ML14350A158

Initial Exam 2014-301 Final Administrative Documents

ML14350A158
Person / Time
Site:	Brunswick
Issue date:	12/16/2014
From:	NRC/RGN-II
To:	Progress Energy Carolinas
Shared Package
ML14350A180	List: ML14350A124 ML14350A125 ML14350A131 ML14350A134 ML14350A137 ML14350A155 ML14350A158 ML14350A161 ML14350A168 ML14350A173
References
50-324/14-301, 50-325/14-301 50-324/OL-14, 50-325/OL-14
Download: ML14350A158 (55)

Text

ES-201, Page 24 of 27ES-201Examination Preparation Checklist Form ES-201-1 Facility: Date of Examination: Examinations Developed by: Facility / NRC (circle one)

TargetDate*Task Description (Reference)

Chief Examiner's Initials-1801.Examination administration date confirmed (C.1.a; C.2.a and b)-1202.NRC examiners and facility contact assigned (C.1.d; C.2.e)-1203.Facility contact briefed on security and other requirements (C.2.c)-1204.Corporate notificat ion letter sent (C.2.d)[-90][5.Reference material due (C.1.e; C.3.c; Attachment 2)]

l{-75}l6.Integrated examinati on outline(s) due, including Forms ES-201-2, ES-201-3,lES-301-1, ES-301-2, ES-301-5, ES-D-1's, ES-401-1/2, ES-401-3, and lES-401-4, as applicable (C.1.e and f; C.3.d) l{-70}l{7.Examination outline(s) reviewed by NRC and feedback provided to facility llicensee (C.2.h; C.3.e)}

l{-45}l8.Proposed examinations (including written, walk-through JPMs, and lscenarios, as applicable), supporting documentation (including Forms lES-301-3, ES-301-4, ES-301-5, ES-301-6, and ES-401-6), and reference lmaterials due (C.1.e, f, g and h; C.3.d)-309.Preliminary license applications (NRC Form 398's) due (C.1.l; C.2.g; lES-202)-1410.Final license applications due and Form ES-201-4 prepared (C.1.l; C.2.i; lES-202)-1411.Examination approved by NRC supervisor for facility licensee review (C.2.h; C.3.f)-1412.Examinations reviewed with facility licensee (C.1.j; C.2.f and h; C.3.g)-713.Written examinations and operating tests approved by NRC supervisor (C.2.i; C.3.h)-714.Final applications reviewed; 1 or 2 (if >10) applications audited to confirm lqualifications / eligibility; and examination approval and waiver letters sent l(C.2.i; Attachment 4; ES-202, C.2.e; ES-204) l-715.Proctoring/written exam administration guidelines reviewedwith facility licensee (C.3.k)-716.Approved scenarios, job per formance measures, and questions distributed to NRC examiners (C.3.i)* Target dates are generally based on facility-prepared examinations and are keyed to the examination date lidentified in the corporate notification letter. They are for planning purposes and may be adjusted on a case-by-case basis in coordination with the facility licensee.[Applies only] {Does not apply} to examinations prepared by the NRC.

l

ES-401 Written Examination Review Worksheet Form ES-401-9 Q# 1. LOK (F/H) 2. LOD (1-5) 3. Psychometric Flaws

4. Job Content Flaws

5. Other 6. B/M/N 7. U/E/S 8. Explanation Stem Focus Cues T/F Cred. Dist. Partial Job-Link Minutia #/ units Back-ward Q= K/A SRO Only RO Three of the five preliminary submittal RO test items were PRELIMINARILY determined to be unacceptable IAW NUREG 1021 for the following reasons:

Cred Dist: Q#

s 4 & 5 K/A mismatch: Q#

s 3 , 4, & 5 LOD=1: Q#

s 4 SRO Five of the five preliminary submittal SRO test items were PRELIMINARILY determined to be unacceptable IAW NUREG 1021for the following reasons:

Cred Dist: Q#s 7 SRO-only: Q#s 6, 7, 8 , 9 & 10 Q=K/A: Q#s 6 Instructions

[Refer to Section D of ES-401 and Appendix B for additional information regarding each of the following concepts.]

1. Enter the level of knowledge (LOK) of each question as either (F)undamental or (H)igher cognitive level.

2. Enter the level of difficulty (LOD) of each question using a 1 - 5 (easy - difficult) rating scale (questions in the 2 - 4 range are acceptable).

3. Check the appropriate box if a psychometric flaw is identified:

The stem lacks sufficient focus to elicit the correct answer (e.g., unclear intent, more information is needed, or too much needless information).

The stem or distractors contain cues (i.e., clues, specific determiners, phrasing, length, etc).

The answer choices are a collection of unrelated true/false statements.

The distractors are not credible; single implausible distractors should be repaired, more than one is unacceptable

. One or more distractors is (are) partially correct (e.g., if the applicant can make unstated assumptions that are not contradicted by stem).

