ML030410071

Initial Submittal of the Walkthrough Jpms for the Monticello Initial Examination - Oct. 2002

ML030410071
Person / Time
Site:	Monticello
Issue date:	11/21/2002
From:	Lanksbury R Division of Reactor Safety III
To:	Forbes J Nuclear Management Co
References
50-263/02-301 50-263/02-301
Download: ML030410071 (67)

Text

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

MONTICELLO NUCLEAR GENERATING PLANT JPM-B.01-.03-006 TITLE: CRD OPERABILITY Revision 8a Page 1 of 8

'JOB PERFO.RMANCE MIEAS.URE SRO: SRO/RO: X SRO/RO/NLO: NLO:

Plant

Reference:

Procedure No. 0074, Rev 30; B.01.03-05.H.4, Rev 14 Task Standard: Perform Weekly Control Rod Drive Exercise No. 0074 K/A

Reference:

201003 Task No: A2.01 Rating RO/SRO: 3.4/3.6 A4.02 3.5/3.5 Recent Events: RE: 92-069, Control Rod 26-27 double notched in and had slow withdrawal time.

Probabilistic Risk Assessment Human Error: None Monticello Specific Task List

Reference:

CR201.101 METHOD OF TESTING TIME FOR COMPLETION Estimated Time to Complete: 10 Min Simulator: X Normal:

Alternate Maximum Time to Complete: 30 Min In-Plant: Path: X Time Critical: Yes X No Prepared By: 1 ,_ Date: e(4,/OZ Reviewed By: "* Date:.

Shift Supv/Shift Mgr Review By: Date: , 7 161 Approved By: 6/s * (SuptOpsTrng) Date: 02-FO ADifISRDATIVEUSEOiLQ 3087 (DOCUMENT CHANGE, HOLD, AND COMMENT FORM) incorporated:

Resp Supv: OTRNG IAssoc Ref: MTCP-03.32 1SR: N TFreq: 0 Vrs ARMS: JPM-B.01.03-006 IDoc Type: 8505 1Admin Initials: Date:

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MONTICELLO NUCLEAR GENERATING PLANT JPM-B.01.03-006 TITLE: CRD OPERABILITY Revision 8aI Page 2 of 8 SJPM SET-UP Simulator Setup:

Initialize to any ICwhich places the reactor at 100% power and the CRD system oper able.

Enter Malfunction CH02 for Control Rod 02-31 on Remote Trigger 1 to prevent the first rod from being withdrawn after it is inserted one notch. Be prepared to remove the malfunction while STEP 6 is being performed.

Obtain a Control Rod Position printout from the Process Computer and place on C-05.

Have Control Room Log accessible.

Fill out 0074 as follows:

• Write in Comments, "Perform PART A, Steps 3-8, for CRDs 02-31, 02-27, 02-23 for training."

• Reason for Performing: Other X

• Initial prerequisites.

0 N/A all CRDs on pagel2 except the first three.

Initial Conditions:

The plant is at 100% power.

The Control Room Supervisor directs you to perform the Weekly Control Rod Drive Exercise No. 0074 for the first three rods only, using the current rod position printout at the operator console. Steps 1 and 2 have been completed.

Initiating Cues:

The Control Room Supervisor directs you to perform the Weekly Control Rod Drive Exercise No. 0074 for the first three rods only, using the current rod position printout at the operator console. Steps 1 and 2 have been completed.

Provide the operator a copy of Procedure 0074.

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MONTICELLO NUCLEAR GENERATING PLANT JPM-B.01 .03-006 TITLE: CRD OPERABILITY Revision 8a Page 3 of 8 PERFORMANCE INFORMATION subsequent tries, rod selects Comments: None but spurious alarms are received) SHALL be considered abnormal conditions and recorded in Table 2, Control Rod Exercise Abnormalities.

Select a withdrawn or partially withdrawn control rod by depressing the appropriate rod select pushbutton.

Verify that the selected rod select pushbutton is illuminated and the selected rod indicates selection on the full-core display.

STEP 2 "C" (Procedure STEP 4) Standard:

CAUTION: Operator inserts the selected control rod one PCRAT should be below the value notch position by placing Rod Movement Control indicated in PREREQUISITE 1 to switch 3A-S2 to the ROD IN position, releases the perform STEPS 4 and 5 on partially switch.

withdrawn rods. Cue:

Insert the selected rod one notchtand If asked by the candidate or if candidate refers to verify the rod position indication for the the computer, PCRAT indicates 0.986.

selected control rod in the single rod and Operator should observe the following:

the four rod group display changes to the next lower latched position. Rod position indication changes to the next lower position on the single-rod and four rod group.

Cue:

If the operator looks at the computer printer, tell them the rod moved from 48 to 46.

Comments:

1. Insert Malfunction on Remote No. 1 after the rod is inserted but before the next step.

2. The simulator computer does not print out each CRD change.

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MONTICELLO NUCLEAR GENERATING PLANT JJPM-B.01 .03-006 TITLE: CRD OPERABILITY Revision 8a Page 4 of 8 Performance Objective Standard STEP 3 "C" (Procedure STEP 5) Standard:

NOTE: The RWM uses the Rod Operator attempts to withdraw the selected Select and Drive signal to control rod one notch position by placing Rod detect completion of the rod Movement Control Switch 3A-S2 to the ROD OUT motion cycle. Because this NOTCH position, releases the switch.

signal does not always drop (Non-Critical portion of Standard) out long enough for the RWM to detect completion of the Operator should observe the following:

rod motion, allow enough 1. Rod position indication does not change to time for the settle cycle to the next higher position on the single-rod and occur to ensure that all the four rod display, as rod withdrawal is control properly.rods are logged attempted.

temtd Cue:

None Withdraw the selected rod one notch and verify the rod position indication for Comments: None the selected control rod in the single rod NOTE: Operator may attempt to reposition and the four rod group display changes control rod a second time.

to the next higher latched position.

STEP 4 (Procedure STEP 6) Standard: None After completion of the first control rod, Cue: None verify computer acknowledgment of the Comments: None rod's change in position. (Alarm typer print-out of rod identification and position changes.)

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MONTICELLO NUCLEAR GENERATING PLANT JPM-B.01 .03-006 TITLE: CRD OPERABILITY Revision 8a Page 5 of 8 Performance Objective Standard STEP 5 "C" (Procedure Step 7) Standard:

NOTE: For the purposes of this Operator should notify the Control Room procedure, drives which Supervisor of the failure of the control rod to require drive pressure move.

greater than 265 psid to (Non-Critical portion of Standard) insert or withdraw, all occurrences of double Records the abnormal indication in Control Room notching, and unusually fast, Log and on Table 2, Control Rod Exercise slow, or erratic drive speeds, Abnormalities.

SHALL be considered an Cue:

abnormal condition. See BASES. The Control Room Supervisor has notified the Nuclear Engineer, and directs the operator to IF an abnormal condition is detected as attempt withdrawal of the CRD using higher drive a result of exercising a rod, pressure per approved procedures.

THEN notify the Control Room Comments: None Supervisor, AND record what the abnormality was (i.e., Double Notch insert, Double Notch withdraw, increase drive pressure to

__E__psi) on Table 2 Control Rod Exercise Abnormalities.

STEP 6 (B.01.03-05.H.4) Standard:

Locates Procedure B.01.03-05.H.4 Locates correct procedure.

(WITHDRAWAL OF A CRD UNDER Cue: None HIGH DRIVE PRESSURE).

Comments: None l/cmb

MONTICELLO NUCLEAR GENERATING PLANT JPM-B.01.03-006 TITLE: CRD OPERABILITY Revision 8a Page 6 of 8 Performance Objective Standard STEP 7 "C" (B.01.03-05.H.4, Standard:

STEP 1) Increases drive water pressure, and attempts to GENERAL NOTE: This procedure withdraw the rod WITHOUT EXCEEDING 400 may be psid. Does not attempt to insert the rod with terminated at any increased drive pressure.

step when CRD (Non-Critical portion of Standard) withdrawal is accomplished. Attempts to withdraw the rod every 30 psid increase in pressure.

NOTE: STEPs 1, 2, and 3 may be Cue: None performed in any order. Comments:

Perform the following: Cue Simulator Operator to clear malfunction after

a. Raise drive water pressure in 2 drive water pressure increases.

increments up to 30 psid, to a maximum of 400 psid and give the drive a withdraw signal after each increment.

b. IF data is not recorded per procedure 0074, THEN leave a message for CRD System Engineer including CRD location and drive pressure required for withdrawal.

c. Before moving a different CRD, return drive water pressure to approximately 265 psid.

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MONTICELLO NUCLEAR GENERATING PLANT JPM-B.01.03-006 TITLE: CRD OPERABILITY Revision 8a Page 7 of 8 Performance Objective Standard STEP 8 "C" (B.01.03-05.H.4, Standard:

STEP 2) Operator gives a rapid series of insert and IF the drive does not unlatch, withdraw signals, then gives the drive a withdraw THEN perform the following: signal. Returns the rod to its pre-exercise

a. Hold the Notch Override Switch position.

in the NOTCH OVERRIDE (Non-Critical portion of Standard)

Position. Exits the B.01.03 procedure per the General Note.

b. Hold the Rod Movement Control Switch in the ROD OUT Documents Table 2 Control Rod Exercise Position. Abnormalities.

c. Give the drive a rapid series of Cue: None emergency ROD IN and NOTCH Comments:

OVERRIDE signals with the rod NOTCH OVERRIDE Switch. Remove the malfunction to allow the rod to move.

STEP 9 "C" (Procedure STEP 8) Standard:

Acknowledge completion of the rod Operator initials the appropriate blank on the exercise on Table 1. Control Rod Exercise Data Sheet after the rod is returned to its original position.

Cue:

PRE-APPROVED PROMPT:

Inform the operator that the JPM has been completed.

Comments:

End the JPM without withdrawing the other two control rods.

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MONTICELLO NUCLEAR GENERATING PLANT JPM-B.01.03-006 TITLE: CRD OPERABILITY Revision 8a Page 8 of 8 CANDIDATES COPY Initial Conditions:

The plant is at 100% power.

The Control Room Supervisor directs you to perform the Weekly Control Rod Drive Exercise No. 0074 for the first three rods only, using the current rod position printout at the operator console. Steps 1 and 2 have been completed.

