Text

Final as Administered Administrative Jpms for the D.C. Cook Examination - Nov/Dec 2002
	ML030700476
Person / Time
Site:	Cook
Issue date:	01/02/2003
From:	Lanksbury R; NRC/RGN-III/DRS/OLB
To:	Bakken A; American Electric Power Co
References
	50-315/02-301, 50-316/02-301 50-315/02-301, 50-316/02-301
	Download: ML030700476 (111)
	v • d • e

FINAL AS-ADMINISTERED ADMINISTRATIVE JPMS FOR THE D. C. COOK EXAMINATION - NOVIDEC 2002

!I . . . ,7 TI*TLE Determine Ultimate Heat Sink Temperature REVISION 0 PROGRAM INRC License Exam TIME 15 Minutes DEVELOPING Name: S. Pettinger 10/23/2002 INSTRUCTOR: Signature:

OPRATIONS REVIEW: Name: ST. Werk 10/23/2002 Signature:

Page 1 of 3

IReferences 02-OHP-4030-STP-030 Daily and Shiftly Surveillance Checks Data Sheet 5 pages 81 & 82 OP-2-5119A, Flow Diagram Circulating Water, Priming System & Screen Wash (P&ID)

Task: STP0390201 Perform Shiftly Surveillance Checks for Modes 5 & 6 K/A CROSS

REFERENCE:

2.1.7 K/A IMPORTANCE: RO 3.7 SRO 4.4 Evaluation Setting Simulator

[Handouts I Task Briefing for N02-Ala 02-OHP-4030-STP-030 Daily and Shiftly Surveillance Checks Data Sheet 5 pages 81 & 82 If requested then provide candidate with OP-2-5119A, CW System (P&ID)

Attachments None Simulator Setup Reset to Mode 6 IC 998 Close CW Condenser Inlet and Outlet valves:

"* A Condenser South 2-WMO-103 & 104

"* C Condenser North 2-WMO-301 & 302 Shutdown #21 &#22 CW Pumps (2 CW Pumps left running)

Page 2 of 3

STask Objectives/Standards The Candidate correctly identifies that the South Waterbox for "A" condenser and the North Waterbox for the "C" condenser are Isolated and does not use the associated temperatures. The Candidate Identifies that CW Temperature is > 76.8 F And Fuel Movement must be stopped until the reactor has been shutdown for >148 hours.

Task Briefing Given the following:

"* Unit 2 is in Mode 6.

"* The reactor was shutdown 130 hours0.0015 days 0.0361 hours 2.149471e-4 weeks 4.9465e-5 months ago.

"* Fuel Movement is in Progress.

MTI reports CW temperature transmitters are not functioning properly, due to a power supply problem, therefore SG-21, Circ Water Temp Recorder and PPC address U0200 are Out Of Service (OOS).

The Unit Supervisor diredts you to perform step 14.2 of 02-OHP-4030-STP-030 Daily and Shiftly Surveillance Checks Data Sheet 5 (pages 81 & 82) and to ensure all Acceptance Criteria are met for the current Circulating Water System configuration.

An AEO has already recorded the following temperature readings from the Unit 2 CW Inlets:

CondenA-P_ CXondenser WTX-106 = 71.8 WTX-206 = 77.2 WTX-306 = 77.1 WTX-107 = 71.8 WTX-207 = 77.1 WTX-307 = 77.0 WTX-108 = 72.2 WTX-208 77.3 WTX-308 = 77.0 WTX-102 = 77.1 WTX-202 = 76.9 WTX-302 = 71.2 WTX-103 = 77.4 WTX-203 776.9 WTX-303 = 70.9 WTX-104 = 76.8 WTX-204 = 77.0 WTX-304 = 71.3 Temperature readings were obtained using Instrument ID CNP-147, Make/Model ELU*EL2175 with Calibration Current (Last Cal. Performed on 05/07/2002)

Page 3 of 3

COURSE NUMBER N02-Ala REVISION: 0 AN IL: Determine Ultimate Heat Sink Temperature I Continuous AI 02-OHY-4030-STP.030 I Rev. 39 I Page 81 of 145 DAILY AND SHIFTLY SURVEILLANCE CHECKS General CUES7 Data Sheet 5 Shift Surveillance Checks Modes 5, 6 and Defuelede Pages:

1 70 -83 I If requested then provide OP-2-5119A, CW System (P&ID)

Instrument IIValue Title & No. 00-08 1 08-16Value 1 Value 16-24 1 Acceptance Criterion

- The temperature monitoring in Step 14.0 is N/A when TS 3.9.3 does not apply, i.e., after the NOTE: 148 hour0.00171 days 0.0411 hours 2.44709e-4 weeks 5.6314e-5 months decay time has been met or when not moving irradiated fuel in the reactor vessel. This monitoring is to validate temperature limits in TS Bases.

Decay Times - at least 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months from September 15 through June 8", or at least 148 hours0.00171 days 0.0411 hours 2.44709e-4 weeks 5.6314e-5 months from June 9* through September 14. ('S 3.9.3)

The June dates were changed to be more conservative than the TS applicability to support the TS 3/4.9.3 Bases discussion to ensure sufficient decay time for June outages.

+Circulating Water Temperature from either unit may be used, indicate unit used.

14.0 14.1 Circ Wtr Temp-: IS 3.9.3"* for Decay T"ne: C4

Take reading from SG-21 U10 U20 S 141 Lesthanor Point 1, Cite Water Temp F OF Fp ZFpt Recorder. Point 1. (i.e., 77.8 +/- 3.2"F Step is N/A due to Temperature Indicator Problems IF recorder is energized and E estnoent uncertainty) the printer is inoperable, OR THEN take readings from Step 14.2 - 0less then or THENt ae r g f0 equal to 76.8 F the PPC, U0200. (i.e., 77.8 +/- V*Finsurment unceta-tuty for M&TE

- OR - calhbrated Fluke-52 with a C8 12"probe, or equivaleut).

14.2 IF Circ Water Temp is greater than or equal to 721F OR V theOUnt is in MODE 6 C8 measurement cannot be obtained in Step 14.1 OR a more with movemuent of irradiated accurate value is desired, THEN obtain an M&TE calibrated fuel in the vessel in progress temperature measurement instrument and perform the following: between September 15 and June 8* with:

Record instrument ID Instrument make/model:

4

-AND---

4 I Enters Instrument ID & Make/Model from briefing Sheet Current calibration Y/N_ _ Cir Wtr Temp 4 -- Marks "Y" for Calibration is Current Take one inlet temperature measurement of each Condenser in Step 14.1 ) OR

> 76.8F (using service using the M&TE calibrated instrument with +/-I*F Step 14.2) uncertainty and calculate the average.

Ul 0 U2 r T o ---v-env- of

-t-Checks "U2" Box Condenser A Cire Water Inlet:' irradiated u until either of the following conditions are met: - CT:Checks one of these boxes and Check box for inlet measured:

Cire Wi Temp.is O WTX-106 or C4 O WTX-107 or sep 14.1 ) OR *76

-enters corresponding temperature.

O WTX-108 or O WTX-102 or WTX-102 = 771

DecayTime is greater o WTX-103 or than 148 hrs. WTX-103 = 774 o WTX-104 J W7X-104 = 76.8 Page 1 of 2 Revision 0

COURSE NUMBER, N02-Ala REVISION: 0 AND TTLE: Determine Ultimate Heat Sink Temperature Continuous 02-OHP-4030-STp-030 Rev. 39 P e 82 of 145 DAILY AND SHIFTLY SURVEILLANCE CHECKS Data Sheet Shift Surveillance Checks Modes 5, 6 and Defueled Pa8es: ]

70-83 CT: Checks one of these boxes and Instrument Title & No. 00-08 08-16 16-24 Aron I..enters corresponding temperature.

Value Value Value 14.0 U1IO U2 WTX-206 = 772 Cont Condenser B Cire Water Inlet:,

W7X-207= 771 Check box for inlet measur e o WVX-206 or WTX-208 = 773 o WTX-207 or WTX-202 = 76.9 O WTX-208 or OF I Ot F

Q WTX-202 or C4 WTX-203 = 76.9 O WTX-203 or o WTX-204 WTX-204 = 770 Condenser C Circ Water Inlet:*

CT: Checks one of these boxes and Check box for inlet ueasured:

O WTX-306 or "

enters corresponding temperature.

0 WTX-307 or J p -F 0 F WTX-306 = 771 1OWTX-302 or WTX-307= 770 Q WTX-303 or 0 WTX-304 WTX-308 = 770 (Cond. A+B+C IF) / 3 IF 'F - CT: Enters average of the three temperatures entered in boxes above in first Box (value should be between 76.9 °F - 77.3 oF) 15.0 Record current MODE*

Per Technical Specification Table 1.1, Operational Modes:

CT: Operator Informs SRO that the Temperature is greater than 76.8 oF and fuel movement must be stopped since the reactor has been shutdown less than 148 hours0.00171 days 0.0411 hours 2.44709e-4 weeks 5.6314e-5 months . Per Tech Spec 3.9.3 Reports task completed.

JPM IS COMPLETE.

Page 2 of 2 Revision 0

COURSE NUMBER N02-Ala REVISION: 0 AND TITLE: Determine Ultimate Heat Sink Temperature B Condenser South Inlet Temp WTX-206 77.2 T P "B ,,,,,-, , Condenser South B Condenser South Inlet Temp WTX-207 WTX-208 77.1 77.3 I L B Condenser North Inlet Temp WTX-202 76.9 SLB Condenser North Inlet Temp WTX-203 76.9

_______________________________ _-_.. B Condenser North Inlet Temp WTX-204 77.0 All Temperatures are valid DP DP '" " i B" EP_4'

""A I TI T IL T~ T 43 1T T) T S.

.x . . . . ..... .. . .. . . *-" . ....

c.,,, i; * ... '.. .,. 'ir*

____ __ __ __ __ __ OW __ N nfT9__

L __ __ __ _ D A (rnntia~n*=r qr%"th Inlof÷ Tg-ar \A/TY_4 t3* "74 Q \^/TY_'*n*

C !nsith Inkt Thmn 77 SotIInlet A Conense I WTX-107 - 71.8 (CCnndAnr CondenserqNorth Inlet Tomp WT-304 771.

A Condenser South Inlet Temp WTX-107 71.8 C Condenser South Inlet Temp WTX-307 77.0 A Condenser South Inlet Temp WTX-108 72.2 C Condenser South Inlet Temp WTX-308 77.0 A Condenser North Inlet Temp WTX-102 77.1 C Condenser North Inlet Temp WTX-302 71.2 A Condenser North Inlet Temp WTX-103 77.4 C Condenser North Inlet Temp WTX-303 70.9 A Condenser North Inlet Temp .WTX-1 04 .76.8 C Condenser North Inlet Temnp WTX-304 -71.3 North Temperatures are valid South Temperatures are valid Page 1 of 1 Revision 0

Task Briefing Given the following:

"* Unit 2 is in Mode 6.

"* The reactor was shutdown 130 hours0.0015 days 0.0361 hours 2.149471e-4 weeks 4.9465e-5 months ago.

"* Fuel Movement is in Progress.

MTI reports CW temperature transmitters are not functioning properly, due to a power supply problem, therefore SG-21, Circ Water Temp Recorder and PPC address U0200 are Out Of Service (OOS).

The Unit Supervisor directs you to perform step 14.2 of 02-OHP-4030-STP-030 Daily and Shiftly Surveillance Checks Data Sheet 5 (pages 81 & 82) and to ensure all Acceptance Criteria are met for the current Circulating Water System configuration.

An AEO has already recorded the following temperature readings from the Unit 2 CW Inlets:

Condens=R77 CondefLne_ C WTX-106 = 71.8 WTX-206 = 77.2 WTX-306 = 77.1 WTX-107 =.71.8 WTX-207 = 77.1 WTX-307 = 77.0 WTX-108 = 72.2 WTX-208 77.3 WTX-308 = 77.0 WTX-102 = 77.1 WTX-202 = 76.9 WTX-302 = 71.2 WTX-103 = 77.4 WTX-203 776.9 WTX-303 = 70.9 WTX-104 = 76.8 WTX-204 =77.0 WTX-304 = 71.3 Temperature readings were obtained using Instrument ID CNP-147, Make/Model ELU.KE/2I5 with Calibration Current (Last Cal. Performed on 05/07/2002)

N02-Ala.doc Page I of 1

N0,oA.b, ]1 TITLE Setup SR & Audio Count Rate for Fuel REVISION 0 "Movement

'PROGRAM- NRC License Exam TIME. 15 Minutes Name: S. Pettinger 10/23/2002 Signature:

2J OPERATIONS REVIEW.: Name: /T. Werk 10/23/2002 Signature:

Page 1 of 3

References 02-OHP-4021-013-005, Visual Audio Count Rate Channel Task: 0130030101: Setup the Audio Count Rate Channel for Mode 6 operation 0130040101: Set up the Scaler Timer for 1/M plotting.

K/A CROSS

REFERENCE:

2.2.30 K/A IMPORTANCE: RO 3.5 Evaluation Setting Simulator IIHandouts Task Briefing for N02-A1 b Field Copy of 02-OHP-4021-013-005, Visual Audio Count Rate Channel ILAttachments None Simulator Setup Mode 6 conditions with snap # IC 998 Set Channel selector to OFF Set Sampling Selector to SEC on Display Side and COUNT on the Preset side Set thumbwheels to 03000 Set Audio Multiplier to 1000 Page 2 of 3

COURSE NUMBER N02-Al b - Setup SR & Audio Count Rate for Fuel REVISION: 0 AND TITLE: MovementI STask Objectives/Standards When directed by the Unit Supervisor, Setup SR & Audio Count Rate for Fuel Movement observing all applicable precautions and limitations and procedure steps.

Task Briefing MTI has just finished repairs on the Scaler Timer & Audio Count Rate Channel.

The US directs you to setup SR & Audio Count Rate for Fuel Movement.

"* Source Range Channel N32 should be the selected channel for audio indication.

"* The Audio Count rate should be setup to beep approximately once every 5 seconds.

Page 3 of 3

COURSE NUMBER N02-Alb -Setup SR & Audio Count Rate for Fuel Movement REVISION: 0 AND TITLE:

Reference 02-0HP-4021-013-005 Rev. 6 Page 4 of 16 VISUAL AUDIO COUNT RATE CHANNEL (NIS)

General CUES7 Attachment I Setup of Audio Count Rate Channel Pages:

4-5 1 PURPOSE AND SCOPE 1-1 This attachment provides direction for setting up Audio Count Rate Channel. Upon completion there will be visual/audible indication in the control room and audible indication in containment.

2 PREREQUISITES 2.1 None.

3 PRECAUTIONS AND LIMITATIONS 3.1 Source assembly movement during core alterations may reduce audible count rate suddenly. Adjustment of audio multiplier setting may be needed to maintain audio count rate signal.

4 DETAILS 4.1 Place scaler timer POWER switch in ON position.

-Operator checks the scaler timer "POWER" toggle switch in the "UP" position 4.2 Check the following lights are lit on AUDIO COUNT RATE CHANNEL drawer:

Operator checks lights lit

"* AUDIO POWER ON

"* SCALER POWER ON 4.3 Place CHANNEL SELECTOR switch to desired source range channel.

I CT: Operator places Channel Selector switch in "SRN32" position 4.4 Place SAMPLING MODE selector switch in the following positions:

COUNT position on DISPLAY side CT: Operator places sampling mode switch in "COUNT/SEC" position

SEC position on PRESET side 4.5 Volume control may be adjusted during sampling to any position that

-Operator checks "VOLUME" switch in any position results in a comfortable volume for the audible count rate.

Page 1 of 2 Revision 0

COURSE NUMBER N02-Alb - Setup SR & Audio Count Rate for Fuel Movement REVISION: 0 AND TITLE:,.

NOTE In the current configuration, the thumbwheels enter time values to the nearest tenth of a second. CUE: If asked, as US request time value of 60 seconds.

4.6 Position thumbwheels to 00600 or other value as desired. __

CT: Operator sets thumbwheels to 00600 4.7 Place SAMPLING MODE toggle switch in AUTO.

4.8 Press the following pushbuttons: Operator checks sampling mode toggle switch in "AUTO" position 4.8.1 STOP 4.8.2 RESET Operator depresses the pushbuttons 4.8.3 START CT: the "START" is the critical portion of this step 4.9 Check GATE light is lit.

