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SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3...

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SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1.a
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Page 1: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

SEQUOYAH NUCLEAR PLANT

1503 NRC RO/SRO ADMIN A.1.a

Page 2: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

SRO

JOB PERFORMANCE MEASURE

Task: Maintain required logs, records, charts, and printouts.

Task#: 1190060301

1503 NRC JPM RO/SRO A.1.a Page 2 of 7

Task Standard: The examinee will assess a high grid voltage condition exists and determine a voltage adjustment cannot be performed, a notification to Transmission Operator must be performed and a log entry must be performed.

Time Critical Task: YES: NO: x ---

KIA Reference/Ratings: 2.1.7 (4.4/4.7)

Method of Testing:

Simulated Performance: Actual Performance: x

Evaluation Method:

Simulator In-Plant Classroom x ----

Main Control Room Mock-up

Performer: Trainee Name

Evaluator: I Name I Signature DATE

Performance Rating: SAT: UNSAT:

Validation Time: 15 min Total Time:

Performance Time: Start Time: Finish Time:

COMMENTS

Page 3: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

1503 NRC JPM RO/SRO A.1.a Page 3 of 7

SPECIAL INSTRUCTIONS TO EVALUATOR:

1. Critical steps are identified in step SAT/UNSAT column by bold print 'Critical Step.'

2. Any UNSAT requires comments.

Tools/Equipment/Procedures Needed:

1. Non LAN connected computer

2. In progress copy of 1-Pl-OPS-000-020.1 OPERATOR AT THE CONTROLS DUTY STATION CHECKLISTS MODES 1-4 Appendix C Monitoring Key Plant Parameters.

References: Reference Title Rev No.

1. 1-Pl-OPS-000-020.1 OPERA TOR AT THE CONTROLS DUTY 64 STATION CHECKLISTS MODES 1-4

2.

====================================================================================

Read to the examinee:

DIRECTIONS TO TRAINEE: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

HAND JPM BRIEFING SHEET TO EXAM/NEE AT THIS TIME!

INITIAL CONDITIONS:

1. Unit 1 is in MODE 1 100%.

2. The intertie transformer is OOS.

3. Main Generator voltage is 22.8 kv.

4. 1-Pl-OPS-000-020.1 OPERATOR AT THE CONTROLS DUTY STATION CHECKLISTS MODES 1-4 Appendix C Monitoring Key Plant Parameters has been completed for the first readings on night shift.

INITIATING CUES:

1. Review the copy of 1-Pl-OPS-000-020.1 OPERATOR AT THE CONTROLS DUTY STATION CHECKLISTS MODES 1-4 Appendix C Monitoring Key Plant Parameters.

2. Assess plant conditions and determine all required actions, if any.

3. Notify the Examiner of your results.

Page 4: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

STEP 3

Comment

STEP 4

Comment

1503 NRC JPM RO/SRO A.1.a Page 5 of 7

500kVSwyd Voltage

(PSO OatAWare P! ~_Jil::M,,.....,,__~--~~-+-~~~~+-~~~

5lOkV (B)

530KV (B)

Appendix E (Page 1of3)

Guidance for Voltage Schedules

1.0 Performance

NOTES

1) In order to ensure compliance with NERC requirements and the Voltage Schedule when the Main Generator is online 500 KV Swyd voltage shall be maintained within 520 ±10 KV (510 KV to 530 KV} as taken during the hourly readings.

2) In the following directions, "achievable reactive power" is defined as the limit for reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter, examples being a stator temperature limit or hydrogen temperature limit or Generator Capability Cuive or limits set by an ODMI.

3) The following step maintains the 500 KV switchyard within an administrative band that provides margin to the NERC Voltage Schedule limits.

[1.3] IF the switchyard voltage is to be lowered, THEN ENSURE the following parameters are maintained:

A. Generator voltage between 22,800 and 24,800 ~~- D

SAT

UNSAT

SAT

UNSAT

Page 5: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

STEP 5

Comment

STEP 6

Comment

Terminating Cue:

1503 NRC JPM RO/SRO A.1.a Page 6 of 7

(8) --MAINTAIN 500kV switchyard voltage within specified limits (520kV+1 OkV) by adjusting reactive load using Appendix E. IF unable to maintain voltage within allowable values, THEN CONTACT Transmission Operator within 30 minutes AND RECORD in narrative logs as specified in Appendix E.

This notification and log entry are required after every hourly reading if voltage remains out of band.

{2.3] LOG the following in narrative log: (This log entry is a NERC requirement)

• Time of voltage deviation D

• Transmission Operator's name D

• Current Reactive Power D

• Generator Voltage D

• Reason SQN is at an achievable limit D

• Transmission Operator Recommendations (if none, state this in log entry.) D

The JPM is complete when the Examinee returns the cue sheet to the Evaluator.

Stop Time

SAT

UNSAT

SAT

UNSAT

STOP

Page 6: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

JPM BRIEFING SHEET DIRECTIONS TO TRAINEE: The examiner will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

INITIAL CONDITIONS:

1. Unit 1 is in MODE 1 100%.

2. The intertie transformer is OOS.

3. Main Generator voltage is 22.8 kv.

4. 1-Pl-OPS-000-020.1 OPERATOR AT THE CONTROLS DUTY STATION CHECKLISTS MODES 1-4 Appendix C Monitoring Key Plant Parameters has been completed for the first readings on night shift.

INITIATING CUES:

1. Review the copy of 1-Pl-OPS-000-020.1 OPERATOR AT THE CONTROLS DUTY STATION CHECKLISTS MODES 1-4 Appendix C Monitoring Key Plant Parameters.

2. Assess plant conditions and determine all required actions, if any.

3. Notify the Examiner of your results.

Acknowledge to the examiner when you are ready to begin.

HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.

Page 7: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

I . (. f.( SQN OPERATOR AT THE CONTROLS DUTY 1-Pl-OPS-000-020.1

Unit 1 STATION Rev.0064 CHECKLISTS MODES 1-4 Paae 32 of 39

Appendix C (Page 4 of 6)

Monitoring Key Plant Parameters

Parameter Min. Max. 1945 2045 2145 2245 2345 0045 0145 0245 0345 0445 0545 0645

Generator Megawatts --- 1230 MW \ 2.\D IXR-57-107)

Generator Mega Vars (7) (7) - \ (1-El-57-8)

Generator H, 45 psig 75 psig -7~ Pressure (10) 11-Pl-'.'l"i-'.'l 1 A\

500 kV Swyd 510kV 530kV Voltage s LIQ

(PSO Da!AWare Pl (8) (8)

s1.;1.;1.on1 \

Condenser 1.6 o,q Pressure --- psi a <PITR-2-2\ m HW Level 15" <LR-2-12)

"'23" \

#1 S/G Level "'33% ""44% 4L\ <FR-3-35)

#2 S/G Level ""33% "'44% 44 IFR-3-48)

#3 S/G Level "'33% ,,,443 Lt4 lFR-3-90)

#4 SIG Level ,,,33% ""44% 41-\ lFR-3-103)

Page 8: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

SQN OPERATOR AT THE CONTROLS DUTY 1-Pl-OPS-000-020.1 Unit 1 STATION Rev.0064

CHECKLISTS MODES 1-4 Page 33 of 39

Appendix C (Page 5 of 6)

Monitoring Key Plant Parameters

Parameter Min. Max. 1945 2045 2145 2245 2345 0045 0145 0245 0345 0445 0545 0645 Pzr Pressure 2220 2260 (PR-68-340) psig psig 22:SS

(2, 3) (2, 3) Pzr Level "" "" ([) (LR-68-339) 25% 60% PRT Level

55% 88% '72-(Ll-68-300) PRT Pressure (p

(Pl-68-301) Auct Tavg (4) (4)

57i.7. (TR-68-28) Tref 547 578.3 S7Z.l (TR-68-28) deg.F deg.F

VCT Level 25% 65% YS (Ll-62-129)

Page 9: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

SQN OPERATOR AT THE CONTROLS DUTY 1-Pl-OPS-000-020.1 Unit 1 STATION Rev.0064

CHECKLISTS MODES 1-4 Page 34 of 39

Appendix C (Page 6 of 6)

Monitoring Key Plant Parameters

Time (9)

Parameter Min. Max. 1945 2045 2145 2245 2345 0045 0145 0245 0345 0445 0545 0645 Ctmt Press (5) 0 .25 ,.02 (PDIR-30-133) psid psid

RM-90-106 N/A N/A li)

(RR-90-106) lS Gas/Particulate

RM-90-112 NIA N/A l.L.71 (RR-90-112)

ft;7 Gas/Particulate NOTES: Specific instruments included for each parameter are recommended data sources for consistency. If the specified instrument is NOT available then use of an alternate is acceptable. (1) - Condenser pressure maximum limit is not applicable when Main Turbine is not in service. (2) - In Modes 1 - 3, log pressure from selected Pressurizer Pressure Channel. Record as N/A when RCS pressure is less than 1700 psig OR when in Mode 4. (3) - RCS pressure limits are applicable at NOP and NOT conditions. (4) - When Main Turbine is in service ENSURE Tavg is within± 5 deg. F ofTref. Minimum RCS temperature in Modes 1 & 2 is 547 deg. F. (5) - Containment pressure channels 1 - 4 computer points may be used if PDIR-30-133 is not available. (6) - US walkdown of MCR panel once prior to mid-shift brief and once prior to end of shift. One walkdown to be a paired observation with OATC. (7) --Minimum and Maximum VAR values can be determined from Appendix D, MVAR Limits for Unit 1 Generator Stability. (8) --MAINTAIN 500kV switchyard voltage within specified limits (520kV±10kV) by adjusting reactive load using Appendix E. IF unable to maintain voltage

within allowable values, THEN CONTACT Transmission Operator within 30 minutes AND RECORD in narrative logs as specified in Appendix E. This notification and log entry are required after every hourly reading if voltage remains out of band.

