ML12299A202

Draft Operating Exam (Sections a, B, and C) (Folder 2)

ML12299A202
Person / Time
Site:	Beaver Valley
Issue date:	08/03/2012
From:	Silk D M Operations Branch I
To:	Rudolph W J FirstEnergy Nuclear Operating Co
Jackson D E
Shared Package
ML12136A033	List: ML12142A240 ML12263A060 ML12298A500 ML12299A089 ML12299A110 ML12299A182 ML12299A202 ML12299A226 ML12299A229 ML12299A276 ML12299A280 ML12307A237 ML12314A266
References
0011-003-01-013, TAC MEU01850
Download: ML12299A202 (274)

Text

RTL#A5.640U 112-ADM-130 I.F04 Page 3 of9 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-007 JPM REVISION:

2 JPM TITLE: Perform An Estimated Critical Position Calculation KIA 2.1.23 (4.3/4.4)

TASK ID: 0011-003-01-013 JPM APPLICATION:

C8J REQUALIFICATION INITIAL EXAM D TRAINING D FAULTEDJPM

[::3:J ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION:

TYPE: ADMINISTERED BY: C8J Perform D Plant Site D Annual Requa] Exam D BVT D Simulate D Simulator D Initial Exam D NRC C8J D OJT/TPE 0 Other: D Training D Other: EVALUATION RESULTS Performer Performer SSN: Time Critical:

D Yes C8J No Allotted Time: 35 Minutes Actual Time: minutes JPM RESULTS: 0 0 SAT UNSAT (Comments required for UNSA T evaluation)

Comments:

OBSERVERS Name/SSN:

Name/SSN:

Name/SSN:

Name/SSN:

EVALUATOR Evaluator (Print): Date: Evaluator Signature:

RTL#A5.640U 112-ADM-130 1.F04 Page 4 of9 Revision I OPERATIONS JOB PERFORMANCE MEASURE TASK STANDARD:

RECOMMENDED STARTING LOCATION:

INITIAL INITIATING

REFERENCES:

TOOLS: HANDOUT: EVALUATOR DIRECTION Boron concentration for startup calculated within the specified tolerance.

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 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 MWDIMTU. The plant computer is NOT available.

The Shift Manager directs you to determine the boron concentration for startup by performing 20M-50A.F, "Performing An Estimated Critical Position Calculation", steps IV. A through IV.C.Lk. 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-10 correction Factor for criticality (Data Sheet 1 block VII) is 0.926. 20M-50A.F, "Performing An Estimated Critical Position Calculation", Rev. 7 BV-2 Curve Book, curves CB-12, 21, 22, 23, 24B, and 29 None 20M-50A.F BV-2 Cycle 16 Curve Book RTL#AS.640U 1I2-ADM-l30 l.F04 Page S of9 Revision I OPERATIONS JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET

• THIS SHEET TO BE GIVEN TO CANDIDATE

• DRead:

You are to perform an Estimated Critical Position Calculation.

INITIAL CONDITIONS: A plant startup is being performed exactly 5 days after a reactor trip from 100% power. Prior to the trip, the plant was at 100% with All Rods Out for 3 months. An RCS Boron sample was taken at 100% power just prior to the Reactor trip. It indicated that the RCS Boron concentration was 826 ppm. Current Core burnup is 10,000 MWDIMTU. The plant computer is NOT available.

INITIATING The Shift Manager directs you to determine the boron concentration for startup by performing 20M-50A.F, "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-IO Correction for Criticality.

They report that the B-IO 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 JPM. o When satisfied that you understand the assigned task, announce "I am now beginning the JPM". Simulate performance or perform as directed the required task. o 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". o Then hand this sheet to the evaluator.

1I2-ADM-1301.F04 Page 6 of9 Revision I 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)

Date/Time Boron Cone. Power Burnup Xenon Samarium Control Rod Position STANDARD Indicate "S" FOR SAT or "u" FOR UNSA T)=> S/U DEVELOPERN ALIDATION 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 ago Boron Cone. 826 ppm Power = 100% Bumup 10,000 (MWD/MTU)

Xenon = 100% (CB-12) Samarium = 100% (CB-22) Control Rod Position ARO at 225 steps COMMENTS:

112-ADM-130 I.F04 Page 7 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 II Expected at Criticality)

Date/Time Bumup Xenon Samarium Control Rod Position STANDARD (Indicate "s" FOR SAT or "u" FOR UNSAT)=> Stu Inputs Critical Data Part A II Expected at Criticality.

Date/Time

== Burnup 10,000 Xenon 0% Samarium 137.5% Control Rod Position = Banks A & B @ 225 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 Conc. = 826 ppm Part IV, B-I0 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 = Conc. 758.26 ppm COMMENTS:

• 1I2-ADM-1301.F04 Page 8 of9 Revision I OPERA nONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-007 JPM TITLE: Perform An Estimated Critical Position Calculation JPMREVISION:

2 STEP STANDARD ( "c" Denotes CRITICAL STEP) (Indicate "s" FOR SAT or "U" FOR UNSAT)=> Stu Calculate Reactivity Balance

4.1 Calculates

Part B, Item 5. (Data Sheet 1, Part B) Part B.l

• Power Defect 2300 = -2300 pcm (CB-21) Part B.2

• Control Rods = 963 0 = + 963 pcm (CB-24B) Part B.3

• Xenon 0 --2699 = -2699 pcm (CB-23) Part BA

• Samarium 862 -627 + 235 pcm (CB-22) Part B.5

• Reactivity Change = -3801 pcm COMMENTS: Calculate Boron Concentration

5.1 Calculates

Part C, Line 1, Item V. for Startup (Data Sheet 1, Part C) Part C.I

• Reactivity Change = -3801 pcm (from Part C.II

• Differential Boron Worth = -7.47 pcrn/ppm Part c.m

• Boron Change = + 509 Part C.IV

• EffBoron Conc. at Shutdown = 758.26 Part C.V

• EffBoron Conc. For Startup 1267.26 ppm COMMENTS: i

1I2-ADM-130 l.F04 Page 9 of9 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-007 JPM TITLE: Perform An Estimated Critical Position Calculation JPM REVISION:

2 ( "e" Denotes CRITICAL 6C. Calculate Boron Concentration for Startup (Data Sheet 1, Part C) Part C.l Part c.n Part C.I11 Part C.IV Part C.V Part C.VI Part c.vn Part C.VIII I STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT => 6.lC. Calculates Part C, Line 2, Item V. Reactivity Change = -3801 pcm (from B.5) Differential Boron Worth = -7.08 pcm/ppm (CB-20) Boron Change = + 537 ppm Eff. Boron Conc. at Shutdown = 758.26 ppm (from A.V) Eff. Boron Conc. For Startup = 1295.26 ppm (+1-50 ppm) Eff. Boron Conc. For Startup = 1295.26 (from C.V) B-10 Correction Factor for Criticality

= 0.926 Boron Concentration for Startup = 1398.76 COMMENTS:

EVALUATOR NOTE: Grader Discretion Required.

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

(Page S of 28) AN BVPS-IFR Unit 2 20M-50A.F Station Startup Operating Procedures Revision 7 Page 5 of 28 Performing An Estimated Critical Position Calculation Reactivity Balance Determine the power reactivity defect for Data Sheet 1, Part B. Column I (Prior to Shutdown) and record in the appropriate space on Data Sheet 1 as follows: Based on the power level and Effective Boron concentration.

Data Sheet 1, Part A, Column V, use BV-1 Curve Book Figure CB-21 , "Power Defect vs. Percent Power" to determine the power defect. OR Have the Reactor Engineer provide the power defect using either the electronic version of the Nuclear Design Report (E-NDR) or other NRC approved nuclear design codes. For the control rod positions listed on Data Sheet 1 (2), Part A (Critical Data) determine and record the control rod reactivity defect for Part B, Columns I and II as follows: BV-2 Curve Book Figure 24A, 24B, or 24C, "Integral Rod Worth vs. Steps Withdrawn Banks D and C Moving with Overlap".

OR Have the Reactor Engineer provide the current value using either the electronic version of the Nuclear Design Report (E-NDR) or other NRC approved nuclear design codes. Determine Xenon worth forData Sheet 1, Part B, Columns I and II as follows: If BV-2 Curve Book Figure CB-12 and/or CB-23, were used in Steps IV.A.1.e and IV.A.2.c, perform the following calculations and record the value obtained in Column C below on Data Sheet 1. Part B, Columns I and II: A C Percent Equil. Xenon Col. A x Col. 8/100% . Part A Critical Data Xenon Worth I Prior to Shutdown Column I em Expected at Criticality Column II em OR b. Have the Reactor Engineer provide Xenon values in pcm using a computer program that approximates Xenon worth.

(Page (; of 28) BVPS-IFR Unit 2 20M-50A.F Station Startup Revision 7 Operating Procedures Page 6 of 28 Performing An Estimated Critical Position Calculation Determine Samarium worth for Data Sheet 1 (2), Part B, Columns 1 and II as follows: If BV-2 Curve Book, Figure CB-22, was used in Step IV.A.2.d, perform the following calculations and record the value obtained in Column C below on Data Sheet 1 (2), Part B, Column,s I and II: 8 C Col. A x Col. 8/100% . Samarium Worth Prior to Column Expected at Column OR Have the Reactor Engineer provide Samarium values in pcm using a computer program that approximates Samarium worth. Calculate the reactivity change as follows: On Data Sheet 1(2), Part B, "Reactivity Balance", subtract Column I from Column II for each line. Enter the results in Column III, "Difference". Sum all the values in Column III and enter on Line 5. Record this value on Data Sheet 1 (2), Part C, Column I, Line 1. Critical Boron Concentration for Startup Data Sheet 1 Calculations Using BV-2 Curve Book, Figure CB-20, "HZP Differential Boron Worth vs. Boron Concentration", AND the Effective Boron Concentration from Data Sheet 1, Part A, Column V, enter the Differential Boron Worth on Data Sheet 1, Part C, Column II, Line 1. Divide the Reactivity Change (Column I, Line 1) by the Differential Boron Worth (Column II, Line 1) and enter the value on Data Sheet 1, Part C, Column III, Line 1. Be cautious of signs. Enter the Effective Boron Concentration from Data Sheet 1, Part A, Column V on Data Sheet 1, Part C, Column IV, Line 1. Add the Boron Change (Column III, Line 1) to the Effective Boron Concentration At Shutdown (Column IV, Line 1) and enter this value on Data Sheet 1, Part C, Column V, Line 1.

page 13 of 28) 20M-50A.F Unit 2 Revision 7 BVPS-lFR Station Startup Page 13 of 28 Operating Procedures Performing An Estimated Critical Position Calculation DATA SHEET FORM A. Critical Data (II) PRIOR TO EXPECTED AT CRITICALITY Date .5"D/tVS Date "J VJ Time-Boron ppm Power/(){) %

, ()()O BumupJf1 tJOO (MWD/MTU) ltJ() Xenon 0 (Use Fig CB-12 or N/A) (Use Fig CB-23 or Xenon % Samarium I f)() % Samarium 137.S-(Use Fig CB-22 or N/A) (Use Fig CB-22 or B"Z. B D L". (III) . (IV) M __Boron Concentration B-10 Correction Factor Effective (Part A. Column I) (use CB -29)

III x I ppm 758.2(P ppm B. Reactivity Balance -(Record absolute values in Columns I and II) (I) (III) Reactivity Defects Prior to Expected at (II-I) Shutdown Criticality Difference

1. Power (OR Consult RX I cm i Control (Circle Fig. (Fig. CB-24A. 24B. \ OR Consult RX ENGR) (Fig.

____________Samarium (Fig. CB-22) Reactivity Change (Sum of 1-4) == DATA SHEET

14 of 2S) BVPS-IFR Unit 2 20M-50A.F Station Startup Operating Procedures Revision 7 Page 14 of 28 Performing An Estimated Critical Position Calculation DATA SHEET 1 (continued)

FORM ECP-1 C. Critical Boron Concentration (I) (II) (III) (IV) (V)[-I Eff. Boron Cone. Eff. Boron Cone. Reactivity Boron Change at for Startup Change (B.5) (I) + (II) Shutdown (III) + (IV) m c_ (VI) Eff. Boron Conc. For B-10 Correction Factor Boron Concentration for Startup for Criticality Startup (Part C, Column V, line (from Rx Eng) (VI) + (VII) ppm 1-/:> 13 2f, 7' ppm D. Estimated Rod Position Correction (I) (II) (III) (IV) Boron Sample Boron Cone. For Boron Deviation Differential Boron Startup C.1.k (I) -(II) Worth (Fig. CB-20) ,-. pcm ppm ppm {+/-} ppm H ppm (V) (VI) (VII} (VIII) Rod Worth Rod Worth Corrected Rod Corr Critical Rod Pos. Correction (III) x (IV) Expected At Criticality (B.2) Worth Expected At Criticality (V) + (VI) (Circle Figure used) (Fig CB-24A, 248, 24C OR Consult RX ENGR) (+/-) pcmi pcm H pcm Steps* DATA SHEET

1I2-ADM-130 l.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 015A1.04 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: REQUALIFICATION INITIAL EXAM D TRAINING D FAULTED JPM D ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION:

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

Comments:

OBSERVERS Name/SSN:

Name/SSN:

EVALUATOR Evaluator Date: Evaluator Signature:

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

RECOMMENDED Simulator/Classroom STARTING LOCA nON:

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

INITIAL Mode 1, The plant computers are unavailable.

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

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 VII.B.1, including normalization values provided on Data Sheet 1.

RTL#A5.640U 1I2-ADM-1301.F04 Page 5 of9 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET

• THIS SHEET TO BE GIVEN TO CANDIDATE

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

INITIAL Mode 1, The plant computers are unavailable.

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

D At this time, ask the evaluator any questions you have on this lPM. D When satisfied that you understand the assigned task, announce HI am now beginning the JPM". Simulate performance or perform as directed the required task. D Point to any indicator or component you verify or check and announce your observations.

After determining the Task has been met announce" I have completed the JPM". , Then hand this sheet to the evaluator.

RTL#A5.640U 1 /2-ADM-130 1.F04 Page 6 of9 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-003 JPM REVISION:

5 Review 20ST-2.4A , "QPTR Manual Calculation" procedure. Record detector current values for each of the power range detectors in the "Current (Uncor.) column of Data Sheet 1, using either of the following methods: Detector current meters located on power range drawers. Test jacks located below the meter faces using a DVM, in accordance with Attachment A. JPM TITLE: Perform a Quadrant Power Tilt Ratio Calculation I STANDARD (Indicate liS" FOR SAT or "U" FOR UNSA T)=> 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 of 20ST-2.4A completed up to step VILB.I. This includes normalization factors filled out on Data Sheet 1. Reviews 20ST-2.4A , "QPTR Manual Calculation" procedure.

COMMENTS:

EVALUATOR 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.

2.1 Records

detector currents for each of the power range detectors (either from the NI cabinets or picture provided) in the Data Sheet 1 Current (Uncor.) column. COMMENTS:

RTL#A5.640U 1I2-ADM-130LF04 Page 7 of9 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-003 JPM TITLE: Perform a Quadrant Power Tilt Ratio Calculation JPM REVISION:

5 STEP STANDARD ( "c" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> Stu Multiply each of the detector 3.1C Determines corrected current by multiplying each current readings by its detectors Current (Uncor.) value by the associated associated normalization factor normalization 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 1: 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 4.3C Determines 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: Determine 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" RTL#A5.640U 1I2-ADM-130 l.F04 Page 8of9 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR*003 JPM TITLE: Perform a Quadrant Power Tilt Ratio Calculation JPM REVISION:

5 STEP STANDARD ( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> Stu Determines the following for 5.1C 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 "A VG". Current (Cor.) column AND Record the results in 5.3C Determines 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 ofthe "AVG" AND Record the "SUM" space by 4(3) results in the "Tilt Ratio" column. AND Record the result in the space marked "AVG". COMMENTS: Determine 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 EV ALUATOR 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.

1/2-ADM-1301.F04 Page 9 of9 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-003 JPM TITLE: Perform a Quadrant Power Tilt Ratio Calculation JPM REVISION:

5 I STANDARD ("e" Denotes CRITICAL (Indicate "S" FOR SAT or "U" FOR UNSAT => Candidate determines if QPTR 7.1 e 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:

minor scale subdivisions AND calculation method is correct. COMMENTS:

STOP TIME: _______

Quadrant Power Tilt Calculation 4/19/201011:13 AM .... '""'" .....",_e---....,. .. --.....

.. J CURRENT N41

, ES DETECTOR CURRENT

, ,

.,

RTL#A5.640U 1I2-ADM-1301.F04 Page 3 of6 Revision 1 JPM NUMBER: 2AD-031 JPM TITLE: Prepare a Clearance Tagout [2QSS-P21 B] Quench Spray JPM REVISION:

0 Pump 2IB KIA

REFERENCE:

2.2.13 4.1 TASK ID: 0481-007-03-043 JPM APPLICATION:

kg] REQUALIFICATION kg] INITIAL EXAM TRAINING FAULTEDJPM kg] ADMU\fISTRA TIVE JPM EV ALUA TION METHOD: LOCATION:

TYPE: ADMINISTERED BY: D Perform D Plant Site D Annual Requal Exam D BVT D Simulate D Simulator D Initial Exam D NRC D Classroom D OJT/TPE D Other: D Training D Other: EVALUATION RESULTS Performer Name: Performer SSN: Time Critical:

D kg] Yes No Allotted Time: 25 Minutes Actual Time: minutes JPM RESULTS: D D SAT UNSAT (Comments for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN:

Name/SSN:

Name/SSN:

Name/SSN:

EVALUATOR Evaluator (Print): Date: Evaluator Signature:

RTL#A5.640U TASK STARTING INITIAL INITIATING TOOLS: HANDOUT: 112-ADM-1301.F04 Page 4 of6 Revision 1 EVALUATOR DIRECTION SHEET Identify the tags and sequence of placement for a tagout of2QSS-P21B Quench Spray Pump 2113. Classroom You are to perform the task Prepare a SAFE Clearance Tagout. The plant is in Refueling Mode, no fuel is in the reactor. [2QSS-P21B]

Quench Spray Pump 2113 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 2113 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. NOP-OP-IOOl, Clearance/Tagging Program, Rev. 18 None NOP-OP-IOOl-1O Clearance Preparation Checklist, Rev. 05 NOP-OP-IOOl, Clearance/Tagging Program, Rev. 18 OP Manual Fig. No. 13-2, 10080-RM-413-2, Rev. 19 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 2QSS-P21B]

Quench Spray Pump 2113 Seal Replacement Yes Mode 4 Use caution when breaching seal package; casing may not completely

• 2R16 -SEAL REPLACEMENT RTL#A5.640U 1I2-ADM-130 l.F04 Page 5 of6 Revision I 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 21 B is to be placed on clearance.

INITIATING You are to identify the required clearance points (equipment), position (placement configuration), and sequence for clearing [2QSS-P21B]

Quench Spray Pump 21B 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. When satisfied that you understand the assigned task, announce "I am now beginning the JPM". Simulate performance or perform as directed the wquired task. D Point to any indicator or component you verify or check and announce your observations.

D After determining the Task has been met announce:

II I have completed the JPM lI

• Then hand this sheet to the evaluator.

RTL#A5.640U 1 12-ADM-130 LF04 Page 6 of6 Revision I OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-031 JPM TITLE: Prepare a Clearance Tagout [2QSS-P21B]

Quench Spray JPM REVISION:

0 Pump21B STANDARD {Indicate "S" FOR SAT or "U" FOR UNSAT => START TIME: ________ EVALUATOR This task is normally performed using the clearance computer and signed electronically.

For JPM, the SOMS computer is NOT available. necessary inform candidates that it is not required follow the instructions for Manual Clearance (lAW NOP-OP-IOO!

section EVALUATOR Provide JPM handout and student copy of I.e Candidate completes the table. 1.1 e Candidates table matches the ANSWER KEY. COMMENTS:

EVALUATOR When the candidate identifies and reports that all are identified, the evaluation for this JPM is STOP TIME: _______

ANSWER KEY (DO NO'. GIVE TO Evaluator NOTE: Student may identify additional points. The points listed below are the minimum required for this lPM. All additional points and different sequences must be evaluated to ensure the clearance is correct. Component ID 2QSS*P21B-CS (DF) 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 Valve Supply to Quench Pump 21B Discharge Isolation Valve Quench Pump 21B Discharge Isolation Valve Quench Pump 21B Suction Isolation Valve Quench Spray Pmp 21B Discharge Drain Isol Valve Vent valve for Quench Spray Pmp 21B Position Pull-Racked OR Bus Sequence 1 2 2 4 4 4 6 7 c o Ii: Q C o E o u Q

)

RTL#A5.640U 1/2-ADM-1301.F04 Page 3 of? Revision 1 OPERATIONS JOB PERFOlUv1ANCE MEASURE JPM NUMBER: 2AD-044 JPM TITLE: Select R WP and Determine Maximum Allowable Stay JPM REVISION:

0 Time KJA 2.3.7 3.5/3.6 TASK ID: 0481-005-03-043 JPM APPLICATION:

[8J REQUALIFICA TION [g] INITIAL EXAM TRAINING FAULTEDJPM

[8J ADMINISTRA TIVE JPM EVALUATION METHOD:

TYPE: ADMINISTERED BY: [g] Perform D Plant Site D Annual Requal Exam D BVT D Simulate D Simulator D Initial Exam D NRC Classroom D OJT/TPE D Other: D Training D Other: EVALUATION RESULTS Performer Name: Performer SSN: Time Critical:

lJ [g] 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:

Name/SSN:

Name/SSN:

EVALUATOR Evaluator (Print): Date: Evaluator Signature:

1/2-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:

INITIATING 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 R WP limit of 25 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-FQT1 00 located in the "A" Penetration. You are assigned the task of connecting a drain hose to 408, located near 2DAS-FQT100, in support clearance. The task will take 1.5 hours0.208 days <br />0.0298 weeks <br />0.00685 months <br /> to perform. You are to SELECT the correct R WP 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 R WP. 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 (112-10]4, 212-2014,112-1001,212-2001)

Radiation Survey Maps (Multiple maps including "A" pentration, ensure dose near 2DAS-FQT1 00 is reflective of calculated numbers used for JPM)

RTL#A5.640U 1/2-ADM-130LF04 Page 5 of? Revision 1 OPERATIONS JOB PERFOruv1ANCE MEASURE CANDIDATE DIRECTION SHEET

• THIS SHEET TO BE GIVEN TO CANDIDATE

• DRead: You are to determine correct RWP and associated Task Number for the given task, maximum stay time, and whether job will be completed based on this stay time. INITIAL CONDITIONS: A clearance is being prepared to work on the containment sump flow integrator 2DAS-FQTl 00 located in the "A" Penetration. You are assigned the task of connecting a drain hose to 408, located near 2DAS-FQT100, in support clearance. The task will take 1.5 hours0.208 days <br />0.0298 weeks <br />0.00685 months <br /> to perform. INITIATING You are to SELECT the correct R WP 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. 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 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 1/2-ADM-1301.F04 Page 6 of7 Revision 1 OPERA nONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-044 JPM TITLE: Select RWP and Determine Maximum Allowable Stay JPM REVISION:

0 Time Review set ofthree (3) RWPs provided and select correct R WP and task number. Calculate the maximum stay time. (Indicate "S" FOR SAT or "U" FOR UNSAT)=> START TIME: EVALUATOR NOTE: This JPM is designed to be performed in a classroom setting. Provide candidate with the set of RWPs, calculator, and Survey Maps. 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 the candidate that connecting the drain hose is considered a clearance activity.

Continue the task. COMMENTS:

2.1 C Determines maximum stay time is 1.25 hours1.042 days <br />0.149 weeks <br />0.0342 months <br /> (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and 15 minutes) and records this time in the candidate answer box. 25 mr I 20 mr/hr 1.25 hrs (EAD dose limit) (highest dose rate) (Stay Time) COMMENTS:

112-ADM-130 I.F04 Page 7 of7 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-044 JPM TITLE: Select R WP and Determine Maximum Allowable Stay JPM REVISION:

0 Time STEP ( "e" Denotes CRITICAL STEP) (Indicate "s" FOR SAT or "U" FOR Determines allowable stay 3.1 e Determines that stay time is 1.25 hours1.042 days <br />0.149 weeks <br />0.0342 months <br />, and estimated time does NOT allow completion for the job is 1.5 hours0.208 days <br />0.0298 weeks <br />0.00685 months <br /> 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 1!2-ADM-130 l.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) KJ A

REFERENCE:

2.1.25 4.2 TASK ID: 0011-006-06-013 JPM APPLICATION:

[8J REQUALIFICATION

[8J INITIAL EXAM o TRAINING o FAULTED JPM [8J ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION:

TYPE: ADMINISTERED BY: [8J Perform 0 Plant Site 0 Annual Requal Exam 0 BVT 0 Simulate 0 Simulator 0 Initial Exam 0 NRC [8J Classroom 0 OJT/TPE 0 Other: 0 Training 0 Other: EVALUATION RESULTS Performer Name: Performer SSN: Time Critical:

0 [8J Yes No Allotted Time: 25 Minutes Actual Time: minutes JPM RESULTS: D D SAT UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN:

Name/SSN:

Name/SSN:

Name/SSN:

EVALUATOR Evaluator (Print): Date: I Evaluator Signature:

RTL#A5.640U 1/2-ADM-1301.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 bumup 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.l, Shutdown Calculation (Plant Critical) (Updated for Cycle 16). Document results of your review in the appropriate section of the 20ST-49.1, 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 %i\klk for inoperable rod worth instead of2.31 %l\k/k 2800 PCM for power defect instead of 2300 PCM 3.0096 %l\k/k for SDM instead of2.054 %i\klk RTL#A5.640U 1/2-ADM-J301.F04 Page 5 of 12 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], TAVG DEVIATION FROM TREF is "NOT LIT". ONE control rod has been determined to be inoperable, untrippable, and immovable during performance of 20ST-1.1, Control Rod Assembly Partial Movement Test. Chemistry has just reported current RCS boron concentration at 833 ppm. Current bumup is 12,000 MWDIMTU. The RO has completed 20ST-49.l, 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 JPM. D 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" r have completed the lPM". Then hand this sheet to the evaluator.

