Text

Draft Operating Exam (Sections a, B, and C) (Folder 2)
	ML12299A202
Person / Time
Site:	Beaver Valley
Issue date:	08/03/2012
From:	David Silk; Operations Branch I
To:	Rudolph W; FirstEnergy Nuclear Operating Co
	Jackson D
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)
	v • d • e

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

REFERENCE:

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 Classroom D OJT/TPE 0 Other:

D Training D Other:

EVALUATION RESULTS Performer Name: Performer SSN:

Time D Yes Allotted 35 Minutes Actual minutes Critical: C8J No Time: Time:

JPM RESULTS:

0 SAT 0 UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

RTL#A5.640U 112-ADM-130 1.F04 Page 4 of9 Revision I OPERATIONS JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET TASK STANDARD: Boron concentration for startup calculated within the specified tolerance.

RECOMMENDED Classroom STARTING LOCATION:

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

INITIAL CONDITIONS:

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

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

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

Current Core bumup is 10,000 MWDIMTU.

The plant computer is NOT available.

INITIATING CUE: 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.

REFERENCES:

20M-50A.F, "Performing An Estimated Critical Position Calculation",

Rev. 7 BV-2 Curve Book, curves CB-12, 21, 22, 23, 24B, and 29 TOOLS: None HANDOUT: 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:

DIRECTIONS: 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 CUE: 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.

RTL#A5.640U 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 STEP STANDARD

( "c" Denotes CRITICAL STEP) Indicate "S" FOR SAT or "u" FOR UNSAT)=> S/U DEVELOPERNALIDATION NOTES:

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

START TIME: _ _ _ _ _ __

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

(Part A I Prior to Shutdown)

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

Burnup Bumup 10,000 (MWD/MTU)

Xenon Xenon = 100% (CB-12)

Samarium Samarium = 100% (CB-22)

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

RTL#A5.640U 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 STEP STANDARD

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

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

(Part A II Expected at Criticality)

Date/Time == NOW Date/Time Burnup 10,000 (MWDIMTU)

Bumup Xenon 0% (CB-23)

Xenon Samarium 137.5% (CB-22)

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

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

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

Part III, Boron Cone. Part III, Boron 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:

RTL#A5.640U 1I2-ADM-1301.F04 Page 8 of9 Revision I OPERAnONS 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

4. 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:

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

for Startup (Data Sheet 1, Part C)

Part C.I

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

Part C.II

Differential Boron Worth = - 7.47 pcrn/ppm (CB-20)

Part c.m

Boron Change = + 509 ppm Part C.IV

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

EffBoron Conc. For Startup 1267.26 ppm COMMENTS:

i i

RTL#A5.640U 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 STEP I STANDARD

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

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

for Startup (Data Sheet 1, Part C)

Part C.l

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

Part c.n

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

Part C.I11

Boron Change = + 537 ppm Part C.IV

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

Part C.VI

Eff. Boron Conc. For Startup = 1295.26 ppm Part c.vn (+1- 50 ppm)

Part C.VIII

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 CUE:

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

STOP TIME: _ _ _ _ _ _ __

Page S of 28)

BVPS-IFR Station Startup AN Unit 2 20M-50A.F Revision 7 Operating Procedures Page 5 of 28 Performing An Estimated Critical Position Calculation B. Reactivity Balance

1. 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:

a. 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

b. 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.

2. 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:

a. BV-2 Curve Book Figure 24A, 24B, or 24C, "Integral Rod Worth vs. Steps Withdrawn Banks D and C Moving with Overlap".

OR

b. 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.

3. Determine Xenon worth forData Sheet 1, Part B, Columns I and II as follows:

a. 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 8 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

4. Determine Samarium worth for Data Sheet 1(2), Part B, Columns 1 and II as follows:

a. 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:

A 8 C Col. A x Col. 8/100% .

Samarium Worth Prior to Shutdown Column I Expected at Criticality Column \I OR

b. Have the Reactor Engineer provide Samarium values in pcm using a computer program that approximates Samarium worth.

5. Calculate the reactivity change as follows:

a. On Data Sheet 1(2), Part B, "Reactivity Balance", subtract Column I from Column II for each line.

b. Enter the results in Column III, "Difference".

c. Sum all the values in Column III and enter on Line 5.

d. Record this value on Data Sheet 1(2), Part C, Column I, Line 1.

C. Critical Boron Concentration for Startup

1. Data Sheet 1 Calculations

a. 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.

b. 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.

c. Enter the Effective Boron Concentration from Data Sheet 1, Part A, Column V on Data Sheet 1, Part C, Column IV, Line 1.

d. 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)

BVPS-lFR Unit 2 20M-50A.F Station Startup Revision 7 Operating Procedures Page 13 of 28 Performing An Estimated Critical Position Calculation DATA SHEET 1 FORM ECP-1 A. Critical Data c (I)

PRIOR TO SHUTDOWN (II)

EXPECTED AT CRITICALITY

\

Date .5"D/tVS "'.!!'" Date "J I~ VJ - Time Boron ~nc. S?~ ppm Power/(){) %

BumuplO~ ()()O (MWD/MTU) BumupJf1 tJOO (MWD/MTU)

Xenon ltJ() % Xenon 0 %

(Use Fig CB-12 or N/A) (Use Fig CB-23 or N/A)

I Samarium f)() % Samarium 137. S- %

(Use Fig CB-22 or N/A) (Use Fig CB-22 or N/A)

~OZflfOd;ii} ~ti~od6n5" B"Z. ~ D B D L".

(III) . ~~ (IV) M _ __

Boron Concentration B-10 Correction Factor Effective Boron (Part A. Column I) (use CB -29) Concentration III x I ppm 758.2(P ppm B. Reactivity Balance - (Record absolute values in Columns I and II)

(I) (II) (III)

Reactivity Defects Prior to Expected at (II-I)

Shutdown Criticality Difference

1. Power (OR Consult RX ENGR) Ii pcm cm

2. Control Rods (Circle Fig. used)

(Fig. CB-24A. 24B. 24C

\ OR Consult RX ENGR)

~~:.e~on (Fig. CB~3) ____________ ~~~-L~~~--~~~~~~~~~~

4. Samarium (Fig. CB-22)

5. Reactivity Change (Sum of 1-4) ==

DATA SHEET 1

~age 14 of 2S)

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

FORM ECP-1 C. Critical Boron Concentration

[-I (I)

Reactivity Change (B.5)

(II) (III)

Boron Change (I) + (II)

(IV)

Eff. Boron Cone.

at Shutdown (V)

Eff. Boron Cone.

for Startup (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)

~=-~~.~----~----~=-~~.~~---~---~~

5.2.~ 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 Expected At Worth Expected At (Circle Figure used)

(III) x (IV) Criticality (B.2) Criticality (V) + (VI) (Fig CB-24A, 248, 24C OR Consult RX ENGR)

(+/-) pcmi pcm H pcm Steps*

DATA SHEET 1

RTL#A5.640U 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

REFERENCE:

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 Name: Performer SSN:

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

JPM RESULTS:

D SAT D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

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

RECOMMENDED Simulator/Classroom STARTING LOCA nON:

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

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

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

REFERENCES:

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

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

HANDOUT: 10ST-2.4A, "Quadrant Power Tilt Ratio Manual Calculation", Rev. 8, place kept up to Step 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:

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

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

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

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".

D 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 TITLE: Perform a Quadrant Power Tilt Ratio Calculation JPM REVISION: 5 I STANDARD (Indicate liS" FOR SAT or "U" FOR UNSAT)=>

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.

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

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

(Uncor.) column of Data Sheet column.

1, using either of the following methods: COMMENTS:

a. Detector current meters located on power range drawers.

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

RTL#A5.640U 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 3.C 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:

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

Sheet 1:

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

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

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

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

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

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 5.C 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

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

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.)"

b. 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:

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

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

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

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

AND Compare the map with the results of the OST.

RTL#A5.640U 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 STEP I STANDARD

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

7.e 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: _ _ _ _ _ __

Quad rant Powe r Tilt Calcu lation 4/19/201011:13 AM

_e---....,.

.... '""'" .. ...",....,.i&i""'fi>~

.. J CURRENT N41

~o ES DETECTOR CURRENT N42

N43

N44

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 ALUATION 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 D Yes Allotted 25 Minutes Actual minutes Critical: kg] No Time: Time:

JPM RESULTS:

D SAT D UNSAT (Comments requin~d for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

RTL#A5.640U 112-ADM-1301.F04 Page 4 of6 Revision 1 EVALUATOR DIRECTION SHEET TASK STANDARD: Identify the tags and sequence of placement for a tagout of2QSS-P21B Quench Spray Pump 2113.

RECOMMENDED Classroom STARTING LOCATION:

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

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

Quench Spray Pump 2113 is to be placed on clearance.

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

Quench Spray Pump 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.

REFERENCES:

NOP-OP-IOOl, Clearance/Tagging Program, Rev. 18 TOOLS: None HANDOUT: 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 2R16-13-QSS-TRNG TodaylNOW 2QSS-P21B]

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

2R16 - SEAL REPLACEMENT 2001005844

RTL#A5.640U 1I2-ADM-130 l.F04 Page 5 of6 Revision I CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

DRead:

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

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

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

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

After determining the Task has been met announce: II I have completed the JPM lI

D Then hand this sheet to the evaluator.

RTL#A5.640U 112-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 NOTE:

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

EVALUATOR NOTE:

Provide JPM handout and student copy of worksheet.

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

COMMENTS:

EVALUATOR CUE:

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

STOP TIME: _ _ _ _ _ __

ANSWER KEY (DO NO'. GIVE TO STUDENTS)

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

c

...,o 1

Ii:

Q m

C GI C

o t

o u E

o U

I Z

LLI Q ....Q t;

~

o U

I Z

w Q

)

t;

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

REFERENCE:

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: LOCATION: TYPE: ADMINISTERED BY:

[g] Perform D Plant Site D Annual Requal Exam D BVT D Simulate D Simulator D Initial Exam D NRC

[8J Classroom D OJT/TPE D Other:

D Training D Other:

EVALUATION RESULTS Performer Name: Performer SSN:

Time lJ Yes Allotted 15 minutes Actual minutes Critical: [g] No Time: Time:

JPM RESULTS:

D SAT D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

RTL#A5.640U 1/2-ADM-130 l.F04 Page 4 of7 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-044 JPM TITLE: Select RWP and Determine Maximum Allowable Stay JPM REVISION: 0 Time EVALUATOR DIRECTION SHEET TASK STANDARD: Select the correct RWP and associated Task Number AND determine the maximum stay time according to survey map dose rates (cannot complete task due to R WP limit of 25 mrem dose)

RECOMMENDED Classroom STARTING LOCATION:

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

INITIAL CONDITIONS:

A clearance is being prepared to work on the containment sump flow integrator 2DAS-FQT1 00 located in the "A" Penetration.

You are assigned the task of connecting a drain hose to 2DAS 408, located near 2DAS-FQT100, in support clearance.

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

INITIATING CUE: 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.

REFERENCES:

NOP-OP-4107, "Radiation Work Permit (RWP)" ,Rev 10 TOOLS: Calculator HANDOUT: 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:

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

INITIAL CONDITIONS:

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

You are assigned the task of connecting a drain hose to 2DAS 408, located near 2DAS-FQT100, in support clearance.

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

INITIATING CUE: 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 JPM.

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

Simulate performance or perform as directed the required task.

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

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

D Then hand this sheet to the evaluator.

RTL#A5.640U 1/2-ADM-1301.F04 Page 6 of7 Revision 1 OPERAnONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-044 JPM TITLE: Select RWP and Determine Maximum Allowable Stay JPM REVISION: 0 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.

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

1.2C Selects Task # 3 (clearance activities).

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

COMMENTS:

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

25 mr I 20 mr/hr 1.25 hrs (EAD dose limit) (highest dose rate) (Stay Time)

COMMENTS:

RTL#A5.640U 112-ADM-130 I.F04 Page 7 of7 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-044 JPM TITLE: Select RWP and Determine Maximum Allowable Stay JPM REVISION: 0 Time STEP STANDARD

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

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

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

Evaluator discretion is required.

COMMENTS:

STOP TIME: _ _ _ _ _ __

RTL#A5.640U 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)

KJA

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 0 Yes Allotted 25 Minutes Actual minutes Critical: [8J No Time: Time:

JPM RESULTS:

D SAT D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

I Evaluator Signature:

RTL#A5.640U 1/2-ADM-1301.F04 Page 4 of 12 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET TASK STANDARD: Incorrect values for Inoperable rod worth, power defect, and SDM are identified and corrected. (See Answer Key for specific values)

RECOMMENDED Classroom STARTING LOCATION:

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

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

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

INITIATING CUE: As Shift Manager, review the completed 20ST-49.l, Shutdown Margin Calculation (Plant Critical) (Updated for Cycle 16). Document the results of your review in the appropriate section of the OST.

REFERENCES:

20ST-49.1, Shutdown Margin Calculation (Plant Critical) (Updated for Cycle 16), Rev. 18, Unit 2 Curve Book Cycle 16.

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

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

0.857 %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:

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

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

Annunciator [A4-3C], TAVG DEVIATION FROM TREF is "NOT LIT". ONE control rod has been determined to be inoperable, untrippable, and immovable during performance of 20ST-1.1, Control Rod Assembly Partial Movement Test. Chemistry has just reported current RCS boron concentration at 833 ppm. Current 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 CUE: As Shift Manager, review the completed 20ST-49.1, Shutdown Margin Calculation (Plant Critical) (Updated for Cycle 16). Document the results of your review in the appropriate section of the OST.

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

D When satisfied that you understand the assigned task, announce "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".

D 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)

STEP STANDARD

( "C" Denotes CRITICAL STEP) (Indicate "s" FOR SAT or "U" FOR UNSAT)=> I SIU I EVALUATOR NOTE:

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

EVALUATOR CUE:

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

Make any necessary corrections and complete the SDM calculation.

START TIME: _ _ _ _ _ _ __

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

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

(Otherwise N/A). COMMENTS:

(Step VILA.1)

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

VerifY that Tavg is less than gOF above Program Tavg as follows: (Otherwise N/A) COMMENTS:

(Step VII.A.2)

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 3.1 Verifies current boron concentration is 833 ppm from determine current RCS Boron initial conditions.

concentration in ppm.

(Step VII.A.3)

COMMENTS:

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

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

(Step VII.A.4)

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

power from [2NME-NR45],

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

U1150, 1MIN AVG PWR RNG NUCLEAR FLUX, on Data Sheet 1.

(Step VILA.5)

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

(Step VILA.6)

COMMENTS:

RTL#A5.640U 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)

STEP STANDARD

( "c" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "V" FOR VNSAT)~ SIU

7. If the number of immovable or 7.1 Verifies Step VILA.7 is NtA.

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

boron concentration with greater than one struck rod and Record below. (Otherwise NtA)

(Step VILA.7)

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

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

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

(Step VILB.I.a)

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

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

Data Sheet 1.

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

%8k/k AND Record on Data Sheet 1.

(Step VII.B.1.b)

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 I STANDARD

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

10. Subtract the integral rod 10.1 Verifies TBW-IRW is 7.571 %~k/k and recorded on worth from the Total Bank Data Sheet] (Block B.Lc).

Worth AND Enter the result on Data Sheet 1.

COMMENTS:

(Step VILB.l.c) 11 Multiply this result by 0.9 to 11.1 Verifies 90% ofTBW to be 6.8139 %~k/k and apply a 10% uncertainty AND recorded on Data Sheet 1 (Block B.l.d).

Enter the result on Data Sheet 1.

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

12.C If ONE rod is inoperable 12.1 C Determines stuck rod worth should be 2.31 0 %~k/k (untrippable), Record "Worst NOT 0.857 and records on Data Sheet 1 (Block Case Stuck Rod with B.2).

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

"B" on Attachment 2: for the appropriate Cycle Burnup.

(Step VII.B.2.b)

EVALUATOR NOTE:

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

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 T)~ 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:

I

14. Determine Power Defect as 14.1 Record RCS Boron Concentration of 833 ppm on follows: Data Sheet 1 (Block B.4.a).

Record RCS Boron Concentration results from COMMENTS:

Chemistry on Data Sheet 1.

(Step VII.B.4.a)

15. 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)

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 Inoperable Rod) (SRO ONLY)

STEP STANDARD

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

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

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

Record on Data Sheet 1.

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

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

this value on Data Sheet 1.

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

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

Sheet!.

(Step VII.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: 0 Inoperable Rod) (SRO ONLY)

STEP STANDARD

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

19.C Add 0.150% LikJk for 19.1C Determines Power Defect plus operating temperature operating temperature band band margin to be 2045 % LikJk NOT 2.95 % LikJk margin to the Power Defect and records on Data Sheet 1 (Block BA.f).

recorded in Step VII.BA.e AND Record on Data Sheet

1. COMMENTS:

(Step VII.BA.t) 20.C Determine SHUTDOWN 20.1C Determines SDM to be 2.054 % LikJkNOT 3.009 %

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

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

1.

(Step VII.B.5)

EVALUATOR CUE:

That Completes this JPM STOP TIME:

swe 20ST-49.1 Revision 18 Operating Surveillance Test Page 12 of 17 Shutdown Margin Calculation (Plant Critical)

(Updated For Cycle 16)

DATA SHEET 1 SHUTDOWN MARGIN CALCULATION A" 4. CBD Steps Withdrawn (OR cec if ceo @ 0 sleps) =225 STEPS

5. Reactor Power .. /tJO %

6. Number of inoperable Rods . - .1--

. ROD(s)

ARO TOTAL BANK WORTH ('Yo AkIk) oto 10000 MWDIMTU I 10000 to EOl 7.046 I 7.571 B. 1. a. AR o Total Bank Worth (See Table above) (TBW) = 1.511 % AkJk

b. Integral Rl0rth (Curve Book Figure 24A, 24B OR 24C) (IRW) .. L - p c m

1) _ _ (pcmfromB.1.b)X~ .. ~%AkIk 1000pcm

c. TBW (B.1.a) - IRW (B.1.b.1) : : 7.S71 %AkJk

d. 90% Current Total Bank Worth 0.9x 7.S71 (B.1.c) .. '.~(3~%AkJk

2. Inoperable (untrippable) OR Dropped Rod(s) Worth Z

31 ..9IJS1%AWk C.

3. (90% Total Bank Worth) - (Inoperable (Untrlppable) OR Dropped rod(s) 7~:Br!lc\ ).O~2.31 (B.1.d) ~

4.5tl3~

4. a. RCS Boron Concentration

b. B-10 Correction Factor (CB Figure 29)

c. (RA Boron Concentration>>)( (B-10 Correction Factor)

( i'i 5 ~

(B.4.a)

.--..Jx( o. 9()()

(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

~fect + Operatlng temperature band margin

(B.4.e) + 0.150% AkJk SHUTDOWN MARGIN (Acce Criteria - Within Li Specified In COL.R)

DATA SHEET 1

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 Final JPM REVISION: 0 Void Volume Calculation (lAW 20M-6.4.T, Response To Voids In The Reactor Vessel) (SRO ONLY)

KIA

REFERENCE:

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 ALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

[g] Perform D Plant Site D Annual Requal Exam D BVT D Simulate D Simulator D Initial Exam D NRC

[g] Classroom D OJT/TPE D Other:

D Training D Other:

EV ALUATION RESULTS I

Performer Name: Performer SSN:

Time D Yes Allotted 12 Minutes Actual minutes Critical: [g] No Time: Time:

JPM RESULTS:

D SAT D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

RTL#A5.640U 112-ADM-130 I.F04 Page 4 of8 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET TASK STANDARD: Incorrect RCS Initial Void Volume is corrected to 5781 FT3 + 4 AND Final Void Volume is corrected to 5477 FT3 +/- 4 RECOMMENDED Classroom STARTING LOCATION:

DIRECTIONS: 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 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.

INITIATING CUE: 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).

REFERENCES:

20M-6.4.T, Response To Voids In The Reactor Vessel, Rev. 3.

TOOLS: Calculator HANDOUT: 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 IV.B.5 calculation of RCS initial void volume.

1800 psig and 1900 psig are reversed in the step IV.B.6 calculation of RCS final void volume.

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

THIS SHEET TO BE GIVEN TO CANDIDATE

DRead:

TASK: 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 CUE: 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 lPM.

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

Simulate performance or perform as directed the required task.

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

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

D Then hand this sheet to the evaluator.

RTL#A5.640U l/2-ADM-130 1.F04 Page 6 of8 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-040 JPM TITLE: Review completed Res 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

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

EVALUATOR NOTE:

Information used to fill-out procedure:

Pi = 1800 psig Pr = 1900 psig Li = 50%

Lr= 25%

EVALUATOR NOTE:

Some judgment may be required to determine satisfactory performance on this JPM.

EVALUATOR NOTE:

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

Make any necessary corrections and complete the void volume I:alculations.

START TIME: _ _ _ _ _ _ __

RTL#A5.640U 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 UNSAT)~ SID I.e 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 - ~ I_~>>

Gi=(( - ~x 12.17) 1 (1 - ('-_ _ __

1 >>

G i =- - - - cu-ft.

G i =(L25~ x 12.17) 1 (1- C.947368421~)

G i =C304.25--> 1(.052631579)

Gi = 5781 cu-ft.

COMMENTS:

RTL#A5.640U l/2-ADM-1301.F04 Page 8 of8 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER:" 2AD-040 JPM TITLE: Review compl(~ted 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 UNSAT =>

2.C 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:

RTL#A5.640U 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

REFERENCE:

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

~ Classroom D OJT/TPE D Other:

D Training D Other:

EV ALUATION RESULTS Performer Name: Performer SSN:

Time D Yes Allotted 15 minutes Actual minutes Critical: [gJ No Time: Time:

JPM RESULTS:

D SAT D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

RTL#A5.640U 1/2-ADM-1301.F04 Page 4 of7 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-041 JPM TITLE: Perform a Risk Assessment [2FWE*P23A Maintenance]

JPM REVISION: 0 (SRO Only)

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

RECOMMENDED Classroom STARTING LOCATION:

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

INITIAL CONDITIONS:

The Unit is in Mode 1 at 100% power.

PRA Risk & Traffic Light are GREEN.

Protected Train is "B".

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

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

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

INITIATING CUE: As Shift Manager you are to evaluate the risk level based on initial plant conditions for upcoming activities (2FWE*P23A repairs) AND determine who must approve this risk level in accordance with NOP OP-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)

REFERENCES:

NOP-OP-1007, "Risk Management", Rev. 14 Technical Specifications Beaver Valley Power Station Units 1 & 2 TOOLS: None HANDOUT: 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)

RTL#A5.640U 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:

TASK: 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 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

INITIATING CUE: As Shift Manager you are to evaluate the risk level based on initial plant conditions for upcoming activities (2FWE*P23A repairs) AND determine who must approve this risk level in accordance with NOP OP-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 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".

D Then hand this sheet to the evaluator.

