Text

Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 970707-11
	ML20211B556
Person / Time
Site:	Davis Besse
Issue date:	09/23/1997
From:	Bies M; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	NUDOCS 9709250273
	Download: ML20211B556 (348)
	v • d • e

l l 2 UNITED STATES

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REGION ill 001 WARRENVILLE ROAD

USLE, ILUNOIS (232-4351 September 23, 1997 NOTE T0: NRC Document Control Desk Mail Stop 0-5-D-24 FROM: Mary Ann Bies, Licensing Assistant hNM u '

Operating Licensing Branch, Rlll

SUBJECT:

OPERATOR LICENSING EXAMINATION ADMINISTERED THE WEEK OF JULY 7, 1997, AT DAVIS-BESSE, DOCKET NG, 50-346 During the week of July 7,1997, Operator Licensing Fxaminations were administered at the referenced facility. Attached, you will find the following information for )rocessing through NUDOCS and distribution to the NRC staff, including tio NRC PDR:

Item #1 - a) Facility submitted outline and initial exam submittal, designated for distribution under RIDS Code A070.

b) As given operating examination, designated for distribution under RIDS Code A070.

Item #2 - Examination Report with the as-given written examination attached, designated for distribution under RIDS Code IE42.

Attachments: As stated Np2kD05 o 0$$46 V PDR

INITIAL SUBM17TALS OF DAVIS-BESSE EXAMINATION THE WEEK OF 07/n7/97 a

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i INITIAL SUBMITTAL OF OUTLINE FOR DAVIS-BESSE EXAM ,

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l ES-301 Administrative Topics Outline Form ES-301-1 l I

Examination Level (Circle One) : RO/ QR !

Facility: _ Davis Besse Week oT Examination 07/07/97 Examiner's Name (print): D. McNeil. E. Plettner Administrative Describe method of evaluation:

Topic / Subject 1. ONE Administrative JPM, OR Description 2. TWO Administrative Questions A.1 Temporary Equipment Operator requests to use a Boric Acid pump mods of in a lineup not authorized by the procedure. He procedures wants SRO to identify if TA or Procedure Change is needed Shift 30 minutes after shift turnover, one of the Safe Staffing Shutdown EOs is called home on a medical emergency.

A.2 Faulted Completed Surveillance Test on an HPI pump will Surveillance contain data that is in the unacceptable range.

Test Candidate will declare pump inoperable and enter the appropriate LCO.

A.3 Knowledge of Required actions to take when radiological conditions significant are changing in an area. Operator working in ECCS-radiation room needs to work above 7 ft to operate valve. When hazards & permission granted by RP and worker goes to valve, RWP dose rates are reported much above expected.

Requirements Candidate identifies required corrective actions.

A.4 Event Candidate will classify a General Emergency and Declaration recommend evacuation of correct sub areas.

and PARS Chief Examiner:

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ES-301 Individual Walk-through Test Outline Form ES-301-2 Examination Level (Circle One): HO / SRO(I) / SRO(U)

Facility: Davia Beane Week of Examination 07/07/97 ,

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Examiner #a Name (print): D. McNeil. E. Plettner

.. um, System /-JPM Safety Planned Follow-up Questions:

Function K/A/G // Importance // Description

1. DitR/RCS IV a. 005000A402 // 3.4/3.1 // Manual Purification control of Dl! flow af ter SA3

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b. 0050000009 // 3.6/3.6 // CTRM indications of Dit pump #1 xfor switch 2.SWS/ Loan of X a. O'76000A202 // 2.7/3.1 // Interlocks Primary loop ancociated with SW 1395/1399

b. 000062K302 // 3.6/3.9 // Service water pump auto atart algnala

3. CPS / Emergency II a. 006000G008 // 3.8/3.8 // Effects of closure of CPIA CTMT temperature on CPT alarma

b. 013000K411 // 3.2/3.8 // Roanon for -

removing an inoperable EDG sequencer

4. Statior. DC / VII a. 0630000009 // 3.1/3.3 // Local Swap to a swing indications of an equalizer charge

b. 000057K302 // 4.1/4.4 // Load shed '

batterica during a LOOP

5. Chemical Add / I a. 004020A105 // 3.7/3.0 // Effect of Emergency Dorate closing inservice Demin inlet valve

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b. 004000K122 // 3.4/3.7 // Interlocks associated with MU Tank lii/Lo levela Exeminer: Chief Examiner:

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ES-301 Scenario Events Form ES-301-3 _

Oimulation Facility: Davis Besse Scenario No.: 1 Examinors _, ,

Applicantst Initial Conditions: 100% Power. BOL ( IC #27)

Turnover: Normal Operatino Conditions with no eculoment out of service.

The Load disoatcher has iust acoroved Power reduction to 50% Power for

)fater Box cleanino.

Cvent Malf. Event Event No. No. Type

Description 1 R Power Reduction to 50% Power 2 MS-11 I Selected Hdr Press Instrument fails to 0 3 MUP-12 C Operating Makeup Pump trips due to shaft seizure.

4 MS-02 M Steam leak intitiated in CTMT which increases'to e line rupture causing major overcooling

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Chief Examiner:

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ES-301 Scenario Events Form ES-301-3 Simulation Facility: _ Davis Besse Scenario No.: 2 j

-1 Examiners: Applicants:

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Initial Conditions: Plant Startuo in Procress with Turbine Load at 110 MWE. (IC 41) ,,

Turnover Power' Increase to 35% Planned .

Event Malf. Event Event No. No. Type

Description 1 R Plant Power Increase to 35% Power and lift off low ,

level limits 2 SG-06 I Stnrtup level instrument for #2 OTSG fails low 3 SG-01 C OTSG tube leak requiring _ plant shutdown .

4 SG-01 M OTSG tube leak becomes a tube rupture

(N)ormal, (R)eactivity, (I) nstrument , (C) omponent, (M)ajor Chief Examiners l

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ES-301 Scenario Events- Form ES-301-3 simulation Facility _Davio Besse Scenario No.: 3 j Examiners: Applicants:

d initial Conditions: Plant is at 50% Power followina renairs to 2 Main i t'eed Pumn . No other eculoment is oos (IC 30)

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Turnovers _#2 Main Feed Pumo was returned to service last shift and is now in full automatic. The load disoatcher has reauested the olant be returned to full oower. F Event Malf. Event Event' No. No. Type

Description 1 R Increase in plant cower following repairs to Main Foed Pump Turbine bearing.

'2 MFW-11 C Restarted Main Feed Pump bearing fails and MFW-01 requires a manual trip 3 PZR-10 I Se3ected pressurizer level instrument fails hi'gh

! 4 RCS-02 M 7..iall RCS leak develops which becomes a LOCA l causing loss of SCM 1

(N)ormal, (R)eactivity, (I)nstrument, (C) omponent , (M)ajor Chief Examiners i

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6 Senior Reactor Operator 033000G015 000032A202 Generic Admin 035010K301 000033A209 194001A101 039000K508 000037K305 194001A103 062000G010 000037K307 194001A100 064000G008 000038A202 194001A108 073000K301 000038A215 194001A116 075000A401 000054K102 194001K101 079000K401 000058A203 194001K102 086000G008 000061A205 194001K103 000065A206 194001K104 Group til Sys 194001K105 005000K408 Group lli Emer.

194001K107 008030A304 194001K115 045050K101 000028K305 194001K110 078000K302 000036K303 194001A107 000056A214 194001A114 Group l Emer.

194001A115 194001A116 000001K301 000003A103 Group i Sys 000005G011 001000K105 000011A115 003000K305 000011A201 004000A205 000015G007 004010K403 000024A205 013OOOK101 000024K302 .

013000G006 000026A105 014000A104 000029A209 015000A202 000029G011 015000G005 000040A205 017020A202 000040G011 022000G007 000051A202 026020K403 000055K302 056000A204 000057A219 059000A201 000067G002 059000G014 000067K102 061000A101 000068K318 061000K101 000068A205 063000K302 000069G003 072000G012 000074K102 000074K204 l Group ll Sys 000076G008 l 002020K500 l

006000A106 Group ll Emer.

010000A203 000007A202 011000G010 000008A201 012000G014 00000PA201 016000A201 000022A201 016000K201 000025A207 028000A202 000027K304

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I INITIAL SUBM7.TTAL OF ADMINISTRATIVE JPMs FOR DAVIS-BESSE !

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e ES-301 Administrative Topics Outline Form 88-301-1 1

Examination Level (Circle One): RO / SRO Facility: _ Davis Besse Week of Examination 07/07/97 Examiner's Name (print) : D. McNeil. E. Plettner !

l Administrative Descr'ibe method of evaluation:

Topic / Subject 1. ONE Administrative JPM, OR Description 2. TWO Administrative Questions A.1 Temporary Equipment Operator requests to use a Boric Acid pump

mods of in a lineup not authorized by the procedure. He procedures wants SRO to identify if TA or Procedure Change is needed Shift 30 minutes after shift turnover, one of the Safe '

Staffing Shutdown EOs is called home on a medical emergency.

A.2 Faulted Completed Surveillance Test on an HPI pump will Surveillknce contain data that is in the unacceptable range.

Test Candidate will declare pump inoperable and enter the appropriate LCO.

A.3 Knowledge of Required actions to take when radiological conditions significant are changing in an area. Operator working in ECCS radiation room needs to work above 7 ft to operate valve. When hazards & permission granted by RP and worker goes to valve, RWP dose rates are reported much above expected.

Requirements Candidate identifies required corrective actions.

A.4 Event. Candidate will classify a General Emergency and Declaration recommend evacuation of correct sub areas.

and PARS 11 l

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Chief Examiner:

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l JOB PERFORMANCE MEASURE NO. A1a Candidate: O----- Examiner: O----- Date: O-----

Facility: Davis Besse Unit 1 Task

Title:

Proper Use of the Temporary Ar ,roval Process Job Performance Measure tG------ Safety Function: 0-----

K/A Referonce: 194 001 A102 4 '3.9 Method of Testina:

Simulated Performance O----- Actual Performance x Simulator x Control Room x in Plant 0-----

Task Standard: Determine if a requested Temporary Approvalis appropriate.

Required Materials: NG NA 00115 Control of Procedures, Revision 2, C-2 ED 7635, Procedure Development Form General

References:

NG NA-00115, Control of Procedures, Revision 2, C-2 ED 7635, Procedure Development Form Time Critical Task: No Estimated /Validatinn Time: 13 minutes Bend to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You will make all written reports, oral reports, and log entries as if the evolution was actually belag performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

During the course of the walkthrough examination, there may be some tasks you will be asked to _

perform that may require you to implement an alternative method directed by plant procedures in order to complete the assigned task. You are expected to make decisions and take actions based on the f acility's procedural guidance and the indications available.

. You may use any' approved reference materials normally available, including logs. Make all

written and/or oral reports as if the evolution was actually being performed.

C 6 JOB PERFORMANCE MEASURE NO. Ala initial Conditions: The plant is in MODE 3, preparing for a cooldown into MODE 5.

Initiating Cue: The outside Assistant Shif t Supervisor on your shif t has requested that both Boric Acid Addition Tanks be used to transfer boric acid into the # 1 CWRT from the Boric Acid Addition Pumps. He has indicated to you that this lineup is not currently in the system procedure. He has asked you to process a Temporary Approval to the procedure to make this lineup work. He has determined the technical aspects of this change and has marked up a copy of DB OP 06031, BAAT Operating Procedure which you have reviewed and you have concurred with the marked up sections. Your task is to process the Temporary Approval. The Shift Manager is available to perform the function of the Qualified Reviewer.

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l Performance intarmation 6 NOTE: Critical steps denoted with a "C", Failure to meet any one of these standards for this i

. item constitutes f ailure. ; Sequence is assumed unless denoted in the " Comments". a l Start Time !

- 1. - Performance Step: Initiate a Temporary Approval to DB OP 06031, BAAT Operating Procedure using a Procedure Development Form, ED 7635 pv NG NA-00115, Control cf j Procedures.

)

Standard: Identifies tisat a PDF must be completed IAW NG NA 00115, Control of .

Procedures.

I Cues:(AS NEEDED) Hand a copy of NG NA 00115 to the candidato and a blank PDF. L A review of Commitments indicates none will be changed.

The PAT number is 97 0123

, - No interf acing documents exist.

A Safety Review has been completed by the outside Assistant SS.

- RP has determined they do not need to review.

- A validation checklist has been completed. :

SAT UNSAT

- 2. Performance Step: Submit the TA to 's Qualified Reviewer for ' approval, i 2 ' ' Standard:- Indicates'that a Qualified Reviewer must approve the TA.

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Cue: The Shift Manager will do the Qual;fied Review. During his review he -

Indicates to you that he has consulted with the Procedure Sponsor and determined that training must he conducted on this lineup before this TA <

is approved.

SAT UNSAT ;

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3. Performance Step: When pre-implementation training is indicated, a Temporary Approval !

.........C....... ' cannot be used. ,

i Standard: Indicate that a Temporary Approval cannot be used for this evolution. !

Com6hent: Step 6,6,1.c of NG NA 00115. -

Cue: None .

SAT 'UNSAT Terminating Cue: This JPM is Complete.

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JPM Ala

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JOB PERFORMANCE MEASURE NO. Alb Candidate: D----- Examiner: 0----- Date: O-----

Facility: Davis Besse Unit 1 Task

Title:

Call Out and Proper Relief for Replacement of Safe Shutdown EO Job Performance Measure tG----- Safety Funct'cn: 0----- .

K/A

Reference:

194 001 A103 2.5/3.4 Method of Testina:

Simulated Performance O----- - Actual Performance x -

Simulator x Control Room x In Plant O-----

Task Standard: Perform callout of operator to relieve the Safe Shutdown EO.

Ensure proper turnover is conducted.

Required Materials: Shift Manning List Overtime Callout List Fitness for Duty callout form General Ref erences: DB-OP-00000, Conduct of Operations, Revision 3, C 2 DB-OP 00100, Shif t Turnover, Revision 3, C 1 FHAR Section 0.3, Revision 16 Time Critical Task: No Estimated / Validation Time: 6 minutes Read to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You will make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be sa-:isfied.

During the course of the walkthrough examination, there may be some tasks you will be asked to perform that may require you to implement an alternative method directed by plant procedures in order to complete the assigned task. You are expected to make decisions and take actions based on the facility's procedural guidance and the indications available.

You may use any approved reference materials normally available, including logs. Make all

-written and/or oral reports as if the evolution was actually being performed. ,

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JOB PERFORMANCE MLASURE NO. Alb Initial Cenditions: The plant is in MODE 1 at 100% power.

Initiating Cue: It is 1910 in the evening and the Safe Shutdown EO on your shift has indicated that he must leave due to a medical emergency with his family. Shif t 2 is the shift that is oncoming and Shift 4 was the shif t that was relieved by the current shift. The Shift Supervisor has directed you to ensure that all shift manning requirements are met.

1 4 4 JPM Alb Peeformance information NOTE: Critical steps denoted with a "C". Failure to meet any one of these standards for this item ennstitutes f ailure. Sequence is assumed untoss denoted in the " Comments".

Start Time

1. Performance Step: Recognize that the shif t is at less than minimum manning and an EO callout is needed.

............C............... :

1 Standard: ' Obtain a current shift Manning List from the Shift Supervisor for the shift to j determine current manning. i Cue: Provide the candidate with a copy of the Shift Manning List.

SAT UNSAT Comments: The sequence of the next two steps can be done in any order as long as they are done prior to the actual phone call to the relief EO

2. Performance StepFill out Fitness for Duty form as required by the FFD program Standard: Obtain a FFD form prior to callout of relief EO Cue: Provide candidate with FFD form.

SAT UNSAT

3. Performance StepVerify callout made in accordance with Overtime Rules.

Standard: Obtain a copy of the current overtime list for the oncoming shift Cue: Provide candidate with the overtime list for shift 2.

f SAT UNSAT 4.-- Performance StepCallout a relief EO for Safe Shutdown EO.

..,,........C...............

- Standard: Callout the selected EO.

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Cuef . The operator indic;t:s that he is fit fer duty cnd will report to th3 pl:nt as i soon cs he etn. i l

.i SAT UNSAT 1 JPM Alb i t

, Terminating Cue: This JPM is Complete.

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1 JOB PERFORMANCE MEASURE NO. A2 Candidate: O----- Examiner: O----- Date: D-----

Fecility: Davis Besse Unit 1 Task

Title:

Review ci Completed Surveillance Test and Declaring Pump inoperable Based on Data.

Job Performance Measure tG----- Safety Function: 0-----

K/A

Reference:

194-001 A108 2.6/3.1 Method of Testino:

- Simu'sted Performance O----- Actuel Performance x Simulator x Control Room x In-Plant O-----

Task Standard: Perform review of a completed surveillance test. Identify inoperability due to f ailure to meet acceptance criteria.

Required Materials: DB-SP 03218, HPl Pump 1 Quarterly Pump and Valve Test, Revision 4 General

References:

DB-DP-00013, Surveillance and Periodic Test Program, Revision 4 DB-SP 03218, HPl Pump 1 Quarterly Pump and Valve Test, Revision 2, C-5 Operations General Policy - GP 21, Operability Determination DB-OP-00005, Operator Logs and Rounds, Revision 6 ,

Time Critical Task: No EstimatedNalidation Time: 10 rninutes Read to Performer:

I will explain the initial conditions, which steps to simulate or discusi, and provide initiating and subsequent cues. You will make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for thia Job Performance Measure will be satisfied.

During the course of the walkthrough examination, there may be some tasks you will be asked to perform that may requiro you to implement an alternative method directed by plant procedures in order to complete the assigned task. You are expected to make decisions and take actions based on the f acility's procedural guidance and the indications available.

You may use any approved reference materials normally available, including logs. Make all wntten and/or oral report 2 as if the evolution was actually being performed.

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JOB PERFORMANCE MEASURE NO. A2 Initial Condithns: The EO assigned to Perform the # 1 HPl Pump Quarterly test has returned the ST to you for your review.

Initiating Cue: Here is the completed Surveillance of the # 1 HPl pump, DB-SP-03218, HPl Pump 1 Quarterly Pump and Valve Test. You are to perform the supervisory review of the test.

JPM A2 Performance Information NOTE: Critical steps denoted with a "C". Failure to meet any one of these standards for this item constitutes failure. Sequence is assumed unless denoted in the " Comments".

Start Time

1. Performance StepReview the completed ST for completeness and accuracy.

Standard: Recognize that Step 5.2 was signed off incorrectly. Actual data on Attatchmc.it 2 has pump in the inoperable range.

Cue: None ,

SAT UNSAT

2. Performance StepMake operability determination for the # 1 HPl pump.

.........C...........

Standard: Declare the # 1 HPI pump inoperable.

Cue: If the candidate asks for System Engineering Support or EO to re-review, the response is: "The data on the ST is accurate."

SAT UNSAT

3. Performance StepNotify the Shift Supervisor and initiate a PCAOR as required per step 6.6.3 of DB DP-00013, Surveillance and Periodic Test Program Standard: Observe communication with the SS and indicate that a PCAOR needs to be initiated.

Cue: The SS aknowleges the notification and informs you that the Shift Manager has initiated the PCAOR.

SAT UNSAT

4. Performance Stepinitiate an entry into the Unit Log.

Standard: Indicate that a Unit Log entry is required.

Cue: The Shift Manager has initiated Unit Log entry.

SAT UNSAT Terminating Cue: This JPM is Complete. End Time JPM A2

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JOB PERFORMANCE MEASURE NO. A3 Candidate: O----- Examiner: O----- Date: O-----

Facility: Davis Besse Unit 1 Task

Title:

Corrective Actions to be Taken When Radiological Conditions Are Changing and Correct check out of a Portable Radiation Instrument Job Performance Measure FE----- Safety Function: 0-----

K/A

Reference:

194-001-K103 2.8/3.4 Method of Testina:

Simulated Performance Actual Performance x Simulator Control Room it, Plant x Task Standard: Perform check out of Portable radiation detector. Notify RC personnel of changing radiological conditions.

Required Materials: Oporations Radiation Work Permit.

DB-HP-01103, Use of Portable Radiation, Contamination and Airborne Survey Equipment General

References:

DB-HP-01901, Radiation Work Permits, Revialon 4, C-5 DB-HP-01103, Use of Portable Radiatica, Contamination and Airborne Survey Equipment, Revision 1, C-1 Time Critical Task: No EstimatedNatidst;ca Time: 16 minutes Read to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You will make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task a successfully, the objective for this Job Performance Measure will be satisfied.

'During the course of the walkthrough examination, there may be some tasks you will be asked to perform that may require you to implement an alternative method directed by plant procedures in order to complete the assigned task. You are expected to make decisions and takc actions based on the facility's procedural guidance and the indications available.

s You may use any approved reference materials normally available, including logs, Make all written and/or oral reports as if the evolution was actually being performed.

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JOB PERFORMANCE MEASURE NO. A3 initial Conditions: The plant is in MODE S on # 1 DH Loop. Lineups are in progress to switch to the # 2 DH Loop to allow the # 1 Loop to be taken OOS for maintenance.

Initiating Cue: You have been directed to vent the #2 DH pump by opening DH 56, #2 DH Pump Casing Vent.

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JPM A3 Performance Information NOTE: Critical steps denoted with a "C". Failure to meet any one of these standards for this item constitutes failure. Sequence is assumed unless denoted in the

" Comments".

Start Time

1. Performance Step: Review the Operations Work Permit for the evolution.

..........C...............

Standard: Notify RP of task and request guidance.

Cuet RP reports that the task may be performed if you monitor dose rateswith either a R02 or an RS05. They also indicate that you only need a lab coat and gloves to cross the boundary to operate the valve. Expected Dose rates in the general area of the pump are 20 mrem /hr.

SAT UNSAY

2. Performance StepCheckout a portable radiation detector.

Standard: Locate proper guidance for checkout of detector.

Cue: Hand the candidatu a copy of DB-HP-01103, Use oi Portable Radiation, Contamination and Airborne Survey Equipment.

SAT UNSAT

3. Performance Step: Verify current calibration.

............C..............

Standard: Ensure calibration sticker exists and is not past due.

Cue: None.

SAT UNSAT

4. Performance Stepinspect instrument for physical damage.

Standard: Visually inspect the detector.

Cue: None.

SAT UNSAT

JPM A3

5. Performance StepEnsure the instrument's mechanical zero is i.et properly.

Standard: Observe check of mechanical zero.

Cue: None.

SAT UNSAT

6. Ferformance Step: Turn on the instrument and check for proper electrical zero.

Standard: Observe switch placed in ZERO position and pointer at zero.

Cue: None.

SAT UNSAT

7. Performance Step: Perform Battery checks.

.............C.............

Standard: Observe the switch placed in the BAT position (s) and pointer moves to BATT OK.

Cue: None.

SAT UNSAT

0. Performance Step: Check that the daily source check has been completed.

.............C.............

Standard: Observe check of sticker on side of instrument.

Cue: None.

SAT UNSAT

9. Performance Step: Perform a response check of the instrument using check source available.

Standard: Observe response check.

Cue: None.

SAT UNSAT l

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JPM A3

10. Performance Step: Select a reading that will show an onscale response based on expected radation levels.

Standard: Either the 50 MR/HR or the 500 MR/HR scale is selected.

Cue: None.

SAT UNSAT

11. Performance Step: Proceed to # 2 ECCS room to perform task.

Standard: Proceed to the # 2 ECCS room.

Cue: (AS CANDIDATE IS WITHIN 4 FEET OF PUMP)

Your M.G dosimeter has started to alarm.

SAT UNSAT

12. Performance Step: Select a scale on radiation detector to obtain Dose reading.

Standard: Select 500 MR/HR scale Cue: (IF on 50 MR/HR Scale) Reading is high off scale.

(When on 500 MR/HR Scale) Meter indicates 120 MR/HR SAT UNSAT

13. Performance Step: Contact RP to inform them of changing radiological conditions and exit area.

..............C................

Standard: Inicate that RP needs to be informed and exit to a low dose area.

Cue: The on duty RP Technician indicates that he will suspend access to the area until another survey is completed and areas are properly posted.

SAT UNSAT Terminating Cue: This JPM is Complete.

End Time

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Y 4 TJOB PERFORMANCE MEASURE NO. A4 - 7

Candidate: O----- - Examineri O-----' Date: O-----

i Facility:- Davis Besse Unit 1. .

. Task

Title:

2 Classification of an Event, Dose Assessment, and Protective Action Recommendations i

Job Performarice Measure No: O------ - Safety Function: O-----

3.1/4.4 K/A~

Reference:

i 194 001 A116 n---

. Method of Tastina -

- Simulated Performance O----- Actual Performance x

~ Simulatr,r x- Control Room x - In-Plant O-----

Task Standa'rd: Classify an event as a General Emergency

Perform an offsite dose assessment using the DADS computer

' Make Protective Action Recommendations -

1

. Required Materials: O-----

- General

References:

RA EP 01500, Emergency Classification, Revision 1, C 2

- HS-EP 02240, Offsite Dose Assessment, Revision 4, C 1 RA EP 02245, Protective Action Guidelines, Revision 0

~ Time Critical Task: No -

, EstimatedNalidation Time: 27 minutes-Raad to Performer: -

1;will explain the initial conditions, which steps to simulate or discuss, and provide-initiating.and subsequent cues. You will make all written reports, oral reports, and log entries as if the evolution was' actually being performed, When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

.During the course of the walkthrough examination, there may be some tasks you will be asked to ~'

perform that'may require you to implement an alternative method directed by plant procedures (in order to complete the assigned task. You are expected t.o make decisions and take actions based on the facility's procedural guidance and the indications available.

.-Yob inay use any approved reference materials normally available, including logs. Make all .

written and/or oral reports as if the evolution was actually being performed.

2' e .L v--se I --s*--- e- .rbv- n- b ae- m- 2 ;t=---"vm + e-Pr- -r P'ewey+= =v yv w+ Yr w' y y te y e *W 'T

JOB PERFORMANCE MEASURE NO A4 Initial Conditions: A plant shutdown was in progress due to a 25 gpm tube leak in the # 1 OTSG. EDG # 1 is OOS for a bearing replacement. Dose Equivalent lodine is reported to be 70 micro curies per gram.

Initiating Cue: A loss of offsite power occurred 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ago. The # 2 EDG started but was manually shutdown due to a bus D1 lockout. The SBODG did not start when a start attempt was made from the Control Room. The prob!em has been identified but repair parts will not be available for 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months . One Main Steam Safety valve is leaking with RE 600 reading 50,000 cpm. Dose Equivalent lodine is now at 110 micro curies per gram. The highest reading on REs 2004,2005,2006,and 2007 is 30 REM /HR. The Load Dispatcher has been contacted and indicates that restoration of offsite power will not be available for 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . You are the Emergency Director, classify the event and take any required actions.

a JPM A4 '

Performance Information -

NOTE: Critical steps denoted with a "C". Failure to meet any one of these standards for this item constitutes failure. Sequence is assumed unless denoted in the " Comments".

Start Time

1. Performance Step: Classify the event in accordance with RA EP-01500.

-..........C............

Standard: Indicate that the event is to be classified as a General Emergency -

per EAL 4.A.5 of RA EP-01500.

Cue: ' The Emergency Plant Manager has relieved -you as Emergency Director and is taking actions per RA-EP- 01900, General Emergency. You are directed to complete offsite dose assement and recommend any offsite protective actions to the Emergency Plant Manager.

SAT UNSAT

2. Performance Step: Conduct dose assessment using the DADS computer per HS-EP-02240, Offsite Dose Assessment.

Standard: Determine that no Protective Action Recommendations will be required based on offsite dose.

Comments: This step may be done out of sequence if candidate chooses to go to RA-EP-02245, Protective Action Guidelines to make minimum PAG recommendations for a General Emergency prior to doing dose assessment.

' Cue: Use current Met data. If as. sed indicate that CTMT pressure is normal.

SAT UNSAT t

.3. Performance Step: Provide Protective Action recommendations to Offsite Agencies per

.........C....RAiEP.-02245, Protective Action Guidelines.

Standard: Using Attachment 1, determine that minimum Protective Action Recommendations are to evacuate subareas 1 and 12, and shelter affected downwind areas to 5 miles.

4

(_ _ .

Cue: None.

SAT UNSAT Tenninating Cue: This JPM is Complete.

End Timo JPM A4 i

-i e

J t

INITIAL SUBMITTAL OF WALKTHROUGH JFMs FOR DAVIS-BESSE

ES-301 Individual Walk-through Test Outline Form ES-301-2 Examination Level (Circle One): RO / SRO(I) / SRO(U)

Facility: Davis Besse Week of Examination 07/07/97 Examiner's Name (print): D. McNeil. E. Plettner System / JPM Safety Planned Follow-up Questions:

Function K/A/G // Importance // Description 1.DHR/RCS IV a. 005000A402 // 3.4/3.1 // Manual Purification control of DH flow after SA3 using' SFP (faulted) b. 005000G009 // 3.6/3.6 // CTRM indications of DH pump #1 xfer switch 2.SWS/ Loss of X a. 076000A202 // 2.7/3.1 // Interlocks Primary loop associated with SW 1395/1399

b. 000062K302 // 3.6/3.9 // Service water pump auto start signals

3. Borate from II a. 006000G008 // 3.8/3.8 // Effects of Outside the CTMT temperature on CFT alarms

b. 013000K411 // 3.2/3.8 // Reason for removing an inoperable ED7 sequencer

4. Swap to a VII a. 063000G009 // 3.1/3.3 // Local Swing Battery indications of an equalizer charge

'9

b. 000057K302 // 4.1/4.4 // Load shed batteries during a LOOP

5. Reset a I a. 004020A105 // 3.7/3.8 // Effect of Spurious SFAS closing inservice Demin inlet valve

^ "" "

b. 004000K122 // 3.4/3.7 // Interlocks associated with MU Tank Hi/Lo levels Examiner: Chief Examiner:

j SIMULATOR INSTRUCTIONS TASK DESCRIPTION: -

Purification of the RCS using SFP Purification with Loss of DH Flowpath INITIAL CONDITION:

u Mode 5. DHR Train 1 in service-ADDITIONAL SETUPIDEYlATION FROM INITIAL CONDITION:

1. Ensure DH Cooler #1 outlet temperature is <120*F.

2. Ensure RCS pressure is <100 psig.

3. Ensure Section 4.14. is completed through Step 4.14.13.

4. Ensure Breaker BF 1129 Is closed for DH 1616.

MALFUNCTION 8/ FAILURE TO INSERT:

DH line leak downstream of DH 18 TVBF0301/0.01/ direct ACTION / CUES:

Step 1. CUES: Role play as each EO to report on station and ready for throttling DH 61.

Step 2. CUES: Pt 1634 roads 60 psig.

FIS 1616 reads 85 gpm.

DH 61 is approximately 21/2 turns open.

ACTION: Use CTS to slowly deposit TABDDH61 to a value of 0.26.

Step 3. - CUES: Role play as EO in MPR #1 that water is spraying from the pipe downstream of DH 1B at approximately 60 75 gpm.

ACTION: Insert DH line leak by opening drain viv as follows:

TVBF0301/0.01/ direct.

I l

l c .. .- .

w JOB PERFORMANCE MEASURE NO.142 Candidate: Examiner: Date:

Facility: Davis-Besse Task

Title:

_ Purification of the RCS Using SFP Purification with Loss of DH Flowpath

= Job Performance Measure No: 142 _ safety Function:

i M/A

Reference:

000426 EA2.02 (3.4/3.8) -

000426 EK1.01 (3.9/4.3)

Method of Tesdng:-

' Simulated Performance X . Actual Performance Simulator X Control Room in Plant Task Standard: Leak isolated by closing DH 15.

DH Pump 2 started.

l Required Materials:- DB-09-06012, Decay Heat and Low Pressure injection Operating Proceoure, Revision 02, C4 DB OP42527, Loss of Decay Heat Removal, Revision 02 08404, Sh.1, Revision 21 08407, Revision 14 General

References:

DB OP46012, Decay Heat and Low Pressure injection Operating Procedure, Revision 02, C4 DB OP42527, Loss of Decay Heat Removal, Revision 02 OS404, Sh.1, Revision 21 08407, Revisiori 14 i

i Time Critical Task: No EstimatedNalidation Time: 25 minutes Road to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and l,

. subsequent cues. You will make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective i: for this Job Pedormance Measure will be satisfied.

During the course of the walkthrough examination, there may be some tasks you will be asked to perform that may require you to implement an attemative method directed by plant procedures in order to complete the assigned task. You are expected to make decisions and take actions

' based on the facility's procedural guidance and the indications available.

{

You may use any approved reference materials normally available, including logs. Make all written and/or oral reports as if the evolution was actually being performed.

- .- m .. . . . . _ . - _ _ _ -- - _ __

- . ~ _ . ..- _ . . . . .- . ~ . .~ ~

l l

JOB PERFORMANCE MEASURE NO.142 l

Initial Conditions: - Mode 5, Decay Heat Train 1 in service. ;

Initiatir.g Cue:- You are the Reactor Operator in the CTRM. The plant is in Mode 8 with -

Decay Heat Removal Train 1 in service. The Shift Supervisor directs you ia direct and monitor the lineup for purification of the RCS using SFP Purification via the SFP Domineralizer and SFP filter. Three Eos are on station to perform the duties outlined in Section 4.14 of DB-OP 06012. You are directed to update the CTRM OS drawings as components are manipulated. 08 004 and 05 007 are marked up through Step 4.14.13.

Here is your copy of DB OP 06012.

i l'

1 L

l i

l l

Performance information NOTE: Critical steps denoted with a 'C". Failure to meet any one of these standards for this item constitutes failure. Sequence is assumed unless denoted in the " Comments".

Start Time

1. Performance Step: Direct placement of three operators for throttling DH 61.

Standard: Ensure dispatch of an EO to DH 61 and to FIS 1616 to monitor flow and to Pt 1634 to monitor pressure.

Cue: None SAT UNSAT

1. Performance Step: Throttle open DH 61 to obtain 80100 gpm on FIS 1616 and <100 psig on Pl1634.

Standard: Communicate with the EO at DH 61, who will throttle open DH 61 while the other two EOs monitor flow and pressure.

Cue: None.

SAT UNSAT

3. Perforreance Step: Recognize, based upon the report from an EO that DH System leaks downstream of DH 18.

Standard: Receive report and report to SS that a leak exists downstream of DH iB.

Cue: SS acknowledges the report and directs that DH 1B be closed to isolate the leak.

SAT UNSAT

4. Performance Step: Close DH 18.

.........C.............

Standard: Place control power on DH 18 and press CLOSE on HIS DH 18.

Cue: SS directs you to perform appropriate actions for a Loss of DHR Flowpath.

SAT UNSAT

8. Performance Step: Locate the correct procedure.

Standard: Identifies DB OP-02527, Loss of Decay Heat Removal, Section 4.2, as the correct procedure and section.

Cue: Hand copy of DB OP 02527 to candidate.

SAT UNSAT

4. Performance Step: Check DH Pump #1 for loss of suction flowpath or cavitation.

Standard: Check for OPEN Indications on HIS DH 11 HIS DH 12, and HIS DH 1517.

Cue: None.

SAT UNSAT

7. Performance Step: Locate the correct procedure section.

Standard: Route to Section 4.1 after recognizite that the Train 1 flowpath can not be restored.

Comment: This will be from either Step 4.2.2 or 4.2.5.

Cue: None.

SAT UNSAT

8. Performance Step: Refer to Attachment 4 to start DH Pump 2.

Standard: Route to Attachment 4.

Comment: Venting should not be required.

Cue: If asked, SS directs that venting is not required.

SAT UNSAT

9. Performance Step: Close DH 14A.

.........C.............

Standard: Push AUTO on HIS DH 14A.

Close DH 14A using HIC DH 14A.

Cue: None.

SAT UNSAT

10. Performance Step: Close DH 13A.

.........C.............

Standard: Push AUTO on HIS DH 13A.

Close DH 13A using HIC DH 13A.

Cue: None.

SAT UNSAT

- 11. Performance Step: Verify DH 1518 open.

Standard: Check HIS 1618 red light ON.

Cue: None.

SAT UNSAT

12. Performance Step: Verify DH 11 and 12 open.

Standard: Check HIS DH 11 and HIS DH 12 red lights ON.

Cue: None.

SAT UNSAT

13. Performance Step: Verify CCW cooling available.

Standard: Observe check of CC Pump 2 running.

Cue: None.

SAT .UNSAT

14. Performance Step: Verify SW cooling available. <

Standard: - Observe check of SW Pump 2 running.

Cue: None.

SAT UNSAT

16. Performance Step: Verify DH 1 A open.

Standard: Check HIS DH 1 A red light ON.

Cue: None.

SAT UNSAT

16. Performance Step:8 tart DH Pump 2.

.........C.............

Standard: Tum HIS DH 6A to START.

Cue: None.

SAT UNSAT Terminating Cue: This JPM is Complete.

End Time

- VERIFICATION OF COMPLETION Operator Evaluator SSN Date Licrense: [ ] RO [ ] SRO Validated Completion Time: minutes Actual Completion Time: m'nutes Acceptable Progress Maintained: Yes No N/A Result: [ ] SATISFACTORY [ ] UNSATISFACTORY NOTE: An " Unsatisfactory" requires Comment and will reqt. ire subsequent remedial training.

Comments /Fcedback:

Evaluator's Signature Date

, NROPUL EXAM imNK PAGE: 4 l FULL QUESTION QUERY DATE: 5/1G/97 Question Nbr.t OLC-7023 Question Type B Category: J Point Value: 1.50 Create Date: 05/12/95 Objective Number : OLC-PWR.043 06K Keywords : Dl! OLC '

Proc Ref/Rev/ step DB.OP.06012(3.5.14) 02 Miscellaneoup Ref:

Attachments :

Action Indicators: REVIEW PROCEDURE CZWiGE VALIDATE REVISE Exam Last Used i FA Ratinge : 005-000. A4.02 3.4/3.1 Comments : JPM 142 Question:

Explain how to take MANUAL control of decay heat flow from the CTRM, after SA 3 han been actuated. All equipment han operated as designed. (Administrative requirementa need NOT be included.)

Answer

- References MAY be used,

n. BLOCK SA 3.

b. Puen the AUTO punhbutton on Dit 14A/D.

c. Control vaive position with Bailey controller.

SAT /UNSAT l

.NRQFUL EXAM BANK PAGE: 2 FULL QUESTION QUERY DATE: 6/2/97 Question Nbr.: OLC 7042 Question Type: E Category: J Point Values 1.00 Create Date: 05/12/95 Objective Number :-OLC-PWR-041-11K Keywords : DH OLC Proc Ref/Rev/Stept DB-OP-06012(2.1) 02 Miscellaneous Reft Attachments s.

Action Indicators: REVIEW PROCEDURE CHANGE VALIDATE REVISE Exam Last Used i KA Ratings : 005 000-GEN.09 3.6/3.6 Comments : JPM 142 Question:

If the DSA and DSB emergency control transfer switches for Decay Heat pump 1-1 are out of the NORMAL position, it will have what effect on the controls for the Decay Heat pump?

Answer References MAY be used.

Decay Heat pump will NOT respond to a SFAS 3 START signal.

The pump cannot be operated from the CTRM (but can be started locally) ,

s SAT /UNSAT End of Report s

1

x,-

-1

-lii JPM - No'. ~ 14B Paga 6 of311-SIMULATOR INSTRUC" IONS TASK _DESCRI_PTIOt! '

Loss of Service Water Loop 1.to Primary Loads INITIATtCONDITION:.

FPSS ADDITIONAL SETUP / DEVIATION FROM INITIAL CONDITION:

Service Water Loop 1 on primary loada.

MALFUNCTIONS / FAILURE TO INSERT:

Trip /Stop Service Water Pump 1.by inserting malfunction TFK6TBR/T. Run until alarm-11-1-B comes in.

ACTION / CUES:

CUE Service Water Pump 1 50/51-A relay target is tripped. ,

(

< w, w g

l DAVIS-BESSE NUCLEAR POWER STATION JOB PERFORMANCE MEASURE WORKSHEET EPM NO. 14B Rev. 06 Page 7 of 11 IASK NO.: 076-002-04-0100 TASK DESCRIPTION: Loss of Service Water Loop 1 to Primary Loads K/A.

REFERENCE:

000-062-EK3.01 (3.2/3.5), 000-062-EK3.03 (4. 0/4. 2) ,

000-062-GEN.10 (3.6/3.5)

APPLICABLE METHOD OF TESTING: Simulate performance Simulator TIME FOR COMPLETION: 7 minutes APPLICABILITY: (X) RO [X) SRO TASK STANDARDS:

1. CCW Pump 2 running supplying essential and non-essential loads.

2. CCW Pump 1 stopped.

REQUIRED MATERIALS:

DB-OP-02511, Loss of SW Pumps / System, Revision 01, C-3 GENERAL

REFERENCES:

DB-OP-02011, Heat Sink Alarm Panel 11 Annunciators, Revision 01, C-3 DB-OP-02511, Loss of SW Pumps / System, Revision 01, C-3 INITIAL CONDITIONS:

The plant is in Mode 1, All systems are in a nonnal lineup, except that SWP-3 in OOS for maintenance. CCW Pump 1 is running and supplying primary equipment. CCW Pump 2 is in standby.

INITIATING CUES:

The following annunciator alarm is received:

CC itX OUTLET TEMP HI (11-1-B)

s.

JPM No. 143 Page 8 of 11 I

INITI A1_qQNDITIplig 4

The plant is in Mode 1. All systema are in a normal lineup,.except that SWP 3 is DOS for maintei.ance. CCW Pump 1 in runc.ing and supplying primary equipment. CCW Pump 2 in in standby.

INITIATING CMas The following annunciator alarm is received:

CC llX OUTLET TEMP 111 (11-1-D)

JPM No. 14B P093 9 of 11 RERFORMANCE INFORMATION HOTE: Critical steps denoted with a 'C". Failure to meet any one of '

these standards for this item constitutes failure. Sequence is assumed unless denoted in the "Commento".

START TIME:

1. PERFORlUd7CE STEP: Locate the correct procedure.

STANDARD: Identifies DB OP 02011, Heat Sink Alarm Panel 11 Annunciators.

CUE: None.

~

SAT UNSAT

2. PERFORMANCE STEP: Locate the correct procedure and section.

STANDARD: Identifies Section 4.1 of DB-OP 02511, loss of SW Pumpa/ System +

as correct procedure.

CUE: None.

SAT UNSAT

3. PERFORMANCE STEP: Investigate the relay targets on the tripped SWP breaker.

STANDARD: Send EO to locally check breaker AC 107 targets.

CUE: None.

SAT UNSAT

4. PERFORMANCE STEP: Verify CAC 1 or 3-as-1 is off, verify SW 1366 and

........C........ SW 1368 are closed.

STANDARD: HIS 5031 for #1 CAC pushed; green light ON.

HIS 1366 for SW 1366 CLOSE pushbutton pressed.

Observe green light ON HIS 1360 for SW 1368.

Observe green light ON HIS 5033A for #3 CAC.

COMMENTt SW 1368 M critical.

HIS 5033A E critical.

CUE: None.

SAT UNSAT

JPM No. 14D P0g3 10 of 11

5. PERFORMANCE STEP: Start CCW Pump 2.

........C........

STANDARD: CCW Pump 2 control switch, HIS 1410, rotated clockwise to START.

COMMENT: SHOULD GET 11-5-B, CC PMI 2 FLOW LO.

CUE: None.

SAT UNSAT

6. PERFORMANCE STEP: Shift non essential loads to CCW Loop 2.

........C........

STANDARD: Push OPEN on HIS 5096, CC Line 2 disch isolation valve, HIS 5098, CC Line 2 return isolation valve, HIS 2649, CC Prom Aux. Bldg. to Line 2 isolation.

COMMENT: Sequence NOT required for thic block.

CUE: None.

SAT UNSAT

7. PERPORMANCE STEP: Isolate CCW Loop 1.

........C........

STANDARD: Puch CLOSE on HIS 5095, CC Line 1 disch. isolation valve, HIS 5097, CC Line 1 return isolation valve, HIS 2645, CC From Aux. Bldg. to Line 1 isolation valve.

COMMENT: Sequence NOT required for this bloch.

CUE: None.

SAT UNS A*t"

8. PERPORMANCE STEP: Check CCW Pump 1 for high temperature trip.

STANDARD: Check CCW temperature or check pump status lights.

CUE: Ncne.

SAT UNSAT TERMINATING CUES: This JPM is complete.

END TIME

. - - - =.

t i

JPM Ho. 14 Pig) 11 cf 11 VERIFICATION OF COMPLETION Operator Evaluator l

SSN _ Date 1,1censen ( ) RO [ } SRO validated Completion Times minutes Actual Completion Times minutes Acceptable Progress Maintained: Yes No N/A Result [j SATIBFACTORY [] UNbATISFACTORY NOTE: An " Unsatisfactory" requires Comment and will require subsequent remedial training.

Comments / Feedbacks

/

Evaluator's Signature Date

t NRQPUL. EXAM BANK PAGE: 3 !

FULL QUE0 TION QUERY DATE: 5/1G/97 Question Nbr.: OLC-5902 Question Type: E Category: J Point Values 1.00 Create Date: 05/12/95 Objective Number OLC-PWR-019-05Ys Keywords OLC SW Proc Ref/Rev/ Step DB OP-02000 TABLE 2- 04 '

DB.OP- 06261 (2. 2. 5) 02 Miscellaneous Reft Attachments

+

Action Indicators: REVIEW PROCEDURE CHANGE VALIDATE REVISE Exam last Used i KA Ratings e 076 000. A2.02 2.7/3.1 Comments : JPM 14 ,

Question State the automatic features and interlocks associated with SW 1395 and SW ~399 (TPCW heat exchanger service water supply header inolation valves) .

Answer:

References MAY be ust L

a. These valves will automatically close if respective SW header pressure (downstream) dropa (to 50 psig).

b. Close on an SA.2.

SAT /UNSAT

. z.l w

w-

NRQFUL EXAM BANK PAGE: 2 FULL QUESTION QUERY DATE: 5/16/97 Question Nt,.. OLC-5898 i Question Type: E Category: J Point Values 1.50 ' Create Date: 05/12/95 Object,1ve Number OL'-PWR 019-05K Keywords : OLC SW Proc ' Re f /Rev/St.ep t DB-OP.02000 TABLE 2- 04 DB-OP 02000 (4.5.2) 04 Miscellaneous Reft Attachments :

Action Indicators: REVIEW PROCEDURE CIUWGE VALIDATE REVISE Exam Last Used-KA Ratings 000 062 EK3.02 3.6/3.9 Comments : JPM 14 Odestion:

What are the specific auto start signals for a service water pump?

Answer References MAY be used.

1 SA Level 2 (without sequencer)

2. SA Level 2 and'UV (or automatic EDG supply of associated 4160 VAC bus) on the sequencer (step 4) 3.. ED0 breaker closure (with 40 second delay) with no SFAS SAT /UNSAT 4

, .,.-w - L. . . . , ;a , , - - ,. --, -

r

e 4

DAVIS BESSE NUCLEAR POWER STATION JOB PERFORMANCE MEASURE WORKSilEET J2M N04 : 57 Rev. 05 Page 1 of 6 TASK NO. . 004-000-04 0100 002-008-04-0100 TASK DESCRIPTION: Borate from Outside the Control Room K/A

REFERENCE:

000-024-EA1.02 (3.7/3.5), 000-024-EA1.04 (3.6/3.7),

000 024-EA1.17 (3.9/3.9) , 000-024-EA1.20 (3.2/3.3),

000-024-EA2. 02 - (3. 9/4.4)

AFPLICABLE METHOD OF TESTING: Simulate perfonnance In-Plant TIME FOR COMPLETION: 20 minutes APPLICA5JLI,II: [X) RO [X) SRO TASK STANDARDS:

1. Lineup for boric acid addition using local valves.

2. Start BA Pump 1.

REQUIRED NATERIALS:

DB-OP-06001, Boron Concentration Control, Revision 01, C-4 GENERAL

REFERENCES:

DB OP-06001,' Boron Concentration Control, Revision 01, C-4 INITIAL CONDITIONS:

The plant is in Mode 1 at 100% power. A load reduction to 50% power is planned.

INITIATIN9 CUES:

The normal boric acid addition method cannot be used. You have been directed to_ add 50 gallons _of boric acid to the MUT_from outside the CTRM using Boric Acid Pump 1, per DB-OP-06001.

Hand copy of DB-OP-06001 to examinee.

JPH 130. 57 P g3 2 cf 6 JNITIAL CONDITIONE:

The plant la in Mode 1 at 100% power. A load reduction to 50% power is planned.

1HIIIATJHG.CVES:

The normal boric acid addition method cannot be used. You have been directed to add 50 gallons of boric acid to the MUT from outside the CTRM using Boric Acid Pump 1, per DD OP-06001.

- -- . __.._ - =_ ..- ~ - - , = - . _ - - _ - - - - . _ . _ . - - . . - . -

JPM No. 57 Pcga 3 of 6 PERFORMANCE INFORadATION NOTE: Critical steps denoted with a "C". Failure to meet any one of these otandards for this item constitutes failure. Sequence is ,

assumed unless denoted in the acomments". !

START TIhE:

1. PERFORMANCE STEP Locate the. correct procedure section.

STANDARD: Identifies DB OP 06001, Boron Concentration Control, Section $.1, as the correct procedure section. j COMMENT: Provide correct procedure to examinee. When the correct ,

procedure section has been located, provide the CUE.

CUE: All prerequisites have been completed.

