ML14282A459

Final Outlines (Folder 3)

ML14282A459
Person / Time
Site:	Susquehanna
Issue date:	07/28/2014
From:	Susquehanna
To:	D'Antonio J Operations Branch I
Shared Package
ML14079A115	List: IR 05000387/2014301 ML14083A036 ML14212A264 ML14220A037 ML14281A555 ML14282A459 ML14282A527 ML14288A319 ML14288A363 ML14288A365 ML15146A419
References
TAC U01896
Download: ML14282A459 (36)

Text

ES-301 Administrative Topics Outline Form ES-301-1 Facility:

SSES Units 1 and 2 Date of Examination:

August 11-22, 2014 Exam Level: RO

• SRO 0 Administrative Topic (see Note)

Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency Procedures/Plan Type Code*

R,M S,D R,M S,N Operating Test No.:

LOC26 Describe activity to be performed Implement Reactor Coolant System Temperature Monitoring, HUR Exceeded (OO.S0.1178.152)

Implement On-Site Class 1 E Operability Test for Inoperable Diesel Generator (24.S0.1475.001)

Review and Verify Blocking Required per NDAP-QA-0322 (OO.AD.327 4.206)

Perform Control Room Actions in Response to Fuel Handling Accident (81.0N.2356.001)

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

• Type Codes & Criteria:

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

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

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

ES-301 Administrative Topics Outline Form ES-301-1 Facility:

SSES Units 1 and 2 Date of Examination:

August 11-22,2014 Exam Level: ROD SRO.

Operating Test No.:

LOC26 Administrative Topic Type Describe activity to be performed (see Note)

Code*

Conduct of Operations R,M Implement Reactor Coolant System Temperature Monitoring, HUR Exceeded (OO.S0.1178.152)

Conduct of Operations S,D Implement On-Site Class 1 E Operability Test for Inoperable Diesel Generator (24.S0.1475.001)

Equipment Control R,M Review and Verify Blocking Required per NDAP-QA-0322 (OO.AD.3274.206)

Radiation Control R,D Respond to SGTS Exhaust High Radiation While Purging Primary Containment (OO.AD.1 018.101)

Emergency Procedures/Plan S,N Classify (scenario)

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

• Type Codes & Criteria:

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

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

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

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:

SSES Units 1 and 2 Date of Examination:

August 11-22, 2014 Exam Level: RO.

SR0-10 SRO-UD Operating Test No.:

LOC26 Control Room Systems@ (8 for RO); (7 for SR0-1); (2 or 3 for SRO-U, including 1 ESF)

System I JPM Title Type Code*

Safety Function

a. Respond to Control Rod Drift In During Performance of A,D,S 1

Rod Exercise Test (55.0N.1998.151)

b. Shutdown RFP Primary Woodward Governor, RFP A,N,S 2

Speed Oscillates (45.0P.1671.151)

c.

Start HPCI in Pressure Control Mode (52.0P.1950.101)

EN,M,S 4

d. Place Shell Warming in Service, Warming Demand A,N,L,S 3

Fails High (93.0P.2440.151)

e.

Vent the Drywell (73.0P.2287.101)

D,P,S 5

f.

Energize ESS Transformer 211, Re-Energize ESS Bus A,EN,N,S 6

2D after Transformer Lockout (04.0P.2529.151)

g. Restore Bypassed Control Rod Position in RWM L,N,S 7

(31.0P.1552.1 01)

h. Perform RBCCW System Flush, RBCCW Pump Trips A,N,S 8

(14.0N.1335.151)

In-Plant Systems@ (3 for RO); (3 for SR0-1); (3 or 2 for SRO-U)

i.

Manual Emergency Shutdown of Diesel Generator A A,D,EN 6

from Panel OC521 A (24.0P.1443.051)

j.

Venting Suppression Chamber without Radiological D,E,EN,R 9

Release Limitations (73.E0.2282.101)

k.

Perform Operator Actions Outside the Control Room in D,E 7

Accordance With ON-1 00-009 (OO.ON.1153.1 02)

All RO and SR0-1 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 I SR0-11 SRO-U (A)Iternate path 4-614-612-3 (C)ontrol room (D)irect from bank

5 91:581:54 (E)mergency or abnormal in-plant 2=112=112=1 (EN)gineered safety feature

- I - I 2=1 (control room system)

(L)ow-Power I Shutdown 2=112=112=1 (N)ew or (M)odified from bank including 1 (A) 2=212=212=1 (P)revious 2 exams

3 I

:; 31::; 2 (randomly selected)

(R)CA 2=112=112=1 (S)imulator

JPM Description JPM A. The monthly control rod exercise is performed. The first 2 control rods are tested with no incident. The 3rd control rod drifts to an intermediate position when an insert signal is applied.

The off-normal procedure for control rod problems is used to insert the control rod to the full-in position.

JPM B. RFP B has just been placed in-service as the second RFP in Flow Control Mode. Speed control is transferred to the Backup Woodward Governor due to concerns with the Primary. After control is transferred RFPT B speed begins oscillating, requiring the RFPT to be tripped to stop the oscillations.

JPM C. A manual startup of the HPCI system is performed for pressure control. HPCI system flow and discharge pressure are to be maximized to initiate a reactor cooldown with MSIVs closed.

JPM D. Unit startup is in progress. Shell warming is returned to service following a planned turbine trip. As HP turbine pressurization begins, the warming demand fails high. Shell warming must be secured or the turbine tripped before a reactor scram on Main Turbine TSV/TCV closure is generated as HP first stage pressure exceeds the RPS scram bypass setpoint.

JPM E. Drywell pressure is elevated with the plant operating at nominal rated power conditions.

SGTS is started and a vent path created to lower Drywell pressure. Once Drywell pressure begins lowering, the vent path is secured.

JPM F. ESS Transformer 201 is to be returned to service following maintenance, with ESS Bus 2D returned to the normal supply. The transformer will be re-energized, but when ESS Bus 2D is transferred the transformer experiences a lockout. ESS Bus 2D is then re-energized from Diesel Generator D.

JPM G. A reactor startup is in progress at less than 5 percent power. A substitute control rod position has been entered for a partially withdrawn control rod with a bad position indication at a specific notch. The control rod has been withdrawn past the position with the bad indication and the substituted position is deleted.

JPM H. A flush of the RBCCW system per G0-1 00-014 for hot weather operation is to be performed. The in-service RBCCW pump trips when the flush is initiated. The standby pump fails to automatically start and must be manually started. The standby pump is air-bound and fails to develop flow, requiring the pump to be vented per the off-normal position.

JPM I. A local emergency stop of Diesel Generator A(B) is to be performed due to loss of cooling water. The emergency stop PB fails to trip the DG. The DG must be stopped by isolating the fuel oil supply.

JPM J. A Station Blackout and LOCA has occurred with Drywell pressure approaching design limits. A vent path from the Suppression Chamber to the Unit 1 Reactor Building is manually established by removal of a ductwork access panel to serve as a vent and manual opening of vent isolation dampers.

JPM K. The Control Room was evacuated due to a fire. Operators failed to scram the Unit 1 reactor before leaving the Control Room. Local actions to scram the reactor and ensure MSIVs remain closed are performed.

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:

SSES Units 1 and 2 Date of Examination:

August 11-22, 2014 Exam Level: RO 0 SR0-1

• SRO-U 0 Operating Test No.:

Control Room Systems@ (8 for RO); (7 for SR0-1); (2 or 3 for SRO-U, including 1 ESF)

System I JPM Title

a. Respond to Control Rod Drift In During Performance of Rod Exercise Test (55.0N.1998.151)

b. Shutdown RFP Primary Woodward Governor, RFP Speed Oscillates (45.0P.1671.151)

c. Start HPCI in Pressure Control Mode (52.0P.1950.101)

d.

