ML12047A159

2011 Clinton Power Station Initial License Examination Miscellaneous Outline Forms

ML12047A159
Person / Time
Site:	Clinton
Issue date:	08/29/2011
From:	Bielby M Operations Branch III
To:	Exelon Nuclear
Shared Package
ML11354A098	List: ML120250581 ML12046A837 ML12047A114 ML12047A159 U-604006, 2011 Clinton Power Station Initial License Examination Outline Submittal Letter
References
ES-301, ES-301-1
Download: ML12047A159 (18)

Text

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Clinton Date of Examination: 08/22/2011 Examination Level: RO SRO Operating Test Number: 2011-301 Administrative Topic Type Describe activity to be performed (See Note) Code*

Complete an SRV Actuation Report Conduct of Operations R,D JPM 407 2.1.18/3.6 Perform Offsite Source Power Verification Conduct of Operations S,D JPM 441 2.1.31/4.6 Print Reading - Tagout Verification Equipment Control S,N JPM 442 2.2.41/3.5 Read Survey Map Radiation Control R,D,P JPM 410 2.3.7/3.5 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

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Clinton Date of Examination: 08/22/2011 Examination Level: RO SRO Operating Test Number: 2011-301 Administrative Topic Type Describe activity to be performed (See Note) Code*

Review of H2 Igniter Temperature Test Conduct of Operations R,N JPM 443 2.1.07/4.7 Review a Completed SRV Actuation Report Conduct of Operations R,D JPM 444 2.1.32/4.0 Print Reading - Tagout Verification Equipment Control S,N JPM 445 2.2.41/3.9 Redirect Worker in a High Radiation Area Radiation Control R,D,P JPM 115 2.3.12/3.7 ERO Activation Emergency Procedures/Plan R,D JPM 446 2.4.38/4.4 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

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Clinton Date of Examination: 8/22/2011 Exam Level: RO SRO-I SRO-U Operating Test Number: 2011-301

@

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. 202001 A4.01 3.7 / JPM 448 Transfer RR Fast to Slow M,S 1

b. 217000 A4.04 3.6 / JPM 204 Manually Startup RCIC System A,D,EN,L,S 2

c. 239001 A4.01 4.2 / JPM 447 RPS MSIV Channel Functional D,S 3

d. 203000 A4.02 4.1 / JPM 440 Inject with SX through RHR B A,N,S,L 4

e. 226001 A4.03 3.5 / JPM 207 Place RHR Loop B in Containment Spray A,D,EN,L,P, 5 Mode S

f. 264000 A4.04 3.7 / JPM 414 Parallel a Diesel A,D,P,S 6

g. 212000 A4.14 3.8 / JPM 449 Reset a SCRAM D,L,S 7

h. 261000 A2.05 3.0 / JPM 206 Standby Gas Treatment (VG) Startup A,D,S 9

@

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

i. 209001 2.4.34 4.2 / JPM 210 Manually Open the LPCS Injection Valve D,E,L,R 2

j. 262002 2.1.30 4.4 / JPM 026 Manual Transfer of Distribution Panel Loads D,R 6 (NSPS Solenoid/RPS) from ALTERNATE POWER to INVERTER

k. 400000 A1.04 2.8 / JPM 031 Makeup of CCW Expansion Tank D,R 7

@ 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 (C)ontrol room (D)irect from bank <9 / <8 / <4 (E)mergency or abnormal in-plant >1 / >1 / >1 (EN)gineered safety feature - / - / > 1 (control room system (L)ow-Power / Shutdown >1 / >1 / >1 (N)ew or (M)odified from bank including 1(A) >2 / >2 / >1 (P)revious 2 exams <3/ <3 / < 2 (randomly selected)

(R)CA >1 / >1 / >1 (S)imulator ES-301, Page 23 of 27

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Clinton Date of Examination: 8/22/2011 Exam Level: RO SRO-I SRO-U Operating Test Number: 2011-301

