Text

Initial Exam 2009-301 Draft SRO Written Exam
	ML092870768
Person / Time
Site:	Browns Ferry
Issue date:	10/14/2009
From:	; Division of Reactor Safety II
To:	;
References
	50-259/09/301, 50-260/09/301, 50-296/09/301
	Download: ML092870768 (120)
	v • d • e

ES*401 Sample Written Examination Question Worksheet Examination Outline Cross-reference:

295003 Partial or Complete Loss of AC 16 G2.4.50 (10CFR 55.43.5* SRO Only)

Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.

I Proposed Question: # 76 Level Tier #

Group #

KIA #

Importance Rating Form ES*401*5 SRO 1

1 295003G2.4.50 4.0 Unit 1 is operating at 100% Reactor Power, when the following alarms are received:

CONTROL ROD WITHDRAWAL BLOCK,1-9-5A, (Window 7)

RPIS INOPERATIVE, 1-9-5A, (Window 14)

CONTROL ROD OVERTRAVEL, 1-9-5A, (Window 35)

ALL Control Rod position indication has been lost (ASSUME NO OPERATOR ACTIONS)

Which ONE of the following completes the statement?

Based on the above conditions, entry into _(1)_ is required AND the loss of ALL control rod position indication will require the operating crew to _(2)_.

[REFERENCE PROVIDED]

A. (1) O-AOI-57-3, "Loss of Plant Preferred,"

(2) insert ALL control rods in 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months AND disarm the associated CRDs in 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

B. (1) 0-AOI-57-3, "Loss of Plant Preferred,"

(2) be in Mode 3 in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months C. (1) 1-AOI-57-4,"Loss of Unit Preferred,"

(2) insert ALL control rods in 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months AND disarm the associated CRDs in 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

D. (1) 1-AOI-57-4,"Loss of Unit Preferred,"

(2) be in Mode 3 in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Proposed Answer: D Explanation (Optional):

A INCORRECT: Part 1 = incorrect, these alarms indicate a loss of Unit Preferred NOT Plant Preferred. Part 2 = incorrect, although entry into TS 3.1.3 Condition C is required, the inoperable control rods can not be inserted. Per1-AOI-57-4 Step 4.2[2], if control rod movement is required while RPIS and the process computer are inoperable, THEN INSERT a MANUAL SCRAM REFER TO 1-AOI-100-1.

B INCORRECT: Part 1 = incorrect, these alarms indicate a loss of Unit Preferred NOT Plant Preferred. Part 2 = correct, as required by TS 3.1.3 Condition E.

ES*401 Sample Written Examination Question Worksheet Examination Outline Cross-reference:

295003 Partial or Complete Loss of AC 16 G2.4.50 (10CFR 55.43.5* SRO Only)

Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.

I Proposed Question: # 76 Level Tier #

Group #

KIA #

Importance Rating Form ES*401*5 SRO 1

1 295003G2.4.50 4.0 Unit 1 is operating at 100% Reactor Power, when the following alarms are received:

CONTROL ROD WITHDRAWAL BLOCK,1-9-5A, (Window 7)

RPIS INOPERATIVE, 1-9-5A, (Window 14)

CONTROL ROD OVERTRAVEL, 1-9-5A, (Window 35)

ALL Control Rod position indication has been lost (ASSUME NO OPERATOR ACTIONS)

Which ONE of the following completes the statement?

Based on the above conditions, entry into _(1)_ is required AND the loss of ALL control rod position indication will require the operating crew to _(2)_.

[REFERENCE PROVIDED]

A. (1) O-AOI-57-3, "Loss of Plant Preferred,"

(2) insert ALL control rods in 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months AND disarm the associated CRDs in 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

B. (1) 0-AOI-57-3, "Loss of Plant Preferred,"

(2) be in Mode 3 in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months C. (1) 1-AOI-57-4,"Loss of Unit Preferred,"

(2) insert ALL control rods in 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months AND disarm the associated CRDs in 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

D. (1) 1-AOI-57-4,"Loss of Unit Preferred,"

(2) be in Mode 3 in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Proposed Answer: D Explanation (Optional):

A INCORRECT: Part 1 = incorrect, these alarms indicate a loss of Unit Preferred NOT Plant Preferred. Part 2 = incorrect, although entry into TS 3.1.3 Condition C is required, the inoperable control rods can not be inserted. Per1-AOI-57-4 Step 4.2[2], if control rod movement is required while RPIS and the process computer are inoperable, THEN INSERT a MANUAL SCRAM REFER TO 1-AOI-100-1.

B INCORRECT: Part 1 = incorrect, these alarms indicate a loss of Unit Preferred NOT Plant Preferred. Part 2 = correct, as required by TS 3.1.3 Condition E.

ES*401 Technical Reference(s):

Sample Written Examination Question Worksheet Form ES*401*5 C

INCORRECT: Part 1 = correct, applicable procedure to reference. Part 2 =

incorrect, as explained above.

o CORRECT: Part 1 = correct, applicable procedure to reference. Part 2 =

correct, with a loss of all position indication, all control rods are inoperable.

Per TS 3.1.3 Condition E, if 9 or more control rods are inoperable, required action is to be in Mode 2 in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

1-9-5A Rev 12, O-AOI-57-3 Rev 40 1-AOI-57 -4 Rev 26 / TS 3.1.3 (Attach if not previously provided)

Proposed references to be provided to applicants during examination:

TS 3.1.3 Learning Objective:

(As available)

Question Source:

Question History:

Bank #

Modified Bank #

New Last NRC Exam x

(Note changes or attach parent)

(Optional-Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level:

10 CFR Part 55 Content:

Comments:

Memory or Fundamental Knowledge Comprehension or Analysis X

55.41 55.43 X

ES*401 Technical Reference(s):

Sample Written Examination Question Worksheet Form ES*401*5 C

INCORRECT: Part 1 = correct, applicable procedure to reference. Part 2 =

incorrect, as explained above.

D CORRECT: Part 1 = correct, applicable procedure to reference. Part 2 =

correct, with a loss of all position indication, all control rods are inoperable.

Per TS 3.1.3 Condition E, if 9 or more control rods are inoperable, required action is to be in Mode 2 in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

1-9-5A Rev 12, O-AOI-57-3 Rev 40 1-AOI-57 -4 Rev 26 / TS 3.1.3 (Attach if not previously provided)

Proposed references to be provided to applicants during examination:

TS 3.1.3 Learning Objective:

(As available)

Question Source:

Question History:

Bank #

Modified BanK #

New X

Last NRC Exam (Note changes or attach parent)

(Optional - Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level:

10 CFR Part 55 Content:

Comments:

Memory or Fundamental Knowledge Comprehension or Analysis X

55.41 55.43 X

ES-401 Sample Written Examination Question Worksheet Form ES-401-5 ACTIONS CONDITION A (continued)

A3 AND A.4

8. Two or more withdrawn B.1 control rods stuct<:.

C. One or more control rods C.1 inoperable for reasons other than Condition A or B.

AND C.2 Control Rod OPERABILITY 3.1.3 REQUIRED ACTION COMPLETION TIME Perfom1 SR 3.1.3.2 and 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from SR 3.1.3.3 for each discover! of withdrawn OPERABLE Condition A control rod.

concurrent with THERMAL POWER greater than the low power setpoint (LPSP) of the RWM Parfom1 SR 3. 1.1.1.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Be in MODE 3.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

NOTE--------

RWM may be bypassed as allowed by LCO 3.3.2.1, if required, to allow insertion of inoperable control roo and continued operation.

Fully insert inoperable 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months control roo.

Disarm the associated 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months CRD.

(continued)

ES-401 Sample Written Examination Question Worksheet Form ES-401-5 ACTIONS CONDITION A (continued)

A3 AND A.4

8. Two or more withdrawn B.1 control rods stuct<:.

C. One or more control rods C.1 inoperable for reasons other than Condition A or B.

AND C.2 Control Rod OPERABILITY 3.1.3 REQUIRED ACTION COMPLETION TIME Perfom1 SR 3.1.3.2 and 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from SR 3.1.3.3 for each discover! of withdrawn OPERABLE Condition A control rod.

concurrent with THERMAL POWER greater than the low power setpoint (LPSP) of the RWM Parfom1 SR 3. 1.1.1.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Be in MODE 3.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

NOTE--------

RWM may be bypassed as allowed by LCO 3.3.2.1, if required, to allow insertion of inoperable control roo and continued operation.

Fully insert inoperable 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months control roo.

Disarm the associated 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months CRD.

(continued)

ES-401 Sample Written Examination Question Worksheet Form ES-401-5 ACTIONS (continued)

CONDITION D. -------------NOTE-----------

D.1 Not applicable when THERMAL POWER

>10% RTP OR D.2 Two or more inoperable control rods not in compliance with banked position withdrawal sequence (BPWS) and not separated by two or more OPERABLE control rods E. Required Action and E.1 associated Completion Time of Condition A, C, or D not met OR Nine or more control rods inoperable SURVEILLANCE REQUIREMENTS SURVEILLANCE Control Rod OPERABILITY 3.'1.3 REQUIRED ACTION COMPLETION TIME Restore compliance with 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months BPWS.

Restore control rod to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months OPERABLE status.

Be in MODE 3.