(9) A 25% grace period is allowed on hourly board monitoring. (10) H2 pressure should be 2: 66 psig if the generator is on line.

Nightshift: OATC SRO (6) Date ___ _

Page 10: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

STEP 1

Standard:

Cue

Comment

STEP 2

Standard:

Comment

1503 NRC JPM RO/SRO A.1.a Page 4 of 7

Start Time

Obtain a copy of 1-Pl-OPS-000-020.1 OPERA TOR AT THE SAT --CONTROLS DUTY STATION CHECKLISTS MODES 1-4 Appendix C

UNSAT Monitoring Key Plant Parameters. --

Copy of 1-Pl-OPS-000-020.1 OPERATOR AT THE CONTROLS DUTY STATION CHECKLISTS MODES 1-4 Appendix C Monitoring Key Plant Parameters is obtained.

Provide an in progress copy of 1-Pl-OPS-000-020.1 OPERA TOR AT THE CONTROLS DUTY STATION CHECKLISTS MODES 1-4 Appendix C Monitoring Key Plant Parameters.

Review the copy of 1-Pl-OPS-000-020.1 OPERA TOR AT THE SAT --CONTROLS DUTY STATION CHECKLISTS MODES 1-4 Appendix C

UNSAT Monitoring Key Plant Parameters. --

The examinee reviews the copy of 1-Pl-OPS-000-020.1 OPERATOR AT THE CONTROLS DUTY STATION CHECKLISTS MODES 1-4 Appendix C Monitoring Key Plant Parameters.

Page 11: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

SEQUOYAH NUCLEAR PLANT

1503 NRC RO/SRO ADMIN A.1.b

Page 12: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

SRO

JOB PERFORMANCE MEASURE

Task: Determine system lineup from a clearance restoration

Task #: 3410280302

1503 NRCJPM RO/SROA.1.b Page 2 of 7

Task Standard: The examinee correctly annotates all components from clearance 1-T0-2014-0038 for restoration.

Time Critical Task: YES: NO: x ---

KIA Reference/Ratings: 2.1.29 (4.1/4.0)

Method of Testing:

Simulated Performance: Actual Performance: x

Evaluation Method:

Simulator In-Plant Classroom x --- ---

Main Control Room Mock-up

Performer: Trainee Name

Evaluator: I Name I Signature DATE

Performance Rating: SAT: UNSAT:

Validation Time: 15 min Total Time:

Performance Time: Start Time: Finish Time:

COMMENTS

Page 13: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

1503 NRC JPM RO/SRO A.1.b Page 3 of 7

SPECIAL INSTRUCTIONS TO EVALUATOR:

1. Critical steps are identified in step SAT/UNSAT column by bold print 'Critical Step.'

2. Any UNSAT requires comments.

Tools/Equipment/Procedures Needed:

1. Non LAN connected computer

2. Copy of clearance 1-T0-2014-0038

References: Reference Title Rev No.

1. NPG-SPP-10.2

Clearance Procedure to Safely Control 9 Energy

1-S0-62-1 Chemical Volume and Control System 69 2.

1-S0-62-1Att1 Chemical and Volume Control System Power Checklist 1-62-1.01

1-S0-62-1 Att 2 Chemical and Volume Control System Power Checklist 1-62-1.02

1-S0-62-1Att3 Chemical and Volume Control System Valve Checklist 1-62-1.03

1-S0-62-1 Att 4 Chemical and Volume Control System Valve Checklist 1-62-1.04

====================================================================================

Read to the examinee:

DIRECTIONS TO TRAINEE: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

HAND JPM BRIEFING SHEET TO EXAM/NEE AT THIS TIME!

INITIAL CONDITIONS:

1. Unit 1 is in MODE 3.

2. 1 B-B Charging Pump has been tagged to replace an Oil Temp Indicator.

3. All work is complete and the clearance has been released for restoration.

INITIATING CUES:

1. Determine the correct restoration position of all components from clearance 1-T0-2014-0038.

2. Notify the Examiner of results.

Page 14: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

STEP 1

Standard:

Cue

Comment

STEP 2

Comment

1503 NRC JPM RO/SRO A.1.b Page 4 of 7

Start Time

SAT Obtain a copy of clearance 1-T0-2014-0038 and 1-S0-62-1 --

attachments. UNSAT --

Copy of clearance 1-T0-2014-0038 and 1-S0-62-1 attachments are obtained.

Provide a copy of clearance 1-T0-2014-0038 and 1-S0-62-1 attachments.

SAT 'lB-B CCP Room 1-62-510 LOCKED

OPEN 1st CV UNSAT

Page 15: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

STEP 3

Comment

STEP 4

Comment

STEP 5

Comment

EQUIPMENT PRINT NO. BREAKER POSITION 1.0.

FUSES INSTALLED

AUX OIL PUMP HANDSWITCH

CCP 18-B 45N765· 16 6.9kV Shutdown Bd 18·8

45N724-2

45N724-4

Comp! 18

1-BCTA-62-104-8

CONNECTED

Eight 30 amp

Buss KLC30

1-FU2-62-104B-B

1-FU2-62-104A-B

1-FU2-62-104C-B

1-FU2-62-104D-B

6.9kV Shutdown Bd IA-A

Comp18

1-HS-62-104M-B

NORMAL

•3 Transfer swrtcnes are located in Aux control Rm.

18-B CCP Aux Oil Pump 45N779-25 480VRx MOV Two 1 amp

[6]

45N751-5 Bd 181-B Buss FRN1 Compt5C2 1-FU2-62-244 1-BCTD-62-244-B

CLOSED

IF in Modes 1-3, THEN

ENSURE 18-B CCP control switch [1-HS-62-104A] in A-AUTO.

1503 NRC JPM RO/SRO A.1.b Page 5 of 7

TRANSFER INITIALS SWITCH '"l SAT

1-XS-62-104 NORMAL ~ CV- UNSAT & SEALED

1st CV

Isl CV

NIA ----1st CV SAT

UNSAT

SAT

UNSAT 1st

IV

Page 16: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

Terminating Cue:

1503 NRC JPM RO/SRO A.1.b Page 6 of 7

The JPM is complete when the Examinee returns the cue sheet to the Evaluator.

Stop Time

STOP

Page 17: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

JPM BRIEFING SHEET DIRECTIONS TO TRAINEE: The examiner will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

INITIAL CONDITIONS:

1. Unit 1 is in MODE 3.

2. 1 B-B Charging Pump has been tagged to replace an Oil Temp Indicator.

3. All work is complete and the clearance has been released for restoration.

INITIATING CUES:

1. Determine the correct restoration position of all components from clearance 1-T0-2014-0038.

2. Notify the Examiner of results.

Acknowledge to the examiner when you are ready to begin.

HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.

Page 18: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

Clearance Coversheet Tagout: 1-T0-2014-0038 Clearance: 1- 62-0468-W/W

Sequoyah Nudear Plant TVA Form 17982 [04-16-2010]

SPP-10.2 Form Date: 04-16-2010

1/9/2015 J.3:38:12

component to be Worked:

( PMP - 62- 104

CENTRIFUGAL CHARGING PUMP 18-B

1-AUX-669-A309 _18 CCPump

Remarks

CENTRIFUGAL CHARGING PUMP 18-B -Replace Oil Temp Indicator. -MMG support WO to drain & refill oil.

NOTE: This clearance provides electrical & flow blocking isolation to support draining of oil from the 18 CCP. No breaching of the eves system is allowed under this clearance.