Place Shell Warming in Service, Warming Demand Fails High (93.0P.2440.151)

e. Vent the Drywell (73.0P.2287.101)

f.

Energize ESS Transformer 211, Re-Energize ESS Bus 2D after Transformer Lockout (04.0P.2529.151)

h.

Perform RBCCW System Flush, RBCCW Pump Trips (14.0N.1335.151)

In-Plant Systems@ (3 for RO); (3 for SR0-1); (3 or 2 for SRO-U)

i.

Manual Emergency Shutdown of Diesel Generator A from Panel OC521 A (24.0P.1443.051}

j.

Venting Suppression Chamber without Radiological Release Limitations (73.E0.2282.1 01}

k.

Perform Operator Actions Outside the Control Room in Accordance With ON-1 00-009 (OO.ON.1153.1 02)

Type Code*

A,D,S A,N,S EN,M,S A,N,L,S D,P,S A,EN,N,S A,N,S A,D,EN D,E,EN,R D,E LOC26 Safety Function 1

2 4

3 5

6 8

6 9

7 All RO and SR0-1 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 I SR0-1 I SRO-U (A)Iternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank

591:581:54 (E)mergency or abnormal in-plant

~11~11~1 (EN)gineered safety feature

- I - I

~1 (control room system)

(L)ow-Power I Shutdown

~11~11~1 (N)ew or (M)odified from bank including 1 (A)

~21~21~1 (P)revious 2 exams

5 3 I :5 3 I :5 2 (randomly selected)

(R)CA

~11~11~1 (S)imulator

JPM Description JPM A. The monthly control rod exercise is performed. The first 2 control rods are tested with no incident. The 3rd control rod drifts to an intermediate position when an insert signal is applied.

The off-normal procedure for control rod problems is used to insert the control rod to the full-in position.

JPM B. RFP B has just been placed in-service as the second RFP in Flow Control Mode. Speed control is transferred to the Backup Woodward Governor due to concerns with the Primary. After control is transferred RFPT B speed begins oscillating, requiring the RFPT to be tripped to stop the oscillations.

JPM C. A manual startup of the HPCI system is performed for pressure control. HPCI system flow and discharge pressure are to be maximized to initiate a reactor cooldown with MSIVs closed.

JPM D. Unit startup is in progress. Shell warming is returned to service following a planned turbine trip. As HP turbine pressurization begins, the warming demand fails high. Shell warming must be secured or the turbine tripped before a reactor scram on Main Turbine TSV/TCV closure is generated as HP first stage pressure exceeds the RPS scram bypass setpoint.

JPM E. Drywell pressure is elevated with the plant operating at nominal rated power conditions.

SGTS is started and a vent path created to lower Drywell pressure. Once Drywell pressure begins lowering, the vent path is secured.

JPM F. ESS Transformer 201 is to be returned to service following maintenance, with ESS Bus 2D returned to the normal supply. The transformer will be re-energized, but when ESS Bus 2D is transferred the transformer experiences a lockout. ESS Bus 2D is then re-energized from Diesel Generator D.

JPM G. A reactor startup is in progress at less than 5 percent power. A substitute control rod position has been entered for a partially withdrawn control rod with a bad position indication at a specific notch. The control rod has been withdrawn past the position with the bad indication and the substituted position is deleted.

JPM H. A flush of the RBCCW system per G0-1 00-014 for hot weather operation is to be performed. The in-service RBCCW pump trips when the flush is initiated. The standby pump fails to automatically start and must be manually started. The standby pump is air-bound and fails to develop flow, requiring the pump to be vented per the off-normal position.

JPM I. A local emergency stop of Diesel Generator A(B) is to be performed due to loss of cooling water. The emergency stop PB fails to trip the DG. The DG must be stopped by isolating the fuel oil supply.

JPM J. A Station Blackout and LOCA has occurred with Drywell pressure approaching design limits. A vent path from the Suppression Chamber to the Unit 1 Reactor Building is manually established by removal of a ductwork access panel to serve as a vent and manual opening of vent isolation dampers.

JPM K. The Control Room was evacuated due to a fire. Operators failed to scram the Unit 1 reactor before leaving the Control Room. Local actions to scram the reactor and ensure MSIVs remain closed are performed.

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:

SSES Units 1 and 2 Date of Examination:

August 11-22, 2014 Exam Level: RO 0 SR0-1 0 SRO-U

• Operating Test No.:

Control Room Systems© (8 for RO); (7 for SR0-1); (2 or 3 for SRO-U, including 1 ESF)

System I J PM Title

b.

Shutdown RFP Primary Woodward Governor, RFP Speed Oscillates (45.0P.1671.151)

C.

d. Place Shell Warming in Service, Warming Demand Fails High (93.0P.2440.151)

e.

f.

Energize ESS Transformer 211, Re-Energize ESS Bus 20 after Transformer Lockout (04.0P.2529.151)

j.

Venting Suppression Chamber without Radiological Release Limitations (73.E0.2282.1 01)

k. Perform Operator Actions Outside the Control Room in Accordance With ON-1 00-009 (OO.ON.1153.1 02)

Type Code*

A,N,S A,N,L,S A,EN,N,S D,E,EN,R D,E LOC26 Safety Function 2

3 6

9 7

All RO and SR0-1 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 I SR0-1/ SRO-U (A)Iternate path 4-6/4-612-3 (C)ontrol room (D)irect from bank

g{

;;81

;;4 (E)mergency or abnormal in-plant

<:1/<:11<:1 (EN)gineered safety feature

- I -

I <:1 (control room system)

(L)ow-Power I Shutdown

<:1/<:1/<:1 (N)ew or (M)odified from bank including 1 (A)

<:2/<:21<:1 (P)revious 2 exams

3/

::; 3 I:::; 2 (randomly selected)

(R)CA

<:1/<:11<:1 (S)imulator

JPM Description JPM A The monthly control rod exercise is performed. The first 2 control rods are tested with no incident. The 3rd control rod drifts to an intermediate position when an insert signal is applied.

The off-normal procedure for control rod problems is used to insert the control rod to the full-in position.

JPM B. RFP B has just been placed in-service as the second RFP in Flow Control Mode. Speed control is transferred to the Backup Woodward Governor due to concerns with the Primary. After control is transferred RFPT B speed begins oscillating, requiring the RFPT to be tripped to stop the oscillations.

JPM C. A manual startup of the HPCI system is performed for pressure control. HPCI system flow and discharge pressure are to be maximized to initiate a reactor cooldown with MSIVs closed.

JPM D. Unit startup is in progress. Shell warming is returned to service following a planned turbine trip. As HP turbine pressurization begins, the warming demand fails high. Shell warming must be secured or the turbine tripped before a reactor scram on Main Turbine TSV/TCV closure is generated as HP first stage pressure exceeds the RPS scram bypass setpoint.

JPM E. Drywell pressure is elevated with the plant operating at nominal rated power conditions.

SGTS is started and a vent path created to lower Drywell pressure. Once Drywell pressure begins lowering, the vent path is secured.

JPM F. ESS Transformer 201 is to be returned to service following maintenance, with ESS Bus 2D returned to the normal supply. The transformer will be re-energized, but when ESS Bus 2D is transferred the transformer experiences a lockout. ESS Bus 2D is then re-energized from Diesel Generator D.