SAT UNSAT t

2. PERFORMANCE STEP: Verify Valves MU 348, Boric Acid Pump 1 Discharge, WC 393, Concentrate Storage Tank to MU Filters Line 2 _

and 394, from Concentrates Storage Tank to BAATs ;

l Discharge, are open.

STANDARD: Handwheel / stem position indicate OPEN.

COMMENT: Sequence is NOT required. ;

CUE: NU 348, valve stem is UP.

WC 394, valve stem is UP.

WC 393, valve otem is UP.

SAT UNSAT ,

3. PERFORMANCE STEP: Verify MU 351, Boric Acid Pump 2 to Makeup Filters open.

STANDARD: MU 351 stem position indicates OPEN. !

CUE: NU 351 valve stem is UP.

SAT UNAAT

4. PERFORMANCE S1EP: Close MU 363, BAAT 1 to Makeup Filters.

STANDARD:- Handwheel to the CLOSE position.

[- _ COMMENT: MU 363 located between BAATa-in CA. 1 CUE: NU'363 has been rotated clockwise / CLOSED; valve stem is DOWN.

SAT UNSAT e ,et -p-a- ee t r e wr w r---y- vv*----ymrmww-v'M#wa4fwg-T'mwyrvw-w'rw-w-y mm te*4y v e*=yv+ y *- er- P wtW 'gir-- **

, __ - _ - ,~ __ _ . _. .. _ _ _ . _ . . _ _ _ _

41H-No. 57. P:93 4 of 6 t

5. PERFORMANCE STEPS Open MU 36G, BAAT 2 to Makeup Filters.

........C....... ,

STANDARD: MU 366 handwheel turned (CCW) until FULLY OPEN.

CUE NU 366 handwheel has been rotated counterclockwise / OPENED) valve stem is UP.

SAT UNSAT

6. PERFORMANCE STEPS Start Boric Acid Pump 1.

........C........

STANDARD: BA pump 1 started using LOCAL pushbutton or started from control Room.

COMMENT: Either method is acceptable. ;

CUE: (If requested to START from Control Room), Control Roost Operator-has started BA Pump 1.-

(If Started Local), I,ocal START pushbutton for BA Pump 1 is pressed; RED light LIGHTS; ORIEN light goes OFF. ,

SAT UNSAT i

7. PERFORMANCE STEP: Stop Boric Acid Pump 1.

STANDARD: BA Pump 1 is stopped using either the LOCAL pushbuttons or from the control Room.

CUE: Control Room Operator reports that 50 gallons have been added to the NUT and BA Pump 1 has been stopped.

(If stopped LOCAL) LOCAL STOP pushbutton for BA Pump 1 is PRESSED; Green light LIGHTS, Red light goes OFF.

SAT UNSAT _ i

8. PERFORMANCE STEP: Close MU 366, BAAT 2 to Makeup Filters.

STANDARD: Rostore L/U, MU 366 handwheel turned (CW) until FULLY CLOSED.

CUE:- NU 366 handwheel has been rotated clockwise / CLOSED; Valve stem is DOWN.

The shift Supervisor directs you to restore the BA System lineup.

SAT UNSAT y ,,, r--- ,

,- -r- e -,---r.e e -.w- e y ey- r, - c t - - , - - - w

JPM !!o. 57 Pcga 5 of G

9. PERFORMA!JCE STEP: Open MU 363, DAAT 1 to Makeup Filters.

STANDARD: Restore L/U. MU 363 handwheel turned (CCW) until FULLY OPEN.

CUE: MU 363 handwheel has been rotated counterclockwise / OPENED valve stem is UP.

SAT UNSAT TERMINATIllG CUES: This JPM is complete.

END TIME I

l l

._ m _ .- ._ _... ._ . . _ . .. _ _ .... ._ _ _ . - _ m ._ _ _._____m._._.__.___. ._. . - _ _ . _ _ . _, _ _ .

JPN No. 57 Prg3 6 cf 6 a VERIFICAT10Af OF CORELET10Al )

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Operator Evaluator

]

t i

SSN- Date l l

1 License: [] RO ' ( ) SRO ; :

f

-j validated Completion Times -minutes -I l

, Actual completion Times minutes l

. Acceptable Progress Maintaineda Yes No N/A Results [ ] SATISFACTORY (-] UNSATISFACTORY NOTE: An " Unsatisfactory" requires Coment and will require ,

3 subsequent remedial training. l f

Comments / Feedbacks ,.

-1 p

I r

J 5

1 l :. -

/

Evaluator's Signature Date

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l NRQFUL EXAM BANK PAGE: 2-FULL QUESTION QUERY. DATE: S/28/97 ,

l Question Nbr.: OLC.7061 l

<Ouestion Type: E Category: J Point Value 1.00 Create Date: 05/12/95 I Objective Number : OLC.PWR.044 02K Keywords : MU/P OLC I

Proc Ref/Rev/ Step l Miscellaneous Ref 09 002 Sh.1 Rev.16 Attachments-Action Indicatorat REVIEW PROCEDURE CHANGE VALIDATE REVISE Exam Last Used i KA Ratings- -

004 020. A1.05 3.7/3.8 Comments : JPM 57 Question The following plant conditions exist Reactor power is 50%

Letdown flow is through #2 Mixed Bed Purification Demineralizer What-would be the effect (increase, decrease or remain the uame) on Pressurizer level and Makeup Tank level if MU 10B, Mix Bed 2 Letdown Inlet Isolation Valve was inadvertently closed? (30 minutes have elapsed with NO operator action)

Answers References MAY be used.

Prensurizer level would drop. (Due to an inter. system LOCA resulting from the lifting of the letdown relief valve.)

Makeup Tank level would' drop.

(Due to Makeup Pump still drawing water from the Makeup Tank,-but letdown water not replacing the =

water in-the Makeup Tank.)

SAT /UNSAT

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NRQFUL EXAM BANK PACE: 3 -i PULL QUESTION QUERY DATE: $/20/97 Question Nbr.: 0LC-7089 Question Types t Category: J Point Values 2.00 Create Date: 05/12/95

+

Objective Number : OLC-PWR-044 08K-Keywords : MU/P OLC r

Proc Ref/Rev/Stept DB.OP-06 006 (2. 2) 03 i Hiscellaneous Reft 08 002 (Cil G/CL 8/CL 10) Sh.1 Rev.16/Sh.2 Rev.15 and Sh.3 Rev.23 Attachments '

Action Indicators REVIEW PROCEDURE CHANGE VALIDATE REVISE Exam Last Used a KA Ratings 004-000. K1.22 3.4/3.7 Conwnents JPM 57 Questions For EACH.ONE of the following makeup tank levels,

-describe the AUTOMATIC actions associated with EACH:

1. 86 inches

2. 10 inches

3. 10 inchen Answere References MAY be used.

1. Transfers MUP suctiona (MU 3971 and MU.6405) to the MUT

2. Transfera MU 11 to the MUT

3. a. Transfers MU 3971 and MU 6405 to the BWST .

s

b. Starts 45 see timer

c. MUPc ' rips if xfor not complete W/I 45 see SAT /UNSAT l

l l :.

, - . _,-m..- _ _ , . . . , _ , , .4 - . - .- . , - . -.., _ . -

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DAVIS BESSE NUCLEAR POWER STATION JOD PERFORMANCE MEASURE WORKSHEET JPN No. 69 Rev. 06 Page 1 of 5 TASK MO.8. 063-006-01-0100 TASK. DESCRIPTION: Swap to a Swing Battery Charger ,

K/A

REFERENCE:

063-000 GEN.09 (3.1/3.3)

APPLICABLE METE 0D OF TESTING: Simulate performance ;

In plant TIME _FOR_.COWPLETION: 10 minutes APPLICABILITY: [X] RO [X) SRO TASK. STANDARDS:

1.

Perform all indicated breaker operations.

2. Position the output selector switch as indicated.

REQUIRED MATERIALS

.DB-OP-06321, 250/125 VDC Station DC Switching Procedure, Revision 01 9ENERAL. REFERENCES DB-OP-06321, 250/125 VDC. Station DC Switching Procedure, Revision 01 l

INITIAL CONDITIONS:

The plant:is'in Mode 1.' All systems are in a norma 1' lineup.

l -_

INITIATING CUESI-i ..

f The" Shift Supervisor directs you to perform a live transfer to place swing-l : battery charger DBC 1PN (which is lined up in STANDBY) in service for charger

!' DBC iP,.in accordance with DB OP-06321, ,

l. ;

Thore is .tig f ault' on charger DBC IP.

i (Hand examinee'a' copy of DB-OP-06321.)

1

- -- _; u ._. -

_ . _. _. . . . ~ . . . . . . _ . .. _ _ . _ . _ . _ _ _ , . . _ - _

JPM No. 69 P gs 2 of S l

IRInA1,Co#DITION5s The plant is in Mode 1. All systems are in a normal lineup.

IMITIATING_ CURS:

The Shitt Supervisor directo you to perforin a live transfer to place swing battery charger DDC 1PN (which is lined up in STANDBY) in service for charger DDC iP, in accordance with DB OP-06321.

There is !!Q f ault on charger DDC 1P.

l t

JPM No. 69 Pcg3 3 of 5 i

PERFORMANCE..INFORMATION i NOTE: Critical step =. denoted with a 'C". Failure to meet any one of ;

these standards for this item constitutes failure. Sequence is '

assumed unless denoted in the "Cemments".

- START TIME: .. i

1. PERFORMANCE STEPS. Locate the correct procedure.

3

. STANDARD' Hand procedure to examinee. Locates the cerrect procedure caction (4.3) .

CUE: None.

5$T wnT

2. PERFORMANCE STEP: Open/ verify open DC Output-Breakers D105 And D121.

STANDARD: Take handswitch to the OPEN position / visual indication.

CUE: D105 indicaten OFF/ TRIPPED.

D121 indicates OFF/ TRIPPED.

SAT UNSAT

3. PERFORMANCE STEP: Verify the AC INPUT ON/OFF switch for charger

........C........ DBC iPN is ON.

STANDARD: Visually verify ON.

CUE: (DBC 1PN AC Input) ON/OFF switch indicates ON.

SAT UNSAT

4. PERFORMANCE STEP: Verify stable voltage on battery charger DBC 1PN.

STANDARD: Voltmeter P2-202 on battery charger DBCIPN reads between 130V and 140V, CUE: Voltage reads 132V and stable.

SAT UNSAT 4

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-JPM No,.69 Pago 4 of 5 i

5. PERFORMANCE STEP: Set the DC Transfer switch to Position 1.

........C........

STANDARD: Place output selector switch in the *1" position.

CUES Handswitch has been placed in Position '1". !

SAT UNSAT l

6. PERFORMANCE STEP: Close DC output Breaker D105. !

........C........

i STANDARD: D105 placed in ON position.

COMMENT: E.7 is posted in LVSR #1 if confusion exists at this step.

CUE: (D105) Breaker has boon placed in ON position.

BAT UNSAT

7. PERFORMANCE DTEP: Open DC Output Breaker D103. l

........C........

STANDARD: D103 placed in OFF/TRIPPRD position. :

CUE Breaker (D103) has been placed in OFF/TRIPPRD.

SAT UNSAT TERMINATING CUES: This JPM is complete, r

END T'IME i P

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JPN No. 69 P:gs 5 of 5 l t

- VERIFICATIM OF CQBEFLETI0tf !

'I t

l

' operator. Evaluator !

- i SCW Date ,

h Licenses- . ( ) RO

[ ) SRO -

s 1

.. Validated Completion Times minutes ;

. Actual completion Times minutes '

i-t

- Acceptable Progress Maintained: '

Yes No N/A r

Results [ ] BATISFACTORY- [ } UNSATISFACTORY NOTE: An " Unsatisfactory" requires Comment and will require i subsequent remedial training. i Comments / Feedbacks h

)

T

+

l Evaluator's Signature Date t'

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NRQFUL EXAM 11ANK PAGE: 4 FUL!, QUESTION QUERY DATE: 5/28/97 Question Nbr.: ONL 0577 Question Type: E Category: J Point Value 1.00 Create Date: 05/12/95

' Objective Number . OPS SYS.409-05K OPS-SYS.409-07K Keywords : IDC OLC ONL Proc Ref/Rev/Stttp Hiscellaneous Reft OS-060 CC 1 Rev.12 Attachments a '

Action Indicators: REVIEW PPOCEDURE CHANGE VALIDATE REVISE ,

Exam Last Used : '

r.A Ratings : 063-000 GEN.09 3.1/3.3 Comments : JPM 69 Question:

What are three (3) indications that the LOCAL battery charger panel provides to the operator when an EQUALIZER charge is in progress?

Answers References MAY be used.

Ar.y 3 of the following:

. Red EQUALIZE CHARGE light is LIT The equalizer timer is running.

. FLOAT / EQUALIZE switch is in the EQUALIZE position.

. DC output. voltage raises to the Equalize Charge setting SAT /UNSAT yy , + y ,ge- y ^ " '

Tv

- e e NRQFUL EXAM BANX PAGE: 5 FULL QUESTION QUERY DATE: 5/28/97 ,

Question Nbr.s ONL 0606 Question Types E Category: J . Point Values 1.00 Create Date: 05/12/95 Objective Number : OPS-SYS-409 09K Keywords : IDC OLC ONL

= Proc Ref/Rev/ Step DB OP-02521 (4.1.6) 01 Miscellaneous Ref:

Attachments :

Action Indicators: REVIEW PROCEDURE CHANGE VALIDATE REVISE Exam Last Used i KA Ratings : 000 057 EK3.02 4.1/4.4 Comments : JPM 69 Question:

What purpose is served by performing selective battery load shedding per Attachment 5 of DB-OP.02521, Loss of AC Bus Power Sources, upon a loss of BOTH 4160 VAC essential busses?

-Anawers References MAY be used.

Allows longer use of the station batteries by removing loads no longer necessary for orderly control of the station.

SAT /UNSAT End of Report

. .,. . . . _ _ _ . . _ _ . - _. ...., _. _. .__..__m.- __ .._ _. _ . . . _ . _ - - ,_ _

JPM No. 1008 P:g3 6 cf 12 i

pIgotAToa IusrRUCTIoMs j TA81LR95CRIPTION:

Reset a Spurious SFAS Level 1 Actuation ZMIIIAL.CONDITIOM Any Mode 3.and above with SFAS normal. '

i ADDITIONAL SETUP /DEVIAI19JLFROM IMITIAL CONDITION:

- Trip CDfT RADIATION HIGH TRIP bistable in SFAS Channel 1 and 2. I MALFUNCTIONS /FA4 LURE TO. INSERT:

None.

ACT10MLCUE8s None..

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F

DAVIS.BESSE NUCLEAR POWER STATION JOB PERFORMANCE MEASURE WORFJHEET ilPM NO t 1008 Rev. 05 Page 7 of 12 TASK No.: 013 017-01-0100 l

~

TASK DESCRIPTION: ~ Reset a Spurious SFAS Level 1 Actuation E/1JEFERENCE: 013-000 A4.02 (4.3/4.4).

APPLICAELE METHOD OF TESTING: Simulate performance Simulator TIME FOR COMPLETION: 17 minutes APPLICAEILITY: [X] RO (X] SRO TASK STANDARDS: ;

1. SFAS Channel 1 bistablu reset

2. SFAS Channel 2 bistable left tripped

3. SFAS output modules reset REQUIRED MATERIALS DB-OP-06405, Safety Features Actuation System Procedure, Revision 02, C5 GENERAL

REFERENCES:

DD-OP.06405, safety Features Actuation System Procedure, Revision 02, C-5 LER 90-007,90-008 INITIAL CONDITIONS:

You are the apare RO.

SFAS Channel 2 CTMT radiation bistable is inoperable and manually tripped.

-SFAS Channel 1 CTMT radiation spiked and tripped, causing a spurious Level 1 SFAS actuation.

INITIATING CUES:

The-Shift Supervisor directs you to reset SFAS Channel 1 per DB-OP-06405.

I.

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-. , . . ~ . - . . _ - . . . - . _ - _ - , _

JPM No. 100D Pags 8 of 12 IMITIAL CONDITLQES:

You are the apare RO.

SFAS Channel 2 CTMT radiation bistable is inoperable and manually tripped.

SPAS Channel 1 CTMT radiation spiked and tripped, causing a spurious Level 1 SFAS actuation.

TNITIATING CUES:

The Shift Supervisor directo you to reset SFAS Channel 1 per DB-OP 06405.

. . . .. - .~. -. - . - . . - - . - . . - . . - - - - - . . . . - . . , ~ . . ~ _ - - . . - . - -

t JPM No. 100D Pega 9 of 12 I

PERFORMANCE INFORMATION t

NOTE: Critical steps denoted with a 'C'. Failure to meet any one of these standards for this item constitutes failure. Sequence is assumed unless denoted in the 'Commentsy.- i START TIME:

~1. PERFORMANCE STEPS Locate the correct procedure and section.

STANDARD: - Identifies DB.OP-06405, Safety Features Actuation System Procedsre, Subsection 3.7, as the correct procedure and (

section. !

CUE: None. (If asked, SS directs you to circle Channel 1. No. steps should be N/Aed due to inoperable components.) [

t BAT UNBAT ~

2. PERFORMANCE STEPS Obtain the door keys for all four SFAS channels.

-STANDARD: SFAS cabin". '- btained.

CUE: None.

SAT UNSAT

3. PERFORMANCE STEP: Verify power to SFAS channels co be reset.=

. STANDARD: Visual check of red power lights lit at top of Channel 1 SFAS i

. cabinet. '

l CUE: None.

1 SAT UNSAT 5

4 '. PERFORMANCE STEP: Check the shutdown bypass power available green LEDs on Channel I cabinet are lit. i STANDARD: Visual check of green LED on each S/D bypass section.

CUE: None.

SAT UNSAT l

2,., :.

J' M Ho. 100B Page 10 of 12

5. PERFORMANCE STEP: Reset the Channel 1 CTMT radiation high trip bistable

........C........ and verify TRIP light goes out.

STANDARD: Depress the RESET pushbutton on the CTMT RADIATION HIGH TRIP bistable in Channel 1.

CUE: None.

SAT UNSAT

6. PERFORMANCE STEP: Reset the tripped output modules in all SPAS channels.

........C........

ST/NDARD: Depress the RESET pushbutton on all tripped output modules in all four SFAS channels.

COMMENT: Two output modules in each SFAS channel.

CUE: None.

SAT UNSAT

7. PERFORMANCE STEP: Verify output modules reset.

STANDARD: Visual check of each output module, TRIP light OFF.

CUE: None.

SAT UNSAT

8. PERFORMANCE STEP: Verify SFAS cabinet doors closed and locked.

STANDARD: Doore CLOSED and LOCKED.

CUE: None.

SAT UNSAT

9. PERFORMANCE STEP: Return the SFAS door keys.

STANDARD: Door keys returned to key cabinet.

CUE: None.

SAT UNSAT

JPM Ho. 200D PE94 11 of 12

10. PERFOPJ4A!1CE STEP: Restore SFAS Equipment.

STA!!DARD: Go to DB OP-06910. Trip Recovery.

COMMENT: Do NOT have the examinee go to this procedure.

CUEr This shift Supervisor will coordinate the restoration of SFAS equiomont.

SAT tRISAT TERMINATING CUED: This JPM in complete.

END TIME

JI'M No. 100 P:ga 12 of 12 VERIFICATION OF COMPLEILQB Operator Evaluator SSN Date License: ( ) RO () SRO validated Completion Times minutes Actual completion Times minuten Acceptable Progress Maintained: Yes No N/A Resultn () SATISFACTORY [ ] UNSATISFACTORY NOTE: An " Unsatisfactory" requires Comment and will require subsequent remedial training.

Comments / Feedback:

/

Evaluator's Signature Date

HROFUL EXAM BANK PAGE: 2 FULL QUESTION QUERY DATE: 6/2/97 Question Hbr.: OLC-7354 Question Type: E Category: J Point Values 2.00 Create Date: 05/12/95 Objective Number : OLC-PWR-051-06K Keywords : 000 syAs Proc Ref/Rev/ Step DD-oP-06405(ATT.2) 02 Hiscellaneous Ref:

Attachments :

Action Indicators: REVI EW PROCEDURE CHANGE VALIDATE REVISE Exam bast Used i KA Ratings : 013-000- A3.02 4.1/4.2 Comments : JPM 100 Question:

Safety Actuation Monitor (SAM) lights relay information to the operator via four (4) difforent indication conditions. Describe each condition AHQ what each condition means. (Include all possibilities for each position.)

Answer References MAY be used, cot!DITIotl gmg

a. OFF - a. 1. No SPAS trip.

2 SFAS trip and equipment did not actuate.

b. DIM - b. SFAS trip and equipment actuated.

c. BRIGilT - c. SFAS trip and equipment actuated then blocked by operator.

d. BRIGitT d. SFAS trip ari equipment and FLASilING . actuateJ, b2ocked by operator, and placed in non-SFAS position.

SAT /UNSAT

,+ . .

NRQFUL EXAM BANK PAGE: 4 FULL QUESTION QUERY DATE: 6/2/97 Question Nbr.: OLC-8347 Question Type: E Category: J 'roitit Value 1.00 Create Date: 01/01/93 ,,

Objective Number . OPS-FHT-104-04K Koywords : HVAC-RW Proc Ret /Rev/ Step Miscellaneous Ref: OS-33D Attachments : NO actaon Indicators: REVIEW PROCEDURE CHANGE VALIDATE REVISE Exam Last Used :

% Ratings : 013-000-GEN.04 3.7/3.8 /

i Comments : JPM 100 f

Question:

It SPAS Level 1 actuated at the same time that RE 8446 and 8447, Fuel Handling Exhaust System Radiation Monitors alarmed, to where would the Station EVS align itr suction?

Answer: '

Referances MAY be usee The Station EVS would align to the negative presti.re areas (Annulus. ECCS Rooms, MPRs. MUP Room).

SAT /i?NSAT End of Report

I INITIAL SUBMITTAL OF SCENARIOS FOR DAVIS-BESSE EXAM h

3 s

E I - - -

Id ES-301 Scenario Events Form ES-301-3 Simulation Facility: Davis Besse Scenario No.- 1 Examiners: Applie: ants :

Initial Conditions: 100% Power. BOL ( IC #27),

Turnover: Normal Operatino Condition <3 with no eauinment out of service.

The Load disoatcher has iust accroved Powgr reduction to 50% Power for Water Box cleaninc. The shift is to start olant cower reduction to 50%

Dower at 3 MWe/ min in orecaration for condenser water box cleaninc. _

Event Malf. Event Event No. No. Type

Description 1 R Power Reduction to 50% Power 2 MS-11 I Selected Hdr Press Instrument fails to 600 psig 3 MUP-12 C Operating Makeup Pump trips dug to shaft seizure.

4 MS-02 M Steam leak intitiated in CTMT which increases to line rupture causing major overcooling

(N) ormal, (R)eactivity, (I)nstrument, (C)omponent. (M) aj or Chief Examiner:

r l

Page 2 of 9 I. INTRODUCTION A. GENERAL DESCRIPTION This guide starts with a power reduction from 100% TO 50% to prepare for condenser water box cleaning. During the - power reduction the selected steam header pressure instrument will fail to zero which will cause turbine throttle valves to close to attempt to restore pressure and consequently a reduction in turbine load. .Once the trubine has been placed in manual and the plant is stabilized, tne operating makeup pump will trip due to a shaft seizure. After the standby makeup pump is started, an unisolable steam leak develops in CTMT. Once the plant is tripped to blew down the affected OTSG, the steam leak becomes a steam line rupture which causes a major overcooling.

ES-301 Operator Actions Form ES-301-4 Scenario No.: 1 . Event No.: 1 Page 3 of 9 Event

Description:

Power redustion to 50% reactor power Time Position Applicant's Actions or Behavior SRO Holds brief und reviews actions per DB-OP-06902, Power Operations. Notifies SOC in Cleveland that power reduction has started to 50% power at 3MWE per minute. Directs reactor operator to decrease power IAW DB-OP-06902, Power Operations.

RO Reduces setting on Unit Load Demand, sets rate of change. Monitors power decrease to ensure correct equipment performance.

BOP Monitors turbine, generator, matches AC and DC voltage regulator output as turbine load decreases.

)

l I

ES-301 Operator Actions Form ES-301-4 Scenario No.: 1 Event No.: 2 Page 4 of 9 Event

Description:

At 93% cower, selected steam header oressure fails to 600 noio over 5 minutes.

l Time Position Applicant's Actions or Behavior RO/ BOP Announces ICS INPUT MISMATCH Alarm 14-4-E. I SRO Directs RO or BOP to SASS rack. Refers to and takes actions per DB-OP-02014, Alarm Panel 14.

RO/ BOP Checks SASS rack, identifies failed instrument as SP-PT16B SRO Directs t ng turbine to Manual. May direct TBVs and/w AVVs to Manual if needed to control pressure. (May) Direct placing SG/RX HAND / AUTO Station to HAND. Refer to DB-OP-06407, NNI System Operataing Procedure, Attachment 7, for effects of instrument failure.

BOP Select Alternate Turbine Hdr Pressure Instrument SP-PT16A. Contact E&C to troubleshoot instrument selected.

SRU Direct returning the following stations to AUTO using DB-OP-06401, Integrated Control System Operating Procedure.

a. Main Turbine at EHC pnl in CTRM

b. TBVS and AVVs (if taken to Manual)

c. SG/RX HAND / AUTO STATION Continue the power reduction if still greater than 50% Power or, if less than 50% power direct power increase to 50% pwr.

ES-301 Operator Actions Form ES-301-4 Scenario No.: 1 Event No.: 3 Page 5 of 9 Event

Description:

_Oneratino Makeun Pumn Trins Due to Shaft Seizure Time Position Applicant's Actions or Behavior ALL Announce Seal Injection Low Alarm.

RO Recognize and announce the previously operating Makeup Pump is not running.

Recognize Pressurizer level decreasing SRO Implement DB-OP-02512, Loss of RCS Makeup.

SRO/RO IF PZR Level falls below 160 inches, THEN trip the reactor and route to DB-OP-02000 "RPS, SFAS, SFRCS Trip or SG Tube Rupture.

RO Isolate letdown by closing MU 2B. Isolate seal injection by reducing demand to 0 in HAND on FIC MU 19. Isolate makeup by reducing den and to 0 in HAND on FIC MU 32.

SRO REFER TO DB-OP-02515, RCP and Motor Abnormal Procedure, for limitations on RCP operation without seal injection.

BOP Verify CCW supply to RCPs. Monitor RCP seal return temperatures.

ALL Maintain constant power until the Makeup pump is restcted or a power reduction is procedurally directed.

SRO Ask the SS to consult Tech Specs.

RO Align standby MU pump to an adequate source.

Start the standby MU pump before PZR level decreases below 160 inches:

a. Start AC oil pump, verify proper ops.

c. Start the MU pump,

d. Restore MU flow

e. Restore RCP seal injection

f. Restore letdown when Pzr. level is restored.

ES-301 Operator Actions Form ES-301-4 L

Scenario No.: 1 Event No.: 4 Page 6 of 9 Event

Description:

Steam .'.eak initiated in CTMT which increases to line ruoture causina maior overcoolina.

Time Position Applicant's Actions or Behavior ALL Identify symptoms of a steam leak in containment:

a. Reactor power increase with MW load decrease.

b. Increased FW flow

c. Decrease in Tave, RCS press, Pzr level

d. Increase in CTMT Temp, Press and sump levels SRO Implement DB-OP-02525, Steam Leaks.

SRO Verify no one in CTMT.

RO Place the running CACs in slow speed, verify SW valves to CACs wide open.

SRO Direct operators to commence a plant Shutdown per DB-OP-02504, Rapid Shutdown BOP Notify Load Dispatcher RO Place SG/RX DEMAND in HAND, decrease load to 203 MWe.

Attempt to maintain Axial Pwr Imbalance between 0 and -10% using the APSR's and/or boration.

BOP Request Chemistry to monitor Condensate Polisher operation and prepare to sample RCS for an isotopic analysis of Iodine.

During the load decrease:

Transfer station electrical loads, align the MDFP to MFW. Direct an EO to start the Aux Boiler.

ES-301 Operator Actions Form ES-301-4 Scenario No.. 1 Event No.: 4 (cont) Page 7 of 9 Event

Description:

Steam leak initiated in CTMT which increases to line ninture causina ma-ior overcoolina.

nm.

Time Position Applicant's Actions or Behavior RO Maintain MUT level between 55" and 86".

BOP Stop one condensate pump when flow is less than 7.0 MPPH if three pumps are running.

At 675 MWE direct an EO to open MS 338 and MS 353.

At ~600 MWE verify high load valves closed and direct EO to decrease low load valves per curve CC.7.10 of misc curve book.

When Condensate flow is less than 3.5 MPPH stop all but one running condensate pump.

Prior to the first SG going or. low level limits, place the Delta Tc controller in HAND at O.

ALL Recognize increase in steam leak severity.

SRO Implement DB-OP-02000, RPS, SFAS, SFRCS Trip or SG Tube Rupture.

DB-OP-02000 IMMEDIATS ACTIONS (SECTION 3)

RESPONSE

RO Manually trip the reactor, verify power decreasing on the Intermediate Range.

BOP Manually trip the turbine.

RO If PZR level drops below 40", isolate letdown by closing MU-2B and verify all PZR heaters off.

SRO Verify Immediate Actions.

ES-301 Operator Actions Form ES-301-4 Scenario No.: 1 Event No.: 4 (cont) Page 8 of 9 Event

Description:

Steam leak initiated in CTMT which increases to line ructure causina maior overcoolina.

Time Position Applicant's Actions or Behavior l SUPPLEMENTARY ACTIONS (SECTION 4) RESPONSE ALL check for control rods inserted.

BOP Check for turbine trip.

RO Check for NNI power available. '

Check for ICS power available.

Check for C1/D1 busses energized with no EDG's running.

BOP Check for instrument air available. Check for secondary systems response.

Establish one condensate pump t w eation.

Check for SFRCS isolation trip.

Verify normal RFR control of MFW to BOTH SGs.

Establish one MFP in operation.

RO Check for Makeup System operation.

Transfer BOTH MU pump suctions to the BWST, and press OFF for each switch.

Start second MU pump.

Set PZR level controller to 100 inches.

Ensuro MU flow rising if level is below setpoint.

BOP Check for SFAS actuations.

Check for SFRCS actuations.

Check for adequate subcooling margin.

Check for lack of heat transfer.

Check for overcooling. Recognize overcooling has occurred.

SRO Route to DB-OP-02000, Section 7,

" Overcooling".

ES-301 Operator Actions Form ES-301-4 Scenario No.: 1 Event No.: 4 (cont) Page 9 of 9 Event

Description:

Steam leak initiated in CTMT which increases to line ruoture causino ma-lor overcoolina.

Time Position Applicant's Actions or Behavior _

OVERCOOLING (SECTION 7) RESPONSE RO Restore / maintain Pzr level at 80"-120".

Isolate letdown if Pzr level decreases below 40".

BOP Check for SFRCS actuation throughout overcooling cause determination. IF SFRCS trip is present, THEN:

a. Verify proper response per Table 1.

b. Route to proper step for the SFRCS trip present.

SRO Direct check for proper SFRCS for trips present as directed by step 7.14 RO Note both SG levels are not rising as per step 7.16 check.

SRO Route to step 7.23, Verify proper AFW to good OTSG, then route to step 7.29 RO Verify proper feeding of the non-icolated SG.

BOP Maintain proper SG level in the available SG at 49" per Specific Rule 3 (55" after low l pressure SFRCS actuates).

ALL Check for overcooling. Crew recognizes overcooling stops when affec'.ed OTSG boils dry.

TERMINATION CRITERIA OTSG #2 has boiled dry, crew making preparations to cooldown plant with one OTSG i

1 I

ES-301 Scenario Events Form ES-301-3 Simulation Facility: Davis Bense Scenaric No.: 2 Examiners: Applicants:

Initial Conditions: Plant Startun in Proaress with Turbine Load at 110 ,

MWE. (IC 41)

Turnover: Power Increase to 35%. Your shift is recoverina from a olant transient that has left the olant at - 20% oower. Your shift is to take

. tin plpnt-to 35 % nower where snecific Turbine vibration readinos are to be taken.

Event 'Malf. Event Event No. No. Type

Description 1 R Plant Power Increase to 35% Power and lift off low $

level limits 2 SG-06 I Startup level instrument for fi2 OTSG fails low 3 SW-01 C SW Pump til shaf t seizure 3 SG-01 C OTSG tube leak requiring plant shutdown 4 SG-01 M OTSG tube leak becomes a tube rupture

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Chief Examiner: _ _

1

Page 2 of 12 I. INTRODUCTION A. GE14ERAL DESCRIPTION This guide starts with a plant startup in progress at approximately 20%

power with plans to increase power to 35%. After the plant is in full Automatic and just .af ter both OTSGs have come of f Low Level Limits, Startup Level' instrument for the #2 OTSG will fail to 0 inches which ,

will'cause an overfeed condition in-the #2 OTSG. After the plant is '

stabilized the Service Water pump supplying the secondary loads will trip, requiring the crew to start the standby pump. Once the standby pump-is started a OTSG tube leak will develop. =This tube leak will become a tube rupture over time.

4

i ES-301 Operator Actions Form ES-301-4 Scenario No.: 't Event No.: __L _. Page 3 of 12 Event

Description:

Plant Power Increase to 35% Power and lift off low level limito Time Position Applicant's Actions or Behavior SRO Holds brief and reviews actions per Db-OP-06bd2, Power Operations. Notifies SOC in Cleveland that power increase has started to 35% power at 3MWE per minute. Directs reector operator to increase power I AW . DB-OP- 06 9 02, Power Operations.

RO Raises setting on Unit Load Demand, sets rate of change. Monitors power increr3e to ensure correct equipment performance.

BOP Monitors turbine, generator, matches AC and DC voltage regulator output as turbine load increases.

l l

ES-301 Operator Actions Form ES-301-4 Scenario No.: 2- Event No.: 2 Page 4 of 12 c Event

Description:

Startun level instrument for #2 OTSG fails low Time- Position Applicant's Actions or Behavior ALL Diagnose a failure of #2 OTSG S/U level transmitter low:

Ann 14-4-E ICS INPUT MISMATCH.

Ann 12-4-B SG 2 LVL LO Increasing FW flow on FW Loop 2.

SRO Direct ROs to place SP 7A, SP 6A' and both FW loop demands in hand.

BOP Place SP 7A, SP 6A and both FW Loop Demands in hand.

SRO Route to DB-OP-02014, MSR/ICS Alarm Panel 14 Annunciators (Can route directly to DB-OP-02526, Steam Generator Overfill)

ALL Recognize that an OTSG overfill condition has or had occurred SRO Route to DB-OP-02526, Steam Generator Overfill Verify that placing #2 MFW Startup Valve ,SP 7A, #2 MFW Regulating Valve, SP 6A and both FW loop demands in hand terminates overfill.

SRO Route to DB-OP-06407, Non Nuclear Instrumentation System Operating Procedure is referred to prior to selecting good instrument.

BOP Select good SG 2 Startup Level Instrument.

Place #2 MFW Startup Valve ,SP 7A, #2 MFW Regulating Valve, SP 6A and both FW loop demands in automatic per DB-OP-06401, Integrated Control System Operating Procedure.

ES-301 Operator Actions Form ES-301-4 Scenario No : 2 Event No.: 3 Page 5 of 12 Event

Description:

SW Pumo #1 shaft seizure Time Position Applicant's Actions or Behavp r ALL Recognize symptoms of loss of SW Pump 1.

(Computer alarm P945, SW LOOP 1 HDR PRESS)

RO Announces Loss of #1 W pump.

SRO Route to DB-OP-02511, Loss of Service Water Pumps / Systems LOSS OF SERVICE WATER PUMPS / SYSTEMS, DB-OP-02511 RESPONSE SRO Dispatch EO to investigate relay targets on tripped SW pump breaker.

Verify CAC 1 is OFF Close SW 1366 BOP Verify CT 2955 open Verify a CCW Pump on CCW loop 2 Verify non-essential CCW loads on CCW Loop 2 as follows:

Verify open CC 5096 - Supply Verify open CC 5098 - CTMT Bldg. Return Verify open CC 2649 - Aux Bldg Return.

Monitor Generator Cold gas temp. If temp increases to 113*F, decrease Turb load.

Dispatch EO to open SW valves for TPCW coolers Restore flow to SW Loop 1 by placing the # 3 Service Water Pump in service.

SRO Direct dispatch of EO to perform Attachment 1,

3 Service Water Pump to SW Loop 1 Lineup RO/ BOP Start SW pump # 3 when correctly lined up.

1 ES-301 Operator Actions Form ES-301-4 Scenario No.: 2 Event No.: 4 Page 6 of 12 Event

Description:

OTSG tube leak reauirina plant shutdown ,_ _

Time Position Applicant's Actions or Behavior ALL Recognize symptoms of OTSG tube leak High activity on condenser off-gas radiation monitors.

High activity on main steam line radiation monitor RE 609.

SRO Route to DB-OP-02531, OTSG Tube Leak.

Steam Generator Tube Leak - DB-OP-02531 RO Check pressurizer level If PZR level decreases below 100 inches, trip the reactor.

SRO Route to DB-OP-02000 "RPS, SFAS, SFRCS Trip or SG Tube Rupture."

RO Isolate Letdown.

Maximize RCS inventory.

Verify PZR level control and MU-32 is open.

Start second makeup pump.

ALL Identify leaking SG as #1.

RO/SRO Steam line rad, monitor RE-609.

Dispatch Rad Con Tech. to survey Steam lines.

Chemistry

ES-301 Operator Actions Form ES-301-4 Scenario No.: 2 Event No.: 5 Page 7 of 12 Event

Description:

OTSG tube leak becomes a tube ruoture Time Position Applicant's Actions or Behavior RO Determine leak rate.

a. Use Attachment 1, steps 1, 2, and 3.

SRO Consult Tech. Spec. 3.4.6.2 for RCS leakage limits and actions.

Determine emergency classification (made at end of scenario).

Initiate plant response activities,

a. Notify chemistry to perform Attachment 2 and report results to SS.

b. Notify Rad. Prot, personnel to perform Attachment 3 and report results to SS.

c. Direct an EO to perform Attachment 4.

ALL Recognize increase in leak rate.

a. Pressurizer level response.

b. Pressurizer pressure response.

c. OTSG level response.

SRO Route to DB-OP-02000, RPS, SFAS, SFRCS TRIP or SG Tube Rupture.

DB-OP-02000 IMMEDIATE ACTIONS (SECTION 3)

RESPONSE

ALL Check for SGTR.

SRO Route to Section 8.

DB-OP-02000, SGTR RESPONSE (SECTION 8, NO TRIP)

I ES-301 Operator Actions Form ES-301-4 Scenario No.: 2 Event No.: 5 (cont) Page 8 of 12 Event

Description:

OTSG tube leak becomes a tube ruoture Time Position Applicant's Actions or Behavior RO If Pressurizer Level decreases below 100 inches, trip the reactor and return to section 3.

Perform the following for RCS inventory control:

a. Verify Letdown is isolated.

b. Lock MU 3971 and MU 6405 in the BWST position.

c. Start the second Makeup Pump,

d. Open V'I 6421.

e. Control MU 6419 and MU 32 to maintain PZR level.

Place SG/Rx Demand in hand and insert control rods as rapidly as possible without causing any cross limits or reactor trip.

ALL Perform or continue performance of Attachments 2, 3, and 4 of DB-OP-02531, SG Tube Leak.

Identify the leaking SG using MS line radiation monitors SRO Direct EO to startup the Aux. Boiler.

a. Transfer Gland Steam,

b. Transfer Aux. Steam.

ALL Lineup and initiate piggyback operation.

a. Start the non-running CCW pump.

b. Start HPI pumps.

c. Open HPI injection valves HP 2A, 2B, 2C, 2D.

d. Start LPI pumps.

e. Open DH 63 and 64.

RO Transfer station electrical loads.

I I

ES-301 Operator Actions Jorm ES-301-4 Scenario No.: 2 Event No.: 5 (cont) Page 9 of 12 Event

Description:

OTOG tube leak becomes a tube rupture Time Position Applicant's Actions or Behavior When both SG levels are back on Low Level Limits, perform the following:

RO Reduce SG/Rx demand to zero.

BOP Place SG1 Feedwater Demand and SG2 Feedwater Demand in HAND and reduce demands to zero.

Place TBV's in HAND rnd transfer steam load from the Turbine.

RO If TBVs are fully open place Rx Demand H/A station in HAND and reduce power RO/ BOP When generator load is < 50 MWe:

Trip the reactor and turbine with TBVs in hand.

Establish auto steam header control via TBVs SRO Route to Section 3 step 2.

DB-OP-02000 IMMEDIAi'E ACTIONS RO Manually trip reactor.

Verify power decreasing on Intermediate Range.

BOP Manually trip turbine.

RO Isolate letdown by closing MU 2B (MU3 alternate), when PZR level drops below 40",

and verify PZR heaters are off.

SRO Verify Immediate Actions.

SUPPLEMENTARY ACTIONS (SECTION 4) RESPONSE 1

1

l

{

ES-301 Operator Actions Form ES-301-4 Scenario No.: 2 Event No.: 5 (cont) Page 10 of 12 Event

Description:

OTSG tube leak becomes a tube ructure j Time Position Applicant's Actions or Behavior RO Check for control rods inserted.

BOP Check for turbine trip.

RO/ BOP Check for NNI power available.

Check for ICS power available.

Check for C1/D1 busses energized with no EDG's running.

Check for instrument air available.

BOP Check for secondary systems response.

a. Establish one condensate pump operation.

b. Check for SFRCS isolation trip.

c. Verify normal RFR control of MFW to BOTH SGs.

d. Establish one MFP in operation.

RO Check for Makeup System operation.

a. Transfer BOTH MU pump suctions to the BWST, but do not press OFF for each r switch.

b. Start second MU pump,

c. Set PZR level controller to 100 inches.

d. Ensure MU flow rising if level is below setpoint.

RO/ BOP Check for SFAS actuations, f

BOP Check for SFRCS actuations.

RO/BCP Check for adequate subcooling margin.

BOP Check for lack of heat transfer.

Check for overcooling.

t

. .y- ._ _ _ __ _ _.. _ _ _ __.. _ . _ _ _ . _ -

'ES-301 Operator Actions Form-ES-301-4 Scenario No.: 2 Event:No.:- S (cont) -Page-11 of 12 Event

Description:

-0TSG' tube leak becomes a tube ruoture Time Position Applicant's Actions or Behavior SRO Route to Section 8, Step 7 for SGTR.

DB-OP-02000, SGTR RESPONSE

~RO Piggyback MU/HPI if not already dor.a.

a. Verify Makeup Pump suctions.are LOCKED onto the BWST.

b. Start non-running CCW pump,

c. Start HPI pumps 1 and 2

d. Open HPI Injection Valves HP 2A, 2B, 2C,

.2D.

e. Start LPI pumps 1 and 2

f. .Open DH 63 and 54 SRO/ BOP Determine RCP availability.

ALL Verify proper SG levels, using Specific Rules.

Begin cooldown and depressurization with RCPs running,

i. RO Depressurize the RCS to near minimum SCM and refill 1the pressurizer.

a. Turn off.all PZR heaters,

b. If RCS Pressure is being manually controlled, then block SFAS.

c. Use PZR Spray to reduce RCS pressure to maintain near minimum adequate subcooling margin.

d. Allow HPI and MU to recover PZR level and maintain PZR level 80" to 120".

ALL Begin'cooldown.and depressurization to Th of 500*F and 1000-psig at 100*F/hr and maximum spray-flow.

Use' TBVs on both sides. If SFRCS was 4

actuated, use AVVs on both' sides.

_.__L.__._ _L____________. , , , . . . . . _ . . . . . , _ . . , . . . , _ _ . . - , , ~ ~ . . . , . , _ . , . _ , , , y. , , ,_.. ,

I ES-301 Operator Actions Form ES-301-4 Scenario No.: 2 Event No.: 5 (cont) Page 12 of 12 Event

Description:

OTSG tube leak becomes a tube ructure Time Position Applicant's Actions or Behavior ALL Maintain close to minimum subcooling margin until RCS reaches 1000 psig then maintain RCS

@ 980-1020 psig.

BOP Block SFRCS when permitted. If required, increase steaming rate of ruptured SG to attempt to keep the level below 2:35" .

IF level exceeds 240 inches, Stop steaming and isolate the affected SG.

SRO SS-A: Classify the event per RA-EP-01500.

CONDITIONS AT TERMINATION Plant in a controlled cooldown and depressurization. Tave moving toward 500*F at approx. 100*F/ hour.

RCS pressure decreasing to between 980 and 1020 psig.

Ruptured SG isolated and level > 240 inches, or still steaming and level < 225 incher. 4 Temperature being controlled with TBVs or AVVs.

I 1

1 i

ES-301- Scenario Events Form ES-301-3 Simulation Facility: Davis Besse Scenario No.: 3 Examiners: Applicants:

Initial Conditions: Plant is at 50% Power followina recairs to 2 Main Feed Pumo. No other eauioment is oos (IC 30)

Turnover: Plant is at 50% Power for the cast week for #2 MFP reoairs.

2 Main Feed Pumo was returned to service last shift and is now in full automatic. The load disoatcher has reauested the olant be returned to full power. There is no eauioment oos. There are no olanned purveillance tests.

^4 Event Malf. Event Event No. No. Type

Description 1 R Increase in plant power following repairs to Main Feed Pump Turbine bearing.

2 MFW-11 C Restarted Main Feed Pump bearing fails and MFW-01 requires a manual trip 3 PZR-10 I Selected pressurizer level instrument fails high 4 RCS-02 M Small RCS leak develops which becomes a LOCA causing loss of SCM 0 (N)ormal, (R) eactivity, (I)nstrument, (C) omponent , (M)ajor Chief Examiner:

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Page 2 of 10 I. INTRODUCTION- ~t )

A. GENERAL DESCRIPTION .V q This scenario starts with the plant commencing a load increase from 50% .' ] i Power. The # 2 Main Feed Pump will have a bearing failure which will require a manual trip of the feed pump and a plant runback. After the 1l plant runs back the celected Pressurizer Level instru.aent will fail ' '

high. One the crew has responded to the Pzr level instrument failure a small RCS leak will occur which will degrade to a LOCA which will result .

in a loss of Subcooling Margin-i i

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l ES-301 Operator Actions Form ES-301-4 Scenario No.: 3 Event No.: 1 Page 3 of 10 Event

Description:

Increase in nlant nower followina repairs to main feed Dumo turbine bearina. _.

Time Position Applicant's Actions or Behavior SRO Holds brief and reviews actions per DB-OP-06902, Power- Operations. Notifies SOC in Cleveland that power increase has started at 3MWE per minute. Directs reactor operator to increase power IAW DB-OP-06902, Power Operations.

RO Raises setting on Unit Load Demand, sets rate of change. Monitors power increase to ensure correct equipment performance.

BOP Monitors turbine, generator, matches AC and DC voltage regulator output as turbine load increases.

i ES-301 Operator Actions Form ES-301-4 Scenario No.: 3 Event No.: 2 Page 4 of 10 Event

Description:

Restarted main feed oumo bearino fails and recuires a manual trip.

Time Position Applicant's Actions or Behavior ALL Recognize high vibation a' arm 10-3-E.

SRO Refer to DB-OP- 02010. Directs to have an EO check Local Vibration Panel and to check pump locally.

ALL Verify proper plant runback after pump trips

ES-301 Operator Actions Form ES '01-4 Scenario No.: 3 Event No.: 3 Page S of 10 Event

Description:

Selected oressurizer level instrument fails hiah Time Position Applicant's Actions or Behavior iLL Recognize PZR level failed high and announce alarm 4-3-E PZR lvl High.

RO Places MU 32 in HAND restore MU flow SRO Routes to DB-OP-02004 and then DB-OP-02513 PZR LVL FAILED HIGH DB-OP-02513, PRESSURIZER SYSTEM ABNORMAL OPERATIONS RO Compare other PZR instruments and select a good instrument Place MU 32 in AUTO ALL Recognize the symptoms of a Small RCS leak

-RCS MU Flow increasing

-CTMT Sump level increasing

-CTMT Radiation levels increasing SRO Route to DB-OP-02522, Small RCS leaks

ES-301 Operator Actions Form ES-301-4 Scenario No.: 3 Event No.: 4 Page 6 of 10 Event

Description:

Small RCS leak develoos which becomes a LOCA causina loss of SCM.

Time Position Applicant's Actions or Behavior DB-OP-02522, SMALL RCS LEAKS RESPONSE Monitor Pressurizer level, if less than 100 inches, then perform the following:

RO Trip the Reactor.

SRO Route to DB-OP-02000, RPS, SFAS, SFRCS. Trip or SG Tube Rupture RO Verify Pressurizer level is being maintained.

Monitor Makeup Pump discharge pressure Monitor Makeup Tank level, attempt to maintain the Makeup Tank level between 55" and 86".

Letdown may be isolated if desired or directed by SS/SS-A.

ALL Locate and control the leak area as follows:

Observe control room indications.

Contact Rad Con supervisor to perform appropriate Rad surveys and control affected area access. Announce the evacuation of potentially hazardous leak areas.

Walk down accessible portions of RCS connected systems.

Evaluate recent plant conditions and the need to disable CTMT Normal Sump Pumps.

Attempt to isolate the source of the leak by performing Attachment 1 of DB-OP-02522 Determine RCS leak rate.

SRO Direct a Rapid Shutdown.

ALL Commence a Rapid plant shutdown in accordai.ce with DB-OP-02504, Rapid Shutdown.

i

ES-301 Operator Actions Form ES-301-4 i '

Scenario No.: 3 Event No.: 4 (cont) Page 7 of 10 Event

Description:

Small RCS leak develoos which becomes a LGOA causina

,_lpas of SCM.

