Text

Initial Exam 2009302 Final Admin JPMs
	ML15141A467
Person / Time
Site:	Saint Lucie
Issue date:	05/27/2010
From:	; NRC/RGN-II
To:	; Florida Power & Light Co
References
	Download: ML15141A467 (98)
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H LC49A JPMs Final 12/21/2009

REGION II ST. LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM A-i Determine Shutdown Margin Criteria (RO/SRO)

This JPM is NOT TIME CRITICAL This is a FAULTED JPM

REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM Detennine Shutdown Margin Criteria KA Statement:

2.1.43

- Ability to use procedures to determine the effects on reactivity of plant changes, such as reactor coolant system temperature, secondary plant, fuel depletion, etc.

KA IR:

R04.l, SRO= 4.3

References:

Unit 2 Plant Physics Curves 2-NOP-100.04, Surveillance Requirements for Shutdown Margin; Modes 2, 3, 4, and 5 (Subcritical)

PSL Unit 2 Tech Spec 3.1.1.1 Candidate:

Name Validation Time:

15 minutes Start Time:

Finish Time:

Performance Rating:

Sat Unsat Examiner:

Signature:

Comments ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-i PAGE 2

NRC ADM 1PM A-i REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM Determine Shutdown Margin Criteria Directions to the candidate for Administrative JPMS:

I will explain the initial conditions and state the task to be performed. You will be allowed to use any reference needed to complete the task. Ensure you indicate to me when you finish your assigned task by returning the material needed for the task that I provided to you.

Initial Conditions Unit 2 was at 100% power for 120 days, 3143 EFPH. An automatic reactor / turbine trip just occurred.

CEA 8 did not drop and is at 132 withdrawn.

Current RCS temperature is 532°F.

RCS Cb is 962 ppm (at 0400).

Current time is 0500.

Reactor Engineering has provided a Reactivity Deviation value of 0 pcm.

Prerequisites/Precautions/Limitations of 2-NOP-1 00.04, Surveillance Requirements for Shutdown Margin; Modes 2, 3, 4, and 5 (Subcritical) are complete Initiating Cue You are directed to verify shutdown margin for the current plant conditions and to determine corrective actions if any apply.

EXAMINERS NOTE: This SDM calculation was conducted using 3143 EFPH.

Figures A.4, B.4, B.5, B.6, & B.7 from the PSL Unit 2 Cycle 18 Plant Curve Book (PSL-ENG-SEFJ-09-008 Rev. 0), dated 05/18/09, were used to perform this calculation.

Ensure the same revisions are given to the applicants for performance of this JPM. Reactor Engineering has provided a Reactivity Deviation value of 0 pcm (Data sheet 2 step 5B).

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-i PAGE 3

NRC ADM 1PM A-i START TIME:

DATA SHEET 2 STEP 1 (1&2):

Prerequisites & Precautions/Limitations complete SAT STANDARD:

All complete EXAMINERS CUE:

NONE UNSAT COMMENTS:

STEP 2 (3):

Record current plant conditions on data sheet 2 STANDARD:

SAT 3.

Current Plant Conditions:

Date TQDY Time5:OO Mode 3

UNSAT Temperature 532..

°F Core Burnup 31 13 EFPH(DCS)

EXAMINERS CUE:

NONE COMMENTS:

STEP 3 (4):

Record target plant conditions on data sheet 2 STANDARD:

SAT 4.

Target Plant Conditions A.

Surveillance time interval (Enter 0 if calculating for UNSAT current conditions)

Hours B.

Minimum expected RCS Temperature during the surveillance interval 32.OF EXAMINERS CUE:

NONE COMMENTS:

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-i PAGE 4

NRC ADM JPM A-i STEP 4 (5A):

Determine Xenon worth from Figure A.4 and record on Data sheet 2.

CRITICAL STEP STANDARD:

2525 pcm

- 2600 pcm SAT EXAMINERS CUE:

NONE COMMENTS:

UNSAT STEP 5 (5B):

Record Reactivity Deviation on data sheet 2 SAT STANDARD:

Opcm EXAMINERS CUE: Reactor Engineering has provided a Reactivity UNSAT Deviation value of 0 pcm.

COMMENTS:

STEP 6 (5C):

Determine stuck rod worth using Figure B.4 and record on data sheet 2 CRITICAL STEP STANDARD:

1654 pcm +/- 0 pcm SAT EXAMINERS CUE:

NONE COMMENTS:

UNSAT STEP 7 (SD & 6A):

Add lines 5A, 5B, & 5C and record on data sheet 2 CRITICAL STEP STANDARD:

871 pcm

- 946 pcm SAT EXAMINERS CUE:

NONE COMMENTS:

UNSAT ST. LUCIE TRATNING DEPT.

ADMINISTRATIVE JPM A-i PAGE 5

NRC ADM JPM A-i STEP 8 (6B):

Determine boron worth using Figure B.5 and record on data sheet 2 CRITICAL STEP STANDARD:

8.01 pcm/ppm 8.04 pcm/ppm SAT EXAMINERS CUE:

NONE COMMENTS:

UNSAT STEP 9 (6C):

Divide line 6A by 68 CRITICAL STEP STANDARD:

108 ppm 118 ppm SAT EXAMINERS CUE:

NONE COMMENTS:

UNSAT STEP 10 (6D):

Determine Shutdown Boron Concentration using figures B.6 or B.7 CRITICAL (preferably 8.7) and record on data sheet 2.

STEP STANDARD:

1130 ppm

- 1150 ppm SAT EXAMINERS CUE:

NONE UNSAT COMMENTS:

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-i PAGE 6

NRC ADM JPM A-i STEP 11 (6E):

Add lines 6C & 6D and record on data sheet 2 CRITICAL STEP STANDARD:

1020 ppm -1032 ppm EXAMINERS CUE:

NONE SAT CoMMENTS:

UNSAT STEP 12 (7A):

Enter present RCS boron concentration.

STANDARD:

Given as 962 ppm SAT EXAMINERS CUE:

NONE UNSAT COMMENTS:

STEP 13 (7B):

Determine if Shutdown Margin is adequate CRITICAL STEP STANDARD:

Determines SDM not met for current plant conditions and that immediate Emergency Boration is required per Technical Specifictions.

SAT COMMENTS:

UNSAT END OF TASK STOP TIME:

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-i PAGE 7

CANDIDATE COPY (TO BE RETURNED TO THE EXAMINER UPON COMPLETION)

Directions to the candidate for Administrative JPMS:

I will explain the initial conditions and state the task to be performed. You will be allowed to use any reference needed to complete the task. Ensure you indicate to me when you finish your assigned task by returning the material needed for the task that I provided to you.

Initial Conditions Unit 2 was at 100% power for 120 days, 3143 EFPH. An automatic reactor! turbine trip just occurred.

CEA 8 did not drop and is at 132 withdrawn.

Current RCS temperature is 532°F.

RCS Cb is 962 ppm (at 0400)

Current time is 0500.

Reactor Engineering has provided a Reactivity Deviation value of 0 pcm.

Prerequisites/Precautions/Limitations of 2-NOP-1 00.04, Surveillance Requirements for Shutdown Margin; Modes 2, 3, 4, and 5 (Subcritical) are complete Initiating Cue You are directed to verify shutdown margin for the current plant conditions and to determine corrective actions if any apply.

K.

REVISION NO.:

PROCEDURE TITLE:

PAGE:

1 SURVEILLANCE REQUIREMENTS FOR SHUTDOWN 11 f

3 PROCEDURE NO.:

MARGIN; MODES 2, 3, 4 AND 5 (SUBCRITICAL) 0 1

2-NOP-100.04 ST. LUCIE UNIT 2 DATA SHEET 2 SHUTDOWN MARGIN VERIFICATION FOR MODES 3,4, 5 (SUBCRITICAL)

(Page 1 of 3)

Prerequisites, Section 3 completed.

RCO 2.

Precautions/Limitations Section 4.0 reviewed, 13 RCO 3.

Current Plant Conditions:

Date TL Time 0:00 Mode 3 Temperature 5 !

°F Core Burnup 3 i 3 EFPH (DCS) 4.

Target Plant Conditions A.

Surveillance time interval (Enter UQI if calculating for current conditions) 0 Hours B.

Minimum expected RCS Temperature during the surveillance interval S 3 1- °F 5.

Reactivity Components:

A.

Xenon Worth corresponding to Current Plant Conditions or the Target Plant Conditions surveillance time interval (Plant Physics Curves, Figure A.4 or the RCS screen on DCS).

(-)5SL) PCM B.

Reactivity Deviation

()

0 PCM (Plant Physics Curves, Figure B.3, Col. 2, observe sign)

C.

Stuck CEA 1.

If there are no actual stuck CEAs, Then ENTER 0.

2.

If there is an actual stuck CEA, Then ENTER the stuck CEA difference between worst and second worst stuck CEA worth (Figure B.4)

(+) /6i PCM D.

Total (Lines 5A + 5B + 5C, observe sign)

(-)

1 (p PCM B7(

REVISION NO.:

PROCEDURE TITLE:

PAGE:

1 SURVEILLANCE REQUIREMENTS FOR SHUTDOWN PROCEDURE NO.:

MARGIN; MODES 2,3,4 AND 5 (SUBCRITICAL) 12 of 13 2-NOP-100.04 ST. LUCIE UNIT 2 DATA SHEET 2 SHUTDOWN MARGIN VERIFICATION FOR MODES 3,4, 5 (SUBCRITICAL)

(Page 2 of 3) 5.

Reactivity Balance:

A.

Reactivity Component Total ( From line 5D, observe 81!

q G sign)

(-) 8(

PCM B.

Boron Worth corresponding to Current Plant Conditions or the Target Plant Conditions expected RCS minimum temperature, (ARI-1) (Plant Physics Curves, Figure B.5) (÷)_8..02..PCM/PPM C.

Reactivity Component Total: Equivalent Boron Worth in

/ o8

/ (8 PPM (Line 6A + 6B, observe sign)

(-) /1 L.

PPM D.

Shutdown Boron Concentration 1130 it.2 (Plant Physics Curves, Figure B.6, B.7** or B.8)

(+) //fl PPM E.

Required Boron Concentration (Line 6C+6D, observe

/02-0 1032...

sign)

(t) lOt? PPM

- Figure B.7 may only be used when calculating the shutdown boron requirements for Modes 2 to 3 with Tavg greater than or equal to 51 5F.

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S 2400 2200 2000 0

U, 3 1800 0

1600 t

1400 1200 1000 800 600 400 200 0

0 5

10 15 20 25 30 35 40 45 50 55 60 65 70 75 Time Following Shutdown (hours)

Date Of Update

/

I

References:

PSL2FJF-09-073 Rev. 0, Attachment 1 Page 65 PSL-ENG-SEFJ-09-008 Rev. 0, Attachment 1 Page 71 4000 3800 3600 Figure A.4 3000 EFPH Rev. 3 St. Lucle Unit 2 Cycle 18 Xenon Worth Following Shutdown 4

O%Po

-3725 m

z:zzz HEEEEE 3 B9pcrn SC Power

-\\

Pos

I 4opcm

\\\\-

\\

ccç

ccç V.

4*

-V

VV

-V 80 85 90 95 10 105

Figure A.4 Rev. 3 Pagei -of 3 St. Lucie Unit 2 Cycle 18 Xenon Worth Following Shutdown (3000 EFPH) 100%

75%

1 50%

25%

HOURS (pcm)

(pcm)

I (pcm)

(porn 0

2550 2317 1965 1361 1

2830 2510 2068 1388 2

3095 2691 2165 1413 3

3330 2850 2247 1431 4

3520 2976 2308 1440 5

3650 3058 2341 1436 6

3712 3089 2342 1418 7

3725 3085 2321 1391 8

3713 3062 2289 1359 9

3680 3023 2247 1323 10 3628 2970 2197 1284 11 3558 2904 2138 1242 12 3474 2828 2074 1198 13 3378 2743 2005 1152 14 3273 2652 1932 1105 15 3162 2556 1857 1058 16 3047 2458 1781 1011 17 2929 2359 1706 965 18 2811 2259 1630 919 19 2692 2160 1556 874 20 2575 2063 1483 831 21 2460 1968 1412 789 22 2348 1875 1344 749 23 2238 1785 1277 710 24 2131 1698 1212 672 25 2027 1613 1150 636 26 1926 1530 1090 601 27 1828 1450 1031 568 28 1732 1373 975 536 29 1639 1298 921 505 30 1549 1226 868 476 31 1463 1156 818 447 32 1379 1089 770 421 33 1298 1024 724 395

References:

PSL-2FJF-09-073 Rev. 0, Attachment 1 Page 66 PSL-ENG-SEFJ-09-008 Rev. 0, Attachment I Page 72

Figure B.4 St. Lucie Unit 2 Cycle 18 CEA Total Worth (3000 EFPH, Rev.

3)

CEA TOTAL WORTH RZP All Rods In to All Rods Out

=

8580 pam STUCK CEA INFORMATION Single Worst Stuck CEA Worth

=

826 pcm

[Location: R3) 2 Combined First and Second Worst

=

2373 pam Stuck CEA Worth

[Locations:

N2, R3) 2 Maximum Difference Between Worst 1654 pcm and Second Worst Stuck CEA Worth 1

HFP DROPPED CEA INFORMATION Highest Single Dropped CEA Worth 96 pam

[Location:

S6)(2)

(1)

This is the maximum difference over all temperature conditions and may not be eq-uivaleut to the delta between the single and combined worthe listed on this sheet.

(2)

Symmetric locations are also applicable.

Date of Update _//_/

References:

PSL-2FJF-09-101 Rev.

0 Attachment 1

Page 4

PSL-ENG-SEFJ-09-008 Rev.

0 Attachment 1 Page 165

10.6 10.4 10.2 0

C.)a-

-c 0

0I0 C

C)

Figure B.5 Rev. 3 St Lucie Unit 2 Cycle 18 Differential Boron Worth vs RCS Temp.

(3000 EFPH, No Xenon, ARI Minus Worst Stuck CEA)

Date of Update

Reference:

PSL-2FJF-09-061 Rev. 0 Attach. 1 Page 5 PSL-ENG-SEFJ-09-00S Rev. 0 Attach. 1 Page 175 Moderator Temperature (Deg F) 50 100 150 200 250 300 350 400 450 500 550 1

I

Figure B.5 Rev. 3 Page 1 of 1 St. Lucie UnIt 2 Cycle 18 (3000 EFPH)

Differential Boron Worth vs Moderator Temperature (No Xenon, ARI Minus Worst Stuck CEA)

Date Of Update

References:

PSt-2FJF-09-061 Rev. 0 Attach. 1 Page &

PSL-ENG-SEFJ-09-008 Rev. 0 Attach. 1 Page 176 RCS Boron RCS Boron Temp.

Worth Temp.