Operator checks gate light lit 0 IF GATE light is NOT lit, THEN notify I&C.

4.10 Place AUDIO MULTIPLIER switch in a position that results in a distinguishable gap between counts. (This step N/A if source range Operator adjusts audio multiplier switch to produce a detectors are deenergized) distinguishable gap in audio output of about 5 seconds 4.11 Verify count rate indication is audible in the following [Ref. 7.2.1a]:

Operator determines Containment Counts are audible by

Control Room (This step N/A if source range detectors are requesting report from operator in Containment.

deenergized)

Containment (Mode 6 only) CUE : A Beeping sound is heard in Containment.

Reports task completed.

JPM IS COMPLETE.

Page 2 of 2 Revision 0

Task Briefing MTI has just finished repairs on the Scaler Timer & Audio Count Rate Channel.

The US directs you to setup SR & Audio Count Rate for Fuel Movement.

"* Source Range Channel N32 should be the selected channel for audio indication.

". The Audio Count rate should be setup to beep approximately once every 5 seconds.

N02-Alb.doc Page 1 of 1

JN0oA2 TITLE Determine the Requirements for Isolating a PAC REVISION 0 Cooler NESW Leak PROGRAM NRC License Exam TIM 15 Minutes DAT3100 DEVELOPING Name: S.Pettinger 10/23/2002 INSTRUCTOR: Signature:

OPERATiONSýS REVIEW: Name: T. Werk 10123/2002 Signature:

Page 1 of 2

N02-A2 - Determine the Requirements for REVISION: 00 COURSE NUMBER AND TITLE: Isolating a PAC Cooler NESW Leak References OP-1-5I 14-84 NESW Flow Diagram (P&ID)

K/A CROSS

REFERENCE:

2.1.24 K/A IMPORTANCE: SRO 3.1 RO 2.8 Evaluation Setting Classroom I Simulator Handouts Task Briefing for N02-A2 OP-1-5114-84 NESW Flow Diagram (P&ID)

Attachments None Simulator Setup N/A Task Objectives/Standards The candidate identifies the valves that must be closed to isolate the safety valve SV-88.

Task Briefing The Unit AEO reports that the Unit 1 NESW Supply to the Plant Air Compressor (PAC) Aftercooler Safety Valve SV-88 has been broken off and NESW water is spraying out. The Unit Supervisor directs you to identify the valves closest to the leak that will isolate the safety valve (leak) from the rest of the NESW system.

Page 2 of 2

COURSE NUMBER .N02-A2 - Determine the Requirements for Isolating a PAC Cooler NESW Leak REVISION: 0 AND TITLE: ir Page 1 of 2

COURSE NUMBER N02-A2 - Determine the Requirements for Isolating a PAC Cooler NESW Leak REVISION: 0 AND TITLE:

The candidate should locate OP-1-5114-84 Flow Diagram for Non Essential Service Water Unit No. 1 CUE: Provide copy of OP-1-5114-84 when candidate correctly locates micro fiche.

Locates SV-88 (@L-1)

Determines that the AEO must isolate the following Valves:

CT: NSW-1 19 - Strainer Isolation Valve

CT: NSW-120 - Strainer Isolation Valve

CT: NSW-405 - NESW from PAC Strainer to Chem Room A/C

CT: NSW-1 26- Air After Cooler outlet

CT: NSW-127 - 1 st Stage Cooler Outlet Isolation

NSW-129 - 1st Stage Cooler Outlet Bypass

"* CT: NSW-130 - 2 nd Stage Cooler Outlet Isolation

"* NSW-1 32 - 2nd Stage Cooler Outlet Bypass

"* CT: NSW-133 - Oil Cooler Outlet Isolation

"* NSW-135 - Oil Cooler Outlet Bypass Reports task completed.

JPM IS COMPLETE Page 2 of 2

Task Briefing The Unit AEO reports that the Unit 1 NESW Supply to the Plant Air Compressor (PAC) Aftercooler Safety Valve SV-88 has been broken off and NESW water is spraying out.

The Unit Supervisor directs you to identify the valves closest to the leak that will isolate the safety valve (leak) from the rest of the NESW system.

N02-A2.doc Page 1 of 1

iN02:3:]

TITLE Terminate a Liquid Release 0 PR[OGRM NRC License Exam 25 Minutes Name:

10/23/2002 DEVELOPING S. Pettinger

,INSTRUCTOR: Signature: SI ,*=

OPERATIONS 10/23/2002 REVIEW: Name: T. Werk Signature:

Page 1 of 3

References I 12-OHP-4021-006-004, Transferring Distillate From Monitor Tanks 12-OH P-4024.139 #16 Annunciator Response Task: 0060230104 Respond to an automatic termination of a liquid release.

0060170104 Release a Monitor Tank to the Circulating Water System.

K/A CROSS

REFERENCE:

2.3.11 K/A IMPORTANCE: SRO 3.2 RO 2.7 LEvaluation Setting In-Plant (RCA) 581' Elevation Auxiliary Building 11Handouts Task Briefing Pages 52 & 53 of 12-OHP-4024.139 #16 Annunciator Response Evaluator - Enter Release Start TIME (1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ago) on:

"* Page 24 (Step 4.12) of 12-OHP-4021-006-004, Attachment 3

"* Page 39 (Record Release Start time) of 12-OHP-4021-006-004, Data Sheet I Prepared Release Package:

12-OHP-4021-006-004, Transferring Distillate From Monitor Tanks:

Attachment 3, Monitor Tank Release To The Circ. Water System Data Sheets 1, Monitor Tank Release Permit Lineup'Sheet 3, Monitor Tank No. 3 Recirc Valve Lineup Line up Sheet 7, Monitor Tank No. 3 Release Valve Lineup Liquid Release Worksheet (1)

I[Attachments None Simulator Setup N/A Page 2 of 3

ITask Objectives/Standards I Terminates liquid release in accordance with:

"* 12-OHP-4024.139 #16 Annunciator Response

"* 12-OHP-4021-006-004, Attachment 3

,EVALUATOR SETUP Enter Release Start TIME (1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ago) on:

"* Page 24 (Step 4.12) of 12-OHP-4021-006-004, Attachment 3

"* Page 39 (Record Release Start time) of 12-OHP-4021-006-004, Data Sheet I I"Task Briefing A Liquid release from Monitor Tank #.3 is in progress. The release is being directed to U2 Circ Water Discharge using the South Monitor Tank Pump. You have been given a turnover and the associated release package for completion once the release is completed. The current level in Monitor Tank # 3 is 43% and lowering.

The Control Room informs you that RRS-1 001 has just went into High Radiation alarm.

They request that you verify/perform actions per 12-OHP-4024.139 #16 Annunciator Response procedure.

Page 3 of 3

COURSE NUMBER N02"A3 REVISION: 0 AND TITLE: Terminate a Liquid Release 12-OHP-4024-139 Level of Use: REFERENCE #16 General CUES1 ANNUNCIATOR #139 RESPONSE: RADIATION RADIOACTIVE LIQUID EFFLUENT INIT-ATING DEVICE(S) NOMINAL AEP_ Alias SETPOINT CHANNEL ID:

RRS- 1001 High Radiation No cues on this page - operator actions start on next page.

(Channel 1 Monitor) Channel Failure RRR-1002 Low sample or effluent flow RRS-1000 (Channel Mnnior 2 Monitor) (ifAarmSet initialized) by RP Monitor Alarm I RRA-1003 Channel Failure (Area Monitor) High Radiation RFS-1010 High flow (90% increasing)

(Sample Flow) Low nlow (207 decreasing) i I PROBABLE CAUSE(S):

1.1 RED:

Movement of radioactive material in specified area.

Low effluent flow.

Highilow sample flow.

Channel failure.

1.2 WHITE

Any channel is in Calibrate, Maintenance, or Check Source staris.

Any channel is in Standby or Flush mode.

Any monitor is in local control.

Any channel is in POLL OFF at RMS CT.

Any channel is in Fail Extenal, Fail High, or Fail Low status.

Any monitor lails communications progranm or Unit's CT is Off-Line.

Sample flow is out of normal range by flow fail sensor.

Page 52 of 95 Rev. 0lýa Page 1 of 4

COURSE NUMBER N02-A3 REVISION: 0 AND TITLE:

Terminate a Liquid Release 12-QH1'-4024-139

16 Candidate may approach DAM and verify that the Red Light on top

". (31. TCACTION(S):

is flashing.

i, I i r \V.Cf Pump nd M nfir Tank P.ni:

I Alarm nn RPS-100kCY ,rip-s cdoyed RRV-25-, CUE: 12-RRV-285, red light lit and green light is dark Ch-an,:! 1ail ure ,on RRS-1001. RRIO-10C.2.

!iih.ow Fl~How on RFS- 1010.

CT Student should simulate taking switch for 12-RRV-285 to the 3 OPERAT['OR ACT ION(S):

Close position.

CUE: "Switch clicks into place, red light is dark and green light is lit'

ý. I 3 1 ciii.' cunilcO 110 'millie a.: on, (Y. 4 Candidate should place Control Switch for South Monitor Tank 12 IF Hieih Alarm e,:',ts on RS-!001. THEN 'i perform thu folivo inn: Pump in Trip

a. V:rif\ Tank 1wins dichiroe has hoern sanphe and apprveIwd tor CUE: "Switch clicks into place, red light is dark and green light is lit

. vif knbiq.,g dischanret c ,! beis t ' illed.

"ChecksData Sheet 1 for Correct Tank Number and Approvals.

c. Netify R" AND ruest Cheisk'y sampe Reviews Lineup Sheet 7 to ensure tank is not being filled.

d. 11: ntes. ar:., THEN re!.-leat process. CUE: "Valves are in positions as indicated by lineup sheet 7"

'.1.3 IF; Chian Failur ei eu ists. IITENisoat tansk.

(Evaluator Note: Candidate may want to physically check

.. ! 1"11:npFjou, ifi- .!.Lo-,. 1THEN rn-cJU:;.-., fl::.-;" to vifii 1i :v~ ,*.IS ,l 12-CS-267-3 CVCS Monitor Tank 12-TK-14-3 Inlet Valve instead 1 1-- 021 .1- 00-(l4. 'imr.ufcrrjn.., Dis:illate fr-o Monmtor Tanks. of Lineup Sheet 7. This valve is a CHAIN operated valve located by the #3 Monitor Tank.)

CUE: (If Required) 12-CS-267-3 is closed

.. tId-, ail'.d cha:reii AND refer to TS Tables . adi 23.3-66r "TS ..1 6. (It afnropriae Action Snaleini.

2 "Notify RP & request another tank sample from Chemistry.

. ut tOste aflected channel(s) to Normal, CUE: "Control Room has notified Radiation Protection and IF chunncl is in,-oai]. THIEN refter to 21 1-40Yj--11S-Wl,.

t 5{*, .'1t-1'11a e Sw vlfanc clth for appropr.oi:o" :icli*,s an',

Chemistry. The Unit Supervisor requests that you close out release 411' 1,.*!;u e paperwork Attachment 3, Steps 4.13 through 4.16."

Page 53 of' 95 R,,v. l0a Page 2 of 4

COURSE NUMBER N02-A3 REVISION: 0 AND TITLE: . :Terminate a Liquid Release Reference 12-OHP-4021-006-004 1 Rev. 25 1 Page 25 of 58 Transferring Distillate From Monitor Tanks This section is N/A

/

L Attachment 3 Monitor Tank Release MONITOR TANK NO.

To The Circ Water System.

RELEASE N Pages:

14-28 4.13 IF release monitor trips off due to external failure, THEN perform following:

4.13.1 Press ALM ACK button on front of RRS-1000 DAM to enable start of release with low sample flow.

4.13.2 Verify amber FAILURE light on RRS-1000 DAM - NOT LIT.

4.13.3 Open 12-RRV-284, Liquid Waste Disposal Effluent Header Control Valve.

4.13.4 Restart Monitor Tank Pump.

4.13.5 Perform Steps 4.10.6, 4.10.7. 4.11.3 through 4.12.

Notifies Radiation Protection INOTE: In order to open 12-RRV-285 after high alarm on RRS-1001, monitor mu CUE: "Radiation Protection has been notified" be flushed to reduce radioactivity below alarm point.

4.14 IF 12-RRV-285 closes because of high radiation detect ,-1001.

THEN perform the following: Obtains seal and closes 12-WD-166. Places seal on the valve.

4.14.1 Notify Radiation Protection.

4.14.2 Close AND seal 12-WD-166, Rad Liquid Waste Disposal Effluent CUE: Handwheel has stopped moving.

Control Valve 12-RRV-285 Inlet Valve.

CUE: Independent Verification is complete 4.14.3 Close the applicable valve:

a. 1-RRV-287

b. 2-RRV-286 - CT Student should simulate taking switch for 2-RRV-286 to the 4.14.4 N/A step 4.15 of this attachment.

Close position.

CUE: "Switch clicks into place, red light is dark and green light is lit" 4.15 IF desired, THEN request Control Room perform the following WHEN at approximately 5 % prior to expected release termination level:

4.15.1 Print release history of RFS-1010 and RFA-1011. N/A - This will be performed in step 4.16.3 4.15,2 Place RFS-1010 and RFA-1011 in POLL OFF at RMS-CT.

Page 3 of 4

COURSE NUMBER N02-A3 REVISION: 0 AND TITLE: . Terminate a Liquid Release Transferring Distillate From Monitor Tanks Monitor Tank Release To The Cire Water Pages:

System. 14-28 MONITOR TANK NO. _ RELEASE NO, Monitor tank pump should have been stopped earlier, if not:

4.16 WHEN desired tank level is reached OR Monitor Tank pump has tripped CUE: "Red light goes out and green light illuminates" on low level or high rad, THEN perform the following:

When Candidate places South Monitor Tank Pump switch to Stop.

4.16.1 Verify Monitor Tank Pump - STOPPED.

4.16.2 Verify following valves - CLOSED: RRV-285 and 2-RRV-286 should already be closed with green

a. 12-RRV-285 lights illuminated and red lights out.

b. One of the following: (N/A valve not used)

"* I-RRV-287 Student may check 1-RRV-287 closed.

" 2-RRV-286 CUE: "Red light out and green light lit."

4.16.3 Request Control Room perform the following:

a. IF available, THEN print release averages for the fowg Candidate should have Control Room perform steps 4.16.3 RRS-1000 channels to attach to Data Sheet 1: CUE: "The Control room has printed the release history. RFS-1010

RRS-1001 & RFA-1011 have been placed in POLL OFF at RMS-CT."

RFS-1010 (N/A if already performed)

RFA-1011 (N/A if already performed)

b. Place RFS-1010 and RFA-1011 in POLL OFF at RMS-CT -Places South Monitor Tank Pump Mode Selector Switch to Recirc (N/A if already performed).

CUE: "Switch is in Recirc and Independent Verification is complete."

4.16.4 Place Monitor Tank Pump Mode Selector Switch used for release to - RECIRC. "Presses ALM ACK button on DAM 4.16.5 Press ALM ACK button on front of DAM to reset local flashing CUE: "Blue Light has stopped flashing and Independent Verification blue light.

is complete.

4.16.6 Mark flow recorder 12-MR-57 with time and date of release completion.

- Marks Flow Recorder- CUE: Recorder is marked and Independent 4.16.7 Record the following information:

Verification is complete.

Time: Date:

Enters Time & Date & Level - CUE: "Monitor Tank 3 level is 42%

// oeease Independent Verification is complete."

Final Tank Volume: %

4.16.8 Close AND seal 12-WD-166 (N/A if previously performed).

- N/A- Already Performed Reports task completed.

JPM IS COMPLETE.

Page 4 of 4

Task Briefing A Liquid release from Monitor Tank # 3 is in progress. The release is being directed to U2 Circ Water Discharge using the South Monitor Tank Pump. You have been given a turnover and the associated release package for completion once the release is completed.

The current level in Monitor Tank # 3 is 43% and lowering.

The Control Room informs you that RRS-1 001 has just went into High Radiation alarm. They request that you verify/perform actions per 12-OHP-4024.139 #16 Annunciator Response procedure.