Remove CCP lB-B from service !AW 50-62-1 section 8.10 prior to dearance placement. 1. Evaluate LCO 3.5.2.; 3.5.3./ 3.1.2.1.; 3.1.2~2./ 3:1.2;3.; & 3,1:.2.4. and 3.8.1.1:/3.8.1.2

Placement Instructions

1. Place clearance.

Caution Tag Information

Release Instructions

1. Release clearance. 2. Perform end device test.

Clearance Attributes:

Attribute

--~~~t:iJ!!~~".1 ----~-·~-------------

FEG Number Work Week or Outage Window

""""""""-- --"""""""""""""-"""" --·--- ""

Scheduled Date Outage Related Clearance? Containment Penetration Breached?

Work Order / CPAL List:

~IJ~l.>~E/ Eq1Jipment I[ 113622564 Oil

CLOSE

1-TI-062-0104A 116026544

CLOSE

1-PMP-062-0104

MMG

'~arance Verification:

Form J.7982 [04-16-2010}

on temperature gauge

CCP lB-B

Attribute Value

1/2

Page 19: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

.~-C/earanc 1 List ?-00 NOT USE FOR TAG P1

'-:MENT OR REMOVAL

Tagout:.;. ..1-2014-0038 Clearance: 1- 62-0468 -W/W

~::e 1~~~i~~:~~ ------------i- - - - - - 1* Equipment Description ,Serial No.!* Equipment Location

r I Ver i Pia iPlacement Reql Seq configuration

' ~------------!*Notes

Place. 1st Verif

Date/Time

Place. 2nd Verif

Date/Time

1 iPULL TO LOCK jWindow III, Tommie C. ~nderson, Terry W. p911s12014 23:12 09;1s;2014 23:13

:oanger 11-HS - 62· 104A -B ' I

j ·1'~9~; --F C-ENtiUFu~~ c~~R~I'N"~ :PUMP lB-B

I. i* 1·CTR·732·MS _MAIN I 1'CONTROL ROOM 1-M-5 ' ' I 145N765·16 . I I :oanger l1~BCTA~ 62~ i04 ·B [IV 2 :oISC OR REMOVED :Smith, David T. r'DeFore, Jason E. i - - - - · ~ ~ · · - · - - · · · · - - · · · - - - ! :- - • -- - -- - - - - - p9!15/2014 23:00 9/15/2014 23:01 11988 f* CENTRIFUGAL CHARGING I I I

!PUMP 18·8 i , ; 1* 2·AUX·734-CN 6900-V i I ' I I - I I ~hutdown Board 18·8, compt I , I 118 I I .

Ver Rest Rest. Conflg. Req Seq *As Left {If Diff.)

Danger il·BCTD· 62· 244 -B ~V 2 pFF pmith, David T. peFore, Jason E. • 2 -~ • -• • • 1· • • -• • • • --"• • -• • "" " • i ,_ • • - """ """ "" " ,09/15/2014 23:03 ,09/15/2014 23:03 I

11993 *CENT CHARGING PUMP ! . '18-B AUX OIL PUMP 1* 1·AUX·749-GJ _480·V tReactor MOV Board 181-B, k:omot SC2

;Dan9er !l·VLV- 62- 510 3 ;~~~~~~---·--· ,Chandler, Phillip E.

:09/15/2014 23:10 ,Lewis, Barry A. 09/15/2014 23:10

11994 i* CENTRIFUGAL CHRG PMP llB-8 SUCT ISOL 1* 1-AUX-669-CCP-B _inside 18·8 CCP Room, 14' up

Component Note No.

213 223

I Note I Text ~t is SQN policy to operate this end device following any activity that removes it from the "CONNECT" position. ~omply with the arc-flash requirements of Safety Procedure 1022 and TI-300.

223 ,Comply with the arc-flash requirements of Safety Procedure 1022 and TI-300. 303 ;Misposition of this device could result in entry into LCO 3.0.3.

Sequoyah ··,ear Plant

SPP-10.2

Rest.1st Verif

Date/Time

01/09/2015 13:38 Rest. 2nd

Verif Date/Time

1-BCTA- 62- 104 -B 1-BCTA- 62- 104 -B

,1-BCTD- 62- 244 -B !1-HS • 62- 104A -B

11 ·HS - 62- 104A -B i

307 Placing the CCP handswitches in the PULL TO LOCK position can render the CCP flowpath inoperable. The CCP and its associated suction valves must be train coordinated, ref. LER 1-92-027, 2-88-010 and 2-88-019. See 47W809-1.

il-BCTA- 62- 104 -B I

11-BCTA- 62- 104 -B

ll-BCTA- 62- 104 -B i ll -BCTD- 62- 244 -8

tl·HS - 62- 104A -B

TVA Form 1.7984 {11.-2005]

Component 11-33-47035-D463

45N724-2 07 4sN765-16 E2 ~5N751-05 '45N765-16

Print Number

Pagel of2

Page 20: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

SEQUOYAH NUCLEAR PLANT

1503 NRC RO ADMIN A.2

Page 21: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

SRO

JOB PERFORMANCE MEASURE

Task: Manually Determine QPTR

Task#: 0150030201

1503 NRC JPM RO A.2 Page 2 of 11

Task Standard: Examinee calculates the highest (worst case) QPTR using O-Sl-NUC-000-133.0 and determines entry into LCO 3.2.4 is required, determines QPTR must be performed hourly, determines power and power range setpoints must be reduced.

Time Critical Task: YES: NO: x ---

KIA Reference/Ratings: 2.1.12(3.7)

Method of Testing:

Simulated Performance: Actual Performance: x

Evaluation Method:

Simulator In-Plant Classroom x --- ----

Main Control Room Mock-up

Performer: Trainee Name

Evaluator: I Name I Signature DATE

Performance Rating: SAT: UNSAT:

Validation Time: 25 min Total Time:

Performance Time: Start Time: Finish Time:

COMMENTS

Page 22: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

SPECIAL INSTRUCTIONS TO EVALUATOR:

1. Critical steps are identified in step SAT/UNSAT column by bold print 'Critical Step.'

2. Any UNSAT requires comments.

Tools/Equipment/Procedures Needed:

1. Non LAN connected computer

2. O-Sl-NUC-000-133.0 QUADRANT POWER TILT RATIO

References: Reference Title

1. O-Sl-NUC-000-133.0 QUADRANT POWER TILT RATIO 2.

1503 NRC JPM RO A.2 Page 3 of 11

Rev No. 15

====================================================================================

Read to the examinee:

DIRECTIONS TO TRAINEE: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

HAND JPM BRIEFING SHEET TO EXAM/NEE AT THIS TIME!

INITIAL CONDITIONS:

1. Unit 1 is in MODE 1 100% power.

2. The Plant Computer is INOPERABLE.

3. QPTR alarm is OPERABLE.

4. DVM was NOT used to collect data.

5. The following data has been obtained from the upper and lower excore detector currents from meters on NIS Drawer B.

N-41A 58 N-43A 63

N-41B 56 N-43B 62

N-42A 64 N-44A 49

N-42B 63 N-44B 55

INITIATING CUES:

1. The SRO has directed you to perform a QUADRANT POWER TILT RATIO calculation.

2. Notify the Examiner of your results and the required actions (if any.)

Page 23: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

I STEP 1

Standard:

Cue

Comment

STEP 2

Standard:

Comment

1503 NRC JPM RO A.2 Page 4 of 11

Start Time

SAT Obtain a copy of O-Sl-NUC-000-133.0 QUADRANT POWER TILT --

RATIO. UNSAT --

Copy of O-Sl-NUC-000-133.0 QUADRANT POWER TILT RATIO is obtained.

Provide a copy of O-Sl-NUC-000-133.0 QUADRANT POWER TILT RATIO.

SAT Select section 6.2 QPTR Determination with plant computer [CTS]

--

inoperable [ITS] nonfunctional. UNSAT --

The Examinee selects section 6.2 QPTR Determination with plant computer [CTS] inoperable [ITS] nonfunctional.

Page 24: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

NOTE

1503 NRC JPM RO A.2 Page 5 of 11

IF a DVM is to be used for section 6.2 then multiply the measured values by 1000 before entering into Step 6.2[1].

[1] RECORD upper and lower excore detector currents from meters on NIS STEP 3 Drawer B below: SAT

NIS Detector NIS Meter Detector Current UNSAT Channel Level (µAmps}

N-41A Upper El-92-5005A It=

N-418 Lower El-92-50058 lb=

N-42A Upper El-92-5006A It=

N-428 Lower El-92-50068 lb=

N-43A Upper El-92-5007 A it=

N-438 Lower El-92-50078 lb=

N-44A Upper El-92-5008A It=

N-448 Lower El-92-50088 lb=

Comment

Page 25: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

NOTE

1503 NRC JPM RO A.2 Page 6 of 11

Values of R1 and Rb change frequently during the initial startup following a refueling outage and periodically throughout the fuel cycle. Reactor Engineering may be contacted for correct values.