RTL#A5.640U 1/2-ADM-130 1.F04 Page 6 of 12 Revision I OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-039 JPM TITLE: Review Shutdown Margin Calculation (At Power and ONE JPM REVISION:

0 Inoperable Rod) (SRO ONLY) ( "C" Denotes CRITICAL If the plant is in Mode 1, VerifY that Tavg is less than 3°F above Tref (Annunciator A4-3C, TAVG DEVIATION FROM TREF is OFF) (Otherwise N/A). (Step VILA.1) If the plant is in Mode 2, VerifY that Tavg is less than gOF above Program Tavg as follows: (Otherwise N/A) (Step VII.A.2) STANDARD (Indicate "s" FOR SAT or "U" FOR UNSAT)=> I SIU I EVALUATOR Some judgment may be required to satisfactory performance on this JPM. Refer attached Data Sheet 1 ANSWER EVALUATOR If the candidate hands in the OST after finding the first error, provide the following Make any necessary corrections and complete SDM START TIME: ________ Verifies Step VII.A.!, (Plant in Mode 1, Tavg <3°P above Tref (Annunciator A4-3C OFF) from Initial Conditions.

COMMENTS: Verifies Step VII.A.2, is N/A (Plant not in Mode 2). COMMENTS:

RTL#A5.640U I 12-ADM-l 30 I.F04 Page 7 of 12 Revision I OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-039 JPM TITLE: Review Shutdown Margin Calculation (At Power and ONE JPM REVISION:

0 Inoperable Rod) (SRO ONLY) STANDARD lITIeAL STEP) (Indicate "s" FOR SAT or "U" FOR UN SAT)=> SIU 3. Request Chemistry to determine current RCS Boro concentration in ppm. n 3.1 Verifies current boron concentratio initial conditions.

n is 833 ppm from (Step VII.A.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 VII.A.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 AVG PWR 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 1I2-ADM-130 l.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) ( "c" Denotes CRITICAL If the number of immovable or untrippable control Rods is greater than I, Use Attachment 1 to determine the required boron concentration with greater than one struck rod and Record below. (Otherwise NtA) (Step VILA.7) Determine control bank reactivity worth per the following:

Using the ARO Total Bank Worth table on Data Sheet I, Enter the total bank worth for the current core burnup range, in the space provided on Data Sheet 1. (Step VILB.I.a) Using Curve Book Figures CB-24A, 24B or CR*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 %8k/k AND Record on Data Sheet 1. (Step VII.B.1.b)

STANDARD (Indicate "S" FOR SAT or "V" FOR SIU 7.1 Verifies Step VILA.7 is Nt A. COMMENTS: Verifies ARO Total Bank Worth (from the Data Sheet 1 table) to be 7.571 %8k1k and recorded on Data Sheet 1 (Block B.l.a). COMMENTS: Verifies integral rod worth to be ZERO and recorded on Data Sheet 1 (Blocks B.l.b.l) and B.l.b). COMMENTS:

RTL#A5.640U 1I2-ADM-130 l.F04 Page 9 of 12 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-039 JPM TITLE: Review Shutdown Margin Calculation (At Power and ONE JPM REVISION:

0 Inoperable Rod) (SRO ONLY) STEP ( "e" Denotes CRITICAL STEP) I STANDARD (Indicate "s" FOR SAT or "U" FOR UNSAT)=> Stu 10. Subtract the integral rod worth from the Total Bank Worth AND Enter the result 10.1 Verifies TBW-IRW is 7.571 Data Sheet] (Block B.Lc). and recorded on on Data Sheet 1. COMMENTS: (Step VILB.l.c) Multiply this result by 0.9 to apply a 10% uncertainty AND Enter the result on Data Sheet 1. (Step VII.B.I.d) If ONE rod is inoperable (untrippable), Record "Worst Case Stuck Rod with Inoperable Rod" worth on Data Sheet 1. Value is determined from Column "B" on Attachment 2: for the appropriate Cycle Burnup. (Step VII.B.2.b) Verifies 90% ofTBW to be 6.8139 and recorded on Data Sheet 1 (Block B.l.d). COMMENTS:

12.1 C Determines stuck rod worth should be 2.31 0 NOT 0.857 and records on Data Sheet 1 (Block B.2). COMMENTS:

EVALUATOR Candidate may need cued to make any corrections and complete the SDM RTL#A5.640U I /2-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 "S" FOR SAT or HUH FOR UN SA StU 13.C Subtract Stuck Rod(s) Worth 13.1 C Determines 90% Total Bank Worth minus Stuck from the 90% Total Bank Rod(s) Worth to be 4.5039 %8kJk and records on Worth value AND Enter the Data Sheet 1 (Block B.3). resulton Data Sheet 1. (Step VII.B.3) COMMENTS: Determine Power Defect as 14.1 Record RCS Boron Concentration of 833 ppm on follows: Data Sheet 1 (Block B.4.a). Record RCS Concentration results COMMENTS: Chemistry on Data Sheet 1. (Step VII.B.4.a) Using Curve Book Figure 29, 15.1 Determines 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 Burnup (If between two Burnup values, Use the COMMENTS:

B-I0 Correction Factor for the greater MWDIMTU Bumup entry) AND Record on Data Sheet 1. (Step VII.BA.b)

I RTL#A5.640U 112-ADM-130 1.F04 Page 11 ofl2 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-039 JPM TITLE: Review Shutdown Margin Calculation (At Power and ONE JPM REVISION:

0 ( "c" 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, Detennine the ABSOLUTE VALUE of the 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!. (Step VII.B.4.e)

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

17.1 C Determines ABSOLUTE V ALUE of the Power Defect to be 2300 pcm NOT 2800 pcm and records on Data Sheet 1 (Block B.4.d). COMMENTS: 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 112-ADM-1301.F04 Page 12 of 12 Revision 1 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% LikJk for operating temperature band margin to the Power Defect recorded in Step VII.BA.e AND Record on Data Sheet 1. (Step VII.BA.t) Determine SHUTDOWN MARGIN by subtracting Power Defect (Step VII.BA.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 UNSAT 19.1C Determines Power Defect plus operating temperature band margin to be 2045 % LikJk NOT 2.95 % LikJk and records on Data Sheet 1 (Block BA.f). COMMENTS:

20.1C Determines SDM to be 2.054 % LikJkNOT 3.009 % LikJk and records on Data Sheet 1 (Block BA.f) AND space provided on candidate direction sheet. COMMENTS:

EVALUATOR CUE: That Completes this JPM STOP TIME:

20ST-49.1 Revision 18 Operating Surveillance Test Page 12 of 17 Shutdown Margin Calculation (Plant Critical) (Updated For Cycle 16) DATA SHEET SHUTDOWN MARGIN A" 4. CBD Steps Withdrawn (OR cec if ceo @ 0 STEPS=225 .. /tJO 5. Reactor % 6. Number of inoperable .. -...1--ROD(s) ARO TOTAL BANK WORTH ('Yo AkIk) o to 10000 MWDIMTU I 10000 to EOl I 7.571 = 1.511 B. 1. a. AR o Total Bank Worth (See Table (TBW) % AkJk b. Integral Rl0rth (Curve Book Figure 24A, 24B OR (IRW) .. L-pcm __

..

1000pcm c. TBW (B.1.a) -IRW

%AkJk::: 7.S71 90% Current Total Bank Worth 0.9x 7.S71 (B.1.c) ..

2. Inoperable (untrippable)

OR Dropped Rod(s) Worth Z *31 ..9IJS1%AWk C. 3. (90% Total Bank Worth) -(Inoperable (Untrlppable)

OR Dropped rod(s) (B.1.d) 4. a. RCS Boron Concentration

b. B-10 Correction Factor (CB Figure 29) c. (RA Boron Concentration>>)( (B-10 Correction Factor) ( i'i 5.--..Jx( o.9()() } (B.4.a) (B.4"b) d. ABSOLUTE VALUE of Power Defect (CB Figure 21) 2 '200 e. 1%Ak/k(pcm from B.4.d) x 1000

+ Operatlng temperature band margin * (B.4.e) + 0.150% AkJk SHUTDOWN (Acce Criteria -Within Li Specified In DATA SHEET I RTL#A5.640U 1I2-ADM-130 l.F04 Page 3 of8 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-040 JPM TITLE: Review comple:ted RCS Initial Void Volume And JPM REVISION:

0 Void Volume Calculation (lAW 20M-6.4.T, Response Voids In The Reactor Vessel) (SRO KIA 2.1.7 4.7 TASK ID: 0061-016-01-013 JPM APPLICATION:

[g] REQUALIFICATION

[g] INITIAL EXAM D TRAINING FAULTEDJPM

[g] ADMINISTRATIVE JPM EV ALUA TION METHOD:

TYPE: ADMINISTERED BY: [g] Perform D Plant Site D Annual Requal Exam D D Simulate D Simulator D Initial Exam D Classroom D OJT/TPE D Other: D Training D Other: EV ALUA TION RESULTS Performer Performer SSN: Time D Yes Actual 12 minutes Critical:

[g] No Time: D SAT JPM D UNSAT (Comments required for UNSAT Comments:

OBSERVERS Name/SSN:

Name/SSN:

EVALUATOR Evaluator Date: Evaluator Signature:

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

RECOMMENDED STARTING LOCATION:

DIRECTIONS:

INITIAL CONDITIONS:

INITIATING CUE:

REFERENCES:

TOOLS: HANDOUT: Incorrect RCS Initial Void Volume is corrected to 5781 FT3 + 4 AND Final Void Volume is corrected to 5477 FT3 +/- 4 Classroom Review completed RCS Initial Void Volume And Final Void Volume Calculation (lAW 20M-6.4.T, Response To Voids In The Reactor Vessel) A Reactor trip from 100% power has occurred. SI has NOT been actuated Power was lost to all RCPs. Both Trains of RVLIS are inoperable. Normal Charging and Letdown are in operation. A plant cooldown was in progress. RCS Hot Leg temperature is stable. Voids are indicated in the Reactor Coolant System by an abnormal changt:: in Pressurizer level due to a change in Reactor Coolant System pressure. The ATC has completed the performance of20M-6.4.T, Response To Voids In The Reactor Vessel through step IV.B.6. Perform the second verification of the RCS initial void volume AND the RCS final void volume IA W 20M-6.4.T, Response To Voids In The Reactor Vessel. Report your results in the space provided. (Space provided on candidate direction sheet). 20M-6.4.T, Response To Voids In The Reactor Vessel, Rev. 3. Calculator 20M-6.4.T, Response To Voids In The Reactor Vessel Rev. 3 completed with the following errors: 1800 psig and 1900 psig are reversed in the step calculation of RCS initial void 1800 psig and 1900 psig are reversed in the step calculation of RCS final void

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RTL#A5.640U 1I2-ADM-130 l.F04 Page 5 of8 Revision I OPERATIONS lOB PERFORMANCE MEASURE CANDIDATE DIRECTION

• THIS SHEET TO BE GIVEN TO CANDIDATE DRead: Review completed RCS Initial Void Volume And Final Void Volume Calculation (lAW 20M-6.4.T, Response To Voids In The Reactor Vessel) INITIAL CONDITIONS:

• A Reactor trip from 100% power has occurred.

• SI has NOT been actuated Power was lost to all RCPs. Both Trains of RVLIS are inoperable. Normal Charging and Letdown are in operation. A plant cooldown was in progress. RCS Hot Leg temperature is stable. Voids are indicated in the Reactor Coolant System by an abnormal change in Pressurizer level due to a change in Reactor Coolant System pressure. The ATC has completed the performance of20M-6.4.T, Response To Voids In The Reactor Vessel through step IV.B.6. INITIATING Perform the second verification of the RCS initial void volume AND the RCS final void volume lAW 20M-6.4.T, Response To Voids In The Reactor Vessel. Report your results in the space provided.

RESULTS: RCS Initial Void Volume RCS Final Void Volume 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 l/2-ADM-130 1.F04 Page 6 of8 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-040 JPM REVISION:

0 ( "C" Denotes CRITICAL JPM TITLE: Review completed Res Initial Void Volume And Final Void Volume Calculation (lAW 20M-6.4.T, Response To Voids In The Reactor Vessel) (SRO ONLY) I STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT => EVALUATOR NOTE: Information used to fill-out Pi = 1800 P r= 1900 Li = Lr= EVALUATOR NOTE: Some judgment may be required to determine satisfactory performance on this JPM. EVALUATOR NOTE: If the candidate hands in the procedure after ONL Y finding the first error, provide the following cue: Make any necessary corrections and complete the void volume I:alculations.

START TIME: ________

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1/2-ADM-1301.F04 Page 7 of8 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-040 JPM TITLE: Review completed RCS Initial Void Volume And Final JPM REVISION:

0 Void Volume Calculation (lAW 20M-6.4.T, Response To Voids In The Reactor Vessel) (SRO ONLY) STEP I STANDARD ( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "u" FOR SID Calculate the size of the RCS 1.1 C Identifies that 1800 psig and 1900 psig have been initial void volume (G i) as reversed, and re-calculates as follows: follows: Gi =((Li% -Lf%) x 12.17)/(1

-(PiPsig/Pfpsig>>

G i =((Li% -Lf%) x 12.17)/(1

-(Pi psig 1 PfPsig>> Gi

-_'l x 12.17) 1 (1 -Gi=(( -12.17) 1 (1 -('-____ 1 >> G i = cu-ft. G i x 12.17) 1 (1-G i =C304.25-->

1 (.052631579)

G i = 5781 cu-ft. COMMENTS:

l/2-ADM-1301.F04 Page 8 of8 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER:" 2AD-040 JPM TITLE: Review RCS Initial Void Volume And Final JPM REVISION: Void Volume Calculation (lAW 20M-6.4.T, Response To Voids In The Reactor Vessel) (SRO ONLY) STEP I ( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT Calculate the size of the RCS 2.1 C Identifies that 1800 psig and 1900 psig have been final void volume (Gt) from reversed, and re-calculates as follows: the initial RCS void volume x ( Pi JPsig / Pfpsig ) (Step B.5) as follows: Gf =Gi x ( Pi psig / Pf psig ) Gf=( ) x ( /

Gf= cu-ft. Gf=L5781->

x L.947368421->

Gf=L5477->

COMMENTS:

EVALUATOR CUE: That Completes this JPM STOP TIME:

1I2-ADM-1301.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 2.2.17 2.6/3.8 TASK ID: 1300-027-03-023 JPM APPLICATION: REQUALIFICATION INITIAL EXAM TRAINING D FAULTED JPM ADMINISTRA TIVE JPM EVALUATION METHOD: LOCATION:

TYPE: ADMn'JISTERED BY: [gJ Perform D Plant Site D Annual Requal Exam D BVT D Simulate D Simulator D Initial Exam D NRC D OJT/TPE D Other: D Training D Other: EV ALUA TION RESULTS Performer Performer SSN: Time Critical:

D [gJ 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:

Name/SSN:

Name/SSN:

EVALUATOR Evaluator (Print): Date: Evaluator Signature:

RTL#A5.640U 1/2-ADM-1301.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 hours2 days <br />0.286 weeks <br />0.0658 months <br />. 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-I007, "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-1007, "Risk Management", Rev. 14 Technical Specifications Beaver Valley Power Station Units 1 & 2 None NOP-OP-I007, "Risk Management", Rev. 14 Technical Specifications Beaver Valley Power Station Units 1 & 2 (Need to be available in the event the candidate wants to reference)

1/2-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 tht: risk level for given plant conditions and required approver for thi s 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 hours2 days <br />0.286 weeks <br />0.0658 months <br />. INITIATING 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-I007, "Risk Management".

Report the results of your risk assessment and required approver of this risk level in the "Candidate Answer" Box below. CANDIDATE ANSWER(S):

D At this time, ask the evaluator any questions you have on this JPM. D D When satisfied that you understand the assigned ta.sk, announce "I am now beginning the JPM". Simulate perfonnance or perfonn as directed the required task. D Point to any indicator or component you verify or check and announce your observations.

After detennining the Task has been met announce" I have completed the JPM". Then hand this sheet to the evaluator.

1I2-ADM-130 l.F04 Page 6 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) "s" FOR SAT or "U" FOR UNSA T START TIME: EVALUATOR CUE: Provide a copy of 1007, "Risk Management".

1. Refers to NOP-OP-l 007, "Risk 1.1 Refers to NOP-OP-1007. Management" EVALUATOR NOTE: The candidate may want to refer to TS 3.7.5 as part of this JPM step. Ensure Technical Specil1cations Beaver Valley Power Station Units 1 & 2 is available for reference.

TS 3.7.5 Condition B applies since 2FWE*P23A is inoperable.

Condition C requires a plant shutdown if2FWE*P23A cannot be returned to service within 72 hours3 days <br />0.429 weeks <br />0.0986 months <br />. Refers to Attachment Risk 2.1 C Determines that this activity is ORANGE risk level. Assessment Worksheet, to This is based on Attachment 3, Section E.5 answer is determine risk. YES because 48 hours2 days <br />0.286 weeks <br />0.0658 months <br /> is greater than half of the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> allowed Technical Specification (TS) Action Statement for any TS which requires a Unit Shutdown if not exited. Records approver in the candidate answer box of the candidate direction sheet. COMMENTS:

RTL#A5.640U 1I2-ADM-130 l.F04 Page? of? Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-041 JPM TITLE: Perform a Risk Assessment

[2FWE*P23A Maintenance]

JPM REVISION:

0 (SRO Only) ("e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "V" FOR 3.C Refers to Attachment 2, Plant 3.1 C Determines that based on an Orange Risk, the Director Risk Matrix or to section 4.3.C of Site Operations (or designee) is the required on page 19, to determine approver for this risk level. required approval.

3.2 Records

approver in the candidate answer box of the candidate sheet.

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

STOP TIME: ________

RTL#A5.640U 1I2-ADM-J30 I.F04 Page 3 of7 Revision I OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-042 JPM TITLE: Determine compensatory actions for 2GWS-P21 and JPM REVISION:

0 2GWS-OA-lOOA being OOS. (SRO ONLY) KIA

REFERENCE:

2.3.11 (4.3) TASK ID: 1300-029-03-023 JPM APPLICATION:

[2J REQUALIFICATION Igj INITIAL EXAM D TRAINING D FAULTED JPM ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION:

TYPE: ADMINISTERED BY: Perform D Plant Site D Annual RequaJ Exam D BVT D Simulate D Simulator D Initial Exam D NRC [2J Classroom D OJT/TPE D Other: D Training D Other: EVALUATION RESULTS Performer Name: Performer SSN: Time D Yes Allotted Actual 20 Minutes minutes Critical:

[2J No Time: Time: D SAT JPM RESULTS: D UNSAT (Comments required for UNSA T evaluation)

Comments:

OBSERVERS Name/SSN:

Name/SSN:

Name/SSN:

Name/SSN:

EVALUATOR Evaluator (Print): Date: Evaluator Signature:

i

1/2-ADM-1301.F04 Page 4 of7 Revision 1 OPERA nONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-042 JPM REVISION:

0 TASK STANDARD:

RECOMMENDED STARTING LOCATION:

INITIAL CONDITIONS:

INITIATING CUE:

REFERENCES:

TOOLS: JPM TITLE: Determine 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 hours1 days <br />0.143 weeks <br />0.0329 months <br /> take grab samples and analyze for Oxygen concentration AND, least once per 24 hours1 days <br />0.143 weeks <br />0.0329 months <br />, verifY that the GW storage tanks contain less or equal to 19,000 curies. Classroom 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 opera.ting 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-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, Rev. TS 5.5.8, Amend liz ODCM Section 3.0.3, Rev. OM Fig. 19-3 Rev.

RTL#A5.640U 1/2-ADM-1301.F04 Page 5 of7 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE CANDIDATE DIRECTlON SHEET >I< THIS SHEET TO BE GIVEN TO CANDIDATE

>I< DRead: 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 al1 system in NSA. Gaseous Waste Storage Tanks (2GWS-TK25A-G) pressures are 8 psig and STABLE. Gaseous Waste Surge Tank (2 GWS-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 compensatory actions in the block below. Required compensatory actions, if any: D At this time, ask the evaluator any questions you have on this JPM. D 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 I 12-ADM-130 1.F04 Page 6 of7 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-042 JPM TITLE: Detennine compensatory actions for 2GWS-P21 and JPM REVISION:

0 2GWS-OA-100A being OOS. (SRO ONLY) STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT =:> STARTTIME:

_______ EVALUATOR CUE: Provide the Candidate with Candidate Direction Sheet and a current copy of Fig. 19-3, LRM, AND Yz ODCM Section EVALUATOR These steps may be perfonned in any EVALUATOR The next step may not be necessary.

The may already be familiar enough with the system know the impact of2GWS-P21 being 1.1 Detennines the impact of 1.1 Refers to OM Fig. 19-3 and detennines that Waste 2GWS-P21 being OOS. Gas Storage Tank Radiation Monitor (2GWS-RQI04) is out of service as a result of2GWS-P21 being OOS. Determines Yz ODCM 2.1 Refers to Yz ODCM Section 3.0.3, Att. 0 item compensatory actions for 4.11.25.1 on page 66. Waste Gas Storage Tank Radiation Monitor 2.2C Detennines that it will be required to verify, least RQ104) being out of service. once per 24 hours1 days <br />0.143 weeks <br />0.0329 months <br />, that the GW storage tanks contain less or equal to 19,000 curies. (when adding radioactive materials to the tank) COMMENTS:

l/2-ADM-1301.F04 Page 7 of? Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-042 JPM TITLE: Determine compensatory actions for 2GWS-P21 and JPM REVISION:

0 2GWS-OA-IOOA being OOS. (SRO ONLY) STEP ( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UN SAT 3.C Determines LRM

3.1 Refers

to LRM 3.3.12 Condition B.t. actions for Oxygen Analyzer (2GWS-OAIOOA) being OOS. 3.2C Determines at least once per 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> take grab samples and analyze for oxygen content. COMMENTS:

EVALUATOR CUE: That completes this JPM. STOP TIME: ______

RTL#A5.640U J/2-ADM-1301.F04 Page 3 of7 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-043 JPM TITLE: Complete Initial Notification Form for a General JPM REVISION:

0 Emergency (SRO ONLY) KIA

REFERENCE:

2.4.40 (4.5) TASK ID: 1350-004-03-023 2.4.44 (4.4) 1350-007-03-023 JPM APPLICATION:

C8J REQUALIFICATION C8J INITIAL EXAM D TRAINING D FAULTED JPM C8J ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION:

TYPE: ADMINISTERED BY: IPerform D Plant Site D Annual Requal Exam D BVT D Simulate D Simulator D Initial Exam D NRC C8J Classroom D OJT/TPE D Other: D Training D Other: EVALUATION RESULTS Performer Name: Performer SSN: Time C8J Yes Allotted Actual 15 Minutes minutes Critical:

D No Time: Time: D SAT JPM D UNSAT (Comments required for UNSAT Comments:

OBSERVERS Narne/SSN:

Narne/SSN:

Narne/SSN:

Name/SSN:

EVALUATOR Evaluator (Print): Date: Evaluator Signature:

1I2-ADM-1301.F04 Page 4 of7 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD JPM REVISION:

0 TASK STANDARD:

RECOMMENDED STARTING LOCATION:

INITIAL CONDITIONS:

INITIATING CUE:

REFERENCES:

TOOLS: TLE: Complete Initial Notification Fonn for a Emergency (SRO ONL EVALUATOR DIRECTION SHEET Complete Initial Notification for General Emergency and correctly documents this infonnation on the FENOC Nuclear Power Plant Initial Notification Fonn in S 15 minutes as per Answer Key Provided.

Classroom You have declared a General Emergency based on EAL Tab 2.3 today at Unit 2 @ 1000 hours41.667 days <br />5.952 weeks <br />1.37 months <br /> following an ATWS and the 3 hottest core exit thennocouples are> 1200 of. A non-routine airborne release of radioactive material as a result of this event is in progress due to 2FWE*P22 [Steam Driven AFW Pump] operation.

Unit 1 continues to operate at 100% power. The following plant conditions exist: 35' wind direction is from 90° at 12 MPH. 150' wind direction is from 110° at 15 MPH. 500' wind direction is from 90° at 20 MPH. No radioactive rdease has occurred or is imminent (within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />). Valid Dose projections are not yet available You are the Emergency Director and the TSC/EOF has NOT yet been activated.

You are to evaluate the above conditions and complete the Initial Notification Fonn provided.

Determine which, if any, offsite Protective Action Recommendations are necessary lAW 4.1, "Offsite Protective Actions".

Return the Initial Notification Fonn to the examiner as soon as you are finished.

This JPM is time critical.

112-EPP-IP-4.l, Offsite Protective Actions, Rev. 29 112-EPP-IP-1.l.FOI, "FENOC Nuclear Power Plant Initial Notification Fonn", Rev. 5 1/2-EPP-IP-l.1.F01, "FENOC Nuclear Power Plant Initial Notification Fonn", Rev. 5 ANSWER KEY (Do NOT Provide to Candidate)

RTL#AS.640U 112-ADM-130 1.F04 Page S of7 Revision 1 OPERA TIONS JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET

• THIS SHEET TO BE GIVEN TO CANDIDATE

• DRead: INITIAL You have declared a General Emergency based on EAL Tab 2.3 today at Unit 2 @ 1000 hours41.667 days <br />5.952 weeks <br />1.37 months <br /> following an ATWS and the 3 hottest core exit thermocouples are> 1200 of. A non-routine airborne release of radioactive material as a result of this event is in progress due to 2FWE*P22 [Steam Driven AFW Pump] operation.