Time Position Applicant's Actions or Behavior ALI. DB-OP-02504, " Rapid Shutdown" RESPONSE BOP Notify Load Dispatcher RO Place SG/RX DEMAND in HAND. g Decrease load to 203 MWe, Attempt to maintain Axial Pwr Imbalance .

between 0 and -10% using the APSR's and/or boration.

SRO Request Chemistry monitor Condensate Polisher operation and prepare to sample RCS for an isotopic analysis of Iodine.

, During the load decrease:

RO Transfer station electrical loads.

BOP Align the MDFP to MFW, Direct an EO to start the Aux Boiler.

RO Maintain MUT level between 55" and 86".

BOP Stop one condensate pump when flow is less than 7.0 MPPH if three pumps are running.

At 675 MWE direct an EO to open MS 338 and MS 353.

At ~600 MWE verify high load valves closed and direct EO to decrease low load valves per curve CC.7.10 of misc. curve book.

When Condensate flow is less than 3.5 MPPH otop all but one running condensate pump.

Prior to the first SG going on low level limits, place the Delta Tc controller in HAND at O.

ALL Recognize increase in RCS leak severity.

1

t ES-301 Operator Actions Form ES-301-4 Scenario No.: 3 Event No.: 4 (cont) Page 8 of 10 Event

Description:

Small RCS leak develoos which becomes a LOCA causino loss of SCM.

Time Position Applicant's Actions or Behavior SRO Implement DB-OP-02000, RPS, SFAS, SFRCS Trip or SG Tube Rupture.G.

DB-OP-02000 IMMEDIATE ACTIONS (SECTION 3)

RESPONSE

RO Manually trip the reac x Verify power decreasins an the Intermediate Range.

BOP Manually trip the turbine.

RO If PZR level drops below 40", isolate letdown by closing MU-2B and verify all PZR heaters off.

SRO Verify Immediate Actions.

SUPPLEMENTARY ACTIONS (SECTION 4) RESPONSE ALL Check for control rods inserted.

BOP Check for turbine trip.

RO/ BOP Check for NNI power available.

Check for ICS power available.

Check for C1/D1 busses energized with no EDG's running.

Check for instrument air available.

BOP _ Check for secondary systems response.

Establish one condensate pump operation.

Check for SFRCS isolation trip.

Verify normal RFR control of MFW to BOTH SGs.

Establish one MFP in operation, i

1

l l

l ES-301 Operator Actions Form ES-301-4 Scenario No.: 3 Event No.: 4 (cont) Page 9 of 10 Event

Description:

Small RCS leak develoos which becomes a LOCA causino loss of SCM.

Time Position Applicant's Actions or Behavior RO Check for Makeup System operation.

Transfer BOTH MU pump suctions to the BWST, and press OFF for each switch.

Start second MU pump.

Set PZR level controllel to 100 inches.

Enaure MU flow rising if level is below setpoint.

RO/SRO Check for SFAS actuations. RCS 1650 PSIG Trip Verify proper SFAS Incident Level 1 and 2 actuation using Table 2.

Verify letdown isolated.

RO Attempt to close RC11, PORV Block Valve.

Close RC10, PZR Spray Block Valve.

, When minimum SCM is lost then trip all RCPs.

Verify HPI System is operating properly using Specific Rules 1 and 2.

BOP Check for SFRCS actuations, verify proper SFRCS Actuation.

Check for adequate subcooling margin.

Recognize loss of SCM SRO Route to DB-OP-02000, Section 5, Inadequate SCM.

I. LACK OF ADEQUATE SCM RESPONSE RO Verify all RCPs tripped.

Control MU/HPI per Specific Rules 1 and 2.

l l

l ES-301 Operator Actions Form ES-301-4, Scenario No.: 3 Event No.: 4 (cont) Page 10 of 10 j Event

Description:

Small RCS leak develoos which becomes a LOCA causinct I loss of SCM.

l Time Position Applicant's Actions or Behavior BOP Re-verify SFRCS response per Table 1.

Re-verify AFP status and proper OTSG level control at 124" per Specific Rules 1 and 3.

Check for overcooling.

RO Isolate possible leaks.

PORV/PORV Block Letdown Spray / Spray Block PZR Sample lines Loop high point vents Check for Inadequate Core Cooling.

Check for adequate SCM. Recognize that Subcooling Margin is restored or being restored. Throttle makeup HPI to maintain SCM.

Restore forced flow (restart RCPs).

SRO Route to step 5.16 to restore forced flow TERMINATION CRITERIA SRO Start directing crew to restore RCPs

. - . . ~ . .- . __ - -. . .. -.- .

1 INITI AL SUBMITTAL OF WRITTEN: EXAMINATIu'N FOR DAVIS-BESSE 5

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.* ANUM: -

4

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FAC= D346 i

'*RTYP .. PWR B&W177 4

EXLEVEL S

EXMNR 'FACILITYL

~

0 VAL- 1.0

SEC ,

-* SUBS 0RT--

KA' 194001A103 .

0VESTION Which ONE of the following statements-identifies the requirements for relief of-'

- the- R0 P by an R0 from relief shift during a shift : to allow the. relieved '

individual to participate in unannounced drug scraening? (Permission has been-1 2 granted by the CTRM SRO.)

a. If the relief attended shift turnover, he needs ONLY to document the transfer of responsibilities in the Unit Log.

' b. If the relief attended shift-turnover and is currently signed into the Unit Log as an R0. an additional entry needs to be made in the Unit Log documenting the transfer of the R0 function.

~

c. If the' relief did NOT attend shift turnover, he must, as a MINIMUM, walkdown the CTRM panels with the off-going R0, discuss evolutions in progress, notify the CTRH SR0 and sign into the Unit Log.

d. If the relief did NOT attend the shift turnover, then he must perform a~ complete shift turnover- per DB-0P-001_00, Shift Turnover and sign-into the Unit Log as a R0.

ANSWER' '

d -

REFERENCE-0P-00000 (6.3.2)-R3

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s*FAC . - 346-

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EXLEVEL' S

EXMNR. FACILITY--

0VAlc 1.01 1

SEC

SUBSORT '

KA- 194001A106

- *00ESTION::

When a task ~ listed on the Monthly Activity Log (MAL) is NOT a rformed Jsatisfactorily, the places an X in the initial block and prepares Jcomments on that zone's MAL Comment Sheet.

a.- Shift Manager or Reactor Operator b, ' Assistant Shift Supervisor or responsible Zone Operator

c. Shift Supervisor or. Reactor 0perator- *

d. -Shift Supervisor _ or SR0 designee- -

ANSWER d

c'

REFERENCE DB-0P 00003 (6,2.5) R2 r

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ACHANGED FALSE

0DATE 1997/07/11-

FAC 346

RTYP PWR-B&W177

EXLEVEL S -

EXMNR- FACILITY

0 VAL 1.0

SEC

SUBSORT '

rA - 194001A108

00ESTION An estimated critical rod position (ECP) has been calculated for a reactor startup that is to be performed 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after a trip from a 60 day full power run. Which ONE of the following events or conditions will result in the actual critical rod position being lower than the ECP?

a. The main steam header pressures are decreased by 35 psig just prior to criticality,

b. The startup is delayed for approximately 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ,

c. A new boron sample shows a current boron concentration 20 ppm higher than that used in the ECP calculation.

d. Steam generator feedwater addition rate is reduced by 5 percent just prior to criticality.

ANSWER a

REFERENCE

-.DB-NE-06201 R3 DB-NE-06202 (5.2) R1

.i .

*ggg ;

HNUM~

(* ANUM- :

0 CHANGED!. FALSE- 1 f*ACHANGEDF FALSE;. :

00 ATE .1997/07/11:. - = ,

'*FAC: 346-- .

RTYP. ~PWR-B&W177~ ,

i EXLEVEL - S

EXMNR ~ FACILITY.

. 0 VAL 10

SEC

-*SUBSORT

?*KA . 1194001A116 ;

00ESTIONz . . . .

^The Shift Supervisor has declared an Alert In the absence of the. Emergency

~

Director.-the Shift Supervisor will turn over the role of Emergency Director to

~

the who is-stationed in the .

a. . Emergency Assistant _ Plant Manager: Emergency Control Center

h. Energency Assistant Plant Manager: Technical Support Center

c. Emergency Plant Manager: Emergency Control Center d- Emergency Plant Manager: Technical Support Center

ANSWER.

d-

REFERENCE

- E-PLAN. 5.2.1.c '

f 6

i

.b 4

C.

c.

i-

+

+ +e < s . . . , ., .- . - - , , . - - - . - , - -

l j

1

0NUM !

HNUM

ANUM

0 CHANGED FALSE

ACHANGED FALSE

00 ATE 1997/07/11

FAC 346

RTYP PWR-B&W177

EXLEVEL S

EXMNR FACILITY

0 VAL 1.0 SEC

SUBSORT '

KA 194001K101

0UESTION According to the general isolation guidelines outlined in DB-0P-00016. Removal and Restoration of Station Equipment, in order to isolate a Main Feed Pump the sequence should be ,

a. 1. Isolate the steam supply.

2. Iselate the suction line.

3. Vent and drain the pump.

4. Isolate the auxiliary systems,

b. 1. Isolate the discharge line.

2. Isolate the steam supply.

3. Isolate the suction line.

4. Isolate the auxiliary systems, c, 1. Isolate the discharge line.

2. Isolate the recirculation line.

3. Isolate the suction line.

4. Vent and drain the pump,

d. 1, Isolate the steam supply.

2. Isolate the recirculation line.

3. Isolate the auxiliary systems.

4. Isolate the discharge line.

ANSWER-c

REFERENCE DB-0P-00016 (6.1.1) R2

?

l l

0NUM-

HNUM-

ANUM

0 CHANGED FALSE

ACHANGED FALSE

0DATE 1997/07/11

FAC 346

RTYP PWR B&W177

EXLEVEL_ S-

EXMNR FACILITY

0 VAL 1.0

SEC

SUBSORT'

' *KA 194001K102

00ESTION

- Which ONE of the following MAY NOT be perforned using a temporary lift of a safety. red tag? -

a. Racking a circuit breaker into the test position while the breaker ir still required for personnel protection.

b. Fan belt running checks,

c. A leak check of a piping system.

d. Installing a megger test unit into a load breaker cubicle.

ANSWER a-

REFERENCE DB-0P-00015 (6,13) R4 5

cj

_ 0NUM

-*HNUM

ANUM

0 CHANGED. FALSE

ACHANGED -FALSE

00 ATE 1997/07/11

FAC 346

RTYP PWR-B&W177

EXLEVEL . S

EXMNR FACILITY.

0 VAL 1.0

SEC

SUBS 0RT

KA 194001K103

00ESTION.

The dose rate in Mechanical Penetration Rcom (MPR) 3 is at the limit for an area

. posted as a Radiation Area. Which DNE of the following is the exposure an operator will receive if he works in MPR 3 for 50 minutes?

a. 2.5 mrem

b. 50 mrem

c. 100 mrem

d. 500 mrem

ANSWER b

REFERENCE DB-HP-01100 (6.3) R2

. . . . , .- _ - . - - . _ . . - - _. _ ..-. ._.. . _ ~ _ _ . _ .

't .l i

, ;;; = :: :

=

0NW -

HNUM' .

(*ANUH:-.. .

.-. *0 CHANGED FALSE:

, *ACHANGEDi FALSE' ;

~ *00 ATE: 1997/07/11 - ,

FAC

--346 ~

RTYP PWR-B&W1'/7

EXLEVEL

S -- '

EXMNR: FACILITY .-

0 VAL- l '. 0

.SEC- -

SUBSORT - .

KA s194001K104

00ESTION - -- ,. -

.Which:0NE of the following represents an administrative limit established at -

Davis-Besse to ensure regulatory limits are NOT-exceeded? -;

- a. 2.0 R/ year TEDE from work at DBNPS only - .

- b.- 4;0.R/ year TEDE from work at DBNPS only

- c. 1.0 R/ year TEDE from ALL~occupati ,aal sources

' d. 2.0 R/ year TEDE from_ALL' occupational sources-

ANSWER d

REFERENCE DB-HP-01201 (6.2, R3 b

)

I " '

~

+

v_w.- 4 y . , . - . - - > ~ - + - - , - , , ,....-m-, , w E ~.

0NUM

HNUM

1. 1UM

0 CHANGED' FALSE

ACHANGED FALSE

00 ATE 1997/07/11

FAC. 346-

RTYP PWR-8&W177

EXLEVEL S

EXMNR FACILITY

0 VAL 1.0

SEC

SUBS 0RT

KA 194001K105

0 VEST 10N The Emergency Key Locker, located in the CTRM, may be utilized as plant conditions dictate and as approved by the Assistant Shift Supervisor,

a. Shift Supervisor, or Shift Supervisor Administrative Assistant

b. Reactor Operator, or Shift Supervisor

c. Shift Supervisor, or Shift Manager d ._ Shift Supervisor, or Nuclear Security Sh, Supervisor

N1SWER c

REFERENCE 08-0P-00000 (6.20.1) R3

+

, . _ . _. - . . . . _ . . . - -. _ ._ _ - . ._ _ ._. . - . - m A- ,_ g.

g. "-'. _ , ?

- * .i

~

0NUM-

-*HNUM

-*ANilM_

"*0 CHM 40ED "fitSE L*ACHANGED' ' FALSE -

x*00 ATE'- L1997/07/11-

FAC !346- .

'*RTYP -

-PWR-B&W177,

EXLEVEL S- s

EXHNR- FACILITY

0 VAL- -1.0

-*SEC - >

SUBSORT- :

KA 194001K107

'*0VESTION- _

A surveillance test has just been completed and restoration includes.the racking out'of a 4160 VAC breaker and the removal of control power fuses. The individual -

? assigned .to perform the racking evolution shall be qualified as at-least an and should remove any metal objects hanging from his belt due-to the

potential shock hazard from .

- a. -Auxiliary Operator: 120 V'C A

~ b. Auxiliary Operator: 125 VDC

- c. Equipment Operator I: 120 VAC

. . d. Equipment Operator I: 125 VDC

ANSWER

d-

REFERENCE DB-0P-01_000 (2.1.2/2.1.4) R1 _

~

1 4

( -

d

~.

,4 y .sq : '4.',--y

- - - _ ,, e-- g , , y , -. 4 , .- .,., a , _

, . - ,, .; . . . . -. -- . . - -. .. . - . -. . . ~

-y 0 ,

F L*(pg .

?HNUH:

t s* ANUM .

i

- :*0 CHANGED- FALSE l

-'ACHANGED FALSE! ;

-*00 ATE- 1997/07/11T

*FAC'- -3461

RTYPi PWR-B&W177

EXLEVEL: -S-

EXMNR- FACILITY-

'*0 VAL- cl.0

SEC-~ ,

SUBSORT L*KAL .

194001K115 :

QUESTION Limit and Precautioni2.2.6 of DB-0P 06210, CO2 and: Hydrogen Procedure, states-- -

~

t

.that ". . . if. Hydrogen purity drops to below 908, the Generator must be shut-

down and the Hydrogen purged out with CO2." The reason for this requirement is

a. the reduced-purity creates the possibility of an explosive mixture. <

Lof hydrogen in air -_

b. the Seal Oil Syste.n pressure regulator will not function properly at reduced purities

c. reduced- purity will ' result in inefficient operation of the main

' generator due to' increased friction

-the stator cooling water inlet pressure regulator will not function

~

d ,-

properly at reduced purities

ANSWER a .

D 0-(2.2.6) R0

.c .

5

, y

.- [ . h ,,

*0NUM' --

HNUM; -

-j

ANUH' - -

1

0 CHANGED LFALSE':

1*ACHANGED 1 FALSE:

00ATEi ?1997/07/11

FAC'. 346

.RTYP PWR-B&W177'

- *EXLEVEL- S-

-*EXMNR- FACillTY

0 VAL 1.0 ,

SEC: '

SUBSORTL L*KA' .

194001K116

0VESTION An HOURLY Operating Specification Fire. Watch (OSFW) in EDG Room #2 has been >

- ongoing for 3 days when it is discovered that the individual responsible for

>erforming the fire watch has NOT checked the firewatch post for 95 minutes.

Which ONE of the: following describes the action that should be l' 1EDIATELY

. performed per 08-FP-00009. Fire Protection Impairment and Firewatch?

a. -Process _a PCAOR and notify the Manager. Plant Operations.

b. Contact Security to have a card reader check of the area performed.

c. Contact Security to post a continuous fire watch.

d. Proceed to the firewatch-post- and perform the fire watch.

ANSWER

d

REFERENCE

- DB FP-00009 (6.5.1) R5 e

p r 1 I '

W

0NUM

HNUM

ANUM

0 CHANGED FALSE

ACHANGED FALSE

00 ATE 1997/07/11

FAC 346

RTYP PWR-B&W177-

EXLEVEL S

EXMNR FACII.ITY

0 VAL 1.0

SEC

SUBSURT

KA- 194001A107

0UESTION OPERATOR AIDS, as described in DB-0P-00004. Operator Aids Control, .

a, are always considered CONTROLLED documents and, therefore, can take the place of approved procedures

b. are usually considered INFORMATION ONLY documents and, therefore, can NOT take the place of approved procedures, unless otherwise specified

c. should always be considered as requirements and, therefore, should be strictly adhered to

d. can be used as a temporary alteration to an approved procedure until the procedure has undergone the alteration process

ANSWER b

REFERENCE DB-0P-00004 (6.1) R2

- . . - . . -. . .~ .- _ - . . . .- ~-- ....- ._ ,

1 - -

7:

-l s , _

1

[

0NUMi c*HNUM.

ANUM <

1*0 CHANGED - FALSE-

. -*ACHANGEDL FALSE? .

m ^

00 ATE- s1997/07/11

FAC 346;

+

L*RTYP. .- PWR-B&W177 -

EXLEVEL ::S: -.

EXMNR FACILITY

.0 VAL. 1.0= 1

-*SEC- !

SUBSORT

KA .- - -194001A114 :

QUESTION The specific activity of the primary coolant has exceeded Technical Specification L limits and a reactor shutdown and cooldown to-less than 530 deg F Tavg has been Mrformed; . Which ONE 'of:the-following is the basis for coo'Iing the Reactor r Coolant System to less than 530 deg F?

a. Allows the iodine to react with the metal in the ' Reactor Coolant

- System minimizing-the release of iodine activity in the event of a LOCA.

- b. Seals the fuel cladding failure thereby reducing the amount - of

- activity released to the coolant and containment in the event of a LOCA.

c, Prevents the release of activity should a steam generator tube rupture occur since the: saturation pressure of the Reactor Coolant System is.below the lift pressure of the main steam safety valves.

d. Minimizes the amount of corrosion and erosion of the Reactor Coolant '

_ System and- the fuel elements caused by the increase of iodine activity _and particulate in the coolant.

ANSWERL L c

REFERENCE

?T;S. 3.4;8. Bases 9

s -

e i \

W

. q .- ,to.. . c, u ..

. . . , - ,. .- , y ,

0NUM

HNUM

ANUM

0 CHANGED FALSE l

ACHANGED FALSE 1

00 ATE 1997/07/11 l

FAC 346- !

i

RTYP .PWR-B&W177

EXLEVEL S

EXMNR. FACILITY

0 VAL 1.0

SEC

SUBSORT

KA 194001A115

0UESTION The following plant conditions exist:

- During a plant startup a heat balance is performed at 55% power.

The results of this calculation agree with indicated NI power.

After power is increased to 95%, a NEW heat balance calculation does not agree with indicated NI power.

Which ONE of the following describes the tXPECTED relationship between indicated NI power and calculated power and the reason for the difference?

a. Indicated NI power will be less than calculated power due to the decreasing steam generator superheat region.

b. Indicated NI power will be less than calculated power due to the decrease in Tcold water temperature.

c. Calculated power will be less than indicated NI power due to increased ambient losses,

d. Calculated power will be less than indicated NI power due to an increase in Tcold water tcmperature.

ANSWER b

REFERENCE DB-0P-02504 (4.1.10) R2 DB-PF-06703 (C.C.6.9) R3

0NUM

HNUM

N4UM -

0CHN4GED FALSE

ACHANGED FALSE

00 ATE 1997/07/11

FAC 346

RTYP PWR-B&W177

EXLEVEL- S

EXMNR FACILITY

0 VAL 1.0

SEC

SUBSORT

KA 194001A116

QUESTION Upon declaration of a Tornado WARNING. which ONE of the following describes the required status of the Emergency Diesel Generators (EDGs)?

a. Idle speed operation

b. C1 or 01 parallel operation

c. C1 and D1 parallel operation d, Isolated bus operation on C1 and 01 (AC110 and A0110 open)

ANSWER a

REFERENCE RA-EP-02810 (6.3.1) R0 1

p i

0NUM h-

HK M ,

~

4

ANUM -

, i*0 CHANGE 0 . FALSE

~*ACHANGED ~ FALSE --

1*00 ATE -1997/07/11

FAC ^346 -

1

RTYPs . PWR-B&W177::

EXLEVEL

S

EXMNR-- . FACILITY:

0 VAL 1.0<

SEC-

=

SUBSORT-

KA - . 001000K105

0UESTION

< Given the following conditions:

. -- The lant'is operating at 80% power ,

All lant systems are operatinq normally i

- A. loss of power to 120 VAC i.=sential Power

-- Panel Y2 has.just occurred What;is the expected effect on the RPS system?

a, RPS_ Channel' 1 will-trip and CR0 Breaker B will open

- b. RPS Channel I will trip and all- CR0 Breakers will open

c. RPS Channel 2 will trip and CR0 Breaker A will open

d. RPS Channel 2 will trip and all CRD Breakers will open ~

ANSWER c

REFERENCE OB-0P 06403 (0.4.1) R1 1-'

e i t. ,_

1-h, 4- x ..- < . . - _ , . . _ . -

l

0NUM

HNUM

ANUM

0 CHANGED FALSE

ACHANGED FALSE

00 ATE 1997/07/11

FAC 346

RTYP PWR-B&W177

EXLEVEL S

EXMNR FACILITY

0 VAL 1.0

SEC

SUBSORT

KA 003000K305

0UESTION Which ONE of the following automatic responses will result from the loss of RCP 1-1 (Loop 1) while at 85% power? (All systems are in automatic control with FOUR RCPs initially operating.)

a. A runback to 75% ULO at 20% per minute and the affected loop SG being on low level limits

b. Tave input to ICS from Loop 1 selected and delta Tcold near zero.

c. Reactor power reduced to less than 75% and the ICS upper load limit automatically reset to 80%.

d. A 2.4:1 ratio of SG feed flow and the ICS in a runback to 75% at 20%

per minute.

d

REFERENCE DB-0P-06401 (4.9.4) R2 DB-0P-02515 (4.1.2) R1

'l

CNUM

HNUM

NJUM

0 CHANGED FALSE

A. CHANGED FALSE

0DATE 1997/07/11 .

FAC 346 I

RTYP PWR B&W177

EXLEVEL S

EXMNR FAllllTY

0 VAL 1.0

SEC

SUBSORT

KA 004000A205

0UESTION The following plant conditions exist:

- 72% RTP RCP 2 2 secured due to oil cooler leak Due to Hakeur System operating problems the following Reactor Coolant Pump parameters are observed with the exception of pump 2-2 which is NOT running:

1-1 1-2 2-1 Seal Rtrn Temp 180 deg F 185 deg F 175 deg F Seal Inj Flow 2.4 gpm 3.5 gpm 2.7 gpm Seal Rtrn Flow 1,.8 gpm 2.0 gpm 1.5 gpm Seal Diff Press 600 psid 5d0 psid 650 psid Which ONE of the following actions is required because of the above Reactor Coolant Pump indications?

a. TRIP the reactor, STOP the 2-1 Reactor Coolant Pump, GO TO 08-OP 02000 RPS. SFAS, SFRCS Trip or SG Tube Rupture,

b. TRIP the reactor, STOP the 1-2 Reactor Coolant Pump, GO TO DB-OP-02000, RPS, SFAS, SFRCS Trip or SG Tube Rupture

c. REDUCE reactor power to 45%, STOP the 2-1 Reactor Coolant Pump, verify proper feedwater flow ratios and transfer of Tave control, o, REDUCE reactor power to 45%, STOP the 1-2 Reactor Coolant Pump, verify proper feedwater flow ratios and transfer of Tave control.

ANSWER b

REFERENCE DB CP-02515 (4,1.3) R1

0NUM

HNUM

ANUM

0 CHANGED FALSE

ACHANGED FALSE

00 ATE 1997/07/11

FAC 346

RTYP PWR-B&W177

EXLEVEL S

EXMNR FACILITY

0 VAL 1.0

SEC

SUBSORT

KA 004010K403

QUESTION Which ONE of the following describes a design aspect of the letdown portion of the Makeup and Purification System?

a. The RCS inlet valve (MulA or 1B) to EACH letdown cooler OPENS AFTER and CLOSES BEFORE the coolers CCW supply valves (CC1409 or 1410).

b. The letdown line is sized to limit a LOCA outside containment to within the capacity of ONE makeup pump.

c. The letdown HIGH temperature isolation (160 deg F) isolates all letdown flow except 3 gpm to RE1998 (Failed Fuel Monitor).

d. The letdown coolers )rovide TWO primary functions, cooling of the letdown fluid and N-,6 decay.

N4SWER a

REFERENCE OS 002. Sh. 1 (CL 2) R16 I

0NUM

HNUM

ANUM

0 CHANGED FALSE

ACHANGED FALSE

0DATE 1997/07/11

FAC 346

RTYP PWR B&W177

EXLEVEL S

EXMNR FACILITY

0 VAL 1.0

SEC

SUBSORT

+KA 013000K101

0VESTION A plant heatup from COLD SHUTDOWll 15 in pr@ ress, Which DNE of the following describes the consequences of the o.erators failing to HANUALLY RESET any of the SFAS RC PRESSURE LO LO TRIP bistab es as the plant heats up?

a. An SFAS trip will initiate at approximately 450 psig,

b. An SFAS trip will in'tiate at approximately 600 psig.

c. An SFAS trip will initiate at approximately 1650 psig.

d. The plant will be without low pressure SFAS protection until the bistables are manually reset.

ANSWER b

REFERENCE DB-0P-06900 (4.62) R4 l

I

0NUM' i

LINUM -

ANUM .

0 CHANGED FALSE'

ACHANGED -FALSE i

00 ATE 1997/07/11-

FAC- -346 ,

RTYP PWR B&W177

EXLEVEL S -

EXMNR- FACILITY

0 VAL .1.0 L*SEC- .

t

SUBSORT

KA- 013000G006 i

0VESTION , -

At DBNPS, the Emergency Core Cooling Systems are designed such that .

l t

a. CFTs w111' provide a sufficient volume of borated water to be forced !

into the Rx-vessel at less than 600 psig in the RCS ;

b. above 200 deg F, two independent ECCS subsystems are required to t ensure sufficient core cooling even in the event of a single failure

c. Trisodium Phosphate loaded-into baskets in CTMT will ensure a post-LOCA pH of less than 3.0

d. the BWST water volume and boron concentration are sufficient to i maintain post-LOCA CTMT pH between 5.0 and 13.0, which will minimize the evolution.of Xenon gas -

ANSWER a

REFERENCE ,

T.S. 3/4.5 Bases 4-V 1

I

.i i

$ s. w , e4Wy et-U--p--Muw r,y.,, w ,,,,,.c,,,_cy y- g-g. yy ,, , , am ,..- w g. ., e9-e.,- p,r9-- g ,,.ra< ee,r,-m w- ew-eww=w

0NUM '

HNUM .

ANUM , x

0 CHANGED FALSE ! '

ACHANGEO FALSE

+00 ATE 1997/07/11

FAC 346

RTYP PWR B&W177

EXLEVEL S

EXHNR FACILITY

0 VAL 1.0

SEC

SUBSORT

rA 014000A104

0UESTION The following plant conditions exist:

- The plant is operating at 100% power.

- Reactor Engineering reports that the results of yesterday's incore flux map indicate that Control Rod 4-1 is fully insertea inte the core.

CTRM API for Rod 4-1 indicates 100% withdrawn.

CTRM RPI for Rod 41 indicates 100% withdrawn.

Which ONE of the following actions should be pcrformed?

a. Declare the rod inoperable and reduce power to less than 60% while evaluating,

b. Trip the reactor and GO TO DB-0P-02000,

c. Declare the rod inoperable and remain at 100% power while evaluating,

d. Commence a rapid shutdown to HOT STANDBY and GO TO DB-0P-02504.

Rapid Shutdown.

ANSWER a

REFERENCE DB 0P-02516 (4.1.4) R3

~ ,. . . . . _ . - -

.y, f ,

"Ie l

Qi

'M e 4 ANUM

0CliANGED FALSE

ACHANGED FALSE

0DATE 1997/07/11-

FAC 346

RTYP PWR.B&W177

EXLEVEL S

EXMNR FACILITY

0 VAL 1.0

SEC

SUBSORT

KA 015000A202

0 VEST 10N Which ONE of the following is an indication that Intermediate Range NI-3 is OVER-compensated, during a reactor startup?

a. NI 3 reads 3 E-6 amps NI 4 reads 8 E 7 amps

b. NI-1 and 2 read 8 E+5 cps NI 3 reads 2 E 11 amps

c. N1 1 and 2 read 3 E+4 cps NI-3 reads 8 E-11 amps

d. NI 3 reads 5 E-11 amps NI-4 is not on scale

ANSWER b

REFERENCE DB 0P-06912 (4.21.3) R1 ,

r

- -- -s. - - . .--- r. -m-, ,

i

) . $

, i 8

g

HNUM. l

..'* ANUM

0 CHANGED FALSE- !

ACHANGED FALSE -i i

00 ATE: 1997/07/11

FAC- 346

RTYP -. i PWR B&W177

EXLEVEl. S

EXMNR- LFACILITYJ i

0 VAL 1.0. -l

- *SEC- !

SUBSORT i

KA -015000G005; .:

0UESTION:.. -

l The following plant conditions exist':- j

- Reactor power-is 50%.- - -

1

- BOTH Intermediate Range (IR) NI detectors have failed HIGH. '

- The IR-detector-. repairs will take 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months to complete.

Which ONE of the following actions must be performed?

a. POWER OPERATION may continue, but power must be maintained greater :

than 5%.

b.- POWER OPERATION may continue with no limitations. !

. c. Within ONE hour action must-be taken to place the unit in COLD .

SHUT 00WN with Rx trip breakers open within the next 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months ,

d. Within ONE hour actions must be taken to place the unit in-HOT STANDBY with Rx' trip breakers open within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . !

ANSWER l

-d

,

REFERENCE :

-T.S. Table 3.3-1 !

T.S. 3.0.3-r i

1 i

I s ,

4 - + , . - - - . . , , _ . . . . . ~ , , , _ _ . - . - . . ~ . _ . , ,

. . - - . . . _ . - . , - , . _ . - . ~ . . _ . , . - . - _ _ . _ _ . - _

3

0NUM I

HNUM ,

i

ANUM

0 CHANGED FALSE .

ACHANGED FALSE

00 ATE 1997/07/11 ,

fAC 346

RTYP PWR B&W177

EXLEVEL S

EXMNR FACILITY

0 VAL 1.0

SEC :

SUBSORT

KA 017020A202

0 VEST!0N The )lant has experienced a LOCA. Plant conditions are such that the upper portoon of the core may be uncovered. Which ONE of the following indications

-could be used to confirm this condition?

a. Both Source Range Nis reading 4000 counts and slowly decreasing

b. Average Incore thermocouple temperatures - 586 deg F and decreasing rapidly,

c. Incore Self-Powered Neutron Detectors (SPND) showing large positive currents in the upper portion of the core, with SPND output in lower portion of the core remaining constant.

d. Three Incore thermocouples showing negative Subcooling Margin with two Post Accident Monitoring channels operable.

ANSWER C

REFERENCE B&DD (9.9), R7 e - , n- , , -

0NUM ,

HNUM l

ANUM i

0 CHANGED FALSE i

ACIWiGEO FALSE

0DATE 1997/07/11 i

FAC 346 i 3

RTYP PWR B&W177

EXLEVEL S

EXMNR FAClllTY

0 VAL 1.0

SEC

SUBS 0RT

rJ4 022000G007

0UESTION-The CTHT Air Cooling System combined with the CTHT Spray system comarise the CTHT Heat Removal system. The purposes of this system are to keep CTiT ,

tem)erature less than 120 deg F during and removal of post LOCA air >orne ,

a, normal power operations: lodine

b. a Design Basis LOCA: Xenon

c. normal power operations: Xenon <

d. a Design Basis LOCA: lodine

ANSWER a

REFERENCE USAR 6.2.2.2.1 USAR 6.2.2.2.2 T.S. 3.6.2.1 T.S. 3.6.2.2 4

I

~

0NUM

HNUM

ANUM

0 CHANGED - FALSE-

. *ACHANGED FALSE i 1

0DATE 1997/07/11

FAC - 346 .

i

RTYP -

PWR B&W177

EXLEVEL .S ;

EXMNR FACILITY

0 VAL 1.0 ,

. ~

SEC !

- *SUBSORT l

KA ; 026020K403

00ESTl0N:

Following a primary LOCA. BWST LO LO LVL XFER TO EMER SUMP (5 3-A) is received. !

-Which ONE of the following describes the required operator actions? ;

1

a. BLOCK and OPEN the suction of the DH and CS pumas to the emergency sump (DH 9A/B) .and then BLOCK and SHUT the 3WST outlet valves - !

i

- (DH 7A/B).

j

b. BLOCK and SHUT the suction of the DH and CS pumps to the emergency sump (DH 9A/B) and BLOCK and OPEN the BWST outlet valves (DH 7A/B). t

c. BLOCK and OPEN the BWST outlet valves (DH 7A/B) which allows !

automatic opening of the suction of the DH and CS pumps to the

emergency sump (DH 9A/B).

. d. BLOCK and OPEN the suction of the DH and CS pumps to the emergency -

- sump (DH 9A/B) which automatically CLOSES the BWST outlet valves (DH-7A/B).

, -. ANSWER

d

REFERENCE 10B-0P-02000 (Att. 7) R4 r'

f i

[

-f Y- ._

l 1

t

, 5 j

" e, dc6 -,. e - s- [w- --

wa> - e.,w--w.- w -fy,-e.<w.pr -w w w.--gi te + m--vt-r

u 2 w 'r i + Pww w w W -* m rw w e W*- T

1

0NUM i *HNUM

ANUM

0 CHANGED FALSE

ACHANGED FALSE

0DATE 1997/07/11 l *FAC 346 l *RTYP PWR-B&W177 l *EXLEVEL S l

EXMNR FACILITY .

0 VAL 1.0 l

SEC

SUBSORT

KA 056000A204 l *00ESTION Which ONE of the following describes the interlocks associated with STARTING and RUNNING a condensate pump?

a. The pump will TRIP if hotwell level goes below 36 inches. This interlock is BYPASSED for 60 seconds to allow pump START.

t, . The pump will TRIP or be prevented from starting if hotwell level goes below 24 inches.

c. The pump will TRIP if vacuum becomes less than 24 inches of mercury.

This interlock is BYPASSED for 60 seconds to allow pump START. .

d. The pump will TRIP or be prevented from starting if vacuum becomes less than 12 inches of mercury.

ANSWER b

REFERENCE DB 0P 06221 (2.2.5) R1

f lr i

0NLM

HNLM l

ANLH

0 CHANGED. FALSE-

ACHANGED FALSE

0DATE 1997/07/11 i

FAC -346- j

RTYP PWR B&W177 1 i

EXLEVEL S

EXMNR FACILITY

0 VAL 1.0 .

SEC- -

SUBSORT

KA .

059000A201

0UESTION- l The following plant conditions exist:

-. Containment pressure is 20 sia and increasing.

- OTSG #1 pressure is 600 psi decreasing rapidly. ,

. OTSG #2 pressure is 655 psi decreasing slowly. ;

- .0TSG #1 level is 5 inches on the SU range, decreasing rapidly. ;

- OTSG #2 level is 50 inches-on the 50 range. increasing slowly.

Which ONE of the following. describes the operation of the Steam feed Rupture I

. Control-System (SFRCS)? ,

a. Initiates AFW and. level setpoint for both OTSGs will be 49 inches. ! ;

b. Ini_tiates AFW and level setpoint for both OTSGs will be 124. inches. ;

c. Isolates MFW to OTSG #1. initiates AFW and level setpoint for #2 OTSG will be 55 inches,

d. Isolates MFW-to OTSG #1 Initiates AFW and level setpoint for #2 ,

OTSG will be 130 inches,

ANSWER !

.d

REFERENCE-DB-0P 02000-(Table 1) R4

+

0NUM

HNUM

ANUM

0 CHANGED FALSE

ACHANGED FALSE

00 ATE 1997/07/11

FAC 346

RTYP PWR B&W177

EXLEVEL S

EXHNR FACILITY

0 VAL 1.0

SEC

SUBSORT

KA 059000G014

0UESTION Which ONE of the following would require immediate initiation of MU/HPI cooling in accordance with DB 0P-02000 RPS, SFAS SFRCS TRIP or SG Tube Rupture.

Specific Rule 2. MU/HDI Flow initiation Throttling, and Termination?

a. Hot leg temperatures are 560 deg F, all feedwater is lost AND D1 Bus is locked out,

b. RCS Subcooling margin is 25 deg F. ,

c. RCS pressure is less than 1650 psig, d, Loop 1 hot leg temperature is 605 deg F. AND both AFW pumps are aligned to SG 2.

ANSWER a

REFERENCE DB-0P-07.000 (Spec. Rule 2.1.2) R4

i i

3

u

0NUM~

HNUM

ANUM

0 CHANGED FALSE !

- *ACHANGEO- FALSE :

00 ATE 1997/07/11 l

FAC 346

RTYP PWR B&W177 i

EXLEVEL S

EXMNR ' FACILITY ,

0 VAL- 1.0 ,

SEC-

-*SUBSORT

KA 061000A101

00ESTION -. :

Auxiliary Feedwater has automatically started and each train is supplying its own !

0TSG. Which ONE of the following describes the response of AF 6d51 and AF >

16452 (SG Level Control Valves) controllers when the automatic initiation signal- ;

clears?

-a. Continue to operate on level control until the MANUAL pushbutton is i depressed.

1

b. - Continue to operate on speed control until the AUTO initiation

- signal--is reset. -

c. Shifts to MANUAL as soon as the AUTO initiation signal clears. <

d. Shifts to MANUAL after the AFPT reaches the HIGH Speed Stop (HSS).

ANSWER-a- -

REFERENCE OB 0P-06233 (3.3.3) R4 6 '

( <

l.

l, o

[ &

._. .-~ _ _ _ _- . . _ _ .-- _ . _ _ _ _ _ , . _ . . _ . _ , _ , . . _ , -

l *QutiM

HNUM

ANUM

0 CHANGED FALSE

ACHANGED FALSE

0DATE 1997/07/11

FAC 346

RTYP PWR B&W177

EXLEVEL S

EXMNR FACILITY

0 VAL 1.0

SEC

SUBSORT

KA 061000K101

0UESTION The cavitating venturis in the Auxiliary Feedwater (AFW) System are installed to

a. limit AFW flow to 1050 gpm to EACH steam generator

b. ensure AFW flow is maintained greater than 1050 gpm to EACH steam generator

c. limit AFW flow to 800 gpm to EACH steam gerierator

d. ensure AFW flow is maintained greater than 800 gpm to EACH stean, generator c

REFERENCE USAR 9.2.7.3 i

0NUM

HNUM

NJUM

0 CHANGED FALSE l

AOlANGED FALSE

0DATE 1997/07/11

FAC 346

RTYP PWR B&W177

EXLEVEL S

^EXHNR FACILITY

0 VAL 1.0

SEC

SUBSORT

KA 063000K302

0UESTION Which ONE of the following sets of DC buses, when lost, will result in an imediate reactor 1 RIP, if operating at 100% power?

a. DIN and DAN

b. 02N and DBN

c. D1P and DAP

d. 02P and DBP

ANSWER d

REFERENCE DB-0P-02538 (4.1.1) R0 SOER 83 5

--.r- , - ., ,. -,, - -

+

(.

f, l,

', e *0NUM

Q

ANUM

'*0 CHANGED FALSE

ACHANGE0 FALSE ~

00 ATE- 1997/07/11

fAC- 346

RTYP PWR B&W177

- *EXLEVEL S

-*EXMNR FACILITY

0 VAL 1.0

SEC

SUBS 0RT

KA- -

072000G012

-*0UESTION ..

When a' HIGH alarm comes in on'an AREA radiation monitor, the local alarm and

< ,- indicating panel (if so equipped) will alarm and .

a. the CTRH module's red light will light on the Radiation Monitoring Panel but its amber light will be off.

b. the CTRH module's red light will light on the Radiation Monitoring Panel only if it is a Tech Spec required monitor,

c. the CTRM module's amber and red lights will light on the Radiation Monitoring Panel and the alarming monitor will be displayed on the CTRH Fire and Radiation CRT.

-d. there will ONLY bc a local panel red light and horn if the unit is an AREA monitor, with PROCESS monitors being the ONLY units to provide Radiation Monitoring Panel alarms.

ANSWER c

REFERENCE DB 0P 06412 (4.12.2) R3

~*0NUM

HNUM

ANUM

0 CHANGED FALSE

ACHANGED FALSE i

00 ATE 1997/07/11

FAC 346

R1YP PWR 8&W177

EXLEVEL S

EXHNR- FACILITY

0 VAL 1.0

SEC

SUBSORT '

KA 002020K506

0UESTION Which ONE of the following sets of conditions requires tripping of all RCP's during a small break LOCA?

Temperature RCS pressure Ave T/C Temp (TI-RC4A2) (P732)

a. 579 deg F 1800 psig 590 deg F

b. 535 deg F 1300 psig 540 deg F

c. 525 deg F 1000 psig 540 deg F

d. 460 deg F 700 psig 445 deg F -

ANSWER c

REFERENCE DB 0P 02000 (Fig. 1) R4

i l

y l u

0NUM ! '

, *HNUM

ANUM

0 CHANGED FALSE l

ACHANGED FALSE-

00 ATE '1997/07/11- .!

FAC- - + -346 '

RTYP PWR B&W177

EXLEVEL S

EXMNR FACILfTYL !

1.0

0 VAL-

? *SEC

SUBSORT

XA 006000A100

00ESTION -

I A' LOCA has occurred and HPI has AUTOMATICALLY initiated. Which ONE of the following conditions will allow the operator to throttle HPlcflod

a,- HPI flow is 35 gpm with the minimum recirc valves closed.

b, .Subcooling Margin is 25 deg F on Channel 1 and 32 deg F on Channel l 2 using Thot.

c. HPI- flow is greater than 250 gpm-per HPI pump except while LPI piggybacked to the BWST. t 4

d. LPI flow has been above 1000 gpm per line for 10 minutes.

ANSWER b

REFERENCE DB 0P-02000 (Spec. Rule 2.4.2) R4 f

d 9 a

7 l '

.i i

.4-- , < ~ ,-y.., . -._ , ' . . - - m--, , .,m,,.k. 4.1 , , . , , , . . , .-.++.w , ,,,. . . . .--,eg'-, , _ - . . . . , . . - . , , - - - , . M.~ . w

l

QNUM

HNUM

ANUM i

0CIWDED FALSE

ACHANGt'D FALSE i

00 ATE 1997/07/11 4FAC 346 '

RTYP PWR B&W177

EXLEVEL . S

EXMNR FACILITY

0 VAL 1.0

SEC

SUBSORT

$KA 010000A203

00ESTION Which ONE ef the following describes a PORV indication that is available to the operator?

a. Ar: illuminated blue light AB0VE the control switch indicates that the PORV pilot solenoid valve has 125 VDC available to open the PORV, oc .,^ red light ON the controi switch indicates that the acoustical detectors have detected flow thrca h the PORV. <

c. An extinguished blue light ABOVE the control switch indicates that the PORV solenoid has de energized to open the PORV.

d. Lighted LEDs ON the PAM panel indicating .25 means that the PORV is FULL open.

ANSWER a

REFERENCE DB 0P 02004 (Att. 4-1-0) R3 OS 001A. Sh. 2 (CL-2) R10 DB 0P 02513 (2.1) R2 DB-0P 02513 Operator Aid

i' :

1-

-i

0NUM .

.; w r

. *ANUM .

0 CHANGED- FALSE- ;

d. *ACHANGED- FALSE i L *00 ATE 1997/07/11 ,

!- *FAC . 346-g *RTYP- PWR B&W177 !

-*EXLEVEL- S- .

I

*EXMNR- -FACILITY R *0 VAL 1.0.

i *SEC :

. SUBSORT -i

*KA 011000G010- ,

0UESTION -

Which ONE of the following describes the normal position and the purpose of RC ;

49. PZR HINIMUM FLOW SPRAY VALVE 7

- a. LNormally CLOSED and is opened to provide emergency spray'if RC 2 l fails closed.

' bl- Normally CLOSED and is opened to reduce temperature differential in the spray and surge lines during startup.

j

c. Normally OPEN to maintain a constant boron concentration between the

.PZR surge line and-spray.line. .3

d. Normally OPEN to minimize the temperature differential across the l PZR spray line.

ANSWER t

.d-

~* REFERENCE !

DB 0P-06003 (2.2.3/4.5,9) R3-I f

i

- fs, i

-i e

5

r th , e * +--g ey- rq--a--g w or ,w- w t- r ,+r,<y e-, y m . m w w-* w- y vw w- - wir y- wv m' ,-%- -- r w e~E-r,ww-- we4#w-- <,w., ,,, * . ,y v = - Wr'

0NUM

HNUM

ANUM

0 CHANGED FALSE

ACHANGED FALSE

0DATE 1997/07/11

FAC 346

RTYP PWR-B&W177

EXLEVEL S

EXHNR FACILITY

0 VAL 1.0

SEC

SUBSORT

KA 012000G014

0UESTION Which initiate aDNE of thereactor MANUAL following TRIPp?lant conditions would require the operator to

a. Pressurizer level is 245" and INCREASING in MODE 3.

b.. An OTSG Tube Leak larger than MAXIMUM MU flow with letdown in service in MODE 1.

c. An overcooling event in excess of Tech. Spec, cooldc.n rate limits occurs in MODE 3.

d. An SFAS Level 1 actuation (HIGH CTMT RADIATION) in MODE 1.

ANSWER C

REFERENCE DB 0P-02000 (1.5) R4

+

0NUM

HNUM

ANUM

0 CHANGED FALSE

ACHANGED FALSE

0DATE 1997/07/11

FAC 346 ,

RTYP PWR B&W177

EXLEVEL S

EXMNR FACILITY

0 VAL 1.0

SEC

SUBSORT

KA 016000A201

00ESTION A low failure of the selected feedwater temperature detector in the ICS will be indicated by .

a. an increase in OTSG Operate Range level indication

b. a decrease in feedy'ater flow demand

c. an increase in reactor power

d. a decrease in Tave

ANSWER b

REFERENCE M533-176 1 T1 .

t

i

0NUM -

HNUM <

ANUM . '

0 CHANGED- FALSE

ACHANGED FALSE- ^

'*0DATE 1997/07/11

- *FAC= ' 346 i

RTYP PWR B&W177 i

=

EXLEVEL S=

EXMNR - FACILITY- -

4

.*0 VAL - 1.0 l

SEC- . .

SUBSORT -

KA ,016000K201 '

- *00ESTION: :

Which ONE of the following conditions will cause an AUTOMATIC TRIP of the S1 and S2 switches in the NNI Y cabinet?:

a. Loss of ONE +24 VDC and ONE 24 VDC power supply. ,

b. Fuses from _YAU'and YBU feeding the NNI ABT blow.

c. Loss of the +24 VDC bus-or the -24 VDC. bus. :

d.- Loss of voltage from panel YAU.

ANSWLR !

C

REFERENCE .

i DB 0P 02014 (Att. 14 2 0) R1 .

6 9

i t

,7 ..- .

I y

b i 4 -

1 i~!

.7 n,,,--,+.-+ -e,.,.,wmvem,y.w.e,

~ , - , . ., , . . - - ,.---.v. v y---e,, , . . - , . . w., , - e e.,+, e ,- w , -,.y - , , ,, , ,

i

.i

0 NUN' '

i

HNUM -

ANUM- !

0 CHANGED FALSE j

/ CHANGED FALSE--

r

-1997/07/11-

.6 *00 ATE m *FAC- 346 4 ' *RTYP PWR B&W177.

EXLEVEL S .

EXMNR FACILITY

0 VAL- 1.0-

- *SEC .

SUBSORT.

KA- 028000A202 ,

- *0VESTION

-OP-02000.

A large Break TableLOCA has Hydrogen

3. CTMT necurred,concentration and CTMThas conditions reached 3 are being Which%. monitored ONE of- per D i

the following -combinations -represents the PREFERRED order of CTMT Hydrogen

' control systems to be placed in service per Table 37 (Assume all equipment is 4

- on site). ,

a

1. Hydrogen Dilution Blowers

2. Hydrogen Purge System

3. Hydrogen Recombiner i

a. -2 then 1 then 3 ,

b. 3 then 2 then 1 ,

c. 3 then 1 then 2 -

d. I then 2 then 3

ANSWER C

REFERENCE DB 0P 02000 (Table 3) R4 ;

c

- e ,v-e 4 ,e-~~+ - - e i - + , wu r n - - ,,,--c.w, ~,, .n---

- - ;+ , - - . - - - - - , , . - ~ - - , . - - - - - - -+-,~-.,r-

E

0NUM

HNUM

ANUM :

0 CHANGE 0 FALSE'

ACHANGED FALSE

0DATE 1997/07/11

FAC 346

RTYP PWR-B&W177

EXLEVEL S

EXMNR FACILITY

0 VAL 1.0

SEC

SUBSORT

KA 033000G015

0 VEST 10N The following plant conditions exist:

The Reactor has been de fueled for one week.