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

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ITITLE:

MONTICELLO NUCLEAR GENERATING PLANT ISOLATE CORE SPRAY LOOP A JPM-B.03.01-002 Revision 5a Page 1 of 5 I

JOB PERFORMANCE MEASURE SRO: SRO/RO: X SRO/RO/NLO: NLO:

Plant

Reference:

B.3.1-05.E.2, Rev 11 Task Standard: Isolate Core Spray Loop A K/A

Reference:

209001 Task No: A4.03 Rating RO/SRO: 3.7/3.6 Recent Events: None Probabilistic Risk Assessment Human Error: None Monticello Specific Task List

Reference:

CR209.108 METHOD OF TESTING TIME FOR COMPLETION Estimated Time to Complete: 5 Min Simulator: X Normal: X Alternate Maximum Time to Complete: 10 Min In-Plant: Path:

Time Critical: Yes X No Prepared By: Date:

Reviewed By: Date:

Shift Supv/Shift Mgr Review By: ) 1 *{4j Date: -7A f o Approved By: (Supt Ops Trng) Date: -t., o -_

3087 (DOCUMENT CHANGE, HOLD, AND COMMENT FORM) incorporated:

Resp Supv: OTRNG Assoc Ref: MTCP-03.32 ISR: N Freq: 0 yrs ARMS: JPM-B.03.01-002 Doc Type: 8505 Admin Initials: Date:

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MONTICELLO NUCLEAR GENERATING PLANT JPM-B.03.01-002 TITLE: ISOLATE CORE SPRAY LOOP A Revision 5a Page 2 of 5 JPM SET-UP Plant Setup:

Initialize to any IC that places the plant at 100% power with the Core Spray System operable.

Initial Conditions:

The plant is at 100% power. No. 11 Core Spray pump failed to start during the performance of an operability test.

Initiating Cues:

The Control Room Supv directs you to isolate Core Spray Loop "A"per the operations manual.

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MONTICELLO NUCLEAR GENERATING PLANT JPM-B.03.01-002 TITLE: ISOLATE CORE SPRAY LOOP A Revision 5a Page 3 of 5 PERFORMANCE INFORMATION Performance Objective Standard STEP 1 Standard:

Locate procedure B.03.01-05.E.2. (11 Locates appropriate procedure.

Core Spray Loop Isolation). Cue: None Comments: None STEP 2 "C" (Procedure STEP 1) Standard:

NOTE: The following steps may be Places 11 CS pump control switch 14A-S5A, in performed in any order. PULL-TO-LOCK.

Place 14A-S5A, 11 Core Spray Pump, (Non-Critical portion of Standard) control switch (Panel C-03) in PULL-TO- Operator should observe that annunciator LOCK position. C03-A-14, CORE SPRAY PUMP 11 OL/MAN-OVRD alarms.

Cue: None Comments: None STEP 3 (Procedure STEP 2) Standard:

CLOSE MO-1753 using 14A-SIA, Verifies MO-1753 is closed by observing that the MO-1 753 Div I CS Injection Inboard, green position indication is lit.

control switch. Cue: None Comments:

MO-1 753 is normally closed.

STEP 4 "C" (Procedure STEP 3) Standard:

Place 14A-S16A, MO-1751 Div I CS 1. Places MO-1 751 CS INJ. OTBD BYP switch Injection Bypass, keylocked switch in 14A-S16A in BYPASS, BYPASS position, AND AND CLOSE MO-1751 using 14A-S2A, 2. Closes MO-1751 using HS-14A-S2A.

MO-1751 Div I CS Injection Outboard, control switch. (Non-Critical portion of Standard)

Operator should observe the following:

1. C03-A-47, CORE SPRAY ISOL VLV 1751 BYPASS alarms.

2. Valve position indication changes from red to green.

Cue: None Comments: None I/cmb

MONTICELLO NUCLEAR GENERATING PLANT JPM-B.03.01-002 TITLE: ISOLATE CORE SPRAY LOOP A Revision 5a Page 4 of 5 Performance Objective Standard STEP 5 (Procedure STEP 4) Standard:

Declare 11 Core Spray inoperable. Operator informs Shift Supv that 11 Core Spray is inoperable.

Cue: None Comments:

Operator may/may not log Core Spray inoperable in Simulator Control Room Log.

STEP 6 Standard:

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

Cue: None Comments: DO NOT PROMPT! -

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MONTICELLO NUCLEAR GENERATING PLANT JPM-B.03.01-002 TITLE: ISOLATE CORE SPRAY LOOP A Revision 5a Page 5 of 5

.CANDIDATES COPY Initial Conditions:

The plant is at 100% power. No. 11 Core Spray pump failed to start during the performance of an operability test.

The Control Room Supv directs you to isolate Core Spray Loop "A" per the operations manual.

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

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MONTICELLO NUCLEAR GENERATING PLANT JPM-B.02.04-003 TITLE: MSIV EXERCISE TEST Revision 7a Page 1 of 7 JOB PERFORMANCE MEASURE SRO: SRO/RO: X SRO/RO/NLO: NLO:

Plant

Reference:

Test No. 0160-A, Rev. 2 Task Standard: Perform MSIV Exercise Test No. 0160-A K/A

Reference:

2.1 Conduct of Operations Task No: 2.1.23 Rating RO/SRO: 3.9/4.0 239001 A4.01 4.2/4.0 Recent Events: None Probabilistic Risk Assessment Human Error: None Monticello Specific Task List

Reference:

CR240.101 METHOD OF TESTING TIME FOR COMPLETION Estimated Time to Complete: 5 Min Simulator: X Normal:

Alternate Maximum Time to Complete: 15 Min In-Plant: Path: X Time Critical: Yes X No Prepared By: Date: ,/a'/o Reviewed By: Date:

Shift Supv/Shift Mgr Review By: g Date: '7/o//d Approved By: (Supt Ops Trng) Date: -, 73 .2_

, TI I-FOR ADMINISTRATIVE USE ONLYrr kflR7 tflflriiMFT r."AIrZP(~ i-4nI n Amn~ ry)KANAPwT PflPKA) inrjr',-rnfnr~ti-F Resp Supv: OTRNG lAssoc Ref: MTCP-03.32 SR: N Freq: 0 yrs ARMS: JPM-B.02.04-003 Doc Type: 8505 Admin Initials: Date:

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MONTICELLO NUCLEAR GENERATING PLANT JPM-B.02.04-003 TITLE: MSIV EXERCISE TEST Revision 7a Page 2 of 7

[, JPM SET-UP i Simulator Setup:

Initialize to any IC with the Reactor at 100% power and all MSIVs open to allow the MSIV Exercise test to be performed. Override the light indications for MSIV AO-2-80A by entering the following lOS's:

DS111-02 Digital value to ON DS1 12-02 Digital value to OFF Fill in Test 0160-A as follows:

• Reason for Performing - Other: X 0 Write in Comments, "Perform STEPS 1 through 4 for AO-2-80A and AO-2-86A only."

0 Initial Prereq 1 stating no other half scram procedures are in progress.

0 Sign Shift Supv approval to commence on cover sheet.

• N/A for all other valves on Table 1 and Table 2.

Initial Conditions:

The plant is operating normally at power. No abnormal conditions exist.

Initiating Cues:

The Control Room Supv directs you to perform MSIV Exercise Test No. 0160-A only on Main Steam Line "A".

Provide the operator with a marked up copy of Test No. 0160-A.

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MONTICELLO NUCLEAR GENERATING PLANT JPM-B.02.04-003 TITLE: MSIV EXERCISE TEST Revision 7a Page 3 of 7 PERFORMANCE INFORMATION SPerformance Objective Standard STEP 1 (Procedure STEP 1) Standard:

GENERAL NOTE: Verifies red lights are ON and green lights are OFF for MSIVs.

MSIV movement is verified by Cue: None sequentially exercising each valve while observing position indication Comments: None and protective relay status.

Verify MSIVs are open by observing that red position indicating lights (Panel C-03) only are ON.

STEP 2 (Procedure STEP 2) Standard:

Station an operator by Control Room Requests operator to be stationed at panels C-1 5 Panels C-15 and C-1 7 to provide status and C-1 7.

of protective relay position during Cue:

performance of subsequent steps.

Operator is at panels C-15 and C-17.

Comments: None STEP 3 "C" (Procedure STEP 3.a) Standard:

CAUTION Depresses and holds pushbutton, notes that the green light doesn't come on and the relays do not A half scram may occur during de-energize. Releases the TEST button BEFORE performance of this step if an RPS full closure of the MSIV and informs Control Room limit switch is currently inoperable or Supervisor of light indication and protection relay becomes inoperable during test. failure.

Perform the following for each inboard Cue:

MSIV, AND document completion of substeps by initialing appropriate boxes (Provide ONLY if relay status is asked for by the in Table 1: operator):

Depress and hold Steam Line Protective relays have not de-energized.

Isolation Test pushbutton (Panel Comments:

C-03) for the respective inboard Reactor scram will not occur with complete MSIV until green indicating light closure of a MSIV. Examinee should identify comes ON or until protective relays failure of the MSIV light indication and protective de-energize. relays to de-energize and notify Control Room Supervisor. Examinee may check light bulb.

Should request CRS permission to retest.

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MONTICELLO NUCLEAR GENERATING PLANT JPM-B.02.04-003 TITLE: MSIV EXERCISE TEST Revision 7a Page 4 of 7 Performance Objective Standard STEP 4 (Procedure STEP 3.b) Standard:

Verify MSIV returns to full open position Verifies that only the red indicating light is on.

by observing that red indicating light only Cue: None is on.

Comments:

Sometime before the end of the JPM the operator should fill in comments for results of test.

STEP 5 "C" Standard:

Notifies Shift Supervisor. Notifies Shift Supv.

Cue:

Shift Supv will notify appropriate personnel, Shift Supv directs the operator to continue with the test procedure.

Comments: None STEP 6 (Procedure STEP 3.c) Standard:

Verify protective relays are energized. Operator verifies the protective relays are energized.

Cue:

Protective relays are energized.

Comments: None STEP 7 (Procedure STEP 3.d) Standard:

IF half scram is received, Operator resets half scram AND notifies the Shift THEN reset using handswitch 5A-$9, Supervisor and Main Steam System Engineer, if Scram Logic Reset, necessary AND notify Shift Supervisor and Main Cue: None Steam System Engineer.

