Text

Initial Submittal of the Administrative Jpms for the D.C. Cook Examination - Nov/Dec 2002
	ML030700197
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: ML030700197 (145)
	v • d • e

INITIAL SUBMITTAL OF THE ADMINISTRATIVE JPMS FOR THE D. C. COOK EXAMINATION - NOV/DEC 2002

A1a TITLE Determine Ultimate Heat Sink Temperature

[ROGRM NRC License Exam REVISION 0

15 Minutes DEVELOPING rNSTRUCTQR:

Name:

Signature:

OPERATIONS REVIEW:

Name:

Signature:

S. Pettinger T. Werk Page 1 of 3 Revision 0 DATE:

9/7/0 2

COURSE NUMBER N02-Ala REVISION:s o

AND TITLE:

Determine Ultimate Heat Sink Temperature

[References I

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 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)

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

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

", C Condenser North 2-WMO-301 & 302 Shutdown 2 CW Pumps (2 CW Pumps left running)

Page 2 of 3 Revision 0

COURSE NUMBER N02-Ala tREVISION:

0 AND TTLE:

Determine Ultimate Heat Sink Temperature Task 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 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:

Cond.enserA Condenser R CondnP nsr C WTX-106 = 71.8 WTX-107 = 71.8 WTX-108 = 72.2 WTX-102 = 77.1 W'TX-103 = 77.4 WTX-104 = 76.8 WTX-206 = 77.2 WTX-207 = 77.1 WTX-208 77.3 WTX-202 = 76.9 WTX-203 76.9 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 ELUKE12.5 with Calibration Current (Last Cal. Performed on 05/07/2002)

Page 3 of 3 Revision 0

,COURSE NUMBER. N02-Ala REVISION: 0

AND TITLE-:

Di n

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i*::::i::][Determine Ultimate Heat Sink Temperature Continuous I

02-OHP-4030-STP-030 I

Rev. 39 1 Page 81 of 145 DAILY AND Surv iL Y SURVEILLANCE CHECKS Data Sheet 5 Shift Surveilance Checks Modes 5, 6 and Defiele~d P'ages:

C&00081 08-16 16-24 1 Acceptance Criterion Instrument Title & No.

Value 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. MrS 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÷:

"I 3.9.3** for Decay Time:

Take reading from SG-21 UI0 U20 S

14.1 Leasthanor Point 1, Circ Water Temp "F

F

-Io p

F I Recorder.

Point 1, (i.e., 77.8 :,3.2ýF

IF recorder is energized and Instrument uncertainty) the printer is inoperable,

-OR THEN take readings from Step 14.2 - less than or THENt ake rea s

U equal to 76.8' the PPC, U0200.

(i.e., 77.8 +/- 1F instrument unoertainty for M&TE

- OR-calibrated Pluke-52 with a

. 12 probe, or equivalent).

14.2 EF Circ Water Temp is greater than or equal to 72F OR IFtheUnitMODE6 measurement cannot be obtained in Step 14.1 OR a more with monert of hradi accurate value is desired, THEN obtain an M&TE calibrated fael in the vesel in prouaesa temperature measurement instrument and perform the following: between epmber 15 and June 8* with:

Record instrument ID Decay,ta.,

Instrument make/model:

-AND Current calibration YIN cite Wir Tepr Take one inlet temperature measurement of each Condenser in Step 14.1 ) OR

> 76.,F (tuing service using the M&TE calibrated instrument with +/-:*F Step 14.2) uncertainty and calculate the average.

Condenser A Circ Water Inlet:

Check box for inlet measured:

O WTX-106 or O WrTX-107 or 0 WTX-108 or 0 WTX-102 2"r O W7x-103 or*

O WTX-104 --

Ul Q U20 4

-TiNSTOPmovesnst of irradiated fuel until either of the following ronditions are srtat:

Cis WtrTemp

174*

p 14.1 )OR !V6 (usin Decay Time Is greater than 148 hrs.

C4 C8 C8 General CUES:

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

- Step is N/A due to Temperature Indicator Problems

= ý= Enters Instrument ID & Make/Model from briefing Sheet Marks "Y" for Calibration is Current

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

-enters corresponding temperature.

WTX-102 z 771 WTX-103 = 774 WTX-104 z 76.8 Page 1 of 2 Revision 0

=t-

COURSE NUMBER;% N02-AlaREION0 AND TTLE:

Determine Ultimate Heat Sink Temperature DAILY AND SHIFMLY SURVEILLANCE CHECKS DataShee 5

Sift Surveillance Checks Modes 5, 6 and Defueled JPM IS COMPLETE.

Page 2 of 2 Revision 0 Intuent Title & No.

%on Condenser B Clrc Water Inlet:*

l0U Check box for inlet mn 03 WTX-206 or E3 WTX-207 sr "O

WTX-208 or 0

F 0

"O WTX-202 or O WTX-203 or O WTX-204 Condenser C Circ Water Inlet:*

Check box for inlet zeasured:

O WDC-306 Ror I o3 WTX-307 or O WTX-308 orT IJFI o WTX-302 or C1 WTX-303 or 0 WTX-304 (Cond. A+B3+C -F) 13-1~ -F 4-4;~ F 1Pý 15.0 Record current MODE*

[

~

l SPer Technical Specification Table 1. 1. Operational Modes:

- CT: Checks one of these boxes and

.,enters corresponding temperature.

WTX-206 = 772 WTX-207= 771 WTX-208 z 773 WTX-202 = 76.9 WTX-203 = 76.9 WTX-204 = 770

- CT: Checks one of these boxes and

-enters corresponding temperature.

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 oF - 77.3 oF)

CT: Operator Informs SRO that the Temrnerature 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.

14.0 Coat

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

\\

MB Condenser South Inlet Temp WTX-208 77.3 B Condenser North Inlet Temp WTX-202 76.9 B Condenser North Inlet Temp WTX-203 76.9 B Condenser North Inlet Temp WTX-204 77.0 All Temperatures are valid 101 4

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L OP Opi R A ri B

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Circulating ;;'ater pumps should nc* bi 6 L

!reia 'AýAef Dump A Condenser South Inlet Temp WTX-1 06 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 Page 1 of I Revision 0 C Condenser South Inlet Temp WTX-306 77.1 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 Condenser North Inlet Temp WTX-304 71.3 South Temperatures are valid

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:

Wond0nse=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 Condpnspe*

WTX-206 = 77.2 WTX-207 = 77.1 WTX-208 = 77,3 WTX-202 = 76.9 WTX-203 = 76.9 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,ELUKFL21Z5 with Calibration Current (Last Cal. Performed on 05/07/2002)

N02-Ala.doc Page 1 of 1 Revision 0

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JEA I TITLE Setup SR & Audio Count Rate for Fuel Movement PRO A

INRC License Exam DEVELOPING Name:

INSTRUCTOR:.

Signature:

OPERATIONS REVIEW:

Name:

Signature:

REVISION0 TIMEi 15 Minutes DATE:

91710 2 S. Pettinger T. Werkx~

Page 1 of 3 Revision 0

.COURSE NUMBER N02-Al b - Setup SR & Audio Count Rate for Fuel REVISION: 0 AND TITLE:

Movement 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 SEvaluation Setting Simulator Handouts Task Briefing for N02-Al b Field Copy of 02-OHP-4021-013-005, Visual Audio Count Rate Channel Attachments None simulatoraSetup Mode 6 conditions with snap # IC 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:

Movement Task 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 I

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 30 seconds.

Page 3 of 3

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

Reference 02-O-P-4021-013-005 Rev. 6 P

e 4 of 16 VISUAL AUDIO COUNT RATE CHANNEL (NIS)

Attachment I Setup of Audio Count Rate Channel Pages:

I

[

4-5 REVISION: 0 General CUES:

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.

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 Operator checks the scaler timer "POWER" toggle switch in the "UP" position Operator checks lights lit

COURSE NUMBER N-Alb - Setup SR & Audio Count Rate for Fuel Movement J REVISION: 0 NOTE In the current configuration, the thumbwheels enter time values to the nearest tenth of a second.

Position thum.bwheels 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. '

] 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 30 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 I.

4.6 4.7 4.8 4.9 4.10 4.11 I

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 30 seconds.

N02-Al b.doc

.Page, 1 of 1

TITL Determine the Requirements for Isolating a PAC Cooler NESW Leak NRC License Exam REVISION TIME 15 Minutes DEVELOPING OPERATIONS REVIEW:

Name:

Signature:

Name:

Signature:

DATE:

9/7/02 S.Pettinger T. WerL 9/e)To?-

Page 1 of 2 koý-A2

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

ANDTITLE:........

Isolating a PAC Cooler NESW Leak References OP-1-5114-84 NESW Flow Diagram (P&ID)

K/A CROSS

REFERENCE:

2.1.24 K/A IMPORTANCE:

SRO 3.1 RO 2.8 I Evaluation Setting Classroom / Simulator Handouts I

Task Briefing for N02-A2 H

Attachments II None 1 Simulator Setup H

N/A Task Objectives/Standards II 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 I 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

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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 - 1 st Stage Cooler Outlet Bypass

"* CT: NSW-1 30 - 2nd Stage Cooler Outlet Isolation

"* NSW-132 - 2nd Stage Cooler Outlet Bypass

"* CT: NSW-1 33 - Oil Cooler Outlet Isolation

"* NSW-1 35 - 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

11_ N0A3ý 2:

TITLE Terminate a Liquid Release PNRC License Exam 0

20 Minutes DEVELOPING INSTRUCTOR:

Name:

Signature:

DATE:

9/7102 S. Pettinger OPERATIONS EVIEW:

Name:

Signature:

Page 1 of 3 "7

q/9o/z_

T. Werk

CO*URSE NUMBER N02-A3 - Terminate a Liquid Release RII ON: 0 AND TITLE:

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

0060170104 Release a Monitor Tank to the Ciculating Water System.

K/A CROSS

REFERENCE:

2.3.11 K/A IMPORTANCE:

SRO 3.2 RO 2.7 Evaluation Setting In-Plant (RCA)

I Handouts Task Briefing Pages 52 & 53 of 12-OHP-4024.139 #16 Annuciator Response 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)

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

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

12-OHP-4024.139 #16 Annuciator Response 12-OHP-4021-006-004, Attachment 3 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-1001 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 AND TITLE:

Terminate a Liquid Release REVISION:

I...................

II 12-OHP-4024-139 Level of Use: REFERENCE

16 ANNNUNCIATOR #139 RESPONSE: RADIATION RADIOACTIVE LIQUID EFFLUENT INITIATING DEVICE(S)

I NOMINAL

AEP, Alias SETPOINT CHANNEL ID:

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

Monitor Alarm Set by RP RRA-1003 Channel Failure (Area Monitor)

High Radiation RFS-1010 High flow (90% increasing)

(Sample Flow)

Low Flow (20 % decreasing) 1 PROBABLE CAUSE(S):

1.1 RED:

Movement of radioactive material in specified area.

[Low effluent flow.

High/low sample flow.

Channel failure.

1.2 WHITE

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

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 External, Fail High, or Fail Low status.

Any monitor fails communications program or Unit's CT is Off-Line.

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

Page 52 of 95 Rev. 10a General CUE1S No cues on this page - operator actions start on next page.

Page 1 of 4 I

q ip It It

COURSE NUMBER N02-A3

!ANDTITLE: iTerminate a Liquid Release REVISION: 0 12-014P-4024-139 L.evel of Use: REFERUENCE 2

AUTOMATIC ACTION(S);

2.1 Any of the following will trip selected WECT Punp and Monitor Tank Pump:

Hilh Alarm on RRS-.1001 trips closed RRV-2&5.*._

Chaanel Failure on RRS-1001, RRRh1002.

Hi h/Low Flow on RFS-1010, 3

3,1

16 OPERAT'OR ACTION(S):

3.1..1 Verify required automatic actions occur.

3.1.2 XIF Hig Alarm exists on RAS-10OI, THEN perform the following:

a.

Verify tank being discharge has bee, sa and approved for

release, Verify tank being discharged is not beig filled.

c, Notify RP AND reqyest Chemistry sample tank.

d.

IF necessary, TIEEN repeat process.

3.1.3 IF Channel Failure exists, THEN isolate tank, 3.1.4 IF Sample Flow h-ligh/Low, THEN readjust flow to within limits per.

12-OIIP-4021-O06-0014, '1"rr ferring Distillate froom Monitor Tanks,

3.2 WHITE

3.2.1 Ideantify failed channelts) AND refer to TS Tables 3,3-3 andfor 3.3-6 or TS 3.4.6.1 for appropriate Action Statement.

3.2.2 Attempt to restore affecewd channel(s) to Normal.

3.2,3 IF chamuel is inoperable, THEN refer to PMP-.4030.-EIS-OO1, Event-Initiated Surveillance Testing, for appropriate actions and surveilances, Page 53 of 95 Rev. 10a 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" Notify RP & request another tank sample from Chemistry.