DH Pump 1 is aligned to the SFP

- SFP temperature is increasing

- Erratic flow indication exists on FYI DH28. DH Pump 1 Outlet flow The Assistant Shift Supervisor should initially GO T0 which DNE of the following procedures?

a. DB 0P-06012, Decay Heat and Low Pressure Injection System Operating Procedure,

b. DB-0P-02527. Loss of Decay Heat Removal Procedure,

c. DB-0P-06021. Spent Fuel Pool Operating Procedure,

d. DB-0P-02003. ECCS Alarm Panel 3 Annunciators. Attachment 3 1-B. SFP l.VL '

ANSWER b

REFERENCE DB 0P-02527 (2.4) R2 s

f

V

0NUM

HNUM .

ANUM. l

0 CHANGE 0- FALSE- ->

ACHANGED . FALSE

00 ATE 1997/07/11' :

FAC 346- !

RTYP- PWR B&W177

FXLEVEL S

EXMNR - FACILITY

0 VAL- 1.0

- *SEC .

- *SUBSORT. >

KA 03S010K301

QUESTION .' ;

The-following plant conditions exist: ;

The reactor is TRIPPED I

.RCPs SubcoolingRIPP0 Mar in is 0 deg F are '

AFW-is supplying BOTH SGs at 49 inches

-- RCS pressure-is 1700 psig

- T-cold and SG T-sat are 40 deg F apart Which ONE of the following actions will be consistent with the expected DB- !

- OP 02000 routing for this scenario?

o a. Once SCM is regained, start 2 RCPs in the loop with the highest SG level.

b. Raise 50 pressure until secondary T sat is greater than Incore T/C temperature. -

c. ' Open the PORV and reduce RCS pressure until it is 40 to 60 deg F '

below SG T-sat..

d. Full pen the 'AVVs and cooldown at a maximum of 235 deg F/ hour untik ieat transfer is regained.

'

ANSWER a

REFERENCE. .

08-0P_02000.(6.13) R4 :

I t

W

s . -

'f. .

1

.U._..-,._e.

,-wdm v+ . - , . c~ - . . . , , , , . [ ,,,r.,,, _.y..,_..._ s. , ,, , 3,, ,,. , . , .. ..,--.-,

0NUM

HNUM

NJUM

0CIWJGED FALSE

ACHANGED FALSE

0DATE 1997/07/11

FAC 346

RTYP PWR-8&W177

EXLEVEL S

EXMNR FACIL11Y

0 VAL 1.0

SEC

SUBSORT

rA 039000K508

QUESTION A normal plant startup is in progress with the reactor CRITICAL at 1.0 E-8 amps power when an atmospheric vent valve fails OPEN. Which ONE of the following is the expected plant response? (No operh or action.)

a. Reactor power will INCREASE. temperature will DECREASE. and pressure will DECREASE.

b. Reactor power will DECREASE. temperature will DECREASE and pressure will DECREASE.

c. Reactor power will INCREASE, temperature will INCREASE. and pressure will DECREASE.

d. Reactor power will INCREASE. temperature will DECREASE and pressure will INCREASE.

ANSWER a

REFERENCE DB-0P 02525 (2.2) R1

0 CHANGED FALSE

ACHANGED FALSE

00 ATE 1997/07/11

FAC 346

RTYP PWR-B&W177

EXLEVEL S

EXMNR FACILITY

0 VAL 1.0

SEC

SUBSORT

KA 062000G010

0UESTION A_ is provided between generator output ground switch 34645 and the to prevent shorting the ,

a. kirk key interlock: exciter field breaker: main generator output to I ground

b. mechanical slide link: generator field breaker: main generator output to ground

c. kirk key interlock: generator field breaker; main generator output to ground

d. kirk key interlock: generator field breaker; main generator rotor to ground

ANSWER c

REFERENCE DB-0P-06311 (2.1.14) R0

0NilM

HNUrl

ANUM

0 CHANGED FALSE

ACHANGED F'LSE

00 ATE D97/07/11

FAC 346

RTYP PWR-B&W177

EXLEVEL S

EXMNR FACILITY

0 VAL 1.0

SEC

SUBSORT

KA 064000G008

00ESTION The following plant conditions exist:

- A conolete loss of offsite power BOTH EDGs runnin'1 1-3 H. BUS D1 LOCK 0UT is lit EDG 1 output breaker AC101 is closed Which ONE of the following is an IMMEDIATE operator action?

a. Align bus 02 to be supplied froin the SBODG,

b. Direct an equip;aent operator to reset the lockout on D1 bus,

c. Shutdown EDG 2 by depressing the locai EMERGENCY SHUTDOWN pushbutton.

d. Align Bus 02 to be supplied from EDG 1.

ANSWER c

REFERENCE DB 0P-02521 (3.2.2) R1 1

0NUM.

HNUM

NIUM

0 CHANGED FALSE

ACHANGED FALSE

00 ATE 1997/07/11

FAC 346

RTYP PWR-B&W177

EXLEVEL S

EXMNR FACllllY

0 VAL 1,0

SEC

SUBSORT

KA 073000K301

0UESTION The following conditions exist:

The green RESET pushbutton on radioactive Jnitor RE 600 (MS line RE) was incorrectly installed following a light bulb replacement.

This caused it to bind in the " depressed" position.

Which ONE of the following describes how this condition affects the operation of the RE?

a. No effect, the RE is still OPERABLE.

b. The ALERT and HIGH lights will be ON.

c. The ALERT light will be ON. the HIGH light will be OFF.

d. The ALERT and HIGH lights will NOT function.

NISWER d

REFERENCE ICM DSM-87-25083 (OPS-SYS-IS08 BACKGROUND FOLDER)

PCAQR 87-0071

~

~ *0NUM

HNUML

-

ANUM E - -

0 CHANGE 0' FALSE-

ACHANGED - FALSE

-*00 ATE - 1997/07/111 ~

FAC . 346:

- *RTYP PWR-B&W177;

EXLEVEL< ' S?

EXMNR: FACILITY

*0 VAL 1.0

SEC

SUBSORT. - . -

- *KA -

075000A401 .

QUESTION. '

- Which ONE of the following-describes the relationship between SW 1395/1399 (TPCW Heat Exchanger Inlet Header Isolation Valves) and CT.2955 (TPCW Heat Exchanger

Supply from Cire. Water-System Stop Valve) operating sequence? -

a. -- - At 30 psig INCREASING SW header pressure. SW . 1395/1399 will

- 0 PEN to supply SW to the TPCW Hxs _ .

C -- At 50 p.cig INCREASING Cooling Water Heat Exchanger SW header.

pressure. CT 2955 wil' CLOSE to isolate circ, water to the TPCW Hxs

b. -

At 30 psig INCREASING Cooling Water Heat Exchanger SW header pressure, CT 2955 will CLOSE to isolate water to the TPCW Hxs

- - - At 50 psig INCREASING SW header pressure, SW 1395/1399 will OPEN to supply to-the TPCW Hxs- -

c. -

At 50 psig'0ECREASING Cooling Water Heat Exchanger SW header pressure CT 2955 will 0 PEN to supply circ, water to the TPCW-

- Hxs.

- At 30 psig-DECREASING SW header )ressure. SW 1395/1399 will CLOSE to isolate SW to the TPCW Exs d, - .

At 50 psig DECREASING SW header 3ressure. SW 1395/1399 will -

CLOSE.to isolate SW to the TPCW Fxs At 30 psig DECREASING Cooling Water Heat Exchanger SW header pressure. CT 2955 will-0 PEN to supply;rirc. water to the TPCW Hxs_

'*ANSWERJ '

d .

REFERENCE-0S-020. Sh. 2 (CL 9)=R17 L

1 d

I

0NUM

HNUM

NIUM

0 CHANGED FALSE

ACHANGED FALSE

00 ATE 1997/07/11

FAC 346

RTYP PWR-B&W177

EXLEVEL S

EXMNR FACILITY

GVAL 1.0

SEC

SUBSORT

KA 079000K401

QUESTION The following plant conditions exist:

- SAC 1-1 running SAC 1-1 receiver pressure 110#

- EIAC running

- EIAC receiver pressure 93# and decreasing SA 6445 IA to SA crosstie valve closed These symptoms are a result of which ONE of the following conditions?

a. CC 1495 NON ESSENTIAL CCW TO AUX BLOG ISOLATION ir rument air line has ruptured.

b. A pneumatic grinder connected to a Turbine Bldg. service connection has a ruptured air hose,

c. Station Air Receiver 1-1 outlet moisture trap failed open.

d. SAC 1-2 intercooler solenoid operated drain failed open.

ANSWER a

REFERENCE 05-019B. Sh. 1 R10 OPS-SYS-1602. TP-2A l

0NUM

HNUM

ANUM

' *0CtW1GED FALSE

ACHANGED FA.LSE

00 ATE 1997/07/11

FAC 346

RTYP PWR-B&W177

EXLEVEL S

EXMNR FACILITY

0 VAL 1.0

SEC

SUBSORT

'KA 086000G008

0UESTION The following plant conditions exist:

The plant is operating at 100% RTP.

- The Jockey Fire Pump trips.

Annunciator Alarm 9 5-G. FIRE WTR TURB BLDG PRESS LO. is illuminated.

Which ONE of the following describes control room indication of system response if the Fire Protection System pressure continues to DECREASE to 90 psig?

a. FIRE WTR DSL PMP DN annunciator followed by DSL OIL STRG TK LVL annunciator,

b. FIRE WTR ELEC PMP DN annunciator followed by FIRE WTR DSL PMP ON annuaciator,

c. FIRE WTR ELEC PHP DN annunciator followed by FIRE WTR ELEC PMP SYS TRBL annunciator.

d. FIRE WTR STRG TK LVL annunciator followed by FIRE WTR ELEC PMP ON annunciator.

ANSWER b

REFERENCE DB-0P-02529 (2.1.2) R2

, m. . , , . . . . . _ .__ - . . - _ . - . .

k' -

l D

HNUH; t*ANUN/-

1*0CH/NGED: -FALSE 1 --

ACHANGED FALSE

-*00ATEc i1997/07/11--

FAC:. 346 - - - -

'*RTYP

.- . .PWR-B&W177 ~

EXLEVEL. S .

EXMNRl FACILITY- :

1*0 VAL- 1.0

~

1*SEC' '

SUBSORT' -

KA- - 005000K408

00ESTIONs '

When called for concerning piggyback operation of the MU/HPI System. .

'-a,> MU flow shall NOT exceed 250 gpm during piggyback' operation from LPI

. with suction on the BWST

b. if LPI pump suction is from the CTMT Emergency sump; MU pumps shall.-

be operated ONLY-in' piggyback mode: -

- c; if there is LPI flow into the RCS during an LOCA and LPI suction is 1 aligned to the BW31l. piggyback operation is-NOT allowed

d. MU/HPI piggyback operation is ONLY to be utilized when directed to

.be initiated by DB-0P-02000~

ANSWER-C

REFERENCE .. . -

- DB-0P-02000 (Spec.-Rule 2.2/2.3) R4 -

6 Y

P-

=>

e-

0NUM

HNUM

ANUM

0 CHANGED FALSE

ACIW1GED FALSE

00 ATE 1997/07/11

FAC- 346

RTYP PWR-B&W177

EXLEVEL S

EXMNR FACILITY

0 VAL 1.0

SEC

SUBS 0RT

KA 008030A304

0UESTION DB-0P-02523. CCW Malfunctions, directs the operator to MANUALLY TRIP certain SFAS modules in the event of a total loss of CCW pumps to defeat the HIGH temperature and LOW flow CCW pump TRIPS. The results of tripping DNE side's SFAS modules is that CTMT vacuum reliefs for that side will and SG level setpoint will automatically ,

a. OPEN: INCREASE from 49" to 124".

b. CLOSE: DECREASE from 124" to 49".

-c. OPEN: DECREASE from 124" to 49"

d. CLOSE: INCREASE from 49" to 124".

ANSWER d

REFERENCE DB-0P-02523 (4.6.13) R1

0NUM

HNUM ,,,

ANUM

0 CHANGED' FALSE

ACHANGED -FALSE

00 ATE 1997/07/11

FAC 346

RTYP PWR B&W177

EXLEVEL S

EXMNR FACILITY-

0 VAL 1.0

SEC

SUBSORT

-*KA 045050K101

0UESTION Given the following cenditions:

- The plant is at'48% power The Main Turbine has received a valid trip signal The Turbine Stop Valves and Turbine Control Valves have NOT closed The Reactor Operator has tripped the reactor and has depressed "SFRCS Manual Actuation switches" (Start AFPT and Isolate SG pushbuttons), per DB-0P-02000, Step 4.2 The operator is directed to initiate SFRCS for these conditions because SFRCS actuation will ; .

a. prevent a reactor coolant system overcooling transient

b. prevent the Main Turbine from overspeeding

c. provide Auxiliary Feedwater flow to maintain steam generator levels at 124 inches

d. ensure total steam flow stays within the capacity of the Turbine Bypass Valves (TBV)

ANSWER d'

REFERENCE DB-0P-02000 (4.2) R4 B&DD (Step 4.2) R7

J 8- I l

i i*0NUMi -

i *HNUM.-

ANUME

-*0 CHANGE 01 FALSE- -

ACHANGED' ~ FALSE ,

.00 ATE - 1997/07/11-t*FAC- 346- ;

-*RTYPJ PWR B&W177 i

EXLEVEL- S-

EXMNR FACILITY-0 VAL 1.0

SEC '

SUBSORT

KA- - 078000K302

0VESTION--

The. following plant conditions exist: .

-1 The reactor is operating at 100% rated aower a - Instrument Air pressure is rapidly DECREASING-

- NO SFAS-actuation signals have been received ,

Which ONE of the following describes the effect of.a COMPLETE LOSS of Instrument Air on the Makeup _'and Pressurizer Level Control Systems? (Assume N0 operator -

actions are taken.)

a. MU Tank level will DECREASE and the running MU Pump will fail when-the MU Tank.is drained.

b. MU Tank level will DECREASE. and INCREASED injection flow will INCREASE pressurizer level,

c. MU Tank level will INCREASE off-scale HIGH causing the lifting of the-letdown line relief valve.

-d; MU Tank level will- INCREASE-causing MU 11 to automatically align to the Clean ~ Waste Receiver Tank.

ANSWER. '

b - -

^

REFERENCE' DB-0P 02528 (Att. 18) R2 08-0P-02000-(4.8.3)-R4 4

r se M4 -s %+ .>-,- y w ar- y(

~

0NUM

HNUM

ANUM

0 CHANGED FALSE

ACHANGED FALSE

00 ATE 1997/07/11

FAC- 346-

RTYP PWR B&W177

,EXLEVEL S

EXMNR FACILITY

0 VAL 1.0

SEC

, *SUBSORT

KA 000001K301

0UESTION At 1105, while operating at 70% reactor power, a regulating control rod becomes misaligned by 7% from the group average due to a malfunction. At 1125 (the same day).-the rod is ready to be recovered. Which ONE of the following power levels is the maximum at which the rod may be realigned?

a. 60%

b. 70%

c. 00%

d. 100%

ANSWER b'

REFERENCE DB-0P-02516 (4.2.6) R3

a

0NUML

HNUM

ANUM-

. *0 CHANGED: . FALSE

ACHANGED ' FALSE 1*00 ATE- .- 1997/07/11 o t

>*FAC-. 1 346- -

RTYP :. . - - PWR B&W177-

-*EXLEVEL- ' SJ -

EXMNR FACILITY = .

'*0 VAL ,

1,0-

. *SEC-

' *SUBSORT-

KA-i*0UESTION. . 000003A103- .

Given .the following conditions:

The

=

All plant is operating at 55% power-systems are operating as designed ,

Which rod position' indicating'(PI): system is selected on the Control Room Rod Position Indication Panel for- normal monitoring and why is this one selected?

a. ABSOLUTE -- allows-immediate verification that all control rods are fully inserted on a reactor trip .

b c- RELATIVE -- allows ~ continuous monitoring of sequence fault conditions during control: rod motion

c. ABSOLUTE -- allows continuous monitoring of sequence fault

-conditions.during control- rod motion

'd. RELATIVE -- allows immediate-verification that all control rods are fully-inserted on a: reactor trip a:

-

REFERENCE ~

- DB-0P-06402 (3.9.18) R1 f

y , -

g s

,r-.

, ,-. ,. ,- . ..r- - -

.-. .- c - 1 e e

.g..

~(

~

e j f ( .

p .

z <

!*0NUM

'*HNUMi

ANUM s*0 CHANGED.- . FALSE- +

-*ACHANGED FALSE?-

?*0DATE: 1997/07/11 '

i L*FAC L346 1

RTYP4 tPWR B&W177.- '

EXLEVEL -S: .

'*EXMNR FACILITY-:

-- *0 VAL: 1.0: -

*SEC J .

SUBSORT

KA ~ ; . 000005G011 o .

-* QUESTION..

Initial conditions:

-- -100% RTP. . . .

Groups 1-6: ' 100%_ withdrawn

- < Group 7- 92% withdrawn APSRS - 30% withorawn

-An: event occurs and the following alarms / conditions are observed:.

~ --

-(5-2-E) CRD ASYMMETRIC R00 (5-1-3) CRD LCO.

(5-3 E) CRD SAFETY-RODS NOT-WITHDRAWN ~

Control Rod Drive isechanism Position Indication Panel: ASYM ALARM light LIT-s i

NO zero percent lights LIT Rod' Control Indication Panel: AUTO INHIBIT Which ONE of the following sections of DB-0P-02516. CRD Malfunctions, should be

- entered?

c- . a .- Misaligned rod-b .- ' Rod Position Indication malfunction

^

c.: - Dropped rod

. .- d . . ' Undesired rod motion-

ANSWER

.a-

REFERENCE

. 08-0P-02516 (2.2) R3

~

s

'4- F j

._'J L..- ** ,, .c_, + - , - - . , ~ . , - - - - ,.

y b

~.-

0NUM .

1*HNUM-

=* ANUM? - .

1*0 CHANGED- FALSE-

ACHANGED- FALSE

00 ATE- l1997/07/11

FAC 346?

RTYP-

. PWR B&W177'

EXLEVEL: -- S a

EXMNR FACILITY-

0 VAL 11.0:'

SEC -

SUBSORT? - .

L*KA- .

000011A115 ,

0VESTION' -

Which ONE of the following incore conditions ^ meets the-requirements for entry >

--into 08-0P-02000, Section 9,. Inadequate Core Cooling?-

a.' -With BOTH channels available, four (4): working incore detectors _

display a NEG MARGIN light.

b. With only ONE channel available, two (2) working incore detectors display a NEG MARGIN light, r

c. With BOTH channels ~available, three (3) working incore detectors indicate a NEG MARGIN: light,

d. With only ONE channel available, five-(5) working incore detectors indicate a NEG MARGIN light.

ANSWER d

REFERENCE .

DB-0P-02000-(5.9) R4 t

2 l

~

4-

, , , . _ , _ ._ - .,.__ _. _.~....

p

0NUM

HNUM

ANUM-

0 CHANGED- FALSE

ACHANGED FALSE

00 ATE. 1997/07/11

FAC 346

RTYP .PWR-B&W177 -

EXLEVEL S

EXMNR FACILITY

0 VAL 1.0

SEC

SUBSORT

KA 000011A201

0UESTION Which ONE of the following sets of conditions would require an attempt to bump ALL-four (4) RCP's by jumpering interlocks?

RCS 3ressure Incore Thermocouples (PIRC2A4) (ave)

a. 400 psig 440 deg F

b. 1000 psig 680 deg F

c. 1600 psig 130 deg F

d. 2200 psig. 1280 deg F

ANSWER d

REFERENCE DB-0P-02000 (9.16) R4 l

l

/

u. ;

m 2 J' , s ?

E

0NUM- -

HNUM-

ANUM '.

'*0 CHANGE 01 JFM.SE'

-*ACHANGED- FALSE:

-*00

-. ATE- (1997/07/11 >

FAC -346

RTYP- :PWR B&W1772 -

EXLEVEL S~

t*EXMNR- ,FACILITYJ >

0 VAL -- 1. 0 -

i*SEC .

SUBSORT. - - .-

J*KA 000015G007- 4

0VESTION'

-Which -ONE of the following- describes niY-MINIMIZED with RCS pressures be

, a. To minimize excessive seal wear:

b, :To minimize excessive thrust bearing wear

c. To prevent idproper seal staging.

d. -To prevent- excess seal bleed-off flow'

-* ANSWER

a

REFERENCE

DB-0P-06900 (4.1) R4 DB-0P-06005-(2.2.1.e)'R2 iJ t

h}I O

N q,

~

4.

D

, * ~ y , ,,f g- m ,y- e- f s

I

0NUMl

'*HNUM-

-* ANUM ..

. 0 CHANGED- l FALSE L*ACH/GED FALSE-

00ATEs - 1997/07/11.

FAC. 346- '

RTYP - - PWR B&W177

EXLEVEL. - S.

EXMNR- FACILITY.-

0 VAL 1.0

SEC .

SUBSORT

KA - 000024A205

0UESTION- . _

The plant -is at' 2* ' xwr during 'a plant shutdown when the reactor operetor (

, reports that the SMlT00WN. MARGIN has been calculated to be 0.985. The proper-operator action that must be taken is to initiate .

a. boration with the Makeup ' pumps taking a suction on the BWST-at a MINIMUM of 25 gpm

b. a batch addition directly to the RCS from the Boric- Acid Mix Tank (BAMT) with.a MINIMUM concentration of 7875 ppm-at a MINIMUM of 95 ;

.. gpm

.c. boration with the Clean Waste Booster pum Concentrates Storage Tank at a MINIMUM of ps taking a suction on a a 95 gpm

d. a batch addition with the Boric Acid pumps taking a suction an the Boric Acid Addition- Tanks (BAATs) with a MINIMUM concentrat ton of

- 7875 ppm at a MINIMUM of 25.gpm d

REFERENCE DB-0P-02510 (4.1.2) ria -

-Tech. Spec. 3.1.1.1 I

M 4

4 6., x

0NUM-

llNUM

ANUM-

0CHANGr.D . FALSE

ACHANGED FALSE

00 ATE- 1997/07/11

FAC- 346

RTYP PWR-8&W177

EXLEVEL S

EXMNR FACILITY

0 VAL 1.0

SEC

SUBSORT

KA 000024K302

0UEST10N Following a reactor trip, six control rods are stuck out. The Reactor Operator has started boration as directed by DB-0P-02000. "RPS, SFAS SFRCS Trip or SG Tube Rupture". Termination of the boration is allowed when it has been verified that .

a.- SHUTDOWN MARGIN has been calculated to be 1.15%

b. Source Range counts on all channels are less than 100 cps

c. Reactor Coolant System boron concentration reaches 2000 ppm

d. Source Range startup rate reaches negative 1/3 dpm

ANSWER a

REFERENCE DB-0P-02000 (4.1.2) R4

0NUM

HNUM

ANUM-

0 CHANGE 0- FALSE

ACiW4GEO FALSE-

0DATE 1997/07/11-~

FAC. 346

RTYP PWR-B&W177

EXLEVEL S

EXMNR FACILITY

0 VAL 1.0

SEC

SUBSORT

KA 000026A105

0UESTION The following plant conditions exist:

The plant is at 100% power, normal system alignment Annunciator 11-3-A CCW SURGE TK LVL L0 in alarm The R0 S has opened DW 2643, DEMIN WATER TO CCW SURGE TANK LI 1402 and 1403 (CCW SURGE TANK LEVEL SIDE 1 AND 2) are on a downward trend If this trend continues, there a leak on the ,

a. Aux. Building non-essential-header will be isolated and surge tank level will stop at 35 inches

b. CTMT non-Ossentia ieader will be isolated and surge tank level will stop at 35 inches

c. Train 2 essential header will be isolated and surge tank level will stop at 45 inches

d. makeup pump header will be isolated, the makeup pumps will trip due to loss of cooling, and surge tank level will stop at 45 inches

ANSWER b

REFERENCE DB-0P-02523 (4.1.6) R1

y a+

i

0NUMI

':*HNUME <

ANUM. - .

"I

0 CHANGED: -- FALSE : ;

ACHANGED -FALSE

0DATE- 1997/07/11' L*FAC 346

RTYP- =PWR-B&W177 . :

'*EXLEVEL". S: '

FACILITY

'*EXMNR.

0 VAL 1.0 *

SEC

SUBSORT- . .

-*KA. .

000029A209

0UESTION'

. After attempting to TRIP the reactor in the Control Room, the NIs still read 50%.-

Which ONE of the follosing cctabinations represents the preferred order in which the control' rod drives should be MANUALLY deenergized, according to DB-0P-02000, ,

Immediate Operator Actions?

a. - MANUALLY TRIP the three (3) reactor trip breakers in the low voltage switchgear rooms.

- MANUALLY DEENERGIZE the CRD System by tripping BE-211 and BF-211.

' ~ M0MENTARILY -DEENERGIZE 480 LVAC_ Unit Substations E-2_ and F-2 -

simultaneously.

- b. - MANUALLY TRIP the three (31 reactor trip breakers in the low voltage

.switchgear rooms.

'- HOMENTARILY DEENERGIZE ~480 VAC Unit Substations E-2 and F-2 simultaneously.

- MANUALLY DEENERGIZE the CRD System by tripping BE-211 and BF-211.

c. -- M0MENTARILY DEENERGIZE 480 VAC Unit Substations E-2 and F-2 simultaneously.

- MANUALLY TRIP the three (3) reactor trip breakers in the low voltage switchgear rooms.

- MANUALLY DEENERGIZE the CRD System by tripping BE-211 and BF-211.

~d. -

- MOMENTARILY DEENERGIZE 1480 .VAC Unit Substations E-2 and F;2 simultaneously.

- MANUALLY DEENERGIZE the CR0 System by tripping BE-211 and BF-211.

- MANUALLY TRIP the three (3) reactor trip breakers in the low voltage switchgear rooms.

m

.C-L*REFERENCEJ

DB-0P-02000: (2 2.2) R4 .

er,L ~ .-- - - ,

m s 3

- 53 t'

- a

~ *0NUHi-i *nNW -

?* ANUM /

j L*0 CHANGED;-FALSE.- -

?m i*ACHANGED: FALSE = l

" ~

t*00 ATE' 21997/07/11E

FAC.. -346

-*RTYRL PWR-B&W177:

- *EXLEVE0 :.SL--- l

EXMNR-- :

FACILITY 3 ~

0 VAL'~ 1.0L x 1*SEC: .

.h

.SUBSORTl

KA :

Oh0029G011

. -- QUESTION - -- . -

The plant is in the process of- a pr increase to 100% power following repairs to#1-MFfr. At 78%. power, the foilowing-indications are observed:-

~

-- SP68; SG 1 MAIN FW CONTROL VALVE is 0% open- -

r

- :Tave 586_deg F' increasing--

RCS pressure 2375 psig increasing-

- 0TSG #1 level decreasing

--- 0TSG #2-level increasing slightly-:

- - NI power decreasi_ng slightly 3 Based'upon the above' indications the crew should .:

'a.. . trip the reactor using either manual pushbutton, then enter Tech.

Spec. 3.0.3'

b. - open the PZR spray valve to mitigate the. transient, then perform a.

normal shutdown

c. ' take both FW Loop Demands to HAND along with SP78. SG 1 STARTUP FW.

CONTROL VALVE

d. take-both.FW-Loo) Demands to RAND along with SP6A. SG 2 MAIN FW CONTROL VALVE anc SP7A;-SG 2 STARTUP FW CONTROL VALVE

ANSWER

.a

REFERENCE

- DB 0P-02000.(1.1) R4 9

s.

l 4

...J2 e

p.

I -

4,

0NUM

HNUM

ANUM,

0 CHANGED FALSE

ACHANGED FALSE

00 ATE - 1997/07/11

FAC 346

RTYP PWR-B&W177

EXLEVEL S.

EXMNR FACILITY

0 VAL 1.0

SEC

SUBSORT

KA 000040A205

0VESTION After a LBLOCA. HPI cooling may be FIRST terminated when flow has been established at > gpm per line for > minutes,

a. LPI. 1500. 30

b. HU. 250..30

c. LPI. 1000. 20

d. MU. 250, 20--

ANSWER c

REFERENCE DB-0P-02000-(Spec. Rule 2) R4

i

0NUM

HNUM

ANUM '

0 CHANGED- FALSE

ACHANGED FALSE-

0DATE 1997/07/11

FAC 346

RTYP- PWR-B&W177

EXLEVEL. S

EXMNR FACILITY

0 VAL -1.0

SEC

SUBSORT

KA 000040G011

QUESTION The following plant conditions exist:

Reactor TRIPPED Containment Pressure 15.0 psia Pressuri?er level 90 in, and DECREASING RCS pressure 1750 psig and DECREASING RCS temperature 539 deg F NI 5, 6. and 7 0%

NI 8 125%

OTSG Pressure Level 1 850 psig 245 in.

2 860 psig 240 in.

Which ONE of the following events caused the above conditions?

a. Steam Line Break

b. Steam Generator Overfeed

c. Steam Generator Tube Rupture

d. Stuck Open Main Steam Safety Valve

ANSWER b

REFERENCE DB-0P-02000 (2.1.3/2.1.4) R4

0NUM

HNUM

ANUM

0 CHANGE 0 ' FALSE

ACHANGEO FALSE

0DATE 1997/07/11

FAC 346

RTYP PWR-B&W177

EXLEVEL S

EXMNR FACILITY-

0 VAL 1.0

SEC

SUBSORT

KA 000051A202

0UESTION The plant is experiencing a loss of condenser vacuum. According to DB-0P-02518, High Condenser Pressure, at 10 inches HgA, the operator is required to perform the following actions:

1. TRIP the Reactor.

2. Initiate AFW flow AND isolation of BOTH SGs.

These actions are taken ,

a. in anticipation of a loss of the RCPs wher the turbine is TRIPPED manually by the operator,

b. to ensure adequate heat removal from the reactor coolant system when the condenser is lost,

c. to MINIMIZE the potential for condenser tube leaks due to the HIGH differential pressure,

d. due to the potential loss of the interconnect water seal between the condenser sections.

ANSWER b

REFERENCE DB-0P-02518 (4.1.1.d) R0

= _

e 1*0NUM

-- HNUM ?

, ;* ANUM . .

?*0 CHANGED FALSE- .

L*ACHANGED' . FALSE- . .

.00 ATE? 11997/07/11 +

.*FAC: 346 .

L*RTYP . PWR-B&W177-

EXLEVELL

:S- .

H*EXMNR- :FACILITYi .

.*0 VAL .l.0

SEC-

SUBSORT .

KA . . -000055K302

*0UESTION : . . .- .

-The_ following-plant conditions exist:

- Reactor? . TRIPPED from ful_1 power.

- Bus A voltage-- 0 VAC Bus B voltage 0 VAC' Both EDG's- .

FAIL TO START MU aump #2 breaker CLOSED SB0X3 FAIL T0. START ~

Which 'ONE of the following describes the correct sequence that should be followed when EDG #2: is available -.to be started?- _

(Assume :EDG #2 is - the ONLY EDG -

-- available. )

- a. Immediately-start EDG #2 and energize Bus 01 to restore essential-

~ bus loads,

b. Immediately start EDG #2 energize' Bus 01 then immediately energize

- Bus 02.

c. TRIP MU Pump #2 breaker _ and then immediately start EDG #2 to energize Bus 01.

c d. : Place MU 19 controller in MANUAL, CLOSE MU 19 and then start EDG #2

.and energize Bus D1.

" C

REFERENCE!

OB-0P-02000-_(4.5.4) R4 .

.7 J

i h a

+ -4' 9 Mr y 4-- #t'a. -

'1 w' 8-+---- e- "r'w- -'E1 - dT' '-

0NUM

HNUM

ANUM FALSE

'*0 CHANGE 0

ACHANGED FALSE

00 ATE 1997/07/11

FAC 346-

RTYP- PWR-B&W177

EXLEVEL S

EXMNR FACILITY

0 VAL 1.0

SEC

SUBSORT

KA- 000057A219

QUESTION The following conditions exist:

Bus lockout has occurred on 4160 VAC Bus C1.

- All other plant systems are in a normal lineup.

Which ONE of the following correctly describes the Instrument AC system essential power alignment?

a. Y1 NORMALLY powered from Inverter YV1. is on ALTERNATE power supplied to YV1 AUTOMATICALLY from Voltage Regulator XYl.

b. Y3. NORMALLY powered from Inverter YV3. is on ALTERNATE power supplied to YV3 AUTOMATICALLY from YAR.

c, Y1A. NORMALLY powered from Inverter YV1. is on ALTERNATE power supplied to Y1A MANUALLY from Uninterruptable Bus YAR.

d. Y1A. NORMALLY powered from Inverter YV1. 1s on ALTERNATE power supplied to YV1 AUTOMATICALLY from DC MCC 2.

ANSWER c

REFERENCE DB-0P-06319 (Att. 12. 14) R2

m s>. .- _ _ __ _ _ _

.y - . . _

. t. ?

_ ,ggg

HNUM+

.*ANUMJ .

<*0 CHANGED? FALSE o, *ACHANGED4 1 FALSE-

-:*00 ATE :1997/07/11:-

. *FAC - 346-

~*RTYP - PWR-B&W177 s.*EXLEVELi S-

" *EXMNR- FACILITY' "

0 VAL. 1.0:

SEC-'. '

SUBSORT- .

KA . 000067G002..

1*00ESTION .

A fire is in progress at Davis-Besse, and the Fire Brigade is manned and on the.

scene. The Fire- Brigade - Captain - should request Carroll Township Fire-Department's assistance if .

a.. the fire is affectinglmore than one systen:. and a hose has been --

6 laid, even though no water has flowed

~

.b. .the fire is located in a Radiologically Restricted Area and is NOT-out-c, . fire suppression systems have been in operation for 10 minutes-ana

-the fire is NOT out

d. the Fire Brigade was unable to respond.to the fire location within the first 10 minutes

ANSWER c

REFERENCE DB-0P-02529 (4.1 16) R2 t

Q 'm- w

0NUM

HNUM

ANUM

QCHANGED FALSE

ACHANGED FALSE

00 ATE 1997/07/11

FAC 346

RTYP PWR-B&W177

EXLEVEL S

EXMNR FACILITY

0 VAL 1.0

SEC

SUBSORT

KA 000067K102

QUESTION The following plant conditions exist:

The )lant is in MODE 3. preparing to startup the reactor.

- A LARGE fire is in progress in Mechanical Penetration Room 1.

Fire fighting operations are in progress.

Off-site fire department assistance has been called and is en-route to the plant.

If a loss of ALL off-site power occurs while efforts to fight the fire are in progress, the water for the Station Fire Protection System will be supplied from the . .

a. Electric Fire Pump (EFP) with suction on the intake structure

b. Diesel Fire Pump (DFP) with suction on the intake structure

c. Jockey Fire Pump with suction on the FWST

d. Fire de)artment pumper connection with backup lines taking suction on the :WST

ANSWER b

REFERENCE DB-0P-06610 (2.2.14) R1 OPS-SYS-1601

0NUM

llNUM

NJUM

0CIW4GE0 FALSE

ACHANGED FALSE

00 ATE 1997/07/11

FAC 346

RTYP PWR B&W177

EXLEVEL S

EXMNR FACILITY

0 VAL 1.0

SEC

SUBSORT

KA 00006BK318

0 VEST 10N in the event that the control room must be evacuated, which ONE of the following actions has the LCMEST priority to be eccomplished?

a. Sound the INITIATE EMERGENCY PROCEDURES alarm and announce control room evacuation

b. Isolate letdown

c. Initiate SFRCS

d. Start the standby Mdkeup Pump

ANSWER a

REFERENCE DB 0P 02508 (4.1.1) R0

l

0NUM

llNUM

ANUM

0CilANGEO FALSE

ACHANGED FALSE

0DATE 1997/07/11

FAC 346

RTYP PWR Bt.W177

EXLEVEL S

EXMNR FAClllTY

0 VAL 1.0

SEC

SUBSORT

KA 00006BA205

0VESTION The following plant conditions exist:

- A serious CTRM fire has occurred requiring evacuation of the CTRM and local plant control to be established at the Auxiliary Shutdown Panel (ASP).

- The SS is attempting to determine the presence of primary to secondary heat transfer from the ASP, Which ONE of the following actions should be performed to allow him to make this determination?

a, Direct the R0 S to locally throttle ICS118, OTSG 11 ATMOSPHERIC VENT VALVE and observe Tcold indications for a decrease, b, Direct the R0-S to locally throttle open ICS118. OTSG l-1 AIMOSPHERIC VENT VALVE and observe Thot indications for a decrease,

c. Raise the setting on AFP 1-1 governor from the ASP and observe Tcold indications for a decrease,

d. Raise the setting on AFP 1-1 governor from the ASP and observe Thot indications for a decrease.

ANSW2R b

REFERENCE DB-0P-02519 (Att. 1) R3

l l

0NUH

HNUM

ANUM

0 CHANGED FALSE

ACHANGED FALSE

0DATE 1997/07/11

FAC 346

RTYP PWR B&W177

EXLEVEL S

EXMNR FACILITY

0 VAL 1.0

SEC

SUBSORT

KA 000069G003

0 VEST 10N Which ONE of the following conditions would affect CTMT INTEGRITY?

a. A #2 side MS Safety Valve is removed with N0 secondary side openings on #2 OTSG.

b. The door to the CTMT Vessel annulus is removed in #4 Mechanical Penetration Room,

c. MS 100, #2 SG MS isolation Valve is CLOSED.

d. A CTMT lsolation Valve failed its local Leak Rate Test (LLRT).

ANSWER d

REFERENCE USAR Ch._6.2. Table 6.2-23 Tech Spec Defn 1.8 i

i

0NUM

HNUM

ANUM

0 CHANGED FALSE

ACHANGED FALSE

00 ATE 1997/07/11

FAC 346

RTYP PWR B&W177

FXLEVEL S

EXMNR FACILITY

0 VAL 1.0

SEC

SUBSORT

KA- 000074K102

0 VEST 10N-Given the following conditions:

A station blackout has occurred

- High Pressure injection and Auxiliary feedwater have failed to o>erate

- 11e reactor core has become partially uncovered Core damage may be unavoidable if the crew identifies that .

a. T sat monitors indicate O deg F b, there is no indication of natural circulation

c. the self powered neutron detectors indicate 100% reactor power 3 minutes after the above transieat

d. RCS presse e/ temperature is in Region 4 of Figure 2 for inadequate Core Cooling

ANSWER d

REFERENCE DB 0P 02000 (9.16) R4 BDD (Step 9.9) R7

i i

i

0NUM- !

HNUM ,

ANUM ,

'*0 CHANGED FALSE ,

ACHANGED FALSE !

00 ATE 1997/07/11

FAC' . 346 .

RTYP PWR B&W177 i

EXLEVEL= S i

EXMNR FACILITY l

0 VAL 1.0 ;

SEC !

SUBSORT- .

KA- 000074K204

0 VEST 10N ;

Plant conditions are as follows:

- -A-small break LOCA has occurred, i HP1 Pump 1 2 AUTOMATICALLY started.

- HP1 Pump 1 1 CANNOT be started. !

t Which DNE of the following is the reason that the operator must balance the

-injection line flows in HPI Train 2?

a. To prevent a break in Train 1 from robbing most of the injection !

flow from Train 2.

b. - To prevent a break in one of the Train 2 injection lines from robbing most of the injection flow from the intact injection line. .

c. To prevent excessive thermal stress to the injection nozzle in the Train 2 injection line with the higher flow. ,

d. To prevent excessive thermal stress.to the reactor vessel wall near theinjectionlinewiththehigherflow, j b

REFERENCE OB OP-02000 (Spec. Rule 2) R4 BDD (Spec.-Rule 2) R7 1

i i

?

)

s

('. k -~

. . - . . v ,v.. ,~ . r._., ,_w,.,- o_...., ..~n... ,m-.. .., . . . ,... c,. v_y...w_,-......~--,,.,_,-,,--, ,,..,-w. , _ , , ,

0NUM

HNUM

ANUM

0 CHANGED FALSE ,

ACHANGED FALSE

00 ATE 1997/07/11 <

FAC 346

RTYP PWR-B&W177

EXLEVEL S ,

EXMNR FACILITY

0 VAL 1.0 '

'*SEC

SUBSORT

KA 000076G008

QUESTION The following plant conditions exist:

-- Chemistry re) orts that a high activity condition exists in the RCS based upon tie latest sample.

- The control room operator is directed to check the failed fuel detector RE 1998 for proper response.

Which directs ONE of the RE 1998 followingtodescribes response how be checked in DB this0P-02535.

situation Hig/h Activity in the RCS

a. Perform DB-SC-03200. Shift Channel Check of the Radiation Monitoring System for RE 1998.

b .' VERIFY power available to RE 1998 and that the scale reading corresponds to chemistry sample results.

c. Perform DB-SC 04187. Daily Check of the Radiation Monitoring Syster for RE 1998.

d. Depress the check source button on the digital radiation monitor for RE 1998.

ANSWER d

REFERENCE DB 0P 02535 (4.1.1) R3

I i

i I

0NUM:

HNUM

ANUM

0 CHANGE 0; FALSE !

ACHANGED- FALSE' i

0DATE 1997/07/11- ;

FAC- 346 1

RTYP PWR B&W177-

EXLEVEL S ,

EXMNR FACILITY '

0 VAL 1.0-

. *SEC' ,

- *SUBSunT-1

KA 000007A202-

0 VEST 10N '

In an attempt to trip the turbine from 24% power the o>erator has depressed the EHC - EMERGENCY TRIP pushbutton and a turbine. TRIP has h0T occurred. The reactor is still 3roducing 24t power. The immediate action that the CTRH operator is j required ;o perform per DB 0P 02500. Turbine Trip, is to -

, i a.- Open BOTH generator output breakers (ACB 34560 and 34561) to prevent

-reverse motorization of the main generator ,

b. Send an operator to TURN And PULL the local. turbine trip lever at the front standard ,

c. Sto) the Main Turbine Motor Suction Lube Oil Pump by placing in -

LOC (0UT HIS 2400

d. Initiate AFW flow to BOTH SGs by depressing SFRCS manual actuation switches HIS 6401 and HIS 6402

ANSWER 6

REFERENCE -

DB-0P-02500 (3.1.1) R1 l-t

. a 9

L. . = _ - . -

l o j l

4 i i

1

0NUM;

, *HNUM l

ANtM 1*0 CHANGED FALSE i

ACHANGED ' FALSE

0DATE 1997/07/11 i

FAC- 346 .

I

RTYP -PWR B&W177 I

EXLEVEL. 'S !

EXMNR FACILITY-' "

0 VAL 1.0

*SEC

SUBSORT

KA 000008A201

0VESTION - -

Reactor power is at 86% when the controlling RCS pressure channel fails HIGH. .

With N0 operator action, which ONE of the following statements d0 scribes plant l

' response?-

a. Actual RCS pressure will INCREASE ,

b.- Pressurizer spray will go full CLOSED i

'c. . Pressurizer heaters will energize ;

-d. SFAS will be actuated

ANSWER d

REFERENCE DB 0P-02513 (2.6.3) R2 ,

t i

b

...w.c e , - - , , ---+v

, -.n., - ,._r , - . . . - , . , , - . , ~ , + . . ,,,,.,,,n..... ,w.,.,~,,,.,-,,,,,w . . . . . . , - e

0NUM '

HNUM

ANUM ,

FALSE i

0 CHANGED l

ACHANGED FALSE

0DATE 1997/07/11

FAC 346

RTYP PWR B&W177

EXLEVEL S

EXMNR. FACILITY

0 VAL 1.0

SEC

SUBSORT

KA 000009A201

0UESTION During a severe plant transient where Region 2 inadequate core cooling exists, the crew is directed to depressurize the SGs while maintaining secondary side SG 1evels. - SGs- are depressurized to obtain a drop in secondary Tsat below existing primary Tsat which is done to .

a. 40 to 60 deg F: increase the primary to secondary DT to promote natural circulation heat transfer ;

b. 40 to 60 deg F: enhance the strength of the heat source to promote natural circulation heat transfer

c. 90 to 110 deg F: increase the primary to secondary DT to promote natural circulation heat transfer

d. 90 to 110 deg F: enhance the strength of the heat source to promote natural circulation he6t transfer

ANSWER c

REFERENCE DB-0P-02000 (9,4.1) R4

0NUM

HNUM

ANUM

0 CHANGED FALSE .

ACHANGED FALSE

00 ATE 1997/07/11

FAC 346

RTYP PWR-B&W177

EXLEVEL S .

EXMNR FACillTY

0 VAL 1.0

SEC

SUBSORT

KA 000022A201

0 VEST 10N The following plant conditions exist:

- Reactor Power 95% steady RCS pressure 2150 psig steady PRZR level 220 inches and slowly DECREASING-

- MU TK LEVEL LO, 2 2-C ALARM

- MU FLOW HI TRN 2, 2-4 C ALARM '

RCP seal flow NORMAL No operator actioris have been taken Which ONE of the following abnormal conditions would explain the above conditions?

a. MU pumps are tripped

b. MU 32 fails open

c. Loss of suction to running MU pump

d. Normal MU injection line leak

ANSWER d

REFERENCE DB 0P-02522 (4.1.6) R1

0NUM-

llNUM

ANUM

0 CHANGED FALSE

ACHANGED FALSE "

QDA1E 1997/07/11

FAC 346

RTYP PWR B&W177

EXLEVEL S

EXMNR FACILITY

0 VAL 1.0

SEC i

SUBSORT- '

KA 000025A207

QUESTION '

The following conditions exist:

- The plant is in MODE 5 with Decay Heat Removal (DHR) Pump 1 3roviding RCS flow.

- Erratic flow is seen c1 DHR Pump 1 flow indicator FYI DH 28.

If DHR Pump 1 is experiencing cavitation, this flow indicatior, will be supported by .

a, motor amps decreasing, pressure erratic, and pump noise increasing,

b. motor amps erratic, pressure increasing, and pump noise increasing

c. motor amps erratic, pressure erratic, and pump noise decreasing

d. motor amps erratic, pressure erratic, and pump noise increasing

-* ANSWER d

REFERENCE DB 0P 02527 (4,3.1) R2 ,

h 1

i

0NUM j

HNUM i

ANLM !

0 CHIMED FALSE

ACHANGED FALSE a

00 ATE 1997/07/11 ;

FAC 346

RTYP PWR B&W177 i

EXLEVEL- S !

EXHNR. FACILITY i 0 VAL 1.0 ,

SEC r

-*SUBSORT ;

'*KA .000027K304

0UESTION A plant transient at 70% power has occurred, which resulted in a drop in Tave of - -

7 deg F. Tave has been recovered over the past 10 minutes and is again at

.setpoint. At the point-where the heatup stops, RCS pressure will ,

j

a. decrease because of mixing of the relatively cold RCS liquid _in the. >

PZR

b. . increase because of mixing of the relatively hot RCS liquid in the PER ,

c. decrease because the RCS pressure instrument is temperature-compensated and Thot will be decreasing after the heatup stops

d. increase because the RCS pressure instrument will see a higher DP with That increasing after the heatup stops

ANSWER a

REFERENCE CE Steam Tables '

DB 0P 02000 (7,10) R4 ;

t 5

o

' \

a 6

0NUM i

HNUM i

ANUM l

0 CHANGED ._ FALSE -I

~

ACHANGEO FALSE- !

00 ATE- 1997/07/11 !

FAC 346 ;

- *RTYP PWR 8&W177

EXLEVEL 's ;

EXMNR FACILITY

0 VAL - 1.0. ,

SEC ..

SUBS 0RT i

.*KA ' ' 000032A202 ;

00ESTION -

LG1ven the _following coriditions::

j

-A plant startup is in progress. I

-. - Safety rod Groups 1-4 are at their OUT LIMIT. !

- The Reactor Operator (RO) conmenced withdrawing Group 5 rods and has i now stopped; l t

What will be the indication that sub-critical multiplication is _ occurring? !

a,- A constant, positive start up rate with increasing source range I counts

b. A constant, negative start-up rate with source range counts i decreasing to a previous level r

c. Start-up rate leveling off at zero DPM with source range counts increasing and leveling- off at a higher value than previously :

observed p

d. Start-up rate leveling off at zero DPM with intermediate range power level increasing and leveling off at 1.0 E-8 amps :

ANSWER :

C '

REFERENCE

- DB 0P 06912 (4.14) R1 i

i f

u

.{

~

,e e. ~ ,, .s- ,, ..E.,._'4w..s . ..,_[#,m.m. ....,s.6,,_.. .m. _ _ . . - . , ,,.___..._._.__L,. .

.m..-.6._.w. -- -

0NUM

HNUM

ANUM

$0 CHANGED FALSE

ACHANGED FALSE

0DATE 1997/07/11

FAC 346

RTYP PWR-8&Wl'1

EXLEVEL S

EXMNR FACILITY

0 VAL 1.0

SEC

SUBSORT

KA 000033A209

00ESTl0N Plant conditions are as follows:

- Plant startup in progress at 6% power.

- Intermediate Range Nuclear Instrument NI 3 has failed DOWNSCALE.

