Latest revision as of 22:28, 1 March 2020

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Final Operating Exam (Sections a, B, and C) (Folder 3)
	ML12299A280
Person / Time
Site:	Beaver Valley
Issue date:	08/03/2012
From:	Rudolph W; FirstEnergy Nuclear Operating Co
To:	David Silk; Operations Branch I
	Jackson D
Shared Package
ML12136A033	List: ML12142A240; ML12263A060; ML12298A500; ML12299A089; ML12299A110; ML12299A182; ML12299A202; ML12299A226; ML12299A229; ML12299A276; ML12299A280; ML12307A237; ML12314A266;
References
	2AD-007, nxp, TAC U01850
	Download: ML12299A280 (276)
	v • d • e

RTL#A5.640U 1I2-ADM-1301.F04 Page 1 of9 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE (JPM)

TRAINING MATERIAL TITLE: Perfonn An Estimated Critical Position Calculation TRAINING MATERIAL NUMBER: 2AD-007 PROGRAM TITLE: Licensed Operator Training COMPUTER CODE: 2AD-007 REVISION NUMBER: 2 TECHNICAL

REFERENCES:

20M-50A.F, "Perfonning An Estimated Critical Position Calculation", Rev. 7 BV-2 Curve Book, Cycle 16 INSTRUCTIONAL SETTING: Classroom APPROXIMATE DURATION: 35 Minutes PREPARED BY: R. J. Brooks Date PEER REVIEW BY:

Date APPROVED FOR USE:

Training Supervisor or Designee Date

RTL#A5.640U 1I2-ADM-130 l.F04 Page 2 of7 Revision 1 TRAINING MATERIAL CHANGE FORM Affected Training Materials: 2AD-007 Type of Change:

[gJ Changes Requiring Learning Objective Related Change? New Rev. # 2 Revision DYes [gJ No D Changes Not The Change Does Not Impact Learning Existing Rev. # 1 Requiring Revision Objectives or Material Quality.

New Change #

List/Description of Change( s):

Updated content for Cycle 16 data.

Reason for Change (s):

Maintain JPM current APPROVALS:

NOTE: Additions, deletions or R. J. Brooks changes to training materials Prepared by Date must be reviewed for their possible impact to the Training Qualification Matrix. See Incumbent Impact Review,

. Training Superintendent/Supervisor/Peer Date NOBP-TR-II04. i

("Changes Not Requiring Changes" only)

RTL#A5.640U 1I2-ADM-1301.F04 Page 3 of9 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-007 JPM TITLE: Perfonn An Estimated Critical Position Calculation JPM REVISION: 2 KIA

REFERENCE:

2.1.23 (4.3/4.4) TASK ID: 0011-003-01-013 JPM APPLICATION: r8J REQUALIFICATION r8J INITIAL EXAM 0 TRAINING o FAULTED JPM ~ ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

~ Perfonn 0 Plant Site 0 Annual Requal Exam o BVT 0 Simulate 0 Simulator 0 Initial Exam o NRC r8J Classroom 0 OJT/TPE 0 Other:

0 Training 0 Other:

EVALUATION RESULTS Perfonner Name: Perforrner SSN:

Time 0 Yes Allotted 35 Minutes Actual minutes Critical: ~ No Time: Time:

JPM RESULTS:

0 SAT 0 UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

RTL#A5.640U 112-ADM-1301.F04 Page 4 of9 Revision 1 OPERA TIONS JOB PERFORMANCE MEASURE EVALUATOR ])IRECTION SHEET TASK STANDARD: Boron concentration for startup calculated within the specified tolerance.

RECOMMENDED Classroom STARTING LOCATION:

])IRECTIONS: You are to perform an Estimated Critical Position Calculation.

INITIAL CONDITIONS:

A plant startup is being performed exactly 5 days after a reactor trip from 100% power.

Prior to the trip, the plant was at 100% with All Rods Out for 3 months.

An RCS Boron sample was taken at 100% power just prior to the Reactor trip. It indicated that the RCS Boron concentration was 826 ppm.

Current Core bumup is lO,OOO MWD/MTU.

The plant computer is NOT available.

INITIATING CUE: The Shift Manager directs you to determine the boron concentration for startup by perfOlming 20M-50A.P, "Performing An Estimated Critical Position Calculation", steps IV. A through IV.C.l.k. Control rod position Expected at Criticality is Bank D at 100 steps.

Reactor Engineering was consulted regarding B- 10 Correction for Criticality. They report that the B- 1O correction Factor for criticality (Data Sheet 1 block VII) is 0.926.

REFERENCES:

20M-50AP, "Performing An Estimated Critical Position Calculation",

Rev. 7 BV-2 Curve Book, curves CB-I2, 21, 22, 23, 24B, and 29 TOOLS: None HANDOUT: 20M-50AP BV-2 Cycle 16 Curve Book

RTL#A5.640U 112-ADM-130 1.F04 Page 5 of9 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GWEN TO CANDIDATE

DRead:

DIRECTIONS: You are to perfonn an Estimated Critical Position Calculation.

INITIAL CONDITIONS:

A plant startup is being perfonned exactly 5 days after a reactor trip from 100% power.

Prior to the trip, the plant was at 100% with All Rods Out for 3 months.

An RCS Boron sample was taken at 100% power just prior to the Reactor trip. It indicated that the RCS Boron concentration was 826 ppm.

Current Core bumup is 10,000 MWD/MTU.

The plant computer is NOT available.

INITIATING CUE: The Shift Manager directs you to detennine the boron concentration for startup by perfOlming 20M-SO.4.F, "Perfonning An Estimated Critical Position Calculation", steps IV. A through IV.C.l.k. Control rod position Expected at Criticality is Bank D at 100 steps.

Reactor Engine<:::ring was consulted regarding B- ID Correction for Criticality. They report that the WID correction Factor for criticality (Data Sheet 1 block VII) is 0.926.

o At this time, ask the evaluator any questions you have on this lPM.

o When satisfied that you understand the assigned task, announce "I am now beginning the lPM".

Simulate perfonnance or perfonn as directed the required task.

o Point to any indicator or component you V(~rify or check and announce your observations.

After detennining the Task has been met announce" I have completed the lPM".

o Then hand this sheet to the evaluator.

RTL#A5.640U 112-ADM-130 1.F04 Page 6 of9 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-007 JPM TITLE: Perform An Estimated Critical Position Calculation JPM REVISION: 2 UNSAT)~ I SIU I STEP STANDARD

( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR DEVI~LOPERNALIDATION NOTES:

When updating this JPM for the current plant cycle, use care to choose parameters that will not require interpolation.

START TIME: ,_ _ _ _ _ __

1. Input Critical Data 1.1 Inputs Critical Data Part A I Data Sheet 1) Prior to Shutdown.

(Part A I Prior to Shutdown)

Daterrime Date/Time = 5 days ago Boron Conc. Boron Cone. 826 ppm Power Power 100%

Burnup Burnup 10)000 (MWDIMTU)

Xenon Xenon = 100% (CB-12)

Samarium Samarium = 100% (CB-22)

Control Rod Position Control Rod Position = ARO at 225 steps COMMENTS:

RTL#A5.640U 1I2-ADM-1301.F04 Page 7 af9 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-007 JPM TITLE: Perform An Estimated Critical Position Calculation JPM REVISION: 2 STEP STANDARD

( "c" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> SIU

2. Input Critical Data 2.1 Inputs Critical Data Part A II Data Sheet 1, Expected at Criticality.

(Part A II Expected at Criticality)

Date/Time = NOW DatelTime Burnup = 10,000 (MWD/MTU)

Bumup Xenon = 0% (CB-23)

Xenon Samarium = 137.5% (CB-22)

Samarium Control Rod Position = Banks A & B @ 225 steps Control Rod Position Bank C @ 225 steps Bank D @ 100 steps COMMENTS:

3. Determine Effective boron 3.1 Determines the Effective Boron Concentration Concentration Part A III, IV, & V)

Data Sheet 1, (Part A III, IV, & V)

Part III, Boron Cone. Part III, Boron Cone. 826 ppm Part IV, B-IO Corr factor Part IV, B-I0 Correction Factor = 0.918 (CB-29)

Part V, Effective Boron Part V Effective Boron Conc. = 826 ppm X 0.918 Cone. 758.26 ppm COMMENTS:

I i

RTL#A5.640U 112-ADM-1301.F04 Page 8 of9 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-007 JPM TITLE: Perfonn An Estimated Critical Position Calculation JPM REVISION: 2 STEP STANDARD

( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UN8AT)=> 81U

4. Calculate Reactivity Balance 4.1 Calculates Part B, Item 5.

(Data Sheet 1, Part B)

PartB.l

Power Defect - 0,- 2300 = - 2300 pcm (CB-21)

Part B.2

Control Rods 963 0 = + 963 pcm (CB-24B)

Part B.3

Xenon = 0 2699 = - 2699 pem (CB-23)

Part B.4

Samarium 862 627 = + 235 pem (CB-22)

Part B.5

Reactivity Change = - 3801 pcm COMMENTS:

5. Calculate Boron Concentration 5.1 Calculates Part C, Line 1, Item V.

for Startup (Data Sheet 1, Part C)

Part C.I

Reactivity Change = - 3801 pem (from B.5)

Part c.n

Diffierential Boron Worth = - 7.47 pem/ppm (CB-20)

Part c.m

Boron Change = + 509 ppm Part C.IV

Eff Boron Cone. at Shutdown 758.26 ppm Part C.V

EffBoron Cone. For Startup 1267.26 ppm COMMENTS:

RTL#A5.640U 1/2-ADM-130 l.F04 Page 9 of9 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-007 JPM TITLE: Perfonn An Estimated Critical Position Calculation JPM REVISION: 2 STEP STANDARD

( "C" Denotes CRITICAL STEP) Indicate "s" FOR SAT or "U" FOR UNSAT)=>

6C. Calculate Boron Concentration 6.1C. Calculates Part C, Line 2, Item V.

for Startup (Data Sheet 1, Part C)

Part C.l

Reactivity Change = - 3801 pcm (from B.5)

Part c.n

Differential Boron Worth = - 7.08 pcm/ppm (CB-20)

Part C.1lI

Boron Change = + 537 ppm Part C.IV

Eff. Boron Cone. at Shutdown 758.26 ppm (from Part C.V A.V)

Part C.VI

Eff. Boron Cone. For Startup 1295.26 ppm Part C.VII (+1- 50 ppm)

Part C.VIII

Eff. Boron Cone. For Startup = 1295.26 (from C.V)

B-I0 Correction Factor for Criticality = 0.926

Boron Concentration for Startup 1398.76 COMMENTS:

EVALUATOR NOTE:

Grader Discretion Required.

TERMINATING CUE:

When the Candidate completes the calculation, the evaluation for this JPM is complete.

STOP TIME:

RTL#A5.640U 112-ADM-130 1.F04 Page 1 of9 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE (JPM)

TRAINING MATERIAL TITLE: PerfonTI a Quadrant Power Tilt Ratio Calculation TRAINING MATERIAL NUMBER: 2CR-003 PROGRAM TITLE: Licensed Operator Training COMPUTER CODE: 2CR-003 REVISION NUMBER: 5 TECHNICAL

REFERENCES:

20ST-2.4A, Quadrant Power Tilt Ratio Manual Calculation", Rev. 8 INSTRUCTIONAL SETTING: Simulator/Classroom APPROXIMATE DURATION: 15 minutes PREPARED BY: R. J. Brooks Date PEER REVIEW BY:

Date APPROVED FOR USE:

Training Supervisor or Designee Date

RTL#A5.640U 112-ADM-130 1.F04 Page 2 of9 Revision 1 TRAINING MATERIAL CHANGE FORM Affected Training Materials: 2CR-003 Type of Change:

[8J Changes Requiring Learning Objective Related Change? New Rev. # 5 Revision DYes ~No D Changes Not The Change Does Not Impact Learning Existing Rev. # 4 Requiring Revision Objectives or Material Quality.

New Change #

ListiDescription of Change(s):

Updated JPM to reflect most current JPM format Revised JPM to reflect most current plant procedure.

Added pictures ofNI drawers to allow for classroom performance of this JPM.

Reason for Change (s):

JPM Enhancement.

APPROVALS:

NOTE: Additions, deletions or R. J. Brooks changes to training materials Prepared by Date

must be reviewed for their possible impact to the Training Qualification Matrix. See Incumbent Training SuperintendentiSupervisorlPeer Date

("Changes Not Requiring Revision" only)

RTL#A5.640U l!2-ADM-130 1.F04 Page 3 of9 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-003 JPM TITLE: Perform a Quadrant Power Tilt Ratio Calculation JPM REVISION: 5 KIA

REFERENCE:

015Al.04 3.5/3.7 TASK ID: 0021-005-06-013 015A4.02 3.9/3.9 2.1.37 4.3/4.6 JPM APPLICATION: I2?J REQUALIFICATION [8j IN ITIAL EXAM D TRAINING D FAULTEDJPM D ADMINISTRATIVE JPM EV ALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

D Perform D Plant Site D Annual Requal Exrun D BVT D Simulate D Simulator D Initial Exrun D NRC D Classroom D OJT/TPE D Other:

D Training D Other:

EVALUAnON RESULTS Performer Name: Performer SSN:

Time D Yes Allotted 15 minutes Actual minutes Critical: I2?J No Time: Time:

JPM RESULTS:

D SAT D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Nrune/SSN:

Nrune/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

RTL#A5.640U 112-ADM-130 1.F04 Page 4 of9 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET TASK STANDARD: The QPTR calculation is completed within the allowable tolerances and compared to Technical Specification limits, as specified in the OST Acceptanct~ Criteria.

RECOMMENDED Simulator/Classroom STARTING LOCATION:

DIRECTIONS: You are to perform a Quadrant Power Tilt Ratio (QPTR) Manual Calculation.

INITIAL CONDITIONS: Mode 1, The plant computers are unavailable.

INITIATING CUE: The Unit Supervisor directs you to perform a QPTR manual calculation and report the results in accordance with 20ST-2.4A, "Quadrant Power Tilt Ratio Manual Calculation".

REFERENCES:

20ST-2.4A, "Quadrant Power Tilt Ratio Manual Calculation", Rev. 8.

TOOLS: Calculator, NI Cabinet Pictures (if performed in the Classroom).

HANDOUT: 10ST-2.4A, "Quadrant Power Tilt Ratio Manual Calculation", Rev. 8, place kept up to Step VILB.1, including normalization values provided on Data Sheet 1.

RTL#A5.640U 112-ADM-1301.F04 Page 5 of9 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE CANDIDATE IHRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

DRead:

TASK: You are to perfonn a Quadrant Power Tilt Ratio (QPTR) Manual Calculation.

INITIAL CONDITIONS: Mode 1, The plant computers are unavailable.

INITIATING CUE: The Unit Supervisor directs you to perfonn a QPTR manual calculation and report the results in accordance with 20ST-2.4A, "Quadrant Pow(Jr Tilt Ratio Manual Calculation".

D At this time, ask the evaluator any questions you have on this JPM.

D When satisfied that you understand the assigned task, announce "I am now beginning the JPM".

Simulate perfonnance or perfonn as directed the required task.

D Point to any indicator or component you verify or check and announce your observations.

After detennining the Task has been met announce" I have completed the JPM It

D Then hand this sheet to the evaluator.

RTL#A5.640U 112-ADM-1301.F04 Page 6 of9 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-003 JPM TITLE: Perform a Quadrant Power Tilt Ratio Calculation JPM REVISION: 5 STEP STANDARD

( "c" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> [ SIU [

Il'" START TIME:

EVALUATOR NOTE: This JPM is designed to use an accompanying Data Sheet Set and can be performed either in the Simulator or Classroom setting. For any of the following data cues, refer to the accompanying Data Sheet Set. This JPM can also be performed in a classroom using NI pictures.

EVALUATOR CUE: Provide a copy of20ST-2.4A completed up to step VII.B.l. This includes normalization factors filled out on Data Sheet 1.

1. Review 20ST-2.4A, "QPTR 1.1 Reviews 20ST-2.4A, "QPTR Manual Calculation" Manual Calculation" procedure.

procedure.

COMMENTS:

EVAL UATOR CUE: If asked, inform the candidate that no uncertainty exists and the use of a DVM is NOT required.

J EVALUATOR NOTE: Acceptable detector current tolerance is +/-3 minor scale subdivisions of actual indication.

2.C Record detector current values 2.1C Records detector currents for each of the power range for each of the power range detectors (either from the NI cabinets or picture detectors in the "Current provided) in the Data Sheet 1 Current (Uncor.)

(Uncor.) column of Data Sheet column.

1, using either of the following methods: COMMENTS:

a. Detector current meters located on power range drawers.

b. Test jacks located below the meter faces using a DVM, in accordance with Attachment A.

RTL#A5.640U 112-ADM-130 1.F04 Page 7 of9 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-003 JPM TITLE: Perforrn a Quadrant Power Tilt Ratio Calculation JPM REVISION: 5 STEP STANDARD

( "e" Denotes CRITICAL STEP) (Indicate "s" FOR SAT or "u" FOR UNSAT)~ StU 3.C Multiply each of the detector 3.1C Determines corrected current by multiplying each current readings by its dete(:tors Current (Uncor.) value by the associated associated normalization factor nomLalization factor and records the result in the AND recored the result in the appropriate Data Sheet 1 Current (Cor.) column.

"Current (Cor)" colums of Data Sheet 1. COMMENTS:

4.C Determines the following for 4.1C Adds the values in the Current (Cor.) column AND the Upper Detectors on Data records the results in the space marked "SUM".

Sheet I:

4.2C Divides the value in the "SUM" space by 4(3) AND

a. Add the values in the records the result in the space marked "AVG".

Current (Cor.) column AND Record the results in 4.3C Determines the Tilt Ratio for each ofthe upper the space marked "SUM". detectors by dividing each value in the "Current(Cor.)"

b. Divide the value in the colums by the value of the "AVG" AND Record the "SUM" space by 4(3) results in the "Tilt Ratio" column.

AND Record the result in the space marked "AVG". COMMENTS:

c. Determine the Tilt Ratio for each of the upper detectors by dividing each value in the "Current(Cor.)" colums by the value of the "AVG" AND Record the results in the "Tilt Ratio" column.

RTL#AS.640U 112-ADM-130 1.F04 Page 8 of9 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-003 JPM TITLE: Perfonn a Quadrant Power Tilt Ratio Calculation JPM REVISION: S STEP STANDARD

( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "V" FOR VNSAT)=> 8/U S.C Detennines the following for S.lC Adds the values in the Current (Cor.) column AND the Lower Detectors on Data records the results in the space marked "SUM".

Sheet 1:

S.2C Divides the value in the "SUM" space by 4(3) AND

a. Add the values in the records the result in the space marked "AVO".

Current (Cor.) column AND Record the results in S.3C Detennines the Tilt Ratio for each of the upper the space marked "SUM". detectors by dividing each value in the "Current(Cor.)"

b. Divide the value in the colums by the value of the "AVO" AND Record the "SUM" space by 4(3) results in the "Tilt Ratio" column.

AND Record the result in the space marked "AVO". COMMENTS:

c. Detennine the Tilt Ratio for each of the upper detectors by dividing each value in the "Current(Cor.)" colums by the value of the "AVO" AND Record the results in the "Tilt Ratio" column..

EVALUATOR CUE: Inform the candidate that no uncertainty exists and a computer tilt map is NOT required.

6. If uncertainty exists with 6.1 This step is NIA based on cue provided.

calculated values, request the Tilt Review Map from the IPC COMMENTS:

AND Compare the map with the results of the OST.

RTL#A5.640U 112-ADM-1301.F04 Page 9 0[9 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-003 JPM TITLE: Perforrn a Quadrant Power Tilt Ratio Calculation JPM REVISION: 5 STEP STANDARD

( "c" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=>

7.C Candidate determines if QPTR 7.1 C Compares test data with Acceptance Criteria to is within specifications. determine if QPTR exceeds 1.02.

EVALUATOR NOTE: After candidate determines tilt is either within OR out of specification, compare candidates data sheet with the Answer Key to ensure calculations are within the specified tolerances: +/-3 minor scale subdivisions AND calculation method is correct.

COMMENTS:

STOP TIME:

RTL#A5.640U 112-ADM-130 1.F04 Page lof6 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE (JPM)

TRAINING MATERIAL TITLE: Prepare a Clearance Tagout [2QSS-P21B] Quench Spray Pump 21B TRAINING MATERIAL NUMBER: =2A..;;;;.D=--.-::..0=-31=--_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

PROGRAM TITLE: Licensed Op,erator Training COMPUTER CODE: 2AD-031 REVISION NUMBER:

° TECHNICAL

REFERENCES:

NOBP-OP-! 001, Manual Clearance Generation, Rev. 3 NOP-OP-I 001, Clearance/Tagging Program, Rev. 18 INSTRUCTIONAL SETTING: Classroom APPROXIMATE DURATION: 25 Minutes PREPARED BY: R. J. Brooks Date PEER REVIEW BY:

Date APPROVED FOR USE:

Training Supervisor or Designee Date

RTL#A5.640U 1I2-ADM-1301.F04 Page 2 of6 Revision 1 TRAINING MATERIAL CHANGE FORM I Affected Training Materials: JPM 2AD-031 Type of Change: i

, D Changes Requiring I Learning Objective Related Change? New Rev. #0 Revision

DYes DNo D Changes Not The Change Does Not Impact Learning Existing Rev. # N/A Requiring Revision Objectives or Material Quality.

New Change #

List/Description of Change( s):

Updated for Updated for OM Fig 13-2 Rev 20 Reason for Change (s):

APPROVALS:

R. J. Brooks NOTE: Additions, deletions or Prepared by Date changes to training materials must be reviewed for their possible impact to the Training

. Training Superintendent/Supervisor/Peer Date , Qualification Matrix. See Incumbent Impact Review,

("Changes Not Requiring Revision" only)

NOBP-TR-II04.

I

RTL#A5.640U 1/2-ADM-1301.F04 Page30f6 Revision 1 JPM NUMBER: 2AD-03l JPM TITLE: Prepare a Clearance Tagout [2QSS-P21B] Quench Spray JPM REVISION: 0 Pump 21B KIA

REFERENCE:

2.2.13 4.1 TASK ID: 0481-007-03-043 JPM APPLICATION: ~ REQUALIFICATION ~ INITIAL EXAM D TRAINING D FAULTED JPM ~ ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

D Perform D D Simulate B Plant Site Simulator D Classroom B

D Annual Requal Exam Initial Exam OJT/TPE BVT D NRC D Other:

D Training D Other:

EVALUATION RESULTS Performer Name: Performer SSN:

Time D Yes Allotted 25 Minutes Actual minutes Critical: ~ No Time: Time:

JPM RESULTS:

D SAT D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

I

RTL#A5.640U 1I2-ADM-130 1.F04 Page 4 of6 Revision 1 EVALUATOR DIRECTION SHEET TASK STANDARD: Identify the tags and sequence of placement for a tagout of2QSS-P21B Quench Spray Pump 21 B.

RECOMMENDED Classroom STARTING LOCATION:

DIRECTIONS: You are to perfonn the task Prepare a SAFE Clearance Tagout.

INITIAL CONDITIONS: The plant is in Refueling Mode, no fuel is in the reactor. [2QSS-P21B]

Quench Spray Pump 21 B is to be placed on clearance.

INITIATING CUE: You are to identify the required clearance points (equipment), position (placement configuration), and sequence for clearing [2QSS-P21 B]

Quench Spray Pump 21 B for pump seal replacement IAVl the attached clearance coversheet. Document your results on the worksheet provided. For this JPM, it is NOT necessary to complete the Clearance Preparation Checklist, but it may be used as a tool.

REFERENCES:

NOP-OP-lOOl, Clearance/Tagging Program, Rev. 18 TOOLS: None HANDOUT: NOP-OP-IOOI 0 Clearance Preparation Checklist, Rev. 05 NOP-OP-IOOl, Clearance/Tagging Program, Rev. 18 OP Manual Fig. No. 13-2, 10080-RM-413-2, Rev. 20 OM Chapter 20M-13.3.C, Power Supply and Control Switch Checklist Rev.9.

OM Chapter 20M-13.3.B.l, Valve List Rev. 11 Clearance coversheet 2R16-13-QSS-TRNG TodaylNOW 2QSS-P21B]

Quench Spray Pump 21 B Seal Replacement Yes Mode 4 Use caution when breaching seal package; casing may not be completely drained.

2R16 - SEAL REPLACEMENT 2001005844

RTL#A5.640U 1/2-ADM-130 l.F04 Page50f6 Revision 1 CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

DRead:

TASK: You are to perform the task Prepare a SAFE Clearance Tagout.

INITIAL CONDITIONS: The plant is in Refueling Mode, no fuel is in the reactor. [2QSS-P21B]

Quench Spray Pump 21B is to be placed on clearance.

INITIATING CUE: You are to identify the required clearance points (equipment), position (placement configuration), and sequence for clearing [2QSS-P21 B]

Quench Spray Pump 21 B for pump seal replacement lAW the attached clearance coversheet. Document your results on the worksheet provided. For this JPM, it is NOT necessary to complete the Clearance Preparation Checklist, but it may be used as a tool.

D At this time, ask the evaluator any questions you have on this JPM.

D When satisfied that you understand the assigned task, announce "I am now beginning the JPM".

Simulate performance or perform as directed the required task.

D Point to any indicator or component you verify or check and announce your observations.

After determining the Task has been met announce" I have completed the JPM".

D Then hand this sheet to the evaluator.

RTL#A5.640U I/2*ADM*l30 l.F04 Page 6 of6 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-031 JPM TITLE: Prepare a Clearance Tagout [2QSS-P21BJ Quench Spray JPM REVISION: 0 Pump 21B UNSAT)~ i SIU I STANDARD (Indicate "S" FOR SAT or "U" FOR START TIME: _ _ _ _ _ __

EVALUATOR NOTE:

This task is normally performed using the SOMS clearance computer and signed electronically. For this JPM, the SOMS computer is NOT available. IF necessary inform candidates that it is not required to follow the instructions for Manual Clearance Generation (lAW NOP-OP-lOO! section 4.14).

EVALUATOR NOTE:

Provide JPM handout and student copy of worksheet.

I.e Candidate completes the table. 1.1 e Candidates table matches the ANSWER KEY.

COMMENTS:

EVALUATOR CUE:

When the candidate identifies and reports that all tags are identified, the evaluation for this JPM is complete.

STOP TIME: _ _ _ _ _ _ __

ANSWER KEY (DO NOT GIVE TO STUDENTS)

Evaluator NOTE: Student may identify additional points. The points listed below are the minimum required for thislPM. All additional points and different sequences must be evaluated to ensure the clearance is correct.

Component ID Component Description Position Sequence 2QSS*P21B-CS (OF) Control Switch for Quench Spray Pump 21B Pull-To-Lock 1 2QSS*P21B (DF) (PTL) 2QSS*MOV101B-CS Quench Pump 21B Discharge Isolation Shut 2 Valve 2QSS*MOV100B-CS Quench Pump 21B Suction Isolation Valve Shut 2 4KVS-2DF-2F2 Supply to Quench Spray Pump 21B Racked Out 3 2QSS*P21B OR Bus Barrier 2QSS-9 Quench Pump 21B Recirc Isol Shut 4 480 VAC MCC*2-E12 Supply to Quench Pump 21B Suction Open 4 Cub 1A Isolation Va Ive 480 VAC MCC*2-E12 Supply to Quench Pump 21B Discharge Open 4 Cub 2A Isolation Valve 2QSS*MOV101B-HW Quench Pump 21B Discharge Isolation Shut 5 Valve 2QSS*MOV100B-HW Quench Pump 21 B Suction Isolation Valve Shut 5 2QSS-206 Quench Spray Pmp 21 B Discharge/Suction Open 6 And/Or Drain Isol Valve 2QSS-204 2QSS-310 Vent valve for Quench Spray Pmp 21B Open 7

~

o U

I Z

w Q

Iii

c o

UI Q.

o

~

o U

I Z

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)

Ii;

RTL#A5.640U 1/2-ADM-130 l.F04 Page 1 of7 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE (JPM)

TRAINING MATERIAL TITLE: Select RWP and Determine Maximum Allowable Stay Time TRAINING MATERIAL NUMBER: 2AD-044 PROGRAM TITLE: Licensed Operator Training COMPUTER CODE: 2AD-044 REVISION NUMBER: o TECHNICAL

REFERENCES:

NOP-OP-4107, "Radiation Work Permit (RWP)" ,Rev 10 INSTRUCTIONAL SETTING: Classroom APPROXIMATE DURATION: 20 minutes PREPARED BY: R. J. Brooks Date PEER REVIEW BY:

Date APPROVED FOR USE:

Training Supervisor or Designee Date

RTL#A5.640U 1I2-ADM-1301.F04 Page 2 of7 Revision 1 TRAINING MATERIAL CHANGE FORM Affected Training Materials: 2AD-044 Type of Change:

D Changes Requiring Learning Objective Related Change? New Rev. #0 Revision DYes DNo D Changes Not The Change Does Not Impact Learning Existing Rev. #

Requiring Revision Objectives or Material Quality.

New Change #

ListiDescription of Change(s):

Original Issue Reason for Change (s):

APPROVALS:

NOTE: Additions, deletions or R. J. Brooks changes to training materials Prepared by Date must be reviewed for their possible impact to the Training Qualification Matrix. See Incumbent Impact Review, Training Superintendent/Supervisor/Peer Date NOBP-TR-I104.

("Changes Not Requiring Revision" only)

RTL#A5.640U 1!2-ADM-1301.F04 Page 3 00 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-044 JPM TITLE: Select RWP and Determine Maximum Allowable Stay JPM REVISION: 0 Time KIA

REFERENCE:

2.3.7 3.5/3.6 TASK ID: 0481-005-03-043 JPM APPLICATION: k8J REQUALIFICATION k8J INITIAL EXAM o TRAINING o FAULTED JPM k8J ADMINISTRATrVE JPM EV ALUA TION METHOD: LOCATION: TYPE: ADMINISTERED BY:

k8J Perform 0 Plant Site 0 Annual Requal Exam 0 BVT D Simulate D Simulator D Initial Exam D NRC k8J Classroom 0 OJT/TPE D Other:

D Training 0 Other:

EVALUATION RESULTS Performer Name: Performer SSN:

Time D Yes Allotted 15 minutes Actual minutes Critical: k8J No Time: Time:

JPM RESULTS:

D SAT D UN SAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

RTL#A5.640U 1I2-ADM-130 l.F04 Page 4 of7 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-044 JPM TITLE: Select RWP and Determine Maximum Allowable Stay JPM REVISION: 0 Time EVALUATOR DIRECTION SHEET TASK STANDARD: Select the correct RWP and associated Task Number AND determine the maximum stay time according to survey map dose rates (cannot complete task due to RWP limit of25 mrem dose)

RECOMMENDED Classroom STARTING LOCATION:

DIRECTIONS: You are to determine correct RWP and associated Task Number for the given task, maximum stay time, and whether job will be completed based on this stay time.

INITIAL CONDITIONS:

A clearance is being prepared to work on the containment sump flow integrator 2DAS-FQTl 00 located in the "A" Penetration.

You are assigned the task of connecting a drain hose to 2DAS 408, located near 2DAS-FQTl 00, in support of clearance posting.

The task will take 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months to perform.

INITIA TING CUE: You are to SELECT the correct RWP and associated task number to perform the task from the R WPs provided, AND calculate your MAXIMUM stay time using the appropriate survey map and RWP.

Report your results in the "Candidate Answer" Box, including whether job can be completed based on calculated stay time.

REFERENCES:

NOP-OP-4107, "Radiation Work Permit (RWP)" ,Rev 10 TOOLS: Calculator HANDOUT: Set of 4 RWPs (112-1014, 212-2014,112-1001,212-2001)

Radiation Survey Maps (Multiple maps including "A" pentration, ensure dose near 2DAS-FQTI 00 is reflective of calculated numbers used for JPM)

RTL#A5.640U 112-ADM-130 1.F04 Page 5 of7 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

DRead:

TASK: You are to detennine correct RWP and associated Task Number for the given task, maximum stay time, and whether job will be completed based on this stay time.

INITIAL CONDITIONS:

A clearance is being prepared to work on the containment sump flow integrator 2DAS-FQTlOO located in the "A" Penetration.

You are assigned the task of connecting a drain hose to 2DAS 408, located near 2DAS-FQTl 00, in support of clearance posting.

The task will take 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months to perfonn.

INITIATING CUE: You are to SELECT the correct RWP and associated task number to perfonn the task from the RWPs provided, AND calculate your MAXIMUM stay time using the appropriate survey map and R WP.

Report your results in the "Candidate Answer" Box, including whether job can be completed based on calculated stay time.

CANDIDATE ANSWER(s):

D At this time, ask the evaluator any questions you have on this JPM.

D When satisfied that you understand the assigned task, announce "I am now beginning the JPM".

Simulate perfonnance or perfonn as directed the required task.

D Point to any indicator or component you verify or check and announce your observations.

After detennining the Task has been met announce II I have completed the JPM".

D Then hand this sheet to the evaluator.

RTL#A5.640U 1/2-ADM-130 1.F04 Page 6 of7 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-044 JPM TITLE: Select RWP and Determine Maximum Allowable Stay JPM REVISION: 0 Time STEP STANDARD

( liCit Denotes CRITICAL STEP) (Indicate Its" FOR SAT or "U" FOR UNSAT)::::> SIU START TIME: ----------------

.'!;+, *'I . . ..

EVALUATOR NOTE: This JPM is designed to be performed in a classroom setting. Provide candidate with the set of RWPs, calculator, and Survey Maps.

I.C Review set ofthree (3) RWPs 1.IC Selects RWP 212-2001 based on Operations provided and select correct clearance activities and records RWP # in candidate RWP and task number. answer box.

1.2C Selects Task # 3 (clearance activities).

EVALAUTOR NOTE: If asked, inform the candidate that connecting the drain hose is considered a clearance activity. Continue the task.

COMMENTS:

2.C Calculate the maximum stay 2.1 C Determines maximum stay time is 1.25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months (1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months time. and 15 minutes) and records this time in the candidate answer box.

25 mr / 20 mrlhr = 1.25 hrs (EAD dose limit) (highest dose rate) (Stay Time)

COMMENTS:

RTL#A5.640U 1I2-ADM-130I.F04 Page 7 of7 Revision I OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-044 JPM TITLE: Select RWP and Determine Maximum Allowable Stay JPM REVISION: 0 Time STEP STANDARD

( "c" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)::::>

3.e Determines allowable stay 3.1 e Determines that stay time is 1.25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months , and estimated time does NOT allow completion for the job is 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months and records that job completion of the work. CANNOT be completed in candidate answer box.

EVALUATOR eUE: When candidate reports results in candidate answer box, This COMPLETES this JPM.

Evaluator discretion is required.

COMMENTS:

STOP TIME:

RTL#A5.640U 112-ADM-130I.F04 Page 1 of 12 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE (JPM)

TRAINING MATERIAL TITLE: Review Shutdown Margin Calculation (At Power and ONE Inoperable Rod) (SRO ONLY)

TRAINING MATERIAL NUMBER: 2AD-039 PROGRAM TITLE: Licensed Operator Training COMPUTER CODE: 2AD-039 REVISION NUMBER: o TECHNICAL

REFERENCES:

20ST-49.1, Shutdown Margin Calculation (Plant Critical), Rev. 18 Unit 2 Curve Book Cycle 16 INSTRUCTIONAL SETTING: Classroom APPROXIMATE DURATION: 25 Minutes PREPARED BY: R. J. Brooks Date PEER REVIEW BY:

Date APPROVED FOR USE:

Training Supervisor or Designee Date

RTL#A5.640U }/2-ADM*1301.F04 Page 3 of 12 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-039 JPM TITLE: Review Shutdown Margin Calculation (At Power and ONE JPM REVISION: 0 Inoperable Rod) (SRO ONLY)

KIA

REFERENCE:

2.1.25 4.2 TASK ID: 0011-006-06-013 JPM APPLICATION: I2SI REQUALIFICATION I2SI INITIAL EXAM D TRAINING o FAULTED JPM I2SI ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

I2SI Perform 0 Plant Site D Annual Requal Exam 0 BVT 0 Simulate 0 Simulator 0 Initial Exam 0 NRC I2SI Classroom 0 OJTfTPE 0 Other:

0 Training D Other:

EVALUATION RESULTS Performer Name: Performer SSN:

Time 0 Yes Allotted 25 Minutes Actual minutes Critical: I2SI No Time: Time:

JPM RESULTS:

0 SAT 0 UN SAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

RTL#A5.640U 112-ADM-130 I.F04 Page 4 of 12 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET TASK STANDARD: Incorrect values for Inoperable rod worth, power defect, and SDM are identified and corrected. (See Answer Key for specific values)

RECOMMENDED Classroom STARTING LOCATION:

DIRECTIONS: Review completed Shutdown Margin calculation that was performed in accordance with 20ST-49.1, Shutdown Margin Calculation (Plant Critical) (Updated for Cycle 16).

INITIAL CONDITIONS: The Unit is in Mode 1, 100% power. All rods at 225 steps.

Annunciator [A4-3C], TAVG DEVIATION FROM TREF is "NOT LIT". ONE control rod has been determined to be inoperable, untrippable, and immovable during performance of 20ST-1.1, Control Rod Assembly Partial Movement Test. Chemistry has just reported current RCS boron concentration at 833 ppm. Current burnup is 12,000 MWD/MTU. The RO has completed 20ST-49.1, Shutdown Margin Calculation (Plant Critical) (Updated for Cycle 16), and has requested the Shift Manager to review the completed OS1'.

INITIATING CUE: As Shift Manager, review the completed 20ST-49.1, Shutdown Margin Calculation (Plant Critical) (Updated for Cycle 16). Document the results of your review in the appropriate section of the OST.

REFERENCES:

20ST-49.l, Shutdown Margin Calculation (Plant Critical) (Updated for Cycle 16), Rev. 18, Unit 2 Curve Book Cycle 16.

TOOLS: Calculator HANDOUT: Unit 2 Curve Book Cycle 16.

20ST-49.1, Shutdown Margin Calculation (Plant Critical) (Updated for Cycle 16), Rev. 18 Filled out with the following errors on Data Sheet 1:

0.857 %~k/k for inoperable rod worth instead of 2.31 %~kIk 2800 PCM for power defect instead of2300 PCM 3.0096 %~kIk for SDM instead of2.054 %L\klk

RTL#A5.640U 112-ADM-130 1.F04 Page 5 ofl2 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

DRead:

TASK: Review completed Shutdown Margin calculation that was performed in accordance with 20ST-49.1, Shutdown Margin Calculation (Plant Critical) (Updated for Cycle 16).

INITIAL CONDITIONS: The Unit is in Mode 1, 100% power. All rods at 225 steps.

