ML18038A748

Final Outlines (Folder 3)

ML18038A748
Person / Time
Site:	Nine Mile Point
Issue date:	12/06/2017
From:	Todd Fish Operations Branch I
To:	Exelon Generation Co
Shared Package
ML17138A089	List: IR 05000410/2017302 ML17156A842 ML17342A568 ML18038A748 ML18038A751
References
U01947
Download: ML18038A748 (25)

Text

Appendix D Scenario Outline Form ES-D-1 Facility: Nine Mile Point Unit 2 Scenario No.: NRC-1 Op-Test No.: LC2 16-1 Examiners: Operators:

Initial Conditions: The plant is operating at approximately 4.5% power with a reactor startup in progress. Narrow range 'C' level transmitter has failed high and CRD-P1 B is out of service due to high pump vibrations.

Turnover: Continue reactor startup and raise power to 8%

Critical Tasks: See page 2 Event Malt. Event Event No. No. Type* Description N/A R-ATC, Continue the reactor startup by withdrawing rods per N2-0P-101 A.

1 SRO N2-0P-101A RD07 C-ATC, Stuck Control Rod 2 SRO N2-0P-30 NM06 I-ATC, IRM D Fails Upscale 3 SRO TS-SRO ARP's, N2-0P-97, T.S. 3.3.1.1 RC10 C-BOP, Inadvertent Initiation of RCIC 4 SRO TS-SRO ARP's, T.S. 3.5.3 IA02A C-BOP, Trip of Instrument Air Compressor A IA04A SRO 5

IA04B N2-S0P-19 RH13A C-BOP, Inadvertent initiation of Division 1 ECCS systems with minimum RH15 SRO flow valve failure.

6 TS-SRO N2-0P-31, T.S. 3.5.1, T.S. 3.6.1.6, T.S. 3.6.2.3, T.S. 3.6.2.4 MT01 C-ATC, Seismic Event causes FWLC failure.

7 FWOB SRO N2-S0P-90, N2-S0P-6 RC12 M (All} RCIC Steam Leak in Reactor Building 8

N2-EOP-RPV, N2-EOP-SC Overrides C-BOP, RCIC Isolation valves fail to close leading to degrading Secondary SRO Containment conditions.

9 N2-EOP-SC, N2-EOP-C2

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

Appendix D Scenario Outline Form ES-D-1 Facility: Nine Mile Point Unit 2 Scenario No.: NRC-2 Op-Test No.: LC2 16-1 Examiners: Operators:

Initial Conditions: The plant is operating at approximately 92% power. It is required to perform a Live Bus Transfer of 2NNS-SWG013 to 2NNS-SWG012. 21AS-C3C, Instrument air compressor 3C is out of service.

Turnover: Perform a Live Bus Transfer of 2NNS-SWG013 to 2NNS-SWG012.

Critical Tasks: See page 2 Event Malf. Event Event No. No. Type* Description N/A N-BOP, Live Bus Transfer of 2NNS-SWG013 to 2NNS-SWG012.

1 SRO N2-0P-718 N/A R-ATC, Raise reactor power to 98%.

2 SRO N2-0P-101D RR52A C-ATC, 'A' RCS FCV fails open.

3 SRO, TS-SRO N2-S0P-08, N2-SOP-101D, ARP's, T.S. 3.4.1 MS20A C-BOP, Gland seal exhaust fan TME-FN 1A trip.

4 SRO N2-0P-25 ED04D C-AII, Loss of NNS-SWG014 switchgear. Restore CRD, and other lost TS-SRO loads with HCU accumulator trouble.

5 N2-S0P-03, SOP-30, SOP-68, SOP-19, SOP-97, T.S. 3.1.5 Overrides M-AII EHC Regulator slow failure causes Reactor Pressure to lower, MS13 crew must scram and shut MSIV's.

6 N2-S0P-23, N2-S0P-101C, N2-EOP-RPV ED02A C-AII Loss of all offsite power with Div II EOG failing to start. Crew will

&B manually start Div II EOG.

7 DG04B N2-S0P-03 RR20 M-AII LOCA in Drywell.

8 N2-EOP-RPV, N2-EOP-PC RH01A( C-AII First RHR pump used for Drywell sprays trips.

9 B)

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

Appendix D Scenario Outline Form ES-D-1 Facility: Nine Mile Point Unit 2 Scenario No.: NRC-3 Op-Test No.: LC2 16-1 Examiners: Operators:

Initial Conditions: The plant is operating at 100% power. It is required to complete N2-0SP-EGS-M@001 for Division I EOG. 2TMB-P1 B, EHC Fluid Pump 1Bis out of service for maintenance.

Turnover: Complete N2-0SP-EGS-M@001 for Division I EOG. Next step to be performed is 8.2.22.

Critical Tasks: See page 2 Event Malf. Event Event No. No. Type* Description N/A N-BOP, Complete N2-0SP-EGS-M@001 for Division I EOG.

1 SRO N2-0SP-EGS-M@001 DG02A TS-SRO Division I EOG lockout trip.

2 T.S. 3.8.1.B RR088 I-ATC, Loss of recirculation flow input to APRM #2.

3 SRO, TS-SRO ARP's, T.S. 3.3.1.1 RD09- R-ATC, Control rod 10-31 scram.

4 10-31 SRO, TS-SRO N2-S0P-08, N2-SOP-101D, T.S. 3.1.3 CW14 C-BOP, RBCLC TCV fails causing a reduction in cooling.