JPM G. A reactor startup is in progress at less than 5 percent power. A substitute control rod position has been entered for a partially withdrawn control rod with a bad position indication at a specific notch. The control rod has been withdrawn past the position with the bad indication and the substituted position is deleted.

JPM H. A flush of the RBCCW system per G0-1 00-014 for hot weather operation is to be performed. The in-service RBCCW pump trips when the flush is initiated. The standby pump fails to automatically start and must be manually started. The standby pump is air-bound and fails to develop flow, requiring the pump to be vented per the off-normal position.

JPM I. A local emergency stop of Diesel Generator A(B) is to be performed due to loss of cooling water. The emergency stop PB fails to trip the DG. The DG must be stopped by isolating the fuel oil supply.

JPM J. A Station Blackout and LOCA has occurred with Drywell pressure approaching design limits. A vent path from the Suppression Chamber to the Unit 1 Reactor Building is manually established by removal of a ductwork access panel to serve as a vent and manual opening of vent isolation dampers.

JPM K. The Control Room was evacuated due to a fire. Operators failed to scram the Unit 1 reactor before leaving the Control Room. Local actions to scram the reactor and ensure MSIVs remain closed are performed.

Appendix D Scenario Outline Form ES-D-1

(

Facility:

SSES Units 1 and 2 Scenario No.:

1 Op-Test No.:

LOC26 Examiners:

Operators:

Initial Conditions Unit 1 95 percent power for control rod pattern adjustment, EOL HPCI OOSVC, DG E substituted for DG A (IC-380)

Turnover RFP lube oil conditioner swapped from A to B last shift Control rods 42-15 and 46-19 declared slow last scram time test Severe thunderstorm watch in effect Event Malf.

Event Event No.

No.

Type*

Description 1

N/A R

Withdraw control rods to raise reactor power 3 percent SRO,ATC (OP-AD-338, G0-1 00-012) 2 N/A N

Place CRD Pump B in-service, secure CRD Pump A SRO,BOP (OP-155-001) 3 mfFW145 c

RFPT B vibration rises, reduce RFPT speed to lower 0078 SRO,ATC vibration (AR-1 01-A 16) 4 mfFW145 C (ON)

RFPT B trips on high vibration, Recirc LIM2 runback 0078 All (ON-164-002) cmfTR03 -

I (TS)

APRM 2 and 3 Recirc Loop A drive flows fail high during 5

FT831 1N014C SRO,ATC Recirc LIM2 runback (TS 3.3.1.1) cmfAV04_

c RBCCW TCV fails, ESW placed in-service to restore 6

TV11028 SRO,BOP RBCCW cooling (ON-114-001), ESW loop declared inoperable when aligned to RBCCW (TS 3.7.2) rfCU161001 RWCU fails to automatically isolate on high temperature, 7

rfC.U161009 I

cmfMVOG SRO,ATC manual isolation successful (AR-1 01-A01)

HV144F004 8

mfRD155 M

Hydraulic-block ATWS (E0-1 00-113, OP-145-005, 017 ALL ES-158-002) cmfPM03 -

SLC pump trips after start, standby SLC pump 9

1P208A c

cmfPM03 -

SRO,BOP successfully injects boron (OP-153-001) 1P2088 10 cmfTR01 I

Wide Range level instrument fails, RFP flow must be LT14201A SRO,ATC raised to maintain reactor level in ATWS band 11 mfFW148 c

In-service RFPT trips after first scram, RCIC restored to 002 ALL maintain RPV level while standby RFPT placed in-service

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

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

Scenario Actual Events Attributes

1.

Total malfunctions (5-8) 3,6,7,9,10,11 6

2. Malfunctions after EOP entry (1-2) 9,10,11 3

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

4. Major transients (1-2) 8 1

5. EOPs entered/requiring substantive actions (1-2)

E0-100-102 1

6. EOP contingencies requiring substantive actions (0-2)

E0-100-113 1

7. Critical tasks (2-3) 3 CT -1 Inject SLC CT -2 Lowers RPV level to < -60" but > -161" CT-3 Inserts control rods lAW E0-100-113 Sht. 2

(

Appendix D Scenario Outline Form ES-D-1

(

Facility:

SSES Units 1 and 2 Scenario No.:

2 Op-Test No.:

LOC26 Examiners:

Operators:

Initial Conditions Unit 1 80 percent power starting up from forced outage, 80L HPCIOOSVC Turnover Swap RFP A main lube oil pumps RFP lube oil conditioner being swapped from A to 8 Control rods 42-15 and 46-19 declared slow last scram time test Severe thunderstorm watch in effect Event Malf.

Event Event No.

No.

Type*

Description 1

N/A N

Swap RFP A main lube oil pumps (OP-145-003)

SRO,BOP

(

2 rfDB105106 c

18227 feeder trips (AR-016-804) and is inoperable All (TS 3.8. 7), re-energize RPS B from alternate (ON-158-001) 3 cmfPM02 c

RFP A main lube oil pump trips due to FME 1P124A(B)

SRO,ATC (AR-120-A03), RFP A manually secured (OP-145-001) 4 N/A R

Reduce power to< 65 percent using recirc flow and SRO,ATC control rods to secure RFP A (OP-AD-338) cmfRL01 I

MSL flow transmitter fails high causing MSIV half-5 B211K3B TS isolation (TS 3.6.1.3)

SRO cmfRL02 Insert manual scram on loss of Feedwater (only 1 RFP 6

C721K6A-D I

in-service), RPS low-level auto-scram is failed (OP-AD-cmfPM02 SRO,ATC 1P124C-D 004) 7 rfDS0010xx M

Loss of offsite power on reactor scram (ON-104-001) crfAB03_xx ALL 8

mfDG024 c

Diesel Generator 8 fails to automatically start, manual 0018 SRO,BOP start from Control Room successfu I (ON-1 04-001) mfRR164 9

010 M

Drywell LOCA (E0-102, E0-103) mfRR164 ALL 011A cmfRV02_

I ADS auto-initiation fails, perform Rapid Depressurization 10 PSV141 F13G-N ALL (E0-112)

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

Event No.

11 12 Malf.

No.

cmfMV06_

HV152 FOOSA cmfRL01_

E111Kxxx cmfMV06_

HV151 F015B Event Type*

ALL ALL Event Description Division 1 Core Spray injection valve fails to automatically open, can be manually opened from Control Room Division 2 RHR LPCI initiation logic fails to initiate, manual alignment to LPCI required

• (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes (Per Scenario; See Section D.5.d)

Scenario Actual

1. Total malfunctions (5-8)

2. Malfunctions after EOP entry (1-2)

3. Abnormal events (2-4)

4. Major transients (1-2)

5. EOPs entered/requiring substantive actions (1-2)

6. EOP contingencies requiring substantive actions (0-2)

7. Critical tasks (2-3)

CT-1 Rapid Depressurization at TAF CT-2 Manually align Division 1 Core Spray and Division 2 RHR for reactor vessel injection Events Attributes 2,3,6,8, 10,11' 7

12 8,10,11,12 4

2,6 2

7,9 2

E0-100-102 2

E0-100-103 E0-100-102 (ALC) 2 E0-100-112 2

Appendix D Scenario Outline Form ES-D-1

• Facility:

SSES Units 1 and 2 Scenario No.:

3 Op-Test No.:

LOC26 Examiners:

Operators:

Initial Conditions Unit 1 33 percent power shutting down for DW RCS leak, MOL HPCIOOSVC Turnover Insert control rods, then test Turbine Bypass valve #3 RFP lube oil conditioner being swapped from A to B Control rods 42-15 and 46-19 declared slow last scram time test Event Malf.

