ML15245A303

Initial Exam 2015-301 Final Administrative Documents

ML15245A303
Person / Time
Site:	Catawba
Issue date:	08/31/2015
From:	NRC/RGN-II
To:	Duke Energy Carolinas
References
50-413/15-301, 50-414/15-301
Download: ML15245A303 (38)

Text

ES.201 Examination Outline Quality Checklist Form ES-2O12 Facihty: Catawba Nuclear Station Dale of Exaruntiorr 05118/2015

.p Item Task Descr:pt:on b

1: a. Verify the: the out: nss host the app opra:e model, n accordance with ES 4O N h. Assess whethpr toe uuthoe was systemat:Ce! and rancorny prepared in cercence w:th Section D of ES-SC 1 and oneiher all K/A catecoriss are spprnpriateh ampied C T

T o Assess woother thc-uutlneover.ernptiasrzes any systems. evolutions, or generic epics. çv 1 4

k

d. Assess erether th justifications for deselected or rejected K/A statements are appropriate (\ ,.

2. a. Using Form ES-3C1-5, eri5 hat the prnocsed scer;arjo eros cover the required n.jer ot normal evolutions. instromem and component faures, technical sceictlcations. and major S tr5nsients /i rr b. Assess whet trr there are encuqo scenario se:s lard spares) to test the projected numbe nd j six of app/cents in a000Tance mn :Pe expected Drew compositren arid rotation scbedu.e C wifhciutcornpmnisnq exam inteqrty. OOi ensure that each appl:canf can be hestec using at A east one new or significantly .-norrfiert scenario, that no scenarios are dupiicated from the 4 f4)

T appecarts audit tesde i. one that ace-arios will riot be repeated on subsequent days 0

c. To the Oxtent Oo5sib.. assess wiretner t:e ontiirie(s) cenfoni)sr m: tn the uuaftat:ve V

I .irdve criteria pe lied on or n ES rOl 4 a C deco bednAppndia gte

3. a. Verify that the systems .caik-ttrougn outline insets the criteria soec:iec an Fern 55-3(11-2 th eulirEi(s) cortain:s the eqnrec nmber of control room and np!arit tasks disc/outed W among the safety functions as specified an toe twin

/ (2) task reOettion from toe last two NRC exarn:urtrorrs is wthsr the imts speciflec on the form 5 (3) no isks are duplicated from the applicants audit test(s)

\ th@ r cr of rime ci mcdifled I eke rices r cxcceds the rilnirnun ee it oct on hi Ii or

5) the number et Citernate path. em cower. emergency arid RCA tasks rest th coterie (

On te form.

b. Verifythatthe udninistratve outline meets the criteria spec/dec on Form ES.301-t

( 1 the tasks are rtistibutod among the topics as specified on the for:::

12) at least one task s new or sirjnfic.antiy rncctihied \ I (3) no more than one task s repeated from the iast two NRC im000sing_exenripatmoris it. Dutemttrinemfthete are croua different outilnes 10 set the projected number and mix *

1 phc mis ann cii re bit no tome are d iplicatod on ubseqoent ls /

P

3. a. Assess wrether plantspecic priorities (1ncluding PRA and p5 insights; are covered - .

in he appropriate xc I SCotiOnS -

er2 o Asse eheti er the C CCR 55 33 arid oS artipt ng a auprop dtc

c. Ensure toat K/A imp000rce ratings (except for giant-specific: priorities) as st cast 2.5.

R ii ,tjcktur dug ii icr: rid rlap en mo exwi ccl ins &\ j,,,

L e. Check the entmre exan: Icr oalance of coverage

.Assess wtietr:ei the exam Sc tIre appropriate joe level (RO or SPO) (,o Pruntece/Sig / Date I a h her Ri st Mi le -

F 1 mit) R i nri I sailer Hunn Cull Sn i icr ci C

61 I Note .nceoerimfer:t NRC resewer ic/mI tens in Column c: eh:et e>rarn:rer concurrence req..reo.

Not appi:canie for NRCprepamed examinaton Outi nec

ES-301 Administrative Topics Outline Form ES-301-1 NRC EXAM Facility: Catawba Nuclear Station Date of Examination: May 2015 Examination Level: RO SRO Operating Test Number: 2015301 Administrative Topic Type Describe activity to be performed (See Note) Code*

Calculate Head Vent Time Conduct of Operations R,D G 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc. 3.9/4.2 Perform a Manual NC System Leakage Calculation G 2.1.7 Ability to evaluate plant performance and make Conduct of Operations R,M operational judgments based on operating characteristics, reactor behavior, and instrument interpretation. 4.4/4.7 Calculate RL System Heat Rise G 2.2.44 Ability to interpret control room indications to Equipment Control R,N verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions. 4.2/4.4 Determine RP Requirements Radiation Control R,M G 2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions. 3.5/3.6 Emergency Procedures/Plan NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 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 (> 1)

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

ES 301, Page 22 of 27

Admin JPMs JPM A.1 Calculate Reactor Vessel Head Venting Time (Common RO & SRO) - Bank JPM CSF-003 K/A Generic 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc. (CFR 41.10 / 43.5 / 45.12) RO 3.9 SRO 4.2 Initial conditions are that a LOCA has occurred on Unit 1. The applicants are directed to calculate and record the maximum reactor vessel head venting time per EP/1/A/5000/FR-I.3 (Response to Voids in Reactor Vessel) Enclosure 5 (Allowable Hydrogen Venting Time). The applicants are given Enclosure 5 of FR-I.3 and pictures of control board meters for Containment Pressure, Hydrogen Concentration, Lower Containment Air Temperature, and Wide Range NC System Pressure which will be used in the calculation. Applicants will calculate the allowable head venting time of 3.4 - 5.2 minutes based off of bounding values determined.

JPM A.1 Perform a Manual NC System Leakage Calculation (Different RO & SRO) - Modified bank JPM NC-094 (Values changed to produce a different answer for identified, unidentified, and total accumulated leakage and to cause the plant to be in a different Selected License Commitment condition). RO applicants will perform the calculations and determine that the Standby Makeup Pump #1 will not function as designed. SRO applicants will have to perform the calculations and determine any applicable Tech Spec/SLC actions.

K/A Generic 2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation. (CFR 41.5 / 43.5 / 45.12 /

45.13) RO 4.4 SRO 4.7 Initial conditions are that Unit 1 Operator Aid Computer is out of service due to emergent system failures and will not be returned to service for an estimated 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The applicants are directed to perform a manual NC system leakage calculation per PT/1/A/4150/001 D (NC System Leakage Calculation). The applicants will be given a data sheet with needed values for times 2000 & 2101 (required to be > 60 minutes). RO applicants, once calculations are complete, will determine that the Standby Makeup Pump #1 will not function as designed per Step 19. SRO applicants, once calculations are complete, will determine that entry into T.S. 3.4.13 Condition A is required for Unidentified Leakage being > 1 gpm (~10.6 gpm) and entry into SLC 16.7-9 Condition B is required for Total Accumulated Leakage being > 20 gpm making the Standby Makeup Pump #1 Non-Functional.