N02-A3.doc Page 1 of 1

"L N02'=A41r TITLE Complete EMD-32a Nuclear Plant Notification Form REVISION . 0 PROGRAM NRC License Exam TIME 10 Minutes Revision 0: Initial Issue DEVELOPING Name: 10/23/2002 Dale Tidwell INSTRUCTOR: Signature:

SOPERATIONS REVIEW: Name:

Signature:

JjT.Werk 10/23/2002 V

Page 1 of 3

COURSE NUMBER N02.A4 REVISION: 0 AND TITLE: Complete EMD-32a Nuclear Plant Event Notification References Procedure: PMP-2080-EPP-107 revision 16, Notification Task: EPP 0030701 Perform Initial Offsite Notification K/A CROSS

REFERENCE:

2.4.39 K/A IMPORTANCE: SRO 3.1 RO 3.3 I.Evaluation Setting Classroom 1"Handouts Task Briefing & MIDAS Summary EMD-32a Nuclear Plant Event Notification (blank form)

L'Attachments None Simulator Setup H None Page 2 of 3

Task Objectives/Standards Complete the EMD-32a, Nuclear Plant Event Notification for notification of state agencies.

Task Briefing II You are an extra Control Room Operator on Unit 1. At the beginning of your shift, Unit 1 is operating at 100% rated power with the turbine-driven auxiliary feed water pump tagged out for maintenance.

During your shift, a severe electrical storm causes a total loss of offsite power when lightning strikes the 345 KV Switchyard.

Although both emergency diesel generators start, a total loss of AC power occurs on Unit 1 when neither emergency diesel generator successfully energizes their associated busses.

The crew successfully restores power to the T11 C and Ti 1D safety related busses from the 1CD Diesel within 8 minutes of the loss of AC power.

Although the plant is stable, efforts to restore power from the lAB Diesel as well as offsite power have not been successful and are expected to take at least one hour.

The Shift Manager has just declared an Alert per initiating condition S-2, Loss of AC.

Classification Time is (Use Current Time & have candidate enter on briefing handout)

THIS IS A TIME CRITICAL JPM After classifying the Alert condition The Shift Manager appoints you as the Plant Communicator and instructs you to complete EMD-32a, Nuclear Plant Event Notification form for approval.

All radiation monitors are indicating normal activity / expected levels. There are NO radiation alarms.

Meteorological Data - MIDAS Summary is provided.

Page 3 of 3

COURSE NUMBER LN02-A4 AND TITLE: E I Complete EMD-32a Nuclear Plant Event Notification REVISION: 0 II IL Reference PMP-2080-EPP-1f07 Rev. 16 Page 4 of 13 Notification FOR AN ALERT:

"Attention all personnel. Attention all personnel. An Alert has been declared due to - (brief description)

Activate the Operations Support Center, Technical Support Center, Emergency Operations Facility and the Emergency News Center. All other personnel stand by for further announcement."

FOR A SITE AREA EMERGENCY OR GENERAL EMERGENCY:

Sound the Nuclear Emergency Alarm from the Control Room and broadcast the following:

"Attention all personnel. Attention all personnel. A_. (Si Area Emergeny or General Emereency) has been declared due to - (brief description) . Activate the Technical Support Center, Operations Support Center, Emei-gency Operations Facility, and Joint Public Information Center.

All other personnel report for accountability."

3.2.4 On any touch-tone telephone, dial 1646 to access the Training Center and Buchanan Office Building PA and repeat the announcement that was made in step 3.2.3 twice.

3.2.5 Within 15 minutes of the classliication of any emergency'perform the following:

a. Complete Nuclear Plant Accident Notification form, EMD 32a, (from Emergency Kit or DAP printout). - EMD-32a must be completed and the state and county

b.

Contact:

notifications made within 15 minutes of the Alert classification.

Michigan State Police (MSP) at 8-1-517-336-6250 using the MSP bridge phone (extension 1088) in the back of the Control Room.

fBerrien County Sheriff's Department at 8-1-616-983-3911.

c. Document phone calls on Data Sheet 1. Shift Manager initial Notification List.

Page 1of 3

COURSE AN TIL:Comlt NUMBER N02-A4 lete EMD-32a E

!ANDTIT LE : Com Nuclear Plant Event Notification REVISION: 0 F Reference PeP-2080-EPP-107 Re. 16 Page 5 of 13 Calu tiuaon

d. Provide the information from Nuclear Plant Accident Notification form, verbally to the MSP and the Berrien County Sheriff's Department.

c. Request a call back froni the MSP and Berrien County Sheriffs Department.

f. Inform the MSP that Nuclear Plant Accident Notification form will be faxed.

3.2.6 Fax Nuclear Plant Accident Notification form, to the MSP: Fax number 8-1-517-336-6257.

NOTE: If BROADCAST is pushed on the step 3.2.7 will receive the fax- fax machine all isofNOT If BROADCAST the locations used thenlisted each inof the locations wi have to be individually faxed at the numbers listed in step 3.2.7.

3.2.7 IF an Alert, Site Area Emergency or General Emergency exists, THEN make follow-up notifications to the below listed facilities by faxing:

. EMD-32a, Nuclear Plant Accident Notification, within 15 minutes of a change of classification or Protective Action Recommendation

. EMD-32b, -Nuclear Plant Event Technical Data, every 30 minutes there after until relieved by the EOF.

Michigan State Police 8-1-517-336-6257 State Emergency Operations Center 8-1-517-333-4987 Emergency Operations Facility 8-284-2942 Emergency News Center/JPIC 8-284-5892 Visitors' Center 2906 or 2907 3.2.8 For all classifications, including classification upgrades, the Shift Manager or designee shall:

a. Provide the information on Data Sheet 2, Plant Status, to the NRC as soon a-s a.

been notified, btate --.and Couuty have and within one huur of classification.

Make the notification in accordance with the'instructions in PMp 7030-001-001, Prompt NRC Notification.

Page 2 of 3

COURSE NUMBER N02-A4 AND TITLE: Complete EMD-32a Nuclear Plant Event Notification REVISiON: 0 I.

All items should be completed on the form prior to submitting

.,, - . .. .- " .. v. .. .-..... . ... .. .. to the Site Emergency Coordinator for approval.

"Actual Event" box marked (for purposes of this JPM Pla,. t Contact information . .. "Drill" is also acceptable)

,111--,Pow r anti .... X.. CT: - "D. C. Cook" the plant MUST be identified IPlarnt rornmuniark ,~~

"1" entered since this is the initial notification (CR1 is Callivg 0 SO pb0 IrmUo QCnto Loo1 f: also acceptable)

Cai 86ýTelep$1on e NitMber: k3~~.9 Plnt messe.e lUmber "Control Room" box marked Current ClassificAtion .. : Plant number given, however other control room Q lws.ustal Ev-entXAr h Aa mroi Gnri1mraic asnt Tb'Te c-ass~ficatfon was declared, a., oý--Pate telephone numbers are acceptable

. Tj m6 ie i g r 4

.R . .. :R ...a ,,iono" toi

t. . \ CT: - "Alert" box MUST be marked "Abnormiabl .Rad LeelI ad: .li:.op

.i :r:P y rnril~ncrn tti CT: - Today's date and time of Classification (Given "0Fission Produt Barrier De0 dalont - -:.

z.y d..." r..*ndifl" .. :

during the briefing) MUST be filled in Cook _10 Nirnber

"""___________"____5 .

"System Malfunction" box marked i Plant,4tatus. S.......*.....:: * ...- .... .:..:.:.::

T: - "S-2" MUST be filled in L _... s.*... 0*De , .* .. .;i::iijora""dino "'g :: ::* ..

______a.

Radi~~Aol Yos rea~ae in Prr~gresý 01;*Og -y Een'. 1ECT: - "Stable" box MUST be marked EProtectivetActloo oRecommedaIons "41: - "No" box MUST be marked CT: - "None" box MUST be marked Wind from "262o" to "82o" filled in IV,,.nd Drectnn (dpgewa): Firm T TO: -o z*

Ve4MSUdQVPI

. n Wind speed "10" mph filled in Stability Class "E" filled in Precipitation uYes" box marked f 3:.

Student reports form complete and ready for SEC approval.

Mani.;r wale: .. : .... _ fl'_..n ___ JPM IS COMPLETE.

Page 3 of 3

Task Briefing You are an extra Control Room Operator on Unit 1. At the beginning of your shift, Unit 1 is operating at 100% rated power with the turbine-driven auxiliary feed water pump tagged out for maintenance.

During your shift, a severe electrical storm causes a total loss of offsite power when lightning strikes the 345 KV Switchyard.

Although both emergency diesel generators start, a total loss of AC power occurs on Unit I when neither emergency diesel generator successfully energizes their associated busses.

The crew successfully restores power to the TI 1C and T11 D safety related busses from the 1CD Diesel within 8 minutes of the loss of AC power.

Although the plant is stable, efforts to restore power from the lAB Diesel as well as offsite power have not been successful and are expected to take at least one hour.

The Shift Manager has just declared an Alert per initiating condition S-2, Loss of AC. Classification Time is After classifying the Alert condition The Shift Manager appoints you as the Plant Communicator and instructs you to complete EMD-32a, Nuclear Plant Event Notification form for approval.

All radiation monitors are indicating normal activity / expected levels. There are NO radiation alarms.

Meteorological Data - MIDAS Summary is provided.

N02-A4.doc Page 1 of 2

Meteorological Data - MIDAS Summary Delta Temperature - Main Tower -0.3oF Wind Direction 10M - Main Tower 2620 Wind Speed 10M - Main Tower 10 mph Precipitation - Main Tower Rain Wind Direction 10M - Backup Tower 2680 Wind Speed 10M - Backup Tower 12 mph Wind Direction 60M - Main Tower 2710 Wind Speed 60M - Main Tower 13 mph Standard Deviation 10M Main 0o Standard Deviation 10M Backup 0o Standard Deviation 10M Main Go Pasquill Category E Outside Temperature 60.8oF Lake Breeze NA N02-A4.doc Page 2 of 2

rI.Ia3D TITLE Verify Ultimate Heat Sink Temperature REVISION 0 Determination (SRO review)

[RO AM NRC License Exam TIME! 15 Minutes DEVELOPING Name: S. Pettinger 10/23/2002 INSTRUCTOR: Signature:

OPERATIONS REVIEW: Name: 10/23/2002 T Werk Signature:

Page 1 of 3

COURSE NUMBER N02-A5a - Verify Ultimate Heat Sink Temperature REVISION: 0 AND TITLE: Determination 11References 02-OHP-4030-STP-030 Daily and Shiftly Surveillance Checks Data Sheet 5 pages 81 & 82 OP-2-5119A, Flow Diagram Circulating Water, Priming System & Screen Wash (P&ID)

Task: STP0390201 Perform Shiftly Surveillance Checks for Modes 5 & 6 K/A CROSS

REFERENCE:

2.1.7 K/A IMPORTANCE: RO 3.7 SRO 4.4

[Evaluation Setting Simulator IHandouts Task Briefing of N02-A5a Completed Data Sheet 5, step 14.0 If requested then provide candidate with OP-2-5119A, CW System (P&ID)

Attachments, None

[Simulator Setup Reset to Mode 6 IC 998 Close CW Condenser Inlet and Outlet valves:

"* A Condenser South 2-WMO-1 03 & 104

"* C Condenser North 2-WMO-301 & 302 Shutdown #21 & #22 CW Pumps (2 CW Pumps left running)

Page 2 of 3

COURSE NUMBER N02-A5a - Verify Ultimate Heat Sink Temperature REVISION: 0 AND TITLE: Determination Task Objectives/Standards The Candidate performs a review of a complete surveillance, identifies that the South Waterbox for "A" condenser and the North Waterbox for the "C" condenser are Isolated and the associated temperatures are not used for the calculations. The Candidate identifies that CW Temperature is >

76.8 F And Fuel Movement must be stopped until the reactor has been shutdown for >148 hours.

Task Briefing Given the following:

"* You are the Unit 2 Unit Supervisor

"* Unit 2 is currently in MODE 6.

"* The reactor was shutdown 130 hours0.0015 days 0.0361 hours 2.149471e-4 weeks 4.9465e-5 months ago.

"* Fuel Movement is currently in progress.

MTI reports CW temperature transmitters are not functioning properly, due to a power supply problem, therefore SG-21, Circ Water Temp Recorder and PPC address U0200 are Out Of Service (OOS).

The RO has just performed step 14.2 of 02-OHP-4030-STP-030 Daily and Shiftly Surveillance Checks Data Sheet 5 (pages 81 & 82) based on the following local circ. Water inlet temperature readings obtained by the AEO:

CTondnse =A WoTdXn-20 =7 Cond*nseeLC WTX-106 = 71.8 WTX-206 =77.2 WTX-306 = 77.1 WTX-107 =71.8 WTX-207 = 77.1 WTX-307 = 77.0 WTX-108 = 72.2 WTX-208 = 77.3 WTX-308 = 77.0 WTX-102 = 77.1 WTX-202 = 76.9 WTX-302 = 71.2 WTX-103 = 77.4 WTX-203 = 76.9 WTX-303 = 70.9 WTX-104 = 76.8 WTX-204 = 77.0 WTX-304 = 71.3 Temperature readings were obtained using Instrument ID CNP-147, Make/Model ELUKEL2175 with Calibration Current (Last Cal. Performed on 05/07/2002)

Review step 14.2 of 02-OHP-4030-STP-030 (pages 81 & 82) for accuracy and to ensure all Acceptance Criteria are met for the current Circulating Water System configuration. Be sure to mark any and all errors identified Page 3 of 3

COURSE NUMBER N02-A5a - Verify Ultimate Heat Sink Temperature Determination REVISION: 0 AND TITLE:R General CUES:

Continuous I 02-OHP-4030-STP-030 I Rev. 39 I Page 81 of 145 DAILY AND SHIFTLY SURVEILLANCE CHECKS If requested then provide OP-2-5119A, CW System (P&ID)

Data Sheet 5 Shift Surveillance Checks Modes 5, 6 and Defueled7 Pages:

170 - 83 The SRO review of the data should identify the following errors:

Instrument Title & No. 00-08 1 08-16 1 16-24 1 Acceptance Criterion 1. Temperature readings were averaged vice specific temperature I IValue Value I.ValueI selected and recorder NOTE: "*'The temperature monitoring in Step 14.0 is N/A when TS 3.9.3 does not apply, i.e., after the 148 hour0.00171 days 0.0411 hours 2.44709e-4 weeks 5.6314e-5 months decay time has been met or when not moving irradiated fuel in the reactor vessel.

monitoring is to validate temperature limits in TS Bases.

This 2. Temperature readings for isolated waterboxes should be Decay Times - at least 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months from September 15 through June 8", or at least 148 hours0.00171 days 0.0411 hours 2.44709e-4 weeks 5.6314e-5 months excluded (WTX-106, 107,108, 302, 303 and 304) from June 9* through September 14. (TS 3.9.3)

The June dates were changed to be more conservative than the TS applicability to support the TS 3/4.9.3 Bases discussion to ensure sufficient decay time for June outages.

+ Circulating Water Temperature from either unit may be used, indicate unit used.

14.u 14.1 Ci rc Wtr T'emnp: IS 3.9.3-= for Decy m: ".4

." Take reading from SG-21 l1 U2g Step14.1-Lessthanor Point 1, Circ Water Temnp AO- 'F F equal *o74.6'Fo S-.21 Recorder. Point 1, (La., 77.8

3.2OF

IF recorder is energized and OOS =

the printer is inoperable, PPC Step e14-14.2 - less l than or Step is N/A due to Temperature Indicator Problems THEN take readings from INOPERABLE equal to 76.8*F the PPC, U0200. (i.e., 77.8 +/- lOF instrument uneertainty for M&TE

" UK - cuaiiUatod Flue-52 with a 12"probe, or equivalent).

C8 14.2 IF Circ Water Temp is greater than or equal to 72°F OR ff the Unit is in MODE 6 C8 measurement cannot be obtained in Step 14.1 OR a more with movenent of irradinted accurate value is desired, THEN obtain an M&TE calibrated fuel in the vessel in progress temperature measurement instrument and perform the following: between September 15 and June 8. with:

Record instrument ID CNP-147 " Decay Tane from Instrument make/model: FLUKE/2175 10r 148 bri Current calibration Y/N Yes

Cire Wtr Temp -Reviews instrument data for accuracy.

>74.6*F (using Take one inlet temperature measurement of each Condenser in Step 14.1 ) OR service using the M&TE calibrated instruent with +/-S°F >76.8F (using Step 14.2) uncertainty and calculate the average.

UI Q U20 4 - sssIT OP Identifies that "U2" Box is not checked.