4. Check the appropriate box if a job content error is identified:

The question is not linked to the job requirements (i.e., the question has a valid K/A but, as written, is not operational in content). The question requires the recall of knowledge that is too specific for the closed reference test mode (i.e., it is not required to be known from memory). The question contains data with an unrealistic level of accuracy or inconsistent units (e.g., panel meter in percent with question in gallons). The question requires reverse logic or application compared to the job requirements.

5. Check questions that are sampled for conformance with the approved K/A and those that are designated SRO

-only (K/A and license level mismatches are unacceptable

). 6. Enter question source: (B)ank, (M)odified, or (N)ew. Check that (M)odified questions meet criteria of ES

-401 Section D.2.f. 7. Based on the reviewer's judgment, is the question as written (U)nsatisfactory (requiring repair or replacement), in need of (E)ditorial enhancement, or (S)atisfactory?

8. At a minimum, explain any "U" ratings (e.g., how the Appendix B psychometric attributes are not being met).

ES-401 2 Form ES-401-9 Q# 1. LOK (F/H) 2. LOD (1-5) 3. Psychometric Flaws

4. Job Content Flaws

5. Other 6. B/M/N 7. U/E/S 8. Explanation Stem Focus Cues T/F Cred. Dist. Partial Job-Link Minutia #/ units Back-ward Q= K/A SRO Only 1 H 2 N S 201002 REACTOR MANUAL CONTROL SYSTEM Al Ability to predict and/or monitor changes in parameters associated with operating the REACTOR MANUAL CONTROL SYSTEM controls including:

04 Overall reactor power 2 F 2 X B E 201003 CONTROL ROD AND DRIVE MECHANISM A2 Ability to (a) predict the impacts of the following on the CONTROL ROD AND DRIVE MECHANISM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

09 Low reactor pressure The word "single" is not used in the I.A.'s section. Change to use the word "one" in distractor A "If one control rod scrams"

. 9/29 Agreed to change wording.

3 F 3 N S 201006 ROD WORTH MINIMIZER SYSTEM (RWM)

K6 Knowledge of the effect that a loss or malfunction of the following will have on the ROD WORTH MINIMIZER SYSTEM (RWM):

05 Steam flow input 4 H 3 N S 203000 RHR/LPCI: INJECTION MODE Al Ability to predict and/or monitor changes in parameters associated with operating the RHR/LPCI:

INJECTION MODE controls including: 05 Suppression pool level Q# 1. LOK (F/H) 2. LOD (1-5) 3. Psychometric Flaws

4. Job Content Flaws

5. Other 6. B/M/N 7. U/E/S 8. Explanation Stem Focus Cues T/F Cred. Dist. Partial Job-Link Minutia #/ units Back-ward Q= K/A SRO Only 5 #1P F 2 X M?/B S 203000 RHR/LPCI: INJECTION MODE (A3) Ability to monitor automatic operations of the RHR/LPCI: INJECTION MODE including:

(03) Pump discharge pressure

. The change to this question does not meet the criteria to be considered modified.

Change stem. 2 nd sentence to read "Reactor pressure is lowering".

3 rd sentence. Delete "RHR pump discharge" and change to "reactor" pressure that will "allow RHR injection "flow to be seen on FI

-XXX at Panel XX?"

R: Licensee agrees that this is a bank question. Will change on QA sheet. Not modified.

7/24/14 Changes made by the licensee

. 6 H 3 X N E S 205000 SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE)

K4 Knowledge of SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) design feature(s) and/or interlocks which provide for the following:

05 Reactor cooldown rate Does the stem need to contain information that shows that a heatup is occurring and Reactor water level

? Why does the 2 nd fill in the blank end with a "?".

9/24 Agreed to remove the question mark, no other corrections needed. No other modifications needed. The question is OK as written.

Q# 1. LOK (F/H) 2. LOD (1-5) 3. Psychometric Flaws

4. Job Content Flaws

5. Other 6. B/M/N 7. U/E/S 8. Explanation Stem Focus Cues T/F Cred. Dist. Partial Job-Link Minutia #/ units Back-ward Q= K/A SRO Only 7 F 3 X B E S 206000 HIGH PRESSURE COOLANT INJECTION SYSTEM A2 Ability to (a) predict the impacts of the following on the HIGH PRESSURE COOLANT INJECTION SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

08 High suppression pool temperature: BWR-2,3,4 B does not appear plausible. Why would someone with GFES knowledge pick this?

Choice C & D in comparison are related to high temperature issues.

9/24 Reworded distractor plausibility statement to better define benefit of warm water.

8 F 2 N S 206000 HIGH PRESSURE COOLANT INJECTION SYSTEM K2 Knowledge of electrical power supplies to the following:

04 Turbine control circuits: BWR

-2,3,4 9 F 3 N S 209001 LOW PRESSURE CORE SPRAY SYSTEM K5 Knowledge of the operational implications of the following concepts as they apply to LOW PRESSURE CORE SPRAY SYSTEM: 05 System venting 10 H 2 X N E S 211000 STANDBY LIQUID CONTROL SYSTEM A4 Ability to manually operate and/or monitor in the control room: 02 SBLC control switch A is not plausible. If someone thought that in distractor A that squib valve A failed to fire, why would they choose to place the corresponding pump to run? Shouldn't choice A state pump B?