Which ONE of the following describes when the Source Range nuclear instrument detector high voltage power supply will be AUTOMATICALLY cut off if reactor power is INCREASED?

a. Exceeding 10% power indication on NI-7 and 8.

b. When NI 3 fell below 5 X 10 10 amps

c. Exceeding 10% power indication on NI-6 and 7.

d. Exceeding 5% power indication on NI-5 and 7.

ANSWER c

REFERENCE OB 0P-02505 (4.2.1) R1 I

1

0NUM

HNUM

NJUM

0 CHANGED FALSE

ACHANGED FALSE

00 ATE 1997/07/11

FAC 346

RTYP PWR B&W177

EXLEVEL S

EXMNR FACILITY

0 VAL 1.0

SEC

SUBSORT

KA 000037K305

0UESTION The following plant conditions exist:

- 100% power RE 600 (MS Line 2 RE) in alarm

- PZR level decreasing (currently 210")

Both makeup pumps are running

- MU 28. Letdown Isolation, is closed

- HU 32. PZR Level Control. is fully open Which DNE of the following describes the correct course of action and reason for those actions under tt'ese conditions?

a. CONTROLLED shutdown; avoids INCREASING the RCS leakage rate.

b. CONTROLLEO shutdown: avoids lifting the main steam safety valves. ,

c. Reactor TRIP: MINIM 1ZES the amount of secondary side contamination.

d. Reactor TRIP: MINIMlZES the duration of offsite releases.

NJSWER b

REFERENCE DB-0P 02000 (8.6.3) R4

0NUM

HNUM

ANUM

0 CHANGED FALSE

ACHANGED FALSE

00 ATE 1997/07/11

FAC 346

RTYP PWR B&W177

EXLEVEL S

EXMNR FACILITY

0 VAL 1.0

SEC

SUBSORT

KA 000037K307

0UESTION The following plant conditions exist:

An SG Tube Rupture is in progress on OTSG #1.

- All RCPs are running.

- The R0 S has reported that affected 0TSG 1evel has reached 225 inches and continues to increase.

The CTRH SRO should direct the R0 S to __ .

I a. initiate AFW flow and isolation of both SGs to prevent a high level SFRCS trip.

b. increase his steaming rate to achieve up to a 235 deg F/hr. rate down to a Thot of 500 deg F.

c. trip all four RCPs to minimize driving head for flow into ruptured OTSG.

d. increase his steaming rate to achieve up to a 235 deg F hr. rate down to a That of 520 deg F.

ANSWER b

REFERENCE DB-0P-02000 (8.18.6) R4 i

l

l I

0NUM , !

HNUM. i

ANUM i

0 CHANGED FALSE :

ACHANGED FALSE ..

l

00 ATE 1997/07/11- !

FAC 346 i

RTYP .

PWR B&W177 i

EXLEVEL S- !

EXMNR F/SILITY !

0 VAL 1.0 3

SEC !

SUBSORT- l

KA 000038A202 i

0UESTION .- .

The following plant conditions exist:- '

- 'The plant is-at 28% power. .

- Primary to secondary leakage has been diagnosed. I

- Both Makeup Pumas are running

.A decision has >een made to shutdown-the plant.

Which ONE- of the following is consistent with the indications of a SG tube rupture? :

a. Priod to the power reduction letdown is isolated. !

- Makeup Tank level is dropping at 5_ inches / minute. i

b. - Prior to the power reduction letdown is isolated. :

- PZR level is dropping at 5 inches / minute,

c. - During the power reduction, letdown is isolated. 'r

- Makeup Tank level is dropping and the rate of drop slows when the power ramp rate slows.

d. - During the power reduction. letdown is isolated. '

- PZR level is dropping and the rate of drop slows when the power ramp rate slows.

ANSWER b- i

REFERENCE

- DB-0P 02000 (1.4) R4 DB 0P 02531-(4.3.1) R1 +

t i

1 1

. - - , , = _ . ~ , , - . , , - . . . _ . . , . _ - . . , _ _ . . , _ , _ . _ . , , . - , .

I t

h c .ggg !

HNUM' {

ANUM t

0 CHANGED - FALSE t

ACHANGED FALSE r

00 ATE 1997/07/11 i

fAC 346 !

RTYP - PWR B&W177 !

EXLEVEL S j

EXMNR ' FACILITY- ;

0 VAL 1. 0 - !

SEC i

SUBSORT- -!

KA- -

000038A215 <

00EST104 . I Given the following conditions: l

-- - The plant has experienced a steam generator tube leak of GREATER .

than 50 gpm .

- N0 reactor coolant pumps are available -

- A natural circulation cooldown is in progress i The operator is directed to REDUCE RCS pressure to maintain a MINIMUM subcooling ,

margin during the cooldown. A minimum subcooling margin . .i t

a. ensures normal makeup will be capable of .natntaining pressurizer i level greater than 100-inches

b. -will reduce the differential pressure between the RCS and the l 1eaking steam generator ;

c. allows a greater cooldown rate by reducing the steam generator tube- !

to shell thermal stresses i

d. prevents a pressurized thermal shock condition when HPI is required l for RCS makeup '

ANSWER i

.'b i

REFERENCE DB 0P 02531 (4.5.6) R1 I

t.

~

,3 - d:- , -yE..-w.e-%-r- 'e--,,e .-i .h I .,w,=em..- >n ever-e m - =e 's W

k

'ONUM ,

HNUM

ANUM '

0 CHANGE 0 FALSE

ACHANGED FALSt

QDATE 1997/07/11

FAC 346

RTYP PWR-B&W177

EXLF'/EL S

EXMNR FACILITY

0 VAL 1.0

SEC

SUBSORT

KA 000054K102

QUESTION The following plant conditions exist:

- #1 AFP is tagged cut for maintenance on its governor.

- The reactor has been tripped because of a large fire in the West Condenser Pit 565' elevation,

- The fire has been put out.

- The Fire Captain reports that the fire was limited to the Condensate Pumps and #2 NFP,

2 OTSG, which has an indicated SU level of 10 inches, should be fed using a, the SUFP, provided flowrate is maintained less than 300 gpm b, the MDFP in its MFW lineup, provided flowrate is maintained > 800 gpm c, the HDFP in its normal 100% power lineup d, either MFP, provided flowrate is maintained less than 1000 gpm

ANSWER c

REFERENCE DB-0P 02000 (Att, 1) R4

e

0NUM

HNUM

ANUM

0 CHANGED FALSE

ACHANGED FALSE

00 ATE 1997/07/11

FAC 346

RTYP PWR 8&W177

EXLEVEL S-

EXMNR FACILITY

0 VAL 1,0 :

SEC

SUBS 0RT

KA 000058A203

0 VEST 10N After operating at full power for three months you note the following:

1,- ANNUNCIATORS:

DC PANEL VOLTAGE LO, 1-5 F DC BUS 1 TRBL, 1-6-E

2. VOLTAGE INDICATORS:

+125 VDC PANEL D1P El C271 reads 0 VDC All other indicators read NORMAL values

3. BREAKER STATUS LICHTS:

A bus load breaker indicators are 0FF C1 bus breaker indicators are OFF Which ONE of the following represents AUTOMATIC system response to this transient, if N0 operator actiora are taken?

a. ICS will RUNBACK the unit to 55% power due to LOW level in the Deaerators, b, RCP's 1-1 and 2 2 will automatically TRIP on loss of DC control power.

c, Annunciator 14 1 C, ICS 24 VDC BUS TRIP will alarm,

d. The #1 AFP will AUTOMATICALLY START and feed the OTSGs to 49" on the startup range.

a

REFERENCE DB 0P-02537 (4,1.1) R1

0NUM

HNUM-

ANUM

0 CHANGED FALSE

ACHANGED FALSE

0DATE 1997/07/11

FAC 346

RTYP PWR B&W177

EXLEVEL S

EXMNR FACILITY

0 VAL 1.0

SEC

SUBSORT

KA 000061A205

0VESTION The following plant conditions exist:

- The plant is in MODE 5 with the CTHT Equipment Hatch removed and fuel shuffling in progress in the SFP.

- CTMT Purge is running on the Penetration Rooms.

- Area Monitors RE 8446 and 8447 have just gone into alarm (ALERT and HIGH).

- SFAS is NOT in Shutdown Bypass.

- RP personnel have increased dose rates on their dose rate monitors.

The correct CTRM response to these indications is to .

a. sound the CTMT Evacuation alarm and evacuate persnnnel from the Auxiliary Building and CTMT b, sound the Initiate Emergency Procedures alarm and evacuate personnel from the Auxiliary Building and CTMT

c. manually initiate Station EVS Trains 1 and 2 since they are prevented from running under current plant conditions

d. realign CTMT Purge to CTHT to aid Station EVS Trains 1 and 2 in removing any harmful atmosphere

ANSWER a

RFFERENCE DB OP 02530 (Step 3.2.1) R2 ,

DB 0P 06504 (Step 2.1.2) R2

1

0NUM

HNUM

ANUM

0 CHANGED FALSE

ACHANGED FALSE

00 ATE. 1997/07/11

FAC 346

RTYP- PWR B&W177

EXLEVEL S

EXMNR' FACILITY

0 VAL- 1.0

SEC

SUBSORT

KA 00006SA206

0 VEST 10N After receiving the INSTR AIR HDR PRESS L0 alarm at 100% power, the Reactor Operator reports that instrument air pressure (using P1810) reads 72 psig and the -

secondary plant appears STABLE. Which ONE of the following sets of actions is l required to be performed?

a.- Manually TRIP the reactor and initiate AFW flow and isolation of both SGs.

b. START the standby Station Air Compressor and the Emergency instrument Air Compressor, and perform a Rapid Shutdown per DB-OP 02504. Rapid Shutdown,

c. Dispatch operators to locate the cause of excessive air demand and maintain reactor power at the present level.

d. Rapidly DECREASE power per DB 0P 02504 until instrument air INCREASES to approximately 90 psig.

ANSWER a

REFERENCE DB 0P-02528 (3.1.1) R2 h

[1

0NUM

HNUM

ANUM

0 CHANGED FALSE

ACHANGED FALSE

00 ATE .1997/07/11

FAC 346

RTYP PWR B&W177

EXLEVEL S

EXHNR FACILITY

0 VAL 1.0

SEC

SUBSORT

KA 000028K305

0UESTION The following plant c .:f'+4nns exist:

Annunciator Alarms:

(4 1-E) PZR LO LVL HTR TRIP (4 2-E) PZR LVL LO Other Symptoms:

Pressurizer Heaters are deenergized.

20" indicated on Pressurizer level indication LRS RC14 and DECREASING RCS pressure is INCREASING Which ONE of the following immediate operator actions is required by DB-0P-02513.

Pressurizer System Abnormal Operation for the above plant symptoms?

a. Close RC 11. PORV BLOCK.

b. CLOSE RC 2. PRESSURIZER SPRAY

c. Place MU 32 in HAND, adjust demand to obtain desired makeup flow.

d. START the standby Makeup Pump.

ANSWER c

REFERENCE DB-0P-02513 (3.5.2) R2

0NUM

HNUH' L* ANUM

0 CHANGED FALSE;

ACHANGED FALSE-

00 ATE 1997/07/11

FAC -346

RTYP PWR B&W177-

EXLEVEL- S.

EXMNR FACILITY

0 VAL- -1.0

SEC

SUBSDRT

KA 000036K303

0UESTION - ,

The following plant conditions exist:

- The plant is in MODE 6.

-Core off load is in progress.-

Refueling Canal level'is noticed.to be dropping at the rate of 1 foot / minute, The fuel Handling Director should ,

a .- -direct installation of the gate between the SFP rad the Cask Fill Pit

b. order the Fuel St? cage Bridge Operator (FSB0) .to place his spent fuel assembly in the ne6 rest transfer basket and leave the basket vertical?

c. direct all personnel to abandon the bridges- and evacuate the area before canaI level drops to 19 feet (S97* elevation)

d. order the Main Bridge Operator (MB0) to place his spent fuel assembly,in the deep end of the canal 19 feet below the normal ZZ tape reading

ANSWER c

REFERENCE:

DB 0P 00030 (Att. 1) R0 X '

m-

+

r -

b

0NUM ;

HNUM

ANUM .

0 CHANGE 0 FALSE i

ACHANGEO FALSE -

00 ATE 1997/07/11- .!

FAC 346

RTYP PWR B&W177

EXLEVEL S

EXMNR FACILITY

0 VAL 1.0

SEC t *SUBSORT-

KA 000056A214

0UESTION The following plant conditions exist:

LSU Transformer 01 is tagged out.

An SFAS Level 2 Actuation has occurred.

-The Emergency Diesel Generators (EDGs)-have been BLOCKED and SHUT 00WN.

The EDG Lockout Relays have been reset.

Which ONE of the followingl describes the response of the EDGs to a subsequent overpressure trip of SU Transformer 027

a. Fail to AUTOMATICALLY. start but can be MANUALLY started and tied to associated buses,

b. AUTOMATICALLY start and tie to . associated bases due to an b

undervoltage condition on associated buses.

,~ c. AUTOMATICALLY start but #2 EDG is BLOCKED froin tying to its associated bus due to the condition of SU Transformer 02.

d. Fail to AUTOMATICALLY start but can be MANUALLY started: however BLOCKE0 from tying to associated buses, b

REFERENCE B 0P 06316 (5.8.6) R1

END-11 L i

v. ,,

e i4 FINAL AS-ADMINISTERED OPERATING TEST FOR DAVIS-BESSE EXAM Tile WF;EK OF JULY 7, 1997 OI f;gGD

i i

l f

)

i FINAL AS-ADMINISTERED ADMINISTRATIVE JPHs FOR DAVIS-BESSE EXAM i

3 I

.f h

4 f

+

ES-301 Administrative Topics Outline Form ES-301-1 Examination Level (Circle One) : RO / 'e RO Facility: Davis Besee Week af Examination J7 '07/97 Examiner's Name (print): D. McNeil. E. P l t. '.t ne r __

Administrative Describe method of evaluation:

Topic / Subject 1. ONE Administrative JPM, OR Description 2. WO Administrative Questions l

A.1 Temporary mods JPM - Equipment Operator requests approval of a ;

of procedures Te porary Procedure Ch&nge that is n:t permicted.

shift Staffing JFM - 30 minutes aftt 't turr ever, one of the Safe shu:d:wn Eos is callec. .ae on a medi:al emergency.

Restore shift to minimum tr.anning leve'.s.

A.2 Faulted JFM - Completed Surveillance Test on an HPI pump will Surveillance centain insufficient data to be a valid test.

Test Appliennt rejects ST.

A.3 Knowledge of JFM + Portable detector checkout and required actiono significant to take when rediological conditions are changing in radiation an area.

hazards s. kWP Requirements A.4 Event Candidate will classify a General Emergency and Declaration and recom end evacuation of correct sub areas.

PARS Chief Examiner:, S

ES-3,01 Administrative "opics Outline Form ES-301-1 Examination Level (Circle One): RO / SRO Facility: Javis Besse Week of Examination 07/07/97 Examiner's Name (print): D. McNeil, E. Plettner i ~ Administrative Describe method of evaluations Topic /Sub,4ect 1. ONE Administrative JPM, OR

-1 Description 2. TWO Administrative Questions A.1 Temporary m<>ds 194001A116 // 3.1/4.4 // Approval for procedure of procedures deviation 194001A102 // 4.1/3.9 // Requirements for temporary procedure change approval Shift Staffing JPM 30 minutes after shift turnover, one of the Safe Shutdown EOs is called home on a medical emergency.

Restore shift to minimum manning levels.

A.2 Faulted JPM - Completed Surveillance Test on an HFI pump will Surveillance contain insufficient data to be a valid test.

Test Applicant rejects ST.

A.3 Knowledge of JPM - Portable detector checkout and required actions significant to take when rediological conditions are changing in radiation an area.

hazards & RWP Requirements A.4 Event Candidate will classify a General Energency and Declaration and recommend evacuation of correct sub areas.

PARS his or eglicant Questions for Admin JPM1 were substituted

'l 4*

Chief Examiner:

afe' /UMyA 1

N

.. 4 JPM/ QUESTION # A.I.a-1 RErERENCES ALLOWED: NO Question:

During a major plant casualty, the Shin Supervisor is faced with a .druation qdring him to doiate froin an approved procedure in order to protect the health and safety o' ke ;v blic. Whose authorization is required to allow him to deviate and is NRC notification required prior to the desiationi

/

Answer:

The SS is authorized to make this decision.

- NRC notification is not required prior to taking the action. (Notification will come later.)

SAT /UNSAT

Reference:

DB-OP-00000 (6.1.1) R03 ** '

10 CFR 50.54 (X)

K/A 194 001-Al.03

~

JPM/ QUESTION # A.I.a-2 REFERENCES ALLOWED: NO Question:

According to DB Technical Specifications Section 6.0, list the requirements for temporatily approsing plant procalure changes.

Answer: ,

1. Cannot change the intent of the procedure.

2, Made by two members of the plant management staff, at least one of w hom liolds an SRO license.

SAT /UNSAT

Reference:

Tech Spec. 6.5.3.1.b IUA 194-001-A1.03 l

l

'O: =.

JOB PERFORMANCE MEASURE No. Ata Candidate: ' _ Examiner: Date:

Facility: Davis Besse Unit 1 Task

Title:

- Proper Use of the Temporary Approval Process Job Performance Measure No: Safety Function:

K/A

Reference:

194-001 A102 4.1/3.9 Method of Testina:

Simulated Performance Actual Performance g Simulator g Control Room 3 in Plant Task Standard: Determine if a requested Temporary Approvalis appropriate.

' Required Materials: NG-NA-00115, Control of Procedures, Revision 2, C 2 ED 7635 Procedure Development Form General Refemnces: NG.NA-00115, Control of Procedures, Revision 2, C 2 ED 7635, Procedure Development Form Tims Critical Task: No EstimatedNalidation Time: 13 minutes Read to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You will make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

During the course of the walkthrough examination, there may be some tasks you will be asked to perform that may require you to implement an alternative method directed by plant procedures in order to complete the assigned task. You are expected to make decisions and take actions based on the facility's procedural guidance and the indications available.

You may use any approved reference materials rormally available, including logs. Make all written and/or oral reports as if the evolution was actually being performed.

.):

o

o .

JOB PERFORMANCE MEASURE NO. A10 initial Conditions: The plant is in MODE 3, preparing for a cooldown into MODE 5.

Initiating Cue: The outside Assistant Shift Supervisor on your shift has requested that both Boric Acid Addition Tanks be used to transfer boric acid into the # 1 CWRT from the Boric Acid Addition Pumps. He has indicated to you that this lineup is not currently in the system procedure. He has asked you to process a Temporary Approval to the procedure to make this lineup work.

He has determined the technical aspects of this change and has marked up a copy of DB-OP-06031. BAAT Operating Procedure which you have reviewed and you have concurred with the marked up sections. Your task is to process the Temporary Approval. The Shift Manager is available to perform the function of the Qualified Reviewer.

.m f

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JPhi Ala l

a- w :. 4

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Performance Information NOTE: Critical steps denoted with a "C". Failure to meet any one of these standards for this item constitutes failure. Sequence is assumed unless denoted in the " Comments".

Start Time

1. Performance Step: Initiate a Temporary Approval to DB-OP 06031, BAAT Operating Procedure using a Frocedure Development Form, ED 7635 per NG-NA-00115, Control of Procedures.

Standard: Identifies that a PDF must be ccmpleted IAW NG NA-00115, Control of-Procedures.

Cues:(AS NEEDED) Hand a copy of NG NA-00115 to the candidate and a blank PDF.

- A review of Commitments indicates none will be changed.

The PAT number is 97-0123

- No interfacing documents exist.

A Safaty Review has been completed by the outside Assistant SS.

,, - RP has determined they do not need to review.

y, A validation checklist has been completed. .

SAT UNSAT

2. Performance Step: Submit the TA to a Qualified Reviewer for approval.

Standard; indicates that a Qualified deviewer must approve the TA.

Cue: The Shift Manager will do the Qualified Review. During his review he indicates to you that he has consulted Wth tb. *>rocedure Sponsor and determined that training must be conducted on this lineup before this TA is approved.

l SAT UNSAT

)

JPM Aia i

I i

.i , .-- . __

3. Perfcrmanco St:p: Wh n pre-implement: tion tr ining is indic:t:d, a Tempor:ry Appiov:1

.........C....... Cannot be us3d.

l Standard: Indicate that a Temporary Approval cannot be used for this evolution.

Comment: Step 6.5.1.c of NG-NA-00115.

Cue: None SAT UNSAT Terminating Cue: This JPM is Complete.

End Time _

!W)

/

)

JPM Ala

PROCEDURE DEVELOPMENT FORJ IN Y PROCEDU@ ACJIVITY TRACKING NO. '

EO 7635-Mo SHEET- OF ~T/t 77- 8/2 3 SECTlON 1. IDENTIFY -

PROCEDURE NO. PROPOSED PROPOSED ONEW OCANCELLATION REVISION NO. CHANGE NO. ESTRICT 7!/#[ [

f'2/ OREVISION O INACTIVATION EXPlRES

- QV5 kli I* Q)"" ~ ~ ~ ~ ~ ~ ~ ~ ' OCHANGE O REACTIVATION (DATE/ EVENT) 97-d/2 3 '

Nb CIT [MPORARY APPROVAL PROCEDURE llTLE e

PROCEDURE CLASSIFICATION PAT /PCR NOS. CLOSED OUT

-g SR O OR O N4R CHANGE TO? O YES O NO A)dA/h - O CONTINUED A'CilVITY

SUMMARY

/ PURPOSE .

0Y Qcp op\l Dl CRY G NE Sk C N O l/

O CONTINUED

~

SECTION 2 - CONCURRENT EFFECTIVE DOCUMENTS O CONTINUED DOCUMENT NO. I REVISION DOCUMENT TITLE PAT NO. / CHANGE REQUEST Mety b c le& blQ dt SECTION 3 - REVIEW ORGANIZATIONS DUE:

REQUIRED REQUESTED O CONTINUED 0 CONTINUED EPAREfL DATE 6 4" OUALIFIED REVIEWER DATE FK[EDURp-P/(4g

( ov0Wa b.c;ded1(4 Bdk SECTION 4 - ATTACHMENTS YE . N/A (Mr "')/

Asfv#gg Q4 wwg s./

64 COMPLETED AND ATTACHED N/A YES N/A O VALIDATION CliECKUST R n +*n4v Q SAFETY REVIEW Q Q REVISED CROSS REFERENCES LIST 0 0 Couu TueNTVERIFICAT'ON

SUMMARY

Q Q DOCUMENT REVIEW SHEETS O O PCRs O O SAFETY EVALUATION O O OTHER FINAL AUALIFIED REVIEWER CONCURRENCE DATE SECTION 5-TEMPORARY APPROVAL MANAGEMENT SRO DATE APPROVAL AUTHORITY DATE SECTION 6 - CONCURRENCE / FINAL APPROVAL PROCEDURE SPONSOR DATti O SRB DATE D DIRECTOR - RA DATE O PLANT MANAGER DATE iCTOR-E&S- DATE APPROVAL AUTHORITY DATE

~

SECTION 7 - TRAINING / PROCEDURE EFFECTIVITY (RAINING COMPTTE ALTERATION EFFECTIVE DATE PROCEDURE SPONSOR DATE

- O YES O N/A

o i .

I l JOB PERFORMANCE MEASURE NO. A1b Candidate: Examiner: Date:

Facility: Davis Besse Unit 1 Task

Title:

Call Out and Proper Relief for Replacement of Safe Shutdown EO Job Performance Measure No: Safety Function:

K/A

Reference:

194-001 A103 2.5/3.4 Method of Testino:

Simulated Performance ,_,_ Actual Performance 3 Simulator a Control Room x in Plant Task Standard: Perform callout of operator to relieve the Safe Shutdown EO.

Ensure proper turnover is conducted.

Required Materials: Shift Manning List Overtime Callout List Fitness for Duty callout form General

References:

DB-OP-00000, Conduct of Operations, Revision 3, C 2 DB-OP-00100, Shift Tumover, Revision 3, C-1 FHAR Section 8.3, Revision 16 Time critical Task: No Estimated / Validation Time: 6 minutes Read to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You will make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

During the course of the walkthrough exarnination, there may be sue tasks you will be asked to perform that may require you to implement an alternative methoc directed by plant procedures in order to complete the assigned task. You are expected to make decisions and take artlons based on the facility's procedural guidance and the indications available.

You may use any approved reference materials normally available, including logs. Make all written and/or oral reports as if the evolution was actually being performed.

_. , . .- - - ----.- -- - - - - - - = - - - - ^ ^ - -

JOB PERFORMANCE MEASURE No. Alb initial Conditions: The plant is in MODE 1 at 100% power.

Initiating Cue: it is 1910 in the evening and the Safe Shutdown EO on your shift has indicated that he must leave due to a medical emergency with his family.

The Shift Supervisor has directed you to ensure that all shift manning requirements are met.

JPM Alb

,Eggigrmance Information -

NOTE: Critical steps denoted with a "C". Failure to meet any one of these standards for this

= ltem constitutes failure. Sequence is assumed unless denoted in the " Comments". .

I Start Time I

1. Performance Step: Recognize that the shift is at less than minimum manning and an EO /RO

............C............... callout is noeded.

Standard: Obtain a current shift Manning List from the Shift Supervisor for the shift to determine current manning.

Cue: Provide the candidate with a copy of the Shift Manning List.

State:"All personnel are qualified to fill the postions they have been assigned."

SAT UNSAT Comments: The sequence of the next two steps can be done in any order as long as they ere done prior to the actual phone call to the relief EO/RO

2. Performance Step: Fill out Fitness for Duty form as required by the FFD program Standard: Obtain a FFD fonn prior to callout of relief EO/RO Cue: Provide candidate with FFD form.

SAT UNSAT

3. Performance Step: Verify callout made in accordance with Overtime Rules.

Stande.rd: Obtain a copy of the current overtime list for the oncoming shift Cue: Provide candidate with the overtime list for shift 2.

SAT UNSAT JPM A1b

4. P:rferm ncs St:p: Cell:ut a relief EO!RO for Saf) Shutdown EC.

.......C.........

Standard: Callout the selected EO/Ito.

Cue: The operator Indicates that he is fit-for-duty and will report to the plant as soon as he can, SAT UNSAT Terminating Cue: This JPM is Complete.

End Time JPM Alb

e .

I >

" Schedule Char >se Nodce for July 8,97 thru July 11,97 8 July 97 - 9 July 97 10 July 97 . 1I July 97 -

Tuesday. Wednesday - Thursday Friday h .w oe. i ma. u .. .- -- m. .. n. - -. ... im-

.._ m l 6 3 I 6 4 1 6 4 5 6 4 5 g / Oeg Odha _

hkcme . Baldwm -

,g Rebens odig - nt3 .s cas -. Myas Mcces - Myan Baks w Mves Mves bivers Cag Ammet 1.4= wanes La wance Ftulhpa 5twedenen 31 # Conn Lawarme Hartwe Laesew Hause Fbhps - Hueue steenbergen Swtow C C Hanwa C C Hawa C C Hame -C C Lawerwe Sewnnky twmaky , Khen Bonns bo .

Wetenen Sennety LMrguca sawmky LMrgem Khm - Lampison parighe C C 1mmesson C C t# W C C LMne** C -C Sewneky i

shia Mauser Lahs Leka tahs Chambers Mrismen b- - Harvan tabs - Harven Labs - Harvet Chambers Harven Harvet. Harvae Lakas Havey _ h4 slam Fan Hawy Baume Faz Hawy Bonrwe Amys Hawy Bannee Amys g, F C F F F F F- F F F F F fpm Weed Howesd Dimebe Wood Fame %hien Wood Passes labe5 Wood Focaw Isked F F F F F F F F F F F F Asahaugh Tay4w Furian Asebogh Weher Ptsroen Arebaugh Wahs Junes Ambagh Walur Jones F C C F C C F C F F C F 8myte . Feknamn Ahur Emphe Bake Aber Eagke Baker Breken Empha Beker Braken F C C F F C F F C F F C (Danner m- Bias Danum Rohde Base vaueio Reade Iben vesselo Dnnened Bass vasesaa Dreianard F F F F F F F F F F F F Reedei Fwt Swoor komial We suner Retal We Gaw Ramled We Coos F P' F F F F F F F F F F

. .-. . . _ --_. _ . me. . _. ._ _ .. . . _ . _ - . ._ . . - _ _-

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CALL IN QUESTIONNAIRET +

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. SECTION 1 GENERAL INFORM ATION Pf HSON CALLED - DATE: TIME .

- RE ASON -

l r _

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l l" HAS ALCOHOL BELN CONSUMED WiiHIN PREVIOUS 5 HOURE7

-O YEs O NO llF YES, COMPLETE SECTIONS 2 AND 3 -' '

IF NO, COMPLETE SECTION 3'.

SECTION 2. APPROVAL JUSilFY WHY THE INDIVIDUAL IS NEEDED .

- DUTY PLANT MANAGER APPROVAL (Signature)

(May be obtained by telephone) x 0 YEs O NO IF DUTY PLANT MANAGER DOES NOT APPROVE THE REQUEST, COMPLETE SECTION 3 TRANSPORTATION PROVIDED?

O YES ' O NO IF NO, WHY NOTt l

SUPERVIOOH

SHIF T SECUF58TY NOTIFIED TO PERFORM BAC EXAM (Nan.e)

SECTION 3 DOCUMENTATION

~

1 CALL Oui PERFOHMED BY(PRINT Name) -.

SIGNATURE v

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.POSiilONiitTLE --.

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WHEN C,OMPLETE, FORWARD TO ACCESS CONTROL - Mall STOP 4020 br>-a - , * - - - , e +- ++ e- v4+r e = , -* ,e e.- - - +-a e*+J == w - -. *

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.P4791051 . CORPORATE TIME MANAGEMENT SYSTEM .. <

P A3E ' ' toi N YDT: OVERTIME CALL-OUT OPPORTUNITY REPOQT

.PRINTEO OM: - 07s07/97 AT* 18:40 .;.- '.- L

^ COMPANY: TED . PRINTED FOR:BRENDA K.~ '

HOME CENTER: 2182 KRUMPOW

PAY END DATE: '.07/06/97' ADDR: OB1041 ,PH; 81 7641 USER ID: BNB

*

EMPLOYEE * * *~ **

--* WORK * *'C 008 CODE DESCRIPTION ~ NAME / PHONE /~SSN '

............... .... ........................ CHARGED NON-CHARGb EXCUSED, ' TOTAL iAVAILASLE-

....... .......... ........ ...... .........s Reactor Operator MIGOT - . MARTIN - d 7 CtlRRENT WEEK 0.0 ' O . O' O.O i 419/734-1604 -0.0- -- J . . O.O '-

YEAR TO DATE 52.S 0.0 0.0 52.5 l 0.0 299-50-3356L

, Reactor Operator LAWRENCE .RODNEY S CURRENT WEEK 0.0 - 0.0- 0.0- 0.0 419/698-4402 0.0 YEAR TO DATE :92.4 48.O 0.0 92.4 i O.0 303 62-0247 Reactor Operator- WALTER . GREGORY W CURRENT WEEK. '8.0 0.O ' C 0.0 8.O ' ' O.O '

419/836-9152 . YEAR TO DATE 90.9 48.0 ' 6. 0 -

301-44-5304 96.9' 0.0 ,

~ Reactor' Operator -TAYLOR .DARREN A- CURRENT WEEK O. O - 0.0 0.0 419/535-5872 YEAR TO DATE. 5.2

. 0.01 iO.0.

0.0 96.0 101.2 l 577-96-1287

O.O' .

Reactor Operator- BONNETT . WILLIAM D CURRENT WEEK 3.0 I O.C. 0.0 3.0 l 0.0 419/666-4051

" YEAR TO DATE 108.1 52.0- 118.1 082-74-6615 10.0- .0.0

. Reactor Operator- BURK .RANDALL A CURRENT LEEK 15.6' O.O l0.0 15.4 0.0, u 419/435-0753 YEAR TO DATE 124.7 0.0 0.0 -124.7-271-60-0750 0.0

'f Reactor Operator POCINO . CARLO V CURRENT WEEK 7.4 0.0 0.0 7. 4 Ii- 0.0 !

419/862-3695 YEAR TO DATE 130.0. 46.0 145-46-2945 0.0 L130.0 0.0 .

Reactor Operator ISBELL .LAWRENCEW CURRENT WEEK O.0 0.0 0.0 0.0 ' 0. O ' - I 419/691-4838 YEAR T9 DATE 130.6 48.0 0.0 283-54-9591 .130.6- 'O.O !

. Reactor Operator HARTNETT . DANIEL T CURRENT WEEK O.0 0.0 O.0 419/626-8893 YEAR TO DATE 127.3-O' O.

0.0 j l- 32.0 6.0: 133.3. LO.O i 274-68-8895

! Reactor Operator t BECHTEL . ROBERT- H CURRENT WEEK - 7. 4 .O.0 0.0 ' 7.4 : 0.0 I 419/874-2712 YEAR TO DATE ,127.9 ~ O.0 :6.0 2133.9

l. 300-4R-7040 0.0 !

lt Reactor Operator- ANYX . WILLIAM J CURRENT WEEK O.0 -

0.0 0.0 - 0.0- .O.0

-419/898-3538 YEAR TO DATE 140.4 .32.0 0.0 140.4 j 306-66-9682. 0.0 ,

t REACTOR OPERATOR

. JONES t

. MICHAEL 8 CURRENT WEEK' O.O O.0 0.0 419/698-3651 0.0 : 0.0 i 339-40-9273 YEAR TO DATE. 140.9 tc.O 0.0' 140.8' O.O i

. s

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P479D72 P479105! YDT CORPORATE TIME MANAGEMENT SYSTEM.

OVERTIME CALL-OUT OPPORTU*fITY REPORT PAGE 20 COMPANY: TED PRINTED ON: 07/07/97 AT: 18:40

HOME CENTER: 2182 PRINTED FOR:8RENDA K PAY END DATE: 07/04/97 KRUE*0W.

ADOR: CB1041 PH: 81 7641

' USER ID: BN8 JOB CCDE DESCRIPTION

*

EMPLOYEE * * * *

_________ _________ NAME / PHONE / SSN

WORK *** g

________________________ CHARGED NON-CHARGE EXCUSED TOTAL

_______ __________ _______ AVAILABLE Reactor Operator ______ ________.

PIERSON . DAMES .L CURRENT WEEK O.0 419/734-4495 YEAR TO DATE 0.0 0.0 0.0, 468-74-2109 139.0 10.5 0.0' 4.2 143.2 0.O' Reactor Operator-PHILLIPS . THOMAS O CURRENT WEEK O.O 419/666-4385 YEAR TO DATE O.0 0.0 0.0 369-84-6095 147.9 48.0 0.0 0.0 147.9 0.0 Reactor Operator '

VHALEN . TIMOTHY S CURRENT WEEK O.4 419/898-0807 YEAR TO DATE 0.0 0.0 0.4 302-62-8455 154.1 0.0 22.0 0.0

'76.1 0.0 Reactor Operator HAVEY . RICHARD A CURRENT WEEK 419/697-0746 YEAR TO DATE 1.8 0.0 0.0 1.8 525-11-5088 171.6 32.C G.0

. 0.0 177.6 0.0 Reactor Operator FOX . DONALD F CURLENT WEEK OO 419/855-3145 YEAR TO DATE O.0 0.0 0.0 287-44-9071 178.8 0.0 0. 0 -

0.0 178.S 0.0 REACTOR OPE 7ATOR AREBAUGH .THERRAN C CURRENT WEEK 13.3 419/898-2116 YEAR TO DATE 0.0 8.0 21.3 289-62-2009 159.1 16.5 0.0 26.0 185.1 0.0 Reactor Operator CUFF .dEFFREY D CURRENT WEEK 25.2 419/635-2241 YEAR TO OATE 0.0 0.0 25.2 207-58-4374 180.3 16.0 0.0 6.0 186.3 0.0 REACTOR OPERATOR MCPHERSON . MARK A CURRENT WEEK 13.3 419/898-3325 YEAR TO DATE 0.0 8.0 21.3 409-27-5272 185.8 0.0 8.0 193.8 0.0

0.0 Reactor Operator HAUGH . PAUL E CURRENT WEEK 3.7 419/447-7903 YEAR TO DATE 0.0 8.0 11.7 275-58-9127 133.5 0.0 70.0 0.0 203.5 0.0 Reactor Operator WOOD OR , DONALD G CURRENT WEEK 9.3 419/332-6894 YEAR TO DATE 0.0 6.0 15.3' O.O 286-56-9954 149.4 32.0 117.5

=

266.9 0.0 Equipment Operator Iti THAYER . DENNIS L CURRENT WEEK 7.5 419/874-4317 YEAR TO DATE 0.0 0.0 7.5 0.0 181-52-0839 85.5- 0.0 0.0 85.5 0.0 Equ ipine n t Operator 111 MCELHANEY . PAUL R CURRENT WEEK 26.7 419/862-3887 YEAR TO DATE 0.0 6.0 32.7 20e-52-6525 65.5 0.0 0.0 43.0 108.5 0.0

._ = . . . _ . . _ .

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-l P479D72- .

P4791051 .. 1 YDT CORPORATE TIME MANAGEMENT SYSTEM' OVERTIME CALL-0UT OPPORTUNITY REPORT . - PAGE +

' 2 t i. 'e COMPANY - TED PRINTED ON: 07/07/F7 ATt 18:40:

HOME: CENTERS 2182 PRINTED FOR:sRENDA .Xh~ 'l PAY END~DATE: a 07/04/97 KRUNNOW 4

'i ADOR:'DS1041 .FH 41 7641s USER ID: SNS ; - ~-

*

EMPLOYEE * *

008 CODE DESCRIPTION:

.._____.____________ NAME / PHONE /'SSN

- WDRK* *b

. _________.____________ CHARGE 0 NON-CHARGE EXCUSED

_______ __________ TOTAL 1 AVAILABLE Eculpment Operator'Ii1 WITT

.CAVID .S CURRENT WEEK

-419/898-2302 13. C . 0.0 0.0 -

277-66-8761 YEAR TO DATE 121 9 48.0 14.0 0.0-0.0 121.S -0.0 Equtpment Operator Iit BAKER 40HN- D CURRENT WEEK 419/.145-4235 O.0 0.0 ' O.O .

i.

y; viY -4207 YEAR TO DATE 123 1 32.0

0.0 0.0 :

'O.OL .123.1 . 0.0

'Eautpment Operator Ill BRACKEN . FRANK R CURRENT WEEK 419/637-2304 O.0 0.0 ' O.O -

VEAR TO DATE 119.0 O .'O O.0 536-44-9456 32.0 6.0 125.0 0.0 Equfpment Operator Itt GORE . MARTIN D CURREhT WEEK 8. t .

')

4 419/734-2134 YEAR TO DATE 0.0 : 0.0 8.1 297-60-8872 122.8 32.O ' . 0.0 6.0 128.8 0.0, Equipment Operator I11 ROWLANO . DONALD P CURRENT WEEK 419/661-2630 8.5 0.0 6.0 YEAR TO DATE 100.4 '14.5 0.0-275-68-52to 0.0 30.0 130.4 ~ 0.0 Equipment Operator Its .}

BOLTON . TIMOTHY A CURRENT WEEK 6.7

419/332-6343 YEAR TO DATE 0.0 8.0 14.7 280-70-0998 123.5 0.0 17.0.

0.0

' 140.5 : 0.0 Eculpment Operator I1: PURK . RONALD R CURRENT WEEK 419/898-5315 25.2 0.0 YEAR TO DATE 128.3 8.0 33.2 0.0 '

296-64-5333 0.0 14.0 ' 142.3 0.0 '

Equipment Operator Itt SUTTER .CHRISTOPJ CURRENT WEEK 9.6 419/334-7482 YEAR TO DATE 0.0 0.O'- 9.6 093-40-5511 126.6 0.0 0.0 18.0 144.6 0.0 Equipment Operator Ii1 VASSELLO . VINCENT d CURRENT WEEK 15.4 419/898-6068 YEAR TO DATE 0.0 0. 0 ' 15.4 204-60-2371 146.5 48.0 0.0 .

-0.0-146.5 00 Equipment Operator Its DROUILLARD . BRIAN E CURRENT WEEK 419/898-0996 O.O' O.O O.0 YEAR TO DATE 162.9- - 0.'O O.0 262-79-4391 32.0 6.0 168.9 0.0 Equtpment Operator Itt EMPCKE .MARLENE S ,

CURRENT WEEK 17.4

t 419/898-0326 YEAR TO DATE O.O ' 6.0 23.4 'O.O 298-44-3603 159.2 32. 0 -- 14.0 173.2'

0". O

! Eau!pment Operator Iti i- ALTER . DON G

CURRENT WEEK O.3

, 419/862-2733 YEAR TO DATE 0.0 ' O.O ' O.3 525-04-1462 162.4 0.0 ' O.O .

12.0 -174.4 0.0

. ~ e CORPORATE TIMf MANAGEMENT SYSTEM PAGE 22"

YOT OVERTIME CALL-OUT CPPORTUNITY REPORT PRINTED CN:

07/07/97 AT: 18:40 .

pgv COMPANY: TED PRIN'ED FOR:BRENDA K HOME CENTER: 2182 KRUMNCW PAY END DATE: C7/04/97 ADOR: DB1041 PH: 81 7641 USER ID: BNS

*

EMPLOYEE * * * ** .* WORK ***

C03 CCOE DESCRIPTION NAME / PHONE / SSN CHARGED NON-CHARdE EXCUSED TOTAL AVAILA8LE Equipment Operator- 111 FEHRMANN . STEPHEN M CURRENT WEET 9.9 0.0 0.0 9.9 0.0 419/732-3906 YEAR TO DATE 177.3 3.0 0.0 177.3 0.0 391-60-9715 Eculpeent Operator 111 BOSS .KEVIN d CURRENT WEEK 12.4 0.0 6.0 18.4 0.0 419/898-7619 YEAR TO DATE 174.5 16.0 6.0 180.5 0.0 275-60-2792 Equipment Operator I11 ROIDL . MARTIN d CURRENT WEEK 41.2 0.0 0.0 41.2 0.0 419/334-7244 YEAR TO DATE 182.5 34.0 0.0 182.5 0.0 078-44-9058 Equipment Operator 111 ROHDE . GARY K CURRENT WEEK 1.1 0.0 0.0 1.1 , 0.0 419/734-9846 YEAR TO DATE 191.5 1.0 0.0 191.5 0.0 294-68-7105

Ecutpment Operator It1 DENTON .MELVIN A CURRENT WEEK 6.9 0.0 8.0 14.9 0.0 419/797-3818 YEAR TO DATE 190.3 0.0 8.0 198.3 0.0 316-68-5943 Communications Specialist MEECE . CARL D CURRENT WEEK O.0 0.0 0.0 0.0 0.0 419/332-1632 YEAR TO DATE 10.5 0.0 0.0 10.! O.0 u 280-58-4898 Operating Assistant NAVARRO . DAVID L CURRENT WEEK O.O O.0 0.0 0.0 0.0 517/485-3163 YEAR TO DATE 48.6 0.0 0.0 48.6 0.0 366-G6-8120 Operating Assistant ANSLEY . DAVID A . CURRENT VEEK O.0 0.0 0.0 0.0

~

0.0 517/445-2705 YEAR TO DATE 80.6 4.5 0.0 80.6 0.0 289-58-4290 Operating Assistant MAGERS .BERDELt. J CURRENT WEEK O.O O.O O.0 0.0 0.0 419/898-1475 YEAR TO DATE 85.2 0.0 0.0 85.2 0.0 270-46-6176 45 RECORD (S) PRINTED.

CALL IN QUESTIONNAIRE ED 8139 SECTION 1 GENERAL INFORM ATION j

j PE RjON CALLED ljd N DATE f g g%

Dq A?

g .M E

/ QKcf m L^> 0 00/ ( '

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REASON \

Q %' E.v^ fV\ o n dm d *% $%0 $ O M hl/ !)\) /\l@{ )

(Ca b.wde ) r x

/, d' (_ 7 Y O R __

f % ) - % <\e,v HAS ALCOHOL UL EN CONSUMED WiiHIN 'RE VIOUS 5 HOURS?

O VEs Q NO

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I, Mfh,k, b k!$P IF YES. COMPLETE SECTIONS 2 AND 3 g - d gg,g IF NO. COMPLETE SECTION 3 SECTION 2 APPROVAL JUSilF Y WHY THE INDIVIDUAL IS NEEDED -

DUTY PLANT MANAGER APPROVAL (Signature)

(May be obtained by telephone) y 0 YES C NO IF DUTY PLANT MANAGER DOES NOT APPROVE THE REQUEST, COMPLETE SECTION 3 3thNSPORT ATION ( ROVIDED?

O YES O NO IF NO, WHY NOT 7

~

SUPERVISOR SHIF T SEe.URITY NOTiflEL .'O PCRFORM B AC EXAM (Name)

SECTION 3 DOCUMENTATION CALL.OUT PERE ORME BY(DRINI - ame

_ ( O- ih (1 Q( Q Ol J ' OMk SIGN A10RE / '

QM (( f ~

P b' k

POSITIONiitTLE /

WHEN COMPLETE. FORWARD TO ACCESS CONTROL - Mall STOP 4020

.$9 * ..

JOB PERFORMANCE MEASURE NO. A2 -

! Candidate': O------ - Examiner: O----- Date: O-----

Facility: Davis Besse Unit 1 Task

Title:

- ' Rejection of Completed Surveillance Test Due to incomplete Data Taken During

~ Surveillance Job Performance Measure PG----- Safety Function: 01----

K/A

Reference:

194-001 A108 2.6/3.1 Method of Testina:

' Simulatad Parformar.ce O----- Actual Performance x Simulator . Control Room x ' i n-Plant D-----

Task Standard: Perform review of a completed surveillance test. Identify insufficient data and reject surveillance test Required Materials: DB-SP-03218, HPl Pump 1 Quarterly Pump and Valve Test, Revision 4 with errors inserted.

General

References:

DB-DP-OOO13, Surveillance and Periodic Test Program, Revision 4 DB-SP-03218, HPl Pump 1 Quarterly Pump and Valve Test, Revision 2, C 5 Operations General Policy - GP 21, Operav;iity Determination DB-OP-00005, Operator Logs and Rounds, Revision 6 Time Critical Task: No

- Estimated / Validation Time: 10 minutes

- Read to Performer:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. -_You will make all written reports, ora! reports, and log -

entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

During the course of th'a-walkthrough examination, there may be some tasks you will be asked to perform that may require you to implement an alternative method directed by plant procedures-in order to complete the assigned task. -You are expected to make decisions a.1d take actions based on the facility's procedural guidance and the indications available.

'You may use any a'pproved reference materials normally available, including logs. ' Make all-written and/or oral reports as if the evolution was actually being performed.

L4- ;, ,

. JOB PERFORMANCE MFASURE NO. A2 -

?

B in!tial Conditions: The EO assigned to Perform the #11 HPl Pump Quarterly test h'as returned :

- the ST to you for your review.- [

Initiating Cue: ' Here is the completed Surveillance of the # 1 HPl pump, DB-SP-03218, HPl Pump 1 Quarterly Pump and Valve Test. You are to perform the

- supervisory review of the test.

t 1

(

Y

+

r 9

r- y --

-r.vw-,--e ---r- , , , _ , ________._____i______________m_E.

L- .

. JPM A2 Performance information NOTE: Critical steps denoted with a "C". Failure to meet any one of these standards for this item constitutes f ailure. Sequence is assumed unless denoted in the " Comments".

Start lime

1. Performance StepReview the completed ST for completeness and accuracy.

Standard: Recognize several of the following:

Step 3.1.6 - Incorrectly initialed Step 3.1.7 - SS authorizes permission to perform test af ter EO started Step 4.1.14 - FISHP4B is not filled in with value calculated in Step 4.1.11 Attachment 1 - Notes oil pressure is 17 psig on shutdown pump Cue: None SAT UNSAT

2. Performance StepReject the #1 HPI pump test.

........C..........

Standard: Determine Attachement 1 of DB SP-03218 has an insufficient number of readings (20 minutes -vs- required 25 minutes). (May note other errors on Attachment 1, but must note the insufficient data.)

Cue: If asked, "the data on the ST is accurate."

SAT UNSAT

3. Performance 5tepNotify the Shif t Supervisor the test data is incomplete and the ST needs to be rescheduled / redone.

Standard: Observe communication with the SS Cue: The SS aknowleges the f a: lure of the EO to properly complete the ST. Tl.e repeat of the ST will be performed by anothcr operator. A PCIOMR will be generated by the SS.

SAT UNSAT Terminating Cue: This JPM is Complett:. End Time JPM A2 l

,Ql W T' ', .