'12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Control Rod OPERABILITY 3.1.3 FREQUENCY SR 3.1.3.1 Determine the poSition of each control rod.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ES-401 Sample Written Examination Question Worksheet Form ES-401-5 ACTIONS (continued)

CONDITION D. -------------NOTE-----------

D.1 Not applicable when THERMAL POWER

>10% RTP OR D.2 Two or more inoperable control rods not in compliance with banked position withdrawal sequence (BPWS) and not separated by two or more OPERABLE control rods E. Required Action and E.1 associated Completion Time of Condition A, C, or D not met OR Nine or more control rods inoperable SURVEILLANCE REQUIREMENTS SURVEILLANCE Control Rod OPERABILITY 3.'1.3 REQUIRED ACTION COMPLETION TIME Restore compliance with 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months BPWS.

Restore control rod to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months OPERABLE status.

Be in MODE 3.

'12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Control Rod OPERABILITY 3.1.3 FREQUENCY SR 3.1.3.1 Determine the poSition of each control rod.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

ES-401 BFN Sample Written Examination Question Worksheet Loss of Unit Preferred 1*AOI*57-4 Unit 1 Rev. 0026 Page 8 of 29 4.2 Subsequent Actions (continued)

[3]

Perform the following for the CRD system:

[3.1]

Monitor CRD temperatures while CRD SYS FLOW CONTROL VLV 1A IB, 1-FCV-85-11A1B are closed.

[3.2]

IF CRD seal temperatures rise to the alarm setpoint OR the Unit Preferred system cannot be restored within one hour. THEN DISPATCH personnel to MANUALLY OPEN CRD SYS FLOW CONTROL VLV 1A IB, 1-FCV-85-11A1B.

REFER TO 1-01-85 o

(Otherwise N/A) 0 BFN Unit 1

[3.3]

IF Cabinet 5 fails to transfer or is otherwise de-energized, and Cabinet 6 is energized THEN PLACE controller 1-FIC-85-11 in manual and adjust to normal Drive Water Pressure is obtained.

0 Loss of Unit Preferred Illustration 1 (Page 1 of 1)

Vital 120V AC Distribution 1*AOI*57-4 Rev. 0026 Page 14 of 29 Form ES-401-5 ES-401 BFN Sample Written Examination Question Worksheet Loss of Unit Preferred 1*AOI*57-4 Unit 1 Rev. 0026 Page 8 of 29 4.2 Subsequent Actions (continued)

[3]

Perform the following for the CRD system:

[3.1]

Monitor CRD temperatures while CRD SYS FLOW CONTROL VLV 1A IB, 1-FCV-85-11A1B are closed.

[3.2]

IF CRD seal temperatures rise to the alarm setpoint OR the Unit Preferred system cannot be restored within one hour. THEN DISPATCH personnel to MANUALLY OPEN CRD SYS FLOW CONTROL VLV 1A IB, 1-FCV-85-11A1B.

REFER TO 1-01-85 o

(Otherwise N/A) 0 BFN Unit 1

[3.3]

IF Cabinet 5 fails to transfer or is otherwise de-energized, and Cabinet 6 is energized THEN PLACE controller 1-FIC-85-11 in manual and adjust to normal Drive Water Pressure is obtained.

0 Loss of Unit Preferred Illustration 1 (Page 1 of 1)

Vital 120V AC Distribution 1*AOI*57-4 Rev. 0026 Page 14 of 29 Form ES-401-5

ES-401 Un.,

Batty Bd, PNL 11 Unit Preferred 1003 r-.

1001 r--....

1002 r-----

CA8 6 UNIT 1 PREFERRED lIn41 PNL 9-9 cab 4 Plant Preferred

.1 I.

Ne(1 (NO 1101 Sample Written Examination Question Worksheet Form ES-401-5 Unr2 Batty 8d 2 Poll1 UnA Preferred 1003 r-.

1001

~

1180 1171

'002 RMOV~Er......

80 -.3 --

28

) NC r

PNL 9*9 CA8. 5 CAB. 6 VNIT 1 UN'T2 NON*

PREFERRED PREFERRED I

) NO Unit 3 Batty 8d 3 Pnll1 Unit Preferred 1109 1101 1002 RMOV ~ E"--""

80 -.3 -

38

)Nc P~.Jl9*9 CA8.5 CAB 6 UNIT 2 UNrr 3 NON*

PREFERRED PREFERRED NO'l-PREFERPED

)NC PI'<L 9*9 CA8. 5 urm3 NON*

PREFERRED I

)NO UTO TRANSFER r--=~-1~::~~==::~~~----rf~~Ui~~ 2~V LTO 80 2A NORM Unit 2 PNL 9-9 Cab 4 Planl Preferred Ne(1 il NO lM3 PNL 9-9 Call 4 Plant Preferred NCe I I

)NO Batt 3d 4 Bkr 205 (Manual Trans1er) 8att. 8d 6 Bkr 205 24,] V Lf-"~.::..::..cc..:..::..:;.;.;..:.....J L TO 8D 3B ALT ES-401 Un.,

Batty Bd, PNL 11 Unit Preferred 1003 r-.

1001 r--....

1002 F m 8d 2 Panel 11 CA8 6 UNIT 1 PREFERRED lIn41 PNL 9-9 cab 4 Plant Preferred

.1 I.

Ne(1 (C 1101 Sample Written Examination Question Worksheet Form ES-401-5 Unr2 Batty 8d 2 Poll1 UnA Preferred 1003 r-.

1001

~

1180 1171

'002 RMOV~Er......

80 -.3 -

28

) NC I'

PNL 9*9 CA8. 5 CAB. 6 VNIT 1 UN'T2 NON*

PREFERRED PREFERRED I) NO I

Unit 3 Batty 8d 3 Pnll1 Unit Preferred 1109 1101 1002 RMOV ~ E"--""

80 -.3 -

38

)Nc P~.Jl9*9 CA8.5 CAB 6 UNIT 2 UNrr 3 NON*

PREFERRED PREFERRED NO'l-PREFERPED

)NC PI'<L 9*9 CA8. 5 urm3 NON*

PREFERRED I

)NO L ___ -'::::====:::::;----yUTO TRANSFER 24JV LTO 80 2A NORM Unit 2 PNL 9-9 Cab 4 Planl Preferred Ne(1 i1m lM3 PNl9-9 Call 4 Plant Preferred NCe I

I

)NO Batt 3d 4 Bkr 205 (Manual Trans1er) 8att. 8d 6 Bkr 205 24,) V

'-t------' LTO 8D 3B ALT

ES-401 Sample Written Examination Question Worksheet Form ES-401-5 BFN Loss of Unit Preferred 1-AOI-57-4 Unit 1 Rev. 0026 Page 7 of 29

[2]

IF control rod movement is required while RPIS and the process computer are inoperable, THEN BFN Unit 1 INSERT a MANUAL SCRAM REFER TO 1-AOI-100-1.

(Otherwise NIA)

Loss of Unit Preferred 1-AOI-57-4 Rev. 0026 Page 5 of 29 2.0 SYMPTOMS (continued) o G.

The following rod control annunciators are in alarm simultaneously due to a loss of power to the associated circuits BFN Unit 1 I.

CONTROL ROD WITHDRAWAL BLOCK (1-XA-55-5A, Window 7) on Panel.J 5 is in alarm.

2.

CONTROL ROD OVERTRAVEL (1-XA-55-5A, Window 14) on Panel 1-9-5 is in alarm.

3.

RPIS INOPERATIVE (1-XA-55-5A, Window 35) on Panel 1-9-5 is in alarm.

Panel 9-5 1-XA-55-5A SensorlTrip Point:

1-ARP-9-5A R.ev.0012 Page 43 of 43 RPIS INOPERABLE Relay 3A-K5 Receive alarm If thJ;1re is an electronic malfunction such as:

A. Card pUlled.

B. Internal logic stall.

(Page 1 of 1)

Sensor Location:

Probable Cause:

1-PNLA-009-0028 Elev.593' Aux. lost. Room A. 120; unit preferred breaker 612 on Panel 1-9-9 tripped.

B. 1-PX-58-5X(5Y)(6X}(6Y) fme cleared Of Internal breaker open (1-PNLA.-OOO-OO27, Aux. Inst Room).

C. Malfunction of a card in 1-PNLA.-009-0027 D. Spurious trip of sensor.

ES-401 Sample Written Examination Question Worksheet Form ES-401-5 BFN Loss of Unit Preferred 1-AOI-57-4 Unit 1 Rev. 0026 Page 7 of 29

[2]

IF control rod movement is required while RPIS and the process computer are inoperable, THEN BFN Unit 1 INSERT a MANUAL SCRAM REFER TO 1-AOI-100-1.

(Otherwise NIA)

Loss of Unit Preferred 1-AOI-57-4 Rev. 0026 Page 5 of 29 2.0 SYMPTOMS (continued) o G.

The following rod control annunciators are in alarm simultaneously due to a loss of power to the associated circuits BFN Unit 1 I.

CONTROL ROD WITHDRAWAL BLOCK (1-XA-55-5A, Window 7) on Panel.J 5 is in alarm.

2.

CONTROL ROD OVERTRAVEL (1-XA-55-5A, Window 14) on Panel 1-9-5 is in alarm.

3.

RPIS INOPERATIVE (1-XA-55-5A, Window 35) on Panel 1-9-5 is in alarm.

Panel 9-5 1-XA-55-5A SensorlTrip Point:

1-ARP-9-5A R.ev.0012 Page 43 of 43 RPIS INOPERABLE Relay 3A-K5 Receive alarm If thJ;1re is an electronic malfunction such as:

A. Card pUlled.

B. Internal logic stall.

(Page 1 of 1)

Sensor Location:

Probable Cause:

1-PNLA-009-0028 Elev.593' Aux. lost. Room A. 120; unit preferred breaker 612 on Panel 1-9-9 tripped.

