Text

Initial Exam 2012-302 Draft Administrative JPMs
	ML13275A052
Person / Time
Site:	Sequoyah
Issue date:	09/27/2013
From:	; NRC/RGN-II
To:	; Tennessee Valley Authority
References
	Download: ML13275A052 (124)
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RO ADMIN

.1.a

SEQUOYAH NUCLEAR PLANT 1211 NRC RO ADMIN A.1.a

1211 NRC JPM ROA.1.a Page 2 of 7 RO JOB PERFORMANCE MEASURE Task: CONTAINMENT FORMALDEHYDE STAY TIME CALCULATION Task#: 0210030104 Task Standard: Calculate containment formaldehyde stay time and determine respiratory protection requirements in accordance with 0-Tl-OPS-000-00 1.0.

Time Critical Task: YES: NO: X K1A ReferencelRatings: 2.1.26 (3.4/ 3.6)

Method of Testing:

Simulated Performance: Actual Performance: X Evaluation Method:

Simulator In-Plant Classroom X Main Control Room Mock-up Performer:

Trainee Name Evaluator: /

Name I Signature DATE Performance Rating: SAT: UNSAT:

Validation Time: 12 minutes Total Time:

Performance Time: Start Time: Finish Time:

COMMENTS

1211 NRC JPM ROA.1.a Page 3 of 7 SPECIAL INSTRUCTIONS TO EVALUATOR:

ToolslEquipmentlProcedures Needed:

1. 0-Tl-OPS-000-001 .0, Containment Formaldehyde Stay Time Calculation

2. Calculator

References:

Reference Title Rev No.

1. 0-TI-OPS-000-001 .0 Containment Formaldehyde Stay Time Calculation 7 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 EXAMINEE AT THIS TIME!

INITIAL CONDITIONS:

1. Unit 1 is in Mode I at 100% power.

2. A Level Switch inside lower containment needs repair.

3. 0-PI-OPS-000.011.0, Containment Access Control during Modes 1 4, has been initiated in preparation for a lower containment entry to investigate the alarm condition.

4. The containment entry evolution requires at least 120 minutes.

5. A Chemistry sample taken today at 0900 hours0.0104 days 0.25 hours 0.00149 weeks 3.4245e-4 months yielded a lower containment formaldehyde concentration of 1.32 ppm.

6. Section 4.0, Prerequisite Actions, of 0-TI-OPS-000-001 .0 is complete.

INITIATING CUES:

1. Calculate the allowable containment stay time for the given formaldehyde concentration using 0-Tl-OPS-000-001.0 Section 5.1.

2. Identify all required action(s) if any to complete the level switch repair in accordance with 0-TI-OPS-000-001 .0, Containment Formaldehyde Stay Time Calculation.

3. If any actions are required, write them on the JPM briefing sheet.

4. Assume all required tVs have been completed.

1211 NRC JPM ROA.1.a Page 4 of 7 Start Time Obtain a copy of 0-Tl-OPS-000-001 .0, Containment Formaldehyde STEP 1 : Stay Time Calculation. SAT UNSAT Standard Copy of 0-Tl-OPS-000-001 .0, Containment Formaldehyde Stay Time Calculation is obtained.

Provide a copy of 0-Tl-OPS-000-001 .0, Containment Formaldehyde Cue Stay Time Calculation.

Comment NOTES 1> Section 51 may be marked N/A if Unit I Tower containment entry will not be performed

2) Section 5.1 may be marked N/A if only the Annulus or Airlock will be entered OR if breathing apparatus will be worn.

3) O-Tl-CEM-090-016.I or O-Tl-CEM-090-016.2 can be used by Chemistry to determine formaldehyde concentration in containment. Previous sample results may be used if Chemistry or Industrial Safety determines they are valid.

STEP 2 : 5.1 Unit I Lower Containment Entry SAT

[1] RECORD U-i lower containment formaldehyde sample results and sample date/time (from Chemistry). UNSAT ppm DateiTime:

The examinee records the lower containment formaldehyde sample Standard:

results.

Comment

1211 NRC JPM ROA.1.a Page 5 of 7 STEP 3 : 51 Unit I Lower Containment Entry SAT

[2J IF entry to Unit 1 lower containment is required with formaldehyde concentration greater than 1.5 ppm, THEN UNSAT PERFORM the following:

Standard: The Examinee addresses the step as N/A based on the initial conditions.

Comment STEP 4 5.1 Unit I Lower Containment Entry SAT

[31 CALCULATE Unit 1 Lower containment stay time USING the following equation: UNSAT 0.3 ppm X 480 minutes sample recorded Step 5.1 [fi Comment 0.3 ppm X 480 minutes =________ minutes Examiner sample recorded Step 5.1[1]

Note:

0.3 ppm X 480 minutes 144 = 109.1 minutes 1.32 1.32 STEP 5 . 5.1 Unit I Lower Containment Entry SAT

[41 INDEPENDENTLY VERIFY stay time results obtained in Step 5.1[3]. UNSAT Examinee addresses the step as completed based on the initial Standard:

conditions.

Comment

1211 NRC JPM ROA.1.a Page 6 of 7 STEP 6 5.1 Unit I Lower Containment Entry SAT

[71 IF any required task CANNOT be performed within allowed stay time,THEN U NSAT PERFORM the following:

[7.1] CONTACT Industrial Safety for additional guidance.

[7.2] EVALUATE need for Lower Containment Purge in accordance with O-SO-30-3.

17.31 DO NOT CONTINUE task UNTIL one of the following conditions are met:

Job Safety Analysis has been performed.

OR

. Stay time is acceptable.

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 I is in Mode I at 100% power.

2. A Level Switch inside lower containment needs repair.

3. 0-PI-OPS-000.011.0, Containment Access Control during Modes 1 4, has been initiated in preparation for a lower containment entry to investigate the alarm condition.

4. The containment entry evolution requires at least 120 minutes.

5. A Chemistry sample taken today at 0900 hours0.0104 days 0.25 hours 0.00149 weeks 3.4245e-4 months yielded a lower containment formaldehyde concentration of 1.32 ppm.

6. Section 4.0, Prerequisite Actions, of 0-Tl-OPS-000-001 .0 is complete.

INITIATING CUES:

1. Calculate the allowable containment stay time for the given formaldehyde concentration using 0-Tl-OPS-000-001.0 Section 5.1.

2. Identify all required action(s) if any to complete the level switch repair in accordance with 0-TI-OPS-000-001 .0, Containment Formaldehyde Stay Time Calculation.

3. If any actions are required, write them on the JPM briefing sheet.

4. Assume all required IVs have been completed.

Acknowledge to the examiner when you are ready to beg in HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.

C z

SEQUOYAH NUCLEAR PLANT 1211 NRC RO ADMIN A.1.b

1211 NRCJPM ROA.1.b Page 2 of 14 SRO JOB PERFORMANCE MEASURE Task: Monitor Critical Safety Status Trees for Degraded Core Cooling Task#: 3110450601 Task Standard: The Examinee monitors Status Trees and identifies a Red Path for Pressurized Thermal Shock (P.1) and Orange Paths for Core Cooling and Containment.

Time Critical Task: YES: NO: X KIA ReferencelRatings: 2.1.7 (4.4)

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! Signature DATE Performance Rating: SAT: UNSAT:

Validation Time: 6 minutes Total Time:

Performance Time: Start Time: Finish Time:

COMMENTS

1211 NRC JPM ROA.Ib Page 3 of 14 SPECIAL INSTRUCTIONS TO EVALUATOR:

Tools!EquipmentlProcedures Needed:

1-FR-O UNIT 1STATUS TREES

References:

Reference Title Rev No.

1. 1-FR-O UNIT 1 STATUS TREES 2.

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.

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1211 NRC JPM ROA.1.b Page 5 of 14 SIG Pressure SIG NR Levels

1 520 #1 15%

2 550 #2 12%

3 550 #3 12%

4 560 #4 17%

RCS Pressure 0 psig RCS Cold Leg 220 deg F Temperature AFW Flow Containment Pressure 8 psig #1 200 gpm Pressurizer Level 0% #2 170 gpm

3 150 gpm

4 150 gpm INITIATING CUES:

1. You are the Unit 1 CR0.

2. The SRO has directed you to monitor the status trees using 1-FR-0 UNIT I STATUS TREES.

3. Determine if there are any red and/or orange path safety functions.

4. If you have determined there are red and/or orange path safety functions, write them on the JPM Briefing Sheet.

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.

1211 NRCJPM ROA.1.b Page 6 of 14 Start Time Obtain a copy of 1-FR-C UNIT 1 STATUS TREES.

STEP 1 : SAT UNSAT Standard: Copy of 1-FR-C UNIT I STATUS TREES is obtained.

Cue Provide a copy of l-FR-O UNIT I STATUS TREES.

Comment

1211 NRCJPMROA.1.b Page 7 of 14 Monitor Subcriticality STEP 2 SAT sqN SUBCRITICAUTY I-ER-O FO_1 Rev. I UN SAT GO TO FR-Li GO TO FR-S1 GO TO CSF AT NOTE i be1oi 1O %ai nte re ranF.

C peode5 idaio manu GO TO FR42 CF SAT Standard: Examinee determines a green path exists for Subcriticality Comment Examiner The start data is provided to the examinee on the handout sheet.

Note:

1211 NRC JPM RQA.1.b Page 8 of 14 Monitor Core Cooling STEP 3 SAT CORE COOLING SON F-02 Rev I U NSAT GO TO FR.CI GO TO GO TO FR-C 2 GO TO FR-C2 GO TO FR-CL GO TO FR-C2 GOTO FR-C.

Comment Examiner The start data is provided to the examinee on the handout sheet.

Note:

1211 NRC JPM ROA.1.b Page 9 of 14

1211 NRC JPM ROAI.b Page 10 of 14 Monitor Pressurized Therma Shock STEP 5 SAT SQN UNIT 1 PRESSURIZED THERMAL SHOCK lFR-F-O.4 Rv I U NSAT UNIT I CURVE I PTS LiMITS RCS Temprature Oeg F)

Comment Examiner The start data is provided to the examinee on the handout sheet.

Note:

1211 NRCJPM ROA.1.b Page 11 of 14

1211 NRCJPM ROA.1.b Page 12 of 14 Monitor Inventory STEP 7 SAT Inventory SQN F-O6 t-FR--O Rev I U NSAT Standard: Examinee determines a yellow path exists for Inventory Comment Examiner The start data is provided to the examinee on the handout sheet.

Note:

Terminating The JPM is terminated when the Examinee returns the JPM Cue: briefing sheet to the Examiner. STOP Stop Time

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SIG Pressure SIG NR Levels

1 520 #1 15%

2 550 #2 12%

3 550 #3 12%

4 560 #4 17%

RCS Pressure 0 psig RCS Cold Leg 220 deg F Temperature AFW Flow Containment Pressure 8 psig #1 200 gpm Pressurizer Level 0% #2 170 gpm

3 150 gpm

4 l5Ogpm INITIATING CUES:

1. You are the Unit 1 CR0.

2. The SRO has directed you to monitor the status trees using 1-FR-0 UNIT I STATUS TREES.

3. Determine if there are any red and/or orange path safety functions.

4. If you have determined there are red and/or orange path safety functions, write them on the JPM Briefing Sheet.

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.

RO ADMIN A.2

SEQUOYAH NUCLEAR PLANT 1211 NRC SRO ADMIN A.2

1211 NRC JPM RO A.2 Page 2 of 9 SRO JOB PERFORMANCE MEASURE Task: Perform a Reactivity Balance Calculation using 0-SO-62-7, Appendix E Task#: 0040070101 Task Standard: Examinee performs 0-SO-62-7 Appendix E, Reactivity Balance Calculation and determines a dilution is required to reduce RCS boron concentration by 100 ppm. (100 to 104 is allowed)

Time Critical Task: YES: NO: X KIA ReferenceiRatings: 2.2.12 (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: 30 minutes Total Time:

Performance Time: Start Time: Finish Time:

COMMENTS

1211 NRC JPM ROA.2 Page 3 of 9 SPECIAL INSTRUCTIONS TO EVALUATOR:

ToolslEquipmentlProcedures Needed:

1. O-SO-62-7 Boron Concentration Control Appendix E

References:

Reference Title Rev No.

1. O-SO-62-7 Boron Concentration Control Appendix 65 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 EXAMINEE AT THIS TIME!