RTL#A5.640U 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 UNSAT ~

START TIME:

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

1. Refers to NOP-OP-l 007, "Risk 1.1 Refers to NOP-OP- 1007.

Management" provided.

COMMENTS:

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 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

2.C 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 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months is greater than half of the 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months allowed Technical Specification (TS) Action Statement for any TS which requires a Unit Shutdown if not exited.

2.2 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)

STEP

("e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "V" FOR VNSAT)~

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 difl~ction sheet.

COMMENTS:

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 I~ 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 20 Minutes Actual minutes Critical: [2J No Time: Time:

JPM RESULTS:

D SAT D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR i

Evaluator (Print): Date:

Evaluator Signature:

RTL#A5.640U 1/2-ADM-1301.F04 Page 4 of7 Revision 1 OPERAnONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-042 JPM TITLE: Determine compensatory actions for 2GWS-P21 and JPM REVISION: 0 2GWS-OA-I00A being OOS. (SRO ONLY)

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

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

RECOMMENDED Classroom STARTING LOCATION:

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

The plant is 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.

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

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

REFERENCES:

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

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

The plant is operating at 100% power with al1 system in NSA.

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

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

The Gaseous Waste Storage Tanks Recirculation Pump

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

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

Oxygen Analyzer (2GWS-OAIOOB) is OPERABLE.

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

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

Simulate performance or perform as directed the required task.

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

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

D Then hand this sheet to the evaluator.

RTL#A5.640U I12-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 the Candidate Direction Sheet and a current copy of OM Fig. 19-3, LRM, AND Yz ODCM Section 3.0.3, EVALUATOR NOTE:

These steps may be perfonned in any order.

EVALUATOR NOTE:

The next step may not be necessary. The candidate may already be familiar enough with the system to know the impact of2GWS-P21 being OOS.

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.

2.C 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 (2GWS 2.2C Detennines that it will be required to verify, least RQ104) being out of service. once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , that the GW storage tanks contain less or equal to 19,000 curies. (when adding radioactive materials to the tank)

COMMENTS:

RTL#A5.640U 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 STANDARD

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

3.C Determines LRM compensatory 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 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months take grab samples and analyze for oxygen content.

COMMENTS:

EVALUATOR CUE:

That completes this JPM.

STOP TIME: _ _ _ _ _ __

RTL#A5.640U 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:

I ~ Perform 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 15 Minutes Actual minutes Critical: D No Time: Time:

JPM RESULTS:

D SAT D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Narne/SSN: Narne/SSN:

Narne/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

RTL#A5.640U 1I2-ADM-1301.F04 Page 4 of7 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD TLE: Complete Initial Notification Fonn for a General JPM REVISION: 0 Emergency (SRO ONLY)

EVALUATOR DIRECTION SHEET TASK STANDARD: 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.

RECOMMENDED Classroom STARTING LOCATION:

INITIAL CONDITIONS: You have declared a General Emergency based on EAL Tab 2.3 today at Unit 2 @ 1000 hours0.0116 days 0.278 hours 0.00165 weeks 3.805e-4 months 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ).

Valid Dose projections are not yet available INITIATING CUE: 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 1/2-EPP-IP 4.1, "Offsite Protective Actions". Return the Initial Notification Fonn to the examiner as soon as you are finished.

This JPM is time critical.

REFERENCES:

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 TOOLS: 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-1301.F04 Page S of7 Revision 1 OPERA TIONS JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

DRead:

INITIAL CONDITIONS: You have declared a General Emergency based on EAL Tab 2.3 today at Unit 2 @ 1000 hours0.0116 days 0.278 hours 0.00165 weeks 3.805e-4 months 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ).

Valid Dose projections are not yet available INITIATING CUE: 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 1I2-EPP-IP 4.1, "Offsite 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 lPM.

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 lPM",

D 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 =>

STARTTIME:_~_~_ __

EVALUATOR CUE: Provide the Candidate with the Candidate Direction Sheet and a copy of 1I2-EPP-IP 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 TITLE: Complete Initial Notification Form for a General JPM REVISION: 0 Emergency (SRO ONLY)

STEP STANDARD

( "e" Denotes CRITICAL STEP) 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 POWER STATE I COUNTY USE ONLY PLANT INITIAL NOTIFICATION

INITIAL CLASSIFICATIONS,

CHANGES IN CLASSIFICATIONS, DATE: TIME:

FORM

CHANGES IN PROTECTIVE ACTION Beaver Valley MESSAGE NO:

RECOMMENDATIONS.

1I2-EPP-IP-1.1.F01 Rev. 5

EVENT TERMINATION

1. This is the: 0 Beaver Valley Power Station Unit 1 Reactor Power Level ,o~ %

S,..(')A~I.. .J04

~

t.

.. \\

119 Beaver Valley Power Station Unit 2 Reactor Power Level_O=-_%

Code Word

--'0",...--=-;-,-:-,-

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: l()~O on ""fQb:::t based on EAL(s}: 'l.l (TIME) (DATE) o b. The Emergency situation has been terminated at: on (TIME) (DATE) o c. The Protective Action Recommendation is being changed at: on (TIME) (DATE)

4. Brief non-technical description of event: A1" 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 progress.

The release is: I}g~~borne 0 Liquid 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,

~C o N/A I25J 2 Miles - 360 0 05 Miles - 360 0 010 Miles - 360 0 AN D Evacuate Downwind Wedge N/A" ~ 5 Miles (check applicable sectors)

""e" 0 A 0 B COD E OJ OK AND that potassium iodi ea 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

~

e f' "

c

7. Wind Direction is FROM: \\0 degrees at 150' Wind Speed is: 12. mph at 35' Callback number is 724-643-8000 For Utility Use Only

! PEER Check: 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 ALUATION 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 D Yes I A.Hotted 15 minutes Actual minutes Critical: cg] No TIme: Time:

JPM RESULTS:

D S.AT D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

RTL#A5.640U 1/2-ADM-1301.F04 Page 4 of8 Revision 0 JPM NUMBER: 2CR-072 JPM TITLE: Shift From Main Feedwater Reg Valves to Bypasses JPM REVISION: 3 EVALUATOR DIRECTION SHEET TASK STANDARD: The "A" Bypass Feed Regulating Valve is in automatic and controlling steam generator level.

RECOMMENDED SIMULATOR STARTING LOCATION:

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

INITIAL CONDITIONS:

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.

INITIATING CUE:

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%.

REFERENCES:

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

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

RTL#A5.640U 1I2-ADM-130 l.F04 Page 5 of8 Revision 0 CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

DRead:

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

INITIAL CONDITIONS:

The plant is at approximately 25% power.

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

D Then hand this sheet to the evaluator.

RTL#A5.640U 112-ADM-130 I.F04 Page 6 of8 Revision 0 OPERATrONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-072 JPM TITLE: Transfer from Main Feedwater Reg Valves to Bypasses JPM REVISION: 3 I STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT)~ 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.

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

attachment 10.

COMMENTS:

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

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

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

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

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

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

Green light -LIT, Red light- NOT LIT.

COMMENTS:

RTL#A5.640U 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 STANDARD

( "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 in Reg Valve is fully closed, MANUAL.

perform the following:

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

Reg Valve controller in MAN.

3.3 Closes 2FWS-MOV154A by placing CS to close, and Observe Feedwater flow, steam verifies Green light - LIT and Red light NOT LIT.

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

Feed Reg Valve.

Closes [2FWS-MOV154A], 21A S/G Main Feedwater Isol Vlv.

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

Monitor S/G level and flow.

4.2C Place the controller for 2FWS-FCV479 in AUTO.

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

4.3 Monitors AUTO operation of the valve to ensure it controls level between 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

5. 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 Perform 0 Plant Site 0 Annual Requal Exam 0 BVT 0 Simulate ['gJ Simulator 0 Initial Exam 0 NRC 0 Classroom 0 OJT/TPE 0 Other:

0 Training 0 Other:

EVALUATION RESULTS Performer Name: Performer SSN:

Time 0 Yes Allotted 20 Minutes Actual minutes Critical: ['gJ No Time: Time:

JPM RESULTS:

D SAT 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 1/2-ADM-1301.F04 Page 4 of 10 Revision 1 EVALUATOR DIRECTION SHEET TASK STANDARD: Contiguous area ventilaTion aligned through the filtered flowpath.

RECOMMENDED Simulator STARTING LOCATION:

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

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

REFERENCES:

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

High Level Alarm, Issue 1 Revision 5.

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

High Level Alarm, Issue 1 Revision 5.

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

RTL#A5.640U 1I2-ADM-130 l.F04 Page 5 of 10 Revision I CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

DRead:

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

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

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 announc(~ " I have completed the JPM".

D 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 TITLE: Respond to Radiation Monitor Alarm JPM REVISION: 3 STEP STANDARD

( "C" Denotes CRITICAL STEP (Indicate "S" FOR SAT or "U" F'OR UNSA T)=>

SIMULATOR SETUP:

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

(Train A switch removes malfunction from 2HVS MOD202A, Train B switch removes malfunction/rom 2HVS-MOD201B)

EVALUATOR CUE:

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

START TIME: _ _ _ _ _ _ __

EVALUATOR NOTE:

Steps 1 6 are required only if the candidate refers to 20M-43A.AAC. Steps 7 and beyond are to be referenced for 20M-43A.AEB actions.

1. Obtain procedure. (20M** 1.1 Locates copy of procedure 20M-43A.AAC 43A.AAC)

EVALUATOR CUE:

After candidate locates the procedure, the evaluator can provide a copy of 20M-43 A.AAC to candidate.

COMMENTS:

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 UNSAT)~ Stu

2. Determine which radiation 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 COMMENTS:

and select.

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

COMMENTS:

5. Press SYSTEM ACK to silence 5.1 Depresses the SYSTEM ACK pushbutton on the DRMS the console 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 UNSAT)=> SIU

6. Verify if radiation level is greater 6.1 N/A than 1000 times background. r-------.-------------------,

EVALUTORCUE:

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

COMMENTS:

7. Determine 2RMR-RQI301 is in 7.1 Determines 2RMR-RQI301 (Leak Collection alarm and refers to local alarm Ventilation Radiation Monitor) is in alarm.

response procedure for corrective actions. 7.2 Refers to local alarm response procedure (20M 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 UNSAT)=> 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 setpoint. . 9.2 Determines that the actual value is higher than the HIGH alarm setpoint.

COMMENTS:

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

EVALUATOR CUE:

Role-play the SM and acknowledge the report.

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

The SM will perform the other remaining steps of this procedure (1.d., l.g., l.h., & l.i.)

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 "FILT" position. CS' scan be manipulated in any order. 2HVS*MOD20IA and 2HVS*MOD202B will NOT change position. Both Trains Switches will need to be placed to the "FILT" 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 STANDARD

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

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:

12.C 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 FILT position (2HYS*MOD201B will close when the "B" train CS is placed in "FILT").

COMMENTS:

EVALUATOR NOTE:

Candidate should report to supervisor that 2HYS*MOD20IAl202B did not change positions.

EVALUATOR CUE:

That Completes this JPM 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

REFERENCE:

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] Perform 0 Plant Site 0 Annual Requal Exam 0 BVT 0 Simulate [g] Simulator 0 Initial Exam 0 NRC 0 Classroom 0 OJT/TPE 0 Other:

0 Training 0 Other:

EV ALUATION RESULTS I

Performer Name: I Performer SSN:

Time 0 Yes Allotted 16 Minutes Actual minutes Critical: [g] No Time: Time:

JPM RESULTS:

D SAT D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

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

RECOMMENDED Simulator STARTING LOCATION:

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

All shutdown bank rods are fully withdrawn.

Control Bank "D" is at 91 steps.

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

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

REFERENCES:

20M-50A.D2, Reactor Startup From Mode 3 to Mode 2, Rev. 2 Data Sheet 3 20M-50A.F Rev 7 Filled out for 11M plot 20M-53CA.2.1.3, RCCA Control Bank Inappropriate Continuous Movement, Rev. 7 TOOLS: None HANDOUTS: 20M-50A.D2, Reactor Startup From Mode 3 to Mode 2, Rev 2, Placekept up to step IV.C.9 Filled out Data Sheet 3 (11M Plot) 0:f20M-50A.F, Rev 7 (may cue as met) 20M-53CA.2. 1.3, RCCA Control Bank Inappropriate Continuous Movement, Rev. 7 (not provided initially)

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

THIS SHEET TO BE GIVEN TO CANDIDATE

DRead:

DIRECTIONS: You are to "Raise Reactor Power To 10-8 Amps" INITIAL CONDITIONS: A reactor startup is in progress in accordance with 20M-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 CUE: The Unit Supervisor directs you to withdraw control rods to 116 steps on Bank D OR to criticality in accordance with 20M-50.4.D2, beginning at 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 When satisfied that you understand the assigned task, announce "I am now beginning the JPM".

Simulate performance or perform as directed the required task.

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

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

D Then hand this sheet to the evaluator.

RTL#A5.640U 112-ADM-1301.F04 Page 6 of 10 Revision]

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

( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSA T)=>

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: _ _ _ _ _ __

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

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

COMMENTS:

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

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

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

(Step IV.C.9.b)

COMMENTS:

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 STEP STANDARD

( "c" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FORJ'NSAT)=> Stu

2. When Status Light 2.l. Records SR counts for N31 and N32.

Annunciator A12-3B "P6 Pennissive" is on (1 E-l 0 COMMENTS:

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) 3.C De-energize the N31 SR 3.1C Places Source Range' A' Block to the BLOCK High Voltage and block the position.

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

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

(Step IV.C.lO.b) 4.C De-energize the N32 SR 4.lC P1aces Source Range 'B' Block to the BLOCK High Voltage and block the position.

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

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

(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 UNSAT)=> Stu I

5. 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)

6. 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 TITLE: Raise Reactor Power To 10-8 Amps JPM REVISION: 2 I STANDARD

~

STEP

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

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

8.C Continue incremental rod 8.1 C Candidate continues withdrawing control rods to withdrawal until the reactor obtain a stable startup rate.

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

instrumentation once the prompt jump has receded. COMMENTS:

(Step IV.C.12)

9. Determine that rods are 9.1 Candidate dletermines from CONTROL BANK D withdrawing with NO GROUP 1 and GROUP 2 ROD POSITION indication demand signal. that rods are withdrawing with NO demand signal.

COMMENTS:

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 STANDARD

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

w.e 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 FAULTED 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:

EVALUATION RESULTS Performer Name: Performer SSN:

Time D Yes Allotted 15 Minutes Actual minutes Critical: [8J No Time: Time:

JPM RESULTS:

D SAT D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Narne/SSN:

Narne/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

RTL#A5.640U 112-ADM-130 I.F04 Page 4 of 10 Revision 1 EVALUATOR DIRECTION SHEET TASK STANDARD: SI Accumulators 'A' and 'B' are isolated. SI Accumulator 'c' is venting.

RECOMMENDED Simulator STARTING LOCATION:

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

INITIAL CONDITIONS: A LOCA has occurred. The crew is performing ES-l.2, Post LOCA Cooldown and Depressurization.

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

REFERENCES:

20M-53 .A.l.ES-I.2, Post LOCA Cooldown and Depressurization, Issue I C, Rev. 10 20M-It.4.G, Venting A Safety Injection Accumulator, Rev. 21 20M-53A.1.A-5.l, OF Plus Subcooling Based On Core Exit TCs, rev 1 TOOLS: Three Shorting Bars HANDOUT: 20M-53.A.l.ES-1.2, Post LOCA Cooldown and Depressurization, Issue 1C, Rev. 10, place kept up to step 27.

20M-l1.4.G, Venting A Safety Injection Accumulator, Rev. 21 20M-53A.l.A-5.l, OF Plus Subcooling Based On Core Exit TCs rev. 1

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:

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

INITIAL CONDITIONS: A LOCA has occurred. The crew is performing ES-I.2, Post LOCA Cool down and Depressurization.

INITIATING CUE: 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 JPM".

D Then hand this sheet to the evaluator.

RTL#A5.640U 112-ADM-J301.F04 Page 6 of \0 Revision 1 OPERA TIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-6S4 JPM TITLE: Isolate SI Accumulators During a LOCA JPM REVISION: 2 STA~N~D~A~R~D~----------------------------------'-~

STEP

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

SIMULATOR SETUP:

Initialize simulator to any Mode I IC.

Insert SBLOCA @ 500 gpm.

Progress through EOP set up until Step 27 ofES-1.2.

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

Insert VL V -SIS068 (override SIS*MOV865C in the open position).

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

EVALUATOR NOTE:

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

START TIME: _ _ _ _ _ __

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

COMMENTS:

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

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

ATTACHMENT A-S.l.

2.3 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 JPM NUMBER: 2CR-654 JPM TITLE: Isolate SI Accumulators During a LOCA I JPM REVISION: 2 I STANDARD FOR~AT or "U" ~OR '-.}NSAT)=> I SfU I STEP

( "e" Denotes CRITICAL STEP) (Indicate "S"

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

COMMENTS:

4. Power to [2SIS*MOV865A, B, 4.1 Verifies [2SIS*MOV865A, B, 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 5.1 Contacts Shift manager and requests shorting bars.

[2SIS*MOV865A, B, C].

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

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

5.4 Inserts into [2SIS*MOV865C] jack.

COMMENTS:

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 I

I STANDARD U~SAT)::::> I S/U STEP

( lie" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "u" FOR !

FAULT STATEMENT:

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

EVALUATOR NOTE:

Accumulator isolations may be done in any order.

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

C].

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

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

COMMENTS:

7. Vent any unisolated 7.1 Refers to 20M-l1.4.G to vent 2SIS*TK21C.

accumulator. Refer to 20M 11.4.G, "Venting A Safety EVALUATOR CUE:

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

COMMENTS:

RTL#A5.640U 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 FOR~AT or "U" FOR UNSAT):::> I Stu I STEP STANDARD

( "C" Denotes CRITICAL STEP) (Indicate "S"

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

vacuum, close [2SIS*367 (369)

(399)] Accumulator COMMENTS:

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

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

1O.C Open [2GNS*SOV853A(D) 10.1C Places [2GNS*SOV853C OR F] CS to OPEN.

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

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

COMMENTS:

11.C Open [2GNS*SOV854A 11.1 C Places [2GNS*SOV854A OR B] CS to OPEN.

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

Vlv until the Accumulator is lowered to the desired value, 113 Verifies [2SIS-PI929 & 931] indicate accumulator then close [2GNS*SOV854A pressure is lowering.

(854B)].

EVALUATOR NOTE:

Candidate may refer to PCS to monitor accumulator pressure.

COMMENTS:

RTL#A5.640U 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, terminate JPM.

That completes this JPM.

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 ALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

~ Perform D Simulate I~ Plant Site Simulator D

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

D Training D Other:

EVALUATION RESULTS Performer Name: Performer SSN:

Time D Yes Allotted 15 Minutes Actual minutes Critical: [g] No Time: Time:

JPM RESULTS:

D SAT D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

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 TITLE: Perform Manual Makeup to the Charging Suction JPM REVISION: 6 EVALUATOR DIRECTION SHEET TASK STANDARD: Perform control board manipUlations and calculations to perform a manual blender makeup to the VCT in accordance with 20M-7.4.N, "Blender Manual Makeup Operations".

Makeup secured after discovery of no boric acid flow.

RECOMMENDED Simulator STARTING LOCATION:

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

INITIAL CONDITIONS:

The plant is in Mode 1.

The in service Boric Acid Tank concentration is 7487 ppm.

VCT level is currently 22%.

All initial conditions are satisfied.

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

REFERENCES:

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

RTL#A5.640U 1I2-ADM-130 l.F04 Page 5 of 11 Revision 1 CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

DRead:

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

INITIAL CONDITIONS:

The plant is in Mode 1.

The in service Boric Acid Tank concentration is 7487 ppm.

VCT level is currently 22%.

All initial conditions are satisfied.

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

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

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

Simulate performance or perform as directed the required task.

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

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

D Then hand this sheet to the evaluator.

RTL#A5.640U 1I2-ADM-130 l.F04 Page 6 of 11 Revision 1 OPERATIONS JOB PERFORMAN CE MEASURE JPM NUMBER: 2CR-581 .

JPM REVISION: 6 I JPM TITLE: Perform Manual Makeup to the Charging Suction STANDARD (Indicate liS" FOR SAT or "U" FOR UNSAT)=>

START TIME: _ _ _ _ _ _ __

EVALUATOR NOTE: Simulator setup:

EVALUATOR NOTE: - Any Mode 1 IC.

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

Set BA & Total flow totalizers to ZERO.

To fai12CHS*FCV113A as-is (shut), go to Valves tab and select VLV-BATOIO, Select O-Fail As Is.

Set 2CHS*FCVl14A Potentiometer for 100 gpm flow rate.

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

Operation.

COMMENTS:

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

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

Stop.

2.2 Verifies Green Light LIT, Red Light NOT LIT.

COMMENTS:

RTL#A5.640U 1I2-ADM-I301.F04 Page 7 of II Revision 1 OPERATJONS 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 UNSAT)=> StU EVALVATOn. 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:

4.C Adjust [2CHS*FCVl13A] 4.1 C Calculates the desired flow setpoint:

Boric Acid to Blender to the calculated setpoint. _--=-:gp=--m xIOO = 366 4gpm 4.2C 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 S.C 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.

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

EVALUATOR NOTE: Batch amounts are at the operators discretion. Total volume change is approximately 280 gallons. Candidate must set the appropriate amount 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 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 (~14gal/%).

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 value on 2CHS*FQISI13 and adds the Boric Acid on the batch integrators for volume previously calculated (54.6 gallons) 2CHS*FQISl13 and 2CHS*FQIS168. 9.2 Notes the Blender Total Flow value on 2CHS*FQISI68 and adds the Total Volume previously calculated (280 gallons)

COMMENTS:

RTL#A5.640U I12-ADM-130 l.F04 Page 10 of 11 Revision 1 OPERATIONS JOB PERFORMANCE 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 EVALUATOR CUE: Inform the candidate that another and flow verification in the operator will make the Narrative Log entry.

Narrative Log.

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 14.C Place Boric Acid Makeup 14.1 C Places Boric Acid Makeup Blender Control switch to Blender Control switch to START position.

Start..

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

COMMENTS:

FAULT STATEMENT:

Alternate path begins here. Candidate must take manual action to secure th~~ dilution after discovering that no boric acid flow exists. It is expected that the operator will recognize and terminate w/in -1 min (~5-6% level rise)

IS.C Verify proper operation at IS.1 Verifies Boric Acid to Blender and Total MIU Flow recorder [2CHS-FRl13] From Blend~:r 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 0 Yes Allotted 15 minutes Actual minutes Critical: L8J No Time: Time:

0 SAT JPM RESULTS:

0 UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

RTL#A5.640U 1/2-ADM-130 l.F04 Page 4 of 10 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET TASK STANDARD: Bus 2AE is energized from Bus 2A. The 2-1 EDG output breaker is open and the EDG has been shutdown.

