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 PROGRAM INRC License Exam REVISION 0

TIME 15 Minutes DEVELOPING Name:

INSTRUCTOR:

Signature:

OPRATIONS REVIEW:

Name:

Signature:

S. Pettinger 10/23/2002 ST.

Werk 10/23/2002 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:

Cond enA-P_

WTX-106 = 71.8 WTX-107 = 71.8 WTX-108 = 72.2 WTX-102 = 77.1 WTX-103 = 77.4 WTX-104 = 76.8 CXondenser WTX-206 = 77.2 WTX-207 = 77.1 WTX-208 77.3 WTX-202 = 76.9 WTX-203 776.9 WTX-204 = 77.0 WTX-306 = 77.1 WTX-307 = 77.0 WTX-308 = 77.0 WTX-302 = 71.2 WTX-303 = 70.9 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 Data Sheet 5 Shift Surveillance Checks Modes 5, 6 and Defuelede Pages:

I 1

70 -83 Instrument Title & No.

00-08 1 08-16 1 16-24 1 Acceptance Criterion IIValue Value Value

- 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:

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 E IF recorder is energized and estnoent uncertainty) the printer is inoperable, OR THEN take readings from Step 14.2 - less then or THENt ae r g f0 equal to 76.80F the PPC, U0200.

(i.e., 77.8 +/- V*F insurment unceta-tuty for M&TE

- OR -

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

14.2 IF Circ Water Temp is greater than or equal to 721F OR V the OUnt is in MODE 6 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 4

Instrument make/model:

-AND---

Current calibration Y/N_

Cir Wtr Temp 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.

Condenser A Cire Water Inlet:'

Check box for inlet measured:

O WTX-106 or O WTX-107 or O WTX-108 or O WTX-102 or o WTX-103 or o WTX-104 J

Ul 0 U2 r T

o v-env-of irradiated u until either of the following conditions are met:

Cire Wi Temp.is sep 14.1 ) OR *76

DecayTime is greater than 148 hrs.

C4 C8 C8 4

4 General CUES7 If requested then provide OP-2-5119A, CW System (P&ID)

Step is N/A due to Temperature Indicator Problems I Enters Instrument ID & Make/Model from briefing Sheet

-- Marks "Y" for Calibration is Current

-t-Checks "U2" Box C4 - CT:Checks one of these boxes and

-enters corresponding temperature.

WTX-102 = 771 WTX-103 = 774 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 C4 CT: Checks one of these boxes and I..enters corresponding temperature.

WTX-206 = 772 W7X-207= 771 WTX-208 = 773 WTX-202 = 76.9 WTX-203 = 76.9 WTX-204 = 770 CT: Checks one of these boxes and

enters corresponding temperature.

Instrument Title & No.

00-08 08-16 16-24 Aron Value Value Value 14.0 U1IO U2 Cont Condenser B Cire Water Inlet:,

Check box for inlet measur e o WVX-206 or o WTX-207 or O WTX-208 or OF Ot I

F Q WTX-202 or O WTX-203 or o WTX-204 Condenser C Circ Water Inlet:*

Check box for inlet ueasured:

O WTX-306 or 0 WTX-307 or J p

-F 0F 1O WTX-302 or Q WTX-303 or 0 WTX-304 (Cond. A+B+C IF) / 3 IF

'F 15.0 Record current MODE*

Per Technical Specification Table 1.1, Operational Modes:

Page 2 of 2 Revision 0 WTX-306 = 771 WTX-307= 770 WTX-308 = 770

- CT: Enters average of the three temperatures entered in boxes above in first Box (value should be between 76.9 °F - 77.3 oF)

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.

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 Inlet Temp WTX-207 77.1 B Condenser South Inlet Temp WTX-208 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 S..

.x.......

c.,,,

i; *

'ir*

T IL T~

T 43 1T T)

T OW N nfT9 L D

C Condenser South Inlet Temp WTX-307 77.0 C Condenser South Inlet Temp WTX-308 77.0 C Condenser North Inlet Temp WTX-302 71.2 C Condenser North Inlet Temp WTX-303 70.9 (C CondenserqNorth Inlet Tomp WT-304 771.

C Condenser North Inlet Temnp WTX-304

-71.3 A Conense I

SotIInlet WTX-107 71.8 A Condenser South Inlet Temp WTX-107 71.8 A Condenser South Inlet Temp WTX-108 72.2 A Condenser North Inlet Temp WTX-102 77.1 A Condenser North Inlet Temp WTX-103 77.4 A Condenser North Inlet Temp

.WTX-1 04

.76.8 North Temperatures are valid South Temperatures are valid C CnndAnr !nsith Inkt Thmn Page 1 of 1 Revision 0 A (rnntia~n*=r qr%"th Inlof÷ Tg-ar

\\A/TY_4 t3*

"74 Q

\\^/TY_'*n*

77

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:

WTX-106 = 71.8 WTX-107 =.71.8 WTX-108 = 72.2 WTX-102 = 77.1 WTX-103 = 77.4 WTX-104 = 76.8 Condens =R77 WTX-206 = 77.2 WTX-207 = 77.1 WTX-208 77.3 WTX-202 = 76.9 WTX-203 776.9 WTX-204 =77.0 CondefLne_ C WTX-306 = 77.1 WTX-307 = 77.0 WTX-308 = 77.0 WTX-302 = 71.2 WTX-303 = 70.9 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 "Movement

'PROGRAM-NRC License Exam Name:

Signature:

REVISION 0

TIME.

15 Minutes S. Pettinger 2J 10/23/2002 OPERATIONS REVIEW.:

Name:

Signature:

/T. Werk 10/23/2002 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)

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.

4.2 Check the following lights are lit on AUDIO COUNT RATE CHANNEL drawer:

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

4.4 Place SAMPLING MODE selector switch in the following positions:

COUNT position on DISPLAY side SEC position on PRESET side 4.5 Volume control may be adjusted during sampling to any position that results in a comfortable volume for the audible count rate.

General CUES7

-Operator checks the scaler timer "POWER" toggle switch in the "UP" position Operator checks lights lit I CT: Operator places Channel Selector switch in "SRN32" position CT: Operator places sampling mode switch in "COUNT/SEC" position

-Operator checks "VOLUME" switch in any position 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.

Position thumbwheels to 00600 or other value as desired.

Place SAMPLING MODE toggle switch in AUTO.

