high during LIM2 4 FTB31 I (TS) 1N014C SRO.ATC runback (TS 3.3.1.1)

RBCCW TCV fails, ESW placed in-service to restore RBCCW 5

cmfAV04_ C (TS) cooling (ON-RBCCW-101 ), ESW loop declared inoperable when TV11028 SRO,BOP alianed to RBCCW <TS 3.7.2) 6 mfRW1140 01 f:20 c RBCCW rupture on the common discharge header. 'A' RRP SRO.ATC temperature rises raipidly requiring a manual Scram mfRD155 M Hydraulic-block ATWS 7 017 All (E0-100-113, OP-145-005, ES-158-002) cmfPM03-8 1P208A cmfPM03_

c SLC pump trips after start, standby SLC pump successfully injects SRO,BOP boron (OP-153-001) 1P208B cmfTR01 I Wide Range level instrument fails, RFP flow must be raised to 9 LT14201A SRO,ATC maintain reactor level in ATWS band 10 mfFW148 002 c In-service RFPT trips after first scram, RCIC restored to maintain All RPV level while standby RFPT placed in-service

• (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor

Target Quantitative Attributes (Per Scenario; See Section Scenario Events Actual D.5.d) Attributes

1. Malfunctions after EOP entry (1-2) 8,9,10 3

2. Abnormal events (2-4) 4,5,6 3

3. Major transients (1-2) 7 1

4. EOPs entered/requiring substantive actions (1-2) E0-000-102 1

5. EOP contingencies requiring substantive actions (0-2) E0-000-113 1

6. EOP based Critical tasks (2-3) 3 CT-1 Inject SLC CT-2 Lowers RPV level to <-60" but >-161" CT-3 Inserts control rods IAW E0-000-113

Appendix D Scenario Outline Form ES-D-1 Facility: SSES Units 1 and 2 Scenario No.: 3 Op-Test No.: LOC28 Examiners: Operators:

Initial Conditions: Unit 1 is at 33% (2ower shutting down for Or~ell RCS leakage at EOL.

Turnover: Insert Control Rods and test Turbine By(2ass valve #3 for valve functional testing.

Event Malf. Event Event No. No. Type* Description N Test turbine bypass valve #3 1 N/A SRO,BOP (S0-182-001)

R Insert control rods 2 N/A SRO,ATC (OP-156-001, OP-A0-338)

FW heater 2C tube leak (AR-120-C10, 010), Isolate FW heater 3

cmfHX02_ C (TS) extraction steam (ON-147-002), TS MCPR limits not applicable 1E102C SRO,BOP (TS 3.2.2) cmfEB01 -

1A203 I (TS) ESS Bus 1C lockout, Orywell leak severity rises, reactor scram 4 mfRR164 SRO,ATC required (ON-4KV-101, TS 3.8.7) 010 5

mfRP158 003 c Electrical ATWS (E0-000-113)

All ARI inserts control rods cmfMV06 I RCIC injection valve fails to auto open on initiation 6 HV149FOfa SRO,BOP (OP-150-001) 7 mfRR179 003 c Fuel failure with high MSL radiation, MSIV isolation required All (AR-103-001, AR-104-001) cmfMV01 HPCI steam isolation valves fail to automatically close (AR-114-8 HV155F002 I F04, F05}, manual isolation successful after reactor pressure cmfMV07 SRO,BOP HV155F003 reduced mfRC150 M Unisolable RCS leak into Secondary Contrainment, 2 areas above 9 004 All Max Safe Temp (E0-000-104)

• (N}ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor

Target Quantitative Attributes (Per Scenario; See Section Scenario Events Actual 0.5.d) Attributes

1. Malfunctions after EOP entry (1-2) 6,7,8 3

2. Abnormal events (2-4) 3,4,5 3

3. Major transients (1-2) 9 1

4. EOPs entered/requiring substantive actions (1-2) E0-000-102 2

E0-000-104

5. EOP contingencies requiring substantive actions (0-2) E0-000-113 2

E0-000-112

6. EOP based Critical tasks (2-3)

CT-1 Manually initiate ARI CT-2 Emergency Depressurize the reactor when two 2

Secondary Containment Areas exceed Max Safe Temp levels

Appendix D Scenario Outline Form ES-D-1 Facility: SSES Units 1 and 2 Scenario No.: 4 Op-Test No.: LOC28 Examiners: Operators:

Initial Conditions: Unit 1 is at 90% gower. RCIC is out of Service. OBE in Lehigh Valle)'.. ON-NATPHENOM-001 is comglete. Unit 2 is at rated gower.

Turnover: Shutdown the 'B' EDG, the 15-min run at 1OOOKW is comglete. Raise gower 5% with Recirc flow IAW the RMR.

_ _nt Malf. Event Event No. No. Type* Description N Secure 'B' EDG 1 N/A SRO,BOP (S0-024-001 B) 2 R C(TS)

N/A Raise Reactor Power 5% using Recirc flow, RRP runaway SRO,ATC mfRD155 C (TS) Control rod drift in/out 3 0085023 0055023 SRO.ATC (TS 3.1.3) mfDS003 C (TS) Startup Transformer 20 lockout 4 008 SRO.BOP (TS 3.8.1) 5 mfMS183 M Small RCS steam leak in the Drywell 007 All I HPCI fails to automatically initiate on high Drywell pressure, all 6 Various SRO,BOP other high-pressure injection lost 7 mfRH149 c Stem-to-disk separation of RHR F016 Drywell Spray valve 011A(B) SRO,BOP M Loss of reactor level indication - RPV Flooding 8 Various All (E0-000-114)