, DAVIS-BESSE NUCLEAR ItWER STATION Test Cover Sheet

- 'srunot - TtS11ntt Quswiv 19)mio ANav'iwe reg '

( F SP-0321s HPE POMP 1 LV PEnORurn TO MtrT r,aamar ION tQUiPMr nNUMnER l TESTSEp/ el

/ / UN [ -

Cl nnORurn TO rNSunE OPER .niuTY O - COMrtrnON OFSUSPENDEDRST RST INTMATF.D ))) /1 I DATE

/ O Y 30 TIME C MAINTENANCE / POST-MODITICATION TEST /

MWO NUMDER(5) -

vtSt COurtETr0 7/9 / 'l 7 , /037

' DA'fE 0 d k$ b '

TIME Tr.sT trinal O ASSe xumPTANCE CRntRtA MAv sit ArrtCitD COMPEETED TEST SUSPEND [D TEST SUPE.RVIC3R SiltlT SUPERVISOR O T*3T DDICIENCY LIST ATIAQ(ED ANDkESOL\TD REASON FOR SUSPENSION -

(TIST DEI'lCll? ICES AITECTINO ACCE*T ANCE CRTil AlA RISOLVFD STT11 RfQUIRTD SIGNATlrgEs) 0 - itST TtST DATA AND CAlfULATIONS REVIE4TD O ACCErrANCECuitRtrMET O FAD.EDTEST PCAQR8 O TSr$NOTTHED/TISTIDOUPDATE SU TRVISOR*:

FORUARD TO TSPS DATE TIME TECilNICAL SPECIFICATION PLANNESUSCIIEDULER (TSPS) __

OttCHSPEC OCOMPL OoPERABt.E OMAiNT OFrarD RIMARKS:

O itST DEriCrENCY ATTACIIED W DAR SHDT SUPERVISOR

DATE/ TIME

' FORWARD TO RICOPDS MANAGMENT UNLESS REVIEW

RETURN TO TSPS MUIRED FOR O iST ttST ENGINEER. TECHNICAL SPECIF1 CATION PLANNER *5CllEDULER Q DELAY NOTED ON TEST SCHEDULE 1TST ENGINEERING (ASME PUMP OR VALVE ONLY ) 123% LATE DATE:

TEST FRIQUENCY ClLANSE NECESSARY O vis DESIGNATED REVIEWER UNED -

O . Tsr$ NOTirtED Or ntEQUENCY otANOE TSPS DATE REMARKS:

PERFORMING ORCANIZATION O DEtAY WILL EXCEED THE TECH SPLC LATE DATE DOCUMENTED O!< PCAQRN O REASON FOP, SUSPENSION RESOLVED, TEST MAY BE

- COMPLEITD OR REFERFORMED IST DATA REVIEWED BY' DATE O en (FORWARD 1D 11PS WITION 10 WORKING DAYS.

RESPONSIBLE SUPERVISOR DATE REVIEW INDIVIDUAL REMARKS; ,

EARLY DATE _/,,,,,,,_/_

DESRED DAM i f

' asVmWsD aY. DATE l *(toRWARD ? D TSPS WTTHIN 10 WORKING DAYS. TATE DATE ,_,f___/__

i ..', ~ Y..

PROCEDUMt AC1tvifY TRACsuMQ 8epug(Q

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,P,R_O,C, E DURE DEVELOPMENT FORM ' j \ g,gg j SECTION 1. IDENTITY i

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O N SECTION 5 TEMPORARY APPROVAL

. w, SECTION 6 CONCURRENCE / FINAL APPROVAL k,$E (_ W .\ r s , l1f51/4 G l=~ $ )~'

- PLAgtwan.Ac a ! oat g A**6aaval Auf Tv Daft

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Page 1 of 37 +

{ l l Davis.Besse 11uclear Power Etation SURVE1Lt.AllCE TEST PROCEDURE

                    #                              Dfi-SP 03218 IIPI l' UMP 1 QUARTERLY PUtiP AllD VALVE TEST REVISION 02/ TOTAL REVRITE Prepared by:

I!(afft 3 Date b l "b 5* -' ( N " ;* l!D/f 3 ( Sponsors " Date Prima ~ry Systems Supervisor Approved by: __p- A - ////7.? Systems Engineering Hansger _'Da(c Et f active Date s __-. / / 7, (:c tomrntatnn .. ' po< mer,-.

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6 h 6 '

Procedute Classificationi k"< V !! l 'li '1 ' L' U i i X Safety Related O. C Quality Related Non-Quality Related

2 DB-SP-03218 * + Revision 02, . , C-5 HP1 PLMP 1 QUAllTERLY l'tMP At4D VALVE TEST LIST or ErrECTIVE l' AGES ( Change tio. Page Change flo. Page Change 140. Pa r,e _ 1 _23 C& __ C.5 24 C4 2 _ _ _ ___

                                /                 25        C-5 3          _-.C- 1 4                                      26      _
            $                                      27                                          .

28 6 . . C-1 C-3, C-1 29 _ C-1 7 8 C-1 30 9 C-5 31 10 C-1 32 C-1 33 11 12 _ 34 C4 C2 35 C4 __13 C2 36 C4 . 16 ,_ 15 C-1 37 16 C-5 17 C-1 18 C-2 19 C-5 20 C-5 21 C6 22 C-4

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                 &'                                                                      3                                      DB SP.03218
       ^          '

R@ vision 02 , c.1 HP!- PUMP 1 QUARTERLY PUMP AND VALVE TEST TABLE OF CONTENTS 1

                                                                                                                                =                                                                       l 4
                                =1.0      PURPOSE . ..... . . ..... .. ..... . .. . .

5 : 2.0 - L1 HITS AND PRECAUTIONS ..... . . . . ... . .. . . . ! 3.0 PREREQUISITES . ... ., . ..... .-. . .... . ... . . 7 fC*I { 4.0 PRdCEDURE . . . . . . . . . .' . .:. . . . . .. . . _ . . . _ 13 { 4.1' HP1 Pump 1 Quarte:1y Test .. . .. . .. . . . . . 13 1 4.2' BW26 Reverse Plow ..... .. . . ... . . . . . 21 ; S.0 ACCEPTANCE CRITERIA . . .~. . . . . ...... . .. . . 23 , I 6.0 RECORDS . . ........... . . . . .... .. . . 26 7.0 REFERENCES ............. .. .. . . ... . . 26 : ATTACHMENT 1. HP1 Train di Data Sheet . . . . .-. . . .. . . 28 ATTACHMENT 2. HPI Pump di Acceptance Criteria curve . . . . . 31

ATTACHMENT 3. PIShP4A Instrument Valve Manifold Sketch : ..... . . . . ... . .. . .- 32 l

ATTACHMENT 4. HP1 System Leak Test Checklist .... .. . . 33 I ATTACHMENT-5.- FISHP4 Instrument Valve Manifold / Test Instrument Installation Sketch ... . .. . . 37 I i i I s 5 I f i f I e

 ..k.
                          .- - _ _ , .       .~. - ,.   .   ..__s.,              . - _   _. _   _. -. - . _ , ~                 . , . - - _ . _ ~ . _ . . _ . - _ - _ _ , - - - .   -

4, DB SP-03218

Revision 02 1,0 PURPOJ[

This test will verify High Pressure Injection (HPI) Pump ( 1.1 least once every 92 days when in HODE 1 2. or1 3. is OPEP.ABLE at by per f ormin6 the following: 1.1.1 tieasuring the following HPI Pump 1 parameters and veritying they are within acceptable limits o Suction Pressure o Discharge Pressure o flow Rate o Bearing Temperatutes o Vibration Amplitudes o Lube Oil System Pressure 1.2 Per the periodicity requirements of DB-PT-00201, ASME Section X1 Inservice Testing Pumps and Valves, this test will veri'iy proper valve operation of the following valvess 1.2.1 forvard flow testing of the following check valves o HP32. !!PI PUMP 1-1 RECIRC STOP CllECK VALVE ( o HP33. IIPI PUMPS RECIRC LINE TO BWST CllECK VALVE o HP 102. HPI PUMP 1-1 LUBE OIL SYSTEtt AC PUllP CHP.CK o HP 105, llPI PUHP 1-1 LUBE OIL SYS DC PUMP CifECK 1.2.2 Hensure the closed stroke time and valve stem positions o HP32. HPI PUMP 1 1 RECIRC STOP CHECK VALVE 1.2.3 Verify proper operation (Partial forward Flow) of Lt.e following check valves: o HP10, HPI PUMP 1-1 SUCTION Lil4E CHECK VALVE o HP22 HPI PUMP 1 1 DISCHARCE LINE CHECK VALVE

                                                                                                                     ~r_..                                                                   . . . . , . . - - - - , _ . _ _ - _ _ _ _ . . _ -           _ _ _ . _ _ _ _ _ _ _ _ _ _                      _ _ . _ . _ . . _ _ _ -_ _ _ _ _

I

                     '                                       5                              DB.SP-03218

Revision 02 j 1.2.4 Verifles proper operation (Reverse Flow) of the f ollowing check valves: 1 o HP 105. HP1 PUMP 1-1 LUBE 01L SYSTEM DC PUMP CHECK o HP 102. HPI PUMP 1-1 LUBE OIL SYSTEM AC PUMP CHECK o BW 26. HP1 TO EWST RETURN LINE CHECK VALVE 1.3 Perform a channel check of HPI Flow indication by comparison of V iridication to actual system conditions.

1.4 Checks for leakage from HPI Trein 1 components. 1.5 Successful completion of this test fulfills the following Technical Specifications Surveillance Requirementst o 4.0.5 for High Pressure Injection Pump 1 o 4.0.5 f or 9717, h*32. HP22. !!P33. HP102. HP105. (forward flow) o 4.0.5 for HP102. HF105. BW26 (reverse flow)

  -s                        o      4.3.3.6 for FYIHP3C and FYIHP3D.

o 6.8.4 for HPI Train 1 mechanical joints (every 18 months) (- 2.0 LIMITS AND PRECAUTIONS 2.1 Administrat_ive 2.1.1 During performance of this test, the train for which the test is being performed vill be inoperable with HP 29 open. If the system is needed for safety functions, it is the responsibility of the operator performing the test to close HP29 to permit HPI flow to the RCS. 2.2 Equipment 2.2 1 The number of allowed successive starts with motor

initially at ambient temperature is two starts. The number of successive starts with motor initially at operating temperature is one start. In both cases.

5 minutes must elapse before an additienal start.

6 DB.SI.03218 * ' ' R2 Vision 02 , . ,' . C.1 2.2.2 The following are acceptable limits and shall not be exceeded for HPI Pump 1: ( HP1 Pump 1 Computer Points Description Hax. 7462 HP INJ PHP 1 HTR 0/B BRG 07 180er 7463 HP INJ PHP 1 HTR P/E BRG Of 180er 7464 flP INJ PHP 1 HTR STATOR TEMP 256sf T465 HP INJ PHP 1 THR BRG HT ! 1700F 2.2.3 liinimum recirculation flow limit is 35 gpm per

                     !!PI pump. The alarm is set at 37 gpm which indicates insufficient flow for operation.

2.2.4 A total !!PI Pump Flow of 950 gpm shall not be exceeded. 2.2.5 A steady total flow of 400 gpm shall not be exceeded on the flow test line. 2.2.6 Ensure the applicable Component Cooling Water Pump is providing flow to !!P1 Pump 1 Bearing 011 Cooler. 2.2.7 Hinimum Recirculation Flow Indicator FISHP4A (narrow range 0 to 75 gpm) shall be isolated at the (, instrument manifold (il ECCS Room) to prevent over ranging during this test. 2.2.8 Due to the possibility of it strument drif t any Validyne transducer used should be zero checked prior ' to and af ter completion of this test. 2.2.9 During the perfotmance of the Pump Quarterly Test and the performat.ce of subsection 4.2 (BV26 Reverse Flow .c.l Test) the BVST recire pump will be shut down. The SFP purification return flowpath to the BVST also will be isolated during the performance of Subsection 4.2. 2.2.10 HP1 Pump 1 suction and discharge HETE pressure gages shall be isolated when starting HPI Pump 1 if installed without snubbers.

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                            #                                                                               7                                                                               DB.SP.03218

R3visicn 02 ,

C-3 3.0 PREREQUISITES

                                                                                                              *                                                                                                      )

tu!TIAts . 3.1 Administrative [ Col NOTE 3.1.1 This test is written assuming stopvatches are l ' used to record valve stroke times to meet ASME l h' Section XI requiremento. VOTES or recorders 1

                                                                                     -may be substituted for the stopvatch.                                                                         I
                                                                                                                                                                                                    \

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _'. _ _h 3.1.1 Obtain a stopvatch or other equipment to record valve stroke times and record equipment number and cal due date on Attachment 1. bbd 3.1.2 Perform an inspection for operability of the

                                                                                           -redundant train in accordance with DB.OP.00000 Conduct of Operations.

b 3.1.3 Determine from the Computer Surveillance Test Schedule if a HP1 Train 1 leak test must be performed for this test. .b HP1 Train 1 leak test required for this testa YES (circle one)

                                                               .bM              3.1.4       Notify the Metrology Lab that a post test calibration of suction and discharge test pressure gages will be required.                                                                                                   f C-3 k              3.1.5       Obtain permission from the Shift Supervisor to reposition the following locked valves in accordance with DB.0P.00008. Operation anc Control of Locked Valves.

Valve Description HP26* HPI PUMP 1 1 PLOW TEST ISOLATION VALVE HP32* HP1 PUMP 1 1 RECIRC STOP CHECK VALVE

Controlled per DB.0P.00008. Operation and Control of Locked Valves

(. s

_ _ . _ _ _ . . _ _ - . _ . . _ . . _ ___ _ . - . _ . _ _ . _ . - _ . ~ -

                                                                                                                                                   .m__     _ . - _ _ _

8 DB.SP.03218 , i

 ' *-                                                                                                                                Rsvision 02,         ,
                                                                                                                                                                                  .-   i col INITIALS

( l l HOTE 3.1.6 Haintenance that could affect pump or valve I performance may require Performance Engineering l l to re-evaluate ! resent reference values. This 1 l test may be necessary to ensure current reference i j values are reconfirmed or to establish new 0 l reference values. , c 17----. .--- -----.--.--------l M_ 3.1.6 IF this test is being performed for Post Maintenance that could af feet purap or valve performance THEN contact Test Engineering AND record HWO numbers _ below. HWO Nos. Person Contacted h 3.1.7 Sign onto an RWP as necessary. bjA 3.1.8 Obtain Shitt Supervisor's perinission to perform this e 0900 Shift Supervisor: di ~ 3.2 Equipment bk 3.2.1 Perform the HP1 Pump Prestartup and Standby Check-Off List, in DB 0P-06011. High Pressure Injection System ( ' Procedure, for HPI Pump 1. 3.2.2 H the plant is in HODE 6 THEN verify the following valves are closed: 1)A,_, o HP2C HPI LINE 1 1 ISOLATION VALVE . MA o HP2D. HPI LINE 1-2 ISOLATION VALVE 3.2.3 g the plant is in H0DE 6, ' g THEN verify the following breakers are opent NN o BE 1103. HP2C HP1 70 RCS COLD LEG 1-1 ISO VLV (EllA) Mb W o BE 1105. HP2D HPI TO RCS COLD LEG 1-2 ISO VLV (EllA) t b_,, 3.2.4 . Notify Hechanical Haintenance that vibration readings are required in accordance with DB.HH-05003. Vibration Honitoring Instructions. Ensure Hechanical Haintenance is aware that the vibration acceptance criteria is based on the HPI Pump 1 inboard bearing horizontal vibration measurement (C-H). (Refer to Note 5.3) 1

                                                                                                                    ....~,.,_e.',ne..,.,nne._--.
                                                                                                              '~~         '

- ,- , , - - - - i.v--,,, ..w,- ,. .ww.,--- .,..,.-Aw.',

                              '                                                                      9                 DB.SP.03218                      i
                                * .                                                                                    R3 vision 02 a

C.$ INIf!ALS l j NOTE 3.2.5 and 3.2.6 l ; I

                                                       !       Snubbers are optional. If no snubbers are installed H&TE pressure gages shall be isolated               {

l when starting HPI Pump 1. 1 1.-____________---__.---_l 3.2.$ Request I&C to perform the following8 Md.,,. #

a. Remove.PIIS19A Install a 0 to 50 or 0 to 60 psig with a NM b.

10.1 percent accuracy or better, test gage with snubber.

c. Place test gate in service.

_[33 0 3.2.6 Request I&C to perfor1n the following i

                                        ' kN                          a.      Remove PINP58

[ , NOTF. 3.2.6.b l I s A 10.1 percent. accuracy gage must be used. I (.3 ; Acceptable ranges are 0 2000, 0 2500 and h- .0 3000 psig with the 0 2000 psig being preferred. h I___________________________l ; b)b b. Install a o to 2000 psig with a 10.1 percent accuracy or better, test gage with snubber. b c. Place test gage in service. . CAUTION 3.2.7 FISHP4A Narrow range flow indicator is isolated to prevent overranging the gage at the flows encountered during this test. 3.2.7 Have..ILC isolate FISHP4A (narrow range. O to 75 gpm flow indicator) by performing the following . (Refer to Attachment 3, FISHP4A Instrument Valve Manifold Sketch). 4 a. .Close.high pressure isolation valve. k *

b. Open equalizer . valve, b -c. Close low pressure isolation valve.

s I

l - - . -

DB.SP.03218 i 10 , g' Rsvision 02, . ,' . l C-1 INITIALS _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _- ___ ( ! t i i l : l HOTE 3.2.8 -I

                                                   )                                                                                             .

Unless otherwise directed.. intentions are to use ( the installed 0 1000 GPH gage at FISHP4. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _I j H using a Validyne transducer for measurin6 flow 3.2.8 e V TJHEN request 1&C to perform the followings (Refer to Attachment 5. FISHP4 Instrument Valve Manifold / Test Instrument Installation Sketch) NOTE 3 2.8.a f i J H the installed 01000 GPH gage is not used THJEN ' f C-l , the only acceptable test instrument for measuring flow at F15HP4 is a Validyne transducer with a l number 44 diaphrsgm installed.- l g -_________ ______ __________ MA_ a. Instail a validyne transducer with a number 44 diaphragm with snubbers in parallel with F15HP4. g

h. riace test instrument in service. ,

E rJ A "p,Y - bl_ /jt., c. Verify any Validyne transducer used reads 0.0 1 25 mVolts with no flow. , 3.2.9 Record test instrument equipment numbers and

                               -                                   calibration due dates on Attachment 1, HP1 Train 1 Data Sheet.

3.2.10 Record the following on Attachment 1. HP1 Train 1 Data Sheet.

a. Method used to measure HP32* stroke time.

N b. Equipment number and calibration due date of timing device used to measure HP32* stroke time. L ! econtrolled per DB.0P-00008, Operation and control of 1,ocked Valves I i

 '                                                  11                       DB SP-03218

Revicien 02
i C-1 INITIALS kh 3.2.11 Il the computer is available.

THEN verify the following data points have been put , on a Computer Operators' Special Summary, to print ! out at 5 minute intervals. l Description Computer Point ilP INJ PHP 1 TilR BRG MT T465 IIP IHJ PHP 1 HTR P/E BRG OT T463 IIP INJ PMP 1 HTR 0/B BRG 07 T462

                  '               HP INJ PMP 1 ItTR STATOR TEMP         T464 3.2.12        Verify Component Cooling Vater Essential Train 1 is in service and is providing cooling to the llPI Lube 011 Heat Exchanger.

b) 3.2.13 Verify R0-5989 is installed in the system in place of RO-HPl. b)b 3.2.14 Verify personnel are stationed at the local observation points to record data and are in commun! cation with the control rooms o FISHP4B 565 near il Mechanical Penetration Room o FISHP4, #1 ECCS Room L o HPI Pump 1 Suction and Discharge Pressure.

                                         #1 ECCS Room

_hk 3.2.15 Verify HPI Pump 1 instrumentation is in service per DB.0P-06011 Attachment 3. f- C * ! b 3 . .' .16 IF maintenance was performed on HPI piping which drained any portion of the system. THEN ensure the system has been refilled with water by venting the llPI pump casings and discharge high point vents as applicable, per DB SP-03212. Venting g of ECCS Piping. [ 3.2.17 IF required in Step 3.1.3 THEN obtain'a stop watch for use during HPI System Leak checks and record calibration data on Attachment 4 HPI System Leak Test Check List. 3.2.18 Verify FISHP4 is in calibration M A recor( Ct1 Due Date on Attachment 1. HPI Train 1 Data Sheet.

      '                                    22                                    DB.5P.03318                                                                  ,

Revision 02' IllITIALSg [ h 3.2.17 JF performing Subsection 4.2, T!!EN obtain a hose, a bucket and a stopwitch and record equipment number and calibration due date on Attachment 1. Section 3.0 completed by _ ; Date 9 f

w

                             -. _ . . . _ . .              . ._ . . _ .              _            .     .__   .._._     ___._m._m.          . _ _ _ _ _ _ . _ _ _ _ _ . . _ . _ _ .
   ,e                                                                                                13                                   DB-SP-03218
                                                         .                                                                                Revision 02 C.2                                                            l 1

4.0 PROCEDURE 4.1 HPI Pwnp 1 Quarterly Test INITIAt$ i V Mk 4.1.1- H a Va11 dyne transducer is installed THEN verify output reads 0.0 + 25 mVolts with no flow. ~ OR contact ILC Maintenance to re.zero the transducer to 0.0 + 25 mVolts. J FOTE 4.1.2 l l l l- o When the system is operating, no- flow on l

                                                -- l                        FYIHP3C or FYIHP3D is defined as any                                                 l c ')

l indication less than 75 spm. L o At zero system pressure the flow indicator may indicate o to 75 gpm. This is because ! d* A the flow transmitter undergoes a shift in 1. Its output from zero.to system operating l pressure. This shift is compensated for at j zero system pressure and this compensation ( y- can therefore give a flow indication on the l meter. When the system is. pressurized to l ,{, l system operating pressure. then the flow Indicator should read within specified l l tolerance. Therefore, at zero system l pressure a flow indication of 0 to 75 gpm l ( ,, J is acceptable. l____________________________l _ .h( 4.1.2 Verify FYIHP3C and FYIHP3D indicate no flow, from the Control Room. 4.1.3 Record initial set of readings on Attachment 1. HPI Train 1 Data Sheet. 4.1.4 I_F computer is available THEN Start Computer Operators' Special Summary.

       ,                b                        .4.1.5                      Open HP1556. HPI PUMPS RECIRC 70 BWST.
                   %A                               4.1..                    Open HP2...- Hr1 ruaP 1-1 rt0V TEST IS0tATION vAtvs.

Cont rol'1et per DB.0P-00006.: Operation and control of Locked Valves i ,

e -, w -s .# ,.e --.r-iva-- , er ww. -v -,.ew e- w y , - ,.,m.-.rew7. .e, -c, -. rm vv .- -*- --*

14 DB.SP.03216 ,',

      **                                                                                                                         Revision 02,                    .  ,
                                                                                                                                                                          .*    7 C.2                                            !

1NI QA,lj 4.1.7 IF snubbers were NOT installed on H&TE gages for HP1 ( l Pump 1 suction and discharge pressure imilcators. THEN isolate the HLTE gages prior to starting HPI i Pump 1. : 4.1.8 H the torated Water Recirculation Pump is in i operation. THEN stop the pump using HIS 1613 located on control Console C5718. j 7--- l NOTE 4.1.0 l ' l If the DC lt.be oil pump f ails to start or does I not stop when the AC lube oli pump is running a test deficiency shall be written. 1

           .hb _,,,,                                               4.1.9             Start HPI Pump 1 from the Control Room using HIS 1524 A @ verify P197-2. HPI Pump 1 DC Lube 011 Pump.

starts A,N,LD then stops. b,,,, 4.1.10 E HP1 Pump 1 suction and discharge HLTE pressure gages vert isolated. THEN unisolate the H&TE pressure gages. Verify and record minimum recirculation flow is k. ,,, 4.1.11 greater than 37 gpm and less than or equal to $7 spm. ; as read on FISHP48. HP1 Pump 1 Hinimum Recirc Flow Indicator. , FISHP43 $ 7. gpm. , I NOTE 4.1.12 l l i No flow on FYIEP3C or FYIHP3D is defined as any l l Indication of 75 gpm or less. An off-scale low } U"3 l reading (flashing zero) is also acceptable. l l Instrument is calibrated at operating pressure

l l and exhibits a-sero shift when read at sero l l system pressure. l_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _l _h 4.1.12 Verify FY1HP3C and FYIHP3D indicate no flow from the Control Room. bN - 4.1.13- Verify the following-annunciator alarms are received: (3 1.D) HP INJ 1 1 FLOW LO (3 2.D)-HP INJ 1 2 FLOW LO~ l

                 .-.--.w-.--

      +                                                                                                                                                                         r 9                                                                               1S                                DB.SP 03218
'I

d
Revision 02 ,

C-1 INITIAL 4

    <                                                 _ _ _ _        _______________________,                                                                                   l l

NOTE 4.1.14 l I o- Achieve total flow as close as possible to 430 gpm. (FISHP4 plus FISHP45) l o This step makes !!PI Train 1 inoperable. l l l _ _ _ _ _ .. _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _l . CAUTION

                                                                                                                                                     '                          f Test line flow, as read on FISHP4, shall not exceed a steady flow of greater than 400 GPH.

4.1.14 Slowly throttle open HP 29. IIP 1 FLOW TEST L1HE REGULATING VAINE, until a total flow of 421.4 to 438.6 GPH (430 1 8.6 GPH) is indicated by FIS!!P4 or f C-l test instrument, plus F15HP48 (approximately 1.5 turns open). Record the time and total flow rates Time O 9'2A 36_+ = k)2 Total flow Rate h FISHP4 FISHP4B NOTE 4.1.15 l l Page 1 of Attachment 1 HP1 Train 1 Data Sheet l shall be used when taking flow data with the l l installed FISHP4. Page 2 of Attachment i shall l l be used with the Validyne transducer. ! 4.1.15 VHEN the pump has run for at least 5 minutes at this flowrate. THEN record the following data on the appropriate pages of Attachment 1. HPI Train 1 Data Sheet, for

      .'                                                              25 minutes at $ minute intervals, while continuing with the following steps o     . Time ,                                                                                       :

i o Pump Suction Pressure r (Continued) { w - r vr'e+e,r.w.,v-++r- w +----e -, <m ew<= +- ---e--w----*--e- -r-rear---Ae--+r---we - +-,*e=- -a

16 DB.SP-03210 . ' ' R vision 02 , . ,

C-5 INITIALS _ 4.1.15 (Continued) o Pump Discharge Ptessure ( o Test Line flow o Lube 011 System Pressure o Lube 011 System Temperature o Dearing 011 Levels VHEN the pump has run for at least 5 minutes at this h 4.1.16 flovrate THEN obtain llPI Pump 1 pump and motor vibration

                       #      readir.t,s in accordance with DB lDi-05003. Vibration Monitoring Instructions, while continu!ng with the following steps.

4.1.17 Inspect the mechanical seal area of HPI Pump 1 for leakage. p JN 4.1.18 IF a HPI system Leak Check is required (Step 3.1.3). THEN vhile HPI Pump 1 is running perforn an inspection of the llPI System Train 1 mechanical joints for leakage using Attachment 4 HP1 System Leak Test Check List. M 4.1.19 Verify lube oil flow as indicated by FC4988, llPI Pump 1 Lube oil Flow Class. Jk 4.1.20 JF_ P197 2. IIPI Pump 1 DC Lube 011 Pump is not running, g L. THEN verify P197-2. HP1 Pump 1 DC Lube 011 Pump, , shaft is not rotating. L'$ 4.1.21 WHEN vibration data and flow data collection is complete. THEN stop H.I Pump 1 using HIS 1524. Mb 4.1.22 IF Section 4.2 is NOT to be performed. A_NLD the Borsted Vater Recirc Pump was stopped in Step 4.1.8 THEN restart the pump using HIS 1613 located on Control Room Panel C5718. 4.1.23 JF_ HPI Pump 1 meets the acceptance criteria on Attachment 2. HPI Pump 1 Acceptance Criteria Curve.

   .                           using the installed FISHP4 THEN N/A Step 4.1.24 and 4.1.25.

_fdb 4.1.24 IF acceptance criteria was M met using the installed FISHP4 Q)f THEN perform the following: _p k a. Contact Performance Test Engineering @ Systems Engineering. Ob *

b. Close ifP-29. Ay record tiJne .

(Continued)

17 DS4P.03218 . t- .. R3 vision 02 , i Cl I I

\/

INITI ALS_ . 4.1.24 (Continued) l _ ,N k __ c. Perform Step 3.1 8 to have 16C-install test g instrumentation. Nb d. Write a test deficiency.

e. Perfum Steps 4~.1.7 through 4.1.10.

[ HOTE 4.1.24.f ; 1 J See page 2 of Attachment 1. HP1 Train 1 Pump Data l

l Theet. to assist in setting flow using a Va11 dyne 1 l t

l l transducer. ! I I .. . . .

                             . yl.                                                                                                                                   i
          *                        ,'                g$

f. Perform Steps 4.1.14 through 4.1.16 using page 2 of Attachment 1. HP1 Train 1 Data Sheet. -)

g. VHEN vibration data and flow data collection is complete. -

THEN stop HP1 Pump 1 using HIS 1$24.

          ;.                                                4.1.25                 IF the Validyne~ transducer used reads more than 0.0 t                            f 25 mV with no flow, 1                                                                                THEN periorm the fallowing

.(* QA !

a. Contact ILC to re.zero the transducer to 0.0 1 25 mV.

b b. Reperfom Steps 4.1.7 through 4.1.10. Al O _ c. Reperform Steps 4.1.14 through 4.1.16 using an

                                 '                                                         additional Page 2 of Attachment 1. IlPI Train 1                             ,
                                                      @                                    Data Sheet.

d. Return to Step 4.1.24.g.

i _h i l~ v . p - --,w ~ -'

18 D5.SP.03218 R: vision 02 * . * . .

              .                                                                              C2           *.

I

      'ANITIAt8
                                                  .        __       _______________                                             (

l l NOTE 4.1.26 i!

                       'l Ilo flow on TY1HP3C or FY1H3D is defined as any inflication of 75 gpm or less. An off scale lov                         l4*h                    .
                                                                                                                                      -{
                                                                                                                                        !l reading (flashing zero) is also acceptable.

Instrument is calibrated at operating pressare ' t and exhibits a zero shift when read at zero- t

                          ,       system pressure.                                                     L l/       "

i l_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _1 ! Verify TY1HP3C and FYIHP3D indicate no flow, from the 4.1.26 , Control Room.

OAN. _ 4,3.27 IF computer is being used. ;

TjHEN stop Computer Operators' Special Suasnary I '- .A k 4.1.28 Close and stroke time HP32* HP1 PtHP 1 1 RECIRC STOP !

CHECK VALVE. ; Record closing stroke time of HP32* on Attachment 1 4.1.29 HP1 Train 1 Data Sheet page 3 of 3. i b 4.1.30 Verify by valve stem position that HP32* is closed. Dk (<.1.31 Verify HISHP32 indicating lights are green OH and red (' t OFF. Mb 4.1.32 Open and stroke time HP32*. HP1 PLMP 1 1 RECIRC Stop CHECK VALVE. 4.1.33 Record opening stroke time of HP32* on Attachment 1. bb 4.1.34 Verify HISHP32 indicating lights are red ON and green 0FF. i

Controlled per DB 0P 00008. Operation and Control of Locked Valves.

t i i b l,

  - .    ~ . - - -            -        - _ -          . . - . - - -             .

y ,_ . _ .. . - _- - - . . - - . _ . - . . . - _ . - . ~ . . . - . ~ . . - . DB.SP-03218 j y . ; 19 '

RSvision 02 . ;

C.5 j i

IN171ALS f bk 4.1.35 Verify by valve stem position that HP32* is open. SLA i 1.36 Close HP29. HPI FLOW TEST LINE REGULATING VALVE. ! Record time. Time J00 $ Date _7 9 $7 i

                                                                                                        'l (                                                                                      l
                     .O )b             4.1.37           Close and lock HP26*, HP1 PtHP 1 1 FLOW TEST l

ISOLATION VALVE. b '4.1.38 Close HP1556. HP1 PUMPS RECIRC 70 BWST. i 4.1.39 perform the following to verify proper performance of lube oil system check valves:

a. Verify HP 105. HPI PUMP 1 LU6E 01L SYSTEM DC i PUMP CHECK VALVE. passes flow AND that HP 102,

[ HP1 PUMP 1 LUBE OIL SYSTEM AC PUMP CHECK VALVE. does not pass reverse flow by performing the following: ,

1. Start F197 2 HP1 Pump 1 D.C. Lube Oil Pump- ,

dM - with switch NP197 2. I b

                                                                                                                  ~
  "                                                             2. Verify. lube oil fiv as 1ndicated by FC4988.

Sl4 3. Verify P197 1 HP1 Pump 1 A.C. Lube Oil Pump shaft is not rotating. - L5 6.1A 4. Stop HP1 r197 2, HP1 Pump i DC tub. 011 Pump, with switch NP197 2. ,

b. JF_ P197 2. HP1 PUMP 1 DC LUBE OIL PUHP, was running in Step 4.1.20..

THEN perform the follwing

1. Start P1971 HP1 Pump 1 A.C. Lube 011 Pump

_ kM _ with switch NP197-1. bN 2. Verify lube oil flev as indicated by FG4988.

      -                       .bh                                3.      Verify P197 2 HP1 Pump 1 D.C. Lube 011 Pump shaft'is not rotating.

4. ' Stop P197-1. HP1 Pump 1 AC Lube oil Pump, with switch NP197 1 4

Controlled per:DB 0P 00008. Operation and Control of Locked Va lves.

t y v w w a , s b b.,-~. , , , , - -<..,se,_m--.p%.

                                                                                                            .                 , , , . , +,.e,.   +, J  ,2  .gr -c +- e%te.--m   wr-.w--   w---

 -.                      -                . _ ,                             ~- -                      . ~ . . - . , .

20 DB.SP.03218 '

Rovision 02
CS $

J NITI Al.,5 4.1.40 Have ILC return FISHP4A to service by performing the ( following. (Refer to Attachment 3 for sketch of FISHP4A-Instrument Valve Hanifold): k a. Verify equaliter valve is open. _% b.- Open low pressure. isolation valve.

e. Slowly close equalizer valve.

                                             #                   6               Open high pressure isolation valve.

4.1.41 Request that 1&C periosa the following:

        ._..h                                                     a.             Remove test pressure gage and snubber. (if snubber is installed) at pump suction and restore P11519A to service.

k

b. Remove test pressure gage and snubber. (if J snubber is installed) at pump discharge and .

restore P1HPSB to service, l b c. IF installed. THEN remove test instrument at FISHP4. Refer to Attachment S. F15HP4 Instrument Valve ! Manifold / Test Instrument Installation Sketch. bh 4.1.42 Inform Shif t Supervisor that the system is returned to normal operation and that this suction is complete except for post test es11bration of gages. 4.1.43 Deleted ( , {' _ h 4.1.44 H the computer was used. THEN obtain computer printout of Computer Operators' Special Sununary and attach to this procedure. hh 4.1.45 Obtain Vibration Data Eheets from Mechanical Maintenance and attach to this procedure. h- 4.1.66 Notify Shift Supervisor that this subsection is completed. / Times /di(Shift ervisor: Section 4.1 completed by d L ate _7 4 1 (( i e

         ') v'-        y-' w y-w e we-sv 1r     -r, -,-s,w   h -,%-    -s+---,-3   n w   ,,,-    w,,-c+-r-        --m-.-,r-+-ww-----e   -- ,   wra-=2_~,-3w            ==rE       w-

21 D6.SP-03218

       /. .    *        *

R0 vision 02 .

                                                                                                                                                                                                                . I C.h 4.2  BV 26__ Reverse Tiow Test Using d tatic Head I

1HITTALS . h 4.2.1 JJ rurning. THEN stop the BVST Recirc Pump.

            ,,h _             4.2.2        Open BE2283 BVST RECIRC PUHP SUPPLY BREATER, at HCC E220.

4.2.3 Close EV19. BORATED VATER STORAGE TAHK HEATER OUTLET THROTTLE VALVE, and record number of turns closed:

                            ,                                                                                                                                                                     - C- 4
                                                     /O                   turns Verify closed SF98, BRENT FUEL POOL PURIFICATION

_ h 4.2.4 RETURN TO BVST 150 VALVE.

   '                                                             NOTE 4.2.5                                                                l l

l, Punning the hose above the piping is necessary to l l prevent draining that section of piping. l l_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _l Jjk 4.2.5 Connect a hose to BV27 HP1 TO BWST RETURH L1HE DRAlH VALVE, and route hose above and over pipe (3' ilCC 21) to a floor drain. h bb 4.2.6 Open BV27. Atter a few seconds, to allow for initially filling _M/], 4.2.7 of the hose, place hose in an empty 5 gallon bucket and start stopwatch. Sh 4.2.8 VHEN 10 minutes has elapsed. OR when bucket is full, close BW27 and stop st'opwatch. Record elapsed time on Attachment 1 page 3. Hrl

h. 4.2.9 Train 1 Data Sheet.

4.2.10 He'asure amount of water in bucket and record on Attachment 1. _,_bM 4.2.11 Remove hose and replace cap for BV27. 4.2.12 Restore BWST Recirculation Pump / Heater System as _ [~ directed by the Shift Supervises. 4.2.13 Verify BV19, BORATED VATER STORAGE TANK HEATER OUTLET THROTTLE VALVE, throttled open to number o! tutns C.( recorded in Step 4.2.3. (

DB SP-03218 22 R2Violon 02

C-64
I N 171 AI _S, 6.2.14 Determine IW26 leak rate using f orm'J1a on (. l l

At t r clunent 1.

               %_    4.2.15    Hotif y Shif t Supervisor that this subsection is complete and the system is returned for normal operation.        -

Times % Lhift Superv so t j) Y _ b Subsection 4.2 completed by _ g, d Date ,{ j 7 l l 1 C m

              ~                -     . --                         - . - . - _ ~            . _ - -         - . . . . . _ _ . - - . _ _ . ~ . -                . - .   . . _ . .
                  * '                     ,                                                  23                                     DB.SP.03218

Revision 02 C.4 i ----------------------------

l NOTE $.0 , l l . I! l Contact Performance Engineering to concur with j resolution of any test deficiency that affects l T.S. 4.0.5 acce/tance criteria. ll ) l I l I--------------------------- I ; 5.0 ACCEPTANCE CRITERIA

                                             /
                                       ~ $.1   HPI Pump 1 minimum recirculation f!vv was greater than 37 gpm

( ep 4.1.11) I' C- f andlessthanor4gualt 57 spa Verified by-Date 7 k _. [ ! HPI Fump 1 average flow / /anB average differential / pressur/ e are

                                          $.2                                                                                                                                    ;

within the operable range of Acceptance Criteria curve on ;

       .                                       Attachment 2. (T.S. 4.0.5) 5.2.1                    g pump data falls within the Alert Range,                                                                ;

THEN frequency of testing shall be once per month until the cause of the deviation is determined and condition corrected. Note this as a test deficien . -

         -                                     W rified by v

i _/ - Mi Date 7 h[ t ,rg ty P T w D r k 4

           ,s      v      -        r                n--,-v---.ev                                                   , - - - -                                                -e,~

24 DB.SP.03218 ,,s *, j Revigion 02 , C-4 NOTE S.3 , l ( l l Reference Value for pump inboard horizontal l l l measurement is 0.58 mils. l Acceptable Rangen 0.0 to 1.16 mils ! h Alert Ranget >1.16 to 1.74 mils, test frequency l l increased to once per month AND prepare a test _ l , deficiency. l j l 1 l Pump shall be declared inoperable >1.74 mils 1 ' and Systems Engineering and Perforvnance ( Engineering shall be notified. I_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _I 5.3 HP1 Pump 1 inboard bearing horizontal vibration measurement (C.H) is less than or equal to 1.16 mils OR within the alert _ range of >1.16 mils to 1.74 mils and a test deficiency has been written. (DB-HH.05003 Data Sheets from Step 4.1.16) f C-f (T.S. 4.0.5) Verified by Date_) w- _vjj j j Full forward flow has beed verified through stop check valhe

                    $.4 HP32* opened as evidenced by indicatio of greater than 37 g m f C'4 (L

flow on F15HP4B. (Step 4.1.11. T. . 0.5) Verified by 8- Date 7, 8 W ,/, g 3.5 Full forvard flow has been verified through check valve HP33 opened as evidenced by indication-of gr ter than 37 gpm flow . on FISHP4 ($ p 4.1.14. T.S. 4.0 ) fC4 Verified by t M Date 7 kf y gj uj

                    $.6 Check valve HP10 opened as evidenced by indication of greatbr than 300 GPM partial forward flow. on F1 HP4. (Step 4.1. 4                                                                                    f C-4 T.S. 4.0.5)
                                                                                                                   @d               . Date                   h Verified by                          - -               ,,                                -

i,, , 5.7 Check valve HP22 opened as t id need by indication of greater than 300 GPH. partial forward i ov. on F .Hre. (Step 4.1. 4 f C-4 T.S. 4.0.5) Verified by

9 d ' Date 2h

                                                                                                                                               ~l l ' (

Controlled per PB-OP-00006. operation and Control of Locked Valves.

25 DB-SP-03218

Rsvision 02 .

C-5 5.8 HP1 Pump 1-1 Flow Test Isolation Valve, HP32* stroked closed in

  !                        less than 42.3 Sec. (Attachment 1                         .S 4.0.$)

Verifled by , Da1.e )

                              ----------------------------  __ '//                                                           'l /                                                       ,

l NOTE 5.9 i l l l If this step can not be satisfied then Technical l Specification 3.3.3.6 shall be referred to for l appropriate action. I

                               ---------                     ---_-------------I 5.9    FYIllP3C and FYIHP3D demonstrated OPERAB1.E by indication of no flow prior to, during, and after pump operation.                                        (Steps 4.1.2.

4.1.12 and 4.1.26). Verified by . DateyD _ 7 5.10 Indicating lights on !!!S!!P32 are green (OH) and red (OFF) when llP32 is closed. ( tep 4.1.31. T.S. O. Verified by / Date

                                                                     / / (f                                                          { f 5.11 Indicating lights on !!!SHP32 are red (OH) and green (OFF) when (Step 4.1.3 . T.S. 4                 .5)
                                                                                                                                                                      )
     -                       HP32 is open.

Date. [

Verified by _ d, 5.12CheckvalvellP102openedas,evidencedbyidicationofflowat FG 4988. (Step 4.1.19. T.S. .0.5) Verified by /JJ d. Date 7h

                                                                   ~ /'f]/                                                            (l/

5.13 Check valve HP 105 prevented t(verse flow as indicated by the DC lube oil pump (P197-2) shaft NOT rotati g. (Step 4.1.20 or 4.1. M .b . 3. T . S . 4. 0. 5 ) Verified by Date 7 '

                                                                     / '/ /                                                                      /

5.14 Check valve HP 105 opened ad e91denced by indication of flow at FG 4988. (Step 4.1.39.a.2, T.S. 4.0

       .                      Verified by                 .

m. Date /h 5.15 Check valve HP 102 prevent/ /d feverse flow as indicated by the

/'

AC lube oil pump (P197-1) shaft Ny rotating. (Step 4.1.39.a.3. T.S. 490.5) Verified by f8A Date _ j ) a -

                                                                           <g
               ..       , ,-m+j.._,. ym_                -.                                  --     ...._..'.--.s

 ._ . _ ._                          ..___..___._-.--..--.---._...__..___..__.._...m-.                    -
                                                                                                                                                                            ,              L
      ..-                                                                                                                               DB SP 0H18,       .
                           .                                                                  26                                                                        .

l Rovision 02 5.16 HP1 Train 1 mechanical joints have been inspected for leakage, , l and the results recorded on Attachment 4 if required by the ( surveillance test schedule. (S 4.1.17. f.S. 6.8.4) , Date f Verified by i 5.17 Check valve BW26 prevented reverse flow as indicated by a 1 measured leakage of less than or equal to 5 gpm- ( Attactunent 1. . T.S. 4.0.5). Verifled by M N) k Date

I kG ,

6.0 gCORD[ {l ' Follow the requirements of DB-DP-00013. Surveillance and _ 6.1 < Periodic Test Program, for records capture and processing. 7.0 P.E FE PDC E_S, 7.1 Developmental _ f 7.1.1 High Pressure Injection. H 033A 7.1.2 Component Cooling Water System. H 036B 7.1.3 Service _ Water System. H 041 7.1.4 HPI Pump A.C. Lube Oil Pump. E-528. SH63 . 7.1.5 t!PI Pump D.C. Lube 011 Puup. E-528. $1164 b 7.1.6 C.NSA-32.01 003. Rev 3 7.1.7 49A FIS HP-04. HP Injection Pump Recire Flow 7.1.0 49A-FIS-IIP 048. HP Injection Pump Recirc Flow 7.1.9 Haks up & Purification System. H-031C 7.1.10 Spent Fuel-Pool Cooling System. H-035 7.1.11 Decay Heat Train 1. H-0338

           .                             7.2       Implementation 7.2.1                  DB-0P-00000. Station Operations 7.2.2                   DB-0P-00008. Operation and Control of Locked Valves 7.2.3.                _DB 0P-06011. High Pressure Injectien System ra w dute                                                          -
                                                                ~

DB HH 05003. Vibration Monitoring Insttuctions 7.2.4 .. . P J

~'

s . .. . . , . . - . - - . _ . . . . . . _ _ . - _ ..,:_.--.....-....--_-_..,-._a.~_. .._;.--_.-._.;.a...._'

27 DB.SP.03216 . P.evision 02 7.2.5 DB-PF.00201. ASME section XI Inservice Testing of g Pumps and Valves 7.2.6 Technical Specifications sections o 4.0.5 o 3/4.3.3.6 o 3/4.5.2 o 6.B.4

7.2.7 HPI Pump and Valve Basis Document. Vol II and 111. 7.2.8 DB.SP 03212, vecting of ECCS Piping. W L A

~" - 28 DB-SP-03218 *

Revision 02
h l

ATTACHMENT 1: HPI TRAIN #1 DATA SHEET DATA USING INSTA1,1.ED FLOW CAGE ( tube 011 System Test Gage Test Gage at FIS FIS at PRESS LEVEL TEMP _ PI HPSB HP4 HP4B ~ PI 1519A PUMP MTR MTR TI PUMP PUMP TEST HIN 4955 INBD INBD OUBD DISCH LINE FECIRC SUCTION BEAR BEAR PRFSS FLOW FLOV PI 4954 BEAR PRESS _ TIME PSIG GPH GPM PSIG PSIG ** HIL H/L H/L F TARGET Horm florm Norm 106 1500 380 53 25-40 VALUES 30 N d M "o E6 0 0 0 11 GIT. 0T5$ 36,6 lb MI (7 17 tY1 H 0 36.l I4c2 MS 57 il 49T M6 19 6# 96'I f7 #7 ow0 354 ,49 gf 57 ,7 OWI as I4CE Mc E7 _ i/ ( x x x Su"* IM 73 00 162f 7,95 g7 AVERAGE

3S. I 4(o 0 D 57 <7 x x x FISHP4 Cal Due Date 9 16 U Test Gage (Disch)

Test Gage Equipment No. 7 N- [ b Equipment No.(Suct.)f6812. ~f

                                  /Ofd!9 7                                              Cal Due Date                       /0 r[11i /7 7 C'al Due Date                   <

Do not include initial readings in determination of Jum and averages.

esit. than prepare a If lube oil pressure is less than 20 psig or grater than 47 deficiency for System Engineering evalaation. Pump Avg A P jNaNpsid = Avg Disch Press lNhO psig - Avg Suct. Press ,3 5+b psig Avg Test Flow $ gpm + Avg Min Recirc Flow S Pump Avg Flow Attachment 1 Page 1 of 3 ei-i

   ,d   ,                                                    29                            DB SP-03218
                                .                                                          Revision 02                                                               -

C-1 f ATTACHMENT 1: HPI TRAIN #1 DATA SHEET (Continued)_ DATA USING VALIDYNE TRANSDUCER TEST GAGE TEST GAGE AT AT NOTE 1 FIS LUBE OIL SYSTEM PI 1519A PI HP5B HETE HP4B PRESS. LEVEL TEMP. PUMP PUMP TEST HIN PUMP HTP- HTR TI SUCTION DISCH LINE RECIRC INBD r.v. OUBD 4955 TIME PRESS PRESS FLOV FLOW PI 4954 PEAR >; * % BEAR P61G PSIG VOLTS GPH PSIG H/L H/L H/L OF TARGET VALUES 30 1500 4.507 54 25-40 Norm Norm Norm 106 f C*I s INIT* SUH+ X X X AVERAGE

X X X Average flow see Note 1 Test instrument (Validyne) F.quipment No. Cal Due Date (flow) (EDM) Equipment No. Cal Du- Date

Do not include initial readings in determination of sum and averages.

            **If tube oil pressure is <20 psig or >47 psig, then prepare a test deficiency for System Engineering evaluation.

Pump Avg AP psid - Avg Disch Press psig - Avg Suct Press psig Pump Avg Flow gpm = Avg Test Line Flow gpm + Avg Min Recire Flow gpm NOTE 1: H&TE to be used is a Validyne transducer with a number 44 diaphragm installed. 0-5 volts corresponds directly to 0-890 inches of water. To determine GPM use the following equation GPH = 13.4164 )inchesofwater (380 GPM corrisponds to 4.507 Volt., (370 to 390 GPM corresponds to 4.273 to 4.747 Volts) Attachment 1 ( Page 2 of 3 1

               * ' '                                                         30                                       DB-SP-03318

Revision 02 ATTACHMENT 1 = HPI TRAIN #1 DATA SHEET-(Continued)

HP32 STROKE TIMING { Control Breaker Baseline Full Location- Stroke Time Stroke Time Valve- Switch Breaker Open Closed No. (HCC) ~ open- Closed Number (Panel) HISHP32 BE1296 E12E 28.7 29.0 -} N. - HP32- (C5716)- Acceptance Criteria Closing stroke time is less than 42.3 sec. Method.of Stroke Timing k# d' b - Timing Device Equipment No. I57/b Calibration Due Date 9![b 7 i ( BW26 PEVERSF. FLOk TEST 9 h[7 ? { . Stopwatch Equipment Number I 7 / 2-- Cal Due Date

                                                                                                                              /         '

Test Elapsed Time f( MIN. i Measured Leakage b GAL. 4

                                                                                              "'**"                 * * " "      ^
                                                                                            =

Leak Rate (GPM) Elapsed Time (MIN) b GAL, PM = HIN. fg 7 l: Attachment 1 Page 3 of 3 I {. , l l.'