@

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. 202001 A4.01 3.7 / JPM 448 Transfer RR Fast to Slow M,S 1

b. 217000 A4.04 3.6 / JPM 204 Manually Startup RCIC System A,D,EN,L,S 2

c. 239001 A4.01 4.0 / JPM 447 RPS MSIV Channel Functional D,S 3

d. 203000 A4.02 4.1 / JPM 440 Inject with SX through RHR B A,N,S,L 4

e. 226001 A4.03 3.4 / JPM 207 Place RHR Loop B in Containment Spray A,D,EN,L,P, 5 Mode S

f. 264000 A4.04 3.7 / JPM 414 Parallel a Diesel A,D,P,S 6 g.

h. 261000 A2.05 3.1 / JPM 206 Standby Gas Treatment (VG) Startup A,D,S 9

@

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

i. 209001 2.4.34 4.1 / JPM 210 Manually Open the LPCS Injection Valve D,E,L,R 2

j. 262002 2.1.30 4.0 / JPM 026 Manual Transfer of Distribution Panel Loads D,R 6 (NSPS Solenoid/RPS) from ALTERNATE POWER to INVERTER

k. 400000 A1.04 2.8 / JPM 031 Makeup of CCW Expansion Tank D,R 7

@ 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 (C)ontrol room (D)irect from bank <9 / <8 / <4 (E)mergency or abnormal in-plant >1 / >1 / >1 (EN)gineered safety feature - / - / > 1 (control room system (L)ow-Power / Shutdown >1 / >1 / >1 (N)ew or (M)odified from bank including 1(A) >2 / >2 / >1 (P)revious 2 exams <3/ <3 / < 2 (randomly selected)

(R)CA >1 / >1 / >1 (S)imulator ES-301, Page 23 of 27

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Clinton Date of Examination: 8/22/2011 Exam Level: RO SRO-I SRO-U Operating Test Number: 2011-301

@

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.

c.

d. 203000 A4.02 4.1 / JPM 440 Inject with SX through RHR B A,N,S,L 4

e. 226001 A4.03 3.4 / JPM 207 Place RHR Loop B in Containment Spray A,D,EN,L,P, 5 Mode S f.

g.

h. 261000 A2.05 3.1 / JPM 206 Standby Gas Treatment (VG) Startup A,D,S 9

@

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

i. 209001 2.4.34 4.1 / JPM 210 Manually Open the LPCS Injection Valve D,E,L,R 2

j. 262002 2.1.30 4.0 / JPM 026 Manual Transfer of Distribution Panel Loads D,R 6 (NSPS Solenoid/RPS) from ALTERNATE POWER to INVERTER 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 (C)ontrol room (D)irect from bank <9 / <8 / <4 (E)mergency or abnormal in-plant >1 / >1 / >1 (EN)gineered safety feature - / - / > 1 (control room system (L)ow-Power / Shutdown >1 / >1 / >1 (N)ew or (M)odified from bank including 1(A) >2 / >2 / >1 (P)revious 2 exams <3/ <3 / < 2 (randomly selected)

(R)CA >1 / >1 / >1 (S)imulator ES-301, Page 23 of 27

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Clinton Date of Exam: 08/22/2011 Operating Test Number: 2011-301 A E Scenarios P V 1 2 3 4 P E T M L N CREW CREW CREW CREW O I I T POSITION POSITION POSITION POSITION T N C A I A T S A B S A B S A B S A B L M N Y R T O R T O R T O R T O U T P O C P O C P O C P O C P M(*)

E R I U RX 2 2 2 1 1 0 RO 1 1 1 NOR I1 1 1 2 SRO-I I/C 3,4,5,7 3,5 4,8 8 4 4 2 SRO-U MAJ 8,9,10 7,8,9,10 9,10,11 10 2 2 1 TS 4,6 2 0 2 2 RX 2 2 2 1 1 0 RO 1 1 1 NOR I2 1 1 2 SRO-I I/C 3,5 3,4,5,6 5,7 8 4 4 2 SRO-U MAJ 8,9,10 7,8,9,10 9,10,11 10 2 2 1 TS 5,6 2 0 2 2 RX 2 2 2 1 1 0 RO 1

