Text

Beaver Valley Unit 2 - Final Operating Exam (Sections a, B, and C) (Folder 3)
	ML12299A280
Person / Time
Site:	Beaver Valley
Issue date:	08/03/2012
From:	Rudolph W J; FirstEnergy Nuclear Operating Co
To:	David Silk; Operations Branch I
	Jackson D E
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)
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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. BV-2 Curve Book, Cycle INSTRUCTIONAL SETTING: Classroom APPROXIMATE DURATION:

35 Minutes PREPARED BY: R. J. PEER REVIEW 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 Revision Learning Objective Related Change? DYes [gJ No New Rev. # 2 D Changes Not Requiring Revision The Change Does Not Impact Learn Objectives or Material Quality. ing Existing Rev. # 1 New Change # List/Description of Change( s): Updated content for Cycle 16 data. Reason for Change Maintain JPM APPROVALS:

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

("Changes Not Requiring Changes" only) i 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 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 0 OJT/TPE 0 Other: 0 Training 0 Other: EVALUATION RESULTS Perfonner Perforrner SSN: Time Critical:

0 Yes No Allotted Time: 35 Minutes Actual Time: minutes JPM RESULTS: 0 0 SAT UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS 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 TASK STANDARD:

RECOMMENDED STARTING LOCATION:

INITIAL INITIATING

REFERENCES:

TOOLS: HANDOUT: EVALUATOR

])IRECTION SHEET Boron concentration for startup calculated within the Classroom You are to perform an Estimated Critical Position Calculation. 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 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.

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. 20M-50AP, "Performing An Estimated Critical Position Calculation", Rev. 7 BV-2 Curve Book, curves CB-I2, 21, 22, 23, 24B, and 29 None BV-2 Cycle 16 Curve 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:

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 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 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 ( "C" Denotes CRITICAL Input Critical Data Data Sheet 1) (Part A I Prior to Shutdown)

Daterrime Boron Conc. Power Burnup Xenon Samarium Control Rod Position STANDARD (Indicate "S" FOR SAT or "U" FOR I SIU I ALIDATION NOTES: When updating this JPM for the current cycle, use care to choose parameters that will require START TIME: , _______ Inputs Critical Data Part A I Prior to Shutdown.

Date/Time

= 5 days Boron Cone. 826 Power Burnup 10)000 Xenon = 100% Samarium = 100% Control Rod Position = ARO at 225 COMMENTS:

RTL#A5.640U 1I2-ADM-1301.F04 Page 7 af9 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-007 JPM REVISION:

2 JPM TITLE: Perform An Estimated Critical Position Calculation STEP ( "c" Denotes CRITICAL STEP) STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT)=> SIU 2. Input Critical Data Data Sheet 1, (Part A II Expected at Criticality)

DatelTime Bumup Xenon Samarium Control Rod Position 2.1 Inputs Critical Data Part A II Expected at Criticality.

Date/Time

= NOW Burnup = 10,000 (MWD/MTU)

Xenon = 0% (CB-23) Samarium = 137.5% (CB-22) Control Rod Position = Banks A & B @ 225 steps 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 ( "C" Denotes CRITICAL Calculate Reactivity Balance (Data Sheet 1, Part B) PartB.l Part B.2 Part B.3 Part B.4 Part B.5 Calculate Boron Concentration for Startup (Data Sheet 1, Part C) Part C.I Part c.n Part c.m Part C.IV Part C.V STANDARD (Indicate "S" FOR SAT or "U" FOR UN8AT)=> 81U 4.1 Calculates Part B, Item 5.

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

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

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

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

Reactivity Change = -3801 pcm COMMENTS:

5.1 Calculates Part C, Line 1, Item V.

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

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

Boron Change = + 509 ppm

Eff Boron Cone. at Shutdown 758.26 ppm

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 ( "C" Denotes CRITICAL STEP) Indicate "s" FOR SAT or "U" FOR UNCalculate 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 Part c.n

Differential Boron Worth = -7.08 pcm/ppm Part

Boron Change = + 537 ppm Part C.IV

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

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 TERMINATING When the Candidate completes the calculation, evaluation for this JPM is STOP TIME:

RTL#A5.640U 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 20ST-2.4A , Quadrant Power Tilt Ratio Manual Calculation", Rev. INSTRUCTIONAL SETTING: Simulator/Classroom APPROXIMATE DURATION:

15 minutes PREPARED BY: R. J. Brooks PEER REVIEW BY: APPROVED FOR USE: Training Supervisor or Designee 112-ADM-130 1.F04 Page 1 of9 Revision 1 Date Date 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 D Changes Not The Change Does Not Impact Learning Existing Rev. # 4 Requiring Revision Objectives or Material Quality. New Change # ListiDescription of Updated JPM to reflect most current JPM Revised JPM to reflect most current plant Added pictures ofNI drawers to allow for classroom performance of this Reason for Change (s): JPM Enhancement.

APPROVALS:

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

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

("Changes Not Requiring Revision" only)

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 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 ALUA TION 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: EV ALUA nON RESULTS Performer Performer SSN: Time Critical:

D I2?J Yes No Allotted Time: 15 minutes Actual Time: minutes JPM RESULTS: D D SAT UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/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 TASK STANDARD:

RECOMMENDED STARTING LOCATION:

DIRECTIONS:

INITIAL CONDITIONS:

INITIATING CUE:

REFERENCES:

TOOLS: HANDOUT: EVALUATOR DIRECTION SHEET The QPTR calculation is completed within the allowable and compared to Technical Specification limits, as specified in OST Simulator/Classroom You are to perform a Quadrant Power Tilt Ratio (QPTR) Manual Calculation.

Mode 1, The plant computers are unavailable.

The Unit Supervisor directs you to perform a QPTR calculation and report the results in accordance with "Quadrant Power Tilt Ratio Manual 20ST-2.4A , "Quadrant Power Tilt Ratio Manual Calculation", Rev. 8. Calculator, NI Cabinet Pictures (if performed in the Classroom).

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

INITIAL Mode 1, The plant computers are unavailable.

INITIATING 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.

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

Then hand this sheet to the evaluator.

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" Denote s CRI TICAL 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. Review 20ST-2.4A, "QPTR 1.1 Reviews 20ST-2.4A, "QPTR Manual Calculation" Manual Calculation" procedure.

procedure.

COMMENTS:

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

EVALUATOR NOTE: Acceptable detector current tolerance is +/-3 minor scale subdivisions of actual indication. 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: Detector current meters located on power range drawers. 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 StU 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: 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 Add the values in the records the result in the space marked "A VG". 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.)" Divide the value in the colums by the value of the "A VG" AND Record the "SUM" space by 4(3) results in the "Tilt Ratio" column. AND Record the result in the space marked "AVG". COMMENTS: Determine the Tilt for each of the detectors by dividing value in "Current(Cor.)" colums the value of the "AAND Record the results the "Tilt Ratio" 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 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 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.)" 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: Detennine the Tilt for each of the detectors by dividing value in "Current(Cor.)" colums the value of the AND Record the results the "Tilt Ratio" column EVALUATOR CUE: Inform the candidate that no uncertainty exists and a computer tilt map is NOT required. If uncertainty exists with 6.1 This step is NI A 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.

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

("c" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR 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: , D Changes Requiring I Learning Objective Related Change? New Rev. #0 i 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 Prepared by . Training Superintendent/Supervisor/Peer

("Changes Not Requiring Revision" only) I Date Date NOTE: Additions, deletions or changes to training materials must be reviewed for their possible impact to the Training , Qualification Matrix. See Incumbent Impact Review, NOBP-TR-II04.

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

TYPE: ADMINISTERED BY: D Perform B Plant Site B Annual Requal Exam D BVT D Simulate Simulator Initial Exam D NRC D D OJT/TPE D Other: D Training D Other: EV ALUA TION RESULTS Performer Performer SSN: Time D Yes Actual 25 minutes Critical:

No Time:D SAT JPM RESULTS: D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN:

Name/SSN:

EVALUATOR Evaluator Date: -Evaluator Signature:

-I RTL#A5.640U TASK STANDARD:

RECOMMENDED STARTING LOCATION:

INITIAL INITIATING

REFERENCES:

TOOLS: HANDOUT: 1I2-ADM-130 1.F04 Page 4 of6 Revision 1 EVALUATOR DIRECTION SHEET Identify the tags and sequence of placement for a tagout of2QSS-P21B Quench Spray Pump 21 B. Classroom You are to perfonn the task Prepare a SAFE Clearance Tagout. 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.

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 IA Vl 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. NOP-OP-lOOl, Clearance/Tagging Program, Rev. 18 None 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 completely

2R16 -SEAL REPLACEMENT RTL#A5.640U 1/2-ADM-130 l.F04 Page50f6 Revision 1 CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

DRead: You are to perform the task Prepare a SAFE Clearance Tagout. INITIAL 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 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 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 STANDARD (Indicate "S" FOR SAT or "U" FOR i SIU I 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 Component 2QSS*P21B-CS (OF) 2QSS*MOV101B-CS 480 VAC Cub 480 VAC Cub

""""""""

Component Description Control Switch for Quench Spray Pump 21B 2QSS*P21B (DF) Quench Pump 21B Discharge Isolation Valve Quench Pump 21B Suction Isolation Valve Supply to Quench Spray Pump 21B 2QSS*P21B Quench Pump 21B Recirc Isol Supply to Quench Pump 21B Suction Isolation Va Ive Supply to Quench Pump 21B Discharge Isolation Valve Quench Pump 21B Discharge Isolation Valve Quench Pump 21 B Suction Isolation Valve Quench Spray Pmp 21 B Discharge/Suction Drain Isol Valve Vent valve for Quench Spray Pmp 21B Position Pull-Racked OR Bus Sequence 1 2 2 3 4 4 4 6 7

.-o c UI o Q. ::)

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 NOP-OP-4107, "Radiation Work Permit (RWP)" ,Rev INSTRUCTIONAL SETTING:

APPROXIMATE DURATION:

20 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:

R. J. Brooks Prepared by Training Superintendent/Supervisor/Peer

("Changes Not Requiring Revision" only) Date Date NOTE: Additions, deletions or changes to training materials must be reviewed for their possible impact to the Training Qualification Matrix. See Incumbent Impact Review, NOBP-TR-I104.

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 ADMINISTRA TrVE 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 Classroom 0 OJT/TPE D Other: D Training 0 Other: EV ALUA TION RESULTS Performer Name: Performer SSN: Time D Yes Allotted Actual 15 minutes Critical:

k8J No Time: Time: D SAT JPM RESULTS: D UN SAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS 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 REVISION:

0 TASK STANDARD:

RECOMMENDED STARTING LOCATION:

DIRECTIONS:

INITIAL CONDITIONS:

INITIA TING CUE:

REFERENCES:

TOOLS: HANDOUT: JPM TITLE: Select RWP and Determine Maximum Allowable Stay Time EVALUATOR DIRECTION SHEET 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) Classroom 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. 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 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. 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. NOP-OP-4107, "Radiation Work Permit (RWP)" ,Rev 10 Calculator 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: 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 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 You are to SELECT the correct R WP 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 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 ( liCit Denotes CRITICAL

...... ...'!;+, *'I ... Review set ofthree (3) RWPs provided and select correct RWP and task number. Calculate the maximum stay time. STANDARD (Indicate Its" FOR SAT or "U" FOR UNSAT)::::>

SIU START TIME: EVALUATOR NOTE: This JPM is designed to performed in a classroom setting. Provide with the set of R WPs, calculator, and Survey Selects RWP 212-2001 based on Operations clearance activities and records RWP # in candidate answer box. Selects Task # 3 (clearance activities).

EV ALAUTOR NOTE: If asked, inform candidate that connecting the drain hose is a clearance activity.

Continue the COMMENTS:

2.1 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 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 ( "c" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR 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-130 I.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 APPROXIMA TE 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 EV ALUA TION 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 Critical:

0 I2SI Yes No Allotted Time: 25 Minutes Actual Time: minutes 0 SAT JPM RESULTS: 0 UN SAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS 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 TASK STANDARD:

RECOMMENDED STARTING LOCATION:

DIRECTIONS:

INITIAL CONDITIONS:

INITIATING CUE:

REFERENCES:

TOOLS: HANDOUT: Incorrect values for Inoperable rod worth, power defect, and SDM identified and corrected. (See Answer Key for specific Review completed Shutdown Margin calculation that was performed accordance with 20ST-49.1, Shutdown Margin Calculation Critical) (Updated for Cycle The Unit is in Mode 1, 100% power. All rods at 225 Annunciator

[A4-3C], TAVG DEVIATION FROM TREF is LIT". ONE control rod has been determined to be untrippable, and immovable during performance of 20ST-1.1, Rod Assembly Partial Movement Test. Chemistry has just current RCS boron concentration at 833 ppm. Current burnup 12,000 MWD/MTU. The RO has completed 20ST-49.1, Margin Calculation (Plant Critical) (Updated for Cycle 16), and requested the Shift Manager to review the completed As Shift Manager, review the completed 20ST-49.1, Shutdown Calculation (Plant Critical) (Updated for Cycle 16). Document results of your review in the appropriate section of the 20ST-49.l, Shutdown Margin Calculation (Plant Critical) for Cycle 16), Rev. 18, Unit 2 Curve Book Cycle Unit 2 Curve Book Cycle 20ST-49.1, Shutdown Margin Calculation (Plant Critical) for Cycle 16), Rev. 18 Filled out with the following errors on Sheet 0.857 for inoperable rod worth instead of 2.31 2800 PCM for power defect instead of2300 PCM 3.0096 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: Review completed Shutdown Margin calculation that was performed in accordance with 20ST-49.1, Shutdown Margin Calculation (Plant Critical) (Updated for Cycle 16). INITIAL The Unit is in Mode 1, 100% power. All rods at 225 steps. Annunciator

[A4-3C], TA VG 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 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 D When satisfied that you understand the assigned task, announce "I am now beginning the 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 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 JPM REVISION:

0 Inoperable Rod) (SRO STEP STANDARD ( "e" Denotes CRITICAL STEP) (Indicate "8" FOR SAT or "U" FOR UNSAT)=> I S/U I EVALUATOR Some judgment may be required to satisfactory performance on this JPM. Refer attached Data Sheet 1 ANSWER i EVALUATOR If the candidate hands in the OST after ONL finding the first error, provide the following Make any necessary corrections and complete SDM

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

.,.,' " START TIME: .' .< /' . *...... .*.*.*.* ....*.. ..("(;>,; . <j,. If the plant is in Mode 1, 1.1 Verifies Step VII.A.1, (Plant in Mode 1, Tavg Verify that Tavg is less than above Tref (Annunciator A4-3C OFF) from 3°F above Tref (Annunciator A4-3C, T A VO DEVIATION FROM TREF is (Otherwise N/A). (Step VILA I ) If the plant is in Mode 2, 2.1 Verifies Step VILA2, is N/A (Plant not in Mode Verify that Tavg is less gOF above Program Tavg follows: (Otherwise NI A) (Step VILA2) 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 Stu 3. Request Chemistry to 3.1 Verifies current boron concentratio n is 833 ppm from determine current RCS Boron initial conditions.

concentration in ppm. (Step VILA.3) COMMENTS: 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 COMMENTS: (Step VILA.4) 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, B) OR PCS computer point COMMENTS:

U1150, 1 MIN AVGPWR RNG NUCLEAR FLUX, on Data Sheet 1. (Step VILA.5) 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) ( "e" Denotes CRITICAL If the number of immovable or untrippable control Rods is greater than 1, Use Attachment 1 to determine the required boron concentration with greater than one struck rod and Record below. (Otherwise N/A) (Step VIlA.7) Determine control bank reactivity worth per the following:

Using the ARO Total Bank Worth table on Data Sheet 1, Enter the total bank worth for the current core burnup range, in the space provided on Data Sheet 1. (Step VII.Rl.a) Using Curve Book Figures CB-24A, 24B or CB-24C, Determine integral rod worth for the current bank position AND Enter this value on 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)

STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT)=> Stu Verifies Step VILA.7 is N/A. COMMENTS: Verifies ARO Total Bank Worth (from the Data 1 table) to be 7.571 %8k1k and recorded on Data Sheet I (Block R1.a). COMMENTS: Verifies integral rod worth to be ZERO and recorded on Data Sheet 1 (Blocks Rl.b.1) and Rl.b). COMMENTS:

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 I STEP ( "e" Denotes CRITICAL STEP) Subtract the integral rod worth from the Total Bank Worth AND Enter the result on Data Sheet 1. (Step VII.B.I.c)

Inoperable Rod) (SRO ONLY) I STANDARD (Indicate "S" FOR SAT or "U" FOR SIU Verlfies TBW-IRW is 7.571 %L\k1k and recorded Data Sheet 1 (Block COMMENTS: 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: 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: J Candidate may need cued to make any necessary corrections and complete the SDM calculation.

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 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 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 follows: 14.1 Record RCS Boron Concentration of833 ppm on Data Sheet 1 (Block B.4.a). Record RCS Boron Concentration results from Chemistry on Data Sheet 1. (Step VII.BA.a) 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. I 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 ( "e" Denotes CRITICAL Detennine Corrected Boron Concentration by multiplying the RCS Boron Concentration and the B-1 0 Correction Factor AND Record on Data Sheet 1. (Step VII.B.4.c) Using Curve Book Figure 21, Determine the ABSOLUTE VALUE ofthe Power Defect for the current power level and the Corrected Boron Concentration AND Enter this value on Data Sheet 1. (Step VII.B.4.d) Divide value from curve (in pcm) by 1000 to convert to AND Record on Data Sheet 1. (Step VII.B.4.e)

Inoperable Rod) (SRO ONLY) STANDARD (Indicate "S" FOR SAT or "U" FOR UN SAT):::> I SIU I Detennines Corrected Boron Concentration to be 750 ppm and records on Data Sheet 1 (Block B.4.c). COMMENTS:

17.1C Determines ABSOI...UTE VALUE of the Power Defect to be 2300 pem NOT 2800 pcm and records on Data Sheet 1 (Block B.4.d). COMMENTS:

18.1 C Converts ABSOLUTE VALUE of the Power Defect of 2300 pcm to 2.30 and records on Data Sheet 1 (Block 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: ("e" Denotes CRITICAL Add 0.150 %Llklk for operating temperature band margin to the Power Defect recorded in Step VII.B.4.e AND Record on Data Sheet 1. (Step VILBA.t) Determine SHUTDOWN MARGIN by subtracting Power Defect (Step VILBA.t) from the value determined in Step VII.B.3 AND Record on Data Sheet 1. (Step VII.B.5) Inoperable Rod) (SRO ONLY) STANDARD Indicate "s" FOR SAT or "U" FOR UN SAT)=> I SIU I 19.1 C Determines Power Defect plus operating temperature band margin to be 2.45 % Llklk NOT 2.95 %

and records on Data Sheet 1 (Block B.4.t). COMMENTS:

20.1 Dett.'l111ines SDM to be 2.054 %Llklk NOT 3.009 % Llklk and records on Data Sheet 1 (Block B.4.f) AND space provided on candidate direction sheet. COMMENTS:

EVALUATOR CUE: That Completes this 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. #

DYes I:8J D Changes Not The Change Does Not Impact Learning Existing Rev. # N/Requiring Revision Objectives or Material 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 must be reviewed for possible impact to the Qualification Matrix. Incumbent Impact 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 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 Classroom 0 OJT/TPE 0 Other: 0 Training 0 Other: EVALUATION RESULTS Performer Performer SSN: Time Critical:

0 [gI Yes No Allotted Time: 20 minutes Actual Time: minutes JPM RESULTS: D D SAT UN SAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS 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 TASK STANDARD:

RECOMMENDED STARTING LOCATION:

DIRECTIONS:

INITIAL CONDITIONS:

INITIATING CUE:

REFERENCES:

TOOLS: HANDOUT: EVALUATOR DIRECTION 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.