JPM A.2 - Calculate RL System Heat Rise (Common RO & SRO) - NEW JPM K/A Generic 2.2.44 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. (CFR 41.5 / 43.5 / 45.12) RO 4.2 SRO 4.4 Initial conditions are a loss of Unit 1 and Unit 2 Operator Aid Computers occurred 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> ago.

The applicants are directed to calculate the Low Pressure Service Water Heat Rise T and to determine if NPDES permit requirements are met for the day they are given the JPM, per PT/0/A/4250/011 (RL Temperature and Discharge Flow Determination) Enclosure 13.6 (RL System Heat Rise (T) Calculation). The applicants are given a copy of PT/0/A/4250/011 Enclosures 13.4, 13.5 (Values needed to calculate are recorded in these enclosures), and 13.6.

Applicants will calculate a heat rise of between 11°F and 12°F. This value will not meet NPDES permit requirements for the month of May (Apr 1 - Sep 30 is required to be < 10°F). This will require a notification to the shift manager and a plant heat load reduction of the RL system.

JPM A.3 - Determine Radiation Protection Requirements for an Activity (Common RO & SRO) - Modified 2005 NRC JPM R03/SRO4 (Values changed and RWP requirements changed to produce a different answer).

K/A Generic 2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions. (CFR 41.12 / 45.10) RO 3.5 SRO 3.6 Initial conditions are that Unit 1 has entered AP/1/A/5500/019 (Loss of Residual Heat Removal).

The CRS has sent the applicant to the 1A ND pump room to stand by in a low exposure waiting area and await word to vent 1A ND pump. The applicant is given a copy of RWP # 5021 (ECCS venting) and a copy of a plan view for 1A ND pump room and a timeline for the evolution. They are directed to calculate their total dose received for the job and to determine the latest time that they could finish the venting without exceeding any of the RWP requirements (In this case 25 mRem dose).

ES-301 Administrative Topics Outline Form ES-301-1 NRC EXAM Facility: Catawba Nuclear Station Date of Examination: May 2015 Examination Level: RO SRO Operating Test Number: 2015301 Administrative Topic Type Describe activity to be performed (See Note) Code*

Calculate Head Vent Time Conduct of Operations R,D G 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc. 3.9/4.2 Perform a Manual NC System Leakage Calculation G 2.1.7 Ability to evaluate plant performance and make Conduct of Operations R,M operational judgments based on operating characteristics, reactor behavior, and instrument interpretation. 4.4/4.7 Calculate RL System Heat Rise G 2.2.44 Ability to interpret control room indications to Equipment Control R,N verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions. 4.2/4.4 Determine RP Requirements Radiation Control R,M G 2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions. 3.5/3.6 Determine NRC Reporting Requirements Emergency Procedures/Plan R,D G 2.4.40 Knowledge of SRO responsibilities in emergency plan implementation. 2.7/4.5 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 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 (> 1)

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

ES 301, Page 22 of 27

Admin JPMs JPM A.1 Calculate Reactor Vessel Head Venting Time (Common RO & SRO) - Bank JPM CSF-003 K/A Generic 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc. (CFR 41.10 / 43.5 / 45.12) RO 3.9 SRO 4.2 Initial conditions are that a LOCA has occurred on Unit 1. The applicants are directed to calculate and record the maximum reactor vessel head venting time per EP/1/A/5000/FR-I.3 (Response to Voids in Reactor Vessel) Enclosure 5 (Allowable Hydrogen Venting Time). The applicants are given Enclosure 5 of FR-I.3 and pictures of control board meters for Containment Pressure, Hydrogen Concentration, Lower Containment Air Temperature, and Wide Range NC System Pressure which will be used in the calculation. Applicants will calculate the allowable head venting time of 3.4 - 5.2 minutes based off of bounding values determined.

JPM A.1 Perform a Manual NC System Leakage Calculation (Different RO & SRO) - Modified bank JPM NC-094 (Values changed to produce a different answer for identified, unidentified, and total accumulated leakage and to cause the plant to be in a different Selected License Commitment condition). RO applicants will perform the calculations and determine that the Standby Makeup Pump #1 will not function as designed. SRO applicants will have to perform the calculations and determine any applicable Tech Spec/SLC actions.

K/A Generic 2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation. (CFR 41.5 / 43.5 / 45.12 /

45.13) RO 4.4 SRO 4.7 Initial conditions are that Unit 1 Operator Aid Computer is out of service due to emergent system failures and will not be returned to service for an estimated 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The applicants are directed to perform a manual NC system leakage calculation per PT/1/A/4150/001 D (NC System Leakage Calculation). The applicants will be given a data sheet with needed values for times 2000 & 2101 (required to be > 60 minutes). RO applicants, once calculations are complete, will determine that the Standby Makeup Pump #1 will not function as designed per Step 19. SRO applicants, once calculations are complete, will determine that entry into T.S. 3.4.13 Condition A is required for Unidentified Leakage being > 1 gpm (~10.6 gpm) and entry into SLC 16.7-9 Condition B is required for Total Accumulated Leakage being > 20 gpm making the Standby Makeup Pump #1 Non-Functional.

JPM A.2 - Calculate RL System Heat Rise (Common RO & SRO) - NEW JPM K/A Generic 2.2.44 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. (CFR 41.5 / 43.5 / 45.12) RO 4.2 SRO 4.4 Initial conditions are a loss of Unit 1 and Unit 2 Operator Aid Computers occurred 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> ago.

The applicants are directed to calculate the Low Pressure Service Water Heat Rise T and to determine if NPDES permit requirements are met for the day they are given the JPM, per PT/0/A/4250/011 (RL Temperature and Discharge Flow Determination) Enclosure 13.6 (RL System Heat Rise (T) Calculation). The applicants are given a copy of PT/0/A/4250/011 Enclosures 13.4, 13.5 (Values needed to calculate are recorded in these enclosures), and 13.6.

Applicants will calculate a heat rise of between 11°F and 12°F. This value will not meet NPDES permit requirements for the month of May (Apr 1 - Sep 30 is required to be < 10°F). This will require a notification to the shift manager and a plant heat load reduction of the RL system.

Admin JPMs JPM A.3 - Determine Radiation Protection Requirements for an Activity (Common RO & SRO) - Modified 2005 NRC JPM R03/SRO4 (Values changed and RWP requirements changed to produce a different answer).

K/A Generic 2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions. (CFR 41.12 / 45.10) RO 3.5 SRO 3.6 Initial conditions are that Unit 1 has entered AP/1/A/5500/019 (Loss of Residual Heat Removal).

The CRS has sent the applicant to the 1A ND pump room to stand by in a low exposure waiting area and await word to vent 1A ND pump. The applicant is given a copy of RWP # 5021 (ECCS venting) and a copy of a plan view for 1A ND pump room and a timeline for the evolution. They are directed to calculate their total dose received for the job and to determine the latest time that they could finish the venting without exceeding any of the RWP requirements (In this case 25 mRem dose).