I3 NOR 1 1 2 1 1 SRO-I I/C 4,7 4,6 4,5,7,8 8 4 4 2 SRO-U MAJ 8,9,10 7,8,9,10 9,10,11 10 2 2 1 TS 3,6 2 0 2 2 RX 1 1 0 RO NOR 1 1 1 SRO-I I/C 4 4 2 SRO-U 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 serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for 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, Page 26 of 27

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Clinton Date of Exam: 08/22/2011 Operating Test Number: 2011-301 A E Scenarios P V 1 2 3 4 P E T M L N CREW CREW CREW CREW O I I T POSITION POSITION POSITION POSITION T N C A I A T S A B S A B S A B S A B L M N Y R T O R T O R T O R T O U T P O C P O C P O C P O C P M(*)

E R I U RX 2 1 1 1 0 RO U1 1 1 1 NOR 1 1 SRO-I I/C 4,5,7,8 4 4 4 2 SRO-U MAJ 9,10,11 3 2 2 1 TS 3,6 2 0 2 2 RO RX 2 2 2 1 1 0 NOR 1 1 1 I4 SRO-I 1 1 4 4 2 SRO-U I/C 3,4,5,7 4,6 6 MAJ 8,9,10 7,8,9,10 7 2 2 1 TS 4,6 2 0 2 2 RX 2 2 2 1 1 0 RO I5 NOR 1 1 2 1 1 1 SRO-I I/C 4,7 3,4,5,6 4,8 8 4 4 2 SRO-U MAJ 8,9,10 7,8,9,10 9,10,11 10 2 2 1 TS 5,6 2 0 2 2 RO RX 2 1 1 1 0 1 1 1 NOR R1 SRO-I 1 1 2 4 4 2 SRO-U I/C 3,5 3,5 5,7 6 MAJ 8,9,10 7,8,9,10 9,10,11 10 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 serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for 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, Page 26 of 27

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Clinton Date of Exam: 08/22/2011 Operating Test Number: 2011-301 A E Scenarios P V 1 2 3 4 P E T M L N CREW CREW CREW CREW O I I T POSITION POSITION POSITION POSITION T N C A I A T S A B S A B S A B S A B L M N Y R T O R T O R T O R T O U T P O C P O C P O C P O C P M(*)

E R I U RO RX 2 2 2 1 1 0 U2 SRO-I NOR 1 1 2 1 1 1 4 4 2 SRO-U I/C 3,4,5,7 3,4,5,6 8 MAJ 8,9,10 7,8,9,10 7 2 2 1 TS 4,6 5,6 4 0 2 2 RX 2 1 1 1 0 RO R2 1 1 1 NOR 1 1 SRO-I I/C 4,7 4,6 4 4 4 2 SRO-U MAJ 8,9,10 7,8,9,10 7 2 2 1 TS 0 0 2 2 RX 2 1 1 1 0 RO R3 1 1 1 NOR 1 1 SRO-I I/C 3,5 3,5 4 4 4 2 SRO-U MAJ 8,9,10 7,8,9,10 7 2 2 1 TS 0 0 2 2 RX 1 1 0 RO NOR 1 1 1 SRO-I I/C 4 4 2 SRO-U 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 serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for 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, Page 26 of 27

Appendix D Scenario Outline Form ES-D-1 Facility: Clinton Power Station Scenario No.: One Operating Test No.: 2011-301 Examiners: ____________________________ Operators: ____________________

____________________________ ____________________

____________________________ ____________________

Initial Conditions:

• Subcritical ~600 psig, Hot Restart in progress.

• A Thunderstorm Watch is in effect. Thunderstorms are expected in the area within the next hour.

• Suppression Pool Cleanup and Transfer Pump 1B (1SF01PB) is OOS for a motor bearing replacement.

Turnover:

• Continue Hot Restart. Pull Rods to criticality.

• Test the Generator Emergency Seal Oil Pump per CPS 3109.01 Section 8.1.2.3 - First Priority.

Event Malf. No. Event Event No. Type* Description 1 N/A N-BOP Test the Generator Emergency Seal Oil Pump.