INITIAL CONDITIONS:

1. Unit I is in MODE 1, Cycle 19 with initial conditions as follows:

2. Time in Core Life is 200 MWD/MTU.

3. Powerisat25%.

4. Boron Concentration 1400 ppm.

5. CBDl85steps.

6. Current Xenon concentration is -2430 pcm FINAL CONDITIONS:

I. Power 100%.

2. CBD228 steps.

3. Final projected Xenon concentration will be -2250 pcm.

4. Power change rate is 3%/hour.

INITIATING CUES:

1. Perform steps 1 and 2 of 0-SO-62-7, BORON CONCENTRATION CONTROL Appendix E, Reactivity Balance calculation.

2. Determine the change in boron concentration, round to the nearest whole number ppm.

1211 NRCJPM ROA.2 Page 4 of 9 Start Time STEP 1 : SAT Obtain a copy of O-SO-62-7 Boron Concentration Control, Appendix E Reactivity Balance Calculation.

UNSAT Copy of O-SO-62-7 Boron Concentration Control, Appendix E Standard Reactivity Balance Calculation is obtained.

Provide a copy of O-SO-62-7 Boron Concentration Control, Appendix E Cue Reactivity Balance Calculation.

Comment REACTIVITY BALANCE CALCULATION NOTE f One osioulation is required for each malor clrane. Caioi.dation is an approximation of required Baron change. Eyeball interpolation of graptta is expected, NOTE 2 Dilution orBoration value for pcrwerchane from % to P% pcreer in time period T with rods moving from step position R, to Rz (Subscdpt convention I = current point. 2 = tarnet point (11 ENTER the toterang data:

STEP 2 : REQUIRED DATA WhereTo Get SAT Current RCS Boron ppm Chem Lab or Estimate using Appendb 0 CoreBumup MWD/MTU ICSUD98I Current Reactor power UNSAT MS or ICS Final Reactor power As required for plant condtaons Total Reactor Power change A Current aid final Reactor power Rate of Reactor power change %lhr As required for plant conditions Numberof houra to change power hr(s) As required for plant conditions ICS or MCR Board Current Rod Position steps Estimate number of rod steps required to Final Rod Postiion steps control Al and rod withdrawal requirements for power change.

Examinee records the data from O-SO-62-7 Boron Concentration Standard:

Control, Appendix E Reactivity Balance Calculation.

Comment Examiner Note:

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

1211 NRC JPM ROA.2 Page 5 of 9 CAUTION Follow sign conventione explicitly. (See Example Power Ascension and Power Redilctionj Figure 1 UIC19 Power Defect BOL NOTE lisa eye-balr interpoiation between losest parameter lines.

[21 CALCULATE thane m borne concentration by peiioming the fo1owEng:

STEP 3 : Parameter WhereTo Get Ataced Pewer Defect Cwes Cacuiaton Value 1 SAT Ia Apec,r,- . pacPD- paePD tfa,ecrn -

tLerRecttt rese)

1211 NRCJPMROA.2 Page 6 of 9 Figure 4 U1C9 Inserted R:od Worth BOL NOTE Use eye-balr intep1atton between closest parameter lines.

12] CAICULATE change n boron cncenlmbon by proformng the thboing:

STEP 5 Where To Get Cacutatton j Value 1 SAT c]

Rods -pan ,.

It12 e11, t2,c.-3. UNSAT

1211 NRCJPMROA.2 Page 7 of 9 12] CAtCUIATE change to boron coocenbabon by perforntng the foJowing:

STEP 6 Parameter Where To Get Ca1cuIatoo I SAT

[d] ftp Ut REAC1W OLE TO PO DEFECT. XENt AftDttOOS) lal tpPDiERDEFECT + pX9Jcto +

UN SAT Comment (2J CAtCULATE change n boron concentrabon by peformtng the toUowtng STEP 7 Parameter Where To Get Calcutatton Value SAT le] ftp re.rot tG4ANGE IN EOON REFCTtVIT)

(1&pcmftp ro r.xL.ctt.ttctt) X (I)

UNSAT

1211 NRC JPM ROA.2 Page 8 of 9 Figure 7 UIC19 Differential Boron Worth NOTE Use eye-bair interpolation between olosest parameter lines 12] CALCULATE vbane in boron cor,cenbebon by pedoming the totlowing:

STEP 8 : Parameter where To Get Catcutation Value SAT rn ppm ICI4ANGE IN BO4GNcTRLtICN)

I tei ÷ Wortt) =

(__________

mpw &ron tw, F1g 7(U-1w Fig. 14 tU-2 U N SAT Comment Examiner Refer to O-SO-62-7 Boron Concentration Control, Appendix E Figure 7 Note: to determine the differential boron worth of -6.18 to 6.17 pcm/ppm.

Examiner .. . .

Initial boron concentration was given in the initial conditions.

Note:

Terminating The JPM is complete when the examinee returns the JPM briefing Cue: sheet to the Examiner. STOP Stop Time

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 I is in MODE 1, Cycle 19 with initial conditions as follows:

2. Time in Core Life is 200 MWD/MTU.

3. Power is at 25%.

4. Boron Concentration 1400 ppm.

5. CBDl85steps.

6. Current Xenon concentration is -2430 pcm FINAL CONDITIONS:

1. Power 100%.

2. CB D 228 steps.

3. Final projected Xenon concentration will be 2250 pcm.

4. Power change rate is 3%/hour.

INITIATING CUES:

1. Perform steps 1 and 2 of 0-SO-62-7, BORON CONCENTRATION CONTROL Appendix E, Reactivity Balance calculation.

2. Determine the change in boron concentration, round to the nearest whole number ppm.

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.

BORON CONCENTRATION CONTROL 1,2 O-SO-62-7 Rev. 65 I

Pag.e 164 of 201 APPENDIX. E Page 1 of 1.8 REACTIVITY BALANCE CALCULATION NOTE I One calculation is required fOr each major change. CalcUlation is an. approximation of required Boron change. Eyeball interpolation of graphs is Oxpected.

NOTE 2 Dilution or Boration vlué for power change from P1 % to P 2

% power in time period T with rod.s moving from step position R 1 to R 2

, (Subscript convention: I = current point, 2 = target point)

[1] ENTER the following data:

DATA REQUIRED. DATA Where To Get Current RCS Boron ppm Chem Lab or Estimate using Appendix 0 Core Burnup MWD/MTU lOS 1)098.1 Current Reactor power NIS or ICS Final Reactor power As required for plant conditions TOtal Reactor Power change A Current and final Reactor power Rate Of Reactor power change.

%Ihr As required for plant conditions Number of hours to change power hr(s) As required for plant conditions Current Rod Position .ICS or MCR Board steps Final Rod Position Estimate nUmber of rod steps required to steps contrOl M and rod withdrawal requirements for power change.

SQb.

BORON CONCENTRA TION CONTROL O-SO-62-7 I *2 Rev. 65 Page 165 of 201 APPENDIX E Page 2.of 18 CAUTION Follow sign conventions explicitly. (See Example Power Ascensiofl and Power Redüction)

[2] CALCULATE change in boron conc entration by performing the following:

Parameter WhereTo Get Calculation Value Attahed Power Defect Curves:.

tal zxp POWER DEFECV Uhit 1: Figure 1, .2, or3 pcm PD, - = (negative pcm 2 PD for power Unit 2: Figure 8, 9, or 10. (current) iXp POWER DEFECT raise) 1 Xeno n From lCS or REACTF (either curren t

NOTE: Xenon reactivity must be nectative conditions or projection to initial condition) (negative

[b] ip XENON 2

Xenon From ICS* or REACTF for rise in pcm Xenon pcm 2 XE (projection over time period T). 1 XE

(ICS Xenon values mut add negative sign). c)

(current) P XENON

[C] /?cp RODS Attached Rod WOrth Curves:

Unit 1: Figure 4,5, cr6 Rod 2s Rodsi (negative (current) for rod UnIt 2: Figure 11, 12, Or 13. J4) RODS insertion) td] i POWER DEFECT + XENON ÷ RODS (CHANGE IN REACTIVY DUE TO POWER DEFECT, XENO N AND RODS) porn fal pomp POWER DEFECT + Th1 pcm p XENON. + RODS =

Eel ip BoRON (CHANGE IN BORON.REACTIVITY) pcm fdl = zr BORON POWER DEFECT -XENON + RODS) X (1)

Efi Appm BORON (CHANGE IN BORON CONCENTRATION)

(negative for dilutions

( Eel pcm p BORON) pcmlppm Boron Worth) positive for

( = ppm boratip from .Fg. 7 (U1).or Fig. 14.(U-2) n) f3J ENSURE independently verified by SRO in accordance with App endix J.

(N/A. if performed by an SROto verify data provided by Rx. Eng)

SQN BORON CONCENTRATION CONTRO 12 L O.-SO-62-7 Rev. 65 Page 168 of 201 APPENDIX E Page 3 of 18 Example Power Ascension NOTE Typical values:displayed in this example are Unit and Cycle specific, however, the followi ng example indicates proper sign convention Current RCS boron 1000 ppm Core bumup 3000 MWD1MTU Current reactor power 70%

Final reactor power 100%

Total reactor power change 30%

Rate of reactor power change 5%/hr Number of hours to change power 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Current rod. position 180 steps Final Rod Position 220 steps Reactivity Balance:

ía] 4PPowérOfet = 1210 pcm PD1 1720 porn P1)2. = 510 porn.

[b] Ap.Xenon = 2262 p.cm XE2 (2436) pcm XEI = ÷174 porn

[c] Ap = 10 porn Rods2 (275) porn Rodsi

+265 pcm

[dl p POWER OEFEOT + XENON + RODS = 510 porn 174 porn 265 porn

+ + = 71 pcm Eel p BORQN = 71 pcm.x (1) = +71 porn Change in Boron PPM:

EI (÷71) porn Boron ÷ 6.35) porn/ppm Boron worth = 11 ppm (dilution)

SON BORON CONCENTRATION CONTROL 1,2 0-60-62-7 Rev. 65 Page 167 of 201 APPENDIX E Page 4 of 18 Example Power Reduction NOTE Typical values displayed in this example are j Unit and Cycle specific, however, the following example indicates proper sign convention.

Current RCS boron 500 ppm Core burnup 18000 MWDIMTU Current reactor power 100%

Final reactor power 80%

Total reactor power change -20%

Rate of reactor power chang -5%/hr Number of hours to change power 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Current roØ position 220 steps Final Rod Position 200 steps Reactivity Balance:

[a] Ap PerOct = 2630 pcm P01 2100 pcm P02 = +530 pcm APXGnOEi = 3030 pom XE2 (2884). pcm XEI = 146 pcm fc] Ap = 220 pan Rpds2 (20) pom Rodsi = 200 pcm d] tSp POWER DEFEOT + XENON + RODS = +530 porn + (146 pcm) + (200 porn) = +184 porn

[e AØBORON +184 pcrnx(1) = 184 porn Change in Boron PPM:

fJ 184 ) pcm Boron {747) pcm/ppm Boron worth = +25 ppm .(boratIon)

SQN BORON CONCENTRATION CONTROL 1,2 0-SO-62-7 Rev. 65 Page 168 of 201 APPENDIX E Page 5 of 18 Figure 1 UICI9 Power Defect BOL NOTE Use eye-ball interpolation between closest parameter lines.

UNIT I CYCLE 19 POWER DEFECT - BOL (150 4000 MWDJMTU) 1700 1OO ppm 1600 - ----

1500 r

1400 1DO ppm

_4_4:

1300 1200

z::

1100 1000 :::E::::::ZE:

900 = :.=. : =::= :=

800 -

700 600 -

500 :: ::: : ::

400

--/4----

300 200 100 EEEEEEEEEEE:

4t 10 20 30 40 50. 60 70 80 90 1u0 Power Level (%)

Reference:

NDR Table 6-23 to 6-27

SQN BORON CONCENTRATION CONTROL 1,2 :O-SO-62-7 Rev, 65 Page 169 of201 APPENDIX E Page 6 of 18 Figure 2 UICI9 Power Detect MOL NOTE Use eye-ball interpolation between closest parameter lines.

UNIT I CYCLE 19 POWER DEFECT - MOL (10,000 MWDIMTU) 2200 2100.

2000 1900 E III I 400 pn*

1800 7 1700 zzzzzIIz:zzzIzIIzz °° 1600. .

4 1500 1400 ppm 1400 ZzIzzzzzzZzIZ.IzZzI

>1300 i200 1100 1000 zzzzz:zzzzzzzzzz 900 ZIZZIZZZZ_IZIZ 800 IZIZ 700 t..

600 500 --

400 -

300 200 100 z zz:

0 - _

0 10 20 30 40 50 60 70 80 90 100 Power Lev& (%)

Reference:

NDR Table 6-23 to 6-27.

SQN BORON CONCENTRATION CONTROL 1,2 O-SO-627 Rev. 65 Page i7O of 201 APPENDiX E Page 7 of 18 Figure 3 UICI-9 Power Defect EOL NOTE Use eye-ball interpolation between closest parameter lines.