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

Mode 1 100% power. The plant computers are unavailable.

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

20ST-2.4A , "Quadrant Power Tilt Ratio Manual Calculation", Rev. 8. Calculator 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. NI Cabinet Pictures. Attached "Quadrant Power Tilt Ratio Normalization Factors" 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: Review/approve a completed 20ST-2.4A, "Quadrant Power Tilt Ratio Manual Calculation".

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

INITIATING 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 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 UPPER 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: _________ EV ALVA TOR NOTE: This JPM is designed to use an accompanying Quadrant Power Tilt Ratio Nonnalization Factors sheet and NI cabinet pictures.

EV ALVA TOR CUE: Provide an erroneously completed copy of 20ST-2.4A, Quadrant Power Tilt Ratio Normalization Factors sheet and NI pictures. Review 20ST-2.4A, "QPTR 1.1 Reviews 20ST-2.4A, "QPTR Manual Calculation" Manual Calculation" procedure.

procedure.

COMMENTS:

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

2.C Identifies reading error for N42 upper detector.

2.1 Identifies N42 upper detector current is 259 and not the recorded current of249. 2.2C Records in appropriate block of Data Sheet 1. COMMENTS:

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 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. Records problems encountered on the cover sheet and/or the OST problem sheet. Records on the cover sheet and/or the OST problem 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 Page 1 Revision 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. Technical Specifications Beaver Valley Power Station Units 1 & INSTRUCTIONAL SETTING: Classroom APPROXIMATE DURATION:

15 minutes PREPARED PEER REVIEW APPROVED FOR Training Supervisor or Designee 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 Updated to reflect Revision 15 Reason for Change (s): APPROVALS:

R J BwuK:s Prepared by Training Superintendent/Supervisor/Peer

("Changes Not Requiring Revision" only) Date Date NOTE: Additions, deletions or changes to training materials must be reviewed for their possible impact to the Training Qualification Matrix. See Incumbent Impact Review, NOBP-TR-II04.

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 Critical:

0 Yes No Allotted Time: 15 minutes Actual Time: minutes JPM RESULTS: 0 0 SAT UN SAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS 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 REVISION:

0 TASK STANDARD:

RECOMMENDED STARTING LOCATION:

DIRECTIONS:

INITIAL CONDITIONS:

INITIATING CUE:

REFERENCES:

TOOLS: HANDOUT: JPM TITLE: Perform a Risk Assessment [2FWE*P23A Maintenance] (SRO Only) EVALUATOR DIRECTION SHEET Determines Risk Level is ORANGE and the Director of Site Operations (or designee) is the required approver for this condition.

Classroom You are to determine the risk level for given plant conditions and required approver for this level of risk. 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 . 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 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) NOP-OP-I007, "Risk Management", Rev. 15 Technical Specifications Beaver Valley Power Station Units I & 2 None 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: 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 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 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 D When satisfied that you understand the assigned task, announce "I am now beginning the 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 Then hand this sheet to the evaluator.

112-ADM-130 1.F04 Page6of7 Revision 1 OPERA TIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-041 JPM REVISION:

0 ( "c" Denotes CRITICAL Refers to NOP-OP-1007, "Risk Management" provided. Refers to Attachment 3, Risk Assessment Worksheet, to determine risk. JPM TITLE: Perforrn a Risk Assessment

[2FWE*P23A Maintenance] (SRO Only) STANDARD (Indicate "s" FOR SAT or "U" FOR UNSAT)=> I SIU I START TIME: ________ EVALUATOR CUE: Provide a copy 1007, "Risk Management".

1.1 Ref;;:rs to NOP-OP-I007.

COMMENTS:

EVALUATOR NOTE: The candidate may want refer to TS 3.7.5 as part of this JPM step. Technical Specifications Beaver Valley Power Units 1 & 2 is available for reference.

TS Condition B applies since 2FWE*P23A is Condition C requires a plant shutdown cannot be returned to service within 72 2.1 C Deternlines that this activity is ORANGE risk level. This is based on Attachment 3, Section E.5 answer is 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. Records approver in the candidate answer box of the candidate direction sheet. COMMENTS:

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 ( "e" Denotes CRITICAL STEP) (Indicate "s" FOR SAT or "U" FOR 3.C Refers to Attachment 2, 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. 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.

o Yes ONo o Changes Not The Change Does Not Impact Learning i Existing Rev. # N/ Requiring Revision Objectives or Material I New Change ListiDescription of 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:: Training Superintendent/Supervisor/Peer Date NOBP-TR-l104. ("Changes Not Requiring Revision" only) I i 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 ALUA TION 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 Critical:

D Yes I:8J No Allotted Time: 20 Minutes Actual Time: minutes JPM RESULTS: D D SAT UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS 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 REVISION:

0 TASK STANDARD:

RECOMMENDED STARTING LOCATION:

DIRECTIONS:

INITIAL CONDITIONS:

INITIA TING CUE:

REFERENCES:

TOOLS: JPM TITLE: Detemline compensatory actions for 2GWS-P21 and 2GWS-OA-I00A being OOS. (SRO ONLY) EVALUATOR DIRECTION SHEET 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. Classroom Refer to Initiating Cue Below. 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.

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). LRM 3.3.12, Re:v. TS 5.5.8, Amend Y2 ODCM Section 3.0.3, Rev. OM Fig. 19-3 Rev.

RTL#A5.640U 1 12-ADM-130 l.F04 Page 5 of7 Revision 1 OPERA nONS JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

DRead: TASK: Refer to Initiating Cue Below. INITIAL 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 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 D When satisfied that you understand the assigned task, announce "I am now beginning the 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 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) ( "c" Denotes CRITICAL Determines the impact of 2GWS-P21 being OOS. Determines Y2 aDeM compensatory actions for Waste Gas Storage Tank Radiation Monitor RQI04) being out of service. STANDARD (Indicate "S" FOR SAT or "u" FOR UNSAT)=> I S/U I START TIME: ._______ EVALUATOR CUE: Provide the Candidate with Candidate Direction Sheet and a current copy of Fig. 19-3, LRM, AND yz ODeM Section EVALUATOR NOTE: These steps may be performed in any order. EVALUATOR NOTE: The next step may not be necessary.

The may already be familiar enough with the system know the impact of 2GWS-P21 being Ref(:rs to OM Fig. 19-3 and determines that Waste Gas Storage Tank Radiation Monitor (2GWS-RQI04) is out of service as a result of2GWS-P21 being OOS. Refers to Y2 ODeM Section 3.0.3, Att. 0 item 4.11.25.1 on page 66. Determines that it will be required to verity, least 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 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 PREP ARED BY: R. J. PEER REVIEW APPROVED FOR Training Supervisor or Designee 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. #

DYes D Changes Not The Change Does Not Impact Learning Existing Rev. Requiring Revision Objectives or Material New Change List/Description of Original Issue Reason for Change (s): APPROVALS:

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

TYPE: ADMINISTERED BY: bd Perform B Plant Site 0 Annual Requal Exam B BVT o Simulator 0 Initial Exam NRC Classroom 0 OJT/TPE 0 Other: D Training D Other: EV ALUA TION RESULTS Performer Performer SSN: Time Yes Actual 15 minutes Critical: No Time: D SAT JPM RESULTS: D UNSAT (Comments required for VNSAT evaluation)

Comments:

OBSERVERS Name/SSN:

Name/SSN:

Narne/SSN:

EVALUATOR Evaluator Date: Evaluator Signature:

RTL#A5.640U TASK STANDARD:

RECOMMENDED STARTING LOCATION:

DIRECTIONS:

INITIAL CONDITIONS:

INITIATING CUE:

REFERENCES:

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

Simulator You are to perform the task Classify An Emergency Event and complete the initial notification form. The simulator scenario just completed.(2LOT8 NRC Exam) 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 EPP/I-la, Recognition and Classification of Emergency Conditions, Rev. 15 None 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: You are to perform the task Classify An Emergency Event and complete the initial notification form. INITIAL The simulator scenario just completed.(2LOT8 NRC Exam) INITIATING 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 Then hand this sheet to the evaluator.

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

JPM REVISION: I.C Classify the event in accordance with the Emergency Plan. STANDARD (Indicate "S" FOR SAT or "U" FOR UN SAT)=>

____________

__ 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. 1.1 C Candidate correctly classifies the event. 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:

112-ADM-130 1.F04 Page 7 of8 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-046 JPM REVISION:

0 ( "C" Denotes CRITICAL Completes the initial notification form. JPM TITLE: Classify an Emergency Event (Scenario Specific)

STANDARD (Indicate "8" FOR SAT or "U" FOR UNSAT)=> SIU Places the following information on the space provided on the 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 Refer to Answer Key for initial form critical 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 I RTL#A5.640U 1/2-ADM-130 l.F04 Page 2 of8 Revision 1 TRAINING MATERIAL CHANGE Affected Training Materials:

2CR-072 Type of Change: C8J Major Learning Objective Related Change? New Rev. #4 DYes LJ Minor The Change Does Not Impact Learning Objectives or Material Quality. List/Description of Change(s):

Existing Rev. # 3 New Change # 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 EV ALUA TION 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 Critical:

D IZI Yes No Allotted Time: 15 minutes Actual Time: minutes JPM RESULTS: D D SAT UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN:

Name/SSN:

EVALUATOR Evaluator (Print): Date: Evaluator Signature:

-

RTL#A5.640U JPM NUMBER: 2CR-072 JPM REVISION:

4 TASK STANDARD:

RECOMMENDED STARTING LOCATION:

DIRECTIONS:

INITIAL CONDITIONS:

INITIATING CUE:

REFERENCES:

TOOLS: HANDOUT: 1i2-ADM-130 1.F04 Page 4 of8 Revision 1 JPM TITLE: Shift From Main Feedwater Reg Valves to Bypasses EVALUATOR DIRECTION SHEET The "A" Bypass Feed Regulating Valve is in automatic and controlling steam generator level. SIMULATOR You are to Transfer from Main Feed Regulating Valve to Bypass Feed Regulating Valve for the "A" S/G. 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. 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%. 20M-52.4.R.l.F, Revision 23 None 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:

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 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 ( "e" Denotes CRITICAL Review 20M-52.4.R.l.F and attachment

10. Place controller in MANUAL AND Slowly Open the 21A Bypass FCV. As the 21A Bypass FCV is being opened, close FCV478] 21A Main Feedwater Reg Valve, in MANUAL OR AUTO to maintain 21 A S/G level within 39% to 49% STANDARD (Indicate "S" FOR SAT or "U" FOR UN SAT)=> SIU START TIME: _______ EVALUATOR NOTE: Initialize Put Steam Generator Wide Range Levels trend up on BOP's PCS screen. Select then select "SG Wide Range Open MFRV isolation valve 1.1 Reviews 20M-52.4.R.l.F and Attach. 10. COMMENTS:

[ EVALUATOR CUE: Infonn candidate that it is desired to close 2FWS-FCV478 in the MANUAL mode of control. Locates Steam Flow, Feed Flow and Steam Generator level indicators 2.2.C Intermittently opens the Bypass Control Valve [2FVVS-FCV479]

by depressing the up button. 2.3.C Depresses the MANUAL PB then closes the Main Feed Reg Valve [2FWS-FCV478]

by intermittently depressing lower PH. Maintains Feed Flow approximately equal to Steam Flow. Verifies the Main Feed Reg Valve [2FWS-FCV478]

Green light -LIT, Red light-NOT LIT. COMMENTS:

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 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 Verify S/G 21A Main Feedwater past Reg Valve controller in 3.3 Closes 2FWS-MOVI54A by placing CS to close, Observe Feedwater flow, steam verifies Green light -LIT and Red light -NOT flow and S/G level for of leakage past the 21 A Main Feed Reg Closes [2FWS-MOVI54A], S/G Main Feedwater Isol 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 EVALUATOR CUE: Inform candidate that it stable, restore the valve is desired to operate in AUTO mode. If controller to MANUAL candidate feels that control is not stable in AND maintain S/G NR level AUTO they may continue to operate in between 39% and Monitors AUTO operation of the valve to ensure it controls level between 3Q31o and 49%. COMMENTS:

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 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: EVALUATOR CUE: That completes this JPM. 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 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:

Pual T

....... "r..... Prepared by Training Superintendent/Supervisor/Peer

("Changes Not Requiring Revision" only) Date Date NOTE: Additions, deletions or changes to training materials must be reviewed for their possible impact to the Training Qualification Matrix. See Incumbent Impact Review, NOBP-TR-II04.

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 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 ALUA TION METHOD: LOCATION:

TYPE: ADMINISTERED BY: Perfonn Plant Site B Annual Requal Exam B BVT D Simulate Simulator Initial Exam NRC D D OJT/TPE D Other: D Training D Other: EV ALUA TION RESULTS Perfonner Name: Perfonner SSN: Time D Yes Allotted Actual 20 minutes Critical:

r8J No Time: 0 SAT JPM RESULTS: 0 UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN:

Name/SSN:

EVALUATOR Evaluator (Print): Date: Evaluator Signature:

RTL#A5.640U TASK STANDARD:

RECOMMENDED STARTING LOCATION:

DIRECTIONS:

INITIAL CONDITIONS:

INITIATING CUE:

REFERENCES:

TOOLS: HANDOUT: 112-ADM-130 1.F04 Page 4 of 10 Revision 1 EVALUATOR DIRECTION SHEET Contiguous area ventilation aligned through the filtered flowpath.

Simulator You are to perform the task, Respond to a Radiation Monitor Alarm Annunciator A4-5C "Radiation Monitor Level High" has just alarmed. Your supervisor directs you to respond to the alarm using appropriate Alarm Response 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 None 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: You are to perfoffi1 the task, Respond to a Radiation Monitor Alaffi1 INITIAL Annunciator A4-5C "Radiation Monitor Level High" has just alaffi1ed.

INITIATING 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 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 ( "c" Denotes CRITICAL STEP) STANDARD (Indicate "S" FOR SAT or "U" FOR UN SAT)=> 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 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. 43.4.AAC) 1.1 Locates copy of procedure 20M-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 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 the 4-digit numerical code number of the alanning monitor and select. 3.1 Types in 2042 and depresses the SEL pushbutton.

COMMENTS:

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 NI A than 1000 times background.

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

COMMENTS: 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 7.2 Refers to local alann response procedure 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 9.2 Det,ermines that the actual value is higher than HIGH alarm COMMENTS:

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

EVALUATOR Role-play the SM and acknowledge the DIRECT the candidate to perform steps I.e. and The SM will perform the other remaining steps ofprocedure (l.d., l.g., l.h., & 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 "FIL T" 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 "FIL T" 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 FIL T 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: Verify [2HVS*MOD202A]

and [2HVS*MOD202B]

are OPEN. Verifies [2HVS*MOD202A]

and [2HYS*MOD202B]

green lights LIT and red lights -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 HFIL T"). COMMENTS:

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

EVALUATOR ] 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.

changes to training must be reviewed for Prepared by possible impact to the Qualification Matrix.

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 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 ALUA TION 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 Performer SSN: Time Yes Actual 16 minutes Critical: No Time: D SAT JPM RESULTS: D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS 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 TASK STANDARD:

RECOMMENDED STARTING LOCATION:

DIRECTIONS:

INITIAL CONDITIONS:

INITIATING CUE:

REFERENCES:

TOOLS: HANDOUTS:

EVALUATOR DIRECTION SHEET The reactor is tripped in response to inappropriate continuous control rod motion. Simulator You are to "Raise Reactor Power To 10-8 Amps" 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". 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 IV.C.9, and stabilize power at 10-8 amps on IR indication.

20M-50.4.D2 , Reactor Startup From Mode 3 to Mode 2, Rev. Data Sheet 3 20M-50A.F Rev 7 Filled out for 11M 20M-53CA.2.1.3, RCCA Control Bank Inappropriate Movement, Rev. 20M-50A.D2 , Reactor Startup From Mode 3 to Mode 2, Rev Placekept up to step Filled out Data Sheet 3 (11M Plot) of20M-50A.F, Rev 7 (may cue 20M-53CA.2.1.3, RCCA Control Bank Inappropriate Movement, Rev. 7 (not provided 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:

You are to "Raise Reactor Power To 10-8 Amps" INITIAL 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 1 00 steps on Control Bank "D". INITIATING 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. At this time, ask the evaluator any questions you have on this JPM. 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 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". Then hand this sheet to the evaluator.

RTL#A5.640U 1 12-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: 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 ( "e" Denotes CRITICAL WHEN the Inverse Count Rate Ratio is less than 0.25, Reduce rod withdrawal intervals to 25 step increments. (Step IV.C.9.b) When Status Light Annunciator A12-3B "P6 Permissive" is on (lE-lO amps), Block the SR high flux trip by performing the following:

Record Source Range Neutron Level indicators:

[NI-NI-31A]

CPS [NI-NI-32A]

CPS Step IV.C.lO.a) (Indicate "S" FOR SAT or "V" FOR UNSAT)=> I SIV Candidate initiates rod withdrawal at less than 25 step increments.

EVALUATOR CUE: As the Unit Supervisor, inform the candidate that the ICCR is less than 0.25. Withdraw control rods at 5 step to take the reactor COMMENTS:

3.1. Records SR counts for N31 and N32. COMMENTS:

EVALUATOR CUE: The Reactor Engineer has recorded the Source Range Counts.