Cue : "Control Room has performed required notifications &

requests that you close out release paperwork Attachment 3, Steps 4.13 through 4.16."

Page 2 of 4

COURSE NUMBER N02-A3 A N D T IT L E :

T e r m i n at e a us S....

((Terminate a Liquid Release REVISION: 0 II "*:-::" =::""::::>:*'*"'..

. II:::::::::::::::

Reference 12-OiiP4021-006-004 F

Rev. 25 M

Page 25 of 58 Transferring Distillate From Monitor Tanks

- This section is N/A Monito r Tank Release To The Circ Water A m System-I Pages:

14-28 MONITOR TANK NO.

RELEASE NO.

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.

NOTE:

In order to open 12-RRV-285 after high alarm on RRS-1001, monitor must be flushed to reduce radioactivity below alarm point.

4.14 IF 12-RRV-285 closes because of high radiation detected by RRS THEN perform the following:

"4.14.1 Notify Radiation Protection.

4.14.2 Close AND seal 12-WD-166, Rad Liquid W 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 expetted 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.

Notifies Radiation Protection Cue: "Radiation Protection has been notified" Obtains seal and closes 12-WD-1 66. Places seal on the valve.

Cue: Handwheel has stopped moving.

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 Page 3 of 4 L

]

/

COURSE NUMBER N02-A3

-REVISION: 0 AND TTLE:

Terminate a Liquid Release Reference 12-OHP-4021-006-004 I

Rev. 25.

Page 26 of 58 Transferring Distillate From Monitor Tanks Monitor Tank Release To The Circ Water I

Pages:

Attchmnt ank System-ae 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 fo wing RRS-1000 channels to attach to Data Sheet I:

RRS-1001 RFS-1010 (N/A.if already performed)

RFA-101I1 (N/A if already performed)

b.

Place RFS-1010 and RFA-1011 in POLL OFF at RMS-CT (NIA 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:

/ /

of release completion 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.

1 12-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 and placed RFS-1010 & RFA-1011 in POLL OFF at RMS-CT."

Places South Monitor Tank Pump Mode Selector Switch to Recirc

- Presses ALM ACK button on DAM

- Marks Flow Recorder

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

- 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-1001 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

TITLE Complete EMD-32a Nuclear Plant Notification Form REI~~SION 0

NRC License Exam TIME 10 Minutes Revision 0: Initial Issue DEVELOPING, INSTRUCTOR:

OPERATIONS REVIEW:

Name:

Signature:

Name:

Signature:

Dale Tidwell 9/7/02 Page 1 of 3 I T. Werk kcýýý

COURSE NUMBER N02-A4 AND TITLE:

Complete EMD-32a Nuclear Plant 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 Evaluation Setting Classroom I Handouts I

Task Briefing & MIDAS Summary EMD-32a Nuclear Plant Event Notification (blank form) lAttachments None 11 Simulator Setup None Page 2 of 3 11

COURSE NUMBER N02A4 1

REVISION: 0 AND TTLE:

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

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 1 when neither emergency diesel generator successfully energizes their associated busses.

The crew successfully restores power to the T11 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 (Use Current Time

& have candidate enter on briefing handout)

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 N02-A4 REVISION: 0 AND TITLE:

Complete EMD-32a Nuclear Plant Event Notification Reference PMP-2080-EPP-107 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_ (S Area Emergencv or General Emergency) has been declared due to (brief description)

Activate the Technical Support Center, Operations Support Center, Emergency 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 classification of any emergency perform the following:

a.

Complete Nuclear Plant Accident Notification form, EMD-slty 32a, (from Emergency Kit or DAP printout).

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

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.

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

c.

Document phone calls on Data Sheet 1, Shift Manager Initial Notification List.*

Page 1 of 3

COURSE NUMBER N02-A4 AND TITLE:

C E

StComplete EMD-32a Nuclear Plant Event Notification I

EVISION: 0I eference PMP-200-.EPP-107 Rev. 16 j

page 5 of 1 Notification

d.

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

e.

Request a call back front 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.

N E:

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 will 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 as possible after the State and County have been notified, and within one hour of classification.

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

Page 2 of 3 I.

COURSE NUMpeBER.D N02-A4 AND TTLE:

Complete EMD-32a Nuclear Plant Event Notification REVISION: 0

'::No

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1 All items should be completed on the form prior to submitting to the Site Emergency Coordinator for approval.

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

CT: - "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

T: "System Malfunction" box marked CT: - "S-2" MUST be filled in 1_

C:"- "Stable" box MUST be marked 3

- "No" box MUST be marked CT: - "None" box MUST be marked Wind from "2620" to "820" filled in Wind speed "10" mph filled in "Stability Class "E" filled in Precipitation "Yes" box marked Student reports form complete and ready for SEC approval.

JPM IS COMPLETE.

Page 3 of 3 A

...r.-:.,

Task Briefing You are an extra Control Room Operator on Unit 1. At the beginning of your shift, Unit I 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 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 1OM - Main Tower Wind Speed 1OM - Main Tower Precipitation - Main Tower Wind Direction 1 OM - 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 00 00 00 E

60.8oF NA Page 2 of 2

EMD-32a (01 - 02)

MICHIGAN STATE POLICE Nuclear Plant Event Notification El Actuarl Event Drill Plant Contact Information Nuclear Power Plant Plant Communicator, Calling From: C Control Room 0 TSC Q EOF Q Other:

Call Back Telephone Number Plant Message Number Current Classification 0 Unusual Event 0l Alert 0 Site Area Emergency CI General Emergency 0 Termination This classification was declared as of Date Time Reason for Classification o-Abnormal Rad Level / Radiological Effluents El System Malfunction Q Fission Product Barrier Degradation 0 Hazards and Other Condition Affecting Plant Safety or Natural/Destructive Phenomena Cook IC Number Plant Status Q Stable

'Cl Degrading C Improving C3 Recovery Radiological Release in Progress Due to Event Q Yes 1No Protective Action Recommendations ol Non.e vau o--------------------------------------------------------

Evacuation of Area(s).

0.1 0.2 0 3 0 4 0..5 n-P1aceShelterofArea3s)

El 2 0 3 0l4 Q5--

PAR based on: El Dose Calculations (technical data required)

Q Plant Status 0 Security Event 0l Other Meteorological Data Wind Direction (degrees): From To -------

Wind Speed (MPH):.

S'tability Class:_________

Precipitation: 0 Yes 13 No Aulhorily NUREG 0654 Compliance Voluntary Plant Approval: _________________Date:

_________Time:___________

N0A,5a Verify Ultimate Heat Sink Temperature Determination (SRO review)

NRC License Exam REVISION 0

TI ýM E

15 Minutes DEVýELIOPIN 7G INSTRUCTOR:

OPERATIONS REVIEW:

Name:

Signature:

Name:

Signature:

R. Niedzielski Page 1 of 3 Revision 0 9/7/02 919 16Z

COURSE NUMBER i N02-A5a - Verify Ultimate Heat Sink Temperatu REVISION: 0 SAND TITLE:

fIDetermination 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 fl Handouts 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) jj Attachments None Simulator Setup Reset to Mode 6 IC Close CW Condenser Inlet and Outlet valves:

A Condenser South 2-WMO-103 & 104

C Condenser North 2-WMO-301 & 302 Shutdown 2 CW Pumps (2 CW Pumps left running)

Page 2 of 3

COURSE NUMBER N02-A5a - Verify Ultimate Heat Sink Temperature REVIS I 0

.- AND TITLE:.

Determination REVISO:

0 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:

Condenser 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 Condenser B WTX-206 = 77.2 WTX-207 = 77.1 WTX-208 = 77.3 WTX-202 = 76.9 WTX-203 = 76.9 WTX-204 = 77.0 Condenser 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 FLUKE/2175 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 IREVISION: 0 S AND TITLE:

I Continuous I

02-OuiPa030-STP-030 I

Rev. 39 aagd e 81 of 145 DAILY AND SHIFrLY SURVEILLANCE CHECKS Data Sheet 5 Shift Surveillance Checks Modes 5, 6 and Defeled Pages:

1 70- 83 Instrument Title & No.

O0-08 108-16 116-24 Acceptance Criterion IValue 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 Baaes.

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. (MS 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.

14.1 Circ Wtr Temps :

"S 3.9.3** for Decay.Tis=e:

.' Take reading from SG-21 Ulu U20 sop14.1-Lss thanor Point 1, Circ Water Temp

-F

F

F iequal to 74.6°7 on SG-21 Recorder.

o. I(i.e.. 77.8+/-3.rF

IF recorder is energized and the printer is inoperable,

-OR.

Step 14.2 - less than or THIEN take readings from equal to 76.8'F the PPC, U0200.

0.e., 77.8 + 1' instrument uncertainty for M&TE

- OR -

calibrated Fluke-52 with a 12' probe, or equivalent).

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

Record instrument ID

." Decy Time from Instrument make/model: _

_to 148 hrs Current calibration YIN _

Circ Wtr Temp

>74.61t (using Take one inlet temperature measurement of each Condenser in Step 14.1 ) OR

>76.8F (using service using the M&TE calibrated instrument with +/-1lF Step 14.2) usncerainty and cailcu Condenser A Circ W Check box for inlet t O WTX-106 or "O

WTX-107 or "o

WTX-108 or "O

WTX-102 or o WTX-103 or o3 WTX-104 late the average.

Ul 0 U2 0-

T WO ovmetof ater Inlet:'

irradiated fsel until either of the following conditions are met:

neasured:

Cirt Wtr Temp is 1,74

te R5s76.S*F ing Step 14.2)

-OR Decay Time is greater than 148 his.

F OF -F

4 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 CS I C8 Reviews instrument data for accuracy.

--j-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:

W7X-102 = 771 WTX-103 = 774 WTX-104 = 76.8 Page 1 of 2 Revision 0 114.0

..CT: Determines a box is not checked and that the temperature p!gged (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= 771 WTX-208 = 773 WTX-202 = 76.9 WTX-203 = 76.9 WTX-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 = 770 WTX-308 = 770 CT: Determines average temperature logged (75.22 oF) is in error (should be between 76.9 oF - 77.3 oF).

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

JPM IS COMPLETE.

Page 2 of 2 Revision 0

B Condenser South Inlet Temp WTX-207 77.1 8 Condenser South Inlet Temnp WTX-208 77.1 B Condenser South Inlet Temp WTX-208 77.3 B Condenser North Inlet Temp WTX-202 76.9 B Condenser North Inlet Temp WTX-203 76.9 B Condenser North Inlet Temp WTX-204 77.0 I

I F-.-

r P T

All Temperatures are valid t9 4.4 T

PP 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 MAI t/rh1.xq i Iri II I.!L-C Condenser South Inlet Timm p XAI-3Y 07 77 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 Condenser North Inlet Temp WTX-304 71.3 South Temperatures are valid Page 1 of 1 Revision 0 4~'1 4'~3101 193 O~ P

-P R'~ AL Dp T

T T-~

~

i Tr O

r OP C

1. -P DO P

Cnt'.

ttZ; T

p

\\AFry.RnR 77 4

"rr F.ri o B Condenser South Inlet Temp WTX-206 77.2 l Ilt:illr*,*Jl*

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:

Condenser A Condenser B Condenser C WTX-106 = 71.8 WTX-206 = 77.2 WTX-306 = 77.1 WTX-107 = 71.8 WTX-207 = 77.1 WTX-307 = 77.0 WTX-108 = 72.2 WTX-208 = 77.3 WTX-308 = 77.0 WTX-102 = 77.1 WTX-202 = 76.9 WTX-302 = 71.2 WTX-103 = 77.4 WTX-203 = 76.9 WTX-303 = 70.9 WTX-104 = 76.8 WTX-204 = 77.0 WTX-304 = 71.3 Temperature readings were obtained using Instrument ID CNP-147, Make/Model FLUKE/2175 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 I

Instrument Title & No.

00-08 08-16 16-24 Acceptance Criterion n

Value 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. (TS 3.9.3)

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

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

14.1 Cire Wtr Temp*:

Take reading from SG-21 Point 1, Circ Water Temp Recorder.

IF recorder is energized and the printer is inoperable, THEN take readings from the PPC, U0200.

U10J U20J W/A OF OFI OF

- OR 14.2 IF Circ Water Temp is greater than or equal to 72°F OR measurement cannot be obtained in Step 14.1 OR a more accurate value is desired, THEN obtain an M&TE calibrated temperature measurement instrument and perform the following:

Record instrument ID C N P Instrument make/model:

FLUKE Current calibration Y/N

'Fr 147

.1/ Z17 Take one inlet temperature measurement of each Condenser in service using the M&:TE calibrated instrument with +/-1+F uncertainty and calculate the average.