9/24 Accepted distractor reasoning as is.

11 F 3 B S 212000 REACTOR PROTECTION SYSTEM K2 Knowledge of electrical power supplies to the following:

01 RPS motor

-generator sets

Q# 1. LOK (F/H) 2. LOD (1-5) 3. Psychometric Flaws

4. Job Content Flaws

5. Other 6. B/M/N 7. U/E/S 8. Explanation Stem Focus Cues T/F Cred. Dist. Partial Job-Link Minutia #/ units Back-ward Q= K/A SRO Only 12 H 2 N E S 214000 ROD POSITION INFORMATION SYSTEM A4 Ability to manually operate and/or monitor in the control room; 03 Control rod drive temperature The question states that guidance is contained within the App. This is not true, the app references OP

-8.0 to raise flow rate.

9/24 Agree the reference to the OP from the App is good enough.

13 F 2 B S 215003 INTERMEDIATE RANGE MONITOR (IRM) SYSTEM K 1 Knowledge of the physical connections and/or cause effect relationships between INTERMEDIATE RANGE MONITOR (IRM) SYSTEM and the following:

07 Reactor vessel 14 F 1? X X B U E 215004 SOURCE RANGE MONITOR (SRM) SYSTEM K3 Knowledge of the effect that a loss or malfunction of the SOURCE RANGE MONITOR (SRM)

SYSTEM will have on following:

02 Reactor manual control Isn't the highest number correct by default?

LOD=1 R: Remove the words "or above". 15 H 3 N S 215004 SOURCE RANGE MONITOR (SRM) SYSTEM K5 Knowledge of the operational implications of the following concepts as they apply to SOURCE RANGE MONITOR (SRM) SYSTEM: 03 Changing detector position 16 H 3 N S 215005 AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM A2 Ability to (a) predict the impacts of the following on the AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

06 Recirculation flow channels upscale Q# 1. LOK (F/H) 2. LOD (1-5) 3. Psychometric Flaws

4. Job Content Flaws

5. Other 6. B/M/N 7. U/E/S 8. Explanation Stem Focus Cues T/F Cred. Dist. Partial Job-Link Minutia #/ units Back-ward Q= K/A SRO Only 17 F 3 B S 216000 NUCLEAR BOILER INSTRUMENTATION A2 Ability to (a) predict the impacts of the following on the NUCLEAR BOILER INSTRUMENTATION ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

02 Instrument line plugging BW does not have a procedure for a plugged instrument line, so this question was accepted to predict the effect on level indication and associated annunciators illuminated.

18 H 3 M S 217000 REACTOR CORE ISOLATION COOLING SYSTEM (RCIC)

A4 Ability to manually operate and/or monitor in the control room: 07 Reactor pressure 19 H 3 N S 217000 REACTOR CORE ISOLATION COOLING SYSTEM (RCIC)

G2.4.4 Ability to recognize abnormal indications for system operating parameters that are entry

-level conditions for emergency and abnormal operating procedures. 20 H 3 N S 218000 AUTOMATIC DEPRESSURIZATION SYSTEM A3 Ability to monitor automatic operations of the AUTOMATIC DEPRESSURIZATION SYSTEM including:

03 ADS valve acoustical monitor noise

. 21 F N S 219000 RHR/LPCI: TORUS/SUPPRESSION POOL COOLING MODE K2 Knowledge of electrical power supplies to the following:

01 Valves 22 H B S 223002 PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT

-OFF G2.2.36 Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations

. 23 H N S 230000 RHR/LPCI: TORUS/SUPPRESSION POOL SPRAY MODE A3 Ability to monitor automatic operations of the RHRILPCI: TORUS/SUPPRESSION POOL SPRAY MODE including:

01 Valve operation

Q# 1. LOK (F/H) 2. LOD (1-5) 3. Psychometric Flaws

4. Job Content Flaws

5. Other 6. B/M/N 7. U/E/S 8. Explanation Stem Focus Cues T/F Cred. Dist. Partial Job-Link Minutia #/ units Back-ward Q= K/A SRO Only 24 F B S 239002 RELIEFISAFETY VALVES KI Knowledge of the physical connections and/or cause effect relationships between RELIEF/SAFETY VALVES and the following:

05 Plant air systems 25 F B S 239002 RELIEF/SAFETY VALVES K6 Knowledge of the effect that a loss or malfunction of the following will have on the RELIEF/SAFETY VALVES: 03 A.C. power 26 F N S 245000 MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS KI Knowledge of the physical connections and/or cause effect relationships between MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS and the following:

07 Plant air systems 27 H N S 256000 REACTOR CONDENSATE SYSTEM K4 Knowledge of REACTOR CONDENSATE SYSTEM design feature(s) and/or interlocks which provide for the following:

06 Control of extraction steam 28 H N S 259001 REACTOR FEEDWATER SYSTEM K5 Knowledge of the operational implications of the following concepts as they apply to REACTOR FEEDWATER SYSTEM:

03 Turbine operation 29 H B S 259002 REACTOR WATER LEVEL CONTROL SYSTEM K3 Knowledge of the effect that a loss or malfunction of the REACTOR WATER LEVEL CONTROL SYSTEM will have on following: 07 Reactor water level indication 30 H B S 261000 STANDBY GAS TREATMENT SYSTEM Ki Knowledge of the physical connections and/or cause effect relationships between STANDBY GAS TREATMENT SYSTEM and the following:

11 Primary containment pressure

Q# 1. LOK (F/H) 2. LOD (1-5) 3. Psychometric Flaws

4. Job Content Flaws

5. Other 6. B/M/N 7. U/E/S 8. Explanation Stem Focus Cues T/F Cred. Dist. Partial Job-Link Minutia #/ units Back-ward Q= K/A SRO Only 31 #2P H 4 X N E

S 262001 A.C. ELECTRICAL DISTRIBUTION (A4) Ability to (a) predict the impacts of the following on the A.C.

ELECTRICAL DISTRIBUTION ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: (02) Loss of coolant accident. Delete "Orders sent out to crosstie E2 to E4".

Change "Maint" to "the MAINT position" for the 1202 and 1206 times.

Change "Which one-that E4 can.." to -that E4 "is allowed to"-

R: OK once changes have been confirmed.

7/24/14 Changes made by the licensee.

32 H 3 X B E S 262002 UNINTERRUPTABLE POWER SUPPLY (A.C.

/ D.C.) K6 Knowledge of the effect that a loss or malfunction of the following will have on the UNINTERRUPTABLE POWER SUPPLY (AC/D.C.):

03 Static inverter The Big Notes drawing shows these as UPS not as inverters.

Do you expect the applicant to know the DS numbers without reference to the drawing?

R: Will check and make changes if appropriate.

33 F 2 N S 263000 D.C. ELECTRICAL DISTRIBUTION Al Ability to predict and/or monitor changes in parameters associated with operating the D.C.

ELECTRICAL DISTRIBUTION controls including:

01 Battery charging/discharging rate 34 H B S 264000 EMERGENCY GENERATORS (DIESEL/JET)

K4 Knowledge of EMERGENCY GENERATORS (DIESEL/JET) design feature(s) and/or interlocks which provide for the following: (CFR: 41.7) 05 Load shedding and sequencing

Q# 1. LOK (F/H) 2. LOD (1-5) 3. Psychometric Flaws

4. Job Content Flaws

5. Other 6. B/M/N 7. U/E/S 8. Explanation Stem Focus Cues T/F Cred. Dist. Partial Job-Link Minutia #/ units Back-ward Q= K/A SRO Only 35 H X B E

S 271000 OFFGAS SYSTEM K3 Knowledge of the effect that a loss or malfunction of the OFFGAS SYSTEM will have on following:

(CFR: 41.5 /45.3) 01 Condenser vacuum Only one distractor is different from the others. Leading to the correct answer. Need to add another condensate/main condenser distractor.

R: Changed to remove "diminish" from stem. Not necessary. Accept Main Condenser vacuum.

36 H N S 290001 SECONDARY CONTAINMENT G2.0431 Knowledge of annunciator alarms, indications, or response procedures.

37 F  ? E 295001 PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION AKI Knowledge of the operational implications of the following concepts as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION:

02 Power/flow distribution 2 Pedigrees listed? New & Bank (Which one is it?)

38 H B S 295003 PARTIAL OR COMPLETE LOSS OF A.C. POWER AA2 Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF A.C. POWER: 05 Whether a partial or complete loss of A.C. power has occurred 39 H B S 295004 PARTIAL OR COMPLETE LOSS OF D.C. POWER AA1 Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER:

03 A.C. electrical distribution

Q# 1. LOK (F/H) 2. LOD (1-5) 3. Psychometric Flaws

4. Job Content Flaws

5. Other 6. B/M/N 7. U/E/S 8. Explanation Stem Focus Cues T/F Cred. Dist. Partial Job-Link Minutia #/ units Back-ward Q= K/A SRO Only 40 F B U S 295005 MAIN TURBINE GENERATOR TRIP AK1 Knowledge of the operational implications of the following concepts as they apply to MAIN TURBINE GENERATOR TRIP

01 Pressure effects on reactor power Q84 is similar. Bases for Hi Lvl trip from main turb Trip.

Need to change one of these.

Need to rewrite to prevent overlap with Q84

. Rewrote 2 nd part to eliminate overlap.

41 H N S 295006 SCRAM AK1 Knowledge of the operational implications of the following concepts as they apply to SCRAM:

02 Shutdown margin 42 H B S AA2 Ability to determine and/or interpret the following as they apply to HIGH REACTOR WATER LEVEL:

01 Reactor water level 43 F X N E S 295014 INADVERTENT REACTIVITY ADDITION AK1 Knowledge of the operational implications of the following concepts as they apply to INADVERTENT REACTIVITY ADDITION :

06 Abnormal reactivity addition

C seems obvious when compared to choice A. Change A to insert control rods? This is also an IA to prevent a scram.