Worth

(°F)

(pcmlppm)

(°F)

(pcmippm)

RCS Boron Temp.

Worth (DF)

(pcmlppm) 68 72 76 80 84 88 92 96 100 104 108 112 116 120 124 128 132 136 140 144 148 152 156 160 164 168 172 176 180 184 10.73 10.72 10.71 10.69 10.68 10.67 10.66 10.64 10.63 10.62 10.60 10.59 10.57 10.56 10.55 10.53 10,51 10.50 10.48 10.46 10.44 10.43 10.41 10.39 10.37 10.35 10.33 10.31 10.28 10.26 188 192 196 200 204 208 212 216 220 224 228 232 236 240 244 248 252 256 260 264 268 272 276 280 284 288 292 296 300 304 10.24 10.22 10.20 10.18 10.15 10.13 10.11 10.09 10.07 10.05 10.02 10.00 9.98 9.96 9.94 9.91 9.89 9.87 9.85 9.82 9.80 9.78 9.76 9.73 9.71 9.69 9.66 9.64 9.62 9.59 RCS Boron Temp.

Worth

(°F)

(pcmlppm) 428 8.79 432 8.76 436 8.73 440 8.71 444 8.68 448 8.65 452 8.62 456 8.59 460 8.56 464 8.53 468 8.50 472 8.47 476 8.45 480 8.42 484 8.39 488 8.36 492 8.33 496 8.30 500 8.27 504 8.24 508 8.21 512 6.17 516 8.14 520 8.11 524 8.08 528 6.05 532 8.02 308 312 316 320 324 328 332 336 340 344 348 352 356 360 364 368 372 376 380 384 388 392 396 400 404 408 412 416 420 424 9.57 9.55 9.52 9.50 9.47 9.45 9.43 9.40 9.38 9.35 9.33 9.30 9.27 9.25 9.22 9.20 9.17 9.14 9.12 9.09 9.06 9.04 9.01 8.98 8.96 8.93 8.90 8.87 8.85 8.82

/

0 C0 C

C00 0

0 I

Figure 8.6 Rev. 3 St. Lucie Unit 2 Cycle 18 Shutdown Boron Concentration vs RCS Temp.

(Modes 1-4, 3000 EFPH, No Xe, ARI Minus Worst Stuck CEA)

ARI-1 3600 pcm Sf0 Margin Date of Update

/1

Reference:

PSL-2FJF-09-061 Rev. 0 Attach. 1 Page 21 PSL-ENG-SEFJ-09-008 Rev. 0 Attach. I Page 191 1125 200 220 240 260 280 300 320 340 360 380 400 420 440 460 480 500 520 540 Moderator Temperature (Deg F)

f9gre-B.6 Rev 3 Page 1 of I St. Licie Uni[2 Cycle IS (3000 EFPH)

Shutdown Boron Concentration (Modes 1-4 No Xenon, AR? Minus Worst Stuck CEA)

RCS Temp.

Boron

(°F)

(ppm) 201 1363 204 1362 208 1360 212 1359 216 1357 220 1356 224 1354 228 1353 232 1351 236 1350 240 1349 244 1347 248 1346 252 1344 256 1343 260 1341 264 1340 268 1338 272 1336 276 1335 280 1333 284 1332 288 1330 292 1328 296 1327 300 1325 304 1323 308 1322 RCS Temp.

Boron

(°F)

(ppm) 312 1320 316 1318 320 1316 324 1314 328 1313 332 1311 336 1309 340 1307 344 1305 348 1303 352 1301 356 1298 360 1296 364 1294 368 1291 372 1289 376 1286 380 1283 384 1280 388 1277 392 1274 396 1271 400 1267 404 1263 408 1260 412 1256 416 1252 420 1247 RCS Temp.

Boron

(°F)

(ppm) 424 1243 428 1239 432 1234 436 1230 440 1225 444 1221 448 1216 452 1212 456 1207 460 1203 464 1198 468 1194 472 1190 476 1186 480 1181 484 1177 488 1173 492 1170 496 1166 500 1162 504 1159 508 1156 512 1153 516 1150 520 1148 524 1145 528 1143 532 1141 bate Of Update

References:

PSL-2FJF.09-061 Rev. 0 Attach. I Page 22 PSL-ENG-SEFJ-09-008 Rev. 0 Attach. 1 Page 192

/

I

Figure B.7 Rev. 0 St. Lucie Unit 2 Cycle 18 Modes 1-3 Shutdown Boron Concentration vs Bumup HZP, 515 °F 880 830 780 73° RO EE cE N

I-I I

I I

I t

Date of Update I

I

Reference:

PSL-2FJF-09-061 Rev. 0 Attach. 1 Page 33 PSL-ENG-SEFJ-09-008 Rev. 0 Attach. I Page 203 1430 1380 1330 1280 1230 1180 1130 1080 1030 980 o.n t

C 0

0 C.)

Ca o

630 580 530 480 430 380 330 280 230 180 0

2000 4000 6000 8000 10000 12000 Bumup (EFPH)

Figure B:T Rev.O Page 1tf 1 St. Lucie Unit-2 Cycle 18 Modes 1-3 Shutdown Boron Concentration vs Burnup HZP, 515°F Date Of Update

References:

PSL2FJF.-O9-O61 Rev. 0 Attach. 1 Page 34 PSL-ENG-SEFJ-09-008 Rev. 0 Attach. 1 Page 204 Burnup Boron Burnup Boron (EFPH)

(ppm)

(EFPH)

(ppm)

Burnup Boron (EFPH)

(ppm)

Burnup Boron (EFPH)

(ppm) 200 300 400 500 600 700 800 900 1000 1100 1200 1300 1400 1500 1600 1700 1800 1900 2000 2100 2200 2300 2400 2500 2600 2700 2800 2900 3000 3100 1414 1404 1394 1383 1373 1363 1353 1343 1333 1323 1313 1304 1294 1284 1275 1265 1256 1247 1238 1228 1219 1211 1202 1193 1184 1176 1168 1159 1151 1143 3200 3300 3400 3500 3600 3700 3800 3900 4000 4100 4200 4300 4400 4500 4600 4700 4800 4900 5000 5100 5200 5300 5400 5500 5600 5700 5800 5900 6000 6100 1135 1127 1119 1111 1104 1096 1089 1082 1074 1067 1060 1053 1046 1039 1032 1026 1019 1013 1006 1000 993 987 980 974 968 962 955 949 943 936 6200 6300 6400 6500 6600 6700 6800 6900 7000 7100 7200 7300 7400 7500 7600 7700 7800 7900 8000 8100 8200 8300 8400 8500 8600 8700 8800 8900 9000 9100 930 923 917 910 904 897 890 883 876 869 861 854 846 839 831 823 815 806 798 789 781 772 763 754 744 735 725 716 706 696 9200 9300 9400 9500 9600 9700 9800 9900 10000 10100 10200 10300 10400 10500 10600 10700 10800 10900 11000 11100 11200 11300 11400 11500 11600 11700 11800 11900 12000 12100 12200 12300 12400 12500 12550 686 676 665 655 644 633 622 611 600 588 577 565 553 541 529 516 504 491 478 465 452 438 425 411 397 383 370 355 341 327 313 299 284 270 263

/

I

REGION II ST. LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM DETERMINE TIME TO BOIL AND THE MAKEUP FOR BOIL OFF ON LOSS OF SHUTDOWN COOLING A-2 This JPM is NOT TIME CRITICAL This is a NON-FAULTED JPM

REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM DETERMINE TIME TO BOIL AND THE MAKEUP FOR BOIL OFF ON LOSS OF SHUTDOWN COOLING KA Statement: 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc.

KA#:

3.9/4.2

References:

1-0440030 Shutdown Cooling Off-Normal Candidate:

Name Validation Time:

15 minutes Start Time:

Finish Time:

Performance Rating:

Sat Unsat Examiner:

Signature:

Comments ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-2 PAGE 2

NRC ADM JPM A-2 REGION N ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM DETERMINE TIME TO BOIL AND THE MAKEUP FOR BOIL OFF ON LOSS OF SHUTDOWN COOLING Directions to the candidate for Administrative JPMS:

I will explain the initial conditions and state the task to be performed. You will be allowed to use any reference needed to complete the task. Ensure you indicate to me when you finish your assigned task by returning the material needed for the task that I provided to you.

Initial Conditions Unit 1 is in a Refueling outage preparing to lift the Reactor Vessel head. You have just begun your shift.

A loss of shutdown cooling occurs.

Initiating Cue The US has directed you to determine the following using 1-0440030, Shutdown Cooling Off-Normal:

1.

Time boiling will occur 2.

Flow to makeup for Boil-Off lAW 1-0440030, Shutdown Cooling Off-Normal.

Given:

RCS temperature is 95°F RCS level is 35 feet The Unit was tripped on Oct. 18, at 0000 Loss of Shutdown Cooling occurred at: Oct 22, 0100 Current date / time is Oct. 22, 0110 ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-2 PAGE3

NRC ADM JPM A-2 START TIME:

DATA SHEET I STEP 1 (1A):

Record the foflowing information SAT RCS Temperature U NSAT STANDARD:

Records 95°F EXAMINERS CUE:

NONE COMMENTS:

STEP 2 (1A):

Record the following information Vessel/Cavity Level SAT STANDARD:

Records 35 ft.

UNSAT EXAMINERS CUE:

NONE COMMENTS:

STEP 3 (1A):

Record the following information Time since shutdown (hours)

SAT STANDARD:

Records 97 hours0.00112 days 0.0269 hours 1.603836e-4 weeks 3.69085e-5 months (97-97.17)

UNSAT EXAMINERS CUE:

NONE COMMENTS:

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-2 PAGE 4

NRC ADM JPM A-2 STEP 4 (1A):

Record the following information STANDARD:

0100 Time Shutdown Cooling Lost UNSAT EXAMINERS CUE:

NONE COMMENTS:

EXAMINERS NOTE Temperature between columns, select higher temperature Time since shutdown between rows, select the lesser time STANDARD:

16.8 minutes EXAMINERS CUE:

COMMENTS:

NONE UNSAT EXAMINERS NOTE e

Temperature between columns, select higher temperature Time since shutdown between rows, select the lesser time STANDARD:

1.17 minutes EXAMINERS CUE:

NONE COMMENTS:

UNSAT ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-2 PAGE 6 SAT STEP 5 (1 B):

Table 2 Time to Boil at Mid-Loop CRITICAL STEP SAT STEP 6 (1 C):

Table 3 Additional Time to Boil I 100 ft3 CRITICAL STEP SAT

NRC ADM JPM A-2 STEP 7 (1 D):

Table 4 Additional volume of water above mid-loop CRITICAL STEP STANDARD:

4.44 (100 ft3)

SAT EXAMINERS CUE:

NONE UNSAT COMMENTS:

STEP 8 (1 E):

PERFORM the following equation to determine the Corrected Time to Boil CRITICAL as follows:

STEP

(

)+[(

)x(

)]=

Step lB Step 1C Step 1D Time to Boil SAT STANDARD:

Step lB 16.8 SteplCl.17 UNSAT Step 1D 4.44 Time to Boil 21.99 minutes (21.99-22 minutes is acceptable)

EXAMINERS CUE:

NONE COMMENTS:

STEP 9 (2):

j core shuffle or reload has NOT been completed, Then use the step 1.E.

Time to Boil value in step 4.

STANDARD:

Based on cue of Reactor Vessel head being removed, determines step 1.E is SAT applicable.

EXAMINERS CUE:

NONE UNSAT COMMENTS:

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-2 PAGE 6

NRC ADM JPM A-2 STEP 10 (3):

If core shuffle or reload has been completed, Then PERFORM the following equation to adjust the time to boil and use this value in step 4.

STANDARD:

Determines core shuffle I reload has NOT been complete.

SAT EXAMINERS CUE:

NONE UNSAT COMMENTS:

STEP 11(4):

Determine time boiling will occur CRITICAL STEP

+

Time SDC Lost Time to Boil Time Boiling Will Occur SAT STANDARD:

Time SDC Lost 0100 Time to Boil 21.99 (22 minutes is acceptable)

Time Boiling Will Occur 0122 (0121 0122)

UNSAT EXAMINERS CUE:

NONE COMMENTS:

STEP 12:

Determine Flow To Makeup For Boil-Off CRITICAL STEP STANDARD:

Using Figure 1 determines 65 gpm (64-66) makeup for boil-off.

EXAMINERS CUE:

NONE EXAMINERS NOTE:

This step may be performed at any time SAT COMMENTS:

UNSAT END OF TASK STOP TIME:

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-2 PAGE 7

CANDIDATE COPY (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER)

Directions to the candidate for Administrative JPMS:

I will explain the initial conditions and state the task to be performed. You will be allowed to use any reference needed to complete the task. Ensure you indicate to me when you finish your assigned task by returning the material needed for the task that I provided to you.

Initial Conditions Unit 1 is in a Refueling outage preparing to lift the Reactor Vessel head. You have just begun your shift.

A loss of shutdown cooling occurs.

Initiating Cue The US has directed you to determine the following using 1-0440030, Shutdown Cooling Off-Normal:

1.

Time boiling will occur 2.

Flow to makeup for Boil-Off lAW 1-0440030, Shutdown Cooling Off-Normal.

Given:

RCS temperature is 95°F RCS level is 35 feet The Unit was tripped on Oct. 18, at 0000 Loss of Shutdown Cooling occurred at: Oct 22, 0100 Current date /time is Oct. 22, 0110

V tEVISION NO.:

PROCEDURE TITLE:

PAGE:

38B SHUTDOWN COOLING OFF-NORMAL PROCEDURE NO.:

of 36 1-0440030 ST. LUCIE UNIT I DATA SHEET I ESTiMATED TIME TO CORE BOILING AND REQUIRED SHUTDOWN COOLING RESTORATiON (Page 1 of 2)

§ Determine the corrected Time to Core Boiling by performing the following:

A.

Record the following information RCS Temperature VesselICavlty Level ft

1 q.,,7 Time since shutdown (hours) 5i Time Shutdown Cooling Lost 01 b C B.

Table 2 - Time to Boil at Mid-Loop

) L,.

(minutes)

C.

Table 3 - Additional Time to Boil /100 ft3 L

(minutes)

D.

Table 4 - Additional volume of water above mid-loop.

t.N (100 ft3)

E.

PERFORM the following equation to determine the Corrected Time to Boil as follows:

22.

(

ItØ.S

)+[(

).L1 ix(

)]=

minutes Step lB Step IC Step ID Time to Boil 2.,

jf core shuffle or reload has NOT been completed, Then use the step I.E. Time 1t to Boil value In step 4.