Unit 1 continues to operate at 100% power. The following plant conditions exist: 35' wind direction is from 90° at 12 MPH. 150' wind direction is from 110° at 15 MPH. 500' wind direction is from 90° at 20 MPH. No radioactive release has occurred or is imminent (within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />). Valid Dose projections are not yet available INITIATING You are the Emergency Director and the TSC/EOF has NOT yet been activated.

You are to evaluate the above conditions and complete the Initial Notification Form provided.

Determine which, if any, offsite Protective Action Recommendations are necessary lAW 4.1, "Off site Protective Actions", Return the Initial Notification Form to the examiner as soon as you are finished.

This JPM is time critical.

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 1/2-ADM-130 I.F04 Page 6 of7 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-043 JPM TITLE: Complete Initial Notification Fonn for a General f JPM REVISION:

0 Emergency (SRO ONLY) STANDARD (Indicate "S" FOR SAT or "U" FORUNSAT =>

___ EVALUATOR CUE: Provide the Candidate with the Candidate Direction Sheet and a copy of 4.1, Offsite Protective Actions and !h-EPP-IP-FO

1. EVALUATOR CUE: Record start time in the space above after reading the candidate the Candidate Direction Sheet. 1. Perfonns 1/2-EPP-IP-4.1, 1.1 Performs actions as specified 1I2-EPP-IP-4.1, Attachment A, "Offsite Attachment A, "Offsite Protective Action Protective Action Recommendation Flowchart Part I". Recommendation Flowchart Part V'. COMMENTS:

2.C Completes the Steps marked 2.1 e Enters the correct information in all of the spaces critical on the FENOC Nuclear marked critical on the FENOC Nuclear Power Power Plant Initial Notification Plant Initial Notification Fonn. Fonn. COMMENTS:

3.e Completes FENOC Nuclear 3.1 C The difference between the start and stop time as Power Plant Initial Notification recorded is :s 15 minutes. Form 15 minutes from start of JPM. COMMENTS:

RTL#A5.640U 1/2-ADM-1301.F04 Page 7 of7 Revision I OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-043 JPM REVISION:

0 ( "e" Denotes CRITICAL JPM TITLE: Complete Initial Notification Form for a General Emergency (SRO ONL Y) STANDARD Indicate "S" FOR SAT or "U" FOR UNSAT ::::) EV ALUATOR CUE: When the candidate hands in the FENOC Nuclear Power Plant Initial Notification Form, record the time below, and inform the candidate "This JPM is complete".

Grader discretion required.

STOP TIME: _______

FENOC NUCLEAR STATE I COUNTY USE ONLY

• INITIAL CLASSIFICATIONS, PLANT INITIAL NOTIFICATION

• CHANGES IN DATE: TIME: FORM

• CHANGES IN PROTECTIVE ACTION MESSAGE NO: Beaver Valley 1I2-EPP-IP-1.1.F01 Rev. 5

• EVENT S,.....J04This is the: 0 Beaver Valley Power Station Unit 1 Reactor Power Level % .. \\ Code Word *t. 119 Beaver Valley Power Station Unit 2 Reactor Power Level_O=-_%

2. This is: o An Actual Emergency A Drill 3. []3 a. A(n) . GENERAL EMERGENCY SITE AREA EMERGENCY 0 ALERT o UNUSUAL EVENT << , .. r;. was declared at:

on ""fQb:::t based on EAL(s}: 'l.l (TIME) (DATE) o b. The Emergency situation has been terminated at: (TIME) o c. The Protective Action Recommendation is being changed at: (TIME) 4. Brief non-technical description of event: A 1" f.4l 5 f-v """"'}-...... ...\-'" -;3 l,..... } t.J t <:. £. i c:s 5. The radiological conditions are: -,.a. A non-routine releasefuadioactive material, as a result of this event, is in The release is:

0 o b. The release of radioactive material associated with this event has been terminated.

o c. NO Radiological Release is in progress as a result of this event. 6. Utility Protective Action Recommendations (PAR's): ..., t' a. Evacuation:

/c, o N/A I25J 2 Miles -360 0 05 Miles -360 0 010 Miles -360AN D Evacuate Downwind N/A" 5 Miles (check applicable sectors) ""e" 0 A 0 B COD E OJ OK AND that potassium iodi e a e e pu IC in accordance with State procedures.

The general public in unaffected areas should be advised to go indoors and monitor EAS broadcasts . ... It b. Sheltering:

/ t. o N/A Remainder of 10 Mile EPZ 10 Mile EPZ 0-2 Miles 360 0 and 5 Mile Downwind Wedge (check applicable sectors) OA DB OC OD DE F OG OH OJ OK OL M ON OP Oa DR AND that potassium iodide (KI) be administered to the general public in accordance with State procedures.

The general public in unaffected areas should be advised to go indoors and monitor EAS broadcasts.

o c. None ,.. f' " c 7. Wind Direction is FROM: \\0 degrees at 150' Wind Speed is: 12. mph at 35' Callback number is For Utility Use ! PEER Approved:

S R.o RTL#A5.640U l/2-ADM-130 1.F04 Page 3 of8 Revision 0 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:

cg] REQUALIFICATION cg] INITIAL EXAM D TRAn'JING

[] FAULTED JPM D ADMINISTRATIVE JPM EV ALUA TION METHOD: LOCATION:

TYPE: ADMINISTERED BY: cg] Perform D Plant Site D Annual Requal Exam D BVT D Simulate cg] 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 cg] Yes No I A.Hotted TIme: 15 minutes Actual Time: minutes JPM RESULTS: D D S.AT UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN:

Name/SSN:

Name/SSN:

Name/SSN:

EVALUATOR Evaluator (Print): Date: Evaluator Signature:

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

3 TASK STANDARD:

RECOMMENDED STARTING LOCATION:

DIRECTIONS:

INITIAL CONDITIONS:

INITIATING CUE:

REFERENCES:

TOOLS: HANDOUT: 1/2-ADM-1301.F04 Page 4 of8 Revision 0 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/O. The plant is at approximately 25% power. 20M-52.4.R.1.F, "Station Shutdown from 100% Power to Mode 5" has been completed up to Step D.8. The 21A Main Feed Reg Valve [2FWS-FCV478]

operated erratically during the shutdown and is currently in "AUTO" for observation. Your supervisor directs you to place 21A S/O 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/O 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#A5.640U 1I2-ADM-130 l.F04 Page 5 of8 Revision 0 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.8. The 21A Main Feed Reg Valve [2FWS-FCV478]

operated erratically during the shutdown and is currently in "AUTO" for observation.

INITIATING CUE: Your supervisor directs you to place 21A 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%. D At this time, ask the evaluator any questions you have on this .rPM. 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.

RTL#A5.640U 112-ADM-130 I.F04 Page 6 of8 Revision 0 OPERA TrONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-072 JPM TITLE: Transfer from Main Feedwater Reg Valves to Bypasses JPM REVISION: Review 20M-52.4.R.l.F and attachment

10. Place controller in MANUAL AND Slowly Open the 21A Bypass FCY. As the 21A Bypass FCV is being opened, close FCV478] 21A Main Feedwater Reg Valve, in MANUAL OR AUTO to maintain 21A SIG level within 39% to 49% I STANDARD (Indicate "S" FOR SAT or "U" FOR I SfU I STARTTIME:

_______ EVALUATOR NOTE: Initialize IC-224, Put Steam Generator Wide Range Levels on trend up on BOP's PCS screen. Select "Trends" then select "SG Wide Range Level". Open MFRV isolation valve 2FWS-MOV154A.

1.1 Reviews

20M-52.4.R.l.F and Attach.

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

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

by depressing lower Maintains Feed Flow approximately equal to Verifies the Main Feed Reg Valve Green light -LIT, Red light-NOT COMMENTS:

1/2*ADM*1301.F04 Page 7 of8 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-072 JPM TITLE: Transfer from Main Feedwater Reg Valves to Bypasses JPM REVISION:

3 STEP ( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> [ SIU When S/G 21A Main Feedwater

3.1 Verifies

controller for 2FWS-FCV478 remains Reg Valve is fully closed, perform the

3.2 Locates

indicators and observes for evidence of Verify S/G 21A Main Feedwater past Reg Valve controller in 3.3 Closes 2FWS-MOV154A 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 21A Main Feed Reg Closes [2FWS-MOV154A], 21A S/G Main Feedwater Isol Vlv. 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 Place the controller for 2FWS-FCV479 in AUTO. If level 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 49%. MANUAL. Monitors AUTO operation of the valve to ensure it controls level between 39% and 49%. COMMENTS:

RTL#A5.640U 1I2-ADM-130 l.F04 Page 8 of8 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-072 lPM TITLE: Transfer from Main Feedwater Reg Valves to Bypasses JPM REVISION:

3 STEP STANDARD ( "C" Denotes CRITICAL STEP) (Indicate "s" FOR SAT or "U" FOR UNSAT)=> S/U I If level control is NOT stable, 5.1. If in MANUAL, using the auto/manual station for restore the valve controller to [2FWS-FCV479]

slowly adjusts valve controller to MANUAL AND maintain S/G control steam generator level between 39% and 49%. NR level between 39% and 49%. COMMENTS:

EVALUATOR CUE: That completes this lPM. STOP TIME: _______

RTL#A5.640U J/2-ADM-J301.F04 Page 3 of 10 Revision 1 JPM NUMBER: 2CR-622 JPM TITLE: Respond to Radiation Monitor Alarm JPM REVISION:

3 KIA

REFERENCE:

073A4.02 3.7/3.7 TASK ID: 0431-031-04-012 JPM APPLICATION:

['gJ REQUALIFICATION

['gJ INITIAL EXAM o TRAINING ['gJ FAULTED JPM o ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION:

TYPE: ADMINISTERED BY: ['gJ 0 Perform Simulate 0 ['gJ 0 Plant Site Simulator Classroom 0 0 0 0 0 Annual Requal Ex Initial Exam OJT/TPE Training Other: am 0 0 0 BVT NRC Other: EVALUATION RESULTS Performer Name: Performer SSN: Time 0 Yes Allotted Actual 20 Minutes minutes Critical:

['gJ No Time: Time: D SAT JPM RESULTS: D lTNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN:

Name/SSN:

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 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 High Level Alarm, Issue 1 Revision 20M-43.4.AAC Radiation Monitoring Level High, Revision 20M-43.4.AEB, Local-Leak Collection Ventilation

[2RMR High Level Alarm, Issue 1 Revision 20M-43.4.AAC Radiation Monitoring Level High, Revision RTL#A5.640U 1I2-ADM-130 l.F04 Page 5 of 10 Revision I CANDIDATE DIRECTION SHEET

• THIS SHEET TO BE GIVEN TO CANDIDATE

• DRead: You are to perform the task, Respond to a Radiation Monitor Alarm INITIAL Annunciator A4-5C "Radiation Monitor Level High" has just alarmed. INITIATING Your supervisor directs you to respond to the alarm using the appropriate Alarm Response Procedure.

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 " I have completed the Then hand this sheet to the evaluator.

RTL#A5.640U J/2-ADM-1301.F04 Page 6 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-622 JPM REVISION:

3 STEP ( "C" Denotes CRITICAL STEP 1. Obtain procedure.

(20M** 43A.AAC) JPM TITLE: Respond to Radiation Monitor Alarm STANDARD (Indicate "S" FOR SAT or "U" F'OR UNSA T)=> SIMULATOR Use HTML "JPM 2CR-622" to insert commands prevent damper swapping on HIGH radiation level to allow MANUAL re-positioning of the (Train A switch removes malfunction from MOD202A, Train B switch removes malfunction/rom 2HVS-MOD201B)

EVALUATOR When candidate is ready to begin JPM, PLACE simulator in START TIME: ________ EVALUATOR Steps 1 6 are required only if the candidate refers 20M-43A.AAC.

Steps 7 and beyond are to referenced for 20M-43A.AEB

1.1 Locates

copy of procedure 20M-43A.AAC EVALUATOR After candidate locates the procedure, the can provide a copy of 20M-43 A.AAC to RTL#A5.640U 1I2-ADM-130 l.F04 Page 7 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-622 JPM TITLE: Respond to Radiation Monitor Alarm JPM REVISION:

3 STEP I STANDARD ( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR Stu 2. Determine which

2.1 Depresses

the grid 6 pushbutton on the RM-Il monitor is in alarm at the RM-ll console. console. 2.2 Verifies 2GB042 is blinking and has turned red. COMMENTS:

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

the 4-digit numerical code number of the alarming monitor and select. COMMENTS: 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 alarm. keyboard.

COMMENTS:

RTL#A5.640U I 12-ADM-130 I.F04 Page 8 of 10 Revision I OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-622 JPM TITLE: Respond to Radiation Monitor Alarm JPM REVISION:

3 rf.TEP I STANDARD C'C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UN SAT)=> SIU 6. Verify if radiation level is greater 6.1 than 1000 times background.

If asked, role-play SM/US and inform the that 2RMR-RQI301 is NOT 1000 times normal background_

COMMENTS:

7. Determine 2RMR-RQI301 is in alarm and refers to local alarm response procedure for corrective actions. 7.1 7.2 Determines 2RMR-RQI301 (Leak Collection Ventilation Radiation Monitor) is in alarm. Refers to local alarm response procedure 43.4AEB) for corrective actions. EVALUATOR CUE: After candidate locates the procedure, the evaluator can provide a copy of 20M-43.4.AEB to candidate.

! COMMENTS:

8. At the RM-l1 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. I RTL#A5.640U II2-ADM-1301.F04 Page 9 of 10 Revision I OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-622 JPM TITLE: Respond to Radiation Monitor Alarm JPM REVISION:

3 STEP STANDARD ( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UN SAT)=> SfU 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 Determines that the actual value is higher than HIGH alarm COMMENTS:

10. Notify the SM and obtain directions.

10.1 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 (1.d., l.g., l.h., & COMMENTS:

EVALUATOR NOTE: FAULT STATEMENT In the next 2 steps (11 & 12), Dampers 2HVS*MOD201A 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" pos. to isolate the Ventilation Vent & align SLCRS.

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

3 STEP

("c" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UN 11.C Verify [2HYS*MOD201A]

11.1 Verifies [2HYS*MOD201A]

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*MOD20IA will NOT go closed. 2HYS*MOD201B will also remain open unless the "B" train CS was placed in "FILT" position).

COMMENTS: Verify [2HYS*MOD202A]

12.1 Verifies [2HYS*MOD202A]

and and [2HYS*MOD202B]

are [2HYS*MOD202B]

green lights -LIT and red lights OPEN. -NOT LIT (Only 2HYS*MOD202A will open, 2HYS*MOD202B will not open) 12.2C Places the Train B control switch to the FIL T position (2HYS*MOD201B will close when the "B" train CS is placed in "FIL T"). COMMENTS:

EVALUATOR Candidate should report to supervisor 2HYS*MOD20IAl202B did not change EVALUATOR That Completes this STOP TIME: _______

RTL#A5.640U 1I2-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 A2.11 4.4/4.7 TASK ID: 0011-014-01-013 001 AAl.05 4.3/4.2 0535-006-04-013 JPM APPLICATION:

[g] REQUALIFICATION

[g] INITIAL EXAM 0 TRAINING [g] FAULTED JPM o ADMINISTRA TIVE JPM EVALUATION METHOD: LOCATION:

TYPE: ADMINISTERED BY: [g] 0 Perform Simulate 0 [g] 0 Plant Site Simulator Classroom 0 0 0 0 0 Annual Requal Exam Initial Exam OJT/TPE Training Other: 0 0 0 BVT NRC Other: EV ALUA TION RESULTS I Performer Name: I Performer SSN: Time 0 Yes Allotted Actual 16 minutes Critical:

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

Comments:

OBSERVERS Name/SSN:

Name/SSN:

Name/SSN:

Name/SSN:

EVALUATOR Evaluator (Print): Date: Evaluator Signature:

RTL#A5.640U 112-ADM-130 1.F04 Page 4 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 "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-50A.D2 , beginning at Step IV.C.9, and stabilize power at 10-8 amps on IR indication.

20M-50A.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) 0:f20M-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-50.4.D2, Reactor Startup From Mode 3 to Mode 2. The following conditions exist:

• All shutdown bank rods are fully withdrawn.

• Control Bank "D" is at 91 steps.

• The estimated critical position is 100 steps on Control Bank "D". INITIATING 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 Step IV.C.9, and stabilize power at 10-8 amps on IR indication.

D At this time, ask the evaluator any questions you have on this JPM. D 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-1301.F04 Page 6 of 10 Revision]

OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-644 JPM TITLE: Raise Reactor Power To 10-8 Amps JPM REVISION:

2 STEP ( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSA SIMULATOR SETUP: Initialize IC-with Rods at 91 Steps Select FAST speed on NR-45 TROl XB2IOI6B=

=1 IMF CRF04B Uncontrolled Rod Motion Manual Verify CBD = 91 steps Power should be 6E-ll amps EVALUATOR NOTE: Provide Candidate with 11M Plot or cue that another operator is monitoring the data. STARTTIME:

_______ Reviews 20M-50.4.D2 and Data Sheet 3 of 20M-50.4.F (11M plot). WHEN the Inverse Count Rate Ratio is less than 0.25, Reduce rod withdrawal intervals to 25 step increments. (Step IV.C.9.b) Reviews 20M-50.4.D2 and 11M plot. Determines Inverse Count Rate Ratio is < 0.25. COMMENTS: Candidate initiates rod withdrawal at less than 25 step increments.

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

COMMENTS:

RTL#A5.640U 112-ADM-1301.F04 Page 7 of 10 Revision I OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-644 JPM TITLE: Raise Reactor Power To 10-8 Amps JPM REVISION:

2 ( "c" Denotes CRITICAL When Status Light Annunciator A12-3B "P6 Pennissive" is on (1 E-l 0 amps), Block the SR high flux trip by perfonning the following:

Record Source Range Neutron Level indicators:

[NI-NI-31A]

CPS [NI-NI-32A]

CPS Step IV.C.lO.a) De-energize the N31 SR High Voltage and block the Train A SR High Flux trip by perfonning the following.

Momentarily tum the switch, Source Range'A" Block to ..the BLOCK pOSItIon (BB-B). (Step IV.C.lO.b) De-energize the N32 SR High Voltage and block the Train B SR High Flux trip by perfonning the following.

Momentarily tum the switch, Source Range' B' Block to the BLOCK position (BB-B). STANDARD (Indicate "S" FOR SAT or "U" FORJ'NSAT)=>

Stu 2.l. Records SR counts for N31 and N32. COMMENTS: Places Source Range'A' Block to the BLOCK position.

COMMENTS: P1aces Source Range 'B' Block to the BLOCK position.

COMMENTS: (Step IV.C.lO.c)

RTL#A5.640U 112-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 ( "c" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UN SAT)=> Stu I Check that both source 5.1 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.IO.d) Verify that the detector 6.1 Verifies both Source Range DETECTOR VOLTS voltmeters on both source indicate approximately zero. range drawers indicate approximately zero volts. COMMENTS:

! (Step IV.C.IO.e)

7. Select both IR channels to 7.1 Places NI SYS RECORDER SEL SW IN45 and indicate on recorder NR-45. 2N45 to record IR channels N35 and N36. (Step IV.C.11) COMMENTS:

RTL#A5.640U 1/2-ADM-1301.F04 Page 9 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-644 JPM REVISION:

2 JPM TITLE: Raise Reactor Power To 10-8 Amps ("e" Denotes CRITICAL Continue incremental rod withdrawal until the reactor is critical as indicated by a stable positive startup rate with no rod motion, on the intermediate range instrumentation once the prompt jump has receded. (Step IV.C.12) Determine that rods are withdrawing with NO demand signal. I STANDARD (Indicate "s" FOR SAT or "U" FOR UNSAT)=> FAULT STATEMENT:

The following step the alternate path portion of the JPM.

blocking of the SR High Flux Trip, on the next withdrawal, the Rods will begin stepping out in uncontrolled 8.1 C Candidate continues withdrawing control rods obtain a stable startup EVALUATOR CUE: If asked, inform Candidate to withdraw rods at not more than 5 step increments to obtain a stable startup rate. COMMENTS: Candidate dletermines from CONTROL BANK GROUP 1 and GROUP 2 ROD POSITION that rods are withdrawing with NO demand COMMENTS:

RTL#A5.640U 1!2-ADM-130 I.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 ( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR Trip the reactor in response 10.1 e 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#A5.640U 1!2-ADM-130 1.F04 Page 3 of 10 Revision 1 JPM NUMBER: 2CR-654 JPM TITLE: Isolate SI Accumulators During a LOCA JPM REVISION:

2 KIA

REFERENCE:

009 EAl.13 4.4/4.4 TASK ID: 0111-011-01-013 JPM APPLICATION:

[8J REQUALIFICATION

[8J INITIAL EXAM D TRAINING [8J F AUL TED JPM ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION:

TYPE: ADMINISTERED BY: [8J Perform Plant Site D Annual Requal Exam D BVT D Simulate Simulator D Initial Exam D NRC D Classroom D OJT/TPE D Other: D Training D Other: EV ALUA TION RESULTS Performer Name: Performer SSN: Time D Yes Allotted Actual 15 Minutes minutes Critical:

[8J No Time: Time: D SAT JPM D UNSAT (Comments required for UNSAT Comments:

OBSERVERS Name/SSN:

Narne/SSN:

Evaluator (Print): Evaluator RTL#A5.640U TASK STANDARD:

RECOMMENDED STARTING LOCATION:

DIRECTIONS:

INITIAL CONDITIONS:

INITIATING CUE:

REFERENCES:

TOOLS: HANDOUT: 1 12-ADM-130 I.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-l.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 Step 20M-53 .A.l.ES-I.2, Post LOCA Cooldown and Issue I C, Rev. 20M-It.4.G, Venting A Safety Injection Accumulator, Rev. 20M-53A.1.A-5.l, OF Plus Subcooling Based On Core Exit TCs, rev Three Shorting 20M-53.A.l.ES-1.2, Post LOCA Cooldown and Issue 1 C, Rev. 10, place kept up to step 20M-l1.4.G, Venting A Safety Injection Accumulator, Rev. 20M-53A.l.A-5.l, OF Plus Subcooling Based On Core Exit TCs rev.

RTL#A5.640U 1/2-ADM-1301.F04 Page 5 of 10 Revision I 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-I.2, Post LOCA Cool down and Depressurization.

INITIATING The Unit Supervisor directs you to isolate the SI accumulators in accordance with ES-l.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 "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-J30 1.F04 Page 6 of \0 Revision 1 OPERA TIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-6S4 JPM REVISION:

2 ("e" Denotes CRITICAL 1. Review procedure.

JPM TITLE: Isolate SI Accumulators During a LOCA (Indicate "S" FOR SAT or "U" FOR UNSAT):::::>

SIMULATOR SETUP: Initialize simulator to any Mode I Insert SBLOCA @ 500 Progress through EOP set up until Step 27 PZR Level needs to be > 17% and RCS Subcooling to be > 41 F (non adverse Insert VL V -SIS068 (override SIS*MOV865C in the NOTE: This JPM takes significant setup work requires careful attention to C/O rate, AFW flowrate other dynamic EVALUATOR NOTE: RCS pressure may drop low enough to begin injecting accumulators.

Ensure Shorting Bars are available.

START TIME: _______ Reviews 20M-S3A.l.ES-l.2, Post LOCA Cooldown and Depressurization.

COMMENTS:

2. RCS subcooling based on core exit TCs -GREATER THAN SUBCOOLING LISTED ON ATTACHMENT A-S.l. 2.1 2.2 2.3 Verifies RCS subcooling on VB-B (2RCS*YIOOI or 2RCS*YROOI) or the PCS. Compares existing value to Attachment A-S.l. Determines existing RCS subcooling is GREATER than Attachment A-S.I minimum required value. COMMENTS:

RTL#A5.640U 1/2-ADM-130 I.F04 Page 7 of 10 Revision)

OPERATIONS JOB PERFORMANCE MEASURE I JPM NUMBER: 2CR-654 JPM TITLE: Isolate SI Accumulators During a LOCA JPM REVISION:

2 I STANDARD ( "e" Denotes CRITICAL (Indicate "S" or "U" '-.}NSAT)=>

I SfU 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, C] red lights -LIT and C] -AVAILABLE.

green lights -NOT LIT. COMMENTS:

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

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

jack. 5.4 Inserts into [2SIS*MOV865C]

jack.

I RTL#A5.640U 1/2-ADM-1301.F04 Page 8 of 10 Revision I OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-654 JPM REVISION:

2 JPM TITLE: Isolate SI Accumulators During a LOCA ( lie" Denotes CRITICAL Close [2SIS*MOV865A, B, C]. Vent any unisolated accumulator.

Refer to 11.4.G, "Venting A Safety Injection Accumulator".

I STANDARD (Indicate "S" FOR SAT or "u" FOR I S/U ! FAULT Alternate path hegins here: [2SIS*MOV865C] NOT CLOSE in the following EVALUATOR Accumulator isolations may be done in any Places [2SIS*MOV865A, B, C] CS to CLOSE. Verifies Green lights -LIT and Red lights LIT for [2SIS*MOV865A, Verifies Red light LIT and Green light NOT for COMMENTS: Refers to 20M-l1.4.G to vent 2SIS*TK21C.

EVALUATOR If necessary, Role-play the Unit Supervisor and the Candidate to perform Section F for direct venting COMMENTS:

RTL#A5.640U 1I2-ADM-130 1.F04 Page 9 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-654 I JPM REVISION:

2 JPM TITLE: Isolate SI Accumulators During a LOCA ( "C" Denotes CRITICAL 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.