B. 1-PX-58-5X(5Y)(6X}(6Y) fme cleared Of Internal breaker open (1-PNLA.-OOO-OO27, Aux. Inst Room).

C. Malfunction of a card in 1-PNLA.-009-0027 D. Spurious trip of sensor.

ES-401 Sample Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference:

295016 Control Room Abandonment / 7 G2.4.3 (10CFR 55.43.5 - SRO Only)

Level Tier #

Group #

KIA #

SRO 1

Ability to identify post-accident instrumentation.

1 295016G2.4.3 Importance Rating I Proposed Question: # 77 Unit 2 is operating at 100% Reactor Power, when conditions cause the Control Room to be abandoned.

The following conditions exist:

3.9 Time 0730, control has been established per 2-AOI-100-2, "Control Room Abandonment" Reactor Water Level indicates (+) 27 inches and stable Reactor Pressure indicates 850 psig and lowering slowly Time 0800, Unit Operator reports that Reactor Water Level Indicator, 2-U-3-46A, is reading off-scale low and appears broken Time 1200, control has been shifted back to the Control Room Which ONE of the following completes the statement?

Entry into Tech Spec(s) ____ _

A. 3.3.3.1, "PAM Instrumentation," is required upon discovery.

B. 3.3.3.2, "Backup Panel Instrumentation," is required upon discovery.

C. 3.3.3.1, "PAM Instrumentation," AND 3.3.3.2, "Backup Panel Instrumentation," are required upon discovery.

D. 3.3.3.2, "Backup Panel Instrumentation," is required upon discovery, AND 3.3.3.1, "PAM Instrumentation," when control is shifted back to the Control Room.

I Proposed Answer: B. I Explanation (Optional):

A INCORRECT: 2-Ll-3-46A is not a PAM instrument per T.S. 3.3.3.1.

B CORRECT: 2-Ll-3-46A is applicable to T.S. 3.3.3.2 only.

C INCORRECT: 2-Ll-3-46A is not a PAM instrument per T.S. 3.3.3.1.

D INCORRECT: 2-Ll-3-46A is not a PAM instrument per T.S. 3.3.3.1. Even if it were, delay until control is shifted back to the Main Control Room is not prudent.

ES-401 Sample Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference:

295016 Control Room Abandonment / 7 G2.4.3 (10CFR 55.43.5 - SRO Only)

Level Tier #

Group #

KIA #

SRO 1

Ability to identify post-accident instrumentation.

1 295016G2.4.3 Importance Rating I Proposed Question: # 77 Unit 2 is operating at 100% Reactor Power, when conditions cause the Control Room to be abandoned.

The following conditions exist:

3.9 Time 0730, control has been established per 2-AOI-100-2, "Control Room Abandonment" Reactor Water Level indicates (+) 27 inches and stable Reactor Pressure indicates 850 psig and lowering slowly Time 0800, Unit Operator reports that Reactor Water Level Indicator, 2-U-3-46A, is reading off-scale low and appears broken Time 1200, control has been shifted back to the Control Room Which ONE of the following completes the statement?

Entry into Tech Spec(s) ____ _

A. 3.3.3.1, "PAM Instrumentation," is required upon discovery.

B. 3.3.3.2, "Backup Panel Instrumentation," is required upon discovery.

C. 3.3.3.1, "PAM Instrumentation," AND 3.3.3.2, "Backup Panel Instrumentation," are required upon discovery.

D. 3.3.3.2, "Backup Panel Instrumentation," is required upon discovery, AND 3.3.3.1, "PAM Instrumentation," when control is shifted back to the Control Room.

I Proposed Answer: B. I Explanation (Optional):

A INCORRECT: 2-Ll-3-46A is not a PAM instrument per T.S. 3.3.3.1.

B CORRECT: 2-Ll-3-46A is applicable to T.S. 3.3.3.2 only.

C INCORRECT: 2-Ll-3-46A is not a PAM instrument per T.S. 3.3.3.1.

D INCORRECT: 2-Ll-3-46A is not a PAM instrument per T.S. 3.3.3.1. Even if it were, delay until control is shifted back to the Main Control Room is not prudent.

ES*401 Sample Written Examination Question Worksheet Form ES*401*5 Technical Reference( s):

T.S.3.3.3.1, T.S.3.3.3.2 (Attach if not previously provided)

(Including version f revision number)

Proposed references to be provided to applicants during examination:

NONE Learning Objective:

(As available)

Question Source:

Bank #

'I Modified Bank # J I~--,----,--, --"'----"i (Note changes or attach parent)

New X

Question History:

Last NRC Exam.

(Optional-Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level:

10 CFR Part 55 Content:

Comments:

Memory or Fundamental Knowledge Comprehension or Analysis X

55.41 55.43 X

Backup Control System B 3.3.3.2 Table B 3.3.3.2-1 (Page 1 of 4)

BaCkup Control System Instrumentation and Controls FUNCTION Instrument Parameter

1. Reactor Water Level Indication (1-Ll-3-46A. -46B)

2. Reactor Pressure Indication (1-PI-3-79)

3.

Suppression Pool Temperature Indication (1-TI-64-55B)

4.

Suppression Pool Level Indication (1-Ll-64-54B)

5.

Drywell Pressure Indication (1-PI-64-50)

6.

RHR Flow Indication (1-FI-74-79)

7.

RCIC Flow Indication (1-FIC-71-36B)

8. RCIC Turbine Speed Indication (1-SI-71-42B)

9.

Drywell Temperature Indication (1-TI-64-52AA)

10. RHRSW Header Pressure (O-PI-23-58/2. -59/2)

NUMBER REQUIRED 1, note a 1

1 2

ES*401 Sample Written Examination Question Worksheet Form ES*401*5 Technical Reference(s):

T.S.3.3.3.1, T.S.3.3.3.2 (Attach if not previously provided)

(Including version / revision number)

Proposed references to be provided to applicants during examination:

NONE Learning Objective:

Question Source:

Question History:

Bank # 1 Modified Bank # I New Last NRC Exam (As available)

(Note changes or attach parent) x (Optional-Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level:

10 CFR Part 55 Content:

Comments:

Memory or Fundamental Knowledge Comprehension or Analysis X

55.41 55.43 X

Backup Control System B 3.3.3.2 Table B 3.3.3.2-1 (Page I of 4)

Backup Control System Instrumentation and Controls FUNCTION Instrument Parameter

1. Reactor Water Level Indication (I-Ll-3-46A. -46B)

2. Reactor Pressure Indication (1-PI-3-79j

3.

Suppression Pool Temperature Indication (1-TI-64-55B)

4.

Suppression Pool Level Indication (I-Ll-64-546)

5.

Drywell Pressure Indication (I-PI-64-50)

6.

RHR Flow Indication (I-FI-74-79)

7.

RCIC Flow Indication (I-FIC-71-36B)

8. RCIC Turbine Speed Indication (I-SI-71-426)

9.

Drywell Temperature Indication (I-TI-64-52AA)

10. RHRSW Header Pressure (O-PI-23-58/2. -59/2)

NUMBER REQUIREO 1, note a 1

1 2

ES-401 I " I I

BASES Sample Written Examination Question Worksheet Form ES-401-5

2. Reactor Vessel Water Level (LI-3-52. LI-3-62A. LI-3-58A. and LI-3-58B)

PAM Instrumentation B 3.3.3.1 Reactor vessel water level is a Category 1 variable provided to support monitoring of core cooling and to verify operation of the ECCS. Two different range water level channels (Emergency Systems and Post-accident Flood Range) provide the PAM Reactor Vessel Water Level Functions. The water level channels measure from 1 f3 of the core height to 221 inches above the top of the active fuel. Water level is measured by two independent differential pressure transmitters for each required channel. The output from these channels is indicated on two independent indicators, which is the primary indication used by the operator during an accident. Therefore. the PAM Specification deals specifically with this portion of the instrument channel.

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TP-6 Reactor Vessel Level/Pressure Instrumentation ES*401 I " I I

I Sample Written Examination Question Worksheet Form ES*401*5 PAM Instrumentation B 3.3.3.1 BASES C0

~

2. Reactor Vessel Water Level (LI-3-52. LI-3-62A. LI-3-58A. and LI-3-58B)

Reactor vessel water level is a Category 1 variable provided to support monitoring of core cooling and to verify operation of the ECCS. Two different range water level channels (Emergency Systems and Post-accident Flood Range) provide the PAM Reactor Vessel Water Level Functions. The water level channels measure from 113 of the core height to 221 inches above the top of the active fuel. Water level is measured by two independent differential pressure transmitters for each required channel. The output from these channels is indicated on two independent indicators, which is the primary indication used by the operator during an accident. Therefore. the PAM Specification deals specifically with this portion of the instrument channel.

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TP-6 Reactor Vessel Level/Pressure Instrumentation

ES*401 Sample Written Examination Question Worksheet Examination Outline Cross-reference:

295018 Partial or Total Loss of CCW 18 AA2.01 (10CFR 55.43.5 - SRO Only)

Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER:

Component temperatures I Proposed Question: # 78 I Level Tier #

Group #

KIA #

Importance Rating Unit 1 is operating at 100% Reactor Power when the following occur:

Form ES*401*5 SRO 1

1 295018AA2.01 3.4 At 1200 on 5/18/09, a QA auditor reports that Functional Surveillances for ALL Division 1 OPRM Channels have not been performed for 40 months. The required Surveillance frequency per TS 3.3.1.1 is 24 months.

At 1230 on 5/18/09, RECIRC PUMP 1A COOLING WATER FLOW LOW, (1-9-4A, Window

34) alarm is received.