Press the following pushbuttons:

4.8.1 STOP 4.8.2 RESET 4.8.3 START Check GATE light is lit.

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

Place AUDIO MULTIPLIER switch in a position that results in a distinguishable gap between counts. (This step N/A if source range detectors are deenergized)

Verify count rate indication is audible in the following [Ref. 7.2.1a]:

Control Room (This step N/A if source range detectors are deenergized)

Containment (Mode 6 only)

CUE: If asked, as US request time value of 60 seconds.

CT: Operator sets thumbwheels to 00600 Operator checks sampling mode toggle switch in "AUTO" position Operator depresses the pushbuttons CT: the "START" is the critical portion of this step Operator checks gate light lit Operator adjusts audio multiplier switch to produce a distinguishable gap in audio output of about 5 seconds Operator determines Containment Counts are audible by requesting report from operator in Containment.

CUE : A Beeping sound is heard in Containment.

Reports task completed.

JPM IS COMPLETE.

Page 2 of 2 Revision 0 4.6 4.7 4.8 4.9 4.10 4.11

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 DEVELOPING Name:

INSTRUCTOR:

Signature:

OPERATiONSýS REVIEW:

Name:

Signature:

S.Pettinger DAT3100 10/23/2002 10123/2002 T. Werk Page 1 of 2

COURSE NUMBER N02-A2 - Determine the Requirements for REVISION: 0 0 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:

Page 1 of 2 ir

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 - 1st 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 PR[OGRM NRC License Exam DEVELOPING

,INSTRUCTOR:

OPERATIONS REVIEW:

Name:

Signature:

Name:

Signature:

0 25 Minutes S. Pettinger SI

,*=

10/23/2002 10/23/2002 T. Werk 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 11 Handouts 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:, 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 ANNUNCIATOR #139 RESPONSE: RADIATION RADIOACTIVE LIQUID EFFLUENT INIT-ATING DEVICE(S)

NOMINAL AEP_

Alias SETPOINT CHANNEL ID:

RRS-1001 High Radiation (Channel 1 Monitor) Channel Failure RRR-1002 Low sample or effluent flow RRS-1000 (Channel 2 Monitor)

(if initialized)

Mnnior AarmSet 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 General CUES1 No cues on this page - operator actions start on next page.

Page 1 of 4

COURSE NUMBER N02-A3 REVISION: 0 AND TITLE:

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

16 (31.

TCACTION(S):

i, I

i r

\\V.Cf Pump nd M nfir Tank P.ni:

I Alarm nn RPS-100kCY

,rip-s cdoyed RRV-25-,

Ch-an,:! 1ail ure

,on RRS-1001. RRIO-10C.2.

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

3 OPERAT['OR ACT ION(S):

3 1 ciii.' cunilcO 110 'millie a.: on, (Y.

4 1 2 IF Hieih Alarm e,:',ts on RS-!001. 'i THEN perform thu folivo inn:

a.

V:rif\\ Tank 1w ins dichiroe has hoern sanphe and apprveIwd tor vif kn biq.,g dischanret c beis '

t illed.

c.

Netify R" AND ruest Cheisk'y sampe

d.

11: ntes. ar:., THEN re!.-leat process.

'.1.3 IF; Chian Failur ei eu ists. IITEN isoat tansk.

1" 11:np Fjou, ifi-

.!.Lo-,. 1THEN rn-cJU:;.-., fl::.-;" to vifii i v~

1

,*.IS

,l 1

1-- 021.1- 00-(l4. 'imr.ufcrrjn.., Dis:illate fr-o Monmtor Tanks.

tId-, ail'.d cha:reii AND refer to TS Tables.

adi 23.3-6 6r "TS 1

.. 6.

(It afnropriae Action Snaleini.

2 ut tOste aflected channel(s) to Normal, IF chunncl is in,-oai]. THIEN refter to 21 1-40Yj--11S-Wl,.

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

411' 1,.*!;u e Page 53 of' 95 R,,v. l0a Candidate may approach DAM and verify that the Red Light on top is flashing.

CUE: 12-RRV-285, red light lit and green light is dark CT Student should simulate taking switch for 12-RRV-285 to the Close position.

CUE: "Switch clicks into place, red light is dark and green light is lit' Candidate should place Control Switch for South Monitor Tank Pump in Trip CUE: "Switch clicks into place, red light is dark and green light is lit "Checks Data Sheet 1 for Correct Tank Number and Approvals.

Reviews Lineup Sheet 7 to ensure tank is not being filled.

CUE: "Valves are in positions as indicated by lineup sheet 7" (Evaluator Note: Candidate may want to physically check 12-CS-267-3 CVCS Monitor Tank 12-TK-14-3 Inlet Valve instead 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 "Notify RP & request another tank sample from Chemistry.

CUE: "Control Room has notified Radiation Protection and Chemistry. The Unit Supervisor requests that you close out release paperwork Attachment 3, Steps 4.13 through 4.16."

Page 2 of 4

ý. I

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 Monitor Tank Release To The Circ Water System.

Pages:

14-28 MONITOR TANK NO.

RELEASE N 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.

INOTE:

In order to open 12-RRV-285 after high alarm on RRS-1001, monitor mu 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:

4.14.1 Notify Radiation Protection.

4.14.2 Close AND seal 12-WD-166, Rad Liquid Waste Disposal Effluent Control Valve 12-RRV-285 Inlet Valve.

4.14.3 Close the applicable valve:

a.

1-RRV-287

b. 2-RRV-286 4.14.4 N/A step 4.15 of this attachment.

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.

4.15,2 Place RFS-1010 and RFA-1011 in POLL OFF at RMS-CT.

L Page 3 of 4

/

This section is N/A Notifies Radiation Protection CUE: "Radiation Protection has been notified" Obtains seal and closes 12-WD-166. Places seal on the valve.

CUE: Handwheel has stopped moving.

CUE: Independent Verification is complete CT Student should simulate taking switch for 2-RRV-286 to the Close position.

CUE: "Switch clicks into place, red light is dark and green light is lit" N/A - This will be performed in step 4.16.3

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, 4.16 WHEN desired tank level is reached OR Monitor Tank pump has tripped on low level or high rad, THEN perform the following:

4.16.1 Verify Monitor Tank Pump - STOPPED.

4.16.2 Verify following valves - CLOSED:

a.

12-RRV-285

b.