Annunciator [A4-3C], TAVG DEVIATION FROM TREF is "NOT LIT". ONE control rod has been determined to be inoperable, untrippable, and immovable during performance of 20ST-1.1, Control Rod Assembly Partial Movement Test. Chemistry has just reported current RCS boron concentration at 833 ppm. Current burnup is 12,000 MWD/MTU. The RO has completed 20ST-49.1, Shutdown Margin Calculation (Plant Critical) (Updated for Cycle 16), and has requested the Shift Manager to review the completed OST.

INITIATING CUE: As Shift Manager, review the completed 20ST-49.1, Shutdown Margin Calculation (Plant Critical) (Updated for Cycle 16). Document the results of your review in the appropriate section of the OST.

D At this time, ask the evaluator any questions you have on this JPM.

D When satisfied that you understand the assigned task, announce "I am now beginning the JPM".

Simulate performance or perform as directed the required task.

D Point to any indicator or component you verity or check and announce your observations.

After determining the Task has been met announce" I have completed the JPM".

D Then hand this sheet to the evaluator.

RTL#A5.640U 1/2-ADM-1301.F04 Page 6 of 12 Revision I OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-039 JPM TITLE: Review Shutdown Margin Calculation (At Power and ONE JPM REVISION: 0 Inoperable Rod) (SRO ONLY)

STEP STANDARD

( "e" Denotes CRITICAL STEP) (Indicate "8" FOR SAT or "U" FOR UNSAT)=> I S/U I EVALUATOR NOTE:

Some judgment may be required to determine satisfactory performance on this JPM. Refer to attached Data Sheet 1 ANSWER KEY.

i EVALUATOR CUE:

If the candidate hands in the OST after ONLY finding the first error, provide the following cue:

Make any necessary corrections and complete the SDM calculation.

'..;i .**** '" "(c~i\l~i;;; .,.,' " START TIME:

.' .< /' . *...... .*.*.*.* ....*.. ..("(;>,; . <j,.

1. If the plant is in Mode 1, 1.1 Verifies Step VII.A.1, (Plant in Mode 1, Tavg <3°F Verify that Tavg is less than above Tref (Annunciator A4-3C OFF) from Initial 3°F above Tref (Annunciator Conditions.

A4-3C, TAVO DEVIATION FROM TREF is OFF)

(Otherwise N/A). COMMENTS:

(Step VILA I )

2. If the plant is in Mode 2, 2.1 Verifies Step VILA2, is N/A (Plant not in Mode 2).

Verify that Tavg is less than gOF above Program Tavg as follows: (Otherwise NIA) COMMENTS:

(Step VILA2)

I I

RTL#A5.640U 112-ADM-130 I.F04 Page 7 of 12 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-039 JPM TITLE: Review Shutdown Margin Calculation (At Power and ONE JPM REVISION: 0 Inoperable Rod) (SRO ONLY)

STEP STANDARD

( "e" Denotes CRITICAL STEP) (Indicate "s" FOR SAT or "U" FOR UNSAT)~ Stu

3. Request Chemistry to 3.1 Verifies current boron concentration is 833 ppm from determine current RCS Boron initial conditions.

concentration in ppm.

(Step VILA.3)

COMMENTS:

4. Record the number of steps 4.1 Verifies Control Bank: D as 225 steps withdrawn on withdrawn for Control Bank: D Data Sheet 1 (Block AA) from initial conditions.

from the group demand counters, (BB-B) on Data Sheet 1. COMMENTS:

(Step VILA.4)

5. Record the current reactor 5.1 Verifies reactor power as 100% on Data Sheet 1 power level in percent of full (Block A.5).

power from [2NME-NR45],

Power Range Recorder, (VB B) OR PCS computer point COMMENTS:

U1150, 1MIN AVGPWR RNG NUCLEAR FLUX, on Data Sheet 1.

(Step VILA.5)

6. Record the number of 6.1 Verifies number of immovable or untrippable rods as immovable or untrippable "ONE" on Data sheet 1 (Block A.6) (given in Initial control rods on Data Sheet 1. Conditions).

(Step VILA.6)

COMMENTS:

RTL#A5.640U 112-ADM-130I.F04 Page 8 of 12 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-039 JPM TITLE: Review Shutdown Margin Calculation (At Power and ONE JPM REVISION: 0 Inoperable Rod) (SRO ONLY)

STEP STANDARD

( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> Stu

7. If the number of immovable or 7.1 Verifies Step VILA.7 is N/A.

untrippable control Rods is greater than 1, Use Attachment 1 to determine the required COMMENTS:

boron concentration with greater than one struck rod and Record below. (Otherwise N/A)

(Step VIlA.7)

8. Determine control bank 8.1 Verifies ARO Total Bank Worth (from the Data reactivity worth per the Shec~t 1 table) to be 7.571 %8k1k and recorded on following: Data Sheet I (Block R1.a).

Using the ARO Total Bank Worth table on Data Sheet 1, COMMENTS:

Enter the total bank worth for the current core burnup range, in the space provided on Data Sheet 1.

(Step VII.Rl.a)

9. Using Curve Book Figures 9.1 Verifies integral rod worth to be ZERO and recorded CB-24A, 24B or CB-24C, on Data Sheet 1 (Blocks Rl.b.1) and Rl.b).

Determine integral rod worth for the current bank position AND Enter this value on COMMENTS:

Data Sheet 1.

Divide value from curve (in pcm) by 1000 to convert to

%8k1k AND Record on Data Sheet 1.

(Step VII.B.l.b)

RTL#A5.640U 1/2-ADM-1301.F04 Page 9 of 12 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-039 JPM TITLE: Review Shutdown Margin Calculation (At Power and ONE JPM REVISION: 0 Inoperable Rod) (SRO ONLY)

I STEP I STANDARD

( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)~ SIU

10. Subtract the integral rod 10.1 Verlfies TBW-IRW is 7.571 %L\k1k and recorded on worth from the Total Bank Data Sheet 1 (Block B.1.c).

Worth AND Enter the result on Data Sheet 1.

COMMENTS:

(Step VII.B.I.c) 11 Multiply this result by 0.9 to 11.1 Verlfies 90% ofTBW to be 6.8139 %L\kIk and apply a 10% uncertainty AND recorded on Data Sheet 1 (Block B.I.d).

Enter the result on Data Sheet 1.

(Step VII.B.I.d) COMMENTS:

12.C If ONE rod is inoperable 12.1 C Determines stuck rod worth should be 2.310 %L\kIk (untrippable), Record "Worst NOT 0.857 and records on Data Sheet I (Block Case Stuck Rod with B.2).

Inoperable Rod" worth on Data Sheet 1. Value is determined from Column COMMENTS:

"B" on Attachment 2 for the appropriate Cycle Bumup.

(Step VII.B.2.b)

EVALUATOR NOTE:

Candidate may need cued to make any necessary corrections and complete the SDM calculation.

J

RTL#A5.640U 112-ADM-130 I.F04 Page 10 of 12 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-039 JPM TITLE: Review Shutdown Margin Calculation (At Power and ONE JPM REVISION: 0 Inoperable Rod) (SRO ONLY)

STEP STANDARD

( "e" Denotes CRITICAL STEP) (Indicate liS" FOR SAT or "U" FOR UNSAT)=> I SIU I 13.C Subtract Stuck Rod(s) Worth 13.lC Determines 90% Total Bank Worth minus Stuck from the 90% Total Bank Rod(s) Worth to be 4.5039 %~k/k and records on Worth value AND Enter the Data Sheet 1 (Block B.3).

result on Data Sheet 1.

(Step VII.B.3) COMMENTS:

14. Determine Power Defect as 14.1 Record RCS Boron Concentration of833 ppm on follows: Data Sheet 1 (Block B.4.a).

Record RCS Boron Concentration results from COMMENTS:

Chemistry on Data Sheet 1.

(Step VII.BA.a)

I

15. Using Curve Book Figure 29, 15.1 Det,ermines B-1 0 Correction Factor to be 0.900 and Determine the B-1 0 records on Data Sheet 1 (Block B.4.b).

Correction Factor for the present Bumup (Ifbetween two Bumup values, Use the COMMENTS:

B-10 Correction Factor for the greater MWD/MTU Bumup entry) AND Record on Data Sheet 1.

RTL#A5.640U 1I2-ADM-130 I.F04 Page 11 of 12 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-039 JPM TITLE: Review Shutdown Margin Calculation (At Power and ONE JPM REVISION: 0 Inoperable Rod) (SRO ONLY)

STEP STANDARD

( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT):::> I SIU I

16. Detennine Corrected Boron 16.1 Detennines Corrected Boron Concentration to be 750 Concentration by multiplying ppm and records on Data Sheet 1 (Block B.4.c).

the RCS Boron Concentration and the B-1 0 Correction Factor AND COMMENTS:

Record on Data Sheet 1.

(Step VII.B.4.c) 17.C Using Curve Book Figure 21, 17.1C Determines ABSOI.. UTE VALUE of the Power Determine the ABSOLUTE Defect to be 2300 pem NOT 2800 pcm and records VALUE of the Power Defect on Data Sheet 1 (Block B.4.d).

for the current power level and the Corrected Boron Concentration AND Enter COMMENTS:

this value on Data Sheet 1.

(Step VII.B.4.d) 18.C Divide value from curve (in 18.1 C Converts ABSOLUTE VALUE of the Power Defect pcm) by 1000 to convert to of 2300 pcm to 2.30 %~k/k and records on Data

%~k/k AND Record on Data Sheet 1 (Block B.4.e).

Sheet 1.

(Step VII.B.4.e) COMMENTS:

RTL#A5.640U 1/2-ADM-1301.F04 Page 12 of 12 Revision I OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-039 JPM TITLE: Review Shutdown Margin Calculation (At Power and ONE JPM REVISION: 0 Inoperable Rod) (SRO ONLY)

STEP STANDARD

( "e" Denotes CRITICAL STEP) Indicate "s" FOR SAT or "U" FOR UN SAT)=> I SIU I 19.C Add 0.150 % Llklk for 19.1 C Determines Power Defect plus operating temperature operating temperature band band margin to be 2.45 % Llklk NOT 2.95 % i~kIk margin to the Power Defect and records on Data Sheet 1 (Block B.4.t).

recorded in Step VII.B.4.e AND Record on Data Sheet

1. COMMENTS:

(Step VILBA.t) 20.C Determine SHUTDOWN 20.1 C Dett.'l111ines SDM to be 2.054 % Llklk NOT 3.009 %

MARGIN by subtracting Llklk and records on Data Sheet 1 (Block B.4.f) AND Power Defect (Step space provided on candidate direction sheet.

VILBA.t) from the value determined in Step VII.B.3 AND Record on Data Sheet COMMENTS:

1.

(Step VII.B.5)

EVALUATOR CUE: ]

That Completes this JPM STOP TIME:

RTL#A5.640U 112-ADM-130 1.F04 Page 1 of9 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE (JPM)

TRAINING MATERIAL TITLE: Review a Completed Quadrant Power Tilt Ratio Calculation (SRO ONLY)

TRAINING MATERIAL NUMBER: 2AD-045 PROGRAM TITLE: Licensed Operator Training COMPUTER CODE: 2AD-045 REVISION NUMBER: o TECHNICAL

REFERENCES:

20ST-2.4A, Quadrant Power Tilt Ratio Manual Calculation", Rev. 8 INSTRUCTIONAL SETTING: Simulator/Classroom APPROXIMATE DURATION: 20 minutes PREPARED BY: R. J. Brooks Date PEER REVIEW BY:

Date APPROVED FOR USE:

Training Supervisor or Designee Date

RTL#A5.640U 1I2-ADM-1301.F04 Page 20f9 Revision 1 TRAINING MATERIAL CHANGE FORM Affected Training Materials: 2AD-045 Type of Change:

I:8J Changes Requiring Learning Objective Related Change? New Rev. # 0 Revision DYes I:8J No D Changes Not The Change Does Not Impact Learning Existing Rev. # N/A Requiring Revision Objectives or Material Quality.

New Change #

ListlDescription of Change(s):

Original Issue Reason for Change (s):

APPROVALS:

NOTE: Additions, deletions or R. J. Brooks changes to training materials Prepared by Date must be reviewed for their possible impact to the Training Qualification Matrix. See Incumbent Impact Review, Training Superintendent/Supervisor/Peer Date NOBP-TR-1104.

("Changes Not Requiring Revision" only)

RTL#A5.640U 112-ADM-130 1.F04 Page 3 of9 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-045 JPM TITLE: Review a Completed Quadrant Power Tilt Ratio JPM REVISION: 0 Calculation (SRO ONLY)

KJA

REFERENCE:

015Al.04 3.5/3.7 TASK ID: 0021-005-06-013 015A4.02 3.9/3.9 2.1.37 4.3/4.6 JPM APPLICATION: [gI REQUALIFICATION [gI INITIAL EXAM o TRAINING o FAULTED JPM [gI ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

[gI Perform 0 Plant Site 0 Annual Requa] Exam 0 BVT 0 Simulate 0 Simulator 0 Initial Exam 0 NRC

[Z] Classroom 0 OJT/TPE 0 Other:

0 Training 0 Other:

EVALUATION RESULTS Performer Name: Performer SSN:

Time 0 Yes Allotted 20 minutes Actual minutes Critical: [gI No Time: Time:

JPM RESULTS:

D SAT D UN SAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

RTL#AS.640U 1/2-ADM-1301.F04 Page 4 of9 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET TASK STANDARD: The QPTR calculation is corrected and compared to Technical Specification limits, AND a determination is made that the OST Acceptance Criteria are NOT met and TS 3.2.4 Condition A is applicable.

RECOMMENDED Classroom STARTING LOCATION:

DIRECTIONS: Review/approve a completed 20ST-2.4A, "Quadrant Power Tilt Ratio Manual Calculation".

INITIAL CONDITIONS: Mode 1 100% power. The plant computers are unavailable.

INITIATING CUE: The STA has just completed his review of the recently completed 20ST-2.4A, "Quadrant Power Tilt Ratio Manual Calculation". As Shift Manager you are to review/approve the completed 20ST-2.4A, "Quadrant Power Tilt Ratio Manual Calculation". Document the results of your review/approval in the appropriate section of the OST.

Use the providl~d Pictures of the NI cabinets and "Quadrant Power Tilt Ratio Normalization Factors" to perform this review/approval.

REFERENCES:

20ST-2.4A, "Quadrant Power Tilt Ratio Manual Calculation", Rev. 8.

TOOLS: Calculator HANDOUT: 1. 20ST-2.4A, "Quadrant Power Tilt Ratio Manual Calculation",

Rev. 8, completed with the following errors:

N42 upper current is recorded as 249 instead of 259;

N41 and N42 lower detector Normalization Factors are REVERSED.

2. NI Cabinet Pictures.

3. Attached "Quadrant Power Tilt Ratio Normalization Factors"

4. Have additional blank copies of Data sheet 1 and Tech Specs available in case candidates request them.

RTL#A5.640U 112-ADM-130 1.F04 Page 5 of9 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

DRead:

TASK: Review/approve a completed 20ST-2.4A, "Quadrant Power Tilt Ratio Manual Calculation".

INITIAL CONDITIONS: Mode 1 100% power. The plant computers are unavailable.

INITIATING CUE: The STA has just completed his review of the recently completed 20ST-2.4A, "Quadrant Power Tilt Ratio Manual Calculation". As Shift Manager you are to review/approve the completed 20ST-2.4A, "Quadrant Power Tilt Ratio Manual Calculation". Document the results of your review/approval in the appropriate section of the OST.

Use the provided Pictures of the NI cabinets and "Quadrant Power Tilt Ratio Normalization Factors" to perform this review/approval.

D At this time, ask the evaluator any questions you have on this lPM.

D When satisfied that you understand the assigned task, announce !II am now beginning the JPM".

Simulate performance or perform as directed the required task.

D Point to any indicator or component you verify or check and announce your observations.

After determining the Task has been met announce" I have completed the JPM".

D Then hand this sheet to the evaluator.

RTL#A5.640U 112-ADM -130 1.F04 Page 60f9 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE "Quadrant Power Tilt Ratio Normalization Factors" UPPER DETECTORS Norm Factor N41A 0.0543 N42A 0.0447 N43A 0.0556 N44A 0.0400 LOWER DETECTORS Norm Factor N41B 0.0483 N42B 0.0470 N43B 0.0600 N44B 0.0460

RTL#A5.640U 112-ADM-1301.F04 Page 7 of9 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-04S JPM TITLE: Review a Completed Quadrant Power Tilt Ratio JPM REVISION: 0 Calculation (SRO ONLY)

STEP STANDARD

("C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)::::> Stu START TIME: _ _ _ _ _ _ _ __

EVALVATOR NOTE:

This JPM is designed to use an accompanying Quadrant Power Tilt Ratio Nonnalization Factors sheet and NI cabinet pictures.

EVALVATOR CUE: Provide an erroneously completed copy of 20ST-2.4A, Quadrant Power Tilt Ratio Normalization Factors sheet and NI pictures.

1. Review 20ST-2.4A, "QPTR 1.1 Reviews 20ST-2.4A, "QPTR Manual Calculation" Manual Calculation" procedure.

procedure.

COMMENTS:

EVALVATOR NOTE: Acceptable detector current tolerance is +/-3 minor scale subdivisions of actual indication.

2.C Identifies reading error for N42 2.1 Identifies N42 upper detector current is 259 and not upper detector. the recorded current of249.

2.2C Records in appropriate block of Data Sheet 1.

COMMENTS:

RTL#A5.640U 112-ADM-130 1.F04 Page 8 of9 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-045 JPM TITLE: Review a Completed Quadrant Power Tilt Ratio JPM REVISION: 0 Calculation (SRO ONLY)

STEP STANDARD

( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> I Stu I I

3.C Identifies the transposition 3.1 Identifies N41 and N42 lower detector correction error with N41 and N42 lower factors are REVERSED.

detector correction factors.

3.2C Records in appropriate block of Data Sheet 1.

COMMENTS:

EVALUATOR CUE: It may be necessary to ask the candidate to make the necessary corrections to the QPTR calculations.

EVALUATOR NOTE: Refer to answer key for critical steps of the corrected QPTR calculation.

EVALUATOR NOTE: If requested, provide the candidate with blank copies of Data sheet 1.

4.C Corrects the errors in the 4.1 Completes the QPTR calculations.

QPTR calculations.

4.2C Records in appropriate blocks of Data Sheet 1.

COMMENTS:

I

RTL#A5.640U 1/2-ADM-130 l.F04 Page 9 of9 Revision I OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-045 JPM TITLE: Review a Completed Quadrant Power Tilt Ratio JPM REVISION: 0 Calculation (SRO ONLY)

STEP STANDARD

( "c" Denotes CRITICAL STEP) (Indicate "s" FOR SAT or "U" FOR UNSAT)=> SIU 5.C Determines OST acceptance 5.1 Compares QPTR calculation against OST acceptance criteria are NOT met. criteria and determines OST acceptance criteria are NOT met.

5.2C Records problems encountered on the cover sheet and/or the OST problem sheet.

5.3C Records on the cover sheet and/or the OST problem she~~t that TS 3.2.4 LCO actions are applicable.

EVALUATOR NOTE: It may be necessary to ask a follow-up question to determine that the candidate is aware that TS 3.2.4 LCO actions are applicable.

COMMENTS:

STOP TIME: ----------------

RTL#A5.640U 1I2-ADM-1301.F04 Page 1 of7 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE (JPM)

TRAINING MATERIAL TITLE: Perfonn a Risk Assessment [2FWE*P23A Maintenance] (SRO Only)