3.,.) j 1

j core shuffle or reload has been completed, Then PERFORM the following equation to adjust the time to boil and use this value in step 4.

xI.35 Time to boil step I.E Time to Boil

EVISION NO.:

PROCEDURE TFfl.E:

PAGE:

38B SHUTDOWN COOLING OFF-NORMAL PROCEDURE NO.:

1-0440030 ST. LUCIE UNIT I DATA SHEET I ESTIMATED TIME TO CORE BOILING AND REQUIRED SHUTDOWN COOLING RESTORATION (Page 2 of 2)

Determine time boUing will occur,

+

2.2..

=

o2Z Time SDC Lost +

Time to Boil Time Boiling WIll Occur oS31 o172.

Performed by:

I i

I RCO Date Verified by:

/

I I

US Date END OF DATA SHEET I

260 240 220 200 180 160

+.*.

t

.....-÷

......4.....

4

.4

--4----+---

4 i

Ma keup Flow For Goiloff r--

---4

-t

.4.... *.,.

_..L.______._______-4 z:iz.

4 t

+---.--*

C.,

0z t.... -1 Eg 1

40 120 100 80

z..

60

z::z..:

-I---

m 0zzp

-o 0

C) m0c Ill

-f

-lIm

(

0 0

C) o C

QZ oC.,.

0 Co C) m Cz

-4

-r-------

4

i.-.-

..i 40 I 4U I

20 0

-o 0

0 1.

..,.i

-TiI0

-4.0

iiCC, 1

m w0 I:0

-T1 02 C,zC

-1 0

z C)00Iz G) 0

-Ti

-TI+/-0 I-4 4

4

4 6

8 10 12 14 16 18 20 22 24 26 28 30 32 34 36 38 40 Time After SID (Days)

UNIT 1. 25000 EFPH PSL-2FSN-98-001 tP,OPSIl-O4XX-.242)

C)

C.)0 0

C,,

REGION II ST. LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM A-3 Monitoring Linear Heat Rate Using Incore Detectors (DCS)

(RO/SRO)

This JPM is NOT TIME CRITICAL This is a FAULTED JPM

REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM Monitoring Linear Heat Rate Using Incore Detectors (DCS)

KA Statement:

2.2.44

- Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.

KA IR:

RO = 4.2, SRO = 4.4

References:

NOP-1 00.03, Monitoring Linear Heat Rate 2-NOP-1 02.01, Distributed Control System (DCS) Operations PSL Unit 2 Tech Spec 3.2.1 FSAR 13.8.1.2, Incore Detectors 2-ARP-01-L-16, Linear Heat Rate/Incores Equipment Out of Service Log 0-OSP-64.01, Reactor Engineering Periodic Tests, Checks, and Calibrations Operating Surveillance Procedure Candidate:

Name Validation Time:

25 minutes Start Time:

Finish Time:

Performance Rating:

Sat Unsat Examiner:

Signature:

Comments ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-3 PAGE 2 of 10

NRC ADM JPM A-3 REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM Monitoring Linear Heat Rate Using Incore Detectors (DCS)

Directions to the candidate for Administrative JPMS:

I will explain the initial conditions and state the task to be performed. You will be allowed to use any reference needed to complete the task. Ensure you indicate to me when you finish your assigned task by returning the material needed for the task that I provided to you.

Initial Conditions 1.

Unit 2 isat 100% power

2. Annunciator L-16 is in alarm. The ARP has been pulled with the following actions completed:

a.

Reactor Engineering has been notified.

b.

NOP-100.03, Monitoring Linear Heat Rate, has been referred to and the Prerequisites, Precautions, Limitations, and Initial Conditions of NOP 100.03, have been completed.

Initiating Cue The Unit Supervisor has directed you to perform NOP-1 00.03, Monitoring Linear Heat Rate, starting with step 6.2.1.

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-3 PAGE 3 of 10

NRC ADM JPM A-3 START TIME:

NOP-1 00.03 Monitoring Linear Heat Rate CRITICAL STEP 1(6.2.1):

Obtain a Flux Log from the DCS STEP A.

From the Main Menu ACCESS the Process Reports B.

PRINT SAT STANDARD:

Candidate touches Print Demand Log and log prints out EXAMINERS CUE:

NONE UNSAT COMMENTS:

STEP 2 (6.2.2):

Determine which incore detectors are failed or abnormal STANDARD:

Notes failed detectors at location 43 (detectors #1

- #4)

SAT EXAMINERS CUE:

NONE EXAMINERS NOTE: A Failed or Abnormal Detector will be indicated UNSAT by one of 3 colors: Black, White or Red on the Incore Display. #43 (detectors #1, 2, 3, 4) is an add itionallnew failed detector and is RED on the DCS display. An abnormally high flux is indicated on the hard copy flux log is also indication of a failed detector.

COMMENTS:

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-3 PAGE 4 of 10

NRC ADM JPM A-3 STEP 3 (6.2.3):

Compare failed detectors to Equipment Out of Service Log (005), Figure D.6, Incore Operating Status.

CRITICAL STEP STANDARD:

Determines there is four (4) additional failed detectors (location 43 detectors #1 -#4)

EXAMINERS CUE:

Make available the hardcopy Equipment Out of SAT Service Log.

EXAMINERS NOTE: May compare to either Figure 0.6 or to Data Sheet I of O-OSP-64.OI (both are in OOS log book).

UNSAT COMMENTS:

STEP 4 (6.2.4):

Add additional/new failed detectors to the total CRITICAL STANDARD:

Additional failed detector(s) added to the Equipment Out of Service STEP Log (OOS).

EXAMINERS CUE:

NONE EXAMINERS NOTE: This may be accomplished by adding to SAT Attachment I, Data Sheet I of O-OSP-64.OI, OR by annotating (color in block 43) the appropriate block on Figure D.6 or both (both are in OOS log UNSAT book).

EXAMINERS NOTE: Critical step data for Data Sheet I: Group #43, and Todays date.

COMMENTS:

STEP 5 (6.2.5):

Evaluate the total number of failed detectors against criteria on Figure D.6.

STANDARD:

Determines that there are 21 upper detectors and 22 lower detectors SAT still operable in the affected quadrant and that this is greater than the minimums of 4 operable in the upper, 4 in the lower and a total of 10 for that quadrant UNSAT EXAMINERS CUE:

For RO Candidate: SRO is determining operability.

EXAMINERS NOTE: SRO candidates only COMMENTS:

ST. LUCE TRAINING DEPT.

ADMINISTRATIVE JPM A-3 PAGE 5 of 10

NRC ADM JPM A-3 STEP 6 (6.2.6):

If criteria on Figure D.6 is not met, the Incore detector system is NOT Operable CRITICAL STEP STANDARD:

Determines lncore System is Inoperable EXAMINERS CUE: After operability determination, the Unit Supervisor directs you to remove new failed detector(s) from SCAN in DCS using 2-NOP-SAT 102.01, Distributive Control System (DCS)

Operations, step 6.3.

UNSAT EXAMINERS CUE:

For RO candidates, the Unit Supervisor determines the system is inoperable. The Unit Supervisor directs you to remove new failed detector(s) from SCAN in DCS using 2-NOP-102.01, Distributive Control System (DCS)

Operations, step 6.3.

EXAMINERS NOTE: This is not a Tech Spec operability, but is an operability requirement of FSAR 13.8.1.2.

COMMENTS:

2-NOP-1 02.01 Distributed Control System (DCS) Operations STEP 7 (6.3.1):

Select INCORE from Main menu STANDARD:

INCORE selected SAT EXAMINERS CUE:

NONE UNSAT COMMENTS:

STEP 8 (6.3.2):

Select the lncore Group with the failed detector STANDARD:

Correct lncore group (#43) selected EXAMINERS CUE:

NONE SAT COMMENTS:

UNSAT ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-3 PAGE 6 of 10

NRC ADM JPM A-3 ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-3 PAGE 7 of 10

NRC ADM JPM A-3 STEP 9 (6.3.3):

Select DEL FROM SCAN button for the failed detector CRITICAL STANDARD:

DEL SCAN button turns black for detector #1 of string 43 STEP EXAMINERS CUE:

NONE EXAMINERS NOTE: This step will be repeated for detectors 2, 3, and 4.

SAT COMMENTS:

UNSAT STEP 10 (6.3.4):

SELECT the Input Box on the pop-up screen.

STANDARD:

Input Box Selected for detector #1 of string #43 EXAMINERS CUE:

NONE SAT EXAMINERS NOTE: Input Box is above the DEL SCAN button.

EXAMINERS NOTE: This step will be repeated for detectors 2, 3, and 4.

UNSAT COMMENTS:

STEP 1 1 (6.3.5):

Enter zero (0) in the Input Box and then PRESS Enter.

CRITICAL STANDARD:

The Flux value will now be shown in pink on a black background and STEP a small black box with a pink letter 0 will now appear next to the Flux value. Annunciator L-1 6 clears.

EXAMINERS CUE:

NONE SAT EXAMINERS NOTE: When the DEL SCAN button is colored light blue, the lncore detector will have been deleted and the UNSAT DCS will no longer evaluate the incore. When a zero (0) is manually entered, this will positively indicate that the Incore detector was taken out of service and that value will be stored in the log term historian.

EXAMINERS NOTE: This step will be repeated for detectors 2, 3, and 4.

COMMENTS:

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-3 PAGE 8 of 10

NRC ADM JPM A-3 STEP 12 (6.3.6):

Ensure the Flux value now indicates zero (0)

STANDARD:

Flux value indicates zero (0) for detector #1 at string location #43 SAT EXAMINERS CUE: NONE EXAMINERS NOTE: This step will be repeated for detectors 2, 3, and 4.

UNSAT COMMENTS:

STEP 13 (6.3.6):

SELECT CLOSE to return to the main Incore screen STANDARD:

Incore string #43 detector #1 will show a black box in the upper left quad.

SAT EXAMINERS CUE: NONE EXAMINERS NONE: Black box indicates the detector has been UNSAT removed from scan.

EXAMINERS NOTE: This step will be repeated for detectors 2, 3, and 4.

COMMENTS:

STEP 14 (6.3.6):

Document change to Incore Detector status on Data Sheet 1 STANDARD:

Failed detector recorded on Datasheet 1 EXAMINERS CUE:

The US directs tha another operator will provide Independent Verification (IV) on Data Sheet 1. Examiner may SAT need to cue examinee that this is the END of the JPM.

EXAMINERS NOTE: Since no specific direction is given, there may be UNSAT a wide variety of wording that would meet the intent of recording this change on data sheet I COMMENTS:

END OF TASK STOP TIME:

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-3 PAGE 9 of 10

CANDIDATE COPY (TO BE RETURNED TO THE EXAMINER UPON COMPLETION)

Directions to the candidate for Administrative JPMS:

I will explain the initial conditions and state the task to be performed. You will be allowed to use any reference needed to complete the task. Ensure you indicate to me when you finish your assigned task by returning the material needed for the task that I provided to you.

Initial Conditions 1.

Unit 2 is at I 00°/b power

2. Annunciator L-16 is in alarm. The ARP has been pulled with the following actions completed:

a.

Reactor Engineering has been notified.

b.

NOP-lO0.03, Monitoring Linear Heat Rate, has been referred to and the Prerequisites, Precautions, Limitations, and Initial Conditions of NOP 100.03, have been completed.

Initiating Cue The Unit Supervisor has directed you to perform NOP-I 00.03, Monitoring Linear Heat Rate, starting with step 6.2.1.

FLORIDA POWER AND LIGHT ST. LUCIE PLANT k

1 ey UNIT NO. 2 GROUP 9IUX (RH1)

FLUX LOG FLORIDA POWER AND LIGHT

- ST. LUCIE PLANT - UNIT NO 2

NV*10 (12)

FLUX (P.H2)

NV*10 (12)

FLUX (IU{3) 1477*10 (12)

FLUX (R144) 1477*10 (12) 1 0.000000 0.000000 0.000000 0.000000 45.224892 45.568596 45.090939 45.061691 3

0.000000 0.000000 0.000000 0.000000 4

45.215141 45.549103 45.066563 45.039757 5

42.040714 42.328339 41.878723 41.853142 43.071617 43.409214 42.955936 42.926693 7

48.763912 49.188087 48.676270 48.644592

0.000000 0.000000 0.000000 0.000000

51.701099 52.132626 51.584221 51.572033 10 0.000000 0.000000 0.000000 0.000000 11 48.739536 49.134464 48.610462 48.583656 12 0.000000 0.000000 0.000000 0.000000 13 47.545208 47.937691 47.430759 47.399075 14 51.713291 52.159439 51.615910 51.601288 15 0.000000 0.000000 0.000000 0.000000 16 0.000000 0.000000 0.000000 0.000000 17 51.732792 52.130192 51.584221 51.611038 18 0.000000 0.000000 0.000000 0.000000 19 47.515965 47.876755 0.000000 0.000000 20 41.731201 42.051723 41.605774 41.572872 21 0.000000 0.000000 0.000000 0.000000 22 0.000000 0.000000 0.000000 0.000000 23 51.723042 52.161877 51.613472 51.620785 24 51.740101 52.169193 51.632965 51.696358 25 51.771790 52.169189 51.637848 51.737793 26 0.000000 0.000000 0.000000 0.000000 27 51.701099 52.115562 51.562283 51.574471 28 0.000000 0.000000 0.000000 0.000000 29 50.077705 50.501900 49.955944 49.916946 30 0.000000 0.000000 0.000000 0.000000 31 51.764477 52.169189 51.630531 51.691483 32 51.771790 52.169189 51.632965 51.730480 33 0.000000 0.000000 0.000000 0.000000 34 0.000000 0.000000 0.000000 0.000000 35 0.000000 0.000000 0.000000 0.000000 36 0.000000 0.000000 0.000000 0.000000 37 0.000000 0.000000 0.000000 0.000000 38 47.550087 47.930378 47.408821 47.367393 39 51.720604 52.149689 51.584221 51.559849 40 0.000000 0.000000 0.000000 0.000000 41 51.727917 52.144814 51.593971 51.632969 42 51.713291 52.125313 51.572033 51.593975 43 103.375389 104.194557 103.070923 103.039253 44 0.000000 0.000000 0.000000 0.000000 45 0.000000 0.000000 0.000000 0.000000 46 48.771229 49.175900 48.634838 48.590965 47 51.708420 52.132622 51.562283 51.528156 48 0.000000 0.000000 0.000000 0.000000 49 51.693787 52.105816 51.537903 51.508659 50 48.744408 49.129589 48.593395 48.558388 51 0.000000 0.000000 0.000000 0.000000 52 42.066685 42.359276 41.893745 41.855988 53 0.000000 0.000000 0.000000 0.000000 54 46.328270 46.703720 46.191891 46.152893 55 0.000000 0.000000 0.000000 0.000000 56 42.030167 42.327625 41.865753 41.832897 Print Date: 7/1/2005 6:27 AM FluxShftl I PAGE-IOF1

-Q IVISION NO.:

PROCEDURE TITLE:

PAGE:

42B REACTOR ENGINEERING PERIODIC Attachment tcj:

PROCEDURE NO.:

TESTS, CHECKS AND CALIBRATIONS 48 of 64 OPERATING SURVEILLANCE PROCEDURE O-OSP-64.O1 ST. LUCIE PLANT ATTACHMENT 1, DATA SHEET 1 PERIODIC SURVEILLANCE OF INCORE DETECTOR SYSTEM Table of failed individual detectors FOR INFORMATION ONLY This document is not controlled. Before using this substitute form it must be verified

Administratively OOS for observation to contain at least the same minimum information as the original.