At 1245 on 5/18/09, the Unit Operator then reports that Recirc Pump Motor 1 A-Seal No.1 Cavity temperature is 210°F AND rising.

Drywell Temperatures remain stable at normal values.

Based on the above conditions, which ONE of the following describes the required actions to implement?

Immediately _(1)_ AND enter _(2)_.

A. (1) shut down Recirculation Pump 1A (2) 1-AOI-68-1 B, "Recirc Pump Trip/Core Flow Decrease."

B. (1) insert a Core Flow Runback (2) 1-AOI-68-1B, Recirc Pump Trip/Core Flow Decrease."

C. (1) shut down Recirculation Pump 1A (2) 1-AOI-68-1A, "Recirc Pump Trip/Core Flow Decrease OPRMs Operable."

D. (1) insert a Core Flow Runback (2) 1-AOI-68-1A, "Recirc Pump Trip/Core Flow Decrease OPRMs Operable."

I Proposed Answer: C Explanation (Optional):

A INCORRECT: Part 1 correct - See explanation C. Part 2 incorrect as detailed in Explanation C.

B INCORRECT: Part 1 incorrect - RBBCW supplies cooling water to the pump. 1-AOI-70-1, Loss of RBCCW, directs tripping the Recirc Pump if 2!

180°F. 1-9-4A Window 34 directs tripping the Recirc Pump if 2! 200°F. In either case, the action setpoint has been met, requiring the tripping of the pump. If temp limits were exceeded on both Recirc Pump, this would be the correct action followed by Reactor Scram. Part 2 is incorrect as detailed in Explanation C.

ES*401 Sample Written Examination Question Worksheet Examination Outline Cross-reference:

295018 Partial or Total Loss of CCW 18 AA2.01 (10CFR 55.43.5 - SRO Only)

Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER:

Component temperatures I Proposed Question: # 78 I Level Tier #

Group #

KIA #

Importance Rating Unit 1 is operating at 100% Reactor Power when the following occur:

Form ES*401*5 SRO 1

1 295018AA2.01 3.4 At 1200 on 5/18/09, a QA auditor reports that Functional Surveillances for ALL Division 1 OPRM Channels have not been performed for 40 months. The required Surveillance frequency per TS 3.3.1.1 is 24 months.

At 1230 on 5/18/09, RECIRC PUMP 1A COOLING WATER FLOW LOW, (1-9-4A, Window

34) alarm is received.

At 1245 on 5/18/09, the Unit Operator then reports that Recirc Pump Motor 1 A-Seal No.1 Cavity temperature is 210°F AND rising.

Drywell Temperatures remain stable at normal values.

Based on the above conditions, which ONE of the following describes the required actions to implement?

Immediately _(1)_ AND enter _(2)_.

A. (1) shut down Recirculation Pump 1A (2) 1-AOI-68-1 B, "Recirc Pump Trip/Core Flow Decrease."

B. (1) insert a Core Flow Runback (2) 1-AOI-68-1B, Recirc Pump Trip/Core Flow Decrease."

C. (1) shut down Recirculation Pump 1A (2) 1-AOI-68-1A, "Recirc Pump Trip/Core Flow Decrease OPRMs Operable."

D. (1) insert a Core Flow Runback (2) 1-AOI-68-1A, "Recirc Pump Trip/Core Flow Decrease OPRMs Operable."

I Proposed Answer: C Explanation (Optional):

A INCORRECT: Part 1 correct - See explanation C. Part 2 incorrect as detailed in Explanation C.

B INCORRECT: Part 1 incorrect - RBBCW supplies cooling water to the pump. 1-AOI-70-1, Loss of RBCCW, directs tripping the Recirc Pump if 2!

180°F. 1-9-4A Window 34 directs tripping the Recirc Pump if 2! 200°F. In either case, the action setpoint has been met, requiring the tripping of the pump. If temp limits were exceeded on both Recirc Pump, this would be the correct action followed by Reactor Scram. Part 2 is incorrect as detailed in Explanation C.

ES-401 Technical Reference(s):

Sample Written Examination Question Worksheet Form ES-401-5 C

CORRECT: Part 1 correct - RBBCW supplies cooling water to the pump. 1-AOI-70-1, Loss of RBCCW, directs tripping the Recirc Pump if ~ 180°F. 1 4A Window 34 directs tripping the Recirc Pump if ~ 200°F. In either case, the action setpoint has been met, requiring the tripping of the pump. Part 2 correct-Candidate must recognize that although Surveillance has not been performed within its required completion time, per TS SR 3.0.4, if it is discovered that a Surveillance was not performed within its specified Frequency, then compliance with the requirement to declare the LCO not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up to the limit of the specified Frequency, whichever is greater. It has been less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months so Division 1 OPRM Channels are Operable.

o INCORRECT: Part 1 is incorrect as explained above. Part 2 is correct as explained above.

1-AOI-70-1 Rev 9 1 1-AOI-68-1 A Rev 2 (Attach if not previously provided) 1-9-4A Rev16 (Including version / revision number)

Proposed references to be provided to applicants during examination:

NONE Learning Objective:

________ (As available)

Question Source:

r*

sank # I r

Modified Bank # ~

(Note changes or attach parent)

New X

Question History:

Last NRC Exam (Optional-Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level:

Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content:

55.41 55.43 X

Comments:

Reviewed 1-9-4A Rev17 issued 3/25/09. New revision has no impact on this question.

BFN Recirc Pump Trip/Core Flow Decrease 1-AOI-68-1A Unit 1 OPRMs Operable Rev. 0002 Page 3 of 12 1.0 PURPOSE This instruction provides the symptoms, automatic actions, and operator actions for a core flow decrease or Reactor Recire Pump trip in one or two loops with OPRMs operable.

ES-401 Technical Reference(s):

Sample Written Examination Question Worksheet Form ES-401-5 C

CORRECT: Part 1 correct - RBBCW supplies cooling water to the pump. 1-AOI-70-1, Loss of RBCCW, directs tripping the Recirc Pump if ~ 180°F. 1 4A Window 34 directs tripping the Recirc Pump if ~ 200°F. In either case, the action setpoint has been met, requiring the tripping of the pump. Part 2 correct-Candidate must recognize that although Surveillance has not been performed within its required completion time, per TS SR 3.0.4, if it is discovered that a Surveillance was not performed within its specified Frequency, then compliance with the requirement to declare the LCO not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up to the limit of the specified Frequency, whichever is greater. It has been less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months so Division 1 OPRM Channels are Operable.

D INCORRECT: Part 1 is incorrect as explained above. Part 2 is correct as explained above.

1-AOI-70-1 Rev 9 / 1-AOI-68-1A Rev 2 (Attach if not previously provided) 1-9-4A Rev16 (Including version / revision number)

Proposed references to be provided to applicants during examination:

NONE Learning Objective:

________ (As available)

Question Source:

B8nk# 1 Modified Bank # 1 (Note changes or attach parent)

New X

Question History:

Last NRC Exam (Optional-Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level:

Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content:

55.41 55.43 X

Comments:

Reviewed 1-9-4A Rev17 issued 3/25/09. New revision has no impact on this question.

BFN Recirc Pump Trip/Core Flow Decrease 1-AOI-68-1A Unit 1 OPRMs Operable Rev. 0002 Page 3 of 12 1.0 PURPOSE This instruction provides the symptoms, automatic actions, and operator actions for a core flow decrease or Reactor Recire Pump trip in one or two loops with OPRMs operable.

ES-401 BFN Unit 1 Sample Written Examination Question Worksheet Panel 9-4 1-XA-55-4A 1-ARP-9-4A Rev. 0016 Page 46 of 47 RECIRC PUMP 1A COOLING WATER FLOW LOW SenSQriTnp Point:

l-FIS-068-0053 22gpm l-FA-68-53 (Page 1 of 1)

Sensor Location:

Probable Cause:

Automatic Action:

Operator Action:

Recirculation Pump A area Drywell A. Partial or complete loss of RBCCW system B

High RBCCW flow through Fuel Pool Cooling heat exchangers.

None A. CHECK following on RBCCW system:

RBCCW PRI CNTMT OUTLET VAL VE handswitch, l-HS-70-47A (1-FCV-70-47) OPEN RBCCW PUMP lA l-HS-70-SA in service.

RBCCVV PUMP lB. l-HS-70-SA in service.

Surge tank level normal IndIcated by RBCCW SURGE TANK LEVEL LOW l-LA-70-2B (\\<'Vindow 13 on l-XA-55-4C) NOT o

o o Illummated.

0 B

REFER TO l-AOI-70-1 0

C IF the l-TE-68-61U(T). RECIRC PMP MTR lA-SEAL NO. 1(2}

CAVITY temperature on RECIRC PUMP MTR lA & 1B WINDING AND BRG TEMP temperature recorder, l-TR-68-71 on Panel 1-9-21 IS ~200DF, THEN SHUT DOWN ReClfculation Pump lB.

0 REFER TO l-AOI-68-1 A or l-AOI-68-1 B.

0 D IF CRD or RBCCW system is lost, THEN REFER TO 1-01-68, Precautions and Limitations Sections to determine requirements for continued pump operation.

0 1-45E620-5-1 1-47E610-68-1 FSAR Section 13.6.2 Form ES-401-5 ES-401 BFN Unit 1 Sample Written Examination Question Worksheet Panel 9-4 1-XA-55-4A 1-ARP-9-4A Rev. 0016 Page 46 of 47 RECIRC PUMP 1A COOLING WATER FLOW LOW SenSQriTnp Point:

l-FIS-068-0053 22gpm l-FA-68-53 (Page 1 of 1)

Sensor Location:

Probable Cause:

Automatic Action:

Operator Action:

Recirculation Pump A area Drywell A. Partial or complete loss of RBCCW system B

High RBCCW flow through Fuel Pool Cooling heat exchangers.