5 SRO N2-S0P-13 FW368 C-BOP, Feed pump trip causes recirculation flow control valve runback.

FW038 ATC, 6 SRO N2-S0P-06, N2-S0P-29 RD09 C-ATC Two additional control rods scram, manual scram required.

7 SRO N2-S0P-08, N2-S0P-101C, N2-EOP-RPV RD17Z M-AII ATWS with a loss of EHC pumps resulting in heat addition to TC15 Suppression Pool.

8 N2-EOP-PC, N2-EOP-C5 SL03 C-AII RRCS 98 Second Timer Failu're.

9 N2-EOP-6.13 RH36/37 C-AII RHR Suppression Pool Cooling Valve Supply breaker trip.

10

• (N)ormal, (R)eactivitv, (l)nstrument, (C)omoonent, (M)aior

Appendix D Scenario Outline Form ES-D-1 Facility: Nine Mile Point Unit 2 Scenario No.: NRC-4 Op-Test No.: LC2 16-1 Examiners: Operators:

Initial Conditions: The plant is operating at 100% power. HPCS is out of service for pump seal replacement.

Turnover: HPCS is out of service for pump seal replacement. Perform 21SC*RV33A Exercise and Position Indication Test per N2-0SP-ISC-M@002, section 8.2 only.

Critical Tasks: See page 2 Event Malf. Event Event No. No. Type* Description N/A N-BOP, Perform 21SC*RV33A Exercise and Position Indication Test.

1 SRO N2-0SP-1SC-M@002 RR43A I-ATC, FWLC Steam Flow Instrument Fails Downscale.

2 SRO N2-S0P-6 RC01 C-BOP, RCIC Turbine Trip Throttle valve trip and reset.

3 (Remote) TS-SRO ARP's, N2-0P-35, T.S. 3.5.1, 3.5.3 RD12A C-ATC CRD Pump Trip P1 A on Motor Electrical Fault.

4 SRO N2-S0P-30 OVR- R-ATC, Inadvertent ADS SRV opening which can be closed.

13S02DI SRO 5 C-BOP 2014 TS-SRO N2-S0P-34, 101D, T.S. 3.5.1, 3.6.2.1 RR20 M-AII LOCA with degraded high pressure injection systems. RPV blowdown. Restore and maintain RPV water level above the MSCRWL with low pressure injection sources.

6 N2-EOP-RPV, N2-EOP-PC, N2-EOP-C2 RH14A I-All Division I LP ECCS fails to automatically initiate.

7 N2-EOP-RPV ADOSF C-AII ADS SRV (2MSS*PSV130) fails to open requiring the crew to open an additional non-ADS SRV to achieve a total of 7 SRV's open.

8 N2-EOP-C2

• (N)ormal, (R)eactivitv, (l)nstrument, (C)omponent, (M)aior

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Nine Mile Point Unit 2 Date of Examination: December 2017 Examination Level: RO Operating Test Number: LC2 16-1 Administrative Topic Type Describe activity to be performed (see Note) Code*

Perform an APRM Gain Adjust Conduct of Operations D,S N2-0SP-NMS-@004 KA 2.1.31 (4.6)

Determine Operator Overtime Availability Conduct of Operations D,R LS-AA-119, KA 2.1.5 (3.9)

Develop a clearance boundary for a Standby Liquid Control Pump Equipment Control N,R OP-CE-109-101 KA2.2.13 (4.1)

Perform RO Actions for an Injured and Contaminated D,S Person Emergency Procedures/Plan OP-NM-106-300 KA2.4.12 (4.0)

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

• Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (:5 3 for ROs; s; 4 for SROs & RO retakes)

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

(P)revious 2 exams (:5 1; randomly selected)

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Nine Mile Point Unit 2 Date of Examination: December 2017 Examination Level: SRO Operating Test Number: LC2 16-1 Administrative Topic Type Describe activity to be performed (see Note) Code*

Single Loop Thermal Limit Review Conduct of Operations D,R Technical Specifications, KA 2.1.7 (4.7)

Determine Operator Overtime Availability Conduct of Operations D,R LS-AA-119, KA 2.1.5 (3.9)

Review a clearance boundary for a Standby Liquid Control Pump and determine Technical Specification N,R Equipment Control impact.

OP-CE-109-101, KIA 2.2.13 (4.3)

Offsite Dose Calculation Manual (ODCM) Assessment D,R for Inoperable Equipment Radiation Control N2-0P-42, ODCM, KA 2.3.15 (3.1)

Determine NRG and On-Site Notification Requirements Emergency Procedures/Plan D,R EPIP-EPP-02-EAL, LS-AA-1400, OP-AA-106-101, KA 2.4.30 (4.1)

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

• 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 (2: 1)

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

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Nine Mile Point Unit 2 Date of Examination: December 2017 Exam Level: RO/SRO-I Operating Test No.: LC2 16-1 NRC Control Room Systems* (8 for RO); (7 for SRO-I)

System I JPM Title Type Code* Safety Function

a. Swap Mechanical Vacuum Pumps N,L,S 2 KIA 256000 A4.13 (3.3/3.4) N2-0P-9

b. Place SWP*RE23A in service N,S 9 KIA 272000 A4.02 (3.0/3.0) N2-0P-79

c. Depressurizing the RPV to the Main Condenser. {Alternate Path)

A,D,L,S 3 KIA 239001 A4.09 (3.9/3.9) N2-EOP-6.18

d. HPCS Pump Run Following Maintenance. (Alternate Path) A,N,S 4

KIA 209002 A4.01 (3.7/3.7) N2-0P-33

e. Determine containment water level.