JPM A.4 - Determine Reporting Per RP/0/B/5000/013 (NRC Notification Requirements) (SRO ONLY) -

Bank JPM SEP-025.

K/A Generic 2.4.40 Knowledge of SRO responsibilities in emergency plan implementation. (CFR 41.10 /

43.5 / 45.11) RO 2.7 SRO 4.5 Initial conditions are that a vendor was performing work activities in the S/G bowl area during No Mode. The vendor experienced heat exhaustion and fell into the S/G bowl area causing a compound fracture in his leg. Total dose received was 16 Rem. The individual was transferred to a local hospital due to his injuries. Site personnel are preparing a press release for immediate delivery to news vans parked just offsite. The applicants are directed to determine all applicable NRC notifications of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or less per RP/013. The applicants will determine that a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> notification is required due to offsite notification (news release) and an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> notification is required for Offsite Medical (Contaminated Injury).

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 NRC EXAM Facility: Catawba Nuclear Station Date of Examination: May 2015 Exam Level: RO SRO-I SRO-U Operating Test Number: 2015301 Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Safety System / JPM Title Type Code*

Function

a. Emergency Borate the Reactor Coolant System A,L,P,S 1 004 A2.14

b. Transfer ECCS to Cold Leg Recirculation A,D,EN,L,P,S 2 006 A4.07

c. Isolate Cold Leg Accumulators during Shutdown LOCA A,L,N,S 3 006 A1.13

d. Establish NC system Feed and Bleed A,D,L,P,S 4P 002A2.04

e. Loss of Normal Steam Release Capabilities M,S 4S E13 EA1.1

f. Shift Upper Containment Ventilation Units N,S 5 022A4.01

g. Reset radiation monitor Trip setpoints D,S 7 073A4.02

h. Loss of KC AP-21 step 8 (Reactor Trip Sequence) A,D,S 8 008A2.01 In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. Place Hydrogen Recombiners in service D,E,L,R 5 028A2.01

j. Start 2B Diesel Generator A,D,E 6 064A2.01

k. Start Backup Diesel VI compressor D,E 8 APE065AA1.04

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 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 / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (6/-/3)

(C)ontrol room (D)irect from bank <9 / <8 / <4 (7/-/3)

(E)mergency or abnormal in-plant >1 / >1 / >1 (3/-/3)

(EN)gineered safety feature - / - / >1 (1/-/1)

(L)ow-Power / Shutdown >1 / >1 / >1 (5/-/3)

(N)ew or (M)odified from bank including 1(A) >2 / >2 / >1 (3/-/2)

(P)revious 2 exams <3 <3 / <2 (3/-/1)

(R)CA >1 / >1 / >1 (1/-/1)

(S)imulator ES-301, Page 23 of 27

Simulator JPMs JPM a - Emergency Borate the Reactor Coolant System (RO Only) Previous 2 NRC Exams - randomly selected from bank - Alternate Path.

K/A 004 A2.14 - Ability to (a) predict the impacts of the following malfunctions or operations on the CVCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Emergency Boration (CFR: 41.5/43.5/45.3/45.5) RO 3.8 / SRO 3.9 Initial conditions are a valid reactor trip signal has been received, and the reactor will not trip automatically or manually from the control room. This gives a red path on the Subcriticality CSF status tree. The OATC is inserting control rods manually. The CRS directs the applicant to initiate emergency boration per EP/1/A/5000/FR-S.1 (Nuclear Power Generation/ATWS) step 4.

The applicant will open the emergency boration valve (1NV-236B) and start both boric acid transfer pumps. The applicant notices during verification that emergency boration flow is reading 0 gpm and transitions to the RNO to begin the ALTERNATE PATH. The applicant will then align the NV pump suction to the FWST and secure suction from the VCT to finish the JPM.

JPM b - Transfer the ECCS to Cold Leg Recirculation (Common RO & SRO) Previous 2 NRC Exams -

randomly selected from bank - Alternate Path.

K/A 006 A4.07 - Ability to manually operate and/or monitor in the control room: ECCS pumps and valves (CFR: 41.7/45.5 to 45.8) RO 4.4 / SRO 4.4 Initial conditions are a LOCA has occurred on Unit 1. Annunciator 1AD-9, E/8 FWST LO-LO LEVEL is lit and the CRS instructs the applicant to transfer to the Cold Leg Recirculation lineup using EP/1/A/5000/ES-1.3 (Transfer to Cold Leg Recirculation) step 6. During verification of automatic actions, it is determined that 1NI-184B (ND Pump 1B Cont Sump Suct) is not open.

The applicant continues to perform the lineup for CLR and when directed to open 1ND-28A (ND Supply to NV and NI Pmps), it will not open. This is where the applicant will determine that no ND train can be aligned to provide a suction to the NV and NI pumps and transitions to the RNO to begin the ALTERNATE PATH. The applicant will have to secure all NV and NI pumps to finish the JPM.

JPM c - Isolate Cold Leg Accumulators Following a Shutdown LOCA (Common RO & SRO) New -

Alternate Path K/A 006 A1.13 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ECCS controls including: Accumulator pressure (level, boron concentration) (CFR: 41.5 / 45.5) RO 3.5 SRO 3.7 Initial conditions are Unit 1 is in Mode 4 when pressurizer level and pressure begin to decrease uncontrollably. The CRS enters AP/1/A/5500/027 (Shutdown LOCA) to address the LOCA.

The CRS directs the applicant to isolate the Unit 1 Cold Leg Accumulators by performing Enclosure 14 (Isolating Cold Leg Accumulators) of AP/27. The applicant will attempt to close all Cold Leg Accumulator discharge isolation valves, but only 1A and 1D will isolate. The applicant will transition to the RNO to begin the ALTERNATE PATH. Applicant will have to isolate the Nitrogen going to the 1B and 1C Cold Leg Accumulators and then make the valve alignment to vent these accumulators to containment. The JPM is written to terminate at this time since all critical steps have been completed. Complete depressurization of these accumulators would take ~ 30 minutes.

Simulator JPMs JPM d - Establish NC system Bleed and Feed per EP/1/A/5000/FR-H.1 (Loss of Secondary Heat Sink)

(RO Only) Previous 2 NRC Exams - randomly selected from bank - Alternate Path K/A 002 A2.04 Ability to (a) predict the impacts of the following malfunctions or operations on the RCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of heat sinks (CFR 41.5 / 43.5 / 45.3 / 45.5) RO 4.3 SRO 4.6 Initial conditions are that a reactor trip has occurred on Unit 1 due to a loss of both Main Feedwater Pumps. The auxiliary feedwater system will not function. The crew has entered EP/1/A/5000/FR-H.1 (Loss of Secondary Heat Sink) due to a RED path on the CSF status trees.