SRO 2 NA R-ATC Withdraw rods to criticality.

SRO 3 ROD3637TFIA4 C-ATC Control Rod 36-37 is difficult to withdraw.

SRO 4 HP01HP_1E22C0 C-BOP HPCS Water Leg Pump shaft shears.

03_MTFSHEAR 1 TS-SRO 5 SRM_BI_ACTIO I-ATC B SRM fails.

N2 and 1 SRO 6 A05_A02_A0608 TS-SRO SLC A OOS (Loss of Power to SLC Suction Valve A From SLC

_6_TVM Storage Tank - 1C41-F001A).

H_A05_A02_A13 S15_2 H_A05_A02_A13 DS27_1 7 CDSR_VAC_PM C-BOP Vacuum Pump Trip.

P_A SRO 8 YARITPLA_1 M-All RCIC unisolable steam leak.

Override 9 YP_XMFTB_496 M-All Auto Scram failure.

4 10 YP_XMFTB_409 M-All MDRFP Trip.

4

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor 1 of 3 2/16/2012

Appendix D Scenario Outline Form ES-D-1 Scenario No.: One Operating Test No.: 2011-301 Narrative Summary Event # Description

1. The BOP Operator will coordinate with the field operator to test the Generator Emergency Seal Oil Pump per CPS 3109.01 Section 8.1.2.3.

2. The ATC Operator will continue the Hot Restart. First milestone this shift will be withdrawing control rods to criticality.

3. Rod 36-37 will indicate a failure to move upon the ATC Operators initial attempt to withdraw it. The ATC Operator must increase drive water pressure to free the rod per CPS 3304.01 Section 8.3.4.

4. Annunciator HPCS WATER LEG PUMP DISCHARGE PRESSURE LOW (5062-7D) comes in due to the HPCS Water Leg Pump shaft shear. The BOP Operator will dispatch a field operator to investigate. Upon the report of a shaft shear, the BOP operator will stop the HPCS Water Leg Pump and direct the field operator to pull the HPCS Pump Breaker control power fuses per CPS 3309.01 Section 4.3. Technical Specification LCO 3.5.1 Actions B.1 and B.2 will be evaluated requiring verification by administrative means that the RCIC system is operable when required AND the HPCS system is restored to operable status within 14 days.

5. Annunciator ROD OUT BLOCK (5006-2H), SRM UPSC ALARM OR INOP (5005-1K), SRM PERIOD (5005-2K) and SRM DNSC (5005-3K) come in due to SRM B failing downscale. The B SRM channel must be bypassed per CPS 3306.01 Section 8.2.2 to clear the rod block and proceed with the startup. Technical Specification 3.3.1.4 action A.1 and ORM 2.2.2 Action 3.2.2.a will be evaluated and found to be satisfied.

6. Annunciator STANDBY LIQUID CONTROL OUT OF SERVICE (50677-8F) comes in along with postage stamp C001A or F001A PWR LOSS or OVLD due to a loss of power to SLC Suction Valve A From SLC Storage Tank - 1C41-F001A. The valves green indicating light is dark. The BOP Operator will dispatch a field operator to investigate. Technical Specifications LCO 3.1.7, Action A. will be evaluated which will require that the SLC subsystem be restored to operable within 7 days.

7. Annunciator AUTO TRIP PUMP/MOTOR (5019-1A) comes in due to a trip of the Condenser Vacuum Pump 1A (0CA01PA). The BOP Operator notes that the trip is NOT due to Hi MSL Rad and starts the standby Condenser Vacuum Pump per CPS 3112.01 Section 8.1.1.

8. Multiple annunciators are received due to The RCIC steam supply line develops a leak causing the RCIC room temperature to rise resulting in an EOP-8 entry. A scram is required prior to exceeding the Maximum safe temperature.

9. When a Reactor Scram is attempted, an Auto Scram failure occurs due to a fault in the Reactor Protection system. The ATC Operator must perform a manual initiation of the SCRAM OR ARI to insert the control rods.