D,L,S 5 KIA 295029 EA2.03 (3.4/3.5) N2-EOP-6.23

f. Transfer House Loads from Normal Station Service to the Reserve Station Transformers. D,S 6 KIA 262001 A4.01 (3.4/3.7) N2-0P-71 A

g. Manual Actions for Group 8 Isolation Failure on Valid RPS Signal.

(Alternate Path) A,D,EN,S 7 KIA 212000 A2.09 (4.1/4.3) N2-SOP-83

h. Restore 2SWP*MOV50B from Inadvertent Closure (RO Only) D,P,S 8

KIA 400000 A4.01 (3.1/3.0) N2-S0P-11 (NRG 2014)

In-Plant Systems* (3 for RO); (3 for SRO-I)

i. Transfer to 2VBA*UPS2C Maintenance and Shutdown N 6 KIA 262002 A3.01 (2.8/3.1) N2-0P-71 D

j. Diesel Fire Pump Local Start (Alternate Path) A,D 8 KIA 286000 A4.06 (3.4/3.4) N2-0P-43

k. Vent Scram Air Header, ARI Function Not Available.

D,E,R 1 KIA 295037 EA1 .05 (3.9/4.0) N2-EOP-6.14

• All RO and Sft0-1 control room (and in-plant) systems must be different and serve different safety t1;mctions; all 5 SRc;:>-U systems must serve different safety functions; in-plant systems and functions may overlap tho~e tested in the control room.

• i c ..

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

ES-401 Written Examination Outline Form ES-401-1 Facility: Nine Mile Point Unit 2 Date of Exam: 2017 NRC RO K/A 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 3 3 3 4 4 20 3 4 7 Emergency

& 2 1 1 1 1 2 1 7 1 2 3 Plant Evolutions Tier Totals 4 4 4 4 6 5 27 4 6 10 1 2 2 2 3 3 3 1 2 2 3 3 26 3 2 5 2.

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

3. Generic Knowledge & Abilities 10 7 Categories 2 3 2 3 1 2 2 2 Note: 1. Ensure that at least two topics from every applicable K/A 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 K/A is replaced by a K/A 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 and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to section 0.1.b of ES-401 for guidance regarding the elimination of inappropriate K/A 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 KAs 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 K/A categories.

7.* The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section 0.1.b of ES-401 for the applicable K/A's

8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings (IR) for the applicable license level, and the point totals(#) for each system and category. Enter the group and tier totals for each category in the table above. If fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #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 K/A numbers, descriptions, IRs, and point totals(#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10CFR55.43.

ES-401 2 Form ES-401-1 NMP2 2017 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE #/Name Safety Function K1 K2 K3 A1 A2 G KIA Topic(s) Imp. Q#

AA2.01 - Ability to determine and/or interpret the following as they apply to 295019 Partial or Complete X PARTIAL OR COMPLETE LOSS OF 3.6 76 Loss of Instrument Air/ 8 INSTRUMENT AIR: Instrument air system pressure EA2.04 - Ability to determine and/or 295038 High Off-site Release interpret the following as they apply to X 4.5 77 Rate/ 9 HIGH OFF-SITE RELEASE RATE:

Source of off-site release AA2.03 - Ability to determine and/or 295021 Loss of Shutdown interpret the following as they apply to X 3.5 78 Cooling/ 4 LOSS OF SHUTDOWN COOLlhlG:

Reactor water level 2.2.25 Equipment Control: Knowledge 295025 High Reactor Pressure/ of the bases in Technical Specifications X 4.2 79 3 for limiting conditions for operations and safetv limits.

2.4.41 Emergency Procedures/ Plan:

295003 Partial or Complete X Knowledge of the emergency action 4.6 80 Loss of AC Power / 6 level thresholds and classifications.

295001 Partial or Complete 2.1.25 - Conduct of Operations: Ability Loss of Forced Core Flow X to interpret reference materials. such as 4.2 81 Circulation / 1 & 4 oraohs, curves, tables, etc.

2.1.7 - Conduct of Operation: Ability to evaluate plant performance and make 295031 Reactor Low Water X operational judgments based on 4.7 82 Level/ 2 operating characteristics, reactor behavior. and instrument interpretation.