• (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor

Target Quantitative Attributes (Per Scenario; See Section Scenario Events Actual D.5.d) Attributes

1. Malfunctions after EOP entry (1-2) 6,7 2

2. Abnormal events (2-4) 3,4 2

3. Major transients (1-2) 5, 8 2

4. EOPs entered/requiring substantive actions (1-2) E0-000-102 2

E0-000-103

5. EOP contingencies requiring substantive actions (0-2) E0-000-114 1

6. EOP based Critical tasks (2-3)

CT-1 Spray the Drywell when Suppression Chamber pressure exceeds 13 psig 2

CT-2 Performs RPV Flooding when RPV water level becomes indeterminate by establishing RPV Flooded to Steamlines

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Susquehanna Date of Examination: 11/14/2016 Examination Level: RO x SRO Operating Test Number: U01931 Administrative Topic (see Note) Type Describe activity to be performed Code*

Complete Aborted Evolution Log Conduct of Operations D,R Perform LPRM Upscale Alarm Tracking Conduct of Operations D,R Perform Jet Pump Operability Check Equipment Control R,N Radiation Control Activate Fire Brigade Emergency Plan S,D NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

• Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (:::;; 3 for ROs; :::;; 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (;:: 1)

(P)revious 2 exams (:::;; 1; randomly selected)

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Susquehanna Date of Examination: 11/14/2016 Examination Level: RO SRO K Operating Test Number: U01931 Administrative Topic (see Note) Type Describe activity to be performed Code*

Perform Validation of Heat Balance Conduct of Operations R,M Perform LPRM Upscale Alarm Operability Tracking Conduct of Operations R,D and Determine Required Actions Determine Operability ofMSIV Isolation Actuation Equipment Control R,D Determine LCO Applicability and Ability to Bypass Radiation Control R,D Secondary Containment Zone 2 Isolation Classify an Emergency Condition and Complete Emergency Plan R,N Emergency Notification Report NOTE: All items (five total) are required for SROs. RO applicants require only four items .unless they are retaking only the administrative topics (which would require all five items).

• Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (S 3 for ROs; ::; 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (~ 1)

(P)revious 2 exams (S 1; randomly selected)

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Susguehanna Date of Examination: 11/14/2016 Exam Level: RO x SRO-I SRO-U Operating Test No.: U01931 Control Room Systems:* 8 for RO; 7 for SRO-I; 2 or 3 for SRO-U System I JPM Title Type Code* Safety Function

a. Reset Recirc Lim 2 Runback - 64.0N.67049.101 M,S 1

b. Reactor Feed Pump Post Scram Recovery-45.0P.21388.102 L,M,S 2

c. Open MSIVs during Reactor SIU (All rods in) - 84.0P.24666.151 A,D,EN,L,S 3

d. Shutdown Cooling Temperature Control - 49.0N.20294.151 A,M,L,S,P 4

e. Re-establish RBHVAC IAW ES-134-003 - 34.E0.20802.151 A,D,EN,L,S 5

f. Energize Dead 4KV ESS Bus 2D - 04.0N.20641.251 A,D,S 6

g. APRM Gain Adjust - 78.0P.27731.101 D,P,S 7

h. Place Alternate TBCCW Pump l/S - 15.0P.20688.151 A,D,P,S 8 In-Plant Systems* (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. Hydraulically Remove HCU from Service - 55.0P.003.102 D,R 1

j. Start RPS MG Set 2S237A Locally- 58.0P.26824.201 D,R 7

k. Place RHR in SPC at RSDP - 49.0P.1877.201 D,E,R 5

• 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; 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 14-612-3 (C)ontrol room (D)irect from bank  :::;9/:::;8/:::;4 (E)mergency or abnormal in-plant <:1/<:1/<:1 (EN)gineered safety feature <:1 I <:1 I<: 1 (control room system)

(L)ow-Power I Shutdown <:1/<:1/<:1 (N)ew or (M)odified from bank including 1(A) <:2/<:2/<:1 (P)revious 2 exams  :::; 3 /:::; 3 /:::; 2 (randomly selected)

(R)CA <:1/<:1/<:1 (S)imulator

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Susquehanna Date of Examination: 11/14/2016 Exam Level: RO SRO-I x SRO-U Operating Test No.: U01931 Control Room Systems:* 8 for RO; 7 for SRO-I; 2 or 3 for SRO-U System I JPM Title Type Code* Safety Function

a. Reset Recirc Lim 2 Runback, - 64.0N.67049.101 M,S 1

b. Reactor Feed Pump Post Scram Recovery- 45.0P.21388.102 L,M,S 2

c. Open MSIVs during Reactor S/U (All rods in) - 84.0P.24666.151 A,D,EN,L,S 3

d. Shutdown Cooling Temperature Control - 49.0N.20294.151 A,M,L,S,P 4

e. Re-establish RBHVAC IAW ES-134-003- 34.E0.20802.151 A,D,EN,L,S 5

f. Energize Dead 4KV ESS Bus 2D - 04.0N.20641.251 A,D,S 6 g.

h. Place Alternate TBCCW Pump l/S-15.0P.20688.151 A,D,P,S 8 In-Plant Systems* (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. Hydraulically Remove HCU from Service - 55.0P.003.102 D,R 1

j. Start RPS MG Set 2S237A Locally- 58.0P.26824.201 D,R 7

k. Place RHR in SPC at RSDP - 49.0P.1877.201 D,E,R 5

• 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; 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 4-614-612-3 (C)ontrol room (D)irect from bank :S9/:S8/:S4 (E)mergency or abnormal in-plant <::1/<::1/<::1 (EN)gineered safety feature <::1 I <::1 I<:: 1 (control room system)

(L)ow-Power I Shutdown <::1/<::1/<::1 (N)ew or (M)odified from bank including 1(A) <::2/<::2/<::1 (P)revious 2 exams  :::; 3 I:::; 3 I:::; 2 (randomly selected)

(R)CA <::1/<::1/<::1 (S)imulator

ES-401 Written Examination Outline Form ES-401-1 I

Facility: SSES LOC28 NRC Date of Exam: November 2016 RO KIA Category Points SRO-Only Points Tier Group K K K K K K A A A A G Total A2 G* Total 1 2 3 4 5 6 1 2 3 4

• 1.