2 of 3 2/16/2012

Appendix D Scenario Outline Form ES-D-1

10. The MDRFP (1FW01PC) trips due to an actuation of the breakers (1AP05EF) C phase protective relay. The ATC Operator must restore feedwater by either opening the RFP 1A/1B Discharge Bypass Valve (1FW003A/B) or coordinating with the BOP operator to open the Feed Pump Bypass Valve (1FW024).

EOP 8,1A,1 Critical tasks:

• Manual initiation of Reactor Scram prior to exceeding Maximum safe temperature.

• Maintain RPV water level >TAF. Restore and control RPV water level to a band of Level 3 to Level 8.

3 of 3 2/16/2012

Appendix D Scenario Outline Form ES-D-1 Facility: Clinton Power Station Scenario No.: Two Operating Test No.: 2011-301 Examiners: ____________________________ Operators: ____________________

____________________________ ____________________

____________________________ ____________________

Initial Conditions:

• 72% power, power ascension in progress.

• A Thunderstorm Watch is in effect. Thunderstorms are expected in the area within the next hour.

• Suppression Pool Cleanup and Transfer Pump 1B (1SF01PB) is OOS for a motor bearing replacement.

Turnover:

• Raise Reactor Power to 96% using a combination of rods and flow.

• RCIC Surveillance 9054.01 was completed last shift. RHR B is currently in Suppression Pool Cooling to support the RCIC surveillance and is no longer required. Secure Suppression Pool Cooling per CPS 3312.01 Section 8.1.10 - First Priority.

Event Malf. No. Event Type* Event No. Description 1 N/A N-BOP Secure from Suppression Pool Cooling.

SRO 2 N/A R-ATC Raise Reactor Power to 96% using a combination of rods and flow.

SRO 3 YFFWPP C-BOP MC pump 1B coupling fails.

SS_13 1 4 A01_A08 I-ATC Hot well overflow level control valve failure.

_A01_1 SRO 5 YP_XMF C-BOP Train A Control Room Supply Fan (0VC03CA) trips.

TB_5010 TS-SRO 6 YPRR15 I-ATC FWLC level control RPV level instrument fails high.

AA TS-SRO 7 RAT_A_ M-All RAT A trips on Differential Overcurrent. A circuit breaker supplying DIFFER the HPCS injection valve (1E22F004) trips open.

ENTIAL 8 YPXMA M-All An unisolable RR loop leak develops and the RCIC turbine will trip LSE_511 when started and cannot be reset.

9 N/A M-All When RPV water level reaches TAF, enter EOP-3 and blowdown.

Recover and restore RPV level IAW EOP-3.

10 YP- M-All RHR B Pump fails to auto start. Pump will operate as intended by XMFTB_ handswitch manipulation.

4948

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor 1 of 3 2/16/2012

Appendix D Scenario Outline Form ES-D-1 Scenario No.: Two Operating Test No.: 2011-301 Narrative Summary Event # Description

1. The BOP Operator will secure Suppression Pool Cooling per CPS 3312.01 Section 8.1.10.

2. The ATC Operator will raise reactor power to 96% using a combination of control rods and reactor coolant flow.

3. Annunciator LOW PRESS MAKE-UP COND XFER PUMPS DISCH HDR (5014-2C) comes in due to the Make-Up Condensate Transfer Pump 1B (0MC01PB) shaft shear.

The BOP Operator will dispatch a field operator to investigate. Upon the report of a shaft shear, the BOP operator will stop the failed pump and start the standby pump per CPS 3208.01 Section 8.1.1 (or 8.2.2).

4. Annunciator NOT FULLY CLOSED CDSR EMERG O/FLOW VLV 1CD020 (5014-4B) is received or an Operator notes Hot well Level is lowering. Upon discovery, the ATC Operator recognizes the failure of the Hot well Level Control Valve to control in automatic and takes manual control per CPS 3104.01 Section 8.6.1.