UNIT I CYCLE 19 POWER DEFECT - EOL (16 000 -22655 MWD/MTU) 3000-2900 - - 0 ppm 2800 2700-2600 2500 2400 1oo opp 2300 m

2200 2100-2000 1900

>1800 1p 700 =

1r600

-==

=

.___=_______2___=__=

1500 Z.Z 1400 1300.

12O0 z z- = z -Z -Z 1100 1000 900 5

Z ZZZZ0 ZZZZZ0 ZZZZZ 700 Z 600 Z=

500 400 300 -

200 ===ZZ 100 Z=Z 0

0: 10 20 3o 40 50 60 70 80 90 100 PowerLevél (%)

REference: NDR Table 6-23 to 6-27

SQN BORON CONCENTRATION CONTROL I ,2 O-SO-62-7 Rev. 65.

Page 171 of 201 APPENDIX E PageS of 18 Figure 4 Ui C19 inserted Rod Worth BOL NOTE Use eye-ball interpolation between closest parameter lines.

UNIT I CYCLE 19 SQL INSERTED ROD WORTH (150 - 4000 MWD!MTU)

o 20 60 80 100 120 140 160 180 200 220 240 I _L_

11 111:111

-100

-200 - -

-300

-400

-600

-700

$00

-900

.1 1I:i I I L40o0.

i100

.1200

-1300

-1400

-1500 -

-160

-1700

-100

-1900

-2000

-2100

-2200 D BankSteps Withdrawn (steps)

F -

100%Power --75%Power --

-50%Power 25%Pawer p 0%Poj

Reference:

NDR Table 6-34.

SQN BORON CONCENTRATION CONTROL.

1,2 0-SO-62-7 Rev, 65 Page 172 of 201 APPENDIX E Page 9 of 18 Figure 5 UICI9 inserted Rod Worth MOL NOTE Use eye-bail interpolation between closest parameter lines.

UNIT I CYCLE 19 MOL INSERTED ROD WORTH (10,000 MW DIMTU) 0 20

° rrrhrr40t 80 80 100 120 r[rt tc-rr 140 160 180 200 .220 240

LII ILILIL

-300

-400 IHIHHIU

-500

,600 700 ...

c ,.-.. . .

1 -9.00. .

1100

-1300 :

-1400 --

-1500

-1600 * - -

-1700 .-

-1800 - -

-1900 .....-

-2000 .---- . .-.

aimmitiuii 0 Bank Steps Withdrawn (steps) 100% Power Power _--

50% Power 25%PoWer tiv O%Powej

Reference:

NDR Table 6-34.

SON f BORON CONCENTRATION CONTROL 0-SO-62-7 1 2 f Rev. 6:5

[ Page 1 73 of 201 APPENDIX E Page 10 f 18 Figure 6 UICI9 Inserted Rod Worth EOL NOTE Use eye-ball interpolation between closest parameter lines UNIT I CYCLE 19 EOL INSERTED ROD WORTH (16,000 - 22,655 MWDIMTU) a 20 40 60 80 100 120 140 160 180 0 1 200 220 240 L L

-100

-200

-300

-400

-500

-600

-i10U

?;1200

-1300

-160

-1700

-1800.

-1900

-2000

4flfl -

- ,uv -.

-2200 0 Bank Steps Withdrawn (steps)

F 100% Power 75% Power 50% Power 25% Power , 0% Power Reference NOR Table 6-34

[ 1,2 SQN BORON CONCENTRATION CONTROL O-SO-62-7 Rev. 65 Page 174 of 201 APPENDIX E Page Ii of 18 Figure 7 lii Ci 9 Differential Boron Worth NOTE Use eye-ball interpolation between closest parameter lines.

UNIT I CYCLE 19 DIFFERENTIAL BORON WORTH (pcmlp pm).

-6.1

-62 : : ;; BOL 64 b MOL

-6.6 -

-6.7 7.4.

EOL

.7 A.

E -

-78 EE 0 - - - - 400 - - 600 - - BOO - - 1000 1200 - 1400 - 1600 Boron Co noentration. (ppm)

I 801 (2000) MOL (10000) EOL (20671) j Reference NDR Table 6-7

SQN BORON CONCENTRATION CONTROL 1,2 O-SO-62-7 Rev. 65 Page 175 of 201 APPENDIX E Page 12 f 18 Figure 8 U2C18 Power Defect BOL NOTE Use eye-ball interpolation between closest paramete r lines.

UNIT2 CYCLE 18 POWER DEFECT - BOL (0.4000 MWD/MTU) 190 Boo 7 1700 600 1o0 1400 ::: :: :: :: :: :: : .z 1300 12)

EEEEEEEEEHEEEE 1100. ,

F ry 1000 -. 7i

/-

900 0

o800 700 600 500 400 300 200 100 0

0 20 40 60 100 Power LrneI (%)

I 10O0pm 140 )ppm . iaooppmj

Reference:

NOR Table 6-23 to 6-27, Total Power Defect

I SQN 12 BORON CONCENTRATION CONTROL O-SO-62-7 Rev. 65

[ Pagel76of2Ol APPENDIX E Page 13 of 18 Figure 9 U2C18 Power Defect MOL NOTE Use eye-hair interpolation between closest paramete r lines.

UNIT 2CYCLE 48.

POWER DEFECT MOL 4COO-16OOG MWD1VTrU 2300.

2200 2100 2000 1900 .-

1800 .

1700 t_ f 1600 :::::::::::::::,:- ,

1500 1400 .

. 1300 t5 1200 ci 1100 IIOoO 700 600 500 400 300

E::::::::z::::

200

E:::::::E.

100 0

0 10 20 30 40 60 60 70 80 90 100 Power Leve (%)

oqpprn 14o0pPnJ

Reference:

NDR Table 6-23 to 6-27, Total Power Defect

SQN BORON CONCENTRATION CONTROL O-SO-62-7 I ,2 Rev. 65 Page 177 of 201 APPENDIX E Page. 14 of 18 Figure 10 U2C18 Power Defect EOL NOTE Use eye-ban interpolation between closest parameter lines.

UNIT 2 CYCLE 18 POWER DEFECT EOL (16000-20682 MWDIMU) 2900 ---

2800-2700 Z 6W, I

1: : : ZZEI : : :

2400.

2200 7 2100

= EE:ZEE:ZZE 1700

EIEE:EEEEEZ isoo E E E E E EE Z

z : : z z 1200 1100 1000 00 700 600 --::z::EEZ:EEE:

400 ?-E:EEZZZZZ 300 -

0 20 40 6D 80 100

pow&LeI Ø)

Oppm 500 ppm --1000 pmj Referehce: NDR Table 6-23to 6-27, Total Power Defect

SQN BORON CONCENTRATION CONTROL 1,2 O-SO-62-7 Rev. 65 Page 178 of 201 APPENDIX E j

Page 15 of Figure 11 U2C18 Inserted Rod Worth BOL NOTE Use eye-ball interpolation between closest par ameter lines.

UNIT 2 CYCLE 18 BOL INSERTED ROD WORTH (0-4000 MWD IMTIJ) 0

-100

-200 400

-400

-sop

-voo - - -. - -

-800

-1000

-1200 /

-1300 -

- /.:

-1400 -

-1s00

/ ; -.

-1600

-1700 5. - - - - -

1800 - - -- --

1900 2fl00 - I_I -

0 20 40 60 80 100 120 140 180 180 200 220 240 0 Bank StepS Withdrawn (stepa)

I 1O0%Por --75%Power 0%.PGwef ------25%Pawe *

Reference:

NORTable 6-34, HFP Integral Rod Worth as a func tion of Steps withdrawn and burnup for Banks GD, C, B in overlap.

SQN BORON CONCENTRATION CONTROL 0-50-62-7 1,2 Rev. 65 Page 179 of 201 APPENDIX E Page 16 of 18 Figure 12 U2C18 Inserted Rod Worth MOL NOTE Use eye-baII interpolatIon between closest parameter lines.

UNIT 2 CYCLE 18 MOL INSERTED ROD WORTH (4000.1 6000 MWOIMTU) 0 1

-100 :j: :::

-200

-c0

-400

.500

--- -.-- f 00 --

-700 .

0

a. 00

.600 p.,

-1000 1100 I -4200

-Iwo I

-1400 ,

.*I500 1600,

-1700

-1800

.1900 i

-2000 ]:r.L :::::.::::::::::::::_i:

0 20 40 50 0 100 120 140 150 8o 200 220 240 P Bank Steps Withdrawn (steps) iOO%Pow& ---76%ower .50%Pwer .-..-..25Power ..-- 0Pnwej

Reference:

NOR Table 6-34, HFP Integral Rod Worth as a function of Steps withdrawn and burnUp for Banks GD, CC, GB in overlap.

I SON. BORON CONCENTRATION CONTROL O-SO-62-7 1,2 Rev. 65 L Page 180of201 APPENDIX E Page 17 of 18 Figure 13 U2C18 Inserted Rod Worth EOL NOTE Use.éye-baIl interpolation between closest parameter lines.

UNIT 2 CYCLE 1&

EOL INSERTED ROD WORTH 16O0O-2062 MWDJMTU) 0 . . .

-100

-200

-300

-400

-500 00

-700 800

-900.

-1100

.1200

$300

-1400

-1500

-1600 4700 I-

-1800 i/I,.

p

-1900

-2000

-2100

( £ £ I .: : :

220.

0 20 40 80 60 100 120 140 160 180 200 240..

U Bank Steps rawn Øp)

WOPo 75%Powet ----.-5O%Pewe *-2S%Pwe 0%Por

Reference:

NDR.Tabie 6-34, HFP integral Rod Worth as a.function of Step.s withdrawn and burnup forBanks CD,CC, GB in overlap.

(I) 1)

C 0

(3 C

e 0

co 0 jJ

£L 0

Li z

(0 a)

(4 z

a)

(I)

D (wdckwd) 11MUOJOS

SQN BORON CONCENTRATION CONTROL O-SO-62-7 1,2 Rev. 65 ri I2L iç Pagel65of2Ol APPENDIX*.E Page 2 of 18 CAUTION Follow sign conventionsexplicitly. (See Example Power Ascension and Power Reduction.)

12] CALCULATE change in boron concentration by performing the following:

Parameter Where To Get Calculation Value Attached Power Defect Curves:

iegative

[a] tp 30 1 pcm PD - IS 2 pcm PD I ID POWER OEPEcT Unit: 1* Figure 1, 2. 0t3 for power cWrent) POWER DEFECT rse)

Unit 2: Figure8 9, or 10.

Xenoni: From ICS* or REACTF (either Current NOTE: Xenon reacthiity must be negative (negative conditions ørprojectionto initial cónditin) for rise in

[b] tp XENON : From ICS* or REACTF 2

Xenon Xenon (projection over time period T). 21 porn XE 2 i-.1ia pcm XE 1 = conc)

(lcs Xenon values must add negative sign). (current) XENON

[C] RODS Attached Rod Worth Curves: 2 1 Rods (negative pcrn Rods = 3 o.)

Unit 1: Figure 4, 5, or 6 for rod (current) insertion)

Unit 2: Figure 11, 12, or 13. RODS

[dJ zp POWER DEFECT + XENON + RODS (CHANGE IN REACTIVY DUE TO POWER DEFECT, XENON, AND RODS) 2D pcm fal porn Ap POWER DEFECT + N porn ip XENON + fcl pcm ip RODS - at,

= ( -

2. o

{e] BORON (CHANGE IN BORON REACTIVITY) pem p BORON

( fdl PcmPPOWERDEFECT*XENON*RODS) X (1) = 4 1s.

(CHANGE IN BORON CONCENTRATION)

i . - t (negative ppm BORON I7 +o j io for dilution, el IYcrn Ap BORON) + .11 pcm/ppm Boron Wbrth)= 1° ppm

( boration) 14 (U-2)

(from FigL7.(U-i)*or Fig.

[3] ENSURE independently verified by SRO in ccordnce with Appendix .J.

(N/A if performed by an SO to verify data provided byRx. Eng) nH

z U

SEQUOYAH NUCLEAR PLANT 1211 NRC RO ADMIN A.4

1211 NRC JPM ROA.4 Page 2 of 6 SRO JOB PERFORMANCE MEASURE Task: Complete a State Notification Form Task#: 0001460501 Task Standard: The examinee completes an Appendix A from procedure EPIP-5, General Emergency with no errors on items annotated with a .

Time Critical Task: YES: X NO:

KIA ReferencelRatings: 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: /

Name! Signature DATE Performance Rating: SAT: UNSAT:

Validation Time: 10 minutes Total Time:

Performance Time: Start Time: Finish Time:

COMMENTS

1211 NRCJPMROA.4 Page 3 of 6 SPECIAL INSTRUCTIONS TO EVALUATOR:

Tools!EquipmentlProcedures Needed:

1. EPIP-2 NOTIFICATION OF UNUSUAL EVENT Appendix A

2. EPIP-3 ALERT Appendix A

3. EPIP-4 SITE AREA EMERGENCY Appendix A

4. EPIP 5, GENERAL EMERGENCY Appendix A

References:

Reference Title Rev No.