Comments: None I/cmb

MONTICELLO NUCLEAR GENERATING PLANT JPM-B.02.04-003 TITLE: MSIV EXERCISE TEST Revision 7a Page 5 of 7 Performance Objective Standard STEP 8 "C" (Procedure STEP 4.a) Standard:

CAUTION 1 Operator reads supply pressure from computer Opening an outboard MSIV when point AlR1Q0.

main air pressure is initially less than Cue: None 255 psig could cause other open Comments: None outboard MSIVs to drift closed, thereby resulting in a Reactor scram.

CAUTION 2 A half scram may occur during performance of this step if an RPS limit switch is currently inoperable or becomes inoperable during test.

NOTE: Main air supply pressure for outboard MSIVs can be read from computer point AIR100.

Perform the following for each outboard MSIV, AND document completion of substeps by initialing appropriate boxes in Table 2:

Verify main air pressure supply to outboard MSIVs is 255-285 psig.

STEP 9 "C" (Procedure STEP 4.b) Standard:

Depress and hold Steam Line Isolation Depresses and holds pushbutton until green light Test pushbutton (Panel C-03) for the comes on or relays de-energize then releases respective outboard MSIV until green pushbutton.

indicating light comes on, or until Cue:

protective relays de-energize.

(Provide only if relay status is asked for by the operator.)

Protective relays have de-energized.

Comments: None STEP 10 (Procedure STEP 4.c) Standard:

Verify MSIV returns to full open position Verifies that only the red indicating light is on.

by observing that red indicating light only Operator initials Table 2 for AO-2-86A for valve is on. exercised and valve open.

Cue: None Comments: None I/cmb

MONTICELLO NUCLEAR GENERATING PLANT JPM-B.02.04-003 TITLE: MSIV EXERCISE TEST Revision 7a Page 6 of 7 Performance Objective Standard STEP 11 (Procedure STEP 4d) Standard:

Verify protective relays are energized. Operator verifies the protective relays are energized.

Cue:

Protective relays are energized.

Comments: None STEP 12 (Procedure STEP 4.e) Standard: None IF half scram is received, Cue: None THEN reset using handswitch 5A-$9, Comments: None Scram Logic Reset, AND notify Shift Supervisor and Main Steam System Engineer.

STEP 13 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-B.02.04-003 TITLE: MSIV EXERCISE TEST Revision 7a Page 7 of 7 CANDIDATES COPY Initial Conditions:

The plant is operating normally at power. No abnormal conditions exist.

The Control Room Supv directs you to perform MSIV Exercise Test No. 0160-A only on Main Steam Line "A".

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

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MONTICELLO NUCLEAR GENERATING PLANT JPM-B.03.02-05.G.1 TITLE: REACTOR VESSEL PRESSURE CONTROL USING Revision 0 HPCI Page 1 of 7 r MEASURE.NCE.ME.SURE SRO: SRO/RO: X SRO/RO/NLO: NLO:

Plant

Reference:

B.03.02-05, G.1 Part C, Rev. 17 Task Standard: Place HPCI in Service for Controlling Reactor Pressure K/A

Reference:

206000 Task No.: A1.02 Rating RO/SRO: 4.2/4.2 Recent Events: None Probabilistic Risk Assessment Human Error: None Monticello Specific Task List

Reference:

CR206.111 METHOD OF TESTING TIME FOR COMPLETION Estimated Time to Complete: 15 min.

Simulator: X Normal:

Maximum Time to Complete: 20 min.

Alternate In-Plant: Path: X Time Critical: Yes X No Prepared By: J Date:*, ('/O Reviewed By: Date:

Shift Supv/Shift Mgr Review By: pj* 4 _ Date: ,-/7 16 (oz Approved By: ( _ Date: 70z-

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MONTICELLO NUCLEAR GENERATING PLANT JPM-B.03.02-05.G.1 TITLE: REACTOR VESSEL PRESSURE CONTROL USING Revision 0 HPCI Page 2 of 7 JPM SET-UP Simulator Setup: IC-247 Initialize to IC 247 The plant is shutdown following and inadvertent Group I, MSIVs are closed, reactor pressure controlled with Low Low Set, and all available RHR Torus Cooling in service.

lOS alarm 3-B-18 with 15 second time delay Malfunction HP06 stuck open SW relief valve open Initial Conditions:

The plant has experienced a spurious Group 1. All plant actions have occurred as expected. The Low Low Set System is currently controlling reactor pressure from 1052 to 972 psig.

Initiating Cues:

The Control Room Supervisor has requested that you start HPCI for reactor pressure control. Reactor pressure should be controlled between 800 to 1000 psig.

MONTICELLO NUCLEAR GENERATING PLANT JPM-B.03.02-05.G.1 TITLE: REACTOR VESSEL PRESSURE CONTROL USING Revision 0 HPCI Page 3 of 7 PERFORMANCE INFORMATION Performanice Olbjective Standard STEP 1 (Proc. Sect. G, Part A, Step 1) Standard:

IF conditions permit at any time while Recognizes that all available Torus Cooling performing this procedure, is in service.

THEN place RHR in Torus Cooling per Ops Cue: None.

Man B.03.04-05.

Comments: None STEP 2 "C" (Proc. Sect. G, Part A, Step 2) Standard:

IF HPCI is in service Proceeds to PART C THEN proceed to PART B Cue: None Comments: HPCI is in standby.

STEP 3 "C" (Proc. Sect. G, Part A, Step 3) Standard:

IF HPCI is not in service Proceeds to PART C THEN proceed to PART C Cue: None Comments: HPCI is in standby.

STEP 4 "C" (Proc. Sect. G, Part C, Step 7) Standard:

OPEN CV-2065, HPCI Min Flow Valve. Places handswitch for CV-2065 to the OPEN position and observes position indicating lights: red comes on and green goes off.

Cue: None Comments: None

MONTICELLO NUCLEAR GENERATING PLANT JPM-B.03.02-05.G.1 TITLE: REACTOR VESSEL PRESSURE CONTROL USING Revision 0 HPCI Page 4 of 7 Performance Objetive Standard STEP 5 "C" (Proc. Sect. G, Part C, Step 8) Standard:

START HPCI Turbine Gland Seal Condenser Places handswitch for the GLAND SEAL Blower. CONDENSER BLOWER to RUN and observes the red light comes on and the green light goes off.

Cue: None Comments: None STEP 6 "C" (Proc. Sect. G, Part C, Step 9) Standard:

OPEN MO-2071, HPCI Test Return Places handswitch for MO-2071 to the OPEN position and observes position indicating lights: red comes on and green goes off.

Cue: None Comments: None STEP 7 "C" (Proc. Sect. G, Part C, Step 10) Standard:

Set CV-3503, HPCI Test Return Flow, to Adjusts controller to approximately 47%.

approximately 47%.

Cue: None Comments: Bases Step 2: setpoint of 47%

ensures sufficient margin is maintained to ensure that pump discharge overpressure conditions will not occur.

STEP 8 (Proc. Sect. G, Part C, Step 11) Standard:

Verify FIC-23-108, HPCI Pump Flow Control, Verifies that FIC-23-108 is in AUTO and set is in AUTO and set at 87%. at 87%.

Cue: None Comments: None

MONTICELLO NUCLEAR GENERATING PLANT JPM-B.03.02-05.G.1 TITLE: REACTOR VESSEL PRESSURE CONTROL USING Revision 0 HPCI Page 5 of 7 Pierformance Objective Standard STEP 9 "C" (Proc. Sect. G, Part C, Step Standard:

12a)

Places handswitch for AUX OIL PUMP to the Perform the following in quick succession: RUN position and observes indicating lights:

red comes on and green goes off.

a START HPCI Turbine Aux Oil Pump Cue: None Comments: None STEP 10 "C" (Proc. Sect. G, Part C,Stepl2b) Standard:

b. OPEN MO-2036, HPCI Turbine Steam Places handswitch for MO-2036 to the OPEN Supply. position and observes position indicating lights: red comes on and green goes off.

Cue: None Comments: None STEP 11 "C" (Proc. Sect. G Part C,Step 12c) Standard:

c. OPEN MO-2067, HPCI Disch Otbd Places handswitch for MO-2067 to the OPEN Isolation. position and observes position indicating lights: red comes on and green goes off.

Cue: None Comments: None STEP 12 Standard:

As system flow increases to 3000 gpm, Announces alarm "C03-B-18 HPCI OIL Alarm C03-B-18 (HPCI OIL FILTER HI DIF FILTER HI DIF PRESS unexpected" to the PRESS) will annunciate. Control Room Supervisor and enters ARP C03-B-1 8.

Cue:

As the Control Room Supervisor acknowledge report of alarm as follows" "C03-B-18 HPCI OIL FILTER HI DIF PRESS unexpected".

Comments: None

MONTICELLO NUCLEAR GENERATING PLANT JPM-B.03.02-05.G.1 TITLE: REACTOR VESSEL PRESSURE CONTROL USING Revision 0 HPCI Page 6 of 7 Perfrman eObective Standard STEP 13 (ARP 3-B-18 HPCI OIL FILTER Standard:

HI DIF PRESS Step 1)

Operator dispatches an out plant operator to Dispatch an operator to the HPCI HPCI Room to determine HPCI Oil Filter DP Room to determine HPCI OIL Filter DP based on the comparison of PI- Cue: An out plant operator has been 7257, HPCI Oil Filter Inlet Pressure dispatched to the HPCI Room to determine Indicator and PI-7253, HPCI Oil HPCI Oil Filter DP.

Filter Outlet Pressure Indicator at HPCI turbine. Comments: None STEP 14 (ARP 3-B-18 HPCI OIL FILTER Standard:

HI DIF PRESS Step 2) Operator monitors HPCI bearing temperatures on TR-23-115 and determines 2 Monitor HPCI turbine bearing HPCI bearing temps are increasing.

temperature on TR-23-115 points 4,5,6,14,15,and 16 on panel C-21. Cue: None Comments: None STEP 15 "C" (ARP 3-B-18 HPCI OIL FILTER Standard:

HI DIF PRESS Step 3)

• Operator trips HPCI by depressing the HPCI Turbine Trip push button 23A-$22 3 IF any HPCI turbine bearing until the turbine is shutdown then places temperature begins to increase, HPCI Aux Oil Pump in the Pull-To-Lock THEN Immediately trip the turbine position.

AND refer to B.3.2.-05 (HPCI - Cue: None SYSTEM OPERATION),

Comments: Placing HPCI Aux Oil Pump in AND refer to Tech Spec 3.5.A PTL not required to pass this JPM.