None A. CHECK following on RBCCW system:

RBCCW PRI CNTMT OUTLET VAL VE handswitch, l-HS-70-47A (1-FCV-70-47) OPEN RBCCW PUMP lA l-HS-70-SA in service.

RBCCVV PUMP lB. l-HS-70-SA in service.

Surge tank level normal IndIcated by RBCCW SURGE TANK LEVEL LOW l-LA-70-2B (\\<'Vindow 13 on l-XA-55-4C) NOT CJ CJ CJ Illummated.

CJ B REFER TO l-AOI-70-1 CJ C IF the l-TE-68-61U(T). RECIRC PMP MTR lA-SEAL NO. 1(2}

CAVITY temperature on RECIRC PUMP MTR lA & 1B WINDING AND BRG TEMP temperature recorder, l-TR-68-71 on Panel 1-9-21 IS ~200DF, THEN SHUT DOWN ReClfculation Pump lB.

CJ REFER TO l-AOI-68-1 A or l-AOI-68-1 B.

CJ D IF CRD or RBCCW system is lost, THEN REFER TO 1-01-68, Precautions and Limitations Sections to determine requirements for continued pump operation.

CJ 1-45E620-5-1 1-47E61O-68-1 FSAR Section 13.6.2 Form ES-401-5

ES-401 BFN Unit 1

[11]

[12]

[13]

Sample Written Examination Question Worksheet Loss of Reactor Building Closed 1-AOI-70-1 Cooling Water Rev. 0009 Page 9 of 12 MONITOR the following Recirc Pump and Motor 1A(1B) temperatures on 1-TR-68-71, Panel 1-9-21:

TE-68-61A(73A), RECIRC PMP MTR 1A(1B)-THR BRG UPPER FACE <<190°F)

TE-68-61C(73C), RECIRC PMP MTR 1A(1B)-THR BRG LOWER FACE <<190"F)

TE-68-61E(73E), RECIRC PMP MTR 1A(1B)-UPPER GUIDE BRG <<190°F)

TE-68-61N(73N}, RECIRC PMP MTR 1A(1B}-LOWER GUIDE BRG <<190°F)

TE-68-61 G,J,L(73G,J,L), RECIRC PMP MTR 1A(1 B)-

MOTOR WINDING A,B,C <<255 Q F)

TE-68-61T(73T), RECIRC PMP MTR 1A(1 B)-NO.2 CAVITY <<180°F)

TE-68-61U(73U), RECIRC PMP MTR 1A(1B)-NO. 1 SEAL CAVITY <<180°F)

TE-68-54(67), RECIRC PMP MTR 1A(1B)-CLG WTR FROM SEAL CLG <<140°F)

TE-68-57(70), RECIRC PMP MTR 1A(1B)-CLG WTR FROM BRG <<140°F)

IF any of the above temperature limits are exceeded on either Recirc Pump, THEN SHUT DOWN the affected Recirc Pump as follows and REFER TO 1-AOI-68-1A(1B): (othervvise N/A)

DEPRESS RECIRC DRIVE 1A SHUTDOWN, 1-HS-96-19.

DEPRESS RECIRC DRIVE 1B SHUTDOWN, 1-HS-96-20.

IF any of the above temperature limits are exceeded on both Recirc Pumps, THEN PERFORM the following (othervvise N/A):

[13.1]

IF core flow is above 60%, THEN REDUCE core flow to between 50-60%.

[13.2]

MANUALLY SCRAM the Reactor and PLACE Mode Switch in SHUTDOWN. (REFER TO 1-AOI-100-1)

[13.3J SHUT DOWN both Recirc Pumps as follows:

DEPRESS RECIRC DRIVE 1A SHUTDOWN, 1-HS-96-19.

DEPRESS RECIRC DRIVE 1 B SHUTDOWN, Form ES-401-5 0

0 0

0 ES-401 BFN Unit 1

[11]

[12]

[13]

Sample Written Examination Question Worksheet Loss of Reactor Building Closed 1-AOI-70-1 Cooling Water Rev. 0009 Page 9 of 12 MONITOR the following Recirc Pump and Motor 1A(1B) temperatures on 1-TR-68-71, Panel 1-9-21:

TE-68-61A(73A), RECIRC PMP MTR 1A(1B)-THR BRG UPPER FACE <<190°F)

TE-68-61C(73C), RECIRC PMP MTR 1A(1B)-THR BRG LOWER FACE <<190"F)

TE-68-61E(73E), RECIRC PMP MTR 1A(1B)-UPPER GUIDE BRG <<190°F)

TE-68-61N(73N}, RECIRC PMP MTR 1A(1B}-LOWER GUIDE BRG <<190°F)

TE-68-61 G,J,L(73G,J,L), RECIRC PMP MTR 1A(1 B)-

MOTOR WINDING A,B,C <<255 Q F)

TE-68-61T(73T), RECIRC PMP MTR 1A(1 B)-NO.2 CAVITY <<180°F)

TE-68-61U(73U), RECIRC PMP MTR 1A(1B)-NO. 1 SEAL CAVITY <<180°F)

TE-68-54(67), RECIRC PMP MTR 1A(1B)-CLG WTR FROM SEAL CLG <<140°F)

TE-68-57(70), RECIRC PMP MTR 1A(1B)-CLG WTR FROM BRG <<140°F)

IF any of the above temperature limits are exceeded on either Recirc Pump, THEN SHUT DOWN the affected Recirc Pump as follows and REFER TO 1-AOI-68-1A(1B): (othervvise N/A)

DEPRESS RECIRC DRIVE 1A SHUTDOWN, 1-HS-96-19.

DEPRESS RECIRC DRIVE 1B SHUTDOWN, 1-HS-96-20.

IF any of the above temperature limits are exceeded on both Recirc Pumps, THEN PERFORM the following (othervvise N/A):

[13.1]

IF core flow is above 60%, THEN REDUCE core flow to between 50-60%.

[13.2]

MANUALLY SCRAM the Reactor and PLACE Mode Switch in SHUTDOWN. (REFER TO 1-AOI-100-1)

[13.3J SHUT DOWN both Recirc Pumps as follows:

DEPRESS RECIRC DRIVE 1A SHUTDOWN, 1-HS-96-19.

DEPRESS RECIRC DRIVE 1 B SHUTDOWN, Form ES-401-5 0

0 0

0

ES-401 Sample Written Examination Question Worksheet Examination Outline Cross-reference:

295023 Refueling Ace Cooling Mode / 8 AA2.01 (10CFR 55.43.5 - SRO Only)

Ability to determine and/or interpret the following as they apply to REFUELING ACCIDENTS:

Area radiation levels I Proposed Question: # 79 Level Tier #

Group #

KIA #

Importance Rating Form ES-401-5 SRO 1

1 295023AA2.01 4.0 During refueling operations on Unit 2, an irradiated fuel bundle jams on the Upper Core Guide Plate and the Main Hoist Fuel Grapple fails open. The bundle then falls the entire way into the core location.

The following conditions are subsequently noted:

Gas bubbles are seen coming from the fuel bundle REFUEL ZONE EXHAUST RADIATION HIGH, (2-9-3A, Window 34), is alarming and reading 120 mr/hr FUEL POOL FLOOR AREA RADIATION HIGH, (2-9-3A, Window 1), is alarming and reading 100 mr/hr Which ONE of the following completes the statement?

Based on the above conditions, Secondary Containment must be verified intact as directed by_(1)_. This event would be classified as _(2)_ per EPIP-1, "Emergency Classification Procedure."

[REFERENCE PROVIDED]

A. (1) O-EOI-4, "Radioactivity Release Control,"

(2) an Alert B. (1) 0-EOI-4, "Radioactivity Release Control,"

(2) a Site Area Emergency C. (1) 2-AOI-79-1, "Fuel Damage During Refueling,"

(2) an Alert D. (1) 2-AOI-79-1, "Fuel Damage During Refueling,"

(2) a Site Area Emergency I Proposed Answer: C Explanation (Optional):

A INCORRECT: Part 1 is incorrect; The direction to verify Secondary CTMT intact is in 2-AOI-79-1, "Fuel Damage During Refueling". Part 2 is correct; with REFUEL ZONE EXHAUST RADIATION HIGH, (2-9-3A, Window 34),and FUEL POOL FLOOR AREA RADIATION HIGH, (2-9-3A, Window 1) above their alarm set points, and confirmation that fuel damage occurred, an Alert must be declared per EAL 3.2-A ES-401 Sample Written Examination Question Worksheet Examination Outline Cross-reference:

295023 Refueling Ace Cooling Mode / 8 AA2.01 (10CFR 55.43.5 - SRO Only)

Ability to determine and/or interpret the following as they apply to REFUELING ACCIDENTS:

Area radiation levels I Proposed Question: # 79 Level Tier #

Group #

KIA #

Importance Rating Form ES-401-5 SRO 1

1 295023AA2.01 4.0 During refueling operations on Unit 2, an irradiated fuel bundle jams on the Upper Core Guide Plate and the Main Hoist Fuel Grapple fails open. The bundle then falls the entire way into the core location.

The following conditions are subsequently noted:

Gas bubbles are seen coming from the fuel bundle REFUEL ZONE EXHAUST RADIATION HIGH, (2-9-3A, Window 34), is alarming and reading 120 mr/hr FUEL POOL FLOOR AREA RADIATION HIGH, (2-9-3A, Window 1), is alarming and reading 100 mr/hr Which ONE of the following completes the statement?