Ul[]

U2 0 Condenser A Circ Water Inlet: +

Check box for inlet measured:

[] WTX-106 or

[] WTX-107 or

[] WTX-108 or 12 WTX-102 or 12 WTX-103 or C3 WTX-104 TS 3.9.3** for Decay Time:

Step 14.1 - Less than or equal to 74.6°F on SG-21 Point 1, (i.e., 77.8 +/- 3.20F instrument uncertainty)

-OR Step 14.2 - less than or equal to 76.87F (i.e., 77.8 +/- I°F instrument uncertainty for M&TE calibrated Fluke-52 with a 12" probe, or equivalent).

IF the Unit is in MODE 6 with movement of irradiated fuel in the vessel in progress between September 15 and June 8* with:

"* Decay Time from 100 hrs to 148 hrs

-AND

"* Circ Wtr Temp

> 74.6°F (using Step 14.1 ) OR

> 76.8 0F (using Step 14.2)

THEN STOP movement of irradiated fuel until either of the following conditions are met:

Circ Wtr Temp is

_<74.6 0F (using Step 14.1 ) OR <76.8"F (using Step 14.2)

-OR Decay Time is greater than 148 hrs.

F74. 0 F I

°F I

°F Continuous 02-OHP-4030-STP-030 Rev. 39 Page 81 of 145 DAILY AND SHIFTLY SURVEILLANCE CHECKS Data Sheet 5 Shift Surveillance Checks Modes 5, 6 and Defueled Pages:

70-83 14.U C

IC A

'I

T,+...,........... 'r':...i..

fl I

.

I I

J.+/-

L uiinnLt I MlLe a INO.

Va-0u

() I..

14 Cc 08-16 16-24 Acceptance Criterion UIl J U2 Q 1-1.o0F

°F Condenser B Circ Water Inlet:+

Check box for inlet measured:

C) WTX-206 or Qi WTX-207 or El WTX-208 or C3 WTX-202 or C3 WTX-203 or Q WTX-204 Condenser C Circ Water Inlet:+

Check box for inlet measured:

C) WTX-306 or 0i WTX-307 or C) WTX-308 or ci WTX-302 or C] WTX-303 or 0i WTX-304 (Cond. A+B+C OF) / 3 T75.2ZF

°F I FI Record current MODE*

Per Technical Specification Table 1.1, Operational Modes:

Continuous 02-OHP-4030-STP-030 Rev. 39 Page 82 of 145 DAILY AND SHIFTLY SURVEILLANCE CHECKS Data Sheet 5 Shift Surveillance Checks Modes 5, 6 and Defueled Pages:

70 - 83

[74.O9'°F OFI 7F ont 15.0 I

A5

Perform Control Room actions for Fuel Handling Accident in Containment NRC License Exam

=DEVELOPING INSTRUCTOR:

Name:

Signature:

0 15 Minutes R. Niedzielski

-4 e

O1PER ATIONS REVIEW:

Name:

Signature:

Page 1 of 3 9/7/02

K COURSE NUMBER N02-A5b Perform Control Room actions for Fuel I

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 Handouts Task Briefing Attachments 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-105, 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 RII ON:

0

[

AND TITILE:

Handling Accident in Containment REION0 Task 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.

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.

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

N02-A5b Perform Control Room actions for Fuel Handling Accident in Containment Tidc Niwmba IRRADIATED FUEL NDLING ACCIDENT IN 4..4 CONTAINMENT BUILDING'- CONTROL ROOM ACTIONS STEPI ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

1. Actuate Containment Evacuation Alarm

2. Notify All Non-essential Personnel To Evacuate Containment

`Q

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 4

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.

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

.m

COURSE NUMBER I[N02-A5b Perform Control Room actions for Fuel Handling Accident in AND TITLE:

Containment

-REVISION: 0 Iil.

.e N'umnbe" IRRADIATED FUEL HANDLING ACCIDENT IN 12-OHHP 4022.018.004

[

CONTAINMENT BUILDING - CONTROL ROOM ACTIONS STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

6. Verify Containment Purge in the affected Unit - ISOLATED:

Unit 1:

"° Supply Air Valves - CLOSED.

"* I-VCR-103

"* 1-VCR-203

"* 1-VCR-105

"* 1-VCR-205

"* Exhaust Air Valves - CLOSED.

1-VCR-104

I-VCR-204

1-VCR-106 I-VCR-206 OR Unit 2:

"* Supply Air Valves - CLOSED.

"* 2-VCR-203

"* 2-VCR-105

"* 2-VCR-205

"* Exhaust Air Valves - CLOSED.

2-VCR-1041V_

.2-VCR-204" 2-VCR-106 2-VCR-206 Operator Closes Unit 2 supply air valves (at least 1 per penetration):

CT:

Lower Cntmt Supply Air 2-VCR-103 lLower Cntmt Supply Air 2-VCR-203 CT.:

Upper Cntmt Supply Air 2-VCR-105

- Upper Cntmt Supply Air 2-VCR-205 Operator Closes Unit 2 exhaust air valves (at least 1 per penetration):

.. CT_.f_ Lower Cntmt Exhaust Air 2-VCR-104 L Lower Cntmt Exhaust Air 2-VCR-204 CT*f Upper Cntmt Exhaust Air 2-VCR-1 06 L Upper Cntmt Exhaust Air 2-VCR-206 Page 2 of 8 1

I

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

'ANDI TTLE

Containment SREVISION 0

II II IRRADIATED FUEL HANDLING ACCIDENT IN 12-O 4

CONTAINMENT BUILDING - CONTROL ROOM ACTIONS STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

7. Verify Instrument Room Purge in the affected Unit - ISOLATED.

Unit 1:

"* Supply Air Valves - CLOSED.

1-VCR-101 I-VCR-201

"* Exhaust Air Valves - CLOSED 1-VCR-102 I-VCR-202 OR Unit 2:

"* Supply Air Valves - CLOSED.

2-VCR-101 4

"* 2-VCR-201

"* Exhaust Air Valves - CLOSED

"* 2-VCR-102

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

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

Containment REVISION: 0 Tjfle Nun~bý IRRADIATED FUEL HANDLING ACCIDENT IN 12-OILP 4022.018.004 CONTAINMENT BUILDING - CONTROL ROOM ACTIONS 7STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

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

Unit 1:

I-HV-CPR-1 OR Unit 2:

2-HV-CPR-1

.4

9. Verify Containment Pressure Relief Valves in the affected Unit-CLOSED:

Unit I:

"* 1-VCR-107

"* I-VCR-207 OR Unit 2:

"* 2-VCR-107

"* 2-VCR-201 Operator verifies Unit 2 Containment Pressure Relief fan stopped Operator verifies Unit 2 Containment Pressure Relief Valves (2) closed Page 4 of 8

1.

1

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

" Containment REVISION: 0 1

II II Tite Number IRRADIATED FUEL HANDLING ACCIDENT IN 12-OHP 4022.018.004 CONTAINMENT BUILDING - CONTROL ROOM ACTIONS STP ACTON/EXPECTED RESPONSE RESPONSE NOT OB3TAINED0

10. Isolate Control Room Ventilation To BOTH Units:

a. Unit I:

1) 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 l-HV-ACR-DA-1, Control Room Vent Intake Damper Close 1-HV-ACR-DA-1A, control room vent intake damper Align the following Intake Dampers one Partial Open AND one Closed:

I 1-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 1-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 of8 1

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

Containment FREVISION-O 1

I TLRRA Numb IRRADIATED FUEL HANDLING ACCIDENT IN 12-O. P 4022.018.004 CONTAINMENT BUILDING - CONTROL ROOM ACTIONS STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

b. Unit 2:

I

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-ACR-DA-2, Control 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 4

p 14-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 verifies Inst. RM Purge supply and exhaust fans stopped Page 6 of 8

COURSE NUMBER 11 N02-A5b Perform Control Room actions for Fuel Handling Accident in

.AND TITLE:

Containment REVISION: 0 II II Titic Nu b.,

IRRADIATED FUEL HANDLING ACCIDENT IN CONTAINMENT BUILDING - CONTROL ROOM ACTIONS STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 11-

12. Check Additional Auxiliary Building.

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

a. Remove Auxiliary Building Supply Fan from service IAW 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 4

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

Containment K

Reports task completed.

JPM IS COMPLETE.

Page 8 of 8 T i d."

N u m IRRADIATED FUEL HANDLING ACCIDENT IN 12-OHP 4022.018.004 CONTAINMENT BUILDING - CONTROL ROOM ACTIONS STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 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.

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

Page 1 of 1 N02-A5b.doc

TPerform an Initial Dose Assessment

[PROGRA NRC License Exam REVISION 0

TIME 10 Minutes Revision 0: Initial Issue DEVELOPING Name:

I RUCTOR:

Signature:

REVIEW:

Name:

Signature:

Dale Tidwell T. Werk Page 1 of 3 9/7/02 q)/q /Oz 6=1

1-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 E -

EVALUATION SETTING Computer terminal with Dose Assessment Program (DAP) installed.

HANDOUTS Task Briefing

'ATTACHMENTS None B

~SIMULATOR SETUP None Page 2 of 3 Revision 0

COURSE NUMBER N02A6 REVISION: 0 AND TITLE:

Perform an Initial Dose Assessment TASK OBJECTIVES/STANDARDS Terminal Obiectives:

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.

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

~ AN TILE:

Perform an Initial Dose Assessment "Inf oraton O-E ev. 4 Page 3 of 9 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 wil appear at the bottom of the screen.

NOTE:

Dose assessment projections may only be performed using the DAP. IF' projected doses are NOT available and a PAR is necessary, THEN use the default PAR in PMP-2080-EPP-100.

4.1 Determine which forms are requiaed.

4.1.1 EMD-32a, Nuclear Plant Event Notification.

"* Is only transmitted to the StatelCoumy within 15 minutes of a change to,

the 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-mminet, "intervals of the last EMD-32b or.MD-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

4., Pasquill Category, provides for Pasquill Category (Stability Class) determinations.

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

Information I-2080-EP-Rev. 4 Page 4o 9 Initial Dose Assessment 4.3 Obtain RMS radiological data from one of the following sources:

[ NOTE:

ources are listed in order of preference.

PPC RMS Display Terminals Direct readings from.the Local Area Data Acquisition Modules 4.4 Determine the Unit I and Unit 2 reactor shutdown status and the date and time of shutdown as applicable.

4.5 Determine the Coolant Type.

oolant Type Containment High Radiation Monitorig Uig NorMal Coolant

< 10 R/hr Cladding Damage

< I000 R/hr Fuel Melt

> = 100UR/hr 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-2310 and VRA-2410) are less than 10 R/hr.

4.6 Determine whether an actual or potential release is occurring.

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

Valid indication on release point radiation monitoring system channels are present that are associated with a classified event,

- 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)).

Actual release is in progress as provided with briefing.

Page 2 of 12 Revision 0

COURSE NUMBER N02-A6 AND TITLE:

Perform an Initial Dose Assessment REVISION: 0 formation P-I ev. 4 age5 O Initial Dose Assessment 4.7 4.8 Determine the Projected Duration of the Release.

IF the projected duration of the release is unknown, THEN use 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

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

Enter the data into the Dose Assessment Program.

4 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 Sheriff's Department and the State of Michigan.

5 REFERENCES 5.1 Use

References:

5.1.1 Dose Assessment (DAP) Computer Program 5.1.2 EMID-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 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

Under the General tab, the student should I This is a DO Oedthjs boxto pdntTRis is a Dnill'on the EMD-32 Form I

I A"'~

*i~i

r.

'i...

i* ** *i i

7-22374

,*i***

- - - ** :i:* i 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

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

COURSE NUMBER N02-A6 AND TITLE:

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

CT Complete U2 Fuel Status by selecting Normal Coolant per step 4.5 of PMP-2080-EPP-1 08.

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

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

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

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

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

Page 6 of 12 Revision 0

COURSE NUMBER N02-A6 AND TITLE:,

Perform an Initial Dose Assessment Under the Plant Status tab, the student should CT Complete Wind information by entering 10M Main wind speed (4 mph) and wind direction (275o) 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.

Wind and Pasquill Category affect the dose assessment calculation.

Page 7 of 12 Revision 0

.0AP! OV1.,0 14--1 CH.i I !

LEc~il*!iI* Mo*iii

00_

Data__ OYA 141Af Ii oe fiaw~

~

~S M 4 Cii-f Basis I

Under the Calc. Basis tab, the student should CT CT Enter the current date and time.

Complete Calculation Basis by verifying Gaseous Release - In Plant Monitor is selected. This enables the Gaseous Release tab to enter the applicable Radiation Monitor data given with the briefing.

(NOTE: Gaseous Release - In Plant Monitor is the default selection.)

NOTE the Field Team tab will NOT be enabled for this JPM. Field Team Data must be selected to enable the Field Team tab.