Date Verified 2-i Ii Oqinitiais 19 4

75 W-8 12/17/09 18 Low Signal 106 g

ic9 m-i c5 qJ

/3 a.

17 C) 7-if, j

iS 9

1..,1 7

-s I

it 93

--z T-)L 5

pip Substitute Data Sheet

11-3 ee 6 y

Unit 2 Cycle 18 Figure D.6, Incore Operating Status pg 2 of 2 2,

16 1z S

7 5

4 Quadrant 1 II I

0 Notes:

1. North is at the top of the page.

2. Shading indicates a failed detector.

3. Core map current as of:

12118109 Quadrant 3 180 Prepared by:

JDate/ /

Verified by:

Date

Unit 2 lncore Operability Status Fig. D.6 Pg. 1 of 2 4

Test Current Limit Number of operable detectors needed to satisfy NOP-100.03 (Monitoring Linear 124 of 224(

55.36% )

112 of 224(50%)

Heat Rate) Sect. 6.2 Upper Quadrant Number of operable detectors per upper core quadrant (N/A NOP-1 00.03)

Number of operable detectors per lower core quadrant (N/A NOP-1 00.03)

Number of operable detectors per core quadrant (upper + lower, N/A NOP 100.03) 4 10 Final Safety Analysis Report:

(1) 50% of the detectors must be operable (2)

Four detectors in each upper and lower half are operable (3)

Ten detectors must be operable per core quadrant.

Detector String Quadrant Locations Quadrant (1)

Quadrant (2)

Quadrant (3)

Quadrant (4):

32, 40, 6,

13, 1,

2, 12, 18, per core quadrant.

Status as of:

12115109 Prepared by:

Verified by:

41, 42, 46, 47, 48, 49, 50, 52, 53, 54, 55, 56 14, 20, 22, 23, 24, 29, 30, 31, 36, 38, 39, 45 3,

4, 5,

7, 8,

9, 10, 11, 15, 16, 17, 25 19, 21, 26, 27, 28, 33, 34, 35, 37, 43, 44, 51

/

/c DATA SHEET I CHANGE OF DCS DATA (Page 1 of 1)

REVISION NO.:

PROCEDURE TITLE:

PAGE:

8A DISTRIBUTED CONTROL SYSTEM (DCS) f 81 PROCEDURE NO.:

OPERATIONS 2-NOP-102.O1 ST. LUCIE UNIT 2 Parameter As Found As Left Initial IV Date Time

)LS PiD iIc Z,J c(AJ tL O4.t4r

-cY41A ccA4/

cri* 4 Lj3 1rJl

/

Reason Parameter was changed:

Reviewed By:

US/SM END OF DATA SHEET I S

2 OPS DATE____________

DOC Procedure DOCN NOP-1 02.01 SYS COM cpmpleted ITM

REVISION:

PROCEDURE TITLE:

PANEL:

1 ANNUNCIATOR RESPONSE PROCEDURE L

PROCEDURE NO:

W1NDOW; 2-ARP-01-L16 ST. LUCIE UNIT 2 ANNUNCIATOR PANEL L 12345678 9

10 11 12 13 14 15 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 i £.

DEVICE:

DCS Incore Monitor Device LOCATiON:

Control Room SETPOINT:

Various ALARM CONFIRMATION:

1.

Process Alarm located on the DCS system bar is blinking red on the Operators or Engineering workstation.

2.

DCSlncoreMap OPERATOR ACTIONS:

1.

Print Process Report Flux Data Logo 2.

NOTIFY Reactor Engineering.

3.

Refer to 0-NOP-100.03, Monitoring Linear Heat Rate.

CAUSES:

Detector neutron volts exceeds the high alarm limit (1-IAL), for greater than 10 seconds.

LINEAR HEAT RATE / INCORES L-1 6

REFERENCES:

1.

2.

PC/M 02042 CWD 2998-B-327 Sheet 1550

PROCEDURE TITLE:

PAGE:

MONITORING LINEAR HEAT RATE 7 of 10 ST. LUCIE PLANT Monitoring Linear Heat Rate Using the Incore Detection System OBTAIN a Flux Log from the DCS by performing the following:

7 From the Main Menu ACCESS the Process Reports.

PRINT.

A Failed or Abnormal Detector wU4tTrdicated by one of 3 colors: Black, White or Red on the Incore Display.

DETERMINE which incore detectors in the flux log are failed or abnormal.

cl COMPARE the number of failed detectors and their locations to the list of failed incore detectors maintained in the Equipment Out of Service (QOS)

Log, Figure D.6, Incore Operating Status.

If any detectors are discovered as failed in addition to those identified in Figure D.6, Then ADD the additional failed detector to the total.

EVALUATE the total number of failed detectors against the criteria listed in Figure D.6, lncore Operating Status Table.

If the criteria of Figure D.6, lncore Operating Status, is NOT met, Then the re detector system is NOT operable.

d A.

PERFORM the following to monitor LFIR using the Excore Detector tern.

1.

PROCEED to Section 6.3, Monitoring LHR Using the Excore Detection system.

2.

REFER to Technical Specifications 3.2.1, immediately ADVISE the Shift Manager and contact Reactor Engineering.

7.

VERIFY fewer than 2 self-powered moore detectors are in alarm.

NOTE An asterisk next to the detector reading on the flux log indicates that detector has exceeded its alarm setpoint.

A.

If two or more detectors are in alarm, Then NOTIFY Reactor Engineering and l&C Department.

B.

If four or more detectors are in alarm, Then INITIATE corrective action within 15 minutes to reduce LHR to within limits (less than 4 detectors in alarm) within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months in accordance with Technical Specification 3.2.1.

5A NO.:

NOP-1 00.03

REVISION NO.:

PR(XEL)UF< IIILh; PAGE:..

8A DISTRIBUTED CONTROL SYSTEM (DCS) -

f 81 PROCEDURENO.:

OPERATIONS 0

A 2-NOP-102.O1 ST. LUCIE UNIT 2 6

Deleting an Incore Detector From the Main Menu, SELECT the Incore button.

SELECT the lncore group that contains the detector you wish to delete.

4 SELECT the DEL FROM SCAN button located at the bottom of the pop-up screen for the selected detector.

/P(

The DEL FROM SCAN button will now turn black indicating that the

&J detector has been deleted from scan.

SELECT the input box of the pop-up screen above the DEL FROM SCAN button.

ENTER a zero (0) in the Input Box and then PRESS the Enter key.

The Flux value will now be shown in pink on a black background and a small black box with a pink letter 0 will now appear next to the Flux value. This indicates that a manual value has been entered.

ENSURE that the Flux Value now indicates zero (0).

SELECT Close to return to the main lncore screen On the main Incore screen, the Incore string will now show a black box in the upper left quad indicating that at least one (1) of the detectors has been deleted from scan.

Use Datasheet I of this procedure to document the change to the Incore Detector.

When the DEL FROM SCAN butto4-olored light blue, the Incore detector will have been deleted and the DS will no longer evaluate the incore.

When a zero (0) is manually entered, this will positively indicate that the Incore detector was taken out of service and that yalue will be stored in the log-term historian.

END OF SECTION 6.3

13.8.1.1.2 Surveillance Requirements Each of the above seismic monitoring instruments shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown on Table 13.8,1-2.

Each of the above seismic monitoring instruments actuated during a seismic event (greater than or equal to O.Olg) shall be restored to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and a CHANNEL CALIBRATION performed within 5 days.

Data shall be retrieved from actuated instruments and analyzed to determine the magnitude of the vibratory ground motion.

core Detectors Plant operating restrictions associated with the Iricore Detectors were removed from the facility Technical Specifications by License Amendment No. 136 and NRC Safety Evaluation Report issued June 6, 1995.

The operability of the moore detectors with the specified minimum complement of equipment ensures that the measurements obtained from use of this system accurately represent the spatial neutron flux distribution of the reactor core.

The NRC Safety Evaluation Report issued June 6, 1995 with Technical Specification License Amendment #136 removing the incore detector operating restrictions from the Technical Specifications and placing them in the UFSAR recommends that any safety evaluation to reduce the minimum number of operable incore detectors address certain issues.

These issues are specified below; 1)

How an inadvertent loading of a fuel assembly into an improper location will be detected; 2)

How the validity of the tilt estimates will be ensured; 3)

How adequate core coverage will be maintained; 4)

How the measurement uncertainties will be assured and why the added uncertainties are adequate to guarantee that measured peak linear heat rates, peak pin powers radial peaking factors, and azimuthal power tilts will meet Technical Specification limits; and 5)

How the incore detector system will be restored to full (or nearly full) service before the beginning of each cycle.

13.8.12.1 Limiting Conditions for Operation 1.

The moore detection system shall be operable using the BEACON code with; a.

The minimum requirement for detector availability at the beginning of each cycle is 75% for startup testing misload verification. For the rest of the cycle 50% detector availability is needed, and 13.8-2 Amendment No. 22 (05/07)

REGION II ST. LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM A-4 EVALUATE SURVEY MAP DATA (RO/SRO)

This is NOT a TIME CRITICAL JPM This is a Non-Faulted JPM

REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM EVALUATE SURVEY MAP DATA KA Statement:

2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions.

KA IR:

RO 3.5, SRO = 3.6

References:

HPP-20, Area Radiation and Contamination Surveys RWP 09-0002 Routine Maintenance ask Candidate:

Name Validation Time:

20 minutes Start Time:

Finish Time:

Performance Rating:

Sat Unsat Examiner:

Signature:

Comments ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-4 PAGE 2

REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM EVALUATE SURVEY MAP DATA Directions to the candidate for Administrative JPMS:

I will explain the initial conditions and state the task to be performed. You will be allowed to use any reference needed to complete the task. Ensure you indicate to me when you finish your assigned task by returning the material needed for the task and the cue sheet that I provided to you.

Initial Conditions You are an extra Unit I Reactor Operator. All three Charging Pumps have been identified as having a common issue. You have been assigned to perform an inspection tour of all three Charging Pumps.

Initiating Cue Evaluate:

a) the attached survey map for the areas you will be touring b) the ROUTINE MAINTENANCE RWP Determine:

1. The expected required postings for charging pump rooms 1A, 1 B & 1 C in accordance with HPP-20, Area Radiation and Contamination Surveys.

2. Whether the Operations Routine Maintenance RWP may be used for this tour.

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-4 PAGE 3

START TIME:

STEP 1:

Determines the posting for Charging pump room 1A is expected to be a CRITICAL Locked High Radiation Area STEP STANDARD:

LOCKED HIGH RADIATION AREA SAT EXAMINERS CUE:

NONE EXAMINERS NOTE:

A specific RWP is required for entry.

EXAMINERS NOTE:

The candidate may state a HOT SPOT posting is UNSAT necessary. This determination is not part of the CRITICAL step.

COMMENTS:

/

STEP 2:

Determines the posting for Charging pump room 1 B is expected to be CRITICAL Radiation Area and Contaminated Area STEP STANDARD:

RADIATION AREA AND CONTAMINATED AREA SAT EXAMINERS CUE:

NONE COMMENTS:

UNSAT STEP 3:

Determines the posting for Charging pump room 1C is expected to be CRITICAL Radiation Area STEP STANDARD:

HIGH RADIATION AREA SAT EXAMINERS CUE:

NONE EXAMINERS NOTE:

The candidate may state a HOT SPOT posting is UNSAT necessary. This determination is not part of the CRITICAL step.

COMMENTS:

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-4 PAGE 4

STEP 4:

Determines that Operations ROUTINE MAINTENANCE RWP is NOT CRITICAL sufficient for this tour.

STEP STANDARD:

OPERATIONS ROUTINE MAINTENANCE RWP IS NOT SUFFICIENT FOR SAT THIS TASK EXAMINERS CUE:

NONE UNSAT EXAMINERS NOTE:

RWP 09-0002 Task #2 allows entry into contaminated and HRA (after HP brief) as long as RWP dosimetry alarm limits are not exceeded. This RWP does NOT allow entry into a LOCKED HIGH RADIATION AREA for a tour of the IA charging pump. This RWP does allow entry into the 18 and IC charging pump rooms.

COMMENTS:

STOP TIME:

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-4 PAGE 5

CANDIDATE COPY (TO BE RETURNED TO THE EXAMINER UPON COMPLETION)

Directions to the candidate for Administrative JPMS:

I will explain the initial conditions and state the task to be performed. You will be allowed to use any reference needed to complete the task. Ensure you indicate to me when you finish your assigned task by returning the material needed for the task and the cue sheet that I provided to you.

Initial Conditions You are an extra Unit 1 Reactor Operator. All three Charging Pumps have been identified as having a common issue. You have been assigned to perform an inspection tour of all three Charging Pumps.

Initiating Cue Evaluate:

a) the attached survey map for the areas you will be touring b) the ROUTINE MAINTENANCE RWP Determine:

1. The expected required postings for charging pump rooms 1A, lB & 1C in accordance with HPP-20, Area Radiation and Contamination Surveys.

2. Whether the Operations Routine Maintenance RWP may be used for this tour.

FLORIDA POWER & LIGHT - PSL HPS

- 7 LOCArION:

CI-IARG1NG PUMPS

- FL. -.5 FT.

D ATE 81509

10) GRAVE DANGER

- VERY HIGH RAE) AREA (C) CON1AMIN,VIEDAREA IL) I_OCRED HIGH RAE) AREA (P) HOT PARrICLE AREA TIME:

0700 iH) lEIGH RAE) AREA IS) SPECIFIC RWP REQUIRED RPT (PRI\\T)

J. Swift Ill) HI, COVERAGE REQUIRED RPT SIGNATURE:

itRBORNL RADIOACTIVE RWP il)FIl0HIX C()N9A\\IINvrED AREA j IX MDA =

dpm INSTRUMENT TYPE I i/

R020/3603 INSTRUMENT TYPE,1 dpm lot Pan INSTRUMENT TYPE / #

L-177/21829 INSTRUMENT TYPE / /

No probe area y N LLLX SMEARS EN DPMI 100CM 2

A N/A N/A I

<1K /

6

<1K/

I I

<1K/

16 N/A/

21 N/A/

26 N/A /

13 N/A N/A 2

<1K /

7 1.9K /

12

<1K/

17 N/A!

22 N/A/

27 N/A /

C N/A N/A D

N/A N/A 3

<1K /

8 1.5K/

13

<1K/

1$

N/A/

23 N/A/

2$

N/A/

N/A N/A 4

<1K /

9 1.11<!