'movem-1tof Condenser A Circ Water Inlet:' irradiated fuel until either of the following eondititons are Check box for inlet measured: Circ Wtr Temp is -CT: Determines a box is not checked and that the temperature o WTX-106 or C4 O WTX-107 or

!V4.

logged (74.5oF, averaged temperature was used instead of 1 R -76.PF' O WTX-108 or S/ tog Step 14.2)

-OR.

'te temperature) is in error and should be one of the following:

o WTX-102 or S;Decay Time is greater O WTX-103 or o WTX-104

_____, __ _ . than 148 hrs. WTX-102 = 771 WTX-103 = 774 WTX-104 = 76.8 Page 1 of 2 Revision 0

COURSE NUMBER]N2A~ Verify Ultimate Heat Sink Temperature DeterminationREION0 1ANDTITLE:.

,~CT: Determines a box is not checked and that the temperature

,jogged (77.07oF, averaged temperature was used instead of 1 temperature) is in error and should be one of the following:

WTX-206 = 772 WTX-207= 77.1 W7X-208 = 773 W1X-202 = 76.9 WTX-203 = 76.9 W7X-204 = 770 CT: Determines a box is not checked and that the temperature logged (74.08oF, averaged temperature was used instead of 1 temperature) is in error and should be one of the following:

WTX-306 = 771 WTX-307 = 77 0 WTX-308 = 770 CT: Determines average temperature logged (75.22 °F) is in error (should be between 76.9 oF - 77.3 f).

I CT: SRO review of Acceptance Criteria has identified that the average temperature is greater than 76.8 oF and fulmven must be stopped since the reactor has been shutdown less than 148 hours0.00171 days 0.0411 hours 2.44709e-4 weeks 5.6314e-5 months . Per Tech Spec 3.9.3 Reports task completed.

JPM IS COMPLETE.

Page 2 of 2 Revision 0

COURSE NUMBER N02-A5a - Verify Ultimate Heat Sink Temperature Determination REVISION: 0 AND TITLE:.

B Condenser South Inlet Temp WTX-206 77.2 T ' B Condenser South Inlet Temp WTX-207 77.1 B Condenser South Inlet Temp WTX-208 77.3 rt---,

. .B Condenser North Inlet Temp WTX-202 76.9 TB Condenser North Inlet Temp WT-203 76.9 B Condenser North Inlet Temp WTX-204 77.0 T ........ All Temperatures are valid rip Ell . DP) A 11 Cip g ' cop) ?Elp

+,.,.. liDp JA t I- -A IT (i T ) T , ,, .

11.

"7"7 '4

,, . . ... l I, lf l I IS;*l lI M J VV IJ -. ) U U I . I A Condenser South Inlet Temp C Condenser South Inlet Temp WTX-307 77.0 WTX-106 71.8 A Condenser South Inlet Temp C Condenser South Inlet Temp WTX-308 77.0 WTX-107 71.8 A Condenser South Inlet Temp C Condenser North Inlet Temp WTX-302 71.2 WTX-108 72.2 A Condenser North Inlet Temp C Condenser North Inlet Temp .WTX-303 1 70.9 WTX-102 77.1 C Condenser North Inlet Temp VWTX-304. 71.3 A Condenser North Inlet Temp WTX-103 77.4 South Temperatures are valid A Condenser North Inlet Temp WTX-104 {.76.8 North Temperaturesare valid Page 1 of 1 Revision 0

Task Briefing Given the following:

"* You are the Unit 2 Unit Supervisor

"* Unit 2 is currently in MODE 6.

"* The reactor was shutdown 130 hours0.0015 days 0.0361 hours 2.149471e-4 weeks 4.9465e-5 months ago.

"* Fuel Movement is currently in progress.

MTI reports CW temperature transmitters are not functioning properly, due to a power supply problem, therefore SG-21, Circ Water Temp Recorder and PPC address U0200 are Out Of Service (OOS).

The RO has just performed step 14.2 of 02-OHP-4030-STP-030 Daily and Shiftly Surveillance Checks Data Sheet 5 (pages 81 & 82) based on the following local circ. Water inlet temperature readings obtained by the AEO:

CondenserA CondenseLB fLC mGienp WTX-106 = 71.8 WTX-206 = 77.2 WTX-306 = 77.1 WTX-107 = 71.8 WTX-207 = 77.1 WTX-307 = 77.0 WTX-108 = 72.2 WTX-208 = 77.3 WTX-308 = 77.0 WTX-102 = 77.1 WTX-202 = 76.9 WTX-302 = 71.2 WTX-103 = 77.4 WTX-203 = 76.9 WTX-303 = 70.9 WTX-104 = 76.8 WTX-204 = 77.0 WTX-304 = 71.3 Temperature readings were obtained using Instrument ID CNP-1IA, Make/Model ELU.KEL2175 with Calibration Current (Last Cal. Performed on 05/07/2002)

Review step 14.2 of 02-OHP-4030-STP-030 (pages 81 & 82) for accuracy and to ensure all Acceptance Criteria are met for the current Circulating Water System configuration. Be sure to mark any and all errors identified N02-A5a.doc Page 1 of 1

ZN02-A5=bIj TITLE Perform Control Room actions for Fuel Handling Accident in Containment VISION 0 NRC License Exam TIME. 15 Minutes DEVELOPING Name: S. Pettinger 10/2312002 INSTRUCTOR: Signature:

OPERATIONS REVIEW:, Name: 10/23/2002

.. T. Verk Signature:

Page 1 of 3

COURSE NUMBER N02-A5b Perform Control Room actions for Fuel REVISION: 0 AND TITLE: Handling Accident in Containment

[ References 12-OHP-4022-018-004, Irradiated Fuel Handling Accident in Containment Building-CR Actions Task: AOP0640414 Respond to a Fuel Handling Accident in the Containment K/A CROSS

REFERENCE:

2.2.29 K/A IMPORTANCE: RO 1.6 SRO 3.8 Evaluation Setting Simulator SHandouts I Task Briefing Copy of 12-OHP-4022-018-004, Irradiated Fuel Handling Accident in Cont. Building-CR Actions I[Attach ments I None Simulator Setup Simulator in Mode 5/6 IC with Containment Purge Supply and Exhaust System operating:

RMS CT reset and all RMS status lights green Operable RMS with Trip Block switches in NORMAL: 2-VRS-2101, 2201 2-ERS-2300, 2400 OPEN Cntmt Purge valves: 2-VCR-1 05, 205, 103, 104, 106, 203, 204, 206 START Cntmt Purge Supply and exhaust Fans: 2-HV-CPX-1 & 2, 2-HV-CPS-1 & 2 Verify Instrument Room Purge Supply And Exhaust fans are STOPPED and Dampers are CLOSED Verify Containment Pressure Relief Dampers are CLOSED and Fan is STOPPED Verify Control Room Ventilation Fans 2-HV-ACRF-1 & 2 STOPPED, Dampers 2-HV-ACR-DA 1, DA-1A, & DA-3 are OPEN, Dampers 2-HV-ACR-DA-2 & DA-2A are CLOSED (Normal Lineup)

Page 2 of 3

COURSE NUMBER N02-A5b Perform Control Room actions for Fuel FREVISION: 0 AND TITLE: Handling Accident in Containment ITask Objectives/Standards Respond to an Irradiated Fuel Handling Accident in the Containment per 12-OHP-4022-018-004, observing applicable precautions and limitations and procedural steps.

iTask Briefing I The SRO-CA reports to the Control Room that during fuel movements on Unit 2, a top nozzle has failed on an irradiated fuel assembly while moving the manipulator Crane.

The fuel assembly has fallen to the bottom of the Reactor Cavity.

Several fuel pins have ruptured, bubbles have been observed floating to the top of the water.

The US directs you to implement 12-OHP-4022-018-004, Irradiated Fuel Handling Accident in the Containment Building-Control Room Actions.

Page 3 of 3

COURSE NUMBER NO2-A5b Perform Control Room actions for Fuel Handling Accident in AND TITLE :'. .. ContainmentIII ii REVISION: 0 STitk - Numb " General CUES:

IRRADIATED FUEL HANDLING ACCIDENT IN 12-OBP 4022.0 OTM,,r STEP BUILDING - CONTROL ROOM ACTIONS ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I The SRO-CA reports that the top nozzle on an irradiated fuel assembly has failed during movement of the manipulator crane and the fuel assembly fell to the bottom of the reactor cavity. Bubbles are riding from several ruptured pins.

1. Actuate Containment Evacuation Alarm

2. Notify All Non-essential Personnel To Another SRO is performing the Emergency Classification as per Evacuate Containment Section C of this procedure.

3. Notify All Personnel Listed On Containment Penetration Breach List To CT: Operator actuates the containment evacuation alarm on the Set Containment Closure (01/02-OHP-4030-STP-041) For, Any Flux Panel Open Containment Penetrations "CT: Operator notifies evacuation of non-essential personnel from

4. Notify Shift Manager containment using the paging system

5. Verify All Containment Purge Supply And Exhaust Fans - STOPPED

"-CUE: "There are NO open containment penetrations" Operator notifies SM CUE: "Shift Manager acknowledges notification of fuel handling accident."

"-Operator STOPS the following fans:

CT: Containment Purge Supply 2-HV-CPS STOPPED CT: Containment Purge Supply 2-HV-CPS STOPPED CT: Containment Purge Exhaust 2-HV-CPX STOPPED CT: Containment Purge Exhaust 2-HV-CPX STOPPED Page 1-of 8

COURSE NUMBER .N02-A5b Perform Control Room actions for Fuel Handling Accident in AND TITLE:, IIContainment 11i REVISION: 0 1

... II I IRRADIATED FUEL HANDLING ACCIDENT IN IZ-OHP 4022.018.004 CONTAINMENT BUILDING - CONTROL ROOM ACTIONS " -4 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I 6. Verify Containment Purge in the affected I Unit - ISOLATED:

Unit 1:

" Supply Air Valves - CLOSED.

"* 1-VCR-103

"* I-VCR-203

"* I-VCR-105

"* 1-VCR-205

" Exhaust Air Valves - CLOSED.

"* 1-VCR-104

"* 1-VCR-204

"* l-VCR-106

"* I-VCR-206 OR Operator Closes Unit 2 supply air valves (at least 1 per Unit 2:

penetration):

Supply Air Valves - CLOSED.

"* 2-VCR-103 CT:*- Lower Cntmt Supply Air 2-VCR-1 03

"* 2-VCR-203 Lower Cntmt Supply Air 2-VCR-203

"* 2-VCR-105 CT.( Upper Cntmt Supply Air 2-VCR-1 05

"* 2-VCR-205 LUpper Cntmt Supply Air 2-VCR-205

Exhaust Air Valves - CLOSED.

"* 2-VCR-104

"* 2-VCR-204" - -.-.. '

Operator Closes Unit 2 exhaust air valves (at least 1 per

", 2-VCR-1062-R20 penetration):

-QT_.- Lower Cntmt Exhaust Air 2-VCR-1 04 LLower Cntmt Exhaust Air 2-VCR-204

-C.. Upper Cntmt Exhaust Air 2-VCR-106 LUpper Cntmt Exhaust Air 2-VCR-206 t -

ii Page 2 of 8

COURSE NUMBER. 1N02-A5b Perform Control Room actions for Fuel Handling Accident in REVISION: 0 AND TITLE:; fl Containment II IRRADIATED FUEL HANDLING ACCIDENT IN 12-OIIP 4022.018.004 CONTAINMENT BUILDING - CONTROL ROOM ACTIONS STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

7. Verify Instrunent Room Purge in the affected Unit - ISOLATED, Unit 1:

"* Supply Air Valves - CLOSED.

I1-VCR-101 Il-VCR-201

"* Exhaust Air Valves - CLOSED

"* 1-VCR-102

"* I-VCR-202 OR Unit 2:

"* Supply Air Valves - CLOSED.

"Operator verifies Unit 2 supply (2) and exhaust (2) valves closed

2-VCR-101 A

- 2-VCR-201

"* Exhaust Air Valves - CLOSED

"* 2-VCR-102

"* 2-VCR-202 Page 3 of 8

COURSE NUMBER AND TITLE::

IN02-A5b Perform Control Room actions for Fuel Handling Accident in Containment REVISION: 0I I

IRRADIATED FUEL HANDLING Tiilý ACCIDENT IN CONTAINMENT BUILDING - CONTROL ROOM ACTIONS 12-OHP 4022.018.004 STE ACTION/EXPECTED RESPONSE REPONSE NOT ýOBTAINED

8. Verify Containment Pressure Relief Fan in the affected Unit - STOPPED.

Unit 1:

. I-H'V-CPR-I OR Unit 2:

2-HV-CPR-1

9. Verify Containment Pressure Relief erator verifies Unit 2 Containment Pressure Relief fan Valves in the affected Unit- CLOSED: ipped Unit 1:

"* I-VCR-107

"* I-VCR-207 OR Unit 2:

"* 2-VCR-107

"* 2-VCR-207 * - + -(1 erator verifies Unit 2 Containment Pressure Relief Valves (2) sed Page 4 of 8

COURSE NUMBER N02-A5b Perform Control Room actions for Fuel Handling Accident in REVISION: 0 AND TITLE: Co IContainment Till. N-ub IRRADIATED FUEL HANDLING ACCIDENT IN 12-OHP 4022.018.004 CONTAINMENT BUILDING - CONTROL ROOM ACTIONS STEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

10. Isolate Control Room Ventilation To BOTH Units:

- CT: Operator notifies Unit I to isolate Unit 1 CR Ventilation due to

a. Uniti1: Unit 2 fuel handling accident I) System dampers - ALIGNED: 1) Manually align damper(s) as necessary per 01-OHP 4021.028.014, Operation of the Control Room Air Conditioning CUE: "A Unit 1 Operator will align Unit 1 Control Room Ventilation and Prerssurization/Cleanup Filter System, Attachment 12, Corrective per 12-OHP-4022-018-004 Step 10a" Measures.

"* Close I-HV-ACR-DA-1, Control Room Vent Intake Damper

"* Close I-HV-ACR-DA-IA, control room vent intake damper

"* Align the following Intake Dampers one Partial Open AND one Closed:

"* l-HV-ACR-DA-2, Control Room Pressurization Intake Damper

"* 1-HV-ACR-DA-2A, Control Room Pressurization Intake Damper

"* Open 1-HV-ACR-DA-3, Control Room Pressurization Clean-up Recirc Damper

2) START Control Room Pressurization/Cleanup Filter Unit Ventilation Fan l-HV-ACRF-1 OR 1-HV-ACRF-2.

Page 5 of 8

COURSE NUMBER. N02-A5b Perform Control Room actions for Fuel Handling Accident inI REVISION: 0 S A ND TITLE:',. C ontainm ent I Tide .Nml .

IRRADIATED FUEL HANDLING ACCIDENT IN 12-OBP 4022.018.004 CONTAINMENT BUILDING - CONTROL ROOM ACTIONS STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

b. Unit 2:

1) System dampers - ALIGNED 1) Manually align damper(s) as necessary per 02-OHP 4021.028.014, Operation Operator performs Unit 2 CR Ventilation line up of the Control Room Air Conditioning and Prerssurization/Cleanup Filter System, Attachment 13, Corrective Measures.

Close 2-HV-ACR-DA-1, Control Room Vent Intake Damper CT: Operator closes DA-1

Close 2-HV-ACR-DA-IA, control room vent intake 4d damper CT: Operator closes DA-1A

Align the following Intake Dampers one Partial Open AND one Closed:

2-HV-AflR-DA-4 Cnntra!

Room Pressurization Intake Damper

2-HV-ACR-DA-2A, CT: Operator places one damper to partial open Control Room Operator verifies other damper is closed Pressurization Intake Damper Open 2-HV-ACR-DA-3, Control Room Pressurization Clean-up Recirc Damper

2) START Control Room ' Operator verifies open DA-3 Pressurization/Cleanup Filter Unit Ventilation Fan 2-HV-ACRF-1. '.4 OR 2-HV-ACRF-2.

-q CT: Operator starts 1 fan

11. Verify Instrument Room Purge Supply And Exhaust Fans - STOPPED

'-4 Operator directs AEO to verify Inst. RM Purge supply and exhaust fans stopped CUE: "AEO reports that Instrument Room Purge Supply and Exhaust fans are STOPPED."