1 3 4 3 . %~*;~ 3 4 *: . 3 20 3 4 7 I*** ..

Emergency .... '

& 2 1 2 1 .*.  :. .... :***. 1 1 1 7 2 1 3 Plant Evolutions Tier 4 6 4

'*:* .. 4 5 4 27 5 5 10 Totals ** I*

1 3 2 3 2 2 2 3 2 2 2 3 26 3 2 5 2.

Plant 2 1 0 2 2 1 1 1 1 1 1 1 12 0 1 2 3 Systems Tier Totals 4 2 5 4 3 3 4 3 3 3 4 38 4 4 8 1 2 3 4 1 2 3 4

3. Generic Knowledge & Abilities Categories 10 7 2 3 3 2 2 2 2 1 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 outline, the "Tier Totals" in each KIA category shall not be less than two). (One Tier 3 Radiation Control KIA is allowed if the KIA is replaced by a KIA from another Tier 3 Category.)

2. The point total for each group and tier in the proposed outline must match that specified in the table.

The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.

3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted with justification; operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate KIA statements.

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

5. Absent a plant-specific priority, only those KIAs having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

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

7. The generic (G) KIAs in Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable KIAs.

8. On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (I Rs) 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 a category other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.

9. For Tier 3, select topics from Section 2 of the KIA catalog, and enter the KIA numbers, descriptions, IRs, and point totals(#) on Form ES-401-3. Limit SRO selections to KIAs that are linked to 10 CFR 55.43.

G* Generic KIAs

ES-401 2 Form ES-401-1 SSES LOC28 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE #I Name Safety Function K1 K2 K3 A1 A2 G KIA Topic(s) Imp. Q#

EA2.02 - Ability to determine and/or 295030 Low Suppression Pool interpret the following as they apply to Water Level I 5 x LOW SUPPRESSION POOL WATER 3.9 76 LEVEL: Suppression pool temperature AA2.01 - Ability to determine and/or 295006 SCRAM / 1 x interpret the following as they apply to 4.6 77 SCRAM: Reactor power AA2.01 - Ability to determine and/or interpret the following as they apply to 295004 Partial or Complete Loss of DC Power I 6 x PARTIAL OR COMPLETE LOSS OF 3.6 78 D.C. POWER: Cause of partial or complete loss of D.C. power 2.2.44 - Equipment Control: Ability to interpret control room indications to 295038 High Off-site Release verify the status and operation of a Rate 19 x system, and understand how operator 4.4 79 actions and directives affect plant and system conditions.

2.4.9 - Emergency Procedures I Plan:

Knowledge of low power I shutdown 295025 High Reactor Pressure I 3

x implications in accident (e.g., loss of 4.2 80 coolant accident or loss of residual heat removal) mitigation strategies.

2.2.22 - Equipment Control: Knowledge 295026 Suppression Pool High Water Temperature I 5 x of limiting conditions for operations and 4.7 81 safety limits.

2.4.47 - Emergency Procedures I Plan:

Ability to diagnose and recognize trends 295018 Partial or Complete Loss of CCW I 8 x in an accurate and timely manner 4.2 82 utilizing the appropriate control room reference material.

AK1 .02 - Knowledge of the operational implications of the following concepts as 700000 Generator Voltage and they apply to GENERATOR VOLTAGE Electric Grid Disturbances x AND ELECTRIC GRID 3.3 39 DISTURBANCES and the following:

Over-excitation.

EK1 .02 - Knowledge of the operational implications of the following concepts as 295031 Reactor Low Water Level/ 2 x they apply to REACTOR LOW WATER 3.8 40 LEVEL: Natural circulation: Plant-Specific EK1 .03 - Knowledge of the operational implications of the following concepts as 295038 High Off-site Release Rate 19 x they apply to HIGH OFF-SITE 2.8 41 RELEASE RATE: Meteorological effects on off-site release.

AK2.01 - Knowledge of the interrelations between PARTIAL OR COMPLETE 295018 Partial or Complete Loss of CCW I 8 x LOSS OF COMPONENT COOLING 3.3 42 WATER and the following: System loads AK2.01 - Knowledge of the interrelations between CONTROL ROOM 295016 Control Room Abandonment I 7 x ABANDONMENT and the following: 4.4 43 Remote shutdown panel: Plant-Specific AK2.04 - Knowledge of the interrelations 600000 Plant Fire On-site I 8 x between PLANT FIRE ON SITE and the 2.5 44 following: Breakers, relays, and

ES-401 2 Form ES-401-1 SSES LOC28 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE #I Name Safety Function K1 K2 K3 A1 A2 G KIA Topic(s) Imp. Q#

disconnects AK3.04 - Knowledge of the reasons for 295005 Main Turbine Generator the following responses as they apply to Trip/ 3 x MAIN TURBINE GENERATOR TRIP:

3.2 45 Main oenerator trip EK3.03 - Knowledge of the reasons for 295037 SCRAM Conditions the following responses as they apply to Present and Reactor Power SCRAM CONDITION PRESENT AND Above APRM Downscale or x REACTOR POWER ABOVE APRM 4.1 46 Unknown/ 1 DOWNSCALE OR UNKNOWN:

Lowerino reactor water level AK3.01 - Knowledge of the reasons for the following responses as they apply to 295019 Partial or Complete Loss of Instrument Air I 8 x PARTIAL OR COMPLETE LOSS OF 3.3 47 INSTRUMENT AIR: Backup air system supply: Plant-Specific AA 1.03 - Ability to operate and/or monitor the following as they apply to 295003 Partial or Complete Loss of AC/ 6 x PARTIAL OR COMPLETE LOSS OF 4.4 48 A.C. POWER: Systems necessary to assure safe plant shutdown EA 1.07 - Ability to operate and/or 295025 High Reactor Pressure I monitor the following as they apply to 3

x HIGH REACTOR PRESSURE:

4.1 49 ARl/RPT/ATWS: Plant-Specific AA 1.03 - Ability to operate and/or 295004 Partial or Complete monitor the following as they apply to Loss of DC Power I 6 x PARTIAL OR COMPLETE LOSS OF 3.4 50 D.C. POWER: A.C. electrical distribution EA2.02 - Ability to determine and/or 295028 High Drywell interpret the following as they apply to Temperature I 5 x HIGH DRYWELL TEMPERATURE:

3.8 51 Reactor pressure AA2.04 - Ability to determine and/or 295006 SCRAM / 1 x interpret the following as they apply to 4.1 52 SCRAM: Reactor pressure AA2.01 - Ability to determine and/or 295021 Loss of Shutdown interpret the following as they apply to Cooling/ 4 x LOSS OF SHUTDOWN COOLING:

3.5 53 Reactor water heatup/cooldown rate 2.2.22 - Equipment Control: Knowledge 295023 Refueling Accidents I 8 x of limiting conditions for operations and 4.0 54 safety limits.

2.1.23 - Conduct of Operations: Ability 295030 Low Suppression Pool to perform specific system and Water Level I 5 x integrated plant procedures during all 4.3 55 modes of plant operation.

295026 Suppression Pool High 2.2.12 - Equipment Control: Knowledge Water Temperature I 5 x of surveillance procedures.

3.7 56 EK2.11 - Knowledge of the interrelations 295024 High Drywell Pressure I between HIGH DRYWELL PRESSURE 5

x and the following: Drywell spray (RHR) 4.2 57 looic: Mark-1&11 AA2.04 - Ability to determine and/or 295001 Partial or Complete interpret the following as they apply to Loss of Forced Core Flow x PARTIAL OR COMPLETE LOSS OF 3.0 58 Circulation I 1 & 4 FORCED CORE FLOW CIRCULATION:

Individual jet pump flows: Not-BWR-1 &2 KIA Category Totals: 3 4 3 3 4/3 3/4 Group Point Total:

I 2017

ES-401 3 Form ES-401-1 SSES LOC28 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 EAPE #I Name Safety Function K1 K2 K3 A1 A2 G KIA Topic(s) Imp. Q#

EA2.04 - Ability to determine and/or interpret the following as they apply to 500000 High Containment Hydrogen Concentration I 5 x HIGH PRIMARY CONTAINMENT 3.3 83 HYDROGEN CONCENTRATIONS:

Combustible limits for wetwell 2.1.7 - Conduct of Operations: Ability to evaluate plant performance and make 295002 Loss of Main Condenser Vacuum I 3 x operational judgments based on 4.7 84 operating characteristics, reactor behavior, and instrument interpretation.

EA2.02 - Ability to determine and/or 295035 Secondary interpret the following as they apply to Containment High Differential x SECONDARY CONTAINMENT HIGH 4.1 85 Pressure 15 DIFFERENTIAL PRESSURE: Off-site release rate: Plant-Specific AK1 .05 - Knowledge of the operational implications of the following concepts as 295014 Inadvertent Reactivity Addition x they apply to INADVERTENT 3.7 59 REACTIVITY ADDITION: Fuel thermal limits AK2.05 - Knowledge of the interrelations 295010 High Drywell Pressure I between HIGH DRYWELL PRESSURE 5

x and the following: Drywell cooling and 3.7 60 ventilation AK3.03 - Knowledge of the reasons for 295007 High Reactor Pressure the following responses as they apply to

/3 x HIGH REACTOR PRESSURE: RCIC 3.4 61 operation: Plant-Specific EA 1.03 - Ability to operate and/or 295033 High Secondary monitor the following as they apply to Containment Area Radiation x HIGH SECONDARY CONTAINMENT 3.8 62 Levels/ 9 AREA RADIATION LEVELS: Secondary containment ventilation EA2.02 - Ability to determine and/or 295032 High Secondary interpret the following as they apply to Containment Area Temperature x HIGH SECONDARY CONTAINMENT 3.3 63 15 AREA TEMPERATURE: Equipment operability 295035 Secondary 2.4.1 - Emergency Procedures I Plan:

Containment High Differential x Knowledge of EOP entry conditions and 4.6 64 Pressure/ 5 immediate action steps.

AK2.01 - Knowledge of the interrelations 2950201nadvertent between INADVERTENT Containment Isolation I 5 & 7 x CONTAINMENT ISOLATION and the 3.6 65 following: Main steam system KIA Category Totals: 1 2 1 1 1/2 1/1 Group Point Total:

I 7/3

ES-401 4 Form ES-401-1 SSES LOC28 NRC Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A System #I Name A2 G Imp. Q#

1 2 3 4 5 6 1 3 4 A2.01 - Ability to (a) predict the impacts of the following on the INSTRUMENT AIR SYSTEM and (b) based on those predictions, use procedures to 300000 Instrument Air x correct, control, or mitigate the 2.8 86 consequences of those abnormal conditions or operations: Air dryer and filter malfunctions A2.09 - Ability to (a) predict the impacts of the following on the LOW PRESSURE CORE SPRAY SYSTEM; and (b) based on those predictions, use 209001 LPCS x procedures to correct, control, or 3.3 87 mitigate the consequences of those abnormal conditions or operations: Low suppression pool level 2.4.6 - Emergency Procedures I 211000 SLC x Plan: Knowledge of EOP 4.7 88 mitigation strateaies.