5. Annunciator AUTO TRIP PUMP/FAN DIVISION 1 (5050-1A) comes in due to the Train A Control Room Supply Fan (0VC03CA) tripping. The BOP Operator will coordinate with the field operator to shift Control Room HVAC (VC) to Train B per CPS 3402.01 Section 8.1.7. Technical Specification LCO 3.7.3 Actions A.1 will be evaluated requiring restoration of control room ventilation subsystem to an operable status within 7 days. Technical Specification LCO 3.7.4 Actions A.1 will also be evaluated requiring restoration of control room AC subsystem to an operable status within 30 days.

6. Annunciator WTR LVL SIG FAILURE (5002-2P) comes in due to the A channel feedwater level control RPV level instrument failing high. Upon discovery, the ATC Operator will swap feedwater controls to the operable (B) channel. Technical Specification ORM Action 2.2.12.b will also be evaluated requiring restoration of the inoperable channel to an operable status within 7 days.

7. Multiple annunciators are received due to the A Reserve Auxiliary Transformer (RAT A) tripping on Differential Overcurrent. Concurrent with this event, the circuit breaker supplying the HPCS injection valve (1E22F004) trips open on overcurrent.

8. Immediately following the Scram Choreography, an unisolable RR loop leak develops.

The RCIC turbine will trip when started and cannot be reset. This failure completes a loss of all major high pressure feed sources.

9. Reactor Pressure Vessel (RPV) water level will lower until it reaches Top of Active Fuel (TAF). At that time the CRS will enter EOP-3, blowdown, recover and restore RPV level per EOP-3.

2 of 3 2/16/2012

Appendix D Scenario Outline Form ES-D-1

10. The B RHR Pump (1E12AC002B) fails to automatically start. The BOP Operator must manually start the B RHR Pump to maximize injection of available sources per EOP-1.

EOP 1,3,6 Critical tasks:

• Enter EOP-3, Blowdown.

• Maximizes injection to recover level above TAF. Restore and control RPV water level to a band of Level 3 to Level 8.

3 of 3 2/16/2012

Appendix D Scenario Outline Form ES-D-1 Facility: Clinton Power Station Scenario No.: Three Operating Test No.: 2011-301 Examiners: ____________________________ Operators: ____________________

____________________________ ____________________

____________________________ ____________________

Initial Conditions:

• 96% power, steady state operation.

• A Thunderstorm Watch is in effect. Thunderstorms are expected in the area within the next hour.

• Suppression Pool Cleanup and Transfer Pump 1B (1SF01PB) is OOS for a motor bearing replacement.

Turnover:

• MISO has declared a grid emergency and requested that CPS lower generator output by 100 MWe over the next hour.

• Secure Division 2 Diesel Generator (DG 1B) from CPS 9080.02, DG 1B Operability - Manual and Quick Start Operability, by performing Section 8.3.1 through 8.3.7 - First Priority.

Event Malf. No. Event Event No. Type* Description 1 N/A N-BOP Secure DG 1B.

2 N/A R-ATC Lower Reactor Power/Generator Output with flow.

SRO 3 Annunc TS-SRO Low DG Starting Air Pressure.

4 LC08A C-ATC Clogged Oil Filter - CB Pump 1A.

SRO 5 CW06A C-BOP Auto Trip of B CCW Pump.

SRO 6 YP_XMF TS-SRO C APRM fails downscale.

TB_4914 7 YPXMA I-BOP TGLO Temperature Controller Failure.

LSE_612 8 Override C-ATC B RWCU pump seal plate temperature high.

9 Override M-All A Inboard MSIV drifts shut/Group 1 Isolation/Rx Scram.

10 Override M-All Rx Coolant Leak.

11 Override M-All During B/D, 2 SRVs fail to open.

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor 1 of 3 2/16/2012

Appendix D Scenario Outline Form ES-D-1 Scenario No.: Three Operating Test No.: 2011-301 Narrative Summary Event # Description

1. CPS 9080.02, DG 1B Operability - Manual and Quick Start Operability, has been completed. The BOP operator will secure DG 1B and place it back in standby.