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 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) 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 Source Range 'B' Block the BLOCK position (Step IV.C.lO.c) 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 1 12-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 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 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:

FA UL T 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 with no rod motion, on the intermediate range EVALUATOR CUE: If asked, inform Candidate to withdraw rods at not more than 5 step increments to obtain a stable startup rate. instrumentation once the prompt jump has receded. COMMENTS: (Step IV.C.12) 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: 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 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 PREPARED BY: P.T. Eisenmann PEER REVIEW BY: APPROVED FOR USE: Training Supervisor or Designee 1/2-ADM-130 l.F04 Page 1 of9 Revision 1 Date Date 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 Updated JPM to current procedure and JPM Reason for Change (s): EnhanceJPM APPROVALS:

P.T. Eisenmann Prepared by Training Superintendent/Supervisor/Peer

("Changes Not Requiring Revision" only) Date Date NOTE: Additions, deletions or changes to training materials must be reviewed for their possible impact to the Training Qualification Matrix. See Incumbent Impact Review, NOBP-TR-II04.

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 009 EAl.13 4,4/4,4 TASK ID: 0111-011-01-013 JPM REQUALIFICATION INITIAL EXAM D TRAINING FAULTED JPM D ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION:

TYPE: ADMINISTERED BY: Perform Plant Site D Annual Requal Exam D BVT D Simulate Simulator D Initial Exam D NRC D D OJT/TPE D Other: D Training D Other: EVALUATION RESULTS Performer Performer SSN: Time DYes Actual 15 minutes Critical: No Time: D SAT JPM RESULTS: 0 UN SAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN:

Name/SSN:

EVALUATOR Evaluator Date: . Evaluator Signature:

RTL#A5.640U TASK STANDARD:

RECOMMENDED STARTING LOCATION:

DIRECTIONS:

INITIAL CONDITIONS:

INITIATING CUE:

REFERENCES:

TOOLS: HANDOUT: 1/2-ADM-130 l.F04 Page 4 of 10 Revision 1 EVALUATOR DIRECTION SHEET SI Accumulators

'A' and 'B' are isolated.

SI Accumulator

'c' Simulator You are to Isolate the SI Accumulators During a LOCA. A LOCA has occurred.

The crew is performing ES-1.2, Post Cooldown and The Unit Supervisor directs you to isolate the SI accumulators accordance with ES-I.2, Post LOCA Cooldown And beginning at 20M-53.A.1.ES-1.2, Post LOCA Cooldown and Issue 1 C, Rev. 20M-ll.4.G, Venting A Safety Injection Accumulator, Rev. 20M-53A.1.A-S.1, OF Plus Subcooling Based On Core Exit TCs, rev Three Shorting 20M-53.A.1.ES-1.2, Post LOCA Cooldown and Issue IC, Rev. 10, place kept up to step 20M-11.4.G, Venting A Safety Injection Accumulator, Rev. 20M-53A.1.A-S.1, OF Plus Sub cooling Based On Core Exit TCs rev.

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

THIS SHEET TO BE GIVEN TO CANDIDATE

DRead:

You are to Isolate the SI Accumulators During a LOCA. INITIAL A LOCA has occurred.

The crew is performing ES* 1.2, Post LOCA Cool down and Depressurization.

INITIATING 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 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 REVISION:

2 JPM TITLE: Isolate SI Accumulators During a LOCA ( "c" Denotes CRITICAL , "" Review procedure. RCS subcooling based on core exit TCs -GREATER THAN SUBCOOLING LISTED ON ATTACHMENT A-S.l. STANDARI) (Indicate "S" FOR SAT or "U" FOR I S/U I SIMULATOR SETUP: Initialize simulator to any Mode 1 Insert SBLOCA @ 500 Progress through EOP set up until Step 27 of PZR Leve:1 needs to be > 17% and RCS Subcooling to be > 41F (non adverse Insert VLV-SIS068 (override SIS*MOV86SC in the NOTE: This JPM takes significant setup work requires careful attention to C/D rate, AFW flowrate other dynamic EVALUATOR NOTE: :J RCS pressure may drop low enough to begin accumulators.

Ensure Shorting Bars are START TIME: Reviews 20M-S3A.l.ES-l.2, Post LOCA Cool down and Depressurization.

COMMENTS: Verifies RCS subcooling on VB-B (2RCS*YIOOI or 2RCS*YROOl) or the PCS. Compares existing value to Attachment A-S.ll. 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 PRZR level-GREATER THAN 3.1 Verifies [2RCS-LI459A, 460, and 461] are greater 38%. than 38%. COMMENTS: Power to [2SIS*MOV865A, B, 4.1 Verifies [2SIS*MOV865A, B, q red lights -LIT and q -AVAILABLE.

green lights -NOT LIT. COMMENTS:

EVALUATOR Shorting Bars will be needed in the next step. requested, Role-play the Shift Manager and supply shorting 5.C Insert Shorting Bars and closes 5.1 Contacts Shift manager and requests shorting bars. [2SIS*MOV865A, B, 5.2C Inserts into [2SIS*MOV865A] 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 Stu I I FAULT STATEMENT:

i Alternate path begins here: [2SIS*MOV865C]

will NOT CLOSE in the following step. EVALUATOR Accumulator isolations may be done in any Close [2SIS*MOV865A, B, 6.1C Places [2SIS*MOV865A, B, C] CS to Verlfies Green lights LIT and Red lights -NOT LIT for [2SIS*MOV865A, B]. Verifies Red light LIT and Green light -NOT LIT for [2SIS*MOV865C].

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

Refer to 11.4.0, "Venting A Safety EVALUATOR Injection Accumulator".

If necessary, Role-play the Unit Supervisor and 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 ( "c" Denotes CRlTICAL If containment is not under vacuum, close [2SIS*367 (369) (399)] Accumulator

[2SIS*TK21A (B), (C)] Level Isolation to prevent educting liquid into the vent line during venting. Check closed, 1 (101-2), SI ACC Nitrogen Makeup Outside (Inside) Cnmt Isol Vlv. 10.C Open [2GNS*SOV853A(D)

(853B (E>> (853C (F>>] 21A (B) (C) SI Accumulator Nitrogen Makeup Vlv. l1.C Open [2GNS*SOV854A (854B)] SI Accumulator Vent Vlv until the Accumulator is lowered to the desired value, then close [2GNS*SOV854A (854B)]. STANDARD (Indicate "s" FOR SAT or "U" FOR UNSAT)=> SIU No action required.

COMMENTS: Verifies [2GNS*AOVI01-1 and 101-2J Green lights LIT and Red lights -NOT LIT COMMENTS:

10.1 Places [2GNS*SOV853C OR F] CS to OPEN. Verifies Red light LIT and Green light -NOT LIT. COMMENTS: Places [2GNS*SOV854A OR B] CS to OPEN. Verifies Red light LIT and Green light NOT LIT. Verifies [2SIS-PI929

& 931] indicate accumulator pressure is lowering.

EVALUATOR NOTE: Candidate may refer to PCS to monitor COMMENTS:

RTL#A5.640U 112-ADM-130 I.F04 Page 10 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR -654 JPM REVISION:

2 ( "c" Denotes CRITICAL JPM TITLE: Isolate SI Accumulators During a LOCA STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAEVALUATOR CUE: When accumulator pressure begins to lower, That completes this STOP TIME:

RTL#A5.640U Page 1 of Revision 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 20M-7.4.N, Blender Manual Makeup Operations, Rev. INSTRUCTIONAL SETTING:

APPROXIMATE DURATION:

15 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 Updated for current revision of the Reason for Change JPM 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/SupervisorlPeer Date Incumbent Impact Review, ("Changes Not Requiring Revision" only) 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 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: Perform 0 Plant Site B Annual Requal Exam B BVT o

[2J Simulator Initial Exam NRC Classroom 0 OJT/TPE 0 Other: 0 Training 0 Other: EVALUATION RESULTS Performer Name: PerfoTIner SSN: Time Critical:

P [2J Yes No Allotted Time: 15 Minutes Actual Time: minutes JPM RESULTS: D D SAT UN SAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN:

Name/SSN:

EVALUATOR Evaluator 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 REVISION:

6 TASK STANDARD:

RECOMMENDED STARTING LOCATION:

DIRECTIONS:

INITIAL CONDITIONS:

INITIATING CUE:

REFERENCES:

TOOLS: HANDOUT: JPM TITLE: Perfonn Manual Makeup to the Charging Suction EVALUATOR I)IRECTION SHEET Perfonn control board manipulations and calculations to perfonn manual blender makeup to the VCT in accordance with "Blender Manual Makeup Makeup secured after discovery of no boric acid Perfonn a manual makeup to the Charging Pump

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.

Your supervisor directs you to raise VCT level to 42% at 75 gpm, by perfonning a manual makeup to the VCT in accordance with 7.4.N, "Blender Manual Makeup Operations", beginning at step IV.A.6. 20M-7.4.N, Blender Manual Makeup Operations, Rev. 13 None 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:

Perform a manual makeup to the Charging Pump Suction. INITIAL

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 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 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 D When satisfied that you understand the assigned task, announce "I am now beginning the 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 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 EVALUATOR NOTE: This is a FAULTED JPM. When makeup is started, no boric acid flow is present. Reviews 20M-7.4.N, "Blender Manual Makeup Operation. Place Boric Acid Makeup Blender Control switch in Stop. STANDARD (Indicate "s" FOR SAT or "U" FOR UNSAT)=> START TIME: . ________ EVALUATOR NOTE: Simulator -Any Mode 1 -Expert command to set VCT level to 22%: A

-Mark in service BAST 7487 PPM; (RCS Set BA & Total flow totalizers to To fai12CHS*FCVl13A as-is (shut), go to Valves and select VLV-BATOIO, Select O-Fail As Set 2CHS*FCV114A Potentiometer for 100 gpm Reviews 20M-7.4.N, "Blender Manual COMMENTS:

EVALUATOR NOTE: Candidate may flow setpoint calculations prior to making control Places Boric Acid Makeup Blender Control switch in STOP position. Verifies Green Light -LIT, Red Light -NOT LIT.

i 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 ( "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 7487ppm 14.62gpm COMMENTS:

4.C Adjust [2CHS*FCV113A]

Boric Acid to Blender to the calculated setpoint.

4.1 C Calculates the desired flow setpoint:

14.62gpm xl 00 =366 4gpm 4.2C Adjusts [2CHS*FCVl13A]

for the desired flow setpoint, 366 units ::!:5 units. COMMENTS:

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 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. 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 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 ( "c" Denotes CRITICAL STEP) (Indicate "s" FOR SAT or "U" FOR UN 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 and adds it to the gallon set on the batch integrators for 2CHS*FQIS 113 and 2CHS*FQIS168, 9.1 9.2 Notes the Boric Acid Flow to Blender Flow Totalizer value on 2CHS*FQISI13 and adds the Boric Acid volume previously calculated (54.6 gallons) Notes the Blender Total Flow value on 2CHS*FQIS168 and adds the Total Volume previously calculated (280 gallons) COMMENTS:

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

6 ( "c" Denotes CRITICAL Verify a Reactor Coolant Pump is operating in an uniso1ated loop and has ?: 3000 gpm flow through the core and records the commencement of makeup and flow verification in the Narrative Log. 11. Verify the inservice Boric Acid Pump in Auto. Open [2CHS*FCVI13B], Boric Acid Blender Disch to Chg Pumps (BB-A) 13.C Place Mode Selector in MAN. (BB-A) STANDARD (Indicate "s" FOR SAT or "u" FOR UNSAT)::::)

I S/U I Verifies that RCS flow is?: 3000 gpm flow by RCP operation or flow indications. Records information in the Narrative Log. EV AL UATOR CUE: Inform the candidate that operator will make the Narrative Log COMMENTS: Verifies the in-service Boric Acid Transfer Pump is in AUTO. COMMENTS:

12.1 C Places [2CHS*FCVl13B]

control switch to OPEN position.

12.2 Verifies Red Light -LIT and Green Light -NOT LIT COMMENTS:

13.1C Places the Mode Selector Switch in MAN position.

COMMENTS:

I RTL#A5.640U OPERATIONS JOB PERFORMANCE 1I2-ADM-130 l.F04 Page 11 of 11 Revision 1 MEASURE JPM NUMBER: 2CR-581 JPM TITLE: Perform Manual Makeup to the Charging Suction JPM REVISION:

6 ( "c" Denotes CRITICAL Place Boric Acid Makeup Blender Control switch to Start. Verify proper operation at recorder [2CHS-FRl13] (VB-A). .... STANDARD (Indicate "s" FOR SAT or "U" FOR UNSAT)=> SIU Places Boric Acid Makeup Blender Control switch to START position. Verifies Boric Acid Transfer Pump that is in AUTO starts Red Light LIT, Green Light -NOT LIT. COMMENTS:

FAULT Alternate path begins here. Candidate must take action to secure the dilution after discovering that no acid flow exists. It is expected that the operator recognize and terminate wlin -1 min (-5-6% level Verifies Boric Acid to Blender and Total MIU Flow From Blender on [2CHS-FRl13J. 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:

! EV ALU A TOR 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 F eedlBus 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 Objectives or Material Quality. List/Description of Change(s):

Existing Rev. # New Change # 1. 2. New, alternate path JPM, based upon 2CR-097. New number is 2CR-597 Reason for Change (s): 1. Expand Alternate path JPM bank. APPROVALS:

NOTE: Additions, 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-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 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 D OJTITPE D Other: D Training D Other: EVALUATION RESULTS Performer Performer SSN: Time Critical:

D r8J Yes No Allotted Time: 15 minutes Actual Time: minutes JPM RESULTS: 0 0 SAT UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS 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 TASK STANDARD:

RECOMMENDED STARTING LOCATION:

DIRECTIONS:

INITIAL CONDITIONS:

INITIATING CUE:

REFERENCES:

TOOLS: HANDOUT: EVALUATOR DIRECTION SHEET Bus 2AE is energized from Bus 2A. The 2-1 EDG output breaker is open and the EDG has been shutdown.

SIMULATOR You are to Transfer Bus 2AE from Emergency to Normal Feed/Bus 2A. 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. 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.

20M-36.4.E, Revision 10, Transferring 4KV Emergency Bus 2AE to Bus 2A. 20M-36.4.ACS Diesel Gen 2-1 Electrical Fault None 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:

You are to Transfer Bus 2AE from Emergency to Normal FeedlBus 2A INITIAL 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 1 0 and 2E7, are open. The relay crew has replaced a defecti ve relay on breaker 2A 10. INITIATING 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 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". 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 I STEP ("e" D eno tes CRITICAL STEP) I STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT)=> SIU * ..*.**.**...

.........

.. .. ..... ST ART 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 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: Close breaker 2AI0, 4KV 2.1C Plaees breaker 2AlO control switch in the CLOSE Bus 2A to Emergency Bus position.

2AE. Verifies the RED light above breaker 2A 1 0 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 ( "e" Denotes CRITICAL Place the 2-1 Diesel Generator synchronizing switch in the Bus 2A position. Adjust 2-1 EDG until the synchroscope needle is rotating in the SLOW DIRECTION.

STANDARD (Indicate "S" FOR SAT or "U" FOR UN SAT)=> I 8/U I Places 2-1 EMERG GEN SYNCHRONIZING SEL SW in the Bus 2A position.

COMMENTS: Observes the 2-1 Emergency Diesel Generator synehroscope on the Vertical Board and notes it is rapidly rotating in the SLOW direction. Adjusts the 2-1 EMERG GEN GOVERNOR control switch to the RAISE position. 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. 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. 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 ( "e" Denotes CRITICAL Maintain generator power factor between 0.8 and 1.0 lagging, as indicated on Emergency Generator Power Factor, by adjusting Emergency Generator 2-1 Voltage Adjust. Reduce load on the EDG to <100KW. STANDARD Stu I (Indicate "s" FOR SAT or "U" FOR UNSAT)=> Adjusts 2-1 EMERG GEN VOLTGE ADJUST as needed to maintain between 0.8 and 1.0 lagging PF as indicated on Power Factor meter on VB-C. COMMENTS:

FAULT STATEMENT:

At this point the alternate path begins. Atmunciator A8-4C, GEN 2-1 ELECTRICAL FAULT" will when EDG 2-1 loading reaches 1000 KW.

alann DO 2-1 DIFF will also be received.

should respond to ARP and Trip the 2-1 EDG open ACB 2E10 which failed to automatically EV ALVA TOR CUE: As Unit Supervisor, candidate to reduce load to 100 KW over a minute 9.1 C Intennittently places the 2-1 EMERG GEN GOVERNOR control switch in the LOWER Position. 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 A TIS 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 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. ! Trips 2-1 EDG and manually 11.1 Momentarily places breaker 2E 1 0 control switch in opens output breaker 2EIO. TRIP. Verifies the WHITE light above breaker 2EIO control switch is ON. Manually Trips EDG 2-1 by pushing the stop pushbuttons. Verifies EDG 1 is tripped by observing 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"; <, .' .... STOP TIME: " ,.;

', ....'..;*** <;

RTL#A5.640U 112-ADM-1301.F04 Page 1 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE PPM) TRAINING MATERIAL TITLE: TRAINING MATERIAL NUMBER: PROGRAM TITLE: COMPUTER CODE: REVISION NUMBER: Containment Spray Manual Actuation-SWS and QSS Valve Malfunctions 2CR-656 Licensed Operator Training 2CR-656 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 1 C, Rev. 2 INSTRUCTIONAL SETTING: Simulator APPROXIMATE DURATION:

10 Minutes PREPARED BY: PEER REVIEW BY: APPROVED FOR USE: P.T. Eisenmann Training Supervisor or Designee Date Date Date RTL#A5.640U 1/2-ADM-1301.F04 Page 2 of 10 Revision 1 TRAINING MATERIAL CHANGE FORM Affected Training Materials: Type ofl8] Changes Requiring Learning Objective Related Change? New Rev.

Yes D Changes Not The Change Does Not Impact Learning Existing Rev. Requiring Revision Objectives or Material New Change List/Description of New alternate path JPM based upon 2CR-573. Reason for Change Add to alternate path JPM 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 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: D Perform 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 Actual 10 minutes Critical:

I;g] No Time: D SAT JPM RESULTS: D UNSAT (Comments required for UNSA T evaluation)

Comments:

OBSERVERS Name/SSN:

Name/SSN:

EVALUATOR Evaluator (Print): Date: Evaluator Signature:

RTL#A5.640U TASK STANDARD:

RECOMMENDED STARTING LOCATION:

DIRECTIONS:

INITIAL CONDITIONS:

INITIATING CUE:

REFERENCES:

TOOLS: HANDOUT: 1/2-ADM-1301.F04 Page 4 of 10 Revision 1 EVALUATOR DIRECTION SHEET Manually initiate CIB, align both trains of SWS to RSS exchangers and isolate SWS to CCP heat Simulator You are to Verify Containment Spray Actuation. A reactor trip and safety injection have occurred due to a large break LOCA. The actions of E-O are being performed.