Event Event No.

No.

Type*

Description 1

N/A R

Insert control rods (OP-156-001, OP-AD-338)

SRO,ATC 2

N/A N

Test turbine bypass valve #3 (S0-182-001)

SRO,BOP

(

cmfHX02_

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

1E102C SRO,BOP heater extraction steam (ON-147-002), TS MCPR limits not applicable (TS 3.2.2).

4 cmfPM04_

I Diesel Generator C spurious start without cooling, OP504C SRO,BOP manual ESW initiation required cmfEB01 -

ESS Bus 1 C lockout, DW leak severity rises, reactor 5

1A203 I

mfRR164 SRO,ATC scram required (ON-104-203, TS 3.8.7) 010 6

mfRP158 M

Electrical ATWS (E0-100-113), ARI inserts control rods 003 ALL 7

mfRR179 c

Fuel failure with high MSL radiation, MSIV isolation 003 ALL required (AR-1 03-001, AR-1 04-001) 8 cmfMV06 I

RCIC injection valve fails to open on initiation HV149F013 SRO,ATC (OP-150-001) 9 mfRC150 M

Unisolable RCS leak into Secondary Containment, 2 004 ALL areas above Max Safe radiation (E0-1 00-1 04) cmfMV01 RCIC steam isolation valves fail to automatically close 10 HV149F007 I

(AR-108-F04,F05), manual isolation successful after cmfMV09 SRO,BOP HV149F008 reactor pressure reduced

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

(

(

(

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

1. Total malfunctions (5-8)

2. Malfunctions after EOP entry (1-2)

3. Abnormal events (2-4)

4. Major transients (1-2)

5. EOPs entered/requiring substantive actions (1-2)

6. EOP contingencies requiring substantive actions (0-2)

7. Critical tasks (2-3)

CT-1 Manually initiate ARt.

CT-2 Rapidly depressurize the reactor when two Secondary Containment Areas exceed Max Safe Rad levels.

Scenario Actual Events Attributes 3,4,5,7,8,10 6

7,8,10 3

3,5 2

6,9 2

E0-100-102 3

E0-100-104 E0-100-113 2

E0-100-112 2

Appendix D Scenario Outline Form ES-D-1

(

Facility:

SSES Units 1 and 2 Scenario No.:

5 Op-T est No.:

LOC26 Examiners:

Operators:

Initial Conditions Unit 1 Mode 2, 3 percent power, 500 psig Turnover Place RFP in-service in DPM in AUTO per OP-145-001 Control rods 42-15 and 46-19 declared slow last scram time test Severe thunderstorm watch in effect Event Malt.

Event Event No.

No.

Type*

Description 1

N/A N

Place RFP in-service in Discharge Pressure Mode SRO,BOP

( OP-145-001) 2 N/A R

Withdraw control rods to raise reactor power SRO,ATC (OP-AD-338, G0-100-002) mfLS155 I

3 0145435

{TS)

Inoperable control rod position indication (TS 3.1.3)

SRO,ATC set fx10 I

Startup level control bypass valve HV-1 0640 controller 4

SULC B9.

fails to maximum demand, take manuc;~l control OUT=100 SRO,ATC (ON-145-001)

IMF c

Aux Bus 11 B lockout, Start Condensate Pump C to 5

cmfRL02 maintain 2-pump Condensate alignment with RFP 86A1102 SRO,BOP in-service (ON-103-003. OP 144-001) cmfFU01 I

6 1C618FU21 (TS)

RCIC Division 2 initiation logic power loss (TS 3.3.5.1)

SRO 7

cmfRL01 c

Spurious MSIV closure, insert a manual scram due to B211K7x ALL loss of the normal heat sink (ON-100-101) 8 mfMS183 c

Drywell LOCA, place Suppression Chamber spray in-007 ALL service to cool Primary Containment (OP-149-004) cmfMV01 -

c RHR Suppression Chamber cooling isolation valve 9

HV151 breaker trips, place other division of RHR in Suppression F028x SRO,BOP Chamber spray (OP-149-004) 10 mfRH149 M

Unisolable Suppression Pool leak (E0-100-103, 112) 004x ALL

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

(

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

1. Total malfunctions (5-8)

2. Malfunctions after EOP entry (1-2)

3. Abnormal events (2-4)

4. Major transients (1-2)

5. EOPs entered/requiring substantive actions (1-2)

6. EOP contingencies requiring substantive actions (0-2)

7. Critical tasks (2-3)

CT-1 Isolate HPCI when Suppression Pool level cannot be maintained above 17 feet.

CT-2 Rapidly Depressurize the reactor when Suppression Pool level cannot be maintained above 12 feet.

Scenario Actual Events Attributes 4,5,7,8,9 5

8,9 2

4,5 2

10 1

E0-100-102 2

E0-100-103 E0-100-112 1

2

ES-401 BWR Examination Outline Form ES-401-1 Facility: SSES Units 1 and 2 Date of Exam:

08/22/14 {LOC26)

RO KIA Category Points SRO-Only Points Tier Group K

K K

K K

K A

A A

A G

1 2

3 4

5 6

1 2

3 4

Total A2 G*

Total

1.

1 4

3 4

3 3

3 20 3

4 7

Emergency 2

1 1

1 1

2 1

7 2

1 3

Plant Tier Evolutions Totals 5

4 5

4 5

4 27 5

5 10 1

3 3

1 3

3 3

2 2

2 2

2 26 2

3 5

2.

Plant 2

1 1

1 1

1 1

1 1

1 1

2 12 0

1 2

3 Systems Tier Totals 4

4 2

4 4

4 3

3 3

3 4

38 3

5 8

3. Generic Knowledge & Abilities 1

2 3

4 1

2 3

4 10 7

Categories 3

2 3

2 1

2 2

2 Note:

1.

Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KIA category shall not be less than two).

2.

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

3.

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

4.

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

5.

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

6.

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

7.*

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

8.

On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (IR) for the applicable license level, and the point totals (#)for each system and category. Enter the group and tier totals for each category in the table above. If fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.

9.

For Tier 3, select topics from Section 2 of the KIA Catalog, and enter the KIA numbers, descriptions, IRs, and point totals(#) on Form ES-401-3. Limit SRO selections to KIAs that are linked to 1 OCFR55.43

ES-401 2

Form ES-401-1 BWR Examination Outline Emer enc and Abnormal Plant Evolutions-Tier 1 Grou EAPE #I Name Safety Function K1 K2 K3 A1 A2 G

KIA Topic(s)

IR Q#

AA2.04-Ability to determine and interpret the following as they 600000 Plant Fire On-site I 8 X

apply to PLANT FIRE ON SITE: The 3.1 76 fire's extent of potential operational damage to plant equipment AA2.01 -Ability to determine and/or interpret the following as they apply to 700000 Generator Voltage and X

GENERATOR VOLTAGE AND 3.6 77 Electric Grid Disturbances ELECTRIC GRID DISTURBANCES:

Operating point on the generator capability curve.

AA2.02-Ability to determine and/or 295005 Main Turbine Generator X

interpret the following as they apply to 2.7 78 Trip /3 MAIN TURBINE GENERATOR TRIP :

Turbine vibration 295030 Low Suppression Pool 2.4.41 - Emergency Procedures I Plan:

X Knowledge of the emergency action 4.6 79 Water Level/ 5 level thresholds and classifications.