2. The ATC Operator will lower reactor power/generator output using reactor coolant flow.

3. Annunciator OUT OF SERVICE DIESEL GEN 1B (5061-7F) comes in due to low Starting Air Pressure (190 psig). The BOP operator will dispatch a field operator to investigate. No cause will be evident. Technical Specification 3.8.3, Action E.1 will be evaluated requiring starting air receiver pressure be restored to 200 psig within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

4. Annunciator CLOGGED OIL FILTER CONDENSATE BOOSTER PUMP 1A (5001-1H) comes in due to a clogged CUNO filter. The ATC Operator will dispatch a field operator to clear the alarm. Attempts are unsuccessful and the ATC Operator will startup the standby condensate booster pump and shutdown the affected pump per the Annunciator Response Procedure (ARP).

5. Annunciator AUTO TRIP PUMP/MOTOR (5040-1B) and RECIRC MTR A/B WDG CLG WTR FLOW LO (5003-3D/3K) come in due to a trip of the B Component Cooling Water (CCW) Pump. The BOP Operator will start the standby pump per the Annunciator Response Procedure (ARP).

6. Annunciator ROD OUT BLOCK (5006-2H) and APRM DNSC (5004-1L) come in due to APRM C failing downscale. Technical Specification LCO 3.3.1.1 Actions A.1 will be evaluated requiring the channels affected function in trip within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. Technical Specification LCO 3.3.1.3 Actions A.1 or A.2 or A.3 will be evaluated requiring the channel in TRIP or the associated RPS trip system in TRIP or initiate an alternate method to detect and suppress thermal hydraulic instability oscillations all within 30 days.

7. Annunciator HIGH TEMP TURB GEN LUBE OIL (5018-3A) comes in due to a failure in the auto portion of the TURB OIL CLG WTR Controller. The BOP operator will diagnose the problem with the controller, place the controller in MANUAL and coordinate with the ATC Operator to stabilize turbine oil outlet temperature.

8. Annunciator CLEANUP PUMP SEAL GLAND PLATE TEMP HI (5000-2E) comes in due to RWCU Recirc Pump B (1G33-C001B) developing excessive seal leak requiring its removal from service. The ATC Operator will dispatch a field operator and coordinate/perform operations per CPS 3303.01 Sections 8.1.3 and 8.1.4.

9. The A Inboard MSIV drifts shut, resulting in a transient that causes a Group 1 isolation due to the increased steam flow in the remaining three Main Steam Lines which in turn causes a Reactor Scram.

10. A Reactor Coolant Leak develops followed shortly by a Drywell to Containment leak.

When Containment Pressure exceeds Figure N, EOP-3 is entered and a blowdown is performed.

11. Upon the initiation of ADS 2 SRVs 41B and 41D fail to open which requires manual operation to open two more relief valves to complete the blow down 2 of 3 2/16/2012

Appendix D Scenario Outline Form ES-D-1 EOP 1,6,3 Critical tasks:

• Enters EOP-3, Blowdown, and then maximizes injection to recover level above TAF.

• Verify Open/Open seven relief valves upon initiation of ADS.

3 of 3 2/16/2012

MEMORANDUM To: Mike Bielby, NRC Chief Examiner From: Bill Kiser, Clinton Power Station ILT 10-1 NRC Exam Author Date: 02/08/2011

Subject:

OUTLINE METHODOLOGY FOR 2011 CLINTON POWER STATION WRITTEN NRC EXAM (OPERATING TEST NO.: 2011-301)

The 2011 Clinton Power Station Written NRC Examination Outline was developed using the following widely-available commercial product produced by Western Technical Services, Inc.

BOILING WATER REACTOR Outline Generation Software Version 2.0.2 This BWR Random Outline Generator produces NRC Initial License Written Exam outlines in accordance with NUREG 1021, Rev. 9, Supp. 1.

K/A statements selected by the software not meeting the balance of coverage requirements or that were deemed inappropriate for testing (using the guidelines set forth in ES-401) were replaced by systematic and random selection. A method based on ES-401 Attachment 1 Example Systematic Sampling Methodology was utilized. Replacement Candidates were sequentially numbered in each level of the process. Random selection from the numbered tokens representing the candidates produced the replacement K/A statement.