The Unit Supervisor directs you to perform Attachment HVerification Of Automatic Actions", Step 7 to check CIB Containment Spray 20M-53A.l.A-O.l1 , "Verification Of Automatic Actions", Issue I Rev. 20M-53A.l.A-O.5, "Containment Isolation Phase B Checklist", IC, Rev. 20M-53A. l.A-O. 1 1, "Verification Of Automatic Actions", Issue Rev. 6, place kept up to step 20M-53A.l.A-O.5, "Containment Isolation Phase B Checklist", IC, Rev.

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:

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 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 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 REVISION:

0 ( "e" Denotes CRITICAL 1. Reviews procedure.

JPM TITLE: Containment Spray Manual Actuation STANDARD (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: 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 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 53A.l.A-O.5, "Containment Isolation Phase B Checklist". 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) "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. IF NOT, THEN manually 4.1 Simultaneously ROTATES (Clockwise) both Train initiate CIB (both switches for "A" CIB switches to ACTUATE position.

both trains). Simultaneously ROTATES (Clockwise) both Train "B" CIB switches to ACTUATE position.

COMMENTS: Check BLUE CIB marks -LIT. 5.1 Candidate checks all indicating lights with BLUE CIB marks LIT. Determines 2SWS*MOVI06A

/ Band 2S\VS*MOVI03A / B not aligned. EVALUATOR If requested, provide Candidate a copy of 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 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". Plaees 2SWS*MOV103A control switch to OPEN. Verifies RED light -LIT and GREEN light -NOT LIT. Plaees 2SWS*MOVI06B control switch to CLOSE. Verifies GREEN light -LIT and RED light NOT LIT. Places 2SWS*MOVI03B control switch to OPEN. 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 Stop all RCP's. 7.1 Verifies control switches for 2RCS*P21A, 21B and 21 C have been placed to STOP. Verifies 2RCS *P21 A, 21 Band 21 C pump RED lights NOT LIT and WHITE lights -LIT. Verifies 2RCS-FI414 (415)(416);

2RCS-FI424 (425)(426);

2RCS-FI434 (435)(436) flow has lowered. Verifies 2RCS-II21A(B)(C) amps zero. COMMENTS:

EVALUATOR CUE: That completes this JPM . ..... ,""<:,/ .,' STOP TIME: " ,

RTL#A5.640U 112-ADM-1301.F04 Page 1 of 12 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE (JPM) TRAINING MATERIAL TRAINING MATERIAL PROGRAM COMPUTER REVISION TECHNICAL

REFERENCES:

2CR-636 Licensed Operator Retraining 2CR-636 2 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: APPROXIMATE DURATION:

Control Room/Simulator 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 Revision Learning Objective Related Change? DYes rgj No New Rev. #2 D Changes Not Requiring Revision The Change Does Not Impact Learn Objectives or Material Quality. ing Existing Rev. # 1 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 Training Superintendent/Supervisor/Peer Date Incumbent Impact Review, 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 ALUA TION 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 ALUA TION RESULTS Perfonner Name: Perfonner SSN: Time Critical:

D [gj Yes No Allotted Time: 25 Minutes Actual Time: minutes JPM RESULTS: D 0 SAT UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS 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 TASK STANDARD:

RECOMMENDED STARTING LOCATION:

DIRECTIONS:

INITIAL CONDITIONS:

INITIATING CUE:

REFERENCES:

TOOLS: HANDOUT: 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. Control Room You are to perform the task, transfer cooling trains of RHS.

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 Your supervisor directs you to place the B train of RHS in service and then place the A train of RHS in standby. 20M-I0A.B, Parts D & E Revision 30 20M-53CA.2.10.1 revision 11 None 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

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 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 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". 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 UN SAT)=> SfU EVALUATOR NOTE: This is a EVALUATOR NOTE: Simulator FAULTED JPM. The candidate is Init IC-232 Turn on recorders expected to transition to AOP 2.10.1 Place/remove caution tags as following the loss of both RHS Shutdown 'B' Train RHS lAW 20M-lOA.B Part pumps. Close 2RHS*MOV720B and Set PLP RTCI =1 O. Balance Charging and Letdown via 2CHS*FCV122 and 2CHS*HCV 142. START TIME: ________ ", ,,', Reviews procedure.

1.1 Reviews Section D, "To Place RHS Train Service From A Standby Condition" of 20M-l COMMENTS:

EV ALU A TOR 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) Verify CCP temperature 2.1 Checks temperature on 2CCP-TIl OOA(1 OOB)( >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 ( "c" Denotes CRITICAL Check RCS temperature. Align RHS valves. STANDARD (Indicate "s" FOR SAT or "u" FOR LNSAT)=> I S/U I RCS/RHS temperature>

120F. Places control switch to open for 2CCP*MOVl12B, RHR PP SEAL CLR 22B & HX21B COOLING WATER INLET VLV Verifies Red Light** LIT and Green Light -NOT LIT. COMMENTS: Checks OPEN [2RHS*MOV701B].

Verifies Red Light** LIT and Green Light -NOT LIT. Checks OPEN [2RHS*MOV702B].

Verifies Red Light .. LIT and Green Light -NOT LIT. CLOSES [2RHS*FCV605B], demand at zero. Verifies OPEN [2CHS*HCV142], demand not at zero. Che:cks CLOSED [2RHS*MOV750B].

Verifies Red NOT Light -LIT and Green Light LIT. CLOSES [2RHS*HCV758B], demand at 100%. Checks OPEN [2RHS*MOVnOB], Red light lit, Green light not lit. COMMENTS:

EVALUATOR NOTE: If candidate decides to j open 2CHS*HCV142 further, cue as the supervisor 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 UN SAT)=> SIU 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]. Det<:rmines step is NI A based on Attachment

1. EVALUATOR CUE: [2RHS*P21B]

venting not required per Attachment 1 . COMMENTS: 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. 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 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. Starts [2RHS*P21 B]. COMMENTS:

9. If required, maintain PRZR pressure between 275 and 350 psig by the following methods. 9.1 Marks step 16 as N/A. EVALUATOR CUE: RCP operation is not require:d at this time. You do NOT have to adjust pressure, step 16 is N/A. COMMENTS:

lQ.C Adjust RHS system flow. 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 Transfer [2RHS*FCY605B]

11.1 Adjusts auto flow setpoint to desired flowrate and to auto. places the controller in AUTO. COMMENTS: 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]. 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 REVISION:

2 JPM TITLE: Swap RHS Trains ( "e" Denotes CRITICAL Locate procedure. Check [2RHS*P21A]

stopped. EVALUATOR NOTE: Alternate path here. [2RHS*FCV605B]

will ramp fully open and after full open, [2RHS*P21 B] will trip. Candidate is expected to transition to AOP 2.10.1. STANDARD (Indicate "S" FOR SAT or "U" FOR I S/U I Transitions to procedure Section E, To Place RHS Train A in Standby. COMMENTS: STOPS [2RHS*P21A]. CLOSES [2RHS*MOV750B].

Verifies Red Light--NOT LIT and Green Light LIT. SIMULATOR OPERATOR CUES: After candidate secures [2RHS*P21A], ramp OPEN [2RHS*FCV605B]

and after full open, trip [2RHS*P21B].

[2RHS*P21B]

also will not 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 ( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UN SAT)=> [ SIU Transition to AOP 2.10.1. 15.1 May attempt to restart [2RHS*P21Al May attempt to restart [2RHS*P21B]. May refer to annunciator A 1-SH ARP. If so, ensure proper steps are followed. Transitions to AOP 2.10.1. EVALUATOR CUE: The local operator reports [2RHS*P21B]

has an Overcurrent relay tripped. CLOSES [2RHS*HCV7S8A], demand at 100%. CLOSES [2RHS*FCV605A]

demand at zero. Verifies CLOSED [2CHS*HCY142], demand at zero. lS.SC Restarts 2RHS-P21A. 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 1 12-ADM-130 Page 1 of Revision 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 20M-53A.l.A-l.8, "Makeup to PPDWST [2FWE*TK21 0]", Rev. INSTRUCTIONAL SETTING: In-Plant APPROXIMATE DURATION:

15 Minutes PREPARED BY: Ian PEER REVIEW APPROVED FOR Training Supervisor or Designee 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 Revision D Changes Not Requiring Revision Learning Objective Related Change? DYes C8JNo The Change Does Not Impact Learning Objectives or Material Quality. New Rev. # 0 Existing Rev. N/ A New Chan e# List/Description of Change(s):

New JPM Version. Reason for Change (s): Initial Issue. APPROVALS:

Ian Forbes -Prepared by Training Superintendent/Supervisor/Peer

("Changes Not Requiring Revision" only) Date Date NOTE: Additions, deletions or changes to training materials must be reviewed for their possible impact to the Training Qualification Matrix. See Incumbent Impact Review, 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 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 F AUL TED JPM D ADMIN]STRATIVE JPM EV ALUA TION 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 D OJT/TPE D Other: D Training D Other: EVALUATION RESULTS Performer Performer SSN: Time Critical:

D [gI Yes No Allotted Time: 15 Minutes Actual Time: minutes JPM RESULTS: D D SAT UN SAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS 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 REVISION:

0 TASK STANDARD:

RECOMMENDED STARTING LOCATION:

DIRECTIONS:

INITIAL CONDITIONS:

INITIATING CUE:

REFERENCES:

TOOLS: HANDOUT: JPM TITLE: Align Service Water to [2FWE*P23B]

Motor Driven Auxiliary Feed Pump Suction EVALUATOR DIRECTION SHEET Service water v(:nted and aligned to [2FWE*P23B]

Motor Driven Auxiliary Fee.d Pump suction. In-Plant You are to align Service Water Supply to [2FWE*P23B]

Motor Driven Auxiliary Feed Pump Suction. 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. Your supervisor directs you to supply [2FWE*P23B]

Motor Auxiliary Feed Pump suction from Service Water by completing Attachment A-I. 8 beginning with step Mechanical Maintenance and another operator are on station in Safeguards ready to coordinate this 20M-53A.l.A-l.8, "Makeup to PPDWST [2FWE*TK2 I 0]", Rev. Keys 20M-53A.l.A-1.8, "Makeup to PPDWST [2FWE*TK210]", Rev. place kept up to step Ops Manual Figure 24-3 (provide if 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: 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. INITIA TINa 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 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 ("c" Denotes CRITICAL IF PPDWST Level Drops to 25 inches, THEN align Service Water to the Auxiliary Feedwater Pumps by performing the following:

If Containment Isolation Phase B has NOT then perform the Close Close Verify Open [2SWS*MOVI 03B], Recirc Spray HX Service Water Supply Header B Isolation.

STANDARD (Indicate "s" FOR SAT or "V" FOR VNSAT)=> I S/V I START TIME: EV AL,UATOR CUE: Provide a procedure Inform the candidate that you will role play personnel they are required to interact Recognizes from the Initial Conditions that CIB has occurred and perfonnance of this step is not required.

COMMENTS: Recognizes from the Initial Conditions that this step has already been performed.

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 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 (North SFGDS above clockwise 2FWE*23B EVALUATOR CUE: [2FWE*356], Service Water Supply Tell Tale Drain has been rotated CLOCKWISE.

COMMENTS: Vent SWS to AFW piping as follows: Request Mechanical Maintenance Technician loosen flange at RV102], Emergency Water Supply Relief. (South SFGDS above 2FWE-P23A

-718) With Key SRl14, Open [2FWE*98], Service Water Isolation. (North SFGDS above 2FWE*P23B 718) Requests Mechanical Maintenance Technician loosen flange at [2FWE-RV102J, Emergency Water Supply Relief. EV ALUATOR CUE: Flange at Emergency Water Supply Relief has been

COMMENTS: Removes locking device and opens [2FWE*98], Service Water Isolation by rotating valve handwheel chain operator in the counter-clockwise direction.

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 JPM REVISION:

0 Auxiliary Feed Pump STANDARD S/U I ( "e" Denotes CRITICAL (Indicate "S" FOR SAT or "U" FOR UNSAT)=> When a solid stream of water 6.1C Closes [2FWE*98], Service Water Isolation appears at the flange at rotating valve handwheel chain operator in [2FWE*RV102], then Close clockwise EVALlATOR CUE: [2FWE*98], Service Water Isolation is indicating CLOSED. COMMENTS: Request Mechanical 7.1 Requests Mechanical Maintenance Maintenance Technician tighten flange at tighten flange at EVALUATOR CUE: Flange at [2FWE-RVI02], RVI02]. Emergency Water Supply Reliefhas been tightened.

COMMENTS: Open [2FWE*98], Service 8.lC Opens [2FWE*98], Service Water Isolation by Water rotating valve handwheel chain operator in the counter-clockwise direction.

EVALUATOR CUE: [2FWE*98], Service Water Isolation is indicating OPEN. COMMENTS:

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 ( "e" Denotes CRITICAL For [2FWE*P23B], Motor Driven AFW Pump, perform the following:

Slowly Open Service Water Supply (South Safeguards 10.C With Key CRITI19, close [2FWE*95], Primary DWST Supply to [2FWE*P23B]. Observe AFW pump discharge pressure to ensure proper operation.

STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT)=> Stu I 9.1 C Opens [2FWE*92], Service Water Supply to [F\VE*P23B]

by rotating valve handwheel in the counter-clockwise direction.

EVALUATOR CUE: [2FWE*92]

has been EVALUATOR NOTE: Valve position indication is top of the valve and is difficult to COMMENTS:

10.1 C Unlocks and Closes [2FWE*95], Primary DWST Supply to [2FWE*P23B]

by rotating valve handwheel in the clockwise direction.

EVALUATOR CUE: [2FWE*95]

has been CLOSED. Valve position indicates CLOSE. COMMENTS: Observes AFW pump discharge pressure to ensure proper operation by depressing the ON/OFF red pushbutton and reading displayed pressure.

EVALUATOR CUE: When ON/OFF pushbutton is depressed, [2FWE*P23B]

pressure is reading approximately 450 psig. complett:s this COMMENTS:

STOP TIME: _________

RTL#A5,640U Page 1 Revision 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 PEER REVIEW APPROVED FOR Training Supervisor or Designee

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. # Requiring Revision Objectives or Material New Change List/Description Changed instructional setting from classroom to Updated JPM to reflect most current standards

&

Updated to reflect most current copy of Reason for Change (s): Enhanced JPM for use on 2LOT8 Exam. i APPROVALS:

Ian

NOTE: Additions, deletions or Prepared by 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 ("Changes Not Requiring Revision" only) 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 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 D OJT/TPE D Other: D Training D Other: EVALUATION RESULTS Performer Performer SSN: Time D Yes Actual 15 minutes Critical:

I:8J No Time: D SAT JPM RESULTS: D UN SAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN:

Name/SSN:

EVALUATOR Evaluator Date: Evaluator Signature:

RTL#A5.640U 112-ADM-130 1.F04 Page 4 of8 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE TASK STANDARD:

RECOMMENDED STARTING LOCATION:

DIRECTIONS:

INITIAL CONDITIONS:

INITIATING CUE:

REFERENCES:

TOOLS: HANDOUT: EVALUATOR DIRECTION SHEET MG set #2 is running with [2RDS-MG22]

Generator Output breaker CLOSED. In plant You are to simulate starting #2 MG Set. 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. 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. 20M-lA.B Revision 13, "Reactor Rod Drive Control System Startup".

NONE Place kept copy of 20M-1.4.B Revision 13, "Reactor Rod Control System Startup" up to step 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: 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 Then hand this sheet to the evaluator.

1 12-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: At CONT], Place MG22] Motor Circuit Breaker Control switch in CLOSE position, AND check MG set #2 starts. Depress AND Hold MG22] Gen. Field Flash pushbutton until the [2RDS-MG22]

Generator Line Volts voltmeter indicates approximately 260 V AC, THEN release. STANDARD (Indicate "S" FOR SAT or "U" FOR UN SAT):::::>

I SIU I START TIME: ________ 1.1 C Places [2RDS-MG22]

MOTOR Circuit Breaker Control switch to the closed position. Verifies Red Light LIT and Green Light-NOT LIT. EVALUATOR CUE: Red Light LIT, Green Light NOT LIT. #2 MG set is accelerating.

COMMENTS: Simulates depressing

[2RDS-MG22]

Gen. Field Flash pushbutton until [2RDS-MG22]

Generator Line Volts voltmeter indicates approximately 260V AC. EVALUATOR CUE: [2RDS-MG22]

Generator Line Volts voltmeter increased to 260 VAC. 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 ( "C" Denotes CRITICAL Complete 20M-IA.Q, "Administrative Guidelines for Closing the Reactor Trip/Bypass Breakers". Close reactor trip breakers [RTA AND RTB] to provide load. Place [2RDS-MG22]

Generator Circuit Breaker control switch to CLOSE position.

STANDARD (Indicate "s" FOR SAT or "U" FOR UNSAT)=:>

I SIU I Acknowledges the need to complete 20M-IA.Q.

EV ALU A TOR CUE: 20M-IA.Q Guidelines for closing the reactor breakers has been EVALUATOR CUE: CRDM cooling is in service per initial conditions.

COMMENTS: Requests that the RO close the reactor trip breakers from BB-B. EVALUATOR CUE: The RO acknowledges request to close reactor trip breakers and after minutes you hear noise and the RO confirms the are COMMENTS:

5.1 C Places [2RDS-MG22]

GENERATOR Circuit Breaker control switch to CLOSE position.

EVALUATOR CUE: The Mechanical Flag (RED) indicated and the GREEN indicating light is

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 ( "e" Denotes CRITICAL Place [2RDS-MG22]

Synchronize switch in the ON position AND Check the two generators synchronize. When [2RDS-MG22]

Generator circuit breaker CLOSES, THEN place [2RDS-MG22]

Synchronize switch to the OFF position.

STANDARD (Indicate "S" FOR SAT or "U" FOR 6.1 C Places [2RDS-MG22]

Synchronize switch in the ON position. Checks [2RDS-MG22]

GENERA TOR Output 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: Places [2RDS-MG22]

Synchronize switch to the OFF position.

EVALUATOR CUE: Acknowledges Synch switch in OFF position. Informs supervisor that # 2 MG Set is running with output breaker closed or that the task is complete.

COMMENTS:

STOP 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 20M-53C.4.2.2.1 C, "Power Range Channel Malfunction", Revision 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 I RTL#A5.640U 112-ADM-130 I.F04 Page2of8 Revision 1 TRAINING MATERIAL CHANGE FORM

Affected Training Materials:

2PL-009 Type of Change: Changes Requiring Learning Objective Related Change? I New Rev. # 7 Revision DYes D Changes Not The Change Does Not Impact Learning Existing Rev. # 6 Requiring Revision Objectives or Material Quality. New Change # List/Description of Changed step 4.2, 5, & 6 typos from C3 to proper Included information about protection cabinet doors having limit switches which send the room an indication when the doors are Modified starting location from control room to Enhanced Task Standard to be more specific to the actual failed Reason for Change Enhance 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, Training Supenntendent/Supervlsor/Peer Date NOBP-TR-I104.