RECOMMENDED SIMULATOR STARTING LOCATION:

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

INITIAL CONDITIONS: Breaker 2A 10 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.

INITIATING CUE: Your supervisor directs you to transfer Bus 2AE to Bus 2A and to open the 2-1 EDG Output Breaker in accordance with 20M-36.4.E.

REFERENCES:

20M-36.4.E, Revision 10, Transferring 4KV Emergency Bus 2AE to Bus 2A.

20M-36.4.ACS Diesel Gen 2-1 Electrical Fault TOOLS: None HANDOUT: 20M-36.4.E, Revision 10, Transferring 4KV Emergency Bus 2AE to Bus2A 20M-36.4.ACS Diesel Gen 2-1 Electrical Fault (Do NOT provide initially)

RTL#A5.640U 1I2-ADM-1301.F04 Page 5 of 10 Revision 0 OPERAnONS JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

DRead:

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

INITIAL CONDITIONS: 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 CUE: Your supervisor directs you to transfer Bus 2AE to Bus 2A and to open the 2-1 EDG Output Breaker in accordance with 20M-36.4.E.

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

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

Simulate performance or perform as directed the required task.

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

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

D Then hand this sheet to the evaluator.

RTL#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

1. Review the procedure. 1.1 Reviews provided procedure, 20M-36.4.E.

EVALUATOR NOTE: Provide candidate with copy of procedure 20M-36.4.E.

COMMENTS:

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

2AE.

2.2 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 STEP I STANDARD

("e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSA T)=> Stu 3.C Place the 2-1 Diesel 3.1C Places 2-1 EMERG GEN SYNCHRONIZING SEL Generator synchronizing SW in the Bus 2A position.

switch in the Bus 2A position. , COMMENTS:

4.C Adjust 2-1 EDG until the 4.1 Observes the 2-1 Emergency Diesel Generator synchroscope needle is synchroscope on the Vertical Board and notes it is rotating in the SLOW rapidly rotating in the SLOW direction.

DIRECTION.

4.2C Adjusts the 2-1 EMERG GEN GOVERNOR control switch to the RAISE position.

4.3 Verifies the synchroscope rotating slowly in the fast direction.

COMMENTS:

I 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

5. 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 6.1 Monitors th::! 2-1 Emergency Diesel Generator synchroscope, rotating synchroscope on the Vertical Board.

SLOWLY in FAST DIRECTION. 6.2C Momentarily places breaker 2E7 control switch in the CLOSE position when the synchroscope is at the 12 o'clock.

6.3 Verifies the RED light above breaker 2E7 control switch LIT and WHITE light NOT LIT.

COMMENTS:

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

OFF.

COMMENTS:

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 STEP STANDARD

( "e" Denotes CRlTICAL STEP) (Indicate "S" FOR SAT or "U" FOR U~SAT)~ SIU I

8. Maintain generator power 8.1 Adjusts 2-1 EMERG GEN VOLTGE ADJUST as factor between 0.8 and 1.0 needed to maintain between 0.8 and 1.0 lagging PF as lagging, as indicated on indicated on Power Factor meter on VB-C.

Emergency Generator Power Factor, by adjusting COMMENTS:

Emergency Generator 2-1 Voltage Adjust.

FAULT STATEMENT: At this point the JPM alternate path begins. Annunciator A8-4C, "DIESEL GEN 2-1 ELECTRICAL FAULT" will annunciate when EDG 2-1 loading reaches 1000 KW. Computer alarm DO 2-1 DIFF will also be received. Candidate should respond to ARP and Trip the 2-1 EDG and open ACB 2EIO which failed to automatically occur.

9.C Reduce load on the EDG to 9.1C Intermittently places the 2-1 EMERG OEN

<100KW. GOVERNOR control switch in the LOWER Position.

9.2 Monitors the following parameters during the load decrease:

a. EMERG GEN 2-1 VOLTS

b. EMERG GEN 2-1 POWER FACTOR

c. EMERG GEN 2-1 WATTS 9.3 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 STANDARD

( "c" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "u" FOR UNSAT)~

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.C Trips 2-1 EDG and manually 11.1 Momentarily places breaker 2E 10 control switch in opens output breaker 2EI0. TRIP.

11.2. Verifies the WHITE light above breaker 2EI0 control switch is ON.

11.3C Manually Trips EDG 2-1 by pushing the stop pushbuttons.

11.4 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 I 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 Name: Performer SSN:

Time D Yes Allotted 10 Minutes Actual minutes Critical: IZI No Time: Time:

JPM RESULTS:

D SAT D 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 I12-ADM-130LF04 Page 4 of 10 Revision 1 EVALUATOR DIRECTION SHEET TASK STANDARD: Manually initiate CIB, align both trains of SWS to RSS heat exchangers and isolate SWS to CCP heat exchangers.

RECOMMENDED Simulator STARTING LOCATION:

DIRECTIONS: You are to Verify Containment Spray Actuation.

INITIAL CONDITIONS:

A reactor trip and safety injection have occurred due to a large break LOCA.

The actions of E-O are being performed.

INITIATING CUE: The Unit Supervisor directs you to perform Attachment A-O.II, "Verification Of Automatic Actions", Step 7 to check CIB and Containment Spray status.

REFERENCES:

20M-53A.l.A-O.ll, "Verification Of Automatic Actions", Issue IC, Rev. 6 20M-53A.1.A-O.5, "Containment Isolation Phase B Checklist", Issue IC, Rev. 2 TOOLS: None HANDOUT: 20M-53A.1.A-O.ll, "Verification Of Automatic Actions", Issue IC, Rev. 6, place kept up to step 7.

20M-53A.I.A-O.5, "Containment Isolation Phase B Checklist", Issue IC, Rev. 2

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:

DIRECTIONS: You are to Verify Containment Spray Actuation.

INITIAL CONDITIONS:

A reactor trip and safety injection have occurred due to a large break LOCA.

The actions of E-O are being performed.

INITIATING CUE: The Unit Supervisor directs you to perform Attachment A-O.II, "Verification Of Automatic Actions", Step 7 to check CIB and Containment Spray status.

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

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

Simulate performance or perform as directed the required task.

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

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

D Then hand this sheet to the evaluator.

RTL#A5.640U tl2-ADM-130 I.F04 Page 60f 10 Revision 1 OPERA TIONS JOB PERFORMANCE MEASURE

~ JPM NUMBER: 2CR-656 JPM TITLE: Containment Spray Manual Actuation- SWS and QSS I JPM REVISION: 0 Valve Malfunctions STEP

( "C" Denotes CRITICAL STEP "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: _ _ _ _ _ __

1. Reviews procedure. 1.1 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 VNSAT)~ Stu

2. Containment pressure - HAS 2.1 Determines that containment pressure has NOT REMAINED LESS THAN 11 remained less than 11 psig by checking any of the PSIG. following:

AI-2H, "CONTAINMENT ISOLATION PHASE B" in alarm.

2LMS*PR950, Containment Pressure Recorder indicates greater than 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 20M 53A.l.A-O.5, "Containment Isolation Phase B Checklist" .

3. Check BLUE CIB marks - LIT. 3.1 Checks components properly aligned and determines CIB components not positioned as required, and CIB NOT actuated.

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 UNSAT)~ 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.

4.C IF NOT, THEN manually 4.1 Simultaneously ROTATES (Clockwise) both Train initiate CIB (both switches for "A" CIB switches to ACTUATE position.

both trains).

4.2C Simultaneously ROTATES (Clockwise) both Train "B" CIB switches to ACTUATE position.

COMMENTS:

Check BLUE CIB marks - LIT. 5.1 Candidate checks all indicating lights with BLUE CIB marks LIT.

5.2 Determines 2SWS*MOVI06A / B and 2SWS*MOV103A / B not aligned.

EVALUATOR NOTE:

If requested, provide Candidate a copy of Attachment A-O.5.

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 6.C IF CIB NOT actuated, JHEN 6.1C Places 2SWS*MOVI06A control switch to CLOSE.

manually align equipment. If necessary, refer to Attachment 6.2 Verifies GREEN light - LIT and RED light - NOT A-0.5, "Containment Isolation LIT.

Phase B Checklist".

6.3C Places 2SWS*MOVI03A control switch to OPEN.

6.4 Verifies RED light - LIT and GREEN light - NOT LIT.

6.5C Places 2SWS*MOVI06B control switch to CLOSE.

6.6 Verifies GREEN light - LIT and RED light - NOT LIT.

6.7C Places 2SWS*MOVI03B control switch to OPEN.

6.8 Verifies RED light - LIT and GREEN light - NOT LIT.

COMMENTS:

RTL#A5.640U 112-ADM-1301.F04 Page 100f lO Revision 1 OPERA TIONS 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) (1ndicate "S" FOR SAT or "U" FOR UNSAT)=>

7.C Stop all RCP's. 7.lC Places control switches for 2RCS*P21A, 21B and 21C to STOP.

7.2 Verifies 2RCS*P21A, 21B and 21C pump RED lights NOT LIT and WHITE lights LIT.

7.3 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 TITLE: Swap RHS Trains JPM REVISION: 2 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 ALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

[g] Perfonn Plant Site Annual Requal Exam D BVT D Simulate [8J Simulator D Initial Exam D NRC D Classroom D OJT/TPE D Other:

D Training D Other:

EVALUATION RESULTS Performer Name: Perfonner SSN:

Time D Yes Allotted 25 Minutes Actual minutes Critical: [8J No Time: Time:

JPM RESULTS:

D SAT D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

I

RTL#A5.640U 1/2-ADM-1301.F04 Page 4 of 12 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET TASK STANDARD: RHS Train B is placed in service, RHS Train A is placed in standby, then upon failure of B pump, RHS Train A returned to service.

RECOMMENDED Control Room STARTING LOCATION:

DIRECTIONS: You are to perform the task, transfer cooling trains ofRHS.

INITIAL CONDITIONS:

The plant is in Mode 5.

RHS Train A is in service providing RCS cooling.

RHS Train B is in standby.

Both 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 INITIATING CUE: Your supervisor directs you to place the B train of RHS in service and then place the A train of RHS in standby.

REFERENCES:

20M-I0.4.B, Parts D & E Revision 30 20M-53C.4.2.1 0.1 revision 11 TOOLS: None HANDOUT: 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 CONDITIONS:

The plant is in Mode 5.

RHS Train A is in service providing RCS cooling.

RHS Train B is in standby.

Both Trains are Filled & Vented

All P&L's and initial conditions are met.

Operators in the field are standing by as required.

20ST-10.4 Already Completed INITIATING CUE: Your supervisor directs you to place the B train of RHS in service and then place the A train of RHS in standby.

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

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

Simulate performance or perform as directed the required task.

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

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

D Then hand this sheet to the evaluator.

RTL#A5.640U 1/2-ADM-1301.F04 Page 6 of 12 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-636 JPM TITLE: Swap RHS Trains JPM REVISION: 2 STEP

( "e" Denotes CRITICAL STEP)

ISTANDARD (Indicate "s" FOI!~AT or "U" FOR UNSAT EVALUATOR NOTE: This is a EVALUATOR NOTE: Simulator Setup:

FAULTED JPM. The candidate is Ini1IC-232 Turn on recorders 2RHS*TR604A&B.

expected to transition to AOP 2.10.1 Place/remove caution tags as needed following the loss of both RHS Shutdown 'B' Train RHS JAW 20M-JO.4.B Part F.

pumps. Close 2RHS*MOV720B and 2CCP*MOVJJ2B.

Set PLP RTC J =10. Balance Charging and Letdown via 2CHS*FCVJ22 and 2CHS*HCV 142.

START TIME: _ _ _ _ _ __

1. 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)

2. Verify CCP temperature 2.1 Checks temperature on 2CCP-TIl OOA( 1OOB)( 100C)

>50°F. >50°F.

COMMENTS:

RTL#A5.640U 1!2-ADM-130 I.F04 Page 7 of 12 Revision 1 OPERAnONS 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

3. Check RCS temperature. 3.l. Determines RCS/RHS temperature> 120F.

3.2 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:

4.C Align RHS valves. 4.1 Checks OPEN [2RHS*MOV701B].

Verifies Red Light - LIT and Green Light - NOT LIT.

4.2 Checks OPEN [2RHS*MOV702B].

Verifies Red Light - LIT and Green Light - NOT LIT.

4.3C CLOSES [2RHS*FCV605B], demand at zero.

4.4 Verifies OPEN [2CHS*HCV142], demand not at zero.

4.5 Checks CLOSED [2RHS*MOV750B].

Verifies Red NOT Light - LIT and Green Light LIT.

4.6C CLOSES [2RHS*HCV758B], demand at 100%.

4.7 Checks OPEN [2RHS*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 UNSAT)~ I Stu STEP

( "c" Denotes CRITICAL STEP) (Indicate "s" FOR SAT or HU" FOR

5. Monitor RHR Hx DitfTemp. 5.1 Monitors RHR Hx DiffTemp on [2RHS*TR604B]

andlor (T0630A) .

COMMENTS:

6. Vent [2RHS*P21B]. 6.1 Determines step is NIA based on Attachment 1.

EVALUATOR CUE: [2RHS*P21B] venting not required per Attachment 1.

COMMENTS:

7. Monitor [2RHS*P21B] for 7.1 Determines containment is at atmospheric pressure seal leakage during pump and monitor:lng of pump seal leakage on pump start is start. required.

7.2 Requests local operator to monitor pump seal for leakage.

EVALUATOR CUE: Local operator will monitor pump operation.

COMMENTS:

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 STEP STANDARD

( "c" Denotes CRITICAL STEP) (Indicate "S" FOR S;;(lf "U" FOR UNSAT)=> I S/U I 8.C Verify RHS temperature is 8.1 Verifies RCS and RHS temperature indications on within limits then start PCS or recorders, that temperature differential is ~ 50

[2RHS*P21B]. of or RHS temperature rate of increase is < 5 of/Hr.

EVALVATOR NOTE: Candidate may have previously verified temperature is within limits.

8.2C Starts [2RHS*P21Bl COMMENTS:

9. If required, maintain PRZR 9.1 Marks step 16 as N/A.

pressure between 275 and 350 psig by the following EVALVATOR CVE: RCP operation is not methods. required at this time. You do NOT have to adjust pressure, step 16 is N/A.

COMMENTS:

10.C Adjust RHS system flow. to.IC 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 I JPM TITLE: Swap RHS Trains JPM REVISION: 2 STEP I STANDARD

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

11. 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.

12. Maintain RCS temperature, 12.1 Throttles [2RHS*HCV758B] to maintain RCS verify flow is controlled in temperature.

AUTO.

12.2 Verify [2RHS*FCV605A1605B] modulate in AUTO to maintain RHS flow on 2RHS*FI605A1 B].

12.3 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

13. Locate procedure. 13.1 Transitions to procedure Section E, To Place RHS Train A in Standby.

COMMENTS:

14.C Check [2RHS*P21A] 14.lC STOPS [2RHS*P21A].

stopped.

14.1 CLOSES [2RHS*MOV750B].

Verifies Red Light NOT LIT and Green Light-EVALUATOR NOTE:

LIT.

Alternate path here.

[2RHS*FCV605B] will ramp SIMULATOR OPERATOR CUES: After fully open and after full open, candidate secures [2RHS*P21A], ramp OPEN

[2RHS*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:

RTL#A5.640U 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)=>

15.C Transition to AOP 2.10.1. 15.1 May attempt to restart [2RHS*P21A].

15.2 May attempt to restart [2RHS*P21B].

15.3 May refer to annunciator AI-SH ARP. If so, ensure proper steps are followed.

15.4 Transitions to AOP 2.10.1.

EVALUATOR CUE: The local operator reports

[2RHS*P21B] has an Overcurrent relay tripped.

15.5 CLOSES [2RHS*HCV758A], demand at 100%.

15.5 CLOSES [2RHS*FCV60SA] demand at zero.

15.6 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 JPM NUMBER: 2PL-167 JPM TITLE: Align Service \Vater to [2FWE*P23B] Motor Driven I JPM REVISION: 0 Auxiliary Feed Pump Suction KIA

REFERENCE:

061Kl.07 3.6/3.8 TASK ID: 0241-054-04-012 061A1.04 3.9/3.9 0532-010-05-043 JPM APPLICATION: [gJ REQUALIFICATION !:sJ INITIAL EXAM [gJ TRAINING D FAULTEDJPM ADMINISTRATIVE JPM EVALUATION 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 Name: Performer SSN:

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

JPM RESULTS:

D SAT D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

I

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

OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-167 JPM TITLE: Align Service Water to [2FWE*P23B] Motor Driven JPM REVISION: 0 Auxiliary Feed Pump Suction EVALUATOR DIRECTION SHEET TASK STANDARD: Service water vented and aligned to [2FWE*P23B] Motor Driven Auxiliary Feed Pump suction.

RECOMMENDED In-Plant STARTING LOCATION:

DIRECTIONS: You are to align Service Water Supply to [2FWE*P23B] Motor Driven Auxiliary Feed Pump Suction.

INITIAL CONDITIONS:

The Control Room Team has responded to an Inadequate Core Cooling Accident and is now in E-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.

INITIATING CUE: Your supervisor directs you to supply [2FWE*P23B] Motor Driven Auxiliary Feed Pump suction from Service Water by completing EOP Attachment A-I.8 beginning with step 10.

Mechanical Maintenance and another operator are on station in South Safeguards ready to coordinate this evolution.

REFERENCES:

20M-53A.l.A-L8, "Makeup to PPDWST [2FWE*TK210]", Rev. 5 TOOLS: Keys (simulated)

HANDOUT: 20M-53A.l.A-1.8, "Makeup to PPDWST [2FWE*TK21 0]", Rev. 5, place kept up to step 10.

Ops Manual Figure 24-3 (provide if requested)

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:

TASK: You are to align Service Water Supply to [2FWE*P23B] Motor Driven Auxiliary Feed Pump Suction.

INITIAL CONDITIONS:

The Control Room Team has responded to an Inadequate Core Cooling Accident and is now in E-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 CUE: 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 JPM".

D 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 1.1 Recognizes from the Initial Conditions that CIB has 25 inches, THEN align occurred and performance of this step is not Service Water to the Auxiliary required.

Feedwater Pumps by performing the following:

COMMENTS:

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

Close [2SWS*MOVI04B]

Close [2SWS*MOVI04D]

2. Verify Open 2.1 Recognizes from the Initial Conditions that this step

[2SWS*MOV103B], Recirc has already been performed.

Spray HX Service Water Supply Header B Isolation. COMMENTS:

RTL#A5.640U 1I2-ADM-1301.F04 Page 7 of9 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE

'I' 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 3.1C Closes [2FWE*356], Service Water Supply Tell Water Supply Tell Tale Drain. Tale Drain by rotating valve handwheel in the (North SFGDS above clockwise direction.

2FWE*23B -718')

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

COMMENTS:

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

Request Mechanical Maintenance Technician EVALUATOR CUE: Flange at [2FWE-RV102],

loosen flange at [2FWE Emergency Water Supply Relief has been loosened.

RV102], Emergency Water Supply Relief. (South SFGDS above 2FWE-P23A - 718) COMMENTS:

5. With Key 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].

COMMENTS:

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 UNSAT)=> 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 7.1 Requests Mechanical Maintenance Technician Maintenance Technician tighten flange at [2FWE-RVI02].

tighten flange at [2FWE RVI02]. EVALUATOR CUE: Flange at [2FWE-RVI02],

Emergency Wate:r Supply Reliefhas been tightened.

COMMENTS:

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

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

COMMENTS:

I I

RTL#A5.640U 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 STEP STANDARD

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

9.C For [2FWE*P23B], Motor 9.IC Opens [2FWE*92], Service Water Supply to Driven AFW Pump, perform [FWE*P23B] by rotating valve handwheel in the the following: counter-clockwise direction.

EVALUATOR CUE: [2FWE*92] has been OPENED.

Slowly Open [2FWE*92],

EVALUATOR NOTE: Valve position indication is on Service Water Supply to top of the valve and is difficult to observe.

[FWE*P23B]

(South Safeguards 718')

COMMENTS:

IO.C With Key CRITI19, close 10.1 C Unlocks and Closes [2FWE*95], Primary DWST

[2FWE*95], Primary DWST Supply to [2FWE*P23B] by rotating valve Supply to [2FWE*P23B]. hand wheel in the clockwise direction.

EVALUATOR CUE: [2FWE*95] has been CLOSED. Valve position indicates CLOSE.

COMMENTS:

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

EVALUATOR CUE: When ON/OFF red pushbutton is depressed, [2FWE*P23B] discharge pressure is reading approximately 450 psig. That completes this JPM.

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 ALUATION RI~SUL TS Perfonner Name: Performer SSN:

Time 0 Yes Allotted 15 Minutes Actual minutes Critical: [gI No Time: Time:

JPM RESULTS:

D SAT D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

RTL#A5.640U 112-ADM-130 1.F04 Page 4 of8 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET TASK STANDARD: MG set #2 is running with [2RDS-MG22] Generator Output breaker CLOSED.

RECOMMENDED In plant STARTING LOCATION:

DIRECTIONS: You are to simulate starting*#2 MG Set.

INITIAL CONDITIONS:

The plant is in Mode 3.

Reactor Rod Drive Control System Startup is in progress.

MG Set #1 is operating and the reactor trip breakers are open.

INITIATING CUE:

Your supervisor directs you to startup the #2 MG set and close the generator output breaker per procedure 20M-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.

REFERENCES:

20M-1.4.B Revision 13, "Reactor Rod Drive Control System Startup".

TOOLS: NONE HANDOUT: 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:

TASK: You are to simulate starting #2 MG Set INITIAL CONDITIONS:

The plant is in Mode 3.

Reactor Rod Drive Control System Startup is in progress.

MG Set #1 is operating and the reactor trip breakers are open.

INITIATING CUE:

Your supervisor directs you to startup the #2 MG set and close the generator output breaker per procedure 20M-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 JPM".

D 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: 7 STANDARD (Indicate "S" FOR SAT or "U" FOR UNSA T)=>

STARTTIME: _ _ _ _ _ __

I.C At [PNL-2RD-2RD 1.1 C Places [2RDS-MG22] MOTOR Circuit Breaker CONT], Place [2RDS Control switch to the closed position.

MG22] Motor Circuit Breaker Control switch in 1.2 Verifies Red Light LIT and Green Light - NOT CLOSE position, AND LIT.

check MG set #2 starts.

EVALUATOR CUE: Red Light - LIT, Green Light NOT LIT. #2 MG set is accelerating.

COMMENTS:

2.C Depress AND Hold [2RDS 2.1C Simulates depressing [2RDS-MG22] Gen. Field Flash MG22] Gen. Field Flash pushbutton until [2RDS-MG22] Generator Line Volts pushbutton until the voltmeter indicates approximately 260VAC.