Page 6 of 8

COURSE NUMBER N02-A5b Perform Control Room actions for Fuel Handling Accident in I REVISION: 0 AND TITLE:.ý-, Containment IRRPADIATED FUEL HANDLING ACCIDENT IN 12-OHP 4022.018.004 CONTAINMENT BUILDING - CONTROL ROOM ACTIONS STEP I ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED CUE: Ifrequested, "Containment Airlock Doors are closed"

12. Check Additional Auxiliary Building. 11. Go to Step 13 -q Fan In Service With Containment Operator determines airlock doors are closed and containment Airlock Doors Open AND Containment Purge In Service: purge is off, goes to RNO and proceeds to step 13

a. Remove Auxiliary Building Supply Fan from service JAW 12-OHP 4021.028..011, Auxiliary Building Ventilation

13. Locally Verify 12-RRV-306, GDT Release Header To Aux. Bldg. Vent Stack Shutoff Valve at the waste gas Operator directs AEO to verify 12-RRV-306 is closed system panel - CLOSED CUE: 12-RRV-306 has been verified closed locally

14. Notify Radiation Protection To Perform The Following:

a. Survey Containment

-'U CUE: US will notify RP to perform surveys and verify all evacuated personnel are assembled at the control point

b. Establish necessary boundaries

c. Dispatch monitoring team to check for any releases external to the containment AND report results to the Shift Manager

15. Verify All Evacuated Personnel ASSEMBLED AT THE AUXILIARY BUILDING CONTROL POINT Page 7 of 8

I I

COURSE NUMBER.I N02-A5b Perform Control Room actions for Fuel Handling Accident in AND TITLE::I IlContainment II jREVISION: 011f I

I Tid.

~12-OHP IRRADIATED FUEL HANDLING ACCIDENT IN CONTAINMENT BUILDING - CONTROL ROOM ACTIONS 12-HP 4 ue"-.

4022.018.004 STEP ACTiON/EXPECTED RESPONSE RESPONSE NOT OBTAINED SNOTE: Recovery and work will commence after an investigation has been conducted a recovery procedure established.

Reports task completed.

16. Return to Procedure And Step In Effect.

JPM IS COMPLETE.

Page 8 of 8

Task Briefing The SRO-CA reports to the Control Room that during fuel movements on Unit 2, a top nozzle has failed on an irradiated fuel assembly while moving the manipulator Crane. The fuel assembly has fallen to the bottom of the Reactor Cavity.

Several fuel pins have ruptured, bubbles have been observed floating to the top of the water.

The US directs you to implement 12-OHP-4022-018-004, Irradiated Fuel Handling Accident in the Containment Building-Control Room Actions.

N02-A5b.doc Page 1 of 1

N02-TITLE Perform an Initial Dose Assessment REVISIO .N 0 P*ROGRAM NRC License Exam TIME 10 Minutes Revision 0: Initial Issue DEVELOPING Name: Dale Tidwell 10/23/2002 INSTRUCTOR: Signature:

OPERATIONS I W Verk 0 REVIEW: Name: 10/2312002 Signature:

Page 1 of 3

C A..

OLJEU NUMB'*R TITLE:!

N02-A6 Perform an Initial Dose Assessment IR5Vl 0 REFERENCES Procedure: PMP-2080-EPP-1 08 revision 4, Initial Dose Assessment Task: EPP0070701, Perform and Initial Dose Assessment K/A CROSS

REFERENCE:

2.4.38 K/A IMPORTANCE: SRO 4.0 RO 2.2 Il EVALUATION SETTING I1 Computer terminal with Dose Assessment Program (DAP) installed.

I1 .HANDOUTS Task Briefing 1E ATTACHMENTS None SIMULATOR SETUP None Page 2 of 3 Revision 0

COURSE NUMBER N02-A6 REVISION:

ND T : Perform an Initial Dose Assessment TASK OBJECTIVES/STANDARDS Terminal Objectives:

1. Perform an Initial Dose Assessment Enabling Objectives

1. Given a scenario of plant conditions including specific instrumentation values, a computer with DAP installed and procedure PMP-2080-EPP-1 08, perform a dose assessment for the site boundary with protective action recommendations.

jf TASK BRIEFING Given the following:

"* At 06:50 Unit 2 tripped due to a large Steam Generator tube rupture on the Loop 1 Steam Generator.

"* The break flow is estimated at 175 gpm.

"* Due to problems immediately following the trip, all MSIV's were closed.

"* At 06:55 the BOP operator reported that the PORV on the ruptured steam generator is 25% open and can not be closed.

"* MRA-2601, Stm Gen Loop 1 PORV Discharge, has a High Alarm.

"* At 07:00 the Shift Manager declares a Site Area Emergency and assumes the role of Site Emergency Coordinator.

"* Current plant conditions are stable.

At 07:00 you are given a print out of the current PPC Dose Assessment Information screen (attached) and directed to perform an initial offsite dose assessment for the conditions described.

When you have completed the initial offsite dose assessment, report the calculated TEDE and Adult thyroid CDE Site Boundary dose rates to the examiner.

Page 3 of 3 Revision 0

COURSE NUMBER: N02-A6 ANDT ITE Perform an Initial Dose Assessment ormation P -1 R ev. age 3 of9 Initial Dose Assessment 4 DETAILS NOTE. DAP contains extensive on line help. Help for any particular subject may be obtained by placing the mouse over the object in question. If help is available it will appear at the bottom of the screen.

NOTE: Dose assessment projections may only be performed using the DAP. 17 projected doses are NOT available and a PAp, is n=cesary, TH7 J use the A computer terminal with the current version of the default PAR in PMP-2080-EPP-100. Dose Assessment Program (DAP version 7.0.20) is 4.1 Determine which forms are required.

necessary for completion of this JPM.

4.1.1 EMD-32a, Nuclear Plant Event Notification.

Is only trans-itted to the State/County within 15 minutes of a change to

For the conditions described in this JPM, an EMD-32a die emergency classification or PAR.

Must include an EMD-32b, Nuclear Plant Event Technical Data Form would be completed. Completion of the EMD-32a is if the emergency classification is General Emergency and the PAR is NOT necessary for successful completion of this JPM.

based on dose calculations.

4.1.2 EMD-32b, Nuclear Plant Event Technical Data Form.

Required to be transmitted to the State/County within 30-minute "intervalsof the last EMD-32b or EMD-32a form.

4.2 Obtain meteorological data from the PPC. If the PPC is not available, Attachment 1, Meteorological Data, contains additional sources of meteorological data and Attachment 2, Pasquill Category, provides for Pasquill Category (Stability Class)

PPC meteorological data is provided with the briefing.

Sdeterminations NOTE: Sources are listed in order of preference.

10 Meter Main

10 Meter Backup

60 Meter Main Page 1 of 12 Revision 0

COURSE NUMBER N02 -A n AND TITLE: Perform an Initial Dose Assessment 'REVISION: .0 II II information MP-2 -EPP-1 ev. 4 Page 4o Initial Dose Assessment 4.3 Obtain RMS radiological data from one of the following sources:

PPC Radiological data is provided with the briefing.

NOTE: Sources are listed in order of preference.

PPC

RMS Display Terminals Direct readings from.the Local Area Data Acquisition Modules 4.4 Determine the Unit 1 and Unit 2 reactor shutdown status and the date and tine of shutdown as applicable. ONLY Unit 2 is applicable for this JPM. Unit 2 status is 4.5 Determine the Coolant Type. provided with the briefing.

T00o 1type Containment on ontorng eaing Normal Coolant <10 R/hr Cladding Damage

-* Normal Coolant will be used in the calculation. Provided

<1I Fuel Melt > =1000 /hr with briefing - both Containment High Radiation Monitors (VRA-231 0 and VRA-241 0) are less than 10 R/hr.

4.6 Determine whether an actual or potential release is occurring.

4.6.1 An actual release is occurring when any of the following are true:

Valid indication on release point radiation monitoring system channels are present that are associated with a classified event, Actual release is in progress as provided with briefing.

- OR

. Measured off-site radiation readings indicate a release is in progress,

- OR

. Indications exist that an unmonitored release may be occurring.

4.6.2 A potential release exists if calculated data is postulated based on present plant conditions (i.e., Containment Loss of Coolant Accident (LOCA)).

Page 2 of 12 Revision 0

N02-A6 aCOURSEiNUMBER V AND ITLE: Perform an Initial Dose Assessment REVISION: ~0.

Information I " PP -108E

- - Rev. 4. Page 5 of9 II II I!

,i Initial Dose Assessment I 4.7 Determine the Projected Duration of the Release.

IF the projected duration of the release is unknown, THEN use I hour.

Projected duration of release is unknown. The 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

IF releases are occurring from multiple points, THEN use the projected duration.

longest default will be used.

4.8 Enter the data into the Dose Assessment Program.

The following pages illustrate the Dose Assessment Program screens with the information entered. The "tabs" NOTE: The classifications may change based on the results of the assessment being run and must be updated accordingly prior to submitting the EMD-32a or of the dose assessment may be completed in any order.

EMD-32b forms for transmittal to the state or county. However, the Calculation and Results tabs should be 4.9" IF necessary. THEN update the current classification and Initiating Conditions on viewed last.

the EMD-32a and EMD-32b.

4.10 Submit the EMD-32a and/or EMD-32b to the SEC.

4.11 The SEC approves the EMD-32 form(s).

4.12 Transmit the EMD-32 form(s) to the Berrien County Sheriffs Department and the State of Michigan.

A completed EMD-32a is NOT necessary for successful 5 REFERENCES completion of this JPM.

5.1 Use

References:

5.1.1 Dose Assessment (DAP) Computer Program 5.1.2 EMD-32a, Nuclear Plant Event Notification 5.1.3 EMD-32b, Nuclear Plant Event Technical Data Form 5.2 Writing

References:

5.2.1 Source References

a. Donald C. Cook Nuclear Plant Emergency Plan

b. EPA 400-R-92-001, Manual of Protective Action Guides and Protective Actions for Nuclear Incidents Page 3 of 12 Revision 0

COURSE NUMBER 02-A6 ANDT"!TLE: Perform an Initial Dose Assessment ,REVISION: 0 II II Under the General tab, the student should Select "This is a drill".

The student's name, location, and phone number should be entered.

NOTE: Data entered on this tab is used ONLY to complete the EMD-32a and/or EMD-32b form and does NOT affect the dose assessment calculation.

Page 4 of 12 Revision 0

I COURSE NUMBER

-ANDTITLE:, N02-A6 an Initial Dose Assessment Perform REVISION: 0 II '.

I Rumi. ox Under the Event Classification tab, the student should Enter the current date and time.

I Select Site Area Emergency.

Select Degrading Fission Product Barrier and using the drop down screens select at least one Initiating Condition (EAL) for the classification selected.

NOTE: Data entered on this tab is used ONLY to complete the EMD-32a and/or EMD-32b form and does NOT affect the dose assessment calculation.

Page 5 of 12 Revision 0

COURSE NUMBER, N02-A6 AND'TITLE.:I..

,:i:!:*::!*, ro I. P:i:!1eerform an Initial Dose Assessment II S. . . II

-ox I Under the Plant Status tab, the student should I CT Complete the U2 Rx Status by selecting RX shutdown and entering the current date and time (per brief - 10 minutes prior to making classification.

CT Complete U2 Fuel Status by selecting Normal Coolant per step 4.5 of PMP-2080-EPP-108.

U 1 Rx Status is not applicable for the conditions of this JPM and therefore does not need to be completed per step 4.4 of PMP-2080-EPP-1 08.

Complete Plant Status detail by selecting Stable (or Degrading) and providing justification in the narrative box.

Information here is used only to complete EMD form(s).

CT Complete Release Status by selecting Release in Progress and entering the date and time the release started (per brief - five minutes prior to making classification).

NOTE: Data entered for U2 RX Status, U2 Fuel Status, and Release Status affects the dose assessment calculation.

Page 6 of 12 Revision 0

COURSE NN.UMBER A ND TI TLE: IPerform N02-A6 an Initial Dose Assessment REVISION: 01 II II

Under the Plant Status tab, the student should CT Complete Wind information by entering 10M Main wind speed (4 mph) and wind direction (275-)

provided with the briefing.

CT Complete the Pasquill Category (Stability Class) by selecting the correct classification based on the Delta T (-1.0oF) provided with the briefing.

Complete the Precipitation information using the information provided with the briefing.

Downwind Sectors are selected automatically based on the wind direction entered.

NOTE: Wind and Pasquill Category affect the dose assessment calculation.

Page 7 of 12 !

Revision 0 i*-;*:

i:*i!

i*:

i*::

COURSE:NUMBER N02-A6RE SPerform an Initial Dose Assessment [ 1 J Under the Calc. Basis tab, the student should

- o:**-,*.*CT Enter the current date and time.

4. .. - CT Complete Calculation Basis by verifying Gaseous

i. ... . Release - In Plant Monitor is selected. This enables Up114D1"4 the Gaseous Release tab to enter the applicable

'1A me Radiation Monitor data given with the briefing.

V 4.2,4, (NOTE: Gaseous Release - In Plant Monitor is the rýhW Tm Da ýOffRe oDewRae Djai default selection.)

1Th~

e> ldaoflbasisde min dienneadis used. Seelte

ý.9sn , eahb&b~nlpsedonforspea. NOTE the Field Team tab will NOT be enabled for JPM. Field Team Data must be selected to enable this the Field Team tab.

-..- 7 Complete PAR Basis by verifying Dose Calculation is

. *selected. This section is used to complete the EMD p':*,-

form(s). However, the Dose Assessment Program will

_*,__*.._`*Svc, ONLY generate PAR recommendations based on Dose Calculations. (NOTE: Dose Calculation is the default selection.)

NOTE: Calculation Date and Time and Calculation Basis affect the dose assessment calculation.

Page 8 of 12 Revision 0

ICOURSE-NUMBER N02-A6 Perform an Initial Dose Assessment v,za

!l I

Under the Gaseous rel. tab, the student should I CT Complete the Gaseous Release information by entering the Concentration and Flow Rate (percent open) for the affected radiation monitor(s).

Radiological information is provided with the briefing.

(NOTE: ONLY the reading of the affected monitor(s) is required to be entered.)

NOTE: Gaseous Release affects the dose assessment calculation.

Page 9 of 12 Revision 0

'COURSE NUMBER N02-A6 AND TITLE: Proma nta oeAssmn Sl.uox NO additional information is required under the Additional GeJ Gaw MAW JEtm fii FFS, Womaiaim-sv

~ c~

ýýM T Awht.

W ,

RA~i info tab. This information is used when needed to complete the EMD-32 forms. The student may leave these blank.

Page 10 of 12 Revision 0

I'COURSE NUMBER.ý AND TITLE:

N02-A6 Perform an Initial Dose Assessment REVISION: .0 Ii El II NO entries are made under the Calculation tab. This tab provides information only.

When the tab for the affected radiation monitor(s) is selected, information on the different isotopes involved in the release and their contribution to the dose rate / dose is provided.

Atmospheric dispersion factors are also provided.

Page 11 of 12 Revision 0

COURSE NUMBER N02-A6

!AND TITLE: Perform an Initial Dose Assessment Under the Results tab, the student will find The Calculated Dose Rates, Calculated Dose, and Release Characteristics based on the information entered under the preceding tabs.

The calculated dose rate and dose is used in conjunction with PMP-2080-EPP-101, Emergency Classification to determine Emergency Plan Classification and Protective Action Recommendations.

When required, the operator may recommend evacuation by selecting the affected areas.

12 93 The Dose Assessment Program will automatically il 11I I generate Recommended PAR Evacuation Data when the PAR Basis - Dose Calculation is selected under the Cal Basis tab AND the dose assessment calculation indicates action is necessary. Recommendations generated by the Dose Assessment Program can NOT be changed by the operator.

The EMD-32a and/or EMD-32b forms may be printed as required. (NOT required for this JPM)

CT TEDE SB dose rate = 1.57e+01 mRem/hr (1.25e+01 to 1.89e+01 mRem/hr is acceptable) thyroid CDE SB dose rate = 1.26e+02 mRem/hr (1.00e+02 to 1.52e+02 mRem/hr is acceptable)

JPM IS COMPLETE Page 12 of 12 Revision 0

Task Briefing Given the following:

"* At 06:50 Unit 2 tripped due to a large Steam Generator tube rupture on the Loop 1 Steam Generator.

"* The break flow is estimated at 175 gpm.