L2. EPIP-5 GENERAL EMERGENCY 42 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 EXAMINEE AT THIS TIME!

INITIAL CONDITIONS:

1. Unit I has experienced a Reactor trip and Safety Injection Today at 1500.

2. The Shift Manager declared a General Emergency at 1510.

3. The reason for the General Emergency is as follows

a. LOSS of the Fuel Clad Barrier EAL Designator 1.1 .2.L.

b. LOSS of the RCS Barrier EAL Designator 1 .2.3.L.

c. Potential LOSS of the Containment EAL Designator 1.3.1.P

4. Airborne and Liquid Radiological Releases Offsite are NOT known.

5. The Shift Manager has issued a Protective Action Recommendation #2 to the State of Tennessee.

6. The 46 meter data from the Met Tower is the wind is from 270 degrees at 10 mph.

7. There are no indications of an Onsite Security Event.

INITIATING CUES:

1. Using the information provided select and complete the correct TVA Initial Classification form.

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

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

1211 NRCJPM ROA.4 Page 4 of 6 Start Time STEP 1 : SAT Obtain a copy of the State Notification Form Handout.

U N SAT Standard: Copy of State Notification Form Handout is obtained.

Cue Provide a copy of the State Notification Form Handout.

Comment STEP 2 : SAT Select EPIP 5, GENERAL EMERGENCY Appendix A from the handout.

U NSAT Comment STEP 3 : SAT Complete EPIP 5 GENERAL EMERGENCY Appendix A.

UNSAT Comment Examiner Note: Compare examinee answers to the answer key.

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 I has experienced a Reactor trip and Safety Injection Today at 1500.

2. The Shift Manager declared a General Emergency at 1510.

3. The reason for the General Emergency is as follows

a. LOSS of the Fuel Clad Barrier EAL Designator 1.1 .2.L.

b. LOSS of the RCS Barrier EAL Designator I .2.3.L.

c. Potential LOSS of the Containment EAL Designator 1.3.1. P

4. Airborne and Liquid Radiological Releases Offsite are NOT known.

5. The Shift Manager has issued a Protective Action Recommendation #2 to the State of Tennessee.

6. The 46 meter data from the Met Tower is the wind is from 270 degrees at 10 mph.

7. There are no indications of an Onsite Security Event.

INITIATING CUES:

1. Using the information provided select and complete the correct WA Initial Classification form.

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

3. The 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.

Appendix A (Page 1 off)

NOUE INITIAL NOTIFICATION FORM

1. D This is .a Drill El This is an Actual Event Repeat This. is an Actual Event

2. -, the SED St Sequoyah has declared a NOTIFICATION OF UNUSUAL EVENT

3. EAL Designator: (USE ONLY ONE EAL DESIGNATOR)

.4. BriefDescription of th eEveht 5.. Radiological Conditions: (Checkone under both Airborne andLiquid column.)

Airborne RléasEs Offsite Liquid Releases Offsite ID Minor releases within federally approved ED Minor releases within federally approved limits* limits*

El Releases above federally approved hmlts* El Releases above federally approved hmlts*

El Release information not known El Release infrrnation not known

(*Tech Specs!ODCM) (*Tech SpecsJODCM)

6. Eve ht..DecJare: Time: Date:.

Eastern Time 7 Provide Protective Action Recommendation El None Completed By Approved By

SCN ALERT EPtP3 Rev. 0034 Page 1 Z of 28 Appendix A (Page 1 of 1)

ALERT INITIAL NOTIFICATION FORM

1. D Thisisa Drill This is an Actual Event Repeat -This !s an Actual EVent

2. the SED. atSequoyah has.declared an ALERT..

3. EALpesignator: only one EAL designator) 4 Brief Description of the Event 5 Radiological Conditions (Check one under both Airborne and Liquid column)

Airborne Releases Offsite Liciuid Releases Offsite IJ Minor releases within federally approved lamtts* C Minor releases within federally approved limlts*

C Releases above federally approved IimIts* C Releases above federally approved Iimits*

C Release information NOT known C Release information NOT known c*Tech SpeosiODGM) (*Tech Specs/ODCM)

6. Event.Declared: Time: Date:

7. Provide Protective Action Recommendation: D None completed By: Approved By:

SQN SITE AREA EMERGENCY EPIP-4 Unit 0 Rev 0034 Page 11 of 27 Appendix A.

(Page 1 of 1)

SITE AREA EMERGENCY INITIAL NOTIFICATION FORM I 12 This is a Drill C This is an Actual Event Repeat This is an Actual Even t

2. ;SED atSequoyah has dedared a Site Area Emergency.

3 EAL Designator two EAL. designators when using the Fission Product Ba rierM atrix) 4, Brief Descriptionof the Evene 5 Radiological Conditions (Check one under both Airborne and Liquid column)

Airborne Releases Offste Liquid Releases Offsite 0 Minor releases within federally approved hmlts* C Minor releases within federally approved hmlts*

C Releases above federally approved bm,ts* C Releases above federally approved limits 0 Release information not known 0 Release information not known

(*Tec$pecs!ODCM) (*Tech SpesiODCM) 6 Event Declared Time__________________ Date_________________

Eastern TIme 7 Provide Protective Action Recommendation C None Goipleted Approved By:

T SQN Unit 0 GENERAL EMERGENCY EPIP-5 Rev. 0042 Page 12 of 31 Appendix A (Page 1 of 1)

GENERAL EMERGENCY INITIAL NOTIFICATION FORM

1. 0 This is a Drill - 0 This is art Actual Event Repeat This is an Actual Event

2. the SED at Sequoyah, has declared a GENERAL EMER GENCY.

3. EAL Designator:__ - three EAL desilors wnei iising the r:jSSjO, Proeuct Barer Mtrix

4. Brief Description of the Event:

5. Radiological Conditions: (Check one under both Airborne_and Liquid_column.)

Airborne Releases Offsite 0 Minor releases within federally approved limits Liquid R&eases Offsite D Minor releases within federally approved limits 0 Releases above federally approved limits 0 Releases above federally approved limits*

0 Release information NOT known 0 Release information NOT known (Tech SpecsiODCM)

(Tech Specs!ODCM

6. Event Declared: Time: I Date:

Eastern -________

7.The Meteorological Conditions are: (Use 46 meter daia from the Met Tower. IF data is NOT available from the MET tower, contact the Nalion al Weather Service by dialing 9-i -423-586-8400. The National Weather Service will provid e wind direction and wind speed.)

Wind Direction is FROM:

Wind Speed: - m.p.h (15 mm avrrage) (15 mm averaj 8.Provide Protective Action Recommendation USING Appen dix H: (Check either I or 2 or 3) 0 Recommendation I WiND FROM

. EVACUATE LISTED SECTORS (2 mile 0 Recommendation 2 C) DEGREES C) EVACUATE LISTED Radius & 10 miles downwind) 0 (Mark wind SECTO RS (2 mile radius & s o Shelter remainder of 10 mile EPZ. direction from miles downwind) e Consider issuance of POTASSIUM Step 7)

SHELTER remainder of 10 IODINE in accordance with the State . mile EPZ.

Plan. .

Consider issuance of O 0 POTASSIUM IODIDE in

.Z Z.

accordance with the State A-I,B-1,C-1.D -l,C-2.-6,-7,-5.D-2,-3.-5.-6

Plan.

Frorn12-4 A-1,B-1.C-1,D-i,C-2.D-2 A-i. B-IC-I. O-1,D-2.-3, 5, -6 From 5O-7D 9 A-lB-i, C-i, 0-1, 0-2 A-i,B-1.C-l,O-I,A-3,-4.fl-2.-3.-4.-5 From7i-112 A-1,B-1.C-I.O-i,A3.D2 A-1.B-I.C-1.D-1,A-2,-3,-4.-5.-6.D-4 FromlI3-146 A-,B-i,C-1.D.A-2.A3 A-I, B-i, C-i. O-i.A-2, 4. -5, -6. 8-2 From i47-173 A-i, B-i. c-i, D-1,A-2, A-3. B-2 A-i. B-i. C-i, 0-1,42-5-6, B-2-3.-4 From 174-2i4 *.*,

41.8-1, C-1.D-i,A-2 B-2 A-1.B-I.G-i,D-1,B-2,-3.-4.-5,-6-7,-8 From215-256 A-1,6-1,-1,D-1.2.B5 A-i, B-I, C-I. D-i, B-2.-3, -5, -6, -7,-B, C-2, -3.-4.-,-6 . From259-331 A-i,B-1.C-1 0-1, B-2,8-5,C-2 A-tB-i. C.-1,D-1.B-5.C-2.-3. -45 .6.78 Frcm332-W

.* A-1.-1, C-I. D-1.B-5. C-2 0 Recommendation 3

SHELTER all sectors

. CONS!DER issuance of Potassium Iodide in accordance with the State Plan.

Completed By: Approved By:

jLjI NIL-C.. 1-O A-[

SQN GENERAL.EMERGENGY EPIP5 Unit 0 Rev. 042 Pagei2of3l Appendix A (Page 1. of 1)

GENERAL EMERGENCY INITIAL NOTIFICATION FORM

1. D This is a Drill C This is an Actual Event Repeat This is an Actual Event

2. , the SED at Sequoyah, has declared a GENERAL EMERGENCY.

3. EAL .

Designator. .I 1 2 .1 23L 1l P . . .

three EAL designators when using the Fission Product Barrier Matrix)

4. Brief Description of the Event:

5. Radiological Conditions: (Check one under both Airborne and Liquid column.)

Airborne. Releases Offsite Liquid Releases Offsite C Minor releases within federally approved limits* C Minor releases within federally approved limits*

C Releases above federally approved Hmits* C Releases above federallyapproved limits*

D Release information NOT koown Release infprmation NOT known

(*Tech SpecsIODCM) fTeóh SpecsIODCM) 6 Event Declared: Time i ID Date: ToD..f j Eastern 7.The MeteoroogicaI Conditions are: (Use 46 meter data from the.Met Tower IF data is..NOT available from the MET tower, pontact the National Weather Service by dialing 9-1-423-586-84OO The1iâfionl Weather Service will provide winddireótion and wiiid speed.)

Wind Direction sFROM: V7 0 degrees Wind Speed: m.ph

thfavérae (15 mm average..

8.Provide Protective Action Recommendation USING Appendix H: heck either I or2*or 3)

C Recommendation I WIND FROM Recommendation 2

. EVACUATE LISTED SECTORS(2 mile DEGREES

EVCIJA1EL1$TEO Radius & 10 miles downwind) (Mark wind SEGTORS 2 mile radius..3 5 a Shelter remainder of IG mile EPZ. direction from miles downwind)

. Consider issuance of POTASSIUM Step 7)

SHELTER remainder of 10 IODINE in accordance with.the State TYlile EPZ Plan. -

a Consider. issuance, of POTASSIUM IQDIDE in acordance with the State Plan.

A-1,.B-1,C-i)D-1,C-2,$,-7,-8,D-2-3,-5-6 IWf!$ Frorni2°-49° A-1,B-1,C-1,O-tC-ZD-2 A-I,B-i,C-1,D-1,D-2,-3,4,-5,-6 From 50°-T0° A-i,B-1,C-1,D-i.D-2 A1,Bi,C1,D1,A4D2,4,4,5 From7i°-112° A-1,B-1,C-I,O-1,A-3,D-2 A-1,B-1,G-1,D-1,A-2-3.-4-5,-6,D-4. FromIl3°-146° . A-i,8-i,C1,01,A2,A-3 A-i,.B-1,O-1,D-I,A-2,-3,-4,-5,-6B-2 From147°-173 .. A-i, B-i,C-1,D-i,A-2, A-3B-2 A-I, B-I, C-I, D-j,.A-2. -5, -6, 5-2, -3, -4 From 174°-214° O-1,A-2, B,-2 A 1 9-1 C-i 0-i B 2 - 5 6 -7 4 From 215° 2580 A 1 8 1 C-1 0 1 8-2 8 5

.A1,B..1,C..i,D4,B..2,..3,,5,-6,-7,-8,C-2,-3,.4,-5,-5 { From259°-331° A-1,B-1,C-1,D-1,8-Z8-5.C-2 A-I,8-i..C1,D-1.B-5.C-2,.4,4,O5,-6,-7-8 .

% From332°-I? A-i,B.I,CI.Di.B-5.C-2 C Recommendation 3.: , ..

.( .

SHELTER all sectors a CONSIDER issuance of PotassiUm IOdide in accordance with the State Plan.

Completed By: Approved By:

11H M2c )Z? A-j

SRO ADMIN

.1.a

SEQUOYAH NUCLEAR PLANT 1211 NRC SRO ADMIN A.1.a

1211 NRC JPM SRO A.1.a Page 2 of 8 SRO JOB PERFORMANCE MEASURE Task: Determine the Operability of a BAT before use.

Task#: 1190100302 Task Standard: Determine the operability of BAST C prior to placing tank in service.