[2RDS-MG22] Generator Line Volts voltmeter EVALUATOR CUE: [2RDS-MG22] Generator indicates approximately Line Volts voltmeter increased to 260 VAC.

260 V AC, THEN release.

COMMENTS:

RTL#A5.640U 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 STEP STANDARD

( itCH Denotes CRITICAL STEP) (1ndicate "S" FOR SAT or "U" FOR UNSAT):::::. SfU

3. Complete 20M-l.4.Q, 3.1 Acknowledges the need to complete 20M-1.4.Q.

"Administrative Guidelines for Closing the Reactor EVALUATOR CUE: 20M-1.4.Q Administrative Trip/Bypass Breakers". Guidelines for closing the reactor Trip/Bypass breakers has been completed.

EVALUATOR CUE: CRDM cooling is in service per initial conditions.

COMMENTS:

4. Close reactor trip breakers 4.1 Requests that the RO close the reactor trip breakers

[RTA AND RTB] to from BB-B.

provide load.

EVALUATOR CUE: The RO acknowledges the request to close reactor trip breakers and after several minutes you hear noise and the RO confirms the R TBs are CLOSED.

COMMENTS:

5.C Place [2RDS-MG22] 5.le Places [2RDS-MG22] GENERATOR Circuit Breaker Generator Circuit Breaker control switch to CLOSE position.

control switch to CLOSE position. EVALUATOR CUE: The Mechanical Flag (RED) is indicated and the GREEN indicating light is LIT.

COMMENTS:

RTL#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 STEP STANDARD

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

6.C Place [2RDS-MG22] 6.1 C Places [2RDS-MG22] Synchronize switch in the ON Synchronize switch in the position.

ON position AND Check the two generators 6.2 Checks [2RDS-MG22] GENERATOR Output synchronize. breaker RED Light LIT.

EVALUATOR CUE: A few moments after the Synchronize Switch is taken to ON, inform the candidate that [2RDS-MG22] Generator Output breaker RED Light - LIT, Green Light - NOT LIT.

COMMENTS:

7. When [2RDS-MG22] 7.1 Places [2RDS-MG22] Synchronize switch to the OFF Generator circuit breaker position.

CLOSES, THEN place

[2RDS-MG22] EVALUATOR CUE: Acknowledges Synch switch Synchronize switch to the in OFF position.

OFF position.

7.2 Informs supervisor that # 2 MG Set is running with output breaker closed or that the task is complete.

COMMENTS:

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

RTL#A5.640U 1/2-ADM-1301.F04 Page 3 of8 Revision 1 JPM NUMBER: 2PL-009 JPM TITLE: Place a Reactor Protection Channel in the Tripped JPM REVISION: 7 Condition KJA

REFERENCE:

012A4.04 3.3/3.3 TASK ID: 0535-010-04-013 JPM APPLICATION: ~ REQUALIFICATION ~ INITIAL EXAM D TRAINING D FAULTED JPM ADMINISTRATIVE JPM EV ALUATION 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 ALUATION RESULTS I

Performer Name: I Performer SSN:

D

~:al Yes Allotted Actual 7 Minutes minutes

~ No Time: Time:

JPM RESULTS:

D SAT D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

RTL#A5.640U 1I2-ADM-1301.F04 Page 4 of8 Revision 1 EVALUATOR DIRECTION SHEET Power Range Channel N-43 bistables are in the test (tripped) position.

TASK STANDARD:

RECOMMENDED In-plant STARTING LOCATION:

You are to simulate placing a reactor protection channel in the tripped DIRECTIONS:

condition.

INITIAL CONDITIONS:

The plant is in Mode 1 at 100% power.

Power Range Channel N-43 has malfunctioned.

AOP-2.2.1 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.

20M-53CA.2.2.1 C, "Power Range Channel Malfunction", Revision 10

REFERENCES:

Key No. 117 (118)

TOOLS:

20M-53CA.2.2.1C, "Power Range Channel Malfunction", place kept HANDOUT:

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:

TASK: You are to simulate placing a reactor protection channel in the tripped condition.

INITIAL CONDITIONS:

The plant is in Mode 1 at 100% power.

Power Range Channel N-43 has malfunctioned.

AOP-2.2.1 C, "Power Range Channel Malfunction" has been performed through Step l.h.

Your supervisor directs you to trip the appropriate bistables in INITIATING CUE:

accordance with AOP-2.2.1 C, Power Range Channel Malfunction, Step 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 JPM".

D 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 STANDARD

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

EVALUATOR NOTE: Obtain Key # 117(118) prior to JPM performance and inform Shift Manager that Primary Process Rack No.3 door(s) will be opened. These doors have limit switches which will provide the Control Room indication when the doors are opened and closed.

EVALUATOR CUE: Provide the candidate a place kept copy of AOP 2.2.1 C.

START TIME: __~ _ _ _ __

1. Reviews procedure. 20M 1.1 Candidate reviews place kept copy of AOP 2.2.1.C 53C.4.2.2.1 C, Power Range provided.

Channel Malfunction.

COMMENTS:

2. Obtain Keys 117 (1 ] 8) for 2.1 Obtains Key No. 117 (118) for process rack door by process rack doors. requesting keys from the evaluator or indicating that they will need to go to the Control Room to sign out these keys.

EVALUATOR CUE:

Provide the candidate the KEY 117(118) when they request the keys or begin to walk to the control room.

COMMENTS:

RTL#A5.640U 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 STEP I STANDARD

( "c" Denotes CRITICAL STEP) (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.

3. Open process rack door. 3.1 Opens the proper Protection Cabinet No.3 door.

COMMENTS:

4. Refer to Attachment 1, 4.1 Refers to Attachment 1 for bistables to trip.

"Delta T Protection Bistable Switch List". 4.2 Determines bistables BS-3 and BS-4 on Card Frame 7/S10t 21 must be tripped.

COMMENTS:

S.C Place 2TS/432C-l [BS-3] 5.1 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. 5.2 Verifies the RED LED is ON.

EVALUATOR CUE:

2TS/432C-l is in TEST and Red LED is LIT.

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 STANDARD

( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FORPNSAT):::>

6.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.

6.2 Verifies the RED LED is ON.

EVALUATOR CUE:

2TS/432C-2 is in TEST and Red LED is LIT.

COMMENTS:

7. Close and lock Protection 7.1 Closes and locks Protection Rack No.3 door.

Rack No.3 door.

COMMENTS:

EVALUATOR CUE:

That Completes this JPM STOP TIME: _ _ _ _ _ __

AI.ppen d"IX 0 " 0 utrme S cenarlo Form ES 01 -

II 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

I: E~~nt o.

Malf. No. Event Type Event Description 1 (R) ATC Raise power in accordance with reactivity plan.

(N) BOP, SRO 1 (TS) SRO 2FWE*P22 (turbine driven Aux Feedwater pump) trips 3 (I) ATC, SRO 2CHS-PT145, fails high, ATC required to manually control letdown pressure via 2CHS-PCV145.

4 (C) BOP, SRO Loss of 2AE 4kv Emergency bus / 2-1 Emergency Diesel fails (TS) SRO to auto start. BOP required to manually start EDG 2-1.

5 (C) BOP, SRO 2CCS-P21A sheared shaft, auto start failure of2CCS-P21B, requires manually starting standby pump.

6 (M)ALL Feedline break inside CNMT.

7 (C) ATC, SRO CIB actuation failure 8 (C) BOP, SRO MSLI actuation failure with 2SDS* AOVlll 's failing to auto

, close, requires BOP to manually actuate MSLI and close all 6 2SDS*AOV111's 9 (C) BOP, SRO "B" train CREV's fails to actuate, requires BOP to manually actuate.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9 Supplement 1 FENoe Facsimile Rev. 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 ATC to control letdown pressure by manually controlling the Letdown Pressure Control Valve,2CHS*PCV145.

After the crew has stabilized the plant, 4KV emergency bus 2AE will de-energize and EDG 2-1 will fail to automatically start. The crew will enter AOP 2.36.2, Loss of 4KV Emergency Bus, which requires a manual start to restore power to the bus. The SRO will determine appropriate Tech Spec actions.

Secondary Component Cooling Water Pump, 2CCS-P21A, will experience a sheared shaft, requiring the crew to enter AOP 2.28.1, Loss ofSecondary 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, the crew will enter E-O.

MSLI will fail to automatically actuate, requiring the BOP to manually actuate a Steam Line Isolation.

When MSLI is actuated, the main steam line drains (2SDS* AOV111 's) will fail to close requiring the BOP to manually close at least 1 train.

CIB will fail to automatically actuate, The ATC will identify the failure to actuate and manually actuate both trains ofCIB.

The crew will identify the "C" S/G as faulted and transition to E-2 to isolate.

Train "B" CREV's, Control Room Emergency Ventilation System, will fail to actuate requiring the BOP to manually initiate.

The crew will progress through E-2 and transition to E-I.

The scenario will be terminated after the crew transitions to ES-l.l and isolates the HHSIjlowpath by closing 2SIS*MOV867A, B, C, D.

Expected procedure flow path is E-O ---+ E-2 ---+ E-I ---+ ES-I.l.

NUREG-1021, Revision 9 Supplement 1 FENoe Facsimile Rev. 1

BEAVER VALLEY PUWER STATION INITIAL CONDITIONS: 25% Power, CBD = 121, Xe increasing BOL, 1935 PPM Boron, IC-211 ADDITIONAL LINEUP CHANGES STICKERS MONITOR SETUP YCT - 2SAS-C21B CS ATC position -MID POWER display EQUIPMENT STATUS DATEffIME OOS TECHNICAL SPECIFICATION,S}

~SAS-C21B OOS, compressor overhaul ~~aysago SHIFT TURNOVER INFORMATION

1. 25% power, BOL, Xe increasing, main feed regulating valves in service.

2. Shift goal is continue power increase in accordance with 20M-52.4.A.

SCENARIO SUPPORT MATERIAL REQUIRED PROCEDURES NEEDED

1. 20M-52.4.A completed and place kept up through step IV.F.7.g (pg 65) 20M-52.4.A

2. Reactivity plan AOP 2.28.1

3. BOL reactivity placard OM-7 IF, Attachment 3, 2CHS-PT145 AOP 2.36.2 E-O E-l E-2 Attachment A-O.II Attachment A-l.6 BVPS 2L8 NRC Scenario 1, Rev 1 30f23

BEAVER VALLEY f--uWER STATION C]NSTRl.JCTIONAL GUIDELINES LPb6NT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE .~

Initialize IC 211, and establish initial Reactor plant at 25% power, BOL, Xe plant conditions. increasing, RCS boron 935 PPM, CBD 121 steps.

Insert the following per the Simulator Inserts all pre-loads required to support the Setup section of the HTML file for this scenario.

scenano:

PRELOAD COMMANDS TRGSET 1 'JPPLP4(1), Set trigger 1 on reactor trip IMF PMP-CAS004 (0 0) 1 2SAS-C21B OOS IMFDSG01D Inhibit auto start of EDG 2-1 IMF PPL09A (0 0) Inhibit auto CIB TRN A, manual successful IMF PPL09B (0 0) Inhibit auto CIB TRN B, manual successful IMF PPL10A (0 0) Inhibit auto MSLI TRN A, manual successful IMF PPL10B (0 0) Inhibit auto MSLI TRN B, manual successful IMF BST-CCS006 (0 0) 2 Inhibit auto start of2CCS-P21B, manual start successful IMF PMP-CCSOOI (7 0) 0 2CCS-P21A severed leads IMF A6-3B-P0670D (7 0) 0 Ann A6-3B Low CCS pump Disch Press TRGSET 8 'XClI076A = 0' Trigger 8 to clear Ann A6-3B TRG 8 'DMF A6-3B-P0670D' Ann A6-3B clears on start 2CCS-P21 B lOR XBSIOS2P (0 0) ON 2HVC*MOD201A failed open.

lOR XBSI06SP (0 0) ON 2HVC*MOD201B failed open.

TRGSET 6 'XBSIOS2C = l' Set trigger 6 on 2HVC*MOD201A CS to close.

TRG 6 'DOR XBSIOS2P' DOR, 2HVC*MOD201A manually closes.

TRGSET 7 'XBSI02SP = l' Set trigger 7 on "B" Tm CREV'S PB depressed.

TRG 7 'DOR XBSI06SP' DOR, 2HVC*MOD201B manually closes.

TRGSET S 'FNISPR(l) >= 27.S' Trigger 5 on reactor power> 27.5%

IRF LOA-AFW022 (S 0) 1 2FWE*P22 trip throttle valve trips shut IMF VLV-MSS032A (00) 100 Fail 2SDS-AOVIIIAI closed IMF VLV-MSS033A (0 0) 100 Fail 2SDS-AOVIIIA2 closed IMF VLV-MSS034A (00) 100 Fai12SDS-AOVII1Bl closed IMF VLV-MSS03SA (0 0) 100 Fail 2SDS-AOVl11B2 closed BVPS - 2L8 NRC Scenario 1, Rev 1 40f23

BEAVER VALLEY t-0WER STATION

[ INSI~UCIIONAL GUIDELINES r PLANT STATUS / PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE IMF VLV-MSS036A (0 0) 100 Fai12SDS-AOVIIICI closed IMF VLV-MSS037A (0 0) 100 FaiI2SDS-AOVIIIC2 closed TRGSET 10 'XAlI090C l' Set trigger 10 on 2SDS-AOVIIIAI CS to close.

TRG 10 'DMF VLV-MSS032A' DMF, 2SDS-AOVl11Al manually closes.

TRGSET 11 'XAlI077C == l' Set trigger lIon 2SDS-AOVIIIA2 CS to close.

TRG 11 'DMF VLV-MSS033A' DMF, 2SDS-AOVIIIA2 manually closes.

TRGSET 12 'XAII107C = l' Set trigger 12 on 2SDS-AOVIIIBI CS to close.

TRG 12 'DMF VLV-MSS034A' DMF, 2SDS-AOVIIIBI manually closes.

TRGSET 13 'XAlI095C = l' Set trigger 13 on 2SDS-AOVII1B2 CS to close.

TRG 13 'DMF VLV-MSS035A' DMF, 2SDS-AOVI11B2 manually closes.

TRGSET 14 'XAII119C = l' Set trigger 14 on 2SDS-AOV111CI CS to close.

TRG 14 'DMF VLV-MSS036A' DMF, 2SDS-AOVll1Cl manually closes.

TRGSET 15 'XAII110C = l' Set trigger 15 on 2SDS-AOVI11C2 CS to close.

TRG 15 'DMF VLV-MSS037A' DMF, 2SDS-AOVl11C2 manually closes.

Assign shift positions SRO:_____________________

ATC:_ _ _ _ _ _ _ __

BOP:_ _ _ _ _ _ _ __

Conduct a shift turnover with oncoming Simulator Frozen until after shift turnover unless operators. it needs to be run momentarily for an alignment change.

When the shift turnover is completed, Simulator running. Crew assumes control of the Unit.

place the simulator to RUN and commence the scenario.

BVPS 2L8 NRC Scenario 1, Rev 1 50f23

BEAVER VALLEY !-0WER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENT 1:

IA W Reactivity plan, ATC dilutes/withdraws rods to Continue power increase per reactivity SRO directs the crew to continue power increase raise reactor power to 100%.

plan. lAW 10M-52.4.A.

BOP raises turbine load.

RCS temperature rises in response to rod withdrawal and dilution.

BOP raises turbine load at 12%/hour rate by;

Adjusting "setter" as appropriate.

Depressing "GO".

BOP verifies/maintains the following while raising load,

Valve position limiter ~5% above current valve NOTE: Event 2 will occur position.

automatically when Rx power reaches

Voltage regulator is maintaining power factor.

27.5%.

EVENT 2:

2FWE*P22 Trip Throttle Valve trips IMMEDIATE PLANT RESPONSE:

(command preloaded) Computer point Y5172D alarms, TURB DR BOP reports that 2FWE*P22 is tripped.

IRF LOA-AFW022 (5 0) 1 AFW PP TRIPPED A2-3H, Safety System Train A Inoperable ROLE PLAY: 5 minutes after being SRO dispatches operator to investigate 2FWE*P22.

dispatched to inspect 2FWE*P22, report back that the trip throttle valve linkage rod is broken.

SRO enters TS 3.7.5, condition B, w/in 2hrs realign Operable pumps to separate hdrs, (for this failure this action is not required) 72 hrs to restore AFW train to operable status.

BVPS - 2L8 NRC Scenario 1, Rev 1 60f23

BEAVER VALLEY 1-0WER STATION INSTRUCTIONAL GUIDELINES lJ:~NT SfAfOS TPFfOCEDURAL.. GlITiSANC"E I EXPECTED STUDENT RESPONSE n_ I Proceed with next event after power is raised above 30% as indicated by A12 2G (NOT P-8) status panel clearing or at LE discretion.

EVENT 3:

2CHS*PT145 fails high IMF XMT-LDS007A (00) 600 IMMEDIATE PLANT RESPONSE:

A2-3F, Letdown Flow Path Trouble ATC reports unexpected letdown alarm.

2CHS-PI145 indication at 600 psig. BOP refers to ARP.

2CHS*PCV145 opens. ATC notes 2CHS-PI145 at full scale and Letdown flow rises. 2CHS*PCV145 traveling open.

2CHS*RV209 may lift.

SRO enters 20M-7.4.IF, Attachment 3. ATC places 2CHS*PCV145 in manual and positions valve to stahilize net charging and restore letdown flow to pre-event value.

With 2CHS*PCV145 in manual, SRO establishes a control band for manual control of letdown pressure.

ATC monitors for proper operation of2CHS*RV209.

ROLE PLAY: 3 minutes after being dispatched to check local pressure on SRO dispatches operator to check locall/d pressure on 2CHS-PI146, report back that pressure 2CHS-PI146.

indicates 110 psig.

After plant has been stabilized, continue with next event at LE discretion BVPS - 2L8 NRC Scenario 1, Rev 1 70f23

BEAVER VALLEY PUWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENT 4:

Loss of 2AE 4kv emergency bus with an auto start failure of2-1 EDG. IMMEDIATE PLANT RESPONSE:

4KV ACB 2AIO trips open IMF BKR-HIVOl (0 0) 0 4KV bus 2AE voltage reduces to zero (VB-C) BOP reports multiple unexpected electrical alarms.

Multiple electrical related annunciators. BOP identifies 4kv Bus 2AE is de-energized and that the 2-1 EDG has failed to start.

BOP reports that 4kv Bus 2DF is energized.

ATC verifies 2CHS*P21B remains running, verifies primary plant is stable and begins referring to ARP's.

SRO enters AOP 2.36.2 for Loss of 4KV Crew verifies no overcurrent electrical alarms.

Emergency Bus. SRO directs BOP to manually start EDG 2-1.

BOP successfully starts EDG 2-1.

Crew verifies 2SWS*P21A is running and cooling water supply valve is open.

Crew performs EOP Attachment A-I.6, lAW direction of AOP 2.36.2 to verify EDG auto loading is complete.

SRO evaluates TS for emergency bus and EDG 2-1.

SRO determines 20ST-36.7 is required within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to verify operability of remaining sources per TS 3.8.1, Conditions A and B.

BVPS 2L8 NRC Scenario 1, Rev 1 80f23

BEAVER VALLEY l-'uWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS:

Turbine Plant Component Cooling Water Trouble (2CCS-P21A sheared IMMEDIATE PLANT RESPONSE: .;~

shaft) 2CCS-P21A ammeter reduces to ~4 amps. BOP reports unexpected CCS related alarms.

A6-3B, CCS pump discharge press low A TC refers to ARP's TRG! 7 (actuate trigger 7, all required A7-6F, Main Leads Cooling Trouble commands are preloaded.) 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.

Proceed with next event at LE discretion BVPS - 2L8 NRC Scenario 1, Rev 1 90f23

BEAVER VALLEY I-vWER STATION r INSTRUCTIONAL GUIDELINES jPLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 6, 7, 8, & 9 Feed line break inside containment Feedwater header rupture inside containment IMF FLX-CFW33 (0 0) 8700 causes an automatic reactor trip.

Multiple malfunctions occur on reactor trip. Additional failures that occur on the reactor trip; Automatic main steam line isolation actuation All commands preloaded failure, when MSLI is manually initiated, 2SDS IMFPPL09A AOVl11 's fail to automatically close, requiring IMFPPL09B manual closure.

IMFPPLIOA CIB will fail to automatically actuate.

IMFPPLIOB "B" train CREV's fails to automatically actuate.

TRGSET 1 'JPPLP4(1),

lOR XBSI052P (0 0) ON lOR XBSI065P (0 0) ON TRGSET 6 'XBSI052C == l' TRG 6 'DOR XBSI052P' TRGSET 7 'XBSI025P = l' TRG 7 'DOR XBSI065P' SRO enters E-O. 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.

BVPS - 2L8 NRC Scenario 1, Rev 1 10 of23

BEAVER VALLEY I JWER STATION

[ INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 7, 8, & 9: (continued) 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.

SI automatically actuated 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; ATC 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 1 I1of23

BEAVER VALLEY I- v\IVER STATION r-UINSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 7,8, & 9: (continued) 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 List of Attachment A-D.II Discrepancies: SRO directs BOP to perform Attachment A-O.II.

NOTE:

Evaluation of BOP performing Discrepancies:

Attachment A-O.II begins on page 21. MSLI failed to automatically isolate.

2SDS-AOVlll 's, steam line drains failed to automatically close.

CIB failed to automatically actuate.

"B" train CREV's failed to automatically actuate.

I' .,

BVPS - 2L8 NRC Scenario 1, Rev I 120f23

BEAVER VALLEY POWER STATION L INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE-=---;;;...;....;...~----'

EVENTS 7, 8, & 9: (continued) ATC checks RCS Tavg stable at or trending to 547°F NOTE: RCS temperature < 547°F and dropping due to

ATC verifies no steam release is occurring.

Automatic main steamline isolation Safety Injection flow. (Condenser steam dumps closed) was inhibited.

ATC verifies Reheat steam is isolated.

ATC reduces total feedflow to minimize CID.

Critical Task: E-O.P Crew manually actuates main steam Crew determines cooldown is continuing and line isolation before a Severe (orange determines SLI is required.

path) challenge develops to either the If not previously actuated, BOP manually initiates Sub-criticality or Integrity CSF or MSLI and closes 2SDS-AOVIII 's.

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."

CIB not actuated at this time. ATC checks recirc spray pumps - NONE RUNNING BVPS - 2L8 NRC Scenario I, Rev 1 130f23

BEAVER VALLEY rvWER STATION

[ INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 7,8, & 9: (continued) 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 AVAILABLE

Block valves AT LEAST ONE OPEN NOTE: A TC checks if RCPs should be stopped When the crew recognizes Containment

DIP between RCS pressure and highest SIG pressure has exceeded 11 psig and pressure - NOT LESS THAN 205 PSID manually initiates CIB, the crew will

Criteria for stopping is not met - Leaves RCPs shutdown all RCP's due to loss of running based upon DP requirements.

cooling.