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

I-RRV-287 2-RRV-286 4.16.3 Request Control Room perform the following:

a.

IF available, THEN print release averages for the fowg RRS-1000 channels to attach to Data Sheet 1:

RRS-1001 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 (N/A if already performed).

4.16.4 Place Monitor Tank Pump Mode Selector Switch used for release to - RECIRC.

4.16.5 Press ALM ACK button on front of DAM to reset local flashing blue light.

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

4.16.7 Record the following information:

Time:

Date:

//

oeease Final Tank Volume:

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

Monitor tank pump should have been stopped earlier, if not:

CUE: "Red light goes out and green light illuminates" When Candidate places South Monitor Tank Pump switch to Stop. RRV-285 and 2-RRV-286 should already be closed with green lights illuminated and red lights out.

Student may check 1-RRV-287 closed.

CUE: "Red light out and green light lit."

Candidate should have Control Room perform steps 4.16.3 CUE: "The Control room has printed the release history. RFS-1010

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

-Places South Monitor Tank Pump Mode Selector Switch to Recirc CUE: "Switch is in Recirc and Independent Verification is complete."

"Presses ALM ACK button on DAM CUE: "Blue Light has stopped flashing and Independent Verification is complete.

- Marks Flow Recorder-CUE: Recorder is marked and Independent Verification is complete.

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

Independent Verification is complete."

- 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:

INSTRUCTOR:

Signature:

SOPERATIONS REVIEW:

Name:

Signature:

Dale Tidwell Jj T.

Werk 10/23/2002 10/23/2002 Page 1 of 3 V

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 1 D safety related busses from the 1 CD 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 IL II 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).

b.

Contact:

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.

- EMD-32a must be completed and the state and county notifications made within 15 minutes of the Alert classification.

Page 1of 3

COURSE NUMBER N02-A4

!ANDTIT LE :

Com lete E

AN TIL:Comlt EMD-32a Nuclear Plant Event Notification 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 fax machine all of the locations listed in step 3.2.7 will receive the fax-If BROADCAST is NOT used then each of 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 State Emergency Operations Center Emergency Operations Facility Emergency News Center/JPIC Visitors' Center 8-1-517-336-6257 8-1-517-333-4987 8-284-2942 8-284-5892 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.

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

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

REVISION: 0 Page 2 of 3

COURSE NUMBER N02-A4 AND TITLE:

Complete EMD-32a Nuclear Plant Event Notification REVISiON: 0 I.

v...

Pla,. t Contact information

,111--,Pow r anti X..

IPlarnt rornmuniark

,~~

Callivg Irm QCnto Loo1 0 SO pb0 Uo f:

Cai 86ýTelep$1on e NitMber:

k3~~.9 Plnt messe.e lUmber Current ClassificAtion Q lws.ustal Ev-entXAr h Aa mroi Gnri1mraic asnt Tb'Te c-ass~ficatfon was declared, a., oý-- Pate T

j m6 ie i

g r 4

.R a ono"

.. :R i,,

toi

t.

" Abnormiabl.Rad LeelI ad:

.li:.op

. i y rnril~ncrn

r:P tti "0

Fission Produt Barrier De0 dalont z.y d..." r..*ndifl" Plant,4tatus.

L _...

s.*...

0* De,.*..

.;i::iijora""dino "'g :: ::*..

Radi~~Aol rea~ae in Prr~gresý 01;*Og -y Een'.

______a.

Yos EProtectivetActloo oRecommedaIons IV,,.nd Drectnn (dpgewa): Firm TO:

T

-o z*

Ve.

n 4MSUdQVPI Mani.;r wale:

fl'_..n All items should be completed on the form prior to submitting to the Site Emergency Coordinator for approval.

CT:

"Actual Event" box marked (for purposes of this JPM "Drill" is also acceptable)

- "D. C. Cook" the plant MUST be identified "1" entered since this is the initial notification (CR1 is also acceptable)

"Control Room" box marked Plant number given, however other control room telephone numbers are acceptable CT: - "Alert" box MUST be marked CT: - Today's date and time of Classification (Given during the briefing) MUST be filled in "System Malfunction" box marked T: - "S-2" MUST be filled in 1ECT: - "Stable" box MUST be marked "41:

- "No" box MUST be marked CT: - "None" box MUST be marked Wind from "262o" to "82o" filled in Wind speed "10" mph filled in Stability Class "E" filled in Precipitation uYes" box marked Student reports form complete and ready for SEC approval.

JPM IS COMPLETE.

Page 3 of 3 Cook 10 Nirnber 5 f

3:.

\\

i S.......

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 1 C and T11 D safety related busses from the 1 CD 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 Wind Direction 10M - Main Tower Wind Speed 10M - Main Tower Precipitation - Main Tower Wind Direction 10M - Backup Tower Wind Speed 10M - Backup Tower Wind Direction 60M - Main Tower Wind Speed 60M - Main Tower Standard Deviation 10M Main Standard Deviation 10M Backup Standard Deviation 10M Main Pasquill Category Outside Temperature Lake Breeze N02-A4.doc

-0.3oF 2620 10 mph Rain 2680 12 mph 2710 13 mph 0o 0o Go E

60.8oF NA Page 2 of 2

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

[RO AM NRC License Exam REVISION 0

TIME!

15 Minutes DEVELOPING INSTRUCTOR:

OPERATIONS REVIEW:

Name:

Signature:

Name:

Signature:

S. Pettinger T Werk 10/23/2002 10/23/2002 Page 1 of 3

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

Determination 11 References 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 WTX-106 = 71.8 WTX-107 =71.8 WTX-108 = 72.2 WTX-102 = 77.1 WTX-103 = 77.4 WTX-104 = 76.8 WoTdXn-20

=7 WTX-206 = 77.2 WTX-207 = 77.1 WTX-208 = 77.3 WTX-202 = 76.9 WTX-203 = 76.9 WTX-204 = 77.0 Cond*nseeLC WTX-306 = 77.1 WTX-307 = 77.0 WTX-308 = 77.0 WTX-302 = 71.2 WTX-303 = 70.9 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 Continuous I

02-OHP-4030-STP-030 I

Rev. 39 I

Page 81 of 145 DAILY AND SHIFTLY SURVEILLANCE CHECKS Data Sheet 5 Shift Surveillance Checks Modes 5, 6 and Defueled7 Pages:

170

- 83 Instrument Title & No.