Time Critical Task: YES: NO: X KIA ReferencelRatings: 2.1.25 (3.9/4.2)

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! Signature DATE Performance Rating: SAT: UNSAT:

Validation Time: 10 mm Total Time:

Performance Time: Start Time: Finish Time:

COMMENTS

1211 NRC JPM SROA.1.a Page 3 of 8 SPECIAL INSTRUCTIONS TO EVALUATOR:

ToolsIEquipmentlProcedures Needed:

1. TRM

2. TRM Figure 3.1.2.6

3. 1-Sl-OPS-000-003.W, Weekly Shift Log page 24

4. JPM Chemistry Handout

References:

Reference Title Rev No.

1. TRM Technical Requirements Manual 46

2. 1-SI-OPS-000-003.W Weekly Shift Log 51 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 EXAMINEE AT THIS TIME!

INITIAL CONDITIONS:

1. Unit 1 is at 100% power

2. Preparations are in progress to place a clearance on BAT A for Maintenance.

3. BAT C level is indicating 9,600 gallons on 0-Ll-62-242.

INITIATING CUES:

1. You have been directed to determine operability status for BAT C level using 1-Sl-OPS-000-003.W, prior to aligning BAT C to Unit 1.

2. Determine the minimum level for required for the operability of BAT C.

3. Determine if the clearance evolution may continue.

4. Notify the Examiner of results when determination of operability has been completed.

1211 NRC JPM SROA.1.a Page 4 of 8 Start Time STEP 1 : SAT Obtain a copy of 1-Sl-OPS-000-003.W, Weekly Shift Log, JPM 421 Chemistry Handout and the TRM. UNSAT Standard: Copy of 1-Sl-OPS-000-003.W, Weekly Shift Log, JPM 421 Chemistry Handout and the TRM are obtained.

Provide a copy of 1-SI-OPS-000-003.W, Weekly Shift Log page 24, JPM 421 Chemistry Handout and the TRM figure 3.1.2.6.

Comment STEP 2 : SAT Examinee goes to 1-SI-OPS-000-003.W to review BAT C Level operability requirements. UNSAT Standard: Examinee reviews I -SI-OPS-000-003.W, Appendix A, SR requirements for BAT C level operability.

Comment

1211 NRC JPM SROA.1.a Page 5 of 8 STEP 3 : SAT Examinee utilizes the TRM and reviews TR 3.1 .2.6.a.1 requirement for BAT C level. UNSAT Examinee utilizes the TRM and reviews TR 3.1 .2.6.a.1 requirement for Standard BATC level.

Comment STEP 4 : SAT Examinee goes to TRM Figure 3.1.2.6.

UNSAT Standard: Examinee goes to TRM FIGURE 3.1.2.6 Examiner .

The figure required to be used is found on page 3? 4 1-10.

Note Comment STEP 5 : Examinee selects the appropriate line on FIGURE 3.1.2.6, Boric Acid SAT Concentration, as determined from the data on the Operations Information page, Attachment 1, to determine region of acceptable UNSAT operation.

Comment

1211 NRC JPM SROA.1.a Page 6 of 8 STEP Examinee selects the appropriate line on FIGURE 3.1.2.6 based on U-6 SAT 1 RWST Boric Acid Concentration as determined from data on the Operations Information page, Attachment 1, to determine the region of acceptable operation. UNSAT Comment STEP Examinee determines minimum BAT C level in gallons by locating the 7 SAT intersection of the line for the RWST and BAT Boron concentrations and verifying the actual level in the tank is less than the minimum level indicated on TRM page 3/ 4 1-10 Boric Acid Tank Levels. UN SAT Comment If Examinee addresses the statement at the bottom of graph Examiner concerning the indicated values including the unusable volume and Note: the instrument error, they should explain the contained water volume limits include allowance for water not available and is discussed in the TRM bases.

1211 NRC JPM SROA.1.a Page 7 of 8 Terminating The JPM is complete when the Examinee returns the cue sheet to Cue: the Evaluator. STOP Stop Time

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 at 100% power

2. Preparations are in progress to place a clearance on BAT A for Maintenance.

3. BAT C level is indicating 9,600 gallons on 0-Ll-62-242.

INITIATING CUES:

1. You have been directed to determine operability status for BAT C level using 1-SI-OPS-000-003.W, prior to aligning BAT C to Unit 1.

2. Determine the minimum level for required for the operability of BAT C.

3. Determine if the clearance evolution may continue.

4. Notify the Examiner of results when determination of operability has been completed.

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.

Operations nformation 1 (_________________

Sample Point Units Boron Date I Time Goal Limit UI RCS ppm 660 Today/XXXX Variable Variable U2 RCS ppm 968 Today/XXXX Variable Variable UI RWST ppm 2550 Today/XXXX -

2550 2650 -

2500 2700 U2 RWST ppm 2589 Today/XX)(X -

2550 2650 -

2500 2700 BAT A ppm 6764 Today/XXXX Variable Variable BAT B ppm 6872 Today/XX)(X Variable Variable BAT C ppm 6450 Today/XXXX Variable Variable UI CLA #1 ppm 2532 iwo Weeks Ago/XXX) 2470-2630 2400-2700 UI CLA #2 ppm 2542 Fwo Weeks Ago/X)(X) 2470-2630 2400-2700 UI CLA #3 ppm 2546 rwo Weeks Ago/X)(X) 2470-2630 2400-2700 UI CLA #4 ppm 2515 rwo Weeks Ago/XXX) 2470-2630 2400-2700 U2 CLA #1 ppm 2555 Last Week/XXXX 2470-2630 2400-2700 U2 CLA #2 ppm 2502 Last Week/XXXX 2470-2630 2400-2700 U2 CLA #3 ppm 2579 Last Week/XXXX 2470-2630 2400-2700 U2 CLA #4 ppm 2540 Last WeekIXXXX 2470-2630 2400-2700 Spent Fuel Pool ppm 2659 :Last Week/X)(XX > 2050 > 2000

\ LifluiuiResü1ts Pate I11me Goal Midpoint Ui RCS Lithium ppm 2.44 Today/XXXX 2.26-2.52 2.39 U2 RCS Lithium ppm 3.51 Today/XXXX 3.28-3.54 3.41

, *, Prna to Seønda Larae Infornatg Woal GPM RM-9O-9$1 19)

Indicator Units UI Date I Time U2 DatelTime SI 50 5/0 Leakage? Yes/No No Today/)(XXX No Today / Now SI 137.5 CVE Leakrate gpd <0.1 Last Week/XXXX <0.1 Today / Now 5 gpd leak equivalent cpm 115 Today I Now 85 Today / Now 30 gpd leak equivalent cpm 490 Today I Now 308 Today I Now 75 gpd leak equivalent cpm 1165 Today / Now 710 Today / Now 100 gpd leak equivalent cpm 1540 Today I Now 933 Today I Now 150 gpd leak equivalent cpm 2290 Today! Now 1380 Today / Now Bkgd on 99 /119 cpm 40 Last WeekIXXXX 40 Today / Now Correlation Factor 99/119 cpmlgpd 5.31 Last Week/XXXX 0.854 Today! Now Steady State conditions are necessary for an accurate determination of leak rate using the CVE Rad Monitor

WM FIGURE 3.1.2.6 Uni1 & 2)

I BORIC ACID TANK LIMITS

[BASED ON RWST BORON CONCENTRATION 11000 j

I I I I IE.GION_OFACCEPTA8LEOPERAT1] .

1 p 10500. J RWST2500ppmB I I I RWST 255Qpprl 10000

N.. ,/

,RWsT_=_2600 z

U, A_RWST=26 5opprh8 S-J 0

ytRT2700PPm i_

Lii z

-i 0

> 9000

- 6I20 ppm (Mrnurn z .------

I --

0 -

C)

- (6990PPmaxum)J. --

0 0

U I 8000 C.,

I REGION OF UNACCEPTABLE OPERATION 7000 nFra.

6500 :_: i :::::__

6000 6100 6200 6300 6400 6500 6600 6700 6800 6900 7000 7100 BORIC ACID TANK CONCENTRATION PPM BORON RWST Cncnfraoa 42500 PPM 2550PPM w--2600 PPM m2650PPM E2700 PPM SEQUOYAH UNITS 1 AND 2

- 314 1-10 September 26, 2003 TECHNICAL REQUIREMENTS Revision Nos. 13, 26, 27

APPENDIX A Page 17 of 22 SR T.S.

DESCRIPTION MODE NOTE INSTRUMENT UNITS DATA REMARKS REFERENCE LIMITS With Mm of 23 Spent Fuel Pit Water Level 4.9.11 spent 1 Local depth gage (J) ft above el 734 fuel in fuel pool TR 4,5,6 11 6400 Gal.

4.1.2.5.a.2 gal.

Boric Acid Tank A Level TRM 1-M-6 TR 1,2,3 12 figure 1-LI-62-238 Gal.

4.1 .2.6.a.2 3.1.2.6 TR 4,5,6 11 6400 Gal.

4.1.2.5.a.2 gal.

Boric Acid Tank C Level TRM 1-M-6 TR 1,2,3 12 figure 0-Ll-62-242 3.1.2.6 Gal.

4.1.2.6.a.2 TR 370,000 1-Ll-63-46 4.1.2.6.b.2 1,2,3,4 13,14 or Gal.

4.5.5.a. 1 375,000 1 -LI-63-49 RWST Level 10% or 1-Ll-63-50 or TR 4,5,6 11 55,000 1-LI-63-51 or 1-M-6 orGal.

4.1.2.5.b.2 gal 1-Ll-63-52or 1 -Ll-63-53 UO/RO REVIEW NOTES

1. Verify water level is above bottom mark on depth gage installed on west wall of spent fuel pit. If water level is in the bottom of the normal range, then contact MCR to make-up to high in the normal range per 0-SO-78-1.

11. In modes 4, 5 and 6 one boric acid storage tank or RWST is required to be operable. IF Control Room indication is lost, REFER to GOI-6 for alternate means of obtaining RWST level.

12. In modes 1, 2, and 3 one boric acid storage tank is to be operable if required by LCO 3.1.2.2.

13. In modes 1, 2, 3, and 4 RWST is required to be operable. IF Control Room indication is lost, REFER to GOI-6 for alternate means of obtaining RWST level.

14. IF deviation of 1000 gallons exists between channels, THEN submit Service Request (SR) to have transmitter repaired.

So AJ.

IRM FIGURE 3,126 (Units I &

2)

I BORIC ACID TANK LIMItS ON RWST BORON CONCENTRAT ION 6000 6100 6200 6300 &400 65O0 600 6700 6600 600 000 7100 BoR1ACED TANK CONCENT RATION PPM BORON RWST Cm I PO .-.2580PPM W2600 PPM -266OPPM. ?7Ø0 PPM SEQUQAH-UNETS I AND 2. 3/4 1-10 TECHNiCAL REQU IREMENTS September26, 2003 Revision Nos. 13 26,27 1:i

SEQUOYAH NUCLEAR PLANT 1211 NRC SRO ADMIN A.1.b

1211 NRCJPMSROA.1.b Page 2 of 9 SRO JOB PERFORMANCE MEASURE Task: Perform an RCS Void Determination and Apply the Result to Determine RCS Pump Sweep Requirements.

Task #: 33440100302 Task Standard: The examinee will:

1. Determine that the volume required to pressurize the RCS from 50 to 340 psig is 1733 (1733.4 acceptable) gallons.

2. Evaluates Steps 19, 20 and 21 of GO-i, Section 5.5.1 and determines that sweeps and vents must be continued.

Time Critical Task: YES: NO: X KIA ReferencelRatings: 2.1.7 (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! Signature DATE Performance Rating: SAT: UNSAT:

Validation Time: 20 minutes Total Time:

Performance Time: Start Time: Finish Time:

COMMENTS

1211 NRCJPMSROA.1.b Page 3of9 SPECIAL INSTRUCTIONS TO EVALUATOR:

ToolslEquipmentlProcedures Needed:

1. 0-GO-i, UNIT STARTUP FROM COLD SHUTDOWN TO HOT STANDBY Section 5.5.1 and Appendix E Handout

References:

Reference Title Rev No.

1. 0-GO-i UNIT STARTUP FROM COLD SHUTDOWN TO 65 HOT STANDBY 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 EXAMINEE AT THIS TIME!

INITIAL CONDITIONS:

1. 0-GO-I, UNIT STARTUP FROM COLD SHUTDOWN TO HOT STANDBY, Section 5.5.1 RCP Sweeps and Vents, is in progress, completed through step i7.

2. The first 30 second run of #4 RCP is the only RCP sweep that has been completed.

3. 0-GO-I, UNIT STARTUP FROM COLD SHUTDOWN TO HOT STANDBY, Appendix E, RCS Void Volume Determination, has been completed through step 10.