1 (101-2), SI ACC Nitrogen Makeup Outside (Inside) Cnmt Isol Vlv. 1O.C Open [2GNS*SOV853A(D)

(853B (E)) (853C (F))] 21A (B) (C) SI Accumulator Nitrogen Makeup Vlv. 11.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" T or "U" FOR UNSAT):::>

I Stu I 8.1 No action required.

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

10.1C Places [2GNS*SOV853C OR F] CS to OPEN. Verifies Red light LIT and Green light NOT LIT. COMMENTS:

11.1 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 J/2-ADM-1301.F04 Page 10 of 10 Revision I OPERATIONS JOB PERFORMANCE MEASURE

• JPM NUMBER: 2CR-654 I JPM REVISION:

2 JPM TITLE: Isolate SI Accumulators During a LOCA "S" FOR SAT or "U" FOR UNSAT)=> EVALUATOR CUE: When accumulator pressure begins to lower, That completes this STOP TIME: _______

RTL#A5.640U 1I2-ADM-130 l.F04 Page 3 of II Revision 1 OPERATIONS JOB PERFORMANCE MEASURE (JPM) JPM NUMBER: 2CR-581 JPM TITLE: Perform Manual Makeup to the Charging Suction JPM REVISION:

6 KIA

REFERENCE:

004A4.12 3.8/3.3 TASK ID: 0071-025-01-013 JPM APPLICATION:

[g] REQUALIFICATION k8J INITIAL EXAM D TRAINING [g] FAULTED JPM ADMINISTRA TIVE JPM EV ALUA TION METHOD: LOCATION:

TYPE: ADMINISTERED BY: Perform Plant Site D Annual Requal Exam D BVT D Simulate Simulator D Initial Exam D NRC D Classroom D OJT/TPE D Other: D Training D Other: EVALUATION RESULTS Performer Name: Performer SSN: Time D Yes Allotted Actual 15 Minutes minutes Critical:

[g] No Time: Time: D SAT JPM RESULTS: D UNSAT (Comments required for UNSAT OBSERVERS Name/SSN:

Name/SSN:

Name/SSN:

Name/SSN:

EVALUATOR Evaluator (Print): Date: Evaluator Signature:

1 RTL#A5.640U 1/2-ADM-1301.F04 Page 4 of 11 Revision 1 OPERA TIONS lOB PERFORMANCE MEASURE (lPM) JPM NUMBER: 2CR-581 JPM REVISION:

6 TASK STANDARD:

RECOMMENDED STARTING LOCATION:

DIRECTIONS:

INITIAL CONDITIONS:

INITIATING CUE:

REFERENCES:

TOOLS: HANDOUT: JPM TITLE: Perform Manual Makeup to the Charging Suction EVALUATOR DIRECTION SHEET Perform control board manipUlations and calculations to perform manual blender makeup to the VCT in accordance with "Blender Manual Makeup Makeup secured after discovery of no boric acid Perform a manual makeup to the Charging Pump

• 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.

Your supervisor directs you to raise VCT level to 42% at 75 gpm, by performing 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-130 l.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 manual 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 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 O PERATIONS JOB PERFORMAN 1I2-ADM-130 l.F04 Page 6 of 11 Revision 1 CE MEASURE JPM NUMBER: 2CR-581 . JPM REVISION:

6 I JPM TITLE: Perform Manual Makeup to the Charging Suction EVALUATOR NOTE: This is a F AUL TED 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 liS" FOR SAT or "U" FOR UNSAT)=> START TIME: ________ EVALUATOR NOTE: Simulator -Any Mode 1 -Expert command to set vcr level to 22%:

-Mark in service BAST 7487 PPM; (RCS Set BA & Total flow totalizers to To fai12CHS*FCV113A as-is (shut), go to Valves and select VLV-BATOIO, Select O-Fail As Set 2CHS*FCVl14A 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. COMMENTS:

RTL#A5.640U 1I2-ADM-I301.F04 Page 7 of II Revision 1 OPERA TJONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-581 JPM TITLE: Perform Manual Makeup to the Charging Suction JPM REVISION:

6 STEP STANDARD ( "e" Denotes CRITICAL STEP) (Indicate "s" FOR SAT or "u" FOR UNSA T)=> StU EV ALVATOn. CUE: If asked, provide BAST boron of7487 ppm and RCS boron of 1460 ppm. 3.C Determine desired boric acid 3.1C Calculates boric acid flow: flow. 1460ppmX75gpm

= 14.62gpm 7487ppm COMMENTS: Adjust [2CHS*FCVl13A]

4.1 C Calculates the desired flow setpoint:

Boric Acid to Blender to the calculated setpoint.

_--=-:gp=--m xIOO = 366 4gpm Adjusts [2CHS*FCVl13A]

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

RTL#AS.640U 1I2-ADM-1301.F04 Page 8 of 11 Revision I OPERA TIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-S81 JPM TITLE: Perform Manual Makeup to the Charging Suction JPM REVISION:

6 STEP STANDARD ("c" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "V" FOR VNSAT)===>

S/u Set Boric Acid Flow to S.IC Adjusts [2CHS-FQ IS 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 of BA volume for the batch amount. If perfmming full makeup (280 gals) then the amount ofBA is: 14.62 gpm X (280gals / 7S gpm) = 54.6 gal. COMMENTS:

6.C Adjust [2CHS*FCV]

14A] 6.1C Adjusts [2CHS*FCVl14A]

for 75 gpm, setpoint.

(75 gpm/16) xlOO 468 units +/-5 units. COMMENTS: i RTL#A5.640U 1I2-ADM-130 I.F04 Page 9 of 1] Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-581 JPM TITLE: Perform Manual Makeup to the Charging Suction JPM REVISION:

6 STEP I STANDARD ( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "u" FOR UNSAT::::>

SIU 7.C Set [2CHS-FQIS168]

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-FQISI68.

water to be added. EVALUATOR NOTE: Batch amounts are at the operator's discretion.

Total volume change is approximately 280 gallons COMMENTS:

8. Adjust [2CHS*HIC168]

8.1 Adjusts

[2CHS*HIC168]

to 75 gpm, Blender Total Flow Auto (75 gpml16) x 100 = 468 units +/-5 units. Setpoint.

COMMENTS:

9. Note flow totalizer indication

9.1 Notes

the Boric Acid Flow to Blender Flow Totalizer and adds it to the gallon set on the batch integrators for 2CHS*FQISl13 and 2CHS*FQIS168.

9.2 value

on 2CHS*FQISI13 and adds the Boric Acid volume previously calculated (54.6 gallons) Notes the Blender Total Flow value on 2CHS*FQISI68 and adds the Total Volume previously calculated (280 gallons) COMMENTS:

RTL#A5.640U OPERATIONS JOB PERFORMANCE I12-ADM-130 l.F04 Page 10 of 11 Revision 1 MEASURE 4 JPM NUMBER: 2CR-581 I JPM REVISION:

6 JPM TITLE: Perform Manual Makeup to the Charging Suction STEP I STANDARD ( "e" Denotes CRITICAL STEP) (Indicate "s" FOR SAT or "U" FOR UNSA T)=> SIV 10. Verify a Reactor Coolant 10.1 Verifies that RCS flow is ;::: 3000 gpm flow by Pump is operating in an observing Rep operation or flow indicvations.

unisolated loop and has;::: 3000 gpm flow through the 10.2 Records information in the Narrative Log. core and records the commencement of makeup and flow verification in the Narrative Log. EVALUATOR CUE: Inform the candidate that another operator will make the Narrative Log entry. COMMENTS:

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

12.C Open [2CHS*FCVl13B], 12.1C Places [2CHS*FCVI13B]

control switch to OPEN Boric Acid Blender Disch to position.

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

13.C Place Mode Selector in I3.IC Places the Mode Selector Switch in MAN position.

MAN. (BB-A) COMMENTS:

RTL#A5.640U l!2-ADM-I30 l.F04 Page 11 of II Revision I OPERATIONS JOB PERFORMANCE MEASURE j JPM NUMBER: 2CR-581 I JPM REVISION:

6 JPM TITLE: Perform Manual Makeup to the Charging Suction STEP STANDARD ( "c" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> S/U Place Boric Acid Makeup 14.1 C Places Boric Acid Makeup Blender Control switch to Blender Control switch to START position.

Start.. Verifies Boric Acid Transfer Pump that is in AUTO starts Red Light LIT, Green Light -NOT LIT. COMMENTS:

FAULT STATEMENT:

Alternate path begins here. Candidate must take manual action to secure dilution after discovering that no boric acid flow exists. It is expected that the operator will recognize and terminate w/in -1 min level rise) IS.C Verify proper operation at IS.1 Verifies Boric Acid to Blender and Total MIU Flow recorder [2CHS-FRl13]

From on [2CHS-FRlI3]. (VB-A). IS.2 Recognizes boric acid flow is Zero (0) GPM. lS.3C Places Boric Acid Makeup Control Switch to STOP position prior to VCT level reaching 28%. COMMENTS:

EVALUATOR CUE: That completes this JPM. STOP TIME:

RTL#A5.640U 1I2-ADM-130 l.F04 Page 3 of 10 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-597 JPM TITLE: Transfer Bus 2AE from Emergency to Normal Feed/Bus 2A JPM REVISION:

0 KIA

REFERENCE:

064A2.09 3.113.3 TASK ID: 0362-007-01-013 JPM APPLICATION:

k8J REQUALIFICATION k8J INITIAL EXAM o TRAINING FAULTED JPM D ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION:

TYPE: ADMINISTERED BY: L8J Perform D Plant Site D Annual Requal Exam L8J BVT 0 Simulate L8J Simulator L8J Initial Exam D NRC D Classroom 0 OJT/TPE D Other: 0 Training D Other: EVALUATION RESULTS Performer Name: Performer SSN: Time Critical:

0 Yes L8J 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:

Name/SSN:

Name/SSN:

EVALUATOR Evaluator (Print): Date: Evaluator Signature:

RTL#A5.640U 1/2-ADM-130 l.F04 Page 4 of 10 Revision 0 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 2A 1 0 has spuriously tripped open. All normal 4 KV busses are energized from USSr's 2C and 2D. The 2-1 EDG is running and carrying loads on the 2AE Bus. The 4KV normal to emergency tie breakers, 2AtO 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-1301.F04 Page 5 of 10 Revision 0 OPERA nONS JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET

• THIS SHEET TO BE GIVEN TO CANDIDATE

• DRead:

You are to Transfer Bus 2AE from Emergency to Normal Feed/Bus 2A. INITIAL Breaker 2AlO has spuriously tripped open. All norma14KV busses are energized from USSr's 2C and 2D. The 2-1 EDG is running and carrying loads on the 2AE Bus. The 4KV normal to emergency tie breakers, 2AlO and 2E7, are open. The relay crew has replaced a defective relay on breaker 2AlO. INITIATING 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 .TPM. 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#AS.640U 1I2-ADM-130 I.F04 Page 6 of 10 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-597 JPM TITLE: Transfer Bus 2AE from Emergency to Normal Feed/Bus 2A JPM REVISION:

0 STANDARD (Indicate "S" FOR SAT or "U" FOR UNSA T => START TIME: _______ EVALUATOR NOTES: Insert BKR-HIVOI to trip 2AIO, wait for DIG sequencer to complete, then clear BKR-HIVOl, allow plant to stabilize.

Make annunciator A8-4C alarm when EDG load is <= 1000 KW by setting Trigger I as XX8D014M <= 1000 with command as Ensure Sync Scope rotating in SLOW direction.

IMF AS-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 2Al 0, 4KV 2.1 C Places breaker 2Al 0 control switch in the CLOSE Bus 2A to Emergency Bus position.

2AE. Verifies the RED light above breaker 2AIO control switch LIT and WHITE Light NOT LIT. EVALUATOR CUE: Act as another operator and perform the independent verification.

COMMENTS:

RTL#A5.640U 1/2-ADM-1301.F04 Page 7 of 10 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-597 JPM TITLE: Transfer Bus 2AE from Emergency to Normal Feed/Bus 2A JPM REVISION:

0 I STANDARD ("e" Denotes CRITICAL (Indicate "S" FOR SAT or "U" FOR UNSA T)=> Stu Place the 2-1 Diesel 3.1C Places 2-1 EMERG GEN SYNCHRONIZING SEL Generator synchronizing SW in the Bus 2A position.

switch in the Bus 2A position. , COMMENTS:

4.C Adjust 2-1 EDG until the synchroscope needle is rotating in the SLOW DIRECTION.

4.1 4.2C Observes the 2-1 Emergency Diesel Generator synchroscope 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.

4.3 Verifies

the synchroscope rotating slowly in the fast direction.

COMMENTS: I RTL#A5.640U 1I2-ADM-130 l.F04 Page 8 of 10 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-597 JPM TITLE: Transfer Bus 2AE from Emergency to Normal Feed/Bus 2A JPM REVISION:

0 STEP I STANDARD ( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> S/U Adjust 2-1 Diesel Generator

5.1 Locates

2-1 EM ERG GEN VOLTS meter and voltage to be slightly higher compares it to 4KV Bus 2A VOLTS meter. than Bus 2A voltage by using voltage adjust switch. 5.2. Verifies Diesel Generator volts slightly higher than bus volts and adjusts Emergency Generator 2-1 Voltage. COMMENTS:

6.C Close breaker 2E7 when synchroscope, rotating SLOWL Y in FAST DIRECTION.

6.1 6.2C Monitors th::! 2-1 Emergency Diesel Generator synchroscope on the Vertical Board. Momentarily places breaker 2E7 control switch in the CLOSE position when the synchroscope is at the 12 o'clock. 6.3 Verifies the RED light above breaker 2E7 control switch LIT and WHITE light NOT LIT. COMMENTS:

7. Place the 2-1 EDG 7.1 Places 2-1 EMERG GEN SYNCHRONIZING SEL synchronizing Switch in SW in the OFF position.

OFF. COMMENTS:

RTL#A5.640U 112-ADM-130 1.F04 Page 9 of 10 Revision 0 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 CRlTICAL 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 (Indicate "S" FOR SAT or "U" FOR SIU I Adjusts 2-1 EMERG GEN VOL TGE ADJUST as needed to maintain between 0.8 and 1.0 lagging PF as indicated on Power Factor meter on VB-C. COMMENTS:

F AUL T STATEMENT:

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

alarm DO 2-1 DIFF will also be received.

should respond to ARP and Trip the 2-1 EDG open ACB 2EIO which failed to automatically Intermittently places the 2-1 EMERG OEN 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 WATTS Intermittently places the 2-1 EMERG GEN VOLT ADJUST switch in LOWER. COMMENTS:

! I RTL#A5.640U l/2-ADM-130 1.F04 Page 10 of 10 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-597 JPM TITLE: Transfer Bus 2AE from Emergency to Normal Feed/Bus 2A JPM REVISION:

0 STEP I ( "c" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "u" FOR 10. Annunciator AS-4C, 10.1 Acknowledges the alarm and responds by "DIESEL GEN 2-1 reviewing the ARP for AS-4C. ELECTRICAL FAULT", alarms due to 2-1 DO 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 AS-4C once it is located. 11.Trips 2-1 EDG and manually 11.1 Momentarily places breaker 2E 10 control switch in opens output breaker 2EI0. TRIP. Verifies the WHITE light above breaker 2EI0 control switch is ON. Manually Trips EDG 2-1 by pushing the stop pushbuttons. Verifies EDG 2-1 is tripped by observing decreasing 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. STOP TIME: ________

RTL#A5.640U 112-ADM-130 1.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 KJA

REFERENCE:

026 A2.03 4.114.4 TASK ID: 0011-066-01-013 026 A2.04 3.9/4.2 JPM APPLICATION:

IZI REQUALIFICATION 1:8J INITIAL EXAM D TRAINING IZI FAULTED JPM [J ADMINISTRATIVE JPM EV ALUATION METHOD: LOCATION:

TYPE: ADMINISTERED BY: IZI Perform D Plant Site D Annual Requal 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 Performer SSN: Time Critical:

D IZI Yes No Allotted Time: 10 Minutes Actual Time: minutes JPM RESULTS: D D SAT UNSAT (Comments required for UNSA T evaluation)

Comments:

OBSERVERS Narne/SSN:

Name/SSN:

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: I12-ADM-130LF04 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 "Verification Of Automatic Actions", Step 7 to check CIB Containment Spray 20M-53A.l.A-O.ll , "Verification Of Automatic Actions", Issue Rev. 20M-53A.1.A-O.5, "Containment Isolation Phase B Checklist", IC, Rev. 20M-53A.1.A-O.ll , "Verification Of Automatic Actions", Issue Rev. 6, place kept up to step 20M-53A.I.A-O.5, "Containment Isolation Phase B Checklist", IC, Rev.

RTL#A5.640U 1/2-ADM-1301.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 "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 tl2-ADM-130 I.F04 Page 60f 10 Revision 1 OPERA TIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-656 I JPM REVISION:

0 STEP ( "C" Denotes CRITICAL STEP 1. Reviews procedure.

JPM TITLE: Containment Spray Manual Actuation-SWS and QSS Valve Malfunctions "S" FOR SAT or "U" FOR UNSA T)=> SIMULATOR 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*MOV106A VLV-SWS028(1)

Close XAlI084C 2SWS*MOVI03A VLV-SWS018(2)

Open XAII102P 2SWS*MOVI06B VLV-SWS029(1)

Close XA2I068C 2SWS*MOVI03B VLV-SWS019(2)

Open XA2I081P Allow sim 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.1.A-O.ll, "Verification Of Automatic Actions".

COMMENTS:

RTL#A5.640U 1I2-ADM-I30 l.F04 Page 70f 10 Revision I OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-656 JPM TITLE: Containment Spray Manual Actuation-SWS and QSS I JPM REVISION:

° Valve Malfunctions STEP STANDARD ( "e" Denotes CRITICAL STEP) (Indicate "s" FOR SAT or "V" FOR Stu Containment pressure -HAS 2.1 Determines that containment pressure has REMAINED LESS THAN 11 remained less than 11 psig by checking any of PSIG. AI-2H, "CONTAINMENT ISOLATION PHASE B" in alarm. 2LMS*PR950, Containment Pressure Recorder indicates greater than 11 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 CIB marks -LIT. 3.1 Checks components properly aligned and CIB components not positioned as required, and NOT COMMENTS:

RTL#A5.640U 1/2-ADM-130I.F04 Page 80f 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-656 JPM TITLE: Containment Spray Manual Actuation-SWS and QSS I JPM REVISION:

0 Valve Malfunctions STEP I STANDARD ( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR SIU FAULT STATEMENT

/ EVALUATOR NOTE: Either train switches may be actuated first, only "B" train switches will actuate. 2SWS*MOVI 03(s) and 2SWS*MOV106(s) will not automatically actuate. IF NOT, THEN manually 4.1 Simultaneously ROTATES (Clockwise) both initiate CIB (both switches for "A" CIB switches to ACTUATE both Simultaneously ROTATES (Clockwise) both Train "B" CIB switches to ACTUATE position.

COMMENTS:

Check BLUE CIB marks -LIT. Candidate checks all indicating lights with BLUE CIB marks LIT. Determines 2SWS*MOVI06A / B and 2SWS*MOV103A / B not aligned. EVALUATOR If requested, provide Candidate a copy of COMMENTS:

RTL#A5.640U 1I2-ADM-130 l.F04 Page 90f 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-656 JPM TITLE: Containment Spray Manual Actuation-SWS and QSS I JPM REVISION:

0 Valve Malfunctions STEP STANDARD ( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> SfU IF CIB NOT actuated, JHEN 6.1C Places 2SWS*MOVI06A control switch to manually align equipment. necessary, refer to Attachment

6.2 Verifies

GREEN light -LIT and RED light -A-0.5, "Containment Isolation Phase B Places 2SWS*MOVI03A control switch to OPEN. Verifies RED light -LIT and GREEN light -NOT LIT. Places 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:

112-ADM-130 1.F04 Page 100f lO Revision 1 OPERA TIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-656 I JPM REVISION:

0 ( "e" Denotes CRITICAL 7.C Stop all RCP's. JPM TITLE: Containment Spray Manual Actuation-SWS and QSS Valve Malfunctions STANDARD (1ndicate "S" FOR SAT or "U" FOR UNSAT)=> Places control switches for 2RCS*P21A, 21B and 21C to STOP. Verifies 2RCS*P21A, 21B and 21C pump RED lights NOT LIT and WHITE lights LIT. Verifies 2RCS-FI414 (415)(416);

2RCS-FI424 (425)(426);

2RCS-FI434 (435)(436) flows dropping.

7.4 Verifies

2RCS-II21A(B)(C) amps dropping.

COMMENTS:

EVALUATOR CUE: That completes this JPM. STOP TIME: ________

RTL#A5.640U 1I2-ADM-130 l.F04 Page 3 of 12 Revision I 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 JPMAPPLICATION:

[8J REQUALIFICATION

[g] INITIAL EXAM D TRAINING [8J FAULTED JPM D ADMINISTRATIVEJPM EV ALUA TION METHOD: LOCATION:

TYPE: ADMINISTERED BY: [g] Perfonn Plant Site Annual Requal Exam D D Simulate [8J Simulator D Initial Exam D D Classroom D OJT/TPE D Other: D Training D Other: EVALUATION RESULTS Performer Name: Perfonner Time D Yes Allotted 25 Minutes minutes Critical:

[8J No Time: Time: D SAT JPM D UNSAT (Comments required for UNSAT Comments:

OBSERVERS Name/SSN:

Name/SSN:

Name/SSN:

Name/SSN:

EVALUATOR Evaluator (Print): Evaluator I

RTL#A5.640U 1/2-ADM-1301.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: 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 ofRHS.

• 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-I0.4 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-I0.4.B, Parts D & E Revision 30 20M-53C.4.2.1

0.1 revision

11 None 20M-I0.4.B 20M-IO.5 VOND (Only if requested) 20M-53C.4.2.IO.1 revision 11 DO NOT Provide to candiadate Allow candidate to use Simulator copy and then replace after each use.

RTL#A5.640U 1I2-ADM-130 l.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 of RHS. 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 verity 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 12 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-636 JPM TITLE: Swap RHS Trains JPM REVISION:

2 STEP I STANDARD ( "e" Denotes CRITICAL STEP) (Indicate "s" or "U" FOR UNSAT EVALUATOR NOTE: This is a EVALUATOR NOTE: Simulator FAULTED JPM. The candidate is Ini1IC-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 JAW 20M-JO.4.B Part pumps. Close 2RHS*MOV720B and Set P LP RTC J =10. Balance Charging and Letdown via 2CHS*FCVJ22 and 2CHS*HCV 142. START TIME: _______ Reviews procedure.

1.1 Reviews

Section D, "To Place RHS Train Bin Service From A Standby Condition" of20M-1O.4.B.

COMMENTS:

EVALUATOR CUE: If asked, inform the candidate that AS ME 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)( 100C) >50°F. >50°F. COMMENTS:

RTL#A5.640U 1!2-ADM-130 I.F04 Page 7 of 12 Revision 1 OPERA nONS lOB PERFORMANCE MEASURE lPM NUMBER: 2CR-636 lPM TITLE: Swap RHS Trains lPM REVISION:

2 STEP I STANDARD ( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> SfU Check RCS temperature.

3.l. Determines RCS/RHS temperature>

120F. Places control switch to open for 2CCP*MOV112B, RHR PP SEAL CLR 22B & HX21B COOLING WATER INLET VL V 3.3 Verifies Red Light -LIT and Green Light -NOT LIT. COMMENTS: Align RHS valves. 4.1 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. Checks CLOSED [2RHS*MOV750B].

Verifies Red NOT Light -LIT and Green Light LIT. CLOSES [2RHS*HCV758B], demand at 100%. Checks OPEN [2RHS*MOV720B], Red light lit, Green light not lit. COMMENTS:

RTL#A5.640U 1I2-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 I STANDARD ( "c" Denotes CRITICAL (Indicate "s" FOR SAT or HU" FOR I Stu Monitor RHR Hx DitfTemp.

5.1 Monitors

RHR Hx DiffTemp on [2RHS*TR604B]

andlor (T0630A) .

• COMMENTS:

6. Vent [2RHS*P21B]. Determines 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 monitor:lng 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:

RTL#A5.640U 1I2-ADM-130 l.F04 Page 9 of 12 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPMNUMBER:

2CR-636 JPM TITLE: Swap RHS Trains JPM REVISION:

2 ("c" Denotes CRITICAL Verify RHS temperature is within limits then start [2RHS*P21B]. If required, maintain PRZR pressure between 275 and 350 psig by the following methods. Adjust RHS system flow. STANDARD (Indicate "S" FOR S;;(lf "U" FOR UNSAT)=> I S/U I Verifies RCS and RHS temperature indications on PCS or recorders, that temperature differential is 50 of or RHS temperature rate of increase is < 5 of/Hr. EV ALVA TOR NOTE: Candidate may have previously verified temperature is within limits. Starts [2RHS*P21Bl COMMENTS: Marks step 16 as N/ A. EV ALVATOR CVE: RCP operation is required at this time. You do NOT have to pressure, step 16 is N/ COMMENTS: Throttles

[2RHS*FCV605B]

OPEN to establish a flowrate <4000 GPM as indicated on [2RHS *FI605B].

COMMENTS:

RTL#A5.640U 1I2-ADM-1301.F04 Page 10 of 12 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER:. 2CR-636 JPM TITLE: Swap RHS Trains I JPM REVISION:

2 I STANDARD ("e" Denotes CRITICAL (Indicate "S" FOR SAT or "U" FOR UNSAT)=> SIU Transfer [2RHS*FCV605B]

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

EVALUATOR NOTE: RCS temperature is greater than 120 OF, step 19.a-fis N/A. Maintain RCS temperature, 12.1 Throttles

[2RHS*HCV758B]

to maintain RCS verify flow is controlled in temperature.