UNIT 1

NOTE

This data may be updated during the initial startup following a refueling outage as follows: Prior to initial criticality; at 35% or 45% or 75% power; and at 100% power. This data will also be updated periodically during the fuel cycle. Because of the frequent updates, this data must be verified before it is used to perform any Tech Spec related work.

[2] RECORD values of R1 and Rb from Attachment 4 of Tl-28:

STEP 4 NIS Rt Rb SAT Channel (volts/µ. amp) (volts/µ. amp)

N-41 UNSAT N-42

N-43

N-44 I

Rt Rb Vo!ts/µAmp Vo!ts/µAmp

0.0149 0.0153

0.0130 0.0134

0.0140 0.0146

0.0146 0.0140

Comment

Page 26: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

STEP 5 [3]

Comment

1503 NRC JPM RO A.2 Page 7 of 11

CALCULATE isolation amplifier output voltages using data from steps 6.2[1] and 6.2[2] and the following equations, AND SAT

RECORD below: UNSAT

NIS Detector Isolation Amplifier Channel Level Voltage (volts)

N-41A Upper Vt=

N-418 Lower vb=

N-42A Upper Vt=

N-428 Lower vb=

N-43A Upper Vt=

N-438 Lower vb=

N-44A Upper Vi=

N-448 Lower vb=

Page 27: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

STEP 6 [4]

Comment

1503 NRC JPM RO A.2 Page 8 of 11

CALCULATE average output voltage from upper and lower isolation amplifiers, AND SAT

RECORD below: UNSAT

A. Avg Vt = ______ volts

B. Avg Vb = ______ volts

Page 28: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

STEP 7 [5]

Comment

1503 NRC JPM RO A.2 Page 9 of 11

CALCULATE QPTR values using the following equations, AND

RECORD below:

A. QPTRt =Vt from Step 6.2[3]/Avg Vt from Step 6.2[4]

8. QPTRb =Vb from Step 6.2[3]/Avg Vb from Step 6.2[4]

NIS Detector QPTR Channel Level

N-41A Upper QPTR1=

N-418 Lower QPTRb=

N-42A Upper QPTRt =

N-428 Lower QPTRb=

N-43A Upper QPTRt =

N-438 Lower QPTRb=

N-44A Upper QPTRt =

N-448 Lower QPTRb =

SAT

UNSAT

Page 29: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

STEP 8

Comment

STEP 8

Comment

STEP 8

Comment

Terminating Cue:

1503 NRC JPM RO A.2 Page 10 of 11

[6J CHECK appropriate box to indicate whether the following acceptance criteria was satisfied.

Acceptance Criteria: All OPERAE3LE NIS detectors (upper and lower) indicate a QPTR value less than or equal to 1.02.

[7]

[8]

Yes D No D

IF acceptance criteria was NOT satisfied in step 6.2[6], THEN

[CTS] NOTIFY SM that acceptance criteria was NOT satisfied and the aoolicabfe action reauirement of LCO 3.2.4 must be satisfied.

IF acceptance criteria was NOT satisfied in step 6.2[6], THEN

[CTS] CALCULATE the QPTR once per hour to comply with LCO action 3.2.4.a.1, b.1, or c.1 as applicable and reduce RTP as required and reduce PR trip setpoints as required per O-Sl-IXX-092-N40.0.

The JPM is complete when the Examinee returns the cue sheet to the Evaluator.

Stop Time

SAT

UNSAT

SAT

UNSAT

SAT

UNSAT

STOP

Page 30: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

JPM BRIEFING SHEET DIRECTIONS TO TRAINEE: The examiner will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

INITIAL CONDITIONS:

1. Unit 1 is in MODE 1 100% power.

2. The Plant Computer is INOPERABLE.

3. QPTR alarm is OPERABLE.

4. DVM was NOT used to collect data.

5. The following data has been obtained from the upper and lower excore detector currents from meters on NIS Drawer B.

N-41A 0.58 N-43A 0.63

N-41B 0.56 N-43B 0.62

N-42A 0.64 N-44A 0.49

N-42B 0.63 N-44B 0.55

INITIATING CUES:

1. The SRO has directed you to perform a QUADRANT POWER TILT RATIO calculation.

2. Notify the Examiner of your results and the required a_ctions (if any.)

Acknowledge to the examiner when you are ready to begin.

HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.

Page 31: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

SEQUOYAH NUCLEAR PLANT

1503 NRC SRO ADMIN A.2

Page 32: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

SRO

JOB PERFORMANCE MEASURE

Task: Determine Mode Change Requirements

Task#: 1190150301

1503 NRC JPM SRO A.2 Page 2 of 9

Task Standard: The Examinee will determine that the Mode change from Mode 4 to Mode 3 can be made by invoking LCO 3.0.4 a and 3.0.4 b.

Time Critical Task: YES: NO: x

KJA Reference/Ratings: 2.2.35 (4.5)

Method of Testing:

Simulated Performance: Actual Performance: x

Evaluation Method:

Simulator In-Plant Classroom x --- ----

Main Control Room Mock-up

Performer: Trainee Name

Evaluator: I Name I Signature DATE

Performance Rating: SAT: UNSAT:

Validation Time: 45 min Total Time:

Performance Time: Start Time: Finish Time:

COMMENTS

Page 33: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

1503 NRC JPM SRO A.2 Page 3 of 9

SPECIAL INSTRUCTIONS TO EVALUATOR:

1. Critical steps are identified in step SAT/UNSAT column by bold print 'Critical Step.'

2. Any UNSAT requires comments.

Tools/Equipment/Procedures Needed:

1. Non LAN connected computer

References: Reference Title Rev No.

1. O-G0-1 UNIT STARTUP FROM COLD SHUTDOWN 75 TO HOT STANDBY

2. NPG-SPP-09.11.2 Risk Assessment Methods for Technical 1 Specifications

3 Unit 1 Technical Specifications

====================================================================================

Read to the examinee:

DIRECTIONS TO TRAINEE: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

HAND JPM BRIEFING SHEET TO EXAM/NEE AT THIS TIME!

INITIAL CONDITIONS:

1. Unit 1 is MODE 4.

2. O-G0-1 UNIT STARTUP FROM COLD SHUTDOWN TO HOT STANDBY is in progress.

3. Preparations are in progress to perform a mode change to MODE 3 within the next six hours.

4. The following equipment is currently INOPERABLE:

• SG 1 SGBD Sample Isolation Valve (1-FSV-43-55) was declared INOPERABLE seven days ago due to failing to meet valve stroke acceptance criteria of O-Sl-SXV-043-266.0. The manual isolation valve (2-VLV-1-820) was tagged CLOSED to comply with the applicable LCO action(s).

• RCS PZR Level Instrument Loop (1-L-68-320) was declared INOPERABLE (information only) 12 hours ago. The instrument has been removed from service for emergent MIG repairs. Estimated to be returned to service within the next 72 hours.

• Power Range NI Channel I (N-41) was declared INOPERABLE (information only) three hours ago. Estimated to be returned to service within the next 72 hours.

Page 34: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

INITIATING CUES:

1503 NRC JPM SRO A.2 Page 4 of 9

1. Assess plant conditions and determine if the mode change can proceed.

2. Determine all required actions, if any.

3. Notify the Examiner of your results.

Page 35: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

STEP 1

Standard:

Cue

Comment

STEP 2

Standard:

Comment

1503 NRC JPM SRO A.2 Page 5 of 9

Start Time

Obtain a copy of O-G0-1, UNIT STARTUP FROM COLD SAT SHUTDOWN TO HOT STANDBY, NPG-SPP-09.11.2, Risk --

Assessment Methods for Technical Specifications and Unit 1 UNSAT Technical Specifications. --

Copy of O-G0-1, UNIT STARTUP FROM COLD SHUTDOWN TO HOT STANDBY, NPG-SPP-09.11.2, Risk Assessment Methods for Technical Specifications and Unit 1 Technical Specifications. are obtained.

Provide a copy of O-G0-1, UNIT STARTUP FROM COLD SHUTDOWN TO HOT STANDBY, NPG-SPP-09.11.2, Risk Assessment Methods for Technical Specifications and Unit 1 Technical Specifications.

NOTE SAT

[CTS] Tech Spec and TRM LCO 3.0.4 govern entering Mode 3 if any LCO requirement --

applicable in Mode 3 is NOT met. Therefore, mode change is NOT allowed while in a UNSAT Tech Spec or TRM action, UNLESS the exceptions and/or allowances stated in LCO 3.0.4 --

can be applied.

[ITS] Tech Spec LCO 3.0.4 and TRM TR 7.5.4 govern entering Mode 3 if any Tech Spec!TRM requirement applicable in Mode 3 is not met. Therefore, mode change is not allowed while in a Tech Spec Action or TRM Contingency Measure UNLESS the exceptions and/or allowances stated in Tech Spec LCO 3.0.4/TRM TR 7.5.4 can be applied.