R: Agreed to change A to "Insert control rods".

44 F B S 295015 INCOMPLETE SCRAM AK3 Knowledge of the reasons for the following responses as they apply to INCOMPLETE SCRAM:

01 Bypassing rod insertion blocks 45 F B S 295016 CONTROL ROOM ABANDONMENT AK2 Knowledge of the interrelations between CONTROL ROOM ABANDONMENT and the following:

01 Remote shutdown panel

Q# 1. LOK (F/H) 2. LOD (1-5) 3. Psychometric Flaws

4. Job Content Flaws

5. Other 6. B/M/N 7. U/E/S 8. Explanation Stem Focus Cues T/F Cred. Dist. Partial Job-Link Minutia #/ units Back-ward Q= K/A SRO Only 46 H M E S 295018 PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER AA1 Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER: 01 Backup systems Extra space on distractors C & D prior to DG4.

R: Not showing in LXR.

No change needed.

47 H N S 295019 PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR G2.04.47 Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material. 48 F X B U S 295021 LOSS OF SHUTDOWN COOLING AK1 Knowledge of the operational implications of the following concepts as they apply to LOSS OF SHUTDOWN COOLING

02 Thermal stratification Doesn't match the KA. Where does thermal stratification enter into this? R: There is no direct link to the KA for thermal stratification. The KA has been changed to better reflect the primary affect due to NC (AK1.04). 49 F B S 295023 REFUELING ACCIDENTS AK2 Knowledge of the interrelations between REFUELIN G ACCIDENTS and the following:

03 Radiation monitoring equipment 50 H X N E 295024 HIGH DRYWELL PRESSURE EA1 Ability to operate and/or monitor the following as they apply to HIGH DRYWELL PRESSURE:

14 Drywell ventilation system Are the switches referred to as "Override switches" or a DW Cooler control switches?

R: DW Cooler control switch bullet not needed and will be removed.

Q# 1. LOK (F/H) 2. LOD (1-5) 3. Psychometric Flaws

4. Job Content Flaws

5. Other 6. B/M/N 7. U/E/S 8. Explanation Stem Focus Cues T/F Cred. Dist. Partial Job-Link Minutia #/ units Back-ward Q= K/A SRO Only 51 H N S 295025 HIGH REACTOR PRESSURE EK3 Knowledge of the reasons for the following responses as they apply to HIGH REACTOR PRESSURE:

03 HPCI operation 52 H N S 295026 SUPPRESSION POOL HIGH WATER TEMPERATURE G2.01 .28 Knowledge of the purpose and function of major system components and controls 53 H B S 295028 HIGH DRYWELL TEMPERATURE EK2 Knowledge of the interrelations between HIGH DRYWELL TEMPERATURE and the following:

03 Reactor water level indication 54 H X N E S 295030 LOW SUPPRESSION POOL WATER LEVEL G2.2.38 Knowledge of conditions and limitations in the facility license Change to say "LCO & PCCP entry required" or "PCCP entry ONLY".

R: Change 2 nd question to match above.

55 H N S 295031 REACTOR LOW WATER LEVEL EA2 Ability to determine and/or interpret the following as they apply to REACTOR LOW WATER LEVEL:

03 Reactor pressure There is no correlation for determining reactor pressure from level indication but there is from the opposite direction therefore I accepted this question to meet the K/

A. 56 H N S 295032 HIGH SECONDARY CONTAINMENT AREA TEMPERATURE EK2 Knowledge of the interrelations between HIGH SECONDARY CONTAINMENT AREA TEMPERATURE and the following:

04 PCIS/NSSSS 57 F B S 295033 HIGH SECONDARY CONTAINMENT AREA RADIATION LEVELS G2.4.45 Ability to prioritize and interpret the significance of each annunciator or alarm

Q# 1. LOK (F/H) 2. LOD (1-5) 3. Psychometric Flaws

4. Job Content Flaws

5. Other 6. B/M/N 7. U/E/S 8. Explanation Stem Focus Cues T/F Cred. Dist. Partial Job-Link Minutia #/ units Back-ward Q= K/A SRO Only 58 H N E S 295034 SECONDARY CONTAINMENT VENTILATION HIGH RADIATION EK2 Knowledge of the interrelations between SECONDARY CONTAINMENT VENTILATION HIGH RADIATION and the following:

03 SBGT Alarm window in the explanation is incorrect, not (5

-4), should be (3

-5). 59 #3P H 3 X B S 295036 SECONDARY CONTAINMENT HIGH SUMP/AREA WATER LEVEL (EA1) Ability to operate and/or monitor the following as they apply to SECONDARY CONTAINMENT HIGH SUMP/AREA WATER LEVEL : (03) Radwaste Distractor B not plausible. SCCP doesn't list this action; none of the EOIs list this action.