 .-                                                                                     n s       -

s. 3.,..

                                                                                      . .      ..i...                    3....i.i..           :                       :                     :

n 1530 - ....,... : : : :

                                                                                                                                                                      ?
                                                                                              ----?.-------!.--------i.--'--.----

- O 2

1520 '5---- <- - - - - - - - - -:

                                                                                     ?.       -  -   -       - -  - -   -      !.  - -   -    -     Y-       +      INOPERABLE:
                                                                                                                                                                                             -         m n.

_G__ .

                                                             >              ---<*-/

5 1540 : y to - . . a -

AtEnT : -

v :

                     -- - - - - - -      c.- - - ;.        -->--- -----<.-      :

1500 - 3....... .

                                                                                                                                                    . . . . . . . . . >. . . . . . . . . - ,g 1

m jfgg ' : .........:..........>.........<.. fusi.t : : -

                                                                                                                                   .......]..........i.....

[ . OPERABLE : : .

Eo

        --)           :     . . . . . . . 4.PMSE. IF03pItiSIAI.I.ER                              PU.T1tWEUT)*.

g jagg : : :

- w

                                                        .....y.........g..........

0) jffQ

: -oIfMBtE--- : an:cE-

                                                                                                                                                                 -------r-----         -- :
                                                                                                                                                                                                             ~

:- o

: - - - - - - - - - - - - - - - - (IF USING h&TE)

I. n C 1460 - ---- ' -- - -----> --- -

'I.

: -- ----r-------' : : "

3 O .

- - - : - - - - - - - t - :- - - - - - - - -:: ;

o

                                                                                                                                                        .......j........J                               g
                                                         --*-r-----               - <:                     :                                                                                            o
          .l   1450    -: INOPER
                            --- ABLS                                              : ~gylty. fi.inap,c.d. ).n.s.tryren                        g:.: .                       :                     -
                                                                                                                                                                                                -       m 4                    Jung W:i! .W.tann: . . . .                                                   :                                      .                                            -

Q

                                                                                                                                 --**----:- ----~~-* - - - - - - - -:

F- iM -

I d

                                                                 ---    ------s*                                                                                                                -
                                                                                          ---* --G.i&TC)
                                                                                     *---ALERT                               :.                                           .
                                                                                                                                                                       --- ----- =-                      ;

1430 -- - -:- - --- n- -

INOP ERAT 1. E (M&TE) -t- - ~-

                        -------=---------r-------v g                                                                                                                    :                   :                        :

g 1420 : : : : , e LLI Lt_ 14jQ

                                                                                                                                                                                    -----E A 1;' 8 n.

L1- -

,_n

                                     - - - +:..t- - - - -.t- +: -------+--------+:--------i--------+:

e.,>.

 % ;;    O     1400      E- - -                                                     :
                                                                                                     .            ...             ....i....t                                   . .                         -

450 85

 -g n

13ec

. . . . t . .

430 435 440 445 OW 425 N CD o.

 ?                 410                415                  420 94 FLOW (GPM)

33 DB.SP-03318

Revision 02*
ATTACHMENT 3: FISHP4 A INSTRUtfENT VALVE MANIFOLD SKETCll

( d 09UAll2fA

9 I L3W Hi&M m "~ FRetSVRC PRt$5UMC ". l 1 8 230LATION x 50L ATt0N s , b

                                /y                   %                       L I                                                                                 CAtttRATioW

CAle8 RAT 10N FORT

\ PORT' IsotATION lcsotAT10N l 4 (k (r &

                                 /    i l

i I

I t

                                           ..       .4 Attachment 3 Page 1 of 1                                           (

k ',s

DB-SP-03218

* '

33 Revisicn 02 ATTACHMENT 4: HPI SYSTEM LEAK TEST CHECK LIST

( II' leakage is observed. THEN_ record the leak rate OTHERWISE enter 'NONE*. LEAK VORK REQUEST COMP RATE LOCATION NUMBER VALVE DESCRIPTION NUMBER

              #1 ECCS ROOM (RH 105)

HPI PUMP 1-1 SUCTION LINE CffECK VALVE HP 10 DH PUMP 1-1 DISCHARGE TO HPI PUMP 1-1 DH 64 SUCTION s HP 12 ifPI PUMP 1-1 SUCTION VALVE HPI PUMP 1-1-SUCTION LINE FLUSH HP 14 CONNECTION HP 1510 HPI PUMP 1-1 SUCTION LINE FLANGE HPI PUMP 1-1 SUCTION STRAINER DELTA HP 36 P SOURCE VALVE HPI PUMP #1 SUCTION STRAINER --- FLANGES (2) HP 1519 HPI PUMP 1-1 SUCTION PRESS SOURCE PI 1519A HPI PUMP 1-1 SUCTION PRESS GAGE PI 1519B HPI PUMP 1 1 SUCTION PRESS GAGE P58-1 HPI PUMP 1-1 SHAFT SEALS HP 18 HPI PUMP 1-1 VENT VALVE HP 18A HPI PUMP _1-1 VENT VALVE HP 16 HPI PUMP 1-1 DRAIN VALVE HP 16A HPI PUMP 1-1 DRAIN VALVE HP1 PUMP 1-1 DISCHARGE PRESSURE HP 5B SOURCE VALVE HPI PUMP 1-1 DISCHARGE PRESS'JRE HP 5BB SOURCE VALVE

 -              HPI PUMP 1-1 DISCHARGE PRESSURE PI HP5B
      ,         CAGE HPI PUHP 1-1 DISCHARGE LINE FLUSH HP 20
    -           CONNECTION HPI PUMP 1-1 DISCHARGE LINE HP 20A
               -FLUSH CONNECTION HPI PUMP 1-1 FLOW TEST ISOLATION HP 32 VALVE I                 HPI PUMP 1-1 DISCHARGE LINE HP 22 CHECK VALVE ROHP6B Attachment &

lk Page 1 of 4 l

j 34- 'DB-SP-03218- , , , , ,

                                                                            -Ravision 02 .,-          .        .  .=*    -
                                                                                                                             -l

_C-4 l 1 j ATTACHMENT 4: ~ HPI SYSTEM LEAK TEST CHECKLIST (Continued)_ IF;1Gakage is observedi THEN record the-' leak rate _0THERWISE . enter '_NONE'. ( WORK REQUEST l COMP _ LEAK NUMBER- -RATE LOCATION NUMBER VALVE DESCRIPTION HPI PUMP 1-1 DISCHARGE VALVE HP 24 '~~~ HPI PUMP 1-1 DISCHARGE LINE-DRAIN VALVE HP 34 ,, HP1 PUMP 1-1 DISCHARGE LINE DRAIN VALVE HP 34A HPI PUMP 1-1 FLOW#-TEST ISOLATION HP 26' VALVE ~ Fc-4 , il MECHANICAL PENETRATION ROOH (RH 208) t HPI LINE-1-1 FLOV SOURCE K1 HP 3CA HPI LINE 1-1 FLOV SOURCE K1 HP 3CA1 HPI LINE 1-1 FLOW SOURCE K2 HP 3CB HPI LINE 1-1' FLOW SOURCE K2 HP 3CB1 HPI LINE 1-1 FLOV TRANSMITTER FT HP3C HPI LINE 1-1 & 1-2 PRESS SOURCE HP 28835-HPI LINE 1-1 L 1-2-PRESS SOURCE HP 2883B1 HPI LINE 1-1 & 1-2 PRESS INDICATOR PI 2883B k_

     ;HPI LINE 1-1 & 1 . PRESS SWITCH             PSH 2c83B HPI LINE 1-1 ISOLATION VALVE LEAK TEST CONNECTION                           HP 44 HP1 LINE-1-1 ISOLATION VALVE LEAK TEST CONNECTION                           HP 44A HPI LINE 1-1 D".AIN VALVE                 HP 69 HPI LINE~1-1 DRAIN VALVE                  HP 69A HPI LINE 1-1 ISOLATION VALVE              HP 2C HPI LINE'l-2 VENT SOURCE VALVE            HP 72' HPI LINE 1-2 VENT ISOLATION VALVE         HP 72A HPI LINE 1-2 VENT ISCLATION VALVE         HP 72A1 I

Attachment 4 Page 2 of 4 , ( m - ~ - ,

DB-SP-03218

     -! '-? /-'       *;                                                                                                                                                   - 35
                                 +                                     .--*                               *-                                                                                            Revision'02=

C-4 ATTACHMENT'4:~ HPI SYSTEM LEAK TEST CHECKLIST (Continued)

                      ~ I,F leakage is o6 served; THEN record the leak rate OTHERVISE enter 'NONE*.

COMP LEAK WORK REQUEST VALVE DESCRIPTION' NUMBER 4 RATE LOCATION' NUMBER'

                        -HPI LINE 1-2 FLOW SOURCE K1 HP 3DA                                                         ,

HPI LINE 1-2 FLOW SOURCE K1- HP 3DA1 HPI LINE 1-2 FLOW SOURCE K2 HP 3DB

                       ,-HPI LINE 1-2' FLOW SOURCE K2-                                                                                                                       HP 3DB1-HP1 LINE 1-7 FLOW TRANSMITTER                                                                                                                     FT HP3D-THPI LINE 1-2 ISOLATION VALVE LEAK TEST CONNECTION                                                                                                                                   HP 45 i                           HPI LINE 1-2 ISOLATION VALVE LEAK
                          -TEST CONNECTION                                                                                                                                   HP 45A-HPI LINE 1;2 D. RAIN VALVE                                                                                                                        HP 70
                          'HPI'LINE 1-2 DRAIN VALVE                                                                                                                          HP 70A                                                   -
                          'HPI LINE 1-2 ISOLATION VALVE                                                                                                                      HP 2D MECHANICAL PENETRATION ROOM #1 VESTIBULE (RM 207 HPI PUMP 1-1 RECIRC FLOV INDIC SWITCH                                                                                                             FISHP4B CORRIDOR 70 MECHANICAL PENETRATION ROOM #1-(RM 209)

HPI PUMP 1-1 MIN RECIRC TO BWST GATE VLV HP 39 HPI PUMP 1-1 MIN RECIRC FLOW SOURCE. VLV HP4BA HPI PUMP 1-1 MIN.RECIRC FLOW SOURCE VLV HPABB

                           -HPI PUMP RECIRC FLOV ELEMENT                                                                                                                      FEHP4B HPI TO BWST RETURN LINE CHECK VLV-                                                                                                                BV 26 4

MAKE-UP PUMP ROOM (RM 225) MU PUMP 1-1 SUCTION THREE-VAY MU 6405

                                                                                                                                                                                                                             ~ C' 4 MU 482
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MUP 1-1 BVST SUCTION-LINE VENT i - 1 Attachment 4 Page 3 of 4 a e w w --w. % ei w a +-g .. --- - W

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36 DB-SP-03218 *

Revision 02
C-4 ATTACHMENT 4: HPI SYSTEM LEAK TEST CHECKLIST (Continued) i (

LEAK RATE CALCULATION _ _ 20 Drops = 1 cc 60 Minutes 1 CAL. Leak Rate = Volume (cc)_ , 3785 cc f C-4 Time (min) x Hour (GPH) Collect leakage for at least one minute. Comments: J

line not listed here are NOTE: Additional valves on the flow test checked during HPI Pump 2 testing. Stopvatch equipment number _ Cal Due Date 4 e Attachment 4 Page 4 of 4 (

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37 DB.SP-03218 Rsvision 02 ATTACHMENT 5: FISHP4 INSTRt! MENT VALVE MANIFOLD / TEST INSTRUMENT INSTALLATION SKETCH

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                                                . JOB PERFORMANCE MEASURE NO. A3 Candidate:                                           Examiner:                   Date:

Facility: . Davis Besse Unit i Task

Title:

Corrective Actions to be Taken When Radiological Conditions Are Changing and Correct check out of a Portable Radiation instrument i Job Performance Measure No: Safety Function: KIA

Reference:

194 001 K103 2.8/3.4 Method of Testina:

          - Simulated Performance'                                Actual Performance 3 Simulator                     Control Room                   In-Plant g
          . Task Standard:                Perform check out of Portable radiation detector.

Notify RC personnel of changing radiological conditions. Required Materials: Operations Radiation Work Permit. DB HP-01103, Use of Portable Radiation, Contamination and Airborne Survey Equipment l

General

References:

DB HP.01901, Radiation Work Permits, Revision 4, C-5 L DB4tP-01103, Use of Portable Radiation, Contamination and Airborne Survey Equipment, Revision 1, C-1 Time Critical Task: No Estimated / Validation Time: 16 minutes Read to Performer: I will' explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You will make all written reports, oral reports, and log entries as if the evolution was actually being performed. .When you complete the task successfully, the objective

          ' for this Job Performance Measure will be satisfied.

During the court,e of the walkthrough examination, there may be some tasks you will be asked to perform that may require you to implement an attemative method directed by plant procedures in order to complete the assigned task. You are expected to make decisions and take actions based on the facility's procedural guidance and the indications available.

          .You may use any approved reference materials normally available, including logs. Make all written and/or oral reports as if the evolution was actually being performed.

f JOB PERFORMANCE MEASURE NO. A3 initial Conditions: The plant is in MODE 4 on # 1 DH Loop. Lineups are in progress to switch to the # 2 DH Loop to allow the # 1 Loop to be taken OOS for maintenance. initiating Cue: You have been directed to vent the #2 DH pump by opening DH 56, #2 DH Pump Casing Vent. JPM A3

a Performance Information NOTE: Critical steps denoted with a "C". Failure to meet any one of these standards for this item constitutes failure. Sequence is assumed unless denoted in the " Comments".

Start Time

1. Performance Step: Review the Operations Work Permit for the evolution.

         ........C...............

Standard: Notify RP of task and request guidance. Cue: RP reports that the task may be performed if you monitor dose rates with either a R02 or an RS05. They also indicate that you only need a lab coat and gloves to cross the boundary to operate the valve. Expected Dose rates in the general area of the pump are 20 mrem /hr. SAT UNSAT

2. Performance Step: Checkout a portable radiation detector.

 ,          Standard:               Locate proper guidance for checkout of detector.

Cue: Hand the candidate a copy of DB-HP-01103, Use of Portable Radiation, Contamination and Airborne Survey Equipment. SAT UNSAT

3. Performance Step: Verify current calibration.

        ............C..............

Standard: Ensure calibration sticker exists and is not past due. Cue: None. SAT UNSAT

4. Performance Step: Inspect instiument for physical damage.

Standard: Visually inspect the detector. Cue: None. SAT UNSAT JPM A3

5. Performance Step: Ensure the instrument's mechanic:1 rra is set pr:perty.

8tandsrd: Observe check of mechanical zero. Cue: None. SAT UNSAT

6. Performance Step: Turn on the instrument and check for proper electrical zero.

Standard: Observe switch placed in ZERO position and pointer at zero. Cue: None. SAT UNSAT

7. Performance Step: Perform Battery checks.

         .............C.............

Standard: Observe the switch placed in the BAT position (s) and pointer moves to BATT OK. Cue: None. SAT UNSAT h

8. Performance Step: Check that the daily source check has been completed.

          .............C.............

Standard: Observe check of sticker on side of instrument. Cue: None. SAT UNSAT

9. Performance Step: Perform a response check of the instrument using check source available.

Standard: Observe response check. Cue: None. SAT UNSAT s JPM A3

= .

10. Performance Step: Select a reading that will show cn en=le re:ponse based on expected radation levels.

Standard: Either the 60 MR/HR or the 500 MR/HR scale is selected. Cue: None. SAT UNSAT

11. Performance Step: Proceed to # 2 ECCS room to perform task.

Standard: Proceed to the # 2 ECCS room. Cue: (AS CANDIDATE IS WITHIN 4 FcET OF PUMP) Your M-G dosimeter has started to alarm. SAT UNSAT

12. Performance Step: Select a scale on n idiation detector to obtain Dose reading.

Standard: Select 500 MR/HR scale Cue: (IF on 50 MR/HR Scale) Reading is high off scale. (When on 500 MR/HR Scale) Meter indicates 120 MR/HR SAT UNSAT

13. Performance Step: Contact RP to inform them of changing radiological conditions and exit

    ..............C......... area.

Standard: Inicate that RP needs to be informed and exit to a low dose area. Cue: The on duty RP Technician indicates that he will suspend access to the area until another survey is completed and areas are properly posted. SAT UNSAT Temiinating Cue: This JPM is Complete. End Time JPM A3

          . -               . ~ , . . . .         .
                                                              - . ~ - ~ . - - . - .                 - . . . . . . - - .       . - - - .. - .- - - .

7 JOB PERFORMANCE MEASURE NO. A4 ; Candidate:- Examiner: Date:1

                      ' Facility: Davis Besse Unit 1 Task

Title:

- . Classification of an Event, Dose Assessment, and Protective Action Recommendations t , Job Performance Measure No: - Safety Function: , KIA

Reference:

194 001 A116 3.1/4.4 . Method of Testina: Simulated Performance ' Actual Performance g Simulator 1 Control Room g in-Plant Task Standard: Classify an event as a General Emergency , Perform an offsite dose assessment using the DADS computer Make Protective Action Recommendations Required Materials: General

References:

RA EP 01500. Emergency Classification, Revision 1, C-2 HS-EP 02240, Offsite Dose Assessment, Revision 4 C 1 , RA EP 02248, Protective Action Guidelines, Revision 0 L; Time Critical Task: No EstimatedNalidation Time: 27 minutes Read to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You will make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied. 7 During the course of the walkthrough examination, there may be some tasks you will be asked to perform that may require you to implement an alternative method directed by plant procedures in order to complete the assigned task. You are expected to make decisions and take actions based on the facility's procedural guidance and the indications available. You may use any approved reference materials normally available, including logs. Make all . 1 written and/or oral reports as if the evolution was actually being performed. 4

    , - -          n    -r-    ,       .--w,- .nv    --..,n.          ,      ,      ,

JOB PERFORMANCE MEASURE No. A4 - Initial Conditions: -A plant shutdown was in progress due to a 25 gpm tube leak in the 61 OTSO.

                            -EDG # 1 is OOS for a bearing replacement.
                            -Dose Equivalent lodine is reported to be 70 micro curies per gram, initiating Cue:      -A loss of offsite power occurred 2 hours ago.
                           -The # 2 EDO started but was manually shutdown due to a bus D1 lockout, f

The SBODG did not start when a start attempt was made from the Control Room. The problem has been identified but repair parts will not be available for 3 hours. One Main Steam Safety valve is leaking with RE 600 reading 50,000 cpm.

                           -Dose Equivalent lodine is now at 110 micro curies per gram.

The highest reading on REs 2004,2005,2006, and 2007 is 30 REM /HR. The Load Dispatcher has been contacted and indicates that restoration of offsite power will not be available for 6 hours.

                           -You are the Emergency Director, classify the event and take any required  '

actions. J O JPM A4

Performance Information NOTE Critical steps denoted with a "C". Failure to meet any one of these standards for this item constitutes failure _ Sequence is assumed unless denoted in the " Comments". Start Time

1. Performance Step: Classify the event in accordance with RA-EP-01500.

    ..........C............

Standard: Indicate that the event is to be classified as a General Emergency per EAL 4.A.5 of RA EP 01500. Cue: The Emergency Plant Manager has relieved you as Emergency Director and is taking actions per RA EP- 01900, General Emergency You are directed to complete offsite dose assement and recommend any offsite protective actions to the Emergency Plant Manager. SAT UNSAT

2. Performance Step: Conduct dose assessment using the DADS computer per HS-EP-02240, Offsite Dose Assessment.

Standard: Determine the' no Protective Action Recommendations will be required based on offsite dose. Comments: This step may be done out of sequence if candidate chooses to go to RA-EP-02245, Protective Action Guidelines to make minimum PAG recommendations for a General Emergency prior to doing dose assessment. Cue: Use c'Jrrent Met data, if asked indicate that CTMT pressure is normal. SAT UNSAT

3. Performance Step: Provide Protective Action recommendations to Offsite Agencies per

   .........C............. RA-EP-02245, Protective Action Guidelines.

Standard: Using Attachment 1 determine that minimum Protective Action Recommendations are to evacuate subareas 1 and 12, and shelter affected downwind areas to 5 miles. Cue: None. SAT UNSAT Tenninating Cue: This JPM is Complete. End Time JPM A4

JOB PERFORMANCE MEASURE NO. A4 n - . i Initial Conditions: A plant shutdown was in progress due to a 25 gpm tube leak in the # 1 OTSG.

                            -EDG # 1 is OOS for a bearing replacement.
                            -Dose Equivalent lodine 's reported to be 70 micro curies per gram.

Initiating Cue: A loss of offsite power occurred 2 hours ago.

                            -The # 2 EDG started but was manually shutdown due to a bus Di lockout.

The SBODG did not start when a Mart attempt was madt from the Control Room. The problem has been identified but repair parts will not be available for 3 hours.

                            -One Main Steam Safety valve is leaking with RE 600 reading 50,000 cpm.

Dose Equivalent lodine is now at 110 micro curies per gram. The highest reading on REs 2004,2005,2006, and 2007 is 30 REM /HR.

                             -The Load Dispatcher has been contacted and indicates that restoration of offsite power will not be ay111able for 6 hours.

You are the Emergency Director, classify the event and take any required actions.

                             . 63 xc./cc         k JPM A4

DOSE RATE CALCULATIONS 87'$'l7 tiO5LE ER3 FELEASE: .8.37E-01 Ci/sec 10DI! ERR;63E: 1.73E-01 Ci/sec 1.52E+00 uCi/cc 1.10E+02 uCi/cc WiliDSPEED: 5.7 MPH STABILliYCLA33 D ilhE SItEE RX 39)iD0!41: 2.00 HOURS NoLakeBreezeOccurring CALOJLATI0ti5 ASIS: Secondar's DISTRK'E fiO5LEGA3 10DIlE ghhp- IHYROID

                  ;g       C0tEBiTRai!0tl   C0tKBITRATI0tl        pcqg         DOSERATE n!Lgg                                          93UIVAL917 eCi/cc          uCi/cc-          RB1/HR           RB1/HR
                 .75           3.27E-05        6.76E-06          0.414           19.023 2           7.26E-06        1.50E-06          0.092            4.227 I               i 5           1.81E-06        3.76E-07          0.023            1.057 10           6.60E-07        1.37E-07          0.008            0.384 9

PRESS "P" FOR PROTECTIVE RCTIONS

9

PROTECTIVE RCTIONS !$ff RELEASESTARTTINE: 07:00 RELEASEDURATION: 2.0 HOURS WItiDDIRECTI0t110n: 243.9 DEGREES wit 1DSPEED10H: 5.7 HPH PUJnE PLUME THVROID FROTECTIVE DISME WIDTH ARRlVAL TEDE D0SE ACTIONS Irl TF-HILE3 091ERfiL i HILEB R91 REN 31EFSBICY 0-2 t1ILES

               .75          0.4         07:07        8.28E-01    3.80E401      emcuare SUSAFEAS:

1,12 2 0.6 07:21 1.84E-01 8.45E+00 :-s "t'es SUSACEA3: i,i2 5 1.5 07:52 4.60E-02 2.11E+00

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10 2.8 08:45 1.67E-02 7.69E-01 sue *Eas: i,22 . PRESS "M" FOR PROTECTIVE ACTION MRP O h

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FINAL'AS-ADMINISTERED WALKTHROUGH JPMs FOR DAVIS-BESSE EXAM

ES.301 Individual Waik through Test Outline Form ES-3012 Rev.106/02/97 Examination Level (Circle One): RO / SRO(I)/ SRO(U) Facility: Davis Besse Week of Examination: July 7.1997 Examiner's Name (print): System / JPM Safety Planned Follow-up Questions: Function K/A/G //Importance // Description

1. Decay IIcat Removal / IV a. 00500A402 3.4/3.1 How to take manual control of DH Purification of the RCS using flow after SA37 SFP Purification with loss of Dil floupath-

 #142B/NEW/SIM                                   b. 0050000009 3.6/3 6 Effects on controls for DH pump #1 if transfer switches out of normal.

2. Senier Water / Loss of X a. 076000A202 2.7/3.1 What interlocks are associated with Primary louis SW 1395/1399 7

 #14B/SIM                                        b. 000062K302 3.6/3.9 What are senice water pump auto start signals?

3. Remove an SFAS II a. Ol3000A302 4.1/4.2 What information does the S AM light Component from the Shutdown convey for BRIGHT and FLASHING 7 Bypass Mode

 #123B/SIM                                      b. 013000G004 3.7/3.8 Station EVS operation with concurrent sal and high radiation in the SFP area?

4. Station DC / Swap to a VII a. 0630000009 3.1/3.3 Local indications of an equalizer swing charger charge?

 #69/ PLT                                       b. 000057K302 4.1/4.4 Why do we load shed the batteries during a loss of ofTsite power?

5. Chemical Addition / 1 a. 004020A105 3.7/3.8 Effect of closing insenice Dcmin Emergency Borate locally inlet valve?

#57/ PLT                                        b. 004000K122 3.4/3.7 Int:rlocks associated with MU Tank at 10 inches?

Examiner: _. ChicfExaminer: 0

JOB PERFORMANCE MEASURE NO.142 Candidate: Examiner: Date: Facility: Davis Besse Task

Title:

Purification of the RCS Using SFP Purification with Loss of DH Flowpath Job Performance Measure No: 142 Safety Function: K/A

Reference:

000 025-EA2.02 (3.4/3.8) 000-025-EK1.01 (3.9/4.3) Method of Testing: Simulated Performance g Actual Performance Simulator 3 Control Room In-Plant Task Standard: Leak isolated by closing DH 1B. DH Pump 2 started. Required Materials: DB OP 06012 Decay Heat and Low Pressure injection Operating Procedure, Revision 02, C-5 DB-OP-02527, Loss of Decay Heat Removal, Revision 02 OS-004, Sh.1, Revision 21 OS-007, Revision 14 Oeneral

References:

DB OP-06012, Decay Heat and Low Pressure injection Operating Procedure, Revision 02, C 5 DD-OP-02527, Loss of Decay Heat Removal, Revision 02 OS 004, Sh.1, Revision 21 OS 007. Revision 14 Time Critical Task: No Estimatod/ Validation Time: 25 minutes Egad to Performer: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You will make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied. During the course of the walkthrough examination, there may be some tasks you will be asked to perform that may require you to implement an alternative method directed by plant procedures in order to complete the assigned task. You are expected to make decisions an-1 take actions based on the facility's procedural guidance and the Indications available. You may use any approved reference materials normal y available, including logs. Make all written and/or oral reports as if the evolution was actually being perfonned, i l

                          .                    .          _.,        =-.                    -.- -- . - ._.. _ _-. - - . ..- . -

JOB PERFORMANCE MEASURE NO.142 Initial Conditions: Mode 5, t>ecay Heat Train 1 in service. Initiating Cue: You are the Assistant Shift Supervisor in the CTRM. The plant is in Mode 5 with Decay Heat Removal Train 1 in service. The Shift Supervisor directs you to direct and monitor the lineup for purification of the RCS LAW DB. OP 06012, starting at step 4.14.14. All prerequsiltes and steps prior to that step have been completed. Three EOs are on station. You are directed to update the CTRM OS drawings as components are manipulated.- OS-004 and OS-007 are marked up through Step 4.14.13. Here is your copy of DB-OP-06012. _ - _ _ _ _ _ _ _ _ ___________.___._________m_m_

Performance Information NOTE: Critical steps denoted with a "C". Failure to meet any one of these standards for this item constitutes failure. Sequence is assumed unless denoted in the " Comments". Start Time

1. Performance Step: Direct plactment of three operators for throttling DH 61.

Standard: Ensure dispatch of an EO to DH 61 and to FIS 1616 to monitor flow and to Pl 1634 to monitor pressure. Cue: None SAT UNSAT

2. Performance Step: Throttle open DH 61 to obtain 80100 gpm on FIS 1616 and <100 psig on Pl1634.

Standard: Communicate with the EO at DH 61, who will throttle open DH 61 while the other two EOs monitor flow and pressure. Cue: None. Note: Candidate is to perfomi all steps subsequent to acknowledging leak. (Becomes Reactor Operator) SAT UNSAT

3. Performanco Step: Recognize, based upon the report from an EO that DH System leaks downstream of DH 18.

Standard: Receive report and report to SS that a leak exists downstream of DH 1B. Cue: SS acknowledges the report and directs that DH 1B be ciosed to isolate the leak. SAT UNSAT

4. Performance Step: Close DH 18.

     .........C.............

Standard: Place control power on DH 1B and press CLOSE on HIS DH 18. Cue: SS directs you to perform appropriate actions for a Loss of DHR Flowpath. SAT UNSAT

I RM 1

5. Performance Step: Locate the conect prc edure.

St.mdard: Identifies DB-OP 02527. Loss of Deca / Heat Removal, Section 4.2, as the correct procedure and section. Cue: Hand copy of DB-OP 02527 to candidate. SAT UNSAT

6. Performance Step: Check DH Pump W1 for loss of suction flowpath or cavitation.

Standard: Check for OPEN Indications on HIS DH 11, HIS DH 12, and HIS DH 1517. Cue: None. SAT UNSAT

7. Performance Step: Locate the correct procedure section.

Standard: Route to Section 4.1 after recognizing that the Train 1 Howpath can not be restored, ument: This will be from either Step 4.2.2 or 4.2.5. s a: None. SAT UNSAT

8. Perfomiance Step: Refer to Attachment 4 to start DH Pump 2.

Standarrt: Route to Attachment A. Comment: Venting should not be required.

Cue: If askett, SS directs that venting is not required. SAT UNSAT S

s l

9. Performance Step: Close DH 14A.

     .........C.............

Standard: Push AUTO on HIS DH 14A. Close DH 14A using H!C DH 14A. Cue: None. SAT UNSAT

10. Performance Step: Close DH 13A.

      .........C.............

Standard: Push AUTO on HIS DH 13A. Close DH 13A using Hic DH 13A. Cue: None. SAT UNSAT

11. Performance Step: Verify DH 1518 open.

Standard: Check HIS '518 red light ON. Cue: None. SAT UNSAT

12. Performance Step: Verify DH 11 and 12 open.

Standard: Check HIS DH 11 and HIS DH 12 red lights ON. Cue: None. SAT UNSAT

13. Performance Step: Verify CCW cooling available.

Standard: Observe check of CC Pump 2 running. Cue: None. SAT UNSAT l

l I

14. Performance Step: Verify SW cooling available.

Standard: Observe check of SW Pump 2 running. Cue: None. SAT UNSAT

15. Performance Step: Verify DH 1 A open.

Standard: Check HIS DH 1 A red light ON. Cue: None. SAT UNSAT

16. Performance Step: Start DH Pump 2.

     .........C.............

Standard: Turn HIS DH 6A to START. Cue: None. SAT UNSAT Terminating Cue: This JPM is Complete. End Time

SAMULATOR INSTRUCTlONS ; TASK DESCRIPTION: l PurtNcation of the RCS using SFP Purification with Loss of DH Flowpath j lNITIAL CONDITION:

       - Mode 6 DH9 Trale ) in service ADDITIONAL SETUP /DEVIATlON FROM INITIAL CONDITION:

1. Ensure DH Cooler #1 outlet temperature is <120Y.

2. Ensure RCS pressure is <100 psig.

3. Ensure Section 4.14. Is completed through Step 4.14.13.

4. . Ensure Breaker BF 1129 Is open for DH 1616 with Ops info tag hung on His.

6. Ensure SF 74 closed.

4. Ensure SF 2456 closed.

MALFUNCTIONS / FAILURE TO INSERT:

       - DH line leak downstream of DH 18       TVBF0301/0.01/ direct ACTION / CUES:

Step 1. CUES: Role play as each EO to report on station and ready for throttling DH61. Step 2. CUES: Pl 1634 roads 60 psig. FIS 1614 roads 66 gpm. DH 61 is approximately 21/2 turns open. ACTION: Use CTS to slowly deposit TABDDH61 to a value of 0.26. Step 3. CUES: Role play as EO in MPR #1 that water is spraying from the pipe downstream of DH 18 at approximately 60 76 gpm. ; ACTION: Insert DH line leak by opening drain viv as follows: TVBF0301/0.01/ direct.

VEtFICATioN OF COMPLETiohl 0;^. '^- Evaluator asN Date License: ( ) RO [ ] SRO Validated Completion Time: minutes ' l , t Actual Completion Time: minutes Acceptable Progress Maintained: Yes No N/A

     ' Result:       [ ] SATISFACTORY             [ ] UNSATISFACTORY NOTE: An " Unsatisfactory" requires Comment and will require subsequent remedial training.

Comments / Feedback: I Evaluator's signature Date

   <.             o                                                                                                                                                                                                                 l t
                                                                                                                                                                                                                                  'i
                  ,,               JPhMMELSTION # I42a
                                   -- m                                                                                                                                                                                             ;

i Question:- bplain how to take MANUAL control of decay heat flow through DH 14A or DH 148 from the CTRM, !' aner SA 3 has been actuated. All oquipment operated as designed. (Adminiarative requirements need NOT be included ) > i E Answer:

                               . a.       BLOCK SA 3.

b. Push the AUTO pushbutton on Dil 14 A/B.

                              - c.        Control valve position with 13ailey controller.

SAT /UNSAT

Reference:

DBOP 06012 (3.5.14), R02 l K/A 0054XWA4.02

4 I

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REFERENCES ALLOWED: -YES i O.ustion' [ If the DSA and DSB emergency control transfer swithces for Decay Heat Pump l 1 are out of the NORMAL position, it will have what eNect on the Decay Heat pump? ; t Answer: t

a. Decay lleat pump will NOT respond to an SFAS 3 START signal.

b. TI.e pump cannot be operated from the C1RM (but can start locally).

c, There would be no CTRM indication (green light out above control switch). : SAT /UNSAT _ Referenec: DD OP 06012 (3.5.14), R02 - t K/A 005-000 A4.02 ; k 6 9 t F

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4: JPM No. 145~ P:g3 5 of 11 SIMtHATOR INSTRIM!T1cuq 11sz pascRzprzon:

lease of Service Water Loop 1 to Primary Loads INITIAL. CONDITION: FPSS ADDITIONAL SETUP /DEVII.FION FROM INITIAL CONDITION: Service Water Loop 1 on primary loads. MALFUNCTIONS / FAILURE TO INSERTS i Trip /Stop service Water Pump i by inserting malfunction TFK6TBR/T. Run until alarm 11-1-B comes in. ACTION / CUES

         ..       cuss service water Pump 1 so/si-A relay target is tripped.

l 9 r l l-

. 1, DAVIS-BESSE NUCLEAR POWER STATION JOB PERFORMANCE MEASURE WORYJHEET dEH }{ Qts 14B Rev. 06 Page 7 of 11 ZhSK HO. 076-002-04-0100 IASK_DRSCRIPTION: Loss of Service Water Loop i to Primary Loads K/A

REFERENCE:

000-062 EK3.01 (3.2/3.5), 000-062-EK3.03 (4. 0/4. 2) , 000-062-GEN.10 (3.6/3.5)

      &PRLICABLR METitOD OF TRSTING: Simulate performance Simulator IIME FOR COMPLFTION:     7 minr*.es
     &PPLICABILITY:     (X) RO       (X) SRO 7ASK STANDARDS:
 *]

1. CCW Pump 2 running supplying essential and non-essential loads.

2. CCW Pump 1 stopped.

E,.EOUIRED MATERIALS: DB-OP-02511, Loss of SW Pumps / System, Revision 01, C-3 GENERAL REFERENCEg DB-OP-02011, iteat Sink Alann Panel 11 Annunciators, Revision 01, C-3 DB-OP-02511, Loss of SW Pumps / System, Revision 01, C-3 INITIAL CONDITIONS: The plant is in Mode 1. All systems are in a normal lineup, except that SWP-3 is OOS for maintenance. CCW Pump 1 is running and supplying primary equipment. CCW Pump 2 is in standby. INITIhTING CUR $3 The following annunciator alarm is received: CC HX OUTLET T5'MP !!I (11-1-D)

a5 . JPM No. 14D- -. . P gs 8 of 11 INITIAL EXMDITI0ft( The plant is in Mode 1. All systems are in a normal lineup, except that SWP-3 is 008 for maintenance. CCW Pump 1 is running and supplying primary equipment. CCW Pump 2 is ~ in atandby. IMITIATING. CUBS: The following annunciator alarm is received CC ltX- OUTLET TEMP III (11-1 B)

e JPM No. 143 P:gs 9 of 11 FMRFORM&MCR INFORM &TICIf NOTEI Critical steps denoted with a 'Ca. Failure to meet any one of tesese standards for this item constitutes failure. Sequence is assumed unlass denoted in the " Comments".

START TIME:

1. PERFORMANCE STEP: Locate the correct procedure.

STANDARD: Identifies DB OP 02011, Heat Sink Alam Panel 11 Annunciators.

CUE: None.

A {*' . llG*F 6 %5 % ", & SAT eke <f (C LA) 4# re# t s UNSAT 4

2. . PERFORMANCE STEP:-- Locate the correct procedure and section.

STANDARD: Identifies Section 4.1 of DB OP 02511, Loss of SW Pumps / System as correct procedure., tv a n<,,4rn s, {-o bg.o f> pggj yc ;, 7,j CUE: None. SAT UNSAT

3. PERFORMANCE STEP: Investigate the relay targets on the tripped SWP breaker.

STANDARD: Send EO to locally check breaker AC 107 targets. CUE: itonei- 7v)P ( Gdh M. 7,, ,, . ,

                                                                             -o}t
                                                                                    *',  't     5
                                             ,                                                    SAT UNSAT

4. PERFORMANCE STEP: Verify CAC 1 or 3 as-1 is off, verify SW 1366 and

                      ........C........      SW 1368 are closed.

l STANDARD: HIS 5031 for #1 CAC pushed; green light ON. HIS 1366 for 3W 1366 CLOSE pushbuti.on pressed. Observe green light ON HIS 1368 for SW 1368. Observe green light ON HIS 5033A for #3 CAC. CObNENT: SW 1368 }){QI critical. HIS 5033A 11QI critical. CUE: None. SAT UNSAT m:,

- - _ _ . _ .,_.._.._.._._.____m .__.._......_.m _.____...m. ..._.._._.--m

JPM No. 145 - Pag 3 10 cf 11 l

5.- PERFOftMANCE STEP - Start CCW Pump 2.

                                          ........C........                                                                                                                                           -!
                                                                                                                                                                                                         !~

STANDARD: CCW Pump 2 control switch, HIS 1418, rotated clockwise to START. col @4ENT: SHOULD GET 11-5 B, CC PMP 2 FLOW LO. I CUE: - None. SAT CNSAT *

                             .6.         PERFORMANCE STEPS Shift non essential loads to CCW Loop 2.                                                                                                     ,
                                          ........C........                                                                                                                                             t STANDARD:                         Push-OPEN on HIS 5096, CC Line 2 disch, isolation valve, HIS 5098, CC Line 2 return isolation valve,                                                               ,

HIS 2649, CC From Aux. Bldg. to Line 2 isolation. COMMENT - Sequence NOT required for this block. l t ( CUE: None. ' SAT UNSAT k* 7. PERFORMANCE STEP: Isolate CCW Loop 1.

                                         ........C........

STANDARD: Push CLOSE on HIS 5095, CC Line 1 disch, isolation valve, [ HIS 5097, CC Line 1 return isolation valve, HIP P645, CC From Aux. Bldg. to Line 1 isolation valve. COMMENT: Sequenec NOT required for this block. , CUE: None. SAT UNSAT ,

8. PERFORMANCE STEP: Check CCW Pump 1 for high temperature trip. '

STANDARD: Check CCW-temperature or check pump status lights. 4 CUE: None. SAT UNSAT TERMINATING CUES: This JPM is complete. - END TIME f

    - . , - - ,      ,..+-.m      . . . _ .             ,=,-,1~,= .-,,_,._,.r.,,,,w,m,,       .~,-~,,,m,,m                    , + . ,               ..,'..  .
                                                                                                                                                               -w- . , . , .    +,w,-,    -M,,r,,,,,+

I l JPM No. 14 l P:g3 11 cf 11 - VERIFICATION.0F_ CONF 12 TION Operator Eval Aator SSN Date 1.icence: () RO [] SRO Validated Completion Times minutes Actual Completion Times minutes Acceptable Progress Maintained: Yes No le/A Resultn [] SATISFACTORY () UNSATISFACTORY NOTE: An " Unsatisfactory" requires Comment and will requiro , subsequent remedial training. W) Comments / Feedbacks s

Evaluator's Signature Date

ee s I t JPWQUESTION # les t REFERENCES ALLOWED: YES ! t Question: ' I State the automatic features and laterlocks associated with SW 1395 and SW 1399 (TPCW host exchangt service water supply header isolation valws). j

                     - Antwer:                                                                                                                                                                                 i e

s .- These vahes will automatically close if respective (downstream) SW header pressure drops l (to 50 psig) j

b. Close on an SA 24 SAT /tJNSAT ty !

I b Referesa: DB OP 02000, Table 2 R05 - I DD OP,s261 (2.2.5), R02

IUA 076@0 A2.02

)'

a

 ==          ye--my4         p-- y   ae sg T rp e pJ W ge ggy .g-ee&        g grr 9' 9 7                  %eg=wT       T-*D"-Wir ip e-=dM -W 4  sp'MfyW W    " *'      t-F_W'WTt'-+%'M*7'"**& MNT-'*TP:'N

l

e. -o !

I A% QUESTION 8146~ ! REFERENCES ALLOWED: YES Queadon: What are the specine autostart signal for a sen ke water pump? i Answer:

l. SA tact 2 starts immediately

2. SA lael 2 and UV (or EDO tyitig to the 4160 VAC bus) . starts on sequencer (sequencer step 4).

3. AAct bus UV withEDO breaker closure (with 40 second delay) l t

SAT /UNSAT fi h t

Reference:

DB OP42000, Table 2. R05 DB OP 02000 (4.5.2), ROS K/A. - 000 062-EK3,02 4

                                                                                                                        -                                            y   -

y- e *r- pcr. r,,.w..,y,,.r-+--rr-g

       ,                                                   JPM SPECIFICATION                                  DATE: 06/20/97 JPM Number                                   s

ORQ.123 ;

i Rev Nbr/Date : 00 09/13/95 . ,RO (R/S). *R Init Cond Plt Mode : Systen, Group : i JPM Title : Remove an SFAS Component from the Shutdown Bypass 4 Mode l Keyworda : Action Indicatora : REVIEW PROCEDURE CHANGE VALIDATE Ri? VISE Proc Ref/Rev/ Step DB-OP-06405 (C-5) 02 Required Material : DB-OP-06405, Section 3.9 10 CFR 55.59 Itema : Com'r ent s : Sequence : B Create: 09/14/95 Active : Y Completion Times 24,0 Time Critical: N Faulted : N F$ Nbr RO/SRO Rating : 013-000-GEN.13 3.9.4.0 /~*

~
    ; Number                                  : 013-019-01-0100 Mode of Teat / Setting                         : SIM SIMULATOR Sim Guide Cross-Ref Validate By Names                              : MELSSEN                          RISHEL STALLAkD Laat Used JPM Rev/Date:

o 'QRQ 123B PAGE: 2

      )                                JJMgWGQ]LIji1IggI1QHg                                                                                                          I t

TASK DESIBlpfigj{n Remove components from SFAS Shatdown Bypaso IHlT1hlAS.QHD111QHA: Mode 5 with SFAS Shutdown Dypass established ADDIT 191Bk EXIVE: lione iMktVNCTIOND:

         !Jone ACTION /CUJG:

13cno

e QRQa1233 PAGE: 3 INITIAL CONDITIQMR: ,, 4 You are the spare RO. The plant is in Mode 5 with HQ fuel handling activities in progress. AHIIIATING CUES: The Shift Supervisor directs you to remove the SFAS Shutdown Bypass from EVS Pan W1, EVA Fan #2, and Fuel Handling Area to EVS Dampers, CV 5024 and CV 5025.

GRQ.123B pggg, 4 PERFOPMANCE ..INFOP.MATION

   .I      NOTE: Critical steps denoted with a "C".      Failure to meet any one of these standards for this item constitutes failure. Sequence is assumed unless denoted in the ' Comments *.

r i l START TIME: l t i

1. PERFORMANCE STEP: Identify procedure and section.

STANDARD: Identifies DB OP 06405, Section 3.9. COMMENT: When correct section is identified, hand exaninee pre marked Section 3.9. Sequence of channels is NOT critical. CUE 1 None. SAT UNSAT

2. PERFORMANCE STEP: Obtain keys and tools.

STANDARD: Door keys for all four SFAS channels, Shutdown Bypass f?p key, and insertion tool obtained. CUE: None. (If insertion tool Dol available, use bent paperclip.) SAT UNSAT NOTE: Applicant should skip all steps in right cabinet.

3. PERFORMANCE STEPi insert bypass key into beft Cabinet SFAS Channel 1

             ........C........ Shutdown Bypass Module SET / RESET switch.

STANDARD: Key inserted into left module SET / RESET switch. CUE: None. SAT UNSAT

4. PERFORMANCE STEP: Turn SET /PESET switch to RESET and HOLD.

             ........C........

STANDARD: Switch held in RESET. CUE: None. SAT UNSAT

ORQ 1233 . PAGE: 5

     ) 5. PERPORMANCE STEP . Insert tool into hole next to EVS 1.
           ........C........

STANDARD: Tool inserted into EVS 1 hole and held approximately 2 seconds. RED data light goes to GREEN or OFF. COMMENT: Sequence NOT critical for Steps 5 and 6. CUE: None. SAT UNSAT

6. PERFORMANCE STEPr Insert tool into hole next to CV 5024,

           ........C........

STANDARD: Tool inserted into CV 5024 hole and held approximately 2 seconds. RED data light goes to GREEN or OFF. CUE: None. SAT UNSAT

7. 1ERFORMANCE STEP: Release and remove key. Close and lock doors.

STANDARD: Key released and removed. Doors closed and locked.

   .      CUE:               None.

SAT UN7AT

8. PERFORMANCE STEP: Insert bypass key into Left Cabinet SFAS Channel 2

           ........C........ Shutdown Dypaso Module SET / RESET owitch.

STANDARD: Key inserted into left module SET / RESET switch. CUE: None. SAT UNSAT

9. PERPORMANCE STEP: Turn S::T/ RESET awitch to RESET and HOLD.

           ........C........

STANDARD: Switch held in RESET. CUE: None. SAT UNSAT l

GRQ*123D FACE: 6

 ) 10. PERFORMANCE STEP: Insert tool into hole next to EVS 2.
          ........C........

STANDARD: Tool inserted into EVS 2 hole and held approximately 2 seconds. RED data light goes to GREEN or OFF. COMMENT: Sequence NOT critical for Steps 10 and 11. CUT. : None. SAT LUISAT ,

22. FEPFORMAllCE STEP: Insert tool into hole next to CV 5025.

          ........C........

STMIDARD: Tool inserted into CV 5025 hole and held approximately 2 occonds. RED data light goes to GREEN or OFF. CUE None. SAT LU! SAT

12. PEPFORMANCE STEP Release and remove key, Close and lock doors.

STANDARD: Key released and removed. Doors closed and locked. h) CUE: None. SAT UNSAT

13. PERFORMANCE STEP: Insert bypass key into Left Cabinet SFAS Channel 3

          ........C........ Shutdown Bypass Module SET / RESET switch.

STANDARD: Key inserted into lett module SET / RESET switch. CUE: Nono. SAT In1 SAT

14. PERFORMAtJCE STEP: Turn SET / RESET switch to RESET and HOI.D.

          ........C........

STANDARD: Switch held in RESET, CUE: None. SAT UNSAT

i OkO*1238 PAGE: 7 f

15. PERFORMANCE STEP: Insert tool into hole next to EVS 1. t

        ........C........

STANDARD: Tool 1.inerted into EVS 1 hole and held approximately 2 seconds. RED data light goes to GREEN or OFF. COMMENT: Sequence NOT critical for Steps 15 and 16. CUE: None. SAT UNSAT

16. PERFORMANCE STEP Insert tool into hole next to CV 5024.

        ........C........

STAND? 'tD i Tool inserted into CV 5024 hole and held approxistately 2 seconds. RED data light goes to OREEN or OFF. CUE: None. SAT UNSAT 17 PERFORMANCE STEP: Relet.se and remove key. Close and lock doors. STANDARD: Key released and removed. Doors closed and locked. CUE: None. I SAT tRISAT 18 PERPORMANCE STEP: Insert bypass key into L d Cabinet SFAS Channel 4

        ........C........ Shutdown Dypass Module SET / RESET switch.
      -STANDARD:          Key inserted into lett module SET / RESET switch.

CUE: None. SAT UNSAT

19. PERFORMANCE STEP: Turn SET / RESET switch to RESET and HOLD.

        ........C........

STA!C 7: Switch held in RESET. CUE: None. SAT UNSAT

QRO 123D , PAGE: e

20. PERFORMANCE STEP: Insert tool into hole next to EVS 2.

        ........C........

STANDARD: Tool inserted into EVS 2 hole and held approximately 2 secotsds. RED data light goes to GREEN or OFF. COMMENT: Sequence 140T critical for Steps 20 and 21. , CUE None. _ SAT UNSAT

21. PERFORMANCE STEP: Insert tool into hole next to CV 5025.

       ........C........