AK1 .01 - Knowledge of the operational implications of the following concepts as 295003 Partial or Complete X they apply to PARTIAL OR COMPLETE 2.7 39 Loss of AC Power I 6 LOSS OF A.C. POWER: Effect of battery discharge rate on capacity AK1 .01 - Knowledge of the operational implications of the following concepts as they apply to GENERATOR VOLTAGE 700000 Generator Voltage and X AND ELECTRIC GRID 3.3 40 Electric Grid Disturbances DISTURBANCES and the following:

Definition of terms: volts, watts, amps, VARs, oower factor AK1 .02 - Knowledge of the operational implications of the following concepts as 600000 Plant Fire On-site/ 8 X 2.9 41 they apply to Plant Fire On Site: Fire Fightinq EK2.06 - Knowledge of the interrelations 295024 High Drywell Pressure/ between HIGH DRYWELL PRESSURE X 3.9 42 5 and the following: Emergency generators EK2.08 - Knowledge of the interrelations 295031 Reactor Low Water between REACTOR LOW WATER X 4.2 43 Level/ 2 LEVEL and the following: Automatic depressurization system EK2.05 - Knowledge of the interrelations 295025 High Reactor Pressure/ between HIGH REACTOR PRESSURE X 4.1 44 3 and the following: Safety/relief valves:

Plant-Specific AK3.03 - Knowledge of the reasons for 295006 SCRAM / 1 X the following responses as they apply to 3.8 45 SCRAM: Reactor pressure response

ES-401 2 Form ES-401-1 NMP2 2017 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE #/Name Safety Function K1 K2 K3 A1 A2 G KIA Topic(s) Imp. Q#

EK3.06 - Knowledge of the reasons for 295030 Low Suppression Pool the following responses as they apply to X 3.6 46 Water Level / 5 LOW SUPPRESSION POOL WATER LEVEL: Reactor SCRAM AK3.03 - Knowledge of the reasons for 295016 Control Room the following responses as they apply to X 3.5 47 Abandonment/ 7 CONTROL ROOM ABANDONMENT:

Disablina control room controls AA 1.01 - Ability to operate and/or 295021 Loss of Shutdown monitor the following as they apply to X 3.4 48 Cooling/ 4 LOSS OF SHUTDOWN COOLING:

Reactor water cleanup system AA 1.06 - Ability to operate and/or monitor the following as they apply to 295023 Refueling Accidents/ 8 X 3.3 49 REFUELING ACCIDENTS: Neutron monitoring AA 1.01 - Ability to operate and/or monitor the following as they apply to 295004 Partial or Complete X PARTIAL OR COMPLETE LOSS OF 3.3 50 Loss of DC Power I 6 D.C. POWER: D.C. electrical distribution systems AA2.01 - Ability to determine and/or 295005 Main Turbine Generator interpret the following as they apply to X 2.6 51 Trip/ 3 MAIN TURBINE GENERATOR TRIP:

Turbine speed AA2.04 - Ability to determine and/or interpret the following as they apply to 295018 Partial or Complete X PARTIAL OR COMPLETE LOSS OF 2.9 52 Loss of CCW / 8 COMPONENT COOLING WATER:

System flow AA2.01 - 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 3.5 53 Circulation / 1 & 4 FORCED CORE FLOW CIRCULATION:

Power/flow map 2.1.19 - Conduct of Operations: Ability 295038 High Off-site Release X to use plant computers to evaluate 3.9 54 Rate/ 9 system or component status.

295037 SCRAM Condition 2.4.46 - Emergency Procedures/ Plan:

Present and Reactor Power Ability to verify that the alarms are X 4.2 55 Above APRM Downscale or consistent with the plant conditions.

Unknown/ 1 2.1.28 - Conduct of Operations:

295019 Partial or Complete Knowledge of the purpose and function X 4.1 56 Loss of Instrument Air/ 8 of major system components and controls.

2.4.31 - Emergency Procedures/ Plan:

295026 Suppression Pool High X Knowledge of annunciator alarms, 4.2 57 Water Temperature I 5 indications, or response procedures.

EA2.04 - Ability to determine and/or 295028 High Drywell interpret the following as they apply to X 4.1 58 Temperature I 5 HIGH DRYWELL TEMPERATURE:

Drvwell pressure KIA Category Totals: 3 3 3 3 4/3 4/4 Group Point Total:

I 20/7

ES-401 3 Form ES-401-1 NMP2 2017 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 EAPE #/Name Safety Function K1 K2 K3 A1 A2 G KIA Topic(s) Imp. Q#

AA2.01 - Ability to determine and/or interpret the following as they apply to 295013 High Suppression Pool X HIGH SUPPRESSION POOL 4.0 83 Temperature/ 5 TEMPERATURE: Suppression pool temperature 2.4.8 - Emergency Procedures/ Plan:

295029 High Suppression Pool Knowledge of how abnormal operating X 4.5 84 Water Level / 5 procedures are used in conjunction with EOPs.

295035 Secondary 2.1.19 - Conduct of Operations: Ability to Containment High Differential X use plant computers to evaluate system 3.8 85 Pressure/ 5 or component status.