[2.10] [CTS] REVIEW all Tech Spec and TRM actions which have been entered on affected unit and common equipment to verify that mode change is acceptable.

The Examinee will review initial conditions and assess if LCO 3.0.4 can be used to allow the mode change to proceed.

Page 36: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

STEP 3

Comment

STEP 4

Examiner Note

Comment

1503 NRC JPM SRO A.2 Page 6 of 9

3.0A When an LCO is noi. met, entry into a MODE or other specified condition in the Applicability shall only be made:

a_ When the associated ACTIONS to be entered permit continued operation ln the MODE or other specified 0'.1¢1dillon in the Applicab!Uty for an unlimited period of lime;

3.0A When an LCO ls not met, entry into a MODE or other specified condition Jn the Applicabihty shall only be made:

h. After performance of a risk assessment addressing inoperable systems and components, consideration of the results, determrnalion of the acceptability of entering the MODE N other spe<:;ified oondition in the Applfcabi!ity, and establishment of risk managemen! actloos, if appropriate; ext:eplions to this Specification are stated in the individual Specificalions, or

SAT

UNSAT

SAT

UNSAT

Page 37: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

STEP 5

Comment

1503 NRC JPM SRO A.2 Page 7 of 9

-·-- ---------------··-Operations to determine LCOfTR(s) which will become applicable but not met

Multiple Systems/ Components within TSfTR(s) or (a)(4) scope impacted

Yes

Figure 1 (Page 1of1)

Flow Chart for MODE Change Risk Assessment

i r~p~~~;,;~~~~~termin~ . '~~~~ ......... .

~acceptability of -N !Change is i i LCOfTR(s) 3.0.4(b) i ~NOT •

~pplication_;·---···-~j :all~"1>d.:._.._ .. Yes !

.

d·M· e~ .. ·.~:~.·.····~.·.:en!e·e··~ .. ~.a. :·n····a. b. le····· assurance the LCO N will be satisfied in the

0

~.n:J~l~~i_?.~.t.~r::i.~ ______ ,.

Yes

Operations to determine if it Is a System/Component identified as higher risk in Section 3.2.2 (B)?

... !Single TSfTR(s) or (a)(4)

+-------No------~scope System/ Component

·impacted

Yes

...... 1' ...

!Are there any ; unusual conditioos e.g.

,-·---~---------Yes------------------! impending weather condition · ! or grid disturbances

NEDP·26 evaluation lo determine if the results are acceptable?

Identify and establish risk management actions as appropriate

NOTE

.".II modes changes made using the TS LCOITR 3.0.4(b) provision must be approved by the Plant Manager or Designee and documented on Attachment 1 of !his procedure.

2. Mode changes are ailowed without a risk assessment provided !ha! ail four of the following items are true:

a. Only a single TS!TR/Maintenance Rule a(4) system/component impacted.

b. The system/component is not a high risk system.

c_ There is a high probability that the work involved can be completed within the expected completion time.

d. No unusual conditions are present such as impending weather condttions or grid disturbances.

SAT

UNSAT

Page 38: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

STEP 6

Comment

Terminating Cue:

1503 NRC JPM SRO A.2 Page 8 of 9

3.3.3.7 The accident monitoring inslrumentation channels shown in Table 3.3-10 shall be OPERABLE.

APPLICABlLITY: MODES 1, 2 and 3.

ACTIQN: A$ shown in Table 3.:Mo

INSTRUMENT

TABLE 3.3·10

ACCIDENT MONITORING INSTRUMENTATION

TOTAL NO. OF CHANNELS

MINIMUM CHANNELS BEQ!JIRER

7. Pressurizer Level (Wide Range} (Instrument Loops 68·320. ·335.·339)

3 2

ACTION 2 • NOTE:

a.

Also refer to too applicatile action requirements from Tables :t3-1 sinc:e it may contain moi:e res!ricllve actions.

With lhe number of channels one less th.an the minimum cilannels required, restore um iooperable charmel to OPERABLE status within 30 days or be in al least HOT STANDBY within the next 6 hours and in HOT SHUTDOWN within the nexi 6 hours.

The JPM is complete when the Examinee returns the cue sheet to the Evaluator.

Stop Time

SAT

UNSAT

STOP

Page 39: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

JPM BRIEFING SHEET DIRECTIONS TO TRAINEE: The examiner will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

INITIAL CONDITIONS:

1. Unit 1 is MODE 4.

2. O-G0-1 UNIT STARTUP FROM COLD SHUTDOWN TO HOT STANDBY is in progress.

3. Preparations are in progress to perform a mode change to MODE 3 within the next six hours.

4. The following equipment is currently INOPERABLE:

• SG 1 SGBD Sample Isolation Valve (1-FSV-43-55) was declared INOPERABLE seven days ago due to failing to meet valve stroke acceptance criteria of O-Sl-SXV-043-266.0. The manual isolation valve (2-VLV-1-820) was tagged CLOSED to comply with the applicable LCO action(s).

• RCS PZR Level Instrument Loop (1-L-68-320) was declared INOPERABLE (information only) 12 hours ago. The instrument has been removed from service for emergent MIG repairs. Estimated to be returned to service within the next 72 hours.

• Power Range NI Channel I (N-41) was declared INOPERABLE (information only) three hours ago. Estimated to be returned to service within the next 72 hours.

INITIATING CUES:

1. Assess plant conditions and determine if the mode change can proceed.

2. Determine all required actions, if any.

3. Notify the Examiner of your results.

Acknowledge to the examiner when you are ready to begin.

HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.

Page 40: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

SEQUOYAH NUCLEAR PLANT

1503 NRC SRO ADMIN A.3

Page 41: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

1503 NRC SRO ADMIN A.3

SRO

JOB PERFORMANCE MEASURE

Task: Screen Workers for Emergency Exposure.

Task#: 3430290302

Task Standard: Given seven different workers during a life saving emergency, the Examinee will choose two (Varner and Bowman) of the seven for the authorization to exceed the TVA Administrative Dose Levels, determines authorization from the Site Emergency Director is required and the maximum TEDE exposure limit for the conditions given is 25 Rem.

Time Critical Task: YES: NO: x

K/A Reference/Ratings: 2.3.13 (3.8)

Method of Testing:

Simulated Performance: Actual Performance: x

Evaluation Method:

Simulator In-Plant Classroom x --- ----

Main Control Room Mock-up

Performer: Trainee Name

Evaluator: I Name I Signature DATE

Performance Rating: SAT: UNSAT:

Validation Time: 14min Total Time:

Performance Time: Start Time: Finish Time:

COMMENTS

Page 42: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

1503 NRC SRO ADMIN A.3

SPECIAL INSTRUCTIONS TO EVALUATOR:

1. Critical steps are identified in step SAT/UNSAT column by bold print 'Critical Step.'

Tools/Equipment/Procedures Needed:

2. Non LAN connected computer

3. EPIP-15, Emergency Exposure Guidelines

4. Calculator

References: Reference Title

1. EPIP-15 Emerqencv Exposure Guidelines Rev No.

10

=================================================================================== Read to the examinee:

DIRECTIONS TO TRAINEE: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

HAND JPM BRIEFING SHEET TO EXAM/NEE AT THIS TIME!

Page 43: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

1503 NRC SRO ADMIN A.3

INITIAL CONDITIONS:

1. Unit 1 is in MODE 3

2. An event is in progress involving due to failed fuel.

3. The TSC is not operational.

4. An RP Technician reports that an operator working with him in the Unit 1 690 Penetration Room has fallen and is severely injured. He has moved the injured person to an area that is somewhat shielded. Due to rapidly increasing dose rates, the RP Technician leaves to get help. He believes the injuries are life threatening. He also stated that the individual could be retrieved but it would take two people to do so.

5. RP has been contacted and estimates it will take at least 45 minutes to retrieve the victim. Auxiliary Building Area Radiation Monitors indicate extremely high radiation levels.

6. Dose rates at the area needing access are 10.3 Rem/Hr.

7. There are seven people that are available to perform the rescue operation.

Worker Name Age Sex Volunteer YTD TEDE Dose

Shearer 23 years old Male No 137 mrem

Roberts 26 years old Male Yes 132 mrem

Ferry 27 years old Female not declared pregnant Yes 121 mrem

Bowman 45 years old Male Yes 97 mrem

Varner 52 years old Male Yes 65 mrem

Collins 55 years old Male No 25 mrem

Crabtree 57 years old Female not capable of Yes 25 mrem reproduction

8. Crabtree received a planned special exposure of 26 rem TEDE 17 years ago.

INITIATING CUES:

1. You are the Shift Manager in the Control Room.

2. Perform the following:

a) Calculate to three decimal places the total dose each worker would receive performing the rescue operation.

b) Using the guidance provided in EPIP-15 Emergency Exposure Guidelines, assess which two of the seven workers are to be used to perform the rescue operation.

c) Using the guidance provided in EPIP-15 Emergency Exposure Guidelines, determine the required approval prior to the rescue operation.