Bleed and Feed initiation criteria are met. The CRS directs the applicant to initiate NC system Bleed and Feed by performing steps 19-24. Applicants will start with securing all reactor coolant pumps. Then they will initiate Safety Injection on both trains. B train S/I will not actuate and 1NI-9A (NV Pmp C/L Inj Isol) will not open. The applicant will not be able to verify any NV S/I flow and will transition to the RNO to begin the ALTERNATE PATH. Applicants will start the 1B NV and 1B NI pumps and will have to manually open 1NI-10B (NV Pmp C/L Inj Isol) to align the Feed path. Applicants will then open 2 Pressurizer PORVs to align a Bleed path and complete the JPM.

JPM e - Loss of Normal Steam Release Capabilities (Common RO & SRO) Modified from bank JPM CSF-006. Bank JPM is alternate path. JPM was modified to remove the alternate path.

K/A E13 EA1.1 Ability to operate and/or monitor the following as they apply to the (Steam Generator Overpressure) Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features. (CFR 41.7 / 45.5 / 45.6) RO 3.1 SRO 3.3 Initial conditions are that an inadvertent Main Steam Isolation Signal has caused a reactor trip on Unit 1. Steam system failures have caused steam generator pressure to exceed 1175 psig.

Applicants are directed by the CRS to perform EP/1/A/5000/FR-H.4 (Response to Loss of Normal Steam Release Capabilities) to restore steam generator pressure to < 1175 psig. The applicants will have to take each steam generator PORV to manual and then adjust the POT for the PORVs to open them. When steam generator pressure is decreased to < 1175 psig the JPM is complete.

JPM f - Shift Upper Containment Ventilation Units (RO Only) New K/A 022 A4.01 Ability to manually operate and/or monitor in the control room: CCS fans (CFR 41.7 /

45.5 to 45.8) RO 3.6 SRO 3.6 NOTE TO EXAMINER - This JPM can be performed at the same time as JPM e. Both JPMs use the same simulator IC set and neither JPM should cause any alarms that would impede the other. This JPM is performed around the back of the control boards on the ventilation panel, and out of sight of the applicant performing JPM e.

Initial conditions are that Unit 1 is at 48% power. The CRS directs the applicant to shift operating Upper Containment Ventilation Units by starting 1D UCVU and stopping 1C UCVU per OP/1/A/6450/001 (Containment Ventilation (VV) Systems) Enclosure 4.12 (Shifting Operating Upper Containment Ventilation Units). Applicants will start 1D UCVU and verify required fans start. Following this, applicants will secure 1C UCVU and verify it stops.

Simulator JPMs JPM g - Reset Radiation Monitor Trip Setpoints (RO Only) Direct from bank K/A 073 A4.02 Ability to manually operate and/or monitor in the control room: Radiation monitoring system control panel (CFR 41.7 / 45.5 to 45.8) RO 3.7 SRO 3.7 Initial conditions are that Unit 1 is at 100% power. Following a discussion with RP concerning a premature gaseous release termination, the CRS directs the applicant to reset EMF 50L setpoints per OP/0/A/6500/080 (EMF RP86A Output Modules) Enclosure 4.2 (EMF RP86A Trip Setpoint Adjustment). The new setpoints will have a Trip 1 value of 6300 cpm and a Trip 2 value of 9000 cpm. The OAC program EMFLIB is not available. The applicants will input the new values one at a time per procedure and perform a verification of proper setpoints per the procedure. The applicants will then fill out the appropriate setpoint log entries to finish the JPM.

JPM h - Loss of KC AP-21 step 8 (Reactor Trip Sequence) (RO Only) Direct from bank - Alternate Path K/A 008 A2.01 Ability to (a) predict the impacts of the following malfunctions or operations on the CCWS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of CCW pump (CFR 41.5 / 43.5 / 45.3 / 45.13) RO 3.3 SRO 3.6 Initial conditions are Unit 1 is at 100% power. AP/1/A/5500/021 (Loss of Component Cooling) has been entered. The CRS directs the applicant to perform step 8 of AP/21. The applicant will not be able to verify KC flow to the NC pumps and transitions to the RNO. The applicant will attempt to open 1KC-425A (NC Pumps Ret Hdr Cont Isol) which will be unsuccessful and will begin the ALTERNATE PATH. The applicant will place steam dumps in Pressure control mode, ensure the reactor is tripped, when reactor power is verified < 5%will trip the NC Pumps, and will place both Pressurizer Spray Valves in manual and closed. The JPM will be terminated with a cue that the CRS is ready to begin reading EP/1/A/5000/E-0 (Reactor Trip or Safety Injection).

Plant JPMs JPM i - Place 1B Hydrogen Recombiner in Service (Common RO & SRO) Direct from bank (RCA entry required)

K/A 028 A2.01 Malfunctions or operations on the HRPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Hydrogen Recombiner power setting, determined by using plant data book (CFR 41.5 / 43.5 / 45.3 /

45.13) RO 3.4 SRO 3.6 Initial conditions are that a LOCA has occurred on Unit 1. The CRS instructs the applicant to place Hydrogen Recombiner 1B in service at the required power per OP/1/A/6450/010 (Containment Hydrogen Control Systems) Enclosure 4.10 (Operation of the Hydrogen Recombiners Following a LOCA). The applicant will power up the 1B Hydrogen Recombiner and warm it up by adjusting the power output in several increments. The applicant will have to determine the required power output setting per Unit 1 Revised Data Book Figure 10 for the given pressure. Due to containment hydrogen concentration being > 3%, the applicant will have to add 4 KW to value from Figure 10 for the final required power output. Following adjusting the power output to the desired value and notification to the control room of the status of 1B Hydrogen Recombiner, the JPM is complete.

JPM j - Locally Start 2B Diesel Generator (Common RO & SRO) Direct from bank - Alternate Path K/A 064 A2.01 Ability to (a) predict the impacts of the following malfunctions or operations on the ED/G system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Failure modes of water, oil, and air valves (CFR 41.5

/ 43.5 /45.3 / 45.13) RO 3.1 SRO 3.3 Initial conditions are Unit 2 has experienced a loss of all AC power to 2ETB. The reason for the loss of AC power has been corrected. 2ETB load shed is complete. The CRS instructs the applicant to energize 2ETB from 2B D/G by performing AP/1/A/5500/007 (Loss of Normal Power)

Enclosure 11 (Energizing 2ETB From D/G). The applicant will locally start 2B D/G, attain proper frequency and voltage, and close the diesel output breaker to energize 2ETB. Following powering up essential load centers, the applicant would verify proper cooling water flow by verifying the cooling water isolation valve open. This valve is not open and cant be manually opened. This begins the ALTERNATE PATH. The applicant will have to shut down 2B D/G and inform the control room of status to finish the JPM.