("Changes Not Requiring Revision" only) i

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 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:

TYPE: ADMINISTERED BY: o Perfonn Plant Site B Annual Requal Exam B BVT IZI Simulate Simulator Initial Exam NRC Classroom 0 OJT/TPE 0 Other: 0 Training 0 Other: EVALUATION RESULTS Perfonner Perfonner SSN: Time L.J Yes Actual 7 minutes Critical:

L8J No Time: 0 SAT JPM RESULTS: D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN:

Name/SSN:

EVALUATOR Evaluator Date: Evaluator Signature:

RTL#A5.640U TASK STANDARD:

RECOMMENDED STARTING LOCATION:

DIRECTIONS:

INITIAL CONDITIONS:

INITIATING CUE:

REFERENCES:

TOOLS: HANDOUT: 112-ADM-J301.F04 Page 4 of8 Revision 1 EVALUATOR DIRECTION SHEET Power Range Channel N-43 bistables are in the test (tripped) position.

In-plant You are to simulate placing a reactor protection channel in the tripped condition. 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 accordance with AOP-2.2.1 C, Power Range Channel Step 20M-53C.4.2.2.1 C, "Power Range Channel Malfunction", Revision 10 Key No. 117 (18) 20M-53C.4.2.2.1 C, "Power Range Channel Malfunction", place kept 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. The plant is in Mode 1 at 100% power. INITIAL CONDITIONS: 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 D When satisfied that you understand the assigned task, announce "I am now beginning the 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 Then hand this sheet to the evaluator.

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. 53C.4.2.2.1 C, Power Range Channel Malfunction.

1.1 Candidate reviews place kept copy of AOP 2.2.1.C provided.

COMMENTS:

2. Obtain Keys 117 (118) 2.1 Obtains Key No. 117 (118) for process rack door by process rack requesting keys from the evaluator or indicating that they will need to go to the Control Room to sign out thesl;;! keys. EVALUATOR Provide the candidate the KEY 117 (118) when request the keys or begin to walk to the control COMMENTS:

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 STEP STANDARD ( "c" Denotes CRITICAL STEP) (Indicate "s" FOR SAT or "U" FOR I SIU I EV ALVA 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. Open process rack door. 3.1 Opens the proper Protection Cabinet No.3 door. COMMENTS: 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: 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 5.2 Verifies the RED LED is ON.

2TS/432C-l is in TEST and Red LED is COMMENTS:

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 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 2TS/432C-2 is in TEST and Red LED is ] COMMENTS: 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* . 'STOP TIME: ....*. ' .. ..... <"

A d' IX 0 S , cenano 0 tr u me F orm 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 No. (R) ATC 1 (N) BOP, SRO (TS) SRO 2 (I) ATC, SRO 3 (C) BOP, SRO 4 (TS) SRO (C) ATC (C) BOP, SRO 5 (M) ALL 6 (C) ATC, SRO 7 (C) BOP, SRO 8 (C) BOP, SRO 9 Event Description Raisl;:! power in accordance with reactivity plan. 2FWE*P22 (turbine driven Aux Feedwater pump) trips 2CHS-PTI45, fails high, ATC required to manually control letdown pressure via 2CHS-PCVI45.

Loss of 2AE 4kv Emergency bus I 2-1 Emergency Diesel fails to auto start. BOP required to manually start EDG 2-1. ATC manually aligns cooling water flow to EDG 2-1 2CCS-P21 A sheared shaft, auto start failure of 2CCS-P21 B, requires manually starting standby pump. I I Feedline break inside CNMT. CIB actuation failure MSLI actuation failure with 2SDS*AOV111's failing to auto close, requires BOP to manually actuate MSLI and close all 6 2SDS*AOVl11

's "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 1 00% lAW 20Mand the reactivity When reactor power has increased to 27.5%, the linkage for the trip-throttle valve for the Turbine Auxiliary Feedwater Pump, 2FWE*P22, will fail, requiring the US to determine appropriate Tech When Tech Specs have been addressed, Letdown Pressure Transmitter, 2CHS*PTI45, will fail requiring the A TC to control letdown pressure by manually controlling the Letdown Pressure After the crew has stabilized the plant, 4KV emergency bus 2AE will de-energize and EDG 2-1 will fail automatically start. The crew will enter AOP 2.36.2, Loss of 4KV Emergency Bus, which requires manual start to restore power to the bus. The SRO will determine appropriate Tech Spec Secondary Component Cooling Water Pump, 2CCS-P21A, will experience a sheared shaft, requiring crew to enter AOP 2.28.1, Loss of Secondary Component Cooling Water, and the BOP to manually start standby pump, 2CCS-P21B, which failed to auto A Feedwater header rupture will occur inside containment.

The reactor will trip. Upon the reactor trip, crew will enter MSLI will fail to automatically actuate, requiring the BOP to manually actuate a Steam Line When MSLI is actuated, the main steam line drains (2SDS*AOV]

11 's) will fail to close requiring the to manually close at least 1 CIB will fail to automatically actuate, The A TC will identify the failure to actuate and manually both trains of The crew will identify the "c" S/G as faulted and transition to E-2 to Train "B" CREV's, Control Room Emergency Ventilation System, will fail to actuate requiring the BOP manually The crew will progress through E-2 and transition to The scenario will be terminated after the crew transitions to ES-l.l and isolates the HHSI flowpath closing 2SIS*MOV867A, B, C, 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 INITIAL CONDITIONS:

25% Power, CBD = 121, Xe increasing BOL, 1935 PPM Boron, IC-2II ADDITIONAL LINEUP CHANGES STICKERS YCT -2SAS-C21 B CS EQUIPMENT STATUS DATEITIME OOS 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 1. 20M-52.4.A completed and place kept up through step IV.F.7.g (pg 65) 2. Reactivity plan 3. BOL reactivity placard MONITOR SETUP ATC position MID POWER display TECHNICAL SPECIFICATION(S)

PROCEDURES NEEDED 20M-52.4.A AOP 2.28.1 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 INSTRUCTIONAL GUIDELINES Initialize IC 211, and establish initial plant conditions.

Insert the following per the Simulator Setup section of the HTML file for this scenano: PRELOAD COMMANDS TRGSET 1 'JPPLP4(1)'

IMF PMP-CAS004 (0 0) 1 IMF DSGOID IMF PPL09A (0 0) IMF PPL09B (0 0) IMF PPLIOA (0 0) IMF PPLIOB (0 0) IMF BST -CCS006 (0 0) 2 IMF PMP-CCSOOI (7 0) 0 IMF A6-3B-P0670D (7 0) 0 TRGSET 8 'XClI076A

== 0' TRG 8 'DMF A6-3B-P0670D' lOR XBSI052P (0 0) ON lOR XBSI065P (0 0) ON TRGSET 6 'XBSI052C

= l' TRG 6 'DOR XBSI052P' TRGSET 9 'XBSI025P

== l' TRG 9 'DOR XBSI065P' TRGSET 5 'FNISPR(l)

>= 27.5' IRF LOA-AFW022 (5 0) 1 IMF VLV-MSS032A (0 0) 100 IMF VLV-MSS033A (0 0) 100 IMFVLV-MSS034A (0 0) 100 IMF VLV-MSS035A (0 0) 100 BVPS 2L8 NRC Scenario 1, Rev AG PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT Reactor plant at 25% power, BOL, Xe increasing, RCS boron =1935 PPM, CBD = 121 steps. Inserts all pre-loads required to support the scenario.

Set trigger 1 on reactor trip 2SAS-C21 BOOS Inhibit auto start of EDG 2-1 Inhibit auto CIB TRN A, manual successful Inhibit auto CIB TRN B, manual successful Inhibit auto MSLI TRN A, manual successful Inhibit auto MSLI TRN B, manual successful Inhibit auto start of2CCS-P21B, manual start successful 2CCS-P21A severed leads Ann A6-3B Low CCS pump Disch Press Trigger 8 to clear Ann A6-3B Ann A6-3B clears on start 2CCS-P21B 2HVC*MOD20IA failed open. 2HVC*MOD201 B failed open. Set trigger 6 on 2HVC*MOD201A CS to close. DOR, 2HVC*MOD201 A manually closes. Set trigger 9 on "B" Tm CREV'S PB depressed.

DOR, 2HVC*MOD20IB manually closes. Trigger 5 on reactor power> 27.5% 2FWE*P22 trip throttle valve trips shut Fail 2SDS-AOV111Al open FaiI2SDS-AOVI11A2 open Fail2SDS-AOVlllBlopen Fail2SDS-AOVlll B2 open 40f23 BEAVER VALLEY POWER I** INSTRUCTIONAL GUIDELINES IMF VLV-MSS036A (0 0) 100 IMF VLV-MSS037A (0 0) 100 TRGSET 10 'XAlI090C

= l' TRG 10 'DMF VLV-MSS032A' TRGSET 11 'XAlI077C l' TRG 11 'DMF VL V-MSS033A' TRGSET 12 'XAlI107C

= l' TRG 12 'DMF VLV-MSS034A' TRGSET 13 'XAlI095C

== l' TRG 13 'DMF VLV-MSS035A' TRGSET 14 'XAII119C

== l' TRG 14 'DMF VLV-MSS036A' TRGSET 15 'XAII110C

== l' TRG 15 'DMF VLV-MSS037A' Assign shift positions SRO:_________ ATC:BOP:

Conduct a shift turnover with oncoming operators.

When the shift turnover is completed, place the simulator to RlJN and commence the scenario.

BVPS -2L8 NRC Scenario 1, Rev AG PLANT STATUS I PROCEDURAL GUIDANCE FaiI2SDS-AOVIIIC2 Set trigger 10 on 2SDS-AOVI11Al CS to DMF, 2SDS-AOVIIIAI manually Set trigger lIon 2SDS-AOVl11A2 CS to DMF, 2SDS-AOVIIIA2 manually Set trigger 12 on 2SDS-AOVIIIBI CS to DMF, 2SDS-AOVII1BI manually Set trigger 13 on 2SDS-AOVII1B2 CS to DMF, 2SDS-AOVI11B2 manually Set trigger 14 on 2SDS-AOVI11CI CS to DMF, 2SDS-AOVII1CI manually Set trigger 15 on 2SDS-AOVll1C2 CS to DMF, 2SDS-AOVl11 C2 manually Simulator Frozen until after shift turnover unless it needs to be run momentarily for an alignment change. Simulator running. 50f23 I EXPECTED STUDENT Crew assumes control of the Unit.

BEAVER VALLEY POWER r INSTRUCTIONAL GUIDELINES EVENT 1: Continue power increase per reactivity plan. NOTE: Event 2 will occur automatically when Rx power reaches 27.5%. EVENT 2: 2FWE*P22 Trip Throttle Valve trips (command preloaded)

IRF LOA-AFW022 (5 0) 1 ROLE PLAY: 2 minutes after being dispatched to inspect 2FWE*P22, report back that the trip throttle valve linkage rod is broken. PLANT STATUS I PROCEDURAL GUIDANCE SRO directs the crew to continue power increase lAW 10M-52.4.A.

RCS temperature rises in response to rod withdrawal and dilution.

IMMEDIATE PLANT RESPONSE:

Computer point Y5172D alarms, TURB DR AFW PP TRIPPED A2-3H, Safety System Train A Inoperable EXPECTED STUDENT lAW Reactivity plan, ATC dilutes/withdraws rods to raise reactor power to 100%. BOP raises turbine load. 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 position. Voltage regulator is maintaining power factor. BOP reports that 2FWE*P22 is SRO dispatches operator to investigate SRO enters TS 3.7.5, condition w/in 2 hrs realign Operable pumps to separate (for this failure this action is not 72 hrs to restore AFW train to operable BVPS -2L8 NRC Scenario 1, Rev 60f23 BEAVER VALLEY POWER INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE Proceed with next event after power is raised above 30% as indicated by 2G (NOT P-8) status panel clearing or at LE discretion.

EVENT 3: 2CHS*PT145 fails high IMF XMT-LDS007 A (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 INSTRUCTIONAL GUIDELINES EVENT 4: Loss of 2AE 4kv emergency bus with an auto start failure of2-1 EDG. IMF BKR-HIVOI (0 0) 0 ROLE PLAY: If dispatched with Attachment A-1.6 to verifY MCC feeder breakers are closed, wait 10 minutes then report all are closed. PLANT STATUS I PROCEDURAL IMMEDIATE PLANT 4KV ACB 2AlO trips 4KV bus 2AE voltage reduces to zero Multiple electrical related SRO enters AOP 2.36.2 for Loss ofEmergency EXPECTED STUDENT BOP reports multiple unexpected electrical BOP identifies 4kv Bus 2AE is de-energized and the 2-1 EDG has failed to BOP reports that 4kv Bus 2DF is ATC verifies 2CHS*P21B remains running, primary plant is stable and begins referring to Crew verifies no overcurrent electrical SRO directs BOP to manually start EDG BOP successfully starts EDG ATC verifies 2SWS*P21 A is running and cooling water supply valve, Crew performs EO P Attachment A-I. 6, lAW of AOP 2.36.2 to verify EDG auto loading SRO evaluates TS for emergency bus and EDG SRO detennines 20ST-36.7 is required within 1 to verify operability of remaining sources per 3.8.1, Conditions A and BVPS -2L8 NRC Scenario], Rev AG 80f23 BEAVER VALLEY POWER INSTRUCTIONAL GUIDELINES EVENT 5: Turbine Plant Component Cooling Water Trouble (2CCS-P2IA sheared shaft) TRG! 7 (actuate trigger 7, all required commands are preloaded.)

NOTE: IfCCS cooling flow is not quickly re-established, station air compressor, 2SAS-C21A will trip on high temperature and will not be able to be recovered, the diesel air compressor will auto start and supply air as required.

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 PLANT STATUS I PROCEDURAL GUIDANCE IMMEDIATE PLANT 2CCS-P21A ammeter reduces to A6-3B, CCS pump discharge press A 7 -6F, Main Leads Cooling A7-2H, EHC Temperature 2CCS-P21B fails to auto start when reduces to < 75 SRO enters AOP A6-3D, STA and Cond Polishing Air Sys Trb, (alarms later depending on response time) SRO may enter AOP 2.34.1 for Loss of Station Air, no actions are required, AOP steps are not scripted.

EXPECTED STUDENT BOP reports unexpected CCS related alarms. ATC refers to ARP's BOP recognizes failure of2CCS-P21B to auto start on low pressure and manually starts 2CCS-P21B.

BOP recognizes 2SAS-C21A tripped. Crew dispatches an operator to start diesel air compo 90f23 BEAVER VALLEY POWER INSTRUCTIONAL GUIDELINES EVENTS 6, 7, 8, & 9 Feed line break inside containment IMF FLX-CFW33 (0 0) 8700 Multiple malfunctions occur on reactor trip. All commands preloaded IMFPPL09A IMFPPL09B IMFPPLIOA IMF PPLIOB 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' PLANT STATUS / PROCEDURAL GUIDANCE Feedwater header rupture inside causes an automatic reactor Additional failures that occur on the reactor Automatic main steam line isolation failure, when MSLI is manually initiated, AOVIII 's fail to automatically

close, manual cm will fail to automatically "B" train CREV's fails to automatically SRO enters EXPECTED STUDENT 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 INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT EVENTS 7, 8, & 9: (continued)

SI automatically actuated 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 AE bus remains energized from EDG 2-1 and DF bus remains energized from offsite power. Check SI Status Crew checks ifSI is required A TC checks Cnmt press> 5psig A TC checks PRZR press < 1860 psig ATC/BOP checks Steamline press < 500 psig Crew detennines SI is Required; A TC 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 11 of23 BEAVER VALLEY POWER [ uiNSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 7, 8, & 9: (continued)

NOTE: Evaluation of BOP perfonning Attachment A-O.II begins on page 21. List of Attachment A-O.II Discrepancies:

MSLI failed to automatically 2SDS-AOVIIl

's, steam line drains failed automatically cm failed to automatically "B" train CREV's failed to ATC verifies SI System Status. Both 2CHS*P21A and P21B pumps running. HHSI Flow indicated, Both LHSI pumps running. 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 SRO directs BOP to perfonn Attachment A-O.II. BVPS 2L8 NRC Scenario 1, Rev 120f23 BEAVER VALLEY POWER r=::JNSTRUCTIONAL GUIDELINES EVENTS 7, 8, & 9: (continued)

NOTE: Automatic main steamline isolation was inhibited.

Critical Task: E-O.P Crew manually actuates main steam line isolation before a Severe (orange path) challenge develops to either the Sub-criticality or Integrity CSF or before transition to ECA-2.1, whichever occurs first. Basis for Selection:

SAFETY SIGNIFICANCE

--Failure to close the MSIV s 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." PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE ATC checks RCS Tavg stable at or trending to 547°F RCS temperature

< 547°F and dropping due to

A TC verifies no steam release is occurring.

Safety Injection flow. (Condenser steam dumps closed)

A TC verifies Reheat steam is isolated.

ATC reduces total feedflow to minimize C/D. Crew determines cooldown is continuing and determines SLI is required.

If not previously actuated, BOP manually initiates MSLI and closes 2SDS-AOVl11

'so 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 INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT EVENTS 7,8, & 9: (continued)

NOTE: When the crew recognizes Containment pressure has exceeded 11 psig and manually initiates CIB, the crew will shutdo'vvn all RCP's due to loss of 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 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 Block valves -AT LEAST ONE OPEN ATC checks ifRCPs should be stopped DIP between RCS pressure and highest SIG pressure NOT LESS THAN 205 PSID Criteria for stopping is not met -Leaves RCPs running based upon DP requirements.

A TC/BOP checks if any SIGs are taulted

Pressures in all SIGs -ANY DROPPING IN AN 'UNCONTROLLED MANNER OR ANY SIG Crew determines "c" SIG is faulted. SRO transitions to E-2. BVPS 2L8 NRC Scenario 1, Rev 14of23 BEAVER VALLEY POWER r INSTRUCTIONAL GUIDELINES EbANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE EVENTS 7,8, & 9: (continued) "B" Train CREV's automatic failed requiring the crew to All commands Failure ofMSLI should have recognized by this "C" S/G pressure is lower than "A" & "A" & "B" may be slowly lowering as due to the cooldown.

Crew should respond "Stable" for "A" & "B" "C" S/G pressure & level lowering.

A TC/BOP actuates CREVS Verifies the control room air intake and exhaust Dampers are CLOSED. Crew determines "B" Train CREV's failed to actuate, ATC/BOP manually actuates CREV's. SRO requests a BV-I operator to verifY proper Unit 1 CREVS actuation.