3. Inform the evaluator when you are complete.

Page 44: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

STEP 1

Standard:

Comment

Examiner Note

STEP 2

Standard:

Cue

Comment

STEP 3

Standard:

Comment

1503 NRC SRO ADMIN A.3

10.3 Rem/hr+ 60 min/1 hr X 45 min= 7.725 Rem

'

Obtain a copy of EPIP-15, Emergency Exposure Guidelines.

Copy of is obtained EPIP-15, Emergency Exposure Guidelines.

Provide a copy of EPIP-15, Emergency Exposure Guidelines.

4.0 REQUIREMENTS

4.1 Guidance for Emergency Dose Limits

Start Time

SAT

UNSAT

Critical step

SAT --

UNSAT --

SAT

UNSAT

Critical Step

Page 45: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

STEP 4

Standard:

Comment

STEP 5

Standard:

Comment

STEP 5

Standard:

Comment

4.0 REQUIREMENTS

4.1 Guidance for Emergency Dose Limits

4.0 REQUIREMENTS

4.1 Guidance for Emergency Dose Limits

REQUIREMENTS

4.1 Guidance for Emergency Dose Limits

1503 NRC SRO ADMIN A.3

SAT

UNSAT Critical Step

SAT

UNSAT Critical Step

SAT

UNSAT Critical Step

Page 46: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

STEP 6

Standard:

Examiner Note:

Examiner Note:

Comment

Terminating Cue:

1503 NRC SRO ADMIN A.3

4.0 REQUIREMENTS

4.1 Guidance for Emergency Dose Limits SAT

G. During declared emergencies TVA Administrative Dose Levels UN SAT (ADLs) shall be amended as shown in Appendix D, Emergency Exposure Reference Guide, however, efforts shall be taken to hold Critical Step doses to the lowest practicable level that the emergency permits. An individual's remaining allowable dose (RAD) is determined by subtracting the year-to-date dose from the applicable 1 OCFR20 exposure limit. Emergency responders that require additional dose in excess of 10CFR20 limits may obtain consent through the completion of Appendix A.

APPENDIX A

Site Emergency Director *

Both Varner and Bowman are expected to exceed the 1 OCFR limit of 5 rem/year during the rescue.

The Examinee may include Site Rad Protection Mgr, RSO, Plant Manager, and Site VP, however using the guidance of EPIP-15 these approvals are not required.

The task is complete when the Examinee returns the cue sheet to the examiner.

Stop Time

STOP

Page 47: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

1503 NRC SRO ADMIN A.3

JPM BRIEFING SHEET DIRECTIONS TO TRAINEE: The examiner will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

INITIAL CONDITIONS:

1. Unit 1 is in MODE 3

2. An event is in progress involving due to failed fuel.

3. The TSC is not operational.

4. An RP Technician reports that an operator working with him in the Unit 1 690 Penetration Room has fallen and is severely injured. He has moved the injured person to an area that is somewhat shielded. Due to rapidly increasing dose rates, the RP Technician leaves to get help. He believes the injuries are life threatening. He also stated that the individual could be retrieved but it would take two people to do so.

5. RP has been contacted and estimates it will take at least 45 minutes to retrieve the victim. Auxiliary Building Area Radiation Monitors indicate extremely high radiation levels.

6. Dose rates at the area needing access are 10.3 Rem/Hr.

7. There are seven people that are available to perform the rescue operation.

Worker Name Age Sex Volunteer YTD TEDE Dose

Shearer 23 years old Male No 137 mrem

Roberts 26 years old Male Yes 132 mrem

Ferry 27 years old Female not declared pregnant Yes 121 mrem

Bowman 45 years old Male Yes 97 mrem

Varner 52 years old Male Yes 65 mrem

Collins 55 years old Male No 25 mrem

Crabtree 57 years old Female not capable of Yes 25 mrem reproduction

8. Crabtree received a planned special exposure of 26 rem TEDE 17 years ago.

Page 48: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

1503 NRC SRO ADMIN A.3

INITIATING CUES:

1. You are the Shift Manager in the Control Room.

2. Perform the following:

a) Calculate to three decimal places the total dose each worker would receive performing the rescue operation.

b) Using the guidance provided in EPIP-15 Emergency Exposure Guidelines, assess which two of the seven workers are to be used to perform the rescue operation.

c) Using the guidance provided in EPIP-15 Emergency Exposure Guidelines, determine the required approval prior to the rescue operation.

3. Inform the evaluator when you are complete.

Acknowledge to the examiner when you are ready to begin.

HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.

Page 49: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

SEQUOYAH NUCLEAR PLANT

1503 NRC RO ADMIN A.4

Page 50: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

SRO

JOB PERFORMANCE MEASURE

Task: Complete a General Emergency Initial Notification Form

Task#: 0001460501

1503 NRC JPM RO A.4 Page 2 of 6

Task Standard: The examinee completes an Appendix A from procedure EPIP-5, General Emergency with no errors on items annotated with a *within 15 minutes.

Time Critical Task: YES: x NO: ---

KJA Reference/Ratings: 2.4.39 (3.9)

Method of Testing:

Simulated Performance: Actual Performance: x

Evaluation Method:

Simulator In-Plant Classroom x ---

Main Control Room Mock-up

Performer: Trainee Name

Evaluator: I Name I Signature DATE

Performance Rating: SAT: UNSAT:

Validation Time: 10 min Total Time:

Performance Time: Start Time: Finish Time:

COMMENTS

Page 51: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

SPECIAL INSTRUCTIONS TO EVALUATOR:

1. Critical steps are identified in step SAT/UNSAT column by bold print 'Critical Step.'

2. Any UNSAT requires comments.

Tools/Equipment/Procedures Needed:

1. Non LAN connected computer

2. EPIP- 1, Emergency Plan Classification Matrix

3. EPIP-5, General Emergency

4. A clock must be available in classroom that all examinees and evaluator can see

References: Reference Title

1. EPIP-5 General Emergency 2.

1503 NRC JPM RO A.4 Page 3 of 6

Rev No. 44

====================================================================================

Read to the examinee:

DIRECTIONS TO TRAINEE: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

HAND JPM BRIEFING SHEET TO EXAM/NEE AT THIS TIME!

INITIAL CONDITIONS:

1. Unit 1 has had a plant event in the simulator

2. The Shift Manager has provided you with the following information:

3. EAL designator is FG1

4. No effluent release is in progress

5. The event was declared Today at 0425

6. The 15 minute average wind direction is from 235 degrees

7. The 15 minute average wind speed is 5 mph

8. The Protective Action recommendation is Recommendation 2

INITIATING CUES:

1. The Shift Manager has directed you to complete the General Emergency Notification form.

2. Return the notification form when complete.

3. There is (are) an element (s) of this task that is (are) time critical.

Page 52: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

·STEP 1

Obtain a copy of EPIP-5, GENERAL EMERGENCY

Standard: Examinee obtains a copy of EPIP-5, GENERAL EMERGENCY.

Cue Provide a copy of EPIP-5, GENERAL EMERGENCY

Comment

1503 NRC JPM RO A.4 Page 4 of 6

Start Time

SAT --

UNSAr --

Page 53: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

NOTES

1503 NRC JPM RO A.4 Page 5 of 6

• Procedure steps can be performed concurrently. All applicable steps must be completed.

• All procedure steps and appendices can be delegated except as noted.

• Completed appendices must be returned to the SEO.

CAUTION

1) Security events or severe weather may present a danger to normal staffing and other Emergency Plan implementation processes. Procedural steps during severe weather and security related events still apply.

2) Notification to State (15 minutes) and NRC (immediately after the notification of the State not to exceed 60 minutes from classification declaration) are Time Critical.

STEP 2

Comment

Examiner Note:

Terminating Cue:

3.2 SQN Risk County and State of Tennessee Notification

NOTE

• Completion of Appendix A should be peer-checked by STA or another SRO.

[1] RECORD time of General Emergency Event Classification ____ _

[2] COMPLETE Appendix A, "General Emergency Initial Notification Form."

NOTE

• Notification of the Risk Counties/State of Tennessee is required to be completed within 15 minutes from the time of emergency declaration.

Annotate the stop time for the initiation of state notification. __ _

The JPM is complete when the Examinee returns the cue sheet to the Evaluator.