Complete PAR Basis by verifying Dose Calculation is selected. This section is used to complete the EMD form(s). However, the Dose Assessment Program will ONLY generate PAR recommendations based on Dose Calculations. (NOTE: Dose Calculation is the default selection.)

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

Page 8 of 12 Revision 0

, xI

COURSE NUMBER N02-A6 AND TITLE:,t Perform an Initial Dose Assessment llREV 0

E1X1 1SwiwtfJi

k1mrin'

IAUn

Ht I 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.)

Gaseous Release affects the dose assessment calculation.

Page 9 of 12 Revision 0 I-t

COURSE NUMBER, N02-A6 IAND TITLE:

Perform an Initial Dose Assessment i

90 II P

I1 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

COURSE NUMBER. N02-A6 AND TITLE:

Perform an Initial Dose Assessment EI IEIw0ý fKASwII&

R ewgý a

En rdIh JoCc"mI m k 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 "MMMEMMMOMM I*

IT a

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-1 01, 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

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.

N02-A6.doc Page 1 of 2 Revision 0

DOSE ASSESSMENT INFORMATION ID

- RMS052

- RMS054

- RMS055 DATA DESCRIPTION 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-2510 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

- 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 10M -MAIN TOWER ELR-400

- U0805

- PRECIPITATION - MAIN TOWER EFR-413

- U0806

- WIND DIRECTION 10M - BACKUP TOWER EFR-403

- U0807

- WIND SPEED 10M - 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 VALUE UNITS 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 1.1 OOE-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 TAG

CIfCC gOCI/CC gCI/CC R/H R/H gCI/CC pCI/CC 4CI/CC CFM gCI/CC I.CI/CC gCI/CC pCI/CC pCIICC "pCI/CC pCI/CC CFM "4CI/Cc gCI/CC pCI/CC CFM U0802 U0803 U0804 NONE NONE NONE

FTW 1

Calculate QPTR with Inoperable Power Range 0SION Instrume n E

t1 i

nute PRGRMNRC License Exam TIE15 Minutes DEVELOPING INSTRUCTOR:

Name:

Signature:

DAT7E 91/702 R. Niedzielski q(-,

YI OPERATIONS REVIEW:

Name:

Signature:

T. Werk 9

1C)oZ Page 1 of 3 Revision 0

COURSE NUMBER N02-A7a Calculate QPTR with Inoperable Power REVISION: 0 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

[Evaluation Setting Simulator J[Handouts Task Briefing for N02-A7a Copy of 02-OHP-4030-STP-032 Attachments None Simulator Setup Initialize to at power IC (IC 37), with N-42 failed (Malfuction NIIOB, 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)

Verify lit Status lights to ON for 2-SML-16: 2, 27, 32, 42 and 47 AND 2-SML-17: 7 and 12 Hang Caution Tags on above selector switches (7)

Page 2 of 3 Revision 0

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

Range Instrument Task 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.

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 US directs you to perform a QPTR calculation per 02-OHP-4030-STP-032, Quadrant Power Tilt Calculation.

Page 3 of 3 Revision 0 ITask Briefing I

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

I REVISION: 0.

Reference I

02-OHP 4030.STP.032 Rev.

'a Page 3 of 11 QUADRANT POWER TILT RATIO CALCULATION General CUES-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.

-CUE: PPC is inoperable for QPTR calculation Operator determines step 4.4 is correct step Page 1 of 5 Revision 0I I

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

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

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 120% 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:ý N02-A7a Calculate QPTR with Inoperable Power Range Instrument AND TITLE:. : /1 REVISION: 0 Reference-7 02-OHP 4030.STP.032 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.

4.4.2 Obtain power range excore amperages as follows:

NOTE:

ADl 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 3.

4.4.3 Enter the individual upper and lower power range 120% current 4------'

values in the appropriate blanks on Data Sheet 3.

4.4.4 4.4.5

-Operator 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) f,} 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 Divide each individual NI current by its 1206/6 amperage.gOperator divides respective NI channel with its 120% value (from D cards on channel 3 NI panel)

Total the normalized values determined in Step 4.4.4. 4 Operator totals 3 channels of normalized values 4.4.6 Using the formula on Data Sheet 2, determine the upper and lower QPTR.

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

CT: Operator determines upper and lower QPTR using data sheet 3 with an accuracy of.001 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

COURSE NUMBER N02-A7a Calculate QPTR with Inoperable Power Range Instrument FREVISION: 0 ]

I AND TITLE:-

Page 4 of 5 Revision 0 Reference I

02-OH 4030.STP.032 Rev. 8a Page 6 of

]

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 EVISIO AND TITLE:.

REVISIO:.

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

Using 3 NIS 11 Upper Record Detector Record Detector Normalized Value Detector "A" Current "A" 120% value Detector A + 120% value IN-41

.0940

.1139

.8253 N-

.0990

.1206

.8209 N-

.0989 1204

.8214 Upper Total 2.4676 Lower Record Detector Record Detector Normalized Value Detector "B" Current "B" 120% value Detector B - 120". value N-41..0883

.1062

.8333 N-

.0987

.1192

.8280 N-

.0932 M

.8237 Lower Total 1

2.4850 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 Uuper Normalized Vahie Upper Total x 3 eTilt Ratio Max Lower Normalized Value Lower TiltRLower 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 1.0060 N/A ENPR 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.

Acceptance Criteria: Calculated QPTR is less than or equal to 1.02 Date:

Time:

Date:_______

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

JPM IS COMPLETE.

Page 5 of 5 Revision 0 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 US directs you to perform a QPTR calculation per 02-OHP-4030-STP-032, Quadrant Power Tilt Calculation.

N02-A7a.doc Page 1 of 2 Revision 0

N02-A7a.doc Page 2 of 2 Revision 0 NI CALIBRATION DATA DET A 120% I in u Amps N41 =

0.1139 N42 =

0.1196 N43 =

0.1206 N44 =

0A204 DET B 120% I in u Amps N41 =

0.1062 N42 =

0.1136 N43 =

0.1192 N44 =

0.1140 Verified: Print Sign Date

1 NO TITLE Determine Actions to Change Containment Integrity Options During Refueling PROGRAM NRC License Exam DEVELOPING INSTRUCTOR:

OPERATIONS REVIEW:

Name:

REVISION TME 15 Minutes 9/7102 S. Pettinger Signature:

Name:

Signature:

Page 1 of 3 9 cIeoz_

T. We.,H.I ul-3ý

COURSE NUMBER N02-A7b - Determine Actions to Change AND TITLE:

Containment Integrity Options During Refueling RVS.I.

ON:

0 References 1

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 Handouts Task Briefing

,Attachments None Simulator Setup N/A Page 2 of 3

COURSE NUMBER N02-A7b - Determine Actions to Change AND TITLE:

Containment Integrity Options During Refueling REISION: 0 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 I

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-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 1 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 N02-A7b - Determine Actions to Change Containment Integrity Options During REVISION: 0 AND TITLE:

Refueling CONTINUOUS i

01-OHP-4030-127-041 Rev. 0 Page_60of 318 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

"* The reason for NOT HUNG shall be 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 log this valve on Data Sheet 4.

4.2.6 IF 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 trom Data Sheet 1.

c.

Perform and verify lineup for desired option.

1. IF Refneling Integrity is required while changing 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.

General CUEPS Page 1 of 6

COURSE NUMBER N02-A7b - Determine Actions to Change Containment Integrity Options During REVISION:_0 AND TITLE:

RefuelingI CONTINUOUS 0I-OHP-4030-127-041 Rev. 0 Page 297 of 318 Refueling Integrity Data Sheet 5 Daily System Parameters Pages:

295-302 DESCRIPTION Ref. Page INSTRUMENT VALUE INITIALS CPN-75 (2) OPTION A CCW 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 I-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 CPN-29 (1) OPTION C Not Cross Containment Control Air Headers Page 208 tied CPN-29 (2) OPTION A Plant Air Pressure Page 210 I-PPI-10

> 20 psig NO. I SG OUTSIDE CONTAIINMENT (N/A IF INSIDE CONTAINIMENT UTILIZED)

CPN-6 (1) OPTION A WR Level #11 SG Page 223 I-BLI-1 I0

> 5%

CPN-7 (1) OPTION A WR Level #11 SG Page 224 1-BLI-Il0

> 80%

CPN-66 (9) OPTION A WR Level #I1 SG Page 226 1-BLI-110

> 5%

CUE: Alarm is no longer valid Page 2 of 6 -

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

Refueling I

C(ONTIN -oUS-01-OHP-4030-127-i41 Re~v..0 j

11 1ael 1o~8 Refueling Integrity lDita Sheet I CPN.teagitvy Checks For Core Aerations PIZ-e7 12 -2718 (AIN TAG PEORMtED INDUER.

.[.NTFICATON !

REQUIREM1ENT 1UNG BY BY (7PN-74 NOTE:

Containment Conirol Air headers may be cross-tied to support B&C Leak Rate Testing and/or maintenance on Containment isolation valves of CPN-74 or CPN-29. When Cttaninmejn Control Air headers awe cross-tied, care should be taken in selecting the appropriate option. For example, with the headers cross-tinc and I-XCR-101 cdosed, the conditions for Option D may be met but Option E or F would be required to ensure. Refueling Integrity is nssiaantah'd.

(

0 0' P O>TI)N A (Con.trol Poom);

Verify system is pressuriZed; Ansn, 104, Drop 33 "CONTAINMENT CTRL AIR 11DR PRESSU1R.

LOW-ts clear D OPTION B (CAS);

Verify system is pressurized; Ann. 124. Drop 30 "CNMIl' 100 PSI CTRL AIR HDR 2 PRESSURE LOW" is clear (i)/S 5)

ALARM CLEAR (DIS 51 ALARM CLEMR JOPTIION C (Control Room

& CAS.,:

Containanrtt Control Air headers are not cross-tied as indicated by l'tc'dstai shed "Icntpur ary di Log ldex,

-ANND -

IDrS 5)

Not Cross-Tied 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 of6 I

COURSE NUMBER N02-A7b - Determine Actions to Change Containment Integrity Options During REVISION: 0 AND TITLE-Refueling Co NYIMNUOUS 01-O1)lIP-44304127-041 jI Re.

a' 1

f 3718 Refueling Integrity DataI PactI gesý ia Sheet i (N

]qtegriity Cheeks Fox Core Ahterations 1

2752,.

CPN I)ENTUIC' ATI ON Verify two complete cyycles on any of the following valves (verifies 1-CA-385 is cpxn):

l-QRV470, 1 GGRiV-4S1

]- QC(R-301, I-DRV-100 I..VCR-L, 1-VCR-21 REQTTRURETNTr TAG PEtRFORMEO I.NDVER J31NG BY BY 2 CYCLES

-CT: Selects one valve and verifies that it cycles Two (2) times Requests that AEO read pressure on 1-XPI-186 at CAS panel

-.kN])-

1-XP[-I86 returns to

> 75 psiig (ensures C'PN is presswrized) 2 OPTION ) (IC & CAS Panel):

I-CA-385 (Q3 Pipe Anaulas Cortaitnmint Wall Stde between Colnmns 19 arid 20)

(D!S 5)

> 75 psig OPEN

-AND-I-XPI-1836 C(AS Panel" CQ OPTION F:

PC ern*eto SO whiXch -stabishsR'ei (D/S 5)

>v 75 psig C2LOSED O iPTIO:N F':

4

( t'irar,;e to 51(0-C which establishe-s RP.eli)ng Wcrgill CL#

Cue "1-XPI-186 reads 85 psig" CT: Verifies Pressure is > 75 psig

- 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

___1 4r"ý

COURSE NUMBER N02-A7b - Determine Actions to Change Containment Integrity Options During IREVISION: 0 AND TITLE:

Refueling I

CONTINUOUS 01-01P-41'30-127-041 Rev.O 1 age ] 5 of 318 Refueling Integrity D:,a Shet I I CPN integrity Checks For Core Alterations 12e-278 CPN WDENTIFICATION TAG PERFORMED

INDVER,

.IWBNG Y

By o CPN-74, Line (1) option changed

(,=e Step 4.2,6):

TIME 4DATE..

Unit Supervisor (2)

Q OVTION A (Startup Plash Tank Area): Nitrogen to PRT:

I-GCR-30}I (Control Room)

I-GPX-301-VI CLOSED CLOSED U OPTION B:

earenee to SRO-CA which establishes Refueling Inteerity CL #

J CPN-74, Line (21 option changed (see Stop 4.2,6)"

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

)ATE_____

CPN-74 OPTIONS VIBY IF[,

C(M [.,TE BY TIME DATE NAME I Signs that CPN-74 Options are Complete Reviewed By:

Date:.

St'pervisor!M.tage. Sig..r...e Reports task completed.

JPM IS COMPLETE.

Page 5 of 6 I,L DATE

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

Refueling CONTINUOUS

..01.O.P.4030-4 27A)41

Re

v.