RCP's may be sid at this time due to the operator action for the CIB, otherwise RCP's would remain running at this point.

ATCIBOP checks if any SIGs are faulted

Pressures in all SIGs - ANY DROPPING IN AN UNCONTROLLED MANNER OR

ANY SIG COMPLETELY DEPRESSURIZED Crew determines "C" SIG is faulted.

SRO transitions to E-2.

BVPS - 2L8 NRC Scenario 1, Rev 1 I40f23

BEAVER VALLEY t -,WER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EYENTS 7, 8, & 9: (continued) ATCIBOP actuates CREVS "B" Train CREV's automatic actuation

Verifies the control room air intake and failed requiring the crew to manually exhaust Dampers are CLOSED.

initiate.

Crew determines "B" Train CREV's failed to actuate, All commands preloaded ATCIBOP manually actuates CREV's.

SRO requests a BV -1 operator to verify proper Unit 1 CREVS actuation.

SRO directs STA to Commence Control Room ventilation actions. Refer to Attachment A-2.4.

NOTE: ATC/BOP verifies steamline isolation has occurred by Failure ofMSLI should have been checking all YELLOW SLI identified components are recognized by this time. in the designated position. (previously verified)

"C" S/G pressure is lower than "A" & "B. BOP identifie~ "A" & "B" steam generator pressures "A" & "B" may be slowly lowering as expected are "Stable or rising".

due to the cooldoWD. Crew should respond with "Stable" for "A" & "B" S/G's.

"C" S/G pressure & level lowering. Crew identifies "C" S/G as faulted.

BVPS 2L8 NRC Scenario 1, Rev 1 150f23

BEAVER VALLEY t--0WER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 7,8, & 9: (continued) BOP isolates the faulted, "C" S/G as follows, Critical Task: E-2.A

Verifies FWI (previously verified via Crew isolates the faulted S/G and Attachment A-O.ll) directs operator to close isolation

Closes AFW throttle valves on "C" S/G valves operated from outside of the 2FWE*HCVlOOA and 100B control room before transition out of

Verifies Residual Heat Release Valve is E-2. closed.

Directs field operator to isolate 2SVS-29 Basis for Selection:

Isolates steam supply to turbine driven AFW SAFETY SIGNIFICANCE -- Failure to pump, 2MSS*SOV105C and 105F isolate a faulted S/G that can be isolated

Verifies closed, "C" S/G Atmospheric steam causes challenges to CSFs beyond those dump valve.

irreparably introduced by the postulated

Verifies S/G blowdown isolated, conditions. Also, depending upon the 2BDG* AOVlOOCl plant conditions, it could constitute a

Verifies S/G Blowdown sample isolation demonstrated inability by the crew to valves, 2SSR*AOVl17A, B, C closed.

recognize a failure of the automatic actuation of an ESF system or component.

ROLE PLAY: 10 minutes after being dispatched close 2SVS-29, insert IRF LOA-MSSOll (00) 0, then report that 2SVS-29 is closed.

BOP verifies PPDWST level is > 85 inches .

BVPS - 2L8 NRC Scenario 1, Rev 1 l60f23

BEAVER VALLEY I ..JWER STATION r INSTRUCTIONAL GUIDELINES I** PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE~

EVENTS 7,8, & 9 (continued) Crew checks if S/G tubes are intact

Check all S/G levels - NONE RISING IN AN UNCONTROLLED MANNER

Check Secondary Radiation - CONSISTENT WITH PRE-EVENT VALUES Determines no S/G levels are rising in an uncontrolled manner and Secondary Radiation - is CONSISTENT WITH PRE-EVENT VALVES; 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].

NOTE:

Due to timing, procedure progression A TC confirms RCS pressure is stable or rising.

and plant conditions (Adverse cnmt or not adverse), it is possible that the ATC reports Pzr level is < 17% [38% ADVERSE conditions may support direct transition CNMT]

to ES-l.1. If so, E-l steps on pages 18 and 19 are not applicable. Crew determines that current plant conditions do not support SI reduction.

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

BVPS - 2L8 NRC Scenario 1, Rev 1 170f23

BEAVER VALLEY I-vWER STATION

[ ulNSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 7, 8, & 9: (continued) ATC checks if CREVS should be actuated:

Checks EITHER of the following:

Control Room Radiation Monitor 2RMC*RQ201,202 - NOT IN HIGH ALARM

CIB - HAS NOT OCCURRED Crew reports CREV's required and previously actuated.

A TC checks if RCPs should be stopped

DIP between RCS pressure and highest S/G pressure - LESS THAN 205 PSID [220 PSID ADVERSE CNMT]

DP Criteria for stopping RCPs is not met-RCP's previously shutdown due to CIB.

ATC 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 1 180f23

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES nUT PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 7,8, & 9: (continued) 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 - AVAILABLE

PORVs - CLOSED

Block valves - AT LEAST ONE OPEN BVPS - 2L8 NRC Scenario 1, Rev 1 190f23

BEAVER VALLEY l-'uWER STATION 1

m INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 7, 8, & 9: (continued) Crew checks if SI Flow should be Reduced ATC verifies RCS Subcooling is greater than 41 OF [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% r31% ADVERSE CNMT].

A TC confirms RCS pressure is stable or rising.

ATC confirms pzr level is > 17% [38% ADVERSE CNMT]

Crew determines that current plant conditions support SI reduction SRO transitions to ES-l.1, SI Termination Crew resets SI, CIA and CIB signals.

ATC stops 1 charging pump.

ATC verifies RCS pressure is stable or rising.

ATC closes 2SIS*MOV867A,B,C, D.

Terminate scenario when the crew isolates the HHSI flowpath by closing 2SIS*MOV867A, B, C, D in ES-l.l.

Classify Event:

Unusual Event, Tab 2.10, Steam/Feed Line Break due to an Unplanned Rapid depressurization of the Main Steam System resulting in a rapid RCS cool down AND Safety Injection.

BVPS - 2L8 NRC Scenario 1, Rev 1 200f23

BEAVER VALLEY I ..,IWER STATION

[ INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE Attachment A-O.tl '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.

Critical Task E-O.P: Check If main steamline isolation required Crew manually actuates main steam

CNMT pressure - > 7 PSIG line isolation before a Severe (orange -OR path) challenge develops to either the

Steamline pressure - < 500 PSIG Sub-criticality or Integrity CSF or -OR before transition to ECA-2.l,

Steamline pressure high rate of change whichever occurs first PSIG DROP IN 50 SECONDS Basis for Selection: Determines CNMT pressure is > 7 PSIG and SAFETY SIGNIFICANCE -- Failure to Manually actuates steamline isolation by depressing close the MSIVs under the postulated all 4 SLI pushbuttons (BB-C) plant conditions causes challenges to CSFs beyond those irreparably Verifies SLI by checking all YELLOW SLI marks introduced by the postulated conditions. LIT Additionally, such an omission constitutes a !!demonstrated inability by Identifies 2SDS-AOVIIIAl,B1,C1, A2,B2,& C2 all the crew to recognize a failure of the failed to close. Manually closes all valves.

auto actuation of an ESF system or component and to take an action that would prevent a challenge to plant safety."

BVPS 2L8 NRC Scenario 1, Rev 1 210f23

BEAVER VALLEY POWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUSLpROCEDURAL GUIDANCE I** EXPECTED STUDENT RESPONSE Attachment A-O.ll- (continued) Establish domestic water system cooling to station air NOTE: compressors; BOP may have already pre-emptively

Opens 2CCS-AOV118.

opened 2CCS-AOVl18 to provide

Verifies at least 1 air compressor is running.

cooling to the Station Air compressors.

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

Align Neutron Flux Monitoring For Shutdown

Transfer [2NME-NR45] Nuclear Recorder to operable source and intermediate range displays.

Critical Task E-O.E: Check CIB And CNMT Spray Status Crew manually actuates at least the

Containment pressure - HAS REMAINED minimum required complement of LESS THAN 11 PSIG containment cooling equipment before an Extreme (red path) If not - Actuate CIB if required by:

challenge develops to the

Manually initiate CIB BOTH SWITCHES Containment CSF. FOR BOTH TRAINS

Manually align equipment as required Basis for Selection:

Verify all RCPs STOPPED SAFETY SIGNIFICANCE -- Failure to

BV-1 operator verifies CREVS actuation manually actuate the minimum required

Service water established to RSS HX(s) complement of containment cooling equipment under the postulated BOP manually initiates CIB if ATC did not previously conditions constitutes a "demonstrated identify and initiate.

inability by the crew to recognize a failure/incorrect auto actuation of an system or component. "

BVPS - 2L8 NRC Scenario 1, Rev 1 220f23

BEAVER VALLEY !--uWER STATION r- INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE Attachment A-O.ll- (continued) Verify Service Water System In Service

SWS Pumps - TWO RUNNING

Check SWS header pressure - > 55 psig

SWS pump Seal Water Pressure - NOT LOW Verify both CNMT hydrogen analyzers running by 2HCS*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 Attachment A-O.ll COMPLETE Discrepancies: Upon Completion, Report Any Discrepancies to SRO.

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.

BVPS - 2L8 NRC Scenario 1, Rev 1 230f23

Alppen d'I X 0 . 0 utrme Scenarlo Form 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.

1 (C)ATC, SRO N44 fails high, rods automatically step in.

(TS) SRO 2 (R) ATC 2FWS-P21B trips/ reduce power to 52%

(C) BOP, SRO 3 (TS) SRO Misaligned Rod 4 (M)ALL 2RCS*P21B locked rotor trip with Automatic Reactor trip failure and 400 gpm SBLOCA.

5 (C) BOP, SRO Automatic turbine trip failure 6 (M)ALL Loss of all auxiliary feed water, entry into FR-H.l 7 (C) BOP, SRO Failure of2FWS-P24, 2FWS-P21A and P21B (requires secondary depressurization and use of condensate pump.

8 (C) BOP, SRO 2HVS-FN204A and B trip, requires manual starting of at least 1 fan.

9 (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-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 ~ES-l.1.

NUREG-1 021, Revision 9 Supplement 1 FENOC Facsimile Rev. 1

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 ATC {,()sitign HIGH POWER dis{'lay YCT - 2SAS-C21B CS EOUIPMENT STATUS DATEffIME OOS TECHNICAL SPECIFICATION!S}

2FWE*P23A f---- ------

OOS 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ago 3.7.5 condition B 2SAS-C21B OOS

~---------

3 days ago SHIFT TURNOVER INFORMATION

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

SCENARIO SUPPORT MATERIAL REQUIRED PROCEDURES NEEDED L MOL Reactivity placard 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 1 30f23

BEAVER VALLEY t ...;IIVER STATION

[ INSTRUCTIONACGUTOELINES I PLANT STATUS I PROCEDURAL GUIDANCEJ~2<PECTED STUDENT RESPONSE~

Initialize IC 219, and establish initial Reactor plant at 72% power, MOL, Equilibrium plant conditions. Xe, RCS boron = 1140 PPM, CBD = 180 steps.

Insert the following per the Simulator Inserts all pre-loads required to support the Setup section of the HTML File for this scenarlO.

scenano:

PRELOAD COMMANDS TRGSET 1 'JPPLP4(1)' Set trigger 1 on reactor trip IMF RCS02B (1 0) 400 30 400 gpm LOCA on Rx trip IRF LOA-HIVOSS (0 0) 1 2FWE*P23A breaker racked out IMF PMP-CAS004 (0 0) 1 2SAS-C21 BOOS IMF EHC08A (0 0) Turbine fails to auto trip, manual successful TRGSET 2 ' OAFWT22 . SO' Set trigger 2 on 2FWE*P22 start IFR LOA-AFW022 (2 0) 1 2FWE*P22 trips during startup/sequencing IMF VLV-CFW027 (0 0) 0 Prevent 2FWS-P24 start, FR-H.l conditions IMF PMP-AFW002 (lIS) 2 2FWE*P23B trips 15 seconds after reactor trip TRGSET S 'JP760PT(2) = 1 .AND.

Trigger 5 on FWS-P21B trip and pwr < 62%

FNISPR(I) <= 62' IMF CRF03-F6 (S 0) 1 CBD rod F06 movable gripper coil failure IMF PPLOIA (0 0) 0 Prevent AUTO Rx Trip TRN "A" IMF PPLOIB (0 0) 0 Prevent AUTO Rx Trip TRN "B" IMF PPLI0A (0 0) 0 Prevent AUTO MSLI TRN "A" IMF PPLIOB (0 0) 0 Prevent AUTO MSLI TRN "B" lOR XClI04ST (0 0) OFF 2FWS-P21A failure to start TRGSET 8 'OCFWP21B >= 0.6 Set trigger 8 on FWS-P21B start attempt.

AND. XClI046T == l' TRG 8 'IMF PMP-CFWOOS (00) 2' 2FWS-P21B, Trip after 2nd motor starts IMF PMP-MSC036 (1 0) 1 2HVS*FN204A trips on Rx trip TRGSET 4 'XBSI071 T == l' TRG 4 when 2HVS*FN204A CS taken to start TRG 4 'DMF PMP-MSC036' 2HVS*FN204A starts IMF PMP-MSC037 (1 0) 1 2HVS*FN204B trips on Rx trip TRGSET 6 'XBSI083T == l' TRG 6 when 2HVS*FN204B CS taken to start TRG 6 'DMF PMP-MSC037' 2HVS*FN204B starts BVPS - 2L8 NRC Scenario 2, Rev 1 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 EXPECTED STUDENT RESPONSE EVENT 1:

N -44 fails high Rods automatically step inward in response to A TC reports unexpected alarms and rod motion.

IMF NIS03D (0 0) 200 15 N-44 failure.

Crew enters AOP 2.1.3 for Inappropriate Rod A TC verifies no load rejection in progress and places motion. Rod control to manual to stop the rod insertion.

SRO enters AOP 2.2.1 C to address failed NI Crew removes N-44 from service.

channel.

Within 1 hr, verifies P-8, P-9, & P-IO interlocks in required state for 72% power.

Within 72 hrs, trips nuclear bistables by removing control power fuses from Drawer A for N44.

A TC verifies Control rod group selector sw in manual.

BOP verifies Bypass feedwater control valves in manual.

BOP turns Rod Stop Bypass switch for N44 on NIS Rack N50 to BYPASS.

ATC verifies Status light for Overpwr Rod Stop Bypass for N44 is lit.

Crew verifies Rx power is > 50%.

BOP determines all PR channel upper and lower detector inputs to QPTR are operable.

BOP turns "Comparator Channel Defeat Switch" on NIS rack N371N46 to N44 position.

ATC ensures VB recorders are selected to operable detectors.

BVPS - 2L8 NRC Scenario 2, Rev 1 60f23

BEAVER VALLEY I -,WER STATION em INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE After removing Rod block, A TC withdraws control rods to restore Tavg.

SRO addresses TS for N-44 failure, determines TS 3.3.1, condition D is applicable.

Proceed with next event at LE discretion BVPS - 2L8 NRC Scenario 2, Rev 1 70f23

BEAVER VALLEY r __ NER STATION I NSTRUCTIONA-[-GtJ=IO-=E~LI:-::-:N-=E-=-S-""--:P::-:-LA-:-:-:NT=-=S=TA-:-::T=-U-:-=S~/:-::P=R:-::O-=C-=E=O:-CU=-RA-:-:L-G=U:-:":I=O-:-A::-:-NC=E:=--T EXPECTED STUDENT RESPONSE EVENTS 2 &3:

IMMEDIATE PLANT RESPONSE:

2FWS-P21B tripsl Movable gripper Feed flows drop, S/G levels decrease, Main feed failure on Rod F6 when < 62%. regulating valves open.

IMF PMP-CFW005 (0 0) 1 A6-9E, lOE, lIE S/G21A(B)(C) Level IMF CRF03-F6 (5 0) 1 (preloaded) Deviation From Setpoint. Crew determines that 2FWS-P21B has tripped SRO enters AOP 2.24.1 SRO directs an immediate power reduction to < 52%.

BOP depresses 1st STG IN PB then lowers turbine load at 5%/minute rate by,

Adjusting "setter" to 50% power equivalent.

Depressing "GO" ATC inserts control rods and initiates boration for an expected 20% power reduction.

BOP verifies ali avaiiabie pumps are running, Starts 2CNM-P21A When < 62% power, rod F6 will start to ATC identifies rod misalignment, stops inserting "ratchet" in on each rod step. control rods and continues boration.

BOP verifies steam flow is less than available feed flow and that S/G levels are trending to 44%.

After plant is stable and S/G levels are SRO identifies TS 3.1.4, Condition B, as applicable recovering, SRO enters AOP 2.1.8 to address the for the misaligned rod.

misaligned rod. SRO identifies TS 3.4.1 for DNB.

Continue with next event at LE SRO contacts Operations management and notifies discretion I&C of the rod misalignment.

BVPS 2L8 NRC Scenario 2, Rev 1 80f23

BEAVER VALLEY I ,..,VVER STATION

[ INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 4, 5, 6, 7 & 8:

IMMEDIATE PLANT RESPONSE:

2RCS-P21B locked rotor with an A5-2G, 1/3 Reactor Coolant Pump Loop Flow automatic reactor trip failure, turbine Low Reactor Trip trip failure and 400 gpm SBLOCA. ATC reports 2RCS-P21B has tripped and 1st out annunciator is in without an automatic reactor trip.

IMF RCP05B (0 0)

SRO directs ATC to manually trip the reactor SRO enters E-O. ATC and BOP commence lOA's ofE-O.

CRITICAL TASK - E-O.A: Crew Automatic reactor trip failure. A TC verifies Reactor trip after manually tripping manually trips the reactor from the reactor from either BB-B or BB-A Control Room before performing the

A5-6D - LIT.

mitigation strategy of FR-S.1.

Power range indication is < 5%.

Basis for Selection:

Neutron flux is dropping.

SAFETY SIGNIFICANCE -- Failure to manually trip the reactor causes a challenge to the subcriticality CSF beyond that irreparably introduced by the postulated conditions. Additionally, it constitutes an "incorrect performance that necessitates the crew taking compensating action which complicates the event mitigation strategy and demonstrates the inability by the crew to recognize a failure of the automatic actuation of the RPS."

BVPS - 2L8 NRC Scenario 2, Rev 1 90f23

BEAVER VALLEY I ..... vVER STATION

~~STRUCTIONAL GUIDELINES n~ PLANT StATUS I PROCEDURAL GUIDANCE~ EXPECTED STUDENT RESPONSE EVENTS 4, 5, 6, 7 & 8: (continued) Automatic turbine trip failure. BOP verifies Turbine trip did NOT occur

Throttle OR Governor valves NOT closed.

Critical Task: E-O.Q

Main Generator output brks Not open.

Crew manually trips the main

Exciter Circuit breaker not open.

turbine before a Severe (orange path) challenge develops to either the Sub BOP manually trips the turbine, then verifies; criticality or the Integrity CSF or

Throttle OR Governor valves ALL closed.

before transition to ECA-2.1,

Main Generator output brks open.

whichever occurs first.

Exciter Circuit breaker - open.

Basis for Selection:

SAFETY SIGNIFICANCE -- Failure to trip the main turbine under the postulated plant conditions causes 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 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 1 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 Check SI Status Crew checks if SI is required NOTE:

ATC checks Cnmt press> 5psig SI will be required due to 400 gpm

ATC checks PRZR press < 1860 psig SBLOCA, depending on timing, if SI

ATC or BOP checks Steamline pressure < 500 has not actuated, the crew may initially psig enter ES-O.l or may preemptively actuate SI at this time. Crew determines SI is Required; ATC manually actuates SI by turning both trains' control switches.

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

BOP verifies neither leak collection filtered exhaust fan, 2HVS-FN204A nor B are running.

BOP starts at least 1 leak collection filtered exhaust fan.

ATC verifies SI System Status

Both 2CHS*P21A and P21B pumps running.

HHSI Flow indicated,

Both LHSI pumps running BVPS 2L8 NRC Scenario 2, Rev 1 11 of23

BEAVER VALLEY I ..JWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 4, 5, 6, 7 & 8: (continued) BOP verifies AFW System status

Motor-driven AFW Pumps - NONE RUNNING

Turb driven AFW Pump Stm Supply Isol Valves - OPEN but turbine is tripped.

AFW Throttle Vlvs - FULL OPEN

Total AFW Flow - < 340 GPM BOP reports no Aux Feedwater pumps running and no aux feed water flow.

SRO recognizes that AFW flow cannot be established and enters FR-H.l ATC checks if secondary heat sink is required by:

Verifying RCS press is> any non-faulted S/G.

RCS Hot leg temperatures> 350°F.

NOTE: Crew checks if RCS Bleed and Feed should be PORV's may lift several times during initiated.

this transient due to natural circulation

BOP verifies Wide Range level in at least 2 being established while Safety Injection S/G's is> 14%.

flow is occurring.

ATC verifies pzr pressure is < 2330 psig.

With WR levels>14%, PORV's SRO notifies crew that this is a continuous action step.

opening are not due to Loss of Heat Sink; Bleed and Feed is not required.

BOP checks Primary Plant Demineralized Water storage tank level is > 85 inches.

BVPS - 2L8 NRC Scenario 2, Rev 1 120f23

BEAVER VALLEY I ...JWER STATION L IN§TBUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 4, 5, 6, 7 & 8: (continued) Crew tries to establish AFW flow to at least 1 S/G.

ATCIBOP verifies S/G Blowdown and blowdown ROLEPLAY: sample lines are isolated.

When directed to investigate AFW pump status locally, wait 3 minutes Crew confirms then report: * "A" motor-driven pump is OOS 2FWE*P23B is not running, nothing * "B" motor-driven pump has tripped obvious wrong at pump.

Turbine-driven pump tripped on startup.

2FWE*P22 is not running due to the

All AFW throttle valves are open.

trip throttle valve linkage rod being broken.

SRO continues to try to restore AFW flow while If dispatched to DF switchgear, wait 2 continuing in procedure.

minutes then report that overcurrent relay 51-VF218 is tripped on ACB BOP confirms AFW flow is not> 340 gpm.

2F18 for 2FWE*P23B.

Crew dispatches an operator to locally establish AFW flow via Attachment A -1.8.

ATC stops all RCP's. ("A" & "C" RCP's, "B" previously tripped.)

BOP verifies all 3 condensate pumps are running.

ATC verifies CNMT FWI valves are closed.

SRO directs crew to reset SI and FWI signals.

A TCIBOP resets;

SI signal- both trains

FWI signal - both trains.

ATCIBOP 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) BOP attempts to start the S/G Startup Feed pump by;

Verifying 2CNM-DCVlOO is open 2FWS-P24 will not start due to failure of

Placing CS for 2FWS-P24 to start and hold recirculation valve, 2FWR-FCV155 to open. unti12FWR-FCVI55 opens.

BOP recognizes failure of2FWR-FCV155 to open which prevents 2FWS-P24 from starting.