TRAINING MATERIAL NUMBER: 2AD-041

~~~----------------------------------------

PROGRAM TITLE: Licensed Operator Training COMPUTER CODE: 2AD-041 REVISION NUMBER: o TECHNICAL

REFERENCES:

NOP-OP-lO07, "Risk Management", Rev. 15 Technical Specifications Beaver Valley Power Station Units 1 & 2 INSTRUCTIONAL SETTING: Classroom APPROXIMATE DURATION: 15 minutes PREPARED BY:

Date PEER REVIEW BY:

Date APPROVED FOR USE:

Training Supervisor or Designee Date

RTL#A5.640U l!2-ADM-130 1.F04 Page 2 of7 Revision 1 TRAINING MATERIAL CHANGE FORM Affected Training Materials: 2AD-041 Type of Change:

[g] Changes Requiring Learning Objective Related Change? New Rev. #0 Revision DYes [g]No D Changes Not The Change Does Not Impact Learning Existing Rev. N/A Requiring Revision Objectives or Material Quality.

New Change #

List/Description of Change(s):

Updated to reflect Revision 15 ofNOP-OP-1007.

Reason for Change (s):

APPROVALS:

NOTE: Additions, deletions or R J BwuK:s changes to training materials Prepared by Date must be reviewed for their possible impact to the Training Qualification Matrix. See Incumbent Impact Review, Training Superintendent/Supervisor/Peer Date NOBP-TR-II04.

("Changes Not Requiring Revision" only)

I

RTL#A5.640U 112-ADM-130 1.F04 Page 3 of7 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-041 JPM TITLE: Perform a Risk Assessment [2FWE*P23A Maintenance]

JPM REVISION: 0 (SRO Only)

KIA

REFERENCE:

2.2.17 2.6/3.8 TASK ID: 1300-027-03-023 JPM APPLICATION: ~ REQUALIFICATION ~ INITIAL EXAM ~ TRAINING o FAULTED JPM ~ ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

~ Perform 0 Plant Site 0 Annual Requal Exam bd BVT 0 Simulate 0 Simulator 0 Initial Exam o NRC

~ Classroom 0 OJT/TPE o Other:

0 Training 0 Other:

EVALUATION RESULTS Performer Name: Performer SSN:

Time 0 Yes Allotted 15 minutes Actual minutes Critical: ~ No Time: Time:

JPM RESULTS:

0 SAT 0 UN SAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

RTL#A5.640U 112-ADM-130 1.F04 Page 4 of7 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-041 JPM TITLE: Perform a Risk Assessment [2FWE*P23A Maintenance]

JPM REVISION: 0 (SRO Only)

EVALUATOR DIRECTION SHEET TASK STANDARD: Determines Risk Level is ORANGE and the Director of Site Operations (or designee) is the required approver for this condition.

RECOMMENDED Classroom STARTING LOCATION:

DIRECTIONS: You are to determine the risk level for given plant conditions and required approver for this level of risk.

INITIAL CONDITIONS:

The Unit is in Mode 1 at 100% power.

PRA Risk & Traffic Light are GREEN.

Protected Train is "B".

Currently the Unit is in YELLOW Risk due to ongoing scaffold erection over the operable "A" Main Feed pump.

AFW Pump 2FWE*P23A will be taken out of service for repairs to address increasing pump vibrations.

The planned repairs will render the pump inoperable for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

INITIATING CUE: As Shift Manager you are to evaluate the risk level based on initial plant conditions for upcoming activities (2FWE*P23A repairs) AND determine who must approve this risk level in accordance with NOP OP-1007, "Risk Management". Report the results of your risk assessment and required approver of this risk level in the "Candidate Answer" Box below. (provided on candidate direction sheet)

REFERENCES:

NOP-OP-I007, "Risk Management", Rev. 15 Technical Specifications Beaver Valley Power Station Units I & 2 TOOLS: None HANDOUT: NOP-OP-I007, "Risk Management", Rev. 15 Technical Specifications Beaver Valley Power Station Units 1 & 2 (Need to be available in the event the candidate wants to reference)

RTL#A5.640U 112-ADM-1301.F04 Page50f7 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

DRead:

TASK: You are to detennine the risk level for given plant conditions and required approver for this level of risk.

INITIAL CONDITIONS:

The Unit is in Mode 1 at 100% power.

PRA Risk & Traffic Light are GREEN.

Protected Train is "B".

Currently the Unit is in YELLOW Risk due to ongoing scaffold erection over the operable "A" Main Feed pump.

AFW Pump 2FWE*P23A will be taken out of service for repairs to address increasing pump vibrations.

The planned repairs will render the pump inoperable for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

INITIATING CUE: As Shift Manager you are to evaluate the risk level based on initial plant conditions for upcoming activities (2FWE*P23A repairs) AND detennine who must approve this risk level in accordance with NOP OP-I 007, "Risk Management". Report the results of your risk assessment and required approver of this risk level in the "Candidate Answer" Box below.

CANDIDATE ANSWER(S):

D At this time, ask the evaluator any questions you have on this JPM.

D When satisfied that you understand the assigned task, announce "I am now beginning the JPM".

Simulate perfonnance or perfonn as directed the required task.

D Point to any indicator or component you verify or check and announce your observations.

After detennining the Task has been met announce" I have completed the JPM".

D Then hand this sheet to the evaluator.

RTL#A5.640U 112-ADM-130 1.F04 Page6of7 Revision 1 OPERA TIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-041 JPM TITLE: Perforrn a Risk Assessment [2FWE*P23A Maintenance]

JPM REVISION: 0 (SRO Only)

STEP STANDARD

( "c" Denotes CRITICAL STEP) (Indicate "s" FOR SAT or "U" FOR UNSAT)=> I SIU I START TIME: _ _ _ _ _ _ __

EVALUATOR CUE: Provide a copy ofNOP-OP 1007, "Risk Management".

1. Refers to NOP-OP-1007, "Risk 1.1 Ref;;:rs to NOP-OP-I007.

Management" provided.

COMMENTS:

EVALUATOR NOTE: The candidate may want to refer to TS 3.7.5 as part of this JPM step. Ensure Technical Specifications Beaver Valley Power Station Units 1 & 2 is available for reference. TS 3.7.5 Condition B applies since 2FWE*P23A is inoperable.

Condition C requires a plant shutdown if2FWE*P23A cannot be returned to service within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

2.C Refers to Attachment 3, Risk 2.1 C Deternlines that this activity is ORANGE risk level.

Assessment Worksheet, to This is based on Attachment 3, Section E.5 answer is determine risk. YES because 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months is greater than half of the 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months allowed Technical Specification (TS) Action Statement for any TS which requires a Unit Shutdown if nm exited.

2.2 Records approver in the candidate answer box of the candidate direction sheet.

COMMENTS:

RTL#A5.640U 112-ADM-130 I.F04 Page 7 of7 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-041 JPM TITLE: Perform a Risk Assessment [2FWE*P23A Maintenance]

JPM REVISION: 0 (SRO Only)

STEP STANDARD

( "e" Denotes CRITICAL STEP) (Indicate "s" FOR SAT or "U" FOR UNSAT)=:>

3.C Refers to Attachment 2, Plant 3.1 C Determines that based on an Orange Risk, the Director Risk Matrix or to section 4.3.C of Site Operations (or designee) is the required on page 19, to determine approver for this risk level.

required approval.

3.2 Records approver in the candidate answer box of the candidate direction sheet.

COMMENTS:

EVALUATOR CUE: When the candidate determines risk level and approver, This JPM is COMPLETE.

STOP TIME:

RTL#A5.640U 112-ADM-130 1.F04 Page 1 of7 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE (JPM)

Determine compensatory actions for 2GWS-P21 and 2GWS-OA-I00A TRAINING MATERIAL TITLE: being OOS. (SRO ONLY)

TRAINING MATERIAL NUMBER: 2AD-042 PROGRAM TITLE: Licensed Operator Training COMPUTER CODE: 2AD-042 REVISION NUMBER: o TECHNICAL

REFERENCES:

LRM 3.3.12, Rev. 52 Y2 ODCM Section 3.0.3, Rev. 11 OM Fig. 19-3 Rev. 4 INSTRUCTIONAL SETTING: Classroom APPROXIMATE DURATION: 20 Minutes PREPARED BY: R. J. Brooks Date PEER REVIEW BY:

Date APPROVED FOR USE:

Training Supervisor or Designee Date

RTL#A5.640U 1/2-ADM-130 l.F04 Page 2 0[7 Revision 1 TRAINING MATERIAL CHANGE FORM I Affected Training Materials: 2AD-042

Type of Change*

o Changes Requiring Learning Objective Related Change? New Rev. #0 Revision o Yes ONo o Changes Not The Change Does Not Impact Learning i Existing Rev. # N/ A i Requiring Revision Objectives or Material Quality.

I New Change #

ListiDescription of Change(s):

Original Issue.

Reason for Change (s):

APPROVALS:

NOTE: Additions, deletions or R. J. Brooks changes to training materials Prepared by Date must be reviewed for their possible impact to the Training uuLe Qualification Matrix. See Incumbent Impact ReVli:: I Training Superintendent/Supervisor/Peer Date NOBP-TR-l104. ~

("Changes Not Requiring Revision" only)

RTL#A5.640U 1I2-ADM-1301.F04 Page 3 of7 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-042 JPM TITLE: Detemline compensatory actions for 2GWS-P21 and JPM REVISION: 0 2GWS-OA-100A being OOS. (SRO ONLY)

KIA

REFERENCE:

2.3.11 (4.3) TASK ID: 1300-029-03-023 JPM APPLICATION: I:8J REQUALIFICATION I:8J INITIAL EXAM D TRAINING D FAULTED JPM I:8J ADMINISTRATIVE JPM EV ALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

I:8J Perform D Plant Site D Annual Requal Exam D BVT D Simulate D Simulator D Initial Exam D NRC I:8J Classroom D OJT/TPE D Other:

D Training D Other:

EVALUATION RESULTS Performer Name: Perfonner SSN:

Time D Yes Allotted 20 Minutes Actual minutes Critical: I:8J No Time: Time:

JPM RESULTS:

D SAT D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

RTL#A5.640U 112-ADM-130 1.F04 Page 4 of7 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-042 JPM TITLE: Detemline compensatory actions for 2GWS-P21 and JPM REVISION: 0 2GWS-OA-I00A being OOS. (SRO ONLY)

EVALUATOR DIRECTION SHEET TASK STANDARD: The compensatory actions required are determined to be:

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months take grab samples and analyze for Oxygen concentration AND, least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , verify that the GW storage tanks contain less or equal to 19,000 curies.

RECOMMENDED Classroom STARTING LOCATION:

DIRECTIONS: Refer to Initiating Cue Below.

INITIAL CONDITIONS: It is desired to filll the Gaseous Waste Storage Tanks in accordance with 20M-19.4.G, "Filling Unit 2 Gaseous Waste Storage Tanks from Unit 2 Surge Tank".

The plant is operating at 100% power with all system in NSA.

Gaseous Waste Storage Tanks (2GWS-TK25A-G) pressures are 8 psig and STABLE.

Gaseous Waste Surge Tank (2GWS-TK21) pressure is 62 psig and slowly RISING.

The Gaseous Waste Storage Tanks Recirculation Pump

[2GWS-P21] is out of st::rvice (OOS).

Oxygen Analyzer (2GWS-OAI00A) is also OOS.

Oxygen Analyzer (2GWS-OAI00B) is OPERABLE.

INITIA TING CUE: For these plant conditions, determine the REQUIRED LRM/ODCM compensatory actions for filling the Gaseous Waste Storage Tanks.

Document any compensatory actions in the block below. (provided on the candidate direction sheet).

REFERENCES:

LRM 3.3.12, Re:v. 52 TS 5.5.8, Amend 2781170 Y2 ODCM Section 3.0.3, Rev. 11 OM Fig. 19-3 Rev. 4 TOOLS: None

RTL#A5.640U 112-ADM-130 l.F04 Page 5 of7 Revision 1 OPERAnONS JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

DRead:

TASK: Refer to Initiating Cue Below.

INITIAL CONDITIONS: It is desired to fill the Gaseous Waste Storage Tanks in accordance with 20M-19.4.G, "Filling Unit 2 Gaseous Waste Storage Tanks from Unit 2 Surge Tank".

The plant is operating at 100% power with all system in NSA.

Gaseous Waste Storage Tanks (2GWS-TK25A-G) pressures are 8 psig and STABLE.

Gaseous Waste Surge Tank (2GWS-TK21) pressure is 62 psig and slowly RISING.

The Gaseous Waste Storage Tanks Recirculation Pump

[2GWS-P21] is out of service (OOS).

Oxygen Analyzer (2GWS-OAIOOA) is also OOS.

Oxygen Analyzer (2GWS-OAIOOB) is OPERABLE.

INITIATING CUE: For these plant conditions, determine the REQUIRED LRM/ODCM compensatory actions for filling the Gaseous Waste Storage Tanks.

Document any c:ompensatory actions in the block below.

Required compensatory actions, if any:

D At this time, ask the evaluator any questions you have on this JPM.

D When satisfied that you understand the assigned task, announce "I am now beginning the JPM".

Simulate performance or perform as directed the required task.

D Point to any indicator or component you verify or check and announce your observations.

After determining the Task has been met announce "I have completed the JPM".

D Then hand this sheet to the evaluator.

RTL#A5.640U 112-ADM-1301.F04 Page 6 of7 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-042 JPM TITLE: Determine compensatory actions for 2GWS-P21 and JPM REVISION: 0 2GWS-OA-I00A being OOS. (SRO ONLY)

STEP STANDARD

( "c" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "u" FOR UNSAT)=> I S/U I START TIME: ._ _ _ _ _ __

EVALUATOR CUE: Provide the Candidate with the Candidate Direction Sheet and a current copy of OM Fig. 19-3, LRM, AND yz ODeM Section 3.0.3, EVALUATOR NOTE:

These steps may be performed in any order.

EVALUATOR NOTE:

The next step may not be necessary. The candidate may already be familiar enough with the system to know the impact of 2GWS-P21 being OOS.

1.1 Determines the impact of 1.1 Ref(:rs to OM Fig. 19-3 and determines that Waste 2GWS-P21 being OOS. Gas Storage Tank Radiation Monitor (2GWS-RQI04) is out of service as a result of2GWS-P21 being OOS.

2.C Determines Y2 aDeM 2.1 Refers to Y2 ODeM Section 3.0.3, Att. 0 item compensatory actions for 4.11.25.1 on page 66.

Waste Gas Storage Tank Radiation Monitor (2GWS 2.2C Determines that it will be required to verity, least RQI04) being out of service. once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , that the GW storage tanks contain less or equal to 19,000 curies. (when adding radioactive materials to the tank)

COMMENTS:

I

RTL#A5.640U 1/2-ADM-130 l.F04 Page 7 of7 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-042 JPM TITLE: Detem1ine compensatory actions for 2GWS-P21 and JPM REVISION: 0 2GWS-OA-IOOA being OOS. (SRO ONLY)

STEP STANDARD

( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UN SAT)=> I S/U I 3.C Determines LRM compensatory 3.1 Refers to LRM 3.3.12 Condition 8.1.

actions for Oxygen Analyzer (2GWS-OAIOOA) being OOS. 3.2C Det,ermines at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months take grab samples and analyze for oxygen content.

COMMENTS:

EVALUATOR CUE:

That completes this JPM.

STOP TIME:

RTL#A5.640U 112-ADM-130 1.F04 Page 1 of8 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE (JPM)

TRAINING MATERIAL TITLE: Classify an Emergency Event (Scenario Specific)

TRAINING MATERIAL NUMBER: 2AD-046 PROGRAM TITLE: Licensed Operator Training COMPUTER CODE: 2AD-046 REVISION NUMBER: o TECHNICAL

REFERENCES:

EPP/I-l a, Recognition and Classification of Emergency Conditions, Rev. 15 INSTRUCTIONAL SETTING: Simulator APPROXIMATE DURATION: 15 Minutc~s PREP ARED BY: R. J. Brooks Date PEER REVIEW BY:

Date APPROVED FOR USE:

Training Supervisor or Designee Date

RTL#A5.640U 1I2-ADM-130 l.F04 Page 2 of8 Revision I TRAINING MATERIAL CHANGE FORM Affected Training Materials: 2AD-046 Type of Change:

D Changes Requiring Learning Objective Related Change? New Rev. # 0 Revision DYes DNa D Changes Not The Change Does Not Impact Learning Existing Rev. #

Requiring Revision Objectives or Material Quality.

New Change #

List/Description of Change(s):

Original Issue Reason for Change (s):

APPROVALS:

R. J. Brooks NOTE: Additions, deletions or Prepared by Date changes to training materials must be reviewed for their possible impact to the Training Training Superintendent/Supervisor/Peer Date Qualification Matrix. See Incumbent Impact Review, I (ttChanges Not Requiring Revision" only)

NOBP-TR-I104.

RTL#A5.640U 1I2-ADM-130 1.F04 Page 3 of8 Revision 1 JPM NUMBER: 2AD-046 JPM TITLE: Classify an Emergency Event (Scenario Specific)

JPM REVISION: 0 KIA

REFERENCE:

2.4.41 (4.1) TASK ID: 1350-004-03-023 JPM APPLICATION: r8J REQUALIFICATION r8J INITIAL EXAM 0 TRAINING o FAULTEDJPM r8J ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

bd 0 o

Perform Simulate B 0

Plant Site Simulator Classroom 0

0 Annual Requal Exam Initial Exam OJT/TPE B BVT NRC 0 Other:

D Training D Other:

EV ALUATION RESULTS Performer Name: Performer SSN:

~

Time Yes Allotted Actual 15 Minutes minutes Critical: No Time: Time:

JPM RESULTS:

D SAT D UNSAT (Comments required for VNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Narne/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

RTL#A5.640U l/2-ADM-130 1.F04 Page 4 of8 Revision 1 EVALUATOR DIRECTION SHEET TASK STANDARD: The correct EPP classification is made for the associated scenario AND all "critical" steps of the initial notification form are correctly completed.

RECOMMENDED Simulator STARTING LOCATION:

DIRECTIONS: You are to perform the task Classify An Emergency Event and complete the initial notification form.

INITIAL CONDITIONS: The simulator scenario just completed.(2LOT8 NRC Exam)

INITIATING CUE: As the Unit Supervisor, you are to classify the events in the scenario just completed in accordance with EPP/I-Ia, Recognition and Classification of Emergency Conditions AND complete the initial notification foml.

For the purpose of filling out the initial notification form the following conditions exist:

The code word is "Simulator"

Unit 1 is at 100% steady state power

Wind direction at 150' is 135°

Wind speed at 35' is 15 mph THIS IS A TIME CRITICAL JPM

REFERENCES:

EPP/I-la, Recognition and Classification of Emergency Conditions, Rev. 15 TOOLS: None HANDOUT: EPP/I-J a, Recognition and Classification of Emergency Conditions, Rev. 15; Yz-EPP-IP-l.l.FOl, FENOC Nuclear Power Plant Initial Notification Form Rev. 5

RTL#AS.640U 1/2-ADM-1301.F04 Page S of8 Revision 1 CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

DRead:

TASK: You are to perform the task Classify An Emergency Event and complete the initial notification form.

INITIAL CONDITIONS: The simulator scenario just completed.(2LOT8 NRC Exam)

INITIATING CUE: As the Unit Supervisor, you are to classify the events in the scenario just completed in accordance with EPP/I-Ia, Recognition and Classification of Emergency Conditions AND complete the initial notification form.

For the purpose of filling out the initial notification form the following conditions exist:

The code word is "Simulator"

Unit 1 is at 100% steady state power

Wind direction at 150' is 135°

Wind speed at 35' is 15 mph THIS IS A TIME CRITICAL JPM D At this time, ask the evaluator any questions you have on this IPM.

D When satisfied that you understand the assigned task, announce "I am now beginning the IPM".

Simulate performance or perform as directed the required task.

D Point to any indicator or component you verify or check and announce your observations.

After determining the Task has been met announce" I have completed the JPM".

D Then hand this sheet to the evaluator.

RTL#A5.640U 1/2-ADM-1301.F04 Page 6 of8 Revision I OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-046 JPM TITLE: Classify an Emergency Event (Scenario Specific)

JPM REVISION: 0 STANDARD (Indicate "S" FOR SAT or "U" FOR UN SAT)=>

STARTT~E: ______________

EVALUATOR NOTE: The Candidate is being evaluatled on classifying the events in the scenario just completed. (2LOT8 NRC Exam) It may be necessary to review the events before beginning the JPM.

I.C Classify the event in accordance 1.1 C Candidate correctly classifies the event.

with the Emergency Plan.

Scenario #1: Unusual Event, Tab 2.1 0 Steam/Feed Line Break

Scenario #2: Site Area Emergency, Tab 1.1.1 & 1.2.1, Fission Product Matrix Tabs 1.1.1 & 1.2.1 Potential loss Heat Sink Red Path

Scenario #3: Alert, Tab 1.2.4, Steam Generator Tube Rupture that results in a Safety Injection Actuation

Scenario #4: Alert, Tab 2.3, Failure of Reactor Protection

Scenario #5: Alen, Tab 1.2.3, Potential loss ofRCS barrier due to RCS leak rate.

COMMENTS:

RTL#A5.640U 112-ADM-130 1.F04 Page 7 of8 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-046 JPM TITLE: Classify an Emergency Event (Scenario Specific)

JPM REVISION: 0 STEP STANDARD

( "C" Denotes CRITICAL STEP) (Indicate "8" FOR SAT or "U" FOR UNSAT)=> SIU 2.e Completes the initial 2.1 Places the following information on the space provided on the notification form. initial notification form.

C Item 1 places a checkmark in BV 2 block and records 100% power for Unit 1 and 0% power for Unit 2

Item 2 places a checkmark in the this is a drill box

Places/verifies the word "Simulator" in the code space.

C Item 3 places a checkmark in the appropriate classification box (as identified in step 1 of the JPM above) and places a checkmark in the initial declaration box

Item 3 places current time in the declaration time space, places the date in the date space.

C Item 3 places the appropriate EAL tab number in the EAL number space (as identified in step 1 of the JPM above).

Item 4 places the appropriate EAL description in the space provided (as identified in step 1 of the JPM above)

C Item 5 places checkmarks in the non-routine AND airborne radiological release in progress due to this event box.

C Item 6 places a checkmark in NONE box for the PAR

C Item 7 places 135 0 and 15 mph in the wind speed and direction spaces

RTL#A5.640U 112-ADM-1301.F04 Page 8 of8 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-046 JPM TITLE: Classify an Emergency Event (Scenario Specific)

JPM REVISION: 0 STEP STANDARD

( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSA T):::) SIU 2.2 Places candidate name in the approved space.

EVALUATOR NOTE:

Refer to Answer Key for initial notification form critical steps.

TERMINATING CUE:

That completes this JPM I

COMMENTS:

i' ".';"'i . '"

ii, ';

STOP TIME:

RTL#A5.640U 112-ADM-130 1.F04 Page 1 of8 Revision I OPERATIONS JOB PERFORMANCE MEASURE (JPM)

TRAINING MATERIAL TITLE: Shift From Main Feedwater TRAINING MATERIAL NUMBER: 2CR-On

~~-------------------------------------------

PROGRAM TITLE: Licensed Operator Retraining COMPUTER CODE: 2CR-072 REVISION NUMBER: 4 TECHNICAL

REFERENCES:

20M-52.4.R.l.F, Revision 23, Attachment 10 INSTRUCTIONAL SETTING: Simulator APPROXIMATE DURATION: 15 Minutes PREPARED BY: Paul T. Eisenmann Date PEER REVIEW BY:

Date APPROVED FOR USE:

Training Supervisor or Designee Date

RTL#A5.640U 1/2-ADM-130 l.F04 Page 2 of8 Revision 1 TRAINING MATERIAL CHANGE FORM I

Affected Training Materials: 2CR-072 Type of Change:

C8J Major Learning Objective Related Change? New Rev. #4 DYes ~No LJ Minor The Change Does Not Impact Learning Existing Rev. # 3 Objectives or Material Quality.

New Change #

List/Description of Change(s):

Updated to current procedure revision.

Changed KIA System ID from 035 to 059 per TAl 29384 Reason for Change (s):

Procedure revised.

APPROVALS:

P. T. Eisenmann NOTE: Additions, deletions or Prepared by Date changes to training materials must be reviewed for their possible impact to the Training Qualification Matrix. See Training Superintendent/Supervisor/Peer Date Incumbent Impact Review, (Minor Changes Only) i NOBP-TR- 1104-.

I i

RTL#A5.640U 1I2-ADM-1301.F04 Page 3 of8 Revision 1 JPM NUMBER: 2CR-072 JPM TITLE: Shift From Main Feedwater Reg Valves to Bypasses JPM REVISION: 4 KIA

REFERENCE:

059A4.08 3.0*/2.9* TASK ID: 0241-004-01-013 JPM APPLICATION: IZI REQUALIFICATION IZI INITIAL EXAM D TRAINING D FAULTEDJPM D ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

IZI Perform D Plant Site D Annual Requa] Exam D BVT D Simulate IZI Simulator D Initial Exam D NRC D Classroom D OJT/TPE D Other:

D Training D Other:

EVALUATION RESULTS Performer Name: Performer SSN:

Time D Yes Allotted 15 minutes Actual minutes Critical: IZI No Time: Time:

JPM RESULTS:

D SAT D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

RTL#A5.640U 1i2-ADM-130 1.F04 Page 4 of8 Revision 1 JPM NUMBER: 2CR-072 JPM TITLE: Shift From Main Feedwater Reg Valves to Bypasses JPM REVISION: 4 EVALUATOR DIRECTION SHEET TASK STANDARD: The "A" Bypass Feed Regulating Valve is in automatic and controlling steam generator level.

RECOMMENDED SIMULATOR STARTING LOCATION:

DIRECTIONS: You are to Transfer from Main Feed Regulating Valve to Bypass Feed Regulating Valve for the "A" S/G.

INITIAL CONDITIONS:

The plant is at approximately 25% power.

20M-52.4.R.l.F, "Station Shutdown from 100% Power to Mode 5" has been completed up to Step D.8.

INITIATING CUE:

Your supervisor directs you to place 21 A S/G Bypass Feed Reg Valve [2FWS-FCV479] in service in accordance with Attachment 10 of20M-52.4.R.l.F

[2FWS-FCV479] is to be placed in automatic to control steam generator level.

You are to maintain 21A S/G NR level between 39% and 49%.

REFERENCES:

20M-52.4.R.l.F, Revision 23 TOOLS: None HANDOUT: 20M-52.4.R.l.F, "Station Shutdown from 100% Power to Mode 5",

Revision 23, place kept to step D.8 and a separate copy of Attachment 10.

RTL#A5.64QU 1!2-ADM-1301.F04 Page 5 of8 Revision 1 CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

DRead:

DIRECTIONS: You are to Transfer from Main Feed Regulating Valve to Bypass Feed Regulating Valve for the "A" S/G.

INITIAL CONDITIONS:

The plant is at approximately 25% power.

20M-52 .4.R.l.F, "Station Shutdown from 100% Power to Mode 5" has been completed up to Step D.S.

INITIATING CUE:

Your supervisor directs you to place 21A S/G Bypass Feed Reg Valve [2:FWS-FCV479] in service in accordance with Attachment 10 of 20M-S2.4.R.l.F

[2FWS-FCV479] is to be placed in automatic to control steam generator leveL

You are to maintain 21A S/G NR level between 39% and 49%.

D At this time, ask the evaluator any questions you have on this JPM.

D When satisfied that you understand the assigned task, announce "I am now beginning the JPM".

Simulate performance or perform as directed the required task.

D Point to any indicator or component you verify or check and announce your observations.

After determining the Task has been met announce" I have completed the JPM".

D Then hand this sheet to the evaluator.

RTL#A5.640U 112-ADM-130 1.F04 Page 6 0[8 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-072 JPM TITLE: Transfer from Main Feedwater Reg Valves to Bypasses JPM REVISION: 4 STEP STANDARD

( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> SIU START TIME: _ _ _ _ _ __

EVALUATOR NOTE: Initialize IC-224, Put Steam Generator Wide Range Levels on trend up on BOP's PCS screen. Select "Trends" then select "SG Wide Range Level".

Open MFRV isolation valve 2FWS-MOV154A.

1. Review 20M-52.4.R.l.F and 1.1 Reviews 20M-52.4.R.l.F and Attach. 10.

attachment 10.

COMMENTS:

[ EVALUATOR CUE: Infonn candidate that it is desired to close 2FWS-FCV478 in the MANUAL mode of control.

2.C Place controller in 2.1 Locates Steam Flow, Feed Flow and Steam Generator MANUAL AND Slowly level indicators Open the 21A Bypass FCV.

2.2.C Intermittently opens the Bypass Control Valve As the 21A Bypass FCV is [2FVVS-FCV479] by depressing the up button.

being opened, close [2FWS FCV478] 21A Main 2.3.C Depresses the MANUAL PB then closes the Main Feedwater Reg Valve, in Feed Reg Valve [2FWS-FCV478] by intermittently MANUAL OR AUTO to depressing lower PH.

maintain 21 A S/G level within 39% to 49% 2.4 Maintains Feed Flow approximately equal to Steam Flow.

2.5 Verifies the Main Feed Reg Valve [2FWS-FCV478]

Green light -LIT, Red light- NOT LIT.

COMMENTS:

RTL#A5.640U 1I2-ADM-130 l.F04 Page 7 of8 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-072 JPM TITLE: Transfer from Main Feedwater Reg Valves to Bypasses JPM REVISION: 4 STEP STANDARD

( "c" Denotes CRITICAL STEP) (Indicate "s" FOR SAT or "U" FOR UNSAT)=> I S/U I

3. When S/G 21A Main Feedwater 3.1 Verifie:s controller for 2FWS-FCV478 remains in Reg Valve is fully closed, MANUAL.

perform the following:

3.2 Locates indicators and observes for evidence ofleakage Verify S/G 21A Main Feedwater past 2FWS-FCV478.

Reg Valve controller in MAN.

3.3 Closes 2FWS-MOVI54A by placing CS to close, and Observe Feedwater flow, steam verifies Green light - LIT and Red light - NOT LIT.

flow and S/G level for evidence of leakage past the 21 A Main COMMENTS:

Feed Reg Valve.

Closes [2FWS-MOVI54A], 2lA S/G Main Feedwater Isol Vlv.

4.C Place controller for the 21A 4.1 Verify feedwater flow is approximately equal to Bypass FCV in AUTO AND steam flow and level is approximately 44%.

Monitor S/G level and flow.

4.2C Pla(;e the controller for 2FWS-FCV479 in AUTO.

Iflevel control is NOT stable, restore the valve EVALUATOR CUE: Inform candidate that it controller to MANUAL is desired to operate in AUTO mode. If AND maintain S/G NR level candidate feels that control is not stable in between 39% and 49%. AUTO they may continue to operate in MANUAL.

4.3 Monitors AUTO operation of the valve to ensure it controls level between 3Q31o and 49%.

COMMENTS:

RTL#A5.640U 1/2-ADM-1301.F04 Page 8 of8 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-072 JPM TITLE: Transfer from Main Feedwater Reg Valves to Bypasses JPM REVISION: 4 STEP STANDARD

( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "V" FOR VNSAT)=> I SIV I

5. Iflevel control is NOT stable, 5.1. If in MANUAL, using the auto/manual station for restore the valve controller to [2F'WS-FCV479] slowly adjusts valve controller to MANUAL AND maintain S/O control steam generator level between 39% and 49%.

NR level between 39% and 49%. COMMENTS:

I EVALUATOR JPM.

CUE: That completes this STOP TIME: _________

RTL#A5.640U 1I2-ADM-130 l.F04 Page 1 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE (JPM)

TRAINING MATERIAL TITLE: Respond to Radiation Monitor Alann TRAINING MATERIAL NUMBER: 2CR-622 PROGRAM TITLE: Licensed Operator Training COMPUTER CODE: 2CR-622 REVISION NUMBER: 3 TECHNICAL

REFERENCES:

20M-43.4.AEB, Local-Leak Collection Ventilation [2RMR RQI301] High Level Alann, Issue 1 Revision 5 20M-43.4.AAC Radiation Monitoring Level High, Revision 1 INSTRUCTIONAL SETTING: Simulator APPROXIMATE DURATION: 20 Minutes PREPARED BY: Paul T. Eisenmann Date PEER REVIEW BY:

Date APPROVED FOR USE:

Training Supervisor or Designee Date

RTL#A5.640U 1I2-ADM-130 l.F04 Page 2 of 10 Revision 1 TRAINING MATERIAL CHANGE FORM Affected Training Materials: 2CR-622 Type of Change:

~ Changes Requiring Learning Objective Related Change? New Rev. # 3 Revision DYes ~No D Changes Not The Change Does Not Impact Learning Existing Rev. # 2 Requiring Revision Objectives or Material Quality.

New Change #

List/Description of Change(s):

Updated to current procedure revisions.

Updated to current JPM format.

Reason for Change (s):

Procedure Enhancement APPROVALS:

NOTE: Additions, deletions or Pual T Ei~f'1"\ ....... "r..... changes to training materials Prepared by Date must be reviewed for their possible impact to the Training Qualification Matrix. See Incumbent Impact Review, Training Superintendent/Supervisor/Peer Date NOBP-TR-II04.

("Changes Not Requiring Revision" only)

RTL#A5.640U 1I2-ADM-130 l.F04 Page 3 of 10 Revision 1 JPM NUMBER: 2CR-622 JPM TITLE: Respond to Radiation Monitor Alann JPM REVISION: 3 KIA

REFERENCE:

073A4.02 3.7/3.7 TASK ID: 0431-031-04-012 JPM APPLICATION: r8J REQUALIFICATION r8J INITIAL EXAM D TRAINING r8J FAULTED JPM D ADMINISTRATIVEJPM EV ALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

~

~ Perfonn D Simulate D

Plant Site Simulator Classroom B

D Annual Requal Exam Initial Exam OJT/TPE B BVT NRC D Other:

D Training D Other:

EV ALUATION RESULTS Perfonner Name: Perfonner SSN:

Time D Yes Allotted 20 Minutes Actual minutes Critical: r8J No Time: Time:

JPM RESULTS:

0 SAT 0 UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

RTL#A5.640U 112-ADM-130 1.F04 Page 4 of 10 Revision 1 EVALUATOR DIRECTION SHEET TASK STANDARD: Contiguous area ventilation aligned through the filtered flowpath.

RECOMMENDED Simulator STARTING LOCATION:

DIRECTIONS: You are to perform the task, Respond to a Radiation Monitor Alarm INITIAL CONDITIONS: Annunciator A4-5C "Radiation Monitor Level High" has just alarmed.

INITIATING CUE: Your supervisor directs you to respond to the alarm using the appropriate Alarm Response Procedure.

REFERENCES:

20M-43.4.AEB, Local-Leak Collection Ventilation [2RMR RQI301]

High Level Alarm, Issue 1 Revision 5.

20M-43.4.AAC Radiation Monitoring Level High, Revision 1 TOOLS: None HANDOUT: 20M-43.4.AEB, Local-Leak Collection Ventilation [2RMR RQI301]

High Level Alarm, Issue 1 Revision 5.

20M-43.4.AAC Radiation Monitoring Level High, Revision 1

RTL#A5.640U 112-ADM-130 1.F04 Page 5 of 10 Revision 1 CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

DRead:

TASK: You are to perfoffi1 the task, Respond to a Radiation Monitor Alaffi1 INITIAL CONDITIONS: Annunciator A4-5C "Radiation Monitor Level High" has just alaffi1ed.

INITIATING CUE: Your supervisor directs you to respond to the alaffi1 using the appropriate Alarm Response Procedure.

D At this time, ask the evaluator any questions you have on this JPM.

D When satisfied that you understand the assigned task, announce 111 am now beginning the JPM".

Simulate performance or perfoffi1 as directed the required task.

D Point to any indicator or component you verify or check and announce your observations.

After determining the Task has been met announce" I have completed the JPM".

D Then hand this sheet to the evaluator.

RTL#A5.640U 1I2-ADM-130 I.F04 Page 6 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-622 JPM REVISION: 3 JPM TITLE: Respond to Radiation Monitor Alarm STEP STANDARD

( "c" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> Stu SIMULATOR SETUP:

Use HTML "JPM 2CR-622" to insert commands to prevent damper swapping on HIGH radiation level and to anow MANUAL re-positioning of the dampers.

(Train A switch removes malfunction from 2HVS MOD202A, Train B switch removes malfunction from 2HVS-AfOD201B)

EVALUATOR CUE:

When candidate is ready to begin JPM, PLACE the simulator in RUN.

START TIME: _ _._ _ _ __

EVALUATOR NOTE:

Steps - 6 are required only if the candidate refers to 20M-43.4.AAC. Steps 7 and beyond are to be referenced for 20M-43.4.AEB actions.

1. Obtain procedure. (20M 1.1 Locates copy of procedure 20M-43.4.AAC 43.4.AAC)

EVALUATOR CUE:

After candidate locates the procedure, the evaluator can provide a copy of20M-43.4.AAC to candidate.

COMMENTS:

I

RTL#A5.640U 112-ADM-130 I.F04 Page 7 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-622 JPM TITLE: Respond to Radiation Monitor Alann JPM REVISION: 3 STEP STANDARD

( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> I SIU I

2. Detennine which radiation 2.1 Depresses the grid 6 pushbutton on the RM -11 monitor is in alann at the RM-l1 console.

console.

2.2 Verifies 20B042 is blinking and has turned red.

COMMENTS:

3. At the RM-l1 console, type in 3.1 Types in 2042 and depresses the SEL pushbutton.

the 4-digit numerical code number of the alanning monitor COMMENTS:

and select.

4. Press the STATUS pushbutton. 4.1 Depresses the STATUS pushbutton on the DRMS keyboard.

COMMENTS:

5. Press SYSTEM ACK to silence 5.1 Depresses the SYSTEM ACK pushbutton on the DRMS the console alann. keyboard.

COMMENTS:

RTL#A5.640U 1I2-ADM-I30 l.F04 Page 8 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-622 JPM TITLE: Respond to Radiation Monitor Alann JPM REVISION: 3 STEP STANDARD

( "c" Denotes CRITICAL STEP) (Indicate "s" FOR SAT or "u" FOR UNSAT)=> I S/U I

6. Verify if radiation level is greater 6.1 NIA than 1000 times background. .------------------------,

EVALUTOR CUE:

If asked, role-play SM/US and infonn the candidate that 2RMR-RQI301 is NOT 1000 times nonnal background.

COMMENTS:

7. Detennine 2RMR-RQI301 is in 7.1 Det*ennines 2RMR-RQI301 (Leak Collection alann and refers to local alann Ventilation Radiation Monitor) is in alann.

response procedure for corrective actions. 7.2 Refers to local alann response procedure (20M 43.4AEB) for corrective actions.

I EVALUATOR CUE:

After candidate locates the procedure, the evaluator can provide a copy of20M-43.4.AEB to candidate.

COMMENTS:

8. At the RM-ll console, verify the 8.1 Verifies that the red box moves to the right.

indicating box turns red and moves to the right of the COMMENTS:

CHANNEL IN HIGH ALARM.

RTL#A5.640U li2-ADM-130 LF04 Page 9 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-622 JPM TITLE: Respond to Radiation Monitor Alarm JPM REVISION: 3 STEP STANDARD

( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "D" FOR L'NSAT)=> SID

9. Depress the CHANNEL ITEMS 9.1 Depresses the CHANNEL ITEMS pushbutton and button and verify that the actual compares the actual level to the HIGH alarm setpoint.

level is higher than the high alarm setpoint. 9.2 Det,ermines that the actual value is higher than the HIGH alarm setpoint.

COMMENTS:

10. Notify the SM and obtain 10.1 Candidate notifies SM of HIGH radiation monitor directions. alarm and asks for direction.

EVALUATOR CUE:

Role-play the SM and acknowledge the report.

DIRECT the candidate to perform steps I.e. and 1.f.

The SM will perform the other remaining steps of this procedure (l.d., l.g., l.h., & l.i.)

COMMENTS:

EVALUATOR NOTE:

FAULT STATEMENT In the next 2 steps (11 & 12), Dampers 2HVS*MOD20IA and 2HVS*MOD201B Should have automatically CLOSED.

Dampers 2HVS*MOD202A and 2HVS*MOD202B Should have automatically OPENED.

The candidate will be required to manually align these dampers by going to "FILT" position. CS'scan be manipulated in any order. 2HVS*MOD20IA and 2HVS*MOD202B will NOT change position. Both Trains Switches will need to be placed to the "FILT" pas. to isolate the Ventilation Vent & align SLCRS.

RTL#A5.640U 1I2-ADM-I301.F04 Page 10 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-622 JPM TITLE: Respond to Radiation Monitor Alarm JPM REVISION: 3 STEP STANDARD

( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> SIU I 11.C Verify [2HYS*MOD201A] 11.1 Verifies [2HYS*MOD20IA] and and [2HYS*MOD201B] are [2HYS*MOD201B] green lights NOT LIT and red CLOSED. lights LIT 11.2C Places the Train A control switch to the FILT position (2HYS*MOD202A will open, however, 2HYS*MOD201A will NOT go closed.