P..e 116 of 318 Refueling Integrity Data Sheet,.1 CPt'1nrg.x;iy Checks For Coye Alteratio*rs i

Pas:

7 PLANT & CONTROL AIR CPN..74 txhoxt 4.q695 Page 6 of 6 L

OP.1.5120D I -5128A rl*ý).

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-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 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 I

NIIIA87 TITLE Verify a Clearance PROGRAM NRC License Examination REVISION 0

TIME 20 Minutes DEVELOPING Name:

INSTRUCTOR:

Signature:

OPERATIONS REVIEW:

Name:

Signature:

Dale J. Frie 7Z*~+/-r__I T. Werk 9/7/02 4)1<) /~z Page 1 of 3 V

COURSE NUMBER N02lA8 REVISION: 0 AND TIL:

... Verify a Clearance Permit' REFERNICES 12-OH P-21 10-C PS-001 Clearance Permit System Task: 3000040201 Verify a Clearance Permit.

K/A CROSS

REFERENCE:

2.2.13 K/A IMPORTANCE:

SRO 3.8 F

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

ATTACHMENTS 12-OHP-2110-CPS-001 Attachment 3, Clearance Development Checklist - Verifier IlMULATOR SETUP None Page 2 of 3

COURSE NUMBER N02-A8 REVISION: 0 AND TILE K!iVerify a Clearance Permit STask Standards The Candidate performs a review as per 12-OHP-21 10-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.

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

Pump Clearance #211795 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

Information..

12-OHP-2110-CPS-001 i

Re.

4 I

! P!ae33 of 41.

Clewaance Permit System Pages. '

Clearance Development Checklist-Verifier

.ages:

33-34 This checklist is to be used as an aid in Clearance development and is not intended to be a comprehensive list.

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

rainee 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.

Page 1 of 2 ACTIVITY CHECKS U Read JOA description: check unit designation, Clearance type (Red/Striped).

Q Docs activity fit within the boundaries of an existing Clearance?

CLEAJRA:NCE* CHECKS U Clearance written from a standard.

O) Special instructions to explain why specia rics were chosen Q Main equipment removed before suppo

-0 Is Containment Integrity maintained U Properly sequenced to prevent; auto actuation's and minimize retracing of steps Q Coifflict cheek, Sort, Tags-properly labeled (Red-Striped-Caution/Red Stripe)yg O Prints show boundaries and Clearance points Q Prints verified via NDIS U Management approval for Uncontrolled Drawings

COURSE NUMBER N02-A8 REVISION: 3 AND TITLE:

Verify a Clearance Permit Infonsnatsn 12-OtlP-2l11-CPS-001 Rev, 4 I

Pajge 34 of4I Clerance Permit System Clearance Development Checklist-Verifier Pages,.

T33-..34 MECHANICAL ELECTRICAL O Low energy < 100 psig < 130 *F 3 Any electric plant limitations o Steam side of trap isolated first LI Remote switches on HSD Panel High press side of pumped systems isolated first and other unit

Does component have seal water Ll One tag per lifted tead o At least one vent andlor drain tagged open. if U Motor Heater power possible C) Breaker cleaning maps Q Check drains that tie into a common header CU Alternate power O Planning notified if drain hoses affecting HELB C0 Control switch, fuses, breaker barriers L) Ground Clearance separate O Prevent rotation-isolate process flow C, Induced power (PT's) o Hazard&us gases, liquids and solids 0 Grounds required when working on electrical circults > 600 volts FIRE PROTECTION INSTRUMENTATION PM]P 2291,,PLN.001, Work Managemient Activity 0 Control Air isolated Planning Process C0 Failure position Appendix R C) Auto start signals O Document turn counts on Placement and Restoration Special Instructions ADMIN 0 Criteria for conducting infrequently performed tests or evolution: PMt-4090 Q) Event initiated surveillance PMP 4030.EIS.001 Q Racking 4 kV breakers 12-OIP 4021,082,009 D Racking 600 VAC breakers 12-OHP 4021.082.009 U Breaker Cycling PMP 2291.PMT.001

'J Non-positive boundary OHP 21 t0.CPS.001, Data Sheet 5 PMP 2291.OLR.001, On-Line Risk Management PMP 4-00.SDR,001, Plant Shutdown Safety and Risk Management Thi verification of the boundaries is independent and not influenced by the writer.

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

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 1

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

Pump Clearance #211795 per 12-OHP-21 1O-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

NUCLEAR CLEARANCE PERMIT SYSTEM CLEARANCE PERMIT COVER SHEET Print Date: 11/20/02 Page:

I Clearance Type: R Request in Effect Date:

FEG: 219.01 Unit: 2 Status: WRTTEN Time:

Clearance No: 2011795 Train Affected: A Equipment Cleared:

Desc:

2-PP-7E EAST ESSENTIAL SERVICE WATER PUMP Purpose WRITTEN FOR SIMULATOR TRAINING ONLY Tech. Spec. Nbrs: 3.7.4.1 Tags Placed By:

Position Verified By:

Date:

Time:

Clearance in Effect C.C.G./S.S./A.S.S.:

Date:

Time:

Clearance Released By:

Tags Removed By:

Position Verified By:

Date:

Time:

Date:

Equipment Restored to Desired Status (approved Clearance Closed By:

Time:

by S.S. / A.S.S.

below)

Date:

Time:

* * * * * * * * * * * * * * * * *

END OF COVER SHEET * * * * * * * * * * * * * * * * *

Date:

Time:

NUCLEAR CLEARANCE PERMIT SYSTEM CLEARANCE PERMIT ACCEPT/RELEASE ACTIVITIES COVERED BY THIS CLEARANCE PERMIT Print Date: 11/20/02 Clearance No: 2011795 Acceptor Special Instructions:

Unit:

2 Status: WRTTEN NONE Support Clearance JOA/ Pri 10 AR/Procedure No Acceptor Final STPCL Release By:

Date:

Time:

END OFACCEPTORS LIST ******************

Page:

1

NUCLEAR CLEARANCE PERMIT SYSTEM EQUIPMENT POSITION PLACEMENT LIST Print Date: 11/20/02 Page:

2

Clearance No: 2011795 Rev: 00 Equipment Cleared: 2-PP-7E EAST ESSENTIAL SERVICE WATER PUMP Tag [Tag C]-omponent Number Component

[Placeen -

e Place-- Verif No.

Typ

_Cot onent Type Description Position

]:B B

S----..

Written By:

OPERATOR, I.M.

Date:

11/20/02 Time:

13:08 Verified By:

Date:

Time:

END OF EQUIPMENT POSITION PLACEMENT SHEET

NUCLEAR CLEARANCE PERMIT SYSTEM EQUIPMENT POSITION PLACEMENT LIST Print Date: 11/20/02 Clearance No: 2011795 Rev: 00 Equipment Cleared: 2-PP-7E Page:

1 EAST ESSENTIAL SERVICE WATER PUMP Placement Special Instructions:

NONE Ta agIComponent Number Component

[I~l mn

[Se No.

[Tyjp Component Type

z:s:-22:..

2-Z.Z z ---- ?- _

y

"-- 2--

Z Z 2-T21D1O CIRCUIT BREAKER - AIR COOLED(METAL FRAME) 2-101-WMO-703 SWITCH CONTROL 2-201-TD10 SWITCH CONTROL 2-201-WMO-703 SWITCH CONTROL 2-T21DlO-FUSES ONE FUSE BLOCK 2-101-TD10 SWITCH - CONTROL Description EAST ESSENTIAL SERVICE WATER PUMP 2-PP-7E EAST ESW PUMP DISCHARGE 2-WMO-703 EAST ESW PUMP 2-PP-7E EAST ESW PUMP DISCHARGE 2-WMO-703 EAST ESSENTIAL SERVICE WATER PUMP 2-PP-7E BREAKER 2-T21D1O FUSES

{LOC IN REAR COR. OF BKR CTRL CUBE}

EAST ESW PUMP 2-PP-7E Position DISC CLOSE 2

LOCKOUT [

21 CLOSE

[

2 PULLED 3

LOCKOUT 4

Place Verif

-By... By...

1 1-------.

I -----------

6 N

-2 R

3 R

1 R

41 - -R- -

- --N --

*

RED COMPONENT:

2-1 01 -TD 10 TYPE: SWITCH - CONTROL EAST ESW PUMP 2-PP-7E POS.:

LOCKOUT TAG NO.:

I PERMIT #: 2011795

RED

*D COMPONENT: 2-101-WMO-703 TYPE: SWITCH - CONTROL EAST ESW PUMP DISCHARGE 2-WMO-703 TAG POS.:

CLOSE MDRDAI-,

o)( NO.:

2 11795

*

RED COMPONENT: 2-201 -WMO-703 TYPE:

SWITCH - CONTROL EAST ESW PUMP DISCHARGE 2-WMO-703 TAG I POS.: CLOSE PERMIT#: 20 NO.:

4 11795 mp I

d I L-ItlVlll fi';

Z.U

F--7N-?A9' TITLE Reviewing Liquid Release (Alternate Path)

[PROGRAM NRC License Exam SDEVEL OPING INSTRUCTOR:

Name:

Signature:

OPERATIONSj REVIEW:

Name:

Signature:

REVISION 0

TIME 15 Minutes S. Pettinger 9/7/02 jT. Werk Page 1 of 3

COURSE NUMBER N02LA9 REVISION: 0 AND TTLE:

Review Liquid Release (Faulted)

References I

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 Evaluation Setting Classroom / Simulator JFHandouts 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)

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

COURSE NUMBER N02-A9REION0 AND TTLE:

Review Liquid Release (Faulted)

Task Objectives/Standards 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 N02-A9REION0 AND TITLE:

Review Liquid Release (Faulted)

Reference 12-OHP-4021-006-004 I

Rev. 25 Page 20 of 58 Transferring Distillate From Monitor Tanks Monitor Tank Release To The Circ Water Pages:

I System F

14-28 MONITOR TANK NO.

RELEASE NO.

4.5 Align Monitor Tank to be released:

4.5.1 Complete applicable release lineup sheet (4):

D.Lineup Sheet 5, Monitor Tank No. 1 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 D 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 4.5.4 Document release flowpath in Section 3.0 of Data Sheet 1.

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.

SM/WCC SRO Time:

Date: __

4.6 Request RP Tech perform the following:

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 C°:

1P Tech OPS RP Tech CT - Identifies that the discharge alignment was NOT dependeaU

,-verified by two (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 tbw 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)

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

Cue: Reports task completed.

JPM IS COMPLETE.

Page 1 of I

Task Briefing Given the following conditions:

You are the WCC/SRO Both units are at 100% power All Circulating Water Pumps are running in both units Both units Circulating Water Systems are in their normal alignment E All condenser water box halves are in service 0 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 I of 1

Reference 12-OHP-4021-006-004 Rev. 25 Page 14 of 58 Transferring Distillate From Monitor Tanks Monitor Tank Release To The Circ Water Pages:

System-14-28 MONITOR TANK NO.

RELEASE NO. L-OZ-15 1

PURPOSE AND SCOPE 1.1 To release a Monitor Tank to the Circulation Water System.

2 PREREQUISITES 2.1 Circ Water System is in service.

2.2 Operability checks of RRS-1001 and RFS-1010:

A SOURCE CHECK has been performed to verify RRS-1001 is OPERABLE. (N/A if not used)

Verify RRS-1001 and RFS-1010 are OPERABLE. (N/A if not used)

-OR The provision of 12-PMP-6010-OSD-001, Attachment 3.2, will be satisfied prior to release. (N/A if not used) 3 PRECAUTIONS AND LIMITATIONS 3.1 Monitor Tank volume increase after Data Sheet 1, Monitor Tank R~lease Permit, has been submitted for sampling voids the release. Release Permit must be resubmitted.

3.2 IF RRS-1001 or RFS-1010 becomes inoperable during release, THEN release must be terminated until provisions of 12-PMP-6010-OSD-001,.2 are met.

3.3 Monitor Tank release must be terminated any time an alarm is received on RRS-1001 after release has been established (flow stabilized). This does NOT apply if RRS-1000 is out-of-service for maintenance and release is being performed under provisions of 12-PMP-6010-OSD-001, Attachment 3.2.

3.4 SOURCE CHECKS on respective RMS Channels should not be performed during a release.

WA4 14/A_

NA /A "I

0i

_%_U INIT VER

MONITOR TANK NO.

3 RELEASE NO. L-oZ-75 DETAILS Chemical Analysis:

4.1.1 Complete Section 1.0 of Data Sheet 1, Monitor Tank Chemistry Analysis Sample Request.

4.1.2 Verify Section 2.0 of Data Sheet 1 - COMPLETE.

4.1.3 Record Monitor Tank number and release number on each page of this attachment. [Ref: 7.2.2a]

4.2 Approval

Obtain approval from Shift Manager (SM), WCC SRO, or Unit Supervisor to prepare Monitor Tank No.

for release, per this attachment.