295037 SCRAM Conditions 2.4.35-Emergency Procedures I Plan:

Present and Reactor Power X

Knowledge of local auxiliary operator 4.0 80 Above APRM Downscale or tasks during emergency and the Unknown /1 resultant operational effects.

2.4.4 - Emergency Procedures I Plan:

Ability to recognize abnormal 295021 Loss of Shutdown X

indications for system operating 4.7 81 Cooling /4 parameters which are entry-level conditions for emergency and abnormal operating procedures.

295019 Partial or Total Loss of 2.1.19 - Conduct of Operations: Ability lnst. Air /8 X

to use plant computers to evaluate 3.8 82 system or component status.

EK1.01 - Knowledge of the operational 295028 High Drywell implications of the following concepts as X

they apply to HIGH DRYWELL 3.5 39 Temperature I 5 TEMPERATURE : Reactor water level measurement AK1.01 -Knowledge of the operational implications of the following concepts as 700000 Generator Voltage and they apply to GENERATOR VOLTAGE X

AND ELECTRIC GRID 3.3 40 Electric Grid Disturbances DISTURBANCES and the following:

Definition of terms: volts, watts, amps, VARs, power factor.

AK1.04 - Knowledge of the operational 295021 Loss of Shutdown X

implications of the following concepts as 3.6 41 Cooling /4 they apply to LOSS OF SHUTDOWN COOLING : Natural circulation AK2.01 - Knowledge of the 600000 Plant Fire On-site I 8 X

interrelations between PLANT FIRE 2.6 42 ON SITE and the following: Sensors, detectors and valves AK2.02-Knowledge of the 295005 Main Turbine X

interrelations between MAIN TURBINE 2.9 43 Generator Trip I 3 GENERATOR TRIP and the following:

Feedwater temperature EK2.15 - Knowledge of the 295031 Reactor Low Water X

interrelations between REACTOR LOW 3.2 44 Level/2 WATER LEVEL and the following: A.C.

distribution: Plant-Specific AK3.03-Knowledge of the reasons for 295016 Control Room X

the following responses as they apply to 3.5 45 Abandonment I 7 CONTROL ROOM ABANDONMENT :

Disabling control room controls

ES-401 3

Form ES-401-1 BWR Examination Outline Emer enc and Abnormal Plant Evolutions-Tier 1 Grou EAPE #I Name Safety Function K1 K2 K3 A1 A2 G

KIA Topic(s)

IR Q#

EK3.01 -Knowledge of the reasons for 295037 SCRAM Conditions the following responses as they apply to Present and Reactor Power X

SCRAM CONDITION PRESENT AND 4.1 46 Above APRM Downscale or REACTOR POWER ABOVE APRM Unknown /1 DOWNSCALE OR UNKNOWN :

Recirculation pump trip/runback EK3.03-Knowledge of the reasons for 295038 High Off-site Release X

the following responses as they apply to 3.7 47 Rate /9 HIGH OFF-SITE RELEASE RATE:

Control room ventilation isolation EA 1.03-Ability to operate and/or 295026 Suppression Pool High monitor the following as they apply to X

SUPPRESSION POOL HIGH WATER 3.9 48 Water Temp. I 5 TEMPERATURE: Temperature monitoring AA 1.01 -Ability to operate and/or 295004 Partial or Total Loss of monitor the following as they apply to DC Pwr /6 X

PARTIAL OR COMPLETE LOSS OF 3.3 49 D.C. POWER : D.C. electrical distribution systems AA 1.01 -Ability to operate and/or 295018 Partial or Total Loss of monitor the following as they apply to CCW/8 X

PARTIAL OR COMPLETE LOSS OF 3.3 50 COMPONENT COOLING WATER :

Backup systems EA2.03-Ability to determine and/or 295030 Low Suppression Pool X

interpret the following as they apply to 3.9 51 Water Level/ 5 LOW SUPPRESSION POOL WATER LEVEL: Reactor pressure AA2.05 - Ability to determine and/or 295001 Partial or Complete interpret the following as they apply to Loss of Forced Core Flow X

PARTIAL OR COMPLETE LOSS OF 3.1 52 Circulation I 1 & 4 FORCED CORE FLOW CIRCULATION

Jet pump operability: Not-BWR-1&2 EA2.06-Ability to determine and/or 295024 High Drywell Pressure X

interpret the following as they apply to 4.1 53 15 HIGH DRYWELL PRESSURE:

Suppression pool temperature 295023 Refueling Accidents I 8 X

2.4.18 Knowledge of the specific bases 3.3 54 for EOPs.

2.4.49-Emergency Procedures I Plan:

295003 Partial or Complete Ability to perform without reference to Loss of AC /6 X

procedures those actions that require 4.6 55 immediate operation of system components and controls.

2.4.9-Emergency Procedures I Plan:

295019 Partial or Total Loss of Knowledge of low power I shutdown lnst. Air /8 X

implications in accident (e.g., loss of 3.8 56 coolant accident or loss of residual heat removal) mitigation strategies.

EK1.04 - Knowledge of the operational 295025 High Reactor Pressure X

implications of the following concepts as 3.9 57

/3 they apply to HIGH REACTOR PRESSURE : Decay heat generation AK3.06-Knowledge of the reasons for 295006 SCRAM /1 X

the following responses as they apply to 3.2 58 SCRAM : Recirculation pump speed reduction: Plant-Specific KIA Category Totals:

4 3

4 3

3/3 3/4 Group Point Total:

I 20/7

ES-401 4

Form ES-401-1 BWR Examination Outline Emer enc and Abnormal Plant Evolutions-Tier 1 Grou EAPE #I Name Safety Function K1 K2 K3 A1 A2 G

KIA Topic(s)

IR Q#

AA2.03-Ability to determine and/or 295020 Inadvertent Cont.

X interpret the following as they apply to 3.7 83 Isolation I 5 & 7 INADVERTENT CONTAINMENT ISOLATION : Reactor power 2.4.21 - Emergency Procedures I Plan:

Knowledge of the parameters and logic used to assess the status of safety 295002 Loss of Main X

functions, such as reactivity control, core 4.6 84 Condenser Vac I 3 cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.

AA2.03-Ability to determine and/or 295022 Loss of CRD Pumps I 1 X

interpret the following as they apply to 3.2 85 LOSS OF CRD PUMPS : CRD mechanism temperatures AK1.04-Knowledge of the operational 295002 Loss of Main implications of the following concepts as Condenser Vacuum X

they apply to LOSS OF MAIN 3.0 59 CONDENSER VACUUM : Increased offgas flow.

AK2.14 - Knowledge of the 295017 High Off-site Release X

interrelations between HIGH OFF-SITE 4.0 60 Rate I 9 RELEASE RATE and the following:

PCIS/NSSSS EK3.07 - Knowledge of the reasons for 500000 High CTMT Hydrogen the following responses as they apply to X

HIGH PRIMARY CONTAINMENT 3.1 61 Cone. I 5 HYDROGEN CONCENTRATIONS:

Operation of drywell vent AA 1.07-Ability to operate and/or 295008 High Reactor Water X

monitor the following as they apply to 3.4 62 Level I 2 HIGH REACTOR WATER LEVEL : Main turbine: Plant-Specific AA2.02 - Ability to determine and/or 295022 Loss of CRD Pumps I X

interpret the following as they apply to 3.3 63 1

LOSS OF CRD PUMPS : CRD system status 295007 High Reactor Pressure X

2.4.6-Emergency Procedures I Plan:

3.7 64

/3 Knowledge of EOP mitigation strategies.