STEP 16 Standard: None INFORM EVALUATOR THAT THE TASK Cue: APPROVED PROMPT HAS BEEN COMPLETED. Inform the candidate that the task has been completed.

Comments: None

MONTICELLO NUCLEAR GENERATING PLANT JPM-B.03.02-05.G.1 TITLE: REACTOR VESSEL PRESSURE CONTROL USING Revision 0 HPCI Page 7 of7 CANDIDATES COPY Initial Conditions:

The plant has experienced a spurious Group 1. All plant actions have occurred as expected.

The Low Low Set System is currently controlling reactor pressure from 1052 to 972 psig.

The Control Room Supervisor has requested that you start HPCI for reactor pressure control. Reactor pressure should be controlled between 800 to 1000 psig.

INFORM THE EVALUATOR WHEN YOU HAVE COMPLETED THE TASKW!!

MONTICELLO NUCLEAR GENERATING PLANT JPM-C.4-B.04.01 .B Part A TITLE: RESET A GROUP 2 ISOLATION Revision 0 Page 1 of 5 JQ B P ERFORMVANCE MEASUJRE SRO: SRO/RO: X SRO/RO/NLO: NLO:

Plant

Reference:

C.4-B.04.01.B, Part A, Step 5, Rev. 17 Task Standard: Reset a Group 2 Isolation K/A

Reference:

223002 Task No.: A4.03 Rating RO/SRO: 3.6/3.5 Recent Events: None Probabilistic Risk Assessment Human Error: None Monticello Specific Task List

Reference:

CR200.158 METHOD OF TESTING TIME FOR COMPLETION Estimated Time to Complete: 10 min.

Simulator: X Normal: X Maximum Time to Complete: 15 min.

Alternate In-Plant: Path: Time Critical: Yes X No Prepared By: ,/.1 .,L Date:

Reviewed By: Date:

Shift Supv/Shift Mgr Review By: J,- 4 Date:C- /6 "/a Approved By: Date: I So.

/

/

MONTICELLO NUCLEAR GENERATING PLANT JPM-C.4-B.04.01. B Part A TITLE: RESET A GROUP 2 ISOLATION Revision 0 Page 2 of 5 JPM SET-UP1 I-Simulator Setup: -j Initialize to IC 247 the plant shutdown from an inadvertent Group I, a Reactor low Level condition has caused a Group 2 Isolation. The condition should be cleared and steps 1 through 4 of C.4-04.01.B (GROUP II) Part A have been completed.

Initial Conditions:

The plant has experienced a transient that caused a reactor level to decrease to minus 20 (-20) inches and then return to normal. All plant actions have occurred as expected. Reactor level has been restored and the Group 2 isolation is ready to be reset. Steps 1 through 4 of C.4-B.04.01.B, Part A have been completed.

Initiating Cues:

The Control Room Supervisor has requested that you perform the reset actions for Group 2 identified in Ops Man C.4-B.04.01.B, Part A.

MONTICELLO NUCLEAR GENERATING PLANT JPM-C.4-B.04.01. B Part A TITLE: RESET A GROUP 2 ISOLATION Revision 0 Page 3 of 5 PERFORMANCE INFORMATION Performance Objective Standard STEP 1 "C" (Procedure, Part A, Step 5.a) Standard:

WHEN the cause of the isolation is Momentarily places the GROUP 2/SCTMT corrected, ISOLATION RESET switch to the INBD and THEN reset the Group 2 signal as follows: OUTBD position.

a. Momentarily place the GROUP 2/SCTMT Cue: None ISOLATION RESET switch on Panel C-04 to the following positions: Comments: None

1) INBD

2) OUTBD STEP 2 "C" (Procedure, Part A, Step 6) Standard:

Depress the TIP ISOLATION LOGIC RESET Depresses the TIP ISOLATION LOGIC pushbutton on Panel C-13. RESET pushbutton.

Cue: None Comments: None STEP 3 (Procedure, Part A, Step 6.a) Standard:

Verify both Purge Lights are ON. Verifies both Purge lights are ON.

Cue: Both Purge lights are ON.

Comments: Simulator models only one Tip system.

STEP 4 "C" (Procedure, Part A, Step 7) Standard:

Place the following valve handswitches on C- Places handswitches for AO-2541 and AO 04 in the AUTO/OPEN position: 2561 to the AUTO/OPEN position and observes position indicating lights: red

a. 16A-S18, AO-2541 A/B DW Floor Drain comes on and green goes off.

Isolation Cue: None

b. 16A-$19, AO-2561 A/B DW Equip Drain Isolation Comments: None

MONTICELLO NUCLEAR GENERATING PLANT JPM-C.4-B.04.01 .B Part A TITLE: RESET A GROUP 2 ISOLATION Revision 0 Page 4 of 5 Performance Objective Standard STEP 5 "C" (Procedure, Part A, Step 8) Standard:

Place the following switches on C-26 in Places handswitches in the AUTO/OPEN AUTO/OPEN position: position and observes the red light comes on and the green light goes off.

a. HS-3307 SV3307 Sample Point 2 (DW) OTBD lsol

b. HS-3311 CV-3311 Sample Point 4 (Torus) OTBD Isol Cue: None

c. HS-3313 CV-3313 Sample Return OTBD Isol

d. HS-3308 SV-3308 Sample Point 2 (DW) INBD Isol

e. HS-3312 CV-3312 Sample Point4 (Torus) INBD Isol Comments: None

f. HS-3314 CV-3314 Sample Return INBD Isol STEP 6 (Procedure, Part A, Step 9) Standard:

Notify Shift Chemist to restore Drywell CAM Directs the Shift Chemist to restore Drywell to service. CAM to service.

Cue: None Comments: None STEP 7 (Procedure, Part A, Step 10) Standard: None IF RHR system was operating in Shutdown Cue: None Cooling when the isolation occurred, THEN RESET isolation by using the Comments: RHR was not operating in following pushbuttons: Shutdown Cooling prior to the Group 2 Isolation.

a. IOA-S24B, MO-2015, Shutdown Cooling Group 2 Isolation Reset

b. 1OA-S24A, MO-2014, Shutdown Cooling Group 2 Isolation Reset STEP 8 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.4-B.04.01 .B Part A TITLE: RESET A GROUP 2 ISOLATION Revision 0 Page 5 of 5 l-- ~~

i *-.. ~ ' ~ ~

. A .... DI ......

A E COPY initial uonditons:

The plant experienced a transient that caused a reactor level to decrease to minus 20

(-20) inches and then return to normal. All plant actions have occurred as expected.

Reactor level has been restored and the Group 2 isolation is ready to be reset.

The Control Room Supervisor has requested that you perform the reset actions for Group 2 identified in Ops Man C.4-B.04.01.B, Part A, steps I through 4 have been completed.

INFORM THE EVALUATORWHEN YOU HAVE COMPLETED THE TASKII

MONTICELLO NUCLEAR GENERATING PLANT JPM-B.09.08-001 TITLE: MANUALLY START NO. 11 EDG Revision 6a (CONTROL ROOM ACTIONS) Page 1 of 7 JOB PERFORMANCE MEASURE SRO: SRO/RO: X SRO/RO/NLO: NLO:

Plant

Reference:

B.09.08-05.D.1, Rev 11 Task Standard: Manually Start and Load the No. 11 EDG to 2500 KW K/A

Reference:

264000 Task No.: A4.04 Rating RO/SRO: 3.7/3.7 Recent Events: RE 92-007, Concern with loading sequence for Emergency Diesel Generator Probabilistic Risk Assessment Human Error: None Monticello Specific Task List

Reference:

CR264.109 METHOD OF TESTING TIME FOR COMPLETION Estimated Time to Complete: 15 Min Simulator: X Normal: X Alternate Maximum Time to Complete: 30 Min In-Plant: Path:

Time Critical: Yes X No Prepared By: ,dL,* Date: v P/0*

Reviewed By: Date:

Shift Supv/Shift Mgr Review By: ) -v( -Date: 0-7 /d 1/1 2 Approved By: ,,//. (Supt Ops Trng) Date: 1 7,,.

iŽ~. ~ F~OR ADMINISTRATIVE USE ONLY:

3087 (DOCUMENT CHANGE, HOLD, AND COMMENT FORM) incorporated:

Resp Supv: OTRNG lAssoc Ref: MTCP-03.32 SR: N I Freq: 0 yrs ARMS: JPM-B.09.08-001 Doc Type: 8505 Admin Initials: Date:

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MONTICELLO NUCLEAR GENERATING PLANT JJPM-B.09.08-001 TITLE: MANUALLY START NO. 11 EDG Revision 6a (CONTROL ROOM ACTIONS) Page 2 of 7 JPMV SET-UP Simulator Setup:

Initialize to IC-16. The No. 11 EDG-ESW pump must be running prior to commencing JPM.

Initial Conditions:

The Reactor is operating at 100% power. The Emergency Diesel Generator System Engineer has requested that No. 11 EDG be started and loaded to 2500 KW to perform an in-service inspection.

Initiating Cues:

Control Room Supv directs you to manually start and load No. 11 EDG to 2500 KW per the Operations Manual, B.9.8-05. The Turbine Building operator has already completed EDG in-plant pre-start checks. Procedure steps 1 through 8 of the Operations Manual have been completed.

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MONTICELLO NUCLEAR GENERATING PLANT JPM-B.09.08-001 TITLE: MANUALLY START NO. 11 EDG Revision 6a (CONTROL ROOM ACTIONS) Page 3 of 7 PERFORMANCE INFORMATION Performance Objective Standard STEP 1 Standard:

Locate procedure B.09.08-05 D.1., 11 Locates appropriate procedure.

Emergency Diesel Generator Startup. Cue: None Comments: None STEP 2 "C" (Procedure STEP 9) Standard:

Perform the following simultaneously: Places DIESEL GEN CONTROL switch

a. Place the DIESEL GEN (D-G 1/CS) to START and releases.

CONTROL switch to START. (Non-Critical portion of Standard)

b. Verify the following annunciators The operator should observe the following as the did ALARM: diesel Generator starts:

1) 8-B-24 (NO. 11 DIESEL 1. C08-B-24, No. 11 DIESEL ENG CRANKING ENG CRANKING) annunciator momentarily alarms and then

2) 8-B-34 (NO. 11 DIESEL clears.