00-08 1 08-16 1 16-24 1 Acceptance Criterion I

IValue Value I.ValueI 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. 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. (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.

Ci rc Wtr T'emnp:

IS 3.9.3-= for Decy m:

." 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 e14-l Step 14.2 - less than or 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).

14.2 IF Circ Water Temp is greater than or equal to 72°F OR ff the Unit is in MODE 6 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

>74.6*F (using Take one inlet temperature measurement of each Condenser in Step 14.1 ) OR

>76.8F (using service using the M&TE calibrated instruent with +/-S°F Step 14.2) uncertainty and calculate the average.

Condenser A Circ Water Inlet:'

Check box for inlet measured:

o WTX-106 or O WTX-107 or O WTX-108 or o WTX-102 or O WTX-103 or o WTX-104 UI Q U20 4 sssIT OP

'movem-1tof irradiated fuel until either of the following eondititons are Circ Wtr Temp is

!V4.

'te R -76.PF' tog Step 14.2)

S/

-OR.

S;Decay Time is greater than 148 hrs.

".4 C8 C8 General CUES:

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

The SRO review of the data should identify the following errors:

1. Temperature readings were averaged vice specific temperature selected and recorder

2. Temperature readings for isolated waterboxes should be excluded (WTX-106, 107,108, 302, 303 and 304)

Step is N/A due to Temperature Indicator Problems

-Reviews instrument data for accuracy. Identifies that "U2" Box is not checked.

C4

-CT: Determines a box is not checked and that the temperature logged (74.5oF, averaged temperature was used instead of 1 temperature) is in error and should be one of the following:

WTX-102 = 771 WTX-103 = 774 WTX-104 = 76.8 Page 1 of 2 Revision 0 14.u 14.1

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).

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 I

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 t---,

r.

.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 11 g

+,.,..

Ell DP) rip A

Cip cop)

?Elp liDp JA t

-A I-IT (i

T )

T

11.

A Condenser South Inlet Temp WTX-106 71.8 A Condenser South Inlet Temp WTX-107 71.8 A Condenser South Inlet Temp WTX-108 72.2 A Condenser North Inlet Temp WTX-102 77.1 A Condenser North Inlet Temp WTX-103 77.4 A Condenser North Inlet Temp WTX-104

{.76.8 North Temperatures are valid l I, lf l I

IS;*l lI J M

V V I J

-. ) U U I

I C Condenser South Inlet Temp WTX-307 77.0 C Condenser South Inlet Temp WTX-308 77.0 C Condenser North Inlet Temp WTX-302 71.2 C Condenser North Inlet Temp

.WTX-303 1 70.9 C Condenser North Inlet Temp VWTX-304.

71.3 South Temperatures are valid Page 1 of 1 Revision 0 "7"7 '4

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 WTX-106 = 71.8 WTX-107 = 71.8 WTX-108 = 72.2 WTX-102 = 77.1 WTX-103 = 77.4 WTX-104 = 76.8 CondenseLB WTX-206 = 77.2 WTX-207 = 77.1 WTX-208 = 77.3 WTX-202 = 76.9 WTX-203 = 76.9 WTX-204 = 77.0 mGienp fLC WTX-306 = 77.1 WTX-307 = 77.0 WTX-308 = 77.0 WTX-302 = 71.2 WTX-303 = 70.9 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 NRC License Exam DEVELOPING INSTRUCTOR:

OPERATIONS REVIEW:,

Name:

Signature:

VISION 0

TIME.

15 Minutes S. Pettinger 10/2312002 10/23/2002 Name:

Signature:

Page 1 of 3

.. T. Verk

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 ii REVISION: 0 AND TITLE :'... ContainmentIII STitk Numb IRRADIATED FUEL HANDLING ACCIDENT IN 12-OBP 4022.0 OTM,,r BUILDING - CONTROL ROOM ACTIONS I

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

1. Actuate Containment Evacuation Alarm

2. Notify All Non-essential Personnel To Evacuate Containment

3. Notify All Personnel Listed On Containment Penetration Breach List To Set Containment Closure (01/02-OHP-4030-STP-041) For, Any Open Containment Penetrations

4. Notify Shift Manager

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

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.

Another SRO is performing the Emergency Classification as per Section C of this procedure.

CT: Operator actuates the containment evacuation alarm on the Flux Panel "CT: Operator notifies evacuation of non-essential personnel from containment using the paging system

"-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 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 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 Unit 2:

Supply Air Valves - CLOSED.

"* 2-VCR-103

"* 2-VCR-203

"* 2-VCR-105

"* 2-VCR-205

Exhaust Air Valves - CLOSED.

"* 2-VCR-104

"* 2-VCR-204"

", 2-VCR-1062-R20 t -

ii Operator Closes Unit 2 supply air valves (at least 1 per penetration):

CT:*- Lower Cntmt Supply Air 2-VCR-1 03 Lower Cntmt Supply Air 2-VCR-203 CT.( Upper Cntmt Supply Air 2-VCR-1 05 LUpper Cntmt Supply Air 2-VCR-205 Operator Closes Unit 2 exhaust air valves (at least 1 per 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 Page 2 of 8 11i REVISION: 0 1

I

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.

I 1-VCR-101 I l-VCR-201

"* Exhaust Air Valves - CLOSED

"* 1-VCR-102

"* I-VCR-202 OR Unit 2:

"* Supply Air Valves - CLOSED.

2-VCR-101 A

2-VCR-201

"* Exhaust Air Valves - CLOSED

"* 2-VCR-102

"* 2-VCR-202 "Operator verifies Unit 2 supply (2) and exhaust (2) valves closed Page 3 of 8

COURSE NUMBER IN02-A5b Perform Control Room actions for Fuel Handling Accident in REVISION: 0I AND TITLE: :

Containment I Tiilý IRRADIATED FUEL HANDLING ACCIDENT IN 12-OHP 4022.018.004 CONTAINMENT BUILDING - CONTROL ROOM ACTIONS 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 Valves in the affected Unit-CLOSED:

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 fan ipped 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:

a. Uniti1:

I) System dampers - ALIGNED:

1) Manually align damper(s) as necessary per 01-OHP 4021.028.014, Operation of the Control Room Air Conditioning and Prerssurization/Cleanup Filter System, Attachment 12, Corrective 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.