AK1 .04 - Knowledge of the operational implications of the following concepts as 295002 Loss of Main X they apply to LOSS OF MAIN 3.0 59 Condenser Vacuum / 3 CONDENSER VACUUM: Increased offqas flow AK2.04 - Knowledge of the interrelations 295008 High Reactor Water between HIGH REACTOR WATER X 3.1 60 Level/ 2 LEVEL and the following: PCIS/NSSSS:

Plant-Specific AK3.02 - Knowledge of the reasons for 295014 Inadvertent Reactivity the following responses as they apply to X 3.7 61 Addition/ 1 INADVERTENT REACTIVITY ADDITION: Control rod blocks AA 1.05 - Ability to operate and/or monitor the following as they apply to 295007 High Reactor Pressure X HIGH REACTOR PRESSURE: 3.7 62

/3 Reactor/turbine pressure regulating system EA2.03 - Ability to determine and/or 295033 High Secondary interpret the following as they apply to Containment Area Radiation X HIGH SECONDARY CONTAINMENT 3.7 63 Levels/ 9 AREA RADIATION LEVELS: Cause of high area radiation 295035 Secondary 2.2.40 - Equipment Control: Ability to Containment High Differential X apply technical specifications for a 3.4 64 Pressure/ 5 svstem.

EA2.01 - Ability to determine and/or 295032 High Secondary interpret the following as they apply to Containment Area Temperature X HIGH SECONDARY CONTAINMENT 3.8 65

/5 AREA TEMPERATURE: Area temperature KIA Category Totals: 1 1 1 1 2/1 1/2 Group Point Total:

I 7/3

ES-401 4 Form ES-401-1 NMP2 2017 NRC Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A Imp System # / Name A2 G Q#

1 2 3 4 5 6 1 3 4

ES-401 4 Form ES-401-1 NMP2 2017 NRC Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A Imp System # / Name A2 G Q#

1 2 3 4 5 6 1 3 4 A2.16 - Ability to (a) predict the impacts of the following on the REACTOR PROTECTION SYSTEM; and (b) based on those predictions, use 212000 RPS X 4.1 86 procedures to correct, control. or mitigate the consequences of those abnormal conditions or operations: Changing mode switch position A2.05 - Ability to (a) predict the impacts of the following on the HIGH PRESSURE CORE SPRAY SYSTEM (HPCS); and (b) based on those predictions, 209002 HPCS X use procedures to correct, 2.9 87 control, or mitigate the consequences of those abnormal conditions or operations: D.C. electrical failure: BWR-5,6 2.2.37 - Equipment Control:

400000 Component Cooling Ability to determine operability X 4.6 88 Water and / or availability of safety related equipment.

2.1.23 - Conduct of Operations:

Ability to perform specific system 211000 SLC X and integrated plant procedures 4.4 89 during all modes of plant operation.

A2.D4 - Ability to (a) predict the impacts of the following on the SOURCE RANGE MONITOR (SRM) SYSTEM; and (b) based 215004 Source Range on those predictions, use X 3.7 90 Monitor procedures to correct. control, or mitigate the consequences of those abnormal conditions or operations: Upscale and downscale trips K1 .06 - Knowledge of the physical connections and/or cause-effect relationships 239002 SRVs X between RELIEF/SAFETY 3.4 1 VALVES and the following:

Drywell instrument air/ drywell pneumatics: Plant-Specific K1 .07 - Knowledge of the physical connections and/or cause-effect relationships 264000 EDGs X between EMERGENCY 3.9 2 GENERATORS (DIESEUJET) and the following: Emergency core coolino svstems K2.01 - Knowledge of electrical 212000 RPS X power supplies to the following: 3.2 3 RPS motor-generator sets K2.02 - Knowledge of electrical power supplies to the following:

209002 HPCS X 2.8 4 Valve electrical power: BWR-5,6

ES-401 4 Form ES-401-1 NMP2 2017 NRC Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A Imp System # / Name A2 G Q#

1 2 3 4 5 6 1 3 4 K3.01 - Knowledge of the effect that a loss or malfunction of the 263000 DC Electrical D.C. ELECTRICAL X 3.4 5 Distribution DISTRIBUTION will have on following: Emergency generators: Plant-Specific K3.19 - Knowledge of the effect that a loss or malfunction of the PRIMARY CONTAINMENT 223002 PCIS/Nuclear Steam ISOLATION X 2.8 6 Supply Shutoff SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF will have on following: Containment atmosphere sampling.

K4.10 - Knowledge of STANDBY LIQUID CONTROL SYSTEM design feature(s) 211000 SLC X 2.8 7 and/or interlocks which provide for the following: Over pressure protection K4.01 - Knowledge of INTERMEDIATE RANGE MONITOR (IRM) SYSTEM 215003 IRM X 3.7 8 design feature(s) and/or interlocks which provide for the following: Rod withdrawal blocks K5.01 - Knowledge of the operational implications of the 300000 Instrument Air X following concepts as they apply 2.5 9 to the INSTRUMENT AIR SYSTEM: Air compressors K5.01 - Knowledge of the operational implications of the following concepts as they apply 218000 ADS X 3.8 10 to AUTOMATIC DE PRESSURIZATION SYSTEM: ADS loqic operation K6.01 - Knowledge of the effect that a loss or malfunction of the 209001 LPCS X following will have on the LOW 3.4 11 PRESSURE CORE SPRAY SYSTEM: A.C. power K6.11 - Knowledge of the effect that a loss or malfunction of the 203000 RHR/LPCI: Injection X following will have on the 4.1 12 Mode RHR/LPCI: INJECTION MODE (PLANT SPECIFIC): ADS K6.02 - Knowledge of the effect that a loss or malfunction of the following will have on the 262002 UPS (AC/DC) X 2.8 13 UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.): D.C.