14

<1K/

19 N/A/

24 N/A/

29 N/A/

F N/A N/A

<1K /

10

<1K/

N/A/

20 NIA/

25 N/A/

p N/A/

(

N/A N/A LEGEND.

(UiiiI.roi Dte Raws Reviewed By:

(,r:,o Dos Rak D

Sr:,,rLc,caIic,n B. Gold 8-15-09 A

Nucsn Dtse Rai, nr enpI DDE)

I idi:en lEidlh I rini Name Signature Dale R:nli;eior, / (1 tnnI[;.,Ied ]3,>eiidi A..I_ RE\\DINIIS IN IRIIR I \\LI:SS OIIiI:RViSE NOTE!)

Charging Pump Room B REMARKS:

Exposure Received Completing Survey:

15 mrem Charging Pump Room C

Charging Pump Room A S

1 OPS 1)AT E 1)OCF SUR\\/EY DOCN H PS7 SYS HP COM P ITM

a.

FQa a

a.

C

aa a

REVISION NO.:

PROCEDURE TITLE:

PAGE:.

28 AREA RADIATION AND CONTAMINATION f 31*

PROCEDURE NO SURVEYS 0

HPP-20 ST. LUCIE PLANT 6.1 General (continued) 3.

Record information on survey maps and forms as soon as practical. Survey nomenclature on maps and forms should be as follows:

A.

Num ers réiienting mrem/hr general area dose rate are underlined for gamma, boxed for beta, within a triangle for neutron.

B.

Numbers representing mrem/hr contact dose rate are indicated by an asterisk or star next to numbers underlined, boxed or within a triangle, as appropriate.

C.

Levels of removable contamination in dpm/1 00cm 2 should be indicated by circled numbers for smear locations.

D.

Units of Rem/hr or additional pertinent nomenclature shall be clearly td 4.

Postings and updating should be noted on the survey maps and forms before the maps are approved. Outdoor postings should be checked for proper colors and fading due to sun.

5.

Personnel performing surveys are responsible for:

A.

Initiating radiological controls as indicated by the survey results.

B.

Completing and signing the survey forms prior to the end of the shift, if time permits.

C.

Routing th h Physics Shift Supervisor for review and appro 4 fl,441bU D.

Placing th

k&

npleted surveys box during non-outage op*

U 7

E.

Notifying t

-....rvisor when changes to postings were made.

6.

A Health Physics Shift Supervisor is responsible for reviewing and approving the adequacy of completed survey forms.

A.

Copies of approved surveys shall be available for plant personnel to review prior to entering the RCA.

END OF SECTION 6.1

REVISION NO.:

PROCEDURE TITLE:

PAGE:

28 AREA RADIATION AND CONTAMINATION 17 f 37 PROCEDURE NO.:

SURVEYS 0

HPP-20 ST. LUCIE PLANT 6.6 Requirements Based on Survey Results 1.

Radiation Areas A.

§.,,

Any area, accessible to individuals, in which radiation levels could resu I receiving a dose equivalent in excess o mr I hou at 12 inches (30 cm) from the radiation source or from any surface that the radiation penetrates shall be posted with a conspicuous sign bearing the radiation symbol and the words, CAUTION, RADIATION AREA.

B.

§12.3 Any area, accessible to individuals, in which radiation levels could resu iv se equivalent in excess o 00 mrem in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months at che 0 cm) from the radiation sourc or from any u ace that the radiation penetrates shall be posted with a conspicuous sign bearing the radiation symbol and the words, CAUTION, HIGH RADIATION AREA, SPECIFIC RWP REQUIRED. Additionally, the area shall have access control requirements established in accordance with the applicable Technical Specifications.

C.

§2,3 Any area, accessible to individuals, in which radiation levels could resuJ awfrdni rer.PiVing dpse egijyent in excess of

,000 m em inj hour at 12 inches (30 cnfrom the radiation sou or from any surface That the raiation penetrates shall be posted with a conspicuous sign bearing the radiation symbol and the words, CAUTION, LOCKED HIGH RADIATION AREA, SPECIFIC RWP REQUIRED, HP COVERAGE REQUIRED. Additionally, the area shall have access control requirements established in accordance with the applicable Technical Specifications.

D.

§12,3 Any area, accessible to individuals, in which radiation levels ul n indivi eiving an absorbed dose in xcess for 50 s in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months at meter from the radiation so ce any su e radiation penetrates shall be posted with a conspicuous sign bearing the radiation symbol and the words, GRAVE DANGER, VERY HIGH RADIATION AREA, SPECIFIC RWP REQUIRED, HP COVERAGE REQUIRED. Additionally, the area shall have access control requirements established in accordance with 10 CFR 20.

2.

Surveys, postings and placards are not required in overhead areas, unless made accessible by ladders or scaffolding.

REVISION NO.:

PROCEDURE TITLE:

PAGE:

28 AREA RADIATION AND CONTAMINATION f

PROCEDURE NO.:

SURVEYS

18 o 37 HPP-20 ST. LUCIE PLANT 6.6 Requirements Based on Survey Results (continued)

NOTE T5,8 Hot Spot stickers shall not be stuck directly on stainless steel components. Some adhesives contain halogens (i.e., chlorides) that may degrade the component. Alternate means of Hot Spot postings are to be utilized to identify Hot Spots. The recommended method is to affix the Hot Spot sticker to a yellow plastic CAUTION sign attached to the component with Rad rope or ribbon.

Hot Spots need be identified for areas! routinely accessed or for areas accessed only during outages, unless otherwise directed by RP Supervision.

(_

3. § A component or item having a contact reading greater than 100 mrem/hr and more than 5 times the general area radiation levels (i.e. 30 cm from contact) should be posted as a HOT SPOT. The Hot Spot Log should be updated monthly upon completion of the comprehensive surveys.

4. §i The boundary he Radiation Controlled Area N Wb maintained at less than 2 mrem!hr.

If the radiation levels outside the RCA are found to be greater than 2 mrem/hr, barricade and post the area and take action to reduce the radiation levels to less than 2 mrem/hr.

5.

Contamination A. §3 Any area containing removable surface contamination in excess of 1000 dpm/lOOcm 2 betaIgamma or 20 dpmIlOOcm 2 alpha shall be posted as a Contaminated Area.

B.

Any area containing rem[!Urtace contaminatidTiih excess of 100,000 dpm/lOOcm 2 beta I gamma should be posted as a Highly Contaminated Area.

C.

Exits from contaminated areas require as a minimum, a single step-off pad placed on the CLEAN side of the access point for the area.

D.

Areas in which contamination exists over a major portion of the area in excess of 100,000 dpm/lOOcm 2 may require a double step-off pad.

E.

Replace step-off pads between areas of higher and lower contamination levels at a frequency determined by contamination surveys.

F.

Restricted areas established in the controlled area shall be surveyed and posted in accordance with the requirements of 6.6.1 above.

END OF SECTION 6.6

St. Lucle Nuclear Power Plant FPLStLucIe RADIOLOGICAL WORK PERMIT RWP

Title:

Radiation Protection, Nuclear Operations, Security, Chemistry: Entry Int4 RWP No.: 09-0002 Rev. 02 The Ptin Cr,ntrnllp,1 Ar,.,, nd Reactor AnyDiqr Bldn.

I 1.16 Task: ROUTINE MAINTENANCE Comments: Unit! &2RAB/RCA RWP Type: JOB ROUTINE RWP Status:

Begin Date:

Close On Date:

ACTIVE 3/412009 Prepared By:

Job Sunervlsor:

ALARA rD; Stay Time Aiarm(hh:mm):

Estimated Dose: 4,201 snrem Estimated Hours: 246,556.00 Chlro Rate:

Actual Dose: 2,630 mrem Actual Hours: 140,822.08 Buildings

[

Elevations Rooms Jnit 1 & 2 RAB / RCA A11 Areas ALL AREAS

)escrlption General Area Contamination Levels

<1K G/A dpm /100 cm2 General Area Gamma Level

<1 G/A nREM/HR Task Description Status 1

RP Dept: Job Coverage, Surveys, Inspections. Source Check / Calibrate Survey Instr.

Active 2

Operations Dept: Clearances, Tags, Surveillances and Inspections.

Active 3

Security: Walkdowns, Inspections, Patrols.

Active 4

Chemistry Dept: Sampling and Analysis.

Active 5

Operations Dept (Trainees): Clearances, Tags, Surveillances and Inspections.

Active 6

RP Dept (Trainees)

Active 7

Chemistry De t (Trainees) 4kctive Instructions 1:

InstructIons 2:

Instructions 3 Approver Title Name Date SUPERVISOR SEXTON, ALAN B 03/0612009 N/A 10i29/2009 1:36:55PM Page 1 of I

St. Lucie Nuclear Power Plant FPL St. Lucie RADIOLOGICAL WORK PERMIT RWP

Title:

Radiation Protection, Nuclear Operations, Security, Chemistry: Entry Tnt RWP No.: 09-0002 Rev. 02 The Radiation Controlled Area and Reactor Auxiliary Bide.

1.16 Task: ROUTII4.E I4A.I4TEN.A}NTCE WIIM 11111 IIIIIIII 11111 llh IJ 090002 Comments: Unit I & 2 RAB / RCA RWP Type: JOB ROUT1ThJE RWP Status:

Begin Date:

Close On Date:

ACTIVE 3/4/2009 Prepared By:

Job Supervisor:

ALARA ID:

Stay Time Alarm(hh:mm):

Estimated Dose: 4,201 mrem Estimated Hours: 246,556.00 T Chirp Rate:

Actual Dose: 2,630 mrem Actual Hours: 140,822.08 1

Buildings I

Elevations Rooms Unit I & 2 RAB I RCA FAll Areas ALL AREAS

,,i$ig dmbi

)escription 7

aIue Unit General Area Contamination Levels

<1K G/A dpm I 100 cm2 General Area Gamma Level

<1 G!A mREM!HR Task Description Status I________________ RP Dept: Job Coverage, Surveys, Inspections. Source Check! Calibrate Survey Instr.

Active 2

Operations Dept: Clearances, Tags, Surveillances and Inspections.

Active 3

Security: Walkdowns, Inspections, Patrols.

Active 4

Chemistry Dept: Sampling and Analysis.

Active 5

Operations Dept (Trainees): Clearances, Tags, Surveillances and Inspections.

Active 6

RP Dept (Trainees)

Active 7

Chemistry Dept (Trainees)

Active

-:RecLu1reIpents---

Requirement Grpip Requrement Descriptions N/A V

Instructions 1:

Instructions 2:

Instructions 3:

Approver Title Name Date SUPERVISOR SEXTON, ALAN B 03/06/2009 N/A 10/29/2009 1:36:55PM Page 1 of I

St. Lucie Nuclear Power Plant FPL St. Lucie RADIOLOGICAL WORK PERMIT iMliP l1tilJiJf r.

Instructions 3: ALARA HOLDPO1NTS: In case of an EPD alarm leave area immediately and report to RP at RCA control point.

persore1 are authorized to enter a HRA but are not to exceed the RWP EPD dose rate setpoint of 300 mrem/hr.

N/A 10/29/2009 1:37:02PM Page 7 of 7 Task Number:

1 RWP No.: 09-0002 Rev.: 02 Task

Description:

RP Dept: Job Coverage, Surveys, Inspections. Source Check I Task Status: Active Calibrate Survey Instr.

1.16 Task: ROUTINE MAINTENANCE ALARATD:

StayTimeAlarm(hh:mm):

16:00 Estimate Dose:

1,928.00 Estimate Hours: 53,205.00 Chirp Rate:

Hi-Rad: Yes Hot Particle: Yes Locked Hi-Rad: No Hi-Contamination: Yes

Low Gamma Dose (mrem)

Low Gamma Rate (mrem/hr)

High Gamma Dose (inrem)

High Gamma Rate (mremlhr) 12.00 300.00 Low Beta Dose Low Beta Dose High Beta Dose High Beta Rate Low Neutron Dose Low Neutron Dose High Neutron Dose High Neutron Rate Requirement Groups Requirement Descriptions DOSIMETRY (PAM) Required to be worn in HRAs..

GENERAL 11ISTRUCTIONS efer to HPP-15 for hot particle area work. WIB scan with RO-2 or equivalent (open window) shall be done at 2 hr intervals when in HPAs. Use HPP-3.3 form.

Observe & obey ALL RP postings & verbal instructions. Utilize low dose waiting areas.

PROTECTIVE CLOTHiNG tP will determine PC requirements based on radiological conditions in work areas.

UiaHnstfh Instructions 1:

This RWP is to be used for routine shift work including source check and calibration of survey instrumentation.

pJTs shall provide their own surveys, radiological job coverage. *Utffize R.P procedures to provide radiological coverage. *Contact RPSS to obtain appropriate procedures. Contact RPSS to disctiss I resolve issues as needed.

Instructions 2: *Sign in and out on Form BPP-30.I4 while working with Neutron sources.

St. Lucie Nuclear Power Plant FPL St. Lucie RADIOLOGICAL WORK PERMIT Task Number: 2 RWP No.: 09-0002 Rev.: 02 Task

Description:

Operations Dept: Clearances, Tags, Surveillances and Inspections.

Task Status: Active 1.16 Task: ROUTINE MAINTENANCE ALARAID:

StayTimeAlarm(hh:mm): 16:00 Estimate Dose: 1,823.00 Estimate Hours: 40,954.00 Chirp Rate:

HiHad: Yes Hot Particle: Yes Locked Hi-Rad: No

[

Hi-Contamination: Yes

j__r1_

Low Gamma Dose (mrem)

Low Gamma Rate (mremlhr)

High Gamma Dose (mrem)

High Gamma Rate (inrem/hr) 12.00 300.00 Low Beta Dose Low Beta Dose High Beta Dose High Beta Rate Low Neutron Dose Low Neutron Dose High Neutron Dose High Neutron Rate Requirement Groups Requirement Descriptions DOSIMETRY (PAM) Required to be worn in NRAs.

GENERAL INSTRUCTIONS Check EPD frequently (about every iS mm).

Observe & obey ALL RP postings & verbal instructions. Utilize low dose wailing areas.

efer to HPP-15 for hot particle area work. WIB scan with RO-2 or equivalent (open window) shall be done at 2 hr intervals when in HPAs. Use HPP-3.3 form.

ersonne1 SHALL receive a documented High Rad area briefing SPECIFIC to each BRi

,eing accessed and sign in on RP form HPP-3.5 P will survey work areas as needed.