Based on the above conditions, Secondary Containment must be verified intact as directed by_(1)_. This event would be classified as _(2)_ per EPIP-1, "Emergency Classification Procedure."

[REFERENCE PROVIDED]

A. (1) O-EOI-4, "Radioactivity Release Control,"

(2) an Alert B. (1) 0-EOI-4, "Radioactivity Release Control,"

(2) a Site Area Emergency C. (1) 2-AOI-79-1, "Fuel Damage During Refueling,"

(2) an Alert D. (1) 2-AOI-79-1, "Fuel Damage During Refueling,"

(2) a Site Area Emergency I Proposed Answer: C Explanation (Optional):

A INCORRECT: Part 1 is incorrect; The direction to verify Secondary CTMT intact is in 2-AOI-79-1, "Fuel Damage During Refueling". Part 2 is correct; with REFUEL ZONE EXHAUST RADIATION HIGH, (2-9-3A, Window 34),and FUEL POOL FLOOR AREA RADIATION HIGH, (2-9-3A, Window 1) above their alarm set points, and confirmation that fuel damage occurred, an Alert must be declared per EAL 3.2-A

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet B

INCORRECT: Part 1 is incorrect as detailed above. Part 2 is incorrect; area rad levels would have to be above Max Safe levels for a Site Area Emergency.

C CORRECT: Part 1 is correct; per 2-AOI-79-1, "Fuel Damage During Refueling," subsequent actions, operating crew must verify Secondary CTMT intact and refer to TS 3.6.4.1. Part 2 is correct; with REFUEL ZONE EXHAUST RADIATION HIGH, (2-9-3A, Window 34),and FUEL POOL FLOOR AREA RADIATION HIGH, (2-9-3A, Window 1) above their alarm set points, and confirmation that fuel damage occurred, an Alert must be declared per EAL 3.2-A o

INCORRECT: Part 1 is correct and Part 2 incorrect as detailed above.

Technical Reference(s):

2-AOI-79-1 Rev 17 EPIP-1 Rev 44 (Attach if not previously provided) 2-9-3A Window 1 rev 37 (Including version / revision number) 2-9-3A Window 34 rev 37 Proposed references to be provided to applicants during examination:

EPIP-1 Event Classification Matrix Learning Objective:

(As available)

Question Source:

Bank #

(Note changes or attach parent) x Question History:

(Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level:

Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content:

55.41 55.43 X

Comments:

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet B

INCORRECT: Part 1 is incorrect as detailed above. Part 2 is incorrect; area rad levels would have to be above Max Safe levels for a Site Area Emergency.

C CORRECT: Part 1 is correct; per 2-AOI-79-1, "Fuel Damage During Refueling," subsequent actions, operating crew must verify Secondary CTMT intact and refer to TS 3.6.4.1. Part 2 is correct; with REFUEL ZONE EXHAUST RADIATION HIGH, (2-9-3A, Window 34),and FUEL POOL FLOOR AREA RADIATION HIGH, (2-9-3A, Window 1) above their alarm set points, and confirmation that fuel damage occurred, an Alert must be declared per EAL 3.2-A o

INCORRECT: Part 1 is correct and Part 2 incorrect as detailed above.

Technical Reference(s):

2-AOI-79-1 Rev 17 EPIP-1 Rev 44 (Attach if not previously provided) 2-9-3A Window 1 rev 37 (Including version / revision number) 2-9-3A Window 34 rev 37 Proposed references to be provided to applicants during examination:

EPIP-1 Event Classification Matrix Learning Objective:

Question Source:

Question History:

Mod Bank #

Bank #

New X

Last NRC Exam (As available)

(Note changes or attach parent)

(Optional - Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)

Question Cognitive Level:

Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content:

55.41 55.43 X

Comments:

ES-401 Sample Written Examination Question Worksheet BFN Fuel Damage During Refueling 2*AOI*79*1 Unit 2 Rev. 0017 Page 5 of 7 4.0 OPERATOR ACTIONS 4.1 Immediate Actions STOP all fuel handling.

[1]

[2]

EVACUATE all non-essential personnel from Refuel Floor.

4.2 Subsequent Actions CAUTION o

o The release of iodine is of major concern. If gas bubbles are identified at any time, Iodine release should be assumed until RADCON determines otherwise.

[1]

VERIFY secondary containment is intact.

(REFER TO Tech Spec 3.6.4.1)

[2]

IF any EOI entry condition is met, THEN ENTER the appropriate EOI(s).

[3]

VERIFY automatic actions.

[6]

MONITOR radiation levels. for the affected areas. using the following radiation recorders and indicators:

A.

2-RR-90-1 (points 1 and 2), 2-MON-90-50 (Address 11),

o o

o 2-RR-90-142 and 2-RR-90-140 (Panel 2-9-2).

0 B.

2-RM-90-142, 2-RM-90-140, 2-RM-90-143 and 2-RM-90-141 Detectors A and B (Panel 2-9-10).

0 C.

2-RI-90-1 A and 2-RI-90-2A (Panel 2-9-11).

0 D.

O-CONS-90-362A (Address 09, 10,08) for Unit 1,2, 3-RM-90-250, respectively (Panel 1-9-44).

0

[7]

IF possible, MONITOR portable CAMs & ARMs.

Form ES-401-5 ES-401 Sample Written Examination Question Worksheet BFN Fuel Damage During Refueling 2*AOI*79*1 Unit 2 Rev. 0017 Page 5 of 7 4.0 OPERATOR ACTIONS 4.1 Immediate Actions STOP all fuel handling.

[1]

[2]

EVACUATE all non-essential personnel from Refuel Floor.

4.2 Subsequent Actions CAUTION o

o The release of iodine is of major concern. If gas bubbles are identified at any time, Iodine release should be assumed until RADCON determines otherwise.

[1]

VERIFY secondary containment is intact.

(REFER TO Tech Spec 3.6.4.1)

[2]

IF any EOI entry condition is met, THEN ENTER the appropriate EOI(s).

[3]

VERIFY automatic actions.

[6]

MONITOR radiation levels. for the affected areas. using the following radiation recorders and indicators:

A.

2-RR-90-1 (points 1 and 2), 2-MON-90-50 (Address 11),

o o

o 2-RR-90-142 and 2-RR-90-140 (Panel 2-9-2).

0 B.

2-RM-90-142, 2-RM-90-140, 2-RM-90-143 and 2-RM-90-141 Detectors A and B (Panel 2-9-10).

0 C.

2-RI-90-1 A and 2-RI-90-2A (Panel 2-9-11).

0 D.

O-CONS-90-362A (Address 09, 10,08) for Unit 1,2, 3-RM-90-250, respectively (Panel 1-9-44).

0

[7]

IF possible, MONITOR portable CAMs & ARMs.

Form ES-401-5

ES*401 Sample Written Examination Question Worksheet BROWNS FERRY EMERGENCY CLASSIFICATION PROCEDURE EVENT CLASSIFICAHON MATRIX EPIP-1

RA-gC-25~ _ R~cto* _ Tumi"" R~M! Ex")

I

RA-~~ 1<12,0. Rue o. Refuel Exhal..i1

~~'- 1 4C.A RI! I! lng ~ I! : Xt-3ust AND Oll ie:

AND

~y,,'U,,,dJ.ttio... II! eI at or abov~ lIle. " :rm.m Safe OJ;~ra~j"g A 'ea mdi3 *0... r 1 sleel n T~e ~.2.

AND A'I'I.HU rod lion Ie eel :11 or "bove the." m m Sate Oper3."g Aru rad ~tion II I sled n Ta to 2.2.

AND M'I indl

~io'l of po:~nria l or sfgniflCa" fve e addmg f lIU1e exi5"3 Refe to Table 3 l-GI3 _-13 WI RCS 83rrier inuct,,,SJde On'IUry Ccn \\() *nn1enl~

Dill 0 c z c C4 c

~

m z...

co

~

m

~

Gl m

z o Q m z m

~

r-m 3:

~

Q m Z o PAGE 37 OF 206 REVISION 44 Form ES*401*5 ES-401 Sample Written Examination Question Worksheet BROWNS FERRY EMERGENCY CLASSIFICATION PROCEDURE EVENT CLASSIFICATION MATRIX EPIP-1 SECONDARY CONTAINMENT RADIATION ion

RA*gC-25'JA Re<lc<<l'. Turoire R.,fve Ex!>>

RA-gC-142A Ructo' Re<ui!1 Exhalls1

RA~C'- I 4C.A. Re

Ill Zone Sxt-.lusl AND Con'iMl.:l r oy Re e F cor ~~r"'E I nat Irr

'.:lIed e da"'na e ay !-ave OCOI.'Ted.

OPERA TI 0. CO DITtO :

AL 3.2-S AND A...,v.J*U radJ.alio"l Ie el at or above e

.~.J c m""" Safe OJ*rating Area r.:td'

'Otl r ~ sled n T.able ~2.

OPeRA nNo. ccmOITlC Mode 1 o* 2 o* 3 AND Contai nlEo]

A/ly iJfI~(J I1:Idlatio"l Ie I al or above the *.J m m Sate Opera rg A'e.l ra-d 3 ti011 II I sled n T

!! 2.2..