2HYS*MOD201B will also remain open unless the "B" train CS was placed in "FILTH position).

COMMENTS:

12.C Verify [2HVS*MOD202A] 12.1 Verifies [2HVS*MOD202A] and and [2HVS*MOD202B] are [2HYS*MOD202B] green lights LIT and red lights OPEN. - NOT LIT (Only 2HYS*MOD202A will open, 2HVS*MOD202B will not open) 12.2C Places the Train B control switch to the FILT position (2HYS*MOD201 B will close when the "B" train CS is placed in HFILT").

COMMENTS:

EVALUATOR NOTE:

Candidate should report to supervisor that 2HYS*MOD201A/202B did not change positions.

EVALUATOR CUE: ]

That Completes this JPM STOP TIME:

RTL#A5.640U 1/2-ADM-1301.F04 Page 1 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE (JPM)

TRAINING MATERIAL TITLE: Raise Reactor Power to 10-8 Amps TRAINING MATERIAL NUMBER: 2CR-644 PROGRAM TITLE: License COMPUTER CODE: 2CR-644 REVISION NUMBER: 2 TECHNICAL

REFERENCES:

20M-50.4.D2, Reactor Startup from Mode 3 to Mode 2, Rev. 2 20M-53C.4.2.1.3, RCCA Control Bank Inappropriate Continuous Movement, Rev. 7 Data Sheet 3, 20M-50.4.F, Rev 7 INSTRUCTIONAL SETTING: Simulator APPROXIMATE DURATION: 16 Minutes PREPARED BY: P.T. Eisenmann Date PEER REVIEW BY:

Date APPROVED FOR USE:

Training Supervisor or Designee Date

RTL#A5.640U 112-ADM-130 1.F04 Page 2 of 10 Revision 1 TRAINING MATERIAL CHANGE FORM Affected Training Materials: 2CR-644 Type of Change:

[gJ Changes Requiring Learning Objective Related Change? New Rev. #2 Revision DYes [gJ No D Changes Not The Change Does Not Impact Learning Existing Rev. # 1 Requiring Revision Objectives or Material Quality.

New Change #

List/Description of Change(s):

Updated to reflect changes in procedure revisions Reordered steps to match current procedure.

Reason for Change (s):

Procedure Changes I

APPROVALS:

NOTE: Additions, deletions or I P.T. Eisenmann changes to training materials Prepared by Date must be reviewed for their possible impact to the Training Qualification Matrix. se~.

Incumbent Impact Review, Training Superintendent/Supervisor/Peer Date NOBP-TR-I104.

("Changes Not Requiring Revision" only)

RTL#A5.640U 1/2-ADM-1301.F04 Page 3 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-644 JPM TITLE: Raise Reactor Power to 10-8 Amps JPM REVISION: 2 KIA

REFERENCE:

001 A2.l1 4.4/4.7 TASK ID: 0011-014-01-013 001 AA1.05 4.3/4.2 0535-006-04-013 JPM APPLICATION: C8J REQUALIFICATION C8J INITIAL EXAM D TRAINING C8J FAULTED JPM D ADMINISTRATIVE JPM EV ALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

~ Perform D Plant Site D Annual Requa] Exam D BVT D Simulate C8J Simulator D Initial Exam D NRC D Classroom D OJT/TPE D Other:

D Training D Other:

EVALUATION RESULTS Performer Name: Performer SSN:

Time ~ Yes Allotted Actual 16 Minutes minutes Critical: ~ No Time: Time:

JPM RESULTS:

D SAT D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

RTL#A5.640U 112-ADM-1301.F04 Page 4 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET TASK STANDARD: The reactor is tripped in response to inappropriate continuous control rod motion.

RECOMMENDED Simulator STARTING LOCATION:

DIRECTIONS: You are to "Raise Reactor Power To 10-8 Amps" INITIAL CONDITIONS: A reactor startup is in progress in accordance with 20M-50A.D2, Reactor Startup From Mode 3 to Mode 2. The following conditions exist:

All shutdown bank rods are fully withdrawn.

Control Bank I'D" is at 91 steps.

The estimated critical position is 100 steps on Control Bank "D".

INITIATING CUE: The Unit Supervisor directs you to withdraw control rods to 116 steps on Bank D OR to criticality in accordance with 20M-50.4.D2, beginning at Stt:~P IV.C.9, and stabilize power at 10-8 amps on IR indication.

REFERENCES:

20M-50.4.D2, Reactor Startup From Mode 3 to Mode 2, Rev. 2 Data Sheet 3 20M-50A.F Rev 7 Filled out for 11M plot 20M-53CA.2.1.3, RCCA Control Bank Inappropriate Continuous Movement, Rev. 7 TOOLS: None HANDOUTS: 20M-50A.D2, Reactor Startup From Mode 3 to Mode 2, Rev 2, Placekept up to step IV.C.9 Filled out Data Sheet 3 (11M Plot) of20M-50A.F, Rev 7 (may cue as met) 20M-53CA.2.1.3, RCCA Control Bank Inappropriate Continuous Movement, Rev. 7 (not provided initially)

RTL#A5.640U 1I2-ADM-1301.F04 Page 5 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

DRead:

DIRECTIONS: You are to "Raise Reactor Power To 10-8 Amps" INITIAL CONDITIONS: A reactor startup is in progress in accordance with 20M-50A.D2, Reactor Startup From Mode 3 to Mode 2. The following conditions exist:

All shutdown bank rods are fully withdrawn.

Control Bank "D" is at 91 steps.

The estimated critical position is 100 steps on Control Bank "D".

INITIATING CUE: The Unit Supervisor directs you to withdraw control rods to 116 steps on Bank D OR to criticality in accordance with 20M-50A.D2, beginning at St(;:p IV.C.9, and stabilize power at 10-8 amps on IR indication.

D At this time, ask the evaluator any questions you have on this JPM.

D When satisfied that you understand the assigned task, announce "I am now beginning the JPM".

Simulate performance or perform as directed the required task.

D Point to any indicator or component you verify or check and announce your observations.

After determining the Task has been met announce" I have completed the JPM".

D Then hand this sheet to the evaluator.

RTL#A5.640U 112-ADM-130 l.F04 Page 6 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-644 JPM TITLE: Raise Reactor Power To 10-8 Amps JPM REVISION: 2 STEP STANDARD

( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "V" FOR VNSAT)::::) SIV SIMULATOR SETUP:

Initialize IC-with CB "D" Rods at 91 Steps,

Select FAST speed on NR-45

TROl XB2IOl6B= =1

IMF CRF04B Uncontrolled Rod Motion Manual

Verify CBD = 91 steps

Verify CBC at 219 steps.

Power should be ~ 6E-ll amps EVALUATOR NOTE: Provide Candidate with 11M Plot or cue that another operator is monitoring the data .

START TIME:

1. Reviews 20M-50.4.D2 and 1.1 Reviews 20M-50.4.D2 and 11M plot.

Data Sheet 3 of 20M-50.4.F (11M plot). 1.2 Det,errnines Inverse Count Rate Ratio is < 0.25.

COMMENTS:

RTL#A5.640U 1/2-ADM-1301.F04 Page 7 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-644 JPM TITLE: Raise Reactor Power To 10-& Amps JPM REVISION: 2 STEP

( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "V" FOR UNSAT)=> I SIV

2. WHEN the Inverse Count 2.1 Candidate initiates rod withdrawal at less than 25 step Rate Ratio is less than 0.25, increments.

Reduce rod withdrawal EVALUATOR CUE: As the Unit Supervisor, intervals to 25 step inform the candidate that the ICCR is less than increments.

0.25. Withdraw control rods at 5 step increments to take the reactor critical.

(Step IV.C.9.b)

COMMENTS:

3. When Status Light 3.1. Records SR counts for N31 and N32.

Annunciator A12-3B "P6 Permissive" is on (lE-lO COMMENTS:

amps), Block the SR high flux trip by performing the EVALUATOR CUE: The Reactor Engineer has following: recorded the Source Range Counts.

Record Source Range Neutron Level indicators:

[NI-NI-31A] CPS

[NI-NI-32A] CPS Step IV.C.lO.a)

RTL#A5.640U 1/2-ADM-1301.F04 Page 8 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-644 JPM TITLE: Raise Reactor Power To 10-8 Amps JPM REVISION: 2 STEP STANDARD

("e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UN SAT):::) 8/U 4.C De-energize the N31 SR 4.1C Places Source Range 'A' Block to the BLOCK High Voltage and block the position.

Train A SR High Flux trip by performing the following. COMMENTS:

Momentarily turn the switch, Source Range' A" Block to the BLOCK position (BB-B).

(Step IV.C.IO.b)

S.C De-energize the N32 SR S.lC Places Source Range 'B' Block to the BLOCK High Voltage and block the position.

Train B SR High Flux trip by performing the following. COMMENTS:

Momentarily tum the switch, Source Range 'B' Block to the BLOCK position (BB-B).

(Step IV.C.lO.c)

6. Check that both source 6.1 Verifies both source range HV MANUAL ranges HV Manual ON/OFF CONTROL switches in NORMAL. (NI Rack) switches are in the NORMAL position. COMMENTS:

(Step IV.C.l O.d)

EVALUATOR CUE: Another operator has verified that the HV MANUAL Control Switches are in NORMAL.

RTL#A5.640U 112-ADM-130 l.F04 Page 9 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-644 JPM TITLE: Raise Reactor Power To 10-8 Amps JPM REVISION: 2 STEP STANDARD

( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> S/U

7. Verify that the detector 7.1 Verifies both Source Range DETECTOR VOLTS voltmeters on both source indicate approximately zero.

range drawers indicate approximately zero volts. COMMENTS:

(Step IV.C.l O.e) EVALUATOR CUE: Another operator has verified that the Source Range DETECTOR VOLTS indicate zero volts.

8. Select both IR channels to 8.1 Places NI SYS RECORDER SEL SW lN45 and indicate on recorder NR-45. 2N45 to record IR channels N35 and N36.

(Step IV.C.ll) COMMENTS:

FAULT STATEMENT: The following step begins the alternate path portion of the JPM. Following blocking of the SR High Flux Trip, on the next rod withdrawal, the Rods will begin stepping out in an uncontrolled manner.

RTL#A5.640U 112-ADM-1301.F04 Page 10 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-644 JPM TITLE: Raise Reactor Power To 10-8 Amps JPM REVISION: 2 STEP STANDARD

( "e" Denotes CRITICAL STEP) (Indicate "s" FOR SAT or "U" FOR UNSAT)=> I SIU I 9.C Continue incremental rod 9.1 C Candidate continues withdrawing control rods to withdrawal until the reactor obtain a stable startup rate.

is critical as indicated by a stable positive startup rate EVALUATOR CUE: If asked, inform with no rod motion, on the Candidate to withdraw rods at not more than 5 intermediate range step increments to obtain a stable startup rate.

instrumentation once the prompt jump has receded. COMMENTS:

(Step IV.C.12)

10. Determine that rods are 10.1 Candidate determines from CONTROL BANK D withdrawing with NO GROUP 1 and GROUP 2 ROD POSITION indication demand signal. that rods are withdrawing with NO demand signaL COMMENTS:

11.C Trip the reactor in response 11.1 C Manually trips the reactor in response to to inappropriate continuous inappropriate continuous rod motion.

rod motion.

EXAMINER NOTE: Candidate may refer to (AOP-2.1.3, Step 1 RNO) AOP-2.1.3 and determine that a reactor trip is required based on Step 1 RNO.

COMMENTS:

EVALUATOR CUE: When the Candidate trips the reactor, state - That completes this JPM .

STOP TIME: _ _ _ _ _ _ _ __

<,;<,;\. .*. . ,.. . . . ...

RTL#AS.640U 1/2-ADM-130 l.F04 Page 1 of9 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE (JPM)

TRAINING MATERIAL TITLE: Isolate SI Accumulators During a LOCA TRAINING MATERIAL NUMBER: 2CR-654 PROGRAM TITLE: Licensed Operator Training COMPUTER CODE: 2CR-654 REVISION NUMBER: 2 TECHNICAL

REFERENCES:

20M-53.A.1.ES-1.2, Post LOCA CooldownAnd Depressurization, Issue 1C, Rev. 10 20M-ll.4.G, Venting A Safety Injection Accumulator, Rev. 21 20M-53A.l.A-5.1 , OF Plus Subcooling Based On Core Exit TCs, Rev. 1 INSTRUCTIONAL SETTING: Simulator APPROXIMATE DURATION: 15 Minutt~s PREPARED BY: P.T. Eisenmann Date PEER REVIEW BY:

Date APPROVED FOR USE:

Training Supervisor or Designee Date

RTL#A5.640U 1/2-ADM-1301.F04 Page 2 of9 Revision 1 TRAINING MATERIAL CHANGE FORM Affected Training Materials: 2CR-654 Type of Change:

[8J Changes Requiring Learning Objective Related Change? New Rev. # 2 Revision DYes [8J No D Changes Not The Change Does Not Impact Learning Existing Rev. # 1 Requiring Revision Objectives or Material Quality.

New Change #

List/Description ofChange(s):

Updated JPM to current procedure and JPM format.

Reason for Change (s):

EnhanceJPM APPROVALS:

NOTE: Additions, deletions or P.T. Eisenmann changes to training materials Prepared by Date must be reviewed for their possible impact to the Training Qualification Matrix. See Incumbent Impact Review, Training Superintendent/Supervisor/Peer Date NOBP-TR-II04.

("Changes Not Requiring Revision" only) i I

RTL#A5.640U li2-ADM-130 l.F04 Page 3 of 10 Revision 1 JPM NUMBER: 2CR-654 JPM TITLE: Isolate SI Accumulators During a LOCA JPM REVISION: 2 KJA

REFERENCE:

009 EAl.13 4,4/4,4 TASK ID: 0111-011-01-013 JPM APPLICATION: ~ REQUALIFICATION ~ INITIAL EXAM D TRAINING

~ FAULTED JPM D ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

~ Perform D D BVT

~

Plant Site Annual Requal Exam D Simulate Simulator D Initial Exam D NRC D Classroom D OJT/TPE D Other:

D Training D Other:

EVALUATION RESULTS Performer Name: Performer SSN:

Time DYes Allotted Actual 15 Minutes minutes Critical: ~ No Time: Time:

JPM RESULTS:

D SAT 0 UN SAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): . Date:

Evaluator Signature:

RTL#A5.640U 1/2-ADM-130 l.F04 Page 4 of 10 Revision 1 EVALUATOR DIRECTION SHEET TASK STANDARD: SI Accumulators 'A' and 'B' are isolated. SI Accumulator 'c' is venting.

RECOMMENDED Simulator STARTING LOCATION:

DIRECTIONS: You are to Isolate the SI Accumulators During a LOCA.

INITIAL CONDITIONS: A LOCA has occurred. The crew is performing ES-1.2, Post LOCA Cooldown and Depressurization.

INITIATING CUE: The Unit Supervisor directs you to isolate the SI accumulators in accordance with ES-I.2, Post LOCA Cooldown And Depressurization, beginning at St{~P 27.

REFERENCES:

20M-53.A.1.ES-1.2, Post LOCA Cooldown and Depressurization, Issue 1C, Rev. 10 20M-ll.4.G, Venting A Safety Injection Accumulator, Rev. 21 20M-53A.1.A-S.1, OF Plus Subcooling Based On Core Exit TCs, rev I TOOLS: Three Shorting Bars HANDOUT: 20M-53.A.1.ES-1.2, Post LOCA Cooldown and Depressurization, Issue IC, Rev. 10, place kept up to step 27.

20M-11.4.G, Venting A Safety Injection Accumulator, Rev. 21 20M-53A.1.A-S.1, OF Plus Sub cooling Based On Core Exit TCs rev. I

RTL#A5.640U 1I2-ADM-1301.F04 Page 5 of 10 Revision 1 CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

DRead:

DIRECTIONS: You are to Isolate the SI Accumulators During a LOCA.

INITIAL CONDITIONS: A LOCA has occurred. The crew is performing ES* 1.2, Post LOCA Cool down and Depressurization.

INITIATING CUE: The Unit Supervisor directs you to isolate the SI accumulators in accordance with ES* 1.2, Post LOCA Cooldown And Depressurization, beginning at Step 27.

D At this time, ask the evaluator any questions you have on this JPM.

D When satisfied that you understand the assigned task, announce flI am now beginning the JPM".

Simulate performance or perform as directed the required task.

D Point to any indicator or component you verify or check and announce your observations.

After determining the Task has been met announce" I have completed the lPM".

D Then hand this sheet to the evaluator.

RTL#A5.640U 112-ADM-130 1.F04 Page 6 of 10 Revision 1 OPERA TIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-6S4 JPM TITLE: Isolate SI Accumulators During a LOCA JPM REVISION: 2 UNSAT)~ I S/U I STEP STANDARI)

( "c" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR SIMULATOR SETUP:

Initialize simulator to any Mode 1 IC.

Insert SBLOCA @ 500 gpm.

Progress through EOP set up until Step 27 of ES-l.2.

PZR Leve:1 needs to be > 17% and RCS Subcooling needs to be > 41F (non adverse containment).

Insert VLV-SIS068 (override SIS*MOV86SC in the open position).

NOTE: This JPM takes significant setup work and requires careful attention to C/D rate, AFW flowrate and other dynamic items.

EVALUATOR NOTE:

RCS pressure may drop low enough to begin injecting accumulators. Ensure Shorting Bars are available.

J START TIME: ------------------

1. Review procedure. 1.1 Reviews 20M-S3A.l.ES-l.2, Post LOCA Cool down and Depressurization.

COMMENTS:

2. RCS subcooling based on core 2.1 Verifies RCS subcooling on VB-B (2RCS*YIOOI or exit TCs - GREATER THAN 2RCS*YROOl) or the PCS.

SUBCOOLING LISTED ON 2.2 Compares existing value to Attachment A-S.ll.

ATTACHMENT A-S.l.

2.3 Determines existing RCS sub cooling is GREATER than Attachment A**S.l minimum required value.

COMMENTS:

RTL#A5.640U 1I2-ADM-1301.F04 Page 7 of 10 Revision I OPERA TIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-654 JPM TITLE: Isolate SI Accumulators During a LOCA JPM REVISION: 2 STEP STANDARD

( "C" Denotes CRITICAL STEP) (Indicate "s" FOR SAT or "un FOR UNSAT)=> I S/U I

3. PRZR level- GREATER THAN 3.1 Verifies [2RCS-LI459A, 460, and 461] are greater 38%. than 38%.

COMMENTS:

4. Power to [2SIS*MOV865A, B, 4.1 Verifies [2SIS*MOV865A, B, q red lights - LIT and q - AVAILABLE. green lights - NOT LIT.

COMMENTS:

EVALUATOR CUE:

Shorting Bars will be needed in the next step. When requested, Role-play the Shift Manager and supply the shorting bars.

5.C Insert Shorting Bars and closes 5.1 Contacts Shift manager and requests shorting bars.

[2SIS*MOV865A, B, q.

5.2C Inserts into [2SIS*MOV865A] jack.

5.3C Inserts into [2SIS*MOV865B] jack.

5.4 Inserts into [2SIS*MOV865q jack.

COMMENTS:

RTL#A5.640U 112-ADM-1301.F04 Page 8 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-654 JPM TITLE: Isolate SI Accumulators During a LOCA JPM REVISION: 2 STEP STANDARD

( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)~ Stu I

i I FAULT STATEMENT:

Alternate path begins here: [2SIS*MOV865C] will NOT CLOSE in the following step.

EVALUATOR NOTE:

Accumulator isolations may be done in any order.

6.C Close [2SIS*MOV865A, B, 6.1C Places [2SIS*MOV865A, B, C] CS to CLOSE.

C].

6.2 Verlfies Green lights LIT and Red lights - NOT LIT for [2SIS*MOV865A, B].

6.3 Verifies Red light LIT and Green light - NOT LIT for [2SIS*MOV865C].

COMMENTS:

7. Vent any unisolated 7.1 Re£ers to 20M-l1.4.G to vent 2SIS*TK21 C.

accumulator. Refer to 20M 11.4.0, "Venting A Safety EVALUATOR CUE:

Injection Accumulator". If necessary, Role-play the Unit Supervisor and direct the Candidate to perform Section F for direct venting to containment.

COMMENTS:

RTL#A5.640U 112-ADM-130 1.F04 Page 9 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-654 JPM TITLE: Isolate SI Accumulators During a LOCA JPM REVISION: 2 STEP STANDARD

( "c" Denotes CRlTICAL STEP) (Indicate "s" FOR SAT or "U" FOR UNSAT)=> SIU

8. If containment is not under 8.1 No action required.

vacuum, close [2SIS*367 (369)

(399)] Accumulator COMMENTS:

[2SIS*TK21A (B), (C)] Level Isolation to prevent educting liquid into the vent line during venting.

9. Check closed, [2GNS*AOVI01 9.1 Verifies [2GNS*AOVI01-1 and 101-2J Green lights 1 (101-2), SI ACC Nitrogen ~ LIT and Red lights - NOT LIT Makeup Outside (Inside) Cnmt Isol Vlv. COMMENTS:

10.C Open [2GNS*SOV853A(D) 10.1 C Places [2GNS*SOV853C OR F] CS to OPEN.

(853B (E>> (853C (F>>] 21A 10.2 Verifies Red light ~ LIT and Green light - NOT LIT.

(B) (C) SI Accumulator Nitrogen Makeup Vlv.

COMMENTS:

l1.C Open [2GNS*SOV854A II.IC Places [2GNS*SOV854A OR B] CS to OPEN.

(854B)] SI Accumulator Vent 11.2 Verifies Red light LIT and Green light NOT LIT.

Vlv until the Accumulator is lowered to the desired value, 11.3 Verifies [2SIS-PI929 & 931] indicate accumulator then close [2GNS*SOV854A pressure is lowering.

(854B)].

EVALUATOR NOTE:

Candidate may refer to PCS to monitor accumulator pressure.

COMMENTS:

RTL#A5.640U 112-ADM-130 I.F04 Page 10 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-654 JPM TITLE: Isolate SI Accumulators During a LOCA JPM REVISION: 2 STEP STANDARD

( "c" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSA T)~

EVALUATOR CUE:

When accumulator pressure begins to lower, terminate JPM.

That completes this JPM.

STOP TIME:

RTL#A5.640U 1/2-ADM-1301.F04 Page 1 of 11 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE (JPM)

TRAINING MATERIAL TITLE: Perfonn Manual Makeup to the Charging Suction TRAINING MATERIAL NUMBER: 2CR-581 PROGRAM TITLE: Licensed Operator Training COMPUTER CODE: 2CR-581 REVISION NUMBER: 6 TECHNICAL

REFERENCES:

20M-7.4.N, Blender Manual Makeup Operations, Rev. 13 INSTRUCTIONAL SETTING: Simulator APPROXIMATE DURATION: 15 Minutes PREPARED BY: P.T. Eisenmann Date PEER REVIEW BY:

Date APPROVED FOR USE:

Training Supervisor or Designee Date

RTL#A5.640U 1/2-ADM-1301.F04 Page 2 of II Revision 1 TRAINING MATERIAL CHANGE FORM Affected Training Materials: 2CR-581 Type of Change:

I:8J Changes Requiring Learning Objective Related Change? New Rev. #6 Revision DYes I:8J No D Changes Not The Change Does Not Impact Learning Existing Rev. # 5 Requiring Revision Objectives or Material Quality.

New Change #

List/Description ofChange(s):

Updated for current revision of the procedures.

Reason for Change (s):

JPM Enhancement.

APPROVALS:

P.T. Eisenmann NOTE: Additions, deletions or Prepared by Date changes to training materials must be reviewed for their possible impact to the Training Training Superintendent/SupervisorlPeer Date Qualification Matrix. See

("Changes Not Requiring Revision" only) Incumbent Impact Review, NOBP-TR-II04.

RTL#A5.640U li2-ADM-130 1.F04 Page 3 of 11 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE (JPM)

JPM NUMBER: 2CR-581 JPM TITLE: PerfoITn Manual Makeup to the Charging Suction JPM REVISION: 6 KIA

REFERENCE:

004A4.12 3.8/3.3 TASK ID: 0071-025-01-013 JPM APPLICATION: [2J REQUALIFICATION [2J INITIAL EXAM o TRAINING

[2J FAULTED JPM o ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

0 Plant Site

~ Perform o Simulate [2J Simulator 0 Classroom B

0 Annual Requal Exam Initial Exam OJT/TPE B BVT NRC 0 Other:

0 Training 0 Other:

EVALUATION RESULTS Performer Name: PerfoTIner SSN:

Time P Yes Allotted 15 Minutes Actual minutes Critical: [2J No Time: Time:

JPM RESULTS:

D SAT D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

RTL#A5.640U 1/2-ADM-1301.F04 Page 4 of 11 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE (JPM)

JPM NUMBER: 2CR-581 JPM TITLE: Perfonn Manual Makeup to the Charging Suction JPM REVISION: 6 EVALUATOR I)IRECTION SHEET TASK STANDARD: Perfonn control board manipulations and calculations to perfonn a manual blender makeup to the VCT in accordance with 20M-7.4.N, "Blender Manual Makeup Operations".

Makeup secured after discovery of no boric acid flow.

RECOMMENDED Simulator STARTING LOCATION:

DIRECTIONS: Perfonn a manual makeup to the Charging Pump Suction.

INITIAL CONDITIONS:

The plant is in Mode I.

The in service Boric Acid Tank concentration is 7487 ppm.

VCT level is currently 22%.

All initial conditions are satisfied.

INITIATING CUE: Your supervisor directs you to raise VCT level to 42% at 75 gpm, by perfonning a manual makeup to the VCT in accordance with 20M 7.4.N, "Blender Manual Makeup Operations", beginning at step IV.A.6.

REFERENCES:

20M-7.4.N, Blender Manual Makeup Operations, Rev. 13 TOOLS: None HANDOUT: 20M-7.4.N, Blender Manual Makeup Operations, Rev. 13, place kept up to Step IV. 6.

RTL#A5.640U 1I2-ADM-1301.F04 Page 5 of 11 Revision 1 CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

DRead:

DIRECTIONS: Perform a manual makeup to the Charging Pump Suction.

INITIAL CONDITIONS:

The plant is in Mode 1.

The in service Boric Acid Tank concentration is 7487 ppm.

VCT level is currently 22%.

All initial conditions are satisfied.

INITIATING CUE: Your supervisor directs you to raise VCT level to 42% at 75 gpm, by performing a m,mual makeup to the VCT in accordance with 20M 7.4.N, "Blender Manual Makeup Operations", beginning at step IV.A.6.

D At this time, ask the evaluator any questions you have on this JPM.

D When satisfied that you understand the assigned task, announce "I am now beginning the lPM".

Simulate performance or perform as directed the required task.

D Point to any indicator or component you vierify or check and announce your observations.

After determining the Task has been met announce" I have completed the JPM".

D Then hand this sheet to the evaluator.

RTL#A5.640U 1I2-ADM-1301.F04 Page 6 of 11 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-581 JPM TITLE: Perforrn Manual Makeup to the Charging Suction JPM REVISION: 6 STANDARD (Indicate "s" FOR SAT or "U" FOR UNSAT)=>

START TIME: ._ _ _ _ _ _ __

EVALUATOR NOTE: Simulator setup:

EVALUATOR NOTE: - Any Mode 1 IC.

This is a FAULTED JPM. - Expert command to set VCT level to 22%: Set When makeup is started, no A VCTLIQ=6720 boric acid flow is present. - Mark in service BAST 7487 PPM; (RCS Cb=1460).

Set BA & Total flow totalizers to ZERO.

To fai12CHS*FCVl13A as-is (shut), go to Valves tab and select VLV-BATOIO, Select O-Fail As Is.

Set 2CHS*FCV114A Potentiometer for 100 gpm flow rate.

1. Reviews 20M-7.4.N, 1.1 Reviews 20M-7.4.N, "Blender Manual Makeup "Blender Manual Makeup Operation.

Operation.

COMMENTS:

EVALUATOR NOTE: Candidate may perform flow setpoint calculations prior to making any control manipulations.

2. Place Boric Acid Makeup 2.1 Places Boric Acid Makeup Blender Control switch in Blender Control switch in STOP position.

Stop.

2.2 Verifies Green Light - LIT, Red Light - NOT LIT.

COMMENTS:

RTL#A5.640U 1/2-ADM-1301.F04 Page 7 of 11 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-581 JPM TITLE: Perform Manual Makeup to the Charging Suction JPM REVISION: 6 STEP STANDARD

( "c" Denotes CRITICAL STEP) (Indicate "8" FOR SAT or "V" FOR VNSAT)=> [ SIV [

EVALUATOR CUE: Ifasked, provide BAST boron of7487 ppm and RCS boron of 1460 ppm.

3.C Determine desired boric acid 3.1 C Calculates boric acid flow:

flow.

1460ppmX75gpm 14.62gpm 7487ppm COMMENTS:

4.C Adjust [2CHS*FCV113A] 4.1 C Calculates the desired flow setpoint:

Boric Acid to Blender to the calculated setpoint. 14.62gpm xl 00 = 366 4gpm 4.2C Adjusts [2CHS*FCVl13A] for the desired flow setpoint, 366 units ::!:5 units.

COMMENTS:

i

RTL#AS.640U 112-ADM-130 1.F04 Page 8 of 11 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-581 JPM TITLE: Perforrn Manual Makeup to the Charging Suction JPM REVISION: 6 STEP STANDARD

( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> S/u S.C Set Boric Acid Flow to S.lC Adjusts [2CHS-FQIS 113] Boric Acid Flow to Blender Flow Totalizer. Blender Flow Totalizer to the desired value.

S.2C Depresses "RESET" on 2CHS-FQISl13.

EVALUATOR NOTE: Batch amounts are at the operators discretion. Total volume change is approximately 280 gallons. Candidate must set the appropriate amount ofBA volume for the batch amount. If performing full makeup (~280 gals) then the amount of BA is:

14.62 gpm X (280gals I 75 gpm) = 54.6 gaL COMMENTS:

6.C Adjust [2CHS*FCV114A] 6.1C Adjusts [2CHS*FCVI14A] for 75 gpm, setpoint. (75 gpml16) xl00 = 468 units +/-S units.

COMMENTS:

i I

RTL#A5,640U l/2-ADM-130 1,F04 Page 9 of 11 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-581 JPM TITLE: Perform Manual Makeup to the Charging Suction JPM REVISION: 6 STEP STANDARD

( "c" Denotes CRITICAL STEP) (Indicate "s" FOR SAT or "U" FOR UN SAT)=>

7.C Set [2CHS-FQISI68] Total 7.1 C Adjusts Total Makeup From Blender Flow Totalizer Makeup From Blender Flow to the desired value (approximately 280 gallons)

Totalizer to the desired total volume in gallons of makeup 7.2C Depresses "RESET" on 2CHS-FQIS168.

water to be added.

EVALUATOR NOTE: Batch amounts are at the operator's discretion. Total volume change is approximately 280 gallons (-14-15 gal/%).

COMMENTS:

8. Adjust [2CHS *HIC 168] 8.1 Adjusts [2CHS*HICI68] to 75 gpm, Blender Total Flow Auto (75 gpml16) x 100 == 468 units units.

Setpoint.

COMMENTS:

9. Note flow totalizer indication 9.1 Notes the Boric Acid Flow to Blender Flow Totalizer and adds it to the gallon set value on 2CHS*FQISI13 and adds the Boric Acid on the batch integrators for volume previously calculated (54.6 gallons) 2CHS*FQIS 113 and 2CHS*FQIS168, 9.2 Notes the Blender Total Flow value on 2CHS*FQIS168 and adds the Total Volume previously calculated (280 gallons)

COMMENTS:

RTL#A5.640U 112-ADM-130 I.F04 PagelOofll Revision 1 OPERAnONS JOB PERFORM ANCE MEASURE JPM NUMBER: 2CR-581 JPM TITLE: Perform Manual Makeup to the Charging Suction JPM REVISION: 6 STEP STANDARD

( "c" Denotes CRITICAL STEP) (Indicate "s" FOR SAT or "u" FOR UNSAT)::::) I S/U I

10. Verify a Reactor Coolant 10.1 Verifies that RCS flow is?: 3000 gpm flow by Pump is operating in an obsc~rving RCP operation or flow indications.

uniso1ated loop and has ?:

3000 gpm flow through the 10.2 Records information in the Narrative Log.

core and records the commencement of makeup EVALUATOR CUE: Inform the candidate that another and flow verification in the operator will make the Narrative Log entry.

Narrative Log.

COMMENTS:

11. Verify the inservice Boric 11.1 Verifies the in-service Boric Acid Transfer Pump is Acid Pump in Auto. in AUTO.

COMMENTS:

12.C Open [2CHS*FCVI13B], 12.1 C Places [2CHS*FCVl13B] control switch to OPEN Boric Acid Blender Disch to position.

Chg Pumps (BB-A) 12.2 Verifies Red Light -LIT and Green Light - NOT LIT COMMENTS:

13.C Place Mode Selector in 13.1C Places the Mode Selector Switch in MAN position.

MAN. (BB-A)

COMMENTS:

I

RTL#A5.640U 1I2-ADM-130 l.F04 Page 11 of 11 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-581 JPM TITLE: Perform Manual Makeup to the Charging Suction JPM REVISION: 6 STEP STANDARD

( "c" Denotes CRITICAL STEP) (Indicate "s" FOR SAT or "U" FOR UNSAT)=> SIU 14.C Place Boric Acid Makeup 14.lC Places Boric Acid Makeup Blender Control switch to Blender Control switch to START position.

Start.

14.2 Verifies Boric Acid Transfer Pump that is in AUTO starts Red Light LIT, Green Light - NOT LIT.

COMMENTS:

FAULT STATEMENT:

Alternate path begins here. Candidate must take manual action to secure the dilution after discovering that no boric acid flow exists. It is expected that the operator will recognize and terminate wlin -1 min (-5-6% level rise) 15.C Verify proper operation at 15.1 Verifies Boric Acid to Blender and Total MIU Flow recorder [2CHS-FRl13] From Blender on [2CHS-FRl13J.

(VB-A).

15.2 Recognizes boric acid flow is Zero (0) GPM.

15.3C Places Boric Acid Makeup Control Switch to STOP position prior to VCT level reaching 28%.

COMMENTS:

! EVALUATOR CUE: That completes this JPM .

STOP TIME: _ _ _ _ _ _ __

RTL#A5.640U 1I2-ADM-1301.F04 Page 1 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE (JPM)

TRAINING MATERIAL TITLE: Transfer Bus 2AE from Emergency to Normal FeedlBus 2A TRAINING MATERIAL NUMBER: 2CR-597 PROGRAM TITLE: Licensed Operator Training (Retraining)

COMPUTER CODE: 2CR-597 REVISION NUMBER: o TECHNICAL

REFERENCES:

20M-36.4.E, Transferring 4KV Emergency Bus 2AE to Bus 2A, Revision 10 20M-36.4.ACS Diesel Gen 2-1 Electrical Fault, Revision 10 INSTRUCTIONAL SETTING: Simulator APPROXIMATE DURATION: 15 Minutes PREPARED BY: P. T. Eisenmann Date PEER REVIEW BY:

Date APPROVED FOR USE:

Training Supervisor or Designee Date

RTL#A5.640U }/2*ADM*1301.F04 Page 2 of 10 Revision 1 TRAINING MATERIAL CHANGE FORM Affected Training Materials: 2CR-597 Type of Change:

C8J Major Learning Objective Related Change? New Rev. #0 DYes C8J No D Minor The Change Does Not Impact Learning Existing Rev. #

Objectives or Material Quality.

New Change #

List/Description of Change(s):

1. New, alternate path JPM, based upon 2CR-097.

2. New number is 2CR-597 Reason for Change (s):

1. Expand Alternate path JPM bank.

APPROVALS:

NOTE: Additions, del{~tions or P. T. Eisenmann changes to training materials must be reviewed for their Prepared by Date possible impact to the Training Qualification Matrix. See Incumbent Impact Review, Training Superintendent/Supervisor/Peer Date NOBP-TR- 1104.

(Minor Changes Only)

RTL#A5.640U 1/2-ADM-1301.F04 Page 3 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-597 JPM TITLE: Transfer Bus 2AE from Emergency to Normal Feed/Bus 2A JPM REVISION: 0 KIA

REFERENCE:

064A2.09 3.1/3.3 TASK ID: 0362-007-01-013 JPM APPLICATION: k8J REQUALIFICATION k8J INITIAL EXAM D TRAINING k8J FAULTED JPM D ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

k8J Perform D Plant Site D Annual Requal Exam r8J BVT D Simulate r8J Simulator r8J Initial Exam D NRC D Classroom D OJTITPE D Other:

D Training D Other:

EVALUATION RESULTS Performer Name: Performer SSN:

Time D Yes Allotted 15 minutes Actual minutes Critical: r8J No Time: Time:

0 SAT JPM RESULTS:

0 UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

~

RTL#A5.640U 1/2-ADM-130 1.F04 Page 4 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET TASK STANDARD: Bus 2AE is energized from Bus 2A. The 2-1 EDG output breaker is open and the EDG has been shutdown.

RECOMMENDED SIMULATOR STARTING LOCATION:

DIRECTIONS: You are to Transfer Bus 2AE from Emergency to Normal Feed/Bus 2A.

INITIAL CONDITIONS: Breaker 2AlO has spuriously tripped open. All normal4KV busses are energized from USST's 2C and 2D. The 2-1 EDG is running and carrying loads on the 2AE Bus. The 4KV normal to emergency tie breakers, 2AlO and 2E7, are open. The relay crew has replaced a defective relay on breaker 2AlO.

INITIATING CUE: Your supervisor directs you to transfer Bus 2AE to Bus 2A and to open the 2-1 EDG Output Breaker in accordance with 20M-36.4.E.

REFERENCES:

20M-36.4.E, Revision 10, Transferring 4KV Emergency Bus 2AE to Bus 2A.

20M-36.4.ACS Diesel Gen 2-1 Electrical Fault TOOLS: None HANDOUT: 20M-36.4.E, Revision 10, Transferring 4KV Emergency Bus 2AE to Bus2A 20M-36.4.ACS Diesel Gen 2-1 Electrical Fault (Do NOT provide initially)

RTL#A5.640U 1I2-ADM-130 l.F04 Page 50[10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

DRead:

DIRECTIONS: You are to Transfer Bus 2AE from Emergency to Normal FeedlBus 2A INITIAL CONDITIONS: Breaker 2AI0 has spuriously tripped open. All normal4KV busses are energized from USST's 2C and 2D. The 2-1 EDG is running and carrying loads on the 2AE Bus. The 4KV normal to emergency tie breakers, 2A 10 and 2E7, are open. The relay crew has replaced a defecti ve relay on breaker 2A 10.

INITIATING CUE: Your supervisor directs you to transfer Bus 2AE to Bus 2A and to open the 2-1 EDG Output Breaker in accordance with 20M-36.4.E.

D At this time, ask the evaluator any questions you have on this JPM.

D When satisfied that you understand the assigned task, announce "I am now beginning the JPM" .

Simulate performance or perform as directed the required task.

D Point to any indicator or component you v1erify or check and announce your observations.

After determining the Task has been met announce "I have completed the JPM".

D Then hand this sheet to the evaluator.

RTL#A5.640U 1/2-ADM-1301.F04 Page 6 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-597 JPM TITLE: Transfer Bus 2AE from Emergency to Normal Feed/Bus 2A JPM REVISION: 0 STEP

("e" Denotes CRITICAL STEP)

I STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT)=> SIU I

..*.**.**... ...>~

START TIME: ~~_~~_~_

EVALUATOR NOTES: Insert BKR-HIVOI to trip 2AlO, wait for D/G sequencer to complete, then clear BKR-HIVOI, allow plant to stabilize.

Make annunciator A8-4C alarm when EDG load is

<= 1000 KW by setting Trigger 1 as XX8D014M

<= 1000 with command as Ensure Sync Scope rotating in SLOW direction.

1MI' A8-4C-Y2955D (0 0) 0 and SNAP.

ENSURE "B" TRAIN PROTECTED PLACARD is

1. Review the procedure. 1.1 Reviews provided procedure, 20M-36.4.E.

EVALUATOR NOTE: Provide candidate with copy of procedure 20M-36.4.E.

COMMENTS:

2.C Close breaker 2AI0, 4KV 2.1C Plaees breaker 2AlO control switch in the CLOSE Bus 2A to Emergency Bus position.

2AE.

2.2 Verifies the RED light above breaker 2A 10 control switch LIT and WHITE Light NOT LIT.

EVAIJUATOR CUE: Act as another operator and perform the independent verification.

COMMENTS:

RTL#A5.640U 112-ADM-1301.F04 Page 7 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-597 JPM TITLE: Transfer Bus 2AE from Emergency to Normal Feed/Bus 2A JPM REVISION: 0 STEP STANDARD

( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> I 8/U I 3.C Place the 2-1 Diesel 3.1C Places 2-1 EMERG GEN SYNCHRONIZING SEL Generator synchronizing SW in the Bus 2A position.

switch in the Bus 2A position. COMMENTS:

4.C Adjust 2-1 EDG until the 4.1 Observes the 2-1 Emergency Diesel Generator synchroscope needle is synehroscope on the Vertical Board and notes it is rotating in the SLOW rapidly rotating in the SLOW direction.

DIRECTION.

4.2C Adjusts the 2-1 EMERG GEN GOVERNOR control switch to the RAISE position.

4.3 Verifies the synchroscope rotating slowly in the fast direction.

COMMENTS:

RTL#A5.640U l/2-ADM-130 1.F04 Page 8 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-597 JPM TITLE: Transfer Bus 2AE from Emergency to Normal Feed/Bus 2A JPM REVISION: 0 STEP STANDARD

( "c" Denotes CRITICAL STEP) (Indicate "s" FOR SAT or "U" FOR UNSAT):::) I SIU I

5. Adjust 2-1 Diesel Generator 5.1 Locates 2-1 EMERG GEN VOLTS meter and voltage to be slightly higher compares it to 4KV Bus 2A VOLTS meter.

than Bus 2A voltage by using voltage adjust switch. 5.2. Verifies Diesel Generator volts slightly higher than bus volts and adjusts Emergency Generator 2-1 Voltage.

COMMENTS:

6.C Close breaker 2E7 when 6.1 Monitors the 2-1 Emergency Diesel Generator synchroscope, rotating synchroscope on the Vertical Board.

SLOWLY in FAST DIRECTION. 6.2C Momentarily places breaker 2E7 control switch in the CLOSE position when the synchroscope is at the 12 o'clock.

6.3 Verifies the RED light above breaker 2E7 control switch LIT and WHITE light NOT LIT.

COMMENTS:

7. Place the 2-1 EDG 7.1 Places 2-1 EMERG GEN SYNCHRONIZING SEL synchronizing Switch in SW in the OFF position.

OFF.

COMMENTS:

I

RTL#A5.640U 1I2-ADM-1301.F04 Page 9 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-597 JPM TITLE: Transfer Bus 2AE from Emergency to Nonnal Feed/Bus 2A JPM REVISION: 0 STEP STANDARD

( "e" Denotes CRITICAL STEP) (Indicate "s" FOR SAT or "U" FOR UNSAT)=> Stu I

8. Maintain generator power 8.1 Adjusts 2-1 EMERG GEN VOLTGE ADJUST as factor between 0.8 and 1.0 needed to maintain between 0.8 and 1.0 lagging PF as lagging, as indicated on indicated on Power Factor meter on VB-C.

Emergency Generator Power Factor, by adjusting COMMENTS:

Emergency Generator 2-1 Voltage Adjust.

FAULT STATEMENT: At this point the JPM alternate path begins. Atmunciator A8-4C, "DIESEL GEN 2-1 ELECTRICAL FAULT" will annunciate when EDG 2-1 loading reaches 1000 KW. Computer alann DO 2-1 DIFF will also be received. Candidate should respond to ARP and Trip the 2-1 EDG and open ACB 2E10 which failed to automatically occur.