INITIATING CUES:

I. Complete 0-GO-i, UNIT STARTUP FROM COLD SHUTDOWN TO HOT STANDBY, Appendix E, RCS Void Volume Determination, starting at step 11 to determine the volume (total makeup) that was required during the pressurization of the RCS from 50 psig to 340 psig.

2. Review 0-GO-I, UNIT STARTUP FROM COLD SHUTDOWN TO HOT STANDBY, Section 5.5.1, RCP Sweeps and Vents, starting at step 18 to determine the required actions (if any) to be taken.

1211 NRCJPMSROA.1.b Page 4 of 9 Start Time STEP 1 : Obtain a copy of GO-I UNIT STARTUP FROM COLD SHUTDOWN TO SAT HOT STANDBY, Appendix E, RCS Void Volume Determination, and Section 5.5.1 Individual RCP Sweeps and Vents Following Maintenance UNSAT Activities.

Copy of GO-I UNIT STARTUP FROM COLD SHUTDOWN TO HOT Standard: STANDBY, Appendix E, RCS Void Volume Determination, and Section 5.5.1 Individual RCP Sweeps and Vents Following Maintenance Activities.

Provide a copy of GO-i UNIT STARTUP FROM COLD SHUTDOWN TO HOT STANDBY, Appendix E, RCS Void Volume Determination, and Cue Section 5.5.1 Individual RCP Sweeps and Vents Following Maintenance Activities.

Comment 1.0 REACTOR COOLANT SYSTEM LOOPS FILLED STEP 2 DETERMINATION. SAT

[11] DETERMINE volume required to pressurize the RCS U NSAT from 50 psig to 340 psig as follows:

(11.1] Determine makeup volume added based on change in Boric Acid Batch Counter [FQ-62-1 39] totalizer readings.

Final reading Initial reading gallons (step 10) (StepS)

1211 NRCJPMSROA.1.b Page 5 of 9 4,0 REACTOR COOLANT SYSTEM LOOPS FILLED STEP 3 DETERMINATION. SAT (1121 Determine makeup volume added based an change in UNSAT Primary Water Batch Counter [FQ-62-142] readings.

Final reading InThal reading gallons (step 10) (Step 6)

Comment 1.0 REACTOR COOLANT SYSTEM LOOPS FILLED STEP 4 DETERMINATION. SAT 111 .3J Determine change in VCT leveL UNSAT Initial level Final level % change (step 6) (Step 10)

1211 NRCJPMSROA.1.b Page 6 of 9 1.0 REACTOR COOLANT SYSTEM LOOPS FILLED STEP 5 DETERMINATION. SAT 111.41 Convert VCT level change to gallons as follows: U NSAT X 19.27

% change gallons! % gallons (step 11.3)

Comment NOTE A higher final VCT level will result in the change in VCT level being subtracted from total totaiizer change.

1.0 REACTOR COOLANT SYSTEM LOOPS FILLED STEP 6 DETERMINATION. SAT

[121 DETERMiNE total volume required to pressurize RCS. UNSAT

+ +1-change in Bonc change in Pci. change in Total makeup Acid totahzer Water totalizer VCT level required (Step 11.1) (Step 1L2) (Step 1L4)

I gab an ar oa ie o 1733ga11o e

Comment Examiner The following actions are taken from GO-I UNIT STARTUP FROM Note: COLD SHUTDOWN TO HOT STANDBY, Section 5.5.1, RCP Sweeps and Vents.

1211 NRCJPMSROA.1.b Page 7 of 9 5.5.1 Individual RCP Sweeps and Vents Following Maintenance STEP 7 Activities (continued) SAT

[191 IF total makeup required in App. E is less than U N SAT or equal to 465 gal Examinee evaluates step 19 of GO-i, Section 5.5.1 and determines Standard:

step is N/A.

Comment 5.5.1 Individual RCP Sweeps and Vents Following Maintenance STEP 8 : Activities (continued) SAT

[20J IF total makeup required in App. E is between 465 gal UNSAT and 1723 gal Standard: Examinee evaluates step 20 of GO-I, Section 5.5.1 and determines step is N/A.

Comment 5.5.1 Individual RCP Sweeps and Vents Following Maintenance STEP 9 Activities (continued) SAT

[21] IF total makeup required (App E) is greater than 1723 gal UN SAT OR additional RCP sweeps and vents are desired, THEN PERFORM the following:

[211] IF sweeps and vents have NOT been completed for afi four indMdual RCS loops, THEN GO TO Step 55.1[6]. D

1211 NRCJPMSROA.1.b Page 8 of 9 Terminating The JPM is terminated when the Examinee returns the JPM Cue: briefing sheet to the Examiner. STOP Stop Time

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. 0-GO-I, UNIT STARTUP FROM COLD SHUTDOWN TO HOT STANDBY, Section 5.51 RCP Sweeps and Vents, is in progress, completed through step 17.

2. The first 30 second run of #4 RCP is the only RCP sweep that has been completed.

3. 0-GO-I, UNIT STARTUP FROM COLD SHUTDOWN TO HOT STANDBY, Appendix E, RCS Void Volume Determination, has been completed through step 10.

INITIATING CUES:

I. Complete 0-GO-I, UNIT STARTUP FROM COLD SHUTDOWN TO HOT STANDBY, Appendix E, RCS Void Volume Determination, starting at step II to determine the volume (total makeup) that was required during the pressurization of the RCS from 50 psig to 340 psig.

2. Review 0-GO-i, UNIT STARTUP FROM COLD SHUTDOWN TO HOT STANDBY, Section 5.5.1, RCP Sweeps and Vents, starting at step 18 to determine the required actions (if any) to be taken.

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.

SQN UNIT STARTUP FROM COLD Unit I .&2 0-GO1 SHUTDOWN TO HOT STANDBY Rev. 0065 Page 44 of 155 Unit I Date 5.5 RCS Sweeps and Vents Following Mainte nance Activities

.5.5.1 lndMdual RCP Sweeps and Vents Follow ing Maintenance Activities GN

Starting RCP with a large AT between RC S and SIGs (secondary side warmer than primary side) could lead to a rapid. RCS pre ssure change. Maximum delta T .haII be limited tO 25°F.

During UI Cl 6 RFOl 285 gallons of bor ated water was required for.sweeps and ven ts.

4 PERFORM O-Sl-OPS-000-O04.O on an hou rly basis to verify temperatures greater than 70°F (TRM 4,7.

2).

Use of an isolation valve on vent hose is spe cified to avoid spilling borated water

o.n reactor vessel head when hose is disconn ected later.

ENSURE temporary manual valve installed at hos e connection for 168-5971 Reactor Vessel vent valve.

NOTIFY Chemistry and Radiation Protection RCS swe eps and Vents activities will be performed.

ENSURE IFGV-68-340D1 and 1FcV68-340B1, Normal Spr ay 1 valves OPEN.

71 RCP sWeeps and vents could cause a crud burst which could impact filter D/P.

NOTIFY AUO to periodically monitor seal water injection filter and reactor coolant filter D/P during and following sweeps and vents.

.SQN UNIT STARTUP FROM COLD Unit I & 2 0-GO-I SHUTDOWN TO HOT STANDBY Rev 0065.

[

Page45of 155 Unit I Date 9 cv; ,4 5.51 Individual RCP Sweeps and Vents Following Maintenance Activities (continued)

NS Starting RCP #4 FIRST is preferred in order to swee

on the Loop 4 hot p air AWAY from the RHR suction leg.

0 Each RCP wilt need individual copy .of this subs loop Preparations in 1(2)-SO-68-2 for RCP ection for each. sweep performed on a.

start may be in progress on all be started prior to completion ofthis subsection. ROPs to 5 SELECT RCP to be. STARTED.

PUMP RCPNo4 it RCPNo.. I El RCPNo.2 El RCPNo.3 El VERIFY instruments necessary for RCP. operation

/ are available.

CQN Performing sweeps and vents with PCV-62-81 in AUT O could result in erratic RCS pressure changes and possible óverpressure conditi on. (INPO OE 25091)

ENSURE fl-IIC-62-81A1 Letdown Pressure Control in MANUAL.

WHEN.RCS pressure is greater than 100 psig TI-lEN ENSURE 1FCV62-63l, seal return isolation valve OPEN using 1HS-62-63Al ENSURE fFcV-62-611, seal return isolation valve OPEN using IHS-62-61 Al.

INDEPENDENTLY VERIFY fFcV-62-631, seal return isolation valve is OPEN.

IV

SON UNIT STARTUP FROM COLD Unit I &. 2 0-GO-I SHUTDOWN TO HOT STANDBY Rev. 0065 Page 46 of 155 Unit I Date 1P1 5.5.1 Individual RCP Sweeps and Vents Following Main tenance ActivIties (continued) f INDEPENDENTLY VERIFY IFCV-62-611, seal return isolation valve, is OPEN.

lv CA1N RCS pressure should be maintained at approxim ately greatest margin from the setpoint of the RHR syste 340 psig. This will prOvide the m relief valves and ensure adequate RCP seal D/P.

FlOws in the following step may be mismatched to stabilize pressure when RCP is started, E1 ADJUST flhlC-62-81A1 and/or [HIC-62-93A1 to stabilize RCS pressure át340 psig.

NOTE Prior to unit cooldown each Loose Parts: Monitoring Channel for shutdown unit is placed in Inhibit to eliminate unnecessary nuisance alarms Therefore required:during RCP starts (ref. .GOl6 Sect W). , man ual monitoring is

( MONITOR Loose part MonitoringSystem (Aux Inst Rm O-R-1 39) for abnormal noise during each RCP start.

CAUTIONS Operators should be aiertfor pressure changes when RçP.is started Expected Y response is a drop in pressure due to slight temperature drop as flow is circulated through SIGs and air is compressed.

RCS pressure should be controlled within the following limits:

RCP seal DIP greater than 220 psid.

RCS pressure less than 405 psig (RHR press high alarm, M-6C window E-7).

This prevént lifting RRR reliefs and provides margin from LTOPS setpornt Iv V

If any uncontrollable ROS pre.sure changes occurs RCP should be immediately stopped to allow restoring RCS pressure.

START selected RCP per I (2)-SO-68-2.

SQN UNIT STARTUP FROM COLD Unit I & 2 0-GO-I SHUTDOWN TO HOT STANDBY Rev. 0065 Page 47 of 155 Unit I I0AA Date 55.1 Individual RCP Sweeps and Vents Following Ma intenance Activities (continued) j4? WHEN selected RCP has been operated for 30 sec onds AND has been STOPPED.

THEN CONTINUE. with step 5.5.1f14.

ADJUST 1HIC-62-81A and/or IHIC-62-93A1 to initia V te RCS pressure reduction to -50 psig.

WHEN RCS pressure is less than 100 psig,

THEN CLOSE IFcV-62-631, seal return isolation valve.

RCS pressure reduction is acceptable when venting head and pressurizer..

PERFORM Appendix F to vent reactor head.

PERFORM the following to vent, the pressurizer:

!ij OPEN one pressurizer PORV.

[ WHEN level rise observed in PRT, r THEN CLOSE pressurizer PORV.

If Appendix E cannot be completed due to equipment unavailabthty, then Steps 5 5 1 [18]

through 5 5 1 [20) should be marked N/A Additional sweeps and ven ts will be performed in Step 55,i[21]

WHEN reactor head arid pressurizer have been vented, THEN PERFORM Appendix E, RCS Void Volume Determination.

SON UNIT STARTUP FROM COLD Unit I &2 0-GO-I SHUTDOWN TO HOT STANDBY Rev. 0065 Page 48 of 155 Unit_______

Date

.5.5.1 Individual RCP Sweeps.and Vents Follow ing Maintenance Activities (continued)

[19] IF total makeup. required in App. E is less than or equal to 465 gal AND no further sweeps and vents are desired THEN PERFORM the following:

[19.1] RECORD the following in narrative log:

. no further sweeps and vents are required

credit CANNOT be taken for a filled RCS. and 2 S/Gs per Tech. Spe.c LCO 3.4.1.4 UNTIL the RCS is pressurized to 150 psig 119.2] MARK Steps .5.5I 120] and ..5.5.I[21] as N/A.

D

[19.31 GOTO Section 5.3 Step 5.3122.

C

[201 IF total makeup required in App. E is beNveen 465 gal and 1723 gal AND. no further sweeps and vents are.de.sired, THEN PERFORM the following:

120.11 RECORD the, following in narrative log:

no further sweeps and vents are required

credit CANNOT be taken for filled RCS and 2S/Gs per Tech Spec LCO 3.4.1.4 UNTIL opposing loop RCPs are in service (after bubble is drawn).