SRO directs ST A to Commence Control Room ventilation actions. Refer to Attachment A-2A. ATC/BOP verifies steamline isolation has occurred by checking all YELLOW SLI identified components are in the designated position. (previously verified)

BOP identifies "A" & "B" steam generator pressures are "Stable or rising". Crew identifies "C" S/G as faulted. BVPS -2L8 NRC Scenario 1, Rev 150f23 BEAVER VALLEY POWER INSTRUCTIONAL GUIDELINES PLANT STATUS / PROCEDURAL GUIDANCE EXPECTED STUDENT EVENTS 7,8, & 9: (continued)

Critical Task: E-2.A Crew isolates the faulted S/G and directs operator to close isolation valves operated from outside of the control room before transition out of E-2. Basis for Selection:

SAFETY SIGNIFICANCE

--Failure to isolate a faulted S/G that can be isolated causes challenges to CSFs beyond those irreparably introduced by the postulated conditions. Also, depending upon the plant conditions, it could constitute a demonstrated inability by the crew to 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 isolates the faulted, "C" S/G as follows, Verifies FWI (previously verified via Attachment A-0.11) Closes AFW throttle valves on "C" S/G 2FWE*HCV100A and 100B Verifies Residual Heat Release Valve is closed. Directs field operator to isolate 2SVS-29 Isolates steam supply to turbine driven AFW pump, 2MSS*SOV105C and 105F Verifies closed, "C" S/G Atmospheric steam dump valve. Verifies S/G blowdown Verifies S/G Blowdown sample isolation valves, 2SSR

AOV117 A, B, C closed. BOP verifies PPDWST level is > 85 inches. BVPS -2L8 NRC Scenario 1, Rev 160f23 BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 7, 8, & 9 (continued)

NOTE: Due to timing, procedure progression and plant conditions (Adverse cnmt or not adverse), it is possible that the conditions may support direct transition to ES-l.l. If so, E-l steps on pages 18 and 19 are not applicable.

SRO determines transition to E-l, Loss of Reactor or Secondary Coolant is appropriak.

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 A TC 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]. A TC confirms RCS pressure is stable or rising. ATC reports Pzr level is < 17% [38% ADVERSE CNMT] Crew determines that current plant conditions do not support SI reduction.

BVPS -2L8 NRC Scenario 1, Rev 170f23 BEAVER VALLEY POWER 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.

A TC 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 180f23 BEAVER VALLEY POWER INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EVENTS 7, 8, & 9: (continued)

EXPECTED STUDENT RESPONSE 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 190f23 BEAVER VALLEY POWER 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]. A TC confirms RCS pressure is stable or rising. A TC 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. A TC 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 INSTRUCTIONAL Attachment A-O.ll 'Verification of Automatic Actions' perfonned as time & manpower pennit Critical Task E-O.P: Crew manually actuates main steam line isolation before a Severe (orange path) challenge develops to either the Sub-criticality or Integrity CSF or before transition to ECA-2.1, whichever occurs first Basis for Selection:

SAFETY SIGNIFICANCE

--Failure to close the MSIV s 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." BVPS -2L8 NRC Scenario 1, Rev AG 210f23 I PLANT sTAtus I PROCEDURAL GUIDANCE Ensure Reheat Stearn Isolation I .. EXPECTED STUDENT RESPONSE BOP perfonns Attachment A-O.ll, 'Verification of Automatic Actions' as follows: Checks both EDGs running Ensure reheat stearn isolation Verify 2MSS-MOVlOOA and B -CLOSED Reset reheater controller.

Check If main steamline isolation required CNMT pressure -> 7 Stearnline pressure -< 500 Stearnline pressure high rate of change -100 PSIG DROP IN 50 SECONDS Detennines CNMT pressure is > 7 PSIG and Manually actuates stearnline isolation by depressing all 4 SLI pushbuttons (BB-C) Verifies SLI by checking all YELLOW SLI LIT Identifies 2SDS-AOVIIIAl,Bl,CI, A2,B2,& C2 all failed to close. Manually closes all valves.

BEAVER VALLEY POWER INSTRUCTIONAL GUIDELINES Attachment A-O.ll -BOP may have already opened 2CCS-AOV118 to cooling to the Station Air Critical Task E-O.E: Crew manually actuates at least the minimum required complement of containment cooling equipment before an Extreme (red path) challenge develops to the Containment CSF. Basis for Selection:

SAFETY SIGNlFICANCE

--Failure to manually actuate the minimum required complement of containment cooling equipment under the postulated conditions constitutes a "demonstrated inability by the crew to recognize a failure/incorrect auto actuation of an ESF system or component." BVPS -2L8 NRC Scenario 1, Rev AG PLANT STATUS I PROCEDURAL I**** EXPECTED STUDENT RESPONSE Establish domestic water system cooling to station air compressors; Opens 2CCS-AOVI18. Verifies at least 1 air compressor is running. 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.

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 BV-1 operator verifies CREVS actuation Service water established to RSS HX(s) BOP manually initiates CIB if ATC did not previously identify and initiate.

220f23 BEAVER VALLEY POWER L INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE Attachment A-O.ll-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 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 230f23

" 0 -A lppen d" IX D S cenano U F orm 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 Malf. No. Event Type Event Description No. (C) ATC, SRO N44 fails high, rods automatically step in. 1 (TS) SRO (R)ATC 2FWS-P21B trips/ reduce power to 52% 2 (e) BOP, SRO (TS) SRO Misaligned Rod 3 (M) ALL 2ReS*P21B locked rotor trip with Automatic Reactor trip 4 failure and 400 gpm SBLOeA. (e) BOP, SRO Automatic turbine trip failure 5 (M)ALL Loss of all auxiliary feed water, entry into FR-H.l 6 (e) BOP, SRO Failure of2FWS-P24, 2FWS-P21A and P21B (requires 7 secondary depressurization and use of condensate pump. (C) BOP, SRO 2HVS-FN204A and B trip, requires manual starting of at least 8 1 fan. 9 (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG*1021 , Revision 9 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 A TC 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 NUREG-1021, Revision 9 Supplement 1 FENoe Facsimile Rev. AG BEAVER VALLEY POWER INITIAL CONDITIONS:

72% Power, CBD = 180, Equilibrium Xe, MOL, 1140 PPM Boron, IC-219 ADDITIONAL LINEUP CHANGES STICKERS YCT -2FWE*P23A CS YCT -2SAS-C21B CS EOUIPMENT STATUS DATEITIME OOS 2FWE*P23A OOS 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ago 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 1. MOL Reactivity placard MONITOR SETUP ATC position -HIGH POWER display TECHNICAL SPECIFICATION(S) 3.7.5 condition B PROCEDURES NEEDED 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 INSTRUCTIONAL GUIDELINES Initialize IC 219, and establish initial plant conditions.

Insert the following per the Simulator Setup section of the HTML File for this scenarIO:

PRELOAD COMMANDS TRGSET 1 'JPPLP4(1)'

IMF RCS02B (1 0) 400 30 IRF LOA-HIVOSS (0 0) 1 IMF PMP-CAS004 (0 0) 1 IMF EHC08A (0 0) TRGSET 2 'OAFWT22 . SO' IFR LOA-AFW022 (2 0) 1 IMF VLV -CFW027 (0 0) 0 IMF PMP-AFW002 (1 IS) 2 TRGSET S 'JP760PT(2)

= 1 .AND. FNISPR(I)

<= 62' IMF CRF03-F6 (S 0) 1 IMF PPLOIA (0 0) 0 IMF PPLOIB (0 0) 0 IMF PPLI0A (0 0) 0 IMF PPLI0B (00) 0 lOR XClI04ST (0 0) OFF TRGSET 8 'OCFWP21B

>= 0.6 . AND. XClI046T = l' TRG 8 'IMF PMP-CFWOOS (0 0) 2' IMF PMP-MSC036 (1 0) 1 TRGSET 4 'XBSI071T l' TRG 4 'DMF PMP-MSC036' IMF PMP-MSC037 (10) 1 TRGSET 6 'XBSI083T l' TRG 6 'DMF PMP-MSC037' BVPS -2L8 NRC Scenario 2, Rev AG PLANT STATUS I PROCEDURAL GUIDANCE Reactor plant at 72% power, MOL, Xe, RCS boron = 1140 PPM, CBD 180 Inserts all pre-loads required to support Set trigger 1 on reactor 400 gpm LOCA on Rx 2FWE*P23A breaker racked 2SAS-C21B Turbine fails to auto trip, manual Set trigger 2 on 2FWE*P22 2FWE*P22 trips during Prevent 2FWS-P24 start, FR-H.l 2FWE*P23B trips 15 seconds after reactor Trigger 5 on FWS-P21B trip and pwr < CBD rod F06 movable gripper coil Prevent AUTO Rx Trip TRN Prevent AUTO Rx Trip TRN Prevent AUTO MSLI TRN Prevent AUTO MSLI TRN 2FWS-P21A failure to Set trigger 8 on FWS-P21B start attempt 2FWS-P21B, Trip after 2nd motor 2HVS*FN204A trips on Rx TRG 4 when 2HYS*FN204A CS taken to 2IIVS*FN204A 2HVS*FN204B trips on Rx TRG 6 when 2HYS*FN204B CS taken to 2HVS*FN204B 40f23 EXPECTED STUDENT BEAVER VALLEY POWER 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 CTNSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EVENT I: N-44 fails high Rods automatically step inward in response to IMF NIS03D (0 0) 200 15 N-44 failure. Crew enters AOP 2.1.3 for Inappropriate Rod motion. SRO enters AOP 2.2.1 C to address failed NI channel. EXPECTED STUDENT RESPONSE ATC reports unexpected alarms and rod ATC verifies no load rejection in progress and Rod control to manual to stop the rod Crew removes N-44 from Within 1 hr, verifies P-8, P-9, & P-IO interlocks required state for 72% Within 72 hrs, trips nuclear bistables by control power fuses from Drawer A for A TC verifies Control rod group selector sw in BOP verities Bypass feedwater control valves BOP turns Rod Stop Bypass switch for N44 on Rack N50 to ATC verifies Status light for Overpwr Rod Bypass for N44 is Crew verifies Rx power is > BOP determines all PR channel upper and detector inputs to QPTR are BOP turns "Comparator Channel Defeat Switch" NIS rack N371N46 to N44 ATC ensures VB recorders are selected to BVPS -2L8 NRC Scenario 2, Rev AG 60f23 BEAVER VALLEY POWER CINSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE After removing Rod block, A TC 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 INSTRUCTIONAL GUIDELINES EVENTS 2 &3: 2FWS-P21B tripsl Movable gripper failure on Rod F6 when < 62%. IMF PMP-CFW005 (0 0) IMF CRF03-F6 (5 0) 1 Continue with next event at LE discretion BVPS -2L8 NRC Scenario 2, Rev AG PLANT STATUS I PROCEDURAL GUIDANCE IMMEDIATE PLANT RESPONSE:

Feed flows drop, S/G levels decrease, Main regulating valves A6-9E, tOE, lIE S/G 21A(B)(C) Deviation From SRO enters AOP When < 62% power, rod F6 will start "ratchet" in on each rod After plant is stable and S/G levels recovering, SRO enters AOP 2.1.8 to address misaligned 80f23 EXPECTED STUDENT Crew detennines that 2FWS-P2IB has SRO directs an immediate power reduction to < BOP depresses 1 st STG IN PB then lowers turbine load at 5%/minute rate by,

Adjusting "setter" to:S 50% power equivalent.

Depressing "GO" A TC inserts control rods lli'1d initiates boration for an expected 20% power reduction opening 2CHS*MOY350 and starting the "A" Acid BOP verifies all available pumps are Starts ATC identifies rod misalignment, stops control rods and continues BOP verifies steam flow is less than available flow and that S/G levels are trending to SRO identifies TS 3.1.4, Condition B, as for the misaligned SRO identifies TS 3.4.1 for BEAVER VALLEY POWER [ INSTRUCTIONAL GUIDELINES EVENTS 4, 5, 6, 7 & 8: 2RCS-P21B locked rotor with automatic reactor trip failure, trip failure and 400 gpm IMF RCP05B (0 0) CRITICAL TASK -E-O.A: Crew manually trips the reactor from the Control Room before performing the mitigation strategy of FR-S.l. Basis for Selection:

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 PLANT STATUS I PROCEDURAL GUIDANCE IMMEDIATE PLANT RESPONSE:

A5-2G, 113 Reactor Coolant Pump Loop Flow Low Reactor Trip SRO enters Automatic reactor trip EXPECTED STUDENT ATC reports 2RCS-P21B has tripped and 1 st out annunciator is in without an automatic reactor trip. SRO directs ATC to manually trip the reactor ATC and BOP commence lOA's ofE-O. ATC verifies Reactor trip after manually tripping reactor from either BB-B or BB-A

A5-6D -LIT.

Power range indication is < 5%.

Neutron flux is dropping.

90f23 BEAVER VALLEY POWER IN§IRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EVENTS 4, 5, 6, 7 & 8: (continued)

Automatic turbine trip failure. Critical Task: E-O.Q Crew manually trips the main turbine before a Severe (orange path) challenge develops to either the criticality or the Integrity CSF or before transition to ECA-2.1, whichever occurs first. 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." EXPECTEDSTUDENTRESPONSE BOP verifies Turbine trip did NOT occur Throttle OR Governor valves NOT closed. Main Generator output brks -Not open. Exciter Circuit breaker -not open. BOP manually trips the turbine, then verifies; 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 2, Rev 100f23 BEAVER VALLEY POWER INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EVENTS 4, 5, 6, 7 & 8: (continued)

SI automatically actuated NOTE: SI will be required due to 400 gpm SBLOCA, depending on timing, ifSI has not actuated, the crew may initially enter ES-O.l or may preemptively actuate SI at this time. Check SI Status Crew checks if SI is required A TC checks Cnmt press> 5psig A TC checks PRZR press < 1860 psig ATC or BOP checks Steamline pressure < 500 pSlg Crew determines SI is Required; ATC manually actuates SI by turning both trains' control switches.

A TC/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 11 of23 BEAVER VALLEY POWER INSTRUCTIONAl..

GUIDEl..INES-r EVENTS 4, 5, 6, 7 & 8: (continued)

NOTE: PORV's may lift several times during this transient due to natural circulation being established while Safety Injection flow is occurring.

With WR levels> 14%, PORV's opening are not due to Loss of Heat Sink; Bleed and Feed is not required.

PLANT STATUS I PROCEDURAL SRO recognizes that AFW flow cannot be established and enters FR-H.I EXPECTED STUDENT BOP verifies AFW System status Motor-driven AFW Pumps -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. A TC checks if secondary heat sink is required by:

Verifying RCS press is > any non-faulted S/G. w RCS Hot leg temperatures>

350°F. Crew checks ifRCS Bleed and Feed should be initiated. BOP verifies Wide Range level in at least 2 SIG's is > 14%. A TC verifies Pzr pressure is < 2330 psig. SRO notifies crew that this is a continuous action step. BOP checks Primary Plant Demineralized Water storage tank level is > 85 inches. BVPS 2L8 NRC Scenario 2, Rev 120f23 BEAVER VALLEY POWER r INSTRUCTIONAL EVENTS 4, 5, 6, 7 & 8: (continued)

ROLEPLAY:

When directed to investigate AFW pump status locally, wait 3 minutes then report: 2FWE*P23B is not running, nothing obvious wrong at pump. 2FWE*P22 is not running due to the trip throttle valve linkage rod being broken. dispatched to DF switchgear, wait 2 minutes then report that overcurrent relay 51-VF218 is tripped on ACB 2F18 for 2FWE*P23B.

PLANT STATUS I PROCEDURAL EXPECTED STUDENT RESPONSE Crew tries to establish AFW flow to at least 1 S/G. ATCIBOP verifies S/G Blowdown and blowdown sample lines are isolated.

Crew confirms * "A" motor-driven pump is OOS * "B" motor-driven pump has tripped

Turbine-driven pump tripped on startup.

All AFW throttle valves are open. SRO continues to try to restore AFW flow while continuing in procedure.

BOP confinns AFW flow is not> 340 gpm. 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. A TC/BOP resets;

SI signal both trains

FWI signal -both trains. A TC/BOP opens all Feedwater CMNT isol valves, 2FWS*HYV157A, B, C. BVPS -2L8 NRC Scenario Rev AG 13 of23 BEAVER VALLEY POWER INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EVENTS 4,5,6,7 & 8: (continued) 2FWS-P24 will not start due to failure of recirculation valve, 2FWR-FCV155 to open. NOTE: 2FWS-P21A will not start. Crew may not attempt to start P21 B since it had previously tripped, if the crew does attempt a start -it will trip immediately upon 2 nd motor start. EXPECTED STUDENT RESPONSE J BOP attempts to start the S/G Startup Feed pump by; Verifying 2CNM-DCVIOO is open Placing CS for 2FWS-P24 to start and hold untiI2FWR-FCVI55 opens. BOP recognizes failure of2FWR-FCV155 to open which prevents 2FWS-P24 from starting.

BOP attempts to start a main feed pump. 2FWS-P21A start attempt unsuccessful 2FWS-P21 B starts but immediately trips. A TC depressurizes the Res to < 1950 psig hy manually opening 1 PZR PORV. A TC closes PORV when pressure reduces to < 1950 pSlg. possible, A TC restores normal charging by; Opening 2CHS*MOV31 0 Opening 2CHS*MOV289 Adjusting 2CHS*FCV122 to maintain PZR level. A TC blocks Low Steamline Pressure SI and Low Pressurizer Pressure SI signals. BVPS -2L8 NRC Scenario 2, Rev of23 BEAVER VALLEY POWER INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EVENTS 4, 5, 6, 7 & 8: (continued)

ROLE PLAY: when dispatched with Attach A-l.lO, wait 2 minutes then call in that you are in position at MCC to de-energize valves at his direction lAW Attach A-I.] O. Report back verification of local valves as necessary.

Booth instructor NOTE: As directed, de-energize MOVI50AlB.

IMF VL V-CFW043 (0 0) 0 IMF VL V-CFW044 (0 0) 0 Critical Task: FR-H.1.A Crew establishes feedwater flow into at least one S/G before RCS feed and bleed is required.

Basis for Selection:

SAFETY SIGNIFICANCE

--Failure to establish feedwater flow to any S/G 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 EXPECTED STUDENT RESPONSE 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 Press mode. Gradually raising steam dump rate so as to NOT cause a high rate MSLI. When Tavg approaches/less than 541°F, defeats Tavg interlock.