ENG RUNNING) 2. C08-B-34, NO.11 DIESEL ENG RUNNING alarms.

3. 8-B-3 (#11 DESL GEN NOT AUTO DGI/152/502)

Cue: None Comments: None STEP 3 (Procedure STEP 10) Standard:

Check Oil Pressure (PI-7005). It should Contacts Turbine Building APEO to obtain status build up within 90 seconds to above of Oil Pressure.

44 psig. Cue:

APEO reports that Oil Pressure is 50 psig.

Comments: None STEP 4 (Procedure STEP 11) Standard:

Allow the engine to idle for 10 minutes. Monitors Control Room EDG indications and While idling: contacts APEO in No. 11 EDG Room and request

a. Check cylinder vent cocks for status of Diesel after 10 minutes of run time.

leakage. Cue:

b. Check crankcase inspection APEO reports that all EDG local parameters are covers for leakage. normal at idle speed. No. 11 EDG has been

c. Check engine oil level, running at idle speed for 10 minutes.

d. Observe engine, listen for any Comments: None abnormal indications.

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MONTICELLO NUCLEAR GENERATING PLANT JPM-B.09.08-001 TITLE: MANUALLY START NO. 11 EDG Revision 6a (CONTROL ROOM ACTIONS) Page 4 of 7 Performance Objective Standard STEP 5 (Procedure STEP 12) Standard:

Perform the following to check the air Contacts APEO to check the air box drain.

box drain for proper operation: Cue:

a. Remove the air box drain plug. Procedure Step 12 has been satisfactorily

b. Slowly crack OPEN the drain completed.

valve. Comments: None

c. Verify air flow from the air box drain line.

d. CLOSE the air box drain valve.

e. Re-install the air box drain plug.

STEP 6 "C" (Procedure STEP 13) Standard:

Place 11 EDG SPEED DROOP knob to Instructs APEO to place 11 EDG Speed Droop the scribe mark between 40 and 50 on knob to scribe mark between 40-50 on governor the governor dial plate. dial plate.

Cue:

Speed Droop knob is at requested position.

Comments: None STEP 7 (Procedure STEP 14) Standard:

Independently verify 11 EDG SPEED Requests for independent verification of previous DROOP knob is at the scribe mark step, and logs completion.

between 40 and 50 on the governor dial Cue:

plate and log entry.

Independent verification is complete and is logged.

Comments: None STEP 8 "C" (Procedure STEP 15) Standard:

Raise engine speed using SPEED Turns No. 11 EDG SPEED ADJUST (GSC-1/CS)

ADJUST switch on C-08. to RAISE and holds in RAISE until frequency WHEN generator frequency meter meter comes on-scale, then releases.

comes on-scale, C THEN release SPEED ADJUST switch. ue: None Comments: None STEP 9 (Proc STEP 16.a) Standard:

Parallel 11 EDG with 15 bus per the Turns 11 EDG SPEED ADJUST until frequency following: indicates approximately 60 Hz.

a. Adjust diesel speed until the Cue: None frequency is approximately 60 Hz. Comments: None I/cmb

MONTICELLO NUCLEAR GENERATING PLANT JJPM-B.09.08-001 TITLE: MANUALLY START NO. 11 EDG Revision 6a (CONTROL ROOM ACTIONS) Page 5 of 7 Performance Objective Standard STEP 10 "C" (Proc STEP 16.b) Standard:

b. Turn on synchronizing switch as Inserts synchronizing switch handle and turns frequency nears 60 Hz. ACB 152-502/SS to ON.

Cue: None Comments: None STEP 11 "C" (Proc STEP 16.c) Standard:

NOTE: The incoming indicates the 1. Using No. 11 EDG Voltage adjust switch diesel generator voltage. The (190-DG-1/CS), raise or lower voltage to running voltmeter indicates match No. 11 EDG voltage (incoming voltage) the bus voltage, to No. 15 Bus Voltage (running voltage) within 2 volts

c. Adjust the 11 EDG VOLTAGE AND ADJUST and SPEED ADJUST 2. Using No. 11 EDG speed adjust switch (C-08) to synchronize unit. (GSC-1/CS), raise or lower No. 11 EDG speed until synchroscope rotates clockwise at a rate of once every 20 - 120 seconds.

Cue: None Comments:

The voltage mismatch and synchroscope rate are not critical values, but are values for good operating practice.

STEP 12 "C" (Proc STEP 16.d) Standard:

CAUTION 1 Places ACB 152-502/CS to CLOSE position when Allow only one EDG to be paralleled meter synchronous conditions are met.

to the system at a time. At no time (Non-Critical portion of Standard) should an EDG be tied to an off-site power system in anticipation of a Operator should observe the following indications:

loss of off-site power. a. Breaker indication changes from green to CAUTION 2 red.

The Emergency Diesel Generator b. No. 11 EDG AC Kilowatt meter indication does not have synchroscope slightly above 0 Kw.

interlock and therefore can be c. Synchroscope stops at 12 o'clock paralleled out of phase. Ensure synchronous conditions are met Cue: None when closing the EDG output Comments:

breaker. Ifthe breaker does not close on the first attempt, IF 12 EDG is NOT paralleled to the tell the operator (as the Shift Supv and System system, Engineer) that they can try one more time to put THEN close breaker 152-502 by the EDG on line.

operating breaker switch to CLOSE when synchronous conditions are met.

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MONTICELLO NUCLEAR GENERATING PLANT JPM-B.09.08-001 TITLE: MANUALLY START NO. 11 EDG Revision 6a (CONTROL ROOM ACTIONS) Page 6 of 7 Performance Objective Standard STEP 13 "C" (Procedure STEP 17) Standard:

Using SPEED ADJUST switch, pickup 1. Holds SPEED ADJUST switch (GSC-1/CS) in load to 1875 KW. Hold at this load until RAISE position until KW reaches 1700 - 2050 local operator verifies engine is KW operating properly and temperature (Non-Critical portion of Standard) regulating valve opens.

Operator should observe the following as load is increased:

a. KW indication increases to about 1875 KW.

b. AC Amps increases to-255 amps.

2. Directs operator to perform local inspections.

Cue:

1. No. 11 EDG is operating properly.

2. Temperature regulating valve is open.

Comments: None STEP 14 "C" (Procedure STEP 18) Standard:

Increase load as desired up to 2500 KW 1. Holds SPEED ADJUST switch (GSC-1/CS) in maximum. Adjust voltage until RAISE position until KW reaches 2400 - 2500 amperage reading is reduced to KW, AND minimum (to prevent overload on 2. Adjusts VOLTAGE ADJUST switch generator). (190-DG-1/CS) until Amperage indication is at minimum.

Cue: None Comments: Approximately 330 amps indicated.

STEP 15 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-B.09.08-001 TITLE: MANUALLY START NO. 11 EDG Revision 6a (CONTROL ROOM ACTIONS) Page 7 of 7 CANDIDATES COPY Initial Conditions:

The Reactor is operating at 100% power. The Emergency Diesel Generator System Engineer has requested that No. 11 EDG be started and loaded to 2500 KW to perform an in-service inspection.

Control Room Supv directs you to manually start and load No. 11 EDG to 2500 KW per the Operations Manual, B.09.08-05. The Turbine Building Operator has already completed EDG in-plant pre-start checks. Procedure steps 1 through 8 of the Operations Manual have been completed.

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

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MONTICELLO NUCLEAR GENERATING PLANT JPM-B.05.02-001 TITLE: ROD WORTH MINIMIZER OPERABILITY Revision 5a Page 1 of 8 JOB PERFORMANCE MEASURE SRO: SRO/RO: X SRO/RO/NLO: NLO:

Plant

Reference:

Plant Procedure No. 0212, Rev 21 Task Standard: Perform Part A (Reactor Startup) of Test No. 0212 K/A

Reference:

201006 Task No.: A3.02 Rating RO/SRO: 3.5/3.4 Recent Events: None Probabilistic Risk Assessment Human Error: None Monticello Specific Task List

Reference:

CR201.104 METHOD OF TESTING TIME FOR COMPLETION Estimated Time to Complete: 15 Min Simulator: X Normal: X Alternate Maximum Time to Complete: 30 Min In-Plant: Path:

Time Critical: Yes X No Prepared By: Date: 0uc 15 Date:

Reviewed By: Date: 7 Shift Supv/Shift Mgr Review By: g /,L Date: 0-, /d j 2.G 2

Approved By: (Supt Ops Trng) Date:

FOR ADMINISTRATIVE USE ONLY, 3087 (DOCUMENT CHANGE, HOLD, AND COMMENT FORM) incorporated:

Resp Supv: OTRNG IAssoc Ref: MTCP-03.32 ISR: N I Freq: 0 yrs ARMS: JPM-B.05.02-001 I Doc Type: 8505 FAdmin Initials: Date:

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MONTICELLO NUCLEAR GENERATING PLANT JJPM-B.05.02-001 TITLE: ROD WORTH MINIMIZER OPERABILITY Revision 5a Page 2 of 8 JPM SET-UP Simulator Setup:

Initialize to any startup IC which places the CRD system in service, the Reactor shutdown, and the Reactor Mode Switch in the REFUEL position.

Fill out 0212 as follows:

0 Sign Shift Supv approval to commence.

0 Initial all prerequisites, Rod Sequence is Al, Rev 0 0 Reason for Performing - Reactor Startup: X 0 N/A STEPS 12 through 31.

Have a copy of RWM sequence steps listing ready for STEP 1.

Initial Conditions:

A Reactor startup is to begin next shift. The Prestart Checklist states that a RWM Operability Test is to be performed.

Initiating Cues:

The Control Room Supervisor directs you to perform PART A of Test No. 0212 (ROD WORTH MINIMIZER OPERABILITY TEST). The Nuclear Engineer will perform STEP 1 when requested.

Provide operator with a copy of Test No. 0212.

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MONTICELLO NUCLEAR GENERATING PLANT JPM-B.05.02-001 TITLE: ROD WORTH MINIMIZER OPERABILITY Revision 5a Page 3 of 8 PERFORMANCE INFORMATION Performance Objective Standard STEP 1 (Procedure STEP 1) Standard:

GENERAL NOTE: Requests Nuclear Engineer to perform STEP 1.

PART A steps are to be completed if Cue:

this test is being done prior to reactor Provide operator with a copy of the loaded STARTUP, or for OTHER instances when the reactor is below 10% power. sequence.