Jse 1PM A.S.A.P. after exiting contaminated areas (Immediately after removal of PCs, while wearing modesr clothing). IfWM alarms tce, cofltactP immediately.

lIP INSTRUCTIONS eriodic RP coverage required unless otherwise specified.

PROVIDE workers with Low Dose Waiting Area information as appropriate.

PROTECTIVE CLOTHING P will determine PC requirements based on radiologioal conditions in work areas.

Instructions 1: *Surgeon / Rubber gloves, labcoat are the minimum requirements to manipulate valves in posted contaminated areas.

This can be done when valve can be reached from clean side and only the hand will touch the valve. *Change out gloves prior to handling clean material and equipment. *Contact RP prior to moving containers of Radioactive Materials. *Contact RP prior to draining water to floor drains. *Enmre hose is secured in drain. ln the event of a spill, contain spill and notiI RP immediately.

Instructions 2: *U ECCS Yard Sump: Contact RPSS / Shift RP prior to transferring yard sunip water. *Connections on hoses and pumps to be redundantly wrapped or bagged at RP direction.

the event of a leak or spill SECURE all pumping operations, contain the leak or spill and notii RP immediately.

Instructions 3: ALARA HOLDPOINTS: In case of an EPD alarm leave area immediately and report to HP at RCA control point.

Peormel are authorized to enter a BRA but are not to exceed the RWP EPD dose rate setpoint of 300 mrein/br.

CONTACT RP PRIOR TO ENTERING ANY OVERHEAD AREAS.

N/A 10/29/2009 1:37:02PM Page 6 of 7

V,V St. Lucia Nuclear Power Plant 7

FPL St. Lucie J1llhI MP WTV RADIOLOGICAL WORK PERMIT Task Number: 3 RWP No.: 09-0002 Rev.: 02 Task

Description:

Security: Walkdowrs, Inspections, Patrols.

Task Status: Active 1.16 Task: ROUTINE MAINTENANCE ALAPA ID:

Stay Time Alarm(hh:mm): 16:00 Estimate Dose: 40.00 Estimate Hours: 137,507.00 Chirp Rate:

Hi-Rad: Yes Hot Particle: No J

Locked Hi-Rad: No 1

Hi-Contamination: No

Low Gamma Dose (mrem)

Low Gamma Rate (mremlhr)

High Gamma Dose (Inrem)

High Gamma Rate (mremlhr) 5.00 125.00 Low Beta Dose Low Beta Dose High Beta Dose High Beta Rate Low Neutron Dose Low Neutron Dose High Neutron Dose High Neutron Rate Requirement Groups Requirement Descriptions DOSIMETRY (PAM) Required to be worn in NRAs.

GENERAL INSTRUCTIONS Observe & obey ALL RP postings & verbal instructions. Utilize low dose waiting areas.

Check EPD frequently (about every 15 mm).

RP will survey work areas as needed.

Personnel SHALL receive a documented High Rad area brieng SPECIFIC to each HR being accessed and sign in on RP fonn HPP-3.5 Use 1PM A.S.A.P. after exiting contaminated areas (Immediately after removal of PCs, while wearing modesty clothing). 111PM alarms twice, contact RP immediately.

I-IF INSTRUCTIONS eriodic RP coverage required unless otherwise specified.

PROVE workers with Low Dose Waiting Area oimation*as appropriate.

PROTECTIVE CLOTHING P.C.s required for work in Contaminated areas. Full-dress P-.C.s required for wor-k*-in Contaminated areas in the overhead.

- -.E--

ildthonaIrnstrucftons Instructions 1:

Instructions 2:

Instructions 3: ALARA HOLDPOINTS: In case of an EPD alarm leave area immediately, report to RP at RCA control point. *HR.A entry allowed, personnel not to exceed EPD dose rate setpoint of 125 mremlhr. *No work allowed in the 19.5 ft pipe pen with more than (1) charging pump in operation without the RPMs or ALARA supervisors permission. *CONTACT RP PRIOR TO ENTERING ANY OVERHEAD AREAS.

N/A 10/29/2009 1:37:02PM Page 5 of 7

St. Lucie Nuclear Power Plant FPL St. Lucie RADIOLOGICAL WORK PERMIT 1illllllM11P Task Number: 4 RWP No.: 09-0002 Rev.: 02 Task

Description:

Chemistry Dept: Sampling and Analysis.

Task Status: Active 1.16 Task: ROUTINE MAINTENANCE ALAR.A ID:

Stay Time Alarm(hh:mm):

16:00 Estimate Dose: 250.00 Estimate Hours: 13,406.00 Chirp Rate:

Hi-Rad: Yes Hot Particle: Yes Locked Hi-Rad: No Hi-Contamination: Yes Low Gamma Dose (mrem)

Low Gamma Rate (mrern/hr)

High Gamma Dose (mrem)

High Gamma Rate (mremilr) 12.00 125.00 Low Beta Dose Low Beta Dose High Beta Dose High Beta Rate Low Neutron Dose Low Neutron Dose High Neutron Dose High Neutron Rate Requirement Groups Requirement Descriptions DOSIMETRY (PAM) Required to be worn in HRAs.

GENERAL INSTRUCTIONS Use 1PM A.S.A.P. after exiting contaminated areas (Immediately after removal ofPCs, while wearing modesty clothing). 111PM alarms twice, contact RP immediately.

Refer to HPP-15 for hot particle area work. WIB scan with RO-2 or equivalent (open window) shall be done at 2 hr intervals when in HPAs. Use HPP-3.3 form.

Check EPD frequently (about every 15 mm).

Observe & obey ALL RP postings & vrba1 instructions. Utilize low dose waiting areas.

Personnel SHALL receive a documented High Rad area briefmg SPECIFIC to each HRP being accessed and sign in on RP form HPP-3.5 HPINSTRUCTIONS Periodic RP coverage requiied unless otherwise specified:

PROIECTWECLOTBING RP will.determine PC requirements basedn.radiological conditions in work areas..

Instructions 1: *A Minimum of Lab Coat and Rubber Gloves to be worn when sampling or reaching into a Contaminated Space tc manipulate valves. *A Minimum of Lab Coat, Rubber Gloves and shoe covers to be worn when entering (walking into) a Contaminated Area. *Notify RP immediately in case of a spill.

Instructions 2:

VThen taking primary samples wear face shield or Lower Fume Hood as much as possible while acquiring samples to maintain required face velocity. *Keep Fume Hood closed when not sampling. *Be aware of a change in dose rates while performing RCS sampling. *Keep Sample Sinks rinsed out to avoid High Contamination levels. *Personnel are to perform a hand and foot frisk prior to exiting Hot Labs after sample analysis. *personnel are to use 1PM as soon as practical after sampling and analysis ol Primary samples is complete.

Instructions 3: ALARA HOLDPOINTS: In case of an EPD alarm leave area immediately, report to RP at RCA control point. *HRA entry allowed, personnel not to exceed EPD dose rate setpoint of 125 mrem/hr.

No work allowed in the 19.5 ft pipe pen with more than (1) charging pump in operation without the RPMs or ALARA supervisors permission. *CONTACT RP PRIOR TO ENTERING ANY OVERHEAD AREAS.

N/A 10/29/2009 1:37:02PM Page 4 of 7

St. Lucie Nuclear Power Plant FPL St. Lucie RADIOLOGICAL WORK PERMIT TaskNumber: 5 RWPNo.: 09-0002 Rev.: 02 Task

Description:

Operations Dept (Trainees): Clearances, Tags, Surveillances and Task Status: Active Inspections.

1.16 Task: ROUTINE MAINTENANCE ALARA ID:

Stay Time Marm(hh:mm): 16:00 Estimate Dose: 150.00 Estimate Hours: 1,284.00 Chirp Rate:

Hi-Rad: Yes

[

Hot Particle: Yes Locked Hi-Rad: No Hi-Contamination: Yes

V_____________

Low Gamma Dose (mrem)

Low Gamma Rate (mrem/hr)

High Gamma Dose (mrem)

High Gamma Rate (mrem/hr) 12.00 300.00 Low Beta Dose Low Beta Dose High Beta Dose High Beta Rate Low Neutron Dose Low Neutron Dose

- High Neutron Dose High Neutron Rate giij Requirement Groups Requirement Descriptions DOSIMETRY (PAM) Required to be worn in RRAs.

GENERAL INSTRUCTIONS Observe & obey ALL RP postings & verbal instructions. Utilize low dose waiting areas.

Refer to HPP-1 5 for hot particle area work. W/B scan with RO-2 or equivalent (open window) shall be done at 2 hr intervals when in }fPAs. Use BPP-3.3 form.

Yse 1PM A.S.A.P. after exiting contaminated areas (Immediately after removal of PCs, Nhile wearing modesty clothing). If 1PM alarms twice, contact RP immediately.

RP will survey work areas as needed.

ersonnel SHALL receive a documented High Rad area briefing SPECIFIC to each HRA V

being accessed and sign in o.P Vorm.I35 Check.EPD frequently (about eye 15mm).

HP INSTRUCTIONS ROVLDE workers with Low Dose Waiting Area information as appropriate.

eriodic RP coverage required unless otherwise specified.

PROTECTIVE CLOTHING RP will determine PC requirements based on radiological conditions in work areas.

Instructions 1: *surgeon / Rubber gloves, Iabcoat are the minimum requirements to manipulate valves in posted contaminated areas.

Ths can be done when valve can be reached from clean side and only the hand will touch the valve. *Change out gloves prior to handling clean material and equipment. *Contact RP prior to moving containers of Radioactive Materials. *Contact RP prior to draining water to floor drains.

hose is secured in drain. *In the event of a spill, contain spill and notify RP immediately.

Instructions 2: *U#1 ECCS Yard Sump: Contact RPSS / Shift RP prior to transferring yard sump water. *Connections on hoses and pumps to be redundantly wrapped or bagged at RP direction. *In the event of a leak or spill SECURE all pumping operations, contain the leak or spill and notify RP immediately.

Instructions 3: ALARA HOLDPOINTS: In case of an EPD alarm leave area immediately and report to RP at RCA control point.

Personnel are authorized to enter a HRA but are not to exceed the RWP EPD dose rate setpoint of 300 mremlhr.

CONTACT RP PRIOR TO ENTERING ANY OVERHEAD AREAS.

N/A 10/29/2009 1:37:02PM Page 3 of 7 iNMG-P ItJTs

St. Lucie Nuclear Power Plant FPL St. Lucie RADIOLOGICAL WORK PERMIT 1HME P TaskNumber: 6 RWPNo.: 09-0002 Rev.: 02 Task

Description:

RP Dept (Trainees)

Task Status: Active 1.16 Task: ROUTINE MAINTENANCE ALARAID:

StayTimeAlarm(hh:mm):

16:00 Estimate Dose: 5.00 Estimate Hours: 100.00 Chirp Rate:

Hi-Rad: Yes Hot Particle: Yes Locked Hi-Rad: No Hi-Contamination: Yes I

Low Gamma Dose (mrem)

Low Gamma Rate (mremThr)

High Gamma Dose (mrem)

High Gamma Rate (mremlbr) 12.00 300.00 Low Beta Dose Low Beta Dose High Beta Dose High Beta Rate Low Neutron Dose Low Neutron Dose High Neutron Dose High Neutron Rate qi Requirement Groups Requirement Descriptions DOSIMETRY (PAM) Required to be worn in BRAs.

GENERAL INSTRUCTIONS Refer to HPP-15 for hot particle area work. WIB scan with RO-2 or equivalent (open window) shall be done at 2 hr intervals when in BPAs. Use HPP-3.3 form.

Observe & obey ALL RP postings & verbal instructions. Utilize low dose waiting areas.

PROTECTEVE CLOTBING P will determine PC requirements based on radiological conditions in work areas.

AdTh io?Y4 ::

Instructions 1:

This RWP is to be used for RP training including source check and calibration of survey instrumentation. *)Ts shall provide their own surveys, radiological job coverage. *fljZ RP procedures to provide radiological coverage. *Contact RP Training Supervisor / RPSS to obtain appropriate procedures. *Contact RP Training Supervisor I RPSS to discuss / resolve issues as needed.

HPP-30. 14 whiworidng with Neutiqr sources.

Instructions 3: ALARA HOLDPOINTS: In case of an EPD alarm leave area immediately and report to RP at RCA control point.

Personnel are authorized to enter a BRA but are not to exceed the RWP EPD dose rate setpoint of 300 mrem/hr. *Contact RP ALARA Dept prior to any training that may involve personnel receiving dose.

N/A Page2of7 10/29/2009 1:37:02PM

St. Lucie Nuclear Power Plant FPL St. Lucie j1MBP I MrflMP RADIOLOGICAL WORK PERMIT Task Number: 7 RWP No.: 09-0002 Rev.: 02 Task

Description:

Chemistry Dept (Trainees)

Task Status: Active 1.16 Task: ROUTINE MAINTENANCE ALARA ID:

Stay Time Alarm(hh:mm): 16:00 Estimate Dose: 5.00 Estimate Hours: 100.00 Chirp Rate:

Hi-Rad: Yes Hot Particle: Yes Locked Hi-Rad: No Hi-Contamination: Yes Low Gamma Dose (nirem)

Low Gamma Rate (mrem/hr)

High Gamma Dose (mrem)

High Gamma Rate (mrem/hr) 12.00 125.00 Low Beta Dose Low Beta Dose High Beta Dose High Beta Rate Low Neutron Dose Low Neutron Dose High Neutron Dose Neutron Rate V;V Requirement Groups Requirement Descriptions DOSIMETRY V

(PAM) Required to be worn in 1-IRAs.

GENERAL INSTRUCTIONS Observe & obey ALL RP postings & verbal instructions. Utilize low dose waiting areas.

Refer to HPP-15 for hot particle area work. WIB scan with RO-2 or equivalent (open window) shall be done at 2 hr intervals when in HPAs. Use HPP-3.3 form.

Personnel SHALL receive a documented High Rad area briefing SPECIFIC to each HR.A V

being accessed and sign in on RP form BPP-3.5 Check EPD frequently (about every 15 mm).

Use 1PM A.S.A.P. after exiting contaminated areas (Immediately after removal of PCs, while wearing modesty clothing). If 1PM alarms twice, contact RP immediately.

HP INSTRUCTIONS Periodic RP coverage required unless otherwise specified.

V PROTECTiVE CLOTHING V

J? will bascdon radiq.lciginal conditionsinwork areas.

Additional Instructions Instructions 1:

This RWP is to be used for Chemistry training. *A Minimum of Lab Coat and Rubber Gloves to be worn when sampling or reaching into a Contaminated Space to manipulate valves. *A Minimum of Lab Coat, Rubber Gloves and shoe covers to be worn when entering (wafldng into) a Contaminated Area. *Notify RP immediately in case of a spill.