2.1.25 - Conduct of Operations:

Ability to interpret reference 217000 RCIC x materials, such as graphs, 4.2 89 curves, tables, etc.

A2.09 - Ability to (a) predict the impacts of the following on the HIGH PRESSURE COOLANT INJECTION SYSTEM; and (b) based on those predictions, use 206000 HPCI x procedures to correct, control, or 3.7 90 mitigate the consequences of those abnormal conditions or operations: Low condensate storacie tank level: BWR-2,3,4 K1 .04 - Knowledge of the physical connections and/or cause-effect relationships 264000 EDGs x between EMERGENCY 3.2 1 GENERATORS (DIESEUJET) and the following: Emergency generator cooling water svstem K1 .09 - Knowledge of the physical connections and/or cause-effect relationships between HIGH PRESSURE 206000 HPCI x COOLANT INJECTION 4.0 2 SYSTEM and the following:

ECCS keep fill system: BWR-2,3,4(P-Spec)

K2.01 - Knowledge of electrical 203000 RHR/LPCI: Injection Mode x power supplies to the following: 3.5 3 Pumps K2.01 - Knowledge of electrical 215004 Source Range Monitor x power supplies to the following: 2.6 4 SRM channels/detectors

ES-401 4 Form ES-401-1 SSES LOC28 NRC Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A System #I Name A2 G Imp. Q#

1 2 3 4 5 6 1 3 4 K3.03 - Knowledge of the effect that a loss or malfunction of the PRIMARY CONTAINMENT 223002 PCIS/Nuclear Steam ISOLATION Supply Shutoff x SYSTEM/NUCLEAR STEAM 3.6 5 SUPPLY SHUT-OFF will have on following: Off-site radioactive release rates K3.02 - Knowledge of the effect that a loss or malfunction of the SHUTDOWN COOLING 205000 Shutdown Cooling x SYSTEM (RHR SHUTDOWN 3.2 6 COOLING MODE) will have on following: Reactor water level:

Plant-Specific K4.08 - Knowledge of RELIEF/SAFETY VALVES design feature(s) and/or 239002 SRVs x interlocks which provide for the 3.6 7 following: Opening of the SRV from either an electrical or mechanical signal K4.14 - Knowledge of REACTOR WATER LEVEL CONTROL SYSTEM design 259002 Reactor Water Level feature(s) and/or interlocks Control x which provide for the following:

3.4 8 Selection of various instruments to provide reactor water level input K5.04 - Knowledge of the operational implications of the following concepts as they apply 209001 LPCS x to LOW PRESSURE CORE 2.8 9 SPRAY SYSTEM: Heat removal (transfer) mechanisms K5.02 - Knowledge of the operational implications of the 262001 AC Electrical Distribution x following concepts as they apply 2.6 10 to A.C. ELECTRICAL DISTRIBUTION: Breaker control K6.03 - Knowledge of the effect that a loss or malfunction of the 300000 Instrument Air x following will have on the 2.7 11 INSTRUMENT AIR SYSTEM:

Temperature indicators K6.03 - Knowledge of the effect that a loss or malfunction of the following will have on the 262002 UPS (AC/DC) x UNINTERRUPTABLE POWER 2.7 12 SUPPLY (A.C./D.C.): Static inverter A 1.02 - Ability to predict and/or monitor changes in parameters associated with operating the 261000 SGTS x STANDBY GAS TREATMENT 3.1 13 SYSTEM controls including:

Primary containment pressure

ES-401 4 Form ES-401-1 SSES LOC28 NRC Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A System # I Name A2 G Imp. Q#

1 2 3 4 5 6 1 3 4 A 1.09 - Ability to predict and/or monitor changes in parameters associated with operating the 211000 SLC x STANDBY LIQUID CONTROL 4.0 14 SYSTEM controls including:

SBLC system lineup A2.02 - Ability to (a) predict the impacts of the following on the D.C. ELECTRICAL DISTRIBUTION; and (b) based 263000 DC Electrical on those predictions, use Distribution x procedures to correct, control, or 2.6 15 mitigate the consequences of those abnormal conditions or operations: Loss of ventilation durinQ charqinQ A2.01 - Ability to (a) predict the impacts of the following on the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM; and (b) based on those predictions, 215003 IRM x use procedures to correct, 2.8 16 control, or mitigate the consequences of those abnormal conditions or operations: Power supply degraded A3.03 - Ability to monitor automatic operations of the 217000 RCIC x REACTOR CORE ISOLATION 3.7 17 COOLING SYSTEM (RCIC) including: System pressure A3.05 - Ability to monitor automatic operations of the AVERAGE POWER RANGE 215005 APRM I LPRM x MONITOR/LOCAL POWER 3.3 18 RANGE MONITOR SYSTEM including: Flow converter/comparator alarms A4.11 - Ability to manually operate and/or monitor in the 212000 RPS x control room: Scram air header 3.7 19 pressure A4.01 - Ability to manually 400000 Component Cooling operate and/or monitor in the Water x control room: CCW indications 3.1 20 and control 2.1.27 - Conduct of Operations:

218000ADS x Knowledge of system purpose 3.9 21 and I or function.