JPM k - Start Backup Temporary VI Compressor (RO Only) Direct from bank K/A APE 065 AA1.04 Ability to operate and/or monitor the following as they apply to the Loss of Instrument Air: Emergency air compressor (CFR 41.7 / 45.5 / 45.6) RO 3.5 SRO 3.4 Initial conditions are both units at 100% power. VI low pressure annunciator is lit and VI pressure is 75 PSIG and slowly decreasing. AP/0/A/5500/022 (Loss of Instrument Air) is implemented. The CRS directs the applicant to startup and align the Backup Temporary VI Compressor 2 to the Instrument Air Header per the local copy of EP/1/A/5000/G-1 (Generic Enclosures) Enclosure 23 (Backup VI Compressor(s)) step 3. Applicant will begin with making pre start checks of the compressor. Applicant will then start the compressor and make the necessary lineups to tie the compressor to the Instrument Air Header. Once the applicant informs the control room of the status, the JPM is complete.

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 NRC EXAM Facility: Catawba Nuclear Station Date of Examination: May 2015 Exam Level: RO SRO-I SRO-U Operating Test Number: 2015301 Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Safety System / JPM Title Type Code*

Function a.

b. Transfer ECCS to Cold Leg Recirculation A,D,EN,L,P,S 2 006A4.07

c. Isolate Cold Leg Accumulators during Shutdown LOCA A,L,N,S 3 006A1.13 d.

e. Loss of Normal Steam Release Capabilities M,S 4S E13 EA1.1 f.

g.

h.

In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. Place Hydrogen Recombiners in service D,E,L,R 5 028A2.01

j. Start 2B Diesel Generator A,D,E 6 064A2.01 k.

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 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 / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (6/-/3)

(C)ontrol room (D)irect from bank <9 / <8 / <4 (8/-/4)

(E)mergency or abnormal in-plant >1 / >1 / >1 (3/-/3)

(EN)gineered safety feature - / - / >1 (1/-/1)

(L)ow-Power / Shutdown >1 / >1 / >1 (5/-/3)

(N)ew or (M)odified from bank including 1(A) >2 / >2 / >1 (2/-/1)

(P)revious 2 exams <3 <3 / <2 (3/-/1)

(R)CA >1 / >1 / >1 (1/-/1)

(S)imulator ES-301, Page 23 of 27

Simulator JPMs JPM b - Transfer the ECCS to Cold Leg Recirculation (Common RO & SRO) Previous 2 NRC Exams -

randomly selected from bank - Alternate Path.

K/A 006 A4.07 - Ability to manually operate and/or monitor in the control room: ECCS pumps and valves (CFR: 41.7/45.5 to 45.8) RO 4.4 / SRO 4.4 Initial conditions are a LOCA has occurred on Unit 1. Annunciator 1AD-9, E/8 FWST LO-LO LEVEL is lit and the CRS instructs the applicant to transfer to the Cold Leg Recirculation lineup using EP/1/A/5000/ES-1.3 (Transfer to Cold Leg Recirculation) step 6. During verification of automatic actions, it is determined that 1NI-184B (ND Pump 1B Cont Sump Suct) is not open.

The applicant continues to perform the lineup for CLR and when directed to open 1ND-28A (ND Supply to NV and NI Pmps), it will not open. This is where the applicant will determine that no ND train can be aligned to provide a suction to the NV and NI pumps and transitions to the RNO to begin the ALTERNATE PATH. The applicant will have to secure all NV and NI pumps to finish the JPM.

JPM c - Isolate Cold Leg Accumulators Following a Shutdown LOCA (Common RO & SRO) New -

Alternate Path K/A 006 A1.13 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ECCS controls including: Accumulator pressure (level, boron concentration) (CFR: 41.5 / 45.5) RO 3.5 SRO 3.7 Initial conditions are Unit 1 is in Mode 4 when pressurizer level and pressure begin to decrease uncontrollably. The CRS enters AP/1/A/5500/027 (Shutdown LOCA) to address the LOCA.

The CRS directs the applicant to isolate the Unit 1 Cold Leg Accumulators by performing Enclosure 14 (Isolating Cold Leg Accumulators) of AP/27. The applicant will attempt to close all Cold Leg Accumulator discharge isolation valves, but only 1A and 1D will isolate. The applicant will transition to the RNO to begin the ALTERNATE PATH. Applicant will have to isolate the Nitrogen going to the 1B and 1C Cold Leg Accumulators and then make the valve alignment to vent these accumulators to containment. The JPM is written to terminate at this time since all critical steps have been completed. Complete depressurization of these accumulators would take ~ 30 minutes.

JPM e - Loss of Normal Steam Release Capabilities (Common RO & SRO) Modified from bank JPM CSF-006. Bank JPM is alternate path. JPM was modified to remove the alternate path.

K/A E13 EA1.1 Ability to operate and/or monitor the following as they apply to the (Steam Generator Overpressure) Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features. (CFR 41.7 / 45.5 / 45.6) RO 3.1 SRO 3.3 Initial conditions are that an inadvertent Main Steam Isolation Signal has caused a reactor trip on Unit 1. Steam system failures have caused steam generator pressure to exceed 1175 psig.

Applicants are directed by the CRS to perform EP/1/A/5000/FR-H.4 (Response to Loss of Normal Steam Release Capabilities) to restore steam generator pressure to < 1175 psig. The applicants will have to take each steam generator PORV to manual and then adjust the POT for the PORVs to open them. When steam generator pressure is decreased to < 1175 psig the JPM is complete.

Plant JPMs JPM i - Place 1B Hydrogen Recombiner in Service (Common RO & SRO) Direct from bank (RCA entry required)

K/A 028 A2.01 Malfunctions or operations on the HRPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Hydrogen Recombiner power setting, determined by using plant data book (CFR 41.5 / 43.5 / 45.3 /

45.13) RO 3.4 SRO 3.6 Initial conditions are that a LOCA has occurred on Unit 1. The CRS instructs the applicant to place Hydrogen Recombiner 1B in service at the required power per OP/1/A/6450/010 (Containment Hydrogen Control Systems) Enclosure 4.10 (Operation of the Hydrogen Recombiners Following a LOCA). The applicant will power up the 1B Hydrogen Recombiner and warm it up by adjusting the power output in several increments. The applicant will have to determine the required power output setting per Unit 1 Revised Data Book Figure 10 for the given pressure. Due to containment hydrogen concentration being > 3%, the applicant will have to add 4 KW to value from Figure 10 for the final required power output. Following adjusting the power output to the desired value and notification to the control room of the status of 1B Hydrogen Recombiner, the JPM is complete.

JPM j - Locally Start 2B Diesel Generator (Common RO & SRO) Direct from bank - Alternate Path K/A 064 A2.01 Ability to (a) predict the impacts of the following malfunctions or operations on the ED/G system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Failure modes of water, oil, and air valves (CFR 41.5

/ 43.5 /45.3 / 45.13) RO 3.1 SRO 3.3 Initial conditions are Unit 2 has experienced a loss of all AC power to 2ETB. The reason for the loss of AC power has been corrected. 2ETB load shed is complete. The CRS instructs the applicant to energize 2ETB from 2B D/G by performing AP/1/A/5500/007 (Loss of Normal Power)

Enclosure 11 (Energizing 2ETB From D/G). The applicant will locally start 2B D/G, attain proper frequency and voltage, and close the diesel output breaker to energize 2ETB. Following powering up essential load centers, the applicant would verify proper cooling water flow by verifying the cooling water isolation valve open. This valve is not open and cant be manually opened. This begins the ALTERNATE PATH. The applicant will have to shut down 2B D/G and inform the control room of status to finish the JPM.