Using Attachment A-LlO, Crew coordinates with a field operator to open and de-energize at least 1 main feed pump discharge valve. BOP begins fceding S/G's by opening the Bypass Feed regulating valves and verifies that either Core Exit TC's are S/G Wide Range levels are rising. BOP verifies CETC are dropping and WR S/G levels arensmg.

BEAVER VALLEY POWER INSTRUCTIONAL GUIDELINES EVENTS 4, 5, 6, 7 & 8: (continued) Evaluation of BOP Attachment A -0.11 begins on page PLANT STATUS I PROCEDURAL GUIDANCE SRO returns to E-O, Step 8 lAW FR-H-l, step l!.b. List of Attachment A-O.II Discrepancies:

Discrepancies:

NONE RCS temperature

< 547°F and dropping due to Safety Injection flow and Feedwater ( condensate) flow. CIB not actuated at this time. EXPECTED STUDENT RESPONSE Feedwater flow now verified.

SRO directs BOP to perfonn Attachment A-O.1!. ATC checks RCS Tcold stable at or trending to 547°F A TC verifies no steam release is occurring. (Condenser steam dumps closed) A TC verifies Reheat steam is isolated. ATC reduces total feed flow to minimize CID. Crew detennines cooldown is continuing and verifies SLI has previously occurred.

ATC checks recirc spray pumps NONE RUNNING A TC 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 Block valves AT LEAST ONE OPEN BVPS -2L8 NRC Scenario 2, Rev 160f23 BEAVER VALLEY POWER INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EVENTS 4, 5, 6, 7 & 8: (continued)

EXPECTED STUDENT RESPONSE 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 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 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 170f23 BEAVER VALLEY POWER INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EVENTS 4, 5, 6, 7 & 8: (continued)

SRO transitions to E-l. EXPECTED STUDENT RESPONSE 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. A TC 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.

A TC 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 180f23 BEAVER VALLEY POWER 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 190f23 BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 4, 5, 6, 7 & 8: (continued)

NOTE: Due to timing, procedure progression and plant conditions (Adverse cnmt or not adverse), it is possible that the conditions may support direct transition to ES-J.l at this time. 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 ATC ehecks PORV's and block valves.

Power to block valves -A V A1LABLE

PORVs-CLOSED

Block valves -AT LEAST ONE OPEN Crew checks if S1 Flow should be Reduced A TC 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%. A TC confirms RCS pressure is stable or rising. A TC confirms Pzr level is > 17% Crew determines that current plant conditions support S1 reduction.

BEAVER VALLEY POWER INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT Attachment A-O.ll 'Verification of Automatic Actions' performed as time & manpower permit Ensure Reheat Steam Isolation BOP may have already opened 2CCS-AOVl18 to cooling to the Station Air BOP performs Attachment A-O.ll, 'Verification of Automatic Actions' as follows: Checks both EDGs running Ensure reheat steam isolation Verify 2MSS-MOVI OOA and B -CLOSED Reset reheater controller.

Check If main steamline isolation required CNMT pressure -> 7 Steamline pressure -< 500 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. Establish domestic water system cooling to station air compressors; Opens 2CCS-AOVllS. 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 210f23 BEAVER VALLEY POWER [m INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE Attachment A-O.ll -

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 220f23 SEAVER VALLEY POWER INSTRUCTIONAL GUIDELINES r PLANT STATUS / PROCEDURAL GUIDANCE Attachment A-O.ll (continued)

Attachment A-O.ll -COMPLETE Discrepancies:

NONE EXPECTED STUDENT RESPONSE 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 Verify Power To Both AC Emergency Busses Restore power as required Upon Completion, Report Any Discrepancies to SRO. BVPS -2L8 NRC Scenario 2, Rev 230f23 A d' IX 0 S .cenano 0 tr u me F orm 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 Turnover:

Maintain steady state power at 100%, 2FWE*P23A OOS, 2SAS-C21B Critical Tasks:

1. E-O.O Close CNMT isolation 2. E-1.C Stop RCP's 3. FR-S.l.c Insert RCCA's Malf. No. Event (1) ATC, SRO 1 (TS) SRO (N)ATC, SRO 2 (R) ATC 3 (1) ATC, SRO (C) BOP, SRO 4 (C) ATC, SRO 5 (TS) SRO (M) ALL 6 (M)ALL 7 (C) BOP, SRO Event Description 2RCS*LT459 fails low. Restore letdown to service Valve position limiter failure causes load rejection with rod malfunction, A TC required to insert negative During load rejection, "A" Main Feed Regulating controller holds valve in position, BOP required to control "A" S/G 2RCS*PT445 fails high, 2 PORV's open, 2RCS*PCV456 to 18% open with Block valve failed open, requiring crew manually trip the ATWS, crew enters 2000 gpm SBLOCA on return to Train B CIA failure with 2CHS*MOV378 failing to auto (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*L T459 will fail low causing letdown to automatically The crew will enter the Instrument failure procedure to address the failed channel and place the channel in service. The US will determine appropriate Tech Spec After the alternate channel is placed in service, the crew will restore normal letdown to When letdown has been restored, the valve position limiter will fail causing a load rejection with an Rod malfunction requiring the A TC to manually insert control During the load rejection, the "A" Main feed regulating valve will fail to control in auto (the valve remain in its 100% power position), The BOP will be required to recognize the malfunction and control the "A" S/G Once the plant has stabilized, a RCS control pressure transmitter, 2RCS*PT445 will fail high, causing PORV's to open, 2RCS*PCV456 will stick at 18% open, with the block valve failing to close. The will address PORV Tech Spec. RCS pressure will continue to slowly decrease requiring the SRO to the crew to manually trip the reactor and enter The reactor will fail to trip from the control room, the SRO will transition to FR-S.l and the crew dispatch an operator to locally trip the Rx. After the reactor is locally tripped, the crew will return to 1 minute after the reactor is locally tripped, a 2000 gpm LOCA will occur on the "A" loop, the crew transition to E-l. The crew will be required to recognize that RCS I Secondary pressure DP are met to require that the RCP's be manually Train "B" CIA will fail to actuate along with 2CHS*MOV378 failing to auto close on the Train "A" The scenario will be terminated after the crew transitions to 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 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 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 PROCEDURES NEEDED 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 30f23 SEAVER VALLEY POWER r INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT Initialize IC 214, and establish initial plant conditions.

Insert the following per the Simulator Setup section of the HTML File for this scenano: PRELOAD COMMANDS IMF PPLOIA (0 0) I IMF PPLOIB (0 0) I IMF PPL08B (0 0) 0 TRGSET I 'XA4I106C' IMF VLV-SEAOIS-(O

0) I TRG I 'DMF VL V-SEAOIS' TRGSET 10 'JMLEHC6' TRG 10 'SET JWSF478 AUTO=TRUE' IMF CNH-CFWIOC (10 4S) IS 0 0 IMF PPL02A (8 120) 1 IMF PPL02B (8 12S) 1 IRF LOA*CRF007 (8140) I IRF LOA-CRF008 (8 14S) I TRGSET 6 'RRCH4S6 > 0.0' IMF VLV-RCS034A (6 0) 1800 TRGSET 7 'MCRFNS(41)

<= 214' IMF CRFOIA (7 0) 1 IMF VLV-RCSOI2 (0 0) 1 IMF RCS02A (8 180) 2000 30 Reactor plant at 100%power, MOL, Equilibrium Xe, RCS boron =1044 PPM, ARO. Inserts all pre-loads required to support the scenario Train A RTB failed closed Train B RTB failed closed Train B auto CIA actuation failure Set trigger 1 on 2CHS*MOV378 switch to close 2CHS*MOV378 failed open 2CHS*MOV378 closes manually Trigger 10 = VPL failure 2FWS*FCV478 controller failed as is in auto 2FWS*FCV478 controller oscillation during load rejection.

Train A trip BKR open Train B trip BKR open Trip A rod drive MG set Trip B rod drive MG sct Set trigger 6 for PORV 456 position>

0 2RCS*PCV456 PRZR PORV fails to 18% open Set trigger 7 for Rods < 214 steps Inhibit Auto Rod insertion 2RCS*MOV536 failed open 2000 gpm loop A LOCA 1 min after Rx tripped BVPS -2L8 NRC Scenario 4, Rev AG 40f23 BEAVER VALLEY POWER [ 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 place the simulator to RUN commence the BVPS -2L8 NRC Scenario 4, Rev AG 50f23 BEAVER VALLEY POWER INSTRUCTIONAL GUIDELINES EVENTS 1 &2: Pressurizer level transmitter 2RCS*LT459 fails low. IMF XMT-RCS019A (0 0) 04 PLANT STATUS I PROCEDURAL GUIDANCE IMMEDIATE PLANT A4-1B, PZR Control LvI A4-1C, PZR Control LvI Dev A4-1G,PZR Control Htr Group A4-2G, PZR BIU Htr Group Auto A2-3E, Charging Flowpath 2RCS-LI459 indicates 2CHS*FCY122 opens to increase Letdown isolates, 2CHS*LCY460B and AOY200A & B All PZR heaters SRO enters 20M-6.4.IF , attachment

1. EXPECTED STUDENT A TC reports multiple unexpected pressurizer alarms. ATC identifies 2RCS*LT459 failed low and places 2CHS*FCY122 in manual to control PZR level. SRO provides a control band and Rx trip criteria of 14% 10w/85% high for manual PZR level control. BOP begins referring to ARP's. 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 r INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE C EXPECTED STUDENT RESPONSE EVENTS 1 & 2: (continued)

SRO directs ATC to restore letdown lAW 7.4.AB. Proceed with next event at LE discretion ATC restores LID flow. 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. BVPS -2L8 NRC Scenario 4, Rev AG 70f23 BEAVER VALLEY POWER INSTRUCTIONAL GUIDELINES EVENTS 3 &4: Turbine Runback due to Valve Position limiter failure, "A" main feed reg valve auto controller holds val ve in position, Control rods step in until 214 steps then quit moving in Auto. IMF EHC06 (0 0) 79 0 ASIS Continue with next event at LE discretion BVPS 2L8 NRC Scenario 4, Rev AG PLANT STATUS I PROCEDURAL GUIDANCE IMMEDIATE PLANT Rods begin stepping Megawatts RCS temperature and pressure rise Rods stop moving at 214 As power reduces "A" S/G level SRO enters AOP 2.35.2 EXPECTED STUDENT IA W Immediate Operator Action of AOP 2.1.3, ATC announces unexpected rod motion, verifies megawatts decreasing and announces load rejection.

ATC checks Rods are inserting in AUTO and Tavg is dropping to Tref When rods quit moving A TC 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. 80f23 BEAVER VALLEY POWER INSTRUCTIONAL GUII5EiJNES-1 EVENTS: 2RCS*PT445 fails high, 2 open, 2RCS*PCV456 fails to open with Block valve failed requiring crew to manually trip IMF XMT-RCS031A (0 0) 2500 Due to dynamic nature of event, followup question regarding TS may be EVENTS 6, 7, & 8 ATWS 2000 gpm SBLOCA when Rx is tripped Train "B" CIA actuation failure with failure of2CHS*MOV378 to auto close. (all commands preloaded)

PLANT SillOS/PROCEDURAL GUIDANCE IMMEDIATE PLANT RESPONSE:

2 PORV's initially open, 456 sticks at 18% Other PORV will automatically close pressure reduces to 2185 RCS pressure continues to SRO enters SRO enters FR-S.l BVPS 2L8 NRC Scenario 4, Rev AG 90f23 EXPECTE[)

STUDENT RESPONSE . ATC reports multiple unexpected pressurizer ATC identifies 2RCS*PT445 has failed high and 2 PORV's have ATC reports that PORV, 2RCS*PCV456 failed automatically close on low ATC attempts to close 2RCS*PCV456, remains at dual ATC attempts to close block valve, ATC reports 2RCS*MOV536 will not SRO recognizes TS applicability for an PORV and Block TS 3.4.11, Conditions Band Crew determines failure will not support normal SRO directs crew to manually trip and perform for A TC attempts a manual reactor trip, reports failure/ A TWS SRO directs operators to perform lOA's of FR-S.l , implements FR-S.1 at step 1 ofE-O.

BEAVER VALLEY POWER [ INSTRUCTIONAL GUIDELINES EVENTS 6,7, & 8 (continued)

Critical Task FR-S.1.C:

Crew inserts negative reactivity into the core by inserting RCCAs before completing the immediate action steps of FR-S.1. 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)." PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE Crew performs lOA's ofFR-S.l.

BOP manually trips Turbine. A TC manually begins inserting rods. BVPS -2L8 NRC Scenario 4, Rev AG 10 of23 BEAVER VALLEY POWER INSTRUCTIONAL GUIDELINESuul PLANT STATUS I PROCEDURAL GUIDANCE r EXPECTED STUDENT RESPONSE EVENTS 6, 7, & 8 (continued)

NOTE: Dependent upon crew response, SI may not be actuated at this time, if so the crew will initiate Emergency Boration flow by: Opening 2CHS*MOV350 Starting "A" Boric Acid pump Verifying>

30 GPM flow Adjusting 2CHS*FCV122 to establish>

40 GPM flow. BOP verifies AFW BOP manually starts 2FWE*P23B motor-driven BOP manually opens 2MSS*SOV105A-F to Turbine-driven AFW pump, BOP verifies all AFW throttle valves are BOP verifies AFW Crew initiates Emergency Boration Flow Verifying at least 1 charging pump is Checking Safety Injection is actuated and Emergency boration is not required due to SI BOP verifies HHSI ATC verifies RCS pressure is < 2330 BVPS 2L8 NRC Scenario 4, Rev AG 11 of23 BEAVER VALLEY POWER INSTRUCTIONAL GUIDELINES

_uul PLANT STATUS I PROCEDURAL GUIDANCE EVENTS 6, 7, & 8 (continued)

ROLEPLAY:

When requested to open the reactor trip breakers & trip the rod drive MG set 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 IMF PPL02B (8 IRF (8140) IRF LOA-CRF008 (8145) (all commands preloaded)

ROLEPLAY:

When all breakers are open, report actions to the control room. Crew continues in FR-S.l after dispatching an operator to locally trip the Unit 2 reactor. EXPECTED STUDENT RESPONSE Crew alerts plant personnel by;

Sounding the standby alarm.

Announcing a Unit 2 Rx trip w/o SCRAM.

Dispatching an operator to locally trip the Rx. BOP verifies turbine is BOP verifies 2MSS-MOVIOOA, B BOP depresses the RESET Pushbutton on Reheater A TC checks if SI is sr is actuated, first nine steps ofE-O have not BVPS -2L8 NRC Scenario 4, Rev AG 120f23 BEAVER VALLEY POWER [ INSTRUCTIONAL GUIDELINES EVENTS 6, 7, & 8 (continued)

NOTE: is a continuous action step, when the Rx is locally tripped the crew will return to this step and then transition back to E-O, Step 1. NOTE: Event 7, 2000 gpm SBLOCA will occur 1 minute after the Rx is locally tripped. (command preloaded)

PLANT STATUS I PROCEDURAL When the Rx is locally tripped. SRO returns to E-O, step 1. EXPECTED STUDENT ATC checks ifRx is subcritical:

Power range channels < 5%. IR channels negative startup rate. 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 13 of23 BEAVER VALLEY POWER INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT EVENTS 6, 7, & 8 (continued)

SI automatically actuated due to low pressurizer pressure from stuck open PORV. Check SI Status: 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. A TC verifies SI System Status: Both 2CHS*P21A and P21B pumps running.

HHSl Flow " Both LHSI pumps 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 140f23 BEAVER VALLEY POWER C INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT EVENTS 6,7, & 8 (continued) Evaluation of BOP Attaclunent A-OJ I begins on page SRO directs BOP to perfonn Attaclunent List of Attaclunent A-O.II Discrepancies: "B" Train CIA failed to actuate along with failure of2CHS*MOV378 failing to automatically close. Manual actuation successfuL RCS temperature

< 547°F and dropping due to Safety Injection flow. CIB not actuated at this time. SRO transitions to E-l ATC checks RCS Tavg stable at or trending to 547°F: A TC verifies no steam release is occurring. (Condenser steam dumps closed) ATC verifies Reheat steam is isolated. ATC reduces total feedflow to minimize C/D. ATC checks recirc spray pumps NONE RUNNING. A TC verifies PZR isolated: PORVs CLOSED ATC reports PORV 2RCS*PCV456 won't close and block valve 2RCS*MOV536 also has failed to close. A TC 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 150f23 BEAVER VALLEY POWER INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT EVENTS 6, 7, & 8 (continued)

Critical Task E-1.C: Crew trips aU RCPs when RCS to highest SG DIP criteria is exceeded and SI flow verified prior to exiting procedure E-l 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." A TC checks if RCPs should be stopped DIP between RCS pressure and highest S/G pressure -NOT LESS THAN 205 PSID [220 PSID ADVERSE CNMT] DIP Criteria for stopping RCPs is met. ATC shuts down ALL RCP's after verifying HHSI flow. A TC 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 COMPLETEL Crew determines no S/G's are faulted. BVPS -2L8 NRC Scenario 4, Rev 160f23 BEAVER VALLEY POWER INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE r EXPECTED STUDENT RESPONSE EVENTS 6,7, & 8 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 170f23 BEAVER VALLEY POWER r INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT EVENTS 6, 7, & 8 (continued)

NOTE: Due to timing, procedure progression and plant conditions, it is possible that the conditions may support shutdown of the LHSI pumps at this time. Crew checks if SI Flow should be Reduced. A TC 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. A TC verifies no Quench or Recirc Spray pumps A TC resets SI both A TC resets CIA both A TC checks if LHSI pumps should be ATe verifies RCS pressure is > 225 psig [250 ADVERSE CNMT] and NOT stable or ATC leaves both LHSI pumps BVPS -2L8 NRC Scenario 4, Rev AG 180f23 BEAVER VALLEY POWER INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT 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 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 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.

A TC 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 [ INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT Attachment A-O.ll 'Verification of Automatic Actions' perfonned as time & manpower pennit. Ensure Reheat Steam Isolation. BOP may have already opened 2CCS-AOV118 to cooling to the Station Air BOP perfonns Attachment A-O.ll, 'Verification of Automatic Actions' as follows: Checks both EDGs running. Ensure reheat steam isolation: Verify 2MSS-MOVlOOA and B -CLOSED. Reset reheater controller.

Check If main steamline isolation required CNMT pressure -> 7 Steamline pressure -< 500 Steamline pressure high rate of change 100 PSIG DROP IN 50 If steamline isolation IS required, Verifies SLI by checking all YELLOW SLI marks LIT. If steamline isolation is NOT required continues on. Establish domestic water system cooling to station air compressors; Opens 2CCS-AOV118. 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 210f23 BEAVER VALLEY POWER [ INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE Attachment A-O.ll-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 LIT. BVPS 2L8 NRC Scenario 4, Rev 220f23 BEAVER VALLEY POWER INSTRUCTIONAL GUIDELINES Attachment A-O.ll-(continued)

Critical Task E-O.O Crew closes Cnmt isolation valves such that at least one valve is closed on each critical phase A penetration before the end of the scenario.