"* Due to problems immediately following the trip, all MSIV's were closed.

"* At 06:55 the BOP operator reported that the PORV on the ruptured steam generator is 25%

open and can not be closed.

"* MRA-2601, Stm Gen Loop I PORV Discharge, has a High Alarm.

"* At 07:00 the Shift Manager declares a Site Area Emergency and assumes the role of Site Emergency Coordinator.

"* Current plant conditions are stable.

At 07:00 you are given a print out of the current PPC Dose Assessment Information screen (attached) and directed to perform an initial offsite dose assessment for the conditions described.

When you have completed the initial offsite dose assessment, report the calculated TEDE and Adult thyroid CDE Site Boundary dose rates to the examiner.

N02-A6.doc Page 1 of 2 Revision 0

DOSE ASSESSMENT INFORMATION TAC, In I*.*,T.A. r*l:::*t'*DiDTit"*kl TAQ In MATA nl=Qr'DlDTlnKl VALUE UNITS ERS-2305 RMS052 LOWER CONTNT LOW RNG NGAS - TR A 3.685E-06 gCI/CC ERS-2307 RMS054 LOWER CONTNT MED RNG NGAS - TR A 1.050E-03 #Ct/CC ERS-2309 RMS055 LOWER CONTNT HI RNG NGAS - TR A 2.300E-03 PCI/CC VRA-2310 - RMS056 - UPPER CONTNT HI RNG AREA- TR A 1.0003E+00 R/H VRA-2410 - RMS064 - UPPER CONTNT HI RNG AREA-TR B 1.0003E+00 R/H VRS-2505 - RMS068 - UNIT VENT EFFLUENT LOW RNG NGAS 2.331 E-07 I.lCI/CC VRS-2507 - RMS070 - UNIT VENT EFFLUENT MED RNG NGAS 7.600E-04 ACI/CC VRS-2509 - RMS071 - UNIT VENT EFFLUENT HI RNG NGAS 1.100E-01 VFR-251 0 - RMS072 - UNIT VENT EFFLUENT FLOWRATE 8.327E+04 CFM MRA-2601 - RMS073 - STM GEN LOOP 1 PORV DISCHARGE 1,330E+02 "pCI/CC MRA-2602 - RMS074 - STM GEN LOOP 4 PORV DISCHARGE 8.500E-01 "pCI/CC MRA-2701 - RMS075 - STM GEN LOOP 2 PORV DISCHARGE 1.300E+00 "ACI/CC MRA-2702 - RMS076 - STM GEN LOOP 3 PORV DISCHARGE 8.200E-01 "[CI/CC SRA-2805 - RMS077 - GLAND STM VENT EFFL LOW RNG NGAS 3.352E-06 ptCI/CC SRA-2807 - RMS079 - GLAND STM VENT EFFL MED RNG NGAS 1.090E-03 tC I/CC SRA-2809 - RMS080 - GLAND STM VENT EFFL HI RNG NGAS 1.220E-01 ýtCI/CC SFR-2810 - RMS081 - GLAND STM VENT EFFL FLOWRATE 9.969E+02 CFM SRA-2905 - RMS082 - STM JET AIR EJE EFFL LO RNG NGAS 3.750E-05 ACI/CC SRA-2907 - RMS084 - STM JET AIR EJE EFFL MED RNG NGAS 1.120E-03 I.tCI/CC SRA-2909 - RMS085 - STM JET AIR EJE EFFL HI RNG NGAS 1.520E-01 4CIICC SFR-2910 - RMS082 - STM JET AIR EJE EFFL FLOWRATE 4.011 E+00 CFM ETQ-403 U0802 - DELTA TEMPERATURE - MAIN TOWER -1.0 DEGF EFR-412 U0803 - WIND DIRECTION 10M - MAIN TOWER 275.0 DEG/FROM EFR-402 U0804 - WIND SPEED IOM -MAIN TOWER 4.0 MPH ELR-400 U0805 - PRECIPITATION - MAIN TOWER NO RAIN NONE EFR-413 - U0806 - WIND DIRECTION 1OM - BACKUP TOWER 278,0 DEG/FROM EFR-403 - U0807 - WIND SPEED 1OM - BACKUP TOWER 3.6 MPH EFR-410 - U0808 - WIND DIRECTION 60M - MAIN TOWER 280.0 DEG/FROM EFR-400 - U0809 - WIND SPEED 60M - MAIN TOWER 5.0 MPH NONE - U0810 - STANDARD DEVIATION 10M - MAIN 0.0 DEGREES NONE - U0811 - STANDARD DEVIATION 10M - BACKUP 0.0 DEGREES NONE - U0812 - STANDARD DEVIATION 60M - MAIN 0.0 DEGREES N02-A6.doc Page 2 of 2 Revision 0

14 A7a' TITLE Calculate QPTR with Inoperable Power Range REVION 0 Instrument [ 4 NRC License Exam TIM 15 Minutes 1013/2002:

DEVELOPING Name: S. Pettinger 10/23/2002 INSTRUCTOR: Signature:

OPERATIONS REVIEW: Name: .T. Werk 10/2312002 Signature:

Page 1 of 3

CoURSE NUMBER N02-A7a Calculate QPTR with Inoperable Power REVISI0 AND TITLE: Range Instrument References 02-OHP-4030-STP-032, Quadrant Power Tilt Calculation Task: 0130180201 Perform Quadrant Power Tilt Ratio Calculation K/A CROSS

REFERENCE:

2.1.7 K/A IMPORTANCE: RO 3.7 SRO 4.4 IEvaluation Setting Simulator IHandouts,

,I Task Briefing for N02-A7a Copy of 02-OHP-4030-STP-032 Attachments NI Calibration Data Card Caution Tags (7)

Simulator Setup Initialize to IC 989, with N-42 failed (Malfunction NIt0B, final value 0)

Complete actions of 02-OHP-4022-013-004, Power Range Malfunction:

"* Control Rods in Manual

"* Rod Stop Bypass Selector in N-42 position

"* Selector switches in N-42 Position:

Comparator Channel Defeat Upper Section Detector Current Comparator Defeat Lower Section Detector Current Comparator Defeat Power Mismatch Bypass

"* Recorder inputs NOT selected to N-42:

Delta-T Overtemperature Delta-T

"* Trip OTDT Bistable 2-TS-421C - (MRF RPR 123 Trip)

"* Trip OTDT Runback Rod Stop 2-TS-421D - (MRF RPR 124 Trip)

"* Disconnect Power from N42 - (MRF NIR09 Tripped)

"* Insert override for 2-SML-1 8:2 protection Channel 2 in test (ZLOSTMC2[2] to ON)

"* Verify lit Status lights for 2-SML-16: 2, 27, 32, 42 and 47, 2-SML-17: 7 and 12, and 2-SML-18:2

"* Hang Caution Tags on above selector switches (7)

Page 2 of 3 Revision 0

JTask Objectives/Standards Correctly obtain values and calculates a Quadrant Power Tilt Ratio calculation with one power range channel out-of-service using 02-OHP-4030-STP-032.

EETask Briefing =

Given the following:

"* NI Channel N-42 has failed low

"* All actions of 02-OHP-4022-013-004, Power Range Malfunction have been completed

"* The Plant Process Computer PPC is INOPERABLE The US directs you to perform a manual QPTR calculation per 02-OHP-4030-STP-032, Quadrant Power Tilt Calculation.

Page 3 of 3 Revision 0

.,COURSE NUMBER N02-A7a Calculate QPTR with Inoperable Power Range Instrument REVISION: 0 AND TITLE:.. I,:, I N. !.

Reference 02-OHP 4030.STP.032 Rev. 8a Page3 of I1 General CUEPS QUADRANT POWER TILT RATIO CALCULATION 4 DETAILS 4.1 IF the Plant Process Computer (PPC) calculation for QPTR is OPERABLE, THEN obtain the QPTR as follows:

-CUE:, PPC is inoperable for QPTR calculation 4.1.1 Select Tilting Factors by.

Touch area "Tilting Factors" from NSS Menu

-OR

Typing Turn-On Code "TF" 4.1.2- Enter the Upper and Lower Radial Flux Tilts and the Highest Upper or Lower Radial Flux Tilt on Data Sheet 1, Quadrant Power Tilt Ratio From PPC.

4.2 IF the PPC calculation for QPTR is inoperable OR a manual calculation is desired, THEN calculate QPTR using one of the following:

4.2.1 IF all NIs are OPERABLE, THEN calculate QPTR per Step 4.3 using Data Sheet 2, Quadrant Power Tilt Ratio Calculation Sheet;

-OR 4.2.2 IF any NI is inoperable, THEN calculate QPTR per Step 4.4 using Data Sheet 3, Quadrant Power Tilt Ratio Calculation Sheet Using 3 NIS. Operator determines step 4.4 is correct step 4.3 Calculation of QPTR with all Nis operable:

4.3.1 IF detector currents will be used to obtain power range excore amperages, THEN perform the following:

NOTE: All eight amp meter settings do not need to be on the same scale setting.

a. Select the amp meter scales for maximum resolution.

b. Read AND record each individual NI detector current on Data Sheet 2.

Page 1 of 5 Revision 0

COURSE NUMBER N02-A7a Calculate QPTR with Inoperable Power Range Instrument AND TITLE: .. iI REVISION:

Reference I 02-O01' 4030.STP.032 ] Rev. 8a Page 4 of:

QUADRANT POWER TILT RATIO CALCULATION CAUTION: Fluke readings shall not be taken if bistables are tripped on any power range drawer.

4.3.2 IF a FLUKE will be used to determine QPTR, THEN perform the following:

a. Record instrument number and calibration due date on Data Operator determines steps on this page are not applicable Sheet 2.

b. Set fluke to lowest scale for volts DC.

c. Obtain each individual NI detector voltage AND substitute this voltage for NI detector current on Data Sheet 2.

4.3.3 Enter the individual upper and lower power range 120(/ current values in the appropriate blanks.

4.3.4 Divide the individual NI current by its 12(r/. current value.

4.3.5 Total the normalized values determined in Step 4.3.4.

4.3.6 Using the formula on Data Sheet 2, determine the upper and lower QPTR.

4.3.7 Enter the highest upper OR lower tilt ratio in the space provided on Data Sheet 2.

4.3.8 Obtain the'Maximum QPTR from the Plant Process Computer by performing the following (N/A if the PPC is unavailable or inoperable):

a. Select Tilting Factors by:

. Touch area "Tilting Factors" from NSS Menu

-OR

Typing Turn-On Code"TF" Page 2 of 5 Revision 0

I.

COURSE NUMBER N02-A7a Calculate QPTR with Inoperable Power Range Instrument AND TITLE:,:. REVISION: 0.,.,..

' ' " ~~~IREVISION:.... 0 ""I I Reference 02-OHP 4030.STP.032- 7 Rev. 8a - Page 5 of 11 QUADRANT POWER TILT RATIO CALCULATION rOperator determines this is correct step 4.4 Calculation ofQPTR with one NI inoperable:

-Operator records N-41, 43 and 44 on Data Sheet 3 Upper &

4.4.1 Record the OPERABLE NI numbers inthe appropriate blanks on Lower Detector blanks.

Data Sheet 3.

Note: See Page 5 For expected values (Spreadsheet program 4.42 Obtain power range excore amperages as follows: may be used to verify accuracy of candidate readings and calculations)

All eight amp meter settings do not need to be on the same scale settinj INOTE: Operator should select the 0.1 scale

a. Select the amp meter scales for maximum resolution. A- "CT: Operator records data to within +/- .0005 for indicators

b. Read AND record each individual NI detector current on Data reading on a division mark and within the division marks for all Sheet 3. others. (Enter data into spreadsheet for comparison) 4.43 Enter the individual-upper and lower power range 120% current CT: Operator enters data from cards on channel 3 NI Panel values inthe appropriate blanks on Data Sheet 3.

- - Operator divides respective NI channel with its 120% value (from 4.4.4 Divide each individual NI current by its 120% amperage. cards on channel 3 NI panel) 4.4.5 Total the normalized values determined inStep 4.4.4. 4

-Operator totals 3 channels of normalized values 4.4.6 Using the formula on Data Sheet 2,determine the upper and lower QPP,. CT: Operator determines upper and lower QPTR using data sheet 4.4.7 3 with an accuracy of .01 of Exam Team calculated value (Enter Enter the highest upper OR lower filt ratio inthe space provided on Data Sheet 3. data into spreadsheet for comparison)

Operator enters the highest calculated QPTR (CT: Covered on Page 5 of this section)

Page 3 of 5 Revision 0

COURSE NUMBER. N02-A7a Calculate QPTR with Inoperable Power Range Instrument RVSON 0 AND TITLE:. I Reference I 02-OHP 4030.STP.032 I Rev. Ra I Page 6 of 11 I QUADRANT POWER TILT RATIO CALCULATION 5 ACCEPTANCE CRITERIA 5.1 Acceptance criteria is contained on Data Sheets 1, 2, and 3.

6 CORRECTIVE MEASURES 6.1 IF QPTR exceeds Notification Limit, THEN notify SM and Reactor Engineering 6.2 IF QPTR exceeds Acceptance Criteria, THEN perform the following:

Notify SM and Reactor Engineering.

Enter ACTION Statement ofTech Spec 3.2.4.

7 FINAL CONDITIONS 7.1 The QUADRANT POWER TILT RATIO has been calculated.

Page 4 of 5 Revision 0

COURSE NUMBER N02-A7a Calculate QPTR with Inoperable Power Range Instrument REVISION:. 0 AND TITLE:

Reference 02-OHP 4030.STP.032 Rev. 8a Page 11 of 11' QUADRANT POWER TILT RATIO CALCULATION Data Shet 3 Quadrant Power Tilt Ratio Calculation Sheet Page:

Using 3 NIS 11 Upper Detector Record Detector "A" Current Record Detector "A" 120% value Normalized Value Detector A + 120% value j

.N-0940 .1139 .8253 N- noon 19068 -8209 nN-A MR 190AM FAIM '

Upper Total 2.4643 Lower Record Detector Record Detector Normalized Value Detector "B" Current "B" 120% value Detector B .120%,value N- 4 .0883 .1062 .8333 Data entered on this page based on Simulator readings.

N- 0986 1192 .8272 Enter data into QPTR calculation spreadsheet to determine N- n772A41*79 accuracy of candidate's calculation Lower Total 1 2.4877 Upper Tilt Ratio = Max Upper Normalized Valtie x 3 Upper Total x3

.4 Lower Tilt Ratio = Max Lower LowerNormalized Value Total x 3=

CT: Operator enters the highest calculated QPTR of these 2 Enter the max upper or lower tilt ratio (Calculated QPTR) 1.0049 4 Highest Upper or Lower Radial Flux Tilt from PPC (N/A if unavailable values or inoperable) N/A Verify QPTR Consistent with Incore Detector Readings (N/A if reactor Candidate marks "N/A" power is less that or equal to 75%)

Nuclear Engineering states that QPTR is consistent with Notification Limit: 1.015 Incore Readings.

Acceptance Criteria: Calculated QPTR is less than or equal to 1.02 Candidate Signs, Dates, & enters Time Performed by: Date: Time: Reports task completed.

Reviewed by:

JPM IS COMPLETE.

Date:_____ __

(Supervisor/Manager Signature)

Page 5 of 5 Revision 0

Task Briefing Given the following:

"* NI Channel N-42 has failed low

"* All actions of 02-OHP-4022-013-004, Power Range Malfunction have been completed

"* The Plant Process Computer (PPC) is INOPERABLE The US directs you to perform a manual QPTR calculation per 02-OHP-4030-STP-032, Quadrant Power Tilt Calculation.

N02-A7a.doc Page 1 of 1 Revision 0

N0-Ab',

Determine Actions to Change Containment Integrity Options During Refueling -REVISION 0 NRC License Exam TIME 15 Minutes SDEVELOPING, Name: S. Pettinger 1012412002

-INSTRUCTOR; Signature:

SOPERATIONS REVIEW: Name: 10/24/2002 T. Werk Signature:

Page 1 of 3

COURSE NUMBER N02-A7b - Determine Actions to Change REVISION:

AD* TITLE: Containment Integrity Options During Refueling II SReferences I 01-OHP-4030-127-041, Refueling Integrity Task:0340260202 Verify Containment Penetration Integrity checks prior to Core Alterations K/A CROSS

REFERENCE:

2.2.26 K/A IMPORTANCE: SRO 3.7 Evaluation Setting Classroom/simulator tf Handouts II Task Briefing 01-OHP-4030-127-041 Original Data Sheet 1 CPN-74 pages 113 to 116 01-OHP-4030-127-041 Blank Data Sheet I CPN-74 pages 113 to 116

[ Attachments I None ASimulator Setup I NIA Page 2 of 3

COURSE"NUMBER N02-A7b - Determine Actions to Change AND TITL: Containment Integrity Options During Refueling Task Objectives/Standards Verify alignment of valves during Refueling per 01-OHP-4030-127-041, Refueling Integrity, observing applicable precautions and limitations and procedural steps.