Stop Time

SAT

UNSAT

STOP

Page 54: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

SQN Unit 0

GENERAL EMERGENCY

Appendix A (Page 1 of 1)

EPIP-5 Rev.0044 Pa e 14 of 33

GENERAL EMERGENCY INITIAL NOTIFICATION FORM

1. ~This is a Drill D This is an Actual Event - Repeat - This is an Actual Event

2. The SEO at Sequoyah, has declared a GENERAL EMERGENCY.

3. EAL Designator: ___ F (. ________ (Use only ONE EAL)

4. Radiolo ical Conditions: Check one under both Airborne and Li uid column. Airborne Releases Offsite

t&Minor releases within federally approved limits* D Releases above federally approved limits* 0 Release information NOT known *Tech S ecs/ODCM

5. Event Declared: Time: o '-fl. ~ Eastern

Liquid Releases Offsite Jg) Minor releases within federally approved limits* O Releases above federally approved limits* D Release information NOT known *Tech Specs/ODCM

Date: TOP.A:/

6. The Meteorological Conditions are: (Use 46 meter data from the Met Tower. IF data is NOT available from the MET tower, contact the National Weather Service by dialing 9-1-423-586-8400. The National Weather Service will provide wind direction and wind speed.)

Wind Direction is FROM: 1.3 t;' degrees~ Wind Speed: 5 m.p.h

(15 min average) (15 min average)

?.Provide Protective Action Recommendation USING A endix H: Check either 1 or 2 or 3 0 Recommendation 1 WIND FROM -.~. )i'1 Recommendation 2 • EVACUATE LISTED SECTORS (2 mile DEGREES g: • EVACUATE LISTED

Radius & 10 miles downwind) (Mark wind •-~ SECTORS (2 mile radius & 5 • Shelter remainder of 10 mile EPZ. direction from ~· miles downwind) • Consider issuance of POTASSIUM Step 7) •·-~·-.. • SHELTER remainder of 10

IODINE in accordance with the State •.• ~- mile EPZ. Plan. -f • Consider issuance of

.--~-. POTASSIUM IODIDE in N accordance with the State

Plan. A-1, B-1, C-1, D-1, C-2, -6, -7, -8, 0-2, -3, -5, -6 A-1, B-1, C-1, D-1. C-2, D-2 A-1, B-1, C-1, D-1, 0-2,-3,-4, ·5, -6 From 50°-70" A-1, B-1, C-1, D-1, D-2 A-1, B-1, C-1, D-1, A-3, -4, D-2, -3, -4, -5 From 71°-112° A-1, B-1, C-1, D-1, A-3, D-2 A-1, B-1. C· 1, D-1, A-2, -3, -4, -5, -6, D-4 From 113"·146° A-1, 8-1, C-1. D-1, A-2, A-3 A-1, B-1, C·1, D-1, A-2, -3, -4, -5, -6, B-2 From 147°·173° A-1, B-1. C-1, D-1, A-2, A-3, B-2 A-1, B-1. C-1, D-1, A-2. -5, ·6, B-2, -3, -4 From 174·'·214" A-1. B-1, C-1, D-1, A-2, B-2 A-1, B-1, C-1. D-1, B-2, -3, -4, -5, -6, -7, -8 A-1, B-1, C-1, D-1, B-2, B-5 A-1, B-1, C-1. D-1, B-2, -3, -5, -6, -7, -8, C-2, -3. -4, -5, -6 From 259°·331" A-1. B-1, C-1, D-1, B-2. B-5, C-2 A-1. B-1, C-1, D-1, B-5, C-2, -3, -4, 05, -6, -7, -8 From 332°-11° A-1, B-1, C-1. 0-1, B-5, C-2

D Recommendation 3 • SHELTER all sectors • CONSIDER issuance of Potassium Iodide in accordance with the State Plan.

Peer Checked B :

Page 55: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

JPM BRIEFING SHEET DIRECTIONS TO TRAINEE: The examiner will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

INITIAL CONDITIONS:

1. Unit 1 has had a plant event in the simulator

2. The Shift Manager has provided you with the following information:·

3. EAL designator is FG1

4. No effluent release is in progress

5. The event was declared Today at 0425

6. The 15 minute average wind direction is from 235 degrees

7. The 15 minute average wind speed is 5 mph

8. The Protective Action recommendation is Recommendation 2

INITIATING CUES:

1. The Shift Manager has directed you to complete the General Emergency Notification form.

2. Return the notification form when complete.

3. There is (are) an element (s) of this task that is (are) time critical.

Acknowledge to the examiner when you are ready to begin.

HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.

Page 56: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

SEQUOYAH NUCLEAR PLANT

1503 NRC SRO ADMIN A.4

Page 57: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

SRO

JOB PERFORMANCE MEASURE

Task: Classify the Event using the REP

Task#: 3440030302

1503 NRC ADMIN SRO A.4 Page 2 of 12

Task Standard: The Examinee classifies the event as a GENERAL EMERGENCY based on LOSS of any two barriers and Potential LOSS of third barrier and the Examinee completes a TVA Initial Notification for General Emergency form with no errors on items noted with an *.

Time Critical Task: YES: x NO:

KJA Reference/Ratings: 2.4.41. (2.9/4.6)

Method of Testing:

Simulated Performance: Actual Performance: x

Evaluation Method:

Simulator In-Plant Classroom x

Main Control Room Mock-up

Performer: Trainee Name

Evaluator: I Name I Signature DATE

Performance Rating: SAT: UNSAT:

Validation Time: 19 minutes Total Time:

Performance Time: Start Time: Finish Time:

COMMENTS

Page 58: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

1503 NRC ADMIN SRO A.4 Page 3 of 12

SPECIAL INSTRUCTIONS TO EVALUATOR:

1. Critical steps are identified in step SAT/UNSAT column by bold print 'Critical Step.'

2. Any UNSAT requires comments.

Tools/Equipment/Procedures Needed:

1. Non LAN connected computer

2. EPI P- 1, Emergency Plan Classification Matrix

3. EPIP-5, General Emergency

4. A clock must be available in classroom that all examinees and evaluator can see

References: Reference Title

1. EPIP-1 Emergency Plan lnitiatinq Conditions Matrix 2. EPIP-5 General Emerqencv

Rev No. 51 44

====================================================================================

Page 59: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

Read to the examinee:

DIRECTIONS TO TRAINEE:

1503 NRC ADMIN SRO A.4 Page 4 of 12

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

HAND JPM BRIEFING SHEET TO EXAM/NEE AT THIS TIME!

1. Unit 1 has had a plant event

2. Both Containment Spray pumps and Containment Air Return Fans have failed.

3. The TSC has not been manned.

4. The following data was observed

Parameter Indication

Source Range Counts 1 O 4 cps and decreasing

RCS Pressure 1500 psig decreasing

Pressurizer Level Off scale low

Core exit thermocouples All == 650° F and increasing slowly

RCS Subcooling 1O° F superheat

RVLIS Lower range 45% and decreasing

Highest Steam Generator 22% NR and decreasing Level

RCS Cold Leg Temp 245° F and decreasing slowly

AFW Flow to SG 350 gpm

Containment Pressure Peaked at 15 psig and is decreasing rapidly

Wind speed at 46 meters 5 mph

Wind direction at 46 meters 235 degrees

INITIATING CUES: 1. Using the data provided and the applicable procedure (s) classify the event.

2. Do not use SEO judgment as a basis of your classification.

3. Raise your hand when classification is complete.

4. When classification is complete, request from the examiner the correct TVA Initial Classification form, then complete the required form.

5. Determine what, if any, Protective Action Recommendations are required.

6. Raise your hand when you have completed the notification form.

7. There is (are) an element (s) of this task that is (are) time critical.

Page 60: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

STEP 1

Standard:

Cue

Comment

Examiner Note

1503 NRC ADMIN SRO A.4 Page 5 of 12

Start Time

SAT Obtain a copy of EPIP-1, EMERGENCY PLAN CLASSIFICATION --

MATRIX. UNSAT --

Examinee obtains a copy of EPIP-1, EMERGENCY PLAN CLASSIFICATION MATRIX.

Provide a copy of EPIP-1, EMERGENCY PLAN CLASSIFICATION MATRIX.

Annotate start time when the examinee acknowledges the task is understood. Start time

Page 61: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

I

STEP 2

Standard:

Comment

1503 NRC ADMIN SRO A.4 Page 6 of 12

INSTRUCTIONS Note: A condition is considered to be MET if, in the judgment of the SEO, the condition will be MET IMMINENTLY (i.e.: with two hours). The classification shall be made as soon as this determination is made.

1. In the matrix to the left, REVIEW the SAT

initiating conditions in all three barrier -

columns and circle the conditions that UNSAT -

are MET. 2. In each of the three barrier columns,

IDENTIFY if any Loss or Potential Loss INITIATING CONDITIONS have been MET.

Examinee reviews the EMERGENCY PLAN CLASSIFICATION MA TRIX and identifies initiating conditions provided in the initial conditions.