Instructions 2: *When talcing primary samples wear face shield or Lower Fume Hood as much as possible while acquiring samples to maintain required face velocity. *Keep Fume Hood closed when not sampling. *Be aware of a change in dose rates while performing RCS sampling. *Keep Sample Sinks rinsed out to avoid High Contamination levels. *personnel are to perform a hand and foot frisk prior to exiting Hot Labs after sample analysis. *personnel are to use 1PM as soon as practical after sampling and analysis of Primary samples is complete.

Instructions 3: ALARA HOLDPOINTS: In case of an EPD alarm leave area immediately, report to RP at RCA control point. *JIdJ, entry allowed, personnel not to exceed EPD dose rate setpoint of 125 mrem/hr. *No work allowed in the 19.5 ft pipe pen with more than (1) charging pump in operation without the RPMs or ALARA supervisors permission. *CONTACT RP PRIOR TO ENTERING ANY OVERHEAD AREAS.

Contact RP ALARA Dept prior to any training that may involve personnel receiving dose.

Attachments

N/A 10/29/2009 1:37:02PM Page lof7

REGION II ST. LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM RESPOND TO SECURITY EVENT A-5 This JPM is TIME CRITICAL (portions)

This is a NON-FAULTED JPM

REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM RESPOND TO SECURITY EVENT KA Statement: 2.4.28 Knowledge of procedures relating to security event (non safeguards information)

KA#:

3.2/4.1

References:

ONP-72.O1, Response to Security Events EPIP-Ol, Classification of Emergencies EPIP-02, Duties and Responsibilities of the Emergency Coordinator EPIP-08, Off-Site Notifications and Protective Action Recommendations Candidate:

Name Validation Time:

30 minutes Start Time:

Finish Time:

Performance Rating:

Sat Unsat Examiner:

Signature:

Comments ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-5 PAGE 2

NRC ADM JPM A-5 REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM RESPOND TO SECURITY EVENT Directions to the candidate for Administrative JPMS:

I will explain the initial conditions and state the task to be performed. You will be allowed to use any reference needed to complete the task. Ensure you indicate to me when you finish your assigned task by returning the material needed for the task that I provided to you.

Initial Conditions Both Units are at 100% power.

Today at current time, you as the Shift Manager, receives a validated NRC Headquarters phone call to report an Airborne Threat.

The estimated time to site arrival is in 60 minutes.

A track of interest is verified by the NRC due to anomalous flight activity. The Airborne Threat has been validated with the NRC Headquarters Operations Center.

Initiating Cue You are located in Unit 2.

The Unit 2 Unit Supervisor directs you the Shift Manager to:

1. Perform Step 6.0.4 in accordance with ONP-72.01, Response to Security Events Portions of this JPM are time critical ST. LUCIE TRAIMNG DEPT.

ADMINISTRATIVE JPM A-5 PAGE 3

NRC ADM 3PM A-5 START TIME:

ONP-72.O1, Response to Security Events STEP 1 (6.0.4): IMPLEMENT Security Checklist in accordance with EPIP-02, Duties and SAT Responsibilities of the Emergency Coordinator.

STANDARD:

Refers to EPIP-02. Duties and Responsibilities of the Emergency UNSAT Coordinator Security Checklist.

EXAMINERS CUE:

NONE EXAMINERS NOTE:

Start time for time critical step_____________

COMMENTS:

EPIP-02, Duties and Responsibilities of the Emergency Coordinator.

STEP 2 (5.2.1.C): Determine Threat SAT Informational Airborne Threat (greater than 30 minutes)

Verify the Control Rooms are implementing ONP-72.01, Appendix D.

UNSAT

Unit 1

Unit 2 STANDARD:

Informs the Control Rooms to implement ONP-72.01 Appendix D EXAMINERS CUE:

Control Rooms have been notified COMMENTS:

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-5 PAGE 4

NRC ADM JPM A-5 NOTE If a threat has been validated via phone call to the NRC Headquarters, the accelerated notification to the NRC is not required.

SAT STEP 3 (5.2.2): Off Site Notifications UNSAT A. Make an accelerated notification to the NRC in accordance with EPIP 08, Off-site Notifications and Protective Action Recommendations.

STANDARD:

Determines from cue threat has been validated and NRC notification NOT required.

EXAMINERS CUE:

NONE COMMENTS:

STEP 4 (5.2.2): Off Site Notifications and Protective Action Recommendations B. Airborne Threat

- Make an abbreviated State Notification in SAT accordance with EPIP-08.

STAN DARD:

Refers to EPIP-08 and commences filling out the State Notification form.

UNSAT EXAMINERS CUE:

NONE EXAMINERS NOTE:

If asked for shift communicator, state the shift communicator is not available at this time.

COMMENTS:

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-5 PAGE 5

NRC ADM JPM A-5 EPIP-08, Off-Site Notifications and Protective Action Recommendations Appendix A NOTIFICATIONS FROM THE AFFECTED CONTROL ROOM SAT STEP 5 (1):

If Security Event, Then go to Step 3.A.1.a NRC Notification or N/A.

UNSAT STANDARD:

Determines step is N/A due to validation of threat as per cue.

EXAMINERS CUE:

NONE EXAMINERS NOTE:

A potential exists for the candidate to make an accelerated NRC phone call. Step 3.A.1.b will direct the candidate to the next step.

COMMENTS:

STEP 6 (2):

State Watch Office Notification CRITICAL STEP A. Prepare the Florida Nuclear Plant Emergency Notification Form (form similar to Attachment 1).

SAT

1. Airborne Threat Abbreviated State Notification Prepare State Notification Form by filling out the following:

Lines 1 through 6 UNSAT

Line 11 STANDARD:

EXAMINERS CUE:

NONE COMMENTS:

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-5 PAGE 6

NRC ADM 1PM A-5 ATTACHMENT I FLORIDA NUCLEAR PLANT EMERGENCY NOTIFICATION FORM SAT STEP 7 (Line 1):

1.

A.

L]THISISADRILL B.

LITHISISANEMERGENCY UNSAT STANDARD:

Checks A EXAMINERS CUE:

NONE EXAMINERS NOTE:

Per EPIP-08, Attachment IA step 1, drill, exercises or tests, each message shall be checked this is a drill COMMENTS:

STEP 8 (Line 2):

CRITICAL STEP 2.

A. De I

/

8.

Cilac1 Tbne.

C. ReteiJ by Nnie 0.

essage [urnber:

E. Rep1ed froni: U Control R U 1SC U EOF F.

nIiai / Ne CIasseati OR U Upó3te Mo:ifatioi SAT UNSAT STANDARD:

A. Todays Date B. Time contact made left blank at this time C. Applicants name

0. Message # 1 E. Control Room F. Initial / New Classification EXAMINERS CUE:

NONE EXAMINERS NOTE:

Part B Contact time must be within 15 minutes of the emergency classification time EXAMINERS NOTE:

Contact time shall be filled in when contact is made with the state. This is noted in Step 17.

COMMENTS:

ST. LUCIE TRMNING DEPT.

ADMINISTRATIVE JPM A-5 PAGE 7

NRC ADM JPM A-5 STEP 9 (Line 3):

CRITICAL STEP

3. :

A.

Crystal River Unit 3 St. Lucie Urt 1 C,

SI. Lucie Unit 2 D

Turkey Point Unit 3 U Turkey Point Unit 1 SAT STANDARD:

C, St. Lucie Unit 2 (St. Lucie Unit 2 is expected, Unit 1 is acceptable, but not UNSAT both marked)

EXAMINERS CUE:

NONE EXAMINERS NOTE:

EPIP Attachment IA step 3 requires only one affected unit be selected (either one can be selected but not both).

COMMENTS:

STEP 10 (Line 4):

CRITICAL STEP 4*

Elny&lassifltioty A U otification of Unusual Event B, U AIe U Site kee Eergeny 0, Q General Energency SAT STANDARD:

A, Unusual Event UNSAT EXAMINERS CUE:

NONE COMMENTS:

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-5 PAGE 8

NRC ADM JPM A-5 STEP 11 (Line 5):

TIME CRITICAL STEP A

Enercy ecIratioi B

ER1ergy 1llQR Ua 1/

SAT STANDARD:

A, Emergency Declaration, current date and time UNSAT EXAMINERS CUE:

NONE EXAMINERS NOTE:

This is the time emergency declaration is made.

EXAMINERS NOTE:

STOP TIME for Time Critical Action This time must less than 15 minutes from the time in step 1. Also START TIME for second critical time.

START TIME:

COMMENTS:

STEP 12 (Line 6):

CRITICAL STEP G,*

A.

EAL iuhr OR

8. L 1

esr:pt SAT STANDARD:

A. EAL Number 21.A (Validated notification from NRC providing information of an aircraft threat).

UNSAT EXAMINERS CUE:

NONE COMMENTS:

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-5 PAGE 9

NRC ADM JPM A-5 STEP 13 (Line 11):

CRITICAL STEP 11,X UTILITY PROTECTIVE AC1 ION RECOMMENDATIONS FOR THE PUBLIC:

A.

II No utility recommended actions at this time.

SAT 8.

LI The utility recommends the following prective actioqis Evacuate Sects Shelter Sects No Action Sec:os U NSAT Evacuate Zones:

OR 0 2 Shelter Zones:

25 510 AND consider issuance of po1assim iodide IKII STANDARD:

A. No utility protective action recommendations for the public.

EXAMINERS CUE:

NONE COMMENTS:

EPIP-08, Off-Site Notifications and Protective Action Recommendations Appendix A NOTIFICATIONS FROM THE AFFECTED CONTROL ROOM SAT STEP 14 (Appendix A, 2.A.2):

State Watch Office Notification A. Prepare the Florida Nuclear Plant Emergency Notification Form UNSAT (form similar to Attachment 1).

2. All other Security and Non-Security Events Prepare the State Notification Form in accordance with Attachment 1A, Directions for Completing the Florida Nuclear Plant Emergency Notification Form.

STANDARD:

Determines this step is N/A EXAMINERS CUE:

NONE COMMENTS:

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-5 PAGE 10

NRC ADM JPM A-5 EPIP-08, Off-Site Notifications and Protective Action Recommendations Appendix A CRITICAL NOTIFICATIONS FROM THE AFFECTED CONTROL ROOM STEP STEP 15 (A 2.B):

Emergency Coordinator (EC) approval.

ATTACHMENT I FLORIDA NUCLEAR PLANT EMERGENCY NOTIFICATION FORM SAT (Line 15) 15 (Do ri Read) EC or RM ApprvaI Sqnature:

Date I

I Time:

UNSAT Mssaqe ReceLved By. aine:__________________________________

Date.

I

/

Time:

STANDARD:

Documents approval including date and time.

EXAMINERS CUE:

NONE COMMENTS:

EPIP-08, Off-Site Notifications and Protective Action Recommendations Appendix A CRITICAL NOTIFICATIONS FROM THE AFFECTED CONTROL ROOM STEP STEP 16 (A 2.C):

Using the State HOT RINGDOWN PHONE, dial 100 SAT STANDARD:

Dials 100 on the State HOT RINGDOWN PHONE.

U NSAT EXAMINERS CUE:

100 has been dialed, the state watch office picks up the phone.

COMMENTS:

ST. LUCIE TRAIMNG DEPT.

ADMINISTRATIVE JPM A-5 PAGE 11

NRC ADM JPM A-5 STEP 17 (A.2.D):

TIME Hold down the button on the handset while talking. This must be CRITICAL done each time you talk. Release the button in order to listen.

STEP When the State Duty Officer answers, announce:

This is St. Lucie Nuclear Plant [as applicable (Unit 1, 2)] with an SAT emergency message. Contact Time is I am standing by to transmit the Florida Nuclear Plant Emergency Notification Form when you are ready to copy.

UNSAT STANDARD:

Communicates message. States the contact time as the current time.

EXAMINERS CUE:

Answer as the State Watch Office EXAMINERS NOTE:

Contact time above is Stop time for time critical step. This time must be less than 15 minutes from the time listed in step 11.

EXAMINERS NOTE:

Upon completion of communication, terminate the task.

COMMENTS:

END OF TASK ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-5 PAGE 12

CANDIDATE COPY (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER)

Directions to the candidate for Administrative JPMS:

I will explain the initial conditions and state the task to be performed. You will be allowed to use any reference needed to complete the task. Ensure you indicate to me when you finish your assigned task by returning the material needed for the task that I provided to you.

Initial Conditions Both Units are at 100% power.

Today at current time, you as the Shift Manager, receives a validated NRC Headquarters phone call to report an Airborne Threat.

The estimated time to site arrival is in 60 minutes.

A track of interest is verified by the NRC due to anomalous flight activity. The Airborne Threat has been validated with the NRC Headquarters Operations Center.

Initiating Cue You are located in Unit 2.

The Unit 2 Unit Supervisor directs you the Shift Manager to:

Perform Step 6.0.4 in accordance with ONP-72.01, Response to Security Events Portions of this JPM are time critical

I4.9 I ATTACHMENT 1 FLORIDA NUCLEAR PLANT EMERGENCY NOTIF1CATtON FORM (Page 1 of 1)

I4-c e*k.

/

,var l3oThL.

8.

QAlerf D. ] General Emergency Date:

/

Time:

OR B. 0 DescrIption:

7.

AddItional Information pr Vodafe:

A.

Q None OR B. Q

Description:

Weather Data:

A. Wind direction from degrees B. Downwind Sectors Affected:

9.

Release Status:

A. U None (Go to Item 11)

8. Q in progress C. Q Has occurred, but stopped (Go to Item 11) 10.

Release Significance Category (t the She Boundari):

A.

0 Under evaluation.

B.

I]

Release within normal operating limits ( 3.5 E-1 Cl/sec noble gas, 4.6 E-5 Cl/sec iodine)

C.

Q Non-Significant Fraction of PAG Range (release is> normal limits and <500 mrem TEDE and 1000 mrem CDE)

D.

[I PAG Range ( 500 mrem TEDE o 1000 mrem CDE)

E.

D Uquid release (no actions required) if form is completed In the Control Room, go to Item 15. If completed in the TSC or EOF, continue with Item 12.

12.

Plant Conditions:

A. Reactor Shutdown? Q Yes Q No B. Core Adequately Cooled? 0 Yes 0 No C. Containment Intact? Q Yes

[INc

0. Core Condition: [I Stable

(] Degrading 13.

Weather Data:

A.

Wind Speed_____ mph B. Stability Class 14.

AddItional Release information: A.

[I N/A OFt Read this statement 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months projected doses as follows:

Proiected Thyroid Dose (CDEI for 1 Hour Proiected Total Do (TEDE1 tori Hour Distance 1 Mile (Site Boundary) 2 MIles 5 Miles 10 Miles B.

mrem C.

mrem 0.

mrern E.

mrem F.

mrem G.

mrem H.

mrern I.

mremn 15.

(Do Not Read) EC or RM Approval Signature:

Messaoe Received By: Name:_____________________________

Items are evaluated for NRC Performance indicators (P1s)

On-line Verification:

[I SWP/DEM 1.