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.

Attachment A-O.ll -COMPLETE PLANT STATUS / PROCEDURAL GUIDANCE "B" Train CIA failed to 2CHS*MOV378 failed to auto Manual actuations "B" Train CIA failed to 2CHS*MOV378 failed to auto Manual actuations EXPECTED STUDENT RESPONSE 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 marks-Verify Power To Both AC Emergency Busses Restore power as required.

Upon Completion, Report Any Discrepancies to SRO. BVPS -2L8 NRC Scenario 4, Rev 230f23

, 0 tr A d'IX D s cenano u me F orm 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 Turnover:

Maintain steady state power at 100%, 2FWE*P23A OOS, 2SAS-C21B 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. (I) ATC, SRO 2RCS*PT444 drifts Jow, requires ATC to manually control 1 RCS pressure. (TS) SRO 2FWS-LT485 fails high 2 (C) BOP, SRO Voltage regulator failure causes main generator over 3 excitation, requires BOP to tum voltage regulator off and manually lower excitation. (C) ATC, SRO 25 gpm RCS leak on "A" Loop. 4 (TS) SRO (M)ALL 500 gpm RCS leak on "A" Loop.5 (C)ATC, SRO 2RCS-PCV455D fails open on Rx trip, requires ATC to close 6 block valve. (C) BOP, SRO AF\V malfunctions, 2FWE*P23A OOS on turnover, 7 2FWE*P23B auto start failure, requires BOP to manually start. 2FWE*P22 running with reduced flow << 340 gpm) (C) ATC, SRO Auto SIS inhibited, requires ATC to manually actuate SIS. 8 (C) ATC, SRO 2SIS*MOV867's fail to open on SIS actuation signal, ATC 9 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 A TC 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 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 SHIFT TURNOVER INFORMATION

1. 100% power, BOL, Equilibrium Xe, shift goal is to maintain steady state 100% power conditions.

SCENARIO SUPPORT MATERIAL REQUIRED 1. BOL reactivity placard PROCEDURES NEEDED 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 em INSTRUCTIONAL llULlall.l

.."" IC 217, and establish initial plant conditions.

Insert the following per the Simulator Setup section of the HTML File for this scenano: PRELOAD COMMANDS TRGSET 1 'JPPLP4(l)'

IRF LOA-AFWOOI (0 0) 0.1 0 IMF PPL07B (0 0) 5 IRF LOA-HIV055 (0 0) 1 IMF PMP-CAS004 (0 0) 1 IMF VLV-RCS033A (10) 20 0 ASIS IMF PPL05A (0 0) 0 IMF PPL05B (0 0) 0 TRGSET 3 'JMLRCS2A

== 1 .AND. XBlI045P l' TRG 3 'IMF RCS02A (0 0) 500 0 asis IMF VLV-SIS069 (0 0) 2 TRGSET 6 'XA4I081 P' TRG 6 'DMF VLV-SIS069' IMF VLV-SIS070 (0 0) 2 TRGSET 7 'XA4I076P' TRG 7 'DMF VLV-SIS070' IMF VLV-SIS071 (00) 2 TRGSET 8 'XA4I094P' TRG 8 'DMF VLV-SIS071, IMF VL V -SIS072 (0 0) 2 TRGSET 9 'XA4I090P' TRG 9 'DMF VLV-SIS072' BVPS -2L8 NRC Scenario 5, Rev AG PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE Reactor plant at 100% power, BOL, Equilibrium Xe, RCS boron =1458 PPM, ARO. Inserts all pre-loads required to support the scenario Set trigger 1 on reactor trip 2FWE*P22 low flow (discharge valve throttled) 2FWE*P23B auto start failure 2FWE*P23A breaker racked out 2SAS-C21B OOS 2RCS*PCV455D fails to 20% open upon trip Train A auto SI actuation failure Train B auto SI actuation failure Set trigger 3 on 25 gpm leak and 2CHS*LCV460A CS to open. 500 gpm SBLOCA "A" Loop when LID begins to be re-established.

2SIS*MOV867 A failed closed Set trigger 6 on 2SIS*MOV867 A CS to open 2SIS*MOV867 A opens upon manual attempt 2SIS*MOV867B failed closed Set trigger 7 on 2SIS*MOV867B CS to open 2SIS*MOV867B opens upon manual attempt 2SIS*MOV867C failed closed Set trigger 8 on 2SIS*MOV867C CS to open 2SIS*MOV867C opens upon manual attempt 2SIS*MOV867D failed closed Set trigger 9 on 2SIS*MOV867D CS to open 2SIS*MOV867D opens upon manual attempt 40f25 BEAVER VALLEY POWER INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE [ EXPECTED STUDENT RESPONSE Assign shift positions SRO:

ATC:

BOP:________________

__ Conduct a shift turnover with oncoming operators.

Simulator Frozen until after shift turnover unless it needs to be run momentarily for an alignment change. When the shift turnover is completed, place the simulator to RUN and commence the scenario.

Simulator running. Crew assumes control of the Unit. BVPS 2L8 NRC Scenario 5, Rev AG 50f25 BEAVER VALLEY POWER r=JNsTRUCTIONAL GUIDELINES EVENT 1: Pressurizer Pressure control channel fails low IMF XMT-RCS030A (0 0) 1700240 Proceed with next event at BVPS -2L8 NRC Scenario 5, Rev AG PLANT STATUS I PROCEDURAL GUIDANCE IMMEDIATE PLANT RESPONSE:

2RCS-PT444 drifts low PZR htr grps A & D, Backup grps B & E tum on. Pzr htr Control grp C modulates high Spray valves, 2RCS*PCV455A

& 455B modulate closed. A4-1 E, PZR Control Press Dev High/Low A4-2G, PZR BIV Htr Group Auto On/Off SRO enters 20M-6.4.lF, Attachment 2 EXPECTED STUDENT RESPONSE A TC reports unexpected alarm, A4-1 E. ATC identifies 2RCS*PT444 failing low. A TC controls PZR pressure by operating Pressure controller in manual or manually individual PZR heaters and spray BOP refers to With Pzr htrs and spray valve control in Manual, establishes a control band and Rx trip criteria psig low I 2340 psig high for manual PZf SRO evaluates applicable TS 3.3.4 for Remote Shutdown Instrumentation Info SRO contacts Operations management and I&C of pressure transmitter 60f25 BEAVER VALLEY POWER r INSTRUCTIONAL GUIDELINES PLANT STATUS / PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENT 2: 21 B S/G Channel II level transmitter, 2FWS*LT485 fails high. IMF XMT-MSS006A (0 0) 10060 NOTE: No system response occurs on failure of a single channel due to median signal select feature. Continue with next event at discretion IMMEDIATE PLANT RESPONSE:

2FWS*LT485 fails high A6-10D, S/G 21B Level High/Low SRO enters 20M-24.4.1F, Attachment 1 BOP reports unexpected alarm, A6-1 OD BOP verifies actual S/G parameters, steam flow/feed flow and S/G level are stable. ATC refers to ARP. BOP reports failure of2FWS*LT485.

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. SRO contacts Operations management and notifies I&C of level transmitter failure. BVPS 2L8 NRC Scenario 5, Rev AG 70f25 BEAVER VALLEY POWER INSTRUCTIONAL GUIDELINES EVENT 3: Voltage Regulator Failure IMF GEN02 (0 0) 26 20 AS IS Continue with next event at LE discretion PLANT STATUS I PROCEDURAL GUIDANCE IMMEDIATE PLANT RESPONSE:

MUG Excitation increases Main Generator V ARS increase Main Generator Power Factor decreases (more lagging) A7-4C, Generator Field Forcing EXPECTED STUDENT RESPONSE BOP reports unexpected electrical BOP identifies voltage regulator A TC refers to BOP turns voltage regulator off and manually MUG excitation using exciter base adjust to lower V ARS to restore power factor. SRO provides BOP a control band for power factor of 0.9 to 1.0 lagging. SRO contacts Operations management and notifies maintenance of voltage regulator failure. BVPS -2L8 NRC Scenario 5, Rev AG 80f25 BEAVER VALLEY POWER CINSTRUCTIONAL GUIDELINES EVENT 4: 25 gpm leak on "A" RCS loop inside CNMT. IMF RCS02A (0 0) 25 0 0 NOTE: Due to dynamic nature of event, a followup question regarding applicable TS may be necessary.

BVPS 2L8 NRC Scenario 5, Rev AG PLANT STATUS I PROCEDURAL GUIDANCE IMMEDIATE PLANT RESPONSE:

PZR pressure begins decreasing.

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 plant leakage. EXPECTED STUDENT RESPONSE A TC reports indications of a RCS leak inside A TC confinns VCT / PZR level can be Crew checks ifleakage is Crew confinns CNMT radiation and humidity are consistent with pre-event A TC verifies RCS temperature is ATC checks 2CHS*FCV122 is in AUTO and level is NOT ATC places 2CHS*FCV122 in MANUAL and to maintain a constant PZR ATC checks VCT level ATC identifies VCT level is dropping at >

and reports to SRO that leak rate is > 10 gpm. SRO recognizt:s TS 3.4.13 Condition A, is applicable for unidentified leakage. 90f25 BEAVER VALLEY POWER INSTRUCTIONAL GUIDELINES nn] PLANT STATUS I PROCEDURAL GUIDANCE EVENT 4: (continued)

EVENT 5: 500 gpm SBLOCA on "A" RCS Loop NOTE: Command is preloaded to PZR level and pressure decreases occur when 2CHS*LCY460A is opened during lid restoration step of AOP 2.6.7 EXPECTED STUDENT RESPONSE 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. A TC 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; Adjusting 2CHS*FCY122 for 30-50 gpm flow. Verifying PZR level> 14%. Placing 2CHS*PCY145 in MAN & 50% open. Opening 2CHS*LCY460A and B Opening 2CHS* AOY200A and/or 200B/C. Adjusting 2CHS*PCY145 to 260 psig then returning to AUTO. When level is appro x at program, places 2CHS*FCY122 in AUTO. A TC reports degrading primary plant conditions.

BYPS -2L8 NRC Scenario 5, Rev AG 100f25

BEAVER VALLEY POWER INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT EVENTS 6, 7, 8, & (all preloaded to occur on the SI Auto actuation failure 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. SRO directs ATC to trip the reactor. 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 11 of25 BEAVER VALLEY POWER INSTRUCTIONAL GUIDELINES EVENTS 6,7,8, & 9: (continued)

Critical Task: E-O.D Crew manually actuates at least one train of SIS-actuated safeguards before transition to any ORP. Basis for Selection:

SAFETY SIGNIFICANCE

--Failure to manually actuate SI under the postulated conditions constitutes "misoperation or incorrect crew perfonnance that leads to degraded ECCS capacity.

II PLANT STATUS I PROCEDURAL GUIDANCE PORV failing to 20% open on the reactor trip reduce PZR pressure below Auto SI setpoint EXPECTED STUDENT RESPONSE Check SI Status. Crew checks if SI is required.

ATC checks Cnmt press> 5psig

A TC checks PZR press < 1860 psig

ATC! BOP checks Steamline press < 500 psig Crew detennines SI is Required based on PZR pressure being < 1860 psig. ATC manually actuates SI -both trains by turning Control switches (BB-A). A TC!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 INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EVENTS 6, 7, 8, & 9: (continued)

Critical Task: E-O.I Crew establishes flow from at least one high head ECCS pump before transition out of E-O. Basis for Selection:

SAFETY SIGNIFICANCE

--Failure to manually start at least one high-head ECCS pump under the postulated conditions constitutes "misoperation or incorrect crew perfonnance which leads 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." EXPECTED STUDENT RESPONSE A TC verifies SI System Status

Both 2CHS*P21A and P21B pumps running.

HHSI Flow indicated,

Both LHSI pumps running A TC notes zero HHSI flow, identifies MOV867 A, B, C & D all failed to open on the SIS actuation.

SRO directs ATC to align valves to establish flow. ATC manually opens 2SIS*MOV867 A, B, C, & D and confinns HHSI flow exists. BVPS -2L8 NRC Scenario 5, Rev AG 13 of25 BEAVER VALLEY POWER INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT Critical Task: E-O.F Crew establishes the minimum 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.1. 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" BOP verifies AFW System status Motor-driven AFW Pumps -NONE running Turb driven AFW Pump Stm Supply Isol Valves -OPEN AFW Throttle Vlvs -FULL OPEN Total AFW Flow -< 340 gpm BOP starts 2FWE*P23B and verifies total AFW flow is> 340 gpm. BVPS -2L8 NRC Scenario 5, Rev 140f25 BEAVER VALLEY POWER INSTRUCTIONAL GUIDELINES EVENTS 6, 7, 8, & 9: (continued) Evaluation of BOP Attachment A-O.II begins on page PLANT STATUS I PROCEDURAL GUIDANCE List of Attachment A-O.II SIS failed to automatically actuate on low 2SIS*MOV867A, B, C, & D all failed to on SIS actuation, successfully opened 2FWE*P23B failed to auto start, manual was RCS temperature

< 547°F and dropping due Safety Injection CIB not actuated at this EXPECTED STUDENT RESPONSE SRO directs BOP to perform Attachment A-O.II. ATC checks RCS Tavg stable at or trending to 547°F. A TC verifies no steam release is occurring. (Condenser steam dumps closed) A TC verifies Reheat steam is isolated. A TC reduces total feedflow to minimize C/D. ATC checks recire spray pumps NONE RUNNING BVPS -2L8 NRC Scenario 5, Rev 150f25 BEAVER VALLEY POWER INSTRUCTIONAL GUIDELINES EVENTS 6,7,8, & 9: (continued)

Critical Task: E-O.M Crew closes the upstream block MOV of the stuck open Pzr PORV prior to completion of the "Prz PORV check" step of E-O. Basis for Selection:

SAFETY SIGNIFICANCE

--Failure to close the block MOV under the postulated plant conditions constitutes "misoperation or incorrect crew performance which leads to degradation of any barrier to fission product release." In this case, the RCS fission-product barrier can be restored to full integrity simply by closing the 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." PLANT STATUS I PROCEDURAL EXPECTED STUDENT RESPONSE A TC verifies PZR isolated PORVs-CLOSED ATC reports PORV 2RCS*PCV455D indicates dual position and won't close. ATe closes block valve 2RCS*MOV537 to isolate stuck open PORV. A TC continues verifying PZR isolated Spray Valves -CLOSED Safety relief valves -CLOSED (use PSMS) PR T conditions

-CONSISTENT WITH EXPECTED VALVES Power to at least one block valve Block valves -AT LEAST ONE OPEN, 2 are open. 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 16 of25 BEAVER VALLEY POWER INSTRUCTIONAL GUIDELINES PLANT STATUS / PROCEDURAL GUIDANCE EXPECTED STUDENT EVENTS 6, 7, 8, & 9: (continued)

SRO detennines transition to E-1, Loss of Reactor or Secondary Coolant is appropriate.

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 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. BVPS -2L8 NRC Scenario 5, Rev 170f25 BEAVER VALLEY POWER INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EVENTS 6, 7, 8, & 9: (continued)

EXPECTED STUDENT RESPONSE 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. A TC 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 Crew determines no SIG's are faulted. BVPS -2L8 NRC Scenario 5, Rev 18of25 BEAVER VALLEY POWER [ INSTRUCTIONAL GUIDELINES PLANT STATUS / PROCEDURAL GUIDANCE EVENTS 6, 7, 8, & 9: (continued)

EXPECTED STUDENT RESPONSE 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 -A V AILABLE PORVs-CLOSED Block valves -AT LEAST ONE OPEN ATC reports power available to all block valves and block valves are PORV 2RCS*PCV455D was previously identified being stuck open and is isolated with block BVPS -2L8 NRC Scenario 5, Rev 190f25 BEAVER VALLEY POWER INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 6, 7, 8, & 9: (continued)

Crew checks if SI Flow should be Reduced A TC verifies RCS Sub cooling is greater than 41°F [59 OF ADVERSE CNMT] based on CETC's BOP confinns secondary heat sink available by >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; A TC verifies no Quench or Recirc Spray pumps are runmng. ATC resets SI -both trains. ATC resets CIA -both trains. A TC checks if LHSI pumps should be stopped. NOTE: Due to timing, procedure progression A TC 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 INSTRUCTIONAL GUIDELINES PLANT STATUS / PROCEDURAL GUIDANCE EXPECTED STUDENT EVENTS 6,7,8, & 9: (continued)

Check RCS and S/G Pressures BOP checks Pressure in all S/G NOT stable or rising. A TC 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 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 A TC to monitor nuclear instrumentation to ensure adequate Shutdown Margin. BVPS -2L8 NRC Scenario 5, Rev AG 21 of25 BEAVER VALLEY POWER 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 INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT Attachment A-O.ll 'Verification of Automatic Actions' performed as time & manpower permit Ensure Reheat Steam Isolation NOTE: BOP may have already pre-emptively opened 2CCS-AOVI18 to provide cooling to the Station Air compressors.

BOP performs Attachment A-O.11, 'Verification of Automatic Actions' as follows: Checks both EDGs running Ensure reheat steam isolation Verify 2MSS-MOVI OOA and B -CLOSED Reset reheater controller.

Check If main steamline isolation required CNMT pressure -> 7 Steamline pressure -< 500 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. Establish domestic water system cooling to station air compressors; Opens 2CCS-AOVl18. 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 230f25 BEAVER VALLEY POWER INSTRUCTIONAL GUIDELINES!

PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE Attachment A-O.ll-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 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 240f25 INSTRUCTIONAL GUIDELINES Attachment A-O.ll-(continued)

Critical Task: E-O.I Crew establishes flow from at least one high head ECCS pump before transition out of E-O. Critical Task: E-O.F Crew establishes the minimum 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. Attachment A-O.II -COMPLETE BEAVER VALLEY POWER STATION PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE Verify ESF Equipment Status SIS failed to automatically actuate on low PZR

Verify SI status by checking all RED SIS pressure.

marks-LIT 2SIS*MOV867 A, B, C,& D all failed to open on

Verify CIA by checking all ORANGE CIA SIS actuation, successfully opened manually.

marks -LIT

Verify FWI by checking all GREEN FWI marks LIT 2FWE*P23B auto start failed, required to be manually started. Verify Power To Both AC Emergency Busses Restore power as required Discrepancies:

Upon Completion, Report Any Discrepancies to SRO. SIS failed to automatically actuate on low PZR pressure.

2SIS*MOV867 A, 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

ML12299A280

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