Any Inch tfo"l of po:ential or s lQlliflC.1'"

B.lrrie' inuct,.,s>de "'n'1\\al)' Conll3 OPERA

0. CC OlTlO Mode 1 Of ~ o* 3 AND Re'e 10 Table 3 1-0.13 -3 WI RCS c z c (I) c >>

r

~

m Z....

en

~

i C) m z

(')

C) m z m

~

m 3:

!:J Q m z

(')

PAGE 37 OF 206 REVISION 44 Form ES-401-5

ES-401 BROWNS FERRY NOTES CURVESIT ABLES:

Sample Written Examination Question Worksheet EMERGENCY CLASSIFICATION PROCEDURE EVENT CLASSIFICATION MATRIX TABLE 3.2 MAX~MSAFEOPERAnN< AREARArnATiONUMITS EPIP-1 AREA RAD MONITOR MAX SAFE VALUE MRfHR RHR West Room 9O-25A 1000 RHR East Room 90-2eA 1000 HPCtRoom 9O-24A 1000 CSIHCtC Room 90-26A 1000 elm! Spra'j Room 9O-27A 1000 Suppr Pool Area 9O-2QA 1000 CRD-HCU West Area 9O-20A 1000 CRD-HCU East.Area 9O-21A 1000 TIP Drive Area 9O-23A 1000 North RWCU System Area 90-13A 1000 Soul/> RWCU System Area 9O-14A 1000 RWCU System Area QC-9A 1000 MG Set Area

'i1C'-4A 1000 Fuel Pool Area OO-fA 1000 Servi~ Fir Area QO-ZA 1000 New Fuel Storage.

90-3A 1000 TABLE 3.1-G13.2-G INDICATIONS OF POTENTlAl OR SlGN,FtCANT FUEl ClADDING FAJLURE WITH ReS BARRIER MACT INSfOE PRIMARY CONTAJHMENT UNIT 1 DRYWELL RADIATION UNIT 2 DRYWElL RADIATION l-RE-OO-272A I

> 196 RiHR 2-RE-QO-272A I::> 642 RIHR 1-RE-90-ZBA I

>~97 RIHR 2-RE-~0-273A I::> 297 RIHR Reactor Coo13w Acthity Raacror Cool.mt Acrl,ity

. 300 ~Ci gm Dose Equivaleot 230(l ~Cigm ::>o~@ Equl\\'l!Jw Iodme 131 BFN Unit 2 FUEL POOL FLOOR AREA RADIATION HIGH 2*RA*90-1A f1 (Page 1 of 1)

Sensor Location:

RE*90-18 RE-90-2B RE-90-3B IodiDe 131 Pane! 9-3 2-XA-66-3A Sensor/TriD Pojnt:

RI*90-1B RI-OO*2B RI*90*38 EI664' EI664' E1639' Probable Cause:

A Change H1 general radiation levels 8

Refueling aCCident C Sensor o1affunction 2-ARP-9-3A Rev. 0037 Page 4 of 60 For se\\pOmts REFER TO 2*SIMI-OOB.

R*11 P*UNE R-IO V-LINE R-l0Q-UNE UNIT 3 DRYWElL RADIA nON 3-RE-90-272A J :> HIe; RlHR 3-RE-90-273A I::> 297 R"HR Reactor CooLa:ll At:mity

.::. 300 ~Cj gw Dos@ EqulvaJeor IodIne 131 Form ES-401-5 ES-401 BROWNS FERRY NOTES CURVESIT ABLES:

Sample Written Examination Question Worksheet EMERGENCY CLASSIFICATION PROCEDURE EVENT CLASSIFICATION MATRIX TABLE 3.2 MAXIMUM SAFE OPERATIH( AREA RADtATIOH UMfTS EPIP-1 AREA RAD MONITOR MAX SAFE VALUE MRfHR RHR West Room 9O-25A 1000 RHR East Room 90-2eA 1000 HPCtRoom 9O-24A 1000 CSIHCtC Room 90-26A 1000 elm! S~ay Room 9O-27A 1000 Suppr Pool Area 9O-2QA 1000 CRD-HCU West Area 9O-20A 1000 CRD-HCU East.Area 9O-21A 1000 TIP Drive Area 9O-23A 1000 North RWCU System Area 90-13A 1000 Soul/> RWCU System Area 9O-14A 1000 RWCU System Area QC-9A 1000 MG Set Area

'i1C'-4A 1000 Fuel Pool Area OO-fA 1000 Servi~ Fir Area QO-ZA 1000 New Fuel Storage 90-3A 1000 TABLE 3.1-G13.2-G INDICATIONS OF POTENTlAl OR SlGN,FtCANT FUEl ClADDING FAJLURE WITH ReS BARRIER MACT INSfOE PRIMARY CONTAJHMENT UNIT 1 DRYWELL RADIATION UNIT 2 DRYWElL RADIATION l-RE-OO-272A I

> 196 RiHR 2-RE-QO-272A I::> 642 RIHR 1-RE-90-ZBA I

>~97 RIHR 2-RE-~0-273A I::> 297 RIHR Reactor Coo13w Acthity Raacror Cool.mt Acrl,ity

. 300 ~Ci gm Dose Equivaleot 230(l ~Cigm ::>o~@ Equl\\'l!Jw Iodme 131 BFN Unit 2 FUEL POOL FLOOR AREA RADIATION HIGH 2*RA*90-1A r1 (Page 1 of 1)

Sensor Location:

RE*90-18 RE-90-2B RE-90-3B IodiDe 131 Pane! 9-3 2-XA-66-3A Sensor/TriD Pojnt:

RI*90-1B RI-OO*2B RI*90*38 EI664' EI664' E1639' Probable Cause:

A Change H1 general radiation levels 8

Refueling aCCident C Sensor o1affunction 2-ARP-9-3A Rev. 0037 Page 4 of 60 For se\\pOmts REFER TO 2*SIMI-OOB.

R*11 P*UNE R-IO V-LINE R-l0Q-UNE UNIT 3 DRYWElL RADIA nON 3-RE-90-272A I:> HIe; RlHR 3-RE-90-273A I::> 297 R"HR Reactor CooLa:ll At:mity

.::. 300 ~Cj gw Dos@ EqulvaJeor IodIne 131 Form ES-401-5

ES-401 Opuator Action:

References:

BFN Unit 2 Sample Written Examination Question Worksheet A

CHECK 2-RI-90-1 A. 2-RI-90-2A and 2-RI-90-3A on Panel 2 11 B

NOTIFY refuel floor personnel C IF Dry Cask 10admgiunlOading activities are In progress, THEN NOTIFY Cask SUpfY1SOf D IF alfborne levels flse by 100 DAC AND RAD PRO confirms, THEN REFER TO EPIP-1.

E REFER TO 2-AOI-79-1 or 2-AOI-79-2 as applicable.

F. IF thiS alarm IS not valid, THEN REFER TO 0-01-55.

G IF this alarm is valid. THEN MONITOR the other parameters Ihat input to it frequently These other parameters Will be masked from alarming while this alarm is sealed in H ENTER 2-EOI-3 Flowchart 0-47EEiOO-13 2-47E610-90-1 2-45E620-3 GE 730E356 Senes, TVA Calc NDOO0902005001!EDC63693 Panel 9-3 2-XA-55-3A 2-ARP-9-3A Rev, 0037 Page 47 of 50 REFUELING ZONE EXHAUST RADIATION HIGH SensofiTnp POlO)'

a a a

a a a a a 2-RA-90-140A f34 2-RE-90-140A 2-RE-90-140B 2-RE-90-141A 2-RE-90-14IB 72 MRfHR 72MRfHR 72 MRiHR 72 MRiHR ReqUired settmg of

,; 100 MRfHR.

(page 1 of 2)

Sensor Location:

Probable Cause:

Rx Bldg, EI,,64' (Refuel Floor). R-IO P-LiNE A

Radiation levels have risen above alarm setpoin!.

B Refueling aCCident NOTE TV A Calc NDQ0090205008 reqUJres these detectors be temporanly shielded dunng Dry Ca,k loaclng/unloadlng actlvibes.

Form ES-401-5 ES-401 Opuator Action:

References:

BFN Unit 2 Sample Written Examination Question Worksheet A

CHECK 2-RI-90-1 A. 2-RI-90-2A and 2-RI-90-3A on Panel 2 11 B

NOTIFY refuel floor personnel C IF Dry Cask 10admgiunlOading activities are In progress, THEN NOTIFY Cask SUpfY1SOf D IF alfborne levels flse by 100 DAC AND RAD PRO confirms, THEN REFER TO EPIP-1.

E REFER TO 2-AOI-79-1 or 2-AOI-79-2 as applicable.

F. IF thiS alarm IS not valid, THEN REFER TO 0-01-55.

G IF this alarm is valid. THEN MONITOR the other parameters Ihat input to it frequently These other parameters Will be masked from alarming while this alarm is sealed in H ENTER 2-EOI-3 Flowchart 0-47EEiOO-13 2-47E610-90-1 2-45E620-3 GE 730E356 Senes, TVA Calc NDOO0902005001!EDC63693 Panel 9-3 2-XA-55-3A 2-ARP-9-3A Rev, 0037 Page 47 of 50 REFUELING ZONE EXHAUST RADIATION HIGH SensofiTnp POlO)'

a a a

a a a a a 2-RA-90-140A f34 2-RE-90-140A 2-RE-90-140B 2-RE-90-141A 2-RE-90-14IB 72 MRfHR 72MRfHR 72 MRiHR 72 MRiHR ReqUired settmg of

,; 100 MRfHR.

(page 1 of 2)

Sensor Location:

Probable Cause:

Rx Bldg, EI,,64' (Refuel Floor). R-IO P-LiNE A

Radiation levels have risen above alarm setpoin!.

B Refueling aCCident NOTE TV A Calc NDQ0090205008 reqUJres these detectors be temporanly shielded dunng Dry Ca,k loaclng/unloadlng actlvibes.