Task Briefing II Given the following:

"* Unit 1 is in Mode 6

"* Core Offload in Progress

"* You are the Unit I Unit Supervisor Panel 104 Drop 33 "CONTAINMENT CTRL AIR HDR PRESSURE LOW" and Panel 124 Drop 30 CNTMT 100 PSI CTRL AIR HDR 2 PRESSURE LOW" Alarms have annunciated.

MTI has investigated and. determined that pressure transmitter 1-XPA- 104 has failed.

01-OHP-4030-127-041, Refueling Integrity is impacted by this failure. Option A was previously chosen for CPN-74(1) on Data Sheet 5 (page 297).

The Shift Manager directs you select a different option per 01-OHP-4030-127-041,Step 4-2-6 and Data Sheet I for CPN-74 (page 113).

The option Chosen must maintain air to Containment and NOT require a Containment Entry.

Page 3 of 3

COURSE NUMBER :I] N02-A7b - Determine Actions to Change Containment Integrity Options During Ro 0 AND TITLE: H lRefueling .EVI S:..:I CONTINUOUS 01-Oli!-4030"-27-041 Rev. O Page 60of3

_ -I General CU.ES:.

Refueling Integrity NOTE: The following sub-step pertains to significant personnel industrial safety risks for tagging of installed components.

WHEN tagging components for the purpose of "installed AND the Shift Manager determines that personnel "Industrial Safety Risk" is significant enough to take exception to tagging the component(s). THEN:

" 'NOT HUNG" shall be entered in the 'TAG HUNG" column on the applicable pages of the Data Sheet

"* Tht reason for NOT HUNG shall he stated on the page

"* The Shift Manager making the determination shall initial in the PERFORMED BY column 4.2.5 Log any out of position component, on penetrations that do not have administrative controls established, on Data Sheet.4, Loss Of Refueling Integrity Log.

a. IF a valve on a control board is out of position. THEN reverse the tag to show it is out of position and lop this valve on Data Sheet 4.

4.2.6 [F it becomes necessary to change the way a penetration is isolated once Refueling Integrity is established. THEN:

a. Obtain prior SRO-CA approval to ensure change will not interfere with CORE ALTERATIONS.

b. Obtain appropriate page from Data Sheet 1.

c. Perform and verify lineup for desired option, I. IF Refueling Integrity is required while chaniging options, THEN ensure it is maintained.

d. Attach new page to front of original page.

e. Check off on original page that the option was changed, and obtain Unit Supervisor signoff of Name. Date and Time.

Page 1 of 6

COURSE NUMBER jJ N02-A7b - Determine Actions to Change Containment Integrity Options During REVISION,.: 0 I AND TITLE: : Refueling II

()COT!NLLO1S 01-01P4030-127-041 Rev. 0 a'gae 297 o- i-'

Refueling Integrity 1I Data Sheet 5 Daily System Parameters Pa-es:

295 3o2 D1ESCRIPTION Ref. Page INSTRUMENT VALUE INITIALS CPTN-75 (2) OPTION A CC\V Flow to Excess Letdown Hx Page 55 I-CFA-459 > 100 gpm CPN-82 (1) OPTION A CCW Flow to Rx Support Cooler Page 57 1-CFA-457 > 20 gpm CPN-82 (2) OPTION A CCW Flow from RX Support Cooler Page 58 1-CFA-456 > 20 gpmn CPN-74 (1) OPTION A ALARM Ann. 104, Drop 33 is Clear Page 113 CLEAR CUE Alarm is no longer valid CPN-74 (1) OPTION C Not Cross Containment Control Air Headers Page 113 tied CPN-29 (1) OPTION A ALARM Ann. 104, Drop 33 is Clear Page 208 CLEAR

('PN-29 (I) OPTION C Not Cross Containitmet Control Air Headers Page 208 tied CPN-29 (2) OPTION A Plant Air Pressure Page 210 1-P1I'-10 > 20 psig NO. I SG OUT-SJDE CONTAINMENT (N/A IF INSIDE CONTAINNIENT UTILIZED)

CPN-6 (I OPTION A WR Level #11 SG Page 223 I-BLI-110 > 5%

CIPN-7 (I i OPTION A WR Level #11 SG Page 224 1-BLI-l 10 > 80%

C'PN-66 0* OPTION A WIR Level #11 SG Page 226 l-BlI-110 > 5q Page 2 of 6

I COURSE NUMBER.I, N02-A7b - Determine Actions to Change Containment Integrity Options During REVISION: 0 I AND TITLE: lRefuelingRESIN

[~m'.ihiL 4fltmri4 "

L)::4

4=*: q CT.'?,L-ai-*ý mlV': . For Ceorc'.,Pcai-!

" Q°-" TAG IMOR.IMLD

(,1" 1m,.) ER.

"",.. . . . UN". BY C 7'- 7-4 4.' cr'c-'c.'c ' cc 4 c cr

t,2ic i , 2-,'

0im aR fN :SI{'A!in c4:~,c rcr:.,c (u'fr, Cb',i 4 'yc,4'r, alcc.OAir c'x' p cr:: .{

r i"'

tc j;;,c ii t ( ticin 4. *.crF wru ii b¢ i** iccd fo }*cu~.

.*ur- 4;i~',, j.a l* vOil,.th"

.. cl Air.. car c-'

Alarm is not Valid nor clear cF

.\4 \4?',4

('LLA

..,1, 1-!-,: 7i4,c3:*

!R

' Alarm is not Valid nor clear

0',a '1)4 . 4.;41',,.1,'

CU4 -Ak

.3';-0 Roo(

CT: Determines that Option C is required Option

' .: . C:. Ai

';5 Verifies that Air headers are not Crosstied CUE: "Proceduralized Temporary Modification Log Index does NOT list Containment Control Air Header crosstie."

Page 3 of 6

I COURSE NUMBER :1*N02-A7b - Determine Actions to Change Containment Integrity Options DuringAND .REVISION: 0.

I AND TITLE: IRefuelingI I

'0' 1 0 - I OT!WO3ft.1 2O-II . p i v'.

m)nRP'nN f.f}. rICXtFf !\li ' I HI \G \ fix V, i.r'.y o1v , .o ]:.',** - CT: Selects one valve and verifies that it cycles Two (2) times 1f' I ,-IPS -*! *b< -*f lv";.:,:

i70. !-G C\A.3S51 1-f.' .IV - .2 I -D K V 10 "2CYC!,[FS Requests that AEO read pressure on 1-XPI-1 86 at CAS panel

-AM)-

Cue : "1-XPI-186 reads 85 psig" prL:*'-ClU Is.*',

4F- -CT: Verifies Pressure is > 75 psig.

A.."..., Requests Refuel Tag to be Hung on 1-XPI-186

` 'P ', .f.I i , .., Cue: "Refuel Tag is Hung on 1-XPI-186"

-1 \'$:;JI 1/

Can Not be used as it requires operations inside containment.

1*0["

N E: (?::*

.1 - ('I (.: , `_7 .11

.) ,,*."!.,,,C.,1tI

-Can Not be used as air would be isolated

- Can Not be used as air would be isolated Page 4 of 6

I COURSE NUMBER N02-A7b - Determine Actions to Change Containment Integrity Options During REVISION: 0 I AND TITLE: Refueling I I:.

! Ncuel* 9 1 -0 If*P-4139- 12%0-vs I'AC

O I'll' " I; B

- Evaluators Note: The following signature should be made on the Original copy of O1-OHP-4030-127-041 Data Sheet 1 page

'1 2 (: 115.

. . , .. CT: Signs, enters Time & Date that CPN Line (1) was changed

2. P r:kvc .1 1F.h I ;*i a): rn 1v F:

r',IFT.)

t1I'T ( haiv "TI N1.1, fDATFl.

"" , S T'q.IN * . * *L!L!

-Signs that CPN-74 Options are Complete on New Copy of 01 I *,; OHP-4030-127-041 Data Sheet 1 page 115 C

Reports task completed.

JPM IS COMPLETE.

Page 5 of 6

0 (D

cIL 0

0 E

C 0

0 0 0 C

L) U)

I

4) 0) 4 0)

I L.

0 0 4-0.

0

Task Briefing Given the following:

"* Unit 1 is in Mode 6

"* Core Offload in Progress

You are the Unit 1 Unit Supervisor Panel 104 Drop 33 "CONTAINMENT CTRL AIR HDR PRESSURE LOW' and Panel 124 Drop 30 CNTMT 100 PSI CTRL AIR HDR 2 PRESSURE LOW" Alarms have annunciated.

MTI has investigated and determined that pressure transmitter 1-XPA-1 04 has failed.

01-OHP-4030-127-041, Refueling Integrity is impacted by this failure. Option A was previously chosen for CPN-74(1) on Data Sheet 5 (page 297).

The Shift Manager directs you select a different option per 01-OHP-4030-1 27-041,Step 4.2.6 and Data Sheet 1 for CPN-74 (page 113).

The option Chosen must maintain air to Containment and NOT require a Containment Entry.

N02-A7b.doc Page 1 of 1

11. N 8;7 TITLE Verify a Clearance REVISION! 0 PROGRA.:*: NRC License Examination TIME 20 Minutes I ....

.I DEVELOPING Name: Dale J. Frie 10/29/02 INSTRUCTOR: Signature:

OPERATIONS REVIEW:.* Name:

JT. Werk 10/29/02 Signature:

Page 1 of 3

COURSE NUMBER' a REVISION: 002-A AND TTLE: Verify a Clearance Permit IIREFERENCES 12-OHP-2110-CPS-001 Clearance Permit System Task: 3000040201 Verify a Clearance Permit.

K/A CROSS

REFERENCE:

2.?-13 K/A IMPORTANCE: SRO 3.-

SEvaluation Setting Classroom/Simulator I Handouts Task Briefing Clearance Package (Forms, Cards (4), & Prints OP-2-5113-71, OP-2-98721-7, OP-2-98415-47)

ATTACHMENTS 12-OHP-21 10-CPS-001 Attachment 3, Clearance Development Checklist - Verifier SIM,uLAOR SETUP None Page 2 of 3

ITaskStandards I The Candidate performs a review as per 12-OHP-2110-CPS-001 Attachment 3 and determines that the clearance is improperly sequenced and that tags should be required for the breaker and control power fuses.

Task Briefing II The Clearance Control Group Supervisor directs you to verify the 2E Essential Service Water (ESW)

Pump Clearance #2011795 per 12-OHP-21 10-CPS-001 Attachment 3.

The Clearance was written from a directly generated Clearance Request.

There is no Job Order Activity.

The Clearance was not written from a Standard Clearance.

The Clearance does not fit into the boundaries of an existing Clearance.

Page 3 of 3

COURSE NUMBER. N02-A8 REVISION:. 3.

AND TITLE : Verif a Clearance Permit

].eiyaClearance Permit (* i*i Jtfojrmatti~n ]12-OT1P-2t ]0..CPS-00ti . Rei'. 4 Pae'e31 of 41 k

OmnClerace Permit Sytelu For those checks that are not necessary for this Clearance,

. 3 C.ara~nce Devclopme Chi PFelas:

i.e. the checks without arrows, accept any trainee comment.

"C'.ia checkisr is to tie used aPan aid in Clearance devclopment and is not inwnded to be a cot prh:i taVC l:it.

Clearance Developmerti Checklist - VERIFIER ACTIVITY CI-ECKS Trainee determines that there are no support equipment U IOA duscrriptil: check unit desigaiadon. Cicarancc. type (RtV$d"StripWd).

KIad removed from service by this Clearance.

4 Dous amivvy fil wMtili the htvlda"tics of an existing Cle.arance?

NOTE: Trainee may interpret that the Control Switch should be in 'Pull To Lock' and Control Power Fuses CLEARANCE CHUlCKS S'G writtct. from a standard./

ei.a~nce should be 'Pulled' before the Breaker is racked to Disconnect at this point. IF so, this meets the standard for U Spccia" i 'ttr to px'laihi ' hV spccial b, were choswn Main cquipmeum removed betore s* pofr proper sequencing of tags.

4..J 1 e ,~in*:nttI Integrity mnaintained r PepcVITy -,cNlCed toj prevent: =0 aucn-ation's and mini;ni e retracing of steps A c~rfiict cher.~ .sort, Tags promIedl labtled (Rcd-Striped-CautionlRed Stripe].

1 rihnts sIon. blound':,tres ad Clearance points

.J PMrirs verified via NDIS CT: Trainee determines that the Control Switch and the

.. UMan. ax approval ftr Uncontrolled Drawings Breaker are improperly sequenced.

CT: Trainee determines that the Control Power Fuses and the Breaker should be "RED" tagged instead of "NO" tagged.

Page 1 of 2

.COURSE. NUMBERý. N02-A8 REVI ISION: 3

AND TITLE:

_ ~].Ve1~rify a Clearance Permit

[ ILVforJflft&o -- 2-O1TP-210--CP.--1 _ .Pa_.

For those checks that are not necessary for the Clearance, Clearance Permit Sy**en accept any trainee comment.

iAt;a chn rt3 I Clearance Development Checklist-Verifier Pageýs 33 - 34 MECHANICAL ELECtRICAL

-i Low e < I0 p1 g <0

<lry < 30 '*' U Any electric plant liitaions Evaluator Note: HSD Panel Switches are the 201 switches.

JL Steam side of trwp isolated fins J Remote switches ott HSD Panel

A.1li*_ es, ýide of pumped syste*vs isolated first and odler uRit

",J Do tmso,.! have .ýea water D.2Onelag tper ifted lead A A! kct o.ic 'e*\t and/or drait tagged open, if U Motolr Heater power CT: Trainee determines Control Switch, Fuses, and U Bvfre-ker cleanillg Uaps U (Chelk dra:;ns that tie nao a common header UAit-eate power Breaker need to be properly sequenced and RED tagged.

L-1 fa.nnrn; noinfiei if drain hoses affectintm HELB SControl switch, ftiscs, breaker& NOTE: This may have been previously determined J Ground Clearance separcte

.- Preco' rLanaiLoiate urocets flow U Induced power (FT's) on page 33 of the checklist.

'a Tia-zardonas liquids and solids 41 Grounds required when working on electri'al circuits > 6WO volts CUE: When the Trainee completes the ELECTRICAL portion of the checklist announce, FIRE PROTECTION J iNSTRUMENTATION JPM IS COMPLETE.

U3 MP .M'29* . ,-*

$l Work Management Acivity Q Control Air isulated pl9cinig Ptrocess F Failure position U .- p.t..ih R D Auto star, signals

, l)oeu'.n n turn counts on Piacement and Rcýjtc Pccieil Instrution.,_______

ADMIN foritcrit kr ducting iufrqendyperfomnn-d tic tests or evolution.z: PMI-4090

'U Ee, ini.i:ti'twd PMP 4030.EIS.'oi

].irveillanee

.i Rakin- 42V breakers 12-OlP 42 1,082.0,09 JI .ar-,knig 6-iO VAC .ha-ktrs 12-O(4HP 4f021.082.009

JP: ýkez ("citu1 PMP 22"41 .PMTO0J

!No-p*J;I) '."undary -- t2-OIP .! ti.CPSAY.0I. Da Sheet 5

- 1'110P 291 .LR,,91 , On-Lirne Risk< Managerent "j PMP ,1i(W! ;)DR10,0 Vi na SIutdtwa d ,*;fy ad R1sk Mange , [nEiz Q) TIe v'erificaiion of the bou&rieikire. n dependent and not influeneed b, rhe writer. ,

_________________________________________________1 Page 2 of 2

Task Briefing The Clearance Control Group Supervisor directs you to verify the 2E Essential Service Water (ESW)

Pump Clearance #2011795 per 12-OHP-21 10-CPS-001 Attachment 3.

The Clearance was written from a directly generated Clearance Request.