AUTO. Verify [2RHS*FCV605A1605B]

modulate in AUTO to maintain RHS flow on 2RHS*FI605A1 B]. OPENS [2RHS*MOV750B].

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*MOV750B].

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-J30 l.F04 Page 11 of 12 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-636 JPM REVISION:

2 JPM TITLE: Swap RHS Trains STEP STANDARD ( "e" Denotes CRITICAL STEP) (Indicate "s" FOR SAT or "UI! FOR UNSAT)=> Stu Locate procedure.

13.1 Transitions to procedure Section E, To Place RHS Train A in Standby. COMMENTS: Check [2RHS*P21A]

14.lC STOPS [2RHS*P21A].

stopped. CLOSES [2RHS*MOV750B].

Verifies Red Light NOT LIT and Green Light-EVALUATOR NOTE: LIT.Alternate path [2RHS*FCV605B]

will SIMULATOR OPERATOR CUES: After fully open and after full open, candidate secures [2RHS*P21A], ramp OPEN [2RHS*P21B]

will trip. [2RHS*FCV605B]

and after full open, trip Candidate is expected to [2RHS*P21B].

[2RHS*P21B]

also will not transition to AOP 2.10.1. restart. COMMENTS:

1/2-ADM-130 I.F04 Page 12 of 12 Revision I OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-636 JPM TITLE: Swap RHS Trains JPM REVISION:

2 STANDARD " Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "Uti FOR UNSAT)=> Transition to AOP 2.10.1. 15.1 May attempt to restart [2RHS*P21A]. May attempt to restart [2RHS*P21B]. May refer to annunciator AI-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*HCV758A], demand at 100%. CLOSES [2RHS*FCV60SA]

demand at zero. Verifies CLOSED [2CHS*HCV142], demand at zero. 15.5C Restarts 2RHS-P21A.

EVALUATOR CUE: After 2RHS-P21A is restarted, state; "That completes this IPM", COMMENTS:

STOP TlME: _______

RTL#A5.640U 1/2-ADM-1301.F04 Page 3 of9 Revision I OPERATIONS JOB PERFORMANCE MEASURE I JPM NUMBER: 2PL-167 JPM TITLE: Align Service \Vater to [2FWE*P23B]

Motor Driven JPM REVISION:

0 Auxiliary Feed Pump Suction KIA 061Kl.07 3.6/3.8 TASK ID:

061A1.04 3.9/3.9 JPM APPLICATION:

[gJ REQUALIFICATION

!:sJ INITIAL EXAM [gJ TRAINING D ADMINISTRATIVE JPM EV ALUA TION METHOD: LOCATION:

TYPE: ADMINISTERED BY: D Perform Plant Site D Annual Requal Exam D BVT [gJ Simulate D Simulator D Initial Exam D NRC D Classroom D OJT/TPE D Other: D Training Other: EVALUATION RESULTS Performer Performer SSN: Time D Yes Actual 15 minutes Critical:

No Time:D SAT JPM D UNSAT (Comments required for UNSAT Comments:

OBSERVERS Name/SSN:

Name/SSN:

EVALUATOR Evaluator Date: Evaluator Signature:

I RTL#A5.640U 112-ADM-130 I.F04 Page 4 of9 Revision]

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 vented and aligned to [2FWE*P23B]

Motor Driven Auxiliary Feed 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-I, "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*LIl04Al]

and [2FWE*LII04A2]

both indicate 20". Both Demineralized Water Pumps [2WTD-P23A and B] are unavailable, and [2WTD-TK23] is also unavailable. [2SWS*MOV103B]

Recirc. Spray HXs Service Water Sup "B" Isolation Valve has been verified OPEN. S/G 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-L8, "Makeup to PPDWST [2FWE*TK210]", Rev. Keys 20M-53A.l.A-1.8, "Makeup to PPDWST [2FWE*TK21 0]", Rev. place kept up to step Ops Manual Figure 24-3 (provide if RTL#A5.640U 1/2-ADM-1301.F04 Page 5 of9 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-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*LII04AI]

and [2FWE*LI104A2]

both indicate 20". Both Demineralized Water Pumps [2WTD-P23A and B] are unavailable, and [2WTD-TK23] is also unavailable. [2SWS*MOV103B]

Recirc. Spray HXs Service Water Sup "B" Isolation Valve has been verified OPEN. SIG Pressure is approximately 400 psig. INITIATING Your supervisor directs you to supply [2FWE*P23B]

Motor Driven Auxiliary Feed Pump suction from Service Water by completing EOP Attachment A-1.8 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 ttl 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 !II have completed the Then hand this sheet to the evaluator.

RTL#A5.640U 1I2-ADM-130 l.F04 Page 6 of9 Revision I OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-167 JPM TITLE: Align Service \Vater to [2FWE*P23BJ Motor Driven JPM REVISION:

0 Auxiliary Feed Pump Suction STANDARD (Indicate "S" FOR SAT or "u" FOR UNSAT):::::>

I SIU I START TIME: _______ EVALUATOR CUE: Provide a procedure copy. Inform the candidate that you will role play any personnel they are required to interact with. 1. IF PPDWST Level Drops to 25 inches, THEN align Service Water to the Auxiliary Feedwater Pumps by performing the following:

If Containment Isolation Phase B has NOT occurred, then perform the following:

1.1 Recognizes

from the Initial Conditions that CIB has occurred and performance of this step is not required.

COMMENTS:

Close [2SWS*MOVI04B]

Close [2SWS*MOVI04D]

2. Verify Open [2SWS*MOV103B], Recirc Spray HX Service Water Supply Header B Isolation.

2.1 Recognizes

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

COMMENTS:

1I2-ADM-1301.F04 Page 7 of9 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 I STANDARD ( "e" Denotes CRITICAL STEP) (Indicate "s" FOR SAT or "U" FOR UNSAT)=> I Stu 3.C Close [2FWE*356], Service Water Supply Tell Tale Drain. (North SFGDS above 2FWE*23B -718') 3.1C Closes [2FWE*356], Service Water Supply Tell Tale Drain by rotating valve handwheel in the clockwise direction.

EVALUATOR CUE: [2FWE*356], Service Water Supply Tell Tale Drain has been rotated CLOCKWISE.

COMMENTS:

4. Vent SWS to AFW piping as 4.1 Requests Mechanical Maintenance Technician follows: loosen flange at [2FWE-RV102], Emergency Water Supply Relief. Request Mechanical Maintenance Technician EVALUATOR CUE: Flange at [2FWE-RV102], loosen flange at Emergency Water Supply Relief has been loosened.

RV102], Emergency Water Supply Relief. (South SFGDS above 2FWE-P23A

-718) COMMENTS:

5. With Key SR/14, Open 5.1 Removes locking device and opens [2FWE*98], [2FWE*98], Service Water Service Water Isolation by rotating valve handwheel Isolation. (North SFGDS chain operator in the counter-clockwise direction.

above 2FWE*P23B

-718) EVALUATOR CUE: [2FWE*98], Service Water Isolation has been unlocked and is indicating OPEN. A solid stream of water is issuing from the flange at [2FWE*RVI02].

RTL#A5.640U 1I2-ADM-1301.F04 Page 80f9 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPMNUMBER:

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 UN SAT)=> I SIU I 6.C When a solid stream of water 6.1C Closes [2FWE*98], Service WaterIsolation by appears at the flange at rotating valve handwheel chain operator in the [2FWE*RVI02], then Close clockwise direction.

[2FWE*98].

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

7. Request Mechanical Maintenance Technician tighten flange at RVI02]. 7.1 Requests Mechanical Maintenance Technician tighten flange at [2FWE-RVI02].

EVALUATOR CUE: Flange at [2FWE-RVI02], Emergency Wate:r Supply Reliefhas been tightened.

COMMENTS:

8.C Open [2FWE*98], Service Water Isolation.

8.1 C Opens [2FWE*98], Service Water Isolation by rotating valve handwheel chain operator in the counter-clockwise direction.

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

I I

1I2-ADM-130 l.F04 Page 9 of9 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 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 UNSA T)=> Opens [2FWE*92], Service Water Supply to [FWE*P23B]

by rotating valve handwheel in the counter-clockwise direction.

EVALUATOR CUE: [2FWE*92]

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

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

by rotating valve hand wheel in the clockwise direction.

EVALUATOR CUE: [2FWE*95]

has been CLOSED. Valve position indicates CLOSE. COMMENTS:

11.1 Observes AFW pump discharge pressure to ensure proper operation by depressing the ON/OFF red pushbutton and reading displayed pressure.

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

pressure is reading approximately 450 psig. completes this COMMENTS:

STOP TIME: _______

RTL#A5.640U J/2-ADM-1301.F04 Page 3 of8 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-003 JPM TITLE: Startup a Rod Drive MG Set JPM REVISION:

7 KIA

REFERENCE:

001 A4.08 3.7/3.4 TASK ID: 0011-001-01-043 JPM APPLICATION:

L8J REQUALIFICATION

[gI INITIAL EXAM [gI TRAINING o FAULTED JPM o ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION:

TYPE: ADMINISTERED BY: 0 Perfonn [gI Plant Site D Annual Requal Exam 0 BVT [gI Simulate D Simulator D Initial Exam D NRC 0 Classroom D OJT/TPE 0 Other: D Training D Other: EV ALUA TION TS Perfonner Name: Performer SSN: Time Critical:

0 [gI 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:

Name/SSN:

Name/SSN:

EVALUATOR Evaluator (Print): Date: Evaluator Signature:

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-1.4.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-1.4.B Revision 13, "Reactor Rod Drive Control System Startup".

NONE Place kept copy of20M-1.4.B Revision 13, "Reactor Rod Drive Control System Startup" up to step #7.

RTL#A5.640U 1I2-ADM-130 l.F04 Page50fS Revision I 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-lAB 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 "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 1/2-ADM-J301.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 UNSA T)=> STARTTIME:

_______ 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 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 I !2-ADM-130 I.F04 Page 7 ofS Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-003 JPM TITLE: Startup a Rod Drive MG Set JPM REVISION:

7 ( itCH Denotes CRITICAL Complete 20M-l.4.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 (1ndicate "S" FOR SAT or "U" FOR UNSAT):::::.

SfU Acknowledges the need to complete 20M-1.4.Q.

EVALUATOR CUE: 20M-1.4.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 R are COMMENTS: Places [2RDS-MG22]

GENERATOR Circuit Breaker control switch to CLOSE position.

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

---

RTL#A5.640U 112-ADM-130 1.F04 Page 8 of8 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-003 JPM TITLE: Startup a Rod Drive MG Set JPM REVISION:

7 ( "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 UNSAT)=> 6.1 C Places [2RDS-MG22]

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

GENERATOR 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 TIME:

RTL#A5.640U 1/2-ADM-1301.F04 Page 3 of8 Revision 1 JPM NUMBER: 2PL-009 JPM TITLE: Place a Reactor Protection Channel in the JPM REVISION:

7 KJA

REFERENCE:

012A4.04 3.3/3.3 TASK ID: 0535-010-04-013 JPM APPLICATION: REQUALIFICATION INITIAL EXAM D TRAINING D FAULTED JPM ADMINISTRATIVE JPM EV ALUA TION METHOD: LOCATION:

TYPE: ADMINISTERED BY: D Perform Plant Site D Annual Requal Exam D BVT Simulate D Simulator D ] nitial Exam D NRC D Classroom D OJT/TPE D Other: D Training D Other: EV ALUA TION RESULTS I Performer Name: I Performer SSN: Yes Allotted Actual 7 Minutes minutes No Time: Time:

D D SAT JPM D UNSAT (Comments required for UNSAT Comments:

OBSERVERS Name/SSN:

Name/SSN:

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: 1I2-ADM-1301.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-2.2.1 C, "Power Range Channel Malfunction" has been performed through Step l.h. Your supervisor directs you to trip the appropriate bistables accordance with AOP-2.2.1 C, Power Range Channel Step 20M-53CA.2.2.1 C, "Power Range Channel Malfunction", Revision 10 Key No. 117 (118) 20M-53CA.2.2.1C , "Power Range Channel Malfunction", place kept up to and including step l.h.

RTL#A5.640U 1/2-ADM-I301.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 l.i. 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 1I2-ADM-1301.F04 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 ( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR 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 (1 ] 8) 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 these keys. EVALUATOR Provide the candidate the KEY 117(118) when request the keys or begin to walk to the control COMMENTS:

1/2-ADM-130 1.F04 Page 70f8 Revision I OPERA TIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-009 JPM TITLE: Place a Reactor Protection Channel in the Tripped JPM REVISION:

7 Condition I STANDARD ( "c" Denotes CRITICAL (Indicate "S" FOR SAT or "U" FOR UNSAT)::::.

Stu EVALUATOR 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 bistables to trip. "Delta T Protection Bistable Switch 4.2 Determines bistables BS-3 and BS-4 on Card Frame 7/S10t 21 must be tripped. COMMENTS: Place 2TS/432C-l

[BS-3] 5.1 C Places 2TS/432C-I

[BS-3] bistable in the TEST bistable on Card Frame position located on Card Frame 7/S10t 21. 7/SIot 21 in the TEST position. Verifies the RED LED is ON. EVALUATOR 2TS/432C-l is in TEST and Red LED is

• COMMENTS:

RTL#AS.640U 1!2-ADM-1301.F04 Page 80f8 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 ( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FORPNSA6.C Place 2TS/432C-2[BS-4]

6.lC Places 2TS/432C-2[BS-4]

bistable in the TEST bistable on Card Frame 7/SIot position located on Card Frame 7/S10t 21. 21 in the TEST position. 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 STOP TIME: _______

" 0 tr A I.ppen d" IX 0 S cenarlo u me F orm ES-01II Facility:

BVPS Unit 2 Scenario No.:1 Op Test No.: 2LOT8NRC Examiners:

Candidates:

SRO ATC BOP Initial IC 211(7): 25% power, BOL, Xe increasing, CB "D" @ 121 steps, RCS boron -1935 ppm. Conditions:

Main feed regulating valves in service .! , , Turnover:

Increase power to 100%. 2SAS-C21B OOS 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 I Malf. No. Event Type Event Description I: o. (R) ATC Raise power in accordance with reactivity plan. 1 (N) BOP, SRO (TS) SRO 2FWE*P22 (turbine driven Aux Feedwater pump) trips 1 (I) ATC, SRO 2CHS-PT145, fails high, ATC required to manually control 3 letdown pressure via 2CHS-PCV145. (C) BOP, SRO Loss of 2AE 4kv Emergency bus / 2-1 Emergency Diesel fails 4 (TS) SRO to auto start. BOP required to manually start EDG 2-1. (C) BOP, SRO 2CCS-P21A sheared shaft, auto start failure of2CCS-P21B, 5 requires manually starting standby pump. (M)ALL Feedline break inside CNMT. 6 (C) ATC, SRO CIB actuation failure 7 (C) BOP, SRO MSLI actuation failure with 2SDS* AOVlll 's failing to auto 8 , close, requires BOP to manually actuate MSLI and close all 6 2SDS*AOV111's (C) BOP, SRO "B" train CREV's fails to actuate, requires BOP to manually 9 actuate. (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9 Supplement 1 FENoe Facsimile Rev. 1 Appendix 0 Scenario Outline Form ES-O-1 2L8N1 The crew will assume the shift at 25% power with instructions to raise power to I 00% lAW 20M-52.4.A and the reactivity plan. When reactor power has increased to 27.5%, the linkage for the trip-throttle valve for the Turbine Driven Auxiliary Feedwater Pump, 2FWE*P22, will fail requiring the US to determine appropriate Tech Spec action. When Tech Specs have been addressed, Letdown Pressure Transmitter, 2CHS*PTI45, will fail high, requiring the A TC to control letdown pressure by manually controlling the Letdown Pressure Control Valve,2CHS*PCV145.

After the crew has stabilized the plant, 4KV emergency bus 2AE will de-energize and EDG 2-1 will fail to automatically start. The crew will enter AOP 2.36.2, Loss of 4KV Emergency Bus, which requires a manual start to restore power to the bus. The SRO will determine appropriate Tech Spec actions. Secondary Component Cooling Water Pump, 2CCS-P21A, will experience a sheared shaft, requiring the crew to enter AOP 2.28.1, Loss of Secondary Component Cooling Water, and the BOP to manually start the standby pump, 2CCS-P21B, which failed to auto sta,.t. 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* AOV111 's) will fail to close requiring the to manually close at least 1 CIB will fail to automatically actuate, The ATC will identify the failure to actuate and manually both trains 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 jlowpath closing 2SIS*MOV867A, B, C, Expected procedure flow path is E-O ---+ E-2 ---+ E-I ---+ ES-I.l. NUREG-1021, Revision 9 Supplement 1 FENoe Facsimile Rev. 1

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BEAVER VALLEY PUWER INITIAL CONDITIONS:

25% Power, CBD = 121, Xe increasing BOL, 1935 PPM Boron, IC-211 ADDITIONAL LINEUP STICKERS YCT -2SAS-C21B CS EQUIPMENT STATUS DATEffIME OOS OOS, compressor overhaul 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}

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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 30f23 BEAVER VALLEY f--uWER STATION C]NSTRl.JCTIONAL 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 TRGSET 1 IMF PMP-CAS004 (0 0)

IMF PPL09A (0 IMF PPL09B (0 IMF PPL10A (0 IMF PPL10B (0 IMF BST -CCS006 (0 0) IMF PMP-CCSOOI (7 0) IMF A6-3B-P0670D (7 0) TRGSET 8 'XClI076A

= TRG 8 'DMF lOR XBSIOS2P (0 0) lOR XBSI06SP (0 0) TRGSET 6 'XBSIOS2C

= TRG 6 'DOR TRGSET 7 'XBSI02SP

= TRG 7 'DOR TRGSET S 'FNISPR(l)

>= IRF LOA-AFW022 (S 0) IMF VLV-MSS032A (00) IMF VLV-MSS033A (0 0) IMF VLV-MSS034A (00) IMF VLV-MSS03SA (0 0) BVPS -2L8 NRC Scenario 1, Rev 1 L Pb6NT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE Reactor plant at 25% power, BOL, Xe increasing, RCS boron 935 PPM, CBD 121 steps. Inserts all pre-loads required to support the scenario.

Set trigger 1 on reactor trip 2SAS-C21B OOS 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-P21 B 2HVC*MOD201A failed open. 2HVC*MOD201B failed open. Set trigger 6 on 2HVC*MOD201A CS to close. DOR, 2HVC*MOD201A manually closes. Set trigger 7 on "B" Tm CREV'S PB depressed.

DOR, 2HVC*MOD201B manually closes. Trigger 5 on reactor power> 27.5% 2FWE*P22 trip throttle valve trips shut Fail 2SDS-AOVIIIAI closed Fail 2SDS-AOVIIIA2 closed Fai12SDS-AOVII1Bl closed Fail 2SDS-AOVl11B2 closed 40f23

---BEAVER VALLEY t-0WER STATION [

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 VLV-MSS033A' TRGSET 12 'XAII107C

= 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 place the simulator to RUN commence the BVPS 2L8 NRC Scenario 1, Rev 1 r PLANT STATUS / PROCEDURAL GUIDANCE Fai12SDS-AOVIIICI FaiI2SDS-AOVIIIC2 Set trigger 10 on 2SDS-AOVIIIAI CS to DMF, 2SDS-AOVl11Al manually Set trigger lIon 2SDS-AOVIIIA2 CS to DMF, 2SDS-AOVIIIA2 manually Set trigger 12 on 2SDS-AOVIIIBI CS to DMF, 2SDS-AOVIIIBI manually Set trigger 13 on 2SDS-AOVII1B2 CS to DMF, 2SDS-AOVI11B2 manually Set trigger 14 on 2SDS-AOV111CI CS to DMF, 2SDS-AOVll1Cl manually Set trigger 15 on 2SDS-AOVI11C2 CS to DMF, 2SDS-AOVl11C2 manually Simulator Frozen until after shift turnover it needs to be run momentarily for an Simulator 50f23 EXPECTED STUDENT Crew assumes control of the Unit.

BEAVER VALLEY !-0WER 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: 5 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 IA W Reactivity plan, ATC dilutes/withdraws rods to raise reactor power to 100%. BOP raises turbine load. BOP raises turbine load at 12%/hour rate by; Adjusting "setter" as appropriate. Depressing "GO". BOP verifies/maintains the following while raising load, Valve position limiter 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 2hrs 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 I BEAVER VALLEY 1-0WER INSTRUCTIONAL GUIDELINES 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-LDS007A (00) 600 ROLE PLAY: 3 minutes after being dispatched to check local pressure on 2CHS-PI146, report back that pressure indicates 110 psig. After plant has been stabilized, continue with next event at LE discretion BVPS -2L8 NRC Scenario 1, Rev 1 SfAfOS TPFfOCEDURAL..

GlITiSANC"E I IMMEDIATE PLANT A2-3F, Letdown Flow Path 2CHS-PI145 indication at 600 2CHS*PCV145 Letdown flow 2CHS*RV209 may SRO enters 20M-7.4.IF, Attachment

3. EXPECTED STUDENT RESPONSE n_ ATC reports unexpected letdown BOP refers to ATC notes 2CHS-PI145 at full scale 2CHS*PCV145 traveling ATC places 2CHS*PCV145 in manual and valve to stahilize net charging and restore flow to pre-event With 2CHS*PCV145 in manual, SRO establishes control band for manual control of letdown ATC monitors for proper operation SRO dispatches operator to check locall/d pressure 70f23 BEAVER VALLEY PUWER INSTRUCTIONAL GUIDELINES EVENT 4: Loss of 2AE 4kv emergency bus with an auto start failure of2-1 EDG. IMF BKR-HIVOl (0 0) 0 PLANT STATUS I PROCEDURAL IMMEDIATE PLANT 4KV ACB 2AIO trips 4KV bus 2AE voltage reduces to zero Multiple electrical related SRO enters AOP 2.36.2 for Loss of Emergency 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 Crew verifies 2SWS*P21A is running and water supply valve is Crew performs EOP Attachment A-I.6, lAW of AOP 2.36.2 to verify EDG auto loading SRO evaluates TS for emergency bus and EDG SRO determines 20ST-36.7 is required within 1 to verify operability of remaining sources per 3.8.1, Conditions A and BVPS 2L8 NRC Scenario 1, Rev 1 80f23 INSTRUCTIONAL GUIDELINES EVENTS: Turbine Plant Component Cooling Water Trouble (2CCS-P21A sheared shaft) TRG! 7 (actuate trigger 7, all required commands are preloaded.)

Proceed with next event at LE discretion BEAVER VALLEY l-'uWER STATION PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE IMMEDIATE PLANT RESPONSE: 2CCS-P21A ammeter reduces to amps. BOP reports unexpected CCS related alarms. A6-3B, CCS pump discharge press low A TC refers to ARP's A7-6F, Main Leads Cooling Trouble A7-2H, EHC Temperature High SRO enters AOP 2.28.1. 2CCS-P21B fails to auto start when pressure reduces to < 75 psig. BOP recognizes failure of2CCS-P21B to auto start on low pressure and manually starts 2CCS-P21B.

-BVPS -2L8 NRC Scenario 1, Rev 1 90f23 BEAVER VALLEY I-vWER STATION r INSTRUCTIONAL GUIDELINES EVENTS 6, 7, 8, & 9 Feed line break inside IMF FLX-CFW33 (0 0) Multiple malfunctions occur on reactor trip. All commands TRGSET 1 lOR XBSI052P (0 0) lOR XBSI065P (0 0) TRGSET 6 'XBSI052C

== TRG 6 'DOR TRGSET 7 'XBSI025P

= TRG 7 'DOR jPLANT STATUS I 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, AOVl11 's fail to automatically

close, manual CIB will fail to automatically "B" train CREV's fails to automatically SRO enters EXPECTED STUDENT ATC and BOP commence lOA's ofE-O. A TC 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. BVPS -2L8 NRC Scenario 1, Rev 1 10 of23 BEAVER VALLEY I JWER STATION [ INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EVENTS 7, 8, & 9: (continued)

SI automatically actuated EXPECTED STUDENT RESPONSE BOP verifies Power to AC Emergency Busses. Using VB-C voltmeters, verifies either AE or D F 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 if SI is required ATC checks Cnmt press> 5psig A TC checks PRZR press < 1860 psig ATCIBOP checks Steamline press < 500 psig Crew determines SI is Required; A TC manually actuates SI by turning both trains' control switches.

ATCIBOP, SOlli,ds Standby Alarm, announces reactor trip and safety injection.

BOP verifies leak collection filtered exhaust fan 2HVS-FN204A or B running. A TC verifies SI System Status. Both 2CHS*P21A and P21B pumps running. HHSI Flow indicated, Both LHSl pumps running. BVPS 2L8 NRC Scenario 1, Rev I1of23 BEAVER VALLEY I-v\IVER STATION r-UINSTRUCTIONAL GUIDELINES EVENTS 7,8, & 9: (continued) Evaluation of BOP Attachment A-O.II begins on page PLANT STATUS I PROCEDURAL List of Attachment A-D.II MSLI failed to automatically 2SDS-AOVlll

's, steam line drains failed automatically CIB failed to automatically "B" train CREV's failed to I' ., EXPECTED STUDENT RESPONSE 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 SRO directs BOP to perform Attachment A-O.II. BVPS -2L8 NRC Scenario 1, Rev 120f23 BEAVER VALLEY POWER L INSTRUCTIONAL 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 RCS temperature

< 547°F and dropping due to Safety Injection flow. CIB not actuated at this time. EXPECTED STUDENT RESPONSE ATC checks RCS Tavg stable at or trending to 547°F ATC verifies no steam release is occurring. (Condenser steam dumps closed) ATC verifies Reheat steam is isolated. ATC reduces total feedflow to minimize CID. Crew determines cooldown is continuing determines SLI is If not previously actuated, BOP manually MSLI and closes 2SDS-AOVIII ATC checks recirc spray pumps -NONE BVPS -2L8 NRC Scenario I, Rev 130f23 BEAVER VALLEY rvWER STATION [ 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 shutdown 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 Block valves AT LEAST ONE OPEN A TC checks if RCPs 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.