electrical power A 1.02 - Ability to predict and/ or monitor changes in parameters 400000 Component Cooling X associated with operating the 2.8 14 Water CCWS controls including: CCW temperature

ES-401 4 Form ES-401-1 NMP2 2017 NRC Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A Imp System # / Name A2 G Q#

1 2 3 4 5 6 1 3 4 A2.08 - Ability to (a) predict the impacts of the following on the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE); and (b) 205000 Shutdown Cooling X based on those predictions, use 3.3 15 procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of heat exchanoer coolino A2.01 - Ability to (a) predict the impacts of the following on the REACTOR WATER LEVEL CONTROL SYSTEM; and (b) 259002 Reactor Water Level based on those predictions, use X 3.3 16 Control procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of any number of main steam flow inputs A3.04 - Ability to monitor automatic operations of the 217000 RCIC X REACTOR CORE ISOLATION 3.6 17 COOLING SYSTEM (RCIC) includinq: System flow A3.04 - Ability to monitor automatic operations of the 215004 Source Range X SOURCE RANGE MONITOR 3.6 18 Monitor (SRM) SYSTEM including:

Control rod block status A4.03 - Ability to manually 261000 SGTS X operate and/or monitor in the 3.0 19 control room: Fan A4.03 - Ability to manually operate and/or monitor in the 215005 APRM / LPRM X control room: APRM back panel 3.2 20 switches, meters and indicating lights 2.2.12 - Equipment Control:

262001 AC Electrical X Knowledge of surveillance 3.7 21 Distribution procedures.

2.4.20 - Emergency Procedures 223002 PCIS/Nuclear Steam / Plan: Knowledge of operational X 3.8 22 Supply Shutoff implications of EOP warnings, cautions, and notes.

A4.01 - Ability to manually 205000 Shutdown Cooling X operate and/or monitor in the 3.7 23 control room: SDC/RHR pumps 2.1.25 - Conduct of Operations:

203000 RHR/LPCI: Injection Ability to interpret reference X 3.9 24 Mode materials, such as graphs, curves, tables, etc.

K5.02 - Knowledge of the operational implications of the following concepts as they apply 212000 RPS X 3.3 25 to REACTOR PROTECTION SYSTEM: Specific logic arranqements

ES-401 4 Form ES-401-1 NMP2 2017 NRC Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A Imp System # / Name A2 G Q#

1 2 3 4 5 6 1 3 4 K4.03 - Knowledge of AUTOMATIC DEPRESSURIZATION SYSTEM 218000 ADS X 3.8 26 design feature(s) and/or interlocks which provide for the followinq: ADS loqic control KIA Category Totals: 2 2 2 3 3 3 1 2/3 2 3 3/2 Group Point Total:

I 26/5

ES-401 5 Form ES-401-1 NMP2 2017 NRC Written Examination Outline Plant Systems - Tier 2 Group 2 K K K K K K A A A Q System #/Name A2 G Imp.

1 2 3 4 5 6 1 3 4 #

ES-401 5 Form ES-401-1 NMP2 2017 NRC Written Examination Outline Plant Systems - Tier 2 Group 2 K K K K K K A A A Q System # I Name A2 G Imp.

1 2 3 4 5 6 1 3 4 #

A2.08 - Ability to (a) predict the impacts of the following on the REACTOR WATER CLEANUP SYSTEM: and (b) based on those predictions, use 204000 RWCU X 3.1 91 procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: RWCU pump seal failure

2. 1.32 - Conduct of Operations:

201006 RWM X Ability to explain and apply 4.0 92 system limits and precautions.

2.4. 11 - Emergency Procedures 286000 Fire Protection X / Plan: Knowledge of abnormal 4.2 93 condition procedures.

K1 .09 - Knowledge of the physical connections and/or 290001 Secondary cause-effect relationships X 2.9 27 Containment between SECONDARY CONTAINMENT and the followinq: Plant air svstems K2.01 - Knowledge of electrical 215002 RBM X power supplies to the following: 2.5 28 RBM channels: BWR-3,4,5 K3.04 - Knowledge of the effect that a loss or malfunction of the 290003 Control Room X CONTROL ROOM HVAC will 2.8 29 HVAC have on following: Control room pressure K4.10 - Knowledge of MAIN AND REHEAT STEAM SYSTEM design feature(s) 239001 Main and Reheat X and/or interlocks which provide 2.9 30 Steam for the following: Moisture removal from steam lines prior to admitting steam K5.03 - Knowledge of the operational implications of the following concepts as they apply 202001 Recirculation X 2.7 31 to RECIRCULATION SYSTEM:

Pump/motor cooling: Plant-Specific K6.02 - Knowledge of the effect that a loss or malfunction of the 216000 Nuclear Boiler following will have on the X 2.8 32 Instrumentation NUCLEAR BOILER INSTRUMENTATION: D.C.

electrical distribution A 1.09 - Ability to predict and/or monitor changes in parameters 256000 Reactor associated with operating the X 3.1 33 Condensate REACTOR CONDENSATE SYSTEM controls including:

Feedwater temperature

ES-401 5 Form ES-401-1 NMP2 2017 NRC Written Examination Outline Plant Systems - Tier 2 Group 2 K K K K K K A A A Q System # I Name A2 G Imp.