EVALVATOR CUE: As Unit Supervisor, direct candidate to reduce load to 100 KW over a 5 minute period.

9.C Reduce load on the EDG to 9.1 C Intennittently places the 2-1 EMERG GEN

<100KW. GOVERNOR control switch in the LOWER Position.

9.2 Monitors the following parameters during the load decrease:

a. EMERG GEN 2-1 VOLTS

b. EMERG GEN 2-1 POWER FACTOR

c. EMERG GEN 2-1 W ATIS 9.3 Intennittently places the 2-1 EMERG GEN VOLT ADJUST switch in LOWER.

COMMENTS:

I

RTL#A5.640U 1/2-ADM-130 l.F04 Page 10 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-597 JPM TITLE: Transfer Bus 2AE from Emergency to Normal Feed/Bus 2A JPM REVISION: 0 STEP STANDARD

( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UN SAT)=> 8/U

10. Annunciator A8-4C, 10.1 Acknowledges the alarm and responds by "DIESEL GEN 2-1 reviewing the ARP for A8-4C.

ELECTRICAL FAULT",

alarms due to 2-1 DG DIFF, 10.2 Determines the alarm is indicative that an EDG (Y2955D) Trip should have occurred.

COMMENTS:

EVALUATOR NOTE: Provide the candidate a copy of the ARP for A8-4C once it is located.

l1.C Trips 2-1 EDG and manually 11.1 Momentarily places breaker 2E 10 control switch in opens output breaker 2EIO. TRIP.

11.2. Verifies the WHITE light above breaker 2EIO control switch is ON.

11.3C Manually Trips EDG 2-1 by pushing the stop pushbuttons.

11.4 Verifies EDG 1 is tripped by observing d<~creasing RPM's on BB-C tachometer.

COMMENTS:

EVALUATOR CUE: After the candidate trips the EDG and opens the output breaker state, That completes this JPM.

'.i"; <,

" ,.; .,;;.>;~(iI ', . .' . . ;*** <;

STOP TIME:

RTL#A5.640U 112-ADM-1301.F04 Page 1 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE PPM)

TRAINING MATERIAL TITLE: Containment Spray Manual Actuation- SWS and QSS Valve Malfunctions TRAINING MATERIAL NUMBER: 2CR-656 PROGRAM TITLE: Licensed Operator Training COMPUTER CODE: 2CR-656 REVISION NUMBER: o TECHNICAL

REFERENCES:

20M-53A.l.A-0.ll, "Verification Of Automatic Actions", Issue IC, Rev 6.

20M-53A.l.A-0.5, "Containment Isolation Phase B Checklist", Issue 1C, Rev. 2 INSTRUCTIONAL SETTING: Simulator APPROXIMATE DURATION: 10 Minutes PREPARED BY: P.T. Eisenmann Date PEER REVIEW BY:

Date APPROVED FOR USE:

Training Supervisor or Designee Date

RTL#A5.640U 1/2-ADM-1301.F04 Page 2 of 10 Revision 1 TRAINING MATERIAL CHANGE FORM Affected Training Materials: 2CR-656 Type of Change:

l8] Changes Requiring Learning Objective Related Change? New Rev. #0 Revision Yes l8]No D Changes Not The Change Does Not Impact Learning Existing Rev. #

Requiring Revision Objectives or Material Quality.

New Change #

List/Description of Change(s):

New alternate path JPM based upon 2CR-573.

Reason for Change (s):

Add to alternate path JPM banle APPROVALS:

I NOTE: Additions, deletions or P.T. Eisenmann changes to training materials Prepared by Date must be reviewed for their possible impact to the Training Qualification Matrix. See Incumbent Impact Review, Training Superintendent/Supervisor/Peer Date NOBP-TR-I104.

("Changes Not Requiring Revision" only)

RTL#A5.640U 1I2-ADM-130 l.F04 Page 3 of 10 Revision 1 JPM NUMBER: 2CR-656 JPM TITLE: Containment Spray Manual Actuation- SWS and QSS JPM REVISION: 0 Valve Malfunctions KIA

REFERENCE:

026 A2.03 4.114.4 TASK ID: 0011-066-01-013 026 A2.04 3.9/4.2 JPM APPLICATION: I;g] REQUALIFICA TION I;g] INITIAL EXAM D TRAINING I;g] FAULTED JPM D ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

~

~ Perform D Simulate Plant Site Simulator tj Annual Requal Exam Initial Exam tj BVT NRC D Classroom D OJT/TPE D Other:

D Training D Other:

EVALUATION RESULTS Performer Name: Performer SSN:

Time 1:1 Yes Allotted 10 Minutes Actual minutes Critical: I;g] No Time: Time:

JPM RESULTS:

D SAT D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

RTL#A5.640U 1/2-ADM-1301.F04 Page 4 of 10 Revision 1 EVALUATOR DIRECTION SHEET TASK STANDARD: Manually initiate CIB, align both trains of SWS to RSS heat exchangers and isolate SWS to CCP heat exchangers.

RECOMMENDED Simulator STARTING LOCATION:

DIRECTIONS: You are to Verify Containment Spray Actuation.

INITIAL CONDITIONS:

A reactor trip and safety injection have occurred due to a large break LOCA.

The actions of E-O are being performed.

INITIATING CUE: The Unit Supervisor directs you to perform Attachment A-O.ll, HVerification Of Automatic Actions", Step 7 to check CIB and Containment Spray status.

REFERENCES:

20M-53A.l.A-O.l1, "Verification Of Automatic Actions", Issue I C, Rev. 6 20M-53A.l.A-O.5, "Containment Isolation Phase B Checklist", Issue IC, Rev. 2 TOOLS: None HANDOUT: 20M-53A. l.A-O. 11, "Verification Of Automatic Actions", Issue IC, Rev. 6, place kept up to step 7.

20M-53A.l.A-O.5, "Containment Isolation Phase B Checklist", Issue IC, Rev. 2

RTL#A5.640U 112-ADM-130 1.F04 Page 5 of 10 Revision 1 CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

DRead:

DIRECTIONS: You are to Verify Containment Spray Actuation.

INITIAL CONDITIONS:

A reactor trip and safety injection have occurred due to a large break LOCA.

The actions of E-O are being performed.

INITIATING CUE: The Unit Supervisor directs you to perform Attachment A-O.II, "Verification Of Automatic Actions", Step 7 to check CIB and Containment Spray status.

D At this time, ask the evaluator any questions you have on this JPM.

D When satisfied that you understand the assigned task, announce "1 am now beginning the JPM".

Simulate performance or perform as directed the required task.

D Point to any indicator or component you verify or check and announce your observations.

After determining the Task has been met announce \I I have completed the JPM".

D Then hand this sheet to the evaluator.

RTL#A5.640U 1I2-ADM-130 l.F04 Page 6 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-656 JPM TITLE: Containment Spray Manual Actuation JPM REVISION: 0 STEP STANDARD

( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=>

SIMULA TOR SETUP: Initialize to any Mode 1 IC.

Insert MALF RCS03A Insert MALF PPL09A Insert MALF PPL09B Train A CS - XAlI003A and XAlI004A OFF Valve Malfunctions- CS:

2SWS*MOVI06A VLV-SWS028(1) Close XAlI084C 2SWS*MOVI03A VLV-SWS018(2) Open XAII102P 2SWS*MOV106B VLV-SWS029(1) Close XA2I068C 2SWS*MOV103B VLV-SWS019(2) Open XA2I081P Raise RWST level to avoid Transfer to Recirc Signal.

Secure all RCPs. Allow simulator to run until majority of alarms clear and snap into IC.

EVALUATOR CUE:

When the candidate is ready to begin the JPM, Place the simulator to RUN.

START TIME: ---------

1. Reviews procedure. 1.1 Reviews 20M-53A.l.A-O.ll, "Verification Of Automatic Actions".

COMMENTS:

RTL#A5.640U 1I2-ADM-130 1.F04 Page 7 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-656 JPM TITLE: Containment Spray Manual Actuation JPM REVISION: 0 STEP STANDARD

( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "V" FOR VNSAT)=> I SIV I

2. Containment pressure - HAS 2.1 Determines that containment pressure has NOT REMAINED LESS THAN 11 remained less than 11 psig by checking any of the PSIG. following:

AI-2H, "CONTAINMENT ISOLATION PHASE B" in alarm.

2LMS*PR950, Containment Pressure Recorder indicates greater than II psig.

Panel 464, High 3 CHM 1 Pressure CH I IV Lights

-LIT.

2LMS-PI950, 951, 952, and 953 indicate greater than 11 psig.

COMMENTS:

NOTE: It is acceptable that the candidate completes this step out of order and may chose to perform 20M 53A.l.A-O.5, "Containment Isolation Phase B Checklist".

3. Check BLUE eIB marks - LIT. 3.1 Checks components properly aligned and determines CIB components not positioned as required, and CIB NOT actuated.

COMMENTS:

I

RTL#A5.640U 112-ADM-1301.F04 Page 8 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-656 JPM TITLE: Containment Spray Manual Actuation JPM REVISION: 0 STEP STANDARD

("C" Denotes CRITICAL STEP) (IJ1cli~Rt~ "s" FOR SAT or HU" FOR UNSAT)=> SIU FAUl,T STATEMENT I EVALUATOR NOTE:

Either train switches may be actuated first, only HB" train switches will actuate. 2SWS*MOV103(s) and 2SWS*MOVI06(s) will not automatically actuate.

4.C IF NOT, THEN manually 4.1 Simultaneously ROTATES (Clockwise) both Train initiate CIB (both switches for "A" CIB switches to ACTUATE position.

both trains).

4.2C Simultaneously ROTATES (Clockwise) both Train "B" CIB switches to ACTUATE position.

COMMENTS:

5. Check BLUE CIB marks - LIT. 5.1 Candidate checks all indicating lights with BLUE CIB marks LIT.

5.2 Determines 2SWS*MOVI06A / Band 2S\VS*MOVI03A / B not aligned.

EVALUATOR NOTE:

If requested, provide Candidate a copy of Attachment A-OS COMMENTS:

i

RTL#A5.640U 1/2-ADM-130 I.F04 Page 9 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-656 JPM TITLE: Containment Spray Manual Actuation JPM REVISION: 0 STEP STANDARD

( "c" Denotes CRITICAL STEP) (Indicate "s" FOR SAT or "U" FOR eNSAT)=> I Stu I 6.C IF cm NOT actuated, THEN 6.1C Plaees 2SWS*MOVI06A control switch to CLOSE.

manually align equipment. If necessary, refer to Attachment 6.2 Verifies GREEN light - LIT and RED light NOT A-O.5, "Containment Isolation LIT.

Phase B Checklist".

6.3C Plaees 2SWS*MOV103A control switch to OPEN.

6.4 Verifies RED light - LIT and GREEN light - NOT LIT.

6.SC Plaees 2SWS*MOVI06B control switch to CLOSE.

6.6 Verifies GREEN light - LIT and RED light NOT LIT.

6.7C Places 2SWS*MOVI03B control switch to OPEN.

6.8 Verifies RED light -- LIT and GREEN light NOT LIT.

COMMENTS:

RTL#A5.640U 1I2-ADM-130 l.F04 Page 10 of 10 Revision I OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-656 JPM TITLE: Containment Spray Manual Actuation JPM REVISION: 0 STEP STANDARD

( "e" Denotes CRlTICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT):::) SIU

7. Stop all RCP's. 7.1 Verifies control switches for 2RCS*P21A, 21B and 21 C have been placed to STOP.

7.2 Verifies 2RCS *P21 A, 21 Band 21 C pump RED lights NOT LIT and WHITE lights - LIT.

7.3 Verifies 2RCS-FI414 (415)(416); 2RCS-FI424 (425)(426); 2RCS-FI434 (435)(436) flow has lowered.

7.4 Verifies 2RCS-II21A(B)(C) amps zero.

COMMENTS:

EVALUATOR CUE:

That completes this JPM .

'~/ ..... , . ,'

""<:,/ STOP TIME:

,...;;.~i' " ....... ,

RTL#A5.640U 112-ADM-1301.F04 Page 1 of 12 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE (JPM)

TRAINING MATERIAL TITLE:

TRAINING MATERIAL NUMBER: 2CR-636 PROGRAM TITLE: Licensed Operator Retraining COMPUTER CODE: 2CR-636 REVISION NUMBER: 2 TECHNICAL

REFERENCES:

20M-I0.4.B Revision 30, Residual Heat Removal System Running 20M-S3C.4.2.10.1, Loss of Residual Heat Removal Capability INSTRUCTIONAL SETTING: Control Room/Simulator APPROXIMATE DURATION: 2S Minutes PREPARED BY: P.T. Eisenmann Date PEER REVIEW BY:

Date APPROVED FOR USE:

Training Supervisor or Designee Date

RTL#A5.640U 1I2-ADM-1301.F04 Page 2 of 12 Revision 1 TRAINING MATERIAL CHANGE FORM Affected Training Materials: 2CR-636 Type of Change:

rgj Changes Requiring Learning Objective Related Change? New Rev. #2 Revision DYes rgj No D Changes Not The Change Does Not Impact Learning Existing Rev. # 1 Requiring Revision Objectives or Material Quality.

New Change #

List/Description of Change( s):

Update to current procedure revision Added additional actions to strengthen Alternate path.

Scripted to follow AOP flowpath Updated KIA per TAl 19418 Updated Task ID per TAl 19419 Updated duration to 25 minutes per validation Reason for Change (s):

JPM Enhancements APPROVALS:

NOTE: Additions, deletions or P. T. Eisenmann changes to training materials Prepared by Date must be reviewed for their possible impact to the Training Qualification Matrix. See Incumbent Impact Review, Training Superintendent/Supervisor/Peer Date NOBP-TR-I104.

("Changes Not Requiring Revision" only)

RTL#A5.640U 1I2-ADM-1301.F04 Page 3 of 12 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-636 JPM REVISION: 2 JPM TITLE: Swap RHS Trains KIA

REFERENCE:

005 A4.01 3.6/3.4 TASK ID: 0101-031-04-012 JPM APPLICATION: [gj REQUALIFICATJON [gj INITIAL EXAM D TRAINING

[gj FAULTED JPM D ADMINISTRATIVE JPM EV ALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

[gj Perfonn D Plant Site D Annual Requal Exam D BVT D Simulate [gj Simulator D Initial Exam D NRC D Classroom D OJT/TPE D Other:

D Training D Other:

EV ALUATION RESULTS Perfonner Name: Perfonner SSN:

Time D Yes Allotted 25 Minutes Actual minutes Critical: [gj No Time: Time:

JPM RESULTS:

D SAT 0 UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

RTL#A5.640U 1/2-ADM-1301.F04 Page 4 of 12 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE EVALUATOR IHRECTION SHEET TASK STANDARD: RHS Train B is placed in service, RHS Train A is placed in standby, then upon failure of B pump, RHS Train A returned to service.

RECOMMENDED Control Room STARTING LOCATION:

DIRECTIONS: You are to perform the task, transfer cooling trains of RHS.

INITIAL CONDITIONS:

The plant is in Mode 5.

RHS Train A is in service providing RCS cooling.

RHS Train B is in standby.

Both Pumps and Trains are Filled & Vented

All P&L's and initial conditions are met.

Operators in the field are standing by as required.

20ST-lOA Already Completed INITIATING CUE: Your supervisor directs you to place the B train of RHS in service and then place the A train of RHS in standby.

REFERENCES:

20M-I0A.B, Parts D & E Revision 30 20M-53CA.2.10.1 revision 11 TOOLS: None HANDOUT: 20M-IO.4.B 20M-I 0.5 VOND

RTL#A5.640U l/2-ADM-1301.F04 Page 5 of 12 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

DRead:

TASK:

You are to perform the task, transfer cooling trains ofRHS.

INITIAL CONDITIONS:

The plant is in Mode 5.

RHS Train A is in service providing RCS cooling.

RHS Train B is in standby.

Both Trains. are Filled & Vented

All P&L's and initial conditions are met.

Operators in the field are standing by as required.

20ST-10.4 Already Completed INITIATING CUE: Your supervisor directs you to place the B train of RHS in. service and then place the A train of RHS in standby.

D At this time, ask the evaluator any questions you have on this JPM.

D When satisfied that you understand the assigned task, announce "I am now beginning the JPM".

Simulate performance or perform as directed the required task.

D Point to any indicator or component you verify or check and announce your observations.

After determining the Task has been met announce" I have completed the JPM".

D Then hand this sheet to the evaluator.

RTL#A5.640U 112-ADM-130 I.F04 Page 6 of 12 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-636 JPM TITLE: Swap RHS Trains JPM REVISION: 2 STEP STANDARD

( "e" Denotes CRITICAL STEP) (Indicate "s" FOR SAT or "U" FOR UNSAT)=> SfU EVALUATOR NOTE: This is a EVALUATOR NOTE: Simulator Setup:

FAULTED JPM. The candidate is Init IC-232 Turn on recorders 2RHS*TR604A&B.

expected to transition to AOP 2.10.1 Place/remove caution tags as needed.

following the loss of both RHS Shutdown 'B' Train RHS lAW 20M-lOA.B Part F.

pumps. Close 2RHS*MOV720B and 2CCP*MOVl12B.

Set PLP RTCI =1O. Balance Charging and Letdown via 2CHS*FCV122 and 2CHS*HCV 142.

It ", ,,',

START TIME: _ _ _ _ _ _ __

1. Reviews procedure. 1.1 Reviews Section D, "To Place RHS Train Bin Service From A Standby Condition" of 20M-l OAB.

COMMENTS:

EVALU ATOR CUE: If asked, inform the candidate that ASME valve testing is not required and that RHS Train A has been filled and vented (per initial conditions)

2. Verify CCP temperature 2.1 Checks temperature on 2CCP-TIl OOA( 1OOB)( lOOC)

>50°F. >50°F.

COMMENTS:

RTL#A5.640U 112-ADM-130 1.F04 Page 7 of 12 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-636 JPM TITLE: Swap RHS Trains JPM REVISION: 2 STEP STANDARD

( "c" Denotes CRITICAL STEP) (Indicate "s" FOR SAT or "u" FOR LNSAT)=> I S/U I

3. Check RCS temperature. 3.1. Detl~rmines RCS/RHS temperature> 120F.

3.2 Places control switch to open for 2CCP*MOVl12B, RHR PP SEAL CLR 22B & HX21B COOLING WATER INLET VLV 3.3 Verifies Red Light** LIT and Green Light - NOT LIT.

COMMENTS:

4.C Align RHS valves. 4.1 Checks OPEN [2RHS*MOV701B].

Verifies Red Light** LIT and Green Light - NOT LIT.

4.2 Checks OPEN [2RHS*MOV702B].

Verifies Red Light .. LIT and Green Light - NOT LIT.

4.3C CLOSES [2RHS*FCV605B], demand at zero.

4.4 Verifies OPEN [2CHS*HCV142], demand not at zero.

4.5 Che:cks CLOSED [2RHS*MOV750B].

Verifies Red NOT Light - LIT and Green Light LIT.

4.6C CLOSES [2RHS*HCV758B], demand at 100%.

4.7 Checks OPEN [2RHS*MOVnOB], Red light lit, Green light not lit.

COMMENTS:

EVALUATOR NOTE: If candidate decides to open 2CHS*HCV142 further, cue as the supervisor j

to leave the valve as found.

RTL#A5.640U 112-ADM-1301.F04 Page 8 of 12 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-636 JPM TITLE: Swap RHS Trains JPM REVISION: 2 STEP STANDARD

( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> SIU

5. Monitor RHR Hx DiffTemp. 5.1 Monitors RHR Hx DiffTemp on [2RHS*TR604B]

and/or (T0630A).

EVALUATOR NOTE: Candidate may use computer PID to determine differential temperature. Computer point (T0630A) is only the heat exchanger inlet temperature.

COMMENTS:

6. Vent [2RHS*P21B]. 6.1 Det<:rmines step is NI A based on Attachment 1.

EVALUATOR CUE: [2RHS*P21B] venting not required per Attachment 1.

COMMENTS:

7. Monitor [2RHS*P21B] for 7.1 Determines containment is at atmospheric pressure seal leakage during pump and monitoring of pump seal leakage on pump start is start. required.

7.2 Requests local operator to monitor pump seal for leakage.

EVALUATOR CUE: Local operator will monitor pump operation.

COMMENTS; I

RTL#A5.640U l/2-ADM-130 l.F04 Page 9 of 12 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-636 JPM TITLE: Swap RHS Trains JPM REVISION: 2 STEP STANDARD

( "c" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> I S/U I I

8.C Verify RHS temperature is 8.1 Verifies RCS and RHS temperature indications on within limits then start PCS or recorders, that temperature differential is :; 50

[2RHS*P21BJ. OF or RHS temperature rate of increase is < 5 OF/Hr.

EVALUATOR NOTE: Candidate may have previously verified temperature is within limits.

8.2C Starts [2RHS*P21 B].

COMMENTS:

9. If required, maintain PRZR 9.1 Marks step 16 as N/A.

pressure between 275 and 350 psig by the following EVALUATOR CUE: RCP operation is not methods. require:d at this time. You do NOT have to adjust pressure, step 16 is N/A.

COMMENTS:

lQ.C Adjust RHS system flow. 10JC Throttles [2RHS*FCV605B] OPEN to establish a flowrate <4000 GPM as indicated on

[2RHS*FI605B].

COMMENTS:

RTL#A5.640U 1/2-ADM-1301.F04 Page 10 of 12 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-636 JPM TITLE: Swap RHS Trains JPM REYISION: 2 STEP STANDARD

( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=:> I S/U I

11. Transfer [2RHS*FCY605B] 11.1 Adjusts auto flow setpoint to desired flowrate and to auto. places the controller in AUTO.

COMMENTS:

I EVALUATOR NOTE: ReS temperature is greater than 120 of, step 19.a-fis N/A.

12. Maintain RCS temperature, 12.1 Throttles [2RHS*HCY758B] to maintain RCS verify flow is controlled in temperature.

AUTO.

12.2 Verify [2RHS*FCY605A/605B] modulate in AUTO to maintain RHS flow on 2RHS*FI605AI B].

12.3 OPENS [2RHS*MOY750B].

Verifies Red Light - LIT and Green Light - NOT LIT.

EVALUATOR CUE: You are to maintain RCS temperature stable at its current value. It is desired to Open [2RHS*MOY750B]. Then assume this section of the procedure is completed and routed as required. You are now to place RHS Train A in standby.

COMMENTS:

RTL#A5.640U 1I2-ADM-I30 l.F04 Page II of12 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-636 JPM TITLE: Swap RHS Trains JPM REVISION: 2 UNSAT)~ I S/U I STEP STANDARD

( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR

13. Locate procedure. 13.1 Transitions to procedure Section E, To Place RHS Train A in Standby.

COMMENTS:

14.C Check [2RHS*P21A] 14.lC STOPS [2RHS*P21A].

stopped.

14.1 CLOSES [2RHS*MOV750B].

Verifies Red Light-- NOT LIT and Green Light EVALUATOR NOTE:

LIT.

Alternate path here.

[2RHS*FCV605B] will ramp SIMULATOR OPERATOR CUES: After fully open and after full open, candidate secures [2RHS*P21A], ramp OPEN

[2RHS*P21 B] will trip. [2RHS*FCV605B] and after full open, trip Candidate is expected to [2RHS*P21B]. [2RHS*P21B] also will not transition to AOP 2.10.1. restart.

COMMENTS:

RTL#A5.640U 112-ADM-130 1.F04 Page 12 of 12 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-636 JPM TITLE: Swap RHS Trains JPM REVISION: 2 STEP STANDARD

( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> [ SIU [

15.C Transition to AOP 2.10.1. 15.1 May attempt to restart [2RHS*P21Al 15.2 May attempt to restart [2RHS*P21B].

15.3 May refer to annunciator A 1-SH ARP. If so, ensure proper steps are followed.

15.4 Transitions to AOP 2.10.1.

EVALUATOR CUE: The local operator reports

[2RHS*P21B] has an Overcurrent relay tripped.

15.5 CLOSES [2RHS*HCV7S8A], demand at 100%.

15.5 CLOSES [2RHS*FCV605A] demand at zero.

15.6 Verifies CLOSED [2CHS*HCY142], demand at zero.

lS.SC Restarts 2RHS-P21A.

lS.6C If closed prior to restarting 2RHS-P21A, reopens

[2RHS*FCY758A] and [2RHS*FCV605A] to establish temperature and flow controL EVALUATOR CUE: After the candidate reestablishes cooling state; "That completes this JPM".

COMMENTS:

STOP TIME: _________

RTL#A5.640U 112-ADM-130 l.F04 Page 1 of 11 Revision I OPERATIONS JOB PERFORMANCE MEASURE (JPM)

TRAINING MATERIAL TITLE: Align Service Water to [2FWE*P23B] Motor Driven Auxiliary Feed TRAINING MATERIAL NUMBER: 2PL-167

~----------------------------------------

PROGRAM TITLE: Licensed Operator Training COMPUTER CODE: 2PL-167 REVISION NUMBER: o TECHNICAL

REFERENCES:

20M-53A.l.A-l.8, "Makeup to PPDWST [2FWE*TK21 0]", Rev. 5 INSTRUCTIONAL SETTING: In-Plant APPROXIMATE DURATION: 15 Minutes PREPARED BY: Ian Forbes Date PEER REVIEW BY:

Date APPROVED FOR USE:

Training Supervisor or Designee Date

RTL#A5.640U li2-ADM-1301.F04 Page 2 of 11 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE TRAINING MATERIAL CHANGE FORM Affected Training Materials: 2PL-167 Type of Change:

C8J Changes Requiring Learning Objective Related Change? New Rev. # 0 Revision DYes C8JNo D Changes Not The Change Does Not Impact Learning Existing Rev. N/ A Requiring Revision Objectives or Material Quality.

New Chan e#

List/Description of Change(s):

New JPM Version.

Reason for Change (s):

Initial Issue.

APPROVALS:

- Ian Forbes NOTE: Additions, deletions or Prepared by Date changes to training materials must be reviewed for their possible impact to the Training Qualification Matrix. See Training Superintendent/Supervisor/Peer Date Incumbent Impact Review,

("Changes Not Requiring Revision" only) NOBP-TR-II04.

RTL#A5.640U 112-ADM-130 1.F04 Page 3 ofll Revision 1 OPERA TIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-167 JPM TITLE: Align Service Water to [2FWE*P23B] Motor Driven JPM REVISION: 0 Auxiliary Feed Pump Suction KIA

REFERENCE:

061Kl.07 3.6/3.8 TASK ID: 0241-054-04-012 061Al.04 3.9/3.9 0532-010-05-043 JPM APPLICATION: [gI REQUALIFICATION [gI INITIAL EXAM [gI TRAINING D FAULTED JPM D ADMIN]STRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

D Perform [gI Plant Site D Annual Requal Exam D BVT

[gI Simulate D Simulator D Initial Exam D NRC D Classroom D OJT/TPE D Other:

D Training D Other:

EVALUATION RESULTS Performer Name: Performer SSN:

Time D Yes Allotted 15 Minutes Actual minutes Critical: [gI No Time: Time:

JPM RESULTS:

D SAT D UN SAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

RTL#A5.640U 1/2-ADM-1301.F04 Page 4 of 11 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-167 JPM TITLE: Align Service Water to [2FWE*P23B] Motor Driven JPM REVISION: 0 Auxiliary Feed Pump Suction EVALUATOR DIRECTION SHEET TASK STANDARD: Service water v(:nted and aligned to [2FWE*P23B] Motor Driven Auxiliary Fee.d Pump suction.

RECOMMENDED In-Plant STARTING LOCATION:

DIRECTIONS: You are to align Service Water Supply to [2FWE*P23B] Motor Driven Auxiliary Feed Pump Suction.

INITIAL CONDITIONS:

The Control Room Team has responded to an Inadequate Core Cooling Accident and is now in E-l, "Loss of Reactor or Secondary Coolant".

Containment Isolation Phase B actuation has occurred.

PPDWST level has decreased to the low-level alarm setpoint.

PPDWST level indicators [2FWE*LII04Al] and

[2FWE*LII04A2] both indicate 20".

Both Demineralized Water Pumps [2WTD-P23A and B] are unavailable, and [2WTD-TK23] is also unavailable.

[2SWS*MOVI03B] Recirc. Spray HXs Service Water Sup "B" Isolation Valve has been verified OPEN.

SIG Pressure is approximately 400 psig.

INITIATING CUE: Your supervisor directs you to supply [2FWE*P23B] Motor Driven Auxiliary Feed Pump suction from Service Water by completing EOP Attachment A-I. 8 beginning with step 10.

Mechanical Maintenance and another operator are on station in South Safeguards ready to coordinate this evolution.

REFERENCES:

20M-53A.l.A-l.8, "Makeup to PPDWST [2FWE*TK2 I 0]", Rev. 5 TOOLS: Keys (simulated)

HANDOUT: 20M-53A.l.A-1.8, "Makeup to PPDWST [2FWE*TK210]", Rev. 5, place kept up to step 10.

Ops Manual Figure 24-3 (provide if requested)

RTL#A5.640U 1I2-ADM-130 l.F04 Page 5 of 11 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

DRead:

TASK: You are to align Service Water Supply to [2FWE*P23B] Motor Driven Auxiliary Feed Pump Suction.

INITIAL CONDITIONS:

The Control Room Team has responded to an Inadequate Core Cooling Accident and is now in E-1, "Loss of Reactor or Secondary Coolant".

Containment Isolation Phase B actuation has occurred.

PPDWST level has decreased to the low-level alarm setpoint.

PPDWST level indicators [2FWE*LIl 04A 1] and

[2FWE*LIl 04A2] both indicate 20".

Both Demineralized Water Pumps [2WTD-P23A and B] are unavailable, and [2WTD-TK23] is also unavailable.

[2SWS*MOVI03B] Recirc. Spray HXs Service Water Sup "B" Isolation Valve has been verified OPEN.

s/a Pressure is approximately 400 psig.

INITIATINa CUE: Your supervisor directs you to supply [2FWE*P23B] Motor Driven Auxiliary Feed Pump suction from Service Water by completing EOP Attachment A-I.8 beginning with step 10.

Mechanical Maintenance and another operator are on station in South Safeguards ready to coordinate this evolution.

D At this time, ask the evaluator any questions you have on this JPM.

D When satisfied that you understand the assigned task, announce HI am now beginning the JPM".

Simulate performance or perform as directed the required task.

D Point to any indicator or component you verify or check and announce your observations.

After determining the Task has been met announce "I have completed the JPM".

D Then hand this sheet to the evaluator.

RTL#A5.640U 112-ADM-1301.F04 Page 6 of 11 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-I67 JPM TITLE: Align Service Water to [2FWE*P23B] Motor Dl1ven JPM REVISION: 0 Auxiliary Feed Pump Suction STEP STANDARD

( "c" Denotes CRITICAL STEP) (Indicate "s" FOR SAT or "V" FOR VNSAT)=> I S/V I START TIME:

EVAL,UATOR CUE: Provide a procedure copy.

Inform the candidate that you will role play any personnel they are required to interact with.

1. IF PPDWST Level Drops to 1.1 Recognizes from the Initial Conditions that CIB has 25 inches, THEN align occurred and perfonnance of this step is not Service Water to the Auxiliary required.

Feedwater Pumps by performing the following:

COMMENTS:

If Containment Isolation Phase B has NOT occurred, then perform the following:

Close [2SWS*MOVI04B]

Close [2SWS*MOVI04D]

2. Verify Open 2.1 Recognizes from the Initial Conditions that this step

[2SWS*MOVI 03B], Recirc has already been performed.

Spray HX Service Water Supply Header B Isolation. COMMENTS:

RTL#A5.640U 112-ADM-130 1.F04 Page 7 of 11 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-167 JPM TITLE: Align Service Water to [2FWE*P23B] Motor Driven JPM REVISION: 0 Auxiliary Feed Pump Suction STEP STANDARD

( "c" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> I SIU I 3.C Close [2FWE*356], Service 3.1C Closes [2FWE*356], Service Water Supply Tell

. Water Supply Tell Tale Drain. Tale Drain by rotating valve handwheel in the (North SFGDS above clockwise direction.

2FWE*23B -718')

EVALUATOR CUE: [2FWE*356], Service Water Supply Tell Tale Drain has been rotated CLOCKWISE.

COMMENTS:

4. Vent SWS to AFW piping as 4.1 Requests Mechanical Maintenance Technician follows: loosen flange at [2FWE-RV102J, Emergency Water Supply Relief.

Request Mechanical Maintenance Technician EVALUATOR CUE: Flange at [2FWE-RVI02],

loosen flange at [2FWE Emergency Water Supply Relief has been loosened.

RV102], Emergency Water Supply Relief. (South SFGDS above 2FWE-P23A - 718)

COMMENTS:

5. With Key SRl14, Open 5.1 Removes locking device and opens [2FWE*98],

[2FWE*98], Service Water Service Water Isolation by rotating valve handwheel Isolation. (North SFGDS chain operator in the counter-clockwise direction.

above 2FWE*P23B 718)

EVALUATOR CUE: [2FWE*98], Service Water Isolation has been unlocked and is indicating OPEN. A solid stream of water is issuing from the flange at

[2FWE*RV102].

I COMMENTS:

RTL#A5.640U 112-ADM-130 1.F04 Page 8 of 11 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-167 JPM TITLE: Align Service Water to [2FWE*P23B] Motor Driven JPM REVISION: 0 Auxiliary Feed Pump Suction STEP STANDARD

( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> S/U I 6.C When a solid stream of water 6.1C Closes [2FWE*98], Service Water Isolation by appears at the flange at rotating valve handwheel chain operator in the

[2FWE*RV102], then Close clockwise direction.

[2FWE*98].

EVALlATOR CUE: [2FWE*98], Service Water Isolation is indicating CLOSED.

COMMENTS:

7. Request Mechanical 7.1 Requests Mechanical Maintenance Technician Maintenance Technician tighten flange at [2FWE-RVI02].

tighten flange at [2FWE RVI02]. EVALUATOR CUE: Flange at [2FWE-RVI02],

Emergency Water Supply Reliefhas been tightened.

COMMENTS:

8.C Open [2FWE*98], Service 8.lC Opens [2FWE*98], Service Water Isolation by Water Isolation. rotating valve handwheel chain operator in the counter-clockwise direction.

EVALUATOR CUE: [2FWE*98], Service Water Isolation is indicating OPEN.

COMMENTS:

I I I

RTL#AS.640U 1/2-ADM-130 1.F04 Page 9 of 11 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-167 JPM TITLE: Align Service Water to [2FWE*P23B] Motor Driven JPM REVISION: 0 Auxiliary Feed Pump Suction STEP STANDARD

( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> Stu I 9.C For [2FWE*P23B], Motor 9.1 C Opens [2FWE*92], Service Water Supply to Driven AFW Pump, perform [F\VE*P23B] by rotating valve handwheel in the the following: counter-clockwise direction.

EVALUATOR CUE: [2FWE*92] has been OPENED.

Slowly Open [2FWE*92],

EVALUATOR NOTE: Valve position indication is on Service Water Supply to top of the valve and is difficult to observe.

[FWE*P23B]

(South Safeguards 718')

COMMENTS:

10.C With Key CRITI19, close 10.1 C Unlocks and Closes [2FWE*95], Primary DWST

[2FWE*95], Primary DWST Supply to [2FWE*P23B] by rotating valve Supply to [2FWE*P23B]. handwheel in the clockwise direction.

EVALUATOR CUE: [2FWE*95] has been CLOSED. Valve position indicates CLOSE.

COMMENTS:

11. Observe AFW pump 11.1 Observes AFW pump discharge pressure to ensure discharge pressure to ensure proper operation by depressing the ON/OFF red proper operation. pushbutton and reading displayed pressure.

EVALUATOR CUE: When ON/OFF red pushbutton is depressed, [2FWE*P23B] discharge pressure is reading approximately 450 psig. That complett:s this JPM.

COMMENTS:

STOP TIME: __________

RTL#A5,640U 1I2-ADM-130LF04 Page 1 of8 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE (JPM)

TRAINING MATERIAL TITLE: a Rod Drive MG Set TRAINING MATERIAL NUMBER: 2PL-003 PROGRAM TITLE: Licensed COMPUTER CODE: 2PL-003 REVISION NUMBER: 7 TECHNICAL

REFERENCES:

20M-I.4.B Revision 13, "Reactor Rod Drive Control System Startup".

INSTRUCTIONAL SETTING: In-Plant APPROXIMATE DURATION: 15 Minutes PREPARED BY: Ian Forbes Date PEER REVIEW BY:

Date APPROVED FOR USE:

Training Supervisor or Designee Date

RTL#A5.640U 112-ADM-130 1.F04 Page 2 of8 Revision 1 TRAINING MATERIAL CHANGE FORM I Affected Training Materials: 2PL-003 Type .Change:

. I:8J Changes Requiring Learning Objective Related Change? New Rev. # 7 I Revision DYes I:8J No I D Changes Not The Change Does Not Impact Learning Existing Rev. # 6 Requiring Revision Objectives or Material Quality.

New Change #

List/Description ofChange(s):

Changed instructional setting from classroom to in-plant.

Updated JPM to reflect most current standards & expectations.

Updated to reflect most current copy of procedure.

Reason for Change (s):

Enhanced JPM for use on 2LOT8 Exam.

i APPROVALS:

Ian Forbes

NOTE: Additions, deletions or Prepared by Date changes to training materials I must be reviewed for their possible impact to the Training Qualification Matrix. See Training Superintendent/Supervisor/Peer Date

Incumbent Impact Review,

("Changes Not Requiring Revision" only) NOBP-TR-II04.

i

RTL#A5.640U 112-ADM-1301.F04 Page30fS Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-003 JPM TITLE: Startup a Rod Drive MG Set JPM REVISION: 7 KIA

REFERENCE:

001 A4.08 3.7/3.4 TASK ID: 0011-001-01-043 JPM APPLICATION: r8] REQUALIFICA TION r8] INITIAL EXAM r8] TRAINING D FAULTED JPM D ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

D Perform I:8J Plant Site D Annual Requa} Exam D BVT I:8J Simulate D Simulator D Initial Exam D NRC D Classroom D OJT/TPE D Other:

D Training D Other:

EVALUATION RESULTS Performer Name: Performer SSN:

Time D Yes Allotted 15 Minutes Actual minutes Critical: I:8J No Time: Time:

JPM RESULTS:

D SAT D UN SAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

RTL#A5.640U 112-ADM-130 1.F04 Page 4 of8 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET TASK STANDARD: MG set #2 is running with [2RDS-MG22] Generator Output breaker CLOSED.

RECOMMENDED In plant STARTING LOCATION:

DIRECTIONS: You are to simulate starting #2 MG Set.

INITIAL CONDITIONS:

The plant is in Mode 3.

Reactor Rod Drive Control System Startup is in progress.

MG Set #1 is operating and the reactor trip breakers are open.

INITIATING CUE:

Your supervisor directs you to startup the #2 MG set and close the generator output breaker per procedure 20M-lA.B Part A, beginning with Step 7.

All initial conditions are satisfied.

Steps 1 through 6 were completed on the previous shift.

Reactor Trip Breakers will be closed from the Control Room.

REFERENCES:

20M-lA.B Revision 13, "Reactor Rod Drive Control System Startup".

TOOLS: NONE HANDOUT: Place kept copy of 20M-1.4.B Revision 13, "Reactor Rod Drive Control System Startup" up to step #7.

RTL#A5.640U 112-ADM-130 1.F04 Page 5 of8 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

DRead:

TASK: You are to simulate starting #2 MG Set.

INITIAL CONDITIONS:

The plant is in Mode 3.

Reactor Rod Drive Control System Startup is in progress.

MG Set #1 is operating and the reactor trip breakers are open.

INITIATING CUE:

Your supervisor directs you to startup the #2 MG set and close the generator output breaker per procedure 20M-IA.B Part A, beginning with Step 7.

All initial conditions are satisfied.

Steps 1 through 6 were completed on the previous shift.

Reactor Trip Breakers will be closed from the Control Room.

D At this time, ask the evaluator any questions you have on this JPM.

D When satisfied that you understand the assigned task, announce til am now beginning the JPM".

Simulate performance or perform as directed the required task.

D Point to any indicator or component you verify or check and announce your observations.

After determining the Task has been met announce" I have completed the JPM".

D Then hand this sheet to the evaluator.

RTL#A5.640U 112-ADM-130 l.F04 Page 6 of8 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL*003 JPM TITLE: Startup a Rod Drive MG Set JPM REVISION: 7 STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT):::::> I SIU I START TIME: _ _ _ _ _ _ __

I.C At [PNL-2RD-2RD 1.1 C Places [2RDS-MG22] MOTOR Circuit Breaker CONT], Place [2RDS Control switch to the closed position.

MG22] Motor Circuit Breaker Control switch in 1.2 Verifies Red Light LIT and Green Light- NOT CLOSE position, AND LIT.

check MG set #2 starts.

EVALUATOR CUE: Red Light LIT, Green Light NOT LIT. #2 MG set is accelerating.

COMMENTS:

2.C Depress AND Hold [2RDS 2.1C Simulates depressing [2RDS-MG22] Gen. Field Flash MG22] Gen. Field Flash pushbutton until [2RDS-MG22] Generator Line Volts pushbutton until the voltmeter indicates approximately 260VAC.

[2RDS-MG22] Generator Line Volts voltmeter EVALUATOR CUE: [2RDS-MG22] Generator indicates approximately Line Volts voltmeter increased to 260 VAC.

260 V AC, THEN release.

COMMENTS:

RTL#A5.640U 112-ADM-1301.F04 Page 70f8 Revision I OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-003 JPM TITLE: Startup a Rod Drive MG Set JPM REVISION: 7 STEP STANDARD

( "C" Denotes CRITICAL STEP) (Indicate "s" FOR SAT or "U" FOR UNSAT)=:> I SIU I

3. Complete 20M-IA.Q, 3.1 Acknowledges the need to complete 20M-IA.Q.

"Administrative Guidelines for Closing the Reactor EVALU ATOR CUE: 20M-IA.Q Administrative Trip/Bypass Breakers". Guidelines for closing the reactor Trip/Bypass breakers has been completed.

EVALUATOR CUE: CRDM cooling is in service per initial conditions.

COMMENTS:

4. Close reactor trip breakers 4.1 Requests that the RO close the reactor trip breakers

[RTA AND RTB] to from BB-B.

provide load.

EVALUATOR CUE: The RO acknowledges the request to close reactor trip breakers and after several minutes you hear noise and the RO confirms the RTBs are CLOSED.

COMMENTS:

5.C Place [2RDS-MG22] 5.1 C Places [2RDS-MG22] GENERATOR Circuit Breaker Generator Circuit Breaker control switch to CLOSE position.

control switch to CLOSE position. EVALUATOR CUE: The Mechanical Flag (RED) is indicated and the GREEN indicating light is LIT.

COMMENTS:

RTL#AS.640U 112-ADM-130 1,F04 Page 8 of8 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-003 JPM TITLE: Startup a Rod Drive MG Set JPM REVISION: 7 STEP STANDARD

( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)~

6.C Place [2RDS-MG22] 6.1 C Places [2RDS-MG22] Synchronize switch in the ON Synchronize switch in the position.

ON position AND Check the two generators 6.2 Checks [2RDS-MG22] GENERA TOR Output synchronize. breaker RED Light -- LIT.

EVALUATOR CUE: A few moments after the Synchronize Switch is taken to ON, inform the candidate that [2RDS-MG22] Generator Output breaker RED Light - LIT, Green Light NOT LIT.

COMMENTS:

7. When [2RDS-MG22] 7.1 Places [2RDS-MG22] Synchronize switch to the OFF Generator circuit breaker position.

CLOSES, THEN place

[2RDS-MG22] EVALUATOR CUE: Acknowledges Synch switch Synchronize switch to the in OFF position.

OFF position.

7.2 Informs supervisor that # 2 MG Set is running with output breaker closed or that the task is complete.

COMMENTS:

STOP TIME:

RTL#A5.640U l!2-ADM-130 1.F04 Page 1 of8 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE (JPM)

TRAINING MATERIAL TITLE: Place a Reactor Protection Channel in the Tripped Condition TRAINING MATERIAL NUMBER: 2PL-009 PROGRAM TITLE: Licensed Operator Training COMPUTER CODE: 2PL-009 REVISION NUMBER: 7 TECHNICAL

REFERENCES:

20M-53C.4.2.2.1 C, "Power Range Channel Malfunction", Revision 10 INSTRUCTIONAL SETTING: In-Plant APPROXIMATE DURATION: 7 Minutes PREPARED BY: Ian Forbes Date PEER REVIEW BY:

Date APPROVED FOR USE:

Training Supervisor or Designee Date

RTL#A5.640U 112-ADM-130 I.F04 Page2of8 Revision 1 TRAINING MATERIAL CHANGE FORM I

Affected Training Materials: 2PL-009 Type of Change:

~ Changes Requiring Learning Objective Related Change? I New Rev. # 7 Revision DYes ~No D Changes Not The Change Does Not Impact Learning Existing Rev. # 6 Requiring Revision Objectives or Material Quality.

New Change #

List/Description of Change(s):

Changed step 4.2, 5, & 6 typos from C3 to proper nomenclature.

Included information about protection cabinet doors having limit switches which send the control room an indication when the doors are opened.

Modified starting location from control room to in-plant.

Enhanced Task Standard to be more specific to the actual failed channel.

Reason for Change (s):

Enhance lPM.

APPROVALS:

NOTE: Additions, deletions or Ian Forbes changes to training materials Prepared by Date must be reviewed for their possible impact to the Training QualificatiOli. Matrix. See Incumbent Impact Review, i Training Supenntendent/Supervlsor/Peer Date NOBP-TR-I104.

("Changes Not Requiring Revision" only)

RTL#A5.640U 1!2-ADM- I 30 1.F04 Page30f8 Revision 1 JPM NUMBER: 2PL-009 JPM TITLE: Place a Reactor Protection Channel in the Tripped JPM REVISION: 7 Condition KJA

REFERENCE:

012A4.04 3.3/3.3 TASK ID: 0535-010-04-013 JPM APPLICATION: L8J REQUALIFICATION L8J INITIAL EXAM o TRAINING o FAULTEDJPM o ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

o Perfonn IZI Simulate ~

0 Plant Site Simulator Classroom B

0 Annual Requal Exam Initial Exam OJT/TPE B BVT NRC 0 Other:

0 Training 0 Other:

EVALUATION RESULTS Perfonner Name: Perfonner SSN:

Time L.J Yes Allotted 7 Minutes Actual minutes Critical: L8J No Time: Time:

JPM RESULTS:

0 SAT D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

RTL#A5.640U 112-ADM-J301.F04 Page 4 of8 Revision 1 EVALUATOR DIRECTION SHEET Power Range Channel N-43 bistables are in the test (tripped) position.

TASK STANDARD:

RECOMMENDED In-plant STARTING LOCATION:

You are to simulate placing a reactor protection channel in the tripped DIRECTIONS:

condition.

INITIAL CONDITIONS:

The plant is in Mode 1 at 100% power.

Power Range Channel N-43 has malfunctioned.

AOP-2.2.1C, "Power Range Channel Malfunction" has been performed through Step I.h.

Your supervisor directs you to tIip the appropriate bistables in INITIATING CUE:

accordance with AOP-2.2.1 C, Power Range Channel Malfunction, Step l.i.

20M-53C.4.2.2.1 C, "Power Range Channel Malfunction", Revision 10

REFERENCES:

Key No. 117 (18)

TOOLS:

20M-53C.4.2.2.1 C, "Power Range Channel Malfunction", place kept HANDOUT:

up to and including step l.h.

RTL#A5.640U 112-ADM-130 1.F04 Page 5 of8 Revision 1 CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

D Read:

You are to simulate placing a reactor protection channel in the tripped TASK:

condition.

INITIAL CONDITIONS:

The plant is in Mode 1 at 100% power.

Power Range Channel N-43 has malfunctioned.

AOP-2.2.1 C, "Power Range Channel Malfunction" has been performed through Step l.h.

Your supervisor directs you to trip the appropriate bistables in INITIATING CUE:

accordance with AOP-2.2.1 C, Power Range Channel Malfunction, Step 1 j.

D At this time, ask the evaluator any questions you have on this JPM.

D When satisfied that you understand the assigned task, announce "I am now beginning the JPM".

Simulate performance or perform as directed the required task.

D Point to any indicator or component you verify or check and announce your observations.

After determining the Task has been met announce" I have completed the JPM".

D Then hand this sheet to the evaluator.

RTL#A5.640U 1I2-ADM-130 LF04 Page 6 of8 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-009 JPM TITLE: Place a Reactor Protection Channel in the Tripped JPM REVISION: 7 Condition STEP STANDARD

( "c" Denotes CRITICAL STEP) (Indicate "s" FOR SAT or "U" FOR UNSAT)=> I Stu I EVALUATOR NOTE: Obtain Key # 117(118) prior to JPM performance and inform Shift Manager that Primary Process Rack No.3 door(s) will be opened. These doors have limit switches which will provide the Control Room indication when the doors are opened and closed.

EVALUATOR CUE: Provide the candidate a place kept copy of AOP 2.2.1 C.

START TIME:

1. Reviews procedure. 20M 1.1 Candidate reviews place kept copy of AOP 2.2.1.C 53C.4.2.2.1 C, Power Range provided.

Channel Malfunction.

COMMENTS:

2. Obtain Keys 117 (118) for 2.1 Obtains Key No. 117 (118) for process rack door by process rack doors. requesting keys from the evaluator or indicating that they will need to go to the Control Room to sign out thesl;;! keys.

EVALUATOR CUE:

Provide the candidate the KEY 117 (118) when they request the keys or begin to walk to the control room.

COMMENTS:

RTL#A5.640U 112-ADM-130 1.F04 Page 70f8 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-009 JPM TITLE: Place a Reactor Protection Channel in the Tripped JPM REVISION: 7 Condition U~SAT)=> I STEP STANDARD

( "c" Denotes CRITICAL STEP) (Indicate "s" FOR SAT or "U" FOR SIU I EVALVA TOR NOTE: These are several blue cabinet doors that are marked the same. The candidate may need to open more than one door in order to locate the proper bistables.

3. Open process rack door. 3.1 Opens the proper Protection Cabinet No.3 door.

COMMENTS:

4. Refer to Attachment 1, 4.1 Refers to Attachment 1 for bistab1es to trip.

"Delta T Protection Bistable Switch List". 4.2 Det(;:rmines bistables BS-3 and BS-4 on Card Frame 7/S10t 21 must be tripped.

COMMENTS:

S.C Place 2TS/432C-l [BS-3] 5.IC Places 2TS/432C-I [BS-3] bistable in the TEST bistable on Card Frame position located on Card Frame 7/S10t 21.

7/S10t 21 in the TEST position. 5.2 Verifies the RED LED is ON.

EVALUATORCVE:

2TS/432C-l is in TEST and Red LED is LIT.

COMMENTS:

RTL#A5.640U 112-ADM-1301,F04 Page 8 of8 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-009 JPM TITLE: Place a Reactor Protection Channel in the Tripped JPM REVISION: 7 Condition STEP STANDARD

( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "V" FOR VNSAT):::::> I SIV I 6.C Place 2TS/432C-2[BS-4] 6.1C Placies 2TS/432C-2[BS-4] bistable in the TEST bistable on Card Frame 7/S10t position located on Card Frame 7/S10t 21.

21 in the TEST position.

6.2 Verifies the RED LED is ON.

EVALUATOR CUE:

2TS/432C-2 is in TEST and Red LED is LIT. ]

COMMENTS:

7. Close and lock Protection 7.1 Closes and locks Protection Rack No.3 door.

Rack No.3 door.

COMMENTS:

EVALUATOR CUE:

That Completes this JPM

.\i* .>> ' Jll~.,,"

,;,I;!'l/i~; . STOP TIME:

A~ppen d'IX 0 , 0 utrme S cenano Form ES 0 1 .

Facility: BVPS Unit 2 Scenario No.:l OpTestNo.: 2LOT8 NRC Examiners: Candidates: SRO ATC BOP Initial IC 211(7): 25% power, BOL, Xe increasing, CB "0" @ 121 steps, RCS boron - 1935 ppm.

Conditions: Main feed regulating valves in service Turnover: Increase power to 100%. 2SAS-C21 BOOS Critical Tasks: 1. E-O.E Actuate 1 train of CNMT Spray

2. E-O.P Manually actuate SLI

3. E-2.A Isolate Faulted S/G Event Malf. No. Event Type Event Description No.

1 (R) ATC Raisl;:! power in accordance with reactivity plan.

(N) BOP, SRO 2 (TS) SRO 2FWE*P22 (turbine driven Aux Feedwater pump) trips 3 (I) ATC, SRO 2CHS-PTI45, fails high, ATC required to manually control letdown pressure via 2CHS-PCVI45.

4 (C) BOP, SRO Loss of 2AE 4kv Emergency bus I 2-1 Emergency Diesel fails I (TS) SRO to auto start. BOP required to manually start EDG 2-1.

(C) ATC ATC manually aligns cooling water flow to EDG 2-1 I

5 (C) BOP, SRO 2CCS-P21 A sheared shaft, auto start failure of 2CCS-P21 B, requires manually starting standby pump.

6 (M) ALL Feedline break inside CNMT.

7 (C) ATC, SRO CIB actuation failure 8 (C) BOP, SRO MSLI actuation failure with 2SDS*AOV111's failing to auto close, requires BOP to manually actuate MSLI and close all 6 2SDS*AOVl11 's 9 (C) BOP, SRO "B" train CREV's fails to actuate, requires BOP to manually actuate.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021. Revision 9 Supplement 1 FENoe Facsimile Rev. AG

Appendix 0 Scenario Outline Form ES-O-1 2L8N1 The crew will assume the shift at 25% power with instructions to raise power to 100% lAW 20M-52.4.A and the reactivity plan.

When reactor power has increased to 27.5%, the linkage for the trip-throttle valve for the Turbine Driven Auxiliary Feedwater Pump, 2FWE*P22, will fail, requiring the US to determine appropriate Tech Spec action.

When Tech Specs have been addressed, Letdown Pressure Transmitter, 2CHS*PTI45, will fail high, requiring the ATC to control letdown pressure by manually controlling the Letdown Pressure Control Valve,2CHS*PCV145.

After the crew has stabilized the plant, 4KV emergency bus 2AE will de-energize and EDG 2-1 will fail to automatically start. The crew will enter AOP 2.36.2, Loss of 4KV Emergency Bus, which requires a manual start to restore power to the bus. The SRO will determine appropriate Tech Spec actions.

Secondary Component Cooling Water Pump, 2CCS-P21A, will experience a sheared shaft, requiring the crew to enter AOP 2.28.1, Loss of Secondary Component Cooling Water, and the BOP to manually start the standby pump, 2CCS-P21B, which failed to auto start.

A Feedwater header rupture will occur inside containment. The reactor will trip. Upon the reactor trip, the crew will enter E-O.

MSLI will fail to automatically actuate, requiring the BOP to manually actuate a Steam Line Isolation.

When MSLI is actuated, the main steam line drains (2SDS*AOV] 11 's) will fail to close requiring the BOP to manually close at least 1 train.

CIB will fail to automatically actuate, The ATC will identify the failure to actuate and manually actuate both trains of CIB.

The crew will identify the "c" S/G as faulted and transition to E-2 to isolate.

Train "B" CREV's, Control Room Emergency Ventilation System, will fail to actuate requiring the BOP to manually initiate.

The crew will progress through E-2 and transition to E-l.

The scenario will be terminated after the crew transitions to ES-l.l and isolates the HHSI flowpath by closing 2SIS*MOV867A, B, C, D.

Expected procedure flow path is E-O ~ E-2 ~ E-l ~ ES-l.l.

NUREG-1021, Revision 9 Supplement 1 FENoe Facsimile Rev. AG

BEAVER VALLEY POWER STATION INITIAL CONDITIONS: 25% Power, CBD = 121, Xe increasing BOL, 1935 PPM Boron, IC-2II ADDITIONAL LINEUP CHANGES STICKERS MONITOR SETUP YCT - 2SAS-C21 B CS ATC position MID POWER display EQUIPMENT STATUS DATEITIME OOS TECHNICAL SPECIFICATION(S) 2SAS-C2I BOOS, compressor overhaul 3 days ago SHIFT TURNOVER INFORMATION

1. 25% power, BOL, Xe increasing, main feed regulating valves in service.

2. Shift goal is continue power increase in accordance with 20M-52.4.A.

SCENARIO SUPPORT MATERIAL REQUIRED PROCEDURES NEEDED

1. 20M-52.4.A completed and place kept up through step IV.F.7.g (pg 65) 20M-52.4.A

2. Reactivity plan AOP 2.28.1

3. BOL reactivity placard OM-7 IF, Attachment 3, 2CHS-PT145 AOP 2.36.2 E-O E-l E-2 Attachment A-O.II Attachment A-l.6 BVPS - 2L8 NRC Scenario 1, Rev AG 30f23

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE Initialize IC 211, and establish initial Reactor plant at 25% power, BOL, Xe plant conditions. increasing, RCS boron =1935 PPM, CBD = 121 steps.

Insert the following per the Simulator Inserts all pre-loads required to support the Setup section of the HTML file for this scenario.

scenano:

PRELOAD COMMANDS TRGSET 1 'JPPLP4(1)' Set trigger 1 on reactor trip IMF PMP-CAS004 (0 0) 1 2SAS-C21 BOOS IMF DSGOID Inhibit auto start of EDG 2-1 IMF PPL09A (0 0) Inhibit auto CIB TRN A, manual successful IMF PPL09B (0 0) Inhibit auto CIB TRN B, manual successful IMF PPLIOA (0 0) Inhibit auto MSLI TRN A, manual successful IMF PPLIOB (0 0) Inhibit auto MSLI TRN B, manual successful IMF BST-CCS006 (0 0) 2 Inhibit auto start of2CCS-P21B, manual start successful IMF PMP-CCSOOI (7 0) 0 2CCS-P21A severed leads IMF A6-3B-P0670D (7 0) 0 Ann A6-3B Low CCS pump Disch Press TRGSET 8 'XClI076A == 0' Trigger 8 to clear Ann A6-3B TRG 8 'DMF A6-3B-P0670D' Ann A6-3B clears on start 2CCS-P21B lOR XBSI052P (0 0) ON 2HVC*MOD20IA failed open.

lOR XBSI065P (0 0) ON 2HVC*MOD201 B failed open.

TRGSET 6 'XBSI052C = l' Set trigger 6 on 2HVC*MOD201A CS to close.

TRG 6 'DOR XBSI052P' DOR, 2HVC*MOD201 A manually closes.

TRGSET 9 'XBSI025P == l' Set trigger 9 on "B" Tm CREV'S PB depressed.

TRG 9 'DOR XBSI065P' DOR, 2HVC*MOD20IB manually closes.

TRGSET 5 'FNISPR(l) >= 27.5' Trigger 5 on reactor power> 27.5%

IRF LOA-AFW022 (5 0) 1 2FWE*P22 trip throttle valve trips shut IMF VLV-MSS032A (0 0) 100 Fail 2SDS-AOV111Al open IMF VLV-MSS033A (0 0) 100 FaiI2SDS-AOVI11A2 open IMFVLV-MSS034A (0 0) 100 Fail2SDS-AOVlllBlopen IMF VLV-MSS035A (0 0) 100 Fail2SDS-AOVlll B2 open BVPS 2L8 NRC Scenario 1, Rev AG 40f23

BEAVER VALLEY POWER STATION I** INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE IMF VLV-MSS036A (0 0) 100 FaiI2SDS-AOVIIIClopen IMF VLV-MSS037A (0 0) 100 FaiI2SDS-AOVIIIC2 open TRGSET 10 'XAlI090C = l' Set trigger 10 on 2SDS-AOVI11Al CS to close.

TRG 10 'DMF VLV-MSS032A' DMF, 2SDS-AOVIIIAI manually closes.

TRGSET 11 'XAlI077C l' Set trigger lIon 2SDS-AOVl11A2 CS to close.

TRG 11 'DMF VL V-MSS033A' DMF, 2SDS-AOVIIIA2 manually closes.

TRGSET 12 'XAlI107C = l' Set trigger 12 on 2SDS-AOVIIIBI CS to close.

TRG 12 'DMF VLV-MSS034A' DMF, 2SDS-AOVII1BI manually closes.

TRGSET 13 'XAlI095C == l' Set trigger 13 on 2SDS-AOVII1B2 CS to close.

TRG 13 'DMF VLV-MSS035A' DMF, 2SDS-AOVI11B2 manually closes.

TRGSET 14 'XAII119C == l' Set trigger 14 on 2SDS-AOVI11CI CS to close.

TRG 14 'DMF VLV-MSS036A' DMF, 2SDS-AOVII1CI manually closes.

TRGSET 15 'XAII110C == l' Set trigger 15 on 2SDS-AOVll1C2 CS to close.

TRG 15 'DMF VLV-MSS037A' DMF, 2SDS-AOVl11 C2 manually closes.

Assign shift positions SRO:_ _ _ _ _ _ _ __

ATC:

BOP:

Conduct a shift turnover with oncoming Simulator Frozen until after shift turnover unless operators. it needs to be run momentarily for an alignment change.

When the shift turnover is completed, Simulator running. Crew assumes control of the Unit.

place the simulator to RlJN and commence the scenario.

BVPS - 2L8 NRC Scenario 1, Rev AG 50f23

BEAVER VALLEY POWER STATION r INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENT 1:

lAW Reactivity plan, ATC dilutes/withdraws rods to Continue power increase per reactivity SRO directs the crew to continue power increase raise reactor power to 100%.

plan. lAW 10M-52.4.A.

BOP raises turbine load.

RCS temperature rises in response to rod withdrawal and dilution.

BOP raises turbine load at 12%lhour rate by;

Adjusting "setter" as appropriate.

Depressing "GO".

BOP verifies/maintains the following while raising load,

Valve position limiter -5% above current valve NOTE: Event 2 will occur position.

automatically when Rx power reaches

Voltage regulator is maintaining power factor.

27.5%.

EVENT 2:

2FWE*P22 Trip Throttle Valve trips IMMEDIATE PLANT RESPONSE:

(command preloaded) Computer point Y5172D alarms, TURB DR BOP reports that 2FWE*P22 is tripped.

IRF LOA-AFW022 (5 0) 1 AFW PP TRIPPED A2-3H, Safety System Train A Inoperable ROLE PLAY: 2 minutes after being SRO dispatches operator to investigate 2FWE*P22.

dispatched to inspect 2FWE*P22, report back that the trip throttle valve linkage rod is broken.

SRO enters TS 3.7.5, condition B, w/in 2 hrs realign Operable pumps to separate hdrs, (for this failure this action is not required) 72 hrs to restore AFW train to operable status.

BVPS - 2L8 NRC Scenario 1, Rev AG 60f23

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE Proceed with next event after power is raised above 30% as indicated by A12 2G (NOT P-8) status panel clearing or at LE discretion.

EVENT 3:

2CHS*PT145 fails high IMF XMT-LDS007A (0 0) 600 IMMEDIATE PLANT RESPONSE:

A2-3F, Letdown Flow Path Trouble A TC reports unexpected letdown alarm.

2CHS-PI145 indication at 600 psig. BOP refers to ARP.

2CHS*PCV145 opens. ATC notes 2CHS-PI145 at full scale and Letdown flow rises. 2CHS*PCV145 traveling open.

2CHS*RV209 may lift.

SRO enters 20M-7.4.IF, Attachment 3. ATC places 2CHS*PCV145 in manual and positions valve to stabilize net charging and restore letdown flow to pre-event value.

\Vith 2CHS*PCV145 in manual, SRO establishes a control band for manual control ofletdown pressure.

ATC monitors for proper operation of2CHS*RV209.

ROLE PLAY: 3 minutes after being dispatched to check local pressure on SRO dispatches operator to check local lid pressure on 2CHS-PI146, report back that pressure 2CHS-PI146.

indicates 110 psig.

After plant has been stabilized, continue with next event at LE discretion BVPS 2L8 NRC Scenario 1, Rev AG 70f23

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENT 4:

Loss of 2AE 4kv emergency bus with an auto start failure of2-1 EDG. IMMEDIATE PLANT RESPONSE:

4KV ACB 2AlO trips open IMF BKR-HIVOI (0 0) 0 4KV bus 2AE voltage reduces to zero (VB-C) BOP reports multiple unexpected electrical alarms.

Multiple electrical related annunciators. BOP identifies 4kv Bus 2AE is de-energized and that the 2-1 EDG has failed to start.

BOP reports that 4kv Bus 2DF is energized.

ATC verifies 2CHS*P21B remains running, verifies primary plant is stable and begins referring to ARP's.

SRO enters AOP 2.36.2 for Loss of 4KV Crew verifies no overcurrent electrical alarms.

Emergency Bus. SRO directs BOP to manually start EDG 2-1.

BOP successfully starts EDG 2-1.

ATC verifies 2SWS*P21 A is running and opens cooling water supply valve, 2SWS*MOVl13A.

ROLE PLAY: If dispatched with Crew performs EO P Attachment A-I. 6, lAW direction Attachment A-1.6 to verifY MCC of AOP 2.36.2 to verify EDG auto loading is feeder breakers are closed, wait 10 complete.

minutes then report all are closed.

SRO evaluates TS for emergency bus and EDG 2-1.

SRO detennines 20ST-36.7 is required within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to verify operability of remaining sources per TS 3.8.1, Conditions A and B.

BVPS - 2L8 NRC Scenario], Rev AG 80f23

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENT 5:

Turbine Plant Component Cooling Water Trouble (2CCS-P2IA sheared IMMEDIATE PLANT RESPONSE:

shaft) 2CCS-P21A ammeter reduces to ~4 amps. BOP reports unexpected CCS related alarms.

A6-3B, CCS pump discharge press low ATC refers to ARP's TRG! 7 (actuate trigger 7, all required A 7-6F, Main Leads Cooling Trouble commands are preloaded.) A7-2H, EHC Temperature High 2CCS-P21B fails to auto start when pressure BOP recognizes failure of2CCS-P21B to auto start on reduces to < 75 psig. low pressure and manually starts 2CCS-P21B.

SRO enters AOP 2.28.1.

NOTE: IfCCS cooling flow is not A6-3D, STA and Cond Polishing Air Sys Trb, quickly re-established, station air (alarms later depending on response BOP recognizes 2SAS-C21A tripped.

compressor, 2SAS-C21A will trip on time) high temperature and will not be able to Crew dispatches an operator to start diesel air compo be recovered, the diesel air compressor SRO may enter AOP 2.34.1 for Loss of Station will auto start and supply air as Air, no actions are required, AOP steps are not required. scripted.

ROLE PLAY: If dispatched to start 2IAS-C21, wait 2 minutes then insert .

IRF LOA-CASOll (0 0) 1, wait compressor loads then report back.

ROLE PLAY: If dispatched to investigate 2SAS-C21 A trip, wait 2 minutes then report 2SAS-C21 A has tripped on high temperature.

Proceed with next event at LE discretion BVPS - 2L8 NRC Scenario 1, Rev AG 90f23

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS / PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 6, 7, 8, & 9 Feed line break inside containment Feedwater header rupture inside containment IMF FLX-CFW33 (0 0) 8700 causes an automatic reactor trip.

Multiple malfunctions occur on reactor trip. Additional failures that occur on the reactor trip; Automatic main steam line isolation actuation All commands preloaded failure, when MSLI is manually initiated, 2SDS IMFPPL09A AOVIII 's fail to automatically close, requiring IMFPPL09B manual closure.

IMFPPLIOA cm will fail to automatically actuate.

IMF PPLIOB "B" train CREV's fails to automatically actuate.

TRGSET 1 'JPPLP4(1)'

lOR XBSI052P (0 0) ON lOR XBSI065P (0 0) ON TRGSET 6 'XBSI052C = l' TRG 6 'DOR XBSI052P' TRGSET 7 'XBSI025P == l' TRG 7 'DOR XBSI065P' SRO enters E-O. ATe and BOP commence lOA's ofE-O.

ATC verifies Reactor trip.

A5-6D - LIT.

Power range indication is < 5%.

Neutron flux is dropping.

BVPS 2L8 NRC Scenario 1, Rev AG 10 of23

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE BOP verifies Turbine trip.

Throttle OR Governor valves ALL closed.

Main Generator output brks open.

Exciter Circuit breaker open.

EVENTS 7, 8, & 9: (continued) BOP verifies Power to AC Emergency Busses.

Using VB-C voltmeters, verifies either AE or DF has voltage indicated.

BOP identifies that AE bus remains energized from EDG 2-1 and DF bus remains energized from offsite power.

SI automatically actuated Check SI Status Crew checks ifSI is required

ATC checks Cnmt press> 5psig

A TC checks PRZR press < 1860 psig

ATC/BOP checks Steamline press < 500 psig Crew detennines SI is Required; ATC manually actuates SI by turning both trains' control switches.

ATC/BOP, Sounds Standby Alann, announces reactor trip and safety injection.

BOP verifies leak collection filtered exhaust fan 2HVS-FN204A or B running.

BVPS - 2L8 NRC Scenario 1, Rev AG 11 of23

BEAVER VALLEY POWER STATION

[ uiNSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE ATC verifies SI System Status.

Both 2CHS*P21A and P21B pumps running.

HHSI Flow indicated,

Both LHSI pumps running.

EVENTS 7, 8, & 9: (continued) BOP verifies AFW System status.

Motor-driven AFW Pumps - Both pumps RUNNING

Turb driven AFW Pump Stm Supply Isol Valves OPEN

AFW Throttle Vlvs FULL OPEN

Total AFW Flow - > 340 GPM List of Attachment A-O.II Discrepancies: SRO directs BOP to perfonn Attachment A-O.II.

NOTE:

Evaluation of BOP perfonning Discrepancies:

Attachment A-O.II begins on page 21. MSLI failed to automatically isolate.

2SDS-AOVIIl 's, steam line drains failed to automatically close.

cm failed to automatically actuate.

"B" train CREV's failed to automatically actuate.

BVPS 2L8 NRC Scenario 1, Rev AG 120f23

BEAVER VALLEY POWER STATION r=::JNSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE EVENTS 7, 8, & 9: (continued) ATC checks RCS Tavg stable at or trending to 547°F NOTE: RCS temperature < 547°F and dropping due to

ATC verifies no steam release is occurring.

Automatic main steamline isolation Safety Injection flow. (Condenser steam dumps closed) was inhibited.

ATC verifies Reheat steam is isolated.

ATC reduces total feedflow to minimize C/D.

Critical Task: E-O.P Crew manually actuates main steam Crew determines cooldown is continuing and line isolation before a Severe (orange determines SLI is required.

path) challenge develops to either the If not previously actuated, BOP manually initiates Sub-criticality or Integrity CSF or MSLI and closes 2SDS-AOVl11 'so before transition to ECA-2.1, whichever occurs first.

Basis for Selection:

SAFETY SIGNIFICANCE -- Failure to close the MSIVs under the postulated plant conditions causes challenges to CSFs beyond those irreparably introduced by the postulated conditions.

Additionally, such an omission constitutes a "demonstrated inability by the crew to recognize a failure of the auto actuation of an ESF system or component and to take an action that would prevent a challenge to plant safety."

cm not actuated at this time. ATC checks recirc spray pumps NONE RUNNING BVPS 2L8 NRC Scenario 1, Rev AG 13 of23

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 7,8, & 9: (continued) ATC verifies PRZR isolated

PORVs CLOSED

Spray Valves - CLOSED

Safety relief valves - CLOSED (use PSMS)

PRT conditions CONSISTENT WITH EXPECTED VALUES

Power to at least one block valve AVAILABLE

Block valves - AT LEAST ONE OPEN NOTE: ATC checks ifRCPs should be stopped When the crew recognizes Containment

DIP between RCS pressure and highest SIG pressure has exceeded 11 psig and pressure NOT LESS THAN 205 PSID manually initiates CIB, the crew will

Criteria for stopping is not met - Leaves RCPs shutdo'vvn all RCP's due to loss of running based upon DP requirements.

cooling.

RCP's may be sid at this time due to the operator action for the CIB, otherwise RCP's would remain running at this point.

A TC/BOP checks if any SIGs are taulted

Pressures in all SIGs - ANY DROPPING IN AN 'UNCONTROLLED MANNER OR

ANY SIG COMPLETELY DEPRESSURIZED Crew determines "c" SIG is faulted.

SRO transitions to E-2.

BVPS 2L8 NRC Scenario 1, Rev AG 14of23

BEAVER VALLEY POWER STATION r INSTRUCTIONAL GUIDELINES EbANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE EVENTS 7,8, & 9: (continued) ATC/BOP actuates CREVS "B" Train CREV's automatic actuation

Verifies the control room air intake and failed requiring the crew to manually exhaust Dampers are CLOSED.

initiate.

Crew determines "B" Train CREV's failed to actuate, All commands preloaded ATC/BOP manually actuates CREV's.

SRO requests a BV-I operator to verifY proper Unit 1 CREVS actuation.

SRO directs STA to Commence Control Room ventilation actions. Refer to Attachment A-2A.

NOTE: ATC/BOP verifies steamline isolation has occurred by Failure ofMSLI should have been checking all YELLOW SLI identified components are recognized by this time. in the designated position. (previously verified)

"C" S/G pressure is lower than "A" & "B. BOP identifies "A" & "B" steam generator pressures "A" & "B" may be slowly lowering as expected are "Stable or rising".

due to the cooldown. Crew should respond with "Stable" for "A" & "B" S/G's.

"C" S/G pressure & level lowering. Crew identifies "C" S/G as faulted.

BVPS - 2L8 NRC Scenario 1, Rev AG 150f23

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS / PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 7,8, & 9: (continued) BOP isolates the faulted, "C" S/G as follows, Critical Task: E-2.A

Verifies FWI (previously verified via Crew isolates the faulted S/G and Attachment A-0.11) directs operator to close isolation

Closes AFW throttle valves on "C" S/G valves operated from outside of the 2FWE*HCV100A and 100B control room before transition out of

Verifies Residual Heat Release Valve is E-2. closed.

Directs field operator to isolate 2SVS-29 Basis for Selection:

Isolates steam supply to turbine driven AFW SAFETY SIGNIFICANCE -- Failure to pump, 2MSS*SOV105C and 105F isolate a faulted S/G that can be isolated

Verifies closed, "C" S/G Atmospheric steam causes challenges to CSFs beyond those dump valve.

irreparably introduced by the postulated

Verifies S/G blowdown isolated, conditions. Also, depending upon the 2BDG*AOVIOOCI plant conditions, it could constitute a

Verifies S/G Blowdown sample isolation demonstrated inability by the crew to valves, 2SSR*AOV117 A, B, C closed.

recognize a failure of the automatic actuation of an ESF system or component.

ROLE PLAY: 10 minutes after being dispatched close 2SVS-29, insert IRF LOA-MSSOll (0 0) 0, then report that 2SVS-29 is closed.

BOP verifies PPDWST level is > 85 inches.

BVPS - 2L8 NRC Scenario 1, Rev AG 160f23

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 7, 8, & 9 (continued) Crew checks if S/G tubes are intact

Check all S/G levels - NONE RISING IN AN UNCONTROLLED MANNER

Check Secondary Radiation - CONSISTENT WITH PRE-EVENT VALUES Determines no S/G levels are rising in an uncontrolled manner and Secondary Radiation - is CONSISTENT WITH PRE-EVENT VALUES; Crew determines S/G Tubes ARE INTACT.

Crew checks if SI Flow should be Reduced ATC verifies RCS Subcooling is > 41°F [59°F ADVERSE CNMT] based on CETC's BOP confirms secondary heat sink available by >340 gpm of feed flow available OR NR level in at least 1 S/G> 12% [31 % ADVERSE CNMT].

NOTE:

Due to timing, procedure progression ATC confirms RCS pressure is stable or rising.

and plant conditions (Adverse cnmt or not adverse), it is possible that the ATC reports Pzr level is < 17% [38% ADVERSE conditions may support direct transition CNMT]

to ES-l.l. If so, E-l steps on pages 18 and 19 are not applicable. Crew determines that current plant conditions do not support SI reduction.

SRO determines transition to E-l, Loss of Reactor or Secondary Coolant is appropriak.

BVPS - 2L8 NRC Scenario 1, Rev AG 170f23

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE EVENTS 7,8, & 9: (continued) ATC checks if CREVS should be actuated:

Checks EITHER of the following:

Control Room Radiation Monitor 2RMC*RQ201,202 - NOT IN HIGH ALARM

CIB - HAS NOT OCCURRED Crew reports CREV's required and previously actuated.

ATC checks if RCPs should be stopped

DIP between RCS pressure and highest S/G pressure - LESS THAN 205 PSID [220 PSID ADVERSE CNMT]

DP Criteria for stopping RCPs is not met -

RCP's previously shutdown due to CIB.

ATC confinns ClB was previously manually initiated.

ATC verifies SWS flow to all 4 Recirc Spray HX's.

ATC verifies RWST level is NOT < 381 inches.

ATCIBOP checks if any S/Gs are faulted

Pressures in all S/Gs - ANY DROPPING IN AN UNCONTROLLED MANNER OR

ANY S/G COMPLETELY DEPRESSURIZED "C" S/G was previously identified as faulted and has been isolated.

BVPS - 2L8 NRC Scenario 1, Rev AG 180f23

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 7, 8, & 9: (continued) BOP Checks Intact SIG Levels

Narrow range levels - GREATER THAN 12%

[31 % ADVERSE CNMT]

Controls feed flow to maintain narrow range level between 12% [31 % ADVERSE CNMT] and 50%.

Crew checks if SIG tubes are intact

Check all SIG levels NONE RISING IN AN UNCONTROLLED MANNER

Check Secondary Radiation - CONSISTENT WITH PRE-EVENT VALUES Crew detennines no SIG levels are rising m an uncontrolled manner and Secondary Radiation is consistent with pre-event values, therefore all SIG tubes are intact.

ATC checks PORV's and block valves.

Power to block valves AVAILABLE

PORVs CLOSED

Block valves AT LEAST ONE OPEN BVPS - 2L8 NRC Scenario 1, Rev AG 190f23

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 7, 8, & 9: (continued) Crew checks ifSI Flow should be reduced ATC verifies RCS Subcooling is greater than 41°F [59 OF ADVERSE CNMT] based on CETC's BOP confirms secondary heat sink available by >340 gpm of feed flow available OR NR level in at least 1 S/G> 12% [31 % ADVERSE CNMT].

ATC confirms RCS pressure is stable or rising.

ATC confirms Pzr level > 17% [38% ADVERSE CNMT]

Crew determines that current plant conditions support SI reduction SRO transitions to ES-l.l, SI Termination Crew resets SI, CIA and CIB signals.

ATC stops 1 charging pump.

A TC verifies RCS pressure is stable or rising.

ATC closes 2SIS*MOV867A,B,C, D.

Terminate scenario when the crew isolates the HHSI flowpath by closing 2SIS*MOV867A, B, C, D in ES-l.l.

Classify Event:

Unusual Event, Tab 2.10, Steam/Feed Line Break due to an Unplanned Rapid depressurization of the Main Steam System resulting in a rapid RCS cooldown AND Safety Injection.

BVPS - 2L8 NRC Scenario 1, Rev AG 200f23

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES I PLANT sTAtus I PROCEDURAL GUIDANCE I . EXPECTED STUDENT RESPONSE Attachment A-O.ll 'Verification of BOP perfonns Attachment A-O.ll, 'Verification of Automatic Actions' perfonned as time Automatic Actions' as follows:

& manpower pennit Checks both EDGs running Ensure Reheat Stearn Isolation Ensure reheat stearn isolation

Verify 2MSS-MOVlOOA and B - CLOSED

Reset reheater controller.

Critical Task E-O.P: Check If main steamline isolation required Crew manually actuates main steam

CNMT pressure - > 7 PSIG line isolation before a Severe (orange -OR path) challenge develops to either the

Stearnline pressure - < 500 PSIG Sub-criticality or Integrity CSF or -OR before transition to ECA-2.1,

Stearnline pressure high rate of change - 100 whichever occurs first PSIG DROP IN 50 SECONDS Basis for Selection: Detennines CNMT pressure is > 7 PSIG and SAFETY SIGNIFICANCE -- Failure to Manually actuates stearnline isolation by depressing close the MSIV s under the postulated all 4 SLI pushbuttons (BB-C) plant conditions causes challenges to CSFs beyond those irreparably Verifies SLI by checking all YELLOW SLI marks introduced by the postulated conditions. LIT Additionally, such an omission constitutes a "demonstrated inability by Identifies 2SDS-AOVIIIAl,Bl,CI, A2,B2,& C2 all the crew to recognize a failure of the failed to close. Manually closes all valves.

auto actuation of an ESF system or component and to take an action that would prevent a challenge to plant safety."

BVPS - 2L8 NRC Scenario 1, Rev AG 210f23

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE I**** EXPECTED STUDENT RESPONSE Attachment A-O.ll - (continued) Establish domestic water system cooling to station air NOTE: compressors; BOP may have already pre-emptively

Opens 2CCS-AOVI18.

opened 2CCS-AOV118 to provide

Verifies at least 1 air compressor is running.

cooling to the Station Air compressors.

Verifies at least 1 CCP pump is running unless a CIB has occurred.

Align Neutron Flux Monitoring For Shutdown

Transfer (2NME-NR45] Nuclear Recorder to operable source and intermediate range displays.

Critical Task E-O.E: Check CIB And CNMT Spray Status Crew manually actuates at least the

Containment pressure - HAS REMAINED minimum required complement of LESS THAN 11 PSIG containment cooling equipment before an Extreme (red path) If not Actuate CIB if required by:

challenge develops to the

Manually initiate CIB BOTH SWITCHES Containment CSF. FOR BOTH TRAINS

Manually align equipment as required Basis for Selection:

Verify all RCPs STOPPED SAFETY SIGNlFICANCE -- Failure to

BV-1 operator verifies CREVS actuation manually actuate the minimum required

Service water established to RSS HX(s) complement of containment cooling equipment under the postulated BOP manually initiates CIB if ATC did not previously conditions constitutes a "demonstrated identify and initiate.

inability by the crew to recognize a failure/incorrect auto actuation of an ESF system or component."

BVPS - 2L8 NRC Scenario 1, Rev AG 220f23

BEAVER VALLEY POWER STATION L INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE Attachment A-O.ll- (continued) Verify Service Water System In Service

SWS Pumps - TWO RUNNING

Check SWS header pressure - > 55 psig

SWS pump Seal Water Pressure - NOT LOW Verify both CNMT hydrogen analyzers running by 2HCS*SOVIOOAl, Bl - CNMT Sample amber lights

-LIT Verify ESF Equipment Status

Verify SI status by checking all RED SIS marks

-LIT

Verify CIA by checking all ORANGE CIA marks - LIT

Verify FWI by checking all GREEN FWI marks LIT Verify Power To Both AC Emergency Busses Restore power as required Attachment A-O.ll COMPLETE Discrepancies: Upon Completion, Report Any Discrepancies to SRO.

MSLI failed to automatically isolate 2SDS-AOVIll 's, steam line drains failed to automatically close CIB failed to automatically actuate.

"B" train CREV's failed to automatically actuate.

BVPS - 2L8 NRC Scenario 1, Rev AG 230f23

Alppen d"IX D " 0 Utl"Inn S cenano Form ES D 1 -

Facility: BVPS Dnit2 Scenario No.:2 Op Test No.: 2LOT8 NR(

Examiners: Candidates: SRO ATe BOP Initial IC 219(17): 72% power, MOL, Eq Xe, CB "D"@180 steps, RCS boron - 1140 ppm.

Conditions:

Turnover: Maintain steady state power at 72%, 2FWE*P23A OOS, 2SAS-C21B OOS Critical Tasks: 1. E-O.A Manually trip the Reactor

2. E-O.Q Manually trip the turbine

3. FR-H.1.A Establish feedwater flow before Feed and Bleed criteria Event Malf. No. Event Type Event Description No.

1 (C) ATC, SRO N44 fails high, rods automatically step in.

(TS) SRO 2 (R)ATC 2FWS-P21B trips/ reduce power to 52%

(e) BOP, SRO 3 (TS) SRO Misaligned Rod 4 (M) ALL 2ReS*P21B locked rotor trip with Automatic Reactor trip failure and 400 gpm SBLOeA.

5 (e) BOP, SRO Automatic turbine trip failure 6 (M)ALL Loss of all auxiliary feed water, entry into FR-H.l 7 (e) BOP, SRO Failure of2FWS-P24, 2FWS-P21A and P21B (requires secondary depressurization and use of condensate pump.

8 (C) BOP, SRO 2HVS-FN204A and B trip, requires manual starting of at least 1 fan.

9 (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG*1021 , Revision 9 Supplemenl1 FENOC Facsimile Rev. AG

Appendix D Scenario Outline Form ES-D-1 2L8N2 The crew will assume the shift at 72% power with instructions to maintain steady state conditions.