ATCIBOP checks if any SIGs are faulted

• 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 I40f23 BEAVER VALLEY t -,WER STATION INSTRUCTIONAL GUIDELINES EYENTS 7, 8, & 9: "B" Train CREV's automatic failed requiring the crew to All commands Failure ofMSLI should have recognized by this PLANT STATUS I PROCEDURAL "C" S/G pressure is lower than "A" & "A" & "B" may be slowly lowering as due to the cooldoWD.

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

EXPECTED STUDENT RESPONSE ATCIBOP actuates CREVS Verifies the control room air intake and exhaust Dampers are CLOSED. Crew determines "B" Train CREV's failed to actuate, ATCIBOP manually actuates CREV's. SRO requests a BV-1 operator to verify proper Unit 1 CREVS actuation.

SRO directs ST A to Commence Control Room ventilation actions. Refer to Attachment A-2.4. ATC/BOP verifies steamline isolation has occurred by checking all YELLOW SLI identified components are in the designated position. (previously verified)

BOP "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 t--0WER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I 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 (00) 0, then report that 2SVS-29 is closed. BOP isolates the faulted, "C" S/G as follows, Verifies FWI (previously verified via Attachment A-O.ll) Closes AFW throttle valves on "C" S/G 2FWE*HCVlOOA 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 isolated, 2BDG* AOVlOOCl Verifies S/G Blowdown sample isolation valves, 2SSR

• AOVl17 A, B, C closed. BOP verifies PPDWST level is > 85 inches . ...... BVPS -2L8 NRC Scenario 1, Rev l60f23 BEAVER VALLEY I ..JWER STATION r INSTRUCTIONAL GUIDELINES I** PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT 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.1. 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 appropriate.

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 V ALVES; Crew determines S/G Tubes ARE INTACT. Crew checks if SI Flow should be Reduced ATC verifies RCS Subcooling is > 41°F [59°F ADVERSE CNMT] based on CETC's BOP confinns secondary heat SiILk 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 I-vWER STATION [ ulNSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EVENTS 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 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 confirms CIB was previously manually initiated.

ATC verifies SWS flow to all 4 Recire Spray HX's. ATC verifies RWST level is NOT < 381 inches. 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 "c" S/G was previously identified as faulted and has been isolated.

BVPS -2L8 NRC Scenario 1, Rev 180f23 BEAVER VALLEY POWER INSTRUCTIONAL GUIDELINES nUT PLANT STATUS I PROCEDURAL GUIDANCE EVENTS 7,8, & 9: (continued)

EXPECTED STUDENT RESPONSE BOP Checks Intact S/O Levels Narrow range levels -OREATER THAN 12% [31 % ADVERSE CNMT] Controls feed flow to maintain narrow range level between 12% [31 % ADVERSE CNMT] and 50%. Crew checks if S/O tubes are intact Check all S/O levels -NONE RISING IN AN UNCONTROLLED MANNER Check Secondary Radiation

-CONSISTENT WITH PRE-EVENT VALUES Crew determines no S/O levels are rising in an uncontrolled manner and Secondary Radiation is consistent with pre-event values, therefore all S/O 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 BVPS -2L8 NRC Scenario 1, Rev 190f23 BEAVER VALLEY l-'uWER STATION m 1 INSTRUCTIONAL GUIDELINES EVENTS 7, 8, & 9: (continued)

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 cool down AND Safety Injection.

BVPS -2L8 NRC Scenario 1, Rev 1 PLANT STATUS I PROCEDURAL SRO transitions to ES-l.1, SI Termination EXPECTED STUDENT RESPONSE Crew checks if SI Flow should be ATC verifies RCS Subcooling is greater than 41 OF OF ADVERSE CNMT] based on BOP confirms secondary heat sink available by gpm of feed flow available OR NR level in at least S/G> 12% r31% ADVERSE A TC confirms RCS pressure is stable or A TC confirms pzr level is > 17% [38% Crew determines that current plant conditions SI Crew resets SI, CIA and CIB ATC stops 1 charging A TC verifies RCS pressure is stable or ATC closes 2SIS*MOV867 A,B,C, 200f23 BEAVER VALLEY I ..,IWER STATION [ INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT Attachment A-O.tl 'Verification of Automatic Actions' performed as time & manpower permit 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.l, whichever occurs first Basis for Selection:

SAFETY SIGNIFICANCE

--Failure to close the MSIVs under the postulated plant conditions causes challenges to CSFs beyond those irreparably introduced by the postulated conditions.

Additionally, such an omission constitutes a !!demonstrated inability by the crew to recognize a failure of the auto actuation of an ESF system or component and to take an action that would prevent a challenge to plant safety." BVPS 2L8 NRC Scenario 1, Rev 1 210f23 Ensure Reheat Steam Isolation BOP performs Attachment A-O.ll, 'Verification of Automatic Actions' as follows: Checks both EDGs running Ensure reheat steam isolation Verify 2MSS-MOVIOOA and B -CLOSED Reset reheater controller.

Check If main steamline isolation required CNMT pressure -> 7 Steamline pressure -< 500 Steamline pressure high rate of PSIG DROP IN 50 Determines CNMT pressure is > 7 PSIG and Manually actuates steamline isolation by depressing all 4 SLI pushbuttons (BB-C) Verifies SLI by checking all YELLOW SLI LIT Identifies 2SDS-AOVIIIAl,B1,C1, A2,B2,& C2 all failed to close. Manually closes all valves.

INSTRUCTIONAL GUIDELINES Attachment A-O.ll-BOP may have already opened 2CCS-AOVl18 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 SIGNIFICANCE

--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 system or component. " BVPS -2L8 NRC Scenario 1, Rev 1 BEAVER VALLEY POWER STATION PLANT STATUSLpROCEDURAL GUIDANCE I** EXPECTED STUDENT RESPONSE 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.

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 !--uWER STATION r-INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE Attachment A-O.ll-(continued)

Attachment A-O.ll Discrepancies:

MSLI failed to automatically isolate 2SDS-AOVl11

's, stearn line drains failed to automatically close CIB failed to automatically actuate. "B" train CREV's failed to automatically actuate. EXPECTED STUDENT RESPONSE 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 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 Upon Completion, Report Any Discrepancies to SRO. BVPS -2L8 NRC Scenario 1, Rev 230f23

. 0 tr -A lppen d'IX 0 S cenarlo u me F orm ES 0 1 II Facility:

BVPS Unit 2 Scenario No.:2 Op Test No.: 2LOT8NRC "Sxaminers:

Candidates:

SRO ATC BOP IC 212(17): 72% power, MOL, Eq Xe, CB "D"@180 steps, RCS boron -1140 ppm. Conditions:

Tl IRVC! Maintain steady state power at 72%, 2FWE*P23A OOS, 2SAS-C21B OOS Critical Tasks: 1. E-O.A Manually trip the Reactor 2. E-O.Q Manually trip the turbine 3. FR-H.1.A Establish feedwater flow before Feed and Bleed criteria Event Malf. No. Event Type Event Description No. (C)ATC, SRO N44 fails high, rods automatically step in. 1 (TS) SRO (R) ATC 2FWS-P21B trips/ reduce power to 52% 2 (C) BOP, SRO (TS) SRO Misaligned Rod 3 (M)ALL 2RCS*P21B locked rotor trip with Automatic Reactor trip 4 failure and 400 gpm SBLOCA. (C) BOP, SRO Automatic turbine trip failure 5 (M)ALL Loss of all auxiliary feed water, entry into FR-H.l 6 (C) 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-1 021, Revision 9 Supplement 1 FENoe Facsimile Rev. 1 Appendix D Scenario Outline Form ES-D-1 2L8N2 The crew will assume the shift at 72% power with instructions to maintain steady state conditions.

N-44 will fail high causing the control rods to automatically insert. The crew will enter AOP 2.1.3, RCCA Control Bank Inappropriate Continuous Movement, verify no load rejection is occurring and then the ATC will place the control rods in Manual to stop rod insertion.

The US will then enter AOP 2.2.1 C, Power Range Channel Malfunction, to remove the channel from service and determine appropriate Tech Spec action. Main Feedwater pump, 2FWS-P21B will then trip, the crew will enter AOP 2.24.1, Loss of Main Feedwater AOP, and begin an immediate power reduction to 52%. While the rods are inserting, 1 rod will experience a moveable gripper failure causing the rod to ratchet inward on each step demand. The crew will identify the misaligned rod and initiate boration for the remainder of the power reduction.

After the plant has stabilized, the SRO will enter AOP 2.1.8, Rod Inoperability, and address Tech Spec's for the misaligned rod. The "B" reactor coolant pump will then experience a locked rotor trip, the reactor will fail to automatically trip, the ATe 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.I, 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 feed water 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-1. The Ventilation fans, 2HVS-FN204A

& B will trip on the reactor trip, the BOP will start at least I fan. The scenario will be terminated after the crew transitions to ES-1.1. Expected procedure flow path is E-O FR-H.1 E-O E-1 NUREG-1 021, Revision 9 Supplement 1 FENOC Facsimile Rev. 1 L BEAVER VALLEY t -,lIVER STATION INITIAL CONDITIONS:

72% Power, CBD 180, Equilibrium Xe, MOL, 1140 PPM Boron, IC-219 -ADDITIONAL LINEUP CHANGES STICKERS MONITOR SETUP YCT -2FWE*P23A CS A TC {,()sitign HIGH POWER dis{'lay YCT -2SAS-C21B CS EOUIPMENT STATUS DATEffIME OOS TECHNICAL SPECIFICATION!S}

2FWE*P23A OOS 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br /> ago 3.7.5 condition B 2SAS-C21B OOS 3 days ago SHIFT TURNOVER INFORMATION

1. 72% {,ower, MOL Equilibrium Xe, shift goal is to steady state conditions.

SCENARIO SUPPORT MATERIAL PROCEDURES NEEDED MOL Reactivity AOP 2.1.3 AOP 2.2.1C AOP 2.24.1 AOP 2.1.8 E-O FR-H.l Attachment A-0.l1 Attachment A -1.10 BVPS -2L8 NRC Scenario 2, Rev 30f23 BEAVER VALLEY t ...;IIVER STATION [ INSTRUCTIONACGUTOELINES Initialize I C 219, 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 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 (lIS) 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 PPLIOB (0 0) 0 lOR XClI04ST (0 0) OFF TRGSET 8 'OCFWP21B

>= 0.6 *AND. XClI046T == TRG 8 'IMF PMP-CFWOOS (00) IMF PMP-MSC036 (1 0) TRGSET 4 'XBSI071 T == TRG 4 'DMF IMF PMP-MSC037 (1 0) TRGSET 6 'XBSI083T

== TRG 6 'DMF BVPS -2L8 NRC Scenario 2, Rev 1 I PLANT STATUS I PROCEDURAL STUDENT 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-C21 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 < 62% 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 2HVS*FN204A CS taken to 2HVS*FN204A 2HVS*FN204B trips on Rx TRG 6 when 2HVS*FN204B CS taken to 2HVS*FN204B 40f23 BEAVER VALLEY I -,WER STATION I-u INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE Assign shift positions SRO:_________ ATC:__________ BOP:________ Conduct a shift turnover with oncoming Simulator Frozen until after shift turnover unless operators.

it needs to be run momentarily for an alignment change. When the shift turnover is completed, Simulator running. Crew assumes control of the Unit. place the simulator to RUN and commence the scenario.

BVPS -2L8 NRC Scenario 2, Rev 1 50f23 BEAVER VALLEY I -,WER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EVENT 1: 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 A TC reports unexpected alarms and rod A TC 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 verifies 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 1 60f23 BEAVER VALLEY I -,WER STATION em INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT 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 1 70f23 BEAVER VALLEY r __ NER STATION I EVENTS 2 &3: IMMEDIATE PLANT RESPONSE:

2FWS-P21B tripsl Movable gripper Feed flows drop, S/G levels decrease, Main feed failure on Rod F6 when < 62%. regulating valves open. IMF PMP-CFW005 (0 0) 1 A6-9E, lOE, lIE S/G21A(B)(C)

Level IMF CRF03-F6 (5 0) 1 (preloaded)

Deviation From Setpoint.

SRO enters AOP 2.24.1 When < 62% power, rod F6 will start to "ratchet" in on each rod step. After plant is stable and S/G levels are recovering, SRO enters AOP 2.1.8 to address the misaligned rod. Continue with next event at LE discretion BVPS 2L8 NRC Scenario 2, Rev 1 80f23 EXPECTED STUDENT Crew determines that 2FWS-P21B 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 50% power equivalent.

• Depressing "GO" ATC inserts control rods and initiates boration for expected 20% power BOP verifies ali avaiiabie pumps are Starts A TC 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 SRO contacts Operations management and notifies I&C of the rod misalignment.

BEAVER VALLEY I ,..,VVER STATION [ INSTRUCTIONAL GUIDELINES EVENTS 4, 5, 6, 7 & 8: 2RCS-P21B locked rotor with an automatic reactor trip failure, turbine trip failure and 400 gpm SBLOCA. 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.1. 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 of the automatic actuation of the RPS." PLANT STATUS I PROCEDURAL GUIDANCE IMMEDIATE PLANT RESPONSE:

A5-2G, 1/3 Reactor Coolant Pump Loop Flow Low Reactor Trip SRO enters E-O. Automatic reactor trip failure. 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. A TC 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.

BVPS -2L8 NRC Scenario 2, Rev 1 90f23 BEAVER VALLEY I ..... vVER STATION GUIDELINES PLANT StATUS I PROCEDURAL 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 challenges to CSFs beyond those irreparably introduced by the postulated conditions.

Additionally, such an omission constitutes a demonstrated inability by the crew to IItake an action ... that would prevent a challenge to plant safety,lI EXPECTED STUDENT RESPONSE 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 10 of23 BEAVER VALLEY, ...IWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 4, 5, 6, 7 & 8: (continued)

SI automatically actuated NOTE: SI will be required due to 400 gpm SBLOCA, depending on timing, if SI 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 ATC checks Cnmt press> 5psig ATC checks PRZR press < 1860 psig A TC or BOP checks Steamline pressure < 500 psig Crew determines SI is Required; ATC manually actuates SI by turning both trains' control switches.

ATC/BOP, Sounds Standby Alarm, announces reactor trip and safety injection.

BOP verifies neither leak collection filtered exhaust fan, 2HVS-FN204A nor B are running. BOP starts at least 1 leak collection filtered exhaust fan. ATC verifies SI System Status Both 2CHS*P21A and P21B pumps running. HHSI Flow indicated, Both LHSI pumps running BVPS 2L8 NRC Scenario 2, Rev 11 of23

---

BEAVER VALLEY I ..JWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT 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.

SRO recognizes that AFW flow cannot be established and enters FR-H.l 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. ATC checks if secondary heat sink is required by: Verifying RCS press is> any non-faulted S/G. RCS Hot leg temperatures>

350°F. Crew checks if RCS Bleed and Feed should be initiated. BOP verifies Wide Range level in at least 2 S/G's is> 14%. ATC 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 I ...JWER STATION L IN§TBUCTIONAL GUIDELINES 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. If 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 confirms 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 TCIBOP resets;

• SI signal-both trains

• FWI signal -both trains. A TCIBOP opens all Feedwater CMNT isol valves, 2FWS*HYV157A, B, C. BVPS 2L8 NRC Scenario 2, Rev 1 13 of23 BEAVER VALLEY. JWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 4, 5, 6, 7 & 8: (continued) 2FWS-P24 will not start due to failure of recirculation valve, 2FWR-FCV155 to open. 2FWS-P21A will not Crew may not attempt to start P21B since it had previously tripped, the crew does attempt a start -it trip immediately upon 2 nd motor BOP attempts to start the S/G Startup Feed pump by; Verifying 2CNM-DCVlOO is open Placing CS for 2FWS-P24 to start and hold unti12FWR-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-P21B starts but immediately trips. ATC depressurizes the RCS to < 1950 psig by manually opening 1 PZR PORV.

closes POR\' \vhen pressure reduces to < 1950 pSlg. ATC restores normal charging by; Opening 2CHS*MOV310 Opening 2CHS*MOV289 Adjusting 2CHS*FCV122 to maintain PZR level. ATC blocks Low Steamline Pressure SI and Low Pressurizer Pressure SI signals. BVPS -2L8 NRC Scenario Rev 140f23 BEAVER VALLEY I JWER STATION [ INSTRUCTIONAL GUIDELINES EVENTS 4,5,6,7 & 8: (continued)

Booth instructor As directed, de-energize IMF VLV-CFW043 (0 0) IMF VL V -CFW044 (0 0) Critical Task:

Crew establishes feedwater flow at least one SG before RCS feed bleed is Basis for SAFETY SIGNIFICANCE

--Failure establish feedwater flow to any results in the crew's having to rely the lower-priority action of RCS bleed and feed to minimize uncovery.

This constitutes performance that "leads to of any barrier to fission BVPS 2L8 NRC Scenario 2, Rev PLANT STATUS I PROCEDURAL EXPECTED STUDENT RESPONSE BOP depressurizes at least 1 S/G to < 440 psig to establish Condensate flow by; Verifyin,g at least I 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-I.I 0, Crew coordinates with a field operator to open and de-energize at least I main feed pump discharge valve. BOP begins feeding 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 are rising. 150f23 BEAVER VALLEY I JWER STATION INSTRUCTIONAL GUIDELINES EVENTS 4, 5, 6, 7 & 8: (continued) Evaluation of BOP Attachment A-O.II begins on page PLANT STATUS I PROCEDURAL GUIDANCE SRO returns to E-O, Step 8 lAW FR-H-I, step ll.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 perform Attachment A-O.II. ATC checks RCS Tcold stable at or trending to 547°F ATC verifies no steam release is occurring. (Condenser steam dumps closed) A TC verifies Reheat steam is isolated. ATC reduces total feedflow to minimize CID. Crew determines cooldown is continuing and verifies SLI has previously occurred.

ATC checks recife 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 VALUES Power to at least one block valve Block valves AT LEAST ONE OPEN BVPS 2L8 NRC Scenario 2, Rev 160f23 BEAVER VALLEY I ..;WER STATION [ 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 SIG pressure < 205 PSID RCP's previously stopped in FR-H.l 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. Crew checks if SIG tubes are intact. Check all SIG levels -NONE RISING IN AN UNCONTROLLED Check Secondary Radiation

-CONSISTENT WITH PRE-EVENT VALUES Determines no SIG levels are rising in an uncontrolled manner and Secondary Radiation

-is CONSISTENT WITH PRE-EVENT VALUES; Crew determines SIG Tubes ARE INTACT. .. BVPS -2L8 NRC Scenario 2, Rev 170f23 BEAVER VALLEY * ...)WER LJN§JRljCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EVENTS 4, 5, 6, 7 & 8: (continued)

SRO transitions to 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-l 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 previousiy 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 I JWER STATION GUIDELINES nnn I PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 4, 5, 6, 7 & 8: (continued)

ATC confirms CIB 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 SIGs are faulted

• Pressures in all SIGs ANY DROPPING IN AN UNCONTROLLED MANNER OR ANY SIG COMPLETELY DEPRESSURIZED SIG's are faulted. 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 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. BVPS -2L8 NRC Scenario Rev 190f23 BEAVER VALLEY, JWER [ INSTRUCTIONAL GUIDELINES EVENTS 4, 5, 6,7 & 8: (continued)

Tenninate scenario when the detennines transition to ES-I.l Classify SAE, Site Area Emergency appropriate classification per Fission Product Tabs 1.1.1 and 1.2.1 -Potential Heat Sink Red BVPS -2L8 NRC Scenario 2, Rev I STATUS I PROCEDURAL SRO detennines transition to ES-l.I, SI T ennination is appropriate.

STUDENT RESPONSE ATC checks PORV's and block valves.

• Power to block valves A V AILABLE

• PORVs-CLOSED

• Block valves -AT LEAST ONE OPEN Crew checks if SI Flow should be Reduced ATC verifies RCS Subcooling is greater than 41°F based on CETC's BOP confinns secondary heat sink available by >370 gpm of feed flow available OR NR level in at least 1 S/G> 12%. A TC confinns RCS pressure is stable or A TC confinns pzr level is > Crew detennines that current plant conditions SI 200f23 BEAVER VALLEY. JWER 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-AOVl18 to provide cooling to the Station Air compressors.

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

Check If main steam line isolation required CNMT pressure -> 7 Steamline pressure -< 500 Steam line pressure high rate of change 100 PSIG DROP IN 50 SECONDS If steam line 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 2, Rev 210f23 SEAVER VALLEY I JWER STATION 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 cm if required by: Manually initiate cm -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*SOVlOOA1, BI-CNMT Sample amber lights LIT. BVPS -2L8 NRC Scenario 2, Rev 220f23 BEAVER VALLEY. JWER INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE Attachment A-O.ll (continued)

Attachment A-OJl 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 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 2, Rev 230f23

" 0 r A.ppen d" IX 0 S cenarlo F orm ES-0 1 II Facility:

BVPS Unit 2 Scenario No.:3 OpTestNo.:

2LOT8NRC P,xaminers:

Candidates:

SRO ATC BOP Initial IC 213: 5% power, EOL, Increasing Xe, CB "D" @ 117 steps, RCS boron 644 ppm. Conditions:

Turnover:

Raise power to 15% to SIU main turbine, 2SAS-C21B OOS Critical Tasks: 1. E-3.A, Isolate Ruptured SG 2. E-3.B, Cooldown RCS 3. E-3.C, Depressurize RCS Malf. No. Event Type Event Description No. (R) ATC Normal power increase to 15% lAW 20M-52.4.A 1 (N)SRO (TS) SRO 17 gpm S/G 21B Tube Leak 2 (TS), SRO S/G 21B atmospheric dump valve fails open. 3 (C)ATC, SRO 21B RCP high vibration with seal failure (will require 4 manually tripping Rx and RCP) M(ALL) 500 gpm 21 B S/G Tube Rupture 5 C (BOP/SRO) 2SDS-AOV129A failed open, requires RNO actions for S/G 6 isolation.

l I (BOP/SRO)

Condenser steam dumps fail closed. (Requires cool down with 7 21A and 21C Atmospheric Stearn Dumps. (C) ATC, SRO 2RCS*PCV455B, PZR spray valve, fails open following 8 depressurization will require A TC to manually trip RCP( s) (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021 , Revision 9 Supplement FENoe Facsimile Rev. 1 Appendix D Scenario Outline Form ES-D-1 2L8N3 The crew will assume the shift at 5% power with instructions to continue the startup to raise power to 15% to startup the main turbine in accordance with 20M-52.4.A, IV A, Plant Startup, the plant is at 5% power and Step 7 is in progress.

The ATC will withdraw control rods and dilute IA W the reactivity plan. A 17 gpm S/G Tube leak will occur as evidenced by Rad monitor indications, the Unit Supervisor will direct actions per AOP 2.6.4, Steam Generator Tube Leakage, and refer to TS 3.4.13 for Primary to Secondary leakage. 2SVS*PCV101B, 21B S/G atmospheric steam dump valvl;! will then fail open and stick open, the valve will not close in Auto, Manual or Locally, requiring the crew to direct the local isolation.

The SRO will refer to TS 3.7.4 for Inoperable Atmospheric Steam Dumps. A 21 B RCP high vibration condition with a seal failure will develop, the crew will respond using AOP 2.6.8, Abnormal RCP Operation.

After a 2 minute time delay, the high vibration will increase at>1 millhr which requires the crew to trip the reactor, enter E-O and take the reactor coolant pump out of service. Following the reactor trip, a 500 gpm SGTR occurs on the 21B S/G resulting in a Safety Injection actuation.

The crew will transition to at the "Check ifS/G Tubes are Intact" step ofE-O. When isolating lAW E-3 steps, steam lines drain valve, 2SDS* AOV129A will fail open requiring closure of 2SDS* AOV1 29B. When the cooldown is attempted in E-3 the condenser steam dumps will fail closed, requiring the BOP operator to use manual control of the atmospheric steam dump valves and/or 2SVS-HCV104.

After the crew completes the cooldown and depressurization, spray valve, 2RCS*PCV455B will fail open requiring the ATC to manually trip RCP's. The scenario will be terminated after a normal charging flowpath is established in E-3. Expected procedure flow path is EO -E3. NUREG-1021, Revision 9 Supplement 1 FENoe Facsimile Rev. 1 BEAVER VALLEY I -"lIVER STATION INITIAL CONDITIONS:

5% Power, CBn 117, Xe increasing EOL, 664 PPM Boron, IC-216 ADDITIONAL LINEUP CHANGES STICKERS MONITOR SETUP YCT -2SAS-C21B CS A TC position LOW POWER display EOUIPMENT STATUS DATEffIME OOS TECHNICAL SPECIFICATION(S) 2SAS-C21B OOS, WlllJJH;;",,,,W overhaul 3 days ago SHIFT TURNOVER INFORMATION

1. EOL plant startup, Mode 1 just entered, continue plant startup lAW 20M-52.4.A, step IV.A.7.a in progress.

2. SCENARIO SUPPORT REOUIRED 1. 20M-52.4.A completed and place kept up through step IV.A.7.a.

2. Reactivity plan 3. EOL reactivity placard PROCEDURES NEEDED 20M-52.4.A AOP 2.6.4 AOP 2.6.8 E-O E-3 Attachment A-O.ll BVPS -2L8 NRC Scenario 3, Rev 1 30f24 BEAVER VALLEY I -,WER STATION [ u_uINSTRUCTIONAL GUIDELINES Initialize IC 213, and establish plant Insertthe following per the Simulator Setup section of the HTML File for this scenano: PRELOAD COMMANDS TRGSET 1 'JPPLP4(1)'

TRGSET 4 'TPCST AAU <=530' IMF CNH-PCS07A (4 0) 0 IMF VLV-MSS057A (00) 100 TRGSET 6 'JMLRCP6B

= l' TRG 6 'IMF RCP06B (0 120) 21 600 15' IMF RCS04B (3 0) 17.0 30 0 IMF CNH-MSS03A (3 600) tOO lOR XA20024G (100) OFF lOR XA20024R (10 0) OFF TRG 1 'IMF RCS04B (0 0) 500 0 0' IMF RCP06B (5 0) 15 IMF RCPOIB (5 0) 4 30 IMF VLV-RCS031 (75) 0 TRGSET 7 'RRCC455B

>= 0.5' PLAf\JISTATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE Reactor plant at 5% power, EOL, Xe increasing, RCS boron =644 PPM, CBn = 117 steps. Inserts all preloads required to support the scenario.