- CT: Operator notifies Unit I to isolate Unit 1 CR Ventilation due to Unit 2 fuel handling accident CUE: "A Unit 1 Operator will align Unit 1 Control Room Ventilation per 12-OHP-4022-018-004 Step 10a" Page 5 of 8

COURSE NUMBER. N02-A5b Perform Control Room actions for Fuel Handling Accident inI REVISION: 0 S A N D 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 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

Close 2-HV-ACR-DA-IA, control room vent intake damper

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, Control Room Pressurization Intake Damper Open 2-HV-ACR-DA-3, Control Room Pressurization Clean-up Recirc Damper

2) START Control Room '

Pressurization/Cleanup Filter Unit Ventilation Fan 2-HV-ACRF-1.

OR 2-HV-ACRF-2.

11. Verify Instrument Room Purge Supply And Exhaust Fans - STOPPED 4d

'.4

'-4 Operator performs Unit 2 CR Ventilation line up CT: Operator closes DA-1 CT: Operator closes DA-1A CT: Operator places one damper to partial open Operator verifies other damper is closed Operator verifies open DA-3 CT: Operator starts 1 fan 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

-q

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

12. Check Additional Auxiliary Building.

Fan In Service With Containment Airlock Doors Open AND Containment Purge In Service:

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 system panel -

CLOSED

14. Notify Radiation Protection To Perform The Following:

a. Survey Containment

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

11. Go to Step 13

-q

-'U CUE: If requested, "Containment Airlock Doors are closed" Operator determines airlock doors are closed and containment purge is off, goes to RNO and proceeds to step 13 Operator directs AEO to verify 12-RRV-306 is closed CUE: 12-RRV-306 has been verified closed locally CUE: US will notify RP to perform surveys and verify all evacuated personnel are assembled at the control point Page 7 of 8

COURSE NUMBER.I N02-A5b Perform Control Room actions for Fuel Handling Accident in I

AND TITLE::I IlContainment jREVISION: 011f I

II I

Tid.

ue"-.

I IRRADIATED FUEL HANDLING ACCIDENT IN 12-HP 4

~12-OHP 4022.018.004 CONTAINMENT BUILDING - CONTROL ROOM ACTIONS STEP ACTiON/EXPECTED RESPONSE RESPONSE NOT OBTAINED Reports task completed.

JPM IS COMPLETE.

Page 8 of 8 SNOTE:

Recovery work will commence after an investigation has been conducted and a recovery procedure established.

16. Return to Procedure And Step In Effect.

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

TITLE Perform an Initial Dose Assessment P*ROGRAM NRC License Exam REVISIO.N 0

TIME 10 Minutes Revision 0: Initial Issue DEVELOPING INSTRUCTOR:

OPERATIONS I REVIEW:

Name:

Signature:

Name:

Signature:

Dale Tidwell W

0 Verk 10/23/2002 10/2312002 Page 1 of 3 N02-

C

OLJE U

N UMB'*R N02-A6 A..

TITLE:!

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 AND T

ITE Perform an Initial Dose Assessment ormation R

P -1 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 default PAR in PMP-2080-EPP-100.

4.1 Determine which forms are required.

4.1.1 EMD-32a, Nuclear Plant Event Notification.

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

die emergency classification or PAR.

Must include an EMD-32b, Nuclear Plant Event Technical Data Form if the emergency classification is General Emergency and the PAR is 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 "intervals of 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, Pasquill Category, provides for Pasquill Category (Stability Class)

Sdeterminations NOTE:

Sources are listed in order of preference.

10 Meter Main 10 Meter Backup 60 Meter Main A computer terminal with the current version of the Dose Assessment Program (DAP version 7.0.20) is necessary for completion of this JPM.

For the conditions described in this JPM, an EMD-32a would be completed. Completion of the EMD-32a is NOT necessary for successful completion of this JPM.

PPC meteorological data is provided with the briefing.

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:

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.

4.5 Determine the Coolant Type.

T00o 1type Containment on ontorng eaing Normal Coolant

<10 R/hr Cladding Damage

<1I Fuel Melt

> =1000

/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,

- 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)).

PPC Radiological data is provided with the briefing.

ONLY Unit 2 is applicable for this JPM. Unit 2 status is provided with the briefing.

Normal Coolant will be used in the calculation. Provided with briefing - both Containment High Radiation Monitors (VRA-231 0 and VRA-241 0) are less than 10 R/hr.

Actual release is in progress as provided with briefing.

Page 2 of 12 Revision 0

aCOURSEiNUMBER N02-A6 V

AND ITLE:

Perform an Initial Dose Assessment Information I

PP

-108E Rev. 4.

Page 5 of9 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.

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

4.8 Enter the data into the Dose Assessment Program.

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 EMD-32b forms for transmittal to the state or county.

4.9" IF necessary. THEN update the current classification and Initiating Conditions on 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.

5 REFERENCES 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 REVISION: ~0.

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

The following pages illustrate the Dose Assessment Program screens with the information entered. The "tabs" of the dose assessment may be completed in any order.

However, the Calculation and Results tabs should be viewed last.

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

Page 3 of 12 Revision 0 I!

,i

COURSE NUMBER 02-A6 A NDT"!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 N02-A6

-AND TITLE:,

Perform an Initial Dose Assessment REVISION: 0 II Rumi.

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

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 I

I

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

ro

,:i:!:*::!*,

I. P:i:!1eerform an Initial Dose Assessment S.

II I Under the Plant Status tab, the student should 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

-ox I CT II II

COURSE NN.UMBER N02-A6 A ND TI TLE:

IPerform 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 m e Radiation Monitor data given with the briefing.

V 4.2,4, (NOTE: Gaseous Release - In Plant Monitor is the rýhW Tm Da

ýOff Re oDewRae Djai default selection.)

e>

1Th~ ldaoflbasisde min dienneadis used. Seelte

ý.9sn, eahb&b~nlpsedonforspea.

NOTE the Field Team tab will NOT be enabled for this JPM. Field Team Data must be selected to enable 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 ONLY generate PAR recommendations based on Dose

_*,__*.._`*Svc, 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

Under the Gaseous rel. tab, the student should 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 I

COURSE-NUMBER N02-A6 Perform an Initial Dose Assessment v, za I!l I

'COURSE NUMBER N02-A6 AND TITLE:

Proma nta oeAssmn Sl.uox GeJ Gaw fii JEtm sv

~

c~

FFS,

ýýM W

T Awht.,

RA~i MAW Womaiaim -

NO additional information is required under the Additional 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 N02-A6 AND TITLE:

Perform an Initial Dose Assessment REVISION:.0 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 Ii

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.