Manually obtain the sequence loaded in Comments:

the RWM, STEPS la through lm are performed by OR utilizing the RWM services function, Nuclear Engineer. These steps will not work print the sequence desired at a local on the simulator.

printer by performing the following:

STEP 2 (Procedure STEP 2) Standard:

Verify the sequence loaded in the RWM Compares RWM printed sequence and sequence is identical to the sequence on the roller on the roller tape, verifying no discrepancies.

tape. Cue: None Comments:

Evaluator should stop the operator after profi ciency has been demonstrated.

STEP 3 (Procedure STEP 3) Standard:

At the RWM Operators Display (OD), top Verifies that RWM OD "SELF TEST' is followed by status line, verify that SELF TEST: is "OK'.

followed by OK. Cue: None Comments: None STEP 4 (Procedure STEP 4) Standard:

On the OD, top status line, verify that Verifies that RWM OD "SEQUENCE" is followed SEQUENCE: is followed by the specified by proper sequence identifier (Al RO).

(in PREREQUISITE 2) Control Rod Sequence identifier (ie, Al RO, B2R1). Cue: None Comments: None STEP 5 (Procedure STEP 5) Standard:

IF a benchmark critical sequence is N/A step and initial.

loaded, Cue:

THEN place the RWM OD keylock switch in TEST, Benchmark critical sequence is NOT loaded.

AND select the Special Test mode. Comments: None I/cmb

MONTICELLO NUCLEAR GENERATING PLANT JPM-B.05.02-001 TITLE: ROD WORTH MINIMIZER OPERABILITY Revision 5a Page 4 of 8 Performance Objective Standard STEP 6 "C" (Procedure STEP 6) Standard:

Verify the reactor MODE SWITCH is in Places Reactor Mode Switch in the STARTUP STARTUP (Panel C-05). position.

Cue: None Comments: None STEP 7 "C" (Procedure STEP 7) Standard:

Withdraw the first permissible rod to Selects rod 22-27 by depressing pushbutton on Position 02. the rod select matrix, AND places Rod Movement Control switch to the Rod Out Notch position, releases the switch, and withdraws the rod to position 02.

Pauses at STEP 7 until rod position is verified.

(Non-Critical portion of Standard) -

Prior to rod movement, the operator should verify the CRDH system indication and operation as normal. During and after the operator moves the control rod, he should verify the proper cycling of the RMCS lights located above the Rod Movement Control switch on C-05.

Cue:

Rod 22-27 (STEP 7) is verified at position 02.

Comments:

Rod 22-27 is first rod in Group No. 1.

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MONTICELLO NUCLEAR GENERATING PLANT JPM-B.05.02-001 TITLE: ROD WORTH MINIMIZER OPERABILITY Revision 5a Page 5 of 8 Performance Objective Standard STEP 8 "C" (Procedure STEP 8) Standard:

Attempt to withdraw the first rod in the Select rod 14-27 by depressing pushbutton on the next group in the sequence. rod select matrix, AND places Rod Movement Control switch to the Rod Out Notch position, and releases the switch in an attempt to withdraw the selected rod.

Pauses at STEP 8 until action is verified.

(Non-Critical portion of Standard)

Prior to rod movement, the operator should verify the CRDH System indication and operation is normal. During and after the operator moves the control rods, he should verify the proper cycling of the RMCS lights located above the Rod Movement Control switch on C-05.

Cue:

Attempted rod withdrawal (STEP 8) is verified.

Comments:

Rod 14-27 is the first rod in Group No. 2.

STEP 9 (Procedure STEP 9a) Standard:

Verify the following: Verifies no rod movement on the four-rod, full

a. Rod movement is prevented, core, and RWM displays after the Rod Movement Control Switch is released in the previous step.

Cue: None Comments: None STEP 10 (Procedure STEP 9b) Standard:

On the RWM OD top status line Verifies that RWM OD "BLOCKS:" is followed by BLOCKS: is followed by WITHDRAW. "WITHDRAW".

Cue: None Comments:

Simulator RWM indicates Insert and Withdraw.

This will be verified after exam. If candidate questions Insert, inform them to continue and this will be investigated by another operator.

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MONTICELLO NUCLEAR GENERATING PLANT JPM-B.05.02-001 TITLE: ROD WORTH MINIMIZER OPERABILITY Revision 5a Page 6 of 8 Performance Objective Standard STEP 11 (Procedure STEP 9c) Standard:

The first line of the RWM OD lower Verifies that lower display of RWM OD shows the display shows the selected rod, followed same rod selected as on the rod select by SE WB (Select Error and Withdraw pushbutton matrix, Block). AND that it's followed by SE and WB (Select Error and Withdraw Block).

Cue: None Comments:

Simulator RWM indicates SE lB WB. This will be verified after exam. If candidate questions IB, inform them to continue and this will be investigated by another operator.

STEP 12 "C" (Procedure STEP 10) Standard:

Using the printed sequence obtained in Selects rod in group not presently permitted to be STEP 1: withdrawn by depressing the associated pushbut

a. Select one rod from each ROD ton on the Rod Select pushbutton matrix.

GROUP, except group presently (Non-Critical portion of Standard) permitted to be withdrawn (listed in left hand vertical column). Verifies the first line of the RWM OD displays the rod currently selected, followed by SE and WB

b. Verify first line of RWM OD (Select Error and Withdraw Block).

lower display shows selected rod followed by SE WB (select Cue: None Error and Withdraw Block). Comments:

Evaluator may stop operator after satisfactory demonstration on a minimum of three (3) rod groups.

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MONTICELLO NUCLEAR GENERATING PLANT JPM-B.05.02-001 TITLE: ROD WORTH MINIMIZER OPERABILITY Revision 5a Page 7 of 8 Performance Objective Standard STEP 1'3 "C" (Procedure STEP 11) Standard:

Insert all withdrawn control rods to 00. Selects rod 22-27 by depressing the pushbutton NOTE: This completes all on the rod select matrix, requirements for RWM AND places the Rod Movement Control switch to operability prior to pulling the Rod In position, releases the switch, and rods, inserts the rod one notch to position 00.

Requests STEP 11 to be verified.

(Non-Critical portion of Standard)

Prior to rod movement, the operator should verify the CRDH System indication and operation as normal. During and after the operator moves the control rod, he should verify the proper cycling of the RMCS lights located above the Rod Movement Control switch on C-05.

Cue:

STEP 11 has been verified.

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!

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MONTICELLO NUCLEAR GENERATING PLANT JPM-B.05.02-001 TITLE: ROD WORTH MINIMIZER OPERABILITY Revision 5a Page 8 of 8 CANDIDATES COPY Initial Conditions:

A Reactor startup is to begin next shift. The Prestart Checklist states that a RWM Operability Test is to be performed.

The Control Room Supervisor directs you to perform PART A of Test No. 0212 (ROD WORTH MINIMIZER OPERABILITY TEST). The Nuclear Engineer will perform STEP 1 when requested.

INFORM THE EVALUATOR WHEN YOU HAVE COMPLETED THE TASK"!

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ITITLE:

MONTICELLO NUCLEAR GENERATING PLANT MANUAL CONTROL OF RHRSW CV-1729 JPM-B.08.01.03-001 Revision 8a Page 1 of 6 JOB PERFORMANCE MEASURE SRO: SRO/RO: SRO/RO/NLO: X NLO:

Plant

Reference:

B.08.01.03-05.H.3, Rev 20 Task Standard: Taking Manual Control of RHR Heat Exchanger RHRSW Control Valve CV-1 729 K/A

Reference:

205000 Task No: A2.08 Rating RO/SRO: 3.3/3.5 400000 A1.01 2.8/2.8 Recent Events: None Probabilistic Risk Assessment Human Error: None Monticello Specific Task List

Reference:

NL205.118 METHOD OF TESTING TIME FOR COMPLETION Estimated Time to Complete: 10 Min Simulator: Normal: X Alternate Maximum Time to Complete: 20 Min In-Plant: X Path:

Time Critical: Yes X No Prepared By: d Date: 4  ?/d.2 Reviewed By: Date:

Shift Supv/Shift Mgr Review By:

• Date: A Approved By: (Supt Ops Trng) Date:

IResp Supv: OTRNG (DOCUMENT Resp Supv: oT-RNG ........

FOR ADMINISTRATIVE USE ONLY Assoc Ref: MTcP-03.32 HOLD AND COMMENT FORM' inmrrnrntpri

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SR: N SR: N Frep:

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ARMS: JPM-B.08.01.03-001 Doc Type: 8505 Admin Initials: Date:

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MONTICELLO NUCLEAR GENERATING PLANT JPM-B.08.01.03-001 TITLE: MANUAL CONTROL OF RHRSW CV-1729 Revision 8a Page 2 of 6 JPM SET-UP Plant Setup:

Have a copy of B.08.01.03-06, Figure 2.

Initial Conditions:

The Reactor is shutdown and <212'F. The No. 12 RHR Heat Exchanger Control valve CV-1 729 solenoid valve SV-1 729 has failed. The No. 11 and No. 13 RHR pump breakers have been previously removed for breaker maintenance. Shutdown cooling is desired at this time.

Initiating Cues:

The Control Room Supervisor directs you to assume manual control of RHR Heat Exchanger RHRSW control valve CV-1 729.

ALL OPERATOR ACTIONS ARE TO BE SIMULATED!

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MONTICELLO NUCLEAR GENERATING PLANT JPM-B.08.01.03-001 TITLE: MANUAL CONTROL OF RHRSW CV-1729 Revision 8a Page 3 of 6 PERFORMANCE INFORMATION Performance Objective .. Standard STEP 1 Standard:

Locate Procedure B.08.01.03-05.H.3, Locates the appropriate procedure.

"Taking Manual Control of RHRSW Control Valves, CV-1 728 and CV-1 729 Cue:

Upon Failure of SV-1 728 or SV-1 729." Provide operator with a copy of procedure.

Comments: None STEP 2 "C" (Proc PART B, STEP 11) Standard:

Obtain key to unlock handwheel on Obtains key No. 41 from SS Office or from CV-1 729,12 RHR HX RHRSW Outlet. operator key ring.

Cue:

Shift Supv gives you key No. 41 or operator key ring.

Comments: None STEP 3 (Procedure STEP 12) Standard:

Establish communications between B Establishes radio communication between the RHR Room and Control Room Control Room and himself from the B RHR room.