EA2.03 -Ability to determine and/or 295029 High Suppression Pool X

interpret the following as they apply to 3.4 65 Water Level I 5 HIGH SUPPRESSION POOL WATER LEVEL : Drywell/containment water level KIA Category Totals:

1 1

1 1

212 1/1 Group Point Total:

I 7/3

ES-401 5

Form ES-401-1 BWR Examination Outline Emer enc and Abnormal Plant Evolutions-Tier 2 Grou System #I Name K

K K

K K

K A

A A

A G

KIA Topic(s)

IR Q#

1 2

3 4

5 6

1 2

3 4

A2.02-Ability to (a) predict the impacts of the following on the D.C. ELECTRICAL DISTRIBUTION ; and (b) based 263000 DC Electrical X

on those predictions, use 2.9 86 Distribution procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of ventilation during charging A2.01 -Ability to (a) predict the impacts of the following on the LOW PRESSURE CORE SPRAY SYSTEM ; and (b) based on 209001 LPCS X

those predictions, use procedures 3.4 87 to correct, control, or mitigate the consequences of those abnormal conditions or operations: Pump trips 262001 AC Electrical 2.1.32 -Conduct of Operations:

Distribution X

Ability to explain and apply all 4.0 88 system limits and precautions.

223002 PCIS/Nuclear Steam 2.2.40- Equipment Control: Ability Supply Shutoff X

to apply technical specifications 4.7 89 for a system.

400000 Component Cooling X

2.1.20 -Ability to interpret and 4.6 90 Water execute procedure steps.

K1.02 - Knowledge of the physical connections and/or 215004 Source Range cause-effect relationships X

between SOURCE RANGE 3.4 1

Monitor MONITOR (SRM) SYSTEM and the following: Reactor manual control K1.08 - Knowledge of the physical connections and/or cause-effect 205000 Shutdown Cooling X

relationships between 3.9 2

SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) and the following: LPCI K2.02-Knowledge of electrical 212000 RPS X

power supplies to the following:

2.7 3

Analog trip system logic cabinets K2.01 -Knowledge of electrical 239002 SRVs X

power supplies to the following:

2.8 4

SRV solenoids K6.05 - Knowledge of the effect that a loss or malfunction of the 259002 Reactor Water Level X

following will have on the 3.5 5

Control REACTOR WATER LEVEL CONTROL SYSTEM : Reactor water level input K3.01 - Knowledge of the effect that a loss or malfunction of the 211000 SLC X

STANDBY LIQUID CONTROL 4.3 6

SYSTEM will have on following:

Ability to shutdown the reactor in certain conditions

ES-401 6

Form ES-401-1 BWR Examination Outline Emer enc and Abnormal Plant Evolutions Tier 2 Grou K

K K

K K

K A

A A

A G

KIA Topic(s)

IR Q#

System #I Name 1

2 3

4 5

6 1

2 3

4 K4.02-Knowledge of D.C.

ELECTRICAL DISTRIBUTION design feature(s) and/or interlocks 263000 DC Electrical X

which provide for the following:

3.1 7

Distribution Breaker interlocks, permissives, bypasses and cross ties: Plant-Specific K4.02 - Knowledge of AUTOMATIC DEPRESSURIZATION SYSTEM 218000 ADS X

design feature(s) and/or interlocks 3.8 8

which provide for the following:

Allows manual initiation of ADS logic K5.01 - Knowledge of the operational implications of the X

following concepts as they apply 2.6 9

2150031RM to INTERMEDIATE RANGE MONITOR (IRM) SYSTEM :

Detector operation K5.02 - Knowledge of the operational implications of the X

following concepts as they apply 2.8 10 206000 HPCI to HIGH PRESSURE COOLANT INJECTION SYSTEM : Turbine shaft sealino: BWR-2,3,4 K6.02 - Knowledge of the effect that a loss or malfunction of the 262002 UPS (AC/DC)

X following will have on the 2.8 11 UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) : D.C.

electrical power K6.04 - Knowledge of the effect that a loss or malfunction of the following will have on the 217000 RCIC X

REACTOR CORE ISOLATION 3.5 12 COOLING SYSTEM (RCIC):

Condensate storage and transfer system A 1.01 -Ability to predict and I or 400000 Component Cooling monitor changes in parameters X

associated with operating the 2.8 13 Water CCWS controls including: CCW flow rate A 1.09-Ability to predict and/or monitor changes in parameters associated with operating the 203000 RHRILPCI: Injection X

RHRILPCI: INJECTION MODE 2.9 14 Mode (PLANT SPECIFIC) controls including: Component cooling water systems A2.05 -Ability to (a) predict the impacts of the following on the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF ;

223002 PCIS/Nuclear Steam X

and (b) based on those 3.3 15 Supply Shutoff predictions, use procedures to correct, control, or mitigate the consequences of those abn cond or ops. Nuclear boiler instrumentation failures

ES-401 7

Form ES-401-1 BWR Examination Outline Emer enc and Abnormal Plant Evolutions - Tier 2 Grou System # I Name K

K K

K K

K A

A A

A G

KIA Topic(s)

IR Q#

1 2

3 4

5 6

1 2

3 4

A2.02 -Ability to (a) predict the impacts of the following on the AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM ;

215005 APRM I LPRM X

and (b) based on those 3.6 16 predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions : Upscale or downscale trips A3.04 -Ability to monitor automatic operations of the EMERGENCY GENERATORS 264000 EDGs X

(DIESEUJET) including:

3.1 17 Operation of the governor control system on frequency and voltage control A3.02 -Ability to monitor 262001 AC Electrical X

automatic operations of the A. C.

3.2 18 Distribution ELECTRICAL DISTRIBUTION includinq: Automatic bus transfer A4.01 -Ability to manually 300000 Instrument Air X

operate and/or monitor in the 2.6 19 control room: Pressure aauaes A4.04-Ability to manually 261000 SGTS X

operate and/or monitor in the 3.3 20 control room: Primary containment pressure 2.4.46-Emergency Procedures I 209001 LPCS X

Plan: Ability to verify that the 4.2 21 alarms are consistent with the plant conditions.

2.4.2 -Emergency Procedures I Plan: Knowledge of system set 217000 RCIC X

points, interlocks and automatic 4.5 22 actions associated with EOP entry conditions.

K2.02 - Knowledge of electrical 206000 HPCI X

power supplies to the following:

2.8 23 System pumps: BWR-2,3,4 K5.02 - Knowledge of the 262001 AC Electrical operational implications of the Distribution X

following concepts as they apply 2.6 24 to A. C. ELECTRICAL DISTRIBUTION: Breaker control K1.01 - Knowledge of the physical connections and/or cause-effect 261000 SGTS X

relationships between STANDBY 3.4 25 GAS TREATMENT SYSTEM and the following: Reactor building ventilation system K4.01 - Knowledge of CCWS 400000 Component Cooling X

design feature(s) and or interlocks 3.4 26 Water which provide for the following:

Automatic start of standby pump KIA Category Totals:

3 3

2 3

3 2

2 2/2 2 2 2/3 Group Point Total:

I 26/5

ES-401 8

Form ES-401-1 BWR Examination Outline Emer enc and Abnormal Plant Evolutions -Tier 2 Grou System #I Name K

K K

K K

K A

A A

A G

KIA Topic(s)

IR Q#

1 2

3 4

5 6

1 2

3 4

A2.11 -Ability to (a) predict the impacts of the following on the RHRILPCI: CONTAINMENT 226001 RHRILPCI:

SPRAY SYSTEM MODE ; and Containment Spray System X

(b) based on those predictions, 3.0 91 use procedures to correct, Mode control, or mitigate the consequences of those abnormal conditions or operations: Motor operated valve failures 2.4.34 -Emergency Procedures I Plan: Knowledge of RO tasks 241000 Reactor/Turbine X

performed outside the main 4.1 92 Pressure Regulator control room during an emergency and the resultant operational effects.