The Dose Assessment Program will automatically 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 12 93 il 11I I

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 VALUE UNITS RMS052 RMS054 RMS055 LOWER CONTNT LOW RNG NGAS - TR A LOWER CONTNT MED RNG NGAS - TR A LOWER CONTNT HI RNG NGAS - TR A VRA-2310

- RMS056

- UPPER CONTNT HI RNG AREA-TR A VRA-2410

- RMS064

- UPPER CONTNT HI RNG AREA-TR B

- RMS068

- RMS070

- RMS071

- RMS072

- RMS073

- RMS074

- RMS075

- RMS076

- RMS077

- RMS079

- RMS080

- RMS081

- RMS082

- RMS084

- RMS085

- RMS082 VRS-2505 VRS-2507 VRS-2509 VFR-251 0 MRA-2601 MRA-2602 MRA-2701 MRA-2702 SRA-2805 SRA-2807 SRA-2809 SFR-2810 SRA-2905 SRA-2907 SRA-2909 SFR-2910 ETQ-403 EFR-412 EFR-402 ELR-400

- UNIT VENT EFFLUENT LOW RNG NGAS

- UNIT VENT EFFLUENT MED RNG NGAS

- UNIT VENT EFFLUENT HI RNG NGAS

- UNIT VENT EFFLUENT FLOWRATE

- STM GEN LOOP 1 PORV DISCHARGE

- STM GEN LOOP 4 PORV DISCHARGE

- STM GEN LOOP 2 PORV DISCHARGE

- STM GEN LOOP 3 PORV DISCHARGE

- GLAND STM VENT EFFL LOW RNG NGAS

- GLAND STM VENT EFFL MED RNG NGAS

- GLAND STM VENT EFFL HI RNG NGAS

- GLAND STM VENT EFFL FLOWRATE

- STM JET AIR EJE EFFL LO RNG NGAS

- STM JET AIR EJE EFFL MED RNG NGAS

- STM JET AIR EJE EFFL HI RNG NGAS

- STM JET AIR EJE EFFL FLOWRATE

- DELTA TEMPERATURE - MAIN TOWER

- WIND DIRECTION 10M -

MAIN TOWER

- WIND SPEED IOM -MAIN TOWER

- PRECIPITATION - MAIN TOWER EFR-413

- U0806

- WIND DIRECTION 1OM - BACKUP TOWER EFR-403

- U0807

- WIND SPEED 1OM - BACKUP TOWER EFR-410

- U0808

- WIND DIRECTION 60M - MAIN TOWER EFR-400

- U0809

- WIND SPEED 60M - MAIN TOWER

- U0810

- U0811

- U0812

- STANDARD DEVIATION 10M - MAIN

- STANDARD DEVIATION 10M - BACKUP

- STANDARD DEVIATION 60M - MAIN ERS-2305 ERS-2307 ERS-2309

-1.0 275.0 4.0 NO RAIN 278,0 3.6 280.0 5.0 0.0 0.0 0.0 N02-A6.doc 3.685E-06 1.050E-03 2.300E-03 1.0003E+00 1.0003E+00 2.331 E-07 7.600E-04 1.100E-01 8.327E+04 1,330E+02 8.500E-01 1.300E+00 8.200E-01 3.352E-06 1.090E-03 1.220E-01 9.969E+02 3.750E-05

1. 120E-03 1.520E-01 4.011 E+00 DEGF DEG/FROM MPH NONE DEG/FROM MPH DEG/FROM MPH DEGREES DEGREES DEGREES Page 2 of 2 Revision 0

TAC, In gCI/CC

Ct/CC PCI/CC R/H R/H I.lCI/CC ACI/CC CFM "pCI/CC "pCI/CC "ACI/CC

"[CI/CC ptCI/CC tC I/CC

ýtCI/CC CFM ACI/CC I.tCI/CC 4CIICC CFM U0802 U0803 U0804 U0805 NONE NONE NONE TAQ In MATA nl=Qr'DlDTlnKl I*.*,T.A. r*l:::*t'*DiDTit"*kl

14 A7a' TITLE Calculate QPTR with Inoperable Power Range REVION 0

Instrument

[

4 NRC License Exam TIM 15 Minutes DEVELOPING Name:

INSTRUCTOR:

Signature:

OPERATIONS REVIEW:

Name:

Signature:

S. Pettinger

.T.

Werk 1013/2002:

10/23/2002 10/2312002 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 I Evaluation 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 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:

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.

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.

General CUEPS

-CUE:, PPC is inoperable for QPTR calculation Operator determines step 4.4 is correct step 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 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" Operator determines steps on this page are not applicable Page 2 of 5 Revision 0