A. 4 HISISADRILL 2.

A.

Date:1 0.

Message Number.

F.

1nitlal / New Classification 3

jf:

A. UCrystalRiverUnhl3

0. []Turl(ey Point Unit 3 4.

Emergency Classification:

A.

C.

5.

A. Emercrency Declaration:

6.

Reason fr Emergency Declaration:

[I DOH/SRC

[I St. Lucle County/Ft Pierce

[I Martin County B. [I THiS IS AN EMERGENCY B.

Contact Time:

C.

Reported by (Name) J*i.Cti O&7 E.

Reported from; 6ntroi Room - [I TSC

[I EOF OR

[I Update Notification B. St. Lucia Unit 1 E. [I Turley Point Unit 4

$Iollflcatlon of Unusual Event

[I Site Area Emergency C.

LucieUnit2 u,-1.,-

B.

I] Emergency Termination:

A.

BEAL Number Q

2

/ 4 fj*

UTILITY PROTECTIVE ACTiON RECOMMENDATiONS FOR THE PUBLIC:

A.

No utility recommended actions at thIs time.

8.

[I The utility recommends the following protective actions:

Evacuate Sectors Shelter Sectors No Action Sectors Evacuate Zones:

OR 02 Shelter Zones:

25 510 AND consider Issuance of potassium Iodide (Kl)

Data:____

Date:

/

Time: Ncv.J Time:

Form PSL-F070 EP1P-08, Off-Site Notifications and Protective Action Recommendations Approval Data: 05/15/09

EXEMPT FROM PUBLIC DISCLOSURE IN ACCORDANCE WITH 10 CFRi2O.

REVISION NO.:

PROCEDURE TITLE:

PROCEDURE NO.:

RESPONSE TO SECURITY EVENTS

.6 of 27 ONP-72.O1 ST. LUCIE PLANT 6.0 OPERATOR ACTIONS INSTRUCTIONS CONTINGENCY ACTIONS VALIDATE the authenticity of any Airborne Threat by calling NRC Headquarters Operations Center. USE the NRC ENS telephone or a commercial line to call 301-816-5100.

2.

If any of the following conditions exist:

Security Department reports ARMED intruders are within the Protected Area fence.

IMMINENT Aircraft Threat (less than 5 minutes arrival time).

An Aircraft has impacted inside the Protected Area Fence.

Then PERFORM the following:

A.

TRIP Unit 1 Reactor.

B.

TRIP Unit 2 Reactor.

C.

DON headset attached to Control Room Security hotline phone.

3.

.f the Aircraft has impacted the plant site, Then REFER TO EDMG-01, Guideline for Responding to Large Area Fire or Explosion Involving Multiple Fire Zones, AND EDMG-02, Major Loss of Plant Control Systems - Initial Response.

4.)

IMPLEMENT Security Checklist in accordance with EPIP-02, Duties and Responsibilities of the Emergency Coordinator.

5.

it the Security Event is a LAND BASED Threat, Then GO TO Appendix A, Response to LAND BASED Threat.

EXEMPT FROM PUBLIC DISCLOSURE IN ACCORDANCE WITH 10 CFR §2.390

EVIS ION NO.:

PROCEDURE TITLE:

PAGE:

28 DUTIES AND RESPONSIBILITIES OF THE f

7 PROCEDURE NO.:

EMERGENCY COORDINATOR

° EPIP-02 ST. LUCIE PLANT 5.2 Security Checklist INITIAL.

Date:

I I

NOTE This is to be used for Actual Events or Credible Threats.

1.

Determine Threat CAUTION e

Plant page announcements must take in to account the current conditions (e.g., severe weather). Ensure the E-Plan announcements do NOT conflict with Security-related announcements.

Movement of plant personnel, including site evacuation, must take into account the current conditions and safety of personnel.

NOTE The Operations Shift Manager Selects the personnel required to remain in the Control Room in order to perform the actions of this procedure.

A.

Imminent Airborne Threat (less than 5 minutes) 1.

Verify the Control Rooms are implementing ONP-72.O1, Appendix B.

Uniti Unit2 B.

Probable Airborne Threat (5 to 30 minutes) 1.

Verify the Control Rooms are implementing ONP-72.01, Appendix C.

Uniti Unit2 Informational Airborne Threat (greater than 30 minutes) 1.

Verify the Control Rooms are implementing ONP-72.01, Appendix D.

Uniti Unit2

REVISION NO.:

PROCEDURE TITLE:

PAGE:

28 DUTIES AND RESPONSIBILITIES OF THE f

7 PROCEDURE NO.:

EMERGENCY COORDINATOR 16 o 4 EPIP-02 ST. LUCIE PLANT 5.2 Security Checklist (continued)

INITIAL 1.

(continued)

D.

Land-Based Threat 1.

Verify the Control Rooms are implementing ONP-72.O1, Appendix A.

Uniti Unit2 V

(3)

Off-Site Notifications NOTE If a threat has been validated via phone call to the NRC Headquarters, the accelerated notification to the NRC is required.

§2 Make an accelerated notification to the NRC in accordance with EPIP-08, Off-site Notifications and Protective Action Recommendations.

B.

V Airborne Threat - Make an abbreviated State Notification in accordance with EPIP-08.

3.

ERO Activation NOTE The PSL Conference Bridge can be used to communicate with the ERO at an alternate location. Refer to the PSL Emergency Response Directory (ERD) for the phone number and password.

A.

Normal business hours -

1.

Delay activation of the Emergency Response Facilities or direct ERO personnel to an alternate location.

2.

Request off-site responders to go to EOF / alternate facility per EPIP-03, Attachment 4.

B.

Off-normal hours - based on site accessibility, consider directing ERO personnel to report to the EOF or alternate location.

REVISION NO,:

PROCEDURE TITLE:

PAGE:

20 OFF-SITE NOTIFICATIONS AND PROTECTIVE 19 f 56 PROCEDURE NO.:

ACTION RECOMMENDATIONS EPIP-08 ST. LUCIE PLANT APPENDIX A NOTIFICATIONS FROM THE AFFECTED CONTROL ROOM (Page 1 of 6)

INITIAL CAUTION

§i Notification of State and local agencies shall be made as soon as practicable within 15 minutes of declaration of an Emergency Class.

. ¶ A new Florida Nuclear Plant Emergency Notification Form shall be completed for all updates.

NOTE

¶ 1. Completion of this checklist requires the following Attachments (all from EPIP-08):

Attachment I Florida Nuclear Plant Emergency Notification Form A Directions for Completing the Florida Nuclear Plant Emergency Notification Form Determination of Protective Action Recommendations (PARs)

NRC Reactor Plant Event Notification Worksheet A Directions for Completing the NRC Reactor Plant Event Notification Worksheet

2. Checklist Part 1 is for State Watch Office notification.

3. Checklist Part 2 is for NRC notification.

4. Completion of this Appendix (A) may be delegated to the Shift Communicator.

II Security Event, Then go to Step 3.A.1.a NRC Notification or N/A.

State Watch Office Notification A.

Prepare the Florida Nuclear Plant Emergency Notification Form (form similar to Attachment 1).

1.

Airborne Threat Abbreviated State Notification Prepare State Notification Form by filling out the following:

Lines I through 6 Linell

/ 2)

&IP(

OR

REVISION NO.:

PROCEDURE TITLE:

PAGE; 20 OFF-SITE NOTIFICATIONS AND PROTECTIVE PROCEDURE NO.:

ACTION RECOMMENDATIONS 20 of 56 EPIP-08 ST. LUCIE PLANT APPENDIX A NOTIFICATIONS FROM THE AFFECTED CONTROL ROOM (Page 2 of 6) 2.

(continued)

INITIAL All other Security and Non-Security Events

- Prepare the State Notification Form in accordance with Attachment 1A, Directions for Completing the Florida Nuclear Plant Emergency Notification Form.

Emergency Coordinator (EC) approval.

NOTE Primary notification method to the State Watch Office (SWO) is to use the Hot Ring Down (HRD) phone.

2.

If the HRD is out-of-service, alternate notification methods are provided in Section E, below.

C.

Using the State HOT RING DOWN (HRD) Phone, dial 100.

D.

Hold down the button on the handset while talking. This must be done each time you talk. Release the button in order to listen.

When the State Duty Officer answers, announce:

uThis is St. Lucie Nuclear Plant [as applicable (Unit 1, 2)] with an emergency message. Contact Time is am standing by to transmit the Florida Nuclear Plant Emergency Notification Form when you are ready to copy.

Allow the Duty Officer to contact St. Lucie County, Martin County and the Bureau of Radiation Control prior to transmitting the information from the notification form. When the parties are on line, provide the information slowly (e.g., in three word intervals) and deliberately, providing time for the information to be written down.

1.

All four off-site agencies have been notified:

A.

Florida Department of Emergency Management (DEM)

B.

Florida Department of Health, Bureau of Radiation Control (DOH I BRC)

C.

St. Lucie County Department of Public Safety / Ft.

Pierce Control D.

Martin County Department of Emergency Services

REVISION NO.:

PROCEDURE TITLE:

PAGE:

20 OFF-SITE NOTIFICATIONS AND PROTECTIVE 38 f

6 PROCEDURE NO.:

ACTION RECOMMENDATIONS

° EPIP-08 ST. LUCIE PLANT

¶8 ATTACHMENT IA DIRECTIONS FOR COMPLETING THE FLORIDA NUCLEAR PLANT EMERGENCY NOTIFICATION FORM (Page 1 of 8)

ITEM ENTRY On-line Verification

- Check the appropriate boxes as the State Watch Office Florida Division of Emergency Management (DEM) requests that the Department of Health Bureau of Radiation Control, St. Lucie County Department of Public Safety and the Martin County Department of Emergency Management get on the line, prior to initiating the notification. All four agencies must be notified (includes Florida DEM) through tje SWO or alternate means.

( 1.

Check appropriate box for drill or actual emergency as the case may be. During exercises, drills, or tests, each message shall be checked THIS IS A DRILL.

2A.

Enter todays date.

2B.

Enter the time (using the official time, normally synchronized with ERDADS) when contact is made with the State Watch Office. For initial notification of classification, this shall be within 15 minutes of the Emergency Declaration time in item 5.

2C.

Enter the name of the person making the notification call.

2D.

Enter the message number beginning with #1 and following sequentially in all facilities (e.g., if the Control Room transmitted two messages the TSC would start with #3).

2E.

Check the box for the facility from which the notification is being made.

2F.

Check the box for Initial I New Classification or Update Notification.

Check the affected site / unit. Do not check more than one unit. For dual unit events such as the approach of a hurricane or loss of off-site power, the fact that the other unit is affected by the condition should be stated in the Additional Information or Update section.

4.

Emergency Classification Check the box corresponding to current accident classification declared.

REVISION NO.:

PROCEDURE TITLE:

PAGE:

20 OFF-SITE NOTIFICATIONS AND PROTECTIVE 39 f 56 PROCEDURE NO.:

ACTION RECOMMENDATIONS EPIP-08 ST. LUCIE PLANT ATTACHMENT IA DIRECTIONS FOR COMPLETING THE FLORIDA NUCLEAR PLANT EMERGENCY NOTIFICATION FORM (Page 2 of 8)

NOTE When opening and closing an event in one notification:

On line 5, both box A and box B apply e

Date(s) and times of declaration and termination are to be indicated 5.

Emergency Declaration or Emergency Termination Enter the date and time when the current emergency classification was (A) declared OR (B) terminated.

6.

Reason for Emergency Declaration A.

Enter the Emergency Action Level (EAL) number as given in EPIP-Ol, EAL Descriptions for Florida Nuclear Plant Emergency Notification Form (St. Lucie Nuclear Plant).

OR B.

Enter wording like that found in the EAL information in EPIP-Ol, Classification Of Emergencies. Wording should be brief yet descriptive enough for the off-site agencies to gain an understanding of the event. It should be clear from the incident description which EAL has necessitated the emergency declaration. Wording should be as non-technical as possible with no acronyms or abbreviations. This information should remain the same throughout update messages, unless there is a classification change.

7.

Additional Information or Update Check A (None) if there is no information or B to provide additional information/clarification or reason for the update, for example:

A condition is occurring/occurred that would otherwise have resulted in the declaration of the same or lesser emergency classification.

Identify that both units are affected by the condition, e.g., due to a loss of off-site power or hurricane warning, etc.

Change Protective Action Recommendations (PARs)

Change in radiological conditions Change in equipment status Injuries Termination of event

REVISION NO.:

PROCEDURE TITLE:

PAGE:

20 OFF-SITE NOTIFICATIONS AND PROTECTIVE PROCEDURE NO.:

ACTION RECOMMENDATIONS 16 of 56 EPIP-08 ST. LUCIE PLANT 5.1 State and County Notification (continued) 3.

B.

(continued) 2.

If one Unit is in a classified event and the other Unit enters into a more severe event in which a higher Emergency Class would apply, Then a new classification shall be declared and promptly, within the regulatory time limits, issued to the State, Counties and the NRC.

Abbreviated Notification Due to an Airborne Threat NOTE Concurrence for use of an abbreviated notification in response to an on-site airborne threat situation has been obtained from State and county officials.

1.

If the site is under a potential or actual airborne threat, Then complete lines I through 6 and line 11 of the State Notification Form, obtain approval from the Emergency Coordinator or Recovery Manager and transmit the abbreviated notification to the State Watch Office.

END OF SECTION 5.1

REVISION NO.:

16 PROCEDURE NO.:

EPIP-Ol PROCEDURE TITLE:

CLASSIFICATION OF EMERGENCIES ST. LUC A goal of fifteen (15) minutes should be used for assessing and classifying an emergency once indications (Emergency Action Levels (EALs)) are available to Control Room Operators that an Initiating Condition (IC) has been met andlor exceeded.

This goal should allow time for determination of indications (leak rate, etc.) and detailed review of Attachment 1, Emergency Classification Table.

1.

¶8 For EALs that are time-based, a prescribed assessment period is provided.

It is to be acknowledged that the condition described in the EAL has been met if the stated time period has elapsed.

There is not an additional 15 minute assessment period.

Example EALs:

No main or auxiliary feedwater flow available for greater than 15 minutes when required for heat removal and Steam Generator levels are less than 40% wide range OR Uncontrolled fire within the Power Block lasting more than 10 minutes OR LOCA with initially successful ECCS and subsequent failure of containment heat removal systems for greater than 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months NOTE Initiating Conditions / Emergency Action Levels are applicable to jj modes unless otherwise indicated.

The Emergency Coordinator should not wait until the applicable time (as stated in the Initiating Condition I Emergency Action Level) has elapsed, but should declare the event as soon as it is determined that the condition has exceeded, or will likely exceed, the applicable time.

5.2 Classifying the Event

ML15141A467

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