234000 Fuel Handling 2.2.12-Equipment Control:

X Knowledge of surveillance 4.1 93 Equipment procedures.

K1.05-Knowledge of the physical connections and/or 215002 RBM X

cause-effect relationships 3.0 27 between ROD BLOCK MONITOR SYSTEM and the following: Four rod display: BWR-3,4,5 K2.01 - Knowledge of electrical 201001 CRD Hydraulic X

power supplies to the following:

2.9 28 Pumps K3.15 - Knowledge of the effect 239001 Main and Reheat that a loss or malfunction of the X

MAIN AND REHEAT STEAM 3.5 29 Steam SYSTEM will have on following:

Reactor water level control K4.03 - Knowledge of FIRE PROTECTION SYSTEM design 286000 Fire Protection X

feature(s) and/or interlocks which 3.3 30 provide for the following:

Maintenance of fire header pressure K5.05 - Knowledge of the operational implications of the 201003 Control Rod and X

following concepts as they apply 3.0 31 Drive Mechanism to CONTROL ROD AND DRIVE MECHANISM : Reverse power effect K6.05-Knowledge of the effect that a loss or malfunction of the 204000 RWCU X

following will have on the 2.6 32 REACTOR WATER CLEANUP SYSTEM : A. C. power A 1.01 -Ability to predict and/or monitor changes in parameters 230000 RHRILPCI:

associated with operating the X

RHRILPCI:

3.8 33 Torus/Pool Spray Mode TORUS/SUPPRESSION POOL SPRAY MODE controls including:

Suppression chamber pressure

ES-401 9

Form ES-401-1 BWR Examination Outline Emer enc and Abnormal Plant Evolutions - Tier 2 Grou System # I Name K

K K

K K

K A

A A

A G

KIA Topic(s)

IR Q#

1 2

3 4

5 6

1 2

3 4

A2.06 -Ability to (a) predict the impacts of the following on the RHRILPCI: CONTAINMENT SPRAY SYSTEM MODE ; and 226001 RHRILPCI: CTMT X

(b) based on those predictions, 2.8 34 Spray Mode use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: D.C.

electrical failures A3.01 -Ability to monitor 271000 Off-gas X

automatic operations of the 3.3 35 OFFGAS SYSTEM including:

Automatic system isolations A4.07 - Ability to manually 241 000 Reactor/Turbine X

operate and/or monitor in the 3.5 36 Pressure Regulator control room: Main stop/throttle valves (operation) 2.2.42-Equipment Control: :

Ability to recognize system 201006 RWM X

parameters that are entry-level 3.9 37 conditions for Technical Specifications.

290002 Reactor Vessel 2.2.40- Equipment Control:

Internals X

Ability to apply technical 3.4 38 specifications for a system.

KIA Category Totals:

1 1

1 1

1 1

1 1/1 1

1 2/2 Group Point Total:

I 12/3

ES-401 Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-3 Facility: SSES Units 1 and 2 Date of Exam:

08/22/14 (LOC26)

RO SRO-Only Category KIA#

Topic IR Q#

IR Q#

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

Knowledge of procedures, guidelines, or 2.1.37 limitations associated with reactivity 4.3 66

1.

management.

Conduct Ability to interpret reference materials, such of Operations 2.1.25 as graphs, curves, tables, etc.

3.9 67 2.1.28 Knowledge of the purpose and function of 4.1 75 major system components and controls.

Subtotal 3

1 2.2.23 Ability to track Technical Specification limiting 4.6 95 conditions for operations.

2.2.19 Knowledge of maintenance work order 3.4 98 requirements.

2.

2.2.39 Knowledge of less than one hour technical 3.9 68 Equipment specification action statements for systems.

Control Ability to determine the expected plant 2.2.15 configuration using design and configuration 3.9 69 control documentation, such as drawings, line-ups, tag-outs, etc.

Subtotal 2

2 Knowledge of radiation or containment 2.3.14 hazards that may arise during normal, 3.8 96 abnormal, or emergency conditions or activities.

2.3.6 Ability to approve release permits.

3.8 100 Knowledge of Radiological Safety

3.

Procedures pertaining to licensed operator Radiation 2.3.13 duties, such as response to radiation monitor 3.4 70 Control alarms, containment entry requirements, fuel handling responsibilities, access to locked high radiation areas, aligning filters, etc.

2.3.4 Knowledge of radiation exposure limits under 3.2 71 normal or emergency conditions.

2.3.11 Ability to control radiation releases.

3.8 74 Subtotal 3

2 Knowledge of the bases for prioritizing 2.4.23 emergency procedure implementation during 4.4 97 emergency operations.

2.4.32 Knowledge of operator response to loss of all 4.0 99

4.

annunciators.

Emergency Ability to diagnose and recognize trends in Procedures I 2.4.47 an accurate and timely manner utilizing the 4.2 72 Plan appropriate control room reference material.

Knowledge of the bases for prioritizing safety 2.4.22 functions during abnormal/emergency 3.6 73 operations.

Subtotal 2

2 Tier 3 Point Total 10 7

ES-401 Record of Rejected K/As Form ES-401-4 Tier I Group Randomly Reason for Rejection Selected KIA Question 91 Originally selected KIA Ability to (a) predict the impacts of the following on the TRAVERSING IN-CORE PROBE ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Failure to retract during accident conditions: Mark-1&11 (Not-BWR1)

SRO 215001 A2.07 Unable to write a discriminating question at the SRO level 2/2 Traversing for this KIA. Randomly re-sampled system due to low In-core Probe discriminatory potential for TIPs and randomly sampled A2 KIA.

226001 RHRILPCI: Containment Spray System Mode A2.11 -Ability to (a) predict the impacts of the following on the RHRILPCI: CONTAINMENT SPRAY SYSTEM MODE; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Motor operated valve failures (3.0)

Question 76 Originally selected K/A Ability to determine and interpret the following as they apply to PLANT FIRE ON SITE: Whether malfunction is SRO 600000 AA2.07 due to common-mode electrical failures 1 /1 Plant Fire on Site Unable to write a psychometrically sound question related to the KIA at the SRO level. Replaced with randomly sampled KIA within original E/APE.

AA2.04 -Ability to determine and interpret the following as they apply to PLANT FIRE ON SITE: The fire's extent of potential operational damage to plant equipment (3.1)

Question 90 Originally selected KIA Emergency Procedures I Plan: Knowledge of the specific SRO 400000 2.4.12 bases for EOPs 2/1 Component Cooling Water Lack of information related to the CCW systems precluded writing a psychometrically sound question on this KIA.

Replaced with randomly sampled KIA within original system.

2.1.20- Ability to interpret and execute procedure steps.

(4.6)

ES-401 Record of Rejected K/As Form ES-401-4 Tier I Group Randomly Reason for Rejection Selected KJA Question 100 Originally selected KIA Ability to approve release permits.

SRO 2.3 Radiation 3

Control 2.3.6 Rejected due to overlap with already administered audit examination operating test item. Replaced with randomly sampled K/A within Section 2.3.

2.3.6-Knowledge of radiation exposure limits under normal or emergency conditions.