Page 62: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

1503 NRC ADMIN SRO A.4 Page 7 of 12

M'"'"3:·~"'~'ccrr~Jrf5AR~E,tfleun.u'mher'·orharrfer····· STEP 3 . :if1

---- Losses and Potential losses to the SAT

Standard:

Comment

Examiner Note:

Examiner Note:

Examiner Note:

Examiner Note:

Examiner Note:

1 Emergency Class Criteria below and .~~:

~ make the appropriate declaration ~ (i.e.,FG1, FS1, FA 1, FU1 ). ~--~---'-~~~~~~~~~~---=-~~

General Emergency

LOSS of any two barriers and Potential LOSS of third barrier

Annotate the stop time for the event classification here.

Examinee continues with the task to complete the State Notification Form using EPIP-5, GENERAL EMERGENCY. The critical time element continues.

Annotate the start time for the State Notification here.

The start data is provided to the examinee on the JPM briefing sheet.

Examinee transitions to EPIP-5, GENERAL EMERGENCY

UNSAT

Critical Step

Page 63: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

I STEP 4

Standard:

Cue

Comment

Obtain a copy of EPIP-5, GENERAL EMERGENCY

1503 NRC ADMIN SRO A.4 Page 8 of 12

SAT --

UNSAT --

Examinee obtains a copy of EPIP-5, GENERAL EMERGENCY.

Provide a copy of EPIP-5, GENERAL EMERGENCY

Page 64: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

NOTES

1503 NRC ADMIN SRO A.4 Page 9 of 12

• Procedure steps can be performed concurrently. All applicable steps must be completed.

• All procedure steps and appendices can be delegated except as noted.

• Completed appendices must be returned to the SEO.

CAUTION

1) Security events or severe weather may present a danger to normal staffing and other Emergency Plan implementation processes. Procedural steps during severe weather and security related events still apply.

2} Notification to State (15 minutes) and NRC (immediately after the notification of the State not to exceed 60 minutes from classification declaration) are Time Critical.

STEP 5

Comment

Examiner Note:

3.2 SQN Risk County and State of Tennessee Notification

NOTE

• Completion of Appendix A should be peer-checked by STA or another SRO.

[1] RECORD time of General Emergency Event Classification ____ _

[2] COMPLETE Appendix A, "General Emergency Initial Notification Form."

NOTE

• Notification of the Risk Counties/State of Tennessee is required to be completed within 15 minutes from the time of emergency declaration.

Annotate the stop time for the initiation of state notification. __ _

SAT

UNSAT

Page 65: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

STEP 6

Standard:

Examiner Note:

Comment

Terminating Cue:

YES

Appendix H (Page 1of2)

INITIAL· PROTECTIVE ACTION RECOMMENDATIONS

Noto 1~ If (lowc;.hartdeci:>ion block conditions me unknown THl!N an!$wcr NO. Noto 2: S!utu t~go1H~l<.'11> hovo provkh"xi prk,r k.n&NkKJgu of <lrfail(l i<'l'lp()di111nnt~ k1 nvn~~1mlif>tl

1503 NRC ADMIN SRO A.4 Page 10 of 12

SAT

UNSAT

Critical Step

(!>uch 0$ ftoodino. hnrloflfrood 0!o:>ore5. Oii°:} onn rc..-..Qmmond that ;omy nr:Hdc1d PAR shoutrl hu ~•h1'}!h~r(Ft.;,,-. ,:t;~) Noto 3: A ~hort torrn ro!oa1Hl' i~ dofli1od a~ ~:J rofe:ieo that dooi; not oxctwt::l a 15 mtnuto duraHon~

NO To P;agu 2 of2

PAR UPGRADE

The task is complete when the Examinee completes the TVA Initial Notification for General Emergency.

STOP

Stop Time

Page 66: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

1201 NRC SRO ADMIN A.4

JPM BRIEFING SHEET DIRECTIONS TO TRAINEE: The examiner will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

1. Unit 1 has had a plant event

2. Both Containment Spray pumps and Containment Air Return Fans have failed.

3. The TSC has not been manned.

4. The following data was observed

Parameter Indication

Source Range Counts 10 4 cps and decreasing

RCS Pressure 1500 psig decreasing

Pressurizer Level Off scale low

Core exit thermocouples All :::::: 650° F and increasing slowly

RCS Subcooling 1O° F superheat

RVLIS Lower range 45% and decreasing

Highest Steam Generator 22% NR and decreasing Level

RCS Cold Leg Temp 245° F and decreasing slowly

AFW Flow to SG 350 gpm

Containment Pressure Peaked at 15 psig and is decreasing rapidly

Wind speed at 46 meters 5 mph

Wind direction at 46 meters 235 degrees

INITIATING CUES: 1. Using the data provided and the applicable procedure (s) classify the event.

2. Do not use SEO judgment as a basis of your classification.

3. Raise your hand when classification is complete.

4. When classification is complete, request from the examiner the correct TVA Initial Classification form, then complete the required form.

5. Determine what, if any, Protective Action Recommendations are required.

6. Raise your hand when you have completed the notification form.

7. There is (are) an element (s) of this task that is (are) time critical.

Acknowledge to the examiner when you are ready to begin.

HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE

Page 67: SEQUOYAH NUCLEAR PLANT 1503 NRC RO/SRO ADMIN A.1reactive power IAW Appendix D or GOl-6 Section 5.3 without exceeding the Generator Voltage limits or any other generator parameter,

SQN Unit 0

GENERAL EMERGENCY

Appendix A (Page 1of1)

EPIP-5 Rev.0044 Page 14 of 33

GENERAL EMERGENCY INITIAL NOTIFICATION FORM

1. ~ This is a Drill D This is an Actual Event - Repeat - This is an Actual Event

2. The SEO at Sequoyah, has declared a GENERAL EMERGENCY.

3 EAL Designator.-·-'--::..:......_..;;_ _______ , only ONE EAL)

4. Radiolo ical Conditions: Check one under both Airborne and Ll uid column.) · 1 Airborne Releases Offsite Liquid Releases Offsite

~Minor ref eases within federafly approved limits* }zI Minor releases within federally approved limits* D Releases above federally approved limits* 0 Releases above federally approved limits* 0 Release information NOT known D Release information NOT known *Tech Specs/ODCM (*Tech S cs!ODCM

6. The Meteorological Conditions are: (Use 46 meter data from the Met Tower. IF data is NOT available from the MET tower, contact the National Weather Service by dialing 9-1-423-586-8400. The National Weather Service will provide wind direction and_.wind speed.} -1.

Wind Direction is FROM: 13 ;;- degrees""" Wind Speed: . m.p.h ~ (15 min average) 115 mm average)

7.Provide Protective Action Recommendation USING A endix H: 0 Recommendation 1 WIND FROM • EVACUATE LISTED SECTORS (2 mile DEGREES

Radius & 10 miles downwind) (Mark wind • Shelter remainder of 1 O mile EPZ. direction from • Consider issuance of POTASSIUM Step 7)

IODINE in accordance with the State Plan.

A-1.8-1 C-1 D-1.C-2.-6.-7.-8,0-2.-3,-5.-6 A-1, 8-1, C-1, D-i. D-2, -3. -4. -5. -6 A-1. 8-1. C-1. D-1. A-3, -4. D-2. -3. -4. -5 A-1. B-1. C-1, D-1. A-2, -3. -4.-5, -6, 0-4 A-1. 8-1 C-1. D·1. A-2. -3. -4. -5. -6. B-2 A-1. B·1. C-1 D-1. A-2.-5. -6. B-2, -3, -4 A-1. B-1. C-1. D-1, B-2. -3. -4, -5. -6. -7. -8 A-1. B-1, C-1, D-1. 8-2, -3, -5. -6. -7. -8, C-2. ·3, -4, -5. -6 A-1. 8-1, C-1, D·1. B-5. C-2. ·3. -4, 05. -6, -7 -8

0 Recommendation 3 • SHELTER an sectors

From 71"-112' From 113'·146' From 147''-173" From 174"-214'' From 215'-258 From 259°-331° f=rom 332"'~11''

Recommendation 2 :.. EVACUATE LISTED ~ SECTORS (2 mile radius & 5 miles downwind)

• SHELTER remainder of 10 mile EPZ.

• Consider issuance of POTASSIUM IODIDE in accordance with the State Plan.

B-1, C-1, 0-1. C-2. 0-2 A 1. 8-1. C-1. D·1. D-2 A-L B-1. C-1. 0-1. A-3. D-2 A-1 B-1 C-1.D-(.A=2.A-3 A-1. B-1, C-1. D-1 A-2. A-3. B-2 A-1, B-1. C-1 D-1. A-2. B-2 A-1 B-1, C-1, D 1. B-2. B-5 A-1, B·1. C-1, D-1. B·2. B-5. C-2 A-1. 8-1. C-1, D-1. 8-5. C-2

• CONSIDER issuance of Potassium Iodide in accordance with the State Plan.

Peer Checked B :


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