NOTE: BOP attempts to start a main feed pump.

2FWS-P21A will not start.

Crew may not attempt to start 2FWS 2FWS-P21A start attempt - unsuccessful P21B since it had previously tripped, if the crew does attempt a start - it will 2FWS-P21B starts but immediately trips.

trip immediately upon 2nd motor start.

ATC depressurizes the RCS to < 1950 psig by manually opening 1 PZR PORV.

p~TC 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 1 140f23

BEAVER VALLEY I JWER STATION

[ INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 4,5,6,7 & 8: (continued) BOP depressurizes at least 1 S/G to < 440 psig to establish Condensate flow by;

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.

Booth instructor NOTE: Using Attachment A-I.I 0, Crew coordinates with a As directed, de-energize 2FWS field operator to open and de-energize at least I main MOV150AIB. feed pump discharge valve.

IMF VLV-CFW043 (0 0) 0 IMF VLV -CFW044 (0 0) 0 Critical Task: FR-H.1.A BOP begins feeding S/G's by opening the Bypass Crew establishes feedwater flow into Feed regulating valves and verifies that either at least one SG before RCS feed and

Core Exit TC's are dropping bleed is required. OR

S/G Wide Range levels are rising.

Basis for Selection:

SAFETY SIGNIFICANCE -- Failure to BOP verifies CETC are dropping and WR S/G levels establish feedwater flow to any SG are rising.

results in the crew's having to rely upon the lower-priority action of establishing RCS bleed and feed to minimize core uncovery. This constitutes incorrect performance that "leads to degradation of any barrier to fission product release."

BVPS 2L8 NRC Scenario 2, Rev 1 150f23

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

SRO returns to E-O, Step 8 lAW FR-H-I, step Feedwater flow now verified.

ll.b.

List of Attachment A-O.II Discrepancies: SRO directs BOP to perform Attachment A-O.II.

NOTE:

Evaluation of BOP performing Discrepancies: NONE Attachment A-O.II begins on page 21.

ATC checks RCS Tcold stable at or trending to 547°F

ATC verifies no steam release is occurring.

RCS temperature < 547°F and dropping due to (Condenser steam dumps closed)

Safety Injection flow and Feedwater

ATC verifies Reheat steam is isolated.

(condensate) flow.

ATC reduces total feedflow to minimize CID.

Crew determines cooldown is continuing and verifies SLI has previously occurred.

CIB not actuated at this time. ATC checks recife spray pumps NONE RUNNING ATC verifies PRZR isolated

PORVs-CLOSED

Spray Valves CLOSED

Safety relief valves CLOSED (use PSMS)

PRT conditions CONSISTENT WITH EXPECTED VALUES

Power to at least one block valve AVAILABLE

Block valves AT LEAST ONE OPEN BVPS 2L8 NRC Scenario 2, Rev 1 160f23

BEAVER VALLEY I ..;WER STATION

[ INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 4, 5, 6,7 & 8: (continued) ATC checks ifRCPs should be stopped.

DIP between RCS pressure and highest 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 COMPLETELY DEPRESSURIZED Crew determines no SIG's are faulted.

Crew checks if SIG tubes are intact.

Check all SIG levels - NONE RISING IN AN UNCONTROLLED MA1\l}~ER

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 1 170f23

BEAVER VALLEY * ...)WER STATION LJN§JRljCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 4, 5, 6, 7 & 8: (continued) Crew checks if RCS is Intact by checking CNMT conditions consistent with pre-event values.

CNMT radiation

CNMT pressure

CNMT sump level Crew determines the RCS is NOT intact based on CNMT conditions and entry conditions for E-l have been met.

SRO transitions to 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.

ATC checks if RCPs should be stopped

DIP between RCS pressure and highest SIG pressure - LESS THAN 205 PSID [220 PSID ADVERSE CNMT]

DP Criteria for stopping RCPs is not met-RCP's previously shutdown due per FR-H.l.

BVPS 2L8 NRC Scenario 2, Rev 1 180f23

BEAVER VALLEY I JWER STATION nnl!'-lSI~UCTIONAL 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 1 190f23

BEAVER VALLEY, JWER STATION

[ INSTRUCTIONAL GUIDELINES I PI..,l~NT STATUS I PROCEDURAL GUIDANCE ~~EECTED STUDENT RESPONSE EVENTS 4, 5, 6,7 & 8: (continued) ATC checks PORV's and block valves.

Power to block valves AVAILABLE

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%.

ATC confinns RCS pressure is stable or rising.

ATC confinns pzr level is > 17%

Crew detennines that current plant conditions support SI reduction.

SRO detennines transition to ES-l.I, SI Tennination is appropriate.

Tenninate scenario when the crew detennines transition to ES-I.l is appropriate.

Classify Event:

SAE, Site Area Emergency is appropriate classification per the Fission Product Matrix; Tabs 1.1.1 and 1.2.1 - Potential Loss Heat Sink Red Path.

BVPS - 2L8 NRC Scenario 2, Rev 1 200f23

BEAVER VALLEY. JWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE Attachment A-O.ll 'Verification of BOP performs Attachment A-O.ll, 'Verification of Automatic Actions' performed as time Automatic Actions' as follows:

& manpower permit Checks both EDGs running Ensure Reheat Steam Isolation Ensure reheat steam isolation

Verify 2MSS-MOVIOOA and B - CLOSED

Reset reheater controller.

Check If main steam line isolation required

CNMT pressure - > 7 PSIG

-OR

Steamline pressure - < 500 PSIG

-OR

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.

NOTE: Establish domestic water system cooling to station air BOP may have already pre-emptively compressors; opened 2CCS-AOVl18 to provide

Opens 2CCS-AOV118.

cooling to the Station Air compressors.

Verifies at least 1 air compressor is running.

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

BVPS - 2L8 NRC Scenario 2, Rev 1 210f23

SEAVER VALLEY I JWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE Attachment A-O.ll- (continued) Align Neutron Flux Monitoring For Shutdown

Transfer 2NME-NR45 Nuclear Recorder to operable source and intermediate range displays.

Check CIB And CNMT Spray Status.

Containment pressure - HAS REMAINED LESS THAN 11 PSIG If not Actuate 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 1 220f23

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

Verify SI status by checking all RED SIS marks LIT

Verify CIA by checking all ORANGE CIA marks

Verify FWI by checking all GREEN FWI marks LIT Verify Power To Both AC Emergency Busses Restore power as required Attachment A-OJl COMPLETE Discrepancies: Upon Completion, Report Any Discrepancies to SRO.

NONE BVPS 2L8 NRC Scenario 2, Rev 1 230f23

A.ppen d"IX 0 r

" 0 utme S cenarlo -

Form 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 Event Malf. No. Event Type Event Description No.

1 (R) ATC Normal power increase to 15% lAW 20M-52.4.A (N)SRO 2 (TS) SRO 17 gpm S/G 21B Tube Leak 3 (TS), SRO S/G 21B atmospheric dump valve fails open.

4 (C)ATC, SRO 21B RCP high vibration with seal failure (will require manually tripping Rx and RCP) 5 M(ALL) 500 gpm 21 B S/G Tube Rupture 6 C (BOP/SRO) 2SDS-AOV129A failed open, requires RNO actions for S/G isolation.

l 7 I (BOP/SRO) Condenser steam dumps fail closed. (Requires cool down with 21A and 21C Atmospheric Stearn Dumps.

8 (C) ATC, SRO 2RCS*PCV455B, PZR spray valve, fails open following 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 1 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 IAW 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 MATERIAI~ REOUIRED PROCEDURES NEEDED

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

2. Reactivity plan AOP 2.6.4

3. EOL reactivity placard 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 PLAf\JISTATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE Initialize IC 213, and establish initial Reactor plant at 5% power, EOL, Xe increasing, plant conditions. RCS boron =644 PPM, CBn = 117 steps.

Insertthe following per the Simulator Inserts all preloads required to support the Setup section of the HTML File for this scenario.

scenano:

PRELOAD COMMANDS TRGSET 1 'JPPLP4(1)' Set trigger 1 on Reactor Trip TRGSET 4 'TPCSTAAU <=530' Set trigger 4 on Tavg < 530 degrees f IMF CNH-PCS07A (4 0) 0 2MSS-PK464 failed, closes Steam Dumps IMF VLV-MSS057A (00) 100 2SDS*AOV129A failed open TRGSET 6 'JMLRCP6B = l' Set trigger 6 when malfRCP06B is actuated TRG 6 'IMF RCP06B (0 120) 21 600 Ramp RCP vibration to 21 mils over 10 minutes 15' IMF RCS04B (3 0) 17.0 30 0 S/G tube leak: B S/G IMF CNH-MSS03A (3 600) tOO 2SVS*PCVlOIB failed open lOR XA20024G (100) OFF 2SVS*PCVlOIB Green light - off lOR XA20024R (10 0) OFF 2SVS*PCVIOIB Red light - off TRG 1 'IMF RCS04B (0 0) 500 0 0' 500 gpm S/G tube rupture: B S/G ON Rx trip IMF RCP06B (5 0) 15 RCP-B High Vibration - 15 mils on frame IMF RCPOIB (5 0) 4 30 RCP-B No.1 seal leak IMF VLV-RCS031 (75) 0 2RCS*PCV455B fails open TRGSET 7 'RRCC455B >= 0.5' 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 PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENT 1:

Normal Plant Startup, Reactor Power increase to 15% to support Turbine Startup.

20M-52.4.A, step 7.a in progress. Crew commences power increase in accordance with reactivity plan.

Continue reactor startup Reactor at 10% power.

ATC commences raising reactor power to between 10 and 15%.

Status lights on Panel 308 actuate at 10%. ATC verifies P-l 0 bistables lit on Panel 308 ATC verifies AI2-IG, 'P-lO PERMISSIVE' - LIT.

AI2-2B, - 'NIS IR TRIP BLOCKED' 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.

A12-2C, - 'POWER RANGE LOW SETPOINT ATC blocks the Power Range Low Overpower Trip by TRIP BLOCKED' placing the PR BLOCK TRAIN A and TRAIN B control switches to the BLOCK position and verifies annunciator A12-2C is LIT.

AI2-IH, - 'NOT P-T - NOT LIT. ATC verifies that annunciator AI2-IH, 'NOT P-T is NOT LIT.

A4-5G, - 'NIS POWER RANGE HIGH/LOW ATC verifies that annunciator A4-5G is OFF.

SP NEUTRON FLUX HIGH' NOT LIT.

ATC selects highest power ranges on N-45.

BVPS 2L8 NRC Scenario 3, Rev 1 60f24

BEAVER VALLEY I -,WER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE Proceed with next event at LE discretion EVENTS 2 &3:

17 gpm S/G tube leak IMMEDIATE PLANT RESPONSE: A TC reports Alarms to the SRO.

Insert TRG! 3 Rad Monitor alarms IMF RCS04B (3 0) 17.0 30 0 A4-5A; Radiation Monitoring Sys Trouble BOP checks DRMS panel and determines that 2MSS (preloaded) A4-5C, Radiation Monitoring Level High - LIT RQI02B is indicating a 1000 gpd tube leak in the "B" 10 minutes later, A4-5A, Reflash for Alert on 2SSR-RQ100, S/G S/G.

2SVS-PCVIOIB fails open Blowdown.

IMF CNH-MSS03A (3 600) 100 VCT level decreases ATC reports VCT level decreasing.

(preloaded)

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

SRO enters AOP 2.6.4 Estimate initial pri-sec leakrate 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 SRO monitors S/G Tube leak by performing ATTACHMENT 1 of AOP 2.6.4. SRO notifies Chemistry of entry into AOP-2.6.4, requests them to obtain grab samples and identify S/G, and quantify leakrate.

ROLEPLAY:

As chemistry, acknowledge need to SRO notifies RP of entry into AOP-2.6.4, requests identify S/G and quantify lealaate. surveys and analysis to identify and quantify leakrate.

As RP acknowledge need to perform SRO determines leak rate is > 30 gpd and proceeds to surveys and analysis. Wait 5 miutes ACTION LEVEL 1 of Attachment 1.

then report back that the "B" Steam line has elevated radiation levels.

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

Next event occurs 10 minutes from initiation of Tube Leak (preloaded)

EVENT 3:

IMMEDIATE PLANT RESPONSE:

10 minutes after tube leak occurs, STATUS #2 ALARM PANEL on VB-C 2SVS-PCVl OIB fails OPEN, requires indicates S/G 21B ATM STM DUMP, 2SVS manual isolation PCVlOIB is 'NOT CLOSED' Red light illuminated for 2SVS-PCVlOIB IMF CNH-MSS03B (3 600) 100 RCS Tavg shows a slight decrease SRO directs A TC to take manual control of open (Pre-loaded) ADV, (2SVS-PCVlOIB) and close it.

S/G level deviation alarms may actuate.

ADV will NOT close from BB auto/manual ATC places controller for 21B S/G ADV in manual control station. and attempts to close ADV.

BVPS - 2L8 NRC Scenario 3, Rev 1 80f24

BEAVER VALLEY I -,lIVER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS / PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENT 3: (continued) SRO requests I&C assistance.

Crew notifies Field operator to close 2SVS-PCVlOIB Valve requires manual isolation, valve using 20M-21.4.J will not close via either local manual Or locally isolate via 2SVS-24 or de-energize via operation or by de-energizing MCC ROLEPLAY:

IF requested to Isolate 2SVS-24, INSERT 'LOA-MSS017 0' then report to Control Room that 2SVS-24 is isolated NOTE: SRO refers to TS 3.7.4, Condition A for inoperable Followup question may be needed atmospheric dump valve. Requires restoring within 7 regarding TS applicability. days.

Proceed with next event at LE discretion BVPS - 2L8 NRC Scenario 3, Rev 1 90f24

BEAVER VALLEY I -,VVER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENT 4:

B Rep High Vibration/Seal Failure IMMEDIATE PLANT RESPONSE:

Insert the following: 21B RCP sealleakoffrising as indicated on ATC acknowledges RCP Hi vibration alarm, informs 2CHS-FR154A. SRO, BOP refers to A2-5C ARP.

IMF RCP01B (5 0) 4 30 A2-5C, Reactor Coolant Pump Vibration Crew notes 21B RCP Shaft vibrations at 15 mils and IMF RCP06B (5 0) 15 AlertlDanger - LIT stable.

IMF RCP06B (0 120) 21 600 15 (inserted as preload on trg 6) After 2 minute time delay 21 B RCP vibration rises to >20 mils.

SRO enters AOP-2.6.8. Crew checks RCP parameters in Table 1 of AOP 2.6.8 to determine if Criteria is met for an Immediate RCP Shutdown.

NOTE:

Trend on Rep vibration will need to be Crew determines immediate RCP SID is not required.

observed before RCP trip criteria is met. SRO continues in AOP 2.6.8 ATC verifies that EITHER Seal Injection Flow OR Thermal Barrier cooling flow is indicated to EACH Rep.

NOTE: SRO refers to Attachment 3 for RCP Vibration issue.

SRO may not enter Attachment 3 if Trend ofRCP vibration has identified Immediate RCP Trip Criteria has been met.

BVPS 2L8 NRC Scenario 3, Rev 1 of 24

BEAVER VALLEY I ...-IIVER STATION INSTRUCTIONAL GUIDELINES NT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENT 4: (continued) Shaft vibration> 15 mils and rising at> 1.0 When it is determined that RCP vibration is > 15 mils milslhr. rising at> 1 mil/hour, the SRO directs a reactor trip and the stopping of21B RCP after E-O Immediate Actions are completed.

EVENTS 5, 6, 7 & 8: SRO directs ATC to trip the reactor preloaded to occur on the Rx trip) 500 gpm B SGTR ATC manually trips reactor.

IMF RCS04B (1 0) 500 (preloaded) 500 gpm 21B SGTR when the reactor is tripped.

ATC informs SRO of a reactor trip.

SRO enters E-O. ATC and BOP commence lOA's ofE-O.

ATC verifies Reactor trip.

A5-6D - LIT.

Power range indication is < 5%.

Neutron flux is dropping.

BOP verifies Turbine trip.

Throttle OR Governor valves ALL closed.

Main Generator output brks - open.

Exciter Circuit breaker open.

BOP verifies Power to AC Emergency Busses.

Using VB-C voltmeters, verifies either AE or DF has voltage indicated.

BOP identifies that both AE and DF busses are energized from offsite power.

BVPS - 2L8 NRC Scenario 3, Rev 1 11 of24

BEAVER VALLEY I ,..",NER STATION I n-INSTRUCTIONAL GUIDELINES I PL...Il.NT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE EVENTS 5, 6, 7 & 8: (continued) Due to SGTR, PZR level and pressure will be Check SI Status dropping. Crew checks if SI is required NOTE: SI may not have actuated at

A TC checks Cnmt press> 5psig this time however, RCS co"iiUitions are

ATC checks PZR press < 1860 psig degrading due to 21B SGTR. If crew

ATC/BOP checks Steamline press < 500 psig transitions to ES-O.l at this time, they will be required to manually actuate SI Crew determines SI is Required based on PZR and return here. This scenario pressure being < 1860 psig.

assumes SI is actuated at this time and the crew continues with E-O. 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 1 120f24

BEAVER VALLEY. -,WER STATION

[ INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 5, 6, 7 & 8: (continued) List of Attachment A-0.l1 Discrepancies: SRO directs BOP to perform Attachment A-0.l1.

NOTE: Discrepancies:

Evaluation of BOP performing NONE Attachment A-0.l1 begins on page 22.

ATC checks RCS Tavg stable at or trending to 547°F RCS temperature < 547°F and dropping due to

A TC verifies no steam release is occurring.

Safety Injection flow. (Condenser steam dumps closed)

ATC verifies Reheat steam is isolated.

ATC reduces total feedflow to minimize CID.

CIB not actuated at this time. ATC checks recirc spray pumps NONE RUNNING ATC verifies PRZR isolated

PORVs CLOSED

Spray Valves - CLOSED

Safety relief valves - CLOSED (use PSMS)

PRT conditions - CONSISTENT WITH EXPECTED VALUES

Power to at least one block valve AVAILABLE

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 1 13 of24

BEAVER VALLEY I ..JWER STATION INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 5, 6, 7 & 8: (continued) ATC/BOP checks if any S/Gs are faulted

Pressures in all S/Gs - ANY DROPPING IN AN UNCONTROLLED MANNER OR

ANY S/G COMPLETELY DEPRESSURIZED 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.

SRO transitions to E-3 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 1 14 of 24

BEAVER VALLEY I .... IIVER STATION

[U INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 5, 6, 7 & 8: (continued) 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

-OR

High radiation from any S/G sample

-OR

High radiation from any S/G steamline N16 monitor Main steam RM Radiation Protection survey

-OR

High radiation from any S/G blowdown line Radiation Protection survey Crew determines "B" S/G is ruptured.

BVPS - 2L8 NRC Scenario 3, Rev 1 150f24

BEAVER VALLEY I -,WER STATION

,_uINSTRUCTIONAL GUIDELINES Inp-~(\JT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE EVENTS 5, 6, 7 & 8: (continued) ATC/BOP Isolates Flow from the Ruptured S/G.

Critical Task: E-3.A Crew confirms 2SYS*PCYlOIB previously isolated.

Crew isolates feed flow into and steam flow from the ruptured S/G BOP verifies residual heat release valve - CLOSED.

and directs operator to close isolation SRO dispatches operator to locally close 2SYS*28.

valve(s) operated from outside of the control room before a transition to Isolate ruptured S/G to turbine driven AFW pump.

ECA-3.1 occurs. BOP confirms 2 motor driven AFW pps running.

BOP closes 2MSS*SOY105B and 105E.

Basis for Selection:

SAFETY SIGNIFICANCE -- Failure to Verify closes ruptured S/G Blowdown isolation valve isolate the ruptured S/G causes a loss of BOP verifies 2BDG* AOVIOOBI is closed.

differential pressure between the ruptured S/G and the intact S/Gs. Upon Close main steamline drain from ruptured S/G.

a loss of differential pressure, the crew BOP closes 2SDS*AOYII1Bl must transition to a contingency procedure that constitutes an incorrect Close 2SDS* AOV129A, RHR piping drain isolation, performance that lI.necessitates the crew BOP unsuccessfully attempts to close taking compensating action which 2SDS*AOY129A.

complicates the event mitigation BOP successfully closes 2SDS* AOY129B strategy. II Close ruptured S/G main steam isol & bypass vlvs BOP closes 2MSS*AOYIOIB ROLEPLAY: BOP verifies 2MSS* AOY102B closed.

5 minutes after being dispatched to locally isolate 2SYS*28, insert BOP checks ruptured NR S/G level> 12%

IRF LOA-MSSOIO (0 0) 0 0 BOP closes AFW throttle valves on ruptured S/G then report back that 2SVS*28 has been

2FWE*HCYIOOC, D (may have been pre closed. emptively isolated)

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

BYPS - 2L8 NRC Scenario 3, Rev 1 160f24

BEAVER VALLEY I ../IIVER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS / PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 5, 6, 7 & 8: (continued) Condenser available Crew initiates RCS cooldown SRO determines required core exit temperature as a Steam dumps fail closed when function of ruptured S/G pressure:

attempting to use them for cooldown.

(command preloaded) SRO directs A TC to block low steamline pressure SI IMF CNH-PCS07A (4 0) 0 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 TAVG interlock until status light A-12, "Stm Dump Defeat Interlock" (Panel 622) - LIT

Gradually raises steam dump rate to maximum rate (~25% demand)

BOP reports steam dumps are not responding to controller demand.

BVPS - 2L8 NRC Scenario 3, Rev 1 170f24

BEAVER VALLEY I -,WER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE r EXPECTED STUDENT RESPONSE EVENTS 5, 6, 7 & 8: (continued) SRO directs BOP to manually dump steam at NOTE: maximum rate using atmospheric steam dumps.

Before using 2SVS*HCVI 04, crew BOP opens 2SVS*PCVlOIA must recognize that they must have BOP opens 2SVS*PCVlOIC dispatched an operator to locally isolate BOP opens 2SVS*HCV104 from the "B" S/G and received a report that it was isolated.

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 ATC 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 STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 5, 6, 7 & 8: (continued) BOP checks if RCS cooldown should be stopped

When Core exit TCs (average of five hottest)

Critical Task: E-3.B Crew LESS THAN REQUIRED TEMPERATURE establishes/maintains an RCS temperature so that transition from BOP stops RCS cooldown and maintains core exit E-3 does not occur because the RCS TCs LESS THAN REQUIRED TEMPERATURE.

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 BOP verifies ruptured "B" SIG Pressure- STABLE

"... necessitates the crew taking OR RISING compensating action which complicates the event mitigation strategy .... " ATC verifies RCS subcooling based on core exit TCs GREATER THAN 61°F BVPS 2L8 NRC Scenario 3, Rev 1 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 Flow Pzr spray valve, 2RCS*PCV455B fails And Refill PZR open following depressurization.