SM/WCC SRO/Unit Supervisor 4.3 Determine dilution flow rate:

4.3.1 IF release is through a unit at power, THEN perform the following:

a.

Record unit through which release will be performed on Data Sheet 1.

b.

Obtain power level of unit to be used for release using one of the following methods (N/A method not used):

1. Thermal power from PPC address (-4):

El Ul 118 - use average of the ten readings El U0601D - 10 minute averages SU 0601B - verify pow er has been steady for previous hour

2.

Perform 01/02-OHP-4030-114/214-029, Reactor Thermal Power.

w1A

-A Reference 12-OHP-4021-006-004 Rev. 25 Page 15 of 58 Transferring Distillate From Monitor Tanks Monitor Tank Release. To The Circ Water Pages: 1 System 14 -28 4

4.1 INIT VER

(?P

(,7'

Reference 12-OHP-4021-006-004 Rev. 25 Page 16 of 58 Transferring Distillate From Monitor Tanks Monitor Tank Release To The Circ Water Pages:

System-14-28 MONITOR TANK NO.

3 RELEASE NO. L-OZ-75 NOTE:

Local temperatures may be taken and used in place of SG-21 recorder points that are unavailable, provided the instrument number, calibration due date, and recorder points that are substituted are logged in the remarks section.

c. Determine Outlet Circ Water average temperature using one of the following methods (N/A method not used): 4 1

IF ALL Condenser Halves are in service, THEN record Outlet Circ Water average temperature from recorder SG-21, point 2:

Point 2 "T7A.*

0F

2.

IF any Condenser Half is out of service, THEN perform the following:

a) Record in-service Condenser Halves Outlet Circ Water temperature from SG-21:

"* Point 7 (U-2, pt.8), WTR-113 WA F

"* Point 8 (U-2, pt.9), WTR-117 OF

"* Point 9 (U-2, pt.10), WTR-213 OF

"* Point 10 (U-2, pt. 11), WTR-217 OF

"* Point 11 (U-2, pt.12), WTR-313 OF

"* Point 12 (U-2, pt.13), WTR-317 OF Total of all points taken:

OF I/*,

14/A b) Calculate condenser Outlet Circ Water average temperatu e:

Total from step 4.3.1c.2.a)

OF 0

Divided by number of inservice condenser halves OF Average Outlet Temperature F

_F

Reference 12-OHP-4021-006-004 Rev. 25 Page 17 of 58 Transferring Distillate From Monitor Tanks Atta nt 3 Monitor Tank Release To The Circ Water Pages:

System-14 -28 MONITOR TANK NO.

3 RELEASE NO. L--OZ-75

d.

Determine Inlet Circ Water average temperature using one of the following (N/A method not used):

1. IF Circ Water is recirculating directly to Forebay (through WMO-17 or WMO-27), THEN record St.

Joseph Treatment Plant Lake Temperature as average inlet Circ Water temperature:

St. Joseph Plant Lake Temperature 01/A OF

2.

IF Circ Water NOT recirculating directly to Forebay, THEN record average inlet Circ Water temperature from recorder SG-21, point 1:

Point 1 fol

e.

Calculate Circ Water differential temperature as follows:

Average outlet temperature Subtract average inlet temperature Differential Temperature "17.qOF (eJ.OF Ito.4°F

f.

Determine total Circ Water flow rate (dilution flow) using Tech Data Book Figure 1/2-11.16 as follows:

1. Note thermal power on nomograph Line No. 1.

2.

Note Circ Water AT on nomograph Line No. 2.

3. IF on scale on nomograph, THEN determine total Circ Water flow rate (dilution flow) by connecting points previously noted on nomograph with a straight line AND extend to line No. 3.

Record dilution flow rate 935, 000 gpm

-bV-

9 It't-4,02.

O/A 1,i/A r,4,-

Reference 12-O-1P-4021-006-004 Rev. 25 Page 18 of 58 Transferring Distillate From Monitor Tanks Monitor Tank Release To The Circ Water Pages:

System-14-28 MONITOR TANK NO.

3 RELEASE NO. L-D0-75

4.

IF off-scale on nomograph, THEN calculate Circ Water flow (dilution flow) as follows:

%RTP*32.5) - (

Mwe Gross)

0.90 AT°F

= Total dilution flow IJ/A gpm

5. Record total number of Circ Water Pumps operating in release path in Section 3.0 of Data Sheet 1.

6.

Record dilution flow rate in Section 3.0 of Data Sheet 1.

7.

Verify actual dilution flow is greater than or equal to minimum dilution flow rate recorded in Section 2.0 of Data Sheet 1.

4.3.2 IF release is through a shutdown unit, THEN perform the following:

a.

Record Forebay level indicated on 1-XLR-802 (2-XLR-803),

Upstream Forebay:

,J/A Feet

b.

Record pressure indicated on 1-WPI-11(2-WPI-21), CW Pumps Disch Press:

I/A psig

c. Determine flow through a Circ Water Pump using Tech Data Book Figure 12-11.17:

Circ Water Pump flow rate g14 gpm RTP Rated Thermal Power AT = Circ Water diff. temp MWe = Megawatt Electric MWt = Megawatt Thermal (RTP) 6817 BTU

hr* Ibm * 'F

ft3

gallons MWt - MWe MW

hr

min *BTU *lbm

ft3 AT0F 6817

(

ý/A t4ia V--W6 gA I

MONITOR TANK NO.

RELEASE NO. L-- OZ-75

d.

Calculate Total Circ Water Flow:

"* Pump flow rate

.1,J gpm

"* Multiply by number of CW Pumps gpmn Total Circ Water Flow

-- gpm t! APi

e.

Record total number of Circ Water Pumps operating in release path in Section 3.0 of Data Sheet 1.

f.

Record dilution flow rate in Section 3.0 of Data Sheet 1.

g.

Verify actual dilution flow is greater than or equal to minimum dilution flow rate recorded in Section 2.0 of Data Sheet 1.

4.4 IF RRS-1000 is out of service, THEN perform the following:

4.4.1 Close the following valves to isolate RFS-1010 (prevents inadvertent tripping of Monitor Tank Pumps):

0 12-WD-470, Radioactive Liquid Waste Disposal Effluent Header Radiation Sample Assembly Inlet Shutoff Valve 12-WD-473, Radioactive Liquid Waste Disposal Effluent Header Radiation Sample Assembly Outlet Shutoff Valve 4.4.2 N/A the following steps:

4.6

° 4.11.2

° 4.14

° 4.18 4.9 4.11.5 4.16.3 4.20 4.10.2 4.11.6 4.16.5 4.10.3

° 4.13

° 4.17 Reference 12-OHP-4021-006-004 Rev. 25 Page 19 of 58 Transferring Distillate From Monitor Tanks Monitor Tank Release To The Circ Water Pages:

System-14--28

MONITOR TANK NO.

3 4.5 Align Monitor Tank to be released:

RELEASE NO. L- "75 4.5.1 Complete applicable release lineup sheet (J):

El Lineup Sheet 5, Monitor Tank No. 1 Release Valve Lineup El Lineup Sheet 6, Monitor Tank No. 2 Release Valve Lineup V Lineup Sheet 7, Monitor Tank No". 3 Release Valve Lineup El 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 required 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:

Date:

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

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.31

-&-h-_

t/A WLA~

RP Tech

,PS RP ech OPS RP Tech Reference 12-OHP-4021-006-004 Rev. 25 Page 20 of 5 Transferring Distillate From Monitor Tanks Monitor Tank Release To The Circ Water Pages:

System 14 - 28

4.7 4.8 4.9 Reference 12-OHP-4021-006-004 Rev. 25 Page 21 of 58 Transferring Distillate From Monitor Tanks Monitor Tank Release To The Circ Water Pages:

SSystem 14-28 MONITOR TANK NO.

3 RELEASE NO. L-12-75 Align Monitor Tank discharge flowpath (N/A step not used):

4.7.1 For Monitor Tank No. 1 or 2, open the following:

"* 12-CS-285, CVCS Monitor Tanks Transfer Pumps Discharge To Circ Water Discharge Tunnel Shutoff Valve

"* 12-CS-488, CVCS Monitor Tanks North Transfer Pump Discharge To Circ Water Discharge Tunnel Shutoff Valve 4.7.2 For Monitor Tank No. 3 or 4, open 12-WD-320, CVCS Monitor Tanks South Xfer Pump 12-PP-47S Disch To CW Discharge Tunnel Shutoff Valve.

Flush CVCS Monitor Tank Transfer Pump discharge line:

4.8.1 Open 12-WD-164, Rad Liquid Waste Effluent Header To Dirty Waste Hold Up Tank Shutoff Valve.

4.8.2 AFTER two minutes of flushing, THEN close 12-WD-164.

Verify operation of RRS-1000 as follows:

4.9.1 Perform a SOURCE CHECK to verify RRS-1001 is c1Z OPERABLE. (N/A if not used) 4.9.2 Perform CHANNEL CHECK on release instrumentation as follows: [Ref. 7.2. li.3]

a. Verify RRS-1001 indications are approximately the same:

"* Control Room ti/A CPM

"* DAM CPM

"* WDS V _

CPM

b.

Have Radiation Protection place RFS-1010 and RFA-101 I in service at the RMS-CT.

c. Verify RFS-1010 indicates approximately the same %

sample flow" at monitor and WDS panel (12-RFI-1000).

d. Verify RFI-101 1 indicates approximately the same "%

sample flow" at monitor and WDS panel (12-RFI-1000).

P,*1 ic2

Reference 12-OHP-4021-006-004 Rev. 25 Page 22 of 58 Transferring Distillate From Monitor Tanks Monitor Tank Release To The Circ Water Pages:

System-14-28 MONITOR TANK NO.

3 RELEASE NO. L-O2--75 4.10 Align release indications:

4.10.1 Unseal AND open 12-WD-166, Rad Liquid Waste Disposal Effluent Control Valve 12-RRV-285 Inlet Valve.

NOTE:

Actions of Steps 4.10.2, 4.10.3, and 4.13 clear low flow alarm and bypass low flow trip function of RFS-1010 to enable start of release [Ref: 7.2.1g]

4.10.2 Press ALM ACK button on front of RRS-1000 DAM.

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

4.10.4 Record initial tank volume:

4.10.5 Place Monitor Tank Pump Mode Selector Switch to - RELEASE.

4.10.6 Mark flow recorder 12-MR-57 with time and date of release start.

4.10.7 Open 12-RRV-285, Liquid Waste Disposal Effl Disch Hdr Shutoff.

5, 1.-t oz 4.4.2

'PA

,-/A CAUTION:

A good understanding of the following step is important as this step must be completed expeditiously to ensure that release is NOT being made with a failed radiation monitor.

4.11 Expeditiously perform the following to initiate release:

4.11.1 Open discharge valve for applicable Unit (N/A valve not used):

1-RRV-287, Rad Liquid Waste Disposal Effluent Header To Unit 1 Circ Water Disch Tunnel Shutoff Valve 2-RRV-286, Rad Liquid Waste Disposal Effluent Header To Unit 2 Circ Water Disch Tunnel Shutoff Valve SEE

Reference 12-OHP-4021-006-004 Rev. 25 Page 23 of 53 Transferring Distillate From Monitor Tanks Monitor Tank Release To The Circ Water Pages:

System-14 - 28 MONITOR TANK NO.

3 RELEASE NO. L-O2-7*

4.11.2 Verify the following indicate a flow rate (North wall outside BAST Room):

"* RFS-1010

"* RFI-1011 9/A WIA 4.11.3 IF release flow is less than desired, THEN slowly throttle closed the following applicable valve until desired flow rate is obtained:

0 12-CS-275N, CVCS Monitor Tanks North Transfer Pump Recirc To Monitor Tank 1 & 2 Shutoff Valve a

12-CS-275S, CVCS Monitor Tanks South Transfer Pump Recirc To Monitor Tank 3 & 4 Shutoff Valve 4.11.4 IF release flow is greater than desired, THEN slowly throttle closed 12-WD-166 until desired flow rate is obtained.

CAUTION:

Maximum design flow rate through sample line is 15.6 gpm. Closing 12-RRV-284 will increase flow through sample line. Rapidly increasing sample flow rate beyond maximum indicated "% sample flow" reading will damage sample flow line rotometer [REF: 7.2. 1g]

NOTE:

RFS-1010 sample flow is raised to at least 40% to re-arm low flow trip function bypassed by performance of Steps 4.7.2, 4.8.1, and 4.11.1.

Sample flow must be between 20% to 90% or release will trip off on low/high sample flow (monitor will indicate external failure on RRS-1001). [Ref. 2]

RFS-1010 abnormal readings will alarm via RRS-1001.