R: Licensee explained that "Isolate primary system discharge" is in the procedure, must reset RPS to achieve but can't with High DW press. 60 H N S 295037 SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN EA1 Ability to operate and/or monitor the following as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN:

01 Reactor Protection System 61 H X N E S 295038 HIGH OFF

-SITE RELEASE RATE EK3 Knowledge of the reasons for the following responses as they apply to HIGH OFF

-SITE RELEASE RATE: 03 Control room ventilation isolation "by processing intake air through the filter trains" is in all distractors and is not needed. Should B2 & D2 state both the MCR and all areas? Otherwise, it is not plausible to have a combination of MCR only with isolating ventilation in the control bay.

R: Change wording to match areas of the plant.

62 H N S 300000 INSTRUMENT AIR SYSTEM K3 Knowledge of the effect that a loss or malfunction of the INSTRUMENT AIR SYSTEM will have on the following:

01 Containment air system

Q# 1. LOK (F/H) 2. LOD (1-5) 3. Psychometric Flaws

4. Job Content Flaws

5. Other 6. B/M/N 7. U/E/S 8. Explanation Stem Focus Cues T/F Cred. Dist. Partial Job-Link Minutia #/ units Back-ward Q= K/A SRO Only 63 H B S 400000 COMPONENT COOLING WATER SYSTEM (CCWS)

A3 Ability to monitor automatic operations of the CCWS including:

01 Setpoints on instrument signal levels for normal operations, warnings, and trips that are applicable to the CCWS 64 F X N E S 600000 PLANT FIRE ON SITE AA2 Ability to determine and interpret the following as they apply to PLANT FIRE ON SITE:

04 The fires extent of potential operational damage to plant equipment Change A to CSW Pump 1B to make distractor A more plausible.

Change D to CRD Pump 1B to make distractor D plausible.

R: Agreed to change as noted.

65 H B S AK3 Knowledge of the reasons for the following responses as they apply to GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES:

01 Reactor and turbine trip criteria 66 H X B E S G2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc

. Change to give exact generator pressure and MWe values.

R: Will put in actual values.

67 F B S G2.1.27 Knowledge of system purpose and/or functio n 68 H B S G2.1.31 Ability to locate control room switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup 69 F B S G2.2.03 (multi

-unit license) Knowledge of the design, procedural, and operational differences between units.

70 F N S G2.2.13 Knowledge of tagging and clearance procedures

Q# 1. LOK (F/H) 2. LOD (1-5) 3. Psychometric Flaws

4. Job Content Flaws

5. Other 6. B/M/N 7. U/E/S 8. Explanation Stem Focus Cues T/F Cred. Dist. Partial Job-Link Minutia #/ units Back-ward Q= K/A SRO Only 71 #4P F 1 3 X X U

S G2.2.41 Ability to obtain and interpret station electrical and mechanical drawings.

LOD 1. GFES question. Distractors C & D not very plausible. KA not met. This question is answered w/o reference required.

R: Suggested ways to rewrite using a P&ID reference.

7/24/14 New question written that is a LOD > 1 and meets the KA

. 72 F N S G2.3.13 Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high

-radiation areas, aligning filters, etc. 73 #5P F 2 X X E

S G2.3.14 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities.

Does not meet the KA statement.

A not plausible, only performed while SD or in an outage.

C not plausible, stem conditions don't support any HWC items to support a HWC malfunctions D not plausible, only performed while SD or in an outage.

This is a conductivity question per the plausibility distractor analysis.

Only need to know that resin affects conductivity to answer the question. The KA is for radiation or radiological contamination. Also, not a HCL.

R: OK with question, add radiation affects to plausibility statements.

Chemicals are added at power therefore original reasoning for unsat removed. 74 H N S G2.4.9 Knowledge of low power/shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies.

75 H 3 N S G2.4.21 Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.

Q# 1. LOK (F/H) 2. LOD (1-5) 3. Psychometric Flaws

4. Job Content Flaws

5. Other 6. B/M/N 7. U/E/S 8. Explanation Stem Focus Cues T/F Cred. Dist. Partial Job-Link Minutia #/ units Back-ward Q= K/A SRO Only 76 #6P F 3 X X X N U

S 201006 ROD WORTH MINIMIZER SYSTEM (RWM)

G2.4.47 Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

Does not meet the KA. Does not test ability to diagnose/recognize trends; the 1 st sentence in the stem is not needed. Question is not technically correct as the LPAP is not entered at 19.1% steam flow. (It's actually in the transition zone). Also the question as written in not operationally valid. Uses backwards logic.

Note: LP gives information pertaining to inverse video when in the transition zone.

R: Reword question to include CR reference to apply transition zone criteria. 7/24/14 Changes made by the licensee.

77 F B U

S 203000 RHR/LPCI: INJECTION MODE A2 Ability to (a) predict the impacts of the following on the RHR/LPCI: INJECTION MODE; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: (CFR: 41.5 /45.6) 16 Loss of coolant accident

Doesn't appear to meet the KA on 1 st pass. Only a one part question, part (b) is not addressed. How does this predict the impact on RHR/LPCI injection Mode?