STANDARD: Tool inserted into CV $025 hole and held approximately 2 seconds. RED data light goes to GREEN or OFF. CUE: None. SAT UNSAT

22. PERFORMANCE STEPS Release and remove key. Close and lock doors.

STANDARD: Key released and removed. Doors closed and locked. CUE: 1.one. SAT UNSAT

23. PERFORMANCE STEP: Return keys and tool.

STANDARD: Key and tool returned. CUE: None. SAT UNSAT TERMINATING CUES: This JPM in complete. END TIME

e l l VERIFICATION OF Col (EkIILQg Operator Evaluator SSN Date Licenses () RO [ ] SRO Validated Completion Timet minutes Actual Completion Timer minutes Acceptable Progress Maintained Yes No N/A Results [] BATISFACTORY ( ) UNSATISFACTORY NOTE: An " Unsatisfactory" requires Comment and will require cubsequent remedial training. Commento/ Feedbacks

Evaluator's Signature Date

I JPM42URSTION # 123a

REFERENCES AMOWED: NO 'i i Question: ne Safety Actuation Monitor (SAM) light for letdown coolers outlet valve (MU3) is BRIGHT _ and PLASHING. What does INW light condition mean? ; i i Answer; i SFAS tilp and equipment actuated, blocked by operator, and placed in non SFAS position.

                                                                                                                - SAT /UNSAT

Reference:

Dil OP-0640$ (Att. 2), R02 K/A 013 000.A3.02 ,. 1 i

                                                                                                                                                        ~.
           )     6 #12)b                                                                                                                                                 J
                                                                                                                                                                         )

REFERENCES ALLOWED: YES

               ' Ouestion:

If SFAS imel ! actuated at the same time that RE S446 and 8447, Fuel Handling Exhaust Syslem Radiation Monitors alarmed, to where would the Station EVS align its suction? i Ansurr: ! The Station EVS would align to tiie negat}ve pressure areas ( Annulus. ECCS Rooms, MPRs, MUP Room). , f SAT /UNSAT t

Reference:

OS 33D R/A' - 013 000 GEN.04 - I T

        ,)                                                                                                                                                             !

.,c- s , ,+ 4- e --- - r g w w- y-

            .j.           _  _ _ _ . . _          _ _ . _ _ _ _ _ _ _ _          _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ _ _ . _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _                 __

DAVIS-SESSR NUCLEAR POWER STATION i JOB PERPORMANCE MEASURE WORK 8HERT I I HM.224, 69 Rev. 06 Page 1 of 5 TASK NO. 063-006-01-0100 f i TASK DESCRIPTION: Swap to a Swing Battery Charger

'/

E./A RET.3AEMEE: 063 000 GEN.09 (3.1/3.3) APPLICABLE METHOD OF TESTING Simulate performance ' In-plant TIME _FOR_ COMPLETION: 10 minutes MPLICABILIII: [X) RO [X) SRO , IASK STANDARDS:

1. Perform all indicated breaker operations.

2. Position the output selector switch an indicated. -

BXQUIRERJAIERIALS: DB-OP-06321, 250/125 VDC G2ation DC Switching Procedure,. Revision 01 GENERAL RCFElpMCES: DB-OP-06321, 250/115 VDC Station DC Switching Procedure, Revision 01 JNITIA* CONDITIONJ: The. plant is in Mode 1; All systems are in a normal lineup. INITIATING CUES: The Shif t Supervisor directas yw to perfom a live transfer to p) ace swing ' battery charger DDC.1PN (which is ' lined up in STANDBY) in service for charger DBC 1P, . :in e.ccordance with DB-OP-06321. There is HQ fault on charger DBC IP. l

      .                     -~(Hand examinee ~a copy.of DB-OP-06321.)
              . . _ < < ,                n      ,

r --. n -

JPH Ho. 69 Pego 2 of 5 IHJTIAL Col!DIIIp](2 Thts plant is in Mode 1. All systems are in a normal lineup. 1HlIIATIN9 WKlit: The Shitt Supervisor directs you to perform a live tranafer to place swing battery charger DDC iPN (which is lined up in STANDBY) in service for charger DI1C 1P, in accordance with DB-OP-06321. There is LLQ fault on charger DBC IP. '

1 JIH No. 69 Page 3 of 5 PERFORMANCE JNFOP5AT10N NOTE: Critical steps denoted with a "C". Failure to meet any one of these standards for this item constitutes failure. Sequence is accumed unless denoted in the " Comments". START TIME:

1. PERFORMANCE STEP: Locate the correct procedure, y .

STANDARD: Hand procedure to examinee. Locates the correct proceduro acetion (4. 3) . CUE: None. SAT UNSAT

2. PERFOI4tANCE STEP Open/ verify open DC Output Breakers D105 mld D121.

STANDARD: Take handswitch to the OPEN position / visual indication. CUE: D105 indicates OFF/ TRIPPED. D121 indicates GFF/ TRIPPED. SAT UNSAT

3. PERFORMANCd STEP: Verify the AC INPUT ON/OFF switch for charger

          ........C........ DBC IPN in ON.

STA'DARD: Visual.ly verify ON. CUE: (DBC IPN AC Input) ON/OFF Owitch indicates ON. SAT UNSAT

4. PERFORMANCE STEP: Verify stable voltage on battery charger DDC IPN.

STANDARD: Voltmeter P2-2C' on battery charger DBCIPN reads between 130V and 140V. CUE: Voltage reads 1,32V and stable. DAT UNSAT

 *   . JPM No. 69                                                                P ga 4 of 5 l

t

5. -PERFORMANCE STEP: Set the DC Transfer switch to Position 1.

               ........C........

STANDARD: Place output selector switch in the "1" position. CUE: Handswitch has been placed in Position "1". SAT .UNSAT k C. PERFORMANCE STEP: Close DC output Breaker D105.

               .....v .C........

STANDARD: D105 placed in ON position. COMMENT: E-7 is posted in LVSR #1 if confusion exists at this step. CUE: (D105) Breaker has been placed in ON position. SAT UNSAT

7. PERFORMANCE STEP: Open DC Output Breaker D103.

                ........C........

STANDARD: D103 placed in OFF/ TRIPPED position. CUE: Breaker (D103) has been placed in OFF/ TRIPPED. SAT UNSAT TERMINATING CUES: This JPM is complete. END TIME l

JPM No. 69 P:g3 5 of 5 i YERIFICATION OF COMPLETION Operator Evaluator SSN Date License: [] RO () SRO

Validated Completion Time: minutes Actual completion Times minutes Accentable Progress Maintained: Yes No N/A Result [] SATISFACTORY [] UNSATISFACTORY NOTEt An " Unsatisfactory" reguires Comment and will require subse pent remedial trei.ning. Comments /Foedback

Evaluator's Signature Date

1 JPM/ QUESTION # 69a REFERENCES ALLO %T.D: YES Question: What are the indications that the local battery charEcr panel provides to the operator when an EQUALIZER charge is in progress. Answer: Accept any three of the following:

               -        Red EQUALIZE CHARGE light is LIT
               -        The equalizer tiinct is running
               -        FLOAT / EQUALIZE switch is in the EQUAllZE position
               -        DC output voltage raises to the Equalize Charge setting (-139-140 VCD)

SAT /UNSAT

Reference:

OS4MO CD-1, R12 K/A 063-000-GEN,09

  .l. i;                   :a; f                                                                                                                                                                                           ,
                                                                                                                                                                                           'u
                                                               ~
                 . JPM/ QUESTION # 69b ;

REFERENCES AllDWED:- NO - Question:-

                       ..What purpose is served by performing selective bettery load shedding per.

Attachment 5 of DB OP42521, less of AC Bus Power Sources, upon a loss of BOTH 4160 VAC essential busses? - Answer: I Allows longer use of the station batteries by removing loads no longer necessary

                      - for orderly control of the station.

SAT /UNSAT

')

Reference:

DB-OP-02521 (4.1.6) ROI

~>

K/A 000-057 EK3.02 1

.e DAVIS-BESSE NUCLEAR POWER STATION JOB PERFORMANCE MEASURE WORKSHEET dpH NO. 57 Rev. 05 Page 1 of 6 IbSK NO. 004-000-04-0100 002-008-04-0100 TASK DESCRIPTION: Borate from Outside the Control Room K/A

REFERENCE:

000-024-EA1.02 (3.7/3. 5) , 000-024-EA1.04 (3.6/3.7), 000-024-EA1.17 (3.9/3.9), 000-024-EA1.20 (3.2/3.3),

                /      000-024-EA2.02 (3.9/4.4) 6PPLICABLE METHOD OF TESTING: Simulate performance In-Plant TIHR FOR COMPLETION:       20 minutes APPLICABILITY:     (X) RO      (X) SRO T_ASK STANDARDS:

1. Lineup for boric acid addition using local valves.

2. Start DA Pump 1.

REQUIRED MAIERIALSt DB-OP-06001, Boron Concentration Control, Revision 01, C-4 GENERAL

REFERENCES:

DB-OP-06001, Boron Concentration Control, Revision 01, C-4 1NITIAL CONDITIONS: The plant is in Mode 1 at 100% power. A load reduction to 50% power is planned. JfITIATING CUES: The normal boric acid addition method cannot be used. You have been directed to add 50 gallons of boric acid to the MUT from outside the CTRM usinC Boric Acid Pump 1, per DB-OP-06001. Hand copy of DB-OP-06001 to examinee.

                                                                     .- ..            , .          ,           .n-.              . . . . . ....~

a '- ri JPM No.l57? P g2 2 cf 6 ZNITIAL CONDITIONS: .

                  --:The' plant is in-Mode-.1 at 100% power.: 1A-load' reduction to 50% power is E

planned.

                                                                                                                                                   -F INITIATING CUIS:
                    -The normal boric acid addition method cannot be used. You have-been directed
                      -to. add.50 gallons of boric. acid to the MUT from outside the CTRM using Boric
                                                                         ~

Acid Pump 1, per DB-OP-06001. 9- . 4 i j. i

                                                   . , , , . . , . . ,     ,- ,w.w-,,       ,..n,.  , ...n,. ,      , . , ,,

 . JPM No. 57                                                                                                P ga 3 of 6 PERFORMANCE INFORMATION NOTE: Critical steps denoced with a "Ca.               Failure to meet any one of these standards for this item constitutes failure.                                         Sequence is assumed unless denoted in the " Comments".

i i l START TIME: l l 1

1. PERFORMANCE STEP: Locate the correct procedure section.

STANDARD: Identifies DB-OP 06001, Boron Concentration Control, Section 5.1, as the correct procedure section. COMMENT: Provide correct procedure to examinee. When the correct procedure section has been located, provide the CUE. CUE: All prerequisites have been completed. SAT UNSAT

2. PERFORMANCE STEP: Verify Valves MU 348, Boric Acid Pump 1 Discharge, WC 393, Concentrate Storage Tank to MU Filters Line 2 and 394, from concentrates Storage Tank to BAATs Discharge, arc open.

STANDARD: Handwheel / stem position indicate OPEN. COMMENT: Sequence is NOT required. CUE: MU 348, valve stem is UP. WC 394, valve stem is UP. WC 393, valve stem is UP. SAT UNSAT

3. PERFORMANCE STEP: Verify MU 351, Boric Acid Pump 2 to Makeup Filters open.

STANDARD: MU 351 stem position indicates OPEN. CUE: MU 351 valve stem is UP. SAT UNSAT

4. PERFORMANCE STEP: Close MU 363, BAAT 1 to Makeup Filters.

STANDARD: Handwheel to the CLOSE position. COMMENT: MG 363 located be*. ween BAATs in CA. CUE: MU 363 has been rotated clockwise / CLOSED; valve stem is DOWN. l SAT UNSAT l

  . JPM No. 57                                                           P:g3 4 of-6

5. PERFOKMANCE STEP: Open hJ 366, BAAT 2 to Makeup Filters.

          ........C.......

STANDARD: MU 366 handwheel turned (CCW) until FULLY OPEN. CUE: MU 366 handwheel has been rotated counterclockwise / OPENED; valve stem is UP. SAT UNSAT

6. PERFOR)RNCE STEP: Start Boric Acid Pump 1.

          ........C........

STANDARD: BA pump 1 started using IDCAL pushbutton or started from Control Room. COMMENT: Either method is acceptable. CUE: (If requested to START from Control Room), Control Room Operator has started BA Pump 1. (If Started Local), Local START pushbutton for BA Pump 1 is pressed; RED light LIGHTS; GREEN light goes OFF. SAT UNSAT

7. PERFORMANCE STEP: Stop Boric Acid Pump 1.

STANDARD: BA Pump 1 is stopped using either the LOCAL pushbuttons or . from the Control Room. CUE: Control Room Operator reports that 50 gallons have been added to the MUT and BA Pump 1 has been stopped. (If stopped LOCAL) LOCAL STOP pushbutton for BA Pump 1 is PRESSED; Green light LIGHTS, Red light goes OFF. SAT UNSAT

8. PERFORMANCE STEP: Close MU 366, BAAT 2 to Makeup Filters.

STANDARD: Restore L/U, MU 366 handwheel turned.(CW) until FULLY CLOSED. CUE: MU 366 handwheel has been rotated clockwise / CLOSED; Valve stem is DOWN. The Shift Supervisor directs you to restore the BA System lineup. SAT UNSAT

 . JPM No. 57.                                                       Pago 5 of 6

9. PERFORMANCE STEPS Open MU 363, BAAT 1 to Makeup Filters.

STANDARD: Restore L/U, MU 363 handwheel turned (CCW) until FULLY OPEN. CUE: MU 363 handwheel has been rotated counterclockwise / OPE 43D: valve stem is UP. SAT UNSAT TERMINATING CUES: This JPM is complete.

END TIME

y

     ~ 
                               - JPM No.                                                                    .P*g3 6 cf-6 l
                                                                                                        -                                  i YERIFICATICII OF CMPLETICAI
                                                                                                          -.7,,,.                 __
                               - Operator-                                            Evaluator _

SSN - Date^ l 1 Licenses' . [ ) , RO - -[ ].SRO i

*/.

validated Completion Times . minutes-. 1 J

Actual-Completion. Times'- minutes f Acceptable Progress Maintainedi Yes- No N/A Result '[-}, SATISFACTORY - [ } UNSATISFACTORY NOTE: An " Unsatisfactory" requires Comment and will require .

                                                           . subsequent.; remedial training,
                               . Comments / Feedback                                                                          .

i

=: ,

Evaluator's Signature Date r {.' 4

              ', \ ',        L
                                \

( _. . " I- .

 -r. .
                                                                                                                                                                                                                                                                                        ~

l

                                                                                                                                                                                                                                                                                        ~1 I

JPh& QUESTION # $7s REFERENCES ALLOWED: YES-Question-1 The following hiant conditions exist:

                                                                                             -                                 Reactor power is 50% -
                                                                                             -                                 MU 32 is in HAND -
                                                                                             -                                 Letdown flow is through #2 Mixed Bed Purification Demineralizer I What would be the effect on Pressurizer level and Makeup Tank level if MU 10B,
                                                       . Mix Bed 2 letdown inlet isolation Vahr was inadvertently closed? (30 minutes i have elapsed with NO operator action.)

Answer:

                                                          -                                  Pressurizer level would drop. - (Due to an inter system LOCA resulting from the lifting of the letdown relief valve.)
                                                          -                                 Makeup Tank level would drop. (Due to Makeup Pump still drawing water from the Makeup Tank, but letdown water not replacing the water in the                                                                                                                       (

Makeup Tank. [ l, SAT /UNSAT

Reference:

03402, Sh.1, R16 h j i

                                                      .K/A                                                                   004420-Al.05 T        -

s __-- or ..__ ._m._m_.__ _ _ _ _ _ . _ _ . - _ ___.___Em____ __ _ _ _ _ _ _ . _ _ _ - _ _ . _ _ _ _ _ _ _ _ _ _--__._.._ _

                                                         . . . .  .       .   ..          ..     . . . . . . . . - ~  - -    ..       ., .   . . .

A< . JIMQUF3 TION # 57b - 1 REFERENCES ALIDWED: NO-Question: Describe the AUTOMATIC actions that occur at 10 inches in the Makeup Tank. . t

                              ' Answer:
                                            */
                                          -           Transfers MU 3971 and MU 6405 to the BWST.-
                                          -           Starts 45 sec. timer. .
                                          -         . MUP trips if xfer not complite W/l 45 sec.-

SAT /UNSAT - s; ,

Reference:

DB OP 06006 (2.2), R03 OS-002,(CL 6/CL-8/CL 10), Sh.1 R16; Sh. 2 R15; Sh. 3, R23

                             .K/A                     004-000-K1,22 9

i g. J 1 _. _.--..._._.____._.____________i.i_____.

/

r. i FINAL AS-RUN SCENARIOS FOR DAVIS-BESSE EXAM 1

l

 ---             .    .. _           _.      _ _ _. -. _ ~ - _     . _ _ _ . .       ..     . __        . _ _ . __                   .

4 ES-301 Scenario Events Form ES-301-3 Simulation Facility: Davis Besse Scenario No.: -1 Examiners:'- E; Plettner Applicants: HARTNETT, D. (SRO)

                             -D. McNeil                                                              LAWREN,CE,         R.  (BOP)

PHILLIPS, T. (RO) Initial Conditions: 100% Power. BOL ( IC #27) Turnover: Nor5nal Ooeratina Conditions _with no eculoment out of service. The Load dispatcher has iust aooroved Power reduction to 50% Power for Water Box cleanina. -The shift is to start olant oower reduction to J1. c power at 3 MWe/ min. ] Event' Malf. Event Event

            -No.           No.      Type

Description 1 MUP-12 C Operating Makeup Pump trips due to shaft seizure.

2 R Power Reduction to 50% Power 3 MS-11 I Selected Hdr Press Instrument-fails to 600 psig 4 MS-02 M Steam leak intitiated in CTMT which increases to line rupture causing major overcooling

       *      (N)ormal,        (R)eactivity, .           (I)nstrument,         (C)omponent,        (M)ajor Chief Examiner:               ((            / O f

1 4 5 d , . - -

J , t

e :. '

t , , Page 2iof)91

                  . ILLIN1AODUCTION-I

_ A .); GENERAL DESCRIPTION ~ 4 This guide' starts with a trip.ofLthe operating _ makeup; pump:due to , aishaft seizure.' 'After the standby makeup pumpLis; started, a-- .,

                                 ^ power reduction-from;100%LTO 50%1to prepare for condenser water-

i. box: cleaning will be initiated. :During the power reduction 1the L

                                    - selectt,.1 steam header pressure; instrument will' fail to zero which will cause' turbine' throttle valves to close to attempt to--restore pressure and consequently-a reductionfin turbine load.. Once the                                        t turbine has been _ plsced in :tnanual and; the' plant:.is stabilized, an"-                              -

unisolable steam leak will develop in CTMT. Once the plant.is-- '! ' tripped to blow-down the-affected OTSG,.the' steam _ leak'becomes a Esteam line' rupture which causes a major overcooling.- ]

    ,f 4

4' V t W I i 5

              , f ,7 fWQ              ,

o . ES 101 Operator Actions Form ES-301-4 Scenario No.: 1 Event No.: 1 Page 3 of 9 Event

Description:

Operatino Makeuo Pumn Trips Due to Shaft Seizure Time Position Applicant's Actions or Behavior ALL Announce Seal Injection L,w Alarm. RO Recognize and announce the previously cperating Makeup Pump is not running. Recognize Pressurizer level decreasing SRO Irplement DB-OP-02512, Loss of RCS Makeup. SRO/RO IF PZR Level falls below 160 inches, THEN trip the reactor and route to DB-OP-02000 "RPS, SFAS, SFRCS Trip or SG Tube Rupture. PO Isolate letdown by closing MU 28. Isolate seal injection by reducing demand to 0 in RAND on FIC MU 19. Isolate makeup by reducing demand to 0 in HAND on FIC MU 32. SRO REFER TO DB-OP-02515, RCP and Motor Abnormal Procedure, for limitations on RCP operation without seal injection. BOP Verify CCW supply to RCPs, Monitor RCP seal return tempe*.atures. ALL Maintain constant power until the Makeup pump is restored. SRO Ask the SS to consult Tech Specs. (3.1.2.4,) RO Align standby MU pu.no to an adequate source. Start the standby MU pump before PZR level decreases below 160 inches:

a. Start AC oil pump, verify proper ops.

c. Start the MU pump, restore MU flow

e. Restore RCP seal injection

f. Restore letdown when Pzr. level is restored.

ES-301 Operator Actions Form ES-301-4 Scenario No.: 1 Event No.: 2 Page 4 of 9 Event Discription: Power reduction to 50% reactor ocwer Time Position Applicant's Actions or Behavior SRO Holds brief and reviews actions per DB-OP-06902, Power Operations. Notifies SOC in Cleveland that power reduction has started to 50% power at 3MWE per minute. Directs reactor operator to decrease power IAW DB-OP-06902, Power Operations. RO Reduces setting on Unit Load Demand, sets rate of change. Monitors power decrease to ensure correct equipment performance. BOP Monitors turbine, generator, matches AC and DC voltage regulator output as turbine load decreases.

ES-301 Operator Actions Form ES-301-4 Scenario No.: 1 Event No.: 3 Page 5 of 9 Event Descriptions lui 93% power, selected steam header cressure fails to 600 osia over 5 minutes. Time Position Applicant'n Actions or Behavior RO/ BOP Announces ICS INPUT MISMATCH Alarm 14-4-E. SRO Directs RO or BOP to SASS rack. Refers to and takes actions per DB-OP-02014, Alarm Panel 14. RO/ BOP Checks SASS rack, identifies failed instrument as SP-PT16B. SRO Directs taking turbine to Manual. May direct TBVs and/or AVVs to Manual if needed to control pressure. (May) Direct placing SG/RX HAND / AUTO Station to HAND. Refer to DB-OP- ' 06407, NNI System Operataing Procedure, Attachment 7, for effects of instrument failure. BOP Select Alternate Turbine Hdr Pressure Instrument SP-PT16A. Contact E&C to troubleshoot instrument selected. SRO Direct returning the following stations to AUTO using DB-OP-06401, Integrated Control System Operating Procedure,

a. Main Turbine at EHC pn.' in CTRM

b. TBVS and AVVs (if take to Manual)

c. SG/RX HAND / AUTO STATIId Continue the power reduct2on if still greater than 50% Power or, if less than 50% power direct power increase to 50% pwr.

+ . ES-301 Operator Actions Form ES-301-4 Scenario No.: 1 Event No.: 4 Page 6 of 9 Event

Description:

Steam leak initiated in CTMT which increases to line rupture causina maior overcoolina. Time Position Applicant's Actions or Behavior ALL Identify symptoms of a steam leak in containment:

a. Reactor power increase with MW load decrease.

b. Increased FW flow

c. Decrease in Tave, RCS press, Pzr level

d. Increase in CTMT Temp, Press and sump levels SRO Implement DB-OP-02525, Steam Leaks.

SRO Verify no one in CTMT. RO Place the running CACs in slow speed, verify SW valves to CACs wide open. SRO Direct operators to commence a plant Shutdown per DB-OP-02504, Rapid Shutdown BOP Notify Load Dispatcher RO Place SG/RX DEMAND in HAND, decrease load to 203 MWe. Attempt to maintain Axial Pwr Imbalance between 0 and -10% using the APSR's and/or boration. BOP Request Chemistry to monitor Condensate Polisher operation and prepare to sample RCS for an isotopic analysis of Iodine. During the load decrease: Transfer station electrical loads, align the MDFP to MFW. Direct an EO to start the Aux Boiler.

ES-301 Operator Actions _ Form ES-301-4 Scenario No.: 1 Event No.: 4 (cont) Page 7 of 9 Event

Description:

Steam leak initiated in CTMT which increases to line rupture causino maior overcoolina. Time Position Applicant's Actions or Behavior RO Maintain MUT level between 55" and 86". BOP Stop one condensate pump when flow is less than 7.0 MPPH if three pumps are running. At 675 MWE direct an EO to open MS 338 and MS 353. At ~600 MWE verify high load valves closed and direct EO to decrease low load valves per curve CC.7.10 of misc. curve book. When Condensate flow is less than 3.5 MPPH stop all but one running condensate pump. Prior to the first SG going on low level limits, place the Delta Tc controller in HAND at O. ALL Recognize increase in steam leak severity. SRO Implement DB-OP-02000, RPS, SFAS, SFRCS Trip or SG Tube Rupture. DB-OP-02000 IMMEDIATE ACTIONS (SECTION 3)

RESPONSE

RO Manually trip the reactor, verify power decreasing on the Intermediate Range. BOP Manually trip the turbine. RO If PZR level drops below 40", isolate letdown by closing MU-2B and verify all PZR heaters off. SRO Verify Immediate Actions. l l

 .. c ES-301                             Operator Actions                   Form ES-301-4 Scenario No.:         1              Event No.:   4 (cont)           Page 8 of 9 Event

Description:

Steam leak initiated in CTMT which increases to line rupture causina maior overcoolina. r Time Position Applicant's Actions or Behavior SUPPLEMENTARY ACTIONS (SECTION 4) RESPONSE ALL Check for control rods inserted. BOP Check for turbine trip. RO Check for NNI. power available. Check for ICS power available. Check for C1/D1 busses energized with no EDG's running. BOP Check for instrument air available. Check for secondary systems response. Establish one condensate pump operation. Check for SFRCS isolation trip. Verify normal RFR control of MFW to BOTH SGs. Establish one MFP in operation. RO Check for Makeup System operation. Transfer MU pump suction to the BWST, and press OFF for each switch. Set PZR level controller to 100 inches. Ensure MU flow rising if level is below setpoint. BOP Check for SFAS actuations. Check for SFRCS actuations. Check for adequate subcooling margin. Check for lack of heat transfer. Check for overcooling. Recognize overcooling has occurred. SRO Route to DB-OP-02000, Section 7,

                                  " Overcooling".

     ,ES-301                        Operator Actions                    Form ES-301-4 Scenario No.:    1              Event No.:   4 (cont)   .         Page 9 of 9 Event

Description:

Steam leak initiated in CTMT which increases to line ruoture causina maior overcoolina. Time Position Applicant's Actions or Behavior OVERCOOLING (SECTION 7) RESPONSE ERO Restore / maintain Pzr level at 80"-120". Isolate letdown if Pzr level decreases below 40". BOP Check for SFRCS actuation throughout overcooling cause determination. IF SFRCS trip is present, THEN:

a. Verify proper response per Table 1.

b. Route to proper step for the SFRCS trip present.

SRO Direct check for proper SFRCS for trips present as directed by step 7.14 RO Note both SG levels are not rising as per step 7.'.6 check.

SRO Route to step 7.23, Verify proper AFW to good OTSG, then route to step 7.29 RO Verify proper feeding of the non-isolated SG. BOP Maintain proper SG level in the available SG at 49" per Specific Rule 3 (55" after low pressure SFRCS actuates). ALL Check for overcooling. Crew recognizes overcooling stops when affected OTSG boils dry. TERMINATION CRITERIA OTSG #2 has boiled dry, crew making preparations to cooldown plant with one OTSG

e , ES-30,1 Scenario Events Form ES-301-3 Simulation Facility: Davis Besse Scenario No.: 2 Examiners: D_. McNeil Applicants: T. PHILLIPS (SRO) E. Plettner , D. HARTNETT (BOP) R, LAWBfliCI_IRO) Initial Conditions: flant Startun in Proaress with Turbine Load at_ u,g_ [dE (IC 41) Turnover: Power Increase to 35%. Your shift is recoverino from a ol.nnt_ transient that has left the plant at - 2 0 % r> owe r . Your shift is to_take its_nlant to 35 ) nower where onecific Turbine vibration readinas are to _be taken. Event Malf. Event Event No. No. Type

_ ,_

Description 1 R Plant Power Increase to 35% Power and lift off low level limits 2 SG-06 I Startup level instrument for #2 OTSG fails low 3 SW-01 C SW Pump #1 shaft seizure , 3 SG-01 C OTSG tube leak reciuiring plant shutdown 4 SG-01 M OTSG tube leak becomes a tube rupture , _

   *      (N)ormal,        (R)eactivity,      (I)nstrument,                               (C)omponent,               (M)ajor Chief Examiner-                            y/d      /

T Page 2 of 12 I. INTRODUCTION A. GENERAL DESCRIPTION This guide starts with a plant startup in progress at approximately 20% power with plans to increase power to 35%. After the plant is in full Automatic and just after both OTSGs have come off Low Level Limits, the Startup Level instrument for the #2 OTSG will fail to 0 inches which will cause an overfeed condition in the #2 OTSG. After the plant is stabilized the Service Water pump supplying the secondary loads will trip, requiring the crew to start the standby pump. Once the standby pump is started a OTSG tube leak will develop. This tube leak will become a tube rupture over time. u

1 1 ES-301 Operator Actions Form ES-301-4 Scenario No.: 2 Event No.: 1 Page 3 of 12 Event

Description:

_Elant Power Increase to 35% Power and lift off low level limits Time Position Applicant's Actions or Behavior SRO Holds brief.and reviews actions per DB-OP-06902, Power Operations. Notifies SOC in Cleveland that power increase has started to 35% power at 3MWE per minute. Directs reactor operator to increase power IAW DB-OP-06902, Power Operations. RO Raises setting on Unit Load Demand, sets rate of change. Monitors power increase to ensure correct equipment performance. BOP Monitors turbine, generator, matcheo AC and DC voltage regulator output as turbine load increases. .

ES-301 Operator Actions _ _ _ Form ES-301-4 Scenario No.: 2 Event No.: 2 Page 4 of 12 Event

Description:

Startuo level instrument for #2 OTSG fails low Time Position Applicsnt's Actions or Behavior ALL Diagnose a failure of #2 OTSG S/U level transmitter low: Ann 14-4-E ICS INPUT MISMATCH. Ann 12-4-B SG 2 LVL LO Increasing FW flow on FW Loop 2. SRO Direct ROs to place SP 7A. SP 6A and both FW loop demands in hand. BOP Place SP 7A, SP 6A and both FW Loop Demands in hand. SRO Route to DB-OP-02014, MSR/ICS Alarm Panel 14 Annunciators (Can route directly to DB-OP-02526, Steam Generator Overfill) ALL Recognize that an OTSG overfill condition has or had occurred SRO Route to DB-OP-02526, Steam Generator Overfill Verify that placing #2 MFW Startup Valve ,SP 7A, #2 MFW Regulating Valve, SP 6A and both FW loop demands in hand terminates overfill. SRO Route to DB-OP-06407, Non Nuclear Instrumentation System Operating Procedure is referred to prior to selecting good instrument. BOP Select good SG 2 Startup Level Instrument. Place #2 MFW Startup Valve ,SP 7A, #2 MFW Regulating Valve, SP 6A and both FW loop demands in automatic per DB-OP-06401, Integrated Control System Operating Procedure.

ES-301 Operator Actions Form ES-301-4 Scenario No.: 2 Event No.: __3 Page 5 of 12 Event

Description:

SW Pumn #1_ shaft seizure Time Position Applicant's Actions or Behavior ALL Recognize symptoms of loss of SW Pump 1. (Computer alarm P945, SW LOOP 1 HDR PRESS) RO Announces Loss of #1 SW pump. SRO Route to DB-OP-02511, Loss of Service Water Pumps / Systems LOSS OF SERVICE WATER PUMPS / SYSTEMS, DB-OP-02511 RESPONSE SRO Dispatch EO to investigate relay targets on tripped SW pump breaker. Verify CAC 1 in OFF Close SW 1366 BOP Verify CT 2955 open Verify a CCW Pump on CCW loop 2 Verify non-essential CCW loads on CCW Loop 2 as follows: Verify open CC 5096 - Supply Verify open CC 5098 - CTMT Bldg. Return Verify open CC 2649 - Aux Bldg Return. Monitor Generator Cold gas temp. If temp increases to 113 F, decrease Turb load. Dispatch EO to open SN valves for TPCW coolers Restore flow to SW Loop 1 by placing the # 3 Service Water Pump in service. SRO Direct dispatch of EO to perform Attachment 1, #3 Service Water Pump to SW Loop 1 Lineup RO/ BOP Start SW pump # 3 when correctly lir.ed up. l

ES-301 Operator Actions Form ES-301-4 P Scenario No.: 2 Event No.: 4 Page 6 of 12 Event

Description:

OTSG tube leak reauirina olant shutdown h Time Position Applicant's Actions or Behavior ALL Recognize symptoms of OTSG tube leak High activity on condenner off-gae radiation monitors, liigh activity on main steam line radiation monitor RE 609. SRO Route to DB-OP-02531, OTSG Tube Leak. Steam Generator Tube Leak - DB-OP-02531 RO Check presourizer level If PZR level decreases below 100 inches, trip the reactor. SRO Route to DB-OP-02000 "RPS, SFAS, SFRCS Trip or SG Tube Rupture." RO Isolate Letdown. Maximize RCS inventory. Verify PZR level control and MU-32 is open. Start second makeup pump. ALL Identify leaking SG as #1. RO/SRO Steam line rad, monitor RE-609. Dispatch Rad Con Tech, to survey Steam lines. Chemistry

ES-301 , , _ _ _ Operator Actions Form ES-301-4 Scenario No.: 2 Event No.: 5 Page 7 of 12 Event

Description:

OTSG tube leak becomes a tube ructure Time Position Applicant's Actions or Behavior RO Determine leak rate using Attachment 1, steps 1, 2, and 3. SRO Consult Tech. Spec, 3.A.6.2 for RCS leakage litaits and actions. Determine emergency classification (made at end of scenario). Initiate plant response activities,

a. Notify chemistry to perform Attachment 2 i

and report results to SS.

b. Notify Rad. Prot. personnel to perform Attachment 3 and report results to SS.

c. Direct an EO to perform Attachment 4.

ALL Recognize increase in leak rate.

a. Pressurizer level response.

b. Pressurizer pressure response,

c. OTSG level response.

SRO Route to DB-OP-02000, RPS, SFAS, SFRCS TRIP or SG Tube Rupture. DB-OP-02000 IMMEDIATE ACTIONS (SECTION 3)

RESPONSE

ALL Check for SGTR. SRO Route to Section 8. DB-OP-02000, SGTR RESPONSE (SECTION 8, NO TRIP)

ES-301 Operator Actions Form ES-301-4 Scenario No.: 2 Event No.: 5 (cont) Page 8 of 12 Event

Description:

OTSG tube leak becomes a tube ructure _ Time Position Applicant's Actions or Behavior RO If Pressurizer Level decreases below 100 inches, trip reactor and return to section 3. Perform the following for RCS inventory controls

a. Verify Letdown is isolated,

b. Lock MU 3971 and MU 6405 in the BWST position.

c. Start the second Makeup Pump.

d. Open MU 6421.

e. Control MU 6419 and MU 32 to maintain PZR level.

Place SG/Rx Demand in hand and insert control rods as rapidly as possible without causing any cross limits or reactor trip. ALL Perform or continue performance of Attachments 2, 3, and 4 of DB-OP-02531, SG Tube Leak. Identify the leaking SG using MS line radiation monitors SRO Direct EO to startup the Aux. Boiler,

a. Transfer Gland Steam.

b. Transfer Aux. Steam.

ALL Lineup and initiate piggyback operation.

a. Start the non-running CCW pump.

b. Start HPI pumps,

c. Open HPI injection valves HP 2A, 2B, 2C, 2D.

d. Start LPI pumps.

e. Open DH 63 and 64.

RO Transfer station electrical loads.

ES-301 Operator Actions _ Form ES-301-4 Scenario No. 2 Event No.: 5 (cont) Page 9 of 12 Event

Description:

OTSG tube lq3k hscomes a tube rupture Time Position Applicant's Actions or Behavior When both SG 1evels are back on Low Level Limita, perform the following: RO Rcduce SG/Rx demand to zero. BOP Place SG1 Feedwater Demand and SG2 Feedwater Demand in HAND and reduce demands to zero. Place TBV's in HAND and transfer steam load from the Turbine. RO If TBVs are fully open place Rx Demand H/A station in HAND und reduce power RO/ BOP When generator load is < 50 MWe: Trip the reactor and turbine with TBVs in hand. Establish auto steam header control via TBVs SRO Route to Section 3 step 2. DB-OP-02000 IMMEDIATE ACTIONS RO Manually trip reactor. Verify power decreasing on Intermediate Rance. BOP Manually trip turbine. RO Isolate letdown by closing MU 2B (MU3 alternate), when PZR level drops below 40", and verify PZR heaters are off. SRO Verify Immediate Actions.

i ES-301 Operator Actions Form ES-301-4 ; i Scenario No.: 2 Event No.: 5 (cont) Page 10 of 12 Event Doncription: OTSG tube leak becomes a tube ructure j Time Position Applicant's Actions or Behavior RO SUPPLEMENTARY ACTIONS (SECTION 4) RESPONSE o Check for control roda inserted. BOP Check for turbine trip. RO/ BOP Check for NNI & ICS power available. Check for C1/D1 bussea energized with no EDG's running. Check for instrument air available. BOP Check for accondary ayatema response,

a. Establish one condensato pump operation,

b. Check for SFRCS isolation trip.

c. Verify normal RPR control of MFW to BOTH SGa.

d. Establish one MFP in operation.

RO Check for Makeup System operation,

a. Transfer BOTH MU pump suctions to the BWST, but do not presa OFF for each awitch,

b. Start accond MU pump.

c. Set PZR level controller to 100 inchen,

d. Ensure MU flow rising if level la below setpoint.

RO/ BOP Check for SFAS actuations. BOP Check for SFRCS actuations. RO/DOP Check for adequate subcooling margin. BOP Check for lack of heat transfer. Check for overcooling.

o ES-301 Operator Actions Form ES-301-4 Scenario No.: 2 Event No.: 5 (cont) Page 11 of 12 Event

Description:

OTSG tube leak becomes a tube runture Time Position Applicant's Actions or Behavior SRO Route to Section 8, Step 7 for SGTR. DB-OP-02000, SGTR RESPONSE RO Piggyback MU/HPI if not already done.

a. Verify Makeup Pump suctions are LOCKED onto the BWST.

b. Start non-running CCW pump.

c. Start HPI pumps 1 and 2

d. Open HPI Injection Valves HP 2A, 2B, 2C, 2D.

e. Start LPI pumps 1 and 2

f. Open DH 63 and 64 .

SRO/ BOP Determine RCP availability. ALL Verify proper SG levels, using Specific Rules. Begin cooldown and depressurization with RCPs running. RO Depressurize the RCS to near minimum SCM and refill the pressurizer.

a. Turn off all PZR heaters,

b. If RCS Pressure is being manually controlled, then block SFAS.

c. Use PZR Spray to reduce RCS pressure to maintain near minimum adequate subcooling margin,

d. Allow HPI and MU to recover PZR level and maintain PZR level 80" to 120".

ALL Begin cooldown and depressurization to Th of 500'F and 1000 psig at 100*F/hr and maximum spray flow, Use TBVs on both sides. If SFRCS was actuated, use AVVs on both sides.

e a ES-301 _ , , , Operator Actions Form ES-301-4 Scenario No.: 2 Event No.: 5 (cont) Page 12 of 12 Event

Description:

OTSG tube leak becomes a tube rupture Time Position Applicant's Actions or Behavior ALL Maintain close to minimum subcooling margin until RCS reaches 1000 psig then maintain RCS

                                                            @ 980-1020 psig.

BOP Block SFRCS when permitted. If required, increase steaming rate of ruptured SG to attempt to keep the level below 225". IF level exceeds 240 inches, stop steaming and isolate the affected SG. SRO SS-A Classify the event per RA-EP-01500. CONDITIONS AT TERMINATION Plant in a controlled cool.down and depressurization. Tave moving toward 500*F at approx. 100*F/ hour. RCS pressure decreasing to between 980 and

              ,                                             1020 psig.

Ruptured SG isolated and level > 240 inches, or still steaming and level < 225 inches. Temperature being controlled with TBVs or AVVs.

                                                                                                            < --                             y'
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                                    & r                                                         -v  --e-

, Y, i ES-301 Scenario Events Form ES-301-3 l

    ! Simulation Facility:       Davis Besse         Scenario No.:            3 Examiners:      D. McNeil                      Applicants:    R. LAWRENCE (SRO)

E. Plettner D. HARTNETT (RO) L. PHILLIPS (BOP) Initial Conditions: Plant is at 50% Power followina recairs to 2 Main Feed Pumo. No other eauioment is oos (IC 30) Ivrnover: Plant was at 50% unwer for the cast week for #2 MPP repairs.

      #2 Main Feed Pumo was returned to service last shift and is now in full aut oma tic . The load disoatcher has reauested the olant be returned to full power.      There is no eauipment oos. There are no olanned-nurveillance tests. PJr level channel 1 is beino calibrated.

Event Malf. Event Event No. No. Type

Description 1 R Increase in plant power following repairs to Main Feed Pump Turbine bearing.

2 MFW-11 C Restarted Main Feed Pump bearing fails and MFW-01 requires a manual trip 3 PZR-10 I Selected pressurizer level instrument fails high 4 RCS-02 M Small RCS leak develops which becomes a LOCA

 ,,                                causing loss of SCM
  *       (N)ormal,       (R)eactivity,      (I)nstrument,      (C)omponent,     (M)ajor Chief Examiner:   y

o , I. INTRODUCTION A. GENERAL DESCRIPTION This scenario starts with the plant commencing a load increase from 50% Power. The # 2 Main Feed Pump will have a bearing failure which will require a manual trip of the feed pump and a plant runback. After the plant runs back the selected Pressurizer Level instrument-will fail high. Once the crew has responded to the Pzr level instrument failure a small RCS leak will occur which will degrade to a LOCA which will resu)t in a loss of Subcooling Margin

I ES-301 Operator Actions Form ES-301-4 Scenario No.: 3 Event No.: 1 Page 3 of 10 Event Description Increase in nlant power followina reoairs to main feed _ pump turbine bearina. Time Position Applicant's Actions or Behavior SRO Helds brief and reviews actions per JB-OP-06902, Power Operations. Notifies SOC in Cleveland that power increase has started at 3MWE per minute. Directs reactor operator to increase power IAW DB-OP-06902, Power Operations. RO Raises setting on Unit Load Demand, sets rate of change. Monitors power increase to ensure correct equipment performance. BOP Mcnitors turbine, generator, matches AC and DC voltage regulator output as turbine load increases.

ES-301' __ Operator Actions Form ES-301-4 Scenario No.: 3 Event No.: 2 . Page 4 of 10 Event

Description:

Restarted main feed cumo bearina fails and recuires a manual trio. Time Position Applicant's Actions or Behavior ALL Recognize high vibation alarm 10-3-E. SRO Refer to DB-OP-02010. Directs to have an EO check Local Vibration Panel and to check pump locally. ALL Verify proper plant runback after pump trips t i

i l ES-301 Operator Actions Form ES-301-4 Scenario No.: 3_. Event No.: 3 Page 5 of 10 Event

Description:

Selected oressurizer level instrument fails hiah Time Position Applicant's Actions or Behavior ALL Recognize PZR level failed high and announce alarm 4-3-E PZR lvl High. RO Places MU 32 in HAND restore MU flow SRO Routes to DB-OP-02004 and then DB-OP-02513 PZR LVL FAILED HIGH DB-OP-02513, PRESSURIZER SYSTEM ABNORMAL OPERATIONS RO Compare other PZR instruments and select a good instrument Place MU 32 in AUTO SRO Consults Tech Specs. (Failed instrument is tech spec related.) 2 . - . _ _ _ _ _ _ . _ . . _ . _. _ _

ES-301 Operator Actions Form ES-301-4 Scenario No.: 3 Event No.: 4 Page 6 of 10 Event

Description:

Small RCS leak develons which becomes a LOCA causina loss of SCM. Time Position Applicant's Actions or_ Behavior ALL Recognize the symptoms of a small RCS leak

                                                                     -RCS   NU Flow increasing
                                                                     -CTMT Sump level increasing CTMT Radiation levels increasing SRO                        Route to DB-OP-02522, Small RCS leaksDB-OP-02522, SMALL RCS LEAKS RESPONSE Monitor Pressurizer level, if less than 100 inches, then perform the following:

RO Trip the Reactor. SRO Route to DB-OP-02000, RPS, SFAS, SFRCS Trip or SG Tube Rupture RO Verify Pressurizer level is being maintained. Monitor Makeup Pump discharge pressure Monitor Makeup Tank level, attempt to maintain the Makeup Tank level between 55" and 86". Letdown may be isolated if desired or directed by SS/SS-A. ALL Locate and control the leak area as follows: Observe contrcl room indications. Contact Rad Con supervisor to perform appropriate Rad surveys and control affected area access. Announce the evacuation of potentially hazardous leak areas. Walk down accessible portions of RCS connected systems. Evaluate recent plant conditions and the need to disable CTMT Normal Sump Pumps.

ES-301 Operator Actions Form ES-301-4 Scenario No.: 3 Event No.: 4 (cont) Page 7 of 10 Event

Description:

Small RCS leak develons which becomes a LOCA causina loss of SCM. l Time Position Applicant's Actions or Behavior ALL Attempt to isolate the source of the leak by-performing Attachment 1 of DB-OP-02522 Determine RCS leak rate. SRO Direct a Rapid Shutdown. ALL Commence a Rapid plant shutdown in accordance with DB-OP-02504, Rapid Shutdown.ALLDB-OP-02504, " Rapid Shutdown" RESPONSE BOP Notify Load Dispatcher ( RO Place SG/RX DEMAND in HAND. , Decrease load to 203 MWe. 1 Attempt to maintain Axial Pwr Imbalance between 0 and -10% using the APSR's and/or boration. SRO Request Chemistry monitor Condensate Polisher operation and prepare to sample RCS for an isotopic analysis of Iodine. During the load decrease: 90 Transfer station electrical loads. BOP Align the MDFP to MFW. Direct an EO to start the Aux Boiler. RO Maintain MUT level between 55" and 86". BOP Stop one condensate pump when flow is less l l than 7.0 MPPH if three pumps are running. At 675 MWE direct an EO to open MS 338 and MS 353. l l l

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ES-301 Operator Actions Form ES-301-4 , Scenario No.: 3 Event No.: 4 (cont) Page 8 of 10 Event

Description:

Small RCS leak develoos which becomes a LOCA cA%CiDS loss of SCM. . Time Position Applicant's Actions or Behavior BOP At ~600 MWE verify high load valves closed and direct EO to decrease low load valves per curve CC.7.10 of misc. curve book. When Condensate flow is less than 3.5 MPPH stop all but one running condensate pump. Prior to the first SG going on low level limits, place the Delta Tc controller in HAND at O. ALL Recognize increase in RCS leak severity. SRO Implement DB-OP-02000, RPS, SFAS, SFRCS Trip or SG Tube Rupture.G. DB-OP-02000 IMMEDIATE ACTIONS (SECTION 3)

RESPONSE

l RO Manually trip the reactor. Verify power decreasing on the Intermediate Range. BOP Manually trip the turbine. RO If PZR level drops below 40", isolate letdown l by closing MU-2B and verify all PZR heaters off. SRO Verify Immediate Actions. SUPPLEMENTARY ACTIONS (SECTION 4) RESPONSE ALL Check for control rods inserted. l BOP Check for turbine trip, i l L l l 1

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ES-301 Operator Actions Form ES-301-4 Scenario No.: 3 Event No.: 4 (cont) Page 9 of 10 Event

Description:

      , loss of SCM.       Small RCS leak develoos which becomes a LOCA causina Time     Position                         Applicant's Actions or Behavior RO/ BOP    Check for NNI power available.

Check for ICS power available. Check for C1/D1 busses energized with no EDG's running. Check for instrument air available. BOP Check for secondary systems response. Establish one condensate pump operation. Check for SFRCS isolation trip. Verify normal RFR control of MFW to BOTH SGs. Establish one MFP in operation. RO Check for Makeup System operation. Transfer BOTH MU pump suction- to the BWST, and press OFF for each switch. Start second MU pump. Set PZR level controller to 100 inches. Ensure MU flow rising if level is below setpoint. RO/SRO Check for SFAS actuations. RCS 1650 PSIG Trip Verify proper SFAS Incident Level'1 and 2 actuation using Table 2. Verify letdown isolated. RO Attempt to close RC11, PORV Block Valve. Close RC10, PZR Spray Block Valve. When minimum SCM is lost then trip all RCPs. Verify HPI System is operating properly using Specific Rules 1 and 2. BOP Check for SFRCS actuations, verify proper SFRCS Actuation. Check for adequate subcooling margin. Recognize loss of SCM SRO Route to DB-OP-02000, Section 5, Inadequate SCM.

ES-301 Operator Actions Form ES-301-4 i Scenario No.: 3 Event No.: 4 (cont) Page 10 of 10 Event

Description:

Small RCS leak develoos which becomes a LOCA causina _1000 of SCM. _ Time Position Applicant's Actions or Behavior LACK OF ADEQUATE SCM RESPONSE RO Verify all RCPs tripped. Control MU/HPI per Specific Rules 1 and 2. BOP Re-verify SFRCS response per Table 1. Re-verify AFP status and proper OTSG level contrcl at 124" per Specific Rules 1 and 3. Check for overcooling. RO Isolate possible leaks. PORV/PORV Block Letdown Spray / Spray Block PZR Sample lines Loop high point vents Cr3ck for Inadequate Core Cooling, r'. neck for adequate SCM. Recognize that Subcooling Margin is restored or being restored. Throttle makeup HPI to maintain SCM. Restore forced flow (restart RCPs). SRO Route to step 5.16 to restore forced flow TERMINATION CRITERIA SRO Start directing crew to restore RCPs _ _ _ _ _ _ _ . _ _ _}}

ML20211B556

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