12O2] MARK Step 5.5.1(21] as N/A. C 120.3] GO TO Sectin 5.3 Step 5.3t22. C

SON UNIT STARTUP FROM COLD Unit I & 2 0-GO-I SHUTDOWN TO HOT STANDBY Rev. 0065 Page 49 of 1.55 Unit_______

Date 5.5.1 Individual RCP Sweeps and Vents Following Ma intenance Activities (continued)

[21) IF total makeup required App. E) is greater than 1723 gal OR additional RCP sweeps and vents are desired, THEN PERFORM the following:

[21.1) IF sweeps and vents have NOT been completed for all four individual RCS loops, THEN GO TO Step 5.5..1[6].

C

[212] IF sWeeps and vents are complete for all individual RCS loops, THEN PERFORM Section 5.52 for Multiple RCP Sweeps.

End of Section

1 SON UNIT STARTUP FROM COLD 0-GO-I J Unit I &.2 SHUTDOWN TO HOT STANDBY Rev. 0065 L Pagal44of 155 Appendix E (Page 1 of 4)

RCS VOID VOLUME DETERMINATION Unit t Date 1.0 REACTOR COOLANT SYSTEM LOOPS FILLED DETERMINATION.

MONITOR RCS pressure rise by using of the following I EQUIPMENT INDICATION NUMBER jis Hot Leg Press Wide Range P-68-68A (P0499A)

LRCS Hot Leg Press Wide Range P1-68-62 (P2000A)

ADJUST [HlC$2-81A aridior IHIC-62-93A1 as nece ssary to maintain RCS pressure stable at 50 psig.

This appendix will require raising RCS pressure to 340 psig Performance of O-SlOPS-000-004 0 is required to verify SIG temperatu re prior to exceeding 200 psig This SI must. be repeated hourly thereafter UNTIL. RCS and S/G pressures are less than 200 psig OR until an RCP is placed in service.

PERFORM 0-Sl-OPS-000-004.O on an hourly basis to verif y

S1G.temperatures greater than 70°F (TR 4.7.2).

ENSURE RCS temperature is between 85°F and i05°F ENSURE VCT makeup system is aligned for AUTO operation in accordance jth 0-SO-62-7, Boron Concentration Control.

SQN UNIT STARTUP FROM COLD Unit I .& 2 0GO-1 SHUTDOWN TO HOT STANDBY Rev. 0065 Page 145 of 155 Appendix E (Page 2 of 4)

RCS VOID VOLUME DETERMINATION Unit I lOA%4 Date 1.0 REACTOR COOLANTSYSTEM LOOPS FILLED DETERMINATION. (contihued)

RECORD the following nitiaI values:

VCT level using one of the following:

. Computer point [LOl 12A] (tO k OR

s. VCT level indicator [LI-62-129]

Boric AcId Batch Counter [FQ-62-I 39] totalizer

. 91.941 i.) Primary Water Batch Counter [FQ-62142] totalizer

. AON Charging flow must be maintained wtakeup capaci ty. CCP*suction must remain aligned to VCT to allow accurate measurement of volum e changed.

ADJUST IHIC-62-81A1 and/or IHIC-62-93A1 to raise RCS pressure to 340 psig.

4? WHEN RCSpressureis greater than 100 psig, 7 THEN OPEN IFGV-62-63i, seal return isolation valve using IHS-62-63A1.

OPEN IFCV-62-611, seal return isolation valve using IHS$2-61A1.

INDEPENDENTLY VERIFY [FCV-62-631, seal return isolation valve is OPEN.

INDEPENDENTLY VERIFY IFCV-62-611, seal return isolation valve is OPEN.

I SQN UNIT STARTUP FROM COLD Unit I & 2 0-GO-I SHUTDOWN TO HOT STANDBY Rev. 0065 PageI4SofI.65 Appendix E (Page 3 of 4)

RCS VOID VOLUME DETERMiNATION Unit I Date_______

1.0 REACTOR COOLANT SYSTEM LOOPS FILLED DETERMINATION (continued)

WHEN RCS pressure is 340 psig, THEN ADJUST IHI.C-62-BIAI :and/or 1Hi to maihtain RCS pressure stable C-62-93A as necessary at 340 psig.

RECORD the following final values:

VCT level using one of the following:

Computer point tLOi 12A] 2.

VT level indicator [Ll-62-i 29]

2iS Boric Acid Batch Counter [FQ-62-I 39] totalizer

(/

Primary Water Batch Counter [FQ-62-I42 totalizer DETERMINE volume required to pressurize the. RCS from O psig to 340 psig as follows:

Determine makeup volume added based on change, in Boric Acid Batch Counter [FQ-62-I39] totallzer readings.

Final reading Initial reading gallons (step 10) (Step 6)

[1121 Determine makeup volume added based on change in Primary Water Batch Counter [FQ-62-142] readings.

Final reading Initial reading gallons (step 1.0) (Step 6)

S.QN UNIT STARTUP FROM COLD Unit I & 2 0-GO-I SHUTDOWN To HOT STANDBY Rev. 0065 Page 147 oti.S5 Appendix E (Page 4 of 4)

RCS VOID VOLUME DETERMINATION Unit_______

Date 1.0.. REACTOR COOLANT SYSTEM LOOPS FILLED DETERMINATION. (continued)

[11:3] Determine change in VCT level.

initial level Final level % change (step 6) (Step 10)

[1l.4 Convert VCT level change gallons as follows:

X 19.27 =

% change. gallons I % gallbns (step 11.3)

NOTE A higher final VCT level will result in the change in VCT level being subt totalizer .change

[12] DETERMINE total volume required to pressurize RCS.

racted from total I

+ +1-change in Boric change in Pri. change in Total makeup Add totalizer Water totalizer VCT level required (Step 11.1) (Step 11.2) (Step 11.4)

End of Section

SQN UNIT STARTUP cOL Unit I & 2 0-GO-I SHUTDOWN TO HOT STANDBY Rev, 0063.

i2(I N 2 o A.1 Page144of151 Appendix E (Page 3 of 4)

RCS VOID VOLUME DETERMINATION Unit. 1. Date 1..0 REACTOR COOLANT SYSTEM LOOPS FILLED DETERMINATION. (continued)

WHEN RCS pressure is 340 psig,

-T THEN ADJUST FHIC-62-BIAI and/or 1HIC-62-93A as necessary to maintain RCS pressure stable at 340 psig.

RECORD the following final values:

VcT level Using one. of the following:

Computer point [LOII2A] 27 C.R VCT level indicator [LI-62-129]

BOric Acid Batch Counter [FQ-62-I 39] totalizer 7q 51W

Primarv.Water Batch Counter IFQ-62-142] totalizer DETERMINE volume required to pressurize the. RCS T from .50 psig to 340 psig as follows:

(11.1] Determine makeup vólumé added based..on change in Boric Acid Batch Counter [FQ-62-f 39] totalizer readings Final reading. Initial reading gallons (step I 0) (Step 6) 111.21 Determine makeup volume added based on change in rj ma Wte Batch Counter EFQ-6 24421 readings

. Øi3 =

I reading tding gallon CR1TLAL

SON UNIT STARTUP FROM COL0.G Unit I & 2 O-i SHUTDOWN TO HOT STANDBY Rev. 0063 Pagel45of 151 Appendix E (Page 4 of 4)

RCS VOII VOLUME DETERMiNATION Unit I tO Date._______

REACTOR COOLANT SYSTEM LOOPS FILLED DETERMINATION. (continued

[11.3] Determine change in VCT level.

3c initial level Final level % change (step 6) (Step 10)

[11.4) Convert VCT level change to gallobs as follows:

dI, X 19.27 =

% change gallons I %

5clc gallons A higher final VCT level will resUlt in the, chan ge in VCT level being subtracted from total totalizer change..

to pressurize_RCS..

+

= 733q change i.n Boric changE.. in Pri. (iT33 N change in Total ma1eup Acid. totalizer Water totalizer VCT level required (Step 11.1) (Step 11.2) (Step 11.4)

END OF TEXT

SRO ADMIN A.2

SEQUOYAH NUCLEAR PLANT 1211 NRC SRO ADMIN JPM A.2

1211 NRC SROAdm1nA.2 Page 2 of 7 JOB PERFORMANCE MEASURE Task: Determine the risk level for safety systems as identified by PSA for scheduling maintenance.

Task#: 0001720302 Task Standard:

The operator determines the Unit I riskIevel changes from green to orange by using the EOOS test case computer program.

Time Critical Task: YES: NO: X KIA ReferencelRatings: 2.2.14 (3.9/4.3)

Method of Testing:

Simulated Performance: Actual Performance: X Evaluation Method:

Simulator In-Plant Classroom X Main Control Room Mock-up Performer:

Trainee Name Evaluator: /

Name I Signature DATE Performance Rating: SAT: UNSAT:

Validation Time: 5 minutes Total Time:

Performance Time: Start Time: Finish Time:

COMMENTS

1211 NRC SROAdminA.2 Page 3 of 7 SPECIAL INSTRUCTIONS TO EVALUATOR:

Tools/EquipmentiProced ures Needed:

1. NPG-SPP-09. 11.1 Equipment Out of Service (EOOS) Management

2. LAN connected computer with EOOS test case program capability

3. Ensure the 1 B-B EDG is removed from service by inserting WO TAGROLLI B using the EOOS test case program

References:

Reference Title Rev No.

1. NPG-SPP-09.11.1 Equipment Out of Service (EOOS) Management 5 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 EXAMINEE AT THIS TIME!

INITIAL CONDITIONS:

1. Unit I isinMODEl 2 lB-B EDG is OOS in preparation for 1-SI-OPS-082-007 B ELECTRICAL POWER SYSTEM DIESEL GENERATOR lB-B performance.

3. lA-A Diesel Generator was found to be unavailable due to loss of jacket water cooling (flood from the heat exchanger INITIATING CUES:

1. Perform a Risk Assessment for Unit 1 using the EOOS test case program and NPG-SPP 09.11.1 Equipment Out of Service (EOOS) Management starting at step 3.2.1.

2. Notify the examiner of your results.

1211 NRC SRO Admin A.2 Page 4 of 7 Start Time Obtain a copy of NPG-SPP-09. 11.1 Equipment Out of Service (EOOS)

STEP 1 : Management. SAT UNSAT Standard: Copy of NPG-SPP-09. 11.1 Equipment Out of Service (EOOS)

Management is obtained.

C Provide a copy of NPG-SPP-09.1 1.1 Equipment Out of Service (EOOS) Management.

Comment NOTES

1) The Operators Screen is typically used to analyze the risk for the current unit configuration.

The What If mode of the Operators Screen may be used to analyze the potential future maintenance configuration.

2) Changes to the configuration of shared or common systems)components may affect the EOOS model of more than one unit. For example, the unavailability of a diesel generator will have a separate risk impact on each unit.

3) BFN ONLY System alignments in the BFN model can affect EOOS results and therefore must be verified before running an evaluation. Note: The SQN and WBN PRA models do not currently have any system alignments identified.

STEP A. From appropriately installed location, access EOOS for the desired 2 SAT plant and unit.

U NSAT Comment

1211 NRC SRO Admin A.2 Page 5 of 7 STEP . B. Log in using the assigned User Name and Password which are

. available from the Corporate PRA Group. SAT UNSAT Standard: Operator logs in the test case EOOS program Cue If asked, provide the following cue, The password is OPS.

Comment STEP 4 : C. Select the Operators Screen.

SAT U NSAT The operator selects the Operators Screen from the test case EOOS Standard program Comment STEP D. Determine if any Functional Equipment Groups (FEGs) or 5 : SAT components are unavailable.

UNSAT Standard The operator verifies I B-B EDG is OOS by referring to the initial conditions.

Examer The I B-B EDG was QOS in the initial conditions.

Comment

1211 NRC SRO Admin A.2 Page 6 of 7 STEP E. Ensure the list of components/FEGs out of service matches the 6 SAT current Unit configuration or make updates as necessary. The changes may be made in the What- If mode first to determine the risk impact before the component/FEG is actually removed from UN SAT service.

Comment STEP F. BFN only 7 : SAT U NSAT Standard: The operator determines the step is not applicable.

Comment STEP G. Calculate Core Damage Frequency (CDF) and Large Early 8 SAT Release Frequency (LERF) Multiplier (i.e., the risk measure(s) on the Operators Screen or the risk profile on the Schedulers Screen) for the unit configu ration using EOOS (Calculate Risk UNSAT Measure(s) Button).

Examiner CDF remains green with a value of approximately 2.44.

Note LERF changes to orange with a value of approximately 7.2.

Comment Terminating The JPM is terminated when the operator returns the JPM Cue: Briefing sheet to the examiner. STOP Stop Time

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. Uniti isinMODEl

2. lB-B EDG is OOS in preparation for 1-SI-OPS-082-007.B ELECTRICAL POWER SYSTEM DIESEL GENERATOR lB-B performance.