Set trigger 1 on Reactor Trip Set trigger 4 on Tavg < 530 degrees f 2MSS-PK464 failed, closes Steam Dumps 2SDS*AOV129A failed open Set trigger 6 when malfRCP06B is actuated Ramp RCP vibration to 21 mils over 10 minutes S/G tube leak: B S/G 2SVS*PCVlOIB failed open 2SVS*PCVlOIB Green light -off 2SVS*PCVIOIB Red light -off 500 gpm S/G tube rupture: B S/G ON Rx trip RCP-B High Vibration

-15 mils on frame RCP-B No.1 seal leak 2RCS*PCV455B fails open Set TRG 7 when spray valve 455B > 50% open BVPS -2L8 NRC Scenario 3, Rev 1 40f24 BEAVER VALLEY t ...... VVER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE Assign shift positions SRO:_________ ATC:_________ 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 3, Rev 1 50f24 BEAVER VALLEY I -,lIVER STATION INSTRUCTIONAL GUIDELINES EVENT 1: Normal Plant Startup, Reactor Power increase to 15% to support Turbine Startup. 20M-52.4.A, step 7.a in progress.

Continue reactor startup BVPS 2L8 NRC Scenario 3, Rev 1 PLANT STATUS I PROCEDURAL Reactor at 10% power. Status lights on Panel 308 actuate at 10%. AI2-2B, -'NIS IR TRIP BLOCKED' LIT. A12-2C, -'POWER RANGE LOW SETPOINT TRIP BLOCKED' AI2-IH, -'NOT P-T -NOT LIT. A4-5G, -'NIS POWER RANGE HIGH/LOW SP NEUTRON FLUX HIGH' NOT LIT. 60f24 EXPECTED STUDENT Crew commences power increase in accordance with reactivity plan. ATC commences raising reactor power to between 10 and 15%. ATC verifies P-l 0 bistables lit on Panel 308 ATC verifies AI2-IG, 'P-lO PERMISSIVE'

-LIT. ATC blocks the IR High Flux Trip AND IR High Flux Rod Stop by placing the IR BLOCK TRAIN and TRAIN B control switches to the BLOCK position and verifies annunciator A12-2B is LIT. ATC blocks the Power Range Low Overpower Trip by placing the PR BLOCK TRAIN A and TRAIN B control switches to the BLOCK position and verifies annunciator A12-2C is LIT. ATC verifies that annunciator AI2-IH, 'NOT P-T is NOT LIT. ATC verifies that annunciator A4-5G is OFF. ATC selects highest power ranges on N-45.

BEAVER VALLEY I -,WER STATION INSTRUCTIONAL GUIDELINES Proceed with next event at LE discretion EVENTS 2 &3: 1 7 gpm S/G tube leak Insert TRG! 3 IMF RCS04B (3 0) 17.0 30 0 (preloaded) 10 minutes later, 2SVS-PCVIOIB fails open IMF CNH-MSS03A (3 600) 100 (preloaded)

PLANT STATUS I PROCEDURAL IMMEDIATE PLANT RESPONSE:

Rad Monitor alarms A4-5A; Radiation Monitoring Sys Trouble A4-5C, Radiation Monitoring Level High -LIT A4-5A, Reflash for Alert on 2SSR-RQ100, S/G Blowdown.

VCT level decreases SRO enters AOP 2.6.4 Estimate initial pri-sec leakrate EXPECTED STUDENT A TC reports Alarms to the SRO. BOP checks DRMS panel and determines that RQI02B is indicating a 1000 gpd tube leak in the "B" S/G. ATC reports VCT level decreasing.

BOP refers to the ARP and determines entry to AOP 2.6.4 is necessary.

SRO determines that the leak rate is > 30 gpd due to the HIGH alarm on 2MSS-RQ102B actuated.

SRO monitors S/G Tube leak by performing ATTACHMENT I of AOP 2.6.4. Check if PZR level can be maintained PZR Level is stable ATC determines value and trend for PZR level Crew identifies "B" S/G as the affected S/G due to Rad. Monitor alarms. ATC verifies VCT level can be maintained by normal makeup. BVPS -2L8 NRC Scenario 3, Rev 1 70f24 BEAVER VALLEY I -,WER STATION INSTRUCTIONAL GUIDELINES I* PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE As chemistry, acknowledge need identify S/G and quantify As RP acknowledge need to surveys and analysis.

Wait 5 then report back that the "B" Steam has elevated radiation Next event occurs 10 minutes initiation of Tube Leak EVENT 3: 10 minutes after tube leak occurs, 2SVS-PCVl OIB fails OPEN, requires manual isolation IMF CNH-MSS03B (3 600) 100 (Pre-loaded)

BVPS -2L8 NRC Scenario 3, Rev 1 SRO monitors S/G Tube leak by performing ATTACHMENT 1 of AOP 2.6.4. IMMEDIATE PLANT STATUS #2 ALARM PANEL on indicates S/G 21B ATM STM DUMP, PCVlOIB is 'NOT Red light illuminated for RCS Tavg shows a slight S/G level deviation alarms may ADV will NOT close from BB control 80f24 SRO notifies Chemistry of entry into AOP-2.6.4, requests them to obtain grab samples and identify S/G, and quantify leakrate.

SRO notifies RP of entry into AOP-2.6.4, requests surveys and analysis to identify and quantify leakrate.

SRO determines leak rate is > 30 gpd and proceeds to ACTION LEVEL 1 of Attachment

1. SRO references Technical Specification 3.4.13, Condition B is applicable for "RCS Operational Leakage".

SRO directs A TC to take manual control of open ADV, (2SVS-PCVlOIB) and close it. ATC places controller for 21B S/G ADV in manual and attempts to close ADV.

BEAVER VALLEY I -,lIVER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS / PROCEDURAL GUIDANCE EVENT 3: (continued)

Valve requires manual isolation, will not close via either local operation or by IF requested to Isolate INSERT 'LOA-MSS017 0' then to Control Room that 2SVS-24 Followup question may be regarding TS Proceed with next event at EXPECTED STUDENT RESPONSE SRO requests I&C assistance.

Crew notifies Field operator to close 2SVS-PCVlOIB using 20M-21.4.J Or locally isolate via 2SVS-24 or de-energize via MCC SRO refers to TS 3.7.4, Condition A for inoperable atmospheric dump valve. Requires restoring within 7 days. BVPS -2L8 NRC Scenario 3, Rev 1 90f24 BEAVER VALLEY I -,VVER STATION INSTRUCTIONAL GUIDELINES EVENT B Rep High Vibration/Seal Insert the IMF RCP01B (5 0) 4 IMF RCP06B (5 0) IMF RCP06B (0 120) 21 600 (inserted as preload on trg Trend on Rep vibration will need to observed before RCP trip criteria SRO may not enter Attachment 3 Trend ofRCP vibration has Immediate RCP Trip Criteria has BVPS 2L8 NRC Scenario 3, Rev PLANT STATUS I PROCEDURAL GUIDANCE IMMEDIATE PLANT 21B RCP sealleakoffrising as indicated A2-5C, Reactor Coolant Pump AlertlDanger

-LIT After 2 minute time delay 21 B RCP vibration rises to >20 mils. SRO enters AOP-2.6.8.

EXPECTED STUDENT ATC acknowledges RCP Hi vibration alarm, SRO, BOP refers to A2-5C Crew notes 21B RCP Shaft vibrations at 15 mils Crew checks RCP parameters in Table 1 of AOP to determine if Criteria is met for an Immediate Crew determines immediate RCP SID is not SRO continues in AOP ATC verifies that EITHER Seal Injection Flow Thermal Barrier cooling flow is indicated to SRO refers to Attachment 3 for RCP Vibration of 24 BEAVER VALLEY I ...-IIVER STATION INSTRUCTIONAL GUIDELINES NT STATUS I PROCEDURAL GUIDANCE EVENT 4: (continued)

Shaft vibration>

15 mils and rising at> 1.0 milslhr. EVENTS 5, 6, 7 & 8: preloaded to occur on the Rx trip) 500 gpm B SGTR IMF RCS04B (1 0) 500 (preloaded) 500 gpm 21B SGTR when the reactor is tripped. SRO enters E-O. EXPECTED STUDENT When it is determined that RCP vibration is > 15 mils rising at>1 mil/hour, the SRO directs a reactor trip and the stopping of21B RCP after E-O Immediate Actions are completed.

SRO directs ATC to trip the reactor ATC manually trips reactor. ATC informs SRO of a reactor trip. 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 off site power. BVPS -2L8 NRC Scenario 3, Rev 11 of24 BEAVER VALLEY I ,..",NER STATION I n-INSTRUCTIONAL GUIDELINES EVENTS 5, 6, 7 & 8: (continued)

NOTE: SI may not have actuated at this time however, RCS co"iiUitions are degrading due to 21B SGTR. If crew transitions to ES-O.l at this time, they will be required to manually actuate SI and return here. This scenario assumes SI is actuated at this time and the crew continues with E-O. I PL...Il.NT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE Due to SGTR, PZR level and pressure will be Check SI dropping.

Crew checks if SI is A TC checks Cnmt press> 5psig A TC checks PZR press < 1860 psig ATC/BOP checks Steamline press < 500 psig Crew determines SI is Required based on PZR pressure being < 1860 psig. A TC manually actuates SI -both trains by turning Control switches (BB-A). ATC/BOP, Sounds Standby Alarm, announces 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. HHSI Flow indicated, Both LHSI pumps running BOP verifies AFW System status Motor-driven AFW Pumps -BOTH running Turb driven AFW Pump Stm Supply Isol Valves -OPEN AFW Throttle Vlvs -FULL OPEN Total AFW Flow -> 340 gpm BVPS 2L8 NRC Scenario 3, Rev 120f24 BEAVER VALLEY. -,WER [ INSTRUCTIONAL GUIDELINES EVENTS 5, 6, 7 & 8: Evaluation of BOP Attachment A-0.l1 begins on page PLANT STATUS I PROCEDURAL GUIDANCE List of Attachment A-0.l1 Discrepancies:

Discrepancies:

NONE RCS temperature

< 547°F and dropping due to Safety Injection flow. CIB not actuated at this time. EXPECTED STUDENT RESPONSE SRO directs BOP to perform Attachment A-0.l1. 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. ATC reduces total feedflow to minimize CID. 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 VALUES Power to at least one block valve Block valves -AT LEAST ONE OPEN ATC checks if RCPs should be stopped DIP between RCS pressure and highest SIG pressure LESS THAN 205 PSID Criteria for stopping is not met -Leaves RCPs runnmg BVPS 2L8 NRC Scenario 3, Rev 13 of24 BEAVER VALLEY I ..JWER STATION INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 5, 6, 7 & 8: (continued)

SRO transitions to E-3 ATC/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. 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 deterrnines "B" S/G level rising in an uncontrolled manner and Secondary Radiation is NOT CONSISTENT

\\lITH PRE-EVENT VALUES. ATC Checks If CREVS Should Be Actuated:

Check EITHER of the following: Control Room Radiation Monitor 2RMC*RQ201, 202 -NOT IN HIGH ALARM CIB -HAS NOT OCCURRED Crew deterrnines CREVS actuation NOT required SRO directs STA to Commence Control Room ventilation actions. Refer to Attachment A-2.5. BVPS 2L8 NRC Scenario 3, Rev 14 of 24 BEAVER VALLEY I .... IIVER STATION [U INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 5, 6, 7 & 8:

ATC checks if RCPs should be stopped DIP between RCS pressure and highest S/G pressure < 205 PSID Criteria for stopping is not met -Leaves RCPs running Crew Identifies Ruptured S/Gs Unexpected rise in any S/G narrow range level High radiation from any S/G sample High radiation from any S/G steamline N16 monitor Main steam RM Radiation Protection survey High radiation from any S/G blowdown line Radiation Protection survey Crew determines "B" S/G is ruptured.

BVPS -2L8 NRC Scenario 3, Rev 150f24 BEAVER VALLEY I -,WER STATION ,_uINSTRUCTIONAL GUIDELINES EVENTS 5, 6, 7 & 8: (continued)

Critical Task: E-3.A Crew isolates feed flow into and steam flow from the ruptured S/G and directs operator to close isolation valve(s) operated from outside of the control room before a transition to ECA-3.1 occurs. Basis for Selection:

SAFETY SIGNIFICANCE

--Failure to isolate the ruptured S/G causes a loss of differential pressure between the ruptured S/G and the intact S/Gs. Upon a loss of differential pressure, the crew must transition to a contingency procedure that constitutes an incorrect performance that lI.necessitates the crew taking compensating action which complicates the event mitigation strategy.II ROLEPLAY:

5 minutes after being dispatched to locally isolate 2SYS*28, insert IRF LOA-MSSOIO (0 0) 0 0 then report back that 2SVS*28 has been closed.

STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE ATC/BOP Isolates Flow from the Ruptured S/G. Crew confirms 2SYS*PCYlOIB previously isolated.

BOP verifies residual heat release valve -CLOSED. SRO dispatches operator to locally close 2SYS*28. Isolate ruptured S/G to turbine driven AFW pump. BOP confirms 2 motor driven AFW pps running. BOP closes 2MSS*SOY105B and 105E. Verify closes ruptured S/G Blowdown isolation valve BOP verifies 2BDG* AOVIOOBI is closed. Close main steamline drain from ruptured S/G. BOP closes 2SDS*AOYII1Bl Close 2SDS* AOV129A, RHR piping drain isolation, BOP unsuccessfully attempts to close 2SDS*AOY129A.

BOP successfully closes 2SDS* AOY129B Close ruptured S/G main steam isol & bypass vlvs BOP closes 2MSS*AOYIOIB BOP verifies 2MSS* AOY102B closed. BOP checks ruptured NR S/G level> BOP closes AFW throttle valves on ruptured 2FWE*HCYIOOC, D (may have been emptively isolated)

Checks FWI -PREYIOUSL Y YERIFIED BOP checks ruptured S/G pressure-> 240 PSIG.

BYPS -2L8 NRC Scenario 3, Rev 160f24 BEAVER VALLEY I ../IIVER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS / PROCEDURAL GUIDANCE EXPECTED STUDENT EVENTS 5, 6, 7 & 8: (continued)

Condenser available Steam dumps fail closed when attempting to use them for cooldown. (command preloaded)

IMF CNH-PCS07A (4 0) 0 Crew initiates RCS cooldown SRO determines required core exit temperature as a function of ruptured S/G pressure:

SRO directs A TC to block low steamline pressure SI when PRZR pressure less than 1950 PSIG. BOP dumps steam to condenser from B & C S/Gs at maximum rate by; Checking MSIVs -AT LEAST ONE OPEN Checking condenser available Confirming condenser steam dump controller in MANUAL Verifying demand is at ZERO Confirms steam dumps are in STM PRESS Mode Checks TAVG > 541°F by Status light D-11, "2/3 Lo-Lo Tavg" (Panel 622) -LIT Defeats TA VG interlock until status light A-12, "Stm Dump Defeat Interlock" (Panel 622) -LIT Gradually raises steam dump rate to maximum rate demand) BOP reports steam dumps are not responding to controller demand. BVPS -2L8 NRC Scenario 3, Rev 170f24 BEAVER VALLEY I -,WER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE r EXPECTED STUDENT EVENTS 5, 6, 7 & 8: (continued)

NOTE: Before using 2SVS*HCVI 04, crew must recognize that they must have dispatched an operator to locally isolate from the "B" S/G and received a report that it was isolated.

SRO directs BOP to manually dump steam at maximum rate using atmospheric steam dumps. BOP opens 2SVS*PCVlOIA BOP opens 2SVS*PCVlOIC BOP opens 2SVS*HCV104 BOP checks intact S/G levels * "B" & "c" narrow range levels -> 12% BOP controls feed flow to maintain narrow range level between 26% and 50%. ATC Checks PRZR PORVs and Block valves

• Power to block valves -AVAILABLE

• PORVs -CLOSED

• Block valves -AT LEAST ONE OPEN A TC Resets SI, CIA and CIB BOP verifies at least 1 station air compressor running. BOP establishes CNMT instrument air by opening 2IAC*MOV130 and verifying open 2IAC*MOV131.

BOP verifies CNMT instrument air pressure>

85 psig. Check ifLHSI Pumps Should Be Stopped

• ATC checks RCS pressure -> 225 PSIG

• ATC stops LHSI Pumps AND places in AUTO BVPS 2L8 NRC Scenario 3, Rev 1 180f24 BEAVER VALLEY . ...IWER INSTRUCTIONAL GUIDELINES EVENTS 5, 6, 7 & 8: (continued)

Critical Task: E-3.B Crew establishes/maintains an RCS temperature so that transition from E-3 does not occur because the RCS temperature is in either of the following conditions:

Too high to maintain minimum required subcooling for subsequent RCS depressurization OR Below the RCS temperature that causes a red or orange path challenge to Sub-criticality or Integrity CSF Basis for Selection:

SAFETY SIGNIFICANCE

--Failure to establish and maintain the correct RCS temperature during a SGTR leads to a transition from to a contingency procedure, which constitutes an incorrect performance that " ... necessitates the crew taking compensating action which complicates the event mitigation strategy .... " PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE BOP checks if RCS cooldown should be stopped When Core exit TCs (average of five LESS THAN REQUIRED TEMPERATURE BOP stops RCS cooldown and maintains core exit TCs LESS THAN REQUIRED TEMPERATURE.

BOP verifies ruptured "B" SIG Pressure-STABLE OR RISING A TC verifies RCS subcooling based on core exit TCs GREATER THAN 61°F BVPS 2L8 NRC Scenario 3, Rev 190f24 BEAVER VALLEY I .JWER STATION L INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 5, 6, 7 & 8: (continued)

ATC Depressurizes RCS To Minimize Break Pzr spray valve, 2RCS*PCV455B fails And Refill open following depressurization.

• Checks RCPs 21A and 21C -(commands pre-loaded)

• Fully opens available PZR spray IMF VLV-RCS031 (75)

• Opens one PZR TRGSET 7 'RRCC455B

>= Checks depressurization method -IS EFFECTIVELY REDUCING RCS PRESSURE Critical Task: E-3.C A TC continues depressurization until any of Crew depressurizes the RCS to meet following conditions SI termination criteria before release from the ruptured S/G safety PZR level> or atmospheric relief valve. RCS subcooling

< Attachment Basis for Selection: SAFETY SIGNIFICANCE

--Failure to RCS pressure < "B" S/G pressure stop reactor coolant leakage into a PZR level> ruptured S/G by depressurizing RCS needlessly complicates mitigation ATC closes of the event. It also constitutes "significant reduction of safety margin A TC closes spray beyond that irreparably introduced by ATC reports 2RCS*PCV455B failed to the SRO directs ATC to stop 2IC RCP. Checks RCS pressure is rising A TC verifies RCS pressure is rising. BVPS -2L8 NRC Scenario 3, Rev 1 200f24 BEAVER VALLEY I -,WER STATION m '-----_IN_S_TRUCTIONAL GUIDELINES PLANT STATUS / PROCEDURAL GUIDANCE 1 EXPECTED STUDENT RESPONSE EVENTS 5, 6, 7 & 8: (continued)

Crew checks if SI Flow should be Terminated.

ATC verifies RCS Subcooling is > 41°F [59°F ADVERSE CNMT] based on CETC's BOP confirms secondary heat sink available by >340 gpm of feed flow available OR NR level in at least 1 S/G> 12% [31% ADVERSE CNMT]. ATC confirms RCS pressure is stable or rising. A TC reports pzr level is > 17% [38% ADVERSE CNMT] Crew determines that current plant conditions support SI termination.

A TC stops all but 1 Charging pump. Isolate High Head Injection Flow ATC closes 2SIS*MOV867A, B, C, & D A TC verifies HHSI flow indicates zero gpm. A TC Establishes Charging flow by: Closing Terminate scenario when the crew has Opening isolated HHSI flow and established a Opening normal chargIng flowpath.

Adjusting 2CHS*FCV122 as necessary maintain PZR level between 31 % and Classify ALERT due to Tab 1.2.4, LOSS RCS Barrier, Primary to BVPS -2L8 NRC Scenario 3, Rev 1 21 of24

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BEAVER VALLEY. JWER 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-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 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-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 3, Rev 220f24 BEAVER VALLEY, -,WER C:=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 CIS And CNMT Spray Status CNMT press -HAS REMAINED < 11 PSIG If not Actuate CIS 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 RU-N-NING Check SWS header pressure -> 55 psig SWS pump Seal Water Pressure -NOT LOW Verify both CNMT hydrogen analyzers running by 2HCS*SOVI00Al, Bl CNMT Sample amber lights LIT BVPS -2L8 NRC Scenario 3, Rev 23 of 24

--BEAVER VALLEY I ..JWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT Attachment A-O.ll -(continued)

Attachment A-O.ll -COMPLETE Discrepancies:

NONE 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 3, Rev 240f24 A d'.ppen IX 0 S .cenarlo 0 tl" u me F orm ES 0 1 --II Facility:

BVPS Unit 2 Scenario No.:4 Op Test No.: 2LOT8NRC T<,xaminers:

Candidates:

SRO ATC BOP Initial IC 214(18): 100% power, MOL, Eq Xe, eB "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.1.C Insert RCCA's Malf. No. I Event Type Event Description No. (1) ATe, SRO 2RCS*L T459 fails low. 1 (TS) SRO (N)ATe, SRO Restore letdown to service 2 (R) Valve position limiter failure causes load rejection with Auto 3 (I) ATe, SRO rod malfunction, ATC required to insert negative reactivity. (e) BOP, SRO During load rejection, "A" Main Feed Regulating Valve 4 controller holds valve in position, BOP required to manually control "A" S/G level. (C) ATe, SRO 2RCS*PT445 fails high, 2 PORV's open, 2RCS*PCV456 fails 5 (TS) to 18% open with Block valve failed open, requiring crew to manually trip the reactor. ATWS, crew enters FR-S.1. 6 (M)ALL 2000 gpm SBLOCA on return to E-O.7 (e) BOP, SRO Train B CIA failure with 2CHS*MOV378 failing to auto close 8 9 (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor i NUREG-1 021, Revision 9 Supplement 1 FENoe Facsimile Rev. 1 Appendix D Scenario Outline Form ES-D-1 2L8N4 The crew will assume the shift at 100% power with to maintain steady state conditions.

The controlling PZR level channel, 2RCS*LT459 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 3 minutes after the reactor is locally tripped, a 2000 gpm LOCA will occur on the "A" loop, the crew transition to 1. The crew will be required to recognize that RCS / 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 FR-S.l E-O E-l ES-1.2. NUREG*1 021, Revision 9 Supplement 1 FENoe Facsimile Rev. 1 BEAVER VALLEY I -"lIVER STATION INITIAL CONDITIONS:

IC 214(18): 100% power, MOL, Eq Xe, CB "D" @ 225 steps, RCS boron -1044 ppm. ADDITIONAL LINEUP CHANGES STICKERS MONITOR SETUP YCT -2FWE*P23A CS A TC position 1 display YCT -2SAS-C21B CS EOUIPMENT STATUS DATErrIME OOS TECHNICAL SPECIFICATION(S) 2FWE*P23A OOS, motor bearing replacement.

4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br /> 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 2.1.8 AOP 2.35.2 20M-6.4.IF , attachment 2 E-O FR-S.1 Attachment A-O.II BVPS -2L8 NRC Scenario 4, Rev 30f23 BEAVER VALLEY I .JWER STATION r-INSTRUCTIONAL GUIDELINEc=J PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE m 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) 1 IMF PPLOIB (0 0) 1 IMF PPL08B (0 0) 0 TRGSET 1 'XA4I106C' IMF VLV-SEAOI5 (0 0) 1 TRG 1 'DMF VLV-SEAOI5' TRGSET 10 'JMLEHC6' TRG 10 'SET JWSF478 AUTO=TRUE' IMF CNH-CFWI0C (10 45) 1500 IMF PPL02A (8 120) 1 IMF PPL02B (8 125) 1 IRF LOA-CRF007 (8 140) 1 IRF LOA-CRF008 (8145) 1 TRGSET 6 'RRCH456 > 0.0' IMF VLV-RCS034A (6 0) 1800 TRGSET 7 'MCRFNS(41)

<= 214' IMF CRFOIA (7 0) 1 IMF VL V -RCS012 (0 0) 1 IMF RCS02A (8 300) 2000 30 Reactor plant at 100% power, MOL, Equilibrium Xe, RCS boron 044 PPM, ARO. Inserts all pre-loads required to support the scenano 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 set 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 3 min after Rx tripped BVPS -2L8 NRC Scenario 4, Rev 1 40f23 BEAVER VALLEY I __ NER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE Assign shift positions SRO:.____.,--____ ATC:_________ 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, place the simulator to RUN and commence the scenario.