ES-301 Operating Test Quality Checklist Form ES-301-3 Eacit:y Catawba Nuclear Station Dateotaminaeort. May 2015 Opratrr lest Nurnost. 2015301 rrtiais I, General Criteria a b cc a Lie sratinq lest ;;ontorns with the pcviorsiy approved outline: changes are consistent Mth aml nO rcu reme fe g U 5 45 opeaflo all mpo tar 1 jnrtrOn dist Lutçhi Si Pt i h mere a no dna-Ic day repel liOn oeteer hs and otrer operatrrc tsncs to he rninslcrod during this examination O U C The on ran testshafnolctupticale items from the applicants audit testIs). (see Section C l.a.)

d. Overlap with the naitlen esaranation end betweer d-herent pats of the operatiiq test is w thin ,

acceplae t;mrts -r

e. it appears that toe operirtina test mill rtrlhrenta:e between comtreten: and es-than-conrcetenl .

1 srrnhcantsa!thiatedlicenseieve

2. Walk-Through Criteria -. --

a. Each ut-M incudes the following as applicanie:

itt at conditions

• ritiating cues

-efeencits and tonis. ncudina assocafOc pr;edtes reasonable and vabdated ame tir:ts laserage t ine allowed hr Domp.ettcni and pecfm designation it deemed to he time-critical by the facElrty .iceuaee cpera:icra t rnporan specific performance criteria that include

- cetaied expected acrons wtth exact cr.tera sod nornercalice

. caster, respcnse CrO other examiner cues

--- slarcments descrthing important obsenorhons to he made by the opp icant t

cr:teria for successful completion of the task dci lit c-heo-r of Ontic-al and their ascaui r a peborna ce ap a d 1

- rest- Stuns Ott Its secuence of steps, I apolicable h Ercre that arts c-han es from toe orovousty appovea systems and adm:nstraaurr aS-through naIl-nec Fonns ES-301 I SitU 2; have riot causec trie test to deviate trom any of toe acceptance \

criteria eg t5ni cslrhrtijn. cans usir. repettrcr from the laSt 2 NRC evamiratonsi speci ed 6 -

orscrmaroFon -

3 Simulator Criteria -- --

The assorated simrjtatnr operating tests (sceOaria setsl nave been reviewed in accorcance vath .

P5-301--I and a c-oily is attachea.

Ptrt . arne -mtilur.3 Date a Author R-MSeri____________

Far lity P i rr tJal er Hoc-i ic-ut NRC c-Xi nine i I b RC 50cc-S or NO E: mne facety signature s not appycab:e for NRC-developed tests.

C Independent NRC ev:ewer now items in Cotumn c chief examiner concurrence req. red

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Catawba Date of Exam: May 2015 Operating Test No.: 2015301 A E Scenarios P V Scenario 1 Scenario 2 T M P E O I L N CREW CREW CREW CREW T N I T A I C POSITION POSITION POSITION POSITION L M A T S A B S A B S A B S A B U N Y R T O R T O R T O R T O M(*)

T P O C P O C P O C P O C P R I U E

RO 1 RX 1 1 1 1 0 SRO-I NOR 1 1 1 1 1 I/C 4589 357 7 4 4 2 SRO-U MAJ 6 6 2 2 2 1 TS 0 0 2 2 RO 2 RX 1 1 1 1 0 NOR 1 1 1 1 1 SRO-I 1 I/C 2379 28 6 4 4 2 SRO-U MAJ 6 6 2 2 2 1 TS 0 0 2 2 RO 3 RX 1 1 1 1 0 NOR 1 1 1 1 1 SRO-I I/C 4589 357 7 4 4 2 SRO-U MAJ 6 6 2 2 2 1 TS 0 0 2 2 RO 4 RX 1 1 1 1 0 NOR 1 1 1 1 1 SRO-I I/C 2379 28 6 4 4 2 SRO-U MAJ 6 6 2 2 2 1 TS 0 0 2 2 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must do one scenario, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.

3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Catawba Date of Exam: May 2015 Operating Test No.: 301 A E Scenarios - for P V Scenario 1 Scenario 2 T M P E O I L N CREW CREW CREW CREW T N I T A I C POSITION POSITION POSITION POSITION L M A T S A B S A B S A B S A B U N Y R T O R T O R T O R T O M(*)

T P O C P O C P O C P O C P R I U E

RO RX 0 1 1 0 SRO-I NOR 1 1 2 1 1 1 I/C 234579 234578 12 4 4 2 SRO-U 1 MAJ 6 6 2 2 2 1 TS 23 34 4 0 2 2 RO RX 0 1 1 0 NOR 1 1 1 1 1 SRO-I I/C 234579 6 4 4 2 SRO-U 2 MAJ 6 1 2 2 1 TS 23 2 0 2 2 RO RX 0 1 1 0 NOR 1 1 1 1 1 SRO-I I/C 234578 6 4 4 2 SRO-U 3 MAJ 6 1 2 2 1 TS 34 2 0 2 2 RX 1 1 0 NOR 1 1 1 I/C 4 4 2 MAJ 2 2 1 TS 0 2 2 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must do one scenario, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.

3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

ES-301, Rev. 9 Competencies Checklist Form ES-301-6 Facility: Catawba Date of Examination: May 2015 Operating Test No.: 2015301 RO X RO RO SRO-I SRO-I SRO-I SRO-U SRO-U X SRO-U Competencies SCENARIO SCENARIO SCENARIO 1 2 3 4 5 1 2 3 4 5 1 2 3 4 5 Interpret/Diagnose Events 2345 2345 3456 23456 2345 3456 and Conditions 6789 678 78 789 678 78 Comply With and ALL ALL ALL ALL ALL ALL Use Procedures (1)

Operate Control ALL ALL ALL Boards (2)

Communicate ALL ALL ALL ALL ALL ALL and Interact Demonstrate Supervisory ALL ALL ALL Ability (3)

Comply With and 23 3 45 Use Tech. Specs. (3)

Notes:

(1)Includes Technical Specification compliance for an RO.

(2)Optional for an SRO-U.

(3)Only applicable to SROs.

Instructions:

Check the applicants license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant.

The final exam outline can be reconstructed from the draft 401-2 and the final 401-4.

ES-401, Rev. 9 Record of Rejected K/As Form ES-401-4 Tier / Randomly Selected Reason for Rejection Group K/A 1/1 APE026 AA1.04 Unable to write discriminating question due to plant design. No relation between CRDM cooling and CCW. K/A changed from APE026 AA1.04 to APE026 AA1.01 2/1 SYS013 K4.15 Unable to write discriminating question due to plant design. No continuous testing feature at this site. K/A changed from SYS013 K4.15 to SYS013 K4.23.