There is no Job Order Activity.

The Clearance was not written from a Standard Clearance.

The Clearance does not fit into the boundaries of an existing Clearance.

N02-A8.doc Page 1 of 1 Revision 0

II iA TITLE Reviewing Liquid Release (Alternate Path)

[.*ROG"M;...j NRC License Exam TIME 15 Minutes I .DEVELOPING-O::,

INSTRUT' Name:

Signature:

S. Pettinger 9/7102 I PERATIONS iREIEWS ' Name:

IT Werk~

Signature:

ley /Oz Page 1 of 3

C<OU'U..RSE` ýNUM BER N02-A9 AND TTLE: Review Liquid Release (Faulted)

REVISION: 0 References 12-OHP-4021-006-004, Transferring Distillate From Monitor Tanks PMP-6010-OSD-001, Offsite Dose Calculation Manual Task: 0230140102 Verify releases comply with the Offsite Dose Calculation Manual.

0060220103 Authorize a radioactive liquid release to the Circulating Water System.

K/A CROSS

REFERENCE:

2.3.6 K/A IMPORTANCE: SRO 3.1 RO 2.1 EvaluationSetting _

Classroom / Simulator LHandouts Task Briefing Prepared Release Package:

12-OHP-4021-006-004, Transferring Distillate From Monitor Tanks:

Attachment 3, Monitor Tank Release To The Circ. Water System Data Sheets 1, Monitor Tank Release Permit Lineup Sheet 3, Monitor Tank No. 3 Recirc Valve Lineup Line up Sheet 7, Monitor Tank No. 3 Release Valve Lineup

, Liquid Release Worksheet (1)

!1Available References

PMP-6010-OSD-001, Offsite Dose Calculation Manual Simulator Setup N/A Page 2 of 3

COURIS:-N.:1E NUMBER N02-A9 I SION: 0 A!NDTITLE: i Review Liquid Release (Faulted)

[tTask Id~Objectives/Standards

~ tifyi gýen c nd ti s ta t would r vnauh rzto falqi ee s n a c r a c ih Se Identifying 4.5.4 conditions that would Transferring of 12-OHP-4021-006-004, prevent authorization of a liquid release in accordance with Step Distillate From Monitor Tanks.

Task Briefing Given the following conditions:

You are the WCC/SRO

Both units are at 100% power

All Circulating Water Pumps are running in

Both units Circulating Water Systems are inboth units their normal alignment

" All condenser water box halves are in service

"* Neither unit is in De-Ice Mode

RRS-1001, Liquid waste Effluent Monitor is

Monitor Tank # 3 is ready to be released to INOPERABLE the Unit 2 circulating water system.

, The monitor tank release package is ready for your review and authorization.

Authorize monitor tank release (L-02-75) in accordance Transferring Distillate From Monitor Tanks. Be with Step 4.5.4 of 12-OHP-4021_006_004, sure to mark any (and all) conditions that would prevent authorization of this release.

Page 3 of 3

I COURSE: NUMBER. N02dA9 RREVISION: 01.

TTLE:

AND Review Liquid Release (Faulted)

MONITOR TANK NO. RELEASE NO.

4.5 Align Monitor Tank to be released:

4.5.1 Complete applicable release lineup sheet (4):

ol . Lineup Sheet 5, Monitor Tank No. I Release Valve Lineup "OLineup Sheet 6, Monitor Tank No. 2 Release Valve Lineup CT - Identifies that the discharge alignment was NOT indJp.endent "o Lineup Sheet 7, Monitor Tank No. 3 Release Valve Lineup -verified by twI (different) operators for CW (Circ Water) valves o Lineup Sheet 8,.Monitor Tank No. 4 Release Valve Lineup located in the Turb Bldg on first page (page 53) of Lineup Sheet 7 4.5.2 Verify release number has been entered on each page of Lineup (i.e., 1-CW-123, 1-CW-124, 2-CW-123, 2-CW-124).

sheet.

4.5.3 Document release flowpath in Section 3.0 of Data Sheet 1.

4.5.4 Obtain SM/WCC-SRO authorization for release:

Applicable Release Valve Lineup sheet is complete. CT - Identifies that iwa independent samples were NOT performed

-as only on LIQUID RELEASE WORKSHEET form is included in

Plant conditions requir&l for a radioactive release, as specified by ODCM, have been met. the release package.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months have NOT elapsed since Chemistry approval for release.

Time: __ Date:

SM/WCC SRO Identifies that greater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months has elapsed since chemistry 4.6 Request RP Tech perform the following: approved the release (Data Sheet 1, Section 2, Chemistry Approval 4.6.1 Enter RRS-1001 High Alarm setpoint (Section 2 - Data Sheet 1).

Date/Time (Sample: 11/21/02 @ 0601, Exam: 11/22/02 after 0700)

RP Tech OPS Cue.: If the candidate asks, the current time is as-is (real time).

4.6.2 Verify two previous Ten Minute Averages are Normal for RRS-1001.

-_T;;i oPs 4.6.3 Verify parameter files for all RRS-1000 channels are correct.

[Ref. 7.2.1i.3]

cua: Reports task completed.

SRP Tech JPM IS COMPLETE.

Page 1 of I

Task Briefing Given the following conditions:

You are the WCC/SRO

Both units are at 100% power

All Circulating Water Pumps are running in both units

Both units Circulating Water Systems are in their normal alignment

"* All condenser water box halves are in service

"* Neither unit is in De-Ice Mode

RRS-1001, Liquid waste Effluent Monitor is INOPERABLE

Monitor Tank # 3 is ready to be released to the Unit 2 circulating water system.

The monitor tank release package is ready for your review and authorization.

Authorize monitor tank release (L-02-75) in accordance with Step 4.5.4 of 12-OHP-4021-006-004, Transferring Distillate From Monitor Tanks. Be sure to mark any (and all) conditions that would prevent authorization of this release.

N02-A9.doc Page 1 of 1

N102AO TITLE..- Emergency Plan Classification with PAR

ý:.R*;66RAW.. NRC License Exam TIME i 15 Minutes DEVELOIN Name: Dale Tidwell 9/7102 iINST RUCTORI: Signature:

OPgRATIONS RE VIEW:... Name: T. Weirike Signature:

7--Vsýý -qi q17-Page 1 of 3 Revision 0

REFERENCES i Procedure: PMP-2080-EPP-101 revision 3b, Emergency Classification Task: EPP0020703, Classify an Emergency Condition K/A CROSS

REFERENCE:

2.4.41 KIA IMPORTANCE: SRO 4.1 RO 2.3 Procedure: PMP-2080-EPP-100 revision 0, Emergency Response Task EPP0120703, Develop a Protective Action Recommendation K/A CROSS

REFERENCE:

2.4.44 K/A IMPORTANCE: SRO 4.0 RO 2.1 I..EVALUATION SETTING Classroom or office U HANDOUTS Task Briefing ATTACHMENTS None SIMULATOR SETUP None Page 2 of 3 Revision 0

COURSE NUMBER N02-AlO ANDTITLE: Emergency Plan Classification with PAR REVISION: 0.:.'

IL TASK OBJECTIVES/STANDARDS Terminal Objectives:

1. In accordance with procedures, and with an independent assessment from the STA, when an emergency event has occurred or changed, the operator will be able to:

1. Classify an Emergency Condition

2. Change an Emergency Classification based on plant conditions.

3. Develop a Protective Action Recommendation Enabling Obiectives

1. Given a narrative description of a plant condition, an applicable list of plant parameters, and a copy of Emergency Plan Procedure (PMP-2080-EPP-1 01), demonstrate the ability to classify the emergency within 10 minutes.

2. Given a brief event scenario and a copy of PMP 2080. EPP. 100 (Initial Emergency Response) determine the appropriate Protective Action Recommendation.

IF. TASK BRIEFING You are the shift manager. A complete loss of AC power has occurred and it is expected to take at least 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months to restore AC power.

Inform the examiner of the Emergency Classification of this event and any applicable Protective Action Recommendations.

Assume the weather is fair with the wind from 300Qat 4 mph and NO offsite release is occurring.

Page 3 of 3 Revision 0

COURSE NUMB.ER N02-AIO AND TITLE: Emer ency Plan Claissification with PAR ;REVISION:

The trainee should refer to PMP-2080-EPP-1 01, Emergency Classification, Attachment 1, page 15 of 114.

CT The classification for this event is "General Emergency" Pages 88 and 89 should be referred to for the basis of the General Emergency classification (next 2 pages).

Page 1 of 6 Revision 0

COURSE NUMBER. N02-AlI0 AND TITLE: Emergency Plan Classification with PARREION0

IINIuc

-PP-2080.iPI'. i 1 Re.' 3b X of 11-4S Eniergenct- CLA.SSlFIGXTj0N Hasis For D-nui-g~rncy Ac~ion Levels Pafsv,.

f Commriuzient: 6489) 22 - 114

~3

(.ii~l~.'NANME. f2MFRGFhN7CY CL.ASS, AND DESCRI1PTIOII S2.2 GLNELR~.-U C'NiflIGECNCY - LOSS OF AC POWER iN I FLIATNG C.ONDITION I'~loso. 1ALL 1.fir IzFiajwt- and ALL oniz AC r-)vwcr to essential bwcs

[Al T IU~rIIOA)VAIT.I :

I;ý o" 'ktin ;-.I 'he tIo1Iowing T-hu.ý.s (in a unit AND Core~ Cooijng' CSFST Ls ORANC;F,

a. T! i A. TH D iUnjit1

-ORZ I'. T21A1%.2 *1) ( U Iit 21 I 'w~ of botl of Elie ftlIlo- in,-! T-hu~sea dhat is cxpcwY it:, for > 4 hus j; T II A, T" 1) tl.jni; 1)

-OR h 11,2.LA,TnI1)k"Iuit 2) i4& (-V~-l) l~.,iofai~:.of at Uast m,n emer5 ?ers bus..within four (4) Jiolji is. not liaely.

~C '.~vc;(it! IiiS- llplant afc:v syx-:1onmsrcirnrliliz clci:tri powvr Incluc-igs Rti-R 1'~C, 5

~iti.~n I -s 1.aov~al and I'SWi. P--,AoL-ssd loss of all AC nowut r iild lcid m, hoa of AfT- NJIt'.(-l" 1:1..d. zIarJ- R). 19"041 C;-'k Nu~k.,; plazil 'alls wihirr the four hour sirarrori 1 15-.tl4'(1 -ious

".7 -o'~s. is;iii.i evvw amdlii that lr .4 a101 I I Fmenuscn~ cv jr Page 2 of 6 Revision 0

COURSE NUMBER..- N02-AIO AND TITLE: Emergency Plan Classification with PAR :.-REVIS.ION:. 0 Emcmwrncv CL ASSI1FICA'TION

- ~ ~ ~ A,.-~n a,.F~

s nc CUYA ti e mis. Ici, s-l. i, w ý.ý.. t I..: , a .i ,od'nlaitý'sr tc i hr-ts .am produc. Barrier :iisdhat C t ni, a l a~sayt Ia.1 hL icit:a1,:.al C rtr.tiattb t cnrtvcnizy iau , hould be l-ata.cdo~n a reatI1aoc zpprahial of SLit

,0" ;a nif.~ U ad ecsi, rs. i.t~ a :ia Lseelo ing 0th, ascnt culId.

-j LiC.IN;ATION RjiEaCRi-iI taaaeaa.

.... .. ~ ar~he aacrsaply usslalcl tw l. FSF . aýmtblmhitd itat,e and aatiae DENX I ATICK N t liOM,, 'ftMARtC; ltIi,.I laaiI

'I ' i~acai tcsatal ataaw atc, r dlaw ,.,o1-o f a a-niitesan etea Cac Page 3 of 6 Revision 0

COURSE NUMBER N02-AIO AND TITL-t: Emergency Plan Classification with PARREION0 Euiaerttcncy Respons'e tsNict aiCoxutrs' Room Operattor to make the tflkywiitg anhtotlceninit to~r the appropriatie ERO faciliky(s) it, he activated, over the PA system. ia-ve the amoum~enient

-Attentioni all pers,1nnel0. Attention all personniel. The Unustial Ev ent is still hinivlect.. housever repixrt to tand~

aulh ate the 4cTehkl :feýnil Sup ort C te.-rC_ý rtiC%2_ty.rainvr F( cihlr. All other plantt piersotnnel fie prepared for further atiniiuaiecluents."

On anY tucloh-10 Telophione:

. Wait fol th10 tone

. Pier~s Ili? to reces%thet Trajnino- Cenwtr and B~uchanan Ofihe. lisilditot 'PA

. Rpcl)at tlr, above annoumtemcnr twice tIa

-'.7 Giene-rd a oere has heen &es.lared, THEN direct the ettn Rconinndaio de~kh~~elt f; rotctve U~fl~tkA General Emergency requires a protective action r.Prior to tievelophio a PAR consider whethec- the folio-oving recommendation be made to the state.

coould h-:ýse an- effec;t ontthe PAR:

-A forzceas of ubitngoits- weather conditions.

c:teclaraictcrjsiesl~ fpuff N's.crntiruoos)

P~aesttootilneý pr Aitsohineta; 3 of I E'P3t5rr-(clie~t\eAt 1%,l.Ju.. ,t'h JevatEIotis *fromt ihe PAR flosx chart, At\tacholef~tit in dii; mstepit) the prorett:ive .action recnsJoinw! ron..

Page 4 of 6 Revision 0

COURSE NUMBER. N02-AIO AND TITLE: Emergency Plan Classification with PAR REVISION: 0

Rdercnt. ~~PA1P-208(0-EL1111 )IOC________L... Pg r2 Ob[tain the follncvtnc data:

Wind___________________ Wind direction and speed is given in briefing. Wind is from AND - 30Q1 o at 4 mph.

DAP or actual oftsile dose;4rate nlt5Jrwenttsl~. Per briefing, NO ofierelease is occurring.

d. Using Atutchment 1, dete-rinine the appnortt aze PAR. Next page.

e. Enter the Protective Ac-tion Receimneiijdation ont the Nuclear Hamt Accidcat Not~ification forin, obtiinied froma the

)mrcnvI*

it and inforot the State ud Mjehigarn Of the rec ,nntedatonininiediately.

f. Pc-peat Steps .27athrotuig 3.-'1..e every 15 minutes Or asý,

tedtm-csted Until refleved bv th;e ineurning Emergency Responie 3.2. IlcPt form n iitiga ltiO 'fC~ition in accordanice with approprialt: plznr 3.2. 9 IF tePa Process Catxtp-nwr (PQC is inoper-aale THEN, D esi~jtentt somvtwct to complere Data Shee(t 1 , Tvchnideal rnainShve:t. evcry 1:5 mintutes.

Pi ,,w;,zd 1ttý cotttpieteIi Copy to dli, "IS..

F

-Cotainue this'activity tor the duration of the en-iercrncy or witij ithv P1-c' i-, operableI.

3.210 I'nccti itbihtyresukt'ý idfmtil%- a missing person(s) AND the

'ISC iand OSA are NOT activate~d, TIJE1LN hjave Secuirity attemp, io hioca-c [he nikstna pcIscinis ' per P1MP-20815-EIIP- 103,

.A!.scniibly', Aceoittahi~itv, wnd E~vacuation of' Pe-rsornnel.

I..1 UIN -n arris,-tl vf t~c toncoming SEC condut~- a aut timer ats follovvs:

a.Obtain a cepy oi'Data -Sheta 2. Emetr.,ency Turnove, Page 5 of 6 Revision 0

COURSE NUMBER. N02-AIO AND TITLE: I Emergency Plan Classification with PAR JREV 0 I

CT Protective Action Recommendation is to evacuate areas 1, 2, and Wind is from 3000. Downwind sector is F and adjacent sectors are sectors E and G.

CT Even though there is NO offsite release occurring, a protective action recommendation is still required based on the General Emergency classification.

Student informs examiner that this event is classified as a General Emergency with a Protective Action Recommendation to evacuate areas 1, 2, and 3.

JPM IS COMPLETE Page 6 of 6 Revision 0

Task Briefing You are the shift manager. A complete loss of AC power has occurred and it is expected to take at least 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months to restore AC power.

Inform the examiner of the Emergency Classification of this event and any applicable Protective Action Recommendations.

Assume the weather is fair with the wind from 300Qat 4 mph and NO offsite release is occurring.

N02-A10.doc Page 1 of 1 Revision 0

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