N-44 will fail high causing the control rods to automatically insert. The crew will enter AOP 2.1.3, RCCA Control Bank Inappropriate Continuous Movement, verify no load rejection is occurring and then the ATC will place the control rods in Manual to stop rod insertion. The US will then enter AOP 2.2.1 C, Power Range Channel Malfunction, to remove the channel from service and determine appropriate Tech Spec action.

Main Feedwater pump, 2FWS-P21B will then trip, the crew will enter AOP 2.24.1, Loss of Main Feedwater AOP, and begin an immediate power reduction to 52%. While the rods are inserting, 1 rod will experience a moveable gripper failure causing the rod to ratchet inward on each step demand. The crew will identify the misaligned rod and initiate boration for the remainder of the power reduction. After the plant has stabilized, the SRO will enter AOP 2.1.8, Rod Inoperability, and address Tech Spec's for the misaligned rod.

The "B" reactor coolant pump will then experience a locked rotor trip, the reactor will fail to automatically trip, the ATC will manually trip the reactor, a 400 gpm SBLOCA will occur on the Rx trip. The crew will enter E-O.

The turbine will fail to automatically trip, requiring the BOP to manually trip the turbine.

A loss of all aux feed water will then occur, the crew will recognize the loss and enter FR-H.l, Response to Loss of Secondary Heat Sink, to re-establish feedwater.

The crew will attempt to restore normal feedwater via the startup feedwater pump and the main feedwater pumps, Various failures will prevent each pump from starting. The crew will then depressurize the S/G's to establish feedwater flow from a condensate pump. When feedwater flow has been re-established, the SRO will return to E-O and then transition to E-l.

The Ventilation fans, 2HVS-FN204A & B will trip on the reactor trip, the BOP will start at least 1 fan.

The scenario will be terminated after the crew transitions to ES-l.l.

Expected procedure flow path is E-O ~ FR-H.l -+ E-O ~ E-l ~ES-l.l.

NUREG-1021, Revision 9 Supplement 1 FENoe Facsimile Rev. AG

BEAVER VALLEY POWER STATION INITIAL CONDITIONS: 72% Power, CBD = 180, Equilibrium Xe, MOL, 1140 PPM Boron, IC-219 ADDITIONAL LINEUP CHANGES STICKERS MONITOR SETUP YCT - 2FWE*P23A CS ATC position - HIGH POWER display YCT - 2SAS-C21B CS EOUIPMENT STATUS DATEITIME OOS TECHNICAL SPECIFICATION(S) 2FWE*P23A OOS 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ago 3.7.5 condition B 2SAS-C21B OOS 3 days ago SHIFT TURNOVER INFORMATION

1. 72% power, MOL Equilibrium Xe, shift goal is to steady state conditions.

SCENARIO SUPPORT MATERIAL REQUIRED PROCEDURES NEEDED

1. MOL Reactivity placard AOP 2.1.3 AOP 2.1.8 AOP 2.2.1C AOP 2.24.1 E-O E-1 FR-H.1 Attachment A-0.11 Attachment A-1.10 BVPS - 2L8 NRC Scenario 2, Rev AG 30f23

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE Initialize IC 219, and establish initial Reactor plant at 72% power, MOL, Equilibrium plant conditions. Xe, RCS boron = 1140 PPM, CBD 180 steps.

Insert the following per the Simulator Inserts all pre-loads required to support the Setup section of the HTML File for this scenano.

scenarIO:

PRELOAD COMMANDS TRGSET 1 'JPPLP4(1)' Set trigger 1 on reactor trip IMF RCS02B (1 0) 400 30 400 gpm LOCA on Rx trip IRF LOA-HIVOSS (0 0) 1 2FWE*P23A breaker racked out IMF PMP-CAS004 (0 0) 1 2SAS-C21B OOS IMF EHC08A (0 0) Turbine fails to auto trip, manual successful TRGSET 2 'OAFWT22 . SO' Set trigger 2 on 2FWE*P22 start IFR LOA-AFW022 (2 0) 1 2FWE*P22 trips during startup/sequencing IMF VLV-CFW027 (0 0) 0 Prevent 2FWS-P24 start, FR-H.l conditions IMF PMP-AFW002 (1 IS) 2 2FWE*P23B trips 15 seconds after reactor trip TRGSET S 'JP760PT(2) = 1 .AND.

Trigger 5 on FWS-P21B trip and pwr < 62%

FNISPR(I) <= 62' IMF CRF03-F6 (S 0) 1 CBD rod F06 movable gripper coil failure IMF PPLOIA (0 0) 0 Prevent AUTO Rx Trip TRN "A" IMF PPLOIB (0 0) 0 Prevent AUTO Rx Trip TRN "B" IMF PPLI0A (0 0) 0 Prevent AUTO MSLI TRN "A" IMF PPLI0B (00) 0 Prevent AUTO MSLI TRN "B" lOR XClI04ST (0 0) OFF 2FWS-P21A failure to start TRGSET 8 'OCFWP21B >= 0.6 Set trigger 8 on FWS-P21B start attempt.

.AND. XClI046T = l' TRG 8 'IMF PMP-CFWOOS (0 0) 2' 2FWS-P21B, Trip after 2nd motor starts IMF PMP-MSC036 (1 0) 1 2HVS*FN204A trips on Rx trip TRGSET 4 'XBSI071T l' TRG 4 when 2HYS*FN204A CS taken to start TRG 4 'DMF PMP-MSC036' 2IIVS*FN204A starts IMF PMP-MSC037 (10) 1 2HVS*FN204B trips on Rx trip TRGSET 6 'XBSI083T l' TRG 6 when 2HYS*FN204B CS taken to start TRG 6 'DMF PMP-MSC037' 2HVS*FN204B starts BVPS - 2L8 NRC Scenario 2, Rev AG 40f23

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE Assign shift positions SRO:-----------------

BOP:

Conduct a shift turnover with oncoming Simulator Frozen until after shift turnover unless operators. it needs to be run momentarily for an alignment change.

When the shift turnover is completed, Simulator running. Crew assumes control of the Unit.

place the simulator to RUN and commence the scenario.

BVPS 2L8 NRC Scenario 2, Rev AG 50f23

BEAVER VALLEY POWER STATION CTNSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENT I:

N-44 fails high Rods automatically step inward in response to ATC reports unexpected alarms and rod motion.

IMF NIS03D (0 0) 200 15 N-44 failure.

Crew enters AOP 2.1.3 for Inappropriate Rod ATC verifies no load rejection in progress and places motion. Rod control to manual to stop the rod insertion.

SRO enters AOP 2.2.1 C to address failed NI Crew removes N-44 from service.

channel.

Within 1 hr, verifies P-8, P-9, & P-IO interlocks in required state for 72% power.

Within 72 hrs, trips nuclear bistables by removing control power fuses from Drawer A for N44.

ATC verifies Control rod group selector sw in manual.

BOP verities Bypass feedwater control valves in manual.

BOP turns Rod Stop Bypass switch for N44 on NIS Rack N50 to BYPASS.

ATC verifies Status light for Overpwr Rod Stop Bypass for N44 is lit Crew verifies Rx power is > 50%.

BOP determines all PR channel upper and lower detector inputs to QPTR are operable.

BOP turns "Comparator Channel Defeat Switch" on NIS rack N371N46 to N44 position.

ATC ensures VB recorders are selected to operable detectors.

BVPS - 2L8 NRC Scenario 2, Rev AG 60f23

BEAVER VALLEY POWER STATION CINSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE After removing Rod block, ATC withdraws control rods to restore Tavg.

SRO addresses TS for N-44 failure, determines TS 3.3.1, condition D is applicable.

Proceed with next event at LE discretion BVPS 2L8 NRC Scenario 2, Rev AG 70f23

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 2 &3:

IMMEDIATE PLANT RESPONSE:

2FWS-P21B tripsl Movable gripper Feed flows drop, S/G levels decrease, Main feed failure on Rod F6 when < 62%. regulating valves open.

IMF PMP-CFW005 (0 0) 1 A6-9E, tOE, lIE S/G 21A(B)(C) Level IMF CRF03-F6 (5 0) 1 (preloaded) Deviation From Setpoint. Crew detennines that 2FWS-P2IB has tripped.

SRO enters AOP 2.24.1 SRO directs an immediate power reduction to < 52%.

BOP depresses 1st STG IN PB then lowers turbine load at 5%/minute rate by,

Adjusting "setter" to:S 50% power equivalent.

Depressing "GO" ATC inserts control rods lli'1d initiates emergency boration for an expected 20% power reduction by opening 2CHS*MOY350 and starting the "A" Boric Acid pump.

BOP verifies all available pumps are running, Starts 2CNM-P21A.

When < 62% power, rod F6 will start to ATC identifies rod misalignment, stops inserting "ratchet" in on each rod step. control rods and continues boration.

BOP verifies steam flow is less than available feed flow and that S/G levels are trending to 44%.

After plant is stable and S/G levels are SRO identifies TS 3.1.4, Condition B, as applicable recovering, SRO enters AOP 2.1.8 to address the for the misaligned rod.

misaligned rod. SRO identifies TS 3.4.1 for DNB.

Continue with next event at LE discretion BVPS - 2L8 NRC Scenario 2, Rev AG 80f23

BEAVER VALLEY POWER STATION

[ INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 4, 5, 6, 7 & 8:

IMMEDIATE PLANT RESPONSE:

2RCS-P21B locked rotor with an A5-2G, 113 Reactor Coolant Pump Loop Flow automatic reactor trip failure, turbine Low Reactor Trip trip failure and 400 gpm SBLOCA. ATC reports 2RCS-P21B has tripped and 1st out annunciator is in without an automatic reactor trip.

IMF RCP05B (0 0)

SRO directs ATC to manually trip the reactor SRO enters E-O. ATC and BOP commence lOA's ofE-O.

CRITICAL TASK - E-O.A: Crew Automatic reactor trip failure. ATC verifies Reactor trip after manually tripping manually trips the reactor from the reactor from either BB-B or BB-A Control Room before performing the

A5-6D - LIT.

mitigation strategy of FR-S.l.

Power range indication is < 5%.

Basis for Selection:

Neutron flux is dropping.

SAFETY SIGNIFICANCE -- Failure to manually trip the reactor causes a challenge to the subcriticality CSF beyond that irreparably introduced by the postulated conditions. Additionally, it constitutes an "incorrect performance that necessitates the crew taking compensating action which complicates the event mitigation strategy and demonstrates the inability by the crew to recognize a failure ofthe automatic actuation of the RPS."

BVPS - 2L8 NRC Scenario 2, Rev AG 90f23

BEAVER VALLEY POWER STATION IN§IRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTEDSTUDENTRESPONSE ~

EVENTS 4, 5, 6, 7 & 8: (continued) Automatic turbine trip failure. BOP verifies Turbine trip did NOT occur

Throttle OR Governor valves NOT closed.

Critical Task: E-O.Q

Main Generator output brks - Not open.

Crew manually trips the main

Exciter Circuit breaker - not open.

turbine before a Severe (orange path) challenge develops to either the Sub BOP manually trips the turbine, then verifies; criticality or the Integrity CSF or

Throttle OR Governor valves ALL closed.

before transition to ECA-2.1,

Main Generator output brks - open.

whichever occurs first.

Exciter Circuit breaker - open.

Basis for Selection:

SAFETY SIGNIFICANCE -- Failure to trip the main turbine under the postulated plant conditions causes challen!!es to CSFs hevond those irreparably introduced by the postulated conditions. Additionally, such an omission constitutes a demonstrated inability by the crew to "take an action...that would prevent a challenge to plant safety."

BOP verifies Power to AC Emergency Busses

Using VB-C voltmeters, verifies either AE or DF has voltage indicated.

BOP identifies that both AE and DF busses are energized from offsite power.

BVPS 2L8 NRC Scenario 2, Rev AG 100f23

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE -------EXP-E-C-T-ED-ST-U-D-E-N-T-R-E-S-PO-N-S-E-----,

EVENTS 4, 5, 6, 7 & 8: (continued) SI automatically actuated Check SI Status Crew checks if SI is required NOTE:

ATC checks Cnmt press> 5psig SI will be required due to 400 gpm

A TC checks PRZR press < 1860 psig SBLOCA, depending on timing, ifSI

ATC or BOP checks Steamline pressure < 500 has not actuated, the crew may initially pSlg enter ES-O.l or may preemptively actuate SI at this time. Crew determines SI is Required; ATC manually actuates SI by turning both trains' control switches.

ATC/BOP, Sounds Standby Alarm, announces reactor trip and safety injection.

BOP verifies neither leak collection filtered exhaust fan, 2HVS-FN204A nor B are running.

BOP starts at least 1 leak collection filtered exhaust fan.

ATC verifies SI System Status

Both 2CHS*P21A and P21B pumps running.

HHSI Flow indicated,

Both LHSI pumps running BVPS - 2L8 NRC Scenario 2, Rev AG 11 of23

BEAVER VALLEY POWER STATION INSTRUCTIONAl.. GUIDEl..INES-r PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE-***~

EVENTS 4, 5, 6, 7 & 8: (continued) BOP verifies AFW System status

Motor-driven AFW Pumps - NONE RUNNING

Turb driven AFW Pump Stm Supply Isol Valves - OPEN but turbine is tripped.

AFW Throttle Vlvs FULL OPEN

Total AFW Flow < 340 GPM BOP reports no Aux Feedwater pumps running and no aux feed water flow.

SRO recognizes that AFW flow cannot be established and enters FR-H.I ATC checks if secondary heat sink is required by:

Verifying RCS press is > any non-faulted S/G.

w RCS Hot leg temperatures> 350°F.

NOTE: Crew checks ifRCS Bleed and Feed should be PORV's may lift several times during initiated.

this transient due to natural circulation

BOP verifies Wide Range level in at least 2 being established while Safety Injection SIG's is > 14%.

flow is occurring.

ATC verifies Pzr pressure is < 2330 psig.

With WR levels> 14%, PORV's SRO notifies crew that this is a continuous action step.

opening are not due to Loss of Heat Sink; Bleed and Feed is not required.

BOP checks Primary Plant Demineralized Water storage tank level is > 85 inches.

BVPS 2L8 NRC Scenario 2, Rev AG 120f23

BEAVER VALLEY POWER STATION r INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 4, 5, 6, 7 & 8: (continued) Crew tries to establish AFW flow to at least 1 S/G.

ATCIBOP verifies S/G Blowdown and blowdown ROLEPLAY: sample lines are isolated.

When directed to investigate AFW pump status locally, wait 3 minutes Crew confirms then report: * "A" motor-driven pump is OOS 2FWE*P23B is not running, nothing * "B" motor-driven pump has tripped obvious wrong at pump.

Turbine-driven pump tripped on startup.

2FWE*P22 is not running due to the

All AFW throttle valves are open.

trip throttle valve linkage rod being broken.

SRO continues to try to restore AFW flow while dispatched to DF switchgear, wait 2 continuing in procedure.

minutes then report that overcurrent relay 51-VF218 is tripped on ACB BOP confinns AFW flow is not> 340 gpm.

2F18 for 2FWE*P23B.

Crew dispatches an operator to locally establish AFW flow via Attachment A-1.8.

ATC stops all RCP's. ("A" & "C" RCP's, "B" previously tripped.)

BOP verifies all 3 condensate pumps are running.

ATC verifies CNMT FWI valves are closed.

SRO directs crew to reset SI and FWI signals.

ATC/BOP resets;

SI signal both trains

FWI signal - both trains.

ATC/BOP opens all Feedwater CMNT isol valves, 2FWS*HYV157A, B, C.

BVPS - 2L8 NRC Scenario Rev AG 13 of23

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE J EVENTS 4,5,6,7 & 8: (continued) BOP attempts to start the S/G Startup Feed pump by;

Verifying 2CNM-DCVIOO is open 2FWS-P24 will not start due to failure of

Placing CS for 2FWS-P24 to start and hold recirculation valve, 2FWR-FCV155 to open. untiI2FWR-FCVI55 opens.

BOP recognizes failure of2FWR-FCV155 to open which prevents 2FWS-P24 from starting.

NOTE: BOP attempts to start a main feed pump.

2FWS-P21A will not start.

Crew may not attempt to start 2FWS 2FWS-P21A start attempt unsuccessful P21 B since it had previously tripped, if the crew does attempt a start - it will 2FWS-P21 B starts but immediately trips.

trip immediately upon 2nd motor start.

ATC depressurizes the Res to < 1950 psig hy manually opening 1 PZR PORV.

ATC closes PORV when pressure reduces to < 1950 pSlg.

possible, ATC restores normal charging by;

Opening 2CHS*MOV31 0

Opening 2CHS*MOV289

Adjusting 2CHS*FCV122 to maintain PZR level.

ATC blocks Low Steamline Pressure SI and Low Pressurizer Pressure SI signals.

BVPS - 2L8 NRC Scenario 2, Rev AG of23

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 4, 5, 6, 7 & 8: (continued) BOP depressurizes at least 1 S/G to < 440 psig to establish condensate flow by;

Verifying at least 1 MSIV is open.

Verifying the condenser is available.

Placing the condenser steam dumps in Stm ROLE PLAY: when dispatched with Press mode.

Attach A-l.lO, wait 2 minutes then call

Gradually raising steam dump rate so as to in that you are in position at MCC to NOT cause a high rate MSLI.

de-energize valves at his direction lAW

When Tavg approaches/less than 541°F, Attach A-I.] O. Report back verification defeats Tavg interlock.

of local valves as necessary.

Booth instructor NOTE: Using Attachment A-LlO, Crew coordinates with a As directed, de-energize 2FWS field operator to open and de-energize at least 1 main MOVI50AlB. feed pump discharge valve.

IMF VLV-CFW043 (0 0) 0 IMF VLV-CFW044 (0 0) 0 Critical Task: FR-H.1.A BOP begins fceding S/G's by opening the Bypass Crew establishes feedwater flow into Feed regulating valves and verifies that either at least one S/G before RCS feed and

Core Exit TC's are dropping bleed is required. OR

S/G Wide Range levels are rising.

Basis for Selection:

SAFETY SIGNIFICANCE -- Failure to BOP verifies CETC are dropping and WR S/G levels establish feedwater flow to any S/G arensmg.

results in the crew's having to rely upon the lower priority action of establishing RCS bleed and feed to minimize core uncovery. This constitutes incorrect performance that "leads to degradation of any barrier to fission product release."

BVPS - 2L8 NRC Scenario 2, Rev AG 150f23

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 4, 5, 6, 7 & 8: (continued)

SRO returns to E-O, Step 8 lAW FR-H-l, step Feedwater flow now verified.

l!.b.

List of Attachment A-O.II Discrepancies: SRO directs BOP to perfonn Attachment A-O.1!.

NOTE:

Evaluation of BOP perfonning Discrepancies: NONE Attachment A-0.11 begins on page 21.

ATC checks RCS Tcold stable at or trending to 547°F

ATC verifies no steam release is occurring.

RCS temperature < 547°F and dropping due to (Condenser steam dumps closed)

Safety Injection flow and Feedwater

ATC verifies Reheat steam is isolated.

(condensate) flow.

ATC reduces total feed flow to minimize CID.

Crew detennines cooldown is continuing and verifies SLI has previously occurred.

CIB not actuated at this time. ATC checks recirc spray pumps NONE RUNNING ATC verifies PRZR isolated

PORVs CLOSED

Spray Valves CLOSED

Safety relief valves - CLOSED (use PSMS)

PRT conditions CONSISTENT WITH EXPECTED VALVES

Power to at least one block valve AVAILABLE

Block valves AT LEAST ONE OPEN BVPS - 2L8 NRC Scenario 2, Rev AG 160f23

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 4, 5, 6, 7 & 8: (continued) ATC checks ifRCPs should be stopped.

DIP between RCS pressure and highest S/G pressure - < 205 PSID RCP's previously stopped in FR-H.l ATC/BOP checks if any S/Gs are faulted.

Pressures in all S/Gs - ANY DROPPING IN AN UNCONTROLLED MANNER OR

ANY S/G COMPLETELY DEPRESSURIZED Crew determines no S/G's are faulted.

Crew checks if S/G tubes are intact.

Check all S/G levels - NONE RISING IN AN UNCONTROLLED MANNER

Check Secondary Radiation CONSISTENT WITH PRE-EVENT VALUES Determines no S/G levels are rising in an uncontrolled manner and Secondary Radiation - is CONSISTENT WITH PRE-EVENT VALUES; Crew determines S/G Tubes ARE INTACT.

BVPS - 2L8 NRC Scenario 2, Rev AG 170f23

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 4, 5, 6, 7 & 8: (continued) Crew checks if RCS is Intact by checking CNMT conditions consistent with pre-event values.

CNMT radiation

CNMT pressure

CNMT sump level Crew determines the RCS is NOT intact based on CNMT conditions and entry conditions for E-I have been met.

SRO transitions to E-l. ATC checks if CREVS should be actuated:

Checks EITHER of the following:

Control Room Radiation Monitor 2RMC*RQ201,202 - NOT IN HIGH ALARM

CIB - HAS NOT OCCURRED Crew reports CREV's required and previously actuated.

ATC checks if RCPs should be stopped

DIP between RCS pressure and highest SIG pressure - LESS THAN 205 PSID [220 PSID ADVERSE CNMT]

DP Criteria for stopping RCPs is not met RCP's previously shutdown due per FR-H.l.

BVPS 2L8 NRC Scenario 2, Rev AG 180f23

BEAVER VALLEY POWER STATION r INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE ~

EVENTS 4, 5, 6, 7 & 8: (continued) ATC/BOP checks if any S/Gs are faulted

Pressures in all S/Gs - ANY DROPPING IN AN UNCONTROLLED MANNER OR

ANY S/G COMPLETELY DEPRESSURIZED No S/G's are faulted.

BOP Checks Intact S/G Levels

Narrow range levels GREATER THAN 12%

[31% ADVERSE CNMT]

Controls feed flow to maintain narrow range level between 12% [31 % ADVERSE CNMT] and 50%.

Crew checks if S/G tubes are intact

Check all S/G levels - NONE RISING IN AN UNCONTROLLED MANNER

Check Secondary Radiation - CONSISTENT WITH PRE-EVENT VALUES Crew determines no S/G levels are rising in an uncontrolled manner and Secondary Radiation is consistent with pre-event values, therefore all S/G tubes are intact.

BVPS - 2L8 NRC Scenario 2, Rev AG 190f23

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 4, 5, 6, 7 & 8: (continued) ATC ehecks PORV's and block valves.

Power to block valves - AV A1LABLE

PORVs-CLOSED

Block valves - AT LEAST ONE OPEN Crew checks if S1 Flow should be Reduced ATC verifies RCS Subcooling is greater than 41°F based on BOP confirms secondary heat sink available by >370 gpm of feed flow available OR NR level in at least 1 S/G> 12%.

NOTE: ATC confirms RCS pressure is stable or rising.

Due to timing, procedure progression and plant conditions (Adverse cnmt or ATC confirms Pzr level is > 17%

not adverse), it is possible that the conditions may support direct transition Crew determines that current plant conditions support to ES-J.l at this time. S1 reduction.

SRO evaluates if transition to ES-l.l, S1 Terminate scenario when the crew Termination is appropriate.

evaluates transition criteria and determines if transition to ES-l.l is appropriate.

Classify Event:

SAE, Site Area Emergency is appropriate classification per the Fission Product Matrix; Tabs 1.1.1 and 1 1 Potential Loss Heat Sink Red Path.

BVPS - 2L8 NRC Scenario 2, Rev AG 200f23

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE Attachment A-O.ll 'Verification of BOP performs Attachment A-O.ll, 'Verification of Automatic Actions' performed as time Automatic Actions' as follows:

& manpower permit Checks both EDGs running Ensure Reheat Steam Isolation Ensure reheat steam isolation

Verify 2MSS-MOVI OOA and B - CLOSED

Reset reheater controller.

Check If main steamline isolation required

CNMT pressure - > 7 PSIG

-OR

Steamline pressure - < 500 PSIG

-OR

Steamline pressure high rate of change - 100 PSIG DROP IN 50 SECONDS If steamline isolation IS required, Verifies SLI by checking all YELLOW SLI marks - LIT If steamline isolation is NOT required continues on.

NOTE: Establish domestic water system cooling to station air BOP may have already pre-emptive1y compressors; opened 2CCS-AOVl18 to provide

Opens 2CCS-AOVllS.

cooling to the Station Air compressors.

Verifies at least 1 air compressor is running.

Verifies at least 1 CCP pump is running unless a CIB has occurred.

BVPS - 2LS NRC Scenario 2, Rev AG 210f23

BEAVER VALLEY POWER STATION

[m INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE Attachment A-O.ll - (continued) Align Neutron Flux Monitoring For Shutdown

Transfer 2NME-NR45 Nuclear Recorder to operable source and intennediate range displays.

Check cm And CNMT Spray Status.

Containment pressure - HAS REMAINED LESS THAN 11 PSIG If not Actuate CIB if required by:

Manually initiate CIB - BOTH SWITCHES FOR BOTH TRAINS

Manually align equipment as required

Verify all RCPs - STOPPED

BV-1 operator verifies CREVS actuation

Service water established to RSS HX(s)

Verify Service Water System In Service

SWS Pumps - TWO RUNNING

Check SWS header pressure - > 55 psig

SWS pump Seal Water Pressure - NOT LOW Verify both CNMT hydrogen analyzers running by 2HCS*SOVlOOAl, Bl CNMT Sample amber lights LIT.

BVPS 2L8 NRC Scenario 2, Rev AG 220f23

SEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES r PLANT STATUS / PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE Attachment A-O.ll (continued) Verify ESF Equipment Status

Verify SI status by checking all RED SIS marks

-LIT

Verify CIA by checking all ORANGE CIA marks - LIT

Verify FWI by checking all GREEN FWI marks-LIT Verify Power To Both AC Emergency Busses Restore power as required Attachment A-O.ll - COMPLETE Discrepancies: Upon Completion, Report Any Discrepancies to SRO.

NONE BVPS - 2L8 NRC Scenario 2, Rev AG 230f23

A~ppen d'IX 0 . 0 utrme S cenano Form ES 01 -

Facility: BVPS Unit 2 Scenario No.:4 Op Test No.: 2LOT8 NRC Examiners: Candidates: SRO ATC BOP Initial IC 214(18): 100% power, MOL, Eq Xe, CB "D" @ 225 steps, RCS boron 1044 ppm.

Conditions:

Turnover: Maintain steady state power at 100%, 2FWE*P23A OOS, 2SAS-C21B OOS Critical Tasks: 1. E-O.O Close CNMT isolation valves

2. E-1.C Stop RCP's

3. FR-S.l.c Insert RCCA's I~

Malf. No. Event Type Event Description 1 (1) ATC, SRO 2RCS*LT459 fails low.

(TS) SRO 2 (N)ATC, SRO Restore letdown to service 3 (R) ATC Valve position limiter failure causes load rejection with Auto (1) ATC, SRO rod malfunction, ATC required to insert negative reactivity.

4 (C) BOP, SRO During load rejection, "A" Main Feed Regulating Valve controller holds valve in position, BOP required to manually control "A" S/G level.

5 (C) ATC, SRO 2RCS*PT445 fails high, 2 PORV's open, 2RCS*PCV456 fails (TS) SRO to 18% open with Block valve failed open, requiring crew to manually trip the reactor.

6 (M) ALL ATWS, crew enters FR-S.l.

7 (M)ALL 2000 gpm SBLOCA on return to E-O.

8 (C) BOP, SRO Train B CIA failure with 2CHS*MOV378 failing to auto close 9

(N)orrnal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021. Revision 9 Supplement 1 FENoe Facsimile Rev. AG

Appendix 0 Scenario Outline Form ES*D*1 2L8N4 The crew will assume the shift at 100% power with instructions to maintain steady state conditions.

The controlling PZR level channel, 2RCS*LT459 will fail low causing letdown to automatically isolate.

The crew will enter the Instrument failure procedure to address the failed channel and place the alternate channel in service. The US will determine appropriate Tech Spec action.

After the alternate channel is placed in service, the crew will restore normal letdown to service.

When letdown has been restored, the valve position limiter will fail causing a load rejection with an Auto Rod malfunction requiring the ATC to manually insert control rods.

During the load rejection, the "A" Main feed regulating valve will fail to control in auto (the valve will remain in its 100% power position), The BOP will be required to recognize the malfunction and manually control the "A" S/G level.

Once the plant has stabilized, a RCS control pressure transmitter, 2RCS*PT445 will fail high, causing 2 PORV's to open, 2RCS*PCV456 will stick at 18% open, with the block valve failing to close. The SRO will address PORV Tech Spec. RCS pressure will continue to slowly decrease requiring the SRO to direct the crew to manually trip the reactor and enter E-O.

The reactor will fail to trip from the control room, the SRO will transition to FR-S.l and the crew will dispatch an operator to locally trip the Rx. After the reactor is locally tripped, the crew will return to E-O.

1 minute after the reactor is locally tripped, a 2000 gpm LOCA will occur on the "A" loop, the crew will transition to E-l. The crew will be required to recognize that RCS I Secondary pressure DP requirements are met to require that the RCP's be manually tripped.

Train "B" CIA will fail to actuate along with 2CHS*MOV378 failing to auto close on the Train "A" CIA signal.

The scenario will be terminated after the crew transitions to ES-l.2.

Expected procedure flow path is E-O - t FR-S.l -t E-O -t 1 - t ES-l.2.

NUREG*1021, Revision 9 Supplement 1 FENOe Facsimile Rev. AG

BEAVER VALLEY POWER STATION INITIAL CONDITIONS: IC 214(18): 100% power, MOL, Eq Xe, CB "D" @ 225 steps, RCS boron 1044 ppm.

ADDITIONAL LINEUP CHANGES STICKERS MONITOR SETUP YCT - 2FWE*P23A CS A TC p()sition=l OQ~POWER display YCT - 2SAS-C21B CS -------------

EQUIPMENT STATUS DATEffIME OOS TECHNICAL SPECIFICATION(S}

2FWE*P23A OOS,l!lot()f bearing replacement. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ago 3.7.5 condition B 2SAS-C21B OOS, compressor overhaul. 3 days ago SHIFT TURNOVER INFORMATION

1. 100% power, MOL, Equilibrium Xe, shift goal is to maintain steady state conditions.

SCENARIO SUPPORT MATERIAL REQUIRED PROCEDURES NEEDED

1. MOL Reactivity placard 20M-6.4.IF, attachment 1 20M-7.4.AB AOP 2.1.3 AOP 2.35.2 20M-6.4.IF, attachment 2 E-O FR-S.l E-l Attachment A-0.6 Attachment A-O.II BVPS - 2L8 NRC Scenario 4, Rev AG 30f23

SEAVER VALLEY POWER STATION r INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE Initialize IC 214, and establish initial Reactor plant at 100%power, MOL, plant conditions. Equilibrium Xe, RCS boron =1044 PPM, ARO.

Insert the following per the Simulator Inserts all pre-loads required to support the Setup section of the HTML File for this scenario scenano:

PRELOAD COMMANDS IMF PPLOIA (0 0) I Train A RTB failed closed IMF PPLOIB (0 0) I Train B RTB failed closed IMF PPL08B (0 0) 0 Train B auto CIA actuation failure TRGSET I 'XA4I106C' Set trigger 1 on 2CHS*MOV378 switch to close IMF VLV-SEAOIS-(O 0) I 2CHS*MOV378 failed open TRG I 'DMF VLV-SEAOIS' 2CHS*MOV378 closes manually TRGSET 10 'JMLEHC6' Trigger 10 = VPL failure TRG 10 'SET JWSF478 AUTO=TRUE' 2FWS*FCV478 controller failed as is in auto IMF CNH-CFWIOC (10 4S) IS 0 0 2FWS*FCV478 controller oscillation during load rejection.

IMF PPL02A (8 120) 1 Train A trip BKR open IMF PPL02B (8 12S) 1 Train B trip BKR open IRF LOA*CRF007 (8140) I Trip A rod drive MG set IRF LOA-CRF008 (8 14S) I Trip B rod drive MG sct TRGSET 6 'RRCH4S6 > 0.0' Set trigger 6 for PORV 456 position> 0 IMF VLV-RCS034A (6 0) 1800 2RCS*PCV456 PRZR PORV fails to 18% open TRGSET 7 'MCRFNS(41) <= 214' Set trigger 7 for Rods < 214 steps IMF CRFOIA (7 0) 1 Inhibit Auto Rod insertion IMF VLV-RCSOI2 (0 0) 1 2RCS*MOV536 failed open IMF RCS02A (8 180) 2000 30 2000 gpm loop A LOCA 1 min after Rx tripped BVPS - 2L8 NRC Scenario 4, Rev AG 40f23

BEAVER VALLEY POWER STATION

[ INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE Assign shift positions Conduct a shift turnover with oncoming Simulator Frozen until after shift turnover unless operators. it needs to be run momentarily for an alignment change.

When the shift turnover is completed, Simulator running. Crew assumes control of the Unit.

place the simulator to RUN and commence the scenario.

BVPS - 2L8 NRC Scenario 4, Rev AG 50f23

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 1 &2:

Pressurizer level transmitter IMMEDIATE PLANT RESPONSE: ATC reports multiple unexpected pressurizer alarms.

2RCS*LT459 fails low. ALARMS: ATC identifies 2RCS*LT459 failed low and places A4-1B, PZR Control LvI High/Low, 2CHS*FCY122 in manual to control PZR level.

IMF XMT-RCS019A (0 0) 04 A4-1C, PZR Control LvI Dev High/Low, A4-1G,PZR Control Htr Group Trouble, SRO provides a control band and Rx trip criteria of A4-2G, PZR BIU Htr Group Auto On/Off, 14% 10w/85% high for manual PZR level control.

A2-3E, Charging Flowpath Trouble.

2RCS-LI459 indicates downscale. BOP begins referring to ARP's.

2CHS*FCY122 opens to increase flow.

Letdown isolates, 2CHS*LCY460B and 2CHS AOY200A & B close.

All PZR heaters de-energize.

SRO enters 20M-6.4.IF, attachment 1.

ATC places PZR level control channel selector to position II & III.

ATC verifies PZR level recorder selector is positioned to record the controlling level channel.

ATC verifies there is adequate makeup to the YCT.

ATC verifies PZR heaters (Control & Backup) groups have returned to normal or manually energizes heaters as necessary.

BYPS - 2L8 NRC Scenario 4, Rev AG 60f23

BEAVER VALLEY POWER STATION r INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE C EXPECTED STUDENT RESPONSE -]

EVENTS 1 & 2: (continued) SRO directs ATC to restore letdown lAW 20M ATC restores LID flow.

7.4.AB.

SRO references Technical Specifications:

3.3.1 (RTS 1nstrumentation) Condition A; immediately enter the Condition referenced in Table 3.3.1-1 function 9 (PZR level high) Condition K; trip channel in 72 hrs. or reduce power to < P-7 in 78 hrs.

SRO determines following TS are for tracking only 3.3.3 (PAM instrumentation) Table 3.3.3-1 function 11 is met ifLT460 and LT461 are operable.

3.3.4 (Remote Shutdown System) Table B.3.3.4-1 function 4.a requirement is met ifLT460 is operable.

SRO contacts Operations management and notifies I&C of level transmitter failure.

Proceed with next event at LE discretion BVPS - 2L8 NRC Scenario 4, Rev AG 70f23

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 3 &4:

Turbine Runback due to Valve Position IMMEDIATE PLANT RESPONSE: IAW Immediate Operator Action of AOP 2.1.3, ATC limiter failure, "A" main feed reg valve Rods begin stepping in, announces unexpected rod motion, verifies megawatts auto controller holds val ve in position, Megawatts decrease, decreasing and announces load rejection.

Control rods step in until 214 steps then RCS temperature and pressure rise accordingly.

quit moving in Auto. Rods stop moving at 214 steps.

As power reduces "A" S/G level increases.

IMF EHC06 (0 0) 79 0 ASIS SRO enters AOP 2.35.2 ATC checks Rods are inserting in AUTO and Tavg is dropping to Tref When rods quit moving ATC recognizes Tavg-Tref mismatch exists and places rods to manual and continues insertion.

BOP recognizes "A" S/G level is rising, takes manual control of "A" main feed reg valve and reduces flow to control level at SRO provides a control band and Rx trip criteria of 25% 10w/85% high for manual S/G level control.

SRO contacts Operations management and notifies I&C of2FWS*FCV498 controller auto control failure with satisfactory manual control.

Continue with next event at LE discretion BVPS 2L8 NRC Scenario 4, Rev AG 80f23

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUII5EiJNES-1 PLANT SillOS/PROCEDURAL GUIDANCE EXPECTE[) STUDENT RESPONSE .~

EVENTS:

IMMEDIATE PLANT RESPONSE:

2RCS*PT445 fails high, 2 PORV's ATC reports multiple unexpected pressurizer alarms.

open, 2RCS*PCV456 fails to 18% 2 PORV's initially open, 456 sticks at 18% open, ATC identifies 2RCS*PT445 has failed high and that open with Block valve failed open, Other PORV will automatically close when 2 PORV's have opened.

requiring crew to manually trip the pressure reduces to 2185 psig. ATC reports that PORV, 2RCS*PCV456 failed to reactor. RCS pressure continues to decrease. automatically close on low pressure.

IMF XMT-RCS031A (0 0) 2500 20 ATC attempts to close 2RCS*PCV456, PORV remains at dual position.

ATC attempts to close block valve, 2RCS*MOV536.

ATC reports 2RCS*MOV536 will not close.

NOTE: SRO recognizes TS applicability for an inoperable Due to dynamic nature of event, a PORV and Block valve.

followup question regarding applicable TS 3.4.11, Conditions Band C.

TS may be necessary.

Crew determines failure will not support normal plant operations.

SRO directs crew to manually trip and perform lOA's for E-O.

SRO enters E-O EVENTS 6, 7, & 8 ATWS 2000 gpm SBLOCA when Rx is tripped ATC attempts a manual reactor trip, reports trip Train "B" CIA actuation failure with failure/ A TWS condition.

failure of2CHS*MOV378 to auto close.

(all commands preloaded)

SRO enters FR-S.l SRO directs operators to perform lOA's of FR-S.l ,

implements FR-S.1 at step 1 ofE-O.

BVPS 2L8 NRC Scenario 4, Rev AG 90f23

BEAVER VALLEY POWER STATION

[ INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 6,7, & 8 (continued)

Critical Task FR-S.1.C:

Crew inserts negative reactivity into Crew performs lOA's ofFR-S.l.

the core by inserting RCCAs before BOP manually trips Turbine.

completing the immediate action steps of FR-S.1. A TC manually begins inserting rods.

Basis for Selection:

SAFETY SIGNIFICANCE -- Failure to insert negative reactivity, under the postulated plant conditions, results an unnecessary situation in which the reactor remains critical or returns to a critical condition. Performance of the critical task would make the reactor subcritical and provide sufficient shutdown margin to prevent or at least minimize the power excursion associated with any subsequent return to criticality.

Failure to insert negative reactivity constitutes "mis-operation or incorrect crew performance which leads to incorrect reactivity control (e.g., failure to initiate emergency boration or manually insert RCCAs)."

BVPS - 2L8 NRC Scenario 4, Rev AG 10 of23

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINESuul PLANT STATUS I PROCEDURAL GUIDANCE r EXPECTED STUDENT RESPONSE EVENTS 6, 7, & 8 (continued) BOP verifies AFW status.

BOP manually starts 2FWE*P23B motor-driven AFW pump.

BOP manually opens 2MSS*SOV105A-F to start Turbine-driven AFW pump, 2FWE*P22.

BOP verifies all AFW throttle valves are open.

BOP verifies AFW flow.

NOTE: Crew initiates Emergency Boration Flow by; Dependent upon crew response, SI may not be actuated at this time, if so the Verifying at least 1 charging pump is running crew will initiate Emergency Boration Checking Safety Injection is actuated and recognizes flow by: Emergency boration is not required due to SI flow.

Opening 2CHS*MOV350 BOP verifies HHSI flow Starting "A" Boric Acid pump Verifying> 30 GPM flow Adjusting 2CHS*FCV122 to establish> 40 GPM flow.

ATC verifies RCS pressure is < 2330 psig.

BVPS 2L8 NRC Scenario 4, Rev AG 11 of23

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES _uul PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 6, 7, & 8 (continued)

Crew alerts plant personnel by; ROLEPLAY:

Sounding the standby alarm.

When requested to open the reactor trip

Announcing a Unit 2 Rx trip w/o SCRAM.

breakers & trip the rod drive MG set

Dispatching an operator to locally trip the Rx.

output ACBs, insert:

TRG! 8 Following commands are preloaded, activate Trigger 2 as soon as requested, 15t Rx trip breaker will open 2 minutes after actuating Trigger 8. (TRG! 8)

IMF PPL02A (8 120)

IMF PPL02B (8 125)

IRF LOA~CRF007 (8140) 1 IRF LOA-CRF008 (8145) 1 (all commands preloaded)

ROLEPLAY:

When all breakers are open, report actions to the control room.

Crew continues in FR-S.l after dispatching an BOP verifies turbine is tripped.

operator to locally trip the Unit 2 reactor. BOP verifies 2MSS-MOVIOOA, B automatically CLOSED.

BOP depresses the RESET Pushbutton on the Reheater Controller.

ATC checks if SI is actuated.

sr is actuated, first nine steps ofE-O have not been completed.

BVPS - 2L8 NRC Scenario 4, Rev AG 120f23

BEAVER VALLEY POWER STATION

[ INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 6, 7, & 8 (continued)