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

Fully opens available PZR spray valves IMF VLV-RCS031 (75) 0

Opens one PZR PORV TRGSET 7 'RRCC455B >= 0.5' Checks depressurization method - IS EFFECTIVELY REDUCING RCS PRESSURE Critical Task: E-3.C ATC continues depressurization until any of the Crew depressurizes the RCS to meet following conditions satisfied:

SI termination criteria before water release from the ruptured S/G safety PZR level> 76%

or atmospheric relief valve. OR RCS subcooling < Attachment A-5.l Basis for Selection: OR SAFETY SIGNIFICANCE -- Failure to RCS pressure < "B" S/G pressure AND stop reactor coolant leakage into a PZR level> 17%

ruptured S/G by depressurizing the RCS needlessly complicates mitigation ATC closes PORV.

of the event. It also constitutes a "significant reduction of safety margin ATC closes spray valves, beyond that irreparably introduced by ATC reports 2RCS*PCV455B failed to close.

the scenario."

SRO directs ATC to stop 2IC RCP.

Checks RCS pressure is rising ATC 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 ATC verifies HHSI flow indicates zero gpm.

A TC Establishes Charging flow by:

Closing 2CHS*FCV122 Terminate scenario when the crew has Opening 2CHS*MOV310 isolated HHSI flow and established a Opening 2CHS*MOV289 normal chargIng flowpath. Adjusting 2CHS*FCV122 as necessary to maintain PZR level between 31 % and 50%.

Classify Event:

ALERT due to Tab 1.2.4, LOSS of RCS Barrier, Primary to Secondary Leak:.

BVPS - 2L8 NRC Scenario 3, Rev 1 21 of24

BEAVER VALLEY. JWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE Attachment A-O.ll 'Verification of BOP performs Attachment A-O.ll, 'Verification of Automatic Actions' performed as time Automatic Actions' as follows:

& manpower permit Checks both EDGs running Ensure Reheat Steam Isolation Ensure reheat steam isolation

Verify 2MSS-MOVlOOA and B - CLOSED

Reset reheater controller.

Check If main steamline isolation required

CNMT pressure - > 7 PSIG

-OR

Steamline pressure - < 500 PSIG

-OR

Steamline pressure high rate of change - 100 PSIG DROP IN 50 SECONDS If steamline isolation IS required, Verifies SLI by checking all YELLOW SLI marks - LIT If steamline isolation is NOT required continues on.

NOTE: Establish domestic water system cooling to station air BOP may have already pre-emptively compressors; opened 2CCS-AOVl18 to provide

Opens 2CCS-AOV118.

cooling to the Station Air compressors.

Verifies at least 1 air compressor is running.

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

BVPS - 2L8 NRC Scenario 3, Rev 1 220f24

BEAVER VALLEY, -,WER STATION C:=INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE Attachment A-O.ll - (continued) Align Neutron Flux Monitoring For Shutdown

Transfer 2NME-NR45, Nuclear Recorder to operable source and intermediate range displays.

Check 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 1 23 of 24

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

Verify SI status by checking all RED SIS marks

-LIT

Verify CIA by checking all ORANGE CIA marks - LIT

Verify FWI by checking all GREEN FWI marks- LIT Verify Power To Both AC Emergency Busses Restore power as required Attachment A-O.ll - COMPLETE Discrepancies: Upon Completion, Report Any Discrepancies to SRO.

NONE BVPS - 2L8 NRC Scenario 3, Rev 1 240f24

A.ppend'IX 0 . 0 utl"me S cenarlo Form ES 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 ppm.

Conditions:

Turnover: Maintain steady state power at 100%, 2FWE*P23A OOS, 2SAS-C21B OOS Critical Tasks: 1. E-O.O Close CNMT isolation valves

2. E-1.C Stop RCP's

3. FR-S.1.C Insert RCCA's Event Malf. No. I Event Type Event Description No.

1 (1) ATe, SRO 2RCS*L T459 fails low.

(TS) SRO 2 (N)ATe, SRO Restore letdown to service 3 (R) ATC Valve position limiter failure causes load rejection with Auto (I) ATe, SRO rod malfunction, ATC required to insert negative reactivity.

4 (e) BOP, SRO During load rejection, "A" Main Feed Regulating Valve controller holds valve in position, BOP required to manually control "A" S/G level.

5 (C) ATe, SRO 2RCS*PT445 fails high, 2 PORV's open, 2RCS*PCV456 fails (TS) SRO to 18% open with Block valve failed open, requiring crew to manually trip the reactor.

6 (M)ALL ATWS, crew enters FR-S.1.

7 (M)ALL 2000 gpm SBLOCA on return to E-O.

8 (e) BOP, SRO Train B CIA failure with 2CHS*MOV378 failing to auto close 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 instrUl~tions to maintain steady state conditions.

The controlling PZR level channel, 2RCS*LT459 will fail low causing letdown to automatically isolate.

The crew will enter the Instrument failure procedure to address the failed channel and place the alternate channel in service. The US will determine appropriate Tech Spec action.

After the alternate channel is placed in service, the crew will restore normal letdown to service.

When letdown has been restored, the valve position limiter will fail causing a load rejection with an Auto Rod malfunction requiring the A TC to manually insert control rods.

During the load rejection, the "A" Main feed regulating valve will fail to control in auto (the valve will remain in its 100% power position), The BOP will be required to recognize the malfunction and manually control the "A" S/G level.

Once the plant has stabilized, a RCS control pressure transmitter, 2RCS*PT445 will fail high, causing 2 PORV's to open, 2RCS*PCV456 will stick at 18% open, with the block valve failing to close. The SRO will address PORV Tech Spec. RCS pressure will continue to slowly decrease requiring the SRO to direct the crew to manually trip the reactor and enter E-O.

The reactor will fail to trip from the control room, the SRO will transition to FR-S.l and the crew will dispatch an operator to locally trip the Rx. After the reactor is locally tripped, the crew will return to E-O.

3 minutes after the reactor is locally tripped, a 2000 gpm LOCA will occur on the "A" loop, the crew will transition to 1. The crew will be required to recognize that RCS / Secondary pressure DP requirements are met to require that the RCP's be manually tripped.

Train "B" CIA will fail to actuate along with 2CHS*MOV378 failing to auto close on the Train "A" CIA signal.

The scenario will be terminated after the crew transitions to ES-I.2.

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 ATC position 1OO~PqWER display YCT - 2SAS-C21B CS EOUIPMENT STATUS DATErrIME OOS TECHNICAL SPECIFICATION(S) 2FWE*P23A OOS, motor bearing replacement.

-~~~~

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ago 3.7.5 condition B 2SAS-C21B OOS compressor overhaul. 3 days ago SHIFT TURNOVER INFORMATION

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

SCENARIO SUPPORT MATERIAL REQUIRED PROCEDURES NEEDED

1. MOL Reactivity placard 20M-6.4.IF, attachment 1 20M-7.4.AB AOP 2.1.8 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 1 30f23

BEAVER VALLEY I .JWER STATION r- m INSTRUCTIONAL GUIDELINEc=J PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE Initialize IC 214, and establish initial Reactor plant at 100% power, MOL, plant conditions. Equilibrium Xe, RCS boron 044 PPM, ARO.

Insert the following per the Simulator Inserts all pre-loads required to support the Setup section of the HTML File for this scenano scenano:

PRELOAD COMMANDS IMF PPLOIA (0 0) 1 Train A RTB failed closed IMF PPLOIB (0 0) 1 Train B RTB failed closed IMF PPL08B (0 0) 0 Train B auto CIA actuation failure TRGSET 1 'XA4I106C' Set trigger 1 on 2CHS*MOV378 switch to close IMF VLV-SEAOI5 (0 0) 1 2CHS*MOV378 failed open TRG 1 'DMF VLV-SEAOI5' 2CHS*MOV378 closes manually TRGSET 10 'JMLEHC6' Trigger 10 = VPL failure TRG 10 'SET JWSF478 AUTO=TRUE' 2FWS*FCV478 controller failed as is in auto IMF CNH-CFWI0C (10 45) 1500 2FWS*FCV478 controller oscillation during load rejection.

IMF PPL02A (8 120) 1 Train A trip BKR open IMF PPL02B (8 125) 1 Train B trip BKR open IRF LOA-CRF007 (8 140) 1 Trip A rod drive MG set IRF LOA-CRF008 (8145) 1 Trip B rod drive MG set TRGSET 6 'RRCH456 > 0.0' Set trigger 6 for PORV 456 position> 0 IMF VLV-RCS034A (6 0) 1800 2RCS*PCV456 PRZR PORV fails to 18% open TRGSET 7 'MCRFNS(41) <= 214' Set trigger 7 for Rods < 214 steps IMF CRFOIA (7 0) 1 Inhibit Auto Rod insertion IMF VL V-RCS012 (0 0) 1 2RCS*MOV536 failed open IMF RCS02A (8 300) 2000 30 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, Simulator running. Crew assumes control of the Unit.

place the simulator to RUN and commence the scenario.

BVPS - 2L8 NRC Scenario 4, Rev 1 50f23

BEAVER VALLEY, ...-IIVER STATION INSTRUCTIONAL GUIDELINES L PLANT STATUS I PROCEDURAL GUIDANCE r EXPECTED STUDENT RESPONSE EVENTS 1 &2:

Pressurizer level transmitter IMMEDIATE PLANT RESPONSE: ATC reports multiple unexpected pressurizer alarms.

2RCS*LT459 fails low. ALARMS: ATC identifies 2RCS*LT459 failed low and places A4-1B, PZR Control LvI HighILow, 2CHS*FCY122 in manual to control PZR level.

IMF XMT-RCS019A (0 0) 2000 30 A4-1 C, PZR Control LvI Dev High/Low, A4-1 G,PZR Control Htr Group Trouble, SRO provides a control band and Rx trip criteria of A4-2G, PZR BIU Htr Group Auto On/Off, 14% low/85% high for manual PZR level control.

A2-3E, Charging Flowpath Trouble.

2RCS-LI459 indicates downscale. BOP begins referring to ARP's.

2CHS*FCYI22 opens to increase flow.

Letdown isolates, 2CHS*LCY460B and 2CHS AOY200A & B close.

All PZR heaters de-energize.

SRO enters 20M-6.4.IF, attachment 1.

ATC places PZR level control channel selector to position II & III.

ATC verifies PZR level recorder selector is positioned to record the controlling level channel.

ATC verifies there is adequate makeup to the YCT.

ATC verifies PZR heaters (Control & Backup) groups have returned to normal or manually energizes heaters as necessary.

BYPS - 2L8 NRC Scenario 4, Rev 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 20M 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 PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE ul EVENTS 3 & 4:

Turbine Runback due to Valve Position IMMEDIATE PLANT RESPONSE: lAW Immediate Operator Action of AOP 2.1.3, ATC limiter failure, "A" main feed reg valve Rods begin stepping in, announces unexpected rod motion, verifies megawatts auto controller holds valve in position, Megawatts decrease, decreasing and announces load rejection.

Control rods step in until 214 steps then RCS temperature and pressure rise accordingly.

moving in Auto. Rods stop moving at 214 steps.

As power reduces "A" S/G level increases.

IMF EHC06 (0 0) 79 0 ASIS SRO enters AOP 2.35.2 ATC checks Rods are inserting in AUTO and Tavg is dropping to Tref.

When rods quit moving ATC recognizes Tavg-Tref mismatch exists and places rods to manual and continues insertion.

BOP recognizes "A" S/G level is rising, takes manual control of "A" main feed reg valve and reduces flow to control level at 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.

Continue with next event at LE discretion BVPS - 2L8 NRC Scenario 4, Rev 1 80f23

BEAVER VALLEY I -,lIVER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS:

IMMEDIATE PLANT RESPONSE:

2RCS*PT445 fails high, 2 PORV's A TC reports multiple unexpected pressurizer alarms.

open, 2RCS*PCV456 fails to 18% 2 PORV's initially open, 456 sticks at 18% open, ATC identifies 2RCS*PT445 has failed high and that open with Block valve failed open, Other PORV will automatically close when 2 PORV's have opened.

requiring crew to manually trip the pressure reduces to 2185 psig. ATC reports that PORV, 2RCS*PCV456 failed to reactor. RCS pressure continues to decrease. automatically close on low pressure.

IMF XMT-RCS031A (0 0) 2500 20 ATC attempts to close 2RCS*PCV456, PORV remains at dual position.

ATC attempts to close block valve, 2RCS*MOV536.

ATC reports 2RCS*MOV536 will not close.

NOTE: SRO recognizes TS applicability for an inoperable Due to dynamic nature of event, a PORV and Block valve.

followup question regarding applicable TS 3.4.11, Conditions Band C.

TS may be necessary.

Crew determines failure will not support normal plant operations, SRO directs crew to manually trip and perform lOA's for E-O.

SRO enters E-O EVENTS 6, 7, & 8 ATWS 2000 gpm SBLOCA when Rx is tripped A TC attempts a manual reactor trip, reports trip Train "BOO CIA actuation failure with failure! A TWS condition.

failure of2CHS*MOV378 to auto close.

(all commands preloaded)

SRO enters FR-S.l SRO directs operators to perform lOA's of FR-S.1, implements FR-S.l at step 1 of E-O.

BVPS - 2L8 NRC Scenario 4, Rev 1 90f23

BEAVER VALLEY . ..JWER STATION

'----___N'-'-S~TRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 6, 7, & 8 (continued)

Critical Task FR-S.1.C:

Crew inserts negative reactivity into Crewperfonns lOA's ofFR-S.l.

the core by inserting RCCAs before BOP manually trips Turbine.

completing the immediate action steps of FR-S.1. ATC manually begins inserting rods.

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)."

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 (continued) BOP verifies AFW status.

BOP manually starts 2FWE*P23B motor-driven AFW pump.

BOP manually opens 2MSS*SOV105A-F to start Turbine-driven AFW pump, 2FWE*P22.

BOP verifies all AFW throttle valves are open.

BOP verifies AFW flow.

NOTE: Crew initiates Emergency Boration Flow by; Dependent upon crew response, SI may not be actuated at this time, if so the Verifying at least 1 charging pump is running crew will initiate Emergency Boration Checking Safety Injection is actuated and recognizes flow by: Emergency boration is not required due to SI flow.

Opening 2CHS*MOV350 BOP verifies HHSI flow Starting "A" Boric Acid pump Verifying> 30 GPM flow Adjusting 2CHS*FCV122 to establish> 40 GPM flow.

ATC verifies RCS pressure is < 2330 psig.

-t>

BVPS 2L8 NRC Scenario 4, Rev 1 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, insert:

TRG!8 Following commands are preloaded, activate Trigger 2 as soon as requested, 1st Rx trip breaker will open 2 minutes after actuating Trigger 8. (TRG! 8)

IMF PPL02A (8 120)

IMF PPL02B (8 125)

IRF LOA-CRF007 (8140) 1 IRF LOA-CRF008 (8 145) 1 (all commands preloaded)

ROLEPLAY:

When all breakers are open, report actions to the control room.

Crew continues in FR-S.l after dispatching an BOP verifies turbine is tripped.

operator to locally trip the Unit 2 reactor. BOP verifies 2MSS-MOVlOOA, B automatically CLOSED.

BOP depresses the RESET Pushbutton on the Reheater Controller.

ATC checks ifSI is actuated.

SI is actuated, first nine steps of E-O have not been completed.

BVPS 2L8 NRC Scenario 4, Rev 1 120f23

BEAVER VALLEY I .... VVER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 6, 7, & 8 (continued)

NOTE: ATC checks ifRx is subcritical:

This is a continuous action step, when

Power range channels < 5%.

the Rx is locally tripped the crew will

IR channels - negative startup rate.

return to this step and then transition back to E-O, Step 1.

NOTE: When the Rx is locally tripped.

Event 7, 2000 gpm SBLOCA will SRO returns to E-O, step 1.

occur 3 minutes after the Rx is locally tripped. (command preloaded)

ATC verifies Reactor trip:

Rx trip and bypass breakers open.

Power range indication is < 5%.

Neutron flux is dropping.

BOP verifies Turbine trip:

Throttle OR Governor valves ALL closed.

Main Generator output brks open.

Exciter Circuit breaker - open.

BOP verifies Power to AC Emergency Busses:

Using VB-C voltmeters, verifies either AE or DF has voltage indicated.

BOP identifies that both emergency busses are energized from off-site power.

BVPS 2L8 NRC Scenario 4, Rev 1 130f23

BEAVER VALLEY. -"lIVER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 6, 7, & 8 (continued) SI automatically actuated due to low pressurizer Check SI Status:

pressure from stuck open PORV.

ATC checks that SI is actuated.

ATC manually actuates SI by turning both trains Control Switches.

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.

ATC verifies SI System Status:

Both 2CHS*P21A and P21B pumps running.

HHSI Flow indicated.

Both LHSI pumps running.

BOP verifies AFW System status:

Motor-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 1 140f23

BEAVER VALLEY I .AVER STATION CIN$IRlJCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 6, 7, & 8 (continued) SRO directs BOP to perform Attachment A 0.11.

NOTE: List of Attachment A-O.II Discrepancies:

Evaluation of BOP performing Attachment A-0.11 begins on page 21. Discrepancies:

"B" Train CIA failed to actuate along with failure of2CHS*MOV378 failing to automatically close. Manual actuation successful.

ATC checks RCS Tavg stable at or trending to 547°F:

RCS temperature < 547°F and dropping due to

A TC verifies no steam release is occurring.

Safety Injection flow. (Condenser steam dumps closed)

ATC verifies Reheat steam is isolated.

A TC reduces total feedflow to minimize C/D.

CIB not actuated at this time. 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.

SRO transitions to E-I ATC checks if CREVS should be actuated.

Checks EITHER of the following:

Control Room Radiation Monitor 2RMC*RQ201,202 - NOT IN HIGH ALARM.

CIB - HAS NOT OCCURRED.

Crew reports CREV's is NOT required.

BVPS 2L8 NRC Scenario 4, Rev 1 150f23

BEAVER VALLEY I -iWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 6, 7, & 8 (continued) A TC checks if RCPs should be stopped

DIP between RCS pressure and highest S/G Critical Task E-l.C: pressure NOT LESS THAN 205 PSID [220 Crew trips all RCPs when RCS to PSID ADVERSE CNMT]

highest SG DIP criteria is exceeded

DP Criteria for stopping RCPs is met.

and SI Dow verified prior to exiting procedure E-l ATC shuts down ALL RCP's after verifying HHSI flow.

Basis for Selection:

SAFETY SIGNIFICANCE -- Failure to trip the RCPs under the postulated plant conditions leads to core uncovery and to fuel cladding temperatures in excess 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 ATC verifies CIB is NOT actuated.

ATCIBOP checks if any S/Gs are faulted:

Pressures in all S/Gs - ANY DROPPING IN AN UNCONTROLLED MANNER OR

ANY S/G COMPLETELY DEPRESSURIZED Crew determines no S/G's are faulted.

BVPS - 2L8 NRC Scenario 4, Rev 1 160f23

BEAVER VALLEY I __ lIVER STATION

[ IN~,-RUCTIONAL GUIDELINES I. PLAf'!T STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 6, 7, & 8 (continued) 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 1 170f23

BEAVER VALLEY. -,WER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 6, 7, & 8 (continued) Crew checks if SI Flow should be Reduced.

ATC verifies RCS Subcooling is NOT> 41°F [59°F ADVERSE CNMT] based on CETC's Crew verifies subcooling is NOT greater than Attachment A-5.1.

Crew determines that current plant conditions do not support SI reduction and continues with next procedure step.

Check if CNMT spray should be stopped.

ATC verifies no Quench or Recirc Spray pumps are runnmg.

ATC resets SI - both trains.

ATC resets CIA - both trains.

ATC checks if LHSI pumps should be stopped.

ATC verifies RCS pressure is > 225 psig [250 psig ADVERSE CNMTl and NOT stable or rising.

ATC leaves both LHSI pumps running.

BVPS 2L8 NRC Scenario 4, Rev 1 180f23

BEAVER VALLEY. JWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 6, 7, & 8 (continued) Check RCS and S/G Pressures.

BOP checks pressure in all 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 20M 36.4.AF(AG) as time permits.

BOP performs Attachment A-O.6 to verify power available to at least 1 train of Cold Recirculation equipment.

BOP reports Attachment A-O.6 completed SAT with no discrepancies.

Crew evaluates Radiation monitors, determines Auxiliary building and Safeguards radiation is consistent with pre-event values.

SRO determines TSC is not activated.

SRO directs ATC to monitor nuclear instrumentation to ensure adequate Shutdown Margin.

BVPS 2L8 NRC Scenario 4, Rev 1 190f23

BEAVER VALLEY . JWER STATION 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 Event:

SAE, SITE AREA EMERGENCY due to Tab 2.3, Failure of Reactor Protection.

BVPS - 2L8 NRC Scenario 4, Rev 1 200f23

BEAVER VALLEY * .JWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE Attachment A-O.ll 'Verification of BOP performs Attachment A-O.ll, 'Verification of Automatic Actions' performed as time Automatic Actions' as follows:

& manpower permit.

Checks both EDGs running.

Ensure Reheat Steam Isolation. Ensure reheat steam isolation:

Verify 2MSS-MOVIOOA and B - CLOSED.

Reset reheater controller.

Check If main steamline isolation required

CNMT pressure - > 7 PSIG.

-OR

Steamline pressure - < 500 PSIG.

-OR

Steamline pressure high rate of change 100 PSIG DROP IN 50 SECONDS.

If steamline isolation IS required, Verifies SLI by checking all YELLOW SLI marks - LIT.

If steamline isolation is NOT required continues on.

NOTE: Establish domestic water system cooling to station air BOP may have already pre-emptively compressors; opened 2CCS-AOVII8 to provide

Opens 2CCS-AOVII8.

cooling to the Station Air compressors.

Verifies at least 1 air compressor is running.

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

BVPS - 2L8 NRC Scenario 4, Rev 1 2Iof23

BEAVER VALLEY . JWER STATION INSTRUCTIONAL GUIDELINES nnn I PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE Attachment A-O.II (continued) Align Neutron Flux Monitoring For Shutdown

Transfer 2NME-NR45 Nuclear Recorder to operable source and intennediate range displays.

Check CIB And CNMT Spray Status:

CNMT press - HAS REMAINED < 11 PSIG.

If not - Actuate CIB as required by:

Manually initiate CIB BOTH SWITCHES FOR BOTH TRAINS.

Manually align equipment as required.

Verify all RCPs STOPPED.

BV-1 operator verifies CREVS actuation.

Service water established to RSS HX(s).

Verify Service Water System In Service:

SWS Pumps - TWO 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 1 220f23

BEAVER VALLEY . ...JWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE Attachment A-O.ll (continued) Verify ESF Equipment Status:

Verify SI status by checking all RED SIS marks Critical Task E-O.O LIT.