R: Upon review with licensee, agreed with license logic for relationship with LPCI logic.

78 H N S 215003 INTERMEDIATE RANGE MONITOR (IRM) SYSTEM G2.04.30 Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator. 79 F? X N U E 215003 AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM G2.2.3 8? Knowledge of conditions and limitations in the facility license. Question KA does not match sample plan approved number.

Q# 1. LOK (F/H) 2. LOD (1-5) 3. Psychometric Flaws

4. Job Content Flaws

5. Other 6. B/M/N 7. U/E/S 8. Explanation Stem Focus Cues T/F Cred. Dist. Partial Job-Link Minutia #/ units Back-ward Q= K/A SRO Only 80 H 2 N E S 261000 STANDBY GAS TREATMENT SYSTEM G2.02.38 Knowledge of conditions and limitations in the facility license. Distractor B does not appear plausible. You tell them this is a 31 day ST so why would someone think it is a monthly ST?

9/4/14 Reviewing still to replace B distractor.

Question modified to change distractor B.

81 H 3 N E S 290001 SECONDARY CONTAINMENT G2.4.45 Ability to prioritize and interpret the significance of each annunciator or alarm.

Stem Focus: Go over all the items listed and verify they are needed for either the answer or the distractor analysis. With the information given, do you need to tell them the release if via the blowout panels?

9/4/14 Remove blowout panels and change 1 st question to "would be considered" 82 H 2 X N U E S 290003 CONTROL ROOM HVAC A2 Ability to (a) predict the impacts of the following on the CONTROL ROOM HVAC ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

04 Initiation/failure of fire protection system.

Changes made to correct updated logic changes to the system.. 83 H 2 M? 2010-2 NRC E S 295001 PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION G2.1.20 Ability to interpret and execute procedure steps.

Did not include the question that this question was modified from. I can't analyze that this meets the modified criteria w/o the original question.

Q# 1. LOK (F/H) 2. LOD (1-5) 3. Psychometric Flaws

4. Job Content Flaws

5. Other 6. B/M/N 7. U/E/S 8. Explanation Stem Focus Cues T/F Cred. Dist. Partial Job-Link Minutia #/ units Back-ward Q= K/A SRO Only 84 F 2 X N U

E S 295005 MAIN TURBINE GENERATOR TRIP G2.2.22 Knowledge of limiting conditions for operations and safety limits. A is also a correct answer. Subset issue: 23% power is defined as part of MODE 1 therefore this is also correct. 2 nd part of question stem is confusing. You state hi water level twice. This is unnecessary. The basis for the indirect high water level scram from the main turbine trip instrumentation is to -

Need to change choice of hi level trip to protect turbine to something else, the correct choice is obvious by eliminating hi level trip to protect the turbine.

9/4/14 Changed wording in 2 nd question to simplify the question.

85 H 2 X B 2010-1 NRC Exam U

E S 295015 INCOMPLETE SCRAM G2.4.20 Knowledge of the operational implications of EOP warnings, cautions, and notes.

Could this be answered solely through use of procedure hierarchy?

The only info given is that an ARP is in alarm using the EOPs. Would you go use an OP is this situation? OP

-19 is not referenced in this ARP. OP

-17(RHR) is referenced for draining the Torus.

Also, the HPCI System lesson plan states that "Operation below 2100 rpm may result in failure of the AOP due to repeated cycling

". This does not agree with your plausibility for choice C & D. If anything , someone could confuse this with bearing damage also.

9/4/14 Changed choice to HPIC Hard card for injection.

86 H 2 X X B 2008 NRC Exam U E S 295022 LOSS OF CRD PUMPS AA2 Ability to determine and/or interpret the following as they apply to LOSS OF CRD PUMPS: 02 CRD system status

. Wouldn't an RO know that he can control the CRD flow controller in manual via the normal OP? Add the words to 2 nd half question to state it's following a loss of a CRD Pump. AOP

-2.0 step that reference OP is not included as reference.

9/4/14 Licensee agreed to add the words to the 2 nd part to improve plausibility of the 2 nd question.

Q# 1. LOK (F/H) 2. LOD (1-5) 3. Psychometric Flaws

4. Job Content Flaws

5. Other 6. B/M/N 7. U/E/S 8. Explanation Stem Focus Cues T/F Cred. Dist. Partial Job-Link Minutia #/ units Back-ward Q= K/A SRO Only 87 H 3 X M 2004 NRC Exam E S 295025 HIGH REACTOR PRESSURE G2.4.45 Ability to prioritize and interpret the significance of each annunciator or alarm.

Wording of 1 st question is weak and could lead to subset issue. Change to say that "To obtain the above indications, Rx pressure reached a maximum pressure of no less than-."

9/24 Agreed with wording on the question that the license used.

88 #7P H 2 X X N U

S 295026 SUPPRESSION POOL HIGH WATER TEMPERATURE (EA2) Ability to determine and/or interpret the following as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE:

(01) Suppression pool water temperature

. C is not plausible. This would meet the RO responsibility. If the RO is responsible for knowing that at 95 degrees the alarm is received and expected for placing HPCI in test mode then distractor A is not plausible. Otherwise, you could never perform the test and not be a TS condition to suspend the test.