2/1 SYS013 K4.23 Unable to write discriminating question due to plant design. ED/G is not disabled for ESF testing at this site. K/A changed from SYS013 K4.23 to SYS013 K4.09.

2/2 SYS001 A1.11 Unable to write discriminating question for this K/A tied to the system. K/A changed from SYS001 A1.11 to SYS001 A1.02.

2/2 SYS072 A3.01 Unable to write discriminating question due to plant design. No ARMs which alter ventilation alignment. K/A changed from SYS072 A3.01 to SYS072 A2.02.

1/2 APE005 AA2.02 Unable to write discriminating question due to plant design. No Jog/Run speed for CRDM at this site. K/A changed from APE005 AA2.02 to APE005 AA2.04

ES-401 Written Examination Quality Checklist Form ES-401-6 racty Catawba Nuclear Station Dale of Exam May 2015 Exam eve): RD SRO X hitS!

Item Dscpticr 1 Di eslmn ann aris sic teChnicd jr Is and npp cabelo n at.i t 1 Pt)7

2. a. NRC R;As are referCnCed for ar questions B race cx fling nOJectlps are tcincccas aitaMe )

.. SEOquestwns are spprophate di accordance with Section D.2dotES-401 The sampling orocess was random and systemalc 1f more than 4 RD or 2 SRO questions from the last 2 NRC hcensing ex5ms, Consult the NRR OL piogam offdie).

5. Question cucicadon frrrt the iCCfiSC sCreernu/anol: exam was oir%el as indicated 050w check the tern that applies arc sopears Ophrcpraie:

tre a dt exan was eystematcaily end rancomly developed. or the corel exam was completed benr the cense exam was started, cr the exirnin5tirrv were dp:,diopw ntlepedeotiv; or V the cc-nsee certifies that there isnn rhipl.ca:ion or otrer eapiflini ( (

6. Bark use meets limitS no more than 75 percent Bank Modliec New horn tie bark, at east 10 percent new ann he mst I G

new or rnodifid, enter the actual RD SROruily 41%! 28% 2%) 4% 57%! 68%

Question dStnbuf Ofi(Sl at right

7. Between 50 and 60 pet Ceit of te questions Memory CA on the RO exam ae written at the comoerenson -..--_

55i5iS level the .omO aXatti may exceed oh 47/ x1 28 . 53/ 725 *3J percent it tie andemy selected JAs support . .

t-R the hitler cconit:v revels. corer Me actual Q SRO çi.hstaii cisti but On(s) atrjr: I

a. Reurcshandou:s provided do nra rave away answers ot sd in he elimination ol distractors. V P. QuesSon content conforms wIn specific JA statements ri tIre prev.ousty approved examnation outline arid is epprorrrate for the nor to wrich they are assigned .

deviations are ustihec I1I if Oustit yJ otnet L qua it a d forrea mee toe uie mx n ES Append a B 11 Tie esar curtains the required numBer of One-point mutt pIe cholow items: I I the tOtdiscOrre ç i5iith the value on the Cover sheet , _ Z_L_

Prtnted hSigna DaJe

a. Author Rusty Miter .

,, 4?.V2 1- ul I Ri vi.. v jeun1tcutt Note: Tne faciity reviewers ri:iatsrstvratnte arc rot appticabie for NRCdeveiopec examinariurs I idecenient NRC e w I I a tens in CJuixiri f J exam ncr ooncurran rvO it 0

ES-401 Written Examination Review Worksheet Form ES-401-9

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only Three generic comments.

Dont ask what the operator Will do. Ask what is required. No one knows what the operator will do. This affects several questions and I have individually marked where I saw this.

Dont diagnose in the stem, (e.g.A LOCA occurred). The Examiner Standard, Appendix A says To the extent possible, test items should address an actual or conceivable mental or psychomotor activity performed on the job. The diagnosis is not provided to the operator in the control room. Give the symptoms. This affects several questions, and I have individually marked such questions as Dont diagnose in the stem.

The phrase Which ONE of the following completes the statements below? is window dressing. These are extra words that neither help the applicant determine the correct answer nor make a distrator credible. The cover sheet of the exam makes it clear that each question only has one correct answer. Remove this wherever it appears on the exam. Several questions are marked as SAT on this form, but still need this phrase to be extracted. I do not list each example, since the majority of questions contain the phrase. Do a word search to remove this extraneous material where possible.

1 H 1 X N U The question as written really only has one effective part (i.e.

determine minimum flow) Once minimum flow is properly determined, the only remaining ability is to determine if 400 is > 360, which is elementary school knowledge (not RO knowledge).

Revised, Question SAT 2 H 3 B E The first bullet is window dressing. It provides no necessary information.

Dont diagnose in the stem.

Dont ask if the RCPs will be running, since it is not an automatic trip. Ask about what is required.

Revised, Question SAT 3 H 3 N S

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 4 H 3 X N U Connection to pump amps is tenuous. Is there some P&L regarding pump amps, or some procedure reference to pump amps?

If reduced inventory means < 16% NC level, how could an applicant eliminate the Greater than or equal to 11% condition?

Dont ask what the crew will or will not do. Ask about requirements.

Revised, Question SAT 5 H 3 N S 6 H 3 N S 7 H 3 B E Dont diagnose in the stem.

In 2nd part of stem, change permit closure to require closure.

Revised, Question SAT The K/A requires the applicant to demonstrate the knowledge that a 8 H 3 X B U feedline break depressurizes the SG similar to a steamline break Contrary to this, the stem gives the applicant that information.

The K/A seems to mean to give pre-trip indications of feedline break then ask applicant to predict post-trip response.

Revised, Question SAT 9 H 3 X M E Change wording in stem to match the words from ECA-0.1, i.e.

change has been established to can be verified.

The dumping steam part of C and D adds nothing to the question.

There are four unique distractors without it.

Since Increase CA flow is common to all distractors, pull it up into the stem.

Revised, Question SAT 10 H 3 N S 11 F 3 N S 12 H 3 M S 13 H 3 N E Dont diagnose in the stem Change the BOP will to the BOP is required to.

Revised, Question SAT

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 14 F 3 N S 15 H 3 B E Use of capability curve to determine that generator excitation must be reduced is double-jeopardy with the first part of SRO question 80.

Change one of these.

Revised, Question SAT 16 F 3 N E Dont diagnose in stem.

Revised, Question SAT 17 F 3 B S Dont diagnose in stem.

Revised, Question SAT 18 F 3 B S 19 F 3 B S 20 F 3 B S Typo in stem. The reason for ... it to prevent should be is to prevent.

Revised, Question SAT 21 H 3 B S 22 H 3 B S 23 F 3 N S 24 F 3 X B U The K/A is the relationship between Hi RCS activity and the rad monitors. Contrary to this, the relationship is given in the stem, not asked. The question asks the candidate to determine the reason for the high activity, which is a fine question, but does not test this K/A.