2.4.35 - Emergency Procedures I Plan: Knowledge of local 300000 Instrument Air x auxiliary operator tasks during 3.8 22 an emergency and the resultant operational effects.

ES-401 4 Form ES-401-1 SSES LOC28 NRC Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A System # I Name A2 G Imp. Q#

1 2 3 4 5 6 1 3 4 A 1.05 - Ability to predict and/or monitor changes in parameters associated with operating the 259002 Reactor Water Level Control x REACTOR WATER LEVEL 2.9 23 CONTROL SYSTEM controls including: FWRV/startup level control oosition: Plant-Soecific K1 .07 - Knowledge of the physical connections and/or cause-effect relationships 215003 IRM x between INTERMEDIATE 3.0 24 RANGE MONITOR (IRM)

SYSTEM and the following:

Reactor vessel K3.01 - Knowledge of the effect that a loss or malfunction of the 262001 AC Electrical Distribution x A.C. ELECTRICAL 3.5 25 DISTRIBUTION will have on following: Major svstem loads 2.1.28 - Conduct of Operations:

Knowledge of the purpose and 262002 UPS (AC/DC) x function of major system 4.1 26 components and controls.

KIA Category Totals: 3 2 3 2 2 2 3 213 2 2 312 Group Point Total:

I 26/5

ES-401 5 Form ES-401-1 SSES LOC28 NRC Written Examination Outline Plant Systems - Tier 2 Group 2 K K K K K K A A A System #I Name A2 G Imp. Q#

1 2 3 4 5 6 1 3 4 A2.03 - Ability to (a) predict the impacts of the following on the ROD BLOCK MONITOR SYSTEM; and (b) based on those predictions, use 215002 RBM x procedures to correct, control, 3.3 91 or mitigate the consequences of those abnormal conditions or operations: Loss of associated reference APRM channel:

BWR-3,4,5 2.4.8 - Emergency Procedures I Plan: Knowledge of how 288000 Plant Ventilation x abnormal operating procedures 4.5 92 are used in conjunction with EOP's.

2.2.38 - Equipment Control:

272000 Radiation Monitoring x Knowledge of conditions and 4.5 93 limitations in the facility license.

K1 .02 - Knowledge of the physical connections and/or 245000 Main Turbine cause-effect relationships Generator and Auxiliary x between MAIN TURBINE 2.5 27 Systems GENERATOR AND AUXILIARY SYSTEMS and the following:

Condensate system K4.09 - Knowledge of RHR/LPCI:

TORUS/SUPPRESSION POOL 230000 RHR/LPCI:

Torus/Pool Spray Mode x SPRAY MODE design 3.0 28 feature(s) and/or interlocks which provide for the following:

Spray flow cooling.

K3.02 - Knowledge of the effect that a loss or malfunction of the REACTOR MANUAL 201002 RMCS x CONTROL SYSTEM will have 2.9 29 on following: Rod block monitor:

Plant-Specific K4.05 - Knowledge of RHR/LPCI:

TORUS/SUPPRESSION POOL 219000 RHR/LPCI:

Torus/Pool Cooling Mode x COOLING MODE design 3.0 30 feature(s) and/or interlocks which provide for the following:

Pump minimum flow protection K5.02 - Knowledge of the operational implications of the 234000 Fuel Handling following concepts as they apply Equipment x to FUEL HANDLING 3.1 31 EQUIPMENT: Fuel handling equipment interlocks K6.02 - Knowledge of the effect that a loss or malfunction of the following will have on the ROD 214000 RPIS x POSITION INFORMATION 2.7 32 SYSTEM: Position indication probe

ES-401 5 Form ES-401-1 SSES LOC28 NRC Written Examination Outline Plant Systems - Tier 2 Group 2 K K K K K K A A A System # I Name A2 G Imp. Q#

1 2 3 4 5 6 1 3 4 A 1.24 - Ability to predict and/or monitor changes in parameters associated with operating the 241000 Reactor!Turbine Pressure Regulator x REACTOR!TURBINE 2.6 33 PRESSURE REGULATING SYSTEM controls including:

Main turbine eccentricity A2.01 - Ability to (a) predict the impacts of the following on the RADWASTE; and (b) based on those predictions, use 268000 Radwaste x procedures to correct, control, 2.9 34 or mitigate the consequences of those abnormal conditions or operations: System rupture A3.01 - Ability to monitor automatic operations of the 288000 Plant Ventilation x PLANT VENTILATION 3.8 35 SYSTEMS including:

Isolation/initiation sionals A4.07 - Ability to manually operate and/or monitor in the 204000 RWCU x control room: System 3.1 36 temperature 2.4.31 - Emergency Procedures 201003 Control Rod and I Plan: Knowledge of Drive Mechanism x annunciator alarms, indications, 4.2 37 or response procedures.

K3.06 - Knowledge of the effect that a loss or malfunction of the 290002 Reactor Vessel Internals x REACTOR VESSEL 3.1 38 INTERNALS will have on following: PCIS/NSSSS KIA Category Totals: 1 0 2 2 1 1 1 1/1 1 1 1/2 Group Point Total:

I 12/3

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: SSES LOC28 NRC Date: November 2016 RO SRO-Only Category KIA# Topic IR Q# IR Q#

Knowledge of new and spent fuel movement 2.1.42 3.4 94 procedures.

Knowledge of facility requirements for 2.1.13 3.2 99 controlling vital I controlled access.

1. 2.1.41 Knowledge of the refueling process. 2.8 66 Conduct Knowledge of industrial safety procedures of Operations (such as rotating equipment, electrical, high 2.1.26 3.4 67 temperature, high pressure, caustic, chlorine, oxygen and hydrogen).

