Text

Initial Submittal of the Administrative Jpms for the Monticello Initial Examination - Oct. 2002
	ML030410042
Person / Time
Site:	Monticello
Issue date:	10/14/2002
From:	Engen M; Nuclear Management Co
To:	; Office of Nuclear Reactor Regulation
References
	50-263/02-301 50-263/02-301
	Download: ML030410042 (68)
	v • d • e

INITIAL SUBMITTAL OF THE ADMINISTRATIVE JPMS FOR THE MONTICELLO INITIAL EXAMINATION - OCT 2002

r MONTICELLO NUCLEAR GENERATING PLANT JPM-C.2-05.B.1-001 TITLE:

CORE THERMAL LIMITS MONITORING Revision 0 Page 1 of 10 SRO:

X SRO/RO:

SRO/RO/NLO:

NLO:

Plant

Reference:

C.2-05, Rev. 13 Task Standard:

Perform Core Thermal Limits monitoring and identify actions that need to be taken.

K/A

Reference:

Generic Task No.:

2.1.19 Rating RO/SRO:

3.0/3.0 2.1.33 3.4/4.0 Recent Events:

None Probabilistic Risk Assessment Human Error:

None Monticello Specific Task List

Reference:

SS200.136 METHOD OF TESTING TIME FOR COMPLETION Estimated Time to Complete:

20 min.

Simulator:

X Normal:

Maximum Time to Complete:

35 min Alternate X

In-Plant:

Path:

Time Critical:

Yes X

No Prepared By:

Date: 0e.

Reviewed By:

Date:

7//

Shift Supv/Shift Mgr Review By:

Date:

0-7 (a Q_

Approved By:

_W Date: 1,.L/o I

/

MONTICELLO NUCLEAR GENERATING PLANT JPM-C.2-05.B.1-001 TITLE:

CORE THERMAL LIMITS MONITORING Revision 0 Page 2 of 10

~$ JPIV SET-UP, 2

Simulator Setup:

Not Applicable Copy of Operations Daily Log - Part E 3D Monitor printout.

Place a red pencil on the Control Room Desk Have a copy of Form 3389 (EVENT NOTIFICATIONS) available.

Initial Conditions:

Reactor power has just been increased from 90% power to 98%, with the Recirc Flow Control system, per C.2-05 Load Following.

Initiating Cues:

You have been asked to perform the Core Thermal Limits Monitoring for MFLCPR, MAPRAT, and MFLPD, per Ops Man C.2-05, Section B.1, Parts A, B, and C, and determine any required actions if necessary. Record data on Forms 0207, 0208, and 0225, of Operations Daily Log 0000 - E. Report when the task is complete.

1,-

.1

MONTICELLO NUCLEAR GENERATING PLANT JPM-C.2-05.B.1-001 I

TITLE:

CORE THERMAL LIMITS MONITORING Revision 0 Page 3 of 10 PERFORMANCE INFORMATION Perform a n~ceObjective Standard STEP 1 Standard:

Locates procedure C.2-05, "Power Locates appropriate procedure.

Operation".

Cue: None Comments: Parts A, B, and C may be performed in any order.

STEP 2 (Procedure Part A, Step 1)

Standard: None IF process computer is not anticipated to be Cue: None available during a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period, THEN contact a Nuclear Engineer to arrange Comments: Process Computer is available.

determination of MCPR.

STEP 3 "C" (Procedure Part A, Step 2.a)

Standard:

When 3D Monitor computer is available, Cue: Provide candidate with a copy of 3D perform the following:

Monitor Edit

a. Demand Official 3D Monitor to calculate Comments: A 3D Monitor edit cannot be core nodal power distribution, demanded on the simulator.

AND use MCPR data for the fuel assemblies that are closest to the limiting CPR.

NOTE 4:

The most limiting MCPR is edited as MFLCPR on the Periodic Log NOTE 5:

MFLCPR is the Core Maximum ratio of power and flow dependent CPR limit to the bundle's actual CPR.

STEP 4 "C" (Procedure Part A, Step 2.b)

Standard:

b. Record the following data for the most Records data on Form 0225.

limiting fuel bundle on Form 0225:

1) The value of MFLCPR

.883

1) The value of MFLCPR

2) Core location of MFLCPR 13 - 32

2) Core location of MFLCPR

3) Percent rated core flow 89.9%

3) Percent rated core flow Cue: None Comments: None

MONTICELLO NUCLEAR GENERATING PLANT JPM-C.2-05.B.1-001 I

TITLE:

CORE THERMAL LIMITS MONITORING Revision 0 Page 4 of 10 Performance Objective'2 Sta'ndard STEP 5 "C" (Procedure Part A, Step 2.c)

Standard:

c. Verify MFLCPR is below the Action Limit Verifies MFLCPR is below the Action and (0.97 times the Tech Spec Limit) and the Tech Spec limits and checks "YES" on Form Tech Spec Limit.

0225

1) IF MFLCPR is below both limits, Cue: None THEN initial Form 0225.

Comments: None

2) IF MFLCPR is not below both limits, THEN proceed as follows:

a) IF MFLCPR is above the Action

Limit, THEN contact a Nuclear Engineer.

NOTE:

Reducing power with recirc flow will not decrease MFLCPR by a significant fraction and may increase MFLCPR. Rod pattern alteration will always be required to return MFLCPR to an acceptable value.

b) IF MFLCPR exceeds the Tech Spec Limit, THEN immediately contact a Nuclear Engineer.

AND take actions required by Tech Spec 3.11.C and 4 AWI-04.08.01 (EVENT NOTIFICATIONS).

STEP 6 (Procedure Part A, Step 2.d)

Standard: Determines MPR and EPR are not out of service.

d. IF MPR or EPR is out of service, THEN verify that guidance for additional Cue: None actions for Core Thermal Limits Monitoring in Operations Manuals C.4-Comments: None B.05.09.A (ABNORMAL PROCEDURES

- MAIN STEAM PRESSURE REGULATOR FAILURE CAUSING DECREASING PRESSURE) and C.4 B.05.09.B (ABNORMAL PROCEDURES

- MAIN STEAM PRESSURE REGULATOR FAILURE CAUSING INCREASING PRESSURE) is followed.

MONTICELLO NUCLEAR GENERATING PLANT JPM-C.2-05.B.1-001 TITLE:

CORE THERMAL LIMITS MONITORING Revision 0 Page 5 of 10 Performance Objective Standard STEP 7 (Procedure Part B, Step 3)

Standard:

Demand Official 3D Monitor to calculate the Evaluates nodal power distribution to find the nodal power distribution, fuel assembly that has its MAPRAT closest AND use the data for the fuel assembly that to 1.0.

has its MAPRAT closest to 1.0.

Cue: None Comments: All three thermal limits printout on 3D Monitor.

STEP 8 "C"(Procedure Part B, Step 3)

Standard:

Record the following data for the most Records data on Form 0225.

limiting fuel bundle on Form 0225:

a. MAPRAT

.880

a. The value of MAPRAT

b. Core location 13-14-5

b. Core location of MAPRAT

c. % rated core flow 89.9%

c. Percent rated core flow Cue: None Comments: None STEP 9 "C" (Procedure Part B, Step 5.a)

Standard:

Verify MAPRAT is below the Action Limit Verifies MAPRAT is below the Action and (0.97 times the Tech Spec Limit) and the Tech Spec limits and checks "YES" on Form Tech Spec Limit.

0207

a. IF MAPRAT is below both limits, Cue: None THEN initial FORM 0207.

Comments: None

MONTICELLO NUCLEAR GENERATING PLANT JPM-C.2-05.B.1-001 TITLE:

CORE THERMAL LIMITS MONITORING Revision 0 Page 6 of 10 Performance Objective Standard STEP 10 (Procedure Part B, Step 5.b)

Standard: None

b. IF MAPRAT is not below both limits, Cue: None THEN proceed as follows:

Comments: None

1) IF MAPRAT is above the Action Limit, AND below the Tech Spec Limit, THEN contact a Nuclear Engineer.

2) IF MAPRAT exceeds the Tech Spec

Limit, THEN immediately contact a Nuclear

Engineer, AND take action required by Tech Spec 3.11.A and 4 AWI-04.08.01.

NOTE:

Reducing power with recirc flow will not decrease MAPRAT by a significant fraction and may increase MAPRAT. Rod pattern alterations will always be required to return MAPRAT to an acceptable value.

STEP 11 (Procedure Part B, Step 5.c)

Standard: None

c. IF either the MPR or the EPR is out of Cue: None

service, THEN verify that guidance for additional Comments: MPR and EPR are not out of actions for Core Thermal Limits service.

Monitoring in Operations Manuals C.4 B.05.09.A and C.4-B.05.09.B is followed.

STEP 12 (Procedure Part C, Step 6)

Standard:

Demand the Official 3D Monitor to calculate Evaluates nodal power distribution.

the nodal power distribution.

Cue:None Comments: All three thermal limits printout on 3 D Monitor.

MONTICELLO NUCLEAR GENERA TING PLANT J P M-C.2-05. B. 1-001 TITLE:

CORE THERMAL LIMITS MONITORING Revision 0 Page 7 of 10 Performance Objective Standard STEP 13 (Procedure Part C, Step 7)

Standard:

Scan the Periodic Log to find the highest Scans Periodic Log and finds the highest

MFLPD, MFLPD and its location in the core.

AND note the MFLPD and the location in the core where it exists.

Cue: None Comments: None STEP 14 "C" (Procedure Part C, Step 8)

Standard:

Record the following data for the most Records the data on Form 0208.

limiting fuel bundle on Form 0208:

a.

The value of MFLPD.

1.010

a. The value of MFLPD.

b.

The location of MFLPD. 35 5

b. The location of MFLPD.

Cue: None Comments: None STEP 15 (Procedure Part C, Step 9.a)

Standard:

Verify MFLPD is below Action Limit (0.97 Determines MFLPD is not below both limits.

times the Tech Spec Limit) and Tech Spec Limit.

Cue: None

a. IF MFLPD is below both limits, Comments: None THEN initial Form 0208 STEP 16 "C" (Procedure Part C, Step 9.b.1)

Standard: None IF MFLPD is not below both limits, Cue: None THEN proceeds as follows:

Comments: Determines MFLPD is above

1) IF MFLPD is above the Action Limit, Action Limit and the Tech Spec Limit and AND below the Tech Spec Limit, checks "NO" on Form 0208.

THEN contact the Nuclear Engineer.

STEP 17 (Procedure Part C, Step 9.b.2)

Standard:

2) IF MFLPD exceeds the Tech Spec Limit, Immediately contacts the Nuclear Engineer.

THEN immediately contact a Nuclear Engineer.

Cue: None Comments: None

STEP 19 "C"(Proc Part C, Step 9.b.2.b & c) b) Take actions required by Tech Spec 3.11.B.

c) Inform personnel according to 4 AWl 04.08.01.

NOTE:

A rapid estimate of the MFLPD can be made by assuming that a power decrease of 1% leads to a MFLPD decrease of 0.01.

Standard:

Describes actions that need to be taken per Tech Spec 3.11.B.

If at any time during operation it is determined that the limiting value for LHGR is being exceeded, action shall be initiated within 15 minutes to restore operation to within the prescribed limits. Surveillance and corresponding action shall continue until reactor operation is within the prescribed limits. I the LHGR is not returned to within the prescribed limits within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , reduce thermal power to less than 25% within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Describes who needs to be notified per 4 AWI-04.08.01.

Part A of Form 3389 (EVENT NOTIFICATIONS)

General Superintendent Operations General Superintendent Engineering May include the following as a courtesy call:

Plant Manager Site Vice President Superintendent Nuclear Engineering Cue: None Comments: None MONTICELLO NUCLEAR GENERATING PLANT JPM-C.2-05.B.1-001 TITLE:

CORE THERMAL LIMITS MONITORING Revision 0 Page 8 of 10 Performance Objective Standard STEP 18 "C"(Proc Part C, Step 9.b.2.a)

Standard:

CAUTION Identifies that power needs to be reduced by Reducing power can cause an increase in approximately 5%.

MFLCPR or MAPRAT. If any bundle has a MAPRAT or MFLCPR greater than the corresponding Action Limit (0.97 for MAPRAT and Cue: Reactor power has been reduced 0.97 for MFLCPR), do not reduce power more than approximately 5% and MFLPD is now at 3% prior to contacting a Nuclear Engineer.

.960.

a) Reduce power at the maximum Comments: None allowable rate until MFLPD meets the Tech Spec Limit.

MONTICELLO NUCLEAR GENERA TING PLANT JPM-C.2-05.B.1-001 TITLE:

CORE THERMAL LIMITS MONITORING Revision 0 Page P of 10 STEP 20 Standard:

INFORM EVALUATOR THAT THE TASK Operator informs evaluator that the task is HAS BEEN COMPLETED.

completed.

Cue: None Comments: DO NOT PROMPT!

MONTICELLO NUCLEAR GENERATING PLANT JPM-C.2-05.B.1-001 TITLE:

CORE THERMAL LIMITS MONITORING Revision 0 Page 10 of 10 CANDIDATES COPY1 INFORM THE EVALUATOR WHEN ýYOU HAVE COMPLETEDý THE TASK! I!

Initial Conditions:

Reactor power has just been increased from 90% power to 98% with the Recirc Flow Control system per C.2-05 Load Following.

You have been asked to perform the Core Thermal Limits Monitoring for MFLCPR, MAPRAT, and MFLPD, per Ops Man C.2-05, Section B.1, Parts A, B, and C. Record data on Forms 0207, 0208, and 0225, of Operations Daily Log 0000 - E, and determine any required actions if necessary. Report when the task is complete.

I q

MONTICELLO NUCLEAR GENERATING PLANT JPM-4AWI-02.02.05-001 TITLE:

TEMPORARY CHANGE REQUEST Revision 7a Page 1 of 5 JOB PERFORMANCE MEASURE SRO:

X SRO/RO:

SRO/RO/NLO:

NLO:

Plant

Reference:

4 AWI-02.02.05, Rev 9; 0255-04-IA-1, Rev 54 Task Standard: Evaluate Temporary Change to Procedure and Determine Acceptability K/A

Reference:

2.2 Task No: 2.2.11 Rating RO/SRO: 2.5/3.4 Recent Events: None Probabilistic Risk Assessment Human Error:

None Monticello Specific Task List

Reference:

SS007.002 CR299.120 METHOD OF TESTING TIME FOR COMPLETION Estimated Time to Complete:

5 Min Simulator:

X Normal:

Alternate Maximum Time to Complete:

10 Min In-Plant:

X Path:

X Time Critical:

Yes X

No Prepared By:

A C Date:

Reviewed By:

Date:

Shift Supv/Shift Mgr Review By:

Date:

-/ /0 z Approved By:

/.(Supt Ops Trng) Date:

"S*.z 0.A 3087 (DOCUMENT CHANGE, HOLD, AND COMMENT FORM) incorporated:

Resp Supv:

OTRNG IAssoc Ref: MTCP-03.32 SR: N Freq: 0 yrs ARMS:

JPM-4AWI-02.02.05-001 Doc Type: 8505 1 Admin Initials:

Date:

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MONTICELLO NUCLEAR GENERATING PLANT J PM-4AWI-02.02.05-001 TITLE:

TEMPORARY CHANGE REQUEST Revision 7a Page 2 of 5 JPM SET-UP Plant Setup:

Fill in Test 0255-04-IA-1 as follows:

Sign Shift Supv approval to commence.

Reason for Performing: No. 1 - Quarterly Complete in conjunction with:

a. No

b. No

c.

No Fill in prerequisites:

Avg Torus Water temp 80/80°F A&B RWCU RWP-22 East HCU RWP - 51 Initial prerequisite regarding status of Core Spray valve position Fill in numbers and initials for STEPS 1 through 56a.

Cross off STEP 56b, initial and date for system engineer supervisor and initial for system engineer.

Write in Comments:

Delete STEP 56b to allow completion of the operability test and return 11 RHR pump to service. The RHR pump minimum flow valve is NOT required to open to establish the required pump flow. Also, RHR pump minimum flow valve is not required to open for the RHR LPCI mode to perform its intended function.

Initial Conditions:

The Reactor is operating at 100% power with all systems normal. The RHR System Operability Test (No. 0255-04-IA-1) for Loop A is being performed to prove RHR system operability. No. 11 RHR Pump minimum flow valve failed to open after the pump was started. The RHR System Engineer is in the Control Room.

Initiating Cues:

The Control Room Operator brings you, the Duty Control Room Supv, test procedure No. 0255-04-IA-1 with a request for a temporary change to the test procedure. The temporary change has been requested by the RHR System Engineer. You are to review the change and either approve or disapprove the change as appropriate.

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MONTICELLO NUCLEAR GENERATING PLANT JPM-4AWI-02.02.05-001 ITITLE:

TEMPORARY CHANGE REQUEST Revision 7a Page 3 of 5 PERFORMANCE INFORMATION Performance Objective Standard STEP 1 (4 AWI-02.02.05, STEP 4.1.4) Standard:

Determines that a permanent procedure Evaluates the change request against the change is not desired. Temporary requirements delineated in 4AWI-02.02.05.

changes SHALL NOT change the scope Cue:

None or intent of an approved procedure.

Comments:

It is not necessary for the candidate to refer directly to 4 AWI-02.02.05. If knowledge level is sufficient, the candidate may immediately disapprove the request based upon the reasons in STEPS 4 and 5.

STEP 2 (4 AWI-02.02.05, STEP 4.1.5) Standard:

Determines that the procedure being Evaluates the change request against the changed is not a modification procedure. requirements delineated in 4 AWI-02.02.05.

Cue:

None Comments:

None STEP 3 (4 AWI-02.02.05, STEP 4.1.7) Standard:

Determines that the requested change is Evaluates the change request against the not of an emergency nature.

requirements delineated in 4 AWI-02.02.05.

Cue:

None Comments:

None STEP 4 (B.03.04-05 PRECAUTION)

Standard:

Determines that the requested change Makes reference to possible pump damage due to would place the No. 11 RHR pump in an operation without minimum flow when giving operational condition that could result in reason for disapproval of the Temporary pump damage due to prolonged Procedure Change Request.

operation against a shutoff head following LPCI initiation with the reactor Cue:

None vessel at high pressure.

Comments:

None STEP 5 (Tech Spec 1.L &

Standard:

B.03.04-05.A.3.f)

Makes reference to Tech Spec operability Determines that the requested change requirements when giving reason for disapproval for the reason stated is contradictory to of the Temporary Procedure Change Request.

the Tech Spec definition of OPERABLE.

Cue:

None Comments:

None I/cmb

MONTICELLO NUCLEAR GENERATING PLANT JPM-4AWI-02.02.05-001 TITLE:

TEMPORARY CHANGE REQUEST Revision 7a Page 4 of 5 Performance Objective Standard STEP 6 "C"

Standard:

Disapproves the requested temporary Disapproves the Temporary Change.

procedure change, declares No. 11 RHR pump inoperable, and issues a WO.

(Non-Critical portion of Standard)

1. Declares No. 11 RHR Pump inoperable.

2.

Issues a WO.

Cue:

None Comments:

1. Disapproval of the change is the critical part of this step.

2. The intent of the procedure may have been changed.

STEP 7 Standard:

INFORM EVALUATOR THAT THE Operator informs evaluator that the task is TASK HAS BEEN COMPLETED.

completed.

Cue:

None Comments:

DO NOT PROMPT!

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MONTICELLO NUCLEAR GENERATING PLANT JPM-4AWI-02.02.05-001 TITLE:

TEMPORARY CHANGE REQUEST Revision 7a Page 5 of 5 CANDIDATES COPY Initial Conditions:

The Reactor is operating at 100% power with all systems normal. The RHR System Operability Test (No. 0255-04-[A-1) for Loop A is being performed to prove RHR system operability. No. 11 RHR Pump minimum flow valve failed to open after the pump was started. The RHR System Engineer is in the Control Room.

INFORM THE EVALUATOR WHEN YOU HAVE COMPLETED THE TASK!!!

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MONTICELLO NUCLEAR GENERATING PLANT JPM-4AWI-04.04.03-001 TITLE:

INITIATE JUMPER BYPASS FORM Revision 6a Page 1 of 7 JOB PERFORMANCE MEASURE SRO:

X SRO/RO:

SRO/RO/NLO:

NLO:

Plant

Reference:

4 AWI-04.04.03, Rev 16; B.03.02-05, Rev 17; Jumper Bypass Form 3034, Rev 20 Task Standard: Initiate Jumper Bypass Form K/A

Reference:

Generic Task No:

2.2.11 Rating RO/SRO: 3.7/3.8 Recent Events: None Probabilistic Risk Assessment Human Error:

None Monticello Specific Task List

Reference:

CR299.128 SS003.004 METHOD OF TESTING TIME FOR COMPLETION Estimated Time to Complete:

10 Min Simulator:

X Normal:

X Alternate Maximum Time to Complete:

20 Min In-Plant:

X Path:

Time Critical:

Yes X

No Prepared By:

t'/A*.L, Date: (9 /0

/&'b, Reviewed By:

Date:

Shift Supv/Shift Mgr Review By-Date:

-7/a/ /0 Approved By:

(Supt Ops Trng) Date: 1 S7 _t FOR ADMIN19TRATIVE USE ONLY 3087 (DOCUMENT CHANGE, HOLD, AND COMMENT FORM) incorporated:

Resp Supv:

OTRNG jAssoc Ref: MTCP-03.32 ISR: N IFreq:

0 yrs ARMS:

JPM-4AWI-04.04.03-001 Doc Type: 8505 Admin Initials:

Date:

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MONTICELLO NUCLEAR GENERATING PLANT JPM-4AWI-04.04.03-001 TITLE" INITIATE JUMPER BYPASS FORM Revision 6a Page 2 of 7 JPM SET-UP Simulator/Plant Setup:

The operator is not required to perform the steps in order, but is required to complete all steps.

Provide blank Form 3034 to SRO per STEP 1, if requested.

Initial Conditions:

You are the Duty Control Room Supervisor. A packing leak has developed on HPCI Valve MO-2034 (HPCI INBOARD STEAM LINE ISOLATION). It has been decided that MO-2034 will be electrically backseated in an attempt to stop the steam leak per procedure B.03.02-05.H.2. A bypass control is needed to complete the procedure.

Initiating Cues:

Properly document the hanging of the jumper as required in procedure B.03.02-05.H.2. Complete Section #1 of the Jumper Bypass Form.

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MONTICELLO NUCLEAR GENERATING PLANT JPM-4AWI-04.04.03-001 TITLE:

INITIATE JUMPER BYPASS FORM Revision 6a Page 3 of 7 PERFORMANCE INFORMATION SPerformance Objective Standard STEP 1 Standard:

Locate the following procedures:

Locates appropriate procedures.

a. 4 AWI-04.04.03 (BYPASS Cue:

None CONTROL) section 4.2, "Oc Comments:

None Reviewed Procedures".

b. B.03.02-05.H.2, (Backseating HPCI Steam Supply Motor-Operated Valves).

STEP 2 (Proc STEP 4.2.1)

Standard:

OC reviewed procedures are those pro-Determines that B.03.02-05 is an OC reviewed cedures for which OC revision review is procedure and proceeds to the next step.

required.

Cue:

None Comments: None STEP 3 (Proc STEP 4.2.2)

Standard:

Reviews Step 4.2.2.

Determines that a 1 OCFR50.59 screening is not required for B.03.02-05.

Cue:

None Comments:

None I/cmb

MONTICELLO NUCLEAR GENERATING PLANT JPM-4AWI-04.04.03-001 TITLE:

INITIATE JUMPER BYPASS FORM Revision 6a Page 4 of 7 Performance Objective Standard STEP 4 "C"

(Proc STEP 4.2.3)

Standard:

A Form 3034 is not required for OC Operator uses form 3034 to document Jumper/

reviewed procedures provided:

Bypass. If this method is used, then proceed to A. The procedure contains STEP 6.

documented independent Cue:

None verification of installation and Comments:

removal of the bypass device.

For Operations Manual Documentation may be provided by a log entry. If Procedures, documentation may this method is used, then operator completes log be provided by a log entry as entry per 4 AWI-04.04.02, Section 4.3.7.E.

noted in Section 4.3.7 of 4 AWI-04.04.02 (EQUIPMENT POSITIONING, WITNESS CHECK, AND INDEPENDENT VERIFICATION METHODS).

B. The procedure contains a Shift Supervisor or Nuclear Security Specialist sign-off for approval to initiate the procedure. Shift Supervisor sign-off is not required for for Operations Manual Procedures.

C. The bypass is not installed for more than 7 days.

STEP 5 "C"

Standard:

If log entry method is used, inform Log entry must include a Performed By:

evaluator that the task is completed.

and Independent Verification By:

sign-off.

Operator informs evaluator that the task is com pleted.

Cue:

Complete Section #1 of Jumper Bypass Form.

Comments: DO NOT PROMPT!

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MONTICELLO NUCLEAR GENERATING PLANT JPM-4AWI-04.04.03-001 TITLE:

INITIATE JUMPER BYPASS FORM Revision 6a Page 5 of 7 Performance Objective Standard STEP 6 (Proc STEP 4.3.1.A)

Standard:

Check SECURITY RELATED if the Determines that the bypasses are NOT jumper or bypass is to be installed in SECURITY RELATED and leaves SECURITY security systems identified in Operations RELATED [] blank.

Manual Sections B.08.12.01 through Cue:

B.08.12.07 or has Component Master List system codes of SCM, SEL, SHV, or If requested, next jumper bypass number is SIN, except for security doors that 02-100 provide fire barriers.

Comments:

This is not a critical step because if sent to security, it would be returned prior to authorization.

STEP 7 "C"

(Proc STEP 4.3.1.1)

Standard:

Reason For Installation - Identify the Enters "B.03.02-05.H.2 (Backseating-HPCI Steam work to be completed or the purpose of Supply Motor-Operated Valves) in the appropriate the bypass.

space on Form No. 3034.

1. Reference the approved procedure Cue:

None number or work order if applicable.

Comments:

Similar wording may be used. The procedure title is not required to be included.

STEP 8 "C"

(Proc STEP 4.3.1.C)

Standard:

Installed For - Identify the responsible Enters the Duty Shift Supv in the "Installed For" individual, work group, or work docu-space.

ment number requiring the bypass Cue:

None installation. Bypasses installed for Operations may identify the Duty Shift Comments:

Supervisor as the responsible individual. The SRO may also enter "Control Room Ops" or the controlling work group.

STEP 9 (Proc STEP 4.3.1.D)

Standard:

If the bypass is installed for an OC Enter NO for System Engineer required (Section 3 reviewed procedure, the 10 CFR 50.59 of Form 3034).

review requirements have been satisfied. For all other bypasses, a System Engineer review is required to Comments:

determine the need for a 10 CFR 50.59

1. This is an OC reviewed procedure thus, evaluation. The System Engineer Sys EngOC review prequred.

SHALL complete the Jumper Bypass System Engineer review not required.

Form per section 4.5. Note that for an

2.

This is not a critical step because if the Shift Emergency condition, the bypass may Supv sent it for System Engineer review, this be used and the review performed later, would be more conservative, although not needed.

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MONTICELLO NUCLEAR GENERATING PLANT JPM-4AWI-04.04.03-001 TITLE:

INITIATE JUMPER BYPASS FORM Revision 6a Page 6 of 7 Performance Objective Standard STEP 10 (Proc STEP 4.3.1.E)

Standard:

Installation anticipated greater than 7 Enters NO.

days - Indicate YES or NO, and if YES, Cue:

None specify affected critical drawings. The preparer SHALL identify the Bypass Comments:

Form number on the affected critical The bypass will be cleared as soon as MO-2034 drawings by affixing a removable is basswle co adhesive label (available from the Shift is backseated.

Supv) on the drawing preferably in the lower right-hand corner.

STEP 11 (Proc STEP 4.3.1.F)

Standard:

Function Bypassed/Affected Enters "NA" in the "Function Bypassed/Affected Equipment - Identify the function Equipment" space.

bypassed and/or the affected equip-Cue:

None ment.

Comments:

NA should be entered due to involvement of a procedure requiring OC revision review.

STEP 12 (Proc STEP 4.3.1.G)

Standard:

If temporarily modifying electrical circuits, Enters NA in the "Configuration Verified By" block.

perform configuration verification of the C proposed installation.

If not modifying ue:

None electrical circuits, the preparer may NA Comments:

the CONFIGURATION VERIFICATION blank on the Jumper Bypass Form. See NA should be entered due to involvement of a Section 4.4 for details.

procedure requiring OC revision review.

STEP 13 (Proc STEP 4.3.1..H)

Standard:

Prepared By: Provide the name of the Enters own name.

respective work group representative, Cue:

None System Engineer or other individual re questing the jumper bypass.

Comments:

None STEP 14 Standard:

INFORM EVALUATOR THAT THE Operator informs evaluator that the task is com TASK HAS BEEN COMPLETED.

pleted.

Cue:

None Comments:

DO NOT PROMPT!

I/cmb

MONTICELLO NUCLEAR GENERATING PLANT JPM-4AWI-04.04.03-001 TITLE:

INITIATE JUMPER BYPASS FORM Revision 6a Page 7 of 7 CANDIDATES COPY Initial Conditions:

You are the Duty Control Room Supervisor. A packing leak has developed on HPCI Valve MO-2034 (HPCI INBOARD STEAM LINE ISOLATION). It has been decided that MO-2034 will be electrically backseated in an attempt to stop the steam leak per procedure B.03.02-05.H.2. A bypass control is needed to complete the procedure.

Properly document the hanging of the jumper as required in procedure B.03.02-05.H.2. Complete Section #1 of the Jumper Bypass Form.

INFORM THE EVALUATOR WHEN YOU HAVE COMPLETED THE TASK!!!

I/cmb

MONTICELLO NUCLEAR GENERATING PLANT JPM-AWI-08.04.01-001 TITLE:

EXPECTED DOSE DETERMINATION TO INSPECT Revision 0 EQUIPMENT E

Page 1 of 5 JOB PERFORMANCE MEASURE SRO:

X SRO/RO:

SRO/RO/NLO:

NLO:

Plant

Reference:

4 AWI-08.04.01, Rev. 12 Task Standard:

Calculate Expected Dose to Inspect Equipment K/A

Reference:

Generic Task No.:

2.3.4 Rating RO/SRO:

2.5/3.1 Recent Events:

None Probabilistic Risk Assessment Human Error:

None Monticello Specific Task List

Reference:

SS299.248 METHOD OF TESTING TIME FOR COMPLETION Estimated Time to Complete:

15 min.

Simulator:

X Normal:

X Maximum Time to Complete:

25 min.

Alternate In-Plant:

Path:

Time Critical:

Yes X

No Prepared By:

/

Date:

Reviewed By:

Date:

Shift Supv/Shift Mgr Review By:

Date: C-7/'6 16 Approved By:

Date:

,.3jt/,

02 1

/

o

MONTICELLO NUCLEAR GENERATING PLANT JPM-AWI-08.04.01-001 TITLE:

EXPECTED DOSE DETERMINATION TO INSPECT Revision 0 EQUIPMENT Page 2 of 5 JPM SET-7UP Simulator Setup:

Calculator Initial Conditions:

The plant is operating at 100% power.

Initiating Cues:

An inadvertent Group III caused a water hammer requiring the pipe supports and hangers to be inspected for possible damage. You have been requested to inspect the piping for #12 RWCU Pump that runs along the shield wall below RWCU MO 2398. Some climbing is anticipated and the estimated time to complete this task is 15 minutes.

Your task is to determine the expected dose that an operator would receive, class of protective clothing required, and what actions must be taken to gain entry to the area while completing this task. Then determine which of the following operators can be assigned the task. Vocalize your thought process and report when your task is complete.

NAME YEAR TO DATE DOSE John 1950 mr Paul 1800 mr George 1750 mr Fred 1930 mr

MONTICELLO NUCLEAR GENERA TING PLANT J PM-AWI-08.04.01-001 TITLE:

EXPECTED DOSE DETERMINATION TO INSPECT Revision 0 EQUIPMENT Page 3 of 5 PERFORMANCE INFORMATION Performance Objective

-Standard STEP 1 Standard:

Locates a copy of the survey map and the Describes location of survey map and Radiation Work Permit (RWP 22).

Radiation Work Permit (RWP22).

Cue:

When operator describes where survey maps and RWPs are located then provide him with a copy of the appropriate survey map and RWP.

Comments:

Survey maps and RWPs are located on the basement level of the administration building in the same area where personnel obtain their ALANOR.

STEP 2 Standard:

Determine the Dose Rate near the Dose Rate determined to be 440 mrem/hr component.

Cue: None Comments: None STEP 3 "C" Standard:

Calculates expected dose.

Expected dose calculated to be 110 mrem.

Cue: None Comments: None STEP 4 Determines that component is located in a "Locked High Radiation Area (LHRA).

Standard:

Determines that the component is in a LHRA and a key is required for entry to the room (Non-critical step).

Cue: None Comments: None

MONTICELLO NUCLEAR GENERATING PLANT JPM-AWI-08.04.01-001 TITLE:

EXPECTED DOSE DETERMINATION TO INSPECT Revision 0 EQUIPMENT Page 4 of 5 Performance Objec6tive Standard STEP 5 "C" Standard:

Determines the requirements for entering a Determines that:

"Locked High Radiation Area (LHRA).

0 Required to notify Rad Prot Coordinator.

"* Requires a Dose Rate Meter

"* Requires Class 2 protective clothing Cue: None Comments: None STEP 6 "C" Standard:

Determines which of the four operators could Determines that Paul or George can perform perform the task.

the task.

Cue: None Comments:

John and Fred would exceed the 2000 mrem/yr. Administrative limit at Monticello.

John 1950 + 110 = 2060 mrem Fred 1930 + 110 = 2040 mrem Paul and George will not exceed the 2000 mrem/yr administrative limit if assigned the task Paul 1800 + 110 = 1910 mrem George 1750 + 110 = 1860 mrem STEP 7 Standard:

INFORM EVALUATOR THAT THE TASK Operator informs evaluator that the task is HAS BEEN COMPLETED.

completed.

Cue: None Comments: DO NOT PROMPT!

MONTICELLO NUCLEAR GENERATING PLANT JPM-AWI-08.04.01-001 TITLE:

EXPECTED DOSE DETERMINATION TO INSPECT Revision 0 EQUIPMENT Page 5 of 5 CANDIDATES" COPY Initial Conditions:

The plant is operating at 100% power.

Initiating Cue:

An inadvertent Group III caused a water hammer requiring the pipe supports and hangers to be inspected for possible damage. You have been requested to inspect the piping for #12 RWCU Pump that runs along the shield wall below RWCU MO-2398.

Some climbing is anticipated and the estimated time to complete this task is 15 minutes.

Your task is to determine the expected dose that an operator would receive, class of protective clothing required, and what actions must be taken to gain entry to the area while completing this task. Then determine which of the following operators can be assigned the task. Vocalize your thought process and report when your task is complete.

NAME YEAR TO DATE DOSE John 1950 mr Paul 1800 mr George 1750 mr Fred 1930 mr INFORM THE EVALUATOR WHEN YOU HAVE COMPLETED THE TASK.!!!S=

MONTICELLO NUCLEAR GENERATING PLANT JPM-A.2-101-001 TITLE:

E-PLAN CLASSIFICATION Revision 8 Page 1 of 6 JOB PERFORMANCE EASURE SRO:

X SRO/RO:

SRO/RO/NLO:

NLO:

Plant

Reference:

A.2-101, Rev. 27; A.2-204, Rev. 14 Task Standard:

Classify an event and determine Protective Action Recommendation K/A

Reference:

Generic Task No.:

2.4.38 Rating RO/SRO:

2.2/4.0 2.4.44 2.1/4.0 Recent Events:

None Probabilistic Risk Assessment Human Error:

None Monticello Specific Task List

Reference:

SS304.101 SS304.121 METHOD OF TESTING TIME FOR COMPLETION Estimated Time to Complete:

15/08 Simulator:

X Normal:

X Maximum Time to Complete:

15/10 Alternate In-Plant:

Path:

Time Critical:

X Yes No Prepared By:

di AI Date: 0 Reviewed By:.w, Date:

Shift Supv/Shift Mgr Review By:

Date:

7

,/0 Approved By:

Date: I -s

.,2_

MONTICELLO NUCLEAR GENERATING PLANT JPM-A.2-101-001 TITLE:

E-PLAN CLASSIFICATION Revision 8 Page 2 of 6 JPM'SET-'UP Simulator Setup:

Form 5790-102-02 incorrectly filled out Form 5790-102-02 correctly filled out MET Tower Data Sheet.

Initial Conditions:

The plant is operating at 100% power with the MPR providing pressure control due to the EPR being out of service.

There is a sudden pressure increase of 10 psig followed by a rapid pressure decrease to 820 psig. A group 1 Isolation and Reactor scram occur causing all rods to fully insert. In verifying the Group 1 Isolation, it is discovered that MSIVs AO-2-80A and AO-2-86A failed to close.

ARM readings in the Turbine Building (Turbine floor, front standard, etc.) increase above their alarm setpoints. As attempts are made to close the failed MSIVs, radiation levels increase in both the Reactor Building and Turbine Building until Turbine Building ARMs indicate full scale and the Reactor Building vent WRGMs have increased to 7200 pýci/sec. Fuel cladding degradation is confirmed due to Main Steam Line and Offgas Monitor radiation level increases. All applicable abnormal and EOP procedures have been entered.

Reactor water level is being maintained +9 to +48 inches with feedwater level control.

Reactor Building vent monitors are at 20 mR/HR and slowly increasing. Fuel Pool process radiation monitors are at 10 and 15 mR/HR and stable. Standby Gas Treatment/Secondary Containment isolation initiation setpoints have NOT been reached yet.

The shift chemist has just informed you there is an unplanned release and it is currently ten (10) times greater than normal.

Initiating Cues:

Determine the appropriate Emergency Classification which indicates the highest classification. Notify SEC to make Protective Action Recommendations if appropriate.

Time To Classify START TIME:

MONTICELLO NUCLEAR GENERATING PLANT JPM-A.2-101-001 TITLE:

E-PLAN CLASSIFICATION Revision 8 Page 3 of 6 PERFORMANCE INFORMATION Performance Objective 1Standard STEP 1 Standard:

Locates procedure A.2-101, CLASSIFICATION Locates appropriate procedure.

OF EMERGENCIES.

Cue: None Comments: None STEP 2 (Procedure Step 6.1.2.A.2)

Standard:

Refer to FIGURE 7.1 (LIST OF INITIATING Locates appropriate initiating condition(s). (1, 2, CONDITIONS) and identify any guidelines 5, 6, 28, 29) applicable to the initiating condition.

Cue: None Comments:

Operator may locate appropriate initiating condition(s) by searching through FIGURE 7.2 (EMERGENCY CLASSIFICATION GUIDELINES) directly without use of FIGURE 7.1.

STEP 3 (Procedure STEP 6.1.2.A.3))

Standard:

Locate the applicable guideline in FIGURE 7.2 Locates appropriate guideline(s). (1, 2, 5, 6, 28, (EMERGENCY CLASSIFICATION

29)

GUIDELINES).

Cue: None Comments:

Guideline 28 is the most applicable.

STEP 4 (Procedure STEP 6.1.2.A.4)

Standard:

If multiple events and/or indications are involved, Classifies event as a General Emergency lAW classify the emergency based on the event (or Guideline 28 indication) that results in the highest (most conservative) emergency classification.

Cue: None Comments: Classification must be completed within 15 minutes.

Time To Classify STOP TIME:

Time to Make Notification START TIME

MONTICELLO NUCLEAR GENERATING PLANT JPM-A.2-101-001 TITLE:

E-PLAN CLASSIFICATION Revision 8 Page 4 of 6 STEP 5 (Proc A.2-204, STEP 6.1.1.A)

Standard:

Initiate Form 5790-102-02 (MONTICELLO Notifies SEC to make Protective Action EMERGENCY NOTIFICATION REPORT Recommendations if appropriate FORM)

Cue: As SEC, provide candidate with A. Complete Section 1.4 recommending an completed copy of Form 5790-102-02 for evacuation of a 2 mile radius and 5 miles review and approval. (Include MET Tower downwind and advise the remainder of the data) plume EPZ to go indoors to monitor EAS broadcasts.

Comments: None STEP 6 (Proc A.2-204, STEP 6.1.1.1)

Standard:

Determine which geopolitical subareas are Identifies the geopolitical subareas on Form affected by referring to the Sector-Subarea 5790-102-02 should be 5E and 5S.

Conversion Table on Form 5790-102-02.

Instructs SEC to fill out a new form with correct Geopolitcal subareas identified (downwind sectors E, F,G and subareas 5E

& 5S).

Cue: Provide candidate with Form 5790-102 02 correctly completed.

Comments: None STEP 7 (Proc A.2-204, STEP 6.1.1.C)

Standard:

Ensure completion of Parts 1.0 and 2.0 of Form Reviews new Form 5790-102-02 and 5790-102-02 and submit the completed form to approves.

the ED for approval.

Cue: None Comments: None STEP 8 Standard:

INFORM EVALUATOR THAT THE TASK HAS Operator informs evaluator that the task is BEEN COMPLETED.

completed.

Cue: None Time to Make Notification Comments: Form 5790-102-02 must be completed within 10 minutes from STOP TIME classification.

DO NOT -PROMPT!

MONTICELLO NUCLEAR GENERATING PLANT JPM-A.2-101-001 TITLE:

E-PLAN CLASSIFICATION Revision 8 Page 5 of 6 CANDIDATES'COPY Initial Conditions:

The plant is operating at 100% power with the MPR providing pressure control due to the EPR being out of service.

There is a sudden pressure increase of 10 psig followed by a rapid pressure decrease to 820 psig. A group 1 Isolation and Reactor scram occur causing all rods to fully insert. In verifying the Group 1 Isolation, it is discovered that MSIVs AO-2-80A and AO-2-86A failed to close.

ARM readings in the Turbine Building (Turbine floor, front standard, etc.) increase above their alarm setpoints. As attempts are made to close the failed MSIVs, radiation levels increase in both the Reactor Building and Turbine Building until Turbine Building arms indicate full scale and the Reactor Building vent WRGMs have increased to 7200 ýici/sec. Fuel cladding degradation is confirmed due to Main Steam Line and Offgas Monitor radiation level increases. All applicable abnormal and EOP procedures have been entered.

Reactor water level is being maintained +9 to +48 inches with feedwater level control.

Reactor Building vent monitors are at 20 mR/HR and slowly increasing. Fuel Pool process radiation monitors are at 10 and 15 mR/HR and stable. Standby Gas Treatment/Secondary Containment isolation initiation setpoints have NOT been reached yet.

The shift chemist has just informed you there is an unplanned release and it is currently ten (10) times greater than normal.

INFORM THE'EVALUATOR WHEN YOU HAVE COMPLETED THE TASKH!

Initiating Cues:

Determine the appropriate Emergency Classification which indicates the highest classification. Notify SEC to make Protective Action Recommendations if appropriate.

: *51111ii!

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i !:ii !! !7!fii*'l i riii

?,iai;i;;:; +,,

>i; iii

!;iililii7ii!!i!ii iii!ii i

MONTICELLO NUCLEAR GENERATING PLANT JPM-A.2-101-001 TITLE:

E-PLAN CLASSIFICATION Revision 8 Page 6 of 6 Meteoroloaical Data Channel 04 17 Channel 05 297 Channel 11

-1.47 Channel 13 54 0F Channel 16 Y

MONTICELLO NUCLEAR GENERA TING PLANT J PM-C.2-05. B.1-002 TITLE:

CORE THERMAL LIMITS MONITORING Revision 0 Page 1 of 9 JOB PERFORMANCE MEASURE SRO:

SRO/RO:

X SRO/RO/NLO:

NLO:

Plant

Reference:

C.2-05, Rev. 13 Task Standard:

Perform Core Thermal Limits monitoring.

K/A

Reference:

Generic Task No.:

2.1.19 Rating RO/SRO:

3.0/3.0 Recent Events:

None Probabilistic Risk Assessment Human Error:

None Monticello Specific Task List

Reference:

CR200.129 METHOD OF TESTING TIME FOR COMPLETION Estimated Time to Complete:

10 min.

Simulator:

X Normal:

Maximum Time to Complete:

20 min.

Alternate X

In-Plant:

Path:

Time Critical:

Yes X

No Prepared By:

Date:

6/

4 z Reviewed By:

Date:

Shift Supv/Shift Mgr Review By:

Date:

Approved By:

/_Date:

2

MONTICELLO NUCLEAR GENERA TING PLANT JPM-C.2-05.B.1-002 TITLE:

CORE THERMAL LIMITS MONITORING Revision 0 Page 2 of 9 JPM SET-UP Simulator Setup:

Not Applicable Copy of Operations Daily Log - Part E 3D Monitor printout Place a red pencil on the control room desk.

Initial Conditions:

Rx Power has just been increased from 90% power to 98% with the Recirc. Flow Control system per C.2 -05 Load Following.

Initiating Cues:

The Control Room Supervisor has requested reactor power be increased to 100%.

You have been directed to perform the Core Thermal Limits Monitoring for MFLCPR, MAPRAT, and MFLPD, per Ops Man C.2-05, Section B.1, Parts A, B, and C. Record data on Forms 0207, 0208, and 0225, of Operations Daily Log 0000 - E.

MONTICELLO NUCLEAR GENERATING PLANT JPM-C.2-05.B.1-002 TITLE:

CORE THERMAL LIMITS MONITORING Revision 0 Page 3 of 9 PERFORMANCE INFORMATION Performance Objective Stan~dard STEP 1 Standard: Locates appropriate procedure.

Locates procedure C.2-05, "Power Cue: None Operation".

Comments: Parts A, B, and C may be performed in any order.

STEP 2 (Procedure Part A, Step 1)

Standard: None IF process computer is not anticipated to be Cue: None available during a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period, THEN contact a Nuclear Engineer to arrange Comments: Process computer is available.

determination of MCPR.

STEP 3 "C" (Procedure Part A, Step 2.a)

Standard: None When 3D Monicore computer is available, Cue: Provide candidate with copy of 3D perform the following:

Monitor edit.

a. Demand Official 3D Monitor to calculate Comments: A 3D Monitor edit cannot be core nodal power distribution, demanded on the simulator.

AND use MCPR data for the fuel assemblies that are closest to the limiting CPR.

NOTE 4:

The most limiting MCPR is edited as MFLCPR on the Periodic Log NOTE 5:

MFLCPR is the Core Maximum ratio of power and flow dependent CPR limit to the bundle's actual CPR.

STEP 4 "C" (Procedure Part A, Step 2.b)

Standard:

b. Record the following data for the most Records data on Form 0225.

limiting fuel bundle on Form 0225:

a. MFLCPR

.883

a. The value of MFLCPR

b. Core location 13 - 32

b. Core location of MFLCPR

c. % rated core flow 89.9%

c. Percent rated core flow Cue: None Comments: None

MONTICELLO NUCLEAR GENERA TING PLANT J PM-C.2-05. B.1-002 TITLE:

CORE THERMAL LIMITS MONITORING Revision 0 Page 4 of 9 Performance Objective jStandard STEP 5 "C"(Procedure Part A, Step 2.c)

Standard:

c. Verify MFLCPR is below the Action Limit Verifies MFLCPR is below the Action and (0.97 times the Tech Spec Limit) and the Tech Spec limits and checks "YES" on Form Tech Spec Limit.

0225

1) IF MFLCPR is below both limits, Cue: None THEN initial Form 0225.

Comments: None

2) IF MFLCPR is not below both limits, THEN proceed as follows:

a) IF MFLCPR is above the Action

Limit, THEN contact a Nuclear Engineer.

NOTE:

Reducing power with recirc flow will not decrease MFLCPR by a significant fraction and may increase MFLCPR. Rod pattern alteration will always be required to return MFLCPR to an acceptable value.

b) IF MFLCPR exceeds the Tech Spec Limit, THEN immediately contact a Nuclear Engineer.

AND take actions required by Tech Spec 3.11.C and 4 AWI-04.08.01 (EVENT NOTIFICATIONS).

MONTICELLO NUCLEAR GENERA TING PLANT J PM-C.2-05. B.1-002 TITLE:

CORE THERMAL LIMITS MONITORING Revision 0 Pau 5 of 9 Performance Objective Standard STEP 6 (Procedure Part A, Step 2.d)

Standard: Determines that MPR and EPR are not out of service.

d.

IF MPR or EPR is out of service, THEN verify that guidance for additional Cue: None actions for Core Thermal Limits Monitoring in Operations Manuals C.4-Comments: None B.05.09.A (ABNORMAL PROCEDURES

- MAIN STEAM PRESSURE REGULATOR FAILURE CAUSING DECREASING PRESSURE) and C.4 B.05.09.B (ABNORMAL PROCEDURES

- MAIN STEAM PRESSURE REGULATOR FAILURE CAUSING INCREASING PRESSURE) is followed.

STEP 7 (Procedure Part B, Step 3)

Standard:

Demand Official 3D Monitor to calculate the Evaluates nodal power distribution to find the nodal power distribution, fuel assembly that has its MAPRAT closest AND use the data for the fuel assembly that to 1.0.

has its MAPRAT closest to 1.0.

Cue: None Comments:

All three thermal limits are printed out when a 3D Monitor is requested.

STEP 8 "C" (Procedure Part B, Step 3)

Standard:

Record the following data for the most Records data on Form 0225.

limiting fuel bundle on Form 0225:

a. MAPRAT

.880

a. The value of MAPRAT

b. Core location 13-14-5

b. Core location of MAPRAT

c. %rated core flow 89.9%

c. Percent rated core flow Cue: None Comments: None

MONTICELLO NUCLEAR GENERA TING PLANT J P M-C.2-05. B.1-002 TITLE:

CORE THERMAL LIMITS MONITORING Revision 0 Page 6 of 9 Performance Obecitive Standard STEP 9 "C"(Procedure Part B, Step 5.a)

Standard:

Verify MAPRAT is below the Action Limit Verifies MAPRAT is below the Action and (0.97 times the Tech Spec Limit) and the Tech Spec limits and checks "YES" on Form Tech Spec Limit.

0207.

a. IF MAPRAT is below both limits, THEN initial FORM 0207.

Cue: None Comments: None STEP 10 (Procedure Part B, Step 5.b)

Standard: None

b. IF MAPRAT is not below both limits, Cue: None THEN proceed as follows:

Comments: None

1) IF MAPRAT is above the Action Limit, AND below the Tech Spec Limit, THEN contact a Nuclear Engineer.

2) IF MAPRAT exceeds the Tech Spec

Limit, THEN immediately contact a Nuclear

Engineer, AND take action required by Tech Spec 3.11.A and 4 AWI-04.08.01.

NOTE:

Reducing power with recirc flow will not decrease MAPRAT by a significant fraction and may increase MAPRAT. Rod pattern alterations will always be required to return MAPRAT to an acceptable value.

STEP 11 (Procedure Part B, Step 5.c)

Standard: None

c. IF either the MPR or the EPR is out of Cue: None

service, THEN verify that guidance for additional Comments: MPR and EPR are not out of actions for Core Thermal Limits service.

Monitoring in Operations Manuals C.4 B.05.09.A and C.4-B.05.09.B is followed.

MONTICELLO NUCLEAR GENERATING PLANT JPM-C.2-05.B.1-002 TITLE:

CORE THERMAL LIMITS MONITORING Revision 0 Page 7 of 9 Performance Objbctive Standard STEP 12 (Procedure Part C, Step 6)

Standard:

Demand the Official 3D Monitor to calculate Evaluates nodal power distribution.

the nodal power distribution.

Cue:

Comments: All three thermal limits are printed out when a 3D Monitor is requested.

STEP 13 (Procedure Part C, Step 7)

Standard:

Scan the Periodic Log to find the highest Scans Periodic Log and finds the highest

MFLPD, MFLPD and its location in the core.

AND note the MFLPD and the location in the core where it exists.

Cue: None Comments: None STEP 14 "C" (Procedure Part C, Step 8)

Standard:

Record the following data for the most Records the data on Form 0208.

limiting fuel bundle on Form 0208:

a. MFLPD

.990

a. The value of MFLPD.

b. Location of MFLPD 35 5

b. The location of MFLPD.

Cue: None Comments: None STEP 15 (Procedure Part C, Step 9.a)

Standard:

Verify MFLPD is below Action Limit (0.97 Determines MFLPD is not below both limits.

times the Tech Spec Limit) and Tech Spec Limit.

Cue: None

a. IF MFLPD is below both limits, Comments: None THEN initial Form 0208

MONTICELLO NUCLEAR GENERATING PLANT JPM-C.2-05.B.1-002 TITLE:

CORE THERMAL LIMITS MONITORING Revision 0 Page 8 of 9 Performance Objective I

Standard I

Standard:

STEP 16 "C" (Procedure Part C, Step 9.b)

IF MFLPD is not below both limits, THEN proceeds as follows:

1) IF MFLPD is above the Action Limit, AND below the Tech Spec Limit, THEN contact the Nuclear Engineer.

2) IF MFLPD exceeds the Tech Spec Limit, THEN immediately contact a Nuclear Engineer.

CAUTION Reducing power can cause an increase in MFLCPR or MAPRAT. If any bundle has a MAPRAT or MFLCPR greater than the corresponding Action Limit (0.97 for MAPRAT and 0.97 for MFLCPR), do not reduce power more than 3% prior to contacting a Nuclear Engineer.

a) Reduce power at the maximum allowable rate until MFLPD meets the Tech Spec Limit.

b) Take actions required by Tech Spec 3.11.B.

c) Inform personnel according to 4 AWl 04.08.01.

NOTE:

A rapid estimate of the MFLPD can be made by assuming that a power decrease of 1% leads to a MFLPD decrease of 0.01.

STEP 17 Standard:

INFORM EVALUATOR THAT THE TASK Operator informs evaluator that the task is HAS BEEN COMPLETED.

completed.

Cue: None Comments: DO NOT PROMPT!

Observes that MFLPD is above Action Limit but below the Tech Spec limit, and checks "NO" on Form 0208.

1) Immediately contacts the Nuclear Engineer

2) Evaluates that power needs to be reduced approximately 3%. Notifies SS of required actions.

Cue:

Another operator will decrease reactor power within acceptable limits.

Comments: It is not expected for the candidates to make the required notifications.

MONTICELLO NUCLEAR GENERA TING PLANT JPM-C.2-05. B.1-002 TITLE:

CORE THERMAL LIMITS MONITORING Revision 0 Page 9 of 9 CANDIDATES COPY 1

INFORM THE EVALUATOR WHEN YOU HAVE COMPLETED THE TASK!!!

Initiating Conditions:

Rx Power has just been increased from 90% power to 98% with the Recirc. Flow Control system per C.2 -05 Load Following Initiating Cue:

The Control Room Supervisor has requested reactor power be increased to 100%.

You have been directed to perform the Core Thermal Limits Monitoring for MFLCPR, MAPRAT, and MFLPD, per Ops Man C.2-05, Section B.1, Parts A, B, and C. Record data on Forms 0207, 0208, and 0225, of Operations Daily Log 0000 - E.

3MONTICELLO NUCLEAR GENERATING PLANT JPM-3139-001 TITLE:

CONTROL ROOM PANEL WALKDOWN Revision 0 Page 1 of 5 JOB PERFORMANCE MEASURE SRO:

SRO/RO:

X SRO/RO/NLO:

NLO:

Plant

Reference:

Procedure Checklist 3139, Rev. 24 Task Standard:

Perform a Control Room Shift Turnover Checklist and panel walkdown and identify any discrepancies.

K/A

Reference:

Generic Task No.:

2.1.31 Rating RO/SRO:

4.2/3.9 Recent Events:

None Probabilistic Risk Assessment Human Error:

None Monticello Specific Task List

Reference:

CR298.103 METHOD OF TESTING TIME FOR COMPLETION Estimated Time to Complete:

15 min.

Simulator:

X Normal:

X Maximum Time to Complete:

25 min.

Alternate In-Plant:

Path:

Time Critical:

Yes X

No Prepared By:

Date:

4, Reviewed By:

/

Date:

Shift Supv/Shift Mgr Review By: Ae{4 Date:..

Approved By:

Date:

02-

/

I

3MONTICELLO NUCLEAR GENERATING PLANT JPM-3139-001 TITLE:

CONTROL ROOM PANEL WALKDOWN Revision 0 Pa~ge 2 of 5 JPM SET-UP Simulator Setup:

Place simulator in "RUN" until core thermal power updates.

lOS the "green" light "off' for #11 Core Spray Pump.

Place the RCIC Flow Control in "manual".

Place the Master FW controller in "manual".

Place the RFP High Level Trip "Normal/Bypass" switch in the "Bypass" position.

EPR and MPR both in control (married).

Initial Conditions:

The time is 1800. The plant is operating at 100% power with all equipment operating as expected.

Initiating Cues:

As the BOP operator, you are to walkdown the control room panels and complete page #1 of the CONTROL ROOM SHIFT TURNOVER CHECKLIST, Form 3139, and identify any discrepancies discovered during the panel walkdown. (Provide Candidate a copy of Form 3139 (CONTROL ROOM SHIFT TURNOVER CHECKLIST)

3MONTICELLO NUCLEAR GENERATING PLANT JPM-3139-001 TITLE:

CONTROL ROOM PANEL WALKDOWN Revision 0 Page 3 of 5 PERFORMANCE INFORMATION Performance Objective Standa..rd STEP 1 (CHECKLIST 3139)

Standard:

Operator completes "parameter logging" on Operator completes "parameter logging", no Form 3139.

discrepancies identified.

Cue: None Comments: None STEP 2 (CHECKLIST 3139)

Standard:

Operator completes INSTRUMENTATION Operator completes INSTRUMENTATION section of Form 3139.

section, no discrepancies identified.

Cue: None Comments: None STEP 3 "C" (CHECKLIST 3139)

Standard:

Operator completes CONTROLLER MODES Operator Completes CONTROLLER MODES section of Form 3139.

section, and identifies the following discrepancies:

1) Main FW Reg. Valve in MSTR-MAN.

2) RFP level Trip in BYPASS

3) EPR and MPR in service.

Cue: As the CRS, when notified of any of the above discrepancies, inform candidate that another operator will correct the condidtion.

Comments: Candidate must identify 2 of the 3 above listed discrepancies

3MONTICELLO NUCLEAR GENERATING PLANT JPM-3139-001 TITLE:

CONTROL ROOM PANEL WALKDOWN Revision 0 Page 4 of 5 STEP 4 "C"

(CHECKLIST 3139)

Operator completes EMERGENCY SYSTEMS section of Form 3139.

SI 9.Performance Objective Sadr Standard STEP 9 Standard:

INFORM EVALUATOR THAT THE TASK Operator informs evaluator that the task is HAS BEEN COMPLETED.

completed.

Cue: None Comments: DO NOT PROMPT!

I Standard:

Operator completes EMERGENCY SYSTEMS section, and identifies the following discrepancies.

1. #11 Core Spray pump light indication for 152-505 is out. Notifies CRS.

2. RCIC Flow Controller in manual and notifies CRS Cue: When notified for each of the above discrepancies, Inform the candidate that the applicable system is INOP and the problem will be investigated.

When asked:

"A" EFT in service "B" in Auto/Standby 8N11 is closed Comments:

Simulator does not model EFT System.

8N1 1 indication is not available in the Control Room.

Comment: Candidate must identify both discrepancies.

3MONTICELLO NUCLEAR GENERATING PLANT JPM-3139-001 TITLE:

CONTROL ROOM PANEL WALKDOWN Revision 0 Page 5 of 5 4

CANDIDATES COPY Initial Conditions:

The time is 1800. The plant is operating at 100% power with all equipment operating as expected.

As the BOP operator, you are to walkdown the control room panels and complete page

1 of the CONTROL ROOM SHIFT TURNOVER CHECKLIST, Form 3139 and identify any discrepancies discovered during the panel walkdown INFORM THE EVALUATOR WHEN YOU HAVE COMPLETED THE TASK!!

MONTICELLO NUCLEAR GENERATING PLANT JPM-0000-B-001 TITLE:

DAILY JET PUMP OPERABILITY Revision 0 Page 1 of 10 JOB PERFORMANCE MEASURE SRO:

SRO/RO:

X SRO/RO/NLO:

NLO:

Plant

Reference:

0000-B, Test 0133, Rev. 83 Task Standard:

Perform the Daily Jet Pump Operability test.

K/A

Reference:

Generic Task No.:

2.2.12 Rating RO/SRO:

3.0/3.4 Recent Events:

None Probabilistic Risk Assessment Human Error:

None Monticello Specific Task List

Reference:

CR202.101 METHOD OF TESTING TIME FOR COMPLETION Estimated Time to Complete:

15 min.

Simulator:

X Normal:

Maximum Time to Complete:

25 min.

Alternate X

In-Plant:

Path:

Time Critical:

Yes X

No Prepared By:

W Date:

Reviewed By:

Date:

Shift Supv/Shift Mgr Review By:

4 Date:

/, X0.

Approved By:

yz

"/

Date:

-:., ko.

MONTICELLO NUCLEAR GENERATING PLANT JPM-0000-B-001 TITLE:

DAILY JET PUMP OPERABILITY Revision 0 Page 2 of 10 JPM SET-UP Simulator Setup:

100% power lOS Meter 2-184-23A to indicate 3200 volts lOS Meter 2-184-23B to indicate 3400 volts Place a clean set of Operations Daily Log, parts: A, B, D, E, H, G, J, on a clip board.

A Copy of 0000-B, Step 6 with the values for Raw dp filled in for both Loop A and B.

Place simulator in 'RUN" for 15 minutes prior to exam to allow SPDS to update Core Thermal Power.

Initial Conditions:

The plant is operating at 100% power with all systems operating as expected.

Initiating Cues:

You have been directed to perform the Daily Jet Pump Operability Test per 0000-B, "Operations Daily Log-Part B", Test 0133.

MONTICELLO NUCLEAR GENERATING PLANT JPM-0000-B-001 TITLE:

DAILY JET PUMP OPERABILITY Revision 0 Page 3 of 10 PERFORMANCE INFORMATION Performance Objective<

Stand~ard :

STEP 1 Standard: Locates appropriate procedure.

Locates procedure 0000-B, "Operations Daily Cue: None Log-Part B", Test 0133.

Comments: None STEP 2 "C"

(Procedure Step 4)

Standard:

IF the Reactor is in Run, Records the following values in the matrices AND there is recirculation flow, THEN obtain and record the values for the RVP501 99.7%

item described in the matrices below and 0 SI-2-184-16A 82.2%

perform the following:

SI-2-184-16B 82.0%

FI-2-159A 25.5 gpm 0 FI-2-159B 25.7-gpm FI-2-3-92B 25.5 MIbm/hr FI-2-3-92A 25.5 Mlbm/hr (25.5/28.8) X 100 =

88.5%

(25.5/28.8) X 100 =

88.5%

88.5/82.2 =

1.076 88.5/82.2 =

1.076 Cue: None Comments: None STEP 3 "C"

(Procedure Step 4.a)

Standard:

On Figure 17, Recirculation Pump Flow vs Checks "YES" to Answer Questions 1 and 2 Speed, of Ops Man B.01.04-06 (REACTOR RECIRCULATION SYSTEM - FIGURES)

Cue: None plot points for values of variables A vs C and variables B vs D.

Comments: None

1) Does point for A vs C fall in ACCEPTABLE RANGE?

Yes No

2) Does point for B vs D fall in ACCEPTABLE RANGE?

Yes No

MONTICELLO NUCLEAR GENERATING PLANT JPM-0000-B-001 TITLE:

DAILY JET PUMP OPERABILITY Revision 0 Page 4 of 10

- I

*- -Y

-

1--------

PerformanceObjective STEP 4 "C" (Procedure Step 4.b)

Standard:

On Figure 15 Loop A: Jet Pump Loop Checks "YES" to Answer Question Flow/Pump Speed, of Ops Man B.01.04-06 plot point for value of variables J vs A.

Cue: None

1) Does point for J vs A fall in Comments: None ACCEPTABLE RANGE?

Yes No STEP 5 "C"

(Procedure Step 4.c)

Standard:

On Figure 16 Loop B: Jet Pump Loop Checks "YES" to Answer Question Flow/Pump Speed, of Ops Man B.01.04-06 plot point for value of variables K vs B.

Cue: None

2) Does point for K vs B fall in Comments: None ACCEPTABLE RANGE?

Yes No STEP 6 (Procedure Step 4.d)

Standard: None IF any question is checked No, Cue: None THEN notify Shift Supervisor, AND perform Procedure 0442 (SPECIAL Comments: All questions weret checked Yes.

JET PUMP OPERABILITY TEST).

STEP 7 "C"

(Procedure Step 5.a)

Standard:

IF the Reactor is in Run, Records the following:

AND there is recirculation flow, THEN perform the following:

14.1 psid

a. From FPR-2-3-95 (C-04), Core dP Red Cue: None Pen, record dP:

Comments: None STEP 8 "C"

(Procedure Step 5.b)

Standard:

b. Record the square root of Core dP (from Records square root of dP.

a. above): =

3.75 Cue: None Comments: None

MONTICELLO NUCLEAR GENERATING PLANT JPM-0000-B-001 TITLE:

DAILY JET PUMP OPERABILITY Revision 0 Page 5 of 10

[

-.

rerrormance&iniecruve

-

STEP 9 "C"

(Procedure Step 5.c)

Standard:

c. From CRT mimic obtain and record Core Records Core Flow Flow:

x 106 lb/hr

51.7 Cue: None Comments: None STEP 10 "C" (Procedure Step 5.d)

Standard:

Calculate and record 100 x (c.+57.6x10 6 Calculates and records % rated Core Flow lb/hr):' =

% rated Core Flow

89.756%

Cue: None Comments: None STEP 11 "C" (Procedure Step 5.e)

Standard:

On Figure 20 Core Plate dP vs Core Flow, of Checks "YES" to Answer Question Ops Man B.01.04-06 plot point for value of b.

vs d. above.

Cue: None

1) Does point for b. vs d. fall in Comments: None ACCEPTABLE RANGE?

Yes No

2) IF No, THEN notify Shift Supervision to determine actions and notifications.

MONTICELLO NUCLEAR GENERATING PLANT JPM-0000-B-001 TITLE:

DAILY JET PUMP OPERABILITY Revision 0 Page 6 of 10 L-Performance Obje6tiv'e,%

- I Standard STEP 12 "C" (Procedure Step 6.a)

IF the Reactor is in Run, AND there is recirculation flow, THEN From FR-7288, JET PUMP FLOW RECORDER (Panel C-38), record individual Jet Pump and loop average dPs in the matrix below and perform the following:

a. For each loop divide each individual Jet Pump raw dP by its Loop Average dP and record in matrix.

Standard:

Records individual Jet Pump and loop average dPs, and performs action in step 6a 0

0 Loop "A" average = 8.12 Loop "B" average = 8.02 0

Cue:

Here are the current Jet Pump Raw dp readings.

Comments:

The data for Jet Pump Raw dp is not available on the simulator. When candidate explains to evaluator that these readings are in Cable Spreading, THEN provide copy of the jet pump raw dD values.

STEP 13 (Procedure Step 6.b)

Standard:

b. IF acceptance criteria is not met for any Performs action in step 6b.and determines dP/Loop Average, acceptance Criteria is met THEN notify the Shift Supervision to determine actions and notifications.

Cue: None Comments: None

MONTICELLO NUCLEAR GENERATING PLANT JPM-0000-B-001 TITLE:

DAILY JET PUMP OPERABILITY Revision 0 Page 7 of 10

Pqrforn1arice Ooj6tive~r

~

Standard K STEP 14 (Procedure Step 6.c)

Standard

c. During reactor startup with recirc pump Candidate determines step 6c is not speed <60%, data gathered may not meet applicable.

acceptance criteria due to systematic instrument errors at low flow. If this occurs, Cue: None the jet pump dP SHALL be monitored and evaluated every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months until such time as Comments: Recirc pump speed is > 60%.

evaluation at the higher pump speed is made. Complete test 0442 (SPECIAL JET PUMP OPERABILITY TEST) and notify System Engineer for evaluation of this condition.

STEP 15 "C"

(Procedure Step 7.a & b) Standard:

IF the Reactor is in Run, Records Pump Volts for both pumps as AND Recirc Pump speed (SI-2-184-16A&B follows:

on C-04) >50%,

THEN perform the following:

2-184-23A 3200 0 2-184-23B 3400

a. Record 2-184-23A (C-04), A Pump Volts, indication:

Volts Cue: None

b. Record 2-184-23B (C-04), B Pump Volts, Comments: None indication:

Volts STEP 16 "C"

(Procedure Step 7.c & d) Standard:

c. Record SI-2-184-16A, Recirc Pump 11 %

Records Recirc Pump speed as follows:

Speed, indication:

SI-2-184-16A 82.5

d. Record SI-2-184-16B, Recirc Pump 12 %

0 SI-2-184-16B 82.2 Speed, indication:

Cue: None Comments: None STEP 17 "C"

(Procedure Step 7.e)

Standard:

e. Record result of a. + c.:

Records result of a. - c.

=

_Volts/%

Speed for 11 (37.5 -40.5) 38.78 Cue: None Comments: None

MONTICELLO NUCLEAR GENERATING PLANT JPM-0000-B-001 TITLE:

DAILY JET PUMP OPERABILITY Revision 0 Page 8 of 10 SPeiformance O bjective Standard

~2 STEP 18 "C"

(Procedure Step 7.f)

Standard:

f. Record result of b. + d.:

Records result of b. - d.

=

_Volts/%

Speed for 12 (35.5-38.5)

41.36 Cue: None Comments: None STEP 19 "C"

(Procedure Step 7.g)

Standard:

g. IF either acceptance criteria is not met, Determines the following:

THEN on Panel C-21 from TR-2-184-26,

Acceptance criteria for #11 Recirc RECIRC MG SET WINDING TEMP, and pump is met.

TR-2-2-31, RECIRC PUMP AND MTR 9 Acceptance criteria for #12 Recirc TEMP, verify MG Set generator and pump is not met.

Recirc pump motor winding temperatures And then monitors Panel C-21 from TR-2 are normal and not unexpectedly trending 184-26, RECIRC MG SET WINDING TEMP, up, and TR-2-2-31, RECIRC PUMP AND MTR AND notify Shift Supervision to determine TEMP, to verify #12 MG Set generator and actions and notifications.

12 Recirc pump motor winding temperatures are normal and not unexpectedly trending up, and notifies Shift Supervision.

Cue: Acknowledge Shift Supervision notification.

Comments: Temperatures are normal STEP 20 (Procedure Step 7.h)

Standard: None IF the value in e. or f. above is > 41 Volts/%

Notifies system engineer that Operations

Speed, Daily Log Part 0000-B step 7f, is greater than THEN notify the System Engineer.

41 Volts/%speed.

Cue: None Comments: None

MONTICELLO NUCLEAR GENERATING PLANT JPM-0000-B-001 TITLE:

DAILY JET PUMP OPERABILITY Revision 0 Page 9 of 10 Performance Objctive S~tandard~

STEP 21 Standard:

INFORM EVALUATOR THAT THE TASK Operator informs evaluator that the task is HAS BEEN COMPLETED.

completed.

Cue: None Comments: DO NOT PROMPTI

MONTICELLO NUCLEAR GENERATING PLANT JPM-0000-B-001 TITLE:

DAILY JET PUMP OPERABILITY Revision 0

-1 Page 10 of 10 CANDIDATES COPY Initial Conditions:

The plant is operating at 100% power with all systems operating as expected.

You have been directed to perform the Daily Jet Pump Operability Test per 0000-B, "Operations Daily Log-Part B", Test 0133.

INFORM THEVALiJATOR WHEN YOU HAVE COMPLETED THEIASKUII

MONTICELLO NUCLEAR GENERATING PLANT JPM-AWI-08.04.01-002 TITLE:

EXPECTED DOSE DETERMINATION TO INSPECT Revision 0 EUPE Paae 1 of 5 fl~ JOB P~ERFORMANCEMESR SRO:

SRO/RO:

SRO/RO/NLO:

X NLO:

Plant

Reference:

4 AWI-08.04.01, Rev. 12 Task Standard:

Calculate Expected Dose to Inspect Equipment K/A

Reference:

Generic Task No.:

2.3.4 Rating RO/SRO:

2.5/3.1 Recent Events:

None Probabilistic Risk Assessment Human Error:

None Monticello Specific Task List

Reference:

NL299.107 NL299.128 METHOD OF TESTING TIME FOR COMPLETION Estimated Time to Complete:

15 min.

Simulator:

X Normal:

X Maximum Time to Complete:

20 min.

Alternate In-Plant:

Path:

Time Critical:

Yes -

X No Prepared By:

Date:/ 6 Reviewed By:

Date:

Shift Supv/Shift Mgr Review By:

Date:

Id Approved By:

/..,

Date:

-I.

/

MONTICELLO NUCLEAR GENERATING PLANT JPM-AWI-08.04.01-002 TITLE:

EXPECTED DOSE DETERMINATION TO INSPECT Revision 0 EQUIPMENT

.s Page 2 of 5 JPM SET-UP..

Simulator Setup:

Calculator Initial Conditions:

The plant is operating at 100% power.

Initiating Cues:

An inadvertent Group III caused a water hammer requiring the pipe supports and hangers to be inspected for possible damage. You have been requested to inspect the piping for #12 RWCU Pump (highlighted in red) that runs along the shield wall below RWCU MO-2398. Some climbing is anticipated and the estimated time to complete this task is 15 minutes.

Determine the expected dose you would receive while completing this task, class of protective clothing to wear, and what additional actions must be taken to gain entry to the area. Vocalize your thought process and report when your task is complete.

MONTICELLO NUCLEAR GENERA TING PLANT JPM-AWI-08.04.01-002 TITLE:

EXPECTED DOSE DETERMINATION TO INSPECT Revision 0 EQUIPMENT Pale 3of 5 PERFORMANCE INFORMATION Perfor-*a*ce-Objctive.

Sta I nda rd STEP 1 Standard:

Locates a copy of the survey map and the Describes location of survey map and Radiation Work Permit (RWP 22).

Radiation Work Permit (RWP 22)

Cue:

When operator describes where survey maps and RWPs are located then provide him with a copy of the appropriate survey map and RWP.

Comments:

Survey maps and RWPs are located on the basement level of the administration building in the same area where personnel obtain their ALANOR.

STEP 2 Standard:

Determine the Dose Rate near the Dose Rate determined to be 440 mrem/hr.

component.

Cue: None Comments: None STEP 3 "C" Standard:

Calculates expected dose.

Expected dose calculated to be 110 mrem Cue: None Comments:None STEP 4 Standard:

Determines that component is located in a Determines that the component is in a LHRA "Locked High Radiation Area (LHRA).

and a key is required for entry to the room.

(Non-critical step)

Cue: None

[

Comments: None

MONTICELLO NUCLEAR GENERATING PLANT JPM-AWI-08.04.01-002 TITLE:

EXPECTED DOSE DETERMINATION TO INSPECT Revision 0 EQUIPMENT S~Page 4 of 5 Performance Objective

.Standard 7

STEP 5 "C" Standard:

Determines the requirements for entering a Determines that:

"Locked High Radiation Area (LHRA).

Required to notify Rad Prot Coordinator

"* Requires a Dose Rate Meter

", Requires Class 2 protective clothing Cue: None Comments: None STEP 6 Standard:

INFORM EVALUATOR THAT THE TASK Operator informs evaluator that the task is HAS BEEN COMPLETED.

completed.

Cue: None Comments: DO NOT PROMPT!

MONTICELLO NUCLEAR GENERATING PLANT JPM-AWI-08.04.01-002 TITLE:

EXPECTED DOSE DETERMINATION TO INSPECT Revision 0 EQUIPMENT P

~Page 5of 5 CANDIDATES COPY Initial Conditions:

The plant is operating at 100% power.

An inadvertent Group III caused a water hammer requiring the pipe supports and hangers to be inspected for possible damage. You have been requested to inspect the piping for

12 RWCU Pump (highlighted in red) that runs along the shield wall below RWCU MO 2398. Some climbing is anticipated and the estimated time to complete this task is 15 minutes.

Determine the expected dose you would receive while completing this task, class of protective clothing to wear, and what additional actions must be taken to gain entry to the area. Vocalize your thought process and report when your task is complete.

MONTICELLO NUCLEAR GENERATING PLANT JPM-A.3 - 001 TITLE:

DON FIRE FIGHTING PROTECTION GEAR Revision 0 Page 1 of 5 SRO:

SRO/RO:

X SRO/RO/NLO:

NLO:

Plant

Reference:

R7637L-003 Task Standard:

Don Fire Fighting Protection Gear K/A

Reference:

Generic Task No.:

2.4.26 Rating RO/SRO:

2.9/3.3 Recent Events:

None Probabilistic Risk Assessment Human Error:

None Monticello Specific Task List

Reference:

FB006.001 METHOD OF TESTING TIME FOR COMPLETION Estimated Time to Complete:

8 min.

Simulator:

Normal:

X Maximum Time to Complete:

15 min.

X Alternate In-Plant:

Path:

Time Critical:

Yes X

No Prepared By:

,/i Date:

Reviewed By:

Date:

Shift Supv/Shift Mgr Review By:

Date: 0 7 Approved By:

TZ./

Date:

"3" ({7 0Z

/

I MONTICELLO NUCLEAR GENERATING PLANT JPM-A.3 - 001 TITLE:

DON FIRE FIGHTING PROTECTION GEAR Revision 0 Page 2 of 5 Simulator Setup:

Not Applicable Initial Conditions:

The following announcement has just been given over the plant page:

"Attention all plant personnel, a fire has been reported in the Hot Machine Shop Lube Oil Storage Tank area, this is a Class B fire, Fire Brigade members report to the fire brigade room".

Initiating Cues:

You are to report to the fire brigade room and don the appropriate fire fighting protection gear.

MONTICELLO NUCLEAR GENERATING PLANT JPM-A.3 - 001 TITLE:

DON FIRE FIGHTING PROTECTION GEAR Revision 0 Page 3 of 5 PERFORMANCE INFORMATION

-.~ Perfoirm'ance 04jective~}Ij

Standard

~

STEP 1 Standard:

Locates fire brigade room Proceeds to the fire brigade room.

Cue: None Comments: None STEP 2 Standard:

Selects appropriate clothing:

Locates and selects appropriate clothing

"* Boots

"* Bunker Pants Cue: None

"* Coat

"* Gloves Comments: None

"* NOMAX Hood

"* Helmet STEP 3 "C" Standard:

Dons the following protective clothing:

"* Bunker Pants

1. Bunker Pants

"* Boots

2. Boots

"* Coat

2. Coat

"* NOMAX Hood

2. NOMAX Hood Cue: None Comments: Bunker pants must be put on prior to the coat.

MONTICELLO NUCLEAR GENERATING PLANT JPM-A.3 - 001 TITLE:

DON FIRE FIGHTING PROTECTION GEAR Revision 0 Page 4 of 5 SE4"CPerformance Objective I-tanad Standard STEP 4 "C" Standard:

Don Scott Air Pack

1. Removes protective cover from Scott Air Pack

2. Inspects Scott Air Pack and hoses for damage and proper air pressure (2100 psig)

3. Places arms through harness

4. Buckles waist belt

5. Tightens shoulder and waist belt straps

6. Dons face mask and tightens/adjusts straps

7. Performs negative pressure test to prove adequate mask seal.

Cue: Do not valve in air or hook up the mask to the regulator on the Scott Air Pack Comments: None Performan~ceObjoctive~

Standard STEP 5 "C" Standard Dons helmet and gloves Dons the rest of fire fighting gear

"* Gloves Cue: None

"* Helmet Comments: None STEP 6 Standard:

INFORM EVALUATOR THAT THE TASK Operator informs evaluator that the task is HAS BEEN COMPLETED.

completed.

Cue: None Comments: DO NOT PROMPT!

MONTICELLO NUCLEAR GENERATING PLANT JPM-A.3 - 001 TITLE:

DON FIRE FIGHTING PROTECTION GEAR Revision 0 Page 5 of 5 LINFORM 'THE EVALUATOR WHEN YOU HAVE COMPLETED THE TASK!'!

CANDIDATES COPY Initial Conditions:

The following announcement has just been given over the plant page:

"Attention all plant personnel, a fire has been reported in the Hot Machine shop Lube Oil Storage Tank area, this is a Class B fire, Fire Brigade members report to the fire brigade room".

You are to report to the fire brigade room and don the appropriate fire fighting protection gear.

ML030410042

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