4.11.5 Slowly throttle 12-RRV-284 to adjust sample flow as necessary to match "% sample flow" indicated on RFS-1010, with "% release flow" indicated on RFI-10 11.

0/A

_/__

Reference 12-OHP-4021-006-004 I

Rev. 25 Page 24 of 58 Transferring Distillate From Monitor Tanks Monitor Tank Release To The Circ Water Pages:

System 14-28 MONITOR TANK NO.

5 RELEASE NO. L-02-75 4.11.6 Perform CHANNEL CHECK on release instrumentation as follows: [Ref. 7.2.1i.3]

a.

Verify RRS-1001 indications are approximately the same:

0 Control Room DAM WDS MIA CPM CPM CPM

b.

Verify RFS-1010 indicates approximately the same " %

sample flow" at monitor and WDS panel (12-RFI-1000).

c.

Verify RFI-1011 indicates approximately the same "%

sample flow" at monitor and WDS panel (12-RFI-1000).

4.11.7 Verify 12-RFI-285 & 12-MR-57 read within 15 gpm of each other.

4.11.8 IF both 12-RFI-285 & 12-MR-57 are inoperable, THEN initiate actions per PMP-4030-EIS-001, Event-Initiated Surveillance Testing, Event No. 25.

4.12 Record the following data:

Release flow rate:

GPM Check instrument

[I 12-MR-57 used:.

u : 12-RFI-285 E Estimated (OHP-4030-STP-021)

Release Start: Time:

Date:

/ /

4.12.1 Record release start information in Section 3.0 of Data Sheet 1.

/A Srg' I

AA-i

Reference 12-OHP-4021-006-004 Rev. 25 T

Page 25 of 58 Transferring Distillate From Monitor Tanks Monitor Tank Release To The Circ Water Pages:

System 14 - 28 MONITOR TANK NO.

"3 RELEASE NO. L 7S 4.13 IF release monitor trips off due to external failure, THEN perform the 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.

/A NOTE:

In order to open 12-RRV-285 after high alarm on RRS-1001, monitor m'lst be flushed to reduce radioactivity below alarm point.

4.14 IF 12-RRV-285 closes because of high radiation detected by RRS-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 Have Radiation Protection remove RFS-1010 and RFA-10 11 from service at the RMS-CT.

W/A I

1c2

Reference 12-OHP-4021-006-004 Rev. 25 Page 26 of 58 Transferring Distillate From Monitor Tanks Monitor Tank Release To The Circ Water Pages:

System 14 - 28 MONITOR TANK NO.

3 RELEASE NO. L-D'Z-75 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) 0 1-RRV-287 V

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

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

RRS-1001 RFS-1010 (N/A if already performed)

RFA-10 11 (N/A if already performed)

b.

Have Radiation Protection remove RFS-1010 and RFA-1011 from service at the 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.

NA 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:

/

of release completion Final Tank Volume:

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

1c2

.4.4.-,

MONITOR TANK NO.

3 RELEASE NO. L.-02-76 4.17 Flush RRS-1000:

4.17.1 Perform applicable attachment (q):

m] Attachment 5, RRS-1000 Flush for Monitor Tank No. 1 or 2, RRS-1000 Flush for Monitor Tank No. 3 or 4 4.17.2 Verify adequate flush of RRS-1001:

6 Reading less than 4,000 CPM a

IF RRS-1001 can NOT be flushed to less than 4,000 CPM, THEN notify RP AND note in remarks section 4.18 Request RP Tech return RRS-1001 high alarm to desired value.

4.19 Complete Section 3.0 of Data Sheet 1.

4.20 Attach printed release averages for available RRS-1000 Channels to Data Sheet 1.

4.21 IF release was stopped due to high radiation alarm on RRS-1001 AND release is still desired, THEN restart release process with new procedure AND submit another Data Sheet 1 to Chemistry.

4.22 IF procedure was performed with RRS-1000 not in service (step 4.4),

THEN close 12-WD-320, CVCS Monitor Tanks South Xfer Pump 12-PP-47S Discharge to CW Discharge Tunnel Shutoff Valve.

5 CORRECTIVE MEASURES 5.1 None RP Tech OPS Reference 12-OHP-4021-006-004 Rev. 25 Page 27 of 58 Transferring Distillate From Monitor Tanks Monitor Tank Release To The Circ Water Pages:

System.

14 - 28 A > it 7--

MONITOR TANK NO.

3 RELEASE NO. L-C12-75 6

FINAL CONDITIONS 6.1 None Comments:

Verified Complete By:

Reviewed By:

Supervisor/Manager Signature Date: _

/

Date:

/

Reference 12-OHP-4021-006-004 Rev. 25 Page 28 of 58 Transferring Distillate From Monitor Tanks Monitor Tank Release To The Circ Water Pages:

System-14 - 28

Reference 12-OHP-4021-006-004 Rev. 25 Page 37 of 58 Transferring Distillate From Monitor Tanks Data Sheet 1 Monitor Tank Release Permit Pages:

37 - 39 SECTION 1.0 - OPERATIONS Monitor Tank No.

S Level 09 Volume 1 1i05. 4 5 Gal (determined by using Figure 1)

Placedonrecirc: Time: 20-Lto

-Date: 11 /20/02 A Monitor Tank should be recirculated 2 volumes prior to sampling. [7.2. lj]

Recirc Times for Two Volumes Tank Level Recirc Time*

60%-70%

3 hr 70%-80%

3 hr 30 min 90%-100%

4 hr 30 min Ready for sample:

Time: 001 to Date:

I_1/2 I

Da/Z Initiated by:

_Date:

it /20/o2 Time: Zo'4 SRO FORWARD TO CHEMISTY

Recirc time is based on a Monitor Tank Pump discharge pressure of 90 psig t Rev

SECTION 2.0 - CHEMISTY Monitor Tank No.

3 has been sampled and may be released per the following criteria Release Number:

L-oa-TS Sample Number:

W41l36co35

"° Maximum release flow rate:

ISO GPM

"* Minimum dilution flow rate:

a30 1 000 GPM

"* RRS-1001 High Alarm Setpoint: _

CPM A listing of isotope concentrations have been attached.

4k Initials All significant gamma peaks have been identified, quantified, and are in compliance with PMP-6010-OSD-001, Attachment 3.6. This information has been verified accurate and can be used to prepare the ODCM required annual effluent report.

Release authorization is void if greater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months has elapsed from time of approval.

Approved by:

l A

Date:

I I/Ii1/O Time:

O&oVI Chemistry Release NOT approved for the following reason:

/A, NOT Approved by:

C str Date:

Time: ______

Chemistry t

If release is NOT approved by Che ry, Plant Manager approval is required for release.

Approved by:

14/A Date:

/

Time:

t4/1, Plant Manager FORWARD TO UNIT 1 CONTROL ROOM Reference 12-OHP-4021-006-004 Rev. 25 Page 38 of 58 Transferring Distillate From Monitor Tanks Data Sheet I Monitor Tank Release Permit Pages:

I 37 - 39

/

Reference 12-OHP-4021-006-004 Rev. 25 Page 39 of 58 Transferring Distillate From Monitor Tanks Data Sheet 1I Monitor Tank Release Permit Pages:

37 - 39 SECTION 3.0 CONTROL ROOM

"* Release through Unit Record dilution flow rate:

t 000 GPM

" Record total number of Circ Water Pumps operating in release flow path:

'4-pumps

" Document release path (circle one):

"* Unit 1 or t2 discharge tunnel

"* GnHr)or 13 0 Record release flow rate:

GPM Record release started:

Time:

D_

Record release stopped:

Time:

D_

Determine total dilution:

min X (duration of release)

(

ate:

/

ate:

I

/

dilution flowrate)

Initial tank volume:

Final tank volume:

Total volume released:

3PM Release Complete:

Date:

/

Reviewed By:

(Supervisor/Manager Signature)

Date:

/_/

Gal Gal Gal Gal

Number 12-CS-268-3 12-CS-268-4 12-CS-481-3 12-WD-317 12-CS-267-3 12-WD-318 Description Aux. Bldg. 609' Hallway CVCS Monitor Tank 12-TK-14-3 Outlet Valve CVCS Monitor Tank 12-TK-14-4 Outlet Valve CVCS Monitor Tank 12-TK-14-3 Vacuum Cleaning Connection Shutoff Valve CVCS Monitor Tanks South Transfer Pump 12-PP-47S Disch To Monitor Tank 3 Shutoff Valve CVCS Monitor Tank 12-TK-14-3 Inlet Valve CVCS Monitor Tanks South Transfer Pump 12-PP-47S Disch To Monitor Tank 4 Shutoff Valve Aux. Bldg. 587' Hallway 12-CS-270S CVCS Monitor Tanks South Transfer Pump 12-PP-47S Suction Valve 12-CS-274S CVCS Monitor Tanks South Transfer Pump 12-PP-47S Discharge Valve 12-CS-275S CVCS Monitor Tanks South Transfer Pump Recirc To Monitor Tanks 3 & 4 Shutoff Valve 12-CS-508 CVCS Monitor Tanks South Transfer Pump 12-PP-47S Discharge Crosstie Valve 12-CS-511 CVCS Monitor Tanks Transfer Pumps Suction Crosstie Valve CVCS Monitor Tanks 3 & 4 Outlet To South Transfer Pump 12-PP-47S Shutoff Valve CVCS Monitor Tanks South Xfer Pump 12-PP-47S Disch To CW Discharge Tunnel Shutoff Valve 44L Verified Complete:

Reviewed By:

(Supervisor/Manager Signature) j CS CLOSED OPEN J

THROTTLED CLOSED CLOSED Pý OPEN CLOSED J

jO Date:

/00/ 0,a Date: i,/0 ZO/OZ

q

Continuous 12-OHP-4021-006-004 Rev. 25 Page 45 of 58 Transferring Distillate From Monitor Tanks Lineup Sheet 3 Monitor Tank No. 3 Recirc Valve Lineup Pages:

45 -45 Required Position Performed INITIALS IV INITIALS OPEN CLOSED CLOSED OPEN CLOSED CLOSED 12-WD-319 12-WD-320 I

Continuous 12-OHP-4021-006-004 Rev. 25 Page 53 of 58 Transferring Distillate From Monitor Tanks Lineup Sheet 7 Monitor Tank No. 3 Release Valve Lineup Pages:

53 - 55 RELEASE NUMBER L- 02-'75 Description Required Position Performed INITIALS IV INITIALS FOR RELEASE THROUGH UNIT NO. 1 Screenhouse 1-WMO-17 Circ Water Forebay Emergency Intake Shutoff Valve CLOSED FOR RELEASE THROUGH UNIT NO. 2 Screenhouse 2-WMO-27 Circ Water Forebay Emergency Intake Shutoff Valve 1-CW-123 Waste Evap Condens Water Outlet Shutoff 1-CW-124 Waste Evap Condens; Circ Water Outlet Shi CLOSED Unit 1 Turb Bldg 579' Condenser Pit ate To LPT 'A' Condenser Circ OPEN Valve

_CLOSED1,2.

ate To LPT 'B' Condenser SW OPEN Utoff Valve Unit 2 Turb Bldg 579' Condenser Pit 2-CW-123 Waste Evap Condensate To LPT 'A' Condenser Circ Water Outlet Shutoff Valve

/CLOSED"3 2-CW-124 Waste Evap Condensate To LPT 'B' Condenser NW Circ Water Outlet Shutoff Valve Aux. Bldg 609' Hallway 12-CS-267-3 12-CS-268-3 12-CS-268-4 12-WD-3 17 12-WD-318 12-CS-481-3 1

2 3

CVCS Monitor Tank 12-TK-14-3 Inlet Valve CVCS Monitor Tank 12-TK-14-3 Outlet Valve CVCS Monitor Tank 12-TK-14-4 Outlet Valve CVCS Monitor Tanks South Transfer Pump 12-PP-47S Disch To Monitor Tank 3 Shutoff Valve CVCS Monitor Tanks South Transfer Pump 12-PP-47S Disch To Monitor Tank 4 Shutoff Valve CVCS Monitor 12-TK-14-3 Vacuum Cleaning Connection Shutoff Valve Circle correct position.

Closed if release is through Unit 2.

Closed if release is through Unit 1.