NOTE: ATC checks ifRx is subcritical:

is a continuous action step, when

Power range channels < 5%.

the Rx is locally tripped the crew will

IR channels negative startup rate.

return to this step and then transition back to E-O, Step 1.

NOTE: When the Rx is locally tripped.

Event 7, 2000 gpm SBLOCA will SRO returns to E-O, step 1.

occur 1 minute after the Rx is locally tripped. (command preloaded)

ATC verifies Reactor trip:

Rx trip and bypass breakers open.

Power range indication is < 5%.

Neutron flux is dropping.

BOP verifies Turbine trip:

Throttle OR Governor valves ALL closed.

Main Generator output brks - open.

Exciter Circuit breaker - open.

BOP verifies Power to AC Emergency Busses:

Using VB-C voltmeters, verifies either AE or DF has voltage indicated.

BOP identifies that both emergency busses are energized from off-site power.

BVPS 2L8 NRC Scenario 4, Rev AG 13 of23

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 6, 7, & 8 (continued) SI automatically actuated due to low pressurizer Check SI Status:

pressure from stuck open PORV.

ATC checks that SI is actuated.

ATC manually actuates SI by turning both trains Control Switches.

ATC/BOP, Sounds Standby Alarm, announces Unit 2 reactor trip and safety injection.

BOP checks 2HVS*FN204A(B), Leak Collection Filtered Exhaust Fan - at least ONE RUNNING.

ATC verifies SI System Status:

Both 2CHS*P21A and P21B pumps running.

HHSl Flow indicated.

" Both LHSI pumps running.

BOP verifies AFW System status:

Motor-driven AFW Pumps - "B" pump RUNNING.

Turb driven AFW Pump Stm Supply Isol Valves OPEN.

AFW Throttle Vlvs - FULL OPEN.

Total AFW Flow - > 340 GPM.

BVPS - 2L8 NRC Scenario 4, Rev AG 140f23

BEAVER VALLEY POWER STATION C INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 6,7, & 8 (continued) SRO directs BOP to perfonn Attaclunent A 0.11.

NOTE: List of Attaclunent A-O.II Discrepancies:

Evaluation of BOP perfonning Attaclunent A-OJ I begins on page 21. Discrepancies:

"B" Train CIA failed to actuate along with failure of2CHS*MOV378 failing to automatically close. Manual actuation successfuL ATC checks RCS Tavg stable at or trending to 547°F:

RCS temperature < 547°F and dropping due to

ATC verifies no steam release is occurring.

Safety Injection flow. (Condenser steam dumps closed)

ATC verifies Reheat steam is isolated.

ATC reduces total feedflow to minimize C/D.

CIB not actuated at this time. ATC checks recirc spray pumps NONE RUNNING.

ATC verifies PZR isolated:

PORVs CLOSED ATC reports PORV 2RCS*PCV456 won't close and block valve 2RCS*MOV536 also has failed to close.

SRO transitions to E-l ATC checks if CREVS should be actuated.

Checks EITHER of the following:

Control Room Radiation Monitor 2RMC*RQ201,202 NOT IN HIGH ALARM.

CIB - HAS NOT OCCURRED.

Crew reports CREV's is NOT required.

BVPS 2L8 NRC Scenario 4, Rev AG 150f23

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 6, 7, & 8 (continued) ATC checks if RCPs should be stopped

DIP between RCS pressure and highest S/G Critical Task E-1.C: pressure - NOT LESS THAN 205 PSID [220 Crew trips aU RCPs when RCS to PSID ADVERSE CNMT]

highest SG DIP criteria is exceeded

DIP Criteria for stopping RCPs is met.

and SI flow verified prior to exiting procedure E-l ATC shuts down ALL RCP's after verifying HHSI flow.

Basis for Selection:

SAFETY SIGNIFICANCE -- Failure to trip the RCPs under the postulated plant conditions leads to core uncovery and to fuel cladding temperatures in excess of2200°F, which is the limit specified in the ECCS acceptance criteria. Thus, failure to perform the task represents "mis-operation or incorrect crew performance which leads to degradation of the fuel cladding barrier to fission product release" and to "violation of the facility license condition."

ATC verifies CIB is NOT actuated.

A TC/BOP checks if any S/Gs are faulted:

Pressures in all S/Gs - ANY DROPPING IN AN UNCONTROLLED MANNER OR

ANY S/G COMPLETELY DEPRESSURIZED Crew determines no S/G's are faulted.

BVPS - 2L8 NRC Scenario 4, Rev AG 160f23

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE r EXPECTED STUDENT RESPONSE EVENTS 6,7, & 8 (continued) BOP Checks Intact SIG Levels.

Narrow range levels - > 12% [31 % ADVERSE CNMT]

Controls feed flow to maintain narrow range level between 12% [31 % ADVERSE CNMT] and 50%.

Crew checks if SIG tubes are intact:

Check all SIG levels NONE RISING IN AN UNCONTROLLED MANNER.

Check Secondary Radiation - CONSISTENT WITH PRE-EVENT VALUES.

Crew determines no SIG levels are rising in an uncontrolled manner and Secondary Radiation is consistent with pre-event values, therefore all SIG tubes are intact.

ATC checks PORV's and block valves.

Power to block valves AVAILABLE.

PORVs - CLOSED, PORV 456 previously identified as not being closed with failure of block valve to close also.

Block valves - AT LEAST ONE OPEN, ALL open.

BVPS 2L8 NRC Scenario 4, Rev AG 170f23

BEAVER VALLEY POWER STATION r INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 6, 7, & 8 (continued) Crew checks if SI Flow should be Reduced.

ATC verifies RCS Subcooling is NOT> 41°F [59°F ADVERSE CNMT] based on CETC's Crew verifies subcooling is NOT greater than Attachment A-5. L Crew determines that current plant conditions do not support SI reduction and continues with next procedure step.

Check if CNMT spray should be stopped.

ATC verifies no Quench or Recirc Spray pumps are runmng.

ATC resets SI both trains.

ATC resets CIA both trains.

ATC checks if LHSI pumps should be stopped.

NOTE: ATe verifies RCS pressure is > 225 psig [250 psig Due to timing, procedure progression ADVERSE CNMT] and NOT stable or rising.

and plant conditions, it is possible that the conditions may support shutdown ATC leaves both LHSI pumps running.

of the LHSI pumps at this time.

BVPS - 2L8 NRC Scenario 4, Rev AG 180f23

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 6, 7, & 8 (continued) Check RCS and S/G Pressures.

BOP checks pressure in all S/G, NOT stable or rising.

ATC checks RCS pressure is dropping.

SRO determines S/G pressure dropping is NOT due to a faulted S/G and continues with procedure based upon preceding note.

BOP verifies AC Emergency busses are energized by offsite power.

SRO directs BOP to stop unloaded EDG's lAW 20M 36.4.AF(AG) as time permits.

BOP performs Attachment A-O.6 to verify power available to at least 1 train of Cold Leg Recirculation equipment.

BOP reports Attachment A-O.6 completed SAT with no discrepancies.

Crew evaluates Radiation monitors, determines Auxiliary building and Safeguards radiation is consistent with pre-event values.

SRO determines TSC is not activated.

SRO directs ATC to monitor nuclear instrumentation to ensure adequate Shutdown Margin.

BVPS - 2L8 NRC Scenario 4, Rev AG 190f23

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS / PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 6, 7, & 8 (continued) Start additional Plant Equipment to assist in Recovery; SRO directs a field operator to perform Attach. A-I.I Check if RCS cool down and depressurization is required.

ATC checks RCS pressure> 225 psig [250 psig ADVERSE CNMT].

SRO determines plant conditions support transition to ES-I.2.

SRO transitions to ES-I.2 Terminate scenario when the crew transitions to ES-I.2.

Classify Event:

SAE, SITE AREA EMERGENCY due to Tab 2.3, Failure of Reactor Protection.

BVPS - 2L8 NRC Scenario 4, Rev AG 200f23

BEAVER VALLEY POWER STATION

[ INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE Attachment A-O.ll 'Verification of BOP perfonns Attachment A-O.ll, 'Verification of Automatic Actions' perfonned as time Automatic Actions' as follows:

& manpower pennit.

Checks both EDGs running.

Ensure Reheat Steam Isolation. Ensure reheat steam isolation:

Verify 2MSS-MOVlOOA and B - CLOSED.

Reset reheater controller.

Check If main steamline isolation required

CNMT pressure - > 7 PSIG.

-OR

Steamline pressure - < 500 PSIG.

-OR

Steamline pressure high rate of change 100 PSIG DROP IN 50 SECONDS.

If steamline isolation IS required, Verifies SLI by checking all YELLOW SLI marks LIT.

If steamline isolation is NOT required continues on.

NOTE: Establish domestic water system cooling to station air BOP may have already pre-emptively compressors; opened 2CCS-AOV118 to provide

Opens 2CCS-AOV118.

cooling to the Station Air compressors.

Verifies at least 1 air compressor is running.

Verifies at least 1 CCP pump is running unless a CIB has occurred.

BVPS - 2L8 NRC Scenario 4, Rev AG 210f23

BEAVER VALLEY POWER STATION

[ INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE Attachment A-O.ll- (continued) Align Neutron Flux Monitoring For Shutdown

Transfer 2NME-NR45 Nuclear Recorder to operable source and intennediate range displays.

Check CIB And CNMT Spray Status:

CNMT press - HAS REMAINED < 11 PSIG.

If not Actuate CIB as required by:

Manually initiate CIB - BOTH SWITCHES FOR BOTH TRAINS.

Manually align equipment as required.

Verify all RCPs - STOPPED.

BV-1 operator verifies CREVS actuation.

Service water established to RSS HX(s).

Verify Service Water System In Service:

SWS Pumps - TWO RUNNING.

Check SWS header pressure - > 55 psig.

SWS pump Seal Water Pressure - NOT LOW.

Verify both CNMT hydrogen analyzers running by 2HCS*SOVIOOAl, B CNMT Sample amber lights LIT.

BVPS 2L8 NRC Scenario 4, Rev AG 220f23

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS / PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE Attachment A-O.ll- (continued) Verify ESF Equipment Status:

Verify SI status by checking all RED SIS marks Critical Task E-O.O -LIT.

Crew closes Cnmt isolation valves "B" Train CIA failed to actuate,

Verify CIA by checking all ORANGE CIA such that at least one valve is closed 2CHS*MOV378 failed to auto close. marks - LIT.

on each critical phase A penetration Manual actuations successful.

Verify FWI by checking all GREEN FWI before the end of the scenario. marks- LIT.

Basis for Selection:

SAFETY SIGNIFICANCE -- Failure to close at least one containment isolation valve on each critical phase-A penetration, under the postulated plant conditions and when it is possible to do so, constitutes "mis-operation or incorrect crew performance which leads to degradation of any barrier to fission product release." In this case, the containment barrier is needlessly left in a degraded condition.

Verify Power To Both AC Emergency Busses Restore power as required.

Attachment A-O.ll - COMPLETE Discrepancies: Upon Completion, Report Any Discrepancies to SRO.

"B" Train CIA failed to actuate, 2CHS*MOV378 failed to auto close.

Manual actuations successful.

BVPS - 2L8 NRC Scenario 4, Rev AG 230f23

A~ppen d'IX D , 0 utrme s cenano Form ES D 1 -

Facility: BVPS Unit 2 Scenario No.:5 Op Test No.: 2LOT8 NRC Examiners: Candidates: SRO ATC BOP Initial IC 217(10): 100% power, BOL, Eq Xe, CB "D" @ 225 steps, RCS boron 1458 ppm.

Conditions:

Turnover: Maintain steady state power at 100%, 2FWE*P23A OOS, 2SAS-C21B OOS Critical Tasks: 1. E-O.D Crew manually actuates at least one train of SIS

2. E-O.F Crew establishes the minimum required AFW flow

3. E-O.M Crew closes the upstream block MOV of the stuck open Pzr PORV

4. E-O.I Establish flow from at least 1 High head ECCS pump Event Malf. No. Event Type Event Description No.

1 (I) ATC, SRO 2RCS*PT444 drifts Jow, requires ATC to manually control RCS pressure.

2 (TS) SRO 2FWS-LT485 fails high 3 (C) BOP, SRO Voltage regulator failure causes main generator over excitation, requires BOP to tum voltage regulator off and manually lower excitation.

4 (C) ATC, SRO 25 gpm RCS leak on "A" Loop.

(TS) SRO 5 (M)ALL 500 gpm RCS leak on "A" Loop.

6 (C)ATC, SRO 2RCS-PCV455D fails open on Rx trip, requires ATC to close block valve.

7 (C) BOP, SRO AF\V malfunctions, 2FWE*P23A OOS on turnover, 2FWE*P23B auto start failure, requires BOP to manually start.

2FWE*P22 running with reduced flow << 340 gpm) 8 (C) ATC, SRO Auto SIS inhibited, requires ATC to manually actuate SIS.

9 (C) ATC, SRO 2SIS*MOV867's fail to open on SIS actuation signal, ATC required to manually open valves to initiate Safety Injection flow.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9 Supplement 1 FENoe Facsimile Rev. AG

Appendix 0 Scenario OutlinEt Form ES-O-1 2L8N5 The crew will assume the shift at 100% power with instructions to maintain steady state conditions.

The controlling PZR pressure channel, 2RCS*PT444 will drift low causing RCS pressure to rise due to the pressurizer spray valves closing and the heaters energizing. The crew will respond lAW 20M-6.4.1F, attachment 2. The A TC controls Pzr pressure by manually operating the Pzr heaters and spray valves or manual control of the Pzr pressure master controller.

When the plant has stabilized, 2FWS-LT485, S/G 2IB Channel II Narrow Range level transmitter will fail high requiring use of20M-24.4.IF attachment 1, SRO will review TS.

After the SRO completes FWS LT Tech Spec determination, the voltage regulator will fail causing overexcitation ofthe MUG. lAW the alarm response procedure, the BOP will turn the voltage regulator off and manually restore power factor and excitation by lowering the base adjust.

A 25 gpm RCS leak will then occur on the "A" loop, the crew will recognize degrading parameters and enter AOP 2.6.7, Excessive Primary Plant Leakage, to address the primary plant leakage. The SRO will address RCS leakage Tech Spec.

The leak will then become a 500 gpm SBLOCA, RCS pressure and pressurizer level will decrease requiring the SRO to direct the crew to manually trip the reactor and enter E-O.

Upon the reactor trip, PORV 455D will fail partially open, the ATC will recognize PORV failure and close the block valve.

Auxiliary feedwater malfunctions also occur on the reactor trip, the turbine driven pump will start but provide insufficient flow and the remaining available Motor driven AFW pump will fail to auto start, the BOP will manually start 2FWE*P23B.

SIS will fail to automatically actuate on low RCS pressure, the ATC will manually actuate SIS.

Upon SIS actuation, 2SIS*MOV867's will fail to automatically open, the ATC will manually open valves to initiate SIS injection flow.

The crew will transition from E-O to E-l when ch(:cking if RCS is intact based on containment parameters.

E-I will then be performed until transition to ES-l.2.

The scenario will be terminated after the crew transitions to ES-l.2 Expected procedure flow path is E-O ~ E-I ~ ES-l.2.

NUREG-1021, Revision 9 Supplement 1 FENoe Facsimile Rev. AG

BEAVER VALLEY POWER STATION INITIAL CONDITIONS: 100% Power, ARO, Equilibrium Xe, BOL, 1458 PPM Boron, IC-217 (10)

ADDITIONAL LINEUP CHANGES STICKERS VOND MARKINGS YCT - 2FWE*P23A CS ATC position 100% POWER display YCT - 2SAS-C21B CS EOUIPMENT STATUS DATE/TIME OOS TECHNICAL SPECIFICATION(S) 2FWE*P23A OOS, motor bearing replacement 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ago 3.7.5 condition B 2SAS-C21B OOS, compressor overhaul 3 days~g~

SHIFT TURNOVER INFORMATION

1. 100% power, BOL, Equilibrium Xe, shift goal is to maintain steady state 100% power conditions.

SCENARIO SUPPORT MATERIAL REQUIRED PROCEDURES NEEDED

1. BOL reactivity placard 20M-6.4.1F, Attachment 2 20M-24.4.1F, Attachment 1 AOP 2.6.7 E-O ES-O.l 1

Attachment A-0.6 Attachment A-0.l1 BVPS - 2L8 NRC Scenario 5, Rev AG 30f25

BEAVER VALLEY POWER STATION em INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE llULlall.l.."" IC 217, and establish initial Reactor plant at 100% power, BOL, Equilibrium plant conditions. Xe, RCS boron =1458 PPM, ARO.

Insert the following per the Simulator Inserts all pre-loads required to support the Setup section of the HTML File for this scenario scenano:

PRELOAD COMMANDS TRGSET 1 'JPPLP4(l)' Set trigger 1 on reactor trip IRF LOA-AFWOOI (0 0) 0.1 0 2FWE*P22 low flow (discharge valve throttled)

IMF PPL07B (0 0) 5 2FWE*P23B auto start failure IRF LOA-HIV055 (0 0) 1 2FWE*P23A breaker racked out IMF PMP-CAS004 (0 0) 1 2SAS-C21B OOS IMF VLV-RCS033A (10) 20 0 ASIS 2RCS*PCV455D fails to 20% open upon trip IMF PPL05A (0 0) 0 Train A auto SI actuation failure IMF PPL05B (0 0) 0 Train B auto SI actuation failure TRGSET 3 'JMLRCS2A == 1 .AND. Set trigger 3 on 25 gpm leak and XBlI045P l' 2CHS*LCV460A CS to open.

TRG 3 'IMF RCS02A (0 0) 500 0 asis 500 gpm SBLOCA "A" Loop when LID begins to be re-established.

IMF VLV-SIS069 (0 0) 2 2SIS*MOV867 A failed closed TRGSET 6 'XA4I081 P' Set trigger 6 on 2SIS*MOV867 A CS to open TRG 6 'DMF VLV-SIS069' 2SIS*MOV867 A opens upon manual attempt IMF VLV-SIS070 (0 0) 2 2SIS*MOV867B failed closed TRGSET 7 'XA4I076P' Set trigger 7 on 2SIS*MOV867B CS to open TRG 7 'DMF VLV-SIS070' 2SIS*MOV867B opens upon manual attempt IMF VLV-SIS071 (00) 2 2SIS*MOV867C failed closed TRGSET 8 'XA4I094P' Set trigger 8 on 2SIS*MOV867C CS to open TRG 8 'DMF VLV-SIS071, 2SIS*MOV867C opens upon manual attempt IMF VL V-SIS072 (0 0) 2 2SIS*MOV867D failed closed TRGSET 9 'XA4I090P' Set trigger 9 on 2SIS*MOV867D CS to open TRG 9 'DMF VLV-SIS072' 2SIS*MOV867D opens upon manual attempt BVPS - 2L8 NRC Scenario 5, Rev AG 40f25

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE [ EXPECTED STUDENT RESPONSE Assign shift positions SRO:

ATC:

BOP:__________________

Conduct a shift turnover with oncoming Simulator Frozen until after shift turnover unless operators. it needs to be run momentarily for an alignment change.

When the shift turnover is completed, Simulator running. Crew assumes control of the Unit.

place the simulator to RUN and commence the scenario.

BVPS 2L8 NRC Scenario 5, Rev AG 50f25

BEAVER VALLEY POWER STATION r=JNsTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENT 1:

Pressurizer Pressure control channel IMMEDIATE PLANT RESPONSE: ATC reports unexpected alarm, A4-1 E.

fails low 2RCS-PT444 drifts low IMF XMT-RCS030A (0 0) 1700240 PZR htr grps A & D, Backup grps B & E tum ATC identifies 2RCS*PT444 failing low.

on.

Pzr htr Control grp C modulates high ATC controls PZR pressure by operating Master Spray valves, 2RCS*PCV455A & 455B Pressure controller in manual or manually operating modulate closed. individual PZR heaters and spray valves.

A4-1 E, PZR Control Press Dev High/Low BOP refers to ARP.

A4-2G, PZR BIV Htr Group Auto On/Off With Pzr htrs and spray valve control in Manual, SRO establishes a control band and Rx trip criteria 2100 psig low I 2340 psig high for manual PZf pressure controL SRO enters 20M-6.4.lF, Attachment 2 SRO evaluates applicable TS; TS 3.3.4 for Remote Shutdown Instrumentation for Info Only.

SRO contacts Operations management and notifies I&C of pressure transmitter failure.

Proceed with next event at LE discretion BVPS - 2L8 NRC Scenario 5, Rev AG 60f25

BEAVER VALLEY POWER STATION r INSTRUCTIONAL GUIDELINES PLANT STATUS / PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE J EVENT 2:

IMMEDIATE PLANT RESPONSE:

21 B S/G Channel II level transmitter, 2FWS*LT485 fails high BOP reports unexpected alarm, A6-1 OD 2FWS*LT485 fails high. A6-10D, S/G 21B Level High/Low BOP verifies actual S/G parameters, steam flow/feed IMF XMT-MSS006A (0 0) 10060 flow and S/G level are stable.

ATC refers to ARP.

NOTE: No system response occurs on failure of a single channel due to BOP reports failure of2FWS*LT485.

median signal select feature.

SRO enters 20M-24.4.1F, Attachment 1 SRO refers to T.S. 3.3.1, function 14, condition place channel to trip within 72hrs. and TS 3.3.2, functions 5b and 6b, condition D, place channel to trip within 72 hrs.

Continue with next event at SRO contacts Operations management and notifies discretion I&C of level transmitter failure.

BVPS 2L8 NRC Scenario 5, Rev AG 70f25

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENT 3:

IMMEDIATE PLANT RESPONSE:

Voltage Regulator Failure BOP reports unexpected electrical alarm.

IMF GEN02 (0 0) 26 20 AS IS MUG Excitation increases Main Generator V ARS increase BOP identifies voltage regulator failure.

Main Generator Power Factor decreases (more lagging) ATC refers to ARP.

A7-4C, Generator Field Forcing BOP turns voltage regulator off and manually reduces MUG excitation using exciter base adjust to lower VARS to restore power factor.

SRO provides BOP a control band for power factor of 0.9 to 1.0 lagging.

Continue with next event at LE SRO contacts Operations management and notifies discretion maintenance of voltage regulator failure.

BVPS - 2L8 NRC Scenario 5, Rev AG 80f25

BEAVER VALLEY POWER STATION CINSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE ~

EVENT 4:

IMMEDIATE PLANT RESPONSE:

25 gpm leak on "A" RCS loop inside ATC reports indications of a RCS leak inside CNMT.

CNMT. PZR pressure begins decreasing.

IMF RCS02A (0 0) 25 0 0 A4-5A15C, DRMS Trouble / High Alann CNMT Radiation monitors; 2RMR-RQ303A, B HIGH alarms CNMT humidity increasing SRO enters AOP 2.6.7 for excessive primary ATC confinns VCT / PZR level can be maintained.

plant leakage.

Crew checks ifleakage is RCS/CVCS; Crew confinns CNMT radiation and humidity are not consistent with pre-event values.

ATC verifies RCS temperature is stable.

ATC checks 2CHS*FCV122 is in AUTO and PZR level is NOT stable.

ATC places 2CHS*FCV122 in MANUAL and adjusts to maintain a constant PZR level.

ATC checks VCT level trend.

ATC identifies VCT level is dropping at > O.7%/min and reports to SRO that leak rate is > 10 gpm.

NOTE: SRO recognizt:s TS 3.4.13 Condition A, is applicable Due to dynamic nature of event, a for unidentified leakage.

followup question regarding applicable TS may be necessary.

BVPS 2L8 NRC Scenario 5, Rev AG 90f25

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES nn] PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENT 4: (continued) ATC quantifies leak rate, checks if leakage is CYCS Isolates letdown by closing 2CHS*AOY200A, 200B and 2CHS*LCY460A and 460B.

Isolates charging by closing 2CHS*FCY122.

Adjusts 2CHS*HCY186 to obtain net input of 20 gpm.

ATC trends PZR level and verifies PZR level is dropping.

ATC verifies YCT level can be maintained> 5%

normal makeup.

ATC manually controls 2CHS*FCY122 to maintain PZR level at approximately program level.

ATC confirms leakage is not in the CYCS system and restores Charging and Letdown by; EVENT 5: Adjusting 2CHS*FCY122 for 30-50 gpm flow.

Verifying PZR level> 14%.

500 gpm SBLOCA on "A" RCS Loop Placing 2CHS*PCY145 in MAN & 50% open.

Opening 2CHS*LCY460A and B NOTE: Command is preloaded to PZR level and pressure decreases Opening 2CHS* AOY200A and/or 200B/C.

occur when 2CHS*LCY460A is Adjusting 2CHS*PCY145 to 260 psig then opened during lid restoration step of returning to AUTO.

AOP 2.6.7 When level is appro x at program, places 2CHS*FCY122 in AUTO.

ATC reports degrading primary plant conditions.

BYPS - 2L8 NRC Scenario 5, Rev AG 100f25

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 6, 7, 8, & 9: SRO directs ATC to trip the reactor.

(all preloaded to occur on the reactor SI Auto actuation failure trip) 2RCS*PCV455D fails to 20% open block valve can be closed to stop leak.

2FWE*P22 running with minimal flow (-105 gpm to each S/G) 2FWE*P23B Auto start failure (P23A - OOS) 2SIS*MOV867's fail to open on SIS Signal SRO enters E-O. ATC and BOP commence lOA's ofE-O.

ATC verifies Reactor trip.

A5-6D - LIT.

Power range indication is < 5%.

Neutron flux is dropping.

BOP verifies Turbine trip.

Throttle OR Governor valves ALL closed.

Main Generator output brks - open.

Exciter Circuit breaker open.

BOP verifies Power to AC Emergency Busses.

Using VB-C voltmeters, verifies either AE or DF has voltage indicated.

BOP identifies that both AE and DF busses are energized from offsite power.

BVPS - 2L8 NRC Scenario 5, Rev AG 11 of25

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 6,7,8, & 9: (continued) PORV failing to 20% open on the reactor trip Check SI Status.

reduce PZR pressure below Auto SI Crew checks if SI is required.

Critical Task: E-O.D setpoint

ATC checks Cnmt press> 5psig Crew manually actuates at least one

ATC checks PZR press < 1860 psig train of SIS-actuated safeguards

ATC! BOP checks Steamline press < 500 psig before transition to any ORP.

Crew detennines SI is Required based on PZR Basis for Selection: pressure being < 1860 psig.

SAFETY SIGNIFICANCE -- Failure to manually actuate SI under the ATC manually actuates SI - both trains by turning postulated conditions constitutes Control switches (BB-A).

"misoperation or incorrect crew perfonnance that leads to degraded ECCS capacity. II ATC!BOP, Sounds Standby Alann, announces reactor trip and safety injection.

BOP checks 2HVS*FN204A(B), Leak Collection Filtered Exhaust Fan - at least ONE RUNNING.

BVPS 2L8 NRC Scenario 5, Rev AG 120f25

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 6, 7, 8, & 9: (continued) ATC verifies SI System Status

Both 2CHS*P21A and P21B pumps running.

Critical Task: E-O.I

HHSI Flow indicated, Crew establishes flow from at least

Both LHSI pumps running one high head ECCS pump before transition out of E-O. ATC notes zero HHSI flow, identifies 2SIS MOV867 A, B, C & D all failed to open on the SIS Basis for Selection: actuation.

SAFETY SIGNIFICANCE -- Failure to manually start at least one high-head SRO directs ATC to align valves to establish flow.

ECCS pump under the postulated conditions constitutes "misoperation or ATC manually opens 2SIS*MOV867 A, B, C, & D incorrect crew perfonnance which leads and confinns HHSI flow exists.

to degraded ECCS capacity."

The critical task could be restated as "manually open valve(s) to establish injection flow from at least one high-head ECCS pump."

BVPS - 2L8 NRC Scenario 5, Rev AG 13 of25

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE Critical Task: E-O.F BOP verifies AFW System status Crew establishes the minimum

Motor-driven AFW Pumps - NONE running required AFW flow rate to the SGs

Turb driven AFW Pump Stm Supply Isol before transition out of E-O, unless Valves - OPEN the transition is to FR-H.l, in which

AFW Throttle Vlvs - FULL OPEN case the task must be initiated before

Total AFW Flow - < 340 gpm (~300)

RCPs are manually tripped in accordance with FR-H.1. BOP starts 2FWE*P23B and verifies total AFW flow is> 340 gpm.

Basis for Selection:

SAFETY SIGNIFICANCE -- Failure to establish the minimum required AFW flow rate, under the postulated plant conditions, results in "adverse consequence(s) or a significant degradation in the mitigative capability of the plant." In this case, the minimum required AFW flow rate can be established by performing the appropriate manual action. Therefore, failure to manually estabiish the minimum required AFW flow rate also represents a "demonstrated inability by the crew to:

Take an action or combination of actions that would prevent a challenge to plant safety Effectively direct/manipulate ESF controls Recognize a failurelincorrect auto actuation of an ESF system or component" BVPS - 2L8 NRC Scenario 5, Rev AG 140f25

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 6, 7, 8, & 9: (continued) List of Attachment A-O.II Discrepancies: SRO directs BOP to perform Attachment A-O.II.

Discrepancies:

NOTE: SIS failed to automatically actuate on low PZR Evaluation of BOP performing pressure.

Attachment A-O.II begins on page 23.

2SIS*MOV867A, B, C, & D all failed to open on SIS actuation, successfully opened manually.

2FWE*P23B failed to auto start, manual start was successful.

ATC checks RCS Tavg stable at or trending to 547°F.

RCS temperature < 547°F and dropping due to

ATC verifies no steam release is occurring.

Safety Injection flow. (Condenser steam dumps closed)

ATC verifies Reheat steam is isolated.

ATC reduces total feedflow to minimize C/D.

CIB not actuated at this time. ATC checks recire spray pumps NONE RUNNING BVPS - 2L8 NRC Scenario 5, Rev AG 150f25

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 6,7,8, & 9: (continued) ATC verifies PZR isolated

PORVs-CLOSED Critical Task: E-O.M Crew closes the upstream block ATC reports PORV 2RCS*PCV455D indicates dual MOV of the stuck open Pzr PORV position and won't close.

prior to completion of the "Prz PORV check" step of E-O. ATe closes block valve 2RCS*MOV537 to isolate stuck open PORV.

Basis for Selection:

SAFETY SIGNIFICANCE -- Failure to A TC continues verifying PZR isolated close the block MOV under the

Spray Valves - CLOSED postulated plant conditions constitutes

Safety relief valves - CLOSED (use PSMS)

"misoperation or incorrect crew

PRT conditions - CONSISTENT WITH performance which leads to degradation EXPECTED VALVES of any barrier to fission product

Power to at least one block valve release." In this case, the RCS AVAILABLE fission-product barrier can be restored

Block valves - AT LEAST ONE OPEN, 2 are to full integrity simply by closing the open.

block MOV. Therefore, failure to close the MOV also represents a "demonstrated inability by the crew to take an action or combination of actions that would prevent a challenge to plant safety."

A TC checks if Reps should be stopped

DIP between ReS pressure and highest SIG pressure NOT LESS THAN 205 PSID

Criteria for stopping is not met - Leaves Reps runmng BVPS - 2L8 NRC Scenario 5, Rev AG 16 of25

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS / PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 6, 7, 8, & 9: (continued) A TC/BOP checks if any S/Gs are faulted

Pressures in all S/Gs - ANY DROPPING IN AN UNCONTROLLED MANNER OR

ANY S/G COMPLETELY DEPRESSURIZED Crew detennines no S/G's are faulted.

Crew checks if S/G tubes are intact

Check all S/G levels - NONE RISING IN AN UNCONTROLLED MANNER

Check Secondary Radiation - CONSISTENT WITH PRE-EVENT VALUES Crew detennines no S/G levels are rising in an uncontrolled manner and Secondary Radiation is consistent with pre-event values, therefore all S/G tubes are intact.

Crew checks if RCS is intact

CNMT pressure

CNMT Sump Level

CNMT Radiation All CNMT parameters are increasing from pre-event values.

SRO detennines transition to E-1, Loss of Reactor or Secondary Coolant is appropriate.

BVPS - 2L8 NRC Scenario 5, Rev AG 170f25

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 6, 7, 8, & 9: (continued) ATC checks if CREVS should be actuated:

Checks EITHER of the following:

Control Room Radiation Monitor 2RMC*RQ201,202 - NOT IN HIGH ALARM

CIB - HAS NOT OCCURRED Crew reports CREV's is NOT required.

ATC checks if RCPs should be stopped

DIP between RCS pressure and highest SIG pressure LESS THAN 205 PSID [220 PSID ADVERSE CNMT]

DP Criteria for stopping RCPs is not met ATC leaves RCP's in service.

ATC verifies CIB not actuated and is NOT required.

ATCIBOP checks if any SIGs are faulted

Pressures in all SIGs - ANY DROPPING IN AN 'UNCONTROLLED MANNER OR

ANY SIG COMPLETELY DEPRESSURIZED Crew determines no SIG's are faulted.

BVPS - 2L8 NRC Scenario 5, Rev AG 18of25

BEAVER VALLEY POWER STATION

[ INSTRUCTIONAL GUIDELINES PLANT STATUS / PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 6, 7, 8, & 9: (continued) BOP Checks Intact SIG Levels

Narrow range levels - > 12% [31 % ADVERSE CNMT]

BOP maintains AFW flow> 340 gpm until> 12% in at least 1 SIG then controls feed flow to maintain narrow range level between 12% [31 % ADVERSE CNMT] and 50%.

Crew checks if SIG tubes are intact

Check all SIG levels NONE RISING IN AN UNCONTROLLED MANNER

Check Secondary Radiation CONSISTENT WITH PRE-EVENT VALUES Crew determines no SIG levels are rising in an uncontrolled manner and Secondary Radiation is consistent with pre-event values, therefore all SIG tubes are intact.

ATC checks PORV's and block valves.

Power to block valves - AVAILABLE

PORVs-CLOSED Block valves - AT LEAST ONE OPEN ATC reports power available to all block valves and 2 block valves are open.

PORV 2RCS*PCV455D was previously identified as being stuck open and is isolated with block valve, 2RCS*MOV537.

BVPS - 2L8 NRC Scenario 5, Rev AG 190f25

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 6, 7, 8, & 9: (continued) Crew checks if SI Flow should be Reduced ATC verifies RCS Sub cooling is greater than 41°F [59 OF ADVERSE CNMT] based on CETC's BOP confinns secondary heat sink available by > ~40 gpm of feed flow available OR NR level in at least 1 S/G> 12% [31% ADVERSE CNMT].

ATC reports RCS pressure is NOT stable or rising.

Crew detennines that current plant conditions, PZR level, does NOT support SI reduction.

Check if CNMT spray should be stopped; ATC verifies no Quench or Recirc Spray pumps are runmng.

ATC resets SI - both trains.

ATC resets CIA - both trains.

ATC checks if LHSI pumps should be stopped.

NOTE:

Due to timing, procedure progression ATC verifies RCS pressure is > 225 psig and stable or and plant conditions, it is possible that nsmg.

the conditions may not support shutdown of the LHSI pumps at this ATC stops both LHSI pumps and places CS in Auto.

time.

BVPS - 2L8 NRC Scenario 5, Rev AG 200f25

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS / PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 6,7,8, & 9: (continued) Check RCS and S/G Pressures BOP checks Pressure in all S/G NOT stable or rising.

ATC checks RCS pressure is dropping.

SRO determines S/G pressure dropping is NOT due to a faulted S/G and continues with procedure based upon preceding note.

BOP verifies AC Emergency busses are energized by offsite power.

SRO directs BOP to stop unloaded EDG's lAW 20M 36.4.AF(AG) as time permits.

BOP performs Attachment A-O.6 to verify power available to at least 1 train of Cold Leg Recirculation equipment.

BOP reports Attachment A-O.6 completed SAT with no discrepancies.

BOP evaluates Radiation monitors, determines Auxiliary building and Safeguards radiation is consistent with pre-event values.

SRO determines TSC is not activated.

SRO directs ATC to monitor nuclear instrumentation to ensure adequate Shutdown Margin.

BVPS - 2L8 NRC Scenario 5, Rev AG 21 of25

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 6, 7, 8, & 9: (continued) Start additional Plant Equipment to assist in Recovery.

SRO directs a field operator to perform Attach. A-I.1 Check ifRCS cooldown and depressurization is required; ATC checks RCS pressure> 225 psig.

SRO determines plant conditions support transition to ES-l SRO transitions to ES-1.2 Terminate scenario when the crew transitions to ES-l.2.

Classify Event:

ALERT, Tab 1.2.3, Potential Loss of RCS Barrier due to RCS Leak Rate.

BVPS - 2L8 NRC Scenario 5, Rev AG 220f25

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE Attachment A-O.ll 'Verification of BOP performs Attachment A-O.11, 'Verification of Automatic Actions' performed as time Automatic Actions' as follows:

& manpower permit Checks both EDGs running Ensure Reheat Steam Isolation Ensure reheat steam isolation

Verify 2MSS-MOVI OOA and B - CLOSED

Reset reheater controller.

Check If main steamline isolation required

CNMT pressure - > 7 PSIG

-OR

Steamline pressure - < 500 PSIG

-OR

Steamline pressure high rate of change 100 PSIG DROP IN 50 SECONDS If steamline isolation IS required, Verifies S LI by checking all YELLOW SLI marks - LIT If steamline isolation is NOT required continues on.

NOTE: Establish domestic water system cooling to station air BOP may have already pre-emptively compressors; opened 2CCS-AOVI18 to provide

Opens 2CCS-AOVl18.

cooling to the Station Air compressors.

Verifies at least 1 air compressor is running.

Verifies at least I CCP pump is running unless a CIB has occurred.

BVPS NRC Scenario 5, Rev AG 230f25

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES! PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE ~

Attachment A-O.ll- (continued) Align Neutron Flux Monitoring For Shutdown

Transfer 2NME-NR45 Nuclear Recorder to operable source and intermediate range displays.

Check CIB And CNMT Spray Status

Containment pressure - HAS REMAINED LESS THAN 11 PSIG If not Actuate CIB if required by:

Manually initiate CIB BOTH SWITCHES FOR BOTH TRAINS

Manually align equipment as required

Verify all RCPs - STOPPED o BV-1 opcrator vcrifies CREVS actuation

Service water established to RSS HX(s)

Verify Service Water System In Service

SWS Pumps TWO RUNNING

Check SWS header pressure - > 55 psig

SWS pump Seal Water Pressure NOT LOW Verify both CNMT hydrogen analyzers running by 2HCS*SOVIOOAl, Bl - CNMT Sample amber lights LIT BVPS - 2L8 NRC Scenario 5, Rev AG 240f25

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE Attachment A-O.ll- (continued) Verify ESF Equipment Status SIS failed to automatically actuate on low PZR

Verify SI status by checking all RED SIS Critical Task: E-O.I pressure. marks- LIT Crew establishes flow from at least 2SIS*MOV867A, B, C,& D all failed to open on

Verify CIA by checking all ORANGE CIA one high head ECCS pump before SIS actuation, successfully opened manually. marks - LIT transition out of E-O.

Verify FWI by checking all GREEN FWI marks LIT Critical Task: E-O.F 2FWE*P23B auto start failed, required to be Crew establishes the minimum manually started.

required AFW flow rate to the SGs before transition out of E-O, unless the transition is to FR-H.l, in which case the task must be initiated before RCPs are manually tripped in accordance with FR-H.I.

Verify Power To Both AC Emergency Busses Restore power as required Attachment A-O.II - COMPLETE Discrepancies: Upon Completion, Report Any Discrepancies to SRO.

SIS failed to automatically actuate on low PZR pressure.

2SIS*MOV867A, B, C, & D all failed to open on SIS actuation, successfully opened manually.

2FWE*P23B auto start failed, required to be manual! y started BVPS - 2L8 NRC Scenario 5, Rev AG of25

v t e Letter Sequence Other
TAC:U01850, (Open)
Initiation Acceptance... Administration Questions Answers Results Approval... Other: ML12299A226, ML12299A280, ML12314A248, ML12314A266
MONTHYEAR2012-08-03 [Table View]

ML12299A280: Difference between revisions

Latest revision as of 22:28, 1 March 2020

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