Subtotal 2 2 Knowledge of the process for managing 2.2.20 3.8 95 troubleshooting activities.

Knowledge of the process for making 2.2.6 3.6 98 changes to procedures.

Ability to manipulate the console controls as

2. 2.2.2 required to operate the facility between 4.6 68 Equipment shutdown and designated power levels.

Control Knowledge of less than or equal to one hour 2.2.39 Technical Specification action statements for 3.9 69 systems.

Knowledge of the process used to track 2.2.43 3.0 74 inoperable alarms.

Subtotal 3 2 2.3.11 Ability to control radiation releases. 4.3 96 Knowledge of radiation or containment hazards that may arise during normal, 2.3.14 3.8 100 abnormal, or emergency conditions or activities.

Knowledge of radiation exposure limits under 2.3.4 3.2 70 normal or emergency conditions.

3.

Knowledge of radiation or containment Radiation hazards that may arise during normal, Control 2.3.14 3.4 71 abnormal, or emergency conditions or activities.

Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, 2.3.5 2.9 75 I

portable survey instruments, personnel monitoring equipment, etc.

Subtotal 3 2

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Knowledge of EOP implementation hierarchy and coordination with other support 2.4.16 4.4 97 procedures or guidelines such as, operating procedures, AOPs and SAMGs.

4.

Emergency Procedures I Knowledge of the lines of authority during 2.4.37 3.0 72 Plan implementation of the emergency plan.

2.4.17 Knowledge of EOP terms and definitions. 3.9 73 Subtotal 2 1 Tier 3 Point Total 10 7

ES-401 Record of Rejected K/As Form ES-401-4 Randomly Selected KIA Reason for Rejection 295027 High Containment This topic applies to plants with Mark Ill Temperature containments only. The facility has a Mark II 1/ 1 containment.

295011 High Containment This topic applies to plants with Mark Ill Temperature containments only. The facility has a Mark II 1/2 containment.

207000 Isolation (Emergency) This system is not installed at the facility.

2/1 Condenser 209002 HPCS This system is not installed at the facility.

2/1 201004 RSCS This system is no longer installed at the facility.

212 201005 RCIS This system is not installed at the facility.

212 239003 MSIV Leakage Control This system is no longer installed at the facility.

212

The facility has a Mark-II containment, not a Question 57 Mark-Ill.

295024 High Drywell Pressure Randomly resampled KIA 295024 High Drywell EK2.14 - Knowledge of the Pressure EK2.11 Knowledge of the 1/ 1 interrelations between HIGH interrelations between HIGH DRYWELL DRYWELL PRESSURE and the PRESSURE and the following: Drywell spray following: Containment (RHR) logic: Mark-1&11.

pressure: Mark-II I The facility has a Mark-II containment, not a Question 60 Mark-Ill.

295010 High Drywell Pressure Randomly resampled KIA 295010 High Drywell AK2.03 - Knowledge of the Pressure AK2.05 - Knowledge of the 1/ 2 interrelations between HIGH interrelations between HIGH DRYWELL DRYWELL PRESSURE and the PRESSURE and the following: Drywell cooling following: Drywell/containment and ventilation.

differential pressure: Mark-Ill The facility does not have Isolation Question 61 Condensers.

295007 High Reactor Pressure Randomly resampled KIA 295007 High Reactor AK3.01 - Knowledge of the Pressure AK3.03 - Knowledge of the reasons reasons for the following for the following responses as they apply to 1/ 2 responses as they apply to HIGH REACTOR PRESSURE: RCIC operation:

HIGH REACTOR PRESSURE: Plant-Specific.

Isolation condenser operation:

Plant-Specific Question 76 An acceptable question could not be written at the SRO level for the randomly sampled KIA 295030 Low Suppression Pool due to lack of relevant use of Drywell /

Water Level Suppression Chamber differential pressure in EA2.04 -Ability to determine the facility's procedures and Technical and/or interpret the following as Specifications.

1/ 1 they apply to LOW Randomly resampled KIA 295030 Low SUPPRESSION POOL WATER Suppression Pool Water Level EA2.02 -Ability LEVEL: Drywell/ suppression to determine and/or interpret the following as chamber differential pressure:

they apply to LOW SUPPRESSION POOL Mark-1&11 WATER LEVEL: Suppression pool temperature.

Question 84 An acceptable question could not be written at the SRO level for the randomly sampled KIA 295002 Loss of Main due to lack of applicable system limits and Condenser Vacuum precautions related to Loss of Main Condenser 2.1.32 - Ability to explain and Vacuum.

apply all system limits and 1/ 2 Randomly resampled KIA 295002 Loss of Main precautions.

Condenser Vacuum 2.1.7 -Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

Question 88 An acceptable question could not be written at the SRO level for the randomly sampled KIA 211000 SLC due to lack of applicable EOP warnings, 2.4.20 - Knowledge of cautions, and notes related to SLC.

2/ 1 operational implications of EOP Randomly resampled KIA 211000 SLC 2.4.6 -

warnings, cautions, and notes.

Knowledge of EOP mitigation strategies.

Question 94 The randomly sampled KIA is thoroughly and more appropriately tested on the operating 2.1.45 - Ability to identify and exam.

interpret diverse indications to 3

validate the response of another Randomly resampled KIA 2.1.42 - Knowledge indicator. of new and spent fuel movement procedures.

Question 22 An acceptable question could not be written at the RO level for the randomly sampled generic 300000 Instrument Air KIA with the given Tier 2 system.