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

~~~IREVISION:....

0 ""I Reference 02-OHP 4030.STP.032-7 Rev. 8a -

Page 5 of 11 QUADRANT POWER TILT RATIO CALCULATION 4.4 Calculation of QPTR with one NI inoperable:

4.4.1 Record the OPERABLE NI numbers in the appropriate blanks on Data Sheet 3.

4.42 Obtain power range excore amperages as follows:

I NOTE:

All eight amp meter settings do not need to be on the same scale settinj

a. Select the amp meter scales for maximum resolution. A-

b. Read AND record each individual NI detector current on Data Sheet 3.

4.43 Enter the individual-upper and lower power range 120% current values in the appropriate blanks on Data Sheet 3.

4.4.4 rOperator determines this is correct step

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

Lower Detector blanks.

Note: See Page 5 For expected values (Spreadsheet program may be used to verify accuracy of candidate readings and calculations)

Operator should select the 0.1 scale "CT: Operator records data to within +/-.0005 for indicators reading on a division mark and within the division marks for all others. (Enter data into spreadsheet for comparison)

CT: Operator enters data from cards on channel 3 NI Panel Operator divides respective NI channel with its 120% value (from Divide each individual NI current by its 120% amperage.

cards on channel 3 NI panel) 4.4.5 Total the normalized values determined in Step 4.4.4. 4 4.4.6 Using the formula on Data Sheet 2, determine the upper and lower QPP,.

4.4.7 Enter the highest upper OR lower filt ratio in the space provided on Data Sheet 3.

-Operator totals 3 channels of normalized values CT: Operator determines upper and lower QPTR using data sheet 3 with an accuracy of.01 of Exam Team calculated value (Enter 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 I.

REVISION: 0.,.,..

I

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

I Page 4 of 5 Revision 0 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.

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 Record Detector Record Detector Normalized Value j Detector "A" Current "A" 120% value Detector A + 120% value

.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 N-0986 1192

.8272 N-n772A41*79 Lower Total 1

2.4877 Data entered on this page based on Simulator readings.

Enter data into QPTR calculation spreadsheet to determine accuracy of candidate's calculation Upper Tilt Ratio =

Max Upper Normalized Valtie x 3 Upper Total x3

=

Max Lower Normalized Value Lower Tilt Ratio Lower Total x 3=

Enter the max upper or lower tilt ratio (Calculated QPTR)

Highest Upper or Lower Radial Flux Tilt from PPC (N/A if unavailable or inoperable)

Verify QPTR Consistent with Incore Detector Readings (N/A if reactor power is less that or equal to 75%)

.4 1.0049 4 N/A Notification Limit: 1.015 CT: Operator enters the highest calculated QPTR of these 2 values Candidate marks "N/A" Nuclear Engineering states that QPTR is consistent with Incore Readings.

Date:

Time:

Date:_____

Candidate Signs, Dates, & enters Time Reports task completed.

JPM IS COMPLETE.

Page 5 of 5 Revision 0 Acceptance Criteria: Calculated QPTR is less than or equal to 1.02 Performed by:

Reviewed by:

(Supervisor/Manager Signature)

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 NRC License Exam

-REVISION 0

TIME 15 Minutes SDEVELOPING,

-INSTRUCTOR; SOPERATIONS REVIEW:

Name:

Signature:

Name:

Signature:

S. Pettinger 1012412002 10/24/2002 T. Werk 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 A

Simulator 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 I I

()COT!NLL O1S 01-01P4030-127-041 Rev. 0 a'gae 297 o-i-'

Refueling Integrity I

Data Sheet 5 Daily System Parameters Pa-es:

1 2 95 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 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 CUE Alarm is no longer valid 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 4 fltmri4 "

L)::4

4=*:

q CT.'?, L-ai-*ý ':

mlV

. For Ceorc'.,Pcai-!

" Q°-"

TAG

(,1" IMOR.IMLD 1m,.) ER.

UN".

BY C 7'- 7-4 4.' cr'c-'c.'c

' cc 4 c 0im r

c t,2 i c i,

2-,'

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

cr

.{

r i"'

tc j;;,c t ii ti

(

n ci 4. *.cr F wru ii b¢ i** icc d fo

.*ur- }*cu~.

4;i~',,

j.a Air..

car c-'

cl l*

vOil,.th"

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

!R

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

cF

.\\4 \\4?',4

('LLA

CU4 -Ak

.3';-0 Roo(

. C:.

Ai

';5 Alarm is not Valid nor clear

' Alarm is not Valid nor clear CT: Determines that Option C is required Option 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'.

V, i.r'.y o1 v

,.o ]:.',**

lv";.:,:

i70. !-G C\\A.3S51 1f' I

,-IPS

b<

-*f 1-f.'

.IV

.2 I -D K V 10 m)nRP'nN

f.f}. rICXtFf

!\\li

' I HI \\G

\\

fix "2

CYC!,[FS

- CT: Selects one valve and verifies that it cycles Two (2) times Requests that AEO read pressure on 1 -XPI-1 86 at CAS panel

-AM)-

4F-

` 'P ',

.f.I i,..,

1*0["

N E: (?::*

.1 -

('I (.:,

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

-1 \\'$:;JI 1/

`_7

.11 Cue : "1-XPI-186 reads 85 psig"

-CT: Verifies Pressure is > 75 psig.

Requests Refuel Tag to be Hung on 1-XPI-186 Cue: "Refuel Tag is Hung on 1-XPI-186" Can Not be used as it requires operations inside containment.

-Can Not be used as air would be isolated

- Can Not be used as air would be isolated Page 4 of 6 prL:*'-ClU Is.*',

A.."...,

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-I'AC I'll'

O I;

-B Evaluators Note: The following signature should be made on the Original copy of O1-OHP-4030-127-041 Data Sheet 1 page 115.

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

2.

P r:kvc.1 1 F.h I ;*i

a):

rn 1v F:

r', IFT.)

t1 I'T

(

haiv fDA TFl.

-Signs that CPN-74 Options are Complete on New Copy of 01 OHP-4030-127-041 Data Sheet 1 page 115 Reports task completed.

JPM IS COMPLETE.

Page 5 of 6 vs

'1 2 (:

, S T'q.IN *.

*L!L!

"TI N1.1, I *,;

C

0 (D

cIL 0

0 E

0 L)

4) 0

0.

0 C

0 0

0 C

U)

I0)

40)

I L. 0 4-

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 PROGRA.:*:

NRC License Examination DEVELOPING INSTRUCTOR:

OPERATIONS REVIEW:.*

Name:

Signature:

Name:

Signature:

REVISION!

0 TIME 20 Minutes Dale J. Frie JT. Werk 10/29/02 10/29/02 Page 1 of 3 I....

.I

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 1 0-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 OmnClerace Permit Sytelu

. 3 C.ara~nce Devclopme Chi PFelas:

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

Clearance Developmerti Checklist - VERIFIER ACTIVITY CI-ECKS U

KIad IOA duscrriptil: check unit desigaiadon. Cicarancc. type (RtV$d"StripWd).

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

CLEARANCE CHUlCKS S'G ei.a~nce writtct. from a standard./

U Spccia" i 'ttr to px'laihi ' hV spccial b, were choswn Main cquipmeum removed betore s* pofr 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 PM rirs verified via NDIS

.. U Man.

ax approval ftr Uncontrolled Drawings Page 1 of 2 k