Crew closes Cnmt isolation valves "B" Train CIA failed to actuate,

Verify CIA by checking all ORANGE CIA such that at least one valve is closed 2CHS*MOV378 failed to auto close. marks LIT.

on each critical phase A penetration Manual actuations successful.

Verify FWI by checking all GREEN FWI before the end of the scenario. marks LIT.

Basis for Selection:

SAFETY SIGNIFICANCE -- Failure to close at least one containment isolation valve on each critical phase-A penetration, under the postulated plant conditions and when it is possible to do so, constitutes "mis-operation or incorrect crew performance which leads to degradation of any barrier to fission product release." In tbis case, the containment barrier is needlessly left in a degraded condition.

Verify Power To Both AC Emergency Busses Restore power as required.

Attachment A-O.ll - COMPLETE Discrepancies: Upon Completion, Report Any Discrepancies to SRO.

"B" Train CIA failed to actuate, 2CHS*MOV378 failed to auto close.

Manual actuations successfuL BVPS 2L8 NRC Scenario 4. Rev 1 230f23

A,ppend'IX 0 S cenano r

. 0 utme Form 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 ppm.

Conditions:

Turnover: Maintain steady state power at 100%, 2FWE*P23A OOS, 2SAS-C21B OOS Critical Tasks: 1. E-O.D Crew manually actuates at least one train of SIS

2. E-O.F Crew establishes the minimum required AFW flow

3. E-O.M Crew closes the upstream block MOV of the stuck open Pzr PORV

4. E-O.I Establish flow from at least 1 High head ECCS pump I

Event Malf. No. Event Type Event Description No.

1 (1) ATC, SRO 2RCS*PT444 drifts low, requires ATC to manually control RCS pressure.

2 (TS) SRO 2FWS-L T485 fails high 3 (C) BOP, SRO Voltage regulator failure causes main generator over excitation, requires BOP to tum voltage regulator off and manually lower excitation.

4 (C)ATC, SRO 25 gpm RCS leak on "A" Loop.

(TS) SRO 5 (M) ALL 500 gpm RCS leak on "A" Loop.

6 (C) ATC, SRO 2RCS-PCV455D fails open on Rx trip, requires ATC to close block valve.

7 (C) BOP, SRO AFW malfunctions, 2FWE*P23A OOS on turnover, 2FWE*P23B auto start failure, requires BOP to manually start.

2FWE*P22 running with reduced flow << 340 gpm) 8 (C) ATC, SRO Auto SIS inhibited, requires ATC to manually actuate SIS.

9 (C) ATC, SRO 2SIS*MOV867's fail to open on SIS actuation signal, ATC required to manually open valves to initiate Safety Injection flow.

(N)orrnal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1 021, Revision 9 Supplement 1 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 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 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 PROCEDURES NEEDED

1. BOL reactivity placard 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 LelA"'!TSfATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE Initialize IC 217, and establish initial Reactor plant at 100% power, BOL, Equilibrium plant conditions. Xe, RCS boron =1458 PPM, ARO.

Insert the following per the Simulator Inserts all pre-loads required to support the Setup section of the HTML File for this scenarIO scenarIO:

PRELOAD COMMANDS TRGSET 1 'JPPLP4(1)' Set trigger 1 on reactor trip IRF LOA-AFWOOI (00) 0.1 0 2FWE*P22 low flow (discharge valve throttled)

IMF PPL07B (0 0) 5 2FWE*P23B auto start failure IRF LOA-HIV055 (0 0) 1 2FWE*P23A breaker racked out IMF PMP-CAS004 (0 0) 1 2SAS-C21 BOOS IMF VLV-RCS033A (1 0) 20 0 ASIS 2RCS*PCV455D fails to 20% open upon trip IMF PPL05A (0 0) 0 Train A auto SI actuation failure IMF PPL05B (0 0) 0 Train B auto SI actuation failure TRGSET 3 'JMLRCS2A == 1 .AND. Set trigger 3 on 25 gpm leak and XBlI045P = l' 2CHS *LCV460A CS to open.

TRG 3 'IMF RCS02A (0 0) 500 0 asis 500 gpm SBLOCA "A" Loop when LID begins to be re-established.

IMF VL V-SIS069 (0 0) 2 2SIS*MOV867A failed closed TRGSET 6 'XA4I081P' Set trigger 6 on 2SIS*MOV867A CS to open TRG 6 'DMF VLV-SIS069' 2SIS*MOV867A opens upon manual attempt IMF VL V-SIS070 (0 0) 2 2SIS*MOV867B failed closed TRGSET 7 'XA4I076P' Set trigger 7 on 2SIS*MOV867B CS to open TRG 7 'DMF VLV-SIS070' 2SIS*MOV867B opens upon manual attempt IMF VL V-SIS071 (0 0) 2 2SIS*MOV867C failed closed TRGSET 8 'XA4I094P' Set trigger 8 on 2SIS*MOV867C CS to open TRG 8 'DMF VLV-SIS071, 2SIS*MOV867C opens upon manual attempt IMF VL V-SIS072 (0 0) 2 2SIS*MOV867D failed closed TRGSET 9 'XA4I090P' Set trigger 9 on 2SIS*MOV867D CS to open TRG 9 'DMF VLV-SIS072' 2SIS*MOV867D opens upon manual attempt BVPS 2L8 NRC Scenario 5, Rev 1 40f25

BEAVER VALLEY, -,WER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE Assign shift positions SRO:_ _ _ _ _ _ _ __

ATC:_ _ _ _ _ _ _ __

BOP:_ _ _ _ _ _ _ __

Conduct a shift turnover with oncoming Simulator Frozen until after shift turnover unless operators. it needs to be run momentarily for an alignment change.

When the shift turnover is completed, Simulator running. Crew assumes control of the Unit.

place the simulator to RUN and commence the scenario.

BVPS - 2L8 NRC Scenario 5, Rev 1 50f25

BEAVER VALLEY. __ lIVER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS / PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENT 1:

Pressurizer Pressure control channel IMMEDIATE PLANT RESPONSE: ATC reports unexpected alarm, A4-1E.

fails low 2RCS-PT444 drifts low IMF XMT -RCS030A (0 0) 1700 240 PZR htr grps A & D, Backup grps B & E tum ATC identifies 2RCS*PT444 failing low.

on.

pzr htr Control grp C modulates high A TC controls PZR pressure by operating Master Spray valves, 2RCS*PCV455A & 455B Pressure controller in manual or manually operating modulate closed. individual PZR heaters and spray valves.

A4-1E, PZR Control Press Dev High/Low BOP refers to ARP.

A4-2G, PZR BIU Htr Group Auto On/Off With pzr htrs and spray valve control in Manual, SRO establishes a control band and Rx trip criteria 2100 psig low / 2340 psig high for manual pzr pressure control.

SRO enters 20M-6.4.1F, Attachment 2 SRO evaluates applicable TS; TS 3.3.4 for Remote Shutdown Instrumentation - for Info Only.

SRO contacts Operations management and notifies I&C of pressure transmitter failure.

Proceed with next event at LE discretion -

BVPS - 2L8 NRC Scenario 5, Rev 1 60f25

BEAVER VALLEY I -,vVER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENT 2:

IMMEDIATE PLANT RESPONSE:

21B S/G Channel II level transmitter, 2FWS*LT485 fails high BOP reports unexpected alarm, A6-1 OD 2FWS*LT485 fails high. A6-lOD, S/G 21B Level High/Low BOP verifies actual S/G parameters, steam flow/feed IMF XMT-MSS006A (0 0) 10060 flow and S/G level are stable.

ATC refers to ARP.

NOTE: No system response occurs on failure of a single channel due to BOP reports failure of2FWS*LT485.

median signal select feature.

SRO enters 20M-24.4.IF, Attachment 1 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.

Continue with next event at LE SRO contacts Operations management and notifies discretion I&C of level transmitter failure.

BVPS - 2L8 NRC Scenario 5, Rev 1 70f25

BEAVER VALLEY . ..JWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENT 3:

IMMEDIATE PLANT RESPONSE:

Voltage Regulator Failure BOP reports unexpected electrical alarm.

IMF GEN02 (0 0) 26 20 ASIS MUG Excitation increases Main Generator VARS increase BOP identifies voltage regulator failure.

Main Generator Power Factor decreases (more lagging) ATC refers to ARP.

A7-4C, Generator Field Forcing BOP turns voltage regulator off and manually reduces MUG excitation using exciter base adjust to lower VARS to restore power factor.

SRO provides BOP a control band for power factor of 0.9 to 1.0 lagging.

Continue with next event at LE SRO contacts Operations management and notifies discretion maintenance of voltage regulator failure.

BVPS - 2L8 NRC Scenario 5, Rev 1 80f25

BEAVER VALLEY . ..JWER STATION INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENT 4:

IMMEDIATE PLANT RESPONSE:

25 gpm leak on "A" RCS loop inside A TC reports indications of a RCS leak inside CNMT.

CNMT. PZR pressure begins decreasing.

IMF RCS02A (0 0) 25 0 0 A4-5A15C, DRMS Trouble / High Alarm CNMT Radiation monitors; 2RMR-RQ303A, B HIGH alarms CNMT humidity increasing SRO enters AOP 2.6.7 for excessive primary ATC confirms VCT / PZR level can be maintained.

plant leakage.

Crew checks ifleakage is RCS/CVCS; Crew confirms CNMT radiation and humidity are not consistent with pre-event values.

ATC verifies RCS temperature is stable.

ATC checks 2CHS*FCV122 is in AUTO and PZR level is NOT stable.

A TC places 2CHS*FCV122 in MANUAL and adjusts to maintain a constant PZR level.

ATC checks VCT level trend.

ATC identifies VCT level is dropping at> 0.7%/min and reports to SRO that leak rate is > 10 gpm.

NOTE: SRO recognizes TS 3.4.13 Condition A, is applicable Due to dynamic nature of event, a for unidentified leakage.

followup question regarding applicable TS may be necessary.

BVPS 2L8 NRC Scenario 5, Rev 1 90f25

SEAVER VALLEY. ...WER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENT 4: (continued) 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.

ATC confirms leakage is not in the evcs system and restores Charging and Letdown by; EVENTS: Adjusting 2CHS*FCV122 for 30-50 gpm flow.

Verifying PZR level> 14%.

500 gpm SBLOCA on "A" RCS Loop Placing 2CHS*PCVI45 in MAN & 50% open.

Opening 2CHS*LCV460A and B NOTE: Command is preloaded to PZR level and pressure decreases Opening 2CHS* AOV200A and/or 200B/C.

occur when 2CHS*LCV460A is Adjusting 2CHS*PCV145 to 260 psig then opened during lid restoration step of returning to AUTO.

AOP 2.6.7 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: SRO directs ATC to trip the reactor.

preloaded to occur on the reactor SI Auto actuation failure trip) 2RCS*PCV455D fails to 20% open - block valve can be closed to stop leak.

2FWE*P22 running with minimal flow (~105 gpm to each stG) 2FWE*P23B Auto start failure (P23A - OOS) 2SIS*MOV867's fail to open on SIS Signal SRO enters E-O. ATC and BOP commence lOA's ofE-O.

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 1 11 of25

BEAVER VALLEY * ....,WER STATION

[ INSTI3l..!CTlgNAL GUIDELINES rPLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 6, 7, 8, & 9: (continued) PORV failing to 20% open on the reactor trip Check SI Status.

will reduce PZR pressure below Auto SI Crew checks if SI is required.

Critical Task: E-O.D setpoint.

A TC checks Cnmt press> 5psig Crew manually actuates at least one

ATC checks PZR press < 1860 psig train of SIS-actuated safeguards

ATC/ BOP checks Steamline press < 500 psig before transition to any ORP.

Crew determines SI is Required based on PZR Basis for Selection: pressure being < 1860 psig.

SAFETY SIGNIFICANCE -- Failure to manually actuate SI under the ATC manually actuates SI - both trains by turning postulated conditions constitutes Control switches (BB-A).

"misoperation or incorrect crew performance that leads to degraded ECCS capacity."

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 EXPECTED STUDENT RESPONSE n~

EVENTS 6, 7,8, & 9: (continued) A TC verifies SI System Status

Both 2CHS*P21A and P21B pumps running.

Critical Task: E-O.I

HHSI Flow indicated, Crew establishes flow from at least

Both LHSI pumps mnning one high head ECCS pump before transition out of E-O. ATC notes zero HHSI flow, identifies 2SIS MOV867A, B, e & D all failed to open on the SIS Basis for Selection: actuation.

SAFETY SIGNIFICANCE -- Failure to manually start at least one high-head SRO directs ATe to align valves to establish flow.

ECCS pump under the postulated conditions constitutes "misoperation or ATe manually opens 2SIS*MOV867A, B, e, & D incorrect crew performance which leads and confirms HHSI flow exists.

to degraded ECCS capacity."

The critical task could be restated as "manually open valve(s) to establish injection flow from at least one high-head ECCS pump."

BVPS - 2L8 NRC Scenario 5, Rev 1 13 of25

BEAVER VALLEY . ..JWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE Critical Task: E-O.F BOP verifies AFW System status Crew establishes the minimum

Motor-driven AFW Pumps - NONE running required AFW flow rate to the SGs

Turb driven AFW Pump Stm Supply Isol before transition out of E-O, unless Valves OPEN the transition is to FR-H.l, in which

AFW Throttle Vlvs - FULL OPEN case the task must be initiated before

TotalAFWFlow- <340gpm(-300)

RCPs are manually tripped in accordance with FR-H.1. BOP starts 2FWE*P23B and verifies total AFW flow is> 340 gpm.

Basis for Selection:

SAFETY SIGNIFICANCE -- Failure to establish the minimum required AFW flow rate, under the postulated plant conditions, results in "adverse consequence( s) or a significant degradation in the mitigative capability of the plant." In this case, the minimum required AFW flow rate can be established by performing the appropriate manual action. Therefore, failure to manually 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 1 140f25

BEAVER VALLEY I -,WER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 6, 7, 8, & 9: (continued) List of Attachment A-O.II Discrepancies: SRO directs BOP to perform Attachment A-O.II.

Discrepancies:

NOTE: SIS failed to automatically actuate on low PZR Evaluation of BOP performing pressure.

Attachment A-O.II begins on page 23.

2SIS*MOV867A, B, C, & D all failed to open on SIS actuation, successfully opened manually.

2FWE*P23B failed to auto start, manual start was successful.

ATC checks RCS Tavg stable at or trending to 547°F.

RCS temperature < 547°F and dropping due to

ATC verifies no steam release is occurring.

Safety Injection flow. (Condenser steam dumps closed)

ATC verifies Reheat steam is isolated.

ATC reduces total feedflow to minimize C/D.

cm not actuated at this time. ATC checks recirc spray pumps NONE RUNNING BVPS - 2L8 NRC Scenario 5, Rev I 150f25

BEAVER VALLEY I -,WER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 6, 7, 8, & 9: (continued) ATC verifies PZR isolated

PORVs - CLOSED Critical Task: E-O.M Crew closes the upstream block ATC reports PORV 2RCS*PCV455D indicates dual MOV of the stuck open Pzr PORV position and won't close.

prior to completion of the "Prz PORV check" step of E-O. ATC closes block valve 2RCS*MOV537 to isolate stuck open PORV.

Basis for Selection:

SAFETY SIGNIFICANCE -- Failure to ATC continues verifying PZR isolated close the block MOV under the

Spray Valves CLOSED postulated plant conditions constitutes

Safety relief valves CLOSED (use PSMS)

"misoperation or incorrect crew

PRT conditions CONSISTENT WITH performance which leads to degradation EXPECTED VALUES of any barrier to fission product

Power to at least one block valve release." In this case, the RCS AVAILABLE fission-product barrier can be restored

Block valves AT LEAST ONE OPEN, 2 are to full integrity simply by closing the open.

block MOV. Therefore, failure to close the MOV also represents a n demonstrated inability by the crew to take an action or combination of actions that would prevent a chal1enge to plant safety."

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 1 160f25

BEAVER VALLEY, ..JWER STATION CINSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 6, 7, 8, & 9: (continued) ATC/BOP checks if any S/Gs are faulted

Pressures in all S/Gs - ANY DROPPING IN AN UNCONTROLLED MANNER OR

ANY S/G COMPLETELY DEPRESSURlZED 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.

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

BVPS 2L8 NRC Scenario 5, Rev 1 170f25

BEAVER VALLEY, -,WER STATION LIN§IRUc;JIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 6, 7, 8, & 9: (continued) A TC checks if CREVS should be actuated:

Checks EITHER ofthe 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 COMPLETELY DEPRESSURIZED Crew determines no SIG's are faulted.

BVPS 2L8 NRC Scenario 5, Rev 1 180f25

BEAVER VALLEY , -,WER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 6, 7, 8, & 9: (continued) 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 ATC reports power available to all block valves and 2

.... block valves are open.

PORV 2RCS*PCV455D was previously identified as being stuck open and is isolated with block valve, 2RCS*MOV537.

BVPS - 2L8 NRC Scenario 5, Rev 1 190f25

BEAVER VALLEY . .;WER STATION INSTRUCTIONAL GUIDELINES LPLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 6, 7, 8, & 9: (continued) 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 rising.

Crew determines that current plant conditions, PZR level, does NOT support SI reduction.

Check ifCNMT spray should be stopped; ATC verifies no Quench or Recirc Spray pumps are runnmg.

ATC resets SI - both trains.

ATC resets CIA - both trains.

ATC checks if LHSI pumps should be stopped.

ATC verifies RCS pressure is > 225 psig and stable or nsmg.

ATC stops both LHSI pumps and places CS in Auto.

BVPS - 2L8 NRC Scenario 5, Rev 1 200f25

BEAVER VALLEY I JWER STATION I INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 6,7,8, & 9: (continued) Check RCS and S/G Pressures BOP checks Pressure in all S/G NOT stable or rising.

ATC checks RCS pressure is dropping.

SRO determines S/G pressure dropping is NOT due to a faulted S/G and continues with procedure based upon preceding note.

BOP verifies AC Emergency busses are energized by offsite power.

SRO directs BOP to stop unloaded EDG's lAW 20M 36.4.AF(AG) as time permits.

BOP performs Attachment A-O.6 to verify power available to at least 1 train of Cold Leg Recirculation equipment.

BOP reports Attachment A-O.6 completed SAT with no discrepancies.

BOP evaluates Radiation monitors, determines Auxiliary building and Safeguards radiation is consistent with pre-event values.

SRO determines TSC is not activated.

SRO directs A TC to monitor nuclear instrumentation to ensure adequate Shutdown Margin.

BVPS 2L8 NRC Scenario 5, Rev 1 210f25

BEAVER VALLEY. JWER STATION INSTRUCTIONAL GUIDELlNE~ PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE EVENTS 6, 7, 8, & 9: (continued) Start additional Plant Equipment to assist in Recovery.

SRO directs a field operator to perform Attach. A-I.I Check if RCS cooldown and depressurization is required; ATC checks RCS pressure> 225 psig.

SRO determines plant conditions support transition to ES-1.2.

SRO transitions to ES-l.2 Terminate scenario when the crew transitions to ES-l.2.

Classify Event:

ALERT, Tab 1.2.3, Potential Loss of Res Barrier due to Res Leak Rate.

BVPS 2L8 NRC Scenario 5, Rev 1 220f25

BEAVER VALLEY * ...JWER STATION INSTRUCTIOt-J~l..nGUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE n~

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

-OR

Steamline pressure - < 500 PSIG

-OR

Steamline pressure high rate of change 100 PSIG DROP IN 50 SECONDS If steamline isolation IS required, Verifies SLI by checking all YELLOW SLI marks - LIT If steamline isolation is NOT required continues on.

NOTE: Establish domestic water system cooling to station air BOP may have already pre-emptively compressors; opened 2CCS-AOVIl8 to provide .~

Opens 2CCS-AOVlI8 .

cooling to the Station Air compressors.

Verifies at least 1 air compressor is running.

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

BVPS - 2L8 NRC Scenario 5, Rev 1 230f25

BEAVER VALLEY

JWER STATION INSTRUCTIONAL GUIDELINES [~I..At-JT STATUS I PROCEDURAl... GUIDANCE EXPECTED STUDENT RESPONSE-Attachment A-O.ll (continued) Align Neutron Flux Monitoring For Shutdown

Transfer 2NME-NR45 Nuclear Recorder to operable source and intermediate range displays.

Check CIB And CNMT Spray Status

Containment pressure - HAS REMAINED LESS THAN 11 PSIG If not Actuate CIB if required by:

Manually initiate CIB - BOTH SWITCHES FOR BOTH TRAINS

Manually align equipment as required

Verify all RCPs - STOPPED

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 SWS 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 1 240f25

BEAVER VALLEY * ...JWER STATION INSTRUCTIONAL GUIDELINES PLANT STATUS I PROCEDURAL GUIDANCE EXPECTED STUDENT RESPONSE Attachment A-O.ll (continued) Verify ESF Equipment Status SIS failed to automatically actuate on low PZR

Verify SI status by checking all RED SIS Critical Task: E-O.I pressure. marks-LIT Crew establishes flow from at least 2SIS*MOV867A, B, C,& D all failed to open on

Verify CIA by checking all ORANGE CIA one high head ECCS pump before SIS actuation, successfully opened manually. marks - LIT transition out of E-O.

Verify FWI by checking all GREEN FWI marks-LIT Critical Task: E-O.F 2FWE*P23B auto start failed, required to be Crew establishes the minimum manually started.

required AFW flow rate to the SGs before transition out of E-O, unless the transition is to FR-H.l, in which case the task must be initiated before RCPs are manually tripped in accordance with FR-H.1.

Verify Power To Both AC Emergency Busses Restore power as required Attachment A-O.ll - COMPLETE Discrepancies: Upon Completion, Report Any Discrepancies to SRO.

SIS failed to automatically actuate on low PZR pressure.

2SIS*MOV867A, B, C, & D all failed to open on SIS actuation, successfully opened manually.

2FWE*P23B auto start failed, required to be manually started BVPS - 2L8 NRC Scenario 5, Rev 1 250f25

.. J CURRENT N41

~o ES DETECTOR CURRENT N42

N43

N44

ML12299A202

Text

REFERENCE:

REFERENCES:

REFERENCE:

REFERENCES:

REFERENCE:

REFERENCES:

REFERENCE:

REFERENCES:

REFERENCE:

REFERENCES:

REFERENCE:

REFERENCES:

REFERENCE:

REFERENCES:

REFERENCE:

REFERENCES:

REFERENCE:

REFERENCES:

REFERENCE:

REFERENCES:

REFERENCE:

REFERENCES:

REFERENCE:

REFERENCES:

REFERENCE:

REFERENCES:

REFERENCE:

REFERENCES:

REFERENCE:

REFERENCES:

REFERENCE:

REFERENCES:

REFERENCE:

REFERENCES:

REFERENCE:

REFERENCES:

REFERENCE:

REFERENCES:

REFERENCE:

REFERENCES:

Navigation menu

Search