Also the correct answer "D" is a non

-LCO entry criterion. Could argue there is no correct answer.

R: Plant is still reviewing.

7/24/14 Changes made by the licensee. Not SRO Only. Distractor C & D determined as untrue using RO Knowledge of immediate Rx trip criteria and determination of what SP bulk water temperature.

Will hold question until validation results come in? Will ask the SRO validators if RO knowledge to eliminated choice C & D.

9/4/14 Licensee stated that the RO would not know this is TS required information.

89 H 3 B 2007 NRC Exam S 295030 LOW SUPPRESSION POOL WATER LEVEL EA2 Ability to determine and/or interpret the following as they apply to LOW SUPPRESSION POOL WATER LEVEL: 02 Suppression pool temperature.

Q# 1. LOK (F/H) 2. LOD (1-5) 3. Psychometric Flaws

4. Job Content Flaws

5. Other 6. B/M/N 7. U/E/S 8. Explanation Stem Focus Cues T/F Cred. Dist. Partial Job-Link Minutia #/ units Back-ward Q= K/A SRO Only 90 H 2 X N E S 295031 REACTOR LOW WATER LEVEL G2.4.30 Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator.

In the stem, state that the Rx mode switch is placed in SD as directed per GOI- Verified GP procedure contains step to place mode switch in SD.

Also changed A to 4 hrs vs. 1 hr.

91 H 3 N E

S 295033 HIGH SECONDARY CONTAINMENT AREA RADIATION LEVELS G2.02.44 Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.

Missing Attachment referenced in the question? Also, verify this is not a direct lookup.

Reference provided

. 92 H 3 N S 295038 HIGH OFF

-SITE RELEASE RATE EA2 Ability to determine and/or interpret the following as they apply to HIGH OFF

-SITE RELEASE RATE: 03 Radiation levels 93 F 2 N S 400000 COMPONENT COOLING WATER SYSTEM (CCWS)

A2 Ability to (a) predict the impacts of the following on the CCWS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: 01 Loss of CCW pump. Only addresses the 1 st half of the KA statement. OK 94 #8P H 3 X M? BFN Bank U E S G2.1.39 Knowledge of conservative decision making practices.

RO's IA's are to trip the unit if THI is entered.

R: Will rewrite question for scram but that is not RO knowledge.

7/24/14 Changes made by the licensee. Modified? Original question not included.

A comma is required in choice A. (With-MODE 1

,). What procedure contains the criteria to scram the unit?

Q# 1. LOK (F/H) 2. LOD (1-5) 3. Psychometric Flaws

4. Job Content Flaws

5. Other 6. B/M/N 7. U/E/S 8. Explanation Stem Focus Cues T/F Cred. Dist. Partial Job-Link Minutia #/ units Back-ward Q= K/A SRO Only 95 F 2 N E S G2.2.3 (multi-unit license) Knowledge of the design, procedural, and operational differences between units. The combination in Distractor C does not seem plausible.

9/4/14 Agree with plausibility.

96 #9P H 3 X M? 2008 NRC Exam U E S G2.2.37 Ability to determine operability and/or availability of safety related equipment.

Don't need to give Limit (Secs) in the stem, this is given in the TS. Position misspelled.

Distractor D not plausible. LCO 3.1.5 never directs BOTH actions.

Distractor C is technically correct. It does have to be declared SLOW or INOP.

R: Plant will continue working on to clear up.

7/24/14 Changes made by the licensee. Remove the "reference provided" from all questions on the exam. INOPERABLE is always correct for this question therefore A & C not plausible. Will reword to say will SLOW or not SLOW.

97 F 2 B 2007 NRC Exam S G2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions.

98 H 2 B 2010-2 NRC Exam S G2.3.14 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities.

Q# 1. LOK (F/H) 2. LOD (1-5) 3. Psychometric Flaws

4. Job Content Flaws

5. Other 6. B/M/N 7. U/E/S 8. Explanation Stem Focus Cues T/F Cred. Dist. Partial Job-Link Minutia #/ units Back-ward Q= K/A SRO Only 99 #10P H 2 X X B 2008 NRC Exam U

S G2.4.27 Knowledge of "fire in the plant" procedures

. Not SRO Only. C &

D can be determined using RO knowledge. These are IA's of AOP

-32.

Why do we need to tell them that they are in the General Fire Plan?

Stem states you do NOT enter AOP

-32, therefore why would you enter the procedure after entering the two procedures given? Not logical. R: Reviewing still to make corrections. Suggested asking basis for the mitigating action of a step within the procedure.

7/24/14 Changes made by the licensee.

100 H 2 X N E S G2.4.45 Ability to prioritize and interpret the significance of each annunciator or alarm.

4 th bullet should be followed by 5 th bullet "Inboard and Outboard MSIV logic lights are illuminated".