Question 57 Originally selected KIA Knowledge of the operational implications of the following concepts as they apply to HIGH REACTOR RO 295025 EK1.01 PRESSURE : Pressure effects on reactor power 1 /1 High Reactor Pressure Rejected due to KIA sampled on 2013 LOC25 NRC exam, unable to develop a significantly modified question.

Replaced with randomly sample KIA within EK1.

EK1.03 - Knowledge of the operational implications of the following concepts as they apply to HIGH REACTOR PRESSURE : Decay heat generation Question 6 Originally selected K/A Knowledge of the effect that a loss or malfunction of the STANDBY LIQUID CONTROL SYSTEM will have on following: Core plate differential pressure indication RO 211000 K3.03 2/1 SLC Rejected due to overlap on 2013 LOC25 NRC exam, unable to develop a significantly modified question. Replaced with randomly sample KIA within K3.

K3.01 - Knowledge of the effect that a loss or malfunction of the STANDBY LIQUID CONTROL SYSTEM will have on following: Ability to shutdown the reactor in certain conditions

ES-401 Record of Rejected K/As Form ES-401-4 Tier I Group Randomly Reason for Rejection Selected KIA Question 16 Originally selected K/A 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 RO 215005 A2.07 conditions: Recirculation flow channels flow mismatch 2/1 APRM I LPRM Rejected due to overlap with operating test scenario LOC26-NRC-1, Event 5. Replaced with randomly sample KIA within A2.

A2.02 -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: Upscale or downscale trips Question 51 Originally selected K/A Ability to determine and/or interpret the following as they 295030 EA2.02 apply to LOW SUPPRESSION POOL WATER LEVEL :

RO Low Suppression Suppression pool temperature 1 /1 Pool Water Level Rejected due to overlap with Question 48. Replaced with randomly sample KIA within EA2.

EA2.03 -Ability to determine and/or interpret the following as they apply to LOW SUPPRESSION POOL WATER LEVEL: Reactor pressure Question 54 Originally selected K/A RO 295023 2.4.41 Emergency Procedures I Plan: Knowledge of the 1 /1 Refueling emergency action level thresholds and classifications.

Accidents Rejected due to SRO-Ievel knowledge and abilities required for this KIA. Replaced with randomly-sampled generic K/A.

2.4.18 Knowledge of the specific bases for EOPs.

ES-401 Record of Rejected K/As Form ES-401-4 Tier I Group Randomly Reason for Rejection Selected KIA Question 59 Originally selected K/A Knowledge of the operational implications of the following concepts as they apply to HIGH SUPPRESSION 295013 AK1.01 POOL TEMPERATURE : Pool stratification.

RO High Suppression 1/2 Rejected due to overlap with RO questions 48 and 53, and Pool Temperature SRO question 82. Randomly sampled Tier 1 Group 2 APE 295002, Loss of Main Condenser Vacuum, to replace 295013.

Randomly sampled AK1 under 295013 to obtain new KIA.

AK1.04 - Knowledge of the operational implications of the following concepts as they apply to LOSS OF MAIN CONDENSER VACUUM: Increased offgas flow.

Question 2 Originally selected K/A Knowledge of the physical connections and/or cause-effect relationships between SHUTDOWN COOLING 205000 K1.05 SYSTEM (RHR SHUTDOWN COOLING MODE) and the RO Shutdown following: Component cooling water systems 2/1 Cooling Rejected due to overlap with RO question 13, 14, and SRO question 90. Replaced with randomly sample KIA within K1.

K1.08 - Knowledge of the physical connections and/or cause-effect relationships between SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) and the following: LPCI Question 24 Originally selected K/A Knowledge of the operational implications of the following concepts as they apply to the INSTRUMENT AIR SYSTEM: Air compressors RO 300000 K5.01 Rejected due to overlap on 2013 LOC25 NRC exam. Due to 2/1 Instrument Air small number of K5 topics in 300000, randomly resampled for new Tier 2 Group 1 system and obtained 262001 A.C.

Electrical Distribution. Randomly sampled K5 and obtained KIA K5.02 - Knowledge of the operational implications of the following concepts as they apply to A.C. ELECTRICAL DISTRIBUTION: Breaker control

ES-401 Record of Rejected Kl As Form ES-401-4 Tier I Group Randomly Reason for Rejection Selected KIA Question 47 Originally selected K/A Knowledge of the reasons for the following responses as 295038 EK3.01 they apply to HIGH OFF-SITE RELEASE RATE:

RO High Off-site Implementation of site emergency plan 1 /1 Release Rate Rejected due to SRO-Ievel knowledge and abilities required for this KIA. Replaced with randomly-sampled K/A from EK3:

EK3.03 - Knowledge of the reasons for the following responses as they apply to HIGH OFF-SITE RELEASE RATE: Control room ventilation isolation Question 30 Originally selected K/A K4.07 - Knowledge of FIRE PROTECTION SYSTEM design feature(s) and/or interlocks which provide for the RO 286000 K4.07 following: Diesel engine protection 2/2 Fire Protection Rejected due to could not develop a question with reliable discrimination validity. Replaced with randomly-sampled KIA from K4:

K4.03 - Knowledge of FIRE PROTECTION SYSTEM design feature(s) and/or interlocks which provide for the following:

Maintenance of fire header pressure Question 9 Originally selected K/A K5.06 - Knowledge of the operational implications of the following concepts as they apply to HIGH PRESSURE COOLANT INJECTION SYSTEM : Turbine speed RO 206000 K5.06 measurement 2/1 HPCI Rejected due to could not develop a question with reliable discrimination validity. Replaced with randomly-sampled KIA from K5:

K5.02 - Knowledge of FIRE PROTECTION SYSTEM design feature(s) and/or interlocks which provide for the following: Turbine shaft sealing

ES-401 Record of Rejected K/As Form ES-401-4 Tier I Group Randomly Reason for Rejection Selected KJA Question 28 Originally selected K/A K2.02 - Knowledge of electrical power supplies to the RO 201001 CRD following: Scram valve solenoids 2/2 Hydraulic Rejected due to question due to overlap with written and operating exam topics. Replaced with randomly-sampled KIA from K2:

K2.01 - Knowledge of electrical power supplies to the following: Pumps Question 5 Originally selected KIA K3.07 - Knowledge of the effect that a loss or malfunction of the REACTOR WATER LEVEL CONTROL SYSTEM will have on following: Reactor water level 259002 Reactor indication RO 2/1 Water Level Question did not match originally selected KIA; on Chief Control System Examiner direction selected KIA to match question due to high level of discriminatory and operational validity of question. Replaced with appropriate K/A within 259002:

K6.05 - Knowledge of the effect that a loss or malfunction of the following will have on the REACTOR WATER LEVEL CONTROL SYSTEM :Reactor water level input

ES-401 Site-Specific SRO Written Examination Cover Sheet Form ES-401-8 U.S. Nuclear Regulatory Commission Site-Specific SRO Written Examination Applicant Information Name:

Date: August 22, 2014 Facility/Unit: SSES Units 1 and 2 Region:

I

• II D Ill D IV D Reactor Type: W D CE D BW D GE

• Start Time:

Finish Time:

Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination you must achieve a final grade of at least 80.00 percent overall, with 70.00 percent or better on the SRO-only items if given in conjunction with the RO exam; SRO-only exams given alone require a final grade of 80.00 percent to pass. You have 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to complete the combined examination, and 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> if you are only taking the SRO portion.

Applicant Certification All work done on this examination is my own. I have neither given nor received aid.

Applicant's Signature Results RO/SRO-Only/Total Examination Values

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Points Applicant's Scores

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Points Applicant's Grade

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