Form ES-401-5

ES-401 Automatic Action:

Op.rator Action:

Ret.renc.s:

Sample Written Examination Question Worksheet C Temporary shielding not in place for monitors during Dry Cask loading!unloading activitoes D loss of power to NUMAC drawer.

A Control Room and Refuel Zone ventilation isolates B. SGTS initiates C Control Room emergency pressurization units start A

VERIFY alarm conditlOn on the following' 1

REACTOR ZONE EXHAUST RADIATION recorder.

2-RR-90-140 on Panel 2-9-2 2

RX & REFUEL ZONE EXH CH A RAD MON RTMR radiatlOn

",or-Itor. 2-RM*90*140f142 on PaneI2*g*10 3

RX & REFUEL ZONE EXH CH BRAD MON RTMR radl"'lon monltor 2-RM*90-141i143 on PaneI2*g*tO B IF Dry Cask loadingiunloading activities are In progress, THEN NOTIFY the Cask Supervisor to place the MPC In a safe condItion usmg MSI-O-079*DCS037 or as directed by RAD PRO C NOTIFY Shift Manager, Unit 1 and Unit 3 0

IF the TSC is NOT manned. THEN EVACUATE personnel from thE' refuel floor.

E IF the TSC is mannE'd, THEN NOTIFY the TSC to evacuate non-essential personnel from affected areas F

ENTER 2-EOI-3 Flowchart.

G REFER TO 2-AOI-64*2d and. for loss of power to NUMAC drawer, to 2*01*90, Section 6.0.

H. REFER TO 2-AOI-79-1 or 2*AOI-79-2 as applicable.

I.

REFER TO EPIP-t J

REFER TO Technical SpeCIfication Section 3.3.6 2 and 3.3 7 1 2-45E620*3 2-47E610*90*1 GE 2-730E927*21 TVA Calc a

a a

a a a

a a a Technical SpeClfic.ations 3.36.2 and 3.3.7.1 NOOOO90200500 I!EDC63693 Form ES-401-5 ES-401 Automatic Action:

Op.rator Action:

Ret.renc.s:

Sample Written Examination Question Worksheet C Temporary shielding not in place for monitors during Dry Cask loading!unloading activitoes D loss of power to NUMAC drawer.

A Control Room and Refuel Zone ventilation isolates B. SGTS initiates C Control Room emergency pressurization units start A

VERIFY alarm conditlOn on the following' 1

REACTOR ZONE EXHAUST RADIATION recorder.

2-RR-90-140 on Panel 2-9-2 2

RX & REFUEL ZONE EXH CH A RAD MON RTMR radiatlOn

",or-Itor. 2-RM*90*140f142 on PaneI2*g*10 3

RX & REFUEL ZONE EXH CH BRAD MON RTMR radl"'lon monltor 2-RM*90-141i143 on PaneI2*g*tO B IF Dry Cask loadingiunloading activities are In progress, THEN NOTIFY the Cask Supervisor to place the MPC In a safe condItion usmg MSI-O-079*DCS037 or as directed by RAD PRO C NOTIFY Shift Manager, Unit 1 and Unit 3 0

IF the TSC is NOT manned. THEN EVACUATE personnel from thE' refuel floor.

E IF the TSC is mannE'd, THEN NOTIFY the TSC to evacuate non-essential personnel from affected areas F

ENTER 2-EOI-3 Flowchart.

G REFER TO 2-AOI-64*2d and. for loss of power to NUMAC drawer, to 2*01*90, Section 6.0.

H. REFER TO 2-AOI-79-1 or 2*AOI-79-2 as applicable.

I.

REFER TO EPIP-t J

REFER TO Technical SpeCIfication Section 3.3.6 2 and 3.3 7 1 2-45E620*3 2-47E610*90*1 GE 2-730E927*21 TVA Calc a

a a

a a a

a a a Technical SpeClfic.ations 3.36.2 and 3.3.7.1 NOOOO90200500 I!EDC63693 Form ES-401-5

ES-401 Sample Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference:

295025 High Reactor Pressure I 3 Level Tier #

Group #

KIA #

SRO 1

EA2.01 (10CFR 55.43.5 - SRO Only) 1 Ability to determine and/or interpret the following as they apply to HIGH REACTOR PRESSURE:

295025EA2.01 Reactor pressure Importance Rating 4.3 I Proposed Question: # 80 Following a Scram on Unit 2, 2-EOI-1, "RPV Control," 2-EOI-2, "Primary Containment Control,"

and 2-C-5, "Level/Power Control," are being executed. Although direction had been given, an attempt to establish a level band for 2-C-5 resulted in Reactor Water Level dropping to (-) 125 inches before ANY outside action could be completed. Additionally, the following plant conditions exist:

Four SRVs are OPEN at their setpoint(s)

Reactor Water Level is currently being controlled at (-) 75 inches There is NO indication of a steam line break Standby Liquid Control (SLC) is injecting with tank level at 83%

Suppression Pool Level is 17 feet and stable You receive a crew update that 2-EOI-Appendix 8A, "Bypassing Group I RPV Low Low Low Level Isolation Interlocks," has just been completed Which ONE of the following completes the statement?

Based on the above conditions, the correct course of action is to __ _

[REFERENCE PROVIDED]

A. exit the RC/P leg of 2-EOI-1, "RPV Control," AND enter into 2-C-2, "Emergency RPV Depressurization."

B. perform the actions necessary to "Anticipate Emergency Depressurization," per the RC/P Override in 2-EOI-1, "RPV Control."

C. execute 2-EOI-Appendix 8B, "Reopening MSIVs Following a Group I Isolation," per the Override in 2-EOI-1, "RPV Control."

D. augment Pressure Control with RCIC AND RWCU per 2-EOI-Appendix 11 BAND 11 E, "Alternate RPV Pressure Control Systems (RCIC/RWCU)."

I Proposed Answer: A ES-401 Sample Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference:

295025 High Reactor Pressure I 3 Level Tier #

Group #

KIA #

SRO 1

EA2.01 (10CFR 55.43.5 - SRO Only) 1 Ability to determine and/or interpret the following as they apply to HIGH REACTOR PRESSURE:

295025EA2.01 Reactor pressure Importance Rating 4.3 I Proposed Question: # 80 Following a Scram on Unit 2, 2-EOI-1, "RPV Control," 2-EOI-2, "Primary Containment Control,"

and 2-C-5, "Level/Power Control," are being executed. Although direction had been given, an attempt to establish a level band for 2-C-5 resulted in Reactor Water Level dropping to (-) 125 inches before ANY outside action could be completed. Additionally, the following plant conditions exist:

Four SRVs are OPEN at their setpoint(s)

Reactor Water Level is currently being controlled at (-) 75 inches There is NO indication of a steam line break Standby Liquid Control (SLC) is injecting with tank level at 83%

Suppression Pool Level is 17 feet and stable You receive a crew update that 2-EOI-Appendix 8A, "Bypassing Group I RPV Low Low Low Level Isolation Interlocks," has just been completed Which ONE of the following completes the statement?

Based on the above conditions, the correct course of action is to __ _

[REFERENCE PROVIDED]

A. exit the RC/P leg of 2-EOI-1, "RPV Control," AND enter into 2-C-2, "Emergency RPV Depressurization."

B. perform the actions necessary to "Anticipate Emergency Depressurization," per the RC/P Override in 2-EOI-1, "RPV Control."

C. execute 2-EOI-Appendix 8B, "Reopening MSIVs Following a Group I Isolation," per the Override in 2-EOI-1, "RPV Control."

D. augment Pressure Control with RCIC AND RWCU per 2-EOI-Appendix 11 BAND 11 E, "Alternate RPV Pressure Control Systems (RCIC/RWCU)."

I Proposed Answer: A

ES-401 Explanation (Optional):

Sample Written Examination Question Worksheet Form ES-401-5 A

CORRECT: With four SRVs lifting at their setpoint, it can be deduced that Reactor Pressure is 1135 psig. Given a corresponding Suppression Pool Level of 17 feet and the curve for SRV Tail Pipe Limit, the candidate can determine that they are in the ACTION REQUIRED portion of the curve.

Thus, Emergency Depressurization is required for these conditions.

Portions of C-5 will be applicable for the ED, but stem already indicates that candidate is executing C-5. Complexity is compounded by not having the EOI flowchart and the override which is related to the Curve 4, which only says to reduce pressure irrespective of cooldown rate.

S INCORRECT: "Anticipating Emergency Depressurization" is rapidly depressurizing using Turbine Bypass Valves irrespective of cooldown rate.

Stem conditions indicate that we dropped below MSIV Isolation setpoint on Low Reactor Water Level before Appendix 8A was completed. Therefore, MSIVs are closed. Additionally, "Anticipating" is not allowed while in C-5.

C INCORRECT: Although this action would be prudent to pursue, the aforementioned SRV Tail Pipe Limit ACTION REQUIRED dictates otherwise; in that an ED is necessary.

o INCORRECT: Augmenting pressure control might also be a prudent choice. But, because SLC is injecting, RWCU is isolated and not available to augment Pressure Control. RCIC would have an initiation signal present.

Technical Reference(s):

2-EOI-1, Rev. 12

-=~~~~~~------------------

(Attach if not previously provided)

(Including version / revision number) 2-EOI App. 8A / 11 B / 11 E Rev 3 / 5 / 4 Proposed references to be provided to applicants during examination:

2-EOI-1, Curve 4 SRV Tail Pipe Learning Objective:

(As available)

Question Source:

Bank #

(Note changes or attach parent)

New X

~---------

~~----------~