3. lA-A Diesel Generator was found to be unavailable due to loss of jacket water cooling (flood from the heat exchanger INITIATING CUES:

1. Perform a Risk Assessment for Unit I using the EOOS test case program and NPG-SPP 09.11.1 Equipment Out of Service (EOOS) Management starting at step 3.2.1.

2. 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.

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1211 NRC JPM SROA.3 Page 2 of 8 SRO JOB PERFORMANCE MEASURE Task: Determine Reporting Requirements for a Contaminated and Injured Worker Task#: 3440030302 Task Standard:

Time Critical Task: YES: NO: X KIA ReferencelRatings: 2.3.14 (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! Signature DATE Performance Rating: SAT: UNSAT:

Validation Time: 10 minutes Total Time:

Performance Time: Start Time: Finish Time:

COMMENTS

1211 NRC JPM SROA.3 Page 3 of 8 SPECIAL INSTRUCTIONS TO EVALUATOR:

ToolslEquipmentlProcedures Needed:

1. NPG-SPP-03.5, Regulatory Reporting Requirements

References:

[ Reference Title Rev No.

ii NPG-SPP-03.5 Regulatory Reporting Requirements 5 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 EXAMINEE AT THIS TIME!

INITIAL CONDITIONS:

1. Unit 2 is in a Refueling Outage, no fuel is in the Reactor Vessel.

2. A vendor was performing work activities in the SIG bowl area.

3. The vendor was overcome with heat exhaustion and fell into the SIG bowl area.

4. Radcon reports the individual was contaminated 9000 cpm in the area of the wound.

5. The fall caused a compound fracture on his right leg that pierced his bubble suit.

6. Due to congested conditions and other delays in lifesaving activities, the injured individual received an estimated exposure of 16 Rem.

7. Due to the nature of his injury, he was immediately transferred to Erlanger Hospital.

8. Site personnel are preparing a news release for immediate delivery to the media.

INITIATING CUES:

1. You are the Shift Manager.

2. Determine all applicable (if any) NRC notifications of less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months using NPG-SPP-03.5 Regulatory Reporting Requirements.

3. Determine all applicable (if any) Internal Management Notifications the SHIFT MANAGER is required to make using NPG-SPP-03.5 Regulatory Reporting Requirements, Appendix D Site Event Notification Matrix.

4. Record your answers on the JPM briefing sheet.

1211 NRC JPM SROA.3 Page 4 of 8 Start Time STEP 1 : SAT Obtain a copy of NPG-SPP-3.5, Regulatory Reporting Requirements.

UNSAT Standard: Copy of NPG-SPP-3.5, Regulatory Reporting Requirements is obtained.

Cue Provide a copy of NPG-SPP-3.5, Regulatory Reporting Requirements.

Comment

1211 NRCJPMSROA.3 Page 5 of 8 NOTES

1) Internal management notification requirements for plant events are found in Appendix 0 The Operations Shift Manager is responsible for notif4ng Site Operations Management and the Duty Plant ManageL The Duty Plant Manager is responsible for making the remaining internal management notifications.

2) NRC NUREG-1022, Supplements and subsequent revisions should be used as guidance for determining reportability of plant events pursuant to §5012 and §50.73.

A text searchable copy of NtJREG-1022 is maintained on the WA NPG Nuclear Licensing Webpage at address http:lltvanweb.cha.tva.govllicensinglPageslNRC lndustry_GuidanceDocu ments .htm.

3.1 Immediate Notification NRC -

STEP 2 : SAT WA is required by §5072 to notify NRC immediately if certain types of events occur. This appendix contains the types of events and the allotted time in which NRC must be notified.

(Refer to Form NPG-SPP-03.5-1 or NRC Form 361). Operations s responsible for making U NSAT the reportability determinations for §51172 and §50.73 reports. For any event, condition, or issue having the potential for being reportable, contact Site Ucensing for consultation and concurrence on the reportabibty determination. In no event shall the lack of licensing concurrence result in a failure to meet specified reporting tinieframes. Operations is responsible for making the immediate notification to NRC in accordance with §50.72.

A. The fmmediate Notification Criteria of §50.72 is divided into 1-hour, 4-hour, and 8-hour phone calls. Notify the NRC Operations Center within the applicable time limit for any item which is identified in the Immediate Notification Criteria.

C. The following criteria require 4-hour notification:

4. §50.72(b)(2)(xi) Any event or situation, related to the health and safety of the public or onsite personnel, or protection of the environment, for which a news release is planned or notification to other government agencies has been or will be made. Such an event may include an onsite fatality or inadvertent release of radioactive contaminated materials.

1211 NRC JPM SROA.3 Page 6 of 8 NOTE According to §51 12 (b)(3)(vi) events covered by §5O.72{b)(3)(v) may include one or more procedural errors, equipment failures, andlor discovery of design.

analysis, fabrication, construction, andlor procedural inadequacies. However, individual component failures need not be reported pursuant this paragraph if redundant equipment in the same system was operable and available to perform the required safety function 3.1 Immediate Notification NRC -

STEP 3 SAT WA is required by §50.72 to notify NRC immediately if certain types of events occur. This appendix contains the types of events and the allotted time in which NRC must be notified, (Refer to Form NPG-SPP-03.5-1 or NRC Form 361). Operations is responsible for making the reportabulity determinations for §50.72 and §5033 reports. For any event, condition, or UN SAT issue having the potential for being reportable, contact Site Licensing for consultation and concurrence on the reportability determination. In no event shall the lack of licensing concurrence result in a failure to meet specified reporting timeframes. Operations is responsible for making the immediate notification to NRC in accordance with §50.72.

0. The following criteria require 8-hour notification:

5. §50.72(b)(3)(xii) Any event requiring the transport of a radioactively contaminated person to an ofisite medical facility for treatment.

Comment NOTE Tl Opeaiions Shift Manager isv sponsibie for notif Site Operations masagemenL and the Outyplant Manager. The fluty Plant Manager is responsltte for the remaining inteiTJ :fl3nagemflt notifications as noted in the matjix.

A,pendix 0 (Page 2 0f 2)

STEP 4 Site Event Notificaijon Matrix SAT Eneca,Et5n Outz5 FitM s.OutySpec. VP Cp yo U NSAT t1s4te,r.rStewEcaEs, Yes Yes Yesrex Yes pxtdf

,ce,la,ri,sd or scentohos ad foloss 5cxoa oTh Comment

1211 NRC JPM SROA.3 Page 7 of 8 Terminating The JPM is complete when the examinee returns the JPM briefing Cue: sheet to the Examiner. STOP Stop Time

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 2 is in a Refueling Outage, no fuel is in the Reactor Vessel.

2. A vendor was performing work activities in the S/G bowl area.

3. The vendor was overcome with heat exhaustion and fell into the SIG bowl area.

4. Radcon reports the individual was contaminated 9000 cpm in the area of the wound.

5. The fall caused a compound fracture on his right leg that pierced his bubble suit.

6. Due to congested conditions and other delays in lifesaving activities, the injured individual received an estimated exposure of 16 Rem.

7. Due to the nature of his injury, he was immediately transferred to Erlanger Hospital.

8. Site personnel are preparing a news release for immediate delivery to the media.

INITIATING CUES:

1. You are the Shift Manager.

2. Determine all applicable (if any) NRC notifications of less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months using NPG-SPP-03.5 Regulatory Reporting Requirements.

3. Determine all applicable (if any) Internal Management Notifications the SHIFT MANAGER is required to make using NPG-SPP-03.5 Regulatory Reporting Requirements, Appendix D Site Event Notification Matrix.

4. Record your answers on the JPM briefing sheet.

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.

SROADMIN A.4

SEQUOYAH NUCLEAR PLANT I2IINRC SRO ADMIN A.4

1211 NRC JPM SROA.4 Page 2 of 9 SRO JOB PERFORMANCE MEASURE Task: Classify the Event using the EPIP-1 and Complete a WA INITIAL NOTIFICATION.

Task#: 3440190302 Task Standard: The Examinee classifies the event as a GENERAL EMERGENCY based on EAL 1.1.2.L and 1 .2.3.L and I .3.4.L and the Examinee issues a Protective Action Recommendation #3.

Time Critical Task: YES: X NO:

KlAReferencelRatings: 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: 20 minutes Total Time:

Performance Time: Start Time: Finish Time:

COMMENTS

1211 NRC JPM SROA.4 Page 3 of 9 SPECIAL INSTRUCTIONS TO EVALUATOR:

ToolslEquipmentlProcedures Needed:

1. EPIP- 1, EMERGENCY PLAN CLASSIFICATION MATRIX

2. EPIP-5 General Emergency.

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

References:

Reference Title Rev No.

1. EPIP-1 Emergency Plan Classification Matrix 43

2. EPIP-5 General Emergency 39 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 EXAMINEE AT THIS TIME!

1211 NRC JPM SROA.4 Page 4 of 9 INITIAL CONDITIONS:

1. Unit 1 and Unit 2 have experienced a Reactor trip due to major storms that have occurred in East Tennessee.

2. The State of Tennessee has issued notifications of road closures in Northern Hamilton County and Hixson due to flooding.

3. Unit I has had a Safety Injection.

4. Security reports that at the time of the trip, steam started blowing from the roof of the Unit 1 east valve vault and steam flow is still in progress at this time.

5. Steam Generator #2 is isolated per E-3, Steam Generator Tube Rupture.

6. CR0 has informed you that SG #2 pressure is slowly lowering.

7. Containment pressure is 0.1 psig and steady.

8. RCS pressure is 1500 psig.

9. Core exit TCs 532 °F and slowly rising.

10. The most recent Chem Lab sample of RCS indicates that RCS activity has risen to 345 pCi/gm Equivalent Iodine-i 31.

Ii. There are no indications of an Onsite Security Event.

INITIATING CUES:

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

2. Raise your hand when you have classified the event.

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

4. Raise your hand when you have completed the Protective Action Recommendations.

5. Record your answers on the JPM briefing sheet.

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

1211 NRC JPM SROA.4 Page 5 of 9 Start Time Obtain a copy of EPIP-1 EMERGENCY PLAN CLASSIFICATION STEP 1 MATRIX. SAT UNSAT Standard Examinee obtains a copy of EPIP-1, EMERGENCY PLAN CLASSIFICATION MATRIX.

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

Comment Examiner Annotate start time when the examinee acknowledges the task is Note understood. Start time____________

INSTRUCTIONS Note: A condition is considered to be Procedure MET if, in the judgment of the SED, the condition will be MET IMMINENTLY (i.e.:

with two hours). The classification shall be made as soon as this determination is made.

STEP 2 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 MATRIX Standard.

and identifies initiating conditions provided in the initial conditions.

Comment

1211 NRC JPM SROA.4 Page 6 of 9

3. COMPARE the number of barrier STEP 3 Losses and Potential losses to the SAT criteria below and make the appropriate declaration. UNSAT Emergency Class Criteria General Emeraencv LOSS of any two barriers and Potential LOSS of third barrier Comment EXAMINER NOTE: Annotate the stop time for the event classification here.

EXAMINER Annotate the start time for the Protective Action Recommendation NOTE: here.

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

EXAMINER NOTE: Examinee transitions to EPIP-5, GENERAL EMERGENCY

1211 NRCJPMSROA.4 Page 7 of 9 Obtain a copy of EPIP-5 GENERAL EMERGENCY STEP 4 : SAT U NSAT Standard: Examinee obtains a copy of EPIP-5, GENERAL EMERGENCY.

Provide a copy of EPIP-5, GENERAL EMERGENCY Comment

1211 NRC JPM SROA.4 Page 8 of 9 Terminating The task is complete when the Examinee has classified the event Cue: and issued Protective Action Recommendations. STOP Stop Time

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 and Unit 2 have experienced a Reactor trip due to major storms that have occurred in East Tennessee.

2. The State of Tennessee has issued notifications of road closures in Northern Hamilton County and Hixson due to flooding.

3. Unit I has had a Safety Injection.

4. Security reports that at the time of the trip, steam started blowing from the roof of the Unit I east valve vault and steam flow is still in progress at this time.

5. Steam Generator #2 is isolated per E-3, Steam Generator Tube Rupture.

6. CR0 has informed you that SG #2 pressure is slowly lowering.

7. Containment pressure is 0.1 psig and steady.

8. RCS pressure is 1500 psig.

9. Core exit TCs 532 °F and slowly rising.

10. The most recent Chem Lab sample of RCS indicates that RCS activity has risen to 345 pCi/gm Equivalent Iodine-I 31.

11. There are no indications of an Onsite Security Event.

INITIATING CUES:

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

2. Raise your hand when you have classified the event.

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

4. Raise your hand when you have completed the Protective Action Recommendations.

5. Record your answers on the JPM briefing sheet.

6. 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 SAl 1SFACTORILY COMPLETED THE ASSIGNED TASK.

ML13275A052

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