Cue:

Radio communication is established between Control Room and B RHR room.

Comments:

May simulate radio communication to the Control Room after operator exhibits knowledge of obtaining and using a radio.

STEP 4 "C" (Procedure STEP 13) Standard:

NOTE: Completion of following step 1. Unlocks the valve handwheel.

will result in CV-1729's brass 2. Rotates the valve handwheel clockwise until handwheel screw holding resistance is felt.

valve closed via engagement Cue:

with valve stem.

1. Handwheel is unlocked.

Unlock the handwheel on CV-1 729 (see 2. Resistance is felt on the valve handwheel.

Ops Man Section B.08.01.03-06, Figure 2 - RHRSW Control Valve), Comments:

AND turn it clockwise until resistance is felt. Operator does not have to examine figure in Ops Manual ifthey are familiar with the equipment.

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MONTICELLO NUCLEAR GENERATING PLANT JPM-B.08.01.03-001 MANUAL CONTROL OF RHRSW CV-1729 I Revision 8a I I TITLE: I Paae 4of 6 I I Pace 4 of 6 CAUTION Turns the air supply valve to the MANUAL Do not dead head pumps for more position.

than 7 minutes. Cue:

Turn the air supply valve to the Air supply valve is in the MANUAL position.

"MANUAL" position. (See Ops Man Section B.08.01.03-06, Figure 2 Comments:

RHRSW Control Valve for location of the Operator does not have to examine Ops Manual air supply valve). figure if they are familiar with the equipment.

STEP 6 (Procedure STEP 15) Standard:

Notify Control Room of the following: 1. Notifies the Control Room CV-1729 is ready

a. Control valve CV-1 729 is ready for manual operation, AND for manual operation, 2. Notifies the Control Room, the RHRSW pump

b. RHRSW pump may be started.

is ready to be started.

Cue:

Control Room is notified CV-1 729 is ready for manual operation and the RHRSW pump may be started.

Comments: None STEP 7 (Procedure STEP 16) Standard: None START an RHRSW pump per Ops Man Cue:

B.08.01.03-05.D.1, Startup Procedure - Control Room Operators have started the No. 12 Startup of RHRSW Pumps. RHRSW pump.

Comments:

It is not the intent of this JPM for the operator to perform action in the Intake for starting of a RHRSW pump.

STEP 8 "C" (Procedure STEP 17) Standard:

OPEN CV-1 729 to obtain the desired Simulates opening CV-1 729 by turning the valve flow rate by turning the valve handwheel handwheel CCW until valve position is at 60%.

in the counterclockwise direction. Cue:

No. of Approximate Valve position indicates approximately 60%. Flow Pumps Flowrate Valve Position rate is 3500 gpm.

1 3500 gpm 60% open Comments: None 2 7000 gpm 85% open I l/cmb

MONTICELLO NUCLEAR GENERATING PLANT JPM-B.08.01.03-001 1TITLE: MANUAL CONTROL OF RHRSW CV-1729 I Revision 8a I I Paae5of6 I I Pacie 5 of 6 ITITLE:

Verify that RHR HX tube-to-shell side dP Verifies DP is greater than 20 psid by checking is greater than 20 psid by checking DPIS-1 0-92B.

DPIS-1 0-92B (local instrument rack),

AND adjust valve position, as required. Cue:

DPIS indicates 40 psid.

Comments: None STEP 10 "C" (Procedure STEP 19) Standard:

Lock handwheel for CV-1 729 in position. Locks the handwheel in position.

Cue:

Handwheel is locked in position.

Comments:

The valve position may drift unless the handwheel is locked.

STEP 11 (Procedure STEP 20) Standard: None NOTE: Valve CV-1729 is now Cue:

locked in position at Flowrate is being monitored from the Control desired flow rate. An Roonm operator does not need to oom.

be stationed at valve Comments: None continuously.

Monitor system flowrate from Control Room.

STEP 12 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-B.08.01.03-001 TITLE: MANUAL CONTROL OF RHRSW CV-1 729 Revision 8a I-' Page 6 of 6 The Reactor is shutdown and <212'F. The No. 12 RHR Heat Exchanger Control valve CV-1 729 solenoid valve SV-1 729 has failed. The No. 11 and No. 13 RHR pump breakers have been previously removed for breaker maintenance. Shutdown cooling is desired at this time.

The Control Room Supervisor directs you to assume manual control of RHR Heat Exchanqer RHRSW control valve CV-1729.

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MONTICELLO NUCLEAR GENERATING PLANT JPM-B.05.07-002 TITLE: FWCV CONTROL I Revision 6a I Paae 1 of 5 I I

JQB PERFOQRMANCE ME...RI SRO:__ SRO/RO:__ SRO/RO/NLO: X NO Plant

Reference:

B.05.07-05, Rev 10 Task Standard: Take Local Manual Control of Feedwater Reg Valve K/A

Reference:

259001 Task No.: A2.07 Rating RO/SRO: 3.7/3.8 Recent Events: None Probabilistic Risk Assessment Human Error: None Monticello Specific Task List

Reference:

NL259.1 01 iiiiIi

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METHOD OF TESTING TIME FOR COMPLETION Estimated Time to Complete: 5 Min Simulator: ___Normal: X Alternate Maximum Time to Complete: 10 Min In-Plant: X Path:___

Time Critical: ___Yes X No Prepared By: Date:

Reviewed By: Date: /)

Shift Supv/Shift Mgr Review By: 4Lt,1?Date: -7/(AQ Approved By: (Supt Ops Trng) Date: 2 FOR"* *INZSTfIATIVEU

• NLY incorporated: "

FORM) 3087 (DOCUMENT CHANGE, HOLD, AND COMMENT Resp Supv: OTRNG lAssoc Ret MTCP-03.32 ISR: N IFreq: 0 vrs ARMS: JPM-B.05.07-002 Doc Type: 8505 IAdmin Initials: Date:

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MONTICELLO NUCLEAR GENERATING PLANT JPM-B.05.07-002 TITLE: FWCV CONTROL Revision 6a Page 2 of 5 Plant Setup:

None Initial Conditions:

The Plant is operating at 50% power with the Main Feedwater Regulating valves in service. Local manual control of the "A"FWCV, CV-6-12A is required to replace its controller MTS-6-84A on C-05.

Initiating Cues:

The Shift Supv directs you to take local manual control of "A"Main Feed Reg valve CV-6-12A.

ALL OPERATOR ACTIONS ARE TO BE SIMULATED!

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MONTICELLO NUCLEAR GENERATING PLANT JPM-B.05.07-002 TITLE: FWCV CONTROL Revision 6a Page 3 of 5 PERFORMANCE INFORMATION Performance Objective, Standard STEP 1 Standard:

Locate procedure B.05.07-05.G.1, Locates appropriate procedure.

"Local Manual Control of Feedwater Cue:

Valves".

Provide operator with a copy of the procedure.

Comments: None STEP 2 "C" (Procedure STEP 1.a) Standard:

IF necessary to engage the handwheel, Turns large handwheel on CV-6-12A CW until THEN perform the following: snug.

Turn (clockwise) the large handwheel Cue:

until it is snug at its limit of travel. Large handwheel is snug.

Comments: None STEP 3 "C" (Procedure STEP 1.b) Standard:

Turn (counterclockwise) the small hand- Turns small handwheel on CV-6-12A CCW until it wheel until it is tight. is tight.

Cue:

Small handwheel is tight.

Comments: None STEP 4 "C" (Procedure STEP 1.c) Standard:

Turn the Bailey positioner bypass valve Turns positioner bypass valve to the OPEN-HAND from CLOSED-AUTO to OPEN-HAND to position.

equalize the pressure across the valve Cue:

actuator.

Positioner bypass valve is pointing to the OPEN HAND position.

Comments: None STEP 5 "C" (Procedure STEP 1.d) Standard:

OPEN the actuator equalizing valve at Turns actuator equalizing valve CCW until it is the top of the Fw Reg Valve actuator to tight.

equalize pressure during valve lock-up. Cue:

Actuator equalizing valve is full CCW and tight.

Comments: None I/cmb

MONTICELLO NUCLEAR GENERATING PLANT JPM-B.05.07-002 TITLE: FWCV CONTROL Revision 6a Page 4 of 5 Performance Objective Standard STEP 6 "C" (Procedure STEP 1.e) Standard:

Turn the Bailey positioner air supply Turns positioner air supply valve to the valve from AU TO-OPEN to HAND-CLOSED position.

HAND-CLOSED to remove supply air Cue:

from the operator.

Positioner air supply valve is pointing to HAND-CLOSED position.

Comments: None STEP 7 "C" (Procedure STEP 1.f) Standard:

Adjust valve position locally by operation Turns large handwheel clockwise to CLOSE.

of the large handwheel. Cue:

1. Tell them that Control Room requests the operator to slowly close the valve.

2. CV-6-12A changes position as handwheel is turned.

3. If asked, inform them CV-6-12B is opening slowly to control RPV level.

Comments: None STEP 8 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-B.05.07-002 TITLE: FWCV CONTROL Revision 6a Page 5 of 5 CANDIDATES COPY Initial Conditions:

The Plant is operating at 50% power with the Main Feedwater Regulating valves in service. Local manual control of the "A"FWCV, CV-6-12A is required to replace its controller MTS-6-84A on C-05.

INFORM THE EVALUATOR WHEN YOU HAVE COMPLETED THE TASKI!!

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MONTICELLO NUCLEAR GENERATING PLANT JPM-B.06.03-002 TITLE: START THE MECHANICAL VACUUM PUMP Revision 7 (MVP) Page 1 of 8 SRO: SRO/RO: SRO/RO/NLO: X NLO:

Plant

Reference:

B.06.03-05, Rev 12 Task Standard: Placing the MVP in service due to decreasing Condenser Vacuum.