2.4.41 - Knowledge of the Randomly resampled KIA 300000 Instrument 2/ 1 emergency action level Air 2.4.35 - Knowledge of local auxiliary thresholds and classifications.

operator tasks during an emergency and the resultant operational effects.

Question 26 An acceptable question could not be written at the RO level for the randomly sampled generic 262002 UPS (AC/DC)

KIA with the given Tier 2 system due to lack of 2.2.39 - Knowledge of less than appropriate less than one hour Technical one hour technical specification Specification action statements for UPS.

2/1 action statements for systems.

Randomly resampled KIA 262002 UPS (AC/DC) 2.1.28 - Knowledge of the purpose and function of major system components and controls.

Question 28 An acceptable question could not be written for the randomly sampled without overlapping 230000 RHR/LPCI: Torus/Pool Question 3.

Spray Mode Randomly resampled KIA 230000 RHR/LPCI:

K2.02 - Knowledge of electrical Torus/Pool Spray Mode K4.09 - Knowledge of 212 power supplies to the following:

RHR/LPCI: TORUS/SUPPRESSION POOL Pumps SPRAY MODE design feature(s) and/or interlocks which provide for the following: Spray flow cooling.

Question 37 An acceptable question could not be written ~t the RO level for the randomly sampled generic 201003 Control Rod and Drive KIA. Additionally, the randomly sampled Mechanism generic KIA is already sampled in Question 93.

2.2.38 - Knowledge of 212 Randomly resampled KIA 201003 Control Rod conditions and limitations in the and Drive Mechanism 2.4.31 - Knowledge of facility license.

annunciator alarms, indications, or response procedures.

Question 39 An acceptable question could not be written for the randomly sampled KIA without testing GFE 700000 Generator Voltage and knowledge.

Electric Grid Disturbances Randomly resampled KIA 700000 Generator AK 1.O1 - Knowledge of the Voltage and Electric Grid Disturbances AK1 .02 operational implications of the

- Knowledge of the operational implications of following concepts as they 212 the following concepts as they apply to apply to GENERATOR GENERATOR VOLTAGE AND ELECTRIC VOLTAGE AND ELECTRIC GRID DISTURBANCES and the following:

GRID DISTURBANCES and the Over-excitation.

following: Definition of terms:

volts, watts, amps, VARs, power factor Question 40 An acceptable question could not be written for the randomly sampled without overlapping 295031 Reactor Low Water Question 46.

Level Randomly resampled KIA 295031 Reactor Low EK1 .03 - Knowledge of the Water Level EK1 .02 - Knowledge of the 1I 1 operational implications of the operational implications of the following following concepts as they concepts as they apply to REACTOR LOW apply to REACTOR LOW WATER LEVEL: Natural circulation: Plant-WATER LEVEL: Water level Specific.

effects on reactor power

Question 41 An acceptable question could not be written for the randomly sampled KIA without testing GET 295038 High Off-site Release I GFE knowledge.

Rate Randomly resampled KIA 295038 High Off-site EK1 .01 - Knowledge of the Release Rate EK1 .03 - Knowledge of the 1/ 1 operational implications of the operational implications of the following following concepts as they concepts as they apply to HIGH OFF-SITE apply to HIGH OFF-SITE RELEASE RATE: Meteorological effects on off-RELEASE RA TE: Biological site release.

effects of radioisotope ingestion Question 47 An acceptable question could not be written for the randomly sampled KIA due to lack of 295019 Partial or Complete Service Air isolations related to loss of Loss of Instrument Air Instrument Air at this facility.

AK3.03 - Knowledge of the Randomly resampled KIA 295019 Partial or reasons for the following 1/ 1 Complete Loss of Instrument Air AK3.03 -

responses as they apply to Knowledge of the reasons for the following PARTIAL OR COMPLETE responses as they apply to PARTIAL OR LOSS OF INSTRUMENT AIR: COMPLETE LOSS OF INSTRUMENT AIR:

Service air isolations: Plant-Backup air system supply: Plant-Specific.

Specific Question 59 An acceptable question could not be written for the randomly sampled generic KIA due to lack 295013 High Suppression Pool of procedural guidance regarding Suppression Temperature Pool stratification. Additionally, Suppression AK1 .01 - Knowledge of the Pool temperature concepts are already operational implications of the sampled in Questions 56, 76, and 81.

1/2 following concepts as they Randomly resampled KIA 295014 Inadvertent apply to HIGH SUPPRESSION Reactivity Addition AK1 .05 - Knowledge of the POOL TEMPERATURE: Pool operational implications of the following stratification concepts as they apply to INADVERTENT REACTIVITY ADDITION: Fuel thermal limits.

Question 67 The randomly sampled generic KIA is testing extensively on, and better suited for, the 2.1.31 - Ability to locate control operating exam.

room switches, controls, and indications, and to determine Randomly resampled KIA 2.1.26 - Knowledge 3 that they correctly reflect the of industrial safety procedures (such as rotating desired plant lineup. equipment, electrical, high temperature, high pressure, caustic, chlorine, oxygen and hydrogen).

Question 69 The randomly sampled generic KIA is already sampled on the RO exam in Question 69.

2.2.12 - Knowledge of surveillance procedures. Randomly resampled KIA 2.2.39 - Knowledge 3

of less than or equal to one hour Technical Specification action statements for systems.

Question 70 An acceptable question could not be written for the randomly sampled generic KIA without 2.3.11 - Ability to control overlapping other questions on this exam or radiation releases.

previous 2 NRC exams. Additionally, the randomly sampled generic KIA is already 3 sampled in Question 96.

Randomly resampled KIA 2.3.4 - Knowledge of radiation exposure limits under normal or emergency conditions.