For those checks that are not necessary for this Clearance, i.e. the checks without arrows, accept any trainee comment.

Trainee determines that there are no support equipment removed from service by this Clearance.

NOTE: Trainee may interpret that the Control Switch should be in 'Pull To Lock' and Control Power Fuses should be 'Pulled' before the Breaker is racked to Disconnect at this point. IF so, this meets the standard for proper sequencing of tags.

CT: Trainee determines that the Control Switch and the Breaker are improperly sequenced.

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

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

AND TITLE:

~].Ve1~rify a Clearance Permit

[

ILVforJflft&o --

2-O1TP-210--CP.--1

.Pa_.

Clearance Permit Sy**en I

Clearance Development Checklist-Verifier MECHANICAL

-i Low e

<lry

< I0 p1 g <0

< 30 '*'

JL Steam side of trwp isolated fins

A.1 li*_

es, ýide of pumped syste*vs isolated first

",J Do tmso,.! have.ýea water A A! kct o.ic 'e*\\t and/or drait tagged open, if U ( Chelk dra:;ns that tie nao a common header L-1 fa.nnrn; noinfiei if drain hoses affectintm HELB

.- Preco' rLanaiLoiate urocets flow

'a Tia-zardonas liquids and solids Pageýs 33 - 34 ELECtRICAL U Any electric plant liitaions J

Remote switches ott HSD Panel and odler uRit D.2 One lag t per ifted lead U Motolr Heater power U Bvfre-ker cleanillg Uaps UAit-eate power SControl switch, ftiscs, breaker&

J Ground Clearance separcte U Induced power (FT's) 41 Grounds required when working on electri'al circuits > 6WO volts FIRE PROTECTION J

iNSTRUMENTATION 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 tic ducting iufrqendyperfomnn-d tests or evolution.z: PMI-4090

'U Ee, ini.i:ti'twd

].irveillanee PMP 4030.EIS.'oi

.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

J P: 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,1 i(W! ;)DR 10, 0 Vi na SIutdtwa,*;fy a d d

R 1 sk Mange

[nEiz Q) TIe v'erificaiion of the bou&rieikire.

n dependent and not influeneed b, rhe writer.

____________________1 For those checks that are not necessary for the Clearance, accept any trainee comment.

Evaluator Note: HSD Panel Switches are the 201 switches.

CT: Trainee determines Control Switch, Fuses, and Breaker need to be properly sequenced and RED tagged.

NOTE: This may have been previously determined on page 33 of the checklist.

CUE: When the Trainee completes the ELECTRICAL portion of the checklist announce, JPM IS COMPLETE.

Page 2 of 2 iAt;a chn rt 3

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::,

Name:

INSTRUT' Signature:

I PERATIONS iREIEWS Name:

Signature:

S. Pettinger IT Werk~

9/7102 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 L Handouts Task Briefing Prepared Release Package:

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

Page 3 of 3

COURSE:

NUMBER.

N02dA9 RREVISION:

01.

AND TTLE:

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 "O Lineup Sheet 6, Monitor Tank No. 2 Release Valve Lineup "o Lineup Sheet 7, Monitor Tank No. 3 Release Valve Lineup o Lineup Sheet 8,.Monitor Tank No. 4 Release Valve Lineup 4.5.2 Verify release number has been entered on each page of Lineup 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.

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

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:

SM/WCC SRO 4.6 Request RP Tech perform the following:

Date:

4.6.1 Enter RRS-1001 High Alarm setpoint (Section 2 - Data Sheet 1).

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

4.6.3 Verify parameter files for all RRS-1000 channels are correct.

[Ref. 7.2.1i.3]

RP Tech OPS

-_T;;i oPs SRP Tech CT - Identifies that the discharge alignment was NOT indJp.endent

-verified by twI (different) operators for CW (Circ Water) valves located in the Turb Bldg on first page (page 53) of Lineup Sheet 7 (i.e., 1-CW-123, 1-CW-124, 2-CW-123, 2-CW-124).

CT - Identifies that iwa independent samples were NOT performed

-as only on LIQUID RELEASE WORKSHEET form is included in the release package.

Identifies that greater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months has elapsed since chemistry approved the release (Data Sheet 1, Section 2, Chemistry Approval Date/Time (Sample: 11/21/02 @ 0601, Exam: 11/22/02 after 0700)

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

cua: Reports task completed.

JPM IS COMPLETE.

Page 1 of I 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 DEVELOIN iINST RUCTORI:

Name:

Signature:

TIME i 15 Minutes Dale Tidwell OPgRATIONS RE VIEW:...

Name:

Signature:

9/7102 Page 1 of 3 Revision 0

-qi q 17-T. Weirike 7--Vsýý

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 300Q at 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, TnI 1)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-:1onms rcirnrliliz 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-.tl 4' (1

".7

-ious -o'~s. is;iii.i evvw amdlii that lr a101

.4 I I Fmenuscn~ cv jr Page 2 of 6 Revision 0

COURSE NUMBER..- N02-AIO AND TITLE:

Emergency Plan Classification with PAR Emcmwrncv CL ASSI1FICA'TION

- ~

~

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

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 u

ia, hould be l-ata.cd o~n a reatI1aoc zpprahial of SLit

,0"

a n if.~

ad U

ecsi, Lseelo rs.

i.t~

a :ia ing 0th, ascnt culId.

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

usslalcl

~

ar~he aacrsaply tw l.

FSF itat,e

. aýmtblmhitd and aatiae DENX I ATICK N t liOM,, 'ftMARtC; Ii,.I

'I lt laaiI i~acai tcsatal ataaw atc, r dla w,.,o1-o f a a-niitesan etea Cac

.-REVIS.ION:. 0 Page 3 of 6 Revision 0

COURSE NUMBER N02-AIO AND TITL-t:

Emergency Plan Classification with PARREION0 Euiaerttcncy Respons'e tsNict ai Coxutrs' 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 hin ivlect.. housever repixrt to tand~

aulh ate the

feýnil 4cTehkl 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

-'.7 tIa Giene-rd a

oere has heen &es.lared, THEN direct the de~kh~~elt f;

rotctve ettn Rconinndaio U~fl~tkA General Emergency requires a protective action recommendation be made to the state.

r.Prior to tievelophio a PAR consider whethec-the folio-oving coould h-:ýse an-effec;t ont the PAR:

-A forzceas of ubitngoits-weather conditions.

c:teclaraictcrjsiesl~ fpuff N's. crntiruoos)

P~aesttootilneý pr Aitsohineta; 3 of I E'P3t5 rr-(clie~t\\eAt 1%, l.Ju..,t'h JevatEIotis *fromt ihe PAR flosx chart, At\\tacholef~tit in dii; mstep it) 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;4 rate 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 iit iga 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.

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

-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 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 JREV 0

I

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 300Q at 4 mph and NO offsite release is occurring.

Page 1 of 1 Revision 0 N02-A10.doc

ML030700476

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