1 2 3 4 5 6 1 3 4 #

A2.10 - Ability to (a) predict the impacts of the following on the REACTOR/TURBINE PRESSURE REGULATING SYSTEM; and (b} based on 241000 Reactor/Turbine X those predictions, use 3.1 34 Pressure Regulator procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of stator water cooling: Plant-Specific A3.02 - Ability to monitor automatic operations of the 202002 Recirculation Flow X RECIRCULATION FLOW 3.4 35 Control CONTROL SYSTEM including:

Liahts and alarms A4.01 - Ability to manually 230000 RHR/LPCI:

X operate and/or monitor in the 3.7 36 Torus/Pool Spray Mode control room: Pumps 2.4.21 - Emergency Procedures

/ Plan: Knowledge of the parameters and logic used to assess the status of safety 226001 RHR/LPCI: functions, such as reactivity X 4.0 37 Containment Spray Mode control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.

A3.01 - Ability to monitor automatic operations of the 272000 Radiation X RADIATION MONITORING 3.8 38 Monitoring SYSTEM including: Main steam isolation indications KIA Category Totals: 1 1 1 1 1 1 1 1/1 2 1 1/2 Group Point Total:

I 12/3

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: NMP2 2017 NRG Date: 05/24/16 RO SRO-Only Category KIA# Topic IR Q# IR Q#

Knowledge of primary and secondary plant 2.1.34 3.5 94 chemistry limits.

Knowledge of criteria or conditions that

1. 2.1.14 require plant-wide announcements, such as 3.1 66 Conduct pump starts, reactor trips, mode changes, etc.

of Operations Ability to direct personnel activities inside the 2.1.9 2.9 67 control room.

Subtotal 2 1 Ability to recognize system parameters that 2.2.42 are entry-level conditions for Technical 4.6 95 Specifications.

Knowledge of the process for making 2.2.6 3.6 99 chanqes to procedures.

Ability to analyze the effect of maintenance

2. activities, such as degraded power sources, 2.2.36 3.1 68 Equipment on the status of limiting conditions for Control operations.

Knowledge of tagging and clearance 2.2.13 4.1 69 procedures.

Knowledge of less than or equal to one hour 2.2.39 Technical Specification action statements for 3.9 74 systems.

Subtotal 3 2 Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, 2.3.15 3.1 96 portable survey instruments, personnel monitoring equipment, etc.

Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, 2.3.13 3.8 100

3. containment entry requirements, fuel handling Radiation responsibilities, access to locked high Control radiation areas, aligning filters, etc.

2.3.11 Ability to control radiation releases. 3.8 70 Knowledge of radiation exposure limits under 2.3.4 3.2 71 normal or emergency conditions.

Subtotal 2 2

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Knowledge of EOP entry conditions and 2.4.1 4.8 97 immediate action steps.

2.4.18 Knowledge of the specific bases for EOPs. 4.0 98 4.

Emergency 2.4.6 Knowledge of EOP mitigation strategies. 3.7 72 Procedures /

Plan Knowledge of procedures relating to a 2.4.28 3.2 73 security event.

2.4.18 Knowledge of the specific bases for EOPs. 3.3 75 Subtotal 3 2 Tier 3 Point Total 10 7

ES-401 Record of Rejected K/As Form ES-401-4 Tier/ Randomly Selected KIA Reason for Rejection Group The systematic and random sampling process utilized the pre-approved Nine Mile Point Unit 2 KIA suppression list.

The following KlAs were rejected followinq the svstematic and random samplinq process:

Question 80 An acceptable question could not be developed at the SRO level without testing minutia due to 295003 Partial or Complete a lack of appropriate alarms.

Loss of AC Power Randomly re-selected KIA 295003 Partial or 1/ 1 2.4.31 - Knowledge of Complete Loss of AC Power 2.4.41 -

annunciator alarms, indications, Knowledge of the emergency action level or response procedures. thresholds and classifications.

Question 82 An acceptable question could not be developed at the SRO level without testing minutia due to 295031 Reactor Low Water a lack of appropriate alarms.

Level Randomly re-selected KIA 295031 Reactor Low 2.4.45 - Ability to prioritize and Water Level 2.1. 7 - Ability to evaluate plant 1/ 1 interpret the significance of performance and make operational judgments each annunciator or alarm.

based on operating characteristics, reactor behavior, and instrument interpretation.

Question 89 An acceptable question could not be developed at the SRO level due to lack of RO-specific 211000 SLC tasks performed outside the Main Control Room 2.4.34 - Knowledge of RO tasks related to SLC.

2/ 1 performed outside the main Randomly re-selected KIA 211000 SLC 2.1.23 -

control room during an Ability to perform specific system and integrated emergency and the resultant plant procedures during all modes of plant operational effects.

operation.

Question 92 The randomly sampled generic KIA is also sampled on Question 37 and does not fit well 201006 RWM with the RWM system.

2.4.21 - Knowledge of the Randomly re-selected KIA 201006 RWM 2.1.32 parameters and logic used to

- Ability to explain and apply system limits and assess the status of safety precautions.

2/2 functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.

Question 99 The randomly sampled generic KIA is already tested on the SRO exam on Question 88.