With this K/A, the question could simply ask the applicant to determine which Rad monitors are useful to identify High Reactor Coolant Activity.

Revised, Question SAT 25 H 3 X B E The first part of the stem is all window dressing. Start with in accordance with . . . The procedure content is not dependent on plant conditions.

Revised, Question SAT

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 26 F 3 X B U The applicant does not need to know anything about PTS response to answer this question. This only tests the normal SI termination sequence. If you choose to test SI termination in accordance with FR-P.1, test aspects of SI termination that are modified because of the PTS challenge.

Revised, Question SAT 27 H 3 N E Dont diagnose in the stem.

Revised, Question SAT 28 H 3 B E The first part of the question is window dressing. Start with Which of the following.

Revised, Question SAT This is an A.2 K/A statement that only tests the (a) portion of the K/A 29 H 4 X N U (predict the impact . . .). This is not acceptable. See the second paragraph of ES-401 D.2.A.

If only testing one part of this K/A, the question must test use procedures to correct, . . .

Revised, Question SAT 30 F 3 N S 31 H S 32 H 3 N E The first bullet is window dressing. All necessary info is found in the 2nd bullet.

Revised, Question SAT 33 H 3 N S 34 H 3 N E Dont diagnose in stem.

Revised, Question SAT 35 H 3 N S 36 H 3 B S 37 L 3 B S 38 L 3 X N U Subset issues. If C is true, A is also true. If D it true, B is also true.

Add some qualifiers.

Revised, Question SAT

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 39 U 3 X B U The first part of the question does not discriminate. It only requires the applicant to know that a tripped fan is replaced by a redundant fan at the same speed. Replacing one tripped fan with four fans is not credible. No specific knowledge of the system is required to determine this.\ Revised, Question SAT 40 L 3 N E The first paragraph is window dressing.

Revised, Question SAT 41 H 3 B E Dont diagnose in stem.

Revised, Question SAT 42 H 3 N S 43 H 3 N S 44 L 3 N E As I understand your explanation, after a 10 minute delay, the program value begins to ramp. This seems inconsistent with saying that the setpoint will change for a period of 10 minutes.

Revised, Question SAT 45 L N E It seems to me that an applicant could defend a trip as an automatic decrease of pump speed.

The sentence Concerning ... adds nothing.

Revised, Question SAT 46 H 3 N E Dont diagnose in stem.

Revised, Question SAT 47 L 3 B S 48 L 3 N S 49 H 3 B S 50 L 3 N S 51 L 3 B S 52 L 3 N S

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 53 H 3 N E Dont diagnose in the stem.

Is it necessary to know containment pressure and sump level to answer this question or make a distrator credible? If not, delete it.

Revised, Question SAT 54 H 3 N S 55 L 3 N E Dont diagnose in the stem.

Revised, Question SAT 56 H 3 N S 57 H 3 N S 58 L 3 N S 59 L 3 X B U Subsets. If A is true, B is also true. If C is true, D is also true. Add qualifiers.

Revised, Question SAT 60 H 3 N U I dont think this is technically correct. It is my understanding that the load rejection controller does not integrate. So it will not control the temperature at 557F, but will generate a demand signal that is proportional to the error (minus the deadband) and control at some value above 557F dependent on decay heat level.

Revised, Question SAT 61 H 3 B S 62 L 3 N S 63 H 3 N S 64 H 3 N S 65 H 4 N S 66 L 3 B E Are you sure that time to MODE 3 in this instance is RO knowledge?

Revised, Question SAT 67 H 3 N S

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 68 L 3 B S 69 L 3 B S 70 H 3 B S 71 H 3 B S 72 H 3 B S 73 L 3 B S 74 L 3 N E The phrase while maintaining a maximum steam pressure negative rate could be misconstrued to mean cooling down as quickly as possible. Reword this to match the words from the procedure.

Revised, Question SAT 75 L 1 N U This is general employee knowledge (if I use equipment, I inventory/inspect it afterward, and the emergency planning manager does not track or inventory fire protection equipment.) The operations end of this K/A is probably in the Appendix R arena.

Revised, Question SAT 76 H 3 N S 77 H 3 N S 78 H 3 N E If stable at 1125 psig in all SGs means that all SGs are steaming, this is inconsistent with no CA flow and stable levels in the intact SGs. Give more realistic indications on the intact SGs.

Revised, Question SAT 79 L 3 B S 80 H 3 N E See Q 15 explanation. If Q 15 is changed to eliminate the double jeopardy, the question is SAT.

Revised, Question SAT

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 81 H 3 N E Dont diagnose in stem.

If increasing SI flow is credible because SGs are not effective heat sinks, provide that symptom in stem (i.e. give RCS and SG pressures).

Revised, Question SAT 82 H 3 M S 83 L 3 N E Why is it necessary to specify the SR channels that are in service?

It is typically only necessary to specify when equipment is NOT in service.

Why does the applicant need to know the position of the VCT outlet valve interlock keyswitches to answer this question?

Revised, Question SAT 84 H 3 N E Dont diagnose in stem.

Revised, Question SAT 85 H 3 B S 86 H 3 X N U An applicant can answer this question with RO knowledge.

Applicability is above the line info. No RCS flow channels are required < P-7.

The premise of the stem is an instrumentation ATWS. Is there a procedure selection here?

Revised, Question SAT 87 H 3 X B U The justification for SRO says it tests assessment and selection of procedure. Contrary to this, this question only asks about how and why to carry out a specific step Revised, Question SAT 88 H 3 N S 89 H 3 N S 90 H 3 N S

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 91 H 3 N U This is not really a basis question as claimed in the submittal. SLC 16.7-4 lists the monitors that are required to be functional above the line. The applicant can answer the SRO only part of the question with above the line info.

Revised, Question SAT 92 H 3 N S 93 L 3 N S 94 L 3 N S 95 H 3 N S 96 M 3 B S 97 H 3 N S 98 H 3 B S 99 L 3 B S 100 L 3 B S

ES-403 Written Examination Grading Form ES-403-1 Quality Checklist Facility: Catawba Date of Exam: 05/2812015 Exam Level: RO [

Item Description Initials a b c

1. Clean answer sheets copied before grading

2. Answer key changes and question deletions justified and documented

3. Applicants scores checked for addition errors (reviewers spot check> 25% of examinations)

4. Grading for all borderline cases (80 +/-2% overall and 70 or 80, as applicable, +/-4% on the SRO-only) reviewed in detail

5. All other failing examinations checked to ensure that grades are justified a

6. Performance on missed questions checked for training deficiencies and wording problems; evaluate validity of

/

questions missed by half or more of the appIicts Printed Name/Signature / Date

a. Grader

b. Facility Reviewer(*)

c. NRC Chief Examiner (*)

(*)

d. NRC Supervisor \2

(*)

The facility reviewers signature is not applicable for examinations graded by the NRC; two independent NRC reviews are required.