Simulator running. Crew assumes control of the Unit. BVPS -2L8 NRC Scenario 4, Rev 1 50f23 BEAVER VALLEY, ...-IIVER INSTRUCTIONAL GUIDELINES L PLANT STATUS I PROCEDURAL GUIDANCE r EXPECTED STUDENT EVENTS 1 &2: Pressurizer level transmitter 2RCS*LT459 fails low. IMF XMT-RCS019A (0 0) 2000 30 IMMEDIATE PLANT A4-1B, PZR Control LvI A4-1 C, PZR Control LvI Dev A4-1 G,PZR Control Htr Group A4-2G, PZR BIU Htr Group Auto A2-3E, Charging Flowpath 2RCS-LI459 indicates 2CHS*FCYI22 opens to increase Letdown isolates, 2CHS*LCY460B and AOY200A & B All PZR heaters SRO enters 20M-6.4.IF, attachment

1. ATC 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% low/85% high for manual PZR level control. BOP begins referring to ARP's. ATC places PZR level control channel selector to position II & III. A TC 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 1 60f23 BEAVER VALLEY I ,.,VVER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS / PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 1 & 2: (continued)

SRO directs ATC to restore letdown lAW ATC restores LID flow. 7.4.AB. SRO references Technical Specifications:

3.3.1 (RTS Instrumentation)

Condition A; immediately enter the Condition referenced in Table 3.3.1-1 function 9 (PZR level high) Condition K; trip channel in 72 hrs. or reduce power to < P-7 in 78 hrs. SRO determines following TS are for tracking only 3.3.3 (PAM instrumentation)

Table 3.3.3-1 function 11 is met ifLT460 and LT461 are operable.

3.3.4 (Remote Shutdown System) Table B.3.3.4-1 function 4.a requirement is met ifLT460 is operable.

SRO contacts Operations management and notifies I&C of level transmitter failure, Proceed with next event at LE discretion BVPS -2L8 NRC Scenario 4, Rev 1 70f23 BEAVER VALLEY I ...JWER STATION INSTRUCTIONAL GUIDELINES EVENTS 3 & 4: Turbine Runback due to Valve Position limiter failure, "A" main feed reg valve auto controller holds valve in position, Control rods step in until 214 steps then moving in Auto. IMF EHC06 (0 0) 79 0 ASIS Continue with next event at LE discretion BVPS -2L8 NRC Scenario 4, Rev 1 PLANT STATUS I PROCEDURAL GUIDANCE IMMEDIATE PLANT RESPONSE:

Rods begin stepping Megawatts RCS temperature and pressure rise Rods stop moving at 214 As power reduces "A" S/G level SRO enters AOP EXPECTED STUDENT RESPONSE lAW 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 ATC recognizes Tavg-Tref mismatch exists and places rods to manual and continues insertion.

BOP recognizes "A" S/G level is rising, takes manual control of"A" main feed reg valve and reduces flow to control level at 44%. SRO provides a control band and Rx trip criteria of 25% low/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 I -,lIVER STATION INSTRUCTIONAL GUIDELINES 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 "BOO CIA actuation failure with failure of2CHS*MOV378 to auto close. (all commands preloaded)

PLANT STATUS I 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 E-O SRO enters FR-S.l EXPECTED STUDENT A TC 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.1, implements FR-S.l at step 1 of E-O. BVPS -2L8 NRC Scenario 4, Rev 1 90f23 BEAVER VALLEY . ..JWER '----___

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 in 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 ieast minimize the power excursion associated with any subsequent return to criticality.

Failure to insert negative reactivity constitutes "mis-operation or incorrect crew perfonnance 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 Crewperfonns lOA's ofFR-S.l.

BOP manually trips Turbine. ATC manually begins inserting rods. BVPS -2L8 NRC Scenario 4, Rev 1 10 of23 BEAVER VALLEY I ..... IIVER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 6, 7, & 8 BOP verifies AFW status. BOP manually starts 2FWE*P23B motor-driven AFW pump. BOP manually opens 2MSS*SOV105A-F to start Turbine-driven AFW pump, 2FWE*P22.

BOP verifies all AFW throttle valves are open. BOP verifies AFW flow. NOTE: Crew initiates Emergency Boration Flow by; Dependent upon crew response, SI may not be actuated at this time, if so the Verifying at least 1 charging pump is running crew will initiate Emergency Boration Checking Safety Injection is actuated and recognizes flow by: Emergency boration is not required due to SI flow. Opening 2CHS*MOV350 BOP verifies HHSI Starting "A" Boric Acid Verifying>

30 GPM Adjusting 2CHS*FCV122 establish>

40 GPM ATC verifies RCS pressure is < 2330 psig. ,..... -t> BVPS 2L8 NRC Scenario 4, Rev 11 of23 BEAVER VALLEY I ...,NER STATION LIN§IRUGTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE EVENTS 6, 7, & 8 (continued)

Crew alerts plant personnel by; ROLEPLAY:

• Sounding the standby alarm. When requested to open the reactor trip

• Announcing a Unit 2 Rx trip w/o SCRAM. breakers & trip the rod drive MG set

• Dispatching an operator to locally trip the Rx' output ACBs, Following commands are activate Trigger 2 as soon as 1 st Rx trip breaker will open 2 after actuating Trigger 8. (TRG! IMF PPL02A (8 IMF PPL02B (8 IRF LOA-CRF007 (8140) IRF LOA-CRF008 (8 145) (all commands When all breakers are open, actions to the control Crew continues in FR-S.l after dispatching BOP verifies turbine is tripped. operator to locally trip the Unit 2 BOP verifies 2MSS-MOVlOOA, B automatically CLOSED. BOP depresses the RESET Pushbutton on the Reheater Controller.

ATC checks ifSI is SI is actuated, first nine steps of E-O have not BVPS 2L8 NRC Scenario 4, Rev 120f23 BEAVER VALLEY I .... VVER STATION INSTRUCTIONAL GUIDELINES EVENTS 6, 7, & 8 This is a continuous action step, the Rx is locally tripped the crew return to this step and then back to E-O, Step Event 7, 2000 gpm SBLOCA occur 3 minutes after the Rx is tripped. (command 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 130f23 BEAVER VALLEY. -"lIVER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EVENTS 6, 7, & 8 (continued)

SI automatically actuated due to low pressurizer pressure from stuck open PORV.

EXPECTED STUDENT RESPONSE Check SI Status: ATC checks that SI is actuated. ATC manually actuates SI by turning both trains Control Switches.

ATCIBOP, 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. HHSI Flow indicated. Both LHSI pumps running. BOP verifies AFW System status: Motor-Uri ven 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 I .AVER STATION CIN$IRlJCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 6, 7, & 8 Evaluation of BOP Attachment A -0.11 begins on page SRO directs BOP to perform Attachment List of Attachment 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-I 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. A TC reduces total feedflow to minimize C/D. ATC checks recirc spray pumps -NONE RUNNING. ATe 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 I -iWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT EVENTS 6, 7, & 8 (continued)

Critical Task E-l.C: Crew trips all RCPs when RCS to highest SG DIP criteria is exceeded and SI Dow 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 of 2200°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.

11 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] DP Criteria for stopping RCPs is met. ATC shuts down ALL RCP's after verifying HHSI flow. ATC verifies CIB is NOT actuated.

A TCIBOP 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. BVPS -2L8 NRC Scenario 4, Rev 160f23 BEAVER VALLEY I __ lIVER STATION [

GUIDELINES I. PLAf'!T STATUS I PROCEDURAL GUIDANCE EVENTS 6, 7, & 8 (continued)

EXPECTED STUDENT RESPONSE BOP Checks Intact S/G 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 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. 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

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BEAVER VALLEY. -,WER INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EVENTS 6, 7, & 8 (continued)

'.... EXPECTED STUDENT RESPONSE Crew checks if SI Flow should be Reduced. ATC verifies RCS Subcooling is NOT> 41°F [59°F ADVERSE CNMT] based on CETC's Crew verifies subcooling is NOT greater than Attachment Crew determines that current plant conditions do support SI reduction and continues with procedure Check if CNMT spray should be A TC verifies no Quench or Recirc Spray pumps A TC resets SI -both A TC resets CIA -both ATC checks if LHSI pumps should be A TC verifies RCS pressure is > 225 psig [250 ADVERSE CNMTl and NOT stable or ATC leaves both LHSI pumps BVPS 2L8 NRC Scenario 4, Rev 1 180f23 BEAVER VALLEY. JWER 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 SIG, NOT stable or rising. ATC checks RCS pressure is dropping.

SRO determines SIG pressure dropping is NOT due to a faulted SIG 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 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 A TC to monitor nuclear instrumentation to ensure adequate Shutdown Margin. BVPS 2L8 NRC Scenario 4, Rev 1 190f23 BEAVER VALLEY . JWER INSTRUCTIONAL GUIDELINES PLANT STATUS I 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.! Check if RCS cooldown and depressurization is required.

ATC checks RCS pressure>

225 psig [250 psig ADVERSE CNMT]. SRO determines plant conditions support transition to ES-l.2. SRO transitions to ES-l.2 Terminate scenario when the crew transitions to ES-1.2. Classify SAE, SITE AREA due to Tab 2.3, Failure of BVPS -2L8 NRC Scenario 4, Rev 1 200f23 BEAVER VALLEY * .JWER 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-AOVII8 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-MOVIOOA 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-AOVII8. 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 2Iof23 BEAVER VALLEY . JWER INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE nnn Attachment A-O.II 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 Rl.TN-NTN"G. Check SWS header pressure -> 55 psig. SWS pump Seal Water Pressure -NOT LOW. Verify both CNMT hydrogen analyzers running by 2HCS*SOVlOOA1, B -CNMT Sample amber lights LIT. BVPS -2L8 NRC Scenario 4, Rev 220f23 BEAVER VALLEY . ...JWER 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 tbis case, the containment barrier is needlessly left in a degraded condition.

Attachment A-O.ll -COMPLETE PLANT STATUS I 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 r A ,ppen d'IX 0 S cenano F orm ES 01 II Facility:

BVPS Unit 2 Scenario No.:5 OpTestNo.:

2LOT8NRC Bxaminers:

Candidates:

SRO ATC BOP Initial IC 217(10): 100% power, BOL, Eq Xe, CB "DOl @ 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 Malf. No. Event Type Event Description I No. (1) ATC, SRO 2RCS*PT444 drifts low, requires ATC to manually control 1 RCS pressure. (TS) SRO 2FWS-L T485 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 AFW 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)orrnal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1 021, Revision 9 Supplement FENOC Facsimile Rev. 1 Appendix D Scenario Outline Form ES-D-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.IF , 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 21B Channel II Narrow Range level transmitter will fail high requiring use of 20M-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 of the MUG. lAW the alarm response procedure, the BOP will tum the voltage regulator off and manually restore power factor and excitation by lowering the base adjust. A 25 gpm RCS leak will then occur on the "A" loop, the crew will recognize degrading parameters and enter AOP 2.6.7, Excessive Primary Plant Leakage, to address the primary plant leakage. The SRO will address RCS leakage Tech Spec. The leak will then become a 500 gpm SBLOCA, RCS pressure and pressurizer level will decrease requiring the SRO to direct the crew to manually trip the reactor and enter E-O. Upon the reactor trip, PORV 455D will fail partially open, the ATC will recognize PORV failure and close the block valve. Auxiliary feedwater malfunctions also occur on the reactor trip, the turbine driven pump will start but provide insufficient flow and the remaining available Motor driven AFW pump will fail to auto start, the BOP will manually start 2FWE*P23B.

SIS will fail to automatically actuate on low RCS pressure, the ATC will manually actuate SIS. Upon SIS actuation, 2SIS*MOV867's will fail to automatically open, the ATC will manually open valves to initiate SIS injection flow. The crew will transition from E-O to E-l when checking if RCS is intact based on containment parameters.

E-l 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-l ---+ ES-l.2. NUREG-1 021, Revision 9 Supplement 1 FENOC Facsimile Rev. 1 BEAVER VALLEY I ..JWER STATION INITIAL CONDITIONS:

100% Power, ARO, Equilibrium Xe, BOL, 1458 PPM Boron, IC-217 (10) ADDITIONAL LINEUP CHANGES STICKERS VOND MARKINGS YCT -2FWE*P23A CS ATC position -100% POWER display YCT -2SAS-C21B CS EQUIPMENT STATUS DATEffIME OOS TECHNICAL SPECIFICATION(S) 2FWE*P23A OOS, motor bearing replacement 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br /> ago 3.7.5 condition B 2SAS-C21 BOOS, compressor overhaul 3 days ago 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 I 20M-7.4.IF , Attachment 1 AOP 2.6.7 E-O E-l Attachment A-O.II BVPS -2L8 NRC Scenario 5, Rev 1 30f25 BEAVER VALLEY I -,WER STATION INSTRUCTIONAL GUIDELINES Initialize IC 217, 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)'

IRF LOA-AFWOOI (00) 0.1 0 IMF PPL07B (0 0) 5 IRF LOA-HIV055 (0 0) 1 IMF PMP-CAS004 (0 0) 1 IMF VL V -RCS033A (1 0) 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 VL V -SIS069 (0 0) 2 TRGSET 6 'XA4I081P' TRG 6 'DMF VL V -SIS069' IMF VL V -SIS070 (0 0) 2 TRGSET 7 'XA4I076P' TRG 7 'DMF VLV-SIS070' IMF VL V -SIS071 (0 0) 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 1 LelA"'!TSfATUS 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-C21 BOOS 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 *LCV 460A 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, -,WER INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE Assign shift SRO:________ATC:________BOP:________Conduct a shift turnover with oncoming Simulator Frozen until after shift turnover unless operators.

it needs to be run momentarily for an alignment change. When the shift turnover is completed, Simulator running. Crew assumes control of the place the simulator to RUN commence the BVPS -2L8 NRC Scenario 5, Rev 1 50f25 BEAVER VALLEY. __ lIVER STATION INSTRUCTIONAL GUIDELINES EVENT 1: Pressurizer Pressure control channel fails low IMF XMT -RCS030A (0 0) 1700 240 Proceed with next event at LE discretion BVPS -2L8 NRC Scenario 5, Rev 1 PLANT STATUS / 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. A4-1E, PZR Control Press Dev High/Low A4-2G, PZR BIU Htr Group Auto On/Off SRO enters 20M-6.4.1F, Attachment 2 EXPECTED STUDENT RESPONSE ATC reports unexpected alarm, A4-1E. ATC identifies 2RCS*PT444 failing low. A TC controls PZR pressure by operating Master Pressure controller in manual or manually operating individual PZR heaters and spray valves. BOP refers to ARP. With pzr htrs and spray valve control in Manual, SRO establishes a control band and Rx trip criteria 2100 psig low / 2340 psig high for manual pzr pressure control. SRO evaluates applicable TS; TS 3.3.4 for Remote Shutdown Instrumentation

-for Info Only. SRO contacts Operations management and notifies I&C of pressure transmitter failure. -60f25 BEAVER VALLEY I -,vVER STATION INSTRUCTIONAL GUIDELINES EVENT 2: 21B 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 LE discretion PLANT STATUS I PROCEDURAL IMMEDIATE PLANT RESPONSE:

2FWS*LT485 fails high A6-lOD, S/G 21B Level High/Low SRO enters 20M-24.4.IF, Attachment 1 EXPECTED STUDENT 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 E, 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 1 70f25 BEAVER VALLEY . ..JWER INSTRUCTIONAL GUIDELINES EVENT 3: Voltage Regulator Failure IMF GEN02 (0 0) 26 20 ASIS 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 VARS 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 1 80f25 BEAVER VALLEY . ..JWER INSTRUCTIONAL GUIDELINES EVENT 4: 25 gpm leak on "A" RCS loop IMF RCS02A (0 0) 25 0 Due to dynamic nature of event, followup question regarding TS may be BVPS 2L8 NRC Scenario 5, Rev 1 I PLANT STATUS I PROCEDURAL GUIDANCE IMMEDIATE PLANT RESPONSE:

PZR pressure begins A4-5A15C, DRMS Trouble / High CNMT Radiation 2RMR-RQ303A, B HIGH CNMT humidity SRO enters AOP 2.6.7 for excessive primary plant leakage. EXPECTED STUDENT A TC reports indications of a RCS leak inside ATC confirms VCT / PZR level can be Crew checks ifleakage is Crew confirms 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 A TC 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 recognizes TS 3.4.13 Condition A, is applicable for unidentified leakage. 90f25

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SEAVER VALLEY. ...WER INSTRUCTIONAL GUIDELINES EVENT 4: (continued)

EVENTS: 500 gpm SBLOCA on "A" RCS Loop NOTE: Command is preloaded to occur when 2CHS*LCV460A is opened during lid restoration step of AOP 2.6.7 PLANT STATUS I PROCEDURAL PZR level and pressure decreases EXPECTED STUDENT RESPONSE A TC quantifies leak rate, checks if leakage is in CVCS Isolates let.d.o:wn by closing 2CHS* AOV200A, 200B and 2CHS*LCV460A and 460B. Isolates charging by closing 2CHS*FCV122.

Adjusts 2CHS*HCV186 to obtain net input of 20 gpm. A TC trends PZR level and verifies PZR level is dropping.

ATC verifies VCT level can be maintained>

5% with normal makeup. ATC manually controls 2CHS*FCVI22 to maintain PZR level at approximately program level. A TC confirms leakage is not in the evcs system and restores Charging and Letdown by; Adjusting 2CHS*FCV122 for 30-50 gpm flow. Verifying PZR level> 14%. Placing 2CHS*PCVI45 in MAN & 50% open. Opening 2CHS*LCV460A and B Opening 2CHS* AOV200A and/or 200B/C. Adjusting 2CHS*PCV145 to 260 psig then returning to AUTO. When level is approx at program, places 2CHS*FCV122 in AUTO. A TC reports degrading primary plant conditions.

BVPS 2L8 NRC Scenario 5, Rev 1 10 of25 BEAVER VALLEY . .JWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 6, 7, 8, & 9: preloaded to occur on the reactor trip) SI Auto actuation failure 2RCS*PCV455D fails to 20% open -block valve can be closed to stop leak. 2FWE*P22 running with minimal flow gpm to each stG) 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. A TC verifies Reactor trip. A5-6D -LIT. Power range indication is < 5%. Neutron flux is dropping.

BOP verifies Turbine trip. Throttle OR Governor valves 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 * ....,WER [ INSTI3l..!CTlgNAL 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 performance that leads to degraded ECCS capacity." rPLANT STATUS I PROCEDURAL GUIDANCE PORV failing to 20% open on the reactor trip will reduce PZR pressure below Auto SI setpoint.

EXPECTED STUDENT RESPONSE Check SI Status. Crew checks if SI is required.

• A TC checks Cnmt press> 5psig

• ATC checks PZR press < 1860 psig

• ATC/ BOP checks Steamline press < 500 psig Crew determines SI is Required based on PZR pressure being < 1860 psig. A TC manually actuates SI -both trains by turning Control switches (BB-A). ATC/BOP, Sounds Standby Alarm, announces reactor trip and safety injection.

BOP checks 2HVS*FN204A(R), Leak Collection Filtered Exhaust Fan -at least ONE RUNNING. BVPS 2L8 NRC Scenario 5, Rev 1 120f25 BEAVER VALLEY I ""lIVER STATION [ 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 performance 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 mnning ATC notes zero HHSI flow, identifies MOV867 A, B, e & D all failed to open on the SIS actuation.

SRO directs ATe to align valves to establish flow. ATe manually opens 2SIS*MOV867A, B, e, & D and confirms HHSI flow exists. BVPS -2L8 NRC Scenario 5, Rev 1 13 of25 BEAVER VALLEY . ..JWER 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 establish 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 failure/incorrect auto actuation of an ESF system or component" BVPS -2L8 NRC Scenario 5, Rev 140f25 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 TotalAFWFlow-

<340gpm(-300)

BOP starts 2FWE*P23B and verifies total AFW flow is> 340 gpm.

BEAVER VALLEY I -,WER STATION INSTRUCTIONAL GUIDELINES EVENTS 6, 7, 8, & 9: 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 cm not actuated at this time. EXPECTED STUDENT RESPONSE SRO directs BOP to perform Attachment A-O.II. ATC checks RCS Tavg stable at or trending to 547°F. ATC 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. A TC checks recirc spray pumps NONE RUNNING BVPS -2L8 NRC Scenario 5, Rev 150f25

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BEAVER VALLEY I -,WER STATION 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 n demonstrated inability by the crew to take an action or combination of actions that would prevent a chal1enge to plant safety." PLANT STATUS I PROCEDURAL EXPECTED STUDENT RESPONSE ATC verifies PZR isolated PORVs -CLOSED ATC reports PORV 2RCS*PCV455D indicates dual position and won't close. ATC closes block valve 2RCS*MOV537 to isolate stuck open PORV. ATC continues verifying PZR isolated 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, 2 are 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 runnmg BVPS -2L8 NRC Scenario 5, Rev 160f25 BEAVER VALLEY, ..JWER CINSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EVENTS 6, 7, 8, & 9: (continued)

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

EXPECTED STUDENT RESPONSE ATC/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 RlSING 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. Crew checks ifRCS 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, -,WER LIN§IRUc;JIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EVENTS 6, 7, 8, & 9: (continued)

EXPECTED STUDENT RESPONSE A TC checks if CREVS should be actuated:

Checks EITHER of the following: Control Rodin Radiation Monitor 2RMC*RQ201,202

-NOT IN HIGH ALARM CIB -HAS NOT OCCURRED Crew reports CREV's is NOT required.

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 ATC leaves RCP's in service. ATC verifies CIB not actuated and is NOT required.

ATCIBOP 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 SIG's are faulted. BVPS 2L8 NRC Scenario 5, Rev 180f25 BEAVER VALLEY , -,WER INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EVENTS 6, 7, 8, & 9: (continued) EXPECTED STUDENT RESPONSE BOP Checks Intact S/G Levels Narrow range levels -> 12% [31 % ADVERSE CNMT] BOP maintains AFW flow> 340 gpm until> 12% at least 1 S/G then 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 RlSING 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

\-vith pre-event values, therefore all S/G tubes are intact. ATC checks PORV's and block valves. Power to block valves -AVAILABLE PORVs CLOSED Block valves AT LEAST ONE OPEN A TC reports power available to all block valves and block valves are open PORV 2RCS*PCV455D was previously identified being stuck open and is isolated with block BVPS -2L8 NRC Scenario 5, Rev 190f25 BEAVER VALLEY . .;WER INSTRUCTIONAL GUIDELINES LPLANT STATUS I PROCEDURAL GUIDANCE EVENTS 6, 7, 8, & 9: (continued)

EXPECTED STUDENT RESPONSE Crew checks if SI Flow should be Reduced ATC verifies RCS Subcooling is greater than 41°F [59 OF ADVERSE CNMT] based on CETC's BOP confirms secondary heat sink available by>340 gpm of feed flow available OR NR level in at least 1 S/G> 12% [31 % ADVERSE CNMT]. ATC reports RCS pressure is NOT stable or Crew determines that current plant conditions, level, does NOT support SI Check ifCNMT spray should be ATC verifies no Quench or Recirc Spray pumps ATC resets SI -both A TC resets CIA -both ATC checks if LHSI pumps should be A TC verifies RCS pressure is > 225 psig and stable ATC stops both LHSI pumps and places CS in BVPS -2L8 NRC Scenario 5, Rev 1 200f25 I BEAVER VALLEY I JWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EVENTS 6,7,8, & 9: (continued)

EXPECTED STUDENT RESPONSE 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 1 210f25 BEAVER VALLEY. JWER INSTRUCTIONAL PLANT STATUS I PROCEDURAL GUIDANCE EVENTS 6, 7, 8, & 9: (continued)

SRO transitions to ES-l.2 Terminate scenario when the crew transitions to ES-l.2. Classify ALERT, Tab 1.2.3, Potential Loss Res Barrier due to Res Leak EXPECTED STUDENT Start additional Plant Equipment to assist in SRO directs a field operator to perform Attach. Check if RCS cooldown and depressurization ATC checks RCS pressure>

225 SRO determines plant conditions support transition BVPS 2L8 NRC Scenario 5, Rev 1 220f25 BEAVER VALLEY * ...JWER PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE Attachment A-O.ll 'Verification of BOP performs Attachment A-O.ll, 'Verification of Automatic Actions' performed as time Automatic Actions' as follows: & manpower permit Checks both EDGs running Ensure reheat steam isolation Ensure Reheat Steam Isolation Verify 2MSS-MOVIOOA and B -CLOSED Reset reheater controller.

Check If main steamline isolation required CNMT pressure -> 7 PSIG Steamline pressure -< 500 PSIG Steamline pressure high rate of change 100 PSIG DROP IN 50 SECONDS If steamline isolation IS required, Verifies SLI by checking all YELLOW SLI marks -LIT If steamline isolation is NOT required continues on. NOTE: Establish domestic water system cooling to station BOP may have already pre-emptively opened 2CCS-AOVIl8 to provide .* Opens 2CCS-AOVlI8 cooling to the Station Air

• Verifies at least 1 air compressor is Verifies at least 1 CCP pump is running unless a CIB has occurred.

BVPS -2L8 NRC Scenario 5, Rev 230f25 BEAVER VALLEY

• JWER INSTRUCTIONAL GUIDELINES STATUS I PROCEDURAl...

GUIDANCE EXPECTED STUDENT 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 B V-I operator verifies CREVS actuation Service water established to RSS HX(s) Verify Service Water System In Service SWS Pumps -TWO RUNNING Check S WS header pressure -> 55 psig SWS pump Seal Water Pressure NOT LOW Verify both CNMT hydrogen analyzers running by 2HCS*SOVIOOAI, 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.1. Attachment A-O.ll -COMPLETE BEAVER VALLEY * ...JWER 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*MOV867A, 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 manually started BVPS -2L8 NRC Scenario 5, Rev 1 250f25

.. J CURRENT N41

, ES DETECTOR CURRENT

, ,

.,