. st Rev Checked

o. of CS:

Number 122 CLOSED OPEN CLOSED OPEN CLOSED CLOSED

( /

(/2

/2 9

QQý (9

uous 12-OHP-4021-006-004 Rev._25 Page 54 of 53 Transferring Distillate From Monitor Tanks Lineup Sheet 7 Monitor Tank No. 3 Release Valve Lineup Pages:

53) - 55 RELEASE NUMBER L-OZ--75 Required Performed Position INITIALS INE Number Description Aux. Bldg. 587' Hallway 12-CS-508 CVCS Monitor Tanks South Transfer Pump 12-PP-47S Discharge Crosstie Valve 12-CS-270S CVCS Monitor Tanks South Transfer Pump 12-PP-47S Suction Valve 12-CS-274S CVCS Monitor Tanks South Transfer Pump 12-PP-47S Discharge Valve 12-CS-275S CVCS Monitor Tanks South Transfer Pump Recirc To Monitor Tank 3 & 4 Shutoff Valve 12-CS-511 CVCS Monitor Tanks Transfer Pumps Suction Crosstie Valve 12-WD-320 CVCS Monitor Tanks South Xfer Pump 12-PP-47 Disch To CW Discharge Tunnel Shutoff Valve 12-WD-319 CVCS Monitor Tanks 3 & 4 Outlet To South Transfer Pump 12-PP-47S Shutoff Valve 12-CS-285 CVCS Monitor Tanks North Xfer Pumps Disch To Circ Water Disch Tunnel Shutoff Valve 12-DW-308 Demin Water To CVCS Monitor Tank South Transfer Pump 12-PP-47S Shutoff Valve 12-CS-571 CVCS Monitor Tanks Transfer Pumps Disch To Circ Water Discharge Tunnel Drain Valve 12-WD-470 Rad Liquid Waste Disposal Effluent Hdr Rad Sample Assembly Inlet Shutoff Valve 12-WD-471 Rad Liquid Waste Disposal Effluent Hdr Radiation Sample Assembly Drain Valve 12-WD-473 Rad Liquid Waste Disposal Effluent Hdr Rad Sample Assembly Outlet Shutoff Valve 12-WD-472 Rad Lqd Waste Disposal Effluent Hdr Rad Sample Assembly Outlet Test Conn Shutoff Vlv 4

May be N/A if RRS-1000 is out of service.

CLOSED CLOSED OPEN THROTTLED CLOSED CLOSED OPEN CLOSED CLOSED CLOSED OPEN4 CLOSED 4

OPEN 4

CLOSED 4

K/A 14/A WA IV

[IALS f 4/

N/A Con tin' t..ontlnt

Continuous 12-OHP-4021-006-004 Rev. 25 Page 55 of 58 Transferring Distillate From Monitor Tanks T Pages:

Lineup Sheet 7 Monitor Tank No. 3 Release Valve Lineup 53 - 55 RELEASE NUMBER L-OZ-*5 Description Required Position Performed INITIALS IV INITIALS WECT Area Rad Waste Evap Cndnst Tanks Transfer Pumps Discharge Header Shutoff Valve CLOSED BAST Area 12-WD-304 12-WD-163 12-WD-164 12-WD-166 12-RRV-284 Rad Laundry And Radiochemical Drain Tanks Xfer Pumps To Circ Water Disch Tunnel Shutoff Valve Radioactive Liquid Waste Effluent Header Flush Connection Shutoff Valve Rad Liquid Waste Effluent Hdr To Dirty Rad Waste Holdup Tank TK-3-1 Shutoff Valve Rad Liquid Waste Disposal Effluent Hdr Control Valve RRV-285 Inlet Shutoff Valve Liquid Release Control Valve 12-RRV-284 Manual Adjust Verified Complete:

Reviewed By:

(Supervisor/Manager Signature)

Date: / I IoI, / 6ol Date:

/

Number 12-WD-162 CLOSED CLOSED CLOSED SEALED CLOSED OPEN (9

LIQUID RELEASE WORKSHEET RELEASE#: L-02-75 SAMPLE#:

02413635 A

NUCLIDE CO-57 CO-58 CO-60 NB-95 AG-110M SB-124 B

CONCENTRATION (uCi/ml

+/- %error) 8.40E-08 1.40E-05 2.67E-06 4.20E-07 5.69E-07 3.59E-07

+1

+1-41.4 %

4.6 %

4.7 %

18.1 %

11.6 %

24.6 %

TOTAL GAS 0.OOE+00 C

EC (LIMIT) 6.OOE-05 2.00E-05 3.OOE-06 3.00E-05 6.OOE-06 7.001E-06 2.OOE-04 D

ECf (B / C) 1.40E-03 7.01E-01 8.89E-01 1.40E-02 9.48E-02 5.13E-02

0. 00E+00 E

EFFICIENCY 3.80E+07 4.5 8E+07 5.75E+07 3.28E+07 9.93E+07 5.93E+07 F

COUNT RATE (B x E) 3.19E+00 6.42E+02 1.53E+02 1.38E+01 5.65E+01 2.131E+01 Page 1 of 2 02/11/21

RELEASE4: L-02-75 SAMPLE#:

02413635 B

CONCENTRATION (uCi/ml +/- %error)

Tritium 1.29E-01

+/-

0.5 %

C EC (LIMIT) 1.00E-03 TOTAL RELEASE CONCENTRATION:

1.81E-05

[IF >l.OE-3, CONTACT RMC]

D ECf (B / C) 1.29E+02 E

EFFICIENCY 0.00E+00 FRACTIONAL EC:

1.31E+02 F

COUNT RATE (B x E) 0.OOE+00 EXPECTED COUNT RATE 8.90E+02 tA A

( tnq-?,A-n~o,4 0 ~-5

,..1I, 5n 11-21-OZ RMC DATE & TIME Maximum Release Flow Rate Determination:

RELEASE RATES [GPM]:

[MAX. 150 GPM]

GPM GPM GPM GPM FI: =

F2: =

F3: =

F4: =

[ [

[

528 1055 1583 2111

]i

]

Monitor Alarm Setpoint Calculation:

NOTE:

If the calculated RRS-1001 High Alarm Setpoint is <4000 cpm, record as 4000.

If >500,000 cpm, record as 500,000 cpm.

890 Expected Count Rate x

4000 RRS-1001 High x 0.9 Alarm Setpoint BORON CONCENTRATION:

GROSS BETA ACTIVITY:

1780 2.0 410 <<

+

RRS-1001 Background (Maximum 4000 cpm) 3600 RRS-1001 Alert Setpoint 208.0 PPM tA/A uCi/ml 40rWLk.

54) 41.71-OZ Comments:

PERFORMED APPROVED BY:

DATE/TIME:

41/z1/oz 0554 DATE/TIME:

II oI*o

]O Q(Q Page 2 of 2 A

NUCLIDE 02/11/21 230,000 460,000 690,000 920,000

J=N02A 1

TTLE

..Emergency Plan Classification with PAR

,-PROGRAM.-,NRC License Exam DEVELOPING INSTRUCTOR:

fOPERATIONS REVIEW:

Name:

Signature:

Name:

Signature:

REVISION 0

TIME 15 Minutes Dale Tidwell 917102 Page 1 of 3 Revision 0 9l/q/o2Z i*T. Werk

REFERENCES I

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

REFERENCE:

2.4.41 K/A 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 EVALUATION SETTING Classroom or office HAN DOUTS Task Briefing ATTACHMENTS None SIMULATOR SETUP None Page 2 of 3 Revision 0

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-101), 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.

TASK BRIEFING 1

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 3000 at 4 mph and NO offsite release is occurring.

Page 3 of 3 Revision 0

COURSE NUMBER N02-A1o AND TITLE:

Emergency Plan Classification with PAR IREVISION: ý0 H

I I

ic

Page 1 of 6 Revision 0 C

z

-Q z

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).

z

.2

.-r-C-nC

-4 1

I I

-I 14 Fl C'

-.4 C

..'.

z C

"4 C-i

1 C

14 f

1

C 1

1 C

a C

-'4 14 I

{

1

I 0 m C

.14

C) 6

'II z

.i tJI C C)

I.,

7-

I 4 4

7 I

-1 K

-J ri I..)

Iz 0

0 mz c

(D

>)

COURSE NUMBER..: -N02-AIO AND TITLE:

Emergency Plan Classification with PAR REVISION: 0 64S'ý 22 - 114 Ii.F

-tt

'ruc 3.r~c tVnhc.radati. IC..ci,.irt, mS,~C\\aVt 1"

ticlbi~rto I

'a'M-.

tc17 rrp rtvtci(Q bIS shouldl h+/- busa-z -ni a ra~lrtic ;prrzi~a "f1 CrC ii..,

lc-.ssrsu.i C ill p-rcjiailll

-Jt imli, 1

.larcotiti r.blriý 1,0.CLI5iv

.i~ttiit TERM1I NiAllr DAO~

CR1ITIt.IA DEiX ATION1' IZON'I NICUMARI(z AsI' I t','

la istl csttrlftt'lts a t.hEfi (e

0-s4

1.

1, ieriirtai ircit Page 3 of 6 Revision 0

COURSE NUMBER-.. N02-AlO AND TlTLL:

Emergency Plan Classification with PAR Rierittco Emcreno-~w Respontse REVISION: 01 b,

Dirtect a Conttrol Rnoom O~perator to make the tollowin.g aantiotncentvn for the appropriate ERa facilit'y(s) to, he 5acti; a&ted, uver thle PIA systeým.

I [incý the rtuemn broadcast twice.

-Attontion all personnel. Attention all persotnaei. The Unusual Event is, still in effect, howe' c report to anid autivate tile ()pemin St~n 4e'c/nelS oI Cennr/Fme~fmnrO~eano__TcjýiL.

All other plant perormotel beC prep~ared for further auntoniteentes."

e.On any tou~ch-twne telepho ne:

ial 1646

"* Watt for the tonle

Press /i, to iiccessý the Training Certter antd Buochanan Oftfice Buoildito 1PA

Repe~ai the1 alove announceenent twice

.. 2.7 IF a General Enaerazencv:

has ben elarcd, THE I irect the jcVcepls tptnen of a PrOWCtiec Action Recommnendation using tile follow~incz ste.ps:

a.

Priot to developia., a PAR considtt~

-whethec the fuilowing Could have an effect onl thle PAR:

Adverse wveather conditions.

A forcasitq of chýaninglg weather conditions.

Releabe characteristics (Puff vs. Continuous) k*

ljcuatinot tirnes per Atachminoot 3, of PNMPO261-EPP-3tt5. Prmctethe Actmown 1-. Ioe lodc itn des iations fr~ont the. PAR flow.chart. A'ttachmtentt

-s. 1'ýSttd0! tltiý itp n time protective-acnttole~tnnain 4-A General Emergency requires a protective action recommendation be made to the state.

Page 4 of 6 Revision 0 1' 2 0

~R'fP.V eI.~

P-2(i8O

-1"PP-100O Rev.O

___ Ptoe 6 of2('

t~ognyRespon'se Cý. btain the foleji ni data Wind dirzc~t or.

- AND (Otfs;[t &UL rpro~ieýC61n (ii avall1abkc) as Calculated o'.irn D'AP or acrual off'sjte dose rate c aý'ronlcrts.

c.U t 'igi Aruihtnent 1, deterinine ihe appropriate PAR~.

e.

Enter the_ Protective Action Rucminentation on Owe Nuclear Plantn Accident. Norificafion foiritt, obtained froin the.

Erncezrgcric R~ it anid hifti in the State of* Michigan 0! the rccortiirtend~ainsi iurmiediaely, f,

1Ioepeat Steps 3,2.-,.,, throug~h 3,.27.e every 15 mninutes or as rcujt;astcd until reivdb-h in i

ntcEmrgenfcy Response Careanizazion.

1Pcnib llr 11itmeat mnr." detions in accorklance with ipprc..prialc pl;nt IF the. Plant Process (Zonipoter t1PPC) is5 inoperable. TI-TEN:

DeSi!aile SORneime to COMPleTe D7ata Sheet 1, 'Pechnlical Inftormation Shtect. ever"Y 15 minrutes.

" Forward 11w. Completed copy to dthe TSC.

" C'n;tnue this acft viiy for the duration of the Zraergency or mvil 111c 1P1C is opecrafble.

3.2. 10 117 accuntiability re-sulis identfify-a miasgin person(s) AND the 1 SC and OSA ate-IN017 activ'atedi, *ritEN have Seýcurity attenupt te, locatc 0he ~nksin_

ic-on?

per, PIvP-*208tI4EPP-Md3

.\\s~td.Acectiltahilits'.

andJ Evacuation of Persinni.

Upo orif:,

!the oticoninne, SUC condcucl A turnove, as follows:

a.

()ht:in i -cp~y of Data Sheet 2. Emiere.-ncy Turorv.Ž Wind direction and speed is given in briefing. Wind is from 300o at 4 mph.

Per briefing, NO offsite release is occurring.

Next page.

Page 5 of 6 Revision 0 3,2.9

CT Protective Action Recommendation is to evacuate areas 1, 2, and Wind is from 300°. 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 4

Recommendation to evacuate areas 1, 2, and 3.

JPM IS COMPLETE Page 6 of 6 Revision 0

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

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

Assume the weather is fair with the wind from 3000 at 4 mph and NO offsite release is occurring.

N02-A10.doc Page 1 of 1 Revision 0

ML030700197

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4.2 Approval

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