2.2.37 - Ability to determine 3 operability and / or availability of Randomly re-selected KIA 2.2.6 - Knowledge of safety related equipment. the process for making changes to procedures.

Question 1 An acceptable question could not be developed for the randomly sampled KIA because of 239002 SRVs limited and simplistic SRV indication on SPDS.

K1 .02 - Knowledge of the Randomly re-selected KIA 239002 SRVs K1 .06 physical connections and/or

- Knowledge of the physical connections and/or 2I 1 cause-effect relationships cause-effect relationships between between RELIEF/SAFETY RELIEF/SAFETY VALVES and the following:

VALVES and the following:

Drywell instrument air/ drywell pneumatics:

SPDS/ERIS/CRI DS/GDS:

Plant-Specific.

Plant-Specific Question 6 An acceptable question could not be developed for the randomly sampled KIA without testing 223002 PCIS/Nuclear Steam primarily GFES level knowledge.

Supply Shutoff Randomly re-selected KIA 223002 K3.02 - Knowledge of the effect PCIS/Nuclear Steam Supply Shutoff K3.19 -

that a loss or malfunction of the Knowledge of the effect that a loss or 2I 1 PRIMARY CONTAINMENT malfunction of the PRIMARY CONTAINMENT ISOLATION ISOLATION SYSTEM/NUCLEAR STEAM SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF will have on following:

SUPPLY SHUT-OFF will have Containment atmosphere sampling.

on following: Fuel cladding temperature

Question 7 Core plate D/P indication at NMP2 does not use any part of SLC system.

211000 SLC Randomly re-selected KIA 211000 SLC K4.10 -

K4.06 - Knowledge of Knowledge of STANDBY LIQUID CONTROL STANDBY LIQUID CONTROL 2I1 SYSTEM design feature(s) and/or interlocks SYSTEM design feature(s) which provide for the following: Over pressure and/or interlocks which provide protection.

for the following: Core plate differential pressure indication Question 25 An acceptable question could not be developed for the randomly sampled KIA without testing 212000 RPS primarily GFES level knowledge.

K5.01 - Knowledge of the Randomly re-selected KIA 212000 RPS K5.02 -

operational implications of the 2I 1 Knowledge of the operational implications of the following concepts as they following concepts as they apply to REACTOR apply to REACTOR PROTECTION SYSTEM: Specific logic PROTECTION SYSTEM: Fuel arrangements.

thermal time constant Question 46 An acceptable question could not be developed for the randomly sampled KIA without testing 295030 Low Suppression Pool primarily GFES level knowledge. Additionally, Water Level NPSH considerations for ECCS pumps are EK3.07 - Knowledge of the already tested in a more operationally relevant reasons for the following way in Question 24.

responses as they apply to 1/ 1 Randomly re-selected KIA 295030 Low LOW SUPPRESSION POOL Suppression Pool Water Level EK3.06 -

WATER LEVEL: NPSH Knowledge of the reasons for the following considerations for ECCS pumps responses as they apply to LOW SUPPRESSION POOL WATER LEVEL:

Reactor SCRAM.

Question 52 An acceptable question could not be developed without testing very similar concepts as those 295018 Partial or Complete already tested in Question 14.

Loss of CCW Randomly re-selected KIA 295018 Partial or AA2.02 - Ability to determine Complete Loss of CCW AA2.04 -Ability to and/or interpret the following as 1/ 1 determine and/or interpret the following as they they apply to PARTIAL OR apply to PARTIAL OR COMPLETE LOSS OF COMPLETE LOSS OF COMPONENT COOLING WATER: System COMPONENT COOLING flow.

WATER: Cooling water temperature

Question 56 An acceptable question could not be developed for the randomly sampled generic KIA because 295019 Partial or Complete N2-SOP-19, Loss of Instrument Air, does not Loss of Instrument Air have any immediate operator actions.

2.4.49 - Ability to perform 1/ 1 Randomly re-selected KIA 295019 Partial or without reference to procedures Complete Loss of Instrument Air 2.1.28 -

those actions that require Knowledge of the purpose and function of major immediate operation of system system components and controls.

Question 64 An acceptable question could not be developed for the randomly sampled evolution without 295035 Secondary overlapping Question 85.

Containment High Differential Pressure Randomly re-selected KIA 295010 High Drywell 1/ 2 Pressure 2.2.40 - Ability to apply technical 2.2.40 - Ability to apply specifications for a system.

technical specifications for a system.

Question 66 An acceptable RO question could not be .

developed for the randomly sampled generic 2.1.14 - Knowledge of KIA and this topic is already tested adequately conservative decision making on the Operating exam.

practices.

3 Randomly re-selected KIA 2.1.14 - Knowledge of criteria or conditions that require plant-wide announcements, such as pump starts, reactor trips, mode changes, etc.

Question 79 An acceptable SRO question could not be developed for the randomly sampled generic 295025 High Reactor Pressure KIA without overlapping the Operating exam.

2.1.31 - Ability to locate control Randomly re-selected KIA 295025 High 1/ 1 room switches, controls, and Reactor Pressure 2.2.25 - Knowledge of the indications, and to determine bases in Technical Specifications for limiting that they correctly reflect the conditions for operations and safety limits.

desired plant lineup.