K/A

Reference:

295002 Task No.: AA1.02 Rating RO/SRO: 2.9/2.9 Recent Events: None Probabilistic Risk Assessment Human Error: "FPMVACPMPY' Monticello Specific Task List

Reference:

NL255.1 01, CR255.109 METHOD OF TESTING TIME FOR COMPLETION Estimated Time to Complete: 15 Min Simulator: Normal: X Alternate Maximum Time to Complete: 30 Min In-Plant: X Path:

Time Critical: Yes X No Prepared By: Date:

Reviewed By: Date:

Shift Supv/Shift Mgr Review By: -- Date: /_,_

Approved By: _ A,_. (Supt Ops Trng) Date:

CE AplDjNISTRTV USE NL6 ,

3087 (DOCUMENT CHANGE, HOLD, AND COMMENT FORM) incorporated:

__ Resp Supv: OTRNG -Assoc Ref: MTCP-03.32 ISR: N Freq: 0 yrs "ARMS: JPM-B.06.03-002 Doc Type: 8505 Admin Initials: Date: /

I I I/jIg

MONTICELLO NUCLEAR GENERATING PLANT JPM-B.06.03-002 TITLE: START THE MECHANICAL VACUUM PUMP Revision 7 (MVP) Page 2 of 8

... ..JPM SET-UP Plant .Setup:

None NOTE: It is not necessary to enter a posted contaminated area to reach all the components. It is permissible for the operator to point them out if not accessible.

Initial Conditions:

Reactor startup in progress at approximately 2% power on IRMs. Reactor pressure is 750 psig and increasing in preparation for rolling turbine-generator. Startup checklists have been completed.

Initiating Cues:

Both OG recombinerftrains have tripped due to H2 analyzer problems and cannot be restarted. Condenser vacuum is decreasing and C.4-B.06.03.A has been entered.

The SS directs you to start the Mechanical Vacuum Pump (MVP) in order to recover condenser vacuum, using approved procedures.

ALL OPERATOR ACTIONS ARE TO BE SIMULATED!!

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MONTICELLO NUCLEAR GENERATING PLANT JPM-B.06.03-002 TITLE: START THE MECHANICAL VACUUM PUMP Revision 7 (MVP) Page 3 of 8 PERFORMANCE INFORMATION T Pe 9rfrmnce' Objective Standard ~ 7 STEP 1 Standard:

Operator locates appropriate procedure Operator locates procedure B.06.03-05.D.1, for starting MVP. "Startup of the Mechanical Vacuum Pump."

Cue:

None Comments:

Provide operator with copy after locating the procedure.

STEP 2 .(Procedure STEP 1) Standard:

GENERAL NOTE Operator verifies either by observing indications The following sequence for starting on C-06, or by contacting Turbine Building various components of the operator.

Mechanical Vacuum Pump should be Cue:

followed to avoid damage to the Turbine and/or parts of the (Ifasked), Turbine Building operator reports Condensing System. normal operation of the Service Water system.

Verify Service Water Pump(s) in service Comments

None per B.08.01.01 (SERVICE WATER).

STEP 3 (Procedure STEP 2.a) Standard:

To start the Mechanical Vacuum Pump Operator proceeds to OG-66 and closes the (MVP): valve.

NOTE: This step prevents Cue:

radioactive gases from Handwheel on OG-66 turns cW and becomes escaping from the MVP tight.

Separator while the MVP is in operation. (NRC Comments: None Commitment M71031 A).

a. CLOSE OG-66, MVP SEPARATOR OVERFLOW TO CRW.

STEP 4 (Procedure STEP 2.b) Standard: None

b. IF directed by Shift Supervisor, Cue: None THEN verify valve checklist Comments:

Form 2154-16 (OFF-GAS SYSTEM PRESTART VALVE Initial conditions stated all Startup Checklists were CHECKLIST) has been complete.

completed. II I/jig

MOlNTICE*LLO NUCLEAR GENERATING PLANT ~MU ~ ~ p-IN nq-n,-

nrWNCLA I U ~~~ EEAIG~ LN ..... *1 IVl L--#e **.J*.J

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TITLE: START THE MECHANICAL VACUUM PUMP I Revision 7 I

. M(MVP) Paae 4 of 8 STEP 5 "C" (Procedure STEP 2.c) Tianaara:

c. OPEN CST-24, MVP MU VVTR Operator opens CST-24, MVP MU WTR STOP.

STOP.

Cue:

CST-24 handwheel turns CCW and flow is heard.

Comments: None STEP 6 (Procedure STEP 2.d) Standard:

d. Verify seal water level in the Operator observes level in sight glass.

separator is between 1/4 and 3/4 of the height of sight glass Cue:

LG-2452, MVP MOISTURE Sight glass is 1/2 full.

SEPARATOR TANK LEVEL SIGHT GLASS. Comments: None STEP 7 (Procedure STEP 2.e) Standard:

e. Verify the following MVP trip Operator determines the status of the MVP trip relays are energized. relays.

1) 16A-K45 (Panel C-41) Pre-Approved Prompt

2) 16A-K46 (Panel C-42) All 4 MVP trip relays are energized.

3) 16A-K23 (Panel C-41) Cue: None

4) 16A-K24 (Panel C-42) Comments:

This would normally be done by operators from the Control Room.

STEP 8 (Procedure STEP 2.f) Standard: None

f. IF one or more of the relays Cue: None listed in step 2.e are Comments:

de-energized, THEN reset GROUP 2/SCTMT Per Step 2.e all relays are energized.

ISOLATION RESET HANDSWITCH 16A-$56 (Panel C-04).

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MONTICELLO NUCLEAR GENERATING PLANT JPM-B.06.03-002 TITLE: START THE MECHANICAL VACUUM PUMP Revision 7 (MVP) Page 5 of 8 P1erformac Obeciv Standard STEP 9 (Procedure STEP 2.g) Standard:

NOTE: OG-28 must be closed in Operator verifies CLOSED OG-28, COND BW order for the MVP to be REC TANK (T-33) VENT ISOL.

started. Because of this, Cue:

Condensate Demineralizer backwashing cannot be OG-28 indicates closed.

performed when the MVP is Comments: None being placed in service (OG-28 is required to be open for Condensate Demineralizer backwashing).

g. Verify CLOSED OG-28, COND BW REC TANK (T-33) VENT ISOL STEP 10 "C" (Procedure STEP 2.h) Standard:

h. Verify OPEN OG-24, MVP Operator verifies OPEN OG-24 MVP DISCHARGE VLV. DISCHARGE VLV.

Cue:

OG-24 indicates OPEN.

Comments: None STEP 11 "C" (Procedure STEP 2.i) Standard:

i. START the MVP from local Operator starts the MVP from local pushbutton pushbutton station (PB-52-104 station and observes MVP start.

MVP START/STOP CONTROL). Cue:

The MVP has started and sounds normal.

Comments: None STEP 12 (Procedure STEP 2.j) Standard:

j. Verify OPEN AO-1 825A and Operator verifies valves AO-1 825A and AO-1 825B VACUUM PUMP AO-1825B OPEN.

SUCTION ISOLATION valves. Cue:

MVP suction isolation valves have moved to the OPEN position Comments: None I/jig

MONTICELLO NUCLEAR GENERATING PLANT JPM-B.06.03-002 TITLE: START THE MECHANICAL VACUUM PUMP Revision 7 (MVP) Page 6 of 8 Performance Stan,

.jci , - ,* .

STEP 13 (Procedure STEP 2.k) Standard:

k. Verify operation of P-70, MVP Operator verifies operation of P-70.

RECIRC SEAL PUMP. Cue:

MVP Recirc Seal Pump sounds normal and feels cool.

Comments: None STEP 14 (Procedure STEP 2.1) Standard:

I. Verify that seal water inlet Operator verifies seal water inlet pressure.

pressure (PI-7246, MECHANICAL VACUUM PUMP Cue:

SEAL WATER INLET PRESS, Seal water pressure is 15 psig and steady.

Local) is >0 psig and constant. Comments: None STEP 15 (Procedure STEP 2.m) Standard:

m. Regulate service water to the Operator adjusts service water to the cooler as cooler by throttling SW-38, MVP needed.

SEAL CLR SW OUT, to maintain Cue:

outlet temperature <1 00°F.

(TI-1 597, MVP SEAL WATER SW-38 valve turns CCW and outlet temperature is COOLER OUTLET 75 0 F.

TEMPERATURE, Local). Comments: None STEP 16 "C" (Procedure STEP 2.n) Standard:

n. Slowly OPEN the following Operator opens OG-22-1,11 CDSR MVP valves: SUCTION and OG-22-2, 12 CDSR MVP

1) OG-22-1 11 CDSR MVP SUCTION.

SUCTION Cue:

2) OG-22-2, 12 CDSR MVP OG-22-1 and OG-22-2 chain operated valves turn SUCTION counter clockwise. The stems rise, meet resistance and are tight.

Comments: None STEP 17 (Procedure STEP 2.o) Standard:

o. Verify pump and motor Operator verifies pump and motor operating operating properly before properly.

leaving unattended. Cue:

MVP sounds, looks and feels normal.

Comments: None I/jIg

MONTICELLO NUCLEAR GENERATING PLANT JPM-B.06.03-002 TITLE: START THE MECHANICAL VACUUM PUMP Revision 7 (MVP) Page 7 of 8 S Perforanc Obetv Standarcf STEP 18 (Procedure STEP 2.p) Standard:

p. Check the water level in the Operator may question if someone will monitor moisture separator sight glass water level.

hourly, AND drain level to normal, as Cue:

required. Another operator will monitor and drain the sight glass as necessary.

Comments: None STEP 19 "C" (Procedure STEP 2.q) Standard:

q. Throttle OG-22-1 and OG-22-2 Operator observes PI-7451, MVP Suction to minimize spray from MVP Pressure, and MVP Seal Leakage.

packing. Throttle to suction Cue:

pressure of 15 to 25'in. Hg Vac on PI-7451, MVP Suction PI-7451, MVP Suction Pressure, indicates 21 in.

Pressure, then adjust as Hg Vac. Minimal leakage is observed-from the needed. Valves may be opened MVP packing. Throttling of OG-22-1 and fully if required for pump OG-22-2 is not needed.

performance. Comments: PI-7451 is in the MVP Room.

STEP 20 Standard:

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

Cue: None Comments: DO NOT PROMPT!

• 5 I/jig

MONTICELLO NUCLEAR GENERATING PLANT JPM-B.06.03-002 TITLE:

TIL-TRTH(MVP)START THE MECHANICAL VACUUM PUMP Revision 7 8 of 8 Page

-CANDIDATES'COPY > yj \

Initial Conditions:

Reactor startup in progress at approximately 2% power on IRMs. Reactor pressure is 750 psig and increasing in preparation for rolling turbine-generator. Startup checklists have been completed.

IF M THEEVALUATOR '"I""'Y "

• HA E'